* 953*WREVIIN 01 INUDSTIT SERENE FOR IMPLEMENTING TNE REIBBITS f 10 CSR PART 54- TEE UESEB,WALHLE

PAEt 1

I ( E I G I I s I U T I

MARCH 1996

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SUIT 490 li IXA I5 1 1 NWSi W! 14( D N D Z 03 h-3't0 tc. :3Q i 0 NEI 9510 (RESION 0)

NUCLEAR ENERGY INSTITUTE

INDUSTRY QUIDEINE FOR IMPLEMENTING THE REQUIDEMENTS OF 10 OFR PART 50 - THE UCENSE RENEWAL RULE

0 NEI 9510 REVISION 0 Mskrch 1, 1996

INDUSTRY GUIDELINE FOR IMPLEMENTI1G THE LICENSE RENEWAL RULE

TABLE OF CONTENTS PAGE NO.

1.0 Introduction I 1.1 Background I 1.2 Purpose and Scope 1 1.3 Applicability 2 1.4 Utilization of Existing Programs 2 1.5 Resolution of Current Safetylssues 3 1.6 Organization of the Guideline 3

2.0 Overview of Part 54 5

3.0 Identify Th- SSCs Within The Scope Of License Renewal And Their Intended 8 Functions 3.1 Systems, Structures, and Components Within the Scope of License 8 Renewal 3.2 Intended Functions of SSCs Within the Scope of License Renewal 14 3.3 Documenting The Scoping Process 16

4.0 Integrated Plant Assessment 17 4.1 Identification of Suctures and Components Subject to an Aging 18 Management Review and Intrended Functions 4.2 Aging Management Reviews 25 43 Application of Inspections for License Renewal 38 4A Documenting The Integrated Plant Assessment 40

5.0 Time-Limited Aging Analyses Including Exemptions 42 5.1 Time-Limited Aging Analyses 42 5.2 Exemptions 49 5.3 Documenting Xt Evaluation of the Time-Limited Aging Analyses and 50 Exemptions

6.0 Renewal Operating Lizense Applicatior Format and Content 5 1 6.1 Formal Application 53 6.2 Exhibit A - Technical Information 54 6.3 Exhibit B - FSAR Supplement 58 6.4 Exhibit C - Technical Specifications 59 6.5 Exhibit D - Enironmental nformation 60

Appendix A IO CFR Part 54 A-1 Appendix B Typical Structure And Component Groupings And ActivelPassive B-1 Determinationm For The Integrated Plhnt Assessment Apper.'iA C Examples to D:monstrate the License Renewal Process C-1 i NEI 95-10 REVISIONO March 1 1996

LIST OF TABLES

TAIRF: NO, f1ILE 1ENQ.

.1 -I S.AMLE LISTING OF POTENTILL INFORMATION 13 SOURCES

4.1-1 TYPICAL PASSIVE STRUCTURE AND COMPONENT 22 INTENDED FUNCTIONS

5.1-1 DISPOSITION OF POTENTIAL ThAAs AND BASIS FOR 47 DISPOSITION

5.1 -2 POTENTIAL TLAAs 48

6.0-1 SAIMPLE APPLICATION FORMAT 52 NEI 95-10 REVISION 0 March 1, 1996

LIST OF FIGRES

;U L ITLE PAGE N2

2.0-1 LICENSE RENEV-'AL IMPLEMENTATION PROCESS 7

3.0 I A MTHOD TO IDENrIFY SSCs AND INTENDED 9 FUNCTIONS WITHIN THE SCOPE OF LICENSE RENEWAL [§54.4(a) & (b)J

4.1-1 IDENTIFICATION OF STRUCTURES AND COMPONENTTS 20 SUBJEC1 TO AGING MANAGEMENT REVIEW [§54.21(a)(1 )

4.2-1 ASSURING THAT THE EFFECTS OF AGING WILL BE 26 MANAGED [§54.21(a)(3)]

4.2-6 ASSURING THAT THE EFFECTS OF AGING WILL BE 33 MANAGED [§54 21(a)()] USING A PREVIOUS REVIEW

4.2-3 ASSURING THAT TIE EFFECTS OF AGIN.JG WILL BE 35 MANAGED [§54.21(aX3)] USING A MONFrORNG PROGRANI

5.0-1 EVALUATION OF TLAAs AND EXEMPTONS [§54.21(c)] 43

C.1-1 PWR ONCE-THROUGH COOLING SYSTEM C -5

iii NEI 95-10 REVISION 0 March 1, 1996

GUIDELINE TO IMPLEMENT 10 CFR PART 54 THE LICENSE RENEWAL RULE

4 5 1.0 1 }IRQDhifQN 6 7 This guideline provides an acceptable approach for implemcnting the requirements of 10 CFR Part 8 54. the license reneual nie. hereinafter referred to as the Rule. The process outlined in this 9 guideline is founded on industry experience and expertise in implementing the license renewal rule. 10 It is expeced that folloxing tis guideline Will offer a stable and efficient process. resulting in the 11 issuance of a renewed license. However, applicants may elect to rse other suitable methods or 12 approaches for satisfying the Rule's loquirements and completing a license renewal application. 13 14 This guideline uses terminology specific to the license renewal rule. A copy of 10 CFR Part 54 is 1S provided as Appendix A and should be reviewed- 16 17 1.1 Background 18 19 In Decernber 1991, the Nuclear Regulatory Commission (NRC) published 10 CFR Part 54 to 20 establish the procedures, criteria, and standards governing nuclear plant license renemal. Since 21 publishing the original rule, the NRC and the industmy conducted various activities related to its m2 implementation. In September 1994. the NRC proposed an amendment to the rule. The final z.~ amendment was published in May 1995. It focuses on the effects of aging on long-lived passive 24 structures and components and time-limited aging analyses (TLAAs) as defined in 0 CER 25 54.2l(aX) and 54.3, respectively. In addition the amendment allows geater reliance on the 26 current licensing basis (CLB), the mainteace rule, and existing plant programs. 27 28 1.2 Purpose and Scope 29 30 The major elements of the guideline (with their respective guideline sections) include: 31 32 * Identifying the systems, structures, and components within the scope of the Rule (Section 33 3.1): 34 * Identifying the intended finctions oi systems, structures, and components within the scope 35 of the Rule (Section 3.2); 36 * Identifying the structures and components subject to aging management re%aew (Section 37 4.1); 38 * Assuring that effects of aging are managed (Section 4.2); 39 * Application of inspections for license renewal (Section 4.3); 40 * Identifying and resolving tim--Iimited aging analyses (Seczion 5. i?: 41 . Jdentifyinp and evaluating exemptions c6ritaining time-limited aging analyses (Section *.2); 42 and 43 * Identifying a suggested format and content of a license renewal application (Section 6.0). 44 NEI 95-10 REVISION 0 March 1, 1996

1 Applicants interested in license renewal are resporLsible for preparing a plant-specific license 2 renewal application. The license renewal application includes general information and techuical 3 information. The general information is much the same as that provided with the initial operating 4 license application. The technical infornation includes an Integrated Plant Assessment (IPA), the 5 CLB changes during the NRC review of the application, TLAAs, a supplement to the Final Safety 6 Analys.s Report (FSAR), any technical spec ifirafion changes or additions necessary to manage the 7 effects of aging during the period of extended operation and a supplement to the plant's 8 enironmenta report that complies with the requirements of Subpart A of 1O CFR Part 51. 9 10 1.3 Applicability 11 12 This document is applicable to any operating license for nuclear power plants licensed pursuant to 13 Sections 103 or 104b of the Atomic Energy Act of 1954, as amended (68 Stat. 919), and Title II of 14 the Energ Reorganization Act of 1974 (88 Stat. 1242). 15 16 1.4 Utilization of Existing Programs 17 18 This guideline is intended to maximize the use of existing industrv progams studies, initiatives 19 and daabases. Most utilities interested in renewing their operating licen-.:- will prepare their 20 license renewal application after the effective date of the maintenance rui xlO0 CFR 50.65), which 21 is July 10. 1996. This guideline is written uith. the knowledge that some provisions of the license 22 renewal rule may be satisfied with actions take t comply with 10 CFR 50.65. Because of 23 similarities between the two nles, implement.-cr guidance for the maintenance rule' should be 24 reviewed to determine if it can be found acceptable/credited for meeting the license renewal rule 25 requirements. For exarnple, the initial scoping of safety-related systems, structures, and 26 components (SSCs) for license renewal is identical to the scoping of safety-related systems, 27 structures, and components required by the maintenance rule. The license renewal scoping of 28 nonsafety-related systems, structures, and components that support safety-related svstems, 29 structures, and components is similar to the maintenance rule. Applicants are cautioned, however, 30 that there are differences. For instance. the maintenance rule excludes nonsafety-related systems, 31 structures, and components based solely on seismic IL"1 interactions. This is not an exclusion under 32 the license renewal rule. 33 34 The process use to determine the systems, structures, and components within the scope of the 35 maintenance ruk ny have also idertified the system. structure. and component fnctions 36 necessazy for lice. -e rcnewal implementation. In addition. many of the programs used for 37 establishing performance criteria at the plant. system. or train level to meet the intent of the 38 mairtenance rule may be key elements of the license renewal aging management review process. 39 Applicants are encouraged to carefully review and evaluate their maintenance rule documentation 40 for applicability and ease of use in preparing a license renewal applicatiom

' NUMARC 93-01, "Industry Guideline for Mionitoring the Effectiveness of Maintenance at Nuclear Power Plants." to the extent endorsed bv the N'RC n Regulatory Guidc 160. Monnormng the Effectiveness of Maintena.-ct at Nuclear Power Plants, NEI 95-10 REVISION 0 March 1, 1996

1 1.5 Resolution of CurrentSafety Issues (e.g., GSIs and USIs) 7 3 Generic resolution of a generic safety issue (GSI) or unresolved safety issue (USI) is not necessary 4 for the issuance of a renewed license. GSls and USIs that do not contain issues related to the 5 license renewal aging management review or ime-limited aging evaluation need not be reviewed. 6 However, designation of an issue as a GSI or USI does not exclude the issue from the scope of the 7 aging management review or time-limited aging evaluation. (The current process for resolution of 8 GSls and USIs include evaluations based on a 40 year operating life and a 60 year operating life.)

10 For an issue that is both within the scope of the aging mar agement re,.iew or time-lmited aging I1 evaluation and within the scope of a USI or GSI, there are several approaches which can be used to 12 satisfy the finding required by §54.29. 13 14 o If resolution has been achieved before issuance of a renewed license, implementation of that 15 resolution could be incorporated within the renewal application. 16 17 * An applicant rnay choose to submit a technical rationale which demonstrates that the CLB will 18 be maintained until some later point n time in the period of extended operation, at which point 19 one or more reasonable options (e.g., replacernent, analytical evaluation, or a 20 surveillance/maintenance program) would be available to adequately manage the effects of 21 aging. The license renewal application would have to describe the basis for concluding that the 22 CLB is maintained in the period of extended operation and briefly describe options that are 23 technically feasible during the period of extended operation to manage the effects of aging, but 24 it would not have to pre-select which option would be used. 25 26 a Another approach could be for an applicant to develop an aging management program, which. 27 for that plant, incorporates a resolution to the aging effects issue. 2)8 29 a Another option could be to propose to amend the CLB (as a separate action outside the license 30 renewal application) which if approved. would remove the intended function(s) from the CLB.

32- 1.6 Organization of the Guideline

34 Obtaining a renewed operatng licene is a two-phase approach. The first phase is the technical 35 work that must be performed to generate the inforration that is included in the license renewal 36 application. The second phase is the preparation of the license renewal application. 3

38 The technical work includes determining the svstems. structures. and comcinents within the scope 39 of thc Rule. identifying the structures and components suibject to an agin management review. 40 identifyirg aging effects, evaluating plant programs. and reieving TLAAs and exemptions and 41 jsc.ting their applicability for license renewal. The technical phase produces results or 42 information that is ultimatelv incorporated into the license renewal application. so it is important to 431 maintain accurate and detailed supporting documentation. This supporting documentation is not 44 required to be submitted as part of the application: however, it must be auditable and retrievable for 3 NEI 95-10 REVISION 0 March 1, 1996

1 NRC review. Sections 3.0. 4.0 and 5.0 of this document provide guidance on how to proceed 2 through the technical phase. These sections explain Miiat work needs to be done, how to do it. and 3 the expected results. 4 5 Section 6.0 discusses the application phase and identifies the information generated ir the tech .cal 6 phase (Sections 3.0. 4.0 and 5.0) that is incorporated into the license renewal application and t, e 7 FSAR supplement.

4 NEI 95-10 REVISION 0 March , 1996

1 2.0 OVER IEW OF PARr 54

3 The Rule contains the regulators requirements that must be satisfied in order to obtain a renewed 4 operating license which allows continued operation of a nuclear power plant beyond its original S license term. (Figure 2.0-1 reflects the license renewal implementation process.) 6 7 The Rule is founded on two r-inciples. The fix st principle of license renewal is that with the 8 possible exception of the detimental effects of aging on the functionality of certain plant 9 svstems, stucmres, and components in the period of extended operation and possiblv a few other 10 issues related to safety only during the period of extended operation, the regulatory process is 1i adequate to ensure that the licensing bases of all currently operating plants provides and 12 maintains an acceptable level of safety so that operation Will not be inimical to public health and I3 safet or common defense and securitv. The second and equallv important principle of license 14 renewal holds that the plant-specific licensing basis must be maintained during the renewal term 15 in the same manner and to the same extent as during the original licensing term. 16 17 In addition to Lhe identification and evaluation of TLAAs, the focus of the Rule is on providing IS reasonable assurance that the effects of aging on the functionality of long-lived passive structures 19 and components are adequately managed in accordance with the plant- specific CLB design basis 20 conditions such that the intended functions are maintained in the period of extended operation. 2 I This demonstation is documented in the license renewal application.

23 The license renewal application contains general infonnation, technical infonnation, information 24 regarding techniical specifications, and environmental information -25 26 The general information concerns the plant site and the plant owmer(s). The required information is 27 specified in 10 CFR 50.33(a) through (e), (h), and (i). Additionally, the application must include 28 conforming changes to the standard indemnity agreement, 10 CFR 140.92. Appendix B. to account 29 for the expiration term of the proposed renewed license. 30 31 The technical infonnation includes (1) the IPA, which is the demonstration that the effects of aging 32 on long-lived, passive structures and components are being adequately managed such that the 33 intended functions are maintained, consistent with the CLB, in the renewal period. (2) the listing 34 and evaluation of TLAAs and any exemptions in effect which are based oD TLAAs. and (3) a 35 supplement to the plant's FSAR which contains a summary description of the programs and 36 activites that are cited as managing the effects of aging and the evaluation of time-limited aging 37 analyses. 38 39 The application also must include any changes or additions to the plant's technical specifications 40 that are necessar to manage the effects of aging during the period of extended operation. Lastly. 4 1 the application must contain a supplement to the plant's enironmental report that complies with 42 the requirements of 10 CFR Pant 51. 43

5 NEI 95-1o REVISION 0 March 1, 1936

I Once the application is submitted to the NRC. it must be aniended each year to identifv any 2 changes to the CLB that materially affect the contents of the application, including the FSAR 3 supplement. 4 5 Infornation and documentation required by, or otherwi se necessary to docunent compliance with, 6 the Rule must be maintained bv the applicant in an auditable and :etrievable form for the term of 7 the renewed operating license. Additionally. after the renewed license is issued. the FSAR update 8 required by 1O CFR 50.7 1(e) must include any systems, structures. or components newly identified 9 that would have been subject to an aging management review or evaluation of time-limited aging 10 analyses in accordance %ith §54.21.

£, NEI 95-10 REVISION 0 March 1, 1996

FIGURE 2.0 .1 LtCENSE RENEWAL IMPLEMENTATION PROCESS

dAft BygFM. ldentiyTLAAs L StIANAAM. IL COMOaMf, IL MIlCGI wIIhM On s*1.ompuont 0I 54.5J inbmdedof "cahn mh"w theS e ISeclia 5.01 (S.tt*n 3.0)

Modskb t id*oodfy *Vuiem A com- porAft subjuct to agw%g flwtagvm 154.2llaNxi)1 j Is 5A21(s)(2) 1SeCbon 4&t)

UmOCf for daensru"a "* Urhods io vahuat3n TLAAi tho effct of agin9 sr ad.quatelywmnagod ezemons If SA21fc)fl). MI) IS 542t(a) (SeCDho 5.0)

4d*nt long-lived peslve SC$ 5.1(M) -esrh&JuPA"~ meMloff53 4.21 (aJ(2fl D* an~tgig .ff.c inanaged(1I54-21(aKMJ Evaiuau*n of TLAAsF 1 54.21(c))

I~~~~~~S *4

anges affecting tFSAR Supplement nI 544.21fdfl Specificationccane t554.221

7 INEI 95-10 REVISION 0 March 1, 1996

1 3.0 IDENTI THE SSCs WITHIN THE SCOPE OF LICENSE RENEWAL 2 eANDTHEIR INTENDED FTNCTONS

4 This section provides a process for determining which of the many systems, structures, and 5 coTnponents that make up a commercial nuclear power plant are included within the scope of the 6 Rule. The scoping process described in this guideline is at the system and structure level for the 7 majoritv of the systems. structures, and components. In subsequent sections, it is assumed that 8 scoping is performed at the system and structure level. This is not intended to imply that scoping at Q a component lvel is not allowed by the Rule. In fact, for some plants it may be easier to scope at 10 the component level. (Figure 3.0-1 is a process diagram for this section.) I1 12 3.1 Systems, Structures, and Components Within the Scope of License Renewal 13 14 1 Part 54 Reference 16 §54.4 17 (a) Plant s srems, structures, and components within he scope ofthis part are - 18 19 f( Sfetv-relaredsystems, structures, and components which are those relied upon lo remainfunctionalduring andfollowing design-basis events (as defined as in 10 CFR 21 50.49 fb)(1)) to ensure hefollowing functions - fi) The integrity of the reactor coolantpressure boundary; 23 (ii) 7he capability to shut down the reactorand maintain it in a safe shutdown 24 condition; or 25 iii) The capability toprevent or mitigate the consequences of accidents that could 26 result in potentialoffsi:e exposure comparable to the 10 CFR Part 100 guidelines. 27 28 (2) All nonsafety-relatedsystems structures, and components whose failure could 29 prevent satisfactoryaccomplish - ent of any of the functions identzfied in paragraphs 30 (a)l)ti), (Hi, or iii,) of this section. 31 3 2 (3i All systems, srructures, and components reliedon in safety analyses orplant 33 zevluations o perform afimction that demonstrates comp iance with the Commission's 34 regulationsforfireprotection (10 CFR 50.48), environmental qualificarion 10 CFR 35 50.49). pressurizedthermalshock(1OCFR 50.61). anticipatedtransients withourscram 36 (10 CFR 50.62), and station blackout (10 CFR 50.63). 37

8 NEI 95-10 REVISION 0 March 1, 996

FIGURE 3.0.1 A IETHOD TO IDENTFY SSC: AND INTENDED FUNCTIONS WITHIN THE SCOPE OF UCENSE RENEWAL § 54.4(a) &(b)]

For schItMm SMiO^, Of Cepoi fSC)hIn t pfnt Witity Appicabb infonmnaon SUrCos (prom th SSC through ach path)

/ \ /*~~~~~~~~~~~teSSCX fS W rontorad o deonstrate No ?ompnance wth 54AMw NNRC uugto?

IS~~~~~~

Could Pr. ve I d

\ cotld pn co"X

ientfy the funcdofgs) that mefthu |fy the funCtion(s thart demonsbabs compuncl rs rauft' 54(a1 or 2f l wh the Coi lon reulations f5 4.4(a)(3 3

sscS wftin the sco of lw*mt renewal and the asocalte Infended unctons are ider.l1did t

Figure 4.14

9 NEI 95-10 REVISION 0 March 1 1996

1 3.1.1 Safety-Related Systems, Structures and Components

3 There wr a number of viable altcmatives for identifying safety-related systems, structures, and 4 compnents. Tabte 3.1-1 is a listing of information sourcs fot consideration in this process. There 5 mav be information sources available to applicants that are not identified on Table 3.1 -1. These 6 sources may be considered as well. 7 8 Regardless of the approach used. a safety-related system. structure, or component is within the 9 scope of license n:neal if it is relied upon to remain functional during and following design basis 10 events as defied in §50.49(bX1 }to ensure the following finctions: 11 12 * The integrity of the reactor coolant pressure boundary; 13 14 * The capability to shut down the reactor and maintain it in a safe shutdown condition; or 15 16 * The capabilty to prevent or mitigate the consequences of accidents tha could result in 17 potntia offsite exposue comparable to 10 CFR Part 100 guidelines. I18 19 It is conceivable that, because of plant unique considerations and preferences, applicants may 20 have previously elected to designate some systems, structures, and components as safety-related 2 1 that do not perform any of the requirements of Rile §54.4(a)(1). Therefore. a system, structure, 22 or componemn may not meet the requirements of §54.4a)(l) although it is designated as safety- 23 related for plant-specific reasons. However, the systems, structures, and components would still 24 need to be evaluated for inclusion into the scope of the Rule using the criteria in §54.4a)(2) and 25 §54.4(aK3). For example, an applicant may have designated refueling equipment as safety- 26 related even though it does not meet the criteria delineated above. In such cases, the applicant 27 shall imlude a discussion of the process (in accordance with §54.21(a)t2) methodology) for 28 making these determinations. 29 30 3.1.2 Nonsafety-Related SSCs Whose Failure Prevents Safetv-Related SSCs From 31 Fulfiling Their Safety-Related Function 32 33 There are a number of viable altnafives for identifying nonsafety-related systems. structures, and 34 components tha are within the scope of the Rule. Table 3.- is a lisng of information sources for 35 consideration in this process. There may be information sources available to applicants that are not 36 identified on Table 3.1-. These sources may be considered as well. 37 38 egardless of the approach used. the nonsafety-related systems. stuctures, and components 39 considered to be in the scope of the Rule are those: 40 41 * Whose failure prevents a safety function from being fulfilled: or 42 43 * Whose failure as a support system. structure, or component prevents a safety function from 44 being fulfilled. 10 NEl 951 0 REVISION 0 March 1, 1996

2 Examples of these tyes of ;vstems. structures, and components include nonsafey-related 3 instument air svsi-.ms that open containment isotltion valves for purge and vent a nonsafety- 4 related firc damper whose failure would cause the loss of a safety function. or a nonsafety-related S system fluid boundary whose failure would causc loss of a safety fimction. 6 7 An applicant should re'v on the plant s CLB. actual plant-specific experience. industrv-uide 8 operting experience, as appropriate, and existing plant-specific engineering evaluations to 9 determine the appropriate systems, structures, and components in this category. Consideration of 10 hypothetical failures that could resut from system interdependencies that are not part of the CLB 11 and that have not been previously experienced is not required. Hypothetical failures that are part of 12 the CLB may require consideration of second- third- or fourth-level support systems. 13 14 3.13 -Cs ReLied on to Demonstrate Compliance Witb Certain Specific Commission 1 5 Regulations 16 17 Systems, mctures, and components relied on to perform a fimction that demonstrates compliance 18 the following regulations are also in the scope of the Rule: 19 20 * Fire Protection (10 CFR 50.48) 2 1 22 * Environmental Qualification (10 CFR 50.4912 23 24 * Pressuized Theral Shock (IO CFR 50.61I 2Y5 26 * Anticipated Transient Without Scram (10 CFR 50.62) 27 28 * Station Blackot (I0 CFR 50.61) 29 30 'Pe infornation ources in Table 3.1-I could he cons;dered for identifying the svstems, structures. 31 nd components wi ose fimctions are relied on to demonstrate compliance uith the regulatory 32 tequiremens (i.e.. wnose functions were crdited in the analysis or evaluation). Mere mention of a 33 system structure. or component in the analysis or evaluation does not constitute support of a 34 specified regulatory function. An applicant should rely on the plant's CLB. plant-specific 35 expeziemce, industrv-vide operating experience. as appropriate, and existing plant-specific 36 enz4eering evaluations to determine the appropriate systems. structures, and components in this 37 category. Consideration of hypothetical failures that could result from svstem interdependencies 38 that are not part of the plant's CLB and that have not been previously experienced is not required

Thbe Statements of Consideration for the anendments to I CFR Part 54160FR224661 states that "...the Commission agrees that for purposes of 654 4. the scope of U3O 49 equipment to be included u ithin S54 4 is that equipmcnt already identified by licensees under 10 CFR 50 49fb1 Licensees ma- re!I upon their listing of 10 CFR 50.49 equipment, as rr., iired by 10 CFR Part 50.4Q'dj. for purposes of satisf}mig i54 4 with respect to equipment wiEthi the scope of §50.49." NEI 95-10 REVISION 0 March 1, 1996

1 Hyothetical failures that are pan of the CLB may require consideration of secco"d- third- or fourth- ' level support systems. INEI 95-10 REV'ISION 0 March 1, 1996

I TABLE 3.1-1

SAMPLE LISTING OF POTEN:AL INFORNATION SOURCES 4 5 * Verified Daiabases (A database that is subject to administrative controls to assue and mainWn the integrity of the stored data or information) * Master Equipment Lists (including NSSS Vendor Listings) * Q-Lists * Updated Safety Analysis Reports - Piping and Instument Diagrams (P&lDs) * Electrical One-Line or Schematic Drauings * Operations and Training Handbooks * Design Basis Documents * General Arangement or Suctural Outline Drawings * Qualiqt Assurance Plan or Program * Maintenance Rule Compliance Documentation * Desig]. Basis Event Evahations * Emergency Operating Procedures * Docketed Correspondence * Svstem Interaction Comitments * Tccnical Specifications * Envirnmental Qualification Program Documents a Regulatory Compliance Reports (Including Safety Evaluation Reports)

13 NEI 95-10 REVISION 0 March 1, 1996

1 32 Intended Functions of SSCs Within the Scope of License Renewal

3 Psrt 54 Reference 4 §54.4 5 *0*9*0 e 6 7 (b) The intendedfwcrions that these systems. structures.and components must be 8 shown ofufill in §54.21 are thosefunctions that are the basesfor including them within the 9 scope of license renewal as specified in paragraphs i)(l)- (3) of this section. 10 1 1 12 The intended functions define the plant process, condition, or action that must be accomplished 13 in order to perform or support3 a safety function for responding to a design basis event o to 14 perform or suppor a specific requirement of one of the five reguated events in §54.4(aX3). At a 15 system level, the intended fnctions may be thought of as the functions of the system that are the i 6 base for including this system within the scope of license renevAl as specified in §54.4(a)(l)- 17 (3). Whre the plant's licensing basis includes requirements for redundancy, diversity, and 18 defensei ndepth, the systm intended functions include providing for the same redundancy, 19 diversity, ani defense-in-depth during the period of extended operation. For example, a system 20 with two independent trains, according to the plant's CLB, has to perform the intended finctions 21 by each independent train. 22 23 As noted in the above reference, §54.4(b) provides criteria that should be used to identifv the 24 "intended fcions" of systems, structures, and components within the scope of the rule. 25 Therefore, as part of the license renewal process, an applicant should establish a methodology 26 that identifies systems, structures, and components within the scope of the rule and the intended 27 functions which are the basis for their inclusion.

29 In identifying intended functions it is important to understand biat the terms "systems, structures, 30 and components" and "structures and comnponents" are used differently throughout the Rule and 3 statements of consideration (SOC). The SOC, in a footnote (60FR22462), clarifies why 32 "systems. structures and components" is used in some sections of the SOC and Rule versus 33 "stuctures and components t5'cs)". This footnote clarifies that the scoping section (§54.4) 34 includes systems, structures, and components rather than just structures and components to allow 35 an applicant flexibility in how it dcvelops and implements a methodology to identify those 36 structures and components that are subject to an aging management review for license renewal. 37 Also, §54.4 and the associated SOC sections include systems, structu: es, and components to 38 allow the applicant flexibility on how exemptions containing TLAAs can be evaluated for the 39 period of extended operation (§54.21 (c)(2)) because exemptions might have bef .i granted for a 40 particular system. 41

'The term "support" here Tncludes . m, structure, and components whose failure could prevent other SSCs from performing their intended function. 14 NEI 95-10 REVISION 0 March 1, 1996

I The PA required bv §54.21(a) is performed at the structure and component level. Guidance on 2 ithe IPA process is provided in Section 4.0 of this guideline. The Rule contains flexibility to 3 pernit an applicant to start the IPA process at either the system/structure or structure.'component 4 level as long as the passive, long-lived structures and components are identified. The intended 5 fumction- of the structures and components are the same regardless of the starting point. If the 6 strting point is the sstem level, the system intended functions are identified as previously 7 discussed. However, the intended functions of the structures and components still have to be 8 determined as discussed in Section 4.1. These functions are the specific functions of the 9 structures and components that support the systelTistructure intended func!:on(s). Similarly, if 10 the starting point is the structure and component level, the intended functions are those that I I included these structures and components within the scope of license renewal. A structure or 12 component may have multiple functions, but only the function(s) meeting the criteria of §54.4 13 are to be reviewed for license renewal. 14 15 Examples of the application of this step are provided in Appendix C. 16 17 The process leading to the maintenance rule scoping determinations may also have produced a 1 listing of the system and structure functions. Although it is not a requirement of the maintenance 19 rile, such a listing may be based on a documented procedure that ensures a comprehensive and 20 consistent approach to defining the functions for all the systems within the scope of the 21 maintenance rule. If this is the case, then the maintenance rule documentation can be used to help 22 identify the fnctions of safety-related systems and nonsafety-related (affecting safety-related) 23 systems within the scope of the license renewal rule. The information sur:es used to identify the 24 systems required for compliance with the regulations in §54.4(a)(3) should be used to identify 25 their associated functions. If the maintenance rule documentation does not define the sstem 26 fiuctions, does not rely on a procedure which uses a structured approach, or the applicant elects 27 not to use this source, then altemative documentation such as a verified database or a safety 28 analysis report, operations training manuals, etc., can be used to identify the functions of safety- 29 related systems and nonsafety-related (affecting safety-related) systems. A sample listing of 30 infornation sources that can be used to identifi the functions of all sy stems (and structures and 31 components) within the scope of the Rule is provided in Table 3.1 -1. 32 33 NEI 95-10 REVISION 0 March 1, 1996

1 3.3 Documenting the Scoping Process ~1 3 Section 54.37(a) of the Rule requires applicants to retain in an auditable and retrievable form all 4 information and documentation required by, or othermise necessary to document compliance 5 with, the provisions of the Rule. 6 7 The results of the scoping determination should be documented in a format consistent with other 8 plant documentation practices. The infornation may be maintained in "hard-copy" or electronic 9 fornat. If available and appropriate. the infornation may be incorporated into an existing plant 10 database. The applicant should use the quality assurance program in effect at the plant when 11 documenting the results of the scoping process. 12 13 The information to be documented by the applicant should include: 14 15 * A designation of the plant systems, structures, and components that are safety-related 16 (§54.4 (a)(l)), meet the requirements of §54.4(a)(2). or meet the requirements of 17 §54.4(a)(3); 18 19 a Identification of the systems. structures', and components' functions that meet the 20 requirements of §54.4(b) and therefore are intended finctions; and 21 22 * The information sources. used to accomplish the above. and any discussion needed to 23 clarify their use.

16 4 NEI 95-10 RE'VISION 0 March 1, 1996

1 4.0 ENTEGRATER PLANT ASSESSMENT

3 The Integrated Plant Assessment IPA) is the core of the license renewal application. It is the 4 transition from the scoping process tc, the screening process where the focus is on components 5 and structures and their intended functions. Once the svstems. structures. and components within 6 the scope of license renewal are identified, the next step is to determine which structures and 7 components are subject to an aging management review. SpecificalIy. §54.21 (a() states that 8 the aging management review for a structure or component is directly related to whether the 9 structure or component performs an intended function without moving parts or without a change 10 in configuration or properties i.e.. it is passive) and that is not subject to replacement based on a I I qualified ife or spccified time period (i.e. it is long-lived). The IPA also includes a description 12 and justification of the methodology used to determine the "passive. long-lived" structures and 13 components and a demonstration that the effects of aging on those structures and components 14 wil be adequatelv managed so that the intended function(s) will be maintained under all design 15 conditions imposed by the plant specific CLB for the period of extended operation. 16 17 18 19

:I NEI 95-10 REVISION 0 March 1, 1996

4.1 Identification of Structures and Components Subject to an Aging Management Review and Intended Functions 3 4 5 Part 54 Reference 6 I§54.21(a)(IHI) and () 7 8 (1b For those systems, structures, and components within the scope ofthis part. as 9 delineated in 54.4, identif and list those srctures and components subject to an aging 10 management review Structures and components subject to an aging management review 11 sil encompass those structures and components -- 12 13 (s That perform an intendedfunction. as described in p§54.4. without moving 14 parts or withour a change in configuration or properties. These structuresand Is components include. but are not limited to, the reactorvessel, the reactorcoolant 16 system pressure boundary. steam generators, the pressurizer, piping, pump 17 casings, valve bodies, the core shroud, component supports, pressure retaining 18 boundaries, heat exchangers. ventilation ducts, the containment, the containment 19 liner, electricaland mechanicalpenetrations.equipment hatches, seismic 20 CategoryI structures, electricalcables and connections, cable rays, and 21 electricalcabinets, excluding, but not limited to. pumps (except casing), valves (except body), motors, diesel generators, air compressors. snubbers, the control 23 rod drive, ventilation dampers, pressure ransmitters, pressure indicators, water 24 level indicators. switchgears, coolingfans. transistors. batteries, breakers, relavs. 25 sitches, power inverters, circuit boards, battery chargers, and power supplies; 26 and 27 29 (i) That are not subject to replacement based on a qualified life or specified lime 29 period 30 31 §54.21(a)(2) 32 3 3 (2} Describe andjustify the methods used inparagraph(a)ff) of this section. 34 35 There are a number of different methods that will accomplish the same objective of identifying 36 structures and components subject to an aging management review. Regardless of the nethod 37 used, it rius: produce the identificvion and listing of str, ures and components required by 38 §54.21x)(i) and (ii). (Figur4 4.1-1 reflects the method described in this section. ) .39 40 Seletion of an appropriate mthod is highly dependent on the applicant's information 41 management system(s). For ew.ample. the availability of computer databases of plant equipment 4 2 mav result in a more efficient component-by-component review process. Absent such databases. 4 3 an applicant may use a manual review process based on system piping and instrumentation NEI 95-10 REVISION 0 March 1, 1996

1 drawings and electrical one-line diagrams supplemented by other available plant documentation 2 as required.

4 As a minimum, the resulting list developed by the applicant must include all passive, long-lived 5 smructures and components for comnmodity groupings) within the scope of license renewal. 6 However. if an applicanz chooses for its owm reason, the list could be larger (e.g., all passive 7 structures and conmonents). NEI 95-10 REVISION 0 March 1, 1996

FIGURE 4.1 1 IDENTiFICATION OF STRUCTURES AND COMPONENTS SUBJECT TO AGING MANAGEMNT REVIEW 54.21{aX1)]

If rom FIgr 3.0.

For CI SSC deternedto be wtin th scope of w n. dfine the euhFon boundin6 of tie

No Yes

_iid amf NOv1K

\ / Agn \/ ~~~~~~~~~~ormnintH sum Yf or 4npon COMPorwftU~~~~~~~~~~mngmn y~~revesntgupYe /lcns ocdLIS copoefm commd 9tWpi

bOL-am Pe on qu~euirda t uur gn aaeetrve

kg - 4rups I~~~ \= eut tquke aging mnanagament review

|Figure 4.2-1.4.2-2. or 4.2 3 |

230 NEI 95-10 REVISION 0 March 1, 1996

1 4.1.1 Establishing Evaluation Boundaries 2 3 If the license renewal scoping was performed at the svstenvstructure level, as discussed in 4 Section 3.2. the idenefication of structures or components subject to-aging management review 5 begins by first determining the system or structure evaluation boundary. The evaluation 6 boundan. includes those portions of the system or structure that are necessary for ensuring that 7 the intended functions of the system or structure will be performed. This st :p documents which 8 portions of the system make up the evaluation boundary.

10 Documenting the system or structure evaluation boundary is critical and may vary depending on II the applicanfs method of managing information in the PA process. One method is to "flag" 12 components in an equipment database as being either inside or outside the evaluation boundar. 1 AAnother method may be to mark up system drawings to clearly indicate which portions are inside 14 and outside the evaluation boundary. When identifying structures and components within an 15 evaluation boundary, the applicant should rely on the plant's CLB. plant specific experience, 16 industry-wide operating experience. as appropriate. and existing engineering evaluations. 17 Considcation of hypothetical failures that could result from system interdependencies that are 18 nz part of the CLB and that have not been experienced previously is not required. The 19 evaluation boundary may not be the normal system boundarv as defined by existing plant 20 documentation. However, it is not the intent of this guide to change or redefine the norrnal 21 system boundaries as a result of license renewal. 22 23 There are some structures and components that, when combined. are considered a complex 24 assembly (e.g.. diesel generator starting air skids or heating, ventilating, and air conditioning 25 refrigerant units). The Rule and associated SOC do not specifically discuss such assemblies. For 26 purposes of performing an aging management review. it is important to clearlv establish the 27 boundaries for review. An applicant should establish the boundaries for such assemblies by 28 identifying each structure and component that makes up the complex assembly and determining 29 whether or not each structure and component is subject to an aging management review. (See .0 exaunple 5 in Appendix C.) 31

3i 4.1.2 Determining Structures and Components Subject to Aging Management 34 Review and Their Intended Functions 35 36 All long-lived passive structures and components which perform or support an intended function 37 without moving parts or a change in configuration or properties are subject to aging management 38 review. For all such structures or components. the structure or compoient intended function is 39 docunented for use dunng the aging management review steps of the IPA. The structure or 40 component intended functionis) is the specific finction of the structure or component that 41 supports the system intended function. Plant specific CLBs require intended functions to be 42 performed under a variety of &sign conditions. Table 4.1 -1 is a listing of tvpical passive 43 structure and component intended finctions.) 44

,.; NE] 95-10 REVISION 0 March 1, 1996

TABLE 4.1 -1 TYPICAL PASSIVE STRUCTURE AND COMPONENT INTENDED FUNCTIONS Provide structual support to safety-related components Provide rated fire barrier to confine or retard a fire from spreading to or from adjacent areas of the plant Provide sheiter!protection to safety-related components Proi floo protection ier (internal and external flooding event) Provide pressure boundary or fission product retention barrier to protect public health and safet in the event of any postulated design basis events. Provide spray shield or curbs for directing flow (e.g. safety injection flow to containment sump) Provide pressure-retaining boindary so that sufficient flow and adequate pressure is delivered Provide shielding against radiation Provide missile barrier (intenally or extemally generated) Provide shielding against high energy line breaks Provide stictural support to nonsafety-related components whose failure could prevent satisfactory accomplishment of any of the requred safety-related functions Provide insulation resistance to preclude shorts, grounds and unacceptable leakage current Provide pipe whip restraint v

NET 95-10 REVISION 0 March 1, 1996

In making the determinations that a structure s or component's intended function is performed 2 wv*ithout moving parts or a change in configuration or properties. it is not necessary to consider S the piece parts of the structure or component. However. in the case of valves and pumps. the 4 valve bodies and pump casings ma,. perform an intended function by maintaining the pressure Tretaining boundarn and therefore would be subject to an aging management review. 6 7 Ifthe struwtie or component is not subjcct to replacement based on a qualified life or specified 8 time period, then it is considered long-lived pursuant to §54.21 (a)(1)(ii) of the Rule. 9 Replacement programs may be based on vendor recommendations. plant experience, or any 10 means which establishes a specific replacement frequency under a controlled program. However. II a structure's or component's qualified life and its replacement must be less than 40 vears for it to 12 be considered as not lone-live in the IPA process. Structures and components vAith qualified 3 lives greater than or equal to 40 years are considered to be long-lived. Structures and components 14 that are not longld should not be included in the aging management review. 15 16 It may be beneficial to create commodity groupings of like structures or components. including 17 those that are active and passive, to disposition the entire group with a single aging management 18 review. The basis for grouping structures or components can be determined bv such 19 characteristics as similar design, similar materials of construction, similar aging management 20 practices, and similar environments. If the environment in which the structure or component 21 operate suggests potential different environmental stressors, then the commodiv grouping 22 detemination also could consider service time. operational transients, previous failures, and any 23 oEher conditions that would suggest different results. Appendix B of this guideline is a listing, 24 although not all-inclusive. of typical plant components, structures, and co modity groupings. 2 5 along with a determination of whether the group is active or passive. Anplicants are encouraged 26 to use this appendix in detennirung structures and components subject to an aging management 27 review.

29 Structures within the scope of license renewal are long-lived and passive and will require an 30 aging management review. It may be useful. however, to categorize stnctures b tpe (e.g., 31 poured concrete, block concrete, structural steel. shield walls, metal siding. foundation on piles. 32 etc.) in preparation for the aging management review. Subdividing complex structures into 33 discrete elements (e.g., walls, floors, slabs, doors. penetrations. foundations. etc.) may be useful 34 because some elements may not have intended functions as defined in the Rule and. therefore. 35 are not subject to an aging management review. It may also be useful to individually identify 36 spill containrr nt. flood control and fire barrier structural components where applicablt. and 37 appropriate. 38 39 Structural supports either support or restrain mechanica! and electrical equipment (e.g.. hangers. 40 pipe whip restraints, cable travs. and supports). Structural supports can be considered part of or 41 separate from the applicable structure. This guid-line assumes that structural support commodity 42 groupings will be addressed separatel from the applicable structure. 43 NEI %-10 REVISION I March 1, 1996

1 (Examples in Appendix C show the results of doctmenting the evaluation boundary as well as 2 describing the component's intended functions.)

24 NET 95-10 REVISION 0 March 1, 1996

1 4.2 Aging Management Reviews 2 3 Part 54 Reference 4 §54.21(a)(3) 5 6 (3) For each structure and component identified in paragraph(a)(I) of this section, 7 demonstrate that the effects of aging will be adequately managedso that the intended 8 function(s) will be maintained consistent with the CLBfor the period of extended 9 operation. 10 II Although there are several approaches to performing an aging management review, three 12 methods are described in this guideline to demonstrate that the effects of aging are being 13 managed such that dhe intended structure or component function is maintained consistent with 14 the CLB for the period of extended operation. Each method in this section is applicable to I5 evaluations of individual structures, components or commoditY groupings. 16 17 The first method is a specific review of a structure, component, or commodity grouping. The 18 second method references the results of previous reviews of a similar structures or components 19 which have been found acceptable by the NRC. Examples include the license renewral topical 20 repurts developed by the Nuclear Steam Supply System (NSSS) Owners' Groups and previous 21 plant-specific applications. The third method recognizes an applicant's existing performance and 22 conlition monitoring programs. However, other methods may be acceptable provid&d that the 23 demonstration required by §54.21(a)(3) is accomplished. 24 25 4.2.1 Specific Structure and Component or Commodity Grouping Demonstration 26 27 This demonstration is developed by first understandir.g how the structure, component. or 28 commodity grouping performs its intended function(s). Next, the aging effects associated with 29 the structure. component, or commodity grouping are identified. Finally, the applicable plant 30 programs are identified, and the ability to detect and mitigate the aging effects are reviewed. The 31 assembled information is then used to demonstrate either that the effects of azing will be 32- managed by existing programs so that the s. Jcture or component intended f;nction(s) uill be 33 maintained for the pead of extended vperation or that additional aging management activities 34 are necessar-. (Figure 4.2-1 depicts this process.) NE 95-10 REVISION 0 March 1, 1996

FIGURE 4.2-1 ASSURING THAT THE EFFECTS OF AGING WILL BE MANAGED [§ 54.21(a)(3)]

Structre, componono or commodity group spcdihc rwview

IFure42. 1-

Identify and review aging managenint progrms

I 26 NEI 95-10 REVISION 0 March 2, 1996

1 4.2.1.1 Identih and Assess Aging Effects

3 In Section 32. of the guideline. the svstem. structwe. and componcn; intended functions were 4 identified. and in Section 4.1 the structure's or component's intended :unctionts) was determned. 5 There are various techniques used to dentift and assess aging effects. For some structures and 6 components. design margins and'or matenal ptoperties are known and can be reviewed. In such 7 cases. an analysis may be suflicient to demonstrate that the effects of aging are anaged. For other 8 structures and components performance or maintenance historv is available and can be reNiewed 9 to assist in demonstrating that tw effects of aging are managed. These and other considerations 10 point o the need to determine the appropriate level of review for the tpe of structure. I I component, or commodity grouping and plant-unique conditions. 12 13 Assessing the appropriate level of review involves examining information from various 14 investigations and developing a sope statement to describe the depth of review that is needed for i ' the stucture, component, or commodity grouping. As appropriate, the assessment should 16 include the following activities: 1? 18 . Assemble information relative to the structur or component mateial properties and 19 design margins. If the components are made trom different materials or are subject to 20 distinctly different aging effects, a separate review of each may be needed. 21 22 IdentifV the aging effects potentially affecting the structures' and components' ability to 23*perform their intended function(s). 24 25 * Review the design or material properties to determine if certain aging effects can 26 be shown by analysis not to affect the capability of the structure or component to 27 perform its intended function during the period of extended operation. Of panicular 28 interest are parameters such as corrosion allowance, fatigue cycles, loading conditions. 29 fracture toughness, tensile strength, dielectric strength radiation exposure. and 30 environmental exposure. 31 32 * Review and assess the operating and maintenance history for the structure or component. The focus of the review may include the service duty. operational 34 tansients, past failures, or unusual conditions that affected the performance or 35 condition of the strucure or component. Of particular interest is how the 36 performance or decraded condition of the structure or component has affected the 37 capability of the structure or component to perform its intended function and its risk 38 significance The revie9 also ma% include an examination of repairs. modifications. or 39 replacements for relevance o aging considerations 40 41 * Assess industrv operatinz experience and its applicdbilit% to determine whether it changes 42 plant-specific determinations 43' miEI 9r-10 REVISION 0 March 1, 1996

1 To detennine the aging effects of concern. the applicant shoul consider aiid addresc the 2 matenals. environment, and stessor; inat are associated %it ach structure. component or 3 commoditv grouping under reviev. In -nany instances, the proper selecuon of materials for the 4 oprating environment results in few. if any, aging effects of concem. For example. 5 erosionvcorrosion has very little or no ag g effects of concerm on stainless steel piping. 6 ConveTrselv. .arbon steel is subject to erosionfcorroslon in a raw water environment. However, 7 thr shoid be various progams and activities available to manage the effects of 8 erosion'corrosion on carbon steel piping. 9 10 In addition to the cons6deration of materials. environment. and stressors. the applicant should I consider and address the plant-specific CLB. plant and industry operating experience, and 12 existing engineering evaluations in order to identify the aging effects of concem for the structure 13 or component subject o an aging management review. The aging effects of concem are those 14 that have been identified using the considerations described above, and that adversely affect the 15 structe and component such that the intended function(s) may not be maintained consistent 16 with te CLB for the period of extended operation. 17 18 By analvsis. ar. applicant may be able to demonstrate that it is not possible for an aging effect to 19 result in a loss of the structure or component's in:ended function(s) under design basis 20 conditions. The demonstration ultimatelv should conclud- that there is reasonable assurance tha 2I the CLB will be maintained for the period of extended operation and therefore that the effects of 2 aging need not be managed. A commitnent to an inspection for license iewal, as discussed in 23 Section 4.3. n:ay be needed to veritv specific design values, demonstrate that an aging effect is 24 occuring as anticipated. or that an aging effect is not significant. ionitoring industry expenence 25>such as the results of inspections for license renewal at other plants may also contribute to the 26 demonsration in thse cases.

28 4 . 2 Identify- Plant Aging Management Programs 29 30 Plant programs that apply to the structures, components, or commodity groupings should be 31 reviewed to detemiine if they inc1ude actions to dete-:t and mitigate the effects of aging. The 32 Rule does not contain specific requirements for features of an acceptable aging management 33 review prvgram. These features may vary depending on the structure, component. or cormmoditv 34 grouping. However, features to consider are:

36 * Preventive actions are in effect that mitigate or prevent the onset of degradatio. or aging 37 effects. and their effectiveness is periodically verified. 38 9 * Pararneters are m:ionitored. inspected, ancUor tested, that provide direct information 40 about the relevcLni aging effectis), and their impact on inte&nded functions. 41 42 * There is an action, alert value. or condition parameter to determine the need for 43 correctiNe action. 44

4 C NEI 95-10 REVISION O March 1, 1996

I v Corrective actions are aken (this includes root cause determinations and prevention of 2 recurTence where appropriate) in a timely manne or an alternative action is identified.

4 * There is a confirmation process that ensures that th. corrective actiun was taken 5 and was effective. 6 7 * Th. program is administrativei controlled by a formal review and approval 8 process.

10 The monitoring inspection, and/or testing frequency shuuld be identified and reviewed. This may 11 be dnne by examining the plant andlor industry operating experence and confirming that the 12 frequency of the action(s) is appropriate for timely detection of the aging effects. '3 14 4.2.13 Demonstrate That the Effects of Aging Are Managed iD 16 The prenious steps involve investigations to collect and establish supporting information and 17 objective evidence for the aging management demonstration. When it is determined that there is 18 an applicablc aging effect for a particular structure, component or commodity grouping, the Rule 19 requires that the applicant demonstrate that the effects of aging are adequatelv managed so that 20 the intended function(s) wili be maintained consistent with the CLB, for the period of extended 21 operation.

23 This demonstration must consider the aging effect(s and its impact on the intended function. Tne 24 demonstration also should deternine wheher the action taken in accordance with the aging 25 management program provides reasonable assurance that the structure and component function 26 will be maintained, in accordance with the CLB, for the period of extended operation. In 27 performing the demonstration. consider all programs and activiti s associated i&ith the structure 28 ,r component For example, the primary program for .-iping may be an nspection program. 29 However, a water chemistry program also would be relevant to maintaining the condition of the 30 piping. This in tum provides qdditional justification that the intended fur.ction of the piping will 3I be maintained in the period of extended operation. 32 3 The demonstration is not intended to be a reverification of the structure or component design 34 basis: howvever. in some cases, verification of a specific design basis parameter may be necessary 35 if iat parameter or condition is affected by an aging effect and potentially results in a loss of 36 structure or component intended function. This verification may consist of: () a physical 37 measurement at susceptible locations or on a sampling basis as justified. or (2) an evaluation that 38 dmonstrates that the aging effect will be at a sufficiently slow rate such that the design basis 39 paraneter will not be reduced below a value ne':essary to assure that the intended fnction(s) uill 40 be maintained during the per:od of extends l operation. For example. a safety-related piping 41 component is designed to have s -uctura! integrity under design loads. such as normal. upset, 42 emergency. and faulted conditions. in accordance w%ith the plant's CLB. An aging effect that 4 should te evaluated for piping is loss of material duc to erosion/corrosion. A loss of maten2i! 4 could result in pipe wall thinniing belou des-Qn values renderine the pipe mable to sustain is 2G NEI 95-10 REVISIO N March 1, 1996

1 design loads. However, erosion'corrosion affects piping differently depending on the material of 2 consu-uction. Carbon stcel piping may be susceptible to loss of material due to erosion/corrosion S. and it would be appropriate to evaluate the pipe wall thickness to verify that this design value 4 remains acceptable. Conversely, stainless steel piping is resistant to loss of material from ^ crusion.'corrosio- and this aging effect nornallv would not be significant and thas, it would not 6 be necessay to evaLate the pipe vall thickness to verify this design value.

8 To perforrr the requireJ demonstration. the applicant should construct a rview checklist that 4 corresponds to the scope of the review for the structure or component. That is. there is not just 10 one set of criteria for demonstrating that the aging etfects will be managed. The criteria should be II thought of as a logical presentation of the review that leads to the required conclusion. The 12 following are considered to be elements that may be used to construct an appropriate review 13 checklist. 14 1 * The scope of the credited program(s) includes the specific structure or component subject 16 to aging management review. 17 18 * The aging effect(s) are detected by one or more of the credited programs before there is a 19 loss of the structure's or component's intended function. 20 21 * The program(s) contains acceptance criteria against which the need for corrective action 22 will be evaluated, and ensures that timely corrective action will be taken when these 23 acceptance criteria re not met. .24 25 a Monitoring and trending provides an adequate predictability and timely corrective or 26 mitigative actions. 27 28 * The program(s) is subject to adninistrative controls. 29 30 If all the elements of the checklist constructed by th; applicant cannot be s3tisfied, appropriate 3 1 enhancements to existing programs or new programs may be needed Enhancements to existing 32 programs may include, but are not limited to, verification of specific esign values by 33 inspection(s), adding steps to a procedure for specific aging effects, changing the frequency of 34 the required task, adding specific aging ef*ects mitigation rocedures, and/or changing the 35 record-keeping requirernents. The factors that should be considered when selecting an 36 appropriate program enhancement from acceptable altematives include: i7 38 a The risk significance of the structure or component. 39 40 . The nature of the aping effect (i.e.. is it rea,c2v apparentleawily detected?). 41 42 The feasibility of repairfreplacement of the affected component or structure. 4 3

3 ) NEI 95-10 RE1SION 0 March 1, 1996

1 * The compatibility adaptability of cxPsting programs to detect and manage the aging

-I effect(s).

4 * The existence of technology to detect and manage the aging effect(s). 5 6 * The estimated cost. personnel radiation exposure, and impact on normally scheduled 7 outage duration for determining the enhancement. 8 9 If existing programs. with or without enhancements, are not adequate for managing the effects oi 10 aging, new prograns or other actions shall be developed as appropriate. One action an applican 11 should consider is an inspection as discussed in Section 4.3. It is possible that an applicant is 12 alreadv performiing a relevant inspection or has previously performed an inspection that produced 13 appropriate data for license renewal. Other actions for consideration are refu oishmente or 14 replacement. 15 16 Appendix C contains examples of methods that could be used to manage aging effects on the 17 selected structures or c ;nponents in order to ensure that their intended functions are maintained, i8 consistent with the CLB. during the period of extended operations. 19

' Refurbishment. for purposes of this guid-lzne, means planned actions. short of full replacement. to provide reasonable assurance that the effects of amg1n are adequately managed such that the intended functions are maintair : in accordance &ith the CLB for the penod of exlended operation. NEI 95-10 REVISION 0 March 1, 1996

1 4.2.2 Reference Previous Reviews 2 '. The evaluation of the effects of aging on the performance and reliability of plant systems. 4 structures, and components has been and continues to be an ongoing activity of the industry. 5 Considerable effort already has been 3pplied to examining the effects of aging on those 6 components and structures which are long-lived and passive. Several NSSS Owners Groups are 7 preparing generic reports (topical) that address the requirements of the Rule. These reports also 8 will be submitted to the NRC for eview and acceptance. Additional material will become 9 available when applicants prepare and submit their license renewal applications. 10 1 This progress of events is producing a growing "library" of reports which document aging 12 management reviews of a variety of structures, components. or counodity groupings. This 13 librar- will afford license renewal applicants the option of relying on referenccable results of a 14 previous aging manag -. nt reviev Tf such an option is selected, the elements of the aging 15 management reviev h uid i: tu.eidentifying and demonstrating the applicability of a previous

16 review and then d-'6ionstratlm uat the results and conclusions are in effect at the plant 17 18 Guidance is provided below for each element of the review. Figure 4.2-2 is a diagram that 19 depicts this process. The applicant also may elect to perform a specific (or plant-unique) aging 20 managenent review of the structure or component as described in guideline Section 4.2.1. 21 221 4.21.1 Identify and Demonstrate Applicability of the Selected Reference '-3 24 Plant and generic industry references that provide an aging man.gement review of the same type 25 of structure or component should be reviewed. A search of the public docu-nent room indices 26 may be performed to identify any such reports. References that have been reviewed and approved 27 by the NRC provide an acceptable approach.

29 In the selected reference, identify the scope, assumptions, and limitations affecting the results 30 and conclusions of the analysis. Other characteristics that may need to be identified include the 31 configuration, functions. materials, service conditions, and the original design parameters 32 (corrosion allowance. loading cycles. etc.) and protective measures (coatings, cathodic 33 protection. etc.) affecting the expected service life of the structure or component. 34 35 The identified characteristics of the structure or component in the selected reference should be 36 compared to the plant specific structure or component. The objective is to demonstrate that the 37 plant characteristics are the same as. or are bounded by, the reference and therefore. it may be 38 concluded that the seiected report is applicable and may be used as a basis ior the aging 39 management review of the plant structure or component. Any outlier conditions sho-ald be 40 ideitified and reviewed to show that thev are not significant with respect to the results or

32 NEI 95-10 REVISION 0 March 1, 1996

FIGURE 4.2-2 ASSURING THAT THE EFFECTS OF AGING WILL BE MANAGED Li 54.21(a)(3)] USING A PREVIOUS REVIEW

Idefwt the s*td rfence dcumnt

.~~~~~r It.srcju

No~N / w UAw ou\w ewwIi4m mt=db&. etc. coewo so i bounded by One speMc

I 33 NEI 95-10 REVISION 0 March 1, 1996

I conclusions of the selected reterence. Otherwise. a structure or component-specific aging 2 management review (guideline Section 4.2.1 ) of the outlier condition should be performed.

4 4.22.2 Demonstrate Tbat the Effects of Aging are Managed

6 The selected reference should be used to identify the aging effects. It also should be 7 demonstrated that the assumptions and basis used for determining the aging effects are applicable 8 to the plant. To do this, a review of une plant operating and maintenance history should be 9 performed t confirm that all aging effects apply. Adjustments to the referenced aging effects due 10 to plant-specific conditions may be required. The results may be factored into the description of 11 the aging effects. 12 13 The selected reference should be used to identify the programs and features of the programs 14 credited in the review. The comparable plant programs should be identified, and their features 15 should be compared to the programs in the selected reference. Any differences should be 16 identified, and it should be justified that conclusions of the selected reference still apply. The 17 justification may be based on plant-umque features, plant operating and maintenance history, 18 and/or industry developments since the selected reference was issued and reviewed by the NRC. 19 20 Any enhancements to current programs or new programs that are cited in the selected reference 21 should be identified. The enhancement(s) that will be implemented for the plant structure or 22 component should be described.

2i 24 4.2.3 Application of Existing Performance and/or Condition Monitoring Programs 25 26 The Rule does not prescribe the explicit tpes of programs and activities that are necessary to 27 demonstrate that the effects of aging will be adequately managed so that the intended function(s) 28 will be maintained for the period of extended operation. Because of this, there is sufficient 29 flexibilit for an applicant to determine what tpes of programs and activities fit the needs of the 30 structure or component for that facility. This includes the use of performance and/or condition 31 monitoring programs to demonstrate that for long-lived, passive structures or components! the 32 effects of aging will be adequately managed so that the intended fnction(s) will be maintained for 33 the nriod of extended oreration. Condition monitoring programs generally assess pasive aspects of 34 structures and components based on inspection activities. Performance monitoring programs 35 generally assess active fimctions of componznts based on testing activities. However, it may be 36 possible to use the results of performance monitoring programs to assess the passive aspects of 37 strucures, components, or commodity groupings. (Figure 4.2-3 shows the process for sing these 38 programs.)

.4 NEI 95-10 REVISION 0 March 1, 1996

FIGURE4.2-3 ASSURING THAT THE EFFECTS OF AGING WILL BE MANAGED [§54.21(a)(3)] USING A MONITORING PROGRAM

|.1wt

Apl t promne axor condx0om bad monafitw pmoaf

kdetity te scope of t monto,ng progrm

Peftorm an s to d.monst pitomr4we and/or coitiou monitwing program amsule a* ftended functioncsolat wMi tl CLD.

raggocmrt fe ae e

o t1 ag t

35 NE! 95-10 REVISION 0 March 1, 1996

1 4.23.1 Establishing the Relationship Between Degradation and Active

P -rformauce

4 The degradation of mam ssive structures and components may not be as readily apparent 5 through performance and condition monitoring as degradation of active structures and components. 6 This is the reason the Rule requires an aging management review of such passive structures and 7 components and a demonstration that the effects of aging are adequately managed. 8 9 Some passive structures and components may have degradation characteristics that can be 10 monitored through changes in active performance of associated structures and components. In turn, I these changes in active performance generallv are readily detectable through existing performance 12 and conditioning monitoring programs. The aging management review for these passive structures 13 and components could focus on demonstrating the relationship between passive degradation and 14 active performance. Whatever the aging management review approach, including performance or 15 condition monitoring, the applicant must demonsraion that the aging effects of t' structure or 6 component will be adequatelv managed so that the intended function(s) will be maintained !7 consistent uith the CLB dunng the period of extended operation. 18 19 42312 Demonstrating the Effectiveness of the Performance and Condition 20 Monitoring Programs _1 22 Once the link is established between degradation of passive functions and the active performance 23 of the component or commodity grouping, the next step is to demonstrate that the component or 24 commodity grouping is subject to a performance and condition monitoring program. By using 25 the above process the applicant should be able to demonstrate that these comprehensive 26 performance and condition monitoring programs provide reasonable assurance that the azing 27 effects on the intended functions OI the components or commoditv groupings are adequatelv 28 managed in accordance with the plant-specific CLB. 29 30 If existing performanceicondition monitoring programs, with or without enhancements, are not 31 adequate for managing the effects of aging, new programs or other actions shall be developed as 32 appropriate. For example. a particular performance or condition monitoring program may only 33 provide reasonable assurance that the intended function can be performed under normal loading 34 conditiorn.. Additional evaluation and/or inspection may be required to provide reasonable 35 assurance that the component or commodity grouping %ill perform its intended finction(s) under 36 CLB design conditions. Guidance on inspections is provided in Section 4.3. It is possible that 37 an applicant is already performing a relevant inspection or previously has performed e1 38 inspection that produced appropriate data for license renewal. Other actions for consideration are 39 refurbishnent 5 or replacement. 40

Returbishmnent, for purposes of this guideline. means planned actions. shor of full replacement, to provide reasonable assurance that the effects of aging are adequate!. managed such that the ntended functions are maintained in accordance %kiththe CLB for the period of extended operation NEl 95-10 REVISION 0 March 1, 1996

1 4.233 Guideiies for tse of Performance and Cond tion Monitoring Programs 2 3 Because only a select set of plant equipment has the characteri-ac that degradation of passive 4 functions uill be readily apparent in the activ performance of associated components. this 5 approah has limited application in the IPA. The followin guidelines should b used to determine 6 Ahen this approach may be appropriate: 7 8 * The int_nded function is a ptessure-retaining function which directl supports the 9 performance of an active component. This will increase the likelihood that the 10 demonstration that degradation directly affects active performance will be successful: 11 12 * The pressure-rctaining function is not a fission pro!uct boundary function. It is not likelt 13 that an applicant *.illbe able to link degradation of the fissiol product boundary to the 14 active performance of any structure or component which is subject to a perforrnance and I5 condition monitoring program: 16 17 * The system intended finctions are performed by redundant trains. This will ensure that 8 sufficient opportunity exists to conduct comprehensive performance and condition 19 mnonitoring of the equipment; -0 21 * Performance testing is well documented with verification that corrective actions assure 22 tht continued performance of all intended functions. This will -nsure there is sufficient 23 history ith the performance and condition monitoring progra:l to correct any 24 inadequacies in the program's ability to detect degraded perfoi rnance or condition: AND 25 26 * The complex assembly is covered by the maintenance rule. This will ensure that a 27 regulated mechanism is in place for incorporating any adverse expenen^e w;ith the 28 program (either at the utility or in the industry) into appropriate enhancements to the 29 program. 30 31 If these guidelines are met then an applicant should consider use of this approach to provide the 32 §5421l.(aM3) demonsEration rather than the techniques described in previous sections. However. 33 meeting these criteria should not be mterpreted as any part of the demonstration. The criteria are 4 provided here merely as an aid To the applicant in determining when to attempt this approach.

36

37 N'EI 95-10 REVISION 0 March 1, 1996

1 4.3 Application of Inspections for License Renewal

2 3 Skction 4.2 d- .cusses options for performing in aging ianagement review. If the applicant 4 concludes, after reviewAing the options or implementing the option. that the demonstratiun -as not 5 achieved reasonable assurance, an inspection program for license renewal mav be appropriate. 6 This section provides guidance on the elements of an invpection program including the use of 7 sampling and the timing of such inspections. 8 9 4.3.1 Inspection Prograni 10 11 The Rule does not contain any requirements for features of an acceptable inspection program. '29 The elements of an ispection program may vary depending on the specific strcture, 13 compoxienL, or commodity grouping that is subject to aging e ffects of concern. However. 14 features to consider are: 15 16 . Purpose: The inspection program should provide reasonable assurance that the specific 17 aging effect is adequately managed or need not be managed. 18 19 * Scope: The scope of the inspection program mav be a specific component, structure, or 20 commodity grouping. The scope also may be a representative sample of a commodity 21 grouping if justified. 22 2'3 * Inspection Methods: The programs should describe an inspection method that is capable 4 of either (1) detecting the effects of aging before the structure or component would lose 25 the ability to perform its intended function under design conditinns, or (2) demonstrate 26 that the structure or component intended fiuction will be maintained during the period of 27 extended operation without the need for an aging management program. 28 29 * Analysis of Results: The inspection program should include a methodology for analvzing 30 the results of the inspection against applicable acceptance criteria. The methodoingy 31 should be capablc ot determining the ability of the structure or component to perform its j2 intended fimction for the period of extended operation under design conditions required 33 by the plant-specific CLB. The results of the inspection also should be ev luated to 34 zsess whether the sample size is adequate or if it needs to be expanded. 3; 36 . Corrective and Follow-li . ons: The inspection program should discuss when 37 corrective a tions and/or follow-up activities are implemented if appropriate. As 38 . appropriate, consideration should be given to root cause analvsis. actions to prevent 39 recurrence and repair. :eplacement. 40 41 CConclusion: The inspection program should include a final conclusion on whether the 42 purpose been achieved. 43 44 'a NEI 95-10 REVISION 0 March 1, 1996

1 43.2 Sampling

When the pplicant determines an inspection is necessary, sarnplirag ma> be used to evaluate a 4 group of structures or components. If sampling is used. d prograrr should ie developed which S describes and ustufies the methods used for selecing the population and the sample size. 6 7 43.2.1 Population 8 9 A popuation is the collection of the structures or components to be inspected unuer a sampling 10 plan. Selection of the population demands attention to similarity of material of construction, 11 fabricaion. procurement. design, inslation. operating environments. and aging effects. 127 13 43.2.2 Simple Size 14 15 A sample consists of one or more structures or componentc drawn from the population. Thu 16 applicant must determine a sample size at is adequate to provide reasonable assurance that the 17 effects of aging on the structure or component will not prevent the performance of its intendeu 18 function during the period of extended operation. The size of the sample should include 19 consideration of the specific aging effect(s), location, existing technical information, materials of 20 construction, service environment. previous failure history. etc. The sample should be biased 21 towards locations most susceptible to the specific aging effect(s) of concem.

23 43.3 Timing of Inspections 24 25 An inspection for license renewal may be performed at various times. It may be performed prior 26 to submittal of the lic. -se renewal application. The license renewal application may include a 27 commitment to perfom. an inspection prior to the commencement of the period of extended 28 operation. There also maybe justification for perfonning the inspection during the period of 29 extended operatiom NEI 95-10 REVISION 0 March 1, 1996

1 44 Documenting the Integrated Plant Assessment 2 3 Section 54.37 a) of the Rule requires applicants to retain in an auditable and retrievable form all 4 information and documentation required bv. or other'vise necessary to document compliance 5 with the provisions of the Rule. 6 7 The results of the IPA should be documented in a format consistent w&ith other plant 8 documentation practices. The information may be maintained in "hard-copy" or electronic 9 format. It may be appropriate to incorporate he information into an existing plant database if 10 available. The applicant should use the qualit, assurance prrgram in effect at the plant when I I documenting the results of the IPA. 12 13 4.4.1 Documenting the Id ntification of Scs Subject to an Aging Management 14 Review 15 16 T'he information to be documented and retained by the applicant should include: 17 18 * An identification and listing of structures and componentssubject to an aging 19 management review and their intended finctions.

21 * A description and justification of the methods used to detemine the structures and components that are subject to an aging management rev%iew.

24 * The infornation sources used to accomplish the above, and any discussion needed to 25 clarif their use. 26 27 The information documented and retained by the applicant will form the bases of the information 28 contained in the Application as further discussed in Section 6.0. 29 30 4.4.2 Documenting the Aging Management Review 31 3' The infonnation to be documented by the applicant should include:

34 * An identification of the applicable aging eflfects of concem for the structures and 35 components subject to an aging management rview. 36 37 * An identification of the specific programs or activities which will manage the effects of 38 aging for each structure. component. or commodity grouping listed. 39 40 * A description of how the programs and activities vill manage the effects of aging. 41 42 * A discussion of how the determinations were made. 43 44 * A list of substantiating references and source documents. 4:.- NEI 95-10 REVISION 0 March 1, 1996

2 * A discussion f any assumptions or special conditions used in applying or interpreting the 3 source documents 4 5 o A description of inspection prograrns for license rene%%al. 6 7 The information docunented and retained b the applicant will form the bases of the infornation 8 contained in the Application as further discussed in Section 6.0. 9 10

4i NEP )-10 REVISION 0 March 1, 1996

1 5.0 TIIE-LIM ED AGING ANALYSES INCLUDING EXEMPTIONS

3 The Rule requires Time-Limited Aging Analyses (TLAA) be evaluated. It is intended that 4 TL.AAs will capture certain plant-spezific aging analyses that are explicitly based on the current 5 operating term of the plant. In addition, the Rule requires exemptions. based on TLAAs, to be 6 identified and analyzed to justify continuation into the period of extended operation. (Figure 5.0- 7 1 outlines the process for evaluating TLAAs and exemptions.) 8 9 5.1 Time-Limited Aging Analyses 10

12 Part 54 Reference 13 §543 14 15 16 17 Time-limited aging analyses,for the purposes ofthis part, are those 18 licensee calculationsand analyses thai: 19 20 () Involve svstems, structures, and components within he scope of 21 license renewal, as delineated in §54 4(a); 22 (2) Consider the effects of aging: 23 (3) Involve time-limited assumptions defined by he current operating 24 rerm, for example, 40 vears; 25 (4) Were determined o be relevant by the licensee in making a sfety 26 determination; 2? (5) Involve conclusions orprovide the basisfor conclusions related tn 28 the capabiliy ofthe svstem, structure. and component to perform its intended 29 funcrions, as delineated in §54.4(b): and 30 (6) Are containedor incorporatedby reference in the CLB. 31 32 §54.21(c)(1) 33 34 (1) A list oftime-limited aging analyses, as defined in §54.3, must be provided The 35 applicantshall demonstrate that -- 36 37 t'if) The analyses remain validfor theperiod of extended operation, 38 (iiJ The analyses have been projected to the : of the period of extended operaiion, or 39 (iii) The effects ojaging on the intendedfunc.aon'sJ will he adequately managedfor the 40 period of extended operaion. 41

, -NEI 95-10 REVISION 0 March 1, 1996

FIGURE 5.0-1 EVALUATION OF TLAAS AND EXEMPTIONS [§ 54.21(c)]

k*nty Ie*ntify the exonsbo|

TLIssues Ise h~~~~~~Y con mz

No

L Dtimine the method of T t

vtrtty justify tam V__ that VW th*TLAA can the TLAA it N u TAAh be pio.ca nmolved by evlutiona us Vauidfor mDthe end of XO the extended OR flV tex ex"60*6 ~Peod of Ith aging srqiefo opering? openation ofe

Figurv 4.2-1

Documet the evakation

43 NET 95-1 0 REVlSION 0 March 1, 1996

l The applicant must identifV the plant-specific TLAA bv applying the six cfiteria delineated in 2 ~§:4.3. The criteria ma) be applied in any order depending on plant specific document search 3 capabilities that exist. Guidance for applying the six criteria is prnvided below. 4 s 1. Involve svstems, structures, and components within the s.cope of license renewal as 6 delineated in §54.4(a). The system, structure, and component scoping step of the IPA 7 (Section 3.0) should be performed prior to or concurrent w%ith the TLAA identification. 8 9 2. Consider the effects of aging. The effects of aging include but are not limited to: loss 10 of material. loss of toughness. loss of prestress, settlement. cracking, and loss of dielectric I I properties. 12 1; 3. Involve time-limited assumptions defined by the current operating term, for example 14 40 years. The defined operating term should be explicit in the analysis. Simply asserting 15 that a component is designed for a service life or plant life is not sufficient. The assertion 16 must be supported by a calculation or analysis that explicitly includes a time limit. 17 18 4. Were determined relevant by the licensee in making . -fety determination. 19 Relevancy is a determination that the licensee must make based on a r-view of the 20 information available. A calculation or analysis is relevant if it can be shovn to have direct bearing on the action taken as a result of the analysis performed. Analyses are also relevant if they prov ide the basis for the licensee's safety determination and, in the 23 absence of the analvses. the licensee mav have reached a different safety conclusioD. 24 5. Involve conclusions or provide the basis for conclusions related to the capability of the 26 system, structure, or component to perform its intended functions as delineated in 27 §54.4(b). As stated in the first criterion. the intended functions must be identified prior to 28 or concurrent uith the TLAA identification. Analyses that do not affect the intended 29 functions of the system, structure, or components are not TLAAs. 30 31 6. Are contained or incorporated by reference in the CLB. Pant specific documents 32 contained or incorporated by reference in the CLB include the FSAR. SERs, Technical 33 Specifications, the fire protection plan/hazards analyses, correspondence to and from the 34 NRC, QA plan, topical reports included as reference to the FSAR or correspondence to 35 the NRC. Calculations and analyses that are not in the CLB or not incorporated by 36 reference are not TLAAs. When the Code of record is mentioned in the ESAR . for 37 particular groups of structures or components., referenced material includes all 38 calculations required by that Code of record for those structures and components. 39 40 41 All six criteria must be satisfied to conclude that a calculation or analvsis is a TLAA. As an aide 42 to applicants, Table 5.1 - provides examples of how the six criteria may be applied and Table 43 5.1-2 lists potential TLAA's that have been identified from the industry's review of plant-

44 NEI 95-10 REVISION 0 March 1, 1996

1 specific CLB documents, various codes. standards, and regulatory documents. The table also 2 identifies TLkaAs that are specifically identified in the SOC for the Rule

4 Identified plant-specific TLAAs must be evaluated using one of three different approaches, These 5 approaches are described in >54.21(c)(1) of the Rule. One approach is to verify that the analysis 6 remains valid for the period of extended operation. Guidance for this approach is provided under 7 Section 5.1. 1. Another approach is to verify that the analy sis can be projected to the end ofthe 8 period of extended operation. Guidance for this approach is provided in Section S.1.2. A third 9 approach is to show that the effects of aging on the intended function(s) uill be adequately 10 managed for the period of extended operation. Guidance for this approach is provided in Section I1 5.1.3. 12 13 5.1.1 Verifv that the TLAA is Valid for the Period of Extended Operation 14 15 Typically, the existing TLAAs are based on the current operating term (e.g.. 40 vears). Therefore, 16 the approach outlined in this section may not be app!ied for the extended operating term and one of 17 the otherapproaches (see Sections 5.1.' and 5.1.3) should be utilized. However, there may i: 18 cases where the original analysis or efforts to address new issues during plant operation have 19 resulted in an analysis dhat can be demonstrated to remain valid for the period of extended 20 operation. A structure or component may have been qualified for at least 40 years. A detailed 2I review of the analvsis may denonstrate that the qualification is valid for the period of extended 22 operation and no reanalysis is required. An acceptable approach for verifi ing that the TLAA 23 remains valid is described in ie following paragraphs. 24 25 The TLAA issue should be described with respect to the objective(s) of the anal; -sis, conditions and 26 assumptions used in the analysis, acceptance criteria, rcievant aging effect(s), and intended 27 function(s). Itshould be demonstrated that (1) the condituons and assumptions used in the analysis 28 already address the relevant aging effect(s) for the period of extended operation. and (2) acceptance 29 criteria are maintained to provide reasonable assurance that the intended function(s) is maintained. 30 31 Any actions. and an associated implementation plan. for reconciling the affected TLAA source 32 documents should be identified. 33 34 5.1.2 Justifying the TLAA can be Projc-cted to the End of the Period of Exended 3$ Operation 36 37 The current TLAA may not be valid for the period of extended operation: however, it mav be 38 possible to revise the TLAA by recog ng and re-evaluating any conservative conditions and 39 assumptions. Examples include relaxing overly conservative assumptions in the original analysis. 40 using new or refined analytical techniques. andlor performing the analysis using a 60 year life. 41 The Tl AA may then be shown to be valid for the period of extended operation.

45 NEI 95-10 REVISION 0 March 1, 1996

1 5.13 Verify that the TLAA is Resolved by Managing the Aging Effects

3 The structure(s) or componenlts) associated with the TLA-A issue should be identified. The TLAA 4 issue should be descibed with rspK. t to the objectives of the analysis, conditions, and assumptions 5 used in the analvsis, acceptance criteria, relevant aging effect(s)and intended function(s). The 6 guidae provided in Section 4.2 may be used to demonstrate that the effects of aging on the 7 intendod function are adequately managed for the period of extended operation. For exarnple, 8 poisons in the high density spent fuel racks have coupons that are periodically removed and tested 9 to verify that the rack continues to be capable of perfoming its intended fiuction. 10 11 5.1.4 Timing for Evaluation of TLAA 12 13 In general. the evaluation of TLAAs should be completed and submitted at the time of renewal 14 application. However, there may be instances when the completion of the evaluation of TLAAS 1:5 can be deferred to a time after the issuance of the renewal license. 16 17 When an applicant elects to defer completing the evaluation of a T,AA at the time of renewal I8 application, the applicant should submit the following details in the renewal application to support a 19 conclusion that the effects of aging addressed by that ThAA will be managed for a specific 20 structure or component: 21 22 . Details concering the methodology which will be used for TLAA evaluation,

24 * Acceptance criteria that wil! he used to judge the adequacy of the structure or component. 25 consistent with the CLB, when the TLAA evaluation or analysis is performed, 26 27 * Corrective actions that the applicant could perform to provide reasonable assurance that the 28 component in question will perform its intended function when called upon or will not be 29 outside of its design basis established by the plant's CLB, and 30 31 * Identification of when the completed TLAA evaluation uill be subritted to ensure that the 32 necessary evaluation will be performed before the structure or component in question would not 3 be able to perform its intended finctions established by the CLB.

4E NEI 95-10 REVISION 0 March 1, 1996

I TABLE 5.1-1 DISPOSTIO OF POTENTIAL TLAAs AND BASIS FOR DISPOSITION

E EXA_MPLE _ DISPOSITION

Ncoespondence requess a utility to justify Does not qualify as a TLAA because the design that unacceptable cunulative wear did not occur life of control rods is less than 40 years. during the design life of control rods. Therefore does not meet criterion (3 ) of the TLAA definition in § 54.3.

Maximum wind speed of 100 mph is expected Not a TLAA. Does not involve an aging effect. to occur once per 50 vears

Correspondence from the utility to the NRC This example does not meet criterion (4) of the states that the membrane on the containment TLAA definition in § 54.3 and therefore is not basemat is certified by the vendor to last for 40 considered a TLAA. The membrane was not vears. credited in any safety evaluation

Fatigue usage factor for the pressurizer surge This example is a TLAA because it meets all 6 line was determined not to be an issue for the criteria in the definition of TLAA in § 54.3. The current license period in response to NRC utility s fatigue design basis relies on Bulletin 88-11. assumptions related to 40 year operating life for this component. Plant specific data could be used but is more difficult due to thermal stratification.

Containment tendon lift off forces are calculated This example is a TLAA because it meets all 6 for the 40 year life of the plant. This data is criteria of the TLAA definition in § 54.3. The used during Technical Specification surveillance lift off force curves are limited to 40 vear values for comparing measured to predicted lift off currently and are needed to perform a required forces. Technical Specification surveillance.

47 NEI 95-10 REVISION ( March 1, 1996

1 TABLE 5.1-2 POTENTIAL TLAAs

FATIGUE

REACTOR VESSEL NEUTRON EMBRITTLEMENT*

ENVIRONMENTAL AGING (ENVIRONMENTAL QUALIFICAT IN)

LOSS OF PRESTRESS IN CONCRETE CONTAINMENT TENDONS *

IGH DENSITY POISONS OF SPENT FUEL RACKS

METAL CORROSION ALLOWANCE

INSERVICE FLAW GROWTH ANALYSES THAT DEMONSTRATE STRUCTURAL STABILITY FOR 40 YEARS

INSERVICE LOCAL METAL CONTAINMENT CORROSION ANALYSES

HIGH-ENERGY LINE-BREAK POSTULATION BASED ON FATIGUE CUMULATIVE USAGE FACTOR

6 7 All but one (high density poisons of spent fuel racks) of the TLAAs in this Table are cited in the 8 SOC for the final Rule (see Appendix A of ths guideline). The TLAAs with an * have been 9 identified based on plant-specific reviews. 10

48 NEI 95-10 REVISION 0 March 1, 1996

I 5.2 Exemptions

3 Part 54 Reference §5421 (cX2)

(2) A list must beprovidedofalplant-specificexemprions grantedpursuantto J0 CFR 50.]2 and in effect thai are based on time-limited aging analyses as defined in §54.3. 7he applicant shall provide an evaluation thatjustifies the continuation ofthese exemptionsfor the period of extended operation 4 5 Section 54.21 c)(2) of the Rule requires that a list of all exempions granted under 10 CFR 50.12 6 that are in effect and based on a TLAA be provided along with the evaluation of time-limited aging 7 nalvyses. 8 9 Identification of an exemption may require the review of a series of correspondence between the 10 NRC and plant to trace the resolution of the exemption. Many plants have licensing commitment I1 Itacking systems or databases of information on licensing documents available. As an alternate 12 method or as a verification to the search, the NRC docket file in the Public Document Room (PDR) 13 may be utilized to search for licensing corespondence and1 thus, exemptions granted. 14 15 It should be determined that the exemption granted pursuant to 10 CFR 50.12 will be in effect 16 during the period of extended operation, involves a system, structure, or component within the 17 scope of the Rule. and involves a time-limited aging analysis issue. If all of these conditions apply, 18 then an evaluation of the exemption must be performed. The TLAA within the exemption is 19 reevaluated using the guidance in Section 5.1 20 21 The scope of the exemption, the analysis that forms the basis for the exemption, and the affected 22 structure(s) or component(s) and/or the time-linited aging analysis issue should be identified. The 23 analysis that forms the basis foT the exemption may have been identified during the evaluation of 24 the ThAAs. 25 26 The exemption shoud be evaluated to deternine its affect on the capabilitv of the associated plant 27 progams to detect or mitigate the effects of aging or on the conditions and assumptions used in the 28 time-limited aging analysis for the period of extended operation. The evaluation of the associated 29 TLAA issue may provide sufficient justification to continue the exemptioL

49 NEI 95-10 REVISION 0 March 1, 1996

1 5.3 Documenting the Evaluation of the Time Limited Aging Analyses and Exemptions

4 Section 54.37(a) of the Rule requires applicants to retain in an auditable and retrievable form all 5 information and documentation required by, or otherise necessary to document compliance 6 with the provisions of the Rule. 7 8 The results of the time-limited aging analyses and exemptions evaluation should be documented 9 in a format consistent with other plant documentation practices. The information may be 10 maintained in "hard-copy" or electronic format. If available and appropriate, the information 11 may be incorporated into an existing plant database. The applicant should use the quality 12 assurance program in effect at the plant when documenting the results of the time-limited aging 13 analyses and exemptions evaluation. 14 15 The information to be documented by the applicant should include: 16 17 a A list of the time-limited aging analyses and exemptions applicable to the plant. 18 19 * A description of the evaluation performed or to be performed on each plant specific TLAA 20 and exemption. 21 22 * A general discussion of how the determinations were made.

24 * A list of substantiating references and source documenEs. 25 26 * A discussion of any assumptions or special conditions used in applying or interpreting the 27 source documents. 28 29 The infornation documented and retained by the applicant will form the bases of the information 30 contained in the Application as further discussed in Chapter 6.0.

= 1% NEI 95-10 REVISION 0 March 1, 1996

1 6.0 RENEWAL OPERATING LICENSE APPLICATION FORMAI AND

3 4 A sample application format is presented in Table 6.0-1. Contents of the application are divided 5 into two parts. (1) general information required by §54.17 and §54.19 and (2) technical 6 inforrnation required by §54.21. §54.22, and §54.23. As presented, the general information is th. 7 fornal part of the application with the technical information being attached as Exhibits. The 8 Exhibits are presented in the same order that they appear in the license renewal rule application. NEI 95-10 REVISION 0 March 1, 1996

TABLE 6.0-1 SAMPLE APPLICATION FORMAT

GENERAL INFORMATION (§54.17, .19) 1. Name of Applicant (§50.33(a)) 2. Address of Applicant (§50.33(b)) 3. Description of Business or Occupation of Applicant ( 50.33(c)) 4. Organization and Management of Applicant (§50.33(d)) [address also §54.17 (b)] 5. Class of License Applied for, the use to which the facilit will be put, the period of time for which the license is sought (§50.33(e)) 6. Earliest and latest dates for alterations, if proposed (§50.33(h)) 7. Listing of regulatory agencies having jurisdiction and appropriate news publications (§50.33(i)) 8. Conforming changes to the standard indemnity agreement (§54.19 (b)) 9. Restricted Data Agreement (§54.17 (f, g)) 10. Reference to Exhibits A, B, C, and D

EXHIBIT A - TECHNICAL INFORMATION (§54.21 (a)-(c)) 1.0 Introduction 1.1 Scope 1.2 CLB changes during NRC review [§54.21(b)) 1.3 Time Litited Aging Analysis Evaluation [§54.21(c)] 1.3.1 TLAA [identification & resolution] 1.3.2 Exemptions [identification& resolution]

2.0 Integrated Plant Assessment - Structure/Component Identification (§ 54.21 (a)(1) - (2)) 2.1 Introduction 2.2 Structure'Component Selection Process 2.3 List and identify results per §54.21(a)(1) 3.0 Integrated Plant Assessment - Aging Management Review (§ 54.21 (a)(3)) 3.1 Introduction 3.2 Aging Management Review Process

EXHIBIT B - FSAR SUPPLEMENT (§54.21 (d))

EXHIBIT C - TECHNICAL SPECIFICATIONS §54.22)

EXHIBIT D - ENVIRONMENTAL INFORMATION (§5423)(§50.53(c))

52 N'EI 95-10 REVISION 0 March 1, 1996

; 6.1 Formal Application

3 The following information. required by §54.17 and §54.19 is consistent with the 4 information contained in the facilitn 's original operating license application as delineated 5 in OCFR50.33X(a throughe).(h),and(i): 6 7 1. Name of Applicant 8 2. Address of Applicant 9 3. Description of Business or Occupation of Applicant 10 4. Organization and Management of Applicant I I ANote hat the license renewal rule prohibits any-person who is a citizen. 1 national. or agent ofaforeign country or any corporation, or other entitJ 13 which the Commission knows or has reason to know is owned, controlled, or 14 dominated by an alien. aforeign corporation,or aforeign government, from 15 applyingfor and obtaininga renewed license. 16 5. Class of License. the Use of the Facility and the Period of Time for which the 17 License is Sought. 8 6. Earliest and latest dates for alterations. if proposed 19 7. Listing of regilatory agencies having j, 'iction and appropriate news 20 publications 21 8. Conforming changes to the standard indemnity agreement 22 9. Restricted data agreement 2-3 Pursuanrto §54.17 )and fg) f the application contains Restricted Data or 24 other defense information i must be preparedin such a manner that all 25 Restric. f Data and other defense information are separatedfrom 26 unclassified information in accordance with 10 CFR 50.331). As part of its 27 application and in anv event prior to the receipt of Restricted Data or the 28 issuance of a renewed license. the applicantshall agree in writing that it will 29 norpermit an) individual to have access Jo Restricted Data until an 3o investigation is made and reported to the Commission on the character. 31 association, and loyalty ofthe individual and the Commission shall have 32 determined that permitting such persons to have access ro RestrictedData 33 will not endanger the common defense and security The agreement of the 34 applicant in this regardis part of the renewed license, wherher so stated or 35 not. 36 10. Reference to Exhibits A. B, C, and D ;7 38 The conteniz specified for the application are the minimum set required by the 39 regularions. Upon issuance of the renzwal operating license. this part of the application 40 becomes an historical docurnent with no further revisions.

5- NEI 95-10 REV'lS1ON 0 M..rch 1, 1996

1 6.2 Exhibit A - Technical Information - I Exhibit A of the renewal application contains the technical information that the NRC staff 4 uill review to determine f the effects of aging on certain long-lived passive structures 5 and components are being managed such that the associated intended function(s) is 6 m.aintained consistent with the CLB in the period of extended operation. The Technical 7 Information provided in Exhibit A must be of sufficient detail in order that the NRC may 8 make the finding that there is reasonable assurance that the activities authorized by the 9 renewal license will continue to be in accordance Mith the CLB (§54.29(b)). 10 I I The application should contain clear and concise presentations of the required 1 information. Confusing or ambiguous statements and unnecessarily verbose descriptions I 3 do not contribute to expeditious technical review. Claims of adequacy of aging 14 management reviem should be supported by technical bases. The level of detail contained 15 in the application should be commensurate with the level of detail typically contained in 16 responses to regulations, license amendment requests, and NRC generic communications 17 submintted on the licensee docket. 18 19 The information contained in the applicatio: is based on the information contained in 20 plat specific documentation as previously described in Sections 3.3. 4.3, and 5.3 of this 21 guideline. However, detailed procedures/caizulations need not be included in the license 22 renewal application 23 24 The contents of this portion of the application parallel the requirements stated in §54.21 25 (a)4c). Once the Renewal Operating License is issued by the NRC, this exhibit of the 26 application is a licensing historical document and is not tequired to be updated. 27 28 The informauon provided in Exhibit A will provide the basis of the changes made to both 29 the FSAR and the Technical Specifications. The FSAR Supplement and the Technical 30 Specifications changes are provided in lxhibits B and C. respectively. 31 32 Exhibit A is organized into three sections or chapters: Introduction, Integrated Plant 33 Assessment - Structure and Component Selection. and Integrated Plant Assessment - 34 Aging Management Review. Guidance on each of these chapters is provided in the 35 following subsections. 36 37 6.2.1 litroduction 38 39 The first Chapter of Exhibit A is the Introduction which includes the follo'Wing 40 subsections: Scope of Exhibit A. CLB Changes during NRC review. and Time Limited 41 Aging Analvsis Evaluations. 42

54 NEI 95.10 REVISION March 1. 1996

I The subsection Scope of Exhtibi A identifies that Exhibit A will address requiremrents from §54. 1 a) - c).

4 6.2.1.1 Identih CLB Changes

6 7 Part 54 Reference 8 §54.21 (b) 9 CLB changes durng NRC review of application. Each year following submittal of the 10 license renewal applicationand at least 3 months before schedu*.d completion of the I .NRC review. an amendment to the renew-al application must be submitted that itntrifi"s i 2 any hange to the CLB of thefacility that materially affects the contents of the license 13 renewal application including the FS.4R supplement. 14 15 16 The Rule requires that the application be iipdat.d yearly and at least three months before 17 scheduled completion of the NRC review. to identify any changes to the facility's current 18 licensing basis that materially affect the application These changes are provided to the 19 NRC in the form of an amendment to the license renewal application. For the initial 20 rene-al application submittal, this provision does not apply. It is a place holder. 21 22 The CLB Changes subsection will contain any CLB changes that occur during NRC 23 review of the application that materially affect the contents of the license renewal 24 application including the FSAR supplement. 2)5 26 6.2.12 Time Limited Aging Anslysis Evaluations 27 28 The Time-Limited Aging Analyses subsection provides the information required by 29 §54.21 (c). 30 31 The application shall include a list of time-limited aging analyses, as defined bv §54.3. 32 The application should include the identification of the affected systems, structures, an1 33 components s- an explanation of the time dependent aspects of the calculation or analysis. 34 and a discussion of the TLAAs impact on the associated aging effect. 35 36 The application shall include a demonstration t t (1) the analyses remain valid for the 37 perod of extended op'eration. (2) the analyses have been projected to the end oi the 38 period of extended operation. or (3) the effects of aging on the intended finction(s) will 39 be adequaTely managed for the period nf e%tended operation. 40 41 le identification of the results of the time limited aging analysis review. which mav be 42 pros ided in tabular form. mav reference the section in the Integrat.l Plant Assessment - .NEI 95-10 REVISION 0 March 1, 1996

I Aging Nanagement Review chapter where mor details of the actual revieu and 2 disposlton as required bv §54.2l(c)( I Xi)-(ii:) are located.

4 Sunarv descnpons of the of the evaluations of TLAAs for *-c period of extended 5 operation shall be included in the FSAR supplement (Exhibit B). 6 7 The application shall include a list of plant specific exemptions granted pursuant to 8 §50.12 and in effeat that ar: based on ThAAs as deftned in §54.3. The application shal 9 include an evalua that justifies the continuation of these exemptions for the period of 10 extended operatio. 11 12 The text may reference p.oved topical reports or regulatory guides, as applicable.

14 622 Integrated Plant Assesment - Structureand Component Identification 15 16 The second chapter of Exhibit A contains information related to the identification of 17 structure; and components subject to an aging management review as described 18 previously in Section 4.0 of this guideline. 19 20 The application shall identify and list the structures, components, or commodity 2 I groupings subject to an aging management re'ie%.

23 Pursuant to §54.2l(a)(2), the application shall include a description and justification of 24 the methods useu to identify and list those structures and components that arc within the 25 scope of license renewal &--dsubject to an aging management review. 26 27 Reference may be made to approved topical reports or regulatory guides as appropriate. 28 2 9 6.2.3 Integrated Plant Assessment - Aging Management Review 30 3 The third chapter of Exhibit A contains information relative to the structure/component 32 aging management review phase of the Integrated Plant Assessment Process (IPA) as 33 described previously in Section 4.0 of this guideline. 34 35 The following information on the aging management review should be included in the 36 renewal application: 37 38 * Description of the structures and components being evaluatcd. Reference to previous 39 information filed with the NRC may be made. 40 41 * Identification of the systems, structures, or component intended functio-s. as 42 appropriate. 43

56 I

NEI 9'54 REVISION 0 March 1, 1996

1 * Identification and assessment of t' dging effecis I or mechanisms. if apprupriate). 2 mncluding a description of materals of construction and service envirt-ment. Operdting expenence should also be considered in order to dentify applicable aging 4 effects for te structures and comronents.

6 * %uentifil-ationand description of aging management programs necessary for renewal.

8 Demonstration that aging management programs, either new, existin, or enhanced. 9 will adequately manage the effects of aging such that the intended. ctions will be 10 maintained consistent with the CLB for the period of extended a .- in. 11 12 Summ descriptio-i of the prugrams and activities for managing the effects of aging 1S shall be included in the FSAR supplement (Exhibit B) at a level of detail consistent with 14 the current FSAR 15 The results included in Fxhibit A determine and technically support the changes propu"d 16 to the FSAR in Exhibit B and the changes proposed to the plant technical specifications 17 as contained in Exhibit C. 18 19 Time-limited aging analvses that havc been identified pursuant to §54.21(c) should be 20 evaluated and the results may be provided d,ith the appropriate structure or component.

57 NEI 95-10 REVISION 0 March , 1996

i 63 Exhibit B - FSAR Supplement

i 4 Part 54 Reference §54.21(d) 6 7 An FSAR supplement he FS4R supplementfor thefacility must 8 contain a summary descriptionofthe programs and acrivitiksfor managing the 9 effects of aging and the evaluation oftime-limited aging analvsesfor the I (J periocfof extendad operation determinedbyparagraphs ra) and (c) of this I section, respectivelv

13 14 The contents of the FSAR supplement uill be based on the material provided in Exhibit 15 A. Section 54.21(d) of the Rule requires that a summary description of the programs and 16 activities for managing the effects of aging for the period of extended operation as 17 determined by the IPA review and the evaluation of time limited aging analyses for the 18 peTiod of extended operation be included in the FSAR supplement. 19 20 In some instanccs. summary descriptions of programs and activities already exist in the 21 plant FSAR. The applicant may chose to incorporate these existing pages of the FSAR 22 by reference or may choose to include them in the application for the '.onvenience of the 23* reader. 2- 25 In addition, a brief licensing summary of the license renewal proceeding may be located 26 iii the ntroduction chapter of the FSAR. The renewal license application process is 27 historical information and the brief summary may be of assistance to future readers. 28 29 Tthe process to review and apl-ove tus change to the plant FSAR should be the same as 30 th.t' wich the applicant presently utilizes. 31 32 Once the Renewal Operating License is approved by the NRC, the material contained in 33 Exhibit B should be incorporated into the FSAR. The FSAR i a living document and 34 should be naintained ir accordance with applicable regulations and olant procedures.

58 NEI 95-10 REVISION 0 March 1, 1996

1 6.4 Exhibit C - Technical Specifications

; Part 54 Reference 4 §54.22

6 Each application must include any technical specification chatges or 7 additions neressary to manage the effects oJ aging during the period of 8 extended operation as prt of the renewal application hejustification for 9 changes or additions o the technical specifications must be contained in the 10 license renewal application 1 12 Exhibit C includes appr priate technical specification changes prepared and presented in 13 a manner consistent %itl the way the an applicant normally submits proposed technical 14 specification revisions. Justification may be included herein, or mav referenc.: other parts 1 of the license renewzal application. Exhibit C meets the requirements of §54.22. 16 17 Once the Renewal Operaling License is issued by the NRC, the proposed changes to 18 technical specifications will be incorporated ai±za issued along with the renewal license. 19 The technical specifications are in a living docu!nent and should be maintaired in 20 accordance with applicable regulations and plant procedures.

59 NEI 95-10 REVISION 0 March 1, 1996

1 6.5 Exhibit D - Environmental Information 2 3 4 Part 54 Reference 5 §54.23 6 7 Each applicationmust include a supplement to the environmental report 8 that complies with the requirements of Subpart .4 of 10 CFR Part51 9 10 When the Part 51 rulemaking is cormlplete, it is expected that §51 .93(c) will require that 11 certain environmental impacts be addressed in the Supplement to the Environmental 12 Repw.rt contained in the renewal license application. 13 14 The format and content of E:.-hibit D should be based on Supplement to Regulatory 15 Guide 4.2. "Preparation of Envircnmental Reports for Nuclear Power Plants". Exhibit D 16 meets the requirements of §54.23. 17 18 Once the Renewal Operating License is issued by the NRC. the environmental 19 information contained in Exhibit D wi:l be maintained in accordance with applicable 20 regulatons and plant procedures. 21 NEl 95-10 REVISION 0 March 1, 1996

APPENDIX A

10 CPR PART 54 THE LICENSE RENEWAL RULE

A-1 Federal Register I Vol. 60. No. 88 / Monday, May 8. 195 Rules ad Regulations ; :

I upPI.MENTARY FOQATN: dues. and are not deducted from the of ONf under 44 requite xt~e approval producer's gros proe&eds to determine . Background. net proceeds for pavmen: purposes and U. Final Action. .rc deducted from goss proceeds to W. Pnncipel lssues. a. Contnued validiNv of centai find descripuon of the statutory determs.ne net proceeds. . general * . . . * prvious rulemakin. basis for tus finAl nie was set forth .n b. geaffrination of the egulatory the mtes n rule published on 3. Section 1468.18 is amended bv philosophy and appoaea and Septembet 16. 1994. (59 FR 47530). The adding paragrph Id) to rad as follows. clarification of the two principles licensC rgnewal. interin rule provided 60 days for 14.8 4 mance and inspcon of coimments. No comments were received c. Systens. stuctws. and cwnpow dunng the Interum rule comment penod within the scope of license rentw November 15. d The muguatorv proce and angw of Septemifbe 16 througb Id)At a1l times dunng regular managemenC. 1994. This final rule provides tiat in e. 94affflrrtion of concluions conc determfug net proceeds for shom business hours, authorized representatves of COC or USDA shall the cumt licensing basis and wool or mohair. fective for 1993 and maintaining the functn ;Dfssttr subsequent marketing yers. marktig have acces to the prmises of the strucrm. and coiponeUts. caires for commIsionS. coring. or applicant. of the marketing agenyv. and I. itgted plant asessment. grading shall not be deducted. This rtule of the peso who furnished evidence to g Time-limted aging anlyses and provides authon2d represctatives of an applicant for use incon ecton with Vet=tl4n=. th applicatiosn, in order to inspect .5trds for isruatce of a enew, SDA and CX access to the premises hcii and the cp.of banes. of buvers and sellers of wool and examine, and make copies of the books. records. a a:ounts, and other wrinen i. Raulaiory and administrative con mobair in order to inspect teir records IV. Ceneral Conments and Responses. for authenticity. data as spefied In paragrphs [a). fb). V. Pubbc Responses to Spcific Qusl. This provsion had been saccidentally ad (c) of this secion. *1. Availbilitv of Docunn. omitted when the wool regulations and Siped at Washington. DC on May t. 199s. YU. Finding oi No Si^1flant Envronr mohwii regulations were conibined In B L Wder. Imp.d Avaiability. I191. This final rule also larifies the ActIg Ezcusiv Vice President. Cotuodiry Vll. Papwork Reduction Act Staem& defnition of nonaeting c to DL Regulatorv Analysi. COd?t C opowuon. X Regulatsry Flexibility AcT Crtiinceu mAke it consistent with the calcuation IFRDoc. 9S-ltlOoFiald 5-5-g5..45aMl of net proceeds and net proceeds for XL Non-Applzbility of the Bekflt Ru pavment purposes. O C c M5a4 L Backgmund diaon 1468.1 Sd) was inadvertently ru. omitted from the interim rule. This The prvious lices renews omitted when CFR Part 54) was adopted by the provision was accideritly Nuclear Regulatory Commission the mohair mgLstow and the wool NUCLEAR REGULATORY in 191 (55 COMYISYlON on Decenber 13. I9 (56 F 6494 tegulstions wer combined This rule established the procedui FR 40233. August 14. 1991). This fina 10 CFR Pat 2, 51. and 54 rule. in part. merely reinstates the citena. and standards govning II otnitted provsion. renewal of nuclear powr plant RhM 3t50-AF06 operating Ucens. Lj of Subjects in 7 CFK Past 1458 Sin publishfng thepeeVious lit Grant program-agriculture. Uvestock. Nucear Pow PL4nt Uen Ranewl; renewal nle. the NRC staffhas Mohair, Reporting and recordkeeping, conducted varinous avtiesieles The acti ;Wlool. AIICY: Nuclear Regulstory implementing this rule. Accordingly, the interim nile Commtssion. included: developing a drft reguls guide. developing a draft stndard amending 7 CFR part 1468 published on ACTION: Final rule. Septe.nter 16. 1994. '59 FR 47530) is review plan for licen renewL with lead plant Lcens adopte. is §nal with the following SUAY: Tae Nuclear Regulatorv inteacting INRC) has amended its and reviewing generic industry Commitsion technical reporu sponsored by the regulations to mse the requiments Nuclear Managemen' and Reurc PART 1466-WOOL AND MOHAIR thA un applicLnt must meet far Council (now par of ths Nuclar E 1. The authoity citation for 7 CR obiniiig the renewal of * nuclear The rule Institute (NEI)). parl 1468 continues t read as follows: power plant operting licnse. 1992.the law firm required informatio In November AuL.ortry 7 U.S.C. 1781-17a7; 15 U.S.C also clarifies the Shaw. Pittman, Potts. and rowtrir n4b ad 714c. that must be submitted for view so submitted a paper to te NRC tht thi the agency can determie whether 2. In j 146a.3 the defution of been met and prentd the pesptVe of Northf thos requireme have States Power Compay an the licem -onmarketing cares"is revised to cages the administrative equiments read as folows: reewal proce. The paper indudi that aboldar of a enewed ic.nse must spficd^r6omnd D Sfo0o m I 14a.n Dufntori. met These amendments are intended the license rewlproe more to prov a more sable and predictable wzorkable. In addition. idust N rkeing diarges means chare rtglatory process for licnse renewal. htpnsetatis provided 2!he paid by or for the aount of the EfECTW DAt lune 7. 1995. Comission with views OD sevl producer that Are not direlv related to FOR CtuTnmR 0fftST1AT CONTACT: license renewal implementa,n i5t improving the marketability of the shon ' itz.l. Office of Nuclear In late 1992. the NRCstaffcwnduct wool or mohair. such s. -not limitee. Reactor Regultion. U.S. Nuclear senior magement review end to. storage bas. advences. iaterest On Regulatory Cominssion. Washington, discussed key licen sernewal issu, advances, sliearing. Lr-d association IC 20555, telephone: (301) 415-1105. with the Commission, industry m'

I - -MMNh - 0m

a' ------

214 feral tis J VoL . No. 1 Monday, !AaY 8. 9i I Rules id Regulations

ad udwidml isomm Tbe NRC stfa of Sgn on Certan syems. stUctur. ComnLssior received 42 aepaa presented ts reommendaions dAd cnmpooa dunn the penod of rmsponsn concernng the ptopowd regarding seven! of thes key lie nse dne operati An obeuve ko the rulemakin fot lune mnewuL ln early renewa assuee in two Com missio amndment s to tabliab a mori stble Apnl 1995. aftr rnewing SECY-V- polay pspW= SE Y-63-O . and predictable lcese renwal prooe. 67, "Final Amendment to the Nucl-r -ip3sant.ia ot o lR Paut 54. The amendment wili identfy certain Power Piant Lcmeo Renewal Rule 110 itaqwzem for R enewal of Ope ating amS. structures, and usmponenu CFR Pv' 54).' the Nucler Eery Uce mNIe Power Plants* tsa rwqula mviww ndw to provide lxtitutsand Yankee Atomic Electric and SECY-3-113. Additio the cessary asurnce that thev wll Company provided additioal Imnp _oauo informtin or Q0CFR xjtlu to p thir ianded w wmmtL All coments rived have Pant S4 i _zunets for Reewul of function for the penod of extended been cosidered in developng this final f NucJa Power operation. rue. On May 23, 1994. the NRC alf Commenwton the proposed mi e s Commiesionth as hi at wff nwuinats _modumprovided the fr a aiety of sour. The (SRW Of ie 2L 1993. il cm= prop osed smeodment to the licee eitIzen 3 public ha semuul to bave a renea rul in SECY-B-140. iucluded a priate stt tbt intm groups (Siea Cub-Adantic - a dstA :l r u at -Proposed Amndmen to th* Noclks pro cle rly a n d u n q i t 2 l Pow PlanwLlceenwal Rule (o Chapte. Public Cl;e. and the Ohio 4*MWi* the Commi on expectation CMat 54.anI the SRM of Juno 24. Ctzns for Respole E) nc. for lkcens mw~aL This p rft-t would 199. the Comamiui appred the Fedeal orpniaadon (DS t of Permnit licensee to make decisions pubica of the proposd ule Energy (DOE). 4 StAt organizations rWalNfle without being aieodmuto f a 90-diay pubLic (iinois Deparumw of Ntaclws Safety tanuceby a rgulatory pr tt a-pir peuL In tb. SRK the (lnois). Connectct Department of is permeived to be uncertain. ung"bl. or Comnuon direc the staff to 11) Public Utility Cootml C C U. DMt churl deeed The C4cunission ciswre cousistency in tbe use of the New Iery Deparutns of dir Ae NC staff to cov £L ters "xrucPr. sysm=s. and Envuormena) Procion (NM feey). omxents and *strctu and and Nvda Agency hr Nuclear zuf1 onents. (i solcit# comments an Pzu. Nuclr Wasge Project Off taked ~ i w o f existin g h o ms.. lba abilty of is pro9rms to detec N4vad)). 2 nduxtry oanizations (NEI ~~~~~~~aaebasis ix [allure In But structures azid and Nucl Utlity Group on onucl~ ~ wllbe addressed compooenu bfoo thrw a bceo of Equipment Quahficatioc tNUGEQJ). 2 ina repn abl ma ne during the itended sSy or sructa funcuonL veadow r soups (Babco and op ea tion in own= Group and e d ofpd~~~~~~~ esneidei l31 addre the ned for S54.4aXSJ3 In Wil (B & wi pu i ir.th e C m o d irect d t hwe the statemens of consideration for the Weadtghous^ One G0roup). 2 NB taf tO iXXisO the eatent to pmpmd rule. and (4) review tho vandaruconwukants (B A W Nuclear which Nstv r elinemi be placed an nszssity of e 54.4(a)(4) and TechnoIogie and Wetnghoue li the OfimanaM rule (to CR so aS indude the r a r ils conlsions Corpoation), and 27 serate nucla iuf~t Sfor Moniting the inthrpaopd- power plant Lensee. AU 27 licens Eff%L.= o Maintmnce at Nucler On Spiames 9, 1994, (59 FR 46574) endoned the commentsprvided by Power Plansi) as a basis foc cazdniug the prposed revisiw to the Ie NEL and some utiu*s also provided that theefet ofamging w il be rnewal rule w published in the additiona comnews. effectively managea during th, license Federal teglAt for a 90-day public TbaCammission pecally soLcited ruzinwu t= comment pood. TIe publc comment (a -September 30.MI3 the NRC stff response to five quesions w the "...Ada pu li w riz hop in period ende c D bu9 9. 1994 The proposed rule The questions and the liethesaMarylsnd,thatiw mnded 3 7hmegwrcvt Sbummm of Camidwuom. the np to them a be found in by ovar '10 people Attedee in cde Sectin v o the Suppleoeiarv a2'- -ym maap~ wod*ua&As& also known as the nuclear tiuitio ldsrY(VUiZn aa d wcrnmbm n amW af wom&am !zforniAn p uo b it c p u p a. ar hi t ct an d - o d smxm uw the d Statemnt of Consdeat (SOC1. Many of the leters conained similr ~tr0ni. a d Fvederl end Stttn Uw - ah . - and anzp a ' comments. which we gsouped goVe -cW-t hi Decembr 2693. the (S15t.4 L it age aoaJyeM togete and are addresed on an issue RCstaff forwarded SECY3-3 . the mmU~~w. thu jeaOc It- bs. The NRC ha responded to all of -L4=vu Renwal Wwkzhap Psuts th sEant points red by the end StafProposals forReiiuon to 10 commenterS hose comments hat are CFR Part 54. 'Requirements for Renewal 15S4 3L2O p k mMU.. and m~ P F Issat ins v.. uu sauw applicable to a specfic Issue discued oiOpemtg LLo ttNaichurPuwer to Am. ~emmon ofid cuvin i thewg si n p- togg.sasja fh4mt.aln a aiu in a specfic section of the - the CoAnnmion. The NRC tI n PIenu. to _ -~eV"~ ~A J r~ N am d h7mod"and5 5 .mtA i hma b - Supplemenwy Wormaton portion of staff zeoniewnded that the Cominmiio this document are discussd wthin that imndt C0FR Ptt 54. Comments received that am not its of February 3.1994. the section. In SRM responsive to a paricula issue ae CowmAon agreed with the NRC strls addresed Lit Sec*n [V. Public concepual approc (explaind in pqstaedsomor 55.lel& itm SUVttm &an*p p a i u * di tI m.. U m d ba g ou the pdposed S-~ gy -3~ 1 k pa o i n n ic en s antym -y )hwola te parlea. ra. i comnents received rene wal r eview s d re te Lnhestaff to so mhe uSb rule are av*ilabie for ispeioa and tamed ad to eo! m is ayupinob in w m. at th Commion's Inzdwith nlmnaking to -4 10 2 U D W a 8 p 5 o 1 .1 _B t h copying for a ee CM Pan 54. The Co=-'ssiou beleves Publbc Document Room loctd at 2o20 that the It zn.vwsl pr-oce should 'L StM NW. ltAwer Level). to on the af the effes m. WLsuinsto. DC - -

Fedra Rhgur I VoL . No. U I Monday. May S. 1995i Rules and Rulations 2

IL IFWl An "fstv analysis report IFSAR) the proposed rle. "Eu latt otherv Th iaal rule rinses certn supplement have be added. e clarified or reevaluated. eitbr d7l. requirements coaned t 1 CFR Purt requument n 54.21(Cl of te previos or zncadly. n the discuaon kLr 54 and stbiuhes a rrilatory proes rute to rew any rlief from codes and proposed rue. the coclusions in t thatis sampl. more stbl. and mor standards has been delke. and the SOC for the current Lice renew. predictable td a the previou ticanse reqmnur,m in 55421(c) of the previous remain vtlid' **' September 9. 'ninl mle. Th final rule cntinu to rule to rview exemptoans on (S9 PR 46S761. Some of the subject .naure that canunued operatioa heycad reulor rwmuuam bs ben reolved in the previous Pat 54 thentof the ori alpe-nlcane clanii and l*nkd with the tme- rulemaking tha remain unffected wil n be mmical to te publc alth imted agLng analyse this final rle include the concept. and aMy. The mar spificant chns IS) in I St= the rupument to CLB. the nature of the current regu include d l stfaon for certain pr . the rTulatoy promss for ade to du pwevmus licens newal cni-I spefiation change in the rule enas WAows asmanrrg compliance with the C.B. 1)Tann=c!the ban renewal iR supplent hs been modifi to of the renwed licen the ter o rview has been, claified to fzus an te requir that th dtiled jusUfication be renewed lices. antitrus adversteffercsfagirg rab than incuded In the lcene renewal consderatloo and the applicabili sdmia of an aging n_camm application. the pmvisions of the Pelce.Andersc The fizal rni-intanded to ensure that 61 In 554.29, the staudards for Act. impusan system&. sucturs. en wusnce of renewed licens have been Furhbere. regardless of wbett wi cortznte to perform chaned to rflct the revised focus on this Is) ruk constitutes a reusior their minded uinction in the paiod of the detimetal effecs of a the previous rule. the Commission _-ded eian ooperof c cnn sructue and cmponents arees with the commenter that the requirng an managment 'niidaapo ~am is net aing review Adminisative Procedure Act lAP' requiredi a put of the icte renewal for lcene twal and any tme-limited requires the Commission to poiid, rview. The definitins ol agrbeed Iue (including xmptions) reasoned aaysi for the change pplicablfr the renewal term A new Part 54 that are being adopted in tb S 540-ha been added to dUnguish final nile. The Commission takes Lb U rom anmin.1ad bete those te dentified during with the commnter with regad to efepm bare been delata& Lhe los newal pcess that quire whether the SOC for the ptoposed (21 Th de of uineamed plant eolutio during the lnse renewal for the final rule adequatelv explai. n t (PA) ( 5431 and the IPA proctwand tlose 1no than ruqudm bases for the changes. The Commis pro nas( 5 ai1(s)) ba n* ha cLarified rminon during thecuret lcnse believes tht this SOC prvides a to be caziste with the revisd fcus; tam deailed discussion setting forth th in Un I1 o the detuiana effects of f7J(nm5432.cuimzruett for pereived problems with the previt c ninuation of t c nnot licensint license rnewal rule as well as (3) A -w 54.4 batbn added to basis (LB) and conditions of reowed discussion of the bass forthis fina rple the definition of rj-nems. licenss ha bechanged t delet al nzle. In sum. the Commision bas stnfl . ad c oop onunts "pOItZD referenc to age-relted degradation fulfilled its obligation under the Al to limes reoewaV' in 9 5 &Secion unique to licen rnewal IARDILR). provide the bases for this rule. 54.4 dm thoe systemstrucnues, Socliam 54-33(d) of the peiou rule. regrdless of whether the changes t mdcmp s within the p of the which requires specific chag conitrol are being adopted in this fmal rule liamm wrnewal nle and identifie te proess hs been deleted. constitute t recision of the previou imparts. fu ae (irttended (8) In S54.37, aitioal records nd license renewal rule. ,codkeepin requireents have been fhJun s) that must be The b.Reaffirmation of the Reguator.' requiment to includ sstems. chand to be lest prescrptive. Section 54.37(c) has been deleted. Philosophy amd Atpproach ond structur an Cpamuf that have aanfiwzion of the Two? Prz.,r:n!r limiting coedio fr opartio in m.Princpallu License Renewal facility technicl spool laloo s within the Sope f license rnwal bas been a. ConUnued aidit of Cfon i Regulatory Philosophy Findin in flvious Ruemaking deldi In developing the pieviDUS licen! (4) 542 () th EA pross hs The prindpal purpose o filalJis reewal rule. the Commisston boon smplified. The wning has ben rule Is to simplify and clarify the concluded that ssues auterial to tU changd to rsolve any ambiguty prvous license reewal rale. Unless renewal of a nuclear power plant noatd with the of the terms otherwise clarified or reevaluated, either opea;tng bcens ae to be confinec syr.zte utwat . and cmponeuts directly or inity, in the discussion those issues that the Commtsston ISSCs) and sucta and components for s final rukl the conciusions in the detemies an uniquel v rlevant U (SCsi A simplifiod methodology for SOC for the previous license renewal protectng the public health and sa detemlning whether MsuCur or nrle remain vid (S6 FR 64943: and preserving common defense ar cocmpoont meqU s en agng Decfmbe 13. 1991). secunty during the period of exten mansgert review for license renewal One cmmenter stted tha the opention. Other iss would. bv ha been aelineaed OUniv passit long pfevious license newal rule hu been definitio have a relevance to the: liveJ In t m an dlco mpontents ar subsAntie:ly modified Ln the proposed and-secunty of the public dunng subje to an agin management rmew rule so as to consttute a "feasion of current plant option. Given the for in n-a,ewaL Sions 54.22 (h tbe previous rule. Commnsszon s ongoing obligston t and d) hav b deleted. and a new The Commsion does not believe that ovemne the safety and secunty of S 54.21(c) deaUng with Ume-lima±d this final rule represents arecswon of operating reactors. issues hat are agin analses (TLAAI and 5421(dJ the previous licnse retewal nule. 10 relevant to curmnt plant opeation daling with requienrnts frrte fa F Ps 54. As sated n the SOC ft be addressed by the existing regula R - m maimliff," eIkP__r_

Z464 Fedtral Register Vol 60. No 88 Mondav. Mav 8. 1995 Rles and Regulalluns

proces within the present license tetm of systems. structurs. and components (lil Deletion of the term "Agelated raile tha deketd untl the tuss of that the Commission determines require Degradatuon Unique to License licen renewal Consequently. the teview for the period of extended Renewal" Commiaon fornulated two principles operation. are adequately managed. The The use of the term age-related of hense rewJa. license renewal rvifew s intended to degradation unique to License renewal' The first prnple of licensr enew I identify any addiuonal actions that will in the pr'vous License rnewal rule was that, with th* exception of at*e be needed to muntan the lunctionalily caused significant uncertainty and reated deaaon unuque to license of the systems. stnctures. and difficulty tn implemenung the rule. A renewal ad possibly a few other issues components in the penod of extended kev problem tnvolved how "unique" rlated to safety only during t : enod operation. The Commssion has aging issues were tobe identified and. of atended opeuoato of nuclr a. power determined tbat a. can generically in parucula:. bOW exitidng license plans the reulatory procss is exclude from the [PA aging management activities and Commission regulau07' adequate to ensure that the licensng review for license renewal (1t those ativities would be considered in 2he bases of all cuntly operating plants identificatior of systems, structures. and an acptable structures and components that perform prevudes and maintns atve funcuons and (2) sructures and components as either subect to or not leve of safety so that opertion will not subject to AROJLR The difMculy in Leinmical to public health and safety components that am replaced based an qualified life or specified time penod. learly establihinb uniqueness" in or commnon defse and security. connection with the effecs of agmg s Moreover. cusideuon of the range of However. al systems. structures. and components evaluated based on time- underscored by the fact that aging is a 1issuerelevant only to extended continuing process. the fan tbat manv opertion led e Commission to limited aging analyses would be subject to a licnse newil evaluation. licensee programs ind egulatory conclude that the detrimental effects of are already focused on aging is prbay the only issue Stnitures or components may have activities active functiasm. passive huntions, or mitiating the effecs of aging to ensure genrally applicable to all piants. As a safetyi the current opeating term of result, continuing this egulatov both. Detailed discussions conce-jing of those systems. the plant. and the fact that no new aging pros in the futr will ensum that determinuon phenomena have been identified as this prncple ramis valid during any structures. and components requiring a of extended operation if the potentially occurring only during the peniod license renewal review are contained in period of extended operation. regulatory process is modified to Secton M.c of this SOC; detiled The final rule elimintes both the addres age-mlated degradatioa that is discussions of those srtuctues and definiuon of ARDUTLR and use of the of unique televance to license enewal. components subject an aging term in codified rgulatory text. Thus. Consequently, the psevious license management review ar in Section lHl conhsion regarding the detailed renewal rule focused the Commission's of this SOC. and detailed discussions of safetv isue. definition of ARDUTLR in the rule and review on this one systems. stuctures. and components questions regarding which suctures The second and equally important requing a licese renew evaluauon principle of license renewal holds that and components could be sub*ect to are contained in Section lIILg of this ARDUTLR have been eliminated. the plant-spefic liensing bs must SOC. be maintained during the renewal term Public Citizen noted that deletion of in the same mannesr and to the same This tnal rule focuses the license the tem ARDUTLR reprsents alteratuon extent as during the original licensing renewal revw on cetain systems. of the "original premise" of the rule end termn. This principle would be structures. and components that the tis change "has not been precipitated accompished. . part. through a Commisson hts determined require by anv realization about eactor aging program of age-related degradation evaluation to ensure that the effects of and saftv." Under both the ptevious management I'or svstens. structures. and aging wil be adequately managed in the renewal rule as well as this fial rule, components that are important to perod of extended operation. Tlus the obecuve was to supplement the license renewal as defined in the change is viewed as a modifEcation regulator process. if warranted. to previous ruie. consistent with the first principle of provide suificient aurance that The C(minission still believes that license renewal established in the adequate safety will be assured durng mitigation of tihe detnrmental effects of the extended period of operation. The previous rule. In view of this final rule, bas concluded that the aging resulting from operstion bevond the first prnciple can be revised to stale Commission the initial license term should be the only issue where lhe regulatorv process that. with the possible exception of the may not adequately maintain a plant's focus for lacense renewal. After funher detrmental effects of aging on the consideration and expenence in current licensing basis concerns the fcuono ty of certain plant svstems. detnmental effects of aging on the implementing the previous rule the structureS. and components in the Commission has, however. detemined functionality of cen4in svstems. period of extended operation and auctures. and components in the that the requirements for carrving out possibly a few other Issues related to the license rnewai review can and period of extended operation. While the should be simplified and clanfied. The safety only 'urng extended opertion. objective and conclusion has remained Camnmission has concluded that. for the egulatory process s adequate to the sme an the two rulemakings. the certain plant systems. structures. and ensure that the licensng bases of all first prncipie of lcense renewal has conponents. the e'x.zshing regulatory currently operating plants provides and been revised consistent with the process ill c11eontinue to mitigate the mantains an acceptable level of safetv deletion . f ARDLsTLR The Commission effects of aging to provide an acceptable so that operation will not be inimical to recognizes tbat the concept of t level of s fety in the penod of extended public health and safety or common ARDUTLR has been removed inasmuch has been operation. defense and secuniv. As modified. ihe as the term "ARDUTLR- The oblective of a licens -newal Commisskon alfirms its support of the deleted from the firt pnnciple ar l from review is to determine w-hethr. the first pnnciple of license rrnewal. as the rule language tself. However. detrimental effects of agini. which well as the unroodifiedl second corisastent with toe focus of the pre%inus could adierselv affea the functionality prtnciple rule, the rn sl rule will ensure tUia the .o . -_An. -~ hfih - ..--'-~~-- -w.~ - ~.- - "T -W

Federal Register I Vol 60. No. 88 Mondav. Mav . 1995 Rules and Regulations 22465

effects of aging in th oeriod of pnncipal importance to te safety of the svstms. structures. and components extended opertion a.> riequately plant. Tb. Commission also believed imoortant to license renewl. These maged. that the focus of an ging valuatIon for scoping categones concem (1) all safety. The Commission disagrees with the license reneal cannot be Limited to related systems, structaes. and commenters gtatement that this change ony those stems. s' rtures and components and (2) all nonsafetv- was arrived at without egard to ractor components that the l.mssson has related svstems. structures. and aging and safety. As discussed above. traditionally defined as saety-related. componens that support the function of greeter understanding that 111 aging Is a Therefore the Comsnission determined a safetyaeailed system. structure. ot contunuous process and (2) tLat the that, in order to ensure the cOntinued component or whose failure could actual effects of i are no. explidtlv safe Opertion of tho plant dunng the prevent a safety-related svstem. hnked. from a tecical perspective. to renewal term. the tnitial focus of license structure. or component from the term of an operating license. led the re uwal sbould be (1) safety-reted satisfactorily fulfilling its intended Commission to consider deleting systems. struwurs. and components. 121 function(s). These two categones are ARDUTLR. The Commission's current nonsafety-rulated systems. structum. meant to captur. as a minimum. determinton that a nawrower set of and components that direcly suppot automatic reactor shuldown svstems. systems. stuctures, and components the function of a safety-mrlated svstem. engmeered safetY featur svstems. than that of the previous license struct. or component or whose systems required for safe shutdown renewal rule should require evaluation failure could prvent the performance of (achiet and maintain the reactor in a to ensure tht the effects of aging wiLl a required function ora safety-rolted safe shutdown conditionl. and be adequately managed In the period of system.Stuucture. or component. (3) nonsaety-related systems. such as extended operation recognizes that systems. structures, and coponents auxiliary svstems. necessary for the manv lcensoe progrms and regulatory relied upoD to me a specific set of function of safetyrelated svstems. activities will continue to adequately Commission regulaUons, and (41 The third category or systems. mnage he advr effects of agig systems. stmctures. and components stactures. and com*ponents discussed during the period of extended operation. subpct to the operability reqwremes Ln the new scope section (§ 54.4(a)(3)) Therefore. the Commission believes thAt contained in the facility technical arethose systems. structum, and specification limiting conditions for components whose functionality may be this aliertion is firmly based on an analyses or plant appropriate cnsideration of reactor opertion. relied on in safety Since publishing the previous rule. evaluations to perform a function that sa fety a nd a gin g. Th e fin al rule re flec ts compliance with the a gter udestnding of effive the Commission has ganed demonstrates considenble prepplicatlon rule CoMIssion's regulations for 10 CFR aging naeet (focus on efet Protection). 10 CFR 50.49 rather than m echai sms) and more imalementation experience and gained 50.48 (Fire * beter understding of aging fEnvirnmental Qualiicauon). 10 CFR realistc expeaons of aging in the maaet. In pan. tug the 50.61 (Pressuized Thermal Shock). 10 extended p of operation devlopmmt of a regultory guide to CFR 50.62 lAnticipated Transients c. Svstems. Stmures. and Components Imslmentt maintnce rle. 10 Witht Scram). anii lo CFR 50.63 Witkhn the Scope of License Renewal CFR 50.5 The Comisson now (Station Blackout). This category is also that (1Uby apprpriately specified in the previous definition of Review believes 6) Scope of the Iie Renewal crediting easting lien progrms that svstems. structures. and components and Elimiion of the Tenical maae the offects of aging and (21 by important to license reneal and Specificotion Limiting Conditions for appropriately crediting the continuing incuded thoe systems. structurvs. and Operation Scopig Category telaoty proe, tt more narwly components relied upon to meet certain to the final rule. the Commisaon ha dfine tse sytm s. s ures and regulaons. This category was deleted the defiition (in JS4.3) of componts wthin the scope of license developed to ensue that important syu. stun. and compaleu uewaandmoto nrrowly fukthe system. structures. and components licam renewal oview. that mav be considered outside the replaced it with a new seton entitled The Commissio continues to believe trditiona defnitlon of safetv.related j 54.4 Scoe This new setin that the initial scope for the lbeense and outside of the fint two categaries in continues to define the set of plat renew review sbould not b limited to 154.4. would bg included within the systems. structurs. and components only those svAms stucs ot initi focus of license mnewal. Through that ould be the nitsl focu of a c4mptset that the Comission h evaluaton of industrv opeting license renewal review. From this wt of uu'litinly deind as syreltd experence and thrugh continuing svtems. stuctues, and components. a HYover. as dicussed below (see regulatory analysis. the Comcission has license renewl aplicant will Justification for the Elimuatioa of the reafrmed that sfytems. structures. and dtermine those sstems. structures. and Tehnical Spec-fictinn Limiung components required to complv with components that reouire renew for 4aditios r OperstioScoping these regulations are important to sare license rnewal. The Lntent of the CAtegory) the Commssion deterined plant operaton because they provide definition of systems. structures. and that the sequirement to consider substantial additional protection to the c*mponents important to lices additional systems. strtures. and public health and sfety or ar an renewal (i.e.. to initiaUy focus the components ibject to the opeaility imporant element in prmviding review on impottant systems. structures. requiremets conained in the facility adequate votecion to the public health and componnts) remains inta ii the tech nia spciiato lting and sakey. The Commission. thererore. new 154 4. condtios r olpion is unner coneludes that thes svstems. strucres. Ln the SOC for the previous license and has been deled and componts should be included as renewal mle, the Commision The first two ca.gozes of systems. part of the initial scope of the license concluded that applicants for licanse structures. and components discussed renewal review. renewal should focus on the in the new scope secion ( 54.41aH1) In their comments on the propoed mangement of agng for those systems. and ra)()) am the same categones rension to the rule. NUIGEQ nod that strucrs. and components that are or defined in the previous defirti'n of t'ithe is subsanual overlap between the - -;------1~.~*- - - w-I-- Wj'9r4P --

22466 -ederal Register / Vol. 60. No. 88 Monday Mav 8. 995 / Rules and Regulations equipment that would be identified in limiting conditions for operauon resources nn those svstcms. strictures. S 54.4(a) and the electncal equipment scoping categorv to be consislent wvith and components thai are of pnncipal important to safety identified in the Commission's intent not to re- importance in safetv. S 50.49tbJ. To provide clarity atid exauine the enure plant for license In its "Finai Policy Statement on consistency and minimize the potenuIal renewal but to ensure that all svstems. Technical Specifications Lmprovements that a licensee will be required to structs. and components of pnnczpal for Nuclear Power Reactos (SS FR reasse the entire scope of J 50.49 unport5nce to sale plan operation were 39132. juIV 2. 19931.the Commission equipment. NUGEQ sugests that identufied and. if necessary. evaluated. idenufied four entenrt for defining the S 54.4(a)13) be modified to include onlv However. existng technical scope of improved tthnracal the additional electric equipment specifications for many plants have speciications. The four cnitera are as identified in S 50.49b)M3, The fnctional requirements on certan lolluws: Commission concludes that the rule sysems. structums, and components Criterion : nstalled instrumentation modification proposed by NUGEQ is not wlth low or mdirect safetv signuficance. that is used to detect. and indicate in necessary. However, the Commison Preapplication rule implementation the control room. a significnt abnormal grees that for purposes cf S4.4. the experience has indicated that this degradatuon of the reactor coolant scope of S 50.49 equipment to be category of systems. stuctues. and prssur boundary. included within 5 54.4 is that componeots as defined in the previous Critenon 2. A process vanable. design equipmnent almdy identified by rule. could lead to an unwarranted re- feature. or operating resuicon that is licersefs under 10 CFR SD.49(b). examination of plant systems. an initial condition ofa Design Basis Licensees may rely upon their listg of structuzs. and components that are not Acudent or T. ansient ainasts that I0 CFR 50.49 equipment. as required by of principal mportance for license ettber assumes the failure of or presents 10 CFR Part 50.49(d). fur purpos of renewal a challenge to the integnty of a fission satisfving 5 54.4 with re -pect to For rt.a.nplr. limiting conditions for product bamer. eqtupment within the scope of J 50.49. opertion ar .rvquently included an Cnienon 3. A structure. system, or technical spec:ficatnons for plant component that is pan of the pnmar justification for the Elmination of the mneteorological and seismic mnonitoring success path and which functions or Technical Spedi ation Limiting instrumentation. main turb!nr bypas actuates to mitigate a Design Basis Conditions Operationtor Scoping systems. and traversing ancor' probes Acudent or Transuent that either Category Ths equirments. wile imporant for assumes the failure of or prmsents a In the previous Ucense renewal rule, cetain aspects of power plnt chulenge to the uintegnty of a ission the Commission established a fourth opertion, have little or Do durct product barer. category of svstems. structures. and beating on protectoia of pblic health Crerion J: A sructure. siter. u conponents to Le the focus of the initial and safetv. Recotizing this. the component which operating exprieo,..n License rt;;swal review. In this category, Commission concludes that current or probabilisuic safety assessment nAa the Comnussion included all svstems. aci,viLes. for such sysms. structues. shown lo be significant to publi. ailth strcures. and components thit hsve ladcsponents. includinglicensee a n s f ty . opeblitv tequiremnents in the plant prgrms and the NRC rgulatoty Nuclear power plant icniees that tchmcal specifications lmitign process. are sulEiceit and that so voluntariy choose tO *-lmprt' thefir conditions for operationL As de ed in additional etaution usneceay hor technical specifications based nn this Standard Technical Specifications. "a lic nse renew al. The tecnical Commission policy may submit changes stem. subsvstem. train. componen. or speficaton category would onlv add to Lhe Commission for review and de; 6ce sball be operable when it is fi.e.. not captured b 54.41a H.3) approval that will remove sysems. capble o peformng its specied nonsety-relaied systems structures. suuicures. and components ftm thetr satetv funcion() and whaf al and components that do not supprt technical specficions before necessary atiendant instrumentation. safetyrelsted systems. structues and cunducting icense renewal lexprrienu e controls normal or emergency electricai components. As discussed in gater shows that approximately 40 p-rcent ni power. cooling and sea waer. detail below. the Commsson condludes ILmaung eorcirtions for ooer.-'n and lubrication, and other suxibar that these .ddtion nonsafetv-related surlance requirrnientscoula be equipment thatam required for the sstems. structues and components deleted). system. subsystem. train, cmponent, or should not be the subect of license After considenng the substan:ial device to perform its specified safety renewal. over!ap between the fou c.nien4 for aefining the scope of ted hincAI functionfsl are also cApable of Improved performing their related suppot Relationstup Btween snecfications and the first tLe si,upt e Technical Specfications and Lcense categories for license rvnewa!. the funcuontsl. This was intended to Renewal Scoping include Ii) all svstems. stroture- and C,m nission concluded thal tbe ELMi"r componens specificallv identified in Uhile it is ni the Commission's of additional ,vsrems struc1izre anJ the technical specificaian limiting intent to reauire applicants for lIce components that would be conaiderL conditions for operauon. (2) any system. reewral to -mprve` the.r technical as a result of applying the technical structure or component for which a speclications. it remans the soecifica±.on scooig c2regor. tM functional requirement is sp cfically Comrnsr.zu's intent to focus the license urproved tethtiical specificarnan, v idenufied tn the technical s cfication rermewaI review u Lbose sstems. small Tbee addiuona svstem%. limiting conditions for operation. and srI.c-ures. ad components thal are of smutures. and comprients met !r e,. (3) a.nv necessarv supporung svstem. pnncitial !mporiance o safofv would r"sult f.-m iifference' 1u P., structure or component that must be Threfore. a lcense rrnewal srnping plant'scurr'n: icei sangba- j..:J. operable or have operbilitv in order for CAM1or' hat requLres holesaie the applhcdt.rn of thse crter- ;ind a requirted svstem. structure. or consid-ration of systeis. structures. Calmte , on a plant.snecfi- - component to be operable. and cornmonents with:n the rc9e f The _.=:;ssior CanLs2ot ttr. . - The Commission previously techrnicai specificatons na "rr-:C!U.S7M.S e a .. ... U. th;:S*b...l< :-e.maui.1 n,flr. atwJ': considerd the teeiuucal specificaion approp.nIsly foc-s an.i NRC - I - ~ w- -_

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Federal Register I Vol. 60, No. / Mondav. Mav B. 1995 Rules and Regulations 224

additional systems. structures. and Commission's mtent. Therefore. the plantspecirc expeneace. industrv-wi components should be included in an Commission determned that 'required operating expenence. as appropnate. individual plant's tt-hnical function" in the previous license and existing engineering evsluations t specifications. Howeve.. the renewal rule refers to thuse funcuons determne those systems. structures. a Commisston cn conclude tat these that ar resporsble for causing the components thai ae the mutial focus additional systems. structures. and systems. struCturs. and components to the licene renewal review. comporents ae of a relauvely lower be considered important to license Considernuton of hvpotheucl failures safety significance because they a. by renewal. that could result from system ex-lusion. nonsfey-related sstems. To avoid anv confusiom with the interdependences. that are not part ot suctures. and components whose previous rule. the Commission hAs the current likensing bases and that failure cannot prevent the performance changed the term "q uired function to bhve not been pmrviously expenenced or reduce the availability of a safety- "intended function" and explicitly not required. relited system. ructure, or component. stated in 54.4 that the inteDded Several commentets noted that the Addltionally. the Commission believes functions for systems. sntctures. and word "directly" did not preede the that the ecisting rgulatory process for components are the same functions tat phrase '"prevent satisfactory these additional nonslety-related define the systems stuctures. and csompllshment of any of the IucuoD systems. sucurus. and components s componets as being within the scope iden2iSied in parguphs faMil(i). in]. c adequate to ensure tit ae degradtion of the final nil. liii of this sion~ in 5 54.4(l(2) and will tot result n a loss of functionality (iii) Bounding the Scope of Review concluded that. in the absence of the in accordance with the CLB. word 'diactly.- the license renewal The Commission blieves that there is Pre-application rule iplementation review coTtld casade into a review of sufficient experience with its policy on has indcated that the descrption of second-. third-. or fourth-level supporn technical specifications to apply tat systems. sructures and components svstems. The Commission raffirms itu policy generically In revising the lcen subject to revies for license renewal position that consideration of renewal rule conistent with the could be broadly interpreted and result hypohetical failurms that could result Commission's desire to cedit existing in an unnecessry expLaSion Of the from system interdependencies that ci regulstory progams. Therefore. the review. To limit this possibility for the not part of thE CIA and that have not Commission cncludes that the scoping categoy relating to onsfety- been previouslv experienced is not technical specication limitiung related sysems. suctu. and required. However. for some license conditions for operatin scopLng components the Co-mission intends renewal applicants, the Commission category is unwan2nted and has deleted this nonsafety-related category cannot exclude the possibility that the requirement thit dentifi syss. (S54.4(a)12)) to apply to systems. hypothetical failure that are port of t) stuctures, and components with structures. and componensm whose 02B may req ure consideration of operbility requirements in technical filure would pvet the secad-. third-. or fourth-level suppor. specifications as being within the scope accomplishment of an intended stems. In these cases the word of the licenS rnowal rview. hntioo ofa safey-relaed system. "diretly" may cause additional strucu and componeuL An applicant confusion. not clarity. regarding the fill Iiended Function for licne renel should rely on the systems. structures and components The previous lcnerenewal rule plant' C.8. actual plnt-spcific euired to be within the scope of required an applcnt for licenxe expmrence. industry-wide operating licenxe renewal. In removine the wotrd renewal to identif. fr msystems. expenencv. as apprpnte. and existing "direcly"' from this scoping criterion. strucures. and componenus important engineering evaluations to determine the C:ommision believes it hasIl to license renewal. dhosastructun:es and those nonsafety.related systems. achieved gmater consmency between components that contribute to the structures. and componenttat uan the the scope of the license renewval rule performance of a requin;d function" or initial focus of the lices renewal and the scope of the maintenance rule could. if they fail. p-nt systems. review. Cnsideration of hpothetical (S50.65) regardng nonsafety-related structures. arid components from failures that could reult fom system svstems whose failure could prevent performing a "requiied function. This interdependenciaes that re not part of sausfactory accomplishment of safetv- requimment nitially pOe some the CL andthA have not been related functions and thus 123prrnoote difficulty in conducting pre-apphcataor previmsly ie enced is pot required. greter efficiencv and predictabilitv in reviews of proposed scoping Likewise. to limit the potental for the license renewal seoping process. methodologies because it was not clear unnecessary expansion of the review for The inclusion of nonsafeiy.related what was meat by 'requu}d function." the scoping categry concerig those systems. struct-re. and comporents Most svstems. sutures. and svstems. structures, and components whose failure could prevent othu.r components haVe nior tan one whose function is rred upon in cenain svstems. structures. and components function and each could be egarded as plant safety analyse to demonsate from accomplshing a safetv function i ..a uired.- Although the Commission complisn with the Co ion intended to provide protecton aginst could have reuired alicensee to ensure r uitos(i.e.. environmental safety function failure in cas where all functions of svstem. structure. or qualifica8ton staton blacout. the safetv-related structure or component as pan of the aging anticipated tansent without scrum. component is not itse ' impaired bv ag management review. the Commission p reie thermal shock- and fire related degradaton but is vutnerable tr concluded that this requirment would protectionl. the Comssin mtends failure from the failure of another be unrtsonable and inconsistent with that this scoping category include ail structure or component that ma; be so the Cormission's origina intent to systems. sructures. and compcinents impaired. Although it mav be focus onlv on those svstems. structurs. whose function s relied upon tO considemr outside the scope of the and components of primry npcrtance demonstrate comian wth these maintenance rule. the Corn.mnssion to safet CUsidelItIon ot ancillary Commission s rgulatons. An applicart intends to include equipment tnat is n functions would expand the scope of for license renewal shouid reiv an *he seismically qualified located ncar the licens renewel review bevond the plant's cmrrent iicensing bases, actual seLsMically quauifed equipmcnt ti c r -11- - 11

Z2468 Fed" i gte i Vol. 6o, No 8 Monday. Mav . 1995 Rules and Regulations

Sesmic Ul equpment -lradv stuctums ard componts trm en PRA;, the Commsson concludes tt it identied a plfit CB) tI tis st of aging u negewent rewiw Tberefore. is inappropnite to tablsh licen noasaktv-mIated sams.trctr the Commson bellwes it is meneval scopang criteion. s suggsed and clmponaam inapproprate to furtr reducx the bv Ilisnois. that mlies on plant-specic ba of Us cmats the SA svstems. structoia aud comfaoens probabtlistic alWves. Therfor. within Club mdiated t1 all _M v-rLatsd wihlin the Scope of licese enewal the constut of the final ruk. PRA equqmet an -qwrd hmnts RegaJding the uJ of proa c techniques a of vne mited use for should be coxidered bemuse fius nalyses s the bceni mnewal scopin lienw rnewl wcnng could o untAld for a long perod of process, a 5praSesto [.civ) has litlies rnewal. probeldistic time and strtaehianctum ttat been added to the S4C to dl2a the methods may be most uselul. on plant- could lead to cAtastropuc eens role of pobabilstic nsl assesme in specfic bas, Ln belping to amss te Nevado also proposed a fuel lifecvcle license renewal. Regardng systm. relative importance strctutes and approacittoliA renewal thawould suuctures. mad compoents ruimd to cetmpaons at a subic to an agng consider the pSt oputsnons as an make protatva aciow mwiagement eviw by lping to draw *Interated Opetg Svsn." T- e edatio. the Comission attention to spfic vuInnbshies (e.g Commission disagree, with the Sira thoroughly evauatad ergeDcy reslts of an [WE or EE3. Probabiistic Club comme and the Commission P haniocmdeson in tbpre"=s argumn may ast n developmg an concldes that the lIens renewal icene r l nlemk Thse appoac l agng management approach prapand by Nevada weld evaluauo d colusis Teill adequacy. However. probbibstuc result in the consdetion of ums vald and can be found in the SOC for arguments alone will not be an outsde the scope of this rule and r1lt the previous If mn sm uie (56 FR acceptble basis for concluding that ft 64943 at 69. Thot he those s 5uuresnd compornts subjc sucm. an cponts that ame no Common coludes tbt sytems. o an aging maaement review. the directly relaed iD the safe ope an of structu ,d e qu for effects of agig wiU be adequatelv th pan for th pernod of erne emerencY p . i they managed in the period of extended operon 'Tha oms the s citeria in 544. oult operatiL be the fccus ofa icns renewal review Illinois also indicated that as determiid shstiteattune I)reflect an (iv) Use of Probabiisc Risk probabilistic insights are more fully approprat deru ol the axusing Asman an Lns Reews: integrated with our taditional regutry pr 2iI. pr opery focts deteinitc methods of regulation, the initial cene w reTVIW on Severa comnmets hm illns they may defin a narrower safety focus. the system. suuu. and concirned tio use of proiebilsuc Thus. the use of probabilistic insights components thU are m stmportat to analysis technique inthe Hiense could reduce the scope of the very safety and (3)wili nt result in an renewal process. Winos indicated that programs that the license renewal rule unwmrnted rexamination of the the NRC should requie ngorous credits for montorng and identif%ing entir plant probabilstic arilysa. reqir th ee the effects of sging. On cme=ter zn.cazed that rhe analyses to be used in appropriate The Commion reffirms its scope af svstems. strUctus Dd rgtoy applili. and require previous conclusi (see 6 F 64943 at components considered for bcease these p r analyses to be 649562 that PRA techniques are most rene-l could he further reduced by updated. as beeded. In addition. Illinois valuable when they focus the identifig and addrtssag the very few noe that the preios rule and the traditinal derewing"ic.based issues in whih a plant's dgn must propcsed rule did mat requie regulauons and suppo2 the defense-in- speaflcLly coser 40 yea of consideration of individual plant depth philosophy. Lnthis regard. PRA degrdation in one of its comments. em ation l results. The Coision is finalizing a poijcy methods and techgques would focus Illinois suggeeted that those svstns. regulatwnsand progmms on those tems structue and companents required to sitement regarding the tncreaed use of protbilisuc rt assemment IPRAJ most mporan± o safty by elnunating nitigate a squnce ceading to cor unnecessary conservatism o by dmae as determined by plnt-spcxllc methods in nuclr regulatory actitis 159 FR 633W9. December 8. 19941. su pporungaddxomal regulatory probabilistc anaW,me and those requremtts. PRA inszghts would be sA-stems. stuures. and -omponents However. the is curenttv no additionul guidace for icnsees to used to more clearly define a proper required to make protmeuve acuo or reconmndations for the prteton of conduct mote rigorus pTobilisfic safety focus. which mav be iarrower the publc- should also be ianduded in analses becond the guidance for an UIE may be broader. In any case. PRA li the scooe of this rulemaung. and an [WE ternal Events IIPEEEI not be used to usufy poor performance As the comrmter sugged. the (Genefic Letter S6-201. The mnaging management or to reduce Commisson's considertion of regulatory pgrarmatc Commssion did cmsider further requiremens o the exnt that the limiting the scope of lcense rereal to regulatory ruirerents assoctated with imPleMentati O of theregulaUO or issues i developing. maintaining. or using ertain a plant's digu that pm is no loner adequate to cedit weri specificallv based on a ume penod probabilistic aalyses is bevond the for monitonLng or identdvng the effectS bounded bv the wtt license tem (40 scoe of this rukmaking Ot aging. vram). As a esult, the Comm,ion I e B for currentiv opemung explicitly identr5ed te ne- to review plants as lrev based on determinisuc d. The Regulatory Prcrs nd .AngS time-lurited agig analyses and engineenng aitena. Conswcently. there Monagement is considerable logic in establishing incorporated ilis requzt into the (i3 Aging Mmhnams and Effecis Ot final rule. However. as dismissed tr license renewal scoping crtena thal Aging Section lfl,d aDd II of ltis SOrC the recognze the deteministic nature of a Commission determined that. at this plant's licensing basis Without the The license renewal review approach tame. thee was not an adequae bas to necesarv regulatory requirernentS and discussed in the SOC accompanying the genernUv exclude passive. long-lived appmprate cntrols for plant-Pec3fic December 3. 1991. rule emphasited the . ... -- -,----. - . -- -

Federal egister I Vl. 0. No. B8 Mondav. Mav . 1995 1 Rules and Regulations 22459

identification and evaluauon of agng procss will sull need to be adequate to because the MTIs ide,.tifed some mehaniss for syste=s. sructures. and address amn nrtantis. common mintenanc .tated components ithin the scope of the When the Cormnission concluded that weaknesses. such as .idequate root- rule. Prumarly througi peapplacatcon the proper approach for a Leense cause analvsis leading to repetitive mplmenAuoa experence associated renewal review was one that focused on faulures. Lick of equipment performance vit t- prvus Lcens menwal rule miigating the detriental effects of tending. and lack of appropriate and the .viluatios of commena aging rgardless of the mechanisms considertion of plant risk in the resulting bo the September 1993 caas1ng the affects, the intent was to pnoritizauon. planning. and scheduling hcense renewal workshop, the conctttrate efforts on identificaton of of maintenance. Cam= toin determined tbat an huncional degrdation; that is. except The ComnUssion amended its S; ?1`0 to lnse rnwMal tAt foCUSes for well-understood aging mechanisms. regulations. at 10 CFR 50.65. on Julv 10. col, on the identficaun and the strughtforward approach to 1991 (56 FR 31306). to require evaluation of agng mechans aould detecting and mitigating the effec,. commercial nuclear power plant conttute an opetindtd reseath agng begins with a proce that - . es licensees to momtor the effectiveness of prow.c. Ultimtely. this typ of thAt the intended design hnctions of maintenance activities for safetv- approach may no rvd reasonable systems. strucum. and components sigrificant plant equipment to minimize assuwre that cean systems. have not beaD compromised or the likelihood of failures and events smotures. and components will derded. Once hfnctional degdation caused bv the lack of effective coninue to perform th: intened is identified through performnce or mrtintenance. The muntenance rule and functos Ths Commisioni behaves condition monitoring, corrective actions i..impleme. * guidance (I)Provide that regardle of the specific aging c be pphed. The Commission agrees for continued t tiasis on the defense- mechatism only ag degradation that that adver aging effects cannot be in-depth principle bv including selected leads xn derWd perfrol or completely divotred m an balance-of-plant (BOP) svstems. coition 1L.. dtrimetal efes) underst,ading of the aing mechanisms. structures. and components. (21 during tbe penid of extended opation The corrective actions thut sbould be integnate risk considerauton into the is of prinipal coes foa licee taken foUowing de tfication of maintenaDce process. [3) provide an renvew. ERuse the drimenal effet functioal deprdatio logically include enanced regulatory bass for inspectio:r of gngan anfstd in degmded determnstion of the cause of the and enforcement of BOP maintenance- perfornLec or conditio an degradation. whicb could involve related issues. and (4) provide a licn renewal review mechanisms other than ang (e.g.. srengthened regulatory basis for u ure thu cens progrms fauty manufacturing procese. faulty ensuring that the progress achieved to itely mnitr pe o maintenance improper opertion. or date is sustamned in the future. The condtion in a maurie tha allows for personnel ern1. If or mowe aging requiements oF the maintenance rule the tiey identification and correction mechanisms ae the cause of hnctional must be implemented by each licensee degradatou. corrective actions should b July 20. 1996. of degaded condition. The focus. as applpriate. a prevention. ln June 1993. the NRC issued Commison conclues that a Sift in eliminatioL or man en of the Regulatory Guide ".1.'Moitoring focus- to ithe effects caused by the mechanism(s) in the Effectiveness of Maintenance at efecsof gi fornsrewa the futur T se required by Nuclear Power Plants." The regulatory revtes is appropnate and will provide current rebulations to develop and gulde provides an acceptable method for rasoable imun that systems. implezent progTms ta ur th complying with the requirements of the stctures. u:d components ae capable conditions adverse to quality. including maintenance rule and states that a of performing their intended fulnction degraded system structure. and licensee can use alteative methods if duing the period of extended opation. mponent funcion. a promptly the licensee can demonstrate that these T4is sSh in focus of the license identifed and corrced. fitenative methcds satisfy the renewal review bas resulted In several requirements of the rule. Because aging prposed changes to the licens renewal (ii) Reglator Requirements and is a contLnuing process. the Commission rule. These chane indude deleting the Reliance on tie Reguatory Process for has concluded that existing programs definitions of ang mechanism and age- Managmg the Effecu of A&g and regulstory requLrements that relted degudaton aid replacing the Commercial nuclew power plants continue to be applicable in the period requirement to manage ARDUTLR in the have been performing a varety of oi x=ended operation and pro..ie EPA with a requirment to demosutate maintenAnce activities that function adeuate aggng management for svstems. that the effects ofaging will be effectively as aging management smrctuses, and components should be adequatelv managed for the period of programs since plants were intially credited for license renewal. extn ded operation construted. The Commission also Accordingly. the amendment to the Illinois commented thati additional recogizes that both the ndustrv and license renewal rie focuses the renewal reerch should be undertaken to ensure the NRC have acquired extensive review on plant systems. strutures. and aIlagin effects ae understood. experience and knowledge n the area of components for which curent activities Mitigating the effects of aging cannot be nuclear power plant maintnce. aLd rquirements mav not be sufficient completely divorced hf-n Rerding the need for a maintenance to manage the effects of aging in the understanding the aging tnechanisms. rule. the results of the Commission's penod of extended operaton. Illinois indicated that the effects or maintennfce team inspections MTIs) Since publishing the license renewal aging On a system. structur, and indicated that licensees Sner4ly have rile an Detember 13. 1991. the component cannot be managed without adequate minenance programs in regulator process (e.g.. regulatorv some consideration of all the aging pace and have exhbited an uniproving requirements. agtng reseami. inspection mechanisms causing the effects. As trend in umplementing them (56 FR requiements. and inspection some aging mechansms am not well 31307. Iul 10. 1991). However, the philosophy) ror managing the understood. research will still need to Commio determined that a detnmental effects of aging for be performed. and the regulator maintenance ule was needed. in pat important systems. structures. and I

-40 F -edelR r0/ onayo 1 Res--eg-

22470 Fd Retr / oL 60, No. a / Monlday. May . 1995 Rules and Rtegulalons

components bas continued to evolve. monitoring at the component level may failure of any licensee to comply with The chanes in the regulatory process be necesary, altliough. most of the the maintenance rule is enforceable by and iitial experience with the license monitoring could be done at the plant the Commission after July 10. 996. znewal rule have h a direct bearing systm, ar system tin ltvel. For One commenter stated that reliance on the Comnmission's conclusions systems, stuures. and components on the muntenance rule is regarding the appropriate ocus of aging that fall witLin the rquirments of ins *propriate because the NRC does not m 8pment renew for systems, S 50.65(a(1), licensees must establish plan to scrutinize every system. structur. and components that are goals and monitor performance aginst -sucture. and component and how it is within the scope of the licens r wal these goals. These goals should be monitored in assunng compliance with nle, and how hese systems structures. derived om information in the CL. the maintenance rule. According to the and components ae sed in the IPA and should be esablished commenter. If there are uncertainties in proce". commensurate with safety signcace the maintenance rule or its (iii) Maintenanre Rule Requirements of the systems. Structures, or implementatiun. then there is and Implementaion componentL These goas ay be uncenainty in the license renewal rule. performanCe.Oniented (rliability. The commenter also stted that the As discussed in the egulatory unavailability) or cdtion-orented aging management analyses and anysis for the maintenance nae and in (pumnp fow, pressure. vihrtion. valve messurements equired by the licene Regulty Guide 1.150. the stroke tm. currnt. eerical renewal rule for the period of extended Comtmission's detrmination that a resistance). An effective preventive operation should commence for all maintenance rule was needed arse mainteneacc program is required under operating reactors when the rozn the conclusion that proper S 50.651a)f2) if mnitaoing under mainstenance nle ges into effect. ne maintenance was essental to plat S0.6Sal l) isnot perford. NRC disagres with the comnmenter that safetv. A clar link exists betwen The SOC for the maitenance rule (5 the 100-percent inspecton of all effective mainteance and safty as it FR 31308 July 10. 1991 sates that the system. smictUes, and components is mlates to ctos such as the number of scope of 5 50.55(aX2) Includes thos necessmy o verify compliance with trnsients and chlenges in sfe. systems, s ,uctures.and components NRC mquirements. including te related ems and the assodated need that have "inheentlyhi.h reluahiUty" maintenanc rule. The Commission for opeability. availability. and without intace It La expected that disagrees with the commenter that the eliahility of sfety-reled synems. many long-ved, passav. ructures and licenses should be required to structure-. and components. In additin conIpoamts coula be consideed commence aging management reviews O('d maintenance is important to inherntly reliable by ienees nd not reTuird for license renewal wben the providing assuzance that alues of be moitored under 10 CFR 50.651a15). maintenantrule becomes effective. other than sfety-relaed stems. Thu my be few. f any. actie As discused n the SOC for the stnucrs. and componensm that could mainetance ctivities e.. nspection previous rule 56 FR at 649S1) the NRC initiate or advenely affet a trnsien or or condition monitoing) that a licensee inpection methadology utili a accident ae mi-mizvd. Minimizing conducts for such suctue and sampling t-nique. When problems are challenges to safety-related systems is componens. Further, experc gained identified. fii inspection sample Ze s consistent with the Commission's under the previous licese renwal rule broadened to dtmine the tent of the defanse-in.depth philosophy. nerefor. staf raview of industry reports. NWRuC problem. Additionally. whie the nuclea power plant maintenance s agigeserc. ad operti maintenance rle doe nort rquur clearly impotnt to protecting the eprece Indicate that such strure lioenes to submit their maitance public health and safety. ncomponet sould be reviewed for programs to the NRC for review and The maintenance rure requis tat licnse renewl If they a pasive and Approval, cOmplianc with the power reactor licensees monitor the longlirved. Therefore. the Commisio reuiements of the mintenance rle performance orcadition of systems. believes that such structures and will be fied through the NRC stuctures ad components again com ponens ca are techuiy within inspecuon pnss. The NRC will be licensee-established goals in a manner the scope of the mntennc rule conducting inSpecuons on a routine sufficient to provide reasonable should not be geercal exclud fo basis ate to vrly licmnse assurance that these ems. s.ctur. review for lics renewal on th ba complance with the maintenance rule. and components are capable f lfilling of their inerent reliability. Furthermore. as discussed in Scton their intended functions. Peforuance Although the Maintenanc rule does MIldMiv) of this SOC. the aintenance and condition monitoring against not become effecive nd eaforceable rule allows for moutorng at a tain. liucensee-established gols is not until uly 10.1 996. the Commison systen, or plant level. and hat goals required. wer it can be dmonstrzted believes tat cediting the rle (along should be commensute with saety. that the performance or condition of with the entire uatory progam) is perfmanc problem arise. corrective systems. structures, ad components is a:cceptable to support mnaging the action requirements cf ID CFR 50. being effecuvely controlled through the ffec of aging for cerain systems, Appendix . and he mitenance rule performance oappropnate preventive nuctures. ad components. As requite effectve corremve actons to maintenance. erformance and discusd In Regulatory Guide 1.160. precude repeuoa of the ilure. condition-monitoring atvities and implementation or ie maaintnaceU nle Passive, long-lived structures and Lsocated goals nd preventive relies extensively on easting components tht a the focus of the maintenance acziViLies must be mintenance programs and activities. Ucense renewal rule re also within the evaluated ance eery reueling cycle. he indusy has developed guidance requimntts of the maintenance rule. provided the interval between for complying with the tnntenance as discssed in the SC Section evaluations does not exceed 24 months. rle and the '.C saffhas rviewed this 1id)l(vi. Treatment of these ures As duscussed in Regulatory uide gwdmnce ani .ound it accepLable. Manv and components. however, under the 1.160. te extent of monitorjng may vary utilties ae expected to llow he manienLnce rule is likely to involve from svstem to system, depending on industy guidAnce In ImplementinUg the minnal prevenuve maitenace or the sstem's porance to risk. Some mantenance rule. Furthermore. the monitornng to zaintaAn ncuonality ol Pederal Register Vol. 60. No. 88 Andav, May 8. 1995 Rules and Regulations7 2247

such structurs anc ponenLs in the that liceansee aiviues asscated w2th maitenan ruie. Therefore, ar these ongnag operating period. Consequently. the implementaon of the mantenance reasons and as dicussed in Section under the license renewal rule. the rule will continue throughout the llL(d) of this SOL. the Commission Coinmmuioo did not allow for generic renewal penod and are consistent with continues to believe that them is a exclusion of passive, Ion-lived the fist principle of license renewal is sufcient basis for concluding that anctum and components based solely fundamental to esiashin credit for current license progrzas and acuvitie: on maintarace acutvi assocted the euist1ntproparm and the along with the regulatory pr,-. will with mplmnng the requirerne of requimnts of the -aintenance nle. b edequate to mae the effecs of themaintenance il. also would be Asa *st. the ruirements n ths rule agig on the active functions of all toappote to requir at al flect a Stner rel on existn systems. srutues, and componets4 cnss perforo an agng management licesee pogrms that maage the within the scope of lit:ense renewal revew reuie for Lns ineowa detrimental eects of agg on duning the period,of extendedl operatior when som lcnsee y ot seek functionality. including those ctlviLies so that theCLU will be maintained. lis rnewal and do not in to imlpleeted to meet t requirements In addition to the maintenance rule. opate beyond the end of their current of the raite nile. the Commission has many individual operating licnse. Furtharmr.fa Two comments sated that t Is requiremets relative 10 zaintenance issus are identified dur the le inappropriate for the license renewal throughout its regulations. These renewal review that apply to the c rule to rely on the maintanance rule indude 20 CFR 50.34(a)(31(i); opeating term. icenees e uted to impentIon bause tO CFR 50.65 SO.341a1(7J: 50.34(b)l6) (i). Iiil, (iii). and 2ae easus unde their cumu will not b, i effect until July 10. 1996. fivl: 50-34(b)1:50.34(f)(1) til. iil. (Iii; licius, to ensu that the intended 50.34(gl: S0-34ac1; 50.SStaJ Tho ission -dies with the 50.36(c) (Z1 hcton of system. structur . and com nlt A diA s iedSecio (34. (S). and (7): 50-364(al I k 50.49(b): components will be manutined in D1. ff) and (lii) of this SOC_ the results, 50.55alg): Part 50. Appendix A. Criteria cOrdance with the CLB trughout the ofthe Commssion's Mlindicae that 1. 13. 18.21.32.36.37,40.43.45.46. tea of the crrnt license In addition. 52. 53; and Pat 50. Appendix B. if aging ssu ae identified during the liceansm h adequate maintenancza Ucean renewal vigw that apply to the progrms n place and have exhiblited an (vl Excluding Sructurs and current operating term, the NRC wil} improving tend In Implementine them. Components With Active Functions evaluae t isues for genenc Nuclear power plts have been Peformance and condition epplicbillzy " part of the egulatory perfrming vriety of mainteance moitoting for systemns. structures. and aecivities since plts ware bitially components typically involves Therefore, the Commission belevs costztd Mm needforta fuinctial verification. either duc:ly or that with the ddionizl eence It maintanance rule aoe prmarily indirectly. Direct veriication is bas ained with age-a degraat because the MTI identilied three pcucal for active functions such as reviews d with the implemmUton of common maintenanc-related pump now. valve suroke time. or relay maintenance rule- them s a weakness (idequate mootcause actuation when the parameter of sufficient basis for concuding that analysts.lad of eqclpment performance concem (requued function), including current ia programs an activitdes. trending, and lack of appropria any design rm-n. can be directly along wih the regulatory pocess. wiu cz,nd n of pat risk in h dmsured or observed. For ive be adequte to munge th effe of p ittto. plnningand scbeduling functions. the relationsip betwen the aging n ati funcions or a of maintenance). Addition&ly, the SOC meaurabl pers and the rquirtd systs. stntou. and components for the maintenance rule (s ER 313101 function is less directl verified. Passive wthin th cp oflicense eewal sates that tTlhe ffo of the rule is on funcions such as preisure boundary duf:ng th peniod of exed operation the resit achieved through and strcaur.l integnty ae generally so thartl 1Bwill be m.Julid The maintenance. and-L this regard, It s verified indirmtly. bv conarmation of baes for this conclusion are discused not the intent of the rule that exsting physical dimensions or component futher in the fouowng sectias licensers necsarily develop new physical coWdton (e.g.. pipine mAintenance progems.'- Furthermor. structual integrity an be predicted (iv) Integration of tbe Regulatory P s as staed n Regulatory Guide 1.160. it bed on me d wil thic}.ness and and the Maintenance Rule With the Is ntelded that activities currently conditim of suctural suppons. but Its Icense Renewal Rule bei anducted by licensee. such as seismic e ce capabilitv caUnot be Because of the resltant insight and techical specfication surveillance verified by inspection alonel. Although undeandLg tha the NRC gaied n testing. can satisfy monioring the requirements of the maintenance developing the implemntation requirements. Such activities could be rule apply to sems. structus. d guidance for the maintenance ule. the intemted with, and provide the basis compots that perfom bcth acuve Cosmission is now in a positio to for. tho requisite le ofm i ritg and pasive fiuctons. the Commission more Fully integte the maintentnce Finally.a t the time of this r has determined that perfomance and rule and the licerne enewal le. nine licensees volunteered to partcipate condition-monitoring progrms for Berue the intent af the licease in an NRC pilot inspection offo to structues and components that perform mnewal rule and the maintenance ule rview impementation of the passive functions present limitatcns is similar (ensuring hat lhe.detrirental maintenance rule. Five piot inspections that should be considered m effects of agmg on the functionaity of had b{ completed at nUclea power determining that sumtures ad importnt systems. structures. ad plants. The pilot inspections involved a components can be genencallv excluded components a eecuvely maed). step-by-step review of the from an eang management reiew for the Commi-mion has dtermined that t implemnation ofthe main nance lcense rnewaL l.cens newal rule should =dit nle. n generaL the pilot inspecuons On the bass of consideration ihe &j&sting maiDtnan setites and found that licenses wer able to utize effecnenem of euitm programs wnich mna tenancarule req Srotans for mnst existing maintenance activities in monitor the performance and condition structures and component Recogitoa complying with requirements of tle of systems. structures. ard components - - --

22472 Federal Register I Vol. 60. No. 88 / Mondav. Mav 8. 1995 I Rules and Regulations that perform active functions. the can be excluded from an Aging from an aging management review Commissoan concludes that str%ctures management review. The examples because they ae either within the scope and components associated onlv with given by the commenter for catastrophic of S 50.65 or S 50.4B. Compliance with active functions can be genencally failums ar those related to "passive" S0.4B is verified through the NRC excluded rom a lcense renewal aging intended functons (e.t.. structwu l inspection program. m gement review. Functional integnty, pressure boundary). It is the The fire protecon rule 1S 50.461 degradation resulting frm the efrecus of Commission's intent to iclude these reqrs each nuclear power plan: aging on acuve functions s more readily ' passive" functions in the license ICenSee to have in place a fi determinable. and existing progrms rnewal vew, irrespective of the protection plan tFPPI that satisfies 10 and requremets are expected to components "actve" function. For CFR Part 50. Appendix A. Criterion 3 directly detect the effects ofiaging. example. a safety sytem pump casing Licensees are requiired by 1 50.48 to Considerable experience has (i.e., pressur boundary function) w Id retain theFPPaDd each change to the demonsated the effectiveness of these be required to be mewed. while tht- plan until the Comnmission terminates programns ad the perfoannatsed pump (i.e.. the actve pumping function) tDer eor license. The NRC reviews requirements of the maintenance rule would not. The Commission believes ec licensee's total FPP as descrnbed in delineated in S 50.65 ar expected to that considerable expeience has the licensee's safety analysis report futher enhance existing maintenance demonstted that its egulatory proces. (SAR), using basic review guidance programs. For example. many licensee including the perfonman described in 5 50.48. as applicable to progrm that ensure compliance with requirments of the maintenance rule. each plant. technical specifications am based on provide adequate asurance ta The FPP estabishes the fire surveiLlance activities that monitor degradation due to aigof stnutrs protection policy For the protection of performance of systems. stmctures. and and components that perform ctive Ptemns, struresn ad cmponents components that perform active nctions will be appropitly managed imporant to sfty ateach phantand the functions. As a result of the continued to ensure their continued functionaliy procedures. equipmn snd personnel applicability of existing progrms and during the period of extended operation. requirements necessary to implement regulatory requiements. the In additio to address the NEI and the pm t thc pt site. hNCFPP Commission believes that active Yankee Atomic Electric Company is the integaed esort tat ivoles functions of systems. structur, and comments, the Commission has systems. stctures. nd components. components wil be reasonbly assured removed the words "portions of" and procedures. and personnel to carry out in anv eriod of extended opertion. similar wording rom the Sttement of all ativities of fir prtection. The FPP Further discuon and justification for Consideations when it could be includes system and facility design. fire excluding structures and components sinterpreed to mea a suoponnt prevention fire detection. annuation. mat perform active fnctioDns and are piece-p demosion. confinement. suppression within the scope of the license renewal A comrenter argued that the adminiatv controls. fire brigade nae. but outsde thcsL 'eof tbe Commission should not exclude from orpaoization. Inspection and maintenance ile. are presnted in review manual valves that are rely mteance. trunin. quality e Section vi) operated during the life of the pnt. asurant nd test. One commenter argued that the some of which ar relied on as part of The FPi is part of the sR nd Commission should not exclude active contingencyactios in plan emergency contans maintenan and tesIng components because aging can be operating procedures The cmmenter crniar that provide reasonable discontinuous. leading to catastrophic argued that because these valves e aunc tht fire protection systems. failures. Examples of catastrphic Irly 'officially" exercised. te is structures, endcomponents are capable failurs provided by the commenter insuffirient eviden that the active of perforing thir imtded functeon. included overetretching of metal, functions will be maintaied in the phe Com ision concludes that it is bending of bems. and embrittlement In renewal period. The Commission appropate to allow license renewal their supplemental comments. NEI and disagrees with the commenter's appicnts to tra e credit forthe a Yankee" Atomic Electric Company asrtion that there is insufficient an eisting progn tatnanages the indicated that the use of the tenm evidence that the active funcions will detrimental efects of aging. The *pontons or, could be misinterpreted ~-e maintained in the renewal period. Co ion cncudes that inalled and lead to an unnecessar evaluation Such valves are within the scope of fire protection components that performn of all passive subcomponents of acuve atous regulatory pogams including actve fctions can be gene call structures and components. the maintenance rule. Consequently. the excluded from an aging management The commenters appear to have ability of the valves to perform their riew on te basis of performance or misunderstood the Commtission's intent intended function must be ared condition-monitoring prgrams aforded with regard to active" and passte- through either (1) effecve preventive by the FPP that are capable of cetectmg functions. Passive parts of structures maintenance or (2) performance or and subseque tly miptatng the and componens that onlv perform condition monitoring- detrimental effects of aging. active functions do not requir an aging management mview. Structures and (vi) Exrluding Fire Protection lvii)Future Exclusion f Strmu es and components that perform both passive Components With Active Functions Components on the Basispef of RC and active functions require an agmg The scope of the maintenance ule Requirements mnagement review for their wntded does not geneually include installed fire As pant of the ongoing regulato. passive function only The exclusion protection systems, structures. and procs the NRC evaluates emerging regardng active components is focused components because performance and technical issues d, when warranted on active funcions rather than on an condition monitoring is mquir bv establishes new or revised regua n d Axclusion of the entire component. For S 50-48. Therefore. for the purposes of reuirements a pa of the Resoluton of example. diesel generators and air license renewal. installed strucitres and a new technical issue, subaec to the compressors (excluding stuctural components that perform active provisions of the baclfit rule (5 50 1091 supponsl perform active functions and functions can be genencallv excluded Increasins expenence with aging - - - r - -" t...------Federal eistr I Vol. 60. No. 88 Monday. ,y 8. 9M I Rules and Regulations 224

nuclear power pLants has led to the Copilation of the CLB is unnecessary operational concens and suts at imposition or conuderauon of to perform a license renewal review specific plant - idenufied to additional quiremnu. For example. Oneo commcnter augued tht tbe demonstrate he undequscy of the at this time the Commission is definition of CLI in s 54 should be Clis. One comnter std that the considefin rulmmaking actvities clarified Specifically. the commentur Yanke Row, or presure vessel asoatoed with steam geeator interpets that licensee wnUeh prolem Ite plant was rmnoed from performance and contanment commitments made in docketed serice rather than shw compliance inpWcWo. Fot steam geneto, the licensing corespondence such as with its r.I8 for its rctor pres.sure Commison is co rnog the nsed for tuponse to buletns. generic leners. vessel) demonstrates the lndequacv. * pedormance-bsed rule to addres and enforcement acions and 0 As. The ..ommenter suted that tht sum renetrtube integrity. To commitments in safety evaluations and Rowe experience demostrated that addrss conrc rgdin License, event repons (itesrs in the third exmiton of te licznsang basis for amtaints and liris the sence of the dePuition) should be extended opertion could eopard e Commission is consideig amending consdered as part of the 0.8 only to remaining yeas on the current llcens Sso.5S(a) to Incorporate the r rc the extent that thes commitments The Conmuanoz did -t agre with vmion of Subsecions IWE d IWL in eflt Compliance with more formal the comments on the previous rule in the American Socety of Mechanical requirements ad regulations. Thee this a and comments received for t1 Engine (ASME) Code. Sedion XL would Indude thse elements of NRC rulmking did not provide compellir. requirements and regultions identified Then new Mnieetvi rus to lter the previous impleted.w ould be rlev to bot in the fint two sntences of the CornisAon deternunauozs. The aing managment and the stiur definition. AU other cense exampes ited wero all identiied lby and aponents subject conmfmews identified in those the NRC thrugh the inspection and to an aging document types lsted In the third overligM processes. The identificatior. managmet eview for I mrnew'l eentence should not be considered CLt of tk ie through the regulatory (i.e.. p1m. hU"lc v.d snuctum and commitment if thev are not otherwise ps demonstates that the componem. A a resut. as p of necsay to demonsrate complianc Commi sionS progpm areseifcri e * wevn f e ruemakings. the with NRC juquirements and regulatio Commission intds to evahuat identifying and resolving new technic. The Commisson is aware of public ad WeMy ises and aes of whethwh new requiremns: cn be _o~s asociated with the defnitlon nr mpli- in a timely fashion. n considered offecive a continuing to of CiB in S4.3. Sme of the, concwns eac example provided bv the manag the fctsocf ang thro g any abee ictly link towhlat is menters. appmprite corrective renewal tern. A postve concluman mine by ths tm t action was taken or is being taken on a ould estlish th bu for futh usuzrintnnts t reas to the CLE. planspecific or on an indus-wide limg the lice seeewal review Them conc*s latetc ongotng basis so either modifv the CL o resol c. Bwfrnai f ouons consideraton of the rTultory and the ornl r to sure the continued Coacncorik~~~ Om CurGrfr Lkcensing Bosis licse pse for defning. compli with the presmt CB. The and iMnabaingL?rFwcan of lduuifrirg. rucin. and validatg Commission apses that the Yankee Systens Stra . nd Componets licenee commineni. lthough Roww ca rnomated that the identifed in the Licns renewal rgqulr p ms cm leopardize. (i1Curl Ucensing Bais tnkig prom mny of ths curn opeation during license coa tot diretv-associaed renewal acUities. The decision to rvtu As defined in S 54.3 of the ml. the with II== renwal but gm relat to the Yanke Rgo plant was a utilitv CL is the set of NRC requireCmets current Co remmangeen ecorn decsi'-n when aced with th applicable to a specific plant and a methods and prcc T f ,the p of demonsating cv-tinued licenses wnttei commitmus for Commmisio is rvalualing conns compliance with its CLB. Non. ensurin cmplian wit and opertion msodld with the definition of CLB In complian with the CLB. while not within applicable NrCequuments the cao t of currntly operatg shown in the Rowe example. is one of ad the ptspi fl design bss reato and may. in the future. the re*s that justifies the eristence (icudn all molfrAto and detemir t the definibin of CLB the Ml pTDCBtS. additions to audi commi nts owr the needs to be claified Thus. the PuOfiicCWzen sed that the life of the license) that an docketed and Cfnmi COnclde thaL at this Cmisioos contention that all am In effecd A detailed explanation of tire. a 'evionto the defntion of C1B reaos ae in compliance with thoir the CIB. the regulatory pces Is premature and wil not be considered CLBs is both arbitrary and capru:,us underlying the C.B. complian with as nr of this nilanuking. and nihe stands the est of laOSc not the CLE. and cozsideranio of the C.B L"_X tion. the Co,,sion reitv The commenter continued by is contained n the SOC for the previous consclud thLat for the linse renem l staig that the NRC4s assumptioan is licas renewal rule (56 FR 84949: review. cnmderation of wntten based upon the specous argument that Dmber 13. 1991). In summary. the commitmens> only need encompam having opeat without a meltdown fc ondusions made in the SOC for the those commitments that coc= the a fiwtpaiod of time means thst saret Dvious rule remain valid. The C.B capability of systems. suctur, and is adequate -. presents the evolving set of compoets identified In 55211. The CmmissiLn does not contend equirements and commitments for a itgrtd pn asssmet end thaLt al reactors ar n full compliance - ;ipeCfic plant LhAt ae modified as S54-nlt Ic)m-U tdagi ays. with theespecie CLIs on a ecessay over the Wie of a plat to to per their intended fuos s contnuous basis Rather. as discussed :nsure continuation of an adequate level delinaed In 5 54.461. in he SOC for the previous rule. the if safey. Me regulaory process is the For the previous rule as well as fo regulatory promss provides asonable neans by which the Commission this rulemaking, commenus argued assure that them ts compliance with :notially assesses the adequacy of that ts CLB of a number of plants s the CLB. The NRC conducts ts ;nd compliance with the CLEL inadequawe 'e e mpes of inspection and enfortiment actinties -~~~~~ ~ a m .~ - - ~ ~ ~ ~ ~ ~ ~ ~ ~ -- -

22474 Federal Register / Vol. co. No. a Mondav. Mav 8. 1995 / Rules and Regulations

under the prsumption that non- conponents.- the portion of the CLi and a license renewal evaluaton. This compliances will occur. that can be impacted by the detnmental acuvitv will likeilv include examination The Commission does not believe that effects of aging is the design basis. Thus, of the plant itself to understand and an abwnce of accidents over a given there is no compelling reason to verify licensee activities associated with penod of time equates to adequate consider. for lcense renewal. any aging management reviews end actions safety. Neither does the Commission portion of the CLB other than that being taken to miugate detrmental believe that all nsk can be elmnated. which is associated with the structures effects of aging. Adequate safety is a subjective term that and components of the phant (i.e.. that After consideration of all comments cannot be darectly measured. The part of the C..I that can suffer concerning the compilation of the CLB. Commission's perfornance indicators detrimental effects of aging). All other the Commission has reconfirmed its demontrte that, while not aspects of tte CLi have continuing conclusion made for the p:vious rule quantifiable. relauve safety levels ae rlevance in the icenzse renewal period that it is not necessarv to compile. increasing. An absence of accidents ovr as they do in the original operatng teview. and submit a list of documents a finite penod of time can be considered term. but without any association with that compnse the CLIB m orderto as just one sdety performance indicator. an aging process that may cause perform a license renewal review Despite mproving performance invalidaton. From a patical lil Maintaining the Function of iodicators. the Commission intends to standpoint. an applicant mus consult Systems. Structures, and Components continue the meticulous process of the CL for a structur or component in surnng and maintning an adequate order to perform an aging management As discussed in the SOC for the level of protecton. review. The CLB for the structure or p.evious license renewal ne. the Commenten for both the previous component of interest contains the Commission stated thst continued safe rule and for this rulemWig argued that information desribing the functional operauon of nuclear power plant fte pla±ir-speciflccL should be requirements necessarv to determine the requires that svstems. structurms. and compiled and the NRC should veril pesence of any aging degadauon. components that perform or suppon compliance with the flB as pazt of the safety functions continue to perform in l,cenrie renewal process. Public uCizen 'Me definition of ClB in S 54.3(a) aordance with the applicable sateu that "The NIRC must review the states that a pant's CLB consists. in requirements in the licensing basis. In documents which make up the current pat. of a licnsees written addition. the Commission stated that the licensing basis and examine the plant com-mitments * that are docketed effecs of ARDUTLR must be mttigated itself in order to determine wheter the * * ' Because the documents have to ensure that the aged systems. icensee a cor Lied with the curnt aleady been submitted to the NRC and structures, and components will licesing basis." and further. are in the docket files for the plant. they adequately perform their designed submision of the documents, and NRC are not only vailable to the NRC for use safty or intended Fnction. verification of the licensee's compliance in the renewal review. thev an also In developing tis fil rul, a key with its Ci is necessary to avoid available for public inspection and ie that the Commision considered "fraud and abuse.' Public Citizen also copying in the Counmission's public was whether or not a focus on ensuring contends that laibsent the submission document roomS Furhermote. the NRC a system's. sucture's or component's of the documents the public and the may review Any supporting function through performance or Commtission are left to examine the documentation that it may wisb to condition monitoring is a sufficient rctor's license renwal application inspect or audit in connection with its basis for concluding that the Ci will and the IPA in a vacuun.' renewal review. If the renewed license be maintained throughout the period of The Commission disagres with the is granted. those documents continue to etended operation. The Commission commenter. and points out that the remain subject to NRC inspecaon and considered whether the regulatory proposed rule did not explicitly require sudit throughout the term of the process and a focus on functionWlit the renewal applicant to compile the renewed license. The Commission durnng the lcense renewal review or CLB for its plant. The Commission continues to believe fiat resubmission the period of extended operation are retected a compilation requimment for of the documents constituting the CLB suficient to provide reasonable the previous license renewal rule for the is unnecessary. With rest to the assuzrnce that an acceptable level of reasons set forth in the accompanying eommenter's argument that the CJB safetv (i.e.. the CLB) will be maintaned SOC 456 FR at 64952). The Commission needs to be venfied. the Commission c6ntinued safe operation of a continues to believe that a pesciptive had concluded when it adopted the commercial nuclear power plant requirement to compile the CL is not pvious license renewal rule that a requres that systers. structures. and necess.rv. Furtherore. submission of revefication of CJB compliance as par components that perform or support docunit!n:s for the entire CLB is not of the renewal review was unnecessrY safety functions continue to function in necessav for the Commission's review (56 FR at 64g51-5Z. Public Citizen accrdance with the appLicable of the renewal application. As stated a presented no informaton quesuoning requirements in the licensing basis of section l!.b(i) of this SOC, the the continuing souness of the the plant and that others do not Commission bas determined that the Commission's rtonale. and the substantialiv increase the frequencv of single issue genenc to all plants with Commission raffi s its earlier challenges to those required for safetv regard to license renewal is the effes conclusion thAt a special verfication of As a plant ages. a vaety of aging - of age-related degradation during the CLB complince in connection wth the mechanusms are operative. including penod of extended operation. As rvyiew of a license renewal application erosion. coffo011. wear. thermal and explained in the SOC for she previous iS unnecotssary. The CommssioD radiation embnilement. rule. scuior I.cli) 56 FR at 649481. the inlends. as stated bv the commenter. to miaobiologtcal3v induced agmg effects. CLB of any plant is cor;pnsed of examue the planiispecific CLB as acep. shrnkage, and possiblv others vet numerous regulations. blcense necessarv to mnake a Licensing deasion to be identified or fUv understood condition:. the design basis. etc. As on the continued fumcuonalit of However. the detrimental effects of dasc-um'td in Ileliil. "Maintaining the svstems. stuctures. and components aging chnisms an be observed bv runction of systems. structurs. -d subtect to an aging management review deLimenal changes n the performance- . - t

,.7 -* -.- -W - =W r w_ "MM-M-

Federai Register i Vol. 60. No. 88 1 Mondav. Mav . 1995 I Rules and Regulations 224

chamteistics or condition of svstems. personneL Once a detrimental protection (security). and ndiation s2uctum, and componenu if they ar performance or conditlon caused bv protection requirements. ar not subio properlv monitord. agin8 or other factors ISrevealed. to physical aging processes that may Aging can affec all systems. mitiung sctos ae taken to fullv cause noncompliance with thos aspe stctue. and componentu to some rtore the condition to its oniI of the CL. deg. Generallv. the changes sulting design basis. As a sult of these Although the definition of CL in P bfm detrimntal aging effects a progrms, degrdation due to aging 54 is broad and encompasses various gadual. Licsees bavw ample mehanisms (detrimenal SUlg effects) aspects of the NRC regulatory procss oppomitY to detect te dgradations is curntly being adequate y managed. (e.g.. operation and design through perormance and conition either dictly or indirecly. for most rqumments). the Commission momztoing progans. twcbzcal systems, structurs, and components. concludes that a specfic focus an specifcation surveilances required by Conmsequeatly. there is considerable functionality is appropriate for S 50.38. and othw licens manteance logic in ensuring ta the design basis performing the license renewal reVtC wtvite Except for some well- (as defined in 50.21 of systems. Reaonable assurance that the functia undeuood ang mechaniSms Such as structures, and components is of importnt systems. structures. and neutmn embrittlment and inteigranul&r maintained trough activities that components will be maintained sts corroion the ensur continued functionality. This throughout the renewaI period. strightforward ap oa detecting pzoces including surveillance. is relied combined with the rule's stipulation and mitigating the efects of aging on in the current tem to ensure that all aspects ofa plant's CLB (e.g.. begis with a PrOMIS that verifies that continued operabiltv. (i.e.. to the tecical *pecificauions) and the NRC t*intended desip huncions of gratest extent prticaple, the intended regulatory ptocess carry foward into systems. s .utursand componen design fuctions wiSI be properly the renewal period. r viewed as have not been compromised or per.formed). The focus on mintg suficiet to conclude tat thxe CLB degnded. Lces ae requird bv tucialtv rss in te continn (which represents an acceptable level currnt reguations to develop and capability of stems ataue. and safety) will be maintained. Functiona implement prorams that ensure that omNponents. Including supportinlg capability is the pnncipal emphasis f, conditions advme to qualty. including systems. s.rs and components. to much of the CLB and is the focus of tl degaded system. structure, or perform their intended functions as maintenance rle and other regultor component function. are pnomptly equirements to ensure that aging issi idendfied and conrcwd. The licensees' ley element ofthe 10X FR54 are appropriately manaed in the progam include self-impectio, diefinition of t;he CE is the plant. curent license term. maintenance. and technical specific designasinoriauon An example of perfornce specicfion survillance progras that defined In 10 CFR 50.2. According to verification activities that must be monitor and tes the physical condition thiIs defin:ition. "dsipn bases as performed by licensees is the loss of of plnt systems. structures, and tht inmtiotn which identifies the coolant acciadent (LOCAIJloss of oTsii componnwts. spedific functions to be performed by a power lLOOP)Integated tests. This For example. tchnial specfications atnacture. system. or component of a technical speciiication surveilanec i! indude limiting conditions far Canlity.nd tbe spcific vuesaor typically required to be perforr ed at operation (LCOS). which are the lowest ranges of values chosen hor cntrlling least one every 11 monts This test functional capability or perfo prmetesa re esbons for simlates a coincident LOCAILOOP levels of quipment requimd for safe deslgn." In addition. design bas (desi-basis accident) for each train opertion of the fcility. TechnicaI idify specific functionLs to be division of emerency alterating specifcations also require surveillance performe by a sem. structure, and current (ac power soure (e.g.. requirements relatin to test. calibration. wmpooent. ad desin-is values emergency diesel generators). the or inspection to ver that the necessary may bze derived for acieving functional associated emergency core cooling quality of ems. structures. and goals Fof pat stems. structures, and smems (e.g.. safetv injection components is tnunuined. that racility components tht ue not subect to subsystems). and other electncallv opeanon is within safetv limits, and perfoance or oonditioziemonito.n t drivensafet components (e.g.. that LCOs continue to be met programs or for those n which the containment isolstion valves. I ~Furthermore. f SamSe requimes. in pan. detimnta effes of aging myv not be emergency ventilauonrfiltration that svstems. stnctum. and aSreail apaent. verification of components. and auxiliary feedwater components be rted and Inspeed specific design nrlues(e.g. pping w componentsl. All engineered safitv agait qualitv sandards commensurate thickness) or demonlsiuon by eanlyi features required to actuac fS r in act .ih the importance of the safety can be a basis for wcluding that the LOCA/LOOP am required to acruate function to be perhnred. such as requird fnionsl wll be maitained the test and either duplicate the LOC ansevce testig (1ST) and inservice in e pod of extended oferazion. LOOP function compleclv (e.g.. elec itspections ttSsl of pumps and valves. loads arm sequenced onto emergencv Elements for tmeiv mitigation of the suctures, and components can be busses. containment isolation va I ves effects of age-related degrdation eonfited ether indectly by aciually shut from fully open positso mclude scuvities that provide inspetin or drectly by rundcaion or or approxmate the actual function ir reasonAble asurancc tat s%stems. niondfity thrugh or operation. the greatest extent practicable (e.g.. structuws. and Conponents will a esonable concluson c bc drand safetv in,eaion pumps start and run perform their intended functons when th be e ives or wilvibe iuntined. rrwlation mode instead of actuall called on. Through these progrms. This cmnlusionth coases tht the inecing water into the reactor coola licenees identify the degradauon of pormon of e r that can be mpated svstem). Design-basis values that can. components resulting from a number of by the detrmental efeccs o agiyn be only be measured du;rng this testing dairent envionmental stsors is well li..ad lo the desgn-ies aspects of such as load sequence times and as degradation hom iadequate theCen. All other aspects of the CI. em:, encv bus voltage rsponse to t' maintenance or etrors caused bv e.g . quaLty assunce pyscal secuenced loads. are directiv uenfiec 22476 Fdetal Regiw i Vo. 60. No. 88 I Monday. May 8. 1995 / Rules and Re9ulations

Betwee ingated ests. monthly and The apprech reflected Dthis rule agng mnageumt review. However. the quarterly suveillan a verf speciic maintaws the requirement for ecb rommrssim does noz believe that it cm compa pwman crnitia caseu renewal pplcan to address poib genencally exclude sa'ucr ad co,ncy dtil S or stit tzu detriental effects of n aretain comjponents that- or pump now valun. The acp synte srcue aD oimpxtents Donoehae rfomace mad mrtri sated in te surveillance during the period of exeded opea condtn charcerisc that u a reuirmets am derived from desin through the UIA psuxss. The rulwllta redily natorbe Us atvo basis values with apprpriate simpif the £PA p n~ Conisn th componeratsi and consrvatm buit an to accowt r filth Comni' s deamntn tha l21 Are t ubt to pc. any unceftalittis or meau rement the Mg manmgeni neiaws pnd rep >rt focu on unng thtxucturs and Unlike t exeve experinc tolernces. Sa6tsactory accomplisment assoiated withX th performanca 2f and perodic repetition of thewtypes of componei perform their intended funionisl and 2) the additional condit monitong od th actve surveillance provide nresonble fucio of stnuts anld cooonns ass tUr c tat inter. satrCture. and expenenc e Com sin las gained relted to agng aa ent rmiew litle exeiec bas been gained from component functions will be performed the evton of hgtr effects of as desiged. sice pubig t mirn aei renewl nile. aging on the passire funtins ot egra Plan ss The PA --o---s coinnes o require stuts and cOrmaits. The t

Federal Register I Vol. 60. No. 88 Mondav. May . 1995 Rules ad Requlations 2 2477

the aging m-agement review must still Structurtes or components nav have reactor coolant pressure boundarn, to be adequately demonstrate that derimental Active funcuons. passive functions. or included in an aging management effets of aging wiU be managed during both For example. alhough a pump or review e 8.. pressunzed water reactor the penod of extended operation. a valve has some moving parts. a pump main steam lines). The Commission casing or valve body performs a does not lmit the consideration of la) -Pasve- Structus uad pressure boundaries for an aging Components pressure-retaining function wnthout moving pans. A pump casmig or e valve management review to onlr the reactor In Secton ID.d of this SOC. the body meets the Commission's coolant pressure boundary All pressure Commission concluded that structurs descrption and would therefore be retaining boundaries necessary for the and components that perform active considered for an aging management performance of the intended finctions functions car be gencallv excluded review. However. the moving parts of delineated m 5 54.4 would be subject to frm an aging manaement reew on the punp. such as the pump impeller. an aging tmagement review For the basis of performance or condition- would not be subiect to aging example. those portions of a plant's morutonngprograms. The Commnission management review. AddiEionally. the main steam lines thst meet the intended re at stsrutures and mantenaince rule implementation function cnteria of 5 54.4 w¢ould be components that have passive functions guidance (Regulatory Guide 1.1601 included in an aging management gnerallv do not have performance and contains a provision by which licensees review condition chactensucs that are as may classify certair systems. structures. One commenter expressed a belief readilv monitoable as those tat and components (e.g.. racewavs. tanks, that cables were prematurely included perform ctve functions. Therefore. the and suctures) as. "inherently reliable." as -passive" and should not be subject Comusson concludes that an aging tnherentlv relable systems, structures. to an aging management retiew The managmet mew is required for and components by definltion generallv commenter stated that the only aging sructures and components within the do not require anv continuing effects of cables are shoning and oss of scope of the licen renewal rule that maintenance actions and should be continuitv. and for cables not in a harsh perform passive intended functions. considered as "pssive." environment, these effects twould be The Comssion has rewed severl As examples of the implementation of immediately detected during normal industry conaepts of "passive" this screening requirement. the operation or functionsl testing The structus and components and has Commission considers structures and Co mnission considers the examples of determned that they do not accurately components meeting the passive electrical components (e.g.. electrical describe the strctures and components description as including but not limited cables. connections. and elecuical that should be subject to an aging to. the reactor vesse the reactor coolant penetrations) listed in 10 CFR manaement review for license renewal. system pressure boundary. steam 54.21(a)(11(i) and Section IlI.fi)(a) of the Acdngly. the Commission has generators, the pressurizer. piping. SOC to be roperly categorized as developed * description of "passive" pump casingns valve bodies. the cor *passive because thev perform their characteritics of tructrs and shroud. component supports pnsure intended function vithout moving parts components. Furthermore. the tainng boundaries. heat exchgers. or without a change in configuration or Commisson has directly incorporated ventilation ducts. the containment. the properties and thie effects of aging these characteristics into the IPA continment liner. electncal and degrdation for these components are process to avoid the creation of a new mechanical penetrations, equipment not readily monItorable. The term. 'passive.' This SOC uses the term hatches. seismic Category I structum. Commnission dso blieves that this passive" for converuence. electrical cables and connections, cable categorization is not premature as stated Furthermore, the description of trays. and electrical cabinets. bv the commenter "pssive" suuctures and components Additionally. the Commission The Commission disagreesw ith the incorporated into 5 54.21(a) should be determined that structures and commnenter's asse.on .bat the aging used onlv in connection with the IPA components that perform active effects of cable make it easv to mortor re`view in the license renewal process. fumctions art not subject to an agng functional degradation. Although there Tne Commission bas determined that management review (e.g.. pumps bate been significant advanceq in this passive structures and components for (except casLng), valves (except body). area. there is no single methodi cr which aging degradation is not readily motors. diesel generators. air combination of methods that can monitored are those that perform an compressors. snubbers. the control rod provide the necessarv information about itented function without moving parts drnve. ventilation dampers, pressure the condition of electrical cable or without a change in configuration or transmitters. pressure indicators. water currently in service regarding the extent properues. For example. a pump or level indicator. switchgears. cooling of aging degradation or remaining valve has moving parts. an electrical fans, uansistors. battenes. breakers. quahiLed life. De dauon due to aging reoa can change its configuaation. and relays. switches. power inverters. circuit of electrical cables caused by elnated a batterv changes its electrolyte boards. battery chargers. and power temperature and radiation can cause properies when discharging. Therefore. supplies). However. pressur-retaining embittlement in the form of cracking of the performance or condition of these boundanes Ie.g., pump casings. valve insulation and jacket materials. The components is readily monitored and bodies. fluid system piping) and cracks degrade the electncal properties would not be captured bv this structural suppors (e.g.. diesel of the insulation matenals. The major descrpuon. Further. the Commission generator structural supports) that are concern is that failures of deteriorated has concluded that "a ctange in necessary for the structure or cable svstems (cables. connecons. and configuration or properties" should be component to perform its intended penetrauions) ought be induced dunng interpreted to include "a change in funcuon meet the descrption of accident cornditions. Because these state." which is a term sometimes found passive, and will be sub]ect to an aging components ar relied on to remain in the literature relating to "passive." management review fnLctional during and following design For example. a transistor can "Change A commenter requested clarification basis events (including conditions of its state" and therefore would not be as to whether the Commission intended normal operation) and there are screned in under this descnption. pmrssure boundaries. other than the currently no known ef'ecuvt; methods I- | ----

224?$ Fedual RRiiu I VoL 0. No. 8 / Monday, Mav . 1995 Rules and Regulations I for amtinuous znorng of cabe funcions, such gtnc exclusion is uoi tat bave a less rigorous spproe to syems. these example of passve appropate. However, the C-m son oversitht and mIuntenac and those elm±Ac componrs subjec to an does not utand to reclude a licese that have sfficiently hagh level of aging ma inant rvw will rema rnewal appn iom provndg sth- license proams ad regulatory mn 20 CFR 34.Z(saMlIi) and Section Im spcific ustsfiaton license oversight. The commenter then suggests R Ie) of t SOC. ree wval appliauen hat a rpaceent that the rule should recopize the fb) Laag4ived Strutute and quality and effectiveness of the Corpocets condtio fo a pv sur or programs in the second category and compn prle ronabl appropriaitly credit them eWve to an The Commission mopiss that. as a apng management review. Specifically. seall Maner. the effects of gin on& tht pavs sucwe or cpoet will the ciienter provided te reactor structure or component aft cumuive be maiid in theperiod of exdad coolat pJsure boundary as an thrughout its wrce like Ona, way to ion. exampl of pauive lng-lived effectivly mitigate tse e*1d.s is to A commta ro:mended thu the Component bo whic rigorous pogra replwe tha turu or c phaont Commissi specdi eiher li on a spciid hnera be and regulatory overigt cumrntly exist upon the qaiid lf of th stutr to adequstely rmnagthe effects of revithey hve het npl in the agng Curently te Commission cr componts or (i) periodically in hteryas .1 th orIinal lineor d believes i would be too dilc-h to accordanc with. a specified tim period they an subject to rotie lsi h to ptcr Td futher divide th suctwes and poifemascedegradations compoaents quid for an a&g lesifingtolonaffatended fJbdin componet re~nets and manasemenl rview intoh pasve. dunag the period of op£rat-on. "P9cs:IE-= croutntig Where a aucov or componen s long-lived suctr and components awe essaniy rplaents asdo *ngorously" managed and those not as tupl-ced b-- upon a qualified I% - ~or conditicu- Absent the (approprLately deteminedLit &olows rigorosy- managed. The variatiors peicnature of the performance QC aong plant specific designs d tha th mpld sucumo orplacaenterdi cilria (e.g., CmoetWna eoez pgms mae such a determination routin testin ptogram) Is Wmno unm abe t esen. demmmW lets of ag"n sfciet to appropriatfthe Cormlsocto However. as eintended functo This is geically eclude al such thCo ission gains mre experience rwlacmaz programs of ptsive with idustry activities for magement th tl oft str5t,r or compot Is of pasiv , long-lived suctm and X o f X s~~~~~~o autmand onipooanu. howevirm, to dmn thie time perid fo whic the Com mn doe. not precli.We a compo. its. it may consider frther 011641=10 nairowLng the scope cfthoe structures lcenWt wal applicait mo and ccmponents or ur-:_P mt can be resonably providing aLpln-pccJustification requiring agng tbrepacme t progac e s mnagement riew. With rerd to te in a liens rawlapplato tha a Wbe a suire ar component is nple or 0pro ccmmenter¶s specific examtple of the npla periodically in acrdance rector coolat prsuebonay with a specfied time period, the routine tesin ofPeave structuue and buxe of It ihrs sifine h r ta zpnx will enuethat compimis p fideraonabla difeces In platspei da nd, depuded performnce or the £ the assuranCe thtfntinlt will be opertioa histore, and thecf orcoponent epreedduring the mintained athgeperiod of Ede operating experience beyond the replmet inta will e adaey aperation oiginal opating terms, the addreued and the esablisd rep A comnser requeted tha the Commission does not belie ItL interl will be appropt. Tu. t Commitsio provde an example ofa uppropriate to generically exclude the is a high ketaood tAt the denimeal performance-oat cdi-b sd reactor coolat pressure boundary rom. effetsf aging will not &cumu replacezot pogm that coud be used an aging nagement review. during the subsequent period such that to justify tha agg effects will be (Ii) IPA ocess thr is a Ioss of icntned fnctin adequatedy mped dumg eX pod In sum. a sbu=ure or coxpoe that of exded oeaton While an exa The omission revised ad is not rplaced either ( on a specfied appo[.efouc or simplified the PA requi=ments intervi based upon the qual*d lif of condi epcui is nsey (§54.Zl(a)) s sflowt the snuctue or component or rIl dependent on plt.spciflC situations Fist. instead of sting those systems. periodically in ac:ordance with a an tei repetveagn et of structr, nd compmnets that are specied time period, is demed by concern. the Commiswan would important to ese rewL oly a lst 54.21Ce1)(ElW of thEs rule t be*"im- geally expe thatt such a is requird (from those sysaes. lived.' and teefem suhbect to th. replacemest program would have strucur, and components within the 521l(a)(31 aging management rsview. defin perfm or coditien scope of licee renewal) of structures It is importnt to note, however. tat m n th eg all thckness and mmpanents that licen the Commission hs decided not to of hest ex ner t a, estbished determnes to be ubjea to an aging generically exc1ude passive saucurs oanitoring fruency that supports management rviev for the period of and components that are rpLaed based timely disvery of degraidfd cond=tions extended operation. A lcnsee ba the .on performance or condition om an (e.g.. every refelng outge), and an flexibility to determune lr st ol egug mangement review. Absent the appropnt rpcemn cierocL ie.g, struanrs ans cmpnents for which an specific nature of the pezfrmanc or upon reacn a sp e nuber of aging mnagement rnew is performed. condition repla=w- criteria and the tubes plugged). provided that ths eompasses the fact that the Cmisin has Ose comnmenter stated tha he strucu and components for which determined that componeats with Comm on shoualdo sider dividing the Commissin bs determined an "pasive- fuxcins am not as rdily loag-Lved pasave suunures and aging mnagemet review is required morutotable as components with active compoeuLs into two categores: tos for the penod o exen& oeaMon - -. - -~~~~~ ~ - -~~.-.. ~-~ ~ ~ ~ - .- --

Federal Registr I Vol. 80. No. 88 1 Mondav. May . 1995 I Rules and Regulations 22479

hrefore a licens's a DOE commented tt the wording in must be considered for a agng managmet review nst incde S 54.2 1atl31. requuig a demonstration Ganagement rnew. stuctum and components- that the effet ofang will be managed Aging Ana)yses and nctionts) wil be g. TimtUnLimfd 11] Tta e t subect o so that the itndued Examptions replacement bd on * qlfied life or naintained, could be interpreted too aspeied tme peod. and tesctively. Speaaly. DOE assers (i) Time-Limited Aging Analyses 121Thatpotn an intnded function that the PA proes srs to The defintion of ARDUTLR In the (S 54-41 wit1tw mov pmas rwithout demonstrate that a stutue or 1vious licns renewal rul requires a a chae In conSlutio or ies component will perform in manner Ncose, evaluatio and NRC approval In stablishing this OeiAlity. te consistent with b(C rer than to of pevious timie-limited aging analyses Commission rucapime that lizasae provide absolute" assurance that the for systms. st.cures, and cmponents my find it pfrable to no take structur or component will nc' ail within the scope of liccn rnewal that m um advae of the Therefore. DOE rcomens revising eithe wezu based on an ussumed service Commriion's geneic conclusion 5 54.212()(3) to nUd & un life o period of operation defined by regrding seuctues and components demonstration that th effectu of g the original lic n tesm For xample. that do ot an aing are "adequalymanaged" and that the cerasin plantspecific safe management re ew. and m ay unde taks itended unctions ane maitained. "to may have b band an an explt is the extent s by t C(B." abrodr ecope of review than DOE assumed 40-yer plant life (e.g. aspecs aniruil required. For exampe. a The Q11MUi p ith of the rataor vese desig). Asa resut. all that the IPA proce is not intended to li c z m a d es r tO re view demonstt absolute msance that an e vlu ation for license reneA l w ould vs9uve sm and componens. wi l. be required Those time.limited aging Mt oguci m oand components sucnum of components not evaluated for This but rate that there is msonable analys that need to be wuold be accepthle beaus it includes assurancethatt pafaz such renewal ae limited to those analyses "loxlived" aswell as periodically with (ii time-related assumptions. (IU) rep l ac ed st r uc t ur es and co ne nts that th lntad ns. s p delinted in 54.4. am mintained utlized in dem the accptability and,thrfr.. c m e a l consstent with the (25 The of syst. stuctr. nd compoaents ruc s ald com poa ents thatwou ld has claifid the wording within the sope of licene renewal (as alteia (J and (2) rommissIn be identied througl' inS54.21( M)3to uuuire a delned InSecion 54.4). (ii) which ar above. demonstrtio that the effects of agn based upon c period of plant opamtion Send te EPA must contain a be adequaly managed so that ths equal to or geaterthnu the current d asaip tio n of he meth od olo y u s d to intoded funetion(s) wil be mnaintaied lices term. but less than the dee tt hr m sne ys em ~ ti ' , . ur s. an d consistent with the C2. cumulative period of plant opeation como netswihin thescope of licaens OE cmmnter suggest that the (viZ., the existg lces term plus the ree a ad those st u t rs d amendment provid moe unctainty period of extended operation rquested components subject to an a to which stucr and components in the renewal application). Time- management revw. should be ensiduud for anaging limited agin an lyses based On an Third. the IPA must contain a management rview. Specifl, the assumed pefiod of plant opeation short damoaw ution. for eac s u ue and commenter cited faer as an of the current operti ng trm sh ld be mpoent atbject to en aging example of what is iportat but addrsed within the origial license manamentreiew, tha the effec Of appem not to be considered in the and need not be reviewed for license agmg will be naaged so tbathe propoed rue. Th *my-neter states renewal. intended funcion(s) wil be aained that the NRC shoild provide more Becuse the Commission deleted the br the penod of eatnded opeatio. detiled guidance. term of ARDULnR. this licensernewal Thi demnxstin must include a T Commison doesnoagree that nile identifies these explict time- desriptio of aci'wies. aswell as any the rule provides mor uncerinty with lumited ayses as issues that must be chan to the C2. and plnt regard to what nucum and clearly addresd within the license inc dific atrns that are reliedl on to components should be considered. In renewal process. This nle explicitly demonstrate that the intended t r prvides cla criteria fr requis tihat- function(s) wiU be adequately what rypes of s s and (1)Applicnts perform an evaluaition maintained dapite the effecu of aging components must he subject to an aging of time-limited aging issues relevant so in the peiod of eended operation. management Ieview-camely passive. systems. s.uctures, and components A commffnter suggested that the long-lived stwtus and components within the scope of license renewal in gulator text incude a mor from those determid to be within the the licens renewal application; and Compnedeive list of components scope of lcnse ewaL With regard to (21 The adequate resolution of time- subec to an agi m anagemet r vew the specfic cxample of stcrs cited limited aging analysis issues as part of in Order to clarify ttS itent. The by the ommenter. the rule woud the standards for issunce of a rnewed Coinmiss deaided that aort o incdude require en aging Ianagement fevisw for licne. e more detaied list of cD:nponents ustenen because fasteners are The time-limited provisions or subec to an aging maaement review. consideed lo be passive and if the analyses of concern re those that- Components subjct to an aging fasteners (1) were determined to be 1t)Involve the effects of aging; manaftent review ae highy plant within the scope of licene renewal as (2) Involve timelimited assumptions specfic and the Comsion does not defined in S 54.4 and (21 were defned by the current openting term. tend to stablish pLant-speafic lists by determined not to be subect to periodic for example, 40 years: reultion. However. the CommissiOn replacement or rplacement based on a (3) Involve systems. structures. and iti indud, addtional clrifiction and qualiied fastener life. As in the components within the scope of License eamPls of componentS requiring an previous nrle, this rule does not renewal: Mug manament mcw sn its deineate a comprehensve list of the (4) Involve conclusions or provide the ImPlmentato guidan for the rule. spedfic stuctures and components that bass for conclusions related to the z - 0

2240 Federal kegise / VoL 60. No. 8 I Manday. Mav 8. 1995 Rules ard Regulations

apahdility of the systm. stucc, nd tEQI of electrial equipment. metal October 1990 that did not rsult in componet to perform ts tiended corrosion allowance. insence flaw backfits. the Comisson found that growth analyses that demonstrate only 3 issues for wlich a reexamination (s) Wer detenee to be televant by StrtUctral ltaility for 40 years. of the bacflt detemnunatioa ppeared to the liceem in makin a safety insrvic local metal conanment be prudent. 1sn two nstacs the corrosion analyses. and bigh-energy reexmnton COe thie 161 Am contained or incorporated by line-orak postation based on fatigue appropriateness of the no bacfit rkens in the CL2J cuulative usage factor. conclusion for an additional ,D years of The applicant fr linse reewal will Tbree isues were raised bv five operation beyond the orignal 40-year be rwqured in the renewal apphcation conm te rlting to time-limited licen term The third issue lGSI Item to- aging analyses in the rsoposed nle. M-A.13 "Maintain Supply of Thyroid (i) lustfy that thm analyses ar valid (iiT ppo ..d rtZe c ont ins Blocg Aset") had been placed ia the for the period of extznded opertuon; definition of time-limited agiDg anayses resolution process for reasons apart (21 Extend the peiod of evaluation of i5S5S4-3 whichlsflher dis ssdinn from license renewal. Thus, cost-benefit the auslys uch that .wey avalid for the proposed SOC. However, the analses of the resolved GSis were the period of extended opation. for proposed rle definition appered to relatively insensitive to consideration of 6aiG 60 SS; ? contain two criteria in defining time- e period ol tended operaion. The (31 ltibfy &a the ees of agig will limited aging anyses while tie cost-benefit methodologies uWi:;zed in be adequatey managed for the penod of discussion in the proposed SOC resolution of GS are tesame as those extended operaio if enapplican apjdaXSd to contain six cntensL hree used by the NRC in conjuncSion with C Ut n or c o o e or Oto t Or commenters indictted that the may be e full gamut of regulatory ions e end a xs ting ti limit ed aging potential incnsitenrces between the inIvolvring nuxclear power plants. propose rule defiition and thie including rulemaling and enforcemert. 1'be Com iso nc o r aalyse proposed SOC. Tecmmenters Since the methodoloies ae the same. to be 'reutw if te alys promided recommended various methods for the Commision believes that the results the bais fosr th ic n 's ft incorporating the SOC laguage in the of NUREG-0933 can be reasorably deteminto n ad. in2 t abec of the ri extrpolated to other regulatory adayss.,tbe licse may haverecd The proposed SOC discussion was assessm-ns where backfts wen not intended to further clrify the criteria imposed on the basis of cost-benefit limtdagin analyse that need to be contained in tha proposed rule amyses limnted to 40 year of addressed in a Lics rewal defi-itio. After reviewing the operation. Furthermore. cost-nefit evauton aenot n cessrly those comments, the Commission hs decided consdertions simply do not come into a sn ls th at h v e b e pr vi usy to replace the proposed definition of play in backft detesnations involving reviewed or ap proved by the time-limited aing analyses iD § 5W- sdequale protcton-exept In selecting Toisi Te fowig eampls with th ix curia ln the proposed amng different ways of ache'.-zg tiusiste fore-imited agig atyses SOC-as recommended. adequate proEon. as iS cknowiedced taned tgLbe adlestedhad wee ot (21 One commenter recommeded in 10 CR 50.109(all7). The IPE and pviousl aeviwedd pp e by reconsideratiom of all proposed plant -- mg licesaes' studies to for the Commisson. modiScations which wre not imposed plant vulnerabilitlies to intetnal and (1) Te FSAR staes that the desigm by the Commission due to a cost-benefit external ev.;nts. As such. the IPE and complies with a certai ASME Code analysthat had timedependent IP are not intended to identify or requiment. A reew of the ASME factors. The commenter suggested th^at address matters involving adequate Code requirement reveas that a time- tis should inlude any bacts which ection and. Io date. no such issues hmited aging anaysis is required. The the Commission declined to impose. as fvte becn identified. actual calIculatin was performed by the well as potental plant modifications to (3) Two commenters recouniended licensee to meet code requirements. The reduce risk identified in progrnms such claifyn that the requirement of une- specifie calculation was not refgrc -ed as the individual plan examiation limted aging anases does nlOt apply to in the FSAR and the NRC had not (IPE) and the individual plant a cmponent that is replaced baed on reviewed the calculation. exa.mlnaUon of external events ([1Pm) a qualified life less than the full original (2) In response to a generic letter. a for svere acident vulnerabilies. license ter. The commcentens cited the lICLnsee sutted a letter to the NRC The Commission does not regard such EQ of electrical equipment pursuant to committing to perform a time-limited reconsideration to be necessary to 5 50.49 as a specfic example. This type agig analysis that would address the provide tasonble assurance that there of equp-et is replaced dunng the concen in the generic letter. The NRC is no undue risk to the public health current licen tem and wil conunue bad not documented a review of the and safety for tbe period of extnded to be replaced during the renewsi term licensee's respanse end had not opertion of nuclear power plants. based oa its quaHfied life. reviewed the actual analvss As discussed in the SOC for the The Commission's ntent for the The Commission expects that the previous licens reawal rule 156 FR equiement of time-limited aging number nf time-limited aging analyses 64943 at 649481. in NUREG-0933. A aalyses is to capture. for renewal that need to be addressed in a license Priorti.uticn of Generic Safety Issues. review. ceru plant'specific agng renewal evaluation is relatively small the NRC examined 249 geneenc safety analyses that are expUcitly based an the Although the number and type will vry issues (GSIs) that had been rmsolved duztion of the current operating license depending on the plant-specfic CLB. through October 1990, in order to of the plt. The CoMMLssIon s concern these aualyV#s could include reacor idenufy possible cases where is tnAt thee aging analyscs do not cover vesel neutron embrittlement consideraLion of the additional period of the period of extended oneratior.. (pressurizedS thermal shock. upper-shelf operauon dung the renewal term Unless these analvses are evaluated, the energy. suw.illnc psml). concete might have aliered the NRC's regulatory Comission does not have assurance con nient tendon prestress. metal decision not to undertake addiuional that the svstems. stjructures. and fatigue. ecvironisnental qualification aciorn. O[the 139 CSIs irsoived through components addlessed by these '"' i Jf1h - J

Fr Feda Repter I VoL 60. No. 8 Mondav, Mav 8. 1995 f Rules and Regulations 22481

1'vm ca perfom tbaer inwaded because the only axemnpLtns of oncem 11 That thbn ae specuil hacuis]i dunug te penod of for lcene renewal ae those that have circ LtanCes with spect to age- twon*d opeton. The penidic Uvme-lInzted agng analYses related degradation uuque to license I ant prog m dicwussed t te Thus. the Co0misin has revised renewal or environmental protection so pewnow prgaph would enur that S4.Z1(c;(Z) to rquLre a lIsting of only that appication of either 0 CFR Part 54 d* swMcopouent can periwm its those exemptions in effe at the ume of or 20 CFR Part 51 would not serve the ,hded luaCtionl) dunng the penod renewal application that ar based on purpose for which these rules wer of ened orao. Thus. the tune-imited agimg anyses as deftned intended, or C suion i gos with the in I 54.3. 12) BecAuse of circumstances unique mmesiet that cmmponents "placed The Commission will eIy on explict to the penod of extended operation. binml an quab&d lives ke. than the warclngs i t granted exemptions to there would be noncompliance with the 1-tonathe curSat license tem determine i an exemption s an effea at plant's CLB or operabon that is inimical nd ot be addressd undet uie the tme of reewal application. The to the public bcalth and safety during kar1d a" anlys for rnewal i the ConUoo will not requr an the period of extended operation. schdue reaceme continue t be exemption to be considered for Icense The intent of those provisions in the pdur d iu the penod of extnded renewal if the exemption was anted presnous rule was to clarify that saety 0pmnoe. This us tnstrnt with the wnth an explicit expiration date tat has and environmental matters not urnique ddnuion of timi-limited dgang analyses passed prior to the renewal applicauon. to the perioffof extended operaion in 543 liowever. the Comn owill require would not be the subject of the renewal exemptions grated without explcit applicaton or the subject of a heanng in fii Exa=ptions expiration dtes to be coniered for a renewal proceeding absent specific Tbi pr tous lcense renewal rule renewl If an applicant believes that a Commission diection. Rather, issues dquird that an pplicat for 1icese cena exemption has expred and yet that represent a current problem for ruawal p i de * lst of AU plat- the supporting documeaution does not operation would have been addressed in speak exmpt3ons gpanted under 10 have a clearly stated expration date. the accordance with the Commiwan's cm SO. evaDatn that pustif n applicant should updata its CLB pnor to egulatory process and procedures. tL e anafntu mO th eoe nsfor submittng tsrnwl application to Thus, under the previous rue. a te renewal t= must be p d r clearly indicate that the exemption ha member of the public who believed that I Lb- t eth w at on expued. a current problemr eists with a license tb bof a mn-Adsmlfe or o- i matter exists that is not adequately a pmod of operakion bounded by the h. Standards for Issuance of a Renewed aedressed by currnt NRC regulations : onal licn ter of the city or License ond thet Scope of )leurrngs would ha;e either petiutoned the NRC to lww lted to sYMs. suctues. Sectio 54.29 of the previous licens take appropriate action urnder 5 2.206. or tcomponants subject to ARDUnR rewal rule provided that the petiuoned the NRC to institute With the deleuon of the definbon of Commission8 may isu arenewed rulemaking to address the issue under ARDLi and the com5pondig licane f- S 802. atdian ofa separate time-liited aging (a)Actions hav been dendfied and The Commission continues to beiieve analysis uLu e LtU.e Coinz'r::sian. have been ot wil be takn with respect that aging management of certain bancludedthis exempton r .w to age-related degradation unique to mortant systems. sructures. and with the separate time-limited sing license mnewal of systems. uctures. crmponents during this penod of ahass requitmen in S 54.21(c). This arid components impona..t to license *acended operation should be the focus change Liconsistent nth tht meewal, such that ther is reasonable of a renewal proceeding and that issues Com sIt-an sIintent tO review assurance that the acivities authorized concernig operation duriug the exemptions based on tme-mited agig bY the renewe lic s wi! be cmrrntiy authorized term ofoperation aulvua under the curTt rule. conducted an accordauce with the should be addressed aspar of the Tucommenten quesuoned the curent li g , nd that anv current license rather than deferred proposed rtqu ment to list and chnges made to the plant's curet until a renewal review (whch would enluat, al granted exempons. licensing bai in order to co.mply with not occur if the licensee chooses not to icludng those that are no longer in this paragraph aeotherwise in accord renew its operating licse). However. fem One commenter recommended with the Act and the Commission's in this final rule. the Comnnussicn has th aly exemptons in effect at the reuIatioas arowed the scope of strucnrs and ume of renfwal application and I Any applicable requirrments of components that will require an aging contiing Lito the penod of extended subpart A of 10 CFR Pan Si have been management review for the period of operation should be considered for satisfied. extended operation and identification renewa, Furthtr. the other commenter (cl Any matters raised under 10 CFR and evaluation of lime-limited aging indicated that requiring a lusg of all 2.75 have been addressed as equired analyses by the applicaSIL Accrdingly. exemptions is inconsient with the by that secion). conforming changes in 54.29 have removal of other lists curmently required Issues that wre material to the been made to refect the refocused it 10 CPR 54. such as tht list of systems, Endins in S54.29 of the preyious rule. renewal review. Specifically. S 54.29 has s.ctures. and components partant as well as matters approved by the been rvised to delete the trm "age- to bcense renewal. to provide apphcants Commissin for hearing under 2.758, related degrdation unique to license 12exibility in developig suitAble were wnthin the xope of a hearig on renewal," and substitute the findings methodologies to implement the a renewed license. The previous license requtired for cnsistency with the requurmnts of SS4.Z. Th renewal rle' modihed 2.755 to clarify revsed S 54.21 (a)(3) and (l with Cois issimn agre with the that chalenges to the license renewal respect to agtng manvgement review and cometers. Exemptions that have mle in an di4icatory hewing on a time-limited agng anAlyses evalation. ecpied are no IOnget pUt of the CLEfor renews] application would be for the period of extended opeation. that plan. Furlber, a requirement to list considered by the Commni oy in Furthermore. 5 2.758 hs similarly been all cXmptons Ln effect iynneceSMVry the foUowng l d tc: reised to delete the terms "age-related _wr111110 ~

22412 Federal Rister I Vol. 60. No. 88 / Monday. aY 8. 1995 Rules and Regulations

degadauon uique to licens renewal" misinterpreting the scope of the renewal information included the IPA lists of and "uuque to the requested tenn." The rview and finding. systems. structures, and components. elimnaon of ARDUTLjt requirs Section 54.29(1) of the proposed rule justification for assessment methods. eli-inaion of the concept that the set forth the three findings. in and descr%ptions of programs manag mnewal review or hearing must be pargaphs (ji1). a)(2) and a)13). ARDUTLl confined to agig issues that are which the NRC must mike r. order to The simplification of the PA poces ' unique' to liceoe renewl. Instead. issue a renewed license. The first (Section M.f of tis SOC) .nd the limts on the scope of renewal riew finding in paragraph ((I) was divided clarificauon of the concept of ARDLTI and hering an based on careful renew into two numbered paragraphs (!i) and ISection Mlb of tius SOC) have resultet of the sfficiency of the NRC regulatory 1)tiil. DOE comentea that oumbering in a potential inconsistency tegarding process to msolve issues not considered the cliuses could lead to an erroneous the treatment of information assocratec in renewal. interpretioa that two separate. paraLel with the PA. The Con.msiion &as conditions must be met in order to make determned that there is no need to Section 54.29 of the proposed rule (59 the fit findmg. To -oid the potential include the entire [PA in an FSAR FR 465791 was intended to acomplish misinterpmution. DOE recommended a supplement because only the several things. Proposed I 54.29(a) was revised numbering scheme. The infomation as. ated with the PA intended to defiae the findinp that the Commission agres that separtelv regrding the basis for determining tha- Commission must mau in order to numbering clat.ses i) and ii in aging effects are managed during the issue a renewed operatng licenue to a paragaph (lIi) could lead to an penod of extnded operation requires nuclear power plant and the scope of emneous interpretation that two the additional regulstory oversight any hearing on the renewal parallel conditions must be met in order afforded by placing the information in application23 By contrast. proposed to make the finding in paragraph (11(1). the fSAR Therefore. only a summary 5 5429 bl aud (c) wee intended to Therefore. the Commission has adopted descrption of the progas and identify the issues that wor NIT to be an approach similar to the DOE activities for managing the effects of pat of the reewal mview and to .e- proposal. aging during the period of extended emphasize tha rnewal applicanr i. Regzulaory and A dministrative operation for those structures and obligation under its currt operating ControJs components requiring an aging licenia to address. In the contax of hat management review needs to be license, those aging matters identified in Cctain ruatonr ani niJsatuve included in the FSAR supplement. The the couie ofti renewal eview tbAt controls in the prvious license renewal IPA methodology and the list of rule ware unposed to specify the srictures and components need not may reasonAbly be expected to caue a circumces and requirements loss of fhlucion for systems. structures. appear in n FSAR supplement. necemsv t mae changes relating to althougb tis on wil still be or components during the current term the determinauw. and management of of operation. Both DOE and NE required in the application for license ARDUTLR and the recordkeepmg and .enewaL comnnted that by combining these reporting requirements relating to the ahe Commission has also eliminated purpss Ito e single section. the renewal ppication. In view of thae 5 54.21 (b and (dl of the previous rule. proposed rule could be erroneously rter reliance on existig programs in These sections concern C.3 chUges interpreted as requiring a general the license renewal process. as associsted with ARDTLR nd plant demonsation of compliance with the discussd in Sion m.d or ths SOC modifications necesary to ensure that CLB as a prerequisite for issuing a the Commission has determined that ARDUTLR is adequstely managed n:newed license. While the Cornntssion many of these requirements ar no during the period of extended operation believes that the proposed rule was longer necesy. Therefore. the This ilormation is now required as pan sufcienDty cle in distinguishing Commission has dearased the of S54.21 {a)(3) and cl. Relevant between the issues that must be reordkeeping and reporting burden on information concerning changes to the addressed as part of thc renewal review the applicant for license renewal in the CB aRnd plant modifications Muired to vesus those which must be addressed level of detail in he application. demoastrte hat aging effect or in the contem of the current license. the requirenents for supplementing the systems, structures. and components Commission has considered the FSAR. and in recordkeeping requinng an aging management rev-iew comments of DOE and NEI u evidence fqU.ireUntLs for license renewal must be descibed in that he language of the proposed rule The Commission seeks tD ensure that. the application for license renewal could be furher improved. Upon review in gneral. only the information needed (5S4.21 (a)131 and (c)). If a license of NEIs and DOEs proposals, the to akeits safety determination is rnuwal applicant or the Comssion Comission has decided to adopt an submitted to the NRC for licnse determines that C.B changes or plant approach eimila to the DOEprt,posal. renewal rview and that regulawry modifications form the basis far an IPA which narrows S s4.z to the findings to controls imposed by the license renewal conclusion regarding stuctures and be made for isun of a renewed rule are conswstent with existing components requiring an aging license. and describes in a new section. rguhtory controls on similar managemet eview. then an 54.30. the license's esponsibilities for inforinaor tht may be developed by a appropriate description of the CLB addrsing safety matters under its licensee durig the current operaung change or plant modifica aon must I. cunnt licers, that a not witbn the term included in the FSAP suoplement. Susent hanges are controlled t scope of the renwal rvew. Separaing (il Con'ols on Technical Inlormation in the ub)es into two different sectons an Application 6 50.59. should minimize any possibilitv of Setioi 54.21(c) of the previous In S 54.21. the prvious license license renewal rule required that aLn renewal .e requires that an applicant for license newal submit ( 'Thrb e of Coniaonwew d.t~aa th applcation include a supplement to the a list of al plant-specific exempuons :es .* a Cmmm= fiande 10 CFR FSAR that presents the nformauon gnted purunt to IO CFR 50.i2 and J.75& required by this section. This each relief granted pursuant to o CaR . a _ - v- -

red" teim I Vol. o No U Mondawy. Maib 9 1I.ulus 814 1S%letiofii 22483

3sSa.sAod EZI4D t YvaJwanI the deletd tbe r.qurm t to lst td etepoaoruw MM'aWu lad to a eviluvae rli s bo 4 4.2t14- wt b pbe4ed hao the TS" aysta= souch=. or cvmpooei tbat ln Its cma2t. I'M ed u he tUppPi-o L Licenset . wee suiec to AXfUTLX at a tim- reqnuarmnt dctai i 442 of %be hwiDtatwti d bymew lituits hba Thes e mu M Prop osd nile a 8qrsaiu ata Sot luabo wm to be umluded in the t eec ) o ~ p e al c ti n a C ha ag mt h at a e =VpW W la tU FSARL Al that Urn, eeCmeuy to AOt e apng cow3insa In eccordaac. wEbh the CDmm&mo etannined tha thes in te pbed d o b 15 4.5(h). req2irenients wuiw baa7 to mlake an Th e gairy pI will canuet to en maethat p opo e 4cb 5. prapem end acciLu "htm aftd evAluated put of tbe tIc er nW l de t is o r i s n t e S Mw i l r ec i v e pha n g e s 1o nl y~~~~~~~~f s h o ul d b e r e q ui r e d to theh:Db e thttes d._urt wwu iMPOMW domntdtchiciil in th burCos Msecco of lb buus they proVied a m w the n~spsihaton~an ThMEI m lo appabatopl . pb thde N C ho W tt ho nnin theingt puiod af in which ithe nq ursto include the the safft jus ifca i o technt sp c o n cognplian with exist n uary in the ?SAR supplm t and bt fill) Addiunna - wds and wiedumant is not needed to cm-Ist cdanod the nViwemet in i $22 to he that the puhLic heal' amo safety s n ff C52fwth 5S.. Section adequatey Paoected- 54 now saIe that UW JustibcatL021 Sectiort 54.37 of the prevous nile Tb. Ciimmima continues to believe kwchanes addiloos to the thical required that te. 55S0.731.) rwquied. that the ratimnale mAd basis far reuirng specificatns cmus 1. ontaed in the nodpc FA upda: the Infeamaiti4m li ns rnewal appl at 1) Inchide anyevstemssauactur to be subumited an stun mad cam; p -rms newlv identfied as wald fo eiptfa& The Ca=iss1i [il Cndtins of Ra*wtd Licens kms relcated the requirement to list and importent to U-can rWial &atr the wvhuae certain w=apkm to proposed Secido 54.33 of the pevious rule renewed lices s ueod 5421CLThus.these Lsc. required tha, upon nWALL a licen 121 Identity and povWde tustillcar-i marin the prop*= and procdurs for aLny systems, stuctures. and tberefore be considered a su stof which woul hv been zsvwwed eAd copo entsd eleted gro msthe lis of ms-limied agn bgi appsovd by dh MC stkf. for g sysem"."'nes. *nd com Consisten with %beCotniission's ARDUTLER i additin 54.23 impostawtto licens eewWaL ad ratinale for icuding only a sumary establisbed eqirnzmen kwlot making (3) Describe how,.IDUTL.R wil be deeciption of progams and activities n change to peviously approvJd managed fr 2kw"! newly identified the F RsUPPlmenpt. l& comiission prograts and produres to mang systems. suwwrur-s. and compens cocludeslimiedvng tat onlynalses a summaryincudn a F A s u e n t h t a o m a s h su m ar o f h ba e f or e xXi n ARDUTLR consistent with the rula chang that delete the tern dh a ar b se o n ti l I mite do a i g .A.RDLTTL.R" (5S4.37(b)) and deitmned tha t Considering the proposed requimements needed to be modified. As amendmets asoc-Aed with the discussed in See- nu ULi4I of this SOC analyse needs to be icluded n the eliminatio of the term "AEUTLrr the requirement t List systems. FSAR supplement The rCnnxSisO the le requir progams and stucturs, and cmpoments that ar concludes that no needs ex to procedures to Mage the ffcs of *impon e to license renewal In the esublish additional requirements that aging fot cerain system, muures. place the list of execpions or specific and conpones Howev, the exemption evaluations into the FSAR Commission wll not appe speciDC supplement. although thi iuforman gmsa ad prnedu s eanvisioned the controls on :echzucl nformsatin must till be contained in bhe 4r ti pnnrjou lics renewal rule discussed in Section m1i.w te application or licn rnewaL le.g.. effove proms). The Commission has revised the A rlief from Codes need not be Cammison wil: review rogams and requirements for information to be evaluated as part of the lies renewal procedures dsrib-ed in ehms included in the periodic FSAR proces. A relief ganted pursuant to 10 renewl pplication and detome supple:ment. For example, the prev-ious CFR 0.SS is specifically envisioned by whther th progruns and procedues equ.ment to identify and prowde the rulatory proces. A relief expires pruvide esonble asunce that the jusfication, i thd periodic SAR her a specified time interval not to huCtio ity of systems, sucus. and Updte. for any sysWTS. stutUres, ancd exceed 10 yrs) and a licnsee s Components requiring reiew will be components Je1ered from the rquired to repiUfy the basis for the tainged iD the peniod of etended aforementoned It is no longer relief. At that time. the NRC performs operation. Te icene renewal review neicessay and ha been deleted fm= tht another review and may or may not that would be c0nd2cted under this rut e final rule. L. adrtnon. the preious nt the relieL Because a relief is. in mav consider all programs and acuvxties rule's requirment to describe how an NRC-opproved dUon fom to mnage the effects of aging that ARDUTiJ will be ma ed fr thos the Codes and sUei to a periodic enue functiooali.y for these systems. newly identified systems. strcxu-e anc review, the Commission cimcl'ides that su res. ad components. A sum=ary componenits has been modified. For reliefs e adequately manged by the desaiptionl of tfie pnorms and newly identified sstems, structres. wasung regulatory proces and should actUVties for mnatgin the effects of ad coponents that would have not require an -I=g manngemet review apng far thie perod of extended required either an aging management and potenual re;usdfication ior License operntion or evaiuauon of tune lrmi ted review or aoe-hmitedt aging ansis. Tenewsl. Therefore. the Comnission as agig anlses, as apEzopnete. for these the final rule reure that the licensee - 1 __

22454 Fedutl RmAn I VoL 60. No, U Monday. May 8. 19S Rules and Rquza. ons

d"0*b La the pcedw ?SA update Under this nle. the Coz-asta wiU fpeaungac 4UIes power plant inth (Matsu of an MsOUGMi wip to *Ar th the syatams. otww. itw,tlit SI ito loud be rcot ad ~P a pat&Wm thatW wb aptil n n d ntw m i e the * watm bgt bmn tme h mctk n during th pwrio ,ewm dud wwil ald pr "i~~~0r a l e nb petr thduw" antbti it aSasp.t oth thne ~ llt y of p ya mi tw Cow It.Is puo for ce FY Two _ idiemed that tb with tbe mandauw of "h ~ilmu lee of Gna rqauid br S54,37 (a ei MP tsU pq g m w tw Eailaeoikc PI4ct INEPA1 d u.ainp u a o f bo w t * o f agI g bemi ted LB' e s mdo extended H1w. NEPA do aot rqui td wb. ed in the peird of o ti T U l tMvw et w _c a . tni a uss e tan I tan, and that wwujd be ct4iumed under this nalo rulamang 59 FR377341 the may csidw anll prp and acdvtu Cmmin n aidwg whber t dh m w I i - : t wih theX~~~~u le el.of imuli LnIM FSAR ppiament that tn Pi ; of agf and awybwimsaanbe al,,. on;f5 d eemiptian of the p regro and ayst 1s.71m CT ISe. and ponents. Tbe e as g regu hemy p r . a ti and iwbissatg the NEA evuluanca' etcta of g1qij. Mm Comision foe a inaunean mm inpca In belie es thst itIi1q orta t n otbt son. the ComaUi s am itatutrl t he o snati u c iu a rid i p n m withpplcn u m e ptlon of requied. wd don so hbi it is dissuad 5437W ew ,' i to r na v t a sof aging n~i.to p moomic idtatfled sy d int due PS" are m to ensure analyofotuxiamdu opeaathamof component tha wwuld ham bouw that ~ a to proera ms th at could subimc inc a i_j_gmisoama mwisw comn.tu tht an daan 17 the icense renwa Rp-M-11 If p teo manage doe e1 Is f aging man _euntauzw that anvoies an kistifed asput of thu licm umwl (11 otime-lg.. -ig btwa s!" is bein addsd by tb. N s a GSI oran unresd od sahey mmus and ompbamanfawoad hese then ('JS dad Za a p ew- of&.wawud Leped he ~I n t h * ~ g m h li ce n s resolutio of the ua&in, L Do the U00:010liam taayesthe uhu gRull tw. and imAtlon o a USI or GS goeuxca peow.. the ap h md Lb* FSAR f a #tI-p p is ot bnay awts-ant Tbefidormestr~ i supp= monL biged.~zU vib the 0b cmic Wof apwe l iazaSe *na USIs that do not eotin ls Wed to te licens belp amus the efficacy of aing indids tl then Ftoderal nnealgng _afennirve or tib-limte agng evalustion ua not I mprn~ . Abu a guMewu I Is subject of I or Ending fr license isced the in tla in tu PSA po w. need to be & z vp renewaL Hower diain of an supplem eint eww"CIie d mi w so issU as a CS c USI doos not i*uds thnaat Icthe t p poi sia HL y f them the isa f the scope of the aging (11iA smuig thae theb u u m managem enw or meimized along with te utiity. ha o fth- Stt&gv (baF%JALreA; I m1nudU infsxmatica regar"Ing the alauation of -=tv fnats For an Issue that is both withn the aging ciefsk wlffXdhi 6* thee newlyPyAms kidnifewd scope of the aging manamnt eview R.C CiX_r rpmdbt *Ite mcwesi nd compodents poasdned bothe a Eei ct or time-lImited evaluation and and (21 .elsohinqg appmropn deoml sio Rg lator plantsan g within the op of US or CS!. them _dm and ognlUy conucl g *rtionisthe Commisso ofitar am wvrd pproaches which can be an the jwopwes tat nainae aging for ftyan the aruthert d to c usd tofy the findg qiied by - d@tiftshbsdfid scion 54.29. If an aplihbe generic molution has been aheved before the cctthe isuane ofarenewed en. appopata.mchazcti6 wr of to level of detai dslmo naftha itsoPdpe6 w apmd_ 43Miq the N RC ,o a ic osta u d e cotO impleentztloa of that rolution 1uI required hn the FSAR supplemen be gd_-tnS s b s o bd {UIbnt be incrpraed Within the reea While styand the Comisyion authd iuy for re t uatn the edenmio s appliati An appliat may hos ,omuo'malcd 3 i th de socited9scosW o t submits tchnicl rationale which for tis p tb iCie aro si deonstmes that the CE will be Suction 54-37(c) of the pfevious rul cuTenlofS uce apbads, we eneheInso aion. Underth manitir-d until soum latet pint in requied that aUcene do the ths E a nutb Commission. time in the period of eadndd followingi operation. at whicb point one or mie (I3 Submit to the NRC at kea alon gratio as a b . a " tnorui h reanable optiom (eg.. eplacemet. annually a list of eai change. made to analytical evaluRtion. or srvellane. programs for wanapment of AXUUJTLR mantnaCe pupam would be tt do not dasmase the effectivenss of available o dequately manage the effive progrms.&with. a sumary effects ofaging. (An applicant wuld of the juatlficatlo and have to doob Its basis for oonclu (2) Maintmin doeuwtatIox For any that the LB is mainaned. in the c hang esto effa dlw," p,V p.1---thaft a license rTenewal applicatin. and bief. determined noq to re twem desaibe options (bat a thical1v effectivss of the pous m flusible dunng the period o etended Fderal Regir I Vol 60. No 68 Mondav. Mav B. 1995 1 Rules and Regulations ZZ485

oputin tO manaee the affecs or agng. disussd in the SOC of the pnmvinas carglesnl 'oh license renewal ule. b6t would not have to prselt whuch rule (36 FR At 84951). the ComIuaon's Rather the . mmiszson relied slely on option would be used Anotber inspecion propK obtans sufficunt e expertise of epresntauces of apoach could b fot an pplicato informatn on ILpos performance. auclea aulhtes. Indusry organ.atons. d.veclp an apogmsawagement PrOWSM thro dte oservation ard achitecs and enginetnng firms. wicIL hor that plant. rncorpaoae A verfication of icse tvitues to con.ultants and contnctors. and Fedenal rlgtm to the aS" *5t5 i ssu. datemm whethe the laity as b,ng and Stata ageces. Aother opt b to propose to operated safly and w D the The Commission disagrees. Consistent amead the CR (as.UOpae ctin Lcense managemet control program s with tbe Commission's policy of seeLg otM of the liese renews] eectve and to asorriar whether there input from te enture spectrum of the application which. if appod. woud is a asonable assurance that the publc., the Commzion provided ample rseI the CLi such th the m ed ltcene e in compliane with opportunity for public coent. The fuon is no loneT thlin the CLi. oreylt reDqurrumms. Further. as Cmmion helt a public svor'hop on 13) -sE xu tat = i n the SOC for the previous September 30. 1993.10 discuss as plant age. te repilaoxy rl 15 Fat 64947), the Commission altentive apprathes to the licen requirents need to be strengthened bas a progra for the reviw of renewal nl. A notice of the ublic rathe than neljxed~ Them entr optmw* wmts at nucar power workshop we publshed in te federal indicated that the ptopoed pet rm u prog off a high Regis on August 1Z, 1993. la additon renEWa rue is a nltrai of the that are to th Fed Rtgisternotice,1 tbeNRC pIUS NI. n Oly toprvde potnily riksgiiat orpeusr explicitly cotacted four publc :nterest tocetnves hw pplicants rtb ta ma 0 si cant tents are be reviewed groups that bad previously dic ennancent stri public saMy. and resoled expditous. Response to interest in liceam renewaLL The NRC The Cq=enissibn do not arm that events May t in Mir staffcontacted represetatives from the reglatIOS L u1 be suengtheod simply Inpct x aciiisat a single plat up Umon of Concened Scientists, the bau sea plat ages. Mm Commission to geei aeyImpro ets at al Nuclear Information and Resource beliuv t a"dtial pAla0= pb4pzla of lici ts Service, the Natural Resource Defense should be imposed when tbce is some Thus,.the Commission continuouhly Council, and the Public CMzen reason o beled that crzn relaton analyas citins, ads, ad practices Litigation Group. Reprsentatves from am inadequate. The Cosmisti s that could affct saf operation of plts the Nuclear Information and Resource regultor proces co _Jntiitsy and taiw aprort acio. Sevice and the Public itizen Litigation aSXDsese the need for additional IS) Onr cummente askd whether the Group attended the workshop. Written ever>i and imp kmuntspppnasto origmal rue coocemg emerrtucy comments from the Ohio Ctizens ot eplations to ensuo public health and prepadess ae sti in ffet. even Responsible Energy. Inc. were also sa,fet. Equally impoan howee is though the rule changes did reeived. The proposed changes to the the Cn smmIinpolicy to enste that r ot m ionany reisions to emergency licnse renewal rile wem published in its rguiations promo:e a sbe. prparedna requiments The the Federal Regiser on September 9. efficient and predicuible regulator Commissions rexponse is: yes. the 1994. for public comen Thre public . Them r. whee the previous mls provions on emergency interest goups provided coammts: the Commission ;cgies a m efienz prgparenp wr iut in effct Puliic Citzem. the Ohio Citzens for and stable m of achieving (6) Oe comientar staed that the Responsible Euergy. Inc.. and the Sierm partcula level of safety, i strives to rule should be wrtten in lnguage that Mub. Duing the upcomngb imnplxnent tha ppr- the averae. lterate citieD can detelopment of implementation h Caimismon implemented a comprehend. The commete frther guidace a standardreview plan for lice renewal nle because eisting sutes that technical terms, or license newal and a ruatory guide reguLations did not contin cr specialied paseolo whose p e for itceses renewal), exel NRtC gidac on renewals and. hurth. the is to ezpres a pfdese meaing, legal or meeg will be open to te public and Commission beLieved that current ot}evi. c and shou ld be fully thie draft standard revriew plan for jrgulations wem inadequst to addres for ComThed Conmssio agrees wit lis renewl md u;e draf reultory the ef}ects of *&a in the period of e comentr to the ex:-t that NIRC gude for license renewal w;U be made documenlts shfould be wrtic - so tbat as available for public comment. plementation o th pvious liense m y peophe as possible can I8) NEI Itated that 10 CFR 54.Z3 renewal rule. however, the Comision efl-tehnd }|.n. e expectation Is requires au envimnmental mport that eterned that the rule cold be ftzraYffCommission documents to be complies with the requirements of o mendedto create a m e cent and witteiras clewly as possble so that CR Part 52." 10 CFR 51.53 requirs a sable license renewal proces. while they can be easily comprhended. The ;upplemental environmetal report. The e ining the sDe degre of sey Com:ission has taken steps to clari wording should be consistent between ptovide b epnous rul. technical terms and phrsolog in te Parts 51 and 54. t Commission at*s ; 41 * ce tha t the Erial n!!e ."i: SOC. For example: the and the Pan 54 wording wiU be cbwed Commission should be analvzing phrase "a&e-r'ated degradation unique to be consistent with Part Si. whether the was any condition. a. or to license rencial" was not we!' tg Two commentm encouraged the pracce tha ocurred during the period undarsod and not eily explaired; in creatioi of implementation gidance n - of itialtlcnsing that would ffect tse par' becuse of this the Cohrlsicn has the form of a regulatory gude and a period of cxded opertion. In a broad rmoved this phrase from the rule. standardi.inew plan The current NRC sense, the regultory proces (7) One commenter claimed tbat the effott is focused on the completion of cmtinuously evaluates the safety status Commission did not consult with either this license renewal rule and the review of licensed plants and modifies any cnvirmcnental goup or any of the u;:ual license enewsl submittals. licensigbaes a necessary to ensure members of the general public when th- lbe NRC intends to develop and issue that plani operation is ot imical tO Commission was seeing advice during guida-e n the future n tbe fom ofa the publi baith and salety. As a public workshop on the proposed regulatory guide and a standrd review I

2U46 Federal Regiter / VoL 60. No. 88 1 Monday, May . 1995 Rules anc Regulations

plan bowtvar the guidance nay nor be rei saw aurwed in zspon to kg-lived. passive strucxum and isuad pni to the NRC awew oI- question 3 in this Secaa componantL Lt. however. an Mppjlican numk~of subittal.. Discussion. Th IPA in the proposed in the sitepPcc renwal pU to. 110) mcm*aw sAggested tha Amnenrment t the im renewa rule ?n demonuraz tht their facty ba the NC should cwquiz an updat of cOntains a procs to narw the focus pecik progrm or procs In p1w -t eavirs for parameters such as of theagn maaemn reve t to deted ongoing e adation such tha populstic density to awur that the enccpaishoeaasucad failura of wiundanL lo ULived.pasve orai a bi i a kai is till v aid compoe..stai ire "longlived" ad suZcturs and amiponents is avoided. -an l~~ renonal. "pasve" (see 554 AIaI)Wndti(U) l. the Commison may be able o credit The m doas ot aree that In1 SECY-14u. the Cmion such progam and al w redundanf. a rVwW of pin ervi4m is eswy considered the ponbilty that kong-Live, pasve structrs and as a prmditton i boom rewaL redund= lng-ived. passive C"spe to be generically excluded Aside hr ummh a reviw being beyd stuctum and -m-ponentscould be fl= e ng managMent review. the St.Opof01 Li: renwal the geercaLy excluded froma an apg 3. s there fftional informaio for Comniuiawa aregulatiocis in 10 (7K management review for license renwaL the Commission to consider that would 50.71fe) n qAia £fi s- teso e nre that The baxis for his consideration was tAt satsfy the Cowmisioa' n redundancy is oi aspect of a leense- rlative to the dction of degadation the FSR contains the lIat and Io ln-depth desig phlosphy that could &wnw nkv=fi Tbis nqAnmmt in redundant. onglived. pusi ve includes jn plant -e ' provide aspnahls surance that sturs andcoponents such that population dainty, which is coain cg lures would niot render failues tha mit result in los of n lly a m Caapter 2 of the systems. suu . ar companis system function arn unely, and to Incepable of peoring their intended warrnt a goeic exclusion? FSAJL function(s).The staff reasoned that Oe commet staed that -built in- V. PublI Response to SpeciSe not t eous faoilures of edancy iseessutl saty akture redunastructum and cmmponezts ad suggeed that redundn paive. amb imy pornble. the physilu Iong.iad ucne nd IComuaentsb In the Notice of Prpmd RuIn Is9 FR should not_ be exdluded.~~~~~~~~~ie roma aging at 46589. th Cmission requased an th diffrncsi opeational ari maintenan histozie pubUc a an fie spedfi Indutrycomnenm.an the other qum. The Commnission *pprecialee tha will influec= the lncddi*m and rates f aging d*adatiobetwve hand. attmpted to provide sufc i the puhc's m n an these fl e otherwise ietclsuvee and Iu ^Stlct (orgicy ecudn comonpnts make zinsous hiLum an aging management eVIeW thos fAcsa msoa A n agin m a nag enr of dd equipmt unlikly. a mmapanns whoe &ilure wiD not review is requiW kwa s;mall zibe of adiMMo misting progmS and retul in a loss of system hucticm. The s=ctuxas and cmponets within the Sequiets(Le malinna.m nile and industry divided thes components Ino soe of lices ruewal As desdbed 10 CFR Part SD Appenix B3)woul two otegoris (1)redundan in Sectiom m.f of this 2 the result in actiities determi the oot rcmponent and(2)wnallenmponents Com~iin beliemes.on the basis of c e iforlum nd mitig fe that can be solated such as instrument exis nug ir. y requimements and o00muncm of 0- liCeS. Tbe Industry believe that op entg expetl . that the Aging On iwihr csidAtin howver. -v.Ilived component that management rvmiew con be lmited to the Com mission h} opized. have d r ddancy are subject to 'passive," "n-lived" sbuctures and becma it = genetcally determine exteive lcese Programs that verify cmponen that ll lic es have procesin. structura itety ard functioGal 1. Should additional stm ad progrms. or p in pace f the capahiity. Ths extesve prorams. canem v within the sce of licen1 timely of drad d czi,Ms- together with the esublhd renewal be expldly required to receiv as a reslt of redundancy. ensure that the effects of an aging management mview' exuded opa or pve, loag- aging will be detected so th corrective 2. If[ewbat would bethebas s for lived s ctu d po that acti can be aken befor a los of the requiring suh additional suesw and the ptnileit o eue systems intided fcsion. The cmpons to be subjec to an agWng r and i of nedundoi industy beliee that the sringent managemet review? long-lived. passve s 2tctr and seismik desg requirement coupled Comters responded to questions I cponents. If the condition of wth cune plant programs prvides and 2 by afng st addiUoal srures and cmponents wre Wgater mninm that StrUCtUMa structr and cmtpoalOst inl degradedelow their CL I.e., dLi Interty and c bWlIty of passve in the proposed rl requi w agun component wall be maintained during management reew. no additiona without detection and correcive +in an cuthquake. Moeovw. the indust structum and components require &a a fle of edundant. passive beLives at the gow. long-trm aging mwa.gement review. and stiru aI cosuponeaw is possible chcxaarictwc of the agig proom and mrum ad Carmponeats equiring a givn. forexample. th o~rene ofa tba that thisuagg prote s niot i anagement review under Lhe desigss sic ent SU tht the ,ccurrng at an identi rein prpoed rule should be excluded. The ~ylm may Dst be ale to porim its Weunda6nt trains, allodegrded auitioas *o beoe r4I-rviG Co i has reponded to the yde Ch nnLrt TbemD~~~~~~~~~t wthn inc,vidual ets omrequiring aa Meay monitauable performance andIm- beLofi a loss of the iwtnded systm aging management rvew for additicnal codiiorcanaziristiig to reveal functio. s6trcL and components in Section degradain that exceeds CLD levels (as As discussed in the proposed nle d)ofths SOC.Com ents staing in the cae of passive. lng-lived ameudmnt. tii Conrtussma coaduded that additionAl sWuctue and strctum and componntsu the that passive. long-lved copoawts co*ponents should be geneiczilly ommiss= believes it insppropnae a., shuld ha bteCI tD an agi excluded hrnm an aeing management permit ew exch-sior ofredundan. mansgement re w beause. La generaL -- -

_,-4 ':

_,; Federal Register I Vol. 60. No. 88 / Monday. Mav . 1995 / Rules and Lulations 22487 I homoiad.padation of the not result in the lost of the aSSOL. .ed replacement of retired nulear power ponts is not as readily revealable system's intended function. The plants. One utility has recentlv MtAt the rqeultoy pr= and industry cites smal ins.uimzt lines indicaled that deisions 8reag ~ licene proram may not and sensors that can be isolartet (i.e.. license renewal made earlier in The uatelv the detimmta manual isolation by operaLt.: -31 a c. iment license term may ceate -ectl of son the parod of examples of -pones thA .uld be substantial curmnt-day economic ed opeatic. n their comments excluded from an agng mangement advantages while still providing a the psopoed rule amendment. the review usin taw criteris. sufficient plant-specfic history. This industry provided some exampes of The Conmisson cannot genrically utilily suggested ta the earliest dale * ow aingsa cdoerta passve exclude these components from for fiUng lIcens renewal application id cmpooets could be consderation for an aging mangement be changed so thet e license renewal *tuandw,d by the Commisson to be review for several reasons. The application can t,e suabmitted earier Meutaey managed during the period Commission doe not deem it ta 20 years before expination of thc -olennaded opeation. tkvrr . the appropriate to genencally cedit existing operating license. The tetm of begs for the .png magement operator action (e.g.. manual component the .enewed licene would still be -pms desaibed in the examples isolation). exclusively as adequate '&inglimlited to 40 year. r aiin on iidiidual licene psgmms management for portions nf systems tAt 4.1 k Iere a sufficient plant-specdfic tvher than on design rdundancy. would otherwise require an agiga history before 20 year of operation as While the industry examples mav be management rew. Such an exclusion specified in the currst ruke tlat ahsifurit mning th eiag ng of a necessarlIy presumes that manual valve provides reeso abl asu r ti-i 'uu r cat onet is aduwtely isolation would occur-a presuription aBinB concerns would be identified? 1f .omaged in plant spec applic=. th- Commission canot mle. Ir. not. can reliance on industry-wide -4, mez^iC = mi uaccptabilityof a.:tion. ae -pasive. "long.Uvedw experience be used as a basis tar isdimah gpnus th vanauons amol p portions of systms hatierto oah considering an application for license pln dsigus and propams. Howevt.. intended function a eed in renewal befor 20 yeas of operatio' . leNRC gaisuoe expenic with § 54.4(61 require a aing iunaaen ent What should Lie he earliest tume eni th afe, of agng during fhe pnod of review. Instrument ai. or exle. applicanlt ca a pply brarenewe *=eadod opwtion and cLu beaer typically apre, ps e".long.llved license? define the bounday of adeute apng and form parn ol s systemts presunr The NRC reeived six reponses to the Management forpassive. kng -lu bounda'. The omssion cannot question. Four of the six coinmsenter3 ur end emponts. the gnnlly exclud these portions cf opposed coouideretion of license Comisson may cnsider furber sys2"topmfan ganangien st runewa, apphatimis priorio:o wars vr arTro tLh- wape of pav. o- m n t rcsssevfie f these portions opertion. Th. coments included *id structtwis and composents alsystenis ma,retlt nthe loss of the arguments such as: % a am untrevw. syterm's intendted funcion le.B.. (1) Eary applicationas mauv, Ino allow nW titIlj t dussry did not required instuenatin presure for the effets of deterioration due wo adoquatelyadd.es th eCowmston' bousndar. flourte). Terefoe. ane aging to appear in sufficteni diversity or c. relatie to an degaation applicant for liese renewal will be intensty Ear anaeent to acq}uire a below deign bases occu-i requiredto perfonsm an agn Mli]r e of exeiect5 n dealing with Sinahaneoly in redund an tr suck, m anageen t reviw for thies porionIs these prolenm: that an initiating event (eg- a seismic of syste s. H o e an applicant for (21 UiCensees migh apply for renewal ev ns ma l e to f ilu re of the iceLw enewal ay prform. or may over ashorter period betore thse effects intende d y t ' f n u n syheL have performed, additional plam- ofaSn ap¶ lia tinL cou Id indus~'vs argument that aing will not specific anal. . that adequatelv Ocu t identical raeS and th at a falure demonsuate that failure of these non. n '- tvely i mp c h re i w hedu l I n redundant tri wil led to rdundaut ptons of ystems w1l not IC? older plants: and invtigative and corretive actios result in 't loss oanv of ili A! ndated (4) T er is a lac of experience with befoe the remain compont fails. is sstczvs' intended functions. di this the man tenace rule. One of t2ese nOt Campelig. Absent more dailed case. these plant-specific analyses could com enters suggeted theposib iity of inforMlat. the C i-i=oa Cannot provide the bs tfot lIcenS reneAl aipprovn a cense renewat lctpgent preclude tke posshibty of cn=on applicant to nnlude hat these ro- on rmppbegfoer20yn special tetinag ROde ilujues o[red=dan pamv Xduridant portions of systems do not requiremnents du.ruig tie fina2. years ol sM=zW and c=mponants. urte. the m eet the functional scoping conri or spe ongial license remto ensuretat COMIhission beleves that crditing a S 54.4(b) ad, therefore,are not subjec sstati physial derdation of ftuJry r,u"r:meAt fi.i. lton gi management teview. pagive, onesioe d bfe-erifed ridundaocyt as a £rogate for an agng Dsussion. The Cmmssio equimnt ba noSt occUrred NE1. w.hle Managemet prorm o ensur a concluded in the SOC fIt the curnt not pnicllev forindtvrule change 3!ses inteded fhncuon exploits the license rnewaJ rule (56 F 649'-3: allo ingearly applications. stat th Co n~ 0 f's deicnse-indznth December 13. l that o Ye-s of .lepedg 01nthe individual plant and PLiloophy. in addition. this aasument operamutoal and reulatorv exp-nence ts obeaing histoy, tter. may be i *5uQ.rciLI buse the eblished pr'vides a 1i.-ris with subsanual suficient opeang ,stlo. avlable tO ied Lldsancv would, ane be used amounts of uanfonntion and would provide reoble est.iane that rng to "uoe contued reduadinm the d.sce any plant4peific concrns concerns can be identified and period of ex mded opCUation. with regad Ita-rlted degmdaton lierefo?. an appnt ma' reuest an The idusnzv alo p-opoed that toe In adduo. a licen renew decison xemtion. One ohesier DOE' was Coliuaso gensCally exclud bmz lith pprom31ely 20 a5 remalnzM in favor of a rule change ailowing n La agig u.AnAgeMnt itmtoW CeMUD on the cmtrg lcenze would be earo pphczn. Oi sted that. in POItbos ut svs .iis wbc.e faxhl' ca reasonab;e cns;ulnn te eti1mated general. avznu effects are sDwt,oen% afro eflther be solated cr whose f±lu- wil ':m ne r for uJites tO W.Ian "r only a ofewersn oe norxaiOn and that I m

2'488 Federal Register / Vol. 60. No 88 / Mondav. May 8 .95 ! Rules and Regulations

industry-wide data provides a sound VI. Find.ng of No Signifi.ant screening of svstems. structures. and basis to undertand and address the Environmental Impact: Av.-ilability components to identifv those that must effects ofiagng. even at a plant that has The NRC prepared a draft undergo a plant-specific aging operated only a few yeas. DOE foresees environmental ass.,ssment JEA) for the management review and (21 the form of no technical impediment to license proposed rule p;:.suant to the National tht aging m -'mement review. renewal prior to 20 years of opersuon. Under the screening of systems. Environmental Polinc Act of 1969 and components that must be Based on the general nature of the (NEPAl. as amended; the regulations structures. nformation provided by the further reviewed, the proposed rule issued by the Council on Environmental n2rrows the scope of commantur. no change to the flul rule Qualty (40 CFR 1500-1508). and the effectively will be made. The Commission is svstems. structures. and components NRC's egulations (Subpart A of 10 CFR subject to an aging management review willing to consider. however, plant- Sl). Under NJPA and the NRCs specific exemption requests by those rgulations. the Commission must In general. the previous rule contained applicants who believe that they may a !afinition of ARDUTLR that would consider. as an integal part of its ca.se many systems. structures. and have ufficient information available to decisionmaking process on the justify applying for a renewal license components to require further aging proposed action, the expected management review but would allow prior to 20 years from the expiration environmental impacts ofpromulgating date of the current license. existing licensee programs and activities S. What additional safety. the proposed rule and the reasonable (includling the maintenance rule) to environmental. or economic benefits or alternatives to the action. The NRC serve as a basis for concluding that concerns, lfuay. Wou! result from a concluded that promulgation of tL ARDUTLR will be adequatelv managed decision about Jicense rvnewal made proposed rule would n.. significantly in the period of extended operation. The before the 20th year of current plant affect the environment and. therefore. a proposed rule would retain the operation? full environmental impact statement sceenzng of svstems. structures. and The NRC received two msponses to would not be required and a finding or components but would reduce the scope ths quesuon. NEI felt that a significant no significant impact (FON.;tJ could be of sstems. structures, and components economic benefit would likelv be made. Tb. bauis for these * onclusions requiring review to a nrrowly defined derived from license renewal deciSions and the fnding are summrrized below group based on an NRC determination. made before the zOth yer of operuon. Tbe NRC previously aw.ssed the in this rulemaking. of the effectiveness However. they stated that the -sdustrv envLronmental impacts &com of current licensee programs and canot esrimate the exact beuiit promulgatioa of a licenm renewal rule activities and NRC requirements that because it is likely to vary considerably in NUP -1398.4 Envronmental will contnue into the period of from Dlant ; pnt. NEI aJso stated thi: Asessnent for the Fial Rule on extended opeimtion. BecAuse the it is cear that knowledge gained from Nuclear Power Plant .canse Renewal." proposed rule has essentially the same license renewl will enhance the In ths ssessment. the NRC concluded results with respect to management of uLtility's ability to engage in long-range that the promulgatian of 10 CFR 54 will aging effects in the period of extended planning and may enable the utilitv to bave no significant impact on the operation as the previous rule. but modify its electrical rates accordingly environment. Withis assessment as a provides a more efficient process to DOE added that thev were unaware r. baline, the NRC's approach for achieve these results. the environmental any safetv or erivironmental concems assesing the environmental impact of impacts of the proposed rule would be that wouid result from a license rnewal the proposed rule centered on analvzing similar to those under the previous rule. decision before the zoth vear of anv differences in the expected rule. With rtspect to the form of the aging operation. other thai those iss-es that related actions from the previous rule management review. the proposed rule would be considered for any l:cense compared to those under the proposed would establish a clear focus on renewal. rule. managmg the functionaltty of systems. No new specific r.ori-'...-. The rquirements fcr a renewed structures. and components in the face concerning additional safety. license under both the previous rule and of detrimental aging effects as opposed environmental. or economic benefiLs of the proposed rule are sumla Both to identificatUon and mitigation of aging license renewal applications before the approaches could result in the operation mecai.sms. The Commission 20th year was provided bv anv of plants up to 20 years beyotd the concluded that the focus on commenters. Thetefore. the Commission expirtion of the intial lUcense. An identification c-aging mechanisms is has determnined-not to change Section em;phasis would be placed on cena:w not nacess- because regardless of the 54.17. systems. sunctues. and components agin mechatsm. onlv tiose tnat iead undergong a specific agmig management to degraded component performance or VL Availability ofV..cuinents review tprovide assrance that the condition (i.e., potential loss of Copies of all documents oted in the effects of agg ae adequately managed. functionalitv are of concern. Therefore. Supplementan- infornation section are thus ensurng funcuonality dunng the the Commission cuncluded that an available for inspection anKor for penod of extended operatiun Under aging management review that seeks to reproduction tor a fee in the NRC Public both approaches. license rene%al ensure a comoonent's functionahiv is a Document Room 2120 L Stret N.W applicants must screen plant svstems. more efficient and appropnate review Low-er Level). Washinion. DC 2oiSS structures. and components through an This riane oniv improves the in addition. copiet o NURECs cited MA to determine wnica svstems. efficiency of the licensees aging in this document mav be purchasd stuuctures. and compontsis w;:l be management eview. Therefore. the frorn the Supenntendent of Documents. subect to a lcenme renewal review anrc environmental zmpacts wculd be sin. :lar t' S. Governmer Pnnung Offie. Mail then cetermine whether adtuonal to those under the previous rile. Stop SSOP. Washington. DC 20402- actions ar required to manage the The ulumate iicensee actions to 9328. Copies are also available for effects of a.tknv so t .. *e interoed manace aaing in the renewal term under purrhase fom the National Technica' funct.on is mantunec. he pnncipal the proposed ruie are expected to ot Information Service. 5285 Pon Rovai differences betwen tne proposec .. e similar to those uncer the previous rule Road. SpringfLeld. VA 22161. and the previouS ruie are in o I the H,wreve-. ttie reoutred activities to -__ _. - - . _- - P .--- - .-. - .-

federl Regitr Vl. 60. No PA I Monday, Ma! B. 1995 Rules and Regulations 224q4

maug* Lbeeffects of aLng will be Second. for the pwpos. of evaluatng tele art to 10 CFR 54 or anv of ts amied at mon ufficiemly under the the enVirozmenul impacts assoated arenornents. The ormal requireinents proposed rub. Thereo. the urith grantings,renewetd licee. the that an applicant for renewal must meet envuWnetal impact of aicease NRC is pp.Ung "Gnenc and the infummauon that mus be renewal under th. proposed rul* would Enviromentsl Ipact Statement for submitted for tne NRC to conduct a be simuLr to t ko IcSt renewal license Renewal of Nuclar Plaits" licenst renewal review arv established under the prv s rule. Hance. the (GEIS). NUREG-1437. as pat of its in ID CYR 54 The environmental Commuon concluded thAt tho amendmms to 10 CFR 51. Te GEIS assessment forthe previous licene proposed rule would not sagniantly address, in genic fashion. the renewal rule (NJRM-1 3968 assessed impa the nvironment. impts ass Ciai 'th contnued the degret lo wich the renewal of TheCommisionis EA and FONSI for oper.tonf anuc . nit beyond its operating licenses via a formal the poposed le wee nue3 i dr scsergtibe impacts regulatorv process would diffr from and pubic cmments w solhaed. of activitie to counter the effcts of renewal ol operung lcenses under Several public comments wer rece ved aging. the impacts of higblevel and exitng regulations that did not specifW and ar addressed below. low.level waste, aud tse effects of standards for cense enewal The Two om=mte su t teNRC radioactive discharges. In addition. the Comrnmission conduded. in hat should be e dto prep n EIS ktr Commsssion has proposed amendmnls environmenal assessment. that the license rea n mnl. tu to io CFR si that would require that a impacts hrm spent fuel storage urder a com ters beliew -.at the E1S supplement to the GEIS be prepad for formal license menewal proess %ould should indude dusionon the individual icens newal app.ications not differ from the spent el znpacts follow=ing es to addres thos impacts that could not fom licens renewal under exsing lal A full desaiption of proposed bg geercay evaluated In the GES. regulation that did not specifh mpiupin eures to counatin This supplamn would be issued n stanrrs or renewals. Thus conrlu,son reactor degadation due to agrg draft for public commest. does not rely on the Commsion's Ib) The cumulative frect of an added One commeaer stated that the draft was t confidence decision. FONSI for the proposed nle is Upon cosdenng Lhee cormmcs. I z2 vmn of discge of radioactive coolLg waters andor steam: inappopea The commente stated the Comrnon has detercinnd that the I c) The nvironrmtal impacts of that the NRC is u-g incetves for coromntet's conerns do not alter the proleepd stockpiling of ighlevel and the litzmees to seek licenase rnewal by pmposed finding the EA for the low-rvel waste; and easing rules. The commenter stated thut proposed rule. Cooqueitlv. the the reducton in rview of the new zrd Commio bas determined under the II (dl Plans for public ivolvent fom I the first scnping will result in cant enenvimnmental NEPA. and the Commission's P s-on. though impacts. regulaons Ln Subpa A of Q I subsequent public heing. The Commission disgres CFR Part I eFONS fior the proposed ule was S1. that his rule s not a major Fedeal The Commton hs dertaken a based on the FONSI om the previous action sign.ficatlv alkfeng the qtualtv renew of the evironmenal impacts of license rensewa rule Isee NUEG-139B1 of the human envutmrment; therefore. an license newal f two different environmental supect perspectis. Fr. for theurpos of adte analvsis of the difference sutement s not evaluaetin he exwvironrnencalI mpas of betwen che peious rule and the required. This s because this rule will a fol regltory proposed rle. hs discused its tlse e result U the same activities o process for bcense for the proposed ri;e. the amended ue adequately manage the effects of -ging reel. th NRC pepe NiUREG- isill result hn the sarv titis imthe penod of extended operation as 1398. This eio ntal asseren required lo adequsatelyrnmnge the in the previous rule. although. it affves nreed to sse= the degree to wich the effects ofatg in the period of at these sctvities in a more eflicient :newal of peating licseS via a extended opraon s is the pevious manner The EA and FONSI on which fo,l regutory pxess would differ rule hovr, thse ntod fr arrivg at this determination is based am available fom renewal of pt . ir , Ucenses then activities will be more efficient. for nspection at the NRC Public idzr exiing reguLt that do not This effiiency Is gained beouse the Document Room, 2 20 LSueet N.V speci: tandards for licnse renewal NRC is generically crditing. in this (Lower Level). Washington. DC Single applj&-wo The envirornena rule. the exning agng management copies of the envMumental assessient assessm -t discussed the issues of progrms for which the applicant would mav be obtained fram John P. Moulton. ddinonul waste generation. activities have had to descibe and iustIfy under OfMce of Nuclear Reactor Regulation. reuie tci addrss aging dog iaxo in the prmvious rule. The ommi dms U.S. Nucear Regulatory Commission. te reewal period, and impacts of not agme with the cmmenter that the Vashington. DC 20555. 1301) 415-1106 radoactve ischares. The Commission amendments to the prvious rule coauded In that envroena represent any less stingent a review. VIi'. Paperwork Reduction Act ssinent that a formal license ewal The enviromental impat from the Statement ualaior tublishing the sAndds or amendments to the licens r=lew&J rule This final rule amends information hi 5 renewal applicatios would are expeced to be the wnDe ax the collecion requiments that am subpct resit in no p ant mpart horn previous ue beause the utimate to the Paperwork Reducton Aco 19o 0 thos impc= expeaed frm retewal actios to manage aging will be the (44 U.S.C 3501 et seq.). These Wahouta lorm.a.iceneWal same. Therefor. consistent with he requirements were approved by the PoaL T sal performed an rdindg of no gaScant inpact for the Office of Mazagement and Budget. additional evroMul asw=meat for previous mle. the Commission finds ap,roval number 310-0155. te Proposed amendments to the this finl rule will fesult in to Thne publc reporting burden for this Pzftlu [ir= rewal rule and signufimat mpact. collecuo of inlformauon s estimated o alCluded. Cons stnr with t pvious Ore comment sttd that the waste average 94.000 bours per response. MvIir;menta. asesment. that the confidenrc dasios asu=pUons can including tbe tim for reviewing 'mended rule would result n no not beinsxd to lcense renewal. instrcus. searhing exiskiUr data tillficaut impac. Ihe wage cOitdence decision s not souces. gathenng and maintamng the eU a

22491 Federal Retsler I ol. 60. No fl Monday, Mqay . 995 Rules nd RegulationLs data needed. and compltUng and amendment constitutes a change to an pursuant to 10 CFR 50.109 ieed not be reviewng the collection of Information. *usung wulaon. the NRC has parpued for thus rule. Send comments regarding this burden dtesmd ht th*e bacst rule. Ir CFR NEI commented that tsM NRC should eStiale or any othewraspect of this 50.m09. does not apply beuse this review its detemination regarding the Collection of anfmatmon. including aentment only cts prospective applicauin of backflt protecon to sucg ons lor reducing this burde, to applcnts for licens renewal. The license renewal. AlLhough not dlrlv t!e Lifnaintion end Recordi pnmary impetu far the backit rule was stated In its comments. SO sppe to M nugemnt Brnch T6 331. U S. -regulalrystabniliy." OCe the ague that the protecuon arforded by 10 VNtcbar Regulatory Commission. Commion deades to ssue a license. CFR 50.109 should apply in indidual V'ashutgtoa. DC 20555-000: and to the the ter and cwiuons for operuing license renewal proedngs whent hi Desk Office. Office of Information aud under that se would not be NRC *eeks tojmpose irements Liu Regulatory Affairs. NEB-10202. changed Wudy post hoc As the ''beRond what is naceshy for 13150-O15Sl. Office of . t4anagautazd Co-mison ex Sin the preamble aequatly mngng th e.sc-cs ol agin, Budget. Wahingtan. DC 20503. for 10 CR 52. whid t rospecutvlly on Intended futons theX penod ot eitendd Opl.; 'on (i.e.. ix. Regulao r' .aeY"Is changed the requirements for receisng dign cesficatins. the back t rule- enhncmnts). NE! stated thxat in such The NRC prupored a drat regultory tWh stot itended to apply to wy cases. the NRC should perform an analysis of theLvalues and impat*s of the rguiatory a-Mo which changes tened analvsis to demonstrate that the propoed re and of a se o! sugnifican expaa s Cearly. th backfit rule would ptooed additional requim ments will not apply to a rult which mposed mna result n subsntial Incra in overmU smn t rquiremmts on all hu safety and that direc and indirct cosu Comsns public document room applicmnt Ix auctimpermi. e we justified latve o the safetv fc? review be intersted m emb of the tboujrsuch a rule muat arguably have an benefit. Furthermore. NE) iemheves that pulic. Ln aditn, * summary of the Nd impect m a pa who was if teTre a two or mor rean of findinsp and conclusions of the coauideruag applying jara pwst but bad not adequatelv manaing the effets of regulatoy nalysis were published in do. ee y. In this attr ca. the backit aging. cost must be taken into account the FdeM Regter (59 FR 46591. rad peou t cmatom pemi hr. irn sleng an alternatle. September 9. 1994) concurrent with the but ot rw_ pplian. or evn th The industy's desire for a special proposd rule. No comrnents we prMf applzCLaL (54 FR 155; Apnl 18. provison in the rule tht would unmpose receved on the reguatrv avs. The 19gag. backllr-style requirements on tl regulator analsis has been Enaized Regulatory sabilt from a bwcfLuing Cison's reiew is neither and is avaible for npection in the standpoint s not a relevan issue with necessary nor appropriate. The Intent of NRC Public Document Room. 2120 L rpect to this rule. Therc are no the license renewal rule Is clear-io Stmret NW ILower Level], Washington licenee cumntly boing enewed ensure that the efleu of agn on DC. Sngle copi of the analysis may be nucl pow plat operatng licenses functionality of cerutin sstems. obtained frm Joseph J. Mate. Office of wbo would be affected by this rule. No ssuctures. and comonets re Nuclear Reactor Regulation. U.S. applications for cen rnewal have adequately managed in the per_i. i Nuclear Regulatory Commission. beendockete It is alS urikely tLt extended operation. The Commission VasJngton DC 2OSSS. (301) 415-1109. any lice r wal applications will be does not intend to impose reuirments skbmitted before this rule becomes on a licensee that go beyond what is X. Regulatoy Flexibilify Act necessary to adequately manage aging Certificaton effectzve Consequently. there are nL valid licensee or applicant expectations effects- The industrv's As reqwred bv the Regulaorv that may be changed gadng the terms concern appers to be an potenital Flexil'laty Act of 2980. (S U.S.C. 605 and conditions for obtai a renewed digeements between the Commission fb.i. tlp Commission certifies that this opting licnse Accordingly. this rule tnd renewal applicants regruing what r e does not have a significant does not a tu a ckfit" as is or is not considered "adequate" for *- -t impact upon a substanial defined In 10 CFR 50.109(a)(1). Managing the effects of aging. The number of small enutits. The final rule Commission understands the industry's sets forth the application procedur Furthamor. one aso the concern. but does not believe it and the technical requueements for Commission is amending it) CR Part appropriate or consistent with current mreewed operzting licmses for nuclear 54 is because of the concerns of nuclear race to tuther hmit (i.e.. bevond the power plants. The owners of nuclear power plant licenses who were Cits established bv the rule) the NRC power plants do not fall within the dissatisfied with the previous staff in its review of an application for definutui of small business entiti-s as requirements in 0 CFR Part 54 and a retewal license. dt fined m Secion 3 of the Small ured the Commission to modify the Additionally. the Commission sees no Business Act (15 U.S-C 6321. 'he Small rile to address their concerns. Under justticaaon for quiring a Busness Size Standards of the Small txs circumstance. the p!v objective consideraton of costs among alternative Business Adfunwstrion 113 CFR Part of te bcit rule would Dot be served aging mangement progrms. The 1211. or the Commission's Size bv underAking a backfit antivsis. renewal process is desipied such that a Standards :56 FR 56671. November 6. RLgulatory and technical alternatives for renewal applicant pt0pOS05 the 19911. addressing the concens with the al te rna t es it beli ev es rnan ages the previous 10 CFR Pat 54 were analyzed effects f aging for those sw ures and XI. Non-ApplicAbility of the ackfit and considered in the tegulatory components delinet by he rule. The Rule mnalysis that hs been preourd for this NRC staff has the responsibilitv of This rule. like the previous license rule. Prepartion or a separate backlt reviewing the applicant's proposals and renewal rule. addresses the procedural statement vould nct provide anv determining whether they are adequate and techmcal requirements for substantial additional benefit. such that thcre is retsonable assurance obtatning a renewed operting hcense Therefore, the Commission has that acunues authorized bv the for nuclear power plants. Altough this deterrnued tat a back}it anahYsis renewed license will contnue to be , 1. r . 1% ' -. A -

tederal Rstitr Vcl ta No. 8 / Mondav. Mav B. 19,95 Rules and Regulations 22491 -

ronduced in accordance with tht CL. under sc 102. Pub L 91-190. 3 Stat 853. PART S1-ENVIRONMENTAL The Commission beietves that this a amended 148 U S C 43321 Sections PROTECTION REtULATIONS FOR IMNi renewal revtiw muit necessarilv 2 700g. 2 19 sIso isuied under 5 tU S C 554 DOMESTIC LICENSING AND R£LTED be performd without rearp o ost. SOcions 2 7S4. 2.760.: 770 2 70. also REGULATORY FUNCTIONS tssed under S U.S.C 57 Seasm 2 764 and L f Su,* Table IA of AppMdx C A" am sued 3. The uthonty citation for Part S s 20 CPA Pr 2r under s. 15,141. Pub. L 97-425. 96 Stat. revised to read as follows: Adminsitaive pracuci and 2232. 2124 42 U.S.C 101. 1t011 Sectotin Auhenty: Sc. 161. 61 Stat 948. as procedure. Antitusv.Eyproduct 790 also ssu under "c. 103.58 Stt. 936. Lme*dtd. Sec. 1701. 106 Stat. 295. 2932. as amended 142 U.S.C 2331Mand S U.S.C 2953.142 U.S C 2201, 22s1fs. secs. 201. as matwnal. Clafied ifomtion. 552. Secoons z.8 and 2. also isud amnded. 202.8 S5tat 124 as amended. Eanznrstal prection. Nuclear under S U.S.C 551. Sectin 2509 also sd 1244 142 U.S.C 5841.55421. Subpar A also matenis. Nucler powtr plants and under 5 U.S C 553 and sec. 29. Pub. L M5- ;.swud undet Nauonal Envuonmental Policy rmcon. Peals. Sax d scruwaton. 2s0.71 Stat 59. asatrmdad (42 U.S.C. Act of 1969. sec. 102. 104. 203. 83 Sat 53- Source matenL Specal nuckr 209) Subpr IC .Mto issued under tac. 189. e54. as amended 142 U.S.C 4332.. 4334. matenal. Wase tement and disposal 58 Stat 95142 U.S.C. 22391: sac. 134. Pub. 4335); nd Pub. L 95-604. itI 1I. 92 Stat. L 97-425. 3033-3041: and wc 193. Pub. L. 101-575. 10 CFI PonSi 6 Stat 223) (42 U.SC 101541 204 StUL 2835.42 ;.S.C 2243). SecOt Subpan L also sd unde se. Adminstive prace 19. SUt. SI."0. s1.30. 51.6s3. S2.61 51.J0, ar ' .14 and 42 U.S.C 2219J. Appendix A also sued procieure. Envirorntetal impa ss aso ssued under secs. 135. 141. Pui L 7- undet sa. e. Pub. L SI-sWo. 14 StaL 1473 statement. Nudar materia. NucLear 425. r StaL 2232. 2241. and c 148. ru,. power plants and recors. Rporwn (42 US.C 21351. Appendi Blso iued L 100-203.101 Stat. 1330-223 (42 US.C under wc 10. Pub. L 99-240. 99 Sat. 1842 1015'. 10116. 10165). Section 51.22 aso and rordkeepsg requirements. 142 S C. tolb et q1. issued under sec. 274.73 Sut. 686. tO CFR Pan 54 amended bv 92 Stat. 36-3038 42 U.S.C 2. In 5 2.7S8. pargaphs fbi and le) 2021 ud under Nucar Waste Policy Act of Administave practice and L revised to read as foUows: 1982. ec. 121.96 SL 222 (42 U.S.C procedur. Agig. Effects of agn. 10141 . Stions 51.43. 51.67. an 51.109 TL-e-limited analvses. S2.73 ComtdmasUoo of Commission also under Nucler Waste Poliev Act of 1982. Dakfitting.. ,fied iformation. rna"WWtgulem sdpJdcWryIn ec 14(1). 96 Stat. 2215. as amended (42 Criminal paltis. En%otmena U.S.C 10134(nl. prectioo: Nuclear power plts and w . . * S 4. In J5.ZZ. paagapb (c)(3 is rectot. Reporting and recodkeeping revised1o read as fllows: requMreentsE (bi A party to an adfudicatory procedng involving intial or renewal * 81.22 Carion for Catgorical amsc*aion: For the msoo. set out in the licensing subject to this subpart may pAmbe and under the authoi of the ideatfton of Iloen and reguwy ptition that the a ecvoe e4bbe for tegofita! *wJusion or Atomic Energy Act of 1954. as amended application of specfied Commission o rwe not ,equklng anvrentm the Energy Reorganition Act of 1974. rule ortgulation or any provsion thereof. of the type f. as nded. and s U.S C. 552 and 553. * . . . S the Commission is adopting the described in paragrp ( of thv; section. be waived or an exception made following anddments to 1o CFR Parts 13) Amendments to Parts 20. 30. 31. 2, 51. and S4. for the patticular proceeding. The sole srund for pubbon for waiver or 32.33.34.35.39.40. -'. 5. 54. 60.61. PART 2-RULES OF PRACTICE FOR exception shal be that specia 70. 71, 72. 3. 74.81 a. 100 of this OomESTIc LIESING PROCEEDINGS Circumstances chapter which relate to- with espect. to the 1) Procedures for filing and reviewing 1- The authontv citation for Pat 2 is subeci maner of tie pafrucular applications for licenses or construction rised read as follows: proceeding am such that tho applcauon permits or other forms of permission or of the rule or regulation (or provision for amendments to or renewals of Autkerity Se 161. 1. G Sta 94U. thereof) would not erve the purposes 9S3. as amthd*d (42 US. 2201, 2231) S1 licenses or construcuion permits or other 191. a: amended. Pub. L 7-615.76 Stat. 409 for which the rule or regulation was forms of permission: 142 US.C 2241 wc 201. 8 Stat. 242. as adopted. The petition shall be (ii Recordkeeping requirements: or antded 142 U.S.C 5421:5 US.C 52. accompanied by an affidavit that (lii) Reportng tequirements; and Setlion 2 lso issued und.r sea. 53.52. identifies the specific aspect or aspects jiv) Acutons on petitions for 63.81. 103.204. 105.68 Stat. 930.92. 933. of Jue subject matter Or the proceeding rulemaking relating to these 935,936. 931. 938. as anded 142 US.C. as o which the application of the rule amendments. 2073. 2092. 2093.2111.2133. 2134. 2135). or regulation (or provision thereof) sc. i14f1). Pub L 7-42S. 96 Stat. 2213. as anendtd 142 U.S C. 10134(fl). sec 102. Pub. would not serve the purposes for which S. Par 54 is revised to read as follows: L 91-190. aj StaL 853. as amended 142 the rule or regulation was adopted. and USS C 43321; sec. 301. 8 Stat. 1248 (42 shall st forth with particetrinty the PART 54-REOUIREMETS FOR U-SC 5871L Set,ons 2 102.2.103.2.104. special circumstances alleged to justify RENEWAL OF OPERATING UCENSES :.105. 2 7.1 alo 1ssued under c. 02. 103. the waiver or exception requested. Any FOR NUCLEAR POWER PLANTS 134. 105. 183. lag. 68 Stat. 936. 337. 938. other party mav file a response thermto. Cenral Proviions 954. 955. to amended 142 u S.C 2)32. 2133. by counter affidavit or othenwnse. 2134. 2135. 2:33.2239). Secton 2.105 arso Sec. issued under Pub t 97-415.96 Stat. 20. 3 54.1 Purpose 142 L S C 2:39, Sections 2.200-2 206 also (el Whether or not the procedure in 54 3 Deflnzi,ons issued unders ISib. i. 152.1l6. 234. 54 4 Scope. 68 Stat. 945951. 955. 83 Stat. 444.3 paragraph b) of this secuon is avallable. 54.5 Interprelations anetided 142 U.S.C 2201(b). (il. (oa.2236. a partv to an itiual or renewal licensing 54 7 Wrinen communications :782). sec. 206. 56 Sst. 1241142 U.S.C proceing may file a petuuon for 54 9 Information lIection requIremenS 5846) Sections 2.600-.106 also isued rulemaking pursunt to S2.802. DM8 approval 2 e R l 6 No8 - a-

22492 Fed Rie I al. 60. No. /Monday. Mav a. 1995 J Rules and Regulations

54211 Publicl opecnoolopp ;me. docketed licensing corspondence such accomplishment of any of the functions 5%.13 Complui- 3wd accw,yet as licens sponses to NRC bulletLns. identified in paragruphs al (li). (ii). or generc litte, and enforcement actions. (iii) of this 54 5 SpeiBa emption. section. .17 Fng fapplA1mL as wel as licee comutnrents i31 All systems. strucures. and S4 CWo1applIaUoo-generl documentd in NRC saety evaluaLions components relied on n safeti nalvses imsaton or licensee event repos. or plant evaluations i erform a 54.21 Coutnts oapplicaborn-4chaal lntq?ted plant asessment (IPA) is uncuon tat demonstrates complnce licese assessment hat demonsttes with the Commission's egulations for 5422 C s of pa h that i nuclear powe plat Iacility's strudures and components requiring fie protection (O CFR 50.4a). 54.23 Cutn of applicatio- aging m eanagment riew in accordance environmental q-hlification (tO CFR wIth §S4.21(a) or licne rnewal hAe 5O49).pressuzed thermal shock (0 54S Ret f t yAdvioryCommeon been idenfied and that the eftecs of CFR 50.61). anticipated tnsients agig on the fctolity of such without sctm 110 CFR ;c. -.2). and 54 27 Hr sution blackout ( CFR r .63). 54.29 Sndads kw issuae of a vced suutw and components will be managed to maintai the CLB sh that (bi The intended functions that these 54.30 Mrs m subdc toe iwnew there is an acceptable leel of safety systems. strutures. and components .WWW durn the period of extended operion. must be shown to fulfill in 5 54.21 are 54.32 ana of a renewed ltk. Nuclear..'er plant means a nucle th functions that ar the bases for 54 33 Csonuao of CLB end caoditios power e .ofa type descibed i 1o including them within the scope of of mnumd beanie CFR 50.211. o r 50.22. license renewl as specifBed in 54.3 R*s*umu during to, ofnwd Time-imited aging analyse. for the prgraphs (a(1)31 of this section. purposes of ibis pan. ae those licensee 54 7 AddiHina crds and rwcdkpig 154- lnbrprtonws r,quu5inB caluilatio ad anays tha 54.41 Viatios (1) avolve Systems. structures. ad E.xpt as speicallv authorized by 54.43 Crinl pesildes cottponent within the scope of license the Comission in writing. no Autb.r9y S*s 102.103 104, 161. 181. newal, as delianted in S 4.4(a): interprettion of the meaning or the 162. 28.15 239, SUL me. .91S 12' Conside the effects of aging: regulations in this par by any ofucer or 94L 953. 54.95S. as mnded. sr 2 . 3 [3) Involve time-limited assumptions employee of the Commission other han Sat 2244. asameaded,(42I.S.C 2132,2233. defined by te curQnt operating term. 2134. 2135. 220. 2232.22. 2236. 22. a written interpretation by the General for example. 40 year Counsel win be recognized to be 228Zl cs. 201. 2.0. 3 SuL 1242. (4) Wer determined to be relevant by 244. amad 14Z USC 5841. S4zL the liCenSee in making a safety binding upon the Commission. Gen" Provsons determinaUtO: §54.7 WrMnn commuinlcationw. (5) Involve conclusions or provide the 554. PM lasis for conclusions related to the AlD applications. correspondence. This part goves the isuance of capabilty of the smstem. structu, and repors and other wntten renewed opeating licen for nucle component to peorm Its intended cornunicaLions shall be flted in power plants licensed pursuasitto htnctions. as delineated In S 54.4(b): and accordance with applicable portions of Seetons leD or 104b of the Atomic loJ Are noteir ed or incorporated by 10 CFR 50.4. Eergy Act of 2954. as amended (88 reernceo r'aB. * S4 Infomation colletion Stat. 9191. and Title 1!of the Energy Ib) All otbertrt zs In this pat have ruqiwrenW. OMS apmovvaL. Reorganizatioa Aa of 1974 88 StaL the sae meAnir" as set oUt i 10 CFR IZ471. 50.2 or Section .- of the Atomic Energy (a)The Nuclear Regulatory Act. as applicab _ Commission has submitted the 15$4-3 DeaMwma. information collction requirements la) As used in this part 5 54A Sa contained in this part to the Ofice of Cuivent fiesing basis (CL) is the set (a) Plant systms, structures, and Management and Budget (OMB) for of NRC rquirements applicable to a ,omponents within the scope of this approval as quired by the Paperwork specfic plant and a ficsr*'s wntten a are- Reduction Act of 1980 (44 U.S.C. 3502 commitments for ensuring compliance (1) Safety-related systo.s. structures, et seq.). OMB has approved the with and operion witin applicable and compo which are those relied infornation coUection requirments NRC requimment and the plant- upon to e fnctional during and conained in thls par under contl speific design basis (including all folowng design-basis events (as numbes 250-0155. modicaons and addstions to such deEined n CFR 50.49 (bll)) to ensure cmmiments over the ire of the tho following functions- (b) The appruved Infonmation Imnse) thaz are docketed and in effect. (il The inteoityof the reactor coolant collection requirements contatned in The CLB includes the NRC regulations pres..u boundarr, this part pper in S4.13.54.17. contained in 10 CFR Parts 2.29. 20. 21. (ti) The capability to shut down the 54.19. 5421. 5 22. 54.23. 54.33. and 25.30.40.50.51.54.55.70.72. 73. 100 reator and mainan it in a safe 54.37. and appendices thereto; orders; licenso shutdown cndition. or 5541 1 Pub4I Iseton O lc8tion conditions: exemptions: and echnical (iii The capability to pvent r speaficauons. It tLso includes the plaot- mitigate the consequences of accidents Applicatios ano documents specific desrgnbasis informauon that could ril m potential offsite submtted to the Commicion n defined in 10 CFR 50.2 an documented eposure comparable to te 10 CFR Part connecton with reneval applications in tbe most eat find safty saniysis IOU guidelines. mav be made avaiable for public report CFSAR) as requLrsd by 10 CR (2) .11 nonsafety-related svstems. nspection n accordance wtth the 50.72 and the licensees =ontmitius structures, and components whose provisions of the regulatuons cnntined remainig in effect that were Mde In failure could prevent satisctory in 0 CFR Part 2. -. --- ~-- - lr- w -. ~~-.--

Federal Reister I Vol 60. No. 88 Mondav. Mav B. 1995 Rules and Regulations 22493

ComW4 s aW accuracy of a manner that all Restricted Data and cabinets. excl'uding. but not limited to. ton. other defense infomation are separated pumps (except casing). valves lexcept formation provided to the from unclassified infomation in bods 1.motors, diesel generators. air isb0n by an applicant for a accordance with tO CFR 50 33(j). compresors. snubbers. the cuntrol rod I license or information required (g As part of its application and in dnve. ventilation dampers. pressurm 'e or by the Commission's any event prior to the receipt of iransmitters. pressure indicators. water Ins. orders. or license Restricted Data or the issuance of a level indicators. swtchgears. cooling ns o be matnaaed by the renewed license. the ap- Ucant shall fans. transistors. battenes. breakers. must be complete and agree in wnung that t Wall not permni relavs. switches. power inverters. circia' in all matenal respects any individual to have access to boards. batterv churgers. and power *'applicant shall noufy the Restnried Data unul an investigation is supplies; and on of information identified made arsd reported to the Commission ii) That are not subject to alicant as having. for the on the character. assoauon. and replacement based on a qualified life tr activitv. a significant loyalty of the individual and the specified time penod. n for public health and safety Commission shall bave detemuned that (2)Descrtbe and ;ustifv the methods i defense and security. An permitung such persons to have access used in pangraph al() of this section olaOs this paragraph only if to Restncted Data will not endanger the At fails to nou fv the (3) For each structure and component common defense and secunitv The identified in paragraph n if information that the agreement of the applicant i this regargi (a)(1) of this 3s identified as hsvng a section. demonstrate that the effects of is part of the renewed license. whether aging will be adequatelv managed so mpucation for public health so stated or not. r common defense and tha: the iended funcution(s) will be tifiAtion nmust be provided 154.19 Ctemt of apptceon- mintned consistent with the CLB for isirator of the appropriate infon"nasn. the venrod of extended operation. :e within 2 working davs of (a)Each application must provide the fbI CLB changes dunng NRC review if ie nformation. This informaton specfied in 10 CFR 50.33(a) the application. Each vear following s not applicable to through el. (bl. and til. Alternatively. submIttal of the license renewal hat s already rvtured to the applicauon may incorporate by application and at least 3 months before - the Commission bv other reference other documents that provide scheduled completion of the NRC pdatwg requrments the tnformauon required by this secton. revIew, an amendment to the renewal Ibl Each spplxcation must include application must be submitted that c eiemptions. conformig hanges to the sandard identifies anv change to the CLB of the from the requirements of indemnity agrwment. 10 CFR 140.92. facilitv that mnateriallv affects the e grarted bv the Appendix B. to accoun%for the contents of the license renewal accordance with 0 CFR expiration term of the proposed application. including the FS.iR renewed licene. supplement. (c) An evaluation of time-limited appiacaton. 55421 Contnts of pplktion-4.chttcat uto'fion. aging analvses. if a pplication for a (1) A list of time-limited aging must be n accordance Eacb applicauon must contain he analvses. as deftned in S5.4.3. must bo if Io CFR Part 2 and 10 following nformation: provided. The applicant shall 30. (a) An integrated plant assement demonsate that- who is a citzen. (IPA). The PA must- (1) Mi)The analvses remain valid for the of a foreign country. For those sstems. structur. and penod of etended operation. -:. or other entitv components within the scope of this 4il The analvses have been pro;et.ed ssion knows or has part, s delineated in 54.4. dentify owned. controlled. or and slst those struciures and t te end of tbe penod of extended lien. a foreign components subject to a aging operaticn: or nre-i government is management review. Structures and I i ii t-he effects of aging on the for and obtain a components subject to an aging nm.ied fnction(s) will be adequatilv management review shalle ncompass managed for the penod of extended n for mnewedre those structures and components operauor submitted t the II) That perform an intended function, 12) A list must be provided of plant. than 20 years before as described in § 54 4. without moving specific exemptions granted pursuant to operating license pans or without a change in 10 CFR 50.12 and in effect that are configuration or properties. These based on tme-limited aging analvses as say combine in structures and components mclude. but defined in S 54.3. The applicant sball -wed license uith are not limited to. the reactor vessel, the provide an evaluation that justifies the inds of licenses reactor coolant system pressure continuation of tlhese exemptions for the nay incorporate bv boundarv. steam generators. the period of extended cperation. contained n pressunzer. piping. pump casings. alve Id) An FSAR suppiement. The FSAR for licenses or bodies. the core shroud, componen: suppltment for the faclitv must contain statements. suppons. pressurrretaining bounidanes. a sunmarv deicnption of the programs )orts filed with heat exchangers venulation ducts, the and activites for managtng the effects of ded that he containment. the containment liner. aging ad the evaluation of time-lanited I specific. electncal and mecianical penetrauoos. aging analyses for the period of :ontains equipment hatches. seisr-nic Category I extended operaton etermined bv defense structures. electrical cables and paagraphs (a) and (c of tbis secton. prepared such connections. cable tavs. and elerncal -esoectavciv - - - . ZONVIIXV-7 -, -- " - --

22494 Federal Register I Vol. 6. No. 88 I Monday. Mav . 1995 / Rules and Regulattons

54232 Conwoa otopp lbchn (b) Any applicable requirements of continue to perform their ntended Subpart A of 10 CFR Part 51 have been functions for the penod of extended Each application must include any satisfied. operation. In addituon. the renewed technucal specification changes or (cl Any matters raised under 5 2.75 ILctnse wilU be issued hi such form and Additions necessary to manage the have beea addreud. coruin such conditions and limitations effeaof Sgincunng te penod at 54.30 as the Commission deems appropriate extended operation as pait of the Mors not subkaCt to.& eoew and necessay to belp ensure that renewal epplication. The justIication svstems. structures. and components for chnges or additions to the technical (a) If the 'eviews requiti bv 54.21 associated with anv time-limited aging sper-i cations must be contained In the (a) or fc) ow that thre is not analvses will continue to perform their licnse renewal application. reasonable assuance during the currnt intended functions for the period of license term that licensed activities will extended operation. 554.2 Cnans of aot ion- be conducted in accordance with the *n flWnbi kItomaUE (c Eac-h renewed license will include CLB. then the licensee shall take those conditions to protect the Each applicaton must indude a measurs under its current license. as supplement to the environmental report environment that w rnimposed appropriate. to ensure that iheintended pursuant to 10 CFR 50.36b and that are the comphes with the requirements of function of th;:se systems. structures or Subpan A of 10 CFR Pan 51. part of the CLB for the facility at the components will be maintained in time of issuance of the renewed license. s5425 Rportof thAdvoyC*Mne. acordance with the CLB throughout the These conditions may be supplemented on Reatr Safeguard. term of its current License or amended as necessary to protect the Eah renewal application will be (I The licensee's compliance with environment during the term of the refrmd to the Advsory Cominitee on the obligaion under Paragph (a) of renewed license and will be derived Reactor Safeguards for a review and this seton lo taka msures under its from informatioa contained in the report Any report will be made past of current lcense is not within the scope supplement to the environmental repon the ecord of the application nd made of the Ucen renewal mrview. submitted pursuant to 10 CFR Part 51. available to the public. except to the 541 Woice of a eU ceen4. as analyzed and evaluated in the NRC extent that securiy classification (a) A renewed license will be of the record of decision. The conditions will prvents disclsure. d for which the operting license identify the oblipuons of the licensee 55127 Hwog curetly In effect wa issued. in the environmental area. including. as b) A renewed license wiU be appropriate. requirements for reponing A nouce of an opponuxuty for a issued and recordkeeping of environmental bering will be published La the Federal for fixed period of time. which is the tum of the additional amount of time datrand any conditions and monitonng Regier in accordance with 10 CFR requiemenis for the protection of the 2-05. In the absence of a request for a beyond the expiration of the operting licee (not to exceed 20 yea) that is nonaquatic enviry)nment heaing filed within 30 days by a peon (d) The licensing basis for the whose interest may be affected. the equested inl renewal applcaton plus the rmainig number of years on the renewed licens-- includes the CLB. as Commission may iaus a renewed defined in S 54(.3a): the irclusion in the opeating license without * hearing operpaing 1icese currently in effect. The te licer basis of matters such as upon 30-day notice and publication f an renewed licn y not lice rommitments does not change onc* in th Fderal Regter of its intent exeed 40 ya. the . atus of those Matters Unless to do so. (c) A renewed lice wi become effeciv ily upon its iuance. spec. so ordered pursuant to 5429 Stda tor hbaus, ot therebv superseding parmap. fbi or (cl of this secion. - . the operting License previously in effec Ia r1newed 5 54.35 *1equ.rment during te' 01 A renewed license ma'v be issued by license is subsequently set aside upon refiepd Pcecw the Commission up to the full terr further administrative or judicial Durng the term of a renewed license. authoind by 54.31 if the Commissiot appeal. the operating license previously licensees shall be subject to and shall finds that: in effect will be reinsted unless its continue to comply with all (a) Actions have been identified and term has expired and the renewal Commision reulations contained La 10 have been or wiU be takcn with respect application was not filed in a tmely CFR Pats 2 19. 20. 21. 2. 30. 40. 50. to the matters idenufied in Paagraphs manner. SI. S4. 55, 70.72. 73. and 1o. and the (a)(1) and (aJ(2) of this scion. s-h that (d) A renewed license may be appendices to these pans that are then is reasoable assuace hat the subk.quently rnewed in accordance applicable to holders of operating itcuvities authorized by the reoewed with all applicable ruents. lucnses. license wiU cotnus to be conducted m accordance with the CLB. and thaI any 5S423 CwStk n of CLB and 55437 A=*naMrcd nc cbanges made to the plant's CLB in conlOlt ot rmd Ucm order to comply with this paragraph ae (a) Whether stated therin ox not. each (al lbe licensee shall retain n an an accord with the Ac and the renewed License wvill contain and auditable and retrevable form for the Commission's regulauons. Thes otherwise be subject to the conditions term of the renewed operating license mate ae set forth in o CFR 50.54. all informauon tnd documentation (1) managing the effects of ang (i Each rtenewed license will be requred by. or otherwise necessan to dunag the penod of extended operation issued in such form and contain such documentcompliance with. the on the functonality of structues and conditions and linitations. mcluding povisions of this pan. components that have been dent fed to technical speaications, as the fbl After the renewed license is requ.re review nder S 54.2llha)1); and Commzision deems appropnate and issued the FS.R update required bv to 121 time4imited aging analyses t necessary to brp ensure Lhat svstems. CFR 50-71(e) must include iny systems. have bern identified to require revit w structures. aid .omponezts subiect to structures. and compponents newly under 5 54.21 (c). review n accordance with i 54.21 will identified that would have been suolect -__-

_4 "4t cV4F-wa%- - . _ S - ' -- ~ r Federal Xegister I Vol. 60. No. 88 / Mondav. May 8. 1995 Rules and Regulations 22495

to an aging management review or SMALL BUSESS ADMNISTRATIOn eligibility for physical and economic evalusuaon of uime-luted agig injury disster assistance provided analysa ina cordance with S 4.21. 13 CFR Pan 123 under secion (7)(b) I1) and 121 of the Ttis FSAR update must describe hov Small Business Act. 15 U1.S.C. 635(b) (1) th. effects of g will be managed Otas-Water of Judgnent Lion and (21. wbere ther exists good cause such that the intended function(sl in Rest on to do so. § 54-4(o) wiU be offectivlel mantaned AO=: Smll Business Administration. The proposed regulation applied to during te period of extended opeuton ACTIw. Final rule. applicants toe dsaser assistance who * 55 4 41 V IoIag ogL have outstanding udgment liecs in SUMwArY: This fial rule appLies only to favor of SBA or in favor of other (a) The Comm-on mav obai A dLster loan assistanc. It will enable agencies. It identified two nonexciusive injunctm or other cowt order to SBA to waive. for good cause shown. instances in which good cause illI prevent a violation of the pvisons of the restriction in the Federal Debt ordirnaily be found to exist. both of the flowing acts- Colecuon Procedur Act of 1990 them involving adverse crctuistances (I) Tha Atomic Energy Act of 1954. as prohibitng debtors on whose propeny amanded. occasiond by the disaster fo. which the the United Sttes has assistae : (2 Title D of the Easty en ousanding is sought. Judgment lien from recriving disaser Waivers would be grnted denvng Reorganizauton Act of 1974. as a-meded loan aIsnce from the Fedeal or the eligibility review of an app iiUon (3) A guhtion or order i Covemment. for either physical or economic injury puruat to tLose acts. PECmT DATL This Sguatko is disaster assistance. but only upon a (b)The Commrolseonmay obtaiaa effeive on May . 1995. demonsration of good causs by the cout order for the paymens of a civil FO RJRTiER 0oAlN CONTACr. applicant Exampes of good cause penalty imposed under Section 234 oif Bernard Kulik Pt 20212068-734. include, but are not llmited to: (II the Atomic Enery Ac- Associate AdiinistItO for Disa e - Delinquencies eadinp ,0 a judgment (1) For violations of the following- Assistance. U.S. Small Busin lien. which are caused by a disaster. ii Sectins 53. 57.62.63.81.82. 101 Administation. 409 Third Stre SW.. whether the original debt was incured I. 104.107. or 109 of the Atomic Washinton. DC 20416. prior to or after the disaster, and (2) Ene Act of 1954. as amended; SUPPLEMENTARY WFORAT1OW The defaults in an agreement to satisfy a (U)Section Z06 of the Energy Federa Debt Collection Procedures Act judgment lien, which am caused bv a o 199( 28 U.S.C 3201(el pvids that disaster, whether the sgreenwnt has (Ti ne, regulation. or int a debtor who owns propety which Is been made with SBA. another crditor issued t to te sections pecfied subject to a judgment lien for a det agec.Y or anv other Fedeal entitv n (bli1)arph of this eton; owed to the United S5te sha mo be boldtng the len. such as the Resoluijion ter}m .n o i o or limitaton eligible to recaive any nt or loan Trust Corporation or the Federal Deposit of any h i d under the sections wbich s -&d isud. guarmnteed or Insunce Corportion. In the case of specified in paruuapi (bilIlI) of this financed direcUly or indictly bv the agpeetnents with other agencies. SBA United Stat It also pimmdes that such will not waive the restnction on (23 For any violauon orwbich debtor shell not be eligible to receive eligibility until the appropriate Federl iee may be revoked under Section funds directly from the Federal entity has certied that the debtor had S othe Atomicnerg Act of 1954. C;ovemment any propam. except made adher-ng satisfactorily to the as -mended. funds to which thi debtor is enutlod as terms of the agreement prior to the 5 5C4. Cr§Ri pnmtl. beeficary. until the judgment is paid commencemnent date i1the ds.ater [a) SeCion 223 or the Atomic EnemBY ia ful or othw e sausfied. Howeve. The proposed regualtian contemplies the salute that SBA's Associate Administrator for Act of 1954. as amended. provides for permits any agency criminal sanctions for willful violatins responsible for such pants or loans o Disser Assistance. or hislher designec. at anempted violaton of. or conspiracy promulgate regulation to allow for will make the ceterrnnat ion as to to violate. any regulation iued under waivrs of this resuicton. As an agency whether good cause for waiving the authorie to provide seeal fest.rtIoa his betn demonstrited by tilc sectios 251h. iSl. or 110 of the AcL forms of For purpos of seton 223. Al the assistce proscribed by this rwu7cbon. applicant. Althougi such regulations an Part 54 are issued under including dsaer loan assistance and determinations are subject to the one or more ofsections 16tb, 161i. or other types of direct and guaranteed provisions of 5 13 12 Savrrung loans, SBA also has the waiver authority requests for reconsideration. no appval IBt o. wilcept for the sections lised a from an Paragraph (b) of this setio. amneued by the statute. adverse determintaton as (lTe regulains n Par 54 that are SBA ecognizes tat dister losws contemplated. not issued uder Section. Ilb. liili. or may strain the fianucial resouces of SBA rceived no comments frum the tSlo for the purposes of Section Z23 ae responsible debtors to sach extent as to public in esponse to the lune 29. 1994. as follows: S 5 .1. 5.3. 5414. 54.5 5.L 7 prevent them km meting their Notice of Proposed Rulemakig. 54-9. 54.11.5 4.15. 54.1, . 54.19. 54.21. runncial cbligations to the United Tberefore. bv this publication. SBA s 54.22. 54.23. 54.25. 54.2?. 54.29.54 31, States. Such losses also may prevent finalizing the rule as proposed S4-41.and 54.43. debtors who have been complying with Compliance With Executive Orders agreements to satisfy one or more Datd a RackvtUle. .Ur tA tbtt lit day judmets im faor of the Unitrd States 12566. 12822 and 12778; the Regulatory of 4y. 1995 flexibility Act. 5 US.C. 601 et seq.: and from contuntung to omly with the The Paperwork Reduction 44 For tbe Nuclr Reguatory CowenLsion. terms oflthose agreents.Therefare. by Act. U.SC CH 35 pubication n the Federal Register on Secmy ofthe Cmmison June Z9. 1994.59 FR 33456. SBA SBA subrtted th-s final rulb to the IFRt Doc 1-i 113$ Fled S-S95: 8-45 am] proposed to issue a regulation Office of Management and BudJ ct for fLuSO o=n permitting it to vaive the restriction cn purposes of Executive Osde 1 s66 NE] 95-10 Revision 0 March 1, 1996

APPENDIX B

TYPICAL STRUCTURE ,COMPONENT, AND COMMODITY GROUPINGS AND ACTIVE/PASSIWE DETERMINATIONS FOR THE INTEGRATED PLANT ASSE ISMENT

B-1 TYPICAL STRUCTURE COMPONENT AND COMMOOITY GROUPINGS NEI 95-10 AND A%TIVE/PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENTS Revision 0 March l 1996 CATEGORY STRUCTURE, COMPONENT. OR COMMODIlY STRUCTURE, GROUPING COMPONENT, OR ITEM COMMODITY GROUPING IS PASSIVE? (YES/NO) Structures Category I Structures

1 Yes

Pnmary Containment Structure

2 Yes

,Intake Structures

3 Yes

'Intake Canal

4 Yes

tOther Non-Category I Structures Within the Scope of License Renewal 5 Yes

. lEquipment Supports and Foundations . I 6 Yes

'Stncturat Bellows

7 Yes

.Controlled Leakage Doors

8 Yes

Penetration Seals

g Yes

I The applicant shall identify the intended function and apply the IPA process to deternmne of the structure component or commodity grouorng is active or passive B-2 TYPICAL STRUCTURE. COMPONENT AND COMMODITY GROUPINGS NEI 95.10 AND ACTIVE,PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENTS Revision 0 March ,1996 CATEGORY STRUCTURE, COMPONENT. OR COMMODITY STRUCURE. GROUPING COMPONENT, OR ITEM COMMODITY GROUPING IS PASSIVE? (YES/NO) Structures Icontdj Compressible Joints and Seals

10 Yes

Fuel Pool and Sump Liners

11 Yes

Concrete Curbs

12 Yes

Offgas Stack and Flue

13 ' Yes

:Fire Bamers

14 Yes

Pipe Whip Restraints and Jet Impingement -Shields 15 : Yes

Electrical and Instrumentation and Control Penetration Assemblies 1B Yes

:Instrument Racks, Frames, Panels, and Enclosures 17 Yes

.Electncal Panels. Racks. Cabinets. and Other ,Enclosures 18 Yes

The applicant shall identity the intended fundion and apply the IPA process to aelerTnme of the strucure cornponent. or commodrtv grouping iS active or passive 8-3 TYPICAL STRUCTURE. COMPONENT AND COMMODITY GROUPINGS NEI 95-10 AND ACTI1VEPASSIVE ETE RMINATIONS FOR THE INTEGRATED PLANT ASSESSMENTS Revision 0 ,Match 1 1996 CATEGORY STRUCTURE, COMPONENT. OR COMMODITY STRUCTURE, GROUPING COMPONENT. OR ITEM COMMODITY GROUPING IS PASSIVE' (YES/NO) Structures (cont'd) Cable Trays and Supports

19 Yes

Condut

20 Yes

-Tube Track

21 Yes

-Reactor Vessel ntemals

22 Yes

ASME Class 1 Hangers and Supports

23 Yes

iNon-ASME Class 1 Hangers and Supports

24 Yes

'Snubbers

25 No

-Reactor Coolant ;ASME Class 1 Piping Pressure Boundary Components (Note the components of the 26 RCPB are de6ned by Yes each plants CLB and site specfic documentatton

The applicant shall dentity the intendec uncbon anc apply the IPA process to determine of the structure component or comrmodity grouping is active or passive B-4 TYPICAL STRUCTURE COMPONENT AND COMMODITY GROUPINGS NEI 95-10 AND ACTIVE'PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENTS Revision 0 March , 1996 CATEGORY STRUCTURE, COMPONENT. OR COMMODITY STRUCTURE GROUPING COMPONENT, OR ITEM COMMODITY GROUPING IS PASSIVEV (YES/NO) Reactor Cooiant Reactor Vessel Pressure 27 Boundary contd) Yes

Reactor Coolant PL -ps

28 Yes (Casing)

Control Rod Drves

29 No

,Control Rod Dnve Housing

30 Yes

,Stean Generators

31. i Yes

Pressurzers

32 Yes

.Non-Class I Piping Underground Piping -Comporents 33 Yes

iPiping in Low Temperature Demineralized Water -Service 34 Yes

-Piping in High Temperature Single Phase Service

35 Yes

rhe apphicant shall dent:fy the intended function and apply the IPA process to determine of the structure component or commdily grouping is active or passrve B-5 -vPICAL STRUCTURE, COMPONENT AND COMMODITY GROUPINGS NEI 95-10 I AND ACTKVEJPASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENTS Revision 0 March .1996 CATEGORY STRUCTURE. COMPONENT, OR COMMODITY STRUCTURE, GROUPING COMPONENT, OR ITEM COMMODITY GROUPING IS PASSIVE? (YES/NO) Non-Class I Piping 'Piping in Multiple Phase Service Components 36 (cont'd) Yes

Service Water Piping

37 Yes

:Low Temperature Gas Transpcrt Piping

38 Yes

I Stainless Steel Tubing

39 i Yes

jinstrument Tubing

40 Yes

lExpansion Joints

41 Yes

iDuctwvork . ~~~~~~~~~~~~~~~~~i 42 Yes

Sprinklers Heads

43 Yes

Wiscellaneous Appurtenances (includes fittrings, couplings. reducers. elbows, thermowells, flanges,. 44 fasteners, welded attachments, etc Yes

* The applicant shall identify the intended function and apply the IPA process to determine of the Structure. cmp.aent or corr-odrty grouping ISactve or passive B-6 TYPICAL STRUCTURE. COMPONENT AND COMMODITY GROUPINGS NEI 95-10 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSLSSMENTS Revision 0 - ~~~~~~~~~~~~~~~~~March.1996 CATEGORYf STRUCTURE. COMPONENT, ORCOMMODITY STRUCTURE, GROUPING COMPONENT. OR ITEM COMMOD1TY GROUPING IS PASSIVE? (YES/NO) Pumps ECCS Pumps

45 Yes (Casing)

Service Water and Fire Pumps

46 Yes (Casing)

Lube Oil and Closed Cooling Water Pumps

47 . Yes (Casing)

!Condensate Pumps

48 Yes (Casing)

*Borated Water Pumps

49 Yes (Casing)

' Emergency Service Water Pumpc

50 Yes (Casing)

!Submersible Pumps

51 Yes (Casing)

Turbines 'Turbine Pump Drives (excluding pumps)

52 Yes (Casing)

Gas Turbines

53 Yes (Casing)

* The aoplicant shall identify tne mtended functon. and appty the 1PA process t^ deternnne cf h'e swuca6fe ccm.nent or cornodt groupirg Is actve or passive B-7 TYPICAL STRUCTURE COMPONENT AND COMMODITY GROUPINGS NEI 95-10 AND ACTIVEJPASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENTS Revision 0 March . 1996 CATEGORY STRUCTURE. COMPONENT, OR COMMODITY; STRUCTURE, GROUPING COMPONENT, OR ITEM COMMODITY GROUPING IS PASSIVE? (YESINO) 'Turbines (cont'd) Controls (Actuator and Overspeed Tnp)

54 No

Engines Fire Pump Diesel Engines

55 No

,Emergency Diesel iEmergency Diesel Generators 'Generators 56 No

'Heat Exchangers jCondensers

57 Yes

THVAC Coolers

58 . Yes

Primary Water System Heat Exchangers

59I Yes

; 'Treated Water System Heat Exchangers

60 . Yes

. 'Closed Cooling Water System Heat Exchangers

61 Yes

.Lubricating Oil System Heat Exchangers

62 Yes

* The apphcant shall dent:fy the intended fundion and appty the IPA process to determine of the structure. component. or commodity grouping s actrve or passrive B-8 ---

TYPICAL STRUCTURE. COMPONENT AND COMMODITY GROUPINGS NEI 95-10 AND ACTIVEIPASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENTS Revision 0 March 1 1996 CATEGORY STRUCTURE, COMPONENT, OR COMMODITY STRUCTURE, GROUPING COMPONENT, OR ITEM COMMODITY GROUPING IS PASSIVE" (YES/NO) Heat Exchangers Raw Water System Heat Exc.nangers (cont'd) 63 Yes

Containment Atmospheric System Heat Exchangers 64 Yes

;Motors ECCS and Emergency Service Water Pump .Motors 65 No

Small Motors

66 ; No

Miscellaneous 'Gland Seal Blower ;Process 67 :Components No

:Recombiners

68

Flexible Connectors

69 , Yes

-Strainers

70 Yes

,Rupture Disks

71 Yes

* The applicant shall denlify the intended funmion and apply the IPA process to determsne of the str:cture cWmPonent or Commodity grouping Is active or passive B-9 TYPICAL STRUCTURE. COMPONENT AND COMMODITY GROUPINGS NEI 95-10 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENTS Revision 0 March 1 1996 CATEGORY STRUCTURE. COMPONENT, OR COMMODITY STRUCTURE, GROUPING COMPONENT, OR ITEM COMMODITY GROUPING IS PASSIVE? (YES/NO) ;Miscellaneous Steam Traps !Process 72 iComponents Yes (confdj

Restricting Orifices

73 Yes

. lAir Compressor

74 , No

4nstrumentation !Solenoid Operator

: 1 75; No

*Differential Pressure Indicators

76 No

'Differential Pressure Indicabng Switches

77 No

, Differential Pressure Switches

78 No

;Offerential Pressure Transmitters

79 | No

Pressure Indicators

80 No

The applicant shan tdentity the intended funon and apply the IPA process to determre e- the structure cotonent. or comrnodri.t grouping is active or oasstve B-, 0 TYPICAL STRUCTURE. COMPONENT AND COMMODITY GROUPINGS NEI 95-10 AND ACTIVEJPAS$IVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENTS Revision 0 March . 1996 CATEGORY STRUCTURE, COMPONENT. OR COMMODITY STRUCTURE, GROUPINC- COMPONENT. OR ITEM COMMOOTfY GROUPING IS PASSIVE? (YES/NO) Instrumentation Pressure Indicator Switches i(cont'd) 81 No

Pressure Switches

82 No

-Pressure Transmitters

83 , No

* IFlow Switches

84 No

iFlow Transml'ters

65 No

lConductivity Elements

86 Yes (PB only)

iConductivity Swdches

87 No

'Flow Element

88 Yes (PB only)

Level Indicating Switches

No

* The applicant shall identify the intended function and apply the IPA process to determine of the structure component. or commodcity gromung is actlive or passve B3-ii TYPICAl STRUCTURE. COMPONENT ANO COMMODITY GROUPINGS NEI S5-10 AND ACTIVEIPASSIVE DeTERMINATIONS FOR THE iNTEGRATEU PLANT ASSESSMENTS Revision 0 -rchl, 1996 CATEGORY STRUCTURE, COMPONENT. OR COMMODITY STRUCTURE, GROUPING COMPONENT. OR ITEM COMMODITY GROUPING S PASSIVE? (YESINO) Instrumentation Level Transmitters (contd) 90 No

Temperature Indicating Switches

91 No

Temperature Switches

92 . No

,Temperature Sensors

93 1 : Yes (PB only)

Radiation Sensors

94 Yes (PB only)

lRadiation Monitors

95 I No

*Radiation Transmitter

96 No

:Gas Analyzer/Transmtter

97 No

Moisture Switch

98 No

* The applicant shalt identify the intended function and apply the IPA process to deternmine of the structure, component. or commodity grouping is active or passive B12 ryPI&AL STRUCTURE COMPONENT AND COMMODITY GROUPINGS NEI 95-10 AND ACTIVE/PASSIVE DETERMIATINS FOR 1HE INTEGRATED PLANT ASSESSMENTS Revision 0 March' 1996 CATEGORY STRUCTURE COMPONENT OR COMMODITY STRUCTURE. GROUPING COMPONENT OR ITEM COMMODITY GROUPING IS PASSIVE" YES/NO) Instrumentation Position Switch (cont'di 99 No

Vibrato Switch

100 No

Differential Pressure Indicating Controller

101 No

Fow Indicator

102 No

'Flow Indicatng Controller

103 No

Alarm Unit

104 No

Leve. Indicator

105 No

Level Switch

106- No

Temperature Controller

107 No

* The appl:cant shall identify tre intended function and appry the IPA ;rocess to determine of the structure. component or comnodity grouping is aschy oQpassive B 13 TYPICAL STRUCTURE COMPONENT ANt) COMMOIUTY GROUPINGS NEI 95-10 AND ACTIVEJPASSIE METERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENTS Revision 0 ,, . h 1.1996 CATEGORY STRUCTURE. COMPONENT. OR COMMODITY STRUCTURE, GROUPING COMPONENT. OR ITEM COMMODITY GROUPING IS PASSIVE' (YESINO) IFntrumentaton Power Supply (co.t'd) 108 No

Converter-Vohtage!Current

No

Converter-VottagelPneumatic 110 No

iControULr

111 s No

Isolator

112 No

-Signal Conditioner I

113 I No

-Recorder

114 No

Annunciators

115 No

Ammeters

116 No

The appliCant shall identiy the intended function and apply the IPA process to delemine of the structure component or commodity grouping is active or passive B-14 TYPICA' STRUCTURE CM,PONE I AND COMMOD1tY GROUPINGS NEI 95-10 AND ACTIVE,PA$IVE DfEtRMINATIONS FOR THE NTGPA TED PLANT ASSESSMENTS Revision 0 March 1 1996 CATEGOR STPUCTURE. COMPONENT OR CO 'MODITY STRIJCTURE GROUPING '7OMPONENs. OR ITEM COMMODITY GROUPING IS PASSIVE" (YES/NO) Instrumentation Speed ndicators tcont'd) 117 No

Temperature Indicators

118 No

Speed Controllers

119 No

'Watt Transducers 120 . No

,Thermocoupe. RTO

121 Yes

Instrument Transformer

122

Electrical 4.16 kV Switchgear Urtt Components 123 No

480V Load Centers

I^4 No

480V Motor Control Centers

125 No

' The applicant shall :deniffy the internded function and aocly the IPA pfoCuSS t dterrnine of he structure c-omponent or conniud1y grouping s active or passive B3-15 TYP;CAL FTRUCfTURE COMPONENT AND COMMODITY GROUPINGS NE, 95 10 AND ACTIVEVASSIVE DETERMINATICNS Fr TI-HE INTEGRATEO PLANr ASSfSSMENTS Revision 0 1996 CATEGOkY STRUCTURE COMPONENT OR COMMODITY STRUCTURE. GROUPING COMPONEt. i. OR ITEM COMMOITY GROUPING IS PASSIVE? (YEL,/NO) Electncai 250 Motor ml Centersi- Components 126 (con. d) Po

Tranststos

127 No

;Circei Breakers

128 No

Protectve Relays

129 No

*Control (Logic) Relays

130 No

; _ .Control Switches

131 No

. Automatic Transfer Switches

132 : No

Manual T;ansfer and Disconnect Switches

133 No

_- . Batteries

134 No

- The zpplIcart shall ientify the ntended un_: anI a:ply the IPA process to deterrnine of the structure component or commodity groupirg isactuv- Or passive B-16 tYPICAL STRUCTURE COMPeNENT 4n COMMODITY GROuPINGS NEI 9 -10 ANO AP'TIVEJPASSrVE DETERMINAtIONS FOR THE INTEGRATOD PLANT ASSESSMENTS Revision 0 March 1, 1996 CATEGORY STRUCTURE. COMPONENT. OR COMMODITY Si TRUCTURE. GROUPING CONIPONENT. OR G EM C ;0IMODITY GFWOUPING IS PASSWE? (YESINO) Electncal Battery Char!Jersinverters Components 135 (cont'd) No

Motor-Generator Sets

136 No

Distrbution Panel Internal Component Assernblies (includes intemal devices in_;udsng switches. 137 breakers, indicaing lights. etc.) No

_ . l *Electical Cor.tros and Panel Intemral Component :Assemblies (includes intemal devices including 138 switches, breakers, indicating lights. etc) No

Heat Tracing

139

-Electric Heaters

140 1 !

Connectors. electncal splices, terminal blocks II 141 Yes

Pc .I:o, Control, and nstrurrentai;on Cables

142 Yes

_ . ,Load Center Transformers

143

.

* The applicant shall dentrfy he intended function and apply thc IPA process to determine of the structure. component. or commucsty grouping is active or passive B-17, TYPICAL STRUCTURE COMPONENT AND COM.tMODTI -fROUPINr-S NEI 95-10 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE INTEGRATEra PLANT ASSESSMENTS Revision 0 Ma rch 1 19Po CATEGORY STRUCTURE, COMPONENT. OR COMMODITY STRUCTURE, I GROUPING COMPONENT, OR ITEM COMMODITY GROUPING PASSIVE7 (YESINO) Electncal Small Distribution Traiisformers Co:nponerts 144 (cont'd)

Valves Hydraulic Operated Valves

145 Yes (Bodies)

.Explosive Valves

146 i Yes (Bodies

Manual Valves

147 Yes (Bc ..es)

Small Valves

148 Yes (Bodies)

Motor-Operat!d Valves

149 Yes (Bodies)

Air-Operated Valves

150 Yes (Bodies)

Main Steam solnon Valves

151 Yes (Bocies)

_ ...... Small Relief V'r.ies

152 Ye- (2odies)

' Tne appicarnt shall iderthfy . intenoed func.:on anc apply the I;A pczess to Iete'ne cf 'he .--? cw-zromett r =O-nd:jy groupn9 r active or passrve B 18 TYPICAL STRUCTURE. COMPONENT AND COMMODITY GROUPINGS NEI 95-10 AND ACTIVEIPASSIVE DETERMINATIONS F00 T HE INTEGRATED PLANT ASSESSMENTS Revision 0 March 11996 CATEGCRY STRUCTURE, COMPONENT, OR COMiMODITY STRUCTURE, .GROUPING COMPONENT, OR ITEM COMMODIlY GROUPING IS PASSIVE? (YES/NO) 'Valves (contd) Check Valves

153 Yes (Bodies)

.Safety Relief Valves

1 '34 Yes (Bodies)

'Dampers 155 ' No

Tanks 'Air Accumulatsrs

156 Yes

:Discharge Accumulators (Dampers)

157 Yes

Boron Acid Storage Tanks

158 Yes

:Above Ground Oil Tanks

159 Yes

Underground Oil Tanks

160 Yes

*Deniieralized Water Tanks

161 Yes I

The avphwnt shall ider't4y te *ntended FNc-*r. a-C the IP; r-cess : -emmine of te stru;'re t otaome com.modty grouping is aYVe 0 zDassrv 6 -19 TYPICAL STRUCTuPE. ComP, T AND COMMODITY (1ROUPINGS N17 95-1 J AND ACTIVE/PASStVE DETERMINATIONS -uR TH ; .' 'RATED PLANT ASUESSMENTS R-,c 0

IMarch---=:r 96 i Y t I KUL I U-.-CUMFUNtN . UK CMMW;:J I Y STRlCTURE. GRO'UPING COMPONENT. OR ITEM COMMODITY GROUPING IS PASSIVE? (YES/NO) Tanks (conri) Neutron Shild Tank

162 Yes

. Fans v,nf'iatbon Fans

163 No

-ther Fans

164 No

Miscellaner;s *Emergency Lightng

165 No

-Hose Stations

166 Yes

' The applicar shall identfy the ntledt fur±lon and apply the IPA vrocvts to delernine or the Structure component, or conmodity aroL,nQ ts active Or passrve B-2!C NEI 95-10 RE,VISJON 0 Marcb 1. 1996

APPENDIX C

EXAMPLES TO DEMONSTRATI, THE LICENSE RENEWAL PROCESS NEI 95-10 REVISION 0 March 1, 1996

APPENDIX C EXAMPLES TO DEMONSTRATE THE LICENSE RENEWAL PROCESS

Inatroductin

This appendix presents examples to illustrate the iplementation of the various steps delineated in NEI 95-10. These examples are not complete aging management reviews and are still under development. Inclusion in the guideline is not to be misconstrued, at this time, as NRC epjroval of the specific functions, aging effects, aging management programs or level of detail presented in each example.

In addition. when syztem fimctions are identified it should be recoTnized that there may be other system functions not listed that may resul; fron a plant specific review. Sirnilarly, examples I through 4 :iclude an approach for managing a specific aging effect. Other relevant effects would require evaluation as well.

Also. example S is not intended to present an approach for managing the effects of aging. It is included in this appendix to reflect how an evaluation boundary iight be determined on a complex assembly. It is understood that once the boundary is determine, the long- lived passive components would require an aging management review.

C 2 NEI 95-10 REVISION 0 March 1, 1996

EXAMPLE 1 PWR ONCE-THROUGH COOLING SYSTEM

IDENTIFICATiON OF INTENDED FUA 'e'S) (GUIDELiNE SECTIOA 3.2)

A once-through cooling system in a PWR consists of punps, piping, control valves and heat exchangers necessary to transfer the plant heat loads to an ultimate heat sink. Figure C-1 is a simplified diagram of the system. It performs a number of important functions as listed belowv:

1. Transfer heat from the component cooling water heat exchanger to the ultimate heat sink during normal and accident conditions. 2. Transfer heat from the service water heat exchanger to the ultimate heat sink during normal and accident conditions. 3. Transfer heat from the ECCS pump room air cooler. 4. Provide seal water to the main circulating water pumps.

In comparing these four functions to the criteria listed in §54.4(a), it can be seen that functions I , 2, and 3 would prevent the performance of safety related systems (component cooling, service water, and ECCS room cooler) if these fimctions were not performed. Therefore. functions I , 2, and 3 are "intended finctions't under the license renewal rule. Function 4 does not meet any of the criteria in §54.4(a) because it is not a safety-related fnction, it is not a function that would prevent the accomplishment of a safety-related function, and the components necessary to pertorn this function are not required to demonstrate compliance with the regulations referenced in §54. 4(a)(3). Therefore this function is not an "intended function" as this term is used in the IPA.

Each train of the once-through cooling system is included in the scope of license renewal and the "passive. long-lived" components of each train of this system will be included in an aging management review.

DOCUfENTING THE EVALUATION BOUNDARYA.MD DESCRIBING THE STRUCTURE OR COMPONENT'S ITENDED FUNCTION (GUIDELINE SECTION 4.1)

The evaluation boundary includes all structures and components that are necessary for the system to perform its intended function. Once this boundary is established the components and structures that are long-lived and passive must be identified. along ".ith their intended fimction. In accordance %%iththe guideline, the enumponent or structure intended function is the specified finction of the structure or c:-ru ,. nt that supports the svstem intended function. To conclude that the structure or comnponent is passive. it must perform its intended function(s) Xithout moving parts or a change in configuration or NEI 95-10 REVISION O March 1, 1996 properties. The resulti: g passive structures and compolients and their associated intended functions include the foliowing:

* The piping, valves, heat exchangers. pumps and instrument lines provide a pressure retaining boundary under all design loads (internal and external) so that sufficient flow at an adequate pressure is delivered from the pumps to the heat exchangers.

* The electrical panels provide structural support to the electrical components. v The cables provide electrical separation between the conductors and insulation resistance.

* The component supports provide structural support for system piping, valves, heat exchangers, pumps. motors and instrumentation.

The evaluation boundary does not include the following structures and components for the reasons described below:

* System piping which delivers seal water to the main circulating water pumps because this piping does not perforr; an intended fimctions described by §54.4.

* Supports for the seal water piping mentioned above because the supported pipe is not within scope and therefore the supports would also not be within scope.

Cooling ptunp motors because these components exhibit motion and are therefore not passive (active). (Note: motors are excluded, by the rule language in §54.2i(a)(1i).from an aging management reviewfor license renewal.)

DEMOASTRA TING THE EFFECTS OF AGI NG ARE MIANA GED (GUIDELINT ECTI)JN 4.2.1.3)

For the purpose of s example, only the piping is evaluated. The intended function of the piping ., o pro ide a pressure boundarv under all CLB conditions, The piping is carbon steel w-ith an intemal liner.

The aging effect is loss of naterial resulting from corrosion of the pipe. The aging effect is precluded from - rr: by the pipe liner. However, because the liner is relied upon to preclude the aging - .. there is an inspection program in place to detect a loss of liner integrity. Any deficiencies discovered during the inspection program will be corrected in accordance wNith the applicants corrective action program.

C 4 :,gure ... - ..

PWR Once-Through Cooling System Simplified Diagram

I,;egend

Throttled Flow

- Tepwrlture Conirolled

PUMPS ______- ) Pup 8*all

B t N-- rF w SRW N HX 12I HX 11

A 13 5)_ ECC8 1 ECCS

HC 12 _ CR1 I

DIuI2eglr _n:,- F o _~~~~rnreo__ Oleoharo 04~~~~~~~~~~~~~~~~~~~~-

Valve~~~~~~~~~~~~~~~~~~ NEI 95-10 REVISION 0 March 1, 1996

EXAMPLE 2 DIESEL GENERATOR FUEL OIL SYSTEM

IDEATIFICA T7o0 OFRTENDED FUNCTION(S (UIDELINE. SECTION 3.2)

The diese) generator fuel oil system, for each of the four diesel generators, consists of an underground diesel fuel oil storage tank, a diesel oil transfer pump, a diesel oil day tank, engine and DC motor-driven fuel oil pumps, valves, piping, filters, strainers, a dirty fuel oil tank, and an auxliary boiler day tank tansfer pump. The functions of the diesel generator fuel oil systems are:

I. Provide sufficient fuel oil to the diesel engine to support one week of continuous operation at full load during a design basis event.

2. Provide the capability to transfer diesel fuel oil from the diesel storage tanks to the auxiliary boiler fuel oil system.

Function I is a safety-related function. It satisfies the first criterion of §54.4(a) and is therefore an "intended function." Function 2 does not meet any of the criteria in §54.4(a) and is not an "intended function."

DOCUAENTING THE EY4LUATIONBOUNDARYANFD DESCRIBING THE STRUCTURE OR COPONEAT S INTENDED FLWCTION (GUIDELILE SECTION 4.1)

The evaluation boundary includes all structures and components that are necessary for the system to perform its intended function. Once this boundary is established the components and structures that are long-lived and passive must be identified, along with their intended fumction. In accordance with the guideline, the component or structure intended fimction is the specified function of the structure or component that supports the system intended function. To conclude that the structure or component is passive, it must perform its intended function(s) without moxing parts o; a change in configuration or properties. The resulting passive component and associated intended functions include the following:

* The underground fuel oil storage tanks, the fuel oil transfer pumps (casing only), fuel oil day tanks, shaft and DC motor driven fuel oil pumps (casing only), valves, piping, and all instrumentation pressure boundary components provide a pressure boundarv function

* The fuel oil strainer provides a pressure boundary finction.

C 6 NEI 95-10 REVISION 0 March 1, 1996 v The flexible hose connections at the diesel skid provides a pressure boundary function.

* The cables provide electrical separation between the conductors and insulation resistance.

* The cable trays, conduits, and component anchorages provide structural integrity.

DEAfONSTRA TING THE EFFECTSOF AGING ARE MANAGED (GUIDELINE SECTION 4.2.1.3)

For the purpose of this example, only the undergroundstorage tank is evaluated.

The intended function of the underground storage tank is to provide a pressure boundary to ensure that the fuel oil ne.essary to operate the diesel generator is available under all CLB design conditions.

The tank is a horizontal cylindrical carbon steel tank mounted on below grade concrete pads. The extemal surface of the tank is covered with a bitumastic coating. The tank is also connected to the cathodic protection system.

The aging effect of concern for license renewal is loss of material on both the external and internal surfaces of the tank. The loss of material may result from corrosion of the internal surface and degradation of the external coating resulting in corrosion of the underlying material.

The aging management programs for the tank include prevention of water entering the tank, testing for water in the tank, and maintaining operation of the cathodic protection system. In addition the fuel oil is tested prior to being put into the tank to ensure it meets the standard outlined in NTREG 1.137 and ASTM D975.

The plant technical specifications require a monthly check for water in the bottom of the tank. Also. the fuel oil in the tank is tested monthly for water content by sampling oil that has been mixed using the ransfer pump.

The fuel oil storage tank is drained, cleaned, and inspected every ten years as required by the plant technical specifications. The tank inspections consists of an intemal visual inspection and ultrasonic test (UT) of wall thickness in 10 to 12 different locations.

The 13T examinations look for loss of wall thickness on the intemal and extemal surfaces of the tank.

C 7 NEI 95-10 TAf VISION 0 March 1, 1996

The results of checks for water and internal inspections have shown very little, if any, water in the tank. The intemal inspections show the tank is in good condition and free from any degradation. The UT examinations have not revealed any loss of wall thickness, indicating the bitumastic coating and the cathodic protection system are, and should coatinue to be effective.

Continuing these programs provides reasonable assurance that the intended function will be maintained during the period of extended operation.

C 8 NEI 95-10 REVISION 0 March 1. 1996

EXAMPLE 3 AUXILIARY FEEDW ATER SYSTE.MA

IDEINTIFICA TJION OF INTE.NDED FUNCTION(S) (G L'IDELL.%E sL (. TIUX 3.2

The auxiliarv feedwater system consists of control and check valves. turbine driven and motor driven pumps, and piping. The system provides feedwater Irm the condensate storage tanks to the steam generators. There are three trains in this system Its functions include:

1. Provide decay heat removal under post-accident conditions.

2. Supply eedwater during a 4 hour station blackout event to maintain and control water level in the steam generators.

A review of these functions against the criteria in §54.4(a) results in functions I and 2 as being "intended function." Function I is a safety-related finction; function 2 meets the criteria relative to station blackout.

DOCUWENTNG THE EVALUATON BOUNDARYAND DESCRiBING THE STRUCTURE OR COMPONEAr S IATENDED FINCTION GUIDELINE SECTION 4.1)

Each train of te auxiliary feedwater system is includece in the scope of l;ense renewal and the "passive, long-lived" components of each train oi is system will be included in an aging management revi.ew.

The evaluation boundary includes all structures and components thai .are necessary for the system to perform its intended fimction. Once this boundary is eLablished the components and structures that are long-lived and passive must be identified, along wish their intended fimction. In accordance with the guideline the component or structure intended function is the specified function of the structure or component that supports the system intended fimction. To conclude that the structue or component is p2ssive. it must perform its intended function(s) without moving parts or a change in configuration or properties. The resulting passive components and associated intended functions include the following:

* The control valve body must maintain the pressure boundary to ensure the valve performs its fimction.

* The pump casings must maintair pressure boundary to ensure the pumps perform their function.

9 NEI 95.10 REVISION 0 March 1, 1996

* The check valve body must maintain the pressure boundary to ensure the valve performs its function.

* System piping is included because it provides a pressure boundary.

* The component supports provide structural support for system piping, heat exchangers, pumps, valves, motors and instrumentation.

* The electrical panels provide structural support and electrical continuity of power to system pumps.

For purposes of this example, only the pump casing is evaluated. The intended fumction of the pump casing is to provide a pressure boundary under all CLB design conditions. The pump casing is carbon steel.

DEMONSTRA TING THE EFFECTS OFAGING ARE MNAGED (GUIDELINE SECTION 4.2.1.3)

The aging effect of concern for license renewal is loss of material due to gaivanic corrosion, general corrosion, erosion, erosion/corrosion, and microbiological induced corrosion (MIC).

The pump casing is susceptible to general corrosion over a long period of time. Industry operating experience shows that rates of .025 mm per year or greater are possible for carbon steel, and localized pitting corrosion are significantly greater. However, this pump casing has a design corrosion allowance of 3.2 nm or greater which should be sufficient for 60 years.

Galvanic corrosion between dissimilar metals is of concem for this pump because it is in a treated water system. Also, treated water can contain microbes at system temperatures below I 00°C leading to MIC in locations where wetted purnp components are exposed to low fluid velocity.

The pump erosion program examines the pump casing for erosion caused by cavitation due to fouling. Pump erosion control program requirements include:

* Volumetric examination of the pump casing from the outside surface of the pump. The examination technique must be capable of measuring loss of material with an accuracy of + 5% of nominal wall thickness.

* The pump being examined is re-examined at an interval not exceeding ten years from the initial examination date provided the predicted erosion rate %villnot reach 70% of

C 10 a

NEI 95-10 REVISION 0 March 1. 196

nominal uall thickiness or minimum wall thickness, whichever is greater ' ithin that time-frame prior to the re-examination date.

x Trending of quarterly surveillance test data (differential pressure. rotational speed. vibration. and flow rate) and periodic preventive maintenance activities are performed as an early indicator of degraded condition of the purrp internals.

* 'henever the pump. or a similar pump having identical configuration and process variables, is disassembled for maintenance, a visual examination VT-3) is performed on the intemal surfaces of the pump.

Lastlv, the pump is examined in accordance with ASME Section XI In-Service Inspection requirements and the plant's wall thinning management program.

Maintaining these programs will provide reasonable assurance that the intended function will be maintained during the period of extended operation.

C I1 NE1 95-1 REV'ISION 0 Mareb 1, 16

£XAMIPLE 4 POWER CIRCU.IT FOR A REAC t OR 131 111IDING( (OO.INGA ;AN MT'OR

This example examines onlv the electrical components in the power circuit and not the mechanical or ciil components supporting the power pat/i. Thu- -ampe t.s typical of marn power circuits in the plant.

IDENTfFIC.4 IO.S OF ITEN'ED FiU'.VCTIO.tSJ (GUIDELIAE SECTION 3'11

The reactor building coolti g ian motor IA (RBCF-IA). is part of the Reactor Building (RB Cooling System. he intended functions of the system are:

I. Provide heat removal from die containrent atmosphere during post accident conditions to assist in RB pressure and temperature control.

2. Provide post-accident mixing of RB atmosphere, and

3. Maintain RB atnosphere witfhin the environmcntal envelope to assu,e component operability

The reactor building cooling fan motor is located in containment runs continuously during nonnal and shutdownl operations and is designated as IE. The electrical component that make-up the RBCF-IA power circuit are:

I fan niotor, 2. cable(A., 3. penetration. 4. cable(B). 5. motor control center (MCC) (breaker/bus), 6. cable(C), 7. load center transformer 8. cable(D). and 9. suitchgear (breaker/bus).

Cable (A) is in the Reactor Building. cables (B). (C) and part of (D) are in the Auxiliary Building, and part of cable (D) is in the Turbine Building

DOC0E?¶NTI.;N7G THE EV ALU,A TION.S BOLJ'W;DAR Y.AND DESCRIBING TIE STRUYCTVRE OR COMPOJVE.N\7S 1NTEN%DED FUNCTON(GUIDELL\'ESECTIO.N 4.1)

'Tlie fan motor. MCC and switchgear are ac;ive components and thus are nor subject to an aging management review. T he cables and penetration are passive components, and are

C 11 NEI 93-10 REVISI)N 0 March 1, 199 not replaced based on qualificd tfe or specified time pcnod lhesc components are sub ect to an aging management revic. (Acore rhe sstern includeula lad center transtforner 4hich is ,dentrfiled in .4ppendx B of this gutdeline as an item that must e evaluated (for rthe passve-'active determinatinj an a planr-specific basis Therefore it is not evaluird a r parl of :his exampe.)

The entire RBCF-l A power circuit s within the scope of the License Renewal Rule.

The cable intended unctios are to provide electrical separation between the conductors and insulation resistance.

The penetation intended functions are to provide containment integrity, electrical separation between the corductors and insulation resistance.

DE.AOSTPR TIAGy THE EFFECTSOFAGNG ARE V4,VAGED (G UIDEL E SECTIO.1; 4.2.1.3)

(This cxample considers only the temperature as a mechanism leading to aging effects. Relevant effects from other mechanisms would also be evaluated.)

CABLES

Cables (A), (B). (C) and (D) are rated by the manufacturer for 40 years at 90CC (the cable insulation wlould ma. atain its fmction for a minimum of 40 years while being exposed to 900C conductor temperature).

Cable (A) is in the Reactor Building. is included in the EQ Program and is qualified for 40 vears based on analysis and testing. This original analysis was based on conservative, calculated tempeture assumptions. Based on actual temperature measurements, this cable was reanalyzed and found to have a qualified life in excess of 60 years. In addition to he reanaivsis. a cable monitoring program is in place to verifA that the intended fumction of the cable insulation is maintained. Based on the actual thermal environment the cables are exposed to and the cable monitoring program, the aging of is cable will be adequately managed.

Cables ). (C) and part of (D) are n the Auxiliary Building which is a well controlled envirornment. The temperature these cables are exposed to are well below any reasonable threshold to ensure ample thermal insulation life during and beyond the period of extended operation. No further aging rnanagement is required.

Part of cable (D) is in the Turbine Building. Thermography surves were performed that indicate this cable could be exposed to temperatures as high as 60 C on a surimer dav. Ohmic heating due to the continuous powver load causes a I 5C rise in temperature on the

13 NEI 95-10 REVISION 0 March 1, 1996 cable conductors. Therefore. the maximum temperature the insulation is exposed to is 750C 600C- 15"C). Based on the industry rule-of-thumb that for every 1 reduction in temperature the cable insulation life is doubled, and the fact that the cable is exposed to this maximum temperature for short periods during summer days. this cable insulation is eypected to maintain its intended finction at least 60 years.

PENETRATION

The penetration is included in the EQ Program and has been qualified for 40 years with the ability to withstand a post accident environment at the end of that period. This 40 year qualified life is based on thermal accelerated aging using conservative service temperature assumptions. Based on actual temperature measurements, this penetration was reanalyzed and found to have a qualified life exceeding 60 years. In addition to the reanalysis, a one time inspection will be performed on this penetration. This inspection will be performed at least 5 years before the end of the existing qualified life.

The inspection will be focused on the connections and O-ng materials in the penetration assembly. The results of the inspection will be evaluated against applicable acceptance criteria and a judgment made relative to the component end of life. Based on the expected end of life, the penetration w.ill either be refurbished, as needed or replaced.

Based on the actual thermal environment the penetrations are exposed to and the planned inspection, the aging of this penetration will be adequately managed.

r 14 NET 95-10 REVISION 0 March , 1996

EXAMPLE 5 COMPLEX ASSEMBLY CONTROL ROOM CHILLERS

The purpose of this example is to show how a complex assembly (Reference Section 4 1.1) evaluation boundary might be determined. It is understoodthat once the boundary is determine, the long-livedpassive components would require an aging management review.

The control room chillers were purchased as skid n )unted equipment. These chillers are part of the control room chilled water system. Theic are two (2) control room chillers. Each is a 100% capacity refrigeration unit.

The functions of the control room chillers are:

I. to provide a reliable source of chilled water at a maximum temperature of 44°F,

2. to provide a pressre boundary for the control room chilled water system,

3. to provide a pressure boundary for the service water system,

4. to provide a pressure boundary for the refrigerant.

All of theses functions are considered intended functions.

Typically, control room chillers are considered as one finctional unit; however, for purposes of evaluating the effects of aging, it is necessary to consider the individual components. Thereform, the boundary of each control room chiller is established as follows:

1. At the inlet and outlet flanges of the senice water system connections on the control room chiller condenser. Connected piping is part of the service water system.

2. At the inlet and outlet flanges of the control room chilled water system piir.g connections on the control room chiller evaporator. Connected piping is part of the control room chilled water system.

3. For electrical power supplies, the boundarv is the output terminals on the circuit breakers supplying power to the skid. This includes the cables from the circuit breaker to the skid and applies for 480 VAC and 120 VAC.

C IF NEI 95-10 REVISION 0 March 1, 1996

4. The interface for instrument air supplies is at the instrument air tubing connection to the pressure control regulators, temperature controllers and transmitters, and solenoid valves located on the skid. The tubing from the instrument air header to the device on the skid is part of the instrument air system.

S. The interface with the annunciator system is at the externai -onnection of the contacts of the device on the skid (limit switch. pressure switch, level switch, etc.) that indicates the alarm condition. The cables are part of the annunciator system.

Based on the boundary established, thc following components would be subject to an aging management review:

1. condenser

2. evaporator

3. economizer

4. chiller refrigerant piping

5. refrigerant expansion orifice

6. foundations and bolting

7. electrical cabinets

8. cables, conduit. trays and supports

9. valves

C 16 rIE I

( I E E I S I T U E

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