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Safety Evaluation Report NUREG-0847 Supplement 29 Safety Evaluation Report Related to the Operation of Watts Bar Nuclear Plant, Unit 2 Docket Number 50-391 Tennessee Valley Authority Office of Nuclear Reactor Regulation AVAILABILITY OF REFERENCE MATERIALS IN NRC PUBLICATIONS NRC Reference Material Non-NRC Reference Material As of November 1999, you may electronically access Documents available from public and special technical NUREG-series publications and other NRC records at libraries include all open literature items, such as books, NRC’s Library at www.nrc.gov/reading-rm.html. Publicly journal articles, transactions, Federal Register notices, released records include, to name a few, NUREG-series Federal and State legislation, and congressional reports. publications; Federal Register notices; applicant, Such documents as theses, dissertations, foreign reports licensee, and vendor documents and correspondence; and translations, and non-NRC conference proceedings NRC correspondence and internal memoranda; bulletins may be purchased from their sponsoring organization. and information notices; inspection and investigative reports; licensee event reports; and Commission papers Copies of industry codes and standards used in a and their attachments. substantive manner in the NRC regulatory process are maintained at— NRC publications in the NUREG series, NRC regulations, The NRC Technical Library and Title 10, “Energy,” in the Code of Federal Regulations Two White Flint North may also be purchased from one of these two sources. 11545 Rockville Pike Rockville, MD 20852-2738 1. The Superintendent of Documents U.S. Government Publishing Office These standards are available in the library for reference Mail Stop IDCC use by the public. Codes and standards are usually Washington, DC 20402-0001 copyrighted and may be purchased from the originating Internet: bookstore.gpo.gov organization or, if they are American National Standards, Telephone: (202) 512-1800 from— Fax: (202) 512-2104 American National Standards Institute 11 West 42nd Street 2. The National Technical Information Service New York, NY 10036-8002 5301 Shawnee Rd., Alexandria, VA 22312-0002 www.ansi.org www.ntis.gov (212) 642-4900 1-800-553-6847 or, locally, (703) 605-6000 Legally binding regulatory requirements are stated only in A single copy of each NRC draft report for comment is laws; NRC regulations; licenses, including technical speci- available free, to the extent of supply, upon written fications; or orders, not in NUREG-series publications. The request as follows: views expressed in contractorprepared publications in this series are not necessarily those of the NRC. Address: U.S. Nuclear Regulatory Commission The NUREG series comprises (1) technical and adminis- Office of Administration trative reports and books prepared by the staff (NUREG– XXXX) or agency contractors (NUREG/CR–XXXX), (2) Publications Branch proceedings of conferences (NUREG/CP–XXXX), (3) reports Washington, DC 20555-0001 resulting from international agreements (NUREG/IA–XXXX), E-mail: [email protected] (4) brochures (NUREG/BR–XXXX), and (5) compilations of Facsimile: (301) 415-2289 legal decisions and orders of the Commission and Atomic and Safety Licensing Boards and of Directors’ decisions Some publications in the NUREG series that are posted under Section 2.206 of NRC’s regulations (NUREG–0750). at NRC’s Web site address www.nrc.gov/reading-rm/ DISCLAIMER: This report was prepared as an account doc-collections/nuregs are updated periodically and may of work sponsored by an agency of the U.S. Government. differ from the last printed version. Although references to Neither the U.S. Government nor any agency thereof, nor any employee, makes any warranty, expressed or implied, material found on a Web site bear the date the material or assumes any legal liability or responsibility for any third was accessed, the material available on the date cited party’s use, or the results of such use, of any information, may subsequently be removed from the site. apparatus, product, or process disclosed in this publication, or represents that its use by such third party would not infringe privately owned rights. NUREG-0847 Supplement 29 Safety Evaluation Report Related to the Operation of Watts Bar Nuclear Plant, Unit 2 Docket Number 50-391 Tennessee Valley Authority Manuscript Completed: October 2015 Date Published: October 2015 Office of Nuclear Reactor Regulation ABSTRACT This report supplements the Staff’s evaluation of the application filed by the Tennessee Valley Authority (TVA), as applicant and owner, for a license to operate Watts Bar Nuclear Plant (WBN), Unit 2 (Docket No. 50-391). This supplemental evaluation documents the Staff’s findings with respect to the applicable elements of Title 10 of the Code of Federal Regulations (10 CFR) 50.57, which lists the findings the Nuclear Regulatory Commission (NRC) must make to issue an operating license. The application for a construction permit for WBN, Units 1 and 2 was submitted on May 14, 1971, and constructions permits CPPR-91 and CPPR-92 were issued January 23, 1973. Subsequently, on October 4, 1976, an application for operating licenses for WBN, Units 1 and 2 was submitted by TVA. In its safety evaluation report (SER) published June 1982 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML072060491) and Supplemental SERs (SSERs) 1 through 20, issued by the Office of Nuclear Reactor Regulation (NRR) of the NRC, the NRC staff documented its safety evaluation (SE) and determination that WBN, Unit 1, met all applicable regulations and regulatory guidance. Based on satisfactory findings from all applicable inspections, on February 7, 1996, the NRC issued a full-power operating license (OL) to WBN, Unit 1, authorizing operation up to 100-percent power. In SSER 21 published February 2009 (ADAMS Accession No. ML090570741), the NRC staff addressed TVA’s application for a license to operate WBN, Unit 2, and gave information on the status of the items remaining to be resolved that were outstanding at the time that TVA deferred construction of WBN, Unit 2, and were not evaluated and resolved as part of the licensing of WBN, Unit 1. SSERs 22 to 28 documented the NRC staff’s ongoing evaluation and closure of open items in support of TVA’s application for a license to operate WBN, Unit 2. This SSER documents the NRC staff’s completion of its review of open items in related to TVA’s application for an OL for WBN, Unit 2. In addition to closure of remaining open items, this SSER discusses a revision to the motor operated valve testing program, the fire protection program, the technical specifications, and final SER modifications made by the applicant. iii TABLE OF CONTENTS Page ABSTRACT iii TABLE OF CONTENTS v ABBREVIATIONS ix 1 INTRODUCTION AND DISCUSSION 1-1 1.1 Introduction 1-1 1.7 Summary of Outstanding Issues 1-2 1.9 License Conditions 1-27 1.9.1 Flooding License Condition 1-28 1.9.2 Cyber Security License Condition 1-28 1.9.3 Core Operating Limits License Condition 1-28 1.9.4 Electrical Design License Condition 1-29 1.9.5 Fire Protection License Condition 1-29 1.9.6 Core Reload License Condition 1-29 1.13 Implementation of Corrective Action Programs and Special Programs 1-29 1.13.1 Corrective Action Programs 1-30 1.13.2 Special Programs 1-31 1.14 Implementation of Applicable Bulletin and Generic Letter Requirements 1-31 1.17 Financial Assurance for Decommissioning 1-46 1.18 NRC Staff Conclusion 1-47 3 DESIGN CRITERIA – STRUCTURE, COMPONENTS, EQUIPMENT, AND SYSTEMS 3-1 3.8 Design of Seismic Category I Structures 3-1 3.8.3 Other Seismic Category I Structures 3-1 3.9 Mechanical Systems and Components 3-1 3.9.3 ASME Code Class 1, 2, and 3 Components, Component Structures, and Core Support Structures 3-1 6 ENGINEERED SAFETY FEATURES 6-1 6.1 Engineered Safety Feature Materials 6-1 6.1.3 Postaccident Emergency Cooling Water Chemistry 6-1 6.2 Containment Systems 6-1 6.2.1 Containment Functional Design 6-1 6.2.2 Containment Heat Removal Systems 6-14 6.2.3 Secondary Containment Functional Design 6-16 6.2.4 Containment Isolation Systems 6-17 6.2.5 Combustible Gas Control Systems 6-18 6.2.6 Containment Leakage Testing 6-18 6.3 Emergency Core Cooling System 6-18 6.3.1 System Design 6-18 6.3.3 Testing 6-20 6.4 Control Room Habitability 6-20 6.5 Engineered Safety Feature (ESF) Filter Systems 6-20 6.5.1 ESF Atmosphere Cleanup System 6-20 v 7 INSTRUMENTS AND CONTROLS 7-1 7.5 Safety-Related Display Instrumenation 7-1 7.5.2 Postaccident Monitoring System 7-1 7.7 Control Systems Not Required for Safety 7-3 7.7.1 System Description 7-3 8 ELECTRIC POWER SYSTEMS 8-1 8.3 Onsite Power Systems 8-1 8.3.1 Onsite AC Power System Compliance with GDC 17 8-1 9 AUXILIARY SYSTEMS 9-1 9.2 Water Systems 9-1 9.2.1 Essential Raw Cooling Water and Raw Cooling Water System 9-1 9.2.2 Component Cooling System (Reactor Auxiliaries Cooling Water System) 9-1 9.2.6 Condensate Storage Facilites 9-1 9.5 Other Auxiliary Systems 9-2 9.5.1 Fire Protection 9-2 10 STEAM AND POWER CONVERSION SYSTEM 10-1 10.4 Other Features 10-1 10.4.9 Auxiliary Feedwater System 10-1 11 RADIOACTIVE WASTE MANAGEMENT 11-1 11.7 NUREG-0737 Items 11-1 11.7.1 Wide-Range Noble Gas, Iodine, and Particulate Effluent Monitors (II.F.1.1, II.F.1.2.a, and II.F.1.2.b) 11-1 11.7.2 Primary Coolant Outside Containment (III.D.1.1) 11-2 12 RADIATION PROTECTION 12-1 12.7 NUREG-0737 Items 12-1 12.7.1 Plant Shielding (II.B.2) 12-1 12.7.2 High Range In-Containment Monitor (II.F.1.2.c) 12-1 12.7.3 In-Plant Radioiodine Monitor (III.D.3.3) 12-1
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