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Dresden Nuclear Power Station, Units 2 & 3 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, IL 60532-4352 July 19, 2017 Mr. Bryan C. Hanson Senior VP, Exelon Generation Co., LLC President and CNO, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3—NRC INTEGRATED INSPECTION REPORT 05000237/2017002 AND 05000249/2017002 Dear Mr. Hanson: On June 30, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Dresden Nuclear Power Station, Units 2 and 3. On June 30, 2017, the NRC inspectors discussed the results of this inspection with Mr. J. Washko and other members of your staff. The results of this inspection are documented in the enclosed report. Based on the results of this inspection, one issue was self-revealed and was evaluated under the risk significance determination process as having very low safety significance (Green). The NRC has also determined a violation is associated with this issue. Because the licensee initiated a condition report to address this issue, the violation is being treated as a Non-Cited Violation (NCV), consistent with Section 2.3.2 of the Enforcement Policy. This NCV is described in the subject inspection report. If you contest the violations or significance of this NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555–0001, with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at the Dresden Nuclear Power Station. If you disagree with the cross-cutting aspect assignment or any finding not associated with a regulatory requirement in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555–0001; with copies to the Regional Administrator, Region III; and the NRC Resident Inspector at the Dresden Nuclear Power Station. B. Hanson -2- This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, “Public Inspections, Exemptions, Request for Withholding.” Sincerely, /RA/ Jamnes Cameron, Chief Branch 4 Division of Reactor Projects Docket Nos. 50–237; 50–249 License Nos. DPR–19; DPR–25 Enclosure: IR 05000237/2017002; 05000249/2017002 cc: Distribution via LISTSERV® B. Hanson -3- Letter to Bryan C. Hanson from Jamnes Cameron dated July 19, 2017 SUBJECT: DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3—NRC INTEGRATED INSPECTION REPORT 05000237/2017002 AND 05000249/2017002 DISTRIBUTION: Jeremy Bowen RidsNrrDorlLpl3 RidsNrrPMDresden Resource RidsNrrDirsIrib Resource Cynthia Pederson James Trapp Richard Skokowski Allan Barker Carole Ariano Linda Linn DRPIII DRSIII [email protected] ADAMS Accession Number: ML17200D012 OFFICE RIII NAME JCameron:tt DATE 7/19/2017 OFFICIAL RECORD COPY U.S. NUCLEAR REGULATORY COMMISSION REGION III Docket Nos: 05000237; 05000249 License Nos: DPR–19; DPR–25 Report Nos: 05000237/2017002; 05000249/2017002 Licensee: Exelon Generation Company, LLC Facility: Dresden Nuclear Power Station, Units 2 and 3 Location: Morris, IL Dates: April 1 through June 30, 2017 Inspectors: G. Roach, Senior Resident Inspector J. Wojewoda, Acting Resident Inspector R. Elliott, Resident Inspector G. Edwards, Health Physicist L. Kozak, Senior Reactor Analyst V. Myers, Senior Health Physicist Approved by: J. Cameron, Chief Projects Branch 4 Division of Reactor Projects Enclosure TABLE OF CONTENTS SUMMARY .................................................................................................................................... 2 REPORT DETAILS ....................................................................................................................... 3 Summary of Plant Status ........................................................................................................... 3 1. REACTOR SAFETY ....................................................................................................... 3 1R01 Adverse Weather Protection (71111.01) ........................................................... 3 1R04 Equipment Alignment (71111.04) ...................................................................... 4 1R05 Fire Protection (71111.05) ................................................................................. 5 1R06 Flooding (71111.06)........................................................................................... 6 1R11 Licensed Operator Requalification Program (71111.11) ................................... 7 1R12 Maintenance Effectiveness (71111.12) ............................................................. 8 1R13 Maintenance Risk Assessments and Emergent Work Control (71111.13) ........ 9 1R15 Operability Determinations and Functional Assessments (71111.15) ............... 9 1R19 Post-Maintenance Testing (71111.19) ............................................................. 13 1R22 Surveillance Testing (71111.22) ...................................................................... 14 1EP6 Drill Evaluation (71114.06) .............................................................................. 15 2. RADIATION SAFETY ................................................................................................... 16 2RS6 Radioactive Gaseous and Liquid Effluent Treatment (71124.06) .................... 16 2RS7 Radiological Environmental Monitoring Program (71124.07) .......................... 19 4. OTHER ACTIVITIES .................................................................................................... 22 4OA1 Performance Indicator Verification (71151) ..................................................... 22 4OA2 Identification and Resolution of Problems (71152) .......................................... 23 4OA6 Management Meetings .................................................................................... 28 SUPPLEMENTAL INFORMATION ............................................................................................... 1 Key Points of Contact ................................................................................................................ 1 List of Items Opened, Closed, and Discussed ........................................................................... 1 List of Documents Reviewed ..................................................................................................... 2 List of Acronyms Used ............................................................................................................ 17 SUMMARY Inspection Report 05000237/2017002, 05000249/2017002; 04/01/2017 – 06/30/2017; Dresden Nuclear Power Station, Units 2 and 3; Operability Determinations and Functional Assessments. This report covers a 3–month period of inspection by resident inspectors and announced baseline inspections by regional inspectors. One Green finding was self-revealed. The finding involved a Non-Cited Violation (NCV) of the U.S. Nuclear Regulatory Commission (NRC) requirements. The significance of inspection findings is indicated by their color (i.e., greater than Green, or Green, White, Yellow, Red) and determined using Inspection Manual Chapter (IMC) 0609, “Significance Determination Process,” dated April 29, 2015. Cross-cutting aspects are determined using IMC 0310, “Aspects Within the Cross-Cutting Areas,” dated December 4, 2014. All violations of NRC requirements are dispositioned in accordance with the NRC’s Enforcement Policy, dated November 1, 2016. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG–1649, “Reactor Oversight Process,” Revision 6. Cornerstone: Mitigating Systems • Green. A finding of very low safety significance and associated non-cited violation of Technical Specification (TS) 5.4.1, “Procedures”, was self-revealed on May 26, 2017, for the licensee’s failure to maintain configuration control in the Unit 2 containment pressure suppression system. Specifically, the licensee failed to maintain the instrument air stop valve to the actuator for the Unit 2 torus vent, air operated valve (AOV) 2–1601–60, open with the reactor mode switch in Run (Mode 1) and reactor power approximately 100 percent rated thermal power (RTP). The inspectors determined that the licensee’s failure to maintain configuration control of the Unit 2 containment pressure suppression system was contrary to procedures for the emergency depressurization of containment with the reactor in Mode 1 and was a performance deficiency. The inspectors determined that the performance deficiency was more than minor, and thus a finding, in accordance with IMC 0612, Appendix B, “Issue Screening,” dated September 7, 2012, because it was associated with the mitigating systems cornerstone attribute of configuration control with regards to the plant’s operating equipment alignment while affecting the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences (i.e., core damage). The inspectors determined that a Detailed Risk Evaluation was required to be performed based on answering “Yes” to the Mitigating Systems screening question
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