Similar Documents at Perry |
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Category:Letter
MONTHYEARIR 05000440/20230042024-01-30030 January 2024 Integrated Inspection Report 05000440/2023004 L-23-207, License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2024-01-24024 January 2024 License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs L-24-017, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2024-01-24024 January 2024 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative IR 05000440/20234022024-01-10010 January 2024 Cyber Security Inspection Report 05000440/2023402 ML24003A8032024-01-0303 January 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML23321A0472023-12-20020 December 2023 Letter to Rod L. Penfield - Perry Nuclear Power Plant, Unit 1 - License Renewal Regulatory Audit Regarding the Environmental Review of the License Renewal Application L-23-171, CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency2023-12-0808 December 2023 CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency L-23-244, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000440/20230112023-11-28028 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000440/2023011 IR 05000440/20234032023-11-27027 November 2023 Security Baseline Inspection Report 05000440/2023403 ML23292A2972023-11-17017 November 2023 Table of Contents LAR (L-2023-LLA-0111) L-23-238, Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 202023-11-10010 November 2023 Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 20 L-23-052, Submittal of the Updated Safety Analysis Report, Revision 232023-10-27027 October 2023 Submittal of the Updated Safety Analysis Report, Revision 23 ML23292A2482023-10-19019 October 2023 Fws to NRC, Federal Agency Coordination Under ESA Section 7 for Perry Nuclear Plant, Unit 1, License Renewal, and Concurrence with Not Likely to Adversely Affect Determination for Northern Long-eared Bat ML23292A2472023-10-19019 October 2023 Fws to NRC, Perry Nuclear Plant, Unit 1, License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected IR 05000440/20230032023-10-11011 October 2023 Integrated Inspection Report 05000440/2023003 ML23249A1032023-10-0303 October 2023 Letter to Rod L. Penfield, Site Vice President-Perry Nuclear Power Plant, Unit 1-Notice of Intent to Conduct Scoping Process and Prepare an Environmental Impact Statement ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure ML23261C3642023-09-25025 September 2023 License Renewal Application Online Reference Portal ML23261B0192023-09-25025 September 2023 Aging Management Audit Plan Regarding the License Renewal Application Review ML23256A3592023-09-22022 September 2023 Determination of Acceptability and Sufficiency for Docketing, Proposed Review Schedule, and Opportunity for a Hearing Regarding the Energy Harbor Nuclear Corp. Application for License Renewal L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-206, Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD2023-09-12012 September 2023 Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual IR 05000440/20234012023-08-28028 August 2023 Public - Perry Nuclear Power Plant Security Baseline Inspection Report 05000440/2023401 ML23129A1722023-08-25025 August 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1 IR 05000440/20230052023-08-24024 August 2023 Updated Inspection Plan for Perry Nuclear Power Plant (Report 05000440/2023005) ML23172A2852023-08-23023 August 2023 Safety Evaluation Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimate ML23227A2202023-08-15015 August 2023 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Perry Nuclear Power Plant L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-001, License Amendment Request to Remove the Table of Contents from the Technical Specifications2023-08-0707 August 2023 License Amendment Request to Remove the Table of Contents from the Technical Specifications IR 05000440/20230022023-08-0202 August 2023 Integrated Inspection Report 05000440/2023002 L-23-174, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2023-07-19019 July 2023 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative ML23198A2842023-07-17017 July 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-23-146, License Renewal Application for the Perry Nuclear Power Plant2023-07-0303 July 2023 License Renewal Application for the Perry Nuclear Power Plant IR 05000440/20230102023-06-29029 June 2023 Comprehensive Engineering Team Inspection Report 05000440/2023010 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-23-050, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-22022 June 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-051, Plan, Nineteenth Inservice Inspection Summary Report2023-06-22022 June 2023 Plan, Nineteenth Inservice Inspection Summary Report L-22-249, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener2023-06-0505 June 2023 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener ML23144A3562023-05-25025 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End of Cycle Plant Performance Assessment of Perry Nuclear Power Plant, Unit 1 L-23-134, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-23023 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report ML23124A1742023-05-17017 May 2023 Energy Harbor Fleet Vistra License Transfer - Request for Withholding Information from Public Disclosure for Commance Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 ML23129A0112023-05-16016 May 2023 Notice of Consideration of Approval of Indirect and Direct License Transfer for Comanche Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 (EPID L-2023-LLM-0000) (Letter) IR 05000440/20230012023-05-0404 May 2023 Integrated Inspection Report (05000440/2023001) L-23-122, Annual Radiological Environmental Operating Report2023-04-26026 April 2023 Annual Radiological Environmental Operating Report L-23-121, Annual Radiological Effluent Release Report2023-04-26026 April 2023 Annual Radiological Effluent Release Report 2024-01-30
[Table view] Category:Report
MONTHYEARL-23-171, CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency2023-12-0808 December 2023 CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-21-045, 10 CFR 50.55a Request Number VR-4, Revision 0, Exercising Test Frequency, VR-6, Revision 0, Position Verification Testing, and VR-8, Revision 0, Valve Test Frequency Extension2021-02-0808 February 2021 10 CFR 50.55a Request Number VR-4, Revision 0, Exercising Test Frequency, VR-6, Revision 0, Position Verification Testing, and VR-8, Revision 0, Valve Test Frequency Extension L-18-186, Proposed Alternative to Use ASME Code Case N-8312018-09-0707 September 2018 Proposed Alternative to Use ASME Code Case N-831 L-17-234, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the ...2017-08-11011 August 2017 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the ... L-17-229, Mitigating Strategies Assessment (MSA) for Flooding2017-07-24024 July 2017 Mitigating Strategies Assessment (MSA) for Flooding L-17-039, 2016 Annual Report of Emergency Core Cooling System Errors and Model Changes2017-04-0505 April 2017 2016 Annual Report of Emergency Core Cooling System Errors and Model Changes L-17-088, Independent Spent Fuel Storage Installation Changes, Tests and Experiments2017-03-27027 March 2017 Independent Spent Fuel Storage Installation Changes, Tests and Experiments ML21106A0222016-05-31031 May 2016 Enclosure a - Evaluation Attachment 5 - FLO-2D Verification Report (Report Attachment 2) L-16-091, Revision of Flood Hazard Reevaluation Report in Response to NRC Request for Additional Information, Per 10CFR50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukush2016-03-24024 March 2016 Revision of Flood Hazard Reevaluation Report in Response to NRC Request for Additional Information, Per 10CFR50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukush L-15-281, Submittal of Report of Facility Changes, Tests and Experiments2015-10-23023 October 2015 Submittal of Report of Facility Changes, Tests and Experiments ML15208A0342015-08-0303 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force L-15-193, Submittal of the 2015 Silicone Sealant Report Pursuant to License Commitment 172015-06-12012 June 2015 Submittal of the 2015 Silicone Sealant Report Pursuant to License Commitment 17 L-15-108, ISFSI - Summary Report of Changes, Tests and Experiments for the Period of January 1, 2013 Through December 31, 20142015-04-0303 April 2015 ISFSI - Summary Report of Changes, Tests and Experiments for the Period of January 1, 2013 Through December 31, 2014 L-14-401, First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In2014-12-19019 December 2014 First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) L-14-254, 10 CFR 71.95 Report on the TN-RAM Package2014-08-15015 August 2014 10 CFR 71.95 Report on the TN-RAM Package ML14141A4602014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 L-14-198, Report of Changes and Errors Pursuant to 10 CFR 50.462014-06-18018 June 2014 Report of Changes and Errors Pursuant to 10 CFR 50.46 ML14115A2342014-05-30030 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident ML13338A4602014-01-22022 January 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML14014A2092014-01-14014 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Perry Nuclear Power Plant, Unit 1, TAC No.: MF0962 (Revision 1) ML13340A1472013-11-26026 November 2013 Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant - Response to RAI Associated with Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (TAC Nos. MF0116 & MF0 L-13-358, Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (2 of 2)2013-10-0909 October 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (2 of 2) ML13340A1572013-10-0909 October 2013 Perry Nuclear Power Plant Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (1 of 2) ML13340A1562013-10-0909 October 2013 Perry Nuclear Power Plant Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix a ML13340A1552013-10-0909 October 2013 Perry Nuclear Power Plant Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1 L-13-300, Submittal of 10 CFR 71.95 Report on the 8-120B Cask2013-10-0101 October 2013 Submittal of 10 CFR 71.95 Report on the 8-120B Cask L-13-164, Addendum to Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report2013-06-18018 June 2013 Addendum to Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report L-12-347, FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-27027 November 2012 FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML13008A0542012-09-28028 September 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B: Seismic Walkdown Checklists, Page B-1, Sheet 482 of 513 Through Appendix C: Area Walk-by Checklists, Sheet 85 of 212 ML13135A2512012-09-28028 September 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walk-Down Checklists (Swcs), Sheet 204 of 461 Through Sheet 461 of 461 ML13135A2492012-09-28028 September 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walk-Down Checklists (Swcs), Sheet 1 of 461 Through Sheet 203 of 461 ML13135A2482012-09-28028 September 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix a - Resumes and Qualifications ML13135A2472012-09-28028 September 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Cover Through Page 153 ML13135A2292012-09-28028 September 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendices C Through End ML13008A0502012-09-28028 September 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B: Seismic Walkdown Checklists, Page B-1, Sheet 1 of 513 Through Sheet 122 of 513 ML13008A0512012-09-28028 September 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B: Seismic Walkdown Checklists, Page B-1, Sheet 123 of 513 Through Sheet 247 of 513 ML13008A0492012-09-28028 September 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Cover Through Appendix a, Resumes and Qualifications, Page A-36 ML13008A0552012-09-28028 September 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C: Area Walk-by Checklists, Sheet 86 of 212 Through End ML13008A0522012-09-28028 September 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B: Seismic Walkdown Checklists, Page B-1, Sheet 248 of 513 Through Sheet 367 of 513 ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants L-11-017, State of Ohio Water Withdrawal Report2011-01-24024 January 2011 State of Ohio Water Withdrawal Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML0919400712009-06-29029 June 2009 Semi-Annual Sewage Isotopic Report ML0904007952009-02-0404 February 2009 GSI-189 Action Plan, Feb. 09 Update, Publicly Available Version ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0705902852007-02-20020 February 2007 Semiannual Fitness-For-Duty Report for Period of July 1, 2006 Through December 31, 2006 ML0700902662007-01-0808 January 2007 Final Transition Letter and Attachment, Revision 1 (1-8-07) 2023-08-07
[Table view] Category:Technical
MONTHYEARL-21-045, 10 CFR 50.55a Request Number VR-4, Revision 0, Exercising Test Frequency, VR-6, Revision 0, Position Verification Testing, and VR-8, Revision 0, Valve Test Frequency Extension2021-02-0808 February 2021 10 CFR 50.55a Request Number VR-4, Revision 0, Exercising Test Frequency, VR-6, Revision 0, Position Verification Testing, and VR-8, Revision 0, Valve Test Frequency Extension L-17-234, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the ...2017-08-11011 August 2017 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the ... ML21106A0222016-05-31031 May 2016 Enclosure a - Evaluation Attachment 5 - FLO-2D Verification Report (Report Attachment 2) ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML13338A4602014-01-22022 January 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML14014A2092014-01-14014 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Perry Nuclear Power Plant, Unit 1, TAC No.: MF0962 (Revision 1) ML0904007952009-02-0404 February 2009 GSI-189 Action Plan, Feb. 09 Update, Publicly Available Version ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0608804462006-03-31031 March 2006 GE Report, GE-NE-0000-0041-0403-RI-NP, Revision 1, First Energy Corp, Perry Nuclear Power Plant, 12/23/04 Instability Event, OPRM Performance Evaluation, March 2006. L-05-056, Firstenergy Nuclear Operating Company Requests Authorization to Use Delta Protection Supplied-Air Containment Suits as Respiratory Protection Equipment and Assignment of a Protection Factor, Pursuant to 10CFR20.1703 and 10CFR20.17052005-12-0606 December 2005 Firstenergy Nuclear Operating Company Requests Authorization to Use Delta Protection Supplied-Air Containment Suits as Respiratory Protection Equipment and Assignment of a Protection Factor, Pursuant to 10CFR20.1703 and 10CFR20.1705 ML0508101842005-02-14014 February 2005 FEMA Final Exercise Report Perry Nuclear Power Plant Exercise Date Oct 5, 2004 ML0428005552004-09-30030 September 2004 Transmittal of the Performance Improvement Initiative for Perry Nuclear Power Plant ML0403302412004-01-26026 January 2004 Letter Documenting Request of Perry Nuclear Power Plant (Pnpp) Staff to Determine If It Is Allowable to Perform Interference Removal for Chlorine Analysis Using the Hach Pocket Colorimeter ML0300206362003-01-15015 January 2003 Feedwater Isolation Valve Condition Report Review ML0222706722002-08-0707 August 2002 Semiannual Fitness-for-Duty Report 2021-02-08
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Text
January 15, 2003 Mr. William R. Kanda Vice President - Nuclear, Perry FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant P.O. Box 97, A200 10 Center Road Perry, OH 44081
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT 1 - FEEDWATER ISOLATION VALVE CONDITION REPORT REVIEW (TAC NO. MB1905)
Dear Mr. Kanda:
Your letter of August 30, 2001 (PY-CEI/NRR-2590L), provided the results of your comprehensive investigation into issues raised by Perry Condition Report (CR) 01-0853, Basis for Current Feedwater Penetration Operability. The CR identified technical deficiencies associated with Perry Amendment No. 105, dated March 26, 1999, where the staff approved changes to the design and licensing basis for the containment isolation valves of the feedwater system. While you concluded that the majority of the identified issues were adequately addressed, you determined that an improved/supplemented method of testing and/or inspection would be required to assure adequate verification of long term operability of the feedwater check valves. In addition, you identified a number of other areas involving long term actions.
The staff has completed its independent review of the CR, Amendment No. 105, and the Immediate Investigation report dated March 15, 2001. Our analysis of the CR concludes that the modifications to the feedwater penetrations improve the previous feedwater penetration design. Less time is necessary to fill the leakage control system before it is required to perform its safety function and the high integrity gate valve has been made more reliable. In addition, the previous check valve leakage criterion, which was difficult to comply with, has been eliminated by the improved design. However, similar to your results, the staff has identified a number of deficiencies and areas requiring resolution.
The enclosure represents a compilation of the identified issues associated with CR 01-0853.
For completeness and accuracy of the staffs efforts associated with the approval of Amendment No. 105, we request that you respond to the issues identified in the enclosure.
Sincerely,
/RA by Douglas V. Pickett for/
Stephen P. Sands, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-440 cc w/encl: See next page
Perry Nuclear Power Plant, Unit 1 cc:
Mary E. OReilly Carol OClaire, Chief, Radiological Branch FirstEnergy Corporation Ohio Emergency Management Agency 76 South Main St. 2855 West Dublin Granville Road Akron, OH 44308 Columbus, OH 43235-7150 Resident Inspectors Office Mayor, Village of Perry U.S. Nuclear Regulatory Commission P.O. Box 100 P.O. Box 331 Perry, OH 44081-0100 Perry, OH 44081-0331 Regional Administrator, Region III Dennis Clum U.S. Nuclear Regulatory Commission Radiological Assistance Section Supervisor 801 Warrenville Road Bureau of Radiation Protection Lisle, IL 60532-4531 Ohio Department of Health P.O. Box 118 Sue Hiatt Columbus, OH 43266-0118 OCRE Interim Representative 8275 Munson Zack. A. Clayton Mentor, OH 44060 DERR Ohio Environmental Protection Agency Mr. Vernon K. Higaki ATTN: Mr. Zack A. Clayton Manager - Regulatory Affairs P.O. Box 1049 FirstEnergy Nuclear Operating Company Columbus, OH 43266-0149 Perry Nuclear Power Plant P.O. Box 97, A210 Chairman 10 Center Road Perry Township Board of Trustees Perry, OH 44081 3750 Center Road, Box 65 Perry, OH 44081 Timothy Rausch, Plant Manager FirstEnergy Nuclear Operating Company Daniel Z. Fisher Perry Nuclear Power Plant Transportation Department P.O. Box 97, SB306 Public Utilities Commission Perry, OH 44081 180 East Broad Street Columbus, OH 43215-3793 Mayor, Village of North Perry North Perry Village Hall 4778 Lockwood Road North Perry Village, OH 44081 Donna Owens, Director Ohio Department of Commerce Division of Industrial Compliance Bureau of Operations & Maintenance 6606 Tussing Road P. O. Box 4009 Reynoldsburg, OH 43068-9009
January 15, 2003 Mr. William R. Kanda Vice President - Nuclear, Perry FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant P.O. Box 97, A200 10 Center Road Perry, OH 44081
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT 1 - FEEDWATER ISOLATION VALVE CONDITION REPORT REVIEW (TAC NO. MB1905)
Dear Mr. Kanda:
Your letter of August 30, 2001 (PY-CEI/NRR-2590L), provided the results of your comprehensive investigation into issues raised by Perry Condition Report (CR) 01-0853, Basis for Current Feedwater Penetration Operability. The CR identified technical deficiencies associated with Perry Amendment No. 105, dated March 26, 1999, where the staff approved changes to the design and licensing basis for the containment isolation valves of the feedwater system. While you concluded that the majority of the identified issues were adequately addressed, you determined that an improved/supplemented method of testing and/or inspection would be required to assure adequate verification of long term operability of the feedwater check valves. In addition, you identified a number of other areas involving long term actions.
The staff has completed its independent review of the CR, Amendment No. 105, and the Immediate Investigation report dated March 15, 2001. Our analysis of the CR concludes that the modifications to the feedwater penetrations improve the previous feedwater penetration design. Less time is necessary to fill the leakage control system before it is required to perform its safety function and the high integrity gate valve has been made more reliable. In addition, the previous check valve leakage criterion, which was difficult to comply with, has been eliminated by the improved design. However, similar to your results, the staff has identified a number of deficiencies and areas requiring resolution.
The enclosure represents a compilation of the identified issues associated with CR 01-0853.
For completeness and accuracy of the staffs efforts associated with the approval of Amendment No. 105, we request that you respond to the issues identified in the enclosure.
Sincerely,
/RA by Douglas V. Pickett for/
Stephen P. Sands, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-440 cc w/encl: See next page Distribution:
PUBLIC PDIII-2 r/f ACRS SWeerakkody OGC GGrant, R3 AMendiola SSands THarris RLobel ADAMS Accession Number: ML030020636 OFFICE PM:LPD3 LA:LPD3 SC:SPLB SC:LPD3 NAME DPickett for THarris SWeerakkody LRaghavan for SSands AMendiola DATE 01/09/03 01/09/03 01/09/03 01/15/03 OFFICIAL RECORD COPY
FEEDWATER ISOLATION VALVE CONDITION REPORT REVIEW FIRSTENERGY NUCLEAR OPERATING COMPANY PERRY NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-440 As a result of FirstEnergys comprehensive investigation of Condition Report 01-0853, the licensees letter dated August 30, 2001 (PY-CEI/NRR-2590L), identified the corrective actions listed below. Please provide your disposition for each item.
ISSUE 2: FEEDWATER CHECK VALVE TESTING CONFORMANCE WITH 10 CFR 50.55A AND THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) CODE
- Under the heading of FACTOR OF 10 ADJUSTMENT FACTOR FOR LEAK TESTS PERFORMED AT PRESSURES BELOW FUNCTION PRESSURE, two Actions:
- 1. Some form of testing of the parallel (bypass) piping path around the main feedwater pumps needs to be re-instituted; either a disassemble and inspect on check valve 1N27-F0515, or some other check to ensure long term leak integrity of the check or the gate valve (1N27-F0200) in the bypass line.
- 2. Appropriate program changes should be made to ensure that rework is required on the turbine/motor-driven feed pump discharge check valves if the PTI acceptance criteria of no rotation is not met. Consideration should be given to specifying performance of the PTI during the plant shutdown process, to permit rework to be performed if needed. Also, explicit sign-off steps should be added into the PTI to provide better documentation that the two turbine-driven pumps do not rotate.
- Under the heading DOCUMENTATION OF METHODOLOGY, one Action:
The Inservice Testing ASME Section XI Valve Program Basis Document and the Performance Based Leak Testing Program need to be updated by PES to reflect the current methodology. These would be the proper documents to identify the basis for changes related to License Amendment No. 105.
ISSUE 3: LEAKAGE ACCEPTANCE CRITERIA
- Under the heading IMPACT OF TEST PRESSURE AND POSTULATION OF AN ORIFICE, one Action:
Change the Feedwater check valve test method and acceptance criteria, to ensure the issues identified in Issue 3 (as described in FirstEnergys letter dated August 30, 2001) do not become concerns in the future.
- Under the heading SENSITIVITY CALCULATION - TWO HOUR DURATION, one Action:
Although the corrective action for Issue 3 should ensure that the valves will not leak excessively in the future during a Feedwater Line Break, consideration should be given to revising the Motor-Operated Valve (MOV) Program for the Feedwater gate valves. To be consistent with the two hour duration in the Feedwater Line break calculation, consider updating the MOV Program to require that at least a 135 psid (residual heat removal shutdown cooling permissive) closure capability be maintained for these valves in the future.
- Under the heading SENSITIVITY CALCULATION - IODINE SPIKE, one Action:
Perform design interface review to determine if an iodine spike should be included in the Feedwater line break analysis and update the licensing basis accordingly.
ISSUE 6: CLOSED SYSTEMS OUTSIDE CONTAINMENT AND SECONDARY CONTAINMENT BYPASS LEAKAGE
- Under the heading SECONDARY CONTAINMENT BYPASS LEAKAGE, two Actions:
- 1. Evaluate and revise, if determined necessary, Updated Safety Analysis Report (USAR)
Table 6.2-40, Note 25 and supporting procedures to reflect that only one 1E12-F0053 valve should be included in the 0.6 La total, and then only if the Division 1 or 2 grouping has the largest leakage.
- 2. Revise appropriate USAR leak rate testing Tables, the Plant Data Book Containment Isolation Valve Table, and supporting procedures to reflect the stem/bonnet exams on the 1E12-F0050 and 1E12-F0053 valves.
In addition to the items identified above, the staffs review has identified additional concerns identified below. Please provide your disposition to the following:
- 1. While the Nuclear Regulatory Commission safety evaluation supporting Amendment No.
105 removed leak testing of the feedwater check valves from Appendix J and placed it in the Perry Inservice Testing Program (ISTP), it was not done correctly. The Perry ISTP references ASME/ANSI OM Part 10. Section 4.2.2.2 of OM Part 10, Containment Isolation Valves, states that containment isolation valves shall be tested in accordance with Appendix J to 10 CFR Part 50. However, as a result of the staffs actions in Amendment No. 105, the requirements of Appendix J are not applicable to the feedwater check valves.
Section 4.2.2.2 of OM Part 10 further states that containment isolation valves which also provide a reactor coolant system pressure isolation function (i.e., pressure isolation valves) shall be tested in accordance with Paragraph 4.2.2.3. Paragraph 4.2.2.3 contains specific requirements for ISTP valve testing such as test frequency, adjustments from the test pressure to the operating pressure, test methods and corrective actions if the tested valve(s) do not meet their acceptance criteria. Since the feedwater check valves are containment isolation valves but not pressure isolation valves, the requirements of Paragraph 4.2.2.3 are also not applicable.
In summary, the staffs safety evaluation supporting Amendment No. 105 inadvertently failed to provide any alternatives to the leak testing requirements of either Appendix J or OM Part 10 for the feedwater check valves. Therefore, please provide your standards for test frequency, adjustments to the test pressure, test methods, and corrective actions for the feedwater check valves. The adjustment from test pressure to system operating pressure described in OM Part 10 Section 4.2.2.3(b)(4) or an equivalent should apply unless otherwise justified.
- 2. It is not clear that the break exclusion of the reactor water cleanup line was reviewed as part of Amendment No. 105. To qualify as a break exclusion line, the line must satisfy the seven criteria of Standard Review Plan 3.6.2, Branch Technical Position MEB 3-1, B.1.b.1 through 7. Please confirm that these criteria are satisfied.
- 3. Isolation of the feedwater penetrations is not single-failure proof and relies on the closure of the feedwater gate valves. The design changes to the feedwater gate valves in Amendment No. 105 improves their reliability to close. However, if these valves cannot be closed by remote manual means, procedures should be in place for local closure of these valves. It is recommended that such procedures be available.