Letter Sequence Approval |
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EPID:L-2017-LLR-0096, Relief Requests Associated with Fifth Ten-Year Inservice Testing Interval (Approved, Closed) |
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MONTHYEARML17275A0612017-09-29029 September 2017 Relief Requests Associated with Fifth Ten-Year Inservice Testing Interval Project stage: Request ML17286A0832017-10-13013 October 2017 Relief Requests Associated with Fifth Ten-Year Inservice Testing Interval - Withdrawal of Relief Request 01A-VRR-2 Project stage: Withdrawal ML17297B8162017-10-24024 October 2017 Acceptance Review - Peach Bottom Units 2 and 3 - Fifth 10-Year Inservice Testing Interval Relief Requests Project stage: Acceptance Review ML18036A1562018-02-0707 February 2018 Safety Evaluation of Relief Request 01A-VRR-3 Regarding the Fifth 10-Year Interval of the Inservice Testing Program Project stage: Approval 2017-10-24
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Category:Code Relief or Alternative
MONTHYEARML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML22236A6702022-08-30030 August 2022 Authorization and Safety Evaluation for Alternative Request I5R-14, Revision 1, ML22024A1852022-01-24024 January 2022 Acceptance for Review of Relief Request Associated with Reactor Pressure Vessel N-16A Nozzle Repair ML22003A0022021-12-20020 December 2021 Proposed Relief Request Associated with Reactor Pressure Vessel N-16A Nozzle Repair ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML20343A3492020-12-0707 December 2020 Acceptance of Requested Licensing Action: Peach Bottom Relief Request for N-16 Nozzle ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information ML20099D9552020-04-17017 April 2020 Request to Use Provisions in the 2013 Edition of the ASME Boiler and Pressure Vessel Code for Performing Non-Destructive Examinations ML20097D6442020-04-14014 April 2020 Issuance of Relief Request Limited Examination Coverage During Fourth 10-Year Inservice Inspection Interval RS-20-020, Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi)2020-02-28028 February 2020 Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi) ML20036D9622020-02-0404 February 2020 Dresden Nuclear Power Station, Nine Mile Point Nuclear Station, Peach Bottom Atomic Power Station, & Quad Cities Nuclear Power Station - Proposed Alternative to Extend Reactor Pressure Vessel Safety Relief Valve Testing Frequency ML19350A0152019-12-19019 December 2019 Correction to Relief Request I5R-10 Dated December 2, 2019, Errors Introduced During the Issuance of Relief from the ASME Code Dated December 2, 2019 ML19330C6442019-12-0202 December 2019 Issuance of Relief Request Examination of Standby Liquid Control Nozzle Inside Radius Section in Lieu of Specific ASME Code Requirements ML19308A0112019-10-31031 October 2019 Relief Request I4R-63 Associated with the Fourth Inservice Inspection (ISI) Interval ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19149A2392019-06-11011 June 2019 Issuance of Relief Request Examination of Standby Liquid Control Nozzle Inside Radius Section in Lieu of Specific ASME Code Requirements ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins JAFP-19-0023, Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds2019-02-15015 February 2019 Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds ML18346A5002018-12-21021 December 2018 Issuance of Relief Request Use of ASME Code Case N-513-3 in Lieu of Specific ASME Code Requirements ML18331A2162018-12-21021 December 2018 Issuance of Alternative Requests Related to the Fifth Inservice Inspection Interval ML18327A0622018-12-10010 December 2018 Issuance of Relief Request Use of ASME Code Case N-513-4 in Lieu of Specific ASME Code Requirements JAFP-18-0052, Proposed Alternative to Utilize Code Case N-8792018-05-30030 May 2018 Proposed Alternative to Utilize Code Case N-879 ML18141A6002018-05-30030 May 2018 Safety Evaluation of Relief Request GVRR-2 Regarding the Fifth 10-Year Interval of the Inservice Testing Program JAFP-18-0053, Proposed Alternative to Utilize Code Cases N-878 and N-8802018-05-30030 May 2018 Proposed Alternative to Utilize Code Cases N-878 and N-880 ML18109A1162018-04-19019 April 2018 Relief Requests Associated with the Fifth Inservice Inspection Interval ML18107A7602018-04-17017 April 2018 Acceptance Review for Peach Bottom - Relief Requests from ASME Section XI Code - 5th ISI Interval Code Cases N-513-3 and N-513-4 ML18086B1102018-03-26026 March 2018 Relief Requests Associated with the Use of Code Cases N-513-4 and N-513-3 for the Fifth Inservice Inspection Interval ML18036A1562018-02-0707 February 2018 Safety Evaluation of Relief Request 01A-VRR-3 Regarding the Fifth 10-Year Interval of the Inservice Testing Program ML17332A0192017-12-0707 December 2017 Safety Evaluation of Relief Request 01A-VRR-4 Regarding the Fifth 10-Year Interval of the Inservice Testing Program ML17170A0132017-06-26026 June 2017 Proposed Alternative to Eliminate Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. MF8712-MF8729 and MF9548) ML16230A2372016-09-0606 September 2016 Fleet Request for Proposed Alternative to Use ASME Code Case N-513-4 (CAC Nos. MF7301-MF7322) ML15225A5922015-08-13013 August 2015 Responds to Request for Additional Information Regarding Proposed Relief Request Associated with the Common Emergency Service Water (Esw)System Piping ML15210A7502015-07-29029 July 2015 Proposed Relief Request Associated with the Common Emergency Service Water (ESW) System Piping ML12121A6372012-05-10010 May 2012 Request to Use Code Case N-789 ML0817905392008-09-0303 September 2008 Requests for Relief Associated with the Fourth Inservice Testing Interval ML0809803112008-04-30030 April 2008 Relief Request to Use Boiling Water Reactor Vessel & Internals Project Guidelines.. ML0729106992007-10-25025 October 2007 Requests for Relief from ASME OM Code 5-year Test Interval for Safety Relief Valve/Safety Valves, Relief Request (RR) 01A-VRR-2 2023-12-14
[Table view] Category:Letter
MONTHYEARML24022A2262024-01-22022 January 2024 (PBAPS) Unit 3 - Submittal of the Inservice Inspection (ISI) Owner'S Activity Report (OAR) for the 24th Refueling Outage for Unit 3 ML23346A2412024-01-17017 January 2024 Staff Assessment of Updated Seismic Hazards Following the NRC Process for the Ongoing Assessment of Natural Hazards Information (EPID L-2019-PMP-0061) - Letter IR 05000277/20234022024-01-11011 January 2024 Security Baseline Inspection Report 05000277/2023402 and 05000278/2023402 and Independent Spent Fuel Storage Installation Security Inspection 07200029/2023401 ML23354A1922024-01-0505 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML23355A0622023-12-18018 December 2023 Independent Spent Fuel Storage Installation (Isfsi), Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) IR 05000277/20230032023-10-30030 October 2023 Integrated Inspection Report 05000277/2023003 and 05000278/2023003 and Exercise of Enforcement Discretion ML23286A0012023-10-13013 October 2023 Reply to a Notice of Violation (NOV) - NOV 05000277, 05000278/2023010-01 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans ML23271A1342023-10-11011 October 2023 Dtf Analysis Letter IR 05000277/20244012023-10-0505 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000277/2024401 and 05000278/2024401 ML23265A1502023-09-22022 September 2023 License Amendment Request Revise a License Condition and Certain Technical Specifications to Remove Restrictions in Support of Decommissioning Activities ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L IR 05000277/20230102023-09-15015 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000277/2023010 and 05000278/2023010 and Notice of Violation ML23251A2022023-09-11011 September 2023 Cover Letter W/Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement IR 05000277/20230052023-08-31031 August 2023 Updated Inspection Plan for Peach Bottom Atomic Power Station, Units 2 and 3 (Report 05000277/2023005 and 05000278/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). Includes EPP 06-009, Rev. 13 IR 05000277/20230112023-08-15015 August 2023 Comprehensive Engineering Team Inspection Report 05000277/2023011 and 05000278/2023011 ML23226A1112023-08-14014 August 2023 10 CFR 50.46 Annual Report IR 05000277/20230022023-08-0808 August 2023 Integrated Inspection Report 05000277/2023002 and 05000278/2023002 RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000277/20230402023-07-17017 July 2023 95001 Inspection Supplemental Report 05000277/2023040 and Follow-Up Assessment Letter ML23188A0532023-07-0707 July 2023 Registration of Use of Independent Spent Fuel Storage Installation (ISFSI) Casks ML23186A1272023-07-0606 July 2023 Response to Disputed Non-Cited Violation Documented in Peach Bottom Atomic Power Station, Units 2 and 3, Inspection Report 05000277/2022004 and 05000278/2022004 ML23178A0352023-06-27027 June 2023 Senior Reactor and Reactor Operator Initial License Examinations RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23151A4162023-05-31031 May 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) ML23150A2052023-05-30030 May 2023 Independent Spent Fuel Storage Installation (Isfsi), Annual Radiological Environmental Operating Report 80 January 1, 2022 Through December 31, 2022 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23142A1602023-05-23023 May 2023 Summary of April 11, 2023, Public Observation Meeting with Constellation Energy Generation, LLC Re Proposed Exemption Request from Work Hour Requirements ML23132A1582023-05-18018 May 2023 Correction to Technical Specification 3.4.7 (Page 3.4-16) Issued in Amendment No. 337 ML23132A1532023-05-12012 May 2023 Transmittal of 2022 Annual Financial Reports WM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) IR 05000277/20230012023-05-0808 May 2023 Integrated Inspection Report 05000277/2023001 and 05000278/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI 2024-01-05
[Table view] Category:Safety Evaluation
MONTHYEARML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22236A6702022-08-30030 August 2022 Authorization and Safety Evaluation for Alternative Request I5R-14, Revision 1, ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22094A0012022-04-15015 April 2022 Constellation Energy Generation, LLC - Proposed Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles (Epids L-2021-LLR-0057 and L-2021-LLR-0058) ML22039A0752022-02-22022 February 2022 Site Walkdown for the Review of Plant Information to Perform a Risk Analysis in Accordance with LIC-504, Integrated Risk-Informed Decisionmaking for Emergent Issues,Regarding High Energy Arcing Faults ML22004A2582022-02-14014 February 2022 Issuance of Amendment Nos. 341 and 344 Change to Technical Specification 5.5.7, Ventilation Filter Testing Program ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21166A1682021-06-25025 June 2021 ML21074A4112021-05-14014 May 2021 Issuance of Amendment Nos. 338 and 341, Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4B ML21110A6802021-04-23023 April 2021 Approval of One-Time Alternative to Flaw Characterization and Removal Requirements for N-16A Nozzle ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML21005A0612021-01-14014 January 2021 Proposed Alternatives to Extend the Safety Relief Valve Testing Interval (EPID L-2020-LLR-0014 Through L-2020-LLR-0018) ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20097D6442020-04-14014 April 2020 Issuance of Relief Request Limited Examination Coverage During Fourth 10-Year Inservice Inspection Interval ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML19350A0152019-12-19019 December 2019 Correction to Relief Request I5R-10 Dated December 2, 2019, Errors Introduced During the Issuance of Relief from the ASME Code Dated December 2, 2019 ML19330C6442019-12-0202 December 2019 Issuance of Relief Request Examination of Standby Liquid Control Nozzle Inside Radius Section in Lieu of Specific ASME Code Requirements ML19266A6222019-10-29029 October 2019 Issuance of Amendment Nos. 328 and 331 Revising Technical Specifications 3.81, AC Sources - Operating, for a One-Time Extension of Completion Time ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR ML19182A0062019-08-28028 August 2019 Issuance of Amendment Nos. 327 and 330 Reduce High Pressure Service Water System Design Pressure and Temporarily Extend Completion Times ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19149A2392019-06-11011 June 2019 Issuance of Relief Request Examination of Standby Liquid Control Nozzle Inside Radius Section in Lieu of Specific ASME Code Requirements ML19078A0182019-05-24024 May 2019 Issuance of Amendment Nos. 235, 198, 14, 325, and 328 to Revise the Emergency Response Organization Staffing Requirements ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins ML19015A4222019-03-11011 March 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 ML19039A2232019-02-26026 February 2019 Issuance of Amendment Nos. 324 and 327 Expanded Actions for Leading Edge Flow Meter Conditions ML19011A3252019-02-26026 February 2019 Issuance of Amendment Nos. 323 and 326 to Revise Technical Specifications to Allow Continued Operation with Two Safety Relief Valves/Safety Valves Out of Service ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18346A5002018-12-21021 December 2018 Issuance of Relief Request Use of ASME Code Case N-513-3 in Lieu of Specific ASME Code Requirements ML18331A2162018-12-21021 December 2018 Issuance of Alternative Requests Related to the Fifth Inservice Inspection Interval ML18263A2322018-10-25025 October 2018 Issuance of Amendment Nos. 321 and 324 to Adopt 10 CFR 50.69 (CAC Nos. MG0181 and MG0181; EPID L-2017-LLA-0281) ML18249A2402018-09-28028 September 2018 Issuance of Amendment Nos. 320 and 323 Regarding the Adoption of TSTF-500, DC Electrical Rewrite - Update to TSTF-360 ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18179A3942018-07-18018 July 2018 Safety Evaluation of Relief Request I5R-03Regarding the Fifth 10-Year Interval of the Inservice Inspection Program ML18173A0422018-06-23023 June 2018 Issuance of Amendment Nos. 318 & 321 to Revise Technical Specifications 3.8.1 and 3.8.3, One-Time Change Suspending EDG Surveillance Test Completion Requirements (Emergency Situation) ML18141A6002018-05-30030 May 2018 Safety Evaluation of Relief Request GVRR-2 Regarding the Fifth 10-Year Interval of the Inservice Testing Program 2023-08-30
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 7, 2018 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3-SAFETY EVALUATION OF RELIEF REQUEST 01A-VRR-3 REGARDING THE FIFTH 10-YEAR INTERVAL OF THE INSERVICE TESTING PROGRAM (EPID L-2017-LLR-0096)
Dear Mr. Hanson:
By letter dated September 29, 2017, Exelon Generation Company, LLC (Exelon, the licensee) submitted Relief Requests GVRR-2, 01A-VRR-2, 01A-VRR-3, and 01A-VRR-4 to the U.S. Nuclear Regulatory Commission (NRC). In these relief requests, Exelon proposed alternatives to certain inservice testing requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for Peach Bottom Atomic Power Station (Peach Bottom), Units 2 and 3. The subject relief requests are for the fifth 10-year interval of the inservice testing program at Peach Bottom, Units 2 and 3, which will begin on August 15, 2018.
The purpose of this letter is to provide the results of the NRC staff's review of Relief Request 01A-VRR-3, as documented in the enclosed safety evaluation. In this relief request, Exelon proposed an alternative to extend the test interval for certain safety valves and safety relief valves on the basis that the proposed alternative provides an acceptable level of quality and safety. Our safety evaluation concludes that the proposed alternative will provide an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in Title 10 of the Code of Federal Regulations 50.55a(z)(1 ). Therefore, the NRC staff authorizes the proposed alternative for the fifth 10-year inservice testing interval at Peach Bottom, Units 2 and 3.
By letter dated October 13, 2017 (ADAMS Accession No. ML17286A083), Exelon withdrew Relief Request 01A-VRR-2. By letter dated December 7, 2017 (ADAMS Accession No. ML17332A019),
the NRC authorized the proposed alternative for Relief Request 01A-VRR-4. The NRC staff will provide separate correspondence regarding the review of Relief Request GVRR-2.
B. Hanson All other ASME OM Code requirements for which relief was not specifically requested and approved in Relief Request 01A-VRR-3 remain applicable.
If you have any questions concerning this matter, please contact the Peach Bottom Project Manager, Ms. Jennifer Tobin, at (301) 415-2328 or by e-mail to Jennifer.Tobin@nrc.gov.
S~ly, ~
~iCUiv~
Jaml G. Danna, Chief Plant Licensing Branch LPLI Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278
Enclosure:
Safety Evaluation cc: Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO RELIEF REQUEST 01A-VRR-3 FOR THE FIFTH 10-YEAR INTERVAL OF THE INSERVICE TESTING PROGRAM EXELON GENERATION COMPANY, LLC PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-277 AND 50-278
1.0 INTRODUCTION
By letter dated September 29, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17275A061 ), Exelon Generation Company, LLC (Exelon, the licensee) submitted Relief Requests GVRR-2, 01A-VRR-2, 01A-VRR-3, and 01A-VRR-4 to the U.S. Nuclear Regulatory Commission (NRC or the Commission). In these relief requests, Exelon proposed alternatives to certain inservice testing (1ST) requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for Peach Bottom Atomic PoV1.er Station (Peach Bottom or PBAPS),
Units 2 and 3. The subject relief requests are for the fifth 10-year interval of the 1ST program at Peach Bottom, Units 2 and 3, which will begin on August 15, 2018.
The purpose of this safety evaluation is to provide the results of the NRC staff's review of Relief Request 01A-VRR-3. In this relief request, Exelon proposed an alternative to certain 1ST requirements of the ASME OM Code for testing certain safety valves (SVs) and safety relief valves (SRVs) on the basis that the proposed alternative provides an acceptable level of quality and safety. The relief request was submitted pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1) on the basis that the proposed alternative provides an acceptable level of quality and safety.
By letter dated October 13, 2017 (ADAMS Accession No. ML17286A083), Exelon withdrew Relief Request 01A-VRR-2. By letter dated December 7, 2017 (ADAMS Accession No. ML17332A019),
the NRC authorized the proposed alternative for Relief Request 01A-VRR-4. The NRC staff will provide separate correspondence regarding the review of Relief Request GVRR-2.
2.0 REGULATORY EVALUATION
Section 50.55a(f), "Preservice and inservice testing requirements," of 10 CFR requires, in part, that 1ST of certain ASME Boiler and Pressure Vessel Code (B&PV Code) Class 1, 2, and 3 components must meet the requirements of the ASME OM Code and applicable addenda, except where alternatives have been authorized by the NRC pursuant to paragraphs (z)(1) or (z)(2) of 10 CFR 50.55a.
Enclosure
In proposing alternatives, a licensee must demonstrate that the alternatives provide an acceptable level of quality and safety in accordance with 10 CFR 50.55a(z)( 1), or that compliance would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety in accordance with 10 CFR 50.55a(z)(2).
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request, and the Commission to authorize, the alternative requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1 Licensee's Relief Request 01A-VRR-3 Components Affected Alternative testing is requested for the following valves associated with the main steam safety valves (MSSVs) and main steam SRVs:
Valve Description Class Category Unit RV-2-02-0?0A Main Steam Safety Valve 1 C 2 RV-2-02-0?0B Main Steam Safety Valve 1 C 2 RV-2-02-0?0C Main Steam Safety Valve 1 C 2 RV-2-02-071A Main Steam Safety Relief Valve 1 C 2 RV-2-02-071 B Main Steam Safety Relief Valve 1 C 2 RV-2-02-071 C Main Steam Safety Relief Valve 1 C 2 RV-2-02-071 D Main Steam Safety Relief Valve 1 C 2 RV-2-02-071 E Main Steam Safety Relief Valve 1 C 2 RV-2-02-071 F Main Steam Safety Relief Valve 1 C 2 RV-2-02-071 G Main Steam Safety Relief Valve 1 C 2 RV-2-02-071 H Main Steam Safety Relief Valve 1 C 2 RV-2-02-071 J Main Steam Safety Relief Valve 1 C 2 RV-2-02-071 K Main Steam Safety Relief Valve 1 C 2 RV-2-02-071 L Main Steam Safety Relief Valve 1 C 2 RV-3-02-0?0A Main Steam Safety Valve 1 C 3 RV-3-02-0?0B Main Steam Safety Valve 1 C 3 RV-3-02-0?0C Main Steam Safety Valve 1 C 3 RV-3-02-071A Main Steam Safety Relief Valve 1 C 3 RV-3-02-071 B Main Steam Safety Relief Valve 1 C 3 RV-3-02-071 C Main Steam Safety Relief Valve 1 C 3 RV-3-02-071 D Main Steam Safety Relief Valve 1 C 3 RV-3-02-071 E Main Steam Safety Relief Valve 1 C 3 RV-3-02-071 F Main Steam Safety Relief Valve 1 C 3 RV-3-02-071 G Main Steam Safety Relief Valve 1 C 3 RV-3-02-071 H Main Steam Safety Relief Valve 1 C 3 RV-3-02-071 J Main Steam Safety Relief Valve 1 C 3 RV-3-02-071 K Main Steam Safety Relief Valve 1 C 3 RV-3-02-071 L Main Steam Safety Relief Valve 1 C 3
Applicable Code Edition/Addenda The applicable ASME OM Code edition and addenda for Peach Bottom, Units 2 and 3, is the 2012 Edition with no Addenda.
Applicable Code Requirements ASME OM Code, Mandatory Appendix I, "lnservice Testing of Pressure Relief Devices in Light-Water Reactor Nuclear Power Plants," Section 1-1320, "Test Frequencies, Class 1 Pressure Relief Valves," paragraph (a), "5-Year Test Interval," states, in part, that "Class 1 pressure relief valves shall be tested at least once every 5 years. The test interval for any installed valve shall not exceed 5 years. The 5-year interval shall begin from the date of the as-left set pressure test for each valve."
Licensee's Proposed Alternative and Basis for Use
As an alternative to the ASME Code-required 5-year test interval per Appendix I, paragraph l-1320(a), Exelon proposes that the subject Class 1 pressure relief valves be tested at least once every three refueling cycles (approximately 6 years/72 months) with a minimum of 20 percent of the valves tested within any 24-month interval. This 20 percent would consist of valves that have not been tested during the current 72-month interval, if they exist. The test interval for any individual valve would not exceed 72 months, except that a 6-month grace period is allowed to coincide with refueling outages to accommodate extended shutdown periods and certification of the valve prior to installation.
The licensee provided the following basis for the relief request:
After as-found set-pressure testing, the valves shall be disassembled and inspected to verify that parts are free of defects resulting from time-related degradation or service induced wear. As-left set-pressure testing shall be performed following maintenance and prior to returning the valve to service.
Each valve shall have been disassembled and inspected prior to the start of the 72-month interval. Disassembly and inspection performed prior to the implementation of this alternative based on Code Case OMN-17 may be used.
The relief valve testing and maintenance c~le at PBAPS consists of removal of the SRV/SV complement requiring testing and transportation to an off-site test facility. Upon receipt at the off-site facility, the valves are subject to an as-found inspection and set pressure testing. Prior to the return of the complement of SRVs/SVs for installation in the plant, the \elves are disassembled and inspected to verify that internal surfaces and parts are free from defects or service-induced wear prior to the start of the next test interval. During this process, anomalies or damage are identified and dispositioned for resolution. Damaged or worn parts, springs, gaskets and seals are replaced as necessary. Following reassembly, the valve's set pressure is recertified. This existing process is in accordance with ASME OM Code Case OMN-17, paragraphs (d) and (e). PBAPS previously reviewed the as-found set point test results for all of the SRV/SVs tested since 2000 as detailed in Table 1 of the original alternative request associated with the PBAPS fourth 1ST interval dated July 29, 2013. The test results from the original request are summarized in the following paragraph.
Since 2000, the PBAPS, Units 2 and 3 SRVs/SVs ha\ a history of 96 as-found lift tests. Of these 96 tests, 99% IM3re found within a +/-3% tolerance. During the PBAPS Fall 2012 Unit 2 outage, one of the MSSVs (S/N 1095) as-found lift pressure was identified to be 3.4% above the setpoint. An expanded scope removal of the other SV was performed with a satisfactory lift (the S/N 1093 as-found test (November 2012) was exactly at set pressure). An investigation was performed regarding the one valve that lifted outside of a +/-3% tolerance. It was identified that the previous certification practices were not using the current best-known practices and procedure enhancements have been implemented to prevent recurrence. Additionally, PBAPS implemented enhanced subcomponent replacement and testing criteria to provide further assurance of repeatable as-found lift results.
Accordingly, the proposed alternative of increasing the test interval for the subject Class I pressure relief valves from 5 years to 3 fuel cycles (approximately 6 years/72 months) would continue to provide an acceptable level of quality and safety while restoring the operational and maintenance flexibility that was lost when the 24-month fuel cycle created the unintended consequences of more frequent testing. This proposed alternative will continue to provide assurance of the valves' operational readiness and provides an acceptable level of quality and safety pursuant to 10 CFR 50.55a(z)( 1).
Duration of Proposed Alternative The proposed alternative would apply to the fifth 10-year 1ST interval at Peach Bottom, which is currently scheduled to begin on August 15, 2018, and end on August 14, 2028.
3.2 NRC Staff Evaluation The ASME Code requires that the reactor pressure vessel be protected from overpressure during upset conditions by self-actuated SRVs and/or SVs. As part of the nuclear pressure relief system, the size and number of SRVs and SVs are selected such that peak pressure in the nuclear system will not exceed the ASME Code limits for the reactor coolant pressure boundary.
At Peach Bottom, the SRVs are Target Rock three-stage pilot operated safety/relief valves (11 SRVs per unit). The S\/s are Dresser spring-loaded SVs (3 SVs per unit). The SRVs and SVs are located on the main steam lines bet\M3en the reactor vessel and the first isolation valve within the drywell. The SRVs can actuate by either of two modes: the safety mode or the depressurization mode. In the safety mode, the pilot disc opens \Mlen steam pressure at the valve inlet expands the bellows to the extent that the hydraulic seating force on the pilot disc is reduced to zero. Opening of the pilot stage allows a pressure differential to develop across the second stage disc, which opens the second stage disc, thus \enting the chamber over the main valve piston. This causes a pressure differential across the main valve piston, which opens the main valve. The SVs are spring-loaded valves that actuate when steam pressure at the inlet overcomes the spring force holding the valve disc closed. This satisfies the ASME Code requirement. The proposed changes do not impact the depressurization mode function of the SRVs.
ASME OM Code, Mandatory Appendix I, requires that Class 1 pressure relief valves be tested at least once every 5 years. However, Mandatory Appendix I does not require that pressure relief valves be disassembled and inspected prior to the start of the 5-year test interval. In lieu of the 5-year test interval, the licensee proposed to implement ASME OM Code Case OMN-17, which allows a test interval of 6 years plus a 6-month grace period. The ASME Committee on Operation and Maintenance developed Code Case OMN-17 and published it in the 2009 Edition of the OM Code. ASME OM Code Case OMN-17 imposes a special maintenance requirement to disassemble and inspect each pressure relief/safety valve to verify that parts are free from defects resulting from time-related degradation or service-induced wear prior to the start of the extended test interval and at each required test during the interval. The purpose of this maintenance requirement is to reduce the potential for SRV/SV setpoint drift.
ASME OM Code Case OMN-17 is now in Regulatory Guide 1.192, "Operation and Maintenance Code Case Acceptability, ASME OM Code," and is incorporated by reference in 10 CFR 50.55a.
However, its use in conjunction with the 2012 Edition of the ASME OM Code (Peach Bottom code of reference) is still precluded by the applicability language in the code case itself, which limits its use to OM Code editions prior to the 2006 Addenda. Nonetheless, the NRC has allowed licensees to use OMN-17 with later OM Code editions, provided all requirements in the code case are met. Consistent with the special maintenance requirement in ASME OM Code Case OMN-17, each SRV/SV at Peach Bottom is disassembled and inspected to verify that internal surfaces and parts are free from defects or service-induced wear prior to the start of the next test interval. During this process, anomalies or damage are identified for resolution.
Damaged or worn parts, springs, gaskets, and seals are replaced as necessary. Following reassembly, the valve's set pressure is recertified. This existing process is in accordance with ASME OM Code Case OMN-17, paragraphs (d) and (e).
Furthermore, ASME OM Code Case OMN-17 is performance-based in that it requires that the SRVs/SVs be tested more frequently if test failures occur. For example, ASME OM Code Case OMN-17 requires that two additional valves be tested when a valve in the initial test gruup exceeds the set pressure acceptance criteria. All remaining valves in the group are required to be tested if one of the additional valves tested exceeds its set pressure acceptance criteria.
The licensee has provided a summary of test data since 2000 to show that the subject valves have historically exhibited very limited susceptibility to time-related degradation or setpoint drift.
The licensee plans to implement a disassemblyand inspection program in conjunction with the extended test interval, as required by ASME OM Code Case OMN-17.
Based on the historical performance of the setpoint testing of SRVs/SVs and the disassembly and inspection of the SVs/SRVs after as-found set-pressure testing and prior to use, the NRC staff finds that implementation of ASME OM Code Case OMN-17 for the testing of the designated SRVs/SVs, in lieu of the requirements of the 2012 Edition with no Addenda and the requirements of Mandatory Appendix I, Section 1320, of the ASME OM Code, provides an acceptable level of quality and safety.
4.0 CONCLUSION
As set forth above, the NRC staff has determined that the pruposed alternative testing proposed by Relief Request 01A-VRR-3 provides an acceptable level of quality and safety for the Peach Bottom main steam safety relief valves/main steam SVs listed in Table 1 above. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1 ). Therefore, on the basis of the above
determinations, the NRC authorizes the licensee to use the alternative as proposed in Relief Request 01A-VRR-3 for the fifth 10-year 1ST interval at Peach Bottom, Units 2 and 3, which is currently scheduled to begin August 15, 2018, and end on August 14, 2028.
All other ASME OM Code requirements for which relief was not specifically requested and approved in Relief Request 01A-VRR-3 remain applicable.
Principal Contributor: J. Billerbeck Date: February 7, 2018
B. Hanson
SUBJECT:
PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3-SAFETY EVALUATION OF RELIEF REQUEST 01A-VRR-3 REGARDING THE FIFTH 10-YEAR INTERVAL OF THE INSERVICE TESTING PROGRAM (EPID L-2017-LLR-0096) DATED FEBRUARY 7, 2018 DISTRIBUTION:
PUBLIC JBowen, OEDO PM File Copy RidsACRS_MailCTR Resource RidsNrrDorlLpl1 Resource RidsRgn1 MailCenter Resource RidsNrrLALRonewicz Resource RidsNrrDeEpnb Resource RidsNrrPMPeachBottom Resource JBillerbeck, NRR ADAMS Access1on No.: ML18036A156 *b,y saft ety eva Iuat'10n OFFICE DORL/LPL 1/PM DORL/LPL 1/PM DORL/LPL 1/LA DE/EMIB/BC* DORL/LPL 1/BC DORL/LPL 1/PM NAME JTobin REnnis LRonewicz SBailev Joanna JTobin DATE 02/06/2018 02/07/2018 02/06/2018 01/29/2018 02/07/2018 02/07/2018 OFFICIAL RECORD COPY