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Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status IR 05000003/20240022024-08-0606 August 2024 NRC Inspection Report 05000003/2024002, 05000247/2024002, 05000286/2024002 PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024 Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0 ML24171A0122024-06-18018 June 2024 Reply to a Notice of Violation EA-24-037 ML24156A1162024-06-0404 June 2024 Correction - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities IR 05000003/20240052024-05-21021 May 2024 and 3 - NRC Inspection Report Nos. 05000003/2024005, 05000247/2024005, 05000286/2024005, 07200051/2024001, and Notice of Violation ML24128A0632024-05-0707 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024 HDI Annual Occupational Radiation Exposure Data Reports - 2023 ML24116A2412024-04-25025 April 2024 Annual Environmental Protection Plan Report ML24114A2282024-04-23023 April 2024 Annual Radioactive Effluent Release Report L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI) ML24080A1722024-03-20020 March 2024 Reply to a Notice of Violation EA-2024-010 IR 05000003/20240012024-03-20020 March 2024 NRC Inspection Report Nos. 05000003/2024001, 05000247/2024001, and 05000286/2024001 (Cover Letter Only) ML24045A0882024-02-22022 February 2024 Correction to the Technical Specifications to Reflect Appropriate Pages Removed and Retained by Previous License Amendments ML24053A0642024-02-22022 February 2024 2023 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report IR 05000003/20230042024-02-22022 February 2024 NRC Inspection Report Nos. 05000003/2023004, 05000247/2023004, 05000286/2023004, and 07200051/2023004 and Notice of Violation ML24011A1982024-01-12012 January 2024 ISFSI, Notice of Organization Change for Site Vice President ML23342A1082024-01-0909 January 2024 – Independent Spent Fuel Storage Installation Security Inspection Plan ML23353A1742023-12-19019 December 2023 ISFSI, Emergency Plan, Revision 23-04 L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan ML23339A0442023-12-0505 December 2023 Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan ML23338A2262023-12-0404 December 2023 Signed Amendment No. 27 to Indemnity Agreement No. B-19 ML23356A0212023-12-0101 December 2023 American Nuclear Insurers, Secondary Financial Protection (SFP) Program ML23242A2772023-11-30030 November 2023 NRC Letter Issuance - IP LAR for Units 2 and 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs ML23338A0482023-11-30030 November 2023 ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28 ML22339A1572023-11-27027 November 2023 Letter - Indian Point - Ea/Fonsi Request for Exemptions from Certain Emergency Planning Requirements for 10 CFR 50.47 and 10 CFR Part 50, Appendix E IR 05000003/20230032023-11-21021 November 2023 NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003 ML23100A1252023-11-17017 November 2023 Letter and Enclosure 1 - Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement ML23100A1172023-11-17017 November 2023 NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition ML23050A0032023-11-17017 November 2023 Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following Spent Fuel Transfer to Dry Storage ML23100A1432023-11-16016 November 2023 Letter - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286) L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23064A0002023-11-13013 November 2023 NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) ML23063A1432023-11-0101 November 2023 Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML23292A0262023-10-19019 October 2023 LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI ML23289A1582023-10-16016 October 2023 Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit ML23270A0082023-09-27027 September 2023 Registration of Spent Fuel Casks ML23237A5712023-09-22022 September 2023 09-22-2023 Letter to Dwaine Perry, Chief, Ramapo Munsee Nation, from Chair Hanson, Responds to Letter Regarding Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23242A2182023-09-12012 September 2023 IPEC NRC Response to the Town of New Windsor, Ny Board Certified Motion Letter Regarding Treated Water Release from IP Site (Dockets 50-003, 50-247, 50-286) ML23250A0812023-09-0707 September 2023 Registration of Spent Fuel Casks ML23255A0142023-08-31031 August 2023 LTR-23-0211 Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report IR 05000003/20230022023-08-22022 August 2023 NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002 ML23227A1852023-08-15015 August 2023 Request for a Revised Approval Date Regarding the Indian Point Energy Center Permanently Defueled Emergency Plan and Emergency Action Level Scheme ML23222A1442023-08-10010 August 2023 Registration of Spent Fuel Casks ML23208A1642023-07-26026 July 2023 Village of Croton-on-Hudson New York Letter Dated 7-26-23 Re Holtec Wastewater ML23200A0422023-07-19019 July 2023 Registration of Spent Fuel Casks ML23235A0602023-07-17017 July 2023 LTR-23-0194 Dwaine Perry, Chief, Ramapo Munsee Nation, Ltr Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River 2024-09-18
[Table view] Category:Safety Evaluation
MONTHYEARML23339A0442023-12-0505 December 2023 Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan ML23243A8452023-11-30030 November 2023 Enclosure 3: Issuance - IP LAR for SE Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs ML23050A0022023-11-17017 November 2023 Enclosure 2 - Safety Evaluation for Indian Point Unit 2 License Amendment Request to Modify Technical Specifications for Staffing Requirements Following Spent Fuel Transfer to Dry Storage ML23100A1172023-11-17017 November 2023 NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition ML23064A0002023-11-13013 November 2023 NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments ML23067A0822023-11-0101 November 2023 Enclosure 2 - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Safety Exemption Evaluation for Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML21091A3052022-02-28028 February 2022 Issuance of Amendment No. 272 Revision to Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device (EPID L-2020-LLA-0051) (Non-Proprietary) ML21074A0002021-04-22022 April 2021 Issuance of Amendment No. 270 Permanently Defueled Technical Specifications ML21083A0002021-04-14014 April 2021 Issuance of Amendment No. 63 Permanently Defueled Technical Specifications ML21054A3302021-02-24024 February 2021 Approval of Alternative IP3-ISI-RR-16 to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement ML20297A3332020-11-23023 November 2020 Enclosure 3, Safety Evaluation for Transfer of Renewed Facility Operating Licenses to Holtec International, Owner, and Holtec Decommissioning International, LLC, Operator ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI NL-20-050, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-06-24024 June 2020 Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline ML20100H9922020-06-0202 June 2020 Issuance of Amendment No. 269 Proposed Technical Specification Changes to City Water Surveillance Requirement and Condensate Storage Tank Required Action A.1 ML20122A2622020-05-0404 May 2020 Correction to Amendment No. 294 Dated April 28, 2020, Permanently Defueled Technical Specifications ML20081J4022020-04-28028 April 2020 Issuance of Amendment No. 294 Permanently Defueled Technical Specifications ML20078L1402020-04-15015 April 2020 Issuance of Amendment Nos. 62, 293, and 268 Changes to Emergency Plan for Post-Shutdown and Permanently Defueled Condition ML20099A1822020-04-13013 April 2020 Issuance of Relief Request IP3-IST-RR-001 - Alternative to Certain Requirements of the ASME Code for Extension of the Fourth 10-Year Inservice Test Interval ML20071Q7172020-04-10010 April 2020 Issuance of Amendment Nos. 292 and No. 267 Changes to Technical Specification Sections 1.1, 4.0, and 5.0 for a Permanently Defueled Condition ML19333B8682019-12-18018 December 2019 Approval of Certified Fuel Handler Training and Retraining Program ML19254A6032019-09-19019 September 2019 Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1 ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19209C9662019-09-0404 September 2019 Issuance of Amendment No. 290 Storage of Fresh and Spent Nuclear Fuel in the Spent Fuel Pool ML19065A1012019-03-21021 March 2019 Issuance of Amendment No. 61 and No. 289 Deletion of License Conditions Related to Decommissioning Trust Provision ML19039A1492019-02-25025 February 2019 Issuance of Relief Request IP3-ISI-RR-14 Alternative Examination Required by ASME Code Case N-724-4 ML18337A4222018-12-20020 December 2018 Issuance of Amendment No. 265 One-Time Extension of 10 CFR Part 50, Appendix J, Type a, Integrated Leakage Rate Test Interval ML18251A0042018-09-18018 September 2018 Safety Evaluation for Relief Request IP3-ISI-RR-11, RR-12, RR-15 Approval of Alternative Associated with Extension of Fourth Interval Reactor Vessel and Piping Weld Inspections (EPID: L-2017-LLR-0124,0127) ML18193B0302018-07-18018 July 2018 Safety Evaluation for Relief Request IP3-ISI-RR-13 Fourth Ten-year Inservice Inspection Interval Extension ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 ML18142A4312018-05-31031 May 2018 Safety Evaluation for Relief Request IP2-ISI-RR-06 Approval of Alternative to Use Embedded Weld Repair ML18059A1562018-03-0606 March 2018 Safety Evaluation for Relief Request IP2-ISI-RR-05 Alternative Examination Volume Required by ASME Code Case N-729-4 ML18005A0662018-01-23023 January 2018 Safety Evaluation of Relief Requests ISI-RR-20, ISI-RR-21, and ISI-RR-22 Regarding the Fourth 10-Year Interval of the Inservice Inspection Program ML17348A6952018-01-11011 January 2018 Issuance of Amendment Connection of Non-Seismic Boric Acid Recovery System to the Refueling Water Storage Tank (CAC No. MF9578; EPID L-2017-LLA-0202) ML17320A3542017-12-22022 December 2017 Issuance of Amendments Amendment of Inter-Unit Transfer of Spent Fuel (CAC Nos. MF8991 and MF8992; EPID L-2016-LLA-0039) ML17315A0002017-12-0808 December 2017 Issuance of Amendments Cyber Security Plan Implementation Schedule (CAC Nos. MF9656, MF9657, and MF9658; EPID: L-2017-LLA-0217) ML17174B1442017-07-12012 July 2017 Relief Request for EN-ISI-16-1 Regarding Use of Later Edition and Addenda of the ASME Code ML17065A1712017-03-27027 March 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17069A2832017-03-16016 March 2017 Relief Request No. IP3-ISI-RR-09, for Alternative to the Depth Sizing Qualification Requirement ML16336A4922017-01-27027 January 2017 Transmittal Letter: Order Approving Transfer of Master Decommissioning Trust Funds for Indian Point, No. 3 & FitzPatrick Nuclear Plant from the Power Authority of the State of New York to Entergy Nuclear Operations, Inc. ML16358A4442017-01-11011 January 2017 Relief from the Requirements of the ASME Code Regarding Alternate IP3-RR-10 to the Full Circumferential Inspection Requirement of Code Case N-513-3 ML16215A2432016-11-15015 November 2016 Issuance of Amendment Nos. 285 and 261 Conditional Exemption from End-of-Life Moderator Temperature Coefficient ML16179A1782016-09-14014 September 2016 Safety Evaluation for Relief Request IP2-ISI-RR-01, Examination of Upper Pressurizer Welds ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML16167A0812016-07-15015 July 2016 Request for Alternative IP2-ISI-RR-03 to Weld Reference System Examination Required by ASME Code Subarticle IWA-2600 ML16147A5192016-07-14014 July 2016 Safety Evaluation for Relief Request IP2-ISI-RR-02 Alternative Examination Volume Required by Code Case N-729-1 ML16096A2692016-06-0606 June 2016 Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 ML16093A0282016-05-31031 May 2016 Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1 ML16064A2152016-04-12012 April 2016 Issuance of Amendments Cyber Security Plan Implementation Schedule 2023-05-01
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Text
April 13, 2020 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 - ISSUANCE OF RELIEF REQUEST IP3-IST-RR-001 - ALTERNATIVE TO CERTAIN REQUIREMENTS OF THE ASME CODE FOR EXTENSION OF THE FOURTH 10-YEAR INSERVICE TEST INTERVAL (EPID L-2019-LLR-0094)
Dear Sir or Madam:
By letter dated September 24, 2019 (Agencywide Documents Access and Management System Accession No. ML19267A380), Entergy Nuclear Operations, Inc. (the licensee) submitted a proposed alternative to the requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), associated with inservice testing at Indian Point Nuclear Generating Unit No. 3 (Indian Point 3).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2), the licensee requested to use proposed alternative IP3-IST-RR-001 on the basis that the ASME OM Code requirements present an undue hardship without a compensating increase in the level of quality or safety.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2). Therefore, the NRC staff authorizes the proposed alternative for Indian Point 3 for the extension of the fourth 10-year inservice test program interval, which begins on July 21, 2020, and is scheduled to end no later than April 30, 2021.
All other ASME OM Code requirements for which relief was not specifically requested and approved remain applicable.
If you have any questions concerning this matter, please contact the Indian Point 3 Project Manager, Richard Guzman, at (301) 415-1030 or Richard.Guzman@nrc.gov.
Sincerely,
/RA/
James G. Danna, Chief Plant Licensing Branch 1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-286
Enclosure:
Safety Evaluation cc: Listserv
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO RELIEF REQUEST IP3-IST-RR-001 FOR EXTENSION OF THE FOURTH 10-YEAR INSERVICE TEST INTERVAL ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286
1.0 INTRODUCTION
By letter dated September 24, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19267A380), Entergy Nuclear Operations, Inc. (Entergy or the licensee) submitted a proposed alternative to the requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), associated with inservice testing at Indian Point Nuclear Generating Unit No. 3 (IP3).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2)), the licensee requested to use the proposed alternative in Relief Request IP3-IST-RR-001 on the basis that the ASME OM Code requirements present an undue hardship without a compensating increase in the level of quality or safety.
2.0 REGULATORY EVALUATION
Pursuant to 10 CFR 50.55a(f)(4), Inservice testing standards requirements for operating plants, throughout the service life of a boiling or pressurized water-cooled nuclear power facility, pumps and valves that are within the scope of the ASME OM Code must meet the inservice test requirements (except design and access provisions) set forth in the ASME OM Code and addenda that become effective subsequent to editions and addenda specified in 10 CFR 50.55a(f)(2) and (3) and that are incorporated by reference in 10 CFR 50.55a(a)(1)(iv) to the extent practical, within the limitations of design, geometry, and materials of construction of the components.
Pursuant to 10 CFR 50.55a(z), Alternatives to codes and standards requirements, alternatives to the requirements of 10 CFR 50.55a(f) may be used, when authorized by the U.S. Nuclear Regulatory Commission (NRC), if the licensee demonstrates (1) the proposed alternatives would provide an acceptable level of quality and safety or (2) compliance with the specified requirements would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety.
Enclosure
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 NRC to authorize, the alternative requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1 Components Affected All components within the scope of the IP3 inservice test (IST) program.
3.2 Applicable Code Edition and Addenda The applicable ASME OM Code edition for the IP3 fourth 10-year IST program interval is the 2001 Edition through 2003 Addenda of the ASME OM Code.
3.3 Duration of Proposed Alternative The IP3 fourth 10-year IST program interval began on July 21, 2009, and is scheduled to end on July 20, 2020 (including the 1-year extension allowed in ISTA-3120). The licensee submitted the proposed alternative for implementation between July 21, 2020, and the permanent IP3 shutdown date, currently scheduled for no later than April 30, 2021.
3.4 Reason for Request The IP3 fourth IST program interval ends on July 20, 2020, with the 1-year extension allowed in the ASME OM Code. The licensee states that IP3 is planning to permanently cease power operation no later than April 30, 2021. There are no refueling outages scheduled prior to April 30, 2021. The licensee states that updating its fifth IST program interval to the 2012 Edition of the ASME OM Code will require significant personnel resources and procedure and process changes, with minimal impact on the actual pump and valve testing during the planned remaining 9 months of operation.
3.5 Licensees Proposed Alternative Request IP3-IST-RR-001 In IP3-IST-RR-001, the licensee requested an alternative to the IST requirements of the ASME OM Code, as incorporated by reference in 10 CFR 50.55a.
In particular, subparagraph (f)(3), Successive Inservice Test Intervals, in paragraph ISTA-3200, Administrative Requirements, in the 2001 Edition of the ASME OM Code, states, in part, that the test plan for each successive inservice test interval shall comply with the edition and addenda of the sections that have been adopted by the regulatory authority 12 months prior to the start of the inservice test interval, or subsequent editions and addenda that have been adopted by the regulatory authority.
Subparagraph (d) in paragraph ISTA-3120, Inservice Test Interval, in the 2001 Edition of the ASME OM Code states, in part, that each IST program interval may be extended or decreased by as much as 1 year.
As of the date of this safety evaluation, the NRC regulations in 10 CFR 50.55a(f)(4)(ii) state, in part, that inservice tests to verify operational readiness of pumps and valves whose function is required for safety, conducted during successive 120-month intervals, must comply with the
requirements of the latest edition and addenda of the ASME OM Code incorporated by reference in 10 CFR 50.55a(a)(1)(iv) 12 months before the start of the 120-month interval (or the optional ASME Code Cases listed in NRC Regulatory Guide (RG) 1.147, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, or RG 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code, as incorporated by reference in 10 CFR 50.55a(a)(3)(ii) and (iii), respectively, subject to the conditions listed in 10 CFR 50.55a(b).
The NRC regulations in 10 CFR 50.55a(a)(1)(iv)(C)(1) currently identify the 2012 Edition of the ASME OM Code as the latest approved edition.
The licensee has requested to use the proposed alternative described below for all components within the scope of the IP3 IST program. In IP3-IST-RR-001, the licensee states:
In accordance with 10 CFR 50.55a(a)(z)(2), Entergy Nuclear Operations, Inc.
(Energy) proposes to continue implementation of the testing requirements specified in the 2001 Edition with the 2003 Addenda of the OM Code by extending the fourth ten-year interval from July 21, 2020 to the permanent plant shutdown date, currently scheduled for no later than April 30, 2021. This proposal is an alternative to the requirements of ISTA-3200(f)(3) and 10 CFR 50.55a(f)(4)(ii), Applicable IST Code: Successive 120-month intervals, requirements for determining the OM Code Edition and Addenda.
In implementing this proposal, Entergy will comply with all NRC conditions as specified in 10 CFR 50.55a applicable for the 2001 Edition through the 2003 Addenda of the OM Code, including the augmented requirements of (f)(4) and (f)(6)(ii). Code Cases that were adopted per RG 1.192 will continue to be those cases applicable to the 2001 Edition through the 2003 Addenda. In summary, Entergy will continue to implement the current IP3 IST Program Fourth Interval with all applicable Conditions specific to the 2001 Edition through the 2003 Addenda in 10 CFR 50.55a.
There are many changes which occurred in the ASME OM Code between the 2001 with 2003 Addenda and the 2012 Edition. However, none are necessary to ensure an acceptable level of quality and safety nor were these changes made to address a deficiency in the OM Code that adversely impacted safety.
In summary, Entergy proposes to extend the IP3 Fourth IST Program Interval from July 21, 2020 to the permanent plant shutdown date, currently scheduled for no later than April 30, 2021. This extension, if approved, would allow IP3 to continue to implement the requirements of the OM Code, 2001 Edition with the 2003 Addenda, in lieu of the OM Code, 2012 Edition until the permanent plant shutdown. If the decision to permanently shutdown IP3 is later changed, an updated IST Program, developed in accordance with the applicable Edition and Addenda of the OM Code then in effect per 10 CFR 50.55a, will be implemented.
Implementation of this request will provide adequate detection of component degradation and will continue to provide reasonable assurance of the operational readiness of affected IP3 components. Therefore, compliance with the requirements of ISTA-3200(f)(3) and 10 CFR 50.55a(f)(4)(ii) would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety pursuant to 10 CFR 50.55a(z)(2).
3.6 NRC Staff Evaluation The licensee is proposing to extend the current fourth 10-year IST program interval at IP3 for 9 months past the current end date of July 20, 2020. The licensee indicates that IP3 is scheduled to permanently shutdown no later than April 30, 2021. The licensee has previously extended this interval by 1 year, which is the maximum extension allowed by ISTA-3120(d) in the 2001 Edition of the ASME OM Code. The licensee proposes to continue to apply the 2001 Edition of the ASME OM Code with the 2003 Addenda as its OM Code of record, rather than the required 2012 Edition of the ASME OM Code. The licensee states that it will also continue to comply with the 10 CFR 50.55a conditions applicable to the 2001 Edition through the 2003 Addenda of the ASME OM Code, the augmented requirements of 10 CFR 50.55a(f)(4) and (f)(6)(ii), and any OM Code cases currently being applied. If the decision to permanently shutdown IP3 is changed, the licensee will develop and implement an IST program in accordance with the edition of the ASME OM Code that is in effect per 10 CFR 50.55a.
The NRC staff reviewed the changes between the 2001 Edition with 2003 Addenda and the 2012 Edition of the ASME OM Code as part of the evaluation of the licensees alternative request. There are a wide range of IST improvements to the ASME OM Code over that time period. For example, ASME incorporated Mandatory Appendix III, Preservice and Inservice Testing of Active Electric Motor Operated Valve Assemblies in Light-Water Reactor Power Plants, in the 2009 Edition of the OM Code. Therefore, the staff evaluated the IST requirements and licensee commitments applicable to IP3 related to pumps, valves, and dynamic restraints to determine whether compliance with the requirements to update the IST program 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).
If the IP3 IST program is not updated in 2020, the licensee will continue to apply the IST requirements in the 2001 Edition through the 2003 Addenda of the ASME OM Code, as incorporated by reference in 10 CFR 50.55a. In addition, the licensee must satisfy the conditions specified in 10 CFR 50.55a that are applicable to the 2001 Edition through the 2003 Addenda of the ASME OM Code. For example, the NRC regulations in 10 CFR 50.55a(b)(3)(ii) require periodic verification of the design-basis capability of motor-operated valves.
Further, the licensee is required to satisfy the requirements in 10 CFR Part 50, Appendix A, General Design Criteria for Nuclear Power Plants, and Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, for the capability of other power-operated valves to perform their safety functions, as discussed in NRC Regulatory Issue Summary 2000-03, Resolution of Generic Safety Issue 158: Performance of Safety-Related Power-Operated Valves Under Design Basis Conditions, March 15, 2000 (ADAMS Accession No. ML003686003). With respect to commitments, the licensee is implementing its programs in response to Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves, and Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves. The currently NRC-approved alternative and relief requests for the fourth 10-year IST program interval will also be in effect until the end of the extended interval.
While there are significant changes between the 2001 Edition and 2012 Edition of the ASME OM Code, the NRC staff considers that the provisions in the 2001 Edition through the 2003 Addenda of the ASME OM Code, as incorporated by reference in 10 CFR 50.55a,
together with the current regulations and licensee commitments related to power-operated valves, will provide reasonable assurance of the capability of the pumps, valves, and snubbers within the scope of the IP3 IST program to perform their safety functions for the 9-month time period from July 21, 2020, to April 30, 2021. Therefore, the NRC staff finds that the licensee, in alternative request IP3-IST-RR-001, has satisfied the requirements in 10 CFR 50.55a(z)(2) in that compliance with the regulatory requirements to update the IST program at IP3 for this short time period would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety.
4.0 CONCLUSION
As set forth above, the NRC staff has determined that for alternative request IP3-IST-RR-001 for IP3, the proposed alternative provides reasonable assurance that the components in the scope of the IP3 IST program will be operationally ready during a 9-month extension of the current fourth 10-year IST program interval. Accordingly, the NRC staff concludes that the licensee has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(2) for request IP3-IST-RR-001. Therefore, the NRC staff authorizes the use of alternative request IP3-IST-RR-001 for IP3 for the extension of the fourth 10-year IST program interval, which begins on July 21, 2020, and is scheduled to end no later than April 30, 2021.
All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject request remains applicable.
Principal Contributor: R. Wolfgang Date: April 13, 2020
ML20099A182 *by e-mail OFFICE DORL/LPL1/PM DORL/LPL1/LA DEX/EMIB/BC(A)* DORL/LPL1/BC DORL/LPL1/PM NAME RGuzman LRonewicz TScarbrough JDanna RGuzman DATE 04/13/2020 04/13/2020 02/11/2020 04/13/2020 04/13/2020