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| Response to Request for Additional Information Regarding ReliefRequest PRR-50, Implementation of Code Case N-702 (TAC No.MF6362)Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power StationDocket No. 50-293License No. DPR-35REFERENCE:NRC Email to Entergy, "Request for Information Regarding Pilgrim ReliefRequest (PRR)-50, Implementation of Code Case N-702 (TAC No.MF6362), dated September 23, 2015LETTER NUMBER: 2.15.073 | | Response to Request for Additional Information Regarding ReliefRequest PRR-50, Implementation of Code Case N-702 (TAC No.MF6362)Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power StationDocket No. 50-293License No. DPR-35 |
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| | ==REFERENCE:== |
| | NRC Email to Entergy, "Request for Information Regarding Pilgrim ReliefRequest (PRR)-50, Implementation of Code Case N-702 (TAC No.MF6362), dated September 23, 2015LETTER NUMBER: 2.15.073 |
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| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
| Pursuant to the request by the U.S. Nuclear Regulatory Commission staff for additionalinformation contained in the Reference, please find attached the Pilgrim Nuclear Power Stationresponse.Please contact me at (508) 830-8323 or Murray Williams at (508) 830-8275 if you have anyquestions.Sincerely,EveretP (Cip M a nag er," Regul atonryssurancEPP/mewAttachments:1. Response to Request for Additional Information Regarding Relief RequestPRR-50, Implementation of Code Case N-702 (TAC No. MF6362)2. Entergy Calculation M1 396, Structural Integrity Associates, "Evaluation ofProbability of Failure for Recirculation Inlet (N2) in the Nozzle-to-ShellWelds and Nozzle Blend Radii Regions at Pilgrim Nuclear Station,"1400071.301, Revision 0, February 2014,% | | Pursuant to the request by the U.S. Nuclear Regulatory Commission staff for additionalinformation contained in the Reference, please find attached the Pilgrim Nuclear Power Stationresponse.Please contact me at (508) 830-8323 or Murray Williams at (508) 830-8275 if you have anyquestions.Sincerely,EveretP (Cip M a nag er," Regul atonryssurancEPP/mewAttachments:1. Response to Request for Additional Information Regarding Relief RequestPRR-50, Implementation of Code Case N-702 (TAC No. MF6362)2. Entergy Calculation M1 396, Structural Integrity Associates, "Evaluation ofProbability of Failure for Recirculation Inlet (N2) in the Nozzle-to-ShellWelds and Nozzle Blend Radii Regions at Pilgrim Nuclear Station,"1400071.301, Revision 0, February 2014,% |
| Letter Number: 2.15.073Page 2 of 2cc: Mr. Daniel DormanRegional Administrator, Region IU.S. Nuclear Regulatory Commission2100 Renaissance Boulevard, Suite 100King of Prussia, PA 19406-1415Ms. Booma Venkataraman, Project ManagerOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionMS O-8C2AWashington, DC 20555NRC Senior Resident InspectorPilgrim Nuclear Power Station To PNPS Letter 2.15.073Response to Request for Additional Information Regarding Relief Request PRR-50,Implementation of Code Case N-702 (TAC No. MF6362)(1 Page) | | Letter Number: 2.15.073Page 2 of 2cc: Mr. Daniel DormanRegional Administrator, Region IU.S. Nuclear Regulatory Commission2100 Renaissance Boulevard, Suite 100King of Prussia, PA 19406-1415Ms. Booma Venkataraman, Project ManagerOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionMS O-8C2AWashington, DC 20555NRC Senior Resident InspectorPilgrim Nuclear Power Station To PNPS Letter 2.15.073Response to Request for Additional Information Regarding Relief Request PRR-50,Implementation of Code Case N-702 (TAC No. MF6362)(1 Page) |
| RESPONSE TO REQUEST FOR ADDITIONAL INFORMATIONREGARDING RELIEF REQUEST NO. PRR-50,IMPLEMENTATION OF CODE CASE N-702(TAC NO. MF6362)NRC Request 1By letter dated June 4, 2015 (Agencywide Documents Access and Management System(ADAMS) Accession No. ML1 51 66A037), Entergy Nuclear Operations, Inc. (the licensee)submitted pursuant to Title 10 Code of Federal Regulations (10 CFR) 50.55(z)(1 ) a request foran alternative to specific portions of the American Society of Mechanical Engineers (ASME)Boiler and Pressure Vessel Code, Section Xl, "Rules for Inservice Inspection of Nuclear PowerPlant Components," on the basis that the proposed alternatives provide an acceptable level ofquality and safety for the Pilgrim Nuclear Power Station (PNPS). Pursuant to 10 CFR50.55a(z)(1 ), the licensee requested approval to implement the alternative of Code Case N-702in lieu of the code required 100% examination of all nozzles identified in the request.1. Attachment 1 to the licensee's letter, Section 4, Page 4, "Proposed Alternative and Basis forUse", states in relevant part:Therefore, a plant specific probabilistic fracture mechanics evaluation was performed tosupplement the criteria of Code Case N-702 and BWRVIP-241 in order to demonstratethat the probability of failure remains acceptable over this period of extended operation(to 60 years). This analysis was performed using the same methods as were used inBWRVIP-241, with PNPS specific fracture mechanics analyses*. The resultsdemonstrate that for the N2 nozzles at PNPS, the probability of failure was less than theNRC safety goal of 5.0 x 1 0- per year. Therefore, the probabilistic fracture mechanicscriteria of BWRVIP-241 remain applicable to the PNPS N2 nozzles.*The PNPS specific reference document for this statement is cited as Structural IntegrityAssociates, "Evaluation of Probability of Failure for Recirculation Inlet (N2) in the Nozzle-to-Shell Welds and Nozzle Blend Radii Regions at Pilgrim Nuclear Station", 1400071 .301,Revision 0, February 2014.The above reference document was not provided with the submittal. Please provide thereference document in order for NRC to review the probabilistic fracture mechanics analysis ofthe N2 nozzles at PNPS under this relief request, PRR-50.ResponseThe requested document is provided in Attachment 2 to this letter.Attachment 1 -Page 1 of 1 | | RESPONSE TO REQUEST FOR ADDITIONAL INFORMATIONREGARDING RELIEF REQUEST NO. PRR-50,IMPLEMENTATION OF CODE CASE N-702(TAC NO. MF6362)NRC Request 1By letter dated June 4, 2015 (Agencywide Documents Access and Management System(ADAMS) Accession No. ML1 51 66A037), Entergy Nuclear Operations, Inc. (the licensee)submitted pursuant to Title 10 Code of Federal Regulations (10 CFR) 50.55(z)(1 ) a request foran alternative to specific portions of the American Society of Mechanical Engineers (ASME)Boiler and Pressure Vessel Code, Section Xl, "Rules for Inservice Inspection of Nuclear PowerPlant Components," on the basis that the proposed alternatives provide an acceptable level ofquality and safety for the Pilgrim Nuclear Power Station (PNPS). Pursuant to 10 CFR50.55a(z)(1 ), the licensee requested approval to implement the alternative of Code Case N-702in lieu of the code required 100% examination of all nozzles identified in the request.1. Attachment 1 to the licensee's letter, Section 4, Page 4, "Proposed Alternative and Basis forUse", states in relevant part:Therefore, a plant specific probabilistic fracture mechanics evaluation was performed tosupplement the criteria of Code Case N-702 and BWRVIP-241 in order to demonstratethat the probability of failure remains acceptable over this period of extended operation(to 60 years). This analysis was performed using the same methods as were used inBWRVIP-241, with PNPS specific fracture mechanics analyses*. The resultsdemonstrate that for the N2 nozzles at PNPS, the probability of failure was less than theNRC safety goal of 5.0 x 1 0- per year. Therefore, the probabilistic fracture mechanicscriteria of BWRVIP-241 remain applicable to the PNPS N2 nozzles.*The PNPS specific reference document for this statement is cited as Structural IntegrityAssociates, "Evaluation of Probability of Failure for Recirculation Inlet (N2) in the Nozzle-to-Shell Welds and Nozzle Blend Radii Regions at Pilgrim Nuclear Station", 1400071 .301,Revision 0, February 2014.The above reference document was not provided with the submittal. Please provide thereference document in order for NRC to review the probabilistic fracture mechanics analysis ofthe N2 nozzles at PNPS under this relief request, PRR-50.ResponseThe requested document is provided in Attachment 2 to this letter.Attachment 1 -Page 1 of 1}} |
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MONTHYEARML15195A0522015-07-10010 July 2015 Acceptance Review Pilgrim - PRR- 50 and 51, Proposed Alternative: Implementation of Code Case N-702 (PRR-50) and Implementation of BWRVIP-05 (GL 98-05) (PRR-51) (TAC Nos. MF6362 & MF6361) Project stage: Acceptance Review ML15258A2192015-09-14014 September 2015 E-mail Capture - Pilgrim Nuclear Power Station Acceptance Review - PRR-50 and PRR-51 (Proposed Alternative to Nozzle-to-Weld Weld Examination (Code Case N-702) MF6362 and RPV Shell Circumferential Weld Examination (BWRVIP-05) MF6361 Project stage: Acceptance Review ML15266A5312015-09-23023 September 2015 NRR E-mail Capture - Request for Information Regarding Pilgrim Relief Request (PRR)-50, Implementation of Code Case N-702 Project stage: RAI ML15301A2552015-10-21021 October 2015 Response to Request for Additional Information Regarding Relief Request PRR-50, Implementation of Code Case N-702 Project stage: Response to RAI ML15301A2562015-10-21021 October 2015 Calculation M1396, Evaluation of Probability of Failure for Recirculation Inlet (N2) in the Nozzle-to-Shell Welds and Nozzle Blend Radii Regions, 1400071.301, Revision 0, February 2014 Project stage: Other 2015-07-10
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Category:Letter
MONTHYEARML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24129A1042024-05-26026 May 2024 Preapplication Readiness Assessment Plan for the Holtec Decommissioning International License Termination Plan ML24136A2382024-05-14014 May 2024 Annual Radiological Environmental Operating Report for 2023 ML24135A3212024-05-14014 May 2024 Annual Radioactive Effluent Release Report, January 1 Through December 31, 2023 IR 05000293/20240012024-05-0707 May 2024 NRC Inspection Report No. 05000293/2024001 L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024 HDI Annual Occupational Radiation Exposure Data Reports - 2023 L-24-010, Request for Preapplication Readiness Assessment of the Draft License Termination Plan2024-04-22022 April 2024 Request for Preapplication Readiness Assessment of the Draft License Termination Plan 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) IR 05000293/20230032024-02-29029 February 2024 NRC Inspection Report Nos. 05000293/2023003 and 05000293/2023004 L-24-002, Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G2024-02-0202 February 2024 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G ML23342A1182024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23334A1822023-11-30030 November 2023 Biennial Report for the Defueled Safety Analysis Report Update, Technical Specification Bases Changes, 10 CFR 50.59 Evaluation Summary, and Regulatory Commitment Change Summary November 2021 Through October 2023 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 ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) L-23-011, 10 CFR 72.48 Biennial Change Summary Report2023-10-27027 October 2023 10 CFR 72.48 Biennial Change Summary Report IR 05000293/20234012023-08-31031 August 2023 NRC Inspection Report No. 05000293/2023401 & 2023001 (Cover Letter Only) IR 05000293/20230022023-08-0404 August 2023 NRC Inspection Report No. 05000293/2023002 L-23-008, Correction to Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations Holtec Decommissioning International, LLC (HDI)2023-05-23023 May 2023 Correction to Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations Holtec Decommissioning International, LLC (HDI) ML23135A2152023-05-15015 May 2023 Annual Radioactive Effluent Release Report, January 1 Through December 31, 2022 ML23136A7792023-05-15015 May 2023 Annual Radiological Environmental Operating Report, January 1 Through December 31, 2022 L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance ML23069A2782023-03-13013 March 2023 Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1 Subsequent License Renewal Application ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities IR 05000293/20220042023-02-15015 February 2023 NRC Inspection Report No. 05000293/2022004 ML22356A0712023-01-31031 January 2023 Issuance of Exemption for Pilgrim Nuclear Power Station ISFSI Regarding Annual Radioactive Effluent Release Report - Cover Letter ML22347A2782022-12-21021 December 2022 Independent Spent Fuel Storage Installation Security Inspection Plan Dated December 21, 2022 L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 L-22-041, Supplemental Information to Enhance Exemption Request Detail for Pilgrim ISFSI Annual Radioactive Effluent Release Report Due Date Extension2022-12-0909 December 2022 Supplemental Information to Enhance Exemption Request Detail for Pilgrim ISFSI Annual Radioactive Effluent Release Report Due Date Extension IR 05000293/20220032022-11-18018 November 2022 NRC Inspection Report No. 05000293/2022003 L-22-036, Decommissioning Trust Fund Agreement2022-11-0808 November 2022 Decommissioning Trust Fund Agreement ML22276A1762022-10-24024 October 2022 Decommissioning International Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22266A1922022-09-23023 September 2022 and Pilgrim Nuclear Power Station - Request to Withdraw Prior Submissions from NRC Consideration ML22269A4202022-09-22022 September 2022 Citizen Lawsuit ML22272A0352022-09-22022 September 2022 S. Lynch-Benttinen Letter Regarding U.S. Citizen Intent to Sue U.S. Fish and Wildlife and NOAA Fisheries Representing the Endangered Species (Na Right Whale) Which Will Be Adversely Affected by Holtec International Potential Actions ML22241A1122022-08-29029 August 2022 Request for Exemption from 10 CFR 72.212(a)(2), (b)(2), (b)(3), (b)(4), (B)(5)(i), (b)(11), and 72.214 for Pilgrim ISFSI Annual Radioactive Effluent Release Report IR 05000293/20220022022-08-12012 August 2022 NRC Inspection Report No. 05000293/2022002 ML22215A1772022-08-0303 August 2022 Decommissioning International (HDI) Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22221A2592022-08-0101 August 2022 LTR-22-0217-1-NMSS - Town of Duxbury Letter Opposing the Irradiated Water Release from Pilgrim (Docket No. 05000293) ML22206A1512022-08-0101 August 2022 NRC Office of Investigations Case Nos. 1-2022-002 & 1-2022-006 ML22175A1732022-07-28028 July 2022 LTR-22-0153-1 - Response Letter to D. Turco, Cape Downwinders, from A. Roberts, NRC, Regarding Holtec-Pilgrim Plans to Dump One Million Gallons of Radioactive Waste Into Cape Cod Bay ML22193A1662022-07-28028 July 2022 LTR-22-0154-1 - Heather Govern, VP, Clean Air and Water Program, Et Al., Letter Regarding Radioactive Wastewater Disposal from the Pilgrim Nuclear Power Station (Docket No. 05000293) ML22154A4882022-06-0101 June 2022 Letter from Conservation Law Foundation Regarding Irradiated Water Release from Pilgrim ML22154A1622022-05-26026 May 2022 Letter and Email from Save Our Bay/Diane Turco Regarding Irradiated Water Release from Pilgrim ML22136A2602022-05-16016 May 2022 Submittal of Annual Radiological Environmental Operating Report for January 1 Through December 31, 2021 ML22136A2572022-05-16016 May 2022 Submittal of Annual Radioactive Effluent Release Report for January 1 Through December 31, 2021 ML22102A0932022-05-12012 May 2022 LTR-22-0067 Response to Matthew P. Levesque, President, Barnstable Town Council Regarding Irradiated Water Release from Pilgrim IR 05000293/20220012022-05-11011 May 2022 NRC Inspection Report No. 05000293/2022001 2024-06-03
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-21-098, Response to Request for Additional Information (RAI) - License Amendment Request to Approve the Pilgrim Nuclear Power Station Independent Fuel Storage Installation Only Emergency Plan2021-09-0707 September 2021 Response to Request for Additional Information (RAI) - License Amendment Request to Approve the Pilgrim Nuclear Power Station Independent Fuel Storage Installation Only Emergency Plan L-21-090, Response to Request for Additional Information (Rai), License Amendment Request to Approve the Pilgrim Nuclear Power Station Independent Fuel Storage Installation Only Emergency Plan2021-07-29029 July 2021 Response to Request for Additional Information (Rai), License Amendment Request to Approve the Pilgrim Nuclear Power Station Independent Fuel Storage Installation Only Emergency Plan L-21-057, Supplemental Information to Update - License Amendment Request to Approve the Pilgrim Nuclear Power Station Independent Fuel Storage Installation Only Emergency Plan2021-05-20020 May 2021 Supplemental Information to Update - License Amendment Request to Approve the Pilgrim Nuclear Power Station Independent Fuel Storage Installation Only Emergency Plan ML20188A0612020-06-25025 June 2020 Response to NRC Request for Information on Physical Security Plan Revision and License Amendment Request to Incorporate Additional Independent Spent Fuel Storage Installation L-20-029, Response to NRC Request for Clarifying Information2020-04-22022 April 2020 Response to NRC Request for Clarifying Information CNRO-2019-00030, Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary2019-12-30030 December 2019 Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary ML19210E4702019-07-29029 July 2019 Transmittal of Response to NRC Request for Additional Information Regarding Request for Direct and Indirect License Transfers, RAI-PFPB-1 and - 2 ML19197A1142019-07-16016 July 2019 Response to Request for Additional Information - License Amendment Request to Revise the Technical Specifications - Permanently Defueled Technical Specifications ML19170A3912019-06-19019 June 2019 Final Response Regarding Request for Information Pursuant to Title 10 CFR 50.54(f) Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML19109A1772019-04-17017 April 2019 Response to NRC Request for Additional Information ML19056A1912019-02-18018 February 2019 Attachment 1: Response to Request for Additional Information - Exemption from the Requirements of 10 CFR 50.47 and Appendix E to 10 CFR Part 50, Entergy Nuclear Operations, Inc ML19050A1912019-02-14014 February 2019 Response to Request for Additional Information - Exemption from the Requirements of 10CFR50.47 and Appendix E to 10CFR50 ML19016A1352019-01-10010 January 2019 Response to Request for Additional Information - License Amendment Request to Revise the Technical Specifications - Permanently Defueled Technical Specifications ML18341A2192018-12-0404 December 2018 Response to Request for Additional Information - Exemption from the Requirements of 10 CFR 50.47 and Appendix E to 10 CFR Part 50 ML18338A2052018-11-30030 November 2018 Response to Request for Additional Information - Exemption from the Requirements of 10 CFR 50.47 and Appendix E to 10 CFR Part 50 ML18317A0582018-11-0808 November 2018 Response to Request for Additional Information - License Amendment Request to Emergency Plan and Emergency Action Level Scheme to Address the Permanently Defueled Condition ML18317A0592018-11-0808 November 2018 Response to Request for Additional Information - License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme to Address the Permanently Defueled Condition ML18268A1342018-09-21021 September 2018 Response to Request for Information Relating to Notification of Changes to Comprehensive Recovery Plan ML18135A1042018-05-29029 May 2018 Responses to Request for Information - Senator Edward Markey Letter Dated April 23, 2018 (Enclosure) ML18152A8722018-05-23023 May 2018 Attachments 1 & 2: Response to Request for Additional Information - License Amendment Request to Revise the Emergency Plan to Address the Permanently Defueled Condition. Letters of Agreement Enclosed ML18066A0822018-03-19019 March 2018 Enclosure - Letter to Senator Elizabeth Warren, Et Al., from Chairman Svinicki Regarding Winter Storms and an Inspector for Pilgrim Nuclear Power Station ML16333A0052016-11-18018 November 2016 Transmittal of Response to Request for Additional Information - Relief Request on Volumetric Exam Requirements, PNPS-ISI-004 & 005 ML16224B0142016-08-0202 August 2016 Response to Request for Additional Information - Relief Request Number PRR-52, Proposed Alternative to Pressure Testing of Mechanical Joints as a Result of Repair/Replacement Activity and the Use of Code Case N-795. ML16071A4412016-03-0707 March 2016 Entergy Fleet Relief Request No. RR-EN-15-1-Proposed Alternative to Use ASME Code Case N-789-1 - E-mail from G.Davant to R.Guzman - Response to Second RAI (MF6340 - MF6349) CNRO-2016-00005, Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM)2016-02-25025 February 2016 Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2016-00002, Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Secti2016-01-29029 January 2016 Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Section Xl, CNRO-2015-00002, Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 12015-12-0404 December 2015 Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 1 ML15301A2562015-10-21021 October 2015 Calculation M1396, Evaluation of Probability of Failure for Recirculation Inlet (N2) in the Nozzle-to-Shell Welds and Nozzle Blend Radii Regions, 1400071.301, Revision 0, February 2014 ML15301A2552015-10-21021 October 2015 Response to Request for Additional Information Regarding Relief Request PRR-50, Implementation of Code Case N-702 ML15209A6062015-07-17017 July 2015 Station'S Notification of Full Compliance with Order EA-12-051, Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation 2021-09-07
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S'En tergyEntergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station600 Rocky Hill RoadPlymouth, MA 02360October 21, 2015U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001
SUBJECT:
Response to Request for Additional Information Regarding ReliefRequest PRR-50, Implementation of Code Case N-702 (TAC No.MF6362)Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power StationDocket No. 50-293License No. DPR-35
REFERENCE:
NRC Email to Entergy, "Request for Information Regarding Pilgrim ReliefRequest (PRR)-50, Implementation of Code Case N-702 (TAC No.MF6362), dated September 23, 2015LETTER NUMBER: 2.15.073
Dear Sir or Madam:
Pursuant to the request by the U.S. Nuclear Regulatory Commission staff for additionalinformation contained in the Reference, please find attached the Pilgrim Nuclear Power Stationresponse.Please contact me at (508) 830-8323 or Murray Williams at (508) 830-8275 if you have anyquestions.Sincerely,EveretP (Cip M a nag er," Regul atonryssurancEPP/mewAttachments:1. Response to Request for Additional Information Regarding Relief RequestPRR-50, Implementation of Code Case N-702 (TAC No. MF6362)2. Entergy Calculation M1 396, Structural Integrity Associates, "Evaluation ofProbability of Failure for Recirculation Inlet (N2) in the Nozzle-to-ShellWelds and Nozzle Blend Radii Regions at Pilgrim Nuclear Station,"1400071.301, Revision 0, February 2014,%
Letter Number: 2.15.073Page 2 of 2cc: Mr. Daniel DormanRegional Administrator, Region IU.S. Nuclear Regulatory Commission2100 Renaissance Boulevard, Suite 100King of Prussia, PA 19406-1415Ms. Booma Venkataraman, Project ManagerOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionMS O-8C2AWashington, DC 20555NRC Senior Resident InspectorPilgrim Nuclear Power Station To PNPS Letter 2.15.073Response to Request for Additional Information Regarding Relief Request PRR-50,Implementation of Code Case N-702 (TAC No. MF6362)(1 Page)
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATIONREGARDING RELIEF REQUEST NO. PRR-50,IMPLEMENTATION OF CODE CASE N-702(TAC NO. MF6362)NRC Request 1By letter dated June 4, 2015 (Agencywide Documents Access and Management System(ADAMS) Accession No. ML1 51 66A037), Entergy Nuclear Operations, Inc. (the licensee)submitted pursuant to Title 10 Code of Federal Regulations (10 CFR) 50.55(z)(1 ) a request foran alternative to specific portions of the American Society of Mechanical Engineers (ASME)Boiler and Pressure Vessel Code, Section Xl, "Rules for Inservice Inspection of Nuclear PowerPlant Components," on the basis that the proposed alternatives provide an acceptable level ofquality and safety for the Pilgrim Nuclear Power Station (PNPS). Pursuant to 10 CFR50.55a(z)(1 ), the licensee requested approval to implement the alternative of Code Case N-702in lieu of the code required 100% examination of all nozzles identified in the request.1. Attachment 1 to the licensee's letter, Section 4, Page 4, "Proposed Alternative and Basis forUse", states in relevant part:Therefore, a plant specific probabilistic fracture mechanics evaluation was performed tosupplement the criteria of Code Case N-702 and BWRVIP-241 in order to demonstratethat the probability of failure remains acceptable over this period of extended operation(to 60 years). This analysis was performed using the same methods as were used inBWRVIP-241, with PNPS specific fracture mechanics analyses*. The resultsdemonstrate that for the N2 nozzles at PNPS, the probability of failure was less than theNRC safety goal of 5.0 x 1 0- per year. Therefore, the probabilistic fracture mechanicscriteria of BWRVIP-241 remain applicable to the PNPS N2 nozzles.*The PNPS specific reference document for this statement is cited as Structural IntegrityAssociates, "Evaluation of Probability of Failure for Recirculation Inlet (N2) in the Nozzle-to-Shell Welds and Nozzle Blend Radii Regions at Pilgrim Nuclear Station", 1400071 .301,Revision 0, February 2014.The above reference document was not provided with the submittal. Please provide thereference document in order for NRC to review the probabilistic fracture mechanics analysis ofthe N2 nozzles at PNPS under this relief request, PRR-50.ResponseThe requested document is provided in Attachment 2 to this letter.Attachment 1 -Page 1 of 1