|
|
| (7 intermediate revisions by the same user not shown) |
| Line 2: |
Line 2: |
| | number = ML15301A255 | | | number = ML15301A255 |
| | issue date = 10/21/2015 | | | issue date = 10/21/2015 |
| | title = Pilgrim - Response to Request for Additional Information Regarding Relief Request PRR-50, Implementation of Code Case N-702 | | | title = Response to Request for Additional Information Regarding Relief Request PRR-50, Implementation of Code Case N-702 |
| | author name = Perkins E P | | | author name = Perkins E |
| | author affiliation = Entergy Nuclear Operations, Inc | | | author affiliation = Entergy Nuclear Operations, Inc |
| | addressee name = | | | addressee name = |
| Line 19: |
Line 19: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter: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 20555-0001SUBJECT: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: 2.15.073Dear 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,% | | {{#Wiki_filter:S'En tergy Entergy Nuclear Operations, Inc. |
| 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
| | Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 October 21, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 |
|
| |
|
| ==Attachment== | | ==SUBJECT:== |
| 1To 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 Information Regarding Relief Request PRR-50, Implementation of Code Case N-702 (TAC No. |
| 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 | | MF6362) |
| }} | | Entergy Nuclear Operations, Inc. |
| | Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35 |
| | |
| | ==REFERENCE:== |
| | NRC Email to Entergy, "Request for Information Regarding Pilgrim Relief Request (PRR)-50, Implementation of Code Case N-702 (TAC No. |
| | MF6362), dated September 23, 2015 LETTER NUMBER: 2.15.073 |
| | |
| | ==Dear Sir or Madam:== |
| | |
| | Pursuant to the request by the U.S. Nuclear Regulatory Commission staff for additional information contained in the Reference, please find attached the Pilgrim Nuclear Power Station response. |
| | Please contact me at (508) 830-8323 or Murray Williams at (508) 830-8275 if you have any questions. |
| | Sincerely, EveretP (Cip *C--i"rs M a nager," Regulatonryssuranc EPP/mew Attachments: 1. Response to Request for Additional Information Regarding Relief Request PRR-50, Implementation of Code Case N-702 (TAC No. MF6362) |
| | : 2. Entergy Calculation M1 396, Structural Integrity Associates, "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 |
| | |
| | Letter Number: 2.15.073 Page 2 of 2 cc: Mr. Daniel Dorman Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Boulevard, Suite 100 King of Prussia, PA 19406-1415 Ms. Booma Venkataraman, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission MS O-8C2A Washington, DC 20555 NRC Senior Resident Inspector Pilgrim Nuclear Power Station |
| | |
| | Attachment 1 To PNPS Letter 2.15.073 Response 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 INFORMATION REGARDING RELIEF REQUEST NO. PRR-50, IMPLEMENTATION OF CODE CASE N-702 (TAC NO. MF6362) |
| | NRC Request 1 By letter dated June 4, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15166A037), Entergy Nuclear Operations, Inc. (the licensee) submitted pursuant to Title 10 Code of Federal Regulations (10 CFR) 50.55(z)(1 ) a request for an 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 Power Plant Components," on the basis that the proposed alternatives provide an acceptable level of quality and safety for the Pilgrim Nuclear Power Station (PNPS). Pursuant to 10 CFR 50.55a(z)(1 ), the licensee requested approval to implement the alternative of Code Case N-702 in 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 for Use", states in relevant part: |
| | Therefore, a plant specific probabilistic fracture mechanics evaluation was performed to supplement the criteria of Code Case N-702 and BWRVIP-241 in order to demonstrate that 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 in BWRVIP-241, with PNPS specific fracture mechanics analyses*. The results demonstrate that for the N2 nozzles at PNPS, the probability of failure was less than the NRC safety goal of 5.0 x 1 0- per year. Therefore, the probabilistic fracture mechanics criteria of BWRVIP-241 remain applicable to the PNPS N2 nozzles. |
| | *The PNPS specific reference document for this statement is cited as Structural Integrity Associates, "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 the reference document in order for NRC to review the probabilistic fracture mechanics analysis of the N2 nozzles at PNPS under this relief request, PRR-50. |
| | |
| | ===Response=== |
| | The requested document is provided in Attachment 2 to this letter. |
| | Attachment 1 - Page 1 of 1}} |
Letter Sequence Response to RAI |
|---|
|
|
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
[Table View] |
|
|---|
Category:Letter
MONTHYEARL-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)
ML23136A7792023-05-15015 May 2023
Annual Radiological Environmental Operating Report, January 1 Through December 31, 2022
ML23135A2152023-05-15015 May 2023
Annual Radioactive Effluent Release 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
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
ML22269A4202022-09-22022 September 2022
Citizen Lawsuit
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
ML22206A1512022-08-0101 August 2022
NRC Office of Investigations Case Nos. 1-2022-002 & 1-2022-006
ML22221A2592022-08-0101 August 2022
LTR-22-0217-1-NMSS - Town of Duxbury Letter Opposing the Irradiated Water Release from Pilgrim (Docket No. 05000293)
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)
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
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
ML22104A0542022-04-30030 April 2022
LTR-22-0093 Response to Sheila Lynch-Benttinen, Regarding Irradiated Water Release from Pilgrim
L-22-026, Occupational Radiation Exposure Data Report - 20212022-04-29029 April 2022
Occupational Radiation Exposure Data Report - 2021
ML22152A2592022-04-25025 April 2022
Zaccagnini Letter Dated 04/25/22
ML22152A2642022-04-19019 April 2022
Flynn Letter Dated 04/19/22
ML22091A1062022-04-0101 April 2022
Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))
L-22-022, and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec.2022-03-25025 March 2022
and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec.
ML22130A6762022-03-14014 March 2022
Decola Ltr Dtd 03/14/22 Re Potential Discharge of Radioactive Water from Pilgrim Nuclear Power Station
ML22041B0762022-03-0707 March 2022
03-07-22 - Letter to the Honorable William R. Keating, Responds to Letter Regarding Proposed Release of Irradiated Water at Pilgrim Nuclear Power Station Into Cape Cod Bay
ML22054A2962022-02-23023 February 2022
Annual ISFSI Radioactive Effluent Release Report for 2021
2024-02-02
[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
[Table view] |
Text
S'En tergy Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 October 21, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Response to Request for Additional Information Regarding Relief Request PRR-50, Implementation of Code Case N-702 (TAC No.
MF6362)
Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35
REFERENCE:
NRC Email to Entergy, "Request for Information Regarding Pilgrim Relief Request (PRR)-50, Implementation of Code Case N-702 (TAC No.
MF6362), dated September 23, 2015 LETTER NUMBER: 2.15.073
Dear Sir or Madam:
Pursuant to the request by the U.S. Nuclear Regulatory Commission staff for additional information contained in the Reference, please find attached the Pilgrim Nuclear Power Station response.
Please contact me at (508) 830-8323 or Murray Williams at (508) 830-8275 if you have any questions.
Sincerely, EveretP (Cip *C--i"rs M a nager," Regulatonryssuranc EPP/mew Attachments: 1. Response to Request for Additional Information Regarding Relief Request PRR-50, Implementation of Code Case N-702 (TAC No. MF6362)
- 2. Entergy Calculation M1 396, Structural Integrity Associates, "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
Letter Number: 2.15.073 Page 2 of 2 cc: Mr. Daniel Dorman Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Boulevard, Suite 100 King of Prussia, PA 19406-1415 Ms. Booma Venkataraman, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission MS O-8C2A Washington, DC 20555 NRC Senior Resident Inspector Pilgrim Nuclear Power Station
Attachment 1 To PNPS Letter 2.15.073 Response 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 INFORMATION REGARDING RELIEF REQUEST NO. PRR-50, IMPLEMENTATION OF CODE CASE N-702 (TAC NO. MF6362)
NRC Request 1 By letter dated June 4, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15166A037), Entergy Nuclear Operations, Inc. (the licensee) submitted pursuant to Title 10 Code of Federal Regulations (10 CFR) 50.55(z)(1 ) a request for an 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 Power Plant Components," on the basis that the proposed alternatives provide an acceptable level of quality and safety for the Pilgrim Nuclear Power Station (PNPS). Pursuant to 10 CFR 50.55a(z)(1 ), the licensee requested approval to implement the alternative of Code Case N-702 in 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 for Use", states in relevant part:
Therefore, a plant specific probabilistic fracture mechanics evaluation was performed to supplement the criteria of Code Case N-702 and BWRVIP-241 in order to demonstrate that 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 in BWRVIP-241, with PNPS specific fracture mechanics analyses*. The results demonstrate that for the N2 nozzles at PNPS, the probability of failure was less than the NRC safety goal of 5.0 x 1 0- per year. Therefore, the probabilistic fracture mechanics criteria of BWRVIP-241 remain applicable to the PNPS N2 nozzles.
- The PNPS specific reference document for this statement is cited as Structural Integrity Associates, "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 the reference document in order for NRC to review the probabilistic fracture mechanics analysis of the N2 nozzles at PNPS under this relief request, PRR-50.
Response
The requested document is provided in Attachment 2 to this letter.
Attachment 1 - Page 1 of 1