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| | issue date = 02/16/2016 | | | issue date = 02/16/2016 |
| | title = Supplement to Request for Approval of Pilgrim Relief Request (PRR)-52, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) Pressure Testing of Mechanical Joints as a Result of Performance of a Repair/Replacement Activity and Use of | | | title = Supplement to Request for Approval of Pilgrim Relief Request (PRR)-52, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) Pressure Testing of Mechanical Joints as a Result of Performance of a Repair/Replacement Activity and Use of |
| | 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 = |
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| =Text= | | =Text= |
| {{#Wiki_filter:En tei-g Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth. | | {{#Wiki_filter:Entergy Nuclear Operations, Inc. |
| MA 02360 February 16, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 | | En tei-g Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth. MA 02360 February 16, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Supplement to Request for Approval of Pilgrim Relief Request (PRR)-52,"Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) | | Supplement to Request for Approval of Pilgrim Relief Request (PRR)-52, "Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) Pressure Testing of Mechanical Joints as a Result of Performance of a Repair/Replacement Activity and Use of Code Case N-795" Pilgrim Nuclear Power Station Docket No.: 50-293 Renewed License No.: DPR-35 |
| Pressure Testing of Mechanical Joints as a Result of Performance of a Repair/Replacement Activity and Use of Code Case N-795" Pilgrim Nuclear Power Station Docket No.: 50-293 Renewed License No.: DPR-35 | |
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| ==REFERENCE:== | | ==REFERENCE:== |
| | Entergy Letter to NRC, Request for Approval of Pilgrim Relief Request (PRR)- |
| | 52, "Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) Pressure Testing of Mechanical Joints as a Result of Performance of a Repair/Replacement Activity and Use of Code Case N-795," dated October 21, 2015 (2.15.074) |
| | LETTER NUMBER: 2.16.011 |
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| Entergy Letter to NRC, Request for Approval of Pilgrim Relief Request (PRR)-52, "Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)
| | ==Dear Sir or Madam:== |
| Pressure Testing of Mechanical Joints as a Result of Performance of a Repair/Replacement Activity and Use of Code Case N-795," dated October 21, 2015 (2.15.074)
| | |
| LETTER NUMBER: 2.16.011
| | The referenced letter requested an alternative to specific portions of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, "Rules for In-service inspection of Nuclear Power Plant Components," pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(2). This is a request for alternative on the basis that compliance with the specified requirements as described in this request would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. However, the stated basis in the first paragraph of the referenced letter was that "the proposed alternative provides an acceptable level of quality and safety" which corresponds to a request for alternative pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(1). |
| | This letter updates the basis for the request for alternative submitted in the first paragraph of the referenced letter as follows: |
| | Pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(2), Pilgrim Nuclear Power Station (PNPS) hereby requests an alternative to specific portions of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, "Rules for In-service Inspection of Nuclear Power Plant Components," on the basis that compliance with the specified requirements as described in this request would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. |
| | If you have questions concerning this letter, please contact me at 508-830-8323. |
| | /iJP1/2~1 |
| | |
| | Entergy Nuclear Operations, Inc. Letter No. 2.16.011 Pilgrim Nuclear Power Station Page 2 There are no new commitments included in this letter. |
| | Sincerely, Everett (Chip) P. Per Ins,-Jr. |
| | Manager, Regulatory Assurance EPP/mw cc: Mr. Daniel H. Dorman Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 Ms. Booma Venkataraman, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission |
| | *Mail Stop O-8C2A Washington, DC 20555 NRC Senior Resident Inspector Pilgrim Nuclear Power Station |
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| |
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| ==Dear Sir or Madam:==
| | Entergy Nuclear Operations, Inc. |
| The referenced letter requested an alternative to specific portions of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, "Rules for In-service inspection of Nuclear Power Plant Components," pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(2).
| | En tei-g Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth. MA 02360 February 16, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 |
| This is a request for alternative on the basis that compliance with the specified requirements as described in this request would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. However, the stated basis in the first paragraph of the referenced letter was that "the proposed alternative provides an acceptable level of quality and safety" which corresponds to a request for alternative pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(1).
| |
| This letter updates the basis for the request for alternative submitted in the first paragraph of the referenced letter as follows: Pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(2), Pilgrim Nuclear Power Station (PNPS) hereby requests an alternative to specific portions of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, "Rules for In-service Inspection of Nuclear Power Plant Components," on the basis that compliance with the specified requirements as described in this request would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.If you have questions concerning this letter, please contact me at 508-830-8323.
| |
| /iJP1/2~1 Entergy Nuclear Operations, Inc. Letter No. 2.16.011 Pilgrim Nuclear Power Station Page 2 There are no new commitments included in this letter.Sincerely, Everett (Chip) P. Per Ins,-Jr.Manager, Regulatory Assurance EPP/mw cc: Mr. Daniel H. Dorman Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 Ms. Booma Venkataraman, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission
| |
| *Mail Stop O-8C2A Washington, DC 20555 NRC Senior Resident Inspector Pilgrim Nuclear Power Station En tei-g Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth.
| |
| MA 02360 February 16, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 | |
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| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Supplement to Request for Approval of Pilgrim Relief Request (PRR)-52,"Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) | | Supplement to Request for Approval of Pilgrim Relief Request (PRR)-52, "Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) Pressure Testing of Mechanical Joints as a Result of Performance of a Repair/Replacement Activity and Use of Code Case N-795" Pilgrim Nuclear Power Station Docket No.: 50-293 Renewed License No.: DPR-35 |
| Pressure Testing of Mechanical Joints as a Result of Performance of a Repair/Replacement Activity and Use of Code Case N-795" Pilgrim Nuclear Power Station Docket No.: 50-293 Renewed License No.: DPR-35 | |
|
| |
|
| ==REFERENCE:== | | ==REFERENCE:== |
| | Entergy Letter to NRC, Request for Approval of Pilgrim Relief Request (PRR)- |
| | 52, "Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) Pressure Testing of Mechanical Joints as a Result of Performance of a Repair/Replacement Activity and Use of Code Case N-795," dated October 21, 2015 (2.15.074) |
| | LETTER NUMBER: 2.16.011 |
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| |
|
| Entergy Letter to NRC, Request for Approval of Pilgrim Relief Request (PRR)-52, "Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)
| | ==Dear Sir or Madam:== |
| Pressure Testing of Mechanical Joints as a Result of Performance of a Repair/Replacement Activity and Use of Code Case N-795," dated October 21, 2015 (2.15.074)
| |
| LETTER NUMBER: 2.16.011
| |
|
| |
|
| ==Dear Sir or Madam:==
| | The referenced letter requested an alternative to specific portions of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, "Rules for In-service inspection of Nuclear Power Plant Components," pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(2). This is a request for alternative on the basis that compliance with the specified requirements as described in this request would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. However, the stated basis in the first paragraph of the referenced letter was that "the proposed alternative provides an acceptable level of quality and safety" which corresponds to a request for alternative pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(1). |
| The referenced letter requested an alternative to specific portions of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, "Rules for In-service inspection of Nuclear Power Plant Components," pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(2). | | This letter updates the basis for the request for alternative submitted in the first paragraph of the referenced letter as follows: |
| This is a request for alternative on the basis that compliance with the specified requirements as described in this request would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. However, the stated basis in the first paragraph of the referenced letter was that "the proposed alternative provides an acceptable level of quality and safety" which corresponds to a request for alternative pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(1). | | Pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(2), Pilgrim Nuclear Power Station (PNPS) hereby requests an alternative to specific portions of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, "Rules for In-service Inspection of Nuclear Power Plant Components," on the basis that compliance with the specified requirements as described in this request would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. |
| This letter updates the basis for the request for alternative submitted in the first paragraph of the referenced letter as follows: Pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(2), Pilgrim Nuclear Power Station (PNPS) hereby requests an alternative to specific portions of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, "Rules for In-service Inspection of Nuclear Power Plant Components," on the basis that compliance with the specified requirements as described in this request would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.If you have questions concerning this letter, please contact me at 508-830-8323. | | If you have questions concerning this letter, please contact me at 508-830-8323. |
| /iJP1/2~1 Entergy Nuclear Operations, Inc. Letter No. 2.16.011 Pilgrim Nuclear Power Station Page 2 There are no new commitments included in this letter.Sincerely, Everett (Chip) P. Per Ins,-Jr.Manager, Regulatory Assurance EPP/mw cc: Mr. Daniel H. Dorman Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 Ms. Booma Venkataraman, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission | | /iJP1/2~1 |
| *Mail Stop O-8C2A Washington, DC 20555 NRC Senior Resident Inspector Pilgrim Nuclear Power Station}} | | |
| | Entergy Nuclear Operations, Inc. Letter No. 2.16.011 Pilgrim Nuclear Power Station Page 2 There are no new commitments included in this letter. |
| | Sincerely, Everett (Chip) P. Per Ins,-Jr. |
| | Manager, Regulatory Assurance EPP/mw cc: Mr. Daniel H. Dorman Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 Ms. Booma Venkataraman, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission |
| | *Mail Stop O-8C2A Washington, DC 20555 NRC Senior Resident Inspector Pilgrim Nuclear Power Station}} |
Letter Sequence Supplement |
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|
MONTHYEARML16057A1772016-02-16016 February 2016
Supplement to Request for Approval of Pilgrim Relief Request (PRR)-52, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) Pressure Testing of Mechanical Joints as a Result of Performance of a Repair/Replacement Activity and Use of
Project stage: Supplement
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.
Project stage: Response to RAI
ML16257A5732016-09-15015 September 2016
Issuance of Relief Request No. PRR-52-Relief from ASME Code, Section XI Requirements for Pressure Testing of Class 1 Pressure Retaining Components as a Result of Repair/Replacement Activity and Use of Code Case N-795
Project stage: Approval
2016-08-02
[Table View] |
|
|---|
Category:Code Relief or Alternative
MONTHYEARML18128A0672018-06-0808 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
CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 12017-11-17017 November 2017
Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1
ML17093A8942017-05-12012 May 2017
Pilgrim Nuclear Power Station - Relief Requests PNPS-ISI-001 and PNPS-ISI-002, Relief from ASME Code Volumetric Examination Requirements for the Fourth 10-Year Inservice Inspection Interval (CAC Nos. MF8092 and MF8093)
ML16257A5732016-09-15015 September 2016
Issuance of Relief Request No. PRR-52-Relief from ASME Code, Section XI Requirements for Pressure Testing of Class 1 Pressure Retaining Components as a Result of Repair/Replacement Activity and Use of Code Case N-795
ML16194A3262016-08-0404 August 2016
Issuance of Relief Request No. PRR-53 - Relief from ASME Code, Section XI Requirements for Ultrasonic Inspection Qualifications of Weld Overlays
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
ML16042A2912016-03-15015 March 2016
Issuance of Proposed Alternative Relief Request PRR-51, Relief from the Requirements of the ASME Code
ML16057A1772016-02-16016 February 2016
Supplement to Request for Approval of Pilgrim Relief Request (PRR)-52, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) Pressure Testing of Mechanical Joints as a Result of Performance of a Repair/Replacement Activity and Use of
ML15338A3092016-01-0505 January 2016
Relief Request PRR-50, Relief from the Requirement of the ASME Code, Implementation of Code Case N-702
CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - 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 Waster Service, Section XI, D2015-06-0505 June 2015
Entergy Submits Relief Request RR EN-15-1 - 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 Waster Service, Section XI, Division
ML15103A0692015-04-21021 April 2015
Relief Request PRR-24 Regarding Nozzle-to-Vessel Welds and Nozzle Inner Radii Examination
ML14198A1572014-08-0101 August 2014
Relief Requests PR-03 and PR-05 Regarding the Inservice Testing Program (Tac MF0370)
ML12174A1472012-07-10010 July 2012
Safety Evaluation for Relief Request PRR-21, Rev 4, to Install a Weld Overlay on RPV-n14-1 Standby Liquid Control Safe-End Nozzle Weld at Pilgrim
JAFP-11-0112, Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP2011-10-0303 October 2011
Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP
ML0923705492009-09-11011 September 2009
Relief Request (PRR)19, Install a Weld Overlay on Jet Pump Instrumentation Nozzle Weld RPV-N9A-1- Pilgrim Nuclear Power Station
ML0911304562009-04-30030 April 2009
Relief Request ISI-2008-1, Use of Later ASME Section XI Code Edition and Addenda for Repair and Replacement, Pressure Testing, and Destructive Testing Activities-Pilgrim Nuclear Power Station
CNRO-2009-00003, Letter from Entergy Response to Request for Additional Information Regarding Request ISI-2008-1 Use of Later ASME Section Xl Code Edition and Addenda for Repair and Replacement, Pressure Testing, and Non Destructive Examination Activ2009-03-17017 March 2009
Letter from Entergy Response to Request for Additional Information Regarding Request ISI-2008-1 Use of Later ASME Section Xl Code Edition and Addenda for Repair and Replacement, Pressure Testing, and Non Destructive Examination Activities
ML0813004082008-05-27027 May 2008
Relief Request No. RV-07, Alternate to the ASME OM Code 5-Year Test Interval for Main Steam Safety Relief Valves - Pilgrim Nuclear Power Station
ML0805801992008-02-14014 February 2008
Request for Approval of Relief Request No. PRR-16, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection
ML0724201612007-09-27027 September 2007
Relief for the Reactor Core Shroud Stabilizer Assemblies
ML0618701632006-06-28028 June 2006
Request for Approval of ASME Code, Section XI, Third Ten-Year Relief Request, PRR-42, Examinations of Component Welds with Less than Essentially 100% Examination Coverage
ML0606601322006-04-0505 April 2006
Relief Request No. PIL-05-R-002,
ML0602400552006-03-22022 March 2006
Relief Request No. PRR-9,
ML0601201272006-02-17017 February 2006
Relief Request No. PPR-05
ML0519902762005-08-29029 August 2005
Entergy Relief Request PR-03 High-Pressure Coolant Injection Pump
ML0519201572005-06-29029 June 2005
Fourth Ten-Year Inservice Inspection Program Plan and the Associated Relief Requests for NRC Approval
ML0429203582005-02-25025 February 2005
Request - Alternative Repair Plan for Generic Letter 88-01, Reactor Pressure Vessel Nozzle-To Cap Weld in the Control Rod Drive Return Line
ML0423100082005-01-0606 January 2005
Relief Request No. PRR-29, Relief from System Hydrostatic Test Requirements for Small Bore ASME Code Class 1 Reactor Coolant Pressure Boundary Vent, Drain and Branch Lines and Connections
ML0427406642004-10-14014 October 2004
Relief Request Nos. R-33, R-71, R 3-40(A) and R-41, James A. FitzPatrick Nuclear Power Plant, Indian Point Nuclear Generating Unit Nos. 2 and No. 3 and Pilgrim Nuclear Power Station
ML0429505512004-10-12012 October 2004
Response to NRC Request for Additional Information and Revised Relief Request, PRR-39, Rev. 1
ML0417401842004-07-0606 July 2004
Relief Request, Nos. RR-34 and PRR for the Third 10-Year Inservice Inspection (ISI) Interval, MC1999 and MC2006
ML0410700882004-07-0606 July 2004
Relief Request to Use American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Case N-600
ML0407807052004-04-30030 April 2004
Relief Request, Fourth 10-Year Inservice Testing (IST) Program and Request for Approval of IST Relief Requests
ML0408205162004-03-22022 March 2004
Relief Request Nos. RR-68, RR3-37, and PRR-34 (TAC MC1559, MC1560, & MC1561)
ML0402600132004-02-26026 February 2004
Pilgrim Relief Request Review, Relief Request No. 38, Relief from ASME Code, Section XI, Appendix Viii, Supplement 11, Qualification Requirements for Full Structural Overlaid Wrought Austenitic Piping Welds.
JPN-03-020, Indian Point Nuclear Generating Station, Units 2 & 3, Pilgrim Nuclear Power Station, Vermont Yankee Nuclear Power Station, Relief, Relief Request to Use ASME Code Case N-6002003-08-11011 August 2003
Indian Point Nuclear Generating Station, Units 2 & 3, Pilgrim Nuclear Power Station, Vermont Yankee Nuclear Power Station, Relief, Relief Request to Use ASME Code Case N-600
ML0312701492003-05-0808 May 2003
Relief Request, Relief from ASME Code, Section XI, Appendix Viii, Supplement 10, Performance Demonstration for Ultrasonic Examination Systems
ML0306402042003-04-11011 April 2003
Relief Request, Examinations of Reactor Pressure Vessel Circumferential Shell Welds
ML0224002392002-09-17017 September 2002
Relief, Code Relief Request from Section XI, the Pump and Valve Inservice Testing Program Regarding Inclusion of Additional Excess Flow Check Valves
ML0216800622002-06-0505 June 2002
Code Relief, Pilgrim Relief Request (PRR)-27 Relief from 1989 ASME Code Section XI Requirements for Certification of VT-2 Visual Examination Personnel
2018-06-08
[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
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Entergy Nuclear Operations, Inc.
En tei-g Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth. MA 02360 February 16, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Supplement to Request for Approval of Pilgrim Relief Request (PRR)-52, "Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) Pressure Testing of Mechanical Joints as a Result of Performance of a Repair/Replacement Activity and Use of Code Case N-795" Pilgrim Nuclear Power Station Docket No.: 50-293 Renewed License No.: DPR-35
REFERENCE:
Entergy Letter to NRC, Request for Approval of Pilgrim Relief Request (PRR)-
52, "Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) Pressure Testing of Mechanical Joints as a Result of Performance of a Repair/Replacement Activity and Use of Code Case N-795," dated October 21, 2015 (2.15.074)
LETTER NUMBER: 2.16.011
Dear Sir or Madam:
The referenced letter requested an alternative to specific portions of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for In-service inspection of Nuclear Power Plant Components," pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(2). This is a request for alternative on the basis that compliance with the specified requirements as described in this request would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. However, the stated basis in the first paragraph of the referenced letter was that "the proposed alternative provides an acceptable level of quality and safety" which corresponds to a request for alternative pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(1).
This letter updates the basis for the request for alternative submitted in the first paragraph of the referenced letter as follows:
Pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(2), Pilgrim Nuclear Power Station (PNPS) hereby requests an alternative to specific portions of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, "Rules for In-service Inspection of Nuclear Power Plant Components," on the basis that compliance with the specified requirements as described in this request would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
If you have questions concerning this letter, please contact me at 508-830-8323.
/iJP1/2~1
Entergy Nuclear Operations, Inc. Letter No. 2.16.011 Pilgrim Nuclear Power Station Page 2 There are no new commitments included in this letter.
Sincerely, Everett (Chip) P. Per Ins,-Jr.
Manager, Regulatory Assurance EPP/mw cc: Mr. Daniel H. Dorman Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 Ms. Booma Venkataraman, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission
- Mail Stop O-8C2A Washington, DC 20555 NRC Senior Resident Inspector Pilgrim Nuclear Power Station
Entergy Nuclear Operations, Inc.
En tei-g Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth. MA 02360 February 16, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Supplement to Request for Approval of Pilgrim Relief Request (PRR)-52, "Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) Pressure Testing of Mechanical Joints as a Result of Performance of a Repair/Replacement Activity and Use of Code Case N-795" Pilgrim Nuclear Power Station Docket No.: 50-293 Renewed License No.: DPR-35
REFERENCE:
Entergy Letter to NRC, Request for Approval of Pilgrim Relief Request (PRR)-
52, "Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) Pressure Testing of Mechanical Joints as a Result of Performance of a Repair/Replacement Activity and Use of Code Case N-795," dated October 21, 2015 (2.15.074)
LETTER NUMBER: 2.16.011
Dear Sir or Madam:
The referenced letter requested an alternative to specific portions of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for In-service inspection of Nuclear Power Plant Components," pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(2). This is a request for alternative on the basis that compliance with the specified requirements as described in this request would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. However, the stated basis in the first paragraph of the referenced letter was that "the proposed alternative provides an acceptable level of quality and safety" which corresponds to a request for alternative pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(1).
This letter updates the basis for the request for alternative submitted in the first paragraph of the referenced letter as follows:
Pursuant to 10 Code of Federal Regulations (CFR) 50.55a(z)(2), Pilgrim Nuclear Power Station (PNPS) hereby requests an alternative to specific portions of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, "Rules for In-service Inspection of Nuclear Power Plant Components," on the basis that compliance with the specified requirements as described in this request would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
If you have questions concerning this letter, please contact me at 508-830-8323.
/iJP1/2~1
Entergy Nuclear Operations, Inc. Letter No. 2.16.011 Pilgrim Nuclear Power Station Page 2 There are no new commitments included in this letter.
Sincerely, Everett (Chip) P. Per Ins,-Jr.
Manager, Regulatory Assurance EPP/mw cc: Mr. Daniel H. Dorman Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 Ms. Booma Venkataraman, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission
- Mail Stop O-8C2A Washington, DC 20555 NRC Senior Resident Inspector Pilgrim Nuclear Power Station