Letter Sequence Response to RAI |
|---|
|
|
MONTHYEARNG-08-0135, Request for NRC Approval of Alternative to Nozzle to Vessel Weld and Inner Radius Examinations2008-02-28028 February 2008
Request for NRC Approval of Alternative to Nozzle to Vessel Weld and Inner Radius Examinations
Project stage: Request
L-08-111, Inservice Inspection Program Relief Request IR-0542008-03-31031 March 2008
Inservice Inspection Program Relief Request IR-054
Project stage: Request
ML0819806282008-07-31031 July 2008
Request for Additional Information, Inservice Inspection Relief Request IR-054
Project stage: RAI
ML0820400462008-08-29029 August 2008
Safety Evaluation for Request for Alternative to Reactor Pressure Vessel Nozzle to Vessel Weld and Inner Radius Examinations Tac MD8193)
Project stage: Approval
L-08-270, Response to Request for Additional Information Regarding Relief Request IR-054, Revision 02008-09-17017 September 2008
Response to Request for Additional Information Regarding Relief Request IR-054, Revision 0
Project stage: Response to RAI
ML0831104542008-11-0606 November 2008
E-Mail Acceptance Review for Columbia Relief Request
Project stage: Acceptance Review
ML0831108332008-11-14014 November 2008
Request for Additional Information Related to Request for Relief 3ISI-09
Project stage: RAI
RS-08-156, Proposed Alternative to 10CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections2008-12-0303 December 2008
Proposed Alternative to 10CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections
Project stage: Request
ML0829607292008-12-29029 December 2008
Request for Relief Related to Inservice Inspection Relief Request IR-054
Project stage: Other
ML0902700232009-01-27027 January 2009
Acceptance Review of Proposed Alternative 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections
Project stage: Acceptance Review
RS-09-044, Request for Alternative to Nozzle-to-Vessel Weld and Inner Radius Examinations2009-03-13013 March 2009
Request for Alternative to Nozzle-to-Vessel Weld and Inner Radius Examinations
Project stage: Request
ML0923003942009-08-24024 August 2009
Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections
Project stage: Other
ML0929404362009-11-0303 November 2009
Alternative to Nozzle-to-Vessel Weld and Inner Radius Examinations
Project stage: Other
ML1003500962010-02-0101 February 2010
Alternative Examination Requirements for Pilgrim Nozzle-to-Vessel Shell and Inner Radii Welds Using ASME Code Case N-702 an BWRVIP-108
Project stage: Other
ML1020202572010-07-13013 July 2010
Entergy Response to NRC Request for Additional Information Related to Pilgrim Relief Request (PRR)-20, Alternative Examination Requirements for Pilgrim Nozzle-to-Vessel Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108
Project stage: Response to RAI
ML1022901632010-08-25025 August 2010
Relief Request PRR-20, Alternative Examination Requirements for Nozzle-To-Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108 - Pilgrim Nuclear Power Station
Project stage: Other
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
Project stage: Request
2008-09-17
[Table View] |
|
|---|
Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024
Cy 2023 Summary of Decommissioning Trust Fund Status
IR 05000293/20240022024-08-21021 August 2024
NRC Inspection Report No. 05000293/2024002
PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024
Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0
ML24151A6482024-06-0303 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)
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
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
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
2024-09-18
[Table view] |
Text
SEntergy Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 Stephen J. Bethay Director, Nuclear Safety Assurance July 13, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001
SUBJECT:
Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35
REFERENCE:
LETTER NUMBER:
Dear Sir or Madam,
Entergy Response to NRC Request for Additional Information Related to Pilgrim Relief Request (PRR)-20, Alternative Examination Requirements for Pilgrim Nozzle-to-Vessel Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108 (TAC NO. ME3290)1. Entergy Letter No. 2.10.004, Entergy Pilgrim Relief Request (PRR)-20, Alternative Examination Requirements for Pilgrim Nozzle-to-Vessel Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108dated February 1, 2010 2.10Q035 ,'This letter dockets Entergy's response to an NRC Request for Additional Information (RAI)forwarded to Pilgrim's Licensing Staff by E-mail on May 19, 2010.The Entergy response supports the Pilgrim Relief Request (PRR)-20, Alternative Examination Requirements for Pilgrim Nc~z~z e-to-Vessel Shell Welds and Nozzle Inner Radii using the requirements of American Society of Mechanical Engineers (ASME) Code Case N-702 and BWRVI P-108 provisions." ..-" .. : i. : ": .. , ... ." "- '.. : " .: .i : I. ' -." " "' : ;:,',*" :o',.: .:' ,:: '.:: '" ":-!,:; '.: , ,. ,J ." ., Vo 9-Aew?
Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station Letter Number: 2.10.035 Page 2 The proposed alternative along with the attached prior examination's results provide an acceptable level of quality and safety because it follows the requirements of ASME Code N-702 and the NRC approved technical basis (BWRVIP -108) for the alternative examination described in Pilgrim Relief Request (PRR)-20 submitted as Reference 1.There are no commitments made in this submittal.
If you have any questions, please call Mr. Joseph Lynch, Pilgrim Licensing Manager at 508-830-8403.
Sincerely, Ste eJ.ethay Director, Nuclear Safety ssurance SJB/wgl
Attachment:
Entergy Response to NRC Request for Additional Information Related to Pilgrim Relief Request PRR-20 (2 pages)cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Pilgrim Nuclear Power Station Mr. James S. Kim, Project Manager Plant Licensing Branch I-1 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North 0-8C2 11555 Rockville Pike Rockville, MD 20852 Attachment to Entergy Letter Number 2.10.035 ENTERGY RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION RELATED TO PILGRIM RELIEF REQUEST PRR-20 (2 pages)
ENTERGY RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING PILGRIM RELIEF REQUEST PRR-20
Reference:
Pilgrim PRR-20: Alternative Examination Requirements for Nozzle-to-Shell and Inner Radii Welds Using ASME Code Case N-702 and BWRVIP-108 (TAC NO. ME3290)Dated, May 19, 2010 (By E-mail)NRC Request: Please provide a synopsis of what inspections have already been performed on the components for which this alternative is requested, including all indications that were found and how these indications were dispositioned.
Enterg¥/Pilqrim Response: The following Table provides inspections that were performed on the RPV welds during refueling outages and the indications found during inspections.
('nmnnnant in1 DImr~ri ntinn Vi~rQ nf InQn~tinn It ITI Yaars of Insnection
["In RPV-NI A-NV RPV-N1 A-NIR RPV-N1 B-NV RPV-N1 B-NIR RPV-N3A -NV RPV-N3A-NIR RPV-N3B-NV RPV-N3B-NIR RPV-N3C-NV RPV-N3C-NIR RPV-N3D-NV RPV-N3D-NIR RPVN6A-NV RPV-N6A-NIR 28" Recirc Outlet Nozzle to Vessel Weld 28" Recirc Outlet Nozzle to Inner Radius 28" Recirc Outlet Nozzle to Vessel Weld 28" Recirc Outlet Nozzle to Inner Radius 20" Main Steam Nozzle to Vessel Weld 20" Main Steam Nozzle to Inner Radius 20" Main Steam Nozzle to Vessel Weld 20" Main Steam Nozzle to Inner Radius 20" Main Steam Nozzle to Vessel Weld 20" Main Steam Nozzle to Inner Radius 20" Main Steam Nozzle to Vessel Weld 20" Main Steam Nozzle to Inner Radius 12" Core Spray Nozzle to Vessel Weld 12" Core Spray Nozzle to Inner Radius 1977,1983,1999,2009 1977,1983,1999,2009 1980,1995,2005 1980,1995,2005 1974,1983,1997,2007 1974,1983,1997,2007 1981,1987,1997,2007 1987,1997, 2007 1981,1987,1997,2007 1987,1997,2007 1974,1987,1997,2007 1974,1987,1997,2007 1981,1983,1987,1997,2007 1983,1987,1997,2007 NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI Page 1 of 2 ENTERGY RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING PILGRIM RELIEF REQUEST PRR-20 RPV-N6B-NV RPV-N6B-NIR RPV-N7A-NV RPV-N7A-NIR RPV-N7B-NV RPV-N7B-NIR RPV-N8-NV RPV-N8-NIR RPV-N9A-NV RPV-N9A-NIR RPV-N9B-NV RPV-N9B-NIR OUTAGE 12" Core Spray Nozzle to Vessel Weld 12" Core Spray Nozzle to Inner Radius 9" Spare Instrumentation Nozzle to Vessel Weld 9" Spare Instrumentation Nozzle to Inner Radius 9" Spare Instrumentation Nozzle to Vessel Weld 9" Spare Instrumentation Nozzle to Inner Radius 6" Head Vent Nozzle to Vessel Weld 6" Head Vent Nozzle to Inner Radius 5" Jet Pump Instrumentation Nozzle to Vessel Weld 5" Jet Pump Instrumentation Nozzle to Inner Radius 5',' Jet Pump Instrumentation Nozzle to Vessel Weld 5" Jet Pump Instrumentation Nozzle to Inner Radius 1974,1991,2001 1974,1991, 2001 1974, 1995,2005 1974,1995, 2005 1974,1995,2005 1974,1995,2005 NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI 1993,2005 1993,2005 1987,1999,2009 1987,1999,2009 1974,1993,2003 1974,1993,2003 YEAR RFO #1 1974 RFO #2 1976 RFO #3 1977 RFO #4 1980 RFO #5 1981 RFO #6 1983 RFO #7 1987 RFO #8 1991 RFO #9 1993 RFO #10 1995 RFO #11 1997 RFO #12 1999 RFO #13 2001 RFO #14 2003 RFO #15 2005 RFO #16 2007 RFO #17 2009* NRI = NO RECORDABLE INDICATIONS Page 2 of 2