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MONTHYEARML1025101382010-03-31031 March 2010 0000-0105-0835-R2 Pilg-SRVs-T506-ATWS Hipres RPT-Calc-2010, Revision Number: 2, Instrument Limits Calculation Entergy Operations Inc. Pilgrim Nuclear Power Station ATWS High Pressure Recirculation Pump Trip (Rpt), Enclosure 3 to Attachment Project stage: Other ML1019600252010-07-21021 July 2010 Request for Additional Information to Support the Review of Setpoint and Setpoint Tolerance Increases for Safety Relief Valves and Spring Safety Valves Project stage: RAI ML1025101372010-08-30030 August 2010 Response to NRC Request for Additional Information Dated June 3, 2010, in Support of Proposed License Amendment for Pilgrim Setpoint and Setpoint Tolerance Increases for Safety Relief Valves (SRV) and Spring Safe Project stage: Response to RAI ML1027400692010-09-21021 September 2010 Entergy Response to NRC Request for Additional Information Dated July 21, 2010, in Support of Proposed License Amendment for Pilgrim Setpoint & Setpoint Tolerance Increases for Safety Relief Valves (SRV) & Spring Safety Valves (Ssv), and Re Project stage: Response to RAI ML1100900272011-01-10010 January 2011 Request for Additional Information Revision to TS for Setpoint and Setpoint Tolerance Increase for Safety Relief Valves and Spring Safety Valves, and Related Changes (ME3543) Project stage: RAI ML1104203052011-01-31031 January 2011 Entergy - Response to NRC Request for Additional Information Dated January 10, 2011, to Support the Review of Setpoint and Setpoint Tolerance Increases for Safety Relief Valves (SRV) and Spring Safety Valves (SSV) Project stage: Response to RAI ML1106103972011-02-18018 February 2011 Marked-up and Re-typed Technical Specification and Bases Pages for the Proposed License Amendment Related to Setpoint and Setpoint Tolerance Increases for Safety Relief Valves (SRV) and Spring Safety Valves (Ssv). Project stage: Other 2010-09-21
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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:Request for Additional Information (RAI)
MONTHYEARML21223A2422021-08-16016 August 2021 Enclosure - Pilgrim Nuclear Power Station - Request for Additional Information Regarding Pilgrim - License Amendment Request Independent Spent Fuel Storage Installation Only Emergency Plan ML21161A1072021-07-0909 July 2021 Request for Additional Information Regarding Pilgrim License Amendment Request ISFSI Only Emergency Plan ML21013A5232021-01-15015 January 2021 Request for Additional Information Regarding the Request to Change the Physical Security Plan - Alternative Measures ML20297A2382020-10-22022 October 2020 Fleet DQAP RAIs - Enclosure ML20297A2372020-10-22022 October 2020 Request for Additional Information - HDI Fleet Decommissioning Quality Assurance Program ML20142A2422020-05-26026 May 2020 Acceptance of Requested Licensing Action Physical Security Plan Revision and License Amendment Request to Incorporate Additional Independent Spent Fuel Storage Installation with Requests for Additional Information ML20280A1912020-04-17017 April 2020 Request for Additional Information- Clarifying Information for Pilgrim ISFSI Physical Security Amendment Application ML19207B3662019-07-26026 July 2019 NRR E-mail Capture - Pilgrim - RAI Direct and Indirect Transfer of Lic.; Conforming Lic. Amend.; Req. for Exemption 10 CFR 50.82(A)(8)(I)(A) for Holtec Decom. 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S. Ford RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for ISFSI Docket Nos.: 72-43, 72-51, 72-1044, 72-07, 72-12, and 72-59) ML18005A5422018-01-0505 January 2018 NRR E-mail Capture - Second Round of RAI for DAEC Fifth Inservice Inspection Interval Program Plan, Relief Request RR-03 - EPID: L-2017-LLR-0110 ML16347A0042016-12-0909 December 2016 NRR E-mail Capture - Pilgrim: Request for Additional Information for Relief Requests on Volumetric Exam Requirements, PNPS-ISI-001, 002 and 003 ML16013A0642016-01-13013 January 2016 NRR E-mail Capture - Request for Additional Information Entergy CNRO-2015-00023 - Revision to Entergy Quality Assurance Program Manual (Fleet Submittal CAC Nos. MF7086-MF7097) ML15341A1662015-12-0707 December 2015 NRR E-mail Capture - Entergy Fleet RR-EN-15-1, Request for Additional Information (CACs MF6341-MF6349) ML15211A6612015-07-30030 July 2015 Licensed Operator Positive Fitness-For-Duty-Test ML15051A0322015-02-25025 February 2015 Request for Additional Information Regarding the Safety Limit Minimum Critical Power Ratio License Amendment Request ML14342A0942014-12-17017 December 2014 Request for Additional Information Regarding Relief Request PRR-24, Nozzle-to-Vessel Welds and Nozzle Inner Radii Examinations ML14042A0432014-02-18018 February 2014 Request for Additional Information Regarding Safety Limits to Resolve Pressure Regulator Fail-Open Transient License Amendment Request ML13333A9102013-12-0505 December 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool ins ML13323B4702013-11-25025 November 2013 Request for Additional Information Regarding Relief Request PRR-22 ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13179A4622013-07-0505 July 2013 Entergy Nuclear Operations, Inc., Decommissioning Funding Status Report Request for Additional Information Regarding the Decommissioning Funding Status Report ML13182A4252013-07-0101 July 2013 Request for Additional Information E-mail from R.Guzman to W.Lobo PR-03 and PR-05 Fifth Ten-Year Inservice Testing (IST) Program ML13165A2762013-06-20020 June 2013 Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (NRC Order EA-12-051) ML12278A3862012-10-0404 October 2012 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2, and 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford, Request for Additional Information, Round 2, Amendment Request to Revise QA Program Manual and Staff Qualification TSs ML1209604492012-04-0505 April 2012 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Request for Additional Information, Revise Quality Assurance Program Manual and Staff Qualification Technical Specificat ML1208601472012-03-26026 March 2012 Request for Additional Information - Pilgrim Nuclear Power Station Revision to Condensate Storage Tank Low Level Trip Setpoint ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML12056A0502012-03-12012 March 2012 Enclosure 4 - Recommendation 2.3: Flooding ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic ML12056A0472012-03-12012 March 2012 Enclosure 1 - Recommendation 2.1: Seismic ML1132502282011-11-22022 November 2011 Request for Additional Information, Relief Request No. PRR-21 ML1132202342011-11-21021 November 2011 Request for Additional Information 60-Day Response to Bulletin 2011-01, Mitigating Strategies, ML1114402342011-05-25025 May 2011 Request for Additional Information to Support the Review of 2011 Decommissioning Funding Status Report ML1108202082011-04-11011 April 2011 Summary of Telephone Conference Call Held on March 23, 2011, Between the USNRC and Entergy Nuclear Operations, Inc., Concerning the Pilgrim Nuclear Power Station License Renewal Application ML1106101872011-03-0303 March 2011 Request for Additional Information to Support the Review of Pilgrim Nuclear Power Station Cyber Security Plan (Id: 2.10.034) ML1105403302011-02-15015 February 2011 Response to Request for Additional Information (Rai), Dated January 5, 2011 on the Cyber Security Plan ML1100900272011-01-10010 January 2011 Request for Additional Information Revision to TS for Setpoint and Setpoint Tolerance Increase for Safety Relief Valves and Spring Safety Valves, and Related Changes (ME3543) ML1034105062011-01-0707 January 2011 December 1, 2010, Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning the Pilgrim Nuclear Power Station License Renewal Application 2021-08-16
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 21, 2010 Site Vice President Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION TO SUPPORT THE REVIEW OF SETPOINT AND SETPOINT TOLERANCE INCREASES FOR SAFETY RELIEF VALVES AND SPRING SAFETY VALVES (TAC NO. ME3543)
Dear Sir or Madam:
By letter dated March 15, 2010, Entergy Nuclear Operations, Inc., the licensee for Pilgrim Nuclear Power Station, submitted a license amendment request to revise its Technical Specifications to modify the setpoint and setpoint tolerances for Safety Relief Valves (SRVs) and Spring Safety Valves (SSVs) and changes related to the replacement of (i) four (4) Target Rock Two-Stage SRVs with Three-Stage SRVs, and (ii) two existing Dresser 3.749 inch-throat diameter SSVs with Dresser 4.956 inch-throat diameter SSVs.
The Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). A response to this RAI is requested to be provided within 30 days.
Sincerely,
,
~~
James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING REVISION TO TECHNICAL SPECIFICATION FOR SETPOINT AND SETPOINT TOLERANCE INCREASES FOR SAFETY RELIEF VALVES (SRVs) AND SPRING SAFETY VALVES (SSVs), AND RELATED CHANGES PILGRIM NUCLEAR POWER STATION The NRC staff requests that the licensee provide the following additional information concerning this request:
- 1. In Item NO.3 in Table 1: "Proposed TS Changes," of Attachment 1 to the submittal, it was stated that Tailpipe Temperature Indication from Technical Specification (TS) Table 3.2.F and asterisk in Note (5) will be removed, and Note (6) will be revised and relocated to updated final safety analysis report (UFSAR). The staff understands that the limiting conditions for operation (LCOs) for the instrumentation that monitors tail pipe temperature are given in Table 3.2-F. It provides the requirements for number of operable thermocouples (TC) for SRV tail pipe temperature indication. In addition, Note (6) requires that if a TC becomes inoperable, it shall be returned to an operable condition within 31 days, or the reactor shall be placed in a shutdown mode within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Please provide the following additional information:
a) Provide the language that will be added to the UFSAR.
b) Will all of the requirements that currently exist in the TS be maintained after the proposed relocation to the UFSAR? If not, then justify why the requirement is no longer necessary.
c) After removal of Tailpipe Temperature Indication from TS Table 3.2.F and asterisk in Note (5), and relocation of Note (6) to UFSAR, explain how the requirements for tailpipe temperature indication, as currently exist in the TS, will be implemented.
d) As a follow-up to part (c), the staff believes that LCOs for instrumentation must be located in the TS for appropriate regulatory control. Provide justification if you disagree.
e) Are the proposed changes consistent with the Standard Technical Specification (STS)? If so, provide the relevant section numbers of the STS so that the staff can verify.
- 2. In the second paragraph on page 5 of Attachment 1 to the submittal, it was stated that the existing TS surveillance for the Two-Stage Target Rock SRVs for tailpipe temperature monitoring, as specified in TS 3.6.0.3, 4, and 5, is not required and will be revised and relocated into the UFSAR. The staff understands that the objective of Enclosure
-2 these Surveillance Requirements were to detect the leaking SRVs and to make corrective actions, if necessary, according to the LCO. Please provide the following additional information:
a) Provide the language that will be added to the UFSAR.
b) Describe how a potential leak during normal operation in a Three-Stage Target Rock SRV is detected, the corrective actions taken for leaking SRVs, and the LCO. As stated earlier, the staff believes that an LCO should be in the TS, and not in the UFSAR. Justify.
c) Are the proposed changes consistent with the STS? If so, provide the relevant STS section numbers for the staff to verify.
- 3. Results of plant-specific overpressure event for Pilgrim shown in Table 2-2 of the GEH Report, NEDC-33532P, "Pilgrim Nuclear Power Station Safety Valve Setpoint Increase,"
Rev. 0, March 2010, defines several types of pressure. The staff understands that the "Peak Dome Pressure" is the computer code (ODYN) calculated peak pressure at the vessel dome during the event; and the "Peak Vessel Pressure" is the peak pressure at the bottom of the vessel which is higher than the dome pressure by approximately an amount equal to the weight of fluid inside the vessel. The "Vessel Pressure Limit" is the American Society of Mechanical Engineers overpressure limit of 1375 psig [110% X 1250 psig (vessel design pressure)]. Please provide the following additional information:
a) Confirm if the staff's understanding, as described above, is accurate. If not, clarify.
b) Define the "Dome Pressure Safety Limit." Explain how the parameter is used in the safety analyses, methodology to calculate it, and name of the computer code used.
Also, justify the technical basis to arbitrarily increase its value from 1325 psig [106%
of design pressure] to 1340 psig [107.2% of design pressure] in order to cover future cycle-to-cycle variation in cycle-specific calculations, and why it should be acceptable.
- 4. On page 8 of the submittal, it was stated, "All valves reviewed to date were successfully screened with the exception of the reactor core isolation coolant (RCIC) Pump Injection Valve (M01301-49). This motor-operated valve (MOV) does not demonstrate sufficient margin based on a review of the weak link and torque/thrust analyses. PNPS will modify valve components or replace MOVs as a part of the SRV/SSV modification package to assure that sufficient margin exists prior to implementing the full modification package."
Please provide a more specific plan to implement your modification of MOVs.
- 5. Although the NRC staff has previously reviewed and approved NEDC-31753P, the staff notes that the topical report is based on General Electric (GE) fuel core designs. If Pilgrim core is designed with mixed fuel types and/or includes non-GE fuel design, then demonstrate that the NEDC-31753P evaluation is applicable to the Pilgrim core design.
- 6. Is debris generated as a result of the safety valve discharge into the drywell? If so, please describe how this is taken into account in the analysis of the Anticipated Transient Without Scram event, especially the effect of the debris on available net positive suction head of the Residual Heat Removal System.
July 21,2010 Site Vice President Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508 SUB~IECT: REQUEST FOR ADDITIONAL INFORMATION TO SUPPORT THE REVIEW OF SETPOINT AND SETPOINT TOLERANCE INCREASES FOR SAFETY RELIEF VALVES AND SPRING SAFETY VALVES (TAC NO. ME3543)
Dear Sir or Madam:
By letter dated March 15, 2010, Entergy Nuclear Operations, Inc., the licensee for Pilgrim Nuclear Power Station, submitted a license amendment request to revise its Technical Specifications to modify the setpoint and setpoint tolerances for Safety Relief Valves (SRVs) and Spring Safety Valves (SSVs) and changes related to the replacement of (i) four (4) Target Rock Two-Stage SRVs with Three-Stage SRVs, and (ii) two existing Dresser 3.749 inch-throat diameter SSVs with Dresser 4.956 inch-throat diameter SSVs.
The Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). A response to this RAI is requested to be provided within 30 days.
Sincerely, Ira!
James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
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