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MONTHYEARML0223206562002-09-0909 September 2002 Meeting Summary with Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station Proposed Safety-Relief Valve Seismic Analysis Methodology Project stage: Meeting ML0228204672002-09-27027 September 2002 Response to NRC Request for Additional Information Appendix K Measurement Uncertainty Recovery - Power Uprate Request Project stage: Response to RAI ML0226601372002-10-0202 October 2002 Withholding from Public Disclosure, General Electric Proprietary Document, NEDC-33050P, Safety Analysis Report for Pilgrim Nuclear Power Station Thermal Power Optimization, Dated July 2002 Project stage: Other ML0230401802002-10-31031 October 2002 Request for Additional Information, Appendix K Measurement Uncertainty Recovery - 1.5% Power Uprate Request Project stage: RAI ML0231002832002-11-0101 November 2002 Request for Withholding Information from Public Disclosure Pilgrim Nuclear Power Station Project stage: Withholding Request ML0232201472002-11-0606 November 2002 Response to NRC Request for Additional Information, Appendix K Measurement Uncertainty Recovery - Power Uprate Request Project stage: Response to RAI ML0231701742002-11-13013 November 2002 Request for Additional Information, Regarding Appendix K Measurement Uncertainty Recovery, Power Uprate Request Project stage: RAI ML0235400352002-12-20020 December 2002 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML0235703862002-12-23023 December 2002 RAI, Appendix K Measurement Uncertainty Recovery - Power Uprate Request Project stage: RAI ML0302204502002-12-30030 December 2002 Response to NRC Request for Additional Information Appendix K Measurement Uncertainty Recovery - Power Uprate Request Project stage: Response to RAI ML0309000992003-04-0202 April 2003 Request for Additional Information Regarding Appendix K Measurement Uncertainty Recovery - 1.5% Power Uprate Request Project stage: RAI 2002-12-20
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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
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Entergy Nuclear Operations, Inc.
Pilgnm Nuclear Power Station SEntergy 600 Rocky Hill Road Plymouth, MA 02360 Charles M. Dugger Vice President - Operations September 27, 2002 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station Docket 50-293 License No. DPR-35 Response to NRC Request for Additional Information Appendix K Measurement Uncertainty Recovery - Power Uprate Request
REFERENCE:
- 1. NRC Letter, "Request for Additional Information," dated August 30, 2002 (TAC NO. MB5603)
- 2. Entergy Letter 2.02.048, dated July 5, 2002, Appendix K Measurement Uncertainty Recovery - Power Uprate Request LETTER NUMBER: 2.02.087
Dear Sir or Madam:
Entergy has reviewed the subject NRC request for additional information (RAI) dated August 30, 2002 and the requested information is attached. This response supports approval of the license amendment request for the Appendix K Measurement Uncertainty Recovery - Power Uprate Request.
Should you have any question or comments concerning this submittal, please contact Bryan Ford at (508) 830-8403.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the Q "-' day of September 2002.
Sincerely,
("*harl,',c RA r)"n ot~"r JRH/dd 202087
Entergy Nuclear Operations, Inc. Letter Number: 2.02.087 Pilgrim Nuclear Power Station Page 2 Attachments: 1. Response to Request For Additional Information (2 - pages)
- 2. Revised FSAR Table 1.8-1 "Summary of Maximum Offsite Effects of Design Basis Accidents" (1 - page)
- 3. Revised FSAR Table 14.5-2 "Radiological Doses for Loss of Coolant And Steam Line Break Accidents Based on TID-1 4844 Assumptions (1 - page)
- 4. Figure 17-8 "Pilgrim Station Main Generator Capability Curves" (1 - page) cc: Mr. Travis Tate, Project Manager Office of Nuclear Reactor Regulation Mail Stop: 0-8B-1 U.S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockville, MD 20852 U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Pilgrim Nuclear Power Station Mr. Steve McGrail, Director Mass. Emergency Management Agency 400 Worcester Road P.O. Box 1496 Framingham, MA 01702 Mr. Robert Hallisey Radiation Control Program Commonwealth of Massachusetts Exec Offices of Health & Human Services 174 Portland Street Boston, MA 02114 202087
ATTACHMENT 1 Response to NRC Request For Additional Information Appendix K Measurement Uncertainty Recovery- Power Uprate Request NRC Request: Section 9.2 of Attachment 2 to the licensing amendment application dated July 5, 2002, addresses Design Basis Accidents (DBA). The submittal states that radiological consequences due to postulated DBAs have been calculated using a source term of 102% of the current licensed reactor thermal power. However, the staff finds that the analyses addressed in the Updated Final Safety Analysis Report (UFSAR) appears to indicate that the radiological consequences may have been determined at the current rated thermal power. Please provide discussion on the analyses/evaluation addressed in Section 9.2, identifying changes, if any, to the assumptions, methodologies, and accidents analyzed from those documented in the UFSAR. Please provide the results and acceptance criteria of the analyses referenced in Section 9.2.
Response
The radiological consequences for the control rod drop accident (CRDA) and the fuel handling accident (FHA) were previously evaluated at 102% of the current licensed thermal power (CLTP) 1998 MWt. The results are contained in the current PNPS FSAR.
In support of the PNPS thermal power uprate program, calculations for the loss-of coolant accident (LOCA) and the main steam line break (MSLB) accident were updated.
These calculations were performed at 102% CLTP using current NRC guidance information. The calculations updated the evaluation models to be consistent with the current regulatory guidance and to include a power uncertainty factor of 2%. For radiological dose considerations, releases now consider main steam isolation valve leakage and emergency core cooling system leakage in' addition to the drywell leakage.
Also, the atmospheric relative concentration values were based on Regulatory Guide 1.145 models. The resuits of these calculations were below regulatory limits and are provided in Attachments 2 and 3, FSAR tables (Table 1.8-1 and Table 14.5-2). FSAR change requests associated with these tables have been approved and will be included in the next FSAR update.
- 2. NRC Request: Provide details about the grid stability analysis including assumptions and results and conclusions for the power uprate condition.
Response
The grid stability analysis is in progress with > 50 grid system fault scenarios (contingencies) being evaluated at various system loading conditions. These scenarios consist of both normal and extreme contingencies involving different types of electrical faults of increasing severity. These contingencies are-selected based on their system interaction with"Pilgrim Station. Preliminary results indicate that four scenarios result in instability due to the Pilgrim Station power uprate. These four scenarios are all associated with the failure of a breaker at the West Walpole substation to open fast enough to clear an electrical fault. The preliminary recommended fix for this condition is replacement of a stuck breaker lockout relay at the West Walpole substation with a relay that operates more quickly. The final approved results of this analysis (from ISO New England) are expected to be provided to Pilgrim Station by October 2002.
Following Pilgrim Station review, the results will be submitted as stated in Reference 1.
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- 3. NRC Request: Also, provide in detail (including the ratings) the effect of the power uprate on the following equipment:
Response
- a. Main generator The main generator rating remains at 780 MVA. However, with the increased turbine capability, the main generator can be operated at a higher power factor at 780 MVA. This results in an increased MWe output from approximately 694MWe at a 0.89 power factor to an approximate maximum 733 MWe at 0.94 power factor.
The main generator capability curves are provided in Attachment 4 to illustrate this.
- b. Isophase bus The isophase bus rating remains at 20kA for the main section and 850A for the branch section. The power uprate does not change the current in the main section as it remains at 18.764kA for 780MVA at a rated 24,000 volts. Per the main generator vendor manual, the generator may operate at + 5% voltage. Therefore the maximum isophase bus current due to low voltage remains at 19.752kA for 780MVA @ 22,800 volts. The branch section current would increase from approximately 686A to 698A @ 24,000 volts (721A to 734A @22,800 volts) due to the slight increase in non-i E loads on the unit auxiliary transformer.
- c. Main power transformer The main power transformer rating remains at 880 MVA. The maximum load on the main power transformer does not change and remains at 780 MVA if operating at 100% power with the station electrical loads being supplied from the startup transformer. When using the unit auxiliary transformer, the uprate (including the secondary side improvements being implemented) results in an increase from 669MWe (752 MVA @ 0.89 pf.) to 707 MWe (751 MVA @ 0.94 pf.).
- d. Startup transformer The rating of the startup transformer remains at a maximum 37.3 MVA with an increased load from 28.5 to 29 MVA at 100% power.
- e. Unit auxiliary transformer The rating of the unit auxiliary transformer remains at a maximum 37.3 MVA with an increased load from 28.5 to 29 MVA at 100% power.
- f. Non-Class 1E loads increased The increase in Non-Class 1 E loads due to the Pilgrim Station power uprate is negligible but is conservatively estimated at less than 0.5MWe. (See startup and unit auxiliary transformer increases - d & e above). The Class 1E loads do not change.
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