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Category:Letter type:L
MONTHYEARL-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 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 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 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-21-118, Changes to Signature Authority & Addressee for Holtec Decommissioning International, LLC Correspondence Re to Oyster Creek Nuclear Generating Station, Pilgrim Nuclear Power Station, Indian Point Nuclear Generating Units 1, 2, 3, & Palisades2021-11-0909 November 2021 Changes to Signature Authority & Addressee for Holtec Decommissioning International, LLC Correspondence Re to Oyster Creek Nuclear Generating Station, Pilgrim Nuclear Power Station, Indian Point Nuclear Generating Units 1, 2, 3, & Palisades L-2018-064, Submittal of Joint Composite Adversary Force2018-03-0808 March 2018 Submittal of Joint Composite Adversary Force L-HU-07-011, Plants, Decommissioning Funding Status Reports2007-03-30030 March 2007 Plants, Decommissioning Funding Status Reports L-HU-07-004, Withdrawal of Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates for Palisades Nuclear Plant2007-02-0707 February 2007 Withdrawal of Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates for Palisades Nuclear Plant L-HU-07-003, Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds2007-01-30030 January 2007 Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds L-HU-06-036, Response to Request for Additional Information for Palisades Supplement to Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates for the Palisades Nuclear Plant2006-10-10010 October 2006 Response to Request for Additional Information for Palisades Supplement to Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates for the Palisades Nuclear Plant L-HU-06-028, Units 1 and 2, Revision to Correspondence Service Lists for Nuclear Management Company, LLC2006-07-21021 July 2006 Units 1 and 2, Revision to Correspondence Service Lists for Nuclear Management Company, LLC L-HU-06-030, Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power.2006-07-21021 July 2006 Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power. L-HU-06-025, Response to Generic Letter 2006-03: Potentially Nonconforming Hemyc and MT Fire Barrier Configurations2006-06-0808 June 2006 Response to Generic Letter 2006-03: Potentially Nonconforming Hemyc and MT Fire Barrier Configurations L-HU-06-013, Decommissioning Funding Status Report2006-03-22022 March 2006 Decommissioning Funding Status Report L-HU-06-012, Revision of and Supplement to Letter of Intent to Transition to 10 CFR 50.48(c) - National Fire Protection Association Standard NFPA 805, Performance-based Standards for Fire Protection for Light Water Reactor Electric Generating Plants,2006-03-14014 March 2006 Revision of and Supplement to Letter of Intent to Transition to 10 CFR 50.48(c) - National Fire Protection Association Standard NFPA 805, Performance-based Standards for Fire Protection for Light Water Reactor Electric Generating Plants, 20 L-HU-06-006, Nuclear Management Company 30-Day Response to Generic Letter 2006-01, Steam Generator Tube Integrity and Associated Technical Specifications.2006-02-17017 February 2006 Nuclear Management Company 30-Day Response to Generic Letter 2006-01, Steam Generator Tube Integrity and Associated Technical Specifications. L-HU-06-001, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity2006-02-16016 February 2006 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity L-HU-05-023, Letter of Intent to Transition to 10 CFR 50.48(c) - National Fire Protection Association Standard NFPA 805, Performance-based Standards for Fire Protection for Light Water Reactor Electric Generating Plants. 2001 Edition2005-11-30030 November 2005 Letter of Intent to Transition to 10 CFR 50.48(c) - National Fire Protection Association Standard NFPA 805, Performance-based Standards for Fire Protection for Light Water Reactor Electric Generating Plants. 2001 Edition L-HU-05-019, Response to Regulatory Information Summary 2005-19, Preparation and Scheduling of Operator Licensing Examinations2005-09-29029 September 2005 Response to Regulatory Information Summary 2005-19, Preparation and Scheduling of Operator Licensing Examinations L-HU-05-017, Notification of Intent to Apply the Nuclear Management Company (NMC) Quality Assurance Topical Report, NMC-1, to Independent Spent Fuel Storage Installation (Isfsi), Spent Fuel Cask and Radioactive Waste Shipment Activities at NMC Operat2005-09-13013 September 2005 Notification of Intent to Apply the Nuclear Management Company (NMC) Quality Assurance Topical Report, NMC-1, to Independent Spent Fuel Storage Installation (Isfsi), Spent Fuel Cask and Radioactive Waste Shipment Activities at NMC Operated L-HU-05-011, Request for Approval of a Change to the Nuclear Management Company Quality Assurance Topical Report, NMC-12005-06-17017 June 2005 Request for Approval of a Change to the Nuclear Management Company Quality Assurance Topical Report, NMC-1 L-HU-05-008, Decommissioning Funding Status Reports2005-03-31031 March 2005 Decommissioning Funding Status Reports L-HU-05-004, Nuclear Management Company 90-Day Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors.2005-03-0707 March 2005 Nuclear Management Company 90-Day Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors. L-HU-04-047, Nuclear Management Company, LLC, Use of Encryption Software for Electronic Transmission of Safeguards Information2004-12-21021 December 2004 Nuclear Management Company, LLC, Use of Encryption Software for Electronic Transmission of Safeguards Information L-HU-04-045, Supplement 2 to Request for Approval of Nuclear Management Company Quality Assurance Topical Report2004-12-0303 December 2004 Supplement 2 to Request for Approval of Nuclear Management Company Quality Assurance Topical Report L-HU-04-043, to Request for Approval of Nuclear Management Company Quality Assurance Topical Report2004-11-0808 November 2004 to Request for Approval of Nuclear Management Company Quality Assurance Topical Report L-HU-04-033, Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Using the Consolidated Line Item Improvement Process2004-10-0505 October 2004 Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Using the Consolidated Line Item Improvement Process L-HU-04-041, Comments on Proposed Generic Communication; Draft Revision to NRC Inspection Manual Chapter 9900, Technical Guidance, Operability Determination and Resolution of Nonconformances of Structures, Systems, and Components, (Regulatory Issue S2004-10-0101 October 2004 Comments on Proposed Generic Communication; Draft Revision to NRC Inspection Manual Chapter 9900, Technical Guidance, Operability Determination and Resolution of Nonconformances of Structures, Systems, and Components, (Regulatory Issue Summ L-HU-04-040, Nuclear Management Company, LLC, Implementation Status of Independent Spent Fuel Storage Installation Interim Compensatory Measures2004-09-24024 September 2004 Nuclear Management Company, LLC, Implementation Status of Independent Spent Fuel Storage Installation Interim Compensatory Measures L-HU-04-039, Nuclear Management Company, Llc., Response to Request for Additional Information Request for Approval of Nuclear Management Company Quality Assurance Topical Report, Dated August 18, 20042004-09-22022 September 2004 Nuclear Management Company, Llc., Response to Request for Additional Information Request for Approval of Nuclear Management Company Quality Assurance Topical Report, Dated August 18, 2004 L-HU-04-036, Response to Order for Implementation of Additional Security Measures Associated with Access Authorization Dated August 18. 20042004-08-25025 August 2004 Response to Order for Implementation of Additional Security Measures Associated with Access Authorization Dated August 18. 2004 L-HU-04-035, Responses to Requests for Additional Information Regarding Security Plan, Training & Qualification Plans, and Safeguards Contingency Plans2004-08-25025 August 2004 Responses to Requests for Additional Information Regarding Security Plan, Training & Qualification Plans, and Safeguards Contingency Plans L-HU-04-034, Nuclear Management Co, LLC (Nmc), Responses to Requests for Additional Information2004-08-13013 August 2004 Nuclear Management Co, LLC (Nmc), Responses to Requests for Additional Information L-HU-04-031, Nuclear Management Company - Responses to Requests for Additional Information2004-07-29029 July 2004 Nuclear Management Company - Responses to Requests for Additional Information L-HU-04-027, Nuclear Management Co., LLC, 10 CFR 50.55a Request GR-04-01; Request for Authorization to Utilize Code Case N-661,Alternative Requirements for Wall Thickness Restoration of Classes 2 and 3 Carbon Steel Piping for Raw Water Service Sectio2004-07-28028 July 2004 Nuclear Management Co., LLC, 10 CFR 50.55a Request GR-04-01; Request for Authorization to Utilize Code Case N-661,Alternative Requirements for Wall Thickness Restoration of Classes 2 and 3 Carbon Steel Piping for Raw Water Service Section X L-HU-04-030, Response to NRC Staff Request for Additional Information Request for Approval of Nuclear Management Company Quality Assurance Topical Report, Dated June 20, 20042004-07-23023 July 2004 Response to NRC Staff Request for Additional Information Request for Approval of Nuclear Management Company Quality Assurance Topical Report, Dated June 20, 2004 L-01-002, NRC Bulletin 2001-01: Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles - Updated Response2002-10-22022 October 2002 NRC Bulletin 2001-01: Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles - Updated Response 2023-04-24
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r Committed to NuclearExcelence. Operated by NuclearPalisades Nuclear Management Plant Company, LLC October 22, 2002 U.S. Nuclear Regulatory Commission 10 CFR 50.54(f)
ATTN: Document Control Desk Washington, DC 20555-0001 DOCKET 50-255 - LICENSE DPR PALISADES NUCLEAR PLANT NRC BULLETIN 2001-01: CIRCUMFERENTIAL CRACKING OF REACTOR PRESSURE VESSEL HEAD PENETRATION NOZZLES - UPDATED RESPONSE On March 29, 2002, Nuclear Management Company (NMC), LLC provided an updated response to the Nuclear Regulatory Commission (NRC) Bulletin (BL) 2001-01, "Circumferential Cracking of Reactor Vessel Head Penetration Nozzles." On August 9, 2002, the NRC transmitted BL 2002-02, "Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs." While preparing the response to BL 2002-02, an error was discovered in the updated response to BL 2001-01.
A calculation of the effective degradation years (EDY) value was performed as part of the response to BL 2002-02. While developing the EDY calculation, NMC discovered that the equivalent effective full power years (EFPY) value of 22.5 previously reported in the updated response to BL 2001-01 was incorrect. The correct EFPY value is 23.9 years of additional operation from March 1, 2001, until reaching the same time at temperature that the Oconee Nuclear Station Unit 3 had at the time that its leaking nozzles were discovered in February 2001. There is no re-categorizing of susceptibility groups with this change.
Palisades remains in the five to thirty year susceptibility group.
NMC is providing an updated response to items l.a and the reference section. The attachments to the original response remain unchanged and are not included.
SUMMARY
OF COMMITMENTS This letter contains no new commitments and no revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and accurate. Executed on Octo er 22, 2002.
Doug sE. Coper Site Vice-President, Palisades CC Regional Administrator, USNRC, Region III Project Manager, USNRC, NRR A)*
EnclosureNRC Resident Inspector - Palisades * *~
27780 Blue Star Memorial Highway 0 Covert, Ml 49043 Telephone: 616.764.2000
ENCLOSURE NUCLEAR MANAGEMENT COMPANY, LLC PALISADES NUCLEAR PLANT DOCKET 50-255 OCTOBER 22,2002 NRC BULLETIN 2001-01: PALISADES PLANT UPDATED RESPONSE Three Pages Follow
NRC BULLETIN 2001-01: CIRCUMFERENTIAL CRACKING OF REACTOR VESSEL HEAD PENETRATION NOZZLES PALISADES PLANT UPDATED RESPONSE
- 1. Requested Background and Descriptive Information
- a. Plant Specific PWSCC Susceptibility Ranking primary Palisades Nuclear Plant was originally ranked for the potential for vessel water stress corrosion cracking (PWSCC) of the reactor pressure model and plant (RPV) top head nozzles using the time-at-temperature specific input data reported in MRP-48 [1]. Nuclear Management Company in 2002.
(NMC), LLC re-evaluated the Palisades reactor head temperature the five to The re-evaluation results in Palisades being re-categorized into (EFPYs) of thirty year susceptibility group, with 23.9 effective full power years the same time at additional operation from March 1, 2001, until reaching time that temperature that Oconee Nuclear Station Unit 3 (ONS3) had at the its leaking nozzles were discovered in February 2001 [2].
Using the criteria stated in Nuclear Regulatory Commission (NRC) Bulletin 2001-01, Palisades Nuclear Plant falls into the NRC category of plants top head considered to have a moderate susceptibility to PWSCC of the RPV nozzles.
- b. Description of Vessel Head Penetration (VHP) Nozzles CRDM Palisades Nuclear Plant has 54 total RPV head nozzles including 45 The vent nozzles, 8 incore instrument (ICI) nozzles, and one vent nozzle.
nozzle is located near the center of the reactor head, at a center-to-center and vent distance of 11.98 inches from the nearest CRDM. The CRDM, ICI nozzles are made of SB-1 67 Alloy 600. Additional requested nozzle information is provided in Table 2-3 of MRP-48 [1].
- c. Description of Reactor Pressure Vessel (RPV) Head Insulation As reported in Table 2-1 of MRP-48 [1], Palisades Nuclear Plant has blanket contoured RPV head insulation.
Two layers of blanket insulation strips rest upon the reactor head at right angles to each other, beneath a stainless steel cover assembly. The hinged, latched covers are removable. The blankets can be removed and re area installed or replaced. An attached photograph depicts the reactor head with some covers removed. (Attachment 1)
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NRC BULLETIN 2001-01: CIRCUMFERENTIAL CRACKING OF REACTOR VESSEL HEAD PENETRATION NOZZLES PALISADES PLANT UPDATED RESPONSE Years
- d. Description of RPV Head and Nozzle Inspections Within Past Four As reported in Table 2-1 of MRP-48 [1], Palisades Nuclear Plant has the performed visual inspections of the reactor top head area for leaks per current Generic Letter 88-05 leakage detection program, but no additional four RPV head and nozzle inspections have been conducted within the past years (as of August 31, 2001).
of the
- e. Description of the Configuration of Equipment and Cables on Top Reactor Pressure Vessel Head A description of the configuration of equipment and cables on the vessel head is attached to this response. (Attachment 2)
- 2. Previously Experienced Leakage From or Cracking in VHP Nozzles nozzles.
Palisades Nuclear Plant has not experienced leakage or cracking in VHP No further response to this question is required.
of ONS3
- 3. Plans for Future Inspections - If Susceptibility Ranking Is Within 5 EFPY of ONS3.
The susceptibility ranking for Palisades Nuclear Plant is not within 5 EFPY No further response to this question is required.
5 EFPY and
- 4. Plans for Future Inspections - If Susceptibility Ranking Is Greater Than Less Than 30 EFPY of ONS3 upper NMC will perform a 100% effective visual examination of the reactor head be to metal surface during the next refueling outage. Qualification requirements will Pressure the 1989 Edition of American Society of Mechanical Engineers Boiler and leakage from the Vessel Code,Section XI. The acceptance criterion will be zero reactor head and penetration nozzles.
in The bases for concluding that regulatory requirements are met are discussed MRP-48 [1].
If leakage is detected, it will be investigated and repaired as needed, in accordance with the current NMC repair/replacement program at Palisades including applicable and codes and standards. Any indication of leakage or cracks will be evaluated characterized using a combination of surface and/or volumetric examinations.
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NRC BULLETIN 2001-01: CIRCUMFERENTIAL CRACKING OF REACTOR VESSEL HEAD PENETRATION NOZZLES PALISADES PLANT UPDATED RESPONSE
- 5. Reporting of Future Inspection Results Palisades Nuclear Plant will provide the information requested in Item 5 of NRC Bulletin 2001-01, or indicate that no leakage was identified, within 30 days after plant restart following the next refueling outage.
During the next refueling outage, NMC will perform a 100% effective visual examination of the Palisades reactor vessel head upper metal surface in accordance with BL 2001-01.
References
- 1. PWR MaterialsReliability ProgramResponse to NRC Bulletin 2001-01 (MRP-48), EPRI, Palo Alto, CA: 2001. TP-1006284.
- 2. EA-C-PAL-01 -03348-01, Rev. 2, "Upper Head Fluid Temperature for Palisades Reactor (Westinghouse Calculation CN-WFE-02-5, Rev.0)"
Attachments Attachment 1, Photograph of Palisades Reactor Vessel Head Insulation Attachment 2, Configuration of Equipment and Cables on the RPV Head Page 3