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Category:Letter type:JAFP
MONTHYEARJAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023
License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications
JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023
Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements
JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023
and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023
Emergency Plan Document Revision
JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023
Registration of Spent Fuel Cask Use
JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023
Registration of Spent Fuel Cask Use
JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023
Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis
JAFP-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023
Physical Security Plan, Revision 24
JAFP-23-0047, Correction to the 2022 Annual Radioactive Effluent Release Report2023-08-30030 August 2023
Correction to the 2022 Annual Radioactive Effluent Release Report
JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-0303 August 2023
License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis
JAFP-23-0043, 10 CFR 50.46 Annual Report2023-07-31031 July 2023
10 CFR 50.46 Annual Report
JAFP-23-0038, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2023-07-28028 July 2023
License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance
JAFP-23-0033, License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation2023-06-28028 June 2023
License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation
JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023
2022 Annual Radiological Environmental Operating Report
JAFP-23-0023, 2022 Annual Radioactive Effluent Release Report2023-04-27027 April 2023
2022 Annual Radioactive Effluent Release Report
JAFP-23-0010, 2022 REIRS Transmittal of NRC Form 52023-03-20020 March 2023
2022 REIRS Transmittal of NRC Form 5
JAFP-23-0008, Supplement to Inservice Inspection Summary Report Cycle 252023-02-22022 February 2023
Supplement to Inservice Inspection Summary Report Cycle 25
JAFP-22-0053, Inservice Inspection Summary Report Cycle 252022-12-20020 December 2022
Inservice Inspection Summary Report Cycle 25
JAFP-22-0046, Core Operating Limits Report Cycle 262022-10-17017 October 2022
Core Operating Limits Report Cycle 26
JAFP-22-0040, 10 CFR 50.46 Annual Report2022-07-29029 July 2022
10 CFR 50.46 Annual Report
JAFP-22-0033, Core Operating Limits Report Mid-Cycle 252022-06-23023 June 2022
Core Operating Limits Report Mid-Cycle 25
JAFP-22-0032, Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b..2022-06-16016 June 2022
Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b..
JAFP-22-0030, Oswego County and New York State Participation in the Emergency Plan2022-05-13013 May 2022
Oswego County and New York State Participation in the Emergency Plan
JAFP-22-0029, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022
2021 Annual Radiological Environmental Operating Report
JAFP-22-0028, 2021 Annual Radioactive Effluent Release Report2022-04-27027 April 2022
2021 Annual Radioactive Effluent Release Report
JAFP-22-0026, 2021 REIRS Transmittal of NRC Form 52022-04-0707 April 2022
2021 REIRS Transmittal of NRC Form 5
JAFP-22-2020, Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Info2022-03-0404 March 2022
Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Informed
JAFP-22-0017, Amendments to Indemnity Agreements2022-02-15015 February 2022
Amendments to Indemnity Agreements
JAFP-22-0007, Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102022-01-31031 January 2022
Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10
JAFP-22-0010, Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments2022-01-24024 January 2022
Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments
JAFP-22-0008, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary2022-01-14014 January 2022
Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary
JAFP-21-0093, Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation2021-10-18018 October 2021
Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation
JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021
Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021
Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments
JAFP-21-0083, Notification of Readiness for NRC 95001 Inspection2021-09-0909 September 2021
Notification of Readiness for NRC 95001 Inspection
JAFP-21-0081, Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-0303 September 2021
Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
JAFP-21-0075, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2021-08-12012 August 2021
Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs
JAFP-21-0073, Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance.2021-08-0909 August 2021
Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance.
JAFP-21-0069, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2021-07-30030 July 2021
Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
JAFP-21-0070, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b2021-07-30030 July 2021
License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b
JAFP-21-0071, 10 CFR 50.46 Annual Report2021-07-29029 July 2021
10 CFR 50.46 Annual Report
JAFP-21-0064, Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-07-0707 July 2021
Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting
JAFP-21-0053, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-14014 June 2021
Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement
JAFP-21-0052, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021
Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement
JAFP-21-0051, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021
Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement
JAFP-21-0050, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-12012 June 2021
Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement
JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021
Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments
JAFP-21-0042, Reply to a Notice of Violation; EA-20-1382021-06-0303 June 2021
Reply to a Notice of Violation; EA-20-138
JAFP-21-0041, Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2021-05-17017 May 2021
Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing
JAFP-21-0040, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2021-05-14014 May 2021
Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs
2023-08-31
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Text
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315-342-3840 Brian R. Sullivan Site Vice President - JAF JAFP-15-0145 December 15, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Commitment to Maintain Severe Accident Management Guidelines James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-059
Reference:
NEI letter, Industry Initiative to Maintain Severe Accident Management Guidelines, dated October 26, 2015
Dear Sir or Madam:
The Nuclear Energy Institute (NEI) Nuclear Strategic Issues Advisory Committee (NSIAC) recently approved an Industry Initiative to implement and maintain Severe Accident Management Guidelines (SAMGs) [Reference]. This letter establishes commitments related to SAMGs for James A. FitzPatrick Nuclear Power Plant (JAF). These guidelines would be used by emergency response personnel during accident conditions that progress beyond the mitigation capabilities described in Emergency Operating Procedures. SAMG strategies are intended to arrest the progression of fuel damage, maintain the capability of the containment as long as possible, and minimize radiological releases.
The new SAMG commitments for JAF are listed in the Attachment.
It is expected that NRC staff personnel will conduct periodic inspection of the SAMGs and performance deficiencies, if any, will be assessed using the Reactor Oversight Process. It is also understood that inspection activities will not extend to Nuclear Regulatory Commission review and approval of SAMG strategies, or the use of equipment described in the SAMGs.
JAFP-1 5-0145 Page 2 of 2 If you have any questions regarding this report, please contact Chris M. Adnet, Regulatory Assurance Manager, at 315-349-6766.
Sincerely, Brian R. Sullivan Site Vice President BRS/CMNmh
Attachment:
Regulatory Commitments cc: NRC Regional Administrator NRC Resident Inspector Mr. Douglas Pickett, Senior Project Manager Ms. Bridget Frymire, NYSPSC Mr. John B. Rhodes, President NYSERDA NEI David Young
JAFP-15-0145 Attachment Regulatory Commitments (1 Page)
JAFP-15-0145 Attachment Regulatory Commitments This table identifies actions discussed in this letter for which Entergy commits to perform. Any other actions discussed in this submittal are described for the NRCs information and are not commitments.
TYPE (Check one) SCHEDULED ONE- COMPLETION CONTINUING COMMITMENT TIME DATE COMPLIANCE ACTION (If Required)
ENO will consider the site Severe Accident Management Guidelines (SAMGs) within plant configuration management processes X October 31, 2016 in order to ensure that the SAMGs reflect changes to the facility over time.
ENO will update the site Severe Accident Management Guidelines (SAMGs) to revision 3 of the Boiling Water Reactor X June 30, 2017 Owners Group (BWROG) generic severe accident guidelines (published February 2013).
ENO will update the site Severe Accident Management Guidelines (SAMGs) to future revisions of the Boiling Water Reactor Owners Group (BWROG) generic severe Within two refueling accident technical guidelines, and the outages or three SAMGs will be integrated with other years of the emergency response guideline sets and X publication date of symptom-based Emergency Operating the guidelines, Procedures, and validated, using the whichever is guidance in NEI 14-01, Emergency greater Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents. 1 Note 1 - Use of NEI 14-01 guidance begins with the update to revision 4 of the BWROG generic severe accident guidelines.
Page 1 of 1
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315-342-3840 Brian R. Sullivan Site Vice President - JAF JAFP-15-0145 December 15, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Commitment to Maintain Severe Accident Management Guidelines James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-059
Reference:
NEI letter, Industry Initiative to Maintain Severe Accident Management Guidelines, dated October 26, 2015
Dear Sir or Madam:
The Nuclear Energy Institute (NEI) Nuclear Strategic Issues Advisory Committee (NSIAC) recently approved an Industry Initiative to implement and maintain Severe Accident Management Guidelines (SAMGs) [Reference]. This letter establishes commitments related to SAMGs for James A. FitzPatrick Nuclear Power Plant (JAF). These guidelines would be used by emergency response personnel during accident conditions that progress beyond the mitigation capabilities described in Emergency Operating Procedures. SAMG strategies are intended to arrest the progression of fuel damage, maintain the capability of the containment as long as possible, and minimize radiological releases.
The new SAMG commitments for JAF are listed in the Attachment.
It is expected that NRC staff personnel will conduct periodic inspection of the SAMGs and performance deficiencies, if any, will be assessed using the Reactor Oversight Process. It is also understood that inspection activities will not extend to Nuclear Regulatory Commission review and approval of SAMG strategies, or the use of equipment described in the SAMGs.
JAFP-1 5-0145 Page 2 of 2 If you have any questions regarding this report, please contact Chris M. Adnet, Regulatory Assurance Manager, at 315-349-6766.
Sincerely, Brian R. Sullivan Site Vice President BRS/CMNmh
Attachment:
Regulatory Commitments cc: NRC Regional Administrator NRC Resident Inspector Mr. Douglas Pickett, Senior Project Manager Ms. Bridget Frymire, NYSPSC Mr. John B. Rhodes, President NYSERDA NEI David Young
JAFP-15-0145 Attachment Regulatory Commitments (1 Page)
JAFP-15-0145 Attachment Regulatory Commitments This table identifies actions discussed in this letter for which Entergy commits to perform. Any other actions discussed in this submittal are described for the NRCs information and are not commitments.
TYPE (Check one) SCHEDULED ONE- COMPLETION CONTINUING COMMITMENT TIME DATE COMPLIANCE ACTION (If Required)
ENO will consider the site Severe Accident Management Guidelines (SAMGs) within plant configuration management processes X October 31, 2016 in order to ensure that the SAMGs reflect changes to the facility over time.
ENO will update the site Severe Accident Management Guidelines (SAMGs) to revision 3 of the Boiling Water Reactor X June 30, 2017 Owners Group (BWROG) generic severe accident guidelines (published February 2013).
ENO will update the site Severe Accident Management Guidelines (SAMGs) to future revisions of the Boiling Water Reactor Owners Group (BWROG) generic severe Within two refueling accident technical guidelines, and the outages or three SAMGs will be integrated with other years of the emergency response guideline sets and X publication date of symptom-based Emergency Operating the guidelines, Procedures, and validated, using the whichever is guidance in NEI 14-01, Emergency greater Response Procedures and Guidelines for Beyond Design Basis Events and Severe Accidents. 1 Note 1 - Use of NEI 14-01 guidance begins with the update to revision 4 of the BWROG generic severe accident guidelines.
Page 1 of 1
