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Category:Letter
MONTHYEARML24276A1332024-10-17017 October 2024 Issuance of Amendment No. 357 Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision-4, and Administrative Changes ML24282B0302024-10-11011 October 2024 Project Manager Assignment RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing JAFP-24-0051, Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-0882024-10-0303 October 2024 Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-088 ML24270A0742024-09-30030 September 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0134) - LTR ML24270A1452024-09-26026 September 2024 Notice of Enforcement Discretion for James A. Fitzpatrick Nuclear Power Plant JAFP-24-0046, Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation2024-09-25025 September 2024 Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation JAFP-24-0047, License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software2024-09-25025 September 2024 License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software JAFP-24-0045, Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2024-09-20020 September 2024 Supplemental Information for 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 IR 05000333/20240112024-09-19019 September 2024 Follow-up to Inspection Procedure 71153 Report 05000333/2024011 and Preliminary White Finding and Apparent Violation JAFP-24-0044, Core Operating Limits Report Cycle 272024-09-16016 September 2024 Core Operating Limits Report Cycle 27 JAFP-24-0043, Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2024-09-12012 September 2024 Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues 05000333/LER-2024-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2024-09-0404 September 2024 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation ML24165A0382024-09-0404 September 2024 Issuance of Amendment No. 356 Update Fuel Handling Accident Analysis IR 05000333/20240052024-08-29029 August 2024 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2024005) 05000333/LER-2024-001-01, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-08-21021 August 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000333/20240022024-08-0707 August 2024 Integrated Inspection Report 05000333/2024002 JAFP-24-0034, 10 CFR 50.46 Annual Report2024-07-31031 July 2024 10 CFR 50.46 Annual Report ML24208A0492024-07-30030 July 2024 Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Proposed No Significant Hazards Consideration Determination (Letter) JAFP-24-0036, Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-07-29029 July 2024 Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0033, Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test2024-07-23023 July 2024 Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test IR 05000333/20244032024-07-18018 July 2024 Biennial Problem Identification and Resolution Inspection Report 05000333/2024403 (Cover Letter Only) IR 05000333/20244012024-07-15015 July 2024 Security Baseline Inspection 05000333/2024401 RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions ML24190A1932024-07-0909 July 2024 Correction Letter of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance IR 05000333/20240102024-07-0808 July 2024 Commercial Grade Dedication Inspection Report 05000333/2024010 ML24184A1662024-07-0303 July 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24136A1162024-06-26026 June 2024 Issuance of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance ML24176A2412024-06-24024 June 2024 Licensed Operator Positive Fitness-for-Duty Test JAFP-24-0027, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-06-24024 June 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations JAFP-24-0026, Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance2024-06-12012 June 2024 Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 JAFP-24-0023, 2023 Annual Radiological Environmental Operating Report2024-05-0909 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000333/20240012024-05-0909 May 2024 Integrated Inspection Report 05000333/2024001 RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests JAFP-24-0020, 2023 Annual Radioactive Effluent Release Report2024-04-25025 April 2024 2023 Annual Radioactive Effluent Release Report JAFP-24-0019, 2023 REIRS Transmittal of NRC Form 52024-04-18018 April 2024 2023 REIRS Transmittal of NRC Form 5 ML24106A0152024-04-15015 April 2024 Request for Withholding Information from Public Disclosure Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24107A6972024-04-12012 April 2024 Engine Systems, Inc Part 21 Report Re EMD Cylinder Liner Water Leak RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24068A0532024-03-28028 March 2024 Issuance of Amendment No. 354 Revise Technical Specifications Section 3.3.1.2, Source Range Monitors Instrumentation JAFP-24-0014, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-03-25025 March 2024 Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0010, Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2024-02-29029 February 2024 Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance JAFP-24-0009, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-02-28028 February 2024 Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis IR 05000333/20230062024-02-28028 February 2024 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023006) IR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 2024-09-04
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 16, 2017 Mr. Brian Sullivan Site Vice President Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming , NY 13093
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT- RESPONSE REGARDING PHASE 2 STAFFING SUBMITTAL ASSOCIATED WITH NEAR-TERM TASK FORCE RECOMMENDATION 9.3 RELATED TO THE FUKUSHIMA DAl-ICHI NUCLEAR POWER PLANT ACCIDENT (CAC NO.
MF9153)
Dear Mr. Sullivan:
By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340), the U.S. Nuclear Regulatory Commission (NRC) issued a request for information pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Section 50.54(f) (hereafter referred to as the 50.54(f) letter) , regarding Recommendations 2.1 (seismic and flooding evaluations) , 2.3 (seismic and flooding walkdowns) , and 9.3 (emergency preparedness communication and staffing) of the Near-Term Task Force (NTTF) review of insights from the Fukushima Dai-ichi accident. With respect to NTTF Recommendation 9.3, Enclosure 5 to the NRC's letter requested licensees and holders of construction permits to assess their means to power communications equipment onsite and offsite during a prolonged station blackout (SBO) event and to perform a staffing assessment to determine the staff required to fill all necessary positions in response to a multi-unit event.
The 50.54(f) letter, in part, requested licensee responses pursuant to the provisions of 10 CFR 50.54(f) pertaining to onsite and augmented staff availability to implement the strategies discussed in the emergency plan and plant operating procedures, including new staff or functions resulting from the assessment, identified collateral duties, an implementation schedule to perform the assessments, identified modifications, and any changes that have been made or will be made to the emergency plan regarding on-shift or augmented staffing.
In addition, NTTF Recommendation 9.3 has a dependency on the implementation of NTTF Recommendation 4.2 (mitigating strategies). As a result of this dependency, licensees responded to the 50.54(f) letter in phases. The Phase 1 staffing assessments evaluated licensees' ability to respond to a multi-unit extended loss of alternating current (ac) power (ELAP) event utilizing existing processes and procedures. Licensees were not requested to submit Phase 1 staffing assessments for single-unit sites.
Licensees were also requested to submit a Phase 2 staffing assessment for NRC staff review, which provides an assessment of the staffing necessary to perform the functions related to the strategies developed in response to NTTF Recommendation 4.2 and the resulting NRC Order EA-12-049, "Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for
B. Sullivan Beyond-Design-Basis External Events [BDBEE]" (ADAMS Accession No. ML12054A736).
Licensees were requested to provide their Phase 2 staffing assessment to the NRC no later than 4 months prior to the beginning of their second refueling outage (as used in the context of compliance with Order EA-12-049) . By letter dated December 2, 2016 (ADAMS Accession No. ML16173A342), Entergy Nuclear Operations, Inc. (Entergy, the licensee) was granted a relaxation of the schedule requirements for compliance with Order EA-12-049 for James A.
FitzPatrick Nuclear Power Plant (FitzPatrick) until June 30, 2017. By letter dated January 23, 2017 (ADAMS Accession No. ML17023A346), Entergy submitted its Phase 2 staffing assessment for FitzPatrick to the NRC in response to the 50.54(f) letter.
The NRC staff reviewed the licensee's Phase 2 staffing assessment in accordance with the assumptions and guidelines of Sections 2.2, 2.3, and 3 of the Nuclear Energy Institute (NEI) guidance document NEI 12-01 , "Guideline for Assessing Beyond Design Basis Accident Response Staffing and Communications Capabilities" (ADAMS Accession No. ML12125A412),
which was endorsed by the NRC staff by letter dated May 15, 2012 (ADAMS Accession No. ML12131A043). The NRC staff noted that the licensee assessed its current onsite minimum staffing levels to identify any enhancements needed to respond following a beyond-design-basis large-scale natural event, and to ensure that the strategies contained in the existing emergency plan and plant operating procedures, such as those used in response to a SBO, can be performed by the site staff. Consistent with the assumptions stated in Section 2 of NEI 12-01 ,
the licensee's assessment assumed that a large-scale natural event causes: (1) an ELAP, (2) all units on the site to be affected , and (3) access to the site to be impeded for a minimum of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The licensee also assessed its capability to perform the site-specific functions related to the strategies developed in response to Order EA-12-049. The licensee conducted independent reviews and concluded , based on its staffing assessment, that the existing on-shift minimum staff is sufficient to implement the loss of all ac power event response strategies, including those strategies developed to support the requirements of Order EA-12-049, while supporting performance of the required emergency planning duties without unacceptable collateral duties.
The NRC staff reviewed the licensee's Phase 2 staffing assessment, and previously submitted supplemental information (ADAMS Accession Nos. ML12135A395, ML12164A238, and ML16105A358), to verify the assessment's conclusion that the licensee's existing emergency response resources , as described in its emergency plan , are sufficient to perform the required plant actions and emergency plan functions, and implement the event response strategies that were developed in response to Order EA-12-049 without the assignment of collateral duties that would impact the performance of assigned emergency plan functions .
As a result, the NRC staff concludes that the licensee's Phase 2 staffing submittal adequately addresses the response strategies needed to respond to a BDBEE using its procedures and guidelines. The NRC staff will verify the implementation of the licensee's staffing capabilities through the inspection program.
B. Sullivan If you have any questions regarding this letter, please contact Stephen Philpott at (301) 415-2365 or via email at Stephen.Philpott@nrc.gov.
Sincerely, (k9:.a~chief a~~~rs Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket No. 50-333 cc: Distribution via Listserv
ML17069A440 *via email OFFICE NRR/JLD/JOMB/PM NRR/JLD/LA NSIR/DPR/NRLB/BC* NRR/JLD/JOMB/BC(A)
NAME SPhilpott Slent RKahler JBoska DATE 3/13/17 3113/17 3/16117 3/16117