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MONTHYEARML0607300032006-03-29029 March 2006 General Electric Company, Request for Withholding Information from Public Disclosure for James A. FitzPatrick Nuclear Power Plant Project stage: Withholding Request Acceptance ML0630501222006-11-0707 November 2006 Request for Additional Information Regarding Amendment Application for Arts/Meod Modifications Project stage: RAI JAFP-06-0180, Core Operating Limits Report, Revision 222006-12-27027 December 2006 Core Operating Limits Report, Revision 22 Project stage: Request ML0703902602007-02-26026 February 2007 Request for Withholding Information from Public Disclosure Regarding Amendment Application for Arts/Meod Modifications Project stage: Withholding Request Acceptance ML0705904352007-03-0505 March 2007 Draft Safety Evaluation for Implementation of the Average Power Rate Monitor, Rod Block Monitor Technical Specification Improvements with the Maximum Extended Operating Domain Analysis Project stage: Draft Approval ML0714303022007-05-17017 May 2007 Technical Specifications, Allow Additional Startup and Operating Flexibility and an Expanded Operating Domain Project stage: Other ML0704300652007-05-17017 May 2007 License Amendment, Issuance of Amendment Implementation of Average Power Rate Monitor, Rod Block Monitor Technical Specification Improvements with Maximum Extended Operating Domain Analysis Project stage: Approval JAFP-07-0090, Core Operating Limits Report, Revision 232007-07-23023 July 2007 Core Operating Limits Report, Revision 23 Project stage: Other 2007-02-26
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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
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24298A1382024-10-24024 October 2024 Final RAI for FitzPatrick JAFP-24-0047 (L-2024-LLA-0134) ML24197A0162024-07-12012 July 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591 ML24060A0512024-02-28028 February 2024 NRR E-mail Capture - FitzPatrick - Final Arcb RAI Regarding Amendment to Update the Fuel Handling Accident Analysis ML24033A0542024-02-0101 February 2024 NRR E-mail Capture - FitzPatrick - Final HFE RAI Regarding Amendment to Update the Fuel Handling Accident Analysis ML24024A1372024-01-24024 January 2024 NRR E-mail Capture - Final Snsb RAI Regarding FitzPatrick Amendment to Modify Safety Relief Valves Setpoint Lower Tolerance ML24018A0012024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000333/2024010) and Request for Information ML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23164A0322023-06-13013 June 2023 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000333/2023010 ML22321A0102022-11-17017 November 2022 Notification of Conduct of a Fire Protection Team Inspection ML22124A2672022-05-0404 May 2022 Request for Additional Information for James A. FitzPatrick Nuclear Power Plant TSTF-505 ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21187A0522021-07-0606 July 2021 Fitz RAI Regarding FitzPatrick Amendment Request to Modify SR 3.5.1.6 ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21041A1932021-02-10010 February 2021 Request for Information for a Triennial Baseline Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements Inspection; Inspection Report (05000333/2021011) ML20066L3682020-03-0505 March 2020 Request for Additional Information: License Amendment Request for Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment ML20056E7992020-02-25025 February 2020 Request for Additional Information for LAR on Primary Containment Hydrodynamic Loads ML20035D5762020-02-0303 February 2020 Request for Additional Information: License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequence ML20027A0112020-01-23023 January 2020 Request for Additional Information: License Amendment Request for Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation ML19353A9452019-12-19019 December 2019 Request for Additional Information: License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences ML19322A0062019-11-15015 November 2019 NRR E-mail Capture - Fermi 2: Request for Additional Information- Relief Request VRR-006, Proposed Alternative for Preservice Testing of Butterfly Valves ML19280A0372019-10-0505 October 2019 NRR E-mail Capture - FitzPatrick Revised Request for Additional Information: Emergency Amendment to Extend Completion Time of Transformer to 21 Days ML19280A0392019-10-0505 October 2019 NRR E-mail Capture - FitzPatrick Additional Request for Additional Information: Emergency Amendment to Extend Completion Time of Transformer to 21 Days ML19280A0362019-10-0404 October 2019 NRR E-mail Capture - FitzPatrick Request for Additional Information: Emergency Amendment to Extend Completion Time of Transformer to 21 Days ML19099A2672019-04-16016 April 2019 Use of Encryption Software for Electronic Transmission of Safeguards Information ML19099A2852019-03-12012 March 2019 Draft RAI: FitzPatrick Request to Update Electronic Transmission of Safeguards Information ML19025A1202019-01-24024 January 2019 NRR E-mail Capture - Calvert Cliffs, Fitzpatrick, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Response Organization Staffing ML18353B5112018-12-20020 December 2018 Request for Additional Information Relief Request No. 14R-22, for Fourth 10-Year Inservice Inspection Interval ML18164A3652018-06-13013 June 2018 NRR E-mail Capture - FitzPatrick RAIs - LAR to Adopt EAL Schemes Pursuant to NEI 99-01, Revision 6 ML18094B0922018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to B. 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) ML18085A6922018-03-26026 March 2018 NRR E-mail Capture - James A. FitzPatrick Nuclear Power Plant, Unit 1 - Request for Information to Adopt Traveler TSTF-542, RPV Water Inventory Control ML18085A6912018-03-23023 March 2018 NRR E-mail Capture - Draft Request for Information (RAI) for JAFNPP Traveler TSTF-542, RPV Water Inventory Control ML18029A8422018-01-29029 January 2018 NRR E-mail Capture - Request for Additional Information: FitzPatrick License Amendment Request to Revise Technical Specifications to Address Secondary Containment Personnel Access Door Openings ML17335A1002017-11-29029 November 2017 NRR E-mail Capture - FitzPatrick - Request for Additional Information - Relief Request 15R-02 Regarding the Use of BWRVIP Guidelines Instead of ASME Code (CAC: MG0116; EPID: L-2017-LLR-0083) ML17285B1962017-10-27027 October 2017 Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. ML17228A0052017-08-15015 August 2017 NRR E-mail Capture - Request for Additional Information - St. Lucie Relief Request #3 - Icw 30 Pipe Defect Removal (MF9288) ML16299A0192016-11-0202 November 2016 Request for Additional Information Regarding Direct License Transfer from Entergy to Exelon ML16287A6502016-10-21021 October 2016 Request for Additional Information Regarding: License Amendment Request to Revise Technical Specifications Section 5.5.6 for Extension of Type a and Type C Leak Rate Test Frequencies ML16280A5732016-10-18018 October 2016 Request for Additional Information Relief Request for Proposed Alternative for the Implementation of BWRVIP-05 ML16117A1862016-04-26026 April 2016 Entergy Fleet Relief Request EN-ISI-15-1 Request for Additional Information - 04/26/16 Email from R. Guzman to G. Davant (CAC Nos. MF7133-MF7136) 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) ML14240A6122014-09-24024 September 2014 Request for Additional Information Regarding Proposed Changes to the Technical Specification Low Pressure Safety Limit ML14184A6152014-07-25025 July 2014 Request for Additional Information Regarding Proposed Safety Limit Minimum Critical Power Ratio License Amendment ML14195A0972014-07-16016 July 2014 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report ML14164A5382014-07-0202 July 2014 Request for Additional Information Regarding 10 CFR 50.55A Alternate Request PRR-05 (Tac No. MF3680) ML14093A6772014-05-0101 May 2014 SONGS - Request for Additional Information Concerning Pre-Emption Authority 2024-07-12
[Table view] |
Text
November 7, 2006 Mr. Michael R. Kansler President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION REGARDING AMENDMENT APPLICATION FOR ARTS/MEOD MODIFICATIONS (TAC NO. MC9681)
Dear Mr. Kansler:
On January 26, 2006, Entergy Nuclear Operations, Inc. (Entergy), submitted an application for a proposed amendment for the James A. FitzPatrick Nuclear Power Plant which would modify Technical Specification (TS) requirements to support the implementation of Average Power Range Monitor, Rod Block Monitor, TSs/Maximum Extended Operating Domain (ARTS/MEOD) analyses.
The Nuclear Regulatory Commission staff is 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). During a telephone call on October 25, 2006, the Entergy staff indicated that a response to the RAI would be provided within 45 days.
Please contact me at (301) 415-2901 if you have any questions on this issue.
Sincerely,
/RA/
John P. Boska, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
RAI cc w/encl: See next page
ML063050122 OFFICE LPL1-1/PM LPL1-1/LA SBWB/BC LPL1-1/BC NAME JBoska SLittle GCranston RLaufer DATE 11/01/06 11/06/06 11/06/06 11/07/06 FitzPatrick Nuclear Power Plant cc:
Mr. Gary J. Taylor Ms. Charlene D. Faison Chief Executive Officer Manager, Licensing Entergy Operations, Inc. Entergy Nuclear Operations, Inc.
1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601 Mr. John T. Herron Mr. Michael J. Colomb Sr. VP and Chief Operating Officer Director of Oversight Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
440 Hamilton Avenue 440 Hamilton Avenue White Plains, NY 10601 White Plains, NY 10601 Mr. Peter T. Dietrich Mr. David Wallace Site Vice President Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant James A. FitzPatrick Nuclear Power Plant P.O. Box 110 P.O. Box 110 Lycoming, NY 13093 Lycoming, NY 13093 Mr. Kevin J. Mulligan Mr. James Costedio General Manager, Plant Operations Manager, Regulatory Compliance Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant James A. FitzPatrick Nuclear Power Plant P.O. Box 110 P.O. Box 110 Lycoming, NY 13093 Lycoming, NY 13093 Mr. Oscar Limpias Assistant General Counsel Vice President Engineering Entergy Nuclear Operations, Inc.
Entergy Nuclear Operations, Inc. 440 Hamilton Avenue 440 Hamilton Avenue White Plains, NY 10601 White Plains, NY 10601 Regional Administrator, Region I Mr. Christopher Schwarz U.S. Nuclear Regulatory Commission Vice President, Operations Support 475 Allendale Road Entergy Nuclear Operations, Inc. King of Prussia, PA 19406 440 Hamilton Avenue White Plains, NY 10601 Resident Inspector's Office James A. FitzPatrick Nuclear Power Plant Mr. John F. McCann U. S. Nuclear Regulatory Commission Director, Licensing P.O. Box 136 Entergy Nuclear Operations, Inc. Lycoming, NY 13093 440 Hamilton Avenue White Plains, NY 10601
FitzPatrick Nuclear Power Plant cc:
Mr. Charles Donaldson, Esquire Mr. Garrett D. Edwards Assistant Attorney General 814 Waverly Road New York Department of Law Kennett Square, PA 19348 120 Broadway New York, NY 10271 Mr. Peter R. Smith, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Paul Eddy New York State Dept. of Public Service 3 Empire State Plaza Albany, NY 12223-1350 Oswego County Administrator Mr. Steven Lyman 46 East Bridge Street Oswego, NY 13126 Supervisor Town of Scriba Route 8, Box 382 Oswego, NY 13126 Mr. James H. Sniezek BWR SRC Consultant 5486 Nithsdale Drive Salisbury, MD 21801-2490 Mr. Michael D. Lyster BWR SRC Consultant 5931 Barclay Lane Naples, FL 34110-7306
REQUEST FOR ADDITIONAL INFORMATION REGARDING AMENDMENT APPLICATION FOR ARTS/MEOD MODIFICATIONS ENTERGY NUCLEAR OPERATIONS, INC.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 On January 26, 2006, Entergy Nuclear Operations, Inc. (Entergy), submitted an application for a proposed amendment for the James A. FitzPatrick Nuclear Power Plant which would modify Technical Specification (TS) requirements to support the implementation of Average Power Range Monitor (APRM), Rod Block Monitor (RBM), TSs/Maximum Extended Operating Domain (ARTS/MEOD) analyses. The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and has the following questions:
Section 1.0 Introduction 1-1 Allowable value (AV) and analytical limit (AL) are used in a few places in attachment 5 to the application. For example, on page 1-5, the first paragraph states "In the low flow stability region, the scram AVs are based on the scram ALs given in terms of core flow using the JAF
[James A. FitzPatrick] core flow to drive flow relationship...". Provide a clear definition of AV and AL as used in the above statement. What is the difference between AV and AL and how they are related?
1-2 The two tables given on page 1-5 provide the scram and rod block AVs for single-loop operation. Provide the basis for the flow-biased scram and rod block setpoints. How were the specific slopes derived or established?
1-3 Pages 1-4 and 1-5 show the two-loop operation (TLO) and single-loop operation (SLO)
AVs for ranges of drive flow. Explain if the plant can operate at SLO condition at different pump speeds? If not, explain the reasons for the range of flow-biased SLO rod block and scram lines. Are these flow-biased scram lines (which differ from the TLO scram lines) intended to initiate a scram if a transient occurs while the plant is operating at SLO condition? If yes, state what analyses are supporting operation at lower pump speeds for SLO (single pump at maximum capacity).
1-4 During SLO what is the corresponding percent power and percent flow for maximum extended load line limit analysis (MELLLA) operation?
Section 3 Fuel Thermal Limits 3-1 The last paragraph on Page 1-5 discussed RBM setpoint relaxation and that the RBM is not credited in the rod withdrawal error (RWE) for the reload analysis. Did Entergy perform RWE analyses to determine that a thermal limits penalty will not be necessary?
Enclosure
3-2 In Table 3-5, page 3-14, notes b, c, and d in the table were misplaced. Please correct this.
3-3 On Page 3-1, the first paragraph has the statement "The minimum core flow at 100% of rated thermal power (RTP) used in the analysis presented in this section is 81% of RCF [rated core flow ]." Why not use the exact point at 79.8% of RCF corresponding to Figure 1-1 in the analysis?
3-4 At the top of Page 3.2, it states "The other two events (IRLS [idle recirculation loop start-up] and FRFI [fast recirculation flow increase]) are by design most limiting at off-rated conditions. Even when originated from their most limiting off-rated condition, the IRLS and FRFI are less limiting than the fast pressurization events (TTNBP [turbine trip with no bypass],
LRNBP [load rejection with no bypass], or FWCF [feedwater controller failure]) at rated power conditions. Thus, the IRLS and FRFI events were not considered in the determination of the off-rated limits."
(a) Provide additional information (for example, plant response) to support the above statements. Explain why those two events were not analyzed in MELLLA operation domain.
(b) In addition, the table on Page 3-3 (lower left corner) states "The LFWH [loss of feedwater heating], FLE [fuel loading error], IRLS, and FRFI events are not limiting at off-rated conditions." This statement is not consistent with the above statement. Please provide clarification.
3-5 In Table 3-2, the table and footnote showed peak transient response values which occurred at end of cycle (EOC). Confirm if this analysis was performed at other exposures such as beginning of cycle (BOC) and middle of cycle (MOC).
3-6 Section 3.2 has a table for analytical assumptions. Please document that the JAF TS minimum number of SRVs and Turbines Out of Service is consistent with the analyses assumptions.
3-7 Section 3.3.6 stated that "Only adjustment of the P < PBypass portion of the MCPR(P)
[minimum critical power ratio, power dependent] curve is required because, at P $ PBypass, the K(P) applies the rated power OLMCPR [operating limit MCPR] adjustment to the MCPR(P)."
Please reference the appropriate NRC-approved amendment to the General Electric Standard Application for Reactor Fuel or other topical report that explains this off-rated calculation methodology.
This section also provided an equation for the adjustment as follows when operating in SLO:
SLO OLMCPR = OLMCPR dual-loop + SLMCPR [safety limit MCPR] SLO - SLMCPR dual-loop.
Provide additional information on this approach (e.g., how was the above equation obtained?)
and references.
Section 4 Reactor Recirculation (RR) System 4-1 Section 4.0 on the RR System has the following statements:
"The effects of aging and degradation mechanisms (e.g., jet pump crudding) were not included in the evaluation."
"The results of the evaluation indicate that the capability of the [recirculation] system to support operation at 105% of RCF may be marginal during some of the fuel cycle. If so, full 105% core flow may not be available until the end of the fuel cycle when the core differential pressure decreases, which causes the jet pump flow to increase for a given [recirculation] pump flow.
Rotating equipment limitations are economic in nature and do not affect plant safety."
a) Is the recirculation system operating at its nameplate rating in capacity? Explain how plant measured flow data compared to the previous reload analysis in terms of the measured core flow versus assumed AV.
b) What is the potential impact of not accounting for "jet pump crudding," in the safety analyses? Explain why the analyses results are valid if the impact of aging and degradation of the system (such as jet pump crudding) are not accounted for.
c) Discuss what impact jet pump crudding may have on SLO flow calculations.
Section 7 Instability 7-1 Figure 7-1 shows the scram AV and rod block AV lines, which do not appear to be straight linear scram lines as expected from the equations. Specifically, the scram and rod block lines within the stability exclusion appear to be curved lines. Explain why.
7-2 Designate the SLO operating state point in the power/flow map and identify the corresponding scram and rod block lines. Show the flow biased SLO scram and rod block setpoints on Figure 7-1.
7-3 Describe how you obtain core mass flow rates, Wc, for SLO. Specifically, considering the reverse flow in the inoperable loop, explain how the accuracy of the Wc values is determined.
7-4 On page 7-2, it states "For JAF Cycle 16, the core average power-to-flow ratio is estimated to be 56.8 MWt/Mlbm/hr [megawatts thermal per million pounds mass per hour] and the generic DIVOM [delta critical power ratio over initial MCPR versus the oscillation magnitude]
slope is valid for Cycle 16 operation." Explain what core flow state point was used in determining the 56.8 Mwt/Mlbm/hr value? Was this value calculated based on the rated thermal power at 75% core flow? If not, state why the minimum core flow state point is not an appropriate value.
7-5 In the middle of page 7-2, a new APRM flow-biased flux scram line for ARTS/MEOD operation was determined with the additional conservatism in the evaluation. The additional conservatism was listed in numerical order 1, 2, and 3. Please explain why these assumptions
were considered as conservative and how those numbers used in the assumptions were obtained.
Section 8 Loss-of-Coolant Accident (LOCA) 8-1 Please provide additional discussion on what kind of axial power profiles were assumed in the LOCA analysis.
8-2 At the end of the fourth paragraph on page 8-1, it states "These results show that operation in the MELLLA region affects the nominal PCT [peak cladding temperature] by +3F and the Appendix K PCT by +93F." Please explain why the effects on the Appendix K PCT are much more severe than the nominal PCT.
8-3 What were your upper bound PCT results?
8-4 On Page 8-4, there are the following notes for Table 8-2: "(a) The effect on the ECCS
[emergency core cooling systems]-LOCA analysis PCT of operation in the MEOD domain for GE14 is conservatively applicable to GE12 and (b) The effect on the ECCS-LOCA analysis PCT for operation at core flows greater than 100% (ICF [increased core flow]) is negligible. Thus the PCTs for the limiting large break cases at rated conditions are applicable to the ICF condition."
Please provide justification for these notes.
8-5 Please provide all state points including SLO and ICF for the calculation in Table 8-2.
8-6 On page 8-2, there is a statement "The current JAF Licensing Basis PCT for GE12 fuel is 1370EF with a 170EF adder for 10 CFR 50.46 reported errors applicable to the JAF ECCS-LOCA analysis".
Was the adder limited to 10 CFR 50.46 GE12 fuel or are additional adders applicable to the GE14 fuel? In addition, a "170EF" PCT adder is a significant number. Justify why JAF did not perform LOCA reanalysis for the GE12 fuel.
8-7 Did JAF perform full spectrum ECCS-LOCA analysis? If not, please justify.
Section 11 Anticipated Transient Without Scram (ATWS)
GE topical Table 11-2 shows the Peak Vessel Bottom Pressure for ATWS analysis at 1493 psig, which provides very little margin to the ATWS overpressure protection criterion of 1500 psig. The following questions pertain to the key assumptions, conservatism and valve tolerances assumed in the ATWS analysis.
11-1 Table 11-1 shows that the analysis assumed two of the safety-relief valves (SRVs) with the lowest pressure setpoints were assumed to be out of service (OOS). This is conservative.
However, explain why two SRVs OOS was assumed in the analysis? Are there specific known reasons (e.g., tolerances outside TS values) that may lead to declaring SRVs OOS frequently?
11-2 To demonstrate the SRV performance at FitzPatrick, provide the "as found" SRV tolerances data. If the SRV tolerances are outside the TS value, justify why the tolerances assumed in the safety analyses should not be increased.
11-3 The application stated: "The MEOD analysis assumed that the SRVs opened at the upper Analytical Limit of the SRV Electric Lift Subsystem [(SRVELS)], and that the two lowest set SRVs were OOS" The following questions address crediting the SRVELS in the safety analyses.
11-3.1 Table 11-1 specifies the initial conditions assumed in the ATWS analyses and shows that the SRVELS was credited. However, the Updated Final Safety Analysis Report (UFSAR) 4.4.5 (4th paragraph, last sentence) states that "SRVELS is not credited in any accident analysis." Since the SRV electric lift system is not a TS specified safety-grade system, justify why it is acceptable to take credit for it. Most importantly, state why credit for the SRVELS is necessary at FitzPatrick?
11-3.2 Table 11-1 shows SRVELS opening analytical limits at the UFSAR setpoint values of
+1.5%. Justify the basis for not using TS +3% tolerance value.
11-4 Document the reasons why main steam isolation valve (MSIV) and pressure regulator failed open (PRFO) are the most limiting ATWS transients.
11-5 Table 11-2 shows a peak vessel bottom pressure for ATWS analysis of 1493 psig at 31.4 seconds. Since the ATWS peak pressure margin is low, state what conservatisms were assumed in the plant-specific inputs and ATWS analysis methods that will provide some confidence that the small margin is acceptable.
11-6 Confirm standby liquid control system (SLCS) success by providing the following event sequence information, preferably in tabular format:
a) Time of SLCS initiation b) Reactor pressure vessel (RPV) bottom head pressure at time of SLCS initiation c) RPV bottom head pressure at time of SLCS injection (SLCS initiation plus 30 sec SLCS liquid transport time - from Table 11-1) d) SLC pump discharge relief valve setpoint e) Delta psig SLCS pump margin available at time of SLCS initiation f) Time hot shutdown is achieved.
Instrumentation Questions
- 1. Attachment 5 of the January 26, 2006, submittal is the General Electric Technical Report NEDC-33087P, Revision 1, dated September 2005. This report, on pages 1-4 and 1-5, lists the AV for the Flow-Biased APRM neutron flux high trip setting as:
Two Loop Operation:
0.38
- Wd + 61.0% for 0% < Wd # 24.7%
1.15
- Wd + 42.0% for 24.7% < Wd #47.0%
0.63
- Wd + 73.7% for 47.0% < Wd #68.7%
With a maximum of 117.0% power for Wd > 68.7%
Single Loop Operation:
0.38
- Wd + 57.9% for 0% < Wd # 32.7%
1.15
- Wd + 32.8% for 32.7% < Wd # 50.1%
0.58
- Wd + 61.3% for 50.1% < Wd #95.9%
With a maximum of 117.0% power for Wd > 95.9%
By letter dated December 22, 2005, Entergy submitted Revisions 19 and 20 (cycle 17 update) to the Core Operating Limits Report which also listed the same equation. However, these equations are listed as trip settings. Based on this, the NRC staff is unable to determine whether these values have been calculated as AVs or trip settings. As a result, it is not clear as to the setpoint methodology used or how the instrument uncertainties have been addressed.
Therefore, in order for the staff to determine the adequacy of the setpoint determination, please provide the setpoint methodology and calculation performed to determine the trip setpoint and limiting safety system setting. Also provide the information on how the operability of these instruments are determined during the surveillance tests required by the TSs.
- 2. On the bottom of page 5 of Attachment 1 to the December 22, 2005, application, it states that the physical changes to the plant to accommodate the expanded operating region include Flow Control Trip Reference cards. GE Report NEDC- 33087 references GE licensing topical report NEDC -32339P-A, Supplement 2, Revision 1. The staffs acceptance of NEDC -
32339P - A is based on certain design and installation criteria. Please provide the information to show that FitzPatrick meets those criteria. If these criteria are not met then justify the acceptability of these cards to establish the expanded operating region.