ML25077A247: Difference between revisions
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Latest revision as of 10:37, 21 May 2025
| ML25077A247 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/18/2025 |
| From: | Sterio A Constellation Energy Generation |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| Shared Package | |
| ML25077A246 | List: |
| References | |
| JAFP-25-0017 | |
| Download: ML25077A247 (1) | |
Text
Proprietary Information - Withhold Under 10 CFR 2.390 to this letter contains Proprietary Information that should be withheld from public disclosure per 10 CFR 2.390. When Separated from Enclosure 3 there are no applicable withholding criteria.
James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Alex Sterio Site Vice President - JAF JAFP-25-0017 March 18, 2025 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333
Subject:
2025 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal
Dear Sir or Madam:
The changes to the Final Safety Analysis Report (FSAR) for the James A. FitzPatrick Nuclear Power Plant (JAF) are being submitted as required by 10 CFR 50.71(e).
This submittal also includes the changes made to the JAF Technical Specifications Bases and the Technical Requirements Manual (TRM), which are controlled under 10 CFR 50.59, and submitted to the NRC biennially with the changes to the FSAR.
The changes and their bases are summarized in Attachment 1, 2, and 3. The changed pages are included in Enclosures 1, 2, and 3 respectively. contains proprietary information, specifically the TRM Appendix F, Pressure and Temperature Limits Report. The Electric Power Research Institute (EPRI), as the owner of the proprietary information, has executed the enclosed affidavit within Enclosure 3. It identifies which information should be handled as proprietary. Enclosure 3 is requested to be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390 and 9.17. A non-proprietary version of the documentation is provided in Enclosure 4.
There are no new regulatory commitments contained in this letter. If you have any questions, please contact Mr. Mark R. Hawes, Regulatory Assurance, at 315-349-6659.
Proprietary Information - Withhold Under 10 CFR 2.390 JAFP-25-0017 Page 2 of 2 As required by 10 CFR 50.71(e)(2)(i), I certify that the information accurately presents changes made since the previous submittal, necessary to reflect information and analyses submitted to the Commission or prepared pursuant to Commission requirement.
Very truly yours,
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Alex Sterio Site Vice President TCP/CT/mh Attachments 1:
Table of Final Safety Analysis Report (FSAR) 2025 Changes 2:
Table of Technical Specification (TS) Bases 2025 Changes 3:
Table of Technical Requirements Manual (TRM) 2025 Changes Enclosures 1 :
Final Safety Analysis Report (FSAR) 2025 2:
Technical Specification (TS) Bases Revision 62 3:
Technical Requirements Manual (TRM) Revision 116 (Proprietary) 4:
Technical Requirements Manual (TRM) Revision 116 (Non-Proprietary) cc: (w/out enclosures)
NRC Region 1 Administrator NRC Resident Inspector NRC Project Manager NYPSC NYSERDA to this letter contains Proprietary Information that should be withheld from public disclosure per 10 CFR 2.390. When Separated from Enclosure 3 there are no applicable withholding criteria.
JAFP-25-0017 ATTACHMENT 1 Table of Final Safety Analysis Report (FSAR) 2025 Changes (2 Pages)
JAFP-25-0017 Table of Final Safety Analysis Report (FSAR) 2025 Changes Page 1 of 2 FSAR Section /
Table / Figure Description of Change Justification for Change F3.9-1 Add pipe caps to Standby Liquid Control (SLC) pump vent valves 11SLC-104A and 11SLC-104B Engineering Change EC 638918 16.10 Correction to 115 kV underground Oil filled cable Aging Management Program (AMP) by moving it to the preventative maintenance AMP.
NRC Safety Evaluation Report NUERG-1905 T9.6-2 TBCLC Heat exchanger 37E-3A replacement Engineering Change EC 638570 10.2 Turbine Missile Probability changed due to revised calculation JAF-CALC-20-00005 and MPR Associates calculation 0284-0049-CALC-001. Also replacement of Master Trip Solenoid Valve (MTSV) 94MTSV with new design Engineering Change EC 639093 EC 640600 7.6, 14.8, 14.9 T14.8-4, T14.8-6, T14.8-8, T14.8-9, T14.8-10, T14.8-11, F9.17-6 Refuel Bridge Mast upgrade from NF400 to NF500 Mast Engineering Change EC 638505 8.5 Correction to typographical error Editorial 13.8 Procedure OP-7A name change Non-Regulatory Change 9.8 Remove from service condenser pit foam suppression system Engineering Change EC 638647 8.10 Revision to Low Pressure Coolant Injection (LPCI) battery size calculation JAF-CALC-ELEC-01857 Revision 1 Engineering Change EC 627934 9.11, F9.11-1 sheet 1 of 3 Compressed Air System Hardening: Installation Air Dryer Bypass line and 39BAS-2 (Breathing Air Tank-14 Inlet Check Valve) Internals Removal Engineering Change EC 635997 14.5, 14.7, T6.5-1, T14.4-3 Fuel Cycle 27 Reload changes Engineering Change EC 639898
JAFP-25-0017 Table of Final Safety Analysis Report (FSAR) 2025 Changes Page 2 of 2 FSAR Section /
Table / Figure Description of Change Justification for Change 8.4, 8.5, 9.22, F8.5-1, F8.5-3, F8.5-4, Provide new power feeds for the Decay Heat Removal (DHR)
System Engineering Change EC 634221 Rev 2 16.10 Change to AMP Periodic Surveillance and Preventative Maintenance Program for unit cooler 72UC-12B coil replacement with stainless steel Engineering Change EC 639485 5.3 Correction to typographical error Editorial 7.10 Removed thrust bearing wear detector trip of reactor feed pump turbine Engineering Change EC 641518 13.8 Security plan rev 24, 25, 26 10 CFR 50.54(p) 16.10 Change to Electric Power Research Institute (EPRI)
BWRVIP-190, Revision 2, BWR Water Chemistry Guidelines 10 CFR 50.59 Screen JAF-SCN-25-001
JAFP-25-0017 ATTACHMENT 2 Table of Technical Specification (TS) Bases 2025 Changes (1 Page)
JAFP-25-0017 Table of Technical Specification (TS) Bases 2025 Changes Page 1 of 1 TS Bases Section Description of Change Justification for Change 3.4.3 Safety Relief Valve (SRV) lowered as-found setpoint from 3% to 5%
Technical Specification Amendment 355 3.3.6.2, 3.3.7.1, 3.6.4.1, 3.6.4.2, 3.6.4.3, 3.7.3, 3.7.4, 3.8.2, 3.8.5, 3.8.8 Fuel Handling Accident (FHA), New Fuel Mast NF400 to NF500, and recently irradiated fuel Technical Specification Amendment 356 3.0 TSTF-529, Clarify Use and Applicability Rules Technical Specification Amendment 357 2.1 Technical Specification Bases change to adopt NUREG-1433 standardization language for 2.1.1 fuel critical power correlation 10 CFR 50.59 Screen JAF-SCN-24-043
JAFP-25-0017 ATTACHMENT 3 Table of Technical Requirements Manual (TRM) 2025 Changes (1 Page)
JAFP-25-0017 Table of Technical Requirements Manual (TRM) 2025 Changes Page 1 of 1 TRM Page / Table Description of Change Justification for Change Appendix I Surveillance Frequency Control Program (SFCP) changes Change Request Numbers:
JF-23-001 JF-22-008 Rev 1 JF-23-002 JF-18-001 JF-17-012 JF-22-001 JF-21-006 JF-19-012 JF-24-001 JF-24-003 JF-20-007 JF-24-004 3.7.I-2, 3.7.I-3 Frequency Change for Fire Protection Valve Cycling of High Pressure Coolant Injection (HPCI) Fire Foam Tank 76MOV-132 and 76SOV-132 from 12 months to 24 months.
Fire Protection Change Regulatory Review C-4 Refuel Bridge Mast upgrade from NF400 to NF500 Mast. Change in TRM is specific to Refuel Bridge interlock instrumentation setting for weight.
Engineering Change EC 638505 I-5 Update to SFCP wording for SR 3.3.1.2.4 to align with approved license amendment.
Technical Specification Amendment 354 Appendix G Core Operating Limits Report (COLR)
Revision 4 for fuel cycle 27.
Engineering Change EC 639898