ML25045A048
| ML25045A048 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/19/2025 |
| From: | Scott Wall NRC/NRR/DORL/LPL3 |
| To: | Rhoades D Constellation Energy Generation, Constellation Nuclear |
| Wall S, NRR/DORL/LPL3 | |
| References | |
| EPID L-2024-LLA-0046 | |
| Download: ML25045A048 (1) | |
Text
February 19, 2025 David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT 1 - CORRECTION TO PAGES ISSUED FOR AMENDMENT NO. 254 REGRADING ADOPTION OF TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-591 (EPID L-2024-LLA-0046)
Dear David Rhoades:
By letter dated December 18, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24339B729), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 254 to Renewed Facility Operating License (RFOL) No. DPR 63, for Nine Mile Point Nuclear Station, Unit 1 (NMP-1). The amendment consists of changes to the license and technical specifications (TSs) in response to the Constellation Energy Generation, LLC (CEG) application dated April 12, 2024 (ML24103A204), as supplemented by letters dated August 9, 2024, and November 26, 2024 (ML24222A677 and ML24331A279, respectfully). The amendment revised the TSs for NMP-1 in accordance with Technical Specifications Task Force (TSTF) Traveler TSTF-591, Revision 0, Revise Risk-Informed Completion Time (RICT) Program.
The NRC inadvertently issued amendment pages that had errors on RFOL page 4, and TS pages 335c and 358a for NMP-1. Specifically, the amendment number is incorrectly referenced as 354 instead of 254. The NRC staff has determined that these were inadvertent typographical errors and are entirely editorial in nature.
Consistent with NRC staff guidance dated January 16, 1997 (ML103260096), based on the NRCs policy established by SECY-96-238, these errors can be corrected by a letter to the licensee from the NRC staff. Accordingly, the enclosure to this letter provides the corrected Renewed Facility Operating License and TS pages.
If you have any questions concerning this action, please contact me at (301) 415-2855 or by email to Scott.Wall@nrc.gov.
Sincerely,
/RA/
Scott P. Wall, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220
Enclosure:
Corrected Pages to Amendment No. 254 to DPR-63 cc: Listserv
Enclosure NINE MILE POINT NUCLEAR STATION, LLC CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT 1 CORRECTED PAGES
ATTACHMENT TO LICENSE AMENDMENT NO. 254 NINE MILE POINT NUCLEAR STATION, UNIT 1 RENEWED FACILITY OPERATING LICENSE NO. DPR-63 DOCKET NO. 50-220 Replace the following pages of the Renewed Facility Operating License and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert License DPR-63 License DPR-63 Page 4 Page 4 TSs TSs 355c 355c 358a 358a Renewed License No. NPF-63 Revised by letter dated February 21, 2007 Amendment No. 195, 209, 214, 219, 220, 247, 250, 251, 252, 254 (1)
Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 1850 megawatts (thermal).
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. 254, is hereby incorporated into this license. Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications.
(3)
Deleted D.
This license is subject to the following additional conditions:
(1)
NMP LLC will complete construction of a new radwaste facility in conformance with the design defined and evaluated in the FES, to be operational no later than June 1976.
(2)
Deleted by License Amendment No. 51 (3)
Deleted by License Amendment No. 51 (4)
Security, Training and Qualification and Safeguards Contingency Plans Constellation Energy Generation, LLC shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to the provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21 is entitled Nine Mile Point Nuclear Station, LLC Physical Security, Safeguards Contingency, and Security Training and Qualification Plan, Revision 1, and was submitted by letter dated April 26, 2006.
Constellation Energy Generation, LLC shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The licensees CSP was approved by License Amendment No. 209 and modified by License Amendment No. 219. The licensee has obtained Commission authorization to use Section 161A preemption authority under 42 U.S.C 2201a for weapons at its facility.
(5)
Paragraph 2.D(5) of the license has been combined with paragraph 2.D(4) as amended above into a single paragraph.
d.
For emergent conditions, if the extent of condition evaluation for inoperable structures, systems, or components (SSCs) is not complete prior to exceeding the Completion Time, the RICT shall account for the increased possibility of common cause failure (CCF) by either:
1.
Numerically accounting for the increased possibility of CCF in the RICT calculation; or 2.
Risk Management Actions (RMAs) not already credited in the RICT calculation shall be implemented that support redundant or diverse SSCs that perform the function(s) of the inoperable SSCs, and, if practicable, reduce the frequency of initiating events that challenge the function(s) performed by the inoperable SSCs.
e.
A RICT calculation must include the follow hazard groups: internal flood and internal events using a PRA model, internal fires using a PRA model, seismic hazards using penalty factors, and configuration-specific straight wind and tornado wind pressure /
tornado missile hazards using penalty factors. Changes to these means of assessing the hazard groups require prior NRC approval.
f.
The PRA models used to calculate a RICT shall be maintained and upgraded in accordance with the processes endorsed in the regulatory positions of Regulatory Guide 1.200, Revision 3, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities.
g.
A report shall be submitted in accordance with Specification 6.6.8 before a newly developed method is used to calculate a RICT.
AMENDMENT NO.
250 254 355c
b.
The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:
1.
SIR-05-044-A, Pressure-Temperature Limits Report Methodology for Boiling Water Reactors, Revision 0, April 2007.
c.
The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.
6.6.8 Risk Informed Completion Time (RICT) Program Upgrade Report A report describing newly developed methods and their implementation must be submitted following a probabilistic risk assessment (PRA) upgrade associated with newly developed methods and prior to the first use of those methods to calculate a RICT. The report shall include:
a.
The PRA models upgraded to include newly developed methods; b.
A description of the acceptability of the newly developed methods consistent with Section 5.2 of PWROG-19027-NP, Revision 2, Newly Developed Method Requirements and Peer Review; c.
Any open findings from the peer-review of the implementation of the newly developed methods and how those findings were dispositioned; and d.
All changes to key assumptions related to newly developed methods or their implementations.
AMENDMENT NO. 204 254 358a
ML25045A048 NRR-106 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL1/LA NRR/DORL/LPL3/BC (A)
NAME SWall KEntz IBerrios DATE 2/14/2025 2/14/2025 2/18/2025 OFFICE NRR/DORL/LPL3/PM NAME SWall DATE 2/19/2025