L-MT-25-009, Supplement to Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580, Revision 1, Provide Exception from Entering Mode 4.
| ML25059A095 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 02/24/2025 |
| From: | Hafen S Northern States Power Company, Minnesota, Xcel Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-MT-25-009 | |
| Download: ML25059A095 (1) | |
Text
2807 West County Road 75 Monticello, MN 55089 L-MT-25-009 10 CFR 50.90 February 24, 2025 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Subsequent Renewed Facility Operating License No. DPR-22 Supplement to Application to Revise Technical Specifications to Adopt TSTF-566, "Revise Actions for Inoperable RHR Shutdown Cooling Subsystems," and TSTF-580, Revision 1, "Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling," Using the Consolidated Line Item Improvement Process (EPID L-2024-LLA-0154)
Reference:
- 1) Letter L-MT-24-026, "Application to Revise Technical Specifications to Adopt TSTF-566, 'Revise Actions for Inoperable RHR Shutdown Cooling Subsystems,' and TSTF-580, Revision 1, 'Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling,' Using the Consolidated Line Item Improvement Process," dated October 21, 2024 (NRC ADAMS Accession No. ML24327A157)
- 2) Email from B. Ballard (NRC) to M. Miller (NSPM), "Re: MNGP TSTF-566/580 RAI," dated January 22, 2025, dated January 22, 2025 In Reference 1 the Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter NSPM), submitted a license amendment request (LAR) to adopt the above referenced travelers, i.e., TSTF-566 and 580, into the Technical Specifications (TS) for the Monticello Nuclear Generating Plant (MNGP).
Subsequently it was identified that the marked-up TS Bases included in the LAR, for information, was inadvertently changed in one instance (Reference 2). In the second paragraph on TS Bases page B 3.4.7-4, the term "functional availability" accidentally replaced the existing "functioning" wording discussing the alternate method to verify reactor coolant circulation. NSPM is providing the attached replacement TS Bases page restoring the wording.
The information provided herein does not alter the evaluations performed in accordance with 10 CFR 50.92, "Issuance of amendment," in Reference 1. In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b), a copy of this letter, with attachment, is being provided to the designated Minnesota official.
ATTACHMENT MONTICELLO NUCLEAR GENERATING PLANT APPLICATION TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTF-566, "REVISE ACTIONS FOR INOPERABLE RHR SHUTDOWN COOLING SUBSYSTEMS,"
AND TSTF 580, "PROVIDE EXCEPTION FROM ENTERING MODE 4 WITH NO OPERABLE RHR SHUTDOWN COOLING," USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS TECHNICAL SPECIFICATION BASES PAGE B 3.4.7-4 (MARK-UP)
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RHR Shutdown Cooling System - Hot Shutdown B 3.4.7 Monticello B 3.4.7-4 Revision No. 52 BASES ACTIONS (continued)
B.1, B.2, and B.3 With no RHR shutdown cooling subsystem and no recirculation pump in operation, except as permitted by LCO Note 1, reactor coolant circulation by the RHR shutdown cooling subsystem or recirculation pump must be restored without delay.
Until RHR or recirculation pump operation is re-established, an alternate method of reactor coolant circulation must be placed into service. This will provide the necessary circulation for monitoring coolant temperature.
The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on the coolant circulation function and is modified such that the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is applicable separately for each occurrence involving a loss of coolant circulation. Furthermore, verification of the functioning of the alternate method must be reconfirmed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. This will provide assurance of continued temperature monitoring capability.
During the period when the reactor coolant is being circulated by an alternate method (other than by the required RHR shutdown cooling subsystem or recirculation pump), the reactor coolant temperature and pressure must be periodically monitored to ensure proper function of the alternate method. The once per hour Completion Time is deemed appropriate.
SURVEILLANCE SR 3.4.7.1 REQUIREMENTS This Surveillance verifies that one RHR shutdown cooling subsystem or recirculation pump is in operation and circulating reactor coolant. The required flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
This Surveillance is modified by a Note allowing sufficient time to align the RHR System for shutdown cooling operation after clearing the pressure interlock that isolates the system, or for placing a recirculation pump in operation. The Note takes exception to the requirements of the Surveillance being met (i.e., forced coolant circulation is not required for this initial 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period), which also allows entry into the Applicability of this Specification in accordance with SR 3.0.4 since the Surveillance will not be "not met" at the time of entry into the Applicability.
E.1, E.2, and E.3 Place Bases Specification 3.4.7 - Insert A after new Condition B Here TBD