ML23115A407
| ML23115A407 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/26/2023 |
| From: | Ballard B Plant Licensing Branch III |
| To: | Domingos C Northern States Power Co |
| Kuntz R | |
| References | |
| EPID L-2018-LLA-0065 | |
| Download: ML23115A407 (1) | |
Text
April 26, 2023 Mr. Christopher P. Domingos Site Vice President Northern States Power Company - Minnesota Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -
CORRECTION OF LICENSE AMENDMENT NOS. 226 AND 214 RE:
ADOPTION OF TSTF-425, REVISION 3, RELOCATE SURVEILLANCE FREQUENCIES TO LICENSEE CONTROL - RITSTF INITIATIVE 5B (EPID L-2018-LLA-0065)
Dear Mr. Domingos:
By letter dated April 16, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19045A480), the U.S. Nuclear Regulatory Commission issued Amendment No. 226 to Renewed Facility Operating License No. DPR-42 and Amendment No. 214 to Renewed Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2, respectively. The amendments were in response to the license amendment request by Northern States Power Company, a Minnesota Corporation (NSPM, the licensee), doing business as Xcel Energy, dated March 15, 2018 (ML18074A308). The amendments revised the technical specifications (TS) to adopt Technical Specification Task Force (TSTF) Traveler TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specifications Task Force Initiative 5B.
When these amendments were issued, the revised TS page 3.5.2-3, contained a typo in surveillance requirement (SR) 3.5.2.6. Specifically, SR 3.5.2.6 states, Verify each ECCS pumps developed heat, but should state, Verify each ECCS pumps developed head This SR was not changed by Amendment Nos. 226 and 214, and the typo was inadvertently introduced on the TS page when the amendment was issued. After issuance of Amendment Nos. 226 and 214, TS page 3.5.2-3 was revised by Amendment Nos. 235 and 223. These amendments did not revise SR 3.5.2.6.
The NRC staff concludes that the error was introduced during the preparation of license Amendment Nos. 226 and 214 and is entirely editorial in nature. The correction does not change any of the conclusions in the safety evaluation associated with the amendments referenced above and does not affect the associated notices to the public. The corrected Prairie Island TS page 3.5.2-3 is enclosed. Please remove the current page 3.5.2-3 and insert the corrected page 3.5.2-3, which is applicable to both Units 1 and 2. The other pages issued as part of Amendment Nos. 226 and 214 were not affected by this error.
If you have any questions, please contact me at (301) 415-0680 or Brent.Ballard@nrc.gov.
Sincerely,
/RA/
Brent T. Ballard, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosure:
Corrected TS page 3.5.2-3 cc: Listserv
Enclosure ENCLOSURE NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT NOS. 1 AND 2 CORRECTED TECHNICAL SPECIFICATIONS PAGE 3.5.2-3 DOCKET NOS. 50-282 AND 50-306
SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE SR 3.5.2.2
NOTE----------------------------
SR 3.5.2.3 N ot required to be met for system vent flow paths opened under administrative control.
Verify each ECCS manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position.
Verify power to the valve operator has been removed for each valve listed in SR 3.5.2.1.
SR 3.5.2.4 Verify ECCS accessible locations susceptible to gas accumulation are sufficiently filled with water.
ECCS -Operating 3.5.2 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program SR 3.5.2.5 Verify ECCS inaccessible locations susceptible to gas Prior to entering accumulation are sufficiently filled with water.
MODE 3 after exiting shutdown cooling SR 3.5.2.6 Verify each ECCS pump's developed head at the test flow point is greater than or equal to the required developed head.
In accordance with the Inservice Testing Program Prairie Island Units 1 and 2 3.5.2-3 Unit I -Amendment No. 235 Unit 2 -Amendment No. 223
ML23115A407 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DORL/LPL3/BC NAME BBallard SRohrer VSreenivas DATE 4/25/2023 4/ 26 /2023 4/26/2023 OFFICE NRR/DORL/LPL3/PM NAME BBallard DATE 4/26/2023