ML22188A085

Correction Letter for Amendments 238 and 226 to Renewed Facility Operating Licenses

ML22188A085
Person / Time
Site:	Prairie Island
Issue date:	07/15/2022
From:	Robert Kuntz Plant Licensing Branch III
To:	Domingos C Northern States Power Co
Kuntz R
References
EPID L-2021-LLA-0069
Download: ML22188A085 (5)

Text

July 15, 2022 Mr. Christopher P. Domingos Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company Minnesota 1717 Wakonade Drive East Welch, MN 55089

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 -

CORRECTION LETTER FOR AMENDMENTS 238 AND 226 TO RENEWED FACILITY OPERATING LICENSES (EPID L-2021-LLA-0069)

Dear Mr. Domingos:

On April 1, 2022, the U.S. Nuclear Regulatory Commission (NRC or the Commission) issued Amendment No. 238 to Renewed Facility Operating License No. DPR-42 and Amendment No. 226 to Renewed Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2, respectively (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22061A206). The amendments consisted of changes to the technical specification (TSs) regarding incorporation of Technical Specification Task Force (TSTF) travelers TSTF-471 and TSTF-571, as well as administrative changes to TSs Section 5.0 to remove unused pages.

The amendments did not revise any wording in TSs Section 5.0; however, in the course of issuing the revised TS pages, the word year was inadvertently removed from the last sentence in TS 5.5.6, Reactor Coolant Pump Flywheel Inspection Program, on page 5.5-5: of exposed surfaces of the removed flywheels may be conducted at 20 year intervals.

This letter corrects Amendment Nos. 238 and 226 to restore TS 5.5.6 to the wording as approved in Amendment Nos. 170 and 160 when the inspection interval for TS 5.5.6, Reactor Coolant Pump Flywheel Inspection Program, was increased from 10 years to 20 years (ML051510045).

The NRC staff concludes that the error was introduced during the preparation of the license amendments and is entirely editorial in nature. The proposed 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. Enclosed, please find the corrected replacement page.

If you have any questions regarding this matter, please call me at (301) 415-3733.

Sincerely,

/RA/

Robert F. Kuntz, Senior 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 Page to Amendment No. 238 to DPR-42 and Amendment No. 226 to DPR-60 cc: Listserv

ENCLOSURE PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 CORRECTED PAGE TO LICENSE AMENDMENT NOS. 238 AND 226 RENEWED FACILITY OPERATING LICENSE NO. DPR-42 RENEWED FACILITY OPERATING LICENSE NO. DPR-60

Programs and Manuals 5.5 Prairie Island Unit 1 - Amendment No. 238 Units 1 and 2 5.5-5 Unit 2 - Amendment No. 226 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

j.

Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.

5.5.5 Component Cyclic or Transient Limit This program provides controls to track the USAR, Section 4.1.4, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975. In lieu of Position C.4.b(1) and C.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year intervals.

5.5.7 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following:

ML22188A085 OFFICE DORL/LPL3/PM DORL/LPL3/LA DORL/LPL3/BC DORL/LPL3/PM NAME RKuntz SRohrer NSalgado (SWall for)

RKuntz DATE 07/6/2022 07/11/2022 07/15/2022 07/15/2022