ML22194A059

Correction to Amendment Nos. 182 and 182 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections

ML22194A059
Person / Time
Site:	Comanche Peak
Issue date:	07/14/2022
From:	Dennis Galvin Plant Licensing Branch IV
To:	Peters K Vistra Operations Company
Galvin D
References
EPID L-2021-LLA-0134
Download: ML22194A059 (5)

Text

July 14, 2022 Mr. Ken J. Peters Senior Vice President and Chief Nuclear Officer Attention: Regulatory Affairs Vistra Operations Company LLC Comanche Peak Nuclear Power Plant 6322 N FM 56 P.O. Box 1002 Glen Rose, TX 76043

SUBJECT:

COMANCHE PEAK NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -

CORRECTION TO AMENDMENT NOS. 182 AND 182 TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTF-577, REVISION 1, REVISED FREQUENCIES FOR STEAM GENERATOR TUBE INSPECTIONS (EPID L-2021-LLA-0134)

Dear Mr. Peters:

By letter dated February 24, 2022 (Agencywide Documents Access System (ADAMS)

Accession No. ML21321A349), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 182 to Facility Operating License No. NPF-87 and Amendment No. 182 to Facility Operating License No. NPF-89 for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 (Comanche Peak, Units 1 and 2), respectively. The amendments adopted Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, which is an approved change to the Standard Technical Specifications, into the Comanche Peak, Unit 1 and 2, Technical Specifications.

The NRC staff identified errors in the heading on the first page of the safety evaluation (SE) in enclosure 3 of the February 24, 2022, letter. Specifically, the heading refers to renewed facility operating licenses for Comanche Peak Units 1 and 2. However, the facility operating licenses for Comanche Peak Units 1 and 2 have not been renewed. The corrected page 1 of the SE contains marginal lines indicating the areas of change The NRC staff determined that the errors were inadvertently introduced during the preparation of the license amendment and are entirely typographical in nature. The corrections do not change any of the conclusions in the safety evaluation associated with the amendment and do not affect the associated notice to the public.

The enclosure to this letter contains the corrected first page of the SE. Please replace the corresponding page issued by Amendment Nos. 182 and 182 for Comanche Peak, Units 1 and 2, respectively.

K. Peters We regret any inconvenience this may have caused. If you have any questions, please contact me at 301-415-6256 or Dennis.Galvin@nrc.gov.

Sincerely,

/RA/

Dennis J. Galvin, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446

Enclosure:

Correction to page 1 of the SE cc: Listserv

ENCLOSURE CORRECTION TO SAFETY EVALUATION PAGE 1 TO AMENDMENT NOS. 182 AND 182 VISTRA OPERATIONS COMPANY LLC COMANCHE PEAK NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-445 AND 50-446

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 182 TO FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. 182 TO FACILITY OPERATING LICENSE NO. NPF-89 VISTRA OPERATIONS COMPANY LLC COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446 Application (i.e., initial and supplements) Safety Evaluation Date July 27, 2021, ADAMS Accession February 24, 2022 No. ML21208A023 Principal Contributors to Safety August 31, 2021, ADAMS Accession Evaluation:

No. ML21243A232 Clinton Ashley October 25, 2021, ADAMS Accession No. ML21298A260 January 25, 2022, ADAMS Accession No. ML22025A412 February 15, 2022, ADAMS Accession No. ML22046A198

1.0 PROPOSED CHANGE

S Vistra Operations Company LLC (the licensee) requested changes to the Technical Specifications (TSs) for Comanche Peak Nuclear Power Plant (Comanche Peak), Unit Nos. 1 and 2, in its license amendment request (application). In its application, as supplemented, the licensee requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendment under the Consolidated Line Item Improvement Process (CLIIP). The proposed changes would revise the Unit 1 Model D76 and Unit 2 Model D5 Steam Generator (SG) Program and the Unit 1 Model D76 and Unit 2 Model D5 Steam Generator Tube Inspection Report TSs based on Technical Specifications Task Force (TSTF)

Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections, dated March 1, 2021 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML21060B434), and the associated NRC staff safety evaluation (SE) of TSTF-577, dated April 14, 2021 (ADAMS Accession No. ML21098A188).

The tubes within an SG function as an integral part of the reactor coolant pressure boundary and, in addition, isolate fission products in the primary coolant from the secondary coolant and Enclosure 3

ML22194A059 *via e-mail OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA* NRR/DORL/LPL4/BC*

NAME DGalvin PBlechman JDixon-Herrity DATE 7/14/2022 7/14/2022 7/14/2022 OFFICE NRR/DORL/LPL4/PM NAME DGalvin DATE 7/14/2022