ML12341A322

Request for Additional Information Related to Licensing Amendment

ML12341A322
Person / Time
Site:	Perry
Issue date:	12/11/2012
From:	Michael Mahoney Plant Licensing Branch III
To:	Kaminskas V FirstEnergy Nuclear Operating Co
Michael Mahoney, NRR/DORL, 415-3867
References
TAC ME9006
Download: ML12341A322 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 11, 2012 Mr. Vito A Kaminskas Site Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Mail Stop A-PY -A290 P.O. Box 97, 10 Center Road PerrY,OH 44081-0097

SUBJECT:

PERRY NUCLEAR POWER PLANT, UNIT NO.1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSING AMENDMENT REQUEST TO MODIFY TECHNICAL SPECIFICATION 3.8.1, "AC SOURCES OPERATING," TO REMOVE MODE RESTRICTIONS ON CERTAIN DIVISION 3 SURVIELLANCE REQUIREMENTS (TAC NO. ME9006)

Dear Mr. Kaminskas:

By letter to the U.S. Nuclear Regulatory Commission (NRC) dated July 3,2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12188A001),

FirstEnergy Nuclear Operating Company (FENOC or the licensee) submitted a licensing amendment request (LAR) for the Perry Nuclear Power Plant, Unit NO.1. Specifically, the proposed LAR would modify nine surveillance requirements (SRs) by excluding Division 3 from the current mode restrictions, this would allow the performance of the subject SRs in any mode of plant operation.

The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on November 29,2012, it was agreed that you would provide a response within 30 days from the date of this letter.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.

V, Kaminskas -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3867 or Michael.mahoney@nrc,gov.

N~

Michael Mahoney, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440 Enclosure Request for Additional Information cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO MODIFY TECHNICAL SPECIFICATION 3.8.1 PERRY NUCLEAR POWER PLANT, UNIT NO.1 DOCKET NO. 50-440 By letter to the U.S. Nuclear Regulatory Commission (NRC) dated July 3, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12188A001),

FirstEnergy Nuclear Operating Company (the licensee) submitted a license amendment request (LAR) for the Perry Nuclear Power Plant, Unit 1, to modify Technical Specification 3.8.1, "AC Sources - Operating." The proposed amendment would remove the current mode restrictions on certain surveillance requirements (SRs) for the Division 3 diesel generator (DG).

The NRC staff has determined that additional information is required to complete its review:

1. In Section 3.6 of the LAR, the licensee states, "Historical bus voltage data from performing this SR for Division 3 DG has shown that the voltage during the transient remains within the required voltage range for plant loads. Thus, the voltage transient experienced by loads on the affected bus is minimaL" The licensee also stated that because Division 3 power system is an electrically separated distribution system with a dedicated diesel generator, there is minimal opportunity for these SRs to have an impact on other safety-related plant equipment or normal plant operation.

(a) Provide the key voltage data that were monitored during the last performance of SRs 3.8.1.9,3.8.1.10,3.8.1.11,3.8.1.12,3.8.1.13, and 3.8.1.16.

(b) Confirm that performing these SRs at power will have minimal and acceptable voltage transients on loads of the affected bus and on the equipment of the connected electrical distribution system.

(c) Confirm that performing these SRs at power will not perturb the electrical distribution system and affect other safety-related equipment or normal plant operation.

2. In Section 3.1, page five of the LAR, the licensee states, "Finally, testing in the proposed manner does not significantly interfere with normal plant operation." Discuss all potential interferences identified during the above testing, which could impact with normal plant operation, and provide technical bases showing that these interferences will not have any adverse impact on the plant safety systems and plant operation.

Enclosure

V, Kaminskas -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3867 or MichaeLmahoney@nrc,gov, Sincerely, IRAI Michael Mahoney, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No, 50-440

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:

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