ML13037A251

Request for Additional Information Related to Licensing Amendment Request to Revise Technical Specification 3.10.1 Inservice Leak and Hydrostatic Testing Operation

ML13037A251
Person / Time
Site:	Perry
Issue date:	02/07/2013
From:	Michael Mahoney Plant Licensing Branch III
To:	Kaminskas V FirstEnergy Nuclear Operating Co
Michael Mahoneoy, NRR/DORL,415-3867
References
TAC ME9006
Download: ML13037A251 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 7, 2013 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 REVISE TECHNICAL SPECIFICATION 3.10.1 "INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION" (TAC NO. ME9006)

Dear Mr. Kaminskas:

By letter to the U.S. Nuclear Regulatory Commission (NRC) dated February 22, 2012 (Agencywide Documents Access and Management System Accession No. ML12054A061),

FirstEnergy Nuclear Operating Company submitted a licensing amendment request for the Perry Nuclear Power Plant, Unit No. 1 The proposed amendment would revise technical specification 3.10.1, and the associated Bases, to expand its scope to include provisions for temperature excursions greater than 200 degrees Fahrenheit as a consequence of inservice leak and hydrostatic testing, and as a consequence of scram time testing initiated in conjunction with an inservice leak or hydrostatic test, while considering operational conditions to be in MODE 4.

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 January 31, 2013, 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, ichael Mahoney, roject 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: 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 application dated February 22,2012 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML12054A061), FirstEnergy Nuclear Operating Company requested changes to the technical speCifications (TS) for Perry Nuclear Power Plant, Unit No. 1 (PNPP). The proposed amendment would revise PNPP's TS 3.10.1, and the associated Bases, to expand its scope to include provisions for temperature excursions greater than 200 degrees Fahrenheit as a consequence of inservice leak and hydrostatic testing, and as a consequence of scram time testing initiated in conjunction with an inservice leak or hydrostatic test, while considering operational conditions to be in MODE 4. The availability of the TS 3.10.1 revision was announced in the Federal Register on October 27,2006 (71 FR 63050), as part of the consolidated line item improvement process (CUIP).

The NRC staff has identified the need for additional information as stated below, to complete review of the subject amendment.

Regulatory Basis The regulations under Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36 (c}(2)(i), in part, states, "Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility."

The regulations under 10 CFR 50.36 (c)(3), in part, states, "Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met."

Request for Additional Information The model safety evaluation (SE) for the standard TS 3.10.1 specifically requires that secondary containment and standby gas treatment system shall be operable and capable of handling any airborne radioactivity or steam leaks that may occur during performance of testing. After the staff's review of PNPP's current TS 3.10.1, there appears to be a deviation from the Technical Specification Task Force (TSTF}-484 model SE.

l Please provide the technical and licensing bases for the exclusion of operability requirements in TS 3.10.1 for secondary containment and the annulus exhaust gas treatment system (the PNPP equivalent to the standby gas treatment system shown in the TSTFl Enclosure

ML13037A251 *via memorandum OFFICE LPL3-2/PM LPL3-2/LA DSS/STSB/BC* LPL3-2/BC LPL3-2/PM NAME MMahoney SRohrer REIliott JWiebe(A) MMahoney DATE 2/6/13 2/6/13 F