ML102530579

Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request to Modify Required Actions for Inoperability of an Emergency Diesel Generator

ML102530579
Person / Time
Site:	Oyster Creek
Issue date:	09/10/2010
From:	Geoffrey Miller Plant Licensing Branch 1
To:	Chernoff H Plant Licensing Branch 1
Miller G, NRR/DORL, 415-2481
References
TAC ME4141
Download: ML102530579 (3)

Text

September 10, 2010 MEMORANDUM TO: Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: G. Edward Miller, Project Manager /ra/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

OYSTER CREEK NUCLEAR GENERATING STATION - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO MODIFY REQUIRED ACTIONS FOR INOPERABILITY OF AN EMERGENCY DIESEL GENERATOR (TAC NO. ME4141)

The attached draft request for additional information (RAI) was transmitted by electronic transmission on September 10, 2010 to Mr. Frank Mascitelli, at Exelon Generation Company, LLC (Exelon, the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call with Exelon in order to clarify the licensees amendment request dated June 25, 2010(Agencywide Documents Access and Management System Accession No. ML101790064), to modify required actions for an inoperable emergency diesel generator. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow Exelon to evaluate and agree upon a schedule to respond to the RAI.

This memorandum and the attachment do not represent an NRC staff position.

Docket Nos. 50-219

Enclosure:

As stated

ML102530579 LPL1-2/PM ITSB/BC NAME GEMiller RElliott DATE 9/10/10 9/9/10 DRAFT REQUEST FOR ADDITIONAL INFORMATION OYSTER CREEK NUCLEAR GENERATING STATION LICENSE AMENDMENT REQUEST REQUIRED ACTIONS FOR INOPERABILITY OF AN EMERGENCY DIESEL GENERATOR DOCKET NO. 50-219 By letter dated June 25, 2010 (Agencywide Document Access and Management System Accession No. ML101790064), Exelon Generation Company (Exelon or the licensee) requested an amendment to the Technical Specifications (TSs) for the Oyster Creek Nuclear Generating Station (Oyster Creek). Specifically, the requested change would modify the actions required for the inoperability of an Emergency Diesel Generator (EDG).

1. The Oyster Creek TS Section 1.1, Definitions defines OPERABLE as follows, A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling of seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related support function(s). Explain how it can be ensured that the inoperability of an EDG caused by an independently testable component does not affect the OPERABILITY of the opposite EDG if proposed TS 3.7.C.2.d.1 or TS 3.7.C.2.d.2 are not performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. Identify all components of the EDG that are considered independently testable, which would be exceptions to the requirements of proposed TS 3.7.C.2.d.1 and TS 3.7.C.2.d.2.

3. The LAR states that If a common cause failure is suspected, then the EDG will be verified to be operable by testing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to confirm that a common cause failure does not exist. Describe the process or procedure differences, if any, between how a suspected common cause failure and the proposed TS 3.7.C.2.d.1, Determining the remaining OPERABLE diesel generator is not inoperable due to common cause failure, are obtained.

Enclosure