ML092120279

Draft Request for Additional Information Regarding Control Rod Drive Rod Notch Testing Frequency

ML092120279
Person / Time
Site:	Oyster Creek
Issue date:	08/04/2009
From:	Geoffrey Miller Plant Licensing Branch 1
To:	Chernoff H Plant Licensing Branch 1
Miller G, NRR/DORL, 415-2481
References
TAC MD8932
Download: ML092120279 (3)

Text

August 4, 2009 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 - DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING CONTROL ROD DRIVE ROD NOTCH TESTING FREQUENCY (TAC NO. MD8932)

The attached draft request for additional information (RAI) was sent by facsimile on August 4, 2009, to Mr. Frank Mascitelli, Exelon Generation Company, LLC (Exelon). 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 certain items in the licensee=s submittal. The draft RAI is related to Exelon=s submittal dated June 9, 2008, regarding a requested reduction of the frequency of performing control rod notch testing. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow Exelon to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.

Docket No. 50-219

Enclosure:

As stated

August 4, 2009 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 Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

OYSTER CREEK NUCLEAR GENERATING STATION - DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING CONTROL ROD DRIVE ROD NOTCH TESTING FREQUENCY (TAC NO. MD8932)

The attached draft request for additional information (RAI) was sent by facsimile on August 4, 2009, to Mr. Frank Mascitelli, Exelon Generation Company, LLC (Exelon). 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 certain items in the licensee=s submittal. The draft RAI is related to Exelon=s submittal dated June 9, 2008, regarding a requested reduction of the frequency of performing control rod notch testing. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow Exelon to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.

Docket No. 50-219

Enclosure:

As stated DISTRIBUTION:

Public RidsNrrPMGMiller LPL1-2 R/F RElliott, NRR RGrover, NRR Accession No.: ML092120279 *Concurrence Via E-mail OFFICE LPL1-2/PM CPTB/BC NAME GEMiller RElliott*

8/4/09 7/31/09 DATE OFFICIAL RECORD COPY

DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING REDUCTION OF THE FREQUENCY FOR PERFORMING CONTROL ROD NOTCH TESTING OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219 By letter dated June 9, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081620236), as supplemented by letter dated March 30, 2009 (ADAMS Accession No. ML090890777), Exelon Generation Company, LLC, submitted an amendment request for the Oyster Creek Nuclear Generating Station (Oyster Creek). The proposed amendment would reduce the frequency for performing Surveillance Requirement (SR) 4.2.D, which requires control rod notch testing for each partially or fully withdrawn rod at least once per week. The proposed amendment would decrease the frequency to at least once per 31 days.

The Nuclear Regulatory Commission (NRC) Staff has been reviewing the submittal and has determined that additional information is needed to complete its review:

1. The model safety evaluation (SE) referenced in the license amendment request evaluates a reduction of the frequency for performing control rod notch testing for fully withdrawn control rods while the proposed change for Oyster Creek would decrease the frequency for both fully and partially withdrawn control rods. Please provide justification for why the decreased frequency of performing control rod notch testing in accordance with SR 4.2.D for partially withdrawn control rods will adequately assure the necessary quality of the control rod system and its components. Additionally, please identify and discuss any differences in the frequency or method of performing scram time testing for fully and partially withdrawn control rods.

Enclosure