L-08-354, Relocation of Relief Request RR-A18, Snubber Examination and Test Requirements

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Relocation of Relief Request RR-A18, Snubber Examination and Test Requirements
ML083650030
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 12/16/2008
From: Allen B
FirstEnergy Nuclear Generation Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-08-354
Download: ML083650030 (2)


Text

FENOC o 5501 North State Route 2 FirstEnergyNuclear Operating Company Oak Harbor,Ohio 43449 Barry S. Allen 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 December 16, 2008 L-08-354 10 CFR 50.55a(a)(3)(i)

ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Davis-Besse Nuclear Power Station, Unit 1 Docket Number 50-346, License No. NPF-3 Davis-Besse Nuclear Power Station, Unit 1 Relocation of Relief Request RR-A18, Snubber Examination and Test Requirements.

This letter is to inform the Nuclear Regulatory Commission (NRC) of a change in the licensing basis documentation utilized in implementing a 10 CFR 50.55a(a)(3)(i) relief request previously approved by the NRC. By letter dated September 19, 2000 (Serial Number 2672), FirstEnergy Nuclear Operating Company (FENOC) submitted the Third 10-Year Interval Inservice Inspection Program for the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS). Included in this submittal was relief request RR-A18 which requested relief from the examination and testing requirements for snubbers contained in IWF-5200(a) and (b) and IWF-5300(a) and (b) of the 1995 Edition, 1996 Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)Section XI. By letter dated February 6, 2002 (Serial Number 2760),

FENOC revised relief request RR-A1 8 in response to an NRC request for additional information. Subsequently, the NRC, by letter dated September 30, 2002 (TAC No. MB 1607) authorized the use of relief request RR-A18 pursuant to 10 CFR 50.55a(a)(3)(i).

Relief request RR-A1 8 stated that snubber examination and tests would be performed to the requirements of the DBNPS Technical Specification 3/4.7.7 in lieu of the requirements of IWF 5200(a) and (b) and IWF-5300(a) and (b) of the 1995 Edition, 1996 Addenda of ASME Section XI.

By letter dated August 3, 2007 (Serial Number 3351), FENOC submitted an application to amend the operating license for the DBNPS to convert the current Technical Specifications to the Improved Technical Specifications consistent with the Improved Standard Technical Specifications as described in NUREG-1430, "Standard Technical Specifications Babcock and Wilcox Plants," Revision 3.1, and certain generic changes to the NUREG. As part of the conversion process, the requirements for the examination and testing of snubbers were relocated with no change in requirements, to the DBNPS Technical Requirements Manual.

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Davis-Besse Nuclear Power Station, Unit 1 L-08-354 Page 2 Therefore, the snubber examinations and testing requirements described within relief request RR-A18 remain in effect, and will be performed in accordance with the DBNPS Technical Requirements Manual.

There are no regulatory commitments contained in this letter and no response is requested from the NRC. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager - Fleet Licensing, at (330) 761-6071.

Sincerely, Barry S. Allen cc: NRC Region III Administrator NRC Resident Inspector NRR Project Manager Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)

Utility Radiological Safety Board