ML20117K178
| ML20117K178 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/28/1996 |
| From: | Stetz J CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20117K180 | List: |
| References | |
| 2335, NUDOCS 9606100089 | |
| Download: ML20117K178 (2) | |
Text
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CENTERf0R ENERGY 300 uomeon Avenue m,,,,e=
Io6edo, OH 43652-0001 Vice President. Nucesor 419-249 2300 dew-Besse 4
Docket Number 50-346 License Numoer NPF-3 Serial Number 2335 May 28, 1996 i
i-United States Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555
Subject:
Proposed Modification to Davis-Besse Nuclear Power Station (DBNPS) Technical Specifications 3/4.3.1.1 - Reactor Protection System Instrumentation and Technical Specification 3/4.3.2.3 - Anticipatory Reactor Trip System Instrumentation to Increase the Trip Device Test Interval Ladies and Gentlemen:
Enclosed is an application for an amendment to the Davis-Besse Nuclear Power Station (DBNPS) Unit Number 1 Operating License NPF-3, Appendix A, Technical Specifications. The proposed changes involve Technical Speci-fication (TS) 3/4.3.1.1 - Reactor Protection System Instrumentation and Technical' Specification 3/4.3.2.3 - Anticipatory Reactor Trip System Instrumentation. These changes are being proposed because the current Technical Specification required test frequencies, which place the DBNPS in a test configuration susceptible to a spurious reactor trip, have been determined to be unduly restrictive. The technical justification for these proposed changes is provided in the enclosed Babcock & Wilcox Owners Group Topical Report BAW-10167, Supplement 3, January 1995,
" Justification fer Increasing The Reactor Trip System On-Line Test i
Intervals".
F Specifically,-the proposed changes will make the following revisions to i
i Technical Specification 3/4.3.1.1 - Reactor Protection System Instru-I mentation and Technical Specification 3/4.3.2.3 - Anticipatory Reactor Trip System Instrumentation: Table 4.3-1, Reactor Protection System Instrumentation Surveillance Requirements, for Functional Unit 12, Con-trol Rod Drive Trip Breakers, and Functional Unit 13, Reactor Trip Module Logic, revise the channel functional test frequency from monthly on a staggered test basis to semi-annually on a staggered test basis; Table 4.3-17, Anticipatory Reactor Trip System Instrumentation Surveillance Requirements, for Functional Unit 3, Output Logic, revise the channel functional test frequency from monthly to semi-annually on a staggered 7
test basis.
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Docket Number 50-346 License Number NPF-3 iSerial Number 2335 Page 2 i
i These changes are being submitted to the NRC as a Cost Beneficial
. Licensing Action (CBLA). As demonstrated in BAW-10167 these changes will not adversely impact safety. The DBNPS has experienced three reactor trips since 1989 related to Reactor Trip System testing. 'The proposed changes in test interval will provide a potential reduction in the spurious trip rate providing a potential cost savings in excess of
$100,000 over the DBNPS's remaining life. The proposed changes will also provide a reduction in surveillance testing resource requirements with a potential savings of $600,000 over the DBNPS's remaining' life.
These changes are submitted as part of a B&W Owners Group project which involves the Technical Specifications of Arkansas Nuclear One-1 (Entergy),
Crystal River (Florida Power), and Oconee 1,2, and 3 (Duke Power).
BAW-10167,- Supplement 3 will be submitted in parallel by the B&W Owners Group for review and approval by the NRC, and for use by the NRC in approving the proposed License Amendment Applications.
Toledo Edison requests that the NRC approve and issue these changes by February 28, 1997.
Should you have any questions or require additional information, please contact James L. Freels, Manager - Regulatory Affairs, at (419) 321-7744.
Very truly yours, A
DHL Enclosures cc:
L. L. Gundrum, DB-1 NRC/NRR Project Manager H. J. Miller, Regional Administrator, NRC Region III S.- Stasek, DB-1 NRC Senior Resident Inspector J. R. Williamc, Chief of Staff, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
Utility Radiological Safety Board