ML20138C303
| ML20138C303 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/18/1997 |
| From: | Jeffery Wood CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20138C306 | List: |
| References | |
| 2447, NUDOCS 9704300086 | |
| Download: ML20138C303 (2) | |
Text
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Ih'lhb CElNihERN(>R s#vencnr i
5501 N. State Route 2 419-249-2300 John K. Wood Oak Hrbor.OH 43449 FAX: 419 321 8337 Vce Presdert. Nuclear DavitBesse 1
Docket Humber 50-346 License Number NPF-3 Serial Number 2447 April 18, 1997 United States Nuclear Regulatory Commission Document Control Desk Washington, D.
C. 20555-0001
Subject:
Proposed Modification to the Davis-Besse Nuclear Power Station, Unit Number 1, Facility Operating License NPF-3, Appendix A Technical Specifications to Revise the Control Room Emergency Ventilation System Limiting Condition for Operation (License Amendment Request No. 97-0005)
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Ladies and Gentlemen:
Enclosed is an application for an amendment to the Davis-Besse Nuclear Power Station (DBNPS) Unit Number 1, Facility Operating License NPF-3, Appendix A, Technical Specifications. The proposed changes involve Technical Specification (TS) 3/4.7.6, Plant Systems - Control Room Emergency Ventilation System (CREVS), and the associated Bases.
This application proposes to revise the TS Limiting Condition for Operation (LCO) to include new required Actions in the event that one or both channels of Station Vent Normal Range Radiation Monitoring instrumentation becomes inoperable. These radiation monitoring instrumentation channels serve to isolate the control room in the event of high radiation levels in the station vent utack. The associated TS Bases are also proposed to be revised consistent with these proposed changes.
The p'roposed changes will eliminate the potential for an unnecessary plant shutdown in the event both channels of radiation monitoring instrumentation become inoperable during plant operation, by requiring that a CREVS train be placed in operation. The proposed changes will also bring the DBNPS Technical Specifications into closer agreement with II NUREG-1430, " Improved Standard Technical Specifications for Babcock and j' J l
Wilcox Pressurized Water Reactors," Revision 1.
9704300086 970410 llfh l l '
- POR ADOCK 05000346
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Docktt Number 50-346 Licunsc'Numbar NPF-3 Serial Number 2447 Page 2 e
Toledo Edison requests that the NRC approve and issue this change by November 7, 1997.
Should you have any questions or require additional information, please contact Mr. James L.
Freels, Manager - Regulatory Affairs, at (419)321-8466.
Very truly yours, MKL/ aj Enclosure cc:
A. B. Beach, Regional Administrator, NRC Region III A. G. Hansen, DB-1 NRC/NRR Project Manager S.
Stasek, DB-1 NRC Senior Resident Inspector J.
R.
Williams, Chief of Staff, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
Utility Radiological Safety Board
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