ML20064B394
| ML20064B394 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/04/1990 |
| From: | Shelton D CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20064B395 | List: |
| References | |
| 1817, TAC-M80455, NUDOCS 9010160305 | |
| Download: ML20064B394 (2) | |
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l Vu Pmeidut W Toledo, OH 436524001.
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(419)249 2300 i
i Docket Number 50-346
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i License Number NPF-3 Serial Number 1817 1
October 4, 1990
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i United States Nuclear Regulatory Commission Document Control Desk Washington, D. C.
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Subj ect : Administrative Changes to Technical Specifications Bases-to Reflect-l De-energization of Containment Emergency Sump Recirculation Valves 1
During Modes 1, 2, 3 and 4 Gentlemen:
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The attached provides changes to the Davis-Besse Nuclear Power Station (DBNPS), Unit Number 1 Operating License, Appendix A, Technical Specifications' Bases to reflect the de-energization of the Containment Emergency Sump l
Recirculation valves DH-9A and DH-9B during operational Modes 1, 2,'3 and 4.
The Bases Section affected is Section 3/4.5.2 and 3/4.5.3, ECCS Subsystems.
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i The changes to the Bases Section add administrative wording to reflect that-the Containment Emergency Sump Recirculation Valves DH-9A and DH-9B are de-energized during Modes 1, 2, 3 and 4 and that the valves may be energized on an intermittent basis under administrative controls.
These changes are being made as a result of the previously evaluated decision to de-energize valves DH-9A and DH-9B during Modes 1, 2, 3 and 4 to resolve a 10 CFR 50, Appendix R issue concerning the postulated spurious opening of valves DH-9A or DH-9B during a Control Room fire. The spurious opening of either of the valves vould provide a direct flow path for draining of.the Borated Vater Storage Tank inventory to the Containment Emergency Sump and..thereby, vould make this water unavailable for normal plant shutdown.
De-energiration of valves DH-9A and DH-9B as the method of resolving the specific Control Room fire scenario was discussed in a meeting with Nuclear Regulatory Commission (NRC)/ Office of Nuclear Reactor Regulation (NRR) personnel (T. Pambach,-
D. Kubicki, R. Jones) on November 21, 1989 (as documented in Toledo Edison letter Serial Number 1744, dated January 11, 1990). Concurrence with.this method of resolution was received from the NRCI however,-though agreeing that Technical Specifications were not required as a result of de-energizing valves DH-9A and DH-9B, it was recommended by the NRC that the de-energization of the valves be noted-in Technical Specifi:ations. The changes contained herein address that recommendation.
9010160305 901004 PDR ADOCK 05000346
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Cleveland Electne muminating Toledo Edison r
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'Dockot Number 50 346 License Number NPF-3 Serial Number 1817 Page 2 l
Toledo Edison = requests these changes be issued by January 28, 1991.
If you have any questions or comments, please contact Mr. R. V. Schrauder, Manager -
Nuclear Licensing at (419) 249-2366.
Very truly yours, Ses\\m,12:22:
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RMC/mmb Attachment cct P. M. Byron, DB-1 Senior Resident Inspector
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A. B. Davis, Regional Administrator, NRC Region III M.'D. Lynch, DB-1 NRC Senior Project Mahager General J. Villiams, Chief of Staff, Ohio Adjutant Generals Department Utility Radiological Safety Board t
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