ML20043D162
| ML20043D162 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/29/1990 |
| From: | Shelton D TOLEDO EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1749, NUDOCS 9006070193 | |
| Download: ML20043D162 (2) | |
Text
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7 7 TOLEDO BDISON u._,, c.,,
DONALD CJ SHELTON va pr e
(419} P40 2300 Docket Number 50-346 1,1 cense Number NPF-3 Serial Number 1749 May 29, 1990
. United States Nuclear Regulatory Commission Document Control Desk Vashington, D. C. 20555
Subject:
Interpretation of. Technical Specification 3.7.9.1 Action b.2 Gentlemen
=This' letter documents our understanding of the Nuclear Regulatory Commission's (NRC) interpretation of Davis-Besse Nuclear Power Station (DBNPS) Technical Specification (TS) 3.7.9.1 Action b.2 provided by-telephone on-December 6, 1989 by Mr. T. V. Vambach, NRC/ Office,of Nuclear. Reactor Regulation (NRR)-
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LDBNPS Senior Project Manager,'to Toledo Edison repres'entat'ives.
TSl3.7.9.1', Fire Suppression Vater Systems, requires two operable high pressure pumps, each with a' capacity of 2500 gpm, with their discharge aligned
.to:the fire suppression header. 'With one pump (diesel driven) inoperable:due to a mechanical failure, Action a was entered which provides for restoring the inoperable pump to' operable status vithin 7 days or submitting a Special Report to_the NRC within the next 30 days. The second pump (electric' driven) was' declared inoperable when'the manual discharge' valve to the fire suppression header was closed to perform required surveillance testing of the electric fire pump. The manual discharge valve is closed during testing of a fire pump to mitigate any potential cyclic hydraulic shocking of the fire suppression header.
During the time period that both pumps vere considered inoperable, TS 3.7.9.1 Action b was entered.
Action b.1' requires a backup fire suppression water system to be established within 24~ hours.
Action b.2
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requires a Special Report to be submitted to the NRC:
- 1) by telephone within 24~ hours, 2). confirmed.by telegraph,'mailgram or facsimile transmission no later than the first working day following the event, and 3) in writing t
within 14 days following the event outlining the action-taken, the cause of the inoperability and the plans and schedule for restoring the-system to operable status.
6070193 900529 p
ADock 03000346 1_
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THE TOLEDO EOISON COMPANY -
ED! SON PLAZA 300 MADISON AVENUE TOLEDO OHlO 43652 n
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. Dpcket Nurb:r 50-346 a
' License Number NPF-3 Serial Number 1749
~Page 2 The electric fire pump's discharge valve was reopened a short time later (less than the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limit), thereby restoring the electric fire pump to operable status. TS 3.0.2 provides that in the event the Limiting Condition for Operation is restored prior to expiration of the specified time interval, completion of the action statement is not required.
In accordance with the provisions of TS 3.0.2, Action b.1 was not completed, however, it was not clear if.the provisions of TS 3.0.2 vould also allow exiting Action b.2 prior to the completion of the reporting requirements.
l Toledo Edison vas provided with the NRC/NRR's interpretation that the provision of TS 3.0.2 was applicable and that reports required under Action b.2 need not be made or submitted since the electric fire pump was restored to operable status prior to exceeding the time interval of the action statement.
In addition, the NRC Staff considered the electric fire pump (which was running for test purposes) in this particular circumstance to be operable provided an operator was stationed.at the closed discharge valve to open it, if required.
Should you'have any questions concerning this matter or shoald our understanding of the interpretation be incorrect, please contact Mr. R.
V.' Schrauder, Manager - Nuclear Licensing at (419) 249-2366 by July.6, 1990.
Very truly yours,
'L/'s
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DJS/ssg cc: P. H. Byron, DB-1 NRC Senior Resident Inspector A. B. Davis, Regional Administrator, NRC Region III T. V. Vambach, DB-1 NRC Senior Project LHanager l
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