ML19332B307

LER 80-050/01T-0:on 800911,during Mgt Review,Concluded That Operation & Maint on Containment Cooling Sys Had Been Conducted in Less Conservative Manner than Prescribed in Tech Specs.Caused by Sparse & Ambiguous Tech Specs

ML19332B307
Person / Time
Site:	Pilgrim
Issue date:	09/19/1980
From:	Mcloughlin M BOSTON EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19332B303	List: ML19332B302 ML19332B307
References
LER-80-050-01T, LER-80-50-1T, NUDOCS 8009260475
Download: ML19332B307 (2)

Text

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1 d 60 St OOCKET NUMBER 68 69 EVENT OATE EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h I o l 21 l Management revity concluded that station operation and maintenance on the containment l lo lal I cooling system sit.ce che effective date of itera No. 13 of Amendment N.42 of PNPS l j o l4 ; l Technical Specifications has been conducted in a manner less conservative than the 1

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43 e4 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h lil0ll Root cause of this occurrence is sparse and ambiguous technical specifications for l g l operation with installed alternate shutdown panels. I I

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?ILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 Attachment to LER 80-050/01T-0 Description On September 10, 1980 at approximately 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> a management review concluded that a Technical Specification violation had occurred. The violation occurred on September 7, 1980.

On September 7,1980 while performing surveillance tests prior to removing ' A' diesel generator from service it was determined that RBCCW pump P202D was in-operable. Although RBCCW pump P202D was inoperable, the Watch Engineer permitted the diesel generator to be removed from service at that time because Tech. Specs. rec-ognizes these are installed, spares in each of the RBCCW loops.

However, the September 10, 1980 management review concluded that since alternate shutdown panels installed during the last refueling outage restricted ramote control of the RBCCW pump P202D was one of those two, that 'A' diesel generator should not have been removed from service.

Additionally, Salt Service - Water pump maintenance had been performed in August 1980. Similar analysis indicacea that less than the required pumps were avail-able during these maintenance activities and that the required compensatory actions were not initiated.

Cause & Corrective Action The sparse and ambiguous language of' the Technical Specifications is believed to be the root cause of these occurrences in that the Limiting Condition for Operation of the Safe Shutdown Panels is not clearly defined.

Upon identification of the September 10, 1980 situation a reactor shutdown was immediately initiated but terminated at approximately 1810 hours0.0209 days <br />0.503 hours <br />0.00299 weeks <br />6.88705e-4 months <br /> on the same day, following the return of the 'A' diesel generator to service. Additionally, a priority ' A' maintenance request was issued to repair RBCCW pump P202D which was returned to service on September 11, 1980.

A memo has been issued to station Watch Engineers appraising them of this situation and recommending action to preclude its recurrence.

To provide long term corrective action it is contemplated that following ad-ditional review of the existing equipment and their requirements that two action items will be proposed.

1. A design change to plant equipment and,

2. Technical Specification revision to clarify the LCO's for operation with installed alternate shutdown panels. -

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