ML19345F252

LER 81-006/03L-0:on 810108,during Routine Plant Heatup, Unidentified Leakage Exceeding Tech Spec Allowance Existed Because Nitrogen Isolation Valves 2-RC-15 & 2-RC-30 to Pressurizer Were Left Open.Caused by Procedural Inadequacy

ML19345F252
Person / Time
Site:	Millstone
Issue date:	02/06/1981
From:	Rothgeb R NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19345F251	List: ML19345F250 ML19345F252
References
LER-81-006-03L, LER-81-6-3L, NUDOCS 8102170023
Download: ML19345F252 (2)

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I o IDATE e I.3J.ij@ 80 7 60 61 UCCatt %*.*eER 08 EVENT OFSCRiPTIC'J ANO PROG ABLE CONSEQUENCES g [Quring a routine plant heatup, an unidentified leakage in excess of that allowed _by LechJ I

g i nical Specifications existed because 2-RC-15 and 2-RC-30, nitrogen isolation valves _ to j

g [the pressurizer, were lef t open. The plant was operated in accordance with Technical

, , g Specification Action Statement 3.4.6.2.b. l gg Similiar Events: None. g

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• 43 44 47 CAUSE DESCRIP140N AND CORRECTIVE ACTIONS 27 Thnj i O I The valves. 2-RC-15 and 2-RC-30. were out of cositiori duo tn nrnendural inadonnacy

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i i l specific procedures were revised to prevent recurrence.. A generic procedure was cen- 1 I

, , l erated to establish a program for insuring proper system alignments following outages.

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ATTACHMENT TO LER 81-6/3L-0 ,

1 EVENT DESCRIPTION: (cont'd) l During a routine plant heatup following an outage, the high pressure alarm for #1 Safety Injection Tank (SIT) was received. Subsequent investigation revealed that 2-RC-15 and 2-RC-30, isolation valves for high pressure nitrogen 4

i to the pressurizer, were open. Thus, a leakage path from the pressurizer

! steam space to #1 SIT via the nitrogen system was esta'slished, and unidentified leakage in excess of that allowed by Technical Specifications existed. The plant was placed in cold shutdown in accordance with Technical Specification '

Action Statement 3.4.6.2.b.

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Similar Events: None.

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( CAUSE DESCRIPTION: (cont'd) i l

Due to inadequate procedure guidance, 2-RC-15 and 2-RC-30 has been left open j following the cooldown and draining of the pressurizer. A valve line up of this portion of the reactor coolant system was not performed or required prior to commencing the heatup, and the restoration steps of the operating procedure

! that opened the valves was weak. To address the specific case, changes were made to the appropriate operating procedures which will preclude recurrence.

An Administrative Control procedure, ACp-2.12 - System Valve Alignment Control, was generated to establish the program for insuring proper system alignments a following outages.

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