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LER-1981-029, /03L-0:on 810502,leakage Monitoring Valve 2-CV-12 Found Open & Downstream Pipe Cap Missing Following Return to Power on 810428.Caused by Inadequate Procedure.Valve Closed & Pipe Cap Replaced |
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| 2811981029R03 - NRC Website |
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I On May 2, 1981,. following return to power on April 28th, leakage monitoring valve, 2-
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ment isolation valve, TV-CV-250B, was *ineffective as a barrier. However, the inboard
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,1 Lill] j The* cause of the event was due to inadequate procedure*~* The valve was closed and o::::IIJ j the p *i pe cap-replaced.
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ATTACHMENT 1, PAGE 1 OF 1 SURRY POWER STATION, UNIT 2 DOCKET NO:
50-281 REPORT NO:
81-029/03L-O EVENT DATE:
2-CV-12 LEFT OPEN
- 1.
DESCRIPTION OF EVENT
On May 2, 1981, following return to power on April 28th, a higher than normal con-tainment vacuum pump discharge flow rate was noted.
Subsequent investigation re-vealed that leakage monitoring valve, 2-CV-12, was open and the downstream pipe cap was missing.
This is contrary to Tech. Spec. 3.8.A.1 and is reportabl~ per Tech.
Spec. 6.6.2.b. (2).
- 2.
PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT EQUIPMENT:
With 2-CV-12 open and pipe cap removed, the two barrier design criteria for contain-ment isolation cannot be met.
Specifically, the outboard containment isolation valve, TV-CV-250B, was ineffective as a barrier.
However, the inboard isolation valve, TV-CV-250A, would have been effective and was verified operable. Therefore, the health and *safety of the public were not affected.
- 3.
CAUSE
The cause of. this event was improper administrative control over design change testing.
The valve had been opened and the pipe cap removed to facilitate testing
.of components that had been installed for a TMI design change.
The valve and pipe cap were.*n.ot, returned to their normal status following* the design change implementaf::-.i.;., i ion.
Investigation of this event revealed that an approved procedure, for the manip-ulation of.2-CV-12, was not utilized or referenced by the design change.
4:
IMMEDIATE CORRECTIVE ACTIONS
The immediate corrective action was to close the valve and replace the pipe cap.
- 5.
SUBSEQUENT CORRECTIVE ACTIONS:
None required.
- 6.
ACTION TAKEN TO PREVENT RECURRENCE:
Design changes will be reviewed to ensure that the testing of containment penetra-tions,as required, will be performed and documented using approved procedures.
Personnel involved with testing of this nature have been re-instructed in the importance of returning systems to a normal configuration.
].
GENERIC IMPLICATIONS:
This was a random event and therefore not generic.
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