05000302/LER-1981-031-01, /01T-0:on 810624,notification Was Received That Containment Isolation Valves Were Operating Less Conservatively than Vendor re-evaluation for safety-related Application.Caused by Inadequacy of Valve Operators

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/01T-0:on 810624,notification Was Received That Containment Isolation Valves Were Operating Less Conservatively than Vendor re-evaluation for safety-related Application.Caused by Inadequacy of Valve Operators
ML20009C725
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 07/08/1981
From: Hernandez V
FLORIDA POWER CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20009C721 List:
References
LER-81-031-01T, LER-81-31-1T, NUDOCS 8107210401
Download: ML20009C725 (2)


LER-1981-031, /01T-0:on 810624,notification Was Received That Containment Isolation Valves Were Operating Less Conservatively than Vendor re-evaluation for safety-related Application.Caused by Inadequacy of Valve Operators
Event date:
Report date:
3021981031R01 - NRC Website

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lo 8 : 1 I At 1245 durino normal operation, notification was received that containment isola-

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f o i sj l condition contrary to T.S. 3.6.3.1 and T.S. 3.6.1.1 Engineering resolution was to es t [ initiated and coerability was restored at 1340 on 7/1/8'l.

Ther'e was no effect upon I: I7i i the health or safety of the ceneral public.

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SUPPLEMENTARY INFORMATION e

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. Report No.:

50-302/81-031/0lT-0 Facility: Crystal River Unit #3 j

4 Report Date: July 8,1981 l

1 Occurrence Date: June 24, 1981 i

Identification of Occurrence:

i' Containment Isolation Valves AHV-1A, 1B, 1C and ID were operating in a condition less conservative that the vendor's reevaluation for safety-related application. This condition was contrary to Technical Specifications

'3.6.1.1 and 3.6.3.1.

Conditions Prior to Occurrence:

Mode 1 power operation (100%).

Description c! Occurrence:

At 1245 during normal operation, notification was received that the Engineer-ing evaluation of the adequacy oe containment isolation valves AHV-1A,1B,1C and LD performed by Henry Pratt Company as a result of a 1979 commitment to 0

l the NRC, revealed the previously established operating limit of 60 was not adequate.for a LOCA condition. The Reactor B'tilding purge that was in progress was terminated at 1335, and the valves were deactivated pending implementation

' of an Engineering resolution.

l Designation of Apparent Cause:

i The cause'of the event was notification from the Pratt Company.

m

. Analysis of Occurrence:

The revised limit for Pratt Valves with Limitorque operators was determined to be 35 ; for Pratt Valves with the Bettis Actuator, the acceptable angle is 50. There was no effect upon the health or safety of the general public.

Corrective Action

MAR 81-6-37 modified the valves to comply with the recommended operating limits.

No further corrective action'is deemed necessary at this time. Operability was restored at 1340 on July 1, 1981.

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- Failure Data:

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This was the first occurrence of this type, and this is the thirty-sixth l

event reported under Technical Specification 3.6.3'1 and the third under Technical Specification 3.6.1.1.

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