ML19308D433

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RO-77-41:on 770424,primary Containment Average Air Temp Exceeded 130 F.Caused by Closure of Nuclear Svcs Closed Cycle Cooling Valve SWV-151.Personnel Cautioned Re Unauthorized Manipulation of Valves
ML19308D433
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 05/17/1977
From: Stewart W
FLORIDA POWER CORP.
To:
Shared Package
ML19308D405 List:
References
NUDOCS 8002280737
Download: ML19308D433 (2)


Text

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EVENT DESCDiPTION o

l In Mode 1 operation with Reactor Building purge in progress, the primary containment' 7 09 t

@l average temperature $xceeded 130 0 F. contrary to Technical Specificati)n 3.6.1.5.

Re-7 0U U

EE l dun dan cy N/A.

Non-repetitive occurrence.

SWV-151 was opened to allow cooling water to 7 09 t!

bl Industrial cooline System and Reactor Buildin'c averace temoerature decreased re t u rn en 7 U9 a

35 I to less than 130 F.

(LER 77-41) 7 09 m,g L

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hl Nuclear services closed evcle cooling valve SWV-151 was closed. SWV-151 was opened 7 00 6.

30 l and systetr restored operable 24 April 1977; 7 JL9 L.

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OFFSITE CONSEQUENCES IE l N/A l

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SUPPLEMENTARY INFORMATION 1.

Report No:

50-302/77-41 2.

Facility:

Crystal River Unit #3 3.

Report Date:

17 May 1977 4.

Occurrence Date:

24 April 1977 5.

Identification of occurrence:

Primary containment average air temperature exceeded 130 F. contrary to Technical Specification 3.6.1.5.

6.

Conditions Prior to occurrence:

Normal Mode 1 operation.

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7.

Description of occurrence:

At 1945 with Reactor Building purge in progress, the primary containment average air temperature was 1410 F.

Entered action statement of T.S.3.6.1.5.

Nuclear services closed cycle cooling valve SWV-151 was found closed.

SWV-151 was opened allowing cooling water to return to Industrial Cooling Sys-tem, and the containment averago temperature decreased to less than 1300 F.

at 2029.

8.

Designation of Apparent Cause of Occurrence:

Nuclear services closed cycle cooling valve SWV-151 was closed.

The reason for this is unknown.

9.

Analysis of Occurrence:

The initial temperature condition as assumed in LOCA Accident Analysis was exceeded, however, no hazard to plant or public was presented by this occur '

rence.

10.

Corrective Action:

Normal shi ft surve' llance (SP-300) checks Reactor Building temperature once i

per shift. Since this occurrence, plant personnel have been cautioned re-garding unauthorized manipulation of valves.

11.

Failure Data Fir s t. occurrence of this event.

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