ML19308D461

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RO-77-105E:on 770901,reactor Bldg Purged Unmonitored Contrary to Ets.Caused by Failure to Ascertain Monitor Operability Prior to Purge Initiation.More Stringent Procedure Adherence Will Be Followed
ML19308D461
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 09/12/1977
From: Stewart W
FLORIDA POWER CORP.
To:
Shared Package
ML19308D441 List:
References
NUDOCS 8002280773
Download: ML19308D461 (2)


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7 0 57 58 SS GO 61 68 69 74 - 75 EVENT DESCArPTION DE I in mode 1 operation, the Reactor sutiains was purged for 5 minutes unmonitored contrary 7 89 g l to E.T.S. 2.4.2.G and S.T.S. 3.3.2.1, Table 3. 3-4, Redundsmcy N/A. Second occurrence as 7 89 g l reported by LER 77-74E of 26 July 1977.

Upon discovery the purge was terminated inanediately 7 8s 0

[ and RM-Al restored operable.

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  • 8 Q [ Failure to ascertain operability of rionitor operation prior to initiating Reactor Building -i 7 89 t:

Q l purge as required by operating procedure.

A more stringent adherence to procedure will be 7 89 s

lfollowed to preclude recurrence.

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conrENr N!'.EA5 D Of NtLtJ.5E AMOUNT of ACTMTV LOCATCN OF MLEASE 12 C

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0228o 773 ADDITICNAL FACTORS i

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SUPPLEMENTARY INFORMATION 1.

Report No.:

50-302/77-105E 2.

Facility:

Crystal River Unit #3 3.

Paport Date:

12 Septenber 1977 4.

Occurrence Date:

1 September 1977 (discovered 2 September 1977) 5.

Identification of Occurrence:

An unmonitored Reactor Buildi tg purge contrary to Environmental Technical Specitication 2.4.2.G and Standard Technical Specification 3.3.2.1, Table 3. 3-4.

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Conditions Prior to Occurrence:

Mode 1 power operation.

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7.

Description of Occurrenec:

3 At 1700 a purge of the Reactor Building was started with radiation monitor RMA1 sampling pump inoperabla. This constituted an ugmonitored radioactive release for a period of 5 minutes, at a release rate of 1.13x10' microcuries per second.

Upon discovery of the inoperable monitor, the purge uns terminated immediately and RM-Al restored operable.

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VDesignation of Apparent-Cause:

The cause of this event was the failure to escartain operability of monitor operation prior to starting the purge as required by Operating Procedure OP-417.

9.

Analysis of Occurrence l

There was no safety hazard to the plant or public based upon known activity in the J

Reactor Building prior to purging.

10. Corrective Action:

Discussed OP-417 purge requirements with all personnel concerned and a more stringent adherence to Procedures will be followed. OP-417 has been changed to require a visual confirmation of RM-Al operability before initiating a Reactor Building purge.

11.

Failure Data:

This was the second occurrence of this event as reported by LER 77-74E dated 26 July 1977.

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