05000296/LER-1981-020-01, /01T-0:on 810506,while Performing Battery Discharge Test,Valve 3-FCV 73-44 Not Opened & Tagged W/Cantion Order Per Special Instruction T.S.3.5.E.1.Caused by Operator Misinterpretation of Procedure

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/01T-0:on 810506,while Performing Battery Discharge Test,Valve 3-FCV 73-44 Not Opened & Tagged W/Cantion Order Per Special Instruction T.S.3.5.E.1.Caused by Operator Misinterpretation of Procedure
ML20004B018
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 05/20/1981
From:
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20004B016 List:
References
LER-81-020-01T, LER-81-20-1T, NUDOCS 8105270119
Download: ML20004B018 (2)


LER-1981-020, /01T-0:on 810506,while Performing Battery Discharge Test,Valve 3-FCV 73-44 Not Opened & Tagged W/Cantion Order Per Special Instruction T.S.3.5.E.1.Caused by Operator Misinterpretation of Procedure
Event date:
Report date:
2961981020R01 - NRC Website

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1During normal operation, while performing unit 2 battery discharge test, Io j 23 l3-FCV 73-44 was not opened and tagged with a caution order as required by the SI l

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There was no danger to the health or safety of the public.

Isystems were available and operable. There were no previous similar events.

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.- ' Tennessee Valley Authority Form BF-17 Browns Ferry Nuclear Plant BF 15.2 3/24/81 LER SUPPLEMENTAL INFORMATION BFRO 296 / 81020 Technical Specification involved 3.5.E.1 lleported Under Techrical Specification

6. 7.'2. A (2),

Date of Oc urrence 5/ 6/81 Time of Occurrence 2115_

Unit _ 3 Identification and Description of Occurrence:

HPCI not declared inoperable due to FCV 73-44 being closed contrary to procedure.

tanditions Prior to Occurrence:

thit I refueling outage.

Unit 2 at 98%

thit 3 at 100%

Action specified in the Technical Specification Surveillance Requirements met due to inoperable equipment. Describe.

Surveillance requirements of T.S. 4.5.E.2 were not satisfied since personnel were not aware HPCI should be declared inoperable.

Apitarent Cause of Occurrence:

SRO misinterpreted procedure and did not open HPCI discharge valve.

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Analv,iw of Occurrence; j

There was no danger to the health or safety of the public, no release of activity, no damage to the plant or equipment, and no resulting significant f

chain of events.

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Corrective Action

Reinstructed personnel. Recurrence control: Revise SI to require signoff that the HPCI discharge valve be opened.

i F iilur.c Data:

None

  • Reten tion : Period - Lifetime; Responsibility - Document Control Supervisor
  • Revision :

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