05000296/LER-1985-001, :on 850104,during Normal Operation,Employee Accidentally Caused RCIC Sys to Be Inoperable for Approx 2 Minutes.All Other Required Core Standby Cooling Sys Fully Operable

:on 850104,during Normal Operation,Employee Accidentally Caused RCIC Sys to Be Inoperable for Approx 2 Minutes.All Other Required Core Standby Cooling Sys Fully Operable

ML20106B394
Person / Time
Site:	Browns Ferry
Issue date:	01/29/1985
From:	Jones G, Danni Smith TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
LER-85-001, LER-85-1, NUDOCS 8502110586
Download: ML20106B394 (3)

LER-1985-001, on 850104,during Normal Operation,Employee Accidentally Caused RCIC Sys to Be Inoperable for Approx 2 Minutes.All Other Required Core Standby Cooling Sys Fully Operable

Event date:
Report date:
2961985001R00 - NRC Website

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NRC Form see U.S. NtiCLEA J REGULATORY consMeeslON I' 83' APPROVED Owe seO 31to g104 LICENSEE EVENT REPORT (LER)

P ACILITV NAME I4 DOCKET NUMeER (21 PAGE G Browns Ferry - Unit 3 015101010121916 1 lOFl 012 nTtt al Momentary Inoperable Reactor Core Isolation Cooling Due To A Personnel Error EVENT DATE (51 LER NUMSER ($1 REPORT DATE (71 OTHER F ACILITIES INVOLVED (8)

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v ABSTR ACT (trawr to 7400 spaces e e, ansee=+efet Mfeea sme e space typeerstera haert (ISI During normal operation, an employee accidentally caused the Reactor Core Isolation Cooling System to be inoperable for approximately two minutes.

All other required core standby cooling systems were fully operable.

No other occurrences accompanied this event.

8502110586 850129 PDR ADOCK 05000296 S

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During ncrmal plant operations, unit 1 was operating at 98 percent, unit 3 at 98 percent, and unit 2 was in a refueling outage.

As an employee was performing system checks to update plant configuration drawings, he accidentally hit the Reactor Core Isolation Cooling (BN) turbine stop valve (ISV) actuator. This in turn caused the valve, FCV-71-9, to close giving the unit 3 licensed reactor operator an annunciator (ANN) alarm (ALM)71-49A. Within two cinutes, the operator initiated valve reopening.

All required core standby cooling systems were fully operable during this event.

The employee was cautioned to be more vigilant around critical equipment. No other factors were involved, and since this was random in nature, no further corrective action is required.

Resoonsible Plant Section - OPS Previous Similar Events - None i

4 NRC FOP.M 366A t$ $31

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TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, Alabama 35602 January 29, 1985 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C.

20555

Dear Sir:

TENNESSEE VALLEY AUTHORITY - BR7JNS FERRY NUCLEAR PLANT (BFN) UNIT 3 -

l DOCKET NO. 50-2% - FACILITY OPERATING LICENSE DPR REPORTABLE l

OCCURRENCE REPORT BFRO-50-2%/85001 The enclosed report provides details concerning momentary inoperability of the Reactor Core Isolation Cooling due to a personnel error. This report is submitted in accordance with 10 CFR 50 73 (a)(2)(v).

Very truly yours, TENNESSEE VALLEY AUTHORITY

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G. T.

ones Plant Manager Browns Ferry Nuclear Plant Enclosures l

cc (Enclosures):

Regional Administrator INPO Records Center l

U. S. Nuclear Regulatory Commission Suite 1500 Office of Inspection and Enforcement 1100 Circle 75 Parkway Region II Atlanta, Georgia 30339 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 NRC Resident Inspector, BFN I

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