05000296/LER-1979-005, Updated LER 79-005/01T-2:on 790506,RHR Svc Water Supply to RHR HX 2B Isolated Standby Coolant Supply.Caused by Lack of Administrative Control Over Sys Cross Connect Valves. Controls Improved

Updated LER 79-005/01T-2:on 790506,RHR Svc Water Supply to RHR HX 2B Isolated Standby Coolant Supply.Caused by Lack of Administrative Control Over Sys Cross Connect Valves. Controls Improved

ML20092A434
Person / Time
Site:	Browns Ferry
Issue date:	04/27/1984
From:	Holder E, Jones G TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
LER-79-005-01T, LER-79-5-1T, NUDOCS 8406190207
Download: ML20092A434 (3)

LER-1979-005, Updated LER 79-005/01T-2:on 790506,RHR Svc Water Supply to RHR HX 2B Isolated Standby Coolant Supply.Caused by Lack of Administrative Control Over Sys Cross Connect Valves. Controls Improved

Event date:
Report date:
2961979005R00 - NRC Website

text

UPDATE REPORT PREVIOUS RFPORT DATE 11/13/79 N:C P M M 364 U O. NUCl.E AR 9238ULAT@AY COMMsE3aCN APPROVEO Y OMll l'd*,Q n LICENSEE EVENT REPORT 2150 8081 CONTROL BLOCK: l l

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n EVENT DESCRIPTION ANO FRO 3ABLE CONSEQUENCES b10 l o l2 l During normal unit 3 operation, the RER service water supply to the 2B RHR l

j o l 3 l l heat exchanger was isolated for maintenance. The isolation of the watar

______J jol4]l supply also isolated the standby coolant supply to unit 3 (T.S. 3 5.C.3 and l

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There was no hazard to the public health or safety. Previous j

lolsll occurrences: None.

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 l

[igoll Isolation of the unit 3 water a ly during unit 2 maintenance was caused by a lac l, j, l l of administrative control over system cross-connect valves. Upon error discovery, l i l 2 l l RHR heat exchanger 2B was returned to service within four hours and water supply j i l 3 l l restored. Administrative controls have' been improved.

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I t I 4 I l Specs, to allow a 10-day standby coolant supply outage, i

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T nneIsea Vallcy Auth:rity Browns F;rry NuslGrr Plant LER SUPPLEMENTAL INFORMATION I

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- BFRO-50-296/79005 R2 Technical Specification Involved 1.5.C.1 and 9.5.C.5

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Reported Under Technical Specification 6.7.2.A.2 l,

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Date of Occurrence 5/6/70 Time of Occurrence 1900 Unit 3

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Identificaiton and Descrintion of Occurrence l

The RRR service water supply to the 2B RHR heat exchanger was isolated for maintenance.

The isolation of the water supply also isolated the stardby I

ooolant supply to unit 3 l

Conditions Prior to Occurrence:

i Unit 2 - refueling outage in progress.

Unit 3 - operating normally at 755 power.

Action specified in the Technical Specification Surveillance Requirements met i

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due to inonerable ecuinment.

Describe

. Place the unit in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Annarent Cause of Occurrence:

- The isolation of the water supply for maintenance was the direct cause; however, lack of administrative controls over cross-connect valves was the proximate i

cause of the accident.

1 Annivsis of OccurreGC11 There was no hazard to the public health or safety.

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Corrective Action

l Upon discovery of the standby coolant supply isolation, action was immediately taken to restore the heat exchanger and the standby coolant was returned to j

service in four hours. The ' standby coolant supply valve was painted a i

distinctive color and strict administrative controls imposed on its operation.

A revision was made to the technical specification for standby coolant supply to allow removal of the standby coolant supply for up to 10 days. This allows ample time for performing maintenance during future outages.

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i Retention Period: Lifetime. Responsibility - Administrative Services h

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TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, Alabama 35602 April 27, 1984 3

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Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

Dear.Mr. O'Reilly:

TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UNIT 3 - DOCKET NO. 50-296 - FACILITY OPERATING LICENSE DPR REPORTABLE OCCURRENCE REPORT BFRO-50-296/79005 R2 The enclosed report provides followup information concerning isolation of RHR service water supply to the 2B RHR heat exchanger for maintenance.

'This report is submitted in accordance with Browns Ferry Unit 3 Technical Specification 6.7.2.A.2.

Very truly yours, TENNESSEE VALLEY AUTHORITY ks

/)BrownsFerryNuclearPlant f

G. T. Jones Power Plant Superintendent Enclosure oo (Enclosure):

U. S. Nuclear Regulatory Commission Document Control Desk Washington D.C.

20555 NRC Inspector, Browns Ferry Nuclear Plant OFFICI AL COPI, 3

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