View source for 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

{{Adams
| number = ML20092A434
| issue date = 04/27/1984
| title = 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
| author name = Holder E, Jones G
| author affiliation = TENNESSEE VALLEY AUTHORITY
| addressee name = Oreilly J
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION II)
| docket = 05000296
| license number = 
| contact person = 
| document report number = LER-79-005-01T, LER-79-5-1T, NUDOCS 8406190207
| document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
| page count = 3
}}
{{LER
| Title = 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
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000296
| LER year = 2079
| LER number = 5
| LER revision = 
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

=text=
{{#Wiki_filter: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 l@
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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
[ o [s l l 3.5.C.5).                 There was no hazard to the public health or safety. Previous                                                                                               j lolsll occurrences: None.                                                                                                                                                                               l loI7Il                                                                                                                                                                                                  l loisll                                                                                                                                                                                                 l
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o lL l@ lZ l9 l9 l 9 l 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.                                                                Changes were made to Tech.;
I t I 4 I l Specs, to allow a 10-day standby coolant supply outage,                                                                                                                                     j i        ,         . .                                                                                  ,                                                                                                 , , ,
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* NRcUa oNty NA                     i l      lllllllllllll I a l .o I L.RJ@l NAME OF PREPARER                   E. T. Holder                 t PHONE. 205 729-ORM 8400190207 840427                                                                               i PDR ADOCK 05000296 L       U                                      gg                                                       l                                                     ___                               _ _ - _ -

T nneIsea Vallcy Auth:rity
        ,_  Browns F;rry NuslGrr Plant LER SUPPLEMENTAL INFORMATION                                                                               I i
                   - BFRO-50-296/79005 R2                                        Technical Specification Involved                            1.5.C.1 and 9.5.C.5                                   !
                                                                                                                                                                                                   }
Reported Under Technical Specification                                                        6.7.2.A.2                                                                        l, t
Date of Occurrence                                     5/6/70           Time of Occurrence                            1900                 Unit     3         .
l
(
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 i~                  due to inonerable ecuinment.                                           Describe                                                                                              !
                   . Place the unit in cold shutdown within 24 hours.
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.                                                                                                                          ;
I                                                                                                                                                                                                )
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.                                                                                                                l i
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 Pl2 l 'l '}
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 f G. T. Jones
          /)BrownsFerryNuclearPlant 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 g                                       An Equal Opportunity Employer fAW p
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}}

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