ML19331B908

LER 80-037/03L-0:on 800711,reactor Operated in Degraded Mode W/Only One Complete Pcrv Liner Cooling Water Loop Operating. Caused by Removal of Other Prcv Liner from Svc Coupled W/ Three Brief Periods of Reactor Power Operation

ML19331B908
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/08/1980
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19331B905	List: ML19331B904 ML19331B908
References
LER-80-037-03L, LER-80-37-3L, NUDOCS 8008130514
Download: ML19331B908 (1)

Text

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'NRC FORM 366 U, S NUCLEAR REGULATORY COMMISSION (7 77)

O LICENSEE EVENT REPORT .

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(PLEASE PRINT OR TYPE ALL REQUIREO INFORMATIONI le IiI8 l9 Cl olLICENSEE 7

FI slCODEvl 11@l 0101_ l 0 LICENSE 14 15 l 01010 NUMBER l ol_lofol@l 25 4111112101@l 26 LICENSE TYPE Jo l

57 CAT 58 l@

CON'r lolIl SoU CE l L hl 0l 5 l 0 l 0 l O l 216 I 768 @l,_Q 69 l 7 I 1 l1 l 8 l 0 hl 0lREPORT 74 75 8l 0lDATE 8l 8l 0l@ 80 7 8 60 61 QoCKET NUMBER EVENT D ATE EVENT OESCRIPTICN ANO PROBABLE CONSEQUENCES h I o 12 I l On July 11, 1980, the reactor was operated at power with only one complete operating I

,g,3, g PCRV liner cooling water loop. This constitutes operation in a degraded mode per- l l o 14 l l mitted by LCO 4.2.13 a), and is reportable nr Fort St. Vrain Technical Specification I lol5l l AC 7.5_. 2(b) 2. No affect on public health or safetv. No accoreanvine occurrence or I IoleI l probable consequences. l lo171l I 101a 1 I I SG 7 8 9 6 00E AC E COMPONENT CODE SLB ODE Su CCE lo191 7 8 l Cl Bl@ l Xl@ l Z l@ l Zl Zl Zl Zl Zl Zlh lZ l@ W @

9 10 11 12 13 18 19 20

,,, SEQUENTIAL OCOURRENCE REPORT R EvlS3ON lea no EVENT YE AR R EPORT No. COCE *YPE No.

@ sug 1810 l as 21 22 l-l 23 l013l7I 24 26 I/I 27 l 0l 31 28 29 ltl 30 l-l 31 LO_j O

32 K N AC CN O P T ME HOURS SB t POR S. SUPPL E MANUP C RER l33X l@l34Z l@ lBl@ l Z l@ l 0 10 l 0 l 0 l [Y,_j@ l42Nl@ l43Z l@ (Z l9 l9 l947l@

35 2,6 31 40 el 44 CAUSE OESCRIPTION ANO CORRECTIVC ACTIONS @

r i g o ; l Removal of one PCRV liner cooling loop from service, coupled with three brief periods j

[ii,i j of reactor power operation, resulted in operatica in LCO 4.2.13 dMraded mode. Fol- !

i,121llowing the 1500 hour0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> reactor oower reading. no further deeraded _ mode eneration _j

[,l3l l occurred. By 1710 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.50655e-4 months <br />. construction work was comolete and the system returned to l 1t 141l normal. l 7 a 3 80 STI N %PCWER oTHER STATUS 15 DISCOVERY DESCRIPTION ,

l1 6 5 l l C l@ l 01 0l 1l@l N/A l l Al@l Personnel Observation / Review of Loes l )

ACTIVITY CO TENT AELEASE AMOUNT CP ACT)VifY LOCATION op RELEASE l i ( s j l Z l @D OP RELEASEy g l N/A l l N/A l 7 4 3 to 11 44 45 80 PERSONNEL EXPCSURES NUMBER TYPE CESCRIPTICN j l 1 I 71 l 0 ) 0 l 0 l@l Z j@l N/A l PERSONNE'L INJU ES NUMSER DESCRIPTION 11 15 110 l 0 l 0j@l N/A l 7 d 9 11 12 80 LOSS OP OR DAMAGE To PACILtTV TYPE OESCRIPTION .

I1 19 I l_Z_j@l N/A I

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7 8 9 10 80 i ISSU E E CRIPTION 12 I o I l N [@[_,.N/A l lll1ll1IIIlIli1 7 8 3 10 68 69 80 3 .

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