05000267/LER-1980-037-03, /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

/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: 05000267/LER-1980-037, Forwards LER 80-037/03L-0 05000267/LER-1980-037-03, /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
References
LER-80-037-03L, LER-80-37-3L, NUDOCS 8008130514
Download: ML19331B908 (1)

LER-1980-037, /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

Event date:
Report date:
2671980037R03 - NRC Website

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

O LICENSEE EVENT REPORT V

CONTROL BLOCK: l l

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7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE Jo 57 CAT 58 CON'r lolIl l L hl 0l 5 l 0 l 0 l O l 216 I 7 @l,_Q l 7 I 1 l1 l 8 l 0 hl 0l 8l 0l 8l 8l 0l@

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8 60 61 QoCKET NUMBER 68 69 EVENT D ATE 74 75 REPORT DATE 80 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.

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00E AC E COMPONENT CODE SLB ODE Su CCE lo191 l Cl Bl@ l Xl@ l Z l@ l Zl Zl Zl Zl Zl Zlh lZ l@ W @

7 8

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 l-l l013l7I I/I l 0l 31 ltl l-l LO_j as O

21 22 23 24 26 27 28 29 30 31 32 K N AC CN O P T

ME HOURS SB t POR S.

SUPPL E MANUP C RER l X l@l Z l@

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33 34 35 2,6 31 40 el 42 43 44 47 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

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[,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.

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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

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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

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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

7 8 9 10 80 i

12 I o I l N [@[_,.N/A l

lll1ll1IIIlIli ISSU E E CRIPTION 1

7 8 3 10 68 69 80 3 b '"

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