ML20028G271

LER 82-054/03L-0:on 821229,outlet Temps Exceeded 120 F Limit When Reactor Became Critical During Isolation of Svc Water Flow to Pcrv Cooling Water Hx.Caused by Lack of Cooling Source.Design Change Initiated

ML20028G271
Person / Time
Site:	Fort Saint Vrain
Issue date:	01/28/1983
From:	Fuller C PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20028G266	List: ML20028G265 ML20028G271
References
LER-82-054-03L, LER-82-54-3L, NUDOCS 8302070579
Download: ML20028G271 (1)

Text

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NRC FORM 364 U. S. NUCLEAR REEULATORY COMMIS$40N LICENSEE EVENT REPORT

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(PLE ASE PRINT OR TYPE ALL REoulRED INFORMATioN) foTi18 I c l 01 F l S l V l 1 l@l le 15 u 10 l- 101010 la 10 l- lu l 026 l@l26 4l LICENSE LICENSE c.a:.W ER l l1 l 2TYPE l uJol@l61LAT58 l l@

P 'J LICENSE E CODE con'T 7

Iolil $'RC[ l L j@l 0 l 5 l 0 l 0 l 0 l 2 l 6 l 7)@l 6J 1 1212 l9 l 8 l 742 l@l 75 01REPORT 1 l 2181813 C ATE 80 l@

7 8 60 6' DOCK ET NUMBER bd EV ENT D ATE EVF.NT oESCRIPTioN AND pro 6ABLE CONSEQUENCES h 10121 l The service water flow to the PCRV cooling water heat exchangers were isolated to l .

fiTTTl I help maintain the temperatum of the PCRV cooling water system when the reactor was l

[ 0 ,41 l in a shutdown condition. The outlet temperatures exceeded the 120*F limit soecified i r; p;-) l by LCO 4.2.lSlb) when the reacto. was taken critical. This is reportable as a de- l 0 s l graded mode of LC0 4.2.15(b) per Fort St. Vrain lechnical Specification AC 7.5.2(b)2.i ITT71 L No accompanying occurrences. No effect on public health or safety. Related occur- l

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rences are R0's82-045, 82-043,81-048, 81-007,81-001, 80-46, 79-07, and 7/-28. l

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7 8 9 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION +

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33 34 JS 36 31 40 42 43 44 47 CAUSE oESCRIPfloN AND CORRECTIVE ACTIONS h i O l With the service water flow isolated to the PCRV cooling water exchangers, no coolingg g i source was available when the reactor was taken critical. Service water was restomdi

, g to the exchangers. Operation of the PCRV cooling water system will be myiewed with i gl all licensed operators. A design change is in proqress to nrovide early warnina of I g

such conditions approaching. No further corrective action is anticipated or required.i 7 8 9 80 ST US  % POWER OTHER STATUS DISCO DISCOVERv OESCRIPTION

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7 8 9 10 11 PERSONNEL EXPOSURES NUMF E R TYPE DESCRIPTION Ltuj 1010 ! o l@LZ_J@l N/A l

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