05000267/LER-1981-045-03, /03L-0:on 810727,during Normal Startup Operation, Primary Coolant Dewpoint Exceeded Tech Spec Limits.Caused by Contamination Due to Moisture.Contaminants Removed from Primary Coolant

/03L-0:on 810727,during Normal Startup Operation, Primary Coolant Dewpoint Exceeded Tech Spec Limits.Caused by Contamination Due to Moisture.Contaminants Removed from Primary Coolant

ML20010G169
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/26/1981
From:	Mcbride M PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20010G153	List: 05000267/LER-1981-045, Forwards LER 81-045/03L-0.Detailed Event Analysis Encl 05000267/LER-1981-045-03, /03L-0:on 810727,during Normal Startup Operation, Primary Coolant Dewpoint Exceeded Tech Spec Limits.Caused by Contamination Due to Moisture.Contaminants Removed from Primary Coolant
References
LER-81-045-03L, LER-81-45-3L, NUDOCS 8109150401
Download: ML20010G169 (1)

LER-1981-045, /03L-0:on 810727,during Normal Startup Operation, Primary Coolant Dewpoint Exceeded Tech Spec Limits.Caused by Contamination Due to Moisture.Contaminants Removed from Primary Coolant

Event date:
Report date:
2671981045R03 - NRC Website

text

U. 5. NUCLEAR REGULATORY COMMISSION

. N C PQ'.M 366 (7 77) '.

' 8CENSEE EVENT REPORT CONTROL BLOCK: l l

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lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) i e

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7 8 9 LICENSEE CODE 14 15 LICENSE NLM8ER 26 26 LICENSE TYPE JO SF W. $8 CON'T l0l1l SO Ry l L}@l 01 510 l 0 l 0 l 2 l 6 I 7 @l0 l7 12 17 18 11 @l0l8l2I6I8l1l@

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60 61 OOCKET NUM8ER 68 69 EVENT OATE 74 75 REPCR f OATE 80 EVENT DESCRIPTION AND PRC9 ABLE CONSEQUENCES h 1012l l During normal startup operation, the primarv Coolant dewooint exceeded the limits of 1 io,3; ; Figure 4.2.11-1 of LCO 4.2.11.

This is reportable as a degraded mode of LC0_4.2. ll l

l c i4 I I per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

No accO=panying occurrence. l lo (si i No affect on public health cr safety. Related reports are 77-13, 78-16, 78-39, 79-43,1 lo !s ] l S0-19, 80-33, 80-36, and 81-009.

10171 I I

I I o is i I 80 7

8 9 SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUSCODE COMPONENT CODE SUSCODE SueCODE 10191 I ci sl@ l xi@ l z l@ Iz Iz I z Iz lz Iz l@ l zl@ LIJ @

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9 to 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT R EVISION LE RcRO EVENT VE AR REPORT NO.

CODE TYPE N O.

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40 el 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l i l O f l During reactor refueling and maintenance, the primarv coolant became contaminated I

i1 ;il [ with mois ture.

The rise-to-power was delayed according to mois ture level and the I i 6 21 l primary coolant purification train removed the contaminates from the primary coolant. ;

l tilaiI l

11 141 I 80 7

8 9 SA

% POWER OTHER STATUS 31S RY DISCOVERY OESCRIPTION 11 15 ! d@ l0 l 2 l 8 l@l N/A l

[Aj@l Goerator Observatien l

ACTivtTY CO TENT RELEASED AMOUNT OF ACTiv1TY LOCATION OF RELEASE W l zl @08 RELEASE l z l@l N/A l

l N/A l

7 8 9 10 11 4aa 45 80 PERSONNEL EXPOSURES NUV8ER TYPE

DESCRIPTION

l li l 71 l 01 Ol O hl z hl N/A PeRSONNE'L iN3uWiES DESCRIPTION @

NUMBER lTT110101Ol@l N/A I

80 7

8 9 11 12 LOSS OF OR OAMAGE TO FACILITY TYPE

DESCRIPTION

11191 l zi@l N/A l

80 7

8 9 10 ISSUEf@ DESCRIPTION lN l N/A I

l l l I I l l l l l l I l *4 l,2_[o_j 68 69 80 3 7

8 9 10 8109150401 810826 N Weg.I/v (30 3) 785-2224 2

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