ML20010G169

From kanterella
Revision as of 09:15, 17 February 2020 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
LER 81-045/03L-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
ML20010G169
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
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:
References
LER-81-045-03L, LER-81-45-3L, NUDOCS 8109150401
Download: ML20010G169 (1)


Text

. N C PQ'.M 366 U. 5. NUCLEAR REGULATORY COMMISSION (7 77) ' .

' 8CENSEE EVENT REPORT (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

CONTROL BLOCK: l i

l l l l l lh e

10 t 8il 9[ Cl Ol Fl Sl V! II@l O  ! Ol -l 0 $ GM l 0 l 0 l - l 0 l 0 l@l 26 4 l 1LICENSE 26 l l l 2TYPEl OJOl@lSF lj@

W. $8 7 LICENSEE CODE 14 15 LICENSE NLM8ER CON'T l0l1l SO Ry l L}@l 01 510 l 0 l 0 l 2 l 686 I 697 @l0 l7 12 17 18 11 @l0l8l2I6I8l1l@

EVENT OATE 74 75 REPCR f OATE 80 7 8 60 61 OOCKET NUM8ER 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.  !

I 10171 I I

I o is i I 80 7 8 9 COMP.

SYSTEM CAUSE CAUSE VALVE CODE CODE SUSCODE COMPONENT CODE SUSCODE SueCODE 10191 7 8 I ci sl@ l xi@ l z l@ Iz Iz I z Iz lz Iz l@ l zl@ LIJ @

9 to 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT R EVISION EVENT VE AR REPORT NO. CODE TYPE N O.

LE RcRO

@yuga; aE l8l1l l-l 10l4l5l l/l (013 l l LI l-l l0 l 23 24 26 27 28 7 30 31 J2

_ 21 22 .

TK N AC ON ON P NT MET HoVR$ 58 i F R 1 Su PLIER MANUFAC ER LxJ@L:J@ L:J@ L2J@ loIoIoIoI lxJ@ Ls1@ L1_l@ l44z I 9 19 1947l@

33 34 35 36 3/ 40 el 42 43 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 l l N/A l W l 8zl9 @08 RELEASE l z l@l N/A 7 10 11 4aa 45 80 PERSONNEL EXPOSURES NUV8ER TYPE DESCRIPTION li l 71 l 01 Ol 'O hl z hl" N/A "

l PeRSONNE'L iN3uWiES NUMBER DESCRIPTION @

I lTT110101Ol@l 7 8 9 11 12 N/A 80 LOSS OF OR OAMAGE TO FACILITY TYPE DESCRIPTION l

11191 7 8 9 l zi@l10 N/A 80 l,2_[o_j lN l N/ADESCRIPTION ISSUEf@ I l l l I I l l l l l l I l *4 7 8 9 10 68 69 80 3 8109150401 810826 N Weg .I/v

" U"'; (30 3) 785-2224 2 PDR ADOCK 05000267 S PDR _ _ _ _ _ _ _ . _ _ _

- __ __ _ _ ..._, _ __.__ _,_ _ . . _ _ _ _ . . _ _ _