05000255/LER-1980-007-01, /01T-0:on 800407,during Maint on Control Room Ventilation Sys,Discovered Leakage Defects Through Shaft of Fan V-36.Fresh Air Damper D-1 Would Not Close.Caused by Inadequate pre-operational Testing of Ventilation Sys

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/01T-0:on 800407,during Maint on Control Room Ventilation Sys,Discovered Leakage Defects Through Shaft of Fan V-36.Fresh Air Damper D-1 Would Not Close.Caused by Inadequate pre-operational Testing of Ventilation Sys
ML18044A783
Person / Time
Site: Palisades Entergy icon.png
Issue date: 04/21/1980
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML18044A780 List:
References
LER-80-007-01T, LER-80-7-1T, NUDOCS 8004250358
Download: ML18044A783 (3)


LER-1980-007, /01T-0:on 800407,during Maint on Control Room Ventilation Sys,Discovered Leakage Defects Through Shaft of Fan V-36.Fresh Air Damper D-1 Would Not Close.Caused by Inadequate pre-operational Testing of Ventilation Sys
Event date:
Report date:
2551980007R01 - NRC Website

text

PALISADES PLANT NRC FORM 366 (7-77)

U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: j

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(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

[IT2J I M I I I p I A IL I I 101 0 I 0 I-I 0 I 0 I 0 I 0 I 0 I - 10 I 0 101 4 j l I 1 11 I 1 101 I I 0 7

B 9

LICENSEE CODE 14

~5 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T filTI 7

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=;~~~~ l1._1© I o I 5 I o I o I o I 2 I 5 I 5 101 o I 4 I o 17 I 8 I o I© lo I 4 I 2 11 I s I o I CV 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES @

I During maintenance on the control room ventilation system, two defects

((ill I which would have permitted large inleakage of contamination into the

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I control room under accident conditions were discovered.

The defects were CQJIJ I large leakage through the shaft of fan V-36 and a fresh air damper (D-1)

!Im I which won1 a not f1111;,ir cl ase As a result, during an accident with high

[£]2J I airborne activity outside containment, the control room may not have been ITJ)) I habit able.

Reportable per T*. S. 6. 9. 2. a. 9.

I 7

B 9 80 SYSTEM

CAUSE

CAUSE CODE CODE SUBCOOE COMPONENT CODE ETIJ Is !GI@ lli.J@ W@ lz lzlz lz lzl zl@

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9 10 11 12 13 1B SEQUENTIAL OCCURRENCE REPORT NO.

CODE l=.J 1010111

~ 10111 23 24 26 27 28 29

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LERIRO CVENTYEAR

\\}..:/ REPORT

~ 10 I NUMBER 21 22 COMP.

SUBCOOE

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19 REPORT TYPE l!J 30 VALVE SUBCODE

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20 l:::J 31 PRIME COMP.

REVISION NO.

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32 COMPONENT ACTION FUTURE EFFECT SHUTDOWN r:;:::;..

ATTACHMENT NPRD-4 TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM $UB.

SUPPLIER MANUFACTURER W@~@ W@ W I 010 I 01 01 L.!J@

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33 34 35 36 3 7 40 41 42 LU I z I 919 191@

CAUSE DESCRIPTION AND CORR EC rive ACTIONS @

43 44 47 [J]I] I The initial pre-op testing of the control room vent system was apparently OJI] I inadequate.

The defects have been corrected.

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FACILITY

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STATUS

.% POWER OTHER STATUS ~

EE LQJ@ I 0 JO I 0 l@.__IN_A ____ _

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10 12 13 44 ACTIVITY CONTENT Qi RELEASED OF RELEASE AMOUNT OF ACTIVITY ~

l2El Ul@ W@.__I _N_A ______

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9 10 11 44 PERSONNEL EXPOSURES

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METHOD OF DISCOVERY DISCOVERY DESCRIPTION 32

~~!Discovered during mainten nee 45 46 NA LOCATIO.N OF RELEASE @

45 80 80 60 NUMBER

~TYPE

DESCRIPTION

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11 12 13 PERSONNEL INJURIES

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NUMBER DESCRIPTION~

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NRC USE ON Ly [ill] LIJ6~=NA=-=--------'----------------J I I I I I I *I I I I I I I 7

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10 68 69 80

consumers Power company General Offices: 212 West Mlcfilgan Avenue, Jackson, Michigan 49201 * (517) 788-0550 April 21, 1980 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - LICENSEE EVENT REPORT 80-006 - PURGE VALVE T-RING AIR SUPPLIES On the reverse side is Licensee Event Report 80-006 which is reportable under Technical Specification 6.9.2.B.4.

David P Hoffman Nuclear Licensing Administrator CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector-Palisades APR 2 3 1980

PALISADES PLANT NRC FORM366 l7-n1 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: I IQ (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

[B:!J I Ml I Ip I A IL 11 101 0 I 0 I - I 0 I 0 I 0 10 I 0 I - 10 I 0 1014 11 11 111 i 101 I J © 7

8 II LICENSEE CODE 14

,5 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T [BI]

7 8

~~~~~~ ~I o I 5 I o I o I o I 2 I 5 I 5 K?)l l I 111 I o I 7 I 9 @I o 14 I 2 11 I 8 I 0 10 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

I During routine surveillance of containment purge valves, it was found that!

the redundant T-rjng air supplies for the 12-incb and 48-incb purge valves!

~

had leakage in excess of acceptance criteria.

Normal air supply was [Q))J operable.

Condition classified reportable under TS 6.9.2.B.4 on 3-21-80.

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((ill 7

B 9 SYSTEM

CAUSE

CAUSE CODE CODE SUBCODE COMPONENT CODE IITIJ ISIDI@ ~@ ~@ !V!AIL1V1E1X1@

7 B

9 10 11 12 13 18 SEOUENTIAL OCCUR REN CE REPORT NO.

COOE 1010161 10131 23 2*

26 27 28 29 t::::..

LE R /RO LVENT YEAR

\\!:.,/ REPORT I 8 I 0 I NUMBER 21 22 COMP.

VALVE SUB CODE SUBCODE w w@

19 20 REPORT TYPE L!:.J 30 l=l 31 PRIME COMP.

REVISION NO.

LQJ 32 COMPONENT so TAKEN ACTIOll/

ON PLANT METHOD HOURS 22 SUBMITTED ACTION FUTURE EFFECT SHUTDOWN

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ATTACHMENT NPRO-<l FORM SUB.

SUPPLIER MANUFACTURER lEJ@LBJ@

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33 34 35 36 37 40 41 l.IJ§ W IF 11 I 215 I@

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

42 43 47

[)))) I Leaks were primarily through fittings and valve packings.

Replaceinent [II3J of CV-1806 and CV-1807 with blank flanges has been completed.

Repairs [JJ))

to T-ring air supplies to CV-1812 and 1814 will be completed prior to ITTIJ I start-up.

IIill 7

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OTHERSTATUS @

FACILITY STATUS

% POWER EE W@ la I a I al@l~N

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METHOD OF A

DISCOVERY DISCOVERY DESCRIPTION 6 LBJ@! Rlral1rn+ion of Test Res111ts 80 8

9 10 12 13 44 ACTIVITY CONTENT C,.

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46 80 RE LEASED OF RELEASE AMOUNT OF ACTIVITY ~

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9 10 11 LOCATION OF RELEASE @

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NUMBER

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9 11 12 LOSS Q< OR DAMAGE TO FACILITY '43' TYPE

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BO NA

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