05000255/LER-1980-042, Forwards LER 80-042/01T-0

Forwards LER 80-042/01T-0

ML18046A156
Person / Time
Site:	Palisades
Issue date:	11/14/1980
From:	Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML18046A158	List: 05000255/LER-1980-042, Forwards LER 80-042/01T-0 05000255/LER-1980-042-01, /01T-0:on 801031,during Plant Cooldown,Steam Generator Dp Exceeded 1,380 Psid Limit for Approx 85 Minutes.Caused by Operator Misplotting of Power Conversion Sys Vs Pressure.Operator Counseled
References
NUDOCS 8011180730
Download: ML18046A156 (2)

LER-1980-042, Forwards LER 80-042/01T-0

Event date:
Report date:
2551980042R00 - NRC Website

text

consumem Power compa~w General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201

• Area Code 517 788-0550 November 14, 1980 Mr Jam.es G Keppler Office of Inspection and Enforcement Region III U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 -

LICENSE DPR PALISADES PLANT - LICENSEE EVENT REPORT 80-042 -

STE.AM GENERATOR EXCEEDED DP LIMIT On the reverse side is LER 80-042 which is reportable under Technical Specification 6.9.2.A(2).

David P Hoffman Nuclear Licensing Administrator CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector - Palisades Plant 8 0 I /l 8 0 7 ~6,.

NO\\fl 1 71 ~

1 PALISADES PLANT NRC FORM 366 (7-771 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: I 10 IPLEASE PRINT OR TYPE ALL REQUIRED INFORMATION!

1 6

[£LJ ~r I PIA IL 11 101 o I 01-I o I 01 o I 01 o I -10 Io 1014 111 111 I 1101 I 10 7

S 9

LICENSEE CODE 14

,5 LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 58 CON'T [ili]

7 8

~:~~~~I 01 5101 010 I 21 515K2)111 013 111 8!0 KVl1 111ii4 I 8 lo 10 60 61 DOCKET NUMBER 68 69 EVENT CATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

((ID I During plant cooldown. stea.~ generator dp PXCPeded the 1380 psid Jjmit o~

[QJI] I TS 3.1.le for approx 85 minutes.

max.dp was 1590 psid.

Upon discovery,

((ID PCS press.was reduced to return dp to within limits.

Event reportable per1

((II) I TS 6.9.2.A2.

Secondary water analyses and stress calculations were per-

[QJI]

formed and indicated that S/G tube integrity was maintained.

See LER

[£Jil I 78-23 for similar occurrence.

No threat to public health or safety I

• [)))) resulted.

7 8 9 SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCOOE COMPONENT CODE SUB CODE [ill]

I HJBI@ LAJ@ w@ IHI Tl SUBCOCE EIX ! Cl HJ@ l!'..J@ ~@

7 a

9 10 11 12 13 18 19 20

@ LERIRQ CVENTYEAR SEQUENTIAL OCCURRENCE REPORT REPORT NO.

CODE REPORT I 8 I 01 l=1 10 I 412 I,

~ 11 NUMBER 21 22 23 24 26 27 28 ACTION FUTURE EFl"ECT SHUTDOWN

~

ATTACHMENT TAKEN ACTl0"1 ON PLANT METHOD HOURS SUBMITTED W@l..U@ W@

l.&J@)

I 01 01 o I I I NJ@

JJ 34 35 J6 37 40 41 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

TYPE I

LU l:=J 29 JO NPRQ.4 FORM~UB.

L!J@)

42 31 PRIME COMP.

SUPPLIER l!J@

43 REVISION ND.

LQJ' 32 COMPONENT MANUFACTURER 80 I c I 419 Io l@

47 I The operator monitoring the cooldown did not note the out of spec.

[J))] ~-~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~'"--~~~~~~

1JJJJ I condition.

A plot of PCS temp vs Press was being kent but the nress data o:J}] 1was misplotted, such that the plotted data aPPeared to be in limits.

The DJ)) I onerator involved has been counseled regarding his responsibilities; lJJ3] t additional disciPlinary action has been taken with shift nersonnel inyolyed.

8 9

FACILITY

/jQI STATUS

% POWER OTHER STATUS i.;:::;

[2J]J I GI@ I 0 IO I 0 l@I Plant Cooldown l 80 METHOD OF r:;::;..,

DISCOVERY DISCOVERY DESCRIPTION (5/

LA.J~I Observation 8

9 10 12 13 44 ACTIVITY CONTENT Q.,

RELEASED OF RELEASE AMOUNT OF ACTIVITY ~

G:ill LzJ @ LzJ@I N~

I 7

9 9

10 11 44 45 4S 80 LOCATION OF RELEASE@

45 Ti 80 PERSONNEL EXPOSURES Q..

NUMBER A

TYPE

DESCRIPTION

QTI I 0 I 01 0 l'8W@1....-___,N;!.i.JA~. ____________________ ___,

7 B

9 11 12 13 80 PERSONNEL 1"1JURIES

~

. NUMBER DESCRIPT10"1~

~

I 0' 010 1@1.--___

N_A _____________________ __

1 a s 11 12 so LOSS oc DR DAMAGE TO FACILITY t4:J'I TYPE

DESCRIPTION

\\:,;/

~~@

NA 7

8 9

10 so PWBLICITY Q\\

NRC USE ON' Y ISSUED(."";\\ DESCRIPTION~

~

l2El W\\~......._ ______

..:;.~'.-..'*---------------___, I I I I 1. I I I I I I I J a s 10 68 69 so