05000255/LER-2077-044, License Event Report 1977-044-00 Re Turbine Load Limiter Switch

License Event Report 1977-044-00 Re Turbine Load Limiter Switch

ML18348A216
Person / Time
Site:	Palisades
Issue date:	09/22/1977
From:	Hoffman D Consumers Power Co
To:	James Keppler NRC/RGN-III
References
LER 1977-044-00
Download: ML18348A216 (2)

LER-2077-044, License Event Report 1977-044-00 Re Turbine Load Limiter Switch

Event date:
Report date:
2552077044R00 - NRC Website

text

consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201

• Area Code 517 788-0550 September 22, 1977 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regula.tory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PP..LISADES PL../'.\\NT - ER-77 TURBINE LOAD LIMITER SWITCH

.... :_,.,..::*~:...

• \\

. Attached is a reportable occurrence for the Palisades Plant.

David P Hoffman Assistant Nuclear Licensing Administrator CC:

ASchwencer, USNRC

r \\.

~..

J.ICENSEE EVENT REPORT

• a W

Palisades

~ CONT.flOL BLOCK: l..___.._.._I __..I __.l'---..._l __._.I (PLEASE PRINT ALL REQUIRED INFORMATION]

,._.~.*

1 6

LICENSEE NAME fJa!MI II Pl Al LI lj

. ~

14 LICENSE NUMBER I o I o 1-1 o I o I o I o I ol -1 o I o I 15 25 LICENSE TYPE 14111111111 26 30 EVENT TYPE Io 111 31 32 RETYPOPRTE.

REPORT SOURCE COCK~ NUMBER EVENT CATE REPORT CATE

@E]coN'T r

• 1 **I 7

0 57 58 L!I L&J 1015101-101215151 lo 19IO1817171 I o I 9 I 2 1-2 I 1 I 1 I 59 60

. 61 68 69 74 75 80

EVENT DESCRIPTION

1£§1 I During an unanticipated power runback caused by a sticking turbine load limiter 11lower 11 I 7

0 9 00 lol31 I switch, control rods were automatically inserted by the Reactor Regulating System to a I 7

8 9 80 Jol41 jpoint below the limi_ts of TS 3.10.5.a.

This event is similar to ER"".76-24.

Absence of I 7

8 9 80 lol51 l valid income alarms indicates no LHGR limits were exceeded.

Control rods were immedi-I 7

8 9 80 lolsl 1ately borated out with all rods being returned above the PDIL within 11 minutes.

)

7 8 9 PRIME (ER-77-44) so SYSTEM

CAUSE

COMPONENT COMPONENT COOE COOE COMPONENT COOE SUPPLIER MANUFACTURER VIOLATION

@El IHI A I 1£.J I II NI s IT I RI ul UI I zl 9 I 9 I 9 I w

7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION

• @Jfil I The Reactor Regulating System operated as programmed to insert rods 7

0 s during the load -run-I.

80 joj9j I back.

A Technical Specifications change has been submitted to make this type of

.nonreportable.

i.

7 FACILITY STATUS [ill]

L!.I 7

8 9

FORM OF METHOD OF

'l6 POWER OTHER STATUS DISCOVERY 111010 I l __

N_A _____ ~

10 12 13 44 45 ACTIVITY CONTENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY B]j L!J W

_I _, __

N_A ______,

7 8

9 10 11 44 45 P,ERSONNEL EXPOSURES NUMBER TYPE

DESCRIPTION

46 OISCOVERY DESCRIPTION PDIL Annunciation LOCATION OF RELEASE NA event I 80 I

80 80 80 (2)) IOI OI OI l.!j

.___N_A ____________________.._ ____ --.-________________ __.

7 8 9 11 12 13 80 PERS.ONNEL INJURIES NUMBER

DESCRIPTION

EEJ 10101 OI

,___N_A ______________________________________________ ___.

7 8 9 11 12 80 PROBABLE CONSEQUENCES [ill)

NA 7

8 9 80 LOSS OR DAMAGE TO FACILITY TYPE

DESCRIPTION

~

l&j

.___N~A ______________________ ~------------------------------------------__.

7 8 9 10 80 PUBLICITY (I0 NA 7

.ODITIONAL FACTORS 80

!1Ei NA 7

8 9 80 illfil 7

89 80