ML18348A216

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)

Text

consumers

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

• Area Code 517 788-0550 September 22, 1977

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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

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J.ICENSEE EVENT REPORT

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• W Palisades

~ CONT.flOL BLOCK: l..___.._.._I__..I__.l'---..._l__._.I (PLEASE PRINT ALL REQUIRED INFORMATION]

...;,._.~ .* 1 6 LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE fJa!MI II Pl Al LI lj I o I o 1-1 oI oI oI oI ol -1 o I o I 14111111111 Io 111

. ~ 14 15 25 26 30 31 32 RETYPOPRTE. REPORT REPORT CATE r57*1**I SOURCE COCK~ NUMBER EVENT CATE

@E]coN'T L!I L&J 1015101-101215151 lo 19IO1817171 I oI 9 I 2 1- 2 I 1I 1I 7 0 58 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 lower I 11 11 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 7

@El IHI A I 8 9 10 1£.J 11 I II NI s IT I RI ul 12 17 UI 43 I zl 9 I 9 I 9 I 44 . 47 w48 CAUSE DESCRIPTION

• @Jfil I The Reactor Regulating System operated as programmed to insert rods during the load -run-I .

7 0 s 80 joj9j I back. A Technical Specifications change has been submitted to make this type of event I 80 i.

.nonreportable.

7 FACILITY STATUS

'l6 POWER OTHER STATUS METHOD OF DISCOVERY OISCOVERY DESCRIPTION 80 I

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7 8 9 L!.I 111010 I 10 12 13 l _ _N_A_____

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45 46 PDIL Annunciation 80 FORM OF ACTIVITY CONTENT B]j L!J RELEASEO OF RELEASE W AMOUNT OF ACTIVITY

_I_,_ _N_A______, LOCATION OF RELEASE NA 7 8 9 10 11 44 45 80 P,ERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION (2)) IOI OI OI l.!j .___N_A____________________.._____--.-__________________.

7 8 9 11 12 13 80 PERS.ONNEL INJURIES EEJ NUMBER 10101 OI DESCRIPTION

,___N_A_________________________________________________.

7 8 9 11 12 80 PROBABLE CONSEQUENCES

[ill) NA .

7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION

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7 8 9 10 80 PUBLICITY (I0 NA 7 80

.ODITIONAL FACTORS

!1Ei NA 7 8 9 80 7

illfil89 80