05000305/LER-1981-003-03, /03L-0:on 810122,supply Thermal Overloads Tripped During Testing of Valve CC400B (Component Cooling Water Inlet to Residual Heat Exchanger 1B).Caused by Wiring Error. Wiring Fault Identified & Corrected

/03L-0:on 810122,supply Thermal Overloads Tripped During Testing of Valve CC400B (Component Cooling Water Inlet to Residual Heat Exchanger 1B).Caused by Wiring Error. Wiring Fault Identified & Corrected

ML111661482
Person / Time
Site:	Kewaunee
Issue date:	02/20/1981
From:	Smoker C Wisconsin Public Service Corp
To:	NRC/OI/RGN-III/FO
Shared Package
ML111661483	List: 05000305/LER-1981-003, Forwards LER 81-003/03L-0 05000305/LER-1981-003-03, /03L-0:on 810122,supply Thermal Overloads Tripped During Testing of Valve CC400B (Component Cooling Water Inlet to Residual Heat Exchanger 1B).Caused by Wiring Error. Wiring Fault Identified & Corrected
References
LER-81-003-03L, LER-81-3-3L, NUDOCS 8102250560
Download: ML111661482 (3)

LER-1981-003, /03L-0:on 810122,supply Thermal Overloads Tripped During Testing of Valve CC400B (Component Cooling Water Inlet to Residual Heat Exchanger 1B).Caused by Wiring Error. Wiring Fault Identified & Corrected

Event date:
Report date:
3051981003R03 - NRC Website

text

REGULATORY INFORMATION DISTRIBUTION SOTEM (RIDS)

ACCESSION NBR:8102250560 DOCDATE: 81/02/20 NOTARIZED: NO FACIL:50-305 Kewaunee Nuclear Power Plant, Wisconsin Public Servic AUTHNAME AUTHOR AFFILIATION SMOKERC.S.

Wisconsin Public Service Corp.

RECIP.NAME RECIPIENT AFFILIATION Region 3, Chicago, Officetof the D4rector

- SUBJECT:

DOCKET #

05000305 LER 81-003/03L*0:on 810122,supply thermal overloads tripped during testing of valve CC400B (component cooling.water inlet to residual heat exchanger 1B).Caused by wiring error, Wiring fault identified & corrected, DISTRIBUTION CODE: A0028 COPIES RECEIVED:LTR LENCL 4.,

SIZEUZ"L/t..

TITLE:-Incident Reports NOTES:I&E:3 copies all material.

05000305 RECIPIENT ID CODE/NAME!

ACTION:

VARGAS, 04 INTERNAL: A/D COMP&STRU06 A/D MATL & GUO A/D PLANT SYSIO A/D SFTY ASSE12 AEOD AUX SYS BR 15 CONT SYS BR 17, DIRDIV OF LIC DIRHUM FAC S21:

EFF TR SYS BR23 GEOSCIENCES 26, I&Ei 05 LIC GUID BR

30.

MECH ENG BR 33 NRC PDR!

02 OR ASSESS.BR 35 6R39 RE

01.

Y PROG EVA42 SYS INTERAC 845-COPIES LTTR ENCL 3

3 I

1 1

1 3

1 I

1 1

1 1

2 1

1 1

1 I

1 1

1 RECIPIENT ID CODE/NAME A/D ENV TECH 07 A/D OP REACT009 A/D RAD PROT 11 ACC EVAL BR 14 ASLBP/J.*HARD CHEM ENG BR 16 CORE PERF BR 18 DIRsENGINEERI20 DIRSYS INTEG22 EQUIP QUAL BR25' I&C SYS BR 29 JORDAN,E,/IE MATL ENG BR 32" MPA OP EX EVAL BR34 POWER SYS BR 36 REACT SYS BR 40 REL & RISK A 41 STRUCT ENG BR44 COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 I

1 1

3 3

1 1

1 1

EXTERNAL: ACRS NSIC 46 05 16 1

16 1

LPDR 03 1

TERA:DOUG MAY 1

?82 ygg TOTAL NUMBER OF COPIES REQUIRED: LTTR 1

1 i4

I ENCL

NRC-81-27 WISCONSIN PUBLIC SERVICE CORPORATION P.O. Box 1200, Green Bay, Wisconsin 54305 February 20, 1981 Mr. J. G. Keppler, Regional Director Office of Inspection & Enforcement Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

Dear Mr. Keppler:

Docket 50-305 Operating License DPR-43 Reportable Occurrence LER 81-003/03L-0 In accordance with the requirements of Technical Specifications, Section 6.9, the attached Licensee Event Report for reportable occurrence LER 81-003/03L-0 is being submitted.

Very truly yours, E. R. I thews, Vice President Power Supply & Engineering snf Attach.

cc - Dir, Office of Inspection & Enforcement A 0 US NRC, Washington, DC 20555 Dir, Office of Mgt Info & Program Control US NRC, Washington, DC 20555 Mr. W. Lavallee, NSAC PO Box 10412, Palo Alto, CA 94303 Mr. Robert Nelson, NRC Resident Inspector RR #1, Box 999, Kewaunee, WI 54216 i.EB 2 4. 1984

- 111 o

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- T 130 LON'TJ O

1 8 7

8 7 2 9

SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE IW B IL.IA L@ Iv IA IL IV 10 IP I L e IZ 9

10 11 12 13 s

19 20 SEOUENTIAL OCCURRENCE REPORT REVISION LER[RO EVENT YEAR REPORT NO.

CODE TYPE NO.

1~

REOR 111 1-1 1 010131 10 13 j L

LI L-1 L

NUMBER 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD 4

.PRIME CaMP.

COMPONENT TAKEN ACTION ONFPLANT METHOD HOURS 22 SUBMITTED FORM UB.

SUPPLIER MANUFACTURER xi@L2 1I0 L

0 I I IN J@ 1 NJ i

IL 2 10 0 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONSQ(

I Themotor operator failure has been attributed to a wiring error by a plant electri cian, which resulted in the thermal overloads tripping. The wiring fault was iden tified and corrected, and the valve/operator tested satisfactory. The procedure was reviewed with the electrician. No further corrective action is necessary.

7 89 FACILITY STATUS

% POWER OTHER STATUS &

[if] LEi 1101 01@ 1 NA 7

8 9

10 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY ElT 1z 7 J 1

1_Z NA 7

8 9

10 1144 PERSONNEL EXPOSURES NUMBER TYPE

DESCRIPTION

[El 10o0o 0j37-1z II NA S

8t9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONS 1] 01010 IgBI NA 7

8 9

11 12 LOSS OF OR DAMAGETO FACILITY TYPE

DESCRIPTION

[LE] Izi! NA 7t 8

9 10 PUBLICITY ISSUED DESCRIPTION@

[7 8L 1

0 NA 7

8 9

10 C, S. Smoker F A C

METHOD OF DISCOVERY DISCOVERY DESCRIPTION IB IO Operability Test 45 NA LOCATION OF RELEASE 4 NA 45 8

80 0

- I

.0 SD SD 80 NRC USE ONLY 68 69 so 414/388-2560 0

LICENSEE EVENT REPORT cONTROL BLOCK:

(PLEASE PRINT OR TYPE REQUIRED INFORMATION) 1 6

Wil INP 1 0 010-1010101010 10- [00 14 1111IU 0 LI 9

LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 SOURCE LjI0 15 10 10 j0 13 10 15 (1 0 1 12 12 1 81 11 0 12 12 1 O 8j1J@

60 61 DOCKE rNUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES During testing of valve CC400B (Component cooling water inlet to lB residual heat exchanger) following the reinstallation of the motor operator, the supply thermal overloads tripped.

This put the facility under LCO T.S. 3.3.a.2.C (one RHR heat ex changer may be out of service for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) and thus is reportable per T.S.

6.9.2.b.2.

Since this valve was manually operable, and the second RHR heat exchanger was available, there was no effect on public safety or plant operation.

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