ML111661482

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

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: ML111661482 ML20003B795
References
LER-81-003-03L, LER-81-3-3L, NUDOCS 8102250560
Download: ML111661482 (3)

Text

REGULATORY INFORMATION DISTRIBUTION SOTEM (RIDS)

ACCESSION NBR:8102250560 DOCDATE: 81/02/20 NOTARIZED: NO DOCKET #

FACIL:50-305 Kewaunee Nuclear Power Plant, Wisconsin Public Servic 05000305 AUTHNAME AUTHOR AFFILIATION SMOKERC.S. Wisconsin Public Service Corp.

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

SUBJECT:

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 COPIES RECIPIENT COPIES ID CODE/NAME! LTTR ENCL ID CODE/NAME LTTR ENCL ACTION: VARGAS, 04 3 3 INTERNAL: A/D COMP&STRU06 I A/D ENV TECH 07 1 A/D MATL & GUO 1 A/D OP REACT009 1 A/D PLANT SYSIO 1 A/D RAD PROT 11 1 A/D SFTY ASSE12 1 ACC EVAL BR 14 1 AEOD 3 ASLBP/J.*HARD 1 AUX SYS BR 15 1 CHEM ENG BR 16 1 CONT SYS BR 17, I CORE PERF BR 18 1 DIRDIV OF LIC 1 DIRsENGINEERI20 1 DIRHUM FAC S21: 1 DIRSYS INTEG22 1 EFF TR SYS BR23 1 EQUIP QUAL BR25' 1 GEOSCIENCES 26, 1 I&C SYS BR 29 I I&Ei 05 2 JORDAN,E,/IE 1 LIC GUID BR 30. 1 MATL ENG BR 32" 1 MECH ENG BR 33 1 MPA 3 NRC PDR! 02 1 OP EX EVAL BR34 3 OR ASSESS.BR 35 1 POWER SYS BR 36 1 6R39 I REACT SYS BR 40 1 RE 01. 1 REL & RISK A 41 1 Y PROG EVA42 1 STRUCT ENG BR44 1 SYS INTERAC 845- 1 EXTERNAL: ACRS 46 16 16 LPDR 03 1 1 NSIC 05 1 1 TERA:DOUG MAY 1 1

?82 ygg TOTAL NUMBER OF COPIES REQUIRED: LTTR ;I ENCL i4

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 LICENSEE EVENT REPORT 1 cONTROL BLOCK: (PLEASE PRINT OR TYPE REQUIRED INFORMATION) 1 6 o I Wil INP 1140 010-1010101010 10-[00 25 2614 1111IU LICENSE TYPE 30 0 57 LI CAT 58 9 LICENSEE CODE 15 LICENSE NUMBER

-T SOURCE LjI0 15 10 10 j0 13 10 15 (1 0 1 12 12 18111 0 12 12 1 O 8j1J@

130 68 69 EVENT DATE 74 75 REPORT DATE 80 60 61 DOCKE rNUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES LON'TJ During testing of valve CC400B (Component cooling water inlet to lB residual heat O 18 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 I

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.

IL i1, so 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 2 IWB10 IL.IA L@ 12 Iv 13 IA IL IV 10IP Is L e 19 IZ 20 9 11 SEOUENTIAL OCCURRENCE REPORT REVISION TYPE NO.

LER[RO REOR EVENT YEAR 1~111 1-1 REPORT NO.

1010131 CODE 10 13 j LIL L-1 L NUMBER 21 22 23 24 26 27 28 29 30 31 32 SHUTDOWN ATTACHMENT NPRD 4 .PRIME CaMP. COMPONENT ACTION FUTURE EFFECT TAKEN xi@L2 ACTION ONFPLANT METHOD L

HOURS 1I0 0 I 22 SUBMITTED I INJ@ 1NJ FORM UB. SUPPLIER i IL 2 10 0 MANUFACTURER 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONSQ(

Themotor operator failure has been attributed to a wiring error by a plant electri U-16l I cian, which resulted in the thermal overloads tripping. The wiring fault was iden tified and corrected, and the valve/operator tested satisfactory. The procedure F1 was reviewed with the electrician. No further corrective action is necessary.

13 C

7 89 80 FACILITY METHOD OF OTHER STATUS & DISCOVERY DISCOVERY DESCRIPTION STATUS  % POWER

[if] LEi 7 8 9 10 1101 01@ 12 113NA 44 IB IO 45 Operability Test 0

ACTIVITY CONTENT NA LOCATION OF RELEASE RELEASED OF RELEASE AMOUNT OF ACTIVITY 4 NA 7

ElT 8

17J 1z 9

1_Z 10 NA 1144 45 8 -I

.0 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

[El8t910o0o S

0j37-1z 11 12 II NA 13 SD Bo PERSONNEL INJURIES NUMBER DESCRIPTIONS I

1] 01010 11 IgBI12 NA SD sU 7 8 9 LOSS OF OR DAMAGETO FACILITY TYPE DESCRIPTION

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7t 8 Izi! NA 9 10 NRC USE ONLY 80 PUBLICITY ISSUED DESCRIPTION@

[7 8L 1 0 NA 68 69 so 7 8 9 10 C, S. Smoker 414/388-2560 0 rNAMc Or oncEP F A PHOME: