ML112900678

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LER 80-006/03L-0:on 800226,during Refueling Outage,Seven of Main Steam Line Area Temp Switches Found to Trip Above Required Level.Caused by Setpoint Drift.Switches Recalibr
ML112900678
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 03/26/1980
From: Hill W
Northern States Power Co
To:
NRC/OI/RGN-III/FO
Shared Package
ML112900679 List:
References
LER-80-006-03L, LER-80-6-3L, NUDOCS 8003310362
Download: ML112900678 (3)


Text

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REGULATORY IWORMATION DISTRIBUTION SYS*

ACCESSION NBR:8003310362 DOCDATE: 80/03/26 NOTARIZED: NO (RIDS)

FACIL:50-263 Monticello Nuclear Generating Plant, Northern States AUTH.NAME AUTHOR AFFILIATION DOCKET #

05000263 HILLW.J. Northern States Power Co.

RECIPNAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director

SUBJECT:

LER 80-006/03L-O:on 800226,during refueling outagerseven of main steam line area temp switches found to trip above required level.Caused by setpoint drift.Switches recalibr, DISTRIBUTION CODE: A00S2 COPIES RECEIVED:LTR t ENCL / SIZE:.L.) ...

TITLE: Incident Reports NOTES: ---

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL ACTION: 05 BC OIqe #.3 4 4 INTERNAL: 0 G 1 02 NRC PDR 1 2 11 MPA 3 14 TA/EDO 1 15 NOVAK/KNIEL 1 16 EEB 1 17 AD FOR ENGR 1 18 PLANT SYS BR 1 19 I&C SYS BR 1 20 AD PLANT SYS 1 22 REAC SAFT BR 1 23 ENGR BR 1 24 KREGER 1 25 PWR SYS BR 1 26 AD/SITE ANAL 1 27 OPERA LIC BR 1 28 ACDENT ANLYS 1 29 AUX SYS BR 1 AD/ORP*DOR 1 AEOD 1 DOUG MAY*TERA 1 HANAUERS. 1 IRELANDR. 3 JORDANE./IE 1 EXTERNAL: 03 LPDR 1 1 04 NSIC 1 1 29 ACRS 16 16 Npp, 11980 W 0 TOTAL NUMBER OF COPIES REQUIRED: LTTR 52 ENCL 52

'A 0 NORTHERN STATES POWER COMPANY MINNEAPOLIS. MINNESOTA 55401 March 26, 1980 Mr J G Keppler Office of Inspection & Enforcement U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

Dear Mr Keppler:

MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Main Steam Line Area Temperature Switch Setpoint Drift The Licensee Event Report for this occurrence is reproduced on the back of this letter. Enclosed are three copies.

This event is reported in compliance with Technical Specification 6.7.B.2.a. Several main steam line area temperature switches were found to have drifted a small amount. Redundant switches were found to be within specified limits.

Yours very truly, L 0 Mayer, PE Manager of Nuclear Support Services LOM/DMM/ak cc: 'DIrector, IE, USNRC (30)

Director, MIPC, USNRC (3)

MPCA Attn: J W Ferman,

-over-0.

8003310 5 5'9

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7-77)

LICENSEE EVENT REPORT CONTROL BLOCK: (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

[L1 I MI 7 8 9 NIM IN IP l Il1l LICENSEE CODE 14 15 oll -1 01 olo 10 10 1- 1010 LICENSE NUMBER 25 26 14 11 11iolIJ.

LICENSE TYPE 30 57 CAT 58 CON'T REPORT .~

7 8 SOURCE L J 0 1 5 1 0 1 0 1 012 16 31 0 1212 161 8 1O_l l 0 13 12 16 1 8 I0 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES I During a refueling outage surveillance test. seven of the main steam line area

[ OT l temperature switches were found to trip slightly above ( 7 F) the allowable I 1 01 setting established by Technical Specification 3.2.A. The redundant. switches l o Il ble No effe- o blic h 1 alh a d f C i41l reported in M-RO-77-9q 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE 7

02 8

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9 10 CODE 11 SUBCODE L LE (9 1 Il 12 13 COMPONENT CODE NIS ITIRIU 18 SUBCODE W39 LJa 19 SUBCODE 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO EVENTYEAR REPORT NO. CODE TYPE NO

@NUMBER AT21 0a 22 23 L 1001 6131 24 26 27 28 29 30 31 Li 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB.

34 33 3(),C) 350 36 1ool 010 10 40 37 L41 J@ LU( 42 L~I0 SUPPLIER 43 44 MANUFACTURER 1F10 18 11 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 10 I Event caused by setpoint drift. Switch is a Fenwal Model 17002-40. Setpoint I 11 I range is -100 F to +600 F. Switches recalibrated. Redundant switches tested 12 l satisfactorily.

13 I

14 7 8 9 80 FACILITY METHOD OF STATUS %POWER OTHER STATUS 0 DISCOVERY DISCOVERY DESCRIPTION 7

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8 9 10 O10 10 1(3 12 NA1 113 44 L1JC3I Setpoints out of specs.

45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE 7

1 6 8

LZJ 9

@[.J 10 L1 11 NA I I NA 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION 7

T1 8 9 Il ol ol 11 l

12 1NA 13 PERSONNEL INJURIES _

80 NUMBER DESCRIPTION E lo 0E ol 0 1 ~ 4) NA 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION E 1~L.IL 7 8 9 10 NA I PUBLICITY 80 ISSUED DESCRIPTION NRC USE ONLY 2E 0 LNJ81 NA 7 8 9 TO 68 69 80 Hl 0 NAME OF PREPARER Wl'a&

PHONE:0 -_25 11