LER-1980-020, /03L-0:on 800427,during post-maint Startup of Reactor Recirculation Sys,Inaccessible Recirculation Valve Motor Failed.Cause Not Stated.Motor Is Limitorque Type SMB-2 W/Magnetic Brake |
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| 2631980020R03 - NRC Website |
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text
REGULATORY *ORMATION DISTRIBUTION SYd M (RIDS)
ACCESSION NBR:8005300450 DOC.DATE: 80/05/27 NOTARIZED: NO FACIL:50-263 Monticello Nuclear Generating Plant, Northern States AUTHNAME AUTHOR AFFILIATION SHURTSS.J.
Northern States Power Co.
RECIPNAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director DOCKET #
05000263
SUBJECT:
LER 80-020/03L-0:on 800427,during post-maint startup of reactor recirc sysfinaccessible recirc valve motor failed.
Cause not stated,Motor is Limitorque type SMS-2 w/magnetic
- brake, DISTRIBUTION CODE: A002S COPIES RECEIVED:LTR ENCL 2.
SIZE:.J)
,L...
TITLE: Incident Reports NOTES:
RECIPIENT ID CODE/NAME ACTION:
05 aC 0? #3 INTERNAL:
R9i 15 NOVAK/KNIEL 17 AD FOR ENGR 19 I&C SYS BR 22 REAC SAFT BR 24 KREGER 26 AD/SITE ANAL 28 ACDENT ANLYS AD/ORP-DOR BERLINGERC, HANAUER,3S, EXTERNAL:
03 LPDR 29 ACRS COPIES LTTR ENCL 4
4 1I 2
1 1
1 1
1 1
1 1
3 1
1 16 1
2 1
1 1
1 1
1 3
1 1
16 RECIPIENT ID CODE/NAME 02 NRC POR 11 MPA 16 EEB 18 PLANT SYS BR 20 AD PLANT SYS 23 ENGR BR 25 PWR SYS BR 27 OPERA LIC BR 29 AUX SYS BR AEO0 DOUG MAY-TERA JORDAN,E./IE COPIES LTTR ENCL 1
3 1
1 1
1 1
1 1
10 1
1 04 NSIC 1
3 t
1 1
1 1
1 1
10 1
1 1
1 A'
J UN 2 1980 TOTAL NUMBER OF COPIES REQUIRED: LTTR 60 ENCL 60
NORTHERN STATES POWER COMPANY MINNEAPOLIS. MINNESOTA 55401 May 27, 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 Recirc Valve Motor Failure 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 Section 6.7.B.2.b. in that the condition led to operation in a degraded mode permitted by a limiting condition for operation (Section 3.5).
Yours very truly, O ayer, PE ger of Nuclear Support Services LOM/JAG/ak cc:
Director, IE, USNRC (30)
&-Di ector, MIPC, USNRC (3)
MPCA Attn:
J W Ferman
- - over 8OO500
NIC FORM lu4b 1-71 1
8 CONT 7
8 10 2
7 8
7 a
l. %. NUs:I I All III GI II AlA tIY coMMISION occurrences.
9 80 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE L L.O (x5 1zJ@ I IA IL IV 10 IP 19 A
D 9
10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LERO EVENTYEAR REPORT NO.
CODE TYPE NO.
R UoNUMBER.8 1--
10 12 10 Lj 13J1.
LL 1--
L-i L21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRO-4 PRIME COMP.
COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM bUB.
SUPPLIER MANUFACTURER LJ@LzJ@
IL i@ 1zJ 10 10 10I I L NJ2 IN3J LA IL 12 10 101 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Plant startup commenced based on the fact that a rej TTJ could be installed in a matter of days. The motor 1 with magnetic brake.
I 11 7
8 9
FACILITY METHOD OF STATUS
% POWER OTHER STATUS DISCOVERY EU LG j@ 10 l0 10 l1 NA IZ ll NA 7
8 9
10 12 IT 44 45 46 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY I, I L z IZNl IN NA 7
8 9
10 11 44 45 PERSONNEL FXPOSURES I
NUMRER TYPE oflSCRIPTION 1I1 InIn 1 LJizl MA 7
8 9
11 12 13 PERSONNEL INJURIES NUMBER
DESCRIPTION
ET1 10 10 0
1 NA 7
8 9
I 12 LOSS OF OR DAMAGE TO FACILITY TYPE
DESCRIPTION
I79 I INA 7
8 9
10 PUBLICITY ISSUED
DESCRIPTION
[
LB NRI[ N^A a
9 10 NAME OF PREPARER Shurts 3~~5O 0 0hrt lacement motor was available and I Ls a Limitorque TYpe SMR-?, 460 VAll DISCOVERY DESCRIPTION G2 LOCATION OF RELEASE &
1 80 80 so I0 80 80
.E 80 NRC USE ONLY 66 69 so 612/295-5151 0
I LICENSEE EVLN I 'REPOH f CONTROL BLOCK:
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 6 lMINIMINIP111 0 101-10 101010 10 1 (OLOOI411 111111 0[
9 LICENSEE CODE 14 5
LICENSE NUMBER 75 26 LICENSE TYPE JO 57 CAT 58 REPORT 0 510 0101216[3I
) l0j41 2l7l8 ID1 0 151217 18 10 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES During Post-Maintenance Startup of the Reactor Recirc System an inaccessible recirc I valve motor failed.
A compatible replacement motor was removed from the Outboard "A" core spray containment isolation valve and installed on the recirc valve. At thel time of plant startup the "'A" Loop of Core Spray was therefore considered inoperable. I The redundant core spray loop and LPCI system were operable. No previous similar I
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| 05000263/LER-1980-006-03, /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 | /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 | | | 05000263/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000263/LER-1980-007-01, /01T-0:on 800303,during Refuel Shutdown,Cable Routing for HPCI & Automatic Depressurization Sys Cables Identified Lack of Physical Separation Between Automatic Depressurization Sys Cables & Ones for Div of HPCI Sensors | /01T-0:on 800303,during Refuel Shutdown,Cable Routing for HPCI & Automatic Depressurization Sys Cables Identified Lack of Physical Separation Between Automatic Depressurization Sys Cables & Ones for Div of HPCI Sensors | | | 05000263/LER-1980-007, Forwards LER 80-007/01T-0 | Forwards LER 80-007/01T-0 | | | 05000263/LER-1980-011-01, /01T-0:on 800306,during Refueling Outage,Repairs to Outboard MSIV Stop Valve Revealed Flow Path Between Secondary Containment & Turbine Bldg When MSIV Poppet Was Pulled.Caused by Lack of Preventive Procedure Controls | /01T-0:on 800306,during Refueling Outage,Repairs to Outboard MSIV Stop Valve Revealed Flow Path Between Secondary Containment & Turbine Bldg When MSIV Poppet Was Pulled.Caused by Lack of Preventive Procedure Controls | | | 05000263/LER-1980-011, Forwards LER 80-011/01T-0 | Forwards LER 80-011/01T-0 | | | 05000263/LER-1980-013-01, /01T-0:on 800309,during Refueling Operations,Rod Withdrawn Block Not Received When Refueling Bridge Traversed Core.Caused by Actuating Arm Out of Adjustment.Components Readjusted & Interlocks Tested Prior to Refueling | /01T-0:on 800309,during Refueling Operations,Rod Withdrawn Block Not Received When Refueling Bridge Traversed Core.Caused by Actuating Arm Out of Adjustment.Components Readjusted & Interlocks Tested Prior to Refueling | | | 05000263/LER-1980-013, Forwards LER 80-013/01T-0 | Forwards LER 80-013/01T-0 | | | 05000263/LER-1980-015-01, /01T-0:on 800317,during Refueling Outage & Insp Required by IE Bulletin 79-01B,unqualified Splices Found in Power Cables for Inboard MSIV Solenoid Valves.Cause Not Stated.Splices Replaced W/Qualified Matls | /01T-0:on 800317,during Refueling Outage & Insp Required by IE Bulletin 79-01B,unqualified Splices Found in Power Cables for Inboard MSIV Solenoid Valves.Cause Not Stated.Splices Replaced W/Qualified Matls | | | 05000263/LER-1980-015, Forwards LER 80-015/01T-0 | Forwards LER 80-015/01T-0 | | | 05000263/LER-1980-016, Forwards LER 80-016/01T-0 | Forwards LER 80-016/01T-0 | | | 05000263/LER-1980-016-01, /01T-0:on 800327,during Refueling,Supports for SRV Pneumatic Supply Sys Would Not Meet Seismic Class I Requirements.Caused by Inadequate Design & Installation of Sys.Sys Was Upgraded to Satisfy Requirements | /01T-0:on 800327,during Refueling,Supports for SRV Pneumatic Supply Sys Would Not Meet Seismic Class I Requirements.Caused by Inadequate Design & Installation of Sys.Sys Was Upgraded to Satisfy Requirements | | | 05000263/LER-1980-017, Forwards LER 80-017/01T-0 | Forwards LER 80-017/01T-0 | | | 05000263/LER-1980-017-01, /01T-0:on 800328,Bechtel Power Corp Notified Util That Control Rod Driveline Hydraulic Piping Frame Supports Would Not Meet OBE Stress Limits.Caused by Eds Computer Code Error.Supports Modified | /01T-0:on 800328,Bechtel Power Corp Notified Util That Control Rod Driveline Hydraulic Piping Frame Supports Would Not Meet OBE Stress Limits.Caused by Eds Computer Code Error.Supports Modified | | | 05000263/LER-1980-018, Forwards LER 80-018/03L-0 | Forwards LER 80-018/03L-0 | | | 05000263/LER-1980-018-03, /03L-0:on 800411,during Routine Operator Insp, Attachment Weld of Ripple to Level Switch Float Chamber Assembly on Moisture Separator Level Switch LS-1188 Found Cracked.Caused by Improper Weld Procedure | /03L-0:on 800411,during Routine Operator Insp, Attachment Weld of Ripple to Level Switch Float Chamber Assembly on Moisture Separator Level Switch LS-1188 Found Cracked.Caused by Improper Weld Procedure | | | 05000263/LER-1980-020-03, /03L-0:on 800427,during post-maint Startup of Reactor Recirculation Sys,Inaccessible Recirculation Valve Motor Failed.Cause Not Stated.Motor Is Limitorque Type SMB-2 W/Magnetic Brake | /03L-0:on 800427,during post-maint Startup of Reactor Recirculation Sys,Inaccessible Recirculation Valve Motor Failed.Cause Not Stated.Motor Is Limitorque Type SMB-2 W/Magnetic Brake | | | 05000263/LER-1980-020, Forwards LER 80-020/03L-0 | Forwards LER 80-020/03L-0 | | | 05000263/LER-1980-021, Forwards LER 80-021/03L-0 | Forwards LER 80-021/03L-0 | | | 05000263/LER-1980-021-03, /03L-0:on 800515,during Normal Startup,Reactor Core Isolation Cooling Control Power Fuse Opened.Caused by Shorted Relay Coil in Circuit Due to Ac Relay Inadvertently Installed by Maint Personnel.Relay Replaced | /03L-0:on 800515,during Normal Startup,Reactor Core Isolation Cooling Control Power Fuse Opened.Caused by Shorted Relay Coil in Circuit Due to Ac Relay Inadvertently Installed by Maint Personnel.Relay Replaced | | | 05000263/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | | 05000263/LER-1980-022-03, /03L-0:on 800529,primary Containment Oxygen Concentration Exceeded 5% by Weight Tech Spec Limit.Caused by Open Svc Air Isolation Valve to Drywell.Procedures Have Been Revised to Assure Proper Valve Positioning | /03L-0:on 800529,primary Containment Oxygen Concentration Exceeded 5% by Weight Tech Spec Limit.Caused by Open Svc Air Isolation Valve to Drywell.Procedures Have Been Revised to Assure Proper Valve Positioning | | | 05000263/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000263/LER-1980-023-03, /03L-0:on 800601,air Ejector Offgas Radiation Monitors Dropped to About 20% Normal for About 40 Minutes. Caused by Mechanical Vacuum Pump Offgas Sample Valve Being Incorrectly Opened.Valve Now Wired Shut | /03L-0:on 800601,air Ejector Offgas Radiation Monitors Dropped to About 20% Normal for About 40 Minutes. Caused by Mechanical Vacuum Pump Offgas Sample Valve Being Incorrectly Opened.Valve Now Wired Shut | | | 05000263/LER-1980-025, Forwards Updated LER 80-025/03L-1 | Forwards Updated LER 80-025/03L-1 | | | 05000263/LER-1980-025-03, Outboard HPCI Steam Supply Valve Operator Failed & Inboard Valve Closed.Caused by Breakdown of Motor Winding Insulation in Peerless Dc Motor on SMB-O Operator.Motor Replaced W/Class H Motor | Outboard HPCI Steam Supply Valve Operator Failed & Inboard Valve Closed.Caused by Breakdown of Motor Winding Insulation in Peerless Dc Motor on SMB-O Operator.Motor Replaced W/Class H Motor | | | 05000263/LER-1980-027-03, /03L-0:on 80823,during Monthly surveillance,42-11 Test Control Rod Could Not Be Withdrawn After Partial Insertion.Caused by Closed Drive Withdraw Riser Isolation Valve CRD-102.Valve Opened & Rod Was Operable | /03L-0:on 80823,during Monthly surveillance,42-11 Test Control Rod Could Not Be Withdrawn After Partial Insertion.Caused by Closed Drive Withdraw Riser Isolation Valve CRD-102.Valve Opened & Rod Was Operable | | | 05000263/LER-1980-027, Forwards LER 80-027/03L-0 | Forwards LER 80-027/03L-0 | |
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