LER-1980-015, /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 |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2631980015R01 - NRC Website |
|
text
REGULATORY *FORMATION DISTRIBUTION SY,M (RIDS)
ACCESSION NBR:8004010455 DOC,DATE: 80/03/27 NOTARIZED: NO DOCKET #
FACIL:S0-263 Monticello Nuclear Generating Plant, Northern States 05000263 AUTH.NAME AUTHOR AFFILIATION HAMMERMF.
Northern States Power Co.
RECIPNAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director SUBJECT: LER 80*015/01T-0:on 800317,during refueling outage & insp required by IE Bulletin 79-01Bunqualified splices found in power cables for inboard MSIV solenoid valvesCause not stated.Splices replaced w/qualified matis.
DISTRIBUTION CODE: A002S COPIES RECEIVED:LTR -
- ENCL, TITLE: Incident Reports SIZE: APO- /
NOTES: -----------------------
RECIPIENT ID CODE/NAME ACTION:
05 BC 0a INTERNAL:m 14 TA/EDO 16 EEO 18 PLANT SYS BR 20 AD PLANT SYS 23 ENGR BR 25 POR SYS BR 27 OPERA LIC BR 29 AUX SYS BR AEOD HANAUER,S, JORDANE./IE COPIES LTTR ENCL 4
4 1
12 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME 02 NRC PDR 11 MPA 15 NOVAK/KNIEL 17 AD FOR ENGR 19 T&C SYS BR 22 REAC SAFT BR 24 KREGER 26 AD/SITE ANAL 28 ACDENT ANLYS AD/0RP-DOR DOUG MAY*TERA IRELANDR.
COPIES LTTR ENCL 1
3 1
1 1
1 1
1 1
1 3
1 3
1 1
1 1
1 1
1 1
3 EXTERNAL:
03 LPDR 29 ACRS 1
16 1
16 04 NSIC 1
1 LJ~L~
If TOTAL NUMBER OF COPIES REQUIRED: LTTR 52 ENCL 52
NORTHERN STATES POWER COMPANY MINNEAPOLIS. MINNESOTA 55401 March 27, 1980 Mr J G Keppler Office of Inspection &
U S Nuclear Regulatory 799 Roosevelt Road Glen Ellyn, IL 60137 Enforcement Commission
Dear Mr Keppler:
MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Unqualified Splices Found in MSIV Control Cables 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.l.iin that a condition was discovered which was contrary to the design requirements contained in the Final Safety Analysis Report.
Yours very truly, L 0 Mayer, PE Manager of Nuclear Support Services LOM/DMM/ak cc: Hisector, IE, USNRC (40)
Director, MIPC, USNRC (3)
MPCA Attn:
J W Ferman
- - over-
- - 5 80040 1 o52i 4
NRC FORM 366 (7-77)
[E]L 7
8 CON'T 7
8 FOT27)
E5 5
(17771 U. S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK:
I G (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
2 1 0 10 1 -iOIIOI 1 0 10 1 010 10 1-10 0IO L L4_1__I111111@1OWjG)
N I NI mI NI Pl 110lo.1loloollollo j@ 411 110 9
LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 58 R C JO 15 101010121 61 31(10 13 11171 gi0 'I 01 31 21 71 81 01 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES I DURING A REFUELING CUTAGE, WHILE CONDUCTING AN INSPECTION REQUIRED BY IE I BULLETIN 79-01B, UNQUALIFIED SPLICES WERE DISCOVERED IN THE POWER CABLES FOR THE I INBOARD MSIV SOLENOID VALVES, SPLICES LOCATED IN JUNCTION BOXES BETWEEN THE I SOLENOID VALVES AND THE ELECTRICAL PENETRATION. NO EFFECT ON SAFETY SINCE I CATTATT ITATITICZ fPT p.A(T7TT TO rTAC MTTT AMT DfTITTTAhF ATITAAPTT ?iATc 1ATFP l 1fl I Il~P3 7
8 9 80 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE EID3 L@
L..
1.cJ@ I z I z I z1 zIz Iz I Iz I aL j 7
8 9
10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO EVENT YEAR REPORT NO.
CODE TYPE NO.
REPOR 1
[-- 0 1 1
".-j [0 '11[-
0 NUMBER
. L~J 10 1115 1~
011 LiJ L=J L2J 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP.
COMPONENT TAKEN ACTION ON PLANT METHOD HOURS 22 SUBMITTED FORM SUB.
SUPPLIER MANUFACTURER L..JL z @I IL@0 LU@
1o of o o1011L L..J.O@
L.UJ3 LzJ@
I zi 19 19 l@
33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS SITHE SPLICES WERE REPLACED USING QUALIFIED MATERIALS.
THER JUNCTION BOXES FOR [TD 71IEQUIPMENT REQUIRED TO FUNCTION IN A LOCA ENVIRONMENT WERE INSPECTED.
NO ADDITIONAI4
[ T)1 I UNQUALIFIED SPLICES WERE DISCOVERED.
7 89 80 FACILITY METHOD OF STATUS
%POWER OTHERSTATUS DISCOVERY DISCOVERY DESCRIPTION 11 LH G 101 01 01L1 N
j§JI INSPECTION 7
8 9
10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY @
NA O
EI[D IJ @5 L.JG I NA II NAO 7
8 9
10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE
DESCRIPTION
10 10 10
(
Z I
N 7
8 9
11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION4 1 10 lo 10 NA 1
7 8
9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE
DESCRIPTION
TIaAiGI NA 1
7 8
9 10 80 PUBLICITY NRC USE ONLY ISSUED
DESCRIPTION
(IIII I
1NA_
7 8
9 10 6869 80 NAME OF PREPARER 61H/295-er PH(
8004010 8
|
|---|
|
|
| | | Reporting criterion |
|---|
| 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 | |
|