/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| ML112900760 |
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| Site: |
Monticello  |
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| Issue date: |
07/01/1980 |
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| From: |
Jacobson R Northern States Power Co |
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| To: |
NRC/OI/RGN-III/FO |
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| Shared Package |
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| ML112900761 |
List: |
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| References |
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| LER-80-023-03L, LER-80-23-3L, NUDOCS 8007100195 |
| Download: ML112900760 (3) |
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LER-1980-023, /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 |
| Event date: |
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| Report date: |
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| 2631980023R03 - NRC Website |
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text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8007100195 0OC.DATE: 80/07/01 NOTARIZED: NO FACIL:50-263 Monticello Nuclear Generating Plant, Northern States AUTHNAME AUTHOR AFFILIATION JACOBSONR.D.
Northern States Power Co.
RECIPNAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director DOCKET #
05000263 SUBJECT: LER 80*023/03L-0:on 800601,air ejector off gas radiation monitors dropped to about 20% normal for about 40 minutes, Caused by mechanical vacuum pump off gas sample valve being incorrectly openedValve now wired shut, DISTRIBUTION CODE: A0028 COPIES RECEIVED:LTR j ENCL J, SIZE:
TITLE: Incident Reports NOTES :
RECIPIENT ID CODE/NAME ACTION:
BC/f0P/L/TO,7 05 COPIES LTTR ENCL 1
1 RECIPIENT ID CODE/NAME PM K4FtRA,7. 06 COPIES LTTR ENCL 2
2 A/D COMP&STRUCT A/D ENV TECH A/D LICENSING A/D OP REACTORS A/D RAD PROT A/D TECHNOLOGY AEOD CHEM ENG BR CORE PERF BR DIRHUM FAC SFY DIR,8YS INTEG EMERG PREP EQUIP QUAL BR GEOSCIENCES HYD/GEO BR IKE 09 LIC GUID BR MATL ENG BR MOOREV.
NRC POR 02 OR ASSESS BR PPAS GA BR REACT SYS BR REL & RISK A BR SIT ANAL SR SYS INTERAC BR INTERNAL:
EXTERNAL:
1 1
1 1
1 1
'10 1
1 1
1 1
1 1
1 2
1 1
1 1
1 1
1 1
I 1
1 16 04 1
1 1
1 1
1 1
10 1
1 1
1 1
1 1
1 2
1 1
1 1
1 1
1 1
1 1
16 1
A/D CORE & CS AID GEN PROJ A/D MATL & QUAL AID PLANT SYS A/D SFTY ASSESS ACC EVAL BR AUX SYS BR CONT SYS BR DIRENGINEERING DIRSFTY TECH EFF TR SYS BR ENV ENG BR GEN ISSUES BR HUM FACT ENG BR I&C SYS BR JORDANE,/IE LIC QUAL BR MECH ENG BR MPA 11 OP EX EVAL BR POWER SYS BR PROC/TST REV BR G LE VAL/
STRUCT ENG BR TERA:DOUG MAY LPDR 03 1
1 JUL 11 Ig TOTAL NUMBER OF COPIES REQUIRED: LTTR ACRS NSIC 89 ENCL 89
0 9
NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA 55401 July 1, 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 Low Reading on Air Ejector Process Radiation Monitors 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.b. in that it represents operation in a degraded mode for a short period of time as allowed by the Limiting Conditions for Operation.
Yours very truly, L 0 Mayer, PE Manager of Nuclear Support Services LOM/DMM/jh cc: *4.rector, IE, USNRC (30)
Director, MIPC, USNRC (3)
MPCA Attn:
J W Ferman
- - over-10 80 07WO190
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (7.77)
LICENSEE EVENT REPORT CONTROL BLOCK:
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
LIII
.K I IN 1P I
o11o ol oj o1 o 01 0 1 olI 41111 L L
J
- 1) 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T REPORT0 Ir\\III I@6 RR L15I 10 lo10 jZ 12 6_
2 0 16 10 11 18 10 l l0 lJ 7 0
WI SOURCE L LDI 1 08 LLL7j?.Qjj~III IJIIC~IIIj 1
8 j o
8 60 61
- DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES During normal operation, the air ejector off gas radiation monitors dropped to about 20% of normal for about 40 minutes.
Closure of the off gas sample box in Fo-I1~ Ilet valve returned the system to normal. This constituted operation of the system in a degraded mode (T.S.6.7.B.2.b). One previous similar occurrence (M-RO-77-14).
No effect on public health or safety.
7 8
9 80 SYSTEM
CAUSE
CAUSE COMP VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
_1 IM IO(
[Li~ Wi L( VIA1 LIVIEIXO (9
I 1
Wi ZJ@
7 8
9 10 11 12 13 VA 19 2
SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO.rEVENT YEAR REPORT NO.
CODE TYPE NO.
NUMBER L8 10 1
20 3.13 1
21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN HU ATTACHMENT NPRD-4 PRIME COMP COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB.
SUPPLIER MANUFACTURER L J ~@
i Li 1-1 ll~
0 10i0 LU 4
i10 Lw 11 31v 6 15 n2 36 37 40 442 43 44 4
CAUSE DESCRIPTION AND CORRECTIVE ACTIONSR [A
~rarely used mechanical vacuum pump(MVP) off gas sample valve was incorectly [T~jJ opened. This allowed off gas flow to bypass the off gas monitors. A sample box
=12j inlet valve was closed that isolated the open MVP sample valve which was later
~
closed. The MVP sample valve is now wired shut and will be placed on the off gas 14 system valve checklist.
7 89 8
100 FACILITY
(
METHOD OF STATUS
%POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION 32 IY1J i LI Lil NAJ IL erator observation 8 89 10 12 13 44 45 46 s
ACTIVITY.CONTENT RELEASED OP RELEASE NA."MOUNT OP ACTIVITY NALOCATION OF RELEASE 71 6 W W L
L__
89 10 1
44 4
80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION S N
7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONO 0W 0 10 1 1 NA 7
8 9 11 12 80 LOSS OF OR DAMAGE TO FACI LITY TYPE
DESCRIPTION
A PUB LI CITY 45NCUEOL ISSUED
DESCRIPTION
NRC AD~
raeyue ehnAl vaumpm(MP fJa sml av wasincorrectly 7
81 9 0
UI 0
.J IL1 oJN NA 7
8 9
10 68 69 80 R. D. Jacobson NAME OF PREPARER.
_MOUNT OF6ACT2VITY151.
L 0701O,~SPHO0 7u 80 90/11 44
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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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