LER-1980-017, /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 |
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REGULATORY *FORMATION DISTRIBUTION SY 4 M (RIDS)
ACCESSION NBR:8004180472 DOC.DATE: 80/04/11 NOTARIZED: NO FACIL:50-263 Monticello Nuclear Generating Plant, Northern States AUTHNAME AUTHOR AFFILIATION DAY,B.D, Northern States Power Co*
RECIP.NAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director SUBJECT: LER 80-017/01T-0:on 800328,reduction of control rod driveline hydraulic piping frame support.Caused by EDS computer code error.Supports modified.
DISTRIBUTION CODE; A002S COPIES RECEIVED:LTR
.4 NCL t TITLE: Incident Reports DOCKET #
05000263 SIZE:
NOTES: --- --- --- -- --- --- -- --- --- -- --- --- -- --- --- -- --- --- --
RECIPIENT COPIES ID CODE/NAME LTTR ACTION:
05 6CQ 4
INTERNAL:
1 2
14 TA/EDO 1
16 EEB 1
18 PLANT SYS BR 1
20 AD PLANT SYS 1
23 ENGR BR 1
25 PWR SYS BR 1
27 OPERA LIC BR 1
29 AUX SYS BR 1
AEOD 10 DOUG MAY-TERA 1
JORDANE./IE 1
EXTERNAL:
03 LPDR 29 ACRS 1
16 RECIPIENT ID CODE/NAME ENCL 4
02 NRC PDR 11 MPA 15 NOVAK/KNIEL 17 AD'FOR ENGR 19 I&C SYS BR 22 REAC SAFT BR 214 KREGER 26 AD/SITE ANAL 28 ACDENT ANLYS AD/ORP-DOR BERLINGERC.
HANAUERS.
1 2
1 1
1 1
1 1
10 1
1 1
16 04 NSIC COPIES LTTR ENCL 1
3 1
1 1
1 1
1 1
1 3
1 1
1
,980
- 1 TOTAL NUMBER OF COPIES REQUIRED; LTTR 61 ENCL 61
NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA 55401 April 11, 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 Reduction of CRD Hydraulic Piping Frame Support Design Margins Caused by EDS Computer Code Error 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.1.i in 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/jh cc:
Director, IE, USNRC (40)
Director, MIPC, USNRC (3)
MPCA Attn:
J W Ferman
- - over-
$0 0,418 () 4 6 8 S
i/1
7 8
CON'T 7
8 02 7
8 0
7 8
7 8
9 FACILITY STATUS
%POWER OTHER STATUS IT EJ@ Iololo0 1 N^MA 7
8 9
10 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY SI Z
I
@ U lI NA 7
8 9
10 11 44 PERSONNEL EXPOSURES NUM3ER TYPE
DESCRIPTION
0 1] 0 1 0 J5Z l
NA 7
8 9
11 12 13 PERSONNEL INJURIES NUMBER
DESCRIPTION
0 I
1 o 1I NA 7
8 9
11 12 LOSS OF OR DAMAGE TO FACILITY TYPE
DESCRIPTION
[LU I
NA 7
8 9
10 PUBLICITY ISSUED
DESCRIPTION
1 LL181 NA a 9 10.
NAME OF PREPAR METHOD OF DISCOVERY DISCOVERY DESCRIPTION 32 D
Notification from A/E 45 46 8
LOCATION OF RELEASE INA 45 8
80 0
0 80 80 80 NRC USE ONLY 612
- - 5151 PH9 800.4 18 0472 Byron D. Day ER-(1-77)
LICENSEE EVLNI REPORT CONTROL BLOCK:
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 6 MI Nj Ml NJ P1 1101 01 01 - I01j0 0
0 -
0110 1O 14 l1 1 11j 1
(D 9
LICENSEE CODE 14 15 LICENSE NUMIBEII 25 26 LICENSE TYPE 30 57 CAT 58 REPORT [Lj Oj 5 501010121_6131() [01312181810) 101411111810l(D 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES I During a refueling outage, Bechtel Power Corporation notified licensee that CRD l
hydraulic piping frame supports will not meet OBE stress limits. This event is reportable under T.S.6.7.B.1.i. Supports will meet SSE limits. Health or safety j
of public not affected. No previous similar reportable event.
j 9
80 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCOQE SUBCODE IR j Bj(^ (D Bj A I S jU IP 1O IR IT L]
9 10 11 12 13 18 19 20.
SEQUENTIAL OCCURRENCE REPORT REVISION LERRO EVENT YEAR REPORT NO.
CODE TYPE NO.
07 REORT1 8LoJ 0
1ol 11 7 1 j 1.0 [J
L-L R 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.
SUBMITTED FORM SUB.
SUPPLIER MANUFACTURER LLJ@LJ@ IJ@
l o
a 1 JJ I
0 33 34 35 36 37 40 41 42 43 44
- 47.
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (2' Error in computer code used by EDS Nuclear caused original support design loads to I
be inaccurate.
Supportshave been modified to meet stress limits.
Bechtel has re-I viewed other systems affected by computer code error. No other modifications re-I quired.
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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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