LER-1979-021, /03L-0:on 791119,during IE Bulletin 79-02 Evaluation,Snubber SS-31 Base Plate Expansion Anchor Bolt Safety Factor Found to Be Less than One.Caused by Inadequate Base Plate & Expansion Anchor Bolts |
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M=WULfA I UK Y 1l~1NFUN I
IAl U
AN J
D I NADI Al CII I
UN DZ
- - 1 MAIUOI ACCESSON NBR:791227058 DOC.DATE: 79/12/19 NOT ZED: NO FACIL: 0-263 Monticello uclear Generating Plant, rthern States AUTH.NAME AUTHOR AFFILIATION DAYB.D.
Northern States Power Co.
RECIP.NAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director
SUBJECT:
DOCKET #
05000263 LER 79-021/03L-O:on 791119,during normal operation, per IE Bulletin 79-02 evaluationsnubber SS-31 base plate expansion anchor bolt safety factor found to be less than one.Caused by inadequate base plate & expansion anchor bolts.
DISTRIBUTION CODE: A002S COPIES RECEIVED:LTR / ENCL SIZE:
TITLE: Incident Reports NOTES:
RECIPIENT ID CODE/NAME ACTION:
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14 TA/EDO 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 HANAUERS.
STS GROUP LEADR 1
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02 NRC PDR 11 MPA 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 E JORDAN/IE R IRELAND TMI-H STREET EXTERNAL: 03 LPDR 29 ACRS 1
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16 04 NSIC 2)
TOTAL NUMBER OF COPIES REQUIRED: LTTR 1
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1 51 ENCL 51
NORTHERN STATES POWER COMPANY MINNEAPOLIS. MINNESOTA 55401 December 19, 1979 Mr J G Keppler Office of Inspection & Enforcement U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Mr Keppler:
MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Anchor Bolts for Snubber SS-31 Found Inadequate 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.
because operation with an inoperable snubber is a degraded mode permitted by Technical Specification 3.6.H.2.
Yours very truly, L 0 Mayer, PE Manager of Nuclear Support Services LOM/DMM/jh cc: L4)-rector, IE, USNRC (30)
Director, MIPC, USNRC (3)
MPCA Attn:
J W Ferman 0Y (Over) 7 91229o 5
NRC FORM 366 (7-77) 7 8
CON'T 7
8 7
8 7
8 10 m
m 14 U. S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK:
I I
Di (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
MINIMI NIP 11 2 10 10 1-0 0
01010101 0l-010 l (t 111111 1IOL (ED 9
LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 RE""" [Jj l 01 51 01 010 1 2 16 3 (I 11 11 119 17 19 011 1 21 11 9! 71 9 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES IDuring normal operation, evaluation of IE Bulletin 79-02 inspection results Irevealed snubber SS-31 Base Plate Expansion Anchor Bolt Safety Factor Less Than 1.
ISS-31 declared inoperable. Constitutes operation in degraded mode permitted by I
IT.S. 3.6.H.2. No effect on public health or safety. Analysis showed pipe stress I Iwithin code allowable without SS-31 during SSE, Redundant system operable during I I event.
Not a repetitive occurrerne.
II 9
80 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE cl F (D [B@1 L @3 1 Sl U I o
l PRI l
LBJ (5 L Z 9
10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LE R/RO EVENT YEAR REPORT NO.
CODE TYPE NO.
[REPORT SEQ1UENTA 1R12 11 OCREE R
R Ei NUMBER I.B
[---J Lol 2
1
- - j LLO 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
_I L O I1 oI olol LJ@
LN.
IA ]
B 11301 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS IReanalysis indicated that base plate and expansion anchor bolts associated with I
ISS-31 were inadequate. The support was modifipd to inerrpnq Rafpty factor tn At I
Ileast 2 within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of event identification. A safety factor meeting the long l Iterm requirements of IE Bulletin 79-02 will be assured.
7 89 FACILITY STATUS
%POWER OTHER STATUS Em LJ@ Lo0 1 9 18 NA 7
8 9
10 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY C 16 J @5 LI NA 1
7 8
9 10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRI PTION T 1 10 01 0 10 1Z NA 7
8 9
11 12 13 PERSONNEL INJURIES NUMBER
DESCRIPTION
FT1 0101 0 NA 7
8 9
11 12 LOSS OF OR DAMAGE TO FACILITY TYPE
DESCRIPTION
I Ip NA 7
8 9
10 PUBLICITY ISSUED
DESCRIPTION
F201I IN 1ED1 NA 7
8 9
10
/
NAME OF PREPARER B
y 80 METHOD OF DISCOVERY DISCOVERY DESCRIPTION 32 L..l.
Review of inspection results.
45 46 80 INA LOCATION OF RELEASE3 45 80 80 T9122 80 70 5
1 80 NRC USE ONLY 68 69 80 PHONE: 612/295-5151 0.
(D
NRC FORM 366 O
. NUCLEAR REGULATORY COMMISSION (7-7i 7
8 CON'T
]
7 8
rl"I 7
8 10 1
1 12 13 14 LICENSEE EVENT REPORT CONTROLBLOCK:
1 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
MI NI MI NIP 11 o 10 1-1 0 1010 1010-0 0 4 1 111 1 1()
9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 REPORT 0l 5l 01 0010e2 16 1 3 (G)Il 11 11 119 1719 1 11 2 1l 91 71 9 60 61 DOCKET NUMBER 68 69 EVENT DATE 5
RPTDAE 8
EVENT DESCRIPTION AND PROBABLE CONSEQUENCES I During normal operation, evaluation of IE Bulletin 79-02 inspection resifltR Irevealed snubber SS-31 Base Plate Expansion Anchor Bolt Safety Factor Less Than ISS-31 declared inoperable. Constitutes operation in degraded mode permitted by IT.S. 3.6.H.2.
No effect on public health or safety.
Analysis showed pipe stress Iwithin code allowable without SS-31 during SSE.
Redundant system operable during I event.
Not a repetit-ive orrurrence.
9 s0 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
@l LJ L (@ I sIU 1 0 1RI TI 3 B
LLZJ 9
10 11 12' 13 18 -
19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO EVENT YEAR REPORT NO.
CODE TYPE REPORT 1719 1-1 012 111 NUMBERCj 1
- - J L-2 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN
/NATTACHMENT NPRD-4 PRIME COMP, COMPONENT TAKEN ACTION ON PLANT METHOD HOURS A SUBMITTED FORM sUB.
SUPPLIER MANUFACTURER 1F IS-vl. I.J Lz.i@
Lz (
I 1 0 ool l
L.
IINJ@
LJUN^J 33 W
34 37 lol 110 AJ W@
1O 1B11131010 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS ©2 lReanalysis indicated that base-lAte and eXpansion anchor bolts associated with I SS-31 were inadeguate.
The support was, inedifigg ton inrrpe;-e afpt-Y far-n-r 1-0 q I least 2 within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of event identification.
A safety factor meeting the long I term requirements of TE Bul letin 79-02 will be assured, NO.
METHOD OF 7
89 FSATTS
% POWER OTHER STATUS 7
8 9
lo1 12 13 44 ACTIVITY CONTENT RELF-ASED OF RELEASE AMOUNT OF ACTIVITY 788 I
@ L&
NA I
7 8
9 10 11 44 PERSONNEL EXPOSURES NUMBER TYPE
DESCRIPTION
1 7 lol 0 I L J NA 7
89 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION 41 01 01 01 L(0 NA 7
8 9
11 12 LOSS OF OR DAMAGE TO FACILITY TYPE
DESCRIPTION
1 9
Z 1@1 NA 7
8 9
10 PUBLICITY ISSUED
DESCRIPTION
0 IN IRI NA 7
8 9
10 METHOD OF DISCOVERY DISCOVERY DESCRIPTION W O. I Review of inseection results.
45 46 LOCATION OF RE LEASE I NA 45 BO Bo 80 79122 NAME OF PREPARER B D Day 80 70 5I 80 NRC USE ONLY 68 69 80; 0
PHONE:
612/295-5151
- - I s0 45
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| 05000263/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000263/LER-1979-001-03, /03L-0 on 790110:during Normal Operation,Steam Leak Found in Elbow on Turbine Main Steam Bypass Header 1 Inch Drain Line to Condenser,Due to Erosion Caused by Steam & Water Flow of Restricting orifice,RO-2569 | /03L-0 on 790110:during Normal Operation,Steam Leak Found in Elbow on Turbine Main Steam Bypass Header 1 Inch Drain Line to Condenser,Due to Erosion Caused by Steam & Water Flow of Restricting orifice,RO-2569 | | | 05000263/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000263/LER-1979-002-03, /03L-0 on 790118:during Normal Operation,Weekly Average Power Range Monitor Functional Scram Test Was Not Completed within Time Allowed.Caused by Personnel Error | /03L-0 on 790118:during Normal Operation,Weekly Average Power Range Monitor Functional Scram Test Was Not Completed within Time Allowed.Caused by Personnel Error | | | 05000263/LER-1979-003, Forwards LER 79-003/01T-0 | Forwards LER 79-003/01T-0 | | | 05000263/LER-1979-003-01, /01T-0 on 790301:containment Vent & Purge Isolation Valves Would Not Close During DBA-LOCA.Cause Unknown.Fisher Continential 18 & 20 Inch,Type 9220 Butterfly Valves Opening Is Administratively Controlled | /01T-0 on 790301:containment Vent & Purge Isolation Valves Would Not Close During DBA-LOCA.Cause Unknown.Fisher Continential 18 & 20 Inch,Type 9220 Butterfly Valves Opening Is Administratively Controlled | | | 05000263/LER-1979-004-01, /01T-0 on 790313:shipping Cask Model B-2 Found W/ Two Missing Lid Bolt Nuts,Missing Inner Lid Gasket & Damaged Outer Lid Gasket.Caused by Inadequate Insp & Maint by Supplier.Cask Returned Empty | /01T-0 on 790313:shipping Cask Model B-2 Found W/ Two Missing Lid Bolt Nuts,Missing Inner Lid Gasket & Damaged Outer Lid Gasket.Caused by Inadequate Insp & Maint by Supplier.Cask Returned Empty | | | 05000263/LER-1979-005-03, /03L-0 on 790315:results of Special Test of Safety Relief Valve Effects on Torus Indicated Possible Excessive Opening Delay Time.Caused by Improper Installation of Insulation on Valve 67F.Maint Procedure to Modified | /03L-0 on 790315:results of Special Test of Safety Relief Valve Effects on Torus Indicated Possible Excessive Opening Delay Time.Caused by Improper Installation of Insulation on Valve 67F.Maint Procedure to Modified | | | 05000263/LER-1979-006-01, /01T-0 on 790317:during Recirculator Motor Generator Shutdown,Associated Field Breaker Failed to Trip. Caused by Metal Bead Fused to Arc Chute.Bead Removed,Breaker Tested & Returned to Svc | /01T-0 on 790317:during Recirculator Motor Generator Shutdown,Associated Field Breaker Failed to Trip. Caused by Metal Bead Fused to Arc Chute.Bead Removed,Breaker Tested & Returned to Svc | | | 05000263/LER-1979-007-03, /03L-0 on 790318:valve Operability & Motor Current Check Signed Despite Current Outside Formula Spec.Caused by Misaligned Torque Switch.New Components Ordered | /03L-0 on 790318:valve Operability & Motor Current Check Signed Despite Current Outside Formula Spec.Caused by Misaligned Torque Switch.New Components Ordered | | | 05000263/LER-1979-008-01, /01T-0 on 790323:one Trip Output Relay Failed to Initiate Trip in No 12 Recirculation Motor Generator Set Field Breaker Trip Logic.Caused by Contact Which Was Disengaged from Socket.Contact re-engaged in Socket | /01T-0 on 790323:one Trip Output Relay Failed to Initiate Trip in No 12 Recirculation Motor Generator Set Field Breaker Trip Logic.Caused by Contact Which Was Disengaged from Socket.Contact re-engaged in Socket | | | 05000263/LER-1979-009-03, /03L-0 on 790404:steam Leak Found in 90 Degree Elbow in 1-inch Core Isolation Cooling Steam Supply Drain Pot Condenser Line.Caused by Erosion Due to High Velocity Steam from Leaking Valve.Hole Patched.Repairs Planned | /03L-0 on 790404:steam Leak Found in 90 Degree Elbow in 1-inch Core Isolation Cooling Steam Supply Drain Pot Condenser Line.Caused by Erosion Due to High Velocity Steam from Leaking Valve.Hole Patched.Repairs Planned | | | 05000263/LER-1979-010-01, /01T-0 on 790426:informed by General Motors of Potential Diesel Generator Turbocharger Problem.Caused by Inadequate Design of Lube Oil Sys.Mod Being Developed | /01T-0 on 790426:informed by General Motors of Potential Diesel Generator Turbocharger Problem.Caused by Inadequate Design of Lube Oil Sys.Mod Being Developed | | | 05000263/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000263/LER-1979-011-03, /03L-0 on 790529:no Min Flow in B Train Standby Gas Treatment Sys.Caused by Dilution Flow from Compressed Storage Not Isolated by BV-5.Replaced Positioner & Installed Filter in Cylinder Supply/Return Line | /03L-0 on 790529:no Min Flow in B Train Standby Gas Treatment Sys.Caused by Dilution Flow from Compressed Storage Not Isolated by BV-5.Replaced Positioner & Installed Filter in Cylinder Supply/Return Line | | | 05000263/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000263/LER-1979-012-03, /03L-0 on 790702:during Reactor Core Isolation Cooling Sys Test,Governor end-bearing Temp Alarm Received & Bearing Exhibited High Vibration.Sys Inoperative.Caused by Turbine Oil Pump Drive Gear Failure.Gears Replaced | /03L-0 on 790702:during Reactor Core Isolation Cooling Sys Test,Governor end-bearing Temp Alarm Received & Bearing Exhibited High Vibration.Sys Inoperative.Caused by Turbine Oil Pump Drive Gear Failure.Gears Replaced | | | 05000263/LER-1979-013, Forwards LER 79-013/03L-0 | Forwards LER 79-013/03L-0 | | | 05000263/LER-1979-013-03, /03L-0 on 790708:motor Operator Failed,Rendering Torus Cooling Injection Valve Inoperable During Normal Operation.Caused by Failure of Motor Winding Due to Limit Switch Not de-energizing Motor.Switch Replaced | /03L-0 on 790708:motor Operator Failed,Rendering Torus Cooling Injection Valve Inoperable During Normal Operation.Caused by Failure of Motor Winding Due to Limit Switch Not de-energizing Motor.Switch Replaced | | | 05000263/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000263/LER-1979-014-03, /03L-0 on 790709:water Leak Discovered in 1/2 Inch Instrument Line from Reactor Water Cleanup Sys Nonregenerative Heat Exchanger.Cause Not Determined.Leaking Line Isolated & Will Be Further Investigated & Repaired | /03L-0 on 790709:water Leak Discovered in 1/2 Inch Instrument Line from Reactor Water Cleanup Sys Nonregenerative Heat Exchanger.Cause Not Determined.Leaking Line Isolated & Will Be Further Investigated & Repaired | | | 05000263/LER-1979-015, Forwards LER 79-015/03L-0 | Forwards LER 79-015/03L-0 | | | 05000263/LER-1979-015-03, /03L-0 on 790712:discovered Steam Leak from Intermediate Pressure Feedwater Heater.Cause Undetermined. Temporary Patch Installed Pending Replacement of Heater Shell | /03L-0 on 790712:discovered Steam Leak from Intermediate Pressure Feedwater Heater.Cause Undetermined. Temporary Patch Installed Pending Replacement of Heater Shell | | | 05000263/LER-1979-016-03, /03L-0 on 790731:turbine Tripped on Low Oil Pressure.Caused by Clogged Lube Oil Filter.Sys Drained, Inspected & Flushed | /03L-0 on 790731:turbine Tripped on Low Oil Pressure.Caused by Clogged Lube Oil Filter.Sys Drained, Inspected & Flushed | | | 05000263/LER-1979-016, Forwards LER 79-016/03L-0 | Forwards LER 79-016/03L-0 | | | 05000263/LER-1979-017, Forwards LER 79-017/03L-0 | Forwards LER 79-017/03L-0 | | | 05000263/LER-1979-017-03, /03L-0:on 790806,steam Leak Observed on Feedwater Extraction Steam Line Drain 15A.Caused by Steam Erosion Through Wall of Steam Trap on Line.Trap Isolated Pending Repair or Replacement at Next Appropriate Outage | /03L-0:on 790806,steam Leak Observed on Feedwater Extraction Steam Line Drain 15A.Caused by Steam Erosion Through Wall of Steam Trap on Line.Trap Isolated Pending Repair or Replacement at Next Appropriate Outage | | | 05000263/LER-1979-018, Forwards LER 79-018/03L-0 | Forwards LER 79-018/03L-0 | | | 05000263/LER-1979-019, Forwards LER 79-019/03L-0 | Forwards LER 79-019/03L-0 | | | 05000263/LER-1979-019-03, /03L-0:on 790923,ECCS Yarway Level Switches Indicated Falsely High Level & Would Not Have Tripped within Specified Settings.Caused by Effects of Leak Which Developed in Reactor Pressure Gauge During Normal Operation | /03L-0:on 790923,ECCS Yarway Level Switches Indicated Falsely High Level & Would Not Have Tripped within Specified Settings.Caused by Effects of Leak Which Developed in Reactor Pressure Gauge During Normal Operation | | | 05000263/LER-1979-020-03, /03L-0:on 791030,reactor Core Isolation Cooling Isolation Temp Switch Found to Trip Above Allowable Setpoint.Caused by Setpoint Drift.Switch Replaced | /03L-0:on 791030,reactor Core Isolation Cooling Isolation Temp Switch Found to Trip Above Allowable Setpoint.Caused by Setpoint Drift.Switch Replaced | | | 05000263/LER-1979-020, Forwards LER 79-020/03L-0 | Forwards LER 79-020/03L-0 | | | 05000263/LER-1979-021-03, /03L-0:on 791119,during IE Bulletin 79-02 Evaluation,Snubber SS-31 Base Plate Expansion Anchor Bolt Safety Factor Found to Be Less than One.Caused by Inadequate Base Plate & Expansion Anchor Bolts | /03L-0:on 791119,during IE Bulletin 79-02 Evaluation,Snubber SS-31 Base Plate Expansion Anchor Bolt Safety Factor Found to Be Less than One.Caused by Inadequate Base Plate & Expansion Anchor Bolts | | | 05000263/LER-1979-021, Forwards LER 79-021/03L-0 | Forwards LER 79-021/03L-0 | | | 05000263/LER-1979-022, Forwards LER 79-022/03L-0 | Forwards LER 79-022/03L-0 | | | 05000263/LER-1979-022-03, /03L-0:on 791213,during Normal Operation,Leak Discovered in 90-degree Elbow on 1-inch Condensate Line from Steam Supply to Recombiner Train Drain Trap.Caused by Erosion from Hot Steam Drains.Elbow Modified | /03L-0:on 791213,during Normal Operation,Leak Discovered in 90-degree Elbow on 1-inch Condensate Line from Steam Supply to Recombiner Train Drain Trap.Caused by Erosion from Hot Steam Drains.Elbow Modified | | | 05000263/LER-1979-023, Updated LER 79-023/01T-1:on 800103,one Fuel Type Noted to Exceed Max Allowable Max Average Planar Linear Heat Generation Rate Value & Another as Improperly Programmed in Plant Computer.Caused by Inadequate Review | Updated LER 79-023/01T-1:on 800103,one Fuel Type Noted to Exceed Max Allowable Max Average Planar Linear Heat Generation Rate Value & Another as Improperly Programmed in Plant Computer.Caused by Inadequate Review | | | 05000263/LER-1979-024-03, /03L-0:on 791220,during Normal Operation,Routine Operator Insp Revealed Steam Leak in 1-inch 90 Degree Elbow in Reactor Core Isolation Cooling Steam Line Drain to Condenser.Caused by Pinhole Failure of 3,000-lb Socket Weld | /03L-0:on 791220,during Normal Operation,Routine Operator Insp Revealed Steam Leak in 1-inch 90 Degree Elbow in Reactor Core Isolation Cooling Steam Line Drain to Condenser.Caused by Pinhole Failure of 3,000-lb Socket Weld | | | 05000263/LER-1979-024, Forwards LER 79-024/03L-0 | Forwards LER 79-024/03L-0 | |
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