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Haddam Neck 0l5l010101 2 l1 l3 1lorl0[3 TITLE 146 Inonerable Containment Isolation Valve (MS-TV-1212)
EVENT DATE IS)
LER NUMBER 168 REPORT DATE (7)
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A85TR ACT (Lem t to F400 weces o e. sooroarmerey rdreen smre noece rvoe*r rsen heest (166 MS-TV-1212, a containment isolation valve, failed to close during a surveillance test conducted August 23, 1984. The plant was shutdown for refueling and I
maintenance. The valve was repaired and retested satisfactorily. The valve l
also functioned properly during a subsequent containment isolation test.
A body-to-bonnet steam leak was found on MS-TV-1212 during a routine inspection on January 14, 1985. The body-to-bonnet bolts were tightened but the steam leak continued. An attempt to stroke the valve to verify operability was unsuccessful. A manual isolation valve, located downstream was lock-closed l
in order to provide containment isolation.
Furmanite was injected into l
PS-TV-1212 to stop the steam leak. The valve was repaired during the 1986 l
refueling outage.
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It has been concluded that the failure of MS-TV-1212 was an isolated event. The bases of this conclusion are:
- 1) As-found tests prior to 1984 were I
satisfactory, 2) Foreign material caused the 1985 operability failure, eliminating valve design concerns, 3) MS-TV-1213, the same valve model in similar service, continued to operate satisfactorily, and 4) A recent test after a period of service indicates MS-TV-1212 is operating satisfactorily, 8609150240 860910 PDR ADOCK 05000213
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EVENT DESCRIPTION
MS-TV-1212 failed to close during a surveillance test.
The surveillance test was conducted August 23, 1984, during a plant shutdown for refueling and maintenance. The valve was repaired and retested satisfactorily. The valve also functioned properly during a subsequent containment isolation test.
A body-to-bonnet steam leak was found on MS-TV-1212 during a routine inspection on January 14, 1985. The body-to-bonnet bolts were tightened. The steam leak continued. An attempt to stroke the valve to verify operability was unsuccessful. The valve would not close. A manual isolation valve was lock-closed downstream, in order to provide containment isolation.
Furmanite was injected into MS-TV-1212 to stop the steam leak. The valve was repaired during the 1986 refueling outage.
REPORTABILITY
This event is reportable per 10CFR50.73(a)(2)(v)(C) as MS-TV-1212 is relied on to contain contaminated material.
VALVE FUNCTION MS-TV-1212 is an air operated valve that closes on receipt of a containment isolation signal. MS-TV-1212 is located on the main steam line drain header.
The valve discharges to the steam generator blowdown tank.
VALVE FAILURE The cause of the August 23, 1984, failure of MS-TV-1212 to close could not be determined even though a bent stem was reported. This is because it could not be determined if the stem was bent before maintenance or during maintenance. A post-maintenance test indicated that the valve was operating properly.
MS-TV-1212 was repaired during the 1986 refueling outage due to the January 14, 1985 failure.
Foreign material was found under the valve seats. An analysis determined that the material was AIS1 410. The source of the foreign material could not be identified as AISI 410 is a common material. A post-maintenance retest indicated that the valve was functioning properly.
An additional test conducted on July 22, 1986, during a cold shutdown, showed that MS-TV-1212 was operating satisfactorily after two months of service.
MS-TV-1213 is the same valve model as MS-TV-1212 and experiences similar service conditions. There have not been any operability problems associated with MS-TV-1213 during this time interval.
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SAFETY CONSEQUENCES
MS-TV-1212 is the only valve that automatically isolates the main steam drain line header to the blowdown tank. MS-TV-1212 closes upon receipt of a containment isolation signal.
The inability of MS-TV-1212 to close is not an unanalyzed condition. The main steam lines do not become a leakage path of the containment atmosphere during a design' basis loss of coolant accident. The steam generator tube rupture analysis (Calculation No. XX-XXX-57RA) assumes that all radionuclides are released. Therefore, any leakage past MS-TV-1212 is accounted for.
CORRECTIVE ACTION
It is concluded that the failure of MS-TV-1212 was an isolated event. The bases of this conclusion are:
- 1) As-found tests prior to 1984 were satisfactory, 2)
Foreign material caused the 1985 operability failure, eliminating valve design concerns, 3) MS-TV-1213, a similar valve wit! similar service conditions continued to operate satisfactorily, and 4) A recent test after a period of service indicates MS-TV-1212 is operating satisfactorily.
The inservice test schedule for MS-TV-1212 and MS-TV-1213 has recently been revised from cold shutdown to every three months. This change is a result of a review of the valve inservice test program. This will reduce the probability that MS-TV-1212 or MS-TV-1213 are in operable while inservice.
RELATED LICENSEE EVENT REPORTS This LER updates the information provided in LER 84-016-00 and LER 85-001-00.
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CONNECTICUT YANKEE ATO MIC POWER COMPANY HADDAM NECK PLANT RR 41. BOX 127E EAST H AMPTON, CONN. 06424 September 11, 1986 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C.
20555
Reference:
Facility Operating License No. DPR-61 Docket No. 50-213 Reportable Occurrence LER 50-213/85-001-01 Gentlemen:
This letter forwards the Licensee Event Report 85-001-00, required to be submitted within 30 days, pursuant to the requirement of Connecticut Yankee Technical Specifications.
Very truly yours,
[
&^
Richard H. Graves Station Superintendent RHG: MET / lac
Attachment:
LER 85-001-00 cc:
Dr. T. E. Murley, Region I i
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| 05000213/LER-1985-001, :on 850114,body-to-bonnet Steam Leak Found on Containment Isolation Valve MS-TV-1212.Caused by Foreign Matl Under Valve Seats.Inservice Test Schedule Revised from Cold Shutdown to Every 3 Months |
- on 850114,body-to-bonnet Steam Leak Found on Containment Isolation Valve MS-TV-1212.Caused by Foreign Matl Under Valve Seats.Inservice Test Schedule Revised from Cold Shutdown to Every 3 Months
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000213/LER-1985-008, :on 850320,during Test of Fire Protection Sys, Actuation of Carbon Dioxide Sys Failed to Shut Off Containment Cable Vault Exhaust Fan.Caused by Wiring Error. Exhaust Fan Rewired |
- on 850320,during Test of Fire Protection Sys, Actuation of Carbon Dioxide Sys Failed to Shut Off Containment Cable Vault Exhaust Fan.Caused by Wiring Error. Exhaust Fan Rewired
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1985-009-01, :on 850910,one Auxiliary Feedwater solenoid- Operated Valve Failed to Change State Upon Deenergization. Caused by Stuck Valve NP-8320A-185E.Periodic Cycling Will Be Performed Until Problem Resolved |
- on 850910,one Auxiliary Feedwater solenoid- Operated Valve Failed to Change State Upon Deenergization. Caused by Stuck Valve NP-8320A-185E.Periodic Cycling Will Be Performed Until Problem Resolved
| | | 05000213/LER-1985-010, :on 840824,during Surveillance Testing,Both Motor Operated Svc Water Outlet Isolation Valves Failed to Operate When Energized.Caused by Inadequate Maint Records. Motor Operators Repaired & Retested |
- on 840824,during Surveillance Testing,Both Motor Operated Svc Water Outlet Isolation Valves Failed to Operate When Energized.Caused by Inadequate Maint Records. Motor Operators Repaired & Retested
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000213/LER-1985-011, :on 850516,manual Trip Followed Drop of Two Control Rods & Initiation of Automatic Load Runback.Cause Not Determined.Onsite Investigation by Vendor Underway |
- on 850516,manual Trip Followed Drop of Two Control Rods & Initiation of Automatic Load Runback.Cause Not Determined.Onsite Investigation by Vendor Underway
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000213/LER-1985-012, :on 850520,Tech Spec Surveillance Frequency Requirement Not Met in Performance of Rev 2 to Procedure SUR-5.5-26, Periodic Channel Functional Test of Reactor Coolant Pump Heat Detectors |
- on 850520,Tech Spec Surveillance Frequency Requirement Not Met in Performance of Rev 2 to Procedure SUR-5.5-26, Periodic Channel Functional Test of Reactor Coolant Pump Heat Detectors
| | | 05000213/LER-1985-013, :on 850916,licensee Discovered Rod Misalignment Power Peaking Penalty Not Imposed on Fuel Cycle Design & Safety Analysis.Caused by Inadequacy of Design Requirements. Allowable Axial Offset Limit Reduced |
- on 850916,licensee Discovered Rod Misalignment Power Peaking Penalty Not Imposed on Fuel Cycle Design & Safety Analysis.Caused by Inadequacy of Design Requirements. Allowable Axial Offset Limit Reduced
| | | 05000213/LER-1985-014, :on 850620 & 21,operations Dept Discovered Double Doors to Drumming Room Unlocked.Door Unlocked Due to Lack of Door Latch.Door Locked & Yellow Caution Tag Placed on Door to Alert Personnel to Post Fire Watch |
- on 850620 & 21,operations Dept Discovered Double Doors to Drumming Room Unlocked.Door Unlocked Due to Lack of Door Latch.Door Locked & Yellow Caution Tag Placed on Door to Alert Personnel to Post Fire Watch
| 10 CFR 50.73(a)(2)(i) | | 05000213/LER-1985-015, :on 850626,Channel 34 Spiked High,Actuating One Half of Overpower Reactor Trip.Caused by Failure of Gain Potentiometer.Gain Potentiometer ex-core Nuclear Instrumentation Channel Drawer Replaced |
- on 850626,Channel 34 Spiked High,Actuating One Half of Overpower Reactor Trip.Caused by Failure of Gain Potentiometer.Gain Potentiometer ex-core Nuclear Instrumentation Channel Drawer Replaced
| | | 05000213/LER-1985-016, :on 850703,ex-core Channel Failed to Meet Acceptance Criteria for Dropped Rod Load Runback Setpoint During Nuclear Instrumentation Sys Surveillance.Caused by Setpoint Drift.Setpoint Recalibr |
- on 850703,ex-core Channel Failed to Meet Acceptance Criteria for Dropped Rod Load Runback Setpoint During Nuclear Instrumentation Sys Surveillance.Caused by Setpoint Drift.Setpoint Recalibr
| | | 05000213/LER-1985-018, :on 850725,fire Door from Svc Bldg to Diesel Generator a Room Inoperable Due to Security Hardware Repairs.Fire Watch Not Posted Due to Confusion Over Operability Requirements of Fire Doors |
- on 850725,fire Door from Svc Bldg to Diesel Generator a Room Inoperable Due to Security Hardware Repairs.Fire Watch Not Posted Due to Confusion Over Operability Requirements of Fire Doors
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1985-019, :on 850726,ex-core Nuclear Instrumentation Power Range Channel 33 Spiked,Causing Actuation of Dropped Rod Load Runback Circuit.Caused by Failure of Gain Adjustment Potentiometer |
- on 850726,ex-core Nuclear Instrumentation Power Range Channel 33 Spiked,Causing Actuation of Dropped Rod Load Runback Circuit.Caused by Failure of Gain Adjustment Potentiometer
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000213/LER-1985-020, :on 850803,ladder Left Unattended W/O Restricting Access During Permanent Ladder Installation to High Radiation Area.Caused by Miscommunication to Maint Staff.Locked Gate Installed at Ladder Base |
- on 850803,ladder Left Unattended W/O Restricting Access During Permanent Ladder Installation to High Radiation Area.Caused by Miscommunication to Maint Staff.Locked Gate Installed at Ladder Base
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1985-021, :on 850805,open Fire Barrier Discovered Between Cable Spreading Area & Maint Hot Shop.Caused by Exclusion of Sheet Metal Wall Section from Fire Barrier Penetration Program.Program Reviewed & Will Be Revised |
- on 850805,open Fire Barrier Discovered Between Cable Spreading Area & Maint Hot Shop.Caused by Exclusion of Sheet Metal Wall Section from Fire Barrier Penetration Program.Program Reviewed & Will Be Revised
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1985-022, :on 850813,fire Barrier Penetration Discovered Inoperable.Caused by Inadvertent Damage to Seal by Const Personnel.Fire Watch Patrol Established & Seal Repaired W/ Fiberfax Board |
- on 850813,fire Barrier Penetration Discovered Inoperable.Caused by Inadvertent Damage to Seal by Const Personnel.Fire Watch Patrol Established & Seal Repaired W/ Fiberfax Board
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1985-023, :on 850823,determined That Fire Protection Valves FP-V-231 & 234 Not Properly Tested.Caused by Misinterpretation of Tech Spec Requirements.Surveillance Procedure Sur 5.5-24 Revised |
- on 850823,determined That Fire Protection Valves FP-V-231 & 234 Not Properly Tested.Caused by Misinterpretation of Tech Spec Requirements.Surveillance Procedure Sur 5.5-24 Revised
| 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1985-025, :on 850919,unplanned Release of Radwaste to Environ Detected.Caused by Isolation Valve Left Open Through Operator Error & Ambiguous Valve Tag Numbers.Event Reviewed W/Operators & Valves Relabeled Clearly |
- on 850919,unplanned Release of Radwaste to Environ Detected.Caused by Isolation Valve Left Open Through Operator Error & Ambiguous Valve Tag Numbers.Event Reviewed W/Operators & Valves Relabeled Clearly
| 10 CFR 50.73(a)(2)(viii)(A) | | 05000213/LER-1985-026, :on 851011,during Replacement of Low Signal Alarm Unit Associated W/Pressurizer Variable Low Pressure Reactor Trip Circuitry,Channel of Protection Defeated W/O Inserting Trip Signal to Maintain Logic |
- on 851011,during Replacement of Low Signal Alarm Unit Associated W/Pressurizer Variable Low Pressure Reactor Trip Circuitry,Channel of Protection Defeated W/O Inserting Trip Signal to Maintain Logic
| | | 05000213/LER-1985-027, :on 851105,four Open Fire Barrier Penetrations Discovered During Preliminary Walkdown.Caused by Lack of Procedural Guidance During Station Battery Installation.Fire Watch Established.Bolt Openings Repaired |
- on 851105,four Open Fire Barrier Penetrations Discovered During Preliminary Walkdown.Caused by Lack of Procedural Guidance During Station Battery Installation.Fire Watch Established.Bolt Openings Repaired
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1) | | 05000213/LER-1985-028, :on 851110 & 21,during Coastdown,High Steam Flow (Hsf) Reactor Trips Occurred Due to Automatic Reactor Protection Sys Initiation.Caused by Communication Between Hsf Channels 1,2 & 4.Loop 3 Solenoids Replaced |
- on 851110 & 21,during Coastdown,High Steam Flow (Hsf) Reactor Trips Occurred Due to Automatic Reactor Protection Sys Initiation.Caused by Communication Between Hsf Channels 1,2 & 4.Loop 3 Solenoids Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000213/LER-1985-029, :on 851101,interdependence of Emergency Diesel Generators & Common Motor Control Ctr Discovered.Caused by Design Deficiency.Generator Sys Modified to Ensure That Lube Oil Remained Above 85 F Limit |
- on 851101,interdependence of Emergency Diesel Generators & Common Motor Control Ctr Discovered.Caused by Design Deficiency.Generator Sys Modified to Ensure That Lube Oil Remained Above 85 F Limit
| | | 05000213/LER-1985-030, :on 851114,failure to Inspect Portions of Containment Atmosphere & post-accident Sampling Sys During Refueling Cycle Revealed by Sys Integrity Review.Caused by Lack of Applicable Procedures.Revs Underway |
- on 851114,failure to Inspect Portions of Containment Atmosphere & post-accident Sampling Sys During Refueling Cycle Revealed by Sys Integrity Review.Caused by Lack of Applicable Procedures.Revs Underway
| 10 CFR 50.73(a)(2)(1) |
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