LER-1980-080, /01T-0:on 801031,reactor Vessel Relief Valve Rv 203-3A Opened.Caused by Nitrogen Regulator Valve Which Froze in Open Position.Drywell Instruments Will Be Operated by Compressed Air W/Nitrogen Supply Isolated |
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| 2931980080R01 - NRC Website |
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NRC FCCM 384 U. S. NUCLEA'1 REGULATOOY COMMISSION
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8 60 61 0o0 JET NUM8ER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT OESCRIPTION ANO PROBABLE CONSEQUENCES h l o { 21 10n October 31, 1980 at approximately 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> with the reactor at 100 percent steady l (3771 l state power operation, the reactor vessel elief valve RV 203-3A opened. The reactor l
4 1 o 14 l lwas subsequently manually scrammed at 50 percent nower.
Corrective measures to prevent l IOIsI l recurrence were taken and the reactor returned to operation on November 1, 1980 at ap-l 1 O is I I proximately 0317 hours0.00367 days <br />0.0881 hours <br />5.241402e-4 weeks <br />1.206185e-4 months <br /> (Refer to Attachment for additional information).
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CODE TYPE NO.
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- i ; o ; l A nitrogen regulator valve manufactured by C. A. Norgren Company of Littleton, Coloradop
,,,, y g model No. 11-002-097 and rated at 400 and 125 psi maximum inlet and outlet pressure is [-
believed to have frozen in the open position.
160 to 165 psi nitrogen pressure was thereby transmitted to the relief valve's solenoid actuttor valve and initiated the j
pneumatic operator of the relief valve.
(See Attachment for Details)
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8 9 80 STNd 3 POWER OTHER STATUS DISCO Y
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DESCRIPTION
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PILGRIM NUCLEAR POWER STATION
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DOCKET NO. 50-293 Attachment to LER 80-080/01T-0
Description
At approximately 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> on October 31, 1980 with reactor at 100 percent steady state power operation the reactor vessel relief valve RV 203-3A opened.
The relief valve could not be reclosed until reactor pressure dropped to ap-proximately 20 psig. The relief valve's operation was the result of approxi-mately 165 psi nitrogen pressure being fed to the relief valve's ASCO three way, solenoid control valve. Analysis has revealed that the relief valve's setpoint pressure varies inversely to its solenoid actuator's nitrogen pressure above 145 psi. _ A similar event occurred on October 7,1980 and was reported as LER 80-069/01T-0.
The relief valve's solenoid actuator supply was switched from nitrogen to compressed ' air and the reactor returned to criticality on Jovember 1, 1980 at approximately 0317 hours0.00367 days <br />0.0881 hours <br />5.241402e-4 weeks <br />1.206185e-4 months <br />.
Cause and Corrective Action On October 31, 1980 an indepth investigation of the nitrogen. supply system was initiated.
The investigation concluded that liquid nitrogen passing by its ambient air vaporizer froze an in-line regulator. This in-line, blow-down regu-lator froze in the open position. This permitted nitrogen tank pressure main-tained at 180 psi to be transmitted to the relief valve's solenoid actuator.
This regulator, manufactured by C. A. Norgren Company, was installed in parallel to an existing regulator in August, 1980. The existing regulator fails in the closed position so the conditiens resulting from failure of the Norgren regulator could only have occurred since the August installation.
To preclude recurrence of this event the following design changes are being contemplated:
A)
Removal of the " fail open", Norgren, blow-down regulator and its replacement with a " fail close" regulator B)
A reduction of nitrogen tank pressure from 180 psi to less than 135 psi.
C) The addition of a 135 psi relief valve to the nitrogen header down-stream of the regulators.
1 Until these modifications are completed drywell instruments will be operated by compressed air with their nitrogen supply isolated.
These modifications are expected to be completed by December 15, 1980.
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| 05000293/LER-1980-001-01, /01T-0:on 800123,fire Hazard Analysis Determined That Fire in Electrical Raceways in Several Areas of Plant Would Jeopardize Redundant Div of ECCS Sys.Cause Not Stated. Mods Planned to Be Completed by Oct 1980 | /01T-0:on 800123,fire Hazard Analysis Determined That Fire in Electrical Raceways in Several Areas of Plant Would Jeopardize Redundant Div of ECCS Sys.Cause Not Stated. Mods Planned to Be Completed by Oct 1980 | | | 05000293/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000293/LER-1980-002-02, /02T-0:on 800124,cable Separation Inadequacy Discovered Following Review of IE Info Notice 79-32. Affected Automatic Depressurization Sys Cables Will Probably Be Rerouted | /02T-0:on 800124,cable Separation Inadequacy Discovered Following Review of IE Info Notice 79-32. 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Cause Not Stated.House Rebuilt & Returned to Svc | /03L-0:on 800310,hydrant Hose House 5 Damaged When Hit by Truck.House Wrapped Around Hydrant,Preventing Access. Cause Not Stated.House Rebuilt & Returned to Svc | | | 05000293/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000293/LER-1980-011-01, /01T-0:on 800326,utilizing Approved Station Procedure TP80-37,PNPS Jet Pumps Examined & Jet Pump Beams 1,3 & 15 Found to Have Discontinuities.Caused Not Stated. Flawed Beams & Beam Bolt Assemblies Replaced | /01T-0:on 800326,utilizing Approved Station Procedure TP80-37,PNPS Jet Pumps Examined & Jet Pump Beams 1,3 & 15 Found to Have Discontinuities.Caused Not Stated. Flawed Beams & Beam Bolt Assemblies Replaced | | | 05000293/LER-1980-011, Forwards LER 80-011/01T-0 | Forwards LER 80-011/01T-0 | | | 05000293/LER-1980-012-03, /03L-0:on 800312,while Performing Surveillance Test,Found That Pressure Switch 263-52A Setpoint Had Drifted.Cause Not Stated.Setpoint Drift Is Recurring Problem.Pressure Switch Recalibr | /03L-0:on 800312,while Performing Surveillance Test,Found That Pressure Switch 263-52A Setpoint Had Drifted.Cause Not Stated.Setpoint Drift Is Recurring Problem.Pressure Switch Recalibr | | | 05000293/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000293/LER-1980-013-03, /03L-0:on 800313,while Performing Surveillance Test 8.M.1-5,found Pressure Switch 503D Setpoint Drifted. Cause Not Stated.Drift Is Recurring Problem | /03L-0:on 800313,while Performing Surveillance Test 8.M.1-5,found Pressure Switch 503D Setpoint Drifted. Cause Not Stated.Drift Is Recurring Problem | | | 05000293/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000293/LER-1980-014, Forwards LER 80-014/04T-0 | Forwards LER 80-014/04T-0 | | | 05000293/LER-1980-014-04, /04T-0:on 800418,Yankee Atomic Environ Lab Notified Util That Milk Sample Contained High Concentration of Cs-137.Cause Unknown,Probably Not Result of Plant Effluent | /04T-0:on 800418,Yankee Atomic Environ Lab Notified Util That Milk Sample Contained High Concentration of Cs-137.Cause Unknown,Probably Not Result of Plant Effluent | | | 05000293/LER-1980-015-03, /03L-0:on 800401,during Performance of Surveillance Test,Dry Chemical Fire Protection Sys Failed to Automatically Initiate.Caused by Erratic Pyrotronics, Dtf 190 heat-actuated Device.Unit Replaced | /03L-0:on 800401,during Performance of Surveillance Test,Dry Chemical Fire Protection Sys Failed to Automatically Initiate.Caused by Erratic Pyrotronics, Dtf 190 heat-actuated Device.Unit Replaced | | | 05000293/LER-1980-015, Forwards LER 80-015/03L-0 | Forwards LER 80-015/03L-0 | | | 05000293/LER-1980-016-03, /03L-0:on 800513,while Performing Surveillance Test,Core Spray Pump P215B Failed to Start & Core Spray Valve 14000-24B Failed to Automatically Open.Caused by trip-free Operation & Dirty Contact in Logic Circuit | /03L-0:on 800513,while Performing Surveillance Test,Core Spray Pump P215B Failed to Start & Core Spray Valve 14000-24B Failed to Automatically Open.Caused by trip-free Operation & Dirty Contact in Logic Circuit | | | 05000293/LER-1980-016, Forwards LER 80-016/03L-0 | Forwards LER 80-016/03L-0 | | | 05000293/LER-1980-017-03, /03L-0:on 800505,during 24-h Performance Test of a Diesel Generator Per IE Bulletin 79-23,three Attempts Made Before Satisfactory Conclusion on 800510.Caused by Failure of Potential Transformer in High Voltage Chassis | /03L-0:on 800505,during 24-h Performance Test of a Diesel Generator Per IE Bulletin 79-23,three Attempts Made Before Satisfactory Conclusion on 800510.Caused by Failure of Potential Transformer in High Voltage Chassis | | | 05000293/LER-1980-017, Forwards LER 80-017/03L-0 | Forwards LER 80-017/03L-0 | | | 05000293/LER-1980-018, Forwards LER 80-018/03L-0 | Forwards LER 80-018/03L-0 | | | 05000293/LER-1980-018-03, /03L-0:on 800523,while Performing Surveillance Test 8.7.4.3,isolation valves,5065-11,13 & 23 Declared Inoperable.Cause Not Stated.Valve in Each Affected Sample Line Closed & Position Recorded Daily | /03L-0:on 800523,while Performing Surveillance Test 8.7.4.3,isolation valves,5065-11,13 & 23 Declared Inoperable.Cause Not Stated.Valve in Each Affected Sample Line Closed & Position Recorded Daily | | | 05000293/LER-1980-019-03, /03L-0:on 800519,during Startup of Pnps,Hpci Sys Was Declared Inoperable.Caused by Wiring Attendant to Installation of Alternate Shutdown Panel & Seal Exhaust Leakage Interference.Wiring & Leakage Repaired | /03L-0:on 800519,during Startup of Pnps,Hpci Sys Was Declared Inoperable.Caused by Wiring Attendant to Installation of Alternate Shutdown Panel & Seal Exhaust Leakage Interference.Wiring & Leakage Repaired | | | 05000293/LER-1980-019, Forwards LER 80-019/03L-0 | Forwards LER 80-019/03L-0 | | | 05000293/LER-1980-020-03, /03L-0:on 800426,during Refueling Outage 4,14 Primary Containment Isolation Valves Found to Have Seat Leakage Over Requirements.Caused by Normal Deterioration of Disc to Seat Mating Surface | /03L-0:on 800426,during Refueling Outage 4,14 Primary Containment Isolation Valves Found to Have Seat Leakage Over Requirements.Caused by Normal Deterioration of Disc to Seat Mating Surface | | | 05000293/LER-1980-020, Forwards LER 80-020/03L-0 | Forwards LER 80-020/03L-0 | | | 05000293/LER-1980-021-04, /04T-0:on 800508,algae Sample from Discharge Outfall Area Contained Reportable Concentration of Co-60, According to Yankee Environ Lab 800616 Analysis Rept.Cause Not Stated | /04T-0:on 800508,algae Sample from Discharge Outfall Area Contained Reportable Concentration of Co-60, According to Yankee Environ Lab 800616 Analysis Rept.Cause Not Stated | | | 05000293/LER-1980-021, Forwards LER 80-021/04T-0 | Forwards LER 80-021/04T-0 | | | 05000293/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | | 05000293/LER-1980-022-03, /03L-0:on 800527,during Performance of Surveillance Test Re RCIC Steam Line High Temp,Temp Switch 1360-17A Was Found Out of Calibr.Caused by Setpoint Drift | /03L-0:on 800527,during Performance of Surveillance Test Re RCIC Steam Line High Temp,Temp Switch 1360-17A Was Found Out of Calibr.Caused by Setpoint Drift | | | 05000293/LER-1980-023-03, /03L-0:on 800526,during Surveillance Testing, Channel B of Rod Block Monitor Sys Determined to Be Out of Calibr.Caused by Misinterpertation of Tech Specs. Requalification Program Will Include Sys Review | /03L-0:on 800526,during Surveillance Testing, Channel B of Rod Block Monitor Sys Determined to Be Out of Calibr.Caused by Misinterpertation of Tech Specs. Requalification Program Will Include Sys Review | | | 05000293/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000293/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | | 05000293/LER-1980-024-03, /03L-0:on 800530,reactor Core Isolation Cooling Sys Was Declared Inoperable.Caused by Faulty Auto Flow Control.Unit Repaired & Returned to Svc | /03L-0:on 800530,reactor Core Isolation Cooling Sys Was Declared Inoperable.Caused by Faulty Auto Flow Control.Unit Repaired & Returned to Svc | | | 05000293/LER-1980-025, Forwards LER 80-025/03L-0 | Forwards LER 80-025/03L-0 | | | 05000293/LER-1980-025-03, /03L-0:on 800602,fire Detection Alarm from HPCI Quadrant Sounded in Control Room on Panel C-94.Roving Fire Patrol Initiated & Immediate Investigation Conducted.Caused by Leak at Flange on HPCI Drain Line Valve AO2301-29 | /03L-0:on 800602,fire Detection Alarm from HPCI Quadrant Sounded in Control Room on Panel C-94.Roving Fire Patrol Initiated & Immediate Investigation Conducted.Caused by Leak at Flange on HPCI Drain Line Valve AO2301-29 | |
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