LER-1980-065, /03X-1:on 801105,reactor Operated in Degraded Mode.Caused by Removal of Snubbers for Verification of Bleed Rate.Snubbers Were Adjusted & Replaced |
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| 2671980065R03 - NRC Website |
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NRC FOIM 366 U. S. NUCLEAft REGULATO%Y COMMIL40N LICENSEE EVENT REPORT CONTROL 8 LOCK: l l
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- E*CRT O ATE is0 EVENT DESCRIPTION AND PROS A8LE CONSEQUENCES h l3!2l lDuring nor=al operation, while verifying hydraulic snubber bleed rate, five Class 1 l
ydraulic snubbers were removed f rom service when the reactor was not in the shutdown l
,g,3, gg,,, ;cr refueling condition. This censtitutes operation in a degraded mode allowable by l
- LCO 4.3.10 and is reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.,
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- Similar report RO 80-61.
There was no ef f ec t on the health or safety of the public.
,,g, la67l l The five snubbers removed f or test were VSS-101, VSS-104, VSS-107. VSS-110 and I
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40 ei 42 43 44 47 CAUSE CESCRIPTION AND CO ARECTIVE ACTIONS h i i i o ; ]Non-bleeding hydraulic vent stack saubbers were reolaced bv snubbers with bleed caea-l l-lij gbility. Engineerinz evaluation decet nined that the bleed rate should be zero and the 1 l
(snubbers were adiusted to zero blaed rate in olace. Five stubbers were renoved.
I g,;7i g,;3, l tested, and replaced to verify that the actual bleed rate was zero.
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u REPORT DATE:
Januarv 6, 1981 REPORTABLE OCCURRENCE 80-65 ISSUE 1 OCCURRENCE DATE:
November 9, 1980 Page 1 of 3 FORT ST. VRAIN NUCLEAR GENERATIm STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 191/2 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267 /80-65 /03-X-1 Revised Final IDENTIFICATION OF OCCURRENCE:
During November,1980, five Class I hydraulic shock suppressors were removed from service, one at a time, for test. Each event constitutes operation in a degraded mode allowed by LCO 4.3.10 and is reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.
EVENT
DESCRIPTION
On five occasions, while the reactor was at power, operable Class 1 shock suppressors (snubbers) were removed from service for test:
VSS-110 - out of service from 0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br /> to 1235 hours0.0143 days <br />0.343 hours <br />0.00204 weeks <br />4.699175e-4 months <br /> on November 5, 1980 VSS-101 - out of service from 1305 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.965525e-4 months <br /> on November 5,1980, to 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br /> on November 6,1980 VSS-104 - out of service from 1007 hours0.0117 days <br />0.28 hours <br />0.00167 weeks <br />3.831635e-4 months <br /> to 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on November 6, 1980 VSS-111 - out of service from 1325 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.041625e-4 months <br /> on November 6,1980, to 1745 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.639725e-4 months <br /> on November 7,1980 Technical Specificaciou LCO 4.3.10 states that all shock suppressors on i
Class 1 piping systems shall be operable if the reactor is not shutdown or refueling. The LCO further statas that continued power operation af ter a snubber is determined to be inoperable is permissible only during the suc-ceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless the snubber is made operable sooner or replaced.
The five vent stack snubbers removed for test were returned to service with-l in the allowed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in all cases.
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REPORTABLE OCCURRENCE 80-65 ISSUE 1 Page 2 of 3
CAUSE
DESCRIPTION:
During performance of the hydraulic snubber functional test required each refueling by the Fort St. Vrain Technical Specifications, it was found that the 16 vent stack snubbers did not have bleed capability. This was reported as part of Reportable Occurrence 79-13.
The 16 non-bleeding hydraulic snubbers were modified or replaced so that bleed capability was available.
During the evaluation of seismic restraints in accordance with I & E Bul-letin 79-14, it was determined that the bleed rate on these 16 snubbers shou'.d be zero.
The blsed rate of the 16 vent stack snubbers was adjusted to zero with the snt.bbers in place. In order to verify that the bleed rate is in f act zero, each snubber is being removed, cesced, and replaced. During November, 1980, five snubbers were removed from service for test, resulting in five events of operation in a degraded mode allowed by LCO 4.3.10.
CORRECTIVE ACTION:
Each of the five snubbers were returned to service af ter testing was com-ple ted.
No further corrective action is anticipated or required for the f ;ve vent stack snubbers noted in this report.
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REPORTABLE OCCURRENCE 80-65 ISSUE 1 Page 3 of 3 Prepared By:
T.
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Richard R. Frost Technical Services Technician Reviewed By:
c-Tec a Services Supervisor Reviewed By:
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Frank M. Mathie Operations Manager Approved By:
W,o M Don Warembourg
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Manager, Nuclear Production
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| 05000267/LER-1980-001-03, /03X-1:on 800108,leak Found on 1B Helium Circulator Static Seal Internal to Circulator.Caused by Mfg Defect That Acted as Stress Riser & Caused Cyclic Failure of Bellows Matl.Circulator Replaced | /03X-1:on 800108,leak Found on 1B Helium Circulator Static Seal Internal to Circulator.Caused by Mfg Defect That Acted as Stress Riser & Caused Cyclic Failure of Bellows Matl.Circulator Replaced | | | 05000267/LER-1980-001-01, /01T-0:on 800108,while Operating Plant at Approx 1.5% of Rated Power,Leak Discovered on Helium Circulator Static Seal Internal 1B to Circulator.Cause Unknown.Reactor Shut Down & Circulator Replacement Begun | /01T-0:on 800108,while Operating Plant at Approx 1.5% of Rated Power,Leak Discovered on Helium Circulator Static Seal Internal 1B to Circulator.Cause Unknown.Reactor Shut Down & Circulator Replacement Begun | | | 05000267/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000267/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000267/LER-1980-002-03, /03L-0:on 800107,during Region Constraint Device Installation,Found That Startup Channel Scram Protection Not Operable at Less That or Equal to 100,000 Counts/Second. Caused by Improper Setpoints.Setpoint Change Initiated | /03L-0:on 800107,during Region Constraint Device Installation,Found That Startup Channel Scram Protection Not Operable at Less That or Equal to 100,000 Counts/Second. Caused by Improper Setpoints.Setpoint Change Initiated | | | 05000267/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000267/LER-1980-003-03, /03L-0:on 800110,while Reactor Was in Shutdown Condition,Three Hangers Found Impaired,Which Caused 21 Sys to Be Impaired.Caused by Failure to Reinstall Hangers Following Removal for Sys Mod.Hangers Will Be Modified | /03L-0:on 800110,while Reactor Was in Shutdown Condition,Three Hangers Found Impaired,Which Caused 21 Sys to Be Impaired.Caused by Failure to Reinstall Hangers Following Removal for Sys Mod.Hangers Will Be Modified | | | 05000267/LER-1980-004-03, /03L-0:on 800114,following Performance of Class I Shock Suppressor Surveillance Test,Two Snubbers Found Inoperable.Caused by Personnel Using Snubber Units as Stepping Platforms.Snubbers Repositioned | /03L-0:on 800114,following Performance of Class I Shock Suppressor Surveillance Test,Two Snubbers Found Inoperable.Caused by Personnel Using Snubber Units as Stepping Platforms.Snubbers Repositioned | | | 05000267/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000267/LER-1980-005-03, /03L-0:on 800111,during Release from Gaseous Waste Holdup Sys,Recorder Did Not Function Properly.Caused by Bad Bull Drive Gear & Clutch Assembly.Parts Replaced & Recorder Returned to Operation | /03L-0:on 800111,during Release from Gaseous Waste Holdup Sys,Recorder Did Not Function Properly.Caused by Bad Bull Drive Gear & Clutch Assembly.Parts Replaced & Recorder Returned to Operation | | | 05000267/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000267/LER-1980-006-03, /03L-0:on 800218,w/reactor at Less than 2% Power, Vent Stack Snubber VSS-117 Was Inoperable & Degraded Mode of Tech Spec LCO 4.3.10 Existed.Caused by Taking Reactor Critical W/Vent Stack Snubber Out of Svc for Maint | /03L-0:on 800218,w/reactor at Less than 2% Power, Vent Stack Snubber VSS-117 Was Inoperable & Degraded Mode of Tech Spec LCO 4.3.10 Existed.Caused by Taking Reactor Critical W/Vent Stack Snubber Out of Svc for Maint | | | 05000267/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000267/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000267/LER-1980-007-03, During Testing,Four of 12 Helium Circulator Seal Malfunction Pressure Differential Switch Units Tripped Outside Limits.Caused by Accumulation of Dirt on Switches.Switches Replaced | During Testing,Four of 12 Helium Circulator Seal Malfunction Pressure Differential Switch Units Tripped Outside Limits.Caused by Accumulation of Dirt on Switches.Switches Replaced | | | 05000267/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000267/LER-1980-008-03, /03L-0:on 800219,during Routine Surveillance Testing,Setpoints for Low Flow on One Dewpoint Moisture Monitor & for Fixed low-low Flow on Another Monitor Found Less than Min Acceptable.Caused by Instrument Calibr Drift | /03L-0:on 800219,during Routine Surveillance Testing,Setpoints for Low Flow on One Dewpoint Moisture Monitor & for Fixed low-low Flow on Another Monitor Found Less than Min Acceptable.Caused by Instrument Calibr Drift | | | 05000267/LER-1980-009-01, /01T-0:on 800225,while in Shutdown Condition,Test Evaluation Determined Bistable Trip Modules,When Used W/Mtu for Calibr of Process Trips,Induced Calibr off-set Which Could Allow Trips Outside Tech Specs.Bistables Recalibr | /01T-0:on 800225,while in Shutdown Condition,Test Evaluation Determined Bistable Trip Modules,When Used W/Mtu for Calibr of Process Trips,Induced Calibr off-set Which Could Allow Trips Outside Tech Specs.Bistables Recalibr | | | 05000267/LER-1980-009, Forwards LER 80-009/01T-0 | Forwards LER 80-009/01T-0 | | | 05000267/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000267/LER-1980-010-03, /03L-0:on 800303,at 10% Thermal Power,A Emergency Diesel Generator Would Not Load as Required for Weekly 50% Load Test Surveillance.Caused by Diesel Generator Governor Problem Which Reduced Speed Control Response | /03L-0:on 800303,at 10% Thermal Power,A Emergency Diesel Generator Would Not Load as Required for Weekly 50% Load Test Surveillance.Caused by Diesel Generator Governor Problem Which Reduced Speed Control Response | | | 05000267/LER-1980-011-03, /03L-0:on 800306-21,reactor Dewpoint Limiting Conditions for Operation Were Exceeded on One Occasion & Operation in Degraded Mode Occurred on Three Occasions. Caused by Problems W/Buffer Helium Sys | /03L-0:on 800306-21,reactor Dewpoint Limiting Conditions for Operation Were Exceeded on One Occasion & Operation in Degraded Mode Occurred on Three Occasions. Caused by Problems W/Buffer Helium Sys | | | 05000267/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000267/LER-1980-012, Forwards LER 80-012/01T-0 | Forwards LER 80-012/01T-0 | | | 05000267/LER-1980-012-01, /01T-0:on 800311,while Facility Was Operating at Less than 2% Power,Orifice Valves Not Set for Equal Flows & Temp Limit Was Exceeded.Caused by Inability to Close Orifice Valve to Equal Flow Position.Valve Freed Up | /01T-0:on 800311,while Facility Was Operating at Less than 2% Power,Orifice Valves Not Set for Equal Flows & Temp Limit Was Exceeded.Caused by Inability to Close Orifice Valve to Equal Flow Position.Valve Freed Up | | | 05000267/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000267/LER-1980-013-03, /03L-0:on 800310,during 58% Thermal Power Operation,Indicated Flow for Two Low Level Primary Coolant Dewpoint Moisture Monitors Discovered Less than Requirements.Caused by Inaccurate Flow Elements | /03L-0:on 800310,during 58% Thermal Power Operation,Indicated Flow for Two Low Level Primary Coolant Dewpoint Moisture Monitors Discovered Less than Requirements.Caused by Inaccurate Flow Elements | | | 05000267/LER-1980-014-03, /03L-0:on 800311,during Reactor Shutdown,Emergency Feedwater Snubber BFS-228E Observed to Be Missing Pin at Piston Rod Eye & Rendered Inoperable.No Cause Stated for Missing Pin.New Pin Fabricated & Installed | /03L-0:on 800311,during Reactor Shutdown,Emergency Feedwater Snubber BFS-228E Observed to Be Missing Pin at Piston Rod Eye & Rendered Inoperable.No Cause Stated for Missing Pin.New Pin Fabricated & Installed | | | 05000267/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000267/LER-1980-015, Forwards LER 80-015/03L-0 | Forwards LER 80-015/03L-0 | | | 05000267/LER-1980-015-03, /03L-0:on 800320,during Operation at Approx 60% Power,Emergency Feedwater Header Supply to Loop 2 Helium Circulation Water Turbine Drives Was Isolated to Repair Leaking Pressure Control Valve.Caused by Loose Block Bolt | /03L-0:on 800320,during Operation at Approx 60% Power,Emergency Feedwater Header Supply to Loop 2 Helium Circulation Water Turbine Drives Was Isolated to Repair Leaking Pressure Control Valve.Caused by Loose Block Bolt | | | 05000267/LER-1980-016, Forwards LER 80-016/03L-0 | Forwards LER 80-016/03L-0 | | | 05000267/LER-1980-016-03, During Testing,Four of 12 Helium Circulator Seal Malfunction Pressure Differential Switch Units Tripped Outside Limits.Caused by Dirt Accumulation in Electrical Switches.Switches Replaced | During Testing,Four of 12 Helium Circulator Seal Malfunction Pressure Differential Switch Units Tripped Outside Limits.Caused by Dirt Accumulation in Electrical Switches.Switches Replaced | | | 05000267/LER-1980-017-03, /03L-0:on 800311,w/plant Shut Down Due to Loss of Main Cooling Water Return Line,Plant Liquid Effluent Sample Required by SR Nr 1.1 Not Taken.Caused by Preempted Time Due to Plant Upset.Sampling Resumed on Next Shift | /03L-0:on 800311,w/plant Shut Down Due to Loss of Main Cooling Water Return Line,Plant Liquid Effluent Sample Required by SR Nr 1.1 Not Taken.Caused by Preempted Time Due to Plant Upset.Sampling Resumed on Next Shift | | | 05000267/LER-1980-017, Forwards LER 80-017/03L-0 | Forwards LER 80-017/03L-0 | | | 05000267/LER-1980-018-03, /03L-0:on 800327,w/plant Operating at Approx 51% Thermal Power,One Loop 2 Hot Reheat Header Activity Monitor Found Inoperable.Caused by Failure of Motorola Chip (MPS-66A)in Operational Amplifier to Detector Preamp | /03L-0:on 800327,w/plant Operating at Approx 51% Thermal Power,One Loop 2 Hot Reheat Header Activity Monitor Found Inoperable.Caused by Failure of Motorola Chip (MPS-66A)in Operational Amplifier to Detector Preamp | | | 05000267/LER-1980-018, Forwards LER 80-018/03L-0 | Forwards LER 80-018/03L-0 | | | 05000267/LER-1980-019-03, /03L-0:on 800327,operation in Degraded Mode of Limiting Condition 4.2.10 Occurred on Six Occasions & Reactor Dewpoint Limit of Limiting Condition 4.2.11 Was Exceeded Once.Caused by Problem W/Buffer Helium Sys | /03L-0:on 800327,operation in Degraded Mode of Limiting Condition 4.2.10 Occurred on Six Occasions & Reactor Dewpoint Limit of Limiting Condition 4.2.11 Was Exceeded Once.Caused by Problem W/Buffer Helium Sys | | | 05000267/LER-1980-019, Forwards LER 80-019/03L-0 | Forwards LER 80-019/03L-0 | | | 05000267/LER-1980-020, Forwards LER 80-020/03L-0 | Forwards LER 80-020/03L-0 | | | 05000267/LER-1980-020-03, During Testing,Two of 12 Helium Circulator Seal Malfunction Pressure Differential Switch Units Tripped Outside Limits.Caused by Accumulation of Dirt in Switches.Switches Replaced | During Testing,Two of 12 Helium Circulator Seal Malfunction Pressure Differential Switch Units Tripped Outside Limits.Caused by Accumulation of Dirt in Switches.Switches Replaced | | | 05000267/LER-1980-021, Forwards LER 80-021/03L-0 | Forwards LER 80-021/03L-0 | | | 05000267/LER-1980-021-03, /03L-0:on 800421,w/reactor Shut Down,Main Steam Pressure Low Instrument Discovered Inoperable.Caused by Bad Connection Due to Dirty Contact.Contacts Cleaned & Module Returned to Svc | /03L-0:on 800421,w/reactor Shut Down,Main Steam Pressure Low Instrument Discovered Inoperable.Caused by Bad Connection Due to Dirty Contact.Contacts Cleaned & Module Returned to Svc | | | 05000267/LER-1980-022-03, /03L-0:on 800424,during 800424-0510,operation W/Total Primary Coolant Oxidants Greater than 10 Ppm & Average Core Outlet Temp Greater than 1,200 Degrees Occurred on Five Occasions.Caused by Reaction of Moisture W/Core | /03L-0:on 800424,during 800424-0510,operation W/Total Primary Coolant Oxidants Greater than 10 Ppm & Average Core Outlet Temp Greater than 1,200 Degrees Occurred on Five Occasions.Caused by Reaction of Moisture W/Core | | | 05000267/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | | 05000267/LER-1980-023-03, /03L-0:from 800507-17,plant Was Operated W/Emergency Feedwater Header Supply to Helium Circulator Water Turbine Drives of One Loop Isolated on Four Separate Occasions.Caused by Valve Leakage & Line Leakage | /03L-0:from 800507-17,plant Was Operated W/Emergency Feedwater Header Supply to Helium Circulator Water Turbine Drives of One Loop Isolated on Four Separate Occasions.Caused by Valve Leakage & Line Leakage | | | 05000267/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000267/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | | 05000267/LER-1980-024-03, /03L-0:on 800512,at 47% Thermal power,1C Circulator Seal Differential Pressure Decreased Significantly Due to Unknown Causes.Equalizing Valve Closed & 1C Circulator Buffer Helium Pressure Returned to Normal | /03L-0:on 800512,at 47% Thermal power,1C Circulator Seal Differential Pressure Decreased Significantly Due to Unknown Causes.Equalizing Valve Closed & 1C Circulator Buffer Helium Pressure Returned to Normal | | | 05000267/LER-1980-025-03, /03L-0:on 800523,during 800523-30,total Primary Coolant Oxidants Were Greater than 10 Ppm W/Average Core Outlet Temp Above 1,200 F on Six Occasions.Caused by Moisture Increase & Carbon Monoxide & Dioxide Combination | /03L-0:on 800523,during 800523-30,total Primary Coolant Oxidants Were Greater than 10 Ppm W/Average Core Outlet Temp Above 1,200 F on Six Occasions.Caused by Moisture Increase & Carbon Monoxide & Dioxide Combination | |
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