LER-1980-046, Forwards LER 80-046/03L-0 |
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- - 7 public service company or Odendo:
l 16805 ROAD 19%
PLATTEVILLC, COLC AADO 80651 -
Sr.p tember. 19, 1980 lort St. Vrain Unit No. l'
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P-80328 Mr. Karl V. Seyfrit, ' Director Nuclear Regulatory Commission Region IV Office of Inspection and Enforcement 611 Ryan Plaza Drive Suite 1000
- - Arlington, Texas 76012
' Reference: Facility Operating License No. DPR-34 Docket No. 50-267
Dear Mr. Seyfrit:
Enclosed please find a copy of Reportable Occurrence Report No. 50-267/
80-45, Final, submitted per the requirements of Technical Specification AC 7.5.2(b)2..
Also, please find enclosed ona copy of the Licensee Event Report for Reportable Occurrenc'e Report No. 50-267/80-46.
Very truly yours,
$U u.w l%
w Don Warembourg Manager Nuclear Production DW/cis Q
Enclosure cc: Director, MIPC f[
80092305.971
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-. REPORT DATE:
Septemb'er 19, 1980' REPORTABLE OCCURRENCE 80-46'
- - ISSUE O OCCURRENCE - DATE:
'Auaust'20, 1980 Page 1 of 3 FORT ST. VRAIN NUCLEAR GENERATIZ STATION PUBLIC SERVICE CGIPANY'0F COLORADO t16805 WELD COUNTY ROAD 191/2 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/80-46/03-L-0 Final IDENTIFICATION OF-OCCURRENCE:
From 1000lto'1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br /> on August 20, 1980, the plant was operated at power with the outlet 1 water temperature of the PCRV cooling water system greater than 120*F.
This constitutes operation in a degraded mode of LCO 4.2.15 b) and is reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.
EVENT
DESCRIPTION
At 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on August 20, 1980, with the plant operating at approximately 25% thermal power,. an entry was made in the operations log to indicate that the PCRV. cooling water outlet temperature was greater than 120*F.
Technical Specification LCO 4.2.15 b) states that the maximum outlet uater temperature of the PCRV cooling water system shall'not exceed 120*F.
The-reactor plant cooling water system provides cooling water to maintain PCRV concrete temperatures within established limits based on design heat loads.-
The. temperature of cooling water supplied to the PCRV barrel and top head, core support floor, 'and PCRV bottom head and bottom penetrations is via temperature controllers TC-4637 and TC-4638. These controllers are normally
. operated in the ~ automatic mode with the valves modulating to maintain temp-erature at a preset value.
A portion o5 the cooling water supplied via the on-line cooling water pump is diverted _to. the ~ PCRV top penetrations.. If desired, this water can be ad-mitted to the penetrations via -operation of TC-46209 and TC-46210 to vary the temperature by mixing hot and cold cooling. water supply. During normal plant operation, this design fenture is not utilized, and the system is oper-ated with TC-46209 and TC-46210 in manual with the corresponding valves closed.
TC-4637 and TC-4638, controllers for, the remainder of the system, are located in close proximity on~ che same control panel.
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,e REPORTABLE OCCURRENCE 80-46 ISSUE O Page 2 of 3
' EVENT
. DESCRIPTION: (Cont'd).
On. the day of this 'occurr2nce, the Shift Supervisor noticed that TC-46209 and TC-46210. were in the automatic mode with. the corresponding valves fluctu-ating. At that time, TC-4637 and TC-4638 were in automatic, which was the correct configuration. ' Discussion between the Operator and Shif t-Supervisor disclosed no reason f or TC-46209 and TC-46210 being.in automatic, and a.de-cision 'was made to return the ' controllers to manual. However, because of-the clcse proximity on the control ~ panel of-the four controllers in question, the Operator inadvertently placed TC-4637 and TC-463S in manual,-leaving TC-46209 and _ TC-46210 in automatic.1The ~ corresponding valves (TV-4637, 4637-1,14638, and 4638-1) went closed, thus isolating the cooling water to
- - the system. Shortly after TC-4637 and TC-4638 were placed in manual, PCRV outlet cooling water temperature exceeded the Technical Specification limit of 120*F.
Chech of.the temperature. recorder' revealed a maximum temperature of 134*F. was reached-at approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />.
Immediately upon. discovery of the out' of limit temperature, TC-4637 and TC-4638 were~ returned to the automatic position, the valves opened, and by 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />, the temperature had returned to an acceptable' limit. By 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br />, temperature had stabilized 'at approximately 110 to 112*F, which is the normal operating temperature.
No further operation-in a degraded mode of LCO 4.2.13 was observed'.
CAUSE
DESCRIPTION:
Cause of the out of. limit PCRV cooling water. outlet temperature was the in-advertent isolation of the cooling water to system 46 due to operation of the wrong controllers,
= CORRECTIVE ACTION:
Upon discovery that-the temperature had exceeded the Technical Specification limits, TC-46209. and TC-46210 were placed in 'nanual, TC-4637 and TC-4638 were returned 'to automatic, and the corresponding valves opened. PCRV cooling water outlet temperatures returned to acceptable limits by 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br /> and no further operation occurred in a degraded mode-of LCO 4.2.15.
No further corrective-action is anticipated or required.
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o REPORTABLE CCCURRENCE 80-46 ISSUE O Page 3 of 3 Prepared By:
' d('4 de
'Ift/ -
bd.
Cathy C. Hirsch a
Technical Services Technician Reviewed 3y:
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/ Technical Services Supervisor
. f/Gahm
- - Reviewed By:
) % /^ _. \\
Frank M.
!athie
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Operations Manager (E'
[4./tt.A t-Approved By:
'> c..t.fy i;
Don Warembourg
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Manager, Nuclear Production d'~
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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. 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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 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& 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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