LER-1980-061, Forwards LER 80-061/03L-0 |
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PLATTEVILLE, COLOR ADO 80651 October 31, 1980 Fort St. Vrain Unit No. I r.
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Mr. Karl V. Seyf rit, Director rn on
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Nuclear Regulatory Commission V
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/
.80-61, Final, submitted per the requirements of Technical Specification AC 7.5.2(b)2.
Also, please find enclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-267/80-61.
Very truly yours, c(
Don War ybourg Manager, Nuc3 ear Production DW/cis Enclosure cc: Director, MIPC 1
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- - e OCC'JRRENCE REPORT D!5tRIBUtt0'i N 2meer of Copies De pa r tmen t o f Ene r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
1 (P Letter)
San Francisco Operatione Of fice Atta California Patent Group 1333 Broadway.
' Cakland, California 94612' De pa r tment o f E ne r gy. - - - - - - - - - -. - - - - - - - - - - - - - - - - - -
1 (P Letter)
Office of Nuclear Engineerios Programs
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Vashington, D.C.
20545 i
De p a r t ama t o f Ene r gy '. - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
1 (P Letter)
Mr. Glen A. Newby, Chief WTR Branch Diviaton of Nuclear Power Development.
Mail Station 8-107 Washington, D.C.
20$45 De pa r tme nt o f Ene r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
1 (P Letter)
Attat Senior Program Coordinator P. O. Box 81325 San Diego, California 92138 Mr. Ka rl V. S e y f ri t. Dire ctor.. - - - - - - - - - - - - - - - - - - - - - - - -
1 (Original of P Letter Ragion IV and Copy of LER)
Office of Inspection and Enforcement Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 i
Arlington, Texas 16012 Director - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
1 (P Letter, LER)
Of fice of Management Information and Program Co.itrol U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Mr. 11 ch a rd Phe lp e - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (Original of FPLG Letter FSV. CA, Site plus.TVo Copies, One
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Representative Copy of P Letter, One General Atomic Company Copy of LER)
P. O. Box 426 Plattaville, Colorado 80651 3
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1 (P Letter LER) h. clear Safety Analysis Center
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REPORT DATE:
October 31, 1980 REPORTABLE OCCURRENCE 80-61 ISSUE O
' OCCURRENCE DATE:
October 3.1980 Page 1 of 3 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WEIE COUNTY ROAD 191/2 PLATTEVILLE, COLORADO 80651 a
REPORT No. 50-267/80-61/03-L-0 i
Final l
IDENTIFICATION OF OCCURRENCE:
On three. separate occasions between October 3, 1980, and October 13, 1980, the plant was operated with individual suubbers out of service for corrective /
i preventive maintenance.
Although the snubbers were _ operable prior to removal from service, these oc-currences are being. interpreted as a degraded mode of I40 4.'3.10, and are being repo:ted per Fort St. Vrain Technical Specification AC 7.5.2(b)2.
[
EVENT
DESCRIPTION
__ From October 3 through October 13, 1980, three snubbers were removed from service f or preventive / corrective maistenance. All three snubbers were in l
place and operable prior to their removal from service; however, a decision was made to perform the maintenance activities with the plant in operation in order to assure continued snubber operability. Because LCO 4.3.10 does not provide for removal of snubbers from service for preventive maintenance, i
these events are being interpreted as a degraded mode of the LCO. Details I
of ~ each occurrence are provided below.
a 1.
At 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br /> on October 3,1980, with the reactor operating at approximately 4% thermal power, CRS-822 was removed from service to fill the oil reservoir. A Plant Trouble Report had been initiated on September 22, 1980, stating that the snubber was low on oil.
The low oil situation did not render the snubber inoperable; however, on October 3, a decision was made to fill the snubber reservoir, thus ensuring its continued operability. The reservoir-was filled per approved procedure and the snubber returned en service at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on October 3,1980.
I 2.
Analysis' of a Plant Trouble Report initiated on October 7,1980, indicated that re-orientation of HOS-89 would be advisable, although the snubber was operable. On October 10, with the plant operating at 46% power and 133 MWe, H05-89 was still operable, but a decision-
~ was made to re-orient the snubber to assure that possible inter-farence problems would not render it inoperable. It was necessary I'
to remove the snubber from service in order to revise the reservoir orientation.. The snubber was removed at 1020 hours0.0118 days <br />0.283 hours <br />0.00169 weeks <br />3.8811e-4 months <br /> on October 10, 1980, and was returned to. service at 1220 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.6421e-4 months <br /> the same day.
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REPORTABLE OCCURRENCE 80-61 ISSUE O Page 2 of 3 EVENT
DESCRIPTION
(Cont'd) 3.
At 0937 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.565285e-4 months <br /> on October 13, 1980, with the plant operating at ap-proximately 46% thermal power and 130 MWe, HRS-159 was removed from service to elevate the oil reservoir. Analysis of a Plant Trouble Report initiated on October 9 indicated that although tha reservoir was not at the optimum angle, the snubber was operable.
On October 13, the snubber was still operable, but a decision was made to remove it from service to raise the reservoir, thus pro-viding greater gravity feed of oil from the reservoir to the snub-bar, and ensuring continued operability. The work was completed and the snubber returned to service at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on October 13.
Because the snubbers were operable prior to their removal from service, no adjustnent to the surveillance interval for SR 5.3.8a-X is required.
CAUSE
DESCRIPTION:
Cause of degraded mode operation in each instance covered by this report was removal of operable snubbers from service in order to perform preventive /
corrective maintenance. Details are as follows:
1.
Snubber CRS-822 was removed from service to fill the oil reservoir.
Although operable, the snubber was previously noted to be low on oil.
2.
Snubber HOS-89 was removed from service to re-orient the reservoir to preclude the possibility of future interference with structural material.
3.
Snubber ERS-139 was removed from service to elevate the oil reser-voir, thus assuring :ontinued supply of oil to the snubber.
CORRECTIVE ACTION:
Corrective actions for the occurrences described in this report were as follows:
1.
Snubber reservoir of CRS-822 was filled with oil per approved pro -
cedure, and the scubber returned to service.
2.
The reservoir of snubber HOS-89 was re-oriented to preclude inter-ference problems, and the snubber returned to service.
3.
The reservoir of snubber HRS-159 was elevated to assure continued oil supply, and the snubber returned to service.
No further corrective action is anticipated or required.
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.m REPORTABLE OCCURRENCE 80-61 ISSUE O Page 3 of 3 Prepared By:
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Cathy C/ Rirsch Technical Serv' ;es Technician Reviewed By:
W. Gahm Technical Services Supervisor Reviewed By:
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Frank M.jMathiy
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Operations Manager Approved By:
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Don Warenbourg' -/
Managed 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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