LER-1979-102, /03L-0:on 791108,reactor Water Conductivity Exceeded Tech Spec Limit.Caused by Decomposition of Ion Exchange Resins Which Altered Ph Level.Eight Condenser Tubes Plugged & One Condensate Demineralizer Removed |
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POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACHMENT TO LER 79-102/03L-0 Page 1 of 3 During normal operation, reactor water conductivity exceeded the Technical Specification limit. The maximum abserved value of conductivity was 7.5 micromho/cm as compared to a limit of 5.0 micromho/cm as contained in Technical Specification, Appendix A,. Paragraph 3.6.C.4.
Initially a conductivity increase was noted at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on November 8, 1979 and investigation into the cause of the increased conductivity was commenced.
At 1915 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.286575e-4 months <br />, conductivity reached 3 micromho/cm, power was reduced from approximately 100% to 45% of rated power in preparation for possible shut-down, and isolation of main condenser water boxes to determine the source of leakage was commenced. Conductivity exceeded the Technical Specification limit at 2320 hours0.0269 days <br />0.644 hours <br />0.00384 weeks <br />8.8276e-4 months <br /> on November 8,1979 during the condenser tube plugging operation and returned below the limit at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />, November 9,1979, when shutdown preparations were discontinued.
While the reactor water dissolved oxygen concentration was not directly monitored, the feedwater dissolved oxygen concentration was monitored.
Since the dissolved oxygen in reactor water is a, proximately 21/2 times that found in feedwater under equilibrium conditions, C.' maximum concentration was probably less than 100 ppb in the reactor.
In addition, monitoring of conductivity, pH, chloride and feedwater quality continued throughout the event. Complete details of reactor water sampling data and other parameters of concern are included in this attachment.
The FitzPatrick Plant staff has thoroughly reviewed the transient and NED0-10899 titled " Chloride Control in BWR Coolants" which indicates that while high conductivity is undesirable, no damage to the reactor fuel or the reactor coolant pressure boundary should result because both the chloride and dissolved oxygen concentrations remained low throughout the transient.
Therefore, the event did not represent a significant hazard to the pub.ic health and safety.
As indicated in the tabulation of chemistry r asults included in this attachment, conductivity did not respond to the power decrease and the reactor coolant pH decreased to values which would rot be expected as a result of condenser tube leakage alone. Additional investiption indicates that the low pH values were probably due to the addition of some 1on exchange resin material to the reactor vessel. Decomposition of this material at the high temperatures found in the reactor vessel produces quantities of acids which reduce the pH.
Investigation into the possible sources of resins revealed that one condensate demineralizer bed, which was in service throughout the transient, contained a significant quantity of fine material.
It is t r al s he result of fracturing of a quantity o lon exch 9e es n
aning operations or the presence of powdered resin od n the ion exchange bed which should contain on j beaded materia. A o al f 8 condenser tubes were ; lugged and one condensate demineralizer was removed from service permitting a return to rated power.
1528 238
POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRlCK NUCLEAR POWER PLANT cys P
DOCKET NO. 50-333 N
ATTACHMENT TO LER 79-102/03L-0 Page 2 of 3 cy3 N
REACTOR WATER FEEDWATER tr7 CHLORIDE CONDUCTIVITY Diss0LVED CONDUCTIVITY c-DATE TIME (ppb)*
- oji, (mi c romho/cm)
(micromho/cm)
REMARKS 9
i 11/ 8/79 0845 45 5.8 0.73 30 0.06 Reutine Analysis prior to event - Cleanup system influent 1345 5.0 1.20 Cleanup system influent 1430 5.1 1.50 Cleanup system i n f l ue nt 1830 38 5.0 2.7 Cleanup system influent 11/ 8/79 1915 3.0 Power reduction from 100% to 45%, commenced tube plugging operation 2000 40 4.9 3.4 20 0.08 Cleanup system influent Conductivity indication 11/ 8/79 2320 5.0 at Technical Speci fication limi t 2330 38 4.7 5.5 24 0.18 Cleanup system influent 11/ 9/79 0100 5.6 Cleanup system influent 0215 5.4/6.1 Cleanup system influent /
Rec 3,ulation Loop 0330 50 4.6 5 5/6.5 Cleanup system influent /
Recirculation loop 0430 5 1/5.9 Cleanup system influent /
Recirculation Loop 0530 5.2/6.4 Cleanup cystem influent /
Recirculation Loop 0635 4.2 6.7/7.5 Cleanup system influent /
Recirculation Loop i
I l
POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRlCK NUCLEAR POWER PLANT DOCKET NO. 50-333
(([
C'd ATTACHMENT TO LER 79-102/03L-0 Page 3 of 3 CO REACTOR WATER FEEDWATER csJ CHLORIDE CONDUCTIVITY Diss0LVED CONDUCTIVITY Lf7 DATE TIME (ppb) *
- fil, (mi c romho/cm)
(micromho/cm)
REMARKS 9
11/ 9/79 0730 30 4.7 5.75/6.7 Cleanup system influent /
Recirculation Loop 1000 35 5.0 4.9 25 Cleanup system influent 1230
< 20 4.7 6.4 Cleanup system influent 1430 4.95 Cleanup system influent 1630 76 4.9 3.9 Cleanup system influent 2030 70 4.9 3.0 Cleanup system influent 11/10/79 0030
< 20 5.0 2.7 Clean,ip system influent 0400 44 5.0 2.9 Cleanup system influent 0800 90 5.1 2.45 Cleanup system influent 1205 52 5.0
'2.1 Cleanup system influent g
1600 44 5.0 1.65 Cleanup system influent 11/11/79 0600
< 20 5.0 1.40 Cleanup system influent 11/12/79 0145
< 20 5.4 0.82 23 0.06 Cleanup system influent 11/13/79 2100 Tube plugging operations complete, began power ascension to 100%
- Technica l specific ation limits for chloride and conducti d ty are 500 ppt and 5.0 micromho/ cm respectively.
L ER79-076 c nd 79-096 ar e relatc d events.
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| 05000333/LER-1979-001-03, /03L-0 on 790105:failure to Perform Core Performance Surveillance on 781210 & 781223.Currently Developing Surveillance Test Checkoff List,To Ensure That Test Is Not Overlooked Again | /03L-0 on 790105:failure to Perform Core Performance Surveillance on 781210 & 781223.Currently Developing Surveillance Test Checkoff List,To Ensure That Test Is Not Overlooked Again | | | 05000333/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000333/LER-1979-002-03, /03L-0 on 790108:flow Biased Portion of Average Power Range Monitor B Inoperable.Caused by Operational Amplifier Failure.Circuit Board Replaced | /03L-0 on 790108:flow Biased Portion of Average Power Range Monitor B Inoperable.Caused by Operational Amplifier Failure.Circuit Board Replaced | | | 05000333/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000333/LER-1979-003-03, /03L-0 on 790115:during Mainsteam Flow, Surveillance Procedure Instrument 02-DPIS-116B Found Set at 110 psid,2 Psid Above Tech Spec Max Due to Drift in Differential Pressure Switch | /03L-0 on 790115:during Mainsteam Flow, Surveillance Procedure Instrument 02-DPIS-116B Found Set at 110 psid,2 Psid Above Tech Spec Max Due to Drift in Differential Pressure Switch | | | 05000333/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000333/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000333/LER-1979-004-03, /03L-0 on 790119:while Performing Operations Surveillance Test F-St-76D,water Leak Noted on Post Indicator Valve 76-FPS-30 & Discovered Water Leaking from Lubrication Line.Caused by Shovel Cut During Snow Removal | /03L-0 on 790119:while Performing Operations Surveillance Test F-St-76D,water Leak Noted on Post Indicator Valve 76-FPS-30 & Discovered Water Leaking from Lubrication Line.Caused by Shovel Cut During Snow Removal | | | 05000333/LER-1979-005-04, /04L-0 on 790124: Apparent Excessive Solution Release from Makeup Water Treatment Waste Neutralizer Tanks to Circulating Water Discharge Tunnel Noted.Calculations Show Tech Specs Not Exceeded | /04L-0 on 790124: Apparent Excessive Solution Release from Makeup Water Treatment Waste Neutralizer Tanks to Circulating Water Discharge Tunnel Noted.Calculations Show Tech Specs Not Exceeded | | | 05000333/LER-1979-005, Forwards LER 79-005/04L-0 | Forwards LER 79-005/04L-0 | | | 05000333/LER-1979-006, Forwards LER 79-006/03X-1 | Forwards LER 79-006/03X-1 | | | 05000333/LER-1979-006-03, /03X-1:on 790124,during Normal Operations,Ground Fault on 125 Station Battery a Noted.Caused by Bellows Failure on Pressure Switch Circuit safety-relief Valve 02-RV-71J.Ground Cleared.Valve Restored to Operation | /03X-1:on 790124,during Normal Operations,Ground Fault on 125 Station Battery a Noted.Caused by Bellows Failure on Pressure Switch Circuit safety-relief Valve 02-RV-71J.Ground Cleared.Valve Restored to Operation | | | 05000333/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000333/LER-1979-007-03, /03L-0 on 790125:jet Pump Operability Surveillance Had Not Been Conducted on 790123-24 as Required.Procedures Subsequently Revised | /03L-0 on 790125:jet Pump Operability Surveillance Had Not Been Conducted on 790123-24 as Required.Procedures Subsequently Revised | | | 05000333/LER-1979-008-03, /03L-0 on 790125:core Performance Surveillance Not Done on 790120-22.Operations Surveillance Test for Daily Checks Was Being Developed to Include check-off of Surveillance Requirements.Caused by Operator Error | /03L-0 on 790125:core Performance Surveillance Not Done on 790120-22.Operations Surveillance Test for Daily Checks Was Being Developed to Include check-off of Surveillance Requirements.Caused by Operator Error | | | 05000333/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000333/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000333/LER-1979-009-03, /03L-0 on 790205:rod Control Drive Rendered Inoperable in Order to Repair Leak in Control Rod Drive Sys Hydraulic Control Unit.Upon Completion of Repair,All Components Returned to Svc | /03L-0 on 790205:rod Control Drive Rendered Inoperable in Order to Repair Leak in Control Rod Drive Sys Hydraulic Control Unit.Upon Completion of Repair,All Components Returned to Svc | | | 05000333/LER-1979-010, Forwards LER 79-010/03L-0 | Forwards LER 79-010/03L-0 | | | 05000333/LER-1979-010-03, /03L-0 on 790202:step Increase in Indicated Core Flow.Caused by Earlier Failure of Square Root Computation Module for Jet Pump.Square Root Computation Module Replaced W/Identical Unit & Core Flow Evaluation Test Completed | /03L-0 on 790202:step Increase in Indicated Core Flow.Caused by Earlier Failure of Square Root Computation Module for Jet Pump.Square Root Computation Module Replaced W/Identical Unit & Core Flow Evaluation Test Completed | | | 05000333/LER-1979-011-03, /03L-0 on 790214:drywell Atmospheric Sample Isolation Valve 27-SOV-123B Blew a Fuse.Caused by Shorted Valve Solenoid.Incident Recurred 790306.Will Submit Followup Rept When Valve Replacement Is Completed | /03L-0 on 790214:drywell Atmospheric Sample Isolation Valve 27-SOV-123B Blew a Fuse.Caused by Shorted Valve Solenoid.Incident Recurred 790306.Will Submit Followup Rept When Valve Replacement Is Completed | | | 05000333/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000333/LER-1979-014, Forwards LER 79-014/01T-0 | Forwards LER 79-014/01T-0 | | | 05000333/LER-1979-014-01, /01T-0 on 790312:calculations in Piping Stress Analysis Are Being Redone on Accelerated Basis by Architect/Engineer.Shutdown Will Continue Until All Problems Are Resolved.Final Rept on Matter Is Forthcoming | /01T-0 on 790312:calculations in Piping Stress Analysis Are Being Redone on Accelerated Basis by Architect/Engineer.Shutdown Will Continue Until All Problems Are Resolved.Final Rept on Matter Is Forthcoming | | | 05000333/LER-1979-015, Forwards LER 79-015/03X-1 | Forwards LER 79-015/03X-1 | | | 05000333/LER-1979-015-03, /03X-1:on 790315,during Load Reduction & Shutdown, Rod Sequence Control Sys Failed to Pass Operations Surveillance Test F-ST-23A.Cause Unstated.Mode Switch Moved from Shutdown Position.Sys Repaired | /03X-1:on 790315,during Load Reduction & Shutdown, Rod Sequence Control Sys Failed to Pass Operations Surveillance Test F-ST-23A.Cause Unstated.Mode Switch Moved from Shutdown Position.Sys Repaired | | | 05000333/LER-1979-020, Forwards Revised LER 79-020/03X-1 | Forwards Revised LER 79-020/03X-1 | | | 05000333/LER-1979-020-03, During Normal Cold Shutdown,Operations Surveillance Testing Revealed That Emergency Diesel Generator Starting Air Compressor 93-AC-B1 Did Not Load Properly.Caused by Dirt in Unloader | During Normal Cold Shutdown,Operations Surveillance Testing Revealed That Emergency Diesel Generator Starting Air Compressor 93-AC-B1 Did Not Load Properly.Caused by Dirt in Unloader | | | 05000333/LER-1979-023-99, Fire Protection Piping Associated W/Hpci Maint Intentionally to Permit Required HPCI Maint.Partial Disassembly of Fire Protection Piping Required.Following Maint,Piping Restored | Fire Protection Piping Associated W/Hpci Maint Intentionally to Permit Required HPCI Maint.Partial Disassembly of Fire Protection Piping Required.Following Maint,Piping Restored | | | 05000333/LER-1979-023, Forwards Revised LER 79-023/99X-1 | Forwards Revised LER 79-023/99X-1 | | | 05000333/LER-1979-024, Forwards Revised LER 79-024/03X-1 | Forwards Revised LER 79-024/03X-1 | | | 05000333/LER-1979-024-03, Emergency Svc Water Pump Failed to Meet Shutoff Head Requirements of Tech Spec. Caused by Normal Wear.Overhaul & Minor Mod of Impeller by Manufacturer Restored Shutoff Head to within Tech Specs | Emergency Svc Water Pump Failed to Meet Shutoff Head Requirements of Tech Spec. Caused by Normal Wear.Overhaul & Minor Mod of Impeller by Manufacturer Restored Shutoff Head to within Tech Specs | | | 05000333/LER-1979-026, Forwards LER 79-026/03L-0 | Forwards LER 79-026/03L-0 | | | 05000333/LER-1979-026-03, /03L-0 on 790507:radwaste Bldg Exhaust Fan 69-FN-8A Did Not Trip Per Hi-Hi Radiation Signal.Caused by Misadjusted Position Switch Associated W/Discharge Damper. Switch Linkage Adjusted | /03L-0 on 790507:radwaste Bldg Exhaust Fan 69-FN-8A Did Not Trip Per Hi-Hi Radiation Signal.Caused by Misadjusted Position Switch Associated W/Discharge Damper. Switch Linkage Adjusted | | | 05000333/LER-1979-027-03, /03L-0 on 790514:instrument 02-3-LIS-72D Tripped Minus 47.3 Inches.Instrument Recalibr,Then Replaced.Weekly Testing Will Continue to Assure Good Performance | /03L-0 on 790514:instrument 02-3-LIS-72D Tripped Minus 47.3 Inches.Instrument Recalibr,Then Replaced.Weekly Testing Will Continue to Assure Good Performance | | | 05000333/LER-1979-027, Forwards LER 79-027/03L-0 | Forwards LER 79-027/03L-0 | | | 05000333/LER-1979-028-03, /03L-0 on 790517:during Cold Shutdown,Level Instrument of Carbon Dioxide Storage Sys Was Out of Calibr. Caused by Procedural Error.Instrument Racalibr & Satisfactorily Tested | /03L-0 on 790517:during Cold Shutdown,Level Instrument of Carbon Dioxide Storage Sys Was Out of Calibr. Caused by Procedural Error.Instrument Racalibr & Satisfactorily Tested | | | 05000333/LER-1979-028, Forwards LER 79-028/03L-0 | Forwards LER 79-028/03L-0 | | | 05000333/LER-1979-029, Forwards LER 79-029/03L-0 | Forwards LER 79-029/03L-0 | | | 05000333/LER-1979-029-03, /03L-0 on 790518:during Snubber insp,14 Snubbers Required Some Work & Six Snubbers Were Determined to Be Potentially Inoperable.Snubbers Removed & Tested.Two Snubbers Failed Test & Were Declared Inoperable | /03L-0 on 790518:during Snubber insp,14 Snubbers Required Some Work & Six Snubbers Were Determined to Be Potentially Inoperable.Snubbers Removed & Tested.Two Snubbers Failed Test & Were Declared Inoperable | | | 05000333/LER-1979-030, Forwards LER 79-030/03L-0 | Forwards LER 79-030/03L-0 | | | 05000333/LER-1979-030-03, /03L-0 on 790518:during Cold Shutdown,Test Point Was Discovered in Error.Caused by Deviations in Conduction of Surveillance Test Procedures F-ISP-89.Procedure Was Immediately Correted & Surveillance Complete | /03L-0 on 790518:during Cold Shutdown,Test Point Was Discovered in Error.Caused by Deviations in Conduction of Surveillance Test Procedures F-ISP-89.Procedure Was Immediately Correted & Surveillance Complete | | | 05000333/LER-1979-031, Forwards LER 79-031/03L-0 | Forwards LER 79-031/03L-0 | | | 05000333/LER-1979-031-03, /03L-0 on 790519:fire Door Between North & South Emergency Switch Gear Rooms Failed to Close on Automatic Signal.Door & Closing Mechanism Lubricated & Adjusted | /03L-0 on 790519:fire Door Between North & South Emergency Switch Gear Rooms Failed to Close on Automatic Signal.Door & Closing Mechanism Lubricated & Adjusted | | | 05000333/LER-1979-032, Forwards LER 79-032/03L-0 | Forwards LER 79-032/03L-0 | | | 05000333/LER-1979-032-03, /03L-0 on 790519:sequencing Timer Associated W/Total Flooding Carbon Dioxide Sys Not Functioning Properly.Cause Not Stated.Sequencing Timer Cams Adjusted | /03L-0 on 790519:sequencing Timer Associated W/Total Flooding Carbon Dioxide Sys Not Functioning Properly.Cause Not Stated.Sequencing Timer Cams Adjusted | | | 05000333/LER-1979-033-03, /03L-0 on 790524:during Review of Plant Sys, Determined That Reactor Bldg Cooling Sys Supply & Return Lines to Drywell Equipment Drain Sump Did Not Have Seismic Stress Analysis Performed.Uncertain If It Is Required | /03L-0 on 790524:during Review of Plant Sys, Determined That Reactor Bldg Cooling Sys Supply & Return Lines to Drywell Equipment Drain Sump Did Not Have Seismic Stress Analysis Performed.Uncertain If It Is Required | | | 05000333/LER-1979-033, Forwards LER 79-033/03L-0 | Forwards LER 79-033/03L-0 | | | 05000333/LER-1979-034-03, /03L-0 on 790531:data Sheets Associated W/Instrument Surveillance Procedures F-ISP-4.5 Had Not Been Revised as Part of Procedure Revision Which Changed Instruments Calibr Range.Personnel Reinstructed | /03L-0 on 790531:data Sheets Associated W/Instrument Surveillance Procedures F-ISP-4.5 Had Not Been Revised as Part of Procedure Revision Which Changed Instruments Calibr Range.Personnel Reinstructed | | | 05000333/LER-1979-034, Forwards LER 79-034/03L-0 | Forwards LER 79-034/03L-0 | |
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