LER-1981-006, /03L-0:on 810324,rept Not Submitted Per Tech Spec 6.9.2.b.2 When Action Mode of Tech Spec 3.1.5.d Was Entered. Caused by Misinterpretation of Reporting Requirements.Plant in Process of Obtaining Interpretations of Requirements |
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U>> S NUC'LKAR RKOULATORYCOMMISSION NRC PORM 5543 P TTS lPLKASKPRINT OR TYP Al L RKOUIRKO INPORMATION) 0 0Qaa 1 1 1 1 Q>>~Qa LiCm~'455 TYPS J0 Ssi LICENSEE EVEI4IT REPORT CONTROt.'BLCCISI I
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~O TS 6.9.2.b.2 when the action mode of TS 3.1.5.d was entered.
'This finding is documented in I 6 E Inspection Reports 50-250/81-05 and 50-251/81-05.
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44 41 CAUSK OKSCRIPTION ANO CORRKCTIVKACTIONS Q27 The failure to report entry into an action mode was due to a misinterpreta-tion of the reporting requirements associated with TS 6.9.2.b.2.
The plant
~II is in the process of obtaining interpretations (of Regulatory Guide 1.16) made by both the Commission and General Counsel.
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REPORTABLE OCCURRENCE 250-8 6
LICENSEE EVENT REPORT PAGE
'QJO Additional Event Descri tion and Probable Conse uences:
Reference Inspection Report Nos. 50-250/81-05 and 50-251/81-05 During review of Quality Control Surveillance Reports "the (NRC) inspector noted that the technical specification limit for chloride concentration was exceeded in the unit 3 reactor coolant system (RCS) for several days in May 1980 while unit 3 was in cold shutdown.
Technical Specification Limiting Condition for Operation 3.1.5.d.
requires that chloride concentration be maintained at less than 0.15 ppm. 'or several days in May 1980, Unit 3 RCS chloride concentration was 0.20 ppm.
The unit was in cold shutdown which was the. condition required by LCO 3.1.5.d.
The licensee concluded that LCO 3.1.5.d.
had been exceeded but that since the plant was already in the condi-tion required by technical specifications and corrective action was taken that no violation of TS 3.1.5.d.
had occurred and that no report was required.
The inspec-tor noted that the licensee reporting requirements for 30 day reportable occurrences are identical to Regulatory Guide 1.16, 30 day reportable occurrence requirements, less the examples provided in the Regulatory Guide.
The Regulatory Guide paragraphs c.2.a(2) and c.2.b(2)
(reporting requirements for degraded mode) have previously been interpreted to mean that
'...whenever a parameter or system enters an action mode described in the related LCO, no violation of, the specification has occurred, but a 30 day written report is required.
'he licensee is not committed to follow Regulatory Guide 1.16, Reporting of Operating Information Appendix A Technical Specifications.
The licensee's Technical Specification 6.9 "Reporting Requirements" and section 6.9.2.b "Thirty Day
$lritten Reports" is a verbatum copy of Regulatory Guide 1.16 less the examples produced in the regulatory Guide; therefore, the interpretation of that portion of the Regulatory Guide is con-sidered to be an equally valid interpretation of the licensee reporting requirement.
The licensee did not have the benefit of the Inspection and Enforcement Manual Interpretations when he decided that the occurrence was not reportable; however, that not withstanding, the failure to report the out of specification RCS chloride'on-centration is a violation of Technical Specification 6.9.2.b(2).
(250, 251/81-05-02).
The licensee determined that the source of the chloride in the RCS was from. internal leakage in the boron evaporators contaminating the concentrated boric acid solution which was then transferred to the boric acid storage tanks.
Subsequent borations then transferred small amounts of chloride to the RCS of both units.
The dilution of the contaminated boric acid solution by the large volume of pure water in the RCS and the continuous purification of the RCS by the Chemical and Volume Control System (CVCS) demineralizers kept the chloride concentration within specification.
During the Unit 3 cold shutdown,
- however, the continuous purification process was lost for several days as a result of maintenance requirements.
The chloride concentration then slowly increased to 0.20 ppm apparently as a result of achieving a new higher equil-ibrium level with the 'resident'hlorides leaching out of RCS materials and corro-sion product inventory within the RCS and interconnected systems.
3~hen the CVCS system was returned to service, chloride concentrations were brought back into specification.
The boric acid storage tanks have been internally cleaned and are now chloride free.
R'eplacement steam tube bundles (for boric acid evaporators) have been placed on order.
Replacement of these tube bundles will complete the long term, corrective action planned by the licensee."
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| 05000251/LER-1981-001-03, /03L-0:on 810112,during Startup,For 4-h,condensate Storage Tank Contained Less than 185,000 Gallons Required by Tech Spec 3.8.1.C.Caused by Increased Water Demand During Low Power Physics Testing Exceeding Treatment Plant Ou | /03L-0:on 810112,during Startup,For 4-h,condensate Storage Tank Contained Less than 185,000 Gallons Required by Tech Spec 3.8.1.C.Caused by Increased Water Demand During Low Power Physics Testing Exceeding Treatment Plant Output | | | 05000251/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000250/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000250/LER-1981-001-03, /03L-0:on 810101,while Performing Surveillance on Emergency Diesel Generator B,Loss of Voltage Control Occurred.Caused by Fuse Failure.Fuses Were Replaced.Annual Surveillance Will Include Fuse Checks | /03L-0:on 810101,while Performing Surveillance on Emergency Diesel Generator B,Loss of Voltage Control Occurred.Caused by Fuse Failure.Fuses Were Replaced.Annual Surveillance Will Include Fuse Checks | | | 05000250/LER-1981-002, Forwards LER 81-002/01T-0 | Forwards LER 81-002/01T-0 | | | 05000250/LER-1981-002-01, /01T-0:on 810103,during Planned Shutdown,Boric Acid Flowpath from Boric Acid Tanks Found Obstructed.Caused by Reduced Temp Resulting from Failure of One Channel of Heat Tracing Circuit 21.Temp Setpoint Increased | /01T-0:on 810103,during Planned Shutdown,Boric Acid Flowpath from Boric Acid Tanks Found Obstructed.Caused by Reduced Temp Resulting from Failure of One Channel of Heat Tracing Circuit 21.Temp Setpoint Increased | | | 05000251/LER-1981-002-03, /03L-0:on 810214,boric Acid Flow in Normal Flowpath from Boric Acid Tanks Could Not Be Established & Low Temp Reading Found in Flowpath on 810217.Caused by Three Splices Needing Repair on Heat Tracing Circuits | /03L-0:on 810214,boric Acid Flow in Normal Flowpath from Boric Acid Tanks Could Not Be Established & Low Temp Reading Found in Flowpath on 810217.Caused by Three Splices Needing Repair on Heat Tracing Circuits | | | 05000251/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000250/LER-1981-003-01, /01T-0:on 810105,new Coil Assembly in Spare Parts Storage Found to Have Crack in Spool End Plate.Cause Not Stated.One Coil in Svc Found Cracked.Coil Replaced.All New Coils &/Or Relays Will Be Inspected Upon Receipt | /01T-0:on 810105,new Coil Assembly in Spare Parts Storage Found to Have Crack in Spool End Plate.Cause Not Stated.One Coil in Svc Found Cracked.Coil Replaced.All New Coils &/Or Relays Will Be Inspected Upon Receipt | | | 05000251/LER-1981-003-03, /03L-0:on 810218,leak Discovered in Rcs.Caused by Cracked Weld Between Vent Valve Line & 4A Reactor Coolant Pump Seal Supply Line.Vent Line Cut & Rewelded to Seal Line. Mod Will Be Implemented | /03L-0:on 810218,leak Discovered in Rcs.Caused by Cracked Weld Between Vent Valve Line & 4A Reactor Coolant Pump Seal Supply Line.Vent Line Cut & Rewelded to Seal Line. Mod Will Be Implemented | | | 05000250/LER-1981-003, Forwards LER 81-003/01T-0 | Forwards LER 81-003/01T-0 | | | 05000251/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000250/LER-1981-004, Forwards Updated LER 81-004/03X-1 | Forwards Updated LER 81-004/03X-1 | | | 05000251/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000250/LER-1981-004-03, During Power Operation Auxiliary Feedwater Pump a Failed to Meet Acceptance Criteria Per Tech Spec 4.10.1.Caused by Damaged Valve Plug. Cause of Damage Not Determined.Stem & Plug Replaced | During Power Operation Auxiliary Feedwater Pump a Failed to Meet Acceptance Criteria Per Tech Spec 4.10.1.Caused by Damaged Valve Plug. Cause of Damage Not Determined.Stem & Plug Replaced | | | 05000251/LER-1981-004-03, /03L-0:on 810322,reactor Trip Resulted from Steam Flow/Feedwater Flow Mismatch Coincident W/Steam Generator a Low Level.Caused by Failed Solenoid Coil on Feedwater Regulator Valve.Evaluation Continuing | /03L-0:on 810322,reactor Trip Resulted from Steam Flow/Feedwater Flow Mismatch Coincident W/Steam Generator a Low Level.Caused by Failed Solenoid Coil on Feedwater Regulator Valve.Evaluation Continuing | | | 05000250/LER-1981-005, Forwards LER 81-005/01T-0 | Forwards LER 81-005/01T-0 | | | 05000251/LER-1981-005-03, /03L-0:on 810407,need for Governor Adjustment Found During Auxiliary Feedwater Pump a Test & Pump C Taken Out of Svc for IE Bulletin 79-14 Mods.Cause Not Stated. Governors Repaired | /03L-0:on 810407,need for Governor Adjustment Found During Auxiliary Feedwater Pump a Test & Pump C Taken Out of Svc for IE Bulletin 79-14 Mods.Cause Not Stated. Governors Repaired | | | 05000251/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000250/LER-1981-005-01, /01T-0:on 810310,drain Header to Floor of Component Cooling Water Pump & Heat Exchanger Room Backed Up.Caused by Overflow of Laundry Water from Monitor Tank. Laundry Water Transfer Terminated | /01T-0:on 810310,drain Header to Floor of Component Cooling Water Pump & Heat Exchanger Room Backed Up.Caused by Overflow of Laundry Water from Monitor Tank. Laundry Water Transfer Terminated | | | 05000251/LER-1981-006-03, /03L-0:on 810423,snubber on Supply Steam Line to Auxiliary Feedwater Sys Observed to Have Broken Loose. Caused by Failure of Threaded Joint for Connection of Snubber Rod from Turnbuckle to Adaptor Plate.Joint Welded | /03L-0:on 810423,snubber on Supply Steam Line to Auxiliary Feedwater Sys Observed to Have Broken Loose. Caused by Failure of Threaded Joint for Connection of Snubber Rod from Turnbuckle to Adaptor Plate.Joint Welded | | | 05000251/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000250/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000250/LER-1981-006-03, /03L-0:on 810324,rept Not Submitted Per Tech Spec 6.9.2.b.2 When Action Mode of Tech Spec 3.1.5.d Was Entered. Caused by Misinterpretation of Reporting Requirements.Plant in Process of Obtaining Interpretations of Requiremen | /03L-0:on 810324,rept Not Submitted Per Tech Spec 6.9.2.b.2 When Action Mode of Tech Spec 3.1.5.d Was Entered. Caused by Misinterpretation of Reporting Requirements.Plant in Process of Obtaining Interpretations of Requirements | | | 05000250/LER-1981-007-03, /03L-0:on 810401,during Planned Maint,Disc Stud Nut Discovered Missing from 3A Main Feedwater Check Valve & Pivot Pins Missing from 3A Feedwater Bypass Check Valve. Improved Locking Device Will Be Installed During Outage | /03L-0:on 810401,during Planned Maint,Disc Stud Nut Discovered Missing from 3A Main Feedwater Check Valve & Pivot Pins Missing from 3A Feedwater Bypass Check Valve. Improved Locking Device Will Be Installed During Outage | | | 05000251/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000251/LER-1981-007-03, /03L-0:on 810426,component Cooling Water Surge Tank Low Level Alarm Sounded & Containment Sump Level Found Increasing.Caused by Failed Flexitallic Gasket on Inlet Flange of Excess Letdown Heat Exchanger | /03L-0:on 810426,component Cooling Water Surge Tank Low Level Alarm Sounded & Containment Sump Level Found Increasing.Caused by Failed Flexitallic Gasket on Inlet Flange of Excess Letdown Heat Exchanger | | | 05000250/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000251/LER-1981-008-03, /03L-0:on 810717,while Performing Instrumentation Repairs on Pressurizer Spray Valve PCV-4-455B,RCS Leakage Discovered in Unused & Capped Packing Leakoff Line.Caused by Failure of Stem Seal Bellows & Crack in Nipple | /03L-0:on 810717,while Performing Instrumentation Repairs on Pressurizer Spray Valve PCV-4-455B,RCS Leakage Discovered in Unused & Capped Packing Leakoff Line.Caused by Failure of Stem Seal Bellows & Crack in Nipple | | | 05000251/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000250/LER-1981-008-03, /03L-0:on 810416,crack Found in Weld on Drain Line from Charging Sys Downstream of Regenerative Heat Exchanger. Probably Caused by Stress Due to Line Vibration.Defective Area Cut Out,Nipple Shortened & Weld Replaced | /03L-0:on 810416,crack Found in Weld on Drain Line from Charging Sys Downstream of Regenerative Heat Exchanger. Probably Caused by Stress Due to Line Vibration.Defective Area Cut Out,Nipple Shortened & Weld Replaced | | | 05000250/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000251/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000251/LER-1981-009-03, /03L-0:on 810728,bus 4A Failed to Transfer Properly (Startup Acb 4AA05 Did Not Close After Auxiliary Acb 4AA02 Tripped).Probably Caused by Transfer Inhibit Relay 162/4A2 W/Loose Crimp on Coil Wire.Relay Replaced | /03L-0:on 810728,bus 4A Failed to Transfer Properly (Startup Acb 4AA05 Did Not Close After Auxiliary Acb 4AA02 Tripped).Probably Caused by Transfer Inhibit Relay 162/4A2 W/Loose Crimp on Coil Wire.Relay Replaced | | | 05000250/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000250/LER-1981-009-03, /03L-0:on 810420,while Performing Low Power Physics Testing,Reactor Protection Bistables Associated W/ N-43 Found Not in Trip Mode While Instrument Used as Input. Caused by Procedural Inadequacy | /03L-0:on 810420,while Performing Low Power Physics Testing,Reactor Protection Bistables Associated W/ N-43 Found Not in Trip Mode While Instrument Used as Input. Caused by Procedural Inadequacy | | | 05000250/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000251/LER-1981-010-03, /03L-0:on 810903,while Surveillance Testing, Auxiliary Feedwater Pump a Could Not Be Properly Tripped & Was Removed for Repair.Caused by Loose Set Screw & Misaligned Yoke.Yoke & Set Screw Repaired | /03L-0:on 810903,while Surveillance Testing, Auxiliary Feedwater Pump a Could Not Be Properly Tripped & Was Removed for Repair.Caused by Loose Set Screw & Misaligned Yoke.Yoke & Set Screw Repaired | | | 05000250/LER-1981-010-03, /03L-0:on 810501,component Cooling Water Pump 3A Did Not Start During Routine Equipment Rotation.Caused by Closing Latch Spring in Pump Circuit Breaker Detaching, Preventing Charging of Closing Springs.Breaker Repaired | /03L-0:on 810501,component Cooling Water Pump 3A Did Not Start During Routine Equipment Rotation.Caused by Closing Latch Spring in Pump Circuit Breaker Detaching, Preventing Charging of Closing Springs.Breaker Repaired | | | 05000251/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000250/LER-1981-011-03, /03L-0:on 810506,two Electrical Penetration Fire Barriers Found Nonfunctional During Implementation of Surveillance Per Tech Specs.Caused by Incomplete Installation.Personnel Readvised of Fireproofing Procedure | /03L-0:on 810506,two Electrical Penetration Fire Barriers Found Nonfunctional During Implementation of Surveillance Per Tech Specs.Caused by Incomplete Installation.Personnel Readvised of Fireproofing Procedure | | | 05000250/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000251/LER-1981-011-01, /01T-0:on 811021,high Head Safety Injection Line to Cold Legs Found to Be Obstructed During Full Flow Test on Discharge Check Valve of Pumps.Caused by Reduced Temp Due to Missing Insulation Near 4-inch Tee at Bit Inlet | /01T-0:on 811021,high Head Safety Injection Line to Cold Legs Found to Be Obstructed During Full Flow Test on Discharge Check Valve of Pumps.Caused by Reduced Temp Due to Missing Insulation Near 4-inch Tee at Bit Inlet | | | 05000251/LER-1981-011, Forwards LER 81-011/01T-0 | Forwards LER 81-011/01T-0 | | | 05000250/LER-1981-012, Forwards LER 81-012/09T-0 | Forwards LER 81-012/09T-0 | | | 05000250/LER-1981-012-09, /09T-0:on 811020,voltage Spike Discovered to Have Potential to Cause arc-over & Subsequent Open Circuit at Junction Between Coil Winding & Lead Wire.Caused by Design Deficiency.Affected Coils Replaced During Current Outage | /09T-0:on 811020,voltage Spike Discovered to Have Potential to Cause arc-over & Subsequent Open Circuit at Junction Between Coil Winding & Lead Wire.Caused by Design Deficiency.Affected Coils Replaced During Current Outage | | | 05000251/LER-1981-012-03, /03L-0:on 811124,during Safeguard Sys Testing,Bus Clearing Relays Did Not Pick Up 4A Bus.Emergency Diesel Generator Did Not Close in on 4A Bus.Caused by Malfunction of 4kv Breaker Auxiliary Switches Associated W/Bus Logic | /03L-0:on 811124,during Safeguard Sys Testing,Bus Clearing Relays Did Not Pick Up 4A Bus.Emergency Diesel Generator Did Not Close in on 4A Bus.Caused by Malfunction of 4kv Breaker Auxiliary Switches Associated W/Bus Logic | | | 05000251/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000250/LER-1981-013, Forwards Updated LER 81-013/02X-2 | Forwards Updated LER 81-013/02X-2 | | | 05000250/LER-1981-013-02, Small Void in Concrete Found Immediately Below Equipment Hatch Barrel.Cause Not Stated.Similar Void Confirmed on Unit 4.Voids Repaired | Small Void in Concrete Found Immediately Below Equipment Hatch Barrel.Cause Not Stated.Similar Void Confirmed on Unit 4.Voids Repaired | |
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