LER-1982-008, Forwards LER 82-008/03L-0.Detailed Event Analysis Encl |
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February 12, 1982 2 f f' R 22 A S. Qc~Asta 704 v.c, Pnts.ormt itLtewo :
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$tgAu Paoovetion 373-4063 co Mr. J. P. O'Reilly, Regional Administrator o)
U. S. Nuclear Regulatory Commission p
Region II g
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l 101 Macietta Street, Suite 3100 VUD 9;y MAR 0579 Atlanta, Georgia 30303
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Re: McGuire Nucicar Station Unit 1 D
Docket No. 50-369 m
Dear Mr. O'Reilly:
i Please find attached Reportable Occurrence Report R0-369/82-08. This report concerns T.S.3.9.11, "The fuci handling ventilation exhaust system shall be operating and discharging through the llEPA filters and charcoal absorbers".
This incident was considered to be of no significance with respect to the health and safety of the public.
Ve[trulyyours,
~_ fj). e4 1111am O.. Parker, Jr.
P3N/jfw Attachment cc: Director Records Center Office of Management and Program Analysis Institute of Nuclear. Power Operations U. S. Nuc1 car Regulatory Commission 1820 Water Place Washington, D. C.
Atlanta, Georgia 30339 Mr. P. R. Bemis Senior Resident Inspector j
McGuire Nuclear Station 8203000403 820212 098Ula
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PDR ADOCK 05000369 pg(
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DUKE POWER COMPANY McGUIRE NUCLEAR STATION REPORTABLE OCCURRENCE REPORT NO. 82-08 REPORT DATE:
February 12, 1982 FACILITY: McGuire Unit 1, Cornelius, NC IDENTIFICATION: Failure to Take the Required Sample from the Fuel Pool Ventilation System Charcoal Absorber DISCUSSION: On January 15, 1982, while examining various programs on the operator aid computer, it was noticed that the equipment run time on the fuel pool ventilation system (VF) was 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> for the month and 2149.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> for the cumulative total.
(The total actual run time is the sum of the monthly total and cumulative total).
Since Technical Specification Surveillance Requirement 4.9.11.2(b) requires that a sample be taken from the charcoal absorber after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of operation and no samples had been taken, the VF system was declared inoperable. This incident is reportabic pursuant to Technical Specification 3.9.11.
Unto I was in mode 1 at the time the incident was discovered.
Since the VF system was out of specification and required sampling, a sample was taken and sent to Nuclear Containment Systems for analysis. On January 22, it was determined that the sample meet its acceptance criteria.
Therefore, the VF system was declared operable the same day.
EVALUATION: During the early part of 1981, the only safety-related system which was accumulating any run time was the control area llVAC system (VC).
(Note that the equipment run time consists of the time the system runs with flow through its filters and not in bypass).
In October when spent fuel was being received from Oconee, the VF system was started and ran continuously.
There was no need for the VF system to be operating continuously, but the person responsibic did not foresce any problems in doing so.
There was no procedure to cover the monitoring of the filter systems, and apparently the responsible staf f person had just checked the VC system because, to his knowledge, it was the only system accumulating time.
The charcoal absorber is used to remove radiciodine from the air in the fuel pool area during fuel movement and operation of the crane over the fuel pool with a load.
The analysis of the sampic verified that the charcoal absorber was functional during the receiving of the 16 sper.t fuel assemblics from Oconce, liowever, the unnecessary operation of the charcoal absorber reduced the operating life of the charcoal by one-half.
SAFETY ANALYSIS
The VF system serves no function to the plant in the event of a LOCA; therefore, safe operation of the plant was not af fected by this incident.
Since the analysis of the charcoal sample verified the charcoal functional, the charcoal absorber was capable and presently is capable of performing its designed function of removing radioiodine from the atmosphere in the fuel pool area. The health and safety of the public were not compr mised by this event.
CORRECTIVE ACTION
When it was discovered that the time for sampling had passed, the VF system was declared inoperable, and a charcoal sample taken. With the VF system inoperable, no fuel movement was allowed in the fuel pool; therefore the spent fuel cask which arrived on January 18 was put in storage until the VF system was made operable.
a Report No. 82-08 Page 2 A periodic test procedure, " Safety-Related Filter System Run Time Monitoring",
was written to ensure that all the necessary systems are monitored.
The VF system will be operated through the charcoal absorber only when necessary, and the procedure "B&W Spent Fuci Receipt, Storage and Shipping with an NLI Cask",
will be changed accordingly.
The person involved and all personnel in the plant will be reminded that they should be aware of changing conditions in the plant, and they need to respond to these conditions. Also, the section head of the person involved was advised to take the necessary corrective action to prevent recurrence.
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| 05000369/LER-1982-001, Forwards LER 82-001/01T-0.Detailed Event Analysis Encl | Forwards LER 82-001/01T-0.Detailed Event Analysis Encl | | | 05000369/LER-1982-001-01, /01T-0:on 820106,routine Review of Source Document Changes Revealed Class H Piping in Fire Protection Sys in Diesel Generator Room 1A Routed Above One Nuclear safety-related Essential Cable & Instrument Panel | /01T-0:on 820106,routine Review of Source Document Changes Revealed Class H Piping in Fire Protection Sys in Diesel Generator Room 1A Routed Above One Nuclear safety-related Essential Cable & Instrument Panel | | | 05000369/LER-1982-002-03, /03L-0:on 820101,temp Sensing Valve Position Indication Disagreed W/Alternate Position Indication & Declared Inoperable.Caused by Environ Conditions | /03L-0:on 820101,temp Sensing Valve Position Indication Disagreed W/Alternate Position Indication & Declared Inoperable.Caused by Environ Conditions | | | 05000369/LER-1982-002, Forwards LER 82-002/03L-0.Detailed Event Analysis Encl | Forwards LER 82-002/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1982-003, Forwards LER 82-003/03L-0.Detailed Event Analysis Encl | Forwards LER 82-003/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1982-003-03, /03L-0:on 820102,average Temp in Upper Containment Was Reduced Below Temp Requirement.Caused by Cold Weather Cooling Bldg.Temp Increased Using Dihydrogen Recombiner Heaters | /03L-0:on 820102,average Temp in Upper Containment Was Reduced Below Temp Requirement.Caused by Cold Weather Cooling Bldg.Temp Increased Using Dihydrogen Recombiner Heaters | | | 05000369/LER-1982-004-03, /03L-0:on 820103,power Operated Relief Valve NC-32 Found Leaking.Cause Unknown.Insp of Valve to Determine Exact Nature of Component Failure Not Yet Possible.Block Valve Closed & de-energized to Prevent Inadvertent Opening | /03L-0:on 820103,power Operated Relief Valve NC-32 Found Leaking.Cause Unknown.Insp of Valve to Determine Exact Nature of Component Failure Not Yet Possible.Block Valve Closed & de-energized to Prevent Inadvertent Opening | | | 05000369/LER-1982-004, Forwards LER 82-004/03L-0 | Forwards LER 82-004/03L-0 | | | 05000369/LER-1982-005-03, /03L-0:on 820105,during Mode 1 Power Escalation, Small Seal on Lower Personnel Air Lock Auxiliary Bldg Failed to Open.Caused by Design Oversight by Door Manufacturer.Seal Replaced & Successfully Passed Leak Rate Test | /03L-0:on 820105,during Mode 1 Power Escalation, Small Seal on Lower Personnel Air Lock Auxiliary Bldg Failed to Open.Caused by Design Oversight by Door Manufacturer.Seal Replaced & Successfully Passed Leak Rate Test | | | 05000369/LER-1982-005, Forwards LER 82-005/03L-0 | Forwards LER 82-005/03L-0 | | | 05000369/LER-1982-006-03, /03L-0:on 820106,flow Gauge on Remote Auxiliary Shutdown Control Panel Indicated No Flow When Corresponding Control Room Gauge Read 100 Gpm.Caused by Water Leaking Into Differential Pressure Transmitter Electronics Housing | /03L-0:on 820106,flow Gauge on Remote Auxiliary Shutdown Control Panel Indicated No Flow When Corresponding Control Room Gauge Read 100 Gpm.Caused by Water Leaking Into Differential Pressure Transmitter Electronics Housing | | | 05000369/LER-1982-006, Forwards LER 82-006/03L-0 | Forwards LER 82-006/03L-0 | | | 05000369/LER-1982-007, Forwards LER 82-007/03L-0.Detailed Event Analysis Encl | Forwards LER 82-007/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1982-007-03, /03L-0:on 820111,many Instrument Lines Froze W/ Instruments Declared Inoperable Leading to Inadvertent Actuation of ESF Causing Safety Injection,Steamline Isolation & Reactor Trips.Caused by Cold Weather | /03L-0:on 820111,many Instrument Lines Froze W/ Instruments Declared Inoperable Leading to Inadvertent Actuation of ESF Causing Safety Injection,Steamline Isolation & Reactor Trips.Caused by Cold Weather | | | 05000369/LER-1982-008, Forwards LER 82-008/03L-0.Detailed Event Analysis Encl | Forwards LER 82-008/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1982-008-03, /03L-0:on 820115,exam of Programs on Operator Computer Revealed Equipment Run Time on Fuel Pool Ventilation Sys Exceeded Tech Specs W/O Sample Being Taken from Charcoal Absorber.Caused by Lack of Procedure | /03L-0:on 820115,exam of Programs on Operator Computer Revealed Equipment Run Time on Fuel Pool Ventilation Sys Exceeded Tech Specs W/O Sample Being Taken from Charcoal Absorber.Caused by Lack of Procedure | | | 05000369/LER-1982-009, Forwards LER 82-009/03L-0 | Forwards LER 82-009/03L-0 | | | 05000369/LER-1982-009-03, /03L-0:on 820116,during Review of Surveillance Documentation,Periodic Testing of Diesel Generator Battery Trains Edga & Edgb Not Performed within Test Frequency Required by Tech Specs.Caused by Personnel Error | /03L-0:on 820116,during Review of Surveillance Documentation,Periodic Testing of Diesel Generator Battery Trains Edga & Edgb Not Performed within Test Frequency Required by Tech Specs.Caused by Personnel Error | | | 05000369/LER-1982-010, Forwards LER 82-010/03L-0.Detailed Event Analysis Encl | Forwards LER 82-010/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1982-010-03, /03L-0:on 820120,while in Mode 1,all Digital Rod Position Indications for Control Rod K-8 Lost.Caused by Cabling to Detectors Susceptible to Conductor Damage Due to Own Weight.Bulkhead Connector Cable Replaced | /03L-0:on 820120,while in Mode 1,all Digital Rod Position Indications for Control Rod K-8 Lost.Caused by Cabling to Detectors Susceptible to Conductor Damage Due to Own Weight.Bulkhead Connector Cable Replaced | | | 05000369/LER-1982-011-03, /03L-0:on 820120,maint Personnel Working on Spent Fuel Pool Cooling Sys (Kf) Heat Exchanger 1A Discharge Throttle Bypass Relief Valve Discovered That Kf Mechanical Snubber Was Removed Rendering Snubber Inoperable | /03L-0:on 820120,maint Personnel Working on Spent Fuel Pool Cooling Sys (Kf) Heat Exchanger 1A Discharge Throttle Bypass Relief Valve Discovered That Kf Mechanical Snubber Was Removed Rendering Snubber Inoperable | | | 05000369/LER-1982-011, Forwards LER 82-011/03L-0 | Forwards LER 82-011/03L-0 | | | 05000369/LER-1982-012-03, /03L-0:on 820119,routine QA Audit of Fire Protection Sys Test Found Three Valves Marked Not Accessible & Had Not Been Checked.Caused by Personnel Error.Periodic Test Performed & Valves Found in Correct Position | /03L-0:on 820119,routine QA Audit of Fire Protection Sys Test Found Three Valves Marked Not Accessible & Had Not Been Checked.Caused by Personnel Error.Periodic Test Performed & Valves Found in Correct Position | | | 05000369/LER-1982-012, Forwards LER 82-012/03L-0.Detailed Event Analysis Encl | Forwards LER 82-012/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1982-013, Forwards LER 82-013/03L-0.Detailed Event Analysis Encl | Forwards LER 82-013/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1982-013-03, /03L-0:on 820126,two Upper Head Injection Train a Accumulator Tank Level Switches Miscalibr,Rendering Isolation Valves Inoperable.Caused by Faulty Data Programmed Into Computer Memory.Program Corrected | /03L-0:on 820126,two Upper Head Injection Train a Accumulator Tank Level Switches Miscalibr,Rendering Isolation Valves Inoperable.Caused by Faulty Data Programmed Into Computer Memory.Program Corrected | | | 05000369/LER-1982-014-03, /03L-0:on 820128,process Monitoring Sys Containment Gas Monitor EMF-39(L) Declared Inoperable Due to Scale Low Indication & Loss of Indication.Caused by Failure of Quality Bnn Connector.Sys Repaired | /03L-0:on 820128,process Monitoring Sys Containment Gas Monitor EMF-39(L) Declared Inoperable Due to Scale Low Indication & Loss of Indication.Caused by Failure of Quality Bnn Connector.Sys Repaired | | | 05000369/LER-1982-014, Forwards LER 82-014/03L-0 | Forwards LER 82-014/03L-0 | | | 05000369/LER-1982-015, Forwards LER 82-015/01T-0.Detailed Event Analysis Encl | Forwards LER 82-015/01T-0.Detailed Event Analysis Encl | | | 05000369/LER-1982-015-01, /01T-0:on 820212,both Centrifugal Charging Pumps (CCP) Declared Inoperable When Hydrogen from Reciprocating Charging Pump Suction Dampeners Entered CCP Suction,Causing Cavitation | /01T-0:on 820212,both Centrifugal Charging Pumps (CCP) Declared Inoperable When Hydrogen from Reciprocating Charging Pump Suction Dampeners Entered CCP Suction,Causing Cavitation | | | 05000369/LER-1982-016-03, /03L-0:on 820211,discovered Pivot Pin Missing from safety-related Hanger Located in Centrifugal Charging Pump 1B Room Supporting Pump 4-inch Discharge Line Rendering Hanger Inoperable.Cause Undetermined.New Pin Installed | /03L-0:on 820211,discovered Pivot Pin Missing from safety-related Hanger Located in Centrifugal Charging Pump 1B Room Supporting Pump 4-inch Discharge Line Rendering Hanger Inoperable.Cause Undetermined.New Pin Installed | | | 05000369/LER-1982-016, Forwards LER 82-016/03L-0 | Forwards LER 82-016/03L-0 | | | 05000369/LER-1982-017-03, /03L-0:on 820212,control Room Alarms Indicated Closing of 4 Accumulator Discharge Isolation Valves, Rendering Upper Head Injection Portion of ECCS Inoperable. Cause Probably Due to Installation Deficiency | /03L-0:on 820212,control Room Alarms Indicated Closing of 4 Accumulator Discharge Isolation Valves, Rendering Upper Head Injection Portion of ECCS Inoperable. Cause Probably Due to Installation Deficiency | | | 05000369/LER-1982-017, Forwards LER 82-017/03L-0.Detailed Event Analysis Encl | Forwards LER 82-017/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1982-018-03, /03L-0:on 820218,control Room Annunciators Indicated Reactor Coolant Loop B Overtemp & Overpower Delta T Alarms.Caused by Faulty Lead/Lag Amplifier Card in Loop B Delta T Section of 7300 Control Sys Cabinets | /03L-0:on 820218,control Room Annunciators Indicated Reactor Coolant Loop B Overtemp & Overpower Delta T Alarms.Caused by Faulty Lead/Lag Amplifier Card in Loop B Delta T Section of 7300 Control Sys Cabinets | | | 05000369/LER-1982-018, Forwards LER 82-018/03L-0 | Forwards LER 82-018/03L-0 | | | 05000369/LER-1982-019-03, /03L-0:on 820228,during Mode 4,performance of RCS Pressure Isolation Valve Leak Rate Test Determined That 3 Valves Failed Test.Caused by Failure of Valves to Seat Properly.Valves Disassembled & Repaired | /03L-0:on 820228,during Mode 4,performance of RCS Pressure Isolation Valve Leak Rate Test Determined That 3 Valves Failed Test.Caused by Failure of Valves to Seat Properly.Valves Disassembled & Repaired | | | 05000369/LER-1982-020-03, /03L-0:on 820304,during Mode 5,operator-trainee Attempted to Address Status of Fire Zone Through Honeywell Fire Detection Sys Operator Terminal & Mistakenly Dumped Central Processing Unit Memory.Caused by Personnel Error | /03L-0:on 820304,during Mode 5,operator-trainee Attempted to Address Status of Fire Zone Through Honeywell Fire Detection Sys Operator Terminal & Mistakenly Dumped Central Processing Unit Memory.Caused by Personnel Error | | | 05000369/LER-1982-020, Forwards LER 82-020/03L-0 | Forwards LER 82-020/03L-0 | | | 05000369/LER-1982-021-03, /03L-0:on 820309,discovered Cold Leg Injection Accumulator Isolation Valves Not Periodically Tested for Correct Response to P-11 Interlock Signal.Caused by Procedural Deficiency.Tests Performed on 820312 | /03L-0:on 820309,discovered Cold Leg Injection Accumulator Isolation Valves Not Periodically Tested for Correct Response to P-11 Interlock Signal.Caused by Procedural Deficiency.Tests Performed on 820312 | | | 05000369/LER-1982-021, Forwards LER 82-021/03L-0 | Forwards LER 82-021/03L-0 | | | 05000369/LER-1982-022-03, /03L-0:on 820310,while in Mode 5,procedure Review Revealed Pressurizer 1 Power Operated Relief Valve (PORV) Had Not Been Timed.Procedure Change on 800915 Failed to Include PORV for Time Test.Procedure Changed | /03L-0:on 820310,while in Mode 5,procedure Review Revealed Pressurizer 1 Power Operated Relief Valve (PORV) Had Not Been Timed.Procedure Change on 800915 Failed to Include PORV for Time Test.Procedure Changed | | | 05000369/LER-1982-022, Forwards LER 82-022/03L-0 | Forwards LER 82-022/03L-0 | | | 05000369/LER-1982-023, Forwards LER 82-023/03L-0.Detailed Event Analysis Encl | Forwards LER 82-023/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1982-023-03, /03L-0:on 820312,after Filling & Venting of RCS, Sample Indicated Boron Concentration at 1,025 Ppm.Caused by Procedural Deficiency Due to Operating Boric Acid Blender W/O Concentration Verification During Addition to RCS | /03L-0:on 820312,after Filling & Venting of RCS, Sample Indicated Boron Concentration at 1,025 Ppm.Caused by Procedural Deficiency Due to Operating Boric Acid Blender W/O Concentration Verification During Addition to RCS | | | 05000369/LER-1982-024, Forwards LER 82-024/03L-0.Detailed Event Analysis Encl | Forwards LER 82-024/03L-0.Detailed Event Analysis Encl | | | 05000369/LER-1982-024-03, /03L-0:on 820302,while Draining RCS for Insp,Rhr Pump Low Discharge Pressure Alarm Sounded.Caused by Inaccurate Indication of RCS Water Level Due to Misapplication of Control Board Level Gauge Transmitter | /03L-0:on 820302,while Draining RCS for Insp,Rhr Pump Low Discharge Pressure Alarm Sounded.Caused by Inaccurate Indication of RCS Water Level Due to Misapplication of Control Board Level Gauge Transmitter | | | 05000369/LER-1982-025, Forwards LER 82-025/03L-0 | Forwards LER 82-025/03L-0 | | | 05000369/LER-1982-025-03, /03L-0:on 820318,vol Control Tank Makeup Frequency Increased & Containment Floor & Equipment Sump 1A Level Increased During RCS Leak Test.Caused by Failure to Verify Isolation Valves Closed Due to Procedural Deficiency | /03L-0:on 820318,vol Control Tank Makeup Frequency Increased & Containment Floor & Equipment Sump 1A Level Increased During RCS Leak Test.Caused by Failure to Verify Isolation Valves Closed Due to Procedural Deficiency | | | 05000369/LER-1982-026, Forwards LER 82-026/03L-0 | Forwards LER 82-026/03L-0 | |
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