LER-1982-061, Forwards LER 82-061/03L-0.Detailed Event Analysis Encl |
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e Duxu Powna COMPANY STEAM PitODUCTION del'r.
GENEltAL OFFICES vgtspuous: AsirA vo4 P. o. mox sales 422 SOUTH CHURCH STREET 373-4o s CIIAHLOTTE, N. C. 28242 August 27, 1982 Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region 11 101 Marietta Street, Suite 3100 Atlanta,-Georgia 30303 Re: McGuire Nuclear Station Unit 1 Docket No. 50-369
Dear Mr. O'Reilly:
Please find attached Reportable Occurrence Report R0-369/82-61. This report concerns T.S.3.6.1.3, "Each containment air lock shall be operable...".
This incident was considered to be of no significance with respect to the health and safety of the public.
Very truly yours,
/d
+(4 jQ Ital.B. Tucker, Vice President Nuclear Production PBN/jfw Attachment cc: Director Records Center Office of Management and Program Analysis Institute of Nuclear Power Operations U. S. Nuclear Regulatory Commission 1820 Water Place Washington, D. C.
20555 Atlanta, Georgia 30339 Mr. P. R. Bemis i
Senior Resident Inspector-NRC l
McGuire Nuclear Station l
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OFFICTAL COPY PDR ADOCK 05000369
'/6 bL 7-8209160102 820827 S
PDR
e DUKE POWER COMPANY McGUIRE NUCLEAR STATION REPORTABLE OCCURRENCE REPORT NO. 82-61 REPORT DATE: August 27, 1982 FACILITY: McGuire Unit 1, Cornelius, NC IDENTIFICATION: Failure of the Small Seal on the Lower Personnel Airlock (PAL)
Reactor Building Door and Failure of the Large Seal of the Lower PAL Auxiliary Building Door
DESCRIPTION
When two operators attempted to exit lower containment through the lower PAL, the door on the reactor building side of the airlock would not close.
The hydraulics which move the door failed due to a disconnected section of tubing.
During the tubing repair blisters, which prevented the door from closing properly, were discovered on the door seals. A work request was generated to replace the seals.
The lower PAL was declared inoperable on July 28, 1982 pursuant to Technical Specification 3.6.1.3.
At the time of the occurrence, Unit One was in Mode 3, Hot Standby.
A hydraulic fitting on the PAL door opening mechanism and the small seal on the reactor building door were found to be failed. Therefore, this incident is due to Component Failure / Malfunction.
As a result of the testing required for the newly replaced seal, the surveillance test for all the seals on the lower PAL was performed. During this surveillance test, the large seal on the auxiliary building door of the lower PAL failed its integrity test.
The airlock was again declared inoperable on July 29 pursuant to Technical Specification 3.6.1.3.
At this time, Unit One was in Mode 1 at 50% power.
This incident is also due to Component Failure / Malfunction, because the seal leakage exceeded its maximum allowable limit.
EVALUATION: There have been numerous seal failures on the PAL's at McGuire (see Reportable Occurrence Reports 369/81-176,81-190, and 82-05).
It was determined that the most recent failures were due to the seal inflation stem being overtightened into an oversized hole in the door frame and damaging the seal. This caused blisters to form on the seal as the result of ply separation within the seal. When this determination was made, a procedure change was made to the installation procedure to only hand-tightea the stem nut until a modification to the stem hole could be made.
During the March outage, the modification was made, and all the seals which were not installed per the changed procedure were replaced with new seals.
One of the seals which was not replaced during the outage was the small seal on the reactor building side of the lower PAL. This seal was replaced per the changed pro-cedure after a seal failed on the door on December 3, 1981 (see R0-369/81-190). This same seal failed on July 28, 1982 due to blisters which were the cause of previous failures. A visual inspection indicated that this seal also had its stem overtightened.
l However, the stem should not have been overtightened since it was installed per the changed procedure then reinstalled after the modification was made.
Inspection also indicates taht the wrong tool was used on the stem to hold it in place when the air l
supply was connected to the stem.
It is suspected that the stem may have inadvertently l
been overtightened during the installation of the air supply.
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Report No. 82-61 Page 2 The seal which failed was a Sealmaster Corporation Specification Number 10776 2 30 81 S/N 105 JY.
The manufacturer of the airlocks, W. J. Wooley Company, prefers improved Pressrey seals; therefore, the Sealmaster seals are going to be replaced with Pressrey seals.
In this incident, as in R0-369/81-190, the seal failure was discovered as the result of another problem on the door. However, it is believed that the seal failures con-tributed to the other problems in each case. The hydraulic tubing came loose from an Imperial Eastman high seal 1/2 inch fitting.
The large seal on the auxiliary building door of the PAL failed its leakage test, and it was one of the new seals installed after the modification.
It was allowing air to leak to the area between the two seals on the door. This seal had no deformities, and the source of the leak could not be found. The seal was replaced with a new Pressrey seal and successfully retested. This failed seal was leak tested-when it was initially installed; therefore, it developed its leak during its service.
The door seals are leak tested periodically, every 6 m nths, after the initial test i
l to discover such failures. The seals function to maintain containment integrity and leak rate. The leaking seal was technically operable under normal conditions because a constant air supply was available to keep the seal inflated. Even if instrument air was lost, the seal would have remained inflated for a time because each seal has a reserve air storage tank which will provide several cycles of the doors.
SAFETY ANALYSIS
The loss of one of the airlock doors reduces the means of isolating the containment vessel from atmosphere, but the ability to maintain integrity was never lost because the redundant operable door was locked closed. Although the auxiliary building door seal on the lower PAL failed its leak rate test, the overall airlock leak rate test was successfully completed the day before. A constant air supply was available to keep the seal inflated and perform its function.
The health and safety of the public were not affected by these events.
CORRECTIVE ACTION
The hydraulic tubing which came loose was reinstalled with a new fitting, and hydraulic fluid was added to replace the lost fluid. Both of the defec-tive seals were replaced with new Pressrey seals.
They were then retested per pro-cedure, " Lower Containment Airlock Leak Rate Test", and the airlocks tested per the
" Airlock Operability Test".- While one door was inoperable the other door was' locked closed in compliance with the Technical Specification action statements.
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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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