LER-1982-074, Forwards LER 82-074/03L-0.Detailed Event Analysis Encl |
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l DUKE POWER COMPANY 33189 7( 'l '" -. ~.' I A. I P.O. ISOX CHARLOTTE. N.C. 28249 ;i. ',
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HAL II. TUCKER TELEPHONE ver.n..r.a.en (704) 373-4531 g
g November 30, 1982 Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Re: McGuire Nucl, ear 4tation Unit 1 Docket No. 353M
Dear Mr. O'Reilly:
Please find attached Reportable Occurrence Report R0-369/82-74. This report concerns T.S. 3.6.1.3, "Each containment airlock 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, C
cc Hal B. Tucker PBN:jfw Attachment cc: Document Control Desk Records Center U. S. Nuclear Regulatory Commission Institute of Nuclear Power Operations Washington, D. C.
20555 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 Senior Resident Inspector-NRC McGuire Nuclear Station od
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DUKE POWER COMPANY McGUIRE NUCLEAR STATION REPORTABLE OCCURRENCE REPORT No. 82-74 REPORT DATE: November 30, 1982 FACILITY: McGuire Unit 1, Cornelius, NC i
IDENTIFICATION: Various Door Seals Failed on Both the Upper and Lower Personnel Airlocks (PAL)
DESCRIPTION
There were four door seal failures while Unit One was in Mode 1 it 50% power. All of these failures are reportable pursuant to Technical Specification 3.6.1.3, and are the result of Component Failure / Malfunction.
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_2 mediate corrective action for each of these incidents involved securing the operable door closed and initiating replacement of the failed seal.
On October 14, 1982, personnel performing the Air Lock Operability Test noticed that the seals' annulus pressure was increasing on the reactor building door of the upper PAL. This prompted the seal integrity portion of the Upper Personnel Airlock Leak Rate Test to be conducted on the reactor building door seals. The small seal was found to be leaking above the allowable limits as a result of a blister on the seal, and the upper PAL was declared inoperable. The failed door seal was replaced, the new seal passed its leak rate test and the PAL was declared operable on October 15.
While working in the area on October 19, 1982, Maintenance personnel noticed that the large seal on the auxiliary building door of the upper PAL appeared to be dragging. Further investigation revealed that a section of rubber was torn from the seal, revealing the fabric. The upper PAL was declared inoperable on October 20, 1982. The failed seal was replaced, the new seal passed its leak rate test and the PAL was declared operable on October 21.
l On October 25, 1982, when the reactor building door of the upper PAL was being closed, the door seals inflated before the door was completely closed, and the small seal failed.
The upper PAL was declared inoperable. The seal was replaced, l
the new seal passed its leak rate test, and the PAL declared operable on October l
28, 1982.-
On October 28, 1982, when Operations personnel discovered that the sealing rubber on the large seal on the auxiliary building door of the lower PAL was peeling off the surface of the seal, the lower PAL was declared inoperable. The seal was t
replaced, the new seal passed its leak rate test, and the PAL was declared oper-able the same day.
EVALUATION: There have been several seal failures on the PAL's at McGuire (ref.
LER's R0-369/81-176,81-190, 82-05, and 82-61). The most recent failures were determined to be the result of the seal inflation stem being overtightened into an oversized hole in the door frame and damaging the seal. However, the hole size has since been corrected, and all the damaged seals were replaced with new seals. This corrective action should habe prevented further seal failures of this kind.
As with past seals, the number of actual cycles for the new failures was only a fraction of the 50,000 guaranteed cycles; therefore the seals were not over cycled.
Report No. 82-74 Page 2 The seal which failed on 10/14/82 was manufactured by Sealmaster Corporation.
Air was discovered to be leaking into the area between_the seals on the door.-
No distinguishable leaks were_found on the seal, but a small blister was iden-tified. -Despite these failings, the seal was-capable of maintaining containment integrity as long as an air supply was available to keep the seal inflated. This failure is almost identical to the last seal failure occurrence which was_ reported in LER 369/82-61.
The seal which failed on 10/19/82 was also manufactured by Sea 1 master Corporation.
A piece of rubber was torn from the seal, exposing the seal cords.
It was thought that the door seal was the reason for the door dragging; but after a new' improved Pressray seal was installed on the door it still dragged. Further investigation revealed that the problem resulted from the door being out of alignment.
The seal which failed on 10/25/82 was manufactured by Presray Corporation and was in service for eleven days. The reactor building door was not closed when the seals inflated. The small seal which was manufactured by Presray ruptured, but the large seal which was manufactured by Sea 1 master did not feil. The Presray seals are not-designed to. withstand the forces ~of being inflated unrestrained.
There is no continuous fabric support within thePresray seal as there is in the Sealmaster. Therefore, when the seal inflates unrestrained, the Presray seal will distort, weaken, or fail. Failure due to damage is inevitable, but it is impossible to determine the time. In this case, failure was immediate.
There is no evidence that such unrestrained inflations damage the Sealmaster seals. There are limit switches on the. doors which are supposed to prevent inflating the seals with the doors open, but there have been problems with adjustment of these switches and the hydraulics on the doors. If the door closes too fast, the switch can be made and then the door will bounce open.
It could not be determined why these seals were inflated with the door open.
Other possibilities for the door seals inflating with the door open are someone l
doing it manually or power to the door being lost, but neither of these are suspected. An examination of the seal did not reveal a visible blow out, but a bubble was identified on the sealing surface.
The seal which failed on 10/28/82 was manufactured by Presray Corporation. The sealing rubber on the surface of the' seal was peeling off the seal, and the seal ruptured at one of these areas.
It is unknown why the sealing rubber was peeling or why the seal ruptured. This sealing rubber serves no structural function but is used because it provides a better sealing surface than the rubber used in the body of the seal. The ruptured area of the seal looked as though the seal was over-inflated until it failed. The seal was discovered in this condition with the door closed, so it is not possible to determine how or why the seal failed.
It is possible that the seal was inadvertently inflated with the door open at one time, and the seal was damaged.
It could have then ruptured later at this j
damaged area.
1 Both of the Presray seals which failed were due to blow outs, but only the failure on 10/25/82 was known to have occurred while the door was open. Seal-master seals were the companion seals on the doors with the failed Presray seals when they failed. Any damage to the Sealmaster seals due to inflation
Report No. 82 Page 3 with the doors open has not been evident. This is due to the construction of.
the seals.- Although the door seals are not supposed to be inflated with the doors'open, the occurrence has been frequent enough to warrant the need for door seals to be able to withstand such an' accident.
The two Sealmaster seals which failed ~were replaced with Presray seals. one of which failed after 11 days of service due to being inflated with the door open. One of the Sealmaster seals failed its surveillance test due to a blister which developed on the seal. The cause was unknown..The other Sealmaster was damaged due to an alignment problem with the door.
It is possible that such a problem could be contributing to all of the seal failures.-
SAFETY ANALYSIS
The loss of one of the airlock doors reduces the means of isolating the containment vessel from the atmosphere, but the ability to main-tain integrity was never lost because the redundant operable door was locked closed.
The health and safety of the public were not affected by these events.
CORRECTIVE ACTION
In all of the failures the immediate corrective action was to secure the operable airlock door of the respective air lock, and replace the failed seal. At present all of these failed seals have been replaced, inspected by Quality Assurance, passed their leak rate tests, and declared operable.
The door whose seal is dragging due to sagging hinges is having the seals lubri-cated until permanent adjustments can be made to the doors. Duke Power Company is in the process of setting up a meeting with the W. J. Wooley Co., the manufac-turer of the air locks, to discuss present problems concerning the air locks.
Included in the dialog between Duke, Wooley, and Presray is the possibility of expanding the design criteria of the Presray seals to withstand unrestrained inflations. By the end of January 1983 Duke will have met with the Wooley Co.
and will have plans for further corrective actions. In addition, Scalmaster seals will be used as replacements if possible for.any further failures, since they have given-(by far) better service than Presray seals.
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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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