LER-1982-044, Forwards LER 82-044/01T-0.Detailed Event Analysis Encl |
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f SOUTH CAROLINA ELECTRIC & GAC, COMPANY,,,
post oprics Poe
' 'f.
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COLuusiA south CAROLINA 292t8 O
December 16,,er n 72 M0 : 5
- 0. W. DixoN, JR.
vice Passeen?
1982 Nucuan OpenAMNs i
Mr. James P. O'Reilly, Director U.S. Nuclear Regulatory Commission Region II, Suite 3100 101 Marietta Street, N.W.
Atlanta, Georgia 30303
SUBJECT:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Fourteen Day Written Report LER 82-044
Dear Mr. O'Reilly:
Please find attached Licensee Event Report #82-044 for Virgil This Fourteen Day Report is required C. Summer Nuclear Station.
by Technical Specification 6.9 1.12.(F) as a result of inconsistencies indentified in the performance of Inservice Inspection Pump Program testing performed on the Residual Heat Removal Pumps (Technical Specification 3 5 2).
Should there be any questions, please call us at your convenience.
Very truly yours, (b
?
- - t
~
- 0. W Dix
, Jr.
ARK:OWD:dwr Attachment A. R. Koon cc:
V.
C.
Summer G. D. Mof fatt T. C. Nichols, Jr.
Site QA G. H. Fischer C. L. Ligon (NSRC)
O. W. Dixon, Jr.
G. J. Braddick H. N. Cyrus J. L. Skolds H. T. Babb J. B. Knotts, Jr.
D.
A. Nauman B.
A.
Bursey M. B. Whitaker, Jr.
I&E (Washington)
W. A. Williams, J r.
Document Management Branch O.
S. Bradham INPO Records Center R. B.
Clary NPCF M. N. Browne File
'<ia 2.[,; y 8212220498 821216
( /,Z)
DR ADOCK OSOOO34
Mr. James P. O'Reilly LER No.82-044 Page Two December 16, 1982 DETAILED DESCRIPTION OF EVENT On December 2,1982, with the Plant operating in Mode 1, the NRC Resident Inspector informed the Licensee that a surveillance test performed on October 5,1982, for Residual Heat Removal (RHR)
Pump A was approved as being satisfactory when the acceptance criteria was not fully met.
Technical Specification 4.5.2.F.2 requires that a 128 psid be obtained for the RHR pumps on recirculation flow.
The test results on October 5,1982, indicated 127 paid.
This test was performed again on November 5, 1982, with satisfactory results.
During the time period from October 5, 1982, to November 5,1982, the Plant was in Modes 1, 2, and 3 f or approximately 23 days.
Technical Specification 3.5.2, "ECCS Subsystems - Tavg >. 350 F,"
requires that two (2)
RHR pumps be OPERABLE for Modes 1, 2, and 3 PROBABLE CONSEQUENOES There were no adverse consequences.
As a result of the actions taken as described below, there is no indication of abnormal pump performance.
Instead, personnel errors were found to exist in the methods of performing the tests, collecting and analyzing the data.
CAUSE(S) OF THE OCCURRENCE In general, the cause of the occurrence is attributed to personnel error due to lack of experience in the methods that the tests were being performed and the methods that data were being gathered and analyzed.
Specifically, the following items have been identified as contributing causes:
1.
A review of previous RHR pump tests indicated apparent inconsistencies existed in the methods that data were being gathered.
Also, in some cases, the test data were not properly analyzed for acceptability.
2.
Personnel involved in performing pump tests were not properly instructed on proper techniques for taking the required data.
This lack of technical supervision contributed to inconsistent da ta.
Mr. James P. O'Reilly LER No.82-044 Page Three December 16, 1982 3
Due to plant mode restrictions, two methods of testing the RRR pumps were developed.
The procedure was not clear on which method of testing was actually required in Modes 4, 5, and 6.
This resulted in confusion when selecting the correct baseline data for acceptance.
Additionally, the data sheet acceptance criteria for minimum pump differential pressure did not address the Technical Specification limit.
This contributed directly to the personnel error whieb hus been identified.
4.
It has been recognized that the insta.' ed instrumentation calibration schedule was on an 18 mcr.
cycle.
This potentially contributed to the data ! 'ansistencies found in the review.
5 Both trains of RHR were later foula i require venting.
Even though this condition would not adversely affected the operation of the syster 3.n 1e accident mode of operation, it could have affected the ec. curacy of the data gathered.
IMMEDIATE CORRECTIVE ACTIONS TAKEN The following immediate corrective actions were initiat?d bg the Licensee:
1.
To verify OPERABILITY, the RHR pumps were immedi:.tely retested.
These tests were conducted utilizing experienced staff engineering personnel familiar with Inservice Inspection program requirements in order to ensure proper test methods were utilized.
This testing was completed on December 3, 1982, with both pumps found to be acceptable.
r 1
2.
For both RHR pumps, previous test data were reviewed and found to be acceptable.
l
Mr. James P. O'Reilly LER No.82-044 Page Four December 16, 1982 ACTION TAKEN TO PREVENT RECURRENCE The following actions are being taken to prevent recurrence:
1.
In order to ensure that operations and staff technical personnel involved with performing tests as required by the Inservice Inspection Pump Program are knowledgeable of the requirements of the program and understand its importance, a presentation will be prepared and presented to these personnel.
This tra.'.ning will be complete by March 31, 1983.
2.
Until the action identified in item (1) above is accomplished, experienced staff engineering personnel will assist in the performance of the tests.
3 A review of the adequacy of installed instrumentation is in progress.
In cases where it is determined that installed instruments are not adequate for test purposes, calibrated test instrumentation will be used in their place.
In cases where it is determined that installed instruments are adequate for test purposes, the performance of these instruments wil.'. be trended.
The calibration frequency of installed instrumentation used for testing is being increased to six month intervals.
This frequency will be adjusted if trend performance of instruments indicate the need.
This will be accomplished by December 31, 1982.
5.
The RHR pump test procedure is being revised to remove confusion on correct system alignment for mode of operation and proper collection of requiced data.
The associated data sheets are also being revised to include all limits established by the Inservice Inspection Program and Technical Specification acceptance criteria.
This action will be accomplished by December 31, 1982.
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| 05000395/LER-1982-001, Forwards LER 82-001/03L-0 | Forwards LER 82-001/03L-0 | | | 05000395/LER-1982-001-03, /03L-0:on 820813,while Performing Test on Feeder Breaker for Control Room Train B Normal Ventilation Fan, Breaker Would Not Manually Reset.Caused by Random Failure of Square D Breaker (Fhl 36050-15M).Breaker Replaced | /03L-0:on 820813,while Performing Test on Feeder Breaker for Control Room Train B Normal Ventilation Fan, Breaker Would Not Manually Reset.Caused by Random Failure of Square D Breaker (Fhl 36050-15M).Breaker Replaced | | | 05000395/LER-1982-002, Forwards LER 82-002/03L-0 | Forwards LER 82-002/03L-0 | | | 05000395/LER-1982-002-03, /03L-0:on 820818,after Calibr Pressure Transmitter for RHR Train a Suction Isolation Valve,Valve Operator re-energized & Suction Isolation Valve Shut.Caused by Switch Being Left in Test Position.Personnel Reinstructed | /03L-0:on 820818,after Calibr Pressure Transmitter for RHR Train a Suction Isolation Valve,Valve Operator re-energized & Suction Isolation Valve Shut.Caused by Switch Being Left in Test Position.Personnel Reinstructed | | | 05000395/LER-1982-003, Forwards LER 82-003/03L-0 | Forwards LER 82-003/03L-0 | | | 05000395/LER-1982-003-03, /03L-0:on 820820,isolation Valve in Fire Svc Sys Found Closed,Rendering Fire Suppression Sys Inoperable for Control Bldg Cable Spreading Rooms & Chases.Caused by Header Valve Being Tagged Prior to Entering Mode 6 | /03L-0:on 820820,isolation Valve in Fire Svc Sys Found Closed,Rendering Fire Suppression Sys Inoperable for Control Bldg Cable Spreading Rooms & Chases.Caused by Header Valve Being Tagged Prior to Entering Mode 6 | | | 05000395/LER-1982-004-03, /03L-0:on 820915,test Signal Generated Causing B Train RHR Header Isolation Valve to Shut & Isolate Suction. Pump Manually Tripped.Surveillance Test Procedure Revised to Line Up Alternate RHR Train W/Valve Locked Out | /03L-0:on 820915,test Signal Generated Causing B Train RHR Header Isolation Valve to Shut & Isolate Suction. Pump Manually Tripped.Surveillance Test Procedure Revised to Line Up Alternate RHR Train W/Valve Locked Out | | | 05000395/LER-1982-004, Forwards LER 82-004/03L-0.Detailed Event Analysis Encl | Forwards LER 82-004/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-005, Forwards LER 82-005/03L-0.Detailed Event Analysis Encl | Forwards LER 82-005/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-005-03, /03L-0:on 820916,five Smoke Detectors at 400-ft & 412-ft Elevations of Control Bldg Disabled,Rendering Preaction Sprinkler Sys Automatic Actuation Capability Inoperable.Caused by Need to Perform Welding in 400-ft Area | /03L-0:on 820916,five Smoke Detectors at 400-ft & 412-ft Elevations of Control Bldg Disabled,Rendering Preaction Sprinkler Sys Automatic Actuation Capability Inoperable.Caused by Need to Perform Welding in 400-ft Area | | | 05000395/LER-1982-006, Forwards LER 82-006/03L-0.Detailed Event Analysis Encl | Forwards LER 82-006/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-006-03, /03L-0:on 820922,several High Range Monitors Failed High.Caused by Moisture Accumulation in Detector Preamp Connections.Plant Completed Initial Fuel Load But Was Not Critical.Monitors Replaced Except RM-G19B | /03L-0:on 820922,several High Range Monitors Failed High.Caused by Moisture Accumulation in Detector Preamp Connections.Plant Completed Initial Fuel Load But Was Not Critical.Monitors Replaced Except RM-G19B | | | 05000395/LER-1982-007, Forwards LER 82-007/03L-0.Detailed Event Analysis Encl | Forwards LER 82-007/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-007-03, /03L-0:on 820925,diesel Generator Bldg Preaction Sprinkler Sys Heat Detectors Failed to Actuate Sprinkler Valve.Caused by Degraded Circuit Card in Sprinkler Sys Control Cabinet.Card Replaced | /03L-0:on 820925,diesel Generator Bldg Preaction Sprinkler Sys Heat Detectors Failed to Actuate Sprinkler Valve.Caused by Degraded Circuit Card in Sprinkler Sys Control Cabinet.Card Replaced | | | 05000395/LER-1982-008, Forwards LER 82-008/03L-0.Detailed Event Analysis Encl | Forwards LER 82-008/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-008-03, /03L-0:on 820929,svc Water Pond Level Indication Not Verified for Modes 1,2,3 & 4 from 820922-29.Caused by Pond Level Entry Omitted from Operator Logs Due to Personnel Error.Logs Reviewed & Revised | /03L-0:on 820929,svc Water Pond Level Indication Not Verified for Modes 1,2,3 & 4 from 820922-29.Caused by Pond Level Entry Omitted from Operator Logs Due to Personnel Error.Logs Reviewed & Revised | | | 05000395/LER-1982-009, Forwards LER 82-009/03L-0.Detailed Event Analysis Encl | Forwards LER 82-009/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-009-03, /03L-0:on 820929,Surveillance Test Procedure 128.007 Performed Instead of 128.017 Which Implements Tech Spec to Verify Position of Locked Closed Fire Doors.Caused by Personnel/Numerical Error.Personnel Counseled | /03L-0:on 820929,Surveillance Test Procedure 128.007 Performed Instead of 128.017 Which Implements Tech Spec to Verify Position of Locked Closed Fire Doors.Caused by Personnel/Numerical Error.Personnel Counseled | | | 05000395/LER-1982-010-03, /03L-0:on 821001,PORV Block Valve MVG-8000A Would Not Reopen at Conclusion of Reactor Vessel O-ring Leak Test. Caused by Wear in Valve Stem Packing Which Contributed to Overtorque Condition.Stem Packing Replaced | /03L-0:on 821001,PORV Block Valve MVG-8000A Would Not Reopen at Conclusion of Reactor Vessel O-ring Leak Test. Caused by Wear in Valve Stem Packing Which Contributed to Overtorque Condition.Stem Packing Replaced | | | 05000395/LER-1982-010, Forwards LER 82-010/03L-0.Detailed Event Analysis Encl | Forwards LER 82-010/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-011-03, /03L-0:on 820930,Mode 3 Entered W/Pressurizer Relief Tank Level Indication LI-470A Inoperable at Control Room Evacuation Panel.Caused by Transmitter Not Calibr Properly,Due to Defective Amplifier & Calibr Circuit Card | /03L-0:on 820930,Mode 3 Entered W/Pressurizer Relief Tank Level Indication LI-470A Inoperable at Control Room Evacuation Panel.Caused by Transmitter Not Calibr Properly,Due to Defective Amplifier & Calibr Circuit Card | | | 05000395/LER-1982-011, Forwards LER 82-011/03L-0.Detailed Event Analysis Encl | Forwards LER 82-011/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-012, Forwards LER 82-012/03L-0.Detailed Event Analysis Encl | Forwards LER 82-012/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-012-03, /03L-0:on 820928,reactor Bldg high-range Radiation Monitor RM-G7 Had Problems W/Spiking That Caused High Radiation Alarms.Spikes Caused by Electrical Interference in Detection Cable.Monitor Tested & Returned to Svc | /03L-0:on 820928,reactor Bldg high-range Radiation Monitor RM-G7 Had Problems W/Spiking That Caused High Radiation Alarms.Spikes Caused by Electrical Interference in Detection Cable.Monitor Tested & Returned to Svc | | | 05000395/LER-1982-013, Forwards LER 82-013/03L-0.Detailed Event Analysis Encl | Forwards LER 82-013/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-013-03, /03L-0:on 821001,differential Pressure Level Transmitter Accumulator Tank a Level Found Below Tech Specs by Approx 7% Following Recalibr.Caused by Transmitter Showing Incorrect Level Indication.Transmitter Recalibr | /03L-0:on 821001,differential Pressure Level Transmitter Accumulator Tank a Level Found Below Tech Specs by Approx 7% Following Recalibr.Caused by Transmitter Showing Incorrect Level Indication.Transmitter Recalibr | | | 05000395/LER-1982-014-03, /03L-0:on 821002,air Pressure Equalizing Valves Would Not Cycle in Proper Sequence,Rendering Reactor Bldg Airlock Inoperable.Caused by Chain Drive Sprocket Shearing Key,Allowing Sprocket to Slip Into Associated Drive Shaft | /03L-0:on 821002,air Pressure Equalizing Valves Would Not Cycle in Proper Sequence,Rendering Reactor Bldg Airlock Inoperable.Caused by Chain Drive Sprocket Shearing Key,Allowing Sprocket to Slip Into Associated Drive Shaft | | | 05000395/LER-1982-014, Forwards LER 82-014/03L-0.Detailed Event Analysis Encl | Forwards LER 82-014/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-015, Forwards LER 82-015/03L-0.Detailed Event Analysis Encl | Forwards LER 82-015/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-015-03, /03L-0:on 821003,sample Pumps on Reactor Bldg Air Sample Radiation Monitor RMA-2 Tripped Due to Overheating in Cabinet.Caused by Inadequate Cabinet Ventilation.Pumps Cooled & Restarted After Approx 4-h | /03L-0:on 821003,sample Pumps on Reactor Bldg Air Sample Radiation Monitor RMA-2 Tripped Due to Overheating in Cabinet.Caused by Inadequate Cabinet Ventilation.Pumps Cooled & Restarted After Approx 4-h | | | 05000395/LER-1982-016, Forwards Revised LER 82-016/03L-1.Detailed Event Analysis Encl | Forwards Revised LER 82-016/03L-1.Detailed Event Analysis Encl | | | 05000395/LER-1982-016-03, Main Control Board Indicator for Reactor Bldg Pressure (PI-950) Failed Low. Cause Still Under Investigation.Surveillance Test Procedure 303.001 Performed Satisfactorily.Channel Returned to Svc | Main Control Board Indicator for Reactor Bldg Pressure (PI-950) Failed Low. Cause Still Under Investigation.Surveillance Test Procedure 303.001 Performed Satisfactorily.Channel Returned to Svc | | | 05000395/LER-1982-017, Forwards LER 82-017/03L-0.Detailed Event Analysis Encl | Forwards LER 82-017/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-017-03, /03L-0:on 821006,controlled Leakage Exceeded Tech Specs During Surveillance Test Procedure.Caused by Improperly Set Needle Valves Located in Reactor Coolant Pump Seal Injection Line.Valves Positioned Correctly | /03L-0:on 821006,controlled Leakage Exceeded Tech Specs During Surveillance Test Procedure.Caused by Improperly Set Needle Valves Located in Reactor Coolant Pump Seal Injection Line.Valves Positioned Correctly | | | 05000395/LER-1982-018, Forwards LER 82-018/03L-0.Detailed Event Analysis Encl | Forwards LER 82-018/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-018-03, /03L-0:on 821008,during Surveillance Test Procedure 303.006,pressure Bistable Failed to Change Output State.Caused by Failure of Printed Circuit Logic Card.Card Replaced & Test Procedure Performed Satisfactorily | /03L-0:on 821008,during Surveillance Test Procedure 303.006,pressure Bistable Failed to Change Output State.Caused by Failure of Printed Circuit Logic Card.Card Replaced & Test Procedure Performed Satisfactorily | | | 05000395/LER-1982-019-03, /03L-0:on 821010,during Initial Startup in Mode 3, Pressurizer PORV Block Valve Mvg 8000C in RCS Found Leaking in Open Position.Caused by Worn Valve Packing.Packing Replaced.Valve Tested & Returned to Operable Status | /03L-0:on 821010,during Initial Startup in Mode 3, Pressurizer PORV Block Valve Mvg 8000C in RCS Found Leaking in Open Position.Caused by Worn Valve Packing.Packing Replaced.Valve Tested & Returned to Operable Status | | | 05000395/LER-1982-019, Forwards LER 82-019/03L-0.Detailed Event Analysis Encl | Forwards LER 82-019/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-020, Forwards LER 82-020/03L-0.Detailed Event Analysis Encl | Forwards LER 82-020/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-020-03, /03L-0:on 821011,reactor Bldg Base Mat Seismic Monitoring Instrument IYA-1780 Tested Unsatisfactorily. Caused by Battery Charger Failure Resulting in Battery Discharge.Battery Replaced & Surveillance Performed | /03L-0:on 821011,reactor Bldg Base Mat Seismic Monitoring Instrument IYA-1780 Tested Unsatisfactorily. Caused by Battery Charger Failure Resulting in Battery Discharge.Battery Replaced & Surveillance Performed | | | 05000395/LER-1982-021, Forwards LER 82-021/03L-0.Detailed Event Analysis Encl | Forwards LER 82-021/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-021-03, /03L-0:on 821011,steam Line Pressure Dropped Below Tech Spec Min.Caused by Safety Valve 2806P Inadvertently Lifting After Being Freed from stuck-closed Position.Valve & Power Range Neutron Flux High Setpoint Reset | /03L-0:on 821011,steam Line Pressure Dropped Below Tech Spec Min.Caused by Safety Valve 2806P Inadvertently Lifting After Being Freed from stuck-closed Position.Valve & Power Range Neutron Flux High Setpoint Reset | | | 05000395/LER-1982-022-03, /03L-0:on 821012,circuit Breaker for Reactor Bldg Cooling Unit Fan XFN-62B Discovered Open & in Discharged Position.Cause Undetermined.All 480-volt Safeguard Switchgear Checked.Procedures Revised to Verify Position | /03L-0:on 821012,circuit Breaker for Reactor Bldg Cooling Unit Fan XFN-62B Discovered Open & in Discharged Position.Cause Undetermined.All 480-volt Safeguard Switchgear Checked.Procedures Revised to Verify Position | | | 05000395/LER-1982-022, Forwards LER 82-022/03L-0.Detailed Event Analysis Encl | Forwards LER 82-022/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-023, Forwards LER 82-023/03L-0.Detailed Event Analysis Encl | Forwards LER 82-023/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-023-03, /03L-0:on 821014,while in Mode 3,B Train Control Room Ventilation Sys Declared Inoperable for Maint Due to Failure of Pressure Regulator for Damper Actuator.Caused by Ruptured Regulator Diaphragm.Diaphragm Replaced | /03L-0:on 821014,while in Mode 3,B Train Control Room Ventilation Sys Declared Inoperable for Maint Due to Failure of Pressure Regulator for Damper Actuator.Caused by Ruptured Regulator Diaphragm.Diaphragm Replaced | | | 05000395/LER-1982-024-03, /03L-0:on 821018,plant Went Into Mode 4 W/O Performing Surveillance Test Procedure 114.002, Operational Leak Test. Caused by Procedural Inadequacies.Procedure Revised to Comply W/Tech Spec Requirements | /03L-0:on 821018,plant Went Into Mode 4 W/O Performing Surveillance Test Procedure 114.002, Operational Leak Test. Caused by Procedural Inadequacies.Procedure Revised to Comply W/Tech Spec Requirements | | | 05000395/LER-1982-024, Forwards LER 82-024/03L-0.Detailed Event Analysis Encl | Forwards LER 82-024/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1982-025-03, /03L-0:on 821020,during Performance of Surveillance Test Procedure,Porv PCV-445A Found Leaking. Caused by Degraded Seat/Disk Interface Due to Steam Impingement.Valves Will Be Repaired | /03L-0:on 821020,during Performance of Surveillance Test Procedure,Porv PCV-445A Found Leaking. Caused by Degraded Seat/Disk Interface Due to Steam Impingement.Valves Will Be Repaired | | | 05000395/LER-1982-025, Forwards LER 82-025/03L-0.Detailed Event Analysis Encl | Forwards LER 82-025/03L-0.Detailed Event Analysis Encl | |
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