LER-1983-013, Forwards LER 83-013/03L-0.Detailed Event Analysis Encl |
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4 fa SOUTH CAROLINA ELECTRIC & GAS COMPANY Peer odpes',% R E G:
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March 11, 1983 83 MAR 15 AID : 4 '
NucuAR OPERADON.
Mr. James P. O'Reilly Regional Administrator U.S. Nuclear Regulatory Commission Region 11, Suite 2900 101 Marietta Street, N.W.
Atlanta, Georgia 30303
SUBJECT:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Thirty Day Written Report LER 83-013
Dear Mr. O'Reilly:
Please find attached Licensee Event Report #83-013 for Virgil C.
Summer Nuclear Station.
This Thirty Day Report is required by Technical Specification 6.9.1.13.(b) as.a result of entry into Action Statement (a) of Technical Specifications 3.3.3.5,
" Remote Shutdown Instrumentation," and 3.3.3.6,
" Accident Monitoring Instrumentation," on January 13 and 19, 1983.
The submittal of this report is late because the occurrence was not initially documented for NRC reportability in compliance with Technical Specification 6.9.1.13.
As a result of a subsequent review of associated station documents, the reportability was identified, and is now being submitted accordingly.
Should there be any questions, please call us at your convenience.
Very truly yours, O. W.
D'xon, CJM:OWD:dwf/fjc Attachment cc:
V.
C.
Summer G.
D.
Moffatt T.
C. Nichols, Jr.
Site QA E.
C. Roberts C.
L. Ligon (NSRC)
O. W.
Dixon, Jr.
G. J. Braddick H.
N.
Cyrus J.
C. Miller H. T. Babb J. L. Skolds D.
A.
Nauman J.
B.
Knotts, Jr.
M.
B.
Whitaker, Jr.
B. A.
Bursey W. A.
Williams, Jr.
I&E (Washington)
O.
S. Bradham Document Management Branch R.
B.
Clary INPO Records Center C.
A.
Price NPCF A.
R.
Koon File 8303180229 830311 OFFICIAL COPY PDR ADOCK 05000395 S
PDR
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Mr. James P. O'Reilly LER No.-83-013 Page Two March 11, 1983 DETAILED DESCRIPTION OF EVENT On January 13, 1983,.at 0910 hours0.0105 days <br />0.253 hours <br />0.0015 weeks <br />3.46255e-4 months <br />, with the Plant in. Mode 1, the Condensate Storage Tank ~1evel indication (LI-3631A) failed high.
This is a Post Accident Monitoring System (PAMS) instrument, and Action Statement (a) of Technical Specification 3.3.3.6 applied.
The investigation performed by maintenance personnel not only discovered that the previously mentioned failure was due to frozen instrument lines on level transmitter LT-3631, but also identified that the adjacent level transmitter (LT-3631A), which provided indication to the Control Room Evacuation Panel (CREP), was inoperable because of the same frozen lines.
The personnel failed to report the additional failure to Operations personnel because they did not realize the significance of the'CREP indication in regards tx) Technical Specification 3.3.3.5.
On January 19, 1983, at 0849 hours0.00983 days <br />0.236 hours <br />0.0014 weeks <br />3.230445e-4 months <br />, with the Plant in Mode 1, an additional failure of the same instrument channels occurred due to the same circumstances as the January 13, 1983, occurrence.
PROBABLE CONSEQUENCES There were no adverse consequences from either of the events since level indication was available from the redundant Condensate Storage Tank level indicator (LI-3621A).
CAUSE(S) OF THE OCCURRENCE The failure of the condensate Storage Tank level instrumentation was due to frozen instrument lines.
The temperature sensing element for the heat trace system was not located per design and consequently failed to detect the actual temperature of the instrument lines.
I 4
~
e
.Mr. James P.
O'Reilly LER No.83-013 Page Three March.ll, 1983 IMMEDIATE CORRECTIVE ACTIONS TAKEN i
- - The investigation performed on January 13, 1983, indicated that LT-3631. had f ailed.because of f rozen instrument lines.
- - Maintenance personnel found that the same condition existed on the adjacent level transmitter LT-3631A, which provided indication to the CREP. -The heat trace system was verified to be functional but due to the location of the temperature sensing element had failed to detect _the actual temperature of the instrument lines.
Heat was applied, and the transmitter instrument lines were thawed out.
LT-3631 was returned to operable status on January 14, 1983, at 2045 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.781225e-4 months <br />, upon the' satisfactory completion of a Channel Check.
Operations personnel did not perform a Channel Check on the CREP indication since they were still unaware of the failure discovered by Maintenance.
An engineering evaluation was subsequently initiated on the failure of the heat. trace system to detect actual instrument line temperature in order to' prevent recurrence.
Prior to the completion of the engineering evaluation, a repeat of the failure occurred on January 19, 1983, at 0849 hours0.00983 days <br />0.236 hours <br />0.0014 weeks <br />3.230445e-4 months <br />.
As in the previous occurrence on January 13, 1983, Operations personnel were unaware of the possible loss of the CREP indication because of the common transmitter instrument lines.
Maintenance personnel bypassed the automatic controls of the heat trace system and left the system in the energized mode of operation.
The transmitters were returned to operable status by 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br /> on January 19, 1983.
The performance of a satisfactory Channel Check of the CREP instrumentation on February 3, 1983, provides assurance that 4
i transmitter LT-3631A was also returned to operable status at the same time as the Main Control Board indication from LT-3631.
The temperature sensing element for this portion of the-heat trace system on the Condensate Storage Tank level instrumentation was determined to be installed in the wrong location.
The element was 1
relocated on February 9, 1983, to the design location, and the heac trace system was returned to normal operation.
ACTION TAKEN TO PREVENT RECURRENCE The licensee has relocated the temperature sensing element for the heat trace system for Condensate Storage Tank level transmitters LT-3631 and LT-3631A.
An insulated enclosure was also installed on all of'the tank level transmitters in order to provide additional freeze protection.
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| 05000395/LER-1983-001-01, /01T-0:on 830119,w/plant in Mode 1,three Refueling Water Storage Tank Level Transmitters Failed High. Caused by Frozen Instrument Lines.Transmitters Thawed. Insulated Encls Will Be Installed | /01T-0:on 830119,w/plant in Mode 1,three Refueling Water Storage Tank Level Transmitters Failed High. Caused by Frozen Instrument Lines.Transmitters Thawed. Insulated Encls Will Be Installed | | | 05000395/LER-1983-001, Updated LER 83-001/01T-1:on 830119,three Refueling Water Storage Tank Level Transmitters Failed High.Caused by Transmitter Base Freezing.Transmitters Thawed.Insulated Encls & Addl Permanent Heat Trace Will Be Installed | Updated LER 83-001/01T-1:on 830119,three Refueling Water Storage Tank Level Transmitters Failed High.Caused by Transmitter Base Freezing.Transmitters Thawed.Insulated Encls & Addl Permanent Heat Trace Will Be Installed | | | 05000395/LER-1983-003, Forwards LER 83-003/03L-0.Detailed Event Analysis Encl | Forwards LER 83-003/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-003-03, /03L-0:on 830108 & 20,main Control Board Indication for Steam Generator a Feedwater Flow IFI-477 Failed Low.Caused by High Instrument Cabinet Temp.Power Supply Card Replaced & Recalibr | /03L-0:on 830108 & 20,main Control Board Indication for Steam Generator a Feedwater Flow IFI-477 Failed Low.Caused by High Instrument Cabinet Temp.Power Supply Card Replaced & Recalibr | | | 05000395/LER-1983-008-03, W/Plant in Mode 1,main Control Board Indication for Steam Generator B Steam Pressure Decreased Approx 100 Psig.Caused by Plugged Transmitter Sensing Line.Sensing Line Back Flushed | W/Plant in Mode 1,main Control Board Indication for Steam Generator B Steam Pressure Decreased Approx 100 Psig.Caused by Plugged Transmitter Sensing Line.Sensing Line Back Flushed | | | 05000395/LER-1983-008, Forwards Updated LER 83-008/03L-1.Detailed Event Analysis Encl | Forwards Updated LER 83-008/03L-1.Detailed Event Analysis Encl | | | 05000395/LER-1983-009, Forwards LER 83-009/03L-0.Detailed Event Analysis Encl | Forwards LER 83-009/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-009-03, /03L-0:on 830203,main Control Board Indicator (PI-950) for Reactor Bldg Pressure Failed Low.Caused by Intermittent Pressure Transmitter Failure.Transmitter Output Returned to Normal | /03L-0:on 830203,main Control Board Indicator (PI-950) for Reactor Bldg Pressure Failed Low.Caused by Intermittent Pressure Transmitter Failure.Transmitter Output Returned to Normal | | | 05000395/LER-1983-010, Forwards LER 83-010/03L-0.Detailed Event Analysis Encl | Forwards LER 83-010/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-010-03, /03L-0:on 830206,only One Isotopic Iodine Analysis Performed During Power Reduction from 50% to 5%.Caused by Personnel Misinterpreting Power Changes.Chemistry Lab Policy Issued Re Need for Analysis | /03L-0:on 830206,only One Isotopic Iodine Analysis Performed During Power Reduction from 50% to 5%.Caused by Personnel Misinterpreting Power Changes.Chemistry Lab Policy Issued Re Need for Analysis | | | 05000395/LER-1983-011, Forwards LER 83-011/03L-0.Detailed Event Analyis Encl | Forwards LER 83-011/03L-0.Detailed Event Analyis Encl | | | 05000395/LER-1983-011-03, /03L-0:on 830208 & 17,during Mode 1 Operation, Nuclear Sampling Sys Valves 9398 A,B & C Failed to Close. Caused by Limit Switch Failure on One Valve & Crud Buildup on Other Valve Seats.Crud Dislodged.Limit Switches Repaired | /03L-0:on 830208 & 17,during Mode 1 Operation, Nuclear Sampling Sys Valves 9398 A,B & C Failed to Close. Caused by Limit Switch Failure on One Valve & Crud Buildup on Other Valve Seats.Crud Dislodged.Limit Switches Repaired | | | 05000395/LER-1983-012, Forwards LER 83-012/03L-0.Detailed Event Analysis Encl | Forwards LER 83-012/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-012-03, /03L-0:on 830210,flow Indicator for Steam Generator a Feedwater Flow FI-477 Failed Low.Caused by Failure of Power Supply FQY-477.Circuit Board Replaced | /03L-0:on 830210,flow Indicator for Steam Generator a Feedwater Flow FI-477 Failed Low.Caused by Failure of Power Supply FQY-477.Circuit Board Replaced | | | 05000395/LER-1983-013, Forwards LER 83-013/03L-0.Detailed Event Analysis Encl | Forwards LER 83-013/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-013-03, /03L-0:on 830113 & 19,condensate Storage Tank Level Transmitters LT-3631 & LT-3631A Failed Due to Frozen Instrument Lines.Caused by Temp Sensing Element Not Being Located Per Design Specs.Element Relocated | /03L-0:on 830113 & 19,condensate Storage Tank Level Transmitters LT-3631 & LT-3631A Failed Due to Frozen Instrument Lines.Caused by Temp Sensing Element Not Being Located Per Design Specs.Element Relocated | | | 05000395/LER-1983-014-03, /03L-0:on 830217 & 0303,pressurizer PORV PCV-445B Found Leaking.Events Discovered by High Temp Indication in PORV Discharge Piping.Cause Unknown.Valve Will Remain Closed & Be Disassembled During 830317 Outage | /03L-0:on 830217 & 0303,pressurizer PORV PCV-445B Found Leaking.Events Discovered by High Temp Indication in PORV Discharge Piping.Cause Unknown.Valve Will Remain Closed & Be Disassembled During 830317 Outage | | | 05000395/LER-1983-014, Forwards LER 83-014/03L-0.Detailed Event Analysis Encl | Forwards LER 83-014/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-015-03, /03L-0:on 830219,while in Mode 1,5% Discrepancy Observed Between Main Control Board & Control Room Evacuation Panel Indication for Pressurizer Relief Tank Level.Caused by Design Error.New Transmitter Installed | /03L-0:on 830219,while in Mode 1,5% Discrepancy Observed Between Main Control Board & Control Room Evacuation Panel Indication for Pressurizer Relief Tank Level.Caused by Design Error.New Transmitter Installed | | | 05000395/LER-1983-015, Forwards LER 83-015/03L-0.Detailed Event Analysis Encl | Forwards LER 83-015/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-016, Forwards LER 83-016/03L-0.Detailed Event Analysis Encl | Forwards LER 83-016/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-016-03, /03L-0:on 830216,w/plant in Mode 1,discrepancy of 6% Observed Between Main Control Board Indicators for Sodium Hydroxide Storage Tank Level.Caused by Loose Fitting on High Side Sensing Line of Level Transmitter | /03L-0:on 830216,w/plant in Mode 1,discrepancy of 6% Observed Between Main Control Board Indicators for Sodium Hydroxide Storage Tank Level.Caused by Loose Fitting on High Side Sensing Line of Level Transmitter | | | 05000395/LER-1983-017, Forwards LER 83-017/03L-0.Detailed Event Analysis Encl | Forwards LER 83-017/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-017-03, /03L-0:on 830305,remote Info Acquisition Cabinet Experienced Electronic Problems Rendering Four Reactor Bldg Zone 3 Smoke Detectors Inoperable.Caused by Printed Circuit Card Failure.Card Replaced | /03L-0:on 830305,remote Info Acquisition Cabinet Experienced Electronic Problems Rendering Four Reactor Bldg Zone 3 Smoke Detectors Inoperable.Caused by Printed Circuit Card Failure.Card Replaced | | | 05000395/LER-1983-018-03, /03L-0:on 830306,while in Mode 1,nuclear Sampling Sys Valves 9398 A,B & C Failed to Close During Initial Performance of Accelerated Test Program.Caused by Crud Buildup on Valve Seats.Crud Dislodged & Switch Repaired | /03L-0:on 830306,while in Mode 1,nuclear Sampling Sys Valves 9398 A,B & C Failed to Close During Initial Performance of Accelerated Test Program.Caused by Crud Buildup on Valve Seats.Crud Dislodged & Switch Repaired | | | 05000395/LER-1983-018, Forwards LER 83-018/03L-0.Detailed Event Analysis Encl | Forwards LER 83-018/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-019-01, /01L-0:on 830317,trains of RHR & High Head Safety Injection Train a Inoperable for Approx 45 Minutes.Caused by Switching Problems W/Starting Circuitry of Chiller Unit XHX0001C.Switch Apparatus Modified | /01L-0:on 830317,trains of RHR & High Head Safety Injection Train a Inoperable for Approx 45 Minutes.Caused by Switching Problems W/Starting Circuitry of Chiller Unit XHX0001C.Switch Apparatus Modified | | | 05000395/LER-1983-019, Forwards LER 83-019/01L-0.Detailed Event Analysis Encl | Forwards LER 83-019/01L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-020-03, /03L-0:on 830305,fire Detector Sys Control Room Alarm Capability Lost for Intermediate Bldg Zones Aa,Bb & CC & for Diesel Generator Bldg Zones DG (427) & DG (436).Caused by Blown Fuse.Fuse Replaced | /03L-0:on 830305,fire Detector Sys Control Room Alarm Capability Lost for Intermediate Bldg Zones Aa,Bb & CC & for Diesel Generator Bldg Zones DG (427) & DG (436).Caused by Blown Fuse.Fuse Replaced | | | 05000395/LER-1983-020, Forwards LER 83-020/03L-0.Detailed Event Analysis Encl | Forwards LER 83-020/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-021, Forwards LER 83-021/03L-0.Detailed Event Analysis Encl | Forwards LER 83-021/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-021-03, /03L-0:on 830307,steam Generator Blowdown Monitor RM-L3 Failed Low,Reducing Number of Operable Channels. Caused by Moisture in Monitor Detector Due to Overhead Sample Valve O-ring Rupture.Detector Replaced | /03L-0:on 830307,steam Generator Blowdown Monitor RM-L3 Failed Low,Reducing Number of Operable Channels. Caused by Moisture in Monitor Detector Due to Overhead Sample Valve O-ring Rupture.Detector Replaced | | | 05000395/LER-1983-022-03, /03L-0:on 830308,conduit Containing Smoke Detector Circuits Cut During Core Drilling for Plant Mod.Fire Watch Posted.Caused by Failure to See Conduit Embedded in Fireproofing Matl.Conduit & Cable Replaced | /03L-0:on 830308,conduit Containing Smoke Detector Circuits Cut During Core Drilling for Plant Mod.Fire Watch Posted.Caused by Failure to See Conduit Embedded in Fireproofing Matl.Conduit & Cable Replaced | | | 05000395/LER-1983-022, Forwards LER 83-022/03L-0.Detailed Event Analysis Encl | Forwards LER 83-022/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-023, Forwards LER 83-023/03L-0.Detailed Event Analysis Encl | Forwards LER 83-023/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-023-03, /03L-0:on 830309,main Control Board Pressure Indicator for Reactor Bldg Pressure Channel 950 Failed Low. Caused by Intermittent Electronic Failure of Transmitter. Transmitter Replaced | /03L-0:on 830309,main Control Board Pressure Indicator for Reactor Bldg Pressure Channel 950 Failed Low. Caused by Intermittent Electronic Failure of Transmitter. Transmitter Replaced | | | 05000395/LER-1983-024, Forwards LER 83-024/03L-0.Detailed Event Analysis Encl | Forwards LER 83-024/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-024-03, /03L-0:on 830311,main Steam Line C Radiation Monitor Experienced Spurious Alarms.Caused by Slack Detector Cable Allowing Signal Oscillations.Detector Cable Will Be More Adequately Secured by 830501 | /03L-0:on 830311,main Steam Line C Radiation Monitor Experienced Spurious Alarms.Caused by Slack Detector Cable Allowing Signal Oscillations.Detector Cable Will Be More Adequately Secured by 830501 | | | 05000395/LER-1983-025, Forwards LER 83-025/03L-0.Detailed Event Analysis Encl | Forwards LER 83-025/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-025-03, /03L-0:on 830313,containment Bulkhead Door Seal on Personnel Access Air Lock Found W/Excessive Seal Leakage. Caused by Dirt on Door Seal.Seal Cleaned.Air Lock Tested | /03L-0:on 830313,containment Bulkhead Door Seal on Personnel Access Air Lock Found W/Excessive Seal Leakage. Caused by Dirt on Door Seal.Seal Cleaned.Air Lock Tested | | | 05000395/LER-1983-026, Forwards LER 83-026/03L-0 | Forwards LER 83-026/03L-0 | | | 05000395/LER-1983-026-03, /03L-0:on 830318,reactor Bldg Cooling Unit Svc Water Flow Indicators Failed Low & Accident Monitoring Instrumentation Channel 4496 Declared Inoperable.Caused by Internal Failure of Indicator FI-4496.Indicator Replaced | /03L-0:on 830318,reactor Bldg Cooling Unit Svc Water Flow Indicators Failed Low & Accident Monitoring Instrumentation Channel 4496 Declared Inoperable.Caused by Internal Failure of Indicator FI-4496.Indicator Replaced | | | 05000395/LER-1983-027, Forwards LER 83-027/03L-0.Detailed Event Analysis Encl | Forwards LER 83-027/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-027-03, /03L-0:on 830318,main Control Board Temp Indication TE-413 for Reactor Coolant Outlet Temp Exhibited Erratic Indications.Caused by Varying Resistance Between Compensated Lead & Low Side Resistance Leg of TE-413 | /03L-0:on 830318,main Control Board Temp Indication TE-413 for Reactor Coolant Outlet Temp Exhibited Erratic Indications.Caused by Varying Resistance Between Compensated Lead & Low Side Resistance Leg of TE-413 | | | 05000395/LER-1983-028-01, /01T-0:on 830406,out-of-tolerance Measurement Found on Undervoltage (UV) Trip Device Between Moving Core & Rolling Bracket.Caused by Mfg Variation of UV Trip Devices. Devices Will Be Replaced | /01T-0:on 830406,out-of-tolerance Measurement Found on Undervoltage (UV) Trip Device Between Moving Core & Rolling Bracket.Caused by Mfg Variation of UV Trip Devices. Devices Will Be Replaced | | | 05000395/LER-1983-028, Forwards LER 83-028/01T-0.Detailed Event Analysis Encl | Forwards LER 83-028/01T-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-029, Forwards LER 83-029/03L-0.Detailed Event Analysis Encl | Forwards LER 83-029/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-029-03, /03L-0:on 830320,w/reactor Bldg Purge Initiated, Radiation Monitor RM-A4 Read Higher than Normal Pump RM-A4 & Detector Secured to Change Filter,Leaving Purge Unmonitored for 5 Minutes.No Activity Released During Event | /03L-0:on 830320,w/reactor Bldg Purge Initiated, Radiation Monitor RM-A4 Read Higher than Normal Pump RM-A4 & Detector Secured to Change Filter,Leaving Purge Unmonitored for 5 Minutes.No Activity Released During Event | | | 05000395/LER-1983-030, Forwards LER 83-030/03L-0.Detailed Event Analysis Encl | Forwards LER 83-030/03L-0.Detailed Event Analysis Encl | | | 05000395/LER-1983-030-03, /03L-0:on 830324,reactor Bldg Fire Detection Zones Ooo & Ppp Declared Inoperable When Power Supply Breaker Opened.Caused by Faulty Power Supply Transformer in Smoke Detector IXA-4964E in Zone Ppp.Transformer Replaced | /03L-0:on 830324,reactor Bldg Fire Detection Zones Ooo & Ppp Declared Inoperable When Power Supply Breaker Opened.Caused by Faulty Power Supply Transformer in Smoke Detector IXA-4964E in Zone Ppp.Transformer Replaced | |
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