LER-1983-019, Forwards LER 83-019/01L-0.Detailed Event Analysis Encl |
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t SOUTH CAROLINA ELECTRIC & GAS COMPANY p
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CotuustA. S*UTH CAROLINA 29218
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March 30, 1983 Q
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A Mr. James P. O'Reilly
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j Regional Administrator
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U.S.
Nuclear Regulatory Commission Region II, Suite 2900
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101 Marietta Street, N.W.
4 Atlanta, Georgia 30303
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SUBJECT:
Virgil C.
Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 e
Fourteen Day Written Report LER 83-019
Dear Mr. O'Reilly:
3 Plea.se find attached Licensee Event Report #83-019 for Virgil C.
Summer Nuclear Station.
This Fourteen Day Report is required by Technical Specification 6.9.1.12.(b) as a result of entry into 1
Technical Specification 3.0.3,
" Limiting Conditions for Operation i
and Surveillance Requirements, Applicability," on March 17, 1983.
6 Sho,uld there be any questions, please call us at your convenience.
i Ver truly our,
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Attachment cc:
V. C.
Summer G. J.
Braddick T.
C. Nichols, Jr.,/O. W. Dixon, Jr.
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C. Miller 5
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C. Roberts J. L.
Skolds i
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N. Cyrus J.
B. Knotts, Jr.
Group / General Managers I6E (Washington) y R. B.
Clary Document Management C.
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Price Branch E'
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Bradham INPO Records Center j
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Koon NPCF D. A. Lavigne File (Lic./Eng.)
1 C. L. Ligon (NSRC) 2 i
3 8304050443 830330 g
PDR ADOCK 05000395 S
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Mr. : James'~ P.. O' Reilly,
1 LER No.'83-019-Page Two-l March 30,.1983 i
d EVENT DESCRIPTION AND PROBABLE CONSEQUENCES-i Cn March 17, 1983, with the Plant operating in Mode 1, Train "A" of the Residual Heat Removal (RHR) System'and Traini"A" of the High Head. Safety Injection. System were rendered. inoperable'for
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approximately 45 minutes per Technical Specification definition
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L 1.18, " Operability." - The cause of this conditior is' described-below.
The Train "B" RHR pump previously had been. removed from i:
service'for preventive maintenance.- Technical SpecificationL 3.5.2, " Emergency Core Cooling' Systems - Tavg >1350*F," requires that two (2) independent Emergency Core Cooling ~ Systems (ECCS)-
p be OPERABLE for Modes 1, 2, and 3.
Since the associated Technical; Specification Action Statement only; addresses onef(l) ECCS L
inoperable, Specification 3.0.3 was implemented for-the approximate-45 minate time period.
1I There.were no adverse consequences resulting from'this condition.
L The Train "A" Chilled Water Pump remained in service,.thereby j-providing cooling water to the Train'"A" Component: Cooling Water pump motor and the Train "A" Charging / Safety-Injection pump.-
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CAUSE AND CORRECTIVE ACTIONS
I On March 16, 1983, the' Train "B" RHR-pump was removed.from service 4
i in order to perform preventive maintenance.- Technical b
Specification 3.5.2 Action Statement (a)Lwas voluntarily. entered
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in order'to' perform this maintenance.
The Action' Statement j
allowed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to have the pump returned; to operable-status.
2 On March 17,'1983, at approximately'0120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />,, Train "A"jRHR'and i
Train'"A" High Head Safety Injection ~were rendered-inoperable' when a' support-system (Train "A" ~ Chilled Afater System) failed'to j[,
restart subsequent toLperformance of a surveillance test. 'The-s.
Chilled Water: System provides cooling water 0to the: Component r'
j Cooling < Water? pump motor bearings.
The: Component; Cooling' Water:
System la~ turn'supolies cooling waterxto'the1RHRipump?.sealt'and the RHRtheat exchangerishell/sideias'the heat 7 transfer medium.
Thus,:the. cascading failure resulted'in theCinoperability ofETrainL
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"A" RHR.
The Chilled Water: System directly1provides cooling water <
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'for?theLCharging/SafetyJInjection"puup-oil; coolers.-
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Mr.'JamesfP. O'Reilly.
LER.Mo. 83-019-
'Page Three.
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March 30,-1983 i
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CAUSE AND CORRECTIVE ACTIONS"(Continued)
L The Chilled-Water System failure is attributed to problems.
- - experienced in the starting circuitry'of chiller unit XHX0001C L
(swing unit XHX0001C wasialigned to Train "A" chilledLwater-L because the normal Train "A" chiller unit 1XHX0001A had been removed'from service for maintenance).
More specifically,.the1 starting circuit consists of a - roller cam that actuates a micro switch for circuit completion.
The cam was: discovered to be slipping out of' alignment relative to' the micro switch.
After engineering review and. resolution of'the problem, the. chiller unit was returned to service at ~ approximately: 0205, hours.
l l.
To prevent recurrence of this problem,.the cams have been modified -
on all three (3) chiller units.
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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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