LER-1983-031, Forwards LER 83-031/03L-0.Detailed Event Analysis Encl |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3951983031R00 - NRC Website |
|
text
.
' kb SOUTH CAROLINA ELECTRIC & GAS COMPANY post oprics 7e4 COLuusiA south CAROLINA 29218 O. W. DixoN, JR.
nu$*.'d"o"$I,"[o.
April 22, 1983 mw
=>
~o Mr. James P. O'Reilly
((
{y
- - w w
Regional Administrator U.S. Nuclear Regulatory Commission
- k Region II, Suite 2900
,a 101 Marietta Street, N.W.
,If k.;,
,{
Atlanta, Georgia 30303 cn cn
SUBJECT:
Virgil C. Summer Nuclear Station' Docket No. 50/395 Operating License No. NPF-12 Thirty Day Written Report LER 83-031
Dear Mr. O'Reilly:
Please find attached Licensee Event Report #83-031 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 the Action Statement of Technical Specification 3.1.2.3,
" Reactivity Control Systems, Charging Pump - Shutdown," and into Action Statement (a) of Technical Specification 3.4.1.4.2,
" Reactor Coolant System, Cold Shutdown - Loops Not Filled," on March 25, 1983.
Should there be any questions, please call us at your convenience.
Ver truly ours O. W. D' on, Jr.
HCF:OWD/dwf i
Attachment cc:
V. C.
Summer G.
J. Braddick T.
C. Nichols, Jr.,/O. W. Dixon, Jr.
J.
C. Miller E.
C.
Roberts J. L. Skolds H.
N.
Cyrus J.
B.
Knotts, Jr.
Group / General Managers I&E (Washington)
O.
S. Bradham Document Management R. B.
Clary Branch C. A.
Price INPO Records Center.
A. R.
Koon NPCF D. A. Lavigne File (Lic./Eng.)
C.
L. Ligon (NSRC) 8305030627 830422 PDR ADDCK 05000395 S
PDR Te--- A L 2
t Mr. James P. O'Reilly LER No.83-031 Page Two April 22, 1983 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES On March 25, 1983, with the Plant in Mode 5, the Train "B" HVAC System Mechanical Water Chiller (XHX-001B) of the Chilled Water l
System (VU) tripped at 1750. hours.
The chiller was supplying cooling water for the Train "B" Component Cooling Water System pump motor, which was providing cooling water for the Train "B" Residual Heat Removal System heat exchangers and pump shaft seal water cooler.
Additionally, the chiller was providing cooling 1
water to the Train "B" Charging / Safety Injection pump inbe oil cooler.
The action statements of the following Technical Specifications were entered as a result of the trip condition:
i
)
Technical Specification 3.1.2.3,
" Reactivity Control System, Charging Pump - Shutdown," which-requires one (1) charging pump in the bore.'. ion flow path to be operable.
Technical Specification 3.4.1.4.2, Reactor Coolant System, Cold Shutdown - Loops Not Filled," which requires two (2) residual heat removal loops to be operable and at least one (1) loop to be in operation.
There were no adverse consequences resulting from the event as 1
I.
Train "A" of the Emergency Core Cooling Systems were aligned to the Train "A" Chiller (XHX-001A).
At 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br />, on March 25, i
1983, maintenance activities were completed on backup. Chiller t
(XHX-001C), and it was aligned and started on the Train "B" Chilled Water System.
These actions satisfied the Technical Specification Action Statements.
CAUSE AND CORRECTIVE ACTIONS
The Station experienced a loss of bus IDS at 1607 hours0.0186 days <br />0.446 hours <br />0.00266 weeks <br />6.114635e-4 months <br /> on-March 25, 1983, due to an inadvertent opening of breaker OCB-8892.
Subsequently, the Train "B" Solid State Protection System stripped the vital plant loads (including the Chiller, XHX-001B) and started the "B" Diesel Generator (XEG-001B).
The Chiller XHX-001 was then reloaded by the loading sequencer.
Approximately one hour and forty-three minutes later, at 1750 hours0.0203 days <br />0.486 hours <br />0.00289 weeks <br />6.65875e-4 months <br />, Chiller XHX-001B tripped for no apparent reason.
A-common indicator light for. "high motor temperature," "high discharge I
temperature,";and "high oil temperature," located on.the local control panel was found to be energized.
h 4
r 4
y e-n ev---
s Mr. James P. O'Reilly LER No.83-031 Page Three April 22, 1983 CAUSE AND CORRECTIVE ACTIONS Continued A post-trip investigation produced no explanations for the chiller trip.
A manufacturer's representative was procured; and on March 29, 1983, Chiller XHX-001B was restarted to determine the cause of the unexplained chiller trip on March 25, 1983.
It was discovered that the local control switch for isolation valve XVB-3126, which controls cooling water flow to the chiller, was intermittently failing, thereby preventing the valve f rom opening.
This would account for the alarm and subsequent trip of Chiller XHX-001B on March 25, 1983.
A maintenance work request has been generated to repnir the control switch.
This will be accomplished when Chiller XHX-001B is available or before startup af ter the present steam generator modification outage.
i
|
|---|
|
|
| | | Reporting criterion |
|---|
| 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 | |
|