:on 930722,concern Raised Re 4 Kv Vital Bus Second Level Undervoltage Protection Dropout Setpoint Due to Design,Mfg,Const/Installation.Analysis of Event Continuing. Suppl LER Will Be Submitted| ML18100A577 |
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| Site: |
Salem  |
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| Issue date: |
08/27/1993 |
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| From: |
Pastva M Public Service Enterprise Group |
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| To: |
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| Shared Package |
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| ML18100A576 |
List: |
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| References |
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| LER-93-014-01, LER-93-14-1, NUDOCS 9309030259 |
| Download: ML18100A577 (5) |
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text
NRC FORM 366 (6-89)
U.S. NUCLEAR REGULATORY COMMISSION APPROVEO OMB NO. 3150-0104 LICENSEE EVENT REPORT (LER)
FACILITY NAME 111 Salem Generating Station - Unit 1 TITLE 141 EXPIRES: 4/30/92 ESTIMATED BUROEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARO COMMENTS REGAROING BUROEN ESTIMATE TO THE RECOR OS ANO REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, QC 20555, ANO TO THE PAPERWORK REOUCTION PROJECT 13150-0104). OFFICE OF MANAGEMENT ANO BUOGET, WASHINGTON, QC 20503.
I OOCKET NUMBER (2)
I PAGE 131 01s101010121112 1!0F01S 4KV Vital.Bus Second Level Undervoltage Protection Dropout Setpoint Concern (both Units).
EVENT.DATE (5)
LER NUMBER 16)
REPORT DATE (71 OTHER FACILITIES INVOLVED (Bl MONTH DAY YEAR YEAR :ff se~~~~~~AL tt ~~~~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI Salem Unit 2 o 15 Io Io I o 13 11 I 1 ol 1 2 I 2 c 3 913 - o I 114 -
ol 1 o I s *2 I 1 9 I 3 OPERATING MODE (9)
THIS REPORT IS SUBMITTED PURSUANT TO THE Rl.QUIREMENTS OF 10 CFR §: (Chock on* or moro of th* following} (11 I 1
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TELEPHONE NUMBER M. J. Pastva. Jr. ~ LER Coordinator 6 I 0 I 9 3 I 3 I 9 1-I 5 11 16 I 5 COMPLETE ONE LINE FOR EACH C.OMPONENT FAILURE DESCRIBED IN THIS REPORT (131.
CAUSE
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ABSTRACT (Limit to 1400 spac6s, i.e., approximately fifteen single-space ty,nwrittan lines} (161
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I EXPECTED SUBMISSION DATE 115l MONTH DAY YEAR 1 10 2 15 9 I 3 On 7/22/93, it was determined that the present 91.6% dropout setpoint for second level undervoltage (UV) protection of the 4 kilovolt.(KV) vital buses (both Salem Units), may not fully protect motors should the bus voltage degrade to less than 93.2% but greater than 91.6%.
This is contrary to Branch Technical Position (BTP)-PSB-1 and the Updated Final Safety Analysis Report (UFSAR).
However, engineering calculation shows, given the postulated worst case design basis event, vital bus recovery voltage will not degrade to less than 93.2%.
The 91.6% dropout setpoint was based on the lowest voltage the 4.16 KV motors could be allowed to operate (i.e. 90%) due to voltage drops in the motors' cables and relay inaccuracy considerations.
The revised recovery voltage of 93.2% will now maintain all motors operable under degraded voltage conditions.
During the next refueling outage on each Unit, design changes will be implemented to change the relay setpoint to meet the requirements of BTP-PSB-1.
In the interim, administrative controls are being implemented.
Technical Specifications and the UFSAR will be reviewed and revised as appropriate.
Analysis of this event is continuing.
Upon completion of this effort, a supplement to this LER will be submitted.
9309030259 930827 I PDR ADOCK 05000272 S
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NRC Form 366 (6-89)
_*-1
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SUPPLEMENTAL LICENSEE EVENT REPORT (LER} TEXT CONTINUATION Salem Generating Station
- unit 1 DOCKET NUMBER 5000272
PLANT AND SYSTEM IDENTIFICATION
Westinghouse Pressurized Wate~ Reactor LER NUMBER 93-014-01 PAGE 2 of 5 Energy Industry Identification System (EIIS} codes are identified in the text as {xx}
IDENTIFICATION OF OCCURRENCE:
4 KV Vitai Bus Second Level Undervoltage Protection Dropout Setpoint Concern (both Salem Units}
Event Discovery Date:
7/22/93 Supplement Report Date:
8/27/93 This report was initiated by Incident Report No.93-320.
This event is reportable per 10CFR50.73(a} (2} (ii} (B} and 10CFR50.73(a} (2} (v} (D}.
CONDITIONS PRIOR TO OCCURRENCE:
Unit 1:
Mode 1 Reactor Power 80% - Unit Load 815 MWe Unit 2:
Mode 1 Reactor Power 100% - Unit Load 1140 MWe DESCRIPTION OF OCCURRENCE:
On July 22, 1993, it was determined that the present 91.6% dropout setpoint for second level undervoltage (UV} protection of the 4 kilovolt (KV} vital buses {VJ} (both Salem Units}, will not fully protect motors at the 230 and 460 volt level should the 4KV bus voltage degrade to less than 93.2% but greater than 91.6%.
This is contrary to Branch Technical Position (BTP.}-PSB-1 and the Updated Final Safety Analysis.Report (UFSAR}.
However, engineering calculation shows, given the postulated worst case design basis event, vital bus recovery voltage will not degrade to less than 93.2%.
The Nuclear Regulatory Commission was notified of this event per Code of Federal Regulations 10CFR50.72(b} (1) (ii) (B).
ANALYSIS OF OCCURRENCE:
Availability of minimum redundant alternating current (A.C.) power sources and distribution systems ensures sufficient power will be available to safety-related equipment for safe shutdown of the facility and the mitigation and control of accident conditions within the facility, as required by General Design Criteria 17 of Appendix "A" to 10CFR Part 50.
Per BTP-PSB-1, the plant.licensing basis requires a second level of undervoltage protection for 4KV vital buses to ensure minimum motor terminal voltage for all safety-related
-. \\
. SUPPLEMENTAL LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit.1 DOCKET NUMBER 5000272 ANALYSIS OF OCCURRENCE:
(cont'd)
LER NUMBER 93-014-01 PAGE 3 of 5 motors.
At Salem, when vital bus voltage drops below the dropout setpoint for relays providing this protection for greater than 13 seconds, vital bus loads are automatically transferred to their respective emergency diesel generators.
- As part of the self-initiated Electrical Engineering Self-Assessment Program, electrical calculations are being reviewed to ensure guidelines of BTP-PSB-1 are met.
On July 1, 1993, review of Revision 1 of ES-15.00S(Q), "Salem Units 1 and 2 Degraded Grid study" identified a potential concern with the 91.6% dropout setpoint of the Units' 4KV vital buses (lA, lB, lC, 2A, 2B, and 2C).
on July 22, 1993, further analysis of this concern determined the recovery vital bus voltage is 93.2% of 4.16KV following transfer of the Auxiliary Power Transformers (APTs) to the Station Power Transformers (SPTs).
This voltage could result should a group bus transfer to the SPTs occur coincident with a Loss-of-Coolant Accident (LOCA) and the unaffected unit in startup or shutdown.
UFSAR Section 8.3.1.2 describes the setpoint as being determined using the 90% minimum motor terminal voltage as the starting point.
Since 93.2% bus voltage is required to ensure the minimum motor terminal voltage, the existing 91. 6% dropout setpoint is not in compliance with the UFSAR or the BTP.
However, because ES-15.00S(Q) calculations also show that vital bus recovery voltage will not degrade to a level at which actual motor degradation could occur, the intent of the UFSAR and BTP is still met.
These calculations take credit for operation, prior to the event, of the load tap changers which are set to maintain a minimum initial bus.voltage of 4.3KV.
Following *event discovery, an evaluation to justify continued operation of both Salem Units, concluded the present dropout setpoint of the relays does not meet the intent of the BTP.
However, Revision 1 of Engineering Calculation ES-15.00S(Q) determined there is not a significant safety concern with the present dropout setpoint provided the 4.16KV vital buses are maintained at 4.3KV or greater.
Design changes will be implemented during the next refueling outage on each Unit to change the dropout setpoint to meet the intent of the BTP.
For the interim, 4.16KV vital bus voltages are being monitored to assure load tap changers are operating properly to maintain a minimum bus voltage of 4.3KV.
In addition, bus voltages below 4.3KV will be adjusted between 4.3KV and 4.5KV and restrictions concerning vital bus lineup will be in effect (see "CORRECTIVE ACTIONS:" section).
Analysis of this event is continuing..
Included will be a historical assessment of the effect of the revised assumptions at vital bus levels below 4KV.
Upon completion of this effort, a supplement to this LER will be submitted.
SUPPLEMENTAL LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 APPARENT CAUSE OF OCCURRENCE:
DOCKET NUMBER 5000272 LER NUMBER 93-014-01 PAGE 4 of 5 The cause of this event is."Design, Manufacturing, Construction/Installation", per NUREG-1022 *-
The 91. 6% dropout setpoint was based on the lowest voltage the 4.16 KV motors could be allowed to operate (i.e. 90%) due to voltage drops in the motors' cables and relay inaccuracy considerations.
The revised dropout setpoint, based upon the revised recovery voltage of 93.2%, will now maintain all motors operable under degraded voltage conditions.
PRIOR SIMILAR OCCURRENCES:
No prior similar occurrences of this event were identified.
SAFETY SIGNIFICANCE
Engineering is currently completing its evaluation of the safety significance of past operation with the non-conservative second level UV setpoint.
With the current interim controls, the health and safety of the public.is not affected by this event.
Upon completion of this evaluation this LER will be supplemented.
CORRECTIVE ACTION
Design changes will be implemented to change the.relay setpoint on both Units to meet the requirements of BTP-PSB-1 and be in accordance with the plant design basis.
This will be done during the upcoming Unit 1 refueling outage and the next Unit 2 refueling outage.
A License Change Request will be implemented to revise Technical Specifications in accordance with the second level UV reiay setpoint concern.
The UFSAR will be reviewed and revised as appropriate.
Administrative controls are being implemented to ensure the following restrictions are employed as interim action until implementation of design changes:
- 1.
- 4.16KV vital bus voltages will be logged hourly to assure a minimum vital bus voltage of 4.3KV.
Bus voltages less than 4.3KV will be adjusted to between 4.3KV and 4.5KV.
- 2.
Only two vital buses may be energized from their operating transformer if both the corresponding group buses are on their respective APT.
3a.
Three vital*buses may be energized from the operatingtransf ormer if one of the corresponding group buses is transferred to the operating SPT or l
SUPPLEMENTAL LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station Unit 1
CORRECTIVE ACTION
(cont'd)
DOCKET NUMBER 5000272 LER NUMBER 93-014-01 PAGE 5 of 5 3b.
Three vital buses may be energized from the operating transformer if the load which can be transferred from the APTs is reduced by 5 mega volt amps.
MJPJ:pc SORC Mtg.93-077 General Manager -
Salem Operations
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| 05000311/LER-1993-001-01, :on 921209,under-frequency Protection for 2H 4 Kv Group Bus Unknowingly Inoperable Due to Mispositioned Test Switch.Caused by Personnel Error.Group UV & Uf Monthly Procedures Will Be Revised |
- on 921209,under-frequency Protection for 2H 4 Kv Group Bus Unknowingly Inoperable Due to Mispositioned Test Switch.Caused by Personnel Error.Group UV & Uf Monthly Procedures Will Be Revised
| 10 CFR 50.73(a)(2) | | 05000272/LER-1993-001, :on 930111,TS 3.0.3 Intentionally Entered Twice Due to Removal of Main & Auxiliary 115-volt Power Supply Fuses.Caused by Equipment Failure.Design Change Will Be Installed to Relocate Flange |
- on 930111,TS 3.0.3 Intentionally Entered Twice Due to Removal of Main & Auxiliary 115-volt Power Supply Fuses.Caused by Equipment Failure.Design Change Will Be Installed to Relocate Flange
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000272/LER-1993-002, :on 920116,manual Reactor Trip Initiated When 12 SGFP Tripped Due to Turbine Trip FW Isolation Signal. Caused by Equipment Failure.Faulty Turbine Bypass Sys Components Replaced |
- on 920116,manual Reactor Trip Initiated When 12 SGFP Tripped Due to Turbine Trip FW Isolation Signal. Caused by Equipment Failure.Faulty Turbine Bypass Sys Components Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000311/LER-1993-002-01, :on 930128,pumps Tripped on Low Suction Pressure.Caused by Equipment Failure.Loose SGFP Master Controller Test Jack Repaired & Other Jacks in SGFP Speed Control Loop Inspected & Repaired as Required |
- on 930128,pumps Tripped on Low Suction Pressure.Caused by Equipment Failure.Loose SGFP Master Controller Test Jack Repaired & Other Jacks in SGFP Speed Control Loop Inspected & Repaired as Required
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(o)(2) 10 CFR 50.73(o)(2)(i) 10 CFR 50.73(o)(2)(ii) | | 05000311/LER-1993-003-01, :on 930131,level Indicator of 21 Bast Declared Inoperable Due to False High Level Indications.Caused by Design Construction/Installation.Design Change Will Be Developed to Reduce Bast Boron Concentration |
- on 930131,level Indicator of 21 Bast Declared Inoperable Due to False High Level Indications.Caused by Design Construction/Installation.Design Change Will Be Developed to Reduce Bast Boron Concentration
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000272/LER-1993-003, :on 930123 & 27,both Basts Declared Inoperable Due to Respective False High Level Indication.Cause by Bubbler Tube Blockage.Number 11 Bast Level Indicator Bubbler Tube Blown Down to Remove Blockage |
- on 930123 & 27,both Basts Declared Inoperable Due to Respective False High Level Indication.Cause by Bubbler Tube Blockage.Number 11 Bast Level Indicator Bubbler Tube Blown Down to Remove Blockage
| 10 CFR 50.73(o)(2)(v) 10 CFR 50.73(o)(2)(vii) 10 CFR 50.73(o)(2)(i) | | 05000311/LER-1993-004, :on 930206,both Main Turbine first-stage Impulse Pressure Indication Channels Indicated False Readings.Caused by Inadequate Sensing Line Protection. Failed Heat Tracing Will Be Repaired |
- on 930206,both Main Turbine first-stage Impulse Pressure Indication Channels Indicated False Readings.Caused by Inadequate Sensing Line Protection. Failed Heat Tracing Will Be Repaired
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000272/LER-1993-004-01, :on 930216,automatic Reactor Trip Occurred Due to Overtemperature Delta Temp Signal.Caused by Equipment Failure.Module Output Gain Selector Switch 1QM411B Cleaned & Exercised & Capacitors Replaced |
- on 930216,automatic Reactor Trip Occurred Due to Overtemperature Delta Temp Signal.Caused by Equipment Failure.Module Output Gain Selector Switch 1QM411B Cleaned & Exercised & Capacitors Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000272/LER-1993-005, :on 930218,experienced Reactor Protection Sys Reactor Trip/Turbine Trip Signal,When 12 SG Level Decreased. Caused by Personnel Error.Event Will Be Reviewed for Incorporation in Applicable Training Program |
- on 930218,experienced Reactor Protection Sys Reactor Trip/Turbine Trip Signal,When 12 SG Level Decreased. Caused by Personnel Error.Event Will Be Reviewed for Incorporation in Applicable Training Program
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000311/LER-1993-005-01, :on 930316,reactor Trip Occurred on 24 SG low-low Level.Caused by Mgt/Qa Deficiency.Heater Drain Sys Level Control Booster Will Be Replaced |
- on 930316,reactor Trip Occurred on 24 SG low-low Level.Caused by Mgt/Qa Deficiency.Heater Drain Sys Level Control Booster Will Be Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000311/LER-1993-006-01, :on 930415,unexpected Train a SI Sys Signal Occurred Due to Steam Line Differential Pressure.Caused by Operating Characteristics of Error Inhibit Switch.Procedures Re Manipulation of Switches Reviewed |
- on 930415,unexpected Train a SI Sys Signal Occurred Due to Steam Line Differential Pressure.Caused by Operating Characteristics of Error Inhibit Switch.Procedures Re Manipulation of Switches Reviewed
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000272/LER-1993-006, :on 930221,station Power Transformers 12 & 22 Deenergized Due to Tripping of Common 13 Kv Ring Bus Section 4 Breakers & 500 Kv Section 1 Breakers.Caused by Inadequate Communication.Caution Tags Hung on Breakers |
- on 930221,station Power Transformers 12 & 22 Deenergized Due to Tripping of Common 13 Kv Ring Bus Section 4 Breakers & 500 Kv Section 1 Breakers.Caused by Inadequate Communication.Caution Tags Hung on Breakers
| 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(o)(2) | | 05000272/LER-1993-007, :on 930225,initial Investigation Indicated High Resistance Readings at Coil Stacks Resulting to TS 3.0.3 Entry.Caused by Sys Design.Review of Event in Progress & C/A Will Be Implemented Based on Results |
- on 930225,initial Investigation Indicated High Resistance Readings at Coil Stacks Resulting to TS 3.0.3 Entry.Caused by Sys Design.Review of Event in Progress & C/A Will Be Implemented Based on Results
| | | 05000311/LER-1993-007-01, :on 930528,all Four Rods of Control Rod Bank C, Group 1 Unexpectedly Dropped Fully Into Reactor Core.Caused by Degraded Signal from Regulation Board.Card Replaced & Firing Circuit Satisfactorily Tested |
- on 930528,all Four Rods of Control Rod Bank C, Group 1 Unexpectedly Dropped Fully Into Reactor Core.Caused by Degraded Signal from Regulation Board.Card Replaced & Firing Circuit Satisfactorily Tested
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000311/LER-1993-008-01, :on 930527,determined That Postulated Single Failure Concern Existed Where Failure of One Rod Control Sys Slave Cycler Decoder Card,In Conjunction W/Rod Motion Command Signal May Cause Rcca Withdrawal |
- on 930527,determined That Postulated Single Failure Concern Existed Where Failure of One Rod Control Sys Slave Cycler Decoder Card,In Conjunction W/Rod Motion Command Signal May Cause Rcca Withdrawal
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(i)(2) | | 05000272/LER-1993-008, :on 930304,determined That Design of Control Air Sys Containment Outboard Isolation air-operated Valves Inconsistent W/Description in Updated Fsar.Caused by Design/ Mfg Defect.Documentation Will Be Revised |
- on 930304,determined That Design of Control Air Sys Containment Outboard Isolation air-operated Valves Inconsistent W/Description in Updated Fsar.Caused by Design/ Mfg Defect.Documentation Will Be Revised
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000311/LER-1993-008, :on 930527,control Rod 1SA3 Withdrew to Approx 15 Steps from Fully Inserted in Response to Manual Insertion Command Due to Failure of Integrated Circuit Chips.Emergency License Amend Requested on 930617 |
- on 930527,control Rod 1SA3 Withdrew to Approx 15 Steps from Fully Inserted in Response to Manual Insertion Command Due to Failure of Integrated Circuit Chips.Emergency License Amend Requested on 930617
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | | 05000311/LER-1993-009-01, :on 930629,automatic Start of Motor Driven Auxiliary Feedwater Pumps Occurred Due to Mgt/Qa Deficiency. Troubleshooting Procedures Developed |
- on 930629,automatic Start of Motor Driven Auxiliary Feedwater Pumps Occurred Due to Mgt/Qa Deficiency. Troubleshooting Procedures Developed
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000311/LER-1993-010-01, :on 930629,reactor Shutdown Initiated Per TS 3.0.3 Due to Inoperability of More than One Control Rod Analog Rod Position Indication Per Control Bank.Signal Conditioning Modules of Affected Rods Adjusted |
- on 930629,reactor Shutdown Initiated Per TS 3.0.3 Due to Inoperability of More than One Control Rod Analog Rod Position Indication Per Control Bank.Signal Conditioning Modules of Affected Rods Adjusted
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000272/LER-1993-010, :on 930407,determined That Svc Water Flow Through DG Jacket Water & Lube Oil Coolers Less than Design Requirement of 700 Gpm.Caused by Design/Mfg Deficiency. Proper Setpoint Developed & Verified |
- on 930407,determined That Svc Water Flow Through DG Jacket Water & Lube Oil Coolers Less than Design Requirement of 700 Gpm.Caused by Design/Mfg Deficiency. Proper Setpoint Developed & Verified
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000311/LER-1993-010, :on 930629 & 30,TS 3.0.3 Entered Due to More than One Inoperable Analog Rod Position Indicator Per Bank. Caused by Sys Design.Signal Conditioning Modules of Affected Rods Adjusted |
- on 930629 & 30,TS 3.0.3 Entered Due to More than One Inoperable Analog Rod Position Indicator Per Bank. Caused by Sys Design.Signal Conditioning Modules of Affected Rods Adjusted
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000311/LER-1993-011, :on 931019,RMS Channels 2R13 A,B,C Were Inoperable Due to Efficiency Being Adjusted to Reduced Level.Implemented Design Changes & 2R13 A,B, & C Were Calibrated & Returned to Service |
- on 931019,RMS Channels 2R13 A,B,C Were Inoperable Due to Efficiency Being Adjusted to Reduced Level.Implemented Design Changes & 2R13 A,B, & C Were Calibrated & Returned to Service
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000311/LER-1993-011-01, :on 931019,inoperability of Radioactive Liquid Effluent Monitors Discovered Due to Use of Incorrect Source Decay Tables Values.Caused by Mgt/Qa Deficiency.Channels 2R19A,B,C & D Recalibrated |
- on 931019,inoperability of Radioactive Liquid Effluent Monitors Discovered Due to Use of Incorrect Source Decay Tables Values.Caused by Mgt/Qa Deficiency.Channels 2R19A,B,C & D Recalibrated
| | | 05000272/LER-1993-011, :on 930608,automatic Reactor Trip from 85% Power Occurred Due to Main Turbine Trip from Low Condenser Vacuum & P-9 Trip Permissive.Caused by Mgt/Qa Deficiency. Circulating Water Intake Structure Dredged |
- on 930608,automatic Reactor Trip from 85% Power Occurred Due to Main Turbine Trip from Low Condenser Vacuum & P-9 Trip Permissive.Caused by Mgt/Qa Deficiency. Circulating Water Intake Structure Dredged
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000311/LER-1993-012-01, :on 931030,TS 3.0.3 Entered Due to Inoperability of 21 Bast Level Indication While 22 Bast Out of Svc.Caused by Design Deficiency.Design Change Installed |
- on 931030,TS 3.0.3 Entered Due to Inoperability of 21 Bast Level Indication While 22 Bast Out of Svc.Caused by Design Deficiency.Design Change Installed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000272/LER-1993-012, :on 930609,vital Bus 1C Sensed Undervoltage Condition,Resulting in Automatic Start & Blackout Loading of DG 1C.Caused by Inattention to Detail on Part of Personnel. Positive Disciplinary Action Completed |
- on 930609,vital Bus 1C Sensed Undervoltage Condition,Resulting in Automatic Start & Blackout Loading of DG 1C.Caused by Inattention to Detail on Part of Personnel. Positive Disciplinary Action Completed
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000272/LER-1993-013, :on 930711,experienced Reactor/Turbine Trip Signal Due to Steam Flow/Feed Flow Mismatch.Caused by Inattention to Detail.Operations Personnel Disciplined |
- on 930711,experienced Reactor/Turbine Trip Signal Due to Steam Flow/Feed Flow Mismatch.Caused by Inattention to Detail.Operations Personnel Disciplined
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000311/LER-1993-013-01, :on 931202,DG 2C Declared Inoperable Due to Cracking in 3R Cylinder Liner.All Cylinder Liners Installed in 2C & 1B DGs Inspected & Previously Installed Canadian Allied Diesel Liners Replaced W/Alco Liners |
- on 931202,DG 2C Declared Inoperable Due to Cracking in 3R Cylinder Liner.All Cylinder Liners Installed in 2C & 1B DGs Inspected & Previously Installed Canadian Allied Diesel Liners Replaced W/Alco Liners
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | | 05000272/LER-1993-014-01, :on 930722,concern Raised Re 4 Kv Vital Bus Second Level Undervoltage Protection Dropout Setpoint Due to Design,Mfg,Const/Installation.Analysis of Event Continuing. Suppl LER Will Be Submitted |
- on 930722,concern Raised Re 4 Kv Vital Bus Second Level Undervoltage Protection Dropout Setpoint Due to Design,Mfg,Const/Installation.Analysis of Event Continuing. Suppl LER Will Be Submitted
| | | 05000272/LER-1993-014, :on 930722,determine 4 Kv Vital Bus Second Level Undervoltage Protection Dropout Setpoint Would Not Protect Motors.Detailed Study Showed Motors Would Have Performed Intended Safety Functions |
- on 930722,determine 4 Kv Vital Bus Second Level Undervoltage Protection Dropout Setpoint Would Not Protect Motors.Detailed Study Showed Motors Would Have Performed Intended Safety Functions
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) | | 05000311/LER-1993-014-01, :on 931228,ESF Actuation & Resultant & Pressurizer Overpressure Protection Sys Channel 1 Actuation Occurred.Caused by Defective Procedure.Slave Relay Surveillance Procedures Revised |
- on 931228,ESF Actuation & Resultant & Pressurizer Overpressure Protection Sys Channel 1 Actuation Occurred.Caused by Defective Procedure.Slave Relay Surveillance Procedures Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000272/LER-1993-015, :on 930913 & 16,BAST 12 Level Indicator Declared Inoperable Due to False Level Indications.Caused by Design of Bast Level Indication Sys.Design Change to Reduce Boron Concentration Will Be Implemented |
- on 930913 & 16,BAST 12 Level Indicator Declared Inoperable Due to False Level Indications.Caused by Design of Bast Level Indication Sys.Design Change to Reduce Boron Concentration Will Be Implemented
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000272/LER-1993-016, :on 931021,ESF Actuation Occurred Due to Electrical Short within 4 Kv Switchgear.Caused by Personnel Error Associated W/Ongoing Relay Maint Activities.Imposed Vital Bus & Switchyard Work Standdown |
- on 931021,ESF Actuation Occurred Due to Electrical Short within 4 Kv Switchgear.Caused by Personnel Error Associated W/Ongoing Relay Maint Activities.Imposed Vital Bus & Switchyard Work Standdown
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000272/LER-1993-017, :on 931106,infeed Breaker 13BSD from Station Power Transformer (Spt) 13 Failed to Close Due to Personnel Error.Discipline in Accordance W/Util Positive Discipline Program Conducted |
- on 931106,infeed Breaker 13BSD from Station Power Transformer (Spt) 13 Failed to Close Due to Personnel Error.Discipline in Accordance W/Util Positive Discipline Program Conducted
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000272/LER-1993-018, :on 931203,determined That Monthly Testing of Ssps Containment Pressure Hi Hi Input Channels Did Not Verify That Ssps Input Circuit Path Reclosed.Applicable Procedures Will Be Revised |
- on 931203,determined That Monthly Testing of Ssps Containment Pressure Hi Hi Input Channels Did Not Verify That Ssps Input Circuit Path Reclosed.Applicable Procedures Will Be Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000272/LER-1993-019, :on 931203,TS Action Statement Entered Due to Waste Gas Holdup Sys Oxygen Concentration Being Greater than 2% for More than 48 H.Oxygen Concentration within Waste Gas Sys Reduced to Less than 2% on 931212 |
- on 931203,TS Action Statement Entered Due to Waste Gas Holdup Sys Oxygen Concentration Being Greater than 2% for More than 48 H.Oxygen Concentration within Waste Gas Sys Reduced to Less than 2% on 931212
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000272/LER-1993-020, :on 931223,RCS Accumulator Upper Range Level Indication Inaccuracies Affecting Units 1 & 2 Identified. Caused by Use of Incorrect Original Scaling Factors. Accumulators on Both Units Correctly Rescaled |
- on 931223,RCS Accumulator Upper Range Level Indication Inaccuracies Affecting Units 1 & 2 Identified. Caused by Use of Incorrect Original Scaling Factors. Accumulators on Both Units Correctly Rescaled
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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