LER-1992-004, Forwards LER 92-004-00 Re 921009 Invalid Control Room, Containment & Fuel Bldg Ventilation ESF Actuations.Addl Info Provided Re 921014 Event |
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ACCEI.ERAI'j D DISTRIBUTIONDEMONSTRATION SYSTEM REGULi+RY INFORMATION DISTRIBUTZi~ SYSTEM (RIDE)
ACCESSION NBR:9211090101 DOC.DATE: 92/ll/02 NOTARIZED: NO DOCKET FAClL:STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH.NAME AUTHOR AFFILIATION LEVINE,J.M.
Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards LER 92-004-00 re 921009 invalid control room, containment 6 fuel bldg ventilation ESF actuations.Addi info provided re 921014 event.
DISTRIBUTION CODE:
IE22T COPIES RECEIVED:LTR
( ENCL i SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:Standardized plant.
05000530S RECIPIENT ID CODE/NAME PD5 LA TRAMMELLFC INTERNAL:. ACNW AEOD/DOA AEOD/ROAB/DSP NRR/DLPQ/LHFB10 NRR/DOEA/OEAB NRR/DST/SELB 8D
~QDS~SPLB8Dl
%EG=F-I-'DF 0 2 RGN5 FILE 01 EXTERNAL: EGSG BRYCEFJ.H NRC PDR NSIC POOREFW.
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RECIPIENT ID CODE/NAME PD5 PD ACRS AEOD/DSP/TPAB NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB8H3 NRR/DST/SRXB 8E RES/DSIR/EIB L ST LOBBY WARD NSIC MURPHYFG A NUDOCS FULL TXT COPIES LTTR ENCL 1
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NOTE TO ALL RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK.
ROOh< Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROhf DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED:
LTTR 31 ENCL 31
Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O, BOX 52034
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PHOENIX. ARIZONA85072-2034 JAMES M. LEVINE VICE RAESIDENT NVCI.EAARAODUCTION 192-00808-JUL/TRB/KR November 2,
1992 U.
S. Nuclear Regulatory Commission Attention: Document Control Desk Mail Station Pl-37 Washington, D.C.
20555
Dear Sirs:
Subj ect:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 3 Docket No.
STN 50-530 (License No. NPF-74)
Licensee Event Report 92-004-00 File'2-020-404 Attached please find Licensee Event Report (LER) 92-004-00 prepared and submitted pursuant to 10CFR50.73.
This LER reports the October 9, 1992 Unit 3 inadvertent Train A Containment Purge Isolation Actuation System (CPIAS),
Train A Control Room Essential Filtration Actuation System (CREFAS), Train A Control Room Ventilation Isolation Actuation System (CRVIAS), and Train A Fuel Building Essential Ventilation Actuation System (FBEVAS) Balance of Plant Engineered Safety Feature Actuation System (BOP ESFAS)
(JE) actuations resulting from a loss of power to the Train A BOP ESFAS Cabinet (SAA-C02A)
(i.e., relays deenergize to actuate) which occurred when a reactor operator inadvertently deenergized the wrong Train A Class 1E 480V Switchgear Load Center.
This LER also provides additional information on the October 14, 1992 Unit 3 inadvertent Train B CPIAS,
- CREFAS, FBEVAS BOP ESFAS actuations which occurred when a reactor operator did not ensure that the Train B BOP ESFAS relays were placed in bypass.
Although the October 14, 1992 event is no longer reportable under new regulations, an event description is provided in Section V. ADDITIONAL INFORMATION due to the similarities and close proximity of both events.
In accordance with 10CFR50.73(d),
a copy of this LER is being forwarded to the Regional Administrator, NRC Region V.
If you have any questions, please contact T. R. Bradish, Compliance
- Manager, at (602) 393-5421, Very truly yours, JML/TRB/KR Attachment
<nw a 92ii090i 5000gg0 PDR ADaCK 0 PDR S
V i
NRC Document Control Desk Page 2
Licensee Event Report 3-92-004-00 CC:
W, F.
Conway J.
B. Martin J.
A. Sloan INPO Records Center (all with attachment)
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| 05000528/LER-1992-001, :on 920102,pressure Boundary Leak Led to Cold Shutdown Per TS 3.4.5.2.Caused by Crack in Prz Steam Space Instrument Nozzle.Pad Weld Made to Stop Leak & 7 Inconel 600 Nozzles to Be Replaced at Next Outage |
- on 920102,pressure Boundary Leak Led to Cold Shutdown Per TS 3.4.5.2.Caused by Crack in Prz Steam Space Instrument Nozzle.Pad Weld Made to Stop Leak & 7 Inconel 600 Nozzles to Be Replaced at Next Outage
| | | 05000529/LER-1992-001-01, :on 920109,reactor Tripped Due to Low Steam Generator Level.Caused by Failure of Wires Connected to a Switch Assembly.Plant Was Stabilized in Mode 3 at Normal Operating Temperature & Pressure |
- on 920109,reactor Tripped Due to Low Steam Generator Level.Caused by Failure of Wires Connected to a Switch Assembly.Plant Was Stabilized in Mode 3 at Normal Operating Temperature & Pressure
| | | 05000530/LER-1992-001-02, :on 920124,reactor Trip Followed Manual Trip of Mfwp B,Following Receipt of Low Suction Pressure Trip Alarms for Both Mfwps.Caused by Inadequate Original Solder Joint. Instrument Air Valve Replaced and Resoldered |
- on 920124,reactor Trip Followed Manual Trip of Mfwp B,Following Receipt of Low Suction Pressure Trip Alarms for Both Mfwps.Caused by Inadequate Original Solder Joint. Instrument Air Valve Replaced and Resoldered
| 10 CFR 50.73(e)(2) | | 05000529/LER-1992-002-01, :on 920323,reactor Trip & Train a Loss of Power ESFAS Actuation Occurred.Caused by Fault on Startup Transformer Disconnect Switch.Disconnect Pole Assemblies on Disconnect Switch Replaced |
- on 920323,reactor Trip & Train a Loss of Power ESFAS Actuation Occurred.Caused by Fault on Startup Transformer Disconnect Switch.Disconnect Pole Assemblies on Disconnect Switch Replaced
| 10 CFR 50.73(a)(2) | | 05000530/LER-1992-002-02, :on 920722,RCS Leakage Monitor Declared Inoperable to Investigate Sampling Discrepancy.Inleakage Due to Cracked Gasket Was Periodically Diluting Gaseous Sample. Monitor Repaired & Returned to Svc |
- on 920722,RCS Leakage Monitor Declared Inoperable to Investigate Sampling Discrepancy.Inleakage Due to Cracked Gasket Was Periodically Diluting Gaseous Sample. Monitor Repaired & Returned to Svc
| 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)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2) | | 05000528/LER-1992-002, :on 920117,TS Action Missed W/Radiation Monitor Inoperable.Caused by Personnel Error.Containment Air Grab Sample Was Taken & Analyzed |
- on 920117,TS Action Missed W/Radiation Monitor Inoperable.Caused by Personnel Error.Containment Air Grab Sample Was Taken & Analyzed
| | | 05000529/LER-1992-002, :on 920323,Unit 2 Reactor Tripped & Train a LOP ESFAS Actuation Occurred & Train B LOP ESFAS Actuation Occurred in Unit 3.Reactor Trip Caused by Component Failure. Failed Component Replaced |
- on 920323,Unit 2 Reactor Tripped & Train a LOP ESFAS Actuation Occurred & Train B LOP ESFAS Actuation Occurred in Unit 3.Reactor Trip Caused by Component Failure. Failed Component Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2) | | 05000529/LER-1992-003-01, :on 920527,spurious Fuel Bldg Essential Ventilation Sys Actuation Occurred.Caused by age-related Degradation of Output Relay in Kaman Electronic Remote Indication & Control Unit |
- on 920527,spurious Fuel Bldg Essential Ventilation Sys Actuation Occurred.Caused by age-related Degradation of Output Relay in Kaman Electronic Remote Indication & Control Unit
| 10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(6) | | 05000530/LER-1992-004, Forwards LER 92-004-00 Re 921009 Invalid Control Room, Containment & Fuel Bldg Ventilation ESF Actuations.Addl Info Provided Re 921014 Event | Forwards LER 92-004-00 Re 921009 Invalid Control Room, Containment & Fuel Bldg Ventilation ESF Actuations.Addl Info Provided Re 921014 Event | | | 05000529/LER-1992-004-01, :on 920619,Train a Loss of Power ESFAS Actuated Due to Fault Downstream of Startup Transformer. Startup Transformer NAN-X01 Quarantined & Senior Plant Mgt Informed |
- on 920619,Train a Loss of Power ESFAS Actuated Due to Fault Downstream of Startup Transformer. Startup Transformer NAN-X01 Quarantined & Senior Plant Mgt Informed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2) | | 05000530/LER-1992-004-02, :on 921009,containment & Fuel Bldg Ventilation ESF Actuations Occurred Due to Personnel Error.Reactor Operator Disciplined |
- on 921009,containment & Fuel Bldg Ventilation ESF Actuations Occurred Due to Personnel Error.Reactor Operator Disciplined
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(x)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2) | | 05000530/LER-1992-005-02, :on 921023,determined That 11 of 20 Main Steam Safety Valve as-found Relief Setpoints Out of TS 3.7.1.1 Tolerance from 921010-23.Possibly Caused by Setpoint Drift. Valves Will Be Removed & Shipped to Offsite Facility |
- on 921023,determined That 11 of 20 Main Steam Safety Valve as-found Relief Setpoints Out of TS 3.7.1.1 Tolerance from 921010-23.Possibly Caused by Setpoint Drift. Valves Will Be Removed & Shipped to Offsite Facility
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2) | | 05000530/LER-1992-005-01, Forwards LER 92-005-01 Re Main Steam Safety Valve as-found Relief Settings Out of Tolerance Limits in TS 3.7.1.1.Suppl Updates Valve Testing Schedule in Section Iii.B & Provides Main Steam & Pressurizer Safety Valve Test Res | Forwards LER 92-005-01 Re Main Steam Safety Valve as-found Relief Settings Out of Tolerance Limits in TS 3.7.1.1.Suppl Updates Valve Testing Schedule in Section Iii.B & Provides Main Steam & Pressurizer Safety Valve Test Results | | | 05000529/LER-1992-005-01, Forwards LER 92-005-01 Re Failure to Perform ASME Code Class 2 Train B Charging Pump Testing within Max Allowable Surveillance Interval.Encl Discusses Root Cause Determination & Corrective Actions | Forwards LER 92-005-01 Re Failure to Perform ASME Code Class 2 Train B Charging Pump Testing within Max Allowable Surveillance Interval.Encl Discusses Root Cause Determination & Corrective Actions | | | 05000528/LER-1992-006, :on 920419,spurious Train a Containment Purge Isolation Actuation Sys Initiated on balance-of-plant Esfas. Caused by Radiation Monitor RU-37 Dropping Offline Due to Power Supply Failure.Power Supply Replaced |
- on 920419,spurious Train a Containment Purge Isolation Actuation Sys Initiated on balance-of-plant Esfas. Caused by Radiation Monitor RU-37 Dropping Offline Due to Power Supply Failure.Power Supply Replaced
| | | 05000528/LER-1992-008, :on 920508,discovered That Surveillance Requirement for Nonessential Auxiliary Feedwater Pump Not Performed.Caused by Personnel Error.Instruction Change Request Submitted |
- on 920508,discovered That Surveillance Requirement for Nonessential Auxiliary Feedwater Pump Not Performed.Caused by Personnel Error.Instruction Change Request Submitted
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2) | | 05000528/LER-1992-013, :on 920902,determined That Three Economizer Feedwater Isolation 4-way Valve Failures Probably Due to Mfg Defects.Caused by Improper Machining & Less than Acceptable Dedication Program.Also Reported Per Part 21 |
- on 920902,determined That Three Economizer Feedwater Isolation 4-way Valve Failures Probably Due to Mfg Defects.Caused by Improper Machining & Less than Acceptable Dedication Program.Also Reported Per Part 21
| 10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2) | | 05000528/LER-1992-014, :on 921008,discovered Operation in Excess of Licensed Condition for Thermal Power.Caused by Inaccurate Span Correction Factors.Operating Units Reduced Power to 99.5 Percent Power |
- on 921008,discovered Operation in Excess of Licensed Condition for Thermal Power.Caused by Inaccurate Span Correction Factors.Operating Units Reduced Power to 99.5 Percent Power
| 10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2) | | 05000528/LER-1992-016, :on 921208,reactor Tripped on High Pressurizer Pressure Due to Main Turbine Trip.Caused by Failure of Static Negative Sequence Time Over Current Relay.Faulty Relay Replaced W/Identical GE Relay |
- on 921208,reactor Tripped on High Pressurizer Pressure Due to Main Turbine Trip.Caused by Failure of Static Negative Sequence Time Over Current Relay.Faulty Relay Replaced W/Identical GE Relay
| 10 CFR 50.73(a)(2) |
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