LER-1992-005, 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 |
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ACCELERATED DOCUMENT DISTRIBUTION SYSTEM REGULRY" INFORMATION DISTRIBUT
'SYSTEM (RIDE)'CCESSION NBR:9305050206"I 'OL;"DA'0EX 93/b4'/24 -GRO'TARIZED:
NO DOCKET FACIL:STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH.NAME
=
AUTHOR AFZILIATION LEVINE,J.M.
Arizona Public Service Co.
(formerly--Arizona.-Nuclear Power RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards LER 92-005-01 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 s provides main steam
& pressurizer safety valve test results.
DISTRIBUTION CODE:
IE22T COPIES RECEIVED:LTR J ENCL I
SIZE:
H TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:Standardized plant.
05000530 l1
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1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONl I<OL DESK, ROOM Pl-37 (EXT. 504.2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
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. A.rizona.Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O. BOX 52034
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PHOENIX, ARIZONA85072-2034 JAMES M LEVINE VICE PREEXDENT NVCLEAR PRODUCT IDN 192-G0839-PHL/TRB/RR,
. A'pril 24,. 1993 U.
S. Nuclear Regulatory Commission Attention: Document Control Desk Mail Station Pl-37 Washington, D.C.
20555 P ~ i P%
j
Dear Sirs:
Subj ect:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 3 Docket No.
STN 50-530 (License No. NPF-74)
Licensee Event Report 92-005-01 File 93-020-404 Attached please find supplement 1.to Licensee Event Report (LER)92-005 prepared and submitted pursuant to 10CFR50.73.
The LER reports Main Steam Safety Valve as-found relief settings that were out of the tolerance limits specified in Technical Specification 3.7.1.1.
This supplement updates the valve testing schedule in Section III.B and provides the Main Steam and Pressurizer Safety Valve test results in Section V.
In accordance with 10CFR50.73(d),
a copy of this supplement is being forwarded to the Regional Administrator, NRC Region V.
If you have any questions, please contact T. R. Bradish, Nuclear Regulatory Affairs Manager, at (602) 393-5421.
Very truly yours, JML/TRB/RR/ap Attachment (all with attachment) 9305050206 930424 PDR ADOCK 05000530 S
PDR cc:
W. F.
Conway J
~ B. Martin J
~ A. Sloan INPO Records Center fp)P
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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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