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| | issue date = 08/11/1994 | | | issue date = 08/11/1994 |
| | title = Forwards Unit 2 SG IR from Last Mid Cycle Outage.Aps Stated That It Would Present,Within Four & One Half Months of Breaker Closure,Final Regulatory Guide 1.121 Evaluation Results of Pulled Tube Analyses & Statistical Treatment | | | title = Forwards Unit 2 SG IR from Last Mid Cycle Outage.Aps Stated That It Would Present,Within Four & One Half Months of Breaker Closure,Final Regulatory Guide 1.121 Evaluation Results of Pulled Tube Analyses & Statistical Treatment |
| | author name = STEWART W L | | | author name = Stewart W |
| | author affiliation = ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR | | | author affiliation = ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:L JRJLMH.JL JL'Y I t (ACCELERATED RIDS PROCESSING REGULATORY INFORMATXON DISTRXBUTION SYSTEM (RIDS)05000528 05000529 05000530 ACCESSXON NBR:9408230112 DOC.DATE: 94/08/11 NOTARIZED: | | {{#Wiki_filter:t L JRJLMH.JL JL'Y (ACCELERATED RIDS PROCESSING I |
| NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 P AUTH.NAME AUTHOR AFFILIATION STEWART,W.L. | | REGULATORY INFORMATXON DISTRXBUTION SYSTEM (RIDS) |
| Arizona Public Service Co.(formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATXON Document Control Branch (Document Control Desk)+I | | ACCESSXON NBR:9408230112 DOC.DATE: 94/08/11 NOTARIZED: NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 P AUTH. NAME AUTHOR AFFILIATION STEWART,W.L. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Forwards Unit 2 SG XR from last mid cycle outage.APS stated that it would present, within four 6 one half months of breaker closure, final regulatory guide 1.121 evaluation 0 results of pulled tube analyses 6 statistical treatment. | | |
| DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR J ENCL 1 SIZE: 4 104 TITLE: OR Submittal: | | RECIPIENT AFFILIATXON Document Control Branch (Document Control Desk) |
| General Distribution t NOTES:STANDARDIZED PLANT'tandardized plant.Standardized plant.RECIPIENT XD CODE/NAME PD4-2 LA HOLIAN, B INTERNAL: ACRS NRR/DORS/ONDD NRR/DRPW R/DSSA/SRXB OC REG FXL 01 EXTERNAL: NOAC COPIES LTTR ENCL 1 1 2 2 6 6 1 1 1 1 1 1 1 0 1 1 1 1 RECIPIENT ID CODE/NAME PD4-2 PD TRAN,L NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS2 NRC PDR'OPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 0 1 1 D 0 C U N NOTE TO ALL"RIDS" RECIPIENTS:
| | Forwards Unit 2 SG XR from last mid cycle outage.APS stated |
| PLEASE HELP US TO REDUCE iVASTE!CONTACTTHE DOCUMENTCONTROL DESK, ROOM P!-37 (EXT.504-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS I:OR DOCUMENTS You DON T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 22 | | + I that it would present, within four 6 one half months of breaker closure, final regulatory guide 1.121 evaluation 0 results of pulled tube analyses 6 statistical treatment. |
| ~,>Tg C 4/L J r,~pre tb~0" 4 Arizona Public Service Company P.O.BOX 53999~PHOENIX, ARIZONA 85012<999 WILLIAM L.STEWART EXECUTIVEVICEPRESIDENT NUCLEAR 102-03083-WLS/AKK/JRP August 11, 1994 U.S.Nuclear Regulatory Commission | | DISTRIBUTION CODE: AOOID TITLE: OR Submittal: General Distribution COPIES RECEIVED:LTR J ENCL 1 SIZE: 4 104 t |
| .'ATTN: Document Control Desk Mail Station P1-37 Washington, D.C.20555 | | NOTES:STANDARDIZED 05000528 plant. |
| | PLANT'tandardized 05000529 Standardized plant. 05000530 RECIPIENT COPIES RECIPIENT XD CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA 1 1 PD4-2 PD 1 1 HOLIAN, B 2 2 TRAN,L 2 2 INTERNAL: ACRS NRR/DORS/ONDD 6 |
| | 1 6 |
| | 1 PDR'OPIES NRR/DE/EELB NRR/DRCH/HICB 1 |
| | 1 1 |
| | 1 NRR/DRPW 1 1 NRR/DSSA/SPLB 1 1 D R/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OC REG FXL 01 1 |
| | 1 0 |
| | 1 OGC/HDS2 1 0 0 EXTERNAL: NOAC 1 1 NRC 1 1 C U |
| | N NOTE TO ALL"RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE iVASTE! CONTACTTHE DOCUMENTCONTROL DESK, ROOM P! -37 (EXT. 504-2083 ) TO ELIMINATEYOUR NAME FROM DISTRIBUTIONLISTS I:OR DOCUMENTS You DON T NEED! |
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 22 |
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| | Arizona Public Service Company P.O. BOX 53999 ~ PHOENIX, ARIZONA85012<999 WILLIAML. STEWART EXECUTIVEVICEPRESIDENT 102-03083-WLS/AKK/JRP NUCLEAR August 11, 1994 U. S. Nuclear Regulatory Commission |
| | .'ATTN: Document Control Desk Mail Station P1-37 Washington, D.C. 20555 |
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| ==Reference:== | | ==Reference:== |
| | | 'etter'No. 102-02852, dated March 8, 1994, from W..F. Conway, Executive Vice President, Nuclear, APS, to USNRC. |
| 'etter'No. | |
| 102-02852, dated March 8, 1994, from W..F.Conway, Executive Vice President, Nuclear, APS, to USNRC. | |
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| ==Dear Sirs:== | | ==Dear Sirs:== |
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| ==Subject:== | | ==Subject:== |
| "Palo.Verde Nuclear Generating Station (PVNGS)Units 1, 2 and 3..Docket No.STN 50-528, 50-529, 50-530 Status of PVNGS Steam Generator Activities File: 94-056-026 The referenced letter transmitted the Unit 2 Steam Generator inspection Report from the last mid-cycle outage.In that letter, Arizona Public Service Company (APS)stated that it would present, within four and one half months of breaker closure, a final Regulatory
| | "Palo. Verde Nuclear Generating Station (PVNGS) |
| -Guide 1;121'valuation, results of the pulled tube analyses, and a statistical treatment of uncertainties.
| | Units 1, 2 and 3 |
| The enclosed report provides 1)the results of Units 2 and 3 metallurgical tube examinations, 2)results of probabilistic Regulatory Guide 1.121 assessments for Units 1 and 2, and 3)details of the PVNGS integrated outage assessment program.Should you have any questions, please contact Scott A.Bauer at (602)393-5978.WLS/AKK/JRP/dpr | | .. Docket No.STN 50-528, 50-529, 50-530 Status of PVNGS Steam Generator Activities File: 94-056-026 The referenced letter transmitted the Unit 2 Steam Generator inspection Report from the last mid-cycle outage. In that letter, Arizona Public Service Company (APS) stated that it would present, within four and one half months of breaker closure, a final Regulatory Guide 1;121'valuation, results of the pulled tube analyses, and a statistical treatment of uncertainties. |
| | The enclosed report provides 1) the results of Units 2 and 3 metallurgical tube examinations, 2) results of probabilistic Regulatory Guide 1.121 assessments for Units 1 and 2, and 3) details of the PVNGS integrated outage assessment program. |
| | Should you have any questions, please contact Scott A. Bauer at (602) 393-5978. |
| | WLS/AKK/JRP/dpr |
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| ==Enclosure:== | | ==Enclosure:== |
| | Status of PVNGS Steam Generator Activities CC: L. J. Callan K. E. Perkins K. E. Johnston B. E. Holian I; Barnes lI408i 1 9'408230112 "05000528 PDR ADQCK PDR P |
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| Status of PVNGS Steam Generator Activities CC: L.J.Callan K.E.Perkins K.E.Johnston B.E.Holian I;Barnes 9'408230112 lI408i 1 PDR ADQCK"05000528 P PDR
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML17300B3071999-03-31031 March 1999
Seismic Portion of Submittal-Only Screening Review of Palo Verde Nuclear Generating Station Units Ipeee.
ML17312A7631996-05-0808 May 1996
Calculation Summary of Radiological Doses for SG Tube Rupture W/Loss of Offsite Power & Stuck Open Adv.
ML20117J0491996-05-0808 May 1996
At&T Round Cell Nuclear Util User'S Council Charter
ML20113E1631996-05-0808 May 1996
PVNGS Unit 3 SG Eddy Current Exam Fifth Refueling Outage Nov 1995
ML17311A2031994-08-11011 August 1994
Forwards Unit 2 SG IR from Last Mid Cycle Outage.Aps Stated That It Would Present,Within Four & One Half Months of Breaker Closure,Final Regulatory Guide 1.121 Evaluation Results of Pulled Tube Analyses & Statistical Treatment
ML20062M5111993-12-31031 December 1993
1993 Certification Submittal Simulation Facility Simulator Training Suite a
ML20058N7161993-09-21021 September 1993
Independent Safety & Quality Engineering GL-89-01 Motor Operated Valve Programmatic Assessment
ML17306A9361992-08-20020 August 1992
Rev 1 to JCO-91-02-01, Justification for Continued Operation Steam Generator Tube Rupture Analysis Concerns.
ML17305B3381991-01-18018 January 1991
Justification for Continued Operation - Potential for Small Break Loss of Coolant Accident Due to Tube Rupture in Reactor Coolant Pump Seal Cooler.
ML17305A9811990-07-31031 July 1990
Conceptual Design for Palo Verde Nuclear Generator Station for Diverse Auxiliary Feedwater Actuation Sys (Dafas).
ML17305A3351989-10-20020 October 1989
Rev 3 to Justification for Continued Operation Control Element Assembly (CEA) Drop Events.
ML17305A3211989-10-0505 October 1989
Procedure 43OP-3ZZ16,RCS Drain Operations,Not Appropriate for Circumstances.
ML17305A3401989-07-18018 July 1989
Unit 3 Steam Generator Eddy Current Exam,First Refueling Outage Apr 1989, NDE Summary Rept
ML17304B2941989-06-0909 June 1989
Justification for Continued Operation,Control Element Assembly Drop Events.
ML17304B2321989-06-0101 June 1989
Essential & Emergency Lighting Sys Rept.
ML17304B2151989-05-22022 May 1989
Revised Electrical Distribution Sys Design Assessment.
ML17304B2141989-05-19019 May 1989
Unit 3 Reactor Trip Following Large Load Reject.
ML20244B0961989-05-0808 May 1989
Rev 0 to Compressed Gas Sys Evaluation & Analysis for Palo Verde Units 1,2 & 3
ML20247L6921989-05-0808 May 1989
Electrical Distribution Sys Design Assessment
ML20247L6851989-05-0808 May 1989
Compressed Gas Sys Evaluation & Analysis Rept
ML17304B2051989-05-0606 May 1989
Steam Bypass Control Sys Overall Final Rept.
ML20247L7271989-04-30030 April 1989
Atmospheric Dump Valve Engineering Analysis
ML17304B0121989-01-31031 January 1989
Final Rept on Pressure-Temp Limits for Palo Verde Nuclear Generating Stations.
ML17304A7551988-11-0707 November 1988
Analysis of Equipment Functionality W/Essential Chiller Sys Inoperable.
ML20082D9761988-10-30030 October 1988
EE580 Field Verification Suppl to Final Rept Ref NRC Allegation RV-87-A-047 for Palo Verde Nuclear Generating Station,Oct 1988
ML17304A7601988-10-13013 October 1988
Loss of Qualified Life & Functionality of Electrical Equipment Due to Loss of Essential Cooling Sys in Unit 1.
ML17304A2211988-06-0909 June 1988
Justification for Continued Operation of Auxiliary Feedwater Pumps.
ML20082D9991988-05-30030 May 1988
EE580 Field Verification Final Rept Ref NRC Allegation RV-87-A-047
ML17303A8871988-02-16016 February 1988
Special Plant Event Evaluation Rept 87-02-019 & Mods to Valves Sga Uv 134 & Sga Uv 138 Render 2AFA-P01 on 871127
ML17303A6291987-09-24024 September 1987
Arizona Nuclear Power Project Metallurgical Investigation Rept,Palo Verde Nuclear Generating Station Emergency Diesel Generator 3B Number 9L Piston Pin.
ML17303A4541987-06-0404 June 1987
Unit 1 Steam Generator Eddy Current Exam,Feb 1987, NDE Summary Rept
ML17303A3571987-03-12012 March 1987
Torsional Vibration Analysis KSV-20-T SN-7183-88 SO-0391.
ML17303A3071987-02-28028 February 1987
Rev 0 to Rept on Steam Generator Tube Leak at Unit 1.
ML20215G2981987-02-24024 February 1987
Technical Evaluation Rept for SPDS for Palo Verde Nuclear Generating Station Units 1,2 & 3
ML17300A8211987-02-0606 February 1987
Torsional Vibration Analysis of Repaired Crankshaft, KSV-20-T & SN-7187.
ML17303A3551987-02-0606 February 1987
Torsional Vibration Analysis of Repaired Crankshaft KSV-20-T SN-7187 Arizona Public Svc Co,Palo Verde Nuclear Generating Station Diesel Generator III-B.
ML17303A2421987-01-22022 January 1987
Rev 0 to 10CFR50,App R Safe Shutdown Evaluation.Outside Control Room Fire Spurious Actuation Study for Palo Verde Nuclear Generating Station Unit 3.
ML17303A2331987-01-21021 January 1987
Loose Part Monitoring Sys,Loose Part Detection Program Rept.
ML17300A6181986-10-31031 October 1986
Description of Proposed Enhancements to Palo Verde Nuclear Generating Station Control Bldg Elevation 74-Ft 0-Inches Masonry Walls for Units 1,2 & 3.
ML17300A5861986-09-30030 September 1986
Evaluation of Block Masonry Walls at Palo Verde Nuclear Generating Station, Technical Rept
ML17300A5301986-09-18018 September 1986
Factors Influencing Deflections in Grouted Hollow Unit Concrete Masonry Walls.
ML20212A7011986-07-31031 July 1986
Comprehensive Vibration Assessment Program for Palo Verde Nuclear Generating Station Unit 2 (Sys 80 Nonprototype - Category 1),Evaluation of Precore Hot Functional Insp Program, Final Rept
ML17303A3141986-07-29029 July 1986
Suppl to 860610 Application Re Sale & Leaseback Transactions by Public Svc Co of New Mexico
ML20215E9291986-05-23023 May 1986
Observations & Comments,Initial Reactor Startup & Low Power Reactor Physics Tests,Palo Verde Nuclear Generating Station, Unit 2,NRC Region V Insp
ML17299A5771985-08-30030 August 1985
Rev 0 to 10CFR50,App R Safe Shutdown Evaluation,Outside Control Room Fire Spurious Actuation Study.
ML20137A6691985-06-21021 June 1985
Observations & Comments,Initial Reactor Startup & Low Power Reactor Physics Tests,Palo Verde Nuclear Generating Station,Unit 1,NRC Region V Enhanced Insp
ML20116N4701985-04-30030 April 1985
Refueling Cavity Water Seal, Summary Rept in Response to IE Bulletin 84-03
ML17298B9321985-02-28028 February 1985
SPDS Sar.
ML20107H5181984-12-31031 December 1984
Assessment of Bolting Integrity at Palo Verde Nuclear Generating Station Units 1,2 & 3
ML17298B6851984-12-17017 December 1984
Bechtel Study 13-ES-600, Reg Guide 1.75 Low Energy Circuit Analysis.
1999-03-31
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17300B3811999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Pvngs,Units 1,2 & 3.With 991007 Ltr
ML17300B3271999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Pvngs,Units 1,2 & 3
ML17313B0751999-08-27027 August 1999
LER 99-002-00:on 990730,test Mode Trip Bypass for EDG Output Breakers Not Surveilled.Cause Under Investigation.Operations Personnel Conservatively Invoked SR 3.0.3 for SR 3.8.1.13. with 990827 Ltr
ML17313B0611999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Pvngs,Units 1,2 & 3.With 990810 Ltr
ML17313B0191999-07-16016 July 1999
LER 99-005-00:on 990618,RT on Low DNBR Was Noted.Caused by Hardware Induced Calculation Error.Cr Operator Was Taken to Place Reactor in Stable Condition IAW Appropriate Operating Procedure
ML17300B3151999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Pvngs,Units 1,2 & 3.With 990714 Ltr
ML17313A9921999-06-21021 June 1999
Special Rept:On 990525,RMS mini-computer Was Removed from Service to Implement Yr 2000 Mod & Was OOS Longer than 72 H Allowed.Caused by Planned Y2K Mods.Preplanned Alternate Sampling Program Was Initiated
ML17313A9911999-06-18018 June 1999
Special Rept:On 990510,loose-part Detection Sys Channel 2 Was Declared Inoperable.Caused by Malfunction of Mineral Cable Connector to Accelerometer.Licensee Will Implement Modifications Which Will Enhance loose-part Detection Sys
ML17313A9731999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Pvngs,Units 1,2 & 3.With 990608 Ltr
ML17313A9281999-05-0707 May 1999
LER 99-004-00:on 990408,PSV Lift Pressures Were Outside of TS Limits.Caused by Lift Pressure Setpoint Drift.Psvs Have Been Tested,Disassembled,Inspected,Reassembled & Certified at Wyle Labs
ML17313A9201999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Pvngs,Units 1,2 & 3.With 990512 Ltr
ML17313A8951999-04-14014 April 1999
LER 99-003-00:on 990317,required Surveillance Requirement Not Completed Due to Deficient Procedure,Was Determined. Caused by Cognitive Personnel Error.St Procedures Revised to Require Chiller to Be Operating & Oil Temperature Checked
ML17313A8921999-04-13013 April 1999
LER 98-003-01:on 980902,discovered That MSSV as-found Lift Pressures Were Outside TS Limits.Caused by Bonding of Valve Disc to Nozzle Seat.Affected Valves Were Adjusted,Retested & Returned to Svc
ML17313A8891999-04-0909 April 1999
LER 99-001-00:on 990310,RT on High Pressurizer Pressure Was Noted.Caused by Loss of Heat Removal.Cr Supervisor Was Removed from Shift Duties for Diagnostics Skills Training. with 990409 Ltr
ML17300B3071999-03-31031 March 1999
Seismic Portion of Submittal-Only Screening Review of Palo Verde Nuclear Generating Station Units Ipeee.
ML17313A8801999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Pvngs,Units 1,2 & 3.With 990412 Ltr
ML20207M9231999-03-12012 March 1999
Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results
ML20207H7471999-03-10010 March 1999
1999 Emergency Preparedness Exercise 99-E-AEV-03003
ML17313A8361999-03-0101 March 1999
LER 99-001-00:on 990103,TS Violation for Power Dependent Insertion Limit Alarm Being Inoperable.Caused by Personnel Error.Revised Procedure to Clarify How Computer Point Is to Be Returned to Scan Mode.With 990302 Ltr
ML17313A8501999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Palo Verde Nuclear Generating Station.With 990311 Ltr
ML17313A7791999-02-0505 February 1999
Safety Evaluation Accepting Licensee Rev to Emergency Plan That Would Result in Two Less Radiation Protection Positions Immediatelu Available During Emergencies
ML17313A8061999-01-31031 January 1999
Monthly Operating Repts for Jan 1999 for Pvngs,Units 1,2 & 3.With 990218 Ltr
ML17313A7701999-01-15015 January 1999
LER 96-008-00:on 960507,inadequate Procedure Results in Nuclear Power Channels Not Calibrated During Power Ascension Tests Occurred.Caused by Deficient Procedure.Procedure Revised
ML17313A7381998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.With 990113 Ltr
ML20206H2101998-12-31031 December 1998
SCE 1998 Annual Rept
ML17313A7031998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Pvngs,Unit 1,2 & 3. with 981209 Ltr
ML17313A6701998-11-0404 November 1998
Rev 2 to PVNGS Unit 2 Colr.
ML17313A6741998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Pvngs,Units 1,2 & 3.With 981109 Ltr
ML17313A6611998-10-24024 October 1998
LER 98-008-00:on 980729,EQ of Electrical Connectors Were Not Adequately Demonstrated.Caused Because Test Was Conducted with Only Single Lv Connector & Without Fully Ranged Inputs. Revised EQ Requirements
ML17313A6561998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for PVNGS Units 1,2 & 3.With 981007 Ltr
ML17313A5961998-09-14014 September 1998
LER 98-002-00:on 980814,B Train H Recombiner Was Noted Inoperable Due to cross-wired Power Receptacle.Cause of Event Is Under investigation.Cross-wired Power Supply Receptacle for B Train H Recombiner Was re-wired
ML17313A5761998-09-0808 September 1998
LER 98-003-01:on 980113,discovered That One Channel of RWT Level Sys Had Failed High.Caused by Water Intrusion Into Electrical Termination Pull Box.Weep Holes Were Drilled Into Bottoms of Pull Boxes Nearest Level Transmitters
ML17313A5591998-08-28028 August 1998
LER 98-001-00:on 980730,entered TS 3.0.3 Due to Safety Injection Flow Instruments Being Removed from Svc.Caused by Personnel Error.Transmitters Were Unisolated & Returned to svc.W/980828 Ltr
ML20151S0941998-08-21021 August 1998
Rev 6 to COLR for PVNGS Unit 3
ML20151S0861998-08-21021 August 1998
Rev 4 to COLR for PVNGS Unit 1
ML20151S0901998-08-21021 August 1998
Rev 1 to COLR for PVNGS Unit 2
ML18066A2771998-08-13013 August 1998
Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency
ML17313A5401998-08-13013 August 1998
Special Rept:On 980715,declared PASS Inoperable.Caused by Failure of Offgas Flush/Purge Control Handswitch HS0101. Handswitch Replaced & Post Maintenance Retesting Was Initiated
ML17313A5301998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Pvgns,Units 1,2 & 3.W/980812 Ltr
ML17313A5201998-07-30030 July 1998
LER 98-004-00:on 980630,personnel Discovered That Pressure Safety Valve Had Not Received Periodic Set Pressure Test for ASME Class 1 Pressure Safety Valve.Caused by Personnel Error.Pressure Safety Valve reviewed.W/980730 Ltr
ML17313A5791998-07-0707 July 1998
to PVNGS SG Tube ISI Results for Seventh Refueling Outage Mar & Apr 1998.
ML17313A5001998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.W/980710 Ltr
ML17313A4671998-06-19019 June 1998
LER 98-007-00:on 980520,CR Personnel Observed Flow & Pressure Perturbations on Chemical & Vol Control Sys Letdown Sys.Caused by Cyclic Fatigue Due to Dynamic Pressure Transients.Unit Letdown Piping Replaced
ML17313A4521998-06-19019 June 1998
Rev 5 to COLR for Pvngs,Unit 3.
ML17313A4501998-06-19019 June 1998
Rev 4 to COLR for Pvngs,Unit 3.
ML17313A4131998-06-0505 June 1998
LER 98-006-00:on 980507,determined That Plant Was Outside Design Basis Due to SI Discharge Check Valve Reverse Flow. Check Valve Was Disassembled,Examined & Reassembled, Whereupon Valve Met Acceptance Criteria
ML17313A4211998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Pvngs,Units 1,2 & 3.W/980609 Ltr
ML17313A3951998-05-26026 May 1998
LER 98-005-00:on 980428,noted That Required Response Time Testing Had Not Been Performed.Caused by Personnel Error. Coached I&C Personnel Responsible for Reviewing Work Authorization Documentation
ML17313A3691998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for PVNGS.W/980412 Ltr
ML17313A3251998-04-0101 April 1998
LER 98-004-00:on 980304,safety Valves as-found Pressures Out of Tolerance.Cause of Event Is Under Investigation.Three Mssv'S & Psv Will Be Replaced W/Refurbished & Recertified Valves During Refueling Outage U1R7
1999-09-30
[Table view] |
Text
t L JRJLMH.JL JL'Y (ACCELERATED RIDS PROCESSING I
REGULATORY INFORMATXON DISTRXBUTION SYSTEM (RIDS)
ACCESSXON NBR:9408230112 DOC.DATE: 94/08/11 NOTARIZED: NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 P AUTH. NAME AUTHOR AFFILIATION STEWART,W.L. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME
SUBJECT:
RECIPIENT AFFILIATXON Document Control Branch (Document Control Desk)
Forwards Unit 2 SG XR from last mid cycle outage.APS stated
+ I that it would present, within four 6 one half months of breaker closure, final regulatory guide 1.121 evaluation 0 results of pulled tube analyses 6 statistical treatment.
DISTRIBUTION CODE: AOOID TITLE: OR Submittal: General Distribution COPIES RECEIVED:LTR J ENCL 1 SIZE: 4 104 t
NOTES:STANDARDIZED 05000528 plant.
PLANT'tandardized 05000529 Standardized plant. 05000530 RECIPIENT COPIES RECIPIENT XD CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA 1 1 PD4-2 PD 1 1 HOLIAN, B 2 2 TRAN,L 2 2 INTERNAL: ACRS NRR/DORS/ONDD 6
1 6
1 PDR'OPIES NRR/DE/EELB NRR/DRCH/HICB 1
1 1
1 NRR/DRPW 1 1 NRR/DSSA/SPLB 1 1 D R/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OC REG FXL 01 1
1 0
1 OGC/HDS2 1 0 0 EXTERNAL: NOAC 1 1 NRC 1 1 C U
N NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE iVASTE! CONTACTTHE DOCUMENTCONTROL DESK, ROOM P! -37 (EXT. 504-2083 ) TO ELIMINATEYOUR NAME FROM DISTRIBUTIONLISTS I:OR DOCUMENTS You DON T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 22
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Arizona Public Service Company P.O. BOX 53999 ~ PHOENIX, ARIZONA85012<999 WILLIAML. STEWART EXECUTIVEVICEPRESIDENT 102-03083-WLS/AKK/JRP NUCLEAR August 11, 1994 U. S. Nuclear Regulatory Commission
.'ATTN: Document Control Desk Mail Station P1-37 Washington, D.C. 20555
Reference:
'etter'No. 102-02852, dated March 8, 1994, from W..F. Conway, Executive Vice President, Nuclear, APS, to USNRC.
Dear Sirs:
Subject:
"Palo. Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3
.. Docket No.STN 50-528, 50-529, 50-530 Status of PVNGS Steam Generator Activities File: 94-056-026 The referenced letter transmitted the Unit 2 Steam Generator inspection Report from the last mid-cycle outage. In that letter, Arizona Public Service Company (APS) stated that it would present, within four and one half months of breaker closure, a final Regulatory Guide 1;121'valuation, results of the pulled tube analyses, and a statistical treatment of uncertainties.
The enclosed report provides 1) the results of Units 2 and 3 metallurgical tube examinations, 2) results of probabilistic Regulatory Guide 1.121 assessments for Units 1 and 2, and 3) details of the PVNGS integrated outage assessment program.
Should you have any questions, please contact Scott A. Bauer at (602) 393-5978.
WLS/AKK/JRP/dpr
Enclosure:
Status of PVNGS Steam Generator Activities CC: L. J. Callan K. E. Perkins K. E. Johnston B. E. Holian I; Barnes lI408i 1 9'408230112 "05000528 PDR ADQCK PDR P
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