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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
PALO VERDE NUCLEAR GENERATING STATION UNIT 3 STEAM GENERATOR EDDY CURRENT EXAMINATION 1ST REFUELING OUTAGE APRIL 1989 I
ARIZONA NUCLEAR POWER PROJECT P. 0. BOX 52034 PHOENIX, AZ 85072 PREPARED BY: DATE:
REVIEWED BY: DATE:
APPROVED BY: DATE:
COMMERCIAL SERVICE DATE: 1/8/88 REPORT DATE: 7/11/89
INDEX 1.0 Summary 2.0 Examination Results 3.0 Examination Techniques and Equipment APPENDIX A CE Steam Generator Support Reference Drawing APPENDIX B Summary Data Sheets APPENDIX C Tubesheet Maps APPENDIX D Form NIS-1
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The group B as well as two adjacent tubes, (R51, L06 and R52, L07), produced signals indicative of secondary side possible loose parts (PLP). In addition, leakage was visually observed at the Groups A and C tubesheet areas by use of a remote camera installed in each S/G primary channel-head.
A secondary side visual examination for the tubing in Groups B and C was performed utilizing a fiberoptic technique, with accessibility being pro-vided by cutting a window in adjacent tubes via an electron discharge machining (EDM) operation performed by Combustion Engineering. The visual examination confirmed the eddy current results for Groups B and C, and the final disposition of the secondary side loose part issue was addressed in Engineering Evaluation Request //89-RC-051. All tubing associated with Groups A, B, or C were preventatively staked and/or plugged as necessary.
The remaining indications consisted of a small number of tubes exhibiting
( 20X thru-wall signals at various locations. Some minor denting was also evident on several tubes. The majority of these indications were identified during the baseline examination and no significant changes were observed.
Sludge profiling was performed during the examination and found to be mini-mal. Less than 1.0X of the tubing exhibited sludge indications at the top of the tubesheet with the average depth being less than 1.0 inch.
The examination resulted in plugging an additional 7 (seven) tubes in steam generator 31 and 10 (ten) tubes in steam generator 32. Combustion Engineering welded type plugs were used for all tube ends and Engineering Evaluation Requests numbers 89-RC-058 and 89-RC-059 were initiated to track the examination results and subsequent plugging. The tube sheet maps in Appendix C show the total tubes plugged in each steam generator to date.
Appendix B contains the summary data sheets which list all tubes in each steam generator with thru-wall indications from 0-100X and possible loose parts (PLP). The NIS-1 form in Appendix D lists each of the tubes, by row and line, plugged as a result of this examination.
3.0 Examination Techniques and Equipment The eddy current examination was performed by Conam Inspection using Zetec MIZ-18 digital data acquisition and analysis systems. The following fre-quencies were used for the tube examination(s):
550 KHZ NOTE: All frequencies were utilized in both 990 KHZ differential and absolute modes.
100 KHZ 20 KHZ All tubing was tested with standard Zetec manufactured SFM/HF probes.
A rotating pancake probe was used to characterize the indications at various locations. Data acquisition was facilitated by using Zetec SM-10 "no entry" probe positioning fixtures in both hot and cold leg S/G plenums.
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APPENDIX A
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Appendix A CE SYSTEM 80 STEAM GENERATOR TUBE SUPPORT DIAGRAM YS1 2 3 0 5 6 7 BM1 09H 09C
$ 5II 08H 08C 05" 07H 07C I 1" 06C 06H
$ 2I
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$ 3tl d3" 02C 02H 15.5" 32.5" 01H 01C TUBESHEET 23.5" INLET OUTLET SUPPORT SPACINGS ARE IDENTIFIED IN INCHES BETWEEN THE SUPPORT IDENTIFICATION Page 1 oE 1
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APPENDIX B P ry
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Appendix B ROW: Indicates the row number of a given tube.
LIN: Indicates the column number of a given tube.
LEG: Indicates the tube leg from which examination was performed; either the hot (H) leg or cold (C) leg.
EXTIST RE}: Indicates the tube length required to be examined, i.e., F/L full length, 07H-seventh support on hot leg side.
EXTlXZ TST: Indicates the tube length actually examined.
REM Remarks column used for comments relating to examination.
RPI: indicates a plugging limit criteria REEL Indicates reel number'ata was recorded on.
PROBE: Indicates probe diameter and style used for examination.
LOCATION: Gives=indication location relative to known landmarks such as supports and batwings. Location codes are as follows:
¹1 Vertical Support Strap..............VSl
¹1 Bat Wing............................BW1
¹1 Support Plate in Hot. Leg............01H
¹7 Support Plate in Cold Leg...........07C Top Tube Sheet Hot Leg.................TSH Top Tube Sheet Cold Leg................TSC Tube End Hot Leg.......................TEH Tube End Cold Leg......................TEC VOLTS: Indicates the peak-to-peak voltage of a given indication response.
DEG: The measured phase angle of a given indication response.
The percent through the tube wall of a given indication based on the measured phase angle/amplitude and the calibration curve established for that particular channel, or analysis comment codes, e.g., PLP = Possible Loose Parts, etc.
CH: Indicates the channel used to measure and evaluate a given indication.
Page 1 of 3
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Appendix B CUNJLATIVE REPORT 03/89,'ARIZONA PUBLIC SERVICE CO.,'ALO VERDE, UNIT 3-L STEAM GENERATOR: 31 PAGE: 1 OF 1 LOCAT ION: ALL DATE: 07/02/89 CRITERIA: OX TO 100X, PLP TIME: 09: 57: 21 EXAM EXTENT CURRENT
) RCM (LIN(HEAT5(LEG)PROGRAM) ACTUAL/REM)REEL(PROBE) LOCATION ) VOLTS(MIL)DEG) X (CH)
I I I I I I I I I I I I I I I 67)-10) C )
01C-02C ) 01C-02C) RPI ( 188) 620ZR) 01C+ 1.31 04) ) 90) 51) 1(
I I I C )TEC-TEH(TEC-TEH( ) 027(610SL(01C+ 1. 1 1. 1) ) 122) 44 1)
)
- 66) 11) C )01C-02C)01C-02C) RPI I 188(620ZR(01C+ 1. 09 43) ) 42) 78) 1)
I I I C )TEC-TEH(TEC-TEH) I 027(610SL)01C+ 1. 0 9.2( I 78( 77( 1)
Wl 6&) 11( C (TEC-TEH(TEC-TEH( I 027(610SL(01C+ 0. 8 0.7( (110( 37(M1(
I I I C )01C-02C(01C-02C) RPI ( 18&(620ZR) 01C+ 0.71 0.3) ( 77( 57) 1)
~
(144( 591 H )TEH-TEC)TEH-TEC) 1401610SMI VS5- 0. 8 0.8) ( 0) 20)M2)'.
- 28) 73( ) C )TEC-TEH)TEC-TEH) 068) 610SM) 01C+ 0. 7 1( ) 164( <20(M4(
~ "(154( 83) ) H )TEH-TEC)TEH-TEC) 159) 610SM) VS1+ 0. 9 0.5) 0) <20)M2)
I I I ) H )TEH-TEC)TEH-TEC) 159)610SM)VS5+ 0.9 1.9) 0) 32)M2)"
)1591 88( ( H )TEH-TEC)TEH-TEC) 165) 610SM) VS3+ 0. 9 2.7) 0) 39)M2)
)153)100) ) H )TEH-TEC)TEH-TEC) 120)610SMI VS3+ 0. 9 1.3). 0) 28)M2)
- 86) 133) ) C )TEC-TEH(TEC-TEH) 146) 610SM) VS3+ 0. 5 2.2( OI 37(M2(
42)163) ) H )TEH-TEC)TEH-TEC) 052)600SM)02H+ 0.4 0 .6) )129) 21)M1(
I I I I I I I I I I I I M+GER OF TU3ES SELECTED FROM CURRENT OUTAGE: 10 NO TREND ANALYSIS RE(JESTED COhQM, INSPECTION Page 2 of 3
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Appendix B
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CUi%LAT'IVE REPORT 03/&9, ARIZONA PUBLIC SERVICE CO., PALO VERDE, UNIT 3 STREAM GENERATOR: 32 PAGE: 1 OF 1 LOCATION: ALL DATE: 07/02/89 CRITERIA: OX TO 100Ã,PLP TINE: 10: 10: 19 EXAM EXTENT 'CURRENT
) RCM) LIN(HEATS(LEG)PROGRAM) ACTUAL)REM) REEL) PRCGE) LOCATION )VOLTS)MIL)DEG) X )CH)
I I I I I I I I I I I I
- 47) 6) C )TEC-TEH)TEC-TEH) 004 ( 6 10SL ) VS4- 0.8 0. 6) 0)<20)N2)
I I C ) TEC-TEH(TEC-TEH) 004) 610SL) VS4+ 0.8 0.9) 0(<20(N2(
- 49) 6) C )01C-02C)01C-02C(RPI) 192)620ZR)01C+ 0.59TO+ 1.61) 10.4) 0)PLP) S(
C )TEC-TEH)TEC-TEH) 004) 610SL) 01C+ 1 3 0.7) (133) 3S) 1)
C )01C-02C)01C-02C) 192)620ZR)01C+ 1. 27 0.3( )112) 32 ) 1 )
C (TEC-TEH) TEC-TEH) 004) 610SL) 01C+ 1.2 0. 1) )2S9)PLP)08)
~
I 51 I 61 C )01C-02C)01C-02C)RPI) 192)620ZR)01C+ 0.60TO+ 1.58) 2.1) 0)PLP( 5)
I I I C )TEC-TEH)TEC-TEH) 004 (610SL) 01C+ 0.9 TCH. 0.0 ) 3.7) (288)PLP)08) 6( 50) 7) C )01C-02C)01C-02CIRPI) 192)620ZR)01C+ 0. 73TO+ 1.851 3. 01 0(PLP) 5(
) C )TEC-TEH)TEC-TEH) 005) 610SL ( 01C+ 1.6 I )PLP) 8)
C )TEC-TEH)TEC-TEH) 0051610SL I 01C+ 1.5 1.21 )140) 28) 1)
C )
01C-02C )
01C-02C( 192) 620ZR) 01C+ 1. 12 0.3 ) 113) 31) 1)
- 52) 7) I C 101C-02C 101C-02C I RPI I 1921620ZR I 01C+ 1. 17TCH. 2.001 0.9 I 0 IPLP I 51 I I C (TEC-TEH)TEC-TEH) 005) 610SL) 01C+ 1.9 TO+ 0.0 I (PLPI &I 43( 18( ) C )TEC-TEH)TEC-TEH) 008) 610SL ) 01C+ 0.3 0.61 ) 128) <20 (Nl )
- 2) 25( C ) TEC-TEH) TEC-TEH) 003(590SMI02C- 0.5 0.61 0( <20)N2) 851 461 C )TEC-TEH)TEC-TEH) 033) 610SL(VSS+ 0.8 0. 7) 0)<20)N2)
- 99) 52) C ) TEC-TEH) TEC-TEH( 035) 610SL) VS2- 0.5 0.6) OI<20IN21 75 ) 70) C )TEC-TEH)TEC-TEH) 0631600SMI07C- 0.6 0.&I ) 144 ) <20 ) Nl )
- 74) 85) C )TEC-TEH)TEC-TEH) 081) 600SN(BW1+ 10. 7 1. 21 ) 152) <20)N4)
-(159 ) 96) H )TEH-TEC(TEH-TEC) 117) 610SM) VS1+ 0.0 0. 7) 0) 21)N2) 36(103) H (TEH-TEC)TEH-TEC) 166) 610SM) VS4- 0.6 0.6) 0) 20)M2) 99)106( H )TEH-TEC)TEH-TEC) 162)610SN)VS2+ 11.9 1.1) ) 126( 39 ( 1)
)150)127) H )TEH-TEC(TEH-TEC( 091) 610SN) VSS+ 1.7 0. 7) ) 133) 32) 1) 76)143( H (TEH-TEC)TEH-TEC) 078 ) 610SM(BW2+ 0.9 1. 7) ) 180 ) <20 )
Nl )
- ) 100 ) 151) H (TEH-TEC(TEH-TEC) 069) 610SL) VS2+ 2.8 1. 01 )121) 38) 1)
)106)159) H (TEH-TEC)TEH-TEC(RPI) 051 ) 610SL ( VS3- 0.7 1.3) )101) 47)Nl) g( 91)170) C )TEC-TEH)TEC-TEH( 0501600SMI01C+ 1.1 7. 9) 65( 86) 1)
I I I I C 101C-02C I 01C-02CI RPI I 191 ) 620ZR) 01C+ 0. 97 2.4) 35) 83) 1) c,) 93) 170) C ) 01C-02C) 01C-02C) RPI) 191 ) 620ZR) 01C+ 0. 75 0. SI 681 581 11 I I I C )TEC-TEH)TEC-TEH) 10715 90SM) 01C+ 0.6 1. 91 861 66)N1)
- 74) 173) ) C )TEC-TEH)TEC-TEH) 105) 590SM(VSS+ 0.6 0. 81 11571 <20 IN41
- 49) 184) C )TEC-TEH)TEC-TEH) 095 (610SM) VS4+ 0.8 0.8) 0) <20(N2)
I I I I I I I I I I I I I M>GER OF TU3ES SELECTED FROM CURRENT OUTAGE: 22 NO TREND ANALYSIS RE<QUESTED X
CONAN. INSPECTION Page 3 of 3.
APPENDIX C I
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07/89, ARIZONA PUBLIC SERVICE CO., PALO VERDE, UNIT 3 STEAN GENERATOR: 31 OATE: 07/02/89 TINE: 09: 54: 11 LOCATION: ALL CRITERIA: PLG PLG 80 STAYS 150 150 140 140 30 X 130 120 120 110 110 100 100 90 90 80 80 70 70 60 60 50 50 40 40 30
%0 20 20 10 10 90 100 110 120 130 140 150 160 170 180 10 20 30 40 50 60 70 80 CCHAH ItlSPKCTZCM
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07/89, ARIZONA PUBLIC SERVICE CO., PALO VERDE, UNIT 3 STEAN GENERATOR: 32 DATE: 07 02 89, TIME'9: 12: 00 LOCATION: ALL CRITERIA: PLG PLG 93 V V
STAYS
" 15 150 140 14
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130 v 13 C5 120 12 X ~ <
110 11 O 100 10 90 90 80 80" 70 70 60 60 50 50 40 40
, I~ I 30 30 20 20 Vl 10 I vv r; 10 20 30 40 50 60 70 80 90 100 110 120 130 140 150 160 170 180 CCRC IHSPECtTGM
APPENDIX D Cj 1
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~ -.ANPP NIS- I FORM OWNERS'ATA REPORT FOR INSERYICE INSPECTIONS
- 1. OWNER ARIZONA PUBLIC SERYICE COMPANY, ET AL ADDRESS P.O. BOX 53999 PHOENIX, ARIZONA
- 2. PLANT PALO YERDE NUCLEAR GENERATING PLANT ADDRESS 0 MILES SOUTH WINTERSBURG, ARIZONA
- 3. UNIT NUMBER:
- d. OWNERS CERTIFICATE OF AUTHORIZATION NONE
- 5. COMMERCIAL SERVICE DATE: 1/8/88
- 6. COMPONENTS INSPECTED:
COMPONENT OR MANUFACTURER SERIAL STATE OR NATIONAL APPURTENANCE OR INSTALLER NUMBER PROYINCE BOARD NO 3HRCEE01A COHBUSTION 79273-1 N/A 22478 STEAH GENERATOR 31 ENGINEERING TUBING 3HRCEE01B COHBUSTION 79273-2 N/A 22479 STEAH GENERATOR 32 ENGINEERING TUBING PAGE 1.0F 2-
A J ANPP NIS-1 BACK OWNERS'ATA REPORT FOR INSERV ICE INSPECTIONS
- 7. EXAM DATES ~Q39 TO ~12L89
- 8. INSPECTION INTERVAL FROM ~l LGBTO ~1ZL97
- 9. ABSTRACT OF EXAMINATIONS. INCLUDE A LIST OF EXAMINATIONSAND A STATEMENT CONCERNING STATUS OF WORK REQUIRED FOR CURRENT INTERVAL.
One hundred percent of the tubing in each steam generator was examined.
Several degraded/defective tubes were observed. These are documented in Appendix B of this report.
The following tubes were plugged and/or staked as a result of this examination:
S/G 31: R67L10, R66L11, R68L11, R154L83, R159L88, R153L100, R86L133.
S/G 32: R49L06, R51L06, R501,07, R52L07, R99L106, R150L127, R100L151 R106L159, R91L170, R93L170
': Common Interval Date WE CERTIFY THAT THE STATEMENTS MADE IN THIS REPORT ARE CORRECT AND THE EXAMINATIONSAND CORRECTIVE MEASURES TAKEN CONFORM TO THE RULES OF THE ASME CODE, SECTION XI.
DATES'SIGNED: ARIZONA PUBLIC SERVICE COMPANY BY CERTIFICATE OF INSERYICE INSPECTION I, THE UNDERSIGNED, HOLDING A YALID COMMISSION ISSUED BY THE NATIONALBOARD OF BOILER AND PRESSURE VESSEL INSPfCTORS AND THE STATE OF PROYINCE OF ARIZONA f MPLOYED BY KEMPER GROUP OF LONG GROVE, ILLINOIS HAYE INSPECTED THE COMPONENTS DESCRIBED IN THIS OWNERS REPORT DURING THE PERIOD ~4BS TO ~EBS, AND STATE THAT TO THE BfST OF MY KNOWLEDGE AND BELIEF, THE OWNER HAS PERFORMED EXAMINATIONSAND TAKEN CORRf CTIYE MEASURES DESCRIBED IN THIS OWNERS REPORT IN ACCORDANCE WITH THE REQUIREMENTS OF THE ASME CODE, SECTION XI. BY SIGNING THIS CERTIFICATE NEITHER THE INSPECTOR NOR HIS EMPLOYER MAKES ANY WARRANTY, EXPRESSED OR IMPLIED, CONCERNING THE EXAMINATIONSAND CORRECTIYE MEASURES DESCRIBED IN THIS OWNERS REPORT. FURTHERMORE, NEITHER THE INSPECTOR NOR HIS EMPLOYER SHALL BE LIABLE IN ANY MANNER FOR ANY PERSONAL INJURY OR PROPERTY DAMAGE OR A LOSS OF ANY KIND ARISING FROM OR CONNECTED WITH THIS INSPECTION.
INSPECTOR COMMISS ION S DATf + AT'L BOARD, STATE, PROVINCE
,PAGE 2 OF 2 E
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