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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
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Observations and Comments Initial Reactor Startup and Low Power Reactor Physics Tests Palo Verde ~ Nuclear Generating Station, Unit 1 NRC Region V Enhanced Inspection by L. Rolf Peterson, P.E.
Lawrence Livermore National Laboratory June 21, 1985 Backcround I participated as a consultant member of the NRC Region V Enhanced Inspection Team at Palo Verde Nuclear Generating Station, Unit 1 (Palo Verde 1), from May 22 through May 31, 1985. During this inspection I reviewed the procedures for initial criticality and low power physics tests, observed the performance of reactor test and reactor operations personnel during reactor startup and low power operation, and evaluated the preliminary results of the low power reactor physics tests.
The initial startup of Palo Verde 1 was conducted using Arizona Public Service Co. (APS), Palo Verde Nuclear Generating Station Manual, Procedure 72IC-1RX02, Initial Criticality, Revision 1, dated May 20, 1985. Startup and initial criticality was performed with the primary reactor coolant system (RCS) at 320 degrees F temperature and 600 psia pressure. Initial criticality was achieved at 0145 on May 25, 1985.
Low power reactor physics tests were conducted using APS Procedure 72PY-1RX30, Low Power Physics Test, Revision 0, dated May 22, 1985.
Initial low power physics tests were conducted at RCS temperature /
pressure = 320 degrees F / 600 psia. Final low power physics tests were conducted at RCS t em pera t u re / pressure = 565 degrees F / 2250 psia.
The low power physics tests commenced on May 25, 1985, and were concluded on June 1, 1985.
On May 22, 1985, I attended.a briefing by David Hoppes, the supervising APS reactor test engineer, and Frank Philpott, the lead Combustion Engineering (CE) reactor engineer on site for the Palo Verde 1 startup.
The briefing summarized the plans for initial criticality and low power physics tests and reviewed the major evolutions included in the procedures cited.above.
Initial Criticality I reviewed in detail Procedure 721C-1RX02, Initial Criticality. Seven properly approved Procedure Change Notices (PCNs) corrected minor discrepancies in the original Initial Criticality Procedure. I found that the procecure, including the PCNs, was complete and incorporated good operating practices for a safe approach to initial reactor criticality.
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t The procedure included adequate precautions to prevent an unanticipated criticality and to ensure proper detection of the neutron multiplication during startup. The procedure established safe initial conditions for reactor startup with a high boron concentration and all control el em en t assembly ( CEA ) groups fully withdrawn except for CEA. Group 5, which was withdrawn to half insertion.
, The procedure for boron dilution to approach criticality was cautious and orderly. It provided for periodic sampitng and laboratory analysis of the RCS and pressurl=er boron concentra J.ons and for monitoring RCS tboronometer readings during boron dilution and mixing. The procedure called for Inverse Count Rate Ratio (ICRR or 1/M) plots versus boron concentration and versus time during boron dilution and mixing to assist in the prediction of conditions for initial criticality. The preceiure also required verification of at least one decade of nuclear instrumentation response overlap between the startup channels anc the log safety channels during the final portions of the approach to critical.
I observed operations in the control room during early stages of boron dilution on May 24, 1965, and I observed the final two hours of the approach to initial criticality. Initial criticality was declared at 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br /> ( 1 : 45am ) , May 25, 1985. All operations were safely ar.d competently performed in accordance with the Initial Criticality Procedure.
The predicted RCS boron concentration for initial criticality with CEA Group 5 halfway withdrawn and all other CEAs fully withdrawn was 1063- ppm ( q 100 ppm ) . The actual measured boron concentration at initial criticality in this configuration was 1054 ppm. This value was well within the acceptable uncertainty of the predicted critical boron concentration.
Low Power Physics Tests After Palo Verde 1 initial criticality was established, APS entered Procedure 72PY-1RX30, Low Power Physics Test, Revision O. Tests included in this procedure were:
l Critical boron concentration measurements with different control rod configurationsi Isothermal temperature measurements with different control rod configurations; Reactivity worth measurements of regulating CEA Groups 5, 4, 3, 2, and 1 insertions with no overlap at RCS 320 degrees F / 600 psia and withdrawals with no overlap at RCS 565 degrees F / 2250 psia;
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4
, Reactivity worth measurement of shutdown CEA Group B insertion at RCS 320 degrees F / 600 psia; Reactivity worth measurement of insertion of Shutdown CEA Group A minus one CEA (Group A- 1 ) at RCS 320 degrees F / 600 psia, simulating highest reactivity worth element CEA 77 stuck in the i fully withdrawn position;
' Pseudo-ejected CEA reactivity worth measurement at RCS 565 degrees F / 2250 psia; Reactivity worth measurements of pseudo-dropped CEA, Part Length CEA (PLCEA), and-PLCEA Subgroup at RCS 565 degrees F/
2250 palai CEA reactivity worth symmetry checks at RCS 565 degrees F/
2250 psia; Reactivity worth measurement of PLCEA Group P ( an- optional measurement for information only);
CEA reactivity worth ~ measurements by exchange of reactivity between CEA groups ( optional measurements ) .
I reviewed APS Procedure 72PY-1RX30, Rev 0, Low Power Physics Test, prior to and during the time that I observed the low power physics tests at Palo Verde 1. The procedure was modified by four PCNs to correct minor discrepancies and to change the frequency of boron sampling during long periods of boron stability. I found that the procedure was-complete'and explicit for all physics test activities. The procedure established prerequisites for low power physics testing that included comprehensive personnel indoctrinationi pretest briefing of operations personnel; equipment availability, calibration, and configuration requirementsi and special surveillance requirements. Initial conditions for entery into the procedure were clearly stated. Special precautions-to be observed during the procedure were provided.
I observed in the control room representative portions of all activities and measurements during the low power physics tests. All tasks were performed in accordance with the test procedure.and approved PCNs.
During the low power physics tests, the normal shift test. crew was an APS Responsible Engineer,.two assistants, and a Combustion Engineering representative. I-observed that the reactor test and reactor operating crews properly followed test procedures throughout the tests. The APS and Combustion Engineering reactor test personnel had a good basic understaning of the_ measurements being made and used proper test techniques to er.ture that valid data was obtained. I also observed close cooperation between the APS reactor test personnel and the Combustion Engineering representatives.
The APS reactor test pe.rsonnel were noticeably dependent upon the advice of the more experienced Combustion Engineering representatives during the approach to initial criticality and during early portions of the low power physics tests. I noted a definit ~e increase in confidence and independence of the APS reactor test personnel as they gained experience during the course of the low power physics tests.
During the low power physics tests I reviewed raw data and observed the APS data analysis process. All experiment data was analyzed by at least two people to detect errors and minimize interpretive variation. Good records were kept of all raw data for future reference. I found the data analysis effort was well planned and adequately staffed. I did not observe any discrepancies that went undetected or uncorrected. I believe that the' data obtained was gocd and that the final results of data analyses were accurate.
In all cases except one, the measured parameters conformed to predicted
' design values that were provided by Combustion Engineering and incorporated into the APS procedure. The predicted worth for insertion of CEA Group A minus one CEA withdrawn to simulate a stuck rod assembly (CEA Group A-1 ) was -0.37 %Dk/k with an acceptance range between -0.47 and -0.27 %Dk/k. The measured reactivity worth of CEA Group A-1 was
-0.55 %Dk/k. The larger than expected negative reactivity of CEA Group A-1 is not a safety problem since it indicates that more shutdown reactivity than was predicted is available frem insertion of this CEA group when one of the highest worth CEAs in the group is stuck in the fully withdrawn position.
APS test p.arsonnel generated a Test Exception Report (TER) for the CEA Group A-1 11easurement and initiated an Engineering Evaluation Request (EER). The APS Test Results Review Group (TRRG) reviewed the TER on May 30. The TRRG made an interim determination that the higher than expected r.egative reactivity worth of CEA Group A-1 did not impact safety in Mode 1 below 20% power. The TRRG referred the EER'to Combustion Engineering for final evaluation of the impact of exceceding the expected negative reactivity worth. I agree with the TRRG evaluation and disposition of this deviation from predicted test results.
CONCLUSIONS I found that Arizona Public Service had adequate and complete procedures in place to safely conduct the startup to initial criticality and the low power physics tests at Palo Verde Nuclear Generating Station, Unit 1.
The Palo Verde 1 operating crews and reactor test personnel that I observed on shift in the control room during initial startup and throughout the performance of low power physics tests followed established procedures.
I observed that the Palo Verde 1 reactor operating crews and reactor test personnel performed the appt nach to initial criticality and all low power physics tests competently. I also observed good cooperation and assistance from Combustion Engineering representatives on shift during the Palo Verde 1 startup and low power physic's tests.
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I observed representative portions of the data acquisition and analysis activities by the reactor test personnel during initial criticality startup and low power physics tests. Accurate data was obtained for all startup and test evolutions. I concur with the test data analyses and evaluaticns made by Arizona Public Service and Combustion Engineering personnel. No deviations from expected nuclear design characteristics that would adversely affect safety of operations of Palo Verde 1 were observed during the initial reactor startup and the low power physics test program.
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L. Rolf Peterson, P.E.
Nuclear Systems Safety Program Lawrence Livermore National Laboratory
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