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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20210J1561999-07-29029 July 1999 Rev 0 to Wolf Creek Generating Station,Unit 1 Pressure & Temp Limts Rept ML20212H5491999-06-18018 June 1999 Non-proprietary Rev 4 to HI-981983, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20205L2341999-04-0505 April 1999 SFP Criticality Analysis ML17300B3071999-03-31031 March 1999 Seismic Portion of Submittal-Only Screening Review of Palo Verde Nuclear Generating Station Units Ipeee. ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20199E9651998-11-24024 November 1998 Rev 1 to ATI-98-012-T005, DPC Evaluation of McGuire Unit 1 Surveillance Weld Data Credibility ML20195E7591998-11-10010 November 1998 WCNOC Proposed PASS Function Reduction ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20237D5691998-08-31031 August 1998 Rev 0 to MPR-1957, Design Submittal for Oyster Creek Core Plate Wedge Modification ML20237D5711998-08-18018 August 1998 Rev 0 to SE-000222-002, Core Plate Wedge Installation ML20249B2451998-05-18018 May 1998 Nonproprietary Version of Revised Chapters 4 & 5 to Rev 4 of HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants for Ue & Wcnoc. Chapters 4 & 5 Reflect Editorial Revs ML20248C3681998-05-18018 May 1998 Non-proprietary Version of Rev 4 to HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants ML20247F1891998-05-0505 May 1998 Risk Evaluation of Post-LOCA Containment Overpressure Request ML20151Y4651998-03-31031 March 1998 Non-proprietary Version of Rev 1 to GENE-E21-00143, ECCS Suction Strainer Hydraulic Sizing Rept ML20198J5641998-01-0707 January 1998 Unit 2 Pressure & Temp Limits Rept ML20198J5531998-01-0707 January 1998 Unit 1 Pressure & Temp Limits Rept ML20198P6591997-12-31031 December 1997 .0 Volt IPC Full Cycle Operation Technical Basis Supplement to 'Braidwood Unit 1 Cycle 7 Interim Plugging Criteria Rept,Aug 1997.' ML20202F6881997-09-29029 September 1997 Evaluation of Underground Essential Svc Water Pipeline Leak ML20210P8611997-08-31031 August 1997 Cycle 7 Interim Plugging Criteria Rept ML20141K0371997-05-21021 May 1997 Pressure & Temp Limits Rept ML20141K0431997-05-21021 May 1997 Pressure & Temp Limits Rept ML20148P8811997-05-16016 May 1997 Spent Fuel Rack Criticality Analysis Using Soluble B Credit ML20141G6361997-05-15015 May 1997 Interim Plugging Criteria Return to Power Rept ML20138H0001997-04-28028 April 1997 Locked Tube Tts Circumferential Indication Root Cause Determination Evaluation ML20133F8451997-01-0808 January 1997 WCGS Quadrennial Simulator Certification Rept ML20217G0481997-01-0202 January 1997 Rev 0 to Risk Assessment of Deferred Oyster Creek Projects ML20133A7901996-12-20020 December 1996 Volumes 1 & 2 to Plant Referenced Simulator Certification ML20134M3131996-11-13013 November 1996 Revised SG Tube Rupture Analysis for Byron/Braidwood ML20134N8011996-10-31031 October 1996 Spent Fuel Rack Criticality Analysis W/Credit for Soluble Boron ML20134N3131996-10-31031 October 1996 Sys Design Description for Containment Spray ML20134C8851996-10-0404 October 1996 Core Spray Sys Insp Program -16R ML20116H1461996-08-0101 August 1996 Cycle Length Assessment Rept Addendum ML20248D1121996-07-31031 July 1996 Development of Equipment Seismic Fragilities for OCNGS Ipeee ML20117E7331996-07-31031 July 1996 Pressure-Temp Curves Per RG 1.99,Rev 2 for Oncpp ML20112B8521996-05-17017 May 1996 Cycle Length Assessment Rept Suppl ML17312A7631996-05-0808 May 1996 Calculation Summary of Radiological Doses for SG Tube Rupture W/Loss of Offsite Power & Stuck Open Adv. ML20113E1631996-05-0808 May 1996 PVNGS Unit 3 SG Eddy Current Exam Fifth Refueling Outage Nov 1995 ML20117J0491996-05-0808 May 1996 At&T Round Cell Nuclear Util User'S Council Charter ML20106G5891996-04-30030 April 1996 Training Dept Braidwood Simulator 1996 Certification Rept ML20117F1041996-04-11011 April 1996 Response to NRC GL 95-07 Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves ML20101L8041996-03-0101 March 1996 USI A-46 Seismic Evaluation Rept ML20100R7371996-02-29029 February 1996 Cycle 6 Interim Plugging Criteria 90 Day Rept ML20100R4291996-02-28028 February 1996 Incident Investigation Team Rept, Plant Shutdown Due to Circulating Water & Essential Svc Water Intake Icing ML20100Q2031995-12-31031 December 1995 Annual SER 11 for Jan-Dec 1995 ML20094K6101995-11-30030 November 1995 Interim Plugging Criteria Return to Power Rept ML20094N0751995-10-31031 October 1995 Validation of Crest, Interim Rept ML20093G7171995-10-12012 October 1995 Rev 0 to PSA-B-95-18, RELAP5M3 Comparison of Model Boiler 2 MSLB from Hzp Test ML20093G8821995-10-11011 October 1995 Rev 0 to PSA-B-95-17, Calculation of Byron 1/Braidwood 1 D4 SG Tube Support Plate Loads w/RELAP5M3 1999-09-29
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G9961999-10-14014 October 1999 SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & ML20217K4451999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Oyster Creek Nuclear Generating Station.With ML20217G1521999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Wolf Creek Generating Station.With BW990066, Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With ML17300B3811999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pvngs,Units 1,2 & 3.With 991007 Ltr ML20217G7951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2 ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20217F3661999-09-22022 September 1999 Rev 18 to McGuire Unit 1 Cycle 14 Colr ML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20212A7441999-09-10010 September 1999 Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety ML20211N0161999-09-0202 September 1999 Safety Evaluation Supporting GL 95-07 to License NPF-42 BW990056, Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With ML20212A0251999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Wolf Creek Generating Station.With ML20211P6731999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Oyster Creek Nuclear Generating Station.With ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML17300B3271999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pvngs,Units 1,2 & 3 ML20216E8851999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2 ML20217G8101999-08-31031 August 1999 Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20217P6451999-08-30030 August 1999 Requests Commission Approval to Publish Encl Pr,Rg & SRP & to Issue Encl Ltr to Parties of Wolf Creek Transfer Proceeding Re Disposition of Existing Antitrust License Conditions in Event OL Transfer Approved 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 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20210R6421999-08-13013 August 1999 ISI Outage Rept for A2R07 ML20210U8111999-08-0404 August 1999 SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval Because Relief Applies to Valves Not Required by 10CFR50.55a BW990048, Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With ML20210R5741999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Wolf Creek Generating Station ML20211A7051999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Oyster Creek Nuclear Station.With ML20210S2371999-07-31031 July 1999 Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20216E8951999-07-31031 July 1999 Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML17313B0611999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pvngs,Units 1,2 & 3.With 990810 Ltr ML20210K9861999-07-30030 July 1999 Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20210J1561999-07-29029 July 1999 Rev 0 to Wolf Creek Generating Station,Unit 1 Pressure & Temp Limts Rept 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 ML20216D3841999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function M990002, Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function1999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20210S2491999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML17300B3151999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pvngs,Units 1,2 & 3.With 990714 Ltr ML20209H1631999-06-30030 June 1999 Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20210R5921999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Wolf Creek Generating Station ML20209H0821999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Wolf Creek Generating Station BW990038, Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With ML20209G0631999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Oyster Creek Nuclear Generating Station.With 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 ML20212H5491999-06-18018 June 1999 Non-proprietary Rev 4 to HI-981983, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool ML20195D5261999-06-0202 June 1999 Safety Evaluation Approving Proposed ISI Program Alternative for Limited Reactor Vessel Shell Weld Exams & Relief Request from Requirements of ASME Code,Section XI ML20210R5871999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Wolf Creek Generating Station 1999-09-30
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4 i ENCLOSURE 1 i
) AT&T ROUND CELL NUCLEAR UTILITY USER'S COUNCIL CHARTER l
4 9605300096 960515 PDR ADOCK 05000219 P PDH j
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l CHARTER l I
DATE; May 8,1996 TITLE: AT&T Round Cell Nuclear Utility User's Council REVISION: 0 CHAIR: Duke Power MEMBERS: LucentTechnologies Arizona Public Service Comed (Commonwealth Edison)
Duke Power Company GPU Nuclear ,
Wyle Laboratories Wolf Creek Nuclear Operating Corporation PURPOSE AND SCOPE: <
The purpose of the User's Council is to bring together knowledge and experience of AT&T l Lineage 2000 Round Cell Batteries in order to address immediate industry and regulatory concerns of performance and behavioral chameteristics that have evolved from recent testing and i operating experience. Long term, the team will collectively work to resolve questions and issues l
that are unique to Nuclear Utility applications and address applicability of IEEE standards.
OPERATING AGREEMENT:
The Council shall conduct business using Robert's Rules of Oitler. Group positions and rulings shall be established by consensus of majority members present at meetings. Urgent issues will be I
resolved between meetings utilizing written correspondence and balloting of active members.
EXPECTATIONS:
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- 1. Evaluate charging methods for high specific gravity Round Cells
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- Available battery capacity following Performance Test recharge
- Available battery capacity following an unplanned discharge on-line l
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- 2. Identify and resolve concems that apply to Standard Technical Specifications
- 3. Identify and determine applicability ofIEEE Standards l
- 4. Review historical prob; ems and lessons learned .
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- 5. Develop position on testing and correlation of intemal cell impedance / resistance to cell j performance l l
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- 6. Investigate performance and behavioral characteristics of high and low specific Round Cells
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( 7. Establish communication between member and methods of data pooling l 8. Investigate root cause(s) of Palo Verde and Braidwood battery capacity loss MILESTONES GOALS:
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+ Next Meeting in Charlotte, NC -5/22 & 23/96 )
+ - Issue report documendng results of recharge testing - Approx. 9/96 l l + Issue root cause reports for Palo Verde and Braidwood battery - Approx. 9/96 loss of capacity
+ Issue repon addn:ssing cellimpedance/ resistance testing Vs cell - Approx.10/96 performance
- Establish group position on applicability ofIEEE Standards - Fall 96 IEEE Mtg
! and present to IEEE Standards Board
+ Document position and basis of Standard Technical Specification - AfterIEEE Mtg issues t
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Charter Attachment Page 1 of 8 Expectations Discussion / Action / Sponsor / Completion Date 1, Evaluate charging methods for high specific gravity Round Cells
- Available battery capacity following Performance Test recharge :
Discussion: Discharge testing has indicated that 100% capacity is not available immediately following recharging after a battery Performance Test. In order to fully 1
understand this phenomenon, additional testing may need to be performed to determine the characteristics of constant current and constant potential charging.
l Action: Evaluate and compare both constant current and constant potential charging.
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+ Available battery capacity following an unplanned discharge on-line l
Discussion: After en unplanned discharge on-line, plants will use their permanent plant constant potential chargers at float potential to charge the batteries. An issue has been raised concerning the charge retum rate using this method of charging and the available safety margin. i I
Action: Evaluate effectiveness of constant potential charging at float voltage following an on-line discharge. Determine rate of charge retum and evaluate safety margin over accident. duty cycle.
1 Sponsor: APS )
Completion Date: Preliminary - Appmx.6/96 Final - Approx. 9/96
Chaner Attachment Page 2 of 8 Expectations Discussion / Action / Sponsor / Completion Date
- 2. Identify and provide recommendations to resolve concerns that apply to Technical Specifications Discussion: With the unique characteristics of AT&T Round Cells, generic parameters and Surveillance Requirements need to be evaluated for applicability.
Action: Review Standardized Technical Specification for applicability. Document positions and basis.
Sponsor: APS Completion Date: (90 days following resolution of IEEE 450 issue) l l
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Charter Attachment Page 3 of 8 Expectations Discussion / Action / Sponsor / Completion Date
- 3. Identify and determine applicability ofIEEE Standards IEEE Std. 450 Discussion: Due to the unique design and characteristics of AT&T Round Cells, clarification ofIEEE Std. 450 is required.
Action: Request a Standards interpretation based on data submitted from User's Council.
l l IEEE Std 485 l
Discussion: IEEE Std. 485 is normally used for sizing (including various margins) lead-l acid batteries used at Nuclear Stations. Due to unique design and characteristics of '
l AT&T Round Cells, clarification of IEEE Std. 485 is required.
Action: Request a Standards interpretation based on data submitted from User's Council.
Sponsor: Comed l
l Completion Date: (Request submitted prior to fall 96 IEEE Working Group meeting)
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Charter Attachment Page 4 of 8 Expectations Discussion / Action / Sponsor / Completion Date
- 4. Review historical problems and lessons learned Discussion: Significant problems and lessons leamed during service need to be shared wSh the group from both a historical perspective and on-going basis.
Action: Research problem history and record on-going problems and lessons leamed.
Solicit input and share with the group.
Sponsor: GPUN i Completion Date: Initial Rollout Approx.6/96 l
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s Charter Attachment Page 5 of 8 l Expectations Discussion / Action / Sponsor / Completion Date
- 5. Develop position on testing and correlation ofinternal cell impedance / resistance to cell performance Discussion: Comed, Braidwood Nuclear Station has been taking intemal cell impedance measurements on designated strings of Round Cells and comparing values with battery Performance Test results. The emphasis is to establish a correlation between cell impedance and capacity. This testing also explores the effect of entrapped gases genemted during charging on cell impedance.
1 Action: Document test results and determine validity of correlation and benefits of i impedance testing. I Sponsor: Comed Completion Date: Approx.10/96 l
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Charter Attachment Page 6 of 8 Expectations Discussion / Action / Sponsor / Completion Date
- 6. Investigate performance and behavioral characteristics of high and low specific gravity Round Cells Discussion: Recent problems and abnormalities of Round Cells have been limited to those with high specific gravity electrolyte. The effects of high specific gravity electrolyte on performance and behavioral characteristics are not fully understood.
Action: Investigate performance and behavioral characteristics of high and low specific gravity cells. Determine and document differences of each.
Sponsor: WolfCreek Completion Date: Approx. 4/97 t l l
o 1 Charter Attachment Page 7 of 8 Expectations Discussion / Action / Sponsor / Completion Date
- 7. Establish communication between members and methods of data pooling Discussion: With national participation, the User's Council member locations are such that frequent meetings are impractical. In order to share ideas and data, a more direct method of communication is needed. ,
Action: Develop a network between Council members using the Intemet, that will provide convenient distribution of correspondence, information, and test data. Method should be fast, simple and convenient such that frequent correspondence and sharing of data is encouraged.
Sponsor: Duke Power Completion Date: Approx. 6/96 i
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Page 8 of 8 Expectations Discuss, ion / Action / Sponsor / Completion Date
- 8. Investigate root cause(s) of Palo Verde and Braidwood battery capacity loss Discussion: Recent Performance Tests of Round Cell batteries at Palo Verde Unit 2 and
- Braidwood Unit I have indicated unexpected and premature loss of capacity. Root cause evaluations at each station are ongoing. The results of these evaluations should be reviewed and shared such that lessons are learned and applied to develop a better understanding of Round Cell behavior.
Action: Investigate root cause(s) of capacity loss and evaluate results.
- Sponsor
- APS/ Comed Completion Date: Approx. 9/96 l
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ENCLOSURE 2 BATTERY IN PLANT SURVEILLANCE TEST DATA
SUMMARY
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i McGuire Batterv A Service Test 8/12/91 Passed Performance Test 3/16/93 101 %
l Service Test 6/22/93 Passed Service Test 12/28/94 Passed Batterv B '
Service Test 6/2/92 Passed Service Test 3/21/94 Passed Performance Test 12/31/94 106 %
Service Test 10/18/95 Passed i Battery C Service Test 8/26/91 Passed l Performanco Test 3/23/93 100 %
Service Test 7/7/93 Passed Service Test 1/23/95 Passed Batterv D Service Test 6/16/92 Passed .
Service Test 3/7/94 Passed Performance Test 11/14/94 108%
l Service Test 12/11/95 Passed Oyster Creek l
Batterv B Service Test 1/14/93 Passed Performance Test 11/24/94 97.5 %
Service Test 11/24/94 Passed Wolf Creek No operationa! testing to date.
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4 Braidwood Unit 1 Batterv 111 Service Test 3/94 Passed Modified Performance Test 10/95 112 %
Batterv 112 Service Test 4/94 Passed Modified Performance Test 10/95 92% ,
Service Test 11/95 Passed Single CellTests (3) 3/96 <65%
Service Test 3/96 Passed Service Test (Replacement Cells) 3/96 Passed Braidwood Unit 2 Batterv 211 Service Test 10/94 Passed Modified Performance Test 3/96 112.5 %
Batterv 212 Service Test 10/94 Passed Modified Performance Test 4/96 112 %
Palo Verde Unit 1 l l
Batterv A !
l Service Test 3/92 Passed l Performance Test 9/93 108.6 % !
Service Test 4/95 Passed Battery B Service Test 4/92 Passed Performance Test 10/93 105.4 %
Service Test 4/95 Passed l
4 Battery C -
Service Test 3/92 Passed Performance Test 9/93 105.9 %
Service Test 4/95 Passed Battery D Service Test 4/92 Passed Performance Test 10/93 106.6 %
Performance Test 4/95 107.4 % I I Palo Verde Unit 2 l Batterv A l Service Test 5/93 Passed Performance Test 9/94 91.6 %
l Performance Test (Replacement 3/96 106.7 %
Cells)
Battery B Service Test 5/93 Passed Performance Test 1/94 100.0 % !
Performance Test 9/94 89.0 %
Batterv C Service Test 5/93 Passed Performance Test 9/94 90.6%
Performance Test (Replacement 3/96 88.6 %
l Cells) j Batterv D i Service Test 5/93 Passed Performance Test 1/94 100.0 %
Performance Test 9/94 88.3 %
r Palo Verde Unit 3 Battery A -
Service Test 10/92 Passed -
Performance Test 4/94 105.6 %
Service Test 10/95 Passed Battery B Service Test 10/92 Passed Performance Test 3/94 110.0 %
Service Test 10/95 Passed Batterv C Service Test 10/92 Passed Performance Test 4/94 109.2 %
Service Test 10/95 Passed Battery D !
1 Service Test 10/92 Passed Performance Test 3/94 112.9 %
Service Test 10/95 Passed l
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