ML17304A355
| ML17304A355 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/31/1988 |
| From: | BLOOM T J, HAYNES J G ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| S12-00327-JGH-T, S12-327-JGH-T, NUDOCS 8808260071 | |
| Download: ML17304A355 (33) | |
Text
AC CELEMTZD DISI'RIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)II 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 AUTH.NAME AUTHOR AFFILIATION BLOOM,T.J.
Arizona Nuclear Power Project (formerly Arizona Public Serv HAYNES,J.G.
Arizona Nuclear Power Project (formerly Arizona Public Serv RECIP.NAME RECIPIENT AFFILXATION RECIPXENT ID CODE/NAME PD5 LA LICITRA,E COPIES LTTR ENCL 1 0 1 0
SUBJECT:
Monthly operating Generating Statio.W/880815 DISTRIBUTION CODE: IE24D CO TITLE: Monthly Operating Report (per NOTES:Standardized plant.Standardized plant.Standardized plant.ul 1988 for Palo Verde Nuclear l VED:LTR ENCL SIZE: Tech Specs)RECIPIENT ID CODE/NAME PD5 PD DAVIS,M COPIES LTTR ENCL 5 5 1 0 ,R I D S 05000528 05000529 j 05000530 A D XNTERNAL: ACRS AEOD/DSP/TPAB NRR/DLPQ/PEB 11 R RPB 10 REG FILE Ol EXTERNAL EG&G WI LLIAMS i S NRC PDR NOTES 10 10 1 1 1 1 1 1 1 1 1 1 1 1 AEOD/DOA ARM TECH ADV NRR/DOEA/EAB 11 NUDOCS-ABSTRACT RGN5 LPDR NSIC 1 1 2 2 1 1 1 1 1 1 1 1 1 1 D S/A D 8 TOTAL NUMBER OF COPIES REQUIRED: LTTR 33 ENCL 30 e V~~J I~~NRC MONTHLY OPERATING REPORT DOCKET NO.50-528 UNIT NAME PVNGS-1 DATE 08 10 88 COMPLETED BY T J Bloom TELEPHONE 602 3 1-418 OPERATING STATUS 1.2.3.4, 5.6.7.8.Power Level to Which Restricted, If Any (Net MWe): None Reasons For Restrictions, If Any: N A 9.10.This Month Cumulative 21 984.0 Yr.-to-Date Hours in Reporting Period Number of Hours Reactor Was Critical Reactor Reserve Shutdown Hours Hours Generator On-Line Unit Reserve Shutdown Hours Gross Thermal Energy Generated (MWH)Gross Electrical Energy Generated (MWH)Net Electrical Energy Generated (MWH)Unit Service Factor Unit Availability Factor Unit Capacity Factor (Using MDC Net)Unit Capacity Factor (Using DER Net)Unit Forced Outage Rate Shutdowns Scheduled Over Next None 5 112.0 2 710.9 44 0 ll 12 12 688 1 132 1 13.0.0 0 0 0 0 12 346 4 2 629.3 132 1 14.15.0 0 0.0 0 0 16.9 541 006 0 3 330 700,0 503 7 1 0 44 573 843 0 15 474 000 0 17 174 000.0 158 169 0 18 14 447 494.0 3 119 869 0 51.4S 56 2s 17.8%19 20 21 51 4a 50 Os 56.2a 17 8 53.8 17 4a 22.51 82 2%6 Months (Type, Date, and Duration of Each): 29 3 23.24.If Shutdown At End of Report Period, Estimated Date of Startup: 08 15 88 25.Achieved~05 25 85 Forecast~05 85 INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (8808260071 880731 0409A/22644 l PDR RDOOK 05000523 R PDC~06 85 06/610 85~01 28 86~~~~/I ll 85 Unit Name: Palo Verde Nuclear Generatin Station Unit 1 Reporting Period: Jul 1988 Licensed Thermal Power (MWt): 3800 Nameplate Rating (Gross MWe): 1403 Design Electrical Rating (Net MWe): 1270 Maximum Dependable Capacity (Gross MWe): 1303 Maximum Dependable Capacity (Net MWe): 1221 If Changes Occur In Capacity Ratings (Items Number 3 Through 7)Since Last Report, Give Reasons: N A I tl~E "AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.50-528 UNIT NAME PVNGS-1 DATE 08 10 88 COMPLETED BY T J Bloom TELEPHONE 602 371-418 MONTH: JULY 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1 254 17 1 252 18 1 249 19 1 253 20 1 250 21 631 22 23"24'0 25 10 0 26 12'27 28 13 29 14 30 15 31 4 I" I R REFUELING INFORMATION DOCKET NO.50-528 UNIT NAME PVNGS-1 DATE 08 10 88 COMPLETED BY T J Bloom TELEPHONE 602 3 1-418 1.Scheduled date for next: refueling shutdown.03/21/89 2.Scheduled date for restart following refueling.
05/29/89 3.Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendments To be determined 4.Scheduled date for submitting,'ropo'sed licensing action and supporting information.
V 11/88 (If necessary).
Important Licensin'g'onsiderations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
/E.'To be determined 6.The number of fuel assemblies a)In the core.241 b)In the spent fuel storage pool.80 7.Licensed spent fuel storage capacity.1329 Intended change in spent fuel storage capacity.None 8.Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.2004 (18 Month reloads and full core discharge capability).
I)1'J t
SUMMARY
'OF OPERATING EXPERIENCE FOR THE MONTH JULY 1988 DOCKET NO.50-528 UNIT NAME PVNGS-1 DATE 08 10 88 COMPLETED BY T.J Bloom TELEPHONE 602 371-418 07/01 07/06 0000 1208 Reactor power at 100%.A fault on the 13.8KV Bus resulted in an explosion/fire of the unit auxiliary transformer.
The resultant loss of power to the reactor coolant pumps (RCP)led to a reactor trip on Low DNBR and established natural circulation.
07/07 0033 Power was restored to RCP lA, forced circulation was established, and cooldown to Mode 4 was commenced.
07/07 07/12 07/31 1373 0546 2400 Unit 1 entered Mode 4 (Hot Shutdown).
Unit 1 entered Mode 5 (Cold Shutdown).
Unit 1 remains in Mode 5.
f>
SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.50-528 UNIT NAME PVNGS-1 DATE COMPLETED BY T.J.Bloom No.Date Type"-Duration Hours Reason2 Method of Shutting Down Reactor3 LER No.System Component Code4 Code5 Cause and Corrective Action to Prevent Recurrence 7 7/6 F-611;9 1-88-010 EA EA NSBU XFMR A fault on the 13.8KV Bus resulted in an explosion/
fire of the unit auxiliary transformer.
The resultant loss of power to the RCPs led to a reactor trip on Low DNBR.Corrective actions included inspections and cleaning of similar 13.8KV Buses in Unit 1 and a sample of Unit 3's busses.In addition, a review of the Preventive Maintenance associated with the busses is being conducted.
F-Forced S-Scheduled Reason: A-Equipment Failure (Explain)B-Haintenance or Test C-Refueling 0-Regulatory Restriction E-Operator Training 5 License Examination F-Administrative G-Operational Error H-Other (Explain)Hethod: 1-Hanual 2-Hanual Scram 3-Automatic Scram 4-Continuation from Previous Honth 5-Reduction of 20X or Greater in the Past 24 Hours 9-Other-(Explain)
Exhibit F-Instructions for Preparation of the Data Entry Sheets for Licensee Event Report (LER)File (NUREG 0161)Exhibit H-Same Source Pi~~ij, NRC MONTHLY OPERATING REPORT DOCKET NO.50-529 UNIT NAME PVNGS-2 DATE 08 10 88 COMPLETED BY T J Bloom TELEPHONE 602 3 1-418 OPERATING STATUS 1.2.3.4.5.6.7.8.9.10 Unit Name: Palo Verde Nuclear Generatin Station Unit 2 Reporting Period: Jul 1988 Licensed Thermal Power (MWt): 3800 Nameplate Rating (Gross MWe): 1403 Design Electrical Rating (Net MWe):~12 0 Maximum Dependable Capacity (Gross MWe): 1303 Maximum Dependable Capacity.(Net,MWe):
1221 If Changes Occur In Capacity Ratings (Items Number 3 Through 7)Since Last Report, Give Reasons: N A Power Level to Which Restricted, If Any (Net MWe): one Reasons Fo'r Restrictions,-
If Any: N A 11 12 13 14.15.16 17 18.19.20.21.22.23.24.Hours in Reporting Period Number of Hours Reactor Was Critical Reactor Reserve Shutdown Hours Hours Generator On-Line Unit Reserve Shutdown Hours Gross Thermal Energy Generated (MWH)Gross Electrical Energy Generated (MWH)Net Electrical Energy Generated (MWH)Unit Service Factor Unit Availability Factor Unit Capacity Factor (Using MDC Net)Unit Capacity Factor (Using DER Net)Unit Forced Outage Rate Shutdowns Scheduled Over Next None This.Month" 44 0 44 0 Yr.-to-Date 5 112.0 2 256.6 Cumulative 16 368.0 11 531.7 0 0 744 0 0.0 2 142 0 0.0 11 268.2 0 0 2 794 833 0 9 8 100 0 919 688 0 100 0 100.0 0.0 813 952.0 2 729 800.0 2 542 033.0 41.9a 41 9s 0.0 41 021 119 0 14 391 070.0 13 478 915.0 68 8a 68.8a 101 2 40 7S 67.4s 64.8 5 4 0.0a 6 Months (Type, Date, and Duration of Each): 25.If Shutdown At End of Report Period, Estimated Date of Startup: N A INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION-6-Forecast~03 86 06 86 ll 86 Achieved~04 18 86 05 20 86 09 19 86 f'
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.50-529 UNIT NAME PVNGS-2 DATE 08 10 88 COMPLETED BY T.J.Bloom TELEPHONE 602 3 1-4187 MONTH: JULY 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1 230 17 1 24 1 236 1 236 18 19 1 49 1 247 1 245 20 1 246 1 243 21 1 245 1 245 1 238 22 23 1 246 1 245 1 240 1 195 24 25 1 243 1 245 10 1 201 26 1 253 1 245 27 1 233 12 1 25 28 1 249 13 1 259 29 1 245 14 1 257 30 1 090 15 1 255 31 1 198 16 1 255 REFUELING INFORMATION DOCKET NO.50-529 UNIT NAME PVNGS-2 DATE 08 10 88 COMPLETED BY T J Bloom TELEPHONE 602 3 1-4187 1.Scheduled date for next refueling shutdown.09/15/89 2.Scheduled date for restart following refueling.
11/24/89 3.Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendments t, R I To be determined 4.Scheduled date for submitting proposed licensing'action and supporting information.
1 To be determined 5." Important"Licensing considerations associated with, refueling, e.g., new or different fuel design or supplier, unreviewed", design or performance analysis methods, significant changes in fuel design, new operating procedures.
To be determined 6.The number of fuel assemblies a)In the core.241 b)In the spent fuel storage pool.108 7.Licensed spent fuel storage capacity.1329 Intended change in spent fuel storage capacity.None 8.Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.2004 (18 Month reloads and full core discharge capability).
ll CI L 1" I'
SUMMARY
'OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.50-529 UNIT NAME PVNGS-2 DATE 08 10 88 COMPLETED BY T J Bloom TELEPHONE 602 371-418 JULY 1988 07/01 07/09 07/10 07/30 07/31 07/31 0000 0050 2010 0340 (approx.)1535 2400 Reactor power at 100%.Reactor power reduced to 95%for Isothermal Temperature Coefficient/Moderator Temperature Coefficient Testing.Reactor power at 100%.Reactor power reduced to 85%for circulating water system-discharge valve maintenance and control element assembly/core protection calculator surveillance testing.Reactor power at 100%.Reactor power at 100%.
1'l SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.50-529 UNIT NAME PVNGS-2 COMPLETED'Y T.J.Bloom Method of Duration Shutting System Component No.Date Type" Hours Reason Down Reactor LER No.Code Code Cause and Corrective Action to Prevent Recurrence No Reactor Shutdowns or Significant Power Reductions occurred during the month.F-Forced S-Scheduled Reason: A-Equipment Failure (Explain)B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training 5 License Examination F-Administrative G-Operational Error H-Other (Explain)Hethod: 1-Hanua l 2-Hanua l Scram 3-Automatic Scram 4-Continuation from Previous Month 5-Reduction of 20K or Greater in the Past 24 Hours 9-Other-(Explain)
Exhibit F-Instructions for Preparation of the Data Entry Sheets for Licensee Event Report (LER)File (NUREG 0161)Exhibit H-Same Source I I t II'r NRC MONTHLY OPERATING REPORT DOCKET NO.50-530 UNIT NAME PVNGS-3 DATE 08 10 88 COMPLETED BY T J Bloom TELEPHONE 602 371-4187 OPERATING STATUS 1.2.3.4.5.6.7.8.9.10 Unit Name: Palo Verde Nuclear Generatin Station Unit 3 Reporting Period: Jul 1988 Licensed Thermal Power (MWt): 3800 Nameplate Rating (Gross MWe): 1403 Design Electrical Rating (Net MWe): 1270 Maximum Dependable Capacity (Gross MWe): 1303 Maximum Dependable Capacity (Net MWe): 1221 If Changes Occur In Capacity Ratings (Items Number 3 Through 7)Since Last Report, Give Reasons: N A Power Level to Which Restricted, If Any (Net MWe): None Reasons For Restrictions, If Any: N A This Month Yr.-to-Date Cumulative 11 12 13.14.'5.16.17 18 19 20 21 22 23 24 0 Hours in Repo'rting Period Number of Hours Reactor Was Critical Reactor Reserve Shutdown Hours Hours Gen'erator On-Line Unit Reserve Shutdown Hours Gross Thermal Energy Generated (MWH)Gross Electrical Energy Generated (MWH)Net Electrical Energy Generated (MWH)Unit Service Factor Unit Availability Factor Unit Capacity Factor (Using MDC Net)Unit Capacity Factor (Using DER Net)Unit Forced Outage Rate Shutdowns Scheduled Over Next None 744 0 744 0 0 0 736 6 0 0 2 780 396.0 967 500.0 912 625.0 99 Os 99 0 4 944 0 4 944 0 0 0 4 936 6 0 0 18 385 572 0 6 471 500 0 6 112 539.0 99.9 99.9a 4 944.0 4 944.0 0 0 4 936.6 0.0 18 385 572.0 6 4 1 500.0 6 112 539.0 99.9 99.9s 100 5 101 3 101 3 97.4a O.la 97 4a 1 Oa 6 Months (Type, Date, and Duration of Each): 25 If Shutdown At End of Report Period, Estimated Date of Startup: 08 16 88 INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION-ll-Forecast Achieved~07 8~10 25 8~07 87~11 28 87~09 8~01 08 88 t1
'AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.50-530 UNIT NAME PVNGS-3 DATE 08 10 88 COMPLETED BY T.J Bloom TELEPHONE 602 371-4187 MONTH: JULY 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1 258 17 1 244 1 252 1 254 18 19 1 247 1 248 1 256 1 254 1 251 1 245 1 251 1 251 20 21 22 23 24 il 25 1 245 1 248 1 247 1 202 1 234 1 213 10'248 26 1 201 1 211 27 1 209 12 1 253 28 1 230 13 14 1 257 1 253 29 30 1 234 1 230 15 1 255.31 801 16 1 253
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REFUELING INFORMATION DOCKET NO.50-530 UNIT NAME PVNGS-3 DATE 08 10 88 COMPLETED BY T J Bloom TELEPHONE 602 3 1-4187 1~Scheduled date for next refueling shutdown.03/03/89 2.Scheduled date for restart following refueling.
05/27/89 3.Will'refueling or resumption
'f.'peration thereafter require a Technical Specification change or other license amendment?
Yes, these are expected to include the followin'g:
2.1.1.1, 3/4 1.1.2, 3/4 1.1.3, 3/4 1.3.1, 3/4 1.3.6, 3/4 2.1, 3/4 2.3, 3/4 2.4, 3/4 2.5, 3/4 2.8, 3/4 3.1, 3/4 3.2.4.Scheduled date for submitting proposed licensing action and supporting information.
I I" 1"1/88 5.Important Licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
The fuel vendor for the next five reloads will'be Combustion Engineering.
6.The number of fuel assemblies a)In the cores'41 b)In the spent fuel storage pool.0 7.Licensed spent fuel storage capacity.1329 Intended change in spent fuel storage capacity.None 8.Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.2005 (18 Month reloads and full core discharge capability).
'I
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.50-530 UNIT NAME PVNGS-3 DATE 08 10 88 COMPLETED BY T.J Bloom TELEPHONE 602 3 1-418 JULY 1988 07/01 0000 Reactor power at 100%.07/11 1230 Reactor power reduced to 91%as a result of a control element assembly calculator failure.07/11 2142 Reactor power at 100$.07/23 0504 Reactor power reduced to 89%for the performance of control element assembly surveillance testing.07/23 07/24 1300 1845 Reactor power at 100%.Reactor power reduced to 96.5S due to increased temperatures in the main generator stator.07/25 1140 Reactor power at 100%.07/25 1658 Reactor power reduced to 95%due to increased temperatures in the main generator stator.07/29 2123 Reactor power at 100%.07/31 1636 Turbine trip with resultant reactor power cutback occurred following a lighting strike which tripped the B-phase main transformer.
07/31 07/31 1815 2400 Reactor power stabilized at 17%.Unit 3 is in Mode 1 with reactor power at approximately 8%.1'41 K I I SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.50-530 UNIT NAME PVNGS-3 DATE COMPLETED BY T.J.Bloom No.Date Type1-Duration Hours Reason2 Method of Shutting Down Reactor LER No.System Code4 Component Code5 Cause and Corrective Action to Prevent Recurrence 6 07/31 F 7.4 H N/AP N/AP N/AP Turbine trip occurred when a lighting strike tripped the B-phase main transformer.
F-Forced S-Scheduled Reason: A-Equipment Failure (Explain)B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training II License Examination F-Administrative G-Operational Error H-Other (Explain)Method: 1-Hanual 2-Hanual Scram 3-Automatic Scram 4-Continuation from Previous Honth 5-Reduction of 20K or Greater in the Past 24 Hours 9-Other-(Explain)
Exhibit F-Instructions for Preparation of the Data Entry Sheets for Licensee.Event Report (LER)File (HUREG 0161)Exhibit H-Same Source I~s)li i//
~~~0 Arizona Nuclear Power Project P.O.BOX 52034 4 PHOENIX.ARIZONA 85072-2034 212-00327-JGH/TJB August 15, 1988 Docket: Nos.STN 50-528/529/530 Document Control Desk U.S.Nuclear Regulatory Commission Mai,l Station Pl-137 Washington, D.C.20555
Dear Sirs:
Subject:
Palo Verde Nuclear Generat:ing Station (PVNGS)Units 1, 2 and 3 Monthly Operating Reports for July 1988 File: 88-024 404 88-056 026 Attached are the Monthly Operating Reports for July 1988 prepared and submitted pursuant to Specification 6.9.1.6 of Appendix A (Technical Specifications) to the Palo Verde Nuclear Generating Station, Units 1, 2 and 3 Operating Licenses.By copy of this letter, we are also forwarding a copy of the Monthly Operating Reports to the Regional Administrator of the Region V Office.If you have any questions, please contact Mr.T.J.Bloom, at (602)371-4187.Very truly yours, J.G.Haynes Vice President Nuclear Production JGH/TJB/dim Attachments cc: E.E.Van Brunt, Jr.D.B.Karner J.A.Amenta A.C.Gehr M.J.Davis J.B.Martin INFO Records Center (all w/attachments) 1~4 f P 1