ML17304A355

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Monthly Operating Repts for Jul 1988 for Palo Verde Nuclear Generating Station,Units 1,2 & 3.W/880815 Ltr
ML17304A355
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 07/31/1988
From: Bloom T, Haynes J
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)
v • d • e


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

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SUBJECT:

Monthly operating Generating Statio .W/880815 lul 1988 Palo Verde Nuclear I SIZE: D DISTRIBUTION CODE: IE24D CO VED:LTR ENCL TITLE: Monthly Operating Report (per Tech Specs) S NOTES:Standardized plant.

Standardized plant.

Standardized plant.

05000528 05000529 05000530 j

A RECIPXENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 0 PD5 PD 5 5 LICITRA,E 1 0 DAVIS,M 1 0 XNTERNAL: ACRS 10 10 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 ARM TECH ADV 2 2 NRR/DLPQ/PEB 11 1 1 NRR/DOEA/EAB 11 1 1 R RPB 10 1 1 NUDOCS-ABSTRACT 1 1 REG FILE Ol 1 1 RGN5 1 1 EXTERNAL EG&G WILLIAMSi S 1 1 LPDR 1 1 NRC PDR 1 1 NSIC 1 1 NOTES D

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8 TOTAL NUMBER OF COPIES REQUIRED: LTTR 33 ENCL 30

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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. Unit Name: Palo Verde Nuclear Generatin Station Unit 1
2. Reporting Period: Jul 1988
3. Licensed Thermal Power (MWt): 3800 4, Nameplate Rating (Gross MWe): 1403
5. Design Electrical Rating (Net MWe): 1270
6. Maximum Dependable Capacity (Gross MWe): 1303
7. Maximum Dependable Capacity (Net MWe): 1221
8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7)

Since Last Report, Give Reasons: N A

9. Power Level to Which Restricted, If Any (Net MWe): None
10. Reasons For Restrictions, If Any: N A This Month Yr.-to-Date Cumulative ll 12 Hours Number in Reporting Period of Hours Reactor 44 0 5 112.0 21 984.0 Was Critical 132 1 2 710.9 12 688 1
13. Reactor Reserve Shutdown Hours 0 0 0.0 0 0
14. Hours Generator On-Line 132 1 2 629.3 12 346 4
15. Unit Reserve Shutdown Hours 0 0 0.0 0 0
16. Gross Thermal Energy Generated (MWH) 503 7 1 0 9 541 006 0 44 573 843 0 17 Gross Electrical Energy Generated (MWH) 174 000.0 3 330 700,0 15 474 000 0 18 Net Electrical Energy Generated (MWH) 158 169 0 3 119 869 0 14 447 494.0 19 Unit Service Factor 17.8% 51.4S 56 2s 20 Unit Availability Factor 17 8 51 4a 56.2a 21 Unit Capacity Factor (Using MDC Net) 17 4a 50 Os 53.8
22. Unit Capacity Factor (Using DER Net) 51
23. Unit Forced Outage Rate 82 2% 29 3
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

None

25. If Shutdown At End of Report Period, Estimated Date of Startup:

08 15 88 Forecast Achieved INITIAL CRITICALITY ~05 85 ~05 25 85 INITIAL ELECTRICITY ~06 85 06/610 85 COMMERCIAL OPERATION ll 85 ~01 28 86 0409A/22644

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"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 27 12' 28 13 29 14 30 15 31

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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 V

and supporting information.

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.

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.'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).

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SUMMARY

'OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-528 UNIT NAME PVNGS-1 DATE 08 10 88 COMPLETED BY T. J Bloom TELEPHONE 602 371-418 JULY 1988 07/01 0000 Reactor power at 100%.

07/06 1208 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 1373 Unit 1 entered Mode 4 (Hot Shutdown).

07/12 0546 Unit 1 entered Mode 5 (Cold Shutdown).

07/31 2400 Unit 1 remains in Mode 5.

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SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-528 UNIT NAME PVNGS-1 DATE COMPLETED BY T. J. Bloom Method of Cause and Corrective Duration Shutting System Component Action to No. Date Type"- Hours Reason2 Down Reactor3 LER No. Code4 Code5 Prevent Recurrence 7 7/6 F - 611;9 1-88-010 EA NSBU A fault on the 13.8KV Bus EA XFMR 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 Reason: Hethod: Exhibit F- Instructions S-Scheduled A-Equipment Failure (Explain) 1-Hanual for Preparation of the Data B-Haintenance or Test 2-Hanual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File 0-Regulatory Restriction 4-Continuation from (NUREG 0161)

E-Operator Training 5 License Examination Previous Honth F-Administrative 5-Reduction of 20X G-Operational Error or Greater in the Exhibit H-Same Source H-Other (Explain) Past 24 Hours 9-Other-(Explain)

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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. Unit Name: Palo Verde Nuclear Generatin Station Unit 2
2. Reporting Period: Jul 1988
3. Licensed Thermal Power (MWt): 3800
4. Nameplate Rating (Gross MWe): 1403
5. Design Electrical Rating (Net MWe): ~12 0
6. Maximum Dependable Capacity (Gross MWe): 1303
7. Maximum Dependable Capacity .(Net,MWe): 1221
8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7)

Since Last Report, Give Reasons: N A

9. Power Level to Which Restricted, If Any (Net MWe): one 10 Reasons Fo'r Restrictions,- If Any: N A This .Month" Yr.-to-Date Cumulative 11 Hours in Reporting Period 44 0 5 112.0 16 368.0 12 Number of Hours Reactor Was Critical 44 0 2 256.6 11 531.7 13 Reactor Reserve Shutdown Hours 0 0 0.0 0.0
14. Hours Generator On-Line 744 0 2 142 0 11 268.2
15. Unit Reserve Shutdown Hours 0 0 0.0 0.0 16 Gross Thermal Energy Generated (MWH) 2 794 833 0 813 952.0 41 021 119 0 17 Gross Electrical Energy Generated (MWH) 9 8 100 0 2 729 800.0 14 391 070.0
18. Net Electrical Energy Generated (MWH) 919 688 0 2 542 033.0 13 478 915.0
19. Unit Service Factor 100 0 41.9a 68 8a
20. Unit Availability Factor 100.0 41 9s 68.8a
21. Unit Capacity Factor (Using MDC Net) 101 2 40 7S 67.4s
22. Unit Capacity Factor (Using DER Net) 64.8
23. Unit Forced Outage Rate 0.0a 5 4
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

None

25. If Shutdown At End of Report Period, Estimated Date of Startup:

N A Forecast Achieved INITIAL CRITICALITY ~03 86 ~04 18 86 INITIAL ELECTRICITY 06 86 05 20 86 COMMERCIAL OPERATION ll 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 18 1 49 1 236 19 1 247 1 245 20 1 246 1 243 21 1 245 1 245 22 1 246 1 238 23 1 245 1 240 24 1 243 1 195 25 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).

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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 0000 Reactor power at 100%.

07/09 0050 Reactor power reduced to 95% for Isothermal Temperature Coefficient/Moderator Temperature Coefficient Testing.

07/10 2010 Reactor power at 100%.

07/30 0340 Reactor power reduced to 85% for circulating water system-(approx.) discharge valve maintenance and control element assembly/core protection calculator surveillance testing.

07/31 1535 Reactor power at 100%.

07/31 2400 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 Cause and Corrective Duration Shutting System Component Action to No. Date Type" Hours Reason Down Reactor LER No. Code Code Prevent Recurrence No Reactor Shutdowns or Significant Power Reductions occurred during the month.

F-Forced Reason: Hethod: Exhibit F-Instructions S-Scheduled A-Equipment Failure (Explain) 1-Hanua l for Preparation of the Data B-Maintenance or Test 2-Hanua l Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuation from (NUREG 0161)

E-Operator Training 5 License Examination Previous Month F-Administrative 5-Reduction of 20K G-Operational Error or Greater in the Exhibit H-Same Source H-Other (Explain) Past 24 Hours 9-Other-(Explain)

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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. Unit Name: Palo Verde Nuclear Generatin Station Unit 3
2. Reporting Period: Jul 1988
3. Licensed Thermal Power (MWt): 3800
4. Nameplate Rating (Gross MWe): 1403
5. Design Electrical Rating (Net MWe): 1270
6. Maximum Dependable Capacity (Gross MWe): 1303
7. Maximum Dependable Capacity (Net MWe): 1221
8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7)

Since Last Report, Give Reasons: N A

9. Power Level to Which Restricted, If Any (Net MWe): None 10 Reasons For Restrictions, If Any: N A This Month Yr.-to-Date Cumulative 0

11 Hours in Repo'rting Period 744 0 4 944 0 4 944.0 12 Number of Hours Reactor Was Critical 744 0 4 944 0 4 944.0

13. Reactor Reserve Shutdown Hours 0 0 0 0 0 0 14.'5. Hours Gen'erator On-Line 736 6 4 936 6 4 936.6 Unit Reserve Shutdown Hours 0 0 0 0 0.0
16. Gross Thermal Energy Generated (MWH) 2 780 396.0 18 385 572 0 18 385 572.0 17 Gross Electrical Energy Generated (MWH) 967 500.0 6 471 500 0 6 4 1 500.0 18 Net Electrical Energy Generated (MWH) 912 625.0 6 112 539.0 6 112 539.0 19 Unit Service Factor 99 Os 99.9 99.9 20 Unit Availability Factor 99 0 99.9a 99.9s 21 Unit Capacity Factor (Using MDC Net) 100 5 101 3 101 3 22 Unit Capacity Factor (Using DER Net) 97 4a 97.4a 23 Unit Forced Outage Rate 1 Oa O.la 24 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

None 25 If Shutdown At End of Report Period, Estimated Date of Startup:

08 16 88 Forecast Achieved INITIAL CRITICALITY ~07 8 ~10 25 8 INITIAL ELECTRICITY ~07 87 ~11 28 87 COMMERCIAL OPERATION ~09 8 ~01 08 88

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'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 18 1 247 1 254 19 1 248 1 256 20 1 245 1 254 21 1 248 1 251 22 1 247 1 245 23 1 202 1 251 24 1 234 il 1 251 25 1 213

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10 248 26 1 201 1 211 27 1 209 12 1 253 28 1 230 13 1 257 29 1 234 14 1 253 30 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.

cores'41 The fuel vendor for the next five reloads will 'be Combustion Engineering.

6. The number of fuel assemblies a) In the 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).

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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 1300 Reactor power at 100%.

07/24 1845 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 1815 Reactor power stabilized at 17%.

07/31 2400 Unit 3 is in Mode 1 with reactor power at approximately 8%.

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SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-530 UNIT NAME PVNGS-3 DATE COMPLETED BY T. J. Bloom Method of Cause and Corrective Duration Shutting System Component Action to No. Date Type1- Hours Reason2 Down Reactor LER No. Code4 Code5 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 Reason: Method: Exhibit F-Instructions S-Scheduled A-Equipment Failure (Explain) 1-Hanual for Preparation of the Data B-Maintenance or Test 2-Hanual Scram Entry Sheets for Licensee.

C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuation from (HUREG 0161)

E-Operator Training II License Examination Previous Honth F-Administrative 5-Reduction of 20K G-Operational Error or Greater in the Exhibit H-Same Source H-Other (Explain) Past 24 Hours 9-Other-(Explain)

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~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. (all w/attachments)

D. B. Karner J. A. Amenta A. C. Gehr M. J. Davis J. B. Martin INFO Records Center

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