ML17304A642

Monthly Operating Repts for Sept 1988 for Palo Verde Units 1,2 & 3.W/880914 Ltr

ML17304A642
Person / Time
Site:	Palo Verde
Issue date:	09/30/1988
From:	Bloom T, Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
212-00422-JGH-T, 212-422-JGH-T, NUDOCS 8810210403
Download: ML17304A642 (31)

Text

NRC MONTHLY OPERATING REPORT DOCKET NO. 50-528 UNIT NAME PVNGS-1 DATE 10 11 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: Se tember 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): None

10. Reasons For Restrictions, If Any: N A This Month Yr.-to-Date Cumulative 11 ~ Hours in Reporting Period 20 0 6 5 6 0 23 448 0

12. Number of Hours Reactor Was Critical 20 0 3 554 9 13 532 1

13. Reactor Reserve Shutdown Hours 0 0 0 0 0.0

14. Hours Generator On-Line 20.0 3 3 9 8 13 096 9

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 2 565 055 0 4 208 584 0

17. Gross Electrical Energy Generated (MWH) 894 600 0 4 236 500 0 16 3 9 800'0

18. Net Electrical Energy Generated (MWH) 948.552.0 3 967 421.0 15 295 346 0

19. Unit Service Factor 100 0 51 4 55 9

20. Unit Availability Factor 100 0 51 4 55 9

21. Unit Capacity Factor (Using MDC Net) 96.4 49 4 53 4

22. Unit Capacity Factor (Using DER Net) 51.4s

23. Unit Forced Outage Rate 30 6%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refuelin Outa e - 03 21 89 ODas

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

N A Forecast Achieved INITIAL CRITICALITY ~05 85 ~05 25 85 INITIAL ELECTRICITY ~06 85 ~06 10 85 COMMERCIAL OPERATION ~11 85 ~01 28 86 0409A/2264A 8810210403 880930 PDR ADQCgr 05000528 gszH R PDC

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-528 UNIT NAME PVNGS-1 DATE 10 11 88 COMPLETED BY T J Bloom TELEPHONE 602 3 1-418 MONTH'EPTEMBER 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 863 17 1 232 986 18 1 34 1 033 19 1 245 1 110 20 1 214 1 137 21 1 230 1 149 22 1 237

, 7 1 150 23 1 235 1 139 1 245 1 128 25 1 48 10 1 139 26 1 249 1 140 27 1 253 12 1 144 28 1 256 1 180 29 1 256 14 1 203 30 1 256 15 1 20 31 16 1 227

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0 REFUELING INFORMATION DOCKET NO. 50-528 UNIT NAME PVNGS-1 DATE 10 11 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 amendment2 Yes, as a minimum it will include the following: 3/4 1.3.6.

4. Scheduled date for submitting proposed licensing action and supporting information.

01/89.

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 reload will be Combustion Engineering.

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 10 11 88 COMPLETED BY T J. Bloom TELEPHONE 602 371-418 SEPTEMBER 1988 09/01 0000 Reactor power is at 38%.

'9/01 0916 Reactor power is at 80%.

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1 l 09/03 1400 Reactor power is at 87%.

09/04 , 1200 Reactor power is increased to 91% and held there while conducting steam 'ypass valve testing in order to resolve 08/21/88 post trip review concerns'eactor 09/09 2017 power is reduced to 88% to conduct control element assembly calculator surveillance testing.

09/10 0907 Reactor power is returned to 91%.

09/13 0827 Steam bypass valve concerns resolved and reactor power is increased to 93% where the plant is limited by condenser back pressure due to the removal of circulating water pump 'D'rom service.

09/14 1900 Reactor power is increased to 95% as allowed by condenser back (approx.) pressure.

09/16 0430 Reactor power is increased to 97% for Axial Shape Index (ASI) control.

09/18 1900 Reactor power is increased to 98%.

(approx.)

09/24 1030 Reactor power is increased to 100% following resolution of the circulating water pump problems.

09/30 2400 Reactor power is at 100%.

(J 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 Typei 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-Hanual for Preparation of the Data B-Haintenance or Test 2-Hanual Scram Entry Sheets for Licensee C-Refuel ing 3-Automatic Scram Event Report (LER) File 0-Regulatory Restriction 4-Continuation from (HUREG 0161)

E-Operator Training 8 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)

4 NRC MONTHLY OPERATING REPORT DOCKET NO. 50-529 UNIT NAME PVNGS-2 DATE 10 11 88 COMPLETED BY T J Bloom TELEPHONE 602 3 1-418 OPERATING STATUS

1. Unit Name: Pa o Verde Nuclear Generatin Station Unit 2

2. Reporting Period: Se tember 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): None 10 Reasons For Restrictions, If Any: N A This Month Yr.-to-Date Cumulative

11. Hours in Reporting Period 20 0 65760 1 832.0

12. Number of Hours Reactor Was Critical 20 0 3 206 12 995 7

13. Reactor Reserve Shutdown Hours 0 0 0 0 0.0

14. Hours Generator On-Line 20 0 3 606 0 12 732 2

15. Unit Reserve Shutdown Hours 0 0 0 0 0 0

16. Gross Thermal Energy Generated (MWH) 2 702 001 0 13 228 989 0 46 436 156.0

17. Gross Electrical Energy Generated (MWH) 941 800.0 4 606 200 0 16 267 470.0

18. Net Electrical Energy Generated (MWH) 886 320 0 4 306 429 0 15 243 311 0

19. Unit Service Factor 100 0% 54 8 71 4a

20. Unit Availability Factor 100 0 54 8 1 4

21. Unit Capacity Factor (Using MDC Net) 100 8 53 6 70.0z

22. Unit Capacity Factor (Using DER Net) 6 3

23. Unit Forced Outage Rate 4 8S

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 04/618 86 INITIAL ELECTRICITY ~06 86 20 86 COMMERCIAL OPERATION '~11 86 '09~05 19 86

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-529 UNIT NAME PVNGS-2 DATE 10 11 88 COMPLETED BY T J Bloom TELEPHONE 602 3 1-418 MONTH: SEPTEMBER 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1 066 17 1 247 1 234 18 1 247 1 23 19 1 245 1 239 20 1 242 1 243 21 1 244 1 070 22 1 249 1 244 23 1 249 1 243 24 1 248 1 243 25 1 24 10 1 242 1 246 26'7 1 242 1 247 12 1 246 28 1 249 1 252 29 1 249 14 1 248 30 1 249 15 1 250 31 16 1 24

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REFUELING INFORMATION DOCKET NO. 50- 29 UNIT NAME PVNGS-2 DATE 10 11 88 COMPLETED BY T J Bloom TELEPHONE 60 3 1-418

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 amendment'E To be determined

4. Scheduled date for submitting proposed licensing action and supporting information.

To be determined I f

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).

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-529 UNIT NAME PVNGS-2 DATE 10 11 88 COMPLETED BY T J Bloom TELEPHONE 602 3 1-418 SEPTEMBER 1988 09/01 0000 Reactor power is at 68%.

09/01 0230 Reactor power was increased to 75% power where it was stopped due to increased sodium levels in the '1A'ondenser Hotwell.

09/01 1235 Reactor power increased to 908 ~

09/01 1648 Reactor power is at 100%.

09/06 1216 Reactor Power Cutback to approximately 52% was initiated due to the loss of the 'B'ain feedwater pump on low suction pressure.

The feedwater pump tripped when air was isolated to the miniflow recirculation valve during corrective maintenance.

09/06 1757 Reactor power is at 70$ .

I 09/06 2030 Reactor power is at 90%.

09/06 2222 Reactor power is at 100%.

09/30 2400 Reactor power is at 100%.

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SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-529 UNIT NAME PVNGS-2 DATE COMPLETED BY T. J. Bloom Method of Cause and Corrective Duration Shutting System Component Action to No. Date Typei Hours Reason2 Down Reactor LER No. Code4 Code5 Prevent Recurrence 4 09/06 N/A H N/A N/A N/A Reactor Power cutback to approximately 60%

initiated due to the loM of the 'B'ain feedwater pump on low suction pressure. The feedwater pump tripped when air was isolated to the miniflow recirculation valve during corrective maintenance.

F-Forced Reason: Nethod: Exhibit F-Instructions S-Scheduled A-Equipment Failure (Explain) 1-Nanual for Preparation of the Data B-Naintenance or Test 2-Nanual 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 Nonth 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) k.

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NRC MONTHLY OPERATING REPORT DOCKET NO. 50-530 UNIT NAME PVNGS-3 DATE 10 11 88 COMPLETED BY T. J. Bloom TELEPHONE 602 3 1-418 OPERATING STATUS

1. Unit Name: Palo Verde Nuclear Generatin Station Unit 3

2. Reporting Period: Se tember 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 Restricti'ons, If Any: N A This Month Yr.-to-Date Cumulative

11. Hours in Reporting Period 20 0 6 408 0 6 408 0

12. Number of Hours Reactor Was Critical 20 0 5 993 5 993 7

13. Reactor Reserve Shutdown Hours 0 0 0 0 0 0 14 Hours Generator On-Line 20 0 5900 5 970 0 15 Unit Reserve Shutdown Hours 0 0 0 0 0 0 16 Gross Thermal Energy Generated (MWH) 2 568 41 0 22 038 2 0 22 038 72 0 17 Gross Electrical Energy Generated (MWH) 896 00.0 43 200.0 743 200 0 18 Net Electrical Energy Generated (MWH) 846 384 0 289 474.0 7 289 474 0

19. Unit Service Factor 100 0 93 2 93 2

20. Unit Availability Factor 100 0 93 2 93 2

21. Unit Capacity Factor (Using MDC Net) 96 3a 93 2 93 2 22 Unit Capacity Factor (Using DER Net) 92.6a 89.6 23 Unit Forced Outage Rate 0.0a 6 8 24 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refuelin Outa e - 03 03 89 70 Da s

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

N A Forecast Achieved INITIAL CRITICALITY ~087 25 8 INITIAL ELECTRICITY ~07 8 ll

~10 28 8 01 08 88 COMMERCIAL OPERATION ~09 87

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 0-530 UNIT NAME PVNGS-3 DATE 10 11 88 COMPLETED BY T J Bloom TELEPHONE 602 371-4187 MONTH: SEPTEMBER 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1 252 17 1 261 1 24 18 1 258 1 250 19 1 259 1 251 20 1 256 1 256 21 1 259 1 258 22 513 1 258 23 259 1 25 24 813 1 255 25 1 182 10 1 256 26 1 252 1 253 27 1 256 12 1 256 28 1 255 13 1 262 29 1 256 14 1 263 30 1 256 15 1 168 16 1 20

REFUELING INFORMATION DOCKET NO. 50-530 UNIT NAME PVNGS-3 DATE 10 11 88 COMPLETED BY T J Bloom TELEPHONE 602 3 1-418

1. Scheduled date for next refueling shutdown.

03/03/89

2. Scheduled date for restart following refueling.

05/13/89

3. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendments Yes, these are expected to include the following: 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.

12/88

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 reload will be Combustion Engineering.

6. The number of fuel assemblies a) In the core. 241 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 VNGS-3 DATE 10 11 88 COMPLETED BY T J Bloom TELEPHONE 602 3 1-418 SEPTEMBER 1988 09/01 0000 Reactor power is at 100%.

09/04 0841 Reactor power reduced to approximately 98% while the Core Operating Limit Supervisory System was inoperable.

09/04 1035 Reactor power is at 100%.

09/15- 1035 Reactor power was reduced to 88% while repairs to the failed C2 control element assembly calculator were made.

09/16 1010 Reactor power is at 100%.

09/22 0733 Reactor power reduced to 40% in order to repair a condenser tube (approx.) leak.

09/22 1325 Reactor power reduced to 20$ due to Chemistry concerns.

09/22 2350 Reactor power at 298 09/24 0603 Reactor power is at 50$ .

09/24 1200 Reactor power is at 70%.

(approx.)

09/24 1900 Reactor power is at 97.5%.

(approx.)

09/25 0034 Reactor power is reduced to 90% in order to lower feedwater heater '2C'hell pressure..

09/25 1526 Reactor power is at 100%.

09/30 2400 Reactor power is at 100%.

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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 Typei Hours Reason2 Down Reactor LER No. Code4 Code3 Prevent Recurrence 8 09/22 N/A N/AP N/AP N/AP Reactor power reduced to 20% in order to repair condenser tube leak.

- 3 F-Forced Reason: Hethod: Exhibi t F- Instruct i ons S-Scheduled A-Equipment Failure (Explain) 1-Hanual" for Preparation of the Oata 8-Haintenance or Test 2-Hanua l Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File 0-Regulatory Restriction 4-Continuation from (HUREG 0161)

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

Arizona Nuclear Power Project P.O. BOX 52034 ~ PHOENIX. ARIZONA85072-2034 212-00422-JGH/TJB September 14, 1988 Docket Nos. STN 50-528/529/530 Document Control Desk U. S. Nuclear Regulatory Commission Mail Station Pl-137 Washington, D.C. 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2 and 3 Monthly Operating Reports for September 1988 File: 88-024-404 88-056-026 Attached are the Monthly Operating Reports for September 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 truly yours, 'ery J. G. Haynes Vice President Nuclear Production JGH/TJB/j le 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 INPO Records Center

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