ML17304A642

Monthly Operating Repts for Sept 1988 for Palo Verde Units 1,2 & 3

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.

2.

3.

4.

5.

6.

7.

8.

9.

10.

Unit Name:

Palo Verde Nuclear Generatin Station Unit 1 Reporting Period:

Se tember 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):

None Reasons For Restrictions, If Any:

N A 11

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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 Refuelin Outa e - 03 21 89 This Month 20 0

20 0 Yr.-to-Date 6

5 6 0 3 554 9

Cumulative 23 448 0

13 532 1

0 0 20.0 0 0 3

3 9 8 0.0 13 096 9

0.0 2 565 055 0

894 600 0

948.552.0 100 0 100 0 0.0 4 236 500 0

3 967 421.0 51 4 51 4 0.0 4

208 584 0 16 3

9 800'0 15 295 346 0

55 9

55 9

96.4 49 4 53 4 51.4s 30 6%

6 Months (Type, Date, and Duration of Each):

ODas

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

N A INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION 8810210403 880930 0409A/2264A PDR ADQCgr 05000528 R

PDC Forecast Achieved

~05 85

~05 25 85

~06 85

~06 10 85

~11 85

~01 28 86 gszH

~

~

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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 863 986 17 18 1 232 1

34 1 033 1 110 19 20 1 245 1 214 1 137 21 1 230 1 149 22 1 237 7

10 1 150 1 139 1 128 1 139 1 140 23 25 26 27 1 235 1 245 1

48 1 249 1 253 12 1 144 1 180 28 29 1 256 1 256 14 15 1 203 1 20 30 31 1 256 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 I

09/03 0916 1400 Reactor power is at 80%.

t 1

l Reactor power is at 87%.

09/04 1200 09/09 2017 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 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 (approx.)

Reactor power is increased to 95% as allowed by condenser back pressure.

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

09/18 1900 (approx.)

Reactor power is increased to 98%.

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%.

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SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-528 UNIT NAME PVNGS-1 DATE COMPLETED BY T. J.

Bloom Method of Duration Shutting System Component No.

Date Typei 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-Haintenance or Test C-Refuel ing 0-Regulatory Restriction E-Operator Training 8 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 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

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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.

2.

3.

4.

5.

6.

7.

8.

9.

10 Unit Name:

Pa o Verde Nuclear Generatin Station Unit 2 Reporting Period:

Se tember 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):

None Reasons For 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 20 0

Yr.-to-Date 65760 Cumulative 1

832.0 20 0 0 0 20 0 3

206 0 0 3 606 0

12 995 7

0.0 12 732 2

0 0 0 0 0 0 2 702 001 0

941 800.0 886 320 0 100 0%

100 0

13 228 989 0

4 606 200 0

4 306 429 0

54 8

54 8

46 436 156.0 16 267 470.0 15 243 311 0

71 4a 1 4 100 8

53 6

70.0z 6

3 4 8S 6 Months (Type, Date, and Duration of Each):

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

N A INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Forecast Achieved

~03 86 04/618 86

~06 86

~05 20 86

'~11 86

'09 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 1 066 DAY 17 AVERAGE DAILY POWER LEVEL 1 247 1 234 18 1 247 1 23 19 1 245 1 239 20 1 242 1 243 1 070 1 244 21 22 23 1 244 1 249 1 249 1 243 24 1 248 1 243 25 1 24 10 12 14 15 1 242 1 242 1 246 1 252 1 248 1 250 26'7 28 29 30 31 1 246 1 247 1 249 1 249 1 249 16 1 24

)

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.

5.

To be determined I

f 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 09/01 0000 0230 Reactor power is at 68%.

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

09/01 09/01 09/06 1235 1648 1216 Reactor power increased to 908

~

Reactor power is at 100%.

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 09/06 09/06 09/30 1757 I

2030 2222 2400 Reactor power is at 70$.

Reactor power is at 90%.

Reactor power is at 100%.

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 No.

Date Typei Duration Hours Reason2 Method of Shutting Down Reactor LER No.

System Component Code4 Code5 Cause and Corrective Action to 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 S-Scheduled Reason:

A-Equipment Failure (Explain)

B-Naintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training 5 License Examination F-Administrative G-Operational Error H-Other (Explain)

Nethod:

1-Nanual 2-Nanual Scram 3-Automatic Scram 4-Continuation from Previous Nonth 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 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.

2.

3.

4.

5.

6.

7.

8.

9.

10 Unit Name:

Palo Verde Nuclear Generatin Station Unit 3 Reporting Period:

Se tember 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 Restricti'ons, If Any: N A This Month Yr.-to-Date Cumulative 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 Refuelin Outa e

- 03 03 89 20 0 6 408 0

6 408 0

20 0 5 993 5 993 7

0 0 20 0 0 0 5900 0 0 5 970 0 0 0 0 0 0 0 2 568 41 0 896 00.0 846 384 0 100 0 100 0

22 038 2 0 43 200.0 289 474.0 93 2

93 2

22 038 72 0 743 200 0 7 289 474 0

93 2

93 2

96 3a 93 2

93 2

89.6 6

8 92.6a 0.0a 6 Months (Type, Date, and Duration of Each):

70 Da s

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

N A INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Forecast

~087

~07 8

~09 87 Achieved

~10 25 8

ll 28 8

01 08 88

AVERAGE DAILY UNIT POWER LEVEL MONTH: SEPTEMBER 1988 DOCKET NO.

0-530 UNIT NAME PVNGS-3 DATE 10 11 88 COMPLETED BY T J

Bloom TELEPHONE 602 371-4187 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1 252 17 1 261 1 24 18 1 258 1 250 1 251 19 20 1 259 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 1 253 26 27 1 252 1 256 12 13 14 1 256 1 262 1 263 28 29 30 1 255 1 256 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).

0 l

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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 09/04 09/04 09/15-09/16 09/22 09/22 09/22 09/24 09/24 09/24 09/25 09/25 09/30 0000 0841 1035 1035 1010 0733 (approx.)

1325 2350 0603 1200 (approx.)

1900 (approx.)

0034 1526 2400 Reactor power is at 100%.

Reactor power reduced to approximately 98%

while the Core Operating Limit Supervisory System was inoperable.

Reactor power is at 100%.

Reactor power was reduced to 88% while repairs to the failed C2 control element assembly calculator were made.

Reactor power is at 100%.

Reactor power reduced to 40% in order to repair a condenser tube leak.

Reactor power reduced to 20$ due to Chemistry concerns.

Reactor power at 298 Reactor power is at 50$.

Reactor power is at 70%.

Reactor power is at 97.5%.

Reactor power is reduced to 90%

in order to lower feedwater heater '2C'hell pressure..

Reactor power is at 100%.

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 No.

Date Typei Duration Hours Reason2 Method of Shutting System Component Down Reactor LER No.

Code4 Code3 Cause and Corrective Action to 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.

F-Forced S-Scheduled Reason:

A-Equipment Failure (Explain) 8-Haintenance or Test C-Refueling 0-Regulatory Restriction E-Operator Training 5 License Examinati F-Administrative G-Operational Error H-Other (Explain) on

- 3 Hethod:

1-Hanual" 2-Hanua l Scram 3-Automatic Scram 4-Continuation from Previous Honth 5-Reductio'n of 20K or Greater in the Past 24 Hours 9-Other-(Explain)

Exhibi t F-Instruct i ons for Preparation of the Oata Entry Sheets for Licensee Event Report (LER) File (HUREG 0161)

Exhibit H-Same Source Arizona Nuclear Power Project P.O. BOX 52034

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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

'ery truly yours, J.

G. Haynes Vice President Nuclear Production JGH/TJB/j le Attachments cc:

E.

E. Van Brunt, Jr.

D. B. Karner J.

A. Amenta A. C. Gehr M. J. Davis J.

B. Martin INPO Records Center (all w/attachments)

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