ML17304A797
ML17304A797 | |
Person / Time | |
---|---|
Site: | Palo Verde ![]() |
Issue date: | 11/30/1988 |
From: | Borst S, Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
References | |
254-00052-JGH-S, 254-52-JGH-S, NUDOCS 8812190278 | |
Download: ML17304A797 (33) | |
Text
gCCE~~TED DISTR>BUTTON DEMONSTRX~ON SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8812190278 DOC.DATE: 88/11/30 NOTARIZED: NO DOCKET I 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 BORST,S.G. Arizona Nuclear Power Project (formerly Arizona Public Serv HAYNES,J.G. Arizona Nuclear Power Project (formerly Arizona Public Serv R RECIP.NAME RECIPIENT AFFILIATION I
SUBJECT:
Monthly operating repts for Nov 1988 for Palo Verde Nuclear Generating Station, Units 1,2 & 3.W/881215 CODE: IE24D COPIES RECEIVED:LTR i ENCL ltr.'ISTRIBUTION
( SIZE:
TITLE: Monthly Operating Report (per Tech Specs)
NOTES:Standardized plant. 05000528 Standardized plant. 05000529 ~
Standardized plant. 05000530 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 0 PD5 PD 5 5 CHAN,T 1 0 DAVIS,M 1 0 DAVIS,M.J. 1 0 INTERNAL: 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.
RR/DR P RPB 10 1 1 NUDOCS-ABSTRACT 1 1' EG FIX 01 1 1 RGN5 1 EXTERNAL: EG&G SIMPSON,F 1 1 EG&G WILLIAMSI S 1 1 LPDR '1 1 NRC PDR 1 1 NSIC 1 1 R
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Arizona Nuclear Power Project P.O. BOX 52034 ~ PHOENIX. ARIZONA85072-2034 254-00052-JGH/SGB December 15, 1988 Docket Nos. STN 50-528/529/530 Document Control Desk U. S. Nuclear Regulatory Commission Mail Station Pl-137 Washington, D.C. 20555
Dear Sirs:
Sub) ect: Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3 Monthly Operating Reports for November 1988 File: 88-024-404 88-056-026 Attached are the Monthly Operating Reports for November 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. S. G. Borst, at (602) 371-4092.
Very truly yours, J. G. Ha nes Vice President Nuclear Production JGH/SGB/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 T. J. Polich INPO Records Center Z EP+
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NRC MONTHLY OPERATING REPORT DOCKET NO. 50-528 UNIT NAME PVNGS-1 DATE 12 09 88 COMPLETED BY S G. Borst TELEPHONE 602 3 1-4092 OPERATING STATUS
- 1. Unit Name: Palo Verde Nuclear Generatin Station Unit
- 2. Reporting Period: November 1988
- 3. Licensed'hermal 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 8 040 0 24 912 0
- 12. Number of Hours Reactor Was Critical 20 0 5 018 9 14 996.1 13 Reactor Reserve Shutdown Hours 0.0 0 0 0 0 14 Hours Generator On-Line 20 0 4 843 8 14 560 9 15 Unit Reserve Shutdown Hours 0 0 0 0 0 0
- 16. Gross Thermal Energy Generated (MWH) 2 08 768 0 17 543 643 0 52 576 480 0 17 Gross Electrical Energy Generated (MWH) 951 000 0 6 110 800 0 18 254 100 0 18 Net Electrical Energy Generated (MWH) 902 636 0 5 43 476 0 17 071 401.0
- 19. Unit Service Factor 100 0 60.2 58 4
- 20. Unit Availability Factor 100 0 60 2% 58 4
- 21. Unit Capacity Factor "
MDC Net) 'Using 102 7 58 5 56.1
- 22. Unit Capacity Factor (Using DER. Net) 54.0 23 Unit Forced Outage Rate 28.4 24 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refuelin Outa e-'- 03 21 89 0 Da s
- 25. If Shutdown'At End of Report Period, Estimated'ate of Startup:
N A Forecast Achieved INITIAL CRITICALITY ~05 85 ~05 25 85 INITIAL ELECTRICITY ~06 85 06I610 85 COMMERCIAL OPERATION ~11 85 ~01 28 86 0409A/2264A 8812190278 881130 PDR R
ADOCK 05000528 PDC ~E>% ( )
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ERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-528 UNIT NAME PVNGS-1 DATE 12 09 88 COMPLETED BY S G Borst TELEPHONE 602 3 1-4092 MONTH: NOVEMBER 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 17 64 1 255 18 1 264 1 25 19 1 266 1 214 20 1 26 1 091 21 1 26 1 249 22 1 266 1 259 23 1 265 1 254 24 1 265 1 255 25 1 265 10 1 258 26 1 264 1 259 27 1 265 12 1 262 28 1 264 13 1 261 29 1 260 14 1 259 30 1 256 15 1 63 16 1 63
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REFUELING INFORMATION DOCKET NO. 50-528 UNIT NAME PVNGS-1 DATE 12 09 88 COMPLETED BY S G Borst TELEPHONE 602 3 1-4092
- 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 Yes, as a minimum it will include the following: 3/4 1.3.6, 3/4 2.3, 3/4 2.4.
- 4. Sche'duled 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 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).
SUMMAR F OPERATING EXPERIENCE FOR THE NTH DOCKET NO. 50-528 UNIT NAME PVNGS-1 DATE 12 09 88 COMPLETED BY S G Borst TELEPHONE 602 3 1-4092 NOVEMBER 1988 11/01 0000 Reactor power is at 100%.
11/04 1845 Reactor power reduced to 87% for control element assembly calculator surveillance testing.
11/06 0300 Reactor power is at 100%.
11/06 0450 Reactor power reduced to 97% for ASI control.
(approx.)
11/06 1042 Reactor power is at 100%.
11/30 2400 Reactor power is at 100%.
SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-528-UNIT NAME PVNGS-1 DATE COMPLETED BY S. G. Sorst Method of Cause and Corrective Duration Shutting System Component Action to No. Date Typei Hours Reason2 Down Reactor LER No. Code4 Code5 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-Hanua l 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 5 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)
NRC MONTHLY OPERATING REPORT DOCKET NO. 50-529 UNIT NAME PVNGS-2 DATE 12 09 88 COMPLETED BY S G Borst TELEPHONE 602 3 1-4092 OPERATING STATUS
- 1. Unit Name: Palo Verde Nuclear Generatin Station Unit 2
- 2. Reporting Period: November 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: A
- 9. Power Level to Which Restricted, If Any (Net MWe): None 10 Reasons For Restrictions, If Any: A This Month Yr.-to-Date Cumulative
- 11. Hours in Reporting Period 720 0 8 0140 0 19 296 0
- 12. Number of Hours Reactor Was Critical 541 4 5 006 0 14 281 1
- 13. Reactor Reserve Shutdown Hours 0 0 0 0 0 0
- 14. Hours Generator On-Line 532 9 4 882 9 14 009 1
- 15. Unit Reserve Shutdown Hours 0 0 0 0 0 0 16 Gross Thermal Energy Generated (MWH) 1 909 336 0 1 952 885 0 51 160 052 0
- 17. Gross Electrical Energy Generated (MWH) 662 800 0 6 252 200.0 1 913 470.0 18 Net Electrical Energy Generated (MWH) 615 242 0 5 847 243 0 16 784 125 0 19 Unit Service'actor 74 Oa 60 7% 2 6s 20 Unit Availability Factor 74 0 60 2 6a 21 Unit Capacity, Factor (Using MDC 0 0 59 6 1 2 Capacity Factor Net)'nit 22.
(Using DER Net) 68 5a
- 23. Unit Forced Outage Rate 5 6a
- 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 ~11 86 09 19 86
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VERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-529 UNIT NAME PVNGS-2 DATE 12 09 88 COMPLETED BY S G 602 3 Bors'ELEPHONE 1-4092 MONTH'OVEMBER 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1 246 17 1 248 18 1 251 19 1 250 20 1 251 21 1 250 22 1 243 23 1 239 24 56 1 242 25 639 10 1 46 26 1 130 1 24 27 1 263 12 1 250 28 1 234 13 1 240 29 1 234 14 1 245 30 1 244 15 1 206 16
REFUELING INFORMATION DOCKET NO. 50-529 UNIT NAME PVNGS-2 DATE 12 09 88 COMPLETED BY S G Borst TELEPHONE 602 3 1-4092
- 1. Scheduled date for next refueling shutdown.
09/15/89
- 2. Scheduled date for restart following refueling.
11/24/89 l
- 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 proposed licensing action and supporting information.
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).
l, SU F OPERATING EXPERIENCE FOR TH NTH DOCKET NO. 50-529 UNIT NAME PVNGS-2 DATE 12 09 88 COMPLETED BY S G Borst TELEPHONE 602 3 1-4092 11/01 0000 Unit in Mode 1 - Reactor Power 100%.',
11/13 1639 Power reduction to 92% due to inoperability of Core Operating Limit Supervisory System program.
11/13 2135 Reactor power at 100%.
11/15 2001 Plant shutdown initiated to investigate unidentified reactor coolant system leakage.
11/16 0237 Reactor trip occurred due to Steam Generator low level at about 10$ Power during the plant shutdown and the unit was stabilized in Mode 3.
11/17 0222 Unit entered Mode 4.
11/22 2341 Unit entered Mode 3.
11/23 1315 Unit entered Mode 2.
11/23 1746 Unit entered Mode 1.
11/23 2145 Main Turbine synchronized to grid.
11/23 2155 Rector power is at 19%.
11/24 0434. Reactor power maintained at 56% for feedwater heater repairs.
11/26 0145 Reactor power at 72%.
11/26 1315 Reactor power at 100%.
11/28 1725 Reactor power reduction to 90% for isolation of the "A" Low Pressure Feedwater Heater string, 11/29 0937 Reactor power at 100%.
11/30 2400 Unit,in Mode 1 - Reactor Power at 100%.
SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-529 .
UNIT NAME PVNGS-2 DATE COMPLETED BY S. G.'.Borst Method of Cause and Corrective Duration Shutting System Component Action to No. Date Typei Hours Reason2 Down Reactor LER No. Code4 Code5 Prevent Recurrence 5 11/16 F 187.1 H 2-88-014 AB ISV Reactor trip on Low Steam Generator Level occurred at 108 power during a shutdown evaluate an unidentified RCS leak. The trip was due to a combination of events including a site modification which lowered the minimum speed of the main feedwater pump, operator actions to adjust the main feedwater pump speed bias and a procedure which was not specific enough. The procedure has been revised, the event will be included in the operations requalification training program, and the site modification program is bein evaluated.
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-Ref ue l ing 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuation from (NUREG 0161)
E-Operator Training & License Examination Previous Honth F-Administrative 5-Reduction of 20K G-Operational Error or Greater in the Exhibit H-Same Source N-Other (Explain) Past 24 Hours 9-Other-(Explain)
III t NRC MONTHLY OPERATING REPORT t
DOCKET NO ~ 0-530 UNIT NAME PVNGS-3 DATE 12 09 88 COMPLETED BY S. G Borst TELEPHONE 602 3 1-4092 OPERATING STATUS
- 1. Unit Name: Palo Verde Nuclear Generatin Station Unit 3
- 2. Reporting Period: ovember 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): ~122
- 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 720 0 7820 872 0
- 12. Number of Hours Reactor Was Critical 720 0 7 457 7 45 .7 13 Reactor Reserve Shutdown Hours 0 0 0.0 0.0
- 14. Hours Generator On-Line 720 0 7 434 0 7 434.0
- 15. Unit Reserve Shutdown Hours 0 0 0 0 0 0
- 16. Gross Thermal Energy Generated (MWH) 2 671 9 8 0 27 516 564 0 2 516 564 0
- 17. Gross Electrical Energy Generated (MWH) 938 400 0 9 664 100 0 9 664 100.0 I
18 Net Electrical Energy Generated (MWH) 9 103 692 0 9 103 692.0 19 Unit Service Factor 94 4 94 4 20 Unit Availability Factor 94 4 94.4a 21 Unit Capacity Factor (Using MDC Net) 94 7 94 7a
- 22. Unit Capacity Factor 91 1 23 Unit Forced Outage Rate 24 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refuelin Outa e - 03 03 89 - 0 Da s
- 25. If Shutdown At End of Report Period, Estimated Date of Startup:
N A Forecast Achieved INITIAL CRITICALITY ~07 87 ~10 25 87 INITIAL ELECTRICITY 07708 11/128 87 COMMERCIAL OPERATION ~09 8 ~01 08 88
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VERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-530 UNIT NAME PVNGS-3 DATE 12 09 88 COMPLETED BY S G Borst TELEPHONE 602 371-4092 MONTH: NOVEMBER 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 249 17 1 48 1 248 18 1 253 1 250 19 1 255 1 253 20 1 254 1 255 21 1 253 1 255 22 1 252 1 253 23 1 251 1 244 24 1 252 1 253 25 1 253 10 '1 257 26 1 252 1 074 27 1 251 12 835 28 1 252 13 1 093 29 258 14 '
256 30' 1 264 15 1 261 16 1 255
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REFUELING INFORMATION DOCKET NO. 50-530 UNIT NAME PVNGS-3 DATE 12 09 88 COMPLETED BY S. G. Borst TELEPHONE 602 3 1-4092
- 1. Scheduled date for next refueling shutdown.
03/03/89
- 2. Scheduled'date for restart following refueling.
05/13/89
- 3. Vill refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
'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 2.33/4 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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SUMMAR F OPERATING EXPERIENCE FOR THE . NTH DOCKET NO. 50-530 UNIT NAME PVNGS-3 DATE 12 09 88 COMPLETED BY S G Borst TELEPHONE 602 3 1-4092 NOVEMBER 1988 11/01 0000 Reactor power is at 100%.
11/11 0630 Reactor power reduced to 83% for rod testing/control element (approx.) assembly calculator surveillance testing.
11/12 0130 Reactor power reduced to 68% for replacement of feedwater pump (approx.) "B" suction strainer.
11/13 1457 Reactor power is at 91%.
11/13 1835 Reactor power is at 100%.
11/30 2400 Reactor power is at 100%.
SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-530 ~
UNIT NAME PVNGS-3 DATE COMPLETED BY S. G. 'Borst Method of Cause and Corrective Duration Shutting System Component Action to No. Date Type1 Hours Reason2 Down Reactor LER No. Code4 Code~ Prevent Recurrence No Reactor Shutdowns or Significant Power Reductions Occurred During the Month.
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-Manual 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)