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 ltr.'ISTRIBUTION CODE: IE24D COPIES RECEIVED:LTR i ENCL
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SIZE:
TITLE: Monthly Operating Report (per Tech Specs)
NOTES:Standardized plant.
Standardized plant.
Standardized plant.
05000528 05000529 ~
05000530 RECIPIENT ID CODE/NAME PD5 LA CHAN,T DAVIS,M.J.
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Arizona Nuclear Power Project P.O. BOX 52034
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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.
D. B. Karner J.
A. Amenta A. C. Gehr M. J. Davis J.
B. Martin T. J. Polich INPO Records Center (all w/attachments)
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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.
2.
3.
4.
5.
6.
7.
8.
9.
10.
Unit Name:
Palo Verde Nuclear Generatin Station Unit Reporting Period:
November 1988 Licensed'hermal 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 Refuelin Outa e-'-
03 21 89 This Month 20 0 20 0 0.0 20 0
0 0 2
08 768 0 951 000 0
902 636 0
100 0 100 0 102 7
6 Months (Type, 0 Da s Yr.-to-Date 8 040 0 Cumulative 24 912 0
5 018 9
14 996.1 0 0 4 843 8
0 0 14 560 9
0 0 0 0 17 543 643 0
6 110 800 0
5 43 476 0
60.2 60 2%
52 576 480 0
18 254 100 0
17 071 401.0 58 4 58 4 58 5
56.1 54.0 28.4
- Date, and Duration of Each):
- 25. If Shutdown'At End of Report Period, Estimated'ate of Startup:
N A INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Forecast Achieved
~05 85
~05 25 85
~06 85 06I610 85
~11 85
~01 28 86 0409A/2264A 8812190278 881130 PDR ADOCK 05000528 R
~E>%
(
)
t I
jt
ERAGE DAILYUNIT 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 1 255 17 18 64 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 1 259 26 27 1 264 1 265 12 13 14 1 262 1 261 1 259 28 29 30 1 264 1 260 1 256 15 1
63 16 1
63
r I
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 11/04 1845 Reactor power is at 100%.
Reactor power reduced to 87%
for control element assembly calculator surveillance testing.
11/06 11/06 11/06 11/30 0300 0450 (approx.)
1042 2400 Reactor power is at 100%.
Reactor power reduced to 97% for ASI control.
Reactor power is at 100%.
Reactor power is at 100%.
SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-528-UNIT NAME PVNGS-1 DATE COMPLETED BY S.
G. Sorst No.
Date Typei Duration Hours Reason2 Method of Shutting Down Reactor LER No.
System Component Code4 Code5 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-Refueling D-Regulatory Restriction E-Operator Training 5 License Examination F-Administrative G-Operational Error H-Other (Explain) Hethod:
1-Hanual 2-Hanua l 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
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.
2.
3.
4.
5.
6.
7.
8.
9.
10 11.
12.
13.
14.
15.
16 17.
18 19 20 21 22.
23.
24.
25.
Unit Name:
Palo Verde Nuclear Generatin Station Unit 2 Reporting Period:
November 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:
A Power Level to Which Restricted, If Any (Net MWe):
None Reasons For Restrictions, If Any:
A Cumulative 19 296 0
14 281 1
This Month Yr.-to-Date 8
0140 0
5 006 0
720 0
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'actor Unit Availability Factor Unit Capacity, Factor (Using MDC Net)'nit Capacity Factor (Using DER Net)
Unit Forced Outage Rate Shutdowns Scheduled Over Next None 541 4 0 0 0 0 0 0 14 009 1
4 882 9
532 9
0 0 0 0 0 0 51 160 052 0
1 913 470.0 16 784 125 0
1 909 336 0
1 952 885 0 6 252 200.0 662 800 0
615 242 0
74 Oa 5 847 243 0
60 7%
60 2 6s 2 6a 74 0 1
2 59 6
0 0 68 5a 5 6a 6 Months (Type, Date, and Duration of Each):
If Shutdown At End of Report Period, Estimated Date of Startup:
N A Achieved
~04 18 86 Forecast
~03 86 INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION 05 20 86 09 19 86
~06 86
~11 86 a
C
~
P
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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
Bors'ELEPHONE 602 3 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 1 239 1 242 23 24 25 56 639 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.
3.
11/24/89 l
Will refueling or resumption of operation thereafter Specification change or other license amendments require a
Technical 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.
7.
Licensed spent fuel storage capacity.
108 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.
UNIT NAME DATE COMPLETED BY TELEPHONE 50-529 PVNGS-2 12 09 88 S
G Borst 602 3 1-4092 11/13 1639 11/01 0000 Unit in Mode 1 - Reactor Power 100%.',
Power reduction to 92% due to inoperability Limit Supervisory System program.
of Core Operating 11/13 11/15 11/16 2135 2001 0237 Reactor power at 100%.
Plant shutdown initiated to investigate unidentified reactor coolant system leakage.
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 11/22 11/23 11/23 11/23 11/23 11/24 11/26 11/26 11/28 11/29 11/30 0222 2341 1315 1746 2145 2155 0434.
0145 1315 1725 0937 2400 Unit entered Mode 4.
Unit entered Mode 3.
Unit entered Mode 2.
Unit entered Mode 1.
Main Turbine synchronized to grid.
Rector power is at 19%.
Reactor power maintained at 56% for feedwater heater repairs.
Reactor power at 72%.
Reactor power at 100%.
Reactor power reduction to 90%
for isolation of the "A"
Low Pressure Feedwater Heater string, Reactor power at 100%.
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 No.
Date Typei Duration Hours Reason2 Method of Shutting System Down Reactor LER No.
Code4 Component Code5 Cause and Corrective Action to 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 S-Scheduled Reason:
A-Equipment Failure (Explain)
B-Haintenance or Test C-Ref ue l ing D-Regulatory Restriction E-Operator Training
& License Examination F-Administrative G-Operational Error N-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 (NUREG 0161)
Exhibit H-Same Source
III
t t
NRC MONTHLY OPERATING REPORT 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.
2.
3.
4, 5.
6.
7.
8.
9.
10 Unit Name:
Palo Verde Nuclear Generatin Station Unit 3 Reporting Period:
ovember 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):
~122 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.
15.
16.
17.
18 19 20 21 22.
23 24 872 0
7820 720 0 7 457 7
45
.7 0.0 0.0 7 434 0 7 434.0 0 0 0 0 27 516 564 0
9 664 100 0
2 671 9
8 0 2
516 564 0
9 664 100.0 9 103 692.0 938 400 0
I 9 103 692 0
94 4 94 4 94 4 94.4a 94 7
94 7a 91 1
- Date, and Duration of Each):
Hours in Reporting Period Number of Hours Reactor Was Critical 720 0 Reactor Reserve Shutdown Hours 0 0 Hours Generator On-Line 720 0
Unit Reserve Shutdown Hours 0 0 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 Unit Forced Outage Rate Shutdowns Scheduled Over Next 6 Months (Type, Refuelin Outa e
- 03 03 89 0 Da s
- 25. If Shutdown At End of Report Period, Estimated Date of Startup:
N A INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Forecast Achieved
~07 87
~10 25 87 07708 11/128 87
~09 8
~01 08 88
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VERAGE DAILYUNIT POWER LEVEL MONTH: NOVEMBER 1988 DAY AVERAGE DAILY POWER LEVEL 249 DAY 17 DOCKET NO.
50-530 UNIT NAME PVNGS-3 DATE 12 09 88 COMPLETED BY S G
Borst TELEPHONE 602 371-4092 AVERAGE DAILY POWER LEVEL 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 1 244 23 24 1 251 1 252 1 253 25 1 253 10
'1 257 26 1 252 1 074 27 1 251 12 835 28 1 252 13 14 1 093 256 29 30' 258 1 264 15 1 261 16 1 255
.~
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).
tg t
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 11/11 11/12 11/13 11/13 11/30 0000 0630 (approx.)
0130 (approx.)
1457 1835 2400 Reactor power is at 100%.
Reactor power reduced to 83% for rod testing/control element assembly calculator surveillance testing.
Reactor power reduced to 68% for replacement of feedwater pump "B" suction strainer.
Reactor power is at 91%.
Reactor power is at 100%.
Reactor power is at 100%.
SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-530
~
UNIT NAME PVNGS-3 DATE COMPLETED BY S.
G. 'Borst No.
Date Type1 Duration Hours Reason2 Method of Shutting System Down Reactor LER No.
Code4 Component 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)
Method:
1-Hanual 2-Manual 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