ML20215D821

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Monthly Operating Rept for Jul 1986
ML20215D821
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 07/31/1986
From: Keller A, Sisk D, Thornberry R
PACIFIC GAS & ELECTRIC CO.
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
DC0455, DC455, NUDOCS 8610140313
Download: ML20215D821 (9)


Text

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MONTHLY NARRATIVE REPORT OF OPERATION AND MAJOR MAINTENANCE EXPERIENCE This report describes the operating and major maintenance experience for the

. month of July,1986. This narrative report was prepared by the plant staff and is submitted in accordance with Section 6.9.1.7 of the Units 1 and 2 Technical Specifications.

On July 1, 1986 Unit 1 is operating at 88% power as the first step in a unit coastdown in preparation for a refueling outage. Unit 2 is operating at 47% power while awaiting repairs to main circulating water pump 2-2.

On July 3, 1986 Unit 2 experienced a reactor trip and subsequent safety injection.

On July 5,.1986 Unit 2 was synchronized to the PGandE system.

On July 5, 1986 Unit 2 experienced a reactor trip. After recovery, the unit was again synchronized to the PGandE system, but power was restricted to approximately 47% while awaiting repairs to main circulating water pump 2-2.

On July 6, 1986 Unit 2 was separated from the PGandE system to repair a steam leak that had developed on an extraction steam line from the main turbine. After the steam line was repaired, the unit was again synchronized to the PGandE system. Power is restricted to 47% while awaiting repairs to main circulating pump 2-2.

On July 9, 1986 Unit 2 experienced a reactor trip.

On July 10, 1986 A significant event was declared due to a spurious containment ventilation isolation signal (CVI) on Unit 1.

On July 11, 1986 Unit 2 was synchronized to the PGandE system.

On July 13, 1986 Circulating water pump 2-2 was returned to service. Unit 2 was returned to 100% power.

On July 15, 1986 A significant event was declared due to a spurious CVI signal on Unit 1.

On July 17, 1986 Unit 2 was reduced to approximately 50% power to backwash the intake screens and was returned to 100% power.

On July 30, 1986 A significant event was declared following a spurious Unit 1 CVI that is believed to have been caused by maintenance activities. A second significant event was declared following two spurious CVIs that occurred later the same day.

On July 31, 1986 Unit 2 power was reduced to 75% while investigating a salt leak in the main condenser. Unit 2 ended the month at 75%

power and Unit 1 ended the month at 62% power.

8610140313 DR 861014 7 ADOCK 0500 5

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yp DC0455 - u i-1/l

9 Unit 1 optrated this month with a unit availability factor of 100% and a unit capacity factor of _70%. On July 31, Unit 1 completed its 138th consecutive day synchronized to the PGandE system. Unit 1 is currently in a coastdown prior to its first refueling outage. During the month of July, Unit 1 experienced 5 spurious containment ventilation isolations.

Unit 2 operated this month with a unit availability factor of 86% and a unit capacity factor of 66%. During the month of July, Unit 2 expe.rienced a safety injection, two reactor trips, a shutdown to repair a steam leak, a power

- reduction to back wash intake screens and a power reduction while investigating a main condenser salt leak. In addition, Unit 2 power was curtailed (.'oly 1-13) while the motor. for circulating water pump 2-2 was being repaired.

No challenges to the steam generator safety valves or pressurizer power operated relief valves have been made. Major maintenance performed consisted of the repair of circulating water pump 2-2.

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DC0455

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OPERATING DATA REPORT DOCKET N0. 50-275 DATE 08/01/86 COMPLETED BY A.T. Keller TELEPHONE {805)595-7351 OPERATING STATUS

1. Unit Name:- Diablo Canyon Unit 1
2. Reporting Period: July 1986

'3. Licensed Thermal Power (MWt): 3338

4. Nameplate Rating (Gross MWe): 1137 5.. Design Electrical Rating (Net MWe): 1086
6. Maximum Dependable Capacity (Gross MWe): 1125 '
7. Maximum Dependable Capacity (Net MWe): 1073
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): N/A
10. Reasons For Restrictions, If Any: None This Month Yr-to-Date Cumulative *

' 11. Hours In Reporting Period 744.0 5087.0 10821.3

12. Number Of Hours Reactor Was. Critical 744.0 5055.5 10353.8
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 744.0 5030.0 10237.3
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1842336 15561770 32127220
17. Gross Electrical Energy Generated (MWH) 597800 5185300 10699630
18. Net Electrical Energy Generated (MWH) 560977 4928258 10162490
19. Unit Service Factor 100.0 98.9 94.6

- 20. Unit Availability Factor 100.0 98.9 94.6

' 21.- Unit Capacity Factor (Using MDC Net) 70.3 90.3 87.5

22. Unit Capacity Factor (Using DER Net) 69.4 89.2 86.5
23. Unit Forced Outage Rate 0.0 0.0 4.9
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling Outage, September 1, 1986, 63 days i 25. If Shut Down At End Of Report Period, Est. Date of Start-up: N/A

26. Units In Test Status (Prior to Commercial Operation): N/A o As of commercial operation on 5-7-85 at 0243.

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t DC0455

9 OPERATING DATA REPORT DOCKET N0. 50-323 DATE 08/01/86 COMPLETED BY A.T. Keller TELEPHONE (805)S95-7351 OPERATING STATUS

1. Unit Name: Diablo Canyon Unit 2
2. Reporting Period: July 1986
3. Licensed Thermal Power (MWt): 3411
4. Nameplate Rating (Gross MWe): 1164
5. Design Electrical Rating (Net MWe): 1119
6. Maximum Dependable. Capacity (Gross MWe): 1124
7. Maximum Dependable Capacity (Net MWe): 1073
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe): N/A
10. Reasons For Restrictions, If Any: None This Month Yr-to-Date* Cumulative *
11. Hours In Reporting Period 744.0 3380.0 3380.0
12. Number Of Hours Reactor Was Critical

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693.5 3220.5 3220.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 637.5 3117.4 3117.4
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1782564 9519687 9519687
17. - Gross Electrical Energy Generated (MWH) 566500 3100199 3100199
18. Net Electrical Energy Generated (MWH) 531133 2933237 2933237
19. Unit Service Factor 85.7 92.2 92.2
20. Unit Availability Factor 85.7 92.2 92.2
21. Unit Capacity Factor (Using MDC Net) 66.5 80.9 80.9
22. Unit Capacity Factor (Using DER Net) 63.8 77.6 __

77.6

23. Unit Forced Outage Rate

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14.3 7.8 7.8

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

N/A l l

25. If Shut Down At End Of Report Period, Est. Date of Start-up: N/A
26. Units In Test Status (Prior to Commercial Operation): N/A 0 Year-to-date, and cumulative totals started March 13, 1986 at 0300 PST (Date

. of. commercial operation)

DC0455

AVERAGE DAILY UNIT POWER LEVEL DOCKET N0. 50-275 UNIT Diablo Canyon Unit 1-DATE 08/01/86 COMPLETED BY A.T. Keller TELEPHONE (805)595-7351 MONTH July 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 938 17 722 2 922 13 718 3 908 19 705 4 900 20 697 5 884 21 684 6 864 22 681 7 855 23 668 8 842 24 660 9 830 25 647 10 818 26 651 11 807 27 631 12 805 28 626 13 787 29 618 14 792 30 606 15 755 31 606 16 751 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

l DC0455

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AVERAGE DAILY UNIT POWER LEVEL DOCKET N0. 50-323 UNIT Diablo Canyon Unit 2 DATE 08/01/86 COMPLETED BY A.T. Keller TELEPHONE -(805)595-7351 MONTH July 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 417 17 992 2 414 18 1075 3 316 19 1071 4 -34 20 1043 5 17 21 1076 6 290 22 1067 7 372 23 1071 8 423 24 1071 9 231 25 1067 10 -39 26 1067 11 -15 27 968 12 252 28 1022 13 598 29 1067 14 1060 30 1030 15 1072 31 1001 16 1071 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

DC0455

UNIT SHUTDOWNS .

Paga 1 of 1 DOCKET NO. 50-275
UNIT NAME Diablo cany;n unit 1 r y' DATE 08/01/86

-COMPLETED BY D.P. SISK .,

REPORT MONTH JULY 1986 TELEPHONE (805)595-7351 Method of. Licensee .

System Component: Cause & Corrective Duration 2 Event Action to Type 1 3 4 5 No. Da te'- (Hours) Reason Shutdown Report # Code Code Prevent' Recurrence None i

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1 2 3 4 i F: Forced Reason: Method: Exhibit G - Instructions-j S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of 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-1022)

E-Operator Training & License Examination previous month F-Administrative 5-Power reduction S G-Operational Error (Explain) 6,7,8-N/A Exhibit I - Same Source H-Other (Explain) 9-Othe r -

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DC0455 i

LMIT SHUTDOWNS

  • PAGE 1 0F 1 DOCKET NO. 50-323 UNIT NAME' Diablo Cany:n Unit 2 ..

DATE 08/01/86 COMPLETED BY .D.P. SISK- -

j REPORT MONTH JULY 1986 TELEPHONE (805)595-7351 Licensee Cause & Corrective Duration Method of System Component 2 3 Event 4 5 Action to l No. Date Type l (Hours) Reason Shutdown Re> ort # Code ' ' Code Prevent Recurrence 1 07/03/86 5 29.3 B 1 1/A N/A N/A The generator was separated from the-J PGandE system .in preparation for

overspeed trip testing on the main

. turbine.

2 07/05/86 F 18.4 H 3 2-86-020' SJ FCV While manually adjusting the flow rate to SG 2-2, the automatic flow control valve for SG 2-1' allowed excessive feed causing a high high SG water level i turbine trip and subsequent reactor l trip. No corrective action was deemed'

! necessary since operators are already .

. trained for this sensitive transition l from manual-to automatic SG feed l control.

3 .07/06/86 F 3.4 A 1 N/A SE PSF The generator was separated from the.

PGandE system to repair a steam leak on an extraction steam line from the main turbine.

4 07/09/86 F 55.4 A 3 2-86-021 SJ P Main feedwater pump (MFP)'2-1 tripped

! on overspeed resulting in a reactor l trip. .No apparent cause of the pump trip could be found.

1 i 1 2 3 .

4 F: Forced Reason: Method: Exhibit G - Instructions

S
Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data l 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-1022) 1 E-Operator Training & License Examination previous month. l 1 F-Administrative 5-Power reduction 5 L j .G-0perational Error (Explain) 6,7,8-N/A Exhibit I - Same Source 4 H-Other(Explain) 9-Other ,

1 i DC0455 -138-1

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PAC I 'Ei' I C GAS AND E LE C T RIC C O M PANY pgg i DIABLO CANYON POWER PLANT I PO. Box 56 Avila Beach, Califomia 93424 (805) 595-7351 R.C. THORNBERRY PLANT MANAGER August 13, 1986 Director, Office of Resource Management U.S. Nuclear Regulatory Commission Washington, DC 20555 RE: Docket No. 50-275 and 50-323 License No. DPR-80 and DPR-82 Monthly Operating Report for July,1986 Gentlemen:

Enclosed are the completed monthly operating report forms for Diablo Canyon Units 1 and 2 for July, 1986. This report is submitted in accordance with Section 6.9.1.7 of the Units 1 and 2 Technical Specifications.

Sincerely, se e 7PF(

ROBERT C. THORNBERRY RCT:lm Enclosures cc Mr. John B. Martin, Regional Administrator Region V - USNRC DC0455 h

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