ML20084E210

Monthly Operating Rept for Mar 1984

ML20084E210
Person / Time
Site:	Diablo Canyon
Issue date:	03/31/1984
From:	Kelly W, Thornberry R PACIFIC GAS & ELECTRIC CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
NUDOCS 8405020174
Download: ML20084E210 (5)

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! OPERATING DATA EPORT 1

l DOCKET NO. 50-275 DATE 04/05/84 COMPLETED BY W.J. Kelly TELEPHONE (805)595-7351

OPERATING STATUS 1

1. Unit Name: Diablo Canyon Unit 1

2. Reporting Portod

March 1984 Notes:

j 3. Licensed Thermal Power (MWt): 166.9

4. NameplateRating(GrossMWe)

1170

5. Design Electrical Rating (Net MWe): 1084

6. MaximumDependableCapacity(GrossMWe): 1134

7. 1084 I 8. Maximum If Changes Dependable Capacity Occur in capacity (Net Ratings MWo)(:

Items Number 3 Through 7) Since Last Report, j Give Reasons:

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l 9. Power Level To Which Restricted If Any (Net MWe): l 10. Reasons For Restrictions, If Any: Awaiting reinstatement of low power test permit

by the Nuclear Regulatory Commission.

l This Month Yr-to-Date Cumulative i 11. Hours In Reporting Period 0 0 0 i 12. Number Of Hours Reactor Was Critical 0 0 0 j 13. Reactor Reserve Shutdown Hours 0 0 0 i 14. Hours Generator On-Line 0 0 0 1 15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 0 0

, 17. Gross Electrical Energy Generated (MWH) 0 0 0

18. Net Electrical Energy Generated (MWH) 0 0 0

19. Unit Service Factor N/A

20. Unit Availability Factor N/A i

21. Unit Capacity Factor (Using MDC Net) N/A

22. Unit Capacity Factor (Using DER Net) N/A

23. Unit Forced Outage Rate N/A

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

i l 25. If Shut Down At End Of Report Period, Est. Date of Startup: April, 1984 ,.

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26. Units In Test Status (Prior to Commercial Operation): ' '

Forecast Achieved INITIAL CRITICALITY April, 1984 INITIAL ELECTRICITY May, L984

COMMERCIAL OPERATION .?uly, L984 i

$0$$ 0 e

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O AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-275 UNIT Diablo Canyon Unit 1 DATE 04/05/84 COMPLETED BY W.J. Kelly TELEPHONE (805)595-7351 MONTH March 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (NE-NET) (NE-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 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.

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ljNIT ShETIXM6 AND F0WER EDJCTIONS '

DOCET FO. 50-275 UNIT t#E DIABLO CNNON UNIT 1. .

DATE 04/05/84 C&PLETED BY W.J. KELLY TELEF10 E (805)595-/351 EFORT f0mi FARCH 1984 Metnod of Licensee Cause & Corrective Duration Shutting Event System Component Action to No. Date Typel (Hours) Reason 2 Down Reactor 3 Report # Code Code 5 Prevent Recurrence NONE 1 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions 5: 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-Other (Explain) (NUREG-0161)

E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source H-Other (Explain)

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PACIFIC OAS AND E LE C T RIC C O M PANY yp) g , g g' i DIABLO CANYON POWER PLANT I PO. Box 56. Avila Beach, Cahfomia 93424 * (805) 595 7351 R C. THORNBERRY PLANT MANAGEM April 5, 1984 I

Office of Management Information and Program Control U.S. Nuclear Regulatory Comission Washington, DC 20555 i

RE: Docket No. 50-275 License No. DPR-76 Monthly Operating Report for March,1984 Gentlemen:

Enclosed are the completed monthly operating report forms for Diablo Canyon Unit 1 for March 1984. This report is submitted in accordance with Section 6.9.1.10 of our Technical Specifications.

J Sincerely, R. C. THORNBERRY RCT:Jhr F

Enclosures cc Mr. John B. Martin, Regional Administrator Region V - USNRC k

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MONTHLY NARRATIVE REPORT OF OPERATION AND MAJOR NAINTENANCE EXPERIENCE This report describes the operating and major maintenance experience for the month of March, 1984. This narrative report was prepared by the plant staff and is submitted in accordance with Section 6.9.1.10 of the Plant Technical Specifications.

On Saturday, March 3rd, the plant entered Mode 3 (Hot Standby) for the first time in support of continued hot systems testing.

On Friday, March 9th, all testing that could be performed with three Reactor Coolant Pumps was completed, and Mode 4 (Hot Shutdown) was entered. After entering Mode 4, interfarence was observed on pipe supports on the Reactor Coolant System pressurizer safety valve discharge line. (Repairs were completed to these pipe supports on March 24th.)

Entry into Mode 5 (Cold Shutdown) was completed on Friday, March 9th to facilitate replacement of Reactor Coolant Pump motor 1-3. The motor was damaged in February by construction debris entering the pump motor arior to operation.

Motor replacemcnt was completed by Monday, March 19th and t1e plant was returned to Mode 4. Mode 3 was reentered on Saturday, March 24th following the pipe support repairs.

Radiator core replacement on Diesel Generators No.1-1 and 1-2 has been completed and the diesel's returned to service.

Eight advisors have been brought to Diablo Canyon to augment the operations staff during initial plant startup. Training for the 1st group of advisors (4) on Diablo Canyon plant systems has been completed this month.

There were four actuations of Engineered Safeguards Features this month:

Auxiliary building and control room ventilation systems automatically isolated when an operator inadvertently deenergized the 120V Vital Instrument A.C. bus 1-3.

While performing a surveillance test of the Solid State Protection System (SSPS), a technician made a procedural error resulting in a safety injection signal on Train A of the SSPS.

The deenergization of startup power while testing breaker 52-HG-15 resulted in the automatic start of Diesel Generator No.1-3.

Diesel Generator No.1-3 started when the 4KV bus 'F' potential transformer fuse drawer was pulled out during a wire trace by NP0 maintenance.

In addition to the events identified above, three other Significant Events were reported to the NRC Operations Center:

Two challenges to the Power Operated Relief Valves (PORVs) were made to mitigate the effects of an RCS pressure transient. A written report of this event will be submitted to the NRC by April 16, 1984.

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Valve RCV-18 in the liquid radwaste discharge line failed to close during the performance of a surveillance test procedure.

Valve RV-7, Steam Generator No.1-2 safety valve lifted and failed to rescat.

No changes have been made in the Offsite Dose Calculation Procedure, the Environmental Radiological Monitoring Procedure, or any radioactive waste t treatment systems.

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