ML20129H206

Monthly Operating Rept for Mar 1985

ML20129H206
Person / Time
Site:	Diablo Canyon
Issue date:	03/31/1985
From:	Kanick B, Thornberry R PACIFIC GAS & ELECTRIC CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8506070512
Download: ML20129H206 (6)

Text

F ORRATING DATA REPORT DOCKET N0. 50-275 DATE 04/05/85 COMPLETED BY Bob Kanick TELEPHONE (805)595-7351 OPERATING STATUS

1. Unit Name: Diablo Canyon Unit 1

2. Reporting Period: March 1985

3. Licensed Thermal Power (MWt): 3338 ,

4. Nameplate Rating (Gross MWe): 1170 #

5. Design Electrical Rating (Net MWe): 1084

6. Maximum Dependable Capacity (Gross MWe): 1134***

7. Maximum Dependable Capacity (Net MWe): 1084***

If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, 8.-

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 2160 3382*

12. Number Of Hours Reactor Was Critical 650.8 1132.3 2099.5*

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line --

648.3 970.0 1784.0*

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1854601 2436559 3384856*

17. Gross Electrical Energy Generated (MWH) 619400 794200 1056800*

18. Net Electrical Energy Generated (MWH) 584940 722800 926805*

19. Unit Service Factor N/A**

20. Unit Availability Factor N/A**

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):

100 Percent Outage - Maintenance and Startup Testing - March 29, 1985 - 1 month

25. If Shut Down At End Of Report Period, Est. Date of Startup: N/A

26. U'its In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY April 1984 April 1984 INITIAL ELECTRICITY November 1984 Nov. 1984 COMMERCIAL OPERATION April 1985

• Cumulative totals started on the November 11,1984 (Hour and date of initial electric power generation).

• • These sections not applicable until commencement of commercial operation.

• • • These values are predictions - actual values are to be determined by operating experience during the first year of commercial operation.

8 7pg $ 5 7

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-275 UNIT Diablo Canyon Unit 1 DATE 04/05/85 COMPLETED BY Bob Kanick TELEPHONE (805)595-7351 MONTH March 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (fh'E-NET) (FWE-NET) 1 783 17 1060 2 780 18 104<

3 780 19 1065 4 771 20 998 5 780 21 603 6 795 22 77 7 644 23 667 8 845 24 1116 9 965 25 1074 10 965 26 1043 11 895 27 1078 12 838 28 811 13 994 29 -15 14 1076 30 -9 15 991 31 -10 16 886 INSfRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute t) the nearest whole megawatt.

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_ . - _ __ .m ... .

UNIT SHUTDOWNS Af0 POWER REDUCTIONS-PAGE 10F 1 DOCKET N0. 50-275 ,

UNIT NAME Diablo Canyon Unit I DATE 04/05/85 COMPLETED BY D.P. SISK .

REPORT MONTH MARCH, 1985 TELEPHONE (805)595-7351 Licensee Cause & Corrective Duration . System Component Event Action to No. Date Type 7 2 Methodof Report # 4 5 (Hours) Reason Shutdown Code Code Prevent Recurrence 1 3-21 F 21.2 G 3 85-012-00 ED JX Technicians trouble-shooting in the instrument racks drew an arc from th 115 volt power supply to i

refueling water storage tank

channel 921. Arc feedback caused -

the reactor coolant pump breaker logic to momentarily drop out, thus triggering the reactor trip.

To prevent similar feedback from causing recurrences of this, or similar events, a DCR is being initiated to provide fuse pro-tection for the new electronic isolators recently installed in compliance with Regulatory Guide 1.97.

i 3-28 2 S 74.5 B 1 N/A TB GEN Start-up Test 43.4, plant trip j from 100 percent power.

I 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A-Equipnent 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 5 G-Operational Error (Explain) 6,7,8-N/A Exhibit I - Same Source H-0ther (Explain) 9-0ther -

1 i

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' DESCRIPTION OF CHANGES TO THE RADI0 ACTIVE WASTE SYSTEM DC0-EE,EH,EC-29951 As a result of a pre-use operational efficiency and ALARA consideration evaluation of the Solid Waste Storage building, the following modifications are being made:

1. For ALARA consideration an existing rollup door and sliding shield door in the north end of the building are being removed and filled in with concrete.

2. To allow access and operations of a fork lift in the building, the openings in the south end of the building are being enlarged and an unneeded shield cell area will be removed and the exterior shield cell door opening will be filled.

3. Due to the above changes, the monorail control station will be moved.

4. For ALARA considerations, a grab sampling capability is being added to the exhaust duct.

TECHNICAL SPECIFICATION EVALUATION 6.15 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS

1. This modification provides a waste segregation area in the northernmost section of the building and better access to the storage area in the southern part of the building, therefore increasing the effective usage of the storage area. The change is needed to provide for the capability to store low level dry active waste as well as solid waste. Changes in building design and usage are to be reflected in the FSAR. Accidents / malfunctions associated with this modification are less severe than those described and evaluated by the FSAR. No change will occur in operation, function, or failure modes of other systems as described in the FSAR. The margin of safety as defined in the basis for Technical Specification 3/4.11.4 is not reduced since the design and operation of the modified Radwaste Storage Building will comply with the general public total dose limit.

2. See above.

3. See above, there is not involvement with other plant systems.

4. The changes do not affect the release of radioactive materials.

5. Since the changes involve the addition of more shielding, the dose is the unrestricted area will decrease. Past dose analysis indicate that this facility will have a negligible contribution to expected doses in the unrestricted areas.

6. The facility is pre-operational, therefore no actual data is available on releases. Since the changes do not involve systems-only structural modifications, no change is expected in future releases.

7. The changes involve the addition of shielding and therefor will reduce the exposure of plant personnel. Since the facility is pre-operational, an actual expected dose reduction is not available.

8. PSRC minutes of DCN approval are attached.

DC0044 7

. PACIFIC GAS AND E LE C T RIC C O M PANY pgg , DIABLO CANYON POWER PLANT i PO. Box 56. Avila Beach, California 93424 - (805) 595-7351 R.C. THORNBERRY PLANT MANAGER April 5, 1985 Office of Management Infonnation and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 RE: Docket No. 50-275 License No. DPR-80 Monthly Operating Report for March, 1985 l

Gentlemen:

Enclosed are the completed monthly operating report forms for Diablo Canyon Unit I for March,1985. This report is submitted in accordance with Section 6.9.1.10 of our Technical Specifications.

Sincerely,

@ Y&~- _

R. C. THORNBERRY, RCT:jhr o

Enclosures cc Mr. John B. Martin, Regional Administrator

• Pegion V - USNRC hi DC0044 1

. . MONTHLY NARRATIVE REPORT' 0F OPERATION AND MAJOR MAINTENANCE EXPERIENCE This report describes the operating and major maintenance experience for the month of March,1985. 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 March 6, 1985, PSRC approved Design Change DC0-EE,EH,EC-29951, for the Solid Radwaste Storage Building. In accordance with Technical Specification 6.15, a description of the changes is attached.

On March 13, after the 90% power plateau startup testing was completed, Unit 1 increased power to 100% for the first time.

On March 19, 1985, PSRC approved a revision to the Off-site Dose Calculation Procedure (00CP). In accordance with Technical Specification 6.14, a copy of the changed pages (entire procedure) along with documentation of PSRC approval (Procedure History) is attached. Since the methodology for calculation and setpoint determination has not changed (Procedure History), there is no decrease in accuracy or reliability of dose calculations or setpoint determinations.

Ort, March 21, 1985, Unit 1 experienced an automatic reactor and turbine trip.

On March 23, a net load rejection test from 100% power was performed, distinguishing Diablo Canyon as the largest Westinghouse plant ever to successfully complete this test .

The 100-hour run at 100% power was officially completed on March 28.

On March 28, 1985, NRC Region V issued a Severity Level IV Notice of Violation as part of NRC Inspection Reports 50-275/85-12 and 50-323/85-11 for Diablo Canyon Units 1 and 2. The NRC has stated that a discrepancy was observed in the compliance with Security Procedure SP 401(G).

The natural circulation / boron mixing startup test was compelted on March 29 and the plant shut down, signifying the compeltion of the startup test program.

There was no major safety-related maintenance performed in the month of March, 1985.

ho challenges to the PORVs or Steam Generator Safety Valves have been made.

No changes have been made in the Environmental Radiological Monitoring procedure.

DC0209