ML20081M469

Monthly Operating Rept for Sept 1983

ML20081M469
Person / Time
Site:	Diablo Canyon
Issue date:	10/03/1983
From:	Kelly W, Thornberry R PACIFIC GAS & ELECTRIC CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
DC0044, DC44, NUDOCS 8311170265
Download: ML20081M469 (7)

Text

o OPERATING DATA REPORT DOCKET N0. 50-275 DATE 10/03/83 COMPLETED BY W.J. Kelly TELEPHONE (805)595-7351 OPERATING STATUS

1. Unit Name: Diablo Canyon Unit 1

2. Reporting Period: September 1983 Notes

3. Licensed Thermal Power (MWt): 166.9

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

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): 10. Reasons Fcr Restrictions, If Any: Suspended Low Power Test License This Month Yr-to-Date Cumulative

11. Hours In Reporting Period C 0 0

12. Number Of Hours Reactor Was Critical 0 0 0

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 0 0 0

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

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, Da+.e, and Duration of Each):

25. If Shut Down At End Of Report Period, Est. Date of Startup: Oct., 1983 (fuel load)

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY December 1983 INITIAL ELECTRICITY December 1983 COMMERCIAL OPERATION March 1984

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DC0044 4

AVERAGE DAILY UNIT POWER LEVEL DOCKET N0. 50-275 UNIT Diablo Canyon Unit 1 DATE 10/03/83 COMPLETED BY W.J. Kelly TELEPHONE (805)595-7351 MONTH September 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY P0kER LEVEL (MWE-NET) (&'E-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 16 0 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the l reporting month. Compute to the nearest whole megawatt.

DC0044 5 l 1

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-275 UNIT NAME Diablo Canyon Unit 1 DATE 10/03/83 COMPLETED BY W.J. Kelly TELEPHONE (805)S95-7351 REPORT MONTH September 1983 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to No. . Date Typel (Hours) Reason 2 Down Reactor Report # Code 4 Code 5 Prevent Recurrence 810928 F 0 H 4 81-002/01T ZZ ZZZZZZ Halted fuel loading preparations upon discovery of seismic calculation errors. Reanalysis and reviews are being conducted in accordance with Commission's instructions.

1 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions 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-Other(Explain) (NUREG-0161)

E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source H-0ther(Explain)

, DC0044 6

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DISCUSSION OF DESIGN CHANGE REQUEST DC0-EC-11674R0 ITEM:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10CFR50.59.

RESPONSE

The safety evaluation report for DC0-EC-11674R0 was performed in accordance with 10CFR50.59 and concludes that this change will not (i) increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report; (ii) create an accident or malfunction of a different type than any evaluated previously in the safety analysis report; (iii) reduce the margin of safety as defined in the basis for any technical specification.

ITEM:

b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information.

RESPONSE

The change is being provided to allow pretreatment of the liquid radwaste streams before they are processed in the radwaste ion exchangers. This change will increase the effcctiveness of the ion exchangers.

ITEM:

c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems.

RESPONSE

Activated carbon filters will be installed to provide pre-treatment of liquid radioactive waste before it is treated by the radioactive waste ion exchangers. The ion exchanger piping shall be revised to allow series operation of the ion exchangers for improved efficiency. Service air and makeup water will be provided to facilitate the transfer of spent ion exchanger resin and spent carbon filter media to the area immediately east of the Auxiliary Building for solidification by a contractor's mobile solidification system.

ITEM:

d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously estimated in the license application and amendments thereto.

DC0044 7

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• RESPONSE:

The predicted releases of gaseous and liquid radioactive materials are not affected by this change.

ITEM:

e. An evaluation of the change which shows the expected maximum exposures to individuals in the unrestricted area and to the general population that differ.from those previously estimated in the license application and

' amendments thereto.

RESPONSE

Since the release of radioactive materials is essentially unchanged as a

. result of this change, there is no change in exposures to individuals in unrestricted areas or to the general population, ITEM:

f. A comparison of the predicted releases of radioactive materials, in liquid and. gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made.

RESPONSE

There is essentially no change in the predicted releases of radioactive materials in liquid and gaseous effluents. In solid wastes there will not be a change in the predicted releases.

ITEM:

g. An. estimate of the exposure to plant operating personnel as a result of the change.

RESPONSE

There will not be any significant change in radiation exposure to plant operating personnel since the accumulation of activity will be small and the filters will be shielded.

ITEM:

l'

h. Documentation of the fact that the change was reviewed and found acceptable by the PSRC.

RESPONSE

This design change was approved by the PSRC on September 15, 1983.

L' DC0044 8 1

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1 PACIFIC OAS AND E LE C T RIC C O M PANY l pgg . , DIABLO CANYON POWER PLANT i RO. Box 56 Avila Beach, Califomia 93424 * (805) 595-7351 I

R.C. THORNBERRY PLANT MANAGER October 3, 1983 i

Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 RE: Docket No. 50-275 License No. DPR-76 Monthly Operating Report for September,1983 Gentlemen:

Enclosed are the completed monthly operating report forms for Diablo Canyon l

-Unit 1 for September 1983. This rcport is submitted in accordance with Section 6.9.1.10 of our Technical Specifications.

Sincerely, j

$[Y M R. C. THORNBERRY g-RCT:plm l Enclosures

.cc Mr. J. B. Martin, Regional Administrator Region V - USNRC i

l DC0044 1 S , t I

4 MONTHLY NARRATIVE REPORT OF OPERATION AND MAJOR MAINTENANCE EXPERIENCE

- This~ report describes the operating and major maintenance experience for the month of September 1983. 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.

There is-no significant operating experience of major safety related maintenance to report.

No challenges to the PORV's or safety valves have been made. Furthermore, no changes have been made in the Offsite Dose Calculation Procedure or the Environmental Radiological Monitoring Procedure.

One design change has-been approved by the PSRC for work on the radioactive waste treatment system. This design change, DC0-EC-11674R0 is presented within this report in accordance with section 6.15.1.1 of the plant Technical Specifications.

L DC0044 3