ML20077A926

Monthly Operating Rept for May 1983

ML20077A926
Person / Time
Site:	Diablo Canyon
Issue date:	06/02/1983
From:	Kelly W, Thornberry R PACIFIC GAS & ELECTRIC CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8307220496
Download: ML20077A926 (7)

Text

OPERATING DATA REPORT DOCKET NO. 50-275 DATE 6/2/83 COMPLETED BY W.J. Kelly TELEPHONE (805)595-7351 OPERATING STATUS Notes

1. Unit Name: Diablo Canyon Unit 1

2. Reporting Period: May 1983 166.9

3. Licensed Thermal Power (MWt):

4.. Nameplate Rating (Gross MWe): 1170

5. Design Electrical Rating (Net MWe); 1084

6. Maximum Dependable Ca'pacity (Gross MWe): '1134 1084

7. Maxirnum Dependable Capacity (Net MWe):

S. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Gise Reasons:

9. Power LeselTo Which Restricted.if Any(Net MWe): 10. Reasons For Restrictions. lf Any: SusDerided Low Power Test Licenso This Month Yr.-to Date Cumulative 0 0 0

11. Hours In Reporting Period 0 n 0

~ 12. Number Of Hours Reactor Was Critical 0 Q 0

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On Line 0 0 0

15. Unit Resene Shutdown !!ours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 .,; O O

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

18. Net Electrical Energy Generated (MWH)

19. Unit Senice 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):

June,1983 (fuel load)

25. If Shut Down At End df Report Period. Estimated Date of Startup:

26. Units in Test Statu< 'miar to Commercial Operation): Forecast Achieved September 1983 INITIAL CRITICALITY September 1983 INITIAL ELECTRICITY December 1983 l COMMERCIA L OPERATIO'l g [h 11 8307220496 830602 I( r PDR ADOCK 05000275 PDR (9/77:

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- AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-275 Diablo Canyon Unit 1 UNIT DATE 6/2/83 CO5fPLETED BY W.J. Kelly TELEPHONE (805)S95-7351 Sf0 NTH May 1983 DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (51We Net) (5fWe-Net) 1 0 17 0 ,

2 18 0

3 0 39 0 4

0 0 20 5 0 21 0 6

. 0 22 0 0

7 23 8 0 .

24 0 0 0 9 25 10 0 26 0 11 27, 0 12 0 28 0 0

13 29 34 0 30 0 0 0 15 3, 16 0 INSTRUCTIONS On this format.hst the average daily unit power lesel in SIWE-Net fo* each day in the reporting month. Compute to the nearest whole megawait.

(4/77) ,

50-275

~ UNIT SilUTDOWNS AND POWER REDUCTIONg DOCKETNO.

UNIT N AME Eanvnn linit {

REPORT MONTil 'May 1983 COMPLETED BY W J KelIv

' TELEPilONE (805) 595-73M q

= c

- 5; "E -

Licensee 5 t, $%g Caus; & Corrective No. Date h j! $

.j.gj*g 3& Event p go Action to e o2 o ~: y I; ec c Report se mu o Prevent Recurrence m a u 810928 F 0 11 4 81-002/0lT ZZ ZZZZZZ llalted fuel loading preparations upon discovery of seismic calculation errors. Reanalysis and reviews are being conducted in accordance with

' 'T Commission's instructions 1

1 2 3 4 F: Forced . Reason: Method: Exhibit G -Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data n-Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Ausomatic Scram. Event Report (LER) File (NUREG.

D-Regulatory Restriction 4-Other (Explain) 0161)

- E-Operator Training & License Examination

,. F-Administrative 5 G. Operational Error (Explain) Exhibii 1 - Same Source

• (9/77) Il-Other (E xplain) 8

o DIABLO CANYON NUCLEAR POWER PLANT UNIT 1 MONTHLY OPERATING REPORT MAY 1983 DISCUSSION OF DESIGN CHANGE REQUEST DCl-EM-5524 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 DCl-EM-5524 was performed in accordance with 10CFR50.59 and concludes that the installation of activated carbon filters in the Radwaste Water System will not: 1) 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 was made to provide an improved laundry facility for protective clothing and respiration cleaning and added dry active waste storage.

ITEM:

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

RESPONSE

The laundry facility has been expanded to include dry cleaning machines and dryers for protective clothing, washer and dryer for the respirators and added storage for both clothing and respirators.

In addition to expanded storage for dry active waste, steel boxes in lieu of cardboard boxes will be used for dry active waste storage.

ITEM:

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

i DC0188 p

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DC1-EM-5524 R_ESPONSE:

The predicted releases of gaseous and liquid radioactive releases are not affected by this change. The laundry facility and the complete waste storage facility will be continuously ventilated with all vent air released through a HEPA filter bank. The laundry w'ter will, as before, be discharged to the storage tanks and samplea and analyzed in accordance with plant procedures and technical specifications, prior to release. The water in the respirator cleaning facility will be recycled through filter and ion exchanges located in the facility.

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

There is no change in the expected releases of radioactive materials as a result of the change and no change in expected 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 no change in the predicted releases of radioactive materials in liquid and gaseous effluents.

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. Any change could be less exposure because of a more efficient laundry and dry active waste storage facility.

ITEM:

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 May 31, 1983.

DC0188

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o PACIFIC OAS AND E LE C T RIC C O M PANY pgg , DIABLO CANYON POWER PLANT I P.O. Box 56. Avila Beach, California 93424 -(805) 595-7351 R.C. THORNBERRY PLANT MANAGER June 2, 1983 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 May,1983 Gentlemen:

Enclosed are the completed monthly operating report forms for Diablo Canyon Unit 1 for May 1983. This report is submitted in accordance with Section 6.9.1.10 of our Technical Specifications.

Sincerely, Y$f R. C. THORNBERRY RCT:plm Enclosures cc' Mr. J. B. Martin, Regional Administrator Region V - USNRC d

34 i l

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

~the month of May 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 Offiste Dose Calculation Procedure or the Environmental Radiological Monitoring Procedure.

One design change has been approved by the PSRC for work on the Radioactive Waste System. This design change, DCl-E-M-5524 is presented within this report in accordance with section 6.15.1.1 of the plant Technical Specifications.

DC0016 3