ML20084M542

Monthly Operating Rept for Mar 1983

ML20084M542
Person / Time
Site:	Diablo Canyon
Issue date:	04/11/1983
From:	Kelly W, Thornberry R PACIFIC GAS & ELECTRIC CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8306020214
Download: ML20084M542 (9)

Text

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.O A\ ERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-275 3.lT Diablo Canyon Unit 1 DATE 4/11/83 COMPLETED BY W.J. Kelly-TELEPHONE ( 00 E-73M March L983 MONm DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) (Mwe. Net) 0 0 1 37 0

2 0 is 3 0 19 0 0

4 20 0 5 0 21 0

6 0 22 0 7 0 23 0 8 0 0 24 ,

9 0 0 25 '

10 0 26 0 11 0 0. -

27 0 0 12 28 13 0 29 14 0 0 30 15 0 0 31 16 0 INSTRUCTIONS On this format.hst the average daily unit power leselin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77)

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D 50-275 UNIT SilUTDOWNS AND POWER REDUCTIONg DOCKET NO.

UNIT NAME Diablo Canvnn Ifnit 1 DATE 4/11/83 March 1983 COMPLETED BY W.d. Kelly REPORT MONTH

' TELEPilONE (805) 595-7El jg }g ) .Y Licensee p, ~o Cause & Corrective No. Date g 3g jy$ Event p gg" Action to H jE $ 5 ;j. j =g Report 22 mO o u

Prevent Recurrence Q

810928 F 0 4 81-002/0lT

H ZZ ZZZZZZ Halted fuel loading preparations upon discovery of seismic calculation errors. Reanalysis'and reviews are being conducted in accordance with Commission's instructions I 2 3 4, F

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

D Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & Ucense Examination F. Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source (9/77) Il Other (Explain)

OPERATING DATA REPORT DOCKET NO.

50-275 DATE 4/11/83_.

W.J. Kelly COMPLETZD TELEPHONE BY595-7351 (805)

OPERATING STATUS Notes

1. Unit Name: Diablo Canyon Unit 1

2. Reporting Period:

March 1983

3. Licensed Thermal Power (MWt):

166.9 ll70 4,. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe): 1084

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

7. Maximum Dependable Capacity (Net MWe): 1084 S. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

9. Power Lesel To which Restricted. If Any (Net MWe): 10. Reasons For Restrictions,If Any: SUSDended Low Power Test License This Month Yr.-to Date Cumulative

11. Hours In Reporting Period 0 0 a

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 Shutdo.wn Hours 0 0 0~

16. Cross Thermal Energy Generated (MWH) 0 -0 0 j

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

0 0 l

18. Net Electrical Energy Generated (MWH) 0 O n l

l 19. Unit Service Factor N/A

20. Unit Asailability 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 Oser Next 6 Months (Type. Date.and Duration of Each)

i a

25. If Shut Down At End df Report Period Estimated Date of Startup: June,1983 (fuel load)

26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITIA L CRITICALITY August 1983 INITIAL ELECTRICITY August 14M COMMERCIAL OPERATION November 1983 i

! (4/771 L

DISCUSSION OF DESIGN CHANGE REQUEST DCl-EM-1257 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 DC2-E-M-1257 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 or 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

At operating plants similar to Diablo Canyon, the quantity of solid radwaste is substantially greater than was expected when the original Diablo Canyon Drumming Station was specified. Solidification in large containers in mobile solidification equipment will be more economical and efficient for the larger quantity of wastes.

ITEM:

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

RESPONSE

The radioactive waste drumming station will be removed and discharge piping of the waste concentrates pumps will be capped. Radioactive wastes will be solidified and packaged with mobile contractors equipment.

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.

RESPONSE

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

DC0188 -. -

DCl-EM-1257 ITEM:

e. An evaluation of the change which shows the expected maximum exposures to individual 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 is no operating experience that can be used to calculate plant personnel radiation exposure. Experience in the startup tests indicated that the operation of the drumming station was going to be labor-intensive and would result in higher than necessary plant personnel radiation exposure. The use of contractor mobile solidification services and large liners should result in a net decrease in total man-rem exposure in the solidification and handling of solid radwastes.

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 March 24, 1983.

DC0188 t

DISCUSSION OF DESIGN CHANGE REQUEST DCl-EM-1365 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-1365 was performed in accordance with 10CFR50.59 and concludes that the-installation of activated carbon filters in the Radwaste Water System will not: 9i) 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 stream; before they are processed in the radwaste ion exchangers. This change will increase the effectiveness 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. Piping will be provided to allow sluicing 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 predicted in the license application and amendments thereto.

1 I

DC0188 .

., r, DCl-EM-1365

RESPONSE

The predicted ~ releases of gaseous radioactive materials are not.affected by this change. The predicted releases will be decreased since the filter

' function will be to remove suspended solids; the change in the predicted releases is small and has not been calculated.

ITEM:

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e. An evaluation of the change which.shows the expected maximum exposures to individual 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:

j~ 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. A small quantity of redioactive-material that would be contained in other media (e.g. ion exchange resin)

~

will be contained on the filter media.

ITEM:

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

RESPONSE

i' 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:

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 March 24, 1983.

DC0188 - 2.-

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PACIFIC OAS AND E LE C T RIC C O M PANY pgg . DIABLO CANYON POWER PLANT 3 PO. Box 56 Avila Beach, Cali.'omia 93424 - (805) 595-7351 R.C. THORNBERRY PLANT MANAGER April 11, 1983 Office of Management Information and Program Control U.S. Nuclear Regulatory Concission Washington, DC 20555 RE: Docket No. 50-275 License No. DPR-76 Monthly Operating Report for March,1983 Gentlemen:

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

Sincerely, S$f R. C. THORNBERRY Enclosures

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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 March 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.

Two design changes have been approved by the PSRC for work on the Radioactive Waste System. These design changes - DCl-EM-1365 and DC2-EM-1257, are presented within this report in accordance with Section 6.15.1.1 of the plant Technical Specifications.

DC0016 2 u