ML20079E278

Monthly Operating Rept for Dec 1983

ML20079E278
Person / Time
Site:	Diablo Canyon
Issue date:	12/31/1983
From:	Kelly W, Thornberry R PACIFIC GAS & ELECTRIC CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8401170211
Download: ML20079E278 (12)

Text

f, l OPERATING DATA REPORT DOCKET NO. 50-275 DATE 01/13/84 COMPLETED BY W.J. Kelly TELEPHONE (805)595-7351 OPERATING STATUS

1. Unit Name: Diablo Canyon Unit 1

2. Reporting Period: December 1983 Notes: Completed initial fuel

3. Licensed Thermal Power (MWt): 166.9 loading and reactor vessel

4. NameplateRating(GrossMWe): 1170 head installation.

5. Design Electrical Rat;ng (Net MWe): 1084 Presently in Mode 5 (cold)

6. MaximumDependableCapacity(GrossMWe): 1134 shutdown)

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 For Restrictions, If Any: Awaiting granting of low power test permit by the Nuclear Regulatory Commission.

This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 0 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, Date, and Duration of Each):

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

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

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4 DC0044 4

. '. AVERAGE DAILY UNIT NWER LEVEL DOCKET NO. 50-275 UNIT Diablo Canyon Unit 1 DATE 01/13/84 COMPLETED BY W.J. Kelly TELEPHONE (805)595-7351 MONTH December 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (IHE-NET) (MWE-IET) 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.

DC0044 5

UNIT SHUTDOWNS AND POWER REDUCTIONS .

DOCKET NO. 50-275 UNIT NA E DIABLO UNYON UNIT 1 DATE 01/13/84 C0FPLETED BY W.J. KEELY TEEPHONE (805)595-/$51 REPORT M) NTH DECEMBER 1983 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to No. Date Typel (Hours) Reason 2 Down Reactor Report # Code'+ Code 5 Prevent Recurrence NONE None. Just completed initial fuel loading operations.

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-Autumatic 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)

DC0044 6

i DIABLO CANYON NUCLEAR POWER PLANT UNIT I MONTHLY OPERATING REPORT DISCUSSION OF DESIGN CHANGE REQUEST DCO-EM-11674 R2 ADDITION OF RADWASTE PRETREATMENT FILTERS ITEM:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59.

RESPONSE

This design change will allow pretreatment 'of the liquid radwaste streams before they are processed in the radwaste ion exchangers, increasing the effectiveness of the ion exchangers. Installation and use of activated carbon filters and a change in the ion exchangers function to include processing normal liquid radwaste streams in addition to post-accident sample waste streams for processing liquid radioactive waste is unrelated to any'of the accidents evaluated in the FSAR. The type of malfunction or error that could be associated with either the existing liquid radioactive waste processing system, or the use of activated carbon filters and use of ion exchangers, are less severe.than those described in the FSAR. The installation and use of activated ' carbon filters and ion exchangers for processing liquid radioactive waste is unrelated to any of the bases in the slant Technical Specifications and will not affect the margin of safety as defined in the Technical Specification bases.

ITEM:

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

RESPONSE

.This design change improves the operation of the liquid radwaste system by adding additional filtering capability. The change adds activated carbon filters and reroutes piping for series operation of the ion exchangers to process radwaste. The potential for release of radioactive material from the plant is not increased. The changes do not affect safety related equipment.

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- -- DC-EM-11674, R2 ITEM:

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

RESPONSE

In the revised liquid radwaste system, two 36 cubic foot media filters have been added for the purpose of operating in series upstream of the existing two 36 cubic foot ion exchangers whose function has been expanded to include processing of nonnal liquid radwaste streams in addition to waste samples from the post accident sample system. The system piping also allows for the

. liquid flow, if so desired, to pass through the existing cartridge filter prior to flowing through the media filters and ion exchangers. Flow from the Post-LOCA Sample Collection Tanks can, as before, be processed through the ion exchangers.

Liquid radwaste from the Equipment Drain n eceiver Tanks will be pumped through these components and routed to the Waste Concentrator Condensate Tanks for sampling and analysis prior to being released into the circulating water discharge.

ITEM:

d. An evaluation of the change which shows the predicted release 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.-

. RESPONSE:

The predicted releases of gaseous radioactive materials are not affected by this change. The predicted liquid 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 in detail. Solid radwaste volume is-' expected to be reduced, as-the ion exchanger volume should be less than the solid radwaste drum volume.

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 the amendments thereto.

RESPONSE

The release of radioactive materials is essentially unchanged as a result of this DCN, therefore there is no change in exposures to individuals in unrestricted areas or to the general population.

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-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

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Diablo Canyon is not yet operational, and no releases of radioactive materials have been made. Therefore, a comparison.of the predicted releases of radioactive materials .to the actual releases for the, period prior to'when the' changes are to be made, cannot be performed. Predicted releases show no increase over previously anticipated. 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 and a "

small overall volume reduction is anticipated.

ITEM:

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

. change. ,

RESPONSE

There will not be any significant change in radiation exposure to r' ant

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operating personnel since the accumulation of activity will be small and_the "

filters will be shielded. -

ITEM:

h.lDocumentationofthefactthattiiechangewasreviewedandfoundacceptable by the FSRC. * - .

RESPONSE

This design change was approved by the PSRC on December 20, 1983.

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-DIABLO CANYON NUCLEAR POWER PLANT

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. MONTHLY OPERATING REPORT-DECEMBER 29, 1983 DISCUSSION OF-DESIGN CHANGE-REQUEST

- ~DC0-EC-11030 EXPANSION OF SOLID RADWASTE STORAGE BUILDING AND ADDITION OF.NEW LAUNDRY-FACILITY 1

- ITEM:

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

- RESPONSE:

,The waste storage ' remains'in the sane plant area, only to be expanded from Eshort term storage:to slightly less than five years storage. The exterior walls:of.the original solid waste storage vaults are not being changed, therefore the. shielding properties will be unchanged. This modification has no affect on the environment. This modification has not created the

-possibility for an accident or malfunction of a type not previously ,

evaluated.in.the FSAR. -The functionality of the storage facility will act ,

change; only-the capacityfis-increased and a laundry: facility added. The t

. solid radwaste= storage. building-is not addressed-in the Technical

. Specifications?therefore:nof safety margin of the Technical Specifications bases 1is reduced.

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b. ' Sufficient detailed information.to totally support the reason for the change L without'benef t of. additional or supplementa1'information.

RESPONSEi-

, This design change modifies the interior-of-the solid radwaste storage

.vaultsLto accommodate the bridge cranes and transport cask, and modification of.the vault.' exterior to accommodate a' building addition. Structural

. modifications are required 'due to expansion of the original radioactive Lwaste , storage and laundry facilities.' .

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ITEM:

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

- RESPONSE:

The addition to the storage building involves expansion of the storage (new floor. on top of the storage vaults) and the addition of a laundry facility.

The new storage area will have shield walls of the same thickness as the exterior walls of the original structure. The shielding properties will be equivalent to interface with existing process system. Makeup water shall be supplied to the washing machines, respirator cleaner and the sinks.

Drainage shall .be provided from the washing machines, respirator cleaner, sinks and floor drains to the laundry drain tank.

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 the amendments thereto.

RESPONSE

-The predicted releases of gaseous radioactive releases are not affected by this change. The complete waste storage facility will be continuously ventilated with all ventilation air released through a new HEPA filter bank.

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 maximum exposures to individuals in unrestricted areas or to the general population previously estimated in the license' application.

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.

IESPONSE:

There is'no change.in the predicted releases of radioactive materials in liquid and gaseous effluents. No actual release of radioactive materials in any form has been made prior to this design change, therefore no comparison can be made.

DC0-EC-11030 ITEM:

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

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Jchange.'

RESPONSE

There will be a reduction in radiation exposure-to plant operating personnel because of the remote handling provisions of the modified facility and equipment. There will also be less exposure because of a more efficient dry active waste handling and packaging 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 December 5, 1983, a;

DC0044 6I

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

No changes have been made in-the Offsite Dose Calculation Procedure or the Environmental Radiological Monitoring Procedure. ,

During 'this reporting period three challenges were made to the Power Operated Relief Valves (PORV) to mitigate a Reactor Coolant Sys. tem (RCS) pressure transient.

The first event occurred on December 5, 1983 at-1001 PST. The Unit was in operational mode 5 (cold shutdown), the RCS was water solid, and pressure control valve PCV 135 of the Chemical and Volwe Control System (CVCS) was automatically controlling RCS pressure at 400 psig by regulating letdown flow.

The event was initiated when Residual Heat Remova? (RHR) Pump 1-2 was stopped to reduce RHR pump heat. input. The resulting decrose in letdown flow caused an initial decrease in RCS pressure. The.PCV-135 control system then caused the valve to move toward the closed position, slightly overcompensating and subsequently increasing the RCS pressure faster than PCV 135 ceuld control.

Thus, PORV 455C litted at low pressure set point of 430 psig for about three (3) seconds.

The second and' third events occurred on December 9, 1983, at 1140 PST and 1143 PST respectively. The Unit was in operational mode 5, and RCS was water solid,

.and pressure control valve PCV 135 was automatically controlling RCS pressure at 400 psig. The events were initiated when RHR pump discharge valve HCV 637 and HCV 638 were being used to adjust RHR flow. HCV 637 was opened to increase RHR flow resulting in a decreased letdown flow to the CVCS. PCV 135 did not respond fast enough to increase letdown flow, so the RCS pressure increased rapidly and PORV.455C lifted for about 3 seconds. Immediately afterward, the operator placed PCV 135 in manual to adjust letdown flow, and PORV 455C again lifted for about three (3) seconds.

These events occurred during routine RHR system flow adjustments. In.these particular cases, the system pressure control valve did not respond fast enough to sufficiently control RHR pressure. Operators have been cautioned that all RHR and letdown adjustments should be made slowly when the RCS is water solid; the operating procedure has also been revised to include these precautionL We have completed our cold system testing program which included control rod drive mechanism timing, digital rod position indication system functional

testing and cold rod drop testing.-

Two changes were approved in December affecting radioactive waste treatment systems. The discussion of design changes DC0-EM-11674, R2 and DC0-EC-11030 are contained in the. body of this report.

DC0044 3'

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PACIFIC GAS AND E LE C T RIC C O M PANY pgg , DIABLO CANYON POWER PLANT I PO. Box 56 Avila Beach, Califomia 93424 * (805) 595-7351 R C. THORNBERRY PLANT MANAGER January 13, 1984 Office of Management Intormation and Program Control U.S. Nuclear Regulatory Commission Washingten, DC 20555 RE: Docket No. 50-275 License No. DPR-76 Monthly Operating Report for December,1983 Gentlemen:

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

Sincerely,

g. e. T R. C. THORNBERRY RCT:cmr Enclosures cc Mr. John B. Martin, Regional Administrator Region V - USNRC t

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