ML20136B726

Monthly Operating Rept for Aug 1985

ML20136B726
Person / Time
Site:	Davis Besse
Issue date:	08/31/1985
From:	Khazrai M, Storz L TOLEDO EDISON CO.
To:	Haller N NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
K85-1248, NUDOCS 8511200273
Download: ML20136B726 (8)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-346 LWIT Davis-Besse Unit 1 DATE September 9, 1985 COMPLETED BY Morteza Khazrai TELEPHONE (419) 249-5000 Ext. 290 MONTH August 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 g7 0 2 0 18 0 3 0 39 0 4 0 20 0 5 0 0 21 6 0 0 22 7 0 0 23 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 0 28 I 13 0 29 0 14 0 30 0 15 0 3g o 16 0 i

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.

(9/77)

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e OPERATING DATA REPORT DOCKET NO. 50-346 DATE September 9, 1985 COMPLETED BY Morteza Khazrai TELEPHONE (419) 249-5000 Ext. 290 OPERATING STATUS Davis-Besse Unit 1 Notes

1. Unit Name:

2. Reporting Period: Aucust 1985

3. Licensed Thermal Power (MWr): 2772

4. Noneplate Rating (Gross MWe): 925

5. Design Electrical Rating (Net MWe): 906

6. Maximum Dependable Capacity (Gross MWe): 904

7. Maximum Dependable Capacity (Net MWe): 860

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:

This Month Yr.-to-Date Cumulative

11. Hours in Reporting Period 744.0 5.831.0 62,136.0

12. Number Of Hours Reactor Was Critical 0.0 2.845.6 35,877.I

13. Reactor Resene Shutdown Hours 0.0 44.7 4,058.8 I4. Hours Generator On.Line 0.0 2,730.5 34,371.8

15. Unit Reserve Shutdown Hours 0.0 0.0 1,732.5

16. Gross Thermal Energy Generated (MWH) 0.0 6.312.I78 A ,297.600 .

17. Gross Electrical Energy Generated (MWH) 0 . 0_, 2,087,278 26,933,622

18. Net Electrical Energy Generated (MWH) 0.0 1,942,921 25,233,177 j

19. Unit Service Factor 0.0 46.8 55.3

20. Unit Availability Factor nn 46_R 58.I

21. Unit Capacity Factor (Using MDC Net) 0.0 38.7 -

47.2

22. Unit Capacity Factor (Using DER Net) 0.0 36.8 44.8

23. Unit Forced Outage Rate 100.0 43.5 20.3

24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each):

25. If Shut Down At End Of Report Period. Estimated Date of Startup: November 1. 1985

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY l INITIAL ELECTRICITY I COMMERCIAL OPERATION 1

(9/77) .

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DOCKET NO, 50-346 ,

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Davis-Besse Unit 1 DATE September 9. 1985 .

. COMPLETED BY Morteza Khazrai REPORT MONTH August 1985 TELEPHONE (419) 249-5000. Ext. 290 w

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- 8m "a $U Licensee a ,, @ in Cause & Corrective U0 0 3U$ Event 34 $4 Action to No. Date 8$ $

65" Report i EO eO Prevent Recurrence

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7 85 06 09 F 744 A 4 LER 85-013 JK SC -The unit remained shutdown follow-(ContN ) ing the reactor trip on June 9, 1985 See Operational Summary for further details.

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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-Continuation from , (NUREG-0161)

E-Operator Training & License Examination -

Previot.s Month F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-Other (Explain) Exhibit I - Same Source (9/77) H-Other (Explain)

5 OPERATIONAL

SUMMARY

August.1985 e

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The unit remained shutdown the entire month of August following the reactor trip on June 9, 1985.

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~ Investigations of the causes of the event and corrective actions continue.

See NUREG 1154 for further details.

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' REFUELING INFORMATION DATE: -August 1985

1. Name~of facility: Davis-Besse Unit 1

2. Scheduled date for next. refueling shutdown: November 1, 1986

3. Scheduled date for restart following refueling: January 15, 1987

4. Will refueling or' resumption of operation thereafter require a

-technical specification change or other license amendment? If answer is yes, what in. general will these be? If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?.

Ans: Expect the Reload Report to require standard reload fuel design Technical Specification changes (3/4.1 Reactivity Control Systems and 3/4.2 Power Distribution Limits) .

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5. Scheduled date(s) for submitting proposed licensing action and supporting information: . Winter, 1985 6.- Important. licensing considerations associated with refueling, e.g.,

new or different. fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

Ans: None identified to date.

7.. The number of fuel assemblies (a)' in the core and (b) in the spent fuel storage pool.

(a) 177 -(b) 204 - Spent Fuel' Assemblies

8. . The present licensed spent fuelEpool storage capacity and the size of any.increaseEin licensed storage capacity that has been requested or

'is planned..in number of fuel. assemblies.

Present: 735 Increase size by: 'O (zero)

9. The-projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

Date: 1992 - assuming ability-to unload the entire core into the spent fuel pool is maintained.

BMS/005

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. COMPLETED FACILITY CHANGE REQUEST

'FCR NO: 84-120~

SYSTEM: --Startup Feedwater

^ COMPONENT: Startup Feedwater Pump

~ CHANGE,' TEST OR' EXPERIMENT: - FCR 84-120 was initiated to hydrotest the suction and discharge lines serving the Startup Feedwater Pump (SUFP).

LTesting was done under Test Procedure TP 520.64, SUFP Suction and Discharge Lines Hydrostatic Test. Work involved with the testing was completed November 14, 1984 REASON FOR CHANGE: The.hydrotests were performed to verify the pressure retaining capabilities of.these lines within the Auxiliary Feedwater Pump

-(AFP) Rooma 237 and 238 during the operation of the SUFP.

SAFETY-EVALUATION

SUMMARY

LThe. SUFP and its associatied piping in AFP Rooms.237 and 238 are non-safety grade components and have no safety function.' However, this equipment is. located in the same room as the AFP is and associated piping which are safety equipment. The test lineup

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would not cause flooding or result in high temperature damage to any safety grade equipment in the event -of potential boundary valve leakage in response to the hydrostatic test. Therefore, this FCR did not; involve an unreviewed safety question.

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COMPLETED FACILITY CHANGE REQUEST FCR NO: 84-176 SYSTEM: Fire Protection COMPONENT: Temporary Fire Barrier CHANGE, TEST OR EXPERIMENT: FCR 84-176 installed a temporary one hour fire barrier over conduit 46008C in Room 323. This fire barrier is to remain in place until a permanent modification which complies with 10CFR50 Appendix R is implemented. Work was completed December 23, 1984.

REASOM FOR CHANGE: This is the result of a Toledo Edison Appendix R non-compliance " Serious Assessment" meeting held September 24, 1984. It was determined that conduit 46008C should be protected because this conduit contains one half of a parallel feed to MCC EllA.

-SAFETY EVALUATION

SUMMARY

The safety function of the cable contained within conduit 46008C is to provide power to MCC EllA. Therefore, until a permanent fire barrier can be installed, this change will provide acceptable protection of the cable to MCC EllA. Therefore, an unreviewed safety question does not exist.

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TOLEDO

%mm EDISON September 9, 1985 Log No. K85-1248 File: RR 2 (P-6-85-08)

Docket No. 50-346 License No. NPF-3 Mr. Norman Haller Director Office of Management and Program Analysis U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Haller:

Monthly Operating Report, August 1985 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Besse Nuclear Power Station Unit 1 for the month of August 1985.

If you have any questions, please feel free to contact Morteza Khazrai at (419) 249-5000 Extension 290.

Yours truly, M 7 Louis F. Storz Plant Manager Davis-Besse Nuclear Power Station LFS/MK/ljk Enclosures cc: Mr. James G. Keppler, w/1 Regional Administrator, Region III Mr. James M. Taylor, Director, w/2 Office of Inspection and Enforcement I

Mr. Walt Rogers, w/1 1 NRC Resident Inspector

' I LJK/002 THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652 -

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