ML20133H869

Monthly Operating Rept for May 1985

ML20133H869
Person / Time
Site:	Davis Besse
Issue date:	05/31/1985
From:	Khazrai M, Sarsour B TOLEDO EDISON CO.
To:
Shared Package
ML20133H864	List: ML20133H861 ML20133H866 ML20133H869
References
NUDOCS 8508090546
Download: ML20133H869 (7)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-346 UNIT Davis-Besse Unit 1 June 7, 1985 DATE 15 . saruourt COMPLETED BY M. Khazrai TELEPHONE (419) 249-5000 Ext. 384/290 MONTH May, 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) ggw,.3,ig 785 37 788 2 785 gg 78(3 3 786 39 788 4 . 784 20 782 5 782 790 21 6 783 22 791 7 787 789 23 8 787 24 783 9 785 25 781 10 780 26 733 11 778 27 736 12 667 ;g 787 13 757 29 787 14 781 30 783 15 786 33 778 16 744 lNSTRUCTIONS On this format list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole rnegawatt.

19177) 0500090546 850607 PDR ADOCK 05000346 R PDR

L OPERATihG DATA REPORT DOCKET NO. 50-346 DATE June 7. 1985 COMPLETED BY B. sarsour/

TELEPHONE  ?!. Khazrai (419) 249-5000.

OPERATING STATUS Ext. 384/290 Davis-Besse Unit i N0l'S

1. Unit Nmne:

2. Reporting Period: Mnv 1985

3. Licensed Thermal Power (MWt): 2772

4. Namepiste Rating (Grom MWe): 9I5 '

5. Design Electrical Rating (Net MWe): 906

6. Maximum Dependeble Capeciay (Grom MWe): 904

7. Maximum Dependable Capacity (Net MWe): 860

8. If Changes Occur in Capacity Ratings (items Number 3 Theough 7) Since Last Report. Give Reasons:

To obtain an acceptable offset from the Reactor Protection System (RPS) trip sotpoints

9. Power Level To Which Restricted. lf Any (Net MWe):

10. Reasons For Restrictions.lf Any:

This Month it..to Date Cumulative f

11. Hours in Reporting Period 744 1.621.0 59.928.0

12. Number Of Hours Reector Was Critical 744 2.696.H 35,728.3

13. Reactor Reserve Shutdown Hours 0.0 0.0 4,014.I

14. Hours Generator on Line 744 2.590.0 34.231.3

15. Unit Reserve Shutdown Hours 0.0 0.0 1,732.5

16. Grom Thermal Energy Generated (MWH) I.836.172.0 6.032.760 81.018.182 .

17. Grom Electrical Energy Generated (MWH) 610.042 ,

1.996,696 26,843,040

18. Net Electrical Energy Generated (MWH) 577.434 1.861.502 25,151.758

19. Unit Service Factor 100 71.5 57.I

20. Unit Availability Facto, 100 71.5 60.0

21. Unit Capacity Factor (Using MDC Net) 90.2 59.7 .

48.8

22. Unit Capacity Factor (Using DER Net) 85.7 56.7 46.3

23. Unit Forced Outage Rate 0 .,,0,,, 1.3 16,3

24. Shutdowns Scheduled Over Nest 6 Months (Type. Dete, and Duration of Eachl:

25. If Shut th>wn At End Of Report Period. Estimated Date of Startup: i

26. Units in Test Status (Prior to Commercial Operation): Forecast Achlesed i INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION (4/77 l  !

- - . . . - . ~_ - . . - . - - - - - - - - . - . - _ . - - . . _ _ - - ~ . _ . - _ - . - .

DOCKET NO. 50-346 UNIT SHUTDOWNS AND F0WER REDUCTIONS UNIT NAE D?vis-Besse Unit 1 DATE June 7. 1935 C0ffLETED BY B. Sarsour/M. Khazrai REPORT MONTH May, 1985 TELEPHONE (419) 249-5000, Ext. 384/

290 "s.

- E-  % E Licensee ae Ee Cause & Corrective E. UE e 3UI Event 34 5S Action to No. Date N ES "

E 5$" Report i EO I'd Prevent Recurrence

$6 ENE 0 8

NO UNIT SHUTDOWS OR SIGNIFICANT PO'4ER REDUCTIONS 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-Ol61)

E-Operator Training & License Fummination -

Previous Month F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-Other (Explain) Exhibit 1 - Same Source (9/77) B-Other (Explain) e h

. o REFUELING INFORMATION DATE: May 1985

1. Name of facility: Davis-Besse Unit 1

2. Scheduled date for next refueling shutdown: Spring. 1986

3. Scheduled date for restart following refueling: Simmer, t 1986

4. Will refueling or resumption of operation thereaf ter 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)?

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

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.

Ann: Nonn identified to date.

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

(a) 177 (b) 204 - Spent Fuel Annemblies

8. The present licensed spent fuel pool storage capacity and the size of any increane in licensed storage capacity that has been requested or in planned, in number of fuel assemblics.

Present: 735 Increanc size by: 0 (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 - annuming ability to unload the entire core into the npent fuct pool in maintained.

BHS/005

OPERATIONAL

SUMMARY

MAY, 1985 5/1/85 - 5/12/85:

Reactor power was maintained at approximately 90% power (power was limited to 90% due to the noise in the Reactor Coolant System flow transmitters, which is believed to have caused the reactor trip on April 24, 1985),

until 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on May 11, 1985, when a manual power reduction to approxi-mately 78% was initiated due to low load requirements.

5/13/85 - 5/31/85:

Reactor power was increased to approximately 90% power at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> on May 13, 1985.

During the period from May 13, 1985 to May 31, 1985, the unit operated at approximately 90% power except over the weekends when planned load reduc-tions to approximately 75% were initiated to support low load requirements.

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COMPLETED FACILITY CHANGE REQUEST FCR NO: 78-348 SYSTEM: Reactor Coolant System COMPONENT: Reactor Coolant Pumps CRANGE, TEST OR EXPERIMENT: FCR 78-348 changed the controls that automa-tically trip the Reactor Coolant Pump (RCP) and close the RCP seal return valves. This involved:

(1) Removing the closure of the seal return valve on a loss of seal injection for an operating RCP.

(2) Adding a 90 second time delay to the automatic closure of the seal return isolation valve (3) Changing the time delay on the tripping of the RCP motor from 120 seconds to 90 seconds (4) Reducing the trip setpoints on FIS-4133, FIS-4233, FIS-4333, and FIS-4433 from 45 GPM to 25 GPM Work was completed August 15, 1980.

REASON FOR CHANGE: The interlock changes were made to ensure that the seal return valves will close only on a loss of seal injection to an idle RCP. The time delay additions and setpoint revisions were made to prevent spurious closures of the seal return valve from short duration reductions in Component Cooling Water or seal injection flow. These changes were made to improve the reliability of the RCP seals.

SAFETY EVALUATION

SUMMARY

The function of the RCP real injection and seal return valves is to close as required per the Safety Features Actua-tion System. This function is not decreased by the change made by this FCR. Therefore, an unreviewed safety question does not exist.

t

, ,* .e COMPLETED FACILITY CHANGE REQUEST FCR NO: 81-023 SYSTEM: Concrete Masonry Block Wall COMPONENT: Wall 4016 CHANGE, TEST OR EXPERIMENT: FCR 81-023 modified wall 4016 by removing six columns of masonry block throughout the wall and installing steel box pilasters (vertical wall stiffeners) in their place. This wall is located on the 603' level of the Turbine Building and separates the Low Voltage Switchgear Room (428) and Battery Room B (428A). Work was completed August 24, 1984.

REASON FOR CHANGE: The change in the wall structure was required by NRC IE Bulletin 80-11 which showed during a seismic event, wall 4016 could experience masonry overstress. Therefore, steel box pilasters were installed in wall 4016.

SAFETY EVALUATION

SUMMARY

This change does not reduce the fire rating of the wall, nor affect the attached safety related conduits in any adverse manner. Therefore, this modification does not result in an unreviewed safety question.

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