ML20066D507

Monthly Operating Rept for Oct 1981

ML20066D507
Person / Time
Site:	Davis Besse
Issue date:	11/09/1981
From:	Sarsour B TOLEDO EDISON CO.
To:
Shared Package
ML20066D501	List: ML20066D500 ML20066D507 ML20066D511 ML20066D520
References
NUDOCS 8211110373
Download: ML20066D507 (5)

Text

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• AVERAGE DAILY UNIT POWER LEVEL

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DOCKET NO.

. UNIT Davis-Besse Unit 1 November 9, 1981 COMPLETED BY Bilal Sarsour TELEPHONE (419) 259-5000, Ext.~ 251 MONTH * ***

DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe Net) 1 845 o 37 2 845 gg qn 3 878 273 19 4

883 615 20 5 879 , g 802 6 877 22 432 7 883 308 23 8 880 663 24 9 886 803 25 10 878 844 26 II 868 27 844 12 880 833 28 13 882 822 29 14 881 30 767 IS 878 770 33 I6 864 INSTRUCTIONS On this format.hst the average daily unit power level m MWe-Net for cash day in the reporting m.inth. Compute to the nearest whole mepwatt.

(9/77) r211110373 811109 PDR ADOCK 05000346 R PDR

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OPERATING DATA REPORT DOCKET NO. 50-346 DATE November 9, 1981 COSIPLETED llY R4ini R,rsour TELEPilONE (4191 259-5000, OPERATING STATUS Ext. 251 US b'm Davis-Besse Unit 1 Notes

2. Reporting Period: October, 1981 2772 ,

3. Licensed Thennal' Power (51Wt):

4. Nameplate Rating (Gross AlWe): 925

5. Design Electrical Rating (Net A!We): 906

6. Ataximum Dependable Capacity (Gross SIWE): 934

7. Alaximum Dependable Capacity (Net alWe): 890

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 AlWe):

10. Reasons For Restrictions.If Any:

This Month Yr..to Date Cumulatise

11. Ilours In Reporting Period 745 7,296 36,605

12. Number Of flours Reactor Was Critical 716.1 5,111.3 19,495.5

13. Rcactor Reserve Shutdown llours / 9 7 - U9.8 484 4- $ _ ^, ^, '1_ 9

14. Ilours Generatur On.Line 3, 3 2.I.(,

686.8 4.911.3, 17.959.1

15. Unit Reserve Shutdown flours 0 0 1_731.4

16. Gross Thermal Energy Generated (51Wil) 1,746,360 1].698,556 38,603,362 .

17. Gross Electrical Energy Generated (A!Wil) 5 7 7 , S.2.5. . _. 3.896.016 ,12.871.370

18. Net Electrical Energy Generated (51Wil) 545.363 3_656_100 11_920;601

19. Unit Service Factor 92.2_ 67.3 49.8

20. Unit Availability Factor 92.2 67.3 54.9

21. Unit Capacity Factor (Using SIDC Net) 82.3 56.3_ 3R.4

22. Unit Capacity Factor (Using DER Net) 80.8 55.3_ 37.7

23. Unit Forced Outage Rate

7. 8 _ 28.2 25.6

24. Shutdowns Scheduled Oier Next 6 Alonths! Type. Date.and Duration of Each):

1982 Refueline Outane Scheduled February 26. 1982 - May 21. 1982

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

, 26. Units In Test Status ! Prior io Commercial Operation): Forecast Achiesed INITIA L CRITICA LITY INITIAL ELECTRICITY COMMERCIA L OPERATION (9/77)

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DOCKET NO. 50-346 #

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UNIT SHUTDOWNS AND POW: ! REDUCTIO.NS ,

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UNIT NAME Davis-Besse Unit 1 DATE _ November 9.1981 COMPLETED BY Bilal sarsaur REPORT MONTil October. 1981 TELEPiiONE (419) ?so_snnn, Ext. 25

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-, ,[ g 3 jY5 Licensee ,Eg h Cause & Correethe No. Date g 3: R js5 Event g,7 E-3 Action to F

fE $ jgg Report a mo jV Present Recurrence-6 15 81 10.16 F 38.5 A 3 NA NA NA The reactor tripped on high React'or Coolant System pressure.

16 81 10 22 F 19.7 A 2 NA NA NA The turbine was tsken off-line

' following CIV problems. The reactor ,

was manually tripped following a Steam and Feedwater Rupture Control System trip.

See Operational Summary for further details.

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l 2 3 4 F: Forced Reason: Method:

S: Scheduled Exhibit G. Instructions A Equipment Failure (Explain) 1. Manual for Preparation of Data

• D Maintenance of Test 2 Manual Scrani. Entry Sheets for Licensee -

C Refueling 3 Automatic Scram. Event Report (LER) File (NUREG-D Regulatory Restriction 4 Continuation from Previous Month 0161)

E-Operator Training & License Examination 5 Load Reduction F-Administrative 9 Other (Explain) 5 i G Operational Eeror (Explain) Exliibit 1 Same Source P8/77) -

il Oiher (Explain)

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OPERATIONAL

SUMMARY

10/1/81 - 10/16/81 Reactor-power was maintained at approximately 100% full power with the generator gross load at approximately 915 MWe until 2334 hours0.027 days <br />0.648 hours <br />0.00386 weeks <br />8.88087e-4 months <br /> on October 16, 1981, when the reactor tripped on high. Reactor Coolant System (RCS) pressure. The trip was due to a loss of non-essential Bus F-3. Bus F-3 was lost because of a ground fault sensed by transformer BF-3. - As a result, generator stator cooling water and main feedwater block valve indication were lost which led to the trip.

10/17/81 - 10/1'8/81 The reactor was critical at 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />. The turbine generator was synchronized on line at 1403 hours0.0162 days <br />0.39 hours <br />0.00232 weeks <br />5.338415e-4 months <br /> on October 18, 1981.

10/19/81 - 10/22/81 The reactor power was slowly increased and was limited by hav-ing No. 1 High Pressure Feedwater Heater string out of service.

The unit reached approximately 95% power on October 21, 1981.

Reactor power was maintained at 95% until 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on October 22, 1981 when the operator initiated a manual reduction of reactor power due to combined intercept valves (CIVs) 3 and 4 problems.

The reactor power was maintaided at approximately 8% with the turbine off-line until 1519 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.779795e-4 months <br /> on October 22, 1981, when the reactor was manually tripped following a Steam and Feed-water Rupture Control System trip.

When the turbine was reset to get hydraulic pressure for CIV testing, steam pressure control was switched from steam genera-tor outlet to steam header indication. Due to slight differ-ences between these pressure indications, turbine bypass valves -

started closing which eventually led to a low steam generator level causing the Steam and Feedwater Rupture Control System trip.

10/23/81 The reactor was critical at 0119 hours0.00138 days <br />0.0331 hours <br />1.967593e-4 weeks <br />4.52795e-5 months <br />. The turbine generator was synchronized on line at 1019 hours0.0118 days <br />0.283 hours <br />0.00168 weeks <br />3.877295e-4 months <br />.

10/24/81 - 10/31/81 Reactor power was slowly increased and attained 97% power on October 29, 1981. Reactor power was reduced to 94% due to a leaking extraction steam bellows expansion joint in #1 Low Pressure Turbine to 61 Deaerator.

Reactor power was maintained at approximately 94% for the re-

mainder of the month.

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. ' . " .: " October, 1981 REFUELING INFORMATION DATE:

1. Name of facility: Davis-Besse Unit 1

2. Scheduled date for next refueling shutdown: February 26, 1982

3. Scheduled date for restart following refueling: May 21, 1982

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)?

Reload analysis is scheduled for completion as of December, 1981. No tech-nical specification changes or other license amendments identified to date.

5. Scheduled date(s) for submitting proposed licensing action and supporting information. February 1982

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. __

None identified to date

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

44 - Spent Fuel Assemblies 177 (b) 8 - New Fuel Assemblies (a)

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

Present 71s Increase 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. J l

Date 1988 - assuming ability to unload the entire core into the spent fuel pool is maintained l

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