ML19345D398

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Monthly Operating Rept for Nov 1980
ML19345D398
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 12/08/1980
From: Sarsour B
TOLEDO EDISON CO.
To:
Shared Package
ML19345D397 List:
References
NUDOCS 8012150055
Download: ML19345D398 (6)
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Text

.

AVERAGE D AILY UNIT POWER LEVEL

. DOCKET NO. 50-346 eggy Davis-Besse Unit 1 I"ce=ber 8, 1980 DATE CO%fPLETED BY Bilal Sarsour TELEPHONE 419-259-5000, Ext.

251 Nove=ber, 1980 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POhER LEVEL (MWe-Net) (ywe.3, 3 1 0 37 647 0 gg 657 3 0 g, 653 4 . O _ 20 655 5 0 21 655 6 40 2.3 703 7 41 23 817 3 14 24 818 9 228 25 814 10 266 26 830 11 290 g 804 12 171 28 814 13 111 810 29 ,

14 316 30 807-15 582 3g 16 622 INSTRUCTIONS On this fortnat. list the avenge daily unit power leselin MWe Net for each day in the reporting month. Compute to the nearest whcie megawatt.

(9/77)

I 8012150055 .

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OPERATING DATA REPORT DOCKET NO. 50-346 DATE December 8, 1980 COMPLETED BY Bilal Sarsour TELEPHONE 414 754-9000, Ext 251 OPERATING STATUS

1. Unit Name: -

Davis-Besse Unit 1 Notes

2. Reporting Period:

November, 1980

3. Licensed Thermal Power (31W ): 2772
4. Nameplate Rating (Gross MWe): 925
5. Design Electrical Rating (Net 51We): 906
6. Maximum Dependable Capacity (Gross MWe): 934
7. Maximum Dependable Capacity (Net MWe): R90
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Gise Reasons:
9. Power Level To Which Restricted,if Any (Net MWe):
10. Reasons For Restrictions.lf Any:

This Month Yr.-to.Date Cumulative 720 8,040 28,565

11. Hours in Reporting Period 684.7 2,762.7 13,726.7
12. Number Of Hours Reactor Was Critical
13. Reactor Reserve Shutdown flours 6.3 6.3 28,764.3 530.8 2,539.5 12,413.8
14. Hours Generator On-Line
15. Unit Reserve Shutdown Hours 3.42 3.42 1,731.42
16. Gross Thermal Energy Generated (MWH) 1.012.290 5.699.595 25,899,102 .
17. Gross Electrical Energy Generated (MWH) 339.042 , , ,

1,922,601 8,646,112

18. Net Electrical Energy Generated (MWP) 309.064 1,792,851 7,963,429
19. Unit Service Factor 73.7 31.6 44.1
20. Unit Availability Factor 74.2 31.6 50.6
21. Unit Capacity Factor iUsing MDC Net) 48.2 25.1 33.3
22. Unit Capacity Factor (Using DER Net) 47.4 24,6 32.7
23. Unit Forced Outage Rate 25.9 17.0 25.6
24. Shutdowns Scheduled Over Next 6 Months IType. Date.and Duration of Each):
25. If Snut Down At End Of Report Period.EsGmated Date of Startup:
26. Units In Test Status (Prior to Commercial Operation): Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCI A L OPER ATION (4/77 )

I 50-346' DOCKET NO.

UNIT SilUTDOWNS AND 00WE!! REDUCilONS UNIT N AME Dav i "i-B e s m- If 1 uccember 8, 1 DATE COMPLE1 ED l!Y Pilal Sarsour 1 Ell.l*llON E 419-259-5000, Ext. 251 REPORT MONTil _ November. 1980 "t. -

Cause & Corrective

,E g 3 ).

js&

Licensee Event h

gy h'8 e

Aoion to No. Date g 3g i Prevent itecurrence H y5 $ j;gg Repori er in v yO 6

NA NA NA The unit outage which began on April 80 04 07 S' 122.2 C 4 4 7, 1980 was still in progress at the l beginning of the month. l l

NA NA INSTRU Generator automatic voltage control 5 80'11 06 F .7 B 1 problems. ..

i NA XX TRANSF Turbine / reactor trip due to an indi-6 80 11 06 F 22.5 A 3 cated fault on the aux 111ary trans-former (see Operational Summary for i details) J e

3.4 B 6 NA ' NA NA Overspeed turbine trip test. l 7 80 11 07 S

%d XX INSTRU Reactor trip on high reactor coolant 19.4 A 3 NA 22'Sl 8 80 11 08 F system pressure due to faulty header pressure error signal comparitor in the 6 9 inte' grated control system (see Opera- l M tional Summary for details) 3 4 Mi 2 Methud: Exhibit G -Instructions l g F: Forced S: Schedu!ed Reason:

A Equipment Failure (Expfsin) 1 hfanual 2-Manual Scram.

for Preparation of Data Entry Sheets for Licensee ,

i b rg. Maintenance of Test Event Report (1.011) Fde (NUREG-3 Automatic Scram.

1 Refueling 0*61)

+OtheriEmplain) f) Regulatory Restriction ILOperator Training & License Examinatiun 4-Continuation 5

F Adnumstrative 5-Reduction Eshibit i . Same Source

~

G Opesatiimal 1:irut (Explain) 6-Other 11 Other 11:splain) 01/77)

l .

$0-346 * '

UNITSHUTDOWNS ANDIOWEtt REDUCTIONS -

DOCKETNO.

UNIT NAME Davls-liesse Unit 1 DATE December 8. 1980 COMPLETED itY _Hilal sarcnnr REPORT MONTlf

  • November. 1980 TELEPilONE 419-259-5000._ Ext. 251 Eg Cause & Corrective

,$g 3 ) .Y h Licensee h"

g Action to

No. Date & Eg s .a s & Event g,7

. vi V 9g 8 Prevent Recurrence H yE $ 5.

- ;5 c g Report a u, .

O 21.0 C 3 NP-33-80-105 . NA NA Reactor trip on high reactor cooldnt

, 9 80 11 12 F system pressure (see Operational Summary for details).

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2?-50 I?50 l%d '

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3 4 I 2 Exhibit G . Instructions Reason: Method:

F: Forced for Preparation of Data

' A Eiluipment Fai!are(Explain) 1-Manual S: Schedu!cd 2 Manual Scram, Entry Sheets for Licensee B-Maintenance of Test Event Report (LER) File (NUREG.

C Refueling 3 Automatic Scram.

4thtsstExplsmi 016I) L D.Regul.iiory Restiiction l'-Operator Training & License Examination 4-Core.inuat ion 5-Reduction 5

I Attmiintia ive Exlubit 1 Same Source G Op. rational tiros (Explain) 6-Other g 07/17) Il Oihes (1.splain)

e OPERATIONAL SUNMARY NOVEMBER, 1980 Zero Power Physics Testing began on October 31, 1980, and the reactor was deborated to criticality at 0942 hours0.0109 days <br />0.262 hours <br />0.00156 weeks <br />3.58431e-4 months <br /> on November 1, 1980. Physics testing was completed at 0139 hours0.00161 days <br />0.0386 hours <br />2.29828e-4 weeks <br />5.28895e-5 months <br /> on November 3, 1980.

l 11/6/80 The turbine generator was on line at 0214 hours0.00248 days <br />0.0594 hours <br />3.53836e-4 weeks <br />8.1427e-5 months <br />, marking the completion of the unit outage which began on April 7, 1980.

At 0412 hours0.00477 days <br />0.114 hours <br />6.812169e-4 weeks <br />1.56766e-4 months <br /> the turbine generator was taken off line due to generator automatic voltage control problems and was returned on line at 0441 hours0.0051 days <br />0.123 hours <br />7.291667e-4 weeks <br />1.678005e-4 months <br />. At 1557 hours0.018 days <br />0.433 hours <br />0.00257 weeks <br />5.924385e-4 months <br />, a turbine / reactor trio was initiated from 18 percent of full power. While performing electrical lineups (in preparation for testing), an indicated fault on the auxiliary transformer caused the main generator output breakers to open. The reactor was returned to criti-cality at 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br /> after.it was found that the aborting pins

  • were still installed in the "A" phase current transformer causing the erroneo'ts indication. The pins were removed from the cabinets.

11/7/80 The turbine generator was returned on line at 1426 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.42593e-4 months <br />. The turbine overspeed trip test was successfully performed at 1950 hours0.0226 days <br />0.542 hours <br />0.00322 weeks <br />7.41975e-4 months <br />, and the turbine generator was brought back on line at 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br />.

11/8/80 At 0303 hours0.00351 days <br />0.0842 hours <br />5.009921e-4 weeks <br />1.152915e-4 months <br /> the unit experienced a reactor / turbine trip on high reactor coolant system pressure. The unit was in a power escalation at approximately 25 percent of full power coming off of the lov level limit of 35 inches in the steam generator.

The header pressure error signal comparitor in the integrated control system failed resulting in plant oscillations. The r'eactor was returned to criticality at 1652 hours0.0191 days <br />0.459 hours <br />0.00273 weeks <br />6.28586e-4 months <br />, and the unit was on line at 2229 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.481345e-4 months <br /> the same day.

11/9/80 - 11/11/80 Reactor power was increased to 40 percent of full power at 2242 hours0.0259 days <br />0.623 hours <br />0.00371 weeks <br />8.53081e-4 months <br /> on November 9,1980 with turbine generator load at approxi-mately 330 MWe. Reactor power was maintained at approximately 40 percent through November 11, 1980 to perform physics testing.

11/12/80 Reactor power was maintained at 40 percent until 1403 hours0.0162 days <br />0.39 hours <br />0.00232 weeks <br />5.338415e-4 months <br /> when the reactor tripped on high reactor coolant system pressure.

As a check of the input power supply to the steam and feedwater rupture control systen steam generator level power supplies was being performed, the test equipment was shorted out due to instrument and control technician error. Inverter YV2 blew a fuse causing loss of 120 V essential bus Y2. The loss of Y2 caused a trip of the reactor protection system channel 2. At l

1

OPERATIONAL

SUMMARY

NOVEMBER, 1980 PACE 2

.11/12/80 Continued the same time the reactor coolant system flow indication being fed to the integrated control system through the reactor protec-tion system channel 2 vent to zero. The loss of reactor coolant system flow indication caused BTU limits of the integrated con-trol system to immediately cut feedwater flow. This rapid re-duction of feedwater caused the trip from high reactor coolant system pressure.

11/13/80 The reactor was returned to criticality at 0515 hours0.00596 days <br />0.143 hours <br />8.515212e-4 weeks <br />1.959575e-4 months <br />. The turbine generator was returned on line at 1102 hours0.0128 days <br />0.306 hours <br />0.00182 weeks <br />4.19311e-4 months <br />. Reactor power was increased to 40 percent by the end of the day.

11/14/80 - 11/15/80 Power escalation was continued _until 1545 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.878725e-4 months <br /> on November 15, I '

1980 when the 75 percent power level was reached. Preparations were underway to perform physics testing at this power level.

11/16/80 At 0318 hours0.00368 days <br />0.0883 hours <br />5.257936e-4 weeks <br />1.20999e-4 months <br /> the unit experienced a feedwater transient. While at 74 percent of full power,.the ICS received a false indication that the main feedwater block valve 1 was closed and transferred to the startup feedwater flow, which caused the main feedwater control valve to go 100 percent open. This caused the OTSG 1 level to go up to approximately 400 inches (Technical Specifi-cation limit is 348 inches). The operators took manual control of feedwater and reactor power and gradually decreased feedwater and OTSG 1evel to within the technical specification ILmit in 15 minutes. A jumper was installed to hard wire the main block valve positio~n input to the integrated control system.

11/17/80 - 11/21/80 Reactor power was maintained at approximately 75 percent of full power for physics testing.

11/22/80 - 11/30/80 Reactor power was increased to 92 percent of full power at 1915 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.286575e-4 months <br /> on November 22, 1980 and maintained there to the end of the month.

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