ML20085D515
| ML20085D515 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 09/30/1991 |
| From: | Sarsour B, Storz L TOLEDO EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| KB91-0933, KB91-933, NUDOCS 9110160243 | |
| Download: ML20085D515 (6) | |
Text
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TOL f DO EDISON A Gir'T'W t wgy' Cmtpry
( O!5UN FLAZ A IK) f/A0!GUf 4 WI NUf f OLl'DO. OHtO 436'3P 0001 October 9, 1991 KB91-0933 Docket No. 50-346 License No. NPF-3 Document Control Desk U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20814 Centlement Monthly Operating Report, September, 1991 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly operating Report for Davir-Besse Nuclear Power Station Unit No. 1 for the month of So tember, 1991.
If you have any questions, please contact Bilal Sarsour at (419) 321 7384.
Very truly yours, j
g~* ( {7 %.
(7) Cita;p i
louis F. Storz Plant Manager Davis-Besse Nuclear Power Station BMS/ tid Enclosures cc4 Mr. Pau' Byron NRC Rraident Inspector Mr. A. Bert Davis Regional Admir.istrator, Region III Mr. J. D. !!opkins NRC Senior Project Manager a
hi"li$16d243910930 g/
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AVER AGE DAILY UNIT P0hER LEVEL I
DOCKE114).
50-346 Davis-Besse til UN!T D ATE October 9.
1991 1
COMPLETED BY _Illi ni Sarsour TELEPil0NE (419)321-7384 Seistember, 1991 MONT11 DAY AVER AGE DAILY P0hER LEVEL DAY AVER AGE DAILY POWER LEVEL lMhe Neil e ywe.Nei f
0 0
37 0
0 2
,3 3
0 g) 0 4
0 20 0
0 0
21 6
0 O
7 0
0 23 3
0 0
,4 9
0 0
3$
10 0
26 0
0 11 27 0
o 12 2S 0
0 13 29 0
0 14 30 15 0
33 l
16 0
INSTRUCT 10NS On this format,hst the average daily unit power lesel in MWe Net for each da) in the repo.iing inonth. Compute to the nearest whole nwgawatt.
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Ol'LR ATING DATA RLPORT DOCKL1NO.
_50-346 DAIL Qttebet_3,1991 COMPLEllDitY JLilal Sarnour 1ELLPilCNL f610 321-7384 OPIRAllNG S1 ATUS Davis-liesce Unit #1 Notes
,, g,;, 3,
- 2. Reporting Period; Septa ber, 1991
- 3. Licenwd T hermal Power (Mht L 2772 925
- 4. Nameplate Rating (Grou MWe1
- 5. Design Electrical Rating (Nel Mhe):
9 0
938 6, Mnimum Dependable Capacity (Grow (*the t
- 7. Masimum Dependable Capacity (Net Mher 874
- b. If Change Occur in t'apacity Ratings (Items Number 3 Through 7) Since Last Report.Giie Reasons:
- 9. Power Lesel To which Restricted,li Any (Net MWe):
- 10. Reasons For Restrictium.lf An):
This Month Yr..to.Dete Cumulatise i1. Ilours in Reporting PenM 720.0 6,551.0 115,440
- 12. Number Of Ilours Reactor Wai Critical 0.0 5,808.9 64,930.I
- 13. Reactor Resene Shutdown flours 0.0 C.0 5,393.7
- 14. Ilours Generator On Line 0.0 5,808.2 62,877.,
- 15. Unit Resene Shutdown lloun 0.0 0.0 1,732.5
- 16. Grost Thermal f nergy Generated (MWlu 0.0 15,413,204 153,539.691 11 Grow Electrical Energy Generated (MhH) 0. f,L_,,,
5.141,425 50,871,442
- 18. Net Electrical Energy Generated (MWlO 0.0
,,, 4,884,823 47.8'i3,451._
- 19. Unit Senite factor 0.0 88.7 54.5
- 20. Unit Asailability factor 0.0 88.7 56.0
- 21. Unit Capacity f actor (Using MDC Net) 0.0 85.3 47.4 2.L Unit Capacity Factor (Using DER Net) 0.0 82.3 45.7
- 23. Unit Forced Outige Rat, 0.0 0.0_
25.4
- 24. Shutdowns Scheduled Oser Nest 6 Months (1)pe. Date.and Duration of I ach t
- 25. If Shut Down At End Of Report Period lstimated Date of Startup:
- 26. Un;ts in Test Status lPrior to Commercial Operationt forecast Achiesed 4
INITI A L CRlilCA L11Y INiilAL ELECTRICITY COMMLRCl AL OPTR AllON (9D 7 I
tarr samown Ano rowEm REzucrzes nocstr so.
50-347 tatt amE oa,1.-ee.g. el arE October 9. 1991 CORFIZTED BY Balal Sarsour mErwr mern September, 1991 mZramE uls) 321-ne e e
- e Ye0 1,1censee yj Cause & Corrective e_
m c a e e IOe Event a 4 c U Action to
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case e
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jj g Report e go treeent Becurrence a
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R n
3 91-08-31 S
720 C
4 NA NA NA The nuit outage which began on (contd)
August 31, 1991, was still in progress through the end of September, 1901.
See Operational Su= mary for further details.
e F: Forced Beason:
' Method:
Edtabat G - Instructions for Preparation of Data 5: Nhe&aled A 8;quigment Fa11ure (Esplain) 1-Manual Ent_Y sheets for Licensee Even* Report (IZR)
B-Mainter.ance or Test 2 8%eual scram File (R*. REG-0161)
C-Refueling 3-Anztomatse scran 4
EHiegulatory P,striction 4-<.ontinuattoc fr:e E-operator Training 6 License Esausnation Previous Pbmh Enhabit I - Samo Source F-Adninistrative FImad Reinction
- Report challenges to Pmser Operated Relief valves W rational Error (Explain) 9-other (Explain)
(PORval and Pressurager Code Safety valves (PCSVs)
N r (Esplaint i
r m
Operational Summaty September, 1991 The unit outage, which began on August 31, 1991, was still in p ogress through the end of September, 1991.
The following are tne more significant outage activities performed or still in progress during the month of September, 1991.
1)
Steam Generator 1-2 eddy current testing was completed.
- 1) Surveillance specimen activities were successfully completed.
- 3) Completed the integrated Steam and Feedvater Rupture Control System (SFRCS) testing.
- 4) Emergency Core CoollPg System (ECCS) Loop 1 outage vas completed.
- 5) Completed Safety Features Actuation System (SFAS) modification for Channels 2 and 4.
- 6) Completed the eddy current inspection of High fressure Feedvater Heaters 2-4 and 2-5.
- 7) Completed tha heat load test for Decay Heat coolers, Emergency Core Cooling System Room Coo)ers, and Component Cooling Vater heat exchangers.
- 8) Completed initial fuel shuffle and fuel assembly ultrasonic inspection.
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- 9) The ultrasonic insoection of the Figh pressure injection nozzle area HP-59 is still in progress.
- 10) The eddy current inspection of Steam Generator 1-1 is still in progress.
- 11) The Local Leak Rate Testing (LLRT) and hydrostatic testing nie progressing with a total of 125 of the 195 scheduled tests complete.
- 12) Emergency Core Cooling System (ECCS) Loop 2 outage is still in progress.
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REFUELING INFORMATION Date:
September 1991 1.
Name of facility Davis-Desse Unit 1, 2.
Scheduled date for next refueling outege? Hatch 1993 i
3.
The number of fuel assemblies (a) in the core and (b) in the spen' fuel storage pool, and (c) the nov fuel storage areas.
(a) 17S (b) 394 (c) 3 4.
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, in number of fuel assemblies.
Present:
735 Increased size by approximately 900 by 1994 is under reTiew 5.
The projectes Jate of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
Date:
1996 - assuming ability to unload the entire core into the spent j
fuel pool is maintained
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