ML20212P397
| ML20212P397 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/31/1986 |
| From: | Sarsour B, Storz L TOLEDO EDISON CO. |
| To: | Haller N NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| KB87-0001, KB87-1, NUDOCS 8703160095 | |
| Download: ML20212P397 (7) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL 50-346 DOCKET NO.
L Davis-Besse Unit 1 UNIT DATE January 14, 1987 Bilal Sarsour COMPLETED BY TELEPHONE (419) 249-5000, Ext. 7384 MONTH December 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
0 g7 2
0 0
gg 3
0 0
39 4
0 0
20 5
0 0
21 6
0 22 0
7 0
0 23 g
0 0
24 9
0 25 43 10 0
26 86 13 0
233.
27 12 0
28 289 13 0
294 29 14 0
56 30 15 0
0 33 16 0
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 )
8703160095 861231 PDR ADOCK 05000346 R
PDR S
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l OPERATING DATA REPORT f
DOCKET NO. ~50-346 DATE January 14, 1987 COMPLETED BY Bilal Sarsour TELEPHONE (419) 249-5000, Ext. 7384,
OPERATING STATUS
- 1. Unit Name:
Davis-Besse Unit 1 Notes December 1986
- 2. Reporting Period:
- 3. Licensed Thermal Power (MWt):
2772
- 4. Nameplate Rating (Gross MWe):
925
- 5. Design Electrical Rating (Net MWe):
906
- 6. Maximum Dependable Capacity (Gross MWe):
904 860
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
1
- 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 8.759 73.824
- 12. Number Of Hours Reactor Was Critical 178.0 178.0 36.055.I
- 13. Reactor Reserve Shutdown Hours 566.0 566.0 4.624.8
- 14. Hours Generator On-Line 116.8 116.8 34,488.6
- 15. Unit Reserve Shutdown Hours 0.0 0.0 1,732.5
- 16. Gross Thermal Energy Generated (MWH) 129.064.0 129.064.0 81.426.664.0
- 17. Gross Electrical Energy Generated (MWH) 28.765_,
28.765 26.962.387
- 18. Net Electrical Energy Generated (MWH) 3.486 3.486 25,236,663
- 19. Unit Service Factor 15.7 1.3 48.8
- 20. Unit Availability Factor 15.7 1.3 49.1
- 21. Unit Capacity Factor (Using MDC Net) 0.54
.05 39.7
- 22. Unit Capacity Factor (Using DER Net) 0.52
.04 37.7
- 23. Unit Forced Outage Rate 84.3 98.7 37.1
- 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:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY l
COMMERCIAL OPERATION i
(4/77) l
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DOCKET NO.
'50-346 UNIT SHUTDOWNS AND POWER REDUCTIONS
' UNIT NAle!
Davie-Be wa Unit 1-DATE January 14, 1987
' COMPLETED BY Bilal Sarsour REPORT MONTH December 1986 TELEPHONE-419-249-5000, Ext. 7384 4
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Date s
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85 06 09 F
571.4 A
4 LER.85-013
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.SG The unit remained shutdown follow-Contd ing the reactor trip on 6/9/85.
1 86 12 24 F
13.6 A
1 LER 87-01 JA NA
'A manual turbine shutdown was initi-
'ated when a new main generator nega-
~
tive sequence relay actuated upon closure of ACB34560.
2 86 12 26 F
0.6 A
1 N/A SB FCV Turbine generator was taken off line to repair <#1 Main Turbine. Control Valve.
3 86 12 30 F
41.8 A
1 N/A SB PSP Turbine generator was taken off line due to two steam leaks on the steam lines downstream of Control Valves 3 and 4.
I 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 Previous Month F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-Other (Explain)
Exhibit I - Same Source.
(9/77)
H-Other (Explain)
J
a OPERATIONAL
SUMMARY
DECEMBER 1986 The unit remained shutdown until 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on December 22, 1986, when the reactor was deborated to criticality. The turbine generator was synchronized on line at approximately 1011 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.846855e-4 months <br /> on December-24,1986, marking the completion of the unit outage which began on June 9, 1985.
The following are the more significant outage activities performed during this month:
1)
Closing numerous maintenance work orders and surveillance tests 9
required for startup
- I 2)
Verified that CF30 (core flood check valve) had seated properly after indication of earlier leakage 3)
Troubleshooting the Main Steam Isolation valves (MSIVs) after indication of increased stroke time On December 22, 1986, while the unit was at approximately 15%, a reactor trip occurred. A low level in Steam Generator #2 caused a Steam and I
Feedwater Rupture Control System (SFRCS) actuation, which in turn tripped the Anticipatory Reactor Trip System (ARTS) and the Main Turbine. The valve could not be opened fast enough in hand to prevent the trip.
The reactor criticality was established at 1011 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.846855e-4 months <br /> on December 24, 1986.
The turbine generator was synchronized on line at 1922 hours0.0222 days <br />0.534 hours <br />0.00318 weeks <br />7.31321e-4 months <br /> on December 24, 1986.
During the generator synchronization, and at approximately 2038 hours0.0236 days <br />0.566 hours <br />0.00337 weeks <br />7.75459e-4 months <br /> on December 24, 1986, a manual turbine shutdown was initiated when a new main generator negative sequence relay actuated upon closure of ACB34560.
The turbine generator was synchronized on line at 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br /> on December 25, 1986.
The reactor power was maintained at approximately 20% power until 1525 hours0.0177 days <br />0.424 hours <br />0.00252 weeks <br />5.802625e-4 months <br /> on December 26, 1986, when a manual power reduction to approximately 15% was initiated by the operator to take the turbine generator off line to repair Main Turbine Control Valve #1.
The turbine generator was synchronized on line at approximately 1559 hours0.018 days <br />0.433 hours <br />0.00258 weeks <br />5.931995e-4 months <br /> on December 26, 1986.
Reactor power was slowly increased to 40% of full power which was attained at approximately 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> on December 27, 1986.
q
.. OPERATIONAL
SUMMARY
DECEMBER 1986
.PAGE 2 0F 2
' Reactor power was maintained at this power level until 0612 hours0.00708 days <br />0.17 hours <br />0.00101 weeks <br />2.32866e-4 months <br /> on December 30, 1986, when the turbine generator was taken off line due to two steam leaks on the steam lines downstream of Control Valves 3 and 4.
The leaks resulted when instrument stub taps blew off the steam lines.
The reactor stayed critical and maintained at approximately 10% power for the rest of the month.
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REFUELING INFORMATION DATE: December 1986 1;
Name of facility: Davis-Besse Unit 1 2.
Scheduled date for next refueling shutdown: February 1988 3.
Scheduled date for restart.following refueling: April 1988 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).-
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
Summer, 1987
'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 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 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.
Date:
1996 - assuming ability to unload the entire core into the spent fuel pool is maintained.
BMS/005
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- o TOLEDO
%mm EDiGON January 14, 1987 KB87-0001 File: RR 2 (P-6-86-12)
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, December 1986 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 December 1986.
If you have any questions, please feel free to contact Morteza Khazrai at (419) 249-5000 Extension 7290.
Yours truly,
}
5F tr Plant Manager Davis-Besse Nuclear Power Station LFS/MK/ljk Enclosures cc:
Mr. James C. Keppler, w/1 Regional Administrator, Region III Mr. James M. Taylor, Director, w/2 Office of Inspection and Enforcement Mr. Paul Byron, w/1 NRC Resident Inspector
,,( Yj e
Nuclear Records Management, Stop 3220 I
LJK/002 THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652