ML20151L371
| ML20151L371 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 03/31/1988 |
| From: | Cipriani J, Storz L TOLEDO EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| KB88-00176, KB88-176, NUDOCS 8804220044 | |
| Download: ML20151L371 (6) | |
Text
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I OPERATING DATA REPORT DOCKET NO. 50-346 DATE 4/13/06 CO!,lPLETED BY J. Cipriani TELEPHONE (419) Z49-5000 OPERATING STATUS
- l. Unit Name:
Davis-Besse. Unit No. I Notes
- 2. Reporting Period:. March 1988 2772
- 3. Licensed Thermal Power (MWt):
925
- 4. Nameplate Rating (Gross MWe):
906
- 5. Design Electrical Rating (Net MWe).
904
- 6. Maximum Dependable Capacity (Gross MWe):
- 7. Maximum Dependable Capacity (Net MWe):
860
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report Give Reasons:
- 9. Power Level To Which Restricted. lf Any (Net MWe):
- 10. Reasons For Restrictions,if Any:
This Month Yr..to.Dete Cumulative
)
744 21184 84,840 II. Hours in Reporting Period.
221.3 1661.3 45.142,1
- 12. Number Of Hours Reactor Was Critical 0
0 53050.I
- 13. Reactor Reserve Shutdown Hours
- 14. Hours Generator On.Line 220.5 1.560 43,381
- 15. Unit Reserve Shutdown Hours 0
0 1.732.)
l
- 16. Gross Thermal Energy Generated (MWH) 381.871 3.306.442 101,268,641
- 17. Gross Electrical Energy Generated (MWH) 123.340 1.072.485 33.448.288
- 18. Net Electrical Energy Generated (MWH) 111.824 998.787 31.299.434
- 19. Unit Service Factor 29.6 a.3 51.1
- 20. Unit Availability Facto, 29.6 72.3 53.2 i
l
- 21. Unit Capacity Factor (Using MDC Net) 17.5 53.2 42.9 16.6 50.5 40.7 l
- 22. Unit Capacity Factor (Using DER Net) o u
32.5
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each):
(
Refueling - Started on March 10. 1988 - 26 weeks - Enda on September 12. 1988
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCI AL OPER ATION d
g6 p 8804220044 880331 k f PDR ADOCK 05000346 N/77) i R
i p;
+
4<'
AVERAGE DAILY UNIT POWER LEVEL 0-34 DOCKET NO, Davis-Besse. Unit 1 4/13/88 DATE J. Cipriant COMFLETED 8Y (419) 249-5000 TELEPHONE March 1988 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)
(Mwe. Net)
I ~
533 o
,7 538 o
2 532 o
3 521 4
20 0
514 0
5 21 528 0
6 22 7
23 0
517
)
8 24 0
517 0
9 25 10 26 0
1I 0
27 0
0 0
12 28 0
13 n
29 14 0
30 0
0 o
15 3,
0 16 INSTRUCTIONS On this fortnat.hst the average daily unit power lesel an MWe Net for each day in the repoviing inonth. Compute to the nearest whole megawatt.
rsIT11
t: NIT Situ 100WNS AND FCcEn REDUCTIONS pocgET no. 50-346 UNIT NAME Davis-Besee i DATE 4/13/DO March 1988 con't.ETED sv J. csprsaan REPORT MfWfTu TEI.ErnoME (419) 249-5000 est. 2365 Ib f*.
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88-3-10 S
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1 N/A N/A N/A The refueling outage @as initiated to perform scheduled raaintenance and refueling work.
O bthod:
'Enhibit C - Instructione for Freparation of Data Fr Forced Reement S: Scheduled A-Equipment Failure (Emplain) 1-Manuel Entry Sheets for Licensee Event Report (LER) 3-Meintenance or Test 2-Manual Scram File (NUREC-Ol61)
~
C-Refueling 3-Automatic Scree
~
D-Regulatory Restriction 4-Continuation from S
E-Operater Training & License E=eetnetton Previeue Month Enhibit I". sae, source F-Administrativa S-Load Reduettee
- Report challenges to rover Operated Relief valves C-Operational Error (Emplain) 9-Other (Emplain)
(FORVs) and Presouriser Code Safety selves (FCSVs)
IN>ther (Emplain)
W
d OPERATIONAL
SUMMARY
March 1988 3/1/88 - 3/10/88 Reactor power continued to be reduced during the month to six percent due to Cycle 5 coastdown.
3/10/88 - 3/31/88 Plant shutdown and cooldown was initiated to perform scheduled maintenance and refueling activities. The following are the more significant activities performed during this period.
1.
Baseline flov test on Main Generator Seal Oil System.
2.
I!ajor Control Room modifications began including removal of Steam and Feedvater Rupture Control System Panels for replacement.
3.
Turbine overhaul work began including removal on the generator field which was shipped to Chicago for rework.
4.
Significant cooling tower repairs began.
5.
Pre-outage work continued on major modifications to Makeup System as part of Feed and Bleed enhancements.
6.
Performance testing on the Containment Air Coolers, Decay Heat Exchanger 1-1 and Component Cooling Vater Heat Exchanger 1-1 vere completed.
3 5
4 9
J
---.m
c.
REFUELING INFORMATION Date:
March 1988 1.
Name of facility:
Davis-Besse Unit 1 2.
Scheduled date for next refueling outage? harch 1988 3.
Scheduled date for restart following refueling September 1988 4.
Vill refueling or resumption of operation thereafter require a technical specification change or other license amendment? If ansver is yes, what in general vill 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 sefety 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 Specifications changes (2. Safety Limits and Limiting Safety System Settings, 3/4.1 Reactivity Control Systems, 3/4.2 Power Distribution Limits and 3/4.4 Reactor Coolant System.)
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
May 1988 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.
1.
The highly absorbing silver-indium-cadmium axial power shaping rods vill be replaced with reduced absorbing inconel rods.
2.
The discrete neutron sources vill be removed from the core and not replaced.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, and (c) the new fuel storage areas.
(a) 177 (b) 204 - Spent Fuel Assemblies (c) 64 - New 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 i
or is planned, in number of fuel assemblies.
Present:
735 Increased size by: 0 (zero) 9.
The projected date of the last refueling that can be discharged to the j
spent fuel pool assuming the present licensed capacity.
1 Date:
1995 - assuming ability to unload the entire core into the spent fuel pool is maintaine_d I
A 5
e e
E6ISON E 0:50N PLAZA 300 MADtSON AVENUE TOLEDO, OHIO 43652 0001 April 14, 1988 KB88-00176 Docket No. 50-346 License No. NPF-3 Document Control Desk U. S. Nuclear Regulatory Commission Vashington, D. C.
20555 Gentlemen:
Monthly Operating Report, March 1988 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 March 1988.
If you have any questions, please contact Bilal Sarsour at (419) 249-5000, extension 7384.
Very truly yours, v
&Gx%
<U Louis F. Storz b
i Plant Manager Davis-Besse Nuclear Power Station LFS: GAG:ECC:BMS: pig Enclosures cci Mr. A. Bert Davis, v/l Regional Administrator, Region III Mr. Paul Byron, v/l l
NRC Resident Inspector t
Mr. A. V. DeAgazio i
NRC Project Manager
-