ML19224D364
| ML19224D364 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/06/1979 |
| From: | Caba E TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML19224D359 | List: |
| References | |
| MOR-790630, NUDOCS 7907110520 | |
| Download: ML19224D364 (6) | |
Text
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AVERAGE D AILY UNIT POWER LEVEL 50-346 DOCKET NO.
Dav is-Besse Unit 1 g.g 7 uly 6, 1979 DATE COMPLETED BY Erda1 C.
Caba 419-259-5000, Ext.
TELEPHONE 236 MONTil June, 1979 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY PCWER LEVEL (MWe-Net)
(MWe Net) 0 0
37 1
0 0
18 2
0 0
3 39 0
0 20 4
0 5
0 21 0
0 6
22 0
0 23 7
0 C
24 S
9 0
25 0
0 10 0
26 11 0
27 0
0 12 0
28 0
0 29 13 0
0 14 30 0
3y 15 16 0
INSTRUCTIONS On this format.hst the ascrage dar!:. umt power leselin MWe-Net for each day in the reporting month. Compute to the nearest whole mepwatt.
(9 /77 )
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OPERAllNG DATA REPORT 50-346 DOCKET NO.
DATE Jul:
6, 1979 COMPLETED BY.1rd M C Caba TELEPilONE J J.51? ; 0-- 5 00 0, Ext.
236 OPERATING S J \\7 Ui Davis-Eesse Unit 1 Notes
- 1. Unit Nune:
d""U' 3979
- 2. Reporting Per;ud:
2772
- 3. Licensed Thennal Power (MWt):
925
- 4. Nameplate Rating (Gross MWe):
900
- 5. Design Electrical Rating (Net MWe):
to be determined
- 6. Maximum Dependab!c Capacity (Gross MWe):
t de m mined
- 7. Maximum Depend.ihle Capacity (Net MWe):
S. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. %e Reason <.
2CE"
- 9. Power Lesel To which Restricted. If Any (Net MWe):
';RC OIE Bul1 etine and Shutdown Orders
- 10. Rcasons For Restrictiens. If Any:
This Month Yr.-t o-Da t e Cumubtise 720 4,343 16,108
- 11. Ilours In Reporting Period 0
1,747.4 8,379.2
- 12. Number Of flours Reactor Was Critical 720 1,61.2.2 2,402.5
- 13. Reactor Resene Shutdown flours
- 14. Ilours Generator On-Line 1,675.I 7,408.3 O
720 2,464 1,464
- 15. Unit Resene Shutdown flours 0
3,879,097 14,066,66/
- 16. Gross Thermal Energy Generated (M,/II)
- 17. Gross Electrical Energy Generated (MWil) 1,293,268 4,677,023 0
0 1,212,558 4,25',013 IS. Net E!cetrical Energy Generated (Mbil) 0 38.6 47.5
- 19. Unit Senice Factor 100 72.3 57.9
- 20. Unit Asail.ibility Factor to be determined
- 21. Unit Capacity Factor (Using MDC Net) 0 30.8 32.5
- 22. Unit Capacity Factor (Using DER Net) 0 4.8 22.4
- 23. Unit Iorced Outage 8 tate
- 24. Shutdowns Schednfed Oser Next 6 Months (Ty pe. Date,and Duration of Each):
Julv 10[1979
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achiesed INITI A L CRIT lCA LII Y INITI AL EL EC T RICI TY CONI \\lERCI \\t nPER ATION 325 007 (9/77 )
.t i
DOCKET NO.
50-346 _
Davis-Jesse Unit 1 UNil S!!UIDOWNS AND PJW'.!t REDUCTIONS UNIT NAME
~
DATE Ju!v h-1979 1;rJai C,
Caba COMPLETED BY REPORT MONTil Tmo
'o70 TELEPl!ONE 419-2 5 9-5m. Ex t.
236 l
1 3g "h
Y
- 1. icensee E r,,
1, Cat:sc & Corrective No.
Dat e g
3g R
jg5 Event rf 'j Dj Attion to
~
}U Prevent Recurrence gE g ;y, Report a mu H
6 9
79 03 30 S
720 D
1 N/A N/A N/A The unit remained in an outage th'e entire raonth.
Refer to the attached outage sunnary of. lune, 1979, for outap,e activitien this month, s
i
< -a
.q a
1 2
3 4
3 Method:
Ex.ubit G Instructions F: Forced Reason:
1.M.m u al for Pre;wration of Data S: Schedu!ed A 1 <;uipment Failure (Esplain)
II. Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee 3 Automatic Scram.
livent Repost (LER)1:de (NUREG-c.R fort ag D-Reguiatory Rest.iction 4-Other (lixplain) 0161) 1 -Operator Training & License Examination 5
F-Adinumt rat is e Exhibit !- Sa. e Source G-Opera tional 1:n or (E xplain)
(9/77) i1 O:hcr (1:xplain)
OUTACE SDDL\\RY June, 1919 The unit outage which began at 2142 hours0.0248 days <br />0.595 hours <br />0.00354 weeks <br />8.15031e-4 months <br /> on Marci.
1979, was still in pregress through the end of June, 1979. The outage was exts longer than anticipated due to additional NRC startup restraints which were imposed as a result of an ongoing analysin of the Three Mile Island incident.
The following are the nore significant outage activities performed during the menth of June:
In addition, modifi-1.
Procedure modification to comply with NRC requests.
cations of procedures were made due to the re-evaluation of the Bahcoes and Wilcox small break analysis and natural circulation.
2.
'Ihe performance of hydraulic snubber surveillance testing was completed.
Testing of the anticipatory reactor trip system which was installed last 3.
month was conpleted.
4.
Testing of the auxiliary f eed pump flow indication and dynamic braking was completed.
5.
Personnel instruction on what the procedure major modifications invcived.
6.
The containment air cooler fans had to be purged of the old greace and replaced Mth new grease.
7.
Radiography an the first six elbow welds on the number 1 auxiliary feedwater line per NRC concerns.
8.
Ucrk was done on the aux'.liary boilcr due to various s team leaks.
9.
The performance of eighter n month surveillance tests which were required to be completed p
'u. to the reactor internal vent valve test.
This was done lengthen the available operation time af ter this outage.
to 10.
Oil leaks were found or, the 01 Startup Transforner and repaired.
restraints implementation of sarious Facility Change Requests which were 11.
The to startup.
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June, 1979 REFUELING INFORMATION DATE:
Davis-Eesse Nuclear Power Station Unit 1 1.
Name of f acility:
2.
Scheduled date f or next refueling shutdown:
March, 1950 3.
Scheduled date for restart following refueling:
May, 1930 4.
Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment?
If ancwer is yes, what, in general, will these be? If answer is no, has the reload fuel desiga and core configuration been reviewed by your Plant Saf ety Review Conmittee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?
Yes, roe attached 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
Decenber, 1979 6., important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis me thod s, significant changes in fuel design, new operating procedures.
The spent fuel pool capacity expansion program is awaitint a final ':RC Safety Evaluation Report to proceed in time f or completion pri or to ref ut ing.
All licensee submittals are complete including environmental assessnent questions.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
(a) 177 (b) 0 (zero) 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.
475'(735 total)
Present 260 Increase size by 9.
The proj ected date of the last refueling that can be discharged to the spent fuel pool assuaing the present licensed capacity.
Date March, 1980 - May, 1980 (assuming ability to unlead the entire core,into
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the spent fuel pool is maintained. )
n
s REFUELING INIORMATION (Continued)
June, 1979 Page 2 of 2 4.
The follow. y; Technical Specifications (Part A) will require revision:
2.1.1 & 2.1.2 - Reactor Core Safety Limits (and Bases) 2.2.1 - Reactor Protection Systeu Instrucentation Setpoints (and Bases) 3.1.3. 6 - Regulating Rod Inserti on Limits 3.1.3.7 - 1:od Program
- 3. 2.1 - Axia l Powe r Inbalance (and Bases)
The f ollowing Technical Specifications (Part A) nay also require revision:
3.1.2.8 6 3.1.2.9 - Borated Water Sources (and Bases) 3.2.4 - Quadrant Power Tilt (and Eases) 3.2.5 - DSB Parameters (and Bases)
)
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