ML20054A075
| ML20054A075 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/06/1982 |
| From: | Harran G NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20054A068 | List: |
| References | |
| NUDOCS 8204150265 | |
| Download: ML20054A075 (6) | |
Text
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I AVERAGE DAILY UNIT POWER LEVEL
\\
50-245 DOCKET NO. _
]
Millstone 1 UNIT 820603 DATE j
[
COMPLETED By George Harran 203/447-1791 TELEPHONE Ext. 4194 i
FEBRUARY MONDi DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) j 596 37 594 2
sq6 18 596 591 3
19 596 4
596 20 559 5
596 596 21 6
597 22 595 7
598 23 595 8
598 24 592 9
597 596 25 10 593 11 591 27 596 12 0
28 595 13 201 29 14 555 30 15 595 31 16 596 INSTRUCDONS On this format.hst the average duly unit power leselin MWe Net for each day in the reporting month. C the nearest whole megawatt.
MCD of 654 Based on Commitment to New England Power Exchange.
(9/77) 8204150265 820311 DR ADOCK 05000245 PDR
FEBRUARY OPERATING HISTORY February 1982 Reactor Power at 100%
February 3, 1982 0011 Hours Reducing reactor power to 90% for turbine stop valve testing.
0043 Hours Backwashing condensers.
0220 Hours Reactor Power at 100%
February 10, 1982 0010 Hours Reducing Reactor power to 90% for turbine stop valve testing.
0045 Hours Backwashing main condensers.
0145 Hours
' Reactor Power at 100%
February 11, 1982 2305 Hours Reducing reactor power for maintenance to "B" feedwater regulation valve.
2357 Hours Reactor scram on low water level when "A" feedwater regulation valve cycled open and close.
Februa ry 13, 1982 0058 Hours Reactor critical, Rod 34-31, group 8 notch 08, moderator temperature 3930F, period 190 seconds.
0602 Hours Turbine on-line.
2330 Hours Reactor power at 76%.
February 14, 1982 1450 Hours Reactor power at 100%.
February 17, 1982 0001 Hours Reducing reactor power for turbine stop valve testing.
0055 Hours Reactor power at 100%.
0700 Hours Reducing reactor power to 95% because of loss R.S.S. when a fire broke out in the switchyard.
0 745 Hours Reactor power at 100%.
E BRUARY OPERATING d ISTORY - CONTINUED Feb ruary 24, 1982 0006 Ho trs Reducing reactor power to 90% for turbine stop valve testi ng.
0015 Hours Ba ckwashing mai n condens crs.
0027 Hours Control rod pattern a dj tstment.
0 328 Ho trs Rea ctar power at 100%.
Feb ruary 28, 1982 Reactor Power at 100%.
OPERATING DATA REPORT DOCKET NO. 50-245 DATE SEUbuJ l
COMPLETED IJY G. liarrati I
TEl.EPilONE 203/447-1791 Ext. 4194 OPERATING STATUS Millstone Unit 1 Notes
- 1. Unit Name:
- 2. Reporting Period:
February 1982 2011
- 3. Licensed Thermal Power (MW ):
- 4. Nameplate Rating (Gross MWer
- 5. Design Electrical Rating (Net MWe): 660
- 6. Maximum Dependable Capacity (Gross MWe):
684
- 7. Maximum Dependable Capacity (Net MWe):
6 54 i-
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report. Give Reasonc N/A N/A
- 9. Power Lese! To which Restricted.If Any (Net MWe):
Approx. 595 ftWE
- 10. Reasons For Restrictions. lf Any:
Main Turbine Complete 14th stage RLmoval This Month Yr..to Date Cumulatise II, llours In Reporting Period 672 1416
' f.98640
- 12. Number Of Hours Reactor Was Critical 647 1391 72645.1
- 13. Reactor Resene Shutdown llours 0
0 2775.8 I4. Ilours Generator On Line 642 1386 7UUc)./
- 15. Unit Resene Shutdown liours n
0 26.5
- 16. Gross Thermal Energy Generated (MWil) 1prA072 2723516 125763600
- 17. Gross Electrical Energy Generated (MWill 394500 856000 42317996
- 18. Net Electrical Energy Generated (MWil) 376154 814282 4036310b
- 19. Unit Senice factor 95.5 97.9 7 i.u l
j
- 20. Unie Availability Factor 95.5 97.9 71.0 l
- 21. Unit Capacity Factor (Using MDC Net) 85.6 87.9 62.6 l
- 22. Unit Capacity Factor (Using DER Net) 84.8 87.1 62.0 l
- 23. Unie Forced Ourage Rate 4.5 2.1 15.9
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Lacht:
N/A l
N/A
- 25. If Shut Down Ae i nd Of Report Period, fstimated Date of Startup.
N/A
- 26. Unirs in lest Status (Prior io Commercial Operationi:
I orecast Achiesed INI11 Al. CRITICA LIT Y INill AI Ell:01RICII'Y N/A CO%IMERCI AL OPFR ATION Pl/77 )
UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-245 UNIT NAME Millstone i DATE 820603 REPORT MONTH February COMPLETED BY G. Harran TELEPHONE 20'4/447-1791 Ext. 4194 ci 5 _a s
.=E _e g
2.s X Licensee 5*
5%,
c.
Cause & Corrective o
No.
Date g
3g
,;; g y Event
- '2 E3 Action to c$ E j;5g Report a rN G jO Prevent Recurrence Q
2 821202 F
30 A
3 N/A N/A N/A Scram occurred when "A" feedwater regulation valve cycled open.then closed.
e s
I 2
3 F: Forced Reason:
4 S. Scheduled A Equipment Failure (Explain).
Method:
Exhibit G - lastructions 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3 Automatic Scram.
Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination F-Administrative 5
G-Operational Error (Explain) 19/77)
Il-Other (Explain)
Exhibit I.- Same Source
REFUELING IMFORMATION REQUEST 1.
Name of facility:
Millstone 1 2.
Scheduled date for next refueling shutdown:
Fall 1982 3.
Scheduled date for restart foll,owing refueling:
Winter 1982 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes. Technical Specification changes regarding:
(1) Maximum average planar linear heat generating rate (2) Maximum critical power ratio 5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
s Summer 1982 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:
172 " Retrofit" 8 X 8 fuel asse~ mblies are scheduled for insertion in Cycle 9 (Reload 8) 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a) In Core:
580 (b) In SFP:
954 8.
The present licensed spent fuel pool storage capacity and the size of any in-crease in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
2184 Assem!.ies 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
?
1985, Spent Fuel Pool, full core off load capability is reached.
1991, Core Full, spent fuel pool contains 2120 bundles bkH:rmj p
e g e