ML19269B948
| ML19269B948 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/04/1979 |
| From: | Young R NORTHEAST UTILITIES |
| To: | |
| Shared Package | |
| ML19269B947 | List: |
| References | |
| NUDOCS 7901190126 | |
| Download: ML19269B948 (6) | |
Text
-
AVERAGE DAILY UNIT POWER LEVEL 50-245 DOCKET NO.
Millstone - 1 3,lT DATE 790104 COMPLETED BY R. Young 203-447-1792 X475 TELEPilONE December MONT11 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (Mhe-Net) gyg,,3,g 653 654 I
7 655 654 2
is 654 656 3
39 654 4
20 653 21 657 5
653 6
22 656 654 7
23 654 8
654 24 654 654 9
25 495 10 E
26 593 II 654 546 27 12 232 647 28 0
653 13 29 238 34 30 653 488 654 15 3:
625 16 INS 1 RUCTIONS 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.
NOTE: MDC of 654 FM -Net is based on commitment to the flew England e
Power Pool.
(9/77) 7 90119 0 /M
,y.
OPERATING DATA REPORT 50-245 DOCKET NO.
DATE /901U4 C05tPLETED BY R. Youno TELEPHONE 203-447-1792 x-475 OPERATING STATUS Notes
- 1. Unit Name:
Millstone 1 Decer.ber
- 2. Reporting Period:
2011
- 3. Licensed Thermal Power (51Wt):
662
- 4. Nameplate Rating (Gross 5!We):
- 5. Design Electrical Rating (Net SIWE):
684
- 6. Statimum Dependable Capacity (Gross 51We):
654
- 7. Staximum Dependable Capacity (Net 51We):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
NA NA
- 9. Power Level To Which Restricted. If Any (Net StWe).
- 10. Reasons For Restrictions,If Any:
This hionth Yr.-to.Date Cumulative 744 8,760 70,920 II. Hours In Reporting Period
- 12. Number Of Hours Reactor Was Critical 707 7.754 53,487
- 13. Reactor Reserve Shutdown Hours 37 42 892
- 14. Hours Generator On.Line 699.8 7,673.3 51,320.3
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (51WH) 1,346,980, 14,342,748 91,053,288 17 Gross Electrical Energy Generated (.51WH) 458,20,0 4,875,500 30,805,096
- 18. Net Electrical Energy Generated (5tWH) 437,850 4,654,924 29,418,518 94.l%
87.6%
72.4%
- 19. Unit Service Factor 94.lk 87.66 72.4%
- 20. Unit Availability Factor 90.0a 81.3%
63.4%
- 21. Unit Capacity Factor (Usi g SIDC Net) 80.bb 62.94
- 22. Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outage Rate 5.9%
2.8%
17.9%
- 24. Shutdowns Scheduled Oser Ne.st 6 51onths (Type, Date, and Duration of Each):
Annual refuel and maintenance outage tentatively scheduled for nine weeks; commencing April 28, 1979.
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup:
- 26. Units in Test Stat:'s IPrior to Commercial Operation):
Forecast Achiesed INITIAL CRITICA LITY INITIAL ELECTRICITY C0515tERCIA L OPER ATION (9/77)
~"
l 50-245 UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME F1111 stone - I DATE 790104 December COMPLETED BY R. Youno REPORT MONTil 20J-44/-l/92 x-475 TELEPilONE i
We E
c m
5
"*U Licensee Er E%
Cau-
~. o rective
" =
No.
Date h
jj k
3S Event y
Astnen to yE 3 ;jj =
Report a mo Prevent Recurrence H
o g
u Q
17 781212 F
44.2 H
3 NA NA NA The unit was removed from service l
due to an inadvertent reactor scram resulting from main steam isolation valve closure and APRM Hi-Hi flux.
Following main steam line flow in-strumentation check out the unit was
~
l returned to service.
18 781225 F
0 B
4 NA HC HTEXCH Reduced oower for main condenser l
maintenance and control rod pattern adjustment.
Power was increased following maintenance.
I i
i I
2 3
4 F: Forced Reason:
Method:
Exhibit G. Instructions S: Scheduled A Equipment Failure (Explain) 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 4-01her (Explain) 0161)
E-Operator Training & License Examination F-Administrative 5
G-Operational Error (Explain).
Exhibit I. Same Source (9/77)
II-Ot her ( Explain) i
REFUELING IflFORf%TI0fl REQUEST 1.
Name of facility:
Millstone 1 2.
Scheduled date for next refueling shutdown:
790428 3.
Scheduled date for restart foll,owing refueling:
790623 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes! Tech. Spec. changes regarding:
(1) Maximum average planar linear heat generating rate.
(2) Minimum critical power ratio (3) Automatic pressure relief valve mod. includina new settings (4)
Remove the 1.3% AK requirement from rod drop analysis.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information :
February 1979 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:
Yes!
Proposed 143 retrofit 8x8 fuel assemblies purchased from General Electric.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
580 629 (a) In Core:
(b) In SFP:
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:
Modification currently in progress. Approximately 50% complete, to increase storage capacity to 2184 assemblies.
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
March 1978 RHY:rmj
- OPERATING HISTORY -
December 1, 1978:
Reactor power at 100%
December 6,1978:
0035 h rs. -
Reduced power to 90% for Turbine Stop Valve Test 0100 hrs. -
Completed TSVT, increased power 0130 hrs. -
Reactor power at 100%
December 12, 1978:
0832 hrs. -
Reactor scram on ApRM Hi-Hi flux resulting from MSIV closure December 13, 1978:
2012 hrs. -
Commenced reactor startup 2145 hrs. -
Reactor critical #369, C.C.C., Group VII, Rod 18-23, position 4, temp = 3500F, T = 120 sec.
December 14, 1978: 0444 hrs. -
Main generator on line 0800 hrs. -
Holding power at 36% for main condenser repairs 1440 hrs. -
Work completed, increasing power 2400 hrs. -
Reactor power at 72%
December 16, 1978:
1740 hrs. -
Reactor power at 100%
December 20, 1978: 0015 hrs. -
Reduced power for TSVT 0040 hrs. -
Completed TSVT, increased powar 0110 hrs. -
Reactor power at 100%
December 25, 1978:
1220 hrs. -
Reduced reactor power to conduct repairs to "A" main condenser 1325 hrs. -
Reactor power at 45%
1855 hrs. -
Increased power, adjusted control rod pattern December 26, 1978:
1930 hrs. -
Reactor power at 100%
December 27, 1978:
1120 hrs. -
Decreased power to 45% for condenser maintenance 1235 hrs. -
Reactor power at 45%
1630 hrs. -
Repairs completed, increased power December 28, 1978:
0515 hrs. -
Reactor power at 100%
RHY:rmj
Docket No.
50-245 Page 1 of 1
Date 790105 Unit Name Mi llstoile 1 R. Young
[.
Completed By '2 W 47-1792 x475 Telephone CORRECTIVE MAINTENANCE
SUMMARY
FOR SAFETY RELATED EQUIPMENT Report Month Deceniber DATE SYSTEM COMP 0NENT MAINTENANCE ACTION
- 781213 Containment Atmos-Containment Personnel Access Purchased preformed gasket to pass local leak, phere Control rate test.
781213 Main Steam System Main Steam Isolation Valve Cleaned and Lubricated switches.
1-MS-10 Scheduled to replace switches during 1-MS-lC Indicating switches Refuel Outage 1-MS-1A