ML19344A426

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Jul 1980
ML19344A426
Person / Time
Site: Millstone Dominion icon.png
Issue date: 08/01/1980
From: Harran G
NORTHEAST UTILITIES
To:
Shared Package
ML19344A414 List:
References
NUDOCS 8008200277
Download: ML19344A426 (6)


Text

._.

. r.

'h,,

AVERAGE D AILY UNIT POWER LEVEL 1

\\

50-245 DOCKET NO.

I UNIT Millstone-1 800801 DATE COSIPLETED BY i

TELEPilONE 203/447-1792 ext. 655 1

MONTI{

July DAY AVERAGE DAll.Y POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(MWe. Net)

I 657 654-17 656 655 2

,3 656 i

3 19 344 4

634 521 20 653 5

21 642 6

654 22 652 7

655 654 23 654 8

24 655 9

655 25 606 io 646 628 26 607 11 27 655-12 0

657 l

28 363 13

,9 656 3o 652 14 619 i

653 655 is 3,

653 16 INSTRUCTIONS f

On this format, list the average daily unit power leselin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

tiOTE: MDC of 654 MWE based on comitment to New England Power Exchange.

(9/77) 8008200 g.yy

~

OPERATING DATA REPORT DOCKET NO.

50-245 DA rE 800_8_0_1 C051Pl.ETED 11Y G. Harr_an l

TEl.Erl!ONE 203/447-1792 ext. 655 4

OPER ATING STATUS l

N"5

1. Unit Name:

Millstone Unit 1

2. Reporting Period:

July 1980

3. Licensed Thennal Power (stWt):

j011 622

4. Nameplate Rating (Gross atWe):
5. Design Elcetrical Rating (Net alWe): 660
6. Sinimum Dependable Capacity (Gross StWe):

684 654

7. Stasimum Depenilable Capacity (Net.\\lWe):
8. If Chan;;es Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

N/A N/A N/A

9. Power Level To which Restricted. If Any (Net S!We):
10. Reasons For Restrictions. lf Any:

N/A N/A N/A This 5!onth Yr..to Date Cumulative 744 5111.0

' e.

84791.0

11. !!ours In Reporting Period 729 4522.0 64907.0
12. Number Of ifours Reactor Was Critical 16 592.3 1527.3
13. Reactor Resene Shutdown !!ours
14. Ilours Generator On Line 717.5 adon n 62585.9
15. Unit Resene Shutdown fleurs 26.5 26.5 26.5
16. Gross Thermal Energy Generated (.\\tWil) 1,374,632 7552346 111600291 470,100 2567347 37798743
17. Gross Electrical Energy Generated (SIWH1
18. Net Electrical Energy Generated (stWH) 448.876 2447571 36087353
19. Unit Senice Factor 96.4 87.8

.73.8 100.0 88.4 13.8

20. Unit Asai:abi!ity Factor 92.3 73.2 65.1
21. Unit Capacity Factor (Using 51DC Net)
22. Unit Capacity Factor (Using DER Net) 01 a 72_g 64.5
23. Unit Forced Outage Rate 0.0 0.3 15.7-
24. Shutdowns Scheduled Oser Nest 6 Stonths (Type. Date and Duration of Eacht:

Annual Refuel and Maintenance outage scheduloa en cornt,ence October 11, 1980 for apprcximately 8 - 10 weeks.

25. If Shur Down At End Of Report Period. Estimated Date of Startup:

N/A

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achiesed INITIAL CRITICALITY INITI A L ELECTRICITY CO.t!.\\lERCI A L OPER ATION P3/771

-. ~..,.

I REFUEliflG IflFORf%710ft REQUEST 1.

!;ame of facility:

Millstone 1 2.

Schedulad date for next refueling shutdown:

Approximately October 11, 1980 3.

Scheduled date for restart foll,cwing refueiing:

January 1980 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:

5 Summer 1980 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:

168 " Retrofit" 8 x 8 fuel assemblies are scheduled for insertion in cycle 8 (reload 7).

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage i

pool :

(a) In Core:

580 (b) In SFP:

776 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 i

nurter of fuel assemblies:

2184 assemblies i

I 9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

1 1985, Spent Fuel Pool, full core off load capability is reached.

I 1991, Core Full, Spent Fuel Pool contains 2120 bundles.

i RHY :rmj

[

t d

[

s y-i-

.=

i OPERATING HISTORY July '

1980 Steady state 100% power.

July 11,1980 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> Commenced reducing power in preparation for IE Bulletin 80-17 (Scram Testing).

July 12, 1980 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Reactor power at 15%.

0007 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Generato" taken off-line.

0208 hours0.00241 days <br />0.0578 hours <br />3.439153e-4 weeks <br />7.9144e-5 months <br /> Performed a manual scram.

0520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> Commenced reactor star"-up.

0838 hours0.0097 days <br />0.233 hours <br />0.00139 weeks <br />3.18859e-4 months <br /> Reactor critical, group 21, rod 14-39, notch 8, temperature 493*F (period not recorded).

1338 hours0.0155 days <br />0.372 hours <br />0.00221 weeks <br />5.09109e-4 months <br /> Performed an auto scram.

1842 hours0.0213 days <br />0.512 hours <br />0.00305 weeks <br />7.00881e-4 months <br /> Commenced reactor start-up.

2158 hours0.025 days <br />0.599 hours <br />0.00357 weeks <br />8.21119e-4 months <br /> Reactor critical, group 11, rod 50-23, notch 8, temperature 416*F, period 144 sec.

July 13, 1980 0225 hours0.0026 days <br />0.0625 hours <br />3.720238e-4 weeks <br />8.56125e-5 months <br /> Generator on-line.

0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> Reactor power at 60%.

July 14, 1980 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br /> Reactor power at 100%.

July 19, 1980 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br /> Decreasing reactor power to 40% to repair leaking main condenser tubes.

2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> Performed a control rod pattern change.

2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br /> Main condenser tube leaks repaired.

Increasing reactor power.

! July 20,1980 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> Reactor power at 78%.

i July 21, 1980 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> Reactor power at 100%.

~~

r

,--s

---nr----,,--,

g

,- ----