ML19305B301

Monthly Operating Rept for Feb 1980

ML19305B301
Person / Time
Site:	Millstone
Issue date:	03/03/1980
From:	Harran G NORTHEAST UTILITIES
To:
Shared Package
ML19305B297	List: ML19305B296 ML19305B301
References
NUDOCS 8003190480
Download: ML19305B301 (6)

Text

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AVERAGE DAILY UNIT POWER LEVEL ig DOCKET NO.

50-245 Millstone -1 UNIT 03 DATE COMPLETED By G. Harran 203/447-1792 X655 TELEPHONE mom February DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 240 658 37 240 658 2

^

3 239 39 658 4

239 656 20 239 656 5

21 6

239 22 656 7

239 657 23

r 240 655 3

9 241 25 656 240 656 10 26 254 gg 27 655-12 583 655 28 655 653 13 29 14 657 30 658 15 3

16 658 1

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INSTRUCT 10NS l

l 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 MWE-Net is based on commitraent t'o New England Power Exchange.

(9/77) 5003100 f8D

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- OPERATISG DATA REPORT DOCKET NO.

50-245 DATE 800303 COMPLETED BY G_ Harran TELEPHONE 203/447-1792 X655 t-t, OPERATING STATUS

1. Unit Name:

Millstone Unit 1 Notes

2. Reporting Period:

February 1980

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3. Licensed Thermal Power (MWt):

2011 662

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4. Nameplate Rating (Gross MWe):

660

5. Design Electrical Rating (Net MWe):

~ ~'

684

6. Maximum Dependable Capacity (Gross MWe):

654

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report. Give Reasons:,

N/A N/A

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9. Power Level To Which Restricted. lf Any (Net MWe):

N/A 10.' Reasons For Restrictions. If Any:

.N/A I'

, This Month Yr to.Date

. Cumulative II. Hours In Reporting Period 696 1440-

• 81120:

12. Number Of Hours Reactor Was Critical 696 1440 61825

13. Reactor Reserve Shutdown flours 0

0 935 696 1440 59535.9

'14. Hours Generator On Line

15. Unit Reserve Shutdown Hours 0

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1073204 1782656 105830601

16. Gross Thermal Energy Generated (MWH) 17.' Gross Electrical Energy Generated (MWH) 367000 591900 35823296

18. Net Eh ctrical Energy Generated (MWH) 346290 563155 34202937

19. Unit Service Factor 100 100 7t a 100 100 73.4

'20. Unit Availability Factor 76.1 59.8 64.5 21.-Unit Capacity Factor (Using MDC Net) - *

22. Unit Capacity Factor (Using DER Net) 75.4 59.3 63.9 0

0 16.4

,23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Next 6 Months (Type.Date.and Duration of Each):

N/A c

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

N/A

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

Forecast Achieved INITIAL CRITICALITY

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OPERATING HISTORY February 1 --1980 Reactor power holding at 40% due to Isolation Condenser inop.

February 11, 1980 2000 Hours Isolation Condenser declared operational.

2040 Hours Increasing power to 100%

February 12, 1980 2115 Hours Reactor power at 100%

February 20, 1980 0030 Hours Reactor power reduced to 90% for turbine stop valve testing

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0040 Hours Increasing power to 100%

0105 Hours Reactor power at 100%

February 29, 1980 0000 Hours Reactor power reduced to 90% for turbine stop valve testing 0040 Hours Increasing p'ower to 100%

0100 Hours Reactor power at 100%

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Docket No. 50-245 Paga cf Date 800303 7

Unit Name Millstone - 1 1

Completed By G. Harran Telephone 203/447-1792 X655 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Fbnth February DATE SYSTEM COMPONENT MAINTENANCE ACTION 800602 Feedwater Coolant Motor Op'erater.1-MW-96A Rewound motor and replaced moveable contact Injection holder and contacts 801202 Service Water

'A' Service Pump Discharge Piping Replaced the instrument bushing because of Instrument Connection co rosi,on r

..801302-Diesel Generator

1. 6 Injection Nozzle Replaced 'a leaking nozzle assembly (on contact side) 801302 Core Spray Valve Operator, 1-CS-21A.

Replaced a cracked bevel gear housing 801402 Closed Cooling Water "B" TBSCCW Heat Exchanger Plugged leaking tubes

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3 REFUELING INFORitATION REQUEST 1.

Name of facility:

Millstone 1 2.

Scheduled date for next refueling shutdown:

Fall 1980 3.

Scheduled date for restart foll,owing refueling:

Late Fall 1980-4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Yes. Technical Specification chenges regarding:

(1) Maximum Average Planar Linear Heat Generating Rate (2) ' Maximum Critical Powe.r Ratio 5.

Scheduled date(s) for submitting proposed licensing action and supporting information:

Summer 1980 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis

. methods, s'ignificant changes in. fuel design, new operating procedures:

J.

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 pool:

(a) In Core:

580 (b) In SFP:

776 8.

The present licensed spent fuel pool storage capacity and the size of any f a-crease in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

2184 assemblies i

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

14AR. 9nont Fuel Pnnl. full core off load cacability is reached.

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

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