Text

Monthly Operating Rept for Nov 1979
	ML19256F250
Person / Time
Site:	Millstone
Issue date:	12/04/1979
From:	Young R; NORTHEAST UTILITIES
To:	;
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ML19256F248	List: ML19256F247; ML19256F250;
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	NUDOCS 7912180365
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S AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

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Millstone-1 UNIT f

791204 DATE

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oung COMPLETED BY TELEPIIONE 203-447-1792 x-475 t

MONTH November i

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 654 17 655' 653 2

gg 656 3

654 19 656 4

654 657 20 5

631 21 657 6

618 22 657 610 7

23 658 8

615 24 657 9

612 25 657 10 596 26 657 11 178 27 656 542 12 28 654 13 607 656 29 14 603 30 656 15 580 3

16 446 INSTRUCTIONS On this format, list the average daily unit 'ower 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 commitment to New England Power Exchange.

(9/77) 1608 076~

7912180

o 9

OPERATING DATA REPORT

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DOCKET NO. 50-245 DATE 791204 f

C051PLETED BY.1 Youno f

TELEPHONE 203-447-792 X-475' OPERATING STATUS

1. Unit Name:

Millstone 1 Notes

2. Reporting Period: - November 1979

3. Licensed Thermal Power (SiWt):

2011 662

4. Na:ncplate Rating (Gross SIWE):

5. Design Electrical Rat %g (Net SIWE):

660

6. Siaximum Dependable Capacity (Gross Siwe):

684 5

654

7. Maximum Dependable Capacity (Net 51We):

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

N/A

9. Power Level To Which Restricted,If Any (Net 5fWe):

N/A

10. Reasons For Restrictions.If Any:

N/A This Month ~

~

Yr to.Date Cumulative

11. Hours in Reporting Period 720 8,016 78.936

12. Number Of Hours Reactor Was Critical 720 6,197 59.684

13. Reactor Reserve Shutdown Hours n

0 892'

14. Hours Generator On-Line 720 6.083.2 57,403.5

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (31WH) 1,361,488 11,660,220 102.713,508

17. Gross Electrical Energy Generated (MWH) 463,300 3,970,100 34,775,196

18. Net Electrical Energy Generated (51WH) 442.657 3,785,627 33,204.145

19. Unit Service Factor 100 75.9

/2.7

20. Unit Availability Factor 100 75.9 72.7

21. Unit Capacity Factor (Using Af DC Net) 94.0 72.2 64.3

22. Unit Capacity Factor (Using DER Net) 93.2 71.6 63.7

23. Unit Forced Outage Rate 0

5.8 16.8-

24. Shutdowns Scheduled Over Next 6 5fonths (Type. Date.and Duration of Each):

Shutdown tentatively scheduled for the last week in December for installation of acoustic mnnitnre on safety relief valve tailoice.

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

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

Forecast Achieved INITIAL CRITICA LITY N/A.

INITIAL ELECTRICITY COMSIERCIA L OPER ATION kh (4/77)

OPERATING HISTORY November 1, 1979:

Reactor Power at 100%.

November 5, 1979: 0815 hours0.00943 days 0.226 hours 0.00135 weeks 3.101075e-4 months -

Secured 'A' main condenser to stop tube leakage.

0835 hours0.00966 days 0.232 hours 0.00138 weeks 3.177175e-4 months -

Reduced reactor power to stay within ETS limits on main condenser AT.

0845 hours0.00978 days 0.235 hours 0.0014 weeks 3.215225e-4 months -

Reactor power at 95%.

November 10, 1979: 2155 hours0.0249 days 0.599 hours 0.00356 weeks 8.199775e-4 months -

Reduced reactor power in preparation for main condenser maintenance.

2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months -

Reactor power at 45%.

November 11, 1979: 0105 hours0.00122 days 0.0292 hours 1.736111e-4 weeks 3.99525e-5 months -

Reactor power being held at 15%

1110 hours0.0128 days 0.308 hours 0.00184 weeks 4.22355e-4 months -

Condenscr repairs completed, increased reactor power.

1350 hours0.0156 days 0.375 hours 0.00223 weeks 5.13675e-4 months -

Reduced power for additional condenser repairs 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months --

Holding reactor power at 25%.

2025 hours0.0234 days 0.563 hours 0.00335 weeks 7.705125e-4 months -

Completed repairs, increased power.

2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months -

Reactor power at 63%.

November 12, 1979: 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months -

. Reactor power being held at 90% to maintain condenser AT within ETS specification.

November 13, 1979: 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months -

Increased power to 94%.

November 15, 1979: 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months -

Decreased power to enter 'A' main condenser for maintenance.

2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months -

Reactor power at 45%.

November 16, 1979: 1115 hours0.0129 days 0.31 hours 0.00184 weeks 4.242575e-4 months -

Condenser repairs completed, increased reactor power.

1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months -

Reactor power at 94%.

2030 hours0.0235 days 0.564 hours 0.00336 weeks 7.72415e-4 months -

Reactor power at 100%.

November 28, 1979: 0005 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months -

Reduced reactor power for Turbine Stop Valve Testing.

0025 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months -

TSVT complete, increased power.

0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months -

Reactor power at 100%.

1608 078

D**]O *@'3 }N f gig 3 jf

, J UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-245 o

UNIT NAME Millstone 1 DATE 791204 COMPLETED BY R. Young REPORTMONT11 November TELEPIIONE 203-447-1797 x-475

.5?

}

.E Licensee Eg Cause & Corrective No.

Date g

3g oj$

Event g'd Q

Action to H

jE jgg Report a mU Prevent Recurrence g

d 13 791110 S

N/A B

N/A N/A HC HTEXCH Reduced power for main condenser maintenance. Power was increased following maintenance.

14 791115 S

N/A B

N/A N/A HC HTEXCH Reduced power for main condenser maintenance. Power was increased following maintenance, e

O CO O

Nw 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.

0161)

Event Report (LER) File (NUREG.

D-Regulatory Restriction 4-Other (Explain)

E-Operator Training & License Examination F Administrative 5

G-Operational Er.or (Explain)

Exhibit I-Same Source (9/77)

Il-Other (Explain)

e REFUELING INFORf% TION REQUEST 1.

Name of facility:

Millstone 1

~

2.

Scheduled date for next refueling shutdown:

Fall 1980 3.

Scheduled date for restart follo ifng refueling,:

Late Fall 1980 4.

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

Yes. Technical Soecification changes regarding-(1) Maximum averaae olanar linear heat aeneratina rate (2) Minimum critical power 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, significant changes in fuel design, new operating procedures:

168 " Retrofit" 8 x R fuel assomhlips 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:

sRn (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 number of fuel assemblies:

2184 assemb1ies*

9.

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

1986 RHY:rmf 1608 080

Docket No. 50-245 Page 1 of 1 Date 791205 Ut.it Name Millstone 1 Completed By R. Young Telephone 203-447-1792 X-475 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month November DATE SYSTEM COMPONENT MAINTENANCE ACTION 791109 Closed Cooling Water "B" Reactor Building Closed Plugged two leaking tubes.

Cooling Wa ter Heat Exchanger 791111 Condensate System "B" Conc'ensate Booster Pump Replaced " flexitallic gasket on seal water supply, l ine.

791115

. Low Pressure Coolant 1-LP-10B Motor Controller A new controller.was installed as a temporary Injection fix until a Design Change is completed to in-crease the size of the contacts in the motor controller. (see LER 79-34/3L) 791115 480VAC Electrical EF-3 Transfer Switch Solenoid Coil Replaced coil and damaged wiring.

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ML19256F250

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