Text

Monthly Operating Rept for Aug 1980
	ML19332B004
Person / Time
Site:	Millstone
Issue date:	09/03/1980
From:	Harran G; NORTHEAST NUCLEAR ENERGY CO.
To:	;
Shared Package
ML19332B002	List: ML19332B001; ML19332B004;
References
	NUDOCS 8009190459
	Download: ML19332B004 (7)
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OPERATING DATA REPORT 50-245 DOCKET NO.

DATE 800903 COhlPLETED BY G. Harran

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-Ext. 655-2U3-44/-3792 TELEPliONE OPERATING STATUS ~

I Millstone U it I Notes

1. Unit Namet

2. Reporting Period:

August 1980

3. Liecused Thermal Power (MWt):

2011

4. _ Nameplate Ratin;(Gross MWe):

622 660

5. Design Electrical Rating (Net SIWE);

6. Maximum Dependable Capacity (Gross SIWE):

684

7. 5f aximum Dependable Capacity (Net MWe):

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

NA-

9. Power Level To Which Restricted. If Any ( et MWe):

NA

10. Reasons For Restrictions. If Any:

This Month Yr. to.Date Cumulative 744 5,855.0 ' e.

~ 85,535.0

11. I!ours In Reporting Period

12. Number Of ifours Reactor Was Critical 744 5,266.0 65,651.0

13. Reactor Reserve Shutdown liours 0

592.3.

1,527.3

14. Ilours Generator on.Line 744 5.234.0 63.329.9

15. Unit Resene Shutdown llours 0

26.5 26.5

16., Gross Thermal Energy Generated (51Wil) 1,438,111 8,990,457

.113,038,402

17. Gross Electrical Energy Generated (MWi{}

__ 492 s 6@._...

3,059,947 38,291,343

18. Net Electrical Energy Generated (MWti) 474,635 2,922,206 36,561,988

19. Unit Service Factor 100 89.4 74.0

20. Unit Availability Factor 100 89.8 74.1

21. Unit Capacity Factor (Using MDC Net) 97.5 76.3 65.4

22. Unit Capacity Factor (Using DER Net) 96.7 75.6 64.8

23. Unit Forced Ourage Rate -

0.0 0.3 15.6

' 24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Eacht:

Annual' refuel and raintenance outage schedule to commence October 4,1980 for approximately 9 - 11 weeks.

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

NA-c 26. Units in Test Status (Prior o Commercial Operationi:

Forecast Achiesed

. INITIAL CRITICALITY INITIAL ~ ELECTRICITY NA

~- COMM ERCI A L'OPER ATION 22 -

(4/77)

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' ' - 1

. AVERAGE DAILY UNIT POWER LEVEL' 50-245 DOCKET NO.

UNIT. Millstone - 1 D ATE'-

800903 G. Ha nan C051PLETED BY 203-447-1792 TELEPilONE Ext. 6b5 SiONT11 Auaust' DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL l

(SIWE Net).

(51We-Net) 65'4 653 g7 2

654 is 645~

3 655-39 652 653 4

20 653 5

655 653 21 6

650 650 22 7

653-328 23 8

584 24 565 9

653 646 25 l

10 652 26 630 L

11 653-27 644 12 651 28 645 13 639 642 29 34 616 639' 30

(:

15 653 31 638 16 654 INSTRUCTIONS '

On this format, list the average daily unit power levelin htWe Net for each day in the reporting month. Compute to the nearest ihole megawatt.

MDC of 654 MWe based on. commitment to New England Power Exchange.

(4/77I 6

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Page-1 of 2-OPERATING HISTORY August 1,'1980 Steady state 100% power.

T August _ 6,11980 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months Reduce reactor power to'90%

for Turbine Stop Valve Testing.

0110. hours

. Turbine stop valve complete.

Reactor power 100%.

August 8,1980 0755 hours0.00874 days 0.21 hours 0.00125 weeks 2.872775e-4 months Reactor. power reduced to_85%

to repair a condensate booster pump leaking seal.

1 2350 hours0.0272 days 0.653 hours 0.00389 weeks 8.94175e-4 months Condensate booster pump seal

- leak repaired.

Reactor' power returned to 100%.

August 13, 1980 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months Reducing reactor power to 75%

for main condenser backwashing.

2230 hours0.0258 days 0.619 hours 0.00369 weeks 8.48515e-4 months Reactor power at 75%.

2310 hours0.0267 days 0.642 hours 0.00382 weeks 8.78955e-4 months Reactor power reduced to 70%.

August 14,'1980' 0130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months Main condenser backwashing complete.

Increasing reactor power.

0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months Reactor power at 100%.

- August 18, 1980 0330 hours0.00382 days 0.0917 hours 5.456349e-4 weeks 1.25565e-4 months Reduced reactor power to 96%

to maintain condenserd T limits.

.0830 hours0.00961 days 0.231 hours 0.00137 weeks 3.15815e-4 months .

Reactor. power returned to'100%.

' August 23, 1980 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months Decreasing reactor power to maintain main condensere T.

0505 hours0.00584 days 0.14 hours 8.349868e-4 weeks 1.921525e-4 months Reactor power 85%.

0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months Decreasing reactor power to 40%

to. repair leaking main condenser l

tubes.

0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months Reactor power at 40%.

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1

4 Page 2 of 2

- August 24, 1980-0041 hours Main condenser tube leaks repaired.

' Increasing reactor power.

2315 hours0.0268 days 0.643 hours 0.00383 weeks 8.808575e-4 months Reactor power at 100%.

August 27, 1930

- 2l00 hours-Decreasing reactor power to 85%

to valve out.H.P. heater to facilitate feedwater temperature reduction operation.

P.140 hour0.00162 days 0.0389 hours 2.314815e-4 weeks 5.327e-5 months s-Reactor power at 85%.

August 28, 1980 0110 hours0.00127 days 0.0306 hours 1.818783e-4 weeks 4.1855e-5 months Reactor power at 100% with H.P. heaters isolated.

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Docket flo.

50-245

Pag 2 1 of-1 Date 800903-Unit flame.

Millstone 1 Completed By G. Harran l.

Telcohone-203-447-1791, Ext. 655'

. CORRECTIVE-MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT.

Report Month

[ July)

~

s lDATE SYSTEM COMPONENT MAINTENAfEE ACTI0ft 800712.

..CRD #302 I-IC-7 vent valve body to bonnet Disassembled,. inspected' valve internals and

. leak installed a new flex gasket.

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Docket fio, 50-245 "Page: l' of.

1 Date 800903

~

Unit flame.

Millstone 1 Completed-By G. Ha ' ra n -

r Telephone 203-447-1791. Ext 655

-i CORRECTIVE' MAINTENANCE SUfetARY FOR SAFETY RELATED EQUIPMENT Report Month August 7

- DATE

- SYSTEM-COMPONENT MAINTENANCE ACTI0ft 800805' CRD #302 Module.'#42-27 valve #107 drain Install a new bonnet gasket.

valve leaking by seat 800808 Condensate'#315'

'B' Cond. Booster pump, outboard Installed new mechanical seal, 0-rings and mechanical: seal, excessive leakage gaskets-

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.50'245 DOCKET NO.

UNITSilUTDOWNS AND POWER REDUCTIONS UNIT N AME Millstone 1 DATE 800903 COMPLETED BY G. Harran REPORT MONTil AUQust TELEPl!ONE 203-447-1791 txt. 033 M

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'.!E

}-

j,g$ E Licensee j-r,-

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Cause a Corrective g.

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-Event p

N,o.'

Date g

3g o.

Action to H

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. cs. 3gg Report a to O 5U Prevent Recurrence U

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y 08

'800823, S

0 8

4 N/A HC HTEXCH Reduced power'to repair main condenser tube leaks'.

Power was-g:?;ER increased following maintenance.

g ca,

1 I

2 3

4 F: Forced Reason:

Method:

Exhibit G. Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual

~ for Preparation of Dar ll-Maintenance ci 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)

Exhibit I.- Same Source (9/77) 1I-O:her (Explain) g Nh

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' REFUELING INFORf',ATION REQUEST 1.

Name of facility:

Millstone 1 2.

Scheduled date for next refueling shutdown:

W/E 10/11/80 3.

Scheduled date for restart foll,owing refueling:

W/E 12/13/80 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 in formation:

Fall 1980 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis me.1ods, significant changes in fuel design, new ocerating procedures:

168 " Retrofit" 8 x 8 fuel' assemblies are scheduled for insertion in cycle 8 I

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(reload 7).

7.

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

1.

(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 number of fuel assemblies:

2184 assemblies 9.

The projected date of the last' refueling that can be discharged to the spent

^!

-fuel pool assuming the present licensed capacity

l' 1985. Soent Fuel Pool full core off load caDability is reached.

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

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ML19332B004

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