ML19344B544

Monthly Operating Rept for Sept 1980

ML19344B544
Person / Time
Site:	Millstone
Issue date:	10/01/1980
From:	Harran G NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML19344B540	List: ML19344B539 ML19344B544
References
NUDOCS 8010210430
Download: ML19344B544 (6)

Text

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• l AVERAGE DAILY UNIT POWER 11 VEL 1

l DocKLT No. __50-245 s

UNir -

Millstone - 1 DTTE S01001 l'

l 3

COMPl.ETED llY G d aICAn t

TELEPil0NE._223.-s4) 'U.2 Ext. 6bu

.10NTil September l

l l

DAY AVER AGE DAll.Y POWER I.EVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

(MWe Neo 491 i

I ~

___.5 38 37 l

2 638 Is 618 633 608 3

39 4

640-20 601 t

5 639 21 598 6

638 22 596 7

634 23 594 8

633 24

=c92 l

9 630 25 592 l

10 625 26 590 l

-11 624 c

27

_d8 621

.585 12.

,g l

13-619 29 582 1

14 616 30 53 15 615 3:

16 613

~

I

' INSTRUCTIONS r

' On this forrnat. fist the average daily unit power levelin MWe-Net for each day in the rep 6rting mdnth. Compute to the nearest whole megawait.

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

(9/77) t 18 o 1021e'/3R

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OPERATING DATA REPORT DOCKET NO. 50-245 DATE 801001 I-

'CO.\\tPLETED 11Y G. Harran f'

TELEPl!ONE 203-447-1792 Ext. 655 Ol'ERATING STATUS Notes '

I.~ Unit N:nne:

11111stene Unit 1

2. Reporting Period:

SEDtember 1980

3. Licenced Thennal Power (SIWt):

2011 662-

4. Na ieplate Rating (Gross $1We):

5. Design Electrical Rating (Net 31We): _f 0 684

~ 6. Af aximum Dependable Capacity (Gross 5. 'e):

7. 51asimum Dependable Capacity (Net 31We):

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

Although the ratings have not changed, the unit is presently on an end-of-cycle coastdown with feedwater temperature reduced.

9. Po..er Level To which Restricted. If Any (Net 31We): NA NA

10. Reasons For Restrictions. lf Any:

This afonth Yr.-to.Date Cumularise 720 6,575.0 '

r.

86,255.0 II, Ifours In Reporting Period -

r

12. Number Of !!ours Reactor Was Critical 720 5,986.0 65,371.0

- 13. Reactor Resene Shutdown llours

0 592.3-1,527.3 14.!!our: Generator on.Line 720 5.954.0 64.049.9

15. Unit Reserve Shutdown llours 0

26.5 26.5

16. Gross Thermal Energy Generated (51WH) 1,369,333 10,359,790 114,407,735

- 17.' Gross Electrical Energy Generated (11WH) 459,500 3,519,447 38,750,843

18. Net Electrical Energy Generated (51Wil).

438,444 3,360,650 37,000,432

19. Unit Senice Factor 100.0

'90.6.

74.3

20. Unit Availability Factor 100.0 91.0 74.3

21. Unit Capacitv Factor (Using N1DC Net!

93.1 78.2 65.6 92.3 77.4 65.0

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rat,.

0.0 0.2

-15.4

24. Shutdowns Scheduled Oser Ne.st 6.\\fonths (Type.Date,and Duration of Each1:

Annual refuel and maintenance outage-scheduled to commence October 4,1980 for annmvi-a tely 11 wein NA

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

26. Units In Test Status (Prior to Commercial Operationi:

Fore est Achieved I

INITIA L CRITICA LITY INITIA L ELECTRICITY NA CO.\\l%tERCl% L OPER ATION q[

y q

gh diru.=.

cif77)

Page 1 of 2 OPERATING HISTORY

_ September 1, '1980 Steady state 97% power.

September 3,1980 0015 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> -

Reactor power reduced to 90%

for Turbine Stop Valve Testing and Main Condenser Backwashing.

0135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br /> Turbire Stop Valve Testing and Main Condenser Backwashing comple te.

Increasing reactor power to 98%.

0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> Reactor power at 97%.

September 5,1980 Reactor power at 99%.

(Unit begins it end-of-cycle coastdown with feedwater temperature reduced.)

September 10, 1980 0013 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />' Reducing reactor power for Turbine Stop Valve Testing.

0050 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> Turbine Stop Valve Testing complete.

Reactor power at 97%.

l

_ Sep tembe r 17, 1980 1005 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.824025e-4 months <br /> Reducing reactor power to maintain condenserd T limits.

1135 hours0.0131 days <br />0.315 hours <br />0.00188 weeks <br />4.318675e-4 months <br /> Reducing reactor power to_40%

to repair leaking main condenser l

tubes.

1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> Reactor power at 40%.

Turbine Stop Valve Testing started and completed.

l 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br /> Main condenser tube leaks repaired.

Increasing reactor power.

Sep tembe r -18, ' 1980

.0730 hour0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />s-Reactor power at 96%.

1010 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.84305e-4 months <br /> Reducing reactor power to 90%-

f

. September 24 '1980 0

for Turbine Stop Valve Testing.

0035 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> Turbine Stop Valve Testing complete.

Increasing reactor power.

Page 2 of 2 0055 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br /> Reactor power at 93%.

September 30, 1980 Reactor power at 90%.

i i

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50-245 DOCKET NO.

UNIT S!!UTDOWNS AND POWER REDUCTIONS UNITNAME Mil 1 stone - l DATE 801001 REPORT MONTil September COMPLETED HY G. Ilarran TELEPIIONE 203/447-1792 Ext. 655 n.

%.a E e

=

ce

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5't ;

Cause & Corrective No.

Date E.

f

?'5N Event g,7 p.3 Action to g.2 3

g g c::

3mj Report st to o O

Prevent Recurrence c=

m 6

09

801017, S

0 8

4

- f1A IfC IITEXCll Reduced power to repair main condenser tube leaks. Power was increased following maintenance ~.

O Cess x

1. 9b) r i

M DM Cd$

GEED

@W 2

3 4

F: Forced Reason:

Method:

Exhibit G - Instructions S:. Scheduled.

A Equipment Failure (Exp!ain) l Manual for Prep.uation of Data :

IbMaintenance of Test 2-Manual Scrarn.

Entry Sheets for l.Lensee.

C Refueling 3 Automatic Scram.

Esent Report (1.ER) File (NUREG.

D Regu!atory Restriction 4-Other (Explain)

.-01611' E-Operator Training & License Examination F.Adntinistrative 5

G Operational Error (E splain)

Exhibit I - Same Source (9/77)

II.Other (Explain) 4 4

2

REFUELING INFORI%TI0t! REQUEST 1.

'tiame of facility:

Millstone 1 2.

Scheduled date for next refueling shutdown:

Oct. 4, 1980-3.

Scheduled date for restart foll,owing refueling:

Acorox. Dec. 11. 1980 4.

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

Yes. Technical Specification changes regarding:

(1) 11aximun Average Planar Linear-Heat Generating Rate (2) liaximum Critical Power Ratio 5.

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

Submitted 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 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 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:

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

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

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