ML19345H374

Monthly Operating Rept for Apr 1981

ML19345H374
Person / Time
Site:	Millstone
Issue date:	05/06/1981
From:	Harran G NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML19345H371	List: ML19345H370 ML19345H374
References
NUDOCS 8105200218
Download: ML19345H374 (5)

Text

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_1 AVER AGE DAILY UNIT POWER LEVEL --

e DOJKET NO. _50-245

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UNIT _ Millstone i f*

DATE

• A10c;r6

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COMPLETED BY G. Harran TELEPilONE 203J447-g79g A-bbb MONTH April DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 4

(MWe-Net)

(MWe. Net) 3 0'

37 o-2 0

Ia 0

3 0

71 1j 4

0 94 20 5

0 141 21 0

6 0

22 0

7 0

23 8

0 24 0

9 0

25 0

0 10 26 0

0

(

lI 27 0

12 0

0 28 j

0 13 0

29 u

14 0

30 0

Is 31 0

16 e-INSTRUCTIONS On this format.hst the aserage daily unit power levelin MWe Net for each Jayin the reporting month. C l

the nearest whole megawait.

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

(9/77) 81052002lT

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UPERATING HISTORY April 1,19f,1 Unit remains in refuel outage.

April 17, 1981 2017 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.674685e-4 months <br /> Comenced control rod wtthdrawal.

2147 hour0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.169335e-4 months <br />, Reactor critical.

Group 2.gotch16, Rod 22-15.

Temp. 175 F.

Period 298 sec.

2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> Reactor shutdown for snut-down margin requirements.

2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br /> Commenced control rod withdrawal.

April 18,1981 0041 hours4.74537e-4 days <br />0.0114 hours <br />6.779101e-5 weeks <br />1.56005e-5 months <br /> Reactor critical.

Group 2. Rod 22-35. Notch G.

Per.iod 164 sec.

April 19,1981 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br /> Turbine on-line.

Tu'bine trip on moisture 1214 hours0.0141 days <br />0.337 hours <br />0.00201 weeks <br />4.61927e-4 months <br /> r

seperator high level.

1514 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.76077e-4 months <br /> Turbine on-line.

Reactor power RT 15.5%.

April 20,1981 1504 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.72272e-4 months <br /> Turbine off-line for surveillance l

test of turbine over speed trip test.

1817 hours0.021 days <br />0.505 hours <br />0.003 weeks <br />6.913685e-4 months <br /> Turbine on-line. Reactor power at 18%.

April 21,1981 0220 hours0.00255 days <br />0.0611 hours <br />3.637566e-4 weeks <br />8.371e-5 months <br /> Increasing reactor power.

Reactor power at 20%

i l

0226 hours0.00262 days <br />0.0628 hours <br />3.736772e-4 weeks <br />8.5993e-5 months <br /> Turbine trip-manually on high vibration.

0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> Inserting control rods.

0232 hours0.00269 days <br />0.0644 hours <br />3.835979e-4 weeks <br />8.8276e-5 months <br /> High main condenser conductivity.

Manual scram reactor.

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/

i 9

OPERATING DATA REPORT

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DOCKET NO. 50-245 DATE _810506 ~

f.

COh!PLETED BY

_G. Harran TELEPl!ONE -2U3/44 /-1791 X-bbb OPERATING STATUS

1. Unit Name:

Milletnno finit 1 Notes

2. Reporting Pe>iod:

APriI l98I

3. Licensed Thermal Power ($1WI):

2011 662

4. Nameplate Rating (Gross h!We):

5. Design Electrical Rating (Net h!We): -660

6. Af aximum Dependable Capacity (Gross StWe):

7. Af animum Dependable Capacity (Net h!We):

8. If Changes Occur in Capacity Ratings (Iterra Number 3 Through 7) Since Last Report.Gise Reasons:

N/A N/A ___

(Net h!We):

N/A

9. Power Level To Which Restricted.If Any/A

10. Reasons For Restrictions.lf Any:

N I

e f

This Month Yr to-Date Cumulative i

l II. Hours !n Reporting Period 71 9 2879.0

' '91343.0

12. Number Of Hours Reactor Was Critical 74.0 74 66533.0

13. Reactor Reserve Shutdown Hours 237.5 237.5 1764.8

14. Hours Generatar On Line 38.0 38 64164.2

15. Unit Reserve Shutdown Hours 0

0 26.5 I 52 f.,4 152b4 114445361

16. Gross Thermal Energy Generated (h!WH)

17. Gross Electrical Energy Generated (51WHI 4500

_38800396

18. Net Electrica! Energy Generated (51WH) 828

-5925 37024029 l

19. Unit Senice Factor 0,2 4

20. Unit Availability Factor 1.

/0.3 i

0.2 0.0.

62.0

21. Unit Capacity Facter (Using n!DC Net) i

22. Unit Capacity Factor (Using DER Net) 0.2 0.0 61.4

23. Unit Forced Outage Rate 0

0.0 15.4

24. Shutdowns Scheduf:d Over Next 6 Months (Type.Date,and Duration of Each):

NONF

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

June 7, 1981

26. Units in Test Status (Prior Io Commercial Operation s-Forecast

. Achin ed l

INITML CRITICALITY N/A

• e INillAL ELECTRICITY j

CO31%1ERCI AL OITR ATION l

P00R ORSI E m l

C'3 O

"JC3 UNITSHUTDOWNS AND POWER REDUCTIONS DOCKETNO. 50-745 UNIT NAME Millstone 1 DATE DIUDUD REPORT MONTil Appt COMPLETED BY G. Harran gy, TELEPilONE 203/447-1791 X-65b N

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f" Licensec 5 r, b

Cause & Correceive

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No.

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Event t: ?

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Action to j0-c5 E E

j di g Report #

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Prevent Recurrence

[

6 10 801004 S

438.2 C

N/A None N/A N/A N/A F

1 8 0419 F

3.3 A

N/A None HB XXXXX Low power ascensio'n turbine trip on moisture seperator high level.

No change in reactor power.

2 81042p S

3.0 H

N/A None N/A N/A Surveillance testing.

(Turbine trip on high speed.)

3 81 0421 '

F 236.5 A

B R0-81-04/IT CA ZZZZZ Manual turbine trip on high vibration. Manual reactor scram on high main condenser conductivity.

I 2

3 4

F: Forced Reason:

Method:

Exhibit C. Instructions 3: Scheduled A Equipment Failure (Explain) 1-Manual for Preparaison of Data B. Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C Refueling 3 Automatic Scram.

Event Repori(LER) FdeINUREG.

D Regulatory Restriction 4 Other (Explain) 0161)

E Operator Training & Ucense Examination F Administrative G Operational Error (Explain) 5 (9/77) llother (Explain)

Exhbit I -Same Source e

s REFUElitlG IrlF0Ji'ATIOff REjuEST 1.

Name of facility: _millstona 1 2.

S'cheduled date for next refueling shutdown:

Sumer 1982 3.

Scheduled date for restart foll,ouing refueling:

Fall 1982 4.'

Will refucling or res0mption of ' operation thereafter require a technical specification change or other license amendment?

I 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:

Spring 1982

, 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:

172 '%tenfit" 8 x 8 fuel as'semblieS are' scheduled for insertion in cycin 4 (Reload 8)-

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:

-- osa 8.

The present licensed spent fuel pool storage capacity and the size of any in-ciease 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:

a..... _

1985Jpent funi -pon1, fn1Lccre nff inad_canaM1ity i$-reached,--

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1991, Core full, spent fuel pool contains 2120 bundles.

RHY:rraf t

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