ML20071P926

Monthly Operating Rept for Oct 1982

ML20071P926
Person / Time
Site:	Millstone
Issue date:	11/12/1982
From:	Gibson J NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20071P923	List: ML20071P921 ML20071P926
References
NUDOCS 8212290142
Download: ML20071P926 (6)

Text

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OPERATING DATA REPORT 50-336 DOCKET NO.

DATE 11/12/82 i

CO5tPLETED BY J. Gibson TELEPHONE (203) 447-1791 Ext. 4431 OPERATING STATUS Millstone 2 Notes Items 21 and 22

1. Unit Name:

October 1982 cumulative are weighted ave.

2. Reporting Period:

Unit operated at 2560 MWT-

3. Licensed Thermal Power (31Wt):

2700 prior to uprating.to its 909 C.%~eplate Rating (Gross NiWe):

current 2700 MW thermal power

5. Design Electrical Rating (Net StWe): 870 1 eye),

895

6. hiaximum Dependable Capacity (Gross SlWe):

864

7. hiaximum Dependable Capacity (Net 31We):

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

NA l

t NA

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

NA

10. Reasons For Restrictions,if Any:

This Month Yr..to Date Cumulative 744 7295 60047

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 736.8 5201.8 43789.1

13. Reactor Reserve Shutdown Hours 0-128.6 2205.5

- 14. Hours Generator On.Line 639.3 4807.7 41809.2

15. Unit Reserve Shutdown Hours 0

0 468.2

16. Gross Thermal Energy Generated (51WH) 1693915 12440153 104851393

17. Gross Electrical Energy Generated (31WH) 550500 4063580 34065078

18. Net Electrical Energy Generated (51WH) 527744 3887377.3*

32641137.6*

19. Unit Sen-ice Factor 85.9 65.9 69.6

20. Unit Availability Factor 85.9 65.9 70.4

21. Unit Capacity Factor (Using SIDC Net) 82.I 61.7 _

65.3

22. Unit Capacity Factor (Using DER Net) 81.5 61.3 64.3

23. Unit Forced Outage Rate 14.1 13.1

-19.9

24. Shutdowns Scheduled Over Ne.st 6 Sionths (Type.Date,and Duration of Each):

{

NA r

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

NA

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

Forecast Achiesed INITIAL CRITICA LITY NA NA INITIA L ELECTRICITY NA NA CO.\\l%1ERCIAL OPER AllON NA NA 8212290142 821112 (9/771 l

PDR ADOCK 05000336 R

PDR

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AVER AGE DAILY UNIT POWER LEVEL 50-336 DOCKET NO.

Millstone 2

,,7 DATE 11/12/82 I,,

COMPLETED I:Y

.1 Cihton i

l TELEPilONE (203) 447-1791 Ext. 4431 MONTli OCTOBER 1982 DAY AVER AGl' DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)

(MWe Net) 842 836 37 2

842 Ig 847 3

842 769 39 4

842 20 742 5

842 21 760 6

842 22 846 7

842 23 847 8

846 848 24 9

-843 25 848 10 843 26 847 11 845 27 530 12 846 28 0 (-27) 13 845 29 0 (-27) 14 845 30 0 (-27) 15 846 3,

0 (-30) 16 731 INSTRUCTlONS On this format, list the mrge daily unit power levelin MWe. Net for each day in the reporting month. Comp the nearest whole r:vp. ort, (9/77I i

i

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UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-336 UNIT N AME Millstone 2 DATE 11/12/82 REPORT MONTil OCTOBER COMPLETED BY J. Gibson TELEPHONE (203) 447-1791 Ext. 4431 4 to 3 5

c:

en

.E 5

7.s X Licensee 5 *.

E.4 Cause & Currective

~

c c

No.

Date g

3g 4

jg; Event

T S"

Action to c5 3 Ec jsy Report *

$C Prevent Recurrence 6

20 821016 S

0 B

NA NA

. IIA Valvex Power reduction from 100% power to 85%

i for Turb. Control valve testin9 and mussel cooking.

o 21 821019 r

0 A

NA 82-41 RB Instru While at 100% power, Rod #23 dropped fully into core due to a defective power supply.

Power was reduced to

< 70% power.

22 821020 F

0 A

NA 82-41 RB Instru Rod #23 dropped again. Power was reduced to< 70%, and power supply was replaced.

1 2

3 4

F: Forced Reason:

S: Scheduled A l:quipment Failure (Explain).

Method:

Exhibit G. instructions 1 Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram.

Entry Sheets for Licensee C Refuchng 3 Automatic Scram.

0161)

Event Report (LE R) File (NUREG-D Regularory Restrietion 4-O her(Explain) j E. Operator Training & License Examination F Administrative 5

G Operational Error (Explain)

Exhibit I-Same Source 1

(9/77)

Il-Other (Explain)

Y NE DOCKET NO.

UNIT SHUTDOWNS AND POWER REDUCTIONS Mil 1 stone 2 UNIT N A,'1E Dt.iE 11/17/R7 OCTOBER COMPLETED, y J. Gibson REPORT MONTH TELEPHONE (203) 447-1791 Ext. 4431 "k

bi'CDSCC b'.

Cause & Correggeve 1

E'C"'

3,?

3 Action to paig 5 ~i "g 33 0

gs Report a mV V

Prevent Recurrence o.

m d

23 821027 F

104.7 A

3 NA IB Instru While replacing fuses in the Engineering safety. analysis system actuation cabinet 24V power supply, under voltage actuation module fired, causing loss of normal power on one 4160 vital buses. This re-suited in instrument de-energization causing a turb. trip. At the end of the reporting period unit was in hot standby 0% power.

e 19/77)

Docket No.

50-336 Date 11/12/82 UMt Name Millstona 2 Completed By J. Gibson Telephone (203) 447-1791 Ext. 4431 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month OCTOBER 1982 DATE SYSTEM COMPONENT MAINTENANCE ACTION 821021 Main Steam Aux. feed pump terry turbine Repack Aux. Feed Pump 821026 Diesel Generator Diesel generator "A" Standby Change outboard motor bearing Jacket Coolant Pump 821026 Diesel Generator Diesel Generator "A" Install new fuel supply crossover pipe on fuel line to diesel generator "A".

821027 Process & Area Rad-Containment particulate Replace high radiation alarm relay driver iation monitoring radiation monitor transistor 821027 ESAS Engineering safety analysis Replace fuses on 24 volt power supply ESAS system Cabinet S e

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Docket No.

50-336 Date:

11/12/82 Completed By:

J. Gibson Telephone:

(203) 447-1791 X 4431 REFUELING INFORMATION REQUEST 1.

Name of facility:

Millstone 2 2.

Scheduled date for next refueling shutdown:

April 16, 1983 3.

Schedule date for restart following refueling: July 22, 1983 (14 wk outage) 4.

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

It is anticipated that Cycla 6 operations will require Technical Specification changes or other License stendments.

5.

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

Safety Analyses:

January 1, 1983 Steam Generator Licensing Action:

February 1, 1983 6.

Important licensing considerations associated with refueling, e.g., new or different fuel d? sign or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

Additional plugged steam generator tubes will result in potential reactor coolant flow reduction.

Currently planning to install sleeves in steam generator tubes.

7.

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

(a)

In Core:

217 (b) 288 8.

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

667 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.

1987, Core Full, Spent Fuel Pool contains 648 bundles.

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