ML19291C177

Monthly Operating Rept for Dec 1979

ML19291C177
Person / Time
Site:	Millstone
Issue date:	01/03/1980
From:	Young R NORTHEAST UTILITIES
To:
Shared Package
ML19291C171	List: ML19291C170 ML19291C177
References
NUDOCS 8001230069
Download: ML19291C177 (6)

Text

I AVERAGE DAILY UNIT POWElt LEVEL DOCKET NO.

50-245 ugi7 Millstone-1 DATE 800103 COMPLET ED fly R. Youno TELEPilONE 203/447-1792 X-475 MONTil - December DAY AVERAGE D \\1 Y ' WER LEVEL DAY AVEll AGE DAILY POWER LEVEL (M We-Net) 1 656 17 655' 2

656 18 655 3

656 19 436 4

656 20 0

608 5

32 21 6

303 22 462 7

619 23 623 8

656 656 24 9

25 657 10 657 26 657 11 656 27 656 12 651 28 657 I3 29 656 14 655 30 655 15 656 31 657 16 656 INSTRUCTIONS On this format. list the aserage daily unit power levelin MWe. Net for each day in t?. reporting the nearest whoic ruegawatt.

flote:

M]C of 654 MWE-flet is based on commitment to flew England Power Exchange.

P)/77 )

179 196 l

so o12 aoo c q

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e OPERATING DATA REPORT DOCKET NO. _5_0-245 DATE 800}03 COSIPLETED llY _Ed0ltna TELEPil0NE 203/447-1792 X475 OPFR ATING STATUS

1. Unit Name:

Millstone Unit 1 N"I'5

2. Reporting Period:

December 1979 2011

3. Licensed TI mnal Power (51Wt):

4. Nameplate Rating (Gross SIWE):

662

5. Design Electrical Rating (Net alWe):

660

6. blaximum Dependable Capacity (Gross alWe):

684

7. Ma.simum Dependable Capacity (Net alWe):

654

8. if Changes Occur in Capacity Ratin;s (items Number 3 Through 7) Since Last Report. Gise Reasons:

N/A

9. Power Lesel To Which Restricted. If Any (Net 31We):

N/A

10. Reasons For Restrictions. lf Any:

N/A This Month Yr.-to Date Cumulatise

11. Ilours in Reporting Period 744 8760 79680 12 Number Of Ilours Reactnr Was Critical 701 6898 60385

13. Reactor Resene Shutdown flours 43 41 935

14. Ilours Generator On Line 692.4 6775.6 58095.9

15. Unit Resene Shutdown flours 0

0 0

16. Gross Thermal Energy Generatcd (MWil) 1334437 12994557 104047945

17. Gross E!cetrical Ene gy Genciated (MWil) 456200 4426300 3523 396

18. Net Electrical Energy Generated (MWil) 435637 4221264 33639782

19. Unit Senice Factor 91.1 77.3 72.9

20. Unit Avaihbility Factor 93.1 77.3 72.9

21. Unit Capacity Factor (Using MDC Net) 89.5 73.7 64.6

22. Unit Capacity Factor (Using DER Net) d8.7 73.0 64

23. Unit I orced Outage Rare 6.9 5.9 16.7

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date,and Duration of Each):

j N/A

25. If Shut Down At End Of Report Period. F>timated Date of Startup:

26. Units in lest Status (Prior o Commercial Operation):

Forecast Achies ed INITIA L CRi flCA LITY INillT l. LLLC TRIC11 Y COMMERCIA L OPFR ATION

)[))

)h[

(0/77)

UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-245 UNIT NAME Millstone 1 DATE 800103 y 3/447:1792 X475 Ymmn REPORT MONn{ December COMPLETED BY

<0 TELEPIIONE Mt2

(___.

p

.5?

}

)Y Licensee

,Ee, h,

Cause & Corrective

~

No.

Date g

3=

jg5 Event gg 93 Action to g7 fE 5

jgg Report a mV H

yU Prevent Recurrence EEE 15 791205 S

NA B

NA NA HC HTEXCH Reduced power for main condenser y

maintenance.

Power was increased

~

following maintenance.

ps-F 16 791219 F

51.6 A

3 NA Unit inadvertently renoved from service by turbine trip / reactor scram due to loss of main generator loss of excitation.

The unit was returned to service following repairs to the amplidyne generator.

wl so - _

M sC)

CD 1

2 3

4 F: Forced Reason.

Methnd:

Exhibit G-Instructions S: Scheduled A-Ega.pment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C-Refue!!ng 3-Automatic Scram.

Event Report (LER) File (NUREG-D T.egulatory Restriction 4-Other (Explain) 0161)

E-operator Training & License Examination F.Wministrative 5

C Operational Error (Explain)

Exhibit I-Same Source (9/77)

I;-Other (Explain)

~

OPERATING HISTORY December 1, 1979:

Reactor Power at 100%.

December 5, 1979:

0405 Hours -

Secured 'C' Condenser.

Reduced reactor power to naintain condenser AT.

1200 Hours -

Reactor power at 92%.

1715 Hours -

Reduced reactor power to maintain condenser AT.

1800 Hours -

Reactor power at 88%.

2345 Hours -

Reduced power for condenser repairs.

December 6, 1979:

0100 Hours -

Reactor power at 40%.

1835 Hours -

Condenser repairs completed.

2010 Hours -

Increased power to 755.

Held reactor power at 75%

for mussel cooking.

December 7, 1979:

0025 Hours -

Completed mussel cooking.

0245 Hours -

Increasing power.

1330 Hours -

Reactor power at 100%.

December 19, 1979:

1607 Hours -

Reactor Scram from turbine trip.

0630 Hours -

Comnenced start up #379.

. December 21, 1979:

0812 Hours -

Reactor Critical, Group 4, Rod, 42-23, Notch 6, T= 200 sec, Temp. = 344.

0952 Hours -

Reactor scram while testing Electric Pressure Regulator Electronics.

1145 Hours -

C' mnenced start up #380.

o 1258 Hours -

Reactor critical, Group 4, Rod 26-23, Notch 6, T= 66 sec, Temp. = 358.

December 23, 1979:

1445 Hours -

Reactor power at 100%.

1791 199

Page 1 of 1 Docket No.

50-245 Date gnoli Unit Name Millste e 1

~

Completed By R. Young Telephone 203/447-1792 X475 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY REL ATED EQUIPMENT Report Month

pecember, DATE SYF, TEM COMPONENT MAINTENANCE ACTION 791128 Control Rod Drive HCU Accumulator 22-11 Replaced Accumulator.

791205 Control Rod Drive HCU Accumulator 34-07 Replaced Accumulator.

791221 Control Rod Drive Scram Inlet Valve on HCU 10-27 Replaced seat ring and disc.

M N

NO O

CD CD e

e e

REFUELI!!G If FORf'AT10f! REQUEST 1.

riame of facility:

Millstone 1 2.

Scheduled date for next refueling shutdown:

Fall 1980 3.

Scheduled date for restart following refueling:

Late Fall 1980 4.

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

i Yes.

Technical Soecification chances renarding:

(1) Maxinum Average Planar Linear Heat Generatinq Rate (2) Maximum Critical Power Ratio 5.

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

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 "Relrofit" 8 X 8 fuel ssemblies 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:

san (b) In SFP:

77s 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:

1986 RilY:rmj 179i 201

.