ML19256F273

Monthly Operating Rept for Nov 1979

ML19256F273
Person / Time
Site:	Millstone
Issue date:	12/05/1979
From:	Howlett G NORTHEAST UTILITIES
To:
Shared Package
ML19256F265	List: ML19256F264 ML19256F273
References
NUDOCS 7912180403
Download: ML19256F273 (5)

Text

k OPERATING DATA REPORT DOCKET NO.

50-336 DATE December 5,1979 CONIPLETED BY (LH. Howlett TELEPilONE 201/447-791 X364 OPERATING STATUS

1. Unit Name:

Millstone 2 Notes

• Items 2) and 22,

2. Reporting Period: November 1979 Year to Date and Cummulative

3. Licenud Thermal Power (SIWr):

2700 are computed using a weighted

4. Nameplate Rating (Gross 31We):

909 average.

5. Design Electrical Rating (Net 31We): 870

6. Statimum Dependable Capacity (Gross SIWE): 895

7. Statimum Dependable Capacity (Net 31We):

864

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

None

9. Power Leve! To Which Restricted,if Any (Net 31We): None

10. Reasons For Restrictions,1f Any:

None This Month Yr. to-Date Cumulative

11. Hours In Repciting Period 720 8,016 34,464

12. Number Of Hours Reactor Was Critical 0

4.900.1 24,427.8

13. Reactor Resene Shutdown Hours n

71.7 2,072.4

14. Hours Generator On-Line 0

4,752.2 23,183.9

15. Unit Reserve Shutdown Hours 0

109.4 335.4

16. Gross Thermal Energy Generated (SIWH)

O 12,202,873 56,085,106

17. Gross Electrica! Energy Generated (AlWH) 0 4,020,710 18,049,511

18. Net Electrical Energy Generated (SIWH) f-41RR1 3 849 412 17.266.103

19. Unit Senice Factor 0

59.3 67.3

20. Unit Availability Factor 0

60.7 68.2

21. Unit Capacity Factor (Using AIDC Net) n 57.5 61.4

22. Unit Capacity Factor (Using DER Net) 0 56.6 60.1

23. Unit Forced Outage Rate 100 23.0 24.0

24. Shutdowns Scheduled Oser Next 6 N!onths(Type.Date.and Duration of Eacht:

None

~

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

December 5, i m

26. Units in Test Status IPrior to Commercial Operation):

Forecast

, Achieved,

INITIA L CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A CO%131ERCIA L OPER ATION N/A

- N/A 1608 164 (u/77) 7912180 Yo 3

AVERAGE DAILY UNIT POhER LEVEL 50-336 DOCKET NO.

UNIT Millstone 2 December 5,1979 DATE COMPLETED BY G.H. Howlett III TELEPHONE 203/447-1791 X364 MONTH November 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(ywe.Ne:)

1 0

(-10) 0

(-5) j7 2

0

(-6)

.is 0

(-5) 3 0

(-5) 39 0

(-5) 4 0

(-5) 20 0

(-5) 5 0

(-5) 0

(-5) 21 6

0

(-5) 22 0

(-5) 7 0

(-5) 0

(-5) 23 0

(-5)-

0

(-5) s 24 9

0

(-5) 25 0

(-5) 10 0

(-5) 0

(-6) 26 0

(-5) 0

(-12) 11 27 12 0

(-5) 23 0

(-17) 13 0

(-5) 0

(-6) 29 0

(-5) 0

(-6) 14 30 15 0

(-5) 33 16 0

(-5)

INSTRUCTIONS On this format, list the aserage daily unit pow er levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77) 1608 165

Docket No.

50-336 Page 1 of 1 Date December 12. 1979 Unit Name Millstone 2 Completed By G.H. Howlett Telephone 203/447-1791 x364 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT

~

Report Month October 1979 DATE SYSTEM COMPONENT MAINTENANCE ACTION 10/2/79 CEA Position Backup, scanner position Replaced faulty operational amplifiers (Fairchild

{

Indication CEA's 6 &'6 3 No. UA-747) (See LER 79-32/3L-0) 10/5/79 125 Volt DC Vital Battery 2018 Replaced failed cell.

Power Supply f

10/11/79 Clean Liquid Radwaste Suction piping recovered Boric \\

Repak ed cracked pipe (See LER 79-33/3L)

Acid Pump 10/11/79 125 Volt DC Vital Battery 201B Replaced failed cell.

Pcwer Supply 10/17/79 125 Volt DC Vital Battery 201B Replaced failed cell.

1 Power Supply 10/19/79 Service Water 2-SW-8.lC Temperature Control Rebuilt valve.

Valve RBCCW Heat Exchanger 'C' 10/21/79 125 Volt DC Vital Battery 201B Replaced failed cell.

Power Supply t,

10/24/79 Chemical & Volume Charging Pump P-18B Inspection and preventive maintenance f

Control 4

l 10/25/79 Engineering Safeguards Area Radiation Monitor RM-8142 Replaced & calibrated non linear eneter.

Actuation 10/29/79 Engineering Safeguards Channel B, Bistable BA-203 Replace bistable m

Actuation i

i Ch

g oD4-cC d

4 9

6 7

3 9

X 1

t 1

s 2

. t 9

u 5

e 7 o

e l

1 i

n r w

v o e a 7 e

r 6

t b

H 4 r

o 3

s m 4

p t

3 e

_ /

a I

H_

m r

3 l

c 0

o e

0 i

e 5

M G 2 e

e r

n v

c f

e i

n t

O.EEYE c

e G

e or e

r MTBN r

u g

m N

t r

AA D O on c a

a T N D EI Co e t

e I

iR u

t EK T TP

&t o

S E E.

c t I

eAn C N Ll s

e f

e O U P E u

v D

M T a

e o

h C

P r

t O

n C

o o

i t

ta s

u r

n.

i ih a

tt p

nn e

oo r

Cm r

S o

N f

O 9

d I

",3u T

7 X

o C

9 E

i E$ogu P

r U

1 D

I

\\

e r

P p

E e

R b

g R

m n

P,?o E

e i

v H

t W

gm H

r o

O N

o P

p 1

D e

1 N

T r

A N

O e

S e

h N

M et t

t s

nr W

T n e o e v p t

O R

c iEe u.

D O

L R

o g.

T P

U E

h n gi R

l up i

S oi T

rp I

',EE& y,Q h

N td Ygj d 1

e U

nt

-},5.

wa oi d co H

ts

};:E us h a s

d 0

d n

?g0 2

ea 7

n

!,g$

i s ad ml ee rw

,g*

F td i n ne u e ef 1

h a

~

e 3

t T s aD 0

1

y 9

r 7

ammu e.,

S N

8 W

e

Docket No.

50-336 Dats:

December 12. 1979 Completed By:,G.H.

Howlett III Telephone:

203/447-1971 X364 REFUELING INFORMATION REQUEST 1.

Name of facility:

Millstone 2 2.

Scheduled date for next refueling shutdown: July 1, 1980 3.

Schedule date for restart following refueling: September 1,1980 4.

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

Technical Specification changes will be necessary as a result of the change in fuel and safety analysis supplier.

5.

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

The schedule for submitting proposed license action is as follows:

Basic Safety Report 2-1-80 ECCS Results 4-1-80 Reload Safety Evaluation 5-1-80 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:

Cycle 4 will be unique in that it will be the first where the fuel and safety analysis will be supplied by Westinghouse.

7.

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

(a) In Core:

21 7 (b) 144 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 nJmber 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:

1983, Spent Fuel Pool, full core off load capability is reached.

1986, Core Full, Spent Fuel Pool contains 648 bundles.

1608 168