ML19210C959

Monthly Operating Rept for Oct 1979

ML19210C959
Person / Time
Site:	Millstone
Issue date:	11/08/1979
From:	Young R NORTHEAST UTILITIES
To:
Shared Package
ML19210C957	List: ML19210C956 ML19210C959
References
NUDOCS 7911200373
Download: ML19210C959 (6)

Text

'

AVFRAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-245 Millstone-1 UNIT DATE 791108 COMPLETED BY R. Young TELEPHONE 203-447-1792 X-475 MONT11 October DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 654 17 654 653 2

18 651 3

599 19 655 4

653 655 20 5

653 21 655 653 654 6

22 7

654 23 641 655 627 3

24 9

653 2,

653 no 650 653 26 11 654 27 655-12 653 655 28 653 m

13 39 14 654 30 652 654 646 15 3,

16 654

~.

INSTRUCTIONS

~

On this format, list the average daily unit power levelin MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

Note: MDC of 654 MW -Net is based on commitment to New England Power Pool.

e (9/77)

• ?(7 f

~f y911200 d'* 3

e OPERATING DATA REPORT DOCKET NO.

50-245 DATE 791108 C05fPLETED BY R. Young TELEPHONE 203-44/-1792 X-475 OPERATING STATUS Millstone-1 Notes

1. Unit Name:

October 1979

2. Reporting Period:

3. Licensed Thermal Power (SIWt):

2011

4. Nameplate Rating (Gross 51We):

662 660

5. Design Electrical Rating (Net 51We):

004

6. Siaximum Dependable Capacity (Gross 51We):

bb4

7. Maximum Dependable Capacity (Net atWe):

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

N/A

^

9. Power Level To Which Restricted,If Any (Net MWe):

10. Reasons For Restrictions,If Any:

N/A This Month Yr.-to-Date Cumulative 745 7,296 78,216

!!. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 745 5.477 58.964

13. Reactor Reserve Shutdown Hours 0

0 892

14. Hours Generator On-Line 745 5,363.2 56,683.5

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (SIWH) 1,485,077 10,298,732 101,352,020

17. Gross Electrical Energy Generated (SIWH) 506.700._,

3.506.800 34.311.896

18. Net Electrical Energy Generated (MWH) 484,413 3,342,970 32,761,488

19. Unit Senice Factor 100.0 73.5 72.5

20. Unit Availability Factor 100.0 73.5 72.5

21. Unit Capacity Factor (U3ing MDC Net) 99.4 70.1 64.0 98.5 69.4 63.5

22. Unit Capacity Factor (Using DER Net) 0 6.5 17.0

23. Unit Forced Outage Rate

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

N/A

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

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

Forecast Achieved INITIA L CRITICALITY N/A INITIA L ELECTRICITY COMMERCIAL OPERATION 0

(9/77) i 2 (-

)

U

OPERATING HISTORY October 1,19/9:

Reactor power at 100%

October 3, 1979:

0005 hrs Reduced reactor power to 75% for Turbine Stop Valve Test and mussel cooking main condensers 0045 hrs Reactor power at 75%

0415 hrs Completed test and mussel cook 0440 hrs Increased reactor power 1320 hrs Reactor power at 100%

October 10, 1979 0001 hrs Reduced power to 90% for TSVT and main condenser backwash 0035 hrs Completed TSVT 0110 hrs Completed backwash, increasing power 0145 hrs Reactor power at 100%

October 18, 1979 0009 hrs Reduced power to 90% for TSVT 0055 hrs Completed TSVT, increased power 0133 hrs Reactor power at 100%

October 23, 1979 2100 hrs Reduced power for special safety relief valve blowdown test 2400 hrs Reactor power at 94%

October 24, 1979 0710 hrs Completed special test and TSVT 0725 hrs Increased reactor power 0815 hrs Reactor power at 100%

October 31, 1979 0020 hrs Decreased power for TSVT 0140 hrs Completed TSVT 0255 hrs Completed backwash of main condensers 0258 hrs Increased power 0340 hrs Reactor power at 100%

5 7U 359 4

09E t h*

m., m_ _

2 y

mm n -

w ao. c.o c_ c.

O" C.

8

~

na

=.O. m. m. e n. m. >= x Type I n

O O >c O n % E.m u u

e

=Xaooa n oc m c-

^ =- 5 E E. R ::: 5 "

a a e.

,E E s " 2Ba Duration me e

.g E a Ha '* =, 'E (Hours)

"m7EM 5'

aea

2. E.

-2 5"

H,, c, Reason,

o= _.

.a

• n--

~^

-m c

m

.u Cm o

x E O 2-Method of E

E Shutting E

7

~

Down Reactor 3 q

2 m_

e.

m m

m C

H 3

=

E--

x r-4 [ E' M

C z

e s

H E

s>

23 5 3

2 4

a Oz c

w O

F Y '? -- E System R

E W~

ra Code 4 m

O>r

-c u y eo z

3 3 g Q$CC C;.

7 E

n=

e. e. ~

O m

mEm C

5 E' Q Component C

2. wna Code 5 n

u

,,3 mm

-E-O 3

2

(/)

u A

OO 7

O m

ommmm 3

E Mg m

c x

-<m m ?"

n>n Y Y Z_

e 7

Oa~

n y

~3v-&

@Eh QH HM M !OS '

O' C>g>Q E' q

=m 2

QESO

c. mc O

c2E' E-m =< H g 2mmO 2m

"=gF

• E u

3

• {3 E D

n P es C*

A e m F 5k N T m

M

• gg-C=

N 3 W G

D

=e O C

nT W

w w

e E

"T1 "5

e M

W

=

N n

a o o vi a

=

n b

C

@ r+ m

~

2

% 3 o-

>C 1 Q 3

C e

w co 4

e M

N C

W D

@ N e

Docket No.

50-245 Page 1 of 1 Date 791109 Unit Name Millstone 1 Completed By R. Young Telephone 201-447-1797 x 47s; CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month October DATE SYSTEM COMP 0NENT taINTENANCE ACTION 791029 Fuel Pocl Pump "A" Fuel Pool Cooling Pump Removed Foreign Material From Pump Impeller 791005 Containment Atmosphere Control 1-AC-9 Replaced Valve Operator a

s i

h 4

'M T

REFUELING INFORfMTION REOUEST 1.

Name 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?

Yes.

Technical Specification changes regarding:

(1) Maximum average planar linear heat generating rate (2) Minimum critical oower ratio 5.

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

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 " 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:

399 (b) In SFP:

958 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 assemblie's 9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

1986 RHY:rmj i ? /; 7 - ?)b 2

.