ML20148B194

Monthly Operating Rept for Dec 1979

ML20148B194
Person / Time
Site:	Millstone
Issue date:	01/03/1980
From:	Howlett G NORTHEAST UTILITIES
To:
Shared Package
ML20148B184	List: ML20148B179 ML20148B194
References
NUDOCS 8001210162
Download: ML20148B194 (7)

Text

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OPERATING DATA REPORT DOCKET NO.

50-336_

DATE ala.011ML3,1980 COMPLETED 13Y _GJ1._jlnW1ett TELEPIIONE 203/447-1791 X364 OPE RATING STATUS

1. Unit Name:

Millstone 2 Notas

• Items 21 & 22

2. Reporting Period: December 1979 Yr.-to-Date and Cumulative 3.' Licensed Thermal Power (MWt): 2700 are computed using a weighted 7 09 average.

4. Na:neplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe): _R70

6. Masimum Dependable Capacity (Gross MWe):

895

7. Maximum Dependable Capacity (Net MWe):

864

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

None f

~

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

None l

10. Reasons For Restrictions,if Any: _None i,

l This Month Yr. to Date Cumtilative t

11. Ilours in Reporting Period 744 8,760 35,2_08

12. Ntunber Of Hours Reactor Was Critical 651.3 5,551.4 25,079.1

13. Reactor Resene Shutdown llours 0

71.7

___2_,.07 2. 4

14. Ilours Generator On Line 636.3 5,388.5 23,820.2 i

15. Unit Reserve Shutdown flours 0

109.4 3.3 5_JL ___._.

16. Gross Thermal Energy Generated (MWH) 1,613,522 13,816295 57,.698,_6_28 _

17. Gross Electrical Energy Generated (MWH) 535,134 4,555,844 18,584,645

'18. Net Electrical Energy Generated (MWii) 51h155 4J 63 567 1728_0J.58 2

19. Unit Senice Factor 85.5 61.5 67.7

20. Unit Availability Factor 85.5 62.8 68.6 i

21. Unit Capacity Factor (Using MDC Net) 80_,0 59.5 61_,B

22. Unit Capacity Factor IUsing DER Ne )

79 4 58.6 60.5

23. Unit Forced Outage Rate KS 22.1 25.9

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

None

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

N/A

26. Unitiin Te,t S:atus (Psior to Conunercial Operation):

Foreca>t Achies ed f

INI flA L CRITICA LITY

._N/JL.

_N/JL_

l

/r w/_r 96024308 w/A N

INITIA L ELEC IRICITY NA

/

CO\\lMERCIA L OPER M ION l

i 8 0 61 2 $ 0 / b c2--

'"! M l

o0-336 UNITSliUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME Milistone 2 DATE Januarv 3. 1980 COMPLETED DY G H. Howlett REPORT MONTII D cember 1979 TELEPl!ONE 203/447-1791 X364 w.

.!E S

.E Licensee

,E g Cause & Corrective N. i.

Date g

~ ?,

g j gy Event n2 El Action to

$5 5

j @g Report e sk 0 y'

Prevent Recurrence S

6 8

791031 F

107.7 H

1 HH PIPEXX Continuation of outage.from previous month.

9 791213 F

0 H

1 HH PUMPXX Reduced load to replace steam generator feed pump 'A' seal.

s I

Summary: The steam generator safe end weld repair outage continued through the 4th with the unit going on line on the 5th.

Power ascension took place over a period of 3 days while sodium tracer tests were performed on w

the' secondary plant. The unit operated at or near 100% rated thermal power throughout the rest of the W

reporting period except for the power reduction on the 13th.

O N

>W 4

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AVER AGE D AILY L* NIT POWER LEVEL j

50-336 DOCKET NO.

UNIT -Millstone 2 l

DATE January 3, 1980 COMPLETED BY GeorgeH.Howlett!

i TELEPilONE 203/447-1791X364 MONTil. W < lber 1979_

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i

-(MWe Net)

(MWe Net) i 0

(-6) 842' l

,7 0

(-6) 806 2

ig 3

0

• (-6) 19 847 4

0

(-23) 20 861 I

5 144 863 21 6

A 22 81L2 766 7

23 862 l

s 861 24 863 863 862 l

9 25 10, 862 26 663 11 861 27 863 747 862 12 2s 13 517 29 862 637 14 30 862 15 839 31 8.62 16 849' INST 1:UCTIONS On this foiinsi.lisi the :netere 6ily i: nit power ine! in MWe Net for ca:h day in the reps.rtinp in.inth. Compuie to the r.r,sest whole :negzwait.

('I'

• 7 )

91024310 y

w r-,--

+

=ew

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O Docket No.

50-336 Page 1 of 3 Date January 10, 1980 Unit Name Millstone 2 Completed By G. H. Howlett i

Telephone 203/447-1791 X364 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month _Nnvoesor lo7o DATE SYSTEM COMPONENT MAINTENANCE ACTION 11/1/79 125 Volt D.C.

Battery 201 A Replaced Battery 201 A 125 Volt D.C.

Battery 201 B Replaced Battery 201 B 11/3/79 Chemical & Volume 2-CH-515. Letdown Safety Injection Replaced limit switches Control Actuation Iso. Valve 2-CH-516, Letdown Safety Injectior Replaced limit switches

& Containmenc Isolation Actuation Iso. Valve 2-CH-517, Aux. Spray Charging Hdr.

Replaced limit switches Iso. Valve 2-CH-518, Loop 2A Charging Hdr.

Replaced limit switches Iso. Valve.

11/4/79 Safety Injection 2-SI-614, #1 Safety Injection Tank Replaced limit switches Discharge Valve 2-SI-624, #2 Replaced limit switches 2-SI-634, #3 Replaced limit switches 2-SI-644, #4 Replaced limit switches 11/5/79 Feedwater Steam Generator Feed Pump H-5A Replaced pump bearings 11/6/79 Fire Protection Sprinkler System Changed out 94 sprinkler heads e

O CD N

4 u

e-e

I Docket No.

50-336 Page 2 of 3 Date January 10, 1980 Unit Name Millstone 2 Completed By G. H. Howlett Telephone 203/447-1791 X304 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month November 1979 DATE SYSTEM COMPONENT MAINTENANCE ACTION 11/10/79 Enclosure Gdg.Fil tratior 2-EB-42, Enclosure Bldg. Filtratior Replaced damper motor System Fan 'B' Discharge Damper 11/10/79 Enclosure mdg.Fil tratior 2-EB-52, Enclosure Bldg. Filtratior Replaced damper motor System Fan 'A' Discharge Damper 11/10/79 Enclosure Edg.Fil tratior 2-AC-1, Containment & Enclosure Replaced damper motor Bldg. Purge Fan Discharge Valve

'11/11/79 Reactor Coolant 2-RC-0368, Loop 1A Spray Header Repaired body to bonnet gasket leak Drain Valve 11/16/79 Reactor Coolant 2-RC-45 Containment Isolatit Rebuilt valve 11/16/79 Service Water 2-SW-8.18, Temperature Control Rebuilt valve Valve RBCCW Heat Exchanger 'C' 11/17/79 Reactor Coolant 2-RC-003, Pressurizer Steam Space Rebuilt valve, see LER 79-187 Sanple Control Valve 11/20/79 Reactor Coolant P-40A Reactor Coolant Pump Replaced leaking pump motor "0" ring 11/21/79 Feedwater 2-FW-5B, Feedwater Hdr. B Con-Rebuilt valve operator tainment Iso. Check Valve

,y 11/26/7983s Reactor Coolant 2-RC-002, Pressurizer Surge Line Rebuilt valve, see LER 79-187 C{}

Sample Control Valve 11/26/79 Ja-Reactor Coolant 2-RC-001, #1 Hot Leg Sample Rebuilt valves, see LER 79-187 ted Control Valve i

b Docket No.

50-336 Page 3 Of 3

Date January 10, 1980 Unit Name Millstone 2 Completed By G. H. Howlett Telephone 203/44/-1/91 A 364 CORi'ECTIVE MAINTENANCE SUtstARY FOR SAFETY RELATED EQUIPMENT Report Month November 1979 DATE SYSTEM COMPONENT MAINTENANCE ACTION 11/79 Steam Generator / Feed-Steam Generators #1 & 2 Repaired cracked steam generator safe end welds water (X-25 & X-26) Safe Ends and and associated feedwater piping.

Associated Feedwater Piping thi CW N

4 u

Date: _Ja.nuaryA R8.0

[

Completed By:

G._H. Howlett Telephone:

203/447-1971 X364 i

REFUELING INFORIMTI0fl REQUEST i

i l.

Name of facility:

14illstone 2 2.

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

Schedule date for restart following refueling: September 1, 1980

?

4.

11111 refueling or resumption of operation thereafter require a technical.

specification change or other license amendment?

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

.l I

S.

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

The schedule for submitting proposed license action is as follows:

l 1

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 srient fuel storage pool:

(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 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:

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

1986, Core full, Spent fuel Pool contains 648 bundles.

96024314.

.