ML19305E778

Monthly Operating Rept for Apr 1980

ML19305E778
Person / Time
Site:	Millstone
Issue date:	05/07/1980
From:	Howlett G NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML19305E772	List: ML19305E771 ML19305E778
References
NUDOCS 8005200407
Download: ML19305E778 (5)

Text

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8005280 df (vD OPERATING DATA REPORT i DOCKET NO. 50-336 l DATE 5/7/80 CO\lPLETED BY -G.H. Howlett TELEPHONE (2031447-1791 X364 OPERATING STATUS

1. Unit Name; Millstone 2 Notes

• Items 21 & 22

2. Reporting Period. April 1980 cumulative are computed 2700 using a computed . average.

3. Licensed Thermal Power (5tht):

4. Nameplate Rating (Gross stwe): 909

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

6. Stasimum Dependable '~apacity (Gross 31We): 895

7. Slasimum Dependable Capacity (Net StWe): 864

8. If Changes Occur in Capacity Ratings (!tems Number 3 Throu;h 7) Since Last Report. Gis e Reasons:

None

9. Power Level To which Re<tricted.!f Any (Net .\tWe): None

10. Reasons For Restrictions. lf Any: NA This Stonth Yr..to.Da te Cumularise

11. Hours In Reporting Period - 71 9 2,903 38,111

12. Number Of Hours Reactor Was Critical 700.5 2,813.1 27,892.2

13. Reactor Resene Shutdown Hours 0 0 2,072.4

14. Hours Generator On.Line 685.1 2,744.2 26,564.4

15. Unit Resene Shutdown Hours 0 0 - 335.4

16. Gross Thermal Energy Generated (31WH) l.831,957 7,257,501 64,956,129

17. Grus Electrical Energy Generated (31WH) 595,346 , _ , 2,373,815 20,958,460

18. Net E ectrical Energy Generated (31WH) 573.523 2.284.416 20.064.674

19. Unit Senice Factor 95.3 94.5 69.7

20. Unic Asailability Factor 95.3 94.5 70.6 92.3 91.1

• 64.2

21. Unit Capacity Factor (Using \tDC Net) .

91.7 90.5

• 62.8

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Ourage Rate 47 5.5 22.3 l

24. Shutdown, Scheduled Oser Nest 6 Stonths IType. Date,and Duration of Each):

Ref_uelina (Cvele 4). July 1.1980. 9 weeks _

l

25. If Shut Down At End Of Report Period. E3rimated Date of Startup: NA

26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITI A L CRITICA LIT Y N/A N/A INITIAL ELECTRICITY N/A N/A

{

Cost \tERCIAL OPER ATION _NZA._ N/A j (4/77 ) j

( )

4\ ER ACE D Ally L%'lT iOh tR LEVEL 50-336 DOCKET NO.

UNIT Millstone 2 DATE _578/80 cosfPLETED By G.H. Howlett TELEPHONE _(203)447-1791X364 stoNm April 1980 DAY AVER ACE DAILY pohER LEVEL DAY AVERACE Dally POhER LEVEL (S!We Net)

OfWe Ner; 846 845 17 2 ga7 845 1s 3 847 M 838 4 848 20 s 848 846 23

)

6 847 846 22 7 847 846 23 8 847 24 9 846 845 25 10 846 845 26 11 846 845 27 __

12 811 845

~

s 13 846 15 2,

14 845 30 170 15 846 -

31 16 845 INSTRUCTIONS

- a Onne3:esi the this forrms.

wy,ot, , list the

,, ase are d-ils . r.it Pow er eselin .'.1We. Net for each day in the repvrtin PM71

UNIT Sil01DOWN., AND POWER REDUCllONS DOCKET No. 50-336 UNIT N AME fillistone Z DATE S/8/80 April 1980 00%fPLETED Dy G.ll. liowlett REPORT MONTil 1ELEPilONE (203)447-1791 X364 i

. "b -

o 5. E 3g Yk Licensee ,E'r

5 h". Cause & Correceive N. i . Dale g 3g ,3 g 5 Event E3 Atenin tis

• iE 0 '

$E 5 j di j Repmta Prevent Recurrence d

7 800429 F 25.5 A 3 N/A CB VALVEX Pressurizer spray valve stuck open, till VAVEX resulting in a R.C.S. pressure drop.

Subsequently reactor power was reduced ,

during which feed regulating valve (2-FW-51A) locked up (closed). The reactor tripped on low steam generator level.

8 800430 F 8.4 A 3 N/A lill VALVEX Feed regulating valve (2-FW-51 A) locked-up (closed), resulting in a reactor trip on low steam generator level.

SUMMARY

The unit operated at or near 100% rated thermal power throughout the month except for the reactor trips on the 29th and 30th.

I'l/77 ) ,

Page 1 of I Docket No< 50-336 Date 5/'J/ uu Unit Name Millstone z '

Completed By G.H. Howlett Telephone (?03)447-1791 X364 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Fbnth March 1980 DATE SYSTEM '

COMPONENT MAINTENANCE ACTION 3/10/80 Control Element Assem- C.E.A. #29 Cable / Connector Replaced cable / connector assembly (See LER 80-10) bly Position Indica-tion 3/10/80 Chemical & Volume Charging Pump P-18C Replaced pump (See LER 80-06)

Control 3/14/80 Main Steam Snubber #490001 Replaced leaky snubber (See LER 80-12/3L-0) 3/20/80 Control Element CEDM #1 CEA #7-1 Replaced regulating power supply Drive (See LER #80-13) 3/21/80 Auxiliary Feedwater Aux Feed Pump P-9A Replaced failed pump packing (See LER 80-09/3L-0) 3/28/80 Main Control Room Control Room Exhaust Fan Replaced failed motor bearing (See LER 80-14/3L-0)

Ventilation

Docket flo. 50-336 Date: May 12,1980 Completed By: G.H. Howlett Irl Telephone: 203/447-1971 X364 REFUELIflG 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 licensing action and supporting information:

The schedule for submitting license action is as follows:

Basic Safety Report 3-6-80 Additional licensing documentation in support of cycle four (4) operation will be provided in response to Nuclear Regulatory Commission staff questions.

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 l and safety analysis will be supplied by Westinghouse. l

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

(a) In Core: 217 (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 l

9. The projected date of the last refueling that can be discharged to the spent l fuel pool assuming the present licensed capacity: l 1985, Spent Fuel Pool, full core off load capability is reached. '

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

l