ML20077Q116

Monthly Operating Rept for Jul 1991 for Millstone

ML20077Q116
Person / Time
Site:	Millstone
Issue date:	07/31/1991
From:	Neron G, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-91-665, NUDOCS 9108210071
Download: ML20077Q116 (5)

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I M UTEMES

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H ART FORD. CONNECTICUT 06141-0270 A ,,;.. , .c u .. s u .> c n ~ (203) 665-$000 f

August 15, 1991 i MP-91-665 Re: 10CFR50.71(a)

I U.S. Nuclear Regulatory Commission  :

Document Control Desk i Vashington, D. C. 20555 i

Reference:

Facility Operating 1.icense No. DPR-65 i Docket No. 50 336 j 3

Dear Sir:

This letter is forwarded to provide the report of operating and shutdown  ;

experience relating to Millstone Unit 2 for the month of July,1991, in  ;

accordance with Appendix A Technical Specifications, Section 6.9.1.6. One additional copy of the report is enclosed.  ;

f Very truly yours, f

NORillEAST NUCLEAR ENERGY COMPANY  !

[  ! "

(4 < L

/ Stephe E'. Scace .

Station Director v Millstone Nuclear Power Station  :

SES/GN f c: T. T. Martin, Region I Administrator [

G. S. Vissing, NRC Project Manager, Millstone Unit No, 2  !

W. J. Raymond, Senior Resident inspector, Millstone Unit Nos. 1,263 j i.

t-C10043 9  !

o108210071ADOCI OOo336 g,.1..0'731 ppR PDR R / j jh.

' ' OPERATING DATA REPORT DOCKET No. 50-336 DATE 08/06/91 COMPLETED BY G. Neron TELEPHONE (203) 447 1791 EXT. 4417 OPERATING STATUS Notes: Items 21 and 22

1. Unit Name: Millstone Unit 2 cumulative are weighted

2. Reporting Period: July _1901 averages. Unit operated

3. Licensed Thermal Power (MWc): 2700 at 2560 MWTH prior to its

4. Nameplatt Rating (Gross MWe): 909 uprating to the current

5. Design Electrical Rating (Net MWe): 870 2700 MWTH power level.

6. Maximum Dependable Capacity (Cross MWe): 893.8G

7. Maximum Dependabic Capacity (Net MWe): 862.88

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

N/A

9. Power Level To Vhich Restricted If any (Net MWe): N/A

10. Reasons For Restrictions, If Any: N/A This Month Yr.-To Date Cumulative

11. Hours In Reporting Period 744.0 5087.0 136727.0

12. Number Of Hours Reactor Was Critical _ 611.1 3417.2 100329.8

13. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5

14. Hours Generator On-Line 560.1 3289.6 95633.6

15. Unit Reserve Shutdown Hours 0.0 0.0 468.2

16. Gross Thermal Energy Generated (MWH) 1352310.0 8544461.0 263600525.4

17. Gross Electrical Energy Generated (MWH) 444249.0 2835255.0 __80274954.5

18. Net Electrical Energy Generated (MWH) 423931.0 2716398.0 77017447.5

19. Unit Service Factor 75.3 64.7 69.9

20. Unit Availability Factor 75.3 64.7 70.3

21. Unit Capacity Factor (Using MDC Net) 66.0 61.9 66.1

22. Unit Capacity Factor (Using DER Net) 65.5 61.4 64.9

23. Unit Forced Outage Rate 24.7 35.3 14.2

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

N/A

25. If Unit Shutdown At End Of Report Period Estimated Date of Startup: N/A

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

Forecast Achieved INITIAL CRITICALITY N/A _ N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A __

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 336  !

UNIT Millstone Unit 2 DATE: 08 /0(. ')1 '

COMPLETED BY: C. Neron TELEPHONE: (203) 447 1791  ;

EXT: 4417 l

t MONTH: JULY 1991 SAY AVG. DAILY POWER LEVEL DAY AVO. DAILY POVER LEVEL i (MWe Net) (MWe-Net) 1 0 17 864 i 2 0 18 864 3 0 19 853 4 0 20 ,_ 47 5 0 21 247 6 0 22 836 i

7 167 23 863 ~

8 394 24 865 [

9 611 25 867  ;

10 458 26 867 l 11 422 27 821  !

12 819 28 830 r-r 13 854 29 86L 14 864 30 870 ,

15 865 31 870 l i

16 865 i INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each  ;

day in the reporting month. Compute to the nearest whole megawatt.  !

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DOCKET NO. 50-336 UNIT SHUTDO~.'NS AND POWER REDUCTIONS UNIT NAME _.]U11 stone 2' DATE 08/06/91 -

COMPLETED BY G. Neron TELEPHONE (203) 447-1791 JULY 1091 EXT. 4417 REPORT MONTH System Component Cause & Corrective Type l Duration Reason 2 Method of License No. Date Shutting Event Code" Code 3 Action to (Hours) Prevent Recurrence Down Reactor 3 Report

• 91-00S JC PS Continuation of Steam 04 910525 i 147.1 H 1 Generator inspection and r, pair outage from the previous month. The main generator was placed "on line" July 7, 1991. Unit proceeded to 75% power and p+ blems with the main turbine master trip solenoid were discovered.

N/A N/A The main generator was 05 910710 S 9.4 A 6 N/A taken "off line" on July 10, 1991, to re-place the "A" Turbine master trip solenoid and the *2 Stop Valve fast acting solenoid. The reactor was main-tained critical during this period. The main generator was placed ",n line* July ll,1991. Unit achieved 1004 power on July 12, 1991.

N/A N/A The main generator was 06 910720 S 27.4 A 6 N/A taken "off line" en July 20, 1991, to troubleshoot the "A* 6 *B" turbine master trip solenoids.

Both the "A" & *B" caster trip solenoids were replaced (the "B" solenoid did not require replacement). The main generator was placed "on line" July 21, 1991. Unit achieved 1005 rower on July 22. 1001 2 Reason: 3 Method ' Exhibit G - Instructions F: Forced 1-Manual for Preparation of Data 5: Scheduled A-Equipment Failure (Explain) Entry Sheets for License B-Maintenance or Test 2-Manual Scrac 3-Automatic Scram Event Report (LER) Tile C-Re fueling D-Regulatory Restriction 4-Continued from (NCREG-0161)

E-Operator Training & License Examination Previous conth 5-Power Reduction 5 Exhibit 1 -Same Sonrce F-Administrative G-Operational Error (Explain) (Duration -0)

H- Other (Explain) 6-Other (Explain)

( _ _

REFUELING INFORMATION REQUEST

1. Name of facility: Millstone 2

3. Scheduled date for next refueling shutdowns _bpril, 1992

3. Scheduled date for restart following refueling: N/A

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

}{pne at this time

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

None

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:

Mil:. stone 2 will be replacina the Steam Generator sub-assemblien durana the uncomina End of Cycle 11 refuelina outace. It is antLcinated this will be accomplished under 10CFR 50.59.

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

In Core: (a)~ all In Spent Fuel Pool: (b) lla NOTE: These numbers represent the total fuel assemblies and consol-idated fuel storace boxes in these twp (2) Item Control Areas

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:

Currently 1277

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

1994. Snent Fue: Pool Full, core off load capacity is reached (with

-out consolidatnon).

1998. Core Full._ Spent Fuel Pool Full 2009, Snent Fuel Pool Full, core off load canacity is reached-ggntincent upon full scale storage of conso13 dated fuel in the Spent Fuel Pool.

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