ML20042G005

Monthly Operating Rept for Apr 1990 for Millstone Unit 2. W/900508 Ltr

ML20042G005
Person / Time
Site:	Millstone
Issue date:	04/30/1990
From:	Gibson J, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC
References
MP-90-465, NUDOCS 9005100287
Download: ML20042G005 (5)

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May 8, 1990

, t4-MP-90-465 ,

Re: 10CFR50.71(;.)

U.S. Nuclear Regulatory Commission :l Document Control Desk Washington, D. C. 20555-l.

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Reference:

Facility Operating Licente No. DPR-65

, Docket No. 50 336 ,

Dear Sir:

z This letter is forwarded to provide the report of operating 4. n. 4hutdown experience relating to Millstone Unit 2 for the month of April .990, in accordance with Appendix A Technical Specifications, Section 6.,.1.6. One additional copy of the report is enclosed.

.Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY 9

/4 W Ste.pen/ . Scace D rector, Millstone Station i

SES/JC .

'cc: 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 l

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y, OPERATING DATA REPORT DOCKET NO. 50-336-DATE 05/03/90 COMPLETED BY J. Gibson TELEPHONE (203) 447 1791 EXT. 4431 ll

~0PERATING STATUS Notes: Items 21'and 22

~1. Unit "ame: M111 store Unit 2 cumulative are_ weighted

.? Reporting Period: Acril 1990 averages. Unit operated. ,

t.1 Licensed Thermal Power (MWt): 2700 at 2560 MWTH prior to its >

4. LNameplate Rating (Cross MWe): 909 uprating to the' current

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

~6. Maximum Dependable' Capacity (Gross MWe): 893cl

7. Maximum Dependable Capacity (Net MWe): 862.o8

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

,7 N/A ,

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

10. Reasons For Restrictions, If.Any: N/A J

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This Month -Yr. To Date Cumuletive

--11. Hours In Reporting Period 2879.0 125759.0.

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719.0 ,

12. Number Of Hours-Reactor Was Critical 719.0 2879.0 ?3240.1-

13. Reactor Reserve Shutdown Hours 0.0 0.0 2205.5-(14.= Hours Generator On-Line 705.3 2865.3_ ___

88816.7

'15.1 Unit Reserve Shutdown Hours 0.0 0.0 468.2-

-16.! Gross Thermal Energy Generated (MWH) 1870658.0 7701129.0 245836967.4-  !

17. Gross Electrical Energy Generated (MWH) 598621 5-

. 2500609.5- 74419779.5 -

+ '18.-Net; Electrical' Energy Generated (MWH) 576606.5 2412013.5 71408647.5 .

19. Unit Service Factor 98.1 99.5 70.6 1 *

!20.. Unit Availability Factor .

98.1 99.5 71.0 211 Unit = Capacity Factor (Using MDC Net) 92.9 97.1 66.8 m .22.' Unit Capacity Factor (Using DER Net) 92.2 96.3 65.4 123. Unit Forced 0utage Rate _ 13.5

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1.9 0.5 _, .

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

it 'End of Cycle 10 Refueling ~0utare. Sentember 7. 1990. 40 days.

25' If Unit Shutdown At End Of Report Period, Estimated Date of Startup: N/A 26L Units In Test' Status (Prior to Commercial Operation): _

l Forecast Achieved 't INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A-

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- COMMERCIAL OPERATION N/A N/A l

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AVERAGE DAILY UNIT POWER LEVEL -

DOCKET NO. 50-336 UNIT: Millstone Unit 2' DATE: 05/03/90

[ COMPLETED BY:

TELEPHONE:

J. Gibson (203)447-1791

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n EXT: 4431 4 ,

MONTH: APRIL 1990 DAY. AVO. DAILY POWER LEVEL DAY AVG, DAILY POWER LEVEL (NWe-Net) (NWe-Net) -

> 802 17 837 ,

2 836' 18 836 3 836 19 836 4 835 20 836 5 836- 21 83.E 6- 835 22 82 _. .._

7 834 ___ 23 ___

P?7 8 834 24 837 L

0: 9 834 25 837 10 834 26 629 .

r 11 784 -27 133 12 818 28 798  :

13 837 29 837 s 14 837 30 836 15 837 31 4

16 837 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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q- DOCKET NO. 33tr-. . . . - V- '

~ UNIT SHUTDOWNS AND POk'ER REDUCTIONS UNIT NAME Millstone ?- -

'DATE 05/03/90 '.a - '

COMPLETED BY~ J. Gibson + -

TELEPHONE (203) 447-1791-REPORT MONTH ~ APRIL 1990 EXT. 4431~

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N3 .Date- Type l - Duration Reason2 Method of License. . Systgm Compgnent Cause &' Corrective (Hours). Shutting Event . Code Code Action to Down Reactor3 ' Report # Prevent Recurrence 01 26-APR-90 S. 13.7 B 6_ 'N/A N/A N/A Whr.le operating at'100 %

. power,'a power reduction.

was initiated to take the main generator off line-

.te allow'for the removal of a' cloth rag from the; Main Generator Collector Fan. ' The unit was'then restored to 100 % power.-

2 Reason: 3Method I: F Forced ' Exhibit G -' Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for License C-Refueling 3-Automatic Scram Event Report (LER) File D Regulatory Res niction 6-Continued from (NUREG-0161)

E-Operator Trainir:r, & License Examination Previous month

.5 F-Administrative ~5-Power Reduction Exhibit 1 -Same Source-G-Operational Error (Explain) -(Duration -0)

H- Other;(Explain) 6-Other (Explain)'

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REFUELING INFORMATION REOUEST

1. -Name of facility: ' Millstone 2

2. ' Scheduled date for next refueling shutdown: September 7. 1990'

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?

YES

.S. Scheduled date(s) for submitting licensing action and supporting-info"mation:

J_qlys 39eo

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 fue) design, new operating procedures:

None 7.- .The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:

In Core:. (a) 212 In Spent Fuel Pool: (b) 640

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 i the spent fuel pool assuming the present licensed capacity:

.{

1994. SD'ent Fue: Pool Full, core off load capacity is reached (with -

-out consolidat:.on).

1998, Core Full. S. pent Fuel Pool Full 2009. Soent Fuel Pool Full, core off load capacity is reached- l

'continuent uoon full scale storace of consoljdated fuel in the 'I 3"

Soent Fuel Pool.

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