ML20067E558

Monthly Operating Rept for Jan 1991 for Millstone Unit 2.W/

ML20067E558
Person / Time
Site:	Millstone
Issue date:	01/31/1991
From:	Neron G, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-91-121, NUDOCS 9102150124
Download: ML20067E558 (5)

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February ll, 1991 MI'-91-121 Re: -10CFPLO.71(a)

U.S. Nuclear Regulatory Commission Docwnent Control Desk Washington, D. C. 20555

Reference:

- Facility Operating License No. DPR 65 Docket No. 50-336-

Dear Sir:

This letter is forwarded to.provice the report of operating and shutdown experience relating to Millstone Unit 2 for the month of January,1991, in accordance with Appendix A Technical Specifications, Section 6.9.1.6.

One additional' copy of the~ report s enclosed.

Very truly yours, NORTHEAST NUCLEAR ENERCY COMPANY Mf Sbep n E. Scac(EMU Station Director.

Hillstone.Nucinar Power Station SES/GN L e 2.

T. T. Martin, Region 1 Ade:inistrator-G. S,' Vissing,.NRC Icoject Manager, Millstone Unit No. 2 iW. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2 & 3 910215012< 910131

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.{DR :ADOCK 05000336

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I OPERATING DATA REPORT DOCKET NO, 50-336 DATE 02/06/91 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:

January 1991 averages. Unit operated-3-

Licensed Thermal-Power (MWt):

2700 at 2560 MWTH prior to its 4.

Nameplate Rating-(Gross MWe):

909 uprating to the current

.5.

Design Electrical Rating (Net MWe):

870 2700 MWTH power level.

6.

Maximum Dependable Capacity (Gross MWe):

893.81 7.

Maximum Dependable Capacity (Not MWe):

862.88

-8, If Changes Occur in Capacity Ratings (I* cms Number 3 Tttrough 7) Since launt Report, Give Reasons:

N/A L

I 9.--Power Level'To Which Restricted, If any (Net MWe):

N/A

,10 ' Reasons' For Restric tions, If Any:

N/A 1

This Month Yr..To-Date Cumulative 11; Hours In Reporting:Perici 74(,0

-744.0 132384.0

12. Number Of Hours Reactor Was Critical 553 9 553.0 97465.6

13. Reactor Reserve Shutdown hours 0.0 0.0 2205.5 m

14." Hours Generator On Line 511.1 511.1,

92854.9

15. Unit Reserve' Shutdown Hours 0.0 0.0 468.2

'16. Gross Thermal Energy Generated (MWH) 1323684.0-1323684.0 256379148.4

17. Gross Electrical Energy Generated (MWH) 438940.5 438940.5 77878640;0

.18. Net Electrical Energy Generated -(ifRH) 410145.5 420145.5-74721195.0

?

- 19. Unit S.rvice Factor 68.7-68.7 70.1 20.JUnit Availability - Factor 68.7 68.7

-70.5 "21. Unit Capacity Factor (Using MDC Net)~

65.-4 65.4 66.2 l

22.; Unit; capacity Factor (Using DER Net) 64,2 64.9 64.9 L

23. Unit: Forced Outage Rate 31.3' 31 3' 13.3 L

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

'N/A Ld 125. If Unit Shutdown At End Of Report Period, Estimated Date of Startup:

N/A L

--36L Units In Test Status-(Prior to Commercial Operation):

f Forecast-

-Achieved i

INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION.

N/A N/A i

g. _

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1

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AVERAGE DAILY UNIT POVER-LEVEL ~

)

DOCKET NO.

50 336 UNIT Millstone Unit 2-i s

DATE:.

02/06/91:

y' '

COMPLETED BY -

G. Neron

-TELEPHONE:

(203) 447-1791 EXT: '

4417 I

l

.MONTHI JANUARY 1991

~ DAY: -AVG. DAILY' POWER LEVEL DAY AVG. DAILY POWER LEVEL-(MWe-Net)-

(MWe-Net) il 0

17-875

'?

K"'

2:

0' 18 874 l

2-3-

0 19-874 1

h

,4 0

20 875 1

5.-

0 21 873 i61 0

22 871-3 r

(7=

'O' 23 870 s

a

+

h

,8 -

'O' 24 873-19' 217 25-868-

,.:t J101

'481-26=

868

~

i "c

,s 711 to-

,.27

-870

(

12!

376 28 871'

[;

i h

-/13; 856'

, '871 jt 114:

'-870 -

.- 30 :

873

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-y 872-

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il5!

874-

31.

i. :

i.,

1 1 61 873

%ll% +

INSTRUCTIONS I.,. M' Con. this formatX l'ist the average daily. unit-power level in MWe Net foreeach t

ic I\\:

4

.Jday-in;the.. reporting month... Compute to the~ nearest whole megawatt.

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DOCKET NO.

^50-336 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 DATE 02/06/91-COMPLETED BY G. Neron TELEPHONE (203) 447-1791 REPORT MONTH __ JANUARY 1991 EXT.

4417 l

2 No.

Date Type Duration Reason Method of License Systgm Compgnent Cause & Corrective (Hours)

Shutting-Event Code Code Action to 3

Down Reactor Report #

Prevent Recurrence 06 901229 F

197.8 A

1 N/A N/A N/A Continuation of steam generator. primary man-way leak repair outage from previous month; Turbine generator was placed "on line" on 01/09/91; Unit increased power to -92% for condenser cleaning.

01 91011C F

35.1 A

3 91-1 TG P

While operating at ~92%

power, the

'B' Electric-Hydraulic Control pump failed to maintain proper system pressure which caused a turbine trip and subsequent reactor trip on 01/10/91; the Unit achieved criticality on 01/11/91 and turbine genera-tor was placed "on line" on 01/12/91; the Unit achieved 100% power on 01/13/91; See LER.-

l l

l 1: Forced Reason:

Method

' Exhibit G - Instructions 2

3 F

(

S: Scheduled A-Equipment Failure (Explain) 1-Manual for. Preparation of Data l

B-Maintenance or Test 2-Manual Scram Entry Sheets for License l

C-Refueling 3-Automatic Scram Event Report (LER) File l

D-Regulatory Restriction 4-Continued from (NUREG-0161)

.E-Operator Training & License Examination Previous month

~

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

(Duration -0)

H-Other (Explain) 6-Other (Explain) l 1

~

~ - - -

m

REFUELING INFORMATION REQUEST 1.

Name of facility:

Millstone 2 2.

Scheduled date for next refueling shutdown:

March. 1992 3.

Scheduled date for restart following refueling:

_1UA 4.

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

None at this time 5.

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

None at this time 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:

None 7.-

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

In Core:

(a) 211 In Spent Fuel Pool:

(b) 212 NOTE: These numbers represent the total fuel assemblies and consol-

. dated fuel storace boxes in these two (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. Spent Fue:

Pool Fall, c>re off load capacity is rgached (with

-out consolidut:.on).

1998. Core Full, Spent Fuel Pool Full 2909, Spent Fuel Pool Full, core o*f load capacity is reached-continoent upon full scale 7torace of consolldated fuel in the Soent Fuel Pool.

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