ML19332E986

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Nov 1989 for Millstone Unit 1
ML19332E986
Person / Time
Site: Millstone 
Issue date: 11/30/1989
From: Newburgh G, Scace S
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-13824, NUDOCS 8912130234
Download: ML19332E986 (5)


Text

9

4

.g

[

UM General Offices

  • Selden Street, Berlin, Connecticut tesi COsessis' Cut geset ase0 #0eia CoWW 4

.in waww.is iacinc co*=

P.O. box 270

.avo.a.ati..o.in cow."

HARTFoRDs CONNECTICUT 061410270 J ",',[*y "' " 7C" *$'[

(203) 665 5000 j

L L

December 8, 1989 MP-13824 Re:

10CTR50. 71 (a)

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

20555 i

Reference:

Facility Operating License DPR-21 Docket No. 50-245

Dear Sir:

In accordance with Millstone Unit 1 Technical Specification 6.9.1.6, the l

following monthly operating data report for Millstone Unit 1 is enclosed.

One additional copy of the report is enclosed, i.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY au St n

. Scace Station Superintendent Millstone Nuclear Power Station SES/GSN:dlr

Enclosures:

(4)

I cc:

W. T. Russell, Regional Administrator Region I L

M. Boyle, NRC Project Manager, Millstone Unit No. 1 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2 & 3 L

7 1

I t

fry;s ; A' n

l r

l.[

7 1,,4 r_

.j.

s s

.,, y b*

v AVERAGE DAIL1 UNIT POWER LEVEL 8-1 DOCKET NOc 50-245 UNIT = Millstone 1

-DATE 891205 i

COMPiETE BY.:.G. Newburgh,

. TELEPHONE - (203) 447-1791 Extension 4400-MONTH ~ November,1989 DAY' AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 11 659 17 657 2

655 18-660 3

659

.19

'660' 4

659 20 660

'5' 659 21 659

.6 658-22 655 c.

a 7.'

659-23 660-8-

659 24 661 Q

'9" 50'3 25 614

-10 659' 26 642-111 659 27 660 L.

.12

-659 28 656

~13 660 29 660 1

1 1

L.

14' 660 30 660 y'

p-0' 15' 659 31 N/A i

1 3

16 501 l:s i

l.

INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.

Computer to the nearest whole megawatt.

4

l.

. ;; - s '..

'l

\\

OPERATING DATA REPORT

[

DOCKET NO, 50-245 DATE 891205 COMPLETED BY.

G. Newburch-TELEPHONE (203) 447-1791 Extension 4400

[

~ OPERATING STATUS Ll ~.

Unit Name: Millstone-1 Notes:

' '2.

Reporting Period: November, 1989 3.

Licensed Thermal Power (MWt): 2011 4.

Nameplate Rating (Gross MWe):

662 5.

_ Design Electrical Rating (Net MWe) : 660 6.

Maximum Dependable Capacity (Gross MWe): 684 7-. -

Maximum Dependable Capacity. (Net MWe): 654 8.

_ If Changes Occur in Capacity Ratings (Items Number 3 Through 7)

Since Last Report, Give Reasons:

N/A 9.

Power Level to Which Restricted, If Any (Net MWe):

N/A

?l0. Reasons For Restrictions, If Any:

N/A e

'11.

Hours In Reporting Period 720 8,016

'166,608 i

12. Number Of Hours Reactor Was Critical 720 6,633.3 131,620.9 13.- Reactor Reserve Shutdown Hours 0

0 3,283.3

~ 14.. Hours Generator.On-Line 720 6,535.7 128,332.8

15. Unit: Reserve Shutdown Hours 0

0 93.7 L

_16.

Gross Thermal Energy Generated (MWH) 1,413,824 12,743,539 239,928,200 L

17. GrossElec. Energy Generated (MWH) 486,200 4,352,800 80,916,396
18. ' Net Electrical Energy. Generated (MWH) 464,422 4,157,686 77,208,126
19. Unit Service Factor 100 81.5 77.0
20. Unit Availability Factor 100 81.5 77.1

'21.

Unit Capacity Factor (Using MDC Net) 98.6 79.3 70.9

22. Unit Capacity Factor (Using DER Net) 97.7 78.6 70.2 r;
23. ' Unit Forced Outage Rate 0

3.2 10.3-r 12 4. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

N/A 25.

If Shutdown at End of Report Period, Estimated Date of Startup:

N/A

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

Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A CONMERCIAL OPERATION l

y 1

'~

-DOCKET.NO. 50-245 UNIT. SHUTDOWNS AND~ POWER. REDUCTIONS' UNIT NAME Millstone 1 DATE 891205

-COMPLETED BY G. Newburgh

~ REPORT MONTH November, 1989-

. TELEPHONE (203) 447-1791 Extension 4400-No.

Date Type Duration Reason 2 Method of' Licensee

~ System Component l Cause & Corrective-l (Hours)

' Shutting :

Event.

Codei

~ Codes Action to Down. Reactor 3 Report I Prevent Recurrence 89-09 891109 F

0 B

5 N/A

'N/A N/A Power reduction to-perferm maintenance on Feedwater Regulating Valve.

89-10 891116 F

0 B

5 N/A N/A N/A Power reduction to; find and. repair condenser tube leaks..

IF:

Forced 2 Reason:

3 Method:

4 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 Licensee C-Refueling 3-Automatic Scram

Event Report (LER) File D-Regulatory Restriction 4-Continued from (NUREG-0161)

E-Operator Training &. License Examination previous month' F-Administrative ~

.5-Power Reduction 5 Exhibit'l - Same Source G-Operational Error (Explain)-

.(Duration = 0)

H-Other (Explain) -

6-Other (Explain).

4 g;"*ih r

' REFUELING INFORMATION REQUEST 1.

.Name of facility: ' Millstone 1 2.

Scheduled date for next refueling shutdown: March 1991 3.

Schedule date for restart following refueling: April-1991

-4._

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

Yes, Technicial Specification Changes Regarding:

(1) Maximum Average Planar Linear Heat Generating Rate (2) Maximum Critical Power Ratio f

'5.

Scheduled date(s) for submitting licensing action and supporting 4

information:

Winter 1990-91 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:

-196 GE8B Fuel Assemblies

?.

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

(a)

In Core:

(a) 580 (b) 1928 8..

The present licensed' spent fuel pool storage capacity and the size of l

any increase in licensed storage capacity that has been' requested or is i

planned, in number of fuel assemblies:

'j Present capacity,'3229 assemblies 9.

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

j 1997, Spent Fuel Pool, Full Core Off Load Capability is Reached l

-