ML20212P440

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Monthly Operating Rept for Feb 1987
ML20212P440
Person / Time
Site: Millstone Dominion icon.png
Issue date: 02/28/1987
From: Newburgh G, Scace S
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-10130, NUDOCS 8703160110
Download: ML20212P440 (5)


Text

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AVERAGE DAILY UNIT POWER' LEVEL DOCKET NO. 50-245 UNIT Millstone 1

-~DATE 870302 COMPLETED BY G. Newburgh TELEPHONE (203)447-1791 Ext. 4400 MONTH February 1987 DAY

-AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net)-

D 1

656 17 656 2

657 18 650 3

658 19 657 4

657 20 657 5

657 21 656 6

622 22 657 7

655 23 657 8

657 24 657 9

656 25 651 10 656 26 657 11 656 27 657 12 656 28 657 13 655 29 N/A 14 656 30 N/A 15 657 31 N/A 16 657 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.

Oo$$!45 PDR

.. s g.-

'0PERATING' DATA REPORT w

.e DOCKET NO.

50-245 DATE 870302-3 COMPLETED BY G. Newburgh TELEPHONE (203)447-1791 4

OPERATING STATUS.

Ext 4400:

11 ' Unit Name: Millst'one 1 Notes 2.

Reporting Period: February 1987 3.-

Licensed Thermal Power (MWt):. 2011

'4

= Nameplate' Rating (Gross MWe):

662 J 5.'

~ Design Electrical Rating (Net MWe):

660

-6.

4 Maximum Dependable Capacity l(Gross MWe):

684 17.

Maximum Dependable Capacity-(Net MWe):

65T-'-

8.

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

Since'Last Report, Give Reasons:

N/A 19.

Power Level To Which 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 672 1416 142464

12. -Number Of Hours Reactor Was Critical 672 1416 110771.3 13.

Reactor Reserve Shutdown Hours 0

0 3283.3-14.

Hours Generator On-Line 672 1416 107781.4 115.--Unit Reserve Shutdown Hours 0

0 19957538.1 93.7-16.

Gross Thermal Energy-Generated (MWH) 1344256 2817308

17. Gross Elec.' Energy. Generated (MWH)-

459800 962600 67154596

18. ' Net Electrical Energy. Generated (MWH) 440205

'919999 64057711

.19.

Unit Service Factor '

100 100 75.7 20.~

Unit Availability Factor-100 100 75.7

21.. Unit Capacity Factor.(Using MDC Net) 100 99.3-68.8
22. Unit Capacity Factor (Using DER Net) 99.3 98.4-68.1
23. -Unit Forced Outage Rate.

0 0

11.7 24.

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

Refueling Outage, June 1987,-8 week duration.

25. If Shut Down At End Of Report Period, Estimated Date of Startup:

N/A

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

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY N/A COMMERCIAL OPERATION

DOCKET NO.

50-245 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 1 DATE 870302 COMPLETED BY G. Newburgh REPORT MONTH February 1987 TELEPHONE (203)447-1791 Ext 4400 l

2 No.

Date Type Duration Reason Method of Licensee Systeg Compogent Cause & Corrective (Hours)

Shutting Event Code Code Action to 3

Down Reactor Report #

Prevent Recurrence N/A y

1 1

2 3

4 F: Forced Reason:

Method:

Exhibit G - Instructions-5: 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

G-Operational Error (Explain)

(Duration = 0)

Exhibit 1 - Same Source H-Other (Explain) 6-Other (Explain) e

REFUELING INFORMATION REQUEST 1.

Name of facility:

Millstone 1 2.

Scheduled date for next refueling shutdown:

June 1987 3.

Schedule date for restart following refueling: August 1987 4.

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

Yes, Technical Specification Changes Regarding:

(1) Maximum Average Planar Linear Heat Generating Rate (2) Maximum Critical Power Ratio 5.

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

Spcing 1987 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:

200 GE8B Fuel Assemblies 7.

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

(a) In Core: (a) 580 (b) 1546 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:

2184 Assemblies 9.

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

1987, Spent Fuel Pool Full Core Off Load Capability is Reached.

T991, Core Full, Spent Fuel Pool Contains 214f Bundles.

Y N UTHJTIES cenerai Orrices. seiden street. seriin, connecticut 1

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P.O. BOX 270

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(2031 665-5000 March 9, 1987 MP-10130 Re:

10CFR50.71(a)

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

Reference:

Provisional License DPR-21 Docket No. 50-245

Dear Sir:

In accordance with Millstone Unit 1 Technical Specification 6.9.1.6, the following monthly operating data report for Millstone Unit 1 is enclosed.

One additional copy of the report is enclosed.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY f l ul b

atJ- -

Ste en E. Scace Station Superintendent Millstone Nuclear Power Station SES/GSN:jlm

Enclosures:

(

)

cc:

Director, Office of Inspection and Enforcement, Region I l

Director, Office' of Inspection and Enforcement, Washington, D. C.

(10)

U. S. Nuclear Regulatory Commission, c/o Document Management Branch, Washington, D. C. 20555 g?J

.P

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