ML20215L700

Monthly Operating Rept for Apr 1987

ML20215L700
Person / Time
Site:	Millstone
Issue date:	04/30/1987
From:	Newburgh G, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC
References
MP-10353, NUDOCS 8705120332
Download: ML20215L700 (5)

Text

A AVERAGE DAILY UNIT' POWER LEVEL DOCKET NO. 50-245 UNIT Millstone 1 DATE 870501 CO.MPLETED BY G. Newburgh TELEPHONE (203) 447-1791 Ext. 4400 MONTH' April 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1-655

- 17 655 2

650 18 656 3

656 19 655 4

656 20 655 5

628 21 654 6

655 22 651 7

655 23 655 8

655 24 655 9

655 25 655-10 557 26 655 l

11 655 27 655 l

12 654 28 655 l

l 13' 656 29 649 14 657 30 656 15 482 31 N/A t

16 625 l

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.

i 1C-AN 8705120332 870430

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N PDR ADOCK 05000245 R

PDR

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.0PERATING DATA REPORT DOCKET NO.~50-245'

=DATE 870501 COMPLETED BY G. Newburgh TELEPHONE (203) 447-1791 Ext. 4400 OPERATING STATUS l1.

Unit-Name:

Millstone Unit 1 Notes: April report reflects 2.

Reporting Period:

April 1987 change to day light

- 3.'

Licensed Thermal Power (MWt):

2011

' savings time.

<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-10.

Reasons For Restrictions, If Any: N/A i

l

~

l This Month Yr. -to-Date Cumulative l

~11.

Hours In Reporting Period 719

'2879 143927 l

12. Number Of Hours Reactor Was Critical 719 2860.6 112215.9 13.

Reactor Reserve Shutdown Hours

-0 0

3283.3 14.

Hours Generator On-Line 719 2852 109217.4

'15.

Unit Reserve Shutdown Hours 0

0 93.7 16.'

Gross Thermal Energy Generated (MWH) 1420072 5648580 202406653

17. Gross Elec.' Energy Generated (MWH) 484300 192C400 67638896 18.

Het Electrical Energy Generated (MWH) 463479-1843825 64981537 19.

Unit Service Factor 100 99.1 75.9 20.

Unit Availability Factor 100 99.1 75.9 21.

Unit Capacity Factor (Using MDC Net) 98.6 97.9 69.0 22.

Unit Capacity Factor (Using DER Net) 97.7 97.0 68.4 23.

Unit Forced Outage Rate 0

0.9 11.6 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 25.

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

DOCKET NO. 50-245 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 1 DATE 870501 -

. COMPLETED BY G. Newburgh REPORT MONTH April 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 3

870415 S

0 B

5 N/A N/A N/A Power reduction to repair. steam leak.

1 2

3 4

F:

Forced Reason:

Method:

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 G-Operational Error (Explain)

(Duration = 0)

Exhibit 1 - Same Source H-Other (Explain) 9-Other (Explain)

3. :..

a

Docket No. 50-245-

.Date: 870501 L

Completed _By: G.<Newburgh b

.Telephonei (203) 447-1791 Ext. 4400 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 19871 4.

.Will refueling or resumption of operation _thereafter require a technical'

~

specification _ change or.other-license amendment?

e 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:

Spring 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 GE88 Fuel Assemblies 7.

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

(a) In Core:

580 (b)

-1536 8.

The present. licensed speat 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 The 1112 available locations reflects the re-racked Spent Fuel Pool.

The re-racking of the Unit 2 Spent Fuel Pool has been completed.

9.

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

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

1991, Core Full, Spent Fuel Pool Contains 2146 Bundles.

e N 85TILETIES conor i Orric... seio n stro.i. Boriin. Conn.cticui 9

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P.O. BOX 270

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(203) 665-5000 May 8, 1987 MP-10353 Re:

10CFR50.71(a)

Director, Office of Resource Management U. S. Nuclear Regulatory Commission Wachington, 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 4

6 Git 2 St phen /.$cace.-

Station Superintendent Millstone Nuclear Power Station SES/GN:mw cc: Director, Office of Inspection and Enforcement, Region I Director, Office of Inspection and Enforcement, Washington, D. C. (10)

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

20555 q

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