ML20057F933

Monthly Operating Rept for Sept 1993 for Millstone Unit 1.W/

ML20057F933
Person / Time
Site:	Millstone
Issue date:	09/30/1993
From:	Newburgh G, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-93-809, NUDOCS 9310190362
Download: ML20057F933 (5)

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October 12, 1993 MP-93-809 e

Re:

10CFR50.71(a)

U.S. Nuclear Regulatory Commission Document Control Desk f

Washington, D. C. 20555

Reference:

Facility Operating License No. 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, i

NORTHEAST NUCLEAR ENERGY COMPANY k

C4 W tephen'E.

cace e

Vice President - Millstone Station SES/GSN cc: T. T. Martin, Region I Administrator J. W. Andersen, NRC Project Manager, Millstone Unit No. 1 P. D. Swetland, Senior Resident Inspector, Millstone Unit Nos. 1, 2 & 3 I

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AVERAGE DAILY UNIT POWER LEVEL-DOCKET NO.

50-245 I

UNIT:

Millstone Unit 1 DATE: -931007 i

COMPLETED BY:

G. Newburgh i

TELEPHONE:

(203) 447-1791 EXT:

4400 I

MONTH:

SEPTEMBER 1993 j

DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 484 17 629 2

630 18 629 i

3 628 19 630 4

628 20 630 5

627 21 631 6

627 22 624 7

627 23 633 8

622 24 633 9

627 25 632 z

10 627 26 631

?

11 627 27 629 j

12 627 28 629 l

I 13 625 29 624 14 626 30 635 15 625 31 N/A y

16 627

. l INSTRUCTIONS i

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

Compute to the nearest whole megawatt.

1 1

/

- ~

=

+.

OPERATING DATA REPORT I

S UNIT NAME Millstone Unit 1 DATE 931007 COMPLETED BY G. Newburgh j

TELEPHONE (203) 447-1791 EXT-4400 6

OPERATING STATUS 1.

Docket Number:

50-245 Notes:

2.

Reporting Period:

September 1993 3.

Utility

Contact:

G.

Newburgh l

4.

Licensed Thermal Power (MWt):

2011 5.

Nameplate Rating (Gross MWe):

662 6.

Design. Electrical Rating (Net MWe):

660

'7.

Maximum Dependable Capacity (Gross MWe):

684 8.

Maximum Dependable Capacity (Net MWe):

654 9.

If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, i

Give Reasons:

N/A

10. Power Level To Which Restricted, If any (Net MWe):

N/A 111. Reasons For Restrictions, If Any:

14/A i

This Month Yr.-To-Date Cumulative

12. Hours In Reporting Period 720 6551 200207

13. Number Of Hours Reactor Was Critical 720 6453.5 155922.9 l

14 Reactor Reserve Shutdown llours 0

0 3283.3 i

15. Ilours Generator On-Line

-720 6438.7 152214.5

16. Unit Reserve Shutdown Hours 0

0 93.7 j

.17. Gross Thermal Energy Generated (MWH) 1433709 12757974 286624847.0 l

18. Gross Electrical Energy Generated (MWH) 469433 4219934__

96630933.0 1

-19. Net Electrical Energy Generated (MWH) 448854 4036132,

92189043.0 l

20. Unit Service Factor 100 98.3 76.0

21. Unit Availability Factc.-

100 98.3 76.1

22. Unit Capacity Factor (Using MDC Net) 95.3 94.2 70.4 f

23. Unit Capacity Factor (Using DER Net) 94.5 93.;

69.8

'24. Unit Forced Outage Rate 0

1 J, N/A 12.1 l

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

Refuelinr Outar_e. Janua ry 1994. 71 day duration.

t

.26. If Unit Shutdown At Enf Of Report Period, Estimated Date of Startup:

N/A 27.

Units In Test Status (Prior to Commercial Operation):

Achieved l

Forecast' INITIAL CRITICALITY N/A N/A'

]

INITIAL ELECTRICITY N/A N/A J

COMMERCIAL OPERATION N/A-N/A 3

m

J REFUELING INFORMATION REOUEST l

1.

Name of facility:

Millstone 1 i

2.

Scheduled date for next refueling shutdown:

January 1994 f

3.

Scheduled date for restart following refueling:

March 1994 i

?

4.

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

No Technical Specification chances have been identified as of the time of this report.

5.

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

N/A i

J 6.

Important licensing considerations associated with refueling, e.g.,

l new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

4 188 GE10 Fuel Assemblies i

.i 7.

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

{

fuel storage pool:

In Core:

(a) 580 In SFP:

(b) 2116 (Unconsolidated) i l

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:

Present Capacity: Maxiraum 3229 fuel assembiv locations.

9.

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

1997. Scent Fuel Pool Full, Core Off Load capacity is reached.

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DOCKET Noi 50-245 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT RAME Millstone 1 DATE 931007-COMPLETED BY G F th TELEPHONE (203;

-1791:

REPORT MONTH SEPTEMBER 1993

. EXT.

4400 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 193-09 930901 S

0 H

5 N/A N/A N/A Power reduction to obtaiti condenser measurements.

A 2

3 j.

F: Forced Reason:

Method "IEEE Standard 805-1984, S: Scheduled A-Equipment Failure (Explain) 1-Manual

" Recommended PracticesJfor B-Maintenance or Test' 2-Manual Scram System Identification in.

C-Refueling

.3-Automatic Scram Nuclear Power Plants and D-Regulatory Restr:ction 4-Continued from Related Facilities" E-Operator Training & License Examination Previous month F-Administrative 5-Power Reduction SIEEE Standard-803A-1983

.C-Operational Error (Explain)

(Duration -0)

" Recommended Practice for

~

H-Other (E:: plain) Other (Explain)

Unique identification in.

Power Plants and Related Facilities - Component Function Identifiers" i

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