ML20045B380

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Monthly Operating Rept for May 1993 for Millstone Unit 1.W/
ML20045B380
Person / Time
Site: Millstone 
Issue date: 05/31/1993
From: Newburgh G, Scace S
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-93-466, NUDOCS 9306170261
Download: ML20045B380 (5)


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(203) 665-5000 -

1 June 9, 1993 i

MP-93-466 f

Re:

10CFR50.71(a)

U.S. Nuclear Regulatory Commission Document Control Desk h shington, 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, NORTHEAST NUCLEAR ENERGY COMPANY

/

(~GCC Stephen E. Scace Vice President - Millstone Station SES/CSN i

cc: T. T. Martin, Region 1 Administrator J. W. Andersen, NRC Project Manager, Millstone Unit No. 1 i

P. D. Swetland, Senior Resident Inspector, Millstone Unit Nos. 1,2&3 1

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OPERATING DATA REPORT UNIT NAME Millstone Unit 1 DATE 930608 j

COMPLETED BY G. Newburnh j

TELEPHONE (203) 447-1791 1

EXT 4400 OPERATING STATUS P

1.

Docket Number:

50-245 Notes:

2.

Reporting Period:

May 1993 3.

Utility

Contact:

G.

Newburrh 4

Licensed Thermal Power (MWt):

2011

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5.

Nameplate Rating (Gross MWe):

662 6.

Design Electrical Rating (Net MWe):

660 j

7.

Maximum Dependable Capacity (Gross MWe):

684 1

8.

Maximum Dependable Capacity (Net MWe):

654 l

9.

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

Give Reasons:

1

'I N/A

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

N/A

11. Reasons For Restrictions, If Any:

N/A l

This Month Yr.-To-Date Cumulative

12. Hours In Reporting Period 744 3623 197279
13. Number Of Hours Reactor Was Critical 742.2 3525.5 152994.9
14. Reactor Reserve Shutdown Hours 0

0 3283.3 I

15. Hours Generator On-Line 730.8 3510.7 149286.5

- 16. Unit Reserve Shutdown Hours 0

0 93.7

17. Cross Thermal Energy Generated (MWH) 1424766 6949996 280816869.0
18. Gross Electrical Energy Generated (MWH) 472345 2315079 94726075.0,
19. Net Electrical Energy Generated (MWH) 451611 2214462

-90367373.0

20. Unit Service' Factor 98.2 96.9 75.7-
21. Unit Availability Factor 98.2' 96.9 75.1
22. Unit Capacity Factor (Using MDC Net) 92.8 93.5 70.0
23. Unit Capacity Factor (Using DER Net)

'92.0

'92.6 69.4

24. Unit Forced Outage Rate 1.8 3.1 12.3
25. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

N/A

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

N /A -

27.

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 1

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.i AVERAGE DAILY UNIT POWER LEVEL DOCKE':.

50-245

- DA T '

-Millstone Unit 1 18",

30608 COMPLETED BY:

_.G.. Newburch TELEPHONE:

(203) 447-1791 EXT:

4400 MONTH:

MAY 1993 DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL i

(MWe-Net)

(MUe-Net) 1 133 17 637 t

2 638 18 637 t

3 640 19 627 t

4 640 20 639 5

640 21 639 6

498 22 638 l'

7 638 23 638 8

639 24 637 9

639

'25 637 7

10 639 26 638 11 379 27 632 12 594 28

'631 l

t 13 637 29 637 14 638 30 638 15 637 31 637 l

.i 16 637 i

INSTRUCTIONS

.j

-i 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.

E r

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DOCKET NO.

50 245 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 1 DATE 930608 COMPLETED BY G. Newburnh TELEPHONE (203) 447-1791 REPORT MONTH MAY 1993 EXT.

4400 l

2 No.

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

Shutting Event Code Code Action to Down Reactor)

Report #

Prevent Recurrence 93-02A 930426 F

13.2 A

4 93-003 VB ISV Maintenance was performed on the failed valves and associated penetration.

93-03 930506 F

0 B

5 N/A Cleaned "A" Reactor Recirc. lube oil suction strainer.

93-04 930511 F

0 A

5 N/A Replaced failed resistor on "B" Reactor Recirc.

Motor Generator.

I: Forced Reason:

Method "IEEE Standard 805-1983, 2

3 F

S: Scheduled A-Equipment Failure (Explain) 1-Manual

" Recommended Practices for B Maintenance or Test 2-Manual Scram System Identification in C-Refueling' 3-Automatic Scram Nuclear Power Plants and D-Regulatory Restriction 4-Continued from Related Facilities"

'E-Operator Training & License Examination Previous month S

F-Administrative 5-Power Reduction IEEE Standard 803A-1983 G-Operational Error (Explain)

(Duration -0)

" Recommended Practice for H-Other (Explain) 6-Other (Explain)

Unique identification in Power Plants and Related Facilities - Component Function Identifiers"

o REFUELING INFORMATION REGUEST 1.

Name of facility:

Millstone 1 2.

Scheduled date for next refueling shutdown:

February 1994 3.

Scheduled date for restart following refueling:

April 1994 4.

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

Yes. Technical Soecification Chances Recardina:

(1) Maximum Averace Planar Linear Heat Generatina Rate and 121 Maximum Critical Power Ratio 5.

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

Summer 1993 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:

188 GE10 Fuel Assemblies 7.

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

In Core:

(a) 580 (b) 2116 (Unconsolidated) 8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been request <.d ar is planned, in number of fuel assemblies:

Present capacity: Maximum 3229 fuel assembly locations.

9.

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

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