ML20029E600

Monthly Operating Rept 94-04 for Apr 1994 for Haddam Neck Plant

ML20029E600
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	04/30/1994
From:	Bigalbal M, Emmons K, Stetz J CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9405190153
Download: ML20029E600 (7)

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CONNECTICUT YANKEE AT O M IC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON, CT 06424-3099 May 15,1994 Re: Technical Specification 6.9.1.8 Docket No. 50-213 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Dear Sir:

In accordance with reporting requirements of Technical Specification 6.9.1.8, the Connecticut Yankee Iladdam Neck Plant Monthly Operating Report 94-034 covering operations for the period April 1,1994 to April 30,1994 is hereby forwarded.

Very truly yours, df ks

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Jo n P.f tetz Vice President IIaddam Neck Station JPS/va i

cc:

(1)

Regional Administrator, Region I l

U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 (2)

William J. Raymond Sr. Resident Inspector Connecticut Yankee N

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l 9405190153 940430 PDR ADOCK 05000213 l

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i Connecticut Yankee Atbmic Power Company J

IIaddam Neck Plant IIaddam, Connecticut i

Monthly Operating Report No. 94-04 For The Month of April 1994

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w Plant Operations Summarv - April 1994 The following-is a Summary of Plant Operations for April 1994.

On April 1st, at 0000 hour0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant was in Mode 1 (Power Operation) at 100% load On April 7th, at 0724 hours0.00838 days <br />0.201 hours <br />0.0012 weeks <br />2.75482e-4 months <br />, the Connecticut Yankee Atomic Power Company attained 100 llillion Kilowatt hours of power operation.

On April lith at 0650 hours0.00752 days <br />0.181 hours <br />0.00107 weeks <br />2.47325e-4 months <br /> a load reduction was initiated to test the Steam Generator Pressure Operated Relief Pilot Valves.

At 0817 hours0.00946 days <br />0.227 hours <br />0.00135 weeks <br />3.108685e-4 months <br />, power was at 90% and the test started.

At 1237 hours0.0143 days <br />0.344 hours <br />0.00205 weeks <br />4.706785e-4 months <br />, the test was successfully concluded.

At 1311 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.988355e-4 months <br />, a load increase was commenced.

At 1411 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.368855e-4 months <br />, power was at 100% load.

On April 21st, at 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> a load reduction was initiated to test the Steam Generator Pressure Operated Relief Pilot Valves.

At 0657 -hours, power was successfully concluded.

At 1235 hours0.0143 days <br />0.343 hours <br />0.00204 weeks <br />4.699175e-4 months <br />, the plant commenced power ascension.

At 1354 hours0.0157 days <br />0.376 hours <br />0.00224 weeks <br />5.15197e-4 months <br />, the plant was at 100% power.

The plant continued to operate at 100% for tlie remainder of the month.

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AVER AGE DAILY UNIT POWER LEVEL Docket No: 50-213 Unit: Connecticut Yankee IIaddam Neck Date: May 15,1994 Completed ny: K. Emmons/M. Bigalbal Month: April 1994 Telephone: (203) 267-3654 M

AVERAGE POWER LEVEL DAY AVER AGE POWER LEVEL (MWe-Net)

(MWe-Net) 1 5R 17 585 2

183 18 181 3

183 19 131 4

584 20 585 5

183 21 173 6

585 22 584 7

585 23 584 8

585 24 584 9

584 25 584 10 184 26 183 11 568 27 583 I2 183 28 18_2 13 585 29 582 14 586 30 582 15 585 16 186

UNIT SHUTDOWNS AND POWER REDUCTION Docket No:

50-213 Unit Name: Connecticut Yankee Date:

May 15,1994 Report Month:

A ntil 1994 Completed By: Kathy Emmons Te'ephone: (203) 267-3654 No.

Date Type Duration Reason Method of LER System Component (Hours)

Shutting Report Code Code Cause and Corrective Action to Prevent Recurrence down Reactor I

There were no reportable unit shutdowns or powe reductior s for the month of April i

l TYPE REASON METIIOD SYSTEM COMPONENT l

F Forced A Equipment Failure 1 Manual IEEE Standard IEEE Standard S Scheduled B Maintenance or Test 2 Manual Scram 805-1984 and/or 803 A-1983 and/or C Refueling 3 Automatic Scram NUREG-0161 Exhibit F NUREG-0161 Exhibit H D Regulatory Restriction 4 Continued E Operator Training 5 Reduced Load F Administrative 9 Other l

G Operator Error H Other (Explain) l l

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NRC OPERATING STATUS REPORT l

1 Haddam Neck

1. Docket: 50 213

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?. Reporting Period: 04/94 Outage + On-line Hours:

0.0 + 719.0 = 719.0

3. Utility

Contact:

W.M. Herwig (203) 267-3198 4 Licensed Thermal Power (MWt): 1825

5. Nameplate Rating (Gross MWe): 667 x 0.9 = 600.3

6. Design Electrical Rating (Net MWe): 582

7. Maximum Dependable Capacity (0ross MWe): 586.9 8, Maximtsn Dependable Capacity (Net MWe): 560.1

9. If changes occur above since last report, reasons are: NONE

10. Power level to which restricted, if any (Net MWe): N/A

11. Reasons for restriction, if any: N/A MONTH YEAR-TO-DATE CUMULATIVE

12. Report period hours:

719.0 2,879.0 230,807.0

13. Hours reactor critical 719.0 1,811.7 183,764.0

14. Reactor reserve shutdown hours:

0.0 (r. 0 1,285.0

15. Hours generatw on-line:

719.0 1, 795.6 176,998.4

16. Unit reserve shutdown hours:

0.0 C.ti 398.0

17. Gross thermal energy generated (MWtH):

1,308,888.0 3,232,868.(-

306,053,136.0

• 18, Gross electrical energy generated (MWeH):

438,666.0 1,083,873.0 100,345,792.0 *

19. Net electrical energy generated (MWeH):

419,254.9 1,029,144.6 95,330,418.7 *

20. Unit service factor 100.0 62.4 76.7

21. Unit availability factor:

100.0 62.4 76.9

22. Unit capacity factor using MDC net:

104.1 63.8 74.9

23. Unit capacity factor using DER net:

100.2 61.4 71.0

24. Unit forced outage rate:

0.0 37.6 6.0

25. forc W outage hours:

0.0 1,083.5 11,318.7

26. Shutdowns scheduled over next 6 nonths (type,date, duration): NONE

27. If currently shutdown, estimated startup date: N/A 1

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• Cumulative values from the first criticality (07/24/67). (The remaining cumulative values are from the first date of coninercial operation, 01/01/68).

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l Re fueling In form ation Reauest 1.

Name of facility Ilacklam Neck 2.

Scheduled date for neat refueling shutdown.

January 7,1995 3.

Scheduled date for restart following refueling.

l February 21,1995 4.

(a)

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

Yes (b)

If answer is yes, what,in general, will these be?

. changes to linear heat generation rate uncertainties

• necessary changes to the Design Features, Section 5 to support new fuel design

. changes to support storage of new and spent fuel with higher enrichments (c)

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Com.mittee to determine whether any unreviewed safety questions are associated with the core rekni?

n/a (d)

If no such revicw has taken place, when is it scheduled?

n/a 5,

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

May 1994 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or strpplict, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedurcS.

Change in fuel vendor from Il&W Fuel Co. to Westinghouse Electric Corp., and change in fuct assembly.

design.

7.

The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool.

(a) 157 (b) 809 8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has teen requested or is planned,in number of fuel assemblies.

IIfd 9.

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

1998

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