ML20127E571

Monthly Operating Rept for Dec 1992 for HNP

ML20127E571
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	12/31/1992
From:	Bigalbal M, Emmons K, Stetz J CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9301190378
Download: ML20127E571 (10)

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ONNECTICUT YANKEE AT O M IC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON. CT 06424-3099 January 15,1993 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 rr quirements of Technical Specification 6.9.1.8, the Connecticut Yankee Haddarr Neck Plant Monthly Operating Report 93-01 covering operations for the period Daember 1,1992 to December 31,1992 is hereby forwarded.

Very truly yours, John P. Stetz Vice President Haddam Neck Station JPS/va cc:

(1)

Regional Administrator, Region 1 U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 (2)

William Raymond Sr. Resident Inspector Connecticut Yankee 19014u I

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Connecticut Yankee Atomic Power Company lladdam Neck Plant lladdam, Connecticut Monthly Operating Report No. 93-01 For The Month of December 1992 i

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Plant Operations Summarv -December 1992 The following is the Summary of Plant Operations for December 1992:

1he plant was operated at 100% power for the month of December.

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MAINTENANCE DEPARTMENT Report Month December 1992 System MALFUNCTION Effect on Corrective Action Special Precautions Taken To Provide or Safe Taken to Prevent For Reactor Safety During Repair Component Cause Result Operation Repetition

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There were no re portable ite: ns for the Maintenance Department for December 1992

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I&C DEPARTMENT u

Report Month: Decerrber 1992 System

. MALFUNCTION Effect on Corrective Action Special Precautions Taken To-Provide or Safe Taken to Prevent For Reactor Safety During Repair.

Component

- Cause Result Operation Repetition j-f i

There were no reportable iterns for the I&C Department for the month of December 1992.

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1 CONNECrlCUT YANKEE REACIDR COOLANTDATA MONTI1: December 1992 REAC10R COOLANT ANALYSIS MiNihiUht AVERAGE htAXthiUht pit G 25' C 6.39 6 69 6.76 PONDUCTIVITY (itmhos/cm) 11.40 13.76 15.R6 Chlorides (ppm)

<0.050 c0.050

<0.050 Dissolveel Oxygen (ppb)

<5

<5

<5 Boron (ppm) 385 431 475

_ Lithium (ppm) 0R90 1.027 1.232 6

Total Act. 4tcilml) 2 611L01 3.65E-01 4.12E.01 JRatio OM 0.71 0.77 1131 4tCi/ml) 1.6RE-03 1.R3E 03 2.02E 03 Crud (mrfl)

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<1 1.2 1RITlUh1(HCi/mL) 3.58 4.25 4.95 11ydrogen (cc/KO 24.91 26.59 28.07 Aerated Liquid Waste Processed (Gallons): 1.29E+05 Waste Liquid Processed through Boron Recovery (Gallons): 4.60E+04 Average Primary leak Rate (Gallons per Minute): 0.347 Primary to Secondary leak Rate (Gallons per Minute): 4.22E 03

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hRC OPERAftkG STATUS REPORT 1

Haddaft beck i

1. Docket 50 213 j

2. Reporting Period: 12/92 Outage + on line Hours:

0.0 + 744.0 e 744.0 i

3. Utility

Contact:

M. P. Bein (203) 267-3635 j

4. Licensed thermat Power (MWt): 1825 1

5. Nareplate Rating (Gross MWe): 667 a 0.9 600.3

6. Design Electrical Rating (het MWe): 582

7. Maxinsa Ocoendable Capacity (Gross MWe): 586.9 a

8. Maalmum Dependable Capacity (Net MWe): $60.1 j

9. If changes occur above since test report, reasons are NONE 1

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

11. Reasons for restriction, if any: N/A i

MONTH TEAR 10 DATE CUMULAflVE

12. Report period hours:

744.0 8,784.0 219,168.0 f

13. Hours ieactor critical

?44.0 7,030 6 174,806.4 i

14. Reactor reserve shutdown hours:

0.0 0.0 1,285.0

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15. Hours jenerator on lines 744.0 6,955.3 168,287.2

16. Unit reserve shutdown hours:

0.0 0.0 398.0 i

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17. Gross thermat energy generated (MWtH):

1,348,943.0 12,369,852.0 290,912,772.0

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18. Cross electrical energy generated (MWeH):

453,143.0 4,086,458.D 95,322,582.0

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19. het electrical energy generated (MWeH):

432,822.6 3,880,831.0 90,561,201.6 *

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20. Unit service factor:

100.0 79.2 76.8

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21. Unit evalIabitity factor 100.0 79.2 77.0 I

22. Unlt capac1ty foctor using MDC net:

103.9 78.9 75.0 l

23. Unit capac1ty foctor using OfR neti 100.0 75.9 71.0

24. Unit forced outage rate:

0.0 0.6 5.7 l

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25. Forced outage hours:

0.0 39.5 10,078.5

26. Shutdowns schedated over next 6 months (type,date, duration): Refueting 5/1/93 7/5/93 1

27. If currently shutdown, estimated startup dates N/A l

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+ Cunulative values from the first criticality (07/24/67). (The remaining cumulative values are from the first date of connercial operation, 01/01/68),

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AVERAGE DAILY UNIT POWER LEVEL Docket No: 50 213 Unit: Connecticut Yankee lladdam Neck Date: January 15, 1993 Completed Hy: K. W. Emmons/M. Iligalbal Month:

December Telephone: (203) 267-3654/3650 llAX AVERAGE POWER LEVEL llAX AVERAGE POWER LEVEL (MWe Net)

(MWe-Net) 1 181 17 51 2 2

181 18 181 3

18l 19 181 4

183 20 182 5

in 21

$32 6

132 22 181 7

181 23 181 8

in 24 181 9

132 25 582 10 181 26 182 11 181 27 182 12 182 28 182 13 5_S2 29 182 14 181 30 132 15 181 3 1-182 16 582

UNIT SHUTDOWNS AND POWER REDUCTION Docket No: 50-213 Unit Name: Connecticut Yankee Date: January 15, 1993 Report Month:

December 1992 Cornpleted By:

K. W. Emmons TeIephonc: (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 There were no reportable shutdowns 3r power reduction in December 1992 IXff REASON METHOD SYSTFM & COMPONENT F Forced A Equipment Failure 1 Manual Exhibit F & H - Instructions for Preparation of S Scheduled B Maintenance or Test 2 Manual Scram Data Entry Sheets C Refueling 3 Automatic Scram Licensee Event Report (LER)

D Regulatory Restriction 4 Continued File (NUREG-0161)

E Operator Training 5 Reduced Load F Administradve 9 Other G Operator Error H Other (Explain)

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Refueling Infmmation Regiln1 1.

Name of facility a

ILdbm Neck 2.

Scleduled date for next refueling shut (kiwn.

i May 1,1993 1

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Scheduled date for restart following refueling.

l July 5,1993 4.

(a)

Will refueling or resumption of operation therrafter require a technical specification change or eller license amendment?

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Yes (b)

If answer is yes, w hat, in general, will these be?

Technical Specification change to remove three kiop specifications and failed fuel rod limit specification.

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If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to detennine wirther any unreviewed safety questions are associated with tie core mkid N*

(d)

If no such review has taken plxe, when is it scheduled?

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

4 March 1993 6.

Important licensing considerations associated with refueling, e.g., new or different fuct design or supplier, unreviewed design or perfornmnce analysis methods, significant changes in fuel design, new operating procedures, n/a 7.

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

(a) 157 (b) 757 8.

he present licensed spent fuel pool storage caprity and the size of any increase in licensed storage capacity that has been requested or is planned,in numter of fuel assemblics.

1168 9.

he projected date of the last refueling that can te discharged to the spent fuel pool assuming tl e present licensed capacity.

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