ML20044C179

Monthly Operating Rept for Feb 1993 for Haddam Neck Plant.W/

ML20044C179
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	02/28/1993
From:	Bigalbal M, Emmons K, Stetz J CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9303180281
Download: ML20044C179 (11)

Text

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ONNECTICUT YANKEE AT O M IC POWER COMPANY HADDAM NECK PLANT 3S2 INJUN HOLLOW ROAD e EAST HAMPTON, CT 06424-3099 March 15,1993 Re: Technical Specification 6.9.1.8 Docket No. 50-213 U. S. Nuclear Regulatory Commission Document ContmlDesk Washington, D. C. 20555

Dear Sir:

In accordance with reporting requirements of Technical Specification 6.9.1.8, the Connect' cut Yankee EnMam Neck Plant Monthly Operating Report 93-03 covering operations for the period February 1,1993 to February 28,1993 is hereby forwarded.

Very truly yours, k

John P. Stetz Vice President UnMam Neck Station JPS/va oc:

(1)

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

William J. Raymond Sr. Resident Inspector CanMeut Yankee 1 gWLf-'"

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9303180281 930328 4

PDR ADOCK 05000213 R

PDR

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l Connecticut Yankee Atomic Power Company Haddam Neck Plant Haddam, Connecticut i

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1 Monthly Operating Report No. 93 1 For The Month of February, 1993 l..

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l Plant Operations Summarv i

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h The following is the Summary of Plant Operations for February 1993:

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The plant was operated at 100% power for the month of February.

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AVERAGE DAILY UNIT POWER LEVEL t

Docket No: 50-213 Unit: Connecticut Yankee Haddam Neck Date: March 15,1992 Completed By: K. W. Emmons/M. Bigalbal Month:

Febrnarv. 1993 TeIep h o ne: (203) 267-3654 l

M AVER AGE POWER I EVEL M

AVER AGE POWER I EVEL -

(MWe-Net)

(MWe-Net) 1 ill 17 ill l

2 121 18 ill 3

123 19 ill l

4 112 20 ill 5

112 21 ill j

6 ili 22 ill i

7 ill 23 121 8

112 24 ill 9

112 25 ill 10 121 26 ill 11 121 27 ill 12 ill 28 ill i

13 ill 29 NA 14 ill 30 NA 15 ill 31 NA 16 ill Ii

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NRC OPERATING STATUS REPORT l

Haddam Neck

1. Docket: 50-213

2. Reporting Period: 02/93 Outage + On-line Hours:

0.0 + 672.0 = 672.0 l

3. Utility

Contact:

M. P. Bain (203) 267-3635

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 (Cross MWe): 586.9

8. Maximum 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: h/A MONTH YEAR-TO-DATE CUMULATIVE

12. Report period hours:

672.0 1,416.0 220,584.0

13. Hours reactor critical:

672.0 1,416.0 176,222.4 1

14. Reactor reserve shutdown hours:

0.0 0.0 1,285.0 l

15. Hours generator on-line:

672.0 1,416.0 169,703.2 l

16. Unit reserve shutdown hours:

0.0 0.0 398.0

17. Gross thermal energy generated (MWtH):

1,217,936.0 2,565,623.0 293,478,395.0 *

18. Gross electrical energy generated (MWeH):

406,732.0 858,059.0 96,180,641.0 *

19. Net electrical energy generated (MWeH):

388,379.5 819,474.5 91,380,676.1

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20. Unit service f actor:

100.0 100.0 76.9

21. Unit availability factor:

100.0 100.0 77.1

22. Unit capacity factor using MDC net:

103.2 103.3 75.2

23. Unit capacity f actor using DER net:

99.3 99.4 71.2 l

24. Unit forced outage rate:

0.0 0.0 5.6

25. Forced outage hours:

0.0 0.0 10,078.5

26. Shutdowns scheduled over next 6 months (type,date, duration): Renseling 5/15/93-7/26/93

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

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

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CONNECTICUT YANKEE REACFOR COOLWT DATA February 1993 COND CL DO B

Li GAM-ACT I-131 ACT DATE TIME pH pmhos/cm ppm ppb ppm ppm pCi/mL PCi/mL I-RA110 2-1-93 0806 6.91 13.32

<0.050

<5 286

.954 404 1.99E4)3

.72 2-2-93 0739 6.83 8.65

<0.050 285

.787

.375 1.98E4)3

.74 2-3-93 0751 6.87 11.34

<0.050

<5 284

.822

.396 1.93E-03

.75 2 4-93 0818 6.87 10.01

<0.050 276

.894

.358 1.94E4)3

.74 2-5-93 0805 6.88 10.56

<0.050

<5 280

.811

.376 1.76E-03

.68 2-6-93 0833 6.88 11.12

<0.050 276

.811

.354 1.78E-03

.74 2-7-93 0820 6.89 9.59

<0.050 274

.826

.392 1.97E-03

.71 2-8-93 0806 6.89 12.78

<0.050

<5 270

.878

.422 1.98E-03

.72 2-9-93 0802 6.86 10.94

<0.050 265

.759

.384 1.93E-03

.71 2-10-93 0754 6.87 11.00

<0.050

<5 263

.811

.379 1.90E-03

.71 2-11-93 0822 6.90 11.63

<0.050 260

.854

.387 2.03E-03

.74 2-12-93 0749 6.90 11.73

<0.050

<5 256

.807

.381 1.95E-03

.73 2-13-93 0838 6.89 11.56

<0.050 252

.822

.374 1.98E-03

.74 2-14-93 0840 6.92 11.96

<0.050 249

.866

.424 2.10E-03

.77 2-15-93 0650 6.91 12.38

<0.050

<5 247

.822

.391 1.81E-03

.69 2-16-93 0750 6.95 11.43

<0.050 245

.771

.396 1.75E-03

.67 2-17-93 0745 6.88 11 14

<0.050

<5 240

.755

.413 1.88E-03

.70 2-18-93 0755 6.90 11.13

<0.050 236

.811

.3 M 1.85E-03

.75 2-19-93 0812 6.87 10.46

<0.050

<5 234

.719

.416 1.86E-03

.70 2-20-93 0830 6.88 11.03

<0.050 230

.703

.397 1.88E-03

.71 2-21-93 0825 6.93 11.42

<0.050 227

.783

.412 1.84E-03

.69 2-22-93 0750 6.95 12.31

<0.050

<5 223 '.d74

.325 1.81E-03

.69 j

2-23-93 0751 6.86 11.80

<0.050 220

.560 418 2.11E-03

.77 2-24-93 0756 6.95 12.57

<0.050

<5 217

.907

.425 1.97E413

.70 2-25-93 0837 6.92 12.10

<0.050 217

.894 424 1.93E-03

.69 2-26-93 0757 6.96 10.40

<0.050

<5 211

.811

.430 1.94E-03

.69 2-27-93 0828 6.95 10.38

<0.050 210

.811

.415 1.97E-03

.73 2-28-93 0820 6.99 11.11

<0.050 207

.900 410 1.92E-03

.71 Tritium Q11d I

DA7E H-3 pct /mD DA7E mg/L 2-3-93 2.46 2-1-93

<1 2-10-93 2.55 2-8-93

<1 2-17 93 2.59 2-15-93

<1 2-24-93 2 40 2-22-93 cl l

l cc/ke Flashed Gas l

DATE ggEg l

2-4-93 31.10 l

2-11-93 26.54 2-18-93 26.05 2-25-93 27.79 l

l CONNECTICUT YANKEE l

REACIOR COOLANTDATA February,1993 i

REACTOR COOLANT ANALYSIS MINUdUM AVERAGE MAXIMUM pH @ 25" C 6.83 6.90 6.99 CONDUCTIV'7"Y (umhos/cm) 8.65 10.95 13.32 Chlorides (ppm)

<0.050

<0.050

<0.050 Dissolved Oxygen (ppb)

<5

<5

<5 Baron (ppm) 207 248 286 Lithium (ppm)

.560

.818

.954 l

Total Act. (uCi/mn 0.325 0.395 0.430 1-Ratio 0.67 0.72 0.77 I 131 (pCi/ml) 1.75E-03 1.92E-03 2.11E-03 Crud (mg/D

<1

<1

<1 TRITIUM (uCi/mL) 2.40 2.50 2.59 Hvdrocen (cc/Kc) 26.05 27.87 31.10 Aerated Liquid Waste Processed (Gallons): 7.72E+04 Waste Liquid Processed through Baron Recovery (Gallons): 1.30E+04 Average Primary leak Rate (Gallons per Minute): 0.392 Primay to Secondary leak Rate (Gallons per Minute): 6.77E-03 I

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UNIT SHUTDOWNS AND POWER REDUCTION Docket No: 50-213 Unit Name: Connecticut Yankee Date:

March 15,1993 Report Month:

February 1993 Completed By:

K. W. Emmons TeIephone: (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 ar po-ver re luction in February 1993

IJJf, REASON METHOD SYSTEM & 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 (NUREO-0161)

E Operator Training 5 Reduced Load F Administrative 9 Other 0 Operator Error H Other (Explain) s

MAINTENANCE DEPARTMENT Report Month February 1993 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 There were no rc portable ite us for the Maintenance Dep trtment for February 1993 4

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I&C DEPARTMENT Report Month: February 1993 System MALFUNCHON Effect on Corrective Action Special Precautions Taken To Provide or Safe Taken to Prevent For Reactor Safety During Repair Component Cause Result Operation Repetition l

There were no re mrtable iter is for the 1 &C Department for the mont i of February 1993 4

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Refueling Information Request l

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Name of facihty HailmaNed 2.

telwhded date for next refueling shuulown.

May 15,1993 3.

Schaailad dase for restart following refuehng.

I July 26,1993 l

4.

(a)

Will M-- or r-"- *iaa of operanon thereafter require a tarhans specificanon change or other tuvene amesuto-r?

P Yes (b)

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

Technical Specificumn change to remove three loop specificarums and failed fuel rod limit

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(c)

If answa is no, has the reload fuel desgn and core configuranon been reviewed by your Plant Safety Review Comminee to determine whether any unreviewed safety quesnons are associated with the cose acioed?

Wa (d)

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

Wa 5.

Sctwinled date(s) for submining proposed hec==ng action and supparung infonnanon.

March 1993 6.

Important hcensmg enneiderations===aciased with refuehng, e.g., new or different fuel design or suppher.

dc4 design or performance analysis manhade significant changes in fuel design, new operanng Pr'"h'es.

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7.

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

(a) 157 (b) 757 i

8.

'the prenant l===ad spent fuel pool storage capacity and the sire of any iracase in heensed storage capacity that has been requested or is planned,in number of fuel assemblics.

l 1168 9.

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

1998 i

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