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Monthly Operating Rept for Sept 1993 for Connecticut Yankee Haddam Neck Plant
	ML20057G056
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/30/1993
From:	Bigalbal M, Emmons K, Stetz J; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9310200129
	Download: ML20057G056 (10)
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ONNECTICUT YANKEE-ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON. CT OG424-3099 October 15,1993 Re: Technical Specification 6.9.1.8 i

Docket No. 50-213 I

i 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 IInddam Neck Plant Monthly Operating Report 93-10 covering operations for the period September 1,1993 to September 30,1993 is hereby forwarded.

Very truly yours, h7 h,<

4 John P. 'tetz 1

Vice President Iladdam Neck Station JPS/va cc:

(1)

Regional Administrator, Region 1 U. S. Nuclear Regulatory Commission 475 Allendale Road l

King of Prussia, PA 19406 (2)

William J. Raymond Cr. Resident Inspector Connecticut Yankee E(I(1R"~

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9310200129 930930 PDR ADOCK 05000213

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Connecticut Yankee Atomic Power Company IIaddam Neck Plant i

IIaddam, Connecticut i

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Monthly Operating Report No. 93-10 For The Month of l

September 1993 J

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Plant Operations Summary - September 1993 The following is the Summary of Plant Operations for September 1993.

On September 1st at 0000 hours0 days 0 hours 0 weeks 0 months , the plant was in Mode 1, Power Operation at 100% load.

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On Septernber 27th at 1330 hours0.0154 days 0.369 hours 0.0022 weeks 5.06065e-4 months , a load reduction was commenced due to a concern on the position of the containment isolation valve SS-SOV-151D.

At 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months , containment isolation valve SS-SOV-151C was verified to be closed.

At 1407 hours0.0163 days 0.391 hours 0.00233 weeks 5.353635e-4 months , the load reduction was stopped at 87% load.

It was determined that containment integrity was intact by shutting valve SS-SOV-151C. At 1520 hours0.0176 days 0.422 hours 0.00251 weeks 5.7836e-4 months , power breakers for SS-SOV-151 A, B, C, and D were placed in the open position.

At 1630 hours0.0189 days 0.453 hours 0.0027 weeks 6.20215e-4 months , a power ascension was started.

At 1820 hours0.0211 days 0.506 hours 0.00301 weeks 6.9251e-4 months , power reached 100% load.

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

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l NRC DPERAflNG STATUS REPORT i

Haddam Neck

1. Docket: 50 213

2. keporting Period: 09/93 Outage + Dn-Line Hours:

0.0 + 720.0 = 720.0

3. Utility

Contact:

M. P. Bein (203) 267-3635

4. Licensed Thernet Power (MWt): 1825

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

6. Design Electrical Rating (Net MWe): 582 s

7. Maximum Dependable capacity (Gross MWe): 586.9

8. Maximum Dependable capacity (Net MWe): 560.1

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

10. Power levet 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:

720.0 6,551.0 225,719.0

13. Hours reactor critical:

720.0 4,985.2 179,791.6

14. Reactor reserve shutdown hours:

0.0 0.0 1,285.0 t

15. Hours generator on-line:

720.0 4,829.3 173,116.4

16. Unit reserve shutdown hours:

0.0 0.0 398.0 1

1,294,258.0 8,450,438.0 299,363,210.0

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17. Gross thernet energy generated

18. Gross electrical energy generated (MWeH):

420,982.0 2,781,620.0 98,104,202.0 *

19. Net electrical energy generated (MWeH):

401,563.1 2,639,039.2 93,200,240.8

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20. Unit service facto 100.0 73.7 76.7 t

21. Unit availability factor:

100.0 73.7 76.9

22. Unit capacity f actor using MDC net:

99.6 71.9 74.9 1

23. Unit capacity f actor using DER net:

95.8 69.2 71.0

24. Unit forced outage rate:

0.0 2.6 5.6

25. Forced outage hours:

0.0 126.7 10,205.2

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

27. If currently shutdown, estinated startup date: N/A Cumulative values fren the first criticality (07/24/67). (The remaining cumulative values are from the first date of f

commercial operation, b'/01/68).

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l AVER AGE DAILY UNIT POWER LEVEL Docket No: 50-213 Unit: Connecticut Yankee IIaddam Neck Date: October 15, 1993 Completed By: M. Bigalbal/K. Emmons Month: September Telephone: (203) 267-3654 11AX AVER AGE POWER LEVEL lbil AVER AGE POWER LEVEL (MWe-Net)

(MWe-Net) 1 542 17 561 2

544 18 5_61 3

545 19 5f62 4

545 20 564 5

145 21 5_62 6

141 22 15.2 7

546 23 269 8

548 24 569 9

550 25 570 10 551 26 12D 11 554 27 558 12 116 28 163 13 558 29 569 14 512 30 570 15 115 31 16 ill

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

October 15. 1993 Report Month:

Scotember 1993 Completed By:

M. E. Bigalbal Telephone: (203) 267-3141 No.

Date Type Duration R ea.,n Method of LER System Component (Hours)

Shutting Report Code Code Cause and Corrective Action to Prevent Recurrence down Reactor There v ere no icportable shutdowns or power cductions in September 1993 i

IXfE REASON METHOD SYSTEM COMPONENT l

F Forced A Equipment Failure 1 Mamal IEEE Standard IEEE Standard l

$ Scheduled B Maintenance or Test 2 Manual Scram 805-1984 and/or 803 A-1983 and/or l

C Refueling 3 Automatic Scram NUREO-0161 Exhibit F NUREG-0161 Exhibit H l

D Regulatory Restriction 4 Continued i

E Operator Training 5 Reduced Load F Administrative 9 Other O Operator Error H Other (Explain) i 6

l CONNECTICUT YANKEE REACTOR COOLANT DATA SEPTEMBER 1993 i

Reactor Coolant Analysis minimum average maximum pli G 25 degrees C 6.2 6.3 6.4 Conductivity (uS/cm) 16.6 20.4 23.4 Chlorides (ppb) 12.8 15.8 20.5 Dissolved Oxygen (ppb)

<5.0

<5.0 Boron (ppm) 1147 1187 1253 Lithium (ppb) 1758 2018 2237 Total Act. (uCi/ml) 3.35 E-01 513E-01 6.95E-01 I-131/133 ratio 7.90E-01 6.68E-01 7.90E-01 1-131 (uCi/ml) 1.15E-03 1.40E-03 1.54E-03 Cmd (mg/l)

<10 1.2 1.7 Tritium (uCi/ml) 5.96E-01 9.91 E-01 1.47E+00 liydrogen (cc/kg) 25.2 29 4 34.8 Aerated liquid waste processed (gallons).

445E40,4 Waste liquid processed through baron recovery (gallons):

0.00E+00 Average primary leak rate (gallons per minute):

2.83 E-01 Primary to secondary leak rate (gallons per minute):

2.02E+01 r

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p I&C DEPARTMENT Report Month - September 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 re portable items for the ; &C Department in September 1993 e

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1 MAINTENANCE DEPARTMENT Report Month September 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 :ns for the Maintenance Department in September 1993 t

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w Refueling In form ation Reauest 1.

Name of facility IMhmNeck 2.

Scheduled date for next refueling shutdown.

November 12,1994 1

3.

Scheduled date for restan following refueling.

January 5,1995 4.

(a)

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

Unknown at this time

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(b)

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

I (c)

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

reluxl?

i n/a (d)

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

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

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.

n/a 7.

~1he number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

(a) 157 (b) 809 i

8.

'Ihe present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity i

that has been requested or is planned,in number of fuel assemblies.

1168 9.

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

i 1993 i

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ML20057G056

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