ML20045B924

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

ML20045B924
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	05/31/1993
From:	Emmons K, Stetz J CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9306210271
Download: ML20045B924 (10)

Text

+t 1

CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON, CT 0G424-3099 June 15,1993 Re: Technical Specification 6.9.1.8 Docket No. 50-213 U. S. Nuclear Regulatory Commission Document ControlDesk Washington, D. C. 20555

Dear Sir:

In accordance with reponing requirements of Technical Specification 6.9.1.8, the Connecticut Yankee Haddam Neck Plant Monthly Operating Report 93-06 covering

. operations for the period May 1,1993 to May 31,1993 is hereby forwarded.

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

(1)

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

William J. Raymond l.

Sr. Resident Inspector Connecticut Yankee 2100 C 3.

1 9306210271 930531 PDR ADDCK 05000213 R

PDR

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

Monthly Operating Report No. 93-06 For The Month of May 1993

m.

' :p

-i q

Plant-Operations Summarv - Mav' 1993 i

The following is the Summary of Plant Operations for' May' 1993.

l The plant was at 100% load _ until-May 14th, at 21N hours, when a' load-reduction was commenced for the.17th refuelir.g and fmaintenance. outage.

On May 15th, at 0135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br />, load was-less than 5%' and the plant entered

. Mode 2 " Start Up".

~At 0138 hours0.0016 days <br />0.0383 hours <br />2.281746e-4 weeks <br />5.2509e-5 months <br />, the turbine generator wasltaken off line.

c;

~ At.1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br />, the reactor breakers.'were opened-and -the plant' entered !

Mode 3 " Hot Standby".-

On May 16th at 0344 hours0.00398 days <br />0.0956 hours <br />5.687831e-4 weeks <br />1.30892e-4 months <br />, Tavg was 'less than 350 degrees and the plant entered Mode 4 " Hot Shutdown".

On May 17th at 0058 hours6.712963e-4 days <br />0.0161 hours <br />9.589947e-5 weeks <br />2.2069e-5 months <br />, Tavg was less than 200 degrees and the plant:-

entered Mode 5 " Cold Shutdown".

On 'May '23rd at 0927 hours0.0107 days <br />0.258 hours <br />0.00153 weeks <br />3.527235e-4 months <br />, the plant entered Mode 6 " Refueling".

t j

The plant was maintained in Mode 6 for the remainder. of the-month' of May.

I y

4 AVERAGE DAILY UNIT-POWER LEVEL Docket No: 50-213 Unit: Connecticut ' Yankee i

Haddam Neck Date: June 15,1993 Completed By: K. Emmons Month: May Telephone: (203) 267-3654

HAY,

~ AVER AGE POWER LEVEL

DAY, AVER AGE POWER IEVEL (MWe-Net)

(MWe-Net) 1 18_Q 17 Q

2 12_8 18 Q

3 124 19 Q

4 ill 20 Q

5 122

.21 Q

6 12_Q 22 R

7 571 23 Q

8 121 24 Q

9 ifLE 25 Q

10 M

26 Q

1 11 166 27-R.

I2 161 28 Q

13_

161 29 Q

14 544 30 Q.

15 a

31 Q

16 Q

L NRC OPERATING STATUS REPORT Haddam Neck

1. Docket: 50-213

2. Reporting Period: 05/93 Outage + on-line Hours: 406.4 + 337.6 = 744.0

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. Desip Electrical Rating (Net MWe): 582

7. Maximum Dependable capacity (Gross MWe): 586.9

8. Maximum Dependatle Capacity (Net MWJ): 560.1

9. If changes occur above sir:ce 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 k

MONTH YEAR-TO-DATE CUMULATIVE

12. Report period hours:

744.0 3,623.0 222,791.0

13. Hours reactor critical:

350.3 3,199.4 178,005.8

14. Reactor reserve shutdown hours:

0.0 0.0 1,285.0 i

15. Hours generator on-line:

337.6 3,182.5 171,469 7

16. Unit reserve shutdown hours:

0.0 0.0

'398.0

17. Grc,ss thermal energy generated (MWtH):

607,331.0 5,676,616.0 296,589,388.0 *

18. Gross electrical energy generated (MWeH)2 200,294.0 1,895,326.0 97,217,908.0 *

19. Net electrical energy generated (MWeH):

189,088.4 1,806,262.5 92,367,464.1 *

20. Unit service factor:

45.4 87.8 77.0

21. Unit availability factor:

45.4 87.8 77.1-

22. Unit capacity factor using MDC net:

45.4 89.0 75.3

23. Unit capacity factor using DER net:

43.7 85.7 71.3

24. Unit forced outage rate:

0.0 1.1 5.6

25. Forced outage hours:

0.0 34.1 10,112.6

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

27. If currently shutdown, estimated startup date: 7/19/93

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

i e

l i

CONNECTICUT YANKEE REACTOR COOLANTDATA MONTH: May 1993 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM pH @ 25' C 4.53 6.27 8.78 CONDUCDVITY (pmhos/cm) 3.30 7.18 10.20 Chlorides (ppm)

<0.050

<0.050

<0.050 Dissolved Oxygen (ppb)

<5

<5

<5 Boron (ppm)

<1 1202 2675 Lithium (ppm) 0.054 0.256 0.461 Total Act. (pCi/ml) 2.10E-03 3.89E-01 1.95E+00 I-Ratio OI4 0.72 0.78 1131 (uCi/ml) 1.98E-04 4.01E-02 6.50E-01 Crud (mg/l)

<1

<1

<1 TRITIUM ( Ci/mL) 4.51E-02 5.00E+00 1.00E+00 1htirogen (cc/Kg) 23.40 23.85 24.30 Aerated Liquid Waste Processed (Gallons): 1.35E+005 Waste Liquid Pmcessed through Boron Recovery (Gallons): 4.95E+004 Average Primary Leak Rate (Gallons per Minute): 5.34E-01 Primary to Secondary Leak Rate (Gallons per Minute): 6.25E-03

UNIT SHUTDOWNS AND POWER REDUCTION t.

Docket No: 50-213 Unit Name: Connecticut Yankee Date: June 15,1993 Report Month:

- May 1993 Completed By:

K. W. Emmons

' Teiepho n e: (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 1

73-03 5/15/93 S

406.36 C

1 n/a AC RCr Core XVII - XVIll Refueling and Maintenance Outage r

L IXZE REASON METHOD SYSTEM COMPONENT F Forced A Equipment Failure

1. Manual IEEE Standard

' IEEE Standard S Scheduled

-B Maintenance or Test 2 Manual Scram

-805-1984 and/or 803A-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 1 F Administrative 9 Other G-Operator Error

~

H Other (Explain)J 9

-.m

._, -~.

.. J,;

4,..

.4

....e

.a

I&C DEPARTMENT Repon Month: May 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?ortable items for the I&C Department for the montt of May 1993 4

9 4

4

MAINTENANCE DEPARTMENT Report Month May 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 reportable iteins for the Maintenance Dept rtment for May 1993 i

l i

I l

e

+

~

"n

Refuelin'g Information Reauest 1.

Name of facility HaddamNai 2.

Scheduled date for next refueling shutdown.

t November 5,1994 3.

Scheduled date for restart following refueling.

December 25,1994 4.

(a)

Will refueling or 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?

Technical Specification change to remove three loop specifications and failed fuel rod limit spa:ification. Technical specification change to revise shutdown margin requirements due to conversion to Zirraloy clad fuel.

(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 reload?

rVa (d)

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

n/a 5.

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

April 1993 6.

Imponant 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 pmcedures.

n/a 7.

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

(a) 0 (b) 966 8.

The present licensed spent fuel pool storage capxity and the size of any increase in licensed storage capacity 1

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

II 9.

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

licensed capacity.

1998

.1 l

-