ML20247F614

Monthly Operating Rept for Aug 1989 for Haddam Neck Plant

ML20247F614
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	08/31/1989
From:	Miller D, Wall K CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8909180222
Download: ML20247F614 (10)

Text

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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT f

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• BOX 127E o EAST HAMPTON, CT 06424-9341 i

September 15,1989 Re: Technical Specification 6.9.1d 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 6.9.1d, the Connecticut Yankee Haddam Neck Plant Monthly Operating Report 89-08, covering operations for the period August 1,1989 to August 31,1989 is hereby forwarded.

Very Truly yours, 1

Donald B. Miller, Jr.

Station Superintendent DBM/mdw cc:.

(1)

Regional Administrator, Region 1 U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 (2)

John T. Shedlosky Sr. Resident Inspector Connecticut Yankee 8909150222 890831 PDR ADOCK 05000213 R

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Connecticut Yankee Atomic Power Company HaddamNeck Plant Haddam, Connecticut

- Monthly Operating Report No. 89-08 i

For The Month of 1989

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Plant Operations Summarv - August.1989 The following is a~ summary of Plant Operations for August,' 1989.-

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The plant operated in a coast down mode for the month of August, There were no load reductions-

during the month.-

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i AVERAGE DAILY UNIT' POWER LEVEL l

DOCKET NO.

50-213 Conn. Yankee UNIT Haddam Neck DATE September 15, 1989 COMPLETED-BY K. C. Wall TELEPHONE (203) 267 3654 MONTH:-

August, 1989 DAY-AVERACE DAI....

DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 547 17 534 2

547 18 530 3

s4s 19 527 4

542 20 526 5

539 21 523 6

537 22 520 7

539 23 515 8

543' 24 512 9

543 25 511 10 542 26 510 11 543 27 510 12 547 28 508 13 548 29 506 14 545 30 r,n s 13 542 31 504 16 538 INSTRUCTIONS On this format, list the average daily unit nower level in MWe-Net for each day in the reporting month.

Complete the nearest whole megawatt.

(9/77)

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CONNECTICUT YANKEE-REACTOR COOLANT DATA MONTH: AUGUST 1989 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM PH e 25 DEGREES C 8.34E+00 :

8.96E+00 :

9.14E+00 :

CONDUCTIVITY (UMHOS/CM) 6.33E+00 :

9.74E+00 :

1.25E+01 :

CHLORIDES (PPM)

<5.00E-02 : <5.00E-02 : <5.00E-02 :

DISSOLVED OXYGEN (PPB)

<5.00E+00 * <5.00E+00 : <5.00E+00 :

BORON (PPM) 1.00E+00 :

2.39E+00 5.00E+00 :

LITHIUM (PPM) 2.38E-01 :

4.07E-01 :

5.38E-01 :

TOTAL GAMMA ACT. (UC/ML) 4.93E-01 8.73E-01 :

1.04E+00 :

IODINE-131 ACT. (UC/ML) 2.12E-02 :

2.66E-02 :

3.20E-02 :

I-131/I-133 RATIO 2.59E+00 2.92E+00 3.27E+00 :

CRUD (MG/ LITER)

<1.00E-02 : <1.00E-02 : <1.00E-02':

TRITIUM (UC/ML) 9.88E 1.52E+00 :

1.85E+00 :

HYDROGEN (CC/KG) 2.02E+01 I 2.54E+01 :

2.85E+01 :

AERATED LIQUID WASTE PROCESSED (GALLONS):

1.78E+05 WASTE LIGUID PROCESSED THROUGH BORON RECOVERi(GALLONS):

5.32E+04 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):

8.05E-01 PNIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):

6.84E-01 i

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NRC OPERATING STATUS REPORT 1?

'Haddam Neck

1. Docket: 50 213 1 2. Reporting Period: 08/89 Outage + On-line Hours:

0.0 + 744.0 = 744.0

-3. Utility contact: J. Stanford (203) 267 3635

4. Licensed Thermal Power ( Wt): 1825

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

6. Design Electrical Rating (Net MWe): 582

7. Maxinus Dependable capacity (Gross MWe): 591.8

8. Maxinun Dependable Capacity (Net me): 565

9. If changes occur above since test 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:

744.0 5,831.0 189,935.0

13. Hours reactor critical:

744.0 5,831.0 158,197.0 e

14. Reactor reserve shutdown hours:

0.0 0.0 1,285.0

15. Hours generator on-lines 744.0 -

5,831.0 152,059.6

16. Unit reserve shutdown hours:

0.0 0.0 '

~398.0

17. Gross thermal energy generated (MWtH) 1,311,603.0 9,422,757.0 262,823,318.0 *

18. Gross electrical energy generated (MWeM):

414,683.0 3,107,977.0 86,079,188.0 *

19. Net electrical energy generated (MWeH):

394,288.5 2,953,810.6' '

81,820,290.5

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20. Unit service factor:

100.0 100.0 80.1

' 21. Unit availability factor:

100.0 10;).0 80.3

22. Unit capacity factor using MDC net 93.8 89.7 78.5

23. Unit capacity factor using DER nets 91.1 87.0 74.1

24. Unit forced outage rate:

0.0 0.0 5.6

. 25. Forced outage hours:

0.0 0.0 8,975.6

26. Shutdowns scheduled over next 6 months (type,date, duration): Refueling, 9/2/89, 56 days

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

-* Cumulative values from the first criticality 107/24/67). (The remaining cumulative values are from the first date of commercial operation, 01/01/68).

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• Refueling Information Reauest m

1.

Name of facility Haddam Neck 2.

Scheduled date for next refueling shutdown.

September 2,1989 3.

Scheduled date for restart following refueling.

l-November 3,1989 4.

(a)

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

Yes (b)

If answeris yes, what,in general, will these be?

Incorporate the guidance provided in the NRC Generic Letter 88-16. The Generic Letter addresses removing cycle specific parameters from Technical Specifications and transferring them to the technical report supporting cycle operation.

(c)

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Cominittee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR section 50.59)?

n/a (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.

July 28,1989 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.

No 7.

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

(a) 157 (b) 653 8.

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

I168 9.

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

1996 1

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