ML20247A129

Monthly Operating Rept for Apr 1989 for Haddam Neck

ML20247A129
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	04/30/1989
From:	Miller D, Wall K CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8905230049
Download: ML20247A129 (10)

Text

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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT RR#1

• BOX 127E

• EAST HAMPTON, CT 06424-9341 L

May 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 89-04, covering operations for the period April 1,1989 to April 30, 1989 is hereby forwarded.

Very Truly yours, 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. Shediosky i

Sr. Resident Inspector Connecticut Yankee hh 8905230049 890430 1

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Monthly Operating Report No. 89-04

'L For The Month of April 1989

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' Plant: Operdions Summarv - April.1989 e

l The following-is-a summary of Plant Operations for ' April,1989.

-The plant operated at 30% power until April 1 at 1029 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.915345e-4 months <br /> when e

' the unit initiated a 1% per hour load increase.

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8 On April '9 at 1050 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.99525e-4 months <br />, the plant reached = 100% power.~

On April '14 at 0903 hours0.0105 days <br />0.251 hours <br />0.00149 weeks <br />3.435915e-4 months <br />, the plant commenced a load reduction

.because of an inoperable containment isolation valve. - At 0905 g

~ hours, the valve was verified operable a9. per plant procedures and.

the unit started a load increase' from 98% power.

By. 0916 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.48538e-4 months <br />, the plant returned to 100% power.

On April 23. at.0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant commenced a load reduction to.

65% power to conduct a routine' turbine control valve test.

By 0428

, hours, the test was complete and the unit was at 100% power.

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

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AVERAGE DAILY UNIT POWER LEVEL l

DOCKET-NO.

50-213 Conn. Yankee UNIT Haddam Neck DATE 5/15/89 COMPLETED BY K. C. Wall

' TELEPHONE (203) 267-2556 MONTH:

April 1989 DAY AVERAGE DAILY POWER LEVEL DAY

. AVERAGE DAILY. POWER LEVEL 1

(MWe-Net)

'(MWe-Net) l 1

181 17 592 2

an6 18 591 3

407 19 591 4-

'AAi 20 591 5

470 21 592-6 499 22 592 7

san 23 573 8

561 24 592-592 25 9

59, 10 592 26 592 11 593 27

[90 12 592 28 590 13 592 29 590 14 591 30 590 15 so?

31 n/a 16 592 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in'the reporting month.

Complete the nearest whole megawatt.

(9/77)

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REACTOR COOLANT DATA MONTH: APRIL 1989 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM PH & 25 DEGREES C 6.69E+00 :

1 6.88E+00':

7.03E+00 :

CONDUCTIVITY (UMHOS/CM) 7 34E+00 1 16E+01 1 85E+01 :

CHLORIDES (PPM)

<5.00E-02 : <5 00E-02 1.<5.00E-02 :

DISSOLVED OXYGEN (PPB)

<5 00E+00 : <5.00E+00 t' <5.00E+00 :

BORON (PPM) 2.13E+02 :

3 00E+02 :

5.72E+02::

LITHIUM (PPM) 6 49E-01 9.18E-01 :

1.27E+00 :

TOTAL GAMMA'ACT.'(UC/ML).

3 2 24E-01 6 38E-01 : :9 25E-01 :

IODINE-131 ACT. (UC/ML) 9.83E 2.25E-02 ;

4.38E-02 :

I-131/I-133 RATIO 1.91E+00 :

2 61E+00 3.91E+00 :

CRUD (MG/ LITER)

<1.00E-02 : <1 00E-02 : <1.00E-02 :

. TRITIUM tC/ML) 1.36E+00 1 60E+00 :

1.93E+00 :

HYDROGEN (CC/KG) 2.40E+01 :

2 90E+01 :

3.51E+01 :

AERATED LIQUID WASTE' PROCESSED (GALLONS):

1 47E+05 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS):

7.19E+04 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):

3.15E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE);

7.13E-04 0

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NRC OPERATING STATUS REPORT-U

.Haddam Neck i-

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1. Dock'et ~

50 213

, 2. Reporting Feriod 04/89 Outage + On-line Hours: - 0.0 + 719.0 = 719.0' L

3. Utility

Contact:

J. Stanford (203) 267-2556 ext. 452

4. Licensed Thermal Power'(MWt):.1825

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

4. Design Electrical Rating (Net MWe): 582

7. Maximum Dependable Capacity (Gross MWe): 591.8

.8. Maximum Dependable Capacity (Net MWe): 565-

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

- 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 i

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12. Report period hours:

719.0 2,879.0 186,983.0

13. Hours reactor critical:

719.0' 2,879.0 155,245.0 T ;14. Reactor reserve shutdown hours:

0.0 0.0 1,285.0

15. Hours generator on-line:

719.0 2,879.0 149,107.6

16. Unit reserve sh'u'down hours:

0.0 0.0 398.0 t

17. Gross thermal energy generated (MWtN):

.1,218,778.0 4,482,880.0 257,883,441.0.*

18. G'ross electrical energy generated (MWeH):

412,212.0 1,508,495.0 84,479,706.0

• l19 Net electrical energy generated (MWeH):

392,917.0 1,433,332.5 80,299,812.3 *

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20. Unit service factors 100.0 100.0 79.7

'21. Unit availability factor:

100.0 100.0 80.0 e

22. Unit capacity factor using MDC net

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88.1 78.3

23. Unit capacity factor using DER net:

93.9 85.5 73.8 i, *

24. Unit forced outage rate:

0.0 0.0 5.7

25. Forced outege hours:

0.0 0.0 8,975.6

'26. Shutdowns scheduled over next 6 months (type,date, duration): Refueling, 09/09/89, 56 days

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

• Cumulative values from the first criticality (07/24/67). (The remaining canulative values are from the first date of LI connercial operation, 01/01/68).

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2 RefuelindInformation Reauest 1.

Name of facility Connecticut Yankee Atomic Power Company I

2.

Scheduled date for next refueling shutdown.

September 9,1989 3.

Scheduled date for restart following refueling.

November 6,1989 4.

(a)

Will refueling or resumption of op-ration thereafter require a technical specification change or other licen ~ amendment?

No (b)

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

(c)

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

No (d)

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

July,1989 5.

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

6.

Important licensing considerations associated with refueling, e.g., new or di'ferent 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 nssemblies.

I168 9.

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

1996

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