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HADDAM NECK PLANT

RR#1 * DoX 127E * EAST HAMPTON, CT 06424-9341

July 15,1989Re: Technical Specification 6.9.ldDocket .No. 50-213

U. S. Nuclear Regulatory CommissionDocument Control ' DeskWashington, D. C. 20555

Dear Sir:

In accordance with reporting requirements of Technical Specificat'6.9.1d, the Connecticut Yankee Haddam Neck Plant MonthlyOperating Report 89-06, covering operations for the periodJune 1,1989 to June 30, 1989 is hereby forwarded.

Very Truly yours,

'

Donald B. Miller, Jr.Station Superintendent

DBM/mdw

cc: (1) Regional Administrator, Region iU. S. Nuclear Regulatory Commission

g631 Park AvenueKing of Prussia, PA 19406

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(2) John T. ShedioskySr. Resident InspectorConnecticut Yankee

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Monthly Operating Report No. 89-06

For The Month of 1

June 1989

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,,- Plant Operations Summary - June. 1989

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The following is a summary of Plant Operations for June,1989.

On June 1 at 0000 hours, the plant was operatinn at a 30% powerhold to perform maintenance on the Containment Air RecirculationFan Motors and allow trouble shooting the B condensate pump. At1200 hours, the load was increased to test the B condensate pump.At 1244 hours, the plant was at 40% power and the B condensatepump run was initiated. By 1600 hours, the test on the B condensatepump was successfully completed and the unit returned to 30%power for completion of the preventive maintenance on theContainment Air Recirculation Fan Motors.

On June 6 at 1110 hours, the maintenance on the Containment AirRecirculation Fan Motors was complete. The unit then began a 5%per day load increase to be within the limits of fuel conditioning.

On June 11 at 0140 hours, at 50% power, the plant successfullyperformed a routine turbine valve ter and then resumed thegradual lwd increase.

On Jum 13 at 1405 hours, at 65% power and increasing, ConnecticutYankee reached a lifetime cummulative generation of 85 BillionKilowatt Hours of power.

By June 20 at 2015 hours the unit completed ascention to 100%power.

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

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AVERAGE DAILY UNIT POWER LEVEL-,

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, DOCKET NO. 50-213Conn. Yankee

UNIT Haddam Neck

*

DATE July 15, 1989

COMPLETED BY K. C. Wall

TELEPHONE (203) 267-2556

MON 111- June 1989

DAY AVERAGE DAILY POWER LEVEL- DAY AVERAGE DAILY POWER LEVEL(MWe-Net) (MWe-Net)

1 153 17 470

2 135 18 501

3 136 19 532

4 las 20 562

5 135 21 577

6 ian 22 575

7 177 23 572

8 207 24 570_

9 9u 25 569

10 266 26 566_ _ _

11 292 27 563

12 194 28 561

13 354 29 uq

14 ana 30 563

15 412 31 r, /n

16 440

|| INSTRUCTIONSl-

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.

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CONNECTICUT YANKEEREACTOR COOLANT DATAMONTH: JUNE 1989

REACTOR COOLANT ANALYSIS MINIMUM, AVERi.GE MAXIMUM.....................................................................PH E 25 DEGREES C : 6.56E+00 1 6.95E+00 7.36E+00CONDUCTIVITY (UMHOS/CM) : 7.26E+00 1.09E+01 : 1.35E+01 :CHLORIDES'(PPM) <5.00E-02 : <5.00E-02 : <5.00E-02 :DISSOLVED OXYGEN (PPB) : <5.00E+00 : <5.00E+00 : <5.00E+00 :EORON (PPM) 6.80E+01 2.22E+02 : 3.87E+02 :*

LITHIUM (PPM). ! 5.78E-01 7.92E-01 : 1.01E+00 :TOTAL GAMMA ACT. (UC/ML) : 1.56E-01 5.56E-01 : 9.28E-01 :10 DINE-131 ACT. (UC/ML) : 1.19E-02 : 2.04E-02 6.74E-02~I-131/I-133 RATIO 2.35E+00 3.78E+00 8.13E+00 :CRUD (MG/ LITER) : <1.00E-02 : <1.00E-02 : <1.00E-02 :TRITIUM (UC/ML) 5.93E-01 1 02E+00 : 1.45E+00 :*

HYDROGEN (CC/KG) : 2.19E401 : 2.54Ef01 : 3.38E+01 :............,....................... .................. .............

AERATED LIQUID WASTE PROCESSED (GALLONS): 1.54E+05WASTE LIQUID PROCESSED THROUGH' BORON RECDVERY(GALLONS): 8.14E+04

AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE)PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE): . 3.88E-018 60C-04

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NRC OPERATING STATUS REPORT-1

Haddam NeckE

.. 1. Docket: 50-213'~

[! 2.' Reporting Period: 06/89 Outage + On-line Hours: 0.0 + 720.0 = 720.0.

3. Utility contacts.J. Stanford (203) 267-2556 ext. 4524. Licensed Thermal Power (MWt): '18255. Nameplate Rating (Gross MWe): 667 x 0.9 s 600.3

{. ? 6. Design Electrical Rating (Net MWe): 582. 7. Maximum Dependable capacity (Gross MWe): 591.88. Maximum Dependable Capacity (Net MWe): 565.

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

'10. Power level to which restricted, if any (Net MWe): N/A11. Reasons for restriction, if any: N/A

MONTH YEAR-TO-DATE CUMULATIVE

12. Report period hours: . 720.0 4,343.0 188,447.0 -

13. Hours reactor critical. 720.0 4,343.0 .156,709.0

14. Reactor reserve shutdown hours: 0.0 0.0 1,285.0''

15. Hours generator on-line: 720.0 4,343.0 150,571.6

16. Unit reserve shutdown hours: 0.0 0.0 398.0-

.17. Cross thermal energy generated (MWtH): 930,971.0 6,759,671.0 260,160,232.0 *

,18. Gross electrical energy generated (MWeH): 298,264.0 2,259,237.0 85,230,448.0 *

19. Net electrical energv generated (MWeH): 280,228.8 2,145,838.6 81,012,318.5 *~

20. Unit s"ervice factor: 100.0 100.0 79.9

.21. Unit availability factor: 100.0 100.0 80.1

22. Unit capacity factor using MDC net: 68.9 87.4 78.4

- 23. Unit capac8.y f actor using DER net: '66.9 f4.9 73.9

24. Unit forced outora 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 shutdo.#n, estimated startup date: N/A

* Cumulative values from the first criticality (07/24/67). (The remaining cumulative values are from the first date ofconnercial operation, 01/01/68).

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'Refueline Information Reauest.,

1, . Name of facility

Connecticut Yankee Atomic Power Company

2. Scheduled date for next refueling shutdown.

September 2,1989

3. Scheduled date for restart following mfueling.

October 30,1989

4. (a) Will refueling or resumption of operation thereafter require a technicalspecification change or other license amendment?

Yes

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

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

(c) If answer is no, has the reload fuel design and core configuration beenreviewed by your Plant Safety Review Committee to determine whether anyunreviewed safety questions are associatad 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 supportinginformation.

6. Important licensing considerations associated with refueling, e.g., new or differentfuel design or supplier, unreviewed design or performance analysis methods,significant changes in fuel design, new operatmg 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 inlicensed storage capacity that has been mquested or is planned, in number of fuelassemblies.

I168

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

1996

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