ML20237K398

Monthly Operating Rept for Feb 1987

ML20237K398
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	02/28/1987
From:	Dean C, Miller D CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC
References
NUDOCS 8708190236
Download: ML20237K398 (10)

Text

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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT l

HADDAM, CONNECTICUT l

MONTHLY OPERATING REPORT NO. 87-02 FOR THE MONTH OF 4 N

FEBRUARY 1987 / \\

8708190236 870228 PDR ADOCK 05000213 R PDR

I PLANT OPERATIONS The following is a summary of plant operations for February 1987.

On February 2, 1987 at 0916 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.48538e-4 months <br />, the plant commenced a load reduction due to a problem on #1 steam generator feed regulator valve positioner. The positioner was repaired by 1025 hours0.0119 days <br />0.285 hours <br />0.00169 weeks <br />3.900125e-4 months <br />; and at 1555 hours0.018 days <br />0.432 hours <br />0.00257 weeks <br />5.916775e-4 months <br />, the plant returned to 100 percent power.

The plant reduced its load to 65 percent on February 15 at 0555 hours0.00642 days <br />0.154 hours <br />9.176587e-4 weeks <br />2.111775e-4 months <br /> to conduct a routine turbine control valve test. The test was completed at 0423 hours0.0049 days <br />0.118 hours <br />6.994048e-4 weeks <br />1.609515e-4 months <br />; and at 0856 hours0.00991 days <br />0.238 hours <br />0.00142 weeks <br />3.25708e-4 months <br />, the plant reached 100 percent power.

The plant continued to' operate at full power for the remainder of the month.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-213 Conn. Yankee UNIT Haddam Neck DATE March 15, 1987 COMPLETED BY C. B. Dean TELEPHONE (203) 267 2556 MONTH: February 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 562 17 561 2 554 18 561 3 561 19 562' i 4 562 20 562 5 562 21 562 6 562 22 562 l'

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562 24 563 562 563 9 25 10 26 562 562 J

561 11 561 27 ]

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15 521 31 n/a 16 562 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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CONNECTICUT YANKEE REACTOR COOLANT DATA MONTH: FEBRUARY 1987 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUh PH R 25 DEGREES C  : 6 59E+00 6.74E+00 : 6.87E+00 :

CONDUCTIVITY (UMHOS/CM)  : 7.90E+00  ! 1.06E+01  : 1.30E+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)  : 4.08Ef02 : 4.47E+02 : 4.87E+02 :

LITHIUM (PPM)  : 6.49E-01 : 9.23E-01 : 1.21E+00 !

TOTAL GAMMA ACT. (UC/ML)  : 6.62E-01 : 1.03E+00 : 1.28E+00 :

IODINE-131 ACT. (UC/ML)  : 4.35E-03 : 6.43E-03 : 1.16E-02 :

I-131/I-133 RATIO  : 1.41E+00 : 1.98E+00 3.16E+00 :

CRUD (MG/ LITER)  : <1.00E-02 : <1.00E-02 : <1.00E-02 :

TRITIUM (UC/ML)  : 2.37E+00 : 2.50E+00 2.61E+00 :

HYDROGEN (CC/KG)  : 3.46E+01 3.79E+01': 3.93E+01 :

AERATED LIQUID WASTE PROCESSED (GALLONS): 1.46E+05 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS):' 6.72E+04 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE): 2.74E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE): 0.00E+00

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,, NRC Oporating1 Status Raport Haddam Neck

1. Docket: 50-21'3

2. Reporting Period: 02/87 Dutage + On-line Hours: 0.0 + 672.0 = 672.0 g' 3. Utility

Contact:

J.P. Drago (203) 267-2556 ext 4 %

4. Licensed 7hermal Power (Mtle '1825

5. Naseplate Rating (6ross Me): 667 x 0.9 s 600.3

6. Design Electrical Rating (Net Me): 582

7. Maximua Dependable Capacity (Gross Me): 595.8

8. Maxinus Dependable Capacity (Net Me): .569

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

10. Power level to_which restricted, if any (Net Me): N/A

11. Reasons f or restriction, if any: N/A MONTH YEAR-ID-DATE CUMULATIVE

12. Report period hours: ' 672.0 1,416.0 167,976.0

13. Hours reactor critical 672.0 1,416.0 142,876.2

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

15. Hours generator on-line: 672.0 1,416.0 136,903.6

16. Unit reterve shutdown hours: 0.0 0.0 398.0

17. Gross thermal energy generated (MtH): 1,225,139.0 2,578,762.0 236,959,223.0 8

18. Gross electrical energy generated (M eHl: 394,653.0 830,838.0 77,643,760.0 8

19. Net electrical energy generated (MeH): 376,394.7 792,257.5 73,823,745.6 8

20. Un:t service f actor: 100.0 100.0 81.5

21. Unit availability f actor 100.0 100.0 81.7

22. Unit capacity f actor using MDC net: 98.4 98.3 80.5

23. Unit capacity factor using DER net: 96.2 96.1 75.6

24. Unit forced outage rate: 0.0 0.0 6.1

25. Forced outage hours: 0.0 0.0 8,921.2 l

26. Shutdowns scheduled over next 6 sonths (type,date, duration): REFUELIN6 07/18/87 14 WEEKS 27.11 currently shutdown, estiaated startup date: N/A l

8 Cumulative values from the first criticality (07/24/67). (The remaining cumulative values are fros the first date of cossercial operation, 01/01/68).

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. l REFUELING INFORMATION REQUEST

1. Name of facility Connecticut Yankee Atomic Power Company

2. Scheduled date for next refueling shutdown. l l

July 17, 1987 (last day at full power) l

3. Scheduled date for restart following refueling. i l

October 23, 1987 (first day at full power)

4. (a) Will refueling or resumption of operation thereafter require a technical speci-fication change or other license amendment?

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

The following specifications will be revised for 4 loop and 3 loop operation:

RCS flowrate, safety limit curves and axial offset limits.

(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 (Ref. 10 CFR Section 50.59)?

Not applicable.

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

Not applicable.

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

6/1/87

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) 597 NOTE: 8 new fuel assemblics in New Fuel Storage.

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 sasemblies.

1168

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

1994 to 1995

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'I 1RE: TechnicalSpecification6.9.4 Docket No. 50-213 4 $

Director, Office of Resource Management U. S. Nuclear Regulatory Counission Washington, D. C. 20555

Dear Sir:

In accordance with reporting requirements of Technical Specification 6.9.1d, the Connecticut Yankee Haddam Neck ~)lant Monthly Operating Report 87-02, covering operatione for the period February 1, 1987 to February 28, 1987, is hereby forwarded.

Very truly yours, 7

6 $/ r Donal B. Miller, Jr.

Station Superintendent DBM/mdw Enclosur(s cc: (1) Regional Administrator, Region i U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 (2) P. Swetland Sr. Resident Inspector Connecticut Yankee S,#

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