ML20237K567

Monthly Operating Rept for Mar 1987

ML20237K567
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/31/1987
From:	Dean C CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20237K336	List: ML20237K332 ML20237K567
References
NUDOCS 8708190314
Download: ML20237K567 (9)

Text

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4 CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT MONTHLY OPERATING REPORT No. 87-03 l

l FOR THE MONTH OF

! MARCH 1987 8708190314 870415 PDR ADOCK 05000213 g R PDR

( __ _ _ _ _ _ _ _ _ _ _ _ _

PLANT OPERATIONS

SUMMARY

- MARCH 1987 i The following is a summary of plant operations for March 1987.

On March 4, 1987 at 0520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br />, the plant load was reduced to 1 65 percent to check for tube leaks in the main condenser. At 0634 hours0.00734 days <br />0.176 hours <br />0.00105 weeks <br />2.41237e-4 months <br />..the plant reached 400 Megawatts Electric (MWE). At '

1155 hours0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.394775e-4 months <br />, a routine turbine control valve test was conducted. At 2250 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.56125e-4 months <br />, the waterboxes had been checked, chemistry was within acceptable limits, and the plant then commenced increasing load. The plant was returned to 100 percent power on March 5, 1987 at 0300 l hours. j l

On March 14, 1987 at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, a load reduction to 50 percent was  !

initiated to evaluate a low oil level and high bearing temperature  ;

condition on Number 2 reactor coolant pump. At 1256 hours0.0145 days <br />0.349 hours <br />0.00208 weeks <br />4.77908e-4 months <br />, the plant i reached 300 MWE. At 1420 hours0.0164 days <br />0.394 hours <br />0.00235 weeks <br />5.4031e-4 months <br />, plant load was reduced further I to evaluate a potential axial offset problem. At 1425 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.422125e-4 months <br />, normal '

l conditions were restored and a load commenced. At 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br />, the plant was at 100 percent power.

On March 26, 1987 at 1542 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.86731e-4 months <br />, the plant reached 78 Billion Kilowatt Hours generation.

On March 29, 1987 at 0220 hours0.00255 days <br />0.0611 hours <br />3.637566e-4 weeks <br />8.371e-5 months <br />, a load reduction to 50 percent was j initiated to investigate a high valve stem leak off temperature.

Reactor Coolant System leak rate exceeded the 10 gallon per minute limit specified in Technical Specifications by approximately 2 gallons per minute. At 0420 hours0.00486 days <br />0.117 hours <br />6.944444e-4 weeks <br />1.5981e-4 months <br />, the plant reached 300 MWE and three loop stop valves were backseated to correct the problem. At 0810 hours0.00938 days <br />0.225 hours <br />0.00134 weeks <br />3.08205e-4 months <br />, a l routine turbine control valve test was conducted. At 0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br />, l normal conditions were restored and the load increase commenced. At  !

1238 hours0.0143 days <br />0.344 hours <br />0.00205 weeks <br />4.71059e-4 months <br />, the plant was at 100 percent power.

i

) On March 30, 1987 at 1609 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.122245e-4 months <br />, the plant reduced power to 92 percent 3 i due to a problem with a feedwater heater level control valve. At 1640 )

hours, normal conditions were restored and a load increase connenced.

At 1938 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.37409e-4 months <br />, the plant was at 100 percent power. l The plant was operated 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 April 15, 1987 COMPLETED BY C. B. Dean TELEPHONE (203) 267-2556 MONTH: MARCH 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1 561 17 559 l 2 562 18 560 561 3 19 560 4 417 20 564 l 5 552 21 560 l

6 560 22 562 7 560 23 559 8 559 24 561 l

9 560 561 25 10 560 561 26 11 561 561 27 12 562 562 28 561 476 13 29 14 487 557 30 15 560 561 31 16 559 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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i CONNECTICUT YANKEE REACTOR COOLANT DATA MONTH: MARCH 1987 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM PH 0 25 DEGREES C 6.63E+00 6.77E+00 6.92E+00 :

CONDUCTIVITY (UMHOS/CM)  : 7 40E+00 9.86E+00 : .1.26E+01 :

CHLORIDES (PPM) l'<5.00E-02 : <5.00E-02 : <5.00E-02 :

DISSOLVED OXYGEN (PPB)  : <5.00E+00 : <5.00E+00 <5.00E+00 :

BORON (PPM)  : 3.23E+02 3.76E+02 3 4.66E+02 :

LITHIUM (PPM)  : 6.03E-01 7.88E-01 9.67E-01 :

TOTAL GAMMA ACT. (UC/HL) 5.51E-01 : 1.01E+00 :. 1.42E+00 :

10 DINE-131 ACT. (UC/ML) 4.80E-03 : 6.91E-03 : 1.15E-02 :

I-131/I-133 RATIO 1.51E+00 : 2.11E+00 3.44E+00: -

CRUD (MG/ LITER)  : <1'.00E-02 : <1.00E-02 : <1.00E-02 :

TRITIUM (UC/ML)  : 1.97E+00': 2.44E+00 1 3.09E+00 :

HYDROGEN (CC/KG)  : 1.98E+01 : 2.45E+01 : 2.81E+01 :

l AERATED LIGUID WASTE PROCESSED (GALLONS): 2.18E+05 l WASTE LIQUID PROCESSED THROUGH BORON. RECOVERY (GALLONS): 2.16E+04 l AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE): 4.04E-01 l PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE): 0.00E+00 l l  !

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NRC Operatkng Status Report

, .Haddam Neck

1. Locket: 5 b213

2. Eeporting Feriod: 03/E7 Outage + Da-line' Hours: 0.0 + 744.0 = 744.0

3. Utility Centact: J.P. Drago (203) 267-2556 ext 452

4. Licensed Thereal Power (MWt): 1825

5. Naseplate Rating (Eress Meh . 667 x 0.9

• 600.3

6. Cesign Electrical Rating (Net MWe): 5E2

7. Maxieca Dependable Capacity (Gress Se): 595.8 .

B. Maxiaur Dependable Capacity (Wet Gels 569

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

10. Foder level to which restricted, if any (Net Me): N/A

!!. Erasens fer restriction, if any: N/A MONTH YEAR-TO-DATE CUMULATIVE

12. Re;crt period hcurs: 744.0 2,160.0 169,720.0

!!. Hours reacter critical: 744.0 2,160.0 143,620.2

14. Reactor reserve shutdcwa hours: 0.0 0.0 1,225.0

15. Heers generater en-lines 744.0 2,160.0 137,647.6

16. Unit reserve shutdown hcurs: 0.0 0.0 396.0

17. Gross thermal energy ger.erated (StH): 1,333,069.0 3,911,831.0 232,292,292.0 e

19. Ercss electrical energy generated (S eH): 429,545.0 1,260,3B3.0 7E,073,305.0 i

19. Net electrical energy generated (NeH): 409,577.2 1,201,035.! 74,233,323.4 e

20. Unit service factor: 100.0 100.0 Bl.6

21. Unit availability facter: 100.0 100.0 61.8

22. Unit capacity f atter using MDC net: 96.8 97.9 60.6

23. Unit capacity factor using LER net: 94.6 95.6 75.7

24. Unit ferced cuttge rate: 0.0 0.0 6.1 l 25. Forced cutage hours: 0.0 0.0 8,921.2

26. Shutdowns scheduled over next 6 eenths (type,date, duration): REFUELING 07/12/27 14 WEEKS

27. If currently shutdown, estimated startup date: N/A 1

i i Cuculative values frca the first criticality (07/24/67). (The remaining cuculative values are free the first date of certercial operation, 01/01/66).

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REFUELING INFORMATION REQUEST l

1. Name of facility Connecticut Yankee Atomic Power Company

2. Scheduled date for next refueling shutdown.

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

3. Scheduled date for restart following refueling.

October 30, 1987 (first day at full power)

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

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

a U

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)? >

f Not applicable, f

l (d) If no suc'. review has taken place, when is it scheduled?

Not applicable.

l S. Scheduled date(s) for submitting proposed licensing action and supporting information. i 6/1/87 l

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, j NO l

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. 1 (a) 157 (b) 597 NOTE: 44 new fuel assemblies in New Fuel Storage.

8. The present 11cer. sed spent fuel pool storage capacity and the size of any increase in i licensed storage capacity that has been requested or is planned, in number of fuel l assembides, q l 1168 '

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

1996 u__________________________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _J