ML20138B994

Corrected Monthly Operating Rept for Sept 1985

ML20138B994
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/30/1985
From:	Drago J CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20138B982	List: ML20138B979 ML20138B994
References
NUDOCS 8512120433
Download: ML20138B994 (9)

Text

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4  % _a CONNECTICUT YANKEE ATOMIC POWER COMPANY

-HADDAM NECK PLANT HADDAM, CONNECTICUT i.

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i 8512120433 851016 PDR ADOCK 050 g 3 R ,

h MONTHLY OPERATING REPORT NO. 85-09 i ~

FOR THE MONTH OF

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SEPTEMBER 1985 3

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PLANT OPERATIONS On September 12 at 0148, a high temperature alarm was received on the 1A steam generator feed pump thrust bearing. The unit commenced a load reduction at 0151 hours0.00175 days <br />0.0419 hours <br />2.496693e-4 weeks <br />5.74555e-5 months <br /> and at 0225 hours0.0026 days <br />0.0625 hours <br />3.720238e-4 weeks <br />8.56125e-5 months <br />, the thrust bearing temperature dropped to normal.

Subsequent investigation revealed a loose thermocouple lead. At 0240, the plant reached 400 MWe and at 0310, a routine turbine control valve test was performed.

The unit returned to 100% power on September 12 at 0805 hours0.00932 days <br />0.224 hours <br />0.00133 weeks <br />3.063025e-4 months <br />.

On September 27 at 0820, the plant started a load reduction to come off line due to Hurricane Gloria. The unit was off line at 1428 hours0.0165 days <br />0.397 hours <br />0.00236 weeks <br />5.43354e-4 months <br />. On September 28 at 1135 hours0.0131 days <br />0.315 hours <br />0.00188 weeks <br />4.318675e-4 months <br />, the unit phased on line. After completing Chemistry holds at 5% and 25% power, the plant reached full power on September 30 at 0125 hours0.00145 days <br />0.0347 hours <br />2.066799e-4 weeks <br />4.75625e-5 months <br />.

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' INSTRUMENT &' CONTROL

SYSTEM EFFECT ON- CORRECTIVE ACTION SPECIAL PRECAdrio OR- MALFilNCTION SAFE TAKEN TO PREVENT TAKEN TO PROVIDE CAUSE RESULT OPERATION REPETITION FOR REACTOR SARET COMPONENT DURING~ REPAIR Incore Flux Drive Dirty thimble Restricted None ' Thimbles to be cleaned N/A

- operation of during refueling, drive Auto. Aux. Feed Plumbing / wiring Incorrect None Rewrote procedure to N/A Solenoid Control incorrect operation perform surveillance.

Valves Corrective action for plumbing / wiring is being evaluated.

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MAINTENANCE SEPTEMBER 1985 SYSTEM .

EFFECT ON ' CORRECTIVE ACTION SPECIALPRECAdT10)

OR MA1. FUNCTION SAFE TAKEN TO PREVENT TAKEN TO PROVIDE C0t1PONENT CAUSE RESULT OPERATION REPETITION FOR REACTOR SASET DURING REPAIR Th:re were nd rsportable items for the month of September, F

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-213 Conn. Yankee UNIT Haddam Neck DATE September 1985 COMPLETED BY J. P. Drago TELEPHONE (203) 267-2556 MONTH: September 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 565 17 571 2 566 18 571 3 566 19 569 4 563 20 567 5 563 21 565 6 561 22 564 7 560 23 565 8 559 564 24 9 561 566 25 10 564 26 567 11 567 27 229 12 536 28 6 13 571 189 29 14 572 570 30 15 575 g 16 568 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)

COFNECTICUT YANKEE RFanTnR rnniANT nAIA MONTH: SEPTEMBER 1985 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM

................................................. 2..................

PH 9 25 DEGREES C  : 6.21E+00  : 6.89E+00  : 7.13E+00 :

CONDUCTIVITY (UNHOS/CM)  : 3.20E+00 5.67E+00  : 7.15E+00 :

cMtnRTnr4 (ppm) i <s.coE-o? t <s.coE-09 t <s.coE-09 !

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

BORON (PPM)  : 8.60E+01  : 1.53E+02  : 4.36E+02 :

LITHIUM (PPM) 2:29E-01 4:94E-01 + 6 16E-01 ?

TOTAL GAMMA ACT. (UC/ML)  : 3.30E-01  : 7.81E-01  : 1.76E+00 :

IODINE-131 ACT. (UC/ML)  : 3.21E-03  : 8.56E-03  : 5.47E-02 :

T 111 / T-111 DATTn  ? 1.Atr4Ao

• 9.M7F4AA ? 9.10F4A1 ?

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

TRITIUM (UC/ML)  : 9.81E-01 : 1.17E+00 : 1.30E+00 :

HYDROGEN (CC/MG) t 3:02E+01 ? 3:24E+01 ? 3:42E401 ?

AERATED LIQUID WASTE PROCESSED (GALLONS): 1.22E+05 IJaRTE ITOIITn DRnrFRRFn TMRnilGM RORON.RFEnVERY(GALLONS)i A.99E+D_4 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE): 1.93E+00 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE): 0.00E+00 e

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NRC Oporating Statum Roport Haddam Neck

1. Docket: 50-213

2. Reporting Period: 09/85 Outage + On-line Hours: 24.3 + 695.7 = 720.0

3. Utility

Contact:

J.P. Drago (203) 267-2556, ext. 452

4. Licensed 7hereal Power (Mut): 1825

5. Naseplate Rating (Sross MWe): 667 x 0.9 = 600.3

6. Design Electrical Rating (Net MWe): 582

7. Maxinus Dependable Capacity (Srcss MWe): 595.8

8. Marious Dependable Capacity (Net MWe): 569

9. If changes occur above since last 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: 720.0 6,551.0 155,591.0

13. Hours reactor critical: 699.0 6,496.8 134,213.8

14. Reactor reserve shutdown hours: 21.0 21.0 1,285.0

15. Hours generator on-line 695.7 6,447.0 128,651.5

16. Unit reserve shutdown hours: 24.3 24.3 398.0 17, 6ross thereal energy generated (MutH): 1,221,235.0 11,365,650.0 223,552,900.0 t

18. Gross electrical energy generated (MWeH): 395,385.0 3,704,950.0 73,364,100.0 8

19. Net electrical energy generated (MWeH): 376,326.3 3,529,902.0 69,790,970.0 8

20. Unit service factor: 96.6 98.4 82.7

21. Unit availability factor: 100.0 98.8 82.9

22. Unit capacity factor using MDC net: 91.9 94.7 82.4

23. Unit capacity factor using DER net: 89.8 92.6 77.1

24. Unit forced outage rate: 3.4 1.6 5.7

25. Forced outage hours: 24.3 104.0 7,810.1

26. Shutdowns scheduled over n n t 6 sonths (type,date, duration):

REFDELING, 01/04/86, 8 to 12 weeks depending on steas generator test results

27. If currently shutdown, estiaated startup date: N/A 8 Cuaulative values from the first criticality (07/24/67). (The remaining cuaulative values are from the first date of cosearcial operation, 01/01/68).

e-UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-213 UNIT NAME Conn. Yank-b, DATE Oct. 15, 1985 COMPLETED BY C. B. Dean REPORT MONTil September 15. 1985 TELEP110NE (203)267-2556 e c.

O M M M No. Date bm N .o $ g LER e 8e Cause & Corrective "e UE E jg g RPT. 0 EE Action to h E$ 'E gjkg UE 0' " Prevent Recurrence 5" 5  ?**M

• mO O 85-08 09-27-85 F 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> F 1 N/A N/A N/A Shut down reactor due 20 mins to anticipated hurricane conditions.

1 2 3 4 F Forced Reason: Method: Exhibit G-Instructions S Scheduled A-Equipment Failure (Explain) H-Other(Explain 1-Manual for Preparation of Dati B-Maintenance or Test 2-Manual Scram Entry Sheets for Liceni C-Refueling 3-Automatic Scram Event Report (LER) Fil<

D-Regulatory Restriction 4-Other(Explain) (NUREG-0161)

E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit 1 Same Source

REFUELING INFORMATION REQUEST

1. Name of facility Connecticut Yankee Atomic Power Company

2. Scheduled date for next refueling shutdown.

. January 4, 1986 3.. Scheduled date for restart following refueling.

March 1, 1986 - March 29, 1986 4 (a). Will refueling or resumption of operation thereafter require a technical speci-fication change or other license amendment?

t YES

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

1. Revise the allowance factors in calculating core power peaking.

2. Revise the axial offset limits for 4 loop and 3 loop operation.

3. Revise the RCS mass flow specification due to anticipated S/G work.

(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)?

j Core reload design in progress, t

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

November 1985

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

December 1985 I 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) 545

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.

1168

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

, 1994 to 1995