ML20138B610

Monthly Operating Rept for Sept 1985

ML20138B610
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/30/1985
From:	Drago J, Graves R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8512120342
Download: ML20138B610 (10)

Text

I' s

s CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT MONTHLY OPERATING REPORT No. 85-09 FOR THE MONTH OF SEPTEMBER 1985 3 b-j.)

DE12120342 850930 gDR ADOCK 050 g 3 1

.v PI. ANT 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 SEPTEMBER 1985-SYSTEM EFFECT ON CORRECTIVE ACTION SPECIAL'PRECAtr[ IONS 1 OR MALFUNCTION SAFE TAKEN TO PREVENT TAKEN TO PROVIDE l

l COMPONENT CAUSE RESULT OPERATION REPETITION FOR REACTOR SAlETY-

~

DURING REPAIR'

Incore Flux Drive Dirty thimble Restricted None Thimbles to be cleaned N /A' '

l operation of during refueling.

i drive l

t Auto, Aux. Feed Plumbing / wiring Incorrect None Rewrote procedure to N/A Solanoid Control.

incorrect operation perform surveillance.

Velvss Corrective action for plumbing / wiring is being evaluated.

l

'f f

O

MAINTENANCE SEPTEMBER 1985 SYSTEM EFFECT ON CORRECTTVE ACTION SPECIAL PRECAUTIONS OR MALFUNCTION SAFE TAKEM TO PREVENT TAKEN TO PROVIDE COMPONENT CAUSE RESULT OPERATION REPETITION FOR REACTOR SAFFTY DURING REPAIR Thera were nd r:_ portable items for the month of September,

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-213 Conn. Yankee UNIT Haddam Neck DATE September 1985 p.

l COMPLETED BY J. P. Drago TELEPHONE (203) 267-2556 p

MONTH:

Septenber 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 56.5 6

561 22 564 7

560 23 565 8

559 24 564 9

561 25 566 l

10 564 26

.567 229 11 567 27 6

12 536 -

28 13 571 189 29 l

14.

572 570.

30 15 568 g

16 l

l 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)

l l

l i

CONNECTICUT YANKEE REACTOR. COOLANT _ DATA.

MONTH: SEPTEMBER 1985 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE NAXIMUM

_.-a.aaau u m.u u.....

u.......

u

.....u.

u. u...u.

u. u u...

u u.u...u a.u u PH G 25 DEGREES C 6.21E+00 :

6.89E+00 7.13E+00 :

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

7.15E+00 :

cHinRTnFM (PPM)

! <5.OOF-02 ! <5.OOE-02 1 <5.OOE-02 !

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)

'.20E-01 1 4.94E-01 -._ _6.14E-01 1 TOTAL GAMMA ACT. (UC/HL) 3.30E-01 :

7 81E-01 :

1.76E+00 :

IODINE-131 ACT. (UC/ML) 3.21E-03 :

8 56E-03 5.47E-02 :

T-171/r-137 partn t

1.nar4nn !

9.s7r4nn ?

9. tor 4nt t 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 JCC/KG)

_3.02E+01 :- 3.24E+01_ _._3.42E+01_:

o.00.................................................................

AERATED LIQUID WASTE PROCESSED (GALLONS):

1.22Ef05

__ WASTE _LIQULD_lROCESSED-THROUGH_ BORON _ RECOVERY-(GALLONS):__6.99E+04 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):

1.93E+00 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):

0.00E+00

--.m wh enm w.

6h wwe.s

=4p its e

=

NRC Operating Status Report l

Maddam' Neck i

1. Docket: 50-213'

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

'3. Utility

Contact:

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

4. Licensed Thereal Poser (last): 1825

5. Nameplate Eating (Gross MNe): 667 0.9

• 600.3

6. Lesign Electrical Rating (Net Muel 582

7. Manteus Dependable Capacity (Bross MNe): 595.8

8. Manieus Dependable Capacity (Net Mue): 569

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

10. Poser level to which restricted, if any (het Muel N/A

11. Reasons for restriction, if any: N/A i

MONTH YEAR-fD-DATE CUMulAilVE

12. Report period hours:

720.0 6,551.0 155,591.0

13. Hours reactor critical:

699.0 6,496.8 134,213.8 i

14. Reactor reserve shutdoen hours:

21.0 21.0 1,285.0

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

16. Unit reserve shutdoen hours:

24.3 24.3 398.0

17. Gross thereal energy generated (MutH):

1,221,235.0

!!,365,650.0 223,552,900.0 8

18. Grcss electrical energy genera nd (NueHl 395,385.0 3,704,950.0 73,364,100.0 8

19. Net electrital energy generated (MueHl 316,326.3 3,529,902.0 69,790,970.0 t 1

i

20. Unit service factor 96.6 98.4 82.7

21. Unit availability factors 100.0 98.8 82.9

22. Unit capacity factor using NBC 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 1,810.1 i

26. Shutdoens scheduled over next 6 months (type,date, durationli REFUELING, 01/04/84, 8 to 12 seets depending on stese generator test results

27. Il currently shutdoen, esticated startup dates N/A 1

8 Cuaulative values free the first criticality (07/24/67). (The reedining cusi.lative values are free the first date of coseercial operation, 01/01/68).

UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-213 UNIT NAME Conn. Yankee.

DATE Oct. 15, 1985 C0!!PLETED BY C. B. Dean REPORT MONT11 September 15. 1985 TELEPIIONE (203)267-2556 o

O M M M

[}

m,

.o $

LER a

Cause & Corrective No.

Date n

g g

gg g

j gg RPT.

u Action to g

u :c es mo a

Prevent Recurrence

]e a o o 55 ~

• OM mO O

85-03 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) 11-Other(Explain 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for LicenseG C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Other(Explain)

(NUREG-0161)

E-Operator Training & License Examination F-Administrative 5

G-Operational Error (Explain)

Exhibit 1 Same Source

f r

REFUELING INFORMATION REQUEST l

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 l

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 be7

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 saf aty l

questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

Core reload design in progress.

(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 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant l

I changas in fuel design, new operating procedures.

l NO I

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

i (a) 157 (b) 545 l

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 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

O CONNECTICUT YANKEE ATO MIC POWER COMPANY HADDAM NECK PLANT RRs1

• BOX 127E

• EAST HAMPTON. CONN. 06424 October 15, 1985 Docket No. 50-213 Director, Of fice of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Sir:

In accordance with reporting requittaents, the Connecticut Yankee lladdam Neck Plant Monthly Operating Report 85-09, covering operations for the period September 1, 1985 to September 30, 1985 in hereby forwarded.

Very truly yours, h

Wm Richard H. Graves Station Superintendent RHG/dfv Enclosures cc:

(1) Director, Region 1 Division of Inspection and Enforcement U. S. Nucicar Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 (2) Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Ccmmission Washington, D. C. 20555

• I i