ML20211P743

Monthly Operating Rept for Nov 1986

ML20211P743
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	11/30/1986
From:	Dean C, Graves R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8703020426
Download: ML20211P743 (10)

Text

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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT i

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' MONTHLY OPERATING REPORT NO. 86-11 FOR THE MONTH OF NOVEMBER 1986 0703020426 861130

PDR ADOCK 05000213

R PDR

PLANT OPERATIONS The following is a summary of plant operations for November 1986:

The unit conducted a routine turbine valve test while at 65% power on

. November 1 at 0404 hours0.00468 days <br />0.112 hours <br />6.679894e-4 weeks <br />1.53722e-4 months <br />. The test was completed at 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br />. The plant returned to 100% power on November 2 at 0550 hours0.00637 days <br />0.153 hours <br />9.093915e-4 weeks <br />2.09275e-4 months <br />.

The plant commenced a load reduction on November 18 at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> to repair the #2 steam generator feed regulating valve positioner. The unit returned to 100% power at 1745 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.639725e-4 months <br />.

The unit continued operations at full power until November 30 at 1626 hours0.0188 days <br />0.452 hours <br />0.00269 weeks <br />6.18693e-4 months <br /> when the plant automatically tripped due to a steam generator feed flow / steam flow mismatch / coincident low steam generator level while performing maintenance on instrumentation used to control the #3 steam generator feedwater regulating valve.

- e INSTRUMENT & CONTROLS EFFECT SPECIAL PRECAUTIONS NOVDiBER 1986 SYSTD1 ON CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPAIR Wide Range Gas Failure of the Not able to n/a In general, this has been Alternate monitor Monitor photomultiplier continuously a very reliable piece of in: service.

tube and high monitor stack equipment and, therefore, voltage power gas activity, no other action is supply. considered necessary.

Feedwater System Shorting out Loop #3 feed- n/a Reviewed work practices n/a of 10 volt water control related to planning and power supply to valve closed execution of maintenance automatic and causing reactor activities, manual control trip due to low stations, steam generator in coincidence with a steam flow / feed mismatch.

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I MAINTENANCE -

EFFECT SPECIAL PRECAUTIONS SYSTEM NOVEMBER 1986 ON CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPONENT CAUSE RESULT OFERATION REPETITION DURING REPAIR There are no raportable items for the month of November.

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t_ . y 5 t g AVERAGE. DAILY UNIT POWER LEVEL

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<f l DOCKET NO. 50-213

/ Conn. Yankee UNIT Haddam Neck

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DATE December 15, 1986 f..-- ..

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COMPLETED BY C. B. Dean '

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TELEPHONE (203) 267-2556 i MONTH:; NOVDIBER 1936 '

DAY' EE$ RAGE DAILY POER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) fr i g . _ 1.-

/ 409 17 561

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,t' 2 r 555 18 557 1  ;

3 ' f 559 19 561 1

i 559 20 561

(/4/ 559 561 5 21 6 ,

560 22 560

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y 7 560 23, 561 560 560 8 24 k

560 560 9 ,

25

, 560 561 x 10 26 T

, b4 560 g 560 11

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560 i 12 562 28

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\*' 560 560 29

. 0ii[13 g

i Ut ' 14 561 30 377 t

15 561 31 n/a 16 561 i t 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)

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o CONNECTICUT YANKEE REACTOR COOLANT DATA MONTH: NOVEMBER 1986

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REACTOR C00 ANT ANALYSIS HINIMUM AVERAGE MAXIMUM e....................................................................

PH 9 25 DEGREES C 6.57E+00 : 6.65E+00 6.75E+00 :

CONDUCTIVITY (UMHOS/CM)  : 1.10E+01 : 1.36E+01 : 1.75E+'01 :

' CHLORIDES ((PPM)  : <5.00E-02 <5.00E-02 : <5.00E-02' DISSOLVED OXYGEN (PPB)  : <5.00E+00 : <5.00E+00 : <5.00E+00.1 '

BORON (PPM)  ! 6.23E+02 : 6 67E+02 : 7.46E+0?,

LITHIUM (PPM)  : 1.06E+00 : 1.23E+00 1 1.43E+00 ,1 b TOTAL GAMMA ACT. (UC/HL)  : 5.91E-01 : 8.20E-01  : 1.26E+00':

IODINE-131 ACT. (UC/ML)  : 2.99E-03 5 02E-03 : 1.04E-02 : {

I-131/I-133 RATIO  : 1.23E+00 1 67E+00 3.00E+00 :

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

TRITIUM (UC/ML) '  : 2.31E+00 2.53E+00 2.91E+00 :

HYDROGEN (CC/KG)  : 3.37E+01 3.59E+01 3.90E+01 :

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AERATED LIQUID WASTE PROCESSED (GALLONS): '

1.4LEM05 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS): 0.00E-01 AVERAGE PRIMARY LEAK RATE (GALLONS PER HINUTE): 4.45E 0.00E+00 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE)f

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NRC Operating Status Report Haddam Nec t:

1. Decket: 50-213

2. Reporting Period: 11/96 Outage + On-lir.e Hours: 7.6 + 712.4 = 720.0

3. Utility

Contact:

J.P. Drago (203) 267=2556 est 452

4. Licensed Thermal Power (MWt): -1825 5 Naseplate Rating (Gross MWe): 667 0.9 = 600.3

6. Design Electrical Rating (Net MWe): 582

7. Manisua Cependable Crpacity (Gross MWe): 595.8

8. Maxieus Dependable Capacity (Net MNe): 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 0,016.t) 165,816.0

13. Hours reactor critical: 712.4 4,520.3 140,919.7

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

15. Hours generator on-line: 712.4 4,262.3 135,064.0 16.' Unit reserve shutdoun hours: 0.0 0.0 398.0

17. Gross theraal energy generated (MWtH): 1,288,394.0 6,894,273.0 234,000,185.0 8

18. Gross electrical energy generated (MWeHl: 414,653.0 2,166,994.0 76,697,861.0 t

19. Net electrical energy generated (MWeH): 395,235.1 2,031,426.0 72,930,596.3 8

20. Unit service factor: 98.9 53.2 81.5

21. Unit availability factor: 98.9 53.2 81.7

22. Unit capacity # ctor i using MDC net: 96.5 44.5 80.6

23. Unit capacity fatter using DER net: 94.3 43.5 75.6

24. Unit forced outage rate: 1.1 14.7 6.0

25. Forced outage hours: 7.6 732.0 8,600.8

26. Shutdowns scheduled over next 6 sonths (type,date, duration): NONE

27. If currently shutdown, estinated starts date: 12/5/86 I Cusulative values fres the f:rst tr:ticality (07/24/67). (Ite retar-; ::: lat:ve values are frcm the first date of cosaercial cperation, 01/01/69).

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-213 UNIT NAME Conn. Yankee DATE December 15, 1986 COMPLETED BY C. B. Dean REPORT MONTH "OVEMBER 1936 TELEPHONE (203)267-2556

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No. Date - 5j m y5 y LER E Cause & Corrective e uo o ,8

• RPT. e oo Action to h ES E y UE Prevent Recurrence 5" 5 f,Eh@

• CM NO O'

O 86-11 11-30-86 F 7.57 G 3 36-044 -

IA INSTRU While trouble shooting 00 #3 steam generator level control, I6C technicians inadvertantly grounded instrumentation resultinF in an actuation of a Reactor Protection Sys-tem (Feed flow / steam flow mismatch coincident with low steam generator level). Remedial train-ing shall be the correc-tive action.

1 2 3 4 F Forced Reason: Method: Exhibit G-Instructions S Scheduled A-Equipment Failure (Explain) H-Other(Explain '

1-Manual for Freparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee 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 I

REFUELING INFORMATION REQUEST

1. Name of facility Connecticut Yankee Atomic Power Company 2 Scheduled date for next refueling shutdown.

July 18, 1987 (last day at full power)

3. Scheduled date for restart following refueling.

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 and 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

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 ATOMIC POWER COMPANY HADDAM NECK PLANT RR#1 e BOX 127E

• EAST HAMPTON. CONN.06424 December 15, 1986 Docket No. 50-213 Director, Office of Resource Management U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Sir:

In accordance with reporting requirements, the Connecticut Yankee Haddam Neck Plant Monthly Operating Report 86-11, covering operations for the period November 1, 1986 to November 30, 1986, is hereby forwarded.

Very truly yours, i

f M" Richard H. Graves Station Superintendent RHG/mdw Enclosures l cc: (1) Regional Administrator, Region 1 U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 i