ML20043A113

Monthly Operating Rept for Apr 1990 for Haddam Neck Plant

ML20043A113
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	04/30/1990
From:	Debarba E, Wall K CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9005180070
Download: ML20043A113 (10)

Text

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CONNECTICUT YANKEE ATOMIC, POWER COMPANY HADDAM NECK PLANT,

j

'S RR41

• BOX 127E

• EAST HAMPTON. CT 06424-9341 '

j May 15,1990

l Re: Technical Specification 6.9.1d

. Docket No. 50 213, j

i U. S, Nuclear Regulatory Commission Document Control Desk '

- Washington, D. C, 20555 q

Dear Sir:

l In accordance with reportin,; requirements of Technical Specification 6.9.1d the Connecticut Yankee I

' ~

]

lladdam Neck Plant Month' y Operating Report 90-04, covering operations for the period -

April 1,1990 to April 30,1990 is heirby forwarded.

y Very Truly yours, W

E. A.DeBarba l

Station Director Dini/mdw e

cc:

(1)

Regional Administrator, Region 1 j

U. S. Nuclear Regulatory Commission j

475 Allendale Road,

King of Prussia, PA 19406 j

u (2)

John T. Shediosky j

Sr. Resident inspector l.

Connecticut Yankee l

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' Plant Oneratinne Summmev. Anril 1990.

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The following is a summary of Plant Olwrations for April,1990c The 15th refueling and maintenance l

. outage continued for the month of April.

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' SYSTEM EFFECT ON CORRECTIVE ACTION SPECIAL FRECAUTIONS OR MALFUNCTION SAFE TAKEN TO FREVENT TAKEN TO FROVIDE--

COMP 0tfENT CAUSE RESULT OPERATION REFETITION FOR REACTOR SAFETY DURING REFAIR IThere were no reportable items for I&C for the 4

month of April,

'1990.

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s AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-213 Conn. Yankee i

UNIT Haddam Neck DATE 4/1/90 ~

COMPLETED BY K. C. Wall l

' TELEPHONE (203) :267 3654 April j

MONTH:

l DAY AVERAGE DAILY POWER LEVEL DAY-AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net)'

1 0=

17 0

t 2-18 3

19 4

20.

5 21 6

22 7

23 8

24 9

25 10 26 11 27 12 28 13 29 14 30 V'

-15 31-16 N/

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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CONNECTICUTRYANKEE I

' REACTOR-COOLANT: DATA ~

MONTHt APRIL 1990 t

LREACTOR COOLANT ANALYSIS-HINIMUM-AVERAGEc MAXIMUM

>H @ 25. DEGREES'C' t:.4449E+00 *' 4.55E+00.t-4i63E+00 1!

!.00NDUCTIVITY.(UMHOS/CM) t 8.21E+00u!- 9.19E+00 t 9.79E+00't.

HLORIDES.(PPM)

• <5 00E-02'l' <5.00E-02 8 <5 00E-02 !i 91SSOLVED: OXYGEN'(PPB) t <5 00E+00it:<5.00E+0018. <5.00E+00'1 SORON:(PPM)y 1'=2.63E+03?!- 2.65E+03J!' 2.67E+03:3-

...ITHIUM (PPM)

.0.00E-01ot':0.00E-01-t' 0 00E-01'*~

(UC/ML)

• '12 93E-03 t'-3 75E-0311 7.50E-03'l' TOTAL GAMMA'ACT.~

10 DINE-131 ACT,'(UC/ML)

/* ) 10 00E-01't'=0.00E-01a1 - 0.00E-01

• I-131/I-133 RATIO 8

0'.00E-01

• 1 0.00E-01.3 0.'00E-01 t-i<1 00E 02 t <1 00E-021ti

,i CRUD-(MG/ LITER) 1 <1.00E-02et 1RIT1UM -(UC/ML'i t

2 07E-02 8 2.18E-02 1: ' '2 s 34E-02i t.

. HYDROGEN-(CC/KG)

. ! <5 00E+00 t <5.00E4 00E t i<5.00E+00 8 c..oco.o.....................................................-.........-

s AERATED L10VID, WASTE PROCESSED (0ALLONS)t' 2.0'6E+05' NNOTE LIQUIll PROCESSED THROUGH DCRON RECOVERY (GALLONS)1; 1.44E+05l AVERAGE PRIMARY' LEAK RATE (GALLOi48.PER MINUTE)!. O'.00E-01

-PRIMARY TO GECONDARY LEAK RATE (0ALLONS PER MINUTE)*

0.00E+00' t

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_ :7

NRC OPERATING STATUS REPORT Haddam Neck

-1. Docket: 50 213.

. 2. Reporting Period 04/90.

Outage + On line Hours: 719.0 +

0.0 e 719.0 3, Utttity

Contact:

J. Stanford (203) 267 3635

4. Licensed Thermet Power (MWt): 1825 S. Nameplate Rating (Gross MWe): 667 x 0.9 e-600.3

6. Design Electrical Rating (Net MWe): 582

. 7. Maximisn Dependable Capacity (Groot MWe): 591.8

8. Maximum Dependable Capacity (Wet MWe): 56$

l9.Ifchangesoccurabovesincetestreport,.reasonsare: NONE

10. Power levet to which restricted, if any (Net MWe): N/A-

11. Reasons for, restriction, if anys,N/A MONTH YEAR 10 0 ATE

. CUMULATIVE

12. Report period hours:

719.0 2,879.0 195,743.0

13. Hours reactor b iticall 0.0 0.0.

-158,249.2

14. Reactor reserve shutdown hours:

0.0 0.0 1,285.0

15. Houra generator on tine:

0.0-0.0 152,087.6

16. Unit reserve shutdown hours:-

0.0 0.0 398.0

17. Gross thermal energy generated (MWtH):

0.0 0.0 >

262,867,318.0

• 18; Gross wiectrical energy generated (MWeH):

0.0 0.0 86,093,046.0 *

19. Net electrical energy generated (MWeH):

2,116.1 8,151.9 81,814,828.1 *

20. Unit service factor 0.0

'0. 0 77.7-

21. Unit evaltabllIty factor 0.0

' O.'0 77.9

22. Unit capacity factor using MDC net 0.0

' O.0 76.1

23. Unit capacity f actor using DER net 0.0

- 0.0 71.8

24. Unit forced outage rate:

0.0 0.0 5.6

25. Forced outage hours:

0.0 0.0 8,975.6, L

26. Shutdowns scheduled over next 6 months (type,dete, duration): NONE

27. If currently shutdown, estimated startup date: 06/27/90 l'

L

• Ctenulative values from the first criticality (07/24/67). (The remaining cumulative values are 4 rom the first date of comercist operation, 01/01/68).

l a

UNIT SHUTDOWNS AND POWER REDUCTIONS-DOCKET N00 50-213 UNIT MALE Connecticut Yanki DATE II X C *11 April 1990 REPORT MONTH TELEPHONE 203-267-3654 in -

u l" 's ow n N7 Cause & Corrective y.S g

LER--

-,e No.

Date N

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N/A RC-Fuel XX-Continuation of Core XV-XVI Refueling.

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F Forced Reason:

Method:'

Exhibit G-Instructions S Scheduled A-Equipment Failure (Explain) -

.H-Other(Explain 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram

~ Entry Sheets for Licensee,

-C-Refueling-3-Automatic Scram Event Report (LER) File L

D-Regulatory Restriction:.

4-Other(Explain)-

-(NUREG-0161)

~

. E-Oper.itor Training & License Examination

'F-Administrative 5-C-Operational Error (Explain)

Exhibit 1 Same Source 4'

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Refueling Information Reauest l.

Name of facility 4 '

• liaddam Neck 2.

Scheduled date for next refueling shutdown.

' July 11,1991

.]

~3.-

Scheduled date for restart following refueling.

June 27,1990 i

4.

(a)

Will refueling or resumption of operation themafter requim a technical specification change or other license amendment?

Yes

'(b)-

If answer is yes, what, in general, will these be?

l incorporate the guidance provided in the NRC Generic Letter 8816. The Generic -

'l Letter addresses nmoving cycle specific parameters from Technical Specifications and -

transferring them to the technical repon supporting cycle operation.- The amendment to :

H implement these changes has been issued.

(c)

If answer is no, has the reload fuel design and core configuration been teviewed 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) n/a (d)

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

3 n/a f

5.

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

7 The TSCR was submitted to the NRC on July 28,1989.

6.

. important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or perfonnance 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) 0-(b) 858 3

8.

The pasent 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.

1996

'I

.