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Monthly Operating Rept for Sept 1989 for Haddam Neck Plant
	ML19325C697
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/30/1989
From:	Miller D, Wall K; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 8910170190
	Download: ML19325C697 (10)
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i CONNECTICUT YANKEE ATOMIC POWER. COMPANY HADDAM NECK PLANT i

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BOX 127E

EAST HAMPTON. CT 06424 9341

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October 15,1989 -

Re: Technical Specification 6.9.1d Docket No. 50 213

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- U. S. Nuclear Regulatory Commission Document Control Desk '

Washington, D. C. 20555

Dear Sir:

In accordance with reporting requirements of Technical Specification 6.9.1d, the Connecticut Yankee

- Haddam Neck Plant Monthly Operating Report 89-09, covering operations for the period L

September 1,1989 to September 30,1989 is hereby forwarded.

Very Truly yours, f,

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Donidi B. Miller, Jr.

Station Superintendent

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,(1)-

Regional Administrator, Region 1 U. S. Nuclear Regulatory Commission 631 Park Avenue.

King of Prussia, PA 19406

(2)

John T. Shediosky e

Sr. Resident Inspector Connecticut Yankee

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8910170190 890930 PDR ADOCK 05000213

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Monthly Operating Report No. 89-09 For The Month of September 1989

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Plant Onerations Summarv - Sentember.1989 '

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. 'Ihe following is a summary of Plant Operations for September,1989.

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- The plant was operated at.97% load until September 2 at 0016 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months , at which time a nonnal plant.

shutdown for refueling was started. At 0402 hours0.00465 days 0.112 hours 6.646825e-4 weeks 1.52961e-4 months ,'the turbine generator was taken offline and the -

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. ; plant entered Mode 2.. On September 3 at 0330 hours0.00382 days 0.0917 hours 5.456349e-4 weeks 1.25565e-4 months , the reactor was s ut own an t e p ant entered' hd dh l

- " Mode 3. At 1119 hours0.013 days 0.311 hours 0.00185 weeks 4.257795e-4 months , the plant had transitioned to Mode 4. On September 4 at 0653 hours0.00756 days 0.181 hours 0.00108 weeks 2.484665e-4 months , the

. plant entered Mode 5. On September 17 at 2312 hours0.0268 days 0.642 hours 0.00382 weeks 8.79716e-4 months , the plant entered Mode 6. The plant maintained in Mode 6 for the remainder of the month.

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~ 9/89 SYSTEM EFFECT ON CORRECTIVE ACTION-

- SPECIAL PRECAUTIONS 2

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MALFUNCTION SAFE-.

TAKEN TO PREVENT ~

TAKEN TO-PROVIDE' c.

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.. RESULT OPERATION REPETIT1018

- FOR REACTOR SAFETY DURING REPAIR-u.

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There were no reportable items for the month ending September, 1989 e

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- 9/89:

SYSTEN EFFECT ON'

- CORRECTIVE ACTIONi SPECIAL PRECAUTIONS' OR.

MALFUNCTION' SAFE

- TAKEN TO PREVENT TAKEN TO PROVIDE:

' COMPONENT CAUSE-

- RESULT OPERATION REPETITION-FOR REACTOR SAFETY DURING REPAIR

, There were no-reportable I - iten.s for the month ending n

- September, 1939 i

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. AVERAGE DAILY UNIT POWER LEVEL

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LO6KET NO.-

50-213 b.,

Conn. Yankee i

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i UNIT Haddam Neck DATE i

COMPLETED BY K.'C. Wall-TELEP!IONE (203) 267 '3654 l

MONTH:

September, 1989

. DAY.

AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

'(MWe-Net)

(MWe-Net) y 1-499 17 0

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2

-47 18

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-0 19 c,3 4L 20

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INSTRUCTIONS On t.his 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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CONNECTICUTJYANKEE JR 2

-REACTOR COOLANT DATA:

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-MONTH: J SEPT: 1989-

-REACTOR: COOLANT ANALYSIS!

HINIMUM AVERAGE:

MAXIMUM G'

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PHie125 DEGREES Cs 4.54E+00 1 5.11E+00 8.88E+00-:l F

LCONDUCTIVITY?(UMHOS/CM).

6.24E+00 8 80E+00 1.90E+01 '

CHLORIDEST(PPH):

<5.00E-02

<5.00E-021:'

$N S lDISSOLVEDiOXYGEND(PPB)i

-t' <5.00E+00 : <5.00E+00

<5 00E+00 Ntx iBORONP(PPM)

- 5.00E+00't 2 34E+03.

2.68E+03't!

.LLITHIUM1(PPM)/

'4.05E-01 :

--4.40E-01 1 4 76E :

cTOTAL? GAMMA $ACT.v(UC/ML)'

1.14E-03':,

2.81E+00 :

'2.57E+014 1 l

IODINE-131 FACT.(UC/ML)--

2.82E-04 0 55E-01 :

1 14E+01~:

4 LI-131/I-133_ RATIO;:

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-2.69E+00 :

'4.85E+01.

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t 5 CRUDS (MG/ LITER)-

i 1.00E-03 :-

1.29E-04-t 1.00E-03J:-

"'TRITIUML(UC/ML)

'1.46E+00 :

1.46E+00 := 1.'46E+00

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HYDROGENF.(CC/KG)'.

2.31E+01 t'

2.31E+01-2 31E+01. -

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...... AERATED.LIGUID WASTE PROCESSED (GALLONG):

3.36E+05-m fln ~ -[W$STEJLIQUIDz PROCESSED;THROUGH BORON RECOVERY (GALLONS) < 3 92E+04-i i

m :' ' AVERAGE PRIMARYL-LEAK. RATE (GALLONS'PER MINUTE) - -4.40E '

'c' LPRIMARYf1T0fSECONDARY LEAK RATE (GALLONS PER MINUTE):

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. NRC OPERATING STATUS REPORT y

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k Haddam Neck hib n I.h("*

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1. Docket 50 213' f

2. Reporting Period: 09/89.' Outage + on line Hours: 692.0 + 28.0 = 720.0 V

f3. Utility Contact J. stanford (203) 267 3635:

4. Licensed Thermal Power (Wt):

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1825 c5. Nameplate Reting (Gross W e):L 667 x 0.9 = 600.3 K 6v Design Electri:al Rating (Net We): 582

' 7. Maxima Dependable Capacity (Gross We): 591.8

'8. Maxinam Dependable (.apecity (het W e): 565

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

10. Power level to which restrictsd, if env (Net W e): N/A.

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=11. Reasons for restriction, if any: N/A MONTH YEAR TO DATE CUMULATIVE i

it.' Rsport period hours:-

720.0 6,551.0 190,655.0

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=13. Hours reactor' critical 52.3 5,883.3 -

158,249.2

'14.. Reactor reserve shutdown hours:

0.0 0.0 1,285.0 h.L 15.lNours generator on-line:

28.0 5,059.0 152,087.6-

p.,

116. Unit reserve shutdown hours:

0.0 0.0 398.0

" [17. Gross thermal energy generated (WtH):.

44,000.0 9,466,757.0 262,867,318.0 *

' 18. Gross electrical energy generated (WeH):

.13,858.0 3,121,835.0 86,093,046.0

s 119. Net electrical energy generated (MWeH):

9,427.0 2,%3,237.6 81,829,717.5 *

- 20. Unit' service factors 3.9 89.4 79.8

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21. Unit availability factor:

3.9 89.4 80.0

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22. Unit. capacity f actor using MDC net 2.3 80.1 78.2

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23. Unit capacity factor using DER net:

2.2 77.7 73.8

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-24. Unit. forced outage rate:

0.0 0.0 5.6

25. Forced outage hours:

0.0 0.0 8,975.6

26. Shutdowns scheduled over next 6 months (type,date, duration): NONE a ' li [27.' If currently shutdown, estimated startup date: 11/16/89 N,

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Cumulative values from the first criticality (07/24/67) (The remaining claulative values are from the first date of 1 commercial operation, 01/01/68).

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UNIT SHUTDOWNS AND POWER REDUCTIONS-DOCKET NO& 50-213 -

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DATE 10/15/89 COMPLETED BYL c; mii.

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REPORT IMNTH -September, 1989' TELEPHONE 203-267 3694 -

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'n g-om m em y S - -g LER.

,s ee Cause'& Corrective <

No.

Date oa ce U$

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RPT.

E E l' Action to

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E' Prevent Recurrence.

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OM m0 0

89-03 9/2/89 S

692 C

1 n/a RC Fuel XX Core XV-XVI Refueling; d

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2 3

4 F Forced Reason:

' Method:

Exhibit G-instructions S Scheduled A-Equipment Failure (Explain) ll-Other(Explain 1-Manual for Freparation of. Data-

'B-Maintenance or Test 2-Manual. Scram Entry Sheets for Licenset.

-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

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' RCfE na Information Reauest li K j,

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1.

Name of facility.

9 Haddam Neck j

p Scheduled date for next refueling shutdown.

2.

September 2,1989 3.

Scheduled date for restart following refueling.

F November 16,1989 4.

(a)-

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Yes (b)

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

Incorporate the guidance provided in the NRC Generic Letter 88-16. The Generic Letter addresses removing cycle specific parameters from Technical Specifications and transferring them to the technical report supporting cycle operation, (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)?

n/a (d)

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

n/a 5.

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

July 28,1989 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) 0 (b) 858 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.

I168 9.

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

1996

.

ML19325C697

Text

Dear Sir:

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