ML20217A199

Monthly Operating Rept for Oct 1990 for Haddam Neck Plant

ML20217A199
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	10/31/1990
From:	Claffey S, Stetz J CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9011200222
Download: ML20217A199 (10)

Text

1e -ir

-* ' -~ o:  !

CONNECTICUT - YANKEE AT O MIC POWER COMPANY HADDAM NECK PLANT RRW1

• BOX 127E

• EAST HAMPTON. CT 06424-9341

=!

November 15,1990 Re: Technical Specification 6.9.1.8 .i Docket No. 50-213 : _

U. S. Nuclear Regulatory Commission

a. Document Control Desk.

Washington, D. C. 20555 1

Deat Sir:;

+ 9 In accordance with reportin ; requirements of Technical Specification 6.9.1.8, the Connecticut Yankee

. lladdam Neck Plant Month y Operating Report 90-10, covering operations for the period

' October.1,1990 to October 31,1990 is hereby forwarded. .

Very truly yours, ff John P. Stetz :

\

L. Station Diicctor = 1 JPS/va cei '(1); ' Regional Administrator, Region 1 -

U.' S; Nuclear Regulatory Commission 475 Allendale Road . i

( - . King of Prussia. PA 19406 i (2). John T.' Shedlosky . '

.. - Sr. Resident Inspector..

~ Connecucut Yankee  !

a

)

' -4

. , ., c

=, a .i".. 9011200222 901031 g)

PDR ADOCK 05000213 1o284 nty. io-87 R PDC

~ - _ - _ _ _ _ _ _ _ _ _ - - >

,{

-1 I

.-.,- .. ~

, Connecticut Yankee Atomic Power Company I b r Haddam Neck Plant ,

'I k I Haddam, Connecticut .

l t y 1

?

q t.

's i , 1 1

,i:  !

kt

'?

j i

. i. ' . .

1

, j i

-- [ <

I '- -

+

i i

?

k-4

,[ ,', f # ..,

il < s! 1 i

Monthly Operating Report No. 90-10 i

4 -

For The Month of October 1990 1

)

Plant Operations Summarv - October 1990 The following is a summary of Plant Operations for October 1990.

On October 1st at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant was operating in Mode 1 at 100% power.

On October 27th at 1442 hours0.0167 days <br />0.401 hours <br />0.00238 weeks <br />5.48681e-4 months <br />, a load reduction was commenced. The #3 & 4 Containment Air Recirculation (CAR) fan coolers were declared inoperable due to fouling of their tubes. At 2(M5 hours, the plant was in Mode 3, Hot Standby.

' On October 28th at 0226 hours0.00262 days <br />0.0628 hours <br />3.736772e-4 weeks <br />8.5993e-5 months <br /> Mode 4, Hot Shutdown, was entered. By 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> Mode 5, Cold Shutdown, was reached.

The plant remained in Mode 5 the remainder of the month for CAR cooler cleaning and plugging of one Steam Generator Number 2 tube.

h

,* I S  :

AVERAGE DAILY UNIT POWER LEVEL  !

t l

t DOCKET NO. 50-213 f Conn. Yankee UNIT Haddam Neck 1

f DATE.10/90 COMPLETED BY S. F. C1affey ,

TELEPHONE _ (203) 267 3650 :  ;

MONTH: OCTOBER:

I DAY . AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL' (MWe-Ne t) ~

'(MWe-Net) l'- 569' 17 579 2

i 569 18 579 3 1571 579 19 R- [4 '570 20- 582 1 572;

- . 5? _ 21' 583 6: 571 22 ~583

)

7'- 570 .583 23'

8> 5741 582'-

w. :24 .i

9- 571' 25_ '583 ,

o '10 368 26 su Lil:, -

568 27 '406 I J

12; s7n' 28 0 r13 L573 - 0 29

.14 s 573 - '30 0  !

} .d 15. , 573?-

31 0 '

_s

. ' 16 '~ -578 ~

m 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. i s

(9/77)

MAINTENANCE 10/90

.SYSTEN EFFECT ON CORRECTIVE ACTICBI' SPECIAL~PRFfAIITIONS OR MALFUNCTIObl SAFE ..TAEEN TO PREVEllT- -TAKEN TO PROVIDE COMPoblEblT CAUSE RESULT OPERATICII EEPETITICII - FOR REACTOR SAFETY

, . .DURIlb PEPAIR Containment Air Excessive Debris Filters' plugged Improve.related proce'dures Shutdown, clean filters Recirculation Fan and coolers Service Water Filters Steam. Generator Improper Gaskets Minor Leakage Installed proper gaskets, Shutdown and replacement of manway cover.6. corrected problem in of all Steam Generator procurement system manway gaskets 4

k p p -

. . /

_- ,. ~,n.

1; I !% 9 , 1l . -

1 i; ill ,.

t! , ,

+ t i.  % I Ot f rT c hoeh t e rp e C S o or O Y bmI r e MOS

. e o & t rRT r nCaw t

0 E be M M hfl r E 1

9or oee N 9 f in T

0 t o e

m s

C A

U

. S I E M &

A C t

^

L F

U N 1 0

. C /

T 9

~

I

~ O 0 N

R

m. E w S U

L T

O E P F ESF RAF

_ AFI TET I

O k

)

N N

[ ;~ ,'

A

'T RER K N

, ENW P

ETT TOI I V TPE

. IR OEA NVC q'  :

ET NI TO N

w

,,e v*'

DFTS UOAP RRKE I EC MRNI CE A ATL RCO ET P POPR AREF I Df RSVA I AI I FDT EEI T O Y N S

~

t i st j n ,

.l, '

' ' ' ~ '

CONNECTICUT YANKEE REACIOR COOLANTDATA MONTH: OCTOBER 1990 4

-j

. i REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM L pH @ 25 DEGREES C 5.76E+00 6.36E+00 6.53E+00 [

L CONDUCTIVITY (UMHOS/CM) 9.72E+00 1.71E+01 2.18E+01;

.l CHLORIDES (PPM) . <5.00E-02 <5.00E-02 L <5.00E-02  :;

DISSOLVED OXYGEN (PPB): <5.00E+00 <5.00E+00 <5.00E+00 - 1 7

s LBORON (PPM)! 9.32E+02 - 1.05E+03 'l.59E+03 .J f LITHIUM (PPM)  : 7.84E-01 1.70E+00 - 1.97E+(X)

, - TOTALGAMMA ACT,(UC/ML)- 3.79E-01 ' 9.67E-01 4.96E+00 -

' IODINE-131 ACT. (UC/ML) - .

3.14E-03 7.66E 1.28E+00 1

I 131/I 133 RATIO . ' .1.15E+00 7.75E+00 1,17E+02 (CRUD (MG/ LITER) <1.00E-02 1.00E-01 3.00E+00 ,

iTRITIUM (UC/ML)- 7.61E-01 1.33E+00 1.83E+00 ,

l 1 L HYDROGEN (CC/KG) 4.97E+00 ' 2.05E+01 2.98E+01.

& y t

t ';  :- .

• fC .

AERATED LIQUID WASTE PROCESSED (GALLONS): .1.68E+05 - f

!e , ( WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS): - 7.00E+04 o p 1

7. AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE): 5.90E-01 J i--

PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE): 4.30E 02.

f 5 k

i >

f r

62 , - , . - - - - - - - _ - - - - . . _ _ _ _ - - - - - . - _ . - - -'

_ _ _ _ _ _ _ - - . _ _ _ - - _ - - - - - - . _ - . ~ . - . . -- - - - -

~l

, i

.i r NRC OPERATING STATUS REPORT Haddam Neck

% 1; Docket: 50 213i ,

c 2. Reporting Periodi 10/90' - Outage + On line Hoars: 102.0 + 643.0 = 745.0

{

3. Utility contact: J. Stanford (203) 267 3635 .;

i : 4. Licensed Thernet Power (MWt): 1825

.$.' Nameplate Rating (Gross MWe): 667.x 0.9 = 600.3 .j 6.' Design Electrical Rating (Net MWe): 582'

7. Mexisue Dependable capacity (Gross MWe): 591.8.

8. Maxlaun Dependable Capacity (Net MWe): 565 .

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

]

- 10. Power level to which restricted,.lf any (Net MWe): N/A i

11. rem ons for restriction,'If any: N/A : '

MONTH' . YEAR *TO DATE CUMULAT!YE 12.' Report period hourst- '

745.0. 7,296.0 200,160.0' =l 1

13.-Hours reactor critical: 645.0 1,700.5 159,949.7 -

14, Reactor reserve shutdown hourst' O.b 0.0 1,285.0

15. Hours generator onElines. 643.0 1,479.2 153,566.9 i

16. Unit reserve shutdown hours: - 0.0 0.0 398.0 --!

• __.17.. Gross thermal energy generated (MWtH):.

14163,430.0, - 1,874,957.0 264,742,275.0 *

(

i

18. Gross electrical. energy generated (MWeH) .' 386,323.0 - $98,581.0. ~-86,691,627.0

• i 19, Net electrical energy generated (MWeH):> ,368,240.0 535,043.7; 82,358,023.7 *:

20 Unit service factor

- '86.3 20.3 76.7 j

-421. Unit.avalLablLity factor: '86.3 20.3 76.9 t

22. Unit: capacity factor.using MDC net 87.5 13.0- 74.9 -

s

l i

23. Unit.capacityfactor.using'DERnet: 2

. 84.9 - L12.6 ,70.7 J!

l

24. Unit forced outage rate . 13.6 20.t 5.7 j

- 25. Forced outage hourst.

, 101.0 --380.4= 9,356.0 I i

l

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

,j 927211f currently shutdown. . estimated startup date N/A '

f 3 , , .

4 i

'

• Cumulative values from the.first criticality-(07/24/67). (The remaining cumulative values are from the first date of lcommercist operation,' 01/01/68).

UNIT SHUTD0laiS AND POWER REDUCTIONS. DOCKET NO. 50-213 UtilT MAME Conn. Yankee -j IRTE 10/90 l COMPLETED BY K. W. Emmons l REPORT HONTR OCTOBER TELEPHONE 203-267-3654 l an aan  %

g ..

"o. D.ca a ;:- u, .o a g LER , C 5 c ,,,ce1,.

%$ $ .00 g U EFT

• 0-S3 Action to I j5 fj- jjgj { Prevent Recurrence 90-06 10/27/90 F 101 B 1 90-23 'BI- IIX ' Indication of fouling of the Containment Air

' Recirculation (CAR) heat exchangers.

Corrective action consist s of-.proceduralizing screenwell trash rack cleaning'and increasing operator awareness concerning the removal of service water Adams Filters from service.

'.1 2 3- _ .

4.

F Forced Reason:. Method:' Exhibit G-lastructionsi S Schedule'd "A-Equipment Failure (Explain)' U-Other(Explain 1-Manual. .for Preparation of-. Data-

.R-Maintenance or Test 2-Manual Scraa . Entry Sheets'for.Licenset C-Refueling ?3-Automatic Scraa. Event l Report--(LER) File-D-Itagulatory Restriction 4-Other(Explain)? (3835G-0161) o E-Operator. Training & License Examination _

F-Administrative ~ "5

,', -C-Operational Error (Explaia). _

Enhibit;-1 Same Source

~

[ _

= --

+ -

~'

l

i Ref ling Information Reauest .

_,s+< .

- l ', - Name_of facility - ,

Haddam Neck-

.- 2,  ! Scheduled date for next refueling shutdown.

l October 5,1991 ' .

- 3. Scheduled date for restart following refueling.

_. November 26,1991

4. (a) ' Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

,3 1Yes

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

Revise Section 5 of Technical Specifications to allow use of zircaloy clad fuel. Obtain an exemption from 10CFR50 Appendix K Sections I.D 3, l.D.4 and I.D.5.

o y(c) - If answer is no, has the reload fuel design and core configuration been reviewed by your. l" 1 Plant Safety Review Committee to determine whether any unreviewed safety questions

. are associated with the com reload?.

4 t (Ref LIO CFR section 50.59)  ;

y hq .n/a Y '

(d)1 If no sucli review has taken place, when is it scheduled?  !

a r n/a '  !

H5: Scheduled date(s) for submitting proposed licensing' action and supporting infomiation.

. . The exemption request will be submitted to' the NRC in October 1990. The request for license - ~

amendment will be submitted in March 1991.

6.1 .important licensing considerations associated with refueling, e.g., new or different fuel design 1 or supplier, unreviewed de'gn or performance analysis methods, significant changes in fuel 1 dejign, new operating procedures. 1 L Conversion to zirealoyyladding.

J7f 1The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

1(a) -157 , L(b), 709:

q

8'.- The present licensed spent fuel pool storage capacity and the size of any increase in licensed "

, storage capacit'y that has been requested or is planned, in number of fuel assemblies.

I 1168-L 9 .~ The projected date of the last refueling that can be discharged to the spent fuel pool assuming the L present licensed capacity.

L q

l 1996