ML20006E812

Monthly Operating Rept for Jan 1990 for Haddam Neck Plant

ML20006E812
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	01/31/1990
From:	Miller D, Wall K CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9002260374
Download: ML20006E812 (10)

Text

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• BOX 127E
• EAST HAMPTON, CT 06424-9?41.

l1 fI e ^ s J February 15,1990 Re: Technical Specification 6.9,ld Docket No. 50-213 .i fb ' U. S. N'uclear Regulatory Commission, ] Document Control Desk _i Washington;D. C; 20555 j 1 y

i.

Dear Sir:

1 .i' i In accordance with reporting requirements of Technical Specification 6.9.ld, the Connecticut Yankee "Haddam Neck Plant Monthly Operating Report 90-01, covering operations for the period 1l . January 1,1990.to January 31,- 1990 is hereby forwarded. .l +g o - Very Truly yours, e c-6 ' ' ~ Donald B. Mi ler, Jr.' \\! Station Superintendent'. DBM/nxlw ~ 1 Lee: (1) Regional Administrator, Region 1 9 U. S. Nuclear Regulatory Commission 631 Park Avenue - King of Prussia, Ph mi406 ~ _ 2) John T. Shediosky. ( Sr. Resident Inspector l; J ' Connecticut Yankee L w I;ll;!

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9002260374 900131 1 U, PDR ADOCK 050002 i 3 ,t). 'R P >' ' V lL \\ / r t 'f J -

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c ,. :g,. e l; V8e .ag*i ~.< o Connecticut Yarkee Atomic Power Company. s., OJ ' Haddam Neck Plant Haddam, Connecticut ,o. i: i: .\\ s Monthly Operating Report No. 90-01 ForThe Month of ? January 1990 'a' .c } f i- /,[ [j E, i

'g n Plant Onerations Summarv - Februarv.1990 [ The following is a summary of Plant Operations for January,1990. The 15th refueling and . maintenance outage continued for the month of January. D t I \\ s t, y s } 4 1 \\ q'. ) ), t ( 3 'l

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-rm SYSTEM . EFFECT ON

CORRECTIVE ACTION SPECIAL PRECMrtIWS.

OR ' MALFUNCTION SAFE TAKEN TO PREVENT ' TAKEN TO PRDWIDE' g. l. COMPONENT CAUSE .. RESULT OPERATION ~ REPETITION FOR REACTOR SAFErf I -( DURING REPAIR,. ~

)

i: j.'~There.wereno.. j; ' reportable items l~Jfor.I&C for-the . month ~ January, 1990. 't h I i i

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= ._-__,_-__e----_.-.___-.__---=---___~=___a -== r. 2-v: - ___v,~m

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~ ~ Maintenance? '2/90; SYSTEN EFFECT OII~ CORRECTIVE ACTICII' . SPECIAL FEBCAUT1055. ~ : 7 OR- . MALFUNCTION SAFE TAKEN TO PREVENT TAKEll.70 PROFIDE CENIP0HEllT.. CAUSE- - RESULT-- OPERATICII : REFETITION FOR maacTOR SAFErY DURIMC REFAIR There were no reportable items for. Maintenance for the month- -January, 1990. f n t 4 O l t. a ~~ . n r. n

Q P: 4 p 9 ;' s 5 6 p^' (

/

v AVERAGE DAILY UNIT POWER LEVEL 13,;

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m e c h s, DOCKET"NO. 50-213 N Conn. Yankee UNIT Haddam Neck [ DATE 2-15-90 -E' ' COMPLETED BY K. C. Wall TELEPHONE (203) 267 3654' . -a.. W MONTH: JANUARY : 1990 ,s DAY: AVERAGE DAILY POWER LEVEL DAY-AVERAGE DAILY POWER LEVEL, p (MWe-Net) (MWe-Net) l'- 0 17 0 v .c 4 s '2' 18 o . 19- ' ' 4 -; 20 . 5 21 6-22 7 23

.y 18 24 d

9 25 10 26 11 ': 27 { .12 28 '13 29 + 3 i <-14; 30

j 15 31

16

'I l . INSTRUCTIONS l

On tiiis format, list the average daily unit power level in MWe-Net for each day r

j ~ .in the reporting month. Cor.plete the nearest whole megawatt. o l s s a. (9/77)

w. w jg k

'f

4 = M] p;: .. n. : -- + - 4 ., ~ - p.se< f ~ 4 J g: .m

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l e,e, + 1 4 ,.t lBrh p. _y ? *,, ., 7, 0% J > ,-& g, 4 3 CONNECTICUT YANKEE-jj< r REACTOR COOLANT DATA MONTH:-JANUARY 1990 h;fY; - \\ f w.,~ JREACTOR' COOLANT ANALYSIS MINIMUM ~ AVERAGE MAXIMUM- /4 ^NP .PH e 25? DEGREES 1C 4.52E+00 : 4.58E+00 4.73E+00 CONDUCTIVITY.(UMHOS/CM) 7.06E+00 8 79E+00.: 9. t 9 c + 0 0..: ' CHLORIDES (PPM)

<5.00E-02 : <5.00E-02 :. 5.00E-02~:

-DISSOLVED; OXYGEN (PPB)

.<5 00E+00 : <5.00E+00 ; <5.00E+00 ;-

' BORON (PPM)- 2.65E+03 2.66E+03-: 2.67E+03 r 1 LITHIUM.(PPM)' 0.00E-01 : 0.00E-01 : 0.00E-.01 :- TOTAL GAMMA'ACT.' (UC/ML)

.3.82E-03 4.59E-03 :

5.idE-03 l' ' IODINE-lil ACT. (UC/ML)- 0 00E-01': 0.00E-01. 0.00E-01 : 'I-131/I-133 RATIO

. 0.00E-01

.0 M.Q1 :

0. 00E-01' ':

- C R U D' ( M G / L I T E R ).

, <1.00E+00

<l.00E+00

<l.00E+00 - .+ TRITIUM ~-(UC/ML). 2.03E-02 -2.17E-02 : 2. 361:.-D2. :

HYDROGEN (CC/KG)-

1.00E-01.: 1.00E-01 t' 1.00E-01't gg-1,....... .y .i ..d AERATED LIGUID WASTE PROCESSED (GALLONS): 9.28E+04 ui: LWASTE LIGUIDJPROCESSED THROUGH BORGN RECOVERY ~(GALLONS) .0.00E-01

i 3

TAVERAGE-PRIMARY. LEAK RATE (GALLONS PER. MINUTE). 0.00E-01 l

. PRIMARY TO SECONDARY' LEAK RATE (GALLONS PER MINUTE); 0.00E+00 1 q m \\ 1 + i t )

1l i) p os f

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0 1 -~ ~ .. ) 9.p;- w,; e 4 -{ f i ~ ~ NRC OPERATING $?ATUS REPORT-

7 s Haddan Neck

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11. Docket: 50 213 2, Reporting Period: 01/901 Outage + on-line Hours 744.0 +

-0.0 = 744,0 = 3. Utility

Contact:

J. Stanford (203) 267 3635 -4. Licensed Thermal Power (MWt): 1825

5. Nameptate Rating (Gross MWe): 667 x 0.9 s 600.3

6. Design Electrical Rating (Net MWe): $82 q

W

7. Mari::un Dependable Capacity (Gross MWe): 591.8 y

. 8. Masinun Dependable Copa lty (Net MWe): 565

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

10. Fower level to which restricted, If any (Wet MWe): N/A

% s

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

. MONTH YEAR fD-DATF ' CUMULATIVE' .12.' Report period hours: 744.0 744.0 193,608.0 .13. Hours reactor critical. 0.0 0.0 158,249.2

14. Reactor reserve shutdown hourst.

0.0 0.0 1,285.0 15' Hours'generatorlon!!ne: 0.0 0.0 152,087.6 -16. UnitLreserve s'hutd o n h'ourst' O.0 0.0 398.0 x ny.

17. Gross thermet enerJy generated (MWtH):

- 0.0 0.0 262,867,318.0 * -[18.Groseelectricalenergygenerated(MWeH):- 0.0 0.0 86,093,046.0 * ~19. Net electrical energy generated (MWeH): -2,108.9-2,108.9 81,820,U1.1

• 1 llig

20. Unit service factor 0.0 0.0 78.6-

'21. Unit avaltabillt'y factor 0.0 - 0,0 78.8: ~~22.' Unit capacity factor using MDC net 0.0 0.0 77.0 ' 23., Unit capacity factor using DER net 0.0 0.0 72.6 ,24.'. Unit' forced outage rate: 0.0 0.0 5.6

y

25. Forced outaga hours:

0.0 0.0 8,975.6 u.a '. = 26.' Shutdowns scheduled over next 6 months (type,date, duration): NONE l27. if. eurrently shutdown, estitated startup date: 04/28/90 1 .e '

• Cuautative values from the first criticality (07/24/67). (The remaining cumulative values are f rom the first date of lcommercialoperation, 01/01/68).

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, 7 . ~w3 , e ;- L. c&a - 'u. g4 m ge g& Qh hA l ⪈% 4 L- ,g youg. ." F n' E HhAg. ~Skti*V g34 !g g@Cy ~$o 5 f ' t o g' 3 n c e w ea2%T* n) n r eN 4 ee os 2 di o m nd zP Fg 1 ir n ot t wQ. e~ oo ~ >Rt= g e t u o ht nc t e pC-e eR.aA2a* p ao s t uwa sd m y rH a ehoe yo o T u( e MSDR SC C D R $6u - ? m ~g =P Ea* M O gnr= E nn, x $eeare y e " 9En,RR8= ~ m EG8 g n44Eioo"Fg. m 22ec. E88" Fe Ii5u* 'f w E?c.e 2 7251B"m4E2 np%g- = oE@^kUE YEE

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YF"8*h,4g T s F 1 n nrB" ! g iRIn^fgEm E=5.EO 7? 2% E" 7?5 REG E$?;p=. 7e4%E snE" a w ppa EEE p.C,. ~ u 7t5.En2n7". W :" ~ WR 5,2 9SaE oE-mQe p1.EE li L l j.. <Ji'

7 y = n g ". - A Refueling Ihformation Reauest. ~ .1. - Name of facility liaddam Neck 2. Scheduled date for next refueling shutdown. May 15,1991 3. Scheduled date for restart following refueling. April 28,1990 - 4. ~ (a) Will refueling or resumption of operation thenafter require a technical 'f 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 f:om Technical Specifications and 1 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 infonnation. 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 performance analysis methods, significant changes in fuel design, new operating procedures. 'No. 7, - The number of fun assemblies (a) in the core and (b) in the spent fuel storage pool. (a) 0 (b) 858 )r 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. 1996 . m L ,,:1. ' '}}