ML20137B626

From kanterella
Revision as of 10:53, 18 June 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Monthly Operating Rept for Apr 1978
ML20137B626
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 04/30/1978
From: Graves R, Kokoszka C
CONNECTICUT YANKEE ATOMIC POWER CO.
To: Volgenau E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
Shared Package
ML20137B401 List:
References
FOIA-85-723 CYH-78-141, NUDOCS 8511260316
Download: ML20137B626 (9)
v • d • e


Text

. _

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

. , F..

l 4

)

CONNECTICUT YANKEE ATOMIC POWER COMPANY i HADDAM NECK PIANT i

HADDAM, CONNECTICUT 2

i i

i

]

1 I

L j

i, MONTHLY OPERATING REPORT NO. 78-4 l FOR Tile MONTH OF APRIL, 1978 i

8511260316 B51119 i PDR FOIA RATHJE85-723

~~

i PDR ~

?

G -

l_ ,

r ,

_ } ~

, PLANT OPERATIONS The following is a chronological description of plant operations for the month of April, 1978.

4-1 "B" Primary Auxiliary Building Purge Fan was removed from service for maintenance.

4-7 Air charge was made to the containment building.

4-13 1A High Pressure Safety Injection Pump was returned to service.

4-18 "B" main lube oil cooler was removed from service i for maintenance and returned to service on 4/19/78.

j 4-26 During fuel movement assembly A-43 in position S-12 was stuck while trying to lift. The assembly was i later freed.

4-28 IB charging pump removed from service for seal i replacement.

4 i

I i

4 l

4 1

i J

4 4

I e

- s_ -

_. ~~

_ i

- . - . . - . - . . . . ~ . . .. .

' ~

'?

CHD4ISTRY DATA FOR MONTH OF April, 1978 Reactor Coolant Analysis Minimum Avernce Maxinn-Ph @ 250C( 2.OE-01) 6.10 E+00 6.48 E+00 6.60 E+00 Conductivity, unhos/em( 25) 1.10 E+01 1.51 E+01 2.00 E+01 Chlorides, nnm( 7 0E-02) J 3.00 E-02 < 3.00 E-02 < 3.00 E-02

" Dissolved Oxyhen, pob ( 5 0E+00)

. 0.00 E+00 0.00 E+00 0.00 E+00 Boron, ppm ( 25) 8.06 E+02 . 8.30 E+02 8.76 E+02 Lithium, pun ( 55) 9.30 E-01 1.40 E+00 1.90 E+00 Gross Derassed Act.,uCi/n1( 2,0E-02) 3.35 E-01 2.23 E+00 5.32 E+00 Todine-131,uci/m1( 35) 6.38 E-02 2.17 E-01 6.92 E-01 I-131/I-133 Ratio 2.65 E+00 2.89 E+00 3.18 E+00 Crud, ec/1( 1.0E-02) 1.90 E-02 2.48 E-02 3.70 E-02 Tritium, uCi/m1( 5.0E-02) 2.53 E+00 3.06 E+00 3.66 E+00 Hydroren,ce/kg( 2.0E+00) 2.90 E+01 3.55 E+01 3.89 E+01

. s Aerated liquid vaste processed: 5.09 E+04 gallons Waste liquid processed through Boron Recovery System: 1.04 E+04 gallons Average primary plant leak rate: gpm Primary to secondary leak rate: 0.00 E+00 gpm e

e e

  • ~

~w _

e O e f-F* *

,g. _ =-M** sue @ e m N ==.-- - -

bYLL 1sW l'AiLL,W & 10* >

j LrrLL& -

SYSTEM ON CORRECTIVE ACTION TAKEN TO PROVIDE ..

! TAKEN TO PREVENT OR , MALFUNCTION SAFE FOR REACTOR SAFETY .'

COWO1EN'T CAUSE RESULT OPERATION REPETITION DURING REPAIR -

"B" Charging Pump Failed seal Excessive Seal None Replaced seal None - other rafety Leakage train in service .

"A" Safety Injection Broken Wear Excessive Drag None Rebuilt Pump None - other safety .

Pu=p Rings training in service'

't i

. ' i y) b I

I G

9 i ..

t

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

OPERATING D ATA REPORT DOCKET NO 50-213 DATE May 12, 1978 COstPLETED BY .C.A. Kokoszka TELEPilONE 201-267-2556 OPERATING ST 4TUS Connecticut Yankee Note 5

' l. Unit Name:

2. Reporting Period: At> ril . 1978
3. Licensed Thermal Power i3thtl: 1825
4. Narr.eplate Rating # Gross Stue3 600.3
5. Design Electrical Rating iNet 31 Wet: 575
6. Stasimum Dependable Capacity iGross Slw en: 577
7. Stasimum Depen Jable Capacity Net \lhei: 550 S. If Chantes Occur in Capacity Ratings a ttems Number 3 Through 71 Since Last Report.Gne Re2>ons: -

None

9. Power Lesel To Which Restricted. If Any tNet 31We : None I
10. Reasons For Restnerions,if Any: None ,

J This Month Yr..to Date Cumularise

11. Hours In Reporting Period 719.0 2879.0 90,551.0
12. Number Of Hours Reactor was Critical 715.9 2805.9 77,843.2

, 13. Reactor Resene Shutdown Hours 0.0 55.6 813.3

14. Hours Generator On Line 713.4 2705.7 73,753.1
15. Unit Resene Shutdown Hours 0.0 74.8 74.8
16. Gross Thermal Ener2y Gerersted sslWH, 1,284,573 4,734,358 126,556,917 17 Gross Electrical Energy Generated isthH, 424,723 , , ,

1,562,853 41,657,152

18. Net Electrical Energy Generated t3thH) 405,908 1,489,821 39,617,285
19. Unit Senice Factor 99.2 94.0 81.4
20. Unit Availability Factor 99.2 96.6 81.5
21. Unit Capacity Factor iCsing SIDC Net: 102.6 94.1 81.2
22. Unit Capacity Fac:or ICsing DER Net) 93.2 90.0 75.1
23. Unit Forced Outage Rate 0.8 3.1 8.4
24. Shutdowns Scheduled Oser Nest 6 slonths iTy pe. Date.and Duration of Each e:

None

+

25. If Shut Down 4: End Of Report Period. Estim ect i e ,/ s artup. s N/A
26. Units in Test Status ePrior to Commercial Opera .i s: Forecast Achioed

. INITIA L CRITICALITY (Not Required)

INITI \L ELECTRICITY CO\l\lERCI \L OPER \ TION p)f ?3 8 b . . , M i g* e

$ .'r ' ~ _ _ , _ _

[' }

L b

AVERAGE D\lLY UNIT POhER LEVEL

' DOCKET NO. 50-213.. ,

coun. auuncu tygy lladdam Neck DATE May 12, 1978 CO\lPLETED BY C.A. Kokoszka TELEPilONE (203) 267-2556 SIONT11 A gil, 1978 DAY AVERAGE D41LY POhER LEVEL DAY AVERAGE D41LY POhER LEVEL e \1We Neti e siw e.Neg i g 601- 603 37

2. 604 18 603 3 603 -

39 602 4 603 603 20 604 603 s 5  ::

6 603 603 7 604 603 33 8 604 602 24 9 603 602 33 to 603 603 3

Ig 604 602 2-12 604 g 603 13 604 603 29 14 602 282 3g 15 604 3,

16 603 INSTRUCTIONS

, On this fermat..ist the nerage jaily . inst c e :eselin MWe. Net i.or ca.h Jay :n the rep.. ang :n.. nth. C :r.r,te -

the neares: whoie me;2 rat: ,

g00 $

~

. ==-,_.

9 .

- _ . m. "" -

, m---

. n --_ . - . - - _ _ --_dt______-_--_=-_---_--- _ - - _ _ - _ . -

, 00CKE! NO. 50-213 .

. IlNil SiltJ1 DOWNS AN 1 POWER HEDtic110Ns Conn. Yankee .-

UN11 NAME IIA 1E May 12. 1978 COMt.l.i. l g l3 igy c.A. vnyny,y, HI:l'UH I MON g gg April. 1978 ( 20 D 26'/-25 56 e f l.l.l.I'llON E

e. re i u. =

1e r 7s4 I ncnsee ge, ti 't raine a husettive Na llJte h, ~? 4 2sE 1. vent u? g'i E Asii..n i.i

$2 cE 55C! llepint 8' EU 5' l'seveni Heeussense

< u 6

I i-8 78-04-30 F 5.6 H 3 While bringing an isolated loop ,

into service the #2 S.G. experiencec i a mis-match of steam flow with l feed flow coincident with low flow

. in steam generator.

e

  • - 1

'o

't I

i I j 1 4 I. l ' ..is cJ l{cau.n. f.let'niil: i sliilut I; . :nsisuiti.m '

, 5 S.licduled A l .inspment I ailnic tl.splaint I Matinal 1.'s Prepaute..n .I 134r4 II kl.iintenance n les .' klannat Scram. I nie3 Slicch I.o I a.cmec ~

l' l(cIncinig I Antinnatic Strani. I sen Hepine il 11(II ole (NitR: G.

, l} Hrpil.iting Rcstilition 4 Ollice (!!aplanil tiltil i I tspeus.. lunung A I a.cnse I uniinaison I tinanntiair.c 5

6. Ilyreali.nial I si.o il, splatiil I s!.il it I h.inic %.ne.c l.sf 8 8) ll Oilice ll splanil ,

I s

_ _. w

. _ _ _ _ ,  ;. ~ ___ -

.,a . , . ~ -

RErtlEl.INC INFORMATION REQtlEST

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

February, 1979 .

3. Scheduled date for restart following refueling.

Approximately six wecks from shutdown date.

~

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

No. Connecticut Yankee Technical Specifications are reload independent.

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

  • - N/A 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)? '

. Yes, se'e answer to 4 above 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. ,,

Thcre are no scheduled dates because of (4) above.

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.

. None

7. The number of fuel assemblies (a) in the core and (b) in the '

, spent fuel storage pool.. -

(a) 157 (b) 288

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 assemblics.

1168 s

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

1994 or 1995 0

~

.m

_ . . _ Am. -

. ..~ _ . _

4 < .*

CONNECTICUT VA N K EE AT O M I C POWER COMPANY HADDAM NECK PLANT C'd A RR # 1. DOX 127E. EAST H AMPTON. CONN. 06424 May 12, 1978 CYli-78 141 Docket No. 50-213 Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 ATTENTION: Mr. Ernest Volgenau

Dear Sir:

In accordance with reporting requirements the Connecticut Yankee Haddam Neck Monthly Operating Report 78-4, covering operations for the period of April 1, 1978-to April 30, 1978 is hereby forwarded.

Very truly yours, '

g,<. R. 11. Graves Station Superintendent RHG:QB/mts Enclosures cc: (1) Director, Region I Division of Inspection & Enforcement U. S. Nuclear Regulatory Commission 631 Park Avenue '

King of Prussia, Pennsylvania 19406 (2) Director, Office of Management Information and Program Control

. U. S. Nuclear Regulatory Commission Washington, D. C. 20555 1

l j

/,

d l

M .w- s e.. .e,.--. - - - -~- - - -

Retrieved from "https://kanterella.com/w/index.php?title=ML20137B626&oldid=2835522"