Text

Monthly Operating Rept for Sept 1981
	ML20031F613
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	10/08/1981
From:	Donna Anderson; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
Shared Package
ML20031F610	List: ML20031F609; ML20031F613;
References
	NUDOCS 8110200217
	Download: ML20031F613 (11)
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT llADDM1, CONNECTICUT 1

i HONTHLY OPERATING REPORT 210. 81-9 j

FOR THE MONTH OF SEPTDiBER 1981 l

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PLANT OPERATIONS The following is a summary of plant operations for the month of September 1981:

)

The plant operated at 100 percent power until 2154 hours0.0249 days 0.598 hours 0.00356 weeks 8.19597e-4 months on September 10 when the unit was manually tripped. The trip was due to the unexplained At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months the right closing of the right hand turbine stop valve.

j hand stop valve was tested and cycled normally.

A critical approach uas commenced at 0140 hours0.00162 days 0.0389 hours 2.314815e-4 weeks 5.327e-5 months on September 11, and the unit phased on line at 0802.

Full power was reached at 1315 on September 12.

I The load' reduction for a scheduled 6 week refueling outage was started on September 25 at 2220 hours0.0257 days 0.617 hours 0.00367 weeks 8.4471e-4 months . The plant was taken off lino at 0324 hours0.00375 days 0.09 hours 5.357143e-4 weeks 1.23282e-4 months on September 26.

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A natural circulation flow test was started at 1405 and satisfactorily completed at 1630 hours0.0189 days 0.453 hours 0.0027 weeks 6.20215e-4 months on September 26.

I The normal refueling outage activities continued throughout the remainder.

of the month.

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ErjHt!ErIILUT YAtlhEE REAC10R'COOLAUT DATA t10N1 ti: SEPT 1981 MINIMllM AUFRAGF M AX IlillM READJ_Qll_Gf1GL ANT AN AL YS 7 't

>>>5.^5E+00*

6.85E+00 :

4.44E+00 PH @ 25 DEGREES C r q M ntir rT U r r'r /IMMOF/rtO 5.30E-01 L

,oniono :

7.40F+00 !

<4.00E-02

<4.00E-02 * <4.00E-02 :

DISSOLVED OXYGEN (PPB)

<5.00E+00 : :::5. 00 E+ 00 : f.5.00E+00 CHLOR 1 DES (PPM) 2. u(_'!-l 00 I 3+S E+09 9 O '+01 I

nnRnN < PPM >

6.00E-01 :

6.00E-01 6.00E-01 :

TOTAL _ GANMA ACT. (UC/ML) 1.47E-01 :

2.72E+00 :

5.27E+00 :'

LITHIUM ( F Pfi) o. i o c <> "

o o c F - O ')

+

t 17t - n1

+

ronTMe-!x4 mrr. titr nity_

6.69E-01 :

S.44E+00 :

7.32E+01 :

.I-131/I-133 RATIO

f.1.00E-02 : <1.00E-02

<1.00E-02 :

i 3. 3 f1 F - 0 1 !

", 49F-01 !

9 AOF-01 :

CRUD (MG/ LITER)

( CC /l;G )

6.11Ef00 2.49EiO1 :

3.90E401 ;

TRTTTtfM (l!r / r11 )

HYDROGEM

..................................<......+.+...+.+++++++'****

3.A1F+05 AEfuiIED f IDUIILJJADJE PROCEfiSEDiGpt LONS):

2.10E+05 WASTE LIQUID PROCESSEb THRDUGH BORON RECOVERY (GALLONS):

AVERAGE PRIMARY LEAt{ RATE (GALLONS PER MItllTE):

1.88E-01 1

^'U-A' ppyMnRy rn CFrnMn/RY I r ta D ATr t rW ! Ot!q PFry MT!U lTF )

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AVERAGE DAILf UNIT POWER LEVEL DOCKET NO.

50-213 Conn. Yankee

. UNIT Haddam Neck

'DATE Sept. 14, 1981 COMPLETED BY Reactor Engineering TELEP110NE (203) 267-2556 MONTil:

September 1981 4

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE D4ILY POWER LEVEL (MWe-Net)

(!fWe-Net) 1 555 17 554 2

555 18 555 3

557 19 556 4

558 20 555 557 1

21-555 3

554 6

556 22 556 23 -

553 7

555 24 551 g.

543 557 25 9

21 Shut down @0324 for 508 26

~

~-

core 10-11 refueling.

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11-153 27 12 508 28 13 5'54 20 14 553 30

(

15 552 31 553 l

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l INSTRUCTIONS On this format, list the average daily unit power 1cvel in MWe-Net for each day in the reporting month.

Complete the nearest whole megawatt.

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(9/77)

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50-213 DOCK ET NO. _

Ct. Yankee Atomic.

UNIT Silull:0WNS AND POWER REDUCTIONS UNIT NAME 10-14-61 DATE Don Anderson COMPLETED !sY HEPORT hl0NTil September 1981

'IE1.1.I'llONE (203) 267-2556 "i-

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Cauw & Costc6tste E

.$3 l.16esehe'*

, t, A6tsun see DJte f,

~$

,255.

livent Us '?

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$U Picvent Recusseau;c 8

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6 81-12 810910 F

10.1 A

2 N/A ZZ ZZZZZZ Plant manually tripped due to spurious right hand Turbine Stop.

to Valve closu're.

810911 g

1 81-13 810926 S

116.6 C

1 N/A ZZ ZZZZZZ Came off line 00324 on l

September 26, 1981, to initiate to.

core 10-11, Refueling..

810930 sg l

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for Pseparatmn of Data 3

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1Mamul 1.nis) Sheeis lin I nyemee 5 S.iscJufc.l A l'ipiipment I: nlme ll.splain) 2 Manual Sesam.

l sent Repini(1.1 Ril'afe(NilHl.G.

ll-Maintenance on Test 4 Aussunatic Scram.

j C.itet uelmg 4 Othes Ilimplaml 01615 D Repitai.u> Restoicehm l tlpes.itin li.su.ing, A Iiecnw l mainination I sinint I hame h. us.o

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.. - ~ ess esNRC CFERATING-STATUS REFCRT-COMPLETED BT-REACTOR-ENC!NiER!NCmee-- -- --- - -

y eenemememueue 1.

DOCFET... 50-213 0PERAT1NC 3TATUS 2.

SEPORT:C PERIO3.... JULY 1981, 4JTA0E + ON-LINE'HR.... 38.6 + 705.4 = 744.0

CCNNECTICUT YANKEE e

HADCAM NECK PLANT *'

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UTILITT CT; TACT............. 3CN A'CER3tl C03) 267-2556 EX2:3 -

- - easu neee m seeeee 4

t.lCE*.!E: Thi~~AL D0WER W T)...............................

1025

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M.-EeLATE R iT INMc0 33 NE1................ 6 67 X 0.9 = 600. 3 j

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OE!ICN ELECTRICAL ?A'I';C(NET W El......................... 500' "' - ~ ~ ~,~-

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=

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NY:P.1 IEF E*.0 ASLE C AS ACIT T (OR033 FWE).................... 53:

3.

PA11"U7 IEFEN: A3iE Ct? A0!if (hET MWE)...................... 555.

9.

' IF CHANTE3 CCCUR A27Ee 3!NCE LAST REPCRT: CIVE REASONS....NONE,

10. PCbER LEVEL TO WH:CH RESTRICTED.

IF ANT (NET PWE).........NONE

~ ~ ' ~

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~

~ ~ - ~ ~ ~ ~ ' - -

11.- REASON FCR FC3TRICT10N.

I F AN 7....................... :...N /A ~ -

3 CulfjLATIVE TO DATE l

MONTH TR'. TO DATE.

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HOUR 3 IN REPORTINC PER10J 744.0 5087.0 119063.0 e 1030'6.8 e

13. -- NU'CER CF HCURS THE REACTOR WA3 3!TICAL 70?.1-5044.2 0.0 9.1 1192.5 e 14 REACT 02. RESERVE SHUTXWN HCURS

_.__r._.

5031.4 f3*s52.4 e 15.

HOUf...CENERATOR CN LINE 705.4

- 16.- -- 95417 RESERVE STJTDOWN h00R3

' 0.0

-0.0 173.7 -

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CROS3 THER S L ENERGY CETRATED (MWH) 1244286.

8996983.

170548331.

-.s 13.

CM33 ELECTRICAL ENEFGY CENERATED (P'.H) 333330.

2942541.

56045739.

- 19.---- hET ELECTRIC AL ENEDCT CENERATED (M7:0 369723.

2807171.

~ - - - - - 53324779.

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041T SERVICE FACTCR 94.8 te.9 62.8 e 21.

UMT AVAll.AEILITY FACTCR 94.8 98.9 83.1 e r2E.-- UNIT CAPACITY F ACTOR (U51NG MDC NETI 89.5 99.4

- --" - - -- 8 2.7

7 95.1 76.5 e-23.

UNIT CAFACITY FACTOR (U31NG DER NET) 85.7 1.1 6.6

24 UNIT FCRCE3 C'JTA"E RATE 5.2

- 25;

. UNIT FORCED CUTA0E H)USS

--33.6 55.6 - -- -

6973.9 * --- - - - -

l

...._.JT20WN3 3:HEDULED CVER NEXT 6 ?.0 NTH 3(TYPEeDATE AND DURATION OF EACH).... REFUELING APPROXIMATELY, SEPTEMBEP.198 25.

Sc I F CURRENTLY S4JT D0kN, ESTIMAT.ED STARTUP CATE............................. N/A..

27.

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~ *HHNRC 0FERATING STATUS REPORT CCKtETEU LT REACTOR-ENGINEERIN0eun a

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D7.iET... 50-213 0PERATING STATU3

CCNNECTICUT TA NEE a 2.

FEr0:T 0 FEFI2D....Aucusi 1981 QUTAGE + ON-LINE HR.... 47.0 + 697.0 = 744.0

--

HADDAM NECV. PLA?.T e --

UT ILIT Y C9NT A7............. 30N AN0ERSON (20 3) 267-2556 E L o uu*eepununune r ?.

i L:CEN;ED THE: MAL FCWERtMWT)...............................

1525

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N AP EF LATE F AT ING tGR053 MWE)................. 6 67 X 0.9 = 600. 3 4.

OESIGN ELECTRICAL FATIN3(NET MWE)......................... 2 0

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MAI!rri lE EN:A3LE CAFACITT'GR053 MWEl.................... 532

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1 MAIIMU'1 DEFEND AELE CCF ACITY (NET PWEl...................... 555 *

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f 3.

i CIVE REA30fi3;..;t:0NE r?. - IF CPANCE3 GCCUR A30VE, SINCE LAST REPORT:

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( 11. REASON FCR RESTRICTION.

IF ANT...........................N/A

- ' - ~ ~ ~ ~ ~ -

- ~ ~ ~ - -

"- - ~ ~ - - ~

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10. PCWER LEVEL TO WHICH RESTRICTED. IF ANT (NET MWE).........NONE t

I TR TO DATE CUMULATIVE TO CATE l

i h0 NTH t

117207.0

744.0 5831.0 12.

HOUR 3 IN REPORTING FERIGD 5756.8 ~

~---~~ 103729.5 * --

~^

712.7-l 13. - NUM3EP OF HOURS THE FEACTOR WAS CRITICA,L---

9.1 it?2.5

0.0 14 FEACTOP RESEFVE 3HUTDONN H9)RS 5728.4 97:47.4

697.0 15.

HOUc5 CE*,ERATOR ON LINE 373.7 - -

~ - ' -

-7

- 0.0 f

r 16.

UNIT RESERVE SHUTDOWN HOUR 3 04 10:42683.

171774076,

1245675,

....a 17.

GR053 THERMAL ENERGT GENERATED (MWH) 56433500.

3335302, 392761.

13.

CR313 ELECTRICAL ENERG CEMERATED (MWH) 3180410. -

53695010.

r 19.

MET ELECTRICAL ENER0Y GENERATED (MWH)- -

373239;

~

32.8

i 98.2 93.7

' 20.

UNIT SERVICE FACTOR 93.2 G3.2

93.7 21.

UNIT AVAILA3tLITT FACTOR

'62.7 * - - - -

--- 90. 4 -

798.3 r 22.

UNIT CAPACITY FACTOR (USING MDC NET) 94.0

..l 76.5

I S6.5

' 23.

UNIT CAFACITT FACTOR (U3!NG DER NET) 6.6 e 1.8 6.3 24.

UNIT FCRCED OUTAGE RATE

-- - 7025.9 + -

-]

102.6 47.0 1

r 25. - UNIT FORCED OUTAGE HOURS 26, 1981, SIX STEEKS

'3HUTDOWN3 SCFEDULED CUER NEXT 6 MON n3(TTPEeDATE AND DURATION CF EACH)....REPUELING,. APPROXIHATELY, i.4PTEMBER 26.

27.

IF CURRENTLY SHUTDOWNe ESTIMATED STARTUP DATE.............................N/.A

- - - - - - - - - - - ~

L..- i

- - - -e31NCE CATE OF CCMMERCIAL GFERATION 1-1 68 t

l'

3_

(~'

se++NFC OFEFATU:G STATUS REr0RT COMPLETED ET REACTOR ENGINEERINCove) m 8

1.

SCO ET...51-213 0PERATINC STATU3

$ +**,m$.eem men I

g-

C5tsECTD.UT YA:.XEE a g.

FE?tFTD.3 FERIO3.... September 1981.0UTAGE + CN-LINE HR...126.7 + 593.3 = 720.0

- - -..~. a PADLAM NFCK FLANT * --

j la 2.

b3 UTILITY CONTACT..............D01 ANDEF30N (203) 267-2556 EESS m eee m ee m e m m e P

4 LICE'dED THEFMAL F]WER(MWT)............................... 1C5 t

5.

NA'EFLA'E RATIN0(GF033 MWE)................. 667 K 0.9 = 600.3 4,- DESI GN ELECT RI CAL' R ATIN0 (NET t'WE)......................... 50 -

6 r

7.

MAXIMUM DEFENDA3LE CAPACITY (CROSS FWE).................... 5 E 3.

MAXIMUM DEFENDASLE CAFACITT(NET MWE)...................... 555 l'

-9 IF CHANOES OCCUR AD0'E. SINCE LAST REPORTe CIVE REASONS....NONE-lI

10. PCWER LEVEL TO WHICH RESTRICTED.

IF AN'. (NET MWE).........NONE FEASON FCR. RESTRICTION..-IF ANT.......

..-.......N0NE t.

l g...

MCNTH YR. TO DATE CUMULATIVE TO CATE

i

?,

12.

HO'JR3 IN REPORTING PERIOD 720.0 4551.0 120527.0 e l

_13.

N'/M3ER OF HOUR 3 THE REACTOR WAS CRITICAL 608.1 6364.9 104237.6 e._ _ _.' __..._

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9.1 1172.5 *

.14.

REACTOR RESERVE SHUTDOWN HOURS 0.0 8

l 593.3 6321.7 99842.7 e 15.

HOUR 3 CENERATO'4 CN LINE

.16.

UNIT RESEr(VE SHUTDOWN H3)R3 _. _-

0.G4 0.0 373.7 -

-J

l 17.

CROSS THER*AL ENERGY CENERATED (MWH) 1051704.

11294387.

172345720.

I s

i 18.

CROSS ELECTRICAL E*4ERGT CENERATED (Mui) 337133.

3672435, 56775633.

l'

-19.

NET ELECTRICAL ENERCf CENERATED (MWal. _

320227.

3500437.

--.__.-- 54 01324 5.

_. --~~ -

j 20.

UNIT SERVICE FACTOR S2.4 96.5 F2.8 +

' ~

82.4 96.5 83.1

i 21.

UNIT AVAILA31LITY FACTOR.

']

22.

UNIT CAFACITY FACTCR (U3ING MDC NET)._. _

80.1 -

94.3 82.7

S - i 23.

UNIT CAFACITY FACTOR (U31NC DER NET) 76.7 92.1 76.5 +

. 1.8 6.6 e 24.

UNIT FORCED OUTAGE RATE 1.7 7034.0 e

~...

25-UNIT FORCED OUT' AGE HCUR3 _ _ _._ __.-

____._ 10.1 _--..____ __.._ _._

112.7 SHUTDUWN3 SCHEDULED OVER NEXT 4 MONTH 3(TYPE DATE AND DURATI0t. GF EACH).... Core 10-11 Refueling. 3epcomber - October 1981, 5 to J

26.

IF CURRENTLY SHU TDC'fle ESTIMATED STARTUP DATE.............................Novembe r 3, 1981 27.,

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i e3INCE DATE OF CGMMERCIAL OPERATION 1-1-68 i

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s RFFUELING INFORMATION REQUEST 4

1.

Name of facility Connecticut Yankee Atomic Power Company 2.

5cheduleddatefornextrefuelingshutdown.

~

Sept

ember 26, 1981 t

~

3.

Scheduled date for restart following refueling.

November 3, 1981

- 4.

(a) Will refueling or resumption of operation thereafter require a technical specification change or other license a=endment?

No technical specification changes are anticipated at this time.

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

(b')

N/A 5

(c)

If answe'r is nc, has the reload fuel design and core configuration I

been reviewed by your Plant Safety Review Co=rittee to determine

. O whether any unreviewed safety questions are associated with the

. core reload (Ref.10 CFR Section 50.59)? When documents are received from vendor they are reviewed in accordance with 10CFR50.59 to determine if unreviewed safety questions are core reload associated.

(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.

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

6.,

Important licensing considerations associated vith refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis meth~ods, significant changes in fuel design, new operating procedures.

None i

f 7.

The number of fuel aesemblics (a) in the ' core and (b) in the P

4' spent fuel storage pool.

p JA) 157 (B) 441 l

8.

W e present licensed spent fuci pool storage capacity and the size l -

of any increase in iicensed storage capacity dat hac been requested or is planned, in number of fuel assemblics.

1168

9.. ne projected date of the last refueling:that can be discharged i

to the spent fuci pool assuming the present licensed capacity.

1994 to 1995

,

ML20031F613

Text

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