Text

Monthly Operating Rept for Feb 1981
	ML19350A888
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/12/1981
From:	; CONNECTICUT YANKEE ATOMIC POWER CO.
To:	;
Shared Package
ML19350A887	List: ML19350A886; ML19350A888;
References
	NUDOCS 8103170349
	Download: ML19350A888 (8)
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PIANT i

HADDAM, CONNECTICUT i

MONTHLY OPERATING REPORT NO. 81-2 FOR THE MONTH OF FEBRUARY, 1981 O

e 810.81703T9

PLANT OPERATIONS The following is a chronological description of plant operations for the month of February 1981.

2/1/81 The plant was at full load 604 MWe at the beginning of this report period.

2/2/81 NRC Hot Line out of service from 1540 hours0.0178 days 0.428 hours 0.00255 weeks 5.8597e-4 months to 2312 hours0.0268 days 0.642 hours 0.00382 weeks 8.79716e-4 months .

2/5/81

2 Contaiu=ent Recire. Fan out of service 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months to 1126 hou'rs for repair of bypass damper drive motor.

2/6/81 NRC Hot Line out of service 0815 hours0.00943 days 0.226 hours 0.00135 weeks 3.101075e-4 months to 1113 hours0.0129 days 0.309 hours 0.00184 weeks 4.234965e-4 months .

Commenced load decrease for condenser water box cleaning.

Load at 400 MWe at 2320 hours0.0269 days 0.644 hours 0.00384 weeks 8.8276e-4 months . Shut down "C" cire. pump at 2340 hours0.0271 days 0.65 hours 0.00387 weeks 8.9037e-4 months .

2/7/81 Commenced cleaning "C" waterbox at 0018 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

Finished cleaning "C" waterbox and started "C" cire. pump.

Shut down "D" cire. pump at 1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months . Commenced cleaning "D" waterbox at 1908 hours0.0221 days 0.53 hours 0.00315 weeks 7.25994e-4 months .

2/8/81 Completed cleaning "D" waterbox at 0720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months and started "D" cire. pump at 0756 hours0.00875 days 0.21 hours 0.00125 weeks 2.87658e-4 months .

Reduced load to 350 MWe for turbine stop and control valve test.

Completed valve test and commenced load increase at 0850 hours0.00984 days 0.236 hours 0.00141 weeks 3.23425e-4 months .

Plant at full power (606 MWe) at 1335 hours0.0155 days 0.371 hours 0.00221 weeks 5.079675e-4 months .

2/27/81 Plant tripped manually from full power due to loss of control air header and control of Feedwater regulators. Excess heat from air dryer melted soldered joint in air header. Plant maintained in hot standby.

Air header was repaired. Restart-ed #1 and #3 RCPs.

Following precritical checks, a critical approach was commenced at 1220 hours0.0141 days 0.339 hours 0.00202 weeks 4.6421e-4 months . Reactor was critical at 1353 hours0.0157 days 0.376 hours 0.00224 weeks 5.148165e-4 months . Turbine was rolled and unit phased to line at 1818 hours0.021 days 0.505 hours 0.00301 weeks 6.91749e-4 months . Load was increased to 150 MRe and holdiag for S/G chemistry at 1925 hours0.0223 days 0.535 hours 0.00318 weeks 7.324625e-4 months .

2/28/81 Commenced load increase at 0440 hours0.00509 days 0.122 hours 7.275132e-4 weeks 1.6742e-4 months . Plant at full load at 1026 hours0.0119 days 0.285 hours 0.0017 weeks 3.90393e-4 months .

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F2burcry 1981 EF5ECT SPECIAL PRECAUTIONS SYSTEM ON CORRECTIVE ACTION TAKEN TO PROVIDE' OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPONENT CAUSE RESULT

' OPERATION REPETITION DURING REPAIR Prcesurizer Press Failed capacitore Loss of indica-None Installed higher voltage None required Ch 2 in indicator tion on.Ch 2 rated capacitors power supply -

press Iteason: failure (computer backup probably caused still available; by low voltage rating on capacitors.

Control Air System' Soldered joint Turbine' Build-None C' leaned dryer retention None required Parted due to ing air pressure screen and replaced four-high air temper-low way valve.

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Reason: faulty dryer e

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CONNECTICU.' YANKEE REACTOR COOLANT DATA MONTH: FEBUARY 1981 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM 6.04E+00 :

6.27E+00 :

6.45E+00 :

PH G 25 DEGREES C CONDUCTIVITY (UMHOS/CM) 7.40E+00 :

1.25E+01 :

1.86E+01 :

~ CHLORIDES (Pen)

s4 00E-02 ; <A.vvE-02 ;

<4.vut-v-DISSOLVED OXYGEN (PPB)

<5.00E+00 : <5.00E+00 : <5.00E+00 :

5.64E+02 :

6.22E+02 :

7.11E+02 :

SORON (PPM) 7.50E-01 ;

1.17E+00 :

1 70E+00 ;

LITHIUM (PPh>

TOTAL GAMMA ACT. (UC/ML) 1.56E+00 :

3.55E+00 :

4.23E+00 :

IODINE-131 ACT. (UC/ML) 1.02E-02 :

2.16E-02 :

2 65E-02 :

7.27E-01 ;

d.4vE-v1 ;

1 0vtivu 1-131/1-133 XA!iu CRUD (MG/ LITER) 4.20E-02 :

4.44E-02 :

4.64E-02 :

3.68E+00 :

3.95E+00 :

4.47E+00 :

TRITIUM (UC/HL)

'.48E+01 :

2.72E+01 :

3.17E+01 (CC/XG)

HYD,ROGEN l

AERATED LIQUID WASTE PROCESSED (GALLONS):

6.66E+04 WASTE LIQUID PROCESSED THROUGH BURUN RECOVER 1<GsLLONS)*

3.92E+04 2.33E-01 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):

PRIMARY TO SECONDARY LEAK RATE (GALLONS PE' MINUTE): 0.00E+00 l

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-213 Conn. Yankee i

UNIT _Haddam Neck DATE_3 /12/81 COMPLETED BY Reactor Engineering TELEPHONE (203) 267-2556 MONTH:

February 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 580 1

575 17 581 2

576 18 581 3

577 13 581 4

577 20 b

582 5

576 21 583 6

565 22 581 7

370 23 582 8

477 24 582

.9 579 25 10 579 26 581 11 581 27 242 12 581 28 443 13 580 29

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14 580 30 15 580 31 16 580 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.

(9/77)

KET O' UNIT Sl!Ull: OWNS AND POWER REDUCTIONS c

Y nkee

, pA E T/IT/El I)AT E COMPl.ETED isY Reactor Engineering

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i-REPORT MONTil Feb 1981 11.1.1.PiladE (20 0 g67-2W_t I

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0 11 N/A F/A zz rzzzzz Reduced load to 65% power in' order to clean main condensers.

81-5 810227 F

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1 N/A zz zzzzzz Plant. trip d,ue to control air header fitting separation. Tliis caused 1

loss of,feedwater control. Plant, in turn,,was manually tripped.

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IE0 P01 FI lO m esuRC OPERATING STATUS REPORT' COMPLETED BT' REACTOR ENGINEER!NCese#5'

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UNIT NAME....CCelH. YAHREE ATOMIC H4aER C0.

DOCKET NO.

50-213

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FEF06T!MC FE0!O9 : FEBRUARY 1981

1. ~ LICEHtED THE5*AL P M P(P9T?....lPZ5

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. WeESLATE F(T!NCt(-FOSS M4E)....MO.3

~ COMPLETED BT REAcf0A ENCINEERTNO TELEPHLHE (203) 267-2556 5.

1.ES!CN ELECTRICAL RAT!NCINET MyE)... 580 6.

MAtlMUM DEFETAttE CAFPCITTICROSS MWE)... 5t;2

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MAXIMUM !EFEN[4ILE CAPACliTINET l'WE)... 555

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' ' ~ ~IF CHANCES OCCUR IN CAFAClif RATINGSillEMS 3 THROUCH 7)SINCE l AST REPORTe CIVE REASONS.... Item #6 upgraded from 577 to $82 to correspond with

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HDC NET updati fron'550'to 555 ffWe on October 1980 q

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POWER LEVEL 10 Wh!(H RESTRICTED.

IF ANT (NET MWE)....MONE 10.

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-~~EEASON FOR RE5161Cil0N. IF ANT....N/A

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'-~ --" THIS REPORTING PERIOD TR.~TO DATE

-- CUMULATIVE TO DATE- ~~

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' I I.' - HOURS IN REPOPilNC PERIOD 672. 0 ' ' ~

~ 1916.0 115392.0 e

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6 12.

OLMEER OF HOURS THE PEACTOR WAS CRITICAL 667.0

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REACIGR RE!ERVE SHUIDWN HOURS 4.5 9.1

!!92.5 e I

' I4. --~ HOURS CEt! ERA 10R ON LINE

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~~ 1399.0

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UNIT FESERVE 1HUIDOWN HOURS 0.0 0.0 373.7 16.

CF.05S THERMAL ENEGY CENERATED (MWH)

!!67710.

2461957.

164013350.

'177 CROSS ELECTRICAL EERCT CENERATED (MWH) 388233. - ~ '

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53920233.

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_ _ NET ELECTRICAL ENERCT CENERATED (MWH) 370187.

779078.

512964B6.

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tNIT SERVICE FACTOR 98.6 98.8 82.3 e D '20. ~ tHIT AVAILA91Llif FAC10R'

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UNIT CAPACITT U.CTOR (U5ING MDC NEi!

99.3 99.1 02.1 e l

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UNIT CAPACITY FACTOR IUSING IER NET) 9p.0 94.9 75.9 e D

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UNIT FORCED OUTACE RATE 1.4

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24._ SHUTDOWNS (CHEDULED OVER 74 EXT 6 MONTHSlifPEsDATE AND DURATION OF [ACH)....NONE..._

D mammmmer 25.

IF SHUILOWN AT END OF REPORi!NG FERIODe ESTIMATED DATE OF STARTUP....N/A o

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UN115 IN TEST STAittitFRIOR TO CONNERCIAL OFERAi!ON)....NOT APPLICABLE 2 m.

' _ _ *SINCE MIE 0F 'COMMERCI AL DPERATION l-1-68

-EE3CELING INFORETMEGUES;;.

1.' Name cf facility Connecticut N nkee Atomic Feuer Cocpany

' Scheduled date for next refueling shut'down.

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Septe=ber/ October 1981

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3.

Scheduled date for restart following refueling Approximately six to eight weeks.

I 4.

(a) Will refaeling or resu=ption of operation thereafter, require a technical specification change or other license amendment?

No technical specification changes are anticipated at this time.

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

N/A (c) If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Cc==ittee to deter =ine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFK Section 50.59)?

When the above stated docu=ents are received from the fuel vendor they will be reviewed in accordance with 10CFR50.59 to deter =ine if any unreviewed safety questions are associated with the Core reload.

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

N/A 5.

Scheduled date(s) for sub=itting proposed licensing action and supporting information.

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

6.

Important licensing consideration associated with refueling, e.g., new or t

different fuel design or supplier, unreviewed design or perfor=ance analysis methods, significant changes in fuel design, new operating procedures.

None 7.

The number of fuel asse=blies (a) in the core and (b) in the spent fuel storage pool.

(a) 157 (b) 38'9 8.

n e present licensed spent fuel pool storage capacity and t.he size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assc=blics.

1168

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The projected date of the last refueling that can be discharged to the spent a

fuel pool assuming the present licensed capacity.

1994 to 1995

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ML19350A888

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