ML19350E287

Monthly Operating Rept for May 1981

ML19350E287
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	06/12/1981
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML19350E286	List: ML19350E285 ML19350E287
References
NUDOCS 8106170239
Download: ML19350E287 (9)

Text

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CONNECTICUT YANIGi2 ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT

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MONTHLY OPERATING REPORT NO. 81-5 FOR THE MONTH OF MAY 1981 k

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PLANT OPERATIONS The following is a chronological description of plant operations for the month of May 1981:

5/1 The plant was operating at 100 percent full pover (60h MWe) at the beginning of this report period.

Made 60-day air charly to the containment 1703 to 1745 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.639725e-4 months <br />.

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5/2 commenced load reduction at 0356 hours0.00412 days <br />0.0989 hours <br />5.886243e-4 weeks <br />1.35458e-4 months <br /> to. repair leak on gland heating steam line at south gland of high pressure turbine. Load at 50 MWe at 0850 hours0.00984 days <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br /> and repair work commenced. Repairs completed and load increase commenced at 1350 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.13675e-4 months <br />. Backwashed all condenser water boxes.

Performed turbine stop and control valve test at 18h0 hours with load at 350 MWe. Plant was at full load at 2310 hours0.0267 days <br />0.642 hours <br />0.00382 weeks <br />8.78955e-4 months <br />.

5/3

'A' heater drains pump isolated and drained for maintenance to clean suction strainer.

5/h

'B' isolated phase bus duct cooling fan out of service 1330 to 1450 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.51725e-4 months <br /> for maintenance.

5/5

'A' isolated phase bus duct cooling fan out of service 10h5 to lh25 hours for maintenance.

'A' heater drains pump suction strainer cleaned and pump returned to service at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />.

5/8 Chemistry Department reported finding boron in primarf vater system at 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br />. Flushed primary water lines to Refueling Water Storage tank. Notified by Chemistr/ Depart-ment that baron concentration in boric acid mix tank was 13.387 ppm. Load reduction com=enced at 1705 hours0.0197 days <br />0.474 hours <br />0.00282 weeks <br />6.487525e-4 months <br /> because of lov boron concentration in six tank. Finished adding 27 bags of boric acid to boric acid mix tank at 17h5 hours.

Three se.parate samples of boric acid mix tank indicate 18,072, 18,300 and 18,700 ppm at 1850 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br />. Stopped load decrease at hT5 MWe and commenced loading increase.

Plant was at full power at 2035 hours0.0236 days <br />0.565 hours <br />0.00336 weeks <br />7.743175e-4 months <br />.

5/10 Primary vater system lined up from Recycle Primary water storage tank. Primary water tank isolated.

5/1h EG-2A removed from service for maintenance at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />.

1. 2 Steam generator narrow range level failed lov, causing power spike at 1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br />. Placed #2 feedvater control in manual and restored normal level and nor=al power level.

1. 2 S/G level control repaired and returned to automatic control at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />.

5/15 Passed 55 billion kilowatts gross generation at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br />.

5/16 EG-2A tested and returned to service at 0625 hours0.00723 days <br />0.174 hours <br />0.00103 weeks <br />2.378125e-4 months <br />.

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5/18 EG-2B removed from service for maintenance at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />.

Meterologict1 tower and environment data out of service at 1311 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.988355e-4 months <br />.

Construction cut cable.

5/20

' A' Auxiliary steam generator feed pump out of service for maintenance 0905 to lh55 hours. EG-2A tested and returned to service at 0920 hours0.0106 days <br />0.256 hours <br />0.00152 weeks <br />3.5006e-4 months <br />.

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5/21

'B' Auxiliary steam generator feed pump out of service for maintenance 06k5 to 1055 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.014275e-4 months <br />.

5/22 Started draining primary water storage tank 5/26 Completed draining and flushing of FWST.

Commenced refilling primary water storage tank.

5/27 1 B RHR pump out of service for maintenance 0430 to 1405 hours0.0163 days <br />0.39 hours <br />0.00232 weeks <br />5.346025e-4 months <br />.

1 A RHR pump out of service for =aintenence 1422 to 1454 hours0.0168 days <br />0.404 hours <br />0.0024 weeks <br />5.53247e-4 months <br />.

5/28 Met tower data in Control Room returned to service at 1425 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.422125e-4 months <br />.

Slurried B ion exchanger Primary water tank refilled, tested by Chemistry Department and returned to service.

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EFFECT SPI:CIAL PREC.u'TIONS SYSTD1 ON' CORRECTIVE ACTION TAKEN TO pR0'lIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPONENT.

CAUSE RESULT OPERATION REPETITION DURING REPAIR N3. 2 Feed Reg.

Binding in valve Improper opera-None Replaced faulty parts None required Valve positioner -

tion of valve Reason unknown, positioner which but probably could have failed i

related to erraticat a later date, valve movement Sterm generator Span adjust cir-Loss of Narrow None Replaced wirewound resistor Constant operator

1. 2 level Trans-cuit wirewound rante icvel with carbon resistor which monitoring of citter (Narrow resistor failed indication and is less susceptible to this wide range level.

range) due to age and automatic feed-type of failure.

beat.

water control J

Loop 3 AT increase Cause unknown -

Increase of loop None None Loop 3 in defeat problem went 3 AT indication away after check-and low pressure i

ing RTD values.

scram setpoint i

Loop 4 Tavg Partial failure of tnerease of loop None None Loop 4 in defeat j

increase RTD for unknown 4 Tavg and low reason pressure scram setpoint 4

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C-CONNECTICUT YANKEE REACTd'R'CODEANT DATA

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MONTH: MAY 1Y81 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM PH 0 25 DEGREES C 6.15E+00 :

6.42E+00 :

6.62E+00 :

CONDUCTIVITY (UMHOS/CM) 9.75E+00 :

1.22E+01 :

1.84E+01 :

CHLORIDES (PPM)

<4.00E-02 : <4.00E-02 : <4.00E-02 :

DISSOLVED OXYGEN (PPB)

<5.00E+00

%5.00E+00 :

<.5. 0 0 E + 0 0 ;

3.10E+02 :

3.52E+02 :

4.64E+02 :

BORON (PPM)

LITHIUM (PPM) 8.OOE-01 :

1.15E+00 2.00E+00 :

TOTAL GAMMA ACT. (UC/ML) 9.41E-01 ;

3.50E+00 ;

4.34E+00 10 DINE-131 ACT. (UC/ML) 1 71E-02 :

1.98E-02 :

3.24E-02 :

I-131/I-133 RATIO 7.21E-01 :

7.64E-01 :

8.25E-01 :

GNUD (MG/LilEN)

%1.00E-02 ;

<s 1. 0 0 E-0 2 ; <1.00E-02 :

TRITIUM (UC/HL) 2.02E+00 :

2.39E+00 :

3.30E+00 :

HYDROGEN (CC/KG) 2.23E+01 :

2.51E+01 :

2.6SE+01 :

AERATED LIQUID WASTE PROCESSED (GALLONS):

6.70E+04 2.19E+04 WASTE LIGUID PROCESSED THROUGH BORON RECOVERY (GALLONS):

j AVENAUE FRIMARY LEAN NATh(GALLUNS FEN MINUIL);

2.d4E-01 0.00E+00 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):

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AVERAGE DAILf UNIT POWER LEVEL DOCKET NO.

50-213 Conn. Yankee UNIT Haddam Neck DATE June 12, 1981 COMPLETED BY Reactor Engineering TELEPHONE (203) 267-2556 ENTH.

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

(MWe-Net) 579 1

17 576 290 2

18 575 579 576 3

19 578 576 4

20 576 5

21 577 575 6

22 566 7

23 576 573 576 25 04 568 10 26 575 567 g

574 12 28 563 13 29 563 575 575 563 14 30 576 563 15 31 576 16 INSTRUCTIONS On this format, list the average daily unit power Icvel in MWe-Net for each day in the reporting month.

Complete the nearest whole megawatt.

(9/77)

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4 50-213 UNIT Silull:0WNS AND h0WER REDUCTIONS DOCKET NO.

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UNIT NAME Conn. Yankee DATE.Iune 12.-1981_

i May 1981 COMPLETEll i Y -Reactor Engineering 1(EPORT MONTil jgtgg.IIGNE (203) 267-2556 i

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Emluhis G. Instanttiimis A 1:ilni nnent FailiueIl.> plain) 141 annat

f. e P,cpasannoi ni Data jg 5 St.vJuled i

Il Maintenance os Test 241 annat Serain.

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// JOB 0000011!!!

// IEQ BOS FI Ol esseeNRC OPERATING STATUS REPORT COMPLETED BY REACTOR ENGINEERINGenees 6

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UNIT NAME.... CONN. TANKEE ATOMIC POWER CO.

DOCKET N3.

50-213 2.

REPORTING PERIOD....Itw 1981

_..DATE.... JUNE 12, 1981 I3. LICENiED THERMAL POWER (MWT)... 1825 COMPLETED B).... D. ANDERSON, luiACTOR EMG.

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NAMI5 LATE FATINGlGP3SS MWEl... 600.3 TELEPHONE (203) 267-2556

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LESIGN ELECTRICAL RATING (NET MWE)... 590

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MAllMUM DEPENCABLE CAFACITT(CROSS NWE)... 582 7.

MAI! MUM LEPENDALLE CAPACITTINET MWE)... 555

,,8.__ IF CHANCES OCCUR IN CAPACITT RATINGS (ITEMS 3 THROUGH 7)SINCE LAST REPORTe CIVE REASONS.... NONE _ _, _,, _.

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PCWER LEVEL TO WHICH RESTRICTED.

IF ANT (KT MWE).... HONE

,.10.. REASON f0R RESTRICTION.

IF ANT.... N/A

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THIS REPORTING PERIOD TR. TO DATE CUMULATIVE TO DATE

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.11.__ HCURS IN REPORTING PERIOD 744.0 3623.0

'17599.0 m

.J 12, ___ NUMBER OF HOURS THE FEACTOR WAS CR'TICAL __

744.0 3615.1._.. _... __. 101587.7 e.._ ____..

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REACTOR RESERVE SHUTDOWN HOURS 0.0 9.1 1192.5 e g

~14 HOURS CENERATOR ON LINE

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744.0

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97127.0 e 15, UNITRESERVESHi[TDOWNHOURS

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0.0 373.7_

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CROSS THERMAL ENERGT CENERATED (MWH) 1336224.

6442496.

167993879.

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CROSS ELECTRICAL ENERCT CENERATED (MWH) ~~~ 439257. ~ ' ~ ' ~ ~ ~ ^ ' " ~ 2133694

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55236892.

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.18 NET ELECTRICAL ENERCT CENERATED (MWH)...__. 419612..._._...___ _ _

_. 2037219.. _ _..

_.....52554827.

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UNIT SERVICE FACTOR 100.0 99.5 62.6 e e

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UNIT AVAILABILITT FACTOR 100.0 99.5 82.9 e

..... _. J 21 UNIT CAPACITT FACTOR (USING MDC NE*il. _.

_ _ _101.6 101.3. _ _ _

82.5 e.....,_ _

t 27 UNIT CAPACITT FACTOR (USING DER NET) 97.2 96.9 76.3 e i

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WIT FORCED OUTAGE PATE v.0 0.5 6.7 =

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SHUTDOWNS SCHEDULED OVER NCIT 6 MONTHS (TTrEeDATE AND DURATION OF EACH).... REFUELING FOR CORE 11. APPROXIMATELY SEPTutBER 26 1981 FOR.SIX VEEKS,~~1

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'5, IF SHUTDOWN AT END 0F REPORTING PERIOD ESTIMATED DATE OF STARTUP.... N/A

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UNITS IN TEST STATUStPRIOR TO COMMERCIAL GPERATIONI....NOT A*PLICABLE.... NOT APPLICABLE Z

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("""1_____eS!NCEDATEOFCOMMERCIALOPERATION1-1-68

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Naine Cf facility

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Connectics.t Yankee Atomic Pouer Company Scheduled date for next refueling shutdown.

s September / October 1981 L Scheduled date for restart following refueling

,2pproximately six to eight weeks.'

I 4,

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

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 relor.d fuel design and core configuration been reviewed by your Plant Safety Review Cc=mittee to determine whether any unreviewed ' safety questions are associated with the core reload

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(Ref.10 CFK Section 50.59)?

Whtn 'the above stated docu=ents are received from the fuel vendor they will be

.r; viewed in accordance with 10CFR50.59 to <!etermine if any unreviewed safety ;,

qu2ations are associated with the Core reload.

(d)

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

NlA

$. Sch2duled date(s) for submitting proposed licensing action and supporting information.

l Th;re are no scheduled dates because of (4) above.

Important licensing consideration 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

p. Tha nu=ber of fuel assemblies (a) in the core and (b) in the spent fuel I

cc rage pool.

1 (c) 157 (b) 38'9 D..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 assc=blics.

1168

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The projected date of the Inst refueling that can be discharged to the spep 7~'9-a fuel pool assucing the present licensed capacity.

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