ML19351E272

Operation Rept 122 for Feb 1971

ML19351E272
Person / Time
Site:	Yankee Rowe
Issue date:	03/23/1971
From:	YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML19351E271	List: ML19351E270 ML19351E272
References
NUDOCS 8011260430
Download: ML19351E272 (8)

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l YANKEE NUCLEAR POWER STATION OPERATION REPORT NO. 122 I

l For the Month of February 1971 l

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l, Submitted by I

YANKEE ATOMIC ELECTRIC C0!PANY 1

i Westboro Massachusetts March 23,1971 e

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This report covers the operation of the Yankee Atomic Electric Company at Rowe, Massachusetts for the month of February, 1971.

At the start of the period, plant load was 18h.2 MWe.

On February 1h at 0705 hours0.00816 days <br />0.196 hours <br />0.00117 weeks <br />2.682525e-4 months <br /> plant load was reduced to 130 MWe, and the No. 1 main coolant loop was removed from service to effect repairs to CH-V-613 l

vhich was leaking by a leak retaining cap.

A new cap vas successful in stopping the leak; and the loop was returned to service at 0937 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.565285e-4 months <br />.

Following subsequent testing of the turbine throttle valves, plant full load conditions were restored at 1050 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.99525e-4 months <br /> the same day.

One scheduled plant shutdown occurred during the period for the purpose of plant maintenance, testing and operator training.

The turbine generator was separated from the high line at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> on February 27 Following completion of the training period on February 28, the generator was phased to the high line at 1626 hours0.0188 days <br />0.452 hours <br />0.00269 weeks <br />6.18693e-4 months <br />. At 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> the reactor power level was increased to h85 MWt, this level being maintained through the end of the report period preparatory to increase to 600 MWt.

The first, Core IX vapor container air leakage surveillance period was terminated en February 2nd with normal leakhge noted. The cecond, Core IX air charge surveillance period commenced on February 3rd with normal leakage experienced through the balance of the report period.

Plant Abnormal Occurrence-There were no plant abnormal occurrences during the report period.

i Plant Load Reductions February h (llh5-1225):

Load reduction to 177 MWe for control valve exercising.

Feb ruary 10 (1145-1225):

Load reduction to 177 MWe for control valve exercising.

February 1h (0705-1050):

Plant load reduction to 130 MWe to permit removal of main coolant loop No.1 from service for maintenance; and for throttle valve exercising.

February 2h (11h5-1230):

Load reduction to 177 MWe for control valve extecising.

Plant Shutdowns Shutdown No. llh-9-71:

2/27/71 - 2/28/71, plant shutdown for plant maintenance, testing and operator training.

Total outage time: 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br />, 16 minutes, f

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' Plant Maintencnce G

' The following isla list of pertinent. maintenance. items performed by the plant staff during the month of February, 1971.

1.

The No.'s 1 and 3; charging pwnps vere repacked.

2.

The existing No.'l charging pump discharge -line relief valve, which was installed with velded end -joints, vas-replaced by a relief vcive with flanged end joints.

The-purpose of the change is to facilitate f

valve removal'for testing and'mairtenance, l.

3.

The torque multipliers used for removal of reactor head to vessel closure studs, were refurbished.

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4.

Installation has been completed of tvo new mateup pumps for the primary pumps seal vater, tank. Test operation of the pumps showed' them to. function as intended.

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During_the. February 27-28 shutdown the folleving maintenance items I

were perfonned:

a.

The. tubes-in the West water box of the main condenser were. cleaned

=l vith scraper plugs; and leak-tested. No leaking tubes were detected.

b.

The inboard gland of the No. 3 boiler feed pump was repacked.

c.

Vibration veadings were'taken of all four main coolant pumps.

All readings were normal.

Instrumentation and Control The'following is a list of pertinent instrumentation and control maintenance items performed-by the plant staff during.the month of

. February, 1971.

1.

Installation of a level indication gauge for each of the four steam generators, to be used.during periods of fill and drain, was completed.

2.

The two off-site air particulate monitors, which are maintained on a j

standby. basis for use during an accident emergency, were given their useni-annual operational checkout. Both monitors functioned' properly.

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Installation and testing of pressure indication instrumentation for the primary pumps seal vater system was completed during the period.

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Assembly and-installation of a steam generator feedvater flow-test.

integrator.vas completed.

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l Design Changes l

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Additional Sources of On-Site Emergency Power j

During the report period, satisfaction of acceptance criteria i

for the three newly installed 400 KW, h80 volt diesel generator sets was finalized.

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l The three new sources of emergency a-c power, each associated l

with an existing 480 volt station service bus, increase the on-site f

emergency power capacity in the event of loJa of both normal on-site and off-site power sources.

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One 125 volt d-c battery and battery charger has been added as I

a third source of d-c power to ensure that each diesel generator set j

has an independent starting-power source.

4 Reactor Plant Performance l

The following paraneters were determined by means of incore instrumentation:

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599.6 MWt; 526.1 F Tavg; Control Rod Group A @ 83, B,C,D, @ 87 ;

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j 1162 ppm boron.

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Minimum DNBR = 3.5 l

l Maximum Outlet Temperature = 590.8 F l

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Secondary Plant Performance i

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j Feedwater heater terminal differences were as follows:

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No. 1 = 5.5'?

No. 2 = T.1 F No. 3 = 6.4 F t

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l' The condenser performance was as follows:

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l 184.3 MWe; 1.54" Hg. B.P.; 599 5 MWt; 39.7 F C.W. in; TTD = 30.9 F; cleanliness factor = T3.6%.

Chemistry The main coolant boron concentration was reduced from 1178 ppm l

to 1043 ppm on February 27 to compensate for core depletion. The main e

coolant boron concentration was increased to 1140 ppm during the February i

27-28 shutdown period to compensate for the associated Xenon transient.

The main coolant pH averaged 5.15 during the period.

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-h-The main coolant beta-gamma specific ~ activity averaged'1.13 x 10-1 L

Juc/ml during the: period. The crud level averaged.01 ppm except-during the shutdown period when it was 0.38 ppm.

.During'the report perio'd the main coolant tritium averaged 3.92 ue/ml.

. The' iodine-131 speciffc. activity averaged 5.44 x 10 h uc/ml and

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the iodine.131/133. atomic ratio averaged 1.71, a value consistent with (tha' reported in the most previous Operation Report (No. 121), thereby

-indicating :no significant change in the magnitude of fuel clad defects during the. current period.

A crud sample for.the month-collected on February 19, had the-following radiochemical analyses: 'dpm/mg crud Cr-51

""- 5 Fe-59 6

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7.55 x'10 3.20 x 10 2.73 x 10 Co-58' 6' Co-60 Ag-110M 5

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-3.10 x 10 6.23 x'10 7 20 x 10 A main coolant. gas sample, collected on February 9, had the following radiochemical analyses: ue/cc gas 9

Xe-133 Xe-135 Ar-bl 4.85 x 10-1 1.74 x 10-1 h.08 x 10 1 6

The Mn-54 value of 3.56 x 10 dpm/mg crud reported in Operation Report No. 121 is in error, and should be corrected to read 3.56 x 105 dpm/mg. crud.

Health and Safety Waste disposal liquid releases totalled h5,828 gallons containing O.025 me of grosa beta-gamma activity and 1h5.39 caries of tritium.

Gaseous releases during th'e period totalled 508.0 me of gross beta-gamma activity. ' Secondary plant water discharged totalled 390,46C gallons containing 0.191 me.of gross beta-gamma activity and 1.089 curies of tritium.

Radiation exposure doses for Yankee plant personnel as measured by. film badge for the month of February, 1971 were as follows:

Average accumulated exposure dose:

53 mrem Maximum accumulated. exposure dose: 260 mrem j

Operations.

Attached is-a summary of plant' operating statistics and a plot J

of daily average load for'the month of February, 1971.

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.J YA'iKEE Af0MIC ELECTRIC COMPANY - OPERATING SUIGIARY Ji

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l February 1971 MONTH YEAR TO DATE

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'GrossLGeneration KWH 118,154,200' 255,213,800 11,751,085,100

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..Sta.. Service (While-Gen. Incl. Losses) '

KWH 7,088,699

15,2h0,788 763,265,813?'

1 Net Output.

KWH 111,065,501' 239,973,012 10,987,819,287 Station Service-6.00 5 97 6.50

.193,583 193,583:

-32,482,438

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- Sta. Service (While Not Gen. -Incl. Losses) 'KWH i

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Ave. Gen.': For Month (672)

KW 175,824.7 Ave. Gen. Running

.(6hh.74)

KW 183,258.7-1 PLANT PERFORMANCE _

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Net Plant Efficiency 28.94-28.96

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. Net Plant Heat Rate btu /KWH'-

11,793 11,784-11,975

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Plant Capacity Factor 95.19 97 54-7 5.41, y

-Reactor Plant Availability 96.17 98.18 84.18 c

i-i MONTH CORE IX TOTAL-

. NUCLEAR Hours Critical HRS 653.45 2,201.81 77,166.21 0

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Times Scrammed Burnup l

1 Core Avera6e MWD /ICU

'769.8h-2,558.17

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Region Average l

A.(INNER)'

751.36 2,h28.h9 19,632.16 i

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.B (MIDDLE) 917.85 3,025 15 11,767.00 C (OUTER) 624.07 2,105.34 2,105.3h

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YA!TIEE ATOMIC ELLUrRIC CO 'PANY DAILY AVE?dGE IDAD for FEBRUARY 1071

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