ML19351E265

Operation Rept 124 for Apr 1971

ML19351E265
Person / Time
Site:	Yankee Rowe
Issue date:	05/21/1971
From:	YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML19351E264	List: ML19351E263 ML19351E265
References
NUDOCS 8011260403
Download: ML19351E265 (8)

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punyed w/ur cated f 2 I YANKEE NUCLEAR POWER STATION OPERATION REPORT NO.124 For the Month of April 1971 i

Submitted by YANKEE ATOMIC ELECTRIC COMPANY Westboro Massachusetts l

May 21, 1971 2%3 gO11260l.hh R

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This report: covers the operation of the Yankee Atomic Electric Company at Rove, Massachusetts for the month of. April, 1971.

I At the start of the period plant load was 184.6 MWe. On April 2 at 1225 hours0.0142 days <br />0.34 hours <br />0.00203 weeks <br />4.661125e-4 months <br /> plant load was reduced to 132.MWe to permit removal from i

service. of a main coolant loop and location of the source of a high, valve stem leakoff temperature.

Indications were that the leakage source was in either No. 1 or No. 4 main coolant loop. BotL loops were removed from-service, une at a time, No k.being first. The high temperature source was traced to the manual bleed valve CH-V-61h stem leakoff in the No.1 loop. Tightening of the packing gland on this valve caused a reduction in the leakoff temperature; and the loop was returned to service at 1450 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.51725e-4 months <br />.

On' April 8 a reoccurring stem leakoff high temperature necessitated plant load reduction to-130 MWe at 1140 hours0.0132 days <br />0.317 hours <br />0.00188 weeks <br />4.3377e-4 months <br /> and subsequent removal from service of the No. 1 main coolant loop for inspection. The cause of the valve stem leakoff high temperature was again traced to the manual bleed i

valve CH-V-614.

The leakoff was plugged; the temperature returned to normal; l

and the No. 1 loop was returned to service at 1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br />. During the l

balance of the period, plant load varied between 184.1 MWe and 185.2 MWe I

as the ciret'lating water inlet temperature fluctuated between 39 F and 35 F.

The-third, Core IX vapor container air leakage surveillance period was commenced at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on April 1, and was terminated April 9 with normal leakage noted. The fourth, Core IX surveillance period was 9

j commenced April 10 with normal leakage experienced through the balance of the report period.

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Two shipments of spent fuel, each containing nine assemblies removed during the Core VIII-IX refueling period, vere made during the report period. The dates of shipment were April 2 and 21.

These fuel shipments were the 31st and 32nd in the series bringing the number of assemblies shipped in the ten assembly cask to 298, and the total number of i

assemblies shipped to date to 31h.

i Plant Abnormal Occurrences l'

There were no plant abnormal occurrences during the report period.

Plant Load Reductions April 2 (1225-1535): Load reduction to 132 MWe to permit removal from service of a main coolant loop and subsequent alleviation of valve stem leakoff high temperature condition.

April 8 (1140-1520): Load reduction to 130 MWe to permit removal of No.1 l

main loop from service for plugging of the stem leakoff on'CH-V-61h; and for turbine throttle valve i

exercising.

l-l April 14-(llh5-1223): Load reduction to 177 MWe for turbine control valve 1

. exercising.

April 21 (1147-1225): Load reduction to 177 MWe for turbine control valve exercising.

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April 28 (11h5-1215): Load reduction to 177 MWe for turbine control valve exercising.

Plant Shutdowns There were no plant shutdowns during the report period.

Plant Maintenance i

The following is a list of pertinent maintenance items performed by the plant staff during the month of April, 1971.

l 1.

Preventive maintenance van performed on the incore instrumentation j

telescoping tool boom.

2.

The No. 3 charging pump was repacked.

3.

A new pinion was installed on the turbine turning gear.

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Maintenance was performed on universal tool boom for the No. 1 l

manipulator crane.

I Instrumentation and Control The following instrumentation and control maintenance item was j

performed by the plant staff during the month of April, 1971.

1.

The program of recalibration of all primary auxiliary and vaste j

disposal in'strumentation was continued.

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l Reactor Plant Performance

-The following parameters were deter ined by means of incore instrumentation:

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600.0 MWt; 526.7oF Tavg; Control Rod Group A @ 83, B,C,D @ 88 ;

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850 ppm Boron.

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Maximum Outlet Temperature = 593.3 F l

l Secondary Plant Performance Feedvater heater terminal differences were as follows:

I No. 1 = 5 3 F No. 2 = 6.7 F No. 3 = 6.1 I

The condenser performance was as follows:

-18h.8 MWe; 1.30" Hg B.P.; 599 MWt; 37.6 F C.W. in; TTD = 30.52 F; cleanliness factor = 89 7%.

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Chemistry The main ~ coolant boron concentration was reduced from 918 ppm to 772' ppm to compensate for normal core depletion.

The main coolant pH averaged 5.31 during the period, i

i The main coolant beta-gamma specific activity averaged 1.13 x 10-1 l

uc/ml.

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The main coolant crud level averaged 0.02 ppm except for periods of load reduction when a maximum of 1.10 ppm was noted.

The main coolant tritium concentration averaged 3.21 ue/ml during the report period.

'The iodine-131 specific activity averaged 6.08 x 10 4 ue/ml and the iodine 131/133 atomic ratio averaged 2.38, indicating no significant change in the magnitude of fuel clad defects during the month, i-A crud sample for the month collected on April 21, had the following radiochemical analyses: dpm/mg crud Cr-51 Mn-5h Fe-59 6

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l 3.20 x 10 2.45 x 105 1.61 x lo i

l Co-58 Co-60 Agl10M 6

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1.45 x 10 3.99 x 10 6.66 x 10 i

A main coolant gas sample, collected on April 13, had the j

following radiochemical analyses: uc/cc gas i

i Xe-133 Xe-135 Ar-h1 l

1.11-1.58 x 10-1 h.53 x 10-1 l

l Health and Safety Two shipments of spent fuel with respective total activities of lb.h5 megacuries and 13.13 megacuries were made during the report period.

Three shipments of low level radioactive vaste were made during the peri 6d, totaling 170 drums and 212.65 me of activity.

Waste. disposal liquid releases totaled 23,605 gallons containing 0.007 me of gross beta-gamma activity and 77.82 curies of tritium. Gaseous releases during the period totalled 0.859 curies of gross beta-gamma activity and 3.39 me of tritium.

Radiation exposure doses for Yankee plant personnel as measured by film badge, for the month of April, 1970 were as follows:

4 Average accumulated exposure dose: Th.6 mrem Maximum accumulated exposure dose:

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-Operations-iAttached :is a 'snmmary of. plant; operating statistics and a f'

plot of daily average ~1oad for the' month of April; 1971.

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I YANKEE ATOL'IC ELECTRIC COMPAIiY - OPERATING SUBS'ARY April 1971 t

MONTH YEAR TO DATE l

ELECTRICAL _

Gross Generation KWH 132,501,800 524,76h,600 12,020,635,900 Sta. Cervice (While Gen. Incl. Losses)

KWH 7,890,l'(9 31,3h5,hh7 779,370,h72 Net Output KWH 124,611,621 h93,h19,153 11,2hl,265,h28 Station Service 5.95 5 97 6.h8 Sta. Service (While Not Gen. Incl. Losses) KWH 0

193,583 32,482,438 Ave. Gen. For Month (719)

KW 184,286.2 Ave. Gen. Running (T19)

KW 18h,286.2 PLANT PERFORMANCE Net Plant Efficiency 29.02 28.99 28.51 Net Plant Heat Rate btu /KWH 11,760 11,772 11,970 i

Plant Capacity Factor 99.53 98.52 75.85 i

Reactor Plant Availability 100.00 99.11 8h.43 MONTH CORE IX TOTAL NUCLEAR Hours Critical HRS 719.00 3,664.81 78,629.21 0

1 62 Times Scra=ned h

Burnup LMD/MPU 861.21 4,309.38 Core Average 1

Region Average bMD/.VfU A (INNER) 8h3.04 4,138.91 21,342.58 B (MIDDLE) 1,013.75 5,092.'44 13,834.29 C'(OUTER) 710.98 3,545.50 3,5h5.50 D (ZIRCALOY)-

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