Text

Operation Rept 127 for Jul 1971
	ML19351E255
Person / Time
Site:	Yankee Rowe
Issue date:	08/20/1971
From:	; YANKEE ATOMIC ELECTRIC CO.
To:	;
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ML19351E254	List: ML19351E253; ML19351E255;
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	NUDOCS 8011260377
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c 50 - 29 YANKEE NUCLEAR POWER STATION t

1 OPERATION REPORT NO. 127 l

Rocked w/tiv tet;4 [~#0 'M For the Month of I

July 1971 3

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Submitted by

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YANKEE ATOMIC ELECTRIC COMPANY Westboro Massachusetts i

August 20,'1971 l.

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l This report covers the operation of the' Yankee' Atomic Electric j

Company at Rove, Massachusetts for,the month of July, 1971.

During the period plant load varied between 171.1 IWe and 180.6

!Ge as the circulating water temperature fluctuated between 65 F and 53 F.

i One, unscheduled, plant shutdown occurred during the period, initiated by a reactor scram and subsequent turbine trip on July 1 at 15h8

-hours.

Further discussion of this shutdown is precented as Abnormal 0ccurrence 71-2, this report.

A second, scheduled, plant shutdown occurred on July 3 at 0713 hours0.00825 days 0.198 hours 0.00118 weeks 2.712965e-4 months for the purpose of demonstrative testing of reactor operater license candidates. Following completion of the testing the turbine generator was

. phased to the line at 1h33_ hours and the plant was loaded to 600 IWt at 1650 hours0.0191 days 0.458 hours 0.00273 weeks 6.27825e-4 months , that date.

The fifth, Core IX' vapor container air leakage surveillance period was terminated on July 20, and the sixth such period was_ commenced on July 21.

Leakage during the entire report period was normal.

Erratum: Operation Report No. 126, page 1, paragraph 2, sentence 5 should be corrected to read: The reactor power level, which vas 485 MWt at 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months on June 5, was increased to 600 !Gt on June 6 at

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1115 hours0.0129 days 0.31 hours 0.00184 weeks 4.242575e-4 months .

l Plant Abnormal Occurrences j

4 Abnormal Occurrence No. 71-2 " Plant Trip".

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On' July 1, 1971 at.15h8 hours, while operating at a reduced load'of 485 MWt during an electrical storm, a reactor scram and turbine trip occurred.

As a res"It of a severe electrical " bump" the 2126 high line was I

automatically disco aected with the resulting loss of the'No. h main coolant pump.

It is believed that coincidentally the bump resulted in a minor i

turbine load increase to slightly above the single low flow scram condition.

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Since the No. h pump was shutdown, single lov flow scram requirements were j

satisfied, j

A survey.of plant. systems following the trip revealed no. adverse l

or unsafe conditions. The reactor was brought critical and the' turbine l

generator was phased to the line at 1926 hours0.0223 days 0.535 hours 0.00318 weeks 7.32843e-4 months on the day of the occurrence.

Plant full power operation ~of 179 ne was attained at 2330 hours0.027 days 0.647 hours 0.00385 weeks 8.86565e-4 months .

i Plant Load Reductions i

July 6 (1630-1735):

Plant load reduction to 140 MWe due to an electrical storm.

I July 7 (11h5-1220):

Plant load reduction to 170 !Ge for turbine control valve exercising.

July 15 (1155-1220):

Plant load reduction to 169 MWe for turbine control

. valve exercising.

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July 16 (1600-1700):

Plant load reduction to lho We due to an electrical j

storm, i

i July 18 (0615-1215):

Plant load reduction to 132 We to allow mintenance l

on Y177 high line.

t l-July 21 (llh5 1220):

Plant Joad reduction to 166 We for turbine control valve exercising.

July 28 (1143-1220):

Plant load reductiva to 169 We for turbine cuntrol valve exercising.

July 29 (1835-2220):

Plant load reduction to 139 We due to an electrical storm.

July 31 (1100-1305):

Plant load reduction to 140 We due to an electrical i

storm.

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Plant Shutdowns l

Shutdown 117-9-71:

7/1/71, plant trip due.to a load " bump" during an l

electrical storm. Total outage time: 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months , h2 minutes.

Shutdown 118-9-71:

7/3/71, plant shutdown for reactor demonstrative testing of reactor operator license candidates.

Total outage time: 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months , 37 minutes.

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Plant Maintenance i

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

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1.

The No. 1 charging pump was repacked.

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The gravity drain tank No. 2 pump was replaced.

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3 During the July 3 shutdown period the following maintenance items were l

performed:

a.

Vibration readings were taken of all four main coolant pumps. All readings were normal.

b.

The No. 2 boiler feed pump inboard gland was repacked.

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The generator exciter commutator was stoned during turbine coast-l down.

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i Instrumentation and Control l

l The following is a list of pertinent instrumentation and control

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maintenance items performed by the plant staff during the month of July, 1971.

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1.

Installation of supply controls for fuel oil to the emergency diesel generator sets was commenced during the period.

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'2.

Instrumentation for monitoring Core X new fuel was assembled and tested.

Reactor Plant' Performance The following parameters were determined by means of incore j

j instrumentation:

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598.2-MWt; 525.2 Tave; control Rod Group A 8 59, B,C,D, @ 88 ;

333 ppm boron.

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F

=

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FAH = 2.0 Minimum DNBR = 3.4 Maximum outlet temperature = 591.h 7 I

Secondary Plant Performance f

Feedvater heater terminal differences were as follows:

No. 1 = 5.1 F No. 2 = 5.6 F No. 3 = 5.5 F G

The condenser performance was as follows:

175.0 MWe; 2.82"Hg B.P.; 598.5 MWt; 67 5 F C.W. in; TTD = 25.8 F; f

cleanliness factor = 65%.

Chemistry The main coolant boron concentration was reduced from 513 ppm to 333 ppm to compensate for normal core depletion.

The main coolant pH averaged 5.57 during the period.

l The main coolant beta-Samma specific activity and crud level j

averaged 1.0h x 10-1 uc/ml and 0.02 ppm respectively.

i The main coolant tritium concentration averaged 1.98 ue/ml during the report period.

The iodine-131 specific activity averaged 3.37 x lo-ue/cc and the iodine 131/133 atomic ratio averaged 2.08.

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-A crud sample for the month collected on July 19 had the following radiochemical analyses: dpm/mg crud Cr-51 M"-5b Fe-59 6

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7.89 x 10 5.ho x 10 1.26 x 10 9

Co-58 Co-60 Ag-110M 6

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3.87 x 10 9.61 x 10 1.b8 x 10

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h-l A main coolant gas sample, collected on July 13, had the following radiochemical analyses: uc/cc gas.

t Xe-133 Xe-135 Ar-bl I

2.04 1.36 x 10-1 5.95 x 10-1 f.

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Health and Safety

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Waste disposal liquid releases totalled h2,129 gallons containing l

0.015 me of gross beta-gnen activity and 146.57 curies of tritium.

Gaseous raleases during the period totalled 1.831 curies of gross beta-gamma activity. Secondary plant water discharged totalled 375,32h gallons containing 0.011 me of gross beta-gnmmn. activity and 0.h06 curies of tritium.

i Radiation exposure doses for Yankee plant personnel as measured by film badge, for the month of July,1971 vere as follows:

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Average accumulated exposure dose:

35 mrem j

Maximum accumulated exposure dose: 200 mrem

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Orerations

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Attached is a summary of plant operating statist';s and a plot

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of daily average load for the month of July, 1971.

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YAIIKEE ATOMIC ELECTRIC COMPANY - OPERATING SU!C/11RY July 1971 ELECTRICAL MONTH YEAR To DATE Gross Generation KWH 126,056,600 911,151,500 12,h07,022,800 Sta. Service (While Gen. Incl. Losses)

KW 8,029,273 54,989,998 803,015,023 Net Output KWH 120,027,327 856,161,502 11,604,007,777 Station Service 6.27 6.04 6.47 Sta. Service (While Not Gen. Incl. Losses) KWH 67,000 h88,883 32,777,738 h

Ave. Gen. For Month (7h4)

KW 172,119 1 Ave. Gen. Running (T33.03)

KW 17h,694.9 PLANT PERFORMANCE Net Plant Eff!ciency 27.68 28.69 28.50 Net Plant Heat Rate ETu/KWH 12,329 11,895 11,975 Plant Capacity Factor 97.15 97.77 76.37 Reactor Plant Availability 98.90 98.72 84.76 NUCLEAR MONTH CORE IX TOTAL Hnurs Critical HRS 736.95 5,840.39 80,80h.79 Times Scrammed 1

3 6h g

Burnup Core Average MJD/IffU 869 90 6,881.13 Region Average MdD/NfU A (INNER) 79h.26 6,620 75 23,824.h2 3 (MIDDLE) 1,009.26 8,067.52 16.829 37 C (0 UTER) 739.09 5,704.55 5,704.55 D (ZIRCALOY)

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FORM RE-5

ML19351E255

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