ML19351E171

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Operation Rept 78 for June 1967
ML19351E171
Person / Time
Site: Yankee Rowe
Issue date: 07/24/1967
From:
YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML19351E170 List:
References
NUDOCS 8011250707
Download: ML19351E171 (9)


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YANKEE HUCIEAR POWER STATION i

OPERATION REPORT NO. 78 For the month of JUNE 1967 O

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O Submitted by YANKEE ATOMIC ELECTRIC COMPANY Boston Passachusetts July 2h, 1967

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This report covers the operation of the Yankee Atomic Electric Company plant at Rcwe, Massachusetts, for the month of June 1967.

At the beginning of the period the plant was operating at approximately 180 MWe.

Thereafter plant : oad varied between 181 MWe and 170 MWe as circulating water inlet tenperature varied between h5 F and 63 F.

0.1 three different occasions plant load was reduced 0

to decrease the probability of a plant trip due to severe weather conditions. The duration of the load reductions were nine hours, five hours and three hours respectively.

On June 30 two turbine generator exciter commutator brushes were found to have worn devn with abnormal rapidity resulting in a possible scoring of the commutator.

Close surveillance of the com-mutator and brushes will be maintainet until the scheduled shutdown at which time repairs will be effected.

j The lower bearing temperatures of No.1 and No. 3 main coolant pumps continued to increase slowly throughout the reporting pe'ciod. At the end of the ceriod Ho.1 pump bearing temperature was 185 F and No. 3, 158 F; an increase of 12 F and 80F respectively for the month.

On June 29 phase III of the operator training course was

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conclutted by the administration of a four hour written examination.

Approximately 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> of classroom instruction have been i

x s completed during the course to date.

The monthly control rod exercise was conducted June 1.

All rods exercised functioned normally. However, control rods No. 11 and 12 were not exercised because of excessive chatter of one can motor relay contactor. The contactor will be adjusted during the C')

forthcoming maintenance shutdown.

On.Tane 29 the Yankee Atomic Electric Review Committee visited the plant and reviewed the details of plant operations subsequent to their previous visit.

The vapor container air leakage rate was normal through-out the reporting period.

No plant shutdowns or reactor scrams occurred during the month of June.

Plent Maintenance The following is a list of major plant maintenance items performed by the plant staff for the month of June, 196T:

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s. 9 1.

Cleanup of the ion exchange pit was completed.

2.

The spare centrol rod drive dash pot previously dissesembled and inspected was reassembled.

i 3

No. 1 and No. 3 charging pumps were repacked and three plungers were replaced.

h.

The guide busl.ing arms on the lower core barrel lifting f

l fixture were nodified.

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5 The shaft sleeves were replaced cn No. 2 component cooling pump.

I 6.

Both low pressure surge tank makeup pumps were repacked.

I 7.

Preparations were made for the construction of the permanent decontamination building by relocation of the. emergency diesel exhaust discharge point and removal of the greenhouse from the decontamination pad.

Construction of the building was initiated June 20.

Instrumentation and Control The following is a list of major plant instrument and control maintenance items performed by the plant staff during the month of June, 1967:

1.

A precicion t :mpc. c.ture measuring systc= vas installed in the discharge line from J,.1 feedvater heater.

l 2.

A level controller for the auxiliary boiler condensate receiver vss installed.

3 Corrosion damage on the guardhouse portal radiation monitor was repaired.

Reactor Plant Performance Core reactivity depletion was normal at approximately 0.Th % AK/K per 1000 MWtD/PTU.

The following parameters were determined by means of incore instrumentation at 599 5 MWt, 525.00F Tavg, 600 ppm boron, control rod groups B, C and D at 88 4/8 and group A at 86 5/8:

2.h Fq

=

2.0 FAH

=

i Minimum DNER

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3.2

=

591.0 F Maximum Outlet Temperature

=

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g /fe '7 6 g

(f <* > Secondarv Plant Performance Feedvater heater terminal difference at 176 fNe, 2.6"Hg backpressure and 525.co F Tavg:

  1. 1 - 5.5 F
  1. 2 - 13.7 F
  1. 3 - 13.h F Condenser terminal difference at 172 MWe and 3.1"Hg backpresaure was 35.9 F.

Chemistry Steam generator primary to secondary side leakage, as determined by baron and tritium tracer techniques, increased i/

O' during the period frc= approximately 119 gpd to a maximum of 319 gpd.

During the period the main coolant boron decreased from 663 ppm to 509 ppm.

Average main coolant iodine - 131 specific activity was 2.02 x 10-5 uc/ml ; I-131/I-133 atomic ratio was 0.73.

The average system crud level was 0.11 ppm. The averace main coolant tritium specific activity was 2.92 uc/ml.

A repres antative crud sample for the month, collected on June 12, had tht; following radiochemical analyses:

dpm/cg crud Cr-51 NI-131 Mn-Sh Fe-W Co-58 6

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5 6

1.05 x 10 5 13 x 10 6.38 x 10 8.56 x 10 2.84 x 10 0

Co-00 Ag-110M, 5

9.75 x 10 6.13 x 10' Two crud samples previously collected on April 26, 1967 and May 13, 1967 were sent out for independent silver chemical and radiochemical analysis. The silver 110" nuclide concentration 5

2 in these samples was 2.0 x 10 dpm/cg.and 2.1 x 10 dpm/cg, respectively. The chemical silver concentration for both samples was 0.0067,.

A main coolant gas sample collected on June 9 had the following radiochemical analyses:

pc/cc gas Xe-133 Xe-135 Ar bl

-3

-1 7.k1 x 10-9.h6 x 10 7.55 x 10 I

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't Health and Safety On June 7, 1967 during routine ash removal from the clean area incinerator radiation levels of 1 to 3 mr/hr were detected one inch above the vaste material. The contents of the incinerator, approximately 65 ft3, were placed in nine 55 gallon drums for analysis and ultimate disposal as low level radioactive waste. The incin-erator was decontaminated. An investigation of the origin, transport, time of occurrence and health physics aspects of the occurrence was made. From this investigation it was concluded that the burning of radioactive vaste material occurred subseq-

to the previous incinerator cleaning approximately three months before and most probably during, or after, the plant shutdown in March,1967. The total release was estimated to be n 4 pc of particulateactivitycontainingCoSggreaterthan10

, Co60, and Mn5h as the principle 7

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isotopes. A conservative evaluaticn of the release, based on the mass and activity of ccabustible material and related values of ash content and air-fuel ratios, resulted in an estimated release, averaged over the year, of 0.51 M.P.C. for an unrest -icted area, 1 x 10-10 ac/ml. A separate analysis based on meteorological diffusion evaluation methods resulted in an estimated release, averaged over the year, of 0.0033 M.P.C. for an unrestricted area.

No personnel were contaminated or received any abnormal radiation fm exposures as a consequence of this release. To preclude its re-occurrence the doors of the incinerator have been padlocked and administrative controls have been established to restrict access and use of the incinerator to those personnel responsible for disposal of clean area waste.

One shipment of low level radioactive waste was made during the period consisting cf fif ty-five drons containing a total f'

activity of 321.h mc.

During June the waste disposal liquid releases totaled 19h,000 gallons containing 5.15 me, of gross beta-gamma activity and 179.93 curies of tritiu=.

Gaseous waste releases during the same period totaled h21.22 me. of grcss beta-ganma activity.

Secondary water discharged during the period consisted of 29h,000 gallons containing a total of 47.3 uc of gross beta-gn-mn activity and h5.9 curies of tritium.

On June 1 semi-annual environmental soil samples were collected and shipped off site for analysis.

On June 15 all fire protective equipment and systems were inspected or tested in the presence of the NEPIA Fire Insurance Inspector.

4

. Radiation exposure doses for Yankee plant personnel, as measured by film, for the month of June, 1967 vere:

Average accumulated exposure dose; h5 mrem.

Maximum accumulated exposure dose; 187 mrem.

Operations Attached is a su==ary of plant. operating statistics and a plot of daily average load for the month of June,1967 O

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YANKEE ATOMIC ELEETRIC COMPANY -- OPERATING

SUMMARY

JUNE 1967 ENTH YEAR TO DATE ENHICAL Gross Generation Nil 126,630,700 660,830,200 7,023,290,700 Sta. Service (While Gen. Incl. Losses)

KWH 7,798,359 39,615,022 469,637,844 S.'F 118,832,341 621,215,178 6,553,652,856 Net Output Station Service 6.16 5 99 6.69 Sta. Service (While Not Gen. Incl. Iosses)

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509,267 24,304,73h Ave. Gen. For Month (720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br />)

KW 175,875 Ave. Gen. Running (720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br />)

KW 175,875 PIANT PERFORMANCE h

Net Plant. Efficiency 27.70 28.59 28.47 Net Plant Heat Rate Fru/WH 12320 11937 11987 Plant Operating Factor 99.29 83.39 72.35 Reactor Plant Availability 100.00 93.12 83.04 ElfrH CORE V_I

'OTAL NUCLF>R_

Hours Critical las 720 5385.37

.<111.05 Times Scrammed 0

2 Sh Burnup WD/MTU 860.26 5838.51 Core Average Region Average WD/MrU A (INNER) 881.269 5872.900 22,645.40 B (MIDDLE) 1035.472 6991.16h 14,666.45 C (OUTER) 682.326 4681.006 h681.01

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DAILY AVERAGE IDAD for JUNE 1967 200 -

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.. CORE VIREDION IDCATIONS

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