ML19351E072
| ML19351E072 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 08/21/1964 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19351E068 | List: |
| References | |
| NUDOCS 8011250561 | |
| Download: ML19351E072 (8) | |
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YANKEE ITUCIEAR Poller STATION i
i OPERATION REPORT !!O. h3 For the month of I
JULY 196h i
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O susmittea 37 YANKEE ATOMIC ELECTRIC CCf7Alff Boston Massachusetts August 21, 196h i
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This report covers the operation of the Yankee Atomic Electric Company plant at Rowe, Massachusetts for the month of July, 196h.
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The final phases of the Core III " stretch-out" program were
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completed during the month as plant output decreased through burnup with all control rods at the near full out position. Plant load decreased from 11h We at the beginning of the reporting period to 95 We on July 31.
On July 27, an attempt was made to bring the main coolant system to normal chemistry conditions through the removal of ammonia with mixed bed ion exchange. The reactivity loss associsted with the ammonia removal was more gradual than that experienced previously with Core III and more closely approached than experienced at the end of Core II operation.
For the balance of the reporting period the principal activity of plant persoviel was directed towards preparing for the forthcoming refueling r.hutdown in early August.
No reactor scrams or plant shutdowns occurred during July.
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Plant Maintenance Following is a summary of major activities carried out by the plant maintenance staff during July:
1.
Fabrication of two guide tube disposal casks and lif ting fixtures was completed during the month.
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2.
Repairing of spalled concrete on vapor container support
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foundations continued during the month.
3.
Replacement pressurizer heater cables were received and tested.
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No. 2 boiler feed prmp and motor were dismantled for inspec-tion.
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5 The generator connections were checked for hydrogen leaks.
6.
Seals on Nos. 1 and 3 charging pumps were adjusted and rings renewed as required.
7 No. 2 instrurx.nt air compre3ror was inspected.
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The service air compressor was inspected.
9.
No. 3 boiler feed pump motor was realigned so that, on starting tha pump, the thrust bearing now carries the motor thrust through the coupling resulting in a much lower operating temp-erature of the inboard bearing.
10.
The stacking plate for core internals was set-up, aligned and tested.
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Attempts to reduce the ion exchange pit leakage rate by instal-ling and sealing a concrete plug in the pit sump were unsuccess-ful. Further attempts using alternate procedures are planned.
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Chemistry Operations with ammonia adjusted high pH continued until July 27 with the concentration varying between 8 and 9 ppm.
On July 27, amonia removal commenced via mixed bed ion exchange.,
On July 29, the ammonia concentration was measured at < 0.1 ppm and the main coolant pH was reduced to essentially neutral.
On July 17, the loop by pass valves were opened resulting in an increase of the main coolant crud concentration to 10 ppm.
By July 23, the crud level was reduced to 0.8 ppn by purification ion exchange followed by filtration.
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During the month the main coolant Iodine-131 concentration was d c/nl; the I-131/I-133 atomic ratio was _2.7 i
measured at 1.7 x 10 e
The coolant specific activity remained essentially constant at O
3.h x 10-2.,uc/ml until July 27 when the by pass valves were opened and a j
slight increase to 3.7 x 10-2Ac/ml was recorded.
Throughout the reporting period the main coolant oxygen concen-tration remained below the point of detection.
A typical main coolant gas analysis made during the period indicated:
A - hl h.1 x 10 Ac/cc gas Xe - 135 5.9 x 10 Ac/cc gas 4
Xe - 133 6.3 x 10-1.nc/cc gas A typical main coolant crud analysis made during the period indicated:
i Cr - 51 90x dpm/mg Mn - $h 0.9 x 1 dpm/mg O
re - 59 3 6 x 1o dem/m8 Co - 58 5.6 x 10 dpm/mg Co - 60 0.7 x 10 dpm/mg Reactor Plant Performance i
The rate of reactivity loss and the total loss, upon the removal of ammonia at the end of Core III life, followed the pattern of loss at the end of Core II life. From observations and ammonia tests to date it appears-that the reactivity loss at high power levels occurs over_a shorter period of time than reactivity loss at intermediate power levels. The total re--
activity loss, however, appears to be of the same approximate magnitude.
Therefore, it seems reasonable to theorize that pH induced reactivity change rates are power level depenaent.
It is possible that at zero powe a pH induced reactivity change might be observed.
At 100 We a rate of d>out l
.1% /\\ K per day has been observed. At 180 We a rate of about.h% A K per K
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day has been observed.
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v The following were determined by means of in-core instrumentation l
measurements at a power level of'37h Wg with~all rods banked at 90 0/8 inches.
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$26.8 F Hot Channel Outlet Turbine Plant Performance Feedwater heater terminal difference measurements made during the period indicated.
0 106 We 2.2" Hg h67.2 F Tavg No. 1 7.7 F No. 2 12.60F No. 3 5.20F Routine plant calorimetric data was measured and analyzed during hs the period with no abnormalities noted.
During the month moisture content of the main steam was measured at the south cross-under piping on the discharge end of the south moisture separater.
0 9h We 1.95" Hg 267 psig throttle (D) h52.6oF Tavg 20 psig moisture Separator Pressure V
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Instrumentation and Control The following is a list of major activities carried out by the plant Instrumentation and U(ntrol personnel during July.
1.
Ccmpleted construction and leak-testing of the spare coaxi' triaxial panetration which will be installed at the refuell.
outage.
2.
Comp'eted the rewriting of the primary plant instrumentation cali'r ation procedures.
3 Assembled, tested and adjusted the underwater TV for refueling use.
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Installed the turbine trip sequence light panel, relay panel, terminal blocks, and wiring harnesses.
5 Inspected the in-core instrumentation system in the vapor con-tainer under operating conditions to prepare for improvements in critical swite' mounting and control circuit wiring inadeq-uacies.
6.
Conpleted assembly of No. 1 manipulator crane tool bo6m tele-scoping alarm control box.
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7 Reca11brated the THNR main coolant temperature channels as
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temperature.
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Connected the two refueling BF3 counting, channels with pre-amplifiers and amplifiers located in the control room.
Health and Safety During the month of July one drum of special radioactive waste consisting of a shim rod skirt which had seen in-core service in CoreII was prepared. A concrete lined drum was used. The addition of approximately ten inches of molten lead reduced the maximum contact reading on the drum from 3r/hr to 600 mr/hr. The activity content of the drum was estimated to be 5.1 curies.
No drums were shipped from the site during the period.
O Liquid wastes containing a total activity of 0.2 me were discharged during July. Gaseous wastes containing a total aci,1vity of 88 me due to radiochemistry sampling were discharged during the same period.
I Personnel exposure for Yankee plant personnel as measured by film badge for the month of July 196h were Average for all station personnel h6 mrem.
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thri=1m individual exposure 270 mrem.
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Newly Issued Maintenance Instructions
$06E Reactor Refueling, was rewritten to incorporate the necessary changes for the Core III - IV refueling.
Plant Operations O
Attached is a summary of plant oporation statistics for the month f
of July 196h, and a plot of daily average load for the same period.
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p TA h ATOMIC m COMPANT -- OhTING
SUMMARY
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J ELECTRICAL PENTH TEAR TO DATE Gross Generation WH 79,325,100 772,707,800 3,h78,267,700 Sta. Service (While Gec. Incl. Iosses)
NH 7,135,307 51,9h7,871 2h 9,719,906 Net Generation NH 72,18 9,793 720,7$9,929 3,228,5h7,79h Station Service 9.00 7.50 7.17 Sta. Service (While Not Gen. Incl. losses)
WH 0
230,000 13,275,251 Ave. Gen. For Ptmth (7hh IEG)
W 106,620 Ave. Gen. Rnnning (7hh 100)
W 106,620 PLANT PERFORMANCE Net Plant Efficierry 2$.13 27.77 Net Plant Heat Rate Btu /WH 13,5GO 12,239 Ibs. Steam / Net N H 15.76 1h.h9 Circulating Water Inlet Temp.
Maximun F
61 MLnimum F
h7 Flant Operating Factor 6h.3$
Sh.62 68 59 NUCLEAR PON'4 3 CORE III TO DATE Times Critical 0
19 326 Hours Critical HRS 7hh 6227.30 27,770.h1 Times Scrasened 0
6 hh Ihuivalent Reactor Hours @ 600 Et HRS h78.78 h6h3.78 IS,1hl.63 Average Burnup of Core WD/mtU Control Rod Position at Mcath Ed Fquilibrium at 370 Et h$2 F Tavg Noup 1 Rods out-inches 90 0/8 Group 2 90 0/8 Grsup 3 90 0/8
- Rei-ion G2oup h 90 0/8 oup 5 90 0/8 Inner 7h7.56 8738.55 e
roup 6 90 0/8 Middle 666.h3 12,7h7.93 Group 7 90 0/8 Outer h66.19 h863.66 Boron
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for July 1%h_
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