ML19351E227
| ML19351E227 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/23/1966 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19351E226 | List: |
| References | |
| NUDOCS 8011260235 | |
| Download: ML19351E227 (11) | |
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YANKEE NUCIZAR POWER STATION OPERATION REPORT NO. 61 For the month of JANUARY 1966 O
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i Submitted by YANKEE ATOMIC ELECTRIC COMPANY Boston Massachusetts February 23, lo66 D O 8011260 % 3 [
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This report covers the operation of the Yankee Atomic Electric Company plant at Rowe,, Massachusetts for the month of January 1966.
During the entire reporting period, the plant was base loaded at essentially full licensed power equivalent to about 185 IWe. On January 3, the total cumulative gross generation passed five billion kilowatt-hours. The gross and net generation figures also set a record for a single month period.
Work on the yard area crane, which was mentioned in Operation Report No. 60 (December 1965), extended into this reporting period. Some of the modified parts installed in the crane were unacceptable and were replaced by the original parts. The features of the modification which (V) increased the safety factor of the crane were retained. A successful test lift was made in the presence of the crane manufacturer, consultants, and Yankee personnel. Use of the crane was appaved by all present but further recommendations are expected from the crane manufacturer. With the crane available, the spent fuel shipping cask was loaded with 10 of the highest burnup fuel assemblies discharged from Core IV.
The cask was removed from the pit and a series of decay heat measurements tests were run. Data was taken by Westinghouse with various combinations of circu-lating and cooling pumps in operation.
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Upon completion of this series of tests, the Core IV fuel
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assemblies were unloaded and 10 Core I fuel assemblies were loaded and shipped for reprocessing on January 20.
The turb'.ne vibration and noise mentioned in Operation Report No. 60 (December 1%5) occurred again during the evening of January 17 g
Attempts to quiet the noise by taking the #14 and #3 turbine control valves (l
off their back-seat resulted in an intensification of the noise. The main coolant average temperature was then increased 0.15 F from $26.60F to 0
527.0 F.
Coincident with this operation, the turbine quieted down and appeared normal. It is not certain that this small increase in steam pressure caused the noise and vibration to subside. The turbine has passed through this pressure range many tines as this pressure is within the normal operating range. It is evident that some undetermined parameter is involved which causes this noise to occur during certain temperature-pressure cycles while for the most part operation is normal. The total duration of this incident was about eight minutes. The turbine manufacturer has been fully informed and is attempt 3' to theorize the cause of the problem.
The fuel pit boron dilution process which began last month was completed. The final dilution reduced the boron concentration to 59 ppm and the water conductivity to 15 micro-mhos.
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's dilution of tne main coolant system as closely as was expected.
of the pres'surizer capillary vent and measuring the change in pressurizer Closing heater Clectric consumption indicatef that the vent flow had been about 53 lbw/ hoar.
Further investigations and measurements revealed that the pressurizer high set safety valve was leaking at a rate of 30 lbs/ hour.
Present operation is continuing with the capillary vent closed and venting occurring through the safety valve.
Further boron samples indicate a possible increase in the safety valve leakage, but no corresponding increase in heater electric consumption or safety valve discharge line temperature has been observed.
be removed for maintenance.On January 27, the primary drain collecting tank #1 pump necessary to purge the cover gas in the tank,Before the pump could be removed it was Written procedures were (o,/
correctly followed and nitrogen gas was introduced to the tank.
minutes after the operation began, an operator noticed the cover gasForty automatic pressure maintenance valve, from the wacte gas surge drum, was The operation was suspended and a valve line-up check was m valves were found in their proper position.
All Further investigation showed that a path existed because a drain line from the waste gas compressor K.O. drum to the primary drain collecting tank, which is designed to end at the bottom of the tank with a water seal effect either has a leak insid
- DJQ, the tank, or does not go to the bottom of the tank.
the pressure maintenance valve remained closed and gas release to stackThis line was did not further recur.
report for the calculated releases. Refer to the Health and Safety section of this The continuous vapor container leakage monitoring system, which was modified during and following the last refueling, had indicated a leakage rate of 0.0068% per day, to the end of the reporting period.
additional air charge to the system has been required since Core V No startup.
Plant Fbintenance the period by the plant staff:The following is a list of major activities carried out during 1.
The new pinion shaft and bearing were removed from the yard area crane, and the old ones reinstalled, retaining the new pinion.
2.
A new main coolant filter was installed in the No. h position in the ion exchange pit.
3.
A leak in the low pressure sample cooler line was repaired.
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The pressurizer motor operated drain valve stem packing was h.
tightened to stop minor leakage.
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Pipe hangers on the safety injection high head pump discharge line were checi ed and some were tightened.
6.
The #1 pump in the prinary drain collecting tank was removed and overhauled.
Chemistry Main coolant oxygen leve s were less than 0.05 ppm, the limit of detection.
System crud level increased to h.62 ppm after a control rod exercise; six days after the exercise, the crud level had decreased to 0.11 ppm. The system crud half-reduction time was 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />.
Minor
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increases in crud levels not associated with control rod motion have been correlated to relatively large water additions to the low pressure surge tank. Operational changes have been made in the procedure for water addition to reduce agitation of the crud located on the bottom of the low pressure surge tank. The January 26 (per monthly requirement) rod exercise resulted in the main coolant crud level increasing from 0.10 ppm to 15 ppm.
The main coolant average temperature gross activity was measured 3cm at 6.8 x 10-2 pc/ml.
A main coolant crud analysis gave the following
-V results:
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Isotope dpm/mg Isotope dpm/mg Ma-5h 5.0 x 105 Fe-59 8.8 x 105 Cr-51 h.7x10f co-58 1.5 x 106 Hf-181 6.7 x 10" Co-60 2.h x 105 k#
A main coolant gas analysis was as follcws:
Isotope pc/cc gas Xe-133 6.1 x 10-3 Xe-135 1.8 x 10-2 A -h1 6.0 x 10-1 A pressurizer gas sample with a vent flow of 53 lbs/ hour was measured at 63 ce gas /kg of condensate. The analysis of this sample:
02- 0.11%
N2 - 12.2 %
H2 - 86.h %
An earlier sample with a lower vent flow was measured at 83 cc gas /kg of condensate. The analysis was:
Do 0.32%
C 02 1h.9%
N H - 8h.8%
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Reactor Plant Performance Analysis of core reactivity data has resulted in a measured burnup rate of 0.85% 6 K per 1000 Mid/MTU over the first 2100 Mid/MTU of Core V.
The results of a flux wire run at ns 600 Mdt, 526 F T avg., and group A controlling at 73 h/8" were:
stainless clad fuel zircaloy clad fuel Max F 2 57 2.2h q
Max F 2.0h 1 9h H
Min q DNER 3.12 2.8 Max outlet temperature of hot channel 593.5 F (located in stainless clad fuel)
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Turbine Plant Performance An investigation has started in an attempt to determine the cause of the decrease in the outlet temperature of #1 feedwater heater.
The condenser cleanliness factor was measured at 81.6%.
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Feodwater heater terminal difference measurements were:
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- 1 12.6 F
- 2 13.2 F 0
- 3 8.2 F Instrumentation and Control
(~N The following is a list of the major items performed by the
'v' p1r,, staff during January 1966:
1.
Relocated the main coolant bleed line gamma detector to a positicn which reduced the background level.
2.
Repaired the four main coolant pump bearing temperature indicators.
3 Repaired the spent fuel pit level alarm.
h.
Calibrated the #1 feedwater heater outlet temperature indicator.
5.
Calibrated the #1 feedwater heater outlet temperature indicator.
6.
I,fy Repaired and tested two ClO and two UlC neutron detectors.
Another ClO was found to be beyond repair due to low
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internal resistance.
5-Health and Safety During the month of January 1966, no radioactive solid wastes were shipped off site for disposal, One special shipment of ten spent fuel assemblies containing 5,h megacuries was sent off site for reprocessing.
Liquid waste disposal releases totaling 152,100 gallons contain-ing a gross beta-gamma activity of 8.1 m and 112.6 curies of tritium, were discharged during the month of January. Gaseous waste released contained a total gross beta-gamma activity of hholh me and an additional lh2 cc of tritium.
In addition to the above releases, 309,000 gallons of water containing 2 3h curies of tritium wete released from the secondary plant.
The gross beta-gamma activity of this water was less than 10 ic.
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The following release, which is included above, took place during the purging of the primary drain collecting tank. This release was through piping the entire route to the primary vent stack.
A sample of the gas indicated that the principle isotopes were Xe-133 with an activity of 1.0 x 10-5 pc/cc and tritium with an activity of 1.0 x 10-2 j1e/ce, A check of the gas inventory before and after the release indicated a possible release of $00 scf of gas over the LO minute period. The total activity of Xe-133 was 0.lh rr.c and the total activity of tritium was Ih2 me.
The concentration upon relea InQ 8 x 10-9 Jic/cc for Xe-133 arxi 8 x 10 ge from the primary vent stack was pc/cc for tritium.
The filter unit in the ion exchange pit bay #h was removed from service and replaced.
Radiation levels of the used capsule with the top breakir.g the surface of the water were 3 r/hr on contact and 250 mr/hr at one meter The radiation level of a similar filter removed August lh, 1965 has decreased from a maximum of N90 r/hr to a maximum ofm h0r/hr o
{J Both capsules will remain in the pit for further decay.
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contact.
The spent fuel pit skimmer pump filters were changed.
Radiation levels of the bagged filters were 350 mr/hr contact and 7 mr/hr at 1 meter.
A radioisotopic analysis revealed that Ag llom was the principle contaminant.
.The atmosphere of tg vapor container was sampled with the following resultst 1 3 x 10~
pc/ce, gross beta-gamma, and 2 x 10-5 c/cc tritium.
p Personnel exposure for Yankee plant personnel as measured by film badge for the month of January 1966 was:
Average for all station personnel 56 mren Maximum individual exposure 317 mrem hou b
The following is a tabulation of all waste disposal releases and discharges for the entire year of 1965:
Liquida : 828,800 gallons containing a total beta-gamma activity of 29.3 me and 1,290 curies of tritium.
Gas: A total beta-gamma activity of 1 3 curies and 16 curies of tritium.
Ion exchange pit leakage: In addition to the above liquids, hhl,500 gallons containing a gross beta-gamma activity of 30.8 me and n>13 curies of tritium leaked out. The pit was emptied on h/28/65, repaired and refilled on $/2h/65 7 -
(j Solids: The following solids were shipped off site for disposal:
622 drums of routine waste 5,802.9 nc 27 special drums (resins) 1,150 7 me h poly wrapped package 0.h me 16 casks 312 curies
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699 units 319.6h2 curies Design Changes The following list includes changes recently incorporated in the plant systems as allowed by proposed changes and filed as part of Amendment No. 51 to license application dated June 29, 1956 (Docket No.
50-29).
1.
The relocation of the Safety Injection Tank level detector to the tank itself to eliminate erroneous readings due to flow considerations, as allowed in Proposed Change No. 59.
2.
The replacement of the letdown orifices to allow more flex-ible operation as allowed in Proposed Change No. 62.
3 The installation of a heating and purification loop, with pump heat exchanger and associated equipmcnt, on the Safety Injection Tank as allowed in Proposed Change No. 6h.
h.
The operation of Core V with two prototype stainless clad control rods replacing two hafnium control rods as allowed in Proposed Change No. 65 5
The installation of a new sample tap in the main coolant D '~~.
bleed line and associated valves and piping, the modification of the sample system, the installation of a flow meter in the make-up to the Low Pres.sure Surge Tank as allowed in v-Proposed Change No. 66.
6.
The installation of four Secondary Core Supports on the Thermal Shield as allowed in Proposed Change No. 68.
7.
The installation of one stainless steel source blank in Core V as allowed in Proposed Change No. 69 8.
The installation of four Joint Clamp Assemblies on the Thermal Shield as allowed in Proposed Change No. 70.
9 The installation of a permanent filter station in the Waste disposal Plant as allowed in Proposed Change No. 71.
Plant Operations The following Operating Instructions and Emergency Instructions
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(,hsve been recently revised and reissued:
Operating Instructions
$0hA2 - Startup from Hot Standby Condition 50hB2 Increasing Turbine Generation Load
$0hC2 Reactor and Primary Plant Cooldown 50hC3 Scheduled T-G Shutdown
$0hD5 - Startup of Isolated Loop I(-)
$0hL1 Liquid Radioactive Wasto Disposal System
$0bL2 Gaseous Radioactive Waste Disposal System 50hQ Vapor Container Atmosphere Control System Emergency Instruction
$0$D2 Loss of AC Supply
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Attached is a summary of plant operation statistics for the month of January 1966, and a plot of daily average plant load for the same period.
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OMIC ELEETRIhMPANY -- OPDtA3
SUMMARY
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YANKEE.
JANUARY 1966 ELEETRICAL MONTH YEAR TO DATE Gross Generation KWH 138,072,900 138,072,900 5,128,913,800 Sta. Service (While Gen. Incl. ksses)
KWH 8,1h8,685 8,1h8,685 35h,561,179 Net Generation KWH 129,92h,215 129,92h,215 h,77h,352,621 Station Service 5.90 5.90 6.91 Sta. Service (While Not Gen. Incl. Iosses)
KWH 22,2hl,578 Ave. Gen. For Month (7hh)
KW 185.58 Ave. Gen. Running (7hh)
KW 185.58 PIANT PHlFORMANCE Net Plant Efficiency 29 21 29.21 28.h6 Net Plant Heat Rate Btu /KWH 11,683 11,683 11,991 Lbs. Steam / Net IMH 13 9h
- 13. 9h Circulating Water Inlet Temp.
i gwinnm F
h0 cn Minimum F
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Plant Operating Factor 99.63 99.63 68.72 Reactor Plant Availability 100 100 80.83 NUCLEAR WNTH CORE V TO DATE Times Critical 0
lh 371 Hours Critical HRS 7hh 1 % 7 72 37,928.68 Times Scrammed 0
0 hp Equivalent Reactor Hours @ 600 Mit HRS 7hl.27 1823.80 27,982.8h Average Burnup of Core MID/Ml'u
- Cont.rol Rod Position at Month Did Equilibrium at 183,8 gie
- RDION ENTH TOTAL BURNUP Group A Rods out-inches 73 h/8 Group B 87 3/8 A (INNHt) 890.81 17,697.89 Group C 87 3/8 B (MIDDLE) 1008.01 9,2h9.6'3 Group D 87 3/8 C (0UTH1) 766.h7 1,876.l1 ZIRCAIDY TEST ASSSELIES 127h.96 3,212.92 Boron 670 ppm b
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