ML19345A331
| ML19345A331 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 03/16/1962 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19345A329 | List: |
| References | |
| NUDOCS 8011190100 | |
| Download: ML19345A331 (10) | |
Text
{{#Wiki_filter:. ~ .h f'Q 'h8'09 u, ! a ?lle Copy YANKEE NUCLEAR POWER STATION OPERATION REPORT NO. Ih For the month of FEBRUARY 1962 4 6 S 9[%4:.& f#Nf,g*o 7g i m 2 4 t if, O q E s 'ry S i,,I ~ O D 2}lt/>g?{t?rfff st O/A ~ ~ $ $lh. 'A S \\; % I l s y t \\ 's) /? Submitted by YANKEE ATOMIC ELECTRIC COMPAhT Boston Massa:husetts March 16, 1962 80111,90[OO
1. This report covers the operation of the Yankee Atomic Electric Company Plant at Rowe, Massachusetts for the month of February 1962. Plant conditions at the beginning of February saw the power level at 130 We with a main coolant average temperature of approximately h930 F and. all control rods fully withdrawn. Core power production was extended through the month by coolant temperature and power level reductions. By virtue of the core negative temperature and power coefficients, reactivity, through power and temperature reductions, was added to compensate for reactivity lost through burnup. For the first part of the period, the core extension program was based on allowing main coolant temperature to decrease to a predetermined level followed by a step load reduction. Accordingly, 5 We load reductions were made on February 2nd (130 to 125 We) and on February 9th (125 to 120 We). Both load reductions were accompanied by increases.in the coolant temperature of approximately 1.5 F. Temperature fall-off during the period February 1 to 9 averaged less than 10F per day. For the remainder of the month the main coolant temperature was allowed to drift dounward with no step power reductions. Initially, it was possible to maintain load at a nominal level of 120 We. Increased turbine control value opening compensated for the lower main steam pressure arising from main coolant temperature fall-off. On February 26th, however, all four turbine control valves were in'a fully open position. With the turbine unable to admit increasing flow, load had decreased to 118 We by the end of the month with a main coolant average temperature of h710F. With the gradual reduction in main steam pressure and increase in steam flow, there has been no apparent increase _in steam moisture content. Measurements indicated main steam moisture levels of approximately 0.2% during the period. During the latter part of the month, a spare set of air ejector nozzles were modified to operate at a lower steam pressure and installed. Increasing the diameter of the nozzles will permit effective air ejector operation tt pressures as low as 150 psig. The existing nozzles were designed for 300 psig operation. This modification was dictated by the desire to extend ope. ration with Core I and to operate with the accomparging lower nain steam pressures. The spent fuel pit cooling lines were revised during the month to provide more effective cooling during periods of spent fuel storage. The purification system for pit water clean-up was placed in service for a brief period in order to purify the initial charge of water in the pit. A plastic cover has been installed over the pit to prevent introduction of foreign material.
-ee.ge 2 Nine' fuel assemb'.ies were delivered to the plant during February. This marked the final shipment with a total of seventy-six assemblies having been delivered for use in Core II. No.1 condenser circulating water pump was removed and shipped to the manufacturer's plant for testing.. As described in previous reports, the pump power requirements have been higher than specified. Following testing, a decision will be made on possible modification of the pump impeller. No plant outages or scrams occurred during February. Plant Maintenance Following is a description of major maintenance activity during February: 1. The spent fuel pit cooling lines were revised. A complete des-cription is provided under the Design Changes section of this report. 2. Excessive shaft leakage on No. 3 charging pump necessitated removal of the shaft packing box. Wearing of a recently installed set of bakelite seal rings was discovered. 'Ihe 4 existing rings will be replaced by a set of graphite-copper rings on a trial basis. 3. No. 1 charging pump was repacked, b. An eroded section of the No. 1 feedwater heater vent line was replaced. 5. No. 1 condenser circulating water pump was removed and shipped to ~ the manufacturer's plant for testing. 6. The sleeves of No. 1 component cooling water pump were renewed. In addition to the above and routine maintenance operations, prepar-ations for refueling and for extensive secondary plant inspection and overhaul were made during the period. Chemistry During the month of February main coolant oxygen levels remained below the point of detection. Main coolant specific activity measurements ranged from 5.h x 10-2 to6.5x10-2,1c/m1, Secondary side steam generator specific activity measurements continue to indicate background levels only. 1
.7... 3. Iodine - 131 activity in the main coolant varied between 1.8 x 10-b' and 5.1 x 10-h ate /ml with corresponding I - 131/I - 133 atomic ratios of 2.0 to 2.7. This indicates no significant change in the I - 131 activity or I - 131/I - 133 ratio from the latter part of January. A main coolant gas analysis made during the period indicated: A-h1 2.5 x 10-1 c/ccgas Kr-85M 1.3 x 10-2 Ie-133 1.7 x 10-2 Ie-135 2.6 x 10-2 The results of a main coolant crud analysis were: Fe-59 93x1 dpmh Ag-110 9.8 x 1 Co-60 1.1 x 10 Co-58 2.7 x 1066 Cr-51 1.0 x 10 Mn-$h 8.0 x 105 Crud Level 0.06 p;m Reactor Plant Performance Data acquired during the core extension and up to the time of ft$11 opening gf the turbine control valves yielded a burnup rate of approximately 11 x 10- df/ EFFH @ 392 L't. Reactivity coefficients measured during the 6h00 EFPH shutdown and a calculated variation in Ienen poisoning as a function of core power level were employed in the burnup determination. The effective burnup rate for the period was approximately h0% higher than the design burnup ra',. The following were determined by means of in-core instrumentation measurements at a power level of 393 Elt with all control rods withdrawn to 90 inches: F 2.8 AT Fq 3.2 DNB ratio > 3.7
( _m h. A plot of hot channel factors versus time with all control rods at 90 inches indicated reductions in the radial and axial maximum to average power ratio of 3 and 2% respectively over a period of'1000 EFPH @ 392 IMt. Turbine Plant Performance Extension of core life with its attendant deterioration of main steam conditions is reflected in' turbine and secondary plant performance. A reduction in net plant efficiency and a corresponding increase in net plant heat rate and turbine steam rate are evident as the' main steam pressure declines. Calorimetric runs continue to be made during the core extension period in order to check the Vie versus 1Mt correlation. In addition to condenser back pressure, the change in steam pressure is now factored into the relationship. Feedwater heater testing during February indicated the continued-existance of excessive terminal temperature differences. Health and Safety Liquid waste containing 120 pc and gaseous waste containing 302 pc were discharged from the plant during February. Concentrations of waste products discharged from the site were well below the maximum permissible level at all times. Two druns of non-combustible waste consisting of the ceramic portion of the electrodes removed from the evaporator, polyethylene bags, valve packing and pieces of contaminated glassware were prepared. Radiation levels on con-tact with the drums were 0.0h to 0.5 mr/hr. No solid waste was shipped from. the site during the period. A primary system crud sample. with an activity of 10 pc was shipped-off-site for analysis during the month. The fo11'owing contact radiation levels were measured during Feb-ruary in order to determine activity build-up as a function of time. l i i I
) 5. Location Radiation Level on Contact No.1 Creging Pump 8mr/hr No. 2 Charging Pump h mr/hr No. 3 Charging Pump 2-7 mr/hr Charging Line (in pipe chase) 15 mr/hr Yain Coolant. Bleed Line (in pipe chase) 20nr/hr Chemical Injection Line (in pipe chase) 10mr/hr Activity Dilution Decay Tank 20-100 mr/hr Waste Holdup Tank 30-50mr/hr Gas Surge Drum 0.02mr/hr Shutdown Cooling Pump 100-200mr/hr Shutdown Cooling Exchanger 20-30mr/hr No. 1 Purification Pump Drain Line 100mr/hr No. 2 Purification Pump Drain Line 100mr/hr Low Pressure Surge Tank Discharge Line 250mr/hr Low Pressure Surge Tank (Bottom) 5 r/hr The maximum personnel exposure as measured by film badges for the month of January 1962 was 2h0 mr while the average for all station personnel was 13 mr. Continuous monitoring of off-site airborne activity during February indicated levels consistent with pre-operational values. Design Changes The following minor plant design change was made during February: The spent fuel pit recirculating lines were revised to provide improved circulation and cooling. Suction to the cooling pump was fo merly taken close to the bottom of the 36 ft, deep pit. Under the new arrangement suction is taken approxinately h ft. below the water surface. The return line, prior to the charge, discharged just above the suction line. The return line has now been relocated so that discharge of' cooled water takes place at the opposite end of the pit. Changes in Operatirg Procedure Emergency instruction No. 505 C3, covering action to be _ taken in 4 the event of loss of condenser vacuum, was issued durirg February. The instruction describes operator action to be taken after loss of vacuum under normal operatirg conditions, i.e. primary system at 2000 psig and 51hCF, as well as during the core extension period.
= (: f 6 In Plant Training Classroom instruction in basic nuclear physics continued for personnel training for control room operator's positions. In preparation for the refueling operation, additional review and - training in Health Physics was provided for the plant Nuclear Auxiliary Operators. Plant Operations Attached is a plot of daily average plant load and a summary of plant cperating statistics for the month of February. The " CORE I" and "TO DATE" IIMES CRITICAL figures have been revised to conform with plant operating records.- + e 1 i y
vW~--- ..,+4&-.s n 4,-.- m A e_ n a +" .m YANKEE ATOMIC ELBCTRIC COMPANY DAILY AVERAGE LOAD ~. for FEBRUARY 1962' I 150 i Nn ~ i e s 3 100 - Q O A h -c 0: J 30 J ~ o W ? 0 i e i i i
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i i i e i i i e i i g 5 10 15 20 25 30 DAYS
4 T YANKEE ANI!IC ELECTRIC COMPANY - OPERATIfG SU)f!ARY FEBRUARY 1962 MONTil YEAR 'IO DATE ELECTRICAL KWH 81,55ff,900 181,366,300 1,1h2,713,600 Gross Generation Sta.' Service (While Gen. Incl. esses) KWH 6,n6,3h5 13,h07,060 90,939,1h2 KWH 75,h81,555 167,959,2h0 1,051,77h,h58 Net Generation Station Service 7.50 7.39 7 96 Sta. Service (While Not Gen. Incl. Lo ses) KWII O 0 10,091,718 Ave. Gen. For Month (672 Ilrs.) KW 121,h25 Ave. Gen. Running (672 Hrs.) W 121,h25 PLANT PERFORMANCE 28.90 29.h9 Net Plant Efficiency Btu /KWH 11,810 n,573 Not Plant Heat Rate 13 97 13.6h Lbs. Steam / Net KWil Cirt ;b. ting Water Inlet Temp. F 36 Maximum 0F 32 Mininum 80.1h 82.92 70.75 Plant Operating Factor MOff17I CORE I TO DATE !!UCLEAR 0 255 255 Times Critien1 HRS 672 11,2h9.01 H,2h9.01 Hours Critical 0 30 30 Times Scrammed HRS 538.5 7,338.9 7,338.9 Equivalent Reactor Hours @ h85 re't MWD /mtU 521 7,101 Average Burnup of Core Control Rod Position at Month End Equilibriun at 118 IMe, h71 F TAve. Group 1 Rods out-inches 90 Group ? 90 Oroup 3 90 Group h 90 Group 5 90 Group 6 90
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