ML19351E000
| ML19351E000 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 11/20/1962 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| References | |
| NUDOCS 8011250383 | |
| Download: ML19351E000 (10) | |
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' YANKEE NUCLEAR POWER STATION OPERATION REPORT NO. 22
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l For the month of 3
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i OCTOBER 1962
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YANKEE ATOMIC ELECTRIC COMPANY Boston Massachusetts 4
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. November 20, 1962 r
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'C This report covers the operation of the Yankee At'omic Electric Company plant at Rowe, Massachusetts for the month of October 1962 The plant operated continuously throughout the month at or close [
to the licensed full power level.
On October 11, an amended facility license was issued to Yankee authorizing an increase in the maximum power level from h85 Wt to 5h0.Wt. -
The plant power increase was effected in four ' increments between October 11 and October 16 with the final increment bringing the reactor power level to $h0 Wt with a corresponding gross electrical output of approx-imately 16h W.
During the load increase the condenser back pressure increased from 1.8 inenes to 2.0 inches Hg. Some fluctuation in back pressure occurred during the month thereby varying the electrical output.by a few W for a given Wt input. Difficulty in maintaining the condenser
.O cirov1ati 8 weter s19 hen end re1etive17 warm intaxe weter resu1ted in the condenser back pressure.being higher than expected. With colder water and full siphon a gross electric output of close to 170 W should be possible at $h0 Wt.
. At the new licensed power level the turbine is operating with 13 out of h control valves wide open. At a main coolant average temperature of 51h F, the fourth cor^rol valve is throttled by an amount equivalent V
to approximately 3 We and all valves are wide open at an average main 0
coolant temperature of approximately $11 F.
The generator and main station transformer showed little change in the temperature as a result of the power increase and appear to have considerable capa::ity margins.
The steam generators appear to have no increased moisture p
camfoyer at the higher load and the interstage moisture separators have d
shown no increase in moisture content at the discharge to the low pressure turbine.
Operation of the plant at Sh0 Wt has been smooth with no equipment limitations having been experienced.
At the beginning of the period work commenced on the construction of a storage building to house contaminated material and equipment. The building will be constructed of concrete-filled cinder block and will measure approxintely. 30 feet by h0 feet. Facilities will be provided in the bui1Cag for decontamination of tools and equipment.
No reactor scrans or plant shut downs occurred durirg October.
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- L Mainienance Following is a-summary of major activities carried out by plant maintenance personnel during October.
- 1.
Completed the installation, tested and placed No. 3 safety injection pump in service.
'2.
Installed an ion exchange unit in the radioactive liquid waste system for evaporator effluent purification.
3.
Installed new shaft in the shutdown cooling pump.
h.
Replaced seven concrete floor shield blocks in the primary auxiliary building with steel plate.
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- 5. Repaired two leaks in the turbine moisture separators by U
taking up on closure bolts.
6.
Replaced a relay coil on No.1 instrument air compressor.
7.
Replaced two in-core-instrumentation flux wires and replaced defective drive wheel and relay contacts in the flux wire system.
O 8.
Fabricated new packing boxes for No. 2 charging pump.
9.
Installed a heating unit in the fuel chute enclosure.
10 Overhauled the incinerator stack detector pump.
- 11. Overhauled the primary stack gas detector.
Chemistry Main coolant oxygen levels remained low throughout the period ranging from undetectable to 300 ppb. Coolant crud levels were also low, averaging approximately 0 3 ppm.
1 pc/ml to 1.8 x 10 p t specific activity measurements ranged'from 1.0 x ).0-pc/ml.- The I-Main coo at the beginning of the period to 7.h x 10-3yc/ml at the end of the month.
'An increase in I-131 activity from 1.3 x 10-> pc/ml to 5.7 x 10-3 pc/ml was noted during the power increase. A similar increase in the I-131/I-133 ratio was also detected, the ratio being-3.h at the end 'of the period.
Coolant gas analyses indicated Xe-133 activity to be h pc/cc of gas.
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'A polishing ion exchanger was' installed.in the radioactive 11guid waste disposal system during October to provide ~ clean-up of the waste disposal evaporator effluent. The ion exchanger was removed from
' service shortly after testing its operation because of excessjve fines in the effluent and failure of the anion cycle. 'fhis was believed to be the result.of spoilage of the anion resin and replacement resin has
-been ordered.
Traces of boron appeared in main coolant samples obtained during the first half of the month. The fluctuations in measured boron concen-trations coupled with the absence of attendent reactivity changes made the sampling line suspect as the cource of the boron. Thorough flushing of the sampling line was effective in cleaaing out traces of boron which apparently had settled in the line. During the latter part of the month
.the measured main coolant boron concentrati:en was less than 1 ppm.
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=ce-Fo11owing is the' record of the power increase from the previously licensed limit of h85 Wt to 5hD Wt which was authorized on October 11.
~Date Gross We Reactor Wt 10/117670'1700 146 to 153 465 to 500
'10/15/62@12h5 153 to 157 500 to 515 O
10/16/62@1020 156 to 160 515 to 528 10/16/62@1615'~
160 to 16h-528 to 5ho Results from Core II~ in-core-instrumentation data indicated the following:
' Rod Position:
Groups 6, h,'2 @ 90 inches, Group 3 0 38 $/8 inches Core Avg. Power: 520 Wt Fq = 3.7, Minimum Q-DNB Ratio = h.2 A H = 2 3, Minimum 6 H - DNB Ratio = 2.3 F
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A comparable Core I analysis had indicated:
Rod Position:
Groups 6, 3,1 @ 90 inches,' Group h @ 39 6/8 inches Core Avg. Power: 392 Wt
- F ' = 3.8 q
FAT =2.7 i
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-h-Core I DNB ratios are not indicated for the comparison since a different DNB correlation was employed at that time. The true F is calealated dH from Core II data while the corresponding Core I hot channel factor was presented as Fd T.
The reduction in Core II of the Fd H term as compared to the Core I F d T term is the result of several effects:
1.
The FA g term includes a correction for the apparent differtrnees in mass flow rate in the various core positions which results in a value <v 7% lower than for Core I values.
2.
The overall radial power distributions are ~ 11% flatter on Core II than those observed on Core I.
This effect is due to the two Core I fuel assemblies left in the center of Core II and the additional flattening resulting from operating Core II at higher power levels.
,O Turbine Plant Performance Testing of No.1, No. 2 and No. 3 feedwater heaters continued during the period in order to determine the effect of recent modifications on heater performance. Data obtained at a plant load of 150 Mde confirmed results at 120 Ede indicating that No. 3 heater is now operating at its g3 design terminal temperature difference value. While some improvement U
has been noted in terminal difference on No.1 and No. 2 heaters, the operating terminal differences remain higher than the design values.
Plant calorimetric data were acquired before, during and after the power increase to verify the plant MWt te Ede relationship.
Partic-ular emphasis has been placed on the effect of condenser back pressure effects on gross electrical output. Analysis of this effect indicates the following relationship between condenser back pressure and gross electrical output at a constant reactor thermal power level of 5ho Ed.
Back Pressure MWe output In. Hg abs.
Oross 1.0 170.8 1.2 169.6 1.h 168.h 1.6 167.1 1.8 166.0 2.0 16h.7 Steam line vibration-measurements were made during the month.
No significant increase in vibration occurred with the power increase from h85 to 5h0 Edt. However, analysis of the basic vibration problem continues.
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.. 'O Health and Safety Liquid waste containing 0.36 millicuries was discharged from the plant during October. Waste gas containing 2000 millicuries was discharged from the plant during the same period. Of the total, 230 millicuries was discharged from the waste gas disposal system with 1770 mil 11 curies released'as a result of purging the main coolant sample line.
At all times the concentration of wa, e products discharged from the site was well below the maximum permissible.
No solid waste was shipped from the plant during October.
Seventy-nine drums of solid waste containing 9h millicuries were prepared during the same period.
Personnel dosimeters were leak tested.and calibratea durird the month. A total of fif ty dosimeters have been taken out of service O
ta== r r 1= 1962 dece==e or crec*ea 1e==e > re1=t heir 11=e= or excee 1ve leakage.
Decontamination of tools and fixtures used in the refueling operation continued in October.
Cleaning of the core barrel lifting fixture by sanding resulted in a reduction in radiation-level by a factor of three. Upon completion of the new storage building on the site, facilities will be available for both storage and decontamination of CI tools and equipment.
Following maintenance operations on the shutdown cooling pumps, 2
contamination levels of 200,000 to 900,000 dpm/ft were measured in the shutdown cooling pump cubicle with levels of h,000 to 6,000 dpm/ft2 being measured in adjacent corridors. After cleaning of affected areas, contam-2 ination levels were reduced to less than 5000 dpm/ft.
A Personnel exposures as measured by film badges for the month V
of September, 1962 were as follows:
Avg. for all station personnel 590 mr Max. individual exposure 1700 mr Since the film badge exposure period included approximately fif teen days of the refueling period, the exposures are higher than would be expected during routine plant operation.
No discernable increase in neutron or gamma radiation was observed on the site as a result of increasing the reactor power level from h85 wt'to 5ho st.
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Continuous monitoring of off-site airborne activity during October indicated levels consistent with pre-operational values.
Design Changes The following changes in plant design were completed during October.
I.
Listed below are charges made in connection with the increase in the plant power level from h85 Edt to 5ho Mat:
1.
Installed and placed in service a third safety injection pump.
The new pump is a motor driven centrifugal pump with a capacity ranging from 900 gpm at 1600 f t.
TDH to 1780 gpm t.', h75 ft. TDH.
The pump will start automatically during plant cperation at a a
main coolant pressure of not less than 800 psig.
V 2.
The control circuitry and control switch for No. 2 charging pump were changed to provide for automatic starting of the pump on low narrow rarge pressurizer level.
3.
The automatic control rod withdrawal circuit was removed. Out-ward rod motion is now accomplished manually.
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Single step rods out circuitry, to be in effect above h35 Edt, was added to the reactor control systems.
- 5. The following changes in reactor scram settings were mades a.
Reduced the high pressurizer water level scram set point limit from 275 inches maximum to 200 inches maximum.
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b.
Provided for scram on low main coolant flow indication on any one of four channels when above h35 Edt. Below h35 Edt scram will occur on low flow indication on two of four channels as in effect previously. The set point limit (definition of low flow) has been changed from 60% of normal main coolant flow as a minimum to 80% or normal main coolant flow as a minimum.
c.
Additional protection in the form of a neutron flux level decrease scram has been added. A scram will now occur on a neutron flux decrease corresponsing to 15% of $h0 Ndt (maximum) as indicated on any one of six channels with an auto bypass below 15 Mde, d.
Initiation of a high neutron flux level scram has been changed to require indication of high flux on 2 of 6 channels
,m rather than the previous 2 of 3 channels. The set point has y/
also been changed from a neutron flux corresponding to 120%
of rated power (maximum) to a flux corre ponding to 108% of rated power (maximum).
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The high power level scram e et point cutback Miich previously.
occurred on low flow in one loop was removed from channels 6, 7 and 8
'II.
A polishing ion exchanger has been installed to purify the effluent from the evaporator in the radioactive liquid waste disposal-system.
The installation of the ion exchanger is intended to pernit re-cycling of purified liquid waste.
Changes In Operatirg Procedure During October Operating Instructions 50h0:3-6, 50510.0:2-ba and $05Bll:1-5 were 144 sed and reissued. The revised instructions reflect the changes in operating procedure arising from the. increase in the plant power level from h85 W t to 5h0 w t.
- Plant Operations Attached is a summary of plant operation statistics for the month of Oc.ober 1962, and a plot of daily average plant load for the same period.
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O M ATOMIC ELECTRIC COMPANY - OPERATI!G SUM 1ARY OCTOBER 1962 ELECTRICAL MONTH YEAR TO DATE Gross Generation KWH 117,082,200 h99,65h,700 1,h61,002,000 Sta. Service (While Gen. Incl. Losses)
KWH 7,h0h,h35 38,h75,821 116,007,903 Net Generation KWH 109,677,765 h61,178,879 1,3hh,99h,097 6.32 7.70 7.9h Station Service KWH 0
3,83h,096 13,925,81h Sta. Service (While Not Gen. Incl. Losses)
Ave. Gen.
For Month (7h5 HR.)
KW 157,157 Ave. Gen.
Running (7h5 HR.)
KW 157,157 PLANT PERFORMA11CE Net Plant Efficiency 28.72 28.77 Net Plant Heat Rate Btu /KWH 11,883 11,862 Lbs. Steam / Net KWH 1h.05 1h.0h Circulating Water Inlet Temp.
or Sh Maximum Minimum 0F h1 Plant Operating Factor 98.h1 hh.95 58.28
?!UCLEAR MONTH CORE II TO DATE Times Critical 0
27 289 Hours Critical HRS 7h5 1,025.52 1h,272.95 0
2 32 Times Scrammed HRS 707.2 786.1 8535.9 Equivalent Reactor Hours @ $ho MWt Average Burnup of Core MWD /mtU 765.0 850.h Control Rod Position at Month End Equilibrium at 165 MWe Group 1 Rods out-inches O
Group 2 90 Group 3 55 7/8 cm Group h 90 Group 5 0
Group 6 90
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