ML19354C381
| ML19354C381 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 03/29/1968 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19351E124 | List: |
| References | |
| NUDOCS 8011250638 | |
| Download: ML19354C381 (7) | |
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P whtory Ferrni Filo Cy, YAIEEE NUCLEAR POWER STATION OPERATION PZPORT NO. 86 For the month of FEBRUARY 1968 1
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Subnitted by l
YANKEE ATOMIC ELECTRIC COMPANY Boston Massachusetts fn, i -
March 29, 1968 i.
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s This report covers the operation of the Y:.nkee Atcmic Electric l(
Company plant at Rowe, Massachusetts for the month of February,1968.
At the beginning of the period plant lead was 148.7 MWe; normal load reduction, consistent with stretchout operation, resulted in a plant load of 134.2 MWe at the end of the report period Following the plugging of a tube leak in the main condenser west side water box during the previous report period, steam generator blcwdown water chloride concentration equilibriated at 0.2 ppm with increased blowdown levels. On February 2 at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br /> plant load was reduced to 100 MWe and an e-+.ry was made into the condenser east side water box.
One leaking tube was detected and plugged in the non-condensable gas offtake region. Plant load was restored at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />.
Steam generator water chloride levels were maintained at 0.05 ppm with normal blowdown rates during the remainder of the period.
Plant load was reduced to 110 MWe on February 7 at 1145 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.356725e-4 months <br /> fer the monthly exercise of the turbine throttle valves ; no abnormal behavior was observed and plant load was restored at 1252.
The base and tcp protective coatings were applied to the spent fuel pit internal surfaces; this completed the pit surface refinishing program.
i Twelve fuel elements for the Core VII loading were received on
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site; the assemblies were inspected and stored in the new fuel vault.
Vendor representatives commenced on site assembly of two Zircaloy clad fuel elements.
During the period, valve stem leakoff line temperature increases were experienced. Valve stem leakage was re+1ced and near normal temperatures restored by plugging the stem leakage line on the solenoid relief line motor operated valve and by placing the No. 1 and No. 4 loop bypass valves on backseat.
On February 1, the sixth Core VI air charge was completed.
A control rod exercise was performed on February lb; all rods operated normally.
No plant shutdowns or reactor scrans occurred during the month of February.
Plant Maintenance The following is a list of pertinent plant maintenance performed by the plant staff during the month of February, 1968.
1.
A cutter for the conoseal seal bell upper veld was fabricated.
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2.
Steam generator blowdown tank piping modificaticr; were ecmpleted.
3.
The 2.h KV air circuit breakers were inspected.
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. h/ The valve stem leakoff line on the solenoid relief line motor operated valve was plugged.
5 An alignment jig for the reactor vessel instrumentation spires was fabricated.
6.
The expansion joint on the Ho.2 condensate pump suction line was replaced.
7 A new shell and tube bundle were installed in the vaste liquid evaporator rebeller.
Instrumentation and Control The following is a list of pertinent instrumentation and control maintenance items performed by the plant staff during the month of February, 1968.
1.
Investigation of possible improvements to the incore flux wire system were continued.
2.
A spent fuel pit neutron monitoring system was assembled and a f actional check completed.
3.
A high water level alarm for the shield tank cavity was fabricated.
Reactor Plant Performance
,m The following parameters were determined by means of incore instrumentation at 473 MWt, h91.8 F Tavg, O ppm boron, control groups A, B, C and D at 90 3/8 inches.
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2.4
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F A
2.0 H
Minimum DNER 4.8 Maximum outlet temperature Sh9.5 F A change in slope of the core burnup curve that resulted in a K
0.2 % g-reactivity gain at the end of full power life was reported in Operations Report No. 84; December, 1967 This depletion behavior h continued during plant stretchout operation and an additional 0.13% ggr reactivity gain has been realized.
Since the start of Core VI operadion with ammoniated coolant, a total reactivity gain of 0.56% $5 has been n
experienced.
Chemi s try Main coolant ammonia concentration averaged 12.2 ppm. The average e
coolant gross teta-gamma specific activity and crud level were 6.62 x 10-2 ue/ml and 0.17 ppm, respectively. The iodine - 131 'pecific activity was 2.2 x 10-ue/nl; iodine 131/133 atomic ratio was 0.80.
Main coolant tritium
. concentrations have decreased from 1.51 ue/ml to 1.32 uc/ml due to the decreasing power level.
A representative crud sample for the month, collected on February 19, had the following radiochemical analyses: dpm/mg crud cr-51 Hf-181 h-Sh Fe-59 6
5 6
6 h.55 x 10 1.h7 x 10 2.85 x 10 1.66 x 10 co-58 co-60 Ag-110M 3 7
6 2.0h x 10 5.62 x 10 1.40 x 10 A main coolant gas sample collected on February 13 had the following radiochemical analyses: ue/cc gas Xe-133 Xe-135 Ar b1
-3
-3
-2 3 91 x 10 7.30 x 10 2.35 x 10 Health and Safety Waste disposal liquid releases totaling 18,160 gallons contained 30.h7 uc of gross beta-gamma activity and 27.28 curies of tritium. Gaseous releases during this period were 19.69 me of gross beta-gare.a activity.
Secondary plant water discharged was 289,57h gallons and contained a total of 5.04 uc of gross beta-gamma activity and 285.3 me of tritium.
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One shipment of radioactive waste containing 67 drums with a total activity of 55 me was made during February.
In addition to the above releases is an inadvertent gas release that occurred on February 26.
During a scheduled discharge of waste gas to the primary vent stack, a gas leak was detected from the bonnet of a valve in the gas discharge piping. The scheduled release wag secured and the valve repaired; however, a maximum gas quantity of 20 ft uld have 3
been released into the gas ccmpressor room. A maximum 20 ft inadvertent discharge would result in the release of 13.2 ue (beta-gamma) and 19h ue (tritiun) to the envircnment through the waste disposal building exhaust system. A summary of the released gas concentrations averaged over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period is as follows :
Release MPC
-9
-I H-3 2.3 x 10 ue/cc 2.0 x lo ue/cc
-10
-I Xe-133 1.3 x 10 ue/cc 3.0 x lo ue/cc Xe-135 2.8 x 10-uc/cc 1.0 x 10-uc/cc Average accumulated exposure dose 76 mrem.
Maximum accumulated exposure dose 253 mrem.
Operations Attached is a summary of plant operating statistics and a plot of daily average load for the month of February,1968.
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9 YANKEE ATOMIC ELECTRIC COMPANY -- OPEATING SU)0RRY PEBRUARY 1968 EUETRICAL 10 NTH YEAR TO DATE Gross Generation WH 98,101,800 213,796,200 7,924,680,800 Sta. Service (While Gen. Incl. Losses)
DGI 6,895,508 14,398,61h 527,065,5h7 Net Output WH 91,206,292 199,397,586 7,397,615,253 Station Service 7 03 6.73 6.65 Sta. Service (While Not Gen. Incl. Iosses)
DGI O
O 2h,805,527 Ave. Gen. For ibnth W
140,951 Ave. Gen. Running W
1h0,951 PIANT PEEFORMANCE Net Plant, Efficiency 27.92 28.17 28.39 i
Net Plant Heat Rate Bru/WH 12,223 12,115 12,021 f
Plant Operating Factor 78.22 81 92 73.74 Reactor Plant Availability 100.00 100.00 83.76 NUCLEAR 10 NTH CORE VI TOTAL Hours Critical HRS 696.00 10,83h.h9 Sh,560.17 Times Scramed 0
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Burnup Core Average WD/MPU 655.02 11,9ho.55 Region Average ND/MrU A (INN m) 651.h03 12,020.89h 28,793.39 B (MIDDLE) 777.613 14,271.907 21,9h7.19 C (OUT2) 532.807 9,598.546 9,598.55
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