ML19351E365
| ML19351E365 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/20/1972 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| References | |
| NUDOCS 8011280187 | |
| Download: ML19351E365 (8) | |
Text
{{#Wiki_filter:,- 0% s O o ?C Cu? '% ^! FHe Cf; J - 2 3 2 2-G [', N' D v,C:_ El YANKEE NUCLEAR POWER STATION b ?~ OPERATION REPORT NO. 133 O.. . --{ CO -\\ Q9 - tra ./ W For the Month of 'A' N /' January 1972 N-s;, i 4 e Submitted by YANKEE ATOMIC ELECTRIC COMPANY Westboro Massachusetts February 20, 1972 l8011280 c.o ~ .a 1
g U (j This report covers the operation of the Yankee Atomic Electric Company at Rowe, Massachusetts, for the month of January,1972. Plant load at the start of the period was 155 0 MWe; continued plant stretchout operation resulted in a load decrease to 141.0 MWe at the end of the period. Sixteen new Core X fuel assemblies were received on site during the report period. The eighth, Core IX vapor container air lentage surveillance period was terminated January ll, and the ninth such period was commenced on January 12. Leakage during the entire report period was normal. Plant Abnormal Occurrences A main coolant sample cellected at 0810 hours on January 27, 1972 showed the ammonia concentratien had increased to 17 0 ppm.. At 0830 hours the concentration in the ammonia feed tank was diluted to lover the can-centration in the primary system. When a main coolant sample was collected at 1510 hours the ammonia concentration showed 22.1 ppm. The ammonia feed pump was secured at 1545 hours. Radiolytic decomposition was used to decrease the ammonia concentration to 17 7 ppm by 2215 hours. l Plant Load Reductions ~ January 12, 1972 (1202-1312): Plant load reduction to 120 MWe for turbine throttle valve exercising. Plant Shutdowns There were no plant shutdowns during the report period. Changes, Tests and Experiments The following is a list of the changes and teets performed in 1971: 1. Installation of a Motor Operator on No. 1 Service Water Pump Discharge Valve. A motor operator was added to the No. 1 service water pump valve so that the main contro] room operator could restart the pump without waiting for the assistance of the auxiliary operator. A safety evaluation showed that changing the valve to motor operation would not adversely affect the operability of the service water system. 2. Main Coolant Pump Flow Characteristic Test A special test was conducted to determine the flow characteristics of the two operating main coolant pumps upon loss of supply voltage. ( l L
O O 2 I I The reactor had been suberitical for six days prior to and including the period of the test. The test did not involve an unreviewed safety question. In accordance l with Section D.2.d.12 of the Technical Specifications, two main idle main coolant loops were tied to the reactor vessel to provide an l adequate heat sink when the two operating pumps vert deenergized. l 3 Control Room Habitability Test l A test of the habitability of the control room with no forced air cooling or forced venting was conducted at the end of two days of high temperatures. The performance of the control board instrumentation during previous high ambient temperature conditions of longer duration indicated that no unreviewed safety conditions vould exist. l Plant Maintenance The following is a list of pertinent maintenance items performed j by the plant staff during the month of January,1972: l 1. Two new pole mounted lights were installed to improve the security of the screenwell house and the dam roadway. 2. "No Trespassing" signs were affixed to the Restricted Area fence in the interest of plant security. 3 The No. 2 boiler feed pump was cleaned and inspected. h. Tne No. 1 condensate pump motor was disassembled, cleaned and inspected. New bearings were installed. i Instrumentation and Control The following pertinent instrument and control maintenance item was performed by the plant staff during the month of January,1972: l. The narrow range temperature channels were recalibrated to a lower range due to plant coastdown. Reactor Plant Performance l ( The following parameters were determined by means of incore j l instrumentation-i i I 3 h70.2 IGt; 490 F Tavg; Control Rod Group A,B,C,D, 6 90 "; 5.8 ppm boron F = 1.8 Minimum DNBR = 5 1 q Fg = 2.0 Maximum Outlet Temperature = 553.5 F
O O _3_ t Secondary Plant Performance i 7eedwater heater terminal differences were as follovs: Ho. 1 = 4.3 F No. 2 = 7.4 F Ho. 3 = 6.2 F The condenser performancr was as follows: 1h3.1 !Ge ; 1.12" Hg B.P. ; 476.0 !Gt ; 39.h F C.W. in; TTD = 3h.8 F; cleanliness factor = 63.4%. Chemistry The main coolant ammonia and boron concentrations averaged 13 5 ppu und 5 5 ppa, recy9etively. The main coolant pH averaged 9.hk during the period. The main coolant beta-gamma specific activity and crud level averaged 7 06 x 10-2 pc/ml and 0.05 ppm respectively. The main coolant tritium concentration averaged 1.14 pc/ml during I the report period. The iodine-131 specific activity averaged 6 92 x 10-5 pc/cc and the iodine 131/133 atomic ratio averaged 1.lf.4 i A crud sample for the month collected on January 14 had the following radiochemical analyses: dpm/mg crud Cr-51 Mn-54 Fe-59 7 D 6 1 71 x 10 1.60 x 10 1.14 x 10 Co-58 Ja-60 Ag-110M I 6 N i, 1.41 x 10 3.21 x 10 6.67 x 10 A main coolant gas sample, collected on January ll, had the following radiochemical analyses: pc/cc gas Xe-133 -2 5 23 x 10 Xe-135 Ar kl 2.61 x 10-2 3.23 x 10-2 Health and Safety Waste disposal liquid releases totalled 14,311 gallons containing 0.009 me of gross beta-gamma activity and 15.h1 curies of tritium. Gaseous releases during the period totalled 0.221 curies of gross beta-1 gnmma activity. Secondary plant water discharged totalled 300,558 gallons I containing 0.009 me of gross beta-gamma activity and 0.137 curies of l tritium. l f
i i O o 1 Radiation exposure doses for Yankee plant personnel as measured l by film badge, for the month of January,1972 were as follows: i Average accumulated exposure dose: 71 mrem Maxieum accumulated exposure dose: 240 mrem The following is a summary of all liquids, gases, and solids 4 l released, discharged or shipped from the plant during the year 1971. Waste Disposal Liquid: 585,407 gallons containing a total beta-gamma activity of 0.339 me, and 1,632.80 curies of tritium. Gas: A total beta-gnmma activity of 12 341 curies, e..na 10 71 curies of tritium. i Airborne Particulate: A total of 1.068 pc beta-ga mn activity. Solids for Disposal: h61 drums containing a total activity of 2 948 curies; 4 1102 cubic feet of miscellaneous vaste with a total activity of C.031 curies. i Secondary Plant and Miscellaneous Liquid: 5,067,551 gallons containing a total beta-gamma activity of 11.1h me, and 51.h6 curies of tritium. I Fuel Shipments During 1971 there were h shipments of spent fuel totalling 36 assemblies with a total activity of 52.84 megacuries. Operations Attached is a summary of plant operating statistics and a plot of daily average load for the month of January,1972. r i i ~.
YANKEE ATOMIC ELECTRIC COMPANY - OPERATING SL'hiARY January 1972 MONTH YEAR TO DATE ELECTRICAL Gross Generation KWH 110,311,500 110,311,500 13,126,187,h03 Sta. Service (While Gen. Incl. Losses) KWH 7,h05,853 7,h05,853 8h8,475,467 KWH 102,905,647 102,905,647 12,277,711,933 Net Output Station Service 6.71 6.71 6.h6 Sta. Service (While Not Gen. Incl. Losses) KWH 0 0 33,099,138 Ave. Gen. For Month (744) KV 148,268.1 g Ave. Gen. Running (Thh) KW 148,268.1 PLANT PEhF6]JMANCE Net Plant Efft tiency 28.12 28.12 28.h8 Net Flant Heat Rate btu /KWH 12,136 12,136 u,983 Plant Capacity Factor 81.97 81.97 77.04 E' 85.29 Reactor Plant Availability 100.00 100.00 MONTH CORE IX TOTAL NUCLEAR Hours Critical HRS Thh 10,108.34 85,072.74 0 3 64 Times Scrammed Burnup Core Average MdD/MfU T33 97 11,691.76 Region Averase WD/bffU A (INNER) 739.25 11,500.00 28,703.67 B (MIDDLE) 839.27 13,650.90 22,392.75 C (OUTER) 628.15 9,755.85 9,755.85 D (ZIRCALOY)
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