ML19351E340

Operation Rept 103 for Jul 1969

ML19351E340
Person / Time
Site:	Yankee Rowe
Issue date:	08/18/1969
From:	YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML19351E339	List: ML19351E338 ML19351E340
References
NUDOCS 8011280139
Download: ML19351E340 (8)

Text

{{#Wiki_filter:: o o O Eeceived w/ttr Dated [' ~ s s Regulatcry Fife Cy. YANKEE NUCLEAR POWER STATION OPERATION REPORT NO. 103 For the Month of i July 1969 RETUPJ T0 iEGU.A70RY CiNTlAl. fl.ES R00(81b t . ~ 'N e\\g gSt I f 4 [k 6 6 \\D k .,,rp / / / !L \\l\\ &h Q ' q, E f jj G. 0:c>vLD % y :., s uiC

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i O O This report covers the operation of the Yankee Atomic Electric Company plant at Rowe, Massachu.cetts for the month of July,1969 Plant load at the start of the period was 122.7 MWe; continued plant stretchout operation resulted in a load decrease to 111.1 MWe at the end of the period. The third, and final shipment of new fuel for Lore VIII was delivered on-site, and consisted of 12 asseiblies. The ninth vapor container air charge surveillance period continued through the reporting period. Leakage during the period was normal. All routine tests were completed, successfully. On July 29, a sodium tracer wao introduced into the main coolant system for the purpose of rechecking the primary to secondary leak rate. Analysis of the results of the test shorea u.e leak rate in the No.1 steam generator to be 3.3 gallons per day. The combined leak rate in steam generators 50. 2 and No. 3 was less than one gallon per day. I Plant Abnormal ucem rences 1 Gn July 17, 1969 the plant was operating at a power level of 400 KJt under core stretchcut conditions. Huiber 1, 2 and 3 main coolant loops were in service, with Number 4 loop isolated. A positive ground developed on the No.1 battery. The operators, fusingawrittenprocedure,begananattempttolocat? and isolate the fault. This procedure calls for opening, and then reclosing, various circuit breakers on the D.C. bus. The main control board ground voltmeters are observed while operating these circuit breakers. During the testing of the Ho, 1 circuit en the No. 1 battery, a plant trip occurred at 1039 hours. A main coolant low flow scram signal was noted on the FH memory light panel and on the scram sequence panel. A scram auxiliary relay memory light was observed on the turbine board, indicating the reactor s c r amme d fi rs t. Since no main coolant pump trip had taken place, a false flow scram signal had been initiated. The No. 2 and 3 tain ecolant pumps were left on for the normal coastdown to 58 cycles on the generator. Both operating boiler feed pumps tripped. The plant was placed in a hot standby condition. Subsequent investigation showed that the positive ground was in a light bulb in the No. 1 main coolant locp low flow panalarm window. A second ground developed during the scram on the negative side of the No. 1 battery and was traced to an auxiliary relay in the Ho. 2 boiler feed pump control circuit. Both components were rep'.eed, unich normalized the ground voltages on the No.1 battery. 1 Reactor startup was initiated and the generator was phased on the line at 1526 hours, the same day. \\

O O l l Plant Load Reductions

1. Ju?y2 (1200-1300)

Load reduction to 105 Mh'e for monthl, turbine throttle valve test. July lo (1150-lh00 ) Load reduction to 82 Mhe for tube leak check in the East box of the main ( condenser. Two tubes were plugged. j Plant Shutdowns l Shutdown No. 00-7-9 Plant trip due to electrical conditions set up by a solid positive ground indication j on the Ec. 1 battery. 1 Total outage time: h hours, h7 mi?utes. Plant Mai n t enance The following is a list of pertinent maintenance items performed by the plant staff during the month of July,1969 1. An oil trap tank has been installed in-line for use during the upcoming Class A vapcr container over-pressure air leak test. 2. A new limit switch was installed on the lay-down mechanism in the spent fuel pit. 1 l 3. The No. 2 gravity drain tank vertical multistage pump was replaced with a single stage pump. i b. Work is in progress on a new support head for the reactor head stud turning tool. 5 The follcwing pumps were repacked: 1 a. Boiler feed pumps Ho's. 1, 2 and 3. b. Heater drain pump Ho. 2. c. Condensate pumps No's. 1, 2 and 3. 6. A magnetic particle test was performed on both hooks of each of the turbine hall and yard area cranes. All four hooks were found free of de fe c t s. 7. The spare main coolant bleed 20 gpm orifice flange velds were rs graphed and found free of defects. Instrumentation and Control The following is a list of pertinent instrumentatica and control maintenance items performed by the plant staff during the month of July,1969 81. I Recalibration of the No. L main coolant loop steam pressure compensating relays was completed.

l l o o i 3 2. Installation of the fire detection system was completed. The system was tested and accepted by the insurance underwriters. l 3. A monitoring panel was fabricated and tested for use during the controlled leakage phase of the vapor container over-pressure air leak test. Reactor Plant Performance The following parameters were determined by means of incore inst?amentation. 395.2 K4t; 480.4 Tavg; Control Rod Group A, B, C, D 8 90 3/8"; O ppm boron. 1.6 F = q 1.6 F = 3 Minimum DIIER T.1 = 0 Mar' s outlet temperature 527 7 F = Chemistry The main coolant ammonia concentration and pH averaged 119 ppm

1. was se.36 respectively until July 25 at 0920 and 9 cured. On July 25 at 1135 hours a mixed bed-ion exchanger was placed in service. At the end of the period the ammonia concentration was negligible, j

The main coolant beta-gamma activity and crud level averaged 8.bl x 10-2 ue/ml and 0.0h ppm, respectively. The main coolant tritium concentration averaged 3.6h x 10-1 uc/ml during the period. The iodine - 131 specific activity was 1.99 x 10-5 uc/c0 and the iodine 131/133 atomic ratio was 0.hh, indicating the absence of detectable fuel defects. A representative crud sample for the month, collected on July 21, had the following radiochemical analyses: dpm/mg crud Cr-51 Mn-54 Fe-59 1.80 x 107 1.5h x 107 1.02 x 107 I Co-58 Co-60 Ag-110M 8.92 x 107 3.07 x 107 6.86 x 10h l A main coolant gas sample collected on July 10 had the following radicchemical analyses: uc/cc gas 8 Xe-133 Xe-135 Ar bl 2.80 x 10-3 5.82 x 10-3 1.bl x 10-1 1 l l __-.,._,,-._..-._,.___.,_._,.m___.._.__

O O -u-Ilealth and Safety

1. ccatainedatotalactivityof16.05 curies.

i One shipment of radioactive waste, consisting of approximately i h0 ft3 of expended ion exchange resins, was made during the period and Waste dieposal liquid releases totalled 58,771 gallons containing 0.153 me of gross beta-gamma activity and 25.88 curies of tritium. Gaseous releases during the period totalled 310.5 me of gross beta-gamma activity. Secondary plant water discharged, totalled 247,396 gallons containing 1 1.15 me of gross beta-gamma activity and 6.28 curies of tritium. In addition to t he above releases, 0.h5 me of tritium as a vapor l were discharged to the environment through the primary vent stack. l Radiation exposure doses for Yankee plant personnel, as measured by film badge, for the month of July, l')69, were as follows: Average accumulated exposure dose: 83 mrem. Maximum accumulated exposure dose: 370 mrem. Operations j Attached is a summary of plant operating statistics and a plot of daily average load for the month of July,1969 ) 8 1 1 .,.<~.,.,.., - -._. --- - ---..,-n-..-.--_--,.v- _ _ -, - -,. .--.--l

YA?F"3 MOT.N ET TRIC CO:1PANY h* TTX AV"l?GE IOtD for July 1969 t ( 200 -

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l l t YANKEE ATOMIC ELECTRIC COMPANY - OPERATING

SUMMARY

l l July 1969 l ELECTRICAL MONTH YEAR TO DATE i Gross Generation KWH 85,292,800 784,027,200 9,787,789,000 Sta. Service (While Gen. Incl. Losses) KWH 6,150,713 h9,702,566 6hh,296,825 Net Output KWH 79,.h2,087 734,32h,634 9,143,492,175 i Station Service 7.21 6.34 6.58 Sta. Service (While Not Gen. Incl. Losses' KWH 24,321 823,765 27,107,415 Ave. Gen. For Month (Th4 hr.) KW 114,641 Ave. Gen. Running (739.02 hr.) KW 115,382 j PLANT PERFORMANCE Net Plant Efficiency 26.58 28.50 28.38 Net Plant Heat Rate btu /KWH 12,840 11,975 12,025 e i Plant Capacity Factor 66.70 84.43 75.28 e Reactor Plant Availability 99.48 96.51 8h.75 i HUCLEAR MONTH CORE VII TOTAL Hours Critical HRS Th0.13 10,676.11 65,783.53 i Times Scrammed 1 3 58 Burnup O Core Average FMD/FfrU 600.45 11,940.53 Region Average FMD/MTU l A (INNER) 638.12 12,563.90 30,418.18 B (MIDDLE) 677 12 13,920.08 23,907 51 C (OUTER) 512.46 9,630.71 9,630.71 D (ZIRCALOY) 574.79 12,014.06 12,014.06 ) ~

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