ML19351E360
| ML19351E360 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 03/19/1969 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19351E359 | List: |
| References | |
| NUDOCS 8011280166 | |
| Download: ML19351E360 (8) | |
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YA'IKEE IFJCLEAR PCITER STATIO:I OPER/tTICU P5 PORT IIO 98 For the Month of February 1969 s
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YANKEE ATCMIC ELECTRIC COMPAl!Y Boston Mass
. ca tts March 1P
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- This renert covers the operation of the Yankee Atomic Electric Company plant at Rowe, Massachusetts for the month-of February,1969 At the beginning of the period, plant load was 165 8 M4e. On February 15 at 1745 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.639725e-4 months <br />, a scheduled hot standby shutdown commenced for r
reactor operator training. During the shutdown period, both main condenser sater boxes were checked for. leaking tubes. Nine tubes in the West water box-vere plugged. This outage was concluded on February 16.
Plant load during the ren ainder of the period. varied between.185 3 M4e and 186.5 M4e as circulating <ater. inlet temperature fluctuated.between 38 F and 33 F.
All routine tests. vere. completed.successfully. Control Rod Groups B, C, D vere. moved out one step to 90 0/8" as part cf the rod step wear program.
Vaper container leak rate determinations during the period
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l indicated leakage to be 0.05h% per day. Since this value is slightly l
above normal, inspection and. penetration. testing was. performed; no abnormal condition was found.
j Plant Abncrmal Occurrences Abnormal Occurrence No. 69-1 " Oxygen Buildup in Waste Cover l
Gas System".
On February 13, 1969, a routine analysis of waste system cover gas indicated the oxygen and hydrogen constituents to be approx-imately h% and 32%, respectively.. The oxygen concentration in this gas system normally is less than 0.2%.
Routine system operation does not include a mechanism for the buildup of substantial oxygen levels in the waste g2s system.
A. backup analysis, performed off-site, confirmed the oxygen and hydrogen concentrations. As a deterrentto further oxygen buildup. and possible formation of a potentially hazardous 3
mixture, a cont olled release of 13,000 Ft of waste gas was made,3 thereby ret.cing the oxygen inventory. After the release, 5500 Ft of nicrogen was added to the cover gas system. Subsequent analysis of gases in the waste gas surge drum showed 1.7% oxygen; 15% hydrogen; and 83% nitrogen.
Comparison of the recent gas analysis with previous analyses indicates that the oxygen entered the system as air, in a total volume
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of approximately 6C00 Ft3 The cause cf air leakage into the. gas system I
has not been determined.
Investigation is continuine,into possible mechanisms for the inclusion of air into the system.
Abnormal Occurrence No. 69-2 " Waste Gas Leakage From Decay Gas Filter".
During a scheduled waste gas release on February 21 - 22, 1969, l
a slight leak was detected from the decay gas filter, at'the upper head l_
joint gasket. The leak rate was estimated to be 10 cc/ minute, with a h
total of 1.30 x 10 ce being released. The 2100 cfm ceiling exhaust fan provided high dilution at the point of discharge from the building.
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j The total activity released due to the leak was 4.7 uc.
The concentration of the released gases after dilution and when averaged over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, was 5 5 x 10-11 ue/cc. The decay gas filter upper head flange was machined and a new gasket was installed.
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Plant load reductions during the period were as follows:
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February 5.(1145-1257)
Load reduction.to 145 We; turbine throttle valve monthly test.
l February 7 (1203-1520)
Le_.. reduction to 90 We; condenser j
tube leak check.
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Plant Shutdowns Shutdown No. 97-T-9 2/15/69 - P/16/69, scheduled hot standby shutdown; reactor operator training.
Shutdown duration:
25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />, 47 minutes.
Plant Maintenance l
The fouoving is a list of peruinent maintenance items performed by the plant staff during the month of February, 1969 1.
The check valve on the discharge line of each vaste gas compressor, j
was replaced, i
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The No.1 charging pump was disassembled to permit machining the ends of the cross-head stubs. Also one new plunger and new oil seals were l
installed.
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An upper limit alarm was installed in the cab of the turbine hall crane, l
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A frequency meter was installed on the emergency diesel generator.
j lnstrumentation and Control The following is a list of pertinent instrumentation h tol l
maintenance performed by the plant staff during the month of February,1969 1.
The new position indication system was moved from control rod No. 1 to control rod No. 5 for further testing.
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Efforts were continued to obtain a flux wire plot for each available I
flux wire thimble.
Reactor Plant Performance The following parameters were-determined by means of incore instrumentation:
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596.5 Wt; 524.3 Tavg; Control Rod Group A @ T2 3/8; B.C.D
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@ 90 0/8; 9 ppu baron.
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.imum DNBR 3.0
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596.3 F f
Maximum ~ outlet temperature
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Secc.dary Plant Performance i
1 Feedwater heater terminal differences were as follows:
6.7 F 11.5 F No. 3 6.7 F No. 2
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No. 1
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The condenser performance was as follows:
186.2 We; 1.08" Hg B.P. ; 599 0 Wt; 34.2 F C.W. in; 96.31 j
24.5 F; cleanliness factor T.T.D.
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Chemistry The main coolant boron concentration was decreased from 122 ppm 9
to 84 ppm during the period February 1 - 18, ~to compensate for normal core depletion. On February 18, a h5,000 gallon dilution of the main coolant system reduced the boron concentration-to 9 ppm,'and anion exchange further reduced it to 1 5 ppm as of February 20.
On February 20, a mixed bed i
(H+ OH-) ion exchanger was placed in service which reduced the boron j
concentration to <0.1 ppm by the end of the report period. The main coolant pH averaged 5.93 during baron operation and 7.70 during operation
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j with unadjusted pH water chemistry.
i Coolant average gross beta-gamma activity and crud level were l
7 2k x 10-2 ue/ml and 0.02 ppe, respectively.
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The main coolant tritium specific activity averaged 1.20 uc/ml j
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during the month.
f The iodine - 131 specific aut,1vity was 2.12 x 10-5 ue/ml and
.j the iodine 131/133 atomic ratio was 0.83, indicating the absence of l
detectable fuel defects.
I A representative crud sample for the month,. collected on February 12, had the following radiochemical analyses; dpm/mg crud Cr-51 Mn-54 Fe-59 6
6 8.87 x 10 1.h5 x 10 1.61 x 10 I
Co-58 Co-60 Ag-110M b
6 9 28 x lo 3.55 x 10 h.20 x 105
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A main coolant gas sample collected on February 18 had the following radiochemical analyses: ue/cc gas i
Xe-133 Xe-135 Ar 41
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6.00 x 10-3 6.40 x 10-3 2 95 x 10
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1 Health and Safety' i
Waste disposal liquid releases totaling 32,760 gallons contained 0.019 me of gross beta-gamma activity and-100.71 curies of tritium. Gaseous releases during the period were 158.21 me of gross beta-gamma activity and j
156.66 me of tritium. Secondary plant water discharged totaled 2T4,047 i
gs11ons containing 0.09 me of gross beta-gamma activity and 1.37 curies j
of tritium.
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Radiation exposure doses for Yankee plant personnel, as measured by fila badge, for the month of February, 1969 vere as follows:
Average accumulated exposure dose:
h3 mrem.
i Maximum accumulated exposure dose:
320-mrem.
Operations 1
i Attached is a summary of plant operating statistics and a plot j
of daily average load for the month of February, 1969 j
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YANTEE ATOMIC ELECTRIC COMPANY - OPFRATING SUDIARY February 1969 ELECTRICAL MONTH YEAR TO'DATE Grcss Generation WH 118,888,500 252,2h9,100 9,256,010,900 Sta. Service (While Gen. Incl. Losses)
KWH 7,146,213 15,137,113 609,731,372 Net Output WH 111,7h2,287 237,111,987 8,646,279,528 Station Service 6.01 6.00 6.59 Sta. Service (While Not Gen. Incl. Losses) KWH 182,436 362,388 26,6h6,038 O
Isve. Gen. For Month (672.00)
W 176,917 Ave. Gen. Running (6h6.22)
W 183,975 PLALT PERFORMANCE Net Plan. Efficiency 5
29 22 29 26 28.39 Net Plant Heat Rate btu /KWH 11,680 11,664 12,021 Plant Operating Factor 9h.86 95 39 75 01 Reactor Plant Availability 96.40 96.54 84.16 NUCLEAR MONTH CORE VII TOTAL Hours Critical HRS 65h.08 7,121 97 62,229 39 Times Scrammed 0
2 57 Burnup Core Average MWD /MTU 771.31 8,377 91 Region Average IND/MTU A (INNER) 839 163 8,720.324 26,574.59 B (MIDDLE) 905 159 9,815 0h2 19,802.17 C (OUTER) 611 700 6,705.569 6,705 D (ZIRCALOY) 778.450 8,514.735 8,514.
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