ML19351E344
| ML19351E344 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 07/20/1969 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19351E343 | List: |
| References | |
| NUDOCS 8011280144 | |
| Download: ML19351E344 (7) | |
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hebdatcfry YANKEE NUCLEAR POWER STATION OPERATION REPORT NO. 102 For the Month of June 1969 E i! M 1 0 ! E U LAT 0!!Y C E li M L FILE 8 Il00hi013 Submitted by YAUKEE ATOMIC ELECTRIC COMPANY Bosten Massachusetts July 20, 1969 l
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f This report covers the operation of the Yankee Atomic Electric j
Company plant et Rowe, Fassachusetts fo-the month of June,1969 t
Plant load at the start of the period was lh6.3 MWe; continued plant stretchout operation resulted in a load decrease to 123.3 MWe at the i
j end of the period.
The second shipment of new fuel for Core VIII was delivered on-site, and consisted of 12 assemblies.
1 The eighth vapor container air charge surveillance period was j
terminated on June 16 with only negligible leakage recorded..The ninth surveillance period commenced on June 17, and-continued through the end of the report period.
All routine tests were completed, successfully.
I On June 3, with the primary to secondary leak rate at a, prox-imately 600 gallons per day, the No. h loop was isolated from the main coolant system. Just prior to the loop isolation, the No. 4 loop main l
steam line safety valves were tested. The two 2 " valves were tested first, satisfactorily, using a commercial lifting device. The 6" valve lifted at an air pressure corresponding to 1070 psig steam pressure, and stuck open. Attempts to seat the valve by using the hand lifting lever and tappin6 the stem, were unsuccessful. The valve was finally seated by use of a gag.
A slight leak remained after the valve was gagged. At this time, the isolation of the No. h loop was completed, and the stop valves and main coolant pump were rendered inoperative. No adverse effects were detected on other plant systems during the duration of the safety valve blow. The valve blew for approximately 15 minutes, and correlation of feed water flow, for level stabilization, indicated a total blow of about 5720 pounds of water.
I On June ll, a sodium tracer was introduced into the main coolant system for the purpose of determining the steam generator primary to secondary leak rates.
This was accomplished by monitoring for the-codium - 2h activation product. Analysis of the results of the test showed steam generators No.1, 2, and 3 to be leaking at a rate of _less.
than one gallon per day, with No. h steam generator responsible for essentially the entire leakage volume.
Plant Abnormal Occurrences 1
There were no plant abncrmal occurrences during the month of i
June, 1969 Plant Load Reductions Load reduction to 120 MWe; turbine June 3 (1130 - 1230) throttle valve monthly test.
June 3 (1230 - 1LLS)
Further load reduction to 110 MWe; No. L main coolant loop safety valves test.
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i t 4 Plant Shutdowns There were no plant shutdowns during the month of June,1969 l
Plant Maintenance l
The following is a list of pertinent maintenance items performed I
by the plant staff during the month of June,1969 I
1.
The No. 1 heater drain pump and motor vere inspected. The bearings, one top bowl, three intermediate' bowls, and the chaft sleeve. vere i
replaced in the pump; the thrust bearing vas replaced in the motor.
2.
The aluminum and bcral fuel racks and the lay-down rechanism were repositioned in the spent fuel pit.
i 3
One pnewnatic hose line was replaced on the spent fuel pit ~ manipulator crane too2 boom.
4.
The two hydraulic hose lines-on the lay-down mechanism in the spent fuel pit, were replaced.
5.
The steam generator manway diaphragm seal veld cutter performed satisfactorily during mock-up practice cuts.
Instrumentation and Ccatrol The following is a list of pertinent instrumentation and control maintenance items performed by the plant staff during the month of June, 1969 1,
The No. L steam generator steam flow and feed water flov transmitters and integrators were cleaned and recalibrate-l.
Reactor Plant Performance The following parameters were determined by means of-incore instrumentation.
hhh 5 MWt; L96.6cF Tavg; Centrol Rod Group A, E, C, D @
j 90 3/8"; o ppm'boren.
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Sh6.7 F Maximum cutlet temperature
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Chemistry I.
The main coolant ammonia concentration and pH averaged 12.0 ppm and 9.66 respectively.
Operation Report No. 101 (May, 1969) reported this item as Eq = 1 7 This l
item stands corrected to read FAH = l 7-
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. 4 6.Th x 10-2 ue/ml and 0.03 ppm respectively.
The main coolant beta-gamma activity and crud level averaged l
l The main coolant tritium concentration averaged h.29 x 10-1 uc/ml during the period.
The iodine - 131 specific activity was 2.23 x 10-5 ue/ml and the iodine 131/133 atomic ratio was 0.hl, indicating the absence of detectable fuel defects, A representative crud sample for the conth, collected on June 4, had the following radiocheuical analyses:
dpc/mg crud or-51 Mn-SL Fe-59 2.02 x 10 1.56 x 107 1.h0 x 107 7
Co Co-60 Ag-110M 0
2,07 x 10 1.29 x 10' 7
1.17 x 10 A main coolant gas sample collected on June 2h had the following radiochemical analyses: uc/cc gas Xe-133 Xe-135 Ar bl 2.67 x 10-3 7.Th x 10-3 1.30 x 10-1 Health and Safety Four shipments of radioactive waste were made during the period, containing a total activity of ~ 75 curies.
Each of the fcur l
t hipments consisted of approximately LO ft3 of expended icn exchange resins in a single shielded inner container.
Waste disposal liquid releases totalled h3,376 gallcus containing 0.059 me of gross beta-gamma activity and 27.66 curies of tritium. Gasecus releases during the period totalled LL5.2 cc of gross beta-gamma activity and 63.1 me of tritium.
Seccndary plant water discharged, totalled L7b,623 gallons containing h.76 m: of gross beta-gamma activity and 1T.22 curies of tritium.
In addition to the abcVe releases, 0,33 uc of grocs beta-gamma activity and 62 me of tritium as a vapor were discharged to the atmosphere curing the No. L loop main steam line safety valve test.
Radiation exposure doses for Yankee plant personnel, as measured by film badge, for the month of June, 1969, were as fcllows:
Average accumulated expcsure dose:
93 mrem.
I Maximum accumulated exposure dose:
550 trem.
Oteratione Attached is a summary of plant operating statistics and a plot of daily average load for the month of June, 1969
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YANKEE ATOMIC ELECTRIC COMPANY - OPERATING
SUMMARY
June 1969 l
l ELECTRICAL MONTH YEAR TO LATE Gross Generation KWH 93,298,000 698,73h,h00 9,702,496,200 Sta. Service (While Gen. Incl. Losses)
KWH 6,138,363 43,551,853 638,146,112 Net Output KWH 87,159,637 655,182,547 9,06h,350,088 Station Service 6.58 6.23 6.58 Sta. Service (While Not Gen. Incl. Losses) KWH 0
799,44h 27,083,09h p
Ave. Gen. For Month (720.00)
KW 129,581 l
V Ave. Gen. Running (720.00)
KW 129,581 PLANT PERFORMANCE l
Net Plant Efficiency 27.h0 28.75 28.ho l
Net Plant Heat Rate btu /KWH 12,h55 11,870 12,017 Plant Capacity Factor 73.63 87.47 75 37 Reactor Plant Availabil.ity 100.00 96.00 8h.61 I
l MONTH CORE VII TOTAL l
NUCLEAR l
l Hours Critical HRS 720.00 9,935.98 65,0h3.40 i
Times Scrammed 0
2 57 Burnup i!O Core Average M4D/MTU 641.h3 11,340.08 i
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l Region Average MJD/MTU i
l A (INNER) 685.68 11,925.78 29,T80.06 B (MIDDLE) 728.05 G,2h2 96 23,230.39 l
l C (OUTER)
Sh0.h9 9,118.25 9,118.25 l
D (ZIRCALOY) 623 72 11,h39 27 11,439 27 s
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7 tar 4KEE ATOMIC ELECTRIC _C0!jfAM DA.CLY AV!.!UGE LOAD for June 1969 200 -
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