ML19351E174
| ML19351E174 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/20/1967 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19351E173 | List: |
| References | |
| NUDOCS 8011250713 | |
| Download: ML19351E174 (9) | |
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9 Tt'" ij T mal FUa Cy, YANKEE NUCLEAR PGG ST/ TION OPEPaTION REPORT NO. 77 For the month of IRY 1967 O
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YANKEE ATOMIC EIETRIC COMPANY Boston Massachusetts June 20, 1967 8 01 12 r, o 4
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s This report covers the operation of the Yankee Atomic Electric Company plant at Rowe, Massachusetts, for the month of May 1967.
At the beginning of the period the plant was operau ng at i
approximately 180 MWe.
The load gradually decreased.to 179 M4e as a result of continuing deterioration of condenser performance and slowly increasing circulating water inlet temperature.
At 2306 hours0.0267 days <br />0.641 hours <br />0.00381 weeks <br />8.77433e-4 months <br /> May 12 the plant was taken off the line for condenser cleaning and concomitant reactor operator training. By 1558 hours0.018 days <br />0.433 hours <br />0.00258 weeks <br />5.92819e-4 months <br /> May 13 condenser cleaning had been completed, final criticality for plant startup achieved and the turbine phased on the line. At 1715 hours0.0198 days <br />0.476 hours <br />0.00284 weeks <br />6.525575e-4 months <br /> 600 MWt had been attained.
f Throughout the remainder of the period plant load slowly. decreased from 183 MWe to approximately 180 MWe as circulating water inlet temperature increased from h2' tu h6 F.
Concurrent with the condenser cleaning all tubes. vere inspected for leakage by means of both, an ANS soap solution and saran plastic sheets.
Two leaking tubes in the West condenser water box, closely adjacent to the air removal line, were found and plugged.
Sixteen hcurs prior to the shutdown sodium hydroxide was added to the main coolant system "or the purpose of determining the steam 1
generator primary to se adary leak rates.
This was accomplished.by means
/
i off racer techniques usir g the sodium neutron-gamma reaction. product, Na Data analysis showed the inditidual steam generator. leak rates to be as follows; No. 1 - 16 gpd, No. 2 - 60 gpd, No. 3 and No.
h.- less than 0.5 gpd.
At the end of the reporting period the total. primary.to
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secondary leak rate as determined by boron and tritium tracer techniques
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was approximately 110 gpd.
One shipment of spent fuel was made on May.19
.This shipment is the twenty-second in the series of spent fuel shipments, bringing the number of elemants shipped in the ten element cask to 208 and the total number of elements shipped to date to 22h. This shipment constituted.the last of the fuel assemblies stored in the spent fuel storage pit.
On
/D May 1 the control rod shipping cask, loaded with twelve absorber sections and twelve follower sections during the previous r; porting period, left the site.
The cask was returned on May 3, reloaded with an additional ten absorber sections, ten follower sections, and eight irradiAed Charry V-notch test specimens and shipped from the site for disposal May 5 Control rod groups B, C, and D vere banked.at 88 - h/8" on May 25.
This is the fifth step of the Core VI maximum.vithdrawal limit-tation program for..,tribution of guide block wear.
During the reporting period the lower bearing temperatures increased slowly on No. 1 and No. 3 aain coolant pumps indicative of increasing thermal barrier gasket leakage.
At the end of the period No. 1 pump bearing temperature was at 173 F and No. 3 pump, at 150 F; an increase of 12"F and b F respectively for the monLh.
1 The vapor container air leakage rate was normal ohout the reporting period.
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. Plant Scutdowns O
Shutdown No. 89 4 5-12-67 Scheduled shutdown for to condenser cleaning.
5-13-67 Total outage time 16.87 hours0.00101 days <br />0.0242 hours <br />1.438492e-4 weeks <br />3.31035e-5 months <br /> Plant Maintenance The following is a list of the major plant maintenance items performed by the plans staff during the month of May,1967:
J 1.
Seventeen leaking tubes were plugged in the evaporator reboiler and a new shaft seal was installed on the evaporator circulating pump.
Two leaking tubes were plugged in No. 2 feedwater heater during the plant shutdown for the condenser cleaning.
i 3.
All steam generator blowdown radiation monitoring drums were chemically
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cleaned.
h.
No. 3 feedpump outboard end was repacked.
5 No. 1 gravity drain pump shaft and seals were replaced.
l 6.
Cleanup of the ion exchange pit was started, initially by partial pit pump down, and finally by filtration.
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7 Leakage testing of vapor container penetrations was continued with the satisfactory testing cf the main coolant vent header trip valve and the high pressure sample header trip valve.
Instrumentation and Control The following is a list of major instrumentation and control
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maintenance items performed by the plant staff during the month of May,1967:
1.
A defective coil was replaced in the closing circuit of No. 2 ;irculating water pump motor operated discharge valve. The failure of this coil prevented remote operation of the valve.
2.
Two water and air temperature recorders were installed in the Deerfield River downstream of the site.
3.
A tube fitting leak in the charging pump flow transmitter was repaired.
Reactor Plant Performance Core reacti:
,y depleticn was normal at approximately 0.74 % AK/K per 1000 MWtD/lGU.
As a result of the sodium hydroxide addition to the main coolant system for purposes of steam generator primary to secondary leak rate determination, i
i a reactivity gain of approximately 0.23% AK/K was experienced. The addition, at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> May 12 had the following relevant effects on main coolant chemistry:
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. Cond.
Crud Sodium l
Tine j
r a chos a
ppm Prior to addition -
0820 5.2 2.70 0.15 0.0 i
1730 6.0 6.67 2.h8 1.55 At approximately lh50 hours May 13 purification of the main coolant system was initiated for removal of sodium hydroxide and by May 15 excess core reactivity had returned to normal values.
l 1he following parametert were determined by means of incore instrumentation at 599.3 brdt, 524.0 F Tavg.
75 ppm boron, control rod groups B,C, and D at 88 1/8 and group a at 84 6/S:
2.h Fq
=
FaH 1.99
=
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Minimum DIiBh 3.19
=
592.0" F flaximum Outlet Temperature
=
Secondary Plant Performance As a result of
-6 condenser cleaning and plugging of two leaking tubes in !!c. 2 fee'lwater heater a net gain in grosc generation of approximately 3.2 MWe per hour was realized.
Feedwateg heater terminal dif ference at 181 MWe, 2.05" Hg back-pressure and 524.1~F Tavg:
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- 1 - 5.5 F
- 2 - 13. 5 F
- 3 - 1h.6 F Landenser terminal difference:
36.2 F O
Chemistr"y Subsequent to the plugging of the two leaking tubes in the main condenser the team generator average chloride concentrations decreased to less than 0.10 ppm.
Pricr to the repair the average concentration had been apprcximately 0.35 ppm.
The mai coolant boron concentration decreased from 809 ppm to 663 ppm during tt period.
Average main coolant iodine-131 speci'ic activity was 2.05 x 10-5 u:/ml; I-131/I-133 atomic ratio was 0.80.
The average system crud level was 0.16 ppm.
A main coolant crud sample collected on May 12 had the following radiochemical analyses:
dps/mg crud Cr-51 Mn-Sh 00-58 Ag-llom 1.32 x 10 8.85 x 10 3.34 x 10 6.06 x 10 Hf-181 Fe-59 Cc-60 h
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h.27 x 10 1.07 x 10' 1.12 x 10
-h-The silver-110m nuclide was again detected in the crud sample.
Its presence was corrobcrated by analysis of additional camples.
A main coolant gas sample collected on May 11 had the following radioenemical analyses:
pc/cc gas Xe-133 Xe-135 Ar bl
-2
-2
-1 2.E9 x 10 2.02 x 10 2.98 x 10 Health and Safety One shipment of spent fuel was made during the period consi; ting of eight asscmblies with a total activity of 8.32 megacuries.
Gamma radiation levels en contact were a maximum cf 10 mr/hr at the valve box.
Neutron radiation levels at one meter were approximately 0.8 mrad /hr fast and 0.02 mrad /hr slow.
Beta-gamma contamination levels were a maximum of 1.6 x 109 curies /100 cm.
There was no detectable alpha 2
co.camination.
Three shipments of high level radioactive waste were made.
Two, comprising a total of twenty-two complete control rods, absorber and follower sections, and eight Charpy V-notch test specimens were mada on May 1 and May 5 The activity of the two shipments was estimated to e 20,000 curies and 17,000 curies respectively.
Gnmen radia'i.on levels on contact with and at six feet from the external surface of the enclosed vehicle were less than 200 tr/hr and 10 tr/hr respectively, for the shipment on May 1; and less than 18 mr/hr and 4 mr/hr for the shipment on May S.
Eeta-ganna contamination levels were less than 0.1 mrad /hr/100 cm2 for both shipments.
There was no detectable alpha contamination.
The third. shipment was comprised of fourteen drums in a shielded shipping container with a total activity of 1.011 curies.
In addition to the foregoing one shipment of. low level radi -
active waste was made consisting of fifty-six drums with a total activity O
of h67.h me.
1 During May the vaste disposal liquid releases. totaled 260,000 gallcns containing 2.33 =c of grcss beta-gamma activity and 131.79 curies of tritium. Gaseous vaste releases during the.same period totaled 150.2 me of gross beta-g mma activity.
Secondary plant water discharged during the period consisted of 151,000 gallons containing a total of 99 ue of gross beta-gamma activity and 16.h2 curies of tritium.
Radiation exposure doses for Yankee plant personnel, as mea _ured by film badge, for the month of May,1967 were:
Average accumulated exposure dose 93 mrem.
Maximum accumulated exposure dose h68 trem.
. Operations The following Operating Instructions were revised and reissued i
during the period:
OI 50h Al Primary Plant Startup From Cold Condition OI 504 D1 Filling and Venting of Complete System Attached is a sum ary of plant operating statistics and a plot of daily average load for the month of May, 1967 O
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YANKEE ATOMIC ELEDTRIC COMPANY -- OPERATING
SUMMARY
MAY 1967 ELEDTRICAL ENTH TEAR TO DATE Gross Generation WH 131,202,000 53h,199,50C 6,896,660,000 Sta. Service (While Gen. Incl. Losses)
WH 7,86h,511 31,816,663 461,839,485 WH 123,337,489 502,382,837 6,434,820,515 Net Output Station Service 5 99 5.96 6.70 Sta. Service (While Not Gen. Incl. Iosses)
WH 122,052 509,267 24,304,734 Ave Gen. For Month
( 744 h(urs )
Di 176,3h6 Ave. Gen. Running
( 727.13 houra)
W 180,435 PIANT PERFORMANCE Net Plant. Efficiency 28.38 28,81 28.h9 Net Plant Heat Rate btu /WH 12,026 11,846 11,979 Plant Operating Factor 97.37 80.23 71.99 7
Reactor Plant Availability 97 73 91.75 82.83 NUCLEAR ENTH CORE VI TOTAL 727 13 h,665.37 48,391.05 Hours Critical HRS Times Scramed 0
2 5h Burnup Core Average WD/MTU 871.71 h,978.25 Region Average WD/MrU A (INNER) 869.h65 h,991.631 21,764.13 B (MIDDLE) 1,043.168 5,955.692 13,630.9S C (OITTER) 700.136 3,998.680 3,998.68
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YANKEE ATOMIC ELECTRIC COMPANY DAILY AVERAGE IDAD for f4AY 1967 200 -
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100 -
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SHUTDOWN NO. 89-6-4 W
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5 lo 15 20 25 30 DAYS
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CJRE VIRMION IDCATIONS REII)N C REIGN B 4
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