ML19351E023
| ML19351E023 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 08/24/1965 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| References | |
| NUDOCS 8011250447 | |
| Download: ML19351E023 (10) | |
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YANKEE NGOLEAR F0WER STATION 0
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OPHIATION REPORT NO. 55 (gilecopy For the month of JULY 1965 O
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t This report covers the operation of the Yankee Atomic Electric
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Company plant at Rowe, Massachusetts for the month of July 1965 s'
At the beginning of the reporting period the plant was operatini; v
at a pow 6r level of 129 MWe.
" Stretch out" conditions continued throughout the period and the plant was operating at a power level of 108 MRe at the end of the period. The main coolant system was being operated with about 8 ppm of ammonia to elevate the pH and take advantage of the increased core reactivity. On July 7 the ammonia was increased to about 12 ppm and, on July 12, the mumonia was increased further to about 16 ppm to see if a further reactivity gain could be realized with higher pH.
On July 19, the ammonia concentration was reduced to 8 ppm.
The reactivity effects appear in the Reactor Plant Performance section of this report. On July 26, purification flow was started through a mixed bed demineralizer. On July 29, the cation cycle was saturated with ammonia and operation continued in this manner through the end of the period.
The loaded ten element spent fuel cask re nained upon its rail car on our siding with all pumps off and no appreciable heat buildup,
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until July 26, when it was finally shipped to the reprocessing site af ter lengthy nogotiations with railroad representatives.
A cmall, primary to secondary leak has been detected in the No. 3 steam generator.
Presently, the leak rate has been calculated at two gallons per day. Further results are in the Chemistry section of this report.
8 fuel assemblies were received at the plant.
On July 27, fourteen new, h.9h% enriched, stainless steel clad, During the period, group No. h of the pressurizer heaters failed. Investigation and repair will be postponed until the refueling outage, since the remaining groups have more than ample capacity.
r~s A vapor container air charge of 9600 scf was made on July 21
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to restore standard conditions to the internal atmosphere. The average vapor container leakage rate for Core IV operation (since November 196h) has been h.67 scf/hr at an average internal pressure of 1.02 psig.
No plant shutdowns or reactor scrans occurred during July.
Plant Nbintenance Following is a summary of major activities carried out by the plant maintenance staff during July:
1.
Installed sa air conditioning units in the control room.
2.
Disassembled, inspected, modified the gripper, reassembled and returned to service the spent fuel pit manipulator crane.
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. t It is believed that tight tolerances of the gripper head caused the jamming on of the fuel assembly that could not be released (see June 1965 report). The following work was performed: minor burrs smoothed, the slots which accept the nozzle vanes were widened by 1/16", installed new 0-rings on the plunger, the four air hoses were extended four feet above the tool with stainless steel tubing.
3 Installed new hoist limit on the fuel vault crane.
h.
Began installation of the new safety injection tank heating and purification system.
5 Fabricated a fixture for flushing control rod mechanisms.
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6.
Started piping work on the safety injection purification
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7 Disassembled and inspected the No. 3 boiler feed pump.
8.
Reworked No.1 charging pump suction, discharge and relief valves.
9 Replaced a failed coupling half between the spent fuel pit 8
pump and motor. Also replaced the bea: ings on the motor.
10.
Filled and prepared for use a cation bed demineralizer.
11.
Inspected the h80V A.C.B. 's.
12.
A stand for drive shafts was fabricated in order to hold them upright while a weight tube was being removed.
II 13 Began fabrication of a steam generator primary side manwzy seal weld cutter.
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Dye penetrant checked the suction cavity and valve cap of the No. 3 charging pump. This failed to show any crack or pinhole which could be the source of a drip on the inlet flange. The pump will be completely dismantled axi inspeuted during the refueling outage.
Chemister Throughout the reporting period the main coolant oxygen levels were below detection. The system crud level averaged.72 +.20 ppm with no coolant purification and the ammonia at 6.7 ppm.
A rod exercise July 8 increased the crud level to 9.62 ppm.
The previous rod exercise performed with unadjusted pH increased the crud f
i level from 0.77 to 23.2 ppm and, in addition, cansed a reactivity loss.
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A rod exercise July lh increased crud level from 2.5 ppm to
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5.2 ppm.
The I-131 concentration was 9.2 x 10~0 pc/ml rmd I-131/I-133 atomic ratio was 0.39 and they increased to 1.8 x 10-h pc/ml and 2.83 respectively, which are consistent with no purification operation.
The pressurizer capillary vent system was sampled. Flow through the two capillaries was measur A at 57 and h0 lbs/he.
Pressurizer gas concentration was a normal 3?3 ac per liter of condensate. A pressurizer gas analysis was as follows:
N2 23%
H2 72%
0 0.02%
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- Q-A primary to secondary leak has been detected in the No. 3 steam generator. A gross activity of 5 x 10-7 pc/ml was measured in the blowdown water on July 15 Measurement of the I-131/I-133 ratio indicates that the 3% king water is following a somewhat tortuouspath into the secondary water. The leak rate was calculated at 2 gallons per day. At this rate, ealculations indicate that the equilibri tritium concentration in the secondary plant water would be 3 5 x 10- pc/ml. It is unlikely further determinations of the leak rate can be made since purification system
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operation has reduced the main coolant iodine level.
Before purification operation, a buildup in the main coolant of the NA-2h nuclide to 1 7 x 10-1 pc/ml was noted. A 200 ppm sodiuta concentration was detected in the ammonia-feed solution' at the charging pump. A leaking closed valve on the common discharge header of the ammonia and secondary system chemical feed pumps was the cause of sodium contamination. This condition has been corrected.
A 0.02% by volume 02 concentration was measured in flashed gases from the main coolant-system. This is considered normal and is consistent with the to 5 ppb or less dissolved oxygen content in the coolant.
A typical main coolant crud analysis performed on 7/13/65 indicaud:
dpm/mg crud Cr - 51 1.10 x 107
& - 5h 7.88 x 106 6
Fe - 59 5.71 x 10 Co - 58 5.85 x 107 Co - 60 1.06 x 1076 Hf - 181 2 72 x.10 In - ll6m not detectable
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-h-A typical main coolant gas analysis performed on 7/30/65 indicated:
pc/cc gas Xe - 133 2.0 x 10-2 Xe - 135 1.7 x 10-2 A - hl 5.8 x 10-2 The gross beta-gamma activity (without tritium) of the main coolant liquid decreased from 2.1 x 1C-1 Jic/ml to 5.7 x 10-2 pc/ml after purification flow was established.
It is now intended to operate the main coolant system in the high Ph condition,with the ammonia saturated mixed bed domineralizer,
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until refueling in an effort to observe the effects of high pH on the v
cleanliaess of the reactor internal components.
Reactor Plant Performance Routine plant calorimetric data were obtained throughout the reporting period.
Continued the core reactivity follow throughout the period.
8 Approximately 18 Wt had been realized by the injection of approximately 8 ppm of ammonia to the main coolant system. This gain was followed by a four day " flat spot. " A return to a normal depletion rate on July $ resulted in a net gain of +2 Nt from the extrapolated dapletion experienced in May 1965 Llore last month's chemistry test.
The increase in the ammonia concentration from 8 ppm to 12 ppm
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gain in reactivity. Also, the decrease in ammonia from 16 ppm to 8 ppm
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did not result in any measureable loss in reactivity.
The results of one h wire flux wire irradiation ares h06 Wt h75 F T avg.
all rods @ 90 3/8" 2.6 Fq
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$.5 q" DNBR
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52h.$ F Max. outlet temp.
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Turbine Plant Performance Routine secondary plant performance data were acquired and analyzed during the turbine coastdown during the month.
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-Instrumentation and Control i
l Followi:g is a suannary of asjor activities carried -out by the
. plant Instrumentation and Control staff during July:
r 1.
Completed test out of the recently designed and built nuclear l amplifier test setup.
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- 2.. Repaired the primary vent stack gas monitor.
.i 3.
Checked the electronic calibration of the radiation i
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monitoring panel..
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Calibrated two thermomettre for the spent fuel shipping 1
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cask.
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5. Began assembly of equipment to be used-in the forthcoming vapor container leak rate test at elevated pressure.
- 6.. Readjusted the sensitivity of the turbine vibration amplifier.
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Completed the assembly and testing of.a new control rod l
drive test panel.
-8.
Relocated.the pH indicator in the water treatment plant in' an attempt to improve j ts response to pH changes.
9 Repaired several' dosimeter chargers and portable survey meters.
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- 10. Installed tubing for the d/p cell to measure the pressure drop across the purification system filter.
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- 11. Started-installing cable from a vapor container blister for the newrelative humidity deteetor to be installed in the 3
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- vapor container.
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- 12. -Repaired the charging and bleed temperature' indicator.
- 13. Mounted the spare 100 inch manometer in the Primary
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Auxiliary Building for the vapor container pressure test.
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- 14. Recalibrated the main coolant hot leg. narrow range i
temperature channels.
l 15 Installed the new shutdown cooling temperature controller..
- 16. Completed'the installation et the refueling main coolant level indicator wiring in 'aa control room.
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. c Health and Safety During the month of July 196$ the following solid radioactive wastes were prepared and shipped off site for disposal:
1.
Sixty two drums containing a total activity of 1153 millicuries.
19,380 gallons of liquid waste containing a gross beta-gamma activity of 0.03h me and 19.28 curies of tritium were discharged during July. Gaseous waste containing a total activity of 9.5 me was discharged during the same period.
Ten spent fuel assemblies with a total activity of 1.8 megacuries were shipped off site for reprocessing.
The radiation levels on fourteen new fuel assemblies were
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( S 2 - 2.5 mr/hr contact. No evidence of surface contamination or airborne radioactivity was detected.
A check was made of the calibraticn of the radiation monitoring system.
Performed the quarterly cperational check of Civil Defense radiation monitoring equipment, which is stored in the control room.
8 instruments.
Performed calibration checks on various portable curvey A radiation survey of the waste disposal building liquid wtate evaporator showed 500 mr/hr to 2 r/hr on the cone section, and $ - 10 r/hr on the horizontal portion of the reboiler line. Radiation levels on the entrance side of he recently erected shield wall were 20-60 mr/hr general f^)
area.
v Some results of analysis of water samples for tritium by outside firms are:
Sample Tritium activity (pc/ml)
Secondary Side Steam Generators
$.9 x 10-h Circulating Water 4 3 x 10-6 Ion Exchange Pit h.3 x 10-h Drinking Water 43 x 10-6 Sherman Pond c3 x 10-6 Main Coolant (AEK) 1.89 Spent Fuel Pit 5.7 x 10-3 Yankee plant personnel radiation exposures as measured by film badge for the month of July 1965 were:
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102 mr Average for all station personnel
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$00 mr Maximum individual exposure
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Plant Operations Attached is a summary of plant operation statistics for the month of July 1965 and a plot of daily average load for the same period.
The following Operating Instruction (s) and Maintenance Instruction (s) were issued during the month:
506E2 Maintenance Instruction - Reactor Refueling Preparation of Reacter Systems for Refueling - Revised to reflect Core IV-V refueling conditions.
506Eh Maintenance Instruction - Resctor Refueling Fuel and Control Rod Replacement - Revised to reflect Core IV-V refueling conditions.
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(,J sV YANKEE ATOMIC ELECTRIC COMPANY -- OPERATING
SUMMARY
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JULY 1965 EIZOfRICAL M0!TrH YEAR TO DATE Gross Generation WH 89,h30,300 806,559,900 h,769,676,100 Sta. Service (While Gen. Incl. Losses)
WH 6,790,200 51,8hh,680 331,506,789 Net Generation WH 82,6ho,100 75h,715,220 4,h38,169,311 Station Service 7 59 6.10 6.95 Sta. Service (While Not Gen. Incl. Iosses)
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155,936 19,95h,387 Ave. Gen. For honth- (7hh HRS)
W 120,202 Ave. Gen. h nning (7hh HRS)
W 120,202 PIANT PIEFmMANCE Na+, Plant Efficiency 26.91 28.20 Net Plant Heat Rate Btu /WH 12,682 12,102 8
Lbs. Steam / Net W H 13.2 1 1h.00 m
Circulating Water Inlet Temp.
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F h3 Plant Operating Factor 68.79 87.63 71.78 Reactor Plant Availability 100 99.7h 83.89 NUCLEAR
}0 NTH CORE IV TO DATE Times Critical 0
20 3h5 Hours Critical HRS 7hh 7902.62 35,703.31 Times Scransned 0
5 h9 Equivalent Reactor Hours @ 600 Et HRS 511.82 7120.6h 26,009.3h Average Burnup of Core WD/mtU Control Rod Position at Month Ihd Equilibrium at 370 Wt @ h63 P T avg.
REDION*
MONTH TOTAL BUPNUP Oroup A Rods out-inches 90 3/8 Group B 90 3/8 INNER 630.89 17,928.10**
Groitp C 90 3/8 MIDDLE 732.63 15,36h.07 Group D 90 3/8 OUTER h99.28 6,636.80**
E-6 576.0h 29,999.88**
Boron < 1 ppm
- These totals reflect correction of minor errors accumulating since start of Core IV.
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