ML19351E132
| ML19351E132 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/26/1968 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19351E130 | List: |
| References | |
| NUDOCS 8011250648 | |
| Download: ML19351E132 (9) | |
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k YANKEE ?UCLEAR POWER STATION OPERATION REPORT NO. 85 For the month of JANUARY 19frT
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' o Submitted by YANKES ATOMIC ELECTRIC COMPANY l ' ~'
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February 26, 1967-fy'/,
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This report covers the operation of the Yankee Atomic Electric Company plant at Rowe, ' Massachusetts for the month of January,1968.
r~s Plant load at the start of the period was 164 MWe; plant I stretchout operation resulted in a load decrease to 148.7 MWe at the end
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of the period.
On January 22 a rapid increase in the steam generator blowdown water chloride concentration from 0.05 ppm to 0.60 ppm occurred. At 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> plant load was reduced to 90 MWe and an entry into the main condenser vest side water box was made. One leaking tube in the non condensable gas offtake region was found and plugged; in addition, two adjacent tubes were plugged as a precautionary measure. Plant load was restored at 2111 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.032355e-4 months <br />. The steam 6enerator chloride level decreased and appeared to equilibrate at app aximately 0.h ppm. On January 25 at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> plant load was reduced to 95 MWe and a second inspection was made inside the condenser veut water box; no tube leaks vere detected. Plant load was restored at lh00 hours and steam generator blevdown rates were increased. At the end of this report period, steam generator chloride concentration had decreased to C.2 ppm.
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The sandblasting phase of the spent fuel pit refurbishing program
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was completed. Blasting sand was removed from the pit and a general area cleanup was completed in preparation for the application of the protective coating. At the end of the period, the base coating was being applied to the pit valls.
Plant load was reduced to 135 MWe on January 5 at 1205 hours0.0139 days <br />0.335 hours <br />0.00199 weeks <br />4.585025e-4 months <br /> for the monthly exercise of the turbine throttle valves; no abnormal behavior vas observed and plant load was restored at 1303 hours0.0151 days <br />0.362 hours <br />0.00215 weeks <br />4.957915e-4 months <br />.
A control rod exercise was performed on January 10; all rods operated normally. On January 25 control groups A, B, C, D vere moved out one step; this completes the Core VI rod step wear program.
Representatives from the International Atomic Energy Agency visited the plant during the period to verify that the seals on the reactor vessel head missile shield were intact; the vest seal was redated
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and replaced.
The sixth Core VI air charge to the vapor container was in progress at the end of this report period. The containment leak rate from December 1 to January 30 was computed to be 0.025% per day, ho plant shutdown or reactor scrams occurred during the month of January.
Plant Maintenance The following is a list of pertinent plant maintenance performed by the plant staff during the month of January, 1968.
1.
One vaste disposal process bottoms pump was relocated to a position adjacent to the distillate pump; this pump will function as a permanent spare distillate pump.
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Stainless' steel platforms that vill raise -the spent fuel storage racks 2.
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off the bottom of the pit floor are being fabricated.
'3. The No. 1 boiler feed pump was removed from service for routine inspection and maintenance.
4.
A pressure indicator was installed in the safety injection line upstream from the CS-MOV-535 valve; this modification permits leak tightness testing of the check valve dow. tream from the CS-MOV-535 valve.
Instrumentation and Control The following is a list of pertinent instrumentation and control maintenance items performed by the plant staff during the month of January, 1968.
The TCNR and TICIR temgerature channels were recalibrated to a 455 F -
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1.
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505 F and h800F - 530 F range, respectively; this change is required during plant stretchout operation.
2.
A high pressure switch was placed on the recently installed pressure indicator line from the safety injection system piping; a 300 psi signal vill activate a panalarm on the main control board.
3.
Testing or spent fuel pit radiation monitoring equipment was completed.
Reactor Plant Performance The following parameters were determined by means of incore instrumentation at 522 5 MWt, 508 F Tavg, 0 ppm boron, control groups A, B, C, and D at 90 3/8 inches.
2.35 F
=
2.03 A
=
H 3.97 Minimum DNBR
=
568.5 F Maximum outlet temperature
=
Chemistry Main coolant ammonia concentration averaged 12.1 ppm. The average coolant specific activity and crud level were 7.5 x 10-2 ue/ml and 0.25 ppm, respectively.
Iodine-131 specific activity was 2.6 x 10-5 ue/ml; iodine 131-133 atomic ratio was 0.91.
Main coolant tritium concentration varied between 1.59 ue/ml and 1.74 uc/ml.
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.___.__ _ -The third and final phase of the Core VI pressurizer test program was completed. _ Gas concentrations in the vessel vapor space were determined for unborated, ammoniated coolant water chemistry. Phase II and III testing sequences were essentially the same_as phase I testing when substantial oxygen concentration 3 vere observed. However, prior to phase II testing, a leak in the pressurizer-No. 1 safety vlave developed. This leak was equivalent ~to the steam flev produced by one capillary vent. Data analysis must take account of this fact.
. Phase I and II data were reported in Operation Report No. 83;
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phase III test results are as follows:
i Time After Sample
%0
%N
%H 78 **
Date Venting (hr)
Location 2
2 2
Chemistry 1/9/68 2
Middle 0.03 28.8 71.9 Unborated, ammoniated z
1/9/68 3
Middle 0.03 28.6 71.'4 h
ruddle 0.02 28.7 71.3 O
1/9/68 l
1/9/68 1
Top 0.02 20.8 79.2 l
1/10/68 20 Top 0.03 27.0-73.0 i
A representative crud sample'for the month, collected on January 19, j
had the following radiochemical analyses: dpm/mg crud cr-51 Hf-181 Mn-Sh Fe-59 6
g 6
6 3.35 x 10 8.10 x 10 2.94 x 10 1.88 x 10 3
Co-58 co-60 A -110M E
h 7
6 1
2.23 x 10 6.11 x 10 5.38 x 10 4
A main coolant gas sample collected on January 31 had the following radiochemical analyses: uc/cc gas Xe-133 Xe-135
-3
-3
-2 1
5.h5 x 10 9.77 x 10 2.28 x 10 i
Health and Safety Waste disposal liquid releases totaling 28,3ho gallons contained 53.4 ue of gross beta-gar:ma activity and 34. 2 curies of tritium. Gaseous i
releases during this period were 13.8 me of gross beta-gamma activity.
i Secondary plant water discharged was 390,522 gallons and contained a total l
of 15.1 ue of gross beta-gamma -activity and h21.0 me of tritium.
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h-Radiation exposure doses for Yankee plant personnel, as measured by film badge, for the month of January,1968 vere as follows:
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Average accumulated exposure dose 105 mr.
Maximum accumulated exposure dose 400 mr.
The following is a su= mary of all liquids, gases, and solids released, discharged or shipped from the plant during the year 1967.
Waste Dianosal Liquid: 2,567,752 gallons containing a total activity of 55.78 me and 1,463 curies of tritium.
Gas:
A total beta-gamma activity of 2.31 curies and 15.07 curies of tritium.
Airborne Particulate: A total of 139.4 ue of beta-gnema 7-s
(_)
activity.
Solids for Disposal:
827 drums containing a total activity of h.76 curies and h casks containing a total activity of 37,001.55 curies.
Secondary Plant (n)
Liquid: 2,679,776 gallons containing total beta-gamma and tritium activities of 0.36 me and 126.hh curies, respectively.
Fuel Shipments During 1967 there were 6 spent fuel shipments totaling 52 elements with a total activity of 64.95 megacuries.
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The format of reporting plant discharges is being revised; steam generator blowdown water releases which had been reported as a discharge from vaste disposal will be included as a secondary plant release. On this btsis, plant discharges for the year 1967 vould be as follows:
Waste Disposal Liquid:
522,61h gallons containing a total activity of 3.421 me
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and 1,h39.86 curies of tritium.
Gas:
A total beta-gamma activity of 2.31 curies and 15.07 curies of tritium.
Airborne Particulate: A total of 139.h uc of beta-gamma activity.
f 'x Solids for Disposal:
827 drums containing a total activity of N
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4.76 curies and h casks containing a total activity of 37,001.55 curies.
_ _ _ _ _ _ - _ _ _ _ _.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _. _.... _ _ _ _ _ _ _ _ _ _ ~ _ -. _... - _... _ - - _..
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Secondary Plant and Miscellaneous t
Liquid: h,724,914 gallons containing total beta-gamma and I
tritium activities of 51.72 me and lh9 58 curies,
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respectively.
j Fuel Shipments t
During 1967 there were 6 spent fuel shipments totaling 52 l
elements 'vith a total activity of 64.95 megacuries.
Operations r
j The following Operating Instruction and Maintenance Instructions vere revised and reissued during January.
505 B 11 Large or Partial Loss of Main Coolant j
506 E 2 Preparation of Reactor Systems for Refueling 506 E h Fuel and Control Rod Replacement i
4 j
Attached is a summary of plant operating statistics and a q f plot of daily average load for the month of January,1968.
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YANKEE ATUMIC ELEI:TRIC Ci a ANY -- OPERATING
SUMMARY
JANUARY 1968 EIETRICAL 10 NTH YEAR TO DATE Gross Generation WH 115,69h,h00 115,694,h00 7,826,579,000 Sta. Service (While Gen. Incl. Losses)
DGI 7,503,106 7,503,106 520,170,039 Net Output WH 108,191,29h 108,191,29h 7,306,408,961 Station Service 6.49 6.49 6.65 Sta. Service (While Not Gen. Incl. Iosses)
WH 0
0 24,805,527 Ave. Gen. For Ibnth 7hh.c W
155,503 Ave. Gen. Running Thh.0 N
155,503 PIANT PERFORMAN::E Net Plant. Efficiency 5
28.39 28.39 28.39 4
Net Plant hat Rate Bru/WH 12,021 12,021 12,021 Flant Operating Factor 5
85.38 85.38 73.68 Reactor Plant Availability 100.00 100.00 83.58 NUCLEAR 10 NTH CORE VI TOTAL Hours Critical HRS Thh.00 10,138.h9 58,864.17 Times Scr===aa 0
3 55 Burnup Core Average ND/MPU 764.39 11,285.53 Region Average WD/MrU A (INNER) 773.138 11,369.491 28,1hl.99 B (MLDDLE) 913.147 13,h9h.294 21,169.58 C (OU'?ER) 61h.559 9,065.739 9.065.74
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