ML19351E050
| ML19351E050 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/21/1969 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19351E047 | List: |
| References | |
| NUDOCS 8011250536 | |
| Download: ML19351E050 (9) | |
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YAIEEE NUCLEAR POTER 5
- TION 8
OPERATION REPORT NO. 96 For the Month of December 1968 Submitted by YA?EEE ATOMIC ELECTRIC COMPANr 8 U Massachusetts January 21, 1969 i
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NJ This report covers the operation of the Yankee Atomic Electric Company plant at Rowe, Massachusetts for the month of December, 1968.
Plant load varied between 186.2 MVe and 187.9 FMe as circulr_cing water inlet temperature fluctuated between 39 F and 340F.
Vapor container air leakage was normal during December, 1968. The current surveillance period is the fifth for Core VII.
The monthly control rod exercise and other rout':.e tests were completed, successfully. Control rod Groups B, C & D were moved out one step to 89 5/8 as part of the rod step wear program.
No plant shutdowns or reactor scrams occurred during the mcnth of December, 1968.
Plant load reductions during the perioc were as follows:
December 5 (1145 - 1315)
Load reduction to 135 LMe; turbine throttle valve monthly test.
A representative from the International Atomic Energy Agency reinstalled seals on the reactor head missile shield; the seals had been removed t ) permit removal of the missile shield during the scheduled maintenance outage in November.
Plant Maintenance W
The following is a list of pertinent maintenance items performed by the plant staff during the month of December, 1968.
1.
The spent fuel pit laydown mechanism has been removed for inspection.
Six h" ports have been cut in each shell of the No.1 and No. 2 component l
cooling water heat exchangers to facilitate cleaning around the fixed tube bundles.
3.
The No. 1 charging pump was repacked and new plungers were installed.
h.
Fabricatien of an angle head for the underwater television camera was continued.
Instrumentation and Control The following is a list of pertinent instrumentation and centro _ maintenance performed by the plant staff during the month of December, 1968.
1.
Work was continued on modifications to the incore flux wire system.
2.
Work continued on assembly of a control rod position primary indication system.
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, 1 Reactor Plant Performance The following parameters were determined by means of incore instrumentation:
597 7 but; 527 5 Tavg; control Rod Group A @ 81 6/8; B, C, D @ 89 2/8; 291 ppm baron.
1 79 F
=
q l'Ik F
AH l
Minimum DNBR 3.53
=
582.2 Maximum outlet temperature
=
Secondary Plant Performance Feedwater heater terminal differences were as follows:
No. 1 = 6.10F No. 2 = 10 9 F No. 3 = 6.1 F The condenser performance was as follows:
186.h bMe; 1.09" Hg B.P. ; 597.7 FMt; 3h.9 F C.W. in T.T.D. = 22.7CF; cleanliness factor = 100%
Chemistry The main coolant boron concentration was decreased from 382 ppm to 251 ppm during the period to compensate for normal core depletion. Average main coolant pH was 5.6.
-2 Coolant average gross beta-gamma activity and crud level were 7 97 x 10 ue/ml and 0.02 ppm, respectively.
The main coolant tritium specific activity averaged 2.25 ue/ml during the month.
The iodine - 131 specific activity was 1.89 x 10-5 ue/ml and the iodine 131/133 atomic ratio was 0.89, indicating the absence of detectable fuel defects.
A representative crud sample for the month, collected on December 13, had the following radiochemical analyses: dpm/mg crud Cr-51 Mn-Sh Fe-59 6
6 h.18 x 106 2.59 x 10 1 51 x 10 Co-58 Co-60 Ag-110M 1.8h x 107 6.47 x lob 1,oi x 105
5 w 0 A main coolant gas sample collected on December 26, had the f allowing radiochemical analyses: uc/cc gas Xe-133 Xe-135 Ar-kl 2.05 x 10-2 3.01 x 10-2 2.h2 x 10-1 Phase I of the Core VII pressurizer gas test program ha.s been performed.
The top right capillary and the interface capillary were sampled to determine that there was only negligible oxygen in the pressurizer gas phase after the extended tenting period; this was verified and the capillaries were secured.
After remaining unvented for 2 weeks the top right capillary and interface capillary were opened and sampled. The oxygen concentration hsd not increased nor had the quantity of gas increased significantly as in the past.
It appears from these results that the leaking solenoid relier valve had provided sufficient venting to preclude the buildup of gases in the vessel. Test results are as follows:
CC gas Condition Capillary Kg Condensate
%0
% Up
%H 2
2 Vented Top right 352
.05 16.6 83.3 2 weeks unvented Top right h90
.05 15.4 84.5 2 weeks unvented Interface h10
.03 13.7 86.2 Health and Safety Waste disposal liquid releases totaling 57,430 gallons contained 0.0Th me of grocs beta-gamma activity and 18h.1 curies of tritium. Gaseous releases during this period were 168.0 me of gross beta-gamma activity. Secondary plant water discharged was 230,213 gallons and contained 0.003 me of gross beta-gamma activity and 0.73 curies of tritium.
Three shipments of lov level radioactive vaste were made during the period.
A total of 156 drums containing a total activity of 283.16 me were shipped from the site.
Radiation exposure doses for Yankee plant personnel, as measured by film badge, for the month of December, 1968 vere as follows:
Average accumulated exposure dose:
3h mrem f
Maximum accumulated exposure dose:
194 mren Operations Attached is a summary of plant operating statistics and a plot of daily average load for the month of December, 1968.
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A revised " Operating Summary" for November,1968 is includea in this report, correcting an error in the Station Service (while not generating including losses) IGiH to date. The erroneous total of 1,478,123 KWH has l
been corrected to rear. 26,283,650 KWHs 1
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=-mmm apm mmm_
_m, YANKEE ATOMIC EIHRRIC COMPANY DAILY AVERAGE IDAD for December 1068 200 -
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YANKEE ATOMIC ELECTRIC COMPANY - OPERATING
SUMMARY
December 1968 ELECTRICAL MONTH YEAR
% DATE Gross Generation KWH 138,925,000 1,292,877,200 9,003,761,800 Sta. Service (While Gen. Incl. Losses)
KWH 8,262,998 81,927,326 594,594,259 Net Output PH 130,662,002 1,210,949,874 8,k09,167,541 Station Service 5 95 6.34 6.60
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Sta. Service (While Not Gen. Incl. Losses) KWH 0
1,L78,123 26,283,650
~
Ave. Gen. For Month (744.00)
KW 186,727 Ave. Gen. Running (744.00)
KW 186,727 PLAET PERFORMANCE Net Plant Efficiency 29 38 28.23 28.37 Net Plant Heat Rate btu /KWH 11,616 12,089 12,029 Plant Operating Factor 99.63 81.40 Th.58 Reactor Plant Availability 5
100.00 87.68 83.91 NUCLEAR MONTH CORE VII TOTAL Hours Critical HRS 744.00 57h3.26 60,850.68 Times Scrammed 0
2 57 u,J Burnup Core Average MWD /MTU 896.93 6743.56 Region Average MWD /MTU A (INNER) 961.405 6925.71T 2h,779 99 B (KiDDLE) 1051.3h8 7896.382 17,883.81 C (OUTER) 714.545 5412.160 5,412.16 D (ZIRCALOY) 905 349 6866.797 6,866.80 e
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1 YA'.1EE ATOMIC ELECTRIC COMPANY - OPERATING
SUMMARY
November 1968 ELECTRICAL MONTH YEAR
'ID DATE Gross Generation KWH 103,257,000 1,153,952,200 8,864,836,800 Sta. Service (While Gen. Incl. Losses)
KWH 6,136,732 73,664,328 586,331,261 Net Output KWH 97,120,268 1,080,287,872 8,278,505,539 Station Service 5 94 6.38 6.61 L,.
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Sta. Service (While Not Gen. Incl. Losses) KWH 306,892 1,478,123 26,283,650*
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Ave. Gen. For Month (720.00)
KW 1h3,413 Ave. Gen. Running (559 03)
KW 184,707 PLANT PERFORMANCE Net Plant Efficiency 29.20 28.09 28.35 Net Plant Heat Rate btu /KWH 11,688 12,149 12,038 Plant Operating Factor 76.98 79 72 74.29 Reactor Plant Availability 77.75 86.5h 83 74 NUCLEAR MONTH CORE VII TOTAL Hours Critical HRS 572 95 4999.26 60,106.68 O
Times Scrammed 2
2 57
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Burnup Core Average MWD /MTU 670.65 5846.63 Region Average MWD /MTU A (INNER) 710.659 5964.312 23,818.58 B (MIDDLE) 779 775 6845 034 16,832.46 C (OUTER) 542.140 4697.615 4,697.62 D (ZIRCALOY) 678.975 5961.448 5,961.45
- NO ported in error on November 1968 eration Report No. 95
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