ML19351E151
| ML19351E151 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/22/1967 |
| From: | Johnson W YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19351E148 | List: |
| References | |
| NUDOCS 8011250671 | |
| Download: ML19351E151 (8) | |
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o pMn YA!IKEE NUCLEAR PCWER STATION OPERATION REPORT NO. 83 For the month of NOVEMEER 1967 Reaktory Formal File Cy, l
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O Subnitted by YANKEE ATOMIC ELECTRIC COMPANY Boston Massachusetts December 22, 1967 so1uso 67/
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l This report covers the operation of the Yankee Atomic Electric Company plant at Rowe, Massachusetts for the month of November, 1967 Plant load at the beginning of the period was 174 IWe.
On November 15, the end of fuel power core life without ph adjustment was reached; plant stretchout operation commenced. At the end of this repcrt period, stretchout operation had resulted in a reactivity depletion 0.27-7 below the 600 IGt level.
On November 13 at 061L hours, a turbine trip followed by a reactor scram occurred. The plant trip was caur.ed by the total loss of instrument air resulting in a trip of tLe heater drain and boiler feed pumps; low level in the four stemn generators then caused the turbine trip and reactor scram.
The loss of instrument air was the result of a mechanical malfunction of the No. 2 air dryer which plugged the air outlet ports O-to the instrument air header.
Instrument air pressure was restored j
with the No.1 air dryer in service.
Reactor startup was initiated, J
the turbine was phased on the line at 1050 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.99525e-4 months <br />.
l A weep type leak through the packing of the No. 4 loop dp cell bypass valve was found during a routir.e inspection inside the vapor container on November 22.
The. leak was secured by installing a cap on the valve.
On November 17 at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />, plant load was reduced to 155 MWe to permit maintenance on the No.1 boiler feed pump inboard motor bearing; load was restored at 2h00 hours.
Fabrication of the new cypress fuel rack platforms for the spent fuel pit was completed.
During the period it was concluded that the deterioration of tne spent fuel pit phenolic protective coating
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precludes patchwork repair.
In addition, it van determined th9t the total phenolic material would be removed and the pit refurbished with an epoxy base coating. Plans for this job were incomplete at the and of this report period.
The vapor container air leakage rate was normal throughout the reporting period. The fifth core VI air charge to the vapor container began on November 30 and was still in progress at the end of this report period.
Plant Shutdowns:
l Chutdown No. 92-6-7 11/13/67 Reactor scram, due to loss of instrument air.
j Total outage time: 2.6 h*
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s Plant Maintenance The following in a lict of najor plant maintensnee items perforned by the pluit staff during the month of Ilove::.hr,1967:
1 1.
A bypass around the steam supply valve to the vaste di sposal evaporator reboller was installed.
2.
The vaste holdup and activity dilutien decay taru irain cumps were modified to prevent freezing in cold weather.
i 3.
All valves in the No.1 and No. 2 ir.strument air compressors vere replaced.
h.
The No.1 boiler feed pump inboard gland was repacked; the i
coolin6 vater cavity uns cleaned and the inboard notor bearing vaa repaired.
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5 The No. 2 air dryer solenoid valve relay 1,1unger was replaced.
6.
It "hydropad" was installed in the Ha. 2 charging p mp discharge line for suppression of charging line vibration.
7 Two leaking drain line traps under the H.P. turbine were repaired.
Instrumentation and Control The following is a list of major inutrunentation and control maintenance items performed by the plant staff during tl.e month of November, 1967 1.
A new intercom system was assembled for uae during calibraticns.
2.
The design and fabrication of a prototype limit switch for the core flux vire system were ccapleted.
l 3.
A cap was installed on the No. h loop dp cell bypass valve to secu e a veep type leak.
Reactor Plant Performance At 2204 hours0.0255 days <br />0.612 hours <br />0.00364 weeks <br />8.38622e-4 months <br />, on November 15, the end of full power core life without pH adjustment was reached.
Average core burnup at this time was 9225.93 MWtD/MTU.
The following parameters were determined by means of incore instrumentation at 599.5 'Gt, 525.8 Tavg, 40 ppm boren, control grcups B, C, and D at 89 5/8 and group A at 87 3/8.
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2.0 AH 3.13 Min. DNBR
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Maximum outlet temperature 59k.0 F This data was collected on November 3 and is the same information that was submitted in the previous report.
i Chemist ry At the start of the period the coolant boron concentration j
was reduced from 83 ppm to 38 ppm by dilution.
A partially exhausted l
anion demineralizer was placed in service and the coolant boron concentration was further reduced to h ppm on November 6.
A new mixed bed de:nineralizer was installed in the purification system and the remaining boron was removed.
An average crud level of 1.2 ppm van experienced during the period; this crud concentration is somewhat higher than normal. The increase in crud level was caused by control rod movement associated I
with the reactor scram and load reduction that occurred on November 13 l
and November 17, respectively, j
1 The average coolant gross specific activity was 6.1 x 10~
ue/ml. Main coolant avera6e iodine-131 specific activity was 2.0 x 10-5 ue/ml; the iodine 131/133 atomic ratio was 1.01.
Aftor boron was removed from the system, thus ending the need for further dilutions, the coolant tritinn concentration increased from 0.78 ue/ml to 1,81 uc/ml.
O A representative crud sample for the month, collected on November 24, had the folleving radiochcmical analyses :
dpm/mg crud.
Cr-51 Hf-181 Ma-54 Fe-59 1.hl x 106 2.62 x 10 1.h8 x 106 0
1.17 x 10 co-58 Co-60 Ag-110M 6
6 2.h8 x 104 7.68 x 10 2.50 x 10 A main coolant gas sample collected en November 21 had the following radiochemical analyses : ue/cc gas Xe-133 Xe-135 Ar bl
-2 7.26 x 10 b 1.58 x 10-3 2.00 x 10 l
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The second phase of the Core VI pressurizer test program was completed. The purpoce of this phase was to i
determine gas concentrations in the pressurizer vapor phase after a period of plant operation with unborated unadjucted pH main coolant chemistry. This data is compared with inform-f ation compiled during a similar test in February with borated l
coolant.
PRESSURIZER VENT TEST RESULTS 3
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%H M.C. Eystem Time After Sample Date
, Venting (hr)
Locatioa 2
2 2
cho.inery 2/16/67 5
Middle 0.5h 29.6 69.9 Borated; Unadjusted pH 2/16/67 6
Middle 1.68 74 9 23.h Borated; Unadjusted pH
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2/16/67 7
Middle 1.68 75 0 23.3 Borated; Unadjusted pH 2/21/67 6
Top 0.29 19 9 79.8 Borated; Unadjusted pH 11/30/67 3
Middle 0.05 10.h 89.6 Unborated; Unadjusted pH 11/30/67 h
Middle 0.05 9.7 90.3 Unborated;Unaijusted pH 11/30/67 1
Top 0.0L 9.7 90.3 Unborated; Unadjusted pH 11/30/67 2
Top 0.0L 9.6 90.h Unborated; Unadjusted pH Health and Safety One shipment of radioactive waste containing 6C drums with a total activity of 256.6 mc was made during November.
Waste disposal liquid releases totaling 1L2,962 gallons O
contained 195 uc er gross beta, garma activity and 225.31 curies of tritium. Gaseous releases during this period were 6.86 me of gross beta, gamma activity. Secondary plant water discharged was 190,382 gallons and contained a total of 6.3 uc of gross beta, gamma activity and 136.h me of tritium.
Radiation exposure doses for Yankee plant personnel as measured i
by film badge for the month of November 1967 vere as follows:
Average accumulated exposure dose 97 mrem l
Maximum accumulated exposure dose h11 mrem 1
Crerations Attached is a summary of plant operating statistics and a plot of daily average load for the month of November,1967.
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n YANKEE ATOMIC EIETP7: COMPANY -- OPERATING
SUMMARY
- ovesER 1967 EIETRICAL
!ONTH YEAR TO DATE Gross Generation WH 126,066,600 1,221,525,300 7,583,985,800 Sta, Service (While Gen. Incl. Losses)
WH 7,77h,673 Th,67h,3h5 504,697,167 Net Output WH 118,291,927 1,146,850,955 7,079,288,633 Station Service 6.17 6.11 6.65 Sta. Service (While Not Gen. Incl. Iosses)
WH 12,289 1,010,060 24,805,527 Ave. Gen. Scr Enth 720.00 W
175,093 Ave. Gen. Running 717.L0 W
175,727 PIANT PERFORMANCE Net Plant. Efficiency I
27 97 28.05 28.39 h
Net Plant Heat Rate Bru/WH 12,201 12,167 12,021 Plant Operating Factor 97.91 85.00 73.26 Reactor Plant Availability 99.86 91.18 83.19 NUCLEAR 10 NTH CORE VI TOTAL Hours Critical HRS 719.02 8650.h9 52.376.17 Times Scramed 1
3 55 Burnup Core Average WD/MPU 8h8.32 9679.h3 Region Average ND/MTU A (INNat) 66h.790 9,Th3.h39 26,515.94 B (MIDDLE) 1010.32h 11,579 958 19,255.2h C (OUTER) 684.391 7,770.35h 7,770.35
YA ATOMIC EIET OMPANY s
DAILY AVERAGE IDAD for 53VEGER 1967 200 -
m it od 150 -
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S Shutdown No.
84 92-6-7
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100 -
ts 4a m
50 -
W e
m 5
10 15 20 25 30 DAYS
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CORE VIRWIOtl IDCATIOtiS
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