ML19351E158
| ML19351E158 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 11/30/1967 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19351E155 | List: |
| References | |
| NUDOCS 8011250682 | |
| Download: ML19351E158 (9) | |
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YANKEE NUCLEAR F0WER STATION OPERATION REPORT NO. 82 For the month of OCTOBER 1967 i
1 Subai tted by YANKEE ATOMIr ELECTRTC 00:2ANY Boston Massachusetts November 30, 1967 9
son 230 GBR
1 j,
l being fr.bricated.
In addition to the removal of the platforms 4
l the boral fuel storage rack and fuel assembly up-ender vere also removed from ~the pit and transfered to the decontamination.
building for decontamination. Shortly thereafter final cleaning l
and inspection of the pit was initiated. During the course of l
this inspection it was noted that the blisters previously l
observed and inspected in the phenolic coating on the valls l
Vere more prevelent in the area immediately. adjacent.to the i
location of the aluminum storage racks. Additionally, it was noted that there was a small but centinuous vertical crack in the pit approximately fifteen feet in length which ultimately terminated in a construction joint approximately ten feet above grade level. Although the crack was c=all, approximately 0.01 inches in vidth, it was deemed advisable to obtain the opinion
{
of outside consultants. Two structural engineers inspected the
)
pit at the latter part of the reporting period.
As a result of this inspection it was ccncluded that the cracking was caused by shrinkage rather than settlement or strain, a common occurrence in concrete structures. Moreover, it was believed that the width of the crack would not permit liquid leakage.
However, as a pre-cautionary measure the phenolic coating in the vicinity of the crack vill be removed and the entire crack length re-covered with fiberglass prior to re-coating.
On October 25, AEC Reactor Operat<r License written exriminations for six candidates were. adminiotered by an AEC j
examiner. On October.26 Senior Operator written examinations 1
vere administered to five candidates and oral exeninations for the Reactor Operator candidates vere started. Oral examinations vere continued through October 27 and on October 28 demonstrative examincticna for Reactor Op :rator candidates were concluded.
t On October 11 plant load was reduced to.approximately j
lho MWe for one and one half hours to exercise the turbine.
throttle and control valves. All valves functioned normally.
3 The vapor container air leakage rate was normal throughout the reporting period.
Plant Shutdowns:
Chatdown No.
91-6-6 10-28-67 Scheduled shutdown.for administration of. AEC Operator Examinations.
i Total outage time:
9.02 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Plant Maintenance:
4 The following is a list.of major plant maintenance items performed by the plant staff during the month of October,1967:
i 4
l 1.
Deal rings were replaced in No. 1 charging pump.
2.
All fuel storage racks were renoved from the spent fuel pit and decontaminated.
l 3.
The spent fuel pit fuel assembly up-ender was removed from.
the pit, decontaminated, inspected, and the spare recenditioned operating cylinder installed.
h.
The fuel storage rack wood platforms were removed and disposed of and new cypress platforms were fabricated.
5.
Surface imperfections in the spent fuel pit phenolic coating were cleaned, explored, and prepared for patching.
6.
Seven leaking tubes were plugged in the evaporator reboiler.
7 The gravity drain pump was replaced consequent to the failure of the nunp-shaft.
8.
Lighting fixture supports and viring was installed in the new decontamination building.
9 The turbine lube oil reservior vent stack was weather proofed to prevent freezing and reduce building oil staining.
h Instrumentation and Control i
The following is a list of major instrumentation and control maintenance items performed by the plant staff during the month of October, 1967:
1.
Extensive tests were conducted en a mock up of a flux vire drive train and associated relays in the instrument shop.
2.
Water and air temperature recorders were removed from the Deerffeld River test stations.
3.
A smear counter system.for use at the accident emergency plan assembly point was assembled and tested.
4 The gat-house portal monitor was recalibrated.
Reactor Plant Performance Core reactivity depletion was normal at approximately 0.70 % a K/K per 1000 MWtD/MTU.
November 9 is the estimated end of core full power operation without pH variation cr stretchout operations.
l During the period eight new unitized shim rods were delivered. These are replacements for the mechanically coupled rods presently in use in the reactor.
l l
l l
-h-i
(
l The following parameters were determined by means of incore instrumentation at 599.5 MWt, 525.8 F Tavg.
h0 ppm botan, control groups B, C, and D at 89 5/8 and group A at 87 3/8:
1 2.3 F
=
q 1
Y 2.0 bH
=
3.13 Min. DNBR
=
59h.0 F Maximum outlet temperature
=
Secondary Plant Performance 1
Feedvater heater terminal difference 172.0 MWe, 3.2" Hg backpressure and 526.2 F Tavg:
- 1 6.1 F
- 2 16.7 F
- 3 11.1 F l
Condenser terminal difference 39.25 F Chemistry During the period the main coolant boron concentration decreased from 167 ppm to 83 ppm The average main coolant
-2 specific activity waa 6.28 x lo ue/ml and the average system crud level was 0.10 ppm.
The main coolant iodine-131 specific activity was 2.56 x 10-5 uc/ml; the iodine-131/133 atcmic ratio was 0.84 The main coolant tritium specific activity decreased from 2.3h uc/ml to 7.82 x 10-1 uc/ml as a result of main coolant system dilutions to decrease the boron concentration.
A representative crud sample for the month, collected on October 16, had the following radiochemical analyses:
dpm/mg Cr-51 Hf-181 M"-Sh Fe-59 g
5 6
6 4.26 x 10 1.16 x 10 1.63 x 10 2.12 x 10 l
Co-58 Co-60
^E-6 6
l 8.12 x 10 2.88 x 10 2.20 x 105 A main coolant gas sample collected on October 6 had the following radiochemical analyses:
uc/cc gas Xe-133 Xe-135 Ar bl
-3
-2
-1 9.85 x 10 2.59 x 10 3.27 x 10 1
l 1
l
., Health and Safety During October the weste disposal liquid releases totaled 216,000 gallons containing h.42 me of gross beta-gamma activity and 51.322 curies or tritium. Gaseous vaste releaces during the same period totaled 110.80 me of gross beta-gamma activity.
Secondary plant water discharged during the period consisted of 227,000 gallons containing a total of 6.9 ue of gross beta-gamma activity and 0.141 curies of tritium.
fladiation exposure doses for Yankee plant personnel as measured by film badge for the month of October 1967 were:
Average accumulated exposure dose 118 u em.
Maximum accumulated exposure dose 701 mrem.
Ocerations Attached is a sume.ary of plant operating statistics and a plot of daily average load for the month of October 1967 l
YANKEE ATOMIC EIlLTRIC COMPANY -- OPERATING
SUMMARY
OCTOBER 1967 EIJ!CTRICAL 10'JTH YEAR TO DATE Gross Generation DGi 126,565,000 1.095,h58,700 7,h57,919,200 Sta. Service (While Gen. Incl. Losses)
WH 7,982,225 66,899,672 496,922,494 Net Output DGI 118,582,775 1,028,559,028 6,960,996,706 Station Service 6.31 6.11 6.66 Sta. Service (Whih Not Gen. Incl. Iosses)
WH 64,554 997,771 24,793,238 Ave. Gen. For Ibuth (745.00)
W 169,886 Ave. Gen. Running (735.58)
W 172,062 PIANT PEHFORMANCE Net Plant. Efficiency 5
27.22 28.06 28.h0 Not Plant Heat Rate Bru/WH 12,538 12,162 12,017 Plant Operating Factor 5
97.47 83.#2 72.95 E
Reactor Plant Avaihbility 5
99.12 90.33 82.99 NUCLEAR 10KTH CORE VI TOTAL Hours Critical HRS 738.h2 7931.47 51,657.15 Times Scrammed 0
2 5h Burnup Core Average MD/E 873.76 8831.11 Region Average ND/M A (INNER) 894.937 8878.649 25,651.15 B (MIDDI2) 10hh.487 10,569.63h 18,2h4.92 C (OUTER) 700.647 7085.963 7085.96
YANKEE ATOMIC C COMPANT a
DAILY AVERADE IDAD for OCTOBER 1967 200 -
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m N
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o 8
150 -
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100 -
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ca Shutde'c. : 0.
91-6-6 50 -
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5 10 15 20 25 30 DAYS
- t CORE VIREION IDCATIONS 1
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REI')N C 1
i REI']N B 1
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