ML19345A318
| ML19345A318 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/19/1962 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19345A314 | List: |
| References | |
| NUDOCS 8011190082 | |
| Download: ML19345A318 (12) | |
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1*G Tilt C0 Q YANKEE NDCLEAR POWER STATION OPERATION REPORT NO. 13 d
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1 Subritted by YANKEE ATOMIC ELECTRIC COMPAITY Boston Massachusetts February 19, 1962 l
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. This report covers the operation of the Yankee Atomic Electric Company piant at Rowe, Massachusetts for the. month of January, 1962.
The' plant operated continuously during the month and passed the one
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billion DH mark inl gross generation on January 12.
As reported in the December Operating Report,. Core I has been expended to the extent that all control rods are fully withdrawn. A core lifetime'exten-sion program is presently in effect, based on taking advantage of the core re-activity increases associated with reductions in moderator temperature and reactor power level. The operating schedule. calls for maintaining load by al-lowing the average main coolant tenperature to drop to a predetermined value followed by a step load reduction. A correspondi increase in coolant temper-ature.is then realized following which the new load is maintained by further T
reduction.
ave At the beginning of January, the station power lavel was approximately 1ho Kde with an average coolant temperature of-5120F. For the first eleven days of the month these conditions remained essentially constant. On January 12 and
-13, T dropped approximately 7.5 F over a period of.h0 hours. At this point ave a load reduction of 10 K4e was made accompanied oy an increase in T from 50h to 509 F.
For the remainder of the month a nominal power level N 130 MWe a
0 was naintained with T ve exhibiting a gradual reduction of close to 1 F/ day.
a Plant operation during the period was smooth in general.
Intermittent periods of turbine control valve noise and vibration were still in evidence.
Discussions were held with the turbine manufacturer during the month to outline r
a course of action for correcting the turbine problem. Losses of condenser cir-culating. water discharge dphon were experienced on January 22, 23 'and 2h. Methods of correcting this condit1on were also investigt.ted during January.
On January b, a lwak developed in the charging line at' a point outside -
the vapor container. After isolating the line an alternate feed was provided.
.The activity of the dischargedliquid was belcw the point of detection wtile 2
contaminationwaslessthan100DFM/ft. A circumferential crack, about 1 1/2 inches in length, was discovered' approxinately 1/h inch fran the weld a'ttaching the charging line to a thermal sleeve at the point of penetration into the
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vapor container. The defective section of the line has been removed for anal-ysis and the charging line has been repaired and caturned to service.
During January, fifteen fuel assemblies for use 5n Core II were del-ivered to the plant bringing the total of' Core II fuel assen'ely receipts to
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sixty seven. Twenty-two control rod absorber sections for possible use in Core II wem alsc delivered to the plant in January.
Fifty-four of the sixty-seven fuel elements were transferred to the spent fuel pit and placed in storage racks. Also placed in the pit were a WL-6307 BF3 detector and a one-curie Plutonium-Berylium neutron source. During the flooding of the pit with demineralized water, the neutron count rate was monitored.
There were.no plant outages or scrams during January.
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2 Phnt Maintenance Following is a description of the principal maintenance activity during January:
-1.
A defective section of the charging line was removed and a new section of line installed. The-new section was dye-penetrant checked at the welds before beirg restored to service. '
2.
The clean out connections on the purification cooling and drain pumps were shortened and provided with shut-off valves. Pre-viously, the outlet ends of the connections were capped.
3.
Two sway braces were installed on the main steam line to reduce steam line vibration.
h.
The upper shaft bearing on No.1 Primary Drain Collecting Tank Pump was replaced. Considerable shaft wear was noted in the journal area. Additional maintenance will be performed on the pump durirg the refueling shutdown.
5.
Excessive leakage from a recently installed seal on No. 3 charging pump necessitated inspection and adjustment of the seal. The operation reduced leakage to an acceptable level.
6.
A rupture of the inner potting seal at the vap.or container pen-etration of the No. 6 pressurizer heater lead occurred during the month. The break, about 1/h inch in diameter, is believed i
to have been the result of a defective seal or moisture or a conbination of both. Since the outer seal remained intact, leakage from the vapor container is not involved and a final repair will be deferred un al the refueling period.
i 7.
Connection of a steam sample line from nozzles in the right hand steam lead to a samphng station was completed during the month.
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Besides the above, rontine maintenance procedures were carried out during January. Preparations are being made for an extensive maintenance pro-gram scheduled for the refueling period.
Chemistry
- As a result of a persistent solids carryover problem, a design for a new evaporator has been developed. As discussed in previous operation reports, nunerous attempts have been made tc correct the carryover condition associated with the electrode evaporator but with no significant results. The new design encompasses the installation of a conventional shell and tube evaporator with a cyclone separator. The existing evaperator vessel vill remain in place and
-se:ve as a reservoir or storage vessel. A change request has been submitted
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Main coolant oxygen levels continued below the point of detection during January. Main coolant specific activity levels ranged from h.2 x 10-2 to 5.6 x 10-2 pc/ml during the same period.
i Secondary side steam generator specific activity measurements indi-cated background levels only. Iodine-131 measurements on secondary blowdown we.re negative. With the existing primary water Iodine-131 concentration, this method would permit detection of a primary to secondary system leak of as little as 0.003 gallons per hour.
The results of a. main coolant gas anaiysis indicated:
M.C. Bleed Downstream of Low Downstream of Pressure Surge Tank Ion Exchanger A-h1 h.0 x 10-1 pc/cc gas 2.5 x 10-2 pc/cc gas 3 1 x 10-2 pc/cc gas Ie-135 3.5 x 10-2 1.6 x 10-2 2.6 x 10-2 Kr-86M 1.8 x 10-2 3.5 x 10-3 h.6 x 10-3 Xe-133 1.5 x 10-2 1.h x 10-2 1.1 x 10-2 At the beginning of January the main ecolant specific activity varied between 1.h x 10-3 sc/ml and 1.7 x 10-3 pc/ml and the I-131/I-133 atomic ratio was approximately 3.h.
This represented no significant change from values re-ported in December but remained above corresponding levels reported in November and previous months. A period of operation during the month with no purification flow saw the I-131 concentration increase to 1.1 x 10-2 pe/ml;however resum-ption of primary water purification reduced this level to 1.0 x 10-3 pc,/ml.
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By the end of January, the I-131 activity was h.5 x 10-h pc/ml with an I-131/I-133 ratio of approximately 2.6, Whilt m increase in these values in December indicated the possibility of a minor fuel clauding defec',, no new defects appear to have ocetrrred in January.
A main coolant crud analysis made during the period of no prinary coolant purification indicated:
Fe-59 7.3 x 1 dpm/mg Ag-110 3.2 x 1 Co-60 1.h x 106 Co-58 2.1 x 106 Cr-51 1.0 x 10 Pn-5h h.6 x lo>
Crud Level 0.1h ppm No significant increase in crud level was noted while operating with-out purification for approxinately nine days. The main coolant specific attivity
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increased from a level of h.2 x 10-2 pe/ml before the no-purification run to i level of approximately 5.6 p:/ml during and immediately following the run.
j Reactor Plant Performance Defining Core I end of life as that time when core excess reactivity would ' drop below zero at the design conditions of Core Pcwer = 392 Edt Loop Ave. Temp. = 51 hep Main Coolant Press. = 2000 psig Equilibrium Ienon for 392 K4t the following has been deternined:
Ccre I Life = 8000 EFPH
' Ut Hour output = 3,'136,000 Gross Ede Hour Output = 1,008,817 Net Kde. Hour Output = 927,9hh
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The following values were determined by means of in-core instrumen-tation measurements at a power level of h10 Kdt with all control rods with-drawn to 90 inches:
Fq (Heat Flux) 3.h A T (Coolant Rise) 2.9 F
DNB ratio 2.9 Analysis of core reactivity durirg January indicated ersentially a zero burnup rate during the first eleven days of the month. Durirg this period lead was maintained at a nominal lho Ede level with the average main coolant temperature remaining in the 512 to 513 F range. It is possible to attribute this apparent gain in rea:tivity cr indication of zero burnup to a regainirg of reactivity lost during the reacter, scram of December 21.
As described earlier, a f allirg cff of main coolant temperature cecurred on Janu-ary 12 and 13 -- the rate of temperature de:rease corresponding to approximately ten times the design burnup rate. When lead was reduced from lh0 to 130 Ede on January 13, no reactivity gain due to the change in equilibrium Ienon conditions for the two power levels was observed. This may have been the re-sult of a reactivity loss on load reduction or a continuation of the reactivity loss observed prior to the load reduction. During the period of 130 Ede operation (January 1h-31), however, the rate of main coolant temperature decline was generally consistent with the design burnup rate. Analysis of core reactivity changes centinues. in an effort to resolve the apparent gains and losses of reactivity which have occurred frem time to time during the past several months.
During November 1961, a physics test prcgram for determination of core reactivity coefficients was carried out. Data for establishing the power i
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Ocefficient were acquired as the plant power level was increased from 0 to ~
130 4Me. Loading was accomplished in 30 FMe increments with a period of stabilization of approximately two days after each power increase. The power coefficient was determined by measuring the effects of step wise power level changes in terms of moderatcr ' temperature and control rod position tsarges. These were, in turn, converted to reactivity changes in order to determine the power coefficient of reactivity. An average power coefficient over the range 0 - 1:00 FMt of -(0.38 + 0.17) x 100 d[/ FMt was determined and reported at that tins.
'An additional technique was employed by cycling load, in approximately 8 FMe steps, prior to each load increase and allowing the main coolant temper-ature to control'with no rod motion. This method reduces the transient-Ienon correction since it is conducted after allowing Ienon to reach approx-imate equilibrium conditions. In addition, by cycling load at various power levels, improved statistical averaging is possible.
, The. attached curves (page 6) indicate the value of the power coefficient as a function of reactor power level. Curve (1) represents a predicted or theoretical change in power coefficient with power level. - This curve reebgnices the pellet-clad gap variation induced by power level changes and inequality in the temperature coefficient of expansion between the pellet and clad materials.
Curve (2) represents a polynominal fit of the measured power coefficient as determined fron the load cycling technique. The data which yielded curve (2) were corrected for the reactivity effect of variable Xenon concentration.
As indicated on the plot, both curves exhibit the same general characteristic, that is, a less negative power coefficient with increasirg reactc~ power.
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_ hrbine Plant Performance i
Discussions were held during'the month with the manufacturer covering the turbine, feedwater heaters and circulating water pumps.
As described earlier, turbine contiol valve noise and vibration have occurred sporadically for several months.
It.is expected that corrective action will be taken during the refueling outage.
The three secondary plant feedwater heaters have exhibited term'nal temperature differences considerably higher than specified. As ' a re sult, the heater manufacturer has agreed to study the problem and make recommendations designed to improve heater performance. Internal inspection of the heaters is also scheduled for the. refueling shutdown.
One and possibly both condenser circulating water pumps will be returned to the factory for testing. Since initial operation both pumps have cperated at approximately 50 H.P. above rating. If required and if possible, the pump impellers will be modified at that time.
Also discussed was a method for reducing or eliminating vortexing a4 1:4 circulating pump screen-well. The installation of either a floating raJt er pump f3ow stabilizers is being. considered.
H_erJ.th and Safety Liquid waste containing 605 pc and gaseous vaste containing 0.06 ue were discharged from the plant during January.
Thirty-five drums of solid radioactive waste containing 21 milli-curies were shipped from the plant for off-site disposal during the same.
period.
At all times the concentration of aaste products discharged or shipped from the plant was well below the maximum permissible.
Following is a summary of radioactive material discharged or shipped from the plant during the year, 1961.
-Liquid 7968 microcuries Gaseous 1898 microcuries Solid ( 70 concrete drums 107 millicuries for off-site disposal)
Radiatien levels associated with the replacement of a section of the charging line were 5-20 nr/hr in the working area with centamination levels 2
cf 200-3,000 dpm/ft,
Radiation levels on contact 'with the removed sections of the capped tail pipes on lio.1 and No.2 purification pumps were 10 r/hr and 5 r/hr res-
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2 Contamination in the cubicles as.a result of the operation was 800-10,000 dpm/ft,
The pipe sections.were placed in a lead container for shipment and analysis
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Followirg decontanination of the cubicles, a routine radiation survey indi:sted a contamination level of approximately 700,000 dpm/ft2 on the floor-ir No. 1 purification pump cubicle. Since there appeared to be no evidence or leakage, it is believed that a radioactive particle, remaining from the tail pipe removal operaticn, was picked up on the smeur. The decontnM nation procedure was repeated and levels of less than h00 dpm/ft2.were measured.
. Personnel exposur( as measured by film badges for the following periods were:
Averaae Exposure Maximum Exoosure Year 1961 91 e 760 nr.
last Quarter of 1961 33 e 560 mr December 1961 2.5 mr 3
100 mr Continuousmonitoringofoff-siteai$borneactivityduringDecemberindicated levels consistent with pre-operational values.
Changes in Ooerating Procedure A new emergency instruction procedure (50$ B 22:1) was issued in January. Tne new procedure outlines action to be taken to prevent a reactor scram resulting from spurious instrument r,ignals caused by grounds or other faults on the station vital bus feeders.
A portion of operatirq instruction 50LQ has been rewritten and j
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issued. The instruction covers the vaper container atmosphere control system, 1
the revision relating to that section pertaining to establishing and main-L tainirg normal vapor container pressure. The revision provides for averaging l
eight rather than nine temperatures in the vapor container to determine the average ambient temperature of the vapor container atmosphere. The shield tank cavity temperattre has been deleted from the average.
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Another minor charge in the instruction revises the time at which vaper container atmosphere data are recorded and comparisons of temperature and pressure changes made.
Design' Changes Ne changes in plant design were made during the month of January.
In Plant Trairing A program of classroen instruction in basic nuclear physics is
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. control room operator's position and A.E.C.' reactor operator licensing, j
A special training program in Health' Physics has been initiated for i
the: plant I!uclear Anvilian Operators in conjunction with the~over-all
. preparation for' refueling.
Plant Operations 4
Attached is a plot of daily average _ plant load and a summary of plant' operating statistics for the month of January.:
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g YANKEE ATOMIC ELECTRIC COMPAdY - OPERATING SUYe1ARY JANUARY 1962 v
iELECTRICAL MONTH.
YEAR TO DATE Gross Generation -
KWil 99,768,h00 99,766,h00 1,061,119,700.
Sta. Service (While Gen. Incl. Losses)
KWH 7,290,715 7,290,715 8h,822,797'
. Net Generation KWH
'92,h77,685 92,h77,68S-976,292,903; Station Service 7.31 7.31 7.99 i -
Sta. Service (While Not. Gen. Incl. Losses)
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'10,091,710 Ave.. Gen.
For Month (7hh Hrs.)
KW 12h,298 Ave. Gen.
. Running (7hh hrs.)
KW
.12h,298 PLfJTT PERFORMANCE Net Plant Efficiency 30.00 30.00 Net Plant Heat Rato Btu /KWH 11,377 11,377 Lbs. Steam / Net KWH 13 36 13.36 C*rculating Water Inlet Temp.
Maximum F
36 Minimum 0F 33 Plant Operating Factor 85.h3 85.h3 70.10' MONTH CORE I-TO DATE NUCIfAR
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-0 252 252 Hours Critical HRS Thh 10,577.01 13,$77.01 f
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Times Scrammed Equivalent Reactor liours @ h85 iMt HRS 635.6 6,800.h '
6,800.h Average Burnup of Core l#D/mt U 61$
6,580 Control Rod Position at Month End F.quilibrium at 127 IMe, h95 F TAV Group 1 Rods out-inches 90 Oroup 2 90 Group 3 90 Group h 90 3rouc $
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