ML19308C414
| ML19308C414 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/04/1980 |
| From: | Wilson R METROPOLITAN EDISON CO. |
| To: | Jay Collins NRC - TMI-2 OPERATIONS/SUPPORT TASK FORCE |
| References | |
| GQL-1575, NUDOCS 8001240398 | |
| Download: ML19308C414 (35) | |
Text
.
8 Metropolitan Edison Company Post Of fice Box 480 II Middletown, Pennsylvania 17057 717 9444041 "Q,
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Writer's Direct Dial Nurnber January 4, 1980 GQL 1575 TLL 003 TMI Support Attn:
J. T. Collins Deputy Director U. S. Nuclear Regulatory Commission c/o Three Mile Island Nuclear Station Middletown, Pa.
17057
Dear Sir:
Three Mile Island Nuclear Station, Unit II (TMI-2)
License No. DPR-73 Docket No. 50-320 Natural Circulation Enclosed please find the response to your letter of November 5, 1979, concerning Natural Circulation, which discusses the changes in the Reactor Coolant System operating parameters which occurred in mid-October.
- neertly, nW
. Wi son Director - TMI-II RFW:LWH: hah Enclosures cc:
R. Vollmer ko4l 5lt Metropohtan Edison Company is a Member of the General Pubhc Utilities System S
l 8001240
i Enclorura 1
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TLL 003 1 TEM 1 Provide the best estimate of steam generator water level over the last 6 months.
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RESPONSE
Steam Generator Level e
Shortly after the accident it was recognized that steam generator secondary side level instrumentation located external to the Reactor Building would have to be installed. Procedure Z-73 was developed to do this, and the instrumentation was installed and calibrated according to that procedure in early April. The method used existing taps on the main steam lines and main feedwater lines. Calibration of the dp cell utilized the then still functional steam generator " operate" range instrumentation.
Following loss of the in containment instrumentation, the steam line to feed line A P was used for setting steam generator "A" secondary line.
On October 9,1979, diverging "A" loop A T and oscillatory behavior of the temperature in that loop alerted the operating staff to the potential for breakdown of natural circulation. GPUSC Technical Support engineers investigating the circumstances surrounding the sudden change believed that condensate collecting in low points of the main steam lines was causing partial blockage of steam flow v'
to the condenser.
Since the steam generator level pressure tap on the steam line would be adversely affected by this phenomenon also, a cross check method of measuring Steam Generator level using a manometer was devised. This cross check showed that at that time (October 12) the actual "A" steam generator level was approximately 80" to 100" higher than previously thought. Whether this condition had existed since shortly after the calibration, whether the original calibration was in error, or whether the error occurred over a short 2 or 3 day term just before the departure of "A" loop temperature from steady values, is open for conjecture. No supportive logs, instrumentation graphs, or the like for directly placing a time of occurrence exist to our knowledge. However it is, we believe, reasonable to assume that this error occurred gradually over a short time just prior to October 9.
On Sunday, October 6, the Turbine Bypass valve was closed slightly 0
to hold Reactor Coolant "A" loop hot leg temperature in the 160
- 1800 range, this is in accordance with operating procedure Z-39 for natural circulation. At approximately this same time, TMI was experiencing it's first cold weather of the year; dropping temperatures in the annulus around the Reactor Building would have caused, accelerated, or exacerbated the condensation problem in the steam lines.
The resulting bias in the steam generator level measurement would then have led to the over fill problem.
Overfeeding would in turn have made the condensate collection in the steam lines worse due to liquid spill over (for real secondary water levels greater than 423"), and would have masked the fact that too little steam was being vented to the condenser. Assuming this scenario, the probable range of OTSG "A" secondary side water level is shown in Figure A.
(Attach-ment 1 contains more details of the events and actions.)
Enc 1ccuro 1-ptgs 2
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TLL 003 j
ITEM 2 Correlate steam generator water level to loop flow.
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RESPONSE
Steam Generator Water Level to Loop Flow Correlation t
. ;5 '
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Increasing the secondary side water level in a Babcock & Wilcox 0.T.S.G. will increase the driving head available for promoting natural circulation. A simplified method for calculating the driving head for a given steam generator water level is detailed in the Babcock & Wilcox report " Natural Circulation Stability of TMI-II (BAW-1562)" copies of which have been sent to NRC. Using this method and inputting values for reactor coolant temperature and flow prior to October 9, then correcting for possible changes in steam generator secondary side inventory, does not predict the flow and temperature currently existing.
This suggests then a change in flow patterns from those assumed in the original Babcock
& Wilcox simplified model.
Babcock & Wilcox has reviewed the operating data and has offered hypotheses on the changed flow patterns now occurring in the "A" loop. Their conc 1ssions are written up in the attached letter (See Attachment 2).
We agree with their analysis and conclusions but caution that the existing reactor coolant instrumentation (though sufficient is a basis for safe operation of the plant) is not suited to the task of proving the hypotheses in a detailed, conclusive manner.
It should also be noted that while the bulk of the discussion concerns the anomalous behavior of the temperatures, the data clearly shows that natural circulation cooling of the core continues to provide acceptable cooling. This is exemplified by the Incore Thermocouple Data which show the historically highest temperature readings falling off with the decrease in core decay heat. Attachment 3 is a graph of Inco 3 Thermocouple 8-H over the period August 1979 thru the present.
Incore Thermocouple 8-H is located in the center of the core pattern and has consistently given the highest temperature readings.
ITEM 3 Revise EP-34 to reflect higher allowable loop A T (lower flow).
RESPONSE
EP-34 Revision Revisions to the Loss of Natural Circulation Procedure EP-34 have been prepared and are currently in the review process.
Deletion of the administrative alarm loop AT 200F or greater indicating loss of natural circulation is included in this proposed revision. Continued monitoring of his important parameter will obviously be required.
ITEM 4 Place NRC on distribution for regularly recorded Control Room data.
RESPONSE
Documentation of Plant Operating Data The official vehicle for documenting the TMI-II plant operating data is through your Mr. E. Kevin Cornell, Deputy Executive, Director for Operations. He receives microfilmed copies of all data. Due to the processing time, some time lag exists. However, microfilm covering all operating data through November 26, 1979 has been sent.
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- e. 2 Historical review of events surrounding the loss of
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Steam Generator "A" level 10/12/79 ILL 003 On Tuesday, October 9 the cold leg on Steam Generator "A" began to oscillate about i 40 in one hour cycles.
Also the hot leg temperature started increasing at an average rate of 0.10 per hour.
The following is a report of what was found during the investigation to detennine the cause and reaedies for this behavior.
I.
Investication of potential items that caused temperature abnormalities _
A.
The increase in the hot leg temperature (T ) indicates that h
the resistance to flow from the steam generator to the condenser was increasing.
1.
The turbine bypass valve controlling this ficw had been reduced from 16% flow to 14% flow e
Saturday, 10/6/79.
2.
Review of the Main Steam Line Drain process indicated that the steam lines i.ere not being
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drained.
The drain line..ere opaned daily for five r.irates during the f ast few months, n: wever, e no ficw condition i.as indicated by the drain lines being cold during this
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operation.
3.
The drain line connection into the condenser was disasse.-bled and found to be pluged with rust p articles.
The line was cleared and flow was established.
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5.
It..is also noted that the air ts.parature 2round the steam lines had reduced sigr.ificantly.
This drop in te.sparature would increase the heat loss f rom the Main Steam Line and increase condensation in the line.
B.
The rapid increase of condensed water in the steam lines indicated that sources other then condensation c.ay be contributing to the accu ulation.
Possibility of leakage through the steam ger.erator shrcud instrumentation opening was then investigated.
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' actual level be ab:va 423 inch:s in th2 St:am Generator tha ler.kage would y
flew directly into tha steam line, The differential pressure gauge used to measure the 3
1.
Steam Generator water level is connected to the Turbine Bypass line downstream of the Main SteamWith the s hI d!
Line.
would indicate a reference Steam Generator-overpressure 2
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The amount R
less then what would actually exist.
of this error was estimated to be as much as 3.0 Psi.
E I.E., the measured temperature of the bypass line l
was 120 F with a Psat of 1.69 psia and the highsst 0
p expected pressure in the Steam Generator would be 6
Tli = 1600 with Psat = 4.74 Psia.
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The tubing from the steam line to the differential pressure gauge was found to have a vertical dropThis length of tu 2.
of about 10 feet.
steam condensation and cause the differential pressure i
gauge to indicate a pressure of 5.0 psia greater then actually exists.
h"nen this tubing was cleared by allowing atrr.osphere air pressure to draw the condensed water into the steam line, the steam generator level indicator in the Control y
Actual Room pegged at its upper limit of 480'.'
3 estir.atedlevel was assumed to be approximately 50d'when accounting for the two compensating errors.
'*akeup water was being continually added to the 3.
The valving Stear Isr.erator at an :,ntr.own rate.
arrirce.ent..as inually opened to adjust the Without Stear 22r.prator les el irdication the fi c...
of flow could not be detected.
arour.:
... I E edial actions recuired to orevent temperature fluctuntions
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Th5 at a uiation of u3 tar in the st::am line prevents direct
.nichticn of precsure conditions fecm the Turt,ine Mass Vaive A.
c:;o t.,e 5:+am 5cr.erator.
t~.e s tu-1Nr are n ;ittely ull the 1.
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Far tr.i s ri3;;r
- of the "lin Ittar Lir.es should be cors15r.iy pursued to insure a stable ficw conditions.
The exact raeasurement of Steam Ger.erator water 2.
level is necessary to maintain a constant driving force for primary circulation.
Currently an idterin method of rieasurer.ent This is being used for this ceasure.ent. 0 w x ~
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Interia system uses the Steam Generator sample drains to determine the hydraulic water pressure.
It is corrected by using a pressure calculated from
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the primary T hot temperature.
Although this method provides a consistant measurement scheme it 4
is not exact and could indicate as much as 6C. inches higher then actually exists if T cold 4
was used. Another concern with this instrumentation 4
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could be as much as ! pressure measurement system is that the hydraulic i
15 inches off as a result of the physical readings from the chart being used.,
3.
Pressure communication from the turbine bypass line to the Steam Generator will result in exact pressure readings with corrections for steam head and flow lesses. A pressure reading at this location should be used in conjunction with the sample line hydraulic pressure to determine the exact steaming levels.
Caution should be taken to assure that any instrumentation tubing taken from the top of the Turbine Bypass Line has a direct upward slope to the pressure measuring transducer. (i.e., no loop seals to accumulate condensed steam).
4.
The flow rate into the Steam Generator would provide a limiting control of water level. A flow detector and metering device on the feed line would provide assurance of water level control should the level
)
ins tru..antation temporarily malfunction.
This flow device would,also allow a r.ethod for deter..ir.ing the 52ht rejection from steaming of the generator.f- /~
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NATURAL CIRCULATION - LONG TERM C00LI'NG Attechm:nt 2 TLL 003 sg A.
PROBLEM
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Further evaluation and explanation of the variation in natural circu-
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1ation behavior which occurred starting 10/9/79, and has since become
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the norm.
B.
htEFERENCES 1.
Telecopy from S. J. Engel to L. C. Rogers on 10/17/79, Explanation of Deviant Flow Behavior, 03-05-008.
2.
Natural Circulation Stability Report by S. H. Esleeck and J. E.
Lemon, June 29, 1979, BAW-1562.
3.
Memo from L. C, Rogers to B. Elam, LRC-084, " Review of "A" OTSG Steaming Test Data," September 12, 1979.
C.
DISCUSSION CAbSE OF Tile DEVIANT BEHAVIOR The cause of the deviant behavior which started on 10/9/79 is not attributed to any one factor but is due to many factors.
The factors that contributed to the deviant behavior are indicated below:
1.
The TBV setting was reduced from 15% to 13% on 10/7/79 causing a slight imbalance between heat generated and heat removed.
The result was a gradual increase in the temperature of the "A" loop reactor coolant system of approximately 1.5 F from 155 F on 10/7/79 to 156.5 F on 10/8/79 (See Figure 2).
This upset in the equilibrium between decay heat generated and removed continued until 10/14/79 with the "A" loop average primary temperature in-creasing another 4 F to 160.5 (Figure 3).
The gradual temperature increase was finally halted on 10/14/79 as the TSV setting was in-creased to 17%; this allowed an adequate increase in steam flow rate to more than remove decay heat as the "A" loop temperature started an immediate decrease (Figure 3).
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-2. A cold weather front came into the Harrisburg area on approxinately 10/9/79.
This had the effect of reducing makc-up tank tenperature.
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e from approximately 130 F on 10/8/79 to 124 F on 10/12 to 117 on
.,1 10/10., Similarly the feedwater temperactire va. reduced from ap-I
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proximately 75 F on 10/8 to 66 F on 10/11,; it was subsequently in-creased to about 70 F on 10/16/79. The condensor vacuum may have j
also changed slightly though there has been no indication on the
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Instrumentation; the reading ' remained uniform at about 281 -29" Hg.
5 I
3.
When the "B" loop burps it causes temperature oscillation in the "A" loop.
These were very mild prior to 10/2/79 but the 10/2/79 and 10/6 "B" loop burps showed significant temperature oscillations (See Figure 1).
Following the 10/2 and 10/6 burps the "A" loop 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> temperature oscillations were dampened out after about since the system was in steady state equilibrium except for the "B" loop burp perturbations. However, following the "B" loop burp of 10/9 with the addition of the perturbations due to the 13% TBV the position and the temperature changes due to the cold front, system was unable to dampen out the initial "A" loop temperature oscillations (Figure 2).
In fact, the "A" loop temperature oscil-lations got stronger particularly between the "A" loop cold legs, which suggests some form of unstable fluid flow interaction between the cold legs. This fluid flow interaction increases the cold leg
" riser" AP and therefore rc~ duces the driving head for natural circula-tion.
Since the driving head is reduced the flowrate is also reduced.
This results in an increase in the "A" loop equilibrium AT from approxi-mately 8 F on 10/8/ to 12 F on 10/11. With the reduction in driving head the system is even more susceptible to "D" loop burp perturbation than it was on 10/9. For example, the system burped only 2 days later on 10/11 (versus the normal 3-4 day period).
This burp triggered a similar decrease in driving head as did the 10/9 burp, and a new equilibrium AT of 17 F was established. The 10/13 burp resulted in a third flow reduction and a AT increase to about 22 F before the TBV setting was increased (Figure 3).
l r 4.
There are two other factors in addition to the cold leg fluid flow interactions uhich reduce the driving head for natural circulation:
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(1) As the flow ratt. decreases the "A" loop cold leg ter:pera-tures decrease even further since they are transferring es-l{
sentially the same amount of heat to the reactor building I
water;'i.e., as & decreases AT increases.
As the system temprature increased from 155 F on 10/7 to (2) 160.5 F on 10/14 the ambient heat loss is increasesed'and this tends to further decrease the driving head for natural circulation." Natural circulation is best supgiorted by having I
as much of the decay heat removed in the OTSG as possible.
5.
Since there has.been uncertainty about the OTSG water inventory during this per'iod, this may also have been a factor since changes in OTSG level can also affect the driving head for natural circu-lation. A reduction in water level in the OTSG changes the tempera-ture gradient on the primary side such that there is a reduction in the average density of the primary coolant in the OTSG. This.
reduces the AP of the OTSC (which is a downcomer in the natural circulation system) and therefore reduces the driving head for natural circulation. For example, a change in OTSG level from 430" to 330" would cause a reduction in the OTSG downcomer AP of
.0065 psi.
An identical reduction in natural circulation driving head would also occur.
If it is assumed that an OTSG wtih a 430" level had a driving head of.0200 psi ~(Reference 2) and a resultant flow of 375 gpm and an "A" loop AT of 8 F, a reduction in the OTSG level to 330" would result in a driving head of.0135 psi, a flow rate of approximately 300 gpm and an "A" loop AT of about 10 F.
l EVALUATION OF THE F1.UID FLOW INTERACTION PHENOXENON j
Reactor residual heat generation continues to decay (Figure 4) and i
the percent of this heat removed in the generator decreases as the a,mbient losses and heat removed by the makeup flow continue at constant level. For example, on August 29, 1979 the heat removed by the OTSG was estimated to be a maximum of 72% of the decay heat generated (1.9 x lo Btu /hr) as per Reference 3.
This results in ambient and s
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6 Beu/hr. (28%).
On November 15, r
makeup losses of approximately 0.53 x 10 6 Stu/hr (Figure 4).
As-
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1.25 x 10 1979 the decay heat level was about suming no change in ambient and makeup losses, the OTSG is transferring This reduction in the percentage only 57% of the decay heat generated.
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of heat transferred by the OTSG reduces the driving head for natura l
circulation since the heat loss (43%) may not be occurring in a down-Heat loss in a downconer promotes natural circu,lation where comer.
The best example heat loss in a riser impedes natural circulation.
i of this is the heat loss to the reactor building water due.to a port on The two parallel of the pump inlet piping being submerged in the water.
pipes are cooling " risers" in a complex natural circulation configura-Anytime a cooling " riser" occurs in a natural circulation system tion.
The fact that the stability of natural circulation is challenged.
l the cooling risers are in parallel further complicates natural circu a-tion of the system.
In order to evaluate and explain what is happening during the fluid l
flow interaction phenomenon it was decided to obtain detailed accounts of "A" loop inlet and outlet primary temperatures during three differ-The method of obtaining this information was to l
ent periods of time.
borrow the "reactimeter" computer tapes from the site and obtain the hard copy computer printout and a computer p1'ot of the "A" loop tem-The reactimeter tapes record.the measured var-peratures versus time.
computer plots for the three different iable every 10 seconds.
The time periods are shown in Appendix A.
The first time period selected was fr'om 0000-1000 on 10/16/79 (Fig-This period was selected since it represents a " steady state" ure 5).
10/13/79 even though there are period following the "B" loop burp on very large fluctuations in the "A" loop cold leg temperatures every The "TT2" leg temperature fluctuations are greater than 4wo hours.
The second time, period the "TT4" leg temperature fluctuations.
This time period represents selected was from 0000-1000 on 10/17/79. '
the time before and immediately following the "B" loop burp which i
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e
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'i ' occurred at approximately 0330 on 10/17/79.
Again,.very large fluctua-The tions were observed in the "A" loop cold legs during this period.
third period selected was from 1400-2400 on 10/17/79.
This period showed very regular fluctuations of cold leg temperatures similar to a sawtooth pattern, with much smaller temperature changes th$n in the first two time periods.
l The following conclusions have been made regarding the fluid flow inter-f action phenomenon which started on 10/9/79 and is now the norm af ter re-
+
i viewing and evaluating the temperature plots in Appendix A:
f The fluid flow interaction between the pump cold legs is 1.
The actually a " burping" of the "A" loop "TT2" cold leg.
i flow in this leg actually slows down, stops, and reverses for a short period of time resulting in a decrease in the total flow to the reactor coming from the TT4 "A" loop cold leg.
During this phase of the bdrp cycle, the TT2 cold leg is slowing i
down because it is cooling off more rapidly than the TT4 cold Its density increases until the leg is heavy enough to leg.
The reverse flow is only momentary, though, cause reverse flow.
as higher temperature coolant is pulled from the reactor vessel l
i into the TT2 cold leg (See Figure 6).
This low density fluid causes the flow to reverse again with both legs now flowing in the same direction until the next, cycle occurs.
The "A" loop TT2 cold leg burping (or reverse flow) occurs in-2.
dependently of the B loop burps; the cycle time is approximately 3b hours.
Inspection of the temperatures plotted every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (Figure 5) appears to show a dif ferent type of behavior between the period of 0000-1000 on 10/16 and 1400-2400 on 10/17.
The large irregular temperature changes of the "A" loop cold legs in the first period conflict with the small regular sawtooth pattern temperature changes in the third period. However, examination the tem-of the reactimeter tape plots in Appendix A shows that perature behavior for the 2 periods is quite similar but appears different in Figure 5 because the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> plotting interval is so e
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long that it may miss the large temperature fluctuation in the g
TT2 cold leg and becasue the "A" loop TT2 cold Icg burps occur
~" 2-approximately once for every two (2) hour readings; i.e., they are in phase.
3.
The "A" loop TT2 cold leg burping results in a variable primary flow as the AP in the cold Icg changes throughout the flow cycle.
The variable flow rate results in the primary te'mperature fluct-uations observed and is the cause of the steam temperature varia-tions also.
This is verified since the incore Tave is leading the "A" loop steam temperature by approximately 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />'s (See Fip.s 7).
This means that the "A" loop "TT2" cold leg burping is the primary cause of the cyclic primary temperatures, primary flow and steam temperatures observed since 10/9/79.
PROJECTIONS OF EXPECTED BEHAVIOR As the decay heat level continues to decay over the next few months (Figure 4) and if the TBV setting remains at 17%, it is expected that "B" loop burps will continue to occur every 3-4 days and,"A" loop
{
"TT2" cold Icg burps will continue approximately every 3-4 hours.
l The "A" loop "TT2" cold leg burps will continue to be independent of the "B" loop burps and will result in similar "A" loop cyclic primary flows, primary temperatures, and steam temperatures that have been observed in the past.
It is anticipated that the reduction in decay heat level over the next few months will result in reduced "A" loop primary system temperatures' and a slight reduction in the "A" loop AT as the TBV setting remains at 17%.
A gradual reduction in primary system temperature will be required to maintain natural circulation in the future.
Ambient and makeup losses at the present rate of approximately 500,000 Btu /hr are too high to
, support natural circulation when the decay " heat level gets much below 1.0 x 106 Btu /hr.
It is possible, though not anticipated, that the ambient and makeup losses will continue at about 500,000 Beu/hr level.
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due to the possibility of:
(1) primary system temperature not de-creasing or (2) the lower cooling water and the reactor building sump and containment temperatures that will probably occur in the near future
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when the winter weather is here for good.
Should this occur, natural circulation performance will be reduced with a re,sultant increase in l
the "A" loop primary system temperatures. However, stable natural circulation performance can be maintained by monitoring the tempera-I turevariablesandtakingcorrectiveaction,ifrequirdd,inaccordance with the Loss of Natural Circulation Procedure (EP-34)._
I D.
CONCLUSIONS 1
o The "A" loop TI2 cold leg burping is the primary cause of the cyclic primary temperatures, primary flow and steam temperatures observed f'
since 10/9/79.
e There is no concern with respect to core cooling now or in the next few conths with continued operation of steaming in tlie "A" OTSG and j
the accompanying cyclical "B" loop burps and "A" loop "TT2" cold leg burps.
In order to maintain stable natural circulation over the next few months the thermal level of the system ("A" loop average temperature) y must be reduced.
This may require further opening of the "A" loop f
I turbine bypass valve (s).
i B&W recommends that the TBV setting be maintained at its present position of 17% open and that the temperature variables be monitored in accordance f
with EP-34 to ensure that stabic natural circulation to remove decay heat continues.
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FIGUP.E 6 "A" LOOP TT2 COLD LEC " BURPING"' PHENOMENON i
Each pump Icg transfers heat to the reactor building water at approx -
mately the same rate.
inherent g
The TT2 pump leg has less flow than the TT4 pump leg (different flow resistance due to position of the stopped pump rotor).
f temperature The pump leg with the least flow (TT2) has a greater rate o l
decrease as the result of heat loss to the building water.
ater The colder pump leg (TT2) acting through height "H" develops a gre flow head in opposition to available natural circulation head and the in this leg slows down and reverses.
hich dis-The reverse flow pulls hotter water from the reactor vessel w" light" riser and places the colder water in the pump leg making it are-establishi i
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DECAY 0
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APPENDIX A A
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3
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53.040 TINE (SECONDS)
(X10 3)
PERIOD #1 REACTIt1ETER PLOT TSN=1 0000_1000 10/16/79 21-g
I 15.G00_
O i
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k 15.303-yez s
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10 13.200 t
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i 17.040 20.S40 24.240 27.840 31.f40 35.0 to 33.640 42.240 45.840 49.440 53.040 TIME (SECONDS)
(X10 3)
REACTIMET.ER PLOT
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10 16 UN i
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i 17.040 50.640 24.240 27.E40
. 31.440 35.0 0 30.G40 42 240 45.840 49.440 53 040 TINE (SECONDS)
(X10 3)
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43.GtU 53.283 55.8%
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(X10 3)
REACTIi1ETER PLOT TSN:2 PERIOD #2 0000-1000 10/17/79 l
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(X10 3)
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s 46.083 43.6C3 53.283 56.833 0'J.433 6A.Ctc G7.GT 71.280 74.ES3 78.d33 62.0tD TINE (SECONDS)
(X10 3)
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( X1031 REACT.IMETER PLOT TSN 3 PERIOD #3 1400-2400 10/17/79
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i (X10 3) i TINE (SECONOSI PERIOD #3 TSN 3 1400-2400 RERCTIMETER PLOT 10/17/79
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ts.t00 I
I 3
5 4
5 8
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TIME (SECONCS)
(X10 3)
J REACTI.NETER PLOT TSN 3 PERIOD #3 1400-2400 rvM1 tun