ML20006A817
| ML20006A817 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/17/1990 |
| From: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 4410-89-L-0130, 4410-89-L-130, NUDOCS 9001300264 | |
| Download: ML20006A817 (19) | |
Text
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r OPU Nuclear Corporation NQQIMf 1
Post Office Box 480 '
1 Route 441 South Middletown, Pennsylvania 17057 0191 1
717 944 7621 4
TELEX 84 2386 1
Writer's Direct Dial Number:
(717) 948-8400 1
January 17, 1990 4410-89-L-0130/0517P d
,y y
US Nuclear Regulatory Commission
' Washington, DC 20555 Attention: Document Control Desk-Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No.. DPR-73 Docket No. 50-320 Additional Information on the Defueling Completion Report
Dear Sirs:
Attached is GPU Nuclear's response to your reauest for addition:1 information dated December.12, 1989 In this-submittal, we are responding to those
- ouestions related to the Defueling Completion Report; responses to those
- ouestions relating to the. Post-Defueling Monitored Storage Safety Analysis-
- Report will be forthcoming, Sincerely, i
M. B. Roche Director, THI-2 l
- EDS/ emf
' Attachment
~ cc: ' W. T. Russell. - Regional' Administrator, Region I J. F. Stolz - Director, Plant Directorate I-4
~
I L~. H. Thonus - Project Manager, TMI Site 0'
F. I. Young - Senior Resident Inspector, TMI 0
l'
/( \\l 9001300264 900117
{DR ADOCK 05000320 PDC GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation I -
I
, - + -
a ATTACHENT 4410-89-L-0130-RESPONSES TO USNRC REQUEST FOR ADDITIONAL INFORMATION, DATED DECEMBER i2, 1989 DEFUELING COMPLETION REPORT AND RELATED REFERENCES
~
Makeup Pump 1A, Engineering Calculation 4550-3211-87-027 OUESTION 1:
Elaborate on the use of the compensation factor "S" that allowed for the effect of ti.P lead shield around the Nal crystal.
Has the value verified through measurement?
RESPONSE
The method used to determine the amount of UO2 in tanks, pipes, or housings is indirect. Ce-144 activity formed by fission is related to the fuel quantity that produced the Ce-144.
Similar chemistry ensures that fuel debris contains a commensurate amount of Ce-144, which was, in turn, measured by gamma ray spectrometers.
Sodium iodide detectors were used to resolve the 2185 kev maximum energy gamma ray from Pr-144, the daughter of Ce-144.
Fuel determinations were performed as follows.
First, sufficient detector shielding was used to limit dead time to 1-107..
- Second, measurements were made at a number of locations designed to couple to expected fuel deposition in pipes, tanks, or other housings.
Third, the energy and efficiency calibrations were performed with a standard point source (i.e., Ce-144).
Finally, the conversions of data to Ce-144 activity were made as follows:
A.
The unshielded sodium iodide crystal efficiency was determined by comparing the observed emission rate, corrected for the detector shield, to the known source emission rate.
The correction for shielding was the "S" factor:
S - exp (xp) where:
x - counter shield thickness p - linear attenuation coefficient B.
MicroshieldTM, ISOSHLDTM, or QADTM calculations were used to transport the 2185 kev gamma rays from an assumed distribution and l
amount of fuel through the walls of the pipes, tanks, or housings, l
across the air gap, and through the detector shield to the crystal.
The calculated results were compared to the measured response.
The ratios of measured to calculated were used to correct the assumed amount of fuel for the actual measurements.
The technique of determining the unshielded detector efficiency simplifies transport of the gamma rays from the actual geometry to the detector crystal.
Further, this allows the calibrations to be made under conditions of the measurements which require the shield. 0517P
ATTACMENT 4410-89-L-0130 Makeup Pump 1A, Engineering Calculation 4550-3211-87-027 OUESTION 2:
(Page 7 of 97, paragraph 4.12.3)
Provide the basis for using only half of the available count to determine the count in the photopeak of Ce-144.
Indicate if a similar method of analysis was used for measurements made with the HPGe detector.
RESPONSE
Figure 1 is a graphical depiction of data representing the last calibration measurement made in makeup pump room
'A'.
The data was accumulated over more than 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> and clearly shows that the 2185 kev gamma ray peak from Pr-144 is the highest energy peak observed.
Referring to Figure 1, the upper and lower shoulders of the peak are not equal.
This is normal for sodium iodide detectors since the lower shoulder includes the Compton continuum.
Clearly, the signal to background ratto of the upper energy shoulder is superior and, therefore, a more sensitive means of determining activities that approach background.
Employing the upper half peak for the highest energy transition is a standard technique for simple spectra that do not require computer unfolding.
This is certainly the case for makeup pump room
'A'.
Efficiency calibrations were treated the same way with the region of interest set for the upper half peak.
HPGe detectors have much better energy resolution than sodium iodide detectors.
Therefore, the upper half peak technique would not be used with high resolution spectrometry.
Makeup Pump 1A, Engineering Calculation 4550-3211-87-027 OUESTION 3:
(Page 64 of 97)
Explain the basis for using a non-standard technique for calculation of the background correction rather than using the method described in Knoll (1979) p. 347 (Figure 10-24).
RESPONSE
The general background correction method described in KNOLL (1979) p. 347 (see Figure 2) is standard and a form is built into most modern multichannel analyzer operating systems.
This method works well if peaks are present but can produce rapidly changing and even negative values for spectra nar background.
The reason is relatively large counting uncertainty for the 'A' and 'B' values needed to define background according to KNOLL. Other methods average three channel results around the 'A' and 'B' points to improve results.
The technique defined on page 64 of Calculation 4550-3211-87-027 improves on KNOLL's method as follows: A second region of interest (ROI) is taken above the 2185 kev peak.
This second ROI 1s adjusted for the same energy width as the 2185 kev ROI. All data points in the region are used to produce the best linear fit by regression. The equation is used to calculate the
'A' and
'B' values to determine the "best" background value.
The technique is outlined in Figure 3. 0517P
c ATTACMENT 4410-89-L-0130 The two important properties of this technique are:
.A.
The regressed slope and intercept are much less uncertain than the single raw 'A' and 'B' values.
B.
Extending the equation to the 2185 kev ROI will tend toward slightly lower slope which will tend to produce slightly higher net events.
KNOLL's defines this as the peak at: 2.
The first property improves the precision and the second property increases the reported fuel quantity over simplor, more uncertain methods.
Makeup Tank, Engineering Calculation 4550-3211-87-038 OUESTION 4:
Elaborate on the selection of geometrios used to determine the maximum amount of fuel present when no signal was detected.
RESPONSE
As shown in Table 1, all ten spectral determinations made in the makeup tank room were positive.
The analysis method employed here and in general transports gamma rays to measurement locations from all pipes, tanks, and housings in the room, hereafter termed deposit regions.
The measurement locations match places where uncollimated spectra determinations were made.
As discusseo in the response to QJestion #1, an assumed value of fuel for each deposit region has adjusted to correspond to the entire measured gamma fluence rata. This provides independent fuel estimates for the nine pipe and one tank deposit regions for the first measurement location.
This-is repeated for all measurement locations; the results for the makeup tank calculation are shown in Table 2.
Selection of the minimum value for each of the ten deposit regions will overstate the amount of fuel present.
This is because the measured gamma fluence from each location is assumed to be due to deposits in only that region, whereas it is actually from all deposit regions.
The lowest value is always produced by a close measurement location or a place where shielding is minimum between assumed deposit point and measurement location.
This conservative method was adopted because, frequently, fewer measurement locations were used than obvious deposit locations.
Simultaneous solution of an underspecified set of equations is possible
)
but not performed here.
i
! 0517P x
m ATTACHENT 4410-89-L-0130 l
PLANNING STUDY INSTRUMENT SELECTION FOR RESIDUAL FUEL MEASUREMENTS OUESTION 5:
(Appendix C, paragraph C.1, #4) When alpha counting the bare RCS surfaces, was the film diluent factor applied to both the maximum and minimum calculations and how was-this factor derived?
RESPONSE
The film diluent factor was used to account for possible absorption of alpha particles by corrosion film material that is not related to 00 -
2 The factor'was derived by comparing results of the alpha probe measurements to radiochemical analysis of scraping from the same area.
Since then, an independent series of measurements were made which supercede the use of the film diluent factor. An average fuel density.
thickness of approximately 0.7 pg/cm2 (Reference 1) was measured for inconel surfaces.
The measurement on inconel covered approximately 100 times more surface area than the determination on stainless steel referenced in the planning study.
QUESTION 6:
(Appendix C) What is the area of the alpha counter.
Has the effect of dead time considered in the calculations?
RESPONSE
An Eberline PAC-6 was used to make the measurements referenced in the planning study.
The sensitive area of the detector was approximately 60
- cm2, Counting systems used for film assays were adjusted to be totally insensitive to Sr/Y-90 beta fields of approximately 1000 Rad /hr while maintaining alpha efficiencies of approximately 30% determined with a point Am-241 test source.
l Dead time was never a significant concern and was less than 1% for nearly all-measurements.
This can be verified by a process of estimation.
The ORIGEN t.omputer analysis (Reference 2) predicts 7 alpha particles per l
second per square centimeter for a fuel flim density thickness of one l
microgram per square centimeter.
Assuming an efficiency of 33%, the l
calculated count rate at 1.0 pg/cm2 film is:
l-Count Rate -
7 o< x 60 cm2 x c
- 140 CPS l
cm2s 3X One microsecond is a reasonable pulse width produced by the proportional counter detector assembly.
Therefore, approximately 10,000 CPS would be required for 1% dead time; a counting rate seldom if ever equaled.
The largest film thickness measured on a steam generator access plate was approximately 50 pg/cm2 for a count rate of 7000 CPS. 0517P
ATTACMENT 4"
4410-89-L-0130 N
OVESTION 7:
(Appendix C, paragraph C.4.1, assumption 3)
Elaborate on Assumption-number 3 for the Germanium Detector (C.4.1) that the collimated detector is insensitive to distance from the line source (Flux - approx 2 w RL).
i RESPONSE:-
Assumption 3 of Paragraph C.4.1 is incomplete.
The expression for uncollided gamma fluence in air is:
tan-I l + tan-1 l)
(Reference 3) dy(p) -
S 2
4x r f r
r where:
6y(p) - gamma fluence of point p S - y/s
/ "Il + #2
~2 p_
i r
-li If / = [2, then:
i 1
dY(p) =
S tan-I l l
2n r A 2r
?
The planning study was primarily a statement of intention prior to the practice of_ measurement.
The actual determinations of fuel content
'i always accounted for absorption thereby requiring a correct and more complete statement of gamma fluence transport.
In any event, the assumption and incorrectly stated approximation was never used.
I
-l
! 0517P l
~
p 6
ATTACMENT 4410-89-L-0130 i
POST-DEFUELING SURVEY REPORT - REACTOR BUILDING BASEMENT
~00ESTION 8.
(Pages 4 and,5) Provide additional details regarding the geometry and the detector calibration for the gamma spectrometry measurements used to estimate 1.2 kg of fuel in the reactor coolant drain tank (RCDT) discharge area.
RESPONSE
Additional information regarding measurement geometry and detector calibration are included in Appendix A.
QUESTION 9:
(Page 6)
Indicate the location of the drain system that runs from the-tool decontamination facility on the 347-ft elevation to the reactor building basement.
Indicate the basis for the assumption-that the fuel
, particles from the tool decontamination facility would have been washed into the reactor building basement sump.
Provide the basis for the unstated' assumption that additional fuel has not been added since the completion of the PDSR and is currently not being added to the inventory of the reactor' building basement, as a result of the continued decontamination of tools on the 347-ft elevation.
RESPONSE
The Reactor Building basement boundary was taken to include all space below the 305' elevation with one partial exception.
The exception is the Reactor Bu11 ding drain line that was used to transfer defueling tool decontamination wash water to the basement. As stated in the Post-Defueling Survey Report (PDSR) for the Reactor Building basement, a separate PDSR will be issued for this drain line when the decontamination-effort is concluded and final drain measurements can be made.
Interim measurements will be used to define the fuel content of this special drain line for the purposes of the Defueling Completion Report.
'The discharge path from the tool decontamination enclosure located on the 347' elevation of the-RV is from the decon sink to a floor drain located within the decon enclosure.
The discharge piping, from the floor drain, passes through the 347' elevation floor, turns nearly horizontal for about ten feet and then is essentially vertical for about 55 feet to a long horizontal run under the 282' elevation basement floor.
The pipe traverses-from south to the north RB sump under the floor. More than a dozen basement floor drains empty into the line.
To suppress airborne contamination, the basement floor has been maintained under a few inches of water.
Discharges from the decon sink, typically about 200 gallons, effectively flush clean the upper short horizontal section below the 347' elevation floor.
However, the flooded lower section, assisted by pressure relief from the basement floor 0517P
E I
ATTACMENT' 4410-89-L-0130 y
' drains, acts as a hydraulic buffer to reduce the linear velocity of the discharge.
Settlement of dense fuel particles is expected a few feet downstream of the start of the horizontal run.
Since the deposit location is not accessible for direct fuel assay, special means were employed.
Small gamma detectors, strapped to a drain snake, were used to determine the intensity of a significant part of the horizontal pipe run under the basement floor.
Results show an intensity increase'that corresponded to the expected region of debris deposit.
The measurements were modeled for three reasonable orientations of the detector, snake, and debris.
The first placed the detector directly "on" a thin layer of debris.
The second is similar to the first except that the layer of debris is thicker.
The last model considered the detector f
to be displaced to one side with the steel snake-shielding the detector, These models provide total UO2 deposits of 0.27, 0.48, and 5.1 kg, respectively.
Therefore, the UO2 deposit of record is 5.1 kg i 1001..
The last paragraph on page 6 of the Reactor Building Basement PDSR states that the basement fuci content is' expected to remain static. As discussed above, the basement fuel content does not include the RB drain line which serves as a hydraulic buffer between the decon enclosure and the RB basement.
This effectively precludes'the addition of residual fuel to the basement as a result of tool decontamination.
Therefore, an insignificant amount of fuel has been added to the RB basement since the-completion of the POSR.
w i 0517P
r-ATTACMENT 4410-89-L-0130
REFERENCES:
1.
B. H. Brosey, Uranium Film Quantity and Alpha Probe Efficiency.
Engineering Calculation 4530-3224-89-009, Rev. O.
Middletown, PA: GPU Nuclear Corporation.
2.
R. E. Lancaster; LCSA Grid Rib Section C-1 Analysis.
Engineering Calculation 4530-3227-88-025, Rev. O.
Middletown, PA: GPU Nuclear Corporation.
3.
J. R. Lamarsh.
Introduction to Nuclear Engineerina.
Reading, PA:
Addison-Hesley Publications.
1975.
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INTEGRAL AREA UNCERTAINTY 1
314 338 314 2028.08 272242 e*ese seese CH 314 27349 28873 28258 25180 23391 21883 19740 17789 CR 322 15541 13422 11507 9352 7898 8343 4963 3911 CH 330 3070 2245 1882 1282 890 880 480 338 c
CH 338 250 pols EIG END MAX Eh M (KEV)
INTEGRAL AREA UNCERTAINTY 2
339 383 339 2192.27 1422 seese seese CH 339 180 150 117 108 80 57 58 49 CH 347 50 57 42 40 35 44 33 51 CH 355 44 42 34 -
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l' SCINnt.1ATION GUNmts RADIAMON SFBCIltOSCOPY wmt SCtNmhT00tS y'
Ie anotofraction relative to a sodium iochde crystal of the no m ai.m===
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$ efficiency data for any detector, the area under the F
2 in its spectrum must be determined. Even after From Knol1,G.F., Radiation background, nearly all such peaks win be supene.
D"" "o Detection and Measurement,1979.
based by many of the comphcating effects desenbed tal
!ia therefore not always a simple task to determene the pribute to a given full. energy peak.
pie isolated one without any superimposed continuum,
$ its tres could be determined by semple integration p When the spectrum is recorded in a multichannel
" "" ' y #* ~ * ' ' #,. c, c
- process is a simple addition of the content of each e nnoi M8 4
kled limits. If a continuum is.also present, as in Fig.
I.
HA unwanted counts are included i.t this prarm and must A
must therefore be assumed f< r the continuum withis I-cnd a number of fitting proces bres of varying degrees pplied. A linear interpolation between the continuum
, he peak is the easiest approach tu:d wiu give sufficient t
-: N mes.
)D or overlapping peaks do not allow the straightforward
$(pplied. More complex methods must then be used to contnbutions of each of the closely lying peaks.'Ihese ft>8 ha fitting an analytic shape to that portion of the peak solved, tnd assuming that the remainder of the peak is MGUIRE IS M.
Meskuds of chemining peak ssens frean -maa=mm.a yseers.
s 7,j iftnction. It has been demonstrated" that a Gaussian
. thxt lie within one standard deviation on either side of
! ~,' '
(see Chapter 13), applications sometimes arise in which the size lisaitation of represents the shape of the measured photopeak fras over an essortment of source geometry and counting elima detectors or.other considerations dictate the use of scintiHators.
1, The nature of the electron response function depends on the scintiMation D
km shapes tre sometimes necessary for spectra recmded
+*
' nideal circumstances. Because a good deal of complex.
material, its physical thickness, and the angle of ii.dde.a of the electrons.
o Electrons from an external source normany must pass through some protective l0itting routines, nearly all are carried out by computer coming and/or light reflector before reaching the surface of the scantdlator cribed in further detail in Chapter 18.
itself. In the discussion that follows, the energy loss that may occur in these
I unervening materials is not exphcitly considered, but may be important if the N WM NMRS electron energy is small. We win also assunse that the seinenHators und:x
) tpplied to the measurement of fast electrons (such as consideration are thicker than the maximum range of the incident electrons.
3 incident on one surface of the crystal. Although it has Even so, the detector may not be totaHy w to the secondary bremostrab-to use lithium. drifted silicon detectors for this purpose Isas photons which will be generated along the path of the electron.
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O g-g @
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nim 2 -(iz /
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g M g,,,7, g g.172 Slopeof theline.
@'3 Hetain these statistics in your calculator for use in the nest
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g g
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A slope Laneer Estunetoon end Correlseson Coethesent X+
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Lineer Estimation. With statistics accumulated e.n registers Ro j
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heying in a known value for s and pressms @@. Similarly, a Solution: Voltz ciald draw a plot of cual orixtudion against electrical output like the one shown below. Ilowever, with her Cl4 predicted value for z (denoted Al can be calculated by keysag in a llP 10C. Voltz has only to accumulate the statistics (as we have known value for y and pressing @@.
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