ML20352A269

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Response to Request for Additional Information Re Revised Final Status Survey Final Reports, LC-FS-TSD-005, Revision 0, MCNP Modeling of Water Discharge Pipes for the Lacrosse Boiling Water Reactor
ML20352A269
Person / Time
Site: La Crosse  File:Dairyland Power Cooperative icon.png
Issue date: 11/02/2020
From:
La CrosseSolutions
To:
Office of Nuclear Material Safety and Safeguards
Shared Package
ML20356A041 List:
References
LC-2020-0023 LC-FS-TSD-005, Rev 0
Download: ML20352A269 (16)
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LACBWR Site Restoration Project Work Control Procedure MCNP Modeling of Water Discharge Pipes for the LaCrosse Boiling Water Reactor Procedure No. LC-FS-TSD-OOS Revision No~ ~ \ \ j1) \I~

Preparer (Print name/Sign)

Secondary Rmewer (Print Name/Sign)

Regulatory Required Reviews (attach completed LC-RA-PR-001 and QTR forms, as applicable)

Part 50 License: 10 CFR. 50.59 and 50.90 181 YES NO Fire Prot.ection: 10 CFR. 50.48(£) YES 181 NO Conditions of License: PSP: 10 CFR 50.54(p) YES Conditions of License: E-Plan: 10 CPR 50.54(q) 0 YES 181 NO Tennination ofUcense: 10 CFR S0.82(a)(6) and 50.82(a)(7) YES 18] NO Part 72 License: 10 CFR 72.48 YES Program Required Reviews RP: l8J YES O NO ~;__.a&.~.,.,4,(L,,£.,£,L-'--=:::::::::::::::C_DATE: /I/4;!1 QA: YES 181 NO SIGNATURE_ _ _ _ _ _ _ _ _ ____;DATE: _ _ __

QTR: 0 YES [81 NO SIGNATURE_ _ _ _ _ _ _ _ _ _ _DATE:_ _ __

Effective Date: - 11/13/2019

- (assigned by ocument Control or Project Manager)

LC-FS-TSD-005 MCNP Modeling Of Water Discharge Pipes For The Lacrosse Boiling Water Reactor Revision--kO P\

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Table of Contents 1 Introduction ............................................................................................................................................ 3 2 Summary of previous study ................................................................................................................... 3 3 Model description .................................................................................................................................. 4 3.1 PIPE .............................................................................................................................................. 5 3.2 DETECTOR ................................................................................................................................... 6 3.3 SOURCE .......................................................................................................................................6 4 Results .................................................................................................................................................. 8 5 Attachments ........................................................................................................................................ 11 6 References .......................................................................................................................................... 11 Page 2 of 12

LC-FS-TSD-005 MCNP Modeling Of Water Discharge Pipes For The Lacrosse Boiling Water Reactor Revision~ o 1 Introduction ~\3' In January and February 2019, Radiation Safety & Control Services (RSCS) used the MCNP (Monte-Carlo Neutral Particle) radiation transport code to model the response of a Nal detector to a calibration source placed inside a 60-inch concrete pipe. The same model was then used to study the response of the detector with a uniform contamination level of 100 dpm/cm2 deposited over the entire pipe, and for various lengths of contaminated pipe ranging from 1 to 100 feet (Reference 1).

This TSD documents the result of a new MCNP study conducted to evaluate the response of a similar Nal detector placed inside contaminated pipes of various diameters ranging from 10 inches to 48 inches. The response of the detector inside these pipes is compared to the response of the detector positioned on a flexible NIST traceable Cs-137 calibration source.

2 Summary of previous study A first MCNP model was built by placing a flexible Cs-137 calibration source inside a 60-inch steel pipe. The calibration source is 1 foot wide by 1 m long and is flexible. It is positioned on the inner radius of the pipe, perpendicular to the long axis of the detector. Additional MCNP models were built assuming that a Cs-137 contamination was uniformly distributed over the inside of the pipe, with contaminated pipe lengths ranging from 1 foot to 100 feet. For each model, a 2" x 2" Nal Ludlum 44-10 detector was positioned longitudinally in the center of each contaminated section while radially positioned 5.5 inches from the bottom of the pipe. Figure 1 represents an illustration of the modelled geometry.

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Figure 1: Illustration of the MCNP Pipe / Detector model For each contaminated pipe length, a correction factor was calculated. The correction factor is the ratio, R, of the response of the detector to a uniformly Page 3 of 12

LC-FS-TSD-005 MCNP Modeling Of Water Discharge Pipes For The Lacrosse Boiling Water Reactor Revision~ o distributed contamination to the response of the detector positioned on top of the ~,3\,<\

calibration source. It was assumed that the response of the detector is proportional to the average flux inside the Nal crystal volume.

The results of this study are shown in Table 1 and on Figure 2.

Source Source MCNP Calculated Flux in MCNP RE 2 R Length (ft) type Nal / 100cm (Relative Error) 1 Calibration 6.45E-03 2.60E-02 1.00 1 Uniform 8.19E-03 0.0489 1.27 2 Uniform 1.44E-02 0.0532 2.23 3 Uniform 1.86E-02 0.059 2.89 5 Uniform 2.19E-02 0.0218 3.39 10 Uniform 2.77E-02 0.0277 4.30 20 Uniform 3.20E-02 0.0369 4.96 30 Uniform 3.51 E-02 0.0302 5.44 50 Uniform 3.40E-02 0.039 5.28 70 Uniform 3.36E-02 0.0468 5.21 100 Uniform 3.47E-02 0.0565 5.38 Table 1: MCNP simulation results MCNP Slmulatlon of Response of an In-pipe Nal Detector from Cs-137 coat1111 the Inside of an Iron 60 Inch ID pipe vs axlal source len1th. Nal Is at mid-pipe length.

10 1

10 100 Source Lenp along Pipe Axis {ft)

Figure 2: MCNP simulation results 3 Model description Page 4 of 12

LC-FS-TSD-005 MCNP Modeling Of Water Discharge Pipes For The Lacrosse Boiling Water Reactor Revision 'f..i 0 New calculations were conducted with a MCNP model similar to the model described in ~,j\,"1 Reference 1. The detector is positioned inside contaminated pipes, ranging from 1 foot to 30 feet in length. A description of the model is provided on Figure 3.

Pipe Air inside pipe Detector Air outside pipe Outside world Figure 3: XY and ZX projections of the MCNP geometry 3.1 Pipe Calculations were conducted for six different pipes (different materials and diameters).

Table 2 shows the parameters used for each pipe.

Pipe diameter Pipe# Pipe material (inches) 1 Steel 60 2 Concrete 48 3 Concrete 30 4 Steel 18 5 Clay 12 6 PVC 10 Table 2: pipe parameters Pipe materials were provided by LACBWR. However, as the pipe material only impacts the bascattered portion of the flux measured by the Nal detector, it has a minimal effect on the correction factor. Therefore, results provided in this TSO are also valid for pipes made of different materials.

The wall thickness of each pipe is assumed to be 4 inches. This value is higher than the actual thicknesses, but this parameter has no influence over the calculations results, as the goal is to quantify how much backscatter radiation reaches the detector rather than evaluating the amount of shielding provided by the pipe wall.

Pipe materials were defined in MCP using parameters provided in "Compendium of Material Composition Data for Radiation Transport Modeling, Report number PNNL-15870 Rev1" (Reference 3)

Page 5 of 12

LC-FS-TSD-005 MCNP Modeling Of Water Discharge Pipes For The La Crosse Boiling Water Reactor Revision...,._ 0 \ (\

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Correction factors for the 60" steel pipe (case #1) were calculated by RSCS in February 2019 (Reference 1). This case was used to benchmark the new MCNP runs.

3.2 Detector The detector is modeled has a cylinder with a 2-inch diameter. The detector includes 2 parts:

The electronic part is a 4-inch long cylinder. It's assumed to be made of iron with a density of 0.5 g/cm 3 ;

The crystal part is a 2-inch long Nal cylinder with a density of 3.67 g/cm 3 .

Nal Electronics crystal Figure 4: Detector The centerline of the detector is parallel to the pipe. Table 3 shows the distance of the center of the detector to the inside bottom of the pipe for each case.

Distance detector - pipe Pipe#

(inches) 1 5.5 2 6 3 6.25 4 8 5 5 6 5 Table 3: Distance detector - pipe 3.3 Source For each pipe, a first series of calculations was conducted by modeling a calibration source measuring 1 ft x 1 m. The flexible calibration source is laid on the inside bottom of the pipe, perpendicular to the long axis of the pipe. When the source is longer than the pipe circumference, it is assumed that 2 source layers overlay at the top of the pipe.

Page 6 of 12

LC-FS-TSD-005 MCNP Modeling Of Water Discharge Pipes For The Lacrosse Boiling Water Reactor Revision ..,,..._ o i

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Figure 5: calibration source inside the 48" Figure 6: calibration source inside the 10" pipe pipe Subsequent calculations were conducted assuming a uniform contamination over the entire circumference of the pipes, for contaminated pipe lengths ranging from 1 foot to 30 feet.

Figure 7: 48" pipe with uniformly distributed contamination For each MCNP run, it is assumed that the source is uniform with an activity of 100 dpm/cm 2 . Therefore, the flux inside the Nal crystal calculated by MCNP is multipled by the source area to account for the total activity inside the pipe. Table 4 shows the source areas used for each MCNP run:

Page 7 of 12

LC-FS-TSD-005 MCNP Modeling Of Water Discharge Pipes For The Lacrosse Boiling Water Reactor Revision 'k o Source length ~,1\\"\

Pipe#1 Plpe#2 Pipe#3 Plpe#4 Plpe#S Plpe#6 (feet)

Calibration 3048 3048 3048 3048 3048 3048 1 14593 11675 7297 4378 2919 2432 2 29186 23349 14593 8756 5837 4864 3 43780 35024 21890 13134 8756 7297 5 72966 58373 36483 21890 14593 12161 10 145932 116745 72966 43780 29186 24322 20 291864 233491 145932 87559 58373 48644 30 437795 350236 218898 131339 87559 72966 2

Table 4: Source areas (cm )

4 Results An example of MCNP input parameter set (48" diameter- calibration source) is provided in Attachment A.

For each geometry, a correction factor was calculated. The correction factor is the ratio, R, of the response of the detector to a uniformly distributed contamination to the response of the detector positioned on top of the calibration source. The run time of the simulations was adjusted to obtain relative errors lower than 2.5%.

Results of the calculations are provided in Table 5 though Table 10 and on Figure 8.

Source Runtime MCNP Relative Correction length (feet) (mn) values Error factors Calibration 2 4.162E-03 5.300E-03 1.000 1 2 5.458E-03 9.500E-03 1.311 2 2 9.051E-03 1.210E-02 2.174 3 5 1.115E-02 7.700E-03 2.680 5 5 1.410E-02 9.000E-03 3.387 10 8 1.742E-02 1.000E-02 4.185 20 10 1.967E-02 1.300E-02 4.725 30 12 2.107E-02 1.130E-02 5.062 Table 5: Results and correction factors for the 60" pipe Page 8 of 12

LC-FS-TSD-005 MCNP Modeling Of Water Discharge Pipes For The Lacrosse Boiling Water Reactor Revision~ 6 Source Run time MCNP Relative Correction length {feet) (mn) values Error factors Calibration 2 3.954E-03 7.400E-03 1.000 1 2 5.332E-03 1.200E-02 1.349 2 2 8.885E-03 1.300E-02 2.247 3 5 1.125E-02 1.050E-02 2.845 5 5 1.409E-02 1.190E-02 3.564 10 5 1.749E-02 1.270E-02 4.423 20 10 1.930E-02 1.210E-02 4.881 30 10 2.046E-02 1.460E-02 5.176 Table 6: Results and correction factors for the 48" pipe Source Runtime MCNP Relative Correction length (feet) (mn) values Error factors Calibration 2 4.262E-03 8.400E-03 1.000 1 2 5.805E-03 1.080E-02 1.362 2 2 9.389E-03 1.200E-02 2.203 3 5 1.166E-02 8.100E-03 2.736 5 5 1.462E-02 8.900E-03 3.431 10 5 1.672E-02 1.070E-02 3.922 20 10 1.866E-02 9.800E-03 4.379 30 10 1.881E-02 1.200E-02 4.414 Table 7: Results and correction factors for the 30" pipe Source Run time MCNP Relative Correction length (feet) (mn) values Error factors Calibration 2 4.672E-03 6.100E-03 1.000 1 2 6.393E-03 5.700E-03 1.368 2 2 1.009E-02 6.600E-03 2.159 3 2 1.224E-02 7.400E-03 2.620 5 2 1.409E-02 9.300E-03 3.016 10 2 1.590E-02 1.180E-02 3.404 20 5 1.676E-02 1.050E-02 3.588 30 5 1.673E-02 1.240E-02 3.580 Table 8: Results and correction factors for the 18" pipe Page 9 of 12

LC-FS-TSD-005 MCNP Modeling Of Water Discharge Pipes For The Lacrosse Boiling Water Reactor Revision"'1-.

Source Run time MCNP Relative Correction \ f\

length (feet) (mn} values Error factors \\\ \~

Calibration 2 8.712E-03 4.900E-03 1.000 1 2 8.712E-03 5.200E-03 1.000 2 2 1.207E-02 6.500E-03 1.385 3 2 1.367E-02 7.500E-03 1.569 5 2 1.542E-02 9.700E-03 1.770 10 2 1.620E-02 1.330E-02 1.860 20 5 1.654E-02 1.150E-02 1.898 30 5 1.698E-02 1.390E-02 1.949 Table 9: Results and correction factors for the 12" pipe Source Run time MCNP Relative Correction length (feet) (mn} values Error factors Calibration 2 1.092E-02 4.000E-03 1.000 1 2 8.716E-03 3.800E-03 0.798 2 2 1.219E-02 4.300E-02 1.116 3 2 1.337E-02 4.700E-03 1.225 5 2 1.480E-02 6.000E-03 1.355 10 2 1.548E-02 8.200E-03 1.418 20 2 1.554E-02 1.120E-02 1.424 30 5 1.600E-02 9.500E-03 1.465 Table 10: Results and correction factors for the 10" pipe Page 10 of 12

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Figure 8: summary of MCNP results 5 Attachments A. Example of MCNP input deck ((48" diameter- calibration source) 6 References

[1] LC-FS-TSD-003 "Assessment of the LACBWR Circulating Water Discharge Pipe Final Status Survey Data for Detection Efficiency and Detector Background -

Revision 0", EnergySolutions, 2019.

[2] Los Alamos National Laboratory, "MCNP6 Version 1.0" Los Alamos User's Manual LA-CP-13-00634, Rev. 0".

[3] "Compendium of Material Composition Data for Radiation Transport Modeling, Report number PNNL-15870 Rev1 ," Pacific Northwest Laboratory, 2011 .

Page 11 of 12

LC-FS-TSD-005 MCNP Modeling Of Water Discharge Pipes For The Lacrosse Boiling Water Reactor Revision "1.J fl L,- \'"

r1*\\:1 Attachment A ~

mc48-0-1. txt RSCS Calib Factor for NaI vs Cs-137 in Concrete Pipe for Lacrosse (diameter 48")

C Case file name mc48-0-1 C CELLS 1 3 -3.6670 14 -15 -44 $ NaI detector volume 2 2 -0.5000 13 -14 -44 $ electronics volume 3 1 -0.0012 12 -16 -41 #1 #2 $ air inside pipe 4 4 -2.3000 12 -16 41 -42 $ concrete pipe wall 5 1 -0.0012 12 -16 42 -43 $ air outside pipe 6 1 -0.0012 11 -12 -43 $ air outside lower pipe end 7 1 -0.0012 16 -17 -43 $ air outside upper pipe end 9 0,0000 -11 43 17 $ outer kill void 999 0.0000 -999 $ CCC for SOE F C X PLANES 11 px -857,2 $ model lower plane 12 px -757,2 $ pipe lower plane 13 px -12. 7 $ electronics lower 14 px -2.5 $ detector lower lS px 2.5 $ detector upper 16 px 757.2 $ pipe upper 17 px 857.2 $ model upper C R/X CYLINDERS 41 ex 60.96 $ pipe IR (24")

42 ex 71.12 $ pipe DR 43 ex 76.12 $ model OR 44 c/x 0.0 -45.72 2.5 $ detector cylinder 999 RPP -757, 20 757 .20 -76.12 76.12 -76.12 -41. 57 $ Cookie Cutter Cell CCC C DATA CARDS C MATERIALS C air ml 7014 -9.06E-04 8016 -2. 78E-04 18000 -1. 55E-05 $ Air Page l mc48-0-1.txt C iron from pnnl-15870Revl m2 26000 -1 $ iron density 7 .874 c NaI from pnnl-l5870Rev1 m3 11000 0. 49999 53000 0.500001 $ NaI c Concrete from pnnl-15870Revl (concrete, regulat #99) m4 1000 -0. 010 8000 -0.532 11000 -0.029 13000 -0.034 14000 -0.337 20000 -0.044 26000 -0.014 $concrete density 2.3 C PHYSICS imp: p $ Importances l 6r 0 0 mode p C TALLY F4:p l $ particle flux (p/cmsq) averaged over the NaI volume FM4 30 $ source area ( 100 cmsq)

C SOURCE SDEF pos 0 0 0 axs 1 0 0 ext=dl rad=d2 erg=. 662 par 2 CCC=999 SU -15 15 $ source length spl 0 1 SI2 60. 71 60. 96 $ source radial bounds sp2 -21 1 C CONTROL CTME 2.0 PRINT 86 cprdmpjjl Page 2 Page 12 of 12

LC-RA-PR-001 Revision4 ATTACHMENT B-2 50.59 Review Covenheet Form

=* =-W Station: - -....:L..A=CB ---=-------

R Activity/Document Number: LC-FS--TSD-005

Title:

MCNP Modeling of Water Discharge Pipes for the L gaCrosse Boiling Water Reactor NOTE: For 50.59 Evaluations, infonnation on this form will provide the basis for preparing the biennial summary report submitted to the NRC in accordance with the requirements of 10 CPR 50.59(d)(2).

Description of Activity:

(Provide a brief, concise description of what the proposed activity involves.)

Provide clarification regarding the applicability of this TSD for piping made of various materials.

Reason for Activity:

(Discuss why the proposed activity is being performed.)

To ensure it is understood that applying the TSD modeling to a variety of piping materials is acceptable.

Effect of Activity:

(Discuss how the activity impacts plant operations, design bases, or safety analyses described in the UFSAR.)

The changes are considered clarifications regarding the applicability of the TSD and have no adverse impact on LTP compliance.

Summary of Co*clusion for the Activity's 50.59 Review:

(Provide justification for the conclusion, including sufficient detail to recognize and understand the essential arguments leading to the conclusion. Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment Request, as applicable; is not required.)

Revisions lof this TSD provides clarification regarding various piping materials being bounded.

Compliance with the LlP and D-Plan/PSDAR (SAR equivalent) are maintained.

Attachments:

Attach all 50.59 Review forms completed, as apprnpriate.

(NOTE: if both a Screening and Evaluation are completed, no Screening No. is required.)

Forms Attached; (Check all that apply.)

Applicability Review x 50.59 Screening 50.59 Screening No. 2019-015 Rev. __.Q 50.59 Evaluation 50.59 Evaluation No. Rev.

LC-RA-PR-001 Revision4 ATIACHMENT B-4 50.59 Screening Form 50.59 Screening No. ____..20 19:G

~= 15____ ___ Rev. No. _ _..0_ _

Activity/Document Number:MCNP Modeling of Water Discharge Pipes/ LC-FS-TSD--005 Revision Number:.¥ q ., I1/ \C\

I. S0.59 Screening Qu.estiom (Check correct response and provide separate written response providing the basis (l \\

for the answer to each question):

1. Does the proposed Activity involve a change to an SSC that adversely affects YES __x_NO an UFSAR descnbed design fimction?

Revision 1 of this procedure was performed to ensure it is understood that applying the TSO modeling to a variety of piping materials is acceptable. It was determined that pipe material only impacts the backscattered portion of the flux measured by the NAI detector and has minimal impact on the correction factor. Compliance with the LTP and D-Plan/PSOAR is maintained. This procedure does not adversely affect the decommissioning activities discussed in the D-Plan/PSDAR.

2. Does the proposed Activity involve a change to a procedure that adversely YES _x__No affects how UFSAR descn'bed SSC design functions are performed or controlled?

Revision 1 of this TSD provides clarification regarding various piping materials being bounded by the TSO pipe modeling. The difference in bacbcattering for the various pipe materials is insignificant such that there is minimal effect on the overall conection factor. Compliance with the LTP and D-Plan/PSDAR is maintained. This procedure revision does not adversely affect the decommissioning activities discussed in the D-Plan/PSOAR.

3. Does the proposed Activity involve an adverse change to an element of a YES ...x_NO UFSAR described evaluation methodology, or use of an alternative evaluation methodology, that is used in establishing the design bases or used in the safety analyses?

No advene changes to evaluation methodology di8CU8sed in the D-PJanlPSDAR or the LTP resulted from Revision 1 of this TSD. The change provides clarification regarding piping material impact on the dose correction factor.

4. Does the proposed Activity involve a test or experiment not described in the _YES ..A_NO UFSAR, where an SSC is utilized or controlled in a manner that is outside the reference bounds of the design for that SSC or is inconsistent with analyses or descriptions in the UFSAR?

No tests or experiments arc associated with Revision 1 of this TSD.

5. Does 1he proposed Activity require a change in the Technical Specifications YES ..A_NO or Operating License?

Neither the POTS nor the associated licenses are impacted by 1his revision.

Page21 of58

LC-RA-PR-001 Revision4 IL List the documents (e.g., UFSAR. Technical Specifications, other licensing basis, technical, commitments, etc.)

reviewed, including sections numbers where relevant information was found (if not identified in the response to each question).

l)..Plan/PSDAR (November 2017)

LACBWRLTP LC-FS-TSD-003, Rev 0 ID. Select the appropriate conditions:

If Ill questions are answered NO, then complete the 50.59 Screening and iniplement the Activity per X the applicable governing procedure.

If question 1, 2, 3, or4 is answered YES and question 5 is answered NO, then a 50.59 Evaluation shall be performed.

If questions 1, 2, 3, and 4 are answered NO end question 5 is answered YES, then a License Amendment is roqujred prior to implementation of the Activity.

If question 5 is answered YES for any portion of an Activity, then a License Amendment is required prior to implementation of that portion of the Activity. In addition. if question 1, 2, 3, or 4 is answered YES for the remaining portions of the Activity, then a 50.59 Evaluation shall be perfOJllled for the remaining portions of the Activity.

IV. Screening Signoffs:

d ~ ~ /

  • 50.59 S w , I..,..:name) S4,n: fuir~ 11~;;--l'f Jl1iio. IM&II'!,,...

50.59Reviewer: _ Arthur

___ _ _ _ _ _ _Sign: viaema*i1 d ate d 11/7/2019 Adams Date: 1 1 (Print name) {Signature)

Page22 of58

From: Arthur Adams To: Kimberly Martinson Cc: James c Ashley

Subject:

RE: 50.59 Reviewer Date: Thursday, November 07, 2019 6:33:25 AM This email documents my signature on LC-FS-TSD-005 Rev 1 as 59.59 reviewer.

Arthur R. (Bob) Adams Project Engineer EnergySolutions 698 Spartina Ct Sanibel, FL 33957 (239) 472-2243 (847) 219-2483 From: Kimberly Martinson Sent: Tuesday, November 05, 2019 4:05 PM To: Arthur Adams Cc: James C. Ashley

Subject:

50.59 Reviewer Can you sign the 50.59 as reviewer on the last page please. Thanks.

Kim Kimberly Martinson Administrative Assistant 2 EnergySolutions LaCrosseSolutions LACBWR Site Restoration Project Reactor D & D Projects 4601 State Highway 35 Genoa, WI. 54632 khm artin c;on @energysolutions.com Office: 608-689-4218 kh marti nson@energysolutions.com

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