ML20148T751
| ML20148T751 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/06/1996 |
| From: | Parfitt B GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20148T644 | List: |
| References | |
| 6612-96-031, 6612-96-031-R00, 6612-96-31, 6612-96-31-R, NUDOCS 9707090309 | |
| Download: ML20148T751 (8) | |
Text
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\\GU NUCLEAR
\\
CALCULATION SHEET l
l
Subject:
Calc No.
Rev. No.
I ESTIMATE OF RM-G-6 t. 7 READING WITH DECREASED VESSEL LEVEL 6612-96-031 0
Originator-Date Reviewed by:
Date PARFITT 11/05/96 v
1.
Problem Statement The minimum RM-G-6 or 7 reading when a spent fuel assembly in the reactor vessel is almost uncovered is being estimated.
j>
2.
Results Summarv Based on the assumptions made in this calculation, RM-G-6 or 7 will read 1.5 to 2.0 R/hr, if the water level in the-reactor vessel drops to within 6 inches of the top a single spent fuel assembly.
3.
Reference's 3.1 RAF 6612-90-014 3.2 Microshield 4 3.3 RAF 6612-96-022 4.
Assumotions i
4.1 The isotopic activity of a fresh fuel assembly (72 hr post
, shutdown) was taken from Reference 3.1.
4.2 It is assumed that there is one spent fuel assembly left in the reactor vessel when the water level drops to within six inches of the top of the assembly.
Typically there would be many more assemblies in the vessel at any given time.
4.3 It is assumed the age of the fuel assembly is 28 days post shutdown or close to the end of a typical refueling shutdown.
4.4 It is assumed that the fuel handling bridge is parked at the end of the fuel canal, farthest away from the fuel, approximately 50 feet away in the horizontal direction.
'4.5 The distance from the fuel assembly to the monitor is j
assumed to be 35 feet in the vertical direction.
\\GU NUCLEAR CALCULATION SHEET
Subject:
Calc No.
Rev. No.
ESTIMATE OF RM-G-6 & 7 READING WITH DECREASED VESSEL LEVEL 6612-96-031 0
Originator:
Date Reviewed by:
Date PARFITT 11/05/96 4.6 The composition and density c; the source material (fuel assembly) was derived using the volume fractions and densities in Reference 3.1.
The weighted densities are as follows:
WEIGHTED 1
DENSITY DENSITY l
VOLFRAC (g/cc)
(g/cc)
UO2 0.303 18.75 5.68 WATER 0.592 1
0.59 ZlRCALOY 0.102 6.5 0.66 STAINLESS 0.003 7.86 0.02 5.
Data and Calculations 5.1 The activity of a 72 lir old fuel assembly was calculated and input into the Microshield Model.
The. mix was then decayed by Microshield to 25 days.
The results for 0.5 i
feet of water shielding were calculated.
The results are attached.
5.2 The Microshield model warns that when the buildup reference material is a mixed material with a high atomic number element, the model can give incorrect results for energies less than 100 kev.
The results may also be suspect for j
energies between 100 to 500 kev.
Review of the Microshield input shows insignificant dose rate contribution from these energy ranges when either the source or water is used as the buildup' reference material.
As a result, the results of these dose rate calculations are felt to be accurate.
o
a t
Microshield 4.10 - Serial 84.10-00478 GPU Page
- 1 File Ref DOS File: SF50.MS4 Date: _/_/_
Run Date November 5 1996 By:
Run Time 4:12 p.m. Tuesday Checked:
Duration 0:00:38 Case
Title:
<None>
GEOMETRY 13 - Rectangular Volume centimeters feet and inches Dose point coordinate 1:
1524.0 50.0
.0 Dome point coordinate Ya 1524.0 50.0
.0 Dome point coordinate 2:
10.91184 0.0 4.3 Rectangular volume width:
21.82368 0.0 8.6 Rectangular volume length:
426.72 14.0
.0 Rectangular volume height:
21.82368 0.0 0.6 Shield 1:
15.24 0.0 6.0 Air Gap 1002.04 35.0 6.0 Source Volume: 203235. ca"3 7.17718 cu it.
12402.2 cu in.
MATERIAL DENSITIES (g/cm*3)
Material Source Shield 1 Air Gap Immersion
-Shield Slab Shield Air 0.00122 Iron 0.02 i
Uranium 5.68 Water 0.59 1.0 1.0 Zirconium 0.66 BUILDUP Methods Buildup Factor Tables
-The material reference is Source
[
.......... cR m 0,..........
This buildup r9 erence material is a mixed material with a high atomic f
number element (91). Buildup Factors less than and somewhat greater than 113 kev may be incorrect. Please understand your resultsi INTEGRATION PARAMETERS t
Quadrature Order X Direction 10 Y Direction.
20
[
Z Direction 20 L
SOURCE NUCLIDES Nuclide
. curies pCi/ca'3 Nuclide curles pCi/ca"3 Ba-137m 2.6635e+004 1.3106e+005 Ba-140
_1.5452e.005 7.6028e+005 Ce-144 3.9611e*005 1.9490e+006 Cs-134 7.0167e+003 3.4525e+004 Cs-135 2.2276e-007_. 1.0961e-006 Cs-136' 1 0372e+003 5.1032e+003' 2.8156e+004 1.3854e+005 I-129 1.0200e-002 5.0188e-002 Cs-137 I-131 4.6695e+004 2.2976ee005 I-133 1.3573e-004 6.6786e-004
-. ~..
__ ~,.... _ _ _ _ _.. _ -
b r
i Kr-OS 2.97$se+St['1.46473+tue' La-149'
'1.7700e+015 -S.740534015-Ho-99 7.6619e+012 - i.?AI9e +103.
Pr-144 3.96123+615' 1.9491a+336 1'
' Pr-144m ~ 5.6644e+003 2.7071e+C04 Rh-106~
1.5074e+005 7.4160e+005 Ru-106-1.5074e+005 7.4168e+005 Er-09 3.5063e+005 1.7252e+006 3
Sr-90 2.2463e+004 1.1053e+005 Sr-91 2.7091e-016 1.3723e-015 i
- Ye-99 1.6027e-002. 7.8960e-002' Tc-99m 7.4624e+002 3.6753e+003
^
[
[
Ie-131m 1.6623e+003 0.1792e+003 Me-133 2.2409e+004 1.1066e+005" i
Ie-133m-3.4762e+000 1.7104e+001 Me-135 7.3536e-018. 3.6152e-017'
Y-90 2.2453e+004 1.1040e+005 Y-91~
3.9936e+005 1.9650e+006 Y-91m 1.7539e-016- 0.6299e-016
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- e Page
- 2 DOS Files SF50.MS4 Run Cates November 5 1996 Run Time 4:12 p.m. Tuesday' Title
<None>
===.....==..................... RESULTS
======.....====..........
Energy Activity Energy Fluence Rate Exposure Rate In Air (NeV)
(photons /sec )
(Nev/sq cm/sec)
(mR/hr)
No Buildup Mith Buildup No Buildup Mith Buildup O.1 1.680e+013 S.927e-003 3.175e-002 1.366e-005 4.557e-005 0.15 2.056e+015' 2.204e+000 1.401e+001 3.630e-003 2.307e-002
~
0.2 4.065e+013 2.075e-001 1.712e+000 3.662e-004 3.021e-003 1
0.3 1.777e+015.
6.761e+001 6.431e+002 1.202e-001 1.220e+000 0.4 1.095e+015 2.749e+002 2.540e+003 5.356e-001 4.949e+000 I
0.5 5.623e+015 2.144e+003 1.830e+004-4.207e+000 3.592e+001 0.6 2.134e+015 1.721e+003 1.355e+004 3.360e+000 2.644e+001 0.8 2.548e+015 6.353e+003 4.371e+004 1.200e+001 8.313e+001 1.0 9.316e+014 5.392e+003 3.276e4004 9.939e+000 6.035e+001 1.5 6.375e+015 1.475e+005 6.085e+005 2.481e+002 1.158e+003 2.0 1.694e+014 8.815e+003 3.479e+004 1.363e+001 5.379e+001 3.0 2.342e+014 3.219e+004 1.019e+005 4.367e+001 1.393e+002 TOTAL:
2.300e+016 2.044e+005 9.367e+005' 3.356e+002 1.563e+003 i
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e Microshield 4.10 - Serial 54.10-00478 GPU Page
- 1
. File Ref:
DOS Files'SP50.MS4 Date: _/_/_
Run Dates November 5, 1996.
By:-
Run Time 4:13 p.m.-Tuesday Checked Duration:.0:00:36
. Case Titles <Monem GE;OMETRY 13 - Rectangular Volume centimeters feet and inches I
Dose point coordinate X:
1524.0 50.0
.0 Dose point coordina'te Ya 1524.0 50.0
.0 Dose, point coordinate En 10.91104
'O.0 4.3 l
Rectangular volume width :
21.02360 0.0 9.6
-l Rectangular volume length:
426.72 14.0
.0 Rectangular volume height:
21.87360 0.0 8.6 Shield 1:
15.24 0.0 6.0 Air Gaps 1002.04 35.0 6.0 Source Volume 203235, cm*3 7.17715 cu ft.
12402.2 cu in.
i MATERIAL DENSITIES (g/cm*3)-
7 Material source Shield 1 Air Gap Immersion 21 eld Slab
~
Shield i
Air 0.00122-
[
Iron-0.02 Uranium 5.65 Water 0.59 1.0 1.0 l
L Eirconium 0.66 l
BUIIEUP 6
Method: Balldup Factor Tables
[
The material reference is Immersion INTEGRATION PARAMETERS Quadrature Order f
I Direction 10 Y Direction 20 f
2 Direction 20 i
i SOURCE NUCLIDES i
Nuclide curies pCi/ca"3 Nuclide curies pC1/cm*3 Ba-137m 2.6635e+004 1.3106e+005 Ba-140 1.5452e+005 7.6020e+005 I
Ce-144 3.9611e+005 1.9490e+006 Cs-134 7.0167e+003 3.4525e+004 I'
Cs-135 2.2276e-007 1.0961e-006 Cs-136 1.0372e+003 5.1032e+001 Cs-137 2.8156e+004 1.3854e+005 I-129 1.0200e-002 5.0108e-002 1-131 4.6695e+004 2.2976e+005 I-133 1.3573e-004 6.6736e-004 Fr-85 2.9768e+003 1.4647e+004 La-140 1.7730e+005 8.7455e+005 Mo-99 7.6618e+002 3.7699e+003 Pr-144 3.9612e+005 1.9491e+006 Pr-144m 5.6644e+003-2.7071e+004 Rh-106 1.5074e+005 7.4168e+005 l
Sa-106 1.5074e+005 7 4168ee005 Sr-89 3.5063e+005 1.7252e+006 90 2.2463e+004 1.1053e+005 Sr-91 2.7891e-016 1.3723e'015 m
m--
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e.
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~,.. -,. _, -.., -. - - -...,.. -..,
......,_,,_m,
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,m.
m
.,,, m
Ye-9) 1.61273-C02 1.08'Oe-EC2 Tc-99m 7.45;42742 3.C753MC 03
- ~
Ke-131n 1.6623;+L13 8.17922+033 XJ-133 2.2489e+E4 1.106 6 W.E5 Xe-133m 3.4762e+000 1.7104e+001 Xe-135 7.3536e-018 3.6183e-017 Y-90 2.2453e+004 1.1040e+005 Y-91 3.9936e+005 1.9650e+006 Y-91m 1.7539e-016 8.6299e-016 e
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2
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- 2
- DOS File: SF50.MS4 Run Date: November 5, 1995 Run Time: 4:13 p.m. Tuesday Title
- < Nones
.................==....... RESULTS.....===................===
Energy
' Activity Energy Fluence Rate Exposure Rate in Air (Mev)
(photons /sec )
(Mev/sq cm/sec)
(mR/hr)
No Buildup Mith Buildup No Buildup With Buildup 0.1 1.600e+013 8.927e-003 1.416e+000 1.366e-005 2.166e-003 0.15 2.056e+015 2.204e+000 2.555e+002 3.63De-003 4.20se-001 0.2 4.065e+013 2.075e-001 1.440e+001 3.662e-004 2.556e-002
- 0.3 1.777e+015 6.761e+001 2.549e+003 1.282e-001 4.835e+000 0.4 1.095e+015 2.749e+002 6.756e+003 5.356e-001 1.316e+001 0.5 5.623e+015 2.144e+003 3.875e+004 4.207e+000 7.605e+001 0.6 2.134e+015 1.721e+003 2.409e+004 3.360e+000 4.859e+001
- 0. 0 2.540e+015 6.353e+003 6.743e+004 1.200e+001 1.283e+002 1.0 9.316e+014 5.392e+003 4.555e+004 9.939e+000 0.397e+001 1.5 6.375e+015 1.475e+005 8.389e+005 2.4sle+002 1.411e+003 2.0 1.694e+014 8.815e+003 3.953e+004 1.363e+001 6.113e+001 3.0 2.342e+014 3.219e+004 1.090e+005 4.367e+001 1.470e+002 1DTAL:
2.380e+016 2.049e+005 1.174e+006
.3.3569+002 1.976e+003 5
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