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{{#Wiki_filter:ANALYSIS OF HABITABILITY OF THE SHEARON HARRIS NUCLEAR POWER PLANT EMERGENCY OPERATIONS FACILITY Prepared for CAROLINA POVYER 8 LIGHT COMPANY EEASCO EBASCO SERVICES INCORPORATED 8311020118 831025 PDR ADOCK 05000400 F PDR | {{#Wiki_filter:ANALYSIS OF HABITABILITY OF THE SHEARON HARRIS NUCLEAR POWER PLANT EMERGENCY OPERATIONS FACILITY Prepared for CAROLINA POVYER 8 LIGHT COMPANY EEASCO EBASCO SERVICES INCORPORATED SEPTEMBER 1983 8311020118 831025 PDR ADOCK 05000400 F PDR | ||
TABLE OF CONTENTS | TABLE OF CONTENTS 1 .0 INTRODUCTION 2.0 EXPOSURES TO RADIONUCLIDES AIRBORNE INSIDE FACILITY 2.1 Methodology 2.2 Assumptions and Parameters 2.3 Results 3.0 PROTECTION FACTOR ESTIMATE 3.1 Methodology 3.2 Assumptions and Parameters 3.3 Results | ||
== | ==4.0 CONCLUSION== | ||
S PROTECTION FACTOR ESTIMATOR SOLUTION FORM REFERENCES APPENDIX A | |||
LIST OF TABLES TITLE 30-Day Inhalation and Submersion doses at the Emergency Operations Facility Emergency Operations Facility Protection Factors for Outdoor Contamination | |||
LIST OF FIGURES TITLE FIGURE NO. | |||
Ventilation System of the SHNPP Emergency Operations Facility Emergency Operations Facility Emergency Operations Facility Building Key | |||
1 . 0 INTROOUCT ION The Emergency Operations Facility (EOF) will be operated by Carolina Power and Light Company for the management of overall licensee emergency response, coordination of radiological and environmental assessment, development of recommendations for public protective actions and coordination of emergency response activities with Federal, State and Local supporting agencies. The EOF for the Shearon Harris Nuclear Power Plant is located 3,429 meters from the plant site. | |||
2.0 EXPOSURES TO RADIONUCLIDES AIRBORNE INSIDE FACILITY The EOF ventilation system is designed to draw in 720 CFN outside air.In the event of an incident at SHNPP, the outside.air whether drawn in by the air handling unit or injected into the system by the emergency fan serves to pressurize the system and will leave the system by enfiltration.(See Figure 1)The 30-day thyroid, whole body and skin doses to individuals inside the EOF were evaluated for a design basis loss-of-.coolant accident (LOCA).1 2.1~Nh 2 1 A design basis LOCA provides the radionuclide release rate from the containment using the guidance given in Regulatory Guide 1.4.Atmospheric dispersion factors at the EOF were calculated in accordance with Regulatory Guide 1.145.The detailed description of the activity release and dose evaluation models are given in Appendix 15.0.A of the SHNPP FSAR | The Nuclear Regulatory Commission has provided guidance on acceptable design features for EOFs. Supplement 1 to NUREG-0737 indicates that an EOF should have a protection factor of 5, ventilation isolation and HEPA filters. Habitability requirements are only for the part of the EOF in which dose assessments, communications and decision making take place. | ||
This habitability study consists of an assessment of exposures to individuals in the EOF from radionuclides airborne inside the facility and an analysis of the building protection factors for outside contamination. | |||
2.0 EXPOSURES TO RADIONUCLIDES AIRBORNE INSIDE FACILITY The EOF ventilation system is designed to draw in 720 CFN outside air. In the event of an incident at SHNPP, the outside.air whether drawn in by the air handling unit or injected into the system by the emergency fan serves to pressurize the system and will leave the system by enfiltration. (See Figure 1) | |||
The 30-day thyroid, whole body and skin doses to individuals inside the EOF were evaluated for a design basis loss-of-.coolant accident (LOCA). | |||
1 2.1 ~Nh 2 1 A design basis LOCA provides the radionuclide release rate from the containment using the guidance given in Regulatory Guide 1.4. Atmospheric dispersion factors at the EOF were calculated in accordance with Regulatory Guide 1.145. The detailed description of the activity release and dose evaluation models are given in Appendix 15.0.A of the SHNPP FSAR. | |||
2.2 Assum tions and Parameters The following lists the assumptions and parameters used in the analysis of inhalation and submersion doses: | |||
: 1) design basis assumptions presented in FSAR 15.6.5.4.1 are applied, | |||
: 2) accident duration is assumed to be 30 days, | |||
: 3) the net free volume of EOF is estimated to be 31,716 ft 3 3 (898 M ), | |||
allowing 105 of the volume for equipment and furniture. This volume represents the first floor of the EOF where management and coordination of emergency activities, dose assessment, communications and decision making takes place (See Figure 2), | |||
4) | |||
: 5) EOF atmospheric dispersion factors are: | |||
Time Period 0- 8 hrs | |||
//// | |||
1.1 | |||
'/ | |||
radionuclides are uniformly distributed throughout the EOF net free volume, X 10 3 | |||
8 - 24 hrs 8.1 X 10 1 - 4 days 2.9 X 10 4 - 30 days 7.1 X 10 | |||
: 6) occupancy of the EOF is based on the following: | |||
Time Period Occu anc Factor 0 - 24 hours 1 ~ 0 1 - 4 days 0.6 4 - 30 days 0.4 | |||
: 7) a finite cloud correction is used, | |||
: 8) filter efficiency of EOF emergency cleanup system for iodine is 99%, | |||
: 9) a breathing rate of, the occupants of 3.47 X 10 cubic meters per second for the duration of the accident, | |||
: 10) the EOF air intake flow rate is 720 CFM (with no recirculation), and ll) the assumed unfiltered in-leakage into the pressurized EOF is 3 CFM with air locks as a result of opening and closing of doors. | |||
2.3 Results The doses to an EOF occupant are presented in Table 1. These doses are well within the GDC-19 limit of 5 rems to the whole body and the corresponding SRP 6.4 limits of 30 rem to the skin and thyroid. | |||
PFE SOLUTION FORM SHNPP-EMERGENCY OPERATIONS FACILITY- | 3.0 PROTECTION FACTORS ESTIMATE An individual in -the EOF would also receive exposure from outdoor contamination which is 1) airborne and 2) deposited on the ground and roof. Building protection factors have been calculated separately for each type of contamination. | ||
~MM d 1 The models used in the calculation of protection factors for outdoor airborne contamination are included in Appendix- A. Methodology included in Reference 1 was used in the calculation of protection factors for outdoor ground and roof contamination. | |||
Chart 1~01 8 Chart 1 | The analysis has been performed by dividing the first and second floors into six azimuthal sectors as indicated in Figure 2. Figure 3 indicates that the contribution to exposure through walls in sectors E and F is small due to presence of the building complex and therefore has been ignored in the analysis. The parameters used in the evaluation and results for outdoor surface contamination are included on the PFE solution forms. The chart numbers refer to those included in Reference l. | ||
3.2 Assum tions and Parameters The following assumptions and parameters are used in the evaluation of the protection factors for the EOF: | |||
: 1) interior walls of the building, in which the EOF is located, are 8.0 inches thick. | |||
: 2) walls enclosing the EOF are 8.0 inches thick. | |||
: 3) each floor thickness is 8.0 inches. | |||
: 4) the ceiling heights of the first floor, second floor and mezzanine are 9.7 ft., 8.2 ft. and 8 ft., respectively. | |||
: 5) density of concrete is 140 lbs/cu. ft. | |||
3.3 Results Protection factors calculated for the first and second floors of the EOF are included in Table-2. The values for both outdoor surface and airborne contaminations are above 5 and hence exceed the requirements of NUREG-0737. | |||
==4.0 CONCLUSION== | |||
S The analysis of the inhalation and submersion (ski n, whole body and thyroid) doses to an EOF occupant has shown that the 30-day exposures will be well within the GDC-19 and SRP 5.4 limits. Consequently, the EOF location and design of its emergency air filtration system have been demonstrated to be appropriately chosen to ensure more than adequate protection of personnel during relatively long periods of occupancy following even the most severe design-basis accident. | |||
In addition, the structural aspects of the EOF have been analyzed with regards to the protection level it affords against outside airborne and deposited radioactive contaminants. The resultant protection factors, prove that there is sufficient shielding between the critical areas of the EOF to be occupied and the outside contamination carried in and deposited by a radioactive plume. | |||
4 | |||
TABLE 1 30-Day Inhalation and Submersion Doses At The Emergency Operations Facility (Rem) | |||
Dose Whole Body 0. 02 Skin 0.60 Thyroid 1.60 | |||
TABLE 2 Emergency Operations Facility Protection Factors for Outdoor Contamination Protection Factors Radioactive P ume Surface Contamination First Floor 18. 5 50 Second Floor 5.1 33 | |||
f PFE SOLUTION FORM SHNPP - EMERGENCY OPERATIONS FACILITY - FIRST FLOOR SECTOR OR BUILDINGSIDE Parameters Factor A B C D Chart 0 66 40 70 70 W = 52.7 ROOF MASS THICKNESS: | |||
90.5 X',(A,ZX ) = Chart 1 4769 C,(A,ZX, ) = . 0018 Chart 1 22.83 3 | |||
H WALL MASS THICKNESS: | |||
P X',(X,,A,) = 93.6 93.6 93.6 93.6 Chart 2 WC = Xi = | |||
93.6 93.6 DX (HW,) = Chart 3 93.6 zX (A)= | |||
X, = | |||
A B C 0 0,93.6,93.6,0 ~X (E )= | |||
X 187.2 aX (X,)= 6.7 6.7 6.7 6.7 WALL HEIGH X' 100.3 193.9 193.9 100.3 X = | |||
C X, WALL-BY-WALLANALYSIS: | |||
X' Leave out 100.3 193.9 193. 9 100.3 DX (A) 32 48 130 42.5 C'X',r) 012 0012 Chart 8 E | |||
0005 0098 h | |||
PROTECTION FACTOR: | |||
.009 .0005 . 0004 .008 .018 RF=C +C .02 PF= | |||
50 | |||
PFE SOLUTION FORM Project SHNPP - EMERGENCY OPERATIONS FACILITY - SECOND FLOOR SECTOR OR BUILDING SIDE Parameters Factor A B Chart W = 52.7 66 40 70 70 ROOF MASS THICKNESS: | |||
90.5 X',(A,ZX = | |||
) Chart 1 A = C (AZX )= ~ 01 8 Chart 1 13.17 H 12. 66 WALL MASS THICKNESS: | |||
A0 = X',(X,,A ) = 93.6 93.6 93.6 93.6 Chart 2 WC = XI = 0 93.6 93.6 X0 = 93.6 AX (HW,) = 17 17 17 17 Chart 3 X = 93.6 aX (A) = | |||
A B C D 93.6,0 aX (E)= | |||
X =0 93.6 aX (X,)= 9.7 Mall Heigh X = 9.7 9.7 9.7 Rul X' 120.3 13.9 213. 9 120. 3 X = | |||
XC WALL-BY-WALLANALYSIS: | |||
X'l/ Leave out 120.3 213.9 213.9 120.3 DX (A) 32 48 130 42.5 C'X',r) .008 .0008 .00033 .005 Chart 8 E | |||
=Y= | |||
h PROTECTION FACTOR: | |||
I C (X'I) = .006 .0004 .0003 .004 0.11 RF =C +C .03 33 | |||
P F E SOLUTION FORM LIST OF SYMBOLS 6 Azimuthal Angle, W Width, ft L Length, ft A The Plan Area of the Building or the Contributing Roof Area, sq ft Z Distance from Detector Location to Roof, ft H Height of Detector Location Above Ground Contamination, ft A Percent of Apertures in Exterior Wall. | |||
P W | |||
c Width of Ground Contaminated Field, ft X Total Mass Thickness between a Detector Location and Roof, psf Xf + Xr X Exterior Wall Mass Thi,ckness, psf X- = | |||
l Interior Parti ti on Mass Thi ckness, ps f Floor Mass Thickness, psf X Roof Mass Thickness, psf X Basement Ceiling Mass Thickness, psf The Exposed Portion of a Partially Exposed Basement Wall, ft h The Ceiling Height of an Exposed Basement, ft E | |||
x y/h the Exposed Fraction of a Basement Wall X' Adjusted Wall Mass Thickness (Corrected for Apertures) psf C Total Overhead Contribution X' Equivalent Overhead Mass Thickness, psf hX= An Incremental Increase (or Decrease) in the Exterior Wall Mass Thickness Used to Equate the Real Building to an Equivalent Building, psf X' Equivalent Wall Mass Thickness, psf C Total Ground Contribution g | |||
PF = Protection Factor | |||
==References:== | ==References:== | ||
: 1. "Shelter Design And Analysis", TR-20 (Vol. 2), February 1976, Defense Civil Preparedness Agency. | |||
: 2. Meteorology and Atomic Energy, 1968. U.S. Atomic Energy Commission. | |||
: 3. "The Effectiveness of Sheltering as a Protective Action Against Nuclear Accidents Involving Gaseous Releases", Protective Action Evaluation Part 1, April 1978. George H. Anno and Michael A. Dore, U. S. Environmental Protection Agency. | |||
IG a<~te T~ptd(C<q WQA1y~g C | |||
70" | |||
~CV g, .,~rjc c 700 ~r L~ gg~g~s~<.m. | |||
~O MP4414 g Q Q rj~~ | |||
A Qlf ~g IVY | |||
~l I KP~ p>A V>M~g )gal L g~)Jg@ | |||
FIGURE 2 EMERGENCY OPERATIONS FACILITY | |||
Bill I.I) lNG Vl.Y n | |||
I lGURl:. 3 CVCnGrNCV OVrnnT>ONS rnCil.<TV BUtl.OING KFY | |||
'J APPENDIX A PROTECTION FACTOR CALCULATION MODELS Protection Factors (PF) for the buildings due to outdoor ground and roof contaminations were calculated using the methodology presented in Ref. 1, which should be referred to for this purpose. | |||
'F for outdoor plume were calculated using the models presented as follows: | |||
a | A structure provides protection by the geometrical effect of limiting the distance of approach of the cloud and by shielding afforded by walls. | ||
PF is obtained by assuming the plume to be hemispherical in shape and applying equation 7.77 of Ref. 2 . | |||
PF = (1+Kx.Ux.W) exp (-Ux.W) | |||
'K (1+u.rl) | |||
X | |||
( [exp (-v.e) exp (-u.rl) exp (-u.rl) + K (1+u.a) exp (-u.a)j X t.l-exp (-u.rl) K (1+u.rl) | |||
, exp (-u.rl) + Kj Where, Ux = total absorption coefficient for building material; crr2/g or cm-1 u = total absorption coefficient for air; cm /g or cm u = Ua + Us | |||
.Ua = energy absorption coefficient; cm /g or cm Us = scattering absorption coefficient; cm /g or cm 1 W = thickness of shield afforded by building material; g/cm2 Kx = component in the buildup factor = (Ux - Ua)/Ua | |||
K, | |||
~= component in the | |||
~ | |||
buildup factor for air | |||
= 1.25 9 1.0 HeV.* | |||
a = effective building radius, cm V x 3 | |||
~1F V = volume of building; cm3 rl = radioactive plume radius, cm Assuming the plume size is very large and substituting infinity for rl in the above equation; PF = (1+Kx.Ux.W) exp (-Ux.W) X t]+K (1+u.a)j exp (-u.a) 1+K B (i) | |||
The term represented by 8 expresses the PF from the geometrical con-siderations, whereas that represented by A expresses the shielding factor. | |||
The shielding provided through the roof is different from that provided by walls. Also, walls have windows and doors which do not provide any protection. Therefore, the above equation has been modified as follows: | |||
PF = B X Fw (Ap + (1-Ap) x AwI + Fr x Ar Where, Fr**= fraction of garrrna radiation through roof Fw = fraction of gamma radiation through walls Ap = fraction representing aperture (windows, doors, etc.) | |||
in walls. | |||
1.0 MEV gamma energy used in the calculation is close to the value in-dicated in Ref.3 . | |||
** Fr is obtained by using Figure 7.33 of Ref- 2 or hand calculation. | |||
Aw = shielding factor for walls Ar = shielding factor for roof A-3}} | |||
Aw=shielding factor for walls Ar=shielding factor for roof A-3}} |
Latest revision as of 18:36, 3 February 2020
ML18018B429 | |
Person / Time | |
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Site: | Harris |
Issue date: | 09/30/1983 |
From: | EBASCO SERVICES, INC. |
To: | |
Shared Package | |
ML18018B428 | List: |
References | |
NUDOCS 8311020118 | |
Download: ML18018B429 (26) | |
Text
ANALYSIS OF HABITABILITY OF THE SHEARON HARRIS NUCLEAR POWER PLANT EMERGENCY OPERATIONS FACILITY Prepared for CAROLINA POVYER 8 LIGHT COMPANY EEASCO EBASCO SERVICES INCORPORATED SEPTEMBER 1983 8311020118 831025 PDR ADOCK 05000400 F PDR
TABLE OF CONTENTS 1 .0 INTRODUCTION 2.0 EXPOSURES TO RADIONUCLIDES AIRBORNE INSIDE FACILITY 2.1 Methodology 2.2 Assumptions and Parameters 2.3 Results 3.0 PROTECTION FACTOR ESTIMATE 3.1 Methodology 3.2 Assumptions and Parameters 3.3 Results
4.0 CONCLUSION
S PROTECTION FACTOR ESTIMATOR SOLUTION FORM REFERENCES APPENDIX A
LIST OF TABLES TITLE 30-Day Inhalation and Submersion doses at the Emergency Operations Facility Emergency Operations Facility Protection Factors for Outdoor Contamination
LIST OF FIGURES TITLE FIGURE NO.
Ventilation System of the SHNPP Emergency Operations Facility Emergency Operations Facility Emergency Operations Facility Building Key
1 . 0 INTROOUCT ION The Emergency Operations Facility (EOF) will be operated by Carolina Power and Light Company for the management of overall licensee emergency response, coordination of radiological and environmental assessment, development of recommendations for public protective actions and coordination of emergency response activities with Federal, State and Local supporting agencies. The EOF for the Shearon Harris Nuclear Power Plant is located 3,429 meters from the plant site.
The Nuclear Regulatory Commission has provided guidance on acceptable design features for EOFs. Supplement 1 to NUREG-0737 indicates that an EOF should have a protection factor of 5, ventilation isolation and HEPA filters. Habitability requirements are only for the part of the EOF in which dose assessments, communications and decision making take place.
This habitability study consists of an assessment of exposures to individuals in the EOF from radionuclides airborne inside the facility and an analysis of the building protection factors for outside contamination.
2.0 EXPOSURES TO RADIONUCLIDES AIRBORNE INSIDE FACILITY The EOF ventilation system is designed to draw in 720 CFN outside air. In the event of an incident at SHNPP, the outside.air whether drawn in by the air handling unit or injected into the system by the emergency fan serves to pressurize the system and will leave the system by enfiltration. (See Figure 1)
The 30-day thyroid, whole body and skin doses to individuals inside the EOF were evaluated for a design basis loss-of-.coolant accident (LOCA).
1 2.1 ~Nh 2 1 A design basis LOCA provides the radionuclide release rate from the containment using the guidance given in Regulatory Guide 1.4. Atmospheric dispersion factors at the EOF were calculated in accordance with Regulatory Guide 1.145. The detailed description of the activity release and dose evaluation models are given in Appendix 15.0.A of the SHNPP FSAR.
2.2 Assum tions and Parameters The following lists the assumptions and parameters used in the analysis of inhalation and submersion doses:
- 1) design basis assumptions presented in FSAR 15.6.5.4.1 are applied,
- 2) accident duration is assumed to be 30 days,
- 3) the net free volume of EOF is estimated to be 31,716 ft 3 3 (898 M ),
allowing 105 of the volume for equipment and furniture. This volume represents the first floor of the EOF where management and coordination of emergency activities, dose assessment, communications and decision making takes place (See Figure 2),
4)
- 5) EOF atmospheric dispersion factors are:
Time Period 0- 8 hrs
////
1.1
'/
radionuclides are uniformly distributed throughout the EOF net free volume, X 10 3
8 - 24 hrs 8.1 X 10 1 - 4 days 2.9 X 10 4 - 30 days 7.1 X 10
- 6) occupancy of the EOF is based on the following:
Time Period Occu anc Factor 0 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1 ~ 0 1 - 4 days 0.6 4 - 30 days 0.4
- 7) a finite cloud correction is used,
- 9) a breathing rate of, the occupants of 3.47 X 10 cubic meters per second for the duration of the accident,
- 10) the EOF air intake flow rate is 720 CFM (with no recirculation), and ll) the assumed unfiltered in-leakage into the pressurized EOF is 3 CFM with air locks as a result of opening and closing of doors.
2.3 Results The doses to an EOF occupant are presented in Table 1. These doses are well within the GDC-19 limit of 5 rems to the whole body and the corresponding SRP 6.4 limits of 30 rem to the skin and thyroid.
3.0 PROTECTION FACTORS ESTIMATE An individual in -the EOF would also receive exposure from outdoor contamination which is 1) airborne and 2) deposited on the ground and roof. Building protection factors have been calculated separately for each type of contamination.
~MM d 1 The models used in the calculation of protection factors for outdoor airborne contamination are included in Appendix- A. Methodology included in Reference 1 was used in the calculation of protection factors for outdoor ground and roof contamination.
The analysis has been performed by dividing the first and second floors into six azimuthal sectors as indicated in Figure 2. Figure 3 indicates that the contribution to exposure through walls in sectors E and F is small due to presence of the building complex and therefore has been ignored in the analysis. The parameters used in the evaluation and results for outdoor surface contamination are included on the PFE solution forms. The chart numbers refer to those included in Reference l.
3.2 Assum tions and Parameters The following assumptions and parameters are used in the evaluation of the protection factors for the EOF:
- 1) interior walls of the building, in which the EOF is located, are 8.0 inches thick.
- 2) walls enclosing the EOF are 8.0 inches thick.
- 3) each floor thickness is 8.0 inches.
- 4) the ceiling heights of the first floor, second floor and mezzanine are 9.7 ft., 8.2 ft. and 8 ft., respectively.
- 5) density of concrete is 140 lbs/cu. ft.
3.3 Results Protection factors calculated for the first and second floors of the EOF are included in Table-2. The values for both outdoor surface and airborne contaminations are above 5 and hence exceed the requirements of NUREG-0737.
4.0 CONCLUSION
S The analysis of the inhalation and submersion (ski n, whole body and thyroid) doses to an EOF occupant has shown that the 30-day exposures will be well within the GDC-19 and SRP 5.4 limits. Consequently, the EOF location and design of its emergency air filtration system have been demonstrated to be appropriately chosen to ensure more than adequate protection of personnel during relatively long periods of occupancy following even the most severe design-basis accident.
In addition, the structural aspects of the EOF have been analyzed with regards to the protection level it affords against outside airborne and deposited radioactive contaminants. The resultant protection factors, prove that there is sufficient shielding between the critical areas of the EOF to be occupied and the outside contamination carried in and deposited by a radioactive plume.
4
TABLE 1 30-Day Inhalation and Submersion Doses At The Emergency Operations Facility (Rem)
Dose Whole Body 0. 02 Skin 0.60 Thyroid 1.60
TABLE 2 Emergency Operations Facility Protection Factors for Outdoor Contamination Protection Factors Radioactive P ume Surface Contamination First Floor 18. 5 50 Second Floor 5.1 33
f PFE SOLUTION FORM SHNPP - EMERGENCY OPERATIONS FACILITY - FIRST FLOOR SECTOR OR BUILDINGSIDE Parameters Factor A B C D Chart 0 66 40 70 70 W = 52.7 ROOF MASS THICKNESS:
90.5 X',(A,ZX ) = Chart 1 4769 C,(A,ZX, ) = . 0018 Chart 1 22.83 3
H WALL MASS THICKNESS:
P X',(X,,A,) = 93.6 93.6 93.6 93.6 Chart 2 WC = Xi =
93.6 93.6 DX (HW,) = Chart 3 93.6 zX (A)=
X, =
A B C 0 0,93.6,93.6,0 ~X (E )=
X 187.2 aX (X,)= 6.7 6.7 6.7 6.7 WALL HEIGH X' 100.3 193.9 193.9 100.3 X =
C X, WALL-BY-WALLANALYSIS:
X' Leave out 100.3 193.9 193. 9 100.3 DX (A) 32 48 130 42.5 C'X',r) 012 0012 Chart 8 E
0005 0098 h
PROTECTION FACTOR:
.009 .0005 . 0004 .008 .018 RF=C +C .02 PF=
50
PFE SOLUTION FORM Project SHNPP - EMERGENCY OPERATIONS FACILITY - SECOND FLOOR SECTOR OR BUILDING SIDE Parameters Factor A B Chart W = 52.7 66 40 70 70 ROOF MASS THICKNESS:
90.5 X',(A,ZX =
) Chart 1 A = C (AZX )= ~ 01 8 Chart 1 13.17 H 12. 66 WALL MASS THICKNESS:
A0 = X',(X,,A ) = 93.6 93.6 93.6 93.6 Chart 2 WC = XI = 0 93.6 93.6 X0 = 93.6 AX (HW,) = 17 17 17 17 Chart 3 X = 93.6 aX (A) =
A B C D 93.6,0 aX (E)=
X =0 93.6 aX (X,)= 9.7 Mall Heigh X = 9.7 9.7 9.7 Rul X' 120.3 13.9 213. 9 120. 3 X =
XC WALL-BY-WALLANALYSIS:
X'l/ Leave out 120.3 213.9 213.9 120.3 DX (A) 32 48 130 42.5 C'X',r) .008 .0008 .00033 .005 Chart 8 E
Y
h PROTECTION FACTOR:
I C (X'I) = .006 .0004 .0003 .004 0.11 RF =C +C .03 33
P F E SOLUTION FORM LIST OF SYMBOLS 6 Azimuthal Angle, W Width, ft L Length, ft A The Plan Area of the Building or the Contributing Roof Area, sq ft Z Distance from Detector Location to Roof, ft H Height of Detector Location Above Ground Contamination, ft A Percent of Apertures in Exterior Wall.
P W
c Width of Ground Contaminated Field, ft X Total Mass Thickness between a Detector Location and Roof, psf Xf + Xr X Exterior Wall Mass Thi,ckness, psf X- =
l Interior Parti ti on Mass Thi ckness, ps f Floor Mass Thickness, psf X Roof Mass Thickness, psf X Basement Ceiling Mass Thickness, psf The Exposed Portion of a Partially Exposed Basement Wall, ft h The Ceiling Height of an Exposed Basement, ft E
x y/h the Exposed Fraction of a Basement Wall X' Adjusted Wall Mass Thickness (Corrected for Apertures) psf C Total Overhead Contribution X' Equivalent Overhead Mass Thickness, psf hX= An Incremental Increase (or Decrease) in the Exterior Wall Mass Thickness Used to Equate the Real Building to an Equivalent Building, psf X' Equivalent Wall Mass Thickness, psf C Total Ground Contribution g
PF = Protection Factor
References:
- 1. "Shelter Design And Analysis", TR-20 (Vol. 2), February 1976, Defense Civil Preparedness Agency.
- 2. Meteorology and Atomic Energy, 1968. U.S. Atomic Energy Commission.
- 3. "The Effectiveness of Sheltering as a Protective Action Against Nuclear Accidents Involving Gaseous Releases", Protective Action Evaluation Part 1, April 1978. George H. Anno and Michael A. Dore, U. S. Environmental Protection Agency.
IG a<~te T~ptd(C<q WQA1y~g C
70"
~CV g, .,~rjc c 700 ~r L~ gg~g~s~<.m.
~O MP4414 g Q Q rj~~
A Qlf ~g IVY
~l I KP~ p>A V>M~g )gal L g~)Jg@
FIGURE 2 EMERGENCY OPERATIONS FACILITY
Bill I.I) lNG Vl.Y n
I lGURl:. 3 CVCnGrNCV OVrnnT>ONS rnCil.<TV BUtl.OING KFY
'J APPENDIX A PROTECTION FACTOR CALCULATION MODELS Protection Factors (PF) for the buildings due to outdoor ground and roof contaminations were calculated using the methodology presented in Ref. 1, which should be referred to for this purpose.
'F for outdoor plume were calculated using the models presented as follows:
A structure provides protection by the geometrical effect of limiting the distance of approach of the cloud and by shielding afforded by walls.
PF is obtained by assuming the plume to be hemispherical in shape and applying equation 7.77 of Ref. 2 .
PF = (1+Kx.Ux.W) exp (-Ux.W)
'K (1+u.rl)
X
( [exp (-v.e) exp (-u.rl) exp (-u.rl) + K (1+u.a) exp (-u.a)j X t.l-exp (-u.rl) K (1+u.rl)
, exp (-u.rl) + Kj Where, Ux = total absorption coefficient for building material; crr2/g or cm-1 u = total absorption coefficient for air; cm /g or cm u = Ua + Us
.Ua = energy absorption coefficient; cm /g or cm Us = scattering absorption coefficient; cm /g or cm 1 W = thickness of shield afforded by building material; g/cm2 Kx = component in the buildup factor = (Ux - Ua)/Ua
K,
~= component in the
~
buildup factor for air
= 1.25 9 1.0 HeV.*
a = effective building radius, cm V x 3
~1F V = volume of building; cm3 rl = radioactive plume radius, cm Assuming the plume size is very large and substituting infinity for rl in the above equation; PF = (1+Kx.Ux.W) exp (-Ux.W) X t]+K (1+u.a)j exp (-u.a) 1+K B (i)
The term represented by 8 expresses the PF from the geometrical con-siderations, whereas that represented by A expresses the shielding factor.
The shielding provided through the roof is different from that provided by walls. Also, walls have windows and doors which do not provide any protection. Therefore, the above equation has been modified as follows:
PF = B X Fw (Ap + (1-Ap) x AwI + Fr x Ar Where, Fr**= fraction of garrrna radiation through roof Fw = fraction of gamma radiation through walls Ap = fraction representing aperture (windows, doors, etc.)
in walls.
1.0 MEV gamma energy used in the calculation is close to the value in-dicated in Ref.3 .
- Fr is obtained by using Figure 7.33 of Ref- 2 or hand calculation.
Aw = shielding factor for walls Ar = shielding factor for roof A-3