|
|---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F9701999-10-14014 October 1999
Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections
ML20217E4301999-10-12012 October 1999
Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations
ML20211K1201999-08-30030 August 1999
Proposed Tech Specs,Adding New Specification That Addresses Use of Interim Provisions Upon Discovery of Unintended TS Action
ML20211M7341999-08-30030 August 1999
Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times
ML20211K1721999-08-30030 August 1999
Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves
ML20209B7731999-06-30030 June 1999
Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431
ML20196F2211999-06-24024 June 1999
Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters
ML20196G4701999-06-24024 June 1999
Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431
ML20196G7961999-06-22022 June 1999
Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators
ML20196G8071999-06-22022 June 1999
Revs to Technical Requirements Manual
ML20195E9841999-06-0707 June 1999
Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core
ML20206E1611999-04-29029 April 1999
Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance
ML20206E1391999-04-29029 April 1999
Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations
ML20204E8501999-03-21021 March 1999
Plant,Four Yr Simulator Test Rept for Period Ending 990321
ML20204H4081999-03-19019 March 1999
Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual
ML20207F7631999-03-0202 March 1999
Proposed Tech Specs Pages Re Application for Amends to Licenses DPR-77 & DPR-79,deleting Iseg from License Conditions
ML20207D6011999-02-26026 February 1999
Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM
ML20207D6331999-02-26026 February 1999
Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets
ML20199K6001999-01-15015 January 1999
Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection
ML20206S0131999-01-15015 January 1999
Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual
ML20195H6111998-11-16016 November 1998
Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting
ML20154H7251998-10-0808 October 1998
Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS
ML20238F3001998-08-27027 August 1998
Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs
ML20238F1091998-08-27027 August 1998
Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core
ML20209J1631998-08-0707 August 1998
Rev 41 to Sequoyah Nuclear Plant Odcm
ML20236G5961998-06-29029 June 1998
Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions
ML20249C6371998-06-26026 June 1998
Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05
ML20248F0051998-05-28028 May 1998
Proposed Tech Specs for Section 6, Administrative Controls Deletions
ML20217N3511998-04-30030 April 1998
Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4
ML20203J1681998-02-25025 February 1998
Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs
ML20202J7141998-02-13013 February 1998
Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves
ML20202J7651998-02-13013 February 1998
Technical Requirements Manual
ML20202J6961998-02-13013 February 1998
Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431)
ML20202J7601998-02-13013 February 1998
Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements
ML20198T4311998-01-21021 January 1998
Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization
ML20199F8231997-11-30030 November 1997
Cycle 9 Restart Physics Test Summary, for 971011-971130
ML20199K4571997-11-21021 November 1997
Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required
ML20211A3191997-09-17017 September 1997
Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps
ML20203B9731997-08-0505 August 1997
Rev 1 to RD-466, Test & Calculated Results Pressure Locking
ML20217J5581997-07-31031 July 1997
Cycle Restart Physics Test Summary, for Jul 1997
ML20210J1671997-04-30030 April 1997
Snp Unit 1 Cycle 8 Refueling Outage Mar-Apr 1997,Results of SG Tube ISI as Required by TS Section 4.4.5.5.b & Results of Alternate Plugging Criteria Implementation as Required by Commitment from TS License Condition 2C(9)(d)
ML20137T0871997-04-0909 April 1997
Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria
ML20137M8581997-04-0101 April 1997
Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits
ML20137C8421997-03-19019 March 1997
Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel
ML20136J0381997-03-13013 March 1997
Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks
ML20134P8631997-02-14014 February 1997
Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b
ML20134K9981997-02-0707 February 1997
Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs
ML20138F2581997-01-17017 January 1997
Rev 39 to Sequoyah Nuclear Plant Odcm
ML20134L9261996-11-0808 November 1996
Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable
ML20129D2661996-10-18018 October 1996
Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units
1999-08-30
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20196G8071999-06-22022 June 1999
Revs to Technical Requirements Manual
ML20209J1631998-08-0707 August 1998
Rev 41 to Sequoyah Nuclear Plant Odcm
ML20202J7651998-02-13013 February 1998
Technical Requirements Manual
ML20138F2581997-01-17017 January 1997
Rev 39 to Sequoyah Nuclear Plant Odcm
ML20134J9991996-09-23023 September 1996
Fuel Assembly Insp Program
ML20138F2531996-02-23023 February 1996
Rev 38 to Sequoyah Nuclear Plant Odcm
ML20108B4121995-11-0303 November 1995
Rev 37 to Sequoyah Nuclear Plant Odcm
ML20094Q2111995-10-30030 October 1995
Rev 1 to ASME ISI Pump Testing Program Basis Document
ML20094Q1971995-10-30030 October 1995
Rev 1 to SG Tubing ISI & Augmented Insps, Rev 1 to 0-SI-SXI-068-114.2
ML20094Q2301995-10-30030 October 1995
ASME ISI Valve Testing Program Basis Document, Rev 0
ML20094Q1931995-10-30030 October 1995
Rev 1 to ASME Sys Pressure Testing Program Basis Document
ML20094Q1761995-10-13013 October 1995
ASME Section XI Isi/Nde & Augmented Nondestructive Exam Programs, SSP-6.10,rev 2
ML20094Q1841995-10-13013 October 1995
ASME Section XI Isi/Nde Program Units 1 & 2, Rev 0 to 0-SI-DXI-000-114.2
ML20149L6811994-09-30030 September 1994
Concerns Resolution Program - Sequoyah Nuclear Plant
ML20063D6691994-01-24024 January 1994
Rev 4 to Sequoyah Nuclear Plant Restart Plan
ML20065Q6251993-10-13013 October 1993
Rev 31 to Sequoyah Nuclear Plant Odcm
ML20056F3181993-08-20020 August 1993
Rev 0 of Post-Restart Plan
ML20056G1841993-08-10010 August 1993
Rev 2 to Sequoyah Nuclear Plant Restart Plan
ML20044F3081993-05-20020 May 1993
Rev 0 to Sequoyah Nuclear Plant Restart Plan
ML20034F3191993-02-26026 February 1993
Rev 26 to Offsite Dose Calculation/Environ Monitoring Methodologies
ML18036B1961993-01-27027 January 1993
Rev 2 to Nuclear Power Training Procedure TRN-31, Fire Brigade Training.
ML20127P5461992-12-16016 December 1992
Rev 20 to Surveillance Instruction SI-114.1, ASME Section XI ISI Program,Unit 1
ML20127P6361992-12-16016 December 1992
Rev 19 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program,Unit 2
ML20114C8131992-04-17017 April 1992
Rev 27 to Odcm
ML20101F2011992-02-0808 February 1992
Rev 17 to Surveillance Instruction SI-114.1, ASME Section XI ISI Program Unit 1
ML20101F2081992-02-0808 February 1992
Rev 16 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program Unit 2
ML20034C7451990-03-14014 March 1990
Rev 24 to ODCM
ML20033F2631990-02-27027 February 1990
Rev 24 to Odcm
ML19332D2241989-09-22022 September 1989
Rev 23 to Odcm
ML20245H1421989-08-15015 August 1989
Rev 22 to Offsite Dose Calculation Manual Changes
ML20246H4861989-05-16016 May 1989
Rev 1 to Technical Instruction TI-115, Instructions for Sewage Mgt
ML20244E2521989-04-28028 April 1989
Rev 14 to Surveillance Instruction SI-114.2, ASME Section XI Inservice Insp Program
ML20246E7771989-04-25025 April 1989
Rev 14 to Surveillance Instruction SI-114.1, ASME Section XI Inservice Insp Program
ML20206D3421988-10-15015 October 1988
Rev 13 to Surveillance Instruction SI-114.2, Inservice Insp Program
ML20154J3221988-09-0909 September 1988
Procedure EA-OR-003-S, Sequoyah Nuclear Plant - Unit 1 Design Baseline & Verification Program,Supplemental Engineering Assurance Oversight Review Rept
ML20150F9291988-06-17017 June 1988
Diesel Generator Voltage Response Improvement Plan
ML20154L1421988-05-0909 May 1988
Rev 3 to Revised Sequoyah Nuclear Performance Plan
ML20153H3891988-03-30030 March 1988
Rev 19 to Sequoyah Nuclear Plant Offsite Dose Calculation Manual
ML20196G3301988-02-24024 February 1988
Limited Test Program for Determining Axial Load Capacity of Cast One-Hole Conduit Clamps
ML20147E9511988-01-21021 January 1988
Revised, Procedures Generation Package
ML20153H3851988-01-0505 January 1988
Rev 18 to Sequoyah Nuclear Plant Offsite Dose Calculation Manual
ML20147E5691987-12-17017 December 1987
Rev 4 to Special Maint Instruction SMI-0-317-61, Instrumentation Features Walkdown,Rework & Insp Instructions for CAR 87-014
ML20148L9741987-11-0404 November 1987
Instruction Change 2172,Rev 8 to Essential Instrumentation Operability Verification
ML20237C5451987-10-28028 October 1987
Rev 17 to Offsite Dose Calculation Manual
ML20236E6931987-10-17017 October 1987
Rev 2 to Engineering Organization & Operating Procedures, TVA Employee Concerns Special Program
ML20235X0651987-10-10010 October 1987
Rev 0 to Special Maint Instruction SMI-2-74-1, Repair of 2-FCV-74-2
ML20235X0551987-10-10010 October 1987
Rev 0 to Sys Operating Instruction SOI-74.2, Removal of RHR for Repair of 2-FCV-74-2
ML20245D0661987-09-15015 September 1987
Rev 4 to Surveillance Instruction SI-673, RCS Level Verification Using Sight Glass or Tygon Hose
ML20148M0661987-09-11011 September 1987
Rev 8 to SI-604, Essential Instrumentation Operability Verification
ML20245D0591987-08-29029 August 1987
Rev 40 to Sys Operating Instruction SOI-74.1, RHR Sys
1999-06-22
[Table view] |
Text
_ _ _ _ _ _.. _ _ - - - - - -
9
~
1 l
l OFFSITE DOSE CALCULATION MANUAL CHANGES O
8712210370 871215 PDR ADOCK 05000327 R
PDR
!N
4 9
e l
0FFSITE DOSE CALCULATION MANUAL CHANGES j
REVISION NO. 16 l
f I
5:
4 OFFSITE DOSE CALCULATION MANUAL REVISION 16 INSTRUCTIONS Replace the following pages of the Offsite Dose Calculation Manual with the enclosed pages.
The revised pages are identified by amendment number.
Remove Insert (front /back)
(front /back)
Effective Page Listing / Dates of Revisions EPL-1/EPL-2 13/14 13/14 15/ISa 15/15a Table 1.5 Table 1.5 All pages associated with the Process Control Program (PCP)
O O
_ _ - - _ _ - - - - - - - - - - - - ' ^ ' ~ ^ ~ ' ^ ~ ^ ~ ' ^ -
~ ^ ^ ~
SEQUOYAH NUCLEAR PLANT
/'~'N OFF5.TE DOSE CALCULATION MANUAL (ODCM)
\\
)
CONTROLLED COPY DISTRIBUTION I
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RIMS, MR AN 72A-C 1
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TO Distribution Center Clerk, LP 4S 1648-C FROM DATE
SUBJECT:
RECEIPT ACKNOWLEDGEMENT FOR OFFSITE DOSE CALCULATION MANU 1
REVISION 16 I have received the above referenced revision and have entered the revis in my controlled copy (les) of the Offsite Dose Calculation Manual in accordance with the instruction sheet provided.
subject revision have been removed and destroyed. Pages superseded by the Signature Offsite Dose Calculation Manual Copy Number (s)
I b.
f SEQUOYAH NUCLEAR PLANT OFFSITE DCSE CALCULATION MANUAL
- / ]
EFFECTIVE PAGE LISTING l
i.
f REVISION 16 l
'%s Page Revision TOC'l through TOC 2 Revision 15 1
Revision 6 2
Revision 14 3
Revision 12 4
Original 5
Revision 14 i
6 Revision 4 7
Revision 8 8 through 9 Revision 5 10 Revision 14 10a Revision 15 11 Revision 13 12 Revision 12 13 Revision 14 14 through 15a Revision 16 16 Revision 13 16a Revision 8 Table 1.1 (Page 1)
Revision 12 i
Table 1.1 (Page 2)
Revision 15 Table 1.2 (2 pages)
Original p
Table 1.3 (8 pages)
Revision 4 Table 1.4 Revision 12 Table 1.4A (removed from document)
Revision 9 Table 1.5 Revision 16 Tables 1.6 and 1.7 Revision 5 Table 1.8 (2 pages)
Original Figures 1.1 and 1.2 Original Figure 1.3 Revision 3 17 Original 18 Revision 15 19 Revision 15 20 Revision 6 21 through 23 Revision 15 24 through 25 Revision 10
[
26 through 29 Revision 8 Table 2.1 (3 pages)
Revision 7 Table 2.2 Revision 5 Table 2.3 (3 pages)
Revision 10 Table 2.4 a-c Revision 5 30 Revision 13 30a Revision 15 Table 3.1.-1 (5 pages)
Revision 13 Table 3.1-2 Revision 15 Table 3.1-3 Revision 13 Table 3.2-1 (3 pages)
Revision 13 Figure 3.1-1 through 3.1-5 Revision 13 Figure 3.1-6 Revision 15 Figure 3.1-7 l
\\
Revision 14 EPL-1
I l
A O
SEQUOYAH NUCLEAR PLANT l
OFFSITE DOSE CALCULATION MANUAL DATES OF REVISIONS Original ODCM 02/29/80*
Revision 1 04/15/80**
Revision 2 10/07/80**
Revision 3 11/03/80, 02/10/81 04/08/81, 06/04/81**
Revision 4 11/22/82 (10/22/81, 11/28/81, 04/29/82**)
Revision 5 10/21/82**
Revision 6 01/20/83**
Revision 7 03/23/83**
Revision 8 12/16/83**
~
Revision 9 03/07/84**
Revision 10 04/24/84**
Revision 11 08/21/84**
Revision 12 02/19/85**
Revision 13 12/02/85 Revision 14 04/14/86 I
Revision 15 11/05/86***
Revision l' 01/16/87**
O O
- Low Power license for Sequoyah unit 1
- Date approved by RARC Chairman Revision 16 i
Step 2 r'~'N This methodology is to be used if the calculations in Step 1 yield doses
(
)
that exceed 50 percent of the applicable limits.
%.)
Equations and assumptions for calculating doses to air from releases of noble gases are as follows:
Assumptions 1.
Doses to be calculated are gamma and beta air doses.
2.
Doseistobeevaluatedatthenearestlandsiteboundarypointineachl14 sector.
Historical onsite meteorological data from the period 3.
1972-1975 will be used.
4 All measured radionuclides releases are considered.
5.
A semi-infinite cloud model is used.
6.
Radioactive decay is considered.
7.
Building wake effects on effluent dispersion are considered.
B.
Dose factors are calculated using data from TVA's radionuclides library.
/m)
Equations
\\
)
'^~
Equations for calculating air concentration, I, is the same as in Section 1.1.1, step 1, part A.
Air concentrations are calculated for the site boundary in each sector.
For determinin5 the gamma dose to air Dyn = t IniDFyg (1.16) m i
where:
Dyn = gamma dose to air for sector n, mrad.
Kni = nir concentration of radionuclides i in sector n, pCi/m3 DFyia gamma-to-air dose factor for radionuclides i, mrad /yr per pCi/m3 (Table 1.5).
t
= time period considered, yr m
/N 1
\\
)
Revision 14 i
\\,_,/ l e
F Yp For ' determining the beta doce to air:
r~
g%
DBn"tm Xni DFB '
(1.17) i x/
where:
DBn beta dose to air for sector n, mead.
a xi air concentration of radionuclides i in sector n, pCi/m3 a
n DFB[ = beta to air dose factor for radionuclido 1, mead /yr per pCi/m3 t
= time period considered, yr m
The sector having the highest total dose is then uend to check compliance with specification 3.11.2.2.
1.2.2 lodines. Particulate, and Tritium Step 1 Doses will be calculated using the methodology described in this step.
If 50 percent of the applicable limits are exceeded, step 2 will be performed.
Equations and assumptions for calculating doser from releases of iodines, particulate, and tritium are as follows:
l R16 Accumptions 1.
Doses are to be calculated for the infant thyroid from allk ingestion and for the child bone and teen g.i. tract from vegetable ingestion.
2.
Real cow locations are considered for the milk pathway and nearest resident-locations with home-use gardens are considered for the vegetable pathway.
3.
The highest annual-average X/Q and D/Q based on 1972-1975 meteorological data for ground level releases will be used for ingestion pathway doses.
4.
No credit is taken for radioactive decay.
5.
Releases of H-3, 1-131, and I-133 are considered for the milk pathway.
H-3, Sr-89, Sr-90, Cs-134, and Cs-137 releases are considered for the R16 vegetable pathway to the child bone.
H-3, Co-58, and Co-60 releases are considered for the vegetable pathway to the teen 8.i. tract.
6.
The calculations extrapolate doses assuming that only 90 percent of the f
total dose was contributed.
J 7.
The cow is assumed to graze on pasture grass for the whole year. Revision 16 i
Equations For determining the thyroid dose from milk ingestion:
I(Q DF )
D/Q x 106
+ (Q DF )X#9 i i T T DTH = i (1.18)
(0.9) x 3.15 x 107 where:
DTH = thyroid dose from H-3, 1-131, and 1-133, mrem.
Qi monthly release of iodine nuclide i, Ci.
=
QT m nthly release of H-3, Ci
=
DF nuclide i milk ingestion dose factor to infant, 7.24 x 1022
=
i mrem /yr per pCi/m -s for 1-131 and 1.52 x 1020 2
mrem /yr per pCi/m2-s for 1-133.*
DFT=
H-3 milk ingestion dose factor, 3.53 x 10' mrem /yr per pCi/cc.*
D/Q = relative deposition rate, 2.96 x 10-'m 2 x/Q relative air concentration, 1.76 x 10-6 s/m *
=
a R16 0.9 =
fraction of dose expected to be contributed by I-131 and I-133
>( _,/
3.15 x 107 s/yr.
=
10' = pCi/Ci Equation 1.18 then reduces to:
DTH = 1.04x10 2o I Qi DF1 + 2.19 x 10
For determining the bone dose from vegetable ingestion:
E(Q DF ) D/Q 106 +
i i Q DFTX/Q (l*19)
T DBC = i i
7 3.15 x 10 (0.9) where:
DBC = bone dose to child, mrem.
Qi = monthly release of Sr or Cs nuclido 1, Ci.
QT = monthly release of H-3, Ci DFi = Vegetable ingestion dose factor to child, 2.25 x 1011, 1.36 x 1013, 1.59 x 1011, and 2.58 x 1011 mrem /yr per pCi/m2-s for Sr-89, Sr-90, Cs-134, and Cs-137,
~5 respectively.*
i 1 Revision 16 t
L_____.__
DFT = vegetable ingestion dose factor for H-3, 4.53 x 10' arem/yr per pCi/cc.*
[
D/Q =.relativo deposition rate, 7.10x10-*m-2 x/Q = relative air concentration, 2.98 x 10-* s/m8 3.15x107 = s/yr.
10' = pCi/Ci.
j 0.9 = fraction of total bone dose expected to be contributed by
)
H-3, Sr-89, Sr-90, Cs-134, and Cs-137.
Equation 1.19 then reduces to j
)
DBC = 2.50 x 10-2o0 1 Q1 DFt + 4.76 x 10-* QT i
For determining the gastrointestinal (g.1.) tract dose from vegetable
{
ingestion:
E(Q DF ) D/Q. 106 + (Q DF ) x/Q (1.20) t t T T i
DGI T
(0.9) 3,15 x 107 i
where:
DGIT
= teen s.1 tract dose from H-3, Co-58, and Co-60, mrom
\\
Qi = monthly release of cobalt nuclide i, C1.
QT = monthly release of H-3, C1.
DFi = Vegetable ingestion dose factor for the teen g.i. tract, 3.87 x 10' mrem /yr per pC1/m -s for Co-58 and 3.31 x 1020 2
mrem /yr per pCi/m -s for Co-60.*
a DFT = vegetable ingestion dose factor for H-3, 2.92 x 10' mrem /yr per pCi/cc*.
D/Q = relative deposition rate, 7.10 x 10-' m-2
/
=
KQ relative air concentration, 2.98 x 10-5 s/m,
s 3.15 x 107 s/yr
=
105 pCi/Ci
=
0.9 = fraction of total g.i. tract dose expected to be contributed by H-3, Co-58, and Co-60 Equation 1.20 then reduces to DGI T 2.50 x 10-20 E
(Q Drt) + 3.07 x 10-* Q
=
t T
i
-15a-Revision 16
.I 6
TABLE 1.5
's '
DOSE FACTORS
- FOR SUBMERSION IN NOBI.E CASES R16 DFBI DF 2 7
DFSI 2
DFg Kr-85m 1.17(+3)3 g,21(#3)
- 1.46(+3) 3.86(+3)
Kr-85 1.61(+1) 1.69(+1) 1.34(+3) 3.83(+3)
Kr-87 5.92(+3) 6.05(+3) 9.73(+3) 2.01(+4)
Kr-88 1.47(+4) 1.50(+4) 2.37(+3) 5.72(+3)
Kr-88+D 2.02(+4) 3.72(&4)
~
Kr-89 1.66(+4) 1.59(+4) 1.01(+4) 1.88(&4)
Xe-131m 9.15(+1) 1.53(+2)
- 4. 76(+2) 2.18(+3)
Xe-133m 2.51(+2) 3.17(+2) 9.94(+2) 2.90(+3)
Xe-133 2.94(+2) 3.46(+2) 3.06(+2) 2.06(+3)
Xc-135m 3.12(+3) 3.30(+3) 7.11(+2) 1.45(+3)
[
Xe-135 1.81(+3) 1.88(+3) 1.86(+3) 4.84(+3)
\\
Xe-137 1.42(+3) 1.48(+3) 1.22(+4) 2.50(+4)
Xe-138 8.83(+3) 9.00(+3) 4.13(+3) 9.25(+3)
Xe-138+D 2.65(+4) 2.81(+4)
Ar-41 8.84(+3) 9.76(+3) 2.69(+3) 5.54(+3) 4 1.
meem/yr per pCi/m8 2.
mead /yr pee pCi/m8 3.
1.17(+3) = 1.17 x 108
- Based on methodology presented in " Meteorology and Atomic Energy,"
R16 D. H. Slade, Chapters 7-4 and 7-5, 1968.
Revision 16 i
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