ML20217H621
| ML20217H621 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/15/1997 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20217H604 | List: |
| References | |
| PROC-971215, NUDOCS 9804300019 | |
| Download: ML20217H621 (159) | |
Text
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ATTACHMENT I OFFSITE DOSE CALCULATION MANUAL REVISION 21 l
9804300019 9804W PDR ADOCK 05000416 R
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OFFSITE DOSE CALCULATION MANUAL GRAND GULF NUCLEAR STATION-1 a
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i GRAND GULF, UNIT 1 Revision 21 - 12/97 J
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I Revision No.
21 Date 12/97 GRAND CULF NUCLEAR STATION OFFSITE DOSE CALCULATION MANUAL SAFETY RELATED l
EVALUATION' APPLICABILITY SAFETY EVALUATION ENVIRONMENTAL EVALUATION
[ pf APPLICABLE
[ ] APPLICABLE
{] NOT APPLICABLE
( C NOT APPLICABLE Reviewed / Approved:
Wh
/ 0. N.N Preparer Date Reviewed / Approved:
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Review Date
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- l$ ail Reviewed / Approved:
Chemistry %5jerintendent Date Reviewed / Approved:
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d k7 Mana r, Plant OperatiMs Date
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Feviewed/ Approved:
/ / 2-9 -N Chairman Plant Safety Review Conuittee Date l
Reviewed / Approved:
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General Menager,' Plant Qperations Date GRAND GULF, UNIT 1 i
Revision 21 - 12/97
INTRODUCTION The Offsite Dose Calculation Manual (ODCM) describes the methodology and parameters used in the calculation of offsite doses resulting from radioactive liquid and gaseous effluents, in the calculation of liquid and gaseous effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM also contains (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification (TS) 5.5.4, and Technical Requirement 7.6.3.2, (2) descriptions of the information that is included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by TS 5.6.2 and 5.6.3, (3) a list and graphical description of the specific sample locations for the Radiological Environmental Monitoring Program, and (4) diagrams of the liquid and gaseous radwaste treatment systems.
ODCM Revision 21 incorporates the following changes:
Modifies Table 6.3.10-1.2.d:
Containment Ventilation Monitoring System Effluent System Flow Rate Measuring Device to list devices used for each mod 3 of ventilation system operation.
Removes references to the Reverse Osmosis TreatDent System from the Liquid Radwaste Treatment System.
Deletes Table 2.2-lb Pathway Dose Factors.
Incorporates use of dose factor based on historical data for gaseous i
effluent radiation monitor
- default setpoints.
Reinstates REMP fish sample requirement at an annual frequency.
Corrects graph scale for Figure 1.0-1, Example Calibration Curve for Liquid Effluent Monitor.
The ODCM will be maintained at the station for use as a reference guide and training document of accepted methodologies and calculations.
Changes in the calculational methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents the present methodology in all applicable areas.
Computer software to perform the described calculations will be raintained current with the ODCM.
Changes to the ODCM shall be accomplished as specified in TS 5.5.1.
Records of reviews performed for changes made to the ODCM shall be retained for the duration of the Unit Operating License.
r GRAND GULF, UNIT 1 11 Revision 21 - 12/97
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TABLE OF CONTENTS F. ass 1
MANUAL APPROVAL SHEET..........................................
INTRODUCTION..................................................
11 TABLE OF CONTENTS.............................................. iii iv LIST OF FIGURES................................................
LIST OF TABLES................................................. v LIST OF REFERENCES............................................. vi EFFECTIVE PAGES................................................ vii 1.0 LIQUID EFFLUENTS 1.1 Liquid Effluent Monitor Setpoints 1.1.1 Liquid Radweste Effluent Line Monitors.........
1.0-1 t.
1.2 Dose Calculations for Liquid Effluents 1.2.1 Maxianam Exposed Individual Model...............
- 1. 0-7 1.2.2 Dose Projection................................
1.0-8 1.0-15 1.3 Liquid Radweste Treatment System................
3........
2.0 GASEOUS EFFLUENTS 2.1 Gaseous Effluent Monitor Setpoints 2.1.1 Continuous ventilation Monitors................
2.0-1 2.1.2 Text Deleted...................................
2.0-3 2.2 Gaseous Effluent Dose Calculations 2.2.1 Unrestricted Area Boundary Dose................
2.0-7 2.2.2 Unrestricted Area Dose to Individual...........
2.0-9 2.2.3 Dose Projection................................
2.0-10b 2.3 Meteorological Model 2.3,1 Atmospheric Dippersion.........................
2.0-24 2.3.2 Deposition.....................................
2.0-25 2.4 Definitions of Gaseous Effluents Parameters..............
2.0-27 2.5 Gaseous Radweste Treats.ent System........................
2.0-35 2.6 Annual Dose Conmitmant...................................
2.0-36 2.6.1 Direct Radiation Dose Measurement..............
2.0-36 3.0 RADIOIDGICAL INVIROISEENTAL MONITORING 3.1 Sampling Locations.......................................
3.0-1 GRAND GULF, UNIT 1 iii Revision 17 - 03/95 a
M TABLE OF CONTENTS 2.AER APPENDIE A - RADIOIDGICAL EFFLUENT CONTROLS AND A-O RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMS A-2 DEFINITIONS 1.1 GASEOUS RADNASTE TREATMENT (OFFGAS) SYSTEM 1.2 MEMBER (s) OF THE PUBLIC 1.3 OFFSITE DOSI CALCULATION MANUAL (ODCM) 1.4 PROCESS CONTROL PROGRAM (PCP) 1.5 SITE BOUNDARY 1.6 UNRESTRICTED AREA 1.7 VENTILATION EEHAUST TREATMENT SYSTEM SURVEILLANCE FREQUENCY NOTATION (DELETED)
............................A-4 MODES OF OPERATION (DELETED)
.........................................A-5 APPLICAEILITY (DELETED)
..............................................A-6 ADMINISTRATIVE CONTROLS..............................................A-8 5.6.2 Annual Radiological Environmental Operating Report...........................................A-9 5.6.3 Annual Radioactive Effluent Release Report
.............................................A-10 GRAND GULF, UNIT 1 iiia Revision 17 - 03/95
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9EQI TABLE OF CONTENTS I.AER LIMITING CONDITIAWC FOR OPERATION AND SURVEfft h CE ntnUTRB MNTS..... A-12 6.3 INSTRUMENTATION MONITORING INSTRUMENTATION 6.3.9 Radioactive Liquid Effluent Monitoring I
Instrumentation............................... A-13 6.3.10 Radioactive Gassous Effluent Monitoring Instrumentation............................... A-18 6.11 RADIOACTIVE EFFLUSNTS LIQUID EFFLUEKIS 6.11.1 Concentration................................... A-29 6.11.2 Dose / Total Dose................................. A-34 6.11.3 Liquid Neste Treatment.......................... A-36 GASEOUS EFFLUENTS 6.11.4 Dose Rate....................................... A-37 i
6.11.5 Dose - Noble Gases / Total Dose................... A-42 6.11.6 Dose - Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form / Total Dose.. A-44 6.11.7 Gaseous Radwaste Treatment...................... A-46 6.11.8 Ventilation Exhaust Treatment................... A-47 6.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 6.12.1 MONITORING PROGRAM AND i
intra 7 m RATORY COMPARISON PROGRAM.............. A-48 6.12.2 LAND USE CENSUS................................. A-59 l.
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GRAND GULF, UNIT 1 111b Revision 17 - 03/95
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oma TABLE OF CONTENTS F.AER nassa............................................................... A-61 6.3 INSTRUMENTATION MONITORING INSTRUMENTATION 6.3,9 Radioactive Liquid Effluent Monitoring Instrumentation............................... A-62 6.3.10 Radioactive Gaseous Effluent Monitoring Instrumentation............................... A-62 6.11 RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS 6.11.1 Concentration................................... A-63 6.11.2 Dose / Total Dose................................. A-63 6.11.3 Liquid Waste Treatment.......................... A-66 GASEOUS EFFLUENTS 6.11.4 Dose Rate....................................... A-66 6.11.5 Dose - Noble Gases / Total Dose................... A-67 6.11.6 Dose - Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Fors/ Total Dose.. A-69 6.11.7/
Gaseous Radwaste Treatment and Ventilation 6.11.8 Exhaust Treatment............................... A-71 6.12 RADIOLOGICAL ENVIROBBEENTAL MONITORING 6.12.1 MONITORING PROGRAM AND INT N RATORY COMPARISON PROGRAM.............. A-72 6.12.2 LAND USE CENSUS................................. A-73 i
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GRAND GULF, UNIT 1 iiic Revision 17 - 03/95
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LIST OF FIGURES Title Pace Fiaure 1.0-1 Example Calibration Curve for Liquid Effluent Monitor.....
1.0-6 1.3-1 Liquid Radwaste Treatment System..........................
1.0-16 2.3-1 Plume Depletion Ef fect for Ground-Level Releases..........
2.0-31 2.3-2 Vertical Standard Deviation of Material in a Plume........
2.0-32 2.3-3 Relative Deposition for Ground-Level Releases.............
2.0-33 2.3-4 Open Terrain Recirculation Factor....,....................
2.0-34 2.5-1 Gaseous Radwaste Treatment System.........................
2.0-35a 3.0-1 Collection Site Locations, 0-5 Mile Area Map..............
3.0-7 3.0-2 Collection Site Locations, General Area Mky, 0-10 Mile Area Map........................................
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GRAND GULF, UNIT 1 iv Revision 17 - 03/95
ODCM LIST OF TABLES Table Title Page 1.2-1 Bioa c curnul a ti on Fa ct o r s................................... ~ 0-9 1-.2-2 Ingestion Dose Conversion Factors For Adults...............
1.u-10 1.2-3 Site Related Ingestion Dose Commitment Factor..............
1.0-13 2.1-1 Dose Factors for Exposure to a Semi-infinite Cloud of Noble Gases....................................... 2.0-6 2.2-la Pathway Dose Factors for LCO 6.11.4 and Section 2.2.1.b........................................ 2.0-11 2.2-lb D e l e t e d.................................................... 2. 0 - 13 2.2-2a Pathway Dose Factors for LCO 6.11.6 and Section 2.2.2.b........................................ 2.0-15 2.2-2b Pathway Dose Factors for LCO 6.11.6 and Section 2.2.2.b........................................ 2.0-17 2.2-2c Pathway Dose Factors for LCO 6.11.6 and Section 2.2.2.b........................................ 2.0-19 2.2-2d Pathway Dose Factors for LCO 6.11.6 and Section 2.2.2.b........................................ 2.0-21 2.2-3, Controlling Receptors, Locations and Atmospheric 2.2-3a, Dispersion Parameters for LCOs 6.11.4, 6.11.5, 2.2-3b 6.11.6 and 6.11.8.......................................... 2.0-23 2.3-1 Deleted....................................................2.0-26 3.0-1 Air Sampler Collection Sites...............................
3.0-2 l
3.0-2 Miscellaneous Collection Sites.............................
3.0-3 l
3.0-3 TLD Locations..............................................
3.0-4 J
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GRAND GULF, UNIT 1 v
Revision 21 - 12/97 J
ODCM LIST OF REFERENCES
- 1..
Boegli, T.
S., R. R. Bellamy, W. L. Britz, and R. L. Waterfield,
" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG-0133 (October 1978).
2.
' Calculation'of Annual Doses to Man from Routine Releases of Reactor
. Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I, U.S. NRC Regulatory Guide 1.109 (March 3976).
3.
Calculation of Annual Doses to Man-from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR59, Appendix I, U.S. NRC Regulatory Guide 1.109, Rev. 1 (October 1977).
4.
" Environmental Report," Mississippi Power and Light Company, Grand Gulf Nuclear Station, Units 1 and 2.
5.
" Final Safety Analysis Report," Mississippi Power and Light Company, Grand Gulf Nuclear Station.
6.
Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in' Routine Releases from Light - Water - Cooled Reactors, U.S.
NRC Regulatory Guide 1.111 (March 1976).
7.-
Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light - Water - Cooled Reactors, U.S.
NRC Regulatory Guide 1.111, Rev. 1 (July 1977).
8.
Age-Specific Radiation Dose Connitment Factors for a One-Year Chronic Intake, NUREG-0172, November 1977.
9.
EER 93-6246 "X/Q and D/Q Atmospheric Dispersion and Deposition Factors".
{
l 10 NPE Calculation #XC-Q1111-G4002, Revision 0.
11.
GIN 97/01515 " Determination of Composite Dose Factor based on GGNS f
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Historical Gaseous Releases".
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GRAND GULF, UNIT 1 vi Revision 21 - 12/97 i
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ODCM LIST OF EFFECTIVE PAGES
'PAGE REV-PAGE REV
. NO.
NO.
No.
No.
i' 21-2.0-16 17 11' 21 2.0-17 17 111:
17 2.0-18.
17 iiia '
17 2.0-19 17 iiib 17 2.0-20 17 iiic-17 2.0-21 17
.iv 17 2.0-22 17 l
v 21 2.0-23 18 2.0-23a 17 2.0-23b 17.
vi 21 2.0-24 17 v11 21 2.0-25 17 viia 21 2.0-26 17 1.0-1 17 2.0-27 3
1.0-2 17 2.0-28 5
e 1.0-3' 17 2.0-29 21 i
L 1.0-4 15 2.0-30 3
l
'1.0-5 17 2.0 15 g
i 1.0-6 21 2.0-32 15 l
!~
1.0-7 17 2.0-33 15 l
1.0-8 17 2.0-34 15 i.
1.0-9 11 2.0-35 17 1.0-10 0
2.0-35a 8
1.0-11 11 2.0-36 20.
1.0-12 0
2.0-37 20 1.0-13 2
1.0-14
. 11 3.0-1 17 1.0-15 21 3.0-2 20 l
1.0-16 21 3.0-3 20 3.0-3a 21'
')
l 2.0-1 17 2.0 17 3.0-4
'20 2.0-3 2
3.0-5 20 2.0-4 21 3.0-6 20 2.0-5 21 3.0-6a 20 2.0-6 0
3.0-6b 13-2.0-7 17 3.0-6c 20 2.0-8 21 3.0-6d 20 2.0-9 17 3.0-7 20 2.0-10 17 3.0-8 20 2.0-10a 17 2.0-10b 17 2.0-11 17 2.0-12 17 2.0-13 21 2.0-14 21 2.0-15 17
'1 GRAND GULF, UNIT 1 vii Revision 21 - 12/97 i
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r ODCM LIST OF EFFECTIVE PAGES PAGE REV PAGE REV-NO.
NO.
NO.
NO.
l l
Appendix A-l A-0 17 A-34 17-l A-1 17 A-35' 17 A-2 17 A-36 17 A-3 17 A-37 17 A-4
'17 A-38.
17 A-5 17 A-39 17 A-6 17 A-40 17-A-7 17 A-41 17 A-8 17
'A-42 17 A-9 17 A-43 17 A-10 17 A-44 17
~A-11 17 A-45 17 A-12 17 A-46 17 A-13' 18 A-47 17 A-14 17 A-48 17 A-15 17 A-49 17 A-16 17 A-50 20 A-17 18' A-51 20 i
A-18 17 A-52 21
-l'
.A-19 17 A-53 20 A-20 19 A-54 20 A-211 17 A-55 17 A-22 17 A-56 17 A-23 17-A-57 17 A-24 18 A-58 17 A-25 21 A-59 20, l
A-26;
'18 A-60 20 A-27 18
'A-61 17 A-28 21 A-62 17
{
A-29 17 A-63 17 i
A-30 17 A-64 17 A-31' 17 A-65 17 A-32 17 A-66 17
-A 17 A-67 17 A-68 17 A-69 17 A 17 A-71 17 A-72 17 A-73 17 A-74 17 4
' GRAND GULF, UNIT 1 vila Revision 21 - 12/97
1.0 LIQUID EFTLUENTS 1.1 Liouid Effluant Manitor Satooints 1.1.1 Liauid Radwaste Effluent Line Monitors Liquid Radwaste Effluent Line Monitors provide alarm and automatic termination of release prior to exceeding ten times the concentration limits specified in 10CFR20, Appendix B, Table 2, Column 2 at the release point to the unrestricted area. To meet this specification and for the purpose of implementation of LCO 6.3.9, the alarm / trip setpoints for liquid effluent mon'itors and flow measurement devices are set to assure that the following equation is satisfied:
s;L s C F+f (1) where C=
ten times the effluent concentration limit (LCO 6.11.1) implementing 10CFR20 for the site, in pCi/ml.
c=
The setpoint, representative of a radioactivity 1
concentration in gci/ml, cf the radioactivity monitor measuring the radioactivity in the waste tank effluent line prior to dilution and subsequent release; the setpoint, which is inversely proportiona', to the volumetric flow of the effluent line and directly proportional to the volumetric flow of the dilution stream plus the waste tank effluent stream, represents a value which, if exceeded, would result in concentrations exceeding ten times the limits of 10CFR20 in the unrestricted ama.
GRAND GULF, UNIT 1 1.0-1 Revision 17 - 03/95
f=
the waste tank effluent flow setpoint as measured at the radiatior, monitor location, in volume per unit time, but in the same units as F, below.
l F=
the dilution water flow setpoint as measured prior to l
[
the release point, in volume per unit time, l
At Grand Gulf Unit 1, the available dilution water flow (F) should be constant for a given release, and the waste tank l
flow (f) and monitor setpoint (c) are set to meet the 1
i condition of equation 1 for a given effluent concentration, C.
The inethod by which this is accomplished is as follows:
Step 1)
The isotopic concentration for a waste tank to be released is obtained from the sum of the measured concentrations as determined by the analysis required in ODCM Table 6.11.1-1
+C (2)
Ecg = Ec +C,+EC,+C g
t g
where:
EC = the sum of concentrations C of each measured gamma 99 9
emitter observed by gamma-ray spectroscopy of the waste sample.
C, = the concentration C,of gross alpha emitters in liquid waste as measured in the monthly compoeire sample.
E,C, = the measured concentrations of Sr-89 and Sr-90 in liquid waste as observed in the quarterly composite sample.
GRAND GULF, tatIT 1 1.0-2 nevision 17 - 03/95 j
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C = the measured concentration of H-3 in liquid waste as g
determined from analysis of the monthly composite sample.
the concentration of Fe-55 in liquid waste as measured C
a g
in the quarterly composite sample.
The C ters will be included in the analysis of each waste 9
tank bateh to he r.l.as.d, t.rms for alpha, strontiums, tritium and iron are included if analysis of liquid waste has shown the presence of these isotopes.
Step 2)
The measured radionuclide concentrations are used to calculate a Dilution Factor, D.F.,
which is the ratio of total dilution flow rate to waste tank effluent flow rate required to armure that ten times the limiting concentration of 10CFR20, Appendix E, Table 2, Column 2 are met at the point of discharge.
i
[E 1 x S.F.
D.F.
=
i ECg C
C C
C C
= [E I+
"+E 8
t, f
+
j x g,y, (3)
EC, EC EC g EC EC, s
g where:
g = C, C,, C,, C and C s measured concentrations as C
g t
g and C will be defined in Step 1.
Terms C,, C,, Cg g
included in the calculation as appropriate.
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j GRAND GULF, UNIT 1 1.0-3 Revision 17 - 03/95
and EC are ten times the g=
EC, EC,, EC,,ECg g
EC g
limiting concentrations of the appropriate radionuclide from 10CFR20, Appendix E, Table 2, For dissolved or entrained noble gases, l
Column 2.
the concentration shall be limited to 2.0E-4 pC1/ml total activity.
an administrative safety factor normally applied S.F.
=
at Grand Gulf which causes the calculated Dilution
)
Factor to be two (2) times larger than the dilution factor required for compliance with ten l
times 10CFR20 limits.
The maximum permissible waste tank effluent flow rate prior Step 3) to dilution, f ' ** "" ***
- U #"
d the dilution flow rate, F
- d F
+ f F
(
d ** d fd*
D.F.
D.F.
where:= 0.9 x minimum expected dilution flow rate Fd mum pe d ss 21e waste t d effluent flow rate f
'=
t d
D.F. = Dilution Factor from Step 2.
for D.F.si, the waste NOTE:
Equation 4 is valid only for D.F.>1; tank effluent concentration meets the limits of ten times i
the limiting concentrations of 10CFR20 without dilution, and
""Y fd "*Y The dilution flow rate setpoint for minimum dilution flow Step 4) rate, F, and waste tank flow rate setpoint for maximum waste tank effluent flow rate, f, are calculated as follows:
(5) d = 0.9 x minimum expected dilution flow rate F=
F d = 0.9 x calculated maximum waste tank flow f=
0.9 x f (6) rate for the stated release conditions.
Revision 15 - 01/94 1.0 4 GRAND GULF, UNIT 1
Thus, if instrumentation indicates the dilution flow rate falls below the assumed flow rate of 90 percent of the actual dilution flow, or if the waste tank effluent flow rate exceeds 90 percent of the calculated maximum waste tank effluent flow rate, the release is terminated (manually or automatically).
Step 5)
The radioactivity monitor setpoint may now be specified based on the values of I C,
F, and f which were specified to provide compliance with ten times the limits of 10CFR20, Appendix B, Table 2, Column 2.
The monitor response is primarily to gamma radiation; therefore, the actual setpoint is based on I C. The setpoint concentration, C, is gg m
determined as follows:
d IC (pci/nd)
(7)
C =
m g
l f
9 a
where f, is the actual (or maximum expected) waste tank effluent flow rate.
The value of C (pCi/ml) is used to driermine the monitor setpoint (CPM) from a calibration curve similar to ODCM Figure 1.0-1.
NOTE:
Setpoint adjustments are not required if the existing setpoint corresponds to a lower count rate than the calculated value. The actual monitor setpoint is determined from the measured concentration plus background for the detector. The setpoint contains a factor of conservatism, even if the calculated maximum waste tank flow rate is attainable, since the calculated rate contains the safety factor margin, waste tank effluent flow rate margin, and the dilution flow rate margin.
In practice, the actual waste tank effluent flow rate normally is many times less than the calculated tank flow rate, thus providing an additional conservatism during release.
GRAND GULF, UNIT 1 1.0-5 Revision 17 - 03/95
Figura 1.0-1 Example Calibre. tion Curva for Liquid Efflurnt Monitor 1.0E44 J
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1.0E47
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1.0E 08 1.0E+01 1.0E+02 1.0E+03 1.0E+04 Count Rate (counts per minute) 9 GRAND GULF, UNIT 1 150-6 Revision 21 - 12/97
1.2 Dese calculations for Licruid Ef fluents 1.2.1 Mnf== Exoosed Individual Model The dose contribution to the maximum exposed individual from all radionuclides identified in waste tank liquid effluents released to unrestricted areas is calculated for the purpose of implementing LCO 6.11.2, 6.11.3, and TS 5.6.3 using the following expressions m
(1) 1 (millirem)
(e)
- fIA D
il iTau t1 Tau where:
A
= Site-related ingestion dose commitment factor for g
radionuclide i, in millirem /hr per pCi/ml.
=K U BF DF F
g g
g = length of the time period over which Cit g
and F are At averaged for all waste tank liquid releases, in hours.
g = average concentration of radionuclide i observed in C
the undiluted waste tank liquid effluent during time period At from any liquid release from the g
waste tank, in gci/ml. Concentrations are determined primarily from a gamma isotopic analysis of the waste tank liquid effluent sample. For Fe-55, Sr-89, Sr-90, X-3, the last measured value from the most recent monthly and quarterly composite samples will be used in the dose calculation.
NOTE: LLD values are not used in dose calculations.
1 i
l GRAND QULF, UNIT 1 1.0-7 Revision 17 - 03/95
during g = near field average dilution factor for Cg F
any liquid effluent release. Defined as the ratio of the average undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times the applicable factor ef 2 (5)
= avermaa nndiluted liauid waste flow average flow from site discharge x 2
= units conversion factor 1.14 x 10' K
8766 hg
= 10 gC1 x 10 31
+
pC1 kg yr U = adult fish consumption (21 kg/yr)
F g = Bioaccumulation factor for each nuclide, i, in fish, BF in pCi/kg per pCi/1 from ODCM Table 1.2-1.
g = Dose conversion factor for each nuclide, i, for DF adults in preselected organ, Tau, in mrem /pci, from ODC34 Table 1.2-2.
Calculated values of A for radionuclides which might be observed in liquid affluents are given in ODO4 Table 1.2-3.
1.2.2 Dome Proiection Doses from liquid effluents to UNRESTRICTED AREAS are projected at least every 31 days as required by LCO 6.11.3.
These projections are made by averaging the doses (D3) from previous operating history (normally the previous six months) which is indicative of expected future operations.
GRAND GULF, UNIT 1 1.0-8 Revision 17 - 03/95
ZhEnE.L2:.1 mIQACCt3CLATION FACTORE. (EF )
g (pci/kg per pC1/ liter)*
FRESENATER ELIMENT fl33 INVERTERRATE H
9.0E-01 9.0E-01 C
4.65+03 9.1E+03 NA 1.0E+02 2.0E+02 P
1.0E+05 2.0E+04 CR 2.0E+02 2.0E+03 MN 4.0E+02 9.0E+04 FE 1.0E+02 3.2E+03 CO 5.0E+01 2.0E+02 NI 1.0E+02 1.0E+02 CU 5.0E+01 4.0E+02 ZN 2.0E+03 1.0E+04 BR 4.2E+02 3.3E+02 RS 2.0E+03 1.0E+03 SR 3.0E+01 1.0E+02 Y
2.5E+01 1.0E+03 ZR 3.3E+00 6.7E+00 NB 1.OE+04 1.OE+02 MO 1.0E+01 1.0E+01 TC 1.5E+01 5.0E+00 RU 1.0E+01 3.0E+02 RM 1.0E+01 3.0E+02 SB 1.0E+00 1.0E+01 TE 4.0E+02 6.1E+03 I
1.5E+01 5.0E+00 CS 2.0E+03 1.0E+03 BA 4.0E+00 2.0E+02 LA 2.5E+31 1.OE+03 CE 1.0E+00 1.0E+03 PR 2.5E+01 1.0E+03 ND 2.5E+01 1.0E+03 W
1.2E+03 1.0E+01 NP 1.0E+01 4.0E+02
- Values in Table 1.2-1 are taken from Reference 3, Table A-1, except for SB
}
whif*h was taken from Reference 2, Table A-8.
l i
i I
GRAND GULF, UNIT 1 1.0-9 Revision 11 - 06/80
i TABLE 1.2-2 INGESTICEf DOSE CONVIRSION FACTORS FOR ADULTS. (DF )
g (area per PC1 ingested)
Page 1 of 3 NUCLIDE BONE LIVER T. LODY TRYROID KIDNEY LUNG GI-LLI H
3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C
14 2.84E-06 5.685-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.60E-07 NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.703-06 1.705-06 1.70E-06 P
32 1.93E-04 1.20E-05 7.465-06 NO DATA NO DATA NO DATA 2.17E-05 CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 5.863-10 3.535-09 6.69E-07 MN 54 NO DATA 4.57E-06 8.725-07 NO DATA 1.363-06 NO DATA 1.40E-05 NN 56 NO DATA 1.155-07 2.043-08 NO DATA 1.465-07 NO DATA 3.67E-06 FE 55 2.75E.06 1.90E-06 4.43E-07 NO DATA NO DATA 1.068-06 1.09E-06 FE 59 4.34E.06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO 58 NO DATA 7.455-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 CO 60 NO DATA 2.14E-06 4.725 06 NO DATA NO DATA NO DATA 4.025-05 NI 63 1.30E-04 9.015-06 4.36E-06 NO DATA NO DATA NO DATA 1.885-06 NI 65 5.28I-07 6.86E-08 3.135-08 NO DATA NO DATA NO DATA 1.743-06 CU 64 NO DATA 8.335-08 3.91E-08 NO DATA 2.10E-07 WO DATA 7.10E-06 ZN 65 4.04E-06 1.54E-05 6.965-06 NO DATA 1.035-05 NO DATA 9.70E-06 ZN 69 1.03E-00 1.97E-00 1.37E 09 NO DATA 1.285-08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-00 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 BR 85 WO DATA NO DATA 2,14E-09 NO DATA NO DATA NO DATA LT E-24 R3 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB. 8 8 NO DATA 6.055-08 3.21E-08 NO DATA NO DATA NO DATA 5.36E-19 R3 89 NO DATA 4.01E-00 2.02E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.00E-04 NO DATA O.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.50E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E-00 NO DATA NO DATA NO DATA 4.2EE-05 Y
90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 Y
91M 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.678-10 Y
91 1.41E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y
92 0.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.40E-05
- Values taken from Reference 3, Table E-11.
GRAND GULF, UNIT 1 1.o.10 Revision 0 - 08/82
TAILE 1.2-2 (Continued)
INGESTION DOSE CONVIISION FACTORS FOR ADULT 4 (DF )
g (mrom per pC1 ingested)
Page 2 of 3 NUCLIDE SONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 i
ZR 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05
)
ZR 97 1.68E-09 3.39E-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 NE 95 6.22E-09 3.46E-09 1.865-09 NO DATA 3.42E-09 NO DATA 2.10E-05 MO 99 NO DATA 4.31E-06 8.20E-07 MO DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E.10 6.99E-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07 TC101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10E-21 RU103 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05
{
RU105 1.54E-08 NO DATA 6.00E-09 NO DATA 1.995-07 NO DATA 9.42E-06 RU106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31E-06 NO DATA 1.78E-04 AG110M 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.045-05 55124 2.80E-06 5.29E-08 1.11E.06 6.79E-09 0.0 2.18E-06 7.955-05 SE125+D 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.0 1.30E-06 1.975-05 SE126 1.15E-06 2.34E-08 4.15E-07 7.04E-09 0.0 7.05E-07 9.405-05 SE127 2.58E-07 5.65E-09 9.90E-08 3.10E-09 0.0 1.53E-07 5.90E-05 TE125M 2.68E-06 9.71E-07 3.59E-07 8.065-07 1.09E-05 NO DATA 1.07E-05 TE127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 TE129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 TE132 2.52E-06 1.63E-06 1.53E-06 1.80E.06 1.57E-05 NO DATA 7.71E-05 I 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 I 131 4.16E-06 5.95E-06 3.41E-06 1.95E.03 1.02E-05 NO DATA 1.57E-06 I 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07 I 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.515 10 I 135 4.43E-07 1.15E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31E-06 CS134 6.22E-05 1.48E 04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 C9136 6.51E-06 2.57E-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06
- Values taken from Reference 3, Table E-11, except for S4 values which were taken from Reference 8, Table 4.
GRAND GULF, UNIT 1 1.0 11 Revision 11 06/88
- rmat" 1.2-2 (cont 4nuad)
IMGESTICM DOSE CONVIRSION FACTORS FOR ADDLTS. (DF )
(mrem per pC1 ingested)
Page 3 of 3 NUCLIDE SONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI CS137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 CS138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 I
BA139 9.70E.08 6.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 RA140 2.03E-05 2.55E-08 1.33E-06 NO DATA 5.675-09 1.46E-08 4.18E-05 BA141 4.71E-08 3.56E-11 1.59E-09 NO DATA 3.315-11 2.025-11 2.22E-17 BA142 2.135-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.245-11 3.00E-26 LA140 2.50E-09 1.26E-09 3.33E.10 NO DATA NO DATA NO DATA 9.25E-05 LA142 1.20E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE143 1.65E-09 1.22E-06 1.355-10 NO DATA 5.375-10 NO DATA 4.56E-05 CE144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.655-04 PR143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR144 3.01E-11 1.25E.11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.333-18 ND147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W 187 1.03E-07 8.61E-08 3.01E-08 NO DATA NO DATA NO DATA 2.82E-05 NP239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E-05
- Values taken from Reference 3, Table E-11 i
l 1
1 l
GRAND GULF, UNIT 1 1.0-12 Revision 0 08/82
l TABLE 1.2-3 BITE am
- RED i-ziicar name GA-1 FACTOR, (AiTau)
(arem/hr per #C1/ml),
Page 1 of 2 NUCLIDE BONE LIVER T. BODY TEYEDID KIDNEY LUNG GI LLI E-3 0.00E+00 2.26E-01 2.265-01 2.263-01 2.263-01 2.26E-01 2.26E-01 C-14
.3.13E+04 6.263+03 6.265+03:
6.265+03 6.263+03 6.265+03 6.26E+03 Na-24 4.075+02 4.075+02 4.07E+02 4.075+02 4.075+02 4.075+02 4.075+02 P-32 4.62E+07 2.873+06 1.793+06 0.00E+00 0.00E+00 0.00E+00 5.19E+06 Cr-51 0.00E+00 0.00E+00 1.27E+00 7.615-01 2.813-01 1.693+00 3.20E+02 Mn-54 0.00E+00 4.385+03-8.35E+02 0.00E+00 1.30E+03 0.00E+00 1.34E+04 Mn-56 0.00E+00 1.10E+02 1.95E+01 0.00E+00 1.403+02 0.00E+00 3.51E+03 Fe-55 6.585+02 4.55E+02 1.063+02 0.00E+00
'0.00E+00 2.54E+02 2.61E+02 Fe-59 1.04E+03 2.44E+03
- 9.365+02 0.00E+00 0.00E+00 6.82E+02 0.14E+03 Co-58 0.00E+00 8.42E+01 2.00E+02 0.00E+00 0.00E+00 0.00B+00 1.01E+03 Co-60 0.00E+00 2.565+02 5.65E+02 0.00E+00 0.00E+00 0.00E+00 4.81E+03 Ni-63 3.11E+04 2.15E+03-1.04E+03 0.00E+00 0.00E+00 0.00E+00 4.50E+02 Ni-65 1.26E+02 1.64E+01 7.495+00 0.00E+00 0.00E+00 0.00E+00 4.175+02 Cu-64 0.00E+00 9.973+00 4.685+00 0.00E+00 2.51E+01 0.00E+00 8.50E+02 En-65 2.32E+04 7.375+04 3.33E+04 0.00E+00 4.93E+04 0.00E+00 4.64E+04 En-69 4.93E+01 9.43E+01 6.565+00 0.00E+00 6.13E+01 0.00E+00 1.42E+01 Er-83 0.00E+00 0.00E+00 4.04B+01 0.00E+00 0.00E+00 0.00E+00 5.82E+01 Er-84 0.00E+00 0.00E+00 5.24E+01 0.00B+00 0.00E+00 0.00E+00 4.115-04 Br-85 0.00E+00 0.00E+00 2.15B+00 0.00E+00 0.00E+00 0.00E+00 1.01E-15 Rb 0.00E+00
-1.01E+05 4.715+04 0.00E+00 0.00E+00 0.00E+00 1.99E+04 Rb-88 0.00E+00 2.90E+02 1.54E+02 0.00E+00 0.00E+00 0.00E+00 4.00E-09 Rb-89 0.00E+00 1.92E+02 1.35E+02 0.00E+00 0.00B+00 0.00E+00 1.12E-11 Sr-89 2.21E+04 0.00E+00 6.35E+02 0.00E+00 0.00E+00 0.00E+00 3.55E+03 Sr-90 5.44E+05 0.00E+00 1.34E+05 0.00E+00 0.00E+00 0.00E+00 1.57E+04 Sr-91 4.07E+02 0.00E+00 1.64E+01 0.00E+00 0.00E+00 0.00E+00' 1.94E+03 Sr-92 1.54E+02 0.00E+00 6.685+00 0.00E+00 0.00E+00 0.00E+00 3.063+03 Y-90 5.76E-01 0.00E+00 1.54E-02 0.00E+00 0.00E+03 0.00E+00 6.10E+03 Y-91m 5.44E-03 0.00E+00 2.115-04 0.00E+00 0.00E+00
-0.00E+00 1.60E-02 Y-91 8.44E+00 0.00E+00
- 2.265-01 0.00E+00 0.00E+00 0.00E+00 4.64E+03 Y-92 5.06E-02 0.00E+00 1.48E-03 0.00E+00-0.00E+00 0.00E+00 0.865+02~
Y 93 1.60E-01 0.00E+00 4.433-03 0.00B+00 0.00E+00 0.00E+00 5.095+03 Zr-95 2.40E-01 7.70E-02 5.21E-02 0.00E+00 1.21E-01 0.00E+00- 2.44E+02 2r-97 1.33E-02 2.685-03 1.22E-03 0.00E+00 4.04E-03 0.00E+00 0.30E+02 Nb 95-4.47E+02 2.48E+02 1.34E+02 0.00E+00 2.465+02 0.00B+00 1.51E+06 Mo-99 0.00E+04 1.03E+02 1.96E+01 0.00E+00 2.34E+02 0.00E+00 2.39E+02 Te-99m 8.87E-f3 2.515-02 3.19E-01 0.00E+00 3.815-01 1.23E-02 1.48E+01 Tc-101 9.12E-03 1.31E-02 1.29E-01 0.00E+00 2.37E-01 6.72E-03 3.95E-14 Ru-103 4.43E+10 0.00E+00 1.91E+00 0.00E+00 1.693+01 0.00E+00' 5.175+02 Ru-105 3.69E 01 0.00E+00 1.46E-01 0.00E+00 4.76E+00 0.00E+00 2.265+02
'* Calculated from Equation B.
\\
I GRAND GULF, UNIT 1 1.0 13 Revision 2 - 05/84
)
TABLE 1.2-3 (Continued)
SITE REIATED IIRIESTICat DORE CC80tI' MENT FACTQ3. (A1 Tau)
(mres/hr per gci/ml).
Page 2 of 2 NUCLIDE BONE LIVIk T. BODY TRYROID KIDNEY LUNG GI-LLI Ru-106 6.583+01 0.00E+00 8.33E+00 0.00E+00 1.275+02 0.00E+00 4.26E+03 Ag-110m 8.81E-01 8.15E-01 4.84E-01 0.00E+00 1.60E+00 0.00E+00 3.30E+02 Sb-124 6.70E+00 1.27E-01 2.66E+00 1.63E-02 0.00E+00 5.22E+00 1.90E+02 Sb-125 4.29E+00 4.79E-02 1.02E+00 4.36E-03 0.00E+00 3.30E+00 4.72E+01 Sb-126 2.75E+00 5.60E-02 9.943-01 1.69E-02 0.00E+00 1.69E+00 2.25E+02 Sb-127 6.18E-01 1.35E-02 2.37E-01 7.425 03 0.00E+00 3.66E-01 1.41E+02 Te-125m 2.57E+03 9.30E+02 3.44E+02 7.72E+02 1.04E+04 0.00E+00 1.02E+04 Te-127m 6.485+03 2.32E+03 7.90E-02 1.66E+03 2.63E+04 0.00E+00 2.17E+04 Te-127 1.05E+02 3.785+01 2.285+01 7.00E+01 4.295+02 0.00E+00 8.31E+03 Te-129m 1.10E+04 4.11E+03 1.74E+03 3.785+03 4.60E+04 0.00E+00 5.54E+04 Te-129 3.01E+01 1.13E+01 7.33E+00 2.315+01 1.263+02 0.00E+00 2.27E+01 Te-131m 1.665+03 8.10E+02 6.75E+02 1.285+03 8.21E+03 0.00E+00 8.04E+04 Te-131 1.89E+01 7.885+00 5.965+00 1.55E+01 8.26E+01 0.00E+00 2.675+00 Te-132 2.41E+03 1.56E+03 1.47E+03 1.72E+03 1.50E+04 0.00E+00 7.385+04 I-130 2.71E+01 8.01E+01 3.16E+01 6.795+03 1.25E+02 0.00E+00 6.893+01
)
I-131 1.49E+02 2.14E+02 1.22E+02 7.00E+04 3.665+02 0.00E+00 5.64E+01 I-132 7.29E+00 1.95E+01 6.82E+00 6.82E+02 3.11E+01 0.00E+00 3.665+00 I-133 5.10E+01 8.87E+01 2.70E+01 1.30E+04 1.55E+02 0.00E+00 7.975+01 I-134 3.81E+00 1.03E+01 3.70E+00 1.795+02 1.64E+01 0.00E+00 9.01E-03 I-135 1.59E+01 4.173+01 1.54E+01 2.75E+03 6.685+01 0.00E+00 4.70E+01 Cs-134 2.98E+05 7.095+05 5.79E+05 0.00E+00 2.295+05 7.61E+04 1.24E+04 Cs-136 3.12E+04 1.23E+05 8.86E+04 0.00E+00 6.85E+04 9.385+03 1.40E+04 Cs-137 3.82E+05 5.22E+05 3.42E+05 0.00E+00 1.77E+05 5.895+04 '1.01E+04 Cs-138 2.64E+02 5.22E+02 2.59E+02 0.00E+00 3.84E+02 3.795+01 2.23E-03 Ba-139 9.29E-01 6.625-04 2.72E-02 0.00E+00 6.19E-04 3.75E-04 1.65E+00 Ba-140' 1.94E+02 2.44E-01 1.275+01 0.00E+00 8.30E-02 1.40E-01 4.00E+02 Ba-141 4.51E-01 3.41E-04 1.52E-02 0.00E+00 3.17E-04 1.93E-04 2.13E-10 Ba-142 2.04E-01 2.10E-04 1.285-02 0.00E+00 1.77E-04 1.19E-04 2.87E-19 La-140 1.50E-01 7.54E-02 1.995-02 0.00E+00 0.00E+00 0.00E+00 5.54E+03 La-142 7.66E-03 3.48E-03 8.6BE-04 0.00E+00 0.00E+00 0.00E+00 2.54E+01 Ce-141 2.24E-02 1.52E-02 1.72E-03 0.00E+00 7.04E-03 0.00E+00 5.79E+01 Ce-143 3.95E-03 2.92E+00 3.23E-04 0.00E+00 1.295-03 0.00E+00 1.095+02 Co-144 1.17E+00 4.88E-01 6.27E-02 0.00E+00 2.90E-01 0.00E+00 3.95E+02 Pr-143 5.51E-01 2.21E-01 2.73E-02 0.00E+00 1.27E-01 0.00E+00 2.41E+03 Pr-144 1.80E-03 7.48E-04 9.16E-05 0.00E+00 4.22E-04.
0.00E+00 2.59E-10 Nd-147 3.76E-01 4.35E-01 2.60E-02 0.00E+00 2.54E-01 0.00E+00 2.09E+03 W-187 2.96E+02 2.47E+02 8.65E 01 0.00E+00 0.00E+00 0.00E+00 8.10E+04 Np-239 2.85E-02 2.00E-03 1.54E-03 0.00E+00 8.74E-03 0.00E+00 5.75E+02 l
- Calculated from Equation 8.
GRAND GULF, UNIT 1 1.0-14 Revision 11 - 06/88
1.3 Liquid Radwaste Treatment System The essential components of the liquid radwaste treatment system are indicated by an asterisk (*).
NOTES for Figure ODCM 1.3-1 (1)
The essential components outlined on the following page are those necessary to collect, process and sample liquid radwaste prior to discharge to the environment.
(2) only one of the following is required in order to process liquid waste.
a.
Equipment drain filter b.
Floor drain filter c.
Equipment drain demineralizer d.
Floor drain demineralizer (3)
The Waste surge Tanks may be used to replace the Waste Collection i
Tanks.
l l
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I GRAND GULF, UNIT 1 1.0-15 Revision 21 - 12/97 n
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2.0 GASIOUS EFFLUENTS 2.1 d'meous Ef fit 2 ant Manitor Setnoints i
2.1.1 continuous Ventilation Manitors For the purpose of implementation of LCO 6.3.10, the alarm I
setpoint level for continuous ventilation noble gas monitors will be calculated as follows:
I S - count rate (epm) above background of vent noble gas y
monitor at the alarm setpoint level PF x R xD t
= the lesser of or PF x R xD s
es where:
PF = product of allocation factor (AF) and safety factor (SF), normally set at 0.1 AF = allocation factor allowing for a total of four normal effluent release points, normally set at 0.25 SF = safety factor allowing for cumulative uncertainties of measurements, normally set at 0.4 D
- dose rate limit to the total body of an individual g
at the SITE BOUNDARY or at UNRESTRICTED ARIAS inside the SITE BOUNDARY required to limit dose to 500 mrom in one year
- 500 mres/yr D,, - dose rate limit to the skin of the body of an individual at the SITE BOUNDARY or at UNRESTRICTED ARIAS inside the SITE BOUNDARY required to limit dose to 3000 mrom in one year
- 3000 mrea/yr I
GRAND GULF, UNIT 1 2.0-1 Revision
- 7 - 03/95
R = count rate (cpm) per mres/yr to the total body
=C+
[ X76 E K Q' g]
where C = count rate (cpm) above background of the vent monitor corresponding to grab sample radionuclide concentrations X/Q = highest sector annual average atmospheric dispersion at the SITE BotDTDARY or at UNRESTRICTED AREAS inside the SITE BOUNDARY 3
= s.9 x 10 sec/m in the SW sector g - total body dose factor due to gamma emissions from K
each noble gas radionuclide 1 (mram/yr per gCi/m )
from CDCM Table 2.1-1 Q'g = rate of release of noble gas radiomelide 1 (gCusec) from the release point R, = count rate (cym) per arem/yr to the skin
- C + X/Q (Eg (Lg + 1.1 M ) Q' g]
g L = skin dose factor due to beta emissions from isotope 1 (mrem /yr per pCi/m ) from ODCM Table 2.1-1 1.1 = mrom skin dose per arad air dese g - air dose factor due to gasuna emissions from isotope 1 M
3 (mrad /yr per pci/m ) from ODCM Table 2.1-1 The highest annual average X/Q for the GGNS SITE BOUNDARY or UNRESTRICTED AREAS inside the SITE BOUNDARY is at the SITE BOUNDARY, (SW sector, 0.85 i
1 miles). This value is taken from ODCM Reference 9, Table 2.
l GRAND GULF, UNIT 1 2.0-2 Revision 17 - 03/95 j
1
1 2.1.2 i
1
^f 1
l l
TEXT DELETED l
GRAND GULF, UNIT 1 2.0-3 Revision 2 - 05/84
l l
l NOTES For Section 2.1.1 1)
The calculated setpoint values will determine the allowable bounds for the actual setpoint adjustments. That is, setpoint adj'ustments are not required to be performed if the existing setpoint level corresponds to a count rate that la less than or equal to + 25% of the calculated value.
If radionuclides are not detected in the grab sample, then the previously calculated setpoint may remain as the valid setpoint.
2)-
_A conservative setpoint may be calculated using a composite total body l
dose' factor.
This method may be used when there are no valid isotopics 4
l available.
The conservative setpoint will be calculated as follows:
I i
S = count rate (cpm) above background of vent noble gas monitor at the j
i alarm setpoint level *
= PF' xDTB
- t
(
where:
PF = product of allocation factor (AF) and safety factor (SF'), normally set at 0.2 i
AF = allocation factor allowing for a total of four normal effluent
{
release points, normally set at 0.25 l
SF' = safety factor allowing for cumulative uncertainties of measurements, normally set at 0.4.
-R " = conservative count rate per mrem /yr to the total body (Xe-133 i
detection, composite dose factor) j j
(3.53E-5) (60)
=
X/Q (X) (V) (K)
- The setpoint calculation based on a skin dose is not required because the setpoint based on the total body dose is more conservative.
i i
e GRAND GULF, UNIT 1 2.0-4 Revision 21 - 12/97 67 4
p
l where:
X = Xe-133 volume efficiency factor of the detector system in j
pCi/cc/ cpm as determined by the primary calibration
- V = maximum designed ventilation flow rate in cubic feet per minute (cfm) 3.53E-5 = conversion factor, ft per cc 60>= convcraion factor, seconds per minute
(
K = total body dose factor for historical ndxture**,.
~
= 1.51E + 03. mrem /yr per pCi/m
-Other variables as defined in Section 2.1.1 l
i L
l The instrument calibration procedures will include checks to ensure that I
the detector efficiency does not vary by more than t 25%.
i l
ODCM Reference 11 l
4 l
I l
[
I.
GRAND GULF, UNIT 1 2.0-5 Revision 21 - 12/97 l
- 7
l 1
TABLE 2.1-1
)
D0qE FACTORS FOR EXPOSURE TO A SIMI-INFINITE CIDDD OF NOBLE GARES 1
l 1
Nuclide Y-Bodv**(K)i B-EH n**(L)i Y-Air *(M)i B-Air *(N)i I
Kr-85m 1.17E+03***
1.465+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.565+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.275+02 1.48E+03 Xe-133 2.94E+02 3.065+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-130 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9,30E+03 3.28E+03 values taken from Reference 3, Table B-1 mrad - ma pC1 yr
- mram - ma gC1 - yr
- 1.17E+03 1.17 x 10
=
GRAND GULF, UNIT 1 2.0-6 Revision 0 - 08/82
2,2 Gaseous Effinant Dose Calculations 2.2.1 unrestricted Area Boundarv Dese Rate a.
For tne purpose of implementation of LCO 6.11.4.a, the dose rate at the SITI BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY due to noble gases shall be calculated as follows:
eb = average t tal body dose rate in current year D
(mrom/yr)
= 175 rx Q1 1
D,
- average skin dose rate in current year (mrom/yr)
= 176 I (L
+ 1.1M ) Q'g g
g b.
Organ dose rate due to tritium, I-131, I-133 and all l
radioactive materials in particulate form, with half-l lives greater than eight days will be calculated for the purpose of implementation of LCO 6.11.4.b as follows:
D, average organ dose rate in current year (mres/yr)
= IN P Q'g g
i i
where:
i I
GRAND GULF, UNIT 1 2.0-7 Revision 17 - 03/95 l
l W = controlling sector annual average atmospheric dispersion at the SITE BOUNDARY or UNRESTRICTED AREAS inside the SITE BOUNDARY for the appropriate pathway
~*
X/Q 8.9 x 10 sec/m for inhalation
=
and all tritium pathways or
~*
1.6 x 10 m'
for food and D/Q
=
ground plane pathways
]
P = the total dose parameter for radionuclide i, (mrem /yr per pCi/m ) for inhalation and all tritium pathways and (m. mrem /yr per pCi/sec) for food and ground plane pathways, from ODCM Table 2.2-la Q'
= rate of release of noble gas radionuclide 1 (pCi/sec) from the release point Q'
= average release rate of isotope i of tritium, I-131, I-133 or other radionuclide in i
particulate form, with half-lives greater than eight (8) days in the current year (pci/sec) l The highest annual average X/Q for the GGNS SITE BOUNDARY or UNRESTRICTED l
AREAS inside the SITE BOUNDARY is at the SITE BOUNDARY, in the SW sector (0.85 miles).
This value is taken from ODCM Reference 9, Table 2.
The highest annual average D/O for the GGNS SITE BOUNDARY or UNRESTRICTED l
AREAS inside the CITE BOUNDARY is at the SITE BOUNDARY in the SSE sector (0.46 miles). This value is taken from ODCM Reference 9, Table 2.
l I
l GRAND GULF, UNIT 1 2.0-8 Revision 21 - 12/97 n,
5
r.
UnrestrictedAreaDosetoindividunk 2.2.2 a.
For the purpose of implementation of LCO 6.11.5, the air dose at the SITE BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY shall be determined as follows:
D = air dose due to ganuna emissions from noble gas radionuclide 1 (mrad)
= 3.17 x 10"'
X/Q' o g where:
X/Q' = relative concentration for the SITE BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY.
'l 3
= s.9 x 10 sec/m g = air dose factor due to ganmaa emissions from M
noble gas radionuclide 1 (mrad /yr per pCi/m )
from ODCM Table 2.1-1 The highest annual average X/Q for the QGNS SITE BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY is at the SITE BOUNDARY, SW Sector, 0.e5 miles. This value is taken from CDCM Reference 9 Table 2.
GRAND GULF, UNIT 1 2.0-9 Revision 17.- 03/95
l l
Q = cumulative release of radionuclide i of noble l
gas, tritium, I-131, I-133, or material in l
particulate form over the period of interest f.
(gC1)
~
Note:
3.17 x 10 is the inverse of the number of seconds per year, and s
D, = air dose due to beta emissions from noble gas i
radionuclide i (mrad)
-8
= 3.17 x 10 EN X7Q' Qg where:
i = air dose factor due to beta emissions from noble N
I 3
{
gas radionuclide 1 (mrad /yr per pCi/m ) from CDCM Table 2.1-1 X/Q' = relative concentration the SITE BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY.
~
= 8.9 x 10 sec/m g = cumulative release of radionuclide i of noble Q
gas, tritium, I-131, I-133, or material in particulate form over the period of interest
(#Cil J
The highest annual average X/Q for the GGNS SITE BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY is at the SITE BOUNDARY, SW Sector, 0.85 miles. This value is taken-from ODCM Reference 9 Table 2.
i
[
GRAND GULF, UNIT 1 2.0-10 Revision 17 - 03/95
Unrestricted Area Dene to Individual" 2.2.2 b.
Dose to an individual from tritium, I-131, I-133 and radioactive materials in particulate form, with half-lives greater than eight (e) days will be calculated for the purpose of implementation of LCO 6.11.6 as follows:
D = dose to an individual from tritium, I-131, I-133 and radionuclides in particulate form, with
)
half-life greater than eight days (mrem)
= 3.17 x 10 ' IR
~
N' Q
g g
where:
W' = relative concentration at a controlling location I
for an individual W=
0.3 x 10" sec/m' for inhalation and all tritium pathways
)
or
~
~
W=
6.7 x 10 m
for food and ground plane pathways g = the total dose factor for,radionuclide i, R
3 (mres/yr per gci/m ) for inhalation and all tritium pathways and (m. mrom/yr per pci/sec) for food and ground plane pathways from Tables 2.2-2a - d The highest annual average X/Q and D/Q at or beyond the SITI BOUNDARY is in the SW Sector (0.09 miles). These values are for the controlling offsite receptor. These values are taken from ODO( Reference 9, Table 2.
GRAND GUI.F, UNIT 1 2.0-10a Revision 17 - 03/95
2.2.2 Unrestricted Area Dome to individual' l
o - cumulative release of radionuclide i of noble l
g gas, tritium, I-131, I-133, or material in particulate form over the period of interest (pci)
For the purpose of implementing TS 5.6.3, dose c.
calculations will be performed using the above equations or with the substitution of average meteorological parameters (most limiting parameters will be used) which prevailed for the period of the report.
2.2.3 Dose Proinction t
Doses from gaseous effluents to UlstssTRICTED AREAS are projected at least every 31 days as required by LCO 6.11.8.
These projections are made by averaging the doses (D, D,
p D,) from previous operating history (normally the previous six months) which is indicative of future expected operations.
t i
GRAND GULF, UNIT 1 2.0-10b Revision 17 - 03/95
f 1
g TABLE 2.2-la PATHWAY DOSE FACTORS FOR LCO 6.11.4 and SECTION 2.2.1.b, (P )
i Page 1 of 2 AGE GROUP (INFANT)
(
N.A.
)
(INFANT)
ISOTOPE INHat2 TION GROrnm Prwir FOOD H-3 6.468E+02 0.000E+00 2.382E+03 C-14 2.646E+04 0.000E+00 2.340E+09 i
NA-24 1.056E+04 1.979E+07 1.542E+07 l
P-32 2.030E+06 0.000E+0u 1.602E+11 CR-51 1.284E+04 7.864E+06 4.700E+06 l
MN-54 9.996E+05 1.287E+09 3.900E+07 MN-56 7.16BE+04 1.525E+06 2.862E+00 l
FE-55 8.694E+04 0.000E+00 1.351E+08 FE-59 1.015E+06 4.562E+08 3.919E+08 CO-58 7.770E+05 6.194E+08 6.055E+07 CO-60 4.5085+06 5.172E+09 2.098E+08 NI-63 3.388E+05 0.000E+00 3.493E+10 NI-65 5.012E+04 4.930E+05 3.020E+01 CD-64 1.498E+04 9.823E+05 3.807E+06 IN-65 6.4685+05 7.907E+08 1.904E+10 l
EN-69 1.322E+04 0.000E+00 3.855E-09 l
BR-83 3.80BI+02 1.011E+04 9.339E-01 BR-84 4.004E+02 3.376E+05 1.256E-22 BR-85 2.044E+01 0.000E+00 0.000E+00 RB-86 1.904E+05 1.4785+07 2.234E+10 RB-88 5.572E+02 5.399E+04 1.874E-44 RB-89 3.206E+02 2.075E+05 4.193E-53 SR-89 2.030E+06 3.560E+04 1.258E+10 SR-90 4.088E+07 0.000E+00 1.216E+11 SR-91 7.336E+04 3.587E+06 3.215E+05 SR-92 1.400E+05 1.233E+06 5.005E+01 Y-90 2.688E+05 7.583E+03 9.406E+05 Y-91M 2.786E+03 1.658E+05 1.876E-15 Y-91 2.450E+06 1.702E+06 5.251E+06 Y-92 1.266E+05 3.060E+05 1.026E+01 Y-93 1.666E+05 3.620E+05 1.776E+04 ZR-95 1.750E+06 3.975E+08 8.257E+05 ZR-97 1.400E+05 4.921E+06 4.446E+04 NB-95 4.788E+05 2.291E+08 2.062E+0B MO-99 1.34BE+05 6.608E+06 3.10BE+0B TC-99M 2.030E+03 3.013E+05 1.646E+04 TC-101 8.442E+02 3.253E+04 1.423E-56 RU-103 5.516E+05 1.804E+08 1.055E+05 RU-105 4.844E+04 1.030E+06 3.204E+00 RU-106 1.156E+07 3.590E+08 1.445E+06 AG-110M 3.668E+06 3.649E+09 1.4&iE+10 i
l j
GRAND GULF, UNIT 1 2.0-11.
Revision 17 - 03/95
1 1
l l
Tant
- 2.2-la (cant 4nuadi PATHWAY DOSE FACTnna poE tm g,ii,4 nA SECTION 2.2.1.b, (P )
j g
Page 2 of 2 I
AGE danUp (INFANT)
(
N.A.
)
(INFANT)
ISOMPE Tw ifATION mme 97 Am FOGL TE-125M 4.466E+05 3.001E+06 1.500E+08 TE-127M 1.312E+06 1.395E+05 1.037E+09 l
TE-127 2.436E+04 4.704E+03 1.359E+05 TE-129M 1.680E+06 3.290E+07 1.392E+09 TE-129 2.632E+04 4.395E+04 1.678E-07 TE-131M 1.988E+05 1.351E+07 2.288E+07 TE-131 0.218E+03 4.929E+07 1.3845-30 TE-132 3.402E+05 7.0985+06 6.513E+07 l
I-130 1.596E+06 9.560E+06 8.754E+08 l
I-131 1.484E+07 2.985E+07 1.053E+12 I-132 1.694E+05 2.075E+06 1.188E+02 I-133 3.554E+06 4.2595+06 9.601E+09 I-134 4.452E+04 7.5785+05 8.402E-10 I-135 6.9585+05 4.210E+06 2.002E+07 l
CS-134 7.0285+05 3.282E+09 6.801E+10 CS-135 1.345E+05 2.432E+08 5.795E+09 l*
CS-137 6.118E+05 1.3375+09 6.024E+10 CS-138 8.764E+02 5.860E+05 2.1805-22 l
RA-139 5.0965+04 1.705E+05 2.874E-05 RA-140 1.596E+06 3.352E+07 2.410E+08 RA-141 4.746E+03 6.762E+04 3.1415-44 l
RA-142 1.554E+03 7.234E+04 0.000E+00 LA-140 1.680E+05 3.114E+07 1.880E+05 LA-142 5.950E+04 1.269E+06 6.0192-06 CE-141 5.166E+05 2.1995+07 1.366E+07 l
CE-143 1.162E+05 3.753E+06 1.536E+06 CE-144 9.842E+06 6.761E+07 1.334E+08 PR-143 4.326E+05 0.000E+00 7.845E+05 PR-144 4.284E+03 3.0175+03 1.171E-48 CD-147 3.220E+05 1.441E+07 5.743E+05 W-187 3.962E+04 3.915E+06 2.501E+06 NP-239 5.950E+04 2.823E+06 9.400E+04 3
Inhalation 2 nd all tritium pathways - arem/yr per pCi/m Units:
a Others - m. mres/yr per gCi/see Values based on standard NUREG-0133, Section $.2.1 assumptions unless otherwise indicated.
i GRAND GULF, UNIT 1 2.0-12 Revision 17 - 03/95
r
{
l l
t l
I TABLE 2.2-lb l
i l1 TEXT DELETED 1
l GRAND GULF, UNIT 1 2.0-13 Revision 21 - 12/97 m,..
TABLE 2.2-1b (Continued) 1 I
i l
TEXT DELETED l
l GRAND GULF, UNIT 1 2.0-14 Revision 21 - 12/97
~. ~.
TABLE 2.2-2a PATHWAY DOSE FACTORB FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )
Page 1 of 2 AGE nanUP
(
INFANT
)
(
N.A.
)
(
imiFaaPF
)
(
TMFANT )
( INFANT
)
ISOTOPE Tim fATION nante pr.an ann / COW!Mit.r ana/ COW / MEAT VEGETATION H-3 6.468E+02 0.000E+00 2.3820 03 0.000E+00 0.000E+00 C-14 2.646E+04 0.000E+00 2.340E+C) 0.000E+00 0.000E+00 NA-24 1.056E+04 1.385E+07 1.542E+07 0.000E+00 0.000E+00 P-32 2.030E+06 0.000E+00 1.602E+11 0.000E+00 0.000E+00 CR-51 1.284E+04 5.506E+06 4.700E+06 0.000E+00 0.000E+00 MN-54 9.996E+05 1.625E+09 3.900E+07 0.000E+00 0.000E+00 MN-56 7.168E+04 1.068E+06 2.862E+00 0.000E+00 0.000E+00 FE-55 8.694E+04 0.000E+00 1.351E+08 0.000E+00 0.000E+00 FE-59 1.015E+06 3.204E+08 3.9195+08 0.000E+00 0.000E+00 CO-58 7.770E+05 4.464E+08 6.055E+07 0.000E+00 0.000E+00 CO-60 4.5085+06 2.532E+10 2.0985+08 0.000E+00 0.000E+00 NI-63 3.388E+05 0.000E+00 3.493E+10 0.000E+00 0.000E+00 NI-65 5.012E+04 3.451E+05 3.020E+01 0.000E+00 0.000E+00 CD-64 1.4985+04 6.876E+05 3.807E+06 0.000E+00 0.000E+00 EN-65 6.468E+05 8.583E+08 1.904E+10 0.000E+00 0.000E+00 ZN-69 1,322E+04 0.000E+00 3.855E-09 0.000E+00 0.000E+00 ER-83 3.8083+02 7.0795+03 9.3393-01 04000E+00 0.000E+00 EA-84 4.004E+02 2.363E+05 1.2565-22 0.000E+00 0.000E+00 BR-85 2.044E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RE-86 1.904E+05 1.035E+07 2.234E+10 0.000E+00 0.000E+00 RE-SS 5.572E+02 3.7795+04 1.874E-44 0.000E+00 0.000E+00 RE-89 3.206E+02 1.452E+05 4.193E-53 0.000E+00 0.000E+00 SR-89 2.030E+06 2.'095+04 1.258E+10 0.000E+00 0.000E+00 SR-90 4.088E+07 0.000E+00 1.2165+11 0.000E+00 0.000E+00 SR-91 7.336E+04 2.511E+06 3.215E+05 0.000E+00 0.000E+00 SR-92 1.400E+05 0.631E+05 5.005E+01 0.000E+00 0.000E+00 Y-90 2.688E+05 5.3085+03 9.406E+05 0.000E+00 0.000E+00 Y-91M 2.786E+03 1.161E+05 1.876E-15 0.000E+00 0.000E+00 Y-91 2.450E+06 1.2075+06 5.251E+06 0.000E+00 0.000E+00 Y-92 1.266E+05 2.142E+05 1.02EE+01 0.000E+00 0.000E+00 Y-93 1.666E+05 2.534E+05 1.7765+04 0.000E+00 0.000E+00 ZR-95 1.750E+06 2.8375+00, 8.257E+05 0.000E+00 0.000E+00 ZR-97 1.400E+05 3.445E+06 4.446E+04 0.000E+00 0.000E+00 NE-95 4.7883+05 1.605E+08 2.062E+08 0.000E+00 0.000E+00 MD-99 1.340E+05 4.62EE+06 3.1085+08 0.000E+00 0.000E+00 TC-99M 2.030E+03 2.1095+05 1.646E+04 0.000E+00 0.000E+00 TC-101 8.442E+02 2.277E+04 1.4235-56 0.000E+00 0.000E+00 RU-103 5.5165+05 1.265E+08 1.055E+05 0.000E+00 0.000E+00 RU-105 4.844E+04 7.212E+05 3.204E+00 0.000E+00 0.000E+00 RU-106 1.1565+07 5.049E+08 1.445E+06 0.000E+00 0.000E+00 AG-110M 3.6485+06 4.019E+09 1.461E+10 0.000E+00 0.000E+00 GRAND GULF, UNIT 1 2.0-15 Revision 17 - 03/95
TABLE 2.2-2a (continued)
PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )
Page 2 of 2 AGE GROUP
(
INFANT
)
(
N.A.
)
(
INFANT
)
(
INFANT
)
( INFANT )
ISOTOPE IW172 TION caown PrAn nam / cow /gII.E nac/ COW / MEAT VEGETATION TE-125M 4.4663+05 2.128E+06 1.5085+08 0.000E+00 0.000E+00 TE-127M 1.312E+06 1.083E+05 1.037E+09 0.000E+00 0.000E+00 TE-127 2.4365+04 3.293E+03 1.359E+05 0.000E+00 0.000E+00 TE-12fM 1.680E+06 2.305E+07 1.392E+09 0.000E+00 0.000E+00 TE-129 2.632E+04 3.076E+04 1.6788-07 0.000E+00 0.000E+00 l
TE-131M 1.988E+05 9.459E+06 2.288E+07 0.000E+00 0.000E+00 TE-131 8.218E+03 3.450E+07 1.3845-30 0.000R+00 0.000E+00 TE-132 3.402E+05 4.9683+06 6.513E+07 0.000E+00 0.000E+00 I-130 1.596E+06 6.692E+06 8.754E+08 0.000E+00 0.000E+00 I-131 1.484E+07 2.089E+07 1.053E+12 0.000E+00 0.000E+00 I-132 1.694E+05 1.452E+06 1.1885+02 0.000E+00 0.000E+00 I-133 3.556E+06 2.981E+06 9.601E+09 0.000E+00 0.000E+00 I-134 4.452E+04 5.305E+05 8.4025-10 0.000E+00 0.000E+00 I-135 6.9585+05 2.9475+06 2.002E+07 0.000E+00 0.000E+00 CS-134 7.020E+05 8.007E+09 6.801E+10 0.000E+00 0.000E+00 CS-136 1.345E+05 1.702E+08 5.795E+09 0.000E+00 0.000E+00 CS-137 6.118E+05 1.201E+10 6.024E+10 0.000E+00 0.000E+00 CS-138 8.764E+02 4.102E+05 2.1805-22 0.000E+00 0.000E+00 RA-139 5.096E+04 1.194E+05 2.8743-05 0.000E+00 0.000E+00 BA-140 1,596E+06 2.3465+07 2.410E+08 0.000E+00 0.000E+00 RA-141 4.746E+03 4.734E+04 3.1415-44 0.000E+00 0.000E+00 BA-142 1.554E+03 5.064E+04 0.000E+00 0.000E+00 0.000E+00 LA-140 1.680E+05 2.180E+07 1.880E+05 0.000E+00 0.000E+00 LA-142 5.950E+04 8.886E+05 6.0193-06 0.000E+00 0.000E+00 CE-141 5.166E+05 1.540E+07 1.3665+07 0.000E+00 0.000E+00 CE-143 1.162E+05 2.6275+06 1.5365+06 0.000E+00 0.000E+00 CE-144 9.842E+06 8.032E+07 1.334E+08 0.000E+00 0.000E+00 PR-143 4.326E+05 0.000E+00 7.845E+05 0.000E+00 0.000E+00 PR-144 4.284E+03 2.112E+03 1.171E-48 0.000E+00 0.000E+00 ND-147 3.220E+05 1.009E+07 5.743E+05 0.000E+00 0.000E+00 W-187 3.962E+04 2.740E+06 2.501E+06 0.000E+00 0.000E+00 NP-239 5.950E+04 1.9765+06 9.400E+04 0.000E+00 0.000E+00 3
Units:
Inhalation 2and all tritium pathways - mrom/yr per pCi/m Others - m. mrom/yr per pC1/sec values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.
l GRAND GULF, UNIT 1 2.0-16 Revision 17 - 03/95
Taafm 2.2-2b PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )
g Page 1 of 2 AGE GROUP
(
cMTLD )
(
N.A.
)
(
FWTLD
)
(
CHILD
)
( CHILD
)
ISOTOPE INW1YATION nomam pt uu non/ COW /Mfiz ann / COW / MEAT VEGETATION H-3 1.125E+03 0.000E+00 1.570E+03 2.341E+02 4.000E+03 l
4 C-14 3.589E+04 0.000E+00 1.195E+09 3.834E+08 8.894E+08 NA-24 1.610E+04 1.385E+07 8.853E+06 1.725E-03 3.729E+05 P-32 2.605E+06 0.000E+00 7.775E+10 7.411E+09 3.366E+09 CR-51 1.698E+04 5.506E+06 5.398E+06 4.661E+05 6.213E+06 MN-54 1.5765+06 1.625E+09 2.097E+07 8.011E+06 6.648E+08 MN-56 1.232E+05 1.068E+06 1.865E+00 2,437E-51 2.723E+03 FE-55 1.110E+05 0.000E+00 1.118E+08 4.571E+08 8.012E+08 FE-59 1.2695+06 3.204E+08 2.025E+08 6.330E+08 6.693E+08 CO-58 1.1065+06 4.464E+08 7.080E+07 9.596E+07 3.771E+08 CO-60 7.067E+06 2.532E+10 2.391E+08 3.8385+08 2.095E+09 NI-63 8.214E+05 0.000E+00 2.964E+10 2.912E+10 3.949E+10 NI-65 8.399E+04 3.451E+05 1.909E+01 4.061E-51 1.211E+03 CU-64 3.670E+04 6.876E+05 3.502E+06 1.393E-05 5.159E+05 ZN-65 9.953E+05 8.583E+08 1.101E+10 1.000E+09 2.164E+09 ZN-69 1.0185+04 0.000E+00 1.1235-09 0.000E+00 9.893E-04 BR-83 4.736E+02 7.079E+03 4.3995-01 9.5193-57 5.3695+00 BR-84 5.4765+02 2.363E+05 6.5085-23 0.000E+00 3.8225-11 BR-85 2.531E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RE-86 1.983E+05 1.035E+07 8.804E+09 5.816E+08 4.584E+08 RE-88 5.624E+02 3.779E+04 7.150M-45 0.000E+00 4.374E-22 RB-89 3.452E+02 1.452E+05 1.7155-53 0.000E+00 1.642E-26 SR-89
'2.157E+06 2.509E+04 6.6185+09 4.815E+08 3.593E+10 SR-90 1.010E+08 0.000E+00 1.1175+11 1.040E+10 1.243E+12 SR-91 1.739E+05 2.511E+06 2.8785+05 5.292E-10 1.157E+06 I
SR-92 2.424E+05 8.631E+05 4.134E+01 3.492E-48 1.378E+04 Y-90 2.679E+05 5.308E+03 9.171E+05 4.879E+G5 6.5$9E+07 Y-91M 2.812E+03 1.161E+05 5.198E-16 0.000E+00 1.737E-05 Y-91 2.627E+06 1.207E*06 5.1995+06 2.400E+08 2.484E+09 Y-92 2.390E+05 2.142E+05 7.310E+00 6.9595-35 4.576E+04 Y-93 3.885E+05 2.534E+05 1.573E+04 1.5475-07 4.482E+06 ZR-95 2.231E+06 2.8375+08 8.7865+05 6.106E+08 8.843E+08 ZR-97 3.5115+05 3.445E+06 4.1995+04 7.015E-01 1.2485+07 NE-95 6/142E+05 1.605E+08 2.2875+08 2.2285+09 2.949E+08 MO-99 1.354E+05 4.6265+06 1.7385+08 2.456E+05 1.6475+07 TC-99M 4.810E+03 2.109E+05 1.474E+04 6.915E-18 5.255E+03 TC-101 5.846E+02 2.2775+04 5.593I-58 0.000E+00 4.123E-29 RU-103 6.623E+05 1.265E+08 1.108E+05 4.0095+09 3.971E+08 RU-105 9.953E+04 7.212E+05 2.493E+00 5.885E-25 5.981E+04
.RU-106 1.432E+07 5.0495+08 1.437E+06 6.902E+10 1.159E+10 AG-110M 5.476E+06 4.019E+09 1.6785+10 6.742E+01 2.581E+09 GRAND GULF, UNIT 1 2.0 17 Revision 17 - 03/95 1
TABLE 2.2-2b (Continuad)
PATHWAY DOSE FACTORS FOR LCQ 6.11.6 AND SECTION 2.2.2.b, (R )
g Page 2 of 2 AGE GROUP
(
CHILD
)
(
A.A.
)
(
(9tTim
)
(
SILD
)
( (7t t LD
)
ISOTOPE IM'afATION GROtFAD pr. mare ana/ cog /pffE non/ cow / MEAT vgGETATION TE-125M 4.773E+05 2.1283+06 7.377E+07 5.690E+00 3.506E+08 TE-127M 1.40CE*06 1.013E+05-5.932E+08 5.060E+09 3.769E+09
'l TE-127 5.624Ec04 3.293E+03 1.191E+05 1.607E-08 3.903E+05 TE-129M 1.761E+06 2.305E+07 7.961E+08 5.245E+09 2.460E+09 TE-129 2.5495+04 3.076E+04 6.166E 00 0.000E+00 7.204E-02 TE-131M 3.078E+05 9.459E+06 2.244E+07 9.815E+03 2.163E+07 TE-131 2.054E+03 3.450E+07 8.4095-32 0.000E+00 1.349E-14 TE-132 3.774E+05 4.9685+06 4.551E+07 9.325E+06 3.111E+07 I-130 1.846E+06 6.692E+06 3.845E+08 6.758E-04 1.370E+08 I-131 1.624E+07 2.089E+07 4.333E+11 5.503E+09 4.754E+10 I-132 1.935E+05 1.452E+06 5.1295+01 2.429E-57 7.314E+03 I-133 3.8485+06 2.981E+06 3.945E+09 1.304E+02 8.113E+08 I-134 5.0695+04 5.305E+05 3.624E-10 0.000E+00 6.622E-03 I-135 7.910E+05 2.947E+06 0.6075+06 1.0395-14 9.973E+06 CS-134 1.014E+06 8.007E+09 3.715E+10 1.513E+09 2.631E+10 CS-136 1.709E+05 1.702E+00 2.773E+09 4.426E+07 2.247E+08 CS-137 9.065E+05 1.201E+10 3.224E+10 1.334E+09 2.392E+10 CS-138 8.399E+02 4.102E+05 5.5285-23 0.000E+00 9.1335-11 RA-139 5.772E+04 1.194E+05 1.2315-05 0.000E+00 2.950E+00 RA-140 1.743E+06 2.346E+07 1.171E+08 4.384E+07 2.7675+08 BA-141 2.9195+03 4.734E+04 1.2105-45 0.000E+00 1.6055-21 RA-142 1.643E+03 5.064E+04 0.000E+00 0.000E+00 4.105E-39 LA-140 2.257E+05 2.100E+07 1.894E+05 5.492E+02 3.166E+07 LA-142 7.585E+04 8.886E+05 2.9045-06 0.000E+00 1.582E+01 CE-141 5.439E+05 1.540E+07 1.361E+07 1.382E+07 4.082E+08 CE-143 1.273E+05 2.627E+06 1.400E+06 2.516E+02 1.364E+07 CE-144 1.195E+C7 8.032E+07 1.326E+08 1.893E+08 1.039E+10 PR-14'J 4.329E+05 0.000E+00 7.754E+05 3.6095+07 1.575E+08 PR-144 1.565E+03 2.112E+03 2.0405-50 0.000E+00 3.8293-23 ND-147 3.202E+05 1.0093+07 5.712E+05 1.505E+07 9.197E+07 W-187 9.102E+04 2.740E+06 2.420E+06 2.790E+00 5.380E+06 NP-239 6.401E+04 1.9765+06 9.1385+04 2.232E+03 1.357E+07 3
Inhalation 2and all tritium pathways - mres/yr per gci/m Units:
Others - m mres/yr per gci/sec Values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.
l GRAND GULF, UNIT 1 2.0-10 Revision 17 - 03/95 i
]
I I
Tant r 2.2-2c PATHWAY DOSE FACTORS FOR LCO 6.11.6 AMD SECTION 2.2.2.b, (R )
Page 1 of 2 AGE GROUP (TTFNadfD)
(
N.A.
1
(-i-4 622)
( Trs mricFD )
(TEENAI.d 7 ISOTOPE INHALATION cnortarn pr tire nos/ COW / MILE nac/ COW / MEAT VEGETATION H-3 1.272E+03 0.000E+00 9.941E+02 1.938E+02 2.588E+03 C-14 2.600E+04 0.000E+00 4.8595+08 2.040E+08 3.690E+08 NA-24 1.3765+04 1.385E+07 4.255E+06 1.084E-03 2.389E+05 P-32 1.888E+06 0.000E+00 3.153E+10 3.931E+09 1.608E+09 CR-51 2.096E+04 5.506E+06 8.3875+06 9.471E+05 1.037E+07 MN-54 1.984E+06 1.625E+09 2.875E+07 1.436E+07 9.320E+08 MN-56 5.744E+04 1.068E+06 4.856E-01 8.302E-52 9.451E+02 FE-55 1.240E+05 0.000E+00 4.454E+07 2.382E+0B 3.259E+08 FE-59 1.52SE+06 3.204E+0B 2.8613408 1.171E+09 9.895E+08 CO-58 1.344E+06 4.464E+08 1.095E+08 1.942E+08 6.034E+08 CO-60 8.720E+06 2.532E+10 3.621E+08 7.600E+08 3.238E+09 NI-63 5.800E+05 0.000E+00 1.182E+10 1.519E+10 1.606E+10 NI-65 3.672d+04 3.451E+05 4.692E+00 1.305E-51 3.966E+02 CU-64 6.144E+04 6.8765+05 3.293E+06 1.713E-05 6.465E+05 ZN-65 1.240E+06 8.583E+08 7.315E+09 8.6885+08 1.471E+09 ZN-69 1.584E+03 0.000E+00 1.7605-11 0.000E+00 2.067E-05 BR-83 3.440E+02 7.079E+03 1.790E-01 5.0665-57 2.911E+00 BR-84 4.328E+02 2.363E+05 2.8775-23 0.000E+00 2.2515-11 BR-85 1.832E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-36 1.904E+05 1.035E+07 4.746E+09 4.101E+08 2.772E+08 RB-88 5.456E+02 3.779E+04 3.886E-45 0.000E+00 3.168E-22 RB-89 3.520E+02 1.452E+05 9.774E-54 0.000E+00 1.247E-26 SR-89 2.416E+06 2.509E+04 2.674E+09 2.545E+08 1.513E+10 SR-90 1.050E+0B 0.000E+00 6.612E+10 8.049E+09 7.507E+11 SR-91 2.592E+05 2.511E+06 2.4095+05 5.794E-10 1.291E+06 SR-92 1.192E+05 8.631E+05 2.277E+01 2.516E-48 1.012E+04 Y-90 5.592E+05 5.300E+03 1.074E+06 7.470E+05 1.025E+08 Y-91M 3.200E+03 1.161E+05 5.129E-18 0.000E+00 2.285E-07 Y-91 2.9365+06 1.207E+06 6.475E+06 3.910E+08 3.212E+09 Y-92 1.648E+05 2.142E+05 2.8285+00 3.522E-35 2.360E+04 Y-93 5.792E+05 2.534E+05 1.312E+04 1.688E-07 4.983E+06 ZR-95 2.688E+06 2.837E+08 1.201E+06 1.092E+09 1.253E+09 ZR-97 6.304E+05 3.445E+06 4.225E+04 9.231E-01 1.673E+07 NS-95 7.512E+05 1.605E+08 3.338E+0B 4.251E+09 4.551E+08 MO-99 2.6885+05 4.626E+06 1.023E+08 1.392E+05 1.293E+07 TC-99M 6.128E+03 2.109E+05 1.055E+04 6.471E-18 5.011E+03 TC-101 6.672E+02 2.277E+04 3.287E-58 0.000E+00 3.229E-29 RU-103 7.832E+05 1.265E+08 1.513E+05 7.162E+09 5.706E+0B RU-105 9.040E+04 7.212E+05 1.263E+00 3.900E-25 4.039E+04 RU-106 1.608E+07 5.049E+08 1.799E+06 1.130E+11 1.484E+10 AG-110M 6.752E+06 4.019E+09 2.559E+10 1.345E+0F 4.031E+09 GRAND GULF, UNIT 1 2.0-19 Revision 17 - 03/95
TABLE 2. 2-2e (Centinuad)
PA'fMWAY DOSE FAC"PORS FOR LCO 6.11. 6 AND SECTION 2.2.2.b, (R )
g Page 2 of 2 (1----wicyn )
AGE GROUP (TEFuhn**)
(
N.A.
)
h--ainen) h..ainra)
ISOTOPE INH _hf 2 TION GROfMn Pf MW cBR/ CON /MTLE nam / COW / MEAT VEGETATION TE-125M 5.360E+05 2.120E+06 8.863E+07 8.941E+08 4.375E+08 TE-127M 1.656E+06 1.003E+05 3.420E+08 3.816E+09 2.236E+09 TE-127 8.080E+04 3.293E+03 9.572E+04 1.689E-08 4.180E+05 TE-129M 1.976E+06 2.305E+07 4.602E+08 3.966E+09 1.508E+09 TE-129 3.296E+03 3.076E+04 2.196E-09 0.000E+00 3.418E-03 TE-131M 6.208E+05 9.4595+06 2.529E+07 1.447E+04 3.248E+07 TE-131 2.336E+03 3.450E+07 2.879E-32 0.000E+00 6.099E-15 TE-132 4.632E+05 4.9684+06 8.581E+07 2.300E+07 7.818E+07 I-130 1.488E+06 6.692E+06 1.742E+08 4.005E-04 8.276E+07 I-131 1.464E+07 2.089E+07 2.195E+11 3.645E+09 3.140E+10 I-132 1.512E+05 1.452E+06 2.242E+01 1.389E-57 4.262E+03 I-133 2.920E+06 2.981E+06 1.674E+09 7.234E+01 4.587E+08 I-134 3.952E+04 5.305E+05 1.583E-10 0.000E+00 3.8545-03 I-135 6.200E+05 2.947E+06 3.7775+06 5.963I-15 5.832E+06 CS-134 1.1285+06 8.007E+09 2.310E+10 1.231E+09 1.6715+10 CS-136 1.936E+05 1.702E+08 1.75SI+09 3.671E+07 1.708E+08 CS-137 8.480E+05 1.201E+10 1.781E+10 9.634E+08 1.3485+10 CS-138 8.560E+02 4.102E+05 3.149E-23 0.000E+00 6.9355-11 RA-139 6.464E+03 1.194E+05 7.741E-07 0.000E+00 2.472E-01 RA-140 2.032E+06 2.3465+07 7.483E+07 3.663E+07 2.130E+08 RA-141 3.288E+03 4.734E+04 4.9225-46 0.000E+00 8.699E-22 RA-142 1.912E+03 5.064E+04 0.000E+00 0.000E+00 2.269E-39 LA-140 4.872E+05 2.180E+07 2.291E+05 8.689E+02 5.104E+07 LA-142 1.200E+04 8.886E+05 2.5745-07 0.000E+00 1.868E+00 CE-141 6.136E+05 1.540E+07 1.696E+07 2.252E+07 5.404E+0B CE-143 2.552E+05 2.627E+06 1.671E+06 3.695E+02 2.040E+07 CE-144 1.336E+07 8.032E+07 1.655E+08 3.089E+08 1.326E+10 PR-143 4.832E+05 0.000E+00 9.553E+05 5.817E+07 2.310E+08 PR-144 1.752E+03 2.112E+03 1.238E-53 0.000E+00 3.097E-26 ND-147 3.720E+05 1.009E+07 7.116E+05 2.452E+07 1.424E+08 W-187 1.768E+05 2.740E+06 2.646E+06 3.989E+00 7.839E+06 NP-239 1.320E+05 1.976E+06 1.060E+05 3.387E+03 2.097E+07 Units:
Inhalation 2and all tritium pathways ares /yr per pCi/m Others - m mram/yr per pCi/sec Valus;. based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.
GRAND GULF, UNIT 1 2.0-20 R'evision 17 - 03/95
Tant m 2.2 -2d PA'MrWAY mew Fpaa yon tm g.11.5 AMD SECTION 2.2.2.b, (R )
Page 1 of 2 AGE noncP t ADcLT )
(
m.
A.
1
(
- n_rtf t
)
( AorfLt
)
(
ADtfLT )
IscyrOPE INFauTION MA - PT *"
ane/ cog /witr nne/ CON /* *T VE6 m TION H3 1.264E+03 0.000E+00 7.629E+02 3.2485+02 2.260E+03 C-14 1.8165+04 0.000E+00 2.634E+08 2.414E+08 2.2765+08 MA 24 1.024E+04 1.385E+07 2.4385+06 1.356E 03 2.690E+05 P-32 1.320E+06 0.000E+00 1.7095+10 4.651E+09 1.403E+09 CR-51 1.440E+04 5.5065+06 7.1875+06 1.772E+06 1.1685+07 MN-54 1.400E+06 1.625E+09 2.5785+07 2.812E+07 9.585E+08 MN-56 2.024E+04 1.0685+06 1.3285-01 4.958E-52 5.082E+02 FE-55 7.208E+04 0.000E+00 2.511E+07 2.933E+08 2.0965+08 i
FE-59 1.0165+06 3.204E+08 2.3265+08 2.080E+09 9.875E+08 i
CO-58 9.280E+05 4.464E+08 9.565E+07 3.703E+08 6.252E+08 CO 60 5.9685+06 2.532E+10 3.082E+08 1.413E+09 3.1395+09 NI 63 4.320E+05 0.000E+00 6.7295+09 1.0885+10 1.040E+10 NI 65 1.232E+04 3.451E+05 1.2195+00 7.405E-52 2.0265+02 CD-64 4.8965+04 6.8765+05 2.031E+06 2.307E-05 7.841E+05 i
ZN 65 8.640E+05 8.583E+08 4.365E+09 1.132E+09 1.009E+09 KN-69 9.200E+02 0.000E+00 5.2075 12 0.000E+00 1.202E 05 i
IR-83 2.404E+02 7.079E+03 1.3995 01 8.6485-57 4.475E+00 ER-84 3.128E+02 2.363E+05 1.6095 23 0.000E+00 2.4755-11 ER-85 1.280E+01 0.000E+00 0.000E+00 0.0005^00 0.000E+00 RI 86 1.352E+05 1.035E+07 2.604E+09 4.914E+08 2.2175+08 RB-88 3.872E+02 3.779E+04 2.1395-45 0.000E+00 3.4285 22 j
RB-89 2.560E+02 1.452E+05 5.5235 54 0.000E+00 1.3855-26 i
I SR 89 1.400E+06 2.5095+04 1.451E+09 3.014E+08 9.961E+09 SR 90 9 920E+07 0.000E+00 4.680E+10 1.244E+10 6.046E+11 SR 91 1.912B+05 2.511E+06 1.377E+05 7.2335-10 1.451E+06 SR 92 4.304E+04 8.631E+05 9.675E+00 2.3345 48 8.452E+03 Y-90 5.056E+05 5.3085+03 7.511E+05 1.141E+06 1.410E+08 Y-91M 1.920E+03 1.161E+05 1.7435-19 0.000E+00 1.527E 08 Y-91 1.704E+06 1.2075+06 4.7265+06 6.231E+08 2.814E+09 Y-92 7.352E+C4 2.142E+05 9.7725-01 2.6575 35 1.603E+04 Y-93 4.2165+05 2.534E+05 7.3885+03 2.0755 07 5.5175+06 ZR-95 1.7685+06 2.837E+08 9.5875+05 1.903E+09 1.194E+09 ZR-97 5.232E+05 3.445E+06 2.7075+04 1.292E+00 2.1085+07 NE 95 5.0485+05 1.625E+08 2.7865+08 7.748E+09 4.7985+08 MO-99 2.480E+05 4.626E+06 5.741E+07 2.3183+05 1.426E+07 TC 99M 4.160E+03 2.109E+05 5.553E+03 7.4395-18 5.187E+03 TC-101 3.992E+02 2.2775+04 1.8135-58 0.000E+00 3.502E 29 RU-103 5.0485+05 1.265E+08 1.1895+05 1.229E+10 5.5775+08 RU 105 4.8165+04 7.212E+05 5.240E-01 3.533E-25 3.294E+04 RU 106 9.360E+06 5.049E+08 1.320B+06 1.811E+11 1.2475+10 AG 110M 4.632E+06 4.019E+09 2.1985+10 2.523E+09 3.979E+09 GEAND QULF, UNIT 1 2.0 21 Eavision 17 - 03/95
Thate 2.2-2d (Continuad)
PATHWAY DOSE FACToma FOR LCO 6.11.6 AMD, SECTION 2.2.2.b, (R )
Page 2 of 2 AGE dBotJP
(
ADtfLT )
(
M.
A.
)
(
ADtfLT )
(
ADtJLT
)
(
ADifLT )
amm-e prim ana/COM/MTLE ana/ COW / MEAT VEGETATION ISOTOPE TW172TIOg TE-125M 3.136E+05 2.128E+06 6.6265+07 1.460E+09 3.927E+08 TE-127M 9.600E+05 1.083E+05 1.860E+08 4.531E+09 1.418E+09 TE-127 5.735E+04 3.293E+03 5.2785+04 2.034E-08 4.532E+05 TE-129M 1.160E+06 2.305E+07 3.0285+08 5.6985+09 1.261E+09 TE-129 1.936E+03 3.0765+04 9.1675-10 0.000E+00 2.806E-0*
TE-131M 5.560E+05 9.4595+06 1.753E+07 2.190E+04 4.428E+07 TE-131 1.392E+03 3.450E+07 1.5783-32 0.000E+00 6.575E-15 TI-132 5.096E+05 4.9685+06 7.324E+07 4.287E+07 1.312E+08 I-130 1.136E+06 6.692E+06 1.050E+08 5.272E-04 9.809E+07 I-131 1.192E+07 2.0895+07 1.3885+11 5.034E409 3.785E+10 I-132 1.144E+05 1.452E+06 1.342E+01 1.816E-57 5.016E+03 I-133 2.152E+06 2.981E+06 9.891E^08 9.3365+01 5.331E+08 I-134 2.984E+04 5.305E+05 9.4915-11 0.000E+00 4.5445-03 I-135 4.480E+05 2.947E+06 2.2173+06 7.644E-15 6.731E+06 CS-134 8.480E+05 8.007E+09 1.345E+10 1.565E+09 1.110E+10 CS-136 1.464E+05 1.702E+08 1.036E+09 4.724E+07 1.675E+08 CS-137 6.208E+05 1.201E+10 1.010E+10 1.193E+09 8.696E+09 CS-138 6.2085+02 4.102E+05 1.7865-23 0.000E+00 7.7305-11 RA-139 3.760E+03 1.194E+05 8.3225-08 0.000E+00 5.2255-02 RA-140
- 1. 272 E+06 2.346E+07 5.535E+07 5.9175+07 2.646E+08 BA-141 1.9365+03 4.734E+04 2.6775-46 0.000E+00 9.3055-22 RA-142 1.192E+03 5.064E+04 0.000E+00 0.000E+00 2.463E-39 LA-140 4.584E+05 2.180E+07 1.672E+05 1.385E+03 7.327E+07 LA-142 6.328E+03 8.8865+05 3.503E-08 0.000E+00 4.999E-01 CE-141 3.616E+05 1.540E+07 1.253E+07 3.632E+07 5.097E+08 CE-143 2.264E+05 2.627E+06 1.149E+06 5.547E+02 2.758E+07 CE-144 7.776E+06 8.032E+07 1.209E+08 4.9285+08 1.112E+10 PR-143 2.800E+05 0.000E+00 6.923E+05 9.204E+07 2.748E+08 PR-144 1.016E+03 2.112E+03 6.716E-54 0.000E+00 3.303E-26 ND-147 2.200E+05 1.009E+07 5.231E+05 3.935E+07 1.853E+08 W-187 1.552E+05 2.740E+06 1.7965+06 5.912E+00 1.046E+07 NP-239 1.192E+05 1.9765+06 7.385E+04 5.152E+03 2.872E+07 1
Units:
Inhalation 2and all tritium pathways - mres/yr per pCi/m others - m mres/yr per pCi/sec values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.
e GRAND GULF, UNIT 1 2.0-22 Revision 17 - 03/95
l TABLE 2.2-3 CONTROLLING RECEPTORS, LOCATIONS, AND ATMOSPHERIC DISPERSION PAPAMETERS*
for LCO 6.11.5.
6.11.6, AND 6.11.8 NEAREST RESIDENCE, NEAREST SECTOR DIRECTION MILES **
D/Q x/Q D/Q
- GARDEN, MILES **
A N
0.92 6.3E-9 3.30E-6
>5 N/A l
B NNE 0.75 6.18E-9 2.95E-6
>5 N/A l
C NE 0.66 6.1E-9 2.30E-6 4.78 2.18E-10 D
ENE 2.67 4.9E-10 2.00E-7 2.8 4.90E-10 l
E E
0.81 2.96E-9 1.60E-6 0.81 2.96E-09 F
ESE 2.3 6.5E-10 2.57E-7
>5 N/A G
SE 2.11 7.7E-10 3.10E-7
>5 N/A H
SSE 1.13 3.6E-9 1.40E-6 3.7 4.98E-10 l
J S
3.11 7.65E-10 4.95E-7
>5 N/A j
K SSW 2.17 1.3E-9 1.40E-6 2.17 1.30E-9 L
SW 0.89 6.7E-9 8.30E-6 0.89 6.70E-9 M
WSW
>5 N/A N/A
>5 N/A N
W
>5 N/A N/A
>5 N/A P
WNW 4.78 2.3E-10 4.73E-7 4.78 2.30E-10 Q
NW
>5 N/A N/A
>5 N/A R
NNW 1.08 3.6E-9 2.60E-6
>5 N/A l
Table 2.2-3 based on 1995 Land Use Census, onsite gardens are not considered for the j.
Land Use Census.
The most limiting age group, child, is assumed.
Values from CDCM Reference 9.
Distances shown are actual miles in each sector.
In cases where dispersion parameters were not available for a location they were taken from the closest distance interval to the plant.
N/A: No residence / garden within 5 miles.
GRAND GULF, UNIT 1 2.0-23 Revision 18 - 02/96 L
TAILE 2.2-3a SITE BOUNDARY AIMOSPEERIC DISPERSION PARAMETERS
- for LEO 6.11.4 SITE BOUNDARY
- DISTANCE, SECTOR DIRECTION MILES **
x/Q D/Q A
N 0.79 4.1E-6 8.2E-9 B
NNE 0.66 3.6E-6 7.7E-9 C
NE 0.63 2.5E-6 6.6E-9 D
ENE 0.63 2.0E-6 5.8E-9 E
E 0.55 1.9E-6 4.9E-9 F
ESE 0.55 2.0E-6 5.9E-9 G
SE 0.51 2.8E-6 8.25-9 H
SSE 0.46 5.6E-6 1.6E-8 J
S 0.51 5.85-6 1.2E-8 K
SSW 0.65 0.4E-6 1.0E-S L
SW 0.85 0.9E-6 7.2E-9 M
WSW 1.07 8.45-6 5.1E-9 N
W 1.14 5.4E-6 3.4E-9 P
WNW 1.34 2.6E-6 1.9E-9 Q
NW 1.37 1.6E-6 1.6E-9 R
NNW 1.02 2.0E-6 4.0E-9 The most limiting age group, infant, is assumed.
Values from ODCM Reference 9.
Distances shown are actual allas in each sector.
l GRAND GULF, UNIT 1 2.0-23a Revision 17 - 03/95
l 1
1 TARTE 2.2-3h ADDITIN17 RECEPTOR IZX'ATIONE WITNTM THE SITE BOUNDARY I
SECTOR DIRECTION MILES DESCRIPTION x/Q D/Q B
NNE 0.5 Recreational 5.438E-6 1.204E-8 Vehicle Laydown Area R
NNW 0.5 Energy 8.422E-6 1.310E-B Services Center' Q
NW 0.75 Gin Lake' 3.9583-6 4.531E-9 P
WNW 0.75 Hamilton Lake' 6.266E-6 5.215E-9
'These locations occupy multiple sectors. In each case the SITE BOUNDARY locations used in the dose calculation was limiting.
l GRAND GULF, UNIT 1 2.0-23b Revision 17 - 03/95
l 2.3 unteorolonical undal 2.3.1 Atmoscharic Disneraian The atmospheric dispersion for gaseous releases may be calculated using a ground level, wake split form of the straight line flow model.
atmospheric dispersion (sec/m*)
x/Q 2.02 ak rur where:
distance (m) from release point to location of r
f interest plume depletion factor at distance r free ODOE 6
=
Figure 2.3 1 wind speed at ground level (m/sec) u open terrain recirculation factor at distance r, k
frees CDCM Figure 2.3-4 (not used) the lesser of (a8 + hl) or /3 a E
1 where vertical standard deviation (m) of the plume at a
=
distance r for ground level releases under the stabilitycategoryindicatedbyh,fromCDCM Figure 2.3-2 h
temperature differential with vertical
=
separation (*K/100m) height of the reactor building. 57.3m b
=
GRAND GULF, CNIT 1 2.0-24 Revision 17 - 03/95 j
J
2.3.2 Denosition Relative deposition per unit area for all releases is calculated for a ground level release as follows:
D/Q - relative deposition per unit area (m-2)
{
(D )
=
9 I
where:
D
- relative deposition rate at distance r for ground level releases from ODCM Figure 2.3-3 X/Q and D/Q values were calculated using the methodology of NUREG/CR-2919 axoQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations".
GGNS gaseous releases are ground level.
Aaditional information on the X/Q and D/Q calculations can be found in ODCM References 9 and 10.
\\
1 GRAND GULF, UNIT 1 2.0-25 Revision 17 - 03/95
1 l
l I
" TEXT DELETED" l
1 GRAND GULF, UNIT 1 2.0-26 Revision 17 - 03/95
)
2.4 Definitions of Gameoua _Ef fluents Parapnatars height of reactor building (m) (2. 3.1) b
=
count rate of the station vent monitor corresponding to C
=
grab sample radionuclide concentrations (2.1.1) count rate of station vent monitor corresponding to a 1.0
)
C'
=
{
- C1/ml concentration of Xe-133 (2.1.2) i relative deposition rate for ground level releases from D
=
Figure 2.3-3 (m' ) (2.3.2)
D, average organ dose rate in current year (arem) ( 2. 2.1. b) dose to an individual from radiciodines and radionuclides in D
=
p particulate form, with half-life greater than eight days (ares)
(2.2.2.b)
D, average skin dose rate in current year (aren) (2.2.1.a) average total body dose rate in current year (arem)
D
=
g (2. 2.1. a )
D, air dose due to beta emissions from noble gas radio-nuclide 1 (mrad) (2.2.2.a) air dose due to gansna emissions from noble gas radio-nuclide i D
=
Y (mrad) (2.2.2.a) relative deposition per unit area (m-2) (2.3.2)
D/Q
=
plume depletion factor at distance r for appropriate a =
stability class and effective height from Figures 2.3-2 and 2.3-3 (2. 3.1) fraction of current year elapsed at time of calculation F =
l (2.1.1) k open terrain recirculation factor at distance r from
=
Figure 2.3-1 (2. 3.1) 1 GRAND GULF, UNIT 1 2.0-27 Revision 3 - 05/84
2.4 Definitions of Gamaeum Effluents Paramatars (Continued) total body dose factor for Kr-89, the most restrictive K =
isotope (mres/yr per pCi/m ), from Table 2.1-1 (2.1.2) total body dose factor due to ganuna emissions from K
=
isotope 1 (mrom/yr per pCi/m ) from Table 2.1-1 ( 2.1.1) li.niting dose rate to the total body based on the limit D
=
3 of 500 mrom in one year. (2.1.1)
D,,
limiting dose rato to the skin based on the limit of 3000 mrom
=
in one year. (2.1.1) skin dose factor for Kr-89, the most restrictive isotope L
=
(arem/yr per pCi/m*) from Table 2.1-1 (2.1.2) skin dose factor due to beta emissions from isotope 1 (arem/yr L
=
per pCi/m8), from Table 2.1-1 (2.1.1) air dose factor for Kr-89, the most restrictive isotope M
=
(arad/yr per pCi/m*) from Table 2.1-1 (2.1.2) air dose factor due to gasuna emissions from isotope 1 (mrad /yr M
=
g per gCi/m*) from Table 2.1-1 (2.1.1) i air dose factor due to beta emissions from noble gas N
=
radionuclide 1 (mrad /yr per pCi/m8) from Table 2.1-1 (2.2.2.a) dose parameter for radionuclide i, (mrom/yr per pCi/m ) for P
s
=
inhalation from (m8 mrom/yr per #C1/sec) for other pathways, from Table 2.2-1 (2.2.1.b).
rate of release of noble gas radionuclide 1 (pci/sec) (2.1.1)
O'
=
g
{=
average release rate for the current year (gCi/sec) of isotope 1 of tritium, I-131, I-133 or other radionuclide in particulate fom, with half-life greater than eight (8) days (2.2.1.b) cumulative release of radionuclide i of noble gas, tritium, I-Q
=
4 131, I-133, or material in particulate form over the period of interest (gC1) (2.2.2.a) (2.2.2.b)
GRAND GULF, UNIT 1 2.0-28 Revision 5 - 01/85 j
2.4 Definitions of Gaseous Effluents Parameters (Continued)
Q" assigned release rate value of, for example, 1.0 pCi/sec, Xe-
=
133; related to definition of C' for the vent. (Note 3)
R doge factor for radionuclide i, (mrem /yr per pCi/m8) or
=
(m mrem /yr per pCi/sec)
R, count rate per mrem /yr to the skin.
(2.1.1)
=
R count rate per mrem /yr to the total body.
(2.1.1)
=
R" conservative count rate per mrem /yr to the skin.
(2.1.2)
=
R" conservative count rate per mrem /yr to the total body.
(2.1.2)
=
l l
distance (m) from release point to location of interest for r
=
dispersion calculation.
(2. 3.1)
I l
l I
i l
GRAND GULF, UNIT 1 2.0-29 Revision 21 - 12/97 4
)
2.4 Definitions of Gaseous Effluents Paramatars (Continued) count rate of station vent noble gas monitor at alarm setpoint s
=
level. (2.1.1) vertical standard deviation of the plume with building wake I
=
correction (m). (2.3.1) vertical standard deviation (m) of the plume at distance r for a
=
effective height under stability category indicated by T(m) from Figure 2.3-2.
(2.3.1) h temperature differential with vertical separation (*K/100m).
=
(2.3.1) wind speed at ground level (m/sec). (2.3.1) u
=
controlling sector annual average atmospheric dispersion at the W
=
site boundary for the appropriate pathway (sec/m*). (2.2.1.b) relative concentration for unrestricted areas (sec/m*).
w'
=
(2.2.2.b)
X/Q atmospheric dispersion (sec/m*) (2.3.1)
=
l X/Q highest sector annual average atmospheric dispersion at the
=
unrestricted area boundary (sec/m*) (2.1.1)
X/Q' =
relative concentration for unrestricted areas (sec/m*)
(2.2.2.a) l l
l l
GRAND GULF, UNIT 1 2.0 30 Revision 3 - 05/04
Fimi.ra 2.3-1 Pln= Daelation Effect for Granad-hval Relaamas (All Atmospheric stability Classes) eI l
8 1
/
/
/
/
2
)
g'
.e
/
i w
&l u.
1 I
r U
/
=
r t
i E
a.
8 wvz
.I 2
a i
a 9
y e
4 I
g
/
hW
/
I
/
aa I
b 5-r
- d e
e
=
m e
e e
o o
e g
.s E
.g 8, FRACTION REMAINING IN PLUME GRAND GULF, UNIT 1 2.0-31 Revision 15 - 01/94
)
Fierura 2.3-2 vertieni se==Amed Deviation of Matarini in a pln-(Letters denote Pasquill Stability Class)
- 1000, I
r
,r 1
2 7
I I
j-I
/
/
/
/
i V
V r
p A
}
./
,,o*
l l
/
n#
/
/
/
/
/
/
Y j
z r
s
,r um 2'
f f
s-2 t
.r r
3-s 2r r
/
f =.#"
/
F 1"
l
.f
?
/
}
.a
^
n
/ / /
cf/
s s
'~
j
///
/k/ /
/
~
g
/ A/
,f f
/ /
/ af 3,
l M
1 1
1
.1 e
1 1
/
/
/
V 2
/
/
/
/
/
/
/
' /
/
/ l
/
1 0.1 1.0 10 100 r, PLUME TRAVEL DISTANCE (KILOMETERS)
Tammymrunse CW W
8 A Heats f T1('E/l00mm) h
< l.9 A
M m
. t,' to l'.3 C
8 % """M'
.l.3 to 4.5 D
Neueren 4.3 to 1.5 g
gg;g,,y,,g, y
m 1.3 to 4.0 0
W*
Graph taken from Refeience 7, Figure 1 GRAND GULF, UNIT 1 2.0-32 Revision 15 - 01/94
Fimira 2. 3 - 3 malative h aitian for Grmmd-M yel Relan==a (All Atmospheric Stability classes) 10"3 2
1 b 104
\\
E N
as d
N x
T u
a s
Z N %
O
\\
. { 104 g
\\
s w
x a
X W
d
\\
H 3 \\
j 5
W i
- 104 8
i 10-7 0.1 1.0 to.o 100.0 200.0 r, PLUME TRAVEL DISTANCE (KILOMETERS)
Graph taken from Reference 7. Figure 6 i
GRAND GULF, UNIT 1 2.0-33 Revision 15 - 01/94
Fiaura 2.3-4 Onan Tarrain Racirculation Factor l
J S
1 I
n Q
/
Ww
/
8 S
r
}
E a
/
5 a
3 s
C h
I I
E k, CORRECTION FACTOR Graph taken frons Reference 6, Figure 2 GRAND GULF, UNIT 1 2.0-34 Revision 15 - 01/94
2.5 amanous nadwante Trearmant system The instruments required to be checked by LCO 6.11.7 to ensure that the GASEOUS RADWASTE TREA' DENT (Of fgas) SYSTEM is functioning are:
1.
Adsorber train bypass switch (1N64-MS-M611) 2.
Bypass valve indication (IN64-F045)
When the adsorber train bypass rwitch is in the TREAT position and the bypass valve indicates closed, the GASEOUS RADWASTE TREATMENT (7ffgas) SYSTEM is functioning.
NOTES for ODCM Fiaure 2.5-1 A flow diagram for the Gaseous Radwaste Treatment System is provided on the following page. Notes for the diagram are listed below.
(1) The charcoal beds are bypassed during startup until an, adequate dowpoint is obtained in the process stream.
(2) This pathway may be utilized for power levels s St.
(3) Standby Gas Treatment System not normally operated.
I GRAND GULF, UNIT 1 2.0-35 Revision 17 - 03/95
Ficrura 2. 5 - 1 ttamaous *="4==ta Treme==at Svatam to Ansoapucet
... j i:....
~ w,,
.i.@:
l
.e
==
- mammar i
u ur a,,,,,,
.e.ase; c- /
m
..7 37 (CONDENSER)
BED rM 3:
(JECTom jN REC 0teestR coenaeam F pqn imr) ge,aneng CFF CA$
Tuttaa
\\
esECat. M PuhdB (2)
,eg 1 I
I I.
y l
( FLSI IF l
lFL r
nom. art r
i gh{***U l
oursor m i NW,i g
g am gutanc i
.: to
- ^*88P'8mt
)
k anset Ast FLW runess
- i sus, sues FLIB FLf8 FLfut j
suume
,'nenmans'
- LA"0"
- waaror !
- D8 l rn. ml
"'8" J
. nesimme's to ahmospuser
- wowrom.'
h I
b FLW suusso g
-i m cwooiang i
A r
=:
- igi-"
,r.H, caw J..
a
~.
- Renmesij i
- weernnf to aruosimac bN
'IS!
..J..
seem t aneames).
F 2petuwn t."***
GRAND GULF, tJNIT 1 2.0-35a Revision 8 - 08/86
l l
l l
2.6 annum 1 nna. r - 4cm.ne If required, the annual (calendar year) dose or dose conunitment to any MEMBER OF THE PUBLIC will be calculated by summing the following doses for the calendar year:
Direct radiation dose Liquid effluent dose (DTau}
e Noble gas dose (D, D )
g Particulate dose (D )
P These calculations are required only 1,f the liquid or gaseous effluents exceed twice the limits of LCOs 6.11.2, 6.11.5 and 6.11.6.
2.6.1 D4rmer *=d4=einn m-u- - -u ;- - - -. e LCOs 6.11.2, 6.11.5 and 6.11.6 require the determination of cumulative dose contributions to a MEMBER OF THE PUBLIC from direct radiation from the reactor units and from i
l radwaste storage tanks. This requirement is applicable l
only under conditions set forth in Action B.1 of the l
1 applicable LCO.
This determination is made by the utilization of direct radiation measurements from indicator thermoluminescent dosimeters (TLDs) located near the GGNS property line in eight'of the 16 meteorological sectors.
l l
l l
l GRAND GULF, UNIT 1 2.0-36 Revision 20 - 07/96 l
Measurements from these TLDs represent the direct radiation gaaerated by the facility plus normal background radiation. The locations are identified in ODCM Table 3.0-3 by the following TLD numbers:
M-16 M-22 M-23 M-19 M-25 M-17 M-21 M-28 Control TLDs are also utilized to differentiate between background radiation and direct radiation from the facility. The following two TLDs are designated as
~
controls based on the criterion that tiiey are located ten miles or greaterofrom the facility. Exact locations are identified in ODOt Table 3.0-3.
M-14 M-33 The difference between the averaged quarterly radiation measurements of the indicator TLDs and the control TLDs represents the direct radiation dose to a MEMBER OF THE PUBLIC from the operating facility.
GRAND GULF, IRtIT 1 2.0-37 Revision 20 - 07/96
3.0 RADIOf.DGICAL ENVIRORMENTAL MONITORING 3.1 Sammlins Locations Sagling locations to fulfill the requirements of LCO 6.12.1, as described in ODOt Table 6.12.1-1, are identified in ODO4 Tables 3.0-1 through 3.0-3 and shown on maps in ODOt Figures 3.0-1 and 3.0-2.
GRAND GULF, UNIT 1 3.0-1 Revision 17 - 03/95
1
{
QDCH Tamr.e 3.o.i 179 E1MPt.WD MT.T.ff"PTOh? ETTEE I
i AIR RAMPLERS NtMBER ZIGDRE IDCATION Southeast df GGNS at the Port Gibson City Barn AS-1 PG 3.0-2
.(Sector G Radius, 5.5 miles)
AS-3 61VA 3.0-2 NNE of GGNS on Hwy. 61, north of the r
l Vicksburg Airport (Sector B Radius, 18 miles) j AS-7 UH 3.0-1 SSE of GGNS at the IBEN Union Hall (Sector H Radius, 0.5 miles) l l
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GRAND GULF, IEtIT 1 3.0-2 Revision 20 - 07/96
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ansu TAaLE 3.0-2
,]
MISCELL&NEOffE COLLECTION SITER Page 1 of 2 MILE SAMPLES fCONTROL LOCATIONI ZIGURE ALCONT 3.0-2.
Located SSW of GGNS at Alcorn State University (Sector K Radius 10.5 miles) 4 GRotnID MATER -
PGNELL 3.0-1 PORT GIBSON WELi.3 - Taken from distribution system or one of the five wells (Sector G Radius 5.0 miles)
Construction Water Well 3.0-1 GGNS CONSTRUCTION WATER WELL -
Taken from distribution system or the well (Sector P Radius 0.4 miles)
EURFACE WATER Upstream 3.0-1 At least 4500 ft upstream of the OGNS discharge point into the Mississippi River to allow adequate mixing of the Mississippi and Big Black Rivers (Sector Q-R, 1.8 miles)
Downstream 3.0-1 At least 5000 ft downstream of the GGNS discharge point into the Mississippi River near Radial Well No. 1 (Sector N, 1.6 miles)
MS River Downstream 3.0-1 Downstream of the OGNS discharge point (during a liquid radwaste discharge) in the Mississippi i
River near Radial Well No. 5 i
(Sector Q-P, 1.3 miles) i GRAND GULF, UNIT 1 3.0-3 Revision 20 - 07/96
ODCM TABLE 3.0-2 (Continued)
MISCELLANEOUS COLLECTION SITES l
Page 2 of 2 l
SEDIMENT SAMPLES FIGURE SEDRAM 3.0-1 Downstream of the GGNS discharge point in the Mississippi River near Hamilton Lake outlet (Sector N, 1.6 ndles)
SEDCONT' 3.0-1 Upstream of the GGNS discharge point in the Mississippi River (Minimum of 100 yds)
(
VEGETATION Broadleaf Vegetation 3.0-1 S of GGNS near fonmer l
Training Center on Bald Hill Road (Sector J, 0.4 miles), or l
SSE of GGNS between the former training center and the IBEW Union Hall on Bald Hill Road i
(Sector H, 0.4 miles)
NOTE:
The above locations are gardens maintained by GGNS inside the SITE BOUNDARY. These two sampling sites exceed the requirements of LCO 6.12.1.
Alcorn State University SSW of GGNS (Sector K, 10.5 miles) when available, otherwise a location c
15-30 km distant FISH SAMPLES Fish and Invertebrates Downstream of the GGNS discharge point into the Mississippi River Upstream of the GGNS discharge point into the Mississippi River uninfluenced by plant operations GRAND GULF, UNIT 1 3.0-3a Revision 21 - 12/97
~
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ODcM TaRf F 1.0-3 TLD IDCATIONS Page 1 of 2 l
TLD No.
LOCATION FIGURE SECTOR MILE M-01 Across the road from Lake 3.0-2 E
3.5 Claiborne entry gate M-07 AS-1 PG, Port Gibson City Barn 3.0-2 G
5.5 M-09 Warner Tully Y-Camp 3.0-2 D
3.5 l
M-10 Grand Gulf Military Park 3.0-1 A
1.5 M-14 AS-3-61VA, Hwy. 61, north of 3.0-2 B
18.0 (CONTROL)
Vicksburg Airport M-16 Meteorological Tower 3.0-1 A
0.9 l-M-17 S Side, Grand Gulf Road 3.o.1 C
0.5 l
M-19 Eastern SITE BOUNDARY 3.0-1 E
0.5 l
property line, NNE of HMSA l
M-21 Near former Training Center 3.0-1 J
0.4
)
Building, on Bald Hill Road M-22 Former RR entrance crossing on 3.0-1 G
0.5 Bald Hill Road M-23 Gin Lake Road 50 yards north of 3.0-1 Q
0.5 Heavy Haul Road on power pole M-25 Radial Well Number 1 3.0-1 N
1.6 M-28 Former Glodjo residence 3.0-1 L
0.9 i
M-33 Newellton, Louisiana, Water 3.0-2 P
12.5 (CONTROL)
Tower M-36 Curve on NW 608, point nearest 3.0-2 P
5.0 GGNS at power pole M-38 Lake Bruin State ParP., entrance road 3.0-2 M
9.5 M-39 St. Joseph, Louisiana, Aux.
3.0-2 M
13.0 Water Tank M-40 Headley Drive, near River 3.0-2 M
2.3 t
Port entrance GRAND GULF, UNIT 1 3.0-4 Revision 20 - 07/96
l oncu TARTM 1.0-3 (enneinnad) a TLD IDCATIONS l
Page 2 of 2 TLD MO.
IDCAT,1Qt[
FIGURE SECIQR MILE l
M-48 0.4 miles South on Mont Gomer' 3.0-2 K.
4.8 Road on west side M-49 Fork in Bessie Weathers Road /
3.0-2 H
4.5 shaifer Road M-50
- Panola Hunting Club entrance 3.0-2 B
5.3 M-55 Near Ingelside Karnac Ferry Road /
3.0-2 D
5.0 Ashland Road Intersection M-57 Hwy. 61, behind the Welcome 3.0-2 F
4.5 to Port Gibson sign at Glensdale subdivision M-94 Sector R near 3.0-1 R
0.8 Meterological tower l
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GRAND GULF, IDTIT 1 3.0-5 Revision 20 - 07/96 l
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}
OFFSITE DOSE CALCUIATICII MJufDAL APPEIEDIZ A RADIO!4GICAL EFFLUElf? CCIfTROLS AIID RADIO 14GICAL E3fv1RCISIENTAL MOIIITORING PROGRAMS GRAIED N, UltIT 1 A.0 Revision 17 - 03/95
I
" TEXT DELETED" i
I GRAND GULF, tJNIT 1 A-1 Revision 17 - 03/95 l
1.O DEFINITIONS GASEOUS IIAD*81eTE T* NfMENT (OFFaial SYSTEM 1.1 The GASEOUS RADNASTE TREATMENT (OFFGAS) SYSTEM is the system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
MEMBER (S) OF THE PUBLIC 1.2 MEMBER (S) OF THE PUBLIC shall include individuals in a controlled or unrestricted area. However, an individual is not a member of the public during any period in which the individual receives an occupational dose.
OFFEITE DOSE catetffMION MANrtat- (ODCM) 1.3 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of th'a Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification 5.5.4 and Technical Requirement 7.6.3.2 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Technical Specifications 5.6.2 and 5.6.3.
PROFens CONTROL P8N28th8 (PCP) 1.4 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure coupliance with 10CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.
i GRAND GULF, UNIT 1 A-2 Revision 17 - 03/95
SITE B00MDARY 1.5 The SITE BOUNDARY shall be that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee.
ImRESTRICTED AREA 1.6 An UNRESTRICTED ARIA shall be any area, at or beyond the SITE BOUNDARY, access to which is not controlled by the licensee for the purposes of protection of individuals from esposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial commercial, institutional, and/or recreational purposes. The UNRESTRICTED ARIA and SITE BOUNDARY are synonymous with the exception of areas over bodies of water.
VErrILATION IINADST TREA'tMErr SYSTEM 1.7 A VENTIIATION IINAUST TREATMErf SYSTEM is any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the enviran==at (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTIIATION IIHADST TREA'IMElrf SYSTEM components.
Additional Definitions are listed in Technical Specification Section 1.1.
i GRAND GULF, UNIT 1 A-3 Revision 17 - 03/95 J
l f
TABI2 1,1 SURVEILLANCE FREQUENCY NOTATION
~
- i Surveillance Frequencies are specified in individual LCOs. For incre infortnation see Technical Specificaiton Section 1.4.
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GRAND GULF, UNIT 1 A-4 Revision 17 - 03/95
TABLL 1.2 1951 Modes of operation are shown in Technical specification Table 1.1-1 1
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GRAND GULF, IntIT 1 A-5 Revision 17 - 03/95
1 l
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3.O APPLICARILITY f.mi ris tynmTTTom Pom OPammeros (tro)
I 1
l See Technical specification Section 3.0 for LCO Applicability.
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l GRAID 00LF, IEFIT 1 A6 Revision 17 - 03/95 i
APPLICABILITY e-
-1; (gn) suxWIt.t weir se-u See Technical Specification Section 3.0 for SA applicability.
l-GM N, UNIT 1 A.7 Revision 17 - 03/95
(
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SECTICIf 5.0 ADMINISTRATIVE CCETROLS r
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GRAllD GULF, UNIT 1
s,o ar-mirren,-ivi
^-1
.r e s.s.2
=--
- 1. manrnt> wire ar. amrvi-- -
- r ce__m,,_ amanev Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.
The annual radiological environmental operating reports shall include suunnaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an asesoament of the observed ispects of the plant operation on the environment. The reports shall also include the results of 140 6.12.2.
If harmful effects or evidence of land use censuses required by irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.
The annual radiological environmental operating reports shall include summarised and tabulated results in the format of Regulatory Guide 4.8, Looember 1975 of all Deviaticas from radiological environmental sag les taken during the report period. In the event that the sampling program identified in ICO 6.12.1 shall be reported some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
The reports shall also include the following:
a summary description of the radiological environmental monitoring program 1) a map of all sampling locations keyed to a table giving distances and directions 2) from one reactors and the results of licensee (or offsite laboratory's) participation in the 3)
Interlaboratory Comparison Program, required by I4O 6.12.1.
GRAW GULF, UNIT 1 A-9 Revision 17 - 03/95
i 5.0 ANTNISTRATIVE PowfoofE 5.6.3
?_--iat saftforTIVE IFFfnewr enf uner nasant A Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted before May 1 of each year.
The Radioactive Effluent Release Report shall include a summary of the quantities a.
of radioactive liquid and gaseous effluents and solid waste released fraa the unit as outlined in Regulatory Guide 1.21, ' Measuring, Evaluating, and Reporting l
Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and i
Gaseous Effluents from Light Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summiarised on a quarterly basis following the format of Appendix 8 thereof. For solid wastes, the format for Table 3 and Appendix 5 shall be supplemented with three additional categories: class of solid wastes (as defined by 10 CFR Part 61), type of container (e.g., Steel Liner, High Integrity Container) and SOLIDIFICATION Agent or abscrbent (e.g., cement, urea formaldehyde).
The Radioactive Iffluent Release Report shall include an annual susmary of hourly meteorological data collected over the previous year. This annual susanary may be f
either in the form of an hour-by hour listing on magestic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.* 'this same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calends-voar. This same report shall also include an assessment of the radiatir* @ w from radioactive liquid and gaseous effluents to MERSERS OF THE PUBL
- die t s their activities inside the SITE BOUNDARY during the reporting perica.
H 4esumptions used in making these assessments, i.e., specific activity, emposure time, and location, shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement or historical annual average meteorological conditions, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the CFFSITE DOSE CALCULATION MANDRL (CDCM).
l The Radioactive Iffluent Release Report shall also include an assessment of radiation doses to the likely most exposed IEISER OF 'tiEE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from l
primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptanle methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev 1, October 1977 and NURES - 0133.
The Radioactive Effluent Release Report shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
The Radioactive Effluent Release Report shall include any changes made during the reporting period to the OFFSITE DOSE CALCULATICE MANUhL (CDQt), pursuant to Technical Specification 5.5.1, as well as any major change to Liquid, Gaseous, or Solid Radwaste Treatment Systems. It shall also include a listing of new locations for dose calculations and/or enviranamatal monitoring identified by the Land Use census pursuant to LCO 6.12.2.
In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meterological data casite in a file that shall be provided to the IRIC on request.
GRAND GULF, UNIT 1 A 10 Revision 17 03/95
l s.o a w =1srowrva a-rar_a j
r-ar amar%a arresurr nev = mew numer (Continued) s.s.3 The Radioactive Effluent Release Report shall also include the following:
an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in LCOs 6.3.9 or 6.3.10, and description of the events leading to liquid holdup tanks exceeding the limits of Technical specification 5.5.8.b.
Major changes to the Radioactivtn Waste Treatment System (liquid, gaseous and b.
solid **) shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the PSRC.
(1) A summary of the evaluation that led to the determination that the change l
could be made in accordance with 10 CFR 50.59; sufficient detailed information to totally support the reason for the change (2) without benefit of additional or supplemental information; 1
(3) A detailed description of the equipment, P ts and processed involved f
and the interfaces with other plant systems; An evaluation of the change which shows the predicted releases of (4) radioactive materials in liquid and gaseous affluents and/or quantity of solid waste that differ from those previously predicted in the license application and== mad==ats thereto; An evaluation of the change which shows the espected==w4==
emposures to (5)
MEMBERS OF TNI FUSI.IC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendmaats thereto; A comparison of the predicted releases of radioactive materials, in liquid (6) and gaseous affluents and in solid waste, to the actual releases for the
)
period before when the changes are to be made; An estimate of the.esposure to plant operating personnel as a result oI the (7) change; and Documentation of the fact that the change was reviewed and found acceptable (8) by the F4RC.
i
- The information called for in this Specification may be submitted as part of the next UFSAR update.
A-ll Revision 17 - 03/95 GRAND GULF, IEfIT 1
SECTION 6.0 LIMITING Com ITIONS FOR OPERATION AND SURVIIZ1ANCE REQUIRa mrrS l
i GRAND QULF, UNIT 1 A-12 Revision 17 - 03/95
6.3 INSTRUMENTATION 6.3.9 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LCO 6.3.9 The radioactive liquid effluent monitoring instrumentation. channels shown in Table 6.3.9-1 shall be OPERABLE with required alarm / trip l
setpoints set to ensure that the limits of LCO 6.11.1 are not exceeded..The alarm / trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
APPLICABILITY:
At all times.
ACTIONS
........................................... NOTES------------------ '-------------------
1.
Separate condition entry is allowed for each Channel.
2.
The-provisions of LCO 3.0.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more required A.1 Suspend release of Immediately channels inoperable.
radiactive effluent via affected pathway.
98
........--NOTES------------
Once required Action A.2 is entered the C,xigletion Time for Condition B or C can "not be restarted by reentering Required Action A.1.
A.2 Enter the Condition Im;nediately referenced in Table 6.3.9-1 for the channel.
(continued) t l
GRAND GULF, UNIT 1 A.13 Revision 18 - 02/96 l
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ACTIONS (cent a" d_)
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CONDITION REQUIRED ACTION COMPI.ETION TIME 5.
As required by Required B.1 At least two 4adarandaat Prior to each Action A.2 and referenced samples are analysed in
- release, in Table 6.3.9-1.
accordance with ICO 6.11.1.
M B.2 At least two technically Prior to each qualified assisere of the release.
Facility Staff indarandmatly verify the release rate calculations and discharge path valve line-up.
?
M 5.3 Restore ehmanal to 14 days operable.
C.
As required by Required C.1 Estimate the flor rate for Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Action A.2 and referenced the affected pathway during in Table 5.3.9-1.
actual releases. Pulp curves may be used to estimate flow.
l M
l C.2 Restore channel to 30 days operable.
D.
Required Action and D.1 Suspend release of Immediately l
associated Completion Time radiactive effluent via i
of Condition B or C not affected pathway.
l met.
M D.2 Initiate action to emplain Immediately why this inoperability was not correeted in a timely manner in the neat Annual Radioactive Effluent Release Report.
GRAND GUI.F, tarIT 1 A 14 Revision 17 03/95
SURVIIZ1ANCE REQUIRBErfS
..........................................-NOTES.-
Refer to Table 6.3.9-1 to determine which SRs apply to each channel.
SURVIII&ANCE FREQUENCr SR 6.3.9.1
NCFFE--------------------
I For flow rate measurement devices a CHANNEL CHICK 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> shall consist of verifying indication of flow during periods of release. A CNAINEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days which batch releases are made.
Perform CHANNEL CHECK.
]
SR 6.3.9.2 Perform a source check, a qualitative assessment Prior to each of channel response when the channel sensor is release.
exposed to a radioactive source.
.---------IICPfB----------.----------
The CHAIRIEL FUNCTICImL TEST shall also demonstrate 92 days that automatic isolation of this pathway and control room alarm annunciation occur if any of t.he following conditions exists:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Instruent indicates a downscale failure.
4.
Instruent controls not set in operate mode.
Perform CHAMEL FtMCTICIEL TEST.
(continued)
)
1 GRAND GULF, UNIT 1 A.15 Revision 17 - 03/95
1 l
1 SURVIILIANCE FREQUENCY SR 6.3.9.4 Perform CHAmfEL FUNCTIQHAL '11ST.
92 days SR 6.3.9.5
.......................N0TE.......................
The initial CHAMfBL CALIBRATION shall be performed 12 months using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measuremsat range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
Perform a CHANNEL CALIBRATION.
SR 6.3.9.5 Perform a CHANNEL CALIBRATION 18 months GRAND GULF, UNIT 1 A 15 Revision 17 03/95
9999 999 999 AE LM LE 3333 333 333 IR EI 6666 666 666 VU RRRR RRR RRR RQ SSSS SSS SSS UE SR SD 2
IR RUO B
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6.3 INSTRDustrATION 6.3.10 RADIQACTIVE GASECOS EFFIDEarf BE3NITORING INSTRWErfATION LCO 6.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 6.3.10 1 shall be OPen m a with their alarm / trip setpointe set to ensure that the limits of LCO 6.11.4 are not exceeded. The alare/ trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
APPLICABILITY:
As shown in Table 6.3.10 1 ACTIONS
........................................... NOTES...-..............-...................
1.
Separate Condition entry is allowed for each Channel.
i 2.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
CONDITION REQUIRED ACTION CCaspLETION. TIME j
A.
One or more required A.1 Suspend release of Isenediately '
channels inoperable.
radiactive effluent via J
affacted pathway.
QE
..........NOrES............
Once required Action A.2 is entered the Cospletion Time for Condition Referenced on Table 6.3.10 1 can not be restarted by reentering Required Action A.1.
,l A.2 Enter the Condition Innediately referenced in Table 6.3.10 1 for the n.hmanal. -
(continued)
GRAND GULF, UNIT 1 A.18 Revision 17 03/95
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B.
As required by Required 5.1 Take grab samples during once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Action A.2 and referenced release.
in Table 6.3.10-1.
l 3.2 Analyse the above required Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of samples for gross taking the sample l
activity.
E 30 days 3.3 Restore channel to i
I i
C.
As required by Required C.1 Establish an alternate Issmediately l
Action A.2 and referenced means to collect semples in Table 6.3.10 1.
required by Table 6.11.4-1.
l O
C.2 Restore channel to 30 days operable.
D.
As required by Required D.1 Estimate flow rate.
Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Action A.2 and referenced t
in Table 6.3.10-1.
M D.2 Restore channel to 30 days operable.
l (continued) 1 1
I l
l l
1 GRAND GUIX, UNIT 1 A 19 Revision 17 - 03/95
m ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E.
As required by pequired E.1 Place the inoperable 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Action A.2 sad referenced channel in downscale trip.
in Table 6.3.10-1.
...............N0T5............
With both required monitors inoperable take Required Actions I.2.
E.2.1 Take grab sasiples during Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> release.
M E.2.2 Analyse the above Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of required easiples for taking the sample gross activity.
M E.2.3 Restore channel to 30 days operable.
F.
As required by Required F.1 verify the offgas system is Immediately Action A.2 and referenced not bypassed, except for in Table 6.3.10-1.
filtration system bypass during plant startups.
M F.2.1 Verify by administrative Inunediately means that the offgas post-treatment monitoring system is operable.
QB F.2.2.1 Verify by Inunediately administrative means that the charcoal vault radiation monitor and the main steam line radiation monitors are operable.
M F.2.2.2 Take grab samples and Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and
)
analyse.
once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> M
thereafter F.3 Restore channel to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> operable.
(continued)
A-20 Revision 19 - 05/96 GRAND GULF, UNIT 1
l ACTIONS (contia d_)
CONDITION REQUIRED M ION COMPLETION TIME G.
As required by Required G.1 Take grab sosples during Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Action A.2 and referenced release.
in Table 6.3.10 1.
M G.2 Analyse the above required within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of semples for gross taking the sample activity.
M 30 days G.3 Restore chamael to operable.
H.
Required Actions and H.1 Suspend rolosse of Immediately associated Completion radiactive affluent via Times of Condition B,C,D,E this pathway.
or G not met.
M M.2 Initiate action to explain Immediately why this inoperability wee not corrected in a timely'
=aanar in the next han=1 Radioactive Bffluent Release Report.
I.
Required Action and I.1 Be in IE305 3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition F not met.
M I.2 Se in IEI)E 4 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> GRAND GULF, UNIT 1 A-21 navision 17 - 03/95 l
I SURvBILLANCE REQuIRaswr8
.........................................pgrgs............'.............................
1.
Refer to Table 6.3.10 1 to determine which SRs apply to each channel.
2.
When a monitor is placed in an inoperable status solely for performance of required Surveillance's, entry into associated Conditions and Required Actions in accordance with 140 6.3.10 any be delayed for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
SURVEILLANCE FREQUENCY SR 6.3.10.1 Perform CHANNEL CNBCK.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 6.3.10.2 Perform CHANNEL CNBCK.
7 days SR 6.3.10.3
.................-.....N075.......................
1.
Not required to be performed in ICDes 1 and 2 for the offgas pre. treatment monitor if inac::essibile due to a high radiation area.
2.
Not required to be performed for the offgas pretreatment monitor when er.tering ICDES 3 and 4 from acDES 1 or 2 until 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after entering ICDE 3 or 4 if monitor was inaccessible due to a high radiation area.
Perform SOURCE CNBCE, a qualitative assessment of channel response when the channel sensor is 31 days emposed to a radioactive source.
.......................N7FE.......................
The CHAINEL FUNCTICIEL TEST shall also demonstrate the av.toontic isolation capability of the instrumentation for this pathway and the centrol room alarm annunciation capability, if any of the following conditions exists:
1.
Instrument indicates measured levels above the alare/ trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument centrole not set in operate mode.
92 days Perforu OfAMIL FUNCTIONAL TEST.
(continued)
GRAND GULF, UNIT 1 A.22 Revision 17 03/95
SURVIIT ?_^=*E "_mTIREMEIrr$ (continued)
SURVEILLANCE FREQUENCY SR 6.3.10,5
- ------- --- * -- - NOTE --- - - -----*-
':he CHANNEL FUNCTIONAL TEST shall also desenstrate that control room alarm annunciation occur if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controle not set in operate mode.
92 days Perform CHANNEL FUNCTIQMAL TEST.
SR 6.3.10.6 NUTE.----..-..----..--.----
Compare the measured flow rate to the expected design flow rate for existing plant conditions.
Perform CHANNEL FUNCTIONAL TEET.
92 days SR 6.3.10.7 NOTE..--..-.----------
1.
'the initial CHMEIEL rantasa' PION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from e g liers that i
participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHAIEEEL CALIBRATION, sources that have been related to the initial calibration shall be used.
2.
The offgas pre tri atment and offgas post-treatment sensors wil: be calibrated for ar/hr or eps from the calibrat;,on standard. 'the conversion to release rate will be performed during subsequent unit operation, but within one week, Perform a CHAIBIBL CALIBRATION.
12 months SR 6.3.10.8 Perform a CHA MBL CALIBRATICW 18 months GRAIID GULF, UNIT 1 A-23 Revision 17 03/95
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TART.R K _ "4 _10 - 1 f rem P 4 mima 1 DanTAAFTTVR (21CRoffC RFFT.ffRNT MOMTTODTMr3 TMATDTSfFMTATTOM TART.E NOTATTOM (a) At all times.
(b) During main condenser offgas treatment system operation.
(c) When any steam jet air ejector (SJAE) is in operation.
(d) During containment high volume purge.
(e) During containment low volume purge.
i
, l 1
1 GRAND GULF, UNIT 1 A-28 Revision 21 - 12/97
E.11 RADIQACTIVE EFFLUENTS 6.11.1 LIQUID IFFLUIsrFS CONCElrrRATION LCO 6.11.1 ne concentration of radioactive material released in liquid effluents to UNRESTRICTED ARIAS shall be limited to ten times the effluent concentrations specified in 10 CFR Part 20, Appendix E, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10*4 microcuries/ml total activity.
APPLICAEILITY:
At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION, TIME A.
The concentration of A.1 Restore the concentration.
Immediately radioactive material to within the above limits.
released in liquid affluents to UNRESTRICTED M
AREAS exceeds the above limits.
A.2 Declare the liquid effluent waste treatment system ia m rable.
GRAND GULF, UNIT 1 A-29 Revision 17 - 03/95
SURVEILLANCE E M RBIENTS l
SURVEILLANCE FREQUENCY SR 6.11.1.1
'Ihe radioactivity content of each batch of Per (00CN) radioactive liquid waste shall be determined Table 6.11.1 1.
before release by sampling and analysis in accord-ance with (CDCat) Table 6.11.1-1.
(
SR 6.11.1.2 Poet release analyses of samples coeposited from Per (ODC38) l batch releases shall be performed in accordance Table 6.11.1-1.
with (ODCat) Table 6.11.1-1.
l l
GRAID GULF, UNIT 1 A-30 Revision 17.03/95
TaafJr g.11.1 1 manina,m vm 1.fotTID WABT3 ema==t. Turn anm ***TvBIS parwtmau Minisus Type of Lower Limit Liquid Release Sampling Analysis Activity of Detection Type Frequency Prequency Analysis (LLD)
(sci /ml) (a)
A.
Batch waste Prior to Prior ts Principal Gamma 5x10~7 Release Release Release Raitters (d)
Tanks (c)
Each Batch Bach Batch I-131 1x10 8 Prior to 31 days Dissolved and 1x10 5 Release Entrained Gases one Batch /M (Gamma emitters) i Prior to 31 days M3 1x10 5 Release Composite (b)
Each Batch Gross Alpha 1x10*7 Prior to 92 days Sr-89, Sr-90 5x10*8 Re1 ease Composite (b)
Bach Batch Pe-55 1x10 6 B.
SSW Basin Prior to Prior to Principal Gamma 5x10*7 (before Release Release Battters(d) blowdown)
Each Bach Batch Blowdown I-131 1x10*8 GRAND 0012, IsrIT 1 A 31 Revision 17 - 03/95
Timf.m g,ii,1 1 (cant 4mAM RADIN'TIVE LIOCIID WARTE *"*LTIE2 m "*fYSIS PROGRAM TABLE IR7fATION The LLD is the smallest concentration of radioactive asterial in a easple that a.
will yield a not count (above system background) that will be detected with 95%
probability with only 5% probability of falsely concluding that a blank real" signal.
a observation represents a For a particular measurement system (which may include radiochemical separation) :
4.66 sb 3
J LLD =
I e v e 2.22 x 106. y..mp (.xag)
LLD is the "a priori" lower limit of detection as defined above (as gCi per unit mass or volume).
(Current literature defines the LLD as the detection capability for the instrumentation only, and the MDC, minimum detectable concentration, as the detection capability for a given instrument, procedure, and type of sample.)
is the standard deviation of the background counting rate or of the sb counting rate of a blank sample as appropriate (as counts per minute)
I is the counting efficiency (as counts per disintegration)
V is the sample sine (in units of mass or volume) 6 is the number of disintegrations per minute per microcurie 2.22 x 10 Y
is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radionuclide At is the elapsed time between sample collection (or end of the sample collection period) and time of counting The value of ob used in the calculatico of the LZa for a particular measurement system should be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicated variance.
Typical values of E, V, Y and At should be used in the calculation.
i It should be recognised that the LIA is defined as an a criori (before the fact) j limit representing the capability of a measurement system and not as a costeriori i
(after the fact) limit for a particular measurement.
GRAND GULF, UNIT 1 A-32 Revision 17 - 03/95
~
Tlatt 6.11.1 1 ( cont 4 n* *ad )
RADIAAt*fTVE LICDID WARTE 8"LTM3 " "'YRIE PnN281W TABLE NOTATION (Continuad) b.
A composite sample is one in which the quantity of liquid sampled is proportional f
to the quantity of liquid waste discharged and in which the method of sampling
)
esplayed results in a specimen which is representative of the liquids released.
I A batch release is the discharge of liquid vs.stes of a discrete volume. Before c.
sampling for analyses, each batch shall be isolated, and then thoroughly mixed to i
assure representative sampling.
d, The principal gamma entitters for which the L2 specification applies exclusively are the following radionuclides:
Ikt-54, Fe-59, co 53, Co-60, 2n 65, Mo-99, Cs-134, Cs-137, Co 141, and Co 144.
This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
i l
1 GRAIED QULF, UNIT 1 A 33 Revision 17 - 03/95
~
6.11 RADICACTIVE EFFLUEIrf5 6.11.2 LIQUID IFFUENT DOSE LCO 6.11.2 The does or dose commitment to a MEISER OF THE PUBLIC from radioactive materials in liquid offluents released to UNRESTRICTED AREAS shall be a.
5 1.5 mres to the total boey and 5 5 mres to any organ, during any calendar quarter, and b.
5 3 mrom to the total body and 5 10 mres to any organ, during any calendar year.
APPLICABILITY:
At all times.
ACTIONS 3ItyfEE.......................................
1.
The provisions of Specification 3.0.3 are not applicable.
Separate Condition entry is allowed for each of the above 11mits.
2.
COIIDITIQE RECIIIEED ACTIM COMPLETION TIME A.
The calculated dose from A.1 Initiate action to prepare Isundiately the release of radioactive and submit a Epocial Report materials in liquid within 30 days.
effluents greater than any of the above limits.
Agt A.2 Declare the liquid effuent waste treatment system inoperable.
(continued)
GRAIID GULF, UNIT 1 A.34 Revision 17 03/95 J
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3.
The calculated doses from B.1 Initiate action to Immediately the release of radioactive calculate the direct materials in liquid radiation contributione effluents greater than from the reactor unit and twice any of the above freen outside storage tanks to determine whether the
- limits, total annual does or dose conniement to any RE SER OF THE FUBLIC greater than:
a) 25 mrom to the total body or any organ, except the thyroid.
95 b) 75 aren to the thyroid.
sUnvEIIsasCE A-nummers SURVIILIANCE FREQUENCY SR 6.11.2.1 Cumulative dose contributions from liquid 31 days affluente for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters of the CDCM.
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I A-35 Revision 17 - 03/95 GRAlm GULF,IntIT 1
6.11 RADIQACTIVE EFFIDErfS 6.11.3 LIQUID EFFLUENT MASTE TREATNENT LCO E.11.3 The liquid radwaste system shall be used to reduce the radioactive materials in liquid wastes before their discharge when the projected doses due to the liquid effluent to UNRESTRICTED ARIAS would be >
0.06 arem to the total body or > 0.2 mrom to any organ, in a 31-day period.
APPLICARILITY:
At all times.
ACTIONS
...........................................NUFES.......................................
The provisions of Specification 3.0.3 are not applicable.
CONDITION RNQUIRED ACTION COMPLETION TI35 A.
Radioactive liquid waste A.1 Initiate action to prepare Immediately being discharged without and submit, a special treatment and in excess of Report within 30 days.
the above limits.
SURVEILLANCE 9_sihd SURVIILIANCE FREQUENCY SR 6.11.3.1 Doses due to liquid releases to IBRESTRICTED AREAS 31 days shall be projected in accordance with methodology and parameters in the CDCM.
4E
.......................pDFg.......................
Not required to be met when the projected dose less than or equal to the above limit.
Verify the liquid effluent waste treatment system is being used to reduce radioactive materials before discharge.
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GRAND GULF, UNIT 1 A.35 Revision 17 03/95 1
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6.11 RADIQACTIVE EFFLUElrrs 6.11.4 GASEOUS EFFLUEIrrs '- DOSI RATE LCO 6.11.4 The does rate due to radioactive materials released in gaseous effluents from the site to areae at and beyond the SITE BOUNDARY shall be:
a.
For noble gases: 5 500 mres/yr to the total body and 5 3000 mres/yr to the skin, and b.
For all iodine 131, iodine-133, tritium and all radionuclides in particulate form with half lives greater than 8 days: 5 1500 aren/yr to any organ.
APPLICABILITY:
At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLET10N TIME A.
Dose rate exceeding the A.1 Decrease the release rate Immediately above limits.
to within the above limit (s).
451 A.2 Declare the ventilation exhaust treatment system inoperable.
GRAND GULF, UNIT 1 A.37 Revision 17 - 03/95 l
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SURVIILLANCE REQUIREMENTS SURVIILLANCE FREQUENCY SR 6.11.4.1 The dose rate due to noble gases in gaseous Per (ODC3t) effluents shall be determined to be within the Table 6.11.4-1.
above limits by obtaining representative eagles and perforlaing analyses in accordance with (ODC38) Table 6.11.4 1.
SR 6.11.4.2 The dose rate due to iodine 131, iodine-133, Per (ODCM) tritium and to radionuclides in particulate form Table 6.11.4 1.
with half lives greater than 8 days in gaseous offluents shall be determined to be within the above limits by obtaining representative samples and performing analyses in accordancs with (ODCM) Table 6.11.4-1.
t GRAND GULF, UNIT 1 A-38 Revision 17 - 03/95
TAaLE E.11.4 1 RADICACTIVE GASEOUS WASTE emnLING AND m?Y3I3 PROGRAM Minimust Type of Lower Limit Gaseous Release Sampling Analysis Activity of Detection Type Frequency Frequency Analysis (LLD) 4:
(sci /ml) (a)
A.
(1) Radwaste 31 days 31 days Principal Gasuna 1x10*4 Building Grab Sample (f)
Emitters (b,e)
Ventilation Exhaust H3 1x10 6 (2) Fuel Handling Continuous (d) 7 days (c)
I-131 1x10 12 Area ventila-(f) Charcoal tion Exhaust Sample I-133 1x10-10 (3) Containment Continuous (d) 7 days (c)
Principal Gesuna 1x10*11 ventilation (f)
Particulate Emitters (e)
Exhaust Sample (I-131, Others)
(4) Turbine Continuous (d) 31 days Gross Alpha 1x10-ll Building (f) Composite ventilation Particulate Exhaust Sample Continuous (d) 92 days Sr-89, Sr 90 1x10*ll f
(f) Composite Particulate Sample Continuous (f) Noble Gas Noble Gases 1x10-6 Monitor Gross Beta or Gamma l
B.
(1) Offgas Post 31 days 31 days Principal Gamma 1x10*4 Treatment Grab temple (f)
Emitters (e)
Exhaust, whenever
~
there is flow (2) Standby Gas Treatment A Exhaust, whenever there is flow (3) Standby Gas Treatment B Exhaust, whenever there is flow See ' Table Notation" which follows.
e*,/95 GRAND GULF, UNIT 1 A 39
. Revision 17
ThMT.R g,11,(.1 ( f*nnt 4 M"adi RADIQAcrIVE GAAROUS WAS'11 SAMFt.,ING AMD AMkLYSIS PROGRAal IABL L E TI hII M The LLD is the smallest concentration of radioactive material in a sample that a.
will yield a not count (above systest background) that will be detected with 95%
probability with only 5% probability of falsely concluding that a blank observation represents a 'real" signal.
For a particular measurement system (which may include radiochemical separation) :
4.56 sb LLD =
IeVe 2.22 x 100* Y
- exp (-AAt) where LLD is the "a prioria lower limit of detection as deft.:0 3bove (as pCi per unit mass or volume).
(current literatures defines the LLD as the detection capability for the instrumentation only, and the MDC, minianas detectable concentration, as the detection capability for a given instrument, procedure, and type of sample.)
is the standard deviation of the background counting rate or of the sb counting rate of a blank sample as appropriate (as counts per minute)
I is the counting efficiency (as counts per disintegration)
V is the sample sise (in units of mass or volume) 6 is the number of disintegrations per minute per microcurie 2.22 x 10 Y
is the fractional radiochastical yield (when applicable)
A is the radioactive decay constant for the particular radionuclide At is the elapsed time between sample collection (or and of the sample collection period) and time of counting The value of ob used in the calculation of the LIA for a particular measurement system should be based on the actual observed variance of the background counting rate or of the counting rate of the blank esseles (as appropriate) rather than on an unverified theoretically predicated variance.
Typical values of I, V, Y and At should be used in the calculation.
It should be recognised that the LZa is defined as an a nrinri (before the fact) limit representing the capability of a measurement systen and not as a neatariori (after the fact) limit for a particular measurement.
GRAND GULF, UNIT 1 A-40 Revision 17 - 03/95
nat m E.11. 4 1 U nne4an*M manina, uq naes,- a WASTE e-f Tat 2 anm normfygIg pennaw TABLE 30I1TItur (Continued) b.
Analyses shall also be performed following startup from cold shutdown, or a THERMAL POWER change exceeding 15 percent of the RATED THERMkL POWER within a one hour period. his requirement does not apply its (1) routine analysis required by the surveillance Requirements of LCO 3.4.8 shows that the DOSE EQUIvnLErf I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
Samples shall be changed at least once per 7 days and analyses shall be cospleted c.
within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing or after removal from sampler. Sampling and ana'.yses shall be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup or TMBlaskL pouBR change exceeding 15 percent of RATED THERMkL POWER in one hour. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are His analysed, the corresponding LLD's may be increased by a factor of 10.
requirement does not apply if:
(1) routine analysis required by the surveillance Requirements of LCO 3.4.8 shows that the DOSE BQUIVALErr I 131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
J d.
The ratio of the sample flow rate to the sospled stream flow rate shall be known for the time period covered by each does or dose rate calculation made in accordance with ICOs 6.11.4 and 6.11.6.
The principal genna emitters for which the LLD specification applies emelusively e.
are the following radionuclides:
Kr-87, Kr SS, Ze-133, Ze 133m, 1e 135, and Xe-138 for gaseous emissions and akt-54, Fe 59, Co 58, Co 60, 2n 65, 38o 99, Cs 134, Cs 137, Co-141 and Co-144 for particulate emissions. 21s' list does not mean that i
only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported, f.
When a monitor is placed in an inoperable status solely for performance of required surveillance's, entry into associated conditions and Required Actions in accordance with 140 6.3.10 may be delayed for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
)
GRAND GULF, UNIT 1 A-41 Revision 17 - 03/95
6.11 RADIQACTIVE IFFIDEIrfS 6.11.5 GASEQUS EFFLUErf DOSE - NOSLE GASIS LCO 6.11.5 The air dose due to noble gases released in gaseous effluents, from the site to areas at and beyond the SITE SOUNDARY ahall be:
S 5 mrad for gamma radiation and 510 mrad for beta a.
radiation,during any calendar quarter and
{
b.
5 10 mrad for gamma radiation and 5 20 mrad for beta radiation during any calendar year.
APPLICAEILITY:
At all times.
ACTIONS
.......................................... 30738.......................................
1.
The provisions of Specification 3.0.3 are not applicable.
2.
Separate Condition entry is allowed for each of the above limits.
CONDITION REQUIRED ACTION COMFLirfION TIME A.
The calculated air dose A.1 Initiate action to prepare Immediately from the radioactive noble and submit, a Special gases in gaseous effluents Report within 30 days.
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greater than any of the above limits.
M A.2 Declare the ventilation exhaust treatiment systest inoperable..
(continued)
)
j GRAND GULF, UNIT 1 A.42 Davision 17 - 03/95
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I S.
The calculated doses from B.1 Initiate action to Imeediately the release of radioactive calculate the direct materials in gaseous radiation contributions affluents greater than freut the reactor unit and l
twice any of the above frami outside storage tanks to determine whether the l
limits.
total annual dose or dose comutitment to any MERBER OF l
'DtB PUBLIC greater thans l
a) 25 area to the total l
body or any organ, except the thyroid.
QB i
I b) 75 aresi to the l
thyroid.
svavEIT ' m_=r3 n+_-ns-
.s EURVIILIANCE 1
l SR 6.11.5.1 Cumulative dose contributions for noble gases for 31 daye the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the CDQE.
)
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l GRAND GULF, UNIT 1 A-43 Revisica 17 - 03/95 1
6.11 RADIOACTIVE IFFIRENTS 6.11.6 GASBOUS BFFLUENT DOSE. IODINE.131, IODINE.133, TRITIIRf AND RADIONUCLIDES IN PARTICULATE Folet LCO 6.11.6 The dose to a MEISER OF THE FUBLIC from iodine.131, iodine.133, tritium and radionuclides in particulate form with half. lives greater than 8 days in gaseous effluents released, from the site to areas at and beyond the SITE BOUNDARY shall be 5 7.5 mrom to any organ during any calendar quarter, and a.
b.
5 15 ares to any organ during any calendar year.
APPLICABILITY:
At all times.
ACTIONS
.......................................... 30T33.......................................
The provisions of Specification 3.0.3 are not applicable.
1.
Separate condition entry is allowed for each of the above limits.
2.
CONDITION REQUIRED ACTICII CORIFLETION TIME A.
The calculated dose fccat A.1 Initiate action to prepare Ismediately the release of iodine.131, and subsiit, a Special iodine.133, tritium and Report within 30 days, radionuclides in particulate form, with
&E half. lives greater than 8 I
days, in gaseous offluents A.2 Declare the ventilation greater than any of the exhaust treatment system above limits.
(continued) i GRAND OULF, UNIT 1 A.44 Revision 17 03/95 1
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1 3.
'nie calculated doses from 5.1 Initiate action to Immediately the release of radioactive calculate the direct materials in gaseous radiation contributions effluents greater than froba the reactor unit and twice any of the above from outside storage tanks l
limits.
to determine whether the total annual dose or dose commitment to any NE3SER OF THE FUBLIC greater thant l
al 25 ares to the total body or any organ, except the thyroid.
98 b) 75 mrom to the thyroid.
l l
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=vn/IIf t2=CE *arTTI--
a.
l SURVEILLANCE FREQUENCY l
I Cumulative dose contributions from iodine 131, 31 days i
SR 6.11.E.1 iodine 133, tritium and radienuclides in particulate form with half-lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the CDCM.
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l GRAND GULF, UNIT 1 A 45 Revision 17 - 03/95
6.11 RADIOACTIVE EFFLUENTS 1
6.11.7 GASBOOS RADWASTE TREATMENT LCO 6.11.7
'the GASSOUS RADWASTE TREATMENT (OFFGAS) SYSTEM shall be in operation.
APPLICABILITY:
When the steen jet air ejector (SJAE) is in operation.
ACTIONS
.......................................... 30T38.......................................
'Ite provisions of Specification 3.0.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME i
A.
Gaseous radwaste from the A.1 Restore treatment to this 7 days SJAE being discharged discharge.
without treatment.
i B.
Required Action A.1 and 3.1 Initiate action to prepare Immediately Associated Cogletion Time and submit a Special Report to the Casumission within not met, 30 days.
SURVEII1ANCE REQUIREMEIFTS SURVIIIIANCE FREQUENCT SR 6.11.7.1 Insure that the GASBOUS RADWASTE TREATMElrf 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (OFFGAS) SYSTEM is operating.
GRAND GULF, UNIT 1 A.46 Radston 17 03/95
6.11 RADIOACTIVE BFFIDI3rFS 6.11.8 VIIrrILATICII EINADST TREATSIENT SYSTEM The VIIrFILATION IINADST TREATSIBIrr SYSTEM shall be used to reduce LCO 6.11.8 radioactive materials in gaseous weste before their discharge when the projected dose due to gaseous effluent releases to areas at and beyond the SITE m a*Y in a 31 day period would exceed 0.3 mrom to any organ.
APPLICAEILITY:
At all times.
ACTIONS
.......................................... 3IUTES.......................................
The provisions of Specification 3.0.3 are not applicable.
COIIDITION R8 QUIRED ACYION CNFLETICII TI31E I
A.
Gaseous waste being A.1 Initiate action to prepare Immediately discharged without and submit a Special Report treatment and greater than to the Commission within the above limit.
30 days.
SURVIIIIAIICE "mIREBIEIFFS SURVEILLANCE FREQUERICY SR 6.11.0.1 Doses due to gaseous releases to areas at and 31 days beyond the SITE 300BEART shall be projected in accordance with the methodology and parameters in the OD W,
&E
.......................IIUrs..................
- 1. Not required to be met when the ventilation exhaust treatment system is undergoing routine maintenance.
- 2. Not required to be met when the projected dose less than or equal to the above limit.
l verify the ventilation exhaust treatment system is operating.
)
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GRAID GULF, UNIT 1 A.47 Revision 17 - 03/95 i
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6.12 RADIO 14GICAL ENVIROISBrfAL EIIITVRING 6.12.1 3mIII1CRING FROGRAlf D e radiological environmental monitoring program shall be conducted LCO 6.12.1 as specified in ODCRE Table 6.12.1 1.
The results of this program shall be validated by use of an Interlaboratory Comparison Program corresponding to samples required by QDCM Table 6.12.1 1.
APPLICARILITY:
At all times.
ACTIONS
...........................................gsgr33......................................
The provisions tro 3.0.3 are not applicable.
CONDITICII REQUIRED ACTICE CCIIFLETICII TIRE A.
The radiological A.1 Initiate action to include Immediately environmental monitoring in the next Annual program not being Radiological Environmental conducted as specified in Operating Report, a ODCat Table 6.12.1 1.
description of the reasons for not conskacting the program as required and the Q3 plans for preventing a The required recurrence.
Interlaboratory Comparison Program not performed.
a.
ne level of radioactivity B.1 Initiate action to prepare Immediately i as the result of plant and submit a special effluent in an Report within 30 days.
environmental sampling medium at a specified location exceeding the reporting levels of CDCIE Table 6.12.1 2 when averaged over any calendar quarter.
(continued)
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j GRA E GULF, ENIT 1 A 48 Revision 17 03/95 f
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ACTIOWS (conti~ "-)
CONDITION REQUIRED ACTION CONFLETION TIME C.
Milk or broad leaf C.1 Initiate action to identify Isasediately vegetation sampling is this changed location (s) in relocated from one or more the next Annual Radioactive of the sample locations Effluent Release Report, required by ODCM Table 6.12.1-1.
451 C.2 Add this location (s) to the 30 days radiological envi m tal monitoring program.
SURVII" *""W * "?IRERWrfS SURVIILLANCE FR3QUINCY SR 6.12.1.1 Radiological environmental monitoring samples Per ODCM shall be collected pursuant to CDCM Table 6.12.1-1 Table 6.12.1-1.
from the locations given in the table and figures in the ODCM and shall be analysed pursuant to the requirements of ODCM Tables 6.12.1-1 and 6.12.1 3.
SR 6.12.1.2 Conduct an Interlaboratory Co w isca Program and 365 days include a summary of the remales in the Annual Radiological Environmental Operating Report.
GRAND 0017, UNIT 1 A-49 Revision 17 - 03/95
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Timf., s.19_1 1 t rana mmm OpFD ATTr%f17. 9174Tnf af17t*17. ENVf D rusman'NTif. MONTTODTMt2 PRor201ht TABLE NOTATION As described in the ODCM.
If a location is not accessible, instruments may be placed in an adjacent inner or outer location.
specific parameters of distance and direction sector from the centerline of one a
reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 6.12.1-1 in the table (s) and figure (s) in the ODCM.
Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979.
Deviations are permitted from the required sangling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.
If specimens are unobtainable due to sampling equipment, malfunction, every effort shall be made to complete corrective action before the end of the next sampling period. All above deviations from the sampling schedule shall be documented in the Annual Radiological Enviranamental Operating Report.
It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.
In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program.
Identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining replacement samples in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table (s) for the ODCM reflecting the new location (s).
b Particulate sample filters should be analyzed for gross beta 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sangling to allow for radon and thoron daughter decay.
If gross beta activity in air or water is greater than ten times the yearly mean of control samples for any medium, gamma isotopic analysis should be performed on the individual samples, Gamma isotopic analysis means the identification and quantification of gasuna-c emitting radionuclides that may be attributable to the affluents from the facility.
d The purpose of this sample is to obtain background inforination, i
f GRAND GULF, IDTIT 1 A.53 Revision 20 - 07/96
TABLE 6.12.1-1 (Continued)
OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TARM NOTATION (Continued) one or more instrumeists, such as a pressurized ion chamber, for measuring and e-recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters.
For the purposes of this table, a thermoluminescent dosimeter may be considered to be one phosphor and two or more phosphors in a packet may be considered as two or more dosimeters.
Film badges should not be used for measuring direct radiation.
i GRAND GULF, UNIT 1 A-54 Revision 20 - 07/96
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taar.m E.12.1 2 maae4an d narIaEBf VAIREE FOR 'ZME IDWER LIMITS Of DETECTIQE (LLp)
TABLE NOTATIQE Acceptable detection capabilities for thermoluminescent dosimeters used for a.
environmental measurements are given in Regulatory Guide 4.13.
b.
Table 6.12.1 3 andicates acceptable detection capabilities for radioactive materials in enviran==atal samples. These detection capabilities are tabulated in terms of the lower limits of detection (Llas). The LID is defined, for purposes of this guide, as the smallest concentration of radioactive material in a sample that will yield a not count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
I For a particular measurement system (which may include radiochemical separation) :
4.66 og esp (-14t)
I
- V e 2.22
- Y
- where LLD is the "a priori" lower limit of detection as defined above (as pci per unit mass or volume).
(current literature defines the LLD as the detectica capability for the instrumentation only, and the tec, minimum detectable cenoentration, as the detection capability for a given instrument, procedure, and type of sample.)
e is the standard deviation of the background counting rate or of the i
D counting rate of a blank sagle as appropriate (as counts per minute)
E is the counting efficiency (as counts per disintegration) v is the sasyle size (in units of mass or volume) 2.22 is the number of disintegrations per minute per picocurie Y
is the fractional radiochemical yield (when applicable) l 1,
is the radioactive decay constant for the particular radionuclide at is the elapsed time between sample collection (or end of the sample collection period) and time of counting The value of sb used in the calculation of the LLD for a particular measurement system should De based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicated variance.
GRAND GULF, UNIT 1 A 57 Revision 17 - 03/95 j
J TamT_m g,12,1 2 (r'ame 4 anad)
"WT % Vatnme FOR 'f1tB M T NTTS OF L-1-ulder (f fn)
TABLE EDT& TION (Continued)
Typical values of I, V, Y and At should be used in the calculation.
It should be recognised that the LIa is defined as an a agiggi (before the fact) limit representing the capability of a measurement system and not as a naateriori (after the fact) limit for a particular measurement. Occasionally background fluctuations, unavoidable small sample eise, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unschievable.
In such cases, the contributing factors should be identified and described in the Annual Radiological Environmental Operating Report.
c.
LLD for drinking water samples. If no drinking veter pathway exists, the LLD of gasma isotopic may be used.
3 d.
If no drinking water pathway exists, a value of 3 x 10 pCi/1 may be used, i
I j
l i
ORMED GULF, UIFIT 1 A 58 Revisica 17 03/95 J
6.12 RADIOLOGICAL ENVIRODMIlrIAL MONITORING 6.12.2 LAND USE CENSUS LCO 6.12.2 A 2e31 use census shall be conducted and shall identify within a i
dia /.nce of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50 m2 (500 ft2) producing broad leaf vegetation. Broad leaf vegetation, sampling may be performed at the SITE BOUNDARY in one of two different offsite locations with the highest predicted D/Qs in lieu of the garden census.
APPLICABILITY:
'At all times.
ACTIcers
.......................................... NOTES----------------------
The provisions of LCO 3.0.3 are not applicable.
CONDITIOtt REQUIRED ACTION COMPLETION TIME A.
A land use census A.1 Initiate action to identify Inunediately identifies a location (s) the new location (s) in the which yields a calculated next Annual Radioactive dose or dose comunitment Effluent Release Report.
greater than the values currently being calculated in LCO 6.11.6.
B.
A land use census B.1 Initiate action to identify Inunediately identifies a location (s) these higher dose which yields a calculated location (s) in the next dose or dose comunitment Annual Radioactive Effluent (via the same exposure Release Report.
pathway) 20 percent greater than at a location AMD from which samples are currently being obtained B'. 2 Add these location (s) to 30 days in accordance with LCO the radiological 6.12.1.
environmental monitoring program.
GRAND GULF, UNIT 1 A-59 Revision 20 - 07/96 1
l i
SURVEILLANCE REQUIREMBrrs SURVEILLANCE FREQUENCY SR 6.12.2.1 Conduct a land use census during the growing Once per 2 years season. The land use census shall verify the appropriateness of the sagle location used to fulfill the requirements of LCO 6.12.1 l
c I
i l
l GRAND GULF, UNIT 1 A-60 Revision 20 - 07/96 9
Basas FCE SECTION 6.0 LIMITING CCEDITICES FOR OPERATION AND SURVIILIANCE REQUMM i
i l
I 1
GRAND QULF, UNIT 'i A 61 Revision 17 - 03/95 J
1 6.3 INSTEERIErfATIQI(
RASIS 6.3.9 RADIh1W t IOtf1D EFFTMWWT --1inines i
=1-1 ATION The LCO for radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicchle, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip seepoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur before exceeding ten times the effluent concentration limits of 10 CFR Part 20.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General design Criteria 60, 63 and 64 of Appendix A to 10 CFR 50.
6.3.10 m21N* RIVE GARROT!B EFFIDErf MMITORIMI INTICE The LCO for radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, gaseous effluents during actual or potential releases. Those instruments that monitor the activity of gaseous effluents being released to the environment shall have their alarm / trip setpoints calculated in accordance with the methods in the ODQt to ensure that the alarm / trip will occur before exceeding the limits of 10 CFR Part 20.
Other instruments that monitor offgas processing, (i.e., Offges Pre Treatment IIonitor and Offgas Post-Treatment tionitor) are calibrated according to plant procedures. The OPERASILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
GRAND GULF, UNIT 1 A-62 Revision 17 - 03/95 Y
E.11 RADIMIVE EFFtrmrTS RAEEE LIQUID EFFLUENTS E.11.1 t Ontam =ATION This LCO is provided to ensure that the concentration of radioactive materials released in liquid waste affluents to UNRESTRICTED ARIAS will be less than ten times the effluent concentration values specified in Appendix B, Table 2, Colusst 2 to 10 CFR 20.1001 20.2402.
It provides operational flexibility for releasing liquid effluents in concentrations to follow the Section II.A and II.C design objectives of Appendix I to 10 CFR Part 50.
His limitation provides reasonable assurance that the levels of radioective materials in bodies of water in UNREETRICTED AREAS will result in exposures within (1) the Section II.A design objectives of W a* x I, 10 CFR 50, to a MEISER OF THE PUBLIC, and (2) restrictions authorised by 10 CFR 20.1301(a). The concentration limit for dissolved or entrained noble gases is based upon the assuspelon that Xe 135 is the controlling radionuclide and its affluent concentration in air (submersion) was converted to an equivalent concentration in water. This ICO does not affect the requiressme to comply with the annual limitations of 10 CFR 20.1301(a).
The results of pre-release analyses and post release analyses (of composited samples) shall be used with the calculational methods and parameters in the CD M to assure that the concentrations at the point of release are maintained within the limits.
The required detection capabilities for radioactive materials in liquid waste Detailed samples are tabulated in terms of the lower limits of detection (LIDS).
discussion of the LLD, and other detection limits, can be found in:
(1) HASL Procedures Manual, E48Ic222 (2) Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry,* Anal. Chem. 40, 586 99 (1964).
(3) Martwell, J.
K., " Detection Limits for Radioisotopic Counting Techniques,"
Atlantic Richfield Hanford Company Report AEM-2127 (June 22, 1972).
6.11.2 DORE This LCO is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50.
De ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in section IV.A of Appendix I which assure that the releases of radioactive material in liquid offluents to UNRESTRICFED AREAS will be kept 'as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is ramaaaahle assurance that the operation of the facility will not result in radionuclida concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. De dose calculations in the CDCM implement the requirements in section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MERSER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
GRAIS GULF, UNIT 1 A 63
' Revision 17 - 03/95
]
RADIQACTIVE EFFIDElrrs macts s.11.2 DORE (Continued)
The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive eaterials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, ' Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Ivaluating Ccupliance with 10 CFR Part 50, Appendix I,* Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluent from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I,' April 1977.
This I,CO, in conjunction with ICOs 6.11.5 and 6.11.6 is also provided to meet the dose limitation of 40 CFR 190 that has been incorporated into 10 CFR 20.1301(d).
Even if a site contained up to four reactors, it is highly unlikely that the..
resultant dose to a MEISER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within twice the dose design objectives of 10 CFR 50 Appendix I, and the direct radiation doses from the units (including outside storage tanks, etc.) are kept small.
Special Report:
LCO 6.11.2 requires preparation and submittal of a report in accordance with 10 CFR 50.4 and as defined in 10 CFR 20.2203 (a) (4), if the dose design objectives of 10 CFR 50 Appendix I are exceeded.
1 If either the quarterly or the annual limit is exceeded, the report will:
(1) identify the cause(s) for exceeding the limit (s),
(2) define the corrective actions that have been taken to reduce the releases, and (3) define the corrective actions to be taken to ensure that future releases will be in compliance with the limits.
If a drinking water supply is taken from the receiving water body within three miles downstream of the plant discharge, the report shall also includes (1) results.of radiological analyses of the drinking water source, and (2) the radiological ispect on finished drinking water supplies with regard to the requirements of 40 CFR 141.
If the doses exceed the limits of 40 CFR 190, 25 areas to the whole body or any organ, except the thyroid, which is limited to 75 areas, the report shall:
(1) define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits, (2) include the schedule for achieving conformance with the above limits, (3) include an analysis that estimates the radiation esposure (dose) to a NEMBER OF '!1tB PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report, (4) describe the levels of radiation and concentrations of radioactive material
- involved, (5) describe the cause of the esposure level or ecocentratione involved, GRAND GULF, UNIT 1 A 64 Revision 17 - 03/95
RADIOACTIVE EFFIDIFFS macas s.ii.2 Dost (Continued)
(6) describe a course of action that should result in the limitation of the annual dose to a MMSER OF M PUBLIC to within the 40 CFR 190 limits.
For the purposes of the report it may be assumed that the dose ccouaitment to the MEISER OF M PUBLIC from other uranium fuel cycle sources is negligible, with the exception that the dose distribution from other nuclear fuel cycle facilities at the same site or within a radius of 8 kilometers must be considered.
The Special Report with a request for a variance (provided the release conditions resulting in a violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203 (a) (4), is considered to be a timely request and fulfills the requirements of 40 CFR 150 until NRC staff action is completed. '!he variance only relates to the limits of 40 CFR 190, and does not apply in any way to other requirements for dose limitations of 10 CFR 20, as addressed in LCOs 6.11.1 and 6.11.4.
An individual is not considered a MERSER OF THE PUBLIC during any period in whidt he/she is engaged ira carrying out any operation that is part of the nuclear fuel cycle.
Demonstration of compliance with the limits of 40 CFR 190 or with We design objectives of Appendix I to 10 CFR 50 will be considered to descarcrate compliance with the 0.1 rem limit of 10 CFR 20.1301.
i
\\
~
1 i
ORAIS GULF, UNIT 1 A-65 Revision 17 - 03/95
RADIOACTIVE EFFIDElfrS mmenn 6.11.3 LIOt71D M&sTE Tawf*'"I' The LCO that the appropriate portions of this afstem be used when specified provides assurance that the releases of radioactiw materials in liquid effluents will be kept "as low as is reasonably achievable.' Sie LCO implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50, he specified limit governing the use of appropriate portions of the liquid radweste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.
Special Report:
LCO 6.11.3 requires preparation and submittal of a report in accordance with 10 CFR 50.4 if radioactive liquid waste is being discharged without treatment and in excess of the limits. The report shall include:
(1) an emplanation why liquid radweste was being discharged without treatment, (2) identification of any inoperable equipment or subsystems which resulted in liquid radwaste being discharged without treatment, (3) the reason for the inoperability (4) action (s) taken to restore the inoperable equipment to an OPERABLE status, (5) summary descriptions of actions taken to prevent a recurrence.
GASEODS EFFIDENTS E.11.4 Men wf'E i
Thia 140 provides reasonable assurance that radioactive material discharged in gaseous affluents will not result in the emposure of a IE SER OF TER PUBLIC in an UltRESTRICTED AREA, either at or beyond the SITE 30tMnARY in excess of the design objectives of Appendix I to 10 CFR Part 50.
This specification is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled.
It provides operational flexibility for releasing gaseous effluents to satisfy the For Im SERS Section II.A and II.C design objectives of Appendix I to 10 CFR Part 50.
i OF THE FUBLIC who may at times be within the SITE 30tMnARY, the occupancy of that MDBER OF 'DtB PUBLIC will usually be sufficiently low to =Taaante for the reduced i
atmosphere dispersion of gaseous effluents relative to that for the SITE " n m *Y.
The calculational methods and parameters in the ODOE are used to assure that the dose rates are maintained within the limits. kaasples of calculations fos such - man oF THE PUBLIC, with the appropriate occ m factors, shall be given in the CDQt. The specified release rate limits restrict, at all times, the corresponding does rates above background to a ImSER OF THE FUBLIC at or beyond the SITE 300MnARY to less than or equal to 500 ares / year to the total body or to less then or equal to 3000 Rose releases rate limits also restrict, at all times, the mrom/ year to the akin.
corresponding thyroid does rate above background to a child via the inhalation l
pathway to less than or equal to 1500 ares / year. This specification does not affect the requirement to comply with the====M limitations of 10 CFR 20.1301(a).
he does rate due to radioactive gaseous effluents shall be determined in accordance with the methodology and parameters of the CDGE.
GRAND GULF, UNIT 1 A 66 Revision 17 - 03/95
)
RADIQ CJIVE REFIM MTS aAsas s.ii.4 ooss num (Continued)
The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits, can be found ins (1) HASL Procedures Manual, NASL 100 (revised annually).
(2) Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Cham. 40, 586-93 (1968).
(3) Hartwell, J.
K.,
' Detection Limits for Radioisotopic Counting Techniques,*
Atlantic Richfield Hanford Company Report ARE 2537 (June 22, 1972).
g.ii.s nnen. wuarm amena This LCO is provided to implement the requirements of Sections II.5, III.A and IV.A of Appendix I, 10 CFR Part 50.
Se Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I.
Se ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAR will be kept "as low as is reasonably achievable."
The surveillance Requirements implement the requirements in section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual emposure of a Im SER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
The dose calculations established in the CDQt for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Rifluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"
Revision 1, October 1977 and Regulatory Guide 1.111, "Mothods for Estimating h % ric Transport and Dispersion of Gaseous Effluents in Routine Releases frcan Light Water Cooled Reactors," Revision 1, July 1977 The ODC3R equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.
This LCo, in conjunction with LCOs 6.11.2 and 6.11.6 is also provided to meet the dose liuit..:. tion of 40 CFR 190 that has been incorporated into 10 CFR 1301(d). Even if a sito can'.ained up to four reactors, it is highly unlikely that the resultant dose to a M m *R OF THE PS LIC will exceed the dose limits of 40 CFR 490 if the individual reactors remain within twice the dose design objectives of 10 CFR 50 Appendix I, and if the direct radiation doses from the units (including outside storage tanks, etc.) are kept small.
GRAND 00LF, UNIT 1 A 67 Revision 17 - 03/95
)
RADICACTIVE IFFIEIFfS nASES 6.11.5 DOSE - NOaLE M ERE (Continued)
Special Report:
4 LCO 6.11.5 requires preparation and submittal of a report in accordance with 10 CFR 50.4 and as defined in 10 CFR 20.2203 (a) (4), if the dose design objectives of 10 CFR i
50 Appendix I are exceeded.
If either the quarterly or the annual limit is exceeded, the report will:
(1) identify the cause(s) for exceeding the limit (s),
(2) define the corrective actions that have been taken to reduce the releases, and (3) define the corrective actions to be taken to ensure that future releases will be in compliance with the limits.
If the doses exceed the limits of 40 CFR 190, 25 areas to the whole body or any organ, except the thyroid, which is limited to 75 areas, the repott shall:
(1) define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits, (2) include the schedule for achieving conforesace with the above limits, (3) include an analysis that estimates the radiation esposure (dose) to a MIMBER OF T1tI FUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report, describe the levels of radiation and concentrations of radioactive maderial (4)
- involved, (5) describe the cause of the exposure level or concentrations involved, (6) describe a course of action that should result in the limitation of the annual dose to a MERSIR OF THE FUBLIC to within the 40 CFR 190 limits.
For the purposes of the report it may be assumed that the does commitment to the MInEBER OF ' lits PUBLIC from other uranium fuel cycle sources is negligible, with the exception that the dose distribution from other nuclear fuel cycle f acilities at the serae site or within a radius of 8 kilometers must be considered.
The Special Report with a rdquest for a variance (provided the release conditions resulting in a violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203 (a) (4), is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed.
The variance only relates to the limits of 40 CFR 190, and does not apply in any way to other requirements for dose limitations of 10 CFR 20, as addressed in LCOs 6.11.1 and 6.11.4.
An individual is not considered a MBbSER OF THE FtBLIC during any period
- +
in which he/she is engaged in carrying out any operatica that is part of the nuclear fuel cycle.
Demonstration of compliance with the limits of 40 CFR 190 or with the design objectives of Appendix I to 10 CFR 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301.
1 i
GRAND 00LF, UNIT 1 A 68 Revision 17 - 03/95 i
i
RADICACTIVE EFFLUENTS aARER 6.11.6 DoEE IODTwf 111. IODTME-111. TRITItBf m aminesw=t Tnne 13 pantient,ayg yegg This LCO is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50.
1he Limiting Conditions for Operation are the guides set forth in Section II.C of AppanM w I.
The ACTIOgi statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous affluents to UINtBSTRICTED AREAS will be kept "as low as is reasonably achievable." The CDC38 calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A. of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual esposure of a REIBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The OOCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,'
Revision 1, October 1977 and Regulatory Guide 1.111, "Blethods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Rautine Releases from Light water Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for iodine-131, iodine-133, tritium and radionuclides in particulate form are dependent on the existing radionuclide pathway to man in the areas at and beyond the SITE SM unamY. The pathways which were examined in the development of these calculations were (1) individual inhalecion of airborna radianuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and snac producing animals grase with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.
This LCO, in co* junction with LCOs 6.11.2 and 6.11.5 is also provided to meet the dose limitation of 40 CFR 190 that has been incorporated into 10 CFR 1301(d). Even if a site contained up to four reactors, it is highly unlikely that the resultant dose to a MERSER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within twice the dose design objectives of 10 CFR 50 Appendix I, and if the direct radiation doses from the units (including outside storage canas, etc.) are kept small.
Special Report:
LCO 6.11.6 requires preparation and submittal of a report in accordance with 10 CFR 50.4 and as defined in 10 CFR 20.2203 (a) (4), if the dose design objectives of 10 CFR 50 Appendix I are exceeded.
If either the quarterly or the annual limit is exceeded, the report will:
(1) identify the cause(s) for exceeding the limit (s),
j (2) define the corrective actions that have been taken to reduce the releases, and (3) define the corrective actions to be taken to ensure that future relenes 1
- +
will be in compliance with the limits.
{
GaARD GULF, UNIT 1 A-69
' Revisions 17 03/95 i
RADICE" RIVE EFFLDIFFS aists C.11.E DOst - IODTM 111. Tonfun.111. TRITITBf mam manrogy f.TBES IN sARTICDTEf'Eg (Continued)
If the doses exceed the limits of 40 CFR 190, 25 areas to the whole body or any organ, except the thyroid, which is limited to 75 mress, the report shall:
(1) define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits, (2) include the schedule for achieving conformance with the above limits, (3) include an analysis that estimates the radiation esposure (dose) to a MERSER OF THE FUBLIC from uranium fuel cyc1s sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report, (4) describe the levels of radiation and concentrations of radioactive material
- involved, (5) describe the cause of the emposure level or concentrations involved, (6) describe a course of action that should result in the limitation of the annual dose to a man OF THE FUBLIC to within the 40 CFR 190 limits.
For the purposes of the report it may be assumed that the dose cosmitment to J
the MEIBER OF THE FUBLIC from other uranium fuel cycle sources is negligible, with the exception that the dose distribution from other nuclear fuel cycle facilities at the same site or within a radius of 8 kilometers must be considered.
The special Report with a request for a variance (provided,the release conditions resulting in a violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203(a) (4), is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is ccepleted.
'Jhe variance only, relates to the limits of 40 CFR 190, and does not apply in any way to other requirements for dose limitations of 10 CFR 20, as addressed in 140s 6.11.1 and 6.11.4.
An individual is not oansidered a man OF ' lits PtSLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
Demonstration of compliance with the limits of 40 CFR 190 or with the design objectives of Appendix I to 10 CFR 50 will be considered to demonstrate cospliance with the 0.1 rem limit of 10 CFR 20.1301.
l ORAND GULF, UNIT 1 A-70 Revision 17 - 03/95
l RADICACTIVE EFFICIES RAEIs 6.11.7 and E.1i.a amitE w =anumeTE Teen'm==r un verritAtros wrunnet Team 1=mem?
The OPERASILITY of the GASBOUS RADMASTE TREATIE3rf (OFFGAS) SYSTEM and the VElffILATION EXMADST TREATMEarf SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment before release to the environment.
The requirement that the appropriate portions of the system be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification inglements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of The specified limits governing the use of appropriate Appendix I to 10 CFR Part 50.
portions of the system were specified as a suitable fraction of the dose design objectives set forth in Section 11.5 and II.C of Appendix I, 10 CFR 50, for gaseous effluents.
Special Report:
LCOs 6.11.7 and 6.11.8 require preparation and submittal of a report in accordance with 10 CFR 50.4 including:
(1) an explanation of why gaseous redweste was being discharged without treatment, i2) identification of the inoperable equipment or subsystems which resulted in gaseous radwaste being discharged without treatment, (3) the reason for the inoperability, (4) action (s) taken to restore the inoperable equipment to an OPERABLM status, (5) sussnary descriptions of action (s) taken to prevent a recurrence.
.g LCO 6.11.8 is not applicable to the Tarbine Building ventilation exhaust unless filtration media is installed.
Instruments checked to ensure the GASBOUS RADMASTE T1tEATMEIFF (OFFGAS) SYSTEM is functioning are (1) Adsorber Train Bypass Switch (1N64-MS M611),
(2)
Bypass Valve Indication (1N64 FU45).
When the Adsorber Train Bypass Switch is in the TREAT position and the bypass valve indicates CLOSED, the GASEOUS RADWASTE TREATMB3rr (OFFGAS) SYSTEM is functioning.
GRAND GULF, UNIT 1 A 71 Revision 17 - 03/95
i 6.12
- 1 MIN MIF1L ENVW~
M^=-wSN amegg 6.12.1 hamtramann sammana The radiological monitoring program required by this 140 provides measurements of radiation and of radioactive materials in those egosure pathways and for those radionuclides, which lead to the highest potential radiation emposures of MERSERS OF THE PUBLIC resulting from the station operation. This monitoring program isplementsSection IV.R.2 of Appendix I to 10 CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational egorience.
De detection capabilities required by Table 6.12.1-3 are state-of the art for routine environmental measurements in industrial laboratories. It should be recognised that the Lla is defined as an "a priori' (before the fact) limit representing the capability of a particular measurement. Analyses shall be performed in such a manner that the stated L1as will be a&ieved under routine conditions.
Occasionally background fluctuations, unavoidably small sample sises, the presence of interfering nuclides, or other uncontrollable circumstances may render these LIas unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Enviromaantal Operating Report.
For a more cosplete discussion of the LID, and other detection limits, see the followings (1) HASL Procedure Manual, MaaL-200 (revised annually).
(2) Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Cham. 40, 586 93 (1968).
(3) Hartwell, J.
K., " Detection Limits for Radioisotopic Counting Technicms,"
Atlantic Richfield Ranford Company Report M 2321 (June 22,1972).
If milk or broadleaf vegetation sampling locations are relocated, the cause shall be reported in the next Annual Radioactive Effluent Release Report. Also, include in j
revised CDCM figure (s) and table (s) reflecting the new locations. The this report, specific locations from whie sosples were unavailable may then be deleted from the in the CDCM, provided radiological environmental monitoring program and the table (s) the locations from which the replacement sag les were obtained are added to the table (s) as replacement loosticas.
n e requirement for participation in an approved Interlaboratory Comparison i
Program is provided to ensure that indaranAmnt checks on the precision and accuracy of the measures of radioactive material in envircemental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.
GRAIC GULF, UNIT 1 A-72 4, vision 17 - 03/95
I E.12 maintmirat-EEVTL M - -1 r e FM maene E.12.1
--rreTm PWa" (Continued)
Special Report:
LCO 6.12.1 requires preparation and submittal of a report in accordance with 10 CFR 50.4 when:
the level of radioactivity as a result of plant effluents in an environmental sampling medium at a specified location exceeds the reporting (1) 1evel(s) in 0008 Table 6.12.1 2 when averaged over a calendar quarter, or more than one of the radio nuclides in CDQt Table 6.12.1-2 are detected in (2) the sampling meditam and eenmentracian (21
+.. 11.0, or j
,.aa - ceneina (11
+
reporting level (1) reporting level (2) j radio nuclides other than those in CDQt Table 6.12.1-2 are detected, and (3) i the potential annual dose to a M3SER OF 'IER PtBLIC is equal to or greater than the calendar year limits of ICOs 6.11.2, 6.11.5 and 6.11.6.
The report shall (1) identify the cause(s) for escoeding the limit (s), and 1
i (2) define the corrective actions to be taken to reduce radioactive effluents so the potential manumt does to a MP8mm8 0F TIII PERLIC is less than the calendar year limits of LCOs 6.11.2, 6.11.5 and 6.11.6.
The Special Report is not required if the measured level of radioactivity is not the result of plant offluents; however in such an event, the condition shall be reported and identified in the annual Radiological Environmental Operating Report.
~\\
E.12.2
?**
fME f*""'u This LCO is provided to ensure that ebenges in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological envircemental The best monitoring program are made if required by the results of the census.
information from door to door survey, visual or aerial survey or from consulting with
'this census satisfies the requirements local agricultural authorities shall be used.
Restricting the census to gardens of Section IV.S.2 of Appendix I to 10 CFR Part 50.
provides assurance that significant eagposure pathways via leafy 2
of greater then 50 m vegetables will be identified and monitored since a garden of this siae is the minimum required to produce the quantity (26 kg/yearl of leafy vegetables assumed in TW determine this minimum garden Regulatory Guide 1.109 for constaytion by a child.20% of the garden was used for aise, the following assumptions were made:
(1) and (2) a growing broad leaf vegetation (i.e., similar to lettuce med cabbage),
Specifications for broad leaf vegetation sosyling in vegetation yield of 2 kg/m'.
the Table 6.12.1-1 shall be followed, including analysis of control samples.
GRAND GOLF, UNIT 1 A 72 Revision 17 - 03/95
l 6.12 PMf 0fDGICAL ENVIRO 1nmFTAL lONITORI193 BASES l
6.12.2 1AND USE CINEUS (Continued)
The land use census should utilise information which provides the best results, such as a door to door survey, an aerial survey or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual I
Radiological Invironmental Operating Raport pursuant to Technical Specification 5.6.2.
When the Land Use Census requires addition of sampling location (s) to the Environmental Monitoring Program, the sampling locations (s) having the lowest calculated dose or dose ecsuaitments(s), via the same exposure pathway, may be deleted j
from the monitoring program. ' Itis deletion may take place af ter October 31 of the year in which this land use census was conducted.
The new sampling location (s) shall be identified in the next Annual Radioactive l
Effluent Release Report including a revised figure (s) and table (s) for the ODCM.
I GRAND GULF, UNIT 1 A.74 Revisico 17 - 03/95 L