ML15224A893
| ML15224A893 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, Catawba, McGuire  |
| Issue date: | 06/17/1991 |
| From: | Tuckman M DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML15224A894 | List: |
| References | |
| NUDOCS 9106240244 | |
| Download: ML15224A893 (42) | |
Text
DUKE POWER COMPANY EMERGENCY DOSE ASSESSMENT MANUAL April 1, 1991 a1
TABLE OF CONTENTS EDA-1 Procedure for Estimating Food Chain Doses Under Post-Accident Conditions (Rev. 2)
EDA-2 Off-Site Dose Projections for Catawba Nuclear Station (Rev. 6)
EDA-3 Off-Site Dose Projections for McGuire Nuclear Station (Rev. 7)
EDA-4 Off-Site Dose Projections for Oconee Nuclear Station (Rev. 6)
EDA-5 Mesorem, Jr. Atmospheric Dispersion and Dose Assessment Model Users Manual, Version 4A Catawba (Rev. 0)
EDA-6 Mesorem, Jr. Atmospheric Dispersion and Dose Assessment Model Users Manual, Version 4A McGuire (Rev. 0)
EDA-7 Mesorem, Jr. Atmospheric Dispersion and Dose Assessment Model Users Manual, Version 4A Oconee (Rev. 0)
EDA-8 Environmental Monitoring for Emergency Conditions for Catawba Nuclear Station (Rev. 6)
EDA-9 Environmental Monitoring for Emergency Conditions for McGuire Nuclear Station (Rev. 8)
EDA-10 Environmental Monitoring for Emergency Conditions for Oconee Nuclear Station (Rev. 1)
April 1, 1991
CRISIS MANAGEMENT PLAN IMPLEMENTING PROCEDURE EDA-1 "Procedure for Estimating Food Chain Doses Under Post-Accident Conditions" Approved by:
Date Rev. 2 Sept. 1, 1988
IMPLEMENTING PROCEDURE FOR ESTIMATING FOOD CHAIN DOSES UNDER POST-ACCIDENT CONDITIONS CRISIS MANAGEMENT CENTER 1.0 Purpose The determination of potential areas of concern in the ingestion pathway under post-accident conditions will be made by the Radiological Assessment Manager, based initially upon station releases, prevailing meteorological and hydrological conditions, and confirmatory measurements of dose rates and air sample results by field monitoring teams (when available).
This procedure describes the method to be used in order to estimate offsite doses through significant food chain dose pathways under post-accident conditions.
It is to be used only under the direction of the Radiological Assessment Manager.
2.0 Reference 2.1 U.S. NRC Reg. Guide 1.109.
3.0 Limits and Precautions 3.1 Reg. Guide 1.109 is intended to guide the calculation of doses under long term steady state conditions. The body of this procedure contains notes covering cases in which the calculation of doses under accident conditions differs from the calculation of doses under routine conditions.
3.2 This procedure covers only the calculation of the food chain pathway doses most likely to be limiting under post-accident conditions. Other food chain doses must be calculated using the methods of the Duke Power Company Offsite Dose Calculation Manual or Reg Guide 1.109.
General Office Health Physics personnel shall be consulted when these other food chain doses are calculated.
3.3 The errors in the doses calculated through the use of this procedure are not necessarily conservative (on the high side).
3.4 The assumptions outlined in this procedure shall be carefully compared with existing post-accident conditions before this procedure is used.
3.5 This procedure calculates doses by relating concentration to the uptake by the individual and the associated dose factor (mRem/pCi).
3.6 It is expected that the samples will be collected by off-site monitoring teams under the direction of the Field Monitoring Coordinator.
4.0 Procedure 4.1 Vegetation -
Cow or Goat Milk -
Consumer Dose Pathway for Radioiodine.
4.1.1 Assumptions
Child (Infant) milk consumption:
900 ml/day (2 pints approx.)
Adult milk consumption: 850 ml/day (2 pints approx.)
Decay time between iodine deposition on vegetation and milk consumption: 2 days.
All (100%) of the milk animals' feed is fresh pasture vegetation; if this is known not to be the case, calculate the concentration eaten by the animal by multiplying the concentration in the pasture vegetation by the fraction of feed which is fresh pasture vegetation.
The contribution to dose of 1-132 and 1-134 is negligible because of the short half-lives and small dose factors for these radionuclides.
4.1.2 Doses can be calculated on the basis of radioiodine concen trations measured in or on either grass (or other vegetation consumed by milk animals) or milk.- Doses calculated on basis of milk radioiodine concentrations will be much more accurate than those calculated on the basis of vegetation radioiodine concentrations. However, the measurement of vegetation radioiodine concentrations permits the prediction of approxi mate doses due to milk consumption one or two days later.
Follow-up vegetation radioiodine analysis with milk radio iodine analysis for several days to ensure accurate dose assessments.
4.1.3 Calculation of doses through vegetation analysis:
4.1.3.1 Collect samples of vegetation eaten by milk animals and analyze on GeLi counter. Compute radioiodine concentrations in pCi/gram of undried vegetation.
NOTE:
All calculations for vegetation samples are done for cows; however, if the dose from goat milk is desired, simply multiply the dose from cow milk ingestion by 1.2.
4.1.3.2 Calculate thyroid doses by use of the following equations:
DTCV = 3200 CI-131v + 180 CI-1 33v + 1.1 CI-1 35v DTAV =420 CI-131v + 20 C I-133v + 0.1 CI-1 35v 2
where:
D T=
Human child (infant) thyroid dose commitment in Rems per day milk animal consumes contaminated vegetation.
OTAV
= Same as above for human adult.
C I=
Concentration of 1-131 in vegetation (PCi/g).
C I=
Concentration of 1-133 in vegetation (Pci/g).
C 1=
Concentration of 1-135 in vegetation (Pci/g).
4.1.4 Calculation of doses through milk concentrations:
4.1.4.1 Collect samples of milk and analyze on GeLi counter.
Compute radioiodine concentrations in pCi/ml.
4.1.4.2 Calculate thyroid doses by use of the following equations.
DTCM = 13000 CI-13 1m + 3000 CI-13 3m + 590 CI-135m DTAM = 1700 CI-13 1m + 300 C1-133m + 65 CI-135m where:
D TCM
= Human child (infant) thyroid dose commitment in Rems per day of consumption of contaminated milk.
DTAM
= Same as above for human adult.
CI-131m
= Concentration of 1-131 in milk (IpCi/ml)
CI-133m
= Concentration of 1-133 in milk (pCi/ml)
C I 35m
= Concentrations of 1-135 in milk (PCi/ml)
NOTE: Whole body doses due to radioiodine ingestion will always be much smaller than the thyroid dose.
4.2 Drinking Water + Consumer Pathway for Radiolodine.
4.2.1 Assumptions
Child (infant) water consumption: 900 ml/day (2 pints approx.)
3
Adult water consumption:
2000 ml/day (4 1/3 pints approx.)
Decay time in water distribution system: 1 day.
The contribution to dose of 1-132 and 1-134 is neglible because of the short half-lives and small dose factors of these radionuclides.
4.2.2 Calculation of doses through water concentrations:
4.2.2.1 Collect water samples and analyze on GeLi counter.
Compute radioiodine concentrations in pCi/ml.
4.2.2.2 Calculate thyroid doses by use of the following equations:
DTCW = 12000 C I-131w + 1400 C I-133w + 50 C I-135w DTAW = 3700 C I-131w + 320 C I-133w + 12 CI-135w where:
D T=
Human child (infant) thyroid dose commitment in Rems per day of consumption of contaminated water.
DTAW
= Same as above for human adult.
C 13 1
= Concentration of 1-131 in water (PCi/ml)
C I=
Concentration of 1-133 in water (pCi/ml)
C 1=
Concentrations of 1-135 in water (PCi/ml)
NOTE:
Whole body doses due to radioiodine ingestion will always be much smaller than the thyroid dose.
4.3 Water + Fish Consumer Pathway for Radiocesium
4.3.1 Assumptions
Child (teen) fish consumption:
44 g/day (11 oz. approx.)
Adult fish consumption:
56 g/day (2 oz. approx.)
Bioaccumulation factor for cesium in fish:
2000.
The contribution to dose of Cs-138 is negligible because of its short half-life and small dose factor.
4
4.3.2 Doses can be calculated on the basis of radiocesium concen trations in either water or fish. Doses calculated on the basis of concentrations in fish will be more accurate than those calculated on the basis of concentrations in water.
However, the measurement of water radiocesium concentrations permits the prediction of doses due to future consumption of fish.
4.3.3 Calculation of doses through water analysis:
4.3.3.1 Collect water samples and analyze on-GeLi counter.
Compute radiocesium concentrations in pCi/ml.
4.3.3.2 Calculate whole body doses by use of the following equations:
DBCW = 8000 CCs-134w + 2000 CCs-136w + 4600 C Cs-137w DBAW = 14000 C Cs-134w + 2200 C Cs-136w + 8200 C Cs-137w where:
D BCW
= Human child (teen) whole body dose commitment in Rems per day fish are exposed to contaminated water.
DBAW
= Same as above for human adult.
D
= Concentration of Cw-134 in water (Pci/ml)
C C=
Concentration of Cs-136 in water (Pci/ml)
C C=
Concentration of Cs-137 in water (Pci/ml) 4.3.4 Calculations of doses through fish concentrations:
4.3.4.1 Collect fish samples and analyze on GeLi counter.
Compute radiocesium concentrations in pCi/gram (wet weight).
4.3.4.2 Calculate whole body doses by use of the following equations:
DBCF = 4.0 CCs-134F + 1.0 CCs-136F + 2.3 CCs-137F DBAF = 6.9 CCs-134F + 1.1 CCs-136F + 4.1 CCs-137F 5
where:
D B=
Human child (teen) whole body dose commitment in Rems per day of consumption (at 44 g/day) of con taminated fish.
D BAF
= Human adult infinity whole body dose commitment in Rems per day of consump tion (at 57 g/day) of contaminated fish.
C C=
Concentrations of Cs-134 in fish (pCi/g)
CCs-136F
= Concentration of Cs-136 in fish (pCi/g)
CCs-137F
= Concentration of Cs-137 in fish (pCi/g)
NOTE:
In any one day, a person may easily consume 5 or even 10 times the assumed daily quantity of fish.
Liver doses due to radiocesium ingestion are about two times the whole body doses. The whole body dose limit is 5 Rems, and the dose limit for the liver is 15 Rems; therefore, the whole body doses are limiting.
5.0 Enclosures 5.1 Food Chain Dose Calculations Worksheet 6
.1 FOOD CHAIN DOSE CALCULATIONS WORKSHEET Date:
Performed By:
I. Dose to Thyroid from Radioiodine A.
Vegetation -
Cow or Goat Milk -+ Consumer Dose Pathway
- 1.
Vegetation Analysis:
Date Sampled Location Multiplying Factor-Age Isotope Concentration In (rem/d)
Dose Group (I-Vegetation (pCi/g)
(PCi/g)
(rem/d)
Child 131 3200**
=
(In-133 180**
=
fant) 135 1.1**
=
Total Dose
=
Adult 131 420**
=
133 20**
=
135 0.1**
=
NOTE: Dose is per day animals eat Total Dose
=
contaminated vegetation.
- All multiplying factors for vegetation are for cow milk, if the dose from goat milk is desired, multiply the dose from cow milk calculations by 1.2.
- 2.
Milk Analysis:
Date Sampled Location Multiplying Factor Age Isotope Concentration In (rem/d)
Dose Group (I-Milk (pCi/ml)
(PCi/ml)
(rem/d)
Child 131 13000
=
(In-133 3000
=
fant) 135 590
=
Total Dose
=
Adult 131 1700
=
133 300
=
135 65
=
Total Dose
=
.1 (cont'd)
B.
Drinking Water -* Consumer Dose Pathway:
Date Sampled Location Multiplying Factor Age Isotope Concentration In (rem/d)
Dose Group (I-Water (pCi/ml)
(PCi/ml)
(rem/d)
Child 131 12000
=
(In-133 1400
=
fant) 135 50
=
Total Dose
=
Adult 131 3700
=
133 320
=
135 12
=
Total Dose
=
II. Dose to Whole Body from Radiocesium:
A.
Water -
Fish + Consumer Dose Pathway
- 1.
Water Analysis:
Date Sampled Location Multiplying Factor Age Isotope Concentration In (rem/d)
Dose Group (I-
)
Water (pCi/ml)
(pCi/ml)
(rem/d)
Child 134 8000
=
(teen) 136 2000
=
137 4600
=
Total Dose
=
Adult 134 14000
=
136 2200
=
137 8200
=
NOTE: Dose is per day fish are exposed to Total Dose
=
contaminated water.
.1 (cont'd)
- 1.
Fish Analysis:
Date Sampled Location Multiplying Factor Age Isotope Concentration In (rem/d)
Dose Group (I-Vegetation (pCi/g)
(pCi/g)
(rem/d)
Child 134 4.0
=
(teen) 136 1.0
=
137 2.3
=
Total Dose
=
Adult 134 6.9
=
136 1.1
=
137 4.1 Total Dose
=
DUKE POWER COMPANY EMERGENCY DOSE ASSESSMENT MANUAL June 5, 1991
TABLE OF CONTENTS EDA-1 Procedure for Estimating Food Chain Doses Under Post-Accident Conditions (Rev. 3)
EDA-2 Off-Site Dose Projections for Catawba Nuclear Station (Rev. 5)
EDA-3 Off-Site Dose Projections for McGuire Nuclear Station (Rev. 7)
EDA-4 Off-Site Dose Projections for Oconee Nuclear Station (Rev. 5)
EDA-5 Mesorem, Jr. Atmospheric Dispersion and Dose Assessment Model Users Manual, Version 4A Catawba (Rev. 0)
EDA-6 Mesorem, Jr. Atmospheric Dispersion and Dose Assessment Model Users Manual, Version 4A McGuire (Rev. 0)
EDA--7 Mesorem, Jr. Atmospheric Dispersion and Dose Assessment Model Users Manual, Version 4A Oconee (Rev. 0)
EDA-8 Environmental Monitoring for Emergency Conditions for Catawba Nuclear Station (Rev. 6)
EDA-9 Environmental Monitoring for Emergency Conditions for McGuire Nuclear Station (Rev. 8)
EDA-10 Environmental Monitoring for Emergency Conditions for Oconee Nuclear Station (Rev. 1)
June 5, 1991
CRISIS MANAGEMENT PLAN IMPLEMENTING PROCEDURE EDA -
3 "Off-Site Dose Projections for McGuire Nuclear Station" Approved By Date Rev. 7 August 9, 1990
EDA-3 OFF-SITE DOSE PROJECTIONS FOR MCGUIRE NUCLEAR STATION 1.0 Purpose 1.1 To describe a method for projecting dose commitment from a noble gas and/or iodine release, through the containment, the unit vent and/or the steam relief valves, during an emergency. Where appropriate, the Dose Assessment Coordinator, or designee, may deviate from this procedure due to varying plant conditions.
2.0 References 2.1 HP/O/B/1003/08, Determination of Radiation Monitor Setpoints (EMF's).
2.2 HP/0/B/1009/02, Alternative Method for Determining Dose Rate Within the Reactor Building.
2.3 HP/0/B/1009/10, Releases of Liquid Radioactive Material Exceeding Technical Specifications.
2.4 HP/1/B/1009/15 and HP/2/B/1009/15, Post-Accident Containment Air Sampling System Operating Procedures.
2.5 HP/0/B/1009/06, Procedure for Quantifying High Level Radioactivity Releases During Accident Conditions.
2.6 McGuire Nuclear Station Technical Specifications 3.6.1.2.
2.7 Offsite Dose Calucation Manual (ODCM).
2.8 Regulatory Guide 1.4, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors".
2.9 Regulatory Guide 1.109, "Calculations of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I".
2.10 NuReg-0396, EPA 520/1-78-016, "Planning Basis for the Development of State and Local Government Radiological Emergency Response Plans in Support of Light Water Nuclear Power Plants".
2.11 NuReg-0654, FEMA-REP-1,Rev.1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants".
-2 2.12 Letter from F.G. Hudson; September 30, 1985, re: Release Rate Information from McGuire and Catawba Nuclear Station.
2.13 McGuire Nuclear Station Class A Computer Model Validation.
3.0 Limits and Precautions 3.1 This procedure is an alternative method of dose assessment to the Class A Atmospheric Dispersion Model computer code.
3.2 This procedure applies to releases made from McGuire Nuclear Station only. Many of the values contained in this procedure are site specific.
3.3 It is assumed that the whole body dose from an iodine release is very small compared to the thyroid dose; therefore, iodine whole body dose is not considered here.
3.4 This procedure considers all releases to be ground level releases and that all meteorological data are 15 minute averages.
3.5 Once a zone has been added to the list of affected zones, it shall not be removed except under the direction of the Dose Assessment Coordinator.
3.6 Once the Crisis Management Center (CMC) has been activated, the doses calculated by the Technical Support Center (TSC) dose assessment group, shall be compared with those calculated by the CMC before an evacuation recommendation is made.
3.7 EMF's 38, 39, and 40 will isolate on a phase A containment isolation (1 psig in containment).
Therefore, EMT's 38L, 38H, 39L, 39H, 40 and 48 should not be considered valid when containment pressure is > 1 psig.
3.8 The sample pump to EMF's 35, 36, and 37 will trip when there is a Trip 1 on EMF 36 HH. Therefore, EMF's 35L, 35H, 36L, 36H, and 37 should not be considered valid when EMF 36 HH is > Trip 1 (usually set at 5-7 R/Hr).
4.0 Procedure NOTE:
Much of the information for the meteorology assessment can be obtained on the OAC, (Tech. Spec. 04 program).
See Enclosure 5.14 for instructions.
-3 4.1 Meteorology Assessment 4.1.1 Acquire the following information and record on the Dose Assessment Report and Meteorology Worksheet (Enclosures 5.1 and 5.2 respectively).
4.1.1.1 Lower tower wind speed (WS) in miles per hour.
4.1.1.1.1 Use upper tower wind speed if lower tower wind speed is not available.
4.1.1.2 Upper tower wind direction in degrees from North (North = 0).
4.1.1.2.1 Use lower tower wind direction if upper tower wind direction is not available.
4.1.1.2.2 If the wind speed or wind direction can not be obtained from plant systems, obtain them from the National Weather Service (phone 399-6000).
If the NWS information is unavailable, then obtain data from the CNS Control Room (8-831-2338).
4.1.1.3 Temperature gradient (AT) in degrees centigrade.
4.1.1.4 Using Enclosure 5.3, determine the stability class based on AT.
If AT is unknown, then the following applies:
4.1.1.4.1 If between 1000 -
1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, use stability class D; 4.1.1.4.2 If between 1600 -
1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />, use stability class G.
4.1.1.5 If necessary, use forecasted meteorological data for calculating doses due to changing meteorological conditions.
4.1.2 Determine the atmospheric dispersion parameters, X/Q (sec/m 3 ), for.5, 2, 5 and 10 miles (record on Enclosure 5.1).
-4 4.1.2.1 Using AT, determine the two hour relative concentration value (CH) from Enclosure 5.3.
4.1.2.2 Convert the CH values to X/Q:
H X/Q
=
C H WS 4.1.3 Using Enclosure 5.4, circle on Enclosure 5.1 the protective action zones (PAZ), based upon wind speed and wind direction.
4.1.4 Recheck meteorological conditions approximately every 15 minutes to ensure that other zones have not been affected.
4.2 Source Term Assessment -
Steam Relief Valves (Enclosure 5.5)
NOTE:
Much of the information for Steam Relief Valve source term assessment can be obtained from the OAC (General 19 program).
See Enclosure 5.14 for instructions.
4.2.1 Determine the Sub-Noble Gas Release Rates, SQNG (Ci/sec),
by the following method:
4.2.1.1 For Unit 1 -
EMF24, EMF25, EMF26 and EMF27 For Unit 2 -
EMFlO, EMF11, EMF12, and EMF13 SQ
=
mR/hr x 1
x LBM x CF VOPEN where:
mR/hr =
EMF reading Unit 1 = EMF's 24, 25, 26, 27 Unit 2 = EMF's 10, 11, 12, 13 VOPEN =
time the valve is open in seconds LBM =
lbm released for the time the valve was open CF =
the correction factor per Enclosure 5.6 Units
=
Ci lbm mR/hr 4.2.2 Determine the Noble Gas Release Rate, ONG (Ci/sec):
-5 Q NG SQ NG1EMF24 or 2EMF1O)
+I SQ (1EMF25 or 2EMF11)
+
SQ (1EMF26 or 2EMF12)
+
SQNG (1EMF27 or 2EMF13) 4.2.3 Determine the Iodine release rate, Q (Ci/sec):
Q
=
QNG x I/Xe ratio where:
I/Xe ratio
=
ratio of 1-131 eqv./Xe-133 eqv. from.7 4.2.4 Record QNG and Q from the steam relief valves on.1.
4.3 Source Term Assessment -
Containment (Enclosure 5.8)
NOTE:
Some of the information for Containment source term assessment can be obtained from the OAC (Tech Spec 04 program).
See Enclosure 5.14 for instructions.
4.3.1 Determine the Noble Gas Release Rate, QNG (Ci/sec) based on one of the following methods:
NOTE:
See Limit and Precaution 3.7.
4.3.1.1 Based on an EMF reading, where; QNG
=
EMF 39(L), if EMF39(L) < 1E7 cpm, EMF 39(H), if EMF39(L) is offscale and EMF39(H) > 100 cpm, EMF
=
51A or 51B; if EMF39(H) is offscale
-6 CF =
the correction factor per Enclosure 5.9 LR =
Leak Rate, (ml/hr) by one of the following methods:
based on containment pressure:
LR =
RLR (from Enclosure 5.10) based on an opening in containment:
LR =
OIC (from Enclosure 5.11) based on design leak rate:
LR
=
1.714E5 (reference 2.13) assuming bypass leakage of 0.07.
4.3.1.2 Based on PAGS sample or sample collected in accordance with reference 2.5, where; QNG =
Conc.
x CF x LR where:
Conc
=
the Xe-133 equivalent concentration (pCi/ml) from Reference 2.4 or 2.5 CF =
2.78E-10 Ci hr sec pCi LR
=
leak rate, as determined in step 4.3.1.1 above 4.3.2 Determine the Iodine Release Rate Q (Ci/sec), based on one of the following methods:
4.3.2.1 Based on QNG; Q
=
QNG x I/Xe ratio where:
Q NG=
noble gas release rate as
-7 determined in Step 4.3.1 above I/Xe ratio
=
ratio of 1-131 eqv./Xe-133 eqv.
from Enclosure 5.7.
4.3.2.2 Based on EMF40:
Q
=
ACPM x 6.54E-20 Ci hr min x LR Amin sec ml cpm where:
ACPM
=
reading from EMF40 Amin
=
the time interval for EMF40 observation (normally 15 minutes)
LR
=
leak rate as determined in step 4.3.1.1 above 6.54E-20 =
(4.OE-5 pCi/cpm x
.1667 min/ft3 x 3.53E-5 ft3 /ml x
ICi/1E6 pCi x
1 hr/3600 sec) 4.OE-5
=
correlation factor for EMF40 from Reference 2.1
.1667 min/ft3 =
inverse of EMF flow rate 4.3.2.3 Based on PAGS sample or sample collected in accordance with reference 2.5.
Q
=
Conc x 2.78E-10 Ci hr x LR sec pCi where:
Conc
=
1-131 equivalent concentration (pCi/ml) from Reference 2.4 or reference 2.5 LR
=
leak rate as determined in step 4.3.1.1 above 4.3.3 Record QNG and Q from containment on Enclosure 5.1.
4.4 Source Term Assessment -
Unit Vent (Enclosure 5.12)
-8 NOTE:
Some of the information for Unit Vent source term assessment can be obtained from the OAC (Tech Spec 04 program).
See Enclosure 5.14 for instructions.
4.4.1 Determine the Noble Gas Release Rate, QNG (Ci/sec), based on one of the following methods:
4.4.1.1 Based on an EMF reading, where NOTE:
See Limit and Precaution 3.8.
QNG
=
EMF =
36(L) if EMF36(L) < 1E7 cpm EMF =
36(H) if EMF36(L) is offscale and EMF36(H) is > 100 cpm EMF =
36(HH) if EMF36(H) is offscale CF
=
the correction factor per Enclosure 5.13 CFM
=
unit vent flow rate (ft3 /min) 4.4.1.2 Based on unit vent sample, where; QNG
=
Conc.
Conc
=
the Xe-133 equivalent concentration (pCi/ml) from Reference 2.5 CF
=
4.72E-4 Ci min ml sec ft3 pCi CFM =
Unit vent flow (ft3 /min) 4.4.2 Determine the Iodine Release Rate Q (Ci/sec) based on one of the following methods:
4.4.2.1 Based on QNG Q
=
QNG x
I/Xe ratio
-9 QNG
=
noble gas release rate as determined in step 4.4.1 above I/Xe ratio
=
ratio of 1-131 eqv./Xe-133 eqv.
from Enclosure 5.7 4.4.2.2 Based on EMF37:
Q
=
ACPM x 1.11E-13 Ci min min x CFM Amin sec ft 3 cpm where:
ACPM
=
reading from EMF37 Amin
=
the time interval for EMF37 observation (normally 15 minutes)
=
unit vent flow (ft3 /min) 1.11E-13 =
(4.OE-5 pCi/cpm x
.1667 min/ft3 x
1 Ci/1E6 pCi x 1 min/60 sec) 4.OE-5
=
correlation factor for EMF 37 from Reference 2.1
.1667 ft 3 /min =
inverse of EMF flow rate 4.4.2.3 Based on unit vent sample:
QI
=
Conc x 4.72E-4 Ci min ml x CFM sec ft 3 pCi where:
Conc
=
1-131 equivalent concentration (pCi/ml) from Reference 2.5 CFM =
unit vent flow rate (ft3 /min) 4.4.3 Record QNG and Q from the unit vent on Enclosure 5.1.
4.5 Dose Assessment (Enclosure 5.1) 4.5.1 Determine the total Noble Gas and Iodine Release Rates (TQ and TQ ) by summing QNG and Q from all releases.
NG I
NG I
-10 4.5.2 Determine the Projected Whole Body Dose Rate, DRwb (Rem/hr), due to noble gases for.5, 2, 5 and 10 miles:
DRwb
=
X/Q x TQNG x 33.6 Rem m3 hr Ci where:
33.6 is the adult whole body dose conversion factor from Reference 2.9 in Rem m 3 hr Ci 4.5.3 Determine the Projected Whole Body Dose, Dwb (rem), due to noble gases for.5, 2, 5 and 10 miles:
Dwb
=
DRwb x
2 hr where:
dose is integrated over 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time period 4.5.4 Determine the Projected Child Thyroid Dose Rate, DRct (Rem/hr), due to iodine for.5, 2, 5 and 10 miles:
DRct =
X/Q x TQI x 2.26E6 Rem m3 hr Ci where:
2.26E6 is the child thyroid dose conversion factor from Reference 2.13 in Rem m3 hr Ci 4.5.5 Determine the Projected Child Thyroid Dose, Dct(Rem), due to iodine for.5, 2, 5 and 10 miles:
Dct =
DRct x
2 hr where:
dose is integrated over 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time period
4.6 Protective Action Recommendations (Enclosure 5.1, page 2 of 2):
4.6.1 Record the next sequential report number.
4.6.2 Determine release status by the following guidance criteria:
No Release -
no potential release of activity generated by the event.
Potential Release -
activity generated by the event that can potentially be released, but is not currently being released.
Release Within Normal Operating Limits -
activity generated by the event currently or previously released within normal operating limits.
Release Above Normal Operating Limits -
activity generated by the event currently or previously released above normal operating limits.
4.6.3 Circle the PAZs and the actions for the current and previous protective action recommendations.
4.6.4 If the projected dose in a PAZ is < 1 Rem whole body and <
5 Rem thyroid, then recommend no protective action (action A).
4.6.5 If the projected dose in a PAZ is 1 -
5 Rem whole body or 5 25 Rem thyroid, then recommend evacuation of children and pregnant women (unless constraints make it impractical) and shelter others (action B and E).
4.6.6 If the projected dose in a PAZ is > 5 Rem whole body or >
25 Rem thyroid, then recommend evacuation of affected zones and shelter all remaining zones (action C).
4.6.7 If the dose rate at the site boundary is > 5.OE-4 Rem/hr whole body, then recommend an Alert.
4.6.8 If the dose rate at the site boundary is >.05 Rem/hr whole body or >.25 Rem/hr thyroid, then recommend a Site Area Emergency if readings last 30 minutes.
-12 4.6.9 If the dose rate at the site boundary is >.5 Rem/hr whole body or > 2.5 Rem/hr thyroid, then recommend a Site Area Emergency if readings last 2 minutes.
4.6.10 If the dose rate at the site boundary is > 1 Rem/hr whole body of > 5 Rem/hr thyroid, then recommend a General Emergency.
5.0 Enclosures 5.1 Dose Assessment Report 5.2 Meteorology Worksheet 5.3 Two-hour Relative Concentration Factors (CH) 5.4 Protective Action Zones Determination 5.5 Source Term Assessment -
Steam Relief Valves 5.6 EMF24, EMF25, EMF26, EMF27 or EMF10, EMF11, EMF12, EMF13 Noble Gas Correction Factors (Steam Line Monitors) 5.7 1-131 eqv./Xe-133 eqv. Ratio 5.8 Source Term Assessment - Containment 5.9 Containment Monitors -
Correction Factors 5.10 Containment Leakage Rate versus Pressure 5.11 Containment Leakage Rate versus Pressure and Size Opening 5.12 Source Term Assessment - Unit Vent 5.13 Unit Vent Monitors -
Correction Factors 5.14 OAC Instructions
EDA-3.1 McGUIRE NUCLEAR STATION Page 1 of 2 DOSE ASSESSMENT REPORT t
Report #
eactor Trip
/
Projection based on data on
/
(date/time)
(date/time)
Prepared by:
Meteorology Assessment
[ ] Current
[ ] Hypothetical Wind Speed mph Wind Direction degrees from North Temperature Gradient (AT)
C Stability Class A B
C D
E F
G Miles 0 -
2 2 -5 5 -
10 PAZ LB MC NADOR E F G HI J K P Q S Total Source Term Assessment
[ ] Current
[ ] Hypothetical Steam Relief Containment Unit Vent Total (Ci/sec).5.8.12 Ci/sec +
Ci/sec
+
Ci/sec
=
=
TQNG Ci/sec
+
Ci/sec
+
Ci/sec =
=
TQI ose Assessment CH =
X/Q WS Adult whole body <---<
Child thyroid >--->
2 hr 2 hi Dose <--< 2 x DRwb <--< 33.6 x TQ x X/Q X/Q
--> DRct x 2>--> Dost (rem)
(rem/hr)
(Ci/sec (sec/m)
(Ci/sec)
(rem/hr)
(rer Distance TQNG miles TQI
=
2 x
=
33.6 x
_5 x
2.26E6 =
x 2 =
=_ 2 x
=
33.6 x 2
x 2.26E6 =
x 2
=
=_ 2 x
=
33.6 x 5
x 2.26E6 =
x 2
=
=__ 2 x
_=
33.6 x
___0
_x 2.26E6 =
__x 2= =
_=
2 x
=__ 33.6 x
___1
_x 2.26E6 =
__x 2 =
=_ 2 x
=
33.6 x 4
x 2.26E6 =
x 2
=
=_ 2 x
=
33.6 x 7
x 2.26E6 =
x 2
=
=_ 2 x
=
33.6 x 8
x2.26E6 =
x 2 =
Field Data Adult whole body Child thyroid Location Dose Rate 2hr Dose Location Dose Rate 2hr Dose Rem/hr Rem Rem/hr Rem Emergency
[ Drill
EDA-3.1 McGUIRE NUCLEAR STATION Page 2 of 2 DOSE ASSESSMENT REPORT
- Emergency Coordinator Report #
The emergency condition:
(a) No release -
no potential release of activity generated by the event.
(b) Potential release -
activity generated by the event that can potentially be released, but is not currently being released.
(c) Release (within normal operating limits) -
activity generated by the event currently or previously released within normal operating limits.
Started Stopped In progress (d) Release (above normal operating limits) -
activity generated by the event, currently or previously released above normal operating limits.
Started Stopped In progress The following protective actions are recommended:
Current Previous Miles PAZ Actions Actions 0 -
2 L,B,M,C A B C E A B C E 2 -
5 N,A,D,O,R A B C E A B C E 5 -
10 E,F,G,H,I,J,K,P,Q,S A B C E A B C E A -
Monitor environmental radiation levels. No specific actions.
(Less than 1 Rem Whole Body and less than 5 Rem Thyroid)
B - Remain indoors with windows closed, turn off air conditioners and other ventilation, monitor EBS stations. Control access. (Action E also)
(1-5 Rem Whole Body or 5-25 Rem Thyroid)
C - Evacuate affected zones and seek shelter if immediate evacuation is not possible.
Shelter all remaining zones.
Monitor environmental radiation levels.
Control access.
(Greater than 5 Rem Whole Body or greater than 25 Rem Thyroid)
E -
Pregnant women and children evacuate (unless constraints make it impractical) and go t designated shelter.
(1-5 Rem Whole Body or 5-25 Rem Thyroid) based on field data Emergency Classification based on Radiological Data Recommend Alert (Dose rate at 0.5 miles is >.5 mR/hr Whole Body)
[
Potential Site Area Emergency if readings last 30 minutes Recommend Site Area Emergency Now, readings have lasted 30 minutes (Dose rate at 0.5 miles is >.05 Rem/hr Whole Body or >.25 Rem/hr Thyroid)
[
Recommend Site Area Emergency if readings last 2 minutes (Dose rate at 0.5 miles is >.5 Rem/hr Whole Body or > 2.5 Rem/hr Thyroid)
[
Recommend General Emergency (Dose rate at 0.5 miles is > 1 Rem/hr Whole Body or > 5 Rem/hr Thyroid)
Comments:
Woses concur with CMC?
(Yes/No/NA)
Dose Assessment Coordinator Date/Time
( Emergency Drill
EDA-3.2 McGUIRE NUCLEAR STATION METEOROLOGY Unit:
Report #:
Reactor Trip:
/
Prepared by:
Wind speed (WS) mph Wind direction ON AT oC Default Data Wind speed (WS) mph 1000 to 1600 hrs.
Wind direction ON Stability Class D
oC Wind speed (WS) mph 1600 to 1000 hrs.
Wind direction ON Stability Class G
oC NOTE:
If the wind speed or wind direction cannot be obtained from plant systems, obtain them from the National Weather Service, 399-6000.
If NWS information is unavailable, then obtain data from the Catawba Nuclear Station Control Room, 8-831-2338.
WEncloe
- 5.
McGUIRE NUCLEAR STATION TWO-HOUR RELATIVE CONCENTRATION FACTORS (C H)
Temperature Stability Distance (Miles)
Gradient Class
.5 1
2 3
4 5
6 7
8 9
10
- 1) AT < -.6 A
1.4E-5 1.2E-6 5.9E-7 4.1E-7 3.2E-7 2.5E-7 2.OE-7 1.9E-7 1.8E-7 1.6E-7 1.5E-7
- 2) -.6 5 AT < -.5 C
1.5E-4 4.5E-5 1.3E-5 6.3E-6 3.9E-6 2.7E-6 1.9E-6 1.4E-6 1.1E-6 8.3E-7 7.8E-7
- 3) -.5 5 AT < -.2 D
3.8E-4 1.4E-4 4.9E-5 2.7E-5 1.7E-5 1.2E-5 9.2E-6 7.3E-6 6.OE-6 5.OE-6 4.3E-6
- 4) -.2 5 AT < +.4 E
6.9E-4 2.5E-4 9.6E-5 5.5E-5 3.5E-5 2.5E-5 2.OE-5 1.6E-5 1.3E-5 1.1E-5 9.7E-6
- 5) +.4 5 AT <+1.2 F
1.1E-3 5.1E-4 2.OE-4 1.2E-4 8.2E-5 6.3E-5 5.1E-5 4.3E-5 3.8E-5 3.3E-5 3.OE-5
- 6) +1.2 5 AT G
1.8E-3 1.1E-3 4.3E-4 2.7E-4 2.OE-4 1.7E-4 1.3E-4 1.2E-4 8.6E-5 7.8E-5 7.3E-5 NOTE:
If AT is unavailable use:
1000-1600 hours Use Stability Class D 1600-1000 hours Use STability Class G There is no B Stability Class for McGuire.
EDA-3.4 McGUIRE NUCLEAR STATION PROTECTIVE ACTION ZONES DETERMINATION Determine the affected zones (based on wind direction) from the table below and record on Enclosure 5.1.
NOTE:
If wind speed is less than or equal to 5 mph -
the affected zones for 0 -
5 miles shall be L,B,M,C,N,A,D,O,R Wind Direction 0 -
5 Miles 5 -
10 Miles Degrees from North) 0 -
22.5 L,B,M,CD,O,R E,S,F 22.6 -
45.0 L,BM,C,D,O,R E,Q,S 45.1 -
67.5 L,B,M,C,DO,R E,Q,S 67.6 -
90.0 L,B,MC,D,O,R,N P,Q,S 90.1 - 112.5 L,B,M,C,O,R,N KPQS 112.6 - 135.0 L,B,M,C,O,NR,A I,K,P,Q,S 135.1 -
157.5 LBM,C,O,A,N I,K,P,Q 157.6 -
180.0 L,B,M,C,A,N I,J,K,P 180.1 -
202.5 L,B,M,C,A,N G,H,I,J,KP 202.6 -
225.0 L,B,M,C,A,N,D G,H,I,J,K,P 225.1 -
247.5 L,B,M,C,A,D F,G,H,I,J 247.6 -
270.0 L,B,M,C,A,D F,G,H,I,J 270.1 -
292.5 L,B,M,C,A,D E,F,G,H,J 292.6 -
315.0 L,B,M,C,A,D E,F,G 315.1 -
337.5 L,B,M,C,D,R E,F,G 337.6 -
359.9 LBMCDR EFS
EDA-3 McGUIRE NUCLEAR STATION.5 SOURCE TERM ASSESSMENT -
STEAM RELIEF VALVES (BLUE)
Report #
Weactor Trip
/
Projection based on data on
/
(date/time)
(date/time)
Calculations based on Melted Core LOCA NOBLE GAS based on EMF24 or EMF10 mR/hr x
1 x
lbm x
Ci*
=
Ci/sec sec lbm mR/hr
+
based on EMF25 or EMF11 mR/hr x
1 x
lbm x
Ci*
=
Ci/sec sec lbm mR/hr
+
based on EMF26 or EMF12 mR/hr x
1 x
lbm x
Ci*
=
Ci/sec sec 1bm mR/hr
+
based on EMF27 or EMF13 mR/hr x
1 x
lbm x
Ci*
=
Ci/sec sec lbm mR/hr Total from all Steam Relief Valves, QNG
=
Ci/sec IODINE From all Steam Relief valves Q I Ci/sec(Q NG) x 1-131 eqv./Xe-133 eqv. ratio =
Ci/sec (Enclosure 5.7)
[
] Emergency
[
]
Drill Prepared by:
EDA-3.6 (BLUE)
McGUIRE NUCLEAR STATION STEAM LINE MONITOR NOBLE GAS CORRECTION FACTOR EMF24, EMF25, EMF26, EMF27 or EMF10, EMF11, EMF12, EMF13 Time Since Trip (hrs)
Correction Factor
>0 6.3820 x 10
> 2 1.1255 x 10-2
> 4 1.2763 x 10-2
> 8 1.4736 x 10-2
> 24 1.6476 x 10-2
> 48 1.6476 x 10-2
> 100 1.6476 x 10-2
> 250 1.6476 x 10-2
> 500 1.6476 x 10-2
> 720 1.6476 x 10-2 units in Ci 1bm mR/hr Enclosure.5.6 is the correlation factor per Reference 2.13 x 2.83E4 ml x.41 ft3 x
Ci ft3 ibm 1E6 pC
.41
=
specific volume of steam per Reference 2.13.
'EDA-3 McGUIRE NUCLEAR STATION.7 1-131 eqv./Xe-133 eqv. Ratio NOTE:
For containment releases in which I/Xe ratio is utilized to determine 1-131 equiv. concentration, apply the appropriate correction from the table below.
Column 1 Column 2 Time Since Trip (hrs)
Ratio based on LOCA Ratio based on Melted Core 0
2.91E-3 2.24E-3
> 2 3.61E-3 9.66E-3
> 4 4.05E-3 1.59E-2
> 8 4.64E-3 2.85E-2 24 5.08E-3 7.52E-2
> 48 5.11E-3 1.11E-1
> 100 5.42E-3 1.33E-1
> 250 7.OOE-3 1.80E-1 500 1.09E-2 2.90E-1
> 720 1.53E-2 4.33E-1
- Enclosure 5.7 is from Reference 2.13.
NOTE:
For vent releases in which I/Xe ratio is utilized to determine 1-131 equiv. concentration, apply the appropriate correction from the table below:
- 1.
LOCA, use column 1 (based on LOCA).
- 2.
LOCA through charcoal filters, divide column 1 value by 100.
- 3.
Core damage, use column 2 (based on Core Melt).
- 4.
Core damage through charcoal filters, divide column 2 values by 100.
- 5.
Tube rupture, use 1.53E-5. (Column 1 value at > 720 hrs. divided by 1000).
- 6.
New fuel accident, use 2.217E-4. (Column 2 value at > 100 hrs.
divided by 600).
- 7.
Old fuel accident, use 7.217E-4. (Column 2 value at > 720 hrs.
divided by 600).
- 8.
Gas decay tank, assume no radioiodine released, only noble gases are considered to be released from gas tank.
NOTE:
For steam releases in which I/Xe ratio is utilized to determine 1-131 equiv.
concentration, apply the appropriate correction from the table below:
- 1.
Design basis primary coolant, divide column 1 value by 100.
- 2.
Iodine spiked primary coolant, use column 1.
- 3.
Core damage, divide column 2 value by 100.
EDA-3.8 (YELLOW)
McGUIRE NUCLEAR STATION SOURCE TERM ASSESSMENT -
CONTAINMENT Report #_
/
Projection based on data on
/
(date/time)
(da Le/L i ne)
Calculations based on Melted Core LOCA Containment pressure psig LR
=
ml/hr LR based on:
Realistic Leak Rate Opening in Containment Design Leak Rate (circle one)
Opening size:
(1.714E5) assuming bypass leakage of 0.07 NOBLE GAS based on (check one)
EMF39(L)
EMF39(H)
EMF51 if < 1E7 cpm
[
] if > 100 cpm
[
] if 39(H) is offscale EMF CF LR QNG epm or x
x ml/hr
=_
Ci R/hr (Encl. 5.9) sec ed on sample pCi/ml x
2.78E-10 Ci hr x
m2/hr
=
Ci sec pCi sec IODINE based on QNG Ci x
1-131 eqv./Xe-133 eqv.
=
Ci sec ratio (Encl. 5.7) sec based on LR EMF40 Acpm x
6.54E-20 Ci hr min x
ml/hr
=
Ci Amin sec ml cpm sec based on PAGS sample pCi/ml x
2.78E-10 Ci hr x
ml/hr
=
Ci sec pCi sec
]
Emergency
[
] Drill Prepared by:
EDA-*
I..9 (YELLOW)
McGUIRE NUCLEAR STATION CONTAINMENT MONITORS NOBLE GAS CORRECTION FACTORS EMF39L EMF39H EMF51 A or B Time Correction Correction Time Correction Correction Time Correction Correction Since Factor Factor based Since Factor Factor based Since Factor Factor based Trip based on on Melted Trip based on on Melted Trip based on on Melted (hrs)
LOCA Core (hrs)
LOCA Core (hrs)
LOCA Core
> 0 6.394E-18 6.672E-17
> 0 5.56E-14 1.429E-13
> 0 3.781E-10 1.190E-9
> 2 6.394E-18 4.448E-17
> 2 5.56E-14 1.003E-13
> 2 3.114E-10 5.894E-10
> 4 6.394E-18 3.058E-17
> 4 5.56E-14 1.232E-13
> 4 2.780E-10 4.726E-10
> 8 6.394E-18 2.113E-17
> 8 5.56E-14 1.195E-13
> 8 2.446E-10 3.392E-10
> 24 6.394E-18 1.112E-17
> 24 5.56E-14 7.339E-14
> 24 2.335E-10 1.890E-10
> 48 6.394E-18 1.056E-17
> 48 5.56E-14 6.060E-14
> 48 2.335E-10 1.668E-10
> 100 6.394E-18 1.390E-17
> 100 5.56E-14 5.699E-14
> 100 2.335E-10 1.612E-10
> 250 6.394E-18 1.446E-17
> 250 5.56E-14 5.588E-14
> 250 2.335E-10 1.557E-10
> 500 6.394E-18 9.730E-18
> 500 5.56E-14 5.560E-14
> 500 2.335E-10 1.251E-10
> 720 6.394E-18 6.394E-18
> 720 5.56E-14 5.560E-14
> 720 2.335E-10 1.056E-10 Units in Ci hr Units in Ci hr Units in Ci hr sec ml cpm sec ml cpm sec ml R/hr
- Enclosure 5.9 is the correlation factor per Reference 2.13 x hr x
Ci 3600 sec 1E6 uCi
EDA-3.10 (YELLOW)
McGUIRE NUCLEAR STATION CONTAINMENT LEAKAGE RATE VERSUS PRESSURE PSIG ml/hr
> 0 1.460E4
> 2 3.175E4
> 4 5.821E4
> 8 9.779E4
> 10 1.114E5
> 11 1.164E5
> 12 1.199E5
> 13 1.235E5
> 14 1.260E5
= 15 1.285E5
> 15 Use design leak rate (1.714E5 m./hr).10 is the realistic leakage rate (m3/sec) per Reference 2.12 x 1E6 ml/m 3 x 3600 sec/hr x 0.07 (0.07 per Reference 2.6).
EDA-3.11 McGUIRE NUCLEAR-STATION (YELLOW)
CONTAINMENT LEAKAGE RATE VERSUS PRESSURE AND SIZE OPENING r 1" diameter opening PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 2.209E8
>5.0 3.908E8
>12.5 5.862E8
>2.50 2.889E8
>7.5 4.588E8
>15.0 6.287E8
>3.75 3.483E8
>10.0 5.268E8 For 2" diameter opening PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 8.496E8
>5.0 1.512E9
>12.5 2.243E9
>2.50 1.121E9
>7.5 1.784E9
>15.0 2.464E9
>3.75 1.342E9
>10.0 2.022E9 For 4" diameter opening PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 3.144E9
>5.0 5.692E9
>12.5 8.496E9
>2.50 4.248E9
>7.5 6.797E9
>15.0 9.176E9
>3.75 5.098E9
>10.0 7.731E9 For 6" diameter opening PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 7.137E9
>5.0 1.291E10
>12.5 1.937E10
>2.50 9.516E9
>7.5 1.529E10
>15.0 2.124E10
>3.75 1.138E10
>10.0 1.716E10 For 8" diameter opening PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 1.257E10
>5.0 2.243E10
>12.5 3.381E10
>2.50 1.648E10
>7.5 2.634E10
>15.0 3.568E10
>3.75 1.971E10
>10.0 3.042E10 r 12" diameter opening PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 2.719E10
>5.0 5.012E10
>12.5 7.476E10
>2.50 3.738E10
>7.5 5.947E10
>15.0 8.156E10
>3.75 4.452E10
>10.0 6.712E10 For 18" diameter opening PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 5.522E10
>5.0 1.003E11
>12.5 1.529E11
>2.50 7.476E10
>7.5 1.189E11
>15.0 1.665E11
>3.75 8.836E10
>10.0 1.351E11 For 34" diameter opening PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 1.869E11
>5.0 3.398E11
>12.5 5.132E11
>2.50 2.583E1I
>7.5 4.078E11
>15.0 5.607E11
>3.75 3.093E11
>10.0 4.588E11 For Personnel Hatch Opening PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 2.379E12
>5.0 4.690E12
>12.5 6.967E12
>2.50 3.398E12
>7.5 5.573E12
>15.0 7.646E12
>3.75 4.111E12
>10.0 6.372E12 For Equipment Hatch Opening PSIG ml/hr PSIG ml/hr PSIG ml/hr
>1.25 1.121E13
>5.0 2.022E13
>12.5 3.059E13
>2.50 1.478E13
>7.5 2.379E13
>15.0 3.398E13
>3.75 1.767E13
>10.0 2.719E13
- Enclosure 5.11 is the containment leakage for an opening size in standard cubic feet per min (scfm) x 2.83E4 ml/ft3 x 60 min/hr.
EDA-3.12 (GREEN)
McGUIRE NUCLEAR STATION SOURCE TERM ASSESSMENT
- UNIT VENT Repor#_
/
Projection based on data on (date/time)
(date/time Calculations based on Melted Core LOCA CFM
=
ft 3 /min NOBLE GAS based on (check one)
EMF36(L)
EMF36(H)
EMF36(HH)
[ if
< 1E7 cpm
[ ] if > 100 cpm
[ ] if 36(H) is offscale EMF CF CFM QNG cpm or x
x ft 3
Ci R/hr (Encl. 5.13) min sec based on Unit Vent Sample pCi/ml x
4.72E-4 Ci min ml x
ft 3 Ci sec ft pCi min sec 1ODINE based on Q
QNG Ci x
1-131 eqv./Xe-133 eqv.
=
Ci sec ratio (Encl. 5.7) sec based on CFM EMF37 Acpm x
1.11E-13 Ci min min x ft 3
=
Ci Amin sec ft3 cpm min sec based on Unit Vent Sample pCi/ml x
4.72E-4 Ci min ml x
ft 3
=
Ci sec ft3 pCi min sec O
[l Emergency
[ 1 Drill Prepared by:
EDA-3.13 (GREEN)
McGUIRE NUCLEAR STATION UNIT VENT MONITORS NOBLE GAS CORRECTION FACTORS Correction Factors for Melted Core Correction Factors for All Other Accidents Accidents with or without charcoal.
Time EMF36L based EMF36H based EMF 36HH based EMF 36L EMF 36H EMF 36HH Since on Melted Core on Melted Core on Melted Core Accident
(
Ci min (Ci mm
\\
Ci min Trip (
Ci min -
(
Ci min Ci min
\\sec ft3 cpm) \\sec ft3 cpmJ \\sec ft3 R/hr)
(hrs) sec ft3 cpm/
sec ft3 cpm/
\\sec ft3 R/hr New Fuel 2.360E-11 9.676E-8 2.358E-4 0
1.133E-10 2.426E-7 1.887E-3
> 2 7.552E-11 1.704E-7 1.179E-3 All Other Accdens~ 1.086E-11 9.440E-8 2.358E-4 Accidents*
4 5.192E-11 2.091E-7 9.905E-4
> 8 3.587E-11 2.030E-7 6.367E-4
- Accidents include LOCA with or without charcoal, Tube
> 24 1.888E-11 1.246E-7 2.931E-4 Rupture, WGDT, and Old Fuel.
48 1.794E-11 1.029E-7 2.405E-4
> 100 2.360E-11 9.676E-8 2.358E-4
> 250 2.454E-11 9.481E-8 2.358E-4
> 500 1.652E-11 9.440E-8 2.358E-4
> 720 1.086E-11 9.440E-8 2.358E-4
- Enclosure 5.13 is the correlation factor per Reference 2.13 x 2.83E4 ml x min x Ci ftK 60 sec 1E6 pCi
EDA-3.14 INSTRUCTIONS ON HOW TO OBTAIN DATA FROM THE OPERATOR AID COMPUTER OAC
- 1)
Tech Spec 04 Program (Plant Data and Status Summary) a)
At the OAC in the TSC or Computer Room, press [Tech Spec] 04 b)
Then press [Print] and [Enter]
c)
The report will print out
- 2)
General 19 Program (Main Steam Release Program) a)
At the OAC in the TSC or Computer Room, press [General] 19 b)
Then press [Print] and [Enter]
c)
Using the arrow pointer keys, highlight "Main Steam Release" and press enter d)
The report will print out