ML20073L180
| ML20073L180 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 09/16/1994 |
| From: | UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20073L159 | List: |
| References | |
| EPCI-94-04, EPCI-94-04-R00, EPCI-94-4, EPCI-94-4-R, NUDOCS 9410120356 | |
| Download: ML20073L180 (62) | |
Text
_ . _ . . _ _ _ . . ._ ~_ _ . -
94 04 Rev. o
. VION cutx*^r >'xur EMERGENCY PREPAREDNESS ErcI - -
lg{ DEPARTMENT CALCULATION COVER SHEET Callaway Plant
SUBJECT:
Protective Ac' tion Recommendations Based on Plant Conditions.
PURPOSE AND SCOPE:
Using plant conditions as a bases, this bases document was written to evaluate the radiological
- consequences to members of the general public within the EPZ following a variety of severe accidents. It provides plant staff with a method of recommending Protective Actions based on plant conditions.
RESULTS:
Attachment 1 contains the front end (no protective actions included) of an event status tree 3 based on the assumptions and data used in this analysis. It starts with event trees for containment releases with varying degrees of core damage. Steam Generator Tube Ruptures i and Containment Bypass events are similarly analyzed. ~
The data from the event status trees was then entered into version 2 of the NRC's RASCAL computer program. The results are tabulated in Appendix A-FF of Attachment 1. The results were analyzed to determine the appropriate protective actions that would be recommended based on the plant conditions. These results were substituted into the status tree. The resulting tree is documented in Attachment 2. Since many of the protective action recommendations were the same for differing degrees of the same event, an attempt was made to consolidate events where, regardless of the conditions, the protective actions would be the same. A generic consolidated status tree is documented in Attachment 3.
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DEPARTMENT Prepared by: bf hh CALCULATION (continuation sheet)
InitialfDate 88]
Callawa Plant EPCI- 94 - 04 Reviewed by: Y f 'Y Initial /Date Page 2 of 62 RESULTS (cont' d) :
The final results of this analysis are documented as a consolidated site specific status tree in Attachment 4. Up to this point in the analysis, generic terms for various plant conditions were being used in the event status trees. These terms were replaced with Callaway Plant specific values and set points identified in the body of this analysis. .
The final decision tree incorporates a precautionary protective action of sheltering 5 miles down wind and in a 2 mile radius when plant conditions do not warrant a protective action recommendation based on potential dose consequences. This precautionary measure is based on the General Emergency declaration and provides a means for the public to go indoors and monitor EBS broadcasts.c It was also moved to the beginning of the status tree to allow Control Room staff more time to evaluate plant conditions.
Additionally, the decision tree allows protective actions to be upgraded by Dose Assessment personnelif a dose calculation has been performed and the doses to the general public are projected to exceed the EPA protective action guides.
The decision tree also allows upgrading protective action recommendations based on security events that include a loss of shutdown capability.
ASSUMPTIONS:
- 1. No credit is taken for decay of radionuclides that are held-up in the containment building or other structures prior to their release. This is a conservative assumption.
- 2. Protective Action Recommendations based on Plant Conditions will be made for the 2 mile,
, 5 mile, and 10 mile down wind distances. No plume exposure protective actions will be necessary beyond 10 miles.
- 3. Steam generator tubes are assumed to be partition predicated on the efficiency of the Steam Generator Moisture Separators in removing iodines from the steam phase of a steam generator tube rupture release.
- 4. Average meteorological conditions are assumed to exist during the release. This is consistent with NRC guidance (ref.1).
- 5. A one (1) hour release duration was assumed. This is consistent with NRC guidance (ref.1).
- 6. All releases are assumed to be ground level releases since all possible release points are effectively lower than two and one-half times the height of adjacent solid structures.
- 7. Building wake effect was used in the RASCAL program.
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REFERENCES:
- 1. " Source Term Estimation During Incidents Response to Severe N,uclear Power Plant Accidents", USNRC Nureg-1228, October 1988.
- 2. "RTM-93, Response Technical Manual", USNRC Nureg/BR-0150, Vol.1, Rev. 3, November 1993.
- 3. " RASCAL Version 2.0 User's Guide", USNRC Nureg/CR-5247 PNL-8454, Vol.1, Rev.1, February 1993. f
- 4. " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants", USNRC Nureg-0654, FEMA-REP-1, Rev.1, November 1980.
- 5. "The MESORAD Dose Assessment Model", USNRC Nureg/CR-4000, Vol.1, March 19&;.
- 6. "MESOI Version 2.0: An interactive Mesoscale Lagrangian Puff Dispersion Model with Deposition and Decay", USNRC Nureg/CR-3344,1993.
- 7. " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents",
EPA-400-R-92-001, October 1991.
- 8. " Classification of Emergencies", EIP-ZZ-00101, Rev.17, June 1994.
- 9. " Protective Action Recommendations", EIP-ZZ-00212, Rev.12, April 1994.
- 10. " Criteria for Protective Action Recommendations for General Emergencies", USNRC IE Information Notice No. 83-28, May 1983.
- 11. "PWR Dry Containment Issue Characterization", USNRC Nureg/CR-5567, August 1990.
- 12. "Radionuclide Release Under Specific LWR Accident Conditions, Volume VI PWR-Large, Dn/ Containment Design (Zion Plant)", USNRC BMI-2104, Volume VI, July 1984.
- 13. "Best Estimate SGTR lodine and Noble Gas Releases thru the Steam Generator PORV",
Union Electric Calculation ZZ-342, Rev. O, June 1994.
- 14. "Callaway Plant Final Safety Analysis Report - Site Addendum", Rev. OL-0, June 1986.
- 15. "Callaway Plant Final Safety Analysis Report", Rev. OL-2, June 1988.
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Callawa Plant EPCI- 94 - 04 Reviewed by:
f/[f 4 Rev. O Page 4 of 62 ATTACHMENTS:
Attachment ia-e Front-End Status Tree Attachment 1-Appendix A-FF RASCAL Tabular Outputs Attachment 2a-e Status Tree With Protective Actions Attachment 3a-d Consolidated Generic Status Tree Attachment 4a-d Consolidated Site Specific Status Tree r
ANALYSIS:
I. G3neral This bases document provides a method for making protective action recommendations s based on Plant Conditions. During the early phase of an accident, plant parameters can be monitored to determine the extent of core damage and the likeliness oflosing fission product barriers. By identifying these parameters and using consequent analysis, pre-planning can be performed so that emergency personnel can use these parameters to make the appropriate protective action recommendations. This can be done, quite possibly before a release has occurred, and without the need for lengthy dose assessment calculations.
The current method of making protective action recommendations using plant conditions is very limited and is based on Nureg 0654 EAL Methodology (ref. 4). A more recent document (ref.1) has been written which allows a more detailed analysis of the radiological consequences of a severe accident. Using this document and plant specific parameters that can be monitored during a severe accident, protective action recommendations can be developed based on these consequences.
Protective action recommendations based on plant parameters have many advantages.
Plant parameters can be easily monitored from the Control Room by shift personnel. Also, since dose calculations and radiological consequences to the general public from a variety of accident cases can be evaluated during the planning stages, a shift dose assessment person, computer, program and procedures for performing complex dose calculations can be eliminated. Additionally, because of the ability to immediately monitor plant conditions and make protective actions based on them, protective actions can be implemented often O times before a release is underway. Where an evacuation is recommended, this would
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Callawa Plant Rev. O Page 5 of 62 allow county and State emergency workers time to evacuate the general public before plume arrival. This could result in a reduction of dose to the public and possibly eliminate evacuating them through the plume. This is significant since an evacuation can take up to four (4) hours to implement. .It is prudent, therefore, to evacuate the general public, should the conditions warrant, before a release is undenuay. Waiting until a release is underway, then evaluating the radiological consequences based on effluent monitors, and then evacuating the general public through a radioactive plume is unwise from a dose savings standpoint and is not. recommended by federal guidance (ref. 3).
II. Bases So.grce Docurfents A. Nureg 1228 Various documents were used for this analysis. Much of the philosophy was derived g
,g from Nureg-1228 (ref.1). In fact, Nureg-1228 was used as a template for developing the event trees in this document, with only slight modifications. Nureg-1228 uses a combination of core conditions, containment conditions, holdup times, and leak rates to determine the release source term. It also takes into consideration reduction mechanisms such as filtration, partitioning, and containment sprays. These parameters were all evaluated and used as appropriate. The dominant release pathways from Nureg-1228 were also adopted and used in this evaluation. Nureg-1228 uses the MESORAD computer code (ref. 5) as a transport model for projecting doses at various downwind locations. Since only doses at 1 mile are calculated in Nureg-1228, and the units are in Rem Whole Body rather than Total Effective Dose Equivalent, a decision was made to not use the dose results from Nureg-1228.
B. BAECAL A decision was made to use version 2 of the NRC RASCAL Model(ref. 3) for actual data report generation. RASCAL incorporates source term estimations from plant conditions using Nureg-1228 methodology and uses transport subroutines derived from MESORAD and MESOI (ref. 6). It also incorporates dose conversion factors similar to those used in EPA-400-R-92-001 (ref. 7) and uses effective dose terminology consistent with the new EPA-400 protective action guide levels. Although RASCAL uses a reactor power level of 3411 Mw thermal for the Callaway Plant in determining source terms, the 7% difference in Callaway's actual rated power level of 3454 Mw
/ thermal is not significant enough to change the PARS.
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Callawa Plant Initia'l/D' ate Rev. O Page 6 of 62 C. NUMARC EALs Nureg-1228 provides generic guidance for using plant condition parameters which are not site specific. An attempt was made to interpret data from the guidance and make it Callaway specific based on parameters that are monitored by our plant computer system. During this effort, the NUMARC based EALs (ref. 8) provided a source of data for plant conditions. Their respective setpoint limits or numeric values could be easily applied and monitored by CR shift personnel. With the exception of core conditions, which determine the initial source term, the majority of the plant parameters affecting the fission produgt barriers are documented in the NUMARC EALs. A decision was made to adopt the EAL values for this document, where appropriate, since shift personnel are familiar with them and are trained in their use. Additionally, the values used in the EALs are well documented and have been reviewed and approved by the NRC. Also, the shift crew would normally be evaluating them during an emergency.
D. NUREG 0654 '
The current guidance for protective action recommendations used in EIP-ZZ-00212 (ref. 9) is based on EALs in Nureg-0654 (ref. 4) and IE Information Notice No. 83-28 (ref.10). These documents establish protective actions for downwind locations at a distance of either 2 miles,5 miles, or 10 miles. Additionally, when a downwind distance is provided, a radius distance less than the downwind distance is also provided. This radius protective action is conservative and takes into consideration the dose consequences to the public should a wind direction change occur. This concept and relationship is prudent and is adopted in this analysis.
Ill. Core Conditions Four core conditions are discussed in Nureg-1228. These include:
- 1. Normal fuel pin leakage (normal operating temperature 600 F)
- 2. Fuel cladding rupture release (gap release) (1300 - 2100 F)
- 3. Grain boundary release (>3000 F)
- 4. Melt (in vessel) release (>4500 F)
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Rev. O P' age 7 of 62 RASCAL uses the following core conditions:
- 1. Normal RCS activity
- 2. Reactor coolant 100X normal
- 3. Gap release
- 4. In-vessel severe core damage
- 5. Vessel melt through r
Although Nureg-1228 describes the five core conditions used by RASCAL, the status trees in Nureg-1228 are based on: Fuel Cladding Rupture Release (gap release), Grain Boundary Release, and Melt (in vessel) Release. Nureg-1228 further states that it would be difficult to specifically identify the Grain Boundary Release from the Melt (in vessel) release.
For this reason, it was decided to use the RASCAL core condition of In-Vessel severe core damage (Nureg-1228 in-Vessel Melt Release), and the remaining terminology and core conditions used by RASCAL.
A. Vessel Melt Throuah Vessel melt through is referred to in Nureg-1228 as Reactor Vessel Melt-through (ex-vessel meltings), where the core eventually melts through the bottom of the reactor vessel and onto the containment floor. Since this occurs well beyond the temperature range of the core exit thermocouples, temperature is not used as an indicator for this type of accident. For a large dry containment (Zion), average core temperature is approximately 3984 F. Peak core temperature is greater than 5152 F (Table 6.3, ref.12). At this high temperature, containment hydrogen levels of greater than 6%
(Figure B-10, ref. 2) would be observed. Additionally, containment high range area radiation monitor (CHARM) readings above 1,000,000 R/hr (400,000 R/hr Containment Sprays On) would be observed (Table B-7, ref. 2).
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J callaway Plant PC 94 - 04 Reviewed by: 9 Y jg g g Rev. 0 Page 8 of 62 B. Severe Core Damage Fuel melt and severe core damage starts when the peak core temperature reaches 4130*F (Table 6.1, ref.12), and average ( re temperature is between 1978 F and 2335 F (Table 6.3, ref.12). A value of 200 F will be used in this analysis. This is conservative and within the range of Callaway Plant's core exit thermocouples (0-2300 F ) (Table 7A-3, ref.14). At this temperature, containment hydrogen levels of greater than 2% (Figure B-10, ref. 2) would be observed. Additionally, CHARM monitor readings above 30,000 R/hr (10,000 R/hr Containment Sprays On), would be observed (Table B-7, ref. 2).
C. Gap Release Gap release is referred to in Nureg-1228 as fuel cladding rupture / gap release. This occurs when the temperature of fuel cladding reaches a temperature >1300 F (Fig. B-1, ref. 2) and results in the failure of the fuel cladding barrier. As a result, fission proeucts are released from the gap area into the reactor coolant system. Because this temperature is within the range of the core exit thermocouples, they will be used as an indicator of this event. Since this temperature could occur if the core becomes uncovered for longer than 15 minutes (Figure B-2, ref. 2) RVLIS readings will be used as an indicator of this core condition. Core uncovery <40%, and core exit thermocouple readings >1200 F are already evaluated in Emergency Operating Procedures CSF-1, Critical Safety Function Status tree, and FR-C.1, Response to inadequate Core Cooling. Since inadequate core cooling is specified in CSF-1 and FR-C.1, and the values identified are site specific, entry into FR-C.1 will be used as an indicator meeting this condition. Additionally, Containment High Range Area Radiation Monitor readings above 300 R/hr (100 R/hr Containment Sprays On), would be observed (Table B-7, ref.2).
D. Normal and 100X NormaLectivities Nureg-1228 analyzes a steam generator tube rupture event for a release of normal and 100X spike coolant (Figure 5.4A, ref.1). The results indicate that protective actions would not be warranted for members of the general public at any distance down wind from the plant. Additionally, RASCAL was used to project doses based on normal RCS activity and 100X RCS activity. The results indicate that no protective actions are necessary for accidents with these levels of activity. See Attachment 2-D.
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0 Initial /Dato Page 9 of 62 IV. Release Pathways Three release paths are used by RASCAL. Depending on the path selected, appropriate release rates and reduction mechanisms can be selected. The three general pathways are:-
- 1. Containment Failure
- 2. Containment Bypass
- 3. Steam Generator Tube Rupture A. . Containment Faifum For the containment failure, the release path is assumed to be from the Reactor Coolant System into the containment atmosphere and then directly to the environment through a leak greater than 1 ft2, B. Containment Byoass Containment Bypass events are reactor coolant system leaks into a low pressure system located outside of containment. These systems are normally separated from RCS by check valves or isolation valves. The release pathway would bypass the containment atmosphere and release reactor coolant system activity directly into other buildings or the auxiliary building.
C. SHIB For steam generator tube ruptures, the release path from the reactor coolant system is through the ruptured tubes and into the secondary system. Depending on the status of the secondary system, numerous release paths would be available. If the MSIV is closed, the release could be through the monitored PORV or the unmonitored safety relief valves. If the MSIV is open or closed, the release could be through the turbine driven auxiliary feed pump which is a monitored discharge path. If the condenser is available, the release could be through the condenser air removal system which is filtered and monitored by radiation monitoring instruments.
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V. Release Rate A. Containment For the containment failure release path, three general flowrates are used in the RASCAL and Nureg-1228 analysis to transport containment activity into the environment.
- 1. Containment Design Leakage (0.1%/ day)
- 2. Containment isolation Failure (100%/ day)
- 3. Catastrophicf Containment Failure (100%/hr)
Design leakage for the Callaway Plant is 0.2%/ day for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Table 15.6-6, ref.15). RASCAL uses 0.1%/ day. All dose results generated from RASCAL for this a
O y
leakage were doubled to account for this difference.
Nureg-1228 identifies containment isolation failure as a failure to isolate one or more penetrations and failures involving the signal that actuates containment isolation. The bases for the 100%/ day leakage is the corresponding failure of a 40-inch diameter containment purge isolation valve or ventilation system isolation valve disk to body leak.
Nurey-1228 identifies catastrophic containment failure as catastrophic fai!ure of the
- containment to a hole greater than one (1) square foot. This failure mode would result
> in a significant drop in containment pressure, and result in the release of a large fraction of the frission products in the containment atmosphere in a short time period.
B. Containment Bypass Containment bypass flow rates are based on a loss of containment isolation signal
- (CISA or CISB) or failure of containment isolation valves or check valve and a simultaneous LOCA affecting a low pressure system (interfacing LOCA). Indications for this event would be containment pressure or sump level nat increasing with a LOCA.
Flowrates would be dependent on the location of the leak, size of the leak, and pressure of the RCS system. RASCAL attempts to quantify this flowrate using containment design flowrates, containment purge isolation status and catastrophic containment failure indications. These are appropriate for a containment release event,
- but not for a bypass event. To be conservative, all containment bypass events in this ,
analysis are analyzed using the 100%/ hour or 100%/ day flowrate.
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I Page 11 of 62 C. Steam Generator Tube Ruplure For SGTR release rates, Nureg-1228 uses the following plant status parameters to calculate release rates:
- 1. One (1) tube at full pressure
- 2. One (1) CCP pump at low pressure Nureg-1228 Table 4.10 (ref.1) calculates doses for one (1) steam generator tube at full pressure, and doses for one (1) tube at low pressure using a single charging pump flow.
The release rategor one (1) ruptured steam generator tube at low pressure using a single charging pump flow assumes that following the initial steam generator tube rupture, operators will cool-down and depressurize the primary system. This assumption is valid and should take approximately one hour (SGTR Help Screen, 4 ref.3).
VI. Reducino Mechanisms A. Filtration System For containment bypass events into the auxiliary building, the release will be filtered by the Auxiliary / Fuel Building emergency exhaust filter trains. If this system is not operating, the release will be unfiltered.
B. Containment Spray Containment sprays are used for containment cooling and to remove fission products released into the containment atmosphere following an accident. Containment spray is very effective at removing particulates and aerosols, especially elemental and particulate iodines. This mechanism is not effective at removing noble gases or organic forms of iodine. For releases into containment, this analysis evaluates whether containment spray is on or off.
C. SGTR Partitioning /Non-Partitioning in a best estimate analysis performed by the Union Electric Licensing and Fuels Department (ref.13), a reduction factor of 1E-2 for SGTR removal mechanisms was conservatively assumed based on steam generator moisture separator removal of entrained iodines and a reference to a Westinghouse document that concluded that O
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Rev. O Pdge 12 of 62 except for a few seconds immediately after a reactor trip, the SG tube bundle remains covered with several feet of low void fraction mixture. Nureg-1228 and RASCAL use a reduction factor of 2.0E-2 for steam generaar tube rupture events that are considered partitioned. Partitioning means that the tube rupture is below the water / water-steam phase region where much of the particulates are removed. Since the value of 2E-2 used by Nureg-1228 and RASCAL for partitioning is more conservative than the value used in ref.13, the default value used in the RASCAL program will be used for all SGTR cases.
Vll. Meteorological Inouts Since meteorological data can vary significantly from time to time, trying to pre-define a set of meteorological conditions to use in determining radiological consequences to the public is difficult, if not impossible. Using worst case meteorological data would result in overly 2
O conservative results. Nureg-1228 uses average meteorological conditions (4 m/sec wind speed and a D stability class), and assumes a ground level release to derive event tree doses. Therefore, average meteorological data of 3.5 m/sec and an E stability class (Table 2.3-17, ref.14) for the Callaway plant are used in this analysis. Additionally, mixing layer depth is not mentioned in the Nureg-1228 analysis. Since a value is necessary for the RASCAL input, an average value of 237 meters for mixing layer depth using an E stability class (ref. 3)is used.
Vllt. Holduo Time and Release Duration The event status trees in Nureg-1228 incorporates reduction mechanisms that include decay of radionuclides due to holdup time in containment. 5 hr,2-12 hr, and 24 hr holdup times are used in the evaluation. This analysis assumes no containment holdup time.
This simplifies the decision flowchart and is a conservative assumption. A one hour ;
release duration is used in this analysis and is consistent with the release duration in Nureg-1228. :
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[ END STATUS TREE Page 13 c VESSEL MEl T-TIIItOUGil WITil CONTAINM ENT ltEl E ASE OFF _
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- * ' 'Y Yes VESSEL MELT-THROUGH [ * * *
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AT T 10 - FR(V SEVERE CORE DAM AGE WITII CONTAINMENT RET. EASE OFF , . SEE APPENDIX G
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EPCI-94-04, Rav. O Page 16 of 62 ATT 1D 4 FRONT END STATUS TREE STEAM CENERATOILIUf3E RUPTURE No SEE APPENDIX S t
STEAM GENERATOR Yes FILTERED CORE DAf AGE
~ RELEASE
/- - - -
TUBE RUPTURE 7 7
SEE No =_
Yes APPENDIX T No ;_
SEE APPENDIX U f
^ Yes FILTERED l 7 \ RELEASE SEE No Yes APPENDIX V D
if No _
SEE APPENDIX W 100 TIMES NCRMAL _ FILTERED COOLANT Yes ' RELEASE 7 7 N No Yes SEE APPENDIX X No __
SEE APPENDIX Y FILTERED L SE NORMAL COOLANT ACTIVITY SEE Yes APPENDIX Z q
EPCI-94-04, Rev. O ATT 1E . FRONT ENO STATUS TREE Page 17 of 62 k k, CONTAINMENT BYPASS EVENT U _'
SEE APPENOlX AA No FLO SEC
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/ Yes _
SEE No APPENDIX FF f
NOT ANALYZED.
Vatues would be less than gap actrvity.
NO PROTECTNE ACTIONS NECESSARY.
EPC'-94-04, Rev. O Page l8 cf 62 Summary of ST-DOSE inputs 03/02/94 10:38 y. f(
Straight-Line Plume Tf' \: EIP-ZZ-00212 BASES APPENDIX A Plw- '& Unit: CALLAWAY UNIT 1 1 Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data i Shut Down 08/02/94 00:00 winds stb mix Rel-> Cont 08/02/94 00:00 date time precip Rel->Envi OA/02/94 00 i o,0 1 08/02/94 00:00 90 J MPH E 237 M NONE l l
Rel End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Containment Failure; Large, Dry, or Subatmospheric Containment Core Condition: VESSEL M.ELT THROUGH Reactor Power: 3411 Mw(t) ,
Sprays: OFF Leak Rate: 100%/ HOUR Plume Model 7 Maximum doses at selected distances (rem) 5.0 {'
Distance (miles) .5 1.0 2.0 8.0 (km) .8 1.6 3.2 3.7E+03 2.2E+03 1.3E+03 5.5E+02 O Acute Bone Total EDE (EPA) Total 4.3E+04 2.5E+04 1.5E+04 5.9E+03 Thyroid (EPA) 5.4E+05 3.1E+05 1.8E+05 7.4E+04 Acute Lung 2.8E+04 1.6E+04 9.4E+03 3.8E+03 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 2.5E+03 1.4E+03 8.4E+02 3.4E+02 Cloud Shine 1.1E+03 6.8E+02 4.1E+02 2.2E+02 Initial Ground Shine 1.2E+02 6.0E+01 2.5E+01 0.0E+00 4-Day Ground Shine 5.9E+03 3.4E+03 2.0E+03 8.0E+02 CEDE Inhalation 3.5E+04 2.0E+04 1.2E+04 4.9E+03 NOTE: All values below 1.0E-03 have been set to zero.
O 4 B
EPCI 94-04, Rev. O Page 19 of 62 Summary of ST-DOSE inputs 08/02/94 10:51 cg g 'q ,
T EIP-ZZ-00212 BASES APPENDIX B Straight-Line Plume Pv-]:& Unit:.CALLAWAY UNIT 1 D Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data Shut Down 08/02/94 00:00 winds stb mix precip Rel-> Cont 08/02/94 00:00 date time Rel->Envi 08/02/94 00':00 1 08/02/94 00:00 90 8 MPH E 237 M NCHE Rol End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Containment Failure; Large, Dry, or Subatmospheric Containment Core Condition: VESSEL MELT THROUGH Reactor Power: 3411 Mw(t) .
Sprays: ON
. Leak Rate: 100%/ HOUR
, Plume Model r Maximum doses at selected distances (rem)
Distance (miles) .5 1.0 2.0 5.0 1.6 3.2 8.0
' (km) .8 Acute Bone Total 5.4E+02 3.2E+02 1.9E+02 9.7E+01 Total EDE (EPA) 2.2E+03 1.3E+03 7.7E+02 3.3E+02 Thyroid (EPA) 2.2E+04 1.3E+04 7.4E+03 3.0E+03 Acute Lung 1.1E+03 6.4E+02 3.8E+02 1.5E+02 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation 1
Acute Bone Inhalation 1.0E+02 5.9E+01 3.5E+01 1.4E+01 Cloud Shine 4.3E+02 2.6E+02 1.6E+02 8.3E+01 Initial Ground Shine 1.2E+01 5.8E+00 2.4E+00 0.0E+00 4-Day Ground Shine 3.5E+02 2.0E+02 1.2E+02 4.6E+01 CEDE Inhalation 1.5E+03 8.4E+02 5.0E+02- 2.0E+02 NOTE: All values below 1.0E-03 have been set to zero.
e
EPCI-94-04, Rev. O Summary of ST-DOSE inputs 08/02/94 10:52 )f[
T, : EIP-ZZ-00212 BASES APPENDIX C Straight-Line Plume PL, & Unit: CALLAWAY UNIT 1 Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data Shut Down 08/02/94 00:00 winds stb mix precip Rel-> Cont 08/02/94 00:00 date time Rel->Envi 08/02/94 00i00 1 08/02/94 00:00 90 8 HPH E 237 M NONE Rel End 08/02/94 01: 60 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Containment Failure; Large, Dry, or Subatmospheric Containment 4
Core Condition: VESSEL MELT THROUGH Reactor Power: 3411 Mw(t) .
Sprays: OFF Leak Rate: 100%/ DAY Plume Model 7 Maximum doses at selected distances (ren)
Distance (miles) .5 1.0 2.0 5.0 (km) .8 1.6 3.2 8.0 1.5E+02 8.6E+01 5.1E+01 2.2E+01 l
O~ AcuteTotal EDE Bone (EPA) Total Thyroid (EPA) 1.7E+03 9.8E+02 5.8E+02 2.3E+02 2.2E+04 1.2E+04 7.4E+03 3.0E+03 Acute Lung 1.1E+03 6.4E+02 3.8E+02 1.5E+02 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 9.9E+01 5.7E+01 3.4E+01 1.4E+01 Cloud Shine 4.5E+01 2.7E+01 1.7E+01 8.7E+00 Initial Ground Shine 4.8E+00 2.4E+00 9.9E-01 0.0E+00 4-Day Ground Shine 2.4E+02 1.4E+02 8.0E+01 3.2E+01 CEDE Inhalation 1.4E+03 8.2E+02 4.8E+02 1.9E+02 NOTE: All values below 1.0E-03 have been set to zero.
t
EPCI-94-04, Rev. O i Summary of ST-DOSE inputs 08/02/94 10:53 )C( '$g/
EIP-ZZ-00212 BASES APPENDIX D Straight-Line Plume )
T1 l Pl( & Unit: CALLAWAY UNIT 1 Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) j i
event date time Meteorological Data Shut Down 08/02/94 00:00 winds stb mix Rel-> Cont 08/02/94 00:00 date time precip Rel->Envi 08/02/94 00i00 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel End 08/02/94 01:d0 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Containment Failure; Large, Dry, or Subatmospheric Containment Core Condition: VESSEL MELT THROUGH Reactor Power: 3A11 Mw(t)
Sprays: ON Leak Rate: 100%/ DAY Plume Model 7 Maximum do.ces at selected distances (rem) 2.0 5.0 Distance (miles)
.5 1.0 8.0 l (km) .8 1.6 3.2
/\ Acute Bone Total 2.2E+01 1.3E+01 7.8E+00 3.9E+00 (s,) Total EDE (EPA) 8.9E+01 5.2E+01 3.1E+01 1.3E+01 Thyroid (EPA) 8.7E+02 5.0E+02 3.0E+02 1.2E+02 Acute Lung 4.4E+01 2.6E+01 1.5E+01 6.1E+00 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation l
Acute Bone Inhalation 4.1E+00 2.4E+00 1.4E+00 5.6E-01 Cloud Shine 1.7E+01 1.0E+01 6.3E+00 3.3E+00 Initial Ground Shine 4.6E-01 2.3E-01 9.7E-02 0.0E+00 4-Day Ground Shine 1.4E+01 8.0E+00 4.7E+00 1.8E+00 5.9E+01 3.4E+01 2.0E+01 8.0E+00 CEDE Inhalation
' NOTE: All values below 1.0E-03 have been set to zero.
1
EPCI 94-04, Rev. O Page 22 of 62 g
- Summary of ST-DOSE inputs -08/02/94 12:30 -r ((/d y '
Tik ~ EIP-ZZ-00212 BASES APPENDIX E Straight-Line Plume Pil & Unit: CALLAWAY UNIT 1 Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data Shut Down 08/02/94 00:00 time winds stb mix precip Rel-> Cont 08/02/94 00:00 date Rel->Envi 08/02/94 00iOO 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel End 08/02/94 01:0'O 2 Expos End 08/02/94 01:00 3 J
4 Source Term: Plant Conditions Containment Failure; Large, Dry, or Subatmospheric Containment Core Condition: VESSEL MELT THROUGH Reactor Power: 3411 Mw(t)
Sprays: OFF Leak Rate: 0.1%/ DAY (TYPICAL DESIGN) l Plume Model p Maximum doses at selected distances (rem) 2.0 5.0 Distance (miles) .5 1.0 8.0 (km) .8 1.6 3.2 cute Bone Total 1.5E-01 8.6E-02 5.1E-02 2.2E-02 Total EDE (EPA) 1.7E+00 9.8E-01 5.8E-01 2.3E-01 Thyroid (EPA) 2.2EF01 1.2E+01 7.4E+00 3.0E+00 Acuto Lung 1.1E+00 6.4E-01 3.8E-01 1.5E-01 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation 4
Acute Bone Inhalation 9.9E-02 5.7E-02 3.4E-02 1.4E-02 Cloud Shine 4.5E-02 2.7E-02 1.7E-02 8.7E-03 Initial Ground Shine 4.8E-03 2.4E-03 0.0E+00 0.0E+00 4-Day Ground Shine 2.4E-01 1.4E-01 8.0E-02 3.2E-02 CEDE Inhalation 1.4E+00 8.2E-01 4.8E-01 1.9E-01 NOTE: All values below 1.0E-03 have been set to zero.
l
- I
l EPCI 94 04, Rev. O l Summary of ST-DOSE inputs 08/02/94 12:29 /f T- : EIP-ZZ-00212 BASES APPENDIX F Straight-Line Plume ,
P & Unit: CALLAWAY UNIT 1 !
Rel' ease Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data Shut Down 08/02/94 00:00 stb mix Rel-> Cont 08/02/94 00:00 date time winds precip Rel->Envi 08/02/94 0 0 1.0 0 1 08/02/94 00:00 90 8 MPH E 237 M NOME Rel End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Containment Failure; Large, Dry, or Subatmospheric Containment Core Condition: VESSEL MELT THROUGH Reactor Power: 3411 Mw(t) l Sprays: ON {
Leak Rate: 0.1%/ DAY (TYPICAL DESIGN) l I
l Plume Model Maximum doses at selected distances (rem)
Distance (miles) .S 1.0 2.0 5.0 (km) .8 1.6 3.2 8.0 Acute Bone Total 2.2E-02 1.3E-02 7.8E-03 3.9E-03
. Total EDE (EPA) 8.9E-02 5.2E-02 3.1E-02 1. 3 E- 0 2 Thyroid (EPA) 8.7E-01 5.0E-01 3.0E-01 1.2E-01 Acute Lung 4.4E-02 2.6E-02 1.5E-02 6.1E-03 l Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 4.1E-03 2.4E-03 1.4E-03 0.0E+00 Cloud Shine 1.7E-02 1.0E-02 6.3E-03 3.3E-03 Initial Ground Shine 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4-Day Ground Shine 1.4E-02 8.0E-03 4.7E-03 1.8E-03 CEDE Inhalation 5.9E-02 3.4E-02 2.0E-02 8.0E-03 NOTE: All values below 1.0E-03 have been set to zero.
l l
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- - - - - - - - - - - - - - - - - - - - _ - - - - - - - - - - - -- - )
_ _l EPCI-94-04, Rev. O !
I Page 24 of 62 ,,
Summary of ST-DOSE inputs 08/02/94 12:31 /
v 7((hf Ti?N.: 'EIP-ZZ-00212 BASES APPENDIX G Straight-Line Plume P1 & Unit: CALLAWAY UNIT 1 Relea)seHeight: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data Shut Down 08/02/94 00:00 winds stb mix Rel-> Cont 08/02/94 00:00 date time precip Rel->Envi 08/02/94 001.00 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Containment Failure; Large, Dry, or Subatmospheric Containment Core Condition: IN-VESSEL SEVERE CORE DAMAGE (>30 min)
Reactor Power: 3411 Mw(t) .
Sprays: OFF Leak Rate: 100%/ HOUR Plume Model Maximum doses at selected distances (rem)
.5 2.0 5.0 Distance (miles) 1.0 3.2 8.0 (km) .8 1.6 Acute Bone Total 1.6E+03 9.4E+02 5.6E+02 2.5E+02 s Total EDE (EPA) 1.8E+04 1.0E+04 6.0E+03 2.4E+03 Thyroid (EPA) 2.8E+05 1.6E+05 9.6E+04 3.8E+04 Acute Lung 8.8E+03 5.1E+03 3.0E+03 1.2E+03 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 7.7E+02 4.4E+02 2.6E+02 1.0E+02 Cloud Shine 7.8E+02 4.7E+02 2.9E+02 1.5E+02 Initial Ground Shine 6.6E+01 3.3E+01 1.4E+01 0.0E+00 4-Day Ground Shine 2.4E+03 1.4E+03 8.2E+02 3.2E+02 CEDE Inhalation 1.4E+04 8.2E+03 4.9E+0". 2.0E+03 NOTE: All values below 1.0E-03 have been set to zero.
i l
)
EPCI 94-04, Rev. O Page 25 of 62 o
-Summary of ST-DOSE inputs 08/02/94 12:33 p7[fy '
- EIP-ZZ-00212 BASES APPENDIX H Straight-Line Plume :
T4 !
P1 & Unit: CALLAWAY UNIT 1 Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data Shut Down 08/02/94 00:00 winds stb mix precip Rel-> Cont 08/02/94 00:00 date time Rel->Envi 08/02/94 00i00 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3
- 4 Source Term: Plant Conditions Containment Failure; Large, Dry, or Subatmospheric Containment Core Condition: IN-VESSEL SEVERE CORE DAMAGE (>30 min)
Reactor Power: 3411 Mw(t) ,
Sprays: ON Leak Rate: 100%/ HOUR Plume Model 7 Maximum doses at selected distances (rem) 2.0 5.0 Distance (miles) .5 1.0 3.2 8.0 (km) .8 1.6 Acute Bone Total 4.6E+02 2.7E+02 1.7E+02 8.5E+01 Total EDE (EPA) 1.2E+03 7.2E+02 4.3E+02 1.9E+02 Thyroid (EPA) 1.1E+04 6.5E+03 3.8E+03 1.5E+03 Acute Lung 3.5E+02 2.0E+02 1.2E+02 4.8E+01 e Acute Bone Total = Acute Bor e Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 3.5E+01 2.0E+01 1.2E+01 4.8E+00
- Cloud Shine 4.1E+02 2.5E+02 1.5E+02 8.0E+01 Initial Ground Shine 9.5E+00 4.7E+00 2.0E+00 0.0E+00 4-Day Ground Shina 2.1E+02 1.2E+02 6.9E+01 2.7E+01
' CEDE Inhalation 6.2E+02 3.5E+02 2.1E+02 8.4E+01 4
NOTE: All values below 1.0E-03 have been set to zero.
l 1
l l
i
EPCI-94-04, Rev. 0
, Summary of ST-DOSE inputs 08/02/94 12:34 f p {!ftj l Ti# \' EIP-ZZ-00212 t BASES APPENDIX I Straight-Line Plume Pbd & Unit: CALLAWAY UNIT 1 Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) 4 event date time Meteorological Data 08/02/94 00:00 Shut Down '
Rel-> Cont 08/02/94 00:00 date time winds stb mix precip Rel->Envi 08/02/94 00i.00 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel.End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Containment Failure; Large, Dr , or Subatmospheric Containment Core Condition: IN-VESSEL SEVERE CORE DAMAGE (>30 min)
Reactor Power: 3411 Mw(t) ,
Sprays: OFF Leak Rate: 100%/ DAY Plume Model 7 Maximum doses at selected distances (rem)
.5 5.0 Distance (miles) 1.0 2.0 8.0 (km) .8 1.6 3.2 Acute Bone Total 6.4E+01 3.8E+01 2.2E+01 1.0E+01 Total EDE (EPA) 7.0E+02 4.0E+02 2.4E+02 9.7E+01
< Thyroid (EPA) 1.1E+04 6.5E+03 3.8E+03 1.5E+03 Acute Lung 3.5E+02 2.0E+02 1.2E+02 4.8E+01 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation 4
Acute Bone Inhalation 3.1E+01 1.8E+01 1.0E+01 4.2E+00 Cloud Shine 3.1E+01 1.9E+01 1.1E+01 6.0E+00 Initial Ground Shine 2.6E+00 1.3E+00 '5.5E-01 0.0E+00 4-Day Ground Shine 9.8E+01 5.6E+01 3.3E+01 1.3E+01 CEDE Inhalation 5.7E+02 3.3E+02 1.9E+02 7.8E+01 NOTE: All values below 1.0E-03 have been set to zero.
O
-.-_r- - . , _ . _ _ , , , _, . .
.___m_. _ _ _ . , _ _ - - _ _ _ _ _ _ _ _ _- _ _ . _ _ _ _ . . - -
..- .-m m . _ _ - __ _ ~ . _ _
EPCI-94 04, Rev..Q.
Page 27 of 62 "s Summary of ST-DOSE inputs 08/02/94 12:3S ! ?. .Y, Y '
Straight-Line Plume T/y:& EIP-ZZ-00212
' P"q,4 Unit: CALLAWAY BASES APPENDIX J UNIT 1 Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) !
event date time Meteorological Data Shut Down 08/02/94 00:00 stb mix l
Rel-> Cont 08/02/94 00:00 date time winds precip Rel->Envi 08/02/94 001.00 1 08/02/94 00:00 90 8 MPM E 237 M NONE Rel End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 '
4 Source Term: Plant Conditions containment Failure; Large, Dry, or Subatmospheric Containment j Core Condition: IN-VESSEL SEVERE CORE DAMAGE (>30 min) i Reactor Power: 3412 Mw(t),
sprays: ON Leak Rate: 100%/ DAY Plume Model Maximum doses at selected distances (rem)
Distance (miles) .5 1.0 2.0 5.0 4
(km) .8 1.6 3.2 8.0 Acute Bone Total 1.8E+01 1 1E+01 6.6E+00 3.4E+00
$ Total EDE (EPA). 4.9E+01 2.9E+01 1.7E+01 7.7E+00 Thyroid (EPA) 4.5E+02 2.6E+02 1.5E+02 6.2E+01 Acute Lung 1.4E+01 8.1E+00 4.8E+00 1.9E+00 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine
- Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 1.4E+00 8.1E-01 4.8E-01 -1.9E-01 Cloud Shine 1.6E+01 9.9E+00 6.1E+00 3.2E+00 Initial Ground Shine 3.8E-01 1.9E-01 7.9E-02 0.0E+00 4-Day Ground Shine 8.3E+00 4.8E+00 2.8E+00 1.1E+00 ,
CEDE Inhalation 2.5E+01 1.4E+01 8.4E+00 3.4E+00 NOTE: All values below 1.0E-03 have been set to zero.
I h
,e y
EPCI.94-04, Rev. 0 l Page 2S of 62 Summary of ST-DOSE inputs 08/02/94 12:36 ( f 7[(( '
Ti : EIP-ZZ-00212 BASES APPENDIX K Straight-Line Plume i P!, & Unit: CALLAWAY UNIT 1 Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data Shut Down 08/02/94 00:00 winds stb mix Rel-> Cont 08/02/94 00:00 date time precip Rel->Envi 08/02/94 00i.00 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Containment Failure; Large, Dry, or Subatmospheric Containment Core Condition: IN-VESSEL SEVERE CORE DAMAGE (>30 min)
Reactor Power: 3411 Mw(t)
Sprays: OFF Leak Rate: 0.1%/ DAY (TYPICAL DESIGN)
Plume Model 7 Maximum doses at selected distances (rem)
Distance (miles) .5 1.0 2.0 5.0 (km) .8 1.6 3.2 8.0 Acute Bone Total 6.4E-02 3.8E-02 2.2E-02 1.0E-02
( Total EDE (EPA) 7.0E-01 4.0E-01 2.4E-01' 9.7E-02 Thyroid (EPA) 1.1E+01 6.5E+00 3.8E+00 1.5E+00 Acute Lung 3.5E-01 2.0E-01 1.2E-01 4.8E-02 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 3.1E-02 1.8E-02 1.0E-02 4.2E-03 Cloud Shine 3.1E-02 1.9E-02 1.1E-02 6.0E-03 Initial Ground Shine 2.6E-03 1.3E-03 0.0E+00 0.0E+00 4-Day Ground Shine 9.8E-02 5.6E-02 3.3E-02 1.3E-02 CEDE Inhalation 5.7E-01 3.3E-01 1.9E-01 7.8E-02 NOTE: All values below 1.0E-03 have been set to zero.
l
()
EPCI-94-04, Rev. O Summary of ST-DOSE inputs 08/02/94 12:37 .Ir f [.. (
Tl/~N* EIP-ZZ-00212 BASES APPENDIX L Straight-Line Plume l l
P1 & Unit: CALLAWAY UNIT 1 Re ease Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) l event date time Meteorological Data l
Shut Down 08/02/94 00:00 winds stb mix precip Rel-> Cont 08/02/94 00:00 date time Rel->Envi 08/02/94 00iOO 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel End 08/02/94 01:0'O 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Containment Failure; Large, Dry, or Subatmospheric Containment Core Condition: IN-VESSEL SEVERE CORE DAMAGE (>30 min)
Reactor Power: 3411 Mw(t)
Sprays: ON Leak Rate: 0.1%/ DAY (TYPICAL DESIGN)
Plume Model Maximum doses at selected distances (rem)
Distance (miles) .5 1.0 2.0 5.0 (km) .8 1.6 3.2 8.0 Acute Bone Total 1.8E-02 1.1E-02 6.6E-03 3.4E-03 l Total EDE (EPA) 4.9E-02 2.9E-02 1.7E-02 7.7E-03 Thyroid (EPA) 4.5E-01 2.6E-01 1.5E-01 6.2E-02 Acute Lung 1.4E-02 8.1E-03 4.8E-03 1.9E-03 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine i
Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation i
____________________________________________________ {'
Acute Bone Inhalation 1.4E-03 0.0E+00 0.0E+00 0.0E+00 Cloud Shine 1.6E-02 9.9E-03 '6.1E-03 3.2E-03 Initial Ground Shine 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4-Day Ground Shine 8.3E-03 4.8E-03 2.8E-03 1.1E-03 CEDE Inhalation 2.5E-02 1.4E-02 8.4E-03 3.4E-03 l HOTE: All values below 1.0E-03 have been set to zero.
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,. . . . _. . . . -- .-. .- ~ . - -- . . ...- -
I EPCI-94-04, Rev. O Page 30 of 62 {
Summary of ST-DOSE inputs 08/02/94 12:37 ()pf.
Ti'"\: EIP-ZZ-00212 BASES APPENDIX M Straight-Line Plume Pig,)t. Unit: CALLAWAY UNIT 1 Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data Shut Down 08/02/94 00:00 winds stb mix precip Rel-> Cont 08/02/94 00:00 date time Rel->Envi 08/02/94 00:00 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel End 08/02/94 01:00 2
, Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions l
Containment Failure; Large, Dry, or Subatmospheric Containment Core Condition: GAP RELEASE (uncovered 15-30 min) l I
Reactor Power: 3411 Mw(t)
Sprays: OFF Leak Rate: 100%/ HOUR l
Plume Model Maximum doses at selected distances (rem)
Distance (miles) . 5 1.0 2.0 5.0 (km) . 8 1.6 3.2 8.0 Acute Bone Total 1.3E+02 7.5E+01 4.4E+01 2.0E+01 l Total EDE (EPA) 1.6E+03 9.0E+02 5.3E+02 2.2E+02 Thyroid (EPA) 3.7E+04 2.1E+04 1.2E+04 5.0E+03 Acute Lung 3.8E+02 2.2E+02 1.3E+02 5.2E+01 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine l
Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 4.7E+01 2.7E+01 1.6E+01 6.4E+00 Cloud Shine 7.3E+01 4.4E+01 2.7E+01 1.4E+01 Initial Ground Shine 8.4E+00 4.2E+00 1.8E+00 0.0E+00 4-Day Ground Shine 1.8E+02 1.0E+02 6.0E+01 2.3E+01 CEDE Inhalation 1.3E+03 7.5E+02 4.4E+02 1.8E+02 NOTE: All values below 1.0E-03 have been set to zero. ,
(
v-c- y---v-* 1r 7, -w,mn --, -,y-,, - -,w-- v y- m e w CteiS--*
EPCI 94-04, Rev. O Page 31 d 2 c
Summary of ST-DOSE inputs 08/02/94 12:40 (( 7 g Tiu EIP-ZZ-00212 BASES APPENDIX N Straight-Line Plume PIy,) & Unit: CALLAWAY UNIT 1 Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data Shut Down 08/02/94 00:00 stb mix Rel-> Cont 08/02/94 00:00 date time winds precip Rel->Envi 08/02/94 00iOO 1 38/02/94 00:00 90 8 MPH E 237 M NONE Rel End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Containment Failure; Large, Dry, or Subatmospheric Containment Core Condition: GAP RELEASE (uncovered 15-30 min)
Reactor Power: 3411 Mw(t) ,
Sprays: ON Leak Rate: 100%/ HOUR Plume Model p Maximum doses at selected distances (rem)
Distance (miles) .5 1.0 2.0 5.0 8.0 (km) .8 1.6 3.2 Acute Bone Total 2.6E+01 1.5E+01 9.3E+00 4.7E+00 Total EDE (EPA) 9.0E+01 5.3E+01 3.1E+01 1.4E+01 Thyroid (EPA) 1.5E+03 8.4E+02 5.0E+02 2.0E+02 Acute Lung 1.5E+01 8.8E+00 5.2E+00 2.1E+00 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 2.1E+00 1.2E+00 7.1E-0: 2.9E-01 Cloud Shine 2.3E+01 1.4E+01 8.4E+00 4.5E+00 Initial Ground Shine 7.0E-01 3.5E-01 1.4E-01 0.0E+00 4-Day Ground Shine 1.3E+01 7.5E+00 4.3E+00 1.7E+00 CEDE Inhalation 5.4E+01 3.1E+01 1.9E+01 7.4E+00 NOTE: All values below 1.0E-03 have been set to zero.
l EPCI-94 04, Rev. O Page 32 of 6 i Summary of ST-DOSE inputs 08/02/94 12:41 (f~j g /g[9 l EIP-ZZ-00212 BASES APPENDIX 0 Straight-Line Plume Tf]:&
P L ,- Unit: CALLAWAY UNIT 1 ,
Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) l event date time Meteorological Data Shut Down 08/02/94 00:00 stb mix Rel-> Cont 08/02/94 00,:00 date time winds precip Rel->Envi 08/02/94 00:00 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel-End 08/02/94_01: 00 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Containment Failure; Large, Dry, or Subatmospheric containment Core Condition: GAP RELEASE (uncovered 15-30 min)
Reactor Power: 3411 Mw(t) ,
Sprays: OFF Leak Rate: 100%/ DAY Plume Model 7 Maximum doses at selected distances (rem)
Distance (miles) .5 1.0 2.0 5.0 8.0 (km) .8 1.6 3.2 Acute Bone Total 5.1E+00 3.0E+00 1.8E+00 8.0E-01 Total EDE (EPA) 8.6E+00 6.2E+01 3.6E+01 2.1E+01 Thyroid (EPA) 1.5E+03 8.4E+02 5.0E+02 2.0E+02 Acute Lung 1.5E+01 8.7E+00 5.2E+00 2.1E+00 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acuto Bone Inhalation 1.9E+00 1.1E+00 6.4E-01 2.6E-01 Cloud Shine 2.9E+00 1.7E+00 1.1E+00 5.6E-01 Initial Ground Shine 3.4E-01 1.7E-01 7.0E-02 0.0E+00 4-Day Ground Shine 7.2E+00 4.1E+00 2.4E+00 9.4E-01 CEDE Inhalation 5.2E+01 3.0E+01 1.8E+01 7.1E+00 NOTE: All values below 1.0E-03 have been set to zero.
EPCI-94-04, Rev. 0 .
Page 33 of 67 Summary of ST-DOSE inputs 08/02/94 12:42 gf]} /{/,ggI s- f ,
Tf'^q : EIP-ZZ-00212 BASES APPENDIX P Straight-Line Plume P( ) & Unit: CALLAWAY UNIT 1 Retuase Meight: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data Shut Down 08/02/94 00:00 stb mix Rel-> Cont 08/02/94 00:00 date time winds precip Rel->Envi 08/02/94 00:.00 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rol End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
1 Source Term: Plant Conditions Containment Failure; Large, Dry, or Subatmospheric Containment Core Condition: GAP RELEASE (uncovered 15-30 min)
Reactor Power: 3411 Mw(t)
Sprays: ON Leak Rate: 100%/ DAY Plume Model -
Maximum doses at selected distances (rem) r Distance (miles) .5 1.0 2.0 5.0 (km) .8 1.6 3.2 8.0 1.0E+00 6.1E-01 3.7E-01 1.9E-01 O, Acute Bone(EPA)
Total EDE Total 3.6E+00 2.1E+00 1.3E+00 5.4E-01 Thyroid (EPA) 5.9E+01 3.4E+01 2.0E+01 8.0E+00 Acute Lung 6.1E-01 3.5E-01 2.1E-01 8.4E-02 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 8.4E-02 4.8E-02 2.9E-02 -1.1E-02 Cloud Shine 9.2E-01 5.5E-01 3.4E-01 1.8E-01 Initial Ground Shine 2.8E-02 1.4E-02 5.8E-03 0.0E+00 4-Day Ground Shine 5.2E-01 3.0E-01 1.7E-01 6.7E-02 CEDE Inhalation 2.2E+00 1.3E+00 7.4E-01 3.0E-01 l NOTE: All values below 1.0E-03 have been set to zero.
l 1
l l
1 l
EPCI.94-04, Rev. O Page 34 of 62 Summary of ST-DOSE inputs 08/02/94 12:43 (f g c y s_- , , /
EIP-ZZ-00212 BASES APPENDIX Q Straight-Line Plume V'"
Pvc p:& Unit: CALLAWAY UNIT 1 Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event. date time Meteorological Data Shut Down 08/02/94 00:00 winds stb mix precip Rel-> Cont 08/02/94 00:00 date time Rel->Envi 08/02/94 00100 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Containment Failure; Large, Dry, or Subatmospheric Containment Core Condition: GAP RELEASE (uncovered 15-30 min)
Reactor Power: 3411 Mw(t) '
Sprays: OFF Leak Rate: 0.1%/ DAY (TYPICAL DESIGN)
Plume Model Maximum doses at selected distances (rem) 5.0 Distance (miles) .5 1.0 2.0 3.2 8.0 (km) .8 1.6
[ '\ Acute Bono Total 5.1E-03 3.0E-03 1.8E-03 0.0E+00 Total EDE (EPA) 6.2E-02 3.6E-02 2.1E-02 8.6E-03 Thyroid (EPA) 1.5E+00 8.4E-01 5.0E-01 2.0E-01 Acute Lung 1.5E-02 8.7E-03 5.2E-03 2.1E-03 Acuto Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Done Inhalation 1.9E-03 1.1E-03 0.0E+00 0.0E+00 Cloud Shine 2.9E-03 1.7E-03 1.1E-03 0.0E+00 Initial Ground Shine 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4-Day Ground Shine 7.2E-03 4.1E-03 2.4E-03 0.0E+00 CEDE Inhalation 5.2E-02 3.0E-02 1.8E-02 7.1E-03 :
NOTE: All values below 1.0E-03 have been set to zero.
1
(
i )
\
EPCI-94 04, Rev. 0 '
Page 35 0f 62 Summary of ST-DOSE inputs 08/02/94 12:44 jf )gf /
Tf*1p: EIP-ZZ-00212 BASES APPENDIX R Straight-Line Plume F & Unit: CALLAWAY UNIT 1 R(624ase Height:
0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data Shut Down 08/02/94 00:00 Rel-> Cont 08/02/94 00:00 date time winds stb mix precip Rel->Envi 08/02/94 00:00 , 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Containment Failure; Large, Dry, or Subatmospheric Containment Core Condition: GAP RELEASE (uncovered 15-30 min)
Reactor Power: 3411 Mw(t) -
Sprays: oN Leak Rate: 0.1%/ DAY (TYPICAL DESIGN)
Plume Model Maximum doses at selected distances (rem) f Distance (miles) .5 1.0 2.0 5.0 (km) .8 1.6 3.2 8.0 Acute Bone Total 1.0E-03 0.0E+00 0.0E+00 0.0E+00 Total EDE (EPA) 3.6E-03 2.1E-03 1.3E-03 0.0E+00 Thyroid (EPA) 5.9E-02 3.4E-02 2.0E-02 8.0E-03 Acute Lung 0.0E+00 0.0E+00 0.0E+00 0.0E+00 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 0.0E+00 0.0E+00 0.0E+00 0.0E+00 Cloud Shine 0.0E+00 0.0E+00 0.0E+00 0.0E+00 Initial Ground Shine 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4-Day Ground Shine 0.0E+00 0.0E+00 0.0E+00 0.0E+00 CEDE Inhalation 2.2E-03 1.3E-03 0.0E+00 0.0E+00 NOTE: All values below 1.0E-03 have been set to zero.
EPCI-94 04, Rev. 0 Summary'of ST-DOSE inputs 08/02/94 12:46 j{g/',
~' '
Tip' : EIP-ZZ-00212 BASES APPENDIX S Straight-Line Plume PY & Unit: CALLAWAY UNIT 1 Re'k se Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data Shut,Down 08/02/94 00:00 winds stb mix precip Rel-> Cont 08/02/94 00:00 date time Rel->Envi 08/02/94 001,00 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel End 08/02/.94 01:00 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Steam Generator Tube Rupture Core Condition: IM-VESSEL SEVERE CORE DAMAGE (>30 min)
Steam Generator: PARTITIONED -
Leak Rate: 1 TUBE AT FULL PRESSURE Release Point: SAFETY VALVE 1
Plume Model Maximum doses at selected distances (rem) f 2.0 5.0 Distance (miles) .5 1.0 3.2 8.0 (km) .8 1.6 Acute Bone Total 1.5E+02 9.2E+01 5.6E+01 2.9E+01 Total EDE (EPA) 3.5E+02 2.1E+02 1.2E+02 5.6E+01 Thyroid (EPA) 2.6E+03 1.5E+03 8.9E+02 3.6E+02 Acute Lung 8.2E+01 4.8E+01 2.8E+01 1.1E+01 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 8.7E+00 5.0E+00 3.0E+00 1.2E+00 Cloud Shine 1.4E+02 8.5E+01 5.2E+01 2.8E+01 Initial Ground Shine 3.0E+00 1.5E+00 6.3E-01 0.0E+00 4-Day Ground Shine 6.2E+01 3.5E+01 2.1E+01 8.0E+00 CEDE Inhalation 1.5E+02 8.6E+01 5.1E+01 2.0E+01 NOTE: All values below 1.0E-03 have been set to zero.
I i
i 1
e .
, . . . -. . --- - - . _ - . - . = . . _ . . . .-, ._. . _ -.
EPCI.94 04, Rev. O Summary of ST-DOSE inputs 08/02/94 12: 47 Page 37 of 62 (/f (
Straight-Line Plume Tl' : EIP-ZZ-00212 BASES APPENDIX T UNIT 1 P( - & Unit: CALLAWAY Building Wake: Y Calculation Radius: 25 mi (40 km)
ReYease Height: 0M
. event date time Meteorological Data Shut Down 08/02/94 00:00 time winds stb mix precip Rel-> Cont 08/02/94 00:00 date 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel->Envi _08/02/94 00':.00 Rel.End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
J
. Source Term: Plant Conditions Steam Generator Tube Rupture ,
Core Condition: IN-VESSEL SEVERE CORE DAMAGE (>30 min)
Steam Generator: PARTITIONED 4
Leak Rate: 1 TUBE.AT FULL PRESSURE Release Point: STEAM JET AIR EJECTOR Plume Model Maximum doses at selected distances (rem)
' f 2.0 5.0 Distance (miles) .5 1.0 3.2 8.0 (km) .8 1.6 i
Acute Bone Total 1.4E+02 8.6E+01 5.2E+01 2.7E+01 2.0E+02 1.2E+02 7.3E+01 3.5E+01 1- Total EDE (EPA)
Thyroid (EPA) 1.3E+02 7.7E+01 4.5E+01 1.8E+01
- Acute Lung 4.8E+00 2.8E+00 1.6E+00 6.6E-01 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine i
Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 2.0E+00 1.1E+00 6.6E-01 2.7E-01 Cloud Shine 1.4E+02 8.3E+01 5.1E+01 2.7E+01
' Initial Ground Shine 2.5E+00 1.3E+00 5.2E-01 0.0E+00 4.1E+01 2.4E+01 1.4E+01 5.2E+00 4-Day Ground Shine CEDE Inhalation 2.3E+01 1.3E+01 7.8E+00 3.1E+00 NOTE: All values below t.0E-03 have been set to zero.
)
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1 l
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EPCI 94-04, Rev. O Summary of ST-DOSE inputs 08/02/94 12: 49 [v ff - -
. T! , . EIP-ZZ-00212
- BASES APPENDIX U Straight-Line Plume P1 ,1 & Unit: CALLAWAY UNIT 1 Release Height: 0M Building Wake: Y Calcula". ion Radius: 25 mi (40 km) event date time Meteorological Data Shut Down 08/02/94 00:00 stb mix Rel-> Cont 08/02/94 00:00 date time winds precip Rel->Envi 1 08/02/94 00:00 90 8 MPH E 237 M NONE 08/02/94 00:00 ,
Rel End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Steam Generator Tube Rupture Core Co..lition: GAP RELEASE (uncovered 15-30 min)
Steam Generator: PARTITIONED Leak Rate: 1 TUBE'AT FULL PRESSURE Release Point: SAFETY VALVE Plume Model Maximum doses at selected distances (rem) f Distance (miles) .5 1.0 2.0 5.0 8.0 (km) .8 1.6 3.2 Acute Bone Total 8.5E+00 5.1E+00 3.1E+00 1.6E+00
(, Total EDE (EPA) 2.4E+01 1.4E+01 8.5E+00 3.8E+00 Thyroid (EPA) 3.4E+02 2.UE+02 1.2E+02 4.7E+01 Acute Lung 3.6E+00 2.1E+00 1.2E+00 4.9E-01 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 5.2E-01 3.0E-01 1.8E-01 7.1E-02 Cloud Shine 7.8E+00 4.7E+00 2.9E+00 1.5E+00 Initial Ground Shine 2.1E-01 1.0E-01 4.3E-02 0.0E+00 4-Day Ground Shino 3.7E+00 2.1E+00 1.2E+00 4.8E-01 CEDE Inhalation 1.3E+01 7.5E+00 4.4E+00 1.8E+00 NOTE: All values below 1.0E-03 have been set to zero.
U
=_ - ,
EPCI.94-04, Rev. O Page 39 of 62 ,.
Summary of ST-DOSE inputs 08/02/94 12:53 'f j cg /y
- ,t
.Tif-Pl-EIP-ZZ-00212 BASES APPENDIX V
& Unit: CALLAWAY UNIT 1
-Straight-Line Plume Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data
-Shut Down 08/02/94 00:00 Rel-> Cont- 08/02/94 00:00 date time winds stb mix precip
'Rel->Envi 08/02/94 00:00 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions ,
Steam Generator Tube Rupture Core Condition: GAP RELEASE (uncovered 15-30 min)
Steam Generator: PARTITIONED Leak Rate: 1 TUBE AT FULL PRESSURE Release Point: STEAM JET AIR EJECTOR Plume Model Maximum doses at selected distances (rem) f Distance (miles) .5 1.0 2.0 5.0 (km) .8 1.6 3.2 8.0
\ cute Bone Total 7.5E+00 4.5E+00 2.8E+00 1.4E+00 Total EDE (EPA) 1.1E+01 6.5E+00 3.9E+00 1.9E+00
, Thyroid (EPA) 1.7E+01 9.9E+00 5.EE+00 2.3E+00 Acute Lung 2.2E-01 1.2E-01 7.3E-02 2.9E-02 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 1.1E-01 6.1E-02 3.6E-02 1.4E-02
> Cloud Shine 7.3E+00 4.4E+00 2.7E+00 1.4E+00 Initial Ground Shine 1.3E-01 6.8E-02 2.8E-02 0.0E+00 4-Day Ground Shine 2.2E+00 1.3E+00 7.3E-01 7.8E-01 CEDE Inhalation 1.5E+00 8.4E-01 5.0E-01 2.0E-01 NOTE: All values below 1.0E-03 have been set to zero.
- . . - _ .- - - ~ . . .
EPCI-94-04, Rev. 0
. Summary of ST-DOSE inputs 08/02/94 12:54 ( g/g T$' : EIP-ZZ-00212 BASES APPENDIX W Straight-Line Plume Pi. & Unit: CALLAWAY UNIT 1
. Rel, ease Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data
- Shut Down 08/02/94 00:00
-Rel-> Cont 08/02/94 00:00 date time winds stb mix precip
- Rel->Envi 08/02/94 00:00 , 1 08/02/94 00:00 90 8 MPH E 237 M NONE
- Rel End 08/02/94 01:00 2 Expos'End 08/02/94 01:00 3 4
Source Term: Plant Conditions Steam Generator Tube Rupture Core Condition: COOLANT WITH 100x NORMAL NON-NOBLES Steam Generator: PARTITIONED Leak Rate: 1 TUBE AT FULL PRESSURE 4
Release Point: SAFETY VALVE Plume Model Maximum doses at selected distances (rem) r Distance (miles) .5 1.0 2.0 5.0 (km) .8 1.6 3.2 8.0 Acute Bone Total 5.3E-03 3.1E-03 1.8E-03 0.0E+00
,,)TotalEDE ,, EPA) 6.6E-02 3.8E-02 2.2E-02 9.0E-03 Thyroid (EPA) 1.1E-01 -6.3E-02 3.7E-02 1.5E-02 Acute Lung 4.5E-02 2.6E-02 1.5E-02 6.1E-03 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 4.8E-03 2.8E-03 1.6E-03 0.0E+00 Cloud Shine 0.0E+00 0.0E+00 0.0E+00 0.0E+00 Initial Ground Shine 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4-Day Ground Sbino 1.3E-03 0.0E+00 0.0E+00 0.0E+00 CEDE Inhalation 6.4E-02 3.7E-02 2.2E-02 8.7E-03 NOTE: All values below 1.0E-03 have been set to zero.
I i
l
EPCI-94-04, Rev. O Page 41 of 62 rn -
Summary of'ST-DOSE inputs 08/02/94 12:54 (g{ pfg'g
- EIP-ZZ-00212 BASES APPENDIX X Straight-Line Plume T4' P lL_ )l &' Unit:CALLAWAY Building Nake: Y UNIT 1 Calculation Radius: 25 mi (40 km)
Release Height: 0M event date time Meteorological Data Shut Down 08/02/94 00:00 time winds stb mix precip Rel-> Cont 08/02/94 00:00 date 90 8 MPH E 237 M NONE Rel->Envi 08/02/94 00100 1 08/02/94 00:00 Rel End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
Source Termi Plant Conditions Steam Generator Tube Rupture Core Condition: COOLANT WITH 100x NORMAL NON-NOBLES Steam Generator: PARTITIONED Leak Rate: 1 TUBE AT FULL PRESSURE Release Point: STEAM JET AIR EJECTOR Plume Model Maximum deses at selected distances (rem) f Distance (miles) .5 1.0 2.C 5.0 3.6 3.2 8.0 (km) .8 Acute Bone Total 3.7E-03 2.1E-03 1. ', E-0 3 0.0E+00
\ Total EDE (EPA) 7.0E-03 4.0E-03 2.tE-03 0.0E+00 Thyroid (EPA) 9.0E-03 5.2E-03 3.1L-03 1.2E-03 Acute Lung 5.5E-03 3.2E-03 1.9E-03 0.0E+00 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine !
Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation I
Acuto Bone Inhalation 3.5E-03 2.0E-03 1.2E-03 0.0E+00 Cloud Shine 0.0E+00 0.0E+00 0.0E+00 0.0E+00 Initial Ground Shine 0.0E+00 0.0E+00 0.0E+00 0.0E+00 l 4-Day Ground Shine 0.0E+00 0.0E+00 0.0E+00 0.0E+00 j CEDE Inhalation 6.8E-03 3.9E-03 2.3E-03 0.0E+00 l I
)
NOTE: All values below 1.0E-03 have been set to zero.
)
O i V
EPCI-94-04, Rev. O Page 42 of 62 ,9 j
- Summary of ST-DOSE inputs 08/02/94 12:55 ({h {,g ,-
EIP-ZZ-00212 BASES APPENDIX Y Straight-Line Plume !
Ti)\: Unit: CALLAWAY Pi, &
Rel' ease Height: 0M Building Wake: Y UNIT 1 Calculation Radius: 25 mi (40 km) event date time Meteorological Data Shut Down 08/02/94 00:00 Rel-> Cont date time winds stb mix precip 08/02/94 00:00 8 MPH E 237 M NONE Rel->Envi 08/02/94 001,00 1 08/02/94 00:00 90 Rel End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Steam Generator Tube Rupture Core Condition: TYPICAL COOLANT Steam Generator: PARTITIONED -
Leak Rate: 1 TUBE AT FULL PRESSURE Release Point: SAFETY VALVE Plume Model Maximum doses at selected distances (rem) f 2.0 5.0 Distance (miles) .5 1.0 3.2 8.0 (km) .8 1.6 0.0E+00 0.0E+00 0.0E+00 0.0E+00
["'j\,
\ Acute Bone Total EDE Total 0.0E+00 (EPA) 0.0E+00 0.0E+00 0.0E+00 Thyroid (EPA) 1.1E-03 0.0E+00 0.0E+00 0.0E+00 Acute Lung 0.0E+00 0.0E+00 0.0E+00 0.0E+00 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 0.0E+00 0.0E+00 0.0E+00 0.0E+00 Cloud Shine 0.0E+00 0.0E+00 0.0E+00 0.0E+00 Initial Ground Shine 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4-Day Ground Shine 0.0E+00 0.0E+00 0.0E+00 0.0E+00 CEDE Inhalation 0.0E+00 0.0E+00 0.0E+00 0.0E+00 NOTE: All values below 1.0E-03 have been set to zero.
f
(
EPCI-94-04, Rev. O Page 43 of 62 Summary of ST-DOSE-inputs 08/02/94 12:56 j- - - { g
- , f Straight-Line Plume Tit], EIP-ZZ-00212 BASES APPENDIX ZUNIT 1
& Unit: CALLAWAY Plt Rel'ed'se Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data Shut Down 08/02/94 00:00 stb mix Rel-> Cont 08/02/94 00:00 date time winds precip Rel->Envi 08/02/94 00:00, 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
' Source Term: Plant Conditions Steam Generator Tube Rupture
. . Core Condition: TYPICAL COOLANT Steam Generator: PARTITIONED
- Leak Rate: 1 TUDE AT FULL PRESSURE Release Point: STEAM JET AIR EJECTOR plume Model Maximum doses at selected distances (rem) f Distance (miles) .5 1.0 2.0 5.0 (km) .8 1.6 3.2 8.0 cute Bone "_otal 0.0E+00 0.0E+00 0.0E+00 0.0E+00 I Total EDE (EPA) 0.0E+00 0.0E+00 0.0E+00 0.0E+00 Thyroid (EPA) 0.0E+00 0.0E+00 0.0E+00 0.0E+00 Acute Lung 0.0E+00 0.0E+00 0.0E+00 0.0E+00 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 0.0E+00 0.0E+00 0.0E+00 0.0E+00 Cloud Shine 0.0E+00 0.0E+00 0.0E+00 0.0E+00 Initial Ground Shine 0.0E+00 0.0E+00 0.0E+00 0.0E+00 4-Day Ground Shine 0.0E+00 0.0E+00 0.0E+00 0.0E+00 CEDE Inhalation 0.0E+00 0.0E+00 0.0E+00 0.0E+00 NOTE: All values below 1.0E-03 have been set to zero.
6 5
EPCI-94-04, Rev. O Page 44 of 62 Summary of ST-DO$t inputs 08/02/94 12:57 [ff{c7f,[ /
CIP-ZZ-00212 BASES APPENDIX AA Straight-Line Plume Ti[Plh.a)& Unit: CALLAWAY Building Wake: Y UNIT 1 Calculation Radius: 25 mi (40 km)
Release Height: 0M event date time Meteorological Data Shut Down 08/02/94 00:00 winds stb mix precip 08/02/94 00:00 date time fRel-> Cont 1 08/02/94 00:00 90 8 MPH E 237 M NONE i Rel->Envi 08/02/94 00':00 f Rel End 08/02/94 01:00 2
- f. Expos End 08/02/94 01:00 3
' 4 Source Term: Plant Conditions Containment Bypass (Event V)
Core Condition: IN-VESSEL SEVERE CORE DAMAGE (>30 min)
Reactor Power: 3411 Mw(t) -
Filters: UNFILTERED Leak Rate: 100%/ HOUR l
Plume Model Maximum doses at selected distances (rem) -
f
.5 2.0 5.0 Distance (miles) 1.0 3.2 8.0 (km) .8 1.6 7 3E+02 4 3E+02 2 6E+02 1 2E+02
[IlAcute
\~- TotalBone Total EDE (EPA) 5.1E+03 2.9E+03 1.7E+03 7.2E+02 !
Thyroid (EPA) 7.5E+04 4.3E+04 2.6E+04 1.0E404 ]
Acute Lung 2.3E+03 1.3E+03 8.0E+02 3.2E+02 l I
Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine l Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation l Acute Bone Inhalation 2.1E+02 1.2E+02 7.1E+01 2.8E+01 Cloud Shine 5.0E+02 3.0E+02 1.8E+02 9.7E+01 Initial Ground Shine 2.3E+01 1.1E+01 4.7E+00 0.0E+00 4-Day Ground Shine 7.4E+02 4.2E+02 2.5E+02 9.7E+01 CEDE Inhalation 3.8E+03 2.2E+03 1.3E+03 5.3E+02 I
NOTE: All values below 1.0E-03 have been set to zero.
O V
EPCI 94-04, Rev. O Page 45 af 62 ETA Summary of ST-DOSE inputs 08/02/94 12:59 {gg /
Straight-Line Plume I T %' \: EIP-ZZ-00212 BASES APPENDIX BB
'Piw_/ & Unit: CALLAWAY UNIT 1 Release Height: 0M Building Fake: Y Calculation Radius: 25 mi (40 km) event' date time Meteorological Data Shut Down 08/02/94 00:00 winds stb mix precip Rel-> Cont ~ 08/02/94 00:00 date time Rel->Envi 08/02/94 00:.00 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel'End .08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Containment Bypass (Event V)
Core Condition: IN-VESSEL SEVERE CORE DAMAGE (>30 min)
Reactor Power: 3411 Mw(t)
- Filters: UNFILTERED Leak Rate: 100%/ DAY Plume Model Maximum doses at selected distances (rem) f Distance (miles) .5 1.0 2.0 5.0 (km) .8 1.6 3.2 8.0
- Acute Bone Total 2.9E+01 1.7E+01 1.0E+01 5.0E+00 Total EDE (EPA) 2.0E+02 1.2E+02 7.0E+01 2.9E+01 Thyroid (epa) 3.0E+03 1.7E+03 1.0E+03 4.1E+02 Acute Lung 9.3E+01 5.4E+01 3.2E+01 1.3E+01 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 8.3E+00 4.8E+00 2.8E+00 1.1E+00 Cloud Shine 2.0E+01 1.2E+01 7.3E+00 3.9E+00 Initial Ground Shine 9.1E-01 4.6E-01 1.9E-01 0.0E+00 4-Day Ground Shine 2.9E+01 1.7E+01 9.9E+00 3.9E+00 CEDE Inhalation 1.5E+02 8.9E+01 S.2E+01 2.1E+01 l
NOTE: All values below 1.0E-03 have been set to zero.
U
EPCI-94-04. Rev. O i
Summary of ST-DOSE inputs 08/02/94 13:00 Page 46 cf )62[ fpf p ms j (
i 3: EIP-ZZ-00212 BASES APPENDIX CC Straight-Line Plume T(
Pit.. & Unit: CALLAWAY UNIT 1 Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data
,. Shut Down 08/02/94 00:00 winds stb mix precip Rel-> Cont 08/02/94 00:00 date time Rel->Envi 08/02/94 00:.00 1 08/02/94 00:00 90 8 MPH E 237 M NONE Re1 End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4 ;
I DSource Term: Plant Conditions l Containment Bypass (Event V) {
j Core Condition: IN-VESSEL SEVERE CORE DAMAGE (>30 min) l Reactor Power: 3411 Mw(t)
Filters: FILTERED Leak Rate: 100%/ DAY Plume Model '
Maximum doses at selected distances (rem) f Distance (miles) .5 1.0 2.0 5.0 (km) .8 1.6 3.2 8.0 1.6E+01 9.8E+00 6.0E+00 3.iE+00 t
0AcuteBoneTotal Total EDE (EPA) 2.4E+01 1.4E+01 8.6E+00 4.2E+00 Thyroid (EPA) 3.0E+01 1.7E+01 1.0E+01 4.1E+00 Acute Lung 1.0E+00 5.9E-01 3.SE-01 1.4E-01 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine l
Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation l
l Acute Bone Inhalation 2.6E-01 1.5E-01 9.0E-02 3.6E-02
- cloud Shine 1.6E+01 9.5E+00 5.9E+00 3.1E+00 Initial Ground Shine 2.9E-01 1.5E-01 6.0E-02 0.0E+00 4-Day Ground Saine 4.8E+00 2.8E+00 1.6E+00 6.1E-01 CEDE Inhalation 3.4E+00 1.9E+00 1.1E+00 4.6E-01 NOTE
- All values below 1.0E-03 have been set to zero.
l l
l' l
l l
. . j I
- .- - - _ _ _ - - _ --- - - - _ _ _ _ _ __ _ nl
EPCI-94 04, Rev. O Page 47 qQ2 l Summary of ST-DOSE inputs 08/02/94 13:01 ycg Straight-Line Pl ..te Ti' ): EIP-ZZ-00212 BASES APPENDIX DD
_PDd& Unit: CALLAWAY UNIT 1 1
Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data Shut Down 08/02/94 00:00 winds stb mix precip Rel-> Cont 08/02/94 00:00 date time Rel->Envi 08/02/94 00':.00 1 08/32/94 00:00 90 8 MPH E 237 M NONE Rel End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions
'- Containment Bypass (Event V)
Core Condition: GAP RELEASE (uncovered 15-30 min)
Reactor Power: 3411 Mw(t)
Filters: UNFILTERED Leak Rate: 100%/ HOUR Plume Model 7 Maximum doses at selected distances (rem)
Distance (miles) .5 1.0 2.0 5.0 (km) .8 1.6 3.2 8.0 I hAcute Bone Total 5.0E+01 2.9E+01 1.7E+01 8.3E+00 ks / Total EDE (EPA) 4.4E+02 2.5E+02 1.5E+02 6.1E+01 Thyroid (EPA) 9.7Et03 5.6E+03 3.3E+03 1.3E+03 Acute Lung 1.0E+02 5.8E+01 3.4E+01 1.4E+01 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 1.3E+01 7.3E+00 4.3E+00 1.7E+00 Cloud Shine 3.5E+01 2.1E+01 1.3Et01 6.7E+00 l Initial Ground Shine 2."E+00 1.3E+00 5.2E-01 0.0E+00 J 4-Day Ground Shine 5 E+01 3.0E+01 1.8E+01 6.8E+00 CEDE Inhalation 3.5E+02 2.0E+02 1.2E+02 4.8E+01 i NOTE: All values below 1.0E-03 have been set to zero.
i l
O
EPCI-94-04, Rev. 0 j
Summary of ST-DOSE inputs 08/02/94 13:02 Page 43 {p3of 62p] gg/
Ti' h* EIP-ZZ-00212 BASES APPENDIX EE Straight-Line Plume Pi d & Unit: CALLAWAY UNIT 1 Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data
. Shut Down 08/02/94 00:00 Rel-> Cont 08/02/94 00:00 date time winds stb mix precip Rel->Envi 08/02/94 00100 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 4
Source Term: Plant Conditions Containment Bypass (Event V)
Core Condition' ^^P RELEASE (uncovered 15-30 min)
Reactor Power: .,11 Mw(t)
Filters: UNFILTERED Leak Rate: 100%/ DAY Plume Model Maximum doses at selected distances (rem) f Distance (milss) .5 1.0 2.0 5.0 (km) .8 1.6 3.2 8.0 2.0E+00 1.2E+00 7.0E-01 3.3E-01
[# TAcute Bone Tatal 1.0E+01 6.0E+00 2.4E+00
(_s/ Total EDE (EPA) 1.7E+01 5.3E+01 Thyroid (EPA) 3.9E+02 2.2E+02 1.3E+02 Acute Lung 4.0E+00 2.3E+00 1.4E+00 5.5E-01 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 5.0E-01 2.9E-01 1.7E-01 6.9E-02 Cloud Shine 1.4E+00 8.3E-01 5.1E-01 2.7E-01 Initial Ground Shine 1.0E-01 5.1E-02 2.1E-02 0.0E+00 4-Day Ground Shine 2.1E+00 1.2E+00 7.0E-01 2.7E-01 CEDE Inhalation 1.4E+01 8.1E+00 4.8E+00 1.9E+00 NOTE: All values below 1.0E-03 have been set to zero.
EPCI.94-04, Rev. O i
LSummary of ST-DOSE inputs 08/02/94 13:03 Page 49 of 62( h. /
), ]g.
Til EIP-ZZ-00212 BASES APPENDIX FF Straight-Line Plume J Plb.- &' Unit: CALLAWAY UNIT 1 Release Height: 0M Building Wake: Y Calculation Radius: 25 mi (40 km) event date time Meteorological Data
. Shut Down 08/02/94 00:00 stb mix Rel-> Cont 08/02/94 00:00 date time winds precip Rel->Envi 08/02/94 00:00 1 08/02/94 00:00 90 8 MPH E 237 M NONE Rel End 08/02/94 01:00 2 Expos End 08/02/94 01:00 3 1
4 Source Term: Plant Conditions Containment Bypass (Event V)
Core Condition: CAP RELEASE (uncovered 15-30 min) ,
Reactor Power: 3411 Mw(t) -
Filters: FILTERED Leak Rate: 100%/ DAY Plume Model Maximum doses at celected distances (rem) f Distance (miles) .5 1.0 2.0 5.0 (km) .8 1.6 3.2 8.0 f, ' cute Bone Total 8.7E-01 5.2E-01 3.2E-01 1.7E-01 Total EDE (EPA) 1.3E+00 7.9E-01 4.8E-01 2.3E-01 Thyroid (EPA) 3.9E+00 2.3E+00 1.3E+00 5.3E-01 Acute Lung 4.5E-02 2.6E-02 1.5E-02 6.1E-03 Acute Bone Total = Acute Bone Inh. + Cloud Shine + Init. Ground Shine Total EDE = Cloud Shine + 4-Day Ground Shine + CEDE Inhalation Acute Bone Inhalation 1.5E-02 8.4E-03 5.0E-03 2.0E-03 Cloud Shine 8.4E-01 5.0E-01 3.1E-01 1.6E-01 Initial Ground Shine 1.6E-02 8.0E-03 3.3E-03 0.0E+00 4-Day Ground Shine 2.6E-01 1.5E-01 8.6E-02 3.3E-02 CEDE Inhalation 2.4E-01 1.4E-01 8.1E-02 3.2E-02 NOTE: All values below 1.0E-03 have been set to zero.
I 1
i
(
l i
i i;iu w ua,iio,o
- EC E " m
- j. A rT 2A.STA ^ DE WITH PHOTECTr/E ACTIOf45 VESSEL MEI!E-T11ROUC il WIT 11 CONTAh10NT REI. EASE EVACUATE 10 mHe I OF = effected sectors, and 5 mile radius.
- Yes 8"*Y VESSEL MELT THROUGH [ ma ment at e On rOU wMh reiease from containment / ?
/ (100%tv)
EVACUATE 10 mile O- effected Sectors, Snd -
5 mee radius.
1 EVACUATE 10 r* I OTF ;-
y effected sec!c r mM l 5 mile rad:t .
/ Containment Spray y
Purge Isolation Faiture O- On or OFF
( 100% / day) ?
EVACUATE 10 mite
- eMectM sehs, and i ON
~
No 5 mile radius.
EVACUATE 10 mile OFF O- effected sectors, and 5 mile radius.
Spray On or OFF
( 0.2% / day design leak rate ) ?
NO
- ^*"
- ON necessary.
s t x
I q..
6
\
- l!PCI.94-04. Rev. O ATT 28 -
A TREE WITH PROTECTNE ACTIONS p3ge $ g o -
SEVERE CORE DAM AGE WIT 11 CONTAIMtFNT RFl. EASE EVACUATE to mite gg w l effected sectors, and S mite rases. -l l
SEVERE CORE DAMAGE [ ,
,Yes / One OFF 7
j wth release from containment.[
~
EVACUAT E 10 mile
- ef fected sectors, and No ON 5 rru!e radius m-EVACUATE to mae OFF > etfected sectors, and
'/
5 mJe radius.
Containment ' Spray PurDe isotation Failure y,, ;jOn or OFF
( 100% / day) ?
EVACUATE 10 mHe No ON 5 mRe radius.
^ ^ **
OFF a ef fected sectors, and
' 2 mile radius.
Spray On cr OFF
( C 2*& / day dcWgnleak rate ) ?
NO Protectwe Actions g3 necessary. .,
s ~.
.l
,o A-c N1
---~- - _ _____ . _ _ _ _ _ _ _ . _ _
Elti-94-04, Itev, o Page 52 o FM ,
j ATT 20 . TRLE wtTH PROTECTNE ACTecus p .
C AP RE1, EASE WITII CONTAINMEN ItEl.E Ast; }
i l
EVACUATE 10 mae gg ; effected sectors, and 5 mde radius [
r
- pay
- GAP FIELE ASE [ ma P' #
t Faure
'Yes
= OnuOU c
~
with fetease from centainment , ?
/ (100%.hr) i
? '
EVACUATE to mde z effected sectors, and
,g gy S mile radies.
i EVACUATE to mt!e
! OU m- effected sectors, and i
t
\ 5 mile radius.
Containment Spray y,,
Purge Iso!abon Failure On or OFF
( 100% / day) ?
EVACUATE 10 mne
- - effected sectors, and ON 5 mile radius.
OVY z Protective Actions necessary.
Spray
- On or OFF
( 0.2*& / day design lenk rate ) ?
NO
= Protective Ac* ions ,
necessary. ,
s W
w m.
EPCI 94-04, Rev. O Page 53 of 62 ATT 2D. STATUS TREE WTW PROTECTIVE ACTIONS _.
'$ (If
( STEAM GENERATOR TUBE RUPTURE Ag' I
EVACUATE 10 mile No
- ef'ected sectors. and 5 me!e radius.
STEAM GENERATOR [ Yes FILTERED CORE OA AGE RELEASE TUBE RUPTURE
/ 7 7
a EVACUATE to rnile No : cffected sectors, and ye3 5 mHe radius.
EVACUATE 10 mile No
> effected sectors, and
'[
5 mile radius.
GAP FILTERED f
l RELEASE :-
RELEASE 7
7
! EVACUATE 10 mie No effected sectors, and y,3 f' ] 5 mile radius.
j A
NO No
> Protective Actions necessary.
100 TIMES NORMAL FILTEREO COOLANT Yes RELEASE 7 7 N NO
- Protective Actions No Yes necessary.
NO No > Protective Actions necessary.
FILTERED AE NORhtAL COOLANT ACTIVITY NO e- Protectrve Actions g y,3 necessary.
4
{
'u t
ATT 2E STATUS TREE WITH PROTECTNE ACTIONS EPCI-94-04, Rev. O Page 54 of 62 CONTAITO1ENT BYPASS EVENT I
4 4
'b/ EVACUATE 10 mde etfected sectors, and 5 rrate radius.
No FLO EVACUATE 10 mile 100% 10AY : effected sectors, and Y** 5 male radius.
?
a No VERE FILTERED CONTAINMENT / Yes
^ ^ RELEASE BYPASS EVENT / 7 No EVACUATE to mile lYa : effected sectors, and 5 mde racus.
f f EVACUATE 10 mde kj >
l effected sectors, and 5 mde radius.
No FLO EVACUATE 10 mde yg ICO% / OAY > effected sectors, and
? 5 mde radius.
1 l No O#
Yes = FILTEREO SE RELEASE
?
" Protect Actions No necessary, 1
NOT ANAL.YZED.
Values wou!d be less than gap activdy.
NO PROTECTNE ACTIONS NECESSARY.
O V
~ ATT 3A COSOLIDATED GENERIC STATUS TREE EPCf.94 04, Rev. O Page 55 of 62 O START as a GENERAL Protective actions are not EMERGENCY
- - necessary. Continue to
,N evaluate EALs ed
?
Yes t
Go to Vessel ESSEL
"" =
Melt Through MELT - THROUGH r 7 (Page 2)
I No u / to
/ Severe *" SEVERE Core Damage -
CORE DAMAGE 7 (Page 3)
Upgrade PARS '
as appr opriate.
N a
1
\ I Yes Gap Go to
- " = GAP RELEASE i Release is (Page 4) l
?
he projecte , !
= g, f>ase1at Remany locatio TEDE or N
i
\ > 5 Rem No Thyroid ? ,
Recommend 6 mile shelter a in effected sectors and Y" 2 mile radius.
a I
" A No :
a Dose Calc been :
( om page 2,3,4 )
O performed
?
PAGE 1
EPCI-94-04, Rev. O i ATT 30 -COsCLIDATED GENERIC STATUS TREE Page 56 of 62
> &' 9{l6(ty O VESSEL MELT
\\
THROUGH
( from page 1)
I i '(
SGTR or EVACUATE 10 mile Containment
- - effected sectors, and Bypass 5 mile radius.
nt?
No o
Catastrophiv Yes
< Containment Failure -
i or CPIS?
O No Return to A
1.
'i Challeng Yes ~
[ to Containment rrt /,-
integ/y?
s l No l l
Containment OFF
- Sprays ON /OFF ON Recommend 5 mile shelter
- - in effected sectors and 2 mile radius. f PAGE 2 t
l
EPCI-94 04, Rev. O ATT 3C COSOUDATED GENERIC STATUS TREE Page 57 of 62
@89/Ty
' i SEVERE CORE DAMAGE
( from page 1)
~
f l
/ SGTR or EVACUATE 10 mile es effected sectors, and Containment Bypass 7 5 mile radius.
nt?
No 9
Catastrophici Yes Containment Failure =
.jp;r Wa or CPIS?
No Return to
(' > A on page 1.
a
/ hallenge Yes
<' to Contaiament integnty?
No I
Recommend Containment OFF ,
5 mile Evacuation , /
Sprays ON /OF in effected sectors and
? 2 mile radius.
I ON ]
I F Recommend 5 mile shelter (
- in effected sectors and 2 mile radius.
i U j PAGE 3 .
t
)
l EPCI 94-04, Rey, o 5 ATT 3D .COSOUDATED GENERIC ST ATUS TREE Page 58 of 62 l
k i GAP RELEASE
( from page 1) i i
EVACUATE 10 mile
- :- effected sectors, and SGTR 7 5 mile radius, No i-l l ,
1 Catastrophic Yes "
r
! Containment Failure i or CPIS7
-No r .i Challenge Return to I y. -- A to Containment >
integnty?
cn page 1.
j 1
No a 1
a
! Unfiltered J
/
a .
Containment Yes Filtered Bypass Release
" Event? - ?
No Filtered 4
e T
Recommend 5 mile shelter I -
- in effected sectors and 2 mile radius.
- O PAGE 4
l ATT 4A - CONSOLIDATED SITE SPECIFIC STATUS TREE EPCI-94-04, Rev. 0 Pags 59 of 62 l
@I9/lb[9Y O *m1. Cordacaene H2 >6%
M.
CHARMS
- 16 4 RN ( 4 E +5 R,hr sprays on )
START Wie 2 Conterwert H2 = 2%
Wa CHARMS a 30.0C0 R / hr ( 10.000 R I rr sresys on )
4 Core ed twmoccupws = 2 000 aegrees F
- te 3 CHARMS a 300 RIN (100R/hrer<aysen) a-Me i rw envy rneernants for FRc 1 Has a Protective acti are EMERG CY - No Continue to eva!uate EALs a
de ared l 7 Yes y
On initial Nctification, a Recommend 5 mile shelter in effected sectors and a 2 mile radius.
(Jpgrade PARS as appropria[e.
n
-> SUBSEQUENT PARS For short duration releases
( <2 hrs ), recommend she!!ering b for areas that cannot be evacuated prior to plume arrival.
1 d
Yes Go to vessei Yes VESSEL
- T" isN he projecte
( n te $" MELT - THROUGH
( Page 2 )
dose at any location No
> 5 Rem Thyroid ? y 1
a a Go to Severe Yes SEVERE Yes Core Darnage ? =
{ ne 2 CORE DAMAGE
/ -
Has 3 a Dose Cale been pedormed
? 4 No
( Page 3 )
r
- ca \y,, Go to l Release 7 = GAP RELEASE Upgrade Recommendation to
( n te 3 ) [page 4)
Evacuation S mile af'ected r sectors and a 2 mile radius No No
/
o ecunty Even A N Y"' "
s ) ( croup 3 0 ) 7=
= ( from page Nd odicator 1 or 2,3,4 )
?
PAGE 1 . ,,
EPCI 94 04, Rev, O ATT 48 - CONSOLIDATED SITE SPECIFIC STATUS TREE Page 60 of 62
, ( Q 'titc(fy
(-)/
's_- VESSEL MELT THROUGH
( from page 1) r 4
roup 2 EAL
_CLT.LEamethn. Recommend 10 mile indicator 3 for a SGTR Yes EVACUATATION in Con 7 nIent bypass a affected sectors, and event? a 5 mile radius.
No 4
y Group 2 EAL CmLDattit loss indicator la Yes for Catastrephic fatlure >
or indicator 2 for a CPIS failure Return to No A
y on page 1.
Group 2 EAL GotEamet yes Potential Loss W Indicators 4016 No V
containment OFF
" prays ON /OFF 7
l ON Recommend 5 mite shelter fC) > in affected sectors and
- Q a 2 mile radius.
PAGE 2 ,
,-w -
-u . . - - - - - - - _ - - - . - - _
1 EPCI-94-04. Rev. 0 ATT 4C - CONSOLIDATED SITE SPECIFIC STATUS TREE Page 61 of 62 N A b
i SEVERE CORE DAMAGE
( from page 1) 1 I
Group 2 EAL
_C!mL.Barr,er less Recommend 10 mile indicator 3 for a SGTR Yes EVACUATION in
'" A affected sectors, and ContNe'n'tbyp s event? a 5 mife radius.
No y Group 2 EA)
CimL.Brtitt loss indicator ta Yes for Catastrophic failure >
orindicator 2 for a CPIS failure 3 '
(M N
No Return to A
on page 1.
Group 2 EAL CLT1Bamet Yes ~
Potential loss Indicators 4 or 5 No Recommend containmNent prays ON /OFF
.OFF ,
5 mile Evacuation in affected sectors and 7 a 2 mile radius.
ON Recommend 5 mile shelter
> in affected sectors and a 2 mile radius.
q PAGE 3 , ,
p&
i K, & ,@p q IMAGE EVAL.U ATION ,t %
x, c ' --
0;fik TEST TARGET (MT-3)
/ f),Ilf^pg
\)7p////
~
$/ 9 }'W k"; tf
+ %
l.0 .
~j'lim
~
1.1 E'
l.8
==
1.25 1.4 1 1.6
. . _ _ . . _ _ . _ _ _ . _ . - 150mm >
4._
_ _ _ _ . _ . . . _ _ _ _ . - 6" - >
4 ef ,,,!.
O Q, v
/
.h
1
? .,?
,$ a)
- b IMAGE EV AI.U ATION
///// /
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' ATT 4D - CONSOLIDATED SITE SPECIFIC STATUS TREE ( ?Cl-94-04, RIv. 0
. l Page 62 of 62 l
GAP RELEASE i
( from page 1) y U
Group 2 EAL Recommend it- :e~
Ctmt. Bamnf Yes =
EVACUATIO .n cator3 :
15s{n[g 3 affected sectors, and a 5 mile radius.
/ No V
y Group 2 EAL Gknt. Bamer loss indicator ia p Yes for Catastrophic failuro >
or indicator 2 for a CPIS failure?
l No Return to A
Y cn page 1.
roup 2 EAL ctmt eamer Yes Potential Loss -
Indicators 7
4 or 57 No
}
V No l
pamt. Barrier yes
^"#"*'
a g Emergency loss Indicator 1b for a y Exhaust filter train (
Containment bypass perating event? 7 Yes No
'~x, Recommend 5 mile shelter
- - in effected sectors and -
t l
' ' - a 2 mile radius.
PAGE 4 ., ,