ML023540437
| ML023540437 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/18/2002 |
| From: | Colburn T NRC/NRR/DLPM/LPD1 |
| To: | Richard Laufer NRC/NRR/DLPM/LPD1 |
| References | |
| TAC MB6300, TAC MB6301 | |
| Download: ML023540437 (18) | |
Text
I P Document Control Desk PLA-5567 DRAFT U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP 1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION (RAI) FOR REQUEST FOR ADDITIONAL INFORMATION Docket Nos. 50-387 EMERGENCY PLAN (E-PLAN) REVISIONS and 50-388 PLA-5567 Document ControlDesk, "Proposed
Reference:
Emergency Plan Revision Requiring NRC Approvat",
Information (RAI)
- 2) Letter. NRC to B.L. Shriver (PPL), "Requestfor Additional & 2) - Emergency Plan (E I and 2 (SSES I SusquehannaSteam Electric Station, Units
"',dated November 25, 2002.
Plan)Revisions (TA C Nos. MA6300 and MB63 01) information necessary for the NRC The purpose of this letter is to provide supplemental proposed in Reference 1.
staff to complete its review of the emergency plan revision NRC Request for Additional Attachment I to this letter contains responses to the documents referenced in the Information (Reference 2), and supplemental support the Emergency Plan previously responses. Attachment 2 contains new pages for submitted (Reference 1).
Note to reviewers:
implementation. This will be In the cover letter we'will include a paragraph on week.
based on the results of a telecon with the NRC next Sincerely, B. L. Shriver Attachments:
Additional Information Attachment 1 - Response to the NRC's Request for Attachment
Document Control Desk PLA-5567 DRAFT the Emergency Attachment 2 - Updated pages to Proposed Revision to Plan Attachment 3 - Dose Assessment Unit of Instruction copy: NRC Region I Mr. D. J. Allard, PA DEP Mr. T. G. Colbum, NRC Sr. Project Manager Mr. S. Hansell, NRC Sr. Resident Inspector Mr. R. Janati, DEP/BRP
Attachment 1 to PLA-5567 Response to NRC's Request for Additional Information
Attachment 1 to PLA-5567 Page 1 of 7 DRAFT Attachment I - Response to RAI Susquehanna Emergency Action Level (EAL) Review Questions NRC EAL Ouestion 1 Have the EAL changes been reviewed and agreed to with State and local governmental authorities in accordance with Title 10 of the Code ofFederalRegulations, (10 CFR),
Part 50, Appendix E,Section IV.B, "Assessment Actions"?
PPL Response:
Yes, the EAL changes have been reviewed and agreed to by the Commonwealth of Pennsylvania (Pennsylvania Emergency Management Agency and Department of Environmental Protection - Bureau of Radiation Protection), the Luzerne County Emergency Management Agency and the Columbia County Department of Public Safety.
NRC EAL Ouestion 2 What are the units and scale of the Vent Monitors used in EAL 15?
PPL Response:
Each of the five plant vents are monitored by an Eberline Model FAAM (Fixed Airborne Activity Monitor). The FAAM's analyze representative samples via isokinetic probes that are in compliance with ANSI 13.1-1969. Each FAAM has three noble gas detectors that provide overlapping ranges of 1 x 10.7 tCi/cc to 1 x 10+5 g.Ci/cc for Xe-133 gas.
The plant effluent noble gas data is continuously monitored and stored in solid state memory. The flow through the sample line is also measured and stored in solid state memory. The FAAM then calculates and stores activity per unit of volume. This information can be displayed upon request and is periodically printed out for record keeping purposes. This information is displayed and recorded on control room back panel OC630. This information is also displayed on OC677 in the TSC.
High activity alarms for all five vent stacks are annunciated on control room panel OC653. The microprocessor converts the monitor output to units of gCi/min based on the measured vent stack flow rates.
Attachment 1 to PLA-5567 Page 2 of 7 DRAFT NRCEAL uestion 3 EAL 15 for Dose assessment the In the Site Area Emergency and General Emergency for a child instead of an adult. Is this thyroid Combined Dose Estimate is identified as intentional?
PPL Response:
of adult thyroid dose conversion While the EPA PAG guidance provides for the use the use of child thyroid CDE.
factors, the Commonwealth of Pennsylvania requires NRC EAL Question 4 with EPA-400 and refers to the Code.
Page 7-4 indicates that the dose program complies adult physiology is assumed. Is your Referencing EPA-400, Appendix B, it indicates that and how does that impact the dose assessment based on child or adult physiology previous question?
PPL Response:
adult physiology per EPA-400, except for The accident dose assessments are based on the are used in calculating thyroid one case - that is, child thyroid dose conversion factors (adult) dose factors provided in EPA CDE. Calculations of TEDE are made using the to section 7.1.1.3 (replacement pages 400. To capture this answer we added information included in Attachment 2).
NRC EAL Ouestion is run from the Technical Support Page 7-4 indicates that the dose calculation program (EOF). What is used for dose Center (TSC) and Emergency Operations Facility E-plan?
assessment On-shift and where is it described in the PPL Response:
Emergency Director is responsible for The Emergency Plan Section 7.1.1 states "The activities. These activities are initiating off-site dose calculation and assessment who report to the Operations Support performed by health physics trained personnel Event)." The dose calculation Center (OSC) (or the Control Room for an Unusual Section 7.1.1.3 goes on to note "the methodology is described in E Plan Section 7.1.1.3.
running on PC's located in the TSC dose calculation program is a stand alone program to the Emergency Director to and EOF" In summary, the HP technicians report are, they proceed up one flight of determine if dose projections are necessary. If they The TSC is located one floor above our stairs to the TSC and perform those calculations.
Control Room.
Attachment 1 to PLA-5567 Page 3 of 7 DRAFT Susquehanna Staffing Questions NRC Staffing Question 1 Control of The staff requests clarification of the terms used in Section 6, "Organizational Emergencies," of the proposed emergency plan contained in the letter dated on-shift September 6, 2002, to assist with understanding the process for augmenting staffing following the declaration of an Alert or above emergency classification.
it is stated that "the Example terms include: On page 6-2 of the proposed E-plan revision 30 to 60 minutes."
[Operations Support Center] OSC and TSC are fully functional within possible...". In On the same page it is stated that "the TSC will be activated as soon as time for the alternate the same sentence it is stated".... it is recognized that the activation following a TSC...". On page 6-3 it is stated that "The EOF is required to be activated management of Site Area Emergency or General Emergency classification and take over of the the emergency from the TSC...". On the same page it is stated that "Activation Emergency Operations Facility requires the minimum..."
- a. Provide E-plan references where the following terms are defined: "activated",
"activation", "activation time", "take over management of the emergency", and response "fully functional." The response should include a discussion of personnel respective in sequence of response from when they are notified to report to their to perform emergency response facility to the point when all personnel expected respective emergency response functions are ready to perform their functions their in facility.
- b. Discuss the point from which "fully functional" time goal is measured.
PPL Response:
in Table 6.1 and
- a. "Fully functional" means that all minimum required staff as defined "activation" the "shaded" positions in Figures 6.2 and 6.3 are present. "Activated",
sufficient and "take over management of the emergency" all mean that the facility has and staffing to perform required functions and the facility as taken over command an
- in control of the emergency. The positions required to activate are specified with 1.0 Figures 6.2 and 6.3.The terms clarified above have been added to Section Definitions (replacement pages included in Attachment 2).
6-2 Phase II
- b. The goal is measured from the time of notification as described on page Phase III for the TSC and from the time of event declaration as described on page 6-3 is to for the EOF. One of the first steps in the Control Room Communicator procedure activate NERO. This would occur within one to two minutes of event declaration.
Attachment 1 to PLA-5567 Page 4 of 7 DRAFT NRC StaftinE Question 2 times for augmentation personnel, As part of the justification of extending the response expectation that personnel provide documentation that describes the management to their respective emergency assigned emergency response functions are to respond response locations as soon as possible without delay.
PPL Response:
were communicated in a letter to all The Emergency Response Organization expectations expectations is a requirement for on members on November 8, 2001. Included in these an unscheduled 22222 pager call personnel to immediately report upon receiving expectations are proceduralized activation (indicating a requirement to respond). These in NDAP-QA-0014.
NRC Staffine Ouestion 3 who are designated to handle the Discuss the training provided for the on-shift personnel the 30-minute Senior Health Physics offsite dose assessment function to compensate for "Criteria for Preparation and Expertise position described in Table B-I in NUREG-0654, Plans and Preparedness in Support of Evaluation of Radiological Emergency Response Nuclear Power Plants."
PPL Response:
- 1. Emergency Plan Overview Training copy provided in attachment 3))
- 2. Dose Calculator Training (annual retraining required, retraining required)
- 3. On-Site Radiation Monitoring Team Training (annual retraining required)
- 4. Contaminated Injury - Ambulance Training (annual retraining required)
- 5. Contaminated Injury - Hospital Training (annual required)
- 6. In-Plant Team Management Training (annual retraining NRC Staffline Question 4 Protection functions of Explain which on-shift personnel will perform the Radiation and dosimetry issue. Table access control, health physics coverage, personnel monitoring be performed by two on-shift B-1 in NUREG-0654 notes that these functions may personnel who may be assigned other functions.
PPL Response:
Attachment 1 to PLA-5567 Page 5 of 7 DRAFT Access control and dosimetry issue are performed automatically via the Radiation Protection module of our Nuclear Information Management System (NIMS). The two on-shift health physics technicians fulfill health physics coverage requirements.
NRC Staffing Ouestion 5 Discuss shift operating crew performance related to handling emergency preparedness scenarios for 60 minutes without TSC and OSC assistance. In general terms, discuss any deficiencies related to emergency classification, required notifications, or protective action recommendations that may have been caused by or contributed by the lack of on shift staffing.
PPL Response:
In reviewing past drill data as well as lessons learned from recent emergency plan activations, performance overall has been satisfactory. One area for improvement that was noted was communications with the NRC during the initial stages of an event.
Accordingly we are proposing in this response to add a new position for this function.
We will call this position "NRC Communicator" and structure it similar to the NRC Communicator function in the TSC. The qualification for the position of NRC Communicator is that the individual holds or has held a NRC license or STA certification at SSES or other BWR facility or has been certified at SSES or other BWR facility. In lieu of license or certification, the individual has sufficient BWR operating experience as determined by the Manager-Nuclear Operations to facilitate accurate communication with the NRC. Such individuals may be Reactor Engineers, Simulator instructors or individuals from the operations staff. In summary the individual must have sufficient understanding of Control Room operations that they can provide information concerning critical plant parameters, resources available to deal with the event, procedures in use, and priorities and actions minimize the consequences of the event.
NRC Staffing Question 6 Discuss the compensation provided for the repair and corrective actions tasks to be performed by the Mechanical Maintenance/Rad Waste Operator and the Electrical Maintenance Instrument and Control Technician as specified as 60-minute responders in Table B-1 or NUREG-0654.
PPL Response:
In our proposed revision to the Emergency Plan, we proposed the use of five non licensed operators (NLOs). Two are used to fulfill the Fire Brigade responsibilities and three NLOs are used for safe shutdown and plant response. In this response, we are proposing the addition of another NLO. Having six NLOs provides sufficient flexibility
Attachment I to PLA-5567 Page 6 of 7 DRAFT until additional support such that corrective actions can be fulfilled by NLOs on-shift fuses, manipulating valves, arrives. Such activities include racking breakers, changing This number of NLOs is the number moving equipment, and starting equipment locally.
to Table 6.1 to list the in our current Emergency Plan. A footnote will be added activities.
added two positions over that proposed Note: In our response to questions 5 & 6 we have of on-shift individuals in our in Reference 2. These additions increase the total number is included in Attachment 2.
proposed Emergency Plan to 15. A revised Table 6.1 NRC Staffing Ou estion 7_
Support Center, Technical At what emergency classification level are the Operational Support Center and Emergency Operations Facility activated?
PPL Response:
Center are activated at the Alert. The Operational Support Center and Technical Support and activated at the Site Area Emergency Operations Facility is staffed at the Alert Emergency.
NRC Staffing Question 8 staffing the emergency response Describe the notification and call-out processes for facilities.
PPL Response:
Room initiates pager activation via a When an Alert classification is declared, the Control go off typically less than 1 minute single pushbutton in the control room. The pagers immediately to their assigned after the button is pushed. On-call personnel respond Security who activates an automated facility. As a backup, the Control Room contacts NERO personnel not on-call but fit for call-out system. The system sends a second page.
time, call in. The first person to call in duty and at a location within the required response facility. As a result more than for each position is expected to respond to their assigned activation. If no one calls in within one person for each position will respond to the pager automatically calls the people
'10 minutes for a given NERO position, then the system their cell phone). After the assigned to the position (work phone, home phone, and/or or retained to help as facilities are fully functional, extra personnel will be released personnel are scheduled for conditions dictate. If the emergency continues, additional within the TSC, MOC, and EOF.
subsequent shifts via various administrative functions
Attachment I to PLA-5567 Page 7 of 7 DRAFT for NERO personnel, there are provisions to In addition to the processes described above technicians as needed. Management call out maintenance workers and health physics individuals respond as outlined above.
personnel from these areas are on-call and these personnel as needed.
These individuals arrange for call-out of additional
Attachment 2 to PLA-5567 Updated Pages to Proposed Revision to the Emergency Plan
I '1.0 DEFINITIONS in an 1.1 ACCIDENT - an unforeseen and unintentional event which may result emergency.
staffing to perform 1.2 ACTIVATE -an emergency response facility has sufficient and control of the required functions and the facility as taken over command TSC and EOF are specified emergency. The positions required to activate the "activation" and "take with an
- in Figures 6.2 and 6.3. The terms "activated",
definition.
over management of the emergency" have the same 1.3 ALERT - an Emergency Condition.
1 and ending 1.4 ANNUAL - occurring within calendar year starting January December 31.
or after an incident to 1.5 ASSESSMENT ACT"IONS - those actions taken during make decisions to implement obtain and process information that is necessary to specific emergency measures.
on alternate years, to be 1.5 BIENNIAL EXERCISE - NRC/FEMA exercise performed completed within the calendar year scheduled.
7-day week.
1.6 BIWEEKLY - occurring on alternate weeks, with the organ due to an intake of 1.7 CDE - the Committed Dose Equivalent; dose to an the intake.
radioactive material during the 50 year period following (CCDPS') - emergency 1.8 COLUMBIA COUNTY DEPARTMENT OF PUBLIC SAFETY responsible for implementing response coordinating agency for Columbia County, SES or PEMA.
off-site action upon direct notification from Susquehanna from which the reactor and 1.9 CONTROL ROOM - the location of the Control Panels its auxiliary systems are controlled.
PPL Management group which 1.10 CORPORATE LEADERSHIP COUNCIL (CLCI - the The CLC membership determines major policy commitments for the company.
senior executives.
includes the President of the company and other taken to ameliorate or 1.11 CORRECTIVE ACTIONS - those emergency measures terminate an emergency situation.
OF RADIATION 1.12 DEPARTMENT OF ENVIRONMENTAL PROTECTION/BUREAU to provide guidance and PROTECTION (DEP/BRP) - the State agency responsible recommendations for specific off-site protective measures.
Rev. 39, 04/02 1-1
ob t- n -T dose to 1.13 DOSE PROJECTIOI N a calculated estimate of the potential radiation (determined from the quantity of individuals at a given location, normally off-site, meteorological transport and radioactive material released and the appropriate dispersion parameters).
individual can potentially receive per 1.14 DOSE RATE - the amount of radiation an unit of time.
of the products of the dose 1.15 EFFECTIVE DOSE EOUIVAQENT (EDE* - the sum factors applicable to each of equivalent to the organ or tissue and the weighting the body organs or tissues that are irradiated.
1.16 EMERGENCY' ACTION LEVELS ('EAL) - operational or radiological parameters of portions of this plan. EALs which, when exceeded, require the implementation Table 5.1.
for various emergency conditions are specified in a result of exceeding an 1.17 EMERGENCY ACTIONS - those steps taken, as to ensure that the situation is Emergency Action Level in the Emergency Plan, protective actions are taken.
assessed and that the proper corrective and/or television broadcast system used 1.18 EMERGENCY ALERT SYSTEM (EAS) - radio and the public concerning by public emergency management officials to notify of natural disasters, radiological protective actions to be taken in the eventof immediate impact to the public.
protective actions, and other information Broadcast System.
Formerly referred to as the Civil Defense Emergency of several classes of emergency 1.19 EMERGENCY CONDTION - the characterization the entire spectrum of situations consisting of exclusive groupings including The four classes of emergencies, possible radiological emergency situations: incorporated into this Emergency listed in increasing severity, which PPL has Plan, are outlined in Section 5.0 of this plan.
SES staff members 1.20 EMERGENCY COORDINATORS - designated Susquehanna organization functions.
responsible for coordinating specific emergency for direction of on-site 1.21 EMERGENCY DIRECTOR - the PPL individual responsible SES.
activities during an emergency at the Susquehanna SES and General Office 1.22 EMERGENCY MANAGERS - designated Susquehanna emergency organization Personnel who are responsible for managing specific functions.
and county emergency 1.23 EMERGENCY OPERATIONS CENTERS - designated State and equipped for the management agency headquarters facilities, designed Rev. 39, 04/02 1-2
r) a- A 5'T control over disaster operations purpose of exercising effective coordination and carried out within their jurisdiction.
Response Facility co 1.24 EMERGENCY OPERATIONS FACILITY - PPL Emergency Pennsylvania, to located with the Media Operation Center in Plains Township, of PPL activities during an provide continuous coordination and evaluation consequences (Reference emergency having or potentially having environmental REFERENCES, Section 3.18).
1.25 EMERGENCY PLAN BOUNDARY - same as the Exclusion Area, i.e., that area feet determined in accordance around Susquehanna SES within a radius of 1800 with 10CFR100.11. (See Figure 8.1.).
- specific procedures defining 1.26 EMERGENCY PLAN IMPLEMENTING PROCEDURES emergency condition. The in detail the action to be taken in the event of an separate from, but may Emergency Plan Implementing Procedures will be and instructions and incorporate and refer to, normal plant operating procedures Emergency Plan Position Specific Procedures.
Planning Zones. The 1.27 EMERGENCY plANNING ZONE - there are two Emergency around the Susquehanna first is an area, approximately ten (10) miles in radius the plume exposure SES, for which emergency planning consideration of and effective actions can pathway has been given in order to ensure that prompt The second is an area be taken to protect the public in the event of an accident.
SES, for which approximately 50 miles in radius around the Susquehanna pathway has been emergency planning consideration of the ingestion exposure given.
- instructions describing 1.28 EMERGENCY PLAN POSITDON SPECIFIC PROCEDURES Each instruction includes how to perform tasks assigned to emergency positions.
and relevant material.
an overview of the position's tasks, detailed instructions, the Emergency Plan Used together, these instructions are designed to implement during a declared emergency.
within a radius of 1,800 1.29 EXCLUSION AREA - that area around Susquehanna SES 10CFR100.11.
feet (see Figure 8.1) determined in accordance with within the context of 1.30 FEDERAL EMERGENCY MANAGEMENT AGENCY (FEMAM -
Federal assistance; lead this plan, serves as the primary contact for requests for coordinator all non-technical federal response.
Table 6.1 and the j 1.31 FULLY FUNCTIONAL- all minimum required staff as defined in "shaded" positions in Figures 6.2 and 6.3 are present.
1.31 GENERAL EMERGENCY - an Emergency Condition.
Rev. 39, 04/02 1-3
Page 1 Table 6.1 STATION EMERGENCY PLAN MINIMUM STAFFING REQUIREMENTS I Capablifty for Additions
- . I r, ic.n I flnhfi flmin I go miri Major Functional Area I Major Tasks r- 01 , 3- . ............. ......
Plant Operations and Assessment Unit Supervisor (SRO) 1 of Operational Aspects 3 Plant Control Operators 4
Non-Licensed Operators EmrI c Drco ____4 1ý I Emergency Direction and Control Emergency Director (Emergency Director) Communicators 1 21 1
'Notification/Communicationl Notify licensee, State, Local, and EOF Support Supervisor I Federal personnel & maintain communication NRC communicator I II 1 4 1 t Emergency Operations Facility (EOF) Recovery Manager Radiological Accident Assessment and Support of Operational Director ----------------------
I.
Radiation Protection Accident Assessment Radiation Protection & Dose Coordinator 1 Assessment Dose Assessment Supervisor -- 1 1 2 Rad Assessment Staff . ..
2# 2 S............ eam)-----uvI Qffit(iedSuves qr Team .. ...... ......
Personnel . . 2........
.2.#.------------....
siteo .pt.( .)..... .Team Personnel -
Radiation Protection & Dose 3 3 Assessment: HP Technicians 2
-4
- a. Access Control
- b. HP coverage for repair, corrective actions, search and rescue, first aid, & firefighting tC
- c. Personnel Monitoring
- d. Dosimetry
- e. Dose Assessment
- f. In-Plant Surveys 1 --
Chemist r/Radiochem lsty Chemistry Technicians 1 location may be the OSC, TSC, or EOF.
Note: The Capability for Additions column refers to reporting times. Reporting
'7-
- Rad monitoring team personnel (see Figure 6.3) - 2 are dispatched from the vicinity of the plant at 60 minutes.
functions. These individuals may also fulill other respons~bihties
- Indicates the minimum number of individuals onshilft with the capabilities of performing these identified in this table.
Proposed NRC Rev. 5-02
Table 6.1 (cont'd) Page 2 Capability for Additions
.Major Functional Area Major Tasks Pasition ritle or Expertse On Shift 60 min 90 min Plant System Engineering Technical Support Shift Technical Advisor I ....
Operations Coordinator -
Core/Thermal Hydraulics -- ! -
Electrical -- -
Mechanical 1 -
Technical Support Coordinator - 1 Severe Accident Management Coordinator I Engineering Support Supervisor Repair and Corrective Actions Management of Damage Control Teams Damage Control Team Coordinator -- 1 -
OSC Coordinator -- 1 Com muncaons with !n_-planTeým_* T.C Radi Communcato... - I _
Repair and Corrective Actions Mechanical Maintenance/ 1* t -
(onshift requirements may be fulfilled by Rad Waste Operator NLOs) Electrical Maintenance/ l1 Instrument and Control Technician Firefighting .. Fire Brigade Local per Technical Support Requirements Manual Rescue Operations and First Aid -- 2* Local Support Site Access Control and Security, firefighting Security Personnel All per Personnel Accountability communications, personnel Security plan
._. accountability Security Coordinator -- 1 --
15 24 14 plus fire brigade and security plan required personnel Note: The Capability for Additions column refers to reporting times. Reporting location may be the OSC, TSC, or EOF.
- Rad monitoring team personnel (see Figure 6.3) - 2 are dispatched from the vicinity of the plant at 6D minutes.
- Indicates the minimum number of individuals onshift with the capabilrties of performing these functions. These Individuals may also fulfill other responsibilirtes identified in this table.
- Fulfilled by NLOs on-shift to provide inibal damage control repair activities until additional support arrives. Such activities include racking breakers, changing fuses, manipulating valves, moving equipment, and starting equipment locally.
I Proposed NRC Rev. 5-02
DP_ A FT7 and sigma theta at the 33-foot level.
The tower measures wind speed, wind direction, point temperature at a height of The tower also measures temperature and devw from this tower is used only approximately 6.6 feet. The meteorological data collected is an accidental release to support assessment and restoration efforts inthe event there of radioactive material from SSES.
continuous data to the control The meteorological systems are instrumented to provide (PICSY) for utilization in the TSC and room and the Plant Integrated Computer System various display formats and is also EOF. Data that enters PICSY is viewable through are present at all of the SSES transmitted to the NRC via ERDS. Digital dataloggers available for acquisition by and is meteorological towers. All data is stored locally and backup tower strip chart recorders interrogation across telephone lines. Primary are located in the control room.
dose assessment purposes can Site specific, meteorological information for emergency Meteorologist or the National be obtained by contacting either the SSES Contract provided in the SSES Emergency Weather Service Station using the phone numbers Telephone Directory.
7.1.1.2 Health Physics Considerations reactor building vents, In the event of an unplanned radioactive release from either the vent; continuous gross noble the turbine building vents, or the standby gas treatment Each monitor is also equipped with gas readings are available from the vent monitors.
These in-line samples are periodically in-line iodine and particulate sampling capability.
particulate release rate removed and analyzed in order to provide iodine and information.
into account: selection of the The following Health Physics considerations are taken mix and average gamma energies of accident type to closely approximate the isotopic of reactor shutdown, plume decay the release occurring, radioactive decay from time precipitation.
in-transit and iodine and particulate depletion due to 7.1.1.3 Dose Calculations for Airborne Releases specific estimates and predictions A dose calculation model is used to make current, site and immediately following an of atmospheric effluent transport and diffusion during of the prediction is to provide an accidental airborne radioactivity release. The purpose radioactive releases to the input to the assessment of the consequences of accidental response decisions.
atmosphere and to aid in the implementation of emergency time-dependent, variable trajectory The dose calculation model used is a fast running, plume segment "B" model with the following capabilities:
the actual spatial and NOTE: A class "B" model is a numerical model that represents temporal variations of plume distribution.
Proposed NRC Rev. 5-02 7-3
Q0A --T on atmospheric stability Computes atmospheric dispersion at the site based 15-minute upgrades of as a function of site specific terrain conditions with source term and meteorological conditions.
of radioactivity
- Provides estimates of deposition and relative concentration the duration of the release.
within the plume exposure and ingestion EPZs for deposition which enables dose
- Incorporated in the calculations is wet and dry shine, and ingestion.
estimates from three pathways - plume, ground Action Guides and Protective The dose program complies with the "Manual of Protective calculation methodology in the dose Actions for Nuclear Incidents," (EPA-400), adopting based on the adult physiology per ICRP #26/30. The accident dose assessments are dose conversion factors are used in EPA-400, except for one case - that is, child thyroid made using the (adult) dose factors calculating thyroid CDE. Calculations of TEDE are are available:
provided in EPA-400. The following calculational options doses consisting of the sum
- TEDE (Total Effective Dose Equivalent) integrated effective dose of external doses from plume shine, 50 year committed shine doses.
equivalent from inhalation (CEDE), and 4 day ground
- EDE and CDE dose rates for field team management.
of radioactive
- Fifty year thyroid committed dose (CDE), from inhalation materials.
- Population dose (person rem) out to 50 miles.
projection times.
- Summary print of projected doses for each of four by the user.
- Integrated ground dose for projected times specified running on PCs located in the The dose calculation program is a stand alone program TSC and EOF.
7.1.1.4 Liquid Release Calculations are made by employing effluent Estimates of downstream river water concentrations flow rates and river elevation sample analysis or discharge monitor data, discharge travel time to the point of interest.
readings. The river elevation is used to estimate the monitor data and the The calculated degree of mixing, together with the discharge discharge flow rates are used to calculate downstream concentrations.
Proposed NRC Rev. 5-02 7-4