ML20052H542
| ML20052H542 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/09/1982 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20052H527 | List: |
| References | |
| PROC-820409-01, NUDOCS 8205210189 | |
| Download: ML20052H542 (88) | |
Text
BSEP PLANT OPERATING RtNUAL VOLLME XIII, BOOK 2 PLANT EMERGENCY PROCEDURES (PEP) i 8205210189 820513 PDR ADOCK 05000324 F
PDR j
1 PLANT OPERATING MANUAL VOLUME 13, BOOK 2 TABLE OF CONTENTS PLANT EMERGENCY PROCEDURES (PEP)
Rev.
1.0 PLANT EMERGENCY PROCEDURES INTRODUCTION 3
l 1.1 Manual Purpose and Use 1.2 Emergency Response Organization 2.0 EMERGENCY CLASSIFICATIONS AND CONTROL PROCEDURES 2.1 Initial Emergency Actions 4
2.2 Emergency Control - Unusual Event 2
2.3 Emergency Control - Alert 2
2.4 Emergency Control - Site Emergency,
2 2.5 Emergency Control - General Emergency 2
2.6 Emergency Management Guides 2.6.1 Plant Operations Director 1
2.6.2 Emergency Repair Director 1
2.6.3 Logistics Support Director 2
2.6.4 Radiological Control Director 2
2.6.5 Representative to the State Emergency Response Team 1
2.6.6 Environmental Monitoring Team Leader 2
l l
2.6.7 Plant Monitoring Team Leader 1
l 2.6.8 Personnel Protection and Decontamination Team Leader 1
2.6.9 Fire Brigade Leader 2
2.6.10 Emergency Security Team Leader 1
2.6.11 Damage Control Team Leader 1
2.6.12 Operational Support Center / Evacuation Assembly Area Leader 2
2.6.13 Site Public Information Coordinator 1
2.6.14 Site Systems Communications Coordinator 1
2.6.15 Support Services Coordinator 1
2.6.16 Emergency Response Manager 1
2.6.17 Administrative and Logistics Manager 1
2.6.18 Technical Analysis Manager 1
2.6.19 Radiological Control Manager 1
2.6.20 Dose Proje-tion Coordinator 0
l Rev. 4
Rev.
3.0 EMERGENCY ACTION PROCEDURES 3.1 Communications Procedures 3.1.1 Tollow-up Notification and Communications 2
3.1.2 Communications Activities 1
3.1.3 Use of Communications Equipment 1
3.2 Augmentation and hobilization Procedures 1
3.2.1 Notification of Off-duty Personnel 1
3.2.2 Mobilization of Outside Agencies 1
3.3 Plant Monitoring Procedures 3.3.1 In plant Monitoring and Surveys 1
3.3.2 On-site Monitoring and Surveys 2
3.3.3 Collection of Very High Level Samples 2
3.3.4 Analysis of Very High Level Samples 1
3.4 Radiological Consequences 3.4.1 Initial Dose Projections 3
3.4.2 Whole Body Dose Projections 3
l 3.4.3 Thyroid Dose Projections 3
3.4.4 (Reserved) 3.4.5 Automation of Dose Projection Procedures 1
l 3.4.6 (Reserved) 3.5 Environmental Monitoring Procedures 3.5.1 Confirmation of Initial Off-Site Dose Projections 2
3.5.2 Expanded Environmental Monitoring 1
3.5.3 Plume Tracking by Actual Measurement 1
3.5.4 Coordination with State Monitoring 1
3.6 Source Term Assessments and Estimates of Core Damage 3.6.1 Release Estimates Based Upon Stack / Vent Readings 1
3.6.2 (Reserved) 3.6.3 Interpretation of Liquid and Gaseous Samples 1
3.6.4 Consequences of Leakage and Spills 1 Rev. 4
i Rev.
3.7 Radiation Control Procedures 3.7.1 Radiation Work Permits and Exposure Control 2
3.7.2 Emergency Personnel Monitoring and Dosimetry 2
3.7.3 Issuance and Use of Protective Gear 1
3.8 Protective Action Procedures 3.8.1 Evacuation 2
3.8.2 Personnel Accountability 2
3.8.3 Administration of Radioprotective Drugs 2
3.8.4 Access Control 1
3.9 Aid to Affected Personnel 3.9.1 (Reserved) 3.9.2 First Aid and Medical Care 1
3.9.3 Transporting of Contaminated Injured Personnel 1
3.9.4 (Reserved) l 3.9.5 Personnel Decontamination 1
3.9.6 Search and Rescue 1
4.0 SUPPLEMENTAL PROCEDURES 4.1 Record Keeping and Documentation 3
4.2 Emergency Facilities and Equipment 2
4.3 Performance of Training, Exercises and Drills 3
4.4 (Reserved) 4.5 Public Education and Information 2
APPENDIX A A.1 BSEP Personnel 3
l A.2 Federal, State and County Agencies 1
A.3 Fire and Medical Assistance 2
A.4 Other Emergency Response Contacts 2
APPENDIX B (Reserved) Rev. 4
File No.
Unit No.
QtRETcd App'l CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIT NOS. 1 & 2 PLANT EMERGENCY PROCEDURES INTRODUCTION PLANT EMERGENCY PROCEDURE PEP-1.0 VOLUME XIII Rev. 3 I y A
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PEP-1.0 PLANT EMERGENCY PROCEDURES INTRODUCTION l
1.1 Manual Purpose and Use l
The purpose of this manual _is to implement the emergency actions described in the Radiological Emergency Plan for the Brunswick Steam Electric Plant (BSEP) and provide the BSEP staff and supporting agencies with specific instructions, forms and data to ensure prompt actions, proper notifications, and effective communications during potential and actual emergency conditions.
It also denotes the means by which emergency preparedness is maintained by periodic training, exercises, and' equipment inventories and checks.
During and_ subsequent to an emergency, this manual will provide a record of the actions completed in fulfillment of established emergency response requirements.
The Plant Emergency Procedures Manual is organized to facilitate immediate use by both on-site and off-site emergency response personnel. The basic contents of sections are shown on EXHIBIT 1.1-1, USE OF THE PEP MANUAL.
Section 1 is the Introduction and Emergency Organization. This section describes the proper use of the manual and the organization of the key emergency response personnel.
Sections 2 and 3 are the action sections to be implemented during the emergency or potential emergency. Section 2 consists of step-by-step immediate action procedures, and the classification scheme used by plant personnel in reporting potential emergency events, evaluating their extent, classifying them as an Unusual Event, Alert, Site Emergency, General Emergency or as an event of lesser safety significance, and controlling the situation. Also included are management guides for key personnel.
Section 3 contains the specific procedures required to monitor, control and mitigate the consequences of classified emergencies. This section provides step-by-step instructions to direct specific personnel activities l
during an emergency.
[
Section 4 of this manual includes t).e supplemental procedures required to assure the appropriate emergency personnel and equipment are prepared for the onset of emergency conditions.
Appendix A lists emergency response resources and their suggested channels
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for access in emergency communications.
Appendix B contains reference i
materials and forms anticipated to be required to fulfill requirements of the specific procedures.
(
i The controlled copies of this manual are indexed with color-coded tabs to i
facilitate use in emergencies.
I Red Tabs precede portions of the manual which may be required for i
immediate action, or approximately within the first hour after an event is reported to the Control Room.
i BSEP FEP-1.0 Rev. 3
Yellow Tabs denote the Key Personnel Emergency Management Guides.
These guides are used to assure that appropriate actions are addressed by responsible, qualified personnel and that the status of actions may be properly maintained.
Blue Tabs precede those PEPS normally used by emergency response members subsequent to the initial classification of an emergency.
White Tabs preface those sections which provide reference information or emergency preparedness data.
EXHIBITS are numbered according to the procedure in which they are located.
The EXHIBIT number uses the PEP number followed by an assigned integer.
EXHIBITS are located at the end of the respective PEPS in numerical order according to the assigned integer.
Example: The first three EXHIBITS of PEP 3.4.4 are located at the end of that PEP and are numbered as follows:
3.4.4-1, 3.4.4-2, 3.4.4-3.
For informational blanks and checkoffs, the use of "N. A."
for items not available or not applicable is permitted.
BSEP PEP-1.0 Rev. 3
EXHIBIT 1.1-1 USE OF THE PEP MANUAL SECTION 1.0 MANUAL PURPOSE AND USE; EMERGENCY ORGANIZATION SECTION 2.0 EMERGENCY CONTROL AND MANAGEMENT; ItefEDIATE ACTIONS TO EVALUATE EVENT AND CLASSIFY SECTION 3.0 EMERGENCY ACTIONS TO CONTROL, MITIGATE AND TERMINATE AN EMERGENCY SECTION 4.0 ACTIVITIES TO ASSURE EMERGENCY PREPAREDNESS APPENDIX A EMERGENCY RESPONSE RESOURCES APPENDIX B EXTRA MAPS, EXHIBITS AND FORMS BSEP PEP-1.0
~ Rev. 3
1.2 Emergency Response Organization The Emergency Response Organization has been defined to quickly and effectively bring an emergency condition under control.
The organi-zation is compatible with and integrated into the normal mode of operation.
The position of Site Emergency Coordinator will be activated upon declaration of any emergency level from an Unusual Event to General Emergency.
Dependent upon the level of the emergency, other members of the emergency organization will be activated as needed.
EXHIBIT 1.2-1 shows the Emergency Response Organization for BSEP.
Each position in the Emergency Response Organization has been assigned primary, alternate, and interim personnel to function in that position, as indi-cated in EXHIBIT 1.2-2.
The organization consists of the Site Emergency Coordinator with the Technical Support Group reporting to him. This Group consists of a Plant Operations Director, an Emergency Repair Director, a Logistics Suppott Director and a Radiological Control Director. Each of these positions directs one or more teams. The Site Emergency Coordi-nator is the primary interface with the Emergency Response Manager, who interfaces with off-site organizations and individuals, including the Corporate Emergency Operations Center, the Site Public Information Coordi-nator, the Corporate Spokesman, the State Emergency Response Team (SERT)
Headquarters, and other state and federal agencies. Upon activation of the Emergency Operations Facility (EOF), off-site dose assessment and off-site environmental monitoring responsibilities shift from the Site Emergency Coordinator to the Emergency Response Manager. The EOF organi-zation under the direction of the Emergency Response Manager consists of the Technical Analysis Manager, the Radiological Control Manager, Adminis-tration & Logistics Manager, and their supporting staff.
Current phone numbers are maintained in controlled copies of this Manual j
in the Technical Support Center, Operational Support Center, and the Control Room.
Outside support agencies, and the means of contacting each, are also listed in PEP-Appendix A.
BSEP PEP-1.0 Rev. 3
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EXHIBIT 1.2-2 EMERGENCY RESPONSE ORGANIZATION 1.
Site Emergency Coordinator:
Plant General Manager Alternates:
Manager - Plant Operations Manager - Operations Manager - Environmental and Radiation Control Manager - Maintenance Manager - Technical Support Interim:
Shift Operating Supervisor Alternate Interim:
Shift Foreman 2.
Plant Operations Director:
Manager - Operations Alternates:
Manager - Plant Operations Shift Operating Supervisor Interim:
Site Emergency Coordinator 2.a. Plant Operators Leader:
Shift Operating Supervisor l
Alternate:
Shift Foreman or Senior Control Operator l
Interim:
Shift Foreman of Affected Unit 2.b. Accident Assessment Team Leader:
Engineering Supervisor Alternate:
Project Engineer - NSSS Interim:
Site Emergency Coordinator 2.c. Fire Brigade Leader:
Shift Foreman Alternate:
Plant Fire Chief Interim:
Fire Brigade Member BSEP PEP-1.0 Rev. 3
EXHIBIT 1.2-2 EMERGENCY RESPONSE ORGANIZATION (cont.)
3.
Emergency Repair Director:
Manager - Maintenance Alternates:
Mechanical Maintenance Supervisor Electrical Maintenance Supervisor Interim:
Site Emergency Coordinator 3.a. Damage Control Team:
Leader Mechanical Maintenance Supervisor Electrical Maintenance Supervisor The leaders and members of this team will be selected by the Site Emergency Coordinator and/or Emergency Repair Director according to the nature of the task.
3.b. Operaticaal Support Center Leader:
Senior Specialist - Electrical I
4 Logistics Support Director:
Manager - Technical Support Alternates:
Administrative Supervisor Interim:
Site Emergency Coordinator 4.a. Site Communications Systems Coordinator: Technical Aide I (Engineering)
This individual will be designated by the Site Emergency Coordinator when the emergency communications system is activated.
4.b. Support Services Coordinator: Stores Foreman This individual will be designated by the Site Emergency Coordinator to interface with the Administration & Logistics Manager in the Emergency Operations Facility (EOF) when activated. Prior to EOF activation, this individual will interface with the Corporate Operations Coordinator in the Corporate Emergency Operations Facility if corporate support services are required.
4.c. Emergency Security Team:
Leader:
Security Specialist Alternates:
Chief of Security Interim:
Senior Security Person on duty BSEP PEP-1.0 Rev. 3
EXHIBIT 1.2-2 EMERGENCY RESPONSE ORGANIZATION (cont.)
4.d. Evacuation Assembly Area Leader Leader:
Cost Control Specialist Alternate:
Environmental & Chemistry Technician 5.
Radiological Control Director: Manager - Environmental and Radiation Control (E&RC)
Alternates:
Supervisor - Radiation Control Supervisor - Environmental and Chemistry Project Specialist -
Radiation Control Interim:
Site Emergency Coordinator
- 5. s. Environmental Monitoring Team:
Leader:
Supervisor - Environmental and Chemistry Alternate:
Foreman - Environmental and Chemistry Interim:
Radiological Control Director 5.b. Plant Monitoring Team:
Leader:
Project Specialist - Environmental and Chemistry Alternates:
Specialist - Chemistry Specialist - ALARA Interim:
Radiological Control Eirector 5.c. Personnel Protection and Decontamination Team:
Leader:
Supervisor - Radiation Control Alternates:
Foreman - Radiation Control Specialist - Radiation Control Interim:
Radiological Control Director BSEP PEP-1.0 Rev. 3
t EXHIBIT 1.2-2 EMERGENCY RESPONSE ORGANIZATION (cont.)
5.d. Dose Projection Coordinator:
Project Specialist - Radiation Control Alte rnate:
Specialist - Radiation Control Interim:
Radiological Cantrol Director 6.
Emergency Communicator:
Regulatory Compliance - Senior Specialist Alternate:
Regulatory Compliance Specialist Interim:
Available Plant Operator 7.
Representative to State Emergency Response Team Headquarters:
Assistant to the Plant General Manager Alternate:
Emergency Preparedness. Specialist 8.
Site Public Information Coordinator:
Manager - News Services Alternates:
Vice President - Corporate Communications Director - Media Relations Interim:
Plant General Manager or his designee 9.
Emergency Response Manager:
Vice President - Nuclear Operations Alternate:
Manager - Corporate Quality Assurance 10.
Administrative & Logistics Manager:
Manager - Construction Procurement Services Alternate:
Assistant to the Group Executive -
Power Supply 11.
Technical Analysis Manager:
Director - Nuclear Engineering Safety Review Alternate:
Principal Specialist - Special Projects Nuclear Operations Administration BSEP PEP-1.0 Rev. 3
EXHIBIT 1.2-2 EMERGENCY RESPONSE ORGANIZATION (cont.)
12.
Radiological Control Manager:
Manager - Environmental and Radiation Control, HE&EC Alternate:
Principal Specialist - Environmental, HE&EC 13.
Corporate Emergency Operations Center Manager:
Senior Vice President - Power Supply Alternates:
Executive Vice President -
Power Supply and Engineering and Construction 14.
Corporate Spokesman:
Vice President - Nuclear Safety and Research or his designae Alternate:
Vice President - Technical Services 1
BSEP PEP-1.0 Rev. 3 i
t-Q File No.
~
Unit No.
Q+RETcd App'l CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIT NOS. 1 & 2 ENVIRONMENTAL MONITORING TEAM LEADER PLANT EMERGENCY PROCEDURE PEP-2.6.6 VOLUME XIII Rev. 2
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PEP-2.6.6 ENVIRONMENTAL MONITORING TEAM LEADER
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1.0 Responsibilities and Objectives The Environmental Monitpring Team Leader is responsible to the Radiological Control Director for providing technical and administrative direction to the-Environmental Monitoring Team during a declared emergency. Once the Emergency Operations Facility is. activated, the Favironmental Monitoring Team Leader will be~ responsible to the Radiological Control Manager in the Emergency Operations Facility.
2.0 Scope and Applicability This procedure shall be implemented upon activation of the Environmental Monitoring Team. The actions and responsibilities are limited to the Environmental Monitoring' Team Leader and those emergency team members assigned to him.
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3.0 Actions and Limitations 3.1 General Requirements-3.1.1 Report your position and readiness to the Radiological Control Director (the Radiological Control Manager after the Emergeccy Operations Facility is activated).
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3.1.2 Announce your name and assumed posit _ian ettle to all team members.
3.1.3 Ensure that all personnel actively assigned to you'(i.e.,
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not off site or in the Operational Supp, ort Center) are accounted for at all times (see PEP-3.8.2, " Personnel Accountability" for initial. accountability requirements).
3.1.4~
Determine need for additional equipment, supplies and manpower and pake request for same.
3.1.5 A.
When assuming the Environmental Monitoring Team
/
leader position, request a briefing on the, eoergency and emergency actions status from the previous position holder.
B.
When relinquishing the Environmental _ Monitoring Team Leader position, brief your successor on the emergency and, emer gency, actions status.
C.
Nc-tify all appropriate personnel of your name, the
- position you are assuming,s and i_e name of the person you replage.
3.1.6 Ensure documentation of 'he following:
t Communications
. Key decisions'-
r.
BSEPrPEP-2.6.6
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Data collected
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Checklists (in accordance with PEP-4.1, " Record Keeping and Documentation").
3.1.7 Ensure proper use of communications equipment (per PEP-3.1.3, "Use of Communications Equipment").
3.1.8 Ensure exposure control is in accordance with PEP-3.7.1,
" Radiation Work Permits and Exposure Control," (i.e, i
Radiation Work Permits shall be completed).
3.2 Assign personnel to perform Environmental Monitoring procedures as directed by the Radiological Control Director (the Radiological Control Manager after the Emergency Operations Facility is activated).
Priorities for assignments will depend on plant conditions; the following order for priority of assignments is provided as a guide:
3.2.1 Dose confirmation (PEP-3.5.1, " Confirmation of Initial Off-Site Dose Projections").
3.2.2 Off-site monitoring (PEPS-3.5.2, " Expanded Environmental Monitoring," -3.5.3, " Plume Tracking by Active Measurement,"
and -3.5.4, " Coordination with State Monitoring").
3.2.3 Other missions as required (interface with Personnel Protection and Decontamination Team Leader and Plant
)
Monitoring Team Leader).
3.3 Guidelines for Monitoring Missions (per PEP Section 3.5) 3.3.1 Advise team members of expected radiological conditions and protective gear to be worn.
3.3.2 Upon discussion with the Radiological Control Director, (the Radiological Control Manager after Emergency Operations Facility activation) provide recommended locations for initial environmental surveys to the Environmental Monitoring Team. These should be determined based upon prevailing wind directions and locations or roads in that direction. The objective is to take measurements at locations close to the distances assumed in the initial dose projection (4000 feet).
3.3.3 Record location of Monitoring Teams on environmental maps.
3.3.4 Advise the Environmental Monitoring Team whenever it 3
appears that the wind direction has shifted more than 45 during the period when the Environmental Monitoring Team i'
is performing surveys.
3.3.5 Provide the results of initial environmental surveys to i1 }
the Dose Projection Coordinator.
BSEP PEP-2.6.6 Rev. 2
3.3.6 Advise the Radiological Control Director (the
]
Radiological Control Manager af ter Emergency Operations Facility activation) of the results of the comparisons of initial survey readings and dose projections.
3.4 Guidelines for Expanded Environmental Monitoring (per PEP-3.5.2) 3.4.1 Direct the Environmental Monitoring Team to replace existing TLD's, beginning with the TLD's downwind of the plume.
3.4.2 Direct the placement of additional TLD's approximately every 10 meters along the exclusion area fence in the sector within plus or minus 22.5 of the plume centerline (a total sampling area of 45 ).
3.4.3 Direct the initiation of the expanded environmental monitoring program based on the release conditions (e.g., water, and benthic organisms, etc. for liquid releases; grass and milk samples where radioiodine has been released).
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BSEP PEP-2.6.6 Rev. 2
File No.
Unit No.
Q+RETed App'1 CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT LWIT 0 DOSE PROJECTION COORDINATOR PLANT EMERGENCY PROCEDURE:
PEP-02.6.20 VOLL"fE XIII Rev 000 1
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1.0 Responsibilities and Objectives The Dose Projection Coordinator is responsible to the Radiological Control Director for projecting doses off site during a declared emergency. After activation of the Emergency Operations Facility, the Dose Projection Coordinator will provide meteorological data and source term information to EOF personnel.
2.0 Scope and Aeolicability This procedure shall be implemented upon activation of the Dose Projection Team. The actions and responsibilities are limited to the Dose Projection Team Leader and those team members assigned to him.
3.0 Actions and Limitations 3.1 General Requirements:
3.1.1 Report your position and readiness to the Radiological Control Director.
3.1.2 Announce your name and assumed position title to all team members.
3.1.3 Ensure that all personnel actively assigned to you are accounted for at all times.
(See PEP-03.8.2, Personnel Accountability, for initial accountability requirements.)
3.1.4 Determine and procure equipment, supplies and manpower necessary for use by the Dose Projection Team.
3.1.5 A.
When assuming the Dose Projection Team Leader position, request a briefing on the emergency and emergency actions status from the previous position holder.
B.
When relinquishing the Dose Projection Team Leader position, brief your successor on the emergency and emergency actions status.
C.
Notify all appropriate personnel of your name, the position you are assuming, and the name of the person l
you replace.
BSEP/Vol. XIII/ PEP-02.6.20 1
Rev. O
J 3.1.6 Ensure documentation of the following:
Communications Key decisions Data collected Data transmitted (In accordance with PEP-04.1, Record Keeping and Documentation) 3.1.7 Ensure proper use of communications equipment (in accordance with PEP-03.1.3, Use of Communications Equipment).
3.2 Assign personnel to perform dose projection and source term procedures as directed by the Radiological Control Director.
3.3 If the plant computers are not accessible, determine meteorological data in accordance with Exhibit 2.6.20-1, Manual Met Tower Data Acquisition.
3.4 If the on-site meterological station is completely inoperable, National Weather Service data can be used to obtain an estimate of the on-site wind speed and direction, and the appropriate atmospheric stability class.
(Refer to Exhibit 2.6.20-3 for steps to follow.)
3.5 Periodically call Licensing and Permits Section in Raleigh and request meteorological forecast data.
(PEP Appendix A.4 for phone numbers.) Make use of Exhibits 2.6.20-4 and 2.6.20-5 for recording forecast and other meteorological data.
3.6 Use Exhibit 2.6.20-6 to detail wind direction in terms of degrees from north versus sector wind is blowing from and sector wind is blowing to.
3.7 Record source term data on Exhibit 2.6.20-7 and transmit to EOF if activated.
3.8 Ingestion dose projection procedures are contained in the Harris Environmental and Energy Centers Emergency Procedures should they be needed before activation of the EOF. Copies of HEEC Emergency Procedures are available in the TSC.
BSEP/Vol. XIII/ PEP-02.6.20 2
Rev. O
Exhibit 2.6.20-1 Manual Met Tower Data Acquisition 1.0 If the CRT, modem circuit, or telephone system for contacting the met tower is out of service, the data is obtained as follows (if unavailable from process compater):
a.
Obtain key from ELRC (No. 20) or Security to allow access to the Meteorological Building, located at the base of the tower, northwest of the site.
b.
On the shelf in the building, locate the manual pulse counter. This unit should be plugged into a 110 VAC outlet for recharging the internal batteries.
The unit has a stop/ start switch and a position 1/ position 2 switch.
c.
It has a black lead and white lead.
d.
Unplug manual pulse counter.
Open the left-hend cabinet on the right wall of the building.
e.
f.
Inside this cabinet you will observe several black jacks and one white jack.
g.
Each black jack is labeled as to what parameter is involved.
h.
Plug the white lead into the white jack und the black lead into the parameter whose pulses are needed.
j.
Reset counter to zero.
k.
Place switch into position 2.
Observe time, place stop/ start to start.
m.
At the end of 90 seconds, turn stop/ start to stop.
n.
Record number of pulses and multiply number by 10.
This will scale c.
up the pulses to equal 15 minute values.
p.
Proceed to obtain the of:her parameters.
q.
Record readings on Exhibit 2.6.20-2.
Record the wind direc: ion and wind speed from the recorders on the r.
data form.
s.
Turn switch to stop and plug counter into 110 VAC.
BSEP/Vol. XIII/ PEP-02.6.20 3
Rev. 0
i Exhibit 2.6.20-1 (Cont'd) t.
Secure all cabinets, lock building, and return keys to E&RC/ Security.
Perform the E&RC tabletop computer program to convert the pulses to u.
usable parameters as normal.
Compare the wind parameters to the values from q above to see if l
v.
they are reasonable.
2.0 If the calculator is out of service but the pulses can be obtained either automatically or by hand, proceed as follows:
CONVERSION OF PULSES TO ENGINEERNG UNITS WIND SPEED (MPH) = WIND SPEED PULSES + 15 WIND DIRECTION: A = (SIN PULSES - 750)
B = (C0S PULSES - 750)
APPARENT ANGLE = ARCTAN OF ABSOLLTE VALUE OF A/B A
B WIND DIRECTION (DEGREES FROM NORTH)
+
+
APPARENT ANGLE 180 - APPARENT ANGLE 180 + APPARENT ANGLE
+
360 - APPARENT ANGLE AMBIEhT *EMPERATURE (*F) = (TEMP PULSES X 0.12) + ZA ZA = SITE SPECIFIC ZERO ADJUST FACTOR
- DIFFEREhTIAL TEMPERATURE (*F) = (DT PULSES + 60) + ZA ZA = SYSTEM SPECIFIC ZERO ADJUST FACTOR
- ANSWER IN DEGREES F MULTIPLIED BY SITE SPECIFIC NORMALIZING FACTOR (0.5976)
CONVERTS UNITS TO "C/100 METERS.
- NOTE:
THE MOST RECENT ZERO ADJUST FACTORS ARE USUALLY POSTED IN THE MET TOWER BUILDING.
IF CURRENT FACTORS ARE UNAVAILABLE, ASSLNE ZA FOR AMBIENT TEMP = -50 AND ZA FOR DELTA T = -10.
BSEP/Vol. XIII/ PEP-02.6.20 4
Rev. 0 l
Exhibit 2.6.20-1 (Cont'd)
STABILITY CLASS DIITERENTIAL TEMPERATURE AT A
<.-l.9 ( C/100m)
B
-1.9 to -1,7 C
-1.7 to -1.5 D
-1.5 to -0.5 E
-0.5 to +1.5 F
+1.5 to +4.0 G
> +4,0 1
l BSEP/Vol. XIII/ PEP-02.6.20 5
Rev. O
Exhibit 2.6.20-2 MANUAL PCLSE COUNTS
.i DATE TIME PARAMETER PULSES /90 See WSU X 10 =
WSU WDU SIN X 10 =
WDU SIN WDU COS X 10 =
WDU COS WSL X 10 =
WSL WDL SIN X 10 =
WDL SIN WDL COS X 10 =
WDL COS AMB Temp X 10 =
AMB Temp DT 1 X 10 =
DT 1 DT 2 X 10 =
DT 2 Wind speed upper from recorder (avg) mph Wind direction upper from record (avg) degrees Wind speed lower from recorder (avg) mph Wind direction lower from record (avg) degrees 5
BSEP/Vol. XIII/ PEP-02.6.20 6
Rev. O
Exhibit 2.6.20-3 Determining Stability Class from National Weather Service Data 1.
Call the National Weather Service office at Wilmington, North Carolina, for the current weathe'r observations. Obtain the following information from the meteorological forecaster who is on duty:
a.
Station for which data is given b.
Wind speed (kncts) c.
Cloud cover (in tenths of total) d.
Cloud ceiling (feet above ground) e.
Wind direction (N, S, E, etc.)
2.
Load the programmed cassette (the same cassette used in the Automated Dose Projection Procedure, PEP-03.4.5) into the HP9830A, enter LOAD 3 EXECUTE, and enter RUN EXECLTE.
NOTE:
Press the EXECUTE button after each entry into the computer to allow the program to proceed.
3.
The display will read WIND SPEED (knots). The program is asking for the wind speed in knots for the NWS observation station. Enter the appropriate response (example.. 1.0, 3.0, 0.0 for a calm wind).
4.
The display will read CLOUD COVER (tenths). The program is asking for the total cloud cover of the sky in tenths. That is, if the sky is overcast, 10/10ths would be to enter 10.
If the sky was clear, the appropriate response to the computer would be to enter 0.
Enter the appropriate response.
S.
The display will read CLOUD CEILING (feet). The program is asking for the height of the -most obscure cloud deck above the ground level. Enter the appropriate response (example.. 1000.).
For no cloud ceiling enter 99,999 feet.
6.
The display will read JULIAN DATE. The program is asking for the current JULIAN DATE, that is, the number of calendar days since the first of the calendar year. Enter the appropriate response.
7.
The display will read CURRENT TIME (24-hour clock). The program is asking for the current time (eastern standard time) in the common 24-hour clock (that is, noon = 1200 and midnight = 0000; all other times are
)
reported such as 1:00 p.m. = 1300). Enter the appropriate response.
BSEP/Vol. XIII/ PEP-02.6.20 7
Rev. O
Exhibit 2.6.20-3 (Cont'd) 8.
The computer program will now compute the appropriate atmospheric stability class, based upon the weather observations entered into the computer. The output will be displayed on the visual screen as follows:
Wind speed = (number) mph Atmospheric stability class = (letter)
NOTE:
The letter for the atmospheric stability class will be the pasquill stability indicator.
9.
Obtain and record wind direction and speed on Exhibit 3.4.2-1 or 3.4.3-1.
Use the correct atmospheric stability class in the dose calculations.
I 4
y BSEP/Vol. XIII/ PEP-02.6.20 8
Rev. O
Exhibit 2,.6.20-7 Cp&L Carolina Power & Light Company METEO R O L O GIC A L FORECAST FORM Date:
Time Issued:
Issued By:
Received By:
Forecast Location:
i A) Next 1 Hour
- 1) Wind Direction:
Sector Deg.
- 2) Winds Should Remain (Steady; Shif ting; Variable) 2a) Variation Should Be Deg.
- 3) Wind Velocity:
to (MPH)
- 4) Stability Class
- 5) Precipitation Activity Will Be (None, Scattered, Steady)
- 6) Precipitation Type (Rain, Rainshowers, Thunderstor=s, Ice, Snow)
- 7) Precipitation Intensity (Light, Moderate, Severe)
B) Next 3 Hours:
C) Remarks:
i BSEP/Vol. XIII/ PEP-02.6.20 9
Rev. O I
Exhibit 2.6.20-5 Carolina Power & Light Company ONSITE METEOROLOGI C A L DATA Date:
Time (
)
Upper Speed (mph) (m/s)
/
/
/
/
Upper Direc. (DEG)
Lower Speed (mph) (m/s)
/
/
/
/
Lower Direc. (DEG)
AMB Temp. ( F) bT ( C/100m)
Stability Class Time (
)
Upper Speed (mph) (m/s)
/
/
/
/
Upper Direc. (DEC)
Lower Speed (mph) (m/s)
/
/
[
[
Lower Direc. (DEG)
AMB Temp. ( F) bT ( C/100m)
Stability Class BSEP/Vol. XIII/ PEP-02.6.20 10 Rev. 0 0
.m._
Exhibit 2.6.20-6 WIND DIRECTIONS WIND FROM -
EEGREES FROM NORTH WIND TOWARD s
N 349-11 S
NNE 12-33 SSW NE 34-56 SW ENE 57-78 WSW E
79-101 W
ESE 102-123 WNW SE 124-146 NW SSE 147-168 NNW S
169-191 N
SSW 192-213 NNE SW 214-236 NE WSW 237-258 ENE W
259-281 E
WNW 282-303 ESE NW 304-326 SE NNW 327-348 SSE BSEP/Vol. XIII/ PEP-02.6.20 11 Rev. O
Exhibit 2.6.20-7
. SOURCE TERM D / T4.
DATE:
TIME:
ElFVATED RELEASE on GROUND LEVEL REL ALARMING MONITOR:
MONITOR INDICATION:
FLOW RATE (scru):
OTHER:
~
O h
SOURCE TERM =
ci/sec BSEP/Vol. XIII/ PEP-02.6.20 12 Rev. 0
.c a,,
_)
File No.
Unit No.
Q+RT.Ted App'l CAROLINA PO4L~t & LIGHT CC19 ANT BRUN5'4ICK STEAM M CTRIC PLANT l
UNIT NOS. 1 & 2 WOLE BODY DOSE PROJECTIONS PLANT E2ERGENCY PROCEDURE PEP-3. 4. 2 VOLUME IIII J
Rev.
3 o
4 g -
aO g.
6 k
Recon::nended By:
/
q
. Date:
Approved By:
/[gA p3 e7 /IT k[4 Date M/4[fi,-
~
f Plant general m age
)
PEP - 3.4.2 WHOLE BODY DOSE PROJECTIONS 1.0 Responsible Individuals and Objectives The Radiological Control Director or the Dose Projection Coordinator is responsible for calculating Whole Body Dose projections to be used by the Radiological Control Director and the Site Emergency Coordinator in
-determining and evaluating possible off-site consequences from a release of airborne radioactivity. The Radiological Control Manager shall assume responsibility for calculating off-site wbole body dose projections (to be used by the Emergency Response Manager) after the Emergency Operations Facility is activated.
2.0 Scope and Applicability This procedure is intended to be used for all manual calculations of whole body dose subsequent to that in PEP-3.4.1, " Initial Dose Projections."
It is intended to provide realistic assessment of doses at any point in the Emergency Planning Zone (EPZ). This procedure shall be performed periodically as directed by the Radiological Control Director, (Radiological Control Manager after the Emergency Operations Facility is activated).
j These projections pertain to the radioactive gases at ground level and do not include radiations from an overhead cloud that may contribute to the i
I whole body dose at ground level.
Provisions are included for:
1)
Determining the Atmospheric Dispersion Factor (X/Q) at any point downwind in the Plume Exposure Planning Zone based on the Atmospheric Stability Class, wind speed, and the distance to that point from the point of release.
2)
Correcting the dose to account for the time after shutdown that the source data is taken when using an assumed mix of noble gases.
3)
Correcting for distance away from the centerline of the cloud.
4)
Calculating the dose conversion factor for a known nuclide mix of noble gases.
5)
Manually constructing dose isopleths.
3.0 Actions 3.1 List of Exhibits:
3.4.2-1 Whole Body Dose Projections Worksheet 3.4.2-2 Determination of Dose Conversion Factor Worksheet 3.4.2-3 Gamma Whole Body Dose Conversion Factors and Decay Constants of Noble Gases 3.4.2-4 Xy/QwithDistanceforElevatedReleases l
3.4.2-5 Xu/Q with Distance for Ground Level Releases BSEP PEP-3.4.2 Rev. 3
. _~
F I
3.4.2-6 Horizontal Dispersion Coefficient as a Function of Downwind Distance from the Source
]
3.4.2-7' Vertical Dispersion Coefficient as a Function of Downwind 1
Distance from the Source 3.4.2-8 Whole Body Dose Conversion Factors for Unknown Mix 3.4.2-9 Doses at Various Distances from Cloud Centerline 3.2 Source Term (Q)
Use the source term calculated in accordance with appropriate 1
PEP-Section 3.6, " Source Term Assessments and Estimates of Core Damage." The source term should have units of Ci/sec or Ci.
Enter the Source Term Value in Column 1 of Exhibit 3.4.2-1.
Also note the j
source term's units in Column 1.
3.3 Meteorology (X/Q) j 3.3.1 Determine the Atmospheric Stability Class, wind direction, and wind speed. For stack releases, use upper wind speeds and wind directions. For releases from any other location, j.
use lower wind speed and wind directions. The following steps, 3.3.1.1 to 3.3.1.5, should be used in order of.
preference.
4 i
3.3.1.1 If available, use appropriate equipment -to i
access the Met Tower directly. The Control i
Room's process computer can access the Met Tower and compute usable parameters directly. RC&T i
must first access the tower via an acoustic coupler and then use'a tabletop computer to convert the met pulses to usable parameters.
Record the wind speed, wind direction, and i
atmospheric stability class on the worksheet, j
Exhibit 3.4.2-1.
3.3.1.2 If the Met Tower is unaccessible via phone lines, dispatch an-individual to the-Met Tower j
to manually obtain meteorological pulses for each parameter as per PEP 2.6.20 (Exhibit 2.6.20-1).
1 3.3.1.3 If the on-site meteorological station is completely l
inoperable, the necessaryfmet data can be obtained from the National Weather Service (see PEP l
Appendix A.4 for phone numbers) using the steps j
given in Exhibit 2.6.20-3 of PEP 2.6.20.
j' 3.3.1.4 Call the Licensing & Permits Section in Raleigh and request meteorological data (see PEP Appendix A.4 for phone numbers).
4 3.3.1.5 If there is no meteorological data readily l
j
-available, estimate the wind speed and direction, determine, and circle appropriate' Atmospheric Stability Class, t
1
-BSEP PEP-3.4.2 Rev. 3
._,,,,---,-_,.-m.--
.w 4
~,m ---.,. -. -.. ~. - - -,,
c
--r,
Sunuy Cloudy Cloudy Clear Day Day Night Night light wind or calm B
C E
F (14m/s) = (18.9 mph) moderately strong wind C
D D
D
(>4m/s) = (>8.9 mph) 4 Record wind speed, wind direction, and stability class in Exhibit 3.4.2-1.
Note:
Assume Stability Class D whenever it is raining.
3.3.2 Determine the Atmospheric Dispersion Factor (X/Q) 3.3.2.1 Determine the Atmospheric Dispersion Factor, X/Q, by either Step 3.3.2.1.1 or Step 3.3.2.1.2.
3.3.2.1.1 Determine the Atmospheric Dispersion Factor, X/Q, using either Exhibit 3.4.2-4 if the release is via the stack or Exhibit 3.4.2-5 if the release is considered from ground level.
1)
Determine the point of interest from the plant.
2)
Read up or down to the line for the appropriate stability class as determined in Step 3.3.1.
3)
Record the appropriate XE/Q from the vertical scale for use in 5 below.
4)
Record the E (wind speed) from Section 3.3.1 and record below.
5)
Calculate the X/Q for the point of interest and enter in Column 2 of Exhibit 3.4.2-1.
X Xu u
=
Q Q
X
=
a Q
=
3.3.2.1.2 Determine the Atmospheric Dispersion Factor, X/Q, using the following equation where concentration is to be calculated along the centerline of the plume at ground level.
BSEP PEP-3.4.2 Rev. 3
_X_
=
1 eXP { -1
}
Q no au 2
g 7
where X/Q AtmosphericDppersion
=
Factor, sec/m 3.1415 n
=
average wind speed, u
=
m/sec.
H
=
release emission height (100 m for stack releases, 0 m for ground level re-leases).
horizontal dispersion o
=
Y coefficient, m; (see Exhibit 3.4.2-6).
vertical dispersion o
=
coefficient m; (see Exhibit 3.4.2-7).
3.4 Dose Conversion Factor (DCF) 3.4.1 If the nuclide mix of the source term is unknown, go to Step 3.4.2.
If the nuclide mix is known, go to Step 3.4.3.
3.4.2 Determine the Dose Conversion Factor corresponding to the time after Rx shutdown plus the travel time of cloud to the point of interest.
3.4.2.1 Estimate the arrival time of cloud to the point of interest and add it to the time after Rx shutdown.
distance to point of interest (in meters) time after shutdown (in hours) +
3600u hours
=
3.4.2.2 Select the Dose Conversion Factor from Exhibit 3.4.2-8 corresponding to the cloud passage time of 3
3.4.2.1.
Use the value in units of (R/hr)/(Ci/m )
i if the source term being used is given in terms of Ci/sec.
If the source term is in curies, divide the DCF by 3600. Record it in Column 3 of Exhibit 3.4.2-1.
Proceed to Step 3.5.
BSEP PEP-3.4.2 Rev. 3
3.4.3 On Exhibit 3.4.2-2, enter the known noble gas radionuclides of the source term and their respective concentrations in Column 1.
3.4.4 Enter the sample time and release time on the top of Exhibit 3.4.2-2.
If there is a difference between the estimated or actual release time and the sample time, use Exhibit 3.4.2-3 to obtain the decay constant for each 4
nuclide and calculate the exponential decay. Multiply the sample concentration by its exponential decay- (if applicable) for each identified nuclide to obtain the release concentration and record in Column 5.
Determine what percent each nuclide contributes to the total release mix and record in Column 6.
3.4.5 From Exhibit 3.4.2-3 obtain the DCF for each nuclide entered in Column 1 and enter these nuclide specific DCF in Column 7.
3.4.6 Multiply the % mix by its nuclide DCF for each nuclide and record. Sum these adjusted DCFs to obtain tt:e DCF for-that release. Record this DCF on Exhibit 3.4.2-1, Column 3, when the source term is in units of Ci/sec.
When the source term in Column 1 is in units of curies, divide this DCF by 3600 and enter this value in Column 3.
3.5 Dose Projection Results
~
3.5.1 On Exhibit 3.4.2-1 multiply Columns 1, 2, and 3 to obtain the centerline Whole Body Dose Projection in the downwind sector at the point of interest.
If the point of interest is not on the centerline of the cloud, then go to Step 3.6.
Record in Column 5 and enter the time and your initials in Column 6.
Also note in Column-6 the point of interest that the projected dose is calculated for.
3.6 Dose Projection Off the Centerline 3.6.1 If the point of interest is not on the centerline of the cloud, correct the dose for lateral distance (y) deviation.
i 3.6.1.1 Estimate the lateral distance (y) between the point of interest and the centerline of the cloud using the appropriate maps.
Record:
y=
(m)
Note:
If not otherwise known, the lateral distance (y) between the point of interest and the center-line of the cloud is estimated by use of triangu-lation of the point with respect to the plant and the cloud centerline sector on an appropriately scaled map.
(
BSEP PEP-3.4.2 Rev. 3 m
m g
g s-
3.6.1.2 Using Exhibit 3.4.2-6, determine a as a function y
of distance (downwind distance perpendicular to the point of interest) and Stability Class (Step 3.2) by locating the distance on the horizontal axis, read up to the diagonal line for the stability class, and read the o from the left vertical axis.
Y 3.6.1.3 Divide the later ' stance by a to determine the number of a u seen the cYoud centerline and the point of interest.
3.6.1.4 Using the number of a 's, refer to Exhibit 3.4.2-9 and determine the dose conversion factor.
Locate the number of a 's on the horizontal axis and read up to the dislance of aY (meters).
Read across to the vertical axis to obtain the appropriate correction factor (CF). Enter this value in Column 4 of Exhibit 3.4.2-1.
3.6.1.5 Perform the multiplications and record the projected dose in Column 5 of Exhibit 3.4.2-1.
Initial and date each calculation in Column 6.
Also note in Column 6 the point of interest that the projected dose is calculated for.
3.7 Report the Whole Body Projected Dose to the Radiological Control Director or Site Emergency Coordinator. Report to the Radiation Control Manager if the Emergency Operations Facility has been activated.
3.8 To estimate a source term based on measured radiation levels in the environment, these procedures need only by performed in reverse order solving for the unknown value in Column 1 of Exhibit 3.4.2-1.
3.9 Manual Method for Isopleth Determination This step is used to determine the area within which the radiation exposures will be equal to or greater than some specified dose of interest. As an example, a typical need will be to estimate the area where doses will be greater than a Protective Action Guideline.
3.9.1 Select a dose or dose rate of interest and enter into Step 3.9.2.
3.9.2 Solve for XE/q using the values for 5, source term, and DCF as previously determined in this procedure. Note:
Ensure that the units of dose, source term, and DCF are compatible.
XE (Dose:
)
x (5:
m/sec)
=
9 (Source:
)x (DCF:
)
XE (m-2)
BSEP PEP-3.4.2 Rev. 3
3.9.3 Determine the r.aximum distance (X-max) downwind for the Xu/Q in Step 3.9.2.
3.9.3.1 Select the appropriate Exhibit.
Use Exhibit 3.4.2-4 if the release is via the stack; otherwise, use Exhibit 3.4.2-5.
3.9.3.2 Locate the Xu/Q value on the vertical axis and read across to the appropriate Atmospheric Stability Class curve.
If using Exhibit 3.4.2-4, read across to the right-most side of the curve.
3.9.3.3 Read from the horizontal axis the corresponding distance (X-max) for the Xu/Q in Step 3.9.2.
3.9.3.4 Draw a line from the release point (plant) on an appropriately scaled full-size map to X-max in the downwind direction from the plant.
Note:
Given the maximum distance downwind just derived, the cross sectional distance (width) of the plume can be determined by Steps 3.9.4 and 3.9.5 in j
increasing order of sophistication.
3.9.4 Determine maximum width of affected area based on wind speed.
3.9.4.1 If the wind speed is >4 m/sec (8.9 mph), multiply X-max by 0.13 and cross-tee a line at both ends of the X-max line on the map and complete the rectangle.
Note:
This represents the maximum width of the area within X-max where the dose may be > dose of interest. This assumes wind meandering will not exceed 1 sector.
3.9.4.2 If the wind speed is 14 m/sec (8.9 mph), multiply the X-max by 0.26 and complete the rectangle.
Note:
This assumes wind meandering will not exceed 2 sectors.
3.9.5 Determine the width of the affected area based on the B. Turner method.
3.9.5.1 Divide the line from the plant to X-max into ten equal segments.
j 3.9.5.2 Determine the width (y) at each division of X-max by solving for y in:
BSEP PEP-3.4.2 Rev. 3
2
=
-2 o
In Xu/Q of interest y
Y Xu/Q at centerline 1)
Select Exhibit 3.4.2-4 if the release was via the stack; otherwise use Exhibit 3.4.2-5.
2)
For_each distance (division of X-max) determine a Xu/Q at the distance on the horizontal axis, read up or dowr; to the appropriate stability curve and read the Xu/Q from the vertical axis.
E Note:
This is the X /Q at the centerline value to be used in the equation in Step 3.9.2.
3)
For each distance (division of X-max) determine a.
Find the distance on the horizontal axis, iX Exhibit 3.4.2-6, read up to the appropriate stability class and then read the a from the vertical axis.
Y 3.9.5.3 Af ter determining (y) for each division of X-max, draw the isopeth on a map.
1)
Draw in the distance y, perpendicular to the centerline, at the appropriate X-max division.
2)
Connect the ends of the y lines. The area inside the torpedo shaped isopleth is the area within which the dose is greater than or equal to the dose of interest.
BSEP PEP-3.4.2 Rev. 3
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EXHIBIT 3.4.2-2 DETERMINATION OF DOSE CONVERSION FACTOR WORKSHEET Date:
Sample Time Release Time Difference (t)
(hr)
Nuclide Dose Sample Release
% of Conversion Factor Adj usted Nuclide Conc.
A(HR'1)
-t e
Cont.
Mix Exhibit 3.4.2 DCF '
E
/
x 5 1
i ~
I,,
s n.
3 Total DCF (R/hr/(Ci/m ) Is The Sum Of Adjusted DCFs.+
i BSEP PEP-3.4.2 '
Rev 3
'l
y
,T.
p },l -
j:
%,7
- tu
-.w l:
~.
~
~
t N
, y
' EXHIBIT 3 4 2-3 GAMMA WHOLE BODY DOSE CONVERSION FACTORS i
AND DECAY CONSTANTS.0F NOBLE GASES
,,r.
3
...Jc~
- Nuclide Camma'- WB DCF (R/hr)/(Ci/m A(HR-1)-
1 8.46 x 10+0
-6 KR-85M 0.158 N
KR-85 1.12 x 10 7.4 x 10
'3 KR-87 4.79 x.10 0.878 KR-88 s.23 x 10+3 0.248 3
KR-89 1.08 x 10 13.075 XE-131M 4.46 x 10+1 0.002 XE-133M 1.54 x 10 0.013 1
1 1.78 x 10+2
~Ac XE-133 0.005 i
XE-135 2'28 x 10+2 XE-135M.
2.665 i.52-x 10 0.076 XE-137-1.02 x 10 10.662 XE.138^
- 6.70 x 10+2 2.376
/
^
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t IK BSEP PEP-3.4.2 Rev. 3 i
x,
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~
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-.-.._q
..d..,,.-
,,..-,,..-3, y
EXHIBIT 3.4.2-4 g Q/Q Wnt be rBNCE FC2. EurvnWO 9.nERSES O h rn)
By STneu-iTY Class Di+T%cs (km)
ISO s 's i s s ; -
to 2
3 4
L.O 2
3 4 s s7as, i
i l l.
s 0.1 2
3-4 5 67St.
l t
5_. wYr4"Le. 2
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=-
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=-
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=
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=
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EXHIBIT 3.4.2-6 Horizontal Dispersion Coefficient as a Function of Downwind Distance from the Source t
I I
i l
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BSEP PEP-3.4.2 Rev. 3 l
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EXHIBIT 3.4.2-8 WHOLE BODY CONVERSION FACTORS FOR UNKNOWN MIX Time After Rx Dose Conversion Fgetor Shutdown (fir.)
(R/hr)/(Ci/m )
0.5 287 1
244 2
202 5
133 8
97 12 72 24 45 72 19 BSEP PEP-3.4.2 Rev. 3
EXHIBIT 3.4.2-9 Dose at Various Distances From Cloud Centerline IQ *- --
,- p
--- w ---
y =. _ =w = -= =:= y ==== = = =-=====n = = === 7 + = + 3
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[ The Gaussian Distribution represents
\\
th] reduction in concentration as a
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l function of distance from tne cloud 10--
centerline at any distance. The *K =-r= u== Gaussi an m V -4= A N =~ &== M "=T C 1...
yid other curves show the contribution
~~ - *; 4 ;__ _r; 2rr _n:rr_ rbn14 7.
of direct radiation added to innersion 7 __
~~
.~
- both of which contribute to the
~~~
PU ganna dose]
mMEw=
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3.
2.
i i
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2 3
+
Distance From Cloud Center Line (in units of r) y BSEP PEP-3.4.2 Rev. 3
9 File No.
Unit No.
Q+RETed App'l CAROLINA PokZR & LIGHT C0!! PANT BRUNSWICE STEAlf ELECTRIC PLANT
~
UNIT NOS. 1 & 2 THYROID DOSE PROJECTIONS PLANT E!!ERGENCY PROCEDURE PEP-3. 4. 3 VOLUlfE IIII,
Rev.3 Recoc::nended By:
/
s Date; Approved By:
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9 g 'Plang General Oniger
PEP - 3.4.3 THYROID DOSE PROJECTIONS 1.0 Responsible Individuals and Objectives The Radiological Control Director or the Dose Projection Coordinator is responsible for calculating thyroid dose projections to be used by the Radiological Control Director and the Site Emergency Coordinator in determining and evaluating possible off-site consequences from a release of airborne radioactivity. The Radiological Control Manager shall assume responsibility for calculating off-site thyroid dose projections (to be used by the Emergency Response Manager) after the Emergency Operations Facility is activated.
2.0 Scope and Applicability This procedure is intended to be used for all manual calculations of thyroid dose subsequent to that in PEP-3.4.1, " Initial Dose Projections."
It is intended to provide realistic assessment of doses at any point in the Emergency Planning Zone (EPZ). This procedure shall be performed periodically as directed by the Radiological Control Director, (Radiological Control Manager after the Emergency Operations Facility is activated).
Provisions are included for:
1)
Determining the Atmospheric Dispersion Factor (X/Q) at any point downwind in the Plume Exposure Planning 7one based on the Atmospheric Stability Class, wind speed, and the dist.ance to that point from the point of release.
2)
Correcting the dose to account for the time after shutdown that the source data is taken when using an assumed mix of radioiodine gases.
3)
Correcting for distance away from the centerline of the cloud.
4)
Calculating the dose conversion factor for a known nuclide mix of radioiodine gases.
5)
Manually constructing dose isopleths.
3.0 Actions 3.1 List of Exhibits:
3.4.3-1 Thyroid Dose Projections Worksheet 3.4.3-2 Determination of Dose Conversion Factor Worksheet 3.4.3-3 Thyroid (iodine inhalation) Dose Conversion Factors and Decay Constants of Radioiodines 3.4.3-4 Xu/Q with Distance for Elevated Releases 3.4.3-5 Xu/Q with Distance for Ground Level Releases 3.4.3-6 Horizontal Dispersion Coefficient as a Function of Downwind Distance from the Source 3.4.3-7 Vertical Dispersion Coefficient as a Function of Downwind Distance from the Source BSEP PEP-3.4.3 Rev. 3
3.4.3-8 Thyroid Dose Conversion Factors for Unknown Mix 3.4.3-9 Doses at Various Distances from Cloud Centerline 3.2 Source Term (Q) 4 Use the source term calculated in accordance with appropriate PEP-3.6,
" Source' Term Assessments." The source term needs to be in terms of total curies of iodine released.
If the source term is based on stack / vent monitor readings, use 15 percent of this monitor-based source term.
If the curies of iodine released can be determined from isotopic analysis, use this source term directly. Enter the Source Term Value in Column 1 of Exhibit 3.4.3-1.
3.3 Meteorology (X/Q) 3.3.1 Determine the Atmospheric Stability Class, wind direction, and wind speed. For stack releases, use upper wind speeds and wind directions. For releases from any other location, use lower wind speed and wind directions. The following t
steps, 3.3.1.1 to 3.3.1.5, should be used in order of preference.
3.3.1.1 If available, use appropriate equipment to access the Met Tower directly. The Control Room's process computer can access the Met Tower and compute usable parameters directly. RC&T must first access the tower via an acoustic coupler and then use a tabletop computer to convert the met pulses to usable parameters.
Record the wind speed, wind direction, and atmospheric stability class on the worksheet, Exhibit 3.4.3-1.
3.3.1.2 If the Met Tower is unaccessible via phone lines, dispatch an individual to the Met Tower to manually obtain meteorological pulses for each parameter as per PEP-2.6.20 (Exhibit 2.6.20-1).
3.3.1.3 If the on-site meteorological station is completely inoperable, the necessary met data can be obtained from the National Weather Service (see PEP Appendix A.4 for phone numbers) using the steps given in Exhibit 2.6.20-3 of PEP 2.6.20.
3.3.1.4 Call the Licensing & Permits Section in Raleigh and request meteorological data (see PEP Appendix A.4 for phone numbers).
3.3.1.5 If there is no meteorological data readily available, estimate the wind speed and direction, determine, and circle appropriate Atmospheric Stability Class.
BSEP PEP-3.4.3-Rev. 3
Sunny Cloudy Cloudy Clear Day Day Night Night light wind or calm B
C E
F (14m/s) = (18.9 mph) moderately strong wind C
D D
D
(>4m/s) = (>8.9 mph)
Record wind speed, wind direction, and stability class in Exhibit 3.4.2-1.
Note:
Assume Stability Class D whenever it is raining.
3.3.2 Determine the Atmospheric Dispersion Factor (X/Q) 3.3.2.1 Determine the Atmospheric Dispersion Factor, X/Q, by either Step 3.3.2.1.1 or Step 3.3.2.1.2.
3.3.2.1.1 Determine the Atmospheric Dispersion Factor, X/Q, using either Exhibit 3.4.3-4 if the release is via the stack or Exhibit 3.4.3-5 if the release is considered from ground level.
1)
Determine the point of interest from the plant.
2)
Read up or down to the line for the appropriate stability class as determined in Step 3.3.1.
3)
Record the ar ;opriate Xu/Q from the vertical scale for use in 5 below.
4)
Record the u (wind speed) from Section 3.3.1 and record below.
5)
Calculate the X/Q for the point of interest and enter in Column 2 of Exhibit 3.4.3-1.
X Xu
. u Q
~
Q
^
l X
=
2 Q
=
3.3.2.1.2 Determine the Atmospheric Dispersion Factor, X/Q, using the following equation where concentration is to be calculated along the centerline of the plume at ground level.
BSEP PEP-3.4.3 Rev. 3
exPI-1(f}
X 1
=
Q na au 2
y g z
where X/Q AtmosphericDppersion
=
Factor, sec/m 3.1415 n
=
average wind speed, u
=
m/sec.
H
=
release emission height (100 m for stack releases, O m for ground level re-leases),
horizontal dispersion c
=
Y coefficient, m; (see Exhibit 3.4.3-6).
vertical dispersion o
=
coefficient m; (see Exhibit 3.4.3-7).
3.4 Dose Conversion Factor (LCF) 3.4.1 If the nuclide mix of the source term is unknown, go to Step 3.4.2.
If the nuclide mix is known, go to Step 3.4.3.
3.4.2 Determine the Dose Conversion Factor corresponding to the time after Rx shutdown plus the travel time of cloud to the point of interest.
3.4.2.1 Estimate the arrival time of cloud to the point of interest and add it to the time after Rx shutdown.
distance to point of interest (in meters) time af ter shutdown (in hours) +
3600u
=
hours 3.4.2.2 Select the Dose Conversion Factor from Exhibit 3.4.3-8 corresponding to the cloud passage time of 3.4.2.1.
3.4.3 On Exhibit 3.4.3-2, enter the known radioiodine nuclides of the source term and their respective concentrations in Column 1.
BSEP PEP-3.4.3 Rev. 3
3.4.4 Enter the sample time and release time on the top of Exhibit 3.4.3-2.
If there is a difference between the estimated or actual release time and the sample time, use Exhibit 3.4.3-3 to obtain the decay constant for each nuclide and calculate the exponential decay. Multiply the sample concentration by its exponential decay (if applicable) for each identified nuclide to obtain the release concentration and record in Column 5.
Determine what percent each nuclide contributes to the total release mix and record in Column 6.
3.4.5 From Exhibit 3.4.3-3 obtain the DCF for each nuclide entered in Column 1 and enter these nuclide specific DCF in Column 7.
3.4.6 Multiply the % mix by its nuclide DCF for each nuclide and record. Sum these adjusted DCFs to obtain the DCF for that release. Record this DCF on Exhibit 3.4.3-1, Column 3.
3.5 Dose Projection Results 3.5.1 On Exhibit 3.4.3-1 multiply Columns 1, 2, and 3 to obtain the centerline thyroid dose projection in the downwind sector at the point of interest.
If the point of interest is not on the centerline of the cloud, then go to Step 3.6.
Record in Column 5 and enter the time and your initials in Column 6.
Also note in Column 6 the point of interest that the projected dose is calculated for.
3.6 Dose Projection Off the Centerline 3.6.1 If the point of interest is not on the centerline of the cloud, correct the dose for lateral distance (y) deviation.
3.6.1.1 Estimate the lateral distance (y) between the point of interest and the centerline of the cloud using the appropriate maps.
Record:
y=
(m)
Note:
If not otherwise known, the lateral distance (y) between the point of interest and the center-line of the cloud is estimated by use of triangu-lation of the point with respect to the plant and the cloud centerline sector on an appropriately scaled map.
3.6.1.2 Using Exhibit 3.4.3-6, determine o as a function ofdistance(downwinddistanceper[endicularto the point of interest) and Stability Class (Step 3.2) by locating the distance on the horizontal axis, read up to the diagonal line for the stability class, and read the a from the left vertical axis.
Y i
BSEP PEP-3.4.3 Rev. 3
3.6.1.3 Divide the lateral distance by a to determine the number of a 's between the cloud centeriin-and the point oY interest.
3.6.1.4 Using the number of a 's, refer to Exhibit 3.4.3-9 and determine the dose conversion factor.
Locate the number of a 's on the horizontal axis and read up to the Gaulian curve. Read across to the vertical axis to obtain the appropriate correction factor (CF). Enter this value in Column 4 of Exhibit 3.4.3-1.
3.6.1.5 Perform the multiplications and record the projected dose in Cotumn 5 of Exhibit 3.4.3-1.
Initial and date each calculation in Column 6.
Also note in Column 6 the point of interest that the projected dose is calculated for.
3.7 Report the Whale Body Projected Dose to the Radiological Control Director or Site Emergency Coordinator. Report to the Radiation Control Manager if the Emergency Operations Facility has been activated.
3.8 To estimate a source term based on measured radiation levels in the environment, these procedures need only by performed in reverse order solving for the unknown value in Column 1 of Exhibit 3.4.3-1.
3.9 Manual Method for Isopleth Determination i
This step is used to determine the area within which the radiation exposures will be equal to or greater than some specified dose of interest. As an example, a typical need will be to estimate the area where doses will be greater than a Protective Action Guideline (PAG).
3.9.1 Select a dose or dose rate of interest and enter into Step 3.9.2.
3.9.2 Solve for XE/Q using the values for 5, source term, and DCF as previously determined in this procedure. Note:
Ensure that the units of dose, source term, and DCF are compatible.
XE (Dose:
)
x (E:
m/sec) 9 (Source:
)x (DCF:
),
Xu Q
3.9.3 Determine the maximum distance (X-max) downwind for the Xu/Q in Step 3.9.2.
3.9.3.1 Select the appropriate Exhibit. Use Exhibit 3.4.3-4 if the release is via the stack; otherwise, use Exhibit 3.4.3-5.
BSEP PEP-3.4.3 Rev. 3
3.9.3.2 Locate the Xu/Q value on the vertical axis and read across to the appropriate Atmospheric Stability Class curve.
If using Exhibit 3.4.3-4, read across to the right-most side of the curve.
3.9.3.3 Read from the horizontal axis the corresponding distance (X-max) for the Xu/Q in Step 3.9.2.
3.9.3.4 Draw a line from the release point (plant) on an appropriately scaled full-size map to X-max ~in the downwind direction from the plant.
Note:
Given the maximum distance downwind just derived, the cross sectional distance (width) of the plume can be determined by Steps 3.9.4 and 3.9.5 in increasing order of sophistication.
3.9.4 Determine maximum width of affected area based on wind speed.
3.9.4.1 If the wind speed is >4 m/sec (8.9 mph), multiply X-max by 0.13 and cross-tee a line at both ends of the X-max line on the map and complete the rectangle.
Note:
This represents the maximum width of the area within X-max where the dose may be > dose of interest. This assumes wind meandering will not I
exceed I sector.
3.9.4.2 If the wind speed is <4 m/sec (8.9 mph), multiply the X-max by 0.26 and complete the rectangle.
Note:
This assumes wind meandering will not exceed 2 sectors.
3.9.5 Determine the width of the affected area based on the B. Turner method.
3.9.5.1 Divide the line from the plant to X-max into ten equal segments.
3.9.5.2 Determine the width (y) at each division of X-max by solving for y in:
2 y =
-2 o
In xu/Q of interest Y
. Xu/Q at centerline_
1)
Select Exhibit 3.4.3-4 if the release was via the stack; otherwise use Exhibit 3.4.3-5.
BSEP PEP-3.4.3 Rev. 3
2)
For_each distance (division of X-max) determine a Xu/Q at the distance on the horizontal axis, read up or down to the appropriate stability curve and read the Xu/Q from the verti al axis.
Note:
This is the Xu/Q at the centerline value to be used in the equation in Step 3.3.2.
3)
For each distance (division of X-max) determine o.
Find the distance on the horizontal axis, iX Exhibit 3.4.3-6, read up to the appropriate stability class and then read the o from the vertical axis.
Y 3.9.5.3 After determining (y) for each division of X-max, draw the isopeth on a map.
1)
Draw in the distance y, perpendicular to the centerline, at the atoropriate X-max division.
2)
Connect the ends of the y lines. The area inside the torpedo shaped isopleth is the area within which the dose is greater than or equal to the dose of interest.
1 BSEP PEP-3.4.3-Rev. 3
E O
,o EX111 BIT 3.4.3-1 TilYROID DOSE PROJECTIONS WORK SilEET b
Wind Column (1)
Column (2)
Column (3)
Column (4)
Column (5)
Column (6)
Speed Direction Stability Source X/Q DCF Correction Projected Initial (m/sec)
(from)
Class Term (Step 3.3)
(Step 3.4)
Factor Dose Time /Date (Step 3.2)
(Step 3.6)
PT OF INTEREST 8
7
?
U
EX11IBIT 3.4.3-2 DETERMINATION OF DOSE CONVERSION FACTOR WORKSHEET Date.
Sample Time Release Time Difference (t)
(hr)
Nuclide Dose Sample Release
% of Conversion Factor Adjusted Ruclide Conc.
A(HR'I)
-t e
Cont.
Mix Exhibit 3.4.3-3 DCF 3
Total DCF R-M Is The Sum Of Adjusted DCFs.+
Ci-Sec r
BSEP PEP-3.4.3 Rev. 3
l i
EXHIBIT 3.4.3-3 THYROID (IODINE INHALATION) DOSE CONVERSION FACTORS AND DECAY CONSTANTS OF RADI0 IODINES DOSECONVERSj0NFACTOR R-m Nuclide Sec-Ci A(HR~I)
I-130 29 5.64E-2
-I-131 265 3.59E-3 I-132 3
3.07E-1 1-133 64 3.41E-2 I-134 1
7.97E-1 I-135 13 1.04E-1 I
BSEP PEP-3.4.3 Rev. 3 1
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10 100 DISTANCE DOWNWIND, km EXHIBIT 3.4.3-6 Horizontal Dispersion Coefficient as a Function of Downwind Distance from the Source i
1 i
BSEP PEP-3.4.3 Rev. 3
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10 100 DISTANCE DOWNWIND, km EXHIBIT 3.4.3-7 Vertical Dispersion Coefficient as a Function of Downwind Distance from the Source BSEP PEP-3.4.3 Rev. 3
oA EXIIIBIT 3.4.3-8 Tl!YROID DOSE CONVERSION FACTORS FOR UNKNOWN MIX e
i dw II )
n{e[pnFactor s
Sec-Ci 0.5 58 1
63 2
73 5
97 8
111 12 125 24 159 72 223
(
BSEP PEP-3.4.3 Rev. 3
' EXHIBIT 3.4.3-9 Dose at various distances from cloud centerlin:2 s
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4 Distance From Cloud Center Line (in units of ag)
BSEP PEP - 3.4.3 Rev. 3-
l File No.
~
Unit No.
~ )
Q+RETcd App'l CAROLINA POWER & LIGHT COMPA.NT BRUNSWICK STEAM ELECTRIC PLANT UNIT 0 ALT 0MATION OF DOSE PROJECTION PROCEDL"RES PLANT EMERGENCY PROCEDURE:
PEP-03.4.5 VOLUME XIII Rev 001 Recommended By:
/ hHr
[ [d7 w
Date:
/ ~
//!4((2, Approved By:
,... a /2A4_
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E Date:
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1.0 Responsible Individual and Objectives The Radiological Control Director or the Dose Assessment Coordinator is responsible for calculating dose projections to be used by the Radiological Control Director and the Site Emergency Coordinator in determining and evaluating possible off-site consequences 'from a release of radioactivity. The Radiological Control Manager shall assume responsibility for calculating off-site dose projections (to be used by the Emergency Rasponse Manager) after the Emergency Operations Facility is activated.
2.0 Scope and Applicability This procedure is intended to describe the use of a computer program which automates many of the calculations performed in PEP-03.4.2, Whole Body Dose Projections, and PEP-03.4.3, Thyroid Dose Projections. The program is intended for use on i Hewlett-Packard Model 9830A tabletop computer.
Individuals using this program to automate dose projections should be very familiar with the above mentioned procedures. The program allows the capability of calculating downwind centerline doses at any distance including the direction dependent site boundary distance, 1, 2, 5, and 10 miles. The program can also provide X and Y coordinates (X being in the downwind direction) for plotting any desired isopleth. The program does not correct for lateral deviation if the point of interest is not on the centerline of the cloud. These provisions can be included if the correction factors are determined manually and then applied directly to the computer program's results where appropriate.
3.0 Actions Refer to the appropriate Plant Emergency Procedure for guidance in deter-mining the necessary inputs called for by the computer program.
PEP-03.4.2 is for whole body dose projections, and PEP-03.4.3 is for thyroid dose projections. The worksheet EXHIBITS in each of these procedures can be used for recording dose projections.
The computer program uses the same calculational methods as those des-cribed in the procedures mentioned above. The program calculates X/Q values from the basic equation using inputs of release height, stability class, wind direction and wind yelocity. Other inputs include an appro-priate source term and time after reactor shutdown.
Inputting the time after shutdown allows the computer to choose the dose conversion factor corresponding to the time that the cloud is projected to pass by the point of interest. The program calculates isopleth coordinates based on the B.
Turner method.
BSEP/Vol. XIII/ PEP-03.4.5 1
Rev. 1
)
The following steps explain the procedure for using the program.
-i i
3.1 Load the programmed cassette into the HP9830A, enter REWIND, enter LOAD 0 EXECUTE, and enter RUN EXECUTE.
l NOTE:
Press the EXECUTE button after each entry into the ccmputer to allcw the program to proceed.
3.2 The display will read " PRESET (1) OR KNOWN INVENTORY 7" asking if radionuclide mix of the release is known.
The program is If the mix is unknown, enter 1 and proceed to Step 3.3; if the mix is known, enter l
2 and prr cesd to Step 3.11.
I l
3.3 The display will read "O=WHOLE BODY.. 1= THYROID 7" The program is asking whether the user intends to make a whole body dose projection or a thyroid dose projection.
This entry will allow the program to access the correct dose conversion factors.
3.3.1 If a 0 was entered (whole body), then the display will read
" SOURCE TERM =7" Enter the appropriate source ter: in either Ci/see or CIs. The display will then read " SOURCE TER}f UNITS 0=CI/SEC.. 1=CI."
Enter the appropriate response and proceed to Step 3.4.
3.3.2 If a 1 was entered (thyroid), then the display will read
" SOURCE TERM =(CI)?" Enter the source term in total curies.
3.4 The display will read " HEIGHT OF RELEASE (METERS)."
If the release was via the stack, enter 100 meters.
If the release was from anywhere else, enter 0 meters.
3.5 The display will read " TIME SINCE SHUTDCWN..(X.XX HRS)?".
time since reactor shutdown.
Enter the The display will read " STABILITY CLASS.. 1=A, 2=B7" 3.6 Enter ths appropriate stability class, i.e., for stability class E, enter a 5.
3.7 The display will read " WIND, VELOCITY...(MPH)?" Enter the appropriate wind speed in units of miles per hour.
3.8 The display will read " OUTPUT TO PRINTER (Y OR N)?"
The program is asking if a printer is hooked up to the HP9830A for use in printing results.
Without a printer, results will need to be transcribed from the 9830 by hand.
If there is no printer, then enter a 1.
If there is a printer, enter a 0.
a.
NOTE:
The rest of the procedure will refer to computer results being given on the display (assuming there is no printer).
Keep in mind that with a printer, these same results would autcmatically be printed out.
BSEP/Vol. XIII/ PEP-03.4.5 2
Rev. I l
l J
d TheIdisplay will read " DISPLAY TIME EELAY.. 1=1 SEC, 2=2 SEC?"
3.9 This allows the prograa user to delay computer results on the display for any amount of time before displaying the next result. This delay gives the user time to transcribe results from the display. The time delay can be tailored to the user's preference, i.e., an entry of 5 will delay the display for.5 seconds, etc.
3.10 The display' will read " SPECIFIC DISTANCES?..1=YES, 0=N07" The
!.~
program is asking whetherJqhe user wants to look at centerline doses I
corresponding to the specific downwind distances of site boundary,1 l
mile (1609 m), '2 miles (3218 m), 5 miles (8046 m), and 10 miles (16093 m)~or to look at centerline doses st downwind distances yet to be specified.
3.10.1 The display will read "ISOPLETE COORDINATES...l=YES, 0=N07" 3.10.1.1 If s 1 is entered (YES jas isopleth coordinates),
then the display will-read "ISOPLETH VALUE=7"
- Enter, the desired isopleth value keeping in mind that the isopleth dose units will be the same as those just calculated for the centerline (Rem /hr or Rem). The computer will display in sequence the isopleth coordinates for the dose just entered. The X' coordinates give the downwind distances in meters corresponding to the site boundary,1, 2, 5, and 10 miles. The corresponding Y coordinates give in meters one-half the isopleth width at each X distance.
After 421 the isepleth coordinates have been displayed, the display will read "NEXT ISOPLETH.. 1=YES, 0=N07" By entering a 1, a new set of isopleth coordinates for a new isopleth
'value can be determined.
By entering a 0, the display will. read "ANOTHER RUN (Y OR N)?" Enter the Y is Yes and N if No.
If Y is entered, the program will display " ENTER RUN."
By entering rnn, the program will return to Step 3.3.
If N
'is satered, the program will display "PRCGRAM TERMINATED" for about two seconds and then display "TO USE AGAIN, ENTER RUN."
3.10.1.2 If a 0 is entered (NO to isopleth coordinates),
then the display will read "ANOTHER RUN (Y OR N)?" Enter Y if Yes and N if No.
If Y is entered, the program will display " ENTER RUN."
By entering run, the program will return to Step 3.3.
If N is entered, the program will display 5
~
~
" PROGRAM TERMINATED" for about two seconds and then display "TO USE AGAIN, ENTER RUN."
,~
u n
e BSEP/Vol.' XIII/ PEP-03 4.5 3
Rev. 1
-(
.t
's g
4
{-
/
l 1-g 4
O 2
.k 3.10.2
/I?,a 0.is eniered, then the display will read " MAX DISTANCE (MI)?" Enter the maximum downwind distance in miles for
,which centerline doses are desired.
e4 The display will then read " DOWNWIND INCREMENT (MI)?"
Enter an incremental distance in miles for which centerline doses out to the maximum downwind distance are desired.
The computer will display in sequence the centerline doses
~
for each downwind increment out to the maximum distance (X-max).
r e
3.10.2.1 The display will read "ISOPLETH,
COORDINATES...l=YES, 0=N0?" Follow Steps 3.10.1 s
and 3.10.2.
3.11 After a 2 is entered, a brief delay and blank screen will result while the new program is being loaded.
3.12 The display will read " OUTPUT TO PRINTEF (Y OR N)?" ' The program is asking if a printer is hooked up to + 6 HP9830A for use in printing results. Without a printer, results will need to be transcribed from the 9830 by hand.
If there is no printer, then enter an N.
If there is a printer, enter a Y and skip to Section 3.14.
NOTE:
The rest of this procedure will refer to computer results being given on the display (assuming there is no printer).
Keep in etnd that with a printer, these same results would automatically be printed out.
3.13 The display will read " DISPLAY TIME DELAY.. 1-1 SEC, 2-2 SEC7" This allows the pregram user to delay computer results on the display for any amount of time before displaying the next result. This delay gives the user time to transcribe results from the display. The time delay can be tailored to the user's preference, i.e.,
an entry of 5 will delay the display for 5 seconds, etc.
3.14 The display will read "WILL INPUT AMOUNTS BE IN CCNCENTRATION(1) OR PERCENT (2)."
If the concentrations of the nuclides are known, enter a 1, if the percents are known, enter a 2.
3.15 The display will read " RELEASE TO SAMPLE TIME =(HRS)?" Enter the appropriate time between sample time and expected or actual release time.
Zero may be entered if appropriate.
3.16 The display will read " INPUT ISOTOPE 7" Enter the common abbreviation for each isotope, i.e.,
BSEP/Vol. XIII/ PEP-03.4.5 4
Rev. 1
NOTE:
Depending on which nuclide is entered first, the program will decide whether to compute a whole body dose conversion factor or an iodine inhalccion dose conversion factor.
Do not mix noble gases and iodine species when entering isotopes. Also when entering percents of nuclides, ensure that the sum of the percents equal 100 percsnt.
3.17 The display will read "GUTPUT DCF (Y OR N)?" A Y entry will print or display the calculated DCF, an N entry will not.
3.18 The cisplay will flash " WAIT FOR REWINDING." The computer has completed the calculation of the dose conversion factor and is loading the first program.
3.19 The display will read " SOURCE TERM = ?"
Enter the source term and proceed back to Step 3.4 for completion of dose projection calculation.
BSEP/Vol. XIII/ PEP-03.4.5 5
Rev. 1
9 I
.1 File No.
Unit No.
Q+RETed App'l CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIT NOS. 1 & 2 RADIATION WORK PERMITS AND EXPOSURE CONTROL PLANT EMERGENCY PROCEDURE PEP-3.7.1 VOLUME XIII Rev. 2 L
e.
Approved By:
I ///k(d6/
[ [ '#[F f[fE 77 Date:
flant[eneralManager 1
i
I PEP-3.7.1 RADIATION WORK PERMITS AND EXPOSURE CONTROL 1.0 Responsible Individuals and Objectives j
The Site Emergency Coordinator, Radiological Control Director and/or Team Leader (s) are responsible for informing personnel entering a known or potential radiation area of possible health effects.
Individual workers and team leaders are responsible to the Site Emergency Coordinator for ensuring that emergency worke exposures are maintained within the guidelines of this procedure and ALARA to the extent possible.
2.0 Scope and Applicability This procedure shall be implemented following declaration of an Alert, Site Emergency or General Emergency. EXHIBIT 3.7.1-1 provides " Guidelines for Control of Personnel Radiation Exposure."
3.0 Actions and Limitations 3.1 Members of the Personnel Protection and Decontamination Team, as designated by the Team Leader, shall perform the following actions:
3.1.1 Set up a dosimetry area in the Operational Support Center (or where designated by Radiological Control Director or Personnel Protection and Decontamination Team Leader) containing the following items:
3.1.1.1 A supply of TLDs.
3.1.1.2 A supply of Self-Reading Pocket Dosimeters.
3.1.1.3 A supply of Exposure Record Sheets (RC&T-0200).
3.1.1.4 A supply of pencils and/or pens.
3.1.2 Complete Personnel Dosimetry forms, and issue proper dosimetry at the Operational Support Center (OSC) for incoming personnel. Dosimetry shall be issued in accordance with RC&T-0200 whenever possible and if time permits.
If an RIMS computer terminal is not available at the OSC, dosimetry issue information should be recorded for later entry into the RIMS computer by qualified dosimetry personnel.
3.1.3 Place TLDs in various areas outside the protected area as specified by the Personnel Protection and Decontamination Team Leader.
3.1.3.1 Record location of TLD on EXHIBIT 3.7.1-3.
3.1.3.2 Periodically replace TLDs and record readings obtained from removed TLDs on EXHIBIT 3.7.1-3.
l BSEP PEP-3.7.1 Rev. 2
t 3.1.4 Collect all Exposure Record Sheets and all TLDs for exiting personnel from Security for reading, as directed by the team leader. The information from these forms and TLD readings must be retained for later entry into the RIMS computer by qualified dosimetry personnel.
3.2 Actions of all personnel entering a radiation area.
Note:
Contact Personnel Protection and Decontamination Team Leader for where to obtain Radiation Work Permits and special dosimetry.
3.2.1 Obtain and complete a Radiation Work Permit, in accordance with RC&T-0230, " Issuance and Use of Computerized Radiation Work Permits," prior to entering a radiation area.
3.2.2 As directed by Personnel Protection and Decontamination Team member, obtain a high-range dosimeter when:
3.2.2.1 Entering a radiation field 110 R/hr.
3.2.2.2 Entering a radiation field of unknown intensity.
3.2.3 As directed by Personnel Protection and Decontamination Team member, obtain finger badges when:
3.2.3.1 Handling radioactive material where expected extremity dose rate 1100 R/hr.
3.2.3.2 Working on pipes or equipment where expected extremity dose rate is 125 R/hr.
3.2.4 Record any and all additional dosimetry on the Radiation Work Permit for each person entering the radiation area.
Whenever possible, the finger badges should be labeled with the individual's security badge number, and dosimeter serial numbers should be recorded on the RWP. Having this information available will facilitate data input into this RIMS computer.
3.2.5 Obtain authorization for the Radiation Work Permit from the Site Emergency Coordinator, Plant Gener.1 Manager, or l
the Environmental and Radiation Control Manager when exposures are expected to exceed the limits set forth in 10CFR20 (>3 Rem / quarter).
Note:
Guidelines for exposure control in excess of 3 Rem / quarter may be found in EXHIBIT 3.7.1-1.
3.2.6 The Site Emergency Coordinator may, at his discretion and as conditions warrant, defer requirements for a Radiation Work Permit, or portions thereof, prior to entry into a radiation area and give his authorization verbally.
BSEP PEP-3.7.1 Rev. 2 e,
m s
w o
s
i 3.2.6.1 A Radiation Work Permit shall be completed or a RIMS computerized RWP shall be conipleted by the individuals making a verbally authorized entry, as time permits, after the entry.
Note:
Any person that has received a whole body dose totaling >5 Rem by TLD for the yest shall not be permitted to enter a controlled radiation area without approval of the Site Emergency Coordinator or E&RC Manager.
BSEP PEP-3.7.1 Rev. 2
EXHIBIT 3.7.1-1 GUIDELINES FOR CONTROL OF PERSONNEL RADIATION EXPOSURE Although an emergency situation transcends the normal requirements for limiting exposures to ionizing radiation, guideline levels are established for exposures that may be acceptable in emergencies. The maximum whole body dose received by any worker should not exceed established regulatory limits. Every reasonable effort will be used to ensure that an emergency is handled in such a manner that no worker exceeds these limits, including, where recommended by expert medical opinion, the administering of radio-protective drugs. The acceptability of higher exposures is restricted to emergency situations where some clear and definite advantage can be gained by such worker exposure.
It is compatible with the risk concept to accept exposures leading to doses considerably in excess of those appropriate for normal occupational use when recovery from an accident or major operational difficulty is necessary. Saving of life, measures to circumvent substantial exposures to population groups, or preservation of valuable installations may all be sufficient cause for accepting above normal exposures. These higher dose limits cannot be specified; however, they should be commensurate with the significance of the objective and held to the lowest practicable level. As discussed below, all planned exposures should follow the guidelines set forth in Report No. 39 of the National Council on Radiation Protection, and specifically paragraphs 257-259 of that report, which deal with planned occupational exposure under emergency conditions.
Decision making is based on conditions at the time of an emergency and should always consider the probable effects of an exposure prior to allowing any individual to be exposed to radiation levels exceeding the established occupational limits. The probable high radiation exposure effects are:
1.
Up to 50 rem in 1 day - no physiological changes are likely to be observed.
2.
50 to 100 rem - no impairment likely but some physiological changes, including possible temporary blood changes, may occur. Medical observations would be required after exposure.
3.
100 to 300 rem - some physical impairment possible.
Some lethal exposures possible.
The following subsections describe the criteria to be considered for lifesaving and facility protection actions.
BSEP PEP-3.7.1 Rev. 2
Lifesaving Actions
- In emergency situations that require personnel to search for and remove injured persons or entry to prevent conditions that would probably injure numbers of people, a planned dose shall not exceed 100 rem to the whole body and a planned additional dose of up to 200 rem (i.e., a total of 300 rem) to the hands, forea rms, feet, and ankles. The following additional criteria should be considered:
1.
Rescue personnel should be volunteers or professional rescue personnel (e.g., fire fighters or first aid and rescue personnel who volunteer by choice of employment).
2.
Rescue personnel should be broadly familiar with the probable consequences of exposure.
3.
Women capable of reproduction should not take part in these actions.
4.
Other things being equal, volunteers above the age of 45 should be selected whenever possible for the purpose of avoiding unnecessary genetic effects.
5.
Internal exposure should be minimized by the use of the most appropriate respiratory protection, and contamination should be controlled by the use of protective clothing when practical.
6.
Exposure under these conditions shall be limited to once in a lifetime.
7.
Persons receiving exposures as indicated above should avoid procreation for a period up to a few months.
Exposure During Re-entrv/ Repair Efforts There may be situations where saving a life is not at issue, but where it is necessary to enter a hazardous area to protect valuable installations, or to make the facility more secure against events which could Ir.ad to radioactive releases (e.g., assessment actions or entry of damage repair parties who are to repair valve leaks or add iodine-fixing chemicals to spilled liquids).
In such instances, planned dose to emergency workers should not exceed 15 rem to the whole body, 125 rem to the thyroid, or 100 rem to the extremities. The following additional criteria should also be considered:
- This guideline applies to the removal of injured persons if the saving of life is possible, or entry to prevent conditions that, if left uncorrected, could lead to damage or releases that would probably injure numbers of people on or off site.
BSEP PEP-3.7.1 Rev. 2 1
1.
Persons performing the planned actions should be volunteers broadly familiar with exposure consequences.
2.
Women capable of reproduction will not take part in these actions.
3.
Internal exposures shall be minimized by respiratory protection and contamination controlled by the use of prctective clothing.
4.
If the retrospective dose from these actions is a substantial fraction of the prospective limits, the actions shall be limited to once in a lifetime.
5.
Entry into high radiation areas shall not be permitted unless instru-mentation capable of reading radiation levels of up to 1000 R/ hour (gamma) is provided.
6.
Each emergency worker entering a high radiation area shall wear pocket dosimeters capable of measuring the expected exposure to be received.
7.
Entry into radiation fields of greater than 100 R/ hour shall not be permitted unless specifically authorized by the Plant General Manager or Environmental & Radiation Control Manager; in their absence the Site Emergency Coordinator may grant approval.
8.
Planned exposures in excess of 3 rem may only be approved by:
a.
Plant General Manager, or b.
Environmental & Radiation Control Manager, or c.
Site Emergency Coordinator in their absence.
Emergency teams that must enter areas where they might be expected to receive higher than normal doses will be fully briefed regarding their duties and actions and what they are to do while in the area. They will also be fully briefed as to expected dose rates, stay time, and other hazards. All such entries will include one member from the Plant Monitoring Team or other person adequately trained in health physics. All team members will use protective clothing, dosimeters, respiratory devices, and other protective devices as specified by the Radiological Control Director. The team members will be instructed not to deviate from the planned route unless required by unanticipated conditions, such as rescue or performing an operation that would minimize the emergency condition. If the monitored dose rates or stay times encountered during the entry exceed the limits set forth for the operation, the team will immediately communicate with the Site Emergency Coordinator, or the Radiological Control Director, or will return to the area from where they were dispatched.
Once their operation has been completed, the team personnel will follow established monitoring and personnel decontamination procedures or as specified by the Radiological Control Director.
BSEP PEP-3.7.1 Rev. 2
1 (EXAMPLE)
EXHIBIT 3.7.1-2 DOSIMETRY ISSUE INSTRUCTIONS 1.
Fill in Name, Company and Social Security number on Exposure Record Sheet.
2.
Obtain a TLD and a dosiceter.
3.
Record TLD number and dosimeter number above name as shown.
CP&L CO Page FORM NO 1737 1/3/78 EXPOSURE RECORD 5HEET TLD #
Revised October 1, 1976 Dosimeter #
AUTHORIZED EXPOSURE mrem NAME COMPANY BADGE NUMBER POST RESULTS BY BADGE NUMBER, NOT NAME!!
SS NO.
I 2
3 Date Dosimeter TLD '
Total.
Allowed.
Comments 4.
Place dosimetry between waist and shoulders on outside of clothing.
5.
Leave Exposure Record Sheet at the Operational Support Center when entering the plant area.
6.
When Leaving the plant area, turn in dosimetry at the Operational Support Center and complete additional forms as required.
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BSEP PEP-3.7.1 Rev. 2
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EXHIBIT 3.7.1-3 TLD LOCATION AND LOG SHEET Time /Date Time /Date TLD Location TLD#
Placed Retrieved Reading BSEP PEP-3.7.1 Rev. 2
l File No.
Unit No.
Q+RETed App'l CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLAhT UNIT NOS. 1 & 2 EMERGENCY PERSONNEL MONITORING AND DOSIMETRY PLANT EMERGENCY PROCEDURE PEP-3.7.2 VOLUME XIII Rev. 2 mo.l 7.1 7 p P"79,,
- i
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.:af Recommended By:
M Date:
M[
Approved By:
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2.
jlant{eneralManager m
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PEP-3.7.2 EMERGENCY PERSONNEL MONITORING AND DOSIMETRY 1.0 Responsible Individual and Objectives f
The Personnel Protection and Decontamination Team is responsible to the Radiological Control Director for:
1.1 Determining personnel exposures, utilizing the Radiological Information Management Systems (RIMS) or a manual backup system during an emergency.
1.2 Maintaining exposure records through the use of the RIMS computer in a real-time mode or by using an alternate record keeping system which can later be loaded into the RIMS data base.
1.3 Determining need for and issuing special personnel monitoring devices.
2.0 Scope and Applicability This procedure shall be implemented upon activation of the Personnel Protection and Decontamination Team.
3.0 Actions and Limitations 3.1 Designated members of the Personnel Protection and Decontamination Team shall be trained in the use of the RIMS computer terminals to allow them to determine and document personnel exposures in accordance with RC&T-0200, " Control of Personnel Exposure to Ionizing Radiation,"
with the following additions and exceptions:
3.1.1 Set up a dosimetry issue area in the Operational Support Center as detailed in PEP-3.7.1, " Radiation Work Permits and Exposure Control."
3.1.1.1 Assist at the dosimetry issue area and complete additional documentation as required by RC&T-0200 if the RIMS terminal is not available and in use. Such assistance will be given as time and conditions permit.
Note:
Appropriate documentation shall be completed on paper or entered through a RIMS terminal when exiting the plant i
for personnel who bypassed the additional documentation due to plant / emergency j
conditions.
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BSEP PEP-3.7.2 Rev. 2 l
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3.1.1.2 Ensure that all TLDs are read and that results are documented or entered into the RIMS system as conditions allow.
^
3.1.2 Issue special dosimetry (e.g., high-range dosimeters or finger badges) as specified in PEP-3.7.1, " Radiation Work Permits and Exposure Control," or as otherwise directed by the Personnel Protection and Decontamination Team Leader.
3.1.2.1 Record dosimeter numbers and to whom issued on EXHIBIT 3.7.2-1, "Special Dosimetry Log."
3.1.2.2 Instruct personnel issued special dosimetry to have dosimeter numbers recorded on the Radiation Work Permit, either on the printed RWP form or by having a qualified RIMS user enter the information via a computer terminal.
3.1.3 Collect specimens and perform bioassays or whole body counts for personnel suspected of having internal con-tamination using che following guidelines:
3.1.3.1 Contamination present in the hair or on the face.
3.1.3.2 Unremovable contamination on the body.
3.1.3.3 Greater than 3 Rem by TLD.
3.1.3.4 Respirator filters show contamination greater than 100 mR/hr.
3.1.3.5 As indicated by risk situations, e.g.,:
- i. Respirator defeated ii. Retrospective recognition of airborne hazard 3.1.4 The results of body counts and/or bioassays not directly generated by and/or stored in the RIMS computer will be i
documented such that these results can readily be entered into the RIMS data files directly from such documentation i
as time and conditions permit.
l BSEP PEP-3.7.2 Rev. 2
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EXHIBIT 3.7.2-1 l
SPECIAL DOSIMETRY LOG Name Dosimeter Type Dosimeter Number BSEP PEP-3.7.2 Rev. 2
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APPENDIX A.1 ESEP PERSONNEL BSEP Personnel Home Phone Office PLANT GENERAL MANAGER (SITE EMERGENCY COORDINATOR)
C. R. Dietz 210 pager)
(
. Alternate MANAGER - PLANT OPERATIONS R. E. Morgan 342 j(pager)
MANAGER - OPERATIONS (PLANT OPERATIONS DIRECTOR)
R. E. Knoble 214 Alternate R. E. Morgan 342 MANAGER - ENVIRONMENTAL & RADIATION CONTROL (RADIOLOGICAL CONTROL DIRECTOR)
G. J. Oliver 447 Alternate L.. F. Tripp 262 MANAGER - MAINTENANCE (EMERGENCY REPAIR DIRECTOR)
M. D. Hill 212 Alternate J. P. Dimmette 367 i
l MANAGER - TECHNICAL SUPPORT (LOGISTIC SUPPORT DIRECTOR)
W. M. Tucker 213 j
Alternate L. E. Boyer 225 t
., *" m m a :
e.,. s., '
(
T O -
l BSEP PEP-A.1 Rev. 3
ASSISTANT TO PLANT GENERAL MANAGER (REPRESENTATIVE TO THE SERT)
C. R. Gibson I
(Sea Captain) 211 j(Weekends, Cary, N.C.)
RADIATION CONTROL SUPERVISOR (PERSONNEL PROTECTION AND DECONTAMINATION LEADER)
L. F. Tripp j
262 Altaenate Radiation Control Foreman (See Attached)
ENVIRONMENTAL AND CHEMISTRY SUPERVISOR (ENVIRONMENTAL MONITORING LEADER)
R. D. Pasteur 237 Alternate i
A. H. Caylor L
264 PROJECT SPECIALIST - RADIATION CONTROL (DOSE PROTECTION COORDINATOR) t-R. F. Queener j
52I Alternate J. L. Kiser/P. B. Snead 520/521 PROJECT SPECIALIST - ENVIRONMENTAL AND CHEMISTRY (PLANT MONITORING LEADER)
C. E. Robertson 530 i
Alternate J. W. Davis 529 MECHANICAL MAINTENANCE SUPERVISOR (DAliAGE CONTROL LEADER)
J. P. Dimmette 367 G. C. Campbell 367 I&C ELECTRICAL MAINTENANCE SUPERVISOR (DAMAGE CONTROL LEADER)
~
K. E. Enzor 368 J. R. Jefferson 389 SENIOR SPECIALIST ELECTRICAL (OPERATIONAL SUPPORT CENTER LEADER)
K. D. Creech 368 T. L. Brown 389 BSEP PEP-A.1 Rev. 3
l ENGINEERING SUPERVISOR (ACCIDENT ASSESSMENT LEADER) j E. A. Bishop 271 l
l Alternate t
J. S. Boone J
317 SECURITY SPECIALIST (EMERGENCY SECliRITY LEADER)
W. iiatcher 252 Alternate G. Spies 253 COST CONTROL SPECIALIST (EVACUATION ASSEMBLY LEADER)
~
J. L. Bovte 230 Alternate j
R. G. Lee 231 REGULATORY COMPLIANCE (EMERGENCY COMMUNICATOR)
D. E. Novotny 316 M. J. Pastva 315 R. M. Poulk 314 k
-BSEP PEP-A.1 Rev. 3
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Environmental and Radiation Control foreman Home Office A. H. Caylor (E&C) 264 J. B. Cook (RC) 239 B. E. Failor (RC) 241 J. D. Henderson (RC) 453 J. A. Kaham (E&C) 238 W. A. Nurnburger (E&C) 263 J. D. Ward (RC) f j
476 l
Specialists J. W. Davis (E&C) 530 J. L. Kiser (RC ALARA) 520 R. E. Queener (RC) 521 C. E. Robertson (E&C) 529 P. B. Snead (RC) 521 Operations Shift Operating Supervisors
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C. F. Blackmon 312 l
A. S. Hegler 375 C. W. Martin 375 P. T. McNeill 375 W. L. Johnson 375 J. D. Lichty 375 D. C. Cooper
_]
375 Shift Foreman M. R. Foss 200/423 l
J. D. Lichty 201/202 W. D. Link 201/202 J. L. Simon 200/201 R. D. Tart 200/423 S. B. York 200/201 R. A. LaBelle l
200/201 S. C. Carr 384 C. S. Briney 200/201 E. C. Hawkins 200/201 R. M. Stiffler 201/202 K. F. Horn J
200/201 BSEP PEP-A.1 Rev. 3
Electrical and I&C Maintenance Foremen Home Office J. R. Jefferson f
389 G. N. Batton 365 W. M. Bracey 349 R. D. Creech 371 J. E. King 379 C. D. Parker 364 G. W. Stegall 366 J. W. Bruner 365 L. R. Stohler 363 W. B. Moore 366
-a Mechanical Maintenance J. D. Thrift 266 W. M. Cain 348 E. G. Conner 354 H. R. Harrelson 310 T. P. Harrison 355 K. W. Huggins 356 J. D. Schrab 355 D. Stidham 430 C. Treubel 372
--a Qualified Operators for Emergency Switchboard Annette Clemmons 300 Charlotte Frye 219 Kay Hewett 215 Cindy Long 328 Brenda McKeithan 373 Amy Rhodes 369 Sally Stocum 215 Marsha Stone 300 Theresa Tripp 215 Geri Cahill 215 Helen Nichelson 224
_3 Security W. R. Hatcher
{
252 G. Spies 253 BSEP PEP-A.1 Rev. 3