RNP-RA/04-0034, Transmittal of Emergency Procedures Revisions
| ML040710585 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 03/04/2004 |
| From: | Baucom C Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| RNP-RA/04-0034 | |
| Download: ML040710585 (208) | |
Text
, Progress Energy Serial: RNP-RA/04-0034 MAR 0 4 2004 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 TRANSMITTAL OF EMERGENCY PROCEDURE REVISIONS Ladies and Gentlemen:
In accordance with 10 CFR 50.4(b)(5) and Appendix E to 10 CFR 50, Progress Energy Carolinas, Inc. (PEC), formerly known as Carolina Power and Light Company, is transmitting revisions to H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, Emergency Implementing Procedures. The procedure revisions and effective dates are listed in the attachment to this letter.
A description of each procedure change is provided on the "Summary of Changes" page included within each emergency procedure. Please replace the superseded procedures with the enclosed revisions.
If you have any questions concerning this matter, please contact me.
Sincerely, C. T. Baucom Supervisor - Licensing/Regulatory Programs CTB/cac Attachment Enclosures c: L. A. Reyes, NRC, Region II NRC Resident Inspector, HBRSEP C. P. Patel, NRC, NRR (w/o Attachment and Enclosures)
Progress Energy Carolinas, Inc.
Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/04-0034 Page 1 of 1 Procedure Revisions and Effective Dates Procedure Revision Effective No. Date EPEOF-03, "Administrative and Logistics Manager" 10 02/17/04 EPEOF-05, "Radiological Control Manager" 7 02/17/04 EPRAD-01, "Environmental Monitoring" 13 02/17/04 EPTSC-04, "Radiological Control Director" 8 02/17/04 EPNOT-03, "EOF Public Information Emergency 6 03/02/04 Communicator" EPPRO-04, "EP Performance Indicators" 5 03/02/04 EPRAD-03, "Dose Projections" 14 03/02/04 EPTSC-00, "Activation and Operation of the Technical 4 03/02/04 Support Center" EPTSC-09, DELETED - Remove tab and procedure from N/A 03/02/04 books I
Progmss Eneiy Reference Use H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 2 PART 5 EPEOF-03 ADMINISTRATIVE AND LOGISTICS MANAGER REVISION 10 I EPEOF-03 I Rev. 10 l Page 1 of 27l
SUMMARY
OF CHANGES PRR 116606 STEP REVISION COMMENTS Entire Procedure Re-formatted procedure to comply with AP-007.
Re-placed CP&L with Progress Energy Step 3.4.1 Added a step to coordinate access and fitness for duty activities with the Emergency Security Team Leader (ESTL).
Step 3.4.2 Revised step to request assistance from the ESTL for assigning an Evacuation Assembly Area Leader.
Step 8.14.1 Added note to indicate that "coordination of meals for the JIC staff will be performed by JIC administrative staff. "
Attachment 10.11 Re-located quick start guide to the attachment section.
Added a step to coordinate access and fitness for duty activities with the Emergency Security Team Leader (ESTL).
i EPEOF-03 l Rev. 10 l Page 2 of 27
TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ............................ 4
2.0 REFERENCES
............................ 4 3.0 RESPONSIBILITIES ............................ 4 4.0 PREREQUISITES ............................ 4 5.0 PRECAUTIONS AND LIMITATIONS ............................ 4 6.0 SPECIAL TOOLS AND EQUIPMENT ............................ 5 7.0 ACCEPTANCE CRITERIA ............................ 5 8.0 INSTRUCTIONS ............................ 5 9.0 RECORDS ............................ 7 10.0 ATTACHMENTS .. 8 10.1 Emergency Operations Facility (EOF) Sign-In Roster .9 10.2 Emergency Operations Facility (EOF) Four Day Work Schedule .10 10.3 EOF NRC Support Room Recommended Layout .15 10.4 Emergency Operations Facility (EOF) Emergency Supply List .16 10.5 Technical Support Center (TSC) Sign-In Roster .17 10.6 Technical Support Center (TSC) Four Day Work Schedule .19 10.7 Accident Assessment Room Recommended Layout .23 10.8 Support Services Room Recommended Layout .24 10.9 Environmental & Radiological Control (E&RC) Support Room Recommended Layout .25 10.10 TSC NRC Support Room Recommended Layout .26 10.11 Administrative and Logistics Manager (A&LM) Quick Start Guide .27 I EPEOF-03 I Rev. 10 l Page 3 of 27
1.0 PURPOSE This procedure describes the functional responsibilities and procedure steps for the Administrative & Logistics Manager (A&LM).
2.0 REFERENCES
As per EPEOF-00.
3.0 RESPONSIBILITIES 3.1 Plan, schedule and expedite emergency logistical support (including operability, locating, ordering, receiving of equipment, screening, orientation, badging, transportation and lodging of support personnel) as well as accountability of Emergency Response personnel in the Technical Support Center (TSC),
Emergency Operations Facility (EOF), and the Operations Support Center (OSC).
3.2 Establish cost control/accounting system as needed.
3.3 Determine the need for additional contracts, facilities and services.
3.4 Provide technical and administrative direction to the Emergency Security Team Leader (ESTL) and Support Services.
3.4.1 Coordinate access and fitness for duty activities with security personnel.
3.4.2 Request assistance from the ESTL for assigning an individual as Evacuation Assembly Area Leader (EAAL), as needed.
3.5 Serve as a liaison between the Emergency Response Manager (ERM) and the Legal Department.
3.6 Ensure claims processing by Progress Energy and contractor insurance personnel.
4.0 PREREQUISITES As Per EPEOF-00 5.0 PRECAUTIONS AND LIMITATIONS As Per EPEOF-00 EPEOF-03 I Rev. 10 l Page 4of27
6.0 SPECIAL TOOLS AND EQUIPMENT N/A 7.0 ACCEPTANCE CRITERIA N/A 8.0 INSTRUCTIONS 8.1 Determine staffing requirements and shift change assignments. Utilize Attachmentsl 0.2, Emergency Operations Facility (EOF) Four Day Work Schedule, and 10.6, Technical Support Center (TSC) Four Day Work Schedule.
8.2 For evacuations:
8.2.1 In conjunction with the ERM and County Emergency Management officials, determine the appropriate shelter location(s) for non-essential personnel.
- 1. Identify appropriate evacuation route(s).
- 2. Coordinate Health Physics support.
- 3. Provide evacuation vehicles (if necessary).
- 4. Assign an individual from the TSC or EOF to provide assembled evacuees with plant status, shelter location and travel information, relief shift times and a reminder to refer questions concerning plant activities to the Company Spokesperson.
- 5. Release non-essential personnel as soon as possible.
8.2.2 Notify the State and Counties regarding evacuation of personnel to their homes or shelter areas (if county shelters are open). Notifications to State or County agencies may be made by (in order of preference):
- 1. State/County Emergency Communicator (dedicated line)
- 2. Assistant ERM (Bell line)
- 3. ESTL (via radio)
I EPEOF-03 I Rev. 10 l Page 5 of 27 l
8.3 Update the Emergency Security Team Leader (ESTL) on plant status as the Emergency progresses.
8.4 Notify the ESTL of the names and affiliations of individuals requested to report to the plant and where they will report.
8.5 Provide a list of incoming personnel to State and County agencies to facilitate access to the plant after traffic control is established.
8.6 Initiate the Florence Staging Area, if required. Refer to the ERO Telephone Directory for the telephone number.
8.7 Provide safe routes for personnel reporting to the plant.
8.8 Coordinate request for use of government facilities through the State of South Carolina.
8.9 Direct requests for materials or parts to the Unit 1 issue counter, Bulk Warehouse or Unit 2 stockroom.
8.10 Direct clerical support requests to the Manager, Site Support Services or designee.
8.11 Direct requests for installation, maintenance and operation of communications facilities to the Information Technology personnel or the Help Desk. Refer to the ERO Telephone Directory for telephone numbers.
8.12 Ensure planned exposure control for personnel under your supervision in accordance with EPOSC-04, Emergency Work Control.
8.13 Determine the need for and utilize the Institute of Nuclear Power Operations (INPO) Resource Book to request additional resources from neighboring utilities.
EPEOF-03 I Rev. 10 I Page 6 of 27
8.14 Arrange for food, drinks, snacks for Emergency Response Organization (ERO) augmentees.
8.14.1 Determine number of personnel in each facility (TSC, EOF, OSC, Control Room, Joint Information Center).
NOTE: Coordination of meals for the JIC staff will be performed by administrative personnel in the JIC. Payment arrangements for JIC meals will be coordinated through the A&LM.
- 1. For training exercises include Controller/Evaluator and Simulator staff.
- 2. Orders should be placed at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> before meals to allow for vendor preparation and delivery.
8.15 Arrange for hotels, motels for personnel as required.
8.16 Upon notification that teams are deployed, set-up state/NRC support rooms per Attachment 10.3, EOF NRC Support Room Recommended Layout and Attachment 10.10, TSC NRC Support Room Recommended Layout.
8.17 Perform personnel accountability of people reporting to the EOF and for the other emergency response facilities, as requested.
9.0 RECORDS Records generated as result of the performance of this procedure should be forwarded to the EP staff for retention.
I EPEOF-03 I Rev. 10 I Page7of27
10.0 ATTACHMENTS 10.1 Emergency Operations Facility (EOF) Sign In Roster 10.2 Emergency Operations Facility (EOF) Four Day Work Schedule 10.3 EOF NRC Support Room Recommended Layout 10.4 Emergency Operations Facility (EOF) Emergency Supply List 10.5 Technical Support Center (TSC) Sign-In Roster 10.6 Technical Support Center (TSC) Four Day Work Schedule 10.7 Accident Assessment Room Recommended Layout 10.8 Support Services Room Recommended Layout 10.9 Environmental & Radiological Control (E&RC) Support Room Recommended Layout 10.10 TSC NRC Support Room Recommended Layout 10.11 Administrative and Logistics Manager (A&LM) Quick Start Guide I EPEOF-03 I Rev. 10 l Page8of27
ATTACHMENT 10.1 Page 1 of 1 EMERGENCY OPERATIONS FACILITY (EOF) SIGN IN ROSTER NOTE: The positions listed below are recommended for activation purposes, however, partial activation should be considered in order to relieve the Control Room or TSC as soon as practical.
NAME (PLEASE PRINT) /TIME EMERG. RESPONSE MGR. (B1-75) I ASST. EMERG. RESP. MGR. I
__EMERGENCY COMMUNICATOR* I
__PLANT OPERATIONS ADVISOR DOSE PROJECTION LEADER (B1-45) I
_ENVIRON. MON. LEADER (B1-75) I EOF POSITIONS LISTED BELOW ARE NOT REQUIRED FOR INITIAL EOF ACTIVATION.
TECHNICAL ANALYSIS MGR.
ADMIN. & LOGISTICS MGR.
RADIOLOGICAL CONTROL MGR.
l ERM ADMIN. ASSISTANT SEOC REPRESENTATIVE DARLINGTON EOC REPRESENTATIVE CHESTERFIELD EOC REPRESENTATIVE LEE EOC REPRESENTATIVE STATE/COUNTY COMMUNICATOR*
PUBUC INFORMATION COMMUNICATOR*
FACIULTYADMINISTRATIVE ASSISTANTS (2)
OVERFLOW ERO POSITION I l
- Of the 3 Communicator positions (TSC and EOF), 1 additional person is required in 45 minutes and 2 additional personnel are required in 75 minutes.
I EPEOF-03 I Rev. 10 l Page 9 of 27
( c ATTACHMENT 10.2 Page 1 of 5 EMERGENCY OPERATIONS FACILITY (EOF) FOUR DAY WORK SCHEDULE Position Shift Time* Date Date Date Date Emergency : Name Name Name Name Response Manager 1 2
3 Assistant Emergency e Name Name Name Name Response Manager 1 2
3 Emergency _ I__
regSl Name Name Name Name Communicator 1 P operation 2 Le i; Name ader Name Name Name Advisor1 3 Dose Projection Leader 2 ... .. Name Name Name Name
. 3_
3
- Shift times may vary - i.e., (2) 12-hour shifts, (3) 8-hour shifts If (2) 12-hour shifts - use shift 1-shift 2 boxes If (3) 8-hour shifts - use shift 1-shift 2 and shift 3 boxes I EPEOF-03 I Rev.10 I Page 10 of 27
( c c ATTACHMENT 10.2 Page 2 of 5 EMERGENCY OPERATIONS FACILITY (EOF) FOUR DAY WORK SCHEDULE Position Shift Time Date Date Date Date Facility Administrative Name Name Name Name Assistant 1 2
3 FalAdministratName Name Name Name Assistant 1 2 . .
3 Environmental Monitoring Name Name Name Name Leader 1 2
3 Technical Analysis Manager Name Name Name Name 2
3.
Administrative & Logistics Name Name Name Name Manager Radiological Control ._.__f___._____ Name Name Name Name Manager 3
- Shift times may vary -L.e., (2) 12-hour shifts, (3) 8-hour shifts If (2) 1 2-hour shifts - use shift 1 -shift 2 boxes If (3) 8-hour shifts - use shift 1-shift 2 and shift 3 boxes EPEOF-03 I Rev.10 Page 11 of 27
C c c ATTACHMENT 10.2 Page 3 of 5 EMERGENCY OPERATIONS FACILITY (EOF) FOUR DAY WORK SCHEDULE Position Shift Tlme* Date Date Date Date ERM Administrative Name Name Name Name Assistant 3
SEOC Representative _ _ vi _ _ Name Name Name Name 1
2 3
Darllngton EOC v_____---______ Name Name Name Name Representative 2 l 3
- Shift times may vary - i.e., (2) 12-hour shifts, (3) 8-hour shifts If (2) 12-hour shifts - use shift 1-shift 2 boxes If (3) 8-hour shifts - use shift 1-shift 2 and shift 3 boxes I EPEOF-03 I Rev.10 I Page 12 of 27l
(.
C C ATTACHMENT 10.2 Page 4 of 5 EMERGENCY OPERATIONS FACILITY (EOF) FOUR DAY WORK SCHEDULE Position Shift Time* Date Date Date Date
__ __ _ _ _I_ I I I I I I I Chesterfield EOC ._--a ___________' Name Name Name Name Representative 2.
3 Lee EOC Representative Name Name Name 2
3 State/County Name Name Name Name Communicator 2
3 Public Information Name Name Name Name Communicator 1 2
3
- Shift times may vary - i.e., (2) 12-hour shifts, (3) 8-hour shifts If (2) 12-hour shifts - use shift 1-shift 2 boxes If (3) 8-hour shifts - use shift 1-shift 2 and shift 3 boxes I EPEOF-03 I Rev.10 l Page 13 of 27
C {
ATTACHMENT 10.2 Page 5 of 5 EMERGENCY OPERATIONS FACILITY (EOF) FOUR DAY WORK SCHEDULE Position Shift Time* Date Date Date Date Others: Name Name Name Name 2
Name Name Name Name 2 __ ___v_ ___v_
3 . _ _ __ __ _ _l_
Name Name Name Name 1
2
-3 Name Name Name Name 2
3
- Shift times may vary - i.e., (2) 12-hour shifts, (3) 8-hour shifts If (2) 12-hour shifts - use shift 1-shift 2 boxes If (3) 8-hour shifts - use shift 1-shift 2 and shift 3 boxes I EPEOF-03 l Rev.10 I Page 14 of 27
ATTACHMENT 10.3 Page 1 of 1 EOF NRC SUPPORT ROOM RECOMMENDED LAYOUT Storage Cabinets
-VV\/ \/VVV-Storage Cabinets To EOF Room 412 Command Room
ATTACHMENT 10.4 Page 1 of 1 EMERGENCY OPERATIONS FACILITY (EOF) EMERGENCY SUPPLY LIST SUPPLIES EOF LOCATION
- 1. Telecopier Room 434
- 2. Xerox Machine Copy Room 411
- 3. Emergency Kit EOFiTSC Mech. Room
- 4. Clock On Wall
- 5. Emergency Resources Manual (INPO) A&LM
- 6. Maps
- a. 10 mile EPZ Room 434
- b. 50 mile EPZ Room 434
- c. Topo Map of Plant Environments Room 434
- 7. Mechanical Systems Drawings Training Library
- 8. Electrical Systems Drawings Training Library
- 9. FSAR Training Library
- 10. System Descriptions Training Library
- 11. Technical Specifications Training Library
- 12. Emergency Plans
- a. Corporate Plan and Procedures Room 434
- b. Plant Plan and Procedures Training Library
- c. State and Local Plans Room 434
- 13. Emergency Notification Phone Lists Emergency Phone Book
- 14. Progress Energy Emergency Room 434 Organization Chart EPEOF-03 Rev. 10 Page 16 of 27
ATTACHMENT 10.5 Page 1 of 2 TECHNICAL SUPPORT CENTER (TSC) SIGN IN ROSTER NOTE: The positions listed below are recommended for activation purposes, however, partial activation should be considered in order to relieve the Control Room as soon as possible.
NAME (PLEASE PRINT) /TIME SITE EMERGENCY COORDINATOR (B1 -75) I RADIOLOGICAL CONTROL DIRECTOR I PLANT OPERATIONS DIRECTOR I REACTOR ENGINEER (B1-45) I ELECTRICAL ENGINEER (B1-75)
MECHANICAL ENGINEER (B1-75)
__EMERGENCY REPAIR DIRECTOR I
__ERFIS MAINTENANCE I
__EMERGENCY SECURITY TEAM LEADER I
__TECHNICAL ANALYSIS DIRECTOR I NRC COMMUNICATOR* I TSC POSITIONS LISTED BELOW ARE NOT REQUIRED FOR INITIAL TSC ACTIVATION.
__SEC ADMINISTRATIVE ASSISTANT
__SUPPORT SVS. COORDINATOR FACILITY ADMINISTRATIVE ASSISTANT(S) (1) /
(2) I
- Of the 3 Communicator positions (TSC and EOF), 1 additional person is required in 45 minutes and 2 additional personnel are required in 75 minutes.
EPEOF-03 I Rev. 10 I Page 17 of 27
ATTACHMENT 10.5 Page 2 of 2 TECHNICAL SUPPORT CENTER (USC) SIGN IN ROSTER ERO POSITION NAME (PLEASE PRINT) I TIME
___ __l
___ ________l
___ _________I
___ ________l I
___ ________l
___ ________l I
___ ______ ___ ________l
___ ________l
___ ________l
___ ________l
___ ________l I EPEOF-03 I Rev. 10 l Page 18 of 27
c c c ATTACHMENT 10.6 Page 1 of 4 TECHNICAL SUPPORT CENTER (TSC) FOUR DAY WORK SCHEDULE Position Shift Time* Date Date Date Date Site Emergency Coordinator Name Name Name Name 2
l 3 Radiological Control Director ......... ..q Name Name Name Name l2 __ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _
Plant Operations Director Name Name Nam 3
Reactor Engineer ______ -_By.__ Name Name Name Name 2
3
- Shift times may vary - i.e., (2) 12-hour shifts, (3) 8-hour shifts If (2) 12-hour shifts - use shift 1-shift 2 boxes If (3) 8-hour shifts - use shift 1-shift 2 and shift 3 boxes IEPEOF-03 I Rev. 10 I Page 19 of 27
c c ATTACHMENT 10.6 Page 2 of 4 TECHNICAL SUPPORT CENTER (TSC) FOUR DAY WORK SCHEDULE Position Shift Time* Date Date Date Date Facility Administrative Assistants (2) Name Name Name Name 2
3 1
2 3
Electrical Engineer Name Name Name Name 2
3 Mechanical Engineer Name Name Name Name 2
3 Emergency Repair Director Name N Name Name 2
3 ERFIS Maintenance Name Name Name Name 2
3
- Shift times may vary - ILe., (2) 12-hour shifts, (3) 8-hour shifts If (2) 12-hour shifts - use shift 1-shift 2 boxes If (3) 8-hour shifts - use shift 1-shift 2 and shift 3 boxes IEPEOF-03 I Rev. 10 I Page 20 of 27l
c (c c ATTACHMENT 10.6 Page 3 of 4 TECHNICAL SUPPORT CENTER (TSC) FOUR DAY WORK SCHEDULE Position Shift Time* Date Date Date Date EmergencySecurityTeam Name Name Name Name Leader 1 2
3 Technical Analysis Director Name Name Name Name 2
3 NRC Communicator Name Name Name Name 2
3 SEC Administrative Assistant Name Name Name Name 2
3 Support Svs. Coordinator Name Name Name Name 2
3
- Shift times may vary - i.e., (2) 12-hour shifts, (3) 8-hour shifts If (2) 12-hour shifts - use shift 1-shift 2 boxes If (3) 8-hour shifts - use shift 1 shift 2 and shift 3 boxes I EPEOF-03 I Rev. 10 I Page 21 of 271
( ( C ATTACHMENT 10.6 Page 4 of 4 TECHNICAL SUPPORT CENTER (TSC) FOUR DAY WORK SCHEDULE Position Shift Time* Date Date Date Date Others:0 ;- ame:--Nm~1i: X aeNm O :Nam 1 .I Name I II Name Name 1
2 3
_____ - Name Name Name Name 2
3 Name Name Name Name 2
3 Name Name Name Name 2
3 N-pame Name Name Name 2
3
- Shift times may vary - ILe., (2)12-hour shifts, (3)8-hour shifts If (2)12-hour shifts - use shift 1-shift 2 boxes If (3)8-hour shifts - use shift 1-shift 2 and shift 3 boxes EPEOF-03 Rev. 10 Page 22 of 27
ATTACHMENT 10.7 Page 1 of 1 ACCIDENT ASSESSMENT ROOM RECOMMENDED LAYOUT Accident Assessment Room 422 Storaize Cabinets NRC ETS Phone (1)
To TSC Command Room I EPEOF-03 I Rev. 10 I Page 23 of 27
ATTACHMENT 10.8 Page 1 of 1 SUPPORT SERVICES ROOM RECOMMENDED LAYOUT Support Services Room 420 (Library)
Study Cubicles Storage Room Storage Work Lockers Station I
. ALE=
To TSC Command Room l EPEOF-03 I Rev. 10 I Page 24of27
ATTACHMENT 10.9 Page 1 of 1 ENVIRONMENTAL & RADIOLOGICAL CONTROL SUPPORT ROOM RECOMMENDED LAYOUT ENVIRONMENTAL AND RADIOLOGICAL CONTROLS SUPPORT ROOM ROOM 423
<44 SHOWER STORAGE CABINETS l 'l TO TSC COMMAND ROOM EPEOF-03 Rev. 10 l Page 25 of 27
ATTACHMENT 10.10 Page 1 of 1 TSC NRC SUPPORT ROOM RECOMMENDED LAYOUT TSC NRC Support Room 421 Storage Cabinets I [NRC ETS Phones (2) l To TSC Command Room l EPEOF-03 l Rev. 10 l Page 26of27
ATTACHMENT 10.11 Page 1 of 1 ADMINISTRATIVE AND LOGISTICS MANAGER (A&LM) QUICK START GUIDE NOTE: Blanks are provided for place keeping /'s only, logs are the official record.
This is a summary level guide and does not replace the procedure steps.
- 1. Sign-in on the facility sign-in board. Ensure copiers, fax machines, computers, phones are operable.
- 2. If Dialogic was used for callout, upon arrival at the Facility, notify Dialogic.
- 3. Track EOF/TSC augmentation using Attachment 10.1, EOF Sign-in Roster and Attachment 10.5, TSC Sign-in Roster.
- 4. Assign an A&LM staff member to report to the TSC to verify set-up of the Accident Assessment Room, Support Services Room and the Environmental & Radiation Control (E&RC) Room Recommended Layout per Attachment 10.7, Attachment 10.8 and Attachment 10.9.
- 6. Coordinate access and fitness for duty activities with the ESTL.
- 7. Request assistance from the ESTL for assigning an individual as Evacuation Assembly Area Leader.
- 8. At time of EOF activation, synchronize clocks with the Emergency Response Facility Information System (ERFIS).
- 9. Establish an EOF overflow facility, if required.
- 10. Ensure that appropriate access controls (e.g., doors locked, guard stationed) for the EOF/TSC have been instituted.
- 11. Receive plant status briefing. Conduct briefing as appropriate with staff located in the EOF and TSC.
- 12. Notify the Emergency Response Manager as to readiness to activate.
- 13. Refer to procedure steps.
EPEOF-03 I Rev. 10 Page 27 of 27
aJ Progress Enegy H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 2 PART 5 EPEOF-05 RADIOLOGICAL CONTROL MANAGER REVISION 7 I EPEOF-05 I Rev.7 l Page 1 of 11
SUMMARY
OF CHANGES PRR 116604 STEP # REVISION COMMENTS Entire Procedure Re-formatted to comply with AP-007 procedure format Step 8.5.3.3.e Deleted step for managing "facility habitability".
Quick Start Guide Moved quick start guide to Attachments Deleted sentence 2 of Step 9 to uassess eating/drinking conditions for EOFITSC..."
EPEOF-05 Rev. 7 Page 2of 11
TABLE OF CONTENTS SECT ION PAGE 1.0 PURPOSE............................................................................................................4
2.0 REFERENCES
.....................................................................................................4 3.0 RESPONSIBILITIES............................................................................................4 4.0 PREREQUISITES ......................................... 4 5.0 PRECAUTIONS AND LIMITATIONS .......................................... 4 6.0 SPECIAL TOOLS AND EQUIPMENT .......................................... 5 7.0 ACCEPTANCE CRITERIA .......................................... 5 8.0 INSTRUCTIONS ......................................... 5 9.0 RECORDS ......................................... 9 10.0 ATTACHMENTS ......................................... 9 10.1 Protective Action Recommendations ............ ............................. 10 10.2 Radiological Control Manager (RCM) Quick Start Guide ................................... 11 IEPEOF-05 I Rev. 7 l Page of3 1
1.0 PURPOSE This procedure describes the functional responsibilities and procedure steps for the Radiological Control Manager (RCM).
2.0 REFERENCES
2.1 As per EPEOF-00.
3.0 RESPONSIBILITIES 3.1 Manage the radiological control activities in the Emergency Operations Facility (EOF).
3.2 Maintain awareness of meteorology, dose projections, environmental monitoring, and offsite radiological consequences.
3.3 Recommend protective actions to the Emergency Response Manager (ERM).
NOTE: Sector boundaries are defined by the county/state officials and are represented by landmarks familiar to the public, thus appearing odd-shaped and protruding into the geometric 2-mile, 5-mile and 10-mile radii. Protective Action Recommendations (PARs) for a specific sector should be developed and made based on the requirement for the radius number it defines. PARs intended for the 2-mile radius apply only to those sectors which end in 0 (zero). PARs intended for the 5-mile radius only apply to those sectors, which end in 1. PARS intended for the 10-mile radius apply only to those sectors, which end in 2.
(AR #48223) 3.4 Serve as liaison between the EOF and the Radiological Control Director (RCD) in the Technical Support Center (TSC) and corporate radiation control personnel.
3.5 Conduct ALARA review of engineering review and tasks proposed by the emergency organization.
4.0 PREREQUISITES As per EPEOF-00.
5.0 PRECAUTIONS AND LIMITATIONS As per EPEOF-00.
EPEOF-0I Rev. 7 Page 4 of 11
6.0 SPECIAL TOOLS AND EQUIPMENT N/A 7.0 ACCEPTANCE CRITERIA As per EPEOF-00.
8.0 INSTRUCTIONS 8.1 Upon notification, determine if conditions exist which would prevent immediate occupancy of the EOF and require personnel to report to the Alternate Assembly Area at the Darlington County Emergency Operations Center, 1625 Harry Byrd Highway (Highway 151), Darlington, SC.
8.2 Assess Radiological Control (RC) staff availability. The RC staff includes the Environmental Monitoring Team Leader (Enmon TL), the Dose Projection Team Leader (DPTL), the Environmental Monitoring Teams (Enmon Teams) and the Dose Projection Team (DPT).
8.3 Manage RC activities in the EOF to include:
8.3.1 Source term assessments, 8.3.2 Dose projection calculations, 8.3.3 Offsite radiological consequences (Enmon Teams),
8.3.4 Meteorological data (request each 1-hour, 3-hour, 24-hour, and 3 day forecast).
8.4 Assist with notifications to various state and county agencies regarding evacuation and sheltering.
8.5 Determine the need and availability of offsite assistance.
I EPEOF-0 I Rev.7 Page5of 11
8.6 Ensure that necessary information is posted on displays and status boards.
Including:
8.6.1 Offsite radiological status, 8.6.2 Protective Action Recommendations (PARs), and 8.6.3 10 mile emergency planning zone (EPZ) map, 8.7 Direct issuance of dosimetry as necessary.
8.8 Determine evacuation routes of personnel to and from the plant. All personnel not needed to mitigate the accident or casualty will be evacuated as Zone A-0 evacuees. If decontamination of personnel and vehicles is not currently being conducted at the plant, then decontamination will occur as for other Zone A-0 evacuees.
8.9 Based on plant data, dose projections and meteorology, determine the need for protective sheltering or evacuation, including appropriate routes. Utilize Attachment 10.2, Protective Action Recommendations, initially to determine prioritization.
NOTE: Sector boundaries are defined by the county/state officials and are represented by landmarks familiar to the public, thus appearing odd-shaped and protruding into the geometric 2-mile, 5-mile and 10-mile radii. Protective Action Recommendations (PARs) for a specific sector should be developed and made based on the requirement for the radius number it defines. PARs intended for the 2-mile radius apply only to those sectors which end in 0 (zero). PARs intended for the 5-mile radius only apply to those sectors, which end in 1. PARS intended for the 10-mile radius apply only to those sectors, which end in 2.
(AR #48223) 8.10 Implement EPRAD-03, Dose Projections. This function is delegable to the Dose Projection Team Leader (DPTL). Confer with the DPTL to evaluate results and recommend protective actions. Consider the following:
8.10.1 Plume travel time for evacuation purposes (close-in sheltering vs.
evacuation if the plume is already in route or if there will be a short term high dose period),
8.10.2 Evacuation times vs. plume dose duration, and 8.10.3 Hot spots resulting from plume deposition.
I EPEOF-0 I Rev. 7 l Page6of 116
8.11 Utilize EPCLA-01, Emergency Control and the Protective Action Guides to assist in developing protective action recommendations.
8.12 Determine protective action recommendations (PARs) and recommend to the ERM.
8.12.1 PARs should be developed and notification of PARS should be initiated in < 15 minutes of a General Emergency classification.
8.12.2 IF the event conditions (radiological or meteorological) change resulting in revised PARs, THEN the < 15 minute timeliness standard is applicable.
8.12.3 IF field dose data result in a change in PARs, THEN the < 15 minute time standard for PAR development applies from the time the field data is obtained not from the time the dose projection is completed. (AR
- 48774) 8.13 IF the dose projection is > 1 Rem Total Effective Dose Equivalent or 5 Rem Committed Dose Equivalent to the thyroid, THEN verify calculation of doses beyond the site boundary per EPRAD-03, Dose Projections.
8.14 Notify the DPTL of the status of Phase "A" isolation.
8.15 Obtain offsite radiological data from the Environmental Monitoring Team Leader (Enmon TL). Compare with results from the state and other offsite radiological data. Evaluate abnormal results.
8.16 Periodically confer with the Department of Health & Environmental Control (DHEC) regarding dose projections and environmental monitoring data.
8.17 Compare offsite monitoring results and dose projections against the Emergency Action Levels (EALs) to determine if the results warrant a change in emergency classification. Inform the Emergency Response Manager (ERM).
8.18 As requested by state officials, arrange for analysis of environmental samples by the Brunswick or Harris Plants or the Harris Energy & Environmental Center and for whole body counting and bioassay of affected offsite personnel.
I EPEOF-05 I Rev.7 l Page7of 11
8.19 Consider the administration of potassium iodide (KI) to the Environmental Monitoring (Enmon) Teams if the expected thyroid Committed Dose Equivalent will exceed 25 Rem.
8.19.1 IF radioiodine sample analysis results indicate air activity greater than 8.7E-07 pCi/cc 1-131, THEN potassium iodide should be considered for affected workers. Exposure to radioiodine in this concentration will result in a thyroid dose of approximately 1 Rem for one hour of exposure.
8.20 Inform the ERM to recommend KI administration to the offsite agencies.
8.21 Review and approve the Dosimeter Correction Factor (DCF) Worksheet from EPEOF-06 prepared by the Dose Projections Team Leader (DPTL). The Dosimeter Correction Factor is always ONE unless:
8.21.1 A General Emergency has been declared, AND 8.21.2 All recommended off-site evacuations are complete, AND 8.21.3 A release is in progress.
8.21.4 IF all three conditions are true, THEN the exposure limit for the EnMon Teams shall be reduced by the Dosimeter Correction Factor (DCF) to account for internal dose.
8.22 Route the DCF form to the ERM for approval.
8.23 Approve exposure extensions.
8.24 Review PLP-021, "Chemical Storage, Inventory, Spill and Hazard Communication Program", for items to consider in the event of a chemical spill or accident.
8.24.1 Contact the Environmental Compliance Unit to determine reportability.
8.24.2 Ensure the settling pond is isolated from the discharge canal for spills directed toward storm drains.
8.25 Coordinate shift change with the Administration & Logistics Manager (ALM).
8.26 Develop recovery strategy.
I EPEOF-0 I Rev. 7 l Page8of 11
9.0 RECORDS 9.1 Documentation generated as a result of the performance of this procedure should be forwarded to Emergency Preparedness for retention per EPPRO-01.
10.0 ATTACHMENTS 10.1 Protective Action Recommendations 10.2 Radiological Control Manager (RCM) Quick Start Guide EPEOF-05 I Rev. 7 7 Page 9of 11l
c C. C Attachment 10.1 Page 1 of 1 PROTECTIVE ACTION RECOMMENDATIONS DETERMINATION OF AFFECTED ZONES BASED ON WIND DIRECTION (EVACUATION TIME IN MINUTES)
WINTER WINTER SUMMER WINTER WEEKDAY, WEEKNIGHT WEEKDAY INEEKDAY, FAIR FAIR FAIR ADVERSE WIND FROM AFFECTED ZONES WEATHER WEATHER WEATHER WEATHER North A-0, B-1, B-2, C-1, C-2, D-1, D-2 225 180 210 295 (3380 - 0220)
Northeast A-0, C-1, D-1, D-2, E-2 225 180 210 295 (023° - 067°)
East A-0, D-1, D-2, E-1, E-2 225 180 210 295 (068° - 1120)
Southeast A-0, A-1, A-2, D-2, E-1, E-2 225 180 210 295 (1130 - 157°)
South A-0, A-1, A-2, B-1, B-2, E-1, E-2 225 180 210 295 (1580 - 202°)
Southwest A-0, A-1, A-2, B-1, B-2 225 180 210 295 (2030 - 247°)
West A-0, B-1, B-2, C-1, C-2 225 180 210 295 (2480 - 2920)
Northwest A-0. B-1. B-2. C-1. C-2. D-2 225 180 210 295 (2930 - 3370)
ALL ZONES (10 MILE RADIUS) 240 180 215 315 l EPEOF-0 I Rev. 7 l Page 10 of 11I
Attachment 10.2 Page 1 of 1 RADIOLOGICAL CONTROL MANAGER (RCM) QUICK START GUIDE NOTE: Blanks are provided for place-keeping /s only; logs are the official record.
This is a summary level guide and does not replace the procedure steps.
- 1. Sign-in on the facility sign-in board. Log on the Electronic Display System (EDS).
- 2. If dialogic was used for callout, upon arrival at the Facility, notify Dialogic.
- 3. Obtain briefing from Radiological Control Director (RCD) in the Technical Support Center (TSC) or the relieving RCM.
- 4. Assess radiological control staff availability. Notify additional resources if necessary. Brief radiological control staff.
- 5. Obtain a briefing on the cause of the emergency.
- 7. Obtain wind direction (degrees blowing from/to).
- 8. Determine the source term.
- 9. Check alignment of TSC/EOF ventilation through HEPA system (R-38).
- 10. Prompt dispatch of Environmental Monitoring Teams (Enmon Teams) downwind and verify locations.
- 11. Request updates from the Enmon Team Leader and the Dose Projection Team Leader (DPTL) every 30 minutes.
- 12. Establish contact with the Department of Health & Environmental Control. Refer to the ERO Telephone Directory.
- 13. Refer to procedure steps.
EPEOF-05 Rev. 7 Page 11 of 11
Progmss Energy Use H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 2 PART 5 EPRAD-O1 ENVIRONMENTAL MONITORING REVISION 13 I EPRAD-01 I Rev. 13 l Page 1 of 24
SUMMARY
OF CHANGES PRR 117769 STEP REVISION COMMENTS Step 8.1.3.1.9.i Editorial Correction: Revised redundant step "Open window radiation level Bullet 3 at approximately six inches above ground" to "Closed window radiation level at approximately six inches above ground".
I EPRAD-01 Rev. 13 Page 2 of 24
TABLE OF CONTENTS SECTION PAGE 8.1.1 PURPOSE................................................................................................. 4 8.1.2 RESPONSIBILITIES .................. 4 8.1.3 INSTRUCTIONS........................................................................................ 4 8.1.4 RECORDS............................................................................................... 14 8.1.5 ATTACHMENTS...................................................................................... 14 8.1.5.11 Environmental Data .................. 15 8.1 .5.<2 Personnel Dose Data .......................... 16 8.1 .5.% 3 Iodine Activity With a Frisker .......................... 17 8.1 .5.24 Particulate Activity With a Frisker .......................... 19 8.1 .5.! 5 Collection of Environmental Samples .......................... 21 8.1 .5.E6 Communications Log .......................... 23 8.1 .5.,ir Area Dosimetry Log Sheet .......................... 24 I EPRAD-01 I Rev. 13 l Page 3 of 24
8.1.1 PURPOSE
- 1. This procedure provides instructions for Radiological Assessment and Consequences. This procedure addresses in-plant/on-site monitoring and emergency off-site environmental monitoring.
8.1.2 RESPONSIBILITIES
- 1. The Environmental Monitoring Team Leader (EMTL) is responsible for the direction and completion of the applicable requirements of this procedure by the Environmental Monitoring Teams.
- 2. The Radiological Control Director (RCD) and the Environmental &
Radiation Control (E&RC) Lead are responsible for the direction and completion of the applicable requirements of this procedure by the Radiation Monitoring Teams.
8.1.3 INSTRUCTIONS 8.1.3.1 Environmental Monitoring
- 1. The Emergency Environmental Monitoring teams shall report to the Emergency Operations Facility/Technical Support Center at the declaration of an Alert or higher emergency classification.
- a. Report to Room 420, the Training Building Library. Other areas may be used for mustering, as necessary, to expedite team dispatch.
- 2. Immediate dispatch of the Emergency Environmental Monitoring Teams should be performed as soon as the need arises.
- a. Activation of any facility need not be a precursor for team dispatch.
NOTE: Emergency Exposure limits are outlined in EPOSC-04, Emergency Work Control.
- 3. Obtain a briefing from the Site Emergency Coordinator (SEC) OR Radiological Control Manager (RCM) OR, RCD OR EMTL regarding the following:
- a. Required monitoring data (plume tracking, dose projection confirmation, expanded environmental monitoring, etc.)
- b. Anticipated levels of radiation EPRAD-01 Rev. 13 Page 4 of 24
8.1.3.1 Environmental Monitoring (Continued)
- c. Suggested routes/sample points,
- d. Required protective gear
- e. Required dosimetry, TLD, and
- f. Exposure limits allowed.
- 4. Obtain necessary calibrated monitoring and support equipment from designated areas:
- a. Environmental Monitoring emergency monitoring kits are located in the mechanical equipment room in the EOFJTSC.
- The Environmental Monitoring team will ensure that R-38 ventilation has been switched from "Auto" to "Hand".
- b. The portable emergency generators are located in the auto maintenance facility (Building 440 east of the GET Bldg.)
- 5. Emergency Environmental Monitoring off site should proceed as follows:
- a. Obtain survey vehicles and emergency kits as needed.
- b. Verify gas is available for survey vehicles and emergency generators.
- c. Make quick visual check of the Emergency kit inventory.
- Verify calibration dates on survey instruments and air samplers.
- Battery check instruments I EPRAD-01 I Rev. 13 l Page 5 of 24l
8.1.3.1 Environmental Monitoring (Continued)
- 6. Verify radio communications with the EMTL via channel 1-A. Range of the Environmental radios is approximately 20 miles.
- a. Turn radio on using the "Vol-Off' knob.
- b. USLF-t S t" for self test will appear, when finished a beep will be heard.
- c. Verify channel 1-A is indicated. IF not, THEN press the up or down arrows until the 1-A appears.
- d. To talk, key the radio, wait for the tone, then speak.
- 7. Issue dosimetry to each team member. Record TLD and SRPD numbers on Attachment 8.1.5.2, Personnel Dose Data.
- 8. Test start emergency generators to ensure proper operation.
- Start outside building to avoid carbon monoxide hazard.
- 9. Load air samplers with Iodine Cartridge(Silver Zeolite) and a particulate filter. The rough surface of the filter paper should face the open side of the filter.
- Charcoal iodine cartridge may be used in drills/exercises.
- 10. Load emergency kits and generators into survey vehicle(s).
- a. The Potassium Iodide (KI) for the remote facility emergency kit is located in the locked cabinet with the laptop computers.
- b. For an actual radiological event, retrieve the KI from the locked cabinet and place in the emergency kit.
I EPRAD-01 I Rev. 13 l Page6of24
8.1.3.1 Environmental Monitoring (Continued)
CAUTION Prior to entering the plume, vehicle ventilation should be turned to the recirculation mode or turned off to minimize personnel exposure and internal contamination of the vehicle.
- 11. Locate the plume or confirm off-site doses as follows.
- a. Obtain current information from the EMTL.
- Wind direction
- Initial survey location
- Expected radiation levels
- Protective equipment required
- b. Travel downwind to initial survey location observing the compass heading.
- c. Maintain contact with EMTL at least every 30 minutes via radio or phone.
- Attachment 8.1.5.6, Communications Log, may be used to document communications.
- If desired, the EMTL may maintain all communications records.
I EPRAD-01 I Rev. 13 l Page 7 of 24
8.1.3.1 Environmental Monitoring (Continued)
- d. At each designated location, travel at a right angle to the reported wind direction using the most convenient roadway.
NOTE: A micro-Rem survey instrument or equivalent may be required to detect small releases.
- Travel into the plume, observing odometer and compass readings that coincide with the entrance, maximum, and exit radiation levels as indicated by survey meter.
- Maintain survey instruments on and near a window or windshield.
- Drive slowly to ensure accurate readings and locations.
- Report readings greater than or equal to 0.2 mRem/hr to the EMTL.
- e. Repeat survey traveling in the opposite direction.
- f. Proceed to the location of the maximum dose rate and collect, as a minimum, a 20 ft3 air sample. {RNP RAN01-0164; NRC Amendment No. 192: PASS Elimination).
NOTE: The sample period is based on collecting sufficient volume to attain the sensitivity necessary to detect the radioactive concentration. A ten (10) minute air sample at 2 scfm flow rate provides sufficient volume to meet the requirement to measure/detect 1.OE-07 pCi/cc for radioiodines when using the appropriate curve. {RNP RA/01-0164; NRC Amendment No. 192: PASS Elimination)
- g. Place the air sampler so that the exhaust does not stir up loose contamination which would interfere with obtaining a representative sample.
- h. Note the sample start and stop times to the nearest whole minute.
- If no suitable timing device is available, contact the EMTL for "marks" on start and stop times.
EPRAD-01 Rev. 13 Page 8 of 24
8.1.3.1 Environmental Monitoring (Continued)
NOTE: If NO significant difference is noted in the open window and closed window readings, this indicates that the plume is overhead. If there is a significant difference this indicates that the plume is at ground level.
- i. While the air sample is being drawn, perform the following:
- Closed window radiation level at approximately waist level (1 meter from ground).
- Open window radiation level at approximately waist level (1 meter from ground).
- Closed window radiation level at approximately six inches above ground.
- Open window radiation level at approximately six inches above ground.
- Record dose rates in the Radiation Levels section on Attachment 8.1.5.1, Environmental Data.
- j. Periodically read dosimeters AND report any off-scale readings to the EMTL immediately.
- k. Proceed to a location outside the plume.
I. Remove the particulate filter and iodine cartridge from the air sampler and place in separate, clean plastic bags.
- Use tweezers or gloves to prevent cross contamination.
- Mark the bags with sample start/stop times, sample flow rate, activity in ccpm, ambient radiation levels, date, location, volume, and initials of team member.
I EPRAD-01 I Rev. 13 l Page 9 of 24
8.1.3.1 Environmental Monitoring (Continued)
- m. Conduct a field estimate of the airborne iodine activity AND the airborne particulate activity using a frisker type instrument with pancake probe (such as LM-177/44-9 combination) as follows:
- Move to a relatively low background area then measure AND note the background radiation levels.
- Measure the initial activity of the iodine cartridge by placing the probe on contact with each side of the bag AND note the highest reading.
- Determine the corrected counts per minute (ccpm) of the iodine cartridge by subtracting the background reading from the initial sample reading.
- Record the ccpm in the blank for the initial cartridge reading on Attachment 8.1.5.1.
NOTE: If the activity of the second measurement is within 25% of the initial measurement for the iodine cartridge, then it should be presumed that radioiodines are present, pending isotopic analysis.
- Wait for five minutes to allow the cartridge to off-gas.
- Repeat the measurement process for the iodine cartridge on contact with each side of the bag
- Record the ccpm in the blank for the final cartridge reading on Attachment 8.1.5.1.
- n. Repeat the measurement process for the particulate filter.
- Record the ccpm values for initial particulate reading and the final particulate reading on Attachment 8.1.5.1 as appropriate.
O. Report field estimates (marked with an asterisk *) from Attachment 8.1.5.1 to the EMTL for entry into the dose projections program.
EPRAD-01 I Rev. 13 Page 10 of 24
8.1.3.1 Environmental Monitoring (Continued)
- p. Determine the estimated radioiodine airborne activity (estimated 1-131) in pCi/cc using the highest calculated sample activity (ccpm) and the calculated sample volume from the chart on Attachment 8.1.5.3, Iodine Activity with a Frisker AND record the results in pCi/cc in the Airborne Levels section of Attachment 8.1.5.1.
- q. Report estimated 1-131 activity of 8.7 E-07 pCi/cc or greater to the EMTL to aid in evaluation of field protective action considerations for team members.
- r. Determine the estimated particulate activity in pCi/cc using the highest calculated sample activity (ccpm) and the calculated sample volume from the chart on Attachment 8.1.5.4, Particulate Activity with a Frisker AND record the results in pCi/cc in the Airborne Levels section of Attachment 8.1.5.1.
- s. After appropriate samples are collected, return the samples to the site or other designated location for further analysis as directed by the EMTL.
- t. Perform expanded environmental monitoring as assigned by the EMTL.
- Place additional environmental TLDs as directed by the EMTL. Environmental Monitoring Procedures contain locations for TLDs and routine monitoring.
Attachment 8.1.5.7 contains the log sheet for TLD locations.
- 12. Collect Environmental samples as directed by the EMTL.
- a. Attachment 8.1.5.5, Collection of Environmental Samples establishes the method for collecting various liquid, soil, and vegetation samples.
- b. Environmental samples will be collected as conditions permit.
- c. Additional sampling instructions, where required, should be requested from the EMTL.
l EPRAD-01 I Rev. 13 l Page 1 of24
8.1.3.1 Environmental Monitoring (Continued)
- d. All samples collected should be labeled as follows:
- sample type,
- location,
- date and time,
- activity upon collection,
- initials and team designation of sample collector.
- e. Deliver samples to the designated location as directed by the EMTL.
- Ensure samples are properly labeled and the sample container is not externally contaminated. Sample may be placed in another "clean" bag/container.
- Brief the sample recipient/courier on the radiological conditions of the samples.
8.1.3.2 In-Plant/On-site Radiological Monitoring
- 1. Obtain necessary calibrated monitoring and support equipment from designated areas.
- a. Radiation monitoring equipment for in-plant/on-site monitoring is located in the OSC storage location.
- b. Communications equipment available for use includes radios, cell phones, and the public address system.
- 2. For Damage Control Teams entries, observe the following:
- a. Use surveying and sampling practices as per the normal health physic practices.
- Normal plant maps may be used for documentation of all surveys and air samples.
- b. Under emergency conditions, monitor radiation levels continuously while proceeding to the requested locations.
- Document any unanticipated high radiation levels incurred while in route.
I EPRAD-01 I Rev. 13 l Page 12 of 24
8.1.3.2 In-Plant/On-site Radiological Monitoring (Continued)
- c. Report any unanticipated high radiation levels incurred, while in route, to the E&RC Lead.
- d. Samples are to be counted in the Chemistry Lab if available.
- Assure adequate integrity of sample containers and strict handling to avoid contamination of the facilities.
- All samples of greater than 2 Rem/hr will be handled as Very High Level Radioactive Samples (EPRAD-02, Processing Very High Level Radioactive Samples).
- If Robinson facilities are not available consider:
- The use of other Progress Energy sites, or
- Request State/Federal assistance through the State of South Carolina.
- 3. Habitability will meet the following criteria unless other wise directed by the RCD.
- a. Less than 5 mRem/hr direct radiation,
- b. Less than 1000 dpm/1 OOcm2 contamination,
- c. Less than 0.25 DAC airborne.
- 4. Perform surveys as per normal health physics practices in all areas which must remain habitable. Attachment 8.1.5.7 contains a log sheet for area TLD locations. Consideration should be given to placing TLDS in the following areas:
- a. OSC
- b. TSC
- c. EOF
- d. Assembly Areas
- e. Machine Shops
- f. Counting Room
- g. Administrative Building I EPRAD-01 I Rev. 13 l Page 13 of 24
8.1.3.2 In-Plant/On-site Radiological Monitoring (Continued)
- 5. As emergency facilities become inhabited, provisions for personnel monitoring at ingress/egress points must be set up in concert with Security Access Control.
- a. See EPSPA-00, Site Protective Actions, for details on Access Control.
8.1.4 RECORDS
- 1. Forward documentation generated during an emergency or drill/exercise to the Emergency Preparedness Staff.
- Attachments/documentation generated during an emergency will be maintained in the plant vault as vital records.
- Attachments/documentation generated during a drill/exercise may be maintained in the EP files.
8.1.5 ATTACHMENTS 8.1.5.1 Environmental Data 8.1.5.2 Personnel Dose Data 8.1.5.3 Iodine Activity With a Frisker 8.1.5.4 Particulate Activity With a Frisker 8.1.5.5 Collection of Environmental Samples 8.1.5.6 Communications Log 8.1.5.7 Area Dosimetry Log Sheet I EPRAD-01 l Rev. 13 l Page 14 of 24
ATTACHMENT 8.1.5.1 Page 1 of 1 ENVIRONMENTAL DATA Date: Log Page __ of FIELD TEAM DATA.
Team ID: Team Members:
Survey Instrument Model/Serial #: Survey Instrument Model/Serial #:
Air Sampler Model/Serial #: Frisker Model/Serial #:
RADIATION LEVELS Instrument Used: l Dose Rates (mrem/hr) l Time Location/Coordinates 1 Meter* 1 Meter 6 Inch* 6 Inch (degrees/miles) Closed Window Open Window Closed Window Open Window AIRBORNE LEVELS Time Location/Coordinates Sample Initial Cartridge Final Cartridge Cartridge" (degrees/miles) Volume (ccpm) (ccpm)* (PC'/cc) milnutes x Initial Particulate Final Particulate Particulate Flow Rate) (ccpm) (ccpm) (PCi/cc)
C*
P C*
=____LP C*
P
- Report closed window (gamma dose rate) readings and iodine cartridge results in ccpm to the EMTL for entry into the Dose Projections Program.
- Report estimated 1-131 activity of 8.7E-07 pCi/cc or greater to the EMTL to aid in evaluation of field protective action considerations.
I EPRAD-01 I Rev. 13 l Page 15 of 24
ATTACHMENT 8.1.5.2 Page 1 of 1 PERSONNEL DOSE DATA NAME - EMT# 1 TLD # I SRPD# l INITIAL DOSIMETER l FINAL DOSIMETER
_I i ! READING (mRem) I READING (mRem) 9 1- 4- t 4-9 t 1- 4-9 1- 1- 4-9 1- 1- 4-9 t 1-9 4- 4- 4-9 4- 4- 1- 4-t 4- 4- 1- 4-9 4- 4- 4- 4-9 4- 4- 4- 4-9 4- 4- 1- 4-9 4- 4- 4- 4-9 4- 4- 4-9 4- 4- I- 4-9 4- 4- 4- 4-9 4- 4- 4- 4-9 4- 4- 4- 4-9 4- 4- 4- 4-9 4- 4- 4- 4-l EPRAD-01 I Rev. 13 l Page 16 of 24
(7 C ATTACHMENT 8.1.5.3 Page 1of 2 IODINE ACTIVITY WITH A FRISKER TOTAL VOLUME (CUBIC FEET)
CCPM 10 12 15 20 - 25 30 40 50 60 70 80 50 6.5E-08 5.4E-08 4.4E-08 3.3E-08 2.6E-08 2.2E-08 1.6E-08 1.3E-08 1.1 E-08 9.3E-09 8.2E-09 100 1.3E-07 1.1E-07 8.7E-08 6.5E-08 5.2E-08 4.4E-08 3.3E-08 2.6E-08 2.2E-08 1.9E-08 1.6E-08 200 2.6E-07 2.2E-07 1.7E-07 1.3E-07 1.0E-07 8.7E-08 6.5E-08 5.2E-08 4.4E-08 3.7E-08 3.3E-08 300 3.9E-07 3.3E-07 2.6E-07 2.0E-07 1.6E-07 1.3E-07 9.8E-08 7.8E-08 6.5E-08 5.6E-08 4.9E-08 400 5.2E-07 4.4E-07 3.5E 2.6E-07 2.1 E-07 1.7E-07 1.3E-07 1.OE-07 8.7E-08 7.5E-08 6.5E-08 500 6.5E-07 5.4E-07 4.4E-07 3.3E-07 2.6E-07 2.2E-07 1.6E-07 1.3E-07 1.1 E-07 9.3E-08 8.2E-08 600 7.8E-07 6.5E-07 5.2E-07 i 3.9E-07 3.1 E-07 2.6E-07 2.OE-07 1.6E-07 1.3E-07 1.1 E-07 9.8E-08 700 9.2E-07 7.6E-07 6.1 E-07 4.6E-07 3.7E-07 3.1 E-07 2.3E-07 1.8E-07 1.5E-07 1.32-07 1.12-07 800 1.OE-06 8.7E-07 7.0E-07 5.2E-07 4.2E-07 3.5E-07 2.6E-07 2.1 E-07 1.7E-07 1.5E-07 1.3E-07 900 1.2E-06 9.8E-07 7.8E-07 5.9E-07 4.7E-07 3.9E-07 2.9E-07 2.4E-07 2.0E-07 1.7E-07 1.5E-07 1000 1.3E-06 1.1 E-06 8.7E-07 6.5E-07 5.2E-07 4.4E-07 3.3E-07 2.6E-07 2.2E-07 1.9E-07 1.6E-07 1500 2.0E-06 1.6E-06 1.3E-06 9.8E-07 7.8E-07 6.5E-07 4.9E-07 3.9E-07 3.3E-07 2.8E-07 2.5E-07 2000 2.6E-06 2.2E-06 1.7E-06 1.3E-06 1.OE-06 8.7E-07 6.5E-07 5.2E-07 4.4E-07 3.7E-07 3.3E-07 2500 3.3E-06 2.7E-06 2.2E-06 1.6E-06 1.3E-06 1.1 E-06 8.2E-07 6.5E-07 5.4E-07 4.7E-07 4.1 E-07 3000 3.9E-06 3.3E-06 2.6E-06 2.0E-06 1.6E-06 1.3E-06 9.8E-07 7.8E-07 6.5E-07 5.6E-07 4.9E-07 3500 4.6E-06 3.8E-06 3.1 E-06 2.3E-06 1.8E-06 1.5E-06 1.1 E-06 9.2E-07 7.6E-07 6.5E-07 5.7E-07 4000 5.2E-06 4.4E-06 3.5E-06 2.6E-06 2.1 E-06 1.7E-06 1.3E-06 1.OE-06 8.7E-07 7.5E-07 6.5E-07 5000 6.5E-06 5.4E-06 4.4E-06 3.32-06 2.6E-06 2.2E-06 1.6E-06 1.3E-06 1.1 E-06 9.3E-07 8.2E-07 6000 7.8E-06 6.5E-06 5.2E-06 3.9E-06 3.1 E-06 2.6E-06 2.0E-06 1.6E-06 1.3E-06 1.1E-06 9.8E-07 7000 9.2E-06 7.6E-06 6.1 E-06. 4.6E-06 3.7E-06 3.1 E-06 2.3E-06 1.8E-06 1.5E-06 1.3E-06 1.1 E-06 8000 1.OE-05 8.72-06 7.02-06 5.2E-06 4.2E-06 3.5E-06 2.6E-06 2.1 E-06 1.7E-06 1.5E-06 1.3E-06 9000 1.2E-05 9.8E-06 7.8E-06 5.9E-06 4.7E-06 3.9E-06 2.9E-06 2.4E-06 2.0E-06 1.7E-06 1.5E-06 10000 1.3E-05 1.1 E-05 8.7E-06 6.5E-06 5.2E-06 4.4E-06 3.3E-06 2.6E-06 2.2E-06 1.9E-06 1.6E-06 15000 2.0E-05 1.6E-05 1.3E-05 9.8E-06 7.8E-06 6.5E-06 4.9E-06 3.9E-06 3.3E-06 2.8E-06 2.5E-06 20000 2.6E-05 2.2E-05 1.7E-05 1.3E-05 1.0E-05 8.7E-06 6.5E-06 5.2E-06 4.4E-06 3.7E-06 3.3E-06 25000 3.3E-05 2.7E-05 2.2E-05 1.6E-05 1.3E-05 1.1 E-05 8.2E-06 6.5E-06 5.4E-06 4.7E-06 4.1 E-06 30000 3.9E-05 3.3E-05 2.6E-05 -2.0E-05 1.6E-05 1.3E-05 9.8E-06 7.8E-06 6.5E-06 5.6E-06 4.9E-06 35000 4.6E-05 3.8E-05 3.1 E-05 2.3E-05 1.8E-05 1.5E-05 1.1 E-05 9.2E-06 7.6E-06 6.5E-06 5.7E-06 40000 5.22-05 4.4E-05 3.5E-05 2.6E-05 2.1 E-05 1.7E-05 1.3E-05 1.OE-05 8.7E-06 7.5E-06 6.5E-06 50000 6.5E-05 5.4E-05 4.4E-05 3.3E-05 2.6E-05 2.2E-05 1.6E-05 1.3E-05 1.1 E-05 9.3E-06 8.2E-06 Estimated 1-131 activity in air versus corrected counts per minute (CCPM) using Ludlum 177 with pancake probe. The average detector efficiency (DE) is 0.0015.
Cartridge collection efficiency (CCE) Is 0.90. The formula for calculating 1-131 activity IsPCi/cc = CCPM Volume (cc) x DE. x CCE x 2.22 E6 (DPM/pCi) l EPRAD-01 I Rev. 13 l Page 17 of 24 l
C C- (
ATTACHMENT 8.1.5.3 Page 2 of 2 IODINE ACTIVITY WITH A FRISKER U
LI 10G ion l00mm 10000 1momn ccpm Estimated 1-131 activity in air versus corrected counts per minute (CCPM) using Ludlum 177 with pancake probe. The average detector efficiency (DE) is 0.0015.
Cartridge collection efficiency (CCE) Is0.90. The formula for calculating 1-131 activity is pCi/cc = CCPM Volume (cc) x DE. x CCE x 2.22 E6 (DPM/pCi l EPRAD-01 Rev. 13 1 Page 18 of 24 l
( c C ATTACHMENT 8.1.5.4 Page 1 of 2 PARTICULATE ACTIVITY WITH A FRISKER TOTAL VOLUME 'CUBIC FEET CCPM 10 12 15 20 25 30 40 50 60 70 80 50 8.4E-10 7.0E-10 5.6E-10 4.2E-10 3.3E-10 2.8E-10 2.1E-10 1.7E-10 1.4E-10 1.2E-10 1.OE-10 100 1.7E-09 1.4E-09 1.1E-09 8.4E-10 6.7E-10 5.6E-10 4.2E-10 3.3E-10 2.8E-10 2.4E-10 2.1 E-10 200 3.3E-09 2.8E-09 2.2E-09 1.7E-09 1.3E-09 1.1 E-09 8.4E-10 6.7E-10 5.6E-10 4.8E-10 4.2E-10 300 5.OE-09 4.2E-09 3.3E-09 -2.5E-09 2.OE-09 1.7E-09 1.3E-09 1.OE-09 8.4E-10 7.2E-1 0 6.3E-10 400 6.7E-09 5.6E-09 4.5E-09 3.3E-09 2.7E-09 2.2E-09 1.7E-09 1.3E-09 1.1 E-09 9.6E-1 0 8.4E-10 500 8.4E-09 7.OE-09 5.6E-09 4.2E-09 3.3E-09 2.8E-09 2.1 E-09 1.7E-09 1.4E-09 1.2E-09 1.OE-09 600 1.OE-08 8.4E-09 6.7E-09 5.OE-09 4.OE-09 3.3E-09 2.5E-09 2.OE-09 1.7E-09 1.4E-09 1.3E-09 700 1.2E-08 9.8E-09 7.8E-09 5.9E-09 4.7E-09 3.9E-09 2.9E-09 2.3E-09 2.OE-09 1.7E-09 1.5E-09 800 1.3E-08 1.1 E-08 8.9E-09 6.7E-09 5.4E-09 4.5E-09 3.3E-09 2.7E-09 2.2E-09 1.9E-09 1.7E-09 900 1.5E-08 1.3E-08 1.OE-08 7.5E-09 6.OE-09 5.OE-09 3.8E-09 3.OE-09 2.5E-09 2.2E-09 1.9E-09 1000 1.7E-08 1.4E-08 1.1 E-08 ,`:8.4E-09 6.7E-09 5.6E-09 4.2E-09 3.3E-09 2.8E-09 2.4E-09 2.1 E-09 1500 2.5E-08 2.1 E-08 1.7E-08 1.3E-08 1.OE-08 8.4E-09 6.3E-09 5.OE-09 4.2E-09 3.6E-09 3.1 E-09 2000 3.3E-08 2.8E-08 2.2E-08 1.7E-08 1.3E-08 1.1 E-08 8.4E-09 6.7E-09 5.6E-09 4.8E-09 4.2E-09 2500 4.2E-08 3.5E-08 2.8E-08 2.1E-08 1.7E-08 1.4E-08 1.OE-08 8.4E-09 7.OE-09 6.0E-09 5.2E-09 3000 5.0E-08 4.2E-08 3.3E-08 2.5E-08 2.OE-08 1.7E-08 1.3E-08 1.OE-08 8.4E-09 7.2E-09 6.3E-09 3500 5.9E-08 4.9E-08 3.9E-08 2.9E-08 2.3E-08 2.OE-08 1.5E-08 1.2E-08 9.8E-09 8.4E-09 7.3E-09 4000 6.7E-08 5.6E-08 4.5E-08 1 3.3E-08 2.7E-08 2.2E-08 1.7E-08 1.3E-08 1.1 E-08 9.6E-09 8.4E-09 5000 8.4E-08 7.OE-08 5.6E-08 4.2E-08 3.3E-08 2.8E-08 2.1 E-08 1.7E-08 1.4E-08 1.2E-08 1.OE-08 6000 1.OE-07 8.4E-08 6.7E-08 5.OE-08 4.0E-08 3.3E-08 2.5E-08 2.OE-08 1.7E-08 1.4E-08 1.3E-08 7000 1.2E-07 9.8E-08 7.8E-08 5.9E-08 4.7E-08 3.9E-08 2.9E-08 2.3E-08 2.0E-08 1.7E-08 1.5E-08 8000 1.3E-07 1.1 E-07 8.9E-08 6.7E-08 5.4E-08 4.5E-08 3.3E-08 2.7E-08 2.2E-08 1.9E-08 1.7E-08 9000 1.5E-07 1.3E-07 1.OE-07 -.,7.5E-08 6.OE-08 5.OE-08 3.8E-08 3.OE-08 2.5E-08 2.2E-08 1.9E-08 10000 1.7E-07 1.4E-07 1.1 E-07 8.4E-08 6.7E-08 5.6E-08 4.2E-08 3.3E-08 2.8E-08 2.4E-08 2.1 E-08 15000 2.5E-07 2.1 E-07 1.7E-07 1.3E-07 1.OE-07 8.4E-08 6.3E-08 5.0E-08 4.2E-08 3.6E-08 3.1 E-08 20000 3.3E-07 2.8E-07 2.2E-07 --1.7E-07 1.3E-07 1.1E-07 8.4E-08 6.7E-08 5.6E-08 4.8E-08 4.2E-08 25000 4.2E-07 3.5E-07 2.8E-07 2.1 E-07 1.7E-07 1.4E-07 1.OE-07 8.4E-08 7.OE-08 6.OE-08 5.2E-08 30000 5.0E-07 4.2E-07 3.3E-07 2.5E-07 2.OE-07 1.7E 07 1.3E-07 1.OE-07 8.4E-08 7.2E-08 6.3E-08 35000 5.9E-07 4.9E-07 3.9E-07 2.9E-07 2.3E-07 2.OE-07 1.5E-07 1.2E-07 9.8E-08 8.4E-08 7.3E-08 40000 6.7E-07 5.6E-07 4.5E-07 3.3E-07 2.7E-07 2.2E-07 1.7E-07 1.3E-07 1.1 E-07 9.6E-08 8.4E-08 50000 8.4E-07 7.OE-07 5.6E-07 4.2E-07 3.3E-07 2.8E-07 2.1 E-07 1.7E-07 1.4E-07 1.2E-07 1.OE-07 Estimated particulate activity versus corrected counts per minute (CCPM) using Ludlum 177 with pancake probe. The average detector efficiency (DE) is0.10.
Filter collection efficiency (FCE) Is 0.95. The formula for calculating particulate activity is pCi/cc = CCPM Volume (cc) x DE. x FCE x 2.22 E6 (dpm/lCi)
EPRAD-01 Rev. 13 Page 19 of 24]
( c c ATTACHMENT 8.1.5.4 Page 2 of 2 PARTICULATE ACTIVITY WITH A FRISKER 1 r0102-I05 ___
0 ~a.0_ _ _ _ _0 _ _ _ _ _ _ 0 I I - 0El I OOE - --. ... .. IU... .. .i..L1.
Estimated particulate activity versus corrected counts per minute (CCPM) using Ludlum 177 with pancake probe. The average detector efficiency (DE) is 0.10.
Filter collection efficiency (FCE) Is 0.95. The formula for calculating particulate activity is pJCI/cc = CCPM Volume (cc) x DE. x FCE x 2.22 E6 (dpm/fuCi) l EPRAD-01 l Rev. 13 l Page 20 of 24l
ATTACHMENT 8.1.5.5 Page 1 of 2 COLLECTION OF ENVIRONMENTAL SAMPLES SAMPLE TYPE PRECAUTIONS METHODS AND GUIDELINES I. I SOIL 1. Assume ALL samples are 1. When possible, select an open, level area contaminated and handle using for sampling. Avoid areas that are techniques to prevent cross- shielded by buildings, trees, bushes, or contamination. dense vegetation. Avoid areas that show
- 2. Do not seal the container of soil evidence of erosion water runoff or poor UNTIL the sample is delivered drainage.
to the sample control point for 2. Clear an area 5"x 5" of rocks, litter, and transport/analysis. This will non-soil items.
permit radon gases to off-gas. 3. Using a scoop or trowel, evenly dig out enough soil (including any vegetation) from the 5" x 5" area to a depth of 1" (-5 cm).
This should yield a sample of -400 ml.
- 4. Place soil in container.
- 5. Label sample container.
POTABLE WATER 1. Assume ALL samples are 1. Collect at least 1-gallon sample of drinking contaminated and handle using water.
techniques to prevent cross- 2. Flush sample lines and rinse sample contamination. container before filling.
- 3. Cap and label sample container.
SURFACE WATER 1. Assume ALL samples are 1. Surface water samples from the plant contaminated and handle using cooling water and discharge structures may techniques to prevent cross- be collected from the automatic samples contamination. (SW 40 & 41, refer to EMP-001, Attachment 11.1, for sample location.)
- 2. If samplers are out-of-service, obtain a grab sample from boat, bridge, or shore.
Note: More specific sampling instructions will be provided by the EMT Leader.
- 3. If possible collect 1-gallon sample and secure tightly.
- 4. Label sample container.
EPRAD-01 Rev. 13 Page 21 of 24
ATTACHMENT 8.1.5.5 Page 2 of 2 COLLECTION OF ENVIRONMENTAL SAMPLES SAMPLE TYPE PRECAUTIONS METHODS AND GUIDELINES SNOW & ICE 1. Assume ALL samples are 1. Obtain the equivalent of 500 ml liquid of contaminated and handle using snow or ice samples for analysis. This may techniques to prevent cross- require collection in 4-liter sample contamination. containers.
- 2. Label the sample container.
VEGETATION & 1. Assume ALL samples are 1. Obtain small bag (-1 2"xl 2") samples of CROPS contaminated and handle using " broad leaf vegetables and/or other techniques to prevent cross- vegetation as directed by the EMT Leader.
contamination. 2. IF milk is to be collected, THEN collect 1000 gram samples of pasture grass as close to the roots as possible without including dirt in the sample.
- 3. If possible, tree leaves should be sampled from outermost part of tree.
- 4. Large, leafy vegetation is better than small.
- 5. Ground covers should be selected from open areas.
- 6. Label the sample container.
MILK 1. Assume ALL samples are 1. Sampling should begin the day after an contaminated and handle using atmospheric release of radioactive material techniques to prevent cross- and every 2 days thereafter until levels of I-contamination. 131 return to normal.
Note: Peak lodine(I-131) activity is expected on Day 3 following the release.
- 2. If available, collect at minimum a 1-gallon sample from a thoroughly mixed tank OR from a single milk cow.
- 3. Collect approximately 1000 grams of pasture grass and/or feed whenever milk samples are collected.
- 4. Label the sample containers.
I EPRAD-01 I Rev. 13 l Page 22 of 24
ATTACHMENT 8.1.5.6 Page 1of 1 COMMUNICATIONS LOG Location: Device:
Include Telephone # or Radio Call Sign Date:
Time Call Call Remarks (include data transmitted and From To decisions or recommendations made)
.4 4-
+ 4 +
4- .4 4-1- .4 .4 1- .4 1-4- 4 +
4- 4- 4-1- .4 1-4- .4 4-4- + +
4- 4- 4-4- 4- 4-I 4- 4-This log is to be routed to the Radiological Control Manager.
I EPRAD-01 Rev. 13 l Page 23 of 24l
ATTACHMENT 8.1.5.7 Page 1of 1 AREA DOSIMETRY LOG SHEET Location Dosimeter # Time/Date of ITime/Date of I Comments I _ Placement Retrieval I I .4 4- .4 I 4 1-4 4 4- .4 4 4 4. 4 I .4. 4- 4
£ .4 4- .4 4 .4 1- .4 4 4 + 4 1 .4 + 4 1 .4 4. 1 4 .4 .4I 4 4 .4 4 4 4 + 4 4 .4 4 4 4 .4 .4 4 4 4 4 4 4 4 4 4 1 .4 4. 4 4- .4 .4 4 4- 4 4 4 4 .4 4 4 4- .4 .4 4 4- .4 .4 4 IEPRAD-01 I Rev. 13 l Page 24 of 24
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 2 PART 5 EPTSC-04 RADIOLOGICAL CONTROL DIRECTOR REVISION 8 I EPTSC-04 I Rev. 8 l Page 1of 13
SUMMARY
OF CHANGES PRR 98820 SECTION REVISION COMMENTS All Changed layout to match the AP-007 layout Step 8.4.4 Deleted the phrase "as decided by the RCM and ERM" and added step concerning eating and drinking restrictions.
Step 8.8 Added step to determine the frequency for conduct of habitability surveys and to direct the RC Technician to communicate the habitability results. (NCR 106839)
Att 10.1 Moved Quick Start Guide to an Attachment.
I EPTSC-04 Rev. 8 l Page2of 13
TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE............................................................................................................4
2.0 REFERENCES
.....................................................................................................4 3.0 RESPONSIBILITIES............................................................................................4 4.0 PREREQUISITES ........................................ 4 5.0 PRECAUTIONS AND LIMITATIONS ......................................... 4 6.0 SPECIAL TOOLS AND EQUIPMENT ......................................... 4 7.0 ACCEPTANCE CRITERIA ......................................... 4 8.0 INSTRUCTIONS ........................................ 5 9.0 RECORDS ........................................ 11 10.0 ATTACHMENTS ........................................ 11 10.1 Guidelines for Potassium Iodide Administration ........................................ 12 10.2 Radiological Control Director (RCD) Quick Start Guide .................................... 13 I EPTSC-04 Rev. 8 I Page3of 13
1.0 PURPOSE This procedure describes the functional responsibilities and procedure steps for the Radiological Control Director (RCD).
2.0 REFERENCES
2.1 As per EPTSC-00.
3.0 RESPONSIBILITIES 3.1 Manage the radiological control activities in the Technical Support Center (TSC).
3.2 Monitor meteorology, onsite radiological consequences, and dose projections.
3.3 Liaison with the Radiological Control Manager (RCM) in the Emergency Operations Facility (EOF).
3.4 To protect security officers during performance of their duties, inform the Emergency Security Team Leader of changing radiological conditions.
3.5 Ensure that the radiation exposure for off-site emergency personnel is documented as occupational dose. This applies only for those personnel who are assigned emergency responsibilities within the 1400 foot boundary from the centerline of the reactor. (AR #82619).
4.0 PREREQUISITES As per EPTSC-00.
5.0 PRECAUTIONS AND LIMITATIONS As per EPTSC-00.
6.0 SPECIAL TOOLS AND EQUIPMENT N/A 7.0 ACCEPTANCE CRITERIA As per EPTSC-00.
EPTSC-04 I Rev. 8 l Page4of 13
8.0 INSTRUCTIONS NOTE: The Radiation Control (RC) Technician on shift will report to the Superintendent-Shift Operations and support Operations during an emergency.
The technician will continue reporting to the SSO after activation of the Operations Support Center (OSC) unless higher priority actions are required as deemed necessary by the OSC Leader.
8.1 Advise the E&RC Team Lead (either E&RC Supervisor or "lead" technician) of monitoring locations and sample collection points in the plant, collection of required data and assessment of radiological conditions at these points.
8.2 Request in-plant samples to assess plant/fuel conditions.
8.3 E&RC activities should be tracked as a single line item entry on the TSC Mission Status Board. The status of the E&RC activities will be tracked/monitored on the E&RC Personnel Status Board in the OSC and documented in the RCD logs.
(AR #87927) 8.4 Report to the Site Emergency Coordinator (SEC) regarding:
8.4.1 Radiological monitoring and assessment 8.4.2 Radiation exposure control 8.4.3 Team direction & supporting missions 8.4.4 Emergency facility habitability
- TSC/EOF Building eating, drinking, and smoking restrictions will be determined for the entire facility by the RCD. The RCD will promptly communicate the status to the RCM.
8.5 Liaison with Offsite Radiation Control (RC) personnel and the RCM in the EOF.
8.6 Inform the ESTL of changing radiological conditions for security members in the field.
I EPTSC-04 I Rev. 8 l Page 5 of 13l
8.7 Advise the Environmental & Radiation Control (E&RC) Team Supervisor or Lead person regarding:
8.7.1 Prioritizing tasks 8.7.2 Determining protective gear and dosimetry 8.7.3 Development of precautions for the reentry team briefing 8.7.4 Deviations from a full set of anti-contamination clothing 8.7.5 Changes to requirements for protective equipment.
8.8 Determine the frequency for conduct of habitability surveys in the TSC/EOF.
8.8.1 Direct the RC Technician to communicate the habitability conditions in the TSC/EOF by manipulating the lighted facility boards and posting signs as conditions dictate. (NCR 106839) 8.9 Determine the need for on-site protective sheltering or evacuation, along with routes (to and from the plant) based on plant data, dose projections and meteorology.
8.9.1 Recommend site evacuation assembly location.
- 1. Monitor personnel at access points as required.
8.10 Consult the Dose Projection Team Leader (DPTL) in the EOF to determine affected zones in the 10 mile Emergency Planning Zone (EPZ). Assign priorities as necessary.
8.11 Contaminated, injured personnel should be treated on site if possible.
8.12 Direct sampling activities, as necessary, to assist in accident assessment.{RNP RAN01-0164; NRC Amendment No. 1921 8.13 Notify the RCM regarding Phase "A" Isolation.
I EPTSC-04 Rev. 8 l Page6of 13
8.14 Provide guidance to the E&RC Team Supervisor or Lead Person for establishing personnel and vehicle decontamination areas when required.
8.14.1 Determine if an alternate means of transporting personnel from the plant is needed..
8.14.2 Based on wind direction and magnitude of release, determine an appropriate area to set up for vehicle decon.
8.14.3 Determine the proper method of decon and area setup (i.e., masslin wipe down, wash down with soap and water, water supply, water containment, decon supplies, etc.)
8.14.4 Determine release limits.
8.14.5 Consider personnel transport in Progress Energy vehicle(s), and deferring vehicle decon until part of the recovery effort.
8.14.6 If radiation levels on site prohibit adequate decontamination or monitoring these functions may be performed at county operated locations.
- 1. Inform county emergency management officials if this contingency must be used.
8.15 Coordinate with the State and the Nuclear Regulatory Commission (NRC) as required.
8.16 Ensure exposure control and that Special Radiation Work Permits (RWPs) are issued as necessary. Approve exposure extensions.
8.17 Ensure that necessary information is posted on displays and status boards.
Including:
8.17.1 Onsite radiological status 8.17.2 Protective Action Recommendations (PARs) 8.17.3 10 mile emergency planning zone (EPZ) map 8.17.4 TSC Habitability Status.
EPTSC-04 Rev.8 Page7of 13
8.18 Recommend the administration of Potassium Iodide (KI) to Progress Energy personnel and contract employees when the actual or projected Committed Dose Equivalent (CDE) to the thyroid is 25 Rem or greater. Use the guidelines in Attachment 10.1 for determining thyroid dose.
8.18.1 If radiodiodine sample analysis results indicate air activity greater than 8.7E-07 pCi/cc 1-131, then potassium iodide should be considered for affected workers. Exposure to radioiodine in this concentration will result in a thyroid dose of approximately 1 Rem for one hour of exposure. (AR
- 88078) 8.18.2 Determine if KI is required for personnel in buildings designed to maintain habitability such as the Control Room and TSC/EOF building.
8.19 Regulatory limits shall be observed for planned radiation exposures to emergency workers unless the Plant General Manager (PGM), the Radiological Control Director (RCD) or the Site Emergency Coordinator (SEC) authorizes the individual to exceed 5 Rem TEDE in a year.
8.19.1 Document radiation exposure for off-site emergency personnel who are assigned emergency responsibilities within the 1400 foot boundary as occupational dose. (AR #82619)
I EPTSC-04 I Rev. 8 l Page8of13
8.20 Follow these Emergency Worker Dose Guidelines:
NOTE: In all cases, it is the responsibility of each individual, to maintain the total effective dose equivalent ALARA.
Declared pregnant women shall not participate in these actions.
Internal exposures shall be minimized by respiratory protection and contamination controlled by the use of protective clothing.
Entry into High Radiation Areas shall not be permitted unless instrumentation capable of measuring the anticipated radiation levels is provided.
Entry into a High Radiation Area shall require wearing a self-reading dosimeter capable of measuring the expected exposure to be received.
Entry into Radiation Fields of > 100 Rem/hr. shall not be permitted unless specifically authorized by the PGM or RCD. In their absence the SEC shall authorize.
8.20.1 Repair/Reentry efforts may require individuals to enter a hazardous area to protect valuable installations, or to make the facility more secure against events which could lead to radioactivity releases (i.e.,
assessment actions or entry of damage repair parties who are to repair valve leaks or add iodine-fixing chemicals to spilled liquids).
- 1. In such instances, planned dose to emergency workers shall not exceed 10 Rem TEDE to the whole body, 30 Rem to the lens of the eye, or 100 Rem to any other organ including skin and extremities.
EPTSC-04 I Rev. 8 l Page 9 of 13 l
8.20.2 Lifesaving Actions or Protection of Large Population efforts may 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 25 Rem TEDE to the whole body, 75 Rem to the lens of the eye, or 250 Rem to any other organ including skin and body extremities. This applies to:
- 1. The removal of injured persons if the saving of life is possible.
- 2. Entry to prevent conditions that, if left uncorrected, could lead to damage or releases that would probably injure numbers of people on or offsite.
- 3. Justifiable dose limits for situations in which the collective dose avoided by the emergency operation is significantly larger than that incurred by the workers involved.
8.20.3 Actions requiring a dose > 25 Rem shall consider the following in addition:
- 1. Rescue personnel shall be volunteers and shall be instructed about the risks involved. Refer to EPOSC-04, Emergency Work Control.
- 2. Volunteers above the age of 45 shall be selected when possible for the purpose of avoiding unnecessary genetic effects.
8.21 Review PLP-021, "Chemical Storage, Inventory, Spill and Hazard Communication Program", for items to consider in the event of a chemical spill or accident.
NOTE: Contact numbers for the Environmental Compliance Unit are listed in the Emergency Response Organization Phone Book.
8.21.1 Contact the Environmental Compliance Unit to determine reportability.
8.21.2 Ensure the settling pond is isolated from the discharge canal for spills directed toward storm drains.
8.22 Develop recovery strategy.
I EPTSC-04 I Rev. 8 l Page 10 of 13
9.0 RECORDS As per EPTSC-00.
10.0 ATTACHMENTS 10.1 Guidelines for Potassium Iodide Administration 10.2 Radiological Control Director (RCD) Quick Start Guide IEPTSC-04 I Rev. 8 l Page 11 of 13
ATTACHMENT 10.1 Page 1 of 1 GUIDELINES FOR POTASSIUM IODIDE ADMINISTRATION The following formula can be used to determine the concentration of 1-131 that will yield a committed dose equivalent of 25 Rem to the thyroid. The following guidance should be used for considering the administration of KI to on-site personnel. (AR #88078)
Given:
Per ICRP 23, Reference Man breathes 20 liters/minute. During a 24-hour period, Reference Man breathes 2.88E+07 cc (20 1pm x 1440 minutes x 1000 cc).
Per 10 CFR 20 Appendix B, Table 1, Occupational Values, the Inhalation annual limit on intake (ALI) for 1-131 is 50 pCi which yields a committed lifetime dose equivalent of 50 Rem to the thyroid.
RemthyroJd = (uCi/cc 1-131) (2.88E+07cc) (Rem/pCi)
= 8.68e-07 pCi/cc 1-131 or 8.7e-07 pCi/cc 1-131 This value is based on the assumption that the individual is exposed to this concentration for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. An exposure to this concentration for one hour would result in a thyroid dose of -1.041 Rem.
Guidelines and precautions for issuance of KI are contained in EPSPA-03, Administration of Potassium Iodide.
EPTSC-04 Rev. 8 Page 12 of 13
ATTACHMENT 10.2 Page 1 of 1 RADIOLOGICAL CONTROL DIRECTOR (RCD) QUICK START GUIDE NOTE: Blanks are provided for place keeping Vs only, logs are the official record.
This is a summary level guide and does not replace the procedure steps.
- 1. Sign-in on the facility sign-in board, log on Electronic Display System (EDS).
- 2. If dialogic was utilized for callout, upon arrival at the Technical Support Center (TSC), notify Dialogic.
- 3. Obtain a briefing on Plant Status.
- 4. Determine if contaminated individuals have been released from the plant.
- 5. Obtain wind direction (degrees blowing from). Request 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, and 3 day weather forecasts.
- 6. Coordinate with the Radiological Control Manager (RCM) in the Emergency Operations Facility (EOF).
- 7. Determine the E&RC staff available in the emergency facilities, request additional resources as needed.
- 9. Request updates on the E&RC Team status every 30 minutes from an available E&RC Supervisor or assigned "lead" person.
- 11. Notify the SEC of readiness to activate.
- 12. Refer to procedure steps.
I EPTSC-04 I Rev.8 l Page 13of 13
Progress Energy H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 2 PART 5 EPNOT-03 EOF PUBLIC INFORMATION EMERGENCY COMMUNICATOR REVISION 6 I EPNOT-03 I Rev. 6 l Page 1 of 8
SUMMARY
OF CHANGES PRR 101483 SECTION REVISION COMMENTS All Changed layout to match the AP-007 layout Step 8.11 Added step to provide a copy of approved press releases to the NRC Site Response Team for review (NCR #106381) and re-numbered subsequent steps.
Attachment Moved the quick start guide to a new attachment.
10.2 I EPNOT-03 I Rev. 6 P Page2of 8
TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ........................... 4
2.0 REFERENCES
........................... 4 3.0 RESPONSIBILITIES .......................... 4 4.0 PREREQUISITES .......................... 4 5.0 PRECAUTIONS AND LIMITATIONS .......................... 4 6.0 SPECIAL TOOLS AND EQUIPMENT ........................... 4 7.0 ACCEPTANCE CRITERIA ........................... 4 8.0 INSTRUCTIONS .......................... 5 9.0 RECORDS ... 6.......................6 10.0 ATTACHMENTS .. 6 10.1 PRESS RELEASE FLOW CHART .7 10.2 PUBLIC INFORMATION EMERGENCY COMMUNICATOR QUICK START GUIDE.............................................................................................................8 EPNOT-03 I Rev. 6 l Page3of8
1.0 PURPOSE To provide instructions for notifications by the Public Information Emergency Communicator to the Joint Information Center (JIC).
2.0 REFERENCES
2.1 As per EPNOT-00.
3.0 RESPONSIBILITIES 3.1 Formulate press releases and obtain approval from the Emergency Response Manager (ERM).
3.2 Accurately transmit information to the Joint Information Center.
4.0 PREREQUISITES 4.1 As per EPNOT-00.
5.0 PRECAUTIONS AND LIMITATIONS 5.1 As per EPNOT-00.
6.0 SPECIAL TOOLS AND EQUIPMENT N/A 7.0 ACCEPTANCE CRITERIA 7.1 As per EPNOT-00.
EPNOT-03 Rev. 6 1 Page 4 of 8
8.0 INSTRUCTIONS 8.1 REVIEW previous Emergency Notification Forms AND any press releases.
8.2 NOTIFY the EOF Emergency Communicator when you are ready to assume position duties.
8.3 ESTABLISH contact with the Joint Information Center Director when the facility is being manned for activation AND ESTABLISH that the PI-EC will control press release numbering.
NOTE: Attachment 10.1, Press Release Flowchart, describes the process for coordination of press release initiation, approval, and distribution.
8.4 TRANSMIT copies of Emergency Notification Forms AND requested plant information, if not available to the JIC Staff on the Electronic Display System (EDS).
8.4.1 Hard copies of Emergency Notification Forms for faxing may be obtained from the Emergency Communications Staff.
8.5 Once the EOF has been activated, releases should be available to the media following:
8.5.1 A change in emergency classification, OR 8.5.2 A radiological release as a result of the emergency, OR 8.5.3 Other significant events provided to the offsite agencies via an Emergency Notification Form.
8.6 Example press releases (read only format) for use as templates are available in the Emergency Press Release Public Folder.
8.7 Completed draft press releases should be placed in the Draft Press Releases Public Folder.
8.7.1 Hard copies printed for approval should be controlled by marking them "draft" either by word processing or pen and ink.
EPNOT-03 Rev. 6 Page 5 of 8
8.8 OBTAIN approvals for press releases.
8.8.1 The Emergency Response Manager (ERM) must approve the technical content of press releases. Any changes of technical content, after initial approval must be approved by the ERM.
8.8.2 The Company Spokesperson should approve non-technical content of the press release.
- 1. Prior to JIC activation, non-technical content of press releases should be approved by Site Communications or Corporate Communications personnel, time permitting.
8.8.3 Press releases which are entirely non-technical may be formulated by JIC staff and approved by the Company Spokesperson.
- 1. These include facility activation and press briefing times.
8.9 Press releases, which must be faxed to the JIC for approval, should be clearly marked "DRAFT" in the time slot of the release.
8.10 Coordinate with JIC Director to ensure approved press releases are placed in the Approved Press Releases Public Folder.
8.11 Provide a copy of approved press releases to the NRC Site Response Team (when staffed) for review by the Director of Site Operations or designee. (NCR
- 106381) 8.12 Obtain responses for questions from JIC staff.
8.12.1 Keep the EOF Emergency Communicator informed of issues associated with media questions.
- 1. Upon event or drill termination, ensure JIC personnel are informed.
9.0 RECORDS 9.1 As per EPNOT-00.
10.0 ATTACHMENTS 10.1 Press Release Flow Chart 10.2 Public Information Emergency Communicator Quick Start Guide EPNOT-03 I Rev. 6 l Page 6 of 8
ATTACHMENT 10.1 Page 1 of 1 PRESS RELEASE FLOW CHART I EPNOT-03 I Rev. 6 l Page 7 of 8
ATTACHMENT 10.2 Page 1 of 1 PUBLIC INFORMATION EMERGENCY COMMUNICATOR QUICK START GUIDE NOTE: Blanks are provided for place keeping a1ds only, logs are the official record.
This is a summary level guide and does not replace the procedure steps.
- 1. Check equipment status.
- 2. Log on to the LAN network and access the news release folders.
- 3. Review previous emergency notifications and NRC notifications.
- 4. Notify EOF Emergency Communicator when ready to assume duties.
- 5. Refer to procedure.
I EPNOT-03 I Rev. 6 l Page8 of 8
Progress Energy H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 2 PART 5 EPPRO-04 EP PERFORMANCE INDICATORS REVISION 5 I EPPRO-04 I Rev. 5 l Page 1 of 33l
SUMMARY
OF CHANGES 117119 STEP # REVISION COMMENTS Entire Procedure Reformatted to comply with AP-007 format.
Old Attachment Deleted attachment 8.1.6.12 PI&R - Training Feedback 8.1.6.12 0.2 Changed title from Program Objective Demonstration to Drill Objective Performance . Added statement to indicate that the indicator applies to full scale drills and to indicate that data will be blank, if no drills occur during the period. Changes made to reflect common EP performance indicators for RNP, BNP, HNP, and CR3. 0.3 Changed the title from Staffing Depth Maintenance to Staffing Depth. 0.4 Changed "quarterly beeper drill" to AERO Notification and Beeper Drill" to reflect EPPRO-02 changes 0.6 Clarified equipment availability to reflect common EP performance indicators for RNP, BNP, HNP, and CR3. 0.7 Changed title to Offsite Communications Availability and changed the titles of the EPPRO-02 surveillances. 0.9 Changed title to Offsite EP Performance and changed acceptance criteria to reflect common EP performance indicators for RNP, BNP, HNP, and CR3. 0.11 Revised indicator for corrective action average age to reflect common EP performance indicators for RNP, BNP, HNP, and CR3 EPPRO-04 Rev. 5 Page 2 of 33
TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ........................... 4
2.0 REFERENCES
........................... 4 3.0 RESPONSIBILITIES ........................... 4 4.0 PREREQUISITES ........................... 5 5.0 PRECAUTIONS AND LIMITATIONS ........................... 5 6.0 SPECIAL TOOLS AND EQUIPMENT ........................... 5 7.0 ACCEPTANCE CRITERIA ........................... 5 8.0 INSTRUCTIONS ........................... 5 9.0 RECORDS ........................... 8 10.0 ATTACHMENTS .9 10.1 ERO Performance - Classification, Notification and PAR .10 10.2 ERO Performance - Drill Objective Performance .14 10.3 ERO Readiness - Staffing Depth .15 10.4 ERO Readiness - Staffing Activation Response .16 10.5 ERO Readiness - Participation .17 10.6 Facilities and Equipment - Emergency Response Facility Availability .21 10.7 Facilities and Equipment - Offsite Communications Availability .22 10.8 Facilities and Equipment - Alert and Notification System Operability .23 10.9 Offsite EP Performance .24 10.10 Offsite EP - State and Local Agency Interface Status .25 10.11 PI&R - Corrective Action Program Status .27 10.12 ERO Key Member Matrix .30 EPPRO-04 I Rev. 5 l Page 3 of 33
1.0 PURPOSE 1.1 This procedure provides a consistent methodology for the collection, calculation and review of EP program Performance Indicator (PI) data. This is not an Emergency Plan implementing procedure.
1.2 This procedure provides guidance for preparation of information as required to support the NRC Inspection and Oversight Program and the requirements of 10CFR50.54(t).
1.3 This procedure establishes responsibilities associated with the implementation of the Performance Indicator program.
2.0 REFERENCES
2.1 As per EPPRO-00 3.0 RESPONSIBILITIES 3.1 The Emergency Preparedness Supervisor is responsible to:
3.1.1 Provide on-going monitoring and day-to-day oversight for EP Performance indicators.
3.1.2 Approve NRC Performance Indicator data elements prior to transmittal to the Licensing organization and assure timely transmittal.
3.1.3 Evaluate PI trends and initiate the appropriate Corrective Action Program (CAP) activities.
3.1.4 Assure the retention or retrievability of applicable records and documents that support PI data development.
3.2 Data Providers are responsible for 3.2.1 Serving as the primary point of contact and subject matter expert for assigned Performance Indicators; 3.2.2 Collecting and analyzing source documents to provide oversight and monitoring of assigned Performance Indicators; and 3.2.3 Initiating applicable attachments for documenting Performance Indicator data.
EPPRO-04 Rev. 5 Page 4 of 33
4.0 PREREQUISITES N/A 5.0 PRECAUTIONS AND LIMITATIONS N/A 6.0 SPECIAL TOOLS AND EQUIPMENT N/A 7.0 ACCEPTANCE CRITERIA N/A 8.0 INSTRUCTIONS NOTE: Site Performance Indicator colors of green, yellow and red correspond to NRC/NEI 99-02 performance indicator colors of green, white, and yellow, respectively.
8.1 Key Performance Indicators (KPls) - Risk Significant Indicators The NRC and NEI have jointly developed a standard set of Cornerstone NRC Performance Indicators, for monitoring EP program performance by all licensees.
NEI 99-02, "Regulatory Assessment Performance Indicator Guideline," defines the three EP Cornerstone Performance Indicators as:
8.1.1 Drill/Exercise Performance The percentage of all drill, exercise, and actual opportunities when presented with opportunities for classification of emergencies, notification of offsite authorities and development of protective action recommendations that were performed timely and accurately during the previous eight quarters.
8.1.2 Emergency Response Organization (ERO) Drill Participation The percentage of key ERO members (as defined within NEI 99-02) that have participated in a drill, exercise, or actual event during the previous eight quarters, as measured on the last calendar day of the quarter.
Robinson specific positions are listed on Attachment 10.12.
EPPRO-04 I Rev. 5 l Page 5 of 33
8.1 (Continued) 8.1.3 Alert and Notification System (ANS) Reliability 8.1.4 The percentage of ANS sirens that are capable of performing their function, as measured by periodic siren testing, in the previous 12 months. Periodic tests are the regularly scheduled tests that are conducted to actually test the ability of the sirens to perform their function (e.g. silent, growl, full volume test). The data compiled for each month is provided to Licensing by Attachment 10.8 and a data sheet from REG-NGGC-0009. A computer data base provides the rolling calculation that takes into account the previous 12 months.
8.1.5 Second Tier EP Performance Indicators Other Performance Indicators have been developed to monitor additional aspects of the EP program and provide management additional feedback on important areas of performance. The monthly input for the NRC performance indicators are included in this section.
- 1. ERO Performance
- a. Classification Performance (Attachment 10.1)
- b. Notification Performance (Attachment 10.1)
- c. PAR Performance (Attachment 10.1)
- 2. Drill Objective Performance
- 3. ERO Readiness:
- a. Staffing Depth (Attachment 10.3).
- b. Staffing Activation Response (Attachment 10.4)
- c. Participation (Attachment 10.5)
I EPPRO-04 I Rev. 5 l Page6of33
8.1.5 (Continued)
- 4. Facilities and Equipment:
- a. Emergency Response Facility Availability (Attachment 10.6)
- b. Offsite Communications Availability (Attachment 10.7)
- c. Siren System Operability (Attachment 10.8)
- 5. Procedure Quality:
Procedure quality concerns will be addressed in the Problem Identification and Resolution (PI&R) process in the Corrective Action Program Status.
- 6. Offsite Emergency Preparedness
- a. Offsite EP Performance (Attachment 10.9).
- b. State and Local Agency Interface Status (Attachment 10.10)
- 7. Problem Identification and Resolution (PI&R) process
- a. Corrective Action Program Status (Attachment 10.11)
- b. Drill and Exercise corrective actions (Attachment 10.11) 8.2 PI Tracking and Reporting 8.2.1 EP Second Tier Performance Indicators 8.2.2 NRC Performance Indicators (REG-NGGC-0009) 8.3 Data Collection, Calculation and Reporting 8.3.1 Performance Indicator data collection shall be performed on a monthly basis.
- 1. Performance indicator data provided to the NRC, or utilized in assessing the need for 10CFR50.54(t) reviews, shall be based on end of calendar quarter calculations.
- 2. Performance Indicator reports generated from other than end of quarter calculations shall be for management trending use only.
I EPPRO-04 I Rev. 5 l Page7of33
8.3.2 Methods of collecting raw data used in PI calculation are provided in the attachments of this procedure.
8.3.3 Significant changes to the monthly data which may result in adverse changes to the NRC PI quarterly data should be noted in the analysis portion of the monthly report for the affected indicator.
8.3.4 Problem Identification and Resolution
- 1. EP Program performance indicator issues are addressed through the Corrective Action Program. Items which are potentially adverse to program quality are classified, documented and tracked in accordance with CAP-NGGC-0200.
- 2. A Nuclear Condition Report (NCR) should be generated for any of the following conditions:
- Three (3) consecutive months with downward trending data points
- Any two consecutive data points that fall within the yellow indicator.
- Any one data point that falls within the red indicator.
9.0 RECORDS Records for generated from the performance of EPPRO-04 will be retained by the EP staff for a period of 24 months.
IEPPRO-04 I Rev. 5 l Page8 of 33
10.0 ATTACHMENTS 10.1 ERO Performance - Classification, Notification, and PAR Performance 10.2 ERO Performance - Drill Objective Performance 10.3 ERO Readiness - Staffing Depth 10.4 ERO Readiness - Staffing Activation Response 10.5 ERO Readiness - Participation 10.6 Facilities and Equipment - Emergency Response Facility Availability 10.7 Facilities and Equipment - Offsite Communications Availability 10.8 Facilities and Equipment - Alert and Notification System Operability 10.9 Offsite EP Performance 10.10 Offsite EP - State and Local Agency Interface 10.11 Pl&R - Corrective Action Program Status 10.12 ERO Key Member Matrix EPPRO-04 I Rev. 5 l Page9of33
ATTACHMENT 10.1 Page 1 of 4 ERO PERFORMANCE - CLASSIFICATION, NOTIFICATION AND PAR Purpose This indicator monitors timely and accurate performance in drills, exercises and actual events when presented with opportunities for classification of emergencies, notification of offsite authorities and development and notification of protective action recommendations (PARs).
Definition The percentage of pre-identified drill, exercise, and actual opportunities that were performed timely and accurately during the reporting period. Pre-identified opportunities are:
- Actual declared events and those scheduled exercises (drills) that EP coordinates and develops the scenarios with Licensed Operator Continuing Training.
- Pre-identified simulator sessions that use the same scenarios as above when qualified SSOs fill the SSO/SEC position.
- Evaluated simulator sessions involving EAL classification and notification activities when qualified SSOs fill the SSO/SEC position. (AR #85114)
. Unannounced Fire Drills where the scenario results in an EAL classification.
If other drill, exercises, and tabletops that meet the NEI 99-02 performance criteria are pre-identified by memo, then each additional pre-identified opportunity must be counted in the DEP statistics.
- Opportunities are:
Each expected classification or upgrade in classification.
Each PAR developed.
Each initial notification of an emergency class declaration.
Each initial notification of PARs or change to PARs.
An initial notification form completed appropriate to the event to include:
Class of emergency EAL number Description of emergency Wind speed and direction Whether offsite protection measures are necessary Potentially affected population and areas Whether a release is taking place Date and time of declaration of emergency Whether the event is a drill or actual event Plant identification EPPRO-04 I Rev. 5 l Page 10 of 33l
ATTACHMENT 10.1 Page 2 of 4 ERO PERFORMANCE - CLASSIFICATION, NOTIFICATION AND PAR Expectations are:
- Classifications should be made in < 15 minutes per EPCLA-02.
- Off-site notification contact should be made in < 15 minutes per EPNOT-01.
- PARs should be developed and notification initiated in < 15 minutes of a General Emergency classification. If the event conditions change, either radiological or meteorological, resulting in revised PARs then the < 15 minute standard is applicable. The 15 minute time standard for PAR development applies once field data is obtained not from the time the dose projection is completed.
Green - 2 95%
Yellow - Ž 90% < 95%
Red - < 90%
Documentation Information is gathered from Emergency Notification Forms generated from the ERFIS computer and/or the manual Emergency Notification Forms. ERO Performance is tracked on Attachment 10.1 worksheets or equivalent, as applicable.
Data from the Attachment 10.1 worksheets is collated monthly on data sheets contained in REG-NGGC-0009.
Notes Errors on the ENF that do not affect the content or intent of the message do not count as an error. Examples include:
e Typographical errors that do not change the meaning of the information.
. Information left blank instead of "none" or "N/A".
EPPRO-04 I Rev. 5 l Page 11 of 33
ATTACHMENT 10.1 Page 3 of 4 ERO PERFORMANCE - CLASSIFICATION, NOTIFICATION AND PAR ERO PERFORMANCE INDICATOR WORK SHEET Date: Page _ of Sections 1 and 2 to be completed by the evaluator.
Section 1 Actual Emergency El Simulator Evaluation El Exercise/Drill a Scenario #
Name of SEC:
Evaluator Name:
Section 2 ACTIVITY UE ALERT. SAE GE.
Record the time indications are available that an EAL has been exceeded.
Check the expected event declaration Was the expected event declaration made? (yes or no)
Record the time the event was declared.
Record the time the Emergency Notification Form was approved.
Record the time of first voice contact after ENF approval Were the correct initial protective action recommendations made?
Were the State and Counties notified of the PARs within 15 minutes? -_--_.
Record the time conditions were available that resulted in a change In the PARS? :_:--__
Record the time the Emergency Notification Form with the change in PARs was approved. -. -- - -:-- e_
Record the time of first voice contact after ENF approval. , . ..
Were the State and Counties notified of the change in PARs within 15 m inutes?__ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _
Comments:
Section 3 to be completed by EP staff.
Section 3 Classification(s) Expected: UE El Alert El SAE El GE El Classification(s) Declared: UE El Alert El SAE [E GE El Classification Opportunities: Successes:
Notification Opportunities: = Successes: =
PAR Development Opportunities: Successes:
PAR Notification Opportunities: Successes: _
Comments:
Prepared by:
Reviewed by:
I EPPRO-04 I Rev. 5 l Page 12 of 33
ATTACHMENT 10.1 Page 4 of 4 ERO PERFORMANCE - CLASSIFICATION, NOTIFICATION AND PAR Standard: Timely and accurate EAL classifications, notifications, and PARs are performed during actual events, evaluated simulator scenarios with an EAL classification, and EP drills/exercises. Timely is defined as < 15 minutes.
Method of Data Collection: The evaluator will complete Sections 1 and 2 of the attached ERO Performance Tracking Form.
Opportunities: are to be as defined by the activities included In the examination evaluation guide and presence of conditions during the examination as follows (opportunities cannot be excluded due to poor performance):
- Each expected classification should be Included.
- Notification Includes notifications made to the state and/or local government authorities for Initial emergency classification, upgrade of emergency class, Initial PARs and changes in PARs (periodic follow-up notifications and briefings when the classification or PARs have not changed are not included).
Timely:
- Classifications are made consistent with the goal of 15 minutes once plant parameters reach an Emergency Action Level (EAL).
- Offsite state/county notifications are initiated within 15 minutes of event classification. Refer to EPNOT-01.
o Communicating the event with an Emergency Communicator present/simulated.
o Completion of the Emergency Notification Form to include initiation of the Fax with adequate time allotted for an EC (Simulated EC activities) to have completed steps as outlined above when EC not present/simulated.
- PARs are developed and notification initiated within 15 minutes of a General Emergency classification, or change in conditions resulting in revised PARs.
Accurate (numbers in parenthesis indicate Emergency Notification Form line numbers):
- Classifications are performed and declared In accordance with EPCLA-01 and the EALs.
- Notifications o Event declaration notifications, as a minimum, contain indication of Drill or Actual (1), Plant site/unit (2), correct event classification level (5), declaration time & date (6), Emergency description (7), Emergency Release status (10), Wind Speed & direction (14) and PARs (or None) (15).
o Notifications that include PARs must provide the correct Sector information for Evacuation and Sheltering (15).
o The cumulative effect of multiple omissions or errors In other areas of the notification needs to be evaluated for Impact on overall accuracy.
- PARs are appropriate to the event and meteorological conditions as specified in EPCLA-01.
Copies of the completed Emergency Notification Form(s), completed Persons and Agencies Alerted Form(s) if applicable, and any completed Communications Checklist(s) if applicable, are to be attached to the ERO Performance Tracking Form. Route the completed forms to the Emergency Preparedness Group.
Disposition: Once completed and forwarded to Emergency Preparedness, the data collected on the form will be used to track RNP monthly plant key performance indicators and the NRC quarterly cornerstone performance indicators.
Remediation for Unsatisfactory performance: Unsatisfactory performance during evaluated scenarios on the RNP simulator conducted by the RNP Training Section will be Identified in an NCR and remediated in accordance with Training Program Procedures.
EPPRO-04 I Rev. 5 l Page 13 of 33l
ATTACHMENT 10.2 Page 1 of 1 ERO PERFORMANCE - DRILL OBJECTIVE PERFORMANCE Reporting month Total number of required drill objectives Drill objectives not met Drill objectives met Percentage of successful drill objectives Total number of required drill objectives - required Drill objectives not met = Drill objectives met Drill objectives met
% Program Objectives Performance = Total required drill objectives x 100 Purpose This indicator monitors the performance of drill and exercise objectives when presented with opportunities for their demonstration.
Definition The percentage of pre-identified drill and exercise objectives that were performed successfully.
A program objective does not require a drill involving all of the emergency response facilities to be counted in this indicator. A drill is of appropriate scope if it reasonably simulates the interaction or conditions necessary to fully demonstrate the program objective.
A program objective demonstrated by more than one facility is counted as an opportunity for each of the facilities (for example, command and control would present four opportunities for a drill involving the TSC, OSC, EOF, and JIC).
Green - 2 90% of drill objectives Yellow - 2 80% < 90% of drill objectives Red - < 80% of drill objectives Documentation The drill / exercise objectives are stated in pre-drill information. Objective demonstration is documented in the drill / exercise critiques.
Notes EPPRO-04 I Rev. 5 l Page 14 of 33
ATTACHMENT 10.3 Page 1 of 1 ERO READINESS - STAFFING DEPTH Purpose This indicator reflects the ability to maintain a fully staffed ERO for a prolonged response by measuring the ERO staffing depth for all positions.
Definition ERO depth is required to assure 24-7 coverage for emergencies requiring full staffing of the ERFs. A minimum of four personnel per position assures sufficient depth to allow for unavailability due to vacation or illness. ERO positions filled by pools of personnel are not included in this indicator.
Green - No position less than four deep for greater than 4 months.
Yellow - Any position filled less than four deep for greater than 4 months.
Red -Any 2 positions filled less than four deep for greater than 4 months.
Documentation Reporting month Emergency Response Organization Team Roster applicable on the last day of the calendar month.
Vacant Position Date Open Date Filled Months Open Notes EPPRO-04 I Rev. 5 l Page 15 of 33
ATTACHMENT 10.4 Page 1 of 1 ERO READINESS - STAFFING ACTIVATION RESPONSE Purpose This indicator reflects the ability to contact ERO members for augmentation of the on-shift ERO.
Definition This indicator measures the ability to contact ERO members for augmentation of the on-shift ERO per Table 5.3.2-1 of PLP-007.
Use the quarterly beeper test documents to determine
- a. number expected to respond
- b. number that received the code.
Green - 2 90% of on-call personnel issued a beeper responded and all Table B-1 positions filled.
Yellow - - > 80% < 90% of on-call personnel issued a beeper responded or one (1)
Table B-1 position not filled.
Red - < 80% of on-call personnel issued a beeper responded or greater than one (>1)
Table B-1 position(s) not filled.
Documentation Reporting month The ERO Notification and Beeper Drill results per EPPRO-02.
Previous Quarter Previous Quarter Previous Quarter Current Quarter (end of quarter (end of quarter (end of quarter (end of quarter value) value) value) value)
Date Date Date Date
% on-all with beeper % on-all with beeper % on-all with beeper % on-all with beeper responded: responded: responded: responded:
Table B-1 positions filled Table B-1 positions filled Table B-1 positions filled Table B-1 positions filled (all, 1 not, >1 not): _ (all, 1 not, >1 not): (all, 1 not, >1 not): _ (all, 1 not, >1 not): _
Notes I EPPRO-04 I Rev. 5 l Page 16of33
ATTACHMENT 10.5 Page 1 of 4 ERO READINESS - PARTICIPATION Purpose This indicator monitors the opportunities that key ERO members have been provided to gain proficiency as an integrated organization. It measures the percentage of those personnel who were participants, coach/mentors, evaluators or controllers in proficiency-enhancing drill/exercise opportunities or in actual events.
Definition The percentage of key ERO members (per Attachment 10.12) who were participants, coach/mentors, evaluators or controllers in proficiency-enhancing drill/exercise opportunities or in actual events during the reporting period.
Green - 2 90%
Yellow - 280% < 90%
Red - < 80%
Key Members are as follows:
Control Room Site Emergency Coordinator Technical Support Center Site Emergency Coordinator Plant Operations Director Radiological Control Director Technical Analysis Director NRC Emergency Communicator Emergency Operations Facility Emergency Response Manager Radiological Control Manager Emergency Communicator Operational Support Center Operational Support Center Leader Documentation ERO Drill Rosters ERO Database Self-assessments of the drill cycles Data sheets are contained in REG-NGGC-0009.
EPPRO-04 I Rev. 5 l Page 17 of 33
ATTACHMENT 10.5 Page 2 of 4 ERO READINESS - PARTICIPATION Notes Personnel are given credit for the ERO position for which they hold during a drill.
Personnel holding multiple ERO positions must participate in a drill for each position they are qualified for. (CR25154)
Data Collection Method The data and documentation for this indicator is obtained by performing the following steps.
Open in Microsoft Access, folder V:\\Access Databases\Shared\EP\ERO.mdb From this folder, open file EROdata.mdb.
Select Reports Right click on "rptAliQualifiedKPIPositions.
Right click on uPrint Preview."
When accessing "rptAlIQualifiedKPIPositions," the database will ask for the first day of last year, then the last day of this year. These dates must be entered as mm/dd/yyyy and are checking the database for individuals who are currently qualified as a "Key" position.
From the "Print Preview" screen, print the report.
This report will indicate all ERO members who are qualified one or more ERO positions defined in NEI 99-02 as a "Key" position (reference Attachment 10.12).
The other half of the data is obtained from Microsoft Excel by performing the following steps.
EPPRO-04 I Rev. 5 l Page 18of33
ATTACHMENT 10.5 Page 3 of 4 ERO READINESS - PARTICIPATION NOTE: for the following steps, the examples will be based on the month of June 2001 indicator being calculated on the 2nd of July 2001.
Open in Microsoft Excel, folder V:\\Emergency Preparedness\Performance Indicators\ERO Performance From this folder, open the file for the previous month. Remember the previous month may be two months ago depending on the date the indicator is being calculated. For example if this is July2, 2001, then open the file titled "NRC KPI Info Tables May 2001.xis". You would be calculating the indicator for the month of June 2001.
Save this file as "NRC KPI Info Tables {month being calculated and year} June 2001.xls".
After the file has been saved, from the pull-down menu, select "view," then "Headers and Footers." This opens a 'Page Setup" window.
From the "Page Setup" window, select the "Header?Footer"tab, and then select "Custom Header.." This will open the uHeader" window.
In the "Center Section" of the window, scroll down and update the month for the indicator being calculated (June), and the dates for the previous eight quarters then select "Ok."
Select "Ok" to close the "Page Setup" window.
Determine if any drills conducted during the month being calculated were credited as "Drill, Exercise, Performance (DEP) drills. This information may be obtained from the Supervisor-EP.
If DEP drills were conducted during the month being calculated, then enter in the spreadsheet the most recent dates for those who signed the training report. Key ERO positions may receive credit for the positions of participant (P), controller ©, or evaluator (E) only (not mentor/coach). Ensure the individual gets credit only for the ERO position they signed on the training report. For those ERO members who you are adding new dates, ensure the Role column is updated with a P, C, or E to indicate their level of participation. Finally update the Comments column to indicate where you can verify the participation (i.e. training reports, ENFs)
EPPRO-04 I Rev. 5 l Page 19 of 33
ATTACHMENT 10.5 Page 4 of 4 ERO READINESS - PARTICIPATION After entering the participation dates, verify all of the dates on the spreadsheet fall within the previous eight quarters period. Any date that is prior to the previous eight quarters must be removed and replaced with the text uNone" for the Drill Date and "N/A" in the Role column.
Print the spreadsheet. Count the number of qualified individuals and verify the number agrees with the total in the Total Qualified cell.
Count the drill dates for both the Drill Date and Simulator Evaluation Date columns and add the values. Verify the number agrees with the total in the Total Participated cell.
Count the number of qualified individuals from the Access report agrees with the total number of individuals in the Excel spreadsheet, then sign and date the bottom of the Excel spreadsheet.
REG-NGGC-009, "NRC Performance Indicators", contains the data sheets for this indicator. Print the attachment for "Emergency Response Organization Drill Participation." This attachment is where you document the Total number of Key ERO Members from the Excel spreadsheet and the total number of Key ERO members who have participated within the previous eight months also from the spreadsheet.
Attach to the REG-NGGC-009 form the Access database report, the Excel Spreadsheet, and the pages from EPPRO-04 describing the ERO Readiness-Participation.
EPPRO-04 I Rev.5 l Page 20of33
ATTACHMENT 10.6 Page 1 of 1 FACILITIES AND EQUIPMENT - EMERGENCY RESPONSE FACILITY AVAILABILITY Purpose This indicator measures the ability to maintain plant Emergency Facilities (TSC and EOF only) including equipment in a state of readiness to support emergency response activities.
Definition The measure of time, in percent, that the TSC and EOF are fully functional and available to support emergency response activities, as measured on a calendar month basis.
Availability includes the following key capabilities:
Habitability (Ventilation & pressure control)
Electrical Power (as supplied from any source)
Out of service is defined as the time of discovery until operability is restored. Status is a 12 month rolling average.
Green - 299% ERF availability for the calendar month.
Yellow < 99% and 295% ERF availability for the calendar month.
Red <95% ERF availability for the calendar month.
Documentation Reporting month Hours Em. Response Facility available Hours in the calendar month x 100 = % available Autolog, Work order/request queries Facility walkdowns can all be used to determine actual hours available Notes EPPRO-04 I Rev. 5 l Page 21 of 33
ATTACHMENT 10.8 Page 1 of 1 FACILITIES AND EQUIPMENT - OFFSITE COMMUNICATIONS AVAILABILITY Purpose This indicator reflects the ability to maintain plant components and ERF equipment needed to support emergency response activities.
Definition This indicator reflects the operability of the key offsite communications systems to state and local governments: Selective Signaling and ESSX phones This indicator is a ratio of hours each system is unavailable vs. total annual hours that the system is available for use.
%= hours of unavailability annual hours of availability The time of unavailability is defined as the time of discovery until operability is restored.
A system is considered unavailable if one or more lines of the system are out of service.
Green - No individual problem greater than 14 days to resolve and repetitive within 184 days.
Yellow - No two (2)individual problems greater than 21 days to resolve and repetitive within 184 days.
Red - Greater than 2 individual problems greater than 28 days to resolve and repetitive within 184 days.
Documentation Reporting month The following EPPRO-02 Surveillance test results are screened for equipment problems:
Selective Signaling System Communications Drill NRC ETS, ESSX, & SSS Phone Operational Checks OffSite Selective Signaling Phone Test Equipment/Repetitive Problem Date discovered Date resolved Total days Notes EPPRO-04 I Rev. 5 l Page 22of33
ATTACHMENT 10.8 Page 1 of 1 FACILITIES AND EQUIPMENT - ALERT AND NOTIFICATION SYSTEM Purpose This indicator monitors the reliability of the offsite Alert and Notification System (ANS) -
Siren System. It provides the percentage of the sirens that are capable of performing their safety function.
Definition The percentage of ANS sirens that are capable of performing their function, as measured by periodic siren testing. Periodic tests are the regularly scheduled tests conducted to actually test the ability of the sirens to perform their function (e.g., silent, growl, full volume test).
Documentation Records from the silent, growl and full volume tests. Data from these records are compiled to determine ANS operability percentages.
Green - 2 96%
Yellow - 294% < 96%
Red - < 94%
Data sheets are contained in REG-NGGC-0009 Notes A failure of sensing equipment that does not result in the siren being inoperable (e.g.,
rotation sensor) will not count as a siren failure if the siren is verified functional by local observation.
EPPRO-04 l Rev. 5 Page 23 of 33
ATTACHMENT 10.9 Page 1 of 1 OFFSITE EP PERFORMANCE Previous Quarter Previous Quarter Previous Quarter Current Quarter Deficiencies Deficiencies Deficiencies Deficiencies ARCAIARCA__ ARCAIARCAI Purpose This indicator measures the performance of the off site ERO by tracking total offsite:
Deficiencies, Areas Requiring Corrective Actions (ARCAs), and NAS Issues. This indicator applies to Deficiencies and/or ARCAs received during FEMA evaluated exercises with fixed nuclear facilities. This indicator applies to ARCAs received by state agencies and the affected risk/host counties.
Definition If there is no RNP exercise during the period, then the value remains the same as the previous period.
Green: Less than or equal to (< 4) ARCAs Yellow: >4 but < 7 ARCAs Red: Any FEMA Deficiency or > 7 total ARCAs Documentation FEMA reports from the biennial graded exercise and MS-1 drills provide this information.
Notes Agencies from Darlington, Lee, Chesterfield and Florence Counties and the State of South Carolina are considered for this indicator.
Data Collection Method This data is obtained from the State EMD Area 4 Coordinator.
EPPRO-04 I Rev. 5 l Page24 of 33
ATTACHMENT 10.10 Page 1 of 2 OFFSITE EP - STATE AND LOCAL AGENCY INTERFACE STATUS Purpose This indicator measures the effectiveness of the interface with the offsite agencies.
Definition The color codes for this indicator are based on an average rating from the feedback forms completed and returned by the offsite agencies. If feedback is not measured during the quarter, the value remains the same as the previous quarter.
Green - Overall rating 2 4 (meeting expectations)
Yellow - Overall rating Ž 2 or < 4 (meets some expectations)
Red - Overall rating < 2 (below expectations)
The offsite agencies consist of:
South Carolina Emergency Management Division (EMD) and Department of Health and Environmental Control (DHEC)
Lee County Darlington County Chesterfield County Florence County (Florence County is the host county for evacuations.)
Documentation The Offsite Survey.
Notes Data Collection Method Page of this attachment is given to the above off-site agencies then averaged.
EPPRO-04 I Rev. 5 l Page 25 of 33
ATTACHMENT 10.10 Page 2 of 2 OFFSITE EP - STATE AND LOCAL AGENCY INTERFACE STATUS SURVEY Rate the following questions A through E, 1 being the lowest and 5 the highest, for satisfaction of the interface with H.B. Robinson?
A. Does H. B. Robinson meet your classroom training needs? 1 2 3 4 5 B. Are equipment problems resolved in a timely fashion? 1 2 3 4 5 C. Are drills effective in meeting the needs of your agency? 1 2 3 4 5 D. Are problems identified in the quarterly meetings resolved in an efficient manner? 1 2 3 4 5 E. What is your comfort level in communicating with the EP staff at H. B. Robinson? 1 2 3 4 5 Comments:
Agency represented By /
Name Date Please return this sheet to the EP Supervisor at the Robinson Site.
EPPRO-04 I Rev. 5 l Page 26of33
ATTACHMENT 10.11 Page 1 of 3 PI&R - CORRECTIVE ACTION PROGRAM STATUS Purpose This indicator monitors corrective action identification and completion for timely problem resolution assigned to EP staff members for significant adverse and adverse conditions.
This indicator also monitors the ability of the Emergency Response Organization to fix problems that are identified in the corrective action program. This indicator includes significant and adverse corrective actions (CA).
Definition Corrective Action identification and resolution per the CAP program (CAP-NGGC-0200) assigned to EP staff members for significant adverse and adverse conditions.
Green - Average age of significant adverse investigations < 21 days Yellow - Average age of significant adverse investigations > 21 days and < 23 days Red - Average age of significant adverse investigations > 23 days Green - Average age of significant adverse CAPRs < 90 days Yellow - Average age of significant adverse CAPRs > 90 days and < 99 days Red - Average age of significant adverse CAPRs > 99 days Green - Average age of adverse investigations < 30 days Yellow - Average age of adverse investigations > 30 days and < 33 days Red - Average age of adverse investigations > 33 days Green - Average age of corrective actions < 120 days Yellow - Average age of corrective actions < 150 days Red - Average age of corrective actions > 150 days Month/Year Indicator Average Age Color Trend (Cicle one) (circle one)
Significant Adverse Investigations days Green Yellow Red - '4' A Significant Adverse CAPRs days Green Yellow Red - 'V A Adverse Investigations days Green Yellow Red -_ V A Corrective Actions days Green Yellow Red _- V A EPPRO-04 I Rev. 5 l Page 27of33
ATTACHMENT 10.11 Page 2 of 3 Pl&R - CORRECTIVE ACTION PROGRAM STATUS Documentation Information to support this performance indicator is obtained from Business Objects KPI Reports generated for end of month data. These reports automatically print on the first business day following the end of the month.
- 1. Review the reports to ensure that items attributed to EP are identified in the report.
- 2. Select the following report: "Average Age of Priority 1 Evaluations"
- Enter the average age of the open significant adverse investigations on Attachment 10.11.
- If no open significant adverse investigations are found, then enter NA in the table on Attachment 10.11.
- 3. Select the following report: "Average Age of Open CAPRs"
- Enter the average age of the open significant adverse CAPRs on Attachment 10.11.
- If no open significant adverse CAPRs are found, then enter NA in the table on Attachment 10.1 1.
- 4. Select the following report: "Average Age of Priority 2 Evaluations"
- Enter the average age of the open adverse investigations on Attachment 10.11.
- If no open adverse investigations are found, then enter NA in the table on Attachment 10.11.
- 5. Select the following report: "Average Age of Open Priority 1 & Priority 2 Corrective Actions"
- Enter the average age of the open priority 1 and 2 corrective actions on Attachment 10.11.
- If no open priority 1 and 2 corrective actions are found, then enter NA in the table on Attachment 10.11.
- 6. Compare the average age for each of the categories to the performance indicator criteria and circle the appropriate color in the designated column on Attachment 10.11.
I EPPRO-04 I Rev. 5 l Page 28 of 33
ATTACHMENT 10.11 Page 3 of 3 PI&R - CORRECTIVE ACTION PROGRAM STATUS
- 7. Determine if a trend exists by comparing the current month's data with the previous month's data.
- If the performance indicator average age is the same as the previous month, then circle - in the trend column on Attachment 10.11.
- If the performance indicator average age is increasing from the previous 4,
month, then circle in the trend column on Attachment 10.11.
- If the performance indicator average age is decreasing from the previous month, then circle t in the trend column on Attachment 10.11.
The printed Business Objects reports should be maintained with Attachment 10.11 as supporting documentation.
Notes IEPPRO-04 I Rev. 5 l Page 29of33
( (
ATTACHMENT 10.12 Page 1 of 4 ERO KEY MEMBER MATRIX NEI 99-02 HBR ERO position DEP type drill Definition of KEY fulfilling this Basis required to receive Comments ERO Members definition credit for participation?
Control Room The CR - SEC has Reference PLP-007, Shift Manager the responsibility of "Robinson Emergency (Emergency Director) overall command and Plan," Sections 5.3
- Supervision of control in the CR and and 5.4. Because the reactor operations, has the responsibility CR-SEC has responsible for Control Room - Site to notify the state and responsibility for both classification, Emergency local authorities within of these tasks, they notification, and Coordinator the required time. Yes will only be counted determination of (CR - SEC) once in the protective action participation indicator.
recommendations Control Room The CR-SEC compiles Shift Communicator - the data and approves provides initial offsite the ENF (state/local) notification Technical Support Technical Support The TSC - SEC has Reference PLP-007, Center Center - Site the responsibility for all "Robinson Emergency Senior Manager - Emergency events being Plan," Section 5.3.
Management of plant Coordinator conducted outside the Yes operations/corporate (TSC - SEC) Control Room and resources within the Protected Area. The TSC-SEC is the lead position for the TSC.
EPPRO-04 Rev. 5 Page 30 of 33
( C, c ATTACHMENT1 0.12 Page 2 of 4 ERO KEY MEMBER MATRIX Technical Support Plant Operations The POD is either a Reference PLP-007, Center Director currently licensed or "Robinson Emergency Key Operations (POD) previously licensed Plan," Section 5.3.
Support SRO. They are the link Yes between the Control Room and the TSC.
They are an advisor to the TSC - SEC.
Technical Support Radiological Control The RCD is Reference PLP-007, Center Director responsible for Key "Robinson Emergency Key Radiological (RCD) Radiological Controls Plan," Section 5.3.
Controls - - Radiological effluent Yes Radiological effluent and environs and environs monitoring, monitoring, assessment and dose assessment and dose projections within the prolections Protected Area.
Technical Support NRC Emergency The communicator to Reference PLP-007, Center Communicator an offsite agency "Robinson Emergency Key TSC (NRC - EC) within the TSC is to Plan," Section 5.3.
Communicator - the NRC by the NRC provides offsite Emergency Yes (state/local) Communicator. An notification Operator or someone in Operations Training who would be familiar with the operation of the plant staffs this position.
EPPRO-04 Rev. 5 Page 31 of 33
( C (
ATTACHMENT 10.12 Page 3 of 4 ERO KEY MEMBER MATRIX Technical Support Technical Analysis The TAD advises the Reference PLP-007, Center Director TSC - SEC and has a "Robinson Emergency Key Technical Support (TAD) staff of Engineers who Plan," Section 5.3.
are the Accident Yes Assessment Team (Electrical, Mechanical, and Reactor)
Emergency Emergency Response The Emergency Reference PLP-007, Operations Facility Manager Response Manager is "Robinson Emergency Senior Manager - (ERM) standing in for the Plan," Section 5.3.
Management of Plant Vice-President corporate resources during declared Yes events. This individual has overall plant responsibility and the remainder of the company at their disposal if requested through corporate.
Emergency Radiological Control The RCM has the Reference PLP-007, Operations Facility Manager overall responsibility to "Robinson Emergency Key Protective (RCM) advise the ERM of Plan," Section 5.3.
Measures - radiological conditions. Yes Radiological effluent The RCM has the and environs DPTL and the EMTL monitoring, working for them.
assessment, and dose projections Rev._Page_32_of33 EPPRO-04 lRev. 5 lPage 32of 33l
(7 C c ATTACHMENT 10.12 Page 4 of 4 ERO KEY MEMBER MATRIX Emergency Emergency In the EOF, the EC is Reference PLP-007, Operations Facility Communicator responsible for "Robinson Emergency Key EOF (EC) accurate and timely Plan," Section 5.3.
Communicator - completion of the Yes provides offsite notification form and (state/local) notification to the notification offsite agencies within the required time.
Operational Support Operational Support The OSCL is Reference PLP-007, Center Center Leader responsible for "Robinson Emergency Key OSC Operations (OSCL) coordination and No Plan," Section 5.3.
Manager activation of Damage t Control and Search and Rescue missions. .
EPPRO-04 l Rev. 5 l Page33of33
Progress Energy H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 2 PART 5 EPRAD-03 DOSE PROJECTIONS REVISION 14 I EPRAD-03 Rev. 14 Page 1 of 77
SUMMARY
OF CHANGES PRR 116784 STEP.# REVISION COMMENTS Entire Procedure Changed procedure layout to conform with AP-007 requirements.
Step 8.2.12.3 Changed default value for release duration from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Step 8.3.3.3.5 Step 8.3.3.4.5 Step 8.3.3.5.2 Bullet 8 Section 8.5 Manual calculation of dose projections results (NCR #93300)
(new) 0.18 New attachment for calculating and recording dose projection results.
I EPRAD-03 I Rev. 14 l Page 2 of 77l
TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ................................................. 4
2.0 REFERENCES
................................................. 4 3.0 RESPONSIBILITIES ................................................. 4 4.0 PREREQUISITES ................................................. 4 5.0 PRECAUTIONS AND LIMITATIONS ................................................. 4 6.0 SPECIAL TOOLS AND EQUIPMENT ................................................. 4 7.0 ACCEPTANCE CRITERIA ................................................. 4 8.0 INSTRUCTIONS ................................................. 5 8.1 Accessing the Dose Projection Program ................................................. 5 8.2 Use of the Dose Projection Program in the Control Room ................................... 7 8.3 Use of the Dose Projection Program by the Dose Projection Team ................... 15 8.4 Interpretation of the Dose Projections Summary Table ...................................... 30 8.5 Manual Calculation of Dose Projection Results ................................................ 33 9.0 RECORDS ................................................ 34 10.0 ATTACHMENTS .34 10.1 Definitions and Abbreviations .35 10.2 General Information .38 10.3 Quality Codes .39 10.4 Core Uncovery Time Determination .40 10.5 Accident Mitigation Systems .41 10.6 Obtaining and Updating Meteorological Data .42 10.7 Source Time Determination .47 10.8 Flow Rates .52 10.9 Detector Sensitivities .57 10.10 Measuring Radiation Level on Main Steam Lines .62 10.11 Typical RMS Values .63 10.12 RMS Monitored Systems .65 10.13 Weather Service Data .66 10.14 Onsite Meteorological Data .67 10.15 Meteorological Forecast Form .68 10.16 HBRDOSE/RASCAL Comparison Matrix .69 10.17 Manual Calculation of Curies Released .70 10.18 Manual Dose Projection Work Sheet .72 I EPRAD-03 I Rev. 14 l Page3of 77
1.0 PURPOSE This procedure provides instruction for performing dose projections in case of possible offsite emergencies from a release of airborne radioactivity.
2.0 REFERENCES
As per EPRAD-00.
3.0 RESPONSIBILITIES 3.1 Operations personnel under the direction of the Site Emergency Coordinator are responsible for performing the Control Room portion of this procedure until the Dose Projection Team is activated.
3.2 The Radiological Control Manager or the Dose Projection Team Leader is responsible for calculating the TEDE and the thyroid CDE, to be used by the Radiological Control Manager and the Emergency Response Manager in determining and evaluating possible off-site consequences from a release of airborne radioactivity.
4.0 PREREQUISITES As per EPRAD-00.
5.0 PRECAUTIONS AND LIMITATIONS 5.1 Radiation Monitors that are out of service shall not be used for dose projections.
Verification of ERFIS data shall be accomplished by comparing the-Control Room readouts in the event the RMS/ERFIS interface multiplexer is in alarm.
5.2 When manually entering data in HBRDOSE do not leave blank spaces between characters, (e.g., use 3,000,000 or 3E6 NOT 3 E6).
5.3 Additionally, this section contains several Attachments to assist the user that are not specifically referenced in the body of the section.
6.0 SPECIAL TOOLS AND EQUIPMENT N/A 7.0 ACCEPTANCE CRITERIA N/A EPRAD-03 I Rev. 14 l Page4of77
8.0 INSTRUCTIONS 8.1 Accessing the Dose Projection Computer Program NOTE: This section represents a systematic approach to access the dose projection computer program. Steps must be followed in order and you must be logged into EDS with an event declared. Any problems in accessing the program must be promptly reported to Information Technology personnel for resolution.
8.1.1 IF the ERFIS terminal to be used is initially aligned to the site LAN, THEN align the terminal to the ERFIS system.
NOTE: The following error messages may occur indicating the inability to link with the ERFIS host:
If initially in ERFIS during the failure, an "ERR1 1 COMMUNICATIONS TIMED OUT II" message will appear on the top line of the man-machine interface and the EDS icon in the upper right corner will turn red.
If initially on the site LAN during the failure, error text will appear and a log-in prompt.
8.1.2 IF the ERFIS terminal was in the site LAN at the time of the failure and error text and a login prompt are displayed, THEN proceed to Step 8.1.5 for "local mode" operations.
8.1.3 IF the ERFIS terminal to be used is aligned and linked to ERFIS, THEN type the turn on code "hbrdose" in the man-machine interface OR SELECT the EP Menu from the Main Menu and SELECT HBRDOSE.
8.1.3.1 IF the dose projection program is accessed, THEN proceed to Section 8.2, Use of the Dose Projection Program in the Control Room.
8.1.3.2 IF the dose projection program is not accessed, THEN proceed to the next step.
I EPRAD-03 I Rev. 14 l Page 5 of 77l
8.1.4 IF the ERFIS terminal to be used is aligned but NOT linked to ERFIS, THEN dose projection MAY still be used, however, radiological and meteorological data must be manually entered.
8.1.4.1 TYPE the turn on code "hbrdose" in the man-machine interface.
8.1.4.2 NOTIFY Information Technology personnel of problems as soon as practical.
8.1.4.3 IF the dose projection program is accessed, THEN proceed to Section 8.2, Use of the Dose Projection Program in the Control Room.
8.1.4.4 IF the dose projection program is NOT accessed, THEN proceed to the next step.
8.1.5 IF the ERFIS terminal to be used CAN NOT be aligned to ERFIS, THEN continue in this section to configure the ERFIS terminal for "local mode."
NOTE: As long as the ERFIS terminal has power, the following sub-steps should align the terminal to perform dose projection in "local mode". This method will require manual entry of radiological and meteorological data.
8.1.5.1 REBOOT the ERFIS terminal by depressing CTRL, ALT, SHIFT, DEL (numeric keypad delete must be used) simultaneously. The computer may take up to 10 seconds to respond to this key sequence.
8.1.5.2 CHOOSE ERFIS/EDS from the System Commander.
8.1.5.3 IF a grey QNX window appears, THEN press the right mouse button to get the menu, choose "exit," and confirm the exit choice. Otherwise, skip this step and proceed to the next step.
NOTE: The login and password prompts are case sensitive and must be entered in lower case.
8.1.5.4 WHEN the cursor is displayed, possibly after various system messages, THEN press "ENTER" if the login prompt is not displayed. A "Login" prompt should appear.
8.1.5.5 At the login prompt, TYPE "hbrdose" and press "Enter."
8.1.5.6 At the password prompt, TYPE "hbrdose" and press "Enter."
HBRDOSE will automatically start after this step.
I EPRAD-03 I Rev. 14 l Page 6 of 77
8.1.5 (Continued) 8.1.5.7 Do not attempt to print or make electronic notifications in "local mode," as this will further degrade execution of the program.
8.1.5.8 IF "local mode" worked, THEN GO TO Section 8.2, "Use of the Dose Projection Program in the Control Room".
8.1.6 CONTACT Information Technology personnel for instructions to return the ERFIS terminal to normal when dose projections are complete.
8.1.7 IF "local mode" did not work on the initial ERFIS terminal, THEN REPEAT Step 8.1.5 on another ERFIS terminal, and request that Information Technology personnel immediately bring a computer to the Control Room with a current version of the dose projection program installed.
8.1.7.1 Information Technology personnel will provide instructions on accessing the program.
8.1.7.2 Proceed to Section 8.2, "Use of the Dose Projection Program in the Control Room."
8.2 Use of the Dose Projection Program in the Control Room 8.2.1 With the mouse, left click the Projection menu item.
8.2.2 Left click the Control RM menu item.
NOTE: Within each release pathway, the left mouse button can be used to move the cursor to the desired field. Depressing the left mouse button will also select or deselect any of the monitors.
8.2.3 CONTAINMENT => ENVIRONMENT Group 8.2.3.1 IF NO monitor in the CONTAINMENT=>ENVIRONMENT group is in alarm, THEN VERIFY that none of the check boxes are selected. You can deselect any monitor by pressing the left mouse button on the desired monitor. Go to Step 8.2.4.
NOTE: When performing the following step be aware that R-2 values are displayed in units of mR/hr while R-32 A&B values are displayed in R/hr.
8.2.3.2 IF R-32A OR R-32B OR R-2 are in alarm, THEN SELECT the alarming monitor that has the highest radiation level AND GO TO Step 8.2.3.5.
8.2.3.3 IF R-12 is in alarm and is aligned to the CV, THEN select R-12 AND GO TO Step 8.2.3.5.
8.2.3.4 IF R-1 2 is in alarm AND is aligned to the plant vent, THEN GO TO Step 8.2.3.5.
I EPRAD-03 I Rev. 14 l Page 7 of 77
8.2.3.5 IF a bad quality code OR no data is being displayed for the selected monitor, THEN manually enter the reading from the radiation monitor drawer.
NOTE: The default CV release flow of 1.5 CFM is based on the CV design leak rate at design basis CV pressure.
8.2.3.6 IF containment integrity is maintained, THEN GO TO Step 8.2.4.
8.2.3.7 IF containment integrity is NOT maintained, THEN enter the leak rate escaping through an unmonitored pathway in the FLOW field (next to R-32A).
8.2.4 PLANT VENT STACK Group 8.2.4.1 IF NO monitors in the PLANT VENT STACK group are in alarm, THEN GO TO Step 8.2.5.
8.2.4.2 IF R-14E is above 50 cpm, THEN select R-14E AND GO TO Step 8.2.4.6.
8.2.4.3 IF R-14D is above 12 cpm, THEN select R-14D AND GO TO Step 8.2.4.6.
8.2.4.4 IF R-14C is in alarm, THEN select R-14C AND GO TO Step 8.2.4.6.
8.2.4.5 IF R-21 is in alarm, THEN select R-21.
8.2.4.6 IF a bad quality code OR no data is being displayed for the selected monitor, THEN manually enter the reading from the radiation monitor drawer.
8.2.4.7 IF R-21 was selected, THEN GO TO Step 8.2.5.
8.2.4.8 IF a good quality code is provided for stack flow, THEN GO TO Step 8.2.4.9.
8.2.4.9 SELECT the operating ventilation units.
8.2.4.10 IF R-12 is NOT in alarm, THEN GO TO Step 8.2.6.
8.2.4.11 IF R-12 is aligned to the CV, THEN GO TO Step 8.2.6.
8.2.4.12 IF R-14C OR R-14D OR R-14E were selected in Step 8.2.4 THEN GO TO Step 8.2.6.
I EPRAD-03 I Rev. 14 l Page 8 of 77
8.2.4 (Continued) 8.2.4.13 IF R-21 was selected in Step 1.2.4 AND HVE-15 is the only release pathway, THEN GO TO Step 8.2.6.
8.2.4.14 SELECT R-12.
8.2.4.15 IF a bad quality code OR no data is being displayed for R-12, THEN manually enter the reading from the radiation monitor drawer.
NOTE: The groups of HVE units in the PLANT VENT STACK group or Attachment 10.8, Flow Rates, can be used to determine the following flow rate.
8.2.4.16 SELECT the plant vent stack flow field AND ENTER the determined flow rate through the plant vent stack.
8.2.5 LOWER FHB => ENVIRONMENT Group 8.2.5.1 IF NO monitors in the Lower FHB r ENVIRONMENT group are in alarm, THEN GO TO Step 8.2.6.
8.2.5.2 IF R-20 is in alarm AND has NOT failed high, THEN SELECT R-20 AND GO TO Step 8.2.5.4.
8.2.5.3 IF R-20 has failed high, THEN SELECT R-30.
8.2.5.4 IF a bad quality code OR no data is being displayed for the selected monitor, THEN manually enter the reading from the radiation monitor drawer.
8.2.6 SECONDARY RELEASE 8.2.6.1 IF NO R-31 monitors are reading greater than one mRem/hr, THEN GO TO Step 8.2.7.
8.2.6.2 IF steam/water is escaping from a Main Steam Line through a faulted Main Steam System outside containment AND the affected radiation monitor is reading greater than one mRem/hr, THEN GO TO step 8.2.6.4.
8.2.6.3 IF NO PORVs AND NO SRVs are open, THEN GO TO Step 8.2.6.6.
8.2.6.4 Select PORV/SRV.
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8.2.6 (Continued) 8.2.6.5 IF a bad quality code OR NO data is being displayed for the selected monitor, THEN manually enter the reading from the radiation monitor drawer.
8.2.6.6 IF the release is due to a Main Steam System fault as described in Step 8.2.6.2, THEN using the Main Steam indications on the RTGB and Attachment 10.8 to compare flow rates, ENTER the PORV and SRV combination that would produce the same flow rate as the fault, in the fields below the monitor(s) in alarm, AND GO TO Step 8.2.6.9.
8.2.6.7 IF the PORV on the Main Steam Line(s) that has the monitor(s) in alarm are open, THEN ENTER 1 in the PORV field below the monitor(s)in alarm.
8.2.6.8 IF any SRV(s) on the Main Steam Line(s) that has(have) the monitor(s) in alarm are open, THEN enter the number open in the SRV field below the monitor(s) in alarm.
8.2.6.9 IF a bad quality code OR no data is being displayed in the SG Press field(s) below the monitor(s) in alarm, THEN manually enter the correct pressure as obtained from control room readouts.
8.2.7 STEAM > CONDENSER 8.2.7.1 IF R-15 is NOT in alarm, THEN GO TO Step 8.2.8.
8.2.7.2 IF R-14C OR R-14D OR R-14E were NOT selected in the Plant Vent Stack group OR R-1 2 was NOT selected in Step 8.2.5.6, THEN SELECT Steam > Condenser.
8.2.7.3 IF R-1 5 is in alarm AND has NOT failed high, THEN SELECT STEAM=>CONDENSER AND GO TO Step 8.2.7.5.
8.2.7.4 IF a bad quality code OR no data is being displayed for R-1 5, THEN manually enter the reading from the radiation monitor drawer.
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8.2.7 (Continued) 8.2.7.5 IF only one vacuum pump is running, THEN SELECT 310 CFM flow AND GO TO Step 8.2.7.7.
8.2.7.6 IF two vacuum pumps are running, THEN SELECT 610 CFM flow.
8.2.7.7 Left click the Done button.
8.2.8 SPECTRUM DETERMINATION 8.2.8.1 IF the incident does NOT involve the reactor (i.e. spent fuel, waste gas, old spent fuel), THEN GO TO Step 8.2.8.6.
NOTE: The core uncovery time will be the time that a RED status occurs on the CORE COOLING critical safety function status tree until the tree conditions return to yellow status (core covered and core exit thermocouples < 7000 F). This determination can be performed on the TV monitor or on the manual board.
8.2.8.2 IF the incident involves the reactor AND the core has NOT been uncovered, THEN GO TO Step 8.2.8.5.
8.2.8.3 Select the time that the core has been uncovered:
- 1. <30 minutes
- 2. 0.5 - 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (30 minutes - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 48 minutes)
- 3. > 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 48 minutes) 8.2.8.4 GO TO Step 8.2.9.
8.2.8.5 IF the incident involves mechanical damage to fuel in the reactor, THEN select'< 30 minutes' AND GO TO Step 8.2.9.
8.2.8.6 IF the incident involves a Waste Gas Decay Tank, THEN SELECT Waste Gas AND GO TO Step 8.2.9.
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8.2.8 (Continued)
I NOTE: Spent fuel that is being shipped or is in preparation for shipment should be classified as OLD SPENT FUEL. Assume that the spent fuel has been out of the reactor core for less than three years if the true time is unknown.
8.2.8.7 IF the incident is a fuel handling accident AND involves spent fuel that has been out of the reactor core for less than three years, THEN SELECT Spent Fuel AND GO TO Step 8.2.9.
8.2.8.8 IF the incident is a fuel handling accident AND involves spent fuel that has been out of the reactor core for more than three years, THEN SELECT Old Spent Fuel.
8.2.9 FILTRATION/CV SPRAYS/PARTITIONING NOTE: Attachment 10.5, Accident Mitigation Systems, of this procedure describes if Filtration/CV Sprays/Partitioning are "Effective" or "Not Effective".
8.2.9.1 IF Filtration OR CV Sprays OR Partitioning are effective, THEN SELECT Effective AND GO TO Step 8.2.10.
8.2.9.2 IF Filtration OR CV Sprays OR Partitioning are NOT effective, THEN SELECT Not Effective AND GO TO Step 8.2.10.
8.2.1 0 METEOROLOGY CAUTION If direct access to the meteorological tower has failed, the data will appear colored red in the input fields. DO NOT USE THIS DATA.
8.2.10.1 IF meteorological data with a good quality code is being displayed, THEN GO TO Step 8.2.11.
8.2.10.2 IF a bad quality code OR no data is being displayed for meteorological data, THEN left click the REFRESH button to make a second attempt to acquire meteorological data from ERFIS.
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8.2.10 (Continued) 8.2.10.3 IF the computer makes the connection to the meteorological tower AND the meteorological data is properly updated (in accordance with Caution Statement above), THEN GO TO Step 8.2.11.
8.2.10.4 IF meteorological data is NOT available from the control room computer, THEN manually update the meteorological data.
8.2.10.5 Call the Progress Energy offsite meteorological contact (See the ERO Phone Book for number).
8.2.10.6 IF meteorological data is available from the Progress Energy offsite meteorological contact, THEN manually update the meteorological data AND GO TO Step 8.2.10.11.
NOTE: If the Florence Airport or the National Weather Service office is called, the only information that can be obtained is the wind direction, wind speed, and ambient temperature. Stability factor must be obtained from Step 8.2.10.11 of this procedure. If wind speed and direction are only supplied for one point enter these values in both the elevated and ground fields. Do not enter wind gust as the wind speed, and if no Delta T is supplied do not enter one.
8.2.10.7 Call the Florence Airport: (See the ERO Phone Book for numbers) 8.2.10.8 IF meteorological data is available from the Florence Airport, THEN manually update the meteorological data AND GO TO Step 8.2.10.11 8.2.10.9 Call the National Weather Service office in Columbia, South Carolina: (See the ERO Phone Book for numbers) 8.2.10.10 IF meteorological data is available from the National Weather Service, THEN manually update the meteorological data.
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8.2.10 (Continued) 8.2.10.11 IF there is no stability class data available, THEN make an estimate of the current Atmospheric Stability Class by visual observation, using the following table:
Rain, Sunny Cloudy Cloudy Clear Day or Day Day Night Night NgAht light wind or calm D B C E F
(< 11.5 mph) moderately strong D C D D D wind.( 11.5 mph) 8.2.10.12 Enter the stability class in the appropriate field.
8.2.10.13 Left click the Shutdown time field.
8.2.11 REACTOR SHUTDOWN TIME 8.2.11.1 IF the reactor is NOT shutdown, THEN GO TO Step 8.2.12.
8.2.11.2 IF the reactor is shutdown AND the shutdown time is not displayed OR is not correct, THEN manually enter the date and time of shutdown in the space provided.
8.2.12 RELEASE DURATION NOTE: The estimated release duration should be from the start of the release until the projected time that the release should stop. This can be determined by estimating the completion of a damage control mission, performance of a repair to stop the release, or the estimated time until the RCS, CV Sump, or Steam Generator is below 2000 F.
8.2.12.1 IF the release duration is known, THEN manually enter the release duration in the field provided AND GO TO Step 8.2.12.4.
8.2.12.2 IF the release duration is unknown AND an estimate is available, THEN enter the estimated time in the field provided AND GO TO Step 8.2.12.4.
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8.2.12 (Continued) 8.2.12.3 IF the release duration is unknown AND no estimate is available, THEN enter 2 in the field provided AND GO TO Step 8.2.13.
8.2.12.4 Left click the Done button.
8.2.12.5 The dose projection will be given on the screen.
8.2.13 Using the information supplied NOTIFY the government officials as per the requirements of EPNOT-01.
8.3 Use Of The Dose Projection Program By The Dose Projection Team 8.3.1 ACCESS the software using Section 8.1 of this procedure AND RETURN to Step 8.3.2.
8.3.2 The main menu screen will appear. The items in this menu can be accessed by clicking the left button on any of these items. Six menu topics are available for use. They are listed here along with the section in this procedure which explains their use.
Projection 8.3.3 Contingency 8.3.4 Int Phase 8.3.5 Graphics 8.3.6 Utilities 8.3.7 Exit 8.3.8 I EPRAD-03 I Rev. 14 l Page 15 of 77
8.3 (Continued)
NOTE: The Dose Projection Program should be used to calculate the uTotal Dose" from the start of the release until the projected end. To do so conservatively, the Dose Projection Team may decide to use the estimated peak release rate throughout the release period. If no information is available, the current release rate should be considered constant throughout the release period.
8.3.3 PROJECTION This menu item should be used to perform early phase dose projections based on plant radiation monitors, plant samples, or environmental samples.
8.3.3.1 Control Room This function should be used by control room personnel. Its use is described in Step 8.2 of this procedure.
8.3.3.2 RMS This function should be used by the dose projection team to perform dose projections when adequate data is available from the plant effluent monitors.
The following steps are for guidance and are not required to be performed in entirety or in the order in which they are given.
- 1. The first screen that will appear when this menu option is selected is the ROBINSON EFFLUENT MONITORS screen. The following items should be considered when using this screen:
NOTE: Attachment 10.12, RMS Monitored Systems can be used to determine the relationship between radiation monitors and effluent pathways.
- Quality codes will be displayed on this screen as indicated in Attachment 10.3, Quality Codes of this procedure.
- Dose projections for more than one release pathway can be performed using this program. The monitors are grouped on this screen according to the release pathway that they monitor. Therefore, only one monitor from each group can be selected each time the dose projection program is executed.
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8.3.3 (Continued)
- 2. The Containment to Environment release path is a valid release path in most situations even when no containment leakage has been identified. The 1.5 cfm flow is the design basis release rate when the CV is pressurized to design basis pressure. If containment leakage is into the Auxiliary Building and the release is monitored by a stack monitor, a dose projection using the containment monitors is not necessary.
NOTE: If a projection is made using R-1 2 aligned to the plant vent it will be based on a ground level release pathway instead of a mixed mode release.
- R-1 2 is usually lined up to the containment atmosphere.
If a dose projection is performed using R-12, ensure that it aligned the way that it is being used.
- R-12 can be used to perform a dose projection when it is aligned to the plant vent. In order to accomplish this the R-1 2 plant vent flowrate must be manually entered into the containment monitors flowrate field. If this is performed, then it can not be accomplished at the same time that a dose projection is being performed based on containment leakage. For this reason, if a projection is needed based on both release paths, they must be performed separately and manually added together.
- 3. The flow rate for the R-1 4 monitors will be automatically updated by ERFIS to reflect the plant vent stack when ERFIS is available.R-21 has a default flow rate which is equivalent to the flow of HVE-1 5. This default value should normally be used, because this is the effluent volume that this detector is monitoring.
- 4. R-20 and R-30 have a default flow rate which is equivalent to the flow of HVE-1 4.
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8.3.3 (Continued)
- 5. R-31A, 31 B, and 31 C should not normally be used if they are below 1 mRem/hr. However, if they are, they must be background corrected and manually entered. Obtain the latest valid normal reading from the weekly background/alarm setpoint check or other source (Attachment 10.11, Typical RMS Data, may be used) and subtract the normal reading from the control room readout and enter this value.
- If a release is due to a faulted steam line, a dose projection can be performed by selecting the number of SRV's and PORV that would approximate the release (use Attachment 10.8, Flow Rates). The UNKNOWN MIX under the CONTINGENCY menu can be used to perform a dose projection under this condition using Attachment 10.7, Source Term Determination, Part E.
NOTE: If a dose projection is performed using R-15 and the release is due to a break in the line between the condenser vacuum pumps and the plant vent stack, the projection will be based on a mixed mode release, instead of a ground level release.
- 6. The program will allow you to perform dose projections using the R-15 monitor and the plant vent monitors at the same time.
However, this should only be done under the following circumstances:
- R-15 is above background AND the line from the condenser vacuum pumps to the plant vent is allowing leakage, OR
- R-15 is above background AND NEITHER R-14C, R-14D, R-1 4E, NOR R-1 2 when it is aligned to the plant vent, are being used for a dose projection.
- 7. Once selections have been made on this screen, THEN SELECT the DONE field.
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8.3.3 (Continued) 8.3.3.3 The SPECTRUM DETERMINATION screen is the next screen that will appear. Several characteristics of the incident must be entered on this screen in order to identify the source term.
NOTE: Only one of the following conditions can exist for each execution of the Dose Projection Program. If more than one of the following conditions exist, the projection should be executed more than once using the appropriate effluent monitors to accurately quantify the effluent.
- 1. IF the incident involves the reactor, THEN SELECT the time that the reactor core has been uncovered using the guidelines in Attachment 10.4, Core Uncovery Time Determination.
- 2. IF the incident involves Spent Fuel, regardless of the location, THEN IDENTIFY whether the fuel is Spent Fuel or Old Spent Fuel. Old Spent Fuel is fuel that has not been in the reactor while critical for three years or more.
- 3. IF the incident involves a Waste Gas Decay Tank, THEN SELECT the Waste Gas option.
NOTE: The estimated release duration should be from the start of the release until the projected time that the release should stop. This can be determined by estimating the completion. of a damage control mission, performance of a repair to stop the release, or the estimated time until the RCS, CV Sump, or Steam Generator is below 2000 F.
- 4. DETERMINE the Release Duration AND ENTER the value in the appropriate field.
- 5. IF an estimate of the time is not known, THEN ENTER two hours until better information is available.
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8.3.3 (Continued)
NOTE: A Plant Operations Advisor, the Accident Assessment Team, or the Shift Technical Advisor should be consulted to determine whether these mitigation systems are operable.
- 6. DETERMINE the effectiveness of Filtration/CV Sprays/Partitioning using the guidelines in Attachment 10.5, Accident Mitigation Systems, to make this determination.
- 7. ENTER the meteorology data. IF the quality codes are bad or questionable, THEN UPDATE meteorology data using Attachment 10.6, Obtaining and Updating Meteorological Data for guidance.
- 8. IF the reactor is shutdown, THEN ENTER the shutdown date and time in the appropriate fields. Otherwise, these fields can be left as they appear.
- 9. Click on the DONE field when all of the information on this screen has been entered.
8.3.3.4 PLANT SAMPLE This function is for use by the dose projection team to perform dose projections based on plant samples of the effluent stream. It should be used as needed by the dose projection team. The screen that will appear when this menu option is selected should be completed with the help of the following guidelines.
- 1. ENTER the activity of each nuclide that is listed on the screen that is available from the plant sample analysis.
- 2. IDENTIFY the release height of the effluent.
- SELECT mixed if the release is through the plant vent regardless of the wind speed.
- SELECT ground if the release is by any other pathway, or if the pathway is unknown.
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8.3.3 (Continued)
- 3. ENTER the time from sample to release to correct the sample activity for any radioactive decay that has occurred in the sample effluent between the time the sample was collected and the time of the release. DO NOT enter a value in this field unless you wish to decay correct the effluent stream.
- 4. ENTER the flow rate in cfm of the effluent stream. Care should be taken to understand where the sample was obtained, and ensure that the FLOW field data corresponds with the flow of the sampled air with no further dilution. A flow rate can be manually entered using the flow rates in Attachment 10.8, Flow Rates, as a reference, or a flow can be selected by selecting the FLOWS field.
NOTE: The estimated release duration should be from the start of the release until the projected time that the release should stop. This can be determined by estimating the completion of a damage control mission, performance of a repair to stop the release, or the estimated time until the RCS, CV Sump, or Steam Generator is below 2000 F.
- 5. ENTER the release duration in the appropriate field. IF the release duration is unknown, THEN ENTER a default of two hours.
- 6. ENTER the meteorology data in the appropriate fields.
- 7. IF the reactor is shutdown, THEN ENTER the shutdown date and time in the appropriate fields.
- 8. Click on the DONE field when all of the information on this screen has been entered.
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8.3.3 (Continued) 8.3.3.5 ENVIRONMENTAL SAMPLE This function is for use by the dose projection team to perform dose projections based on environmental samples. It should be used as needed by the dose projection team. The screen that will appear when this menu option is selected is titled as the ENVIRONMENTAL MONITORING TEAM. It should be completed with the help of the following guidelines.
NOTE: Protective action recommendations are required to be made within 15 minutes of obtaining environmental sample results. (AR #48774)
- 1. ENTER the closed window dose rate (in mRem/hr) that is obtained at a height of approximately one meter above the ground. The value should be obtained from the Environmental Monitoring Team Leader and should reflect the most recent data that is available from near the centerline of the plume.
- 2. For the air sample dose rate. SELECT the CART field AND ENTER data in the appropriate fields using the following guidance:
- ENTER the sample volume in cubic feet.
- SELECT whether count rate or dose rate will be entered.
- ENTER the count rate or dose rate on contact with the iodine cartridge. This data should be obtained from the Environmental Monitoring Team Leader and should reflect the most recent data that is available from the centerline of the plume.
- SELECT the DONE field and the program will calculate the Thyroid Committed Dose Rate. (This calculation is based on Attachments in EPRAD-01, Environmental Monitoring.)
- SELECT the CANCEL field to exit this window or click the mouse outside of the window.
- ENTER the downwind distance from the plant stack to the sample collection location.
- ENTER the direction from the plant that the sample was collected in degrees.
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8.3.3.5 (Continued)
- ENTER the release duration in the appropriate field. IF the release duration is unknown, THEN ENTER a default of two hours.
- IDENTIFY the release height of the effluent.
- a. SELECT mixed if the release is through the plant vent regardless of the wind speed.
- b. SELECT ground if the release is by any other pathway, or if the pathway is unknown.
- ENTER the meteorology data in the appropriate fields.
- IF the reactor is shutdown, THEN ENTER the shutdown date and time in the appropriate fields.
- 3. The DONE field should be selected when all of the information on this screen has been entered.
8.3.4 CONTINGENCY Contingency calculations are typically "what if" types of calculations that allow the Dose Projection Team to make predictions of off-site dose based on a projected event. However, they can be used to make actual dose projections.
8.3.4.1 KNOWN MIX This function allows the user to input the isotopic analysis of the release in order to perform a dose projection. The screen that will appear when this menu option is selected should be completed with the help of the following guidelines.
- 1. ENTER the activity of each nuclide that is listed on the screen which could be in a postulated release.
- 2. IDENTIFY the release height of the effluent.
- SELECT mixed if the release is through the plant vent regardless of the wind speed.
- SELECT ground if the release is by any other pathway, or if the pathway is unknown.
- 3. ENTER the time from when the isotopic activities were determined until the release could begin. This is not required and should only be entered when it is expected that the activity has decayed since the sample was pulled.
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8.3.4 (Continued)
- 4. ENTER the number of Curies that could be released using Attachment 10.7, Source Term Determination.
- 5. ENTER the meteorology data in the appropriate fields.
- 6. IF the reactor is shutdown, THEN ENTER the shutdown date and time in the appropriate fields.
- 7. The DONE field should be selected when all of the information on this screen has been entered 8.3.4.2 UNKNOWN MIX This function allows the user to project what the offsite dose to the public would be due to a release if the total activity of the release is known but the isotopic abundances are not known. The screen that will appear when this menu option is selected should be completed with the help of the following guidelines.
NOTE: Only one of the following conditions can exist for each execution of the Dose Projection Program. If more than one of the following conditions exist, execute the projection more than once using the appropriate effluent monitors to accurately quantify the effluent.
- 1. IF the incident involves the reactor core, ENTER the time that the reactor core has been uncovered or could be uncovered.
Use Attachment 10.4, Core Uncovery Time Determination, to help make this determination.
- IF the incident involves Spent Fuel, regardless of the location, IDENTIFY whether the fuel is Spent Fuel or Old Spent Fuel. Old Spent Fuel is fuel that has not been in the reactor while critical for three years or more.
- IF the incident involves a Waste Gas Decay Tank, THEN SELECT the Waste Gas option.
- ENTER the number of Curies that could be released using Attachment 10.7, Source Term Determination, to help determine this value.
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8.3.4 (Continued)
- IDENTIFY the release height of the effluent.
- a. SELECT mixed if the release is through the plant vent regardless of the wind speed.
- b. SELECT ground if the release is by any other pathway, or if the pathway is unknown.
- DETERMINE the effectiveness of Filtration/CV Sprays/Partitioning using the guidelines in Attachment 10.5, Accident Mitigation Systems, to make this determination.
- ENTER the meteorology data in the appropriate fields.
- IF the reactor is shutdown, THEN ENTER the shutdown date and time in the appropriate fields.
- 2. The DONE field should be selected when all of the information on this screen has been entered.
8.3.4.3 DEFAULTS This function allows the user to hypothesize what the offsite dose to the public would be due to a postulated release if plant conditions are unknown. A default should only be used when neither the total activity nor the isotopic analysis of the potential release are known. The screen that will appear when this menu option is selected should be completed with the help of the following guidelines.
CAUTION Calculated dose using defaults are EXTREMELY conservative and may assume all of the core activity is released, depending on the spectrum determination.
- 1. IF the incident involves the reactor core, ENTER the time that the reactor core has been uncovered or could be uncovered.
Use Attachment 10.4, Core Uncovery Time Determination, to help make this determination.
- IF the incident involves Spent Fuel, regardless of the location, IDENTIFY whether the fuel is Spent Fuel or Old Spent Fuel. Old Spent Fuel is fuel that has not been in the reactor while critical for three years or more.
- IF the incident involves a Waste Gas Decay Tank, THEN SELECT the Waste Gas option.
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8.3.4 (Continued)
- ENTER the number of Curies that could be released using Attachment 10.7, Source Term Determination, to help determine this value.
- IDENTIFY the release height of the effluent.
- a. SELECT mixed if the release is through the plant vent regardless of the wind speed.
- b. SELECT ground if the release is by any other pathway, or if the pathway is unknown.
- DETERMINE the effectiveness of Filtration/CV Sprays/Partitioning using the guidelines in Attachment 10.5, Accident Mitigation Systems, to make this determination.
- ENTER the meteorology data in the appropriate fields.
- IF the plant has shutdown, THEN ENTER the shutdown date and time in the appropriate fields.
- 2. The DONE field should be selected when all of the information on this screen has been entered.
8.3.5 INTERMEDIATE PHASE Intermediate phase calculations are used during the intermediate phase of an emergency to project the one year, two year, and fifty year committed dose to the public due to exposure from contamination deposited on the ground. The calculations are based on environmental data.
8.3.5.1 DOSE RATE This function is used to calculate the projected doses using dose rate data from environmental monitoring teams. The screen that will appear when this menu option is selected should be completed with the help of the following guidelines.
- 1. DETERMINE if weathering (radioactive decay) should be considered when performing this function.
- 2. IF weathering should be considered, THEN SELECT the UTILITIES function from the main menu AND FOLLOW the guidelines in Step 8.3.7 of this procedure.
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8.3.5 (Continued)
NOTE: If no data has been entered under the "Sample" then the "Average Spectrum" choice will not appear, and only the Default Spectrum can be used.
- 3. ENTER the closed window dose rate in mRem/hr taken at approximately one meter from the ground in the 1 meter dose rate field.
- 4. ENTER the straight line distance in miles or fractions of miles from the plant vent that the sample was taken.
- 5. ENTER the bearing in degrees from the plant for the sample location.
- 6. DETERMINE if the Default Spectrum or the Average Spectrum should be used to perform the projection. The Average Spectrum should be selected if adequate data has been entered in the SAMPLE screen.
- 7. SELECT the DONE field when complete and the dose will be given.
8.3.5.2 SAMPLE This function is used to calculate the projected dose using isotopic analysis of samples collected by environmental monitoring teams. The screen that will appear when this menu option is selected should be completed with the help of the following guidelines.
- 1. DETERMINE if weathering (radioactive decay) should be considered when performing this function.
- 2. IF weathering should be considered, THEN SELECT the UTILITIES function from the main menu AND FOLLOW the guidelines in Step 8.3.7 of this procedure.
- 3. ENTER the isotopic activity of each nuclide that is present in the sample that is listed on the screen. These activities should be entered in units of pCi/M2. The nuclides that are listed on this screen are the only ones in RNP's anticipated source term that have a long enough half-life to contribute significant dose.
- 4. ENTER the sample identification number. This will normally be our radiochemistry form number.
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8.3.5 (Continued)
- 5. DETERMINE if the sample should be added to the sample data base from which the average deposition is calculated. Choosing this option will also include the sample in the average spectrum function of the DOSE RATE option.
- 6. ENTER the straight line distance in miles or fractions of miles from the plant vent that the sample was taken.
- 7. ENTER the direction in degrees from the plant for the sample location.
- 8. SELECT the DONE field when complete and the dose will be given.
8.3.6 GRAPHICS This menu item provides a graphic display of the 10 mile and 50 mile Emergency Planning Zones. It should be used as an aid by the Dose Projection Team to help with Protection Action Recommendations, and determining the adequacy of the environmental monitoring efforts.
NOTE: The latest graphics of the 10 MILE ISOPHLETHS and the 10 MILE PARs are automatically saved to a disk file. They can be printed using the Microsoft Paintbrush program.
8.3.6.1 10 MILE ISOPLETHS This function provides a display of the isopleths within the 10 mile Emergency Planning Zone where the TEDE and Thyroid CDE limits are exceeded. If isopleths do not appear the EPA PAGs are not exceeded by the latest dose projection.
8.3.6.2 10 MILE PARS This function displays the evacuation Protective Action Recommendations for the 10 Mile Emergency Planning Zone. This display consist of a five mile radius with a two mile keyhole superimposed on the map. The two mile keyhole applies to only the two mile sector (AO). Any of the five mile sectors (Al, 1l, Cl, Dl, and El) that are intersected by the five mile radius keyhole should be evacuated. If the dose at the centerline of the plume exceeds the EPA PAGs at any distance five miles or beyond, then the radius of the keyhole is extended to ten miles. Any of the ten mile sectors (A2, B2, C2, D2, and E2) which are intersected by the ten mile keyhole should be evacuated.
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8.3.6 (Continued) 8.3.6.3 10 MILE EMT POINTS This function provides a method to enter and display Environmental Monitoring Team Data in the 10 mile EPZ.
- 1. CLICK the mouse on the map location were the sample was taken.
- 2. ENTER the closed window dose rate taken at approximately one meter above the ground. USE units of mRem/hr AND DEPRESS the enter key when complete.
- 3. The computer will update the sample point with a color coded circle depending on the dose rate recorded at the location.
These color codes are given in the upper right hand corner of the screen.
8.3.6.4 50 MILE INT PHASE 8.3.6.5 This function provides a method to enter Environmental Monitoring Team Data in the 50 mile EPZ, and calculate and display the 1, 2, and 50 year committed doses along with the skin dose.
- 1. CLICK the mouse on the map location were the sample was taken.
- 2. ENTER the closed window dose rate taken at approximately one meter above the ground. USE units of mRem/hr AND DEPRESS the enter key when complete.
- 3. The computer will update the sample point with a color code that represents if the program is above the EPA limits, above normal background, at background level. It will also calculate the 1, 2, and 50 year committed doses along with the skin dose.
8.3.7 UTILITIES This menu item is provided to assist the Dose Projection Team. These functions can be used at any time they are needed while using the program.
8.3.7.1 WEATHERING This function is used when performing an Intermediate Phase Dose Projection to account for reductions in the source term due to weathering and radioactive decay.
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8.3.7 (Continued) 8.3.7.2 PRINTING SETUP This function can be used to configure printing from this application. The user can configure custom printers and enable or disable the automatic printing of dose projection screens.
8.3.7.3 DISTANCES This function allows the user to adjust the distances from the plant that dose projections are calculated. This is done by identifying the maximum distance from the plant and the increment between each distance that is desired. This function is especially useful in determining distances close in to the site or beyond 10 miles.
8.3.7.4 NOTIFICATION This function will saves the on-screen dose projection information to a storage file linked to automatic entry of the dose projection into the Emergency Notification Form.
8.3.7.5 MANUAL SCREEN PRINT Use this menu item to print the currently displayed dialog or screen. The printout will be directed to the default printer for the workstation unless a custom printer has been selected.
8.3.8 EXIT 8.3.8.1 This menu item will exit the dose projection program when it is selected.
8.4 Interpretation Of The Dose Projection Summary Table This summary table appears on the screen after the dose projection calculation has been completed.
8.4.1 The first column at the top of this table is the distance from the plant. These distances default to Site Boundary, 2 Miles, 5 Miles, and 10 Miles. The distance along the centerline of the plume is identified in the Max row.
8.4.2 The second column at the top of this table is the TEDE in mRem. This will give the value that is entered on the Notification Form in the appropriate location.
8.4.3 The third column at the top of this table is the Thyroid CDE in mRem. This will give the value that is entered on the Notification Form in the appropriate location.
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8.4 (Continued) 8.4.4 The next three columns give the Effective Dose Equivalent due to Immersion in the plume, the Committed Effective Dose Equivalent due to inhalation, and the Effective Dose Equivalent due to ground deposition. These columns are provided for information only.
8.4.5 The final column at the top of the table gives the X/Q value in s/m3. This value should be provided to the State and Federal Emergency Response Officials when requested. For stability classes E, F, and G in MIXED MODE RELEASES, the X/Q is extremely small at the site boundary when compared with the other X/Q values.
8.4.6 The Dose Projection Summary Table also contains the Dose Projection Meteorology Data.
8.4.7 The reactor shutdown time is also found on this table.
8.4.8 The Projection Time which the Notification Form refers to is listed on the table as the Calculation Time.
NOTE: The following two steps are very important for proper correlation between the dose projections performed by HBR's Dose Projection Team and the projections performed by State personnel. The Xe-1 33 Equivalent Release and the 1-131 Equivalent Release values are used by South Carolina Department of Health and Environmental Control for input into their dose assessment program.
8.4.9 The Xe-133 Equivalent Release is provided on this table and it is the value that should be entered as the Noble Gas Activity on the Notification Form. If any results are questionable, then Attachment 10.17 should be used to calculate this value.
8.4.10 The 1-131 Equivalent Release is provided on this table and it is the value that should be entered as the Iodine Activity on the Notification Form. If any results are questionable, then Attachment 10.17 should be used to calculate this value.
8.4.11 The Dosimeter Correction Factor that is provided on this table should only be used when the Radiological Control Manager has directed that a Dosimeter Correction Factor is necessary, and there is not adequate data to calculate one using environmental data.
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NOTE: The Emergency Action Level provided by the dose projection program is for INFORMATION ONLY. All Emergency Classifications shall be made by using the EAL procedures.
8.4.12 Emergency Action Levels If an Emergency Action Level due to a dose projection is exceeded, the output screen will indicate the appropriate classification. Evaluate the EAL Flow Charts and compare the dose calculation against the EAL's to determine the Emergency Classification. NOTIFY the RCM of all Emergency Action Levels that the program recommends.
8.4.13 HBRDOSE/RASCAL Attachment 10.16, HBRDOSE/RASCAL Comparison Matrix can be used to discuss differences in plant dose projections and those performed using the NRC's RASCAL program.
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8.5 Manual Calculation of Dose Projection Results This section provides instructions for performing and documenting manual dose projection calculations.
8.5.1 IF ERFIS is unavailable, THEN DETERMINE the atmospheric stability class, wind direction, and wind speed using Attachment 10.6.
NOTE: This manual dose calculation conservatively assumes all releases are ground level releases.
8.5.2 RECORD the meteorological data in the appropriate columns of Attachment 10.18, Manual Dose Projection Work Sheet.
8.5.2.1 IF the meteorological data source indicates a stability class of "G", THEN ENTER stability class 'F" in the appropriate column.
8.5.3 DETERMINE the site boundary X/Q from Table 1 of Attachment 10.18, Manual Dose Projection Work Sheet.
8.5.4 RECORD the selected site boundary X/Q in the appropriate column of Attachment 10.18, Manual Dose Projection Work Sheet.
8.5.5 CALCULATE the source term (Q)in Ci using Attachment 10.7, Source Term Determination.
NOTE: The Curie values entered are the actual Curies of an assumed mix and not dose equivalent Xe-133 or 1-131 Curies.
8.5.6 RECORD the noble gas and iodine source term values in the appropriate column of Attachment 10.18, Manual Dose Projection Work Sheet.
8.5.7 DETERMINE the Dose Conversion Factor (DCF) as follows:
8.5.7.1 IF the nuclide mix of the source term is unknown, THEN DETERMINE the time from reactor shutdown to release AND RECORD in the space provided in Attachment 10.18, Table 3.
8.5.7.2 SELECT the applicable dose conversion factors corresponding to the time from reactor shutdown to release from Table 3 of Attachment 10.18, Manual Dose Projection Work Sheet.
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8.5.7 (Continued) 8.5.7.3 IF the nuclide mix of the source term is known, THEN DETERMINE the time from SAMPLE to release AND RECORD in the space provided in Attachment 10.18, Table 2.
8.5.7.4 CALCULATE the TOTAL DCF using Table 2 of Attachment 10.18, Manual Dose Projection Work Sheet.
8.5.7.5 RECORD the value in the appropriate column of Attachment 10.18, Manual Dose Projection Work Sheet.
8.5.8 MULTIPLY the values in Columns 4, 5, and 6 to obtain the centerline TEDE and Thyroid CDE at the site boundary AND RECORD in the appropriate columns of Attachment 10.18, Manual Dose Projection Work Sheet.
8.5.9 CALCULATE the doses downwind at 2, 5, and 10 miles from the site boundary using the extrapolation factors (Column 9) in Table 1 of Attachment 10.18, Manual Dose Projection Work Sheet 8.5.9.1 MULTIPLY the dose calculated in step 8.5.8 by the extrapolation factors for the 2, 5, and 10-mile distances.
8.5.9.2 RECORD the doses in the appropriate column of Attachment 10.18, Manual Dose Projection Work Sheet.
8.5.10 SUBMIT Attachment 10.18 to the Dose Projection Team Leader AND the Radiological Control Manager for review/approval.
9.0 RECORDS Records generated as a result of the performance of this procedure shall be submitted to Emergency Preparedness for retention in the plant vault.
EPRAD-03 Rev. 14 Page 34 of 77
10.0 ATTACHMENTS 10.1 Definitions and Abbreviations 10.2 General Information 10.3 Quality Codes 10.4 Core Uncovery Time Determination 10.5 Accident Mitigation Systems 10.6 Obtaining and Updating Meteorological Data 10.7 Source Term Determination 10.8 Flow Rates 10.9 Detector Sensitivities 10.10 Measuring Radiation Level on Main Steam Lines 10.11 Typical RMS Values 10.12 RMS Monitored Systems 10.13 Weather Service Data 10.14 Onsite Meteorological Data 10.15 Meteorological Forecast Form 10.16 HBRDOSE/RASCAL Comparison Matrix 10.17 Manual Calculation of Curies Released 10.18 Manual Dose Projection Work Sheet EPRAD-03 I Rev. 14 l Page 35 of 77l
ATTACHMENT 10.1 Page 1 of 3 DEFINITIONS/ABBREVIATIONS Definitions:
Atmosphere Dispersion Factor (X/Q1 - the fraction of activity released that will reach the point of interest (sec/m').
Committed Dose Equivalent- The dose equivalent to organs or tissue of reference that will be received from an intake of radioactive material by an individual during the 50 year period following the intake.
Committed Effective Dose Equivalent - The sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to these organs or tissues.
Core Uncovery Time - The time that inadequate core cooing occurs until the time that adequate core cooling is restored. (See Attachment 10.4).
Early Phase - The period at the beginning of a nuclear incident when immediate decisions for effective use of protective actions are required, and must be based primarily on predictions of radiological conditions in the environment. This phase may last from hours to days. For the purpose of dose projection, it is assumed to last for four days.
Effective Dose Equivalent - The sum of the products of the dose equivalent to each organ and a weighting factor, where the weighting factor is the ratio of the risk of mortality from delayed health effects arising from irradiation of a particular organ or tissue to the total risk of mortality from delayed health effects when the whole body is irradiated uniformly to the same dose. This unit is considered equivalent to be the Deep Dose Equivalent for the purposes of dose projections because the external exposures are considered to be uniform across the whole body.
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ATTACHMENT 10.1 Page 2 of 3 DEFINITIONS/ABBREVIATIONS Intermediate Phase - The period beginning after the incident source and releases have been brought under control and reliable environmental measurements are available for use as a basis for decisions on additional protective actions and extending until these protective actions are terminated. This phase may overlap the early and late phases and may last from weeks to many months. For the purpose of dose projection, it is assumed to last for one year.
Late Phase - The period beginning when recovery action designed to reduce radiation levels in the environment to permanently acceptable levels are commenced, and ending when all recovery actions have been completed. This period may extend from months to years (also referred to as the recovery phase).
Release Duration - The period of time from the beginning of the release until the end of the release or the projected end of the release. This can be determined by estimating the completion of a damage control mission, performance of a repair to stop the release, or the estimated time until the RCS, CV Sump, or Steam Generator temperature is below 2000 F.
Release Rate (Q)- The term in the dose projection which describes the amount of activity that is being released. This is recorded in Curies per second. The total curies released may be calculated from the release rate (Q)and the release duration in seconds.
Total Effective Dose Equivalent - The sum of the deep-dose equivalent (for external exposures) and the committed effective dose equivalent(for internal exposures).
Weathering/Weathering Factor - The fraction of radioactivity remaining after being affected by average weather conditions for a specified period of time.
Abbreviations:
- 1. ALARA - As Low As is Reasonably Achievable
- 2. BSEP - Brunswick Steam Electric Plant
- 3. CDE - Committed Dose Equivalent
- 4. CFM - Cubic Feet per Minute
- 5. CPM - Counts Per Minute
- 6. CV - Containment Vessel
- 7. EAL - Emergency Action Level
- 8. EMT - Environmental Monitoring Team
- 9. EOF - Emergency Operations Facility
- 10. ERFIS - Emergency Response Facility Information System
- 11. ERO - Emergency Response Organization
- 12. GPM - Gallons Per Minute
- 13. HNP - Harris Nuclear Project
- 14. LAN - Local Area Network
- 15. LOCA - Loss Of Coolant Accident EPRAD-03 I Rev. 14 l Page 37 of 77
ATTACHMENT 10.1 Page 3 of 3 DEFINITIONS/ABBREVIATIONS
- 16. PORV - Power Operated Relief Valve
- 17. RCS - Reactor Coolant System
- 18. RMS - Radiation Monitoring System
- 19. SDS - Satellite Display System
- 20. SRO - Senior Reactor Operator
- 21. SRV - Safety Relief Valve
- 22. STA - Shift Technical Advisor
- 23. TEDE - Total Effective Dose Equivalent I EPRAD-03 I Rev. 14 l Page 38 of 77
ATTACHMENT 10.2 Page 1 of 1 GENERAL INFORMATION Backup Capability:
If ERFIS or a computer with the dose projection program are not available, contact computer support personnel and request that they provide a computer with the current revision of the dose projection software installed on it.
R-14 C, D, and E operate as follows:
R-14C is the Normal range Noble Gas monitor.
R-14D is the Intermediate range Noble Gas monitor.
R-14E is the High range Noble Gas monitor.
R-1 4D and R-1 4E normally read between 10 and 11 CPM.
R-14C when increasing will reach its predetermined alarm setpoint. Further increase will cause R-14C to reach its predetermined swap-over setpoint. When the swap-over setpoint is reached, R-1 4C will fail to 1 Meg (1M) which also will cause R-1 4D and R-14E to activate and start providing intermediate and high range noble gas readings.
If R-14C is reading 1 Meg, this SHOULD NOT be used as a valid reading and RMS data SHOULD BE obtained from R-1 4D and R-1 4E.
Special attention should be paid to the quality code of the data on the program. Quality code color schemes are given in Attachment 10.3.
In order to select an item when performing the dose projection press the space bar.
Pressing the space bar will also deselect the item if it had already been selected.
The help menu may be accessed at any time while using the dose projection program.
This can be accomplished by pressing the F1function key. The function can be exited by clicking the mouse on the EXIT field or by pressing the F1 key.
Messages are displayed at the bottom of each screen to describe the function that the cursor is on.
Attachments 10.14, Onsite Meteorological Data, and 10.15, Meteorological Forecast Form, can be used to record weather conditions and forecast.
EPRAD-03 l Rev. 14 l Page 39 of 77
ATTACHMENT 10.3 Page 1 of 1 QUALITY CODES Color of Data Meaning Action Red Stars Computer Entered Bad Data Do Not Use This Data Green Computer Entered Good This Data May Be Used Data Normal Level Yellow Computer Entered Good This Data May Be Used Data Alert Level Red Computer Entered Good This Data May Be Used Data Alarm Level White Manually Entered Data This Data May Be Used I EPRAD-03 I Rev. 14 l Page40of 774
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ATTACHMENT 10.4 Page 1 of 1 CORE UNCOVERY TIME DETERMINATION NOTE: The time determination below is based upon the core level and temperature that the core cooling is insufficient to prevent the cladding from overheating and failing. This basis is conservative for all fuel damage scenarios which result from core uncovery. This time can be determined by consulting a SRO or RO with access to plant data.
- Core uncovery time is defined for dose projection purposes to be the point in time that inadequate core cooling occurs until the time that adequate core cooling is restored. For the purposes of dose projection core uncovery time will be the time that a RED status occurs on the CORE COOLING critical safety function status tree until the tree conditions return to YELLOW status (core covered and core exit thermocouples < 7000 F).
- There are other possible accidents that may result in fuel damage. These events could be initiated by core flow blockage from debris or by localized melting from a rod ejection accident, pump failures, etc. as analyzed by the UFSAR. In this case, judgment may be applied using the bases information for CORE UNCOVERY TIME DETERMINATION above to most closely describe the fuel damage situation. In general choice of "uncovery < 30 min", corresponding to a release of 100% of the gap activity will conservatively account for most mechanical and miscellaneous fuel damage situations.
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ATTACHMENT 10.5 Page 1 of 1 ACCIDENT MITIGATION SYSTEMS The capability to take credit for accident release mitigation systems is built into the dose projection program. Credit is given one of three ways, charcoal filtration, containment sprays, and water partitioning in the steam generator.
NOTE: It is important to note that if the release is mitigated by ANY of the following:
Charcoal Filtration, CV Sprays, or Partitioning, then assume mitigating effects are EFFECTIVE unless information is known to be otherwise. Only if the release pathway is direct to the environment without mitigation, should NOT EFFECTIVE be selected.
Filtration Various fans can be aligned to cleanup effluent from leaking systems. When the release is passing through any one of the following fans, filtration can be considered effective. The general area(s) where the fan draws a suction is listed in parenthesis.
- HVE-1A or HVE-1B (Containment Purge)
- HVE-3 or HVE-4 (Containment Air, In pre-purge mode)
- HVE-5A or HVE-5B (Auxiliary Building Exhaust)
- HVE-15A (Spent Fuel Pit during refueling)
The CV Spray System The CV Spray System is designed to remove radioiodine from containment in the event a radioactive release (typically a LOCA) occurs inside containment. If such a release occurs and the CV Spray System (with NaOH added) is operating, then the CV Sprays are considered effective.
Water Partitioning Occurs during a release through the steam generators (e.g., a tube leak or tube rupture) and level in the affected steam generator is above the top of the tubes.
Partitioning is effective for removing iodines and some particulates when the steam generator level is greater than 10% on the Narrow Range Steam Generator Level Indicator.
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ATTACHMENT 10.6 Page 1 of 5 OBTAINING AND UPDATING METEOROLOGICAL DATA In the manual data entry mode, meteorological data may not be available from ERFIS.
Determine wind direction, wind speed, and atmospheric stability class using one of six methods listed in preferred order of use.
NOTE: Meteorological data will normally display a green value and an UOK' quality code. If the values are displayed in white, or the quality code is "BAD", DO NOT USE THIS DATA.
- 1. If operable, use the data from control room readouts to obtain the atmospheric stability class, wind speed, and wind direction.
- 2. Call the Progress Energy offsite meteorological center (See ERO Phone Book for number).
OR NOTE: If The Florence Airport or the National Weather Service office is called, the only information that can be obtained is the wind direction, wind speed, and ambient temperature. Stability factor must be obtained from Step 5 of this Attachment.
If wind speed and direction are only supplied for one point enter these values in both the elevated and ground fields. Do not enterwind gust as the wind speed, and if no Delta T is supplied do not enter one.
- 3. Call the Florence Airport for Weather Information (See ERO Phone Book for number).
OR EPRAD-03 I Rev. 14 l Page 43 of 77
ATTACHMENT 10.6 Page 2 of 5 OBTAINING AND UPDATING METEOROLOGICAL DATA
- 4. Call the National Weather Service office in Columbia, South Carolina, for daily weather information or in Wilmington, North Carolina, for severe weather information. Use Attachment 10.13 to document this: (See ERO Phone Book for number)
- 5. If there is no stability class data readily available, a general estimate of the current Atmospheric Stability Class can be made by visual observation, using the following table:
Rain, Sunny Cloudy Cloudy Clear Day or Day Day Night Night Night light wind or calm D B C E F
(< 11.5 mph) moderately strong D C D D D wind (> 11.5 mph)
OR l EPRAD-03 I Rev. 14 l Page 44 of 77
ATTACHMENT 10.6 Page 3 of 5 OBTAINING AND UPDATING METEOROLOGICAL DATA
- 6. A manual method may be used to acquire data from the meteorological tower. The following method may be used to manually obtain this data:
A. Obtain the Meteorological Tower Building key from E&RC or Plant Security.
B. Locate the Met Tower recorder inside the building.
C. Locate the Upper Display key on the recorder.
D. Depress the Upper Display key one or more times until the Upper Display is placed in manual control. "MAN" will be displayed in the Lower Display of the recorder.
E. Locate the Channel Up (CH Up) and Channel Down (CH Down) keys on the recorder.
F. Using the Channel Up (CH Up) and Channel Down (CH Down) keys, scroll through the recorder channels to obtain the necessary information required on the "Manual Meteorological Collection Data Sheet" included in this attachment.
G. Using the Differential Temperature values obtained from the recorder, determine the Stability Class as per the table included in this attachment.
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ATTACHMENT 10.6 Page 4 of 5 OBTAINING AND UPDATING METEOROLOGICAL DATA EXAMPLE OF RECORDER CHANNEL SELECTIONS CH 01 LT1 - Lower Temperature #1 (ambient temperature)
CH 02 DT1 - Differential Temperature #1 CH 03 DT2 - Differential Temperature #2 CH 04 LWS - Lower Wind Speed CH 05 LWD - Lower Wind Direction CH 06 UWS - Upper Wind Speed CH 07 UWD - Upper Wind Direction CH 08 DPT - Dew Point MANUAL METEOROLOGICAL COLLECTION DATA SHEET WIND SPEED UPPER WIND SPEED MPH LOWER WIND SPEED MPH WIND DIRECTION UPPER WIND DIRECTION DEGREES LOWER WIND DIRECTION DEGREES AMBIENT TEMPERATURE TEMPERATURE OF DIFFERENTIAL TEMPERATURE DT1 = 0C/1 QOM DT2 = 0C/1 OOM STABILITY CLASS DT1 + DT2 = 0C/1 00M 2
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ATTACHMENT 10.6 Page 5 of 5 OBTAINING AND UPDATING METEOROLOGICAL DATA STABILITY CLASS DIFFERENTIAL TEMP OC/100M (circle one)
A <-1.9 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
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ATTACHMENT 10.7 Page 1 of 5 SOURCE TERM DETERMINATION Part A - Determination of Curies in Containment Atmosphere This calculation can be performed by obtaining the activity in the containment from the RCD or E&RC Team Lead, or by calculating it using the radiation monitor data and their sensitivities. When calculations are performed utilizing radiation levels obtained from R-2, consideration should be given to background correcting the radiation level.
- 1) Containment atmospheric activity:
- As determined by sampling CV atmosphere: "Ci/cc
- Calculation of atmospheric activity from a CV radiation monitor:
Monitor Reading Sensitivity CV Activity R-12 _____cpm / _____cpm/(ACi/cc) = yCi/cc R-2 mRem/hr / __(mRem/hr)/( gCi/cc) = _ gCi/cc R-32A/B rem/hr I (rem/hr)/( giCi/cc) = jiCi/cc
- 2) Equation for determining curies in containment:
Curies in containment' = (CV activity VCi/cc]) (5.7 x 104 [Ci-CC/gCU)
= ( jgCi/cc]) (5.7 x 104 [Ci-cc/gCi])
=_ Ci
- This value can be determined by referencing Attachment 10.9, Table 2. Ensure that the sensitivity that corresponds to the correct accident and shutdown time are used.
I Containment volume as calculated per Calculation RNP-C/CONT-1 002, Determination of Containment Heat Sink, is 2.013 x 106 cubic feet (5.7 x 1010 cc). The value of 5.7 x 104 is used to account for gCi to Ci conversion.
EPRAD-03 I Rev. 14 T Page 48 of 77
ATTACHMENT 10.7 Page 2 of 5 SOURCE TERM DETERMINATION Part B - Determination of Curies in the Reactor Coolant System (RCS)
Obtain the RCS activity from the RCD or the E&RC Team Lead to perform this calculation.
- 1) RCS activity: iiCi/ml
- 2) Equation for determining curies in the RCS:
Curies in RCS = (RCS activity [Ci/mq) (2.65 x 102 Ci-mi/ACi)
= L .j [gCi/ml]) (2.65 x 102 Ci-ml/gpCi)
Ci Part C - Determination of Sump Source Term Obtain the sump activity and the sump volume from the RCD or the E&RC Lead in the OSC to perform this calculation.
- 1) Quantity of liquid in sump gal
- 2) Sump activity _Ci/cc
- 3) Equation for determining curies in sump:
Curies in the sump =
(volume of liquid in sump [galg) (activity of sump [jiCi/mI) (3.79 x 10'3)
= ( [gag) ( [Cim) (3.79 x 10- Ci-ml/jACi-gal)
=_ Ci Part D - Determination of Primary to Secondary Leakage Source Term Obtain the primary to secondary leak rate and RCS activity in order to perform this calculation.
- 1) Primary to Secondary Leakage gal/min
- 2) Source Term (Ci)= (Leakrate gal/min)(6.3E-5)(RCS Activity jiCi/cc) ) (hrs)(3600 sec/hr)
- (ggpm)(6.3E-5)(( jiCi/cc) (hrs)(3600 seclhr)
-CiCissc)( -hhr)(3 600 sec/hr) (hrs)(3600 sec/hr)
Ci EPRAD-03 I Rev. 14 l Page 49 of 77
ATTACHMENT 10.7 Page 3 of 5 SOURCE TERM DETERMINATION Part E - Determination of Source Term Released Due To Secondary Leakage Determine the leakrate from the PORV or SRVs using Attachment 10.8. If the leak is due to a faulted Main Steam System obtain an estimate of the leakrate can be obtained from the Accident Assessment Team.
- 1) Secondary Leakrate cc/sec
- 2) Source Term (Ci) =
mRem/hr x hrx __ _ cc/sec x 3.6E-03 Ci-sec/,Ci-hr R-31 Rad Level Duration Leakrate
- (mRem/hr)/( gCi/cc)
R-31 Sensitivilty Ci
- This value can be determined by referencing Attachment 10.9, Table 2. Ensure that the sensitivity that corresponds to the correct accident and shutdown time are used.
Part F - Determination of Source Term Released Through Main Steam Using Direct Survey Request that the RCD dispatch a member of the plant monitoring team with an extendable probe survey instrument to a location one level below the Main Steam lines as indicated by Attachment 10.10. The probe should be extended to a position adjacent to the low point of each steam line (or as directed by the Dose Projection Team Leader or RCD) to determine the contact dose rate. The status (open/closed) of the PORV and SRVs on the monitored lines should also be noted.
- 1) Contact radiation level on Steam Line: mRem/hr
- 2) Flow Rate: cc /sec (Attachment 10.8 or Accident Assessment Team)
- 3) Detector Sensitivity from Attachment 10.9, Table 1: (mRem/hr)/( PICi/cc*)
- 4) Source Term (Ci) =
mRem/hr x - hrx cc*e 9c x 3.6E-03 Ci-sec/gCi-hr Rid Level Duration Flow Rate
_ (mRem/hr)/(iCi/cc*)
Detector Sensitivity Ci
- Substitute ml for cc when calculations are performed for water filled main steam lines.
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ATTACHMENT 10.7 Page 4 of 5 SOURCE TERM DETERMINATION Part G - Determination of Source Term Released Plant Vent Stack Request that the RCD dispatch a member of the plant monitoring team with an extendable probe survey instrument to obtain a contact radiation level on the side of the plant stack (an instrument with a remote probe can also be used). The measurement should be made inside the shielded orifice which is approximately 4 feet above the Auxiliary Building roof on the south side of the stack.
- 1) Contact radiation level on Plant Vent Stack: mRem/hr
- 2) Release rate = (Use Attachment 10.8)
= (Stack Flow Rate [cfm]) (28320 [cc/ft3]) (60 [min/hr])
= (__ cfm) (28320 cc/ft3) (60 min/hr)
=_ cc/hr
- 3) Detector Sensitivity from Attachment 10.9, Table 1: (mRem/hr)/( iiCi/cc)
- 4) Source Term (Ci) =
mRem/hr x hr x cc/hr x 1E-06 Ci/,Ci Rad Level Duration Release Rate (mRem/hr)/(gCi/cc)
Sensitivity Ci EPRAD-03 Rev. 14 Page 51 of 77
ATTACHMENT 10.7 Page 5 of 5 SOURCE TERM DETERMINATION FOR MANUAL DOSE PROJECTION CALCULATION ONLY RADIOIODINE SOURCE TERM ESTIMATE
- 1) Identify release path (SGTR, Plant Vent, etc):
- 2) Enter the Source Term in Curies as determined in Parts A - G, as applicable. _Ci
- 3) Determine the Iodine/Noble Gas ratio using the following chart:
Iodine/Noble Gas Ratio (Circle the most appropriate value) 1 LOCAN/SGTRN (0-3 hours post 'shutdown) 1
'2. .LOCAN/SGTRN (>3 hours post shutdown) 10
- 3. LOCAG/SGTRG (released from fuel) 0.5 4.': LOCAC/SGTRC (released from fuel) 0.2 5.-.- FHA (ratioat pool/cavity water surface) .... E03
- 6. ' ' . WGDTR (ratio at tank release) 1 E-04
- 4) Multiply the source term from Step 2 by the appropriate Iodine/Noble Gas Ratio. Ci
- 5) Iodine Decontamination Factors - Enter DF for each removal mechanism that exists and multiply together to obtain Total DF:
Partitioning (LOCANSGTR: water flashing): Default DF- 5 . - ---- - - - -
Plateout (LOCA/SGTR in containment or OTSG): Default DF =3 '- ' -: ' . *. '
CV Sprays: Default DF = 10 for 0-2 hrs spray time 100 for> 2 hrs spray time : __'_____________-
SGTR via Condenserror Air.Ejector: Default OF 100 _______________'_
,CV/Aux Bldg HVAC Filters: Default DF 20 i_____'_'_-i Total DF -_-_-_ -__
- 6) Divide the source term as determined in Step 4 by the Total DF to obtain the radioiodine source term. Ci N = Normal RCS, G = Gap Release, C = Core Damage I EPRAD-03 I Rev. 14 Page 52 of 77
ATTACHMENT 10.8 Page 1 of 5 FLOW RATES R-1l1. R-12. R-14 HVE-2A/B ........................................ 4.4 x 104 cfm HVE-2A/B and HVE-15/15A ........................................ 5.5 x 104 cfm HVE-2A/B and HVE-1A/B ........................................ 6.2 x 104 cfm HVE-2A/B and HVE-1A/B & HVE-15/15A ................... 7.2 x 104 cfm R-15. Air Eiector - Noble Gas Flow Rate = 3.10 x 102 cfm (for one vacuum pump running)
Flow Rate = 6.10 x 102 cfm (for two vacuum pumps running)
R-20, R-30, Fuel Building Basement Exhaust - Low and High Range Noble Gas Flow Rate = 1.0 x 104 cfm R-21, Fuel Buildinq UPPER Level Exhaust Flow Rate = 1.34 x 104 cfm R-31A, R-31B, R-31C - Steam-Line Monitors (at 800 psi)
PORV (100% lift) ........... 1.92E06 cc/sec (4.57E05 Ibm/hr)
PORV and 1 SRV .... ....... 4.00E06 cc/sec (9.51 E05 lbm/hr)
PORV and 2 SRV .... ....... 6.11 E06 cc/sec (1.45E06 lbm/hr)
PORV and 3 SRV .... ....... 9.19E06 cc/sec (2.19E06 Ibm/hr)
EPRAD-03 I Rev. 14 l Page 53 of 77
ATTACHMENT 10.8 Page 2 of 5 FLOW RATES R-31A, R-31B. R-31C - Steam-Line Monitors (Filled with Water)
PORV (100% lift) ............... 7.32E04 ml/sec PORV AND 1 SRV ............... 1.56EO5 mi/sec PORV AND 2 SRV ............... 2.42EO5 mi/sec PORV AND 3 SRV ............... 3.68EO5 ml/sec R-2. R-32A. R-32B - Containment Radiation Monitors Containment isolated with no discharge via plant vent ......... 1.5 CFM 1 Containment vented via plant vent ...................................... 2500 CFM 1 Design basis leakage for containment at 0.1 % containment volume per day.
EPRAD-03 I Rev. 14 l Page 54 of 77
ATTACHMENT 10.8 Page 3 of 5 FLOW RATES STEAM LINE FLOW RATE CALCULATION FOR A DRY STEAM GENERATOR 1.0
- 1. RCS Leak Rate (RCSLR) gpm
- 2. RCS Temperature OF
- 3. RCS Pressure psig
- 4. S/G Pressure psig
- 5. S/G Temp OF 2.0 1. From the Steam Tables determine the specific volume of RCS Fluid (RCSsv) at conditions in 1.0 ft3/lb
- 2. From the Steam Tables determine the specific volume of S/G Fluid (SGsv) at condition in 1.0 _ _ft /lb 3.0 Determine the RCS Mass Release Rate (RCSMRR) into S/G by using the following formula:
RCSLR (gal/min)
= Ib/min (7.48 gal/fl3 ) (RCSsv ft3Ilb)
( .. RCSLR gal/min)
_ _ lb/min (7.48 gal/fl3 j L( RCSsv ft3/lb) 4.0 Determine the steam flow rate using the following formula:
RCSMRR (lb/min) SGsv (ft3/lb) (472 cc/sec) = cc/sec ft /min
( )( (472 cc/secp RCSMRR (lb/min) SGsv (ft /Ib) ft /min cc/sec 5.0 Performed by:
Verified by:
I EPRAD-03 I Rev. 14 l Page 55 of 77
ATTACHMENT 10.8 Page 4 of 5 FLOW RATES CONVERSION OF STEAM MASS FLOW RATE TO VOLUMETRIC FLOW RATE(')
- 1. Obtain and record the steam mass flow rate in lbs/hr from the Accident Assessment Team.
lbs/hr [1]
- 2. Obtain and record the main steam pressure in psig.
psig
- 3. Use the figure on the following page to determine the specific volume (cc/lb) for the pressure determined in step 2.
cc/lb [2]
- 4. Determine the volumetric flow rate using the following formula:
(Ibs/hr) (1 hr/3600 sec) (cc/lb) = cc/sec
( Ib/hr) (1 hr/3600 sec) ( cc/lb) = cc/sec
[1] [2]
Performed by: /
Date Time Verified by: /
Date Time
' For use with R-31 readings under any conditions.
I EPRAD-03 I Rev. 14 l Page 56 of 77
C c ATTACHMENT 10.8 Page 5 of 5 FLOW RATES STEAM PRESSURE VS SPECIFIC VOLUME PSIG VS CC PER POUND PSIG 1200 1100 1000 w 900 D 800 0
w 700
- a. 600 2 500 w 400 Cn 300 200 100 0
0 25 50 75 100 125 150 175 200 225 250 SPECIFIC VOLUME - CC/LB (THOUSANDS)
IEPRAD-03 I Rev. 14 l Page 57 of 77
ATTACHMENT 10.9 Page 1 of 5 DETECTOR SENSITIVITIES Determine the appropriate accident scenario classification (1-10) utilizing the following table.
ACCIDENT l PLANT CONDITIONS l FILTRATION/PARTITIONING/SPRAYS SCENARIO . _ _ _ _ _ _ _ _ _ _
1 Core not uncovered Effective or Not Effective 2 Core uncovered <30 minutes Effective 3 Core uncovered <30 minutes Not Effective 4 Core uncovered 0.5 - 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Effective 5 Core uncovered 0.5 - 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Not Effective 6 Core uncovered > 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Effective 7 Core uncovered > 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Not Effective 8 New Spent Fuel Effective or Not Effective 9 Old Spent Fuel Effective or Not Effective 10 Waste Gas Decay Tank Effective or Not Effective Determine the sensitivity of the appropriate detector using the following tables and accident scenarios. (The sensitivities in Table 1 below are based on nuclide mixes at reactor shutdown).
Table 2 provides detector efficiencies(sensitivities) for eight (8)designated accident categories and time steps for each accident sequence.
Table 1 ACCIDENT PLANT VENT STEAM FILLEDMAIN STEAM WATER FILLED MAIN SCENARIO STACK(mRem/hr)/( LINE(mRem/hr)/( [tCi/cc) STEAM LINE(mRem/hr)/(
l zCi/cc) _Ci/mI) 1 3.28E+02 1.49E+01 4.51 E+00 2 1.42E+03 7.11 E+01 2.15E+01 3 2.63E+03 9.66E+01 2.35E+01 4 1.40E+03 7.08E+01 2.16E+01 5 1.98E+03 7.94E+01 2.09E+01 6 1.40E+03 7.08E+01 2.15E+01 7 2.20E+03 8.24E+01 2.06E+01 8 2.80E+03 N/A N/A 9 5.44E+00 N/A N/A 10 2.48E-01 N/A N/A l EPRAD-03 I Rev. 14 l Page 58 of 77
( ( (
ATTACHMENT 10.9 Page 2 of 5 DETECTOR SENSITIVITIES Table 2: Summary of Detector Sensitivities(Efficlencies) for Designated Accident Scenarios Accident ' R.14C IR14D R-14E - R-12 . R-20 R-21 [ R.15 - R-2 , R-30 : R-31A,BC - R-32A -R-32B Tlme step ,cpm per I cpm per cpm per cpm per; cpm per cpm pcpm pm per mR/hr per mR/hr per mRlhr per R/hr per R/hr per
,_____ _ --'uCilcc ' uCI/cc UCi/cc - uCi/cc uCicc , uJCilcc ui UCi/cc
,Ci/cc ,UCI/cc , uCVcc ' uCi/cc . uCIcc Accident 1 Normal RCS t=O 1.50E+07 3.94E+03 2.58E+00 3.03E+07 3.17E+07 3.25E+07 4.42E+05 9.2E+03 6.1 E+01 1.1 E+01 9.2E+00 9.2E+00 t=0.5 1.41 E+07 3.71 E+03 2.43E+00 2.76E+07 2.90E+07 2.97E+07 3.54E+05 6.9E+03 3.6E+01 6.3E+00 6.9E+00 6.9E+00 t=1 1.38E+07 3.63E+03 2.38E+00 2.68E+07 2.81 E+07 2.87E+07 3.23E+05 6.2E+03 2.9E+01 4.9E+00 6.2E+00 6.2E+00 t=2 1.36E+07 3.57E+03 2.34E+00 2.61 E+07 2.74E+07 2.80E+07 2.97E+05 5.4E+03 2.OE+01 3.4E+00 5.4E+00 5.4E+00 t=4 1.33E+07 3.50E+03 2.29E+00 2.54E+07 2.66E+07 2.73E+07 2.64E+05 5.OE+03 1.5E+01 2.5E+00 5.OE+00 5.0E+00 t=8 1.31 E+07 3.43E+03 2.25E+00 2.47E+07 2.59E+07 2.65E+07 2.20E+05 4.3E+03 8.4E+00 1.3E+00 4.3E+00 4.3E+00 t=16 1.29E+07 3.38E+03 2.21 E+00 2.41 E+07 2.53E+07 2.59E+07 1.73E+05 4.OE+03 4.5E+00 6.6E-01 4.OE+00 4.OE+00 t=32 1.29E+07 3.40E+03 2.23E+00 2.41 E+07 2.53E+07 2.59E+07 1.36E+05 3.8E+03 3.3E+00 5.OE-01 3.8E+00 3.8E+00 Accident 2 Core uncovered < 30 minutes/ mechanical damage with sprays/filtration effective t=O 3.26E+07 8.59E+03 5.62E+00 6.42E+07 6.74E+07 6.90E+07 3.41 E+06 4.2E+04 4.OE+02 7.2E+01 4.2E+01 4.2E+01 t=0.5 3.10E+07 8.16E+03 5.34E+00 5.33E+07 5.60E+07 5.73E+07 3.70E+06 3.3E+04 3.OE+02 5.4E+01 3.3E+01 3.3E+01 t=1 3.04E+07 8.00E+03 5.24E+00 4.84E+07 5.08E+07 5.20E+07 3.87E+06 2.8E+04 2.5E+02 4.4E+01 2.8E+01 2.8E+01 t=2 3.01E+07 7.91E+03 5.18E+00 4.44E+07 4.66E+07 4.77E+07 4.07E+06 2.4E+04 2.OE+02 3.6E+01 2.4E+01 2.4E+01 t=4 2.98E+07 7.85E+03 5.14E+00 4.02E+07 4.22E+07 4.32E+07 4.33E+06 1.9E+04 1.4E+02 2.5E+01 1.9E+01 1.9E+01 t=8 2.96E+07 7.78E+03 5.10E+00 3.53E+07 3.70E+07 3.79E+07- 4.63E+06 1.3E+04 8.0E+01 1.3E+01 1.3E+01 1.3E+01 t=16 2.94E+07 7.73E+03 5.06E+00 3.05E+07 3.20E+07 3.27E+07 4.90E+06l 9.OE+03 3.6E+01 4.7E+00 9.OE+00 9.0E+00 t=32 2.92E+07 7.69E+03 5.04E+00 2.67E+07 2.80E+07 2.87E+07 5.11 E+06 I 7.7E+03 2.OE+01 1.8E+00 7.7E+00 7.7E+00 Detector sensitivities derived from Calculation No. RNP-M/MECH 1746.
I EPRAD-03 I Rev. 14 1 Page 59 of 77
C C ATTACHMENT 10.9 Page 3 of 5 DETECTOR SENSITIVITIES Table 2: Summary of Detector Sensitivities(Efficiencies) for Designated Accident Scenarios 1R14C R-14D R.t4E , -R12 1 R-20 RAccident , R-21 R.15 R-2 R 30 l1:-31A,B,C, R-32A R-32B Time step. cpm perI cpm per cpm per: cpm per,, ,' cpm per.. cpm per cpm per, mR/hr per mR/hr per mR/hr per**,Rr per R/hr per
.'..___-.-- uCi/cc - uci/cc uci/cc . uCcc uCVcc'. uci/cc ucl/cc uClj c u ci/cc I .uCl/cc.:.... uCi/cc . uCi/cc Accident 3 Core uncovered < 30 minutes/ mechanical damage with sprays/filtration NOT effective t=O 1.55E+07 4.08E+03 2.67E+00 7.03E+07 7.38E+07 7.55E+07 1.62E+06 7.3E+04 7.4E+02 1.3E+02 7.3E+01 7.3E+01 t=0.5 1.34E+07 3.53E+03 2.31 E+O0 6.60E+07 6.93E+07 7.09E+07 1.60E+06 6.7E+04 6.8E+02 1.2E+02 6.7E+01 6.7E+01 t=1 1.30E+07 3.42E+03 2.24E+00 6.39E+07 6.71 E+07 6.86E+07 1.65E+06 6.2E+04 6.2E+02 1.1 E+02 6.2E+01 6.2E+01 t=2 1.32E+07 3.47E+03 2.27E+00 6.15E+07 6.45E+07 6.60E+07 1.79E+06 5.4E+04 5.3E+02 9.1 E+01 5.4E+01 5.4E+01 t=4 1.37E+07 3.59E+03 2.35E+00 5.82E+07 6.11 E+07 6.25E+07 1.98E+06 4.4E+04 4.2E+02 7.2E+01 4.4E+01 4.4E+01 t=8 1.42E+07 3.72E+03 2.44E+00 5.38E+07 5.65E+07 5.78E+07 2.21 E+06 3.4E+04 3.2E+02 5.4E+01 3.4E+01 3.4E+01 t=16 1.50E+07 3.95E+03 2.59E+00 4.81E+07 5.05E+07 5.17E+07 2.50E+06 2.5E+04 2.3E+02 3.8E+01 2.5E+01 2.5E+01 t=32 1.63E+07 4.28E+03 2.81 E+O0 4.1 OE+07 4.30E+07 4.40E+07 2.84E+06 1.9E+04 1.6E+02 2.5E+01 1.9E+01 1.9E+01 Accident 4 Core uncovered 0.5 < 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with sprays/filtration effective t=O 3.32E+07 8.74E+03 5.72E+o0 6.40E+07 6.71 E+07 6.87E+07 3.47E+06 4.2E+04 4.OE+02 7.2E+01 4.2E+01 4.2E+01 t=0.5 3.17E+07 8.34E+03 5.46E+00 5.28E+07 5.54E+07 5.67E+07 3.78E+06 3.3E+04 3.OE+02 5.4E+01 3.3E+01 3.3E+01 t=1 3.11E+07 8.1BE+03 5.35E+00 4.78E+07 5.01E+07 5.13E+07 3.96E+06 2.8E+04 2.5E+02 4.4E+01 2.8E+01 2.8E+01 t=2 3.07E+07 8.07E+03 5.29E+o0 4.37E+07 4.59E+07 4.70E+07 4.16E+06 2.4E+04 2.OE+02 3.6E+01 2.4E+01 2.4E+01 t=4 3.04E+07 7.99E+03 5.23E+00 3.95E+07 4.14E+07 4.24E+07 4.41 E+06 1.9E+04 1.4E+02 2.5E+01 1.9E+01 1.9E+01 t=8 3.01E+07 7.92E+03 5.18E+00 3.46E+07 3.63E+07 3.72E+07 4.71E+06 1.3E+04 8.0E+01 1.3E+01 1.3E+01 1.3E+01 t=16 2.98E+07 7.84E+03 5.14E+00 2.99E+07 3.13E+07 3.21E+07 4.97E+06 9.OE+03 3.6E+01 4.7E+00 9.OE+00 9.OE+00 t=32 2.96E+07 7.79E+03 5.10E+00 2.63E+07 2.76E+07 2.82E+07 5.17E+06 7.7E+03 2.OE+01 1.8E+00 7.7E+00 7.7E+00
_ ____ _ 1. __ _ _ _ _ I _ _ _ __ _ _ J __ _ __ _ _ L _ _ _ _ __ _ _ _ _ __ £ 1. _ _ _ _ _ _ 1 _ _ _ _ _ __ L 1. __ __ __
Detector sensitivities derived from Calculation No. RNP-M/MECH 1746, (EC 49849, Set-Point, Declaration Evaluation for EP) l EPRAD-03 I Rev. 14 l Page 60 of 77
( C C ATTACHMENT 10.9 Page 4 of 5 DETECTOR SENSITIVITIES Table 2: Summary of Detector Sensitivities(Efficiencies) for Designated Accident Scenarios Accident R-14C R-14D R-14E R-12 R-20 R-21 R-15 R-2 R-30 - R-31A,B,C R-32A R-32B Time step cpmcpm cpm per p: per. cpm per . cpm p per mR/hr per mR/hr per mR/hr per : R/hr per R/hr per ucvc -juCi/cc uCIcc: uC/cc . uC/cc :. uCI/cc uCi/cc uCI/cc uCi/cc uCicc uCI/cc uCI/c Accident S Core uncovered 0.5 < 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with sprays/filtration NOT effective t=O 2.26E+07 5.94E+03 3.89E+00 6.67E+07 7.00E+07 7.16E+07 2.36E+06 5.9E+04 5.9E+02 1.OE+02 5.9E+01 5.9E+01 t=0.5 2.03E+07 5.33E+03 3.49E+00 5.97E+07 6.26E+07 6.41 E+07 2.42E+06 5.3E+04 5.2E+02 9.0E+01 5.3E+01 5.3E+01 t=2 1.97E+07 5.1 8E+03 3.39E+00 5.642E+07 5.92E+07 6.06E+07 2.51 E+06 4.8E+04 4.7E+02 8.1E+01 4.8E+01 4.8E+01 t=2 1.972+07 5.192+03 3.40E+00 5.322+07 5.58E+07 5.712E+07 2.67E+06 4.1E.04 4.02+02 6.82.01 4.124+01 4.1E+01 t=4 2.OOE+07 5.26E+03 3.44E+00 4.93E+07 5.18E+07 5.30E+07 2.90E+06 3.3E+04 3.0E+02 5.2E+01 3.3E+01 3.3E+01 t=8 2.03E+07 5.34E+03 3.50E+00 4.45E+07 4.67E+07 4.78E+07 3.18E+06 2.4E+04 2.1 E+02 3.5E+01 2.4E+01 2.4E+01 t=16 2.09E+07 5.49E+03 3.60E+00 3.90E+07 4.09E+07 4.19E+07 3.48E+06 1.8E+04 1.4E+02 2.2E+01 1.8E+01 1.8E+01 t=32 2.182+07 5.72E+03 3.75E+00 3.32E+07 3.49E+07 3.57E+07 3.80E+06 1.3E+04 8.9E+01 1.4E+01 1.3E+01 1.3E+01 Accident 6 Core uncovered > 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with sprays/filtration effective t=O 3.29E+07 8.64E+03 5.66E+00 6.38E+07 6.70E+07 6.85E+07 3.43E+06 4.2E+04 4.0E+02 7.2E+01 4.2E+01 4.2E+01 t=0.5 3.13E+07 8.22E+03 5.38E+00 5.28E+07 5.54E+07 5.66E+07 3.73E+06 3.3E+04 3.0E+02 5.4E+01 3.3E+01 3.3E+01 t=1 3.06E+07 8.06E+03 5.27E+00 4.78E+07 5.01E+07 5.13E+07 3.90E+06 2.8E+04 2.5E+02 4.4E+01 2.8E+01 2.8E+01 t=2 3.02E+07 7.95E+03 5.21 E+00 4.37E+07 4.59E+07 4.70E+07 4.10E+06 2.4E+04 2.0E+02 3.6E+01 2.4E+01 2.4E+01 t=4 2.99E+07 7.88E+03 5.16E+00 3.95E+07 4.15E+07 4.24E+07 4.35E+06 1.9E+04 1.4E+02 2.5E+01 1.9E+01 1.9E+01 t=8 2.97E+07 7.80E+03 5.11 E+00 3.46E+07 3.64E+07 3.72E+07l 4.64E+06 1.3E+04 8.0E+01 1.3E+01 1.3E+01 1.3E+01 t=16 2.94E+07 7.73E+03 5.06E+00 2.99E+07 3.14E+07 3.21E+07 4.90E+06 9.0E+03 3.6E+01 4.7E+00 9.0E+00 9.0E+00 t=32 2.92E+07 7.68E+03 5.03E+00 2.62E+07 2.75E+07 2.82E+07 5.10E+06 7.7E+03 2.0E+01 1.8E+00 7.7E+00 7.7E+00 Detector sensitivities derived from Calculation No. RNP-M/MECH 1746, (EC 49849, Set-Point, Declaration Evaluation for EP).
l EPRAD-03 I Rev. 14 1 . Page61 of 77
( C ATTACHMENT 10.9 Page 5 of 5 DETECTOR SENSITIVITIES Table 2: Summary of Detector Sensitivities(Efficiencies) for Designated Accident Scenarios Accident -14CR-14D 1 R-14E- R-12 .R-20 -- R-21 , R-15 R-2 , R-30 R-31A,B,C R-32A R-32B Time step l : 'cprnmpetr'l>, cpm per cpm per cpm per cpm per. cpm per cpm per mR/hr per mR/hr per mR/hr per R/hr per R/hr per
'uC/cc ' l : uCi/cc', uCl/cc uCi/cc - uClcc ' uCVcc, uCVcc uCI/c uCi/cc Accident 7 Core uncovered > 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with sprays/filtration NOT effective t=O 1.75E+07 4.60E+03 3.01E+00 6.32E+07 6.63E+07 6.78E+07 1.83E+06 6.6E+04 6.6E+02 1.1E+02 6.6E+01 6.6E+01 t=0.5 1.51 E+07 3.98E+03 2.60E+00 5.70E+07 5.98E+07 6.12E+07 1.80E+06 6.0E+04 5.6E+02 1.OE+02 6.0E+01 6.0E+01 t=1 1.45E+07 3.82E+03 2.50E+00 5.40E+07 5.67E+07 5.80E+07 1.85E+06 5.5E+04 5.1 E+02 9.4E+01 5.5E+01 5.5E+01 t=2 1.45E+07 3.81 E+03 2.49E+00 5.09E+07 5.34E+07 5.46E+07 1.96E+06 4.8E+04 4.7E+02 8.OE+01 4.8E+01 4.8E+01 t=4 1.46E+07 3.84E+03 2.51 E+00 4.70E+07 4.93E+07 5.04E+07 2.12E+06 3.8E+04 3.7E+02 6.3E+01 3.8E+01 3.8E+01 t=8 1.47E+07 3.88E+03 2.54E+00 4.22E+07 4.43E+07 4.53E+07 2.31 E+06 2.9E+04 2.6E+02 4.5E+01 2.9E+01 2.9E+01 t=16 1.51 E+07 3.98E+03 2.61 E+00 3.67E+07 3.85E+07 3.94E+07 2.53E+06 2.1 E+04 1.7E+02 3.OE+01 2.1 E+01 2.1 E+01 t=32 1.59E+07 4.17E+03 2.73E+00 3.08E+07 3.23E+07 3.30E+07 2.77E+06 1.6E+04 1.2E+02 1.9E+01 1.6E+01 1.6E+01 Accident 8 Spent Fuel Assembly (Gap) t=O 3.26E+07 8.59E+03 5.62E+00 6.42E+07 6.74E+07 6.90E+07 N/A 4.2E+04 4.0E+02 N/A 4.2E+01 4.2E+01 t=0.5 3.10E+07 8.16E+03 5.35E+00 5.33E+07 5.60E+07 5.73E+07 N/A 3.3E+04 3.OE+02 N/A 3.3E+01 3.3E+01 t=1 3.04E+07 8.OOE+03 5.24E+00 4.84E+07 5.08E+07 5.20E+07 N/A 2.8E+04 2.5E+02 N/A 2.8E+01 2.8E+01 t=2 3.01 E+07 7.91 E+03 5.1 8E+00 4.44E+07 4.66E+07 4.77E+07 N/A 2.4E+04 2.0E+02 N/A 2.4E+01 2.4E+01 t=4 2.98E+07 7.85E+03 5.14E+00 4.02E+07 4.22E+07 4.32E+07 N/A 1.9E+04 1.4E+02 N/A 1.9E+01 1.9E+01 t=8 2.96E+07 7.78E+03 5.1 OE+00 3.53E+07 3.70E+07 3.79E+07 N/A 1.3E+04 8.0E+01 N/A 1.3E+01 1.3E+01 t=16 2.94E+07 7.73E+03 5.06E+00 3.05E+07 3.20E+07 3.27E+07 N/A 9.0E+03 3.6E+01 N/A 9.01+00 9.02+00 t=32 2.92E+07 7.69E+03 5.04E+00 2.67E+07 2.80E+07 2.87E+07 N/A 7.7E+03 2.0E+01 N/A 7.72+00 7.7E+00 Detector sensitivities derived from Calculation No. RNP-M/MECH 1746, (EC 49849, Set-Point, Declaration Evaluation for EP) l EPRAD-03 Rev. 14 Page 62 of 77
ATTACHMENT 10.10 Page 1 of 1 MEASURING RADIATION LEVEL ON MAIN STEAM LINES Steel Support Wall 5'8" - *-
K-To Turbine 11' 4" Platform Grating Reference l EPRAD-03 I Rev. 14 l Page 63 of 77
ATTACHMENT 10.11 Page 1 of 2 TYPICAL RMS VALUES The background and alarm setpoint for radiation monitors should be obtained from the control room or other current sources if they are needed to perform dose projections. The following two tables provide the typical values for the background and alarm setpoints for radiation monitors, however these values should not be used for performing dose projections unless no other data is available. Table I contains all of the radiation monitors that are used for dose projections, while Table 2 contains other monitors that may be of interest to the dose projection team.
TABLE 1:
RADIATION CHANNEL DESCRIPTION l TYPICAL: SCALE MONITOR BKG/SETPOINT R2 CV LOW RANGE AREA - 10 / 100 mR/HR 0.1 - 10,000 mR/HR R12 CVAIR GAS - 1 K/2.2 K CPM 10-10,000,OOOCPM
= 1.8 times BKG R14C PLANT VENT GAS LOW 30-60/-10,000 CPM 10 - 1,000,000 CPM Default 1 M In high range. switch to high range or 10 M at monitor
- 700 k CPM all R-14 channels R14D PLANT VENT GAS MID 10-11 / 130 CPM 10- 1,000,000 CPM Default 10 In low range R14E PLANT VENT GAS HIGH 10-11 / BKG + 17 CPM 10- 1,000,000 CPM Default 10 In low range R15 CONDENSER AIR EJECTOR 10-15 /100+BKG CPM 10 - 1,000,000 CPM R20 LOWER FUEL HANDLING 10-40 /9,800 CPM 10-10,000,000 CPM BUILDING low range R21 UPPER FUEL HANDUNG 10-25 / 9,730 CPM 10-10,000,000 CPM FUEL HANDLING R30 LOWER FUEL HANDLING - 0.5/ 18+BKG mR/HR 1 - 100,000 mR/HR BUILDING high range R31A MAIN STEAM LINE A - 0.3 /12 mR/HR 1 - 100,000 mR/HR R31 B MAIN STEAM LINE B - 0.4 / 12 mR/HR 1 - 100,000 mR/HR R31C MAIN STEAM LINE C - 0.6/12 mR/HR 1 - 100,000 mR/HR R32A CV HIGH RANGE <1/ 10&1,000 R/HR 1-10,000,000 R/HR R32B CV HIGH RANGE <1/ 10&1,000 R/HR 1-10,000,000 R/HR
- A printscreen can be performed on either the EDS terminal or ERFIS at the onset of an accident to provide more current backgrounds for monitors that are not yet being effected by the accident.
I EPRAD-03 I Rev. 14 l Page 64 of 77
ATTACHMENT 10.11 Page 2 of 2 TYPICAL RMS VALUES TABLE 2:
RADIATION CHANNEL DESCRIPTION TYPICAL BKG/SETPOINT SCALE MONITOR R1 CONTROL ROOM AREA <1 / 2.5 mR/HR 0.1 - 10,000 mR/HR R3 PASS PANEL AREA 0.1-0.3/ 20 mR/HR 0.1 - 10,000 mR/HR R4 CHARGING PUMP AREA -4 /50 mR/HR 0.1 - 10,000 mR/HR R5 SPENT FUEL BLDG. AREA <1 /50 mR/HR 0.1 - 10,000 mR/HR R6 SAMPLiNG ROOM AREA <1 /50 mR/HR 0.1 - 10,000 mR/HR R7 IN-CORE INSTRUMENT AREA -4 / 200 mR/HR 0.1 - 10,000 mR/HR R8 DRUMMING ROOM 1-2 /50 mR/HR 0.1 - 10,000 mR/HR R9 LETDOWN LINE AREA 10-40/ 3000 mR/HR 1 - 100,000 mR/HR Ri1 CV AIR PARTICULATE -20 K / 3.6E4 CPM 10 - 1,000,000 CPM
= 1.8 times BKG R14A PLANT VENT PARTICULATE -500 / 2E6 CPM 10 - 1,000,000 CPM R14B PLANT VENT IODINE -10/90,000 CPM 10 - 1,000,000 CPM R16 HVH COOLiNG WATER -300 / 1,900 CPM 10 - 1,000,000 CPM R17 COMPONENT COOLiNG WATER -300 /830 CPM 10 - 1,000,000 CPM R18 LIQUID WASTE DISPOSAL -18,500/VARIES 10 - 1,000,000 CPM R19A SG "A" BLOWDOWN <2,000/ -10 K CPM 10 -10,000,000 CPM
-R19B SG "B" BLOWDOWN <1,000/ -8 K CPM 10 -10,000,000 CPM R19C SG "C" BLOWDOWN <2,000/ -10 K CPM 10 -10,000,000 CPM R22P E&RC BLDG. PARTICULATE -300 / 10,000 CPM 1 - 1,000,000 CPM R221 E&RC BUILDING IODINE -15 /300 CPM 1 - 1,000,000 CPM R22NG E&RC BUILDING NG -40 / 1,000 CPM 1 - 1,000,000 CPM R23P RADWASTE BLDG. PART. -60 / 9,700 CPM 1 - 1,000,000 CPM R231 RADWASTE BLDG. IODINE <10 / 1090 CPM 1 - 1,000,000 CPM R24A N-16 MAIN STEAM UNE A 1/5 GPD 1 - 150 GPD R24B N-16 MAIN STEAM LINE B 1/5 GPD 1 - 150 GPD R24C N-16 MAIN STEAM LINE C 1/5 GPD 1 - 150 GPD R23NG RADWASTE BLDG. NG -20 /387 CPM 1 - 1,000,000 CPM R33 MONITOR BLDG. AREA <1 / 10 mR/HR I - 100,000 mR/HR R37 COND. POLISHER -100 /18,500 CPM 10 -10,000,000 CPM R38P EOF PARTICULATE -900 / 32,000 CPM 10 - 1,000,000 CPM R381 EOF IODINE -10 / 802 CPM 10 - 1,000,000 CPM R38NG EOF NOBLE GAS -25 / 935 CPM 10 - 1,000,000 CPM I EPRAD-03 I Rev. 14 l Page 65 of 77
( c c ATTACHMENT 10.12 Page 1 of 1 RMS MONITORED SYSTEMS 1 {m
%y imm rwl lA
'u 'Wr' I ct A , ATMtOS tax Wm3D oto W VA IV ox YIK mm 444 all Rtu L _j mI -
Ad_ 1t w waz Reference - System Description, SD-O19, Radiation Monitoring System I EPRAD-03 I Rev. 14 l Page 66 of 77 l
ATTACHMENT 10.13 Page 1 of 1 WEATHER SERVICE DATA
- 1. Call the Weather Service at the Florence Airport, Columbia, South Carolina or Wilmington, North Carolina. Ask for the forecaster on duty and identify yourself.
The following script may be used, 'This is (your name) at the Progress Energy H. B. Robinson Nuclear Plant. This is an emergency (or emergency drill). May I have the last hour surface weather observation from Florence, South Carolina?"
Ifthe last hour data is not available from Florence, then request the last hour surface weather observation from Columbia. The following data should be obtained:
1-Hour Forecast
- Station for which data is given
- Wind Speed (MPH)
- Cloud Cover (intenths of total)
- Cloud Ceiling (feet above ground)
- Wind Direction (from N,S,E,W,etc.)
- Wind Direction Trends (steady, shifting, variable)
- Precipitation Activity
- Probability of Precipitation
- 2. Also, obtain a 3-hour forecast for Florence from the meteorologist on duty.
3-Hour Forecast
- Station for which data is given
- Wind Speed (MPH)
- Cloud Cover (in tenths of total)
- Cloud Ceiling (feet above ground)
- Wind Direction (from N,S,E,W,etc.)
- Wind Direction Trends (steady, shifting, variable)
- Precipitation Activity
- Probability of Precipitation
- 3. Other Information:
Date: Time: Name:_
I EPRAD-03 I Rev. 14 l Page 67 of 77
ATTACHMENT 10.14 Page 1 of 1 ONSITE METEOROLOGICAL DATA Date:
Time Ground Wind Speed (mph)
Elevated Wind Speed (mph)
Ground Wind Dir. (From)
Elevated Wind Dir. (From)
AMB Temp. (OF)
AT (OC/1 00m)
Stability Class Time Ground Wind Speed (mph)
Elevated Wind Speed (mph)
Ground Wind Dir. (From)
Elevated Wind Dir. (From)
AMB Temp. (OF)
AT (0C/1 00m)
Stability Class EPRAD-03 I Rev. 14 l Page 68of77
ATTACHMENT 10.15 Page 1 of 1 METEOROLOGICAL FORECAST FORM Date: Time Issued:_
Issued By: Received By:_
Forecast Location:
A) Next 1 Hour
- 1) Wind Direction: Sector_ Deg.
- 2) Winds Should Remain (Steady; Shifting; 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, Thunderstorms, Ice, Snow)
- 7) Precipitation Intensity (Light, Moderate, Severe)
B) Next 3 Hours:
C) Next 3 Days:
D) Remarks:
I EPRAD-03 I Rev. 14 l Page 69 of 77
( (
ATTACHMENT 10.16 Page 1 of 2 HBRDOSE/RASCAL COMPARISON MATRIX I HBRDOSE l RASCAL DIFFERENCES/COMMENTS j EFFECTS EPA 400 Dose Yes Partial See Note 1 HBRDOSE will give higher ground exposure factors doses. Rascal will give higher external doses.
TEDE may be affected in either direction.
Reg Guide 1.145 Yes No RASCAL uses a single equation with non site- RASCAL generally will use higher X/Q values, XIQs specific wake factors. Also, probably doesn't especially for ground level releases at closer use plume meander default. RASCAL cap on distances. When using default cap on Sigma z, Sigma z is 500 m. R.G. 1.145 shows 3000 m. Rascal will calculate higher doses during unstable met conditions.
Deposition No Yes RASCAL calculates deposition as a separate NONE dose quantity; which does not affect TEDE.
Depletion No No NONE Wet Deposition No Yes RASCAL uses a mass balance for wet RASCAL immersion and inhalation doses will be deposition. lower than HBRDOSE. RASCAL ground doses l_ will be higher.
Finite Model Yes Yes RASCAL converts to a semi-infinite model at Conversion point of finite model, semi-infinite Sigma y = 400 m. HBRDOSE uses Sigma y = model will cause negligible difference. RASCAL 500 m. RASCAL uses horizontal dispersion use of Sigma y instead of an average sigma as coefficient only in determining plume size. described in "Meteorology and Atomic Energy' HBRDOSE uses average Sigma. may cause a big difference in the calculated gamma dose for non-isotropic plumes.
Decay for TAS Yes Yes NONE Downwind Decay No No NONE I EPRAD-03 l Rev. 14 l Page 70 of 77
( ( c ATTACHMENT 10.16 Page 2 of 2 HBRDOSE/RASCAL COMPARISON MATRIX HBRDOSE RASCAL DIFFERENCES/COMMENTS EFFECTS Daughter No Yes RASCAL calculates ingrowth of daughter HBRDOSE may underestimate doses, particularly lngrowth decay products. inhalation doses.
Source RTM-96 NUREG- Different isotopes, RASCAL can dynamically During LOCA sequences, Spent Fuel accidents, or Term 1228 calculate spectrum based on particular Waste Gas Decay Tank rupture, there should be accident sequence. little difference. Other sequences may cause large differences.
Uses Yes Yes RASCAL calculates source term based on NRC predicted dose may be higher. PGN should monitor user defined parameters and the maximum consider a method of providing gross noble gas, reading for expected readings for core-damage states. iodine, and particulate release rates to the NRC.
source term NRC will probably be doing worst case THE EQUIVALENT RELEASE RATES VALUES analysis based on specific accident and PRA CALCULATED BY HBRDOSE SHOULD NOT BE l instead of actual release. REPORTED TO THE NRC.
Source term Yes Yes HBRDOSE uses gross (cpm or mRem/hr) NRC results will not be available for several hours, based on inputs. RASCAL requires isotopic analysis. but may be more accurate.
EMT samples l Intermediate Yes Yes The FMDose module in RASCAL 3.01 NONE Phase computes doses, derived intervention levels Calculations (DILs), and emergency worker turn-back guidance for identified measurement locations.
Note 1: Dose factors for thyroid are identical between the two models. For external dose, RASCAL includes the contribution of short lived daughters in the external dose factors, which EPA-400 does not do. Similarly, RASCAL Includes short lived daughter products in the inhalation and ground exposure dose factors. The most obvious result of this is that some of the noble gases (i.e. Kr-88), are included in inhalation and ground exposure dose in RASCAL. Ground exposure dose factors are calculated in RASCAL assuming a 0.3 cm/s deposition rate and further correction factor of 0.5 to account for rough ground. EPA-400 dose factors assume a deposition velocity of 1 cm/s for iodines and 0.1 cm/s for particulates with no correction factor.
EPRAD-03 Rev. 14 l Page 71 of 77
ATTACHMENT 10.17 Page 1 of 1 MANUAL CALCULATION OF CURIES RELEASED (FOR DOSE PROJECTION TEAM USE)
Use this manual calculation for stability classes E, F, and G in MIXED MODE RELEASES when X/Q is extremely small at the site boundary when compared with the other X/Q values.
The Xenon Dose Equivalent and the Iodine Dose Equivalent are the source term values used by South Carolina Department of Health and Environmental Control for input into their dose assessment program.
Use the following formula, and the data from the most reasonable distance, to calculate Q in Curies.
Q= [3600(D)] / [(1 000)(X/Q)(DCF)]
where:
o = the calculated Dose Equivalent source term in Curies, 3600 converts the release from Ci/sec to Curies 1000 = millirem - rem conversion D = EDE (immersion) or thyroid CDE in mRem, both from the dose projection program printout, XVQ = the dispersion factor (from the same distance as the dose, D),
DCF = the dose conversion factor (Rem per uCi - cm3 - hr); 20 for Xenon-1 33 dose equivalent or 1.3 E +06 for lodine-131 dose equivalent.
Q= [3600(D)] / [(1 000) (X/Q)(DCF)]
Q = [3.6(D)] / [(X/Q)(DCF)]
Q(Xe) = [3.6( )]/i ( ) (20)] = Curies Xe-1 33 Dose Equivalent Q(l) = [3.6( )]/ [( ) (1.3E+06)] = Curies Iodine Dose Equivalent TV~I EPRAD-03 I Rev. 14 I Page 72 of 77
C C' ATTACHMENT 10.18 Page 1 of 5 Manual Dose Projection Worksheet 1 2 3 4 5 6 7 8 Stability Wind Wind Site Boundary 0 DCF Dose Location Class* Direction Speed X/Q (Ci) Re/e (Rem) (ml)
(Wind from) (enter units) (sec/rn) Cl/rnou ns4x
_ _ __ _ __ __ _ _ _ _ _ _ _ _ F ro m Ta b le 1 C~ m s x x NG: TEDE: TEDE:
IODINE: THYROID: THYROID:SI 9
Cornments: Extrap.
Factors TEDE: 2 mi THYROID:
_ __ __ _ __ _ __ ___ __ _ _ _ _ _ _ _ _ _T EDE: 5 mi THYROID:
TEDE: l0 mi THYROID:
Projection Date: Projection Time:
Performed by: Reviewed by:
Approved by:.
- - For Stability Class F or G, use Stability Class F.
IEPRAD-03I Rev. 14 Page 73 of 77
C C ATTACHMENT 10.18 Page 2 of 5 Manual Dose Projection Worksheet Table 1: Site Boundary X/Q Part 1: Site Boundary X/Q (sec/m 3) - T - -- 1I Windspeed A B C D E F MPH W/s 1 0.4 8.39E-05 2.35E-04 5.40E-04 1.40E-03 2.70E-03 6.42E-03 2 0.9 4.19E-05 1.18E-04 2.70E-04 7.OOE-04 1.35E-03 3.21 E-03 3 1.3 2.80E-05 7.85E-05 1.80E-04 4.66E-04 9.00E-04 2.14E-03 4 1.8 2.10E-05 5.88E-05 1.35E-04 3.50E-04 6.75E-04 1.61 E-03 5 2.2 1.68E-05 4.71 E-05 1.08E-04 2.80E-04 5.40E-04 1.28E-03 6 2.7 1.40E-05 3.92E-05 9.00E-05 2.33E-04 4.50E-04 1.07E-03 7 3.1 1.20E-05 3.36E-05 7.71 E-05 2.00E-04 3.86E-04 9.18E-04 8 3.6 1.05E-05 2.94E-05 6.75E-05 1.75E-04 3.37E-04 8.03E-04 9 4.0 9.32E-06 2.62E-05 6.OOE-05 1.55E-04 3.00E-04 7.14E-04 10 4.5 8.39E-06 2.35E-05 5.40E-05 1.40E-04 2.70E-04 6.42E-04 11 4.9 7.63E-06 2.14E-05 4.91 E-05 1.27E-04 2.45E-04 5.84E-04 12 5.4 6.99E-06 1.96E-05 4.50E-05 1.17E-04 2.25E-04 5.35E-04 13 5.8 6.45E-06 1.81 E-05 4.15E-05 1.08E-04 2.08E-04 4.94E-04 14 6.3 5.99E-06 1.68E-05 3.86E-05 1.OOE-04 1.93E-04 4.59E-04 15 6.7 5.59E-06 1.57E-05 3.60E-05 9.33E-05 1.80E-04 4.28E-04 16 7.2 5.24E-06 1.47E-05 3.38E-05 8.75E-05 1.69E-04 4.02E-04 17 7.6 4.94E-06 1.38E-06 3.18E-05 8.23E-05 1.59E-04 3.78E-04 18 8.0 4.66E-06 1.31 E-05 3.00E-05 7.77E-05 1.50E-04 3.57E-04 19 8.5 4.42E-06 1.24E-05 2.84E-05 7.37E-05 1.42E-04 3.38E-04 20 8.9 4.19E-06 1.18E-05 2.70E-05 7.00E-05 1.35E-04 3.21E-04 21 9.4 4.00E-06 1.12E-05 2.57E-05 6.66E-05 1.29E-04 3.06E-04 22 9.8 3.81 E-06 1.07E-05 2.45E-05 6.36E-05 1.23E-04 2.92E-04 23 10.3 3.65E-06 1.02E-05 2.35E-05 6.08E-05 1.17E-04 2.79E-04 24 10.7 3.50E-06 9.81 E-06 2.25E-05 5.83E-05 1.12E-04 2.68E-04 25 11.2 3.36E-06 9.41 E-06 2.16E-05 5.60E-05 1.08E-04 2.57E-04 26 11.6 3.23E-06 9.05E-06 2.08E-05 5.38E-05 1.04E-04 2.47E-04 27 12.1 3.11 E-06 8.72E-06 2.00E-05 5.18E-05 1.OOE-04 2.38E-04 28 12.5 3.OOE-06 8.41 E-06 1.93E-05 5.00E-05 9.64E-05 2.29E-04 29 13.0 2.89E-06 8.12E-06 1.86E-05 4.83E-05 9.31 E-05 2.22E-04 30 13.4 2.80E-06 7.85E-06 1.80E-05 4.66E-05 2.14E-04 5.35E-04 I EPRAD-03 I Rev. 14 l Page 74 of 77
( C ATTACHMENT 10.18 Page 3 of 5 Manual Dose Projection Worksheet Table 1: Site Boundary X/Q Part 2: Extrapolation Factors MILES I A B C D E F 1 2.67E-02 6.84E-02 8.68E-02 1.08E-01 1.12E-01 1.08E-01 2 1.43E-02 1.72E-02 2.47E-02 3.70E-02 3.99E-02 3.95E-02 3 9.89E-03 7.65E-03 1.18E-02 2.01 E-02 2.25E-02 2.27E-02 4 7.63E-03 4.30E-03 7.02E-03 1.31 E-02 1.51 E-02 1.55E-02 5 6.23E-03 2.95E-03 4.68E-03 9.40E-03 1.11 E-02 1.16E-02 6 5.29E-03 2.50E-03 3.36E-03 7.19E-03 8.70E-03 9.20E-03 7 4.60E-03 2.17E-03 2.54E-03 5.73E-03 7.08E-03 7.57E-03 8 4.08E-03 1.93E-03 2.OOE-03 4.71 E-03 5.93E-03 6.40E-03 9 3.67E-03 1.73E-03 1.61 E-03 3.97E-03 5.07E-03 5.52E-03 10 3.33E-03 1.58E-03 1.33E-03 3.40E-03 4.41 E-03 4.84E-03 l EPRAD-03 l Rev. 14 l Page 75 of 77
C ( C ATTACHMENT 10.18 Page 4 of 5 Manual Dose Projection Worksheet Table 2: Dose Conversion Worksheet (Known Mix)
Sample Time: Release Time: _ Difference (t) _ _ (hr) 1 2 3 4 5 6 7 8 Nuclide Sample Release Fraction of Nuclide Dose Adjusted DCF Concentration X (hr 1) e Concentration Mix Conversion Factor Kr-85M 0.158 2.35E-02 Kr-85 7.4E-06 3.11 E-04 Kr-87 0.878 1.33E-01 Kr-88 0.248 _3.42E-01 Kr-89 13.075 3.OOE+01 Xe-131 M 0.002 1.24E-03 Xe-133M 0.013 4.28E-03 Xe-133 0.005 4.94E-03 Xe-135M 2.665 6.33E-02 Xe-1 35 0.076 3.58E-02 Xe-1 37 10.662 2.83E-02 Xe-138 2.376 1.86E-01 (NG) SUM = TOTAL (NG) DCF=
1 2 3 4 5 6 7 8 Nuclide Sample Release Fraction of Nuclide Dose Adjusted DCF Concentration X (hr 1) e Concentration Mix Conversion Factor 1-130 5.64E-02 108 1-131 3.59E-03 951 1-132 3.07E-01 11 1-133 3.41 E-02 226 1-134 7.97E-01 3 1-135 1.04E-01 46 (I) SUM = TOTAL (I) DCF =
EPRAD-03 Rev. 14 l Page 76 of 77
C ( N ATTACHMENT 10.18 Page 5 of 5 Manual Dose Projection Worksheet Table 3: Dose Conversion Factors for Unknown Mix (Rem/sec) / (Ci/M 3)
Reactor Shutdown Time: Release Time: Difference: hrs Time from TEDE DCFs THYROID DCFs Reactor Shutdown to Release
( h rs)_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
0 1.16E-01 171 0.5 9.89E-02 189 1 9.03E-02 215 2 7.86E-02 244 5 5.50E-02 318 8 3.94E-02 363 12 2.64E-02 415 24 1.36E-02 522 72 5.28E-03 800 I EPRAD-03 I Rev. 14 l Page 77 of 77
PATCH T C2 Progress Energy lInformation H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 2 PART 5 EPTSC-OO ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER REVISION 4 I EPTSC-00 I Rev.4 l Page 1 of 12
SUMMARY
OF CHANGES PRR 102622 & 93201 SECTION REVISION COMMENTS All Incorporated EPTSC-09 (EPTSC-09 deleted)
Cover Changed use to Information 8.2.2 Clarified the wording for TSC activations and incorporated actions upon arrival from other step.
8.2.3 Changed AND to OR -
8.2.7 Changed Supervisors to Directors 8.2.14 Changed ueffected" to "affected""
8.3.1 Clarified wording on setting-up a relief schedule 8.4 Added NOTE to ensure all events have been reviewed and deactivation is possible.
Aft 10.1 Moved Quick Start Guide to an Attachment & removed step to call Dialogic.
EPTSC-00 I Rev. 4 l Page 2 of 12 l
TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE .............................. 4
2.0 REFERENCES
.............................. 4 3.0 RESPONSIBILITIES ............................. 5 4.0 PREREQUISITES ............................. 5 5.0 PRECAUTIONS AND LIMITATIONS ............................. 5 6.0 SPECIAL TOOLS AND EQUIPMENT ............................. 5 7.0 ACCEPTANCE CRITERIA .............................. 5 8.0 INSTRUCTIONS ............................. 6 8.1 Support Procedures .............................. 6 8.2 Activation ... 6.......................
8.3 Turnover .............................. 9 8.4 Deactivation ... 9.......................
9.0 RECORDS .10 10.0 ATTACHMENTS .. 10 10.1 TECHNICALSUPPORTCENTER (TSC) ORGANIZATION .11 10.2 TECHNICAL SUPPORT CENTER (TSC) COMMAND ROOM RECOMMENDED LAYOUT .12 EPTSC-00 I Rev. 4 l Page 3of2
1.0 PURPOSE This procedure provides instructions for activation, operation and deactivation of the Technical Support Center (TSC).
2.0 REFERENCES
2.1 PLP-007, Robinson Emergency Plan 2.2 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2.3 Code of Federal Regulations, 10CFR50, Appendix E 2.4 EPA 400-R92-001, Manual for Protective Action Guides and Protective Actions for Nuclear Incidents 2.5 CR 9200167 2.6 Westinghouse Owners Group Document, Core Damage Assessment Methodology, November 1984, Revision 2.0.
2.7 H. B. Robinson Steam Electric Plant Unit 2, Updated Final Safety Analysis Report, Amendment 4.0, July 1986.
2.8 Babcock and Wilcox Radiochemistry for Accident Assessment, Babcock and Wilcox, April 1983.
2.9 Grove Engineering Inc. Microshield, Gamma Radiation Shielding, Version 2.0.
2.10 H. B. Robinson Steam Electric Plant, SRO - Advanced Transient and Accident Analysis, Attachment 7, 8,10, and 11.
2.11 H. B. Robinson Steam Electric Plant, Origen II Source Term Computer Run.
2.12 U. S. NRC, NUREG 0956, Reassessment of the Technical Basis for Estimating Source Term, July 1986.
EPTSC-00 I Rev. 4 l Page4of 12
2.13 CRC Applied Engineering Tables, 2nd Ed., Page 46, Properties of Gases.
2.14 Inadequate Core Cooling Monitor, H. B. Robinson, Unit 2, System Description.
2.15 Siemens Report, "H. B. Robinson Unit 2 Radiological Assessment of Postulated Accidents".
2.16 H. B. Robinson Station Blackout Coping Analysis Report.
3.0 RESPONSIBILITIES See individual support procedures.
4.0 PREREQUISITES The ERO Facilities have been activated.
5.0 PRECAUTIONS AND LIMITATIONS N/A 6.0 SPECIAL TOOLS AND EQUIPMENT See individual support procedures.
7.0 ACCEPTANCE CRITERIA N/A EPTSC-00 I Rev. 4 l Page 5 of 12l
8.0 INSTRUCTIONS 8.1 Support Procedures 8.1.1 EPTSC-01, Site Emergency Coordinator 8.1.2 EPTSC-02, Plant Operations Director 8.1.3 EPTSC-03, Emergency Repair Director 8.1.4 EPTSC-04, Radiological Control Director 8.1.5 EPTSC-05, deleted 8.1.6 EPTSC-06, Emergency Security Team Leader 8.1.7 EPTSC-07, Damage Assessment 8.1.8 EPTSC-08, Technical Analysis Director 8.1.9 EPTSC-09, deleted (incorporated into EPTSC-00) 8.2 Activation 8.2.1 TSC activation is required following declaration of an Alert or higher emergency classification level. Earlier activation is at the discretion of the SEC OR the Shift Superintendent of Operations (SSO).
8.2.2 The TSC Emergency Response Organization (ERO) shall be notified to activate the TSC using any combination of public address (PA), beeper, NREC, OR Dialogic.
- 1. Refer to EPNOT-00, Notification and Emergency Communications for details.
8.2.3 The TSC shall be activated within 60 to 75 minutes following declaration of an ALERT or higher emergency classification OR upon beeper request for activation to support non-emergency events, i.e. weather related activations, increases in the National Terror Threat Level, etc.
- 1. All personnel responding from off-site shall make a Fitness-For-Duty affirmation prior to their initial entry into the Protected Area OR the TSC/EOF Facilities Building, for each event.
- 2. Sign in on the Security Roster
I EPTSC-00 I Rev. 4 l Page6of 12
8.2.4 Dynamic situations which arise in an emergency condition may require that steps be performed out of sequence OR alternate methods be devised to accomplish the intent of the step.
- 1. Deviations which do not violate license requirements may be approved by the SEC or Emergency Response Manager (ERM)
- 2. Deviations which violate license requirements shall be implemented per 10CFR50.54 (x, y, and z). Time permitting, SEC OR ERM approval shall also be obtained.
- 3. Deviations are reportable to the NRC within one hour.
8.2.5 In order to relieve the Control Room of NRC communication activities, the SEC AND the NRC Emergency Communicator can assume and conduct communication activities from the TSC prior to facility activation.
8.2.6 ERO members shall verify operability of equipment and availability of reference materials AND forms necessary. Report deficiencies to the Administrative and Logistics Manager (ALM) in the Emergency Operations Facility (EOF).
8.2.7 Determine the need for additional resources AND report these to ALM in the EOF.
8.2.8 Emergency Response Organization (ERO) Team Leaders/Directors shall verify their readiness to the position they report to.
8.2.9 Leaders/Directors shall verify readiness of staff personnel.
8.2.10 Activate the TSC.
- 1. Notify onsite/offsite locations.
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8.2.11 Each position with a specific procedure to direct their activities shall initiate a written OR electronic log of significant emergency response activities. Generally speaking, logs for teams will be maintained by the team leader.
- 1. Log your name AND the date prior to entry of activities for that shift.
- 2. Logs shall include communications, key decisions, AND data collected OR transmitted in support of those decisions.
- 3. For convenience, log books are available for positions required to maintain a log. Scraps of paper, napkins, etc are not appropriate for the final version of logs. Final versions of logs should be maintained current.
8.2.12 Receive plant status briefing from the SEC-Control Room (CR).
Participate in the initial briefing by providing status information regarding your emergency response area.
- 1. Brief facility members.
8.2.13 Establish a schedule for subsequent TSC facility briefings.
- 1. Communicate times to subordinates.
8.2.14 The SEC OR the ERM shall authorize affected emergency response personnel to exceed the Technical Specification Limits for extended overtime utilizing PLP-015, Program For Nuclear Power Plant Staff Working Hours.
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8.3 Turnover 8.3.1 UPON determination that a shift change is necessary, THEN the Administrative and Logistics Manager (A&LM) in the EOF will coordinate the shift change schedule(s).
- 1. Each ERO member shall have a relief individual.
- 2. Team Leaders/Directors will notify the relief shift personnel under their leadership.
- 3. Relief times should be staggered to promote continuity of response.
8.3.2 Each ERO member shall brief their relief on specific activities or events currently in progress AND any event that took place on their shift that is significant to the control or recovery of the plant/public interest.
8.3.3 Review log AND other documentation. Log the name of oncoming personnel, the date AND the time of turnover in the log/documentation.
8.3.4 Relief staff shall sign-in on the organization chart board, announce name AND position title to TSC staff.
8.4 Deactivation NOTE: A review of the EAL charts and actions taken should be performed to ensure all events have been addressed AND the site is ready for deactivation.
8.4.1 Determine the need to deactivate facilities.
- 1. Consult with the ERM AND offsite agencies which have activated.
8.4.2 Notify offsite/onsite/industry contacts of the deactivation time.
8.4.3 Evaluate condition of equipment/supplies. Report deficiencies to the A&LM in the EOF.
8.4.4 Record the deactivation time, your name, AND the date on the log/documentation.
8.4.5 Provide these materials to the Emergency Preparedness group.
- 1. Training exercise records should be provided to the Lead Facility Controller.
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9.0 RECORDS All forms or documents created by this or any support procedure shall be sent to the Emergency Preparedness Group.
10.0 ATTACHMENTS 10.1 Technical Support Center (TSC) Organization Chart 10.2 Technical Support Center (TSC) Command Room Recommended Layout I EPTSC-00 I Rev. 4 l Page 10 of 12
C (
ATTACHMENT 10.1 Page 1of 1 TECHNICAL SUPPORT CENTER (TSC) ORGANIZATION I
Emergency I
Plant Communicator Operations (NRC) Director Shift Superintendent of Operations EPTSC-00 I Rev. 4 Page 11 of 12
ATTACHMENT 10.2 Page 1 of 1 TECHNICAL SUPPORT CENTER (TSC)
COMMAND ROOM RECOMMENDED LAYOUT IEPTSC-00 I Rev.4 l Page 12of 12