ML032950627
| ML032950627 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Watts Bar, Sequoyah  |
| Issue date: | 10/20/2003 |
| From: | Burzynski M Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML032950627 (118) | |
Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga. Tennessee 37402-2801 October 20, 2003 10 CFR 50, Appendix E Section V U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:
In the Matter of ) Docket Nos. 50-259 50-3 90 Tennessee Valley Authority 50-2 60 50-3 91 50-296 50-327 50-328 TVA CENTRAL EMERGENCY CONTROL CENTER (CECC) - EMERGENCY PLAN IMPLEMENTING PROCEDURE (EPIP) REVISIONS In accordance with the requirements of 10 CFR Part 50, Appendix E, Section V, enclosed are copies of the Effective Page Listing and revisions to CECC EPIPs.
PROCEDURE EFFECTIVE DATE EPIP EPL 10/9/03 EPIP-6 Rev. 25 10/9/03 EPIP-7 Rev. 29 10/9/03 EPIP-8 Rev. 27 10/9/03 EPIP-23 Rev. 19 10/9/03 If you have any questions, please contact Terry Knuettel at (423) 751-6673.
Sincerely, Mark Burz i Manager Nuclear Licensing Enclosures cc: See page 2 pL5 Pfted ,nmcofed MM
U.S. Nuclear Regulatory Commission Page 2 October 23, 2003 cc (Enclosures):
U.S. Nuclear Regulatory Commission (Enclosures 2)
Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector [Enclosures provided Browns Ferry Nuclear Plant by site DCRM]
10833 Shaw Road Athens, Alabama 35611-6970 NRC Senior Resident Inspector [Enclosures provided Sequoyah Nuclear Plant by site DCRM]
2600 Igou Ferry Road Soddy Daisy, Tennessee 37379-36, NRC Senior Resident Inspector [No enclosures, by request Watts Bar Nuclear Plant of site resident]
1260 Nuclear Plant Road Spring City, Tennessee 37381
DOCUMENT RELEASE AND FILING INSTRUCTIONS II I Page 1 of I Release No.
-4o: Management Service!sIRIMIEDM Prepared By: Gail White Other Address: .
Extension: 751-2108 Date Submitted to Management Organization: AS&P Services/RIM/EDM: Address: LP 4D-C Date to Filed By:
Attached are: (select one) Release and Submitted for:
3 QA Records/Documents 0 Distribution Cl Non-QA Records/Documents 0 Retention REC NO. ACCPT REMOVE INSERT DOCUMENT NUMBER REV PAGES N DATE PAGES PAGES CECC-EPIP =_=_=
List of Effective Pages 9 V 10/09/03 1-9 1- 9 CECC EPIP-6, cover sheet 25 1 _ ID- cover sheet cover sheet CECC EPIP-6, rev. log 25 / rev log rev. log CECC EPIP-6 25 23 _ All 1 -23 CECC EPIP-7, cover sheet 29 1 -lo - J _cover sheet cover sheet
- ECC EPIP-7, rev. log 29 2 j Vrev. log rev. log CECC EPIP-7 29 15 _ All 1-15 CECC EPIP-8, cover sheet 27 1 JO -9 -03 cover sheet cover sheet CECC EPIP-8, rev. log 27 2 -_V rev. log rev. log CECC EPIP-8 27 32 All 1 - 32 CECC EPIP-23, cover sheet 19 1 V-= Ad cover sheet cover sheet CECC EPIP-23, rev. log 19 2. / V., rev. log rev. log CECC EPIP-23 19 24 _ All 1 -24 Acceptance:
Date
- QmC-f Of.
Signature
/a" a -- ' o3 Date
Contact:
Ext.
5 PP.2.3-3 [08-29.97]
(8.97)[08-97] Page 1 of 1 TVA 40074B (8-97) [08-971 TVA40074B Page 1 of 1 SPP-2.3-3 [08-29-971
CECC-EPIP EPL Page 1 of 9 10/09/03 V2 TENNESSEE VALLEY AUTHORITY CENTRAL EMERGENCY CONTROL CENTER EMERGENCY PLAN
- ~ IMPLEMENTING PROCEDURES LIST OF EFFECTIVE PAGES This list of effective pages must be retained with the CECC-EPIPs.
Procedure No. Subdivision Page No. Rev. No.
List of Effective Pages 1 of 9 10/09/03 2 of 9 10/09/03 3 of 9 10/09/03 4 of 9 10/09/03 5 of 9 10/09/03 6 of 9 10/09/03 7 of 9 10/09/03 8 of 9 10/09/03 9 of 9 10/09/03 Table of Contents 1 of 2 10/17/02 2 of 2 10/17/02 EPIP-1 Cover Sheet 37 Rev. Log 37 1 of 33 37 2 of 33 37 3 of 33 37 4 of 33 37 5 of 33 37 Appendix A 6 of 33 37 Appendix B 7 of 33 37 8 of 33 37 Appendix C 9 of 33 37 Appendix D 10 of 33 37 Appendix E 11 of 33 37 Appendix F 12 of 33 37 Appendix G 13 of 33 37 14 of 33 37 Appendix H 15 of 33 37 Appendix I 16 of 33 37 17 of 33 37 18 of 33 37 19 of 33 37 Appendix J 20 of 33 37 21 of 33 37 22 of 33 37 23 of 33 37 Appendix K 24 of 33 37 25 of 33 37 26 of 33 37 Appendix L 27 of 33 37 Appendix M 28 of 33 37 Appendix N 29 of 33 37 30 of 33 37
CECC-EPIP EPL Page 2 of 9 10/09/03 List of Effective Pages (Continued)
Procedure No. Subdivision .-
- Page No. Rev. No.
EPIP-1 (Continued) 31 of 33 _ 37 32 of 33 37
- 33of33' 37 EPIP-2 Cover Sheet 30-Rev. Log 30 1 of 5 - , 30 2 of 5 30 3 of 5 30 Appendix A 4 of 5 30 Appendix B 5 of 5 30 EPIP-3 Cover Sheet 31 Rev. Log 31 I of 8 31 2 of 8 31 3 of 8 31 4 of 8 31 5 of 8 31 Appendix A 6 of 8 31 Appendix B 7 of 8 31 Appendix C 8 of 8 31 EPIP-4 Cover Sheet 32 Rev. Log 32 1 of 8 32 2 of 8 32 3 of 8 32 4 of 8 32 5 of 8 32 Appendix A 6 of 8 32 Appendix B 7 of 8 32 Appendix C 8 of 8 32 EPIP-5 Cover Sheet 34 Rev. Log 34 1 of 10 - 34 2 of 10 34 3 of 10 34 4 of 10 34 5 of 10 34 Appendix A - 6 oflO . - 34 7 of 10 34 8 of 10 34 Appendix B 9 of 10 34 Appendix C . 10 of 10 34 EPIP-6 Cover Sheet 25 Rev. Log 25 1 of 23 25 2 of 23 25 3 of 23 25 4 of 23 25
CECC-EPIP EPL Page 3 of 9 10/09/03 List of Effective Pages (Continued)
Procedure No.nu Subdivision Page No... Rev. No.
EPIP-6 (Continued)-. Appendix A 5 of 23 25 6 of 23 25 7 of 23 25 Appendix B 8 of 23- 25 Appendix C 9 of 23 25 Appendix D 10 of 23 25 11 of 23 25 Appendix E 12 of 23 25 13 of 23 25 14 of 23 25 Appendix F 15 of 23 25 Appendix G 16 of 23 25 17 of 23. 25 Appendix H 18 of 23 25 19 of 23 25 Appendix I 20 of 23 25 21 of 23 25 Appendix J 22 of 23 25 Appendix K 23 of 23 25 EPIP-7 Cover Sheet 29 Rev. Log 29 1 of 15 29 2 of 15 29 3 of 15 29 4 of 15 29 5 of 15 29 6 of 15 29 7 of 15 29 8 of 15 29 Appendix A 9 of 15 29 Appendix B1 10 of 15 29 Appendix C 11 of 15 29 Appendix D 12 of 15 29 13 of 15 29 Appendix E 14 of 15 29 Appendix F 15 of 15 29 EPIP-8 Cover Sheet 27 Rev. Log 27 I of 32 27 2 of 32 27 3 of 32 27 4 of 32 27 5 of 32 27 6 of 32 27 Appendix A 7 of 32 27 Appendix B 8 of 32 27 Appendix C 9 of 32 27 10 of 32 27 Appendix D 11 of 32 27
CECC-EPIP EPL Page 4 of 9 10/09/03 List of Effective Pages (Continued)
Procedure No. Subdivision Page No. - Rev. No.
EPIP-8 (Continued) 12 of 32 27 Appendix E 13 of 32 27 14 of 32 27 Appendix F 15 of 32 27 16 of 32 27 17 of 32 27 18 of 32 27 19 of 32 27 20 of 32 27 21 of 32 27 22 of 32 27 Appendix G 23 of 32 27 Appendix H 24 of 32 27 Appendix I 25 of 32 27 26 of 32 27 27 of 32 27 28 of 32 27 29 of 32 27 Appendix J 30 of 32 27 31 of 32 27 32 of 32 27 EPIP-9 Cover Sheet 28 Rev. Log 28 1 of 49 28 2 of 49 28 3 of 49 28 4 of 49 28 5 of 49 28 6 of 49 28 7 of 49 28 8 of 49 28 9 of 49 28 10 of 49 28 11 of 49 28 12 of 49 28 13 of 49 28 14 of 49 28 15 of 49 28 16 of 49 28 17 of 49 28 18 of 49 28 19 of 49 28 20 of 49 28 21 of 49 28 22 of 49 28 23 of 49 28 24 of 49 28 25 of 49 28 Appendix A 26 of 49 28 Appendix B 27 of 49 28 Appendix C 28 of 49 28
CECC-EPIP EPL Page 5 of 9 10/09/03 List of Effective Pages (Continued)
Procedure No. Subdivision Page No. Rev. No.
EPIP-9 (Continued) 29 of 49 28 Appendix D 30 of 49 28 31 of 49 28 Appendix E 32 of 49 28 33 of 49 28 Appendix F 34 of 49. 28 Appendix G 35 of 49 28 Appendix H 36 of 49 28 37 of 49 28 38 of 49 28 39 of 49 28 Appendix I 40 of 49 28 41 of 49 28 42 of 49 28 43 of 49 28 Appendix J 44 of 49 28 Appendix K 45 of 49 28 Appendix L 46 of 49 28 47 of 49 28 48 of 49 28 49 of 49 28 EPIP-1 I Cover Sheet 12 Rev. Log 12 I of 17 12 2 of 17 12 Appendix A 3 of 17 12 Appendix B 4 of 17 12 Appendix C 5 of 17 12 6 of 17 12 Appendix D 7 of 17 12 Appendix E 8 of 17 12 9 of 17 12 10 of 17 12 Appendix F 11 of 17 12 Appendix G 12 of 17 12 Appendix H 13 of 17 12 Appendix I 14 of 17 12 Appendix J 15 of 17 12 16 of 17 12 17 of 17 12 EPIP-12 Cover Sheet 18 Rev. Log 18 1 of 19 18 2 of 19 18 Attachment 1 3 of 19 18 Attachment 2 4 of 19 18 Attachment 3 5 of 19 18 Attachment 3 6 of 19 18 Attachment 3 7 of 19 18 Attachment 3 8 of 19 18
CECC-EPIP EPL Page 6 of 9 10/09/03 List of Effective Pages (Continued)
Procedure No.
%roceaureNo. Subdivision Page No. Rev. No.
EPIP-12 (Continued) Attachment 3 9 of 19 18 Attachment 4 10 of 19 18 Attachment 5 11 of 19 18 Attachment 6 12 of 19 18 Attachment 7 13 of 19 18 Attachment 7 14 of 19 18 Attachment 8 15 of 19 18 Attachment 9 16 of 19 18 Attachment 9 17 of 19 18 Attachment 10 18 of 19 18 Attachment 10 19 of 19 18 EPIP-13 Cover Sheet 10 Rev. Log 10 1 of 15 10 2 of 15 10 3 of 15 10 4 of 15 10 5 of 15 10 6 of 15 10 Appendix A 7 of 15 10 8 of 15 10 9 of 15 10 Appendix B 10 of 15 10 Appendix C 11 of 15 10 12 of 15 10 13 of 15 10 14 of 15 10 Appendix D 15 of 15 10 EPIP-14 Cover Sheet 25 Rev. Log 25 1 of 21 25 2 of 21 25 3 of 21 25 4 of 21 25 5 of 21 25 6 of 21 25 Appendix A 7 of 21 25 8 of 21 25 9 of 21 25 Appendix B 10 of 21 25 11 of 21 25 12 of 21 25 13 of 21 25 14 of 21 25 Appendix C 15 of 21 25 16 of 21 25 17 of 21 25 18 of 21 25 19 of 21 25
CECC-EPIP EPL Page 7 of 9 10/09/03 List of Effective Pages (Continued)
Proced lure No. Subdivision Page No. Rev. No. A:
EPIP-14 (Continued) 20 of 21 25 Appendix D 21 of 21 25 EPIP-15 Cover Sheet 0 Rev. Log 0 1 of 5 0 2 of 5 0 3 of 5 0 Appendix A 4 of 5 0 Appendix B 5 of 5 0 EPIP-17 Cover Sheet 17 Rev. Log 17 1 of 27 17 2 of 27 17 3 of 27 17 4 of 27 17 5 of 27 17 Appendix A 6 of 27 17 Appendix B 7 of 27 17 Appendix C 8 of 27 17 9 of 27 17 10 of 27 17 Appendix D 11 of 27 17 Appendix E 12 of 27 17 Appendix F 13 of 27 17 Appendix G 14 of 27 17 15 of 27 17 16 of 27 17 17 of 27 17 18 of 27 17 Appendix H 19 of 27 17 Appendix I 20 of 27 17 Appendix J 21 of 27 17 Appendix K 22 of 27 17 Appendix L 23 of 27 17 Appendix M 24 of 27 17 25 of 27 17 26 of 27 17 Appendix N 27 of 27 17 EPIP-18 Cover Sheet 9 Rev. Log 9 1 of 6 9 2of6 9 3 of 6 9 4 of 6 9 Appendix A 5of6 9 Appendix B 6 of 6 9
I CECC-EPIP EPL Page 8 of 9 i 10/09/03 List of Effective Pages (Continued) I.
Procedure No. Subdivision Page No. Rev. No.
EPIP-19 Cover Sheet 12 Rev. Log 12 i of 11 12 2 of 11 12 3 of 11 12 4 of 11 12 5 of 11 12 Appendix A 6 of 11 12 7 of 11 12 Appendix B 8 of 11 12 9 of 11 12 10 of 11 12 11 of 11 12 EPIP-21 Cover Sheet 13 Rev. Log 13 1 of 4 13 2 of 4 13 Appendix A 3 of 4 13 Appendix B 4 of 4 13 EPIP-22 Cover Sheet 19 Rev. Log 19 1 of 7 19 2 of 7 19 Attachment A 3 of 7 19 Attachment B 4 of 7 19 5 of 7 19 6 of 7 19 7 of 7 19 EPIP-23 Cover Sheet 19 Rev. Log 19 1 of 24 19 2 of 24 19 3 of 24 19 4 of 24 19 Attachment A 5 of 24 19 Attachment B 6 of 24. 19 7 of 24 19 8 of 24 19 9 of 24 19 10 of 24 19 11 of 24 19 Attachment C 12 of 24 19 Attachment D 13 of 24 19 Attachment E 14 of 24 19 15 of 24 19 Attachment F 16 of 24 19 17 of 24 19 18 of 24 19
CECC-EPIP EPL Page 9 of 9 10/09/03 List of Effective Pages (Continued)
Procedure No. Subdivision Page No. Rev. No.
EPIP-23 (Continued) 19 of 24 19 20 of 24 19 Attachment G 21 of 24 19 22 of 24 19 Attachment H 23 of 24 19 Attachment I 24 of 24 19
CECC EPIP Coversheet Title CECC EPIP-6 Tennessee REV. 25 Valley Authority CENTRAL EMERGENCY CECC PLANT ASSESSMENT STAFF CONTROL CENTER PROCEDURE FOR ALERT, SITE EMERGENCY PLAN AREA EMERGENCY, AND IMPLEMENTING GENERAL EMERGENCY Effective Date:
PROCEDURES ._. _. /a/ 'b/03 WRITTEN BY: , ,/ d REVIEWED BY: (4/a/CZ/zc_/
Signature Signature Date PLAN EFFECTIVENESS DETERMINATION: C 6ate Signature Date CONCURRENCES Concurrence Signature Date 0 Manager, EP Program Planning and Implementation 0 Manager,_ergency Preparedness 0 Manager, Radiological and Chemistry Services \C31o
. . ) ~ ,
.1 -
11 i
CECC-EPIP-6 CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, SITE AREA EMERGENCY, AND GENERAL EMERGENCY REVISION LOG lns DPna Rev. No. - . --
L-- I L
-t --- 0--i-A~
1-'VVQUU rayoua 0 3/22/88 All (Changed from IPD to EPIP) 1 718188 Page 1 of App;-E-2 7/13/89 2, 3, App. A, App. F 3 10/26/89 4, App. A (1-2), App. C, App. G-l 4 7/02/90 1-4, App. E (1-6), App. H (pg. 1), App. J (added) 5 9/14/90 App. A, pg. 1; App. C, pg. 2; App. E, Pgs. 1-4; App. G, pg. 2 6 5/21/91 Page 1 of 4, App. C, Pgs. I & 2, App. E, Pgs. 1 - 5, App. G, Pg. 2, App. H, Pg. 1 7 5/15/92 App. A, pg. 3, App. G, Pg. 1, and App. I, pg. 1 revised. New coversheet & rev. log added. All pages issued.
l!
8 05/17/93 2-4; App. A, pgs. 1 &3; App. C, pg. 1;App. D, pg. 1;App. E, pg. 1: new App. G added; App. H, pgs. 1-2; App. I, pg. 1; App. J; and App. K. All pages issued to maintain rev. level.
9 07/19/93 Appendix C, pgs. 1-3; App. E, pgs. 1-3. All pages issued.
10 11/30/93 App. C, pgs. 1-2; all pages issued.
11 04/19/94 Pgs. 1, 2, & 4; App. A; App. C; App. F (deleted) App. G; App. H; App. I; and App. J 12 6/26/95 App. F; all pages issued.
13 11/01/95 Revise PAR Diagram. All pages issued.
14 10/30/96 Remove non-plant assessment staff responsibilities from the procedure, update PAR chart, update references list, remove references to written status updates provided by sites, remove specific numbers of Technical Advisors to be assigned at different centers, remove reference to locked drawing cabinet. Procedure put in new format. All pages issued.
15 4/7/97 Annual review. Editorial changes, revise PAC checklist, revise insurance notification instructions, streamline instructions. All pages issued.
16 3/6/98 Annual review. Pgs. 12-14 revise critical drawing lists. Pg. 16 revise Plant Assessment Manager Checklist. Pg. 22 revise CECC Assessment Team Leader Checklist. All pages issued.
17 7/7198 Revise critical drawing list (App. E) and Plant Assessment Team Reference Material/Equipment (App. D). All pages issued.
CECC-EPIP-6 CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, SITE AREA EMERGENCY, AND GENERAL EMERGENCY REVISION LOG (Continued)
RevwNo; - Date -- -- Revised Pages-18 10/27/98 Update Plant Assessment Coordinator and Assessment Team Leader checklists. All pages issued.
19 2/22/99 Revise PAR diagram. Annual review. All pages issued.
20 5/1/99 Revise PAR diagram. All pages issued.
21 8/17/00 Annual review. Revise PAR diagram. All pages issued.
22 215/01 Correct PAR diagram. All pages issued.
23 3/30/01 Annual review. Provide new PAR diagram. All pages issued.
24 5-30-03 Update RSC instruction for insurance carrier notification.
25 10/09/03 Annual review. Update instructions for information to be provided to the Insurance Carrier. Add clarification for the WBN and SQN PAT Leader for BFN events. All pages issued.
CECC PLANT ASSESSMENT _
STAFF PROCEDURE FOR ALERT, Page 1 of 23 SITE AREA EMERGENCY, AND CECC EPIP-6 Revision 25 GENERAL EMERGENCY CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, SITE AREA EMERGENCY. AND GENERAL EMERGENCY 1.0 -PURPOSE This procedure is designed to direct the Plant Assessment Manager and staff to ensure a consistent, accurate, and timely response in the event of an accident. This procedure further serves to identify the necessary information which is provided to the CECC Director to ensure that prompt, accurate, public protective action recommendations can be made by the CECC to appropriate State authorities.
2.0 SCOPE
-This procedure covers the actions of the Plant Assessment Manager and staff during an Alert, Site Area Emergency, or General Emergency.
3.0 REFERENCES
Radiological Emergency Plan.
4.0 ABBREVIATIONS AND DEFINITIONS CECC - Central Emergency Control Center EDO - Emergency Duty Officer FSAR - Final Safety Analysis Report NCO - Nuclear Central Office NE - Nuclear Engineering NP - Nuclear Power ODS - Operations Duty Specialist SM -,Shift Manager SPDS - Safety Parameter Display System STC - Sequoyah Training Center SRO - Senior Reactor Operator REND - Radiological Emergency Notification Directory' TAT - Technical Assessment Team (onsite)
TSC -'Technical Support Center 5.0 RESPONSIBILITIES 5.1 The ODS is responsible for contacting the CECC Plant Assessment staff and having them report to the CECC.
The Plant Assessment Manager is responsible for ensuring that the CECC Director is provided with periodic summaries of information needed for overall accident assessment.
i i CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, Page 2 of 23 SITE AREA EMERGENCY, AND CECC EPIP-6 Revision 25 GENERAL EMERGENCY 5.2 CECC Plant Assessment Staff The CECC Plant Assessment staff is responsible for assisting the Plant Assessment Manager in carrying out his responsibilities in providing NCO technical support to the affected plant and to the CECC Director. An assignment of positions and duties of the Plant Assessment staff as well as a description of augmenting support groups is described in appendix A.
5.3 Attachment K or a similar form will be used to document Fitness for Duty when an individual is called and requested to respond to an emergency.
6.0 PROCEDURE REQUIREMENTS 6.1 Initial Actions (Plant-Assessment Manager) 6.1.1 Notify the Technical Assessment Manager that the CECC Plant Assessment staff is activated.
Obtain a current status report.
6.1.2 Review the emergency condition with the CECC Director.
6.1.3 Ensure that the Plant Assessment Team and Boardwriter have established communication with the site control room communication bridge.
6.1.4 Determine if other technical support personnel are required and, if so, have the ODS notify.
(See REND.)
6.2 Accident Assessment 6.2.1 Verify that the ICS is functional.
6.2.2 The Plant Assessment Team shall evaluate site's conditions and develop assessments in terms of current and long-range plant conditions and apply their evaluation to making appropriate public protective action recommendations.
6.2.3 The Plant Assessment Manager shall ensure that accident assessment information is provided to the CECC Director on a frequent basis (at a minimum, hourly). These assessments shall provide summary information (appendix B) as well as appropriate recommended public protective actions in accordance with accident assessment logic specified in Appendix C. The Plant Assessment Manager will ensure the plant information on the status display is correct and current. (See Appendix G for checklist.)
CECC PLANT ASSESSMENT -
STAFF PROCEDURE FOR ALERT, Page 3 of 23 SITE AREA EMERGENCY, AND CECC EPIP-6 Revision 25 GENERAL EMERGENCY 6.2.4 Potential Release Evaluation If after consultation with the Plant Assessment and Radiological Assessment Managers, the CECC Director requests that a predictive release evaluation be performed based on the potential for significant changes in plant conditions, the Plant Assessment Team shall determine the appropriate assumptions to be made and perform the necessary calculations. The areas to be considered are as follows:
- a. Increased fuel failure (changes in primary coolant activity levels).
- b. Anticipated changes in primary coolant leakage rates or break sizes.
- c. Anticipated changes in containment leakage rates (i.e., changes in containment pressure and/or changes in size of containment ruptures or holes).
6.3 General Operation 6.3.1 During the course of an emergency, should the accident upgrade, or terminate, the Plant Assessment Manager shall notify the CECC Director immediately.
6.3.2 If available personnel and equipment of NP are not enough to cope with the emergency, contact the designated representative of other TVA organizations, as necessary, to supply adequate resources to recover from the accident. Log the organizations called for assistance. A description of services available and emergency contacts are available in the TVA Radiological Emergency Notification Directory (REND).
6.3.3 For a Site Area Emergency or General Emergency, the site should be reminded that additional technical personnel are available from the CECC to assist the technical support staff at the TSC.
The Plant Assessment Manager should discuss the need for this upgraded capability with the Technical Assessment Manager. Based upon this discussion, selected technical support personnel may be dispatched by ground or air transportation.
6.3.4 The Plant Assessment Manager will coordinate with the CECC Director the selection of staff to serve as Technical Advisor(s) to the TVA spokesperson at the JIC; the Public Information Manager and the State Communicator in the CECC; and the TVA liaison at the State EOC. This position will be responsible for providing a nontechnical interpretation of the events.
6.3.5 Relief of Duties Should the accident be expected to last for an extended period, the Plant Assessment Manager originates a schedule for relief. The duties of Plant Assessment Manager should only be passed on to qualified individuals for the Plant Assessment Manager's position. He also directs his staff to prepare a schedule for their relief to ensure that necessary Plant Assessment staff is available for the duration of the emergency.
'F CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, Page 4 of 23 SITE AREA EMERGENCY, AND CECC EPXP-6 Revision 25 GENERAL EMERGENCY 6.3.6 The Plant Assessment Manager and staff will support the CECC Director as required for carrying out recovery efforts from the accident.
6.3.7 Upon termination of the emergency, the Plant Assessment Manager and staff shall make themselves available for review of the accident.
7.0 Checklist for Positions Plant Assessment Coordinator - Appendix H Resource Support Coordinator - Appendix I Plant Assessment Team Leader- Appendix J i1
CECC PLANT ASSESSMENT : ,
STAFF PROCEDURE FOR ALERT, Page 5 of 23 SITE AREA EMERGENCY, AND CECC EPIP-6 Revision 25 GENERAL EMERGENCY -
APPENDIX A Page 1 of 3 CECC PLANT ASSESSEMENT STAFF POSITIONS/SUPPORT FUNCTIONS I. PLANT ASSESSMENT STAFF A. Plant Assessment Manager - Directs the CECC Plant Assessment staff and advises the
-CECC Director on protective action recommendations based on plant status. (See CECC-EPIP-1, Appendix A, for specific duties).
B. Plant Assessment Coordinator - Responsible for managing the overall activities of the CECC Plant Assessment Team and keeping the Plant Assessment Manager and CECC Director informed of plant status. (See Appendix H for checklist.)
- 1. Ensures that overall plant assessments are being periodically provided to the Plant Assessment Manager. This assessment (Appendix B) shall be based on an evaluation of plant conditions and its application to the protective action logic diagram (Appendix C). 'The Plant Assessment Manager will use the assessments and recommendations to brief the CECC Director.
- 2. Responsible for coordinating (through the Resource Support Coordination) other support activities as required.
C. Resource Support Coordinator - Coordinates certain staff and logistical support to the CECC. Conveys requests for technical support from NP sources. (See Appendix I for checklist.)
- 1. Provides logistics support as required to the CECC.
- 2. Maintains communications with other NP technical staff representatives to keep them briefed on the emergency conditions and coordinates obtaining support from them as necessary.
- 3. Assists the Plant Assessment Coordinator in other communications needs as necessary.
- - A4. The Resource Support Coordinator provides initial notification to the liability
- insurance carrier (ANI).
- Revision
CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, SITE AREA EMERGENCY, AND GENERAL EMERGENCY-CECC EPIP-6 n Page 6 of 23 Revision 25 I APPENDIX A Page 2 of 3 D. Plant Assessment Team - Provides periodic evaluation of plant status information and protective action recommendations (when applicable) to the Plant Assessment Manager.
Serves as a technical reference. (See Appendix J for checklist.)
The assessment team shall be made up of the following: team leader, engineers, SROs, STAs, core damage assessors, etc. Exact makeup of the team will be determined by the team leader.
Duties
- 1. The Plant Assessment Team Leader will be activated by the ODS. The Plant Assessment Team Leader is responsible for activating the remainder of the required team members.
- 2. The assessment team shall provide a periodic evaluation of the situation and input back to the site and the CECC as appropriate via the Plant Assessment Coordinator.
- 3. The assessment team shall evaluate all current ICS data and previous telecopied information and discuss the key plant events with the Plant Assessment Manager or Plant Assessment Coordinator to ensure they have received all the information necessary to begin an evaluation of plant conditions.
Appendix C provides a methodology to be used as guidance in providing a recommended protective action for the public to the CECC Director.
- 4. The assessment team will draw on their knowledge of SPDS data, FSAR, Emergency Operating Instructions, owners' group work, analytical basis for accident analyses, and communications with the TSC in generating plant assessments (appendix B) in terms of current and long-range plant conditions, and in applying their evaluation to the protective action logic diagram (appendix C). Appendix D provides a list of reference material which is maintained in the Plant Assessment Team area. Appendix E provides a list of the critical drawings which are controlled in the CECC. The overall accident assessment serves to inform the Plant Assessment Manager of the general plant status. It also enables the Plant Assessment Manager to communicate with the CECC Director in planning offsite protective actions with the intent of informing the State through the CECC of the status of the plant and the implications of that status. These assessments shall be updated hourly (minimum).
- 5. If requested, the assessment team may serve as an engineering/ operations reference for the plant. They will reply to plant inquiries to the best of their ability based on the available information. (See Appendix F for recommendation form). Gross predictive actions may be required for offsite emergency planning.
If possible, the change in plant status will be addressed (e.g., the plant's status is improving or the plant's status is degrading).
APPENDIX A Page 3 of 3
- 6. The assessment team, based on the particular accident, will select appropriate safety parameters for trending.
- assit the BWR Team Leader/PAC with general duties, such as
- Boardwriter or Communicator. This role does not require detailed knowledge
- of BWR structures, systems, components and procedures.
E. Encineerina Coordinator - Coordinates corporate engineering support for the CECC and serves as point of contact for the NE representative in the TSC.
- 11. SUPPORTING NP STAFFS Certain organizations may be activated along with the CECC Staff. If requested to staff by the CECC Director, they will report to the assigned location and coordinate support within their areas of expertise.
111. TECHNICAL SUPPORT Certain NP staffs provide expertise in reactor systems and core engineering, electrical engineering, mechanical engineering, chemical engineering, chemistry, shielding, transient analysis, fire protection, electrical distribution (inplant), security, metallurgy, radwaste, and instrumentation. The Plant Assessment Manager delegates to the Resource Support Coordinator the job of contacting these designated individuals by phone or through their respective organizational contacts as needed. If necessary, technical support personnel may be sent to the plant.
- Revision
APPENDIX B Page 1 of I PLANT SYSTEMS ASSESSMENT TO: PLANT ASSESSMENT MANAGER TIME OF ASSESSMENT FROM: PLANT ASSESSMENT TEAM PAGE:
UNIT:
PLANT SYSTEMS ASSESSMENT
- 1. HEAT REMOVAL CAPABILITY oI Stable E3 Improving El Deteriorating Basis:
- 11. FUEL INTEGRITY AND Rx STATUS El Stable Dl Improving El Deteriorating Basis:
Ill. RADIOACTIVITY IN CONTAINMENT O Stable El Improving El Deteriorating Basis:
IV. CONTAINMENT INTEGRITY AND STATUS El Stable El Improving El Deteriorating Basis:
V. OVERALL ASSESSMENT (Including status of other units)
El Stable El Improving El Deteriorating Basis:
Assessment Team Leader Time Plant Assessment Coordinator Time
CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, Page 9 of 23 SITE AREA EMERGENCY, AND CECC EPIP-6 Revision 25 GENERAL EMERGENCY APPENDIX C Page 1 of 1 PROTECTIVE ACTION RECOMMENDATIONS Note 1: If conditions are unknown utilizing the flowchart, then answer NO.
~en eral tD Em e clI ergen a re d c) ICONTINUE ASSESSMENT
, / Modify protec tive actions based I. on availa ble plant and field mI nonitorii ng information.
0 Locate ai id evaluate localized hot spots -
A
/ ~or beyond 5 miles is the Projected NO or Measured Dose Greater than PAG A Table 1 Limits YES a
RECOMMENDATION 1 RECOMMENDATION 2 EVACUATE 2 miles radius EVACUATE 2 mile radius and 10 miles downwind and 5 miles downwind AND AND SHELTER remainder of SHELTER remainder of 10 mile EPZ 10 mile EPZ I
TABLE I Protective Action Guides TYPE LIMIT Measured 3.9E-6 microCi/cc of Iodine 131 or 1 REM/hr External Dose Projected 1 REM TEDE or 5 REM Thyroid CDE i
CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, 6Page 10of 23 SITE AREA EMERGENCY, AND CECC EPIP Revision 25 GENERAL EMERGENCY APPENDIX D -Page 1 of 2 PLANT ASSESSMENT TEAM REFERENCE MATERIAL/EQUIPMENT Seauovah Final Safety Analysis Report (FSAR)
Technical Specifications Emergency Abnormal Procedures (EAP)
Emergency Contingency Action (ECA)
Emergency Plan Implementing Procedures (EPIP)
Emergency Operating Instructions Program Manual (EPM)
Emergency Instructions (ES)
Functional Restoration Guidelines (FR)
Abnormal Operating Procedures (AOP)
PWR Systems Manuals (NRC Training Manual)
Controlled Drawings - Mechanical, Electrical, Logic, Piping Layout Offsite Dose Calculation Manual (ODCM)
Integrated Computer System (ICS)
Technical Instructions (TI-18 and TI-28)
Severe Accident Management Guidelines (SAMGs)
Browns Ferry Final Safety Analysis Report (FSAR)
Technical Specifications Emergency Plan Implementing Procedures (EPIP)
Emergency Operating Instructions (EOI, EOI-PM)
Abnormal Operating Instructions (AOI)
BWR Systems Manuals (NRC Training Manual)
Controlled Drawings - Mechanical, Electrical, Logic, Piping Layout Technical Instruction - (TI-15 and TI-45)
Offsite Dose Calculation Manual (ODCM)
Integrated Computer System (ICS)
Severe Accident Management Guidelines (SAMGs)
Watts Bar Final Safety Analysis Report (FSAR)
Technical Specifications (Tech Specs)
Technical Instructions (TI-4 and TI-18)
Abnormal Operating Instructions (AOl)
PWR Systems Manuals (NRC Training Manual)
Offsite Dose Calculation Manual (ODCM)
Emergency Contingency Actions (ECA)
Emergency Operating Instructions (El)
Emergency Plan Implementing Procedures (EPIP)
Functional Restoration Guidelines (FR)
Emergency Response Facility Data System (ERFDS)
Integrated Computer System (ICS)
Severe Accident Management Guidelines (SAMGs)
I CECC PLANT ASSESSMENT l I STAFF PROCEDURE FOR ALERT, SITE AREA EMERGENCY, AND GENERAL EMERGENCY CECC EPIP-6 Page 11 of 23 Revision 25 APPENDIX D Page 2 of 2 Cornorate Radiological Emergency Plan (REP)
CECC EPIPs Radiological Emergency Notification Directory (REND)
INPO Emergency Resources Manual (ERM)
Westinghouse Owner's Group Emergency Response Guidelines (WOGERG)
CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, Page 12 of 23 SITE AREA EMERGENCY, AND CECC EPIP6 Revision 25 GENERAL EMERGENCY APPENDIX E Page.1 of 3 BROWNS FERRY NUCLEAR PLANT CRITICAL DRAWING LIST These drawings are maintained in the CECC as critical drawings. Example of numbering system (47W800 = 1-47W800 = 1-47E800). All issued sheets, excluding connectivity (A) and insulation (E) sheets, of a listed drawing will be included unless otherwise noted. Other drawings may be kept in the CECC besides these critical drawings.
15W500 17W200 17W201 45W1504 45W1505 45W1506 45W602-3 47W610 Series 47W611 Series (CCDs only) 47W800 Series
.I CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, Page 13 of 23 SITE AREA EMERGENCY, AND CECC EPIP-6 Revision 25 l GENERAL EMERGENCY I--i APPENDIX E Page 2 of 3 SEQUOYAH NUCLEAR PLANT CRITICAL DRAWING LIST These drawings are maintained in the CECC as critical drawings. Example of numbering system (47W800 = 1-47W800 = 1-47E800). All issued sheets, excluding connectivity (A) and insulation (E) sheets, of a listed drawing will be included unless otherwise noted. Other drawings may be kept in the CECC besides these critical drawings.
15E500 47W610-70 47W611-63 47W800 47W856 47W61 0-1 -72 47W611-99 801 857
-2 -74 802 858
-3 -77 803 859
-5 -78 804 860
-6 -81 805 862
-7 -82 807 865
-12 -85 809 866
-14 -87 810 867
-15 -90 811 868
-18 -92 812
-20 -94 813 871
-24 -99 814 872
-25 815 881
-26 816
-27 819
-28 830
-30 831
' 2
-31 832
-31 C 834
-32 835
-34
-35 838
.-36 839
-39 840
-40 841
-41 842
-43 843
-46 844
-47 845
-54 846
-58 848
-59 849
-61 850
-62 851
-63 852
-65 853
-67 854
-68 855
CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, Page 14 of 23 SITE AREA EMERGENCY, AND CECC EPIP-6 Revision 25 GENERAL EMERGENCY APPENDIX E Page 3 of 3 WATTS BAR NUCLEAR PLANT CRITICAL DRAWING LIST These drawings are maintained in the CECC as critical drawings. Example of numbering system (47W800 = 1-47W800 = 1-47E800). All issued sheets, excluding connectivity (A) and insulation (E) sheets, of a listed drawing will be included unless otherwise noted. Other drawings may be kept in the CECC besides these critical drawings.
15E500 47W610-70 47W61 1-00 47W801 47W856 47W610-1 -72 47W61 1-01 803 857
-2 -74 47W611-03 804 859
-3 -77 47W611-63 805 860
-5 -78 47W611-99 807 862
-6 -81 809 865
-7 -82 810 866
-12 -87 811 868
-14 -90 812
-15 -94 813
-18 814
-20 815
-24 816
-26 819
-27 830
-28 831
-30 832
-32 834
-35 835
-36 838
-39 839
-40 840
-41 841
-43 842
-46 843
-47 844
-54 845
-58 846
-59 848
-61 849
-62 850
-63 851
-65 852
-67 853
-68 854 855
CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, Page 15 of 23 SITE AREA EMERGENCY, AND CECC EPIP-6 Revision 25 GENERAL EMERGENCY APPENDIX F Page 1 of I CECC Plant Assessment Team Recommendation to the TSC Recommendation:
Approval Plant Assessment Coordinator Approval Plant Assessment Manager
I.
CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, Page 16 of 23 SITE AREA EMERGENCY, AND -CECC EPIP-6 Revision 25 GENERAL EMERGENCY APPENDIX G Page 1 of 2 PLANT ASSESSMENT MANAGER CHECKLIST Date:_
TIME/INITIAL Designate Systems Technical Advisor to the CECC.
I Designate Systems Technical Advisors to JIC when activated.
I.
Designate Systems Technical Advisor to State EOC.
I.
If emergency was declared at BFN, verify that notification of Plant Assessment Staff
.I has been initiated.
Establish communications with Site Technical Assessment Manager.
l Notify the Site Technical Assessment Manager when the PAT is staffed.
Prepare shift staffing plan, if necessary. (Direct Plant Assessment Coordinator to prepare plan.)
GENERAL OPERATIONS
- 1. Log key events and major actions taken.
- 2. Responsible to the CECC Director to ensure that he is kept periodically briefed on plant status and protective action recommendation assessments.
- 3. Maintains contact with the site Technical Assessment Manager and ensures that necessary support is provided, makes appropriate recommendations to the Technical Assessment Manager and based on the site's disposition, informs the CECC of the site's actions.
- 4. Ensures that periodic status reports are received from the site and provided to the CECC Director, other support organizations as needed, and within the CECC.
- 5. Requests assistance from other organizations, local agencies, government installations, or vendors, as needed.
- 6. Ensures that a sequence of events is being maintained on the status display.
- 7. Verify that ICS is functional.
CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, Page 17 of 23 SITE AREA EMERGENCY, AND CECC EPIP-6 Revision 25 GENERAL EMERGENCY APPENDIX G Page 2 of 2
- 8. May provide support services to the plant by utilizing all of the necessary manpower and equipment under the control of TVAN. (Direct the Plant Assessment Coordinator to arrange these through the Resource Support Coordinator.)
- 9. Ensures that employees who may be required to go to the affected plant are fully briefed prior to leaving and know to whom they are to report. Coordinate with the RAM and State Communicator for radiological and travel conditions enroute to the site. (Delegated to the Plant Assessment Coordinator.)
- 10. Keeps the site emergency organization informed of personnel ordered to the site and expected time of arrival. (May be handled by the Plant Assessment Coordinator and site counterpart or directly through the Technical Assessment Manager.)
CECC PLANT ASSESSMENT II STAF
F. PROCEDURE
FOR ALERT, Page 18 of 23 -
SITE AREA EMERGENCY, AND GENERAL EMERGENCY CECC C EPIP Revision 25 I APPENDIX H Page 1 of 2 PLANT ASSESSMENT COORDINATOR CHECKLIST -'
Date:_
TIME/INITIAL I Ensure ICS is functional.
I Verify that the Plant Assessment Team and Board Writer have established communication with the Control Room bridge and is receiving sufficient information.
I Verify that Plant Assessment Team has established communication with the site Technical Assessment Team and that proper coordination'is taking place.
Ensure that Accident Assessment forms are being generated and provided to Plant Assessment Manager (Appendix B).
I Verify core damage has established communications with Site'RadChem.
Ensures that Core Damage Team has established communications with the site Technical Assessment Team and is receiving sufficient plant information (primary coolant characteristics, core history and conditions, etc.)
to conduct their analyses. Reconciles any discrepancies between Core Damage and Dose Assessment staffs. (Contacts via Rad. Assessment Coordinator or Dose Assessor.)
/ Initiate potential release evaluations as requested by Plant and Radiological Assessment Managers.
I. Verify that the Resource Support Coordinator has made notifications per his checklist.
APPENDIX H Page 2 of 2 GENERAL OPERATIONS
- 1. Log key events and major actions taken.
- 2. Ensures that overall plant assessments are being periodically provided to the Plant Assessment Manager. This assessment shall be based on plant system evaluation (CECC EPIP 6, Appendix B) and its application to the protective action logic diagram (CECC EPIP 6, Appendix C). The Plant Assessment Manager will use the assessments and recommendations to brief the CECC Director.
- 3. Coordinates (through the Resource Support Coordination) other support activities as required.
- 4. Notify Plant Assessment Manager immediately of any change in accident classification or significant plant condition developments.
5 Identify, notify, and brief support personnel being dispatched to the site.
6 Prepare long-term staffing plan and schedule when requested by the Plant Assessment Manager.
- 7. Ensures that the Plant Assessment Team is receiving sufficient plant systems information from their site counterpart.
- 8. Ensures continual staffing for the plant assessment function.
- 9. Provides assistance in evaluation of protective action diagram.
CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, Page 20 of 23 SITE AREA EMERGENCY, AND CECC EPIP-6 Revision 25 GENERAL EMERGENCY _
APPENDIX I Page 1 of 2 RESOURCES SUPPORT COORDINATOR CHECKLIST Date__
TIME/INITIAL I Notify NSSS Vendor (REND - Industry Support)
I Notify INPO (REND - Industry Support)
I Notify DOE (REND - Federal Support)
I Notify Insurance Carrier (REND - Insurance Carrier- Liability Insurance, ANI).
Note: The liability insurance carrier should also be notified of any nuclear plant emergency drill or exercise in which the CECC is activated.
Notify TVA's Nuclear Insurance Support (name and telephone number in REND.
l Upon termination of the REP event, notify those listed above of the termination.
GENERAL OPERATIONS
- 1. Log key events and major actions taken.
- 2. Provides logistics support to the CECC as required. Notifies the State Communicator whenever offsite (non-TVA) resources are needed and/or requested.
- 3. Maintains communications with other TVAN technical staff representatives who have been called on to provide Technical Support to the CECC keep them briefed on the emergency conditions, coordinates obtaining support from them as necessary, and notifies them when the event is terminated.
- Revision
CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, Page 21 of 23 SITE AREA EMERGENCY, AND CECC EPIP6 Revision 25 GENERAL EMERGENCY APPENDIX I Page 2 of 2
- 4. Makes certain initial notifications to industry support and insurance carriers (ANI) and updates them routinely on changing plant and offsite radiological conditions.
- 5. Assists the Plant Assessment Coordinator in other communications needs as necessary.
- 6. Provides logistics support to the plant for food, transportation and lodging.
CECC PLANT ASSESSMENT STAFF PROCEDURE FOR ALERT, Page 22 of 23 SITE AREA EMERGENCY, AND CECC EPIP-6 Revision 25 GENERAL EMERGENCY APPENDIX J Page 1 of I CECC PLANT ASSESSMENT TEAM LEADER OPERATIONAL CHECKLIST Date:
TIME/INITIAL Ensure full staffing of the CECC Plant Assessment Team: Assessment Team Leader, team members, Plant Systems Boardwriter, and CECC Technical Advisor.
l Assemble all available plant data (ODS initial report, site plant parameter data sheets, SPDS outputs, etc.) and provide a briefing to Plant Assessment Coordinator and assessment team members.
Establish contact with the site - Technical Assessment Team's, Reactor Engineer. Avoid contacting the site Technical Assessment Manager directly; his CECC contact is the Plant Assessment Manager.
General Operations
- 1. Ensure that the Plant Assessment Coordinator and other team members are kept informed of plant conditions and significant changes.
- 2. Initiate Plant Systems Summary Sheet (Appendix B) at least hourly or upon significant change in conditions.
- 3. Prepare a Protective Action Recommendation for review by the PAM as requested and for a General Emergency condition.
- 4. As requested by the site, serve as an engineering/operations reference for the plant.
- 5. Based on the particular plant conditions, select and trend appropriate safety parameters on the trending boards provided.
APPENDIX K Page 1 of I FITNESS FOR DUTY PROGRAM ADMINISTRATION TVA NUCLEAR CALL-IN SHEET Person Calling: Date:
Time Time Alcohol 5 Hrs. Fit for Duty Duty Official
. Name Called Needed to Prior to Report (YIN) Comments Report (Y/N)
I .1 I I I I~~~~~~~~~~~
9 1. t 9 9 I 4- 9 4 I 9 9. 9 9 '9 9 4. 9 9 4 9 4. 9 9 4 9 1. 9 9 '9 9 4. 9 9 4 -
_~~~
CECC EPIP Coversheet Title CECC EPIP-7 Tennessee REV. 29 Valley Authority CENTRAL EMERGENCY CECC RADIOLOGICAL ASSESSMENT
-CONTROL CENTER STAFF PROCEDURE FOR ALERT, EMERGENCY PLAN SITE AREA EMERGENCY,-AND IMPLEMENTING GENERAL EMERGENCY Effective Date:
PROCEDURES WRITTEN BY: (,.REVIEWED BY: _ _
Signature Signature Date PLAN EFFECTIVENESS DETERMINATION. get / 62j2b Signature'- Date CONCURRENCES
- Concurrence Signature Date l Ma nrora and Implementation aning 3
.EMa br, Emergen77reparedness -
ElManager, r Servic _s
,0 A
-I 1
CECC-EPIP-7 CECC RADIOLOGICAL ASSESSMENT STAFF PROCEDURE FOR ALERT, SITE AREA EMERGENCY, AND GENERAL EMERGENCY REVISION LOG Rev. No. Date Revised Pages 0 3/22/88 1 7/8/88 2 11/18/88 3 4/26/89 4 9/19/89 5 10/26/89 6 7/2190 7 9/14/90 8 5/21/91 9 10/17/91 10 12/23192 11 05/13/93 12 11/30/93 13 04/19/94 14 6/26/95 15 11/01/95 16 5/30/96 17 10/30/96 18 4/7/97 6/9/98 19 Bu4s 20
CECC-EPIP-7 CECC RADIOLOGICAL ASSESSMENT STAFF PROCEDURE FOR ALERT, SITE AREA EMERGENCY, AND GENERAL EMERGENCY REVISION LOG (Continued)
Rev;-No. Date - ==- .- Revised-Piag-e-- =
21 2-22-99 PAR diagram revised. All pages issued.
22 5/11/99 PAR diagram revised. All pages issued.
23 7/16/99 Page 15, PAR form revised to remove hypothetical bounding option as it was redundant. All pages issued.
24 7/10/00 Annual review and self-assessment items. All pages issued.
25 8117/00 PAR diagram revised. All pages issued.
26 2/5/01 Correct PAR diagram. All pages issued.
27 3/30/01 Annual review. Provide new PAR diagram, revise App. F to match PARs.
All pages issued.
28 6/13/02 Annual review. Delete PAR Form which was combined with CECC Dir.
PAR Form in CECC-EPIP-1, re-label Appendixes and references to them, editorial changes. All pages issued.
29 10/09/03
- Annual review. Add instruction for RAM support of TVAN personnel responding to mitigate an emergency who will be located in the 10-mile EPZ. 'Editorial changes. All pages issued.
[
CECC RADIOLOGICAL ;
ASSESSMENT STAFF Page lof 15 PROCEDURE FOR ALERT, SITE CECC EPIP-7 - Revision 29 AREA EMERGENCY, AND GENERAL EMERGENCY CECC RADIOLOGICAL ASSESSMENT STAFF PROCEDURE FOR ALERT. SITE AREA EMERGENCY. AND GENERAL EMERGENCY 1.0 PURPOSE This procedure provides instructions for a consistent, accurate, and timely response by the Radiological Assessment Manager (RAM) and staff in the event of an accident. This procedure identifies the necessary information which is provided to the CECC Director to ensure that prompt, accurate, protective action recommendations for the public can be made by the CECC to appropriate State authorities.
2.0 SCOPE This procedure covers the actions of the RAM and staff during an Alert, Site Area Emergency, and General Emergency.
3.0 REFERENCES
3.1 Radiological Emergency Plan 4.0 ABBREVIATIONS AND DEFINITIONS CECC - Central Emergency Control Center DA - Dose Assessment EA - Environs Assessment EDS - Environmental Data Station ODS - Operations Duty Specialist RAC - Radiological Assessment Coordinator RAM Radiological Assessment Manager REND - Radiological Emergency Notification Directory RMCC - Radiological Monitoring Control Center FSAR - Final Safety Analysis Report TLD - Thermoluminescent dosimeter TSC - Technical Support Center TVAN - Tennessee Valley Authority Nuclear
11
- CECC RADIOLOGICAL ASSESSMENT STAFF Page 2 of 15 PROCEDURE FOR ALERT, SITE CECC EPIP-7 Revision 29 AREA EMERGENCY, AND GENERAL EMERGENCY 5.0 RESPONSIBILITIES I *NOTE!Appendix F will be used to document fitness for duty when'an individual is'called and requested I
to respond to an emergency outside'of normal work hours-and from a non-duty status.;:-
5.1 Radiological Assessment Manager The RAM is notified of Alert or higher classification emergencies through the automated paging system which is activated by the ODS. If this system is not operable, the ODS will call the RAM.
The RAM reports to the CECC. The RAM is responsible for notifying the members of the CECC Radiological Assessment Staff (i.e., Boardwriter, Rad Assessment Coordinator) that are not activated via the paging system.
The RAM is responsible for committing the support efforts of TVAN to the affected plant to deal with radiological aspects of the emergency. If TVAN cannot fulfill the needs of the affected plant, the RAM has the authority to seek help from other organizations within TVA. The RAM shall provide the CECC Director with periodic summaries of information needed for overall radiological accident assessment. He shall also provide the State with periodic updates of
- radiological information. The RAM shall coordinate any radiological protective support for any TVA personnel responding to mitigate the event who must remain in the EPZ (beyond the Site
- Boundary) after State ordered evacuations. Contact via the ODS (ODS refer to Agency
- Command Center Duty Roster). Coordinate with the Environs Assessor.
5.2 Radiological Assessment Coordinator The RAC is responsible for supervising and coordinating the activities of the Radiological Assessment Staff, serves as the interface between the RAM and the staff, and for providing protective action recommendations to the RAM (see Appendix A). He is the primary contact between the Radiological Assessment Staff and the TSC for exchange of technical information (See Appendix E). He is the primary contact/interface between the TSC and the CECC for coordinating the emergency in-plant RADCON response. He obtains additional RADCON resources which may be required. This position is not activated via the automated paging system. The RAM will fulfill the duties of the RAC until the position is staffed.
5.3 Dose Assessment Dose Assessment (DA) is responsible for the dose assessment activities of the CECC and for providing protective action recommendations to the RAM (see Appendix A) in the absence of the RAC. DA should activate additional staff members to fill the dose assessment positions in a timely manner, if warranted. DA shall ensure that communication occurs between the State staff and the DA staff for the exchange of technical information.
DA is responsible for providing a preliminary assessment concerning any new releases as soon as possible to the RAM. As necessary, DA shall ensure that all appropriate notifications are made of event termination.
- Revision
CECC RADIOLOGICAL ASSESSMENT STAFF Page 3 of 15 PROCEDURE FOR ALERT, SITE CECC EPIP-7 -Revision 29 AREA EMERGENCY, AND GENERAL EMERGENCY 5.4 Environs Assessment Environs Assessment (EA) supports the CECC by assessing offsite radiological conditions in close coordination with the State (through the Field Coordinator) and providing environmental monitoring results to the RAM for use in formulating protective action recommendations. EA draws upon available technical expertise to approximate the location, dimensions, and radiological characteristics of the plume.' EA directs the efforts of TVA's emergency radiological monitoring personnel in the collection of field data in a safe and expeditious manner and coordinates analysis of environmental samples with laboratory supervision. EA coordinates the results of environmental assessments with DA. All other TVA radiological monitoring personnel are subordinate to EA and are responsible for following and implementing EA's directives. EA assists the State as requested to clarify technical assessments of offsite radiological conditions.
EA provides technical support as requested for planning and reentry/recovery operations.
5.5 Field Coordinator The TVA Field Coordinator is responsible for directing TVA emergency radiological monitoring personnel in the field in accordance with the instructions of EA. He coordinates the activities of TVA field personnel with the State in an effort to optimize the collection, analyses,-and transfer of field data to State officials and the CECC. He maintains dose records and provides protective action direction for field personnel. He will provide Radiological Control (RADCON) support to field operations utilizing the sampling van teams and their equipment. The duties of the Field Coordinator may be assumed by EA. .
6.0 PROCEDURES/REQUIREMENTS 6.1 Radiological Assessment Manager
- ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~.......
NT:Aceki.i
~~~~~~~~~~~~~~~~.
i Appendixpod B.
NOTE:-A che'cklist i's .provided Appendi : ... ...... ........
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~. .-...,.. ,..,,....... . .. ...-.-,,,... ... ....... ... :....... . ... ..... ..... ;....
6.1.1 Initial Actions 6.1.1.1 Review the emergency condition with'the CECC Director and make a determination as to proper staffing of the Radiological Assessment staff, taking into consideration, (1) Potential or actual need for offsite dose or environmental assessment, and
- (2) Potential or actual need for inplant RADCON support. ;
6.1.1.2 Activate a RAC to coordinate radiological assessment activities, if sufficient personnel are available.
CECC RADIOLOGICAL .
ASSESSMENT STAFF Page 4 of 15 PROCEDURE FOR ALERT, SITE CECC EPIP-7 Revision 29 AREA EMERGENCY, AND GENERAL EMERGENCY I[
6.1.1.3 Ensure that the DA and EA have established appropriate staffing levels to perform radiological monitoring and dose assessment.
6.1.1.4 Ensure that communications have been established with the TSC RADCON Manager or Radiochemistry Supervisor.
6.1.1.5 Determine if technical support personnel are required and, if so, notify the appropriate personnel.
6.1.1.6 Verify that radiological information is being transmitted to the CECC.
6.1.1.7 Verify that the RAC is receiving timely accident assessment reports and this information is promptly distributed.
6.1.2 General Operations 6.1.2.1 The RAM and the Plant Assessment Manager shall discuss all protective action recommendations to ensure that radiological and plant conditions are properly coordinated.
6.1.2.2 Ensure that accident assessment information is provided to the CECC Director on a frequent basis. These assessments shall provide summary information as well as appropriate recommended protective actions for the public.
6.1.2.3 Ensure that radiological information is provided hourly to the State radiological health authority.
6.1.2.4 Assess actual and projected releases to determine if doses result that would exceed any Emergency Action Level (EAL) limits. If EAL limits are exceeded report to the CECC Director for transmittal of the information to the SED.
6.1.2.5 If available NP personnel and equipment are not enough to cope with the emergency, contact the designated representative of other TVA organizations, as necessary, to supply adequate resources to recover from radiological aspects of the accident. Log the organizations called for assistance. Descriptions of emergency services and contacts are available in the REND.
6.1.2.6 Provide technical assistance to discuss the radiological aspects of protective action recommendations with appropriate State contacts as directed by the CECC Director.
6.1.2.7 Should the accident be expected to last for an extended period, the RAM originates a schedule for relief. He also directs his staff to prepare a schedule for their relief to ensure that necessary Radiological Assessment staff is available for the duration of the emergency.
6.1.2.8 Authorize emergency dose limits for offsite personnel.
6.1.2.9 The RAM and staff support the CECC Director as required for carrying out recovery efforts from the accident.
6.1.2.10 Upon termination of the emergency, the RAM and staff shall make themselves available for review of the accident.
6.1.2.11 The RAM checklist is provided in Appendix B for quick reference by the RAM.
- Revision
CECC RADIOLOGICAL l
- ASSESSMENT STAFF Page 5 of 15 PROCEDURE FOR ALERT, SITE CECC EPIP-7 Revision 29 AREA EMERGENCY, AND GENERAL EMERGENCY 6.2 Radiological Assessment Coordinator NOTE: A checklist Is pided in Append C -
6.2.1 Initial Actions 6.2.1.1 Upon arrival at the CECC, become familiar with plant conditions and radiological assessment activities.
6.2.1.2 Brief the RAM when prepared to assume responsibility for coordinating radiological assessment activities.
6.2.1.3 Brief the RAM on the status of dose assessment staffing preparations.
6.2.1.4 Contact the TSC of the affected plant and coordinate receipt of data from the TSC and transmission of CECC data to the TSC.
6.2.2 General Operations 6.2.2.1 Supervise and coordinate the activities of the staff and keep the RAM informed on staff activities.
K> *6.2.2.2 Provide protective action recommendations to the RAM (Appendix I of CECC-EPIP-1) based on dose assessments or field measurements.
6.2.2.3 Ensure that data generated by the Radiological Assessment Staff (Appendix E and the
- affected sectors portion of Appendix I in CECC-EPIP-1) are transmitted to the TSC routinely.
6.2.2.4 Assist, as needed, the staff and the TSC in obtaining special or nonroutine data.
6.2.2.5 Assist in obtaining additional RADCON resources (manpower, equipment, supplies, and vendor services) which may be required.-
6.2.2.6 Serve as the primary contact/interface between the TSC and the CECC for coordinating the emergency in-plant RADCON response.
6.2.2.7 Provide or assist in obtaining such support as needed for continuing operations of the staff.
6.2.2.8 Provide other assistance as directed by the RAM.
6.3 Dose Assessment NOTE: Checklists are provided in CECC EPIP-8.
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~.. .... -.
Dose assessors provide draft protective action recommendations for protection of the public.
- Revision
I CECC RADIOLOGICAL .
ASSESSMENT STAFF Page 6 of 15 PROCEDURE FOR ALERT, SITE CECC EPIP-7 Revision 29 AREA EMERGENCY, AND GENERAL EMERGENCY ._ __ no ___ _.
6.3.1 Initial Actions 6.3.1.1 When warranted, activate or place on standby additional Dose Assessment staff.
6.3.1.2 Upon arrival at the CECC, initial notifications and assessments shall be recorded as described in CECC EPIP-8.
6.3.1.3 Brief the RAC (or RAM, as appropriate) on the status of dose assessment staffing preparations.
6.3.2 General Operations II 6.3.2.1 Perform functions as described in CECC EPIP-8.
6.3.2.2 Ensure that shift changes occur as described in CECC EPIP-8.
6.3.2.3 Provide other assistance as requested by the RAC. --
6.4 Environs Assessment 6.4.1 Initial Actions NOTE':, A checldist, iwhich Includeis turnover fromTSC, is-poidedi in f 6.4.1.1 When conditions warrant, activate the Field Coordinators, and activate or direct a Field Coordinator to activate field monitoring personnel using the REND. The screening van is activated by notifying the laboratory supervisor to dispatch the screening van.
6.4.1.2 Activate the EP Field Support Staff.
6.4.1.3 Establish and maintain an environs assessment log. Record key events, notifications, etc.
Field data need not be recorded in the log.
6.4.1.4 Obtain and record the field data collected by the plant team from the TSC and assume coordination of field operations if appropriate per Appendix D.
6.4.1.5 Brief the RAC (or RAM, as appropriate) on the status of environs assessment staffing preparations.
6.4.1.6 Ensure that field data are transferred to the State until the Field Coordinator is operating at the RMCC.
CECC RADIOLOGICAL . . - ,
ASSESSMENT STAFF Page 7 of 15 PROCEDURE FOR ALERT, SITE CECC EPIP-7 Revision 29 AREA EMERGENCY, AND I GENERAL EMERGENCY--- _-r _,________-__--
6.4.2 General Operations 6.4.2.1 If a senior instrument mechanic is requested for the EDS, notify the TSC that the request has been made.
6.4.2.2 Provide instructions to the Field Coordinator as necessary to maintain field operations. If conditions warrant, EA may assume the responsibilities of the Field Coordinator. If appropriate for the emergency situation, request permission from the RAM for field team personnel to exceed annual dose limits. Keep the Field Coordinator advised on matters related to radioiodine offsite and any need for potassium iodide to be administered to field personnel.
Authorization for emergency doses and KI use should be indicated on the authorization form contained in EPIP-9, Appendix E. The RAM should advise the CECC Director of any dose extension or KI administration and recommend that the SED be informed.
6.4.2.3 Provide emergency classification, plant status, release data, projected doses, and protective
- actions for the public (recommended or implemented) to the Field Coordinator for transfer to the field teams. This action should not interfere with the flow of operational information.
6.4.2.4 Coordinate the transportation of teams as needed. Resources are listed in the REND.
6.4.2.5 Receives field data from Field Coordinator via facsimile or by transcribing from radio
- - - transmissions. The data are recorded on a form similar to CECC-EPIP-9, Appendix 1. An effort shall be made to keep 1-131 concentrations associated with general exposure rate measurements for a given place and time.
6.4.2.6 As necessary, EA shall ensure special local monitoring of groundwater is conducted in the event of a liquid radioactive release (BFN Final Safety Analysis Report requirement).
6.4.2.7 EA shall arrange for relief for EA personnel and the Field Coordinator. Shift turnovers are to be performed.
6.4.2.8 Provide technical assistance and field monitoring as requested by the State during the recovery phase for planning and operations.
6.4.2.9 Provide other assistance as requested by the RAC.
6.5 Field Coordinator Activities 6.5.1 Initial Actions 6.5.1.1 Refer to CECC-EPIP-9 for additional instructions.
CECC RADIOLOGICAL ASSESSMENT STAFF Page 8 ofIs PROCEDURE FOR ALERT, SITE CECC EPIP-7 Revision 29 AREA EMERGENCY, AND GENERAL EMERGENCY I__ __ _
6.5.1.2 Upon arrival at the RMCC, establish radio and telephone communications with the CECC.
Establish and maintain a Field Coordinator's log, including such information as key events and requests.
6.5.1.3 Assume coordination of field staff as directed by EA.
6.5.2 General Operations 6.5.2.1 Coordinate TVA's field operations with State field operations management in an effort to minimize duplication of effort and optimize efficiency in field monitoring. The Field Coordinator will follow the directives of EA, who is responsible for TVA's overall monitoring effort.
6.5.2.2 Define individual team priorities as needed to acquire field data requested by Environs Assessor.
The Field Coordinator may alter field team practices and procedures provided that the changes do not alter protective action requirements, or techniques and methods of sampling, sample analysis, or direct surveys.
6.5.2.3 Monitor and maintain individual exposures and provide instructions as necessary to keep below 10 CFR 20 limits. No team member is permitted to exceed 5 rem TEDE without emergency dose authorization of the RAM. Exceeding 10 rem TEDE, and greater than 25 rem TEDE, both require additional authorizations at each level by the RAM. Refer to CECC EPIP-9 for additional instructions on implementation of emergency dose levels.
6.5.2.4 Record all field data per CECC-EPIP-9. Provide the appropriate copy to the State and the other to the facsimile operator for transmission.
6.5.2.5 Arrange for maintenance of field operations as needed, including resupply of vans, relief personnel, replacement vehicles and equipment, food for teams, etc. Brief the relief teams at the RMCC and provide them with TLDs and KI. Coordinate these activities with EA.
6.5.2.6 Respond to other requests from EA and coordinate with EA TVA's response to requests received from the State.
1 1 CECC RADIOLOGICAL ASSESSMENT STAFF I
PROCEDURE FOR ALERT, SITE AREA EMERGENCY, AND GENERAL EMERGENCY I APPENDIX A PROTECTIVE ACTION RECOMMENDATIONS Note 1: If conditions are unknown utilizing the flowchart, then answer NO.
General Em ergenc) CONTII %4UEASSESSMENT Declared
- Modify p rotective actions based
' on availa ble plant and field monitori ig information.
\* Locate ai id evaluate localized hot spots. -
6
/ ~or beyond 5 miles is the Projected NO or Measured Dose Greater than PAG I Table 1 Limits RECOMMENDATION 1 RECOMMENDATION 2 EVACUATE 2 miles radius EVACUATE 2 mile radius and 10 miles downwind and 5 miles downwind AND AND AL SHELTER remainder of SHELTER remainder of 10 mile EPZ 10 mile EPZ I
TABLE I Protective Action Guides TYPE LIMIT Measured 3.9E-6 microCi/cc of Iodine 131 or 1 REM/hr External Dose Projected 1 REM TEDE or 5 REM Thyroid CDE
CECC RADIOLOGICAL ASSESSMENT STAFF
- Page 10 of 15 PROCEDURE FOR ALERT, SITE CECC EPIP-7 Revision 29 AREA EMERGENCY, AND i GENERAL EMERGENCY _
APPENDIX B Page 1 of I RADIOLOGICAL ASSESSMENT MANAGER'S CHECKLIST INITIAL ACTIONS Date:
Time/Initials Notify the CECC Director of Radiological Assessment Staff activation status. Activate a RAC and a Boardwriter.
Assess the need for additional technical support and take appropriate actions.
Establish communications with the TSC RADCON Supervisor or Radiochemistry Supervisor to determine radiological status of the plant and to determine if any releases are ongoing or have occurred.
I ., Establish contact with the state.
Verify that radiological data are being transmitted to the CECC.
Verify that the Radiological Assessment Coordinator is receiving accident'assessment reports and that the information is being distributed.
Obtain RADCON Technical Advisors as necessary.
Evaluate preparations for collection of environmental TLD's.
GENERAL OPERATIONS
- 1. Log key events and major actions taken.
- 2. Coordinate protective action recommendations with the Plant Assessment Manager.
- 3. Monitor actual or projected doses for EAL trigger points and notify the CECC Director if a EAL condition is met.
- 4. Provide accident assessment information to the CECC Director and the State Communicator at least hourly.
- 5. Arrange for additional RADCON support resources with other TVA organizations.' Log all contacts.
- 6. Periodically provide for technical discussions with the State as needed.
- 7. Remind the site that additional technical support may be available through the CECC. Coordinate with the Plant Assessment Manager and the Site Emergency Director.
- 8. Ensure that Radiological Assessment Staff relief personnel are scheduled and notified. Coordinate transportation arrangements as needed.
- 9. Ensure that radiological data posted on CECC Radiological status boards is accurate and up-to-date.
- 10. Coordinate any radiological protective support for any TVA personnel responding to mitigate the
- event who must remain in the EPZ (beyond the Site Boundary) after State ordered evacuations.
- Contact via the ODS (ODS refer to the Agency Command Center Duty Roster). Coordinate with the
- Environs Assessor.
- Revision
CECC RADIOLOGICAL ASSESSMENT STAFF Page 11 of 15 PROCEDURE FOR ALERT, SITE CECC EPIP-7 Revision 29 AREA EMERGENCY, AND GENERAL EMERGENCY I___
APPENDIX C Page 1 of 1 RADIOLOGICAL ASSESSMENT COORDINATOR'S CHECKLIST INITIAL ACTIONS Date:
Time/Initials I On arrival, become familiar with emergency status, plant conditions, and CECC activities.
I Inform the Radiological Assessment Manager when prepared to assume responsibility for coordinating staff operations.
I Contact the TSC and coordinate receipt of data from the plant and transmissions to the plant from the CECC (Appendix E).
GENERAL OPERATIONS
- 1. Log key events and major actions taken.
- 2. Supervise and coordinate the activities of the Radiological Assessment Staff.
- 3. Provide protective action recommendations to the RAM based on dose assessments or field measurements.
- 4. Periodically advise the Radiological Assessment Manager of staff activities.
- 5. Ensure that data generated by the Radiological Assessment Staff are transmitted to the TSC routinely.
- 6. If needed, assist the staff and/or TSC in obtaining special or nonroutine data.
- 7. As directed, assist in obtaining additional resources (manpower, equipment, supplies, vendor services).
[ CECC RADIOLOGICAL ASSESSMENT STAFF Page 2 of 15 PROCEDURE FOR ALERT, SITE- CECC EPIP-7 - Revision 29 AREA EMERGENCY, AND I.
L GENERAL EMERGENCY _ _
APPENDIX D Page 1 of 2 ENVIRONS ASSESSMENT INITIAL CHECKLIST INITIAL ACTIONS Date:
Time/initials I If warranted, activate the Field Coordinator, and activate or direct the Field Coordinator to activate offsite field monitoring personnel or screening van using the REND (teams must be dispatched for Site Area Emergency or higher).._
I Activate the EP Field Support Staff (see REND, under the tab, Field Staff).
I Establish contact with the TSC and notify if-a.Senior Instrument Mechanic (SIM) has been activated for EDS from the EP Field Support Staff.
I.-. -Brief the Radiological Assesi-e-nfiCoordinat6r and Radiological Assessment Managerion the status as activities. __;
Test radio communications to determine the repeater to be used and set correct time on radio console. - -
FIELD TEAM TURNOVER FROM SITE
/ Determine location and status of all field teams from the site.
/ Identify all field team members.
I Request the site to notify the teams when command and control has been assumed by the CECC.
I Assume control of all Field Staff.
I Verify that field data are being transmitted to the State until RMCC is staffed and operating.
I As appropriate, transfer coordination of field activities to the Field Coordinator at the RMCC.
Notify all field teams of any transfer of command and control.
l CECC RADIOLOGICAL ASSESSMENT STAFF Page 13 of 15 PROCEDURE FOR ALERT, SITE CECC EPIP-7 Revision 29 AREA EMERGENCY, AND GENERAL EMERGENCY I__
APPENDIX D Page 2 of 2 ENVIRONS ASSESSMENT INITIAL CHECKLIST GENERAL OPERATIONS
- 1. Log notifications, instructions received and given, emergency classifications, and key events in an environs assessment log.
- 2. Remain aware of offsite conditions in order to provide decisions regarding KI for teams.
- 3. Request permission for individual field team members to exceed annual dose limits, if warranted for continued operations.
- 4. Periodically provide field teams with emergency classification, plant status, release data, projected doses, meteorological data, and/or protective action recommendations for the public, provided this does not interfere with field operations or communications.
- 5. Ensure CECC is informed of data received from RMCC or transcribed from radio on
- Appendix G of CECC-EPIP-9. Keep related exposure rates and airborne concentrations together on the form.
- 6. As necessary, ensure that in the event of any unusual release of radioactive liquid which could contaminate groundwater at the site, special local monitoring is conducted to ensure that the use of local groundwater will not result in undue hazards to any person (BFN FSAR requirement).
- 7. When directed by the Radiological Assessment Manager, arrange for relief personnel for Environs Assessment, and the Field Coordinator.
- 8. Coordinate any radiological protective support for any TVA personnel responding to
- mitigate the event who must remain in the EPZ (beyond the Site Boundary) after State
- ordered evacuations. Contact via the ODS (ODS refer to the Agency Command Center
- Duty Roster).
- Revision I
CECC RADIOLOGICAL ASSESSMENT STAFF Page 14 of 15 PROCEDURE FOR ALERT, SITE CECC EPIP-7 Revision 29 AREA EMERGENCY, AND GENERAL EMERGENCY ___ _ I __
APPENDIX E Page 1 of I TSC INFORMATION FORM Approved:
Date/Time:
I. DOSE ASSESSMENT INFORMATION As dose assessments are performed, they are automatically transmitted to TSC. At least hourly, verify last dose assessment was received.
Time of Last Dose Code Run: Date: Time II. PLUME PLOTS Whenever a dose assessment is performed, the plume position plot is also transmitted to site by telecopy. This is not automatically performed. At least hourly, verify last plot was received.
Time of Last Plume Plot: Date: Time III. FIELD DATA As Field Data is received, transmit hard copy to TSC. At least hourly, verify data is being received.
Time of Last Field Data: Date: Time IV. METEOROLOGICAL DATA (Including Met Forecasts)
Met Data is automatically transmitted to the TSC. At least hourly, verify data is being received.
Time of last Met Data: Date: Time Time of last Met Forecast: Date: Time V. TVA RECOMMENDED PROTECTIVE ACTIONS When TVA makes a recommendation, transmit to the TSC. At least hourly, verify TSC is knowledgeable of last recommended protective actions.
Protective Action Recommendation of: Date: Time
Description:
VI. PROTECTIVE ACTIONS TAKEN BY STATE When State takes a protective action, transmit to the TSC. At least hourly, verify TSC is knowledgeable of last protective actions taken.
Protective Actions Taken as of: Date: Time
Description:
CECC RADIOLOGICAL ASSESSMENT STAFF Page 15 of 15 PROCEDURE FOR ALERT, SITE CECC EPIP-7 Revision 29 AREA EMERGENCY, AND GENERAL EMERGENCY __ I a APPENDIX F Page 1 of 1 FITNESS FOR DUTY PROGRAM ADMINISTRATION TVA NUCLEAR CALL-IN SHEET Person Calling: .- Date:
Time Time Alcohol 5 Hrs. Fit for Duty Official -
Name Called Needed to Prior to Report Duty Comments Report (YIN) (YIN)
CECC EPIP Coversheet Title CECC EPIP-8 Tennessee REV. 27 Valley Authority CENTRAL EMERGENCY DOSE ASSESSMENT STAFF ACTIVITIES
.CONTROL CENTER DURING NUCLEAR PLANT EMERGENCY PLAN RADIOLOGICAL EMERGENCIES IMPLEMENTING Effective Date:
PROCEDURES ._._._.__ __ _ __
WRITTEN BY: A a PREVIEWED BY:
Signature Signature Date PLAN EFFECTIVENESS DETERMINATION: F >2zZg:
Signature Date CONCURRENCES Concurrence Signature Date 103 wnafr, EP Progra Pnning and Implementation -
023 Manageg,,Emergency Prepare jness .I: /0, ..
0 Manager, Radiological an Chemistry Services S 2_ - , . ., ~ ~ ~ -11C~o APPROVAL
CECC-EPIP-8 DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR PLANT RADIOLOGICAL EMERGENCIES
- _ REVISION LOG..__
Rev. No. Date Revised Paaes 0 3/22/88 All (Changed from IPD to EPIP) 1 11/18/88 2-7, Apps. A, B, C, & D 2 12/12/88 Appendix A 3 4/26/89 All 4 9/19/89 App. C 5 10/26/89 All 6 5/21/91 App. B, pgs. 1-4; Appendix C, pgs. 1-2; App. D, pg. 1 7 10/17/91 App. B, pgs. 2-4; App. C, pg. 1.
8 05/13/93 1-4: App. A; App. B. pg. 1, 3, & 4; and App. G: App. C deleted. All pages issued.
9 11/22/93 Pg. 4; App. B. pgs. 1&4; App. D changed to App. C; App. E z
changed to App. D; App. F changed to App. E; and App. G changed to App. F.
10 11/30/93 1, 3, 4; App. A, pg. 1; App. B. pgs. 1-2; App. C, pg. 1-5; App. D, pg. 1; App. E, pg. 1; App. F, pg. 1; App. G, pgs. 1-6.
11 06/24/94 App. B, pg. 1; App. D, pgs. 2-5; App. F; App. J added. All pages issued.
12 6/27/95 Pg. 1; App. A; App. B, p.3; App. C, p. 5; App. D, p. 2; App. G.
pgs. 4 and 6 13 1/17/96 App. B, pg. 2, editorial changes, add table for BFN stack release; App. C, pgs. 1 & 3, Add new criteria for Type I and Type II releases; App. D, pgs. 2-5, add nonogram alignment checks 14 5/30/96 Pg. 3, App. A, App. B, App. C, App. D, App. F, App. G; annual review; ground level release tables and nomograms made generic to all three sites; all pages issued.
15 10/30/96 Pg. 3, App. B, and App. D; Add reference to App. I of CECC EPIP-7, remove deleted pages, make correction to Nomogram Alignment Check Table.
16 5/30/97 Editorial changes, update manual dose assessment methodology, update preliminary assessment table, revise river miles on tables in Appendix G, annual review. All pages issued.
17 8/8/97 Revise default river flow rate for BFN, revise responsibilities of Norris Lab, add water intake tables. All pages issued.
CECC-EPIP-8 DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR PLANT RADIOLOGICAL EMERGENCIES REVISION LOG (Continued)
Rev. No. Date Revised Pages 6/9/98 18 Annual review. Organization title changes. In Appendix D clarify RR Type I and Type II formulas. Remove Tennessee River miles from tables. All pages issued.
19 10127/98 Correct reference to CECC EPIP-1 Appendix on Appendix J.
20 5/20/99 Annual review. Editorial and clarification changes, revise public water use tables. All pages issued.
- 21 9/8/00 Annual review. Editorial changes. All pages issued.
22 3/30/01 Revised to incorporate the new source term methodology in the RED suite of codes revision Revised all pages to reflect human factor improvements in REP codes and manual Included changes due to code revision necessary for H-3 23 11/22/02 proiect.
24 3/31/03 Added sections to Appendix F to provide instructions for manual method of calculating TEDE and thyroid CDE doses at Site Boundary (0.62 miles). All pages issued.
25 6/16/03 Make corrections to Appendix F. All pages issued.
26 07/01/03 Revision consistency in accordance with CHPER 03-000257-000.
Revise location indicator in step C.4 on page 18. Correct the location indicator, in step 2.b on page 19. Correct spelling of Circle on page 22.
Minor format alignment changes. All pages issued.
27 10/09/03 Add clarification note for PAG values for low wind speed or low release rates, current WBN default river flow value. All pages issued.
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 1 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES Table of Contents 1.0 PURPOSE ......................... 2 2.0 SCOPE ........................ 2 3.0 STAFFING 3.1 Activation and Notification .2 3.2 Shift Change .2 3.3 Termination .2 4.0 DOSE ASSESSOR INTERFACES 4.1 Radiological Assessment Manager/ Coordinator ......................................... 3 4.2 Meteorologist ......................................... 3 4.3 Environs Assessor / Field Coordinator .................. ...................... 3 4.4 Core Damage Assessor ........................................ 4 4;
4.5 Technical Support Center ......................................... 4 4.6 River Operations ......................................... 4 4.7 State (Radiological) ......................................... 4 5.0 PERFORMING DOSE ASSESSEMENTS 5.1 Data Verification .......................................... 4 5.2 Preliminary Assessments .......................................... 4 5.3 Criteria for Significant Change in Conditions .......................................... 5 5.4 FRED or RED Assessments - Collection of Data ......................................... 5 5.5 Preparing a Protective Action Recommendation (PAR) ............................... 5 5.6 Changes in Conditions for a PAR ......................................... 5 5.7 BRED Assessment - Back Calculation of Release Rate from Field Data ..... 5 5.8 Comparison of Measured Field Data to Dose Projections ............................ 6 5.9 WATERDOSE Assessments ...................... ................................ 6 5.10 Manual Methodologies for Dose Assessments ............................................. 6
6.0 REFERENCES
............... 6 7.0 ABBREVIATIONS ............. 6 Appendixes A. Dose Assessor Initial Reporting Checklist ................................................. 7 B. Shift Change and Termination Checklist ................................................. 8 C. FRED / RED Data Inputs ................................................. 9 D. FRED / RED Assessment of Airborne Releases ........................................ 11 E. BRED Assessment of Airborne Release Field Data ................................... 13 F. Manual Methodology for Assessing Airborne Releases ............................. 15 G. Comparison of Measured Field Data to Dose Projection Models ............... 23 H WATER DOSE Data Inputs ................................................ 24 I. Manual Methodology for Assessing Liquid Releases to the River .............. 25 J. Public and Industrial Surface Water Supplies ............................................ 30
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR PLANT RADIOLOGICAL EMERGENCIES 1.0 PURPOSE To guide Dose Assessment in obtaining necessary information, calculating dose rates and doses, and communicating assessment results used in responding to radiological emergencies at nuclear power plants.
2.0 SCOPE This procedure applies to activities of Dose Assessment in actual and hypothetical radiological emergency situations. While the activities of the Dose Assessment staff are expected to follow this procedure, it is expected that circumstances may arise during an event which will void portions of this procedure. Therefore, this procedure is a guide for the operation of the Dose Assessment staff under the ideal conditions.
3.0 STAFFING 3.1 Activation and Notification The Initial notification of an event comes from the Operations Duty Specialist via the Emergency Paging System (EPS) or manual callout. Additional Dose Assessor support is contacted in accordance with Appendix A. The Dose Assessor isa position required for the CECC to make Protective Action Recommendations and to meet minimum staffing levels.
Upon reporting to the CECC, perform initial activities in accordance with the checklist provided as Appendix A.
3.2 Shift Change Shift change notification and transition and transfer of responsibilities should be conducted in accordance with the Dose Assessment Shift Change and Termination Checklist (Appendix B).
3.3 Termination Termination of an event should include the following actions and follow the Dose Assessment Shift Change and Event Termination Checklist (Appendix B).
'I DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 3 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES 4.0 DOSE ASSESSOR INTERFACES 4.1 Radiological Assessment Manager ) Coordinator (RAMIRAC)
The Dose Assessor should interface directly with the Radiological Assessment Coordinator (RAC). In the absence of the RAC, communication is provided directly to the RAM. Requests for any special-case assessments should come to Dose Assessment through the RAC/RAM or be cleared by the RAC/RAM prior to their performance.
Dose Assessment is responsible for performing the offsite dose assessment activities of the CECC in order to determine Protective Action Recommendations using the appropriate appendix in CECC EPIP-1. Dose assessment results are also evaluated against criteria for declaration of Emergency Classification levels, and evaluations are communicated to the RAM/RAC.
Dose Assessment should provide results of all dose assessments and plume plots from FRED to the RAC/RAM, who will approve them and distribute them to CECC staffs. Initial dose assessments (those made at the start of an event or when the conditions have changed significantly as defined in this procedure) will receive the approval of the RAC/RAM and then are transmitted to the TSC and the State. Under most other conditions, the results are directly transmitted to the TSC and the State on the State Update form via computer spooling. However, if the computer spooling is unavailable, then the Dose Assessor shall prepare a State Update form manually as defined in EPIP-1. CECC Clerical staff have instructions for distribution.
Dose Assessment should provide to the RAC/RAM copies of plume plots from RED for ongoing releases or plots of estimated centerline location (if there is not a known release but potential exists for one to occur). This information should be transmitted by the RAC/RAM to the CECC, TSC, and State. Dose assessment will also support post event recovery efforts.
4.2 Meteorologist (MET)
The CECC Meteorologist is responsible for providing to Dose Assessment the real time and forecast meteorological data and associated advice on atmospheric dispersion and transport.
If a meteorologist isnot initially available for response to the CECC, support can be obtained from Muscle Shoals. Telephone and pager numbers for the Muscle Shoals response personnel are available in the REND.
Meteorological data is provided to the CECC by computer inputs and by the CECC meteorologist. In the event of a monitored airborne release, the 15-minute meteorological data is automatically accessed by the RED and FRED codes. This data should be verified against the distributed meteorological data or by the meteorologist. The meteorologist is also available to convert flow rates to exit velocities for use in the codes. The meteorologists will also provide forecast information for use in the FRED code.
4.3 Environs Assessor/Field Coordinator Dose Assessors provide plume plots to the CECC Environs Assessor and to the Field Coordinator at the Radiological Monitoring Control Center (RMCC) via the RAC. These plume plots are used to assist with decisions on field team deployments. Real time plume plots from the RED code are to be distributed to the EA/FC and the State for that purpose.
Field data isalso shared to assist with comparison of dose projections with field measurements. This comparison can assist with evaluations if field teams are at maximum centerline locations, or if reported plant release rates coincide with actual field measurements.
In the event of an unmonitored release from a site, field team data can be used in the BRED code to assist with determination of a release rate.
4.4 Core Damage Assessors The CECC Core Damage group (in Plant Assessment) is responsible for supplying Dose Assessment with projections of potential, anticipated, and/or worst-case release rates and pathways.
4.5 Technical Support Center (TSC)
The TSC is a source of information for radioactivity release rates, pathways, flow rates, and information on plant status and prognosis. The primary point of contact is TSC Chemistry.
Release information is also available via the Integrated Computer System (ISC) using the CECC computers.
4.6 River Operations River Operations may assist in providing Dose Assessment information on water dispersion characteristics for releases to the river. This information may be used in running the WATERDOSE code, or for use of the manual methodology if the dose code is unavailable.
4.7 State (Radiological)
Dose Assessment shall ensure that communication with the State Dose Assessment Team is established and maintained. The State should be given hourly updates, as a minimum. These updates should include discussions of all technical information relative to dose assessments being made (incoming release rates, assumptions used, problems with information flow). The State should also be contacted if the conditions have changed significantly as defined in this procedure. DO NOT discuss protective action recommendations with the State.
5.0 PERFORMING DOSE ASSESSMENTS 5.1
- Data Verification All dose assessment results (computer generated or hand calculated) involving data input will be verified by a second party verifier. The verifier may be a Dose Assessor or the RAM/RAC. The verifier will verify the accuracy and appropriateness of data input and reasonableness of the results. Both preparer and verifierwill initial and date the results page of the assessment (e.g.,
State Update Form for FRED assessments). ;
5.2 Preliminary Assessments Dose Assessors should provide results of all preliminary assessments to the RAC/RAM.
Preliminary Assessments are provided as part of a FRED run. Preliminary assessments will be performed at the start of an event or when the conditions have changed significantly-as defined in this procedure.
I DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 5 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES 5.3 Criteria for a Significant Change in Conditions Criteria for a significant change which will require a new dose assessment run are:
- the release type / path has changed,
- the release rates have changed by a factor of 10
- the stability class has changed by 2 classes,
- or the wind speed has changed by a factor of 2.
5.4 FRED or RED Assessments - Collection of Data Gather information as provided on Appendix C. Sources of information may include the Technical Support Center (Chemistry), ICS, CECC Meteorologist or CECC Core Damage Assessors. Refer to Appendix C for instructions on running the dose codes.
5.5 Preparing a Protective Action Recommendation (PAR)
TVA must satisfy regulatory requirements to provide State Authorities a PAR within 15 minutes of the declaration of a General Emergency. Therefore, Dose Assessors should anticipate and initiate development of a PAR to allow ample time for review, approval and transmittal to State Authorities.
A Protective Action Recommendation for airborne releases is determined based upon results of a FRED run. If the FRED program is unavailable, then the manual methodology should be utilized as provided in this procedure. A PAR form contained in CECC EPIP-1 should be completed, with attention to identification of affected sectors as page 2 of that document..
Dose Assessment should provide technical guidance to the RAC/RAM in the preparation of protective action recommendations based on dose assessments. The RAC is responsible for written preparation of recommendations to the RAM.
5.6 Changes in Conditions for a PAR Changes to a PAR must be communicated to the State by the CECC Director within 15 minutes of determination. Criteria for a changes which will require evaluation a new PAR are:
- the release type I path has changed,
- the release rates have changed by a factor of 10
- the stability class has changed by 2 classes,
- or the wind speed has changed by a factor of 2.
- a wind direction change resulting in a change of an affected sector 5.7 BRED Assessment - Back Calculation of Release Rate from Measured Field Data Measured field data (consisting of dose rates in mrem/hr and 1-131/H-3 concentrations) are assessed in several ways. If there is a monitored release ongoing, the field data are compared to the results of the most applicable data produced by the RED or FRED computer models.
However, in cases where the release is unknown or questionable, the field data are then input into the BRED computer model to determine the applicable release rates. These calculated release rates are then input into the RED/FRED codes, as applicable, which can be used to perform dose assessments and any applicable Protective Action Recommendation (PAR).
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR PLANT RADIOLOGICAL EMERGENCIES.
CECC EPIP-8 Page 6 of 32 Revision 27 I 5.8 Comparison of Measured Field Data to Dose Projections Field data is compared with dose projections to assist with evaluations if field teams are at maximum centerline locations, or if reported plant release rates coincide with actual field measurements. Appendix G is provided as a reference to perform comparisons.
5.9 WATERDOSE Assessments Liquid releases to the River are assessed using the WATER DOSE code as provided on Appendix H. If the WATER DOSE code is unavailable, a manual methodology is provided as Appendix I.
5.10 Manual Methodologies for Dose Assessments In the event that the FRED, RED or WATERDOSE computer codes are unavailable, instructions are provided in the Appendixes of this procedure for manual calculation methods. In consideration that the computer programs also normally spool data outputs directly to the State, the Dose Assessor will need to ensure that the applicable pages of the State Update Form, contained in CECC EPIP-1, are also manually completed and transmitted accordingly.
6.0 REFERENCES
FRED User's Manual RED/FRED/BRED Documentation FRED User's Manual WATERDOSE User's Manual BRED User's Manual Model Comparison REP CODE Revision 2, Specifications and Documentation, August 2002, L61 020814 800 7.0 ABBREVIATIONS AND DEFINITIONS CECC - Central Emergency Control Center CTM - Containment building SGTR (above) - Steam Generator Tube Rupture above the steam generator water level SGTR (below) - Steam Generator Tube Rupture below the steam generator water level MSLB - Main Steam Line Break TSC - Technical Support Center EPS - Emergency Paging System RED - Radiological Emergency Dose Code RO - River Operations FRED - Forecast Radiological Emergency Dose Code BRED - Back-calculation Radiological Emergency Dose Code TRM - Tennessee River Mile ICS - Integrated Computer System WGDT - Waste Gas Decay Tank (as in rupture event)
RAM/RAC -Radiological Assessment Manager or Radiological Assessment Coordinator
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 7 of 32 PLANT RADIOLOGICAL C ECC EPIP-8 Revision 27 EMERGENCIES APPENDIX A Dose Assessor Initial Reporting Checklist (steps do not need to be performed in sequential order)
- 2. START logkeeping of key activities and notifications in the position logbook.
- 3. ENSURE that the following support staffs are notified and/or staffed. Refer to the REND call out list for contact information.
- Second Dose Assessor, if needed.
- Muscle Shoals Meteorologist (if serving as CECC pager duty person).
- 4. CONFIRM position notebook procedures match revision levels in controlled copies.
- 5. ESTABLISH contact with the TSC Chemistry (programmed on phone and in REND section B). Ascertain if a release has been, or is occurring. IF YES, INITIATE a dose assessment as noted below.
- 6. Perform preliminary assessments and dose projections.
- 7. ESTABLISH initial contact with the State Radiological Dose Assessment staff (programmed on phone and in REND section B).
- 8. OBTAIN a briefing from the RAC/RAM and INFORM the RAC/RAM when the activities above are completed. Report/request if a radiological release has been, or is occurring.
NOTES: COMPARE dose assessment results against the levels for the declared REP class and advise the RAC/RAM to advise the TSC if an upgrade is indicated.
For Preliminary Assessments and Dose Projections use the FRED Code (Appendix C and D).
For Plume Plots to track actual releases in current time, use the RED Code (Appendix C and D).
When the plant release rate is unmonitored or questionable, use the BRED code to arrive at a plant release rate based upon Field Team data. (Appendix E).
For releases to the River, use the WATERDOSE Code (Appendix H) ff computer problems are encountered, immediately contact Computer Support.
If the FRED computer code is inoperative, use the MANUAL METHODOLOGY to assess airborne radioactivity releases (Appendix F).
If the WATERDOSE computer code is inoperative, use the MANUAL METHODOLOGY to assess liquid releases to the river (Appendix I and J).
I
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 8 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES APPENDIX B Dose Assessor Shift Chance and Termination Checklist
- 1. The following should be discussed between staff for Shift Turnover.
- Current release data and projections.
- Current met data and projections.
- Current plant status and projections.
- Current environs data and projections.
- Pertinent historical data/plant conditions
- Status of any Protective Action Recommendations made and the rationale for these
- Status of any (incoming or outgoing) unfulfilled requests for information.
a Dose methodologies being used.
Identification of problems in response capability.
- Time for next periodic update to the State
- Time for next periodic update of the RED plume plot
- Identify individuals external to CECC who were activated or placed on standby
- 2. Transfer of Shift Change Responsibility
- Obtain approval from the RAC for the transfer of responsibility
- The on duty Dose Assessment Staff should remain available or at least respond in case transfer problems are identified
- 3. Termination
- Log off CECC computer system/tum off plotters.
- Notify all on-call staff of event termination, such as:
- Meteorologist (if staffed in Muscle Shoals)
- Additional Dose Assessment staff on standby
- River Operations
- Collect and turn in all records to the EP staff
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 9 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES Appendix C Pagel of 2 FRED RED FRED / RED Data Inputs Data Inputs NOTE: The source for this information may be the site Technical Support Center or from ICS.
- 2. Meteorological data will be: E ACTUAL or El EXERCISE (confirm with drill controller).
- 3. Release start time: El Eastern El Central.
- 4. Elapsed Time from reactor shutdown to start of release: - (hours) (enter 0 if Rx under power)
- 5. Release Vent Type (this is used by the code to calculate effective plume height):
SQNIWBN _.. . BFN.
El Shield Bldg E Stack El Near ground El Radwaste Zone (of Rx Bldg)
El Refueling Bldg zone (of Rx Bldg)
E Reactor Bldg zone (of Rx Bldg)
E Turbine Bldg zone (of Rx Bldg)
El Near ground
- 6. Effluent flow rate (exit speed) (if measured and available): cfm.
NOTE: Consult with the meteorologist as to whether the default Exit Velocity based on this flow rate should be over-ridden. Code defaults can be used for conservatism or if flow datalis unavailable.
- 7. Release Type:
ElRCS [:Core Damage ElUserSpecified ElGap (default) ElFuel Melt (for noble gas and Tritium only)
NOTE: Initially, a GAP Release Type should be used unless otherwise specified by the Core Damage Assessment team. Alternately, particulate-to-1131 field team air concentration data can be used as follows:
Field Team Data Particulate microCi/cc = Ratio Field Team Data Iodine'3' microCi/cc Ratio = Release Type: Gap Core Damage Fuel Melt 2 0.18 2 2.0 2 3.5
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 10 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES Appendix C Page 2 of 2 FRED RED FRED I RED Data Inputs Data Inputs
- 8. Release Path:
SQNIWBN El Filtered via containment (CTM)
El Unfiltered via containment (CTM)
E SGTR with rupture located BELOW water level E Steam Generator Tube Rupture with rupture located ABOVE water level El Turbine Bldg El Reactor Bldg El Auxiliary Bldg.
BFN El Stack (filtered) El Turbine Bldg, Reactor Bldg E] Stack (unfiltered) El Main Steam Line Break (MSLB)
- 9. Release rates:
Basis for rates: O Monitor reading E Plant personnel E BRED estimate Ci/s Noble Gas gCi/s 1-131 (pre-treatment value only, if available) gCi/s Total Particulate (pre-treatment value only, if available) pCi/s H-3 (if applicable see note below)
NOTE:
. For a TPBAR handling accident, the H-3 release can be estimated as:
H-3 Release = uCi/cc H-3 x cfm x 28320 cc/cf Rate 60 min/sec
{H-3 release (gCi/s) = #gCi/cc H-3 x building exhaust flow rate (cfm) x 28320 cc/cf x 1/60 min/s }
- For a WGDT Rupture accident, the default H-3 release is 2500 Ci over one hr or 6.94E+05 gCi/s for 1 hr
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 11 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES Appendix D Page I of2 FRED RED FRED or RED Assessment of Airborne Releases Code Runs
- 1. DOUBLE CLICK on the "CECC VAX" icon if the VAX User Window is not displayed on computer screen.
Depress [RETURN] until prompted for the user name.
- 3. FOLLOWcomputer prompts to begin or exit program.
NOTE: TYPE CTRL Z any time to exit or re-start program.
When executing the RED code you will be asked whether this is a "new run.' ANSWER *Y"and ENTER
'NEW RUN," unless you desire to modify or append to a current run.
- 4. INPUT data as collected on Appendix C.
For a user-specified release (for noble gas and/or tritium releases only), ENTER the nuclide number below (as applicable) and the associated nuclide-specific release rates.
Nuclide # Nuclide - Nuclide # ' Nuclide 1 H-3 '28 XE-131 M 6 KR-85 29 XE-133 7 KR-85M 30 XE-133M 8 KR-87 31 XE-135 9 KR-88 32 XE-138
- 5. CONFIRM whether the release rate data is correct, (Y/N). Edit as necessary.
6 CONFIRM whether the calculated release rate data is correct, (Y/N). Edit as necessary.
- 7. RUN the code for the expected event duration:
0 For FRED Preliminary Assessments use 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; For FRED Dose Projections use a 4-hour duration unless known otherwise.
For RED assessments run once per 15-min during ongoing releases.
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 12 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES Appendix D Page 2 of 2 FRED RED FRED or RED Assessment of Airborne Releases Code Runs
- 8. OBTAIN code outputs by as follows:
- a. ANSWER 'Y" to the prompt to *Print dose charts or plume plots.'
- b. SELECT State Update Form (SUF) and plume plot as minimum outputs
- c. SELECT scale to be used:
I1] for 10 mile, 12] for 50 mile. [3] to exit code or go to next time segment)
- d. For plume plot, CLICK print button at bottom of screen to perform a screen print of plot. Be sure that the pop-up dialog box has the Graphic Image set to 'Swap Black/White."
- e. For Preliminary Assessments, OBTAIN the Protective Action Guide (PAG) release rates from the FRED output and the actuallprojected release rates from the State Update Form.
"NOTE If the PAG values calculated by FRED are zero (due to either low wind speed
- or negligible release rate) perform the PAG release rate calculations manually
- using Appendix F sections A and B.
- f. The Preparer and Verifier shall INITIAL and DATE the results.
- 9. COMPARE the declared REP class with that indicated in the FRED output. Notify the RAC/RAM (to advise the TSC) of the need for REP class changes based on radiological conditions.
- 10. GIVE PAG and actual/projected release rates to the Board Writer.
- 11. GIVE the FRED results (SUF, PAG Release Rates, plume plot, and REP class information) to the RAC for distribution. (The SUF may be sent directly through the computer to the State and the TSC.)
- 12. At the request of the RAC/RAM, PREPARE a PAR using the CECC Protective Action Logic Diagram and the PAR form found in EPIP-7 and give to the RAM with the results of the FRED run.
- 13. REQUEST that the RAC distribute the SUF, and any plume plots to all standard distribution locations, via CECC Clerical instructions.
- 14. Preferably once every 15-min (at least once per hour) during an actual release,
- a. ENTER the release data into the RED code for use in tracking the plume
- b. COMPARE the estimated impacts to measured field data.
- c. GIVE the results (plume plot only) to the RAC for distribution to the CECC, the State, and the TSC.
- 15. TYPE CTRL Z any time to exit or re-start program.
- Revision
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 13 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES Appendix E Page 1 of2 BRED BRED Evaluation of Airborne Field Data Code Run
- 1. Log on to BRED. DOUBLE CLICK on the "CECC VAX' icon. PRESS return until prompted for usemame.
ENTER usemame (BRED) and password (CECC).
- 2. OBTAIN the following field data from Environs Assessment.
NOTE: As a minimum, only need one of the following measurements:
[
Dose Rate OR lodine-131 OR Tritium (H-3)
- Distance (miles) :--'Direction (sector) :: l-' Time Taken - l Dose Rate mremlhr.(1 meterwic]
. . . . . . .~~~~~~~.
l: : -~~:::- odine-131:'OCi/cc~ :..-.-
..... .... .. ... ... .. .". .H:Concentration ' Ci/cc: ... .......... l
- 3. Elapsed Time from reactor shutdown to time of field measurement: (hours) (enters if Rx under power)
- 4. DETERMINE the Release Path:
SQN/WBN D Filtered via containment (CTM)
O Unfiltered via containment (CTM)
El SGTR with rupture located BELOW water level El Steam Generator Tube Rupture with rupture located ABOVE water level D Turbine Bldg D Reactor Bldg El Auxiliary Bldg.
BFN 0 Stack (filtered) E] Turbine Bldg, Reactor Bldg El Stack (unfiltered) El Main Steam Line Break (MSLB)
S. DETERMINE the Release Type: EIRCS [lCore Damage ElGap (default) ElFuel Melt NOTE: Initially, a GAP Release Type should be used unless otherwise specified by the Core Damage Assessment team. Alternately, particulate-to-I131 field team air concentration data can be used as follows:
Field Team Data Particulate microCi/cc = Ratio Field Team Data lodine'31 microCi/cc Ga- Core Damage Fuel Melt Ratio = Release Type: 2 0.18 2 2.0 2 3.5
- I-DOSE ASSESSMENT STAFF I ACTIVITIES DURING NUCLEAR Page 14 of 32 PLANT RADIOLOGICAL ECC EPIP-8 Revision 27 EMERGENCIES Appendix E Page 2 of 2 BRED Code Run BRED Evaluation of Airborne Field Data
- 6. RUN the BRED computer model and follow prompts using the information from sections 2-5. TYPE CTRL Z any time to exit or re-start program.
- 7. RECORD the printed Release Rate output (as applicable) and INPUT into the FRED code.
Noble Gas (gCils) Iodine 131 (pre-treatment) IiCils Tritium (3 H) gCi/s I I I
- 8. COMPARE the new FRED run dose rate output to the previous RED/FRED computer model by CALCULATING a data ratio as follows:
FRED or RED Centerline Dose Rate dividedby the FIELD DATA Centerline Dose Rate divided by = RATIO Unlikely -
Field Team Plant but release possible not on unidentified?
NOBLE GAS RATIO I Not unusual I centerline?
I I I I I I I I I 0.001 0.01 0.1 0.2 0.5 I 10 50 100 1000 A
I Base actions on Base Attempt to verify projections by verified field actions traversing the plume. Ask for measurements on reevaluation and level of projections confidence on plant release data. Must be very confident that field data is correct to override projections based on measured release data.
- 9. PROVIDE feedback to the Environs Assessor and RAC/RAM. UPDATE dose projections as necessary and give the results to the RAC for use in preparing Protective Action Recommendations (PAR), or prepare a PAR in accordance with CECC EPIP-1.
- I
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 15 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES Appendix F Page1 of 8 MANUAL AIR Manual Method for Assessing Airborne Releases' SB TEDE PAG A. Calculating TEDE PAG Release Rate at SITE BOUNDARY (0.62 miles)
Stability Class: (circle) A B C D E F G Release Type: ORCS [Core Damage ElUser Specified lDGap (default) ElFuel Melt: (for noble gas and Tritium only)
Release Path: SQNIWBN BFN O Filtered via CTM El filtered via stack n Unfiltered via CTM El unfiltered via stack El SGTR with rupture BELOW water El Turbine, Reactor Bldg El SGTR with rupture ABOVE water [] Main Steam Line Break E Turbine, Reactor, Auxiliary Building
NOTE: USE ground level for all cases except for BFN stack.
A ~~B C D EF F G -]
Ground 1.7E+09 4.8E+08 12.2E+08 11E+087.4E+07I4.9E+07 2.9E+071 Stack 1.8E+09 9.1 E+08 9.1 E+08 8.3E+08 8.3E+08 8.OE+08 19.1 E+08
- 3. CIRCLE the appropriate TEDE Ratio below, based on release type/path:
TEDE Ratio (for 0.62 mi) BWR PWR Core . Fuel User RCS RCS Gal Damane Melt Spec Stack (unfiltered 2.0 N/A 1.8 1.3 2.0 1.0 Stack (Filtered) 1.9 N/Ar, 1.0 1.0 .1.0 1.0 CTM (unfiltered) or SGTR N/A 7.4 9.0 .5.3 I 1.0 (below)
CTM (filtered) N/A 3.7 1.0 0.9 . 1.0 1.0 SGTR (above water) N/A 95 221 111 263 1.0 MSLB (BFN) 7.4 N/A 84 44 100 1.0 Turbine, Reactor or Aux Bldg 4.4 17 32 16 37 1.0
X I TEDE PAG FACTOR wind speed TEDE Ratio TEDE NGPAG Release Rate
(,uCi/m, item 2) (m/s, item 1). (item 3) SB 0.62 mi (pCi/s)
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 16 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES Appendix F Page 2 of 8 MANUAL AIR Manual Method for Assessinc Airborne Releases SB TEDE PAG S. OBTAIN the actual/projected Noble Gas Release Rate __Ci/s.
THEN radiological conditions indicate a General Emergency.
For Tritium Accidents (e.g., TPBAR handling or WGDT rupture),
A B C D l E F lG 4.0E+09 I 8.7E+08 l2.9E+08 I 1.OE+0815.9E+07l 3.1 E+07 1.42+07
X _ .
Tritium PAG FACTOR wind speed TEDE Tritium PAG Release Rate (I+/-Cim, ite~ii7)~
~ ~ (nm/s item 1) SB 0.62 Ml (i+/-Ci/s)
- 9. OBTAIN the actual/projected Tritium Release Rate (see below) RCi/s.
NOTE:
- For a TPBAR handling accident, the H-3 release can be estimated as:
H-3 Release =_ Clicc H-3 x cfm x 28320 cc/cf Rate 60 min/sec
{ H-3 release (gCi/s) = #gCi/cc H-3 x building exhaust flow rate (cfm) x 28320 cc/cf x 1/60 min/s)
- For a WGDT Rupture accident, the default H-3 release is 2500 Ci over one hr or 6.94E+05 gCi/s for 1 hr
THEN radiological conditions indicate a General Emergency.
- 11. IF tritium accident also involves noble gases, THEN perform the following calculation:
NG Release Rate + Tritium Release Rate TEDE NG PAG Release Rate TEDE Tritium PAG Release Rate (item 5) (item 9) =
(item 4) (item 8) Ratio
- 12. IF the value in item 11 2 1.0, THEN radiological conditions indicate a General Emergency.
Appendix F Page 3 of 8 Manual Method for Assessina Airborne Releases IB. Calculating THYROID CDE PAG Release Rate at SITE BOUNDARY (0.62 MILES)
- 1. USE the data from section A.1
NOTE: USE ground level for all cases except for BFN stack.
A l B C D EF G Ground 4.1 E+05 8.6E+04 I 3.OE+04 11.OE+04 I 6.OE+03 1 3.1 E+03 1.4E+03 Stack 4.1 E+05 2.3E+05 3.7E+05 6.5E+05 1.4E+06 2.1 E+07 4.9E+11
X '=
____CDE PAG FACTOR . _ wind speed_ 1_CDE PAG Release Rate (pCi/m, item 2) (mIs) SB 0.62 mi (giCi/s)
- 4. a. If known, RECORD the actual/projected 1-131 release rate pCi/s and go to Step 5.
If unknown, CIRCLE the 1-131 to NG ratio below, based on release type and path and continue with step 4 b.
>i>;~
$ , , , ;, ~~~~~~~~~~~~~. $..!N.
. ooi
'. ..... ....bl'...
..... \.,....
... Gas atio$~:
-CTMfiltered .. I .7E06 30E-05 .2E.05... 2.2E-05
........ tack filtre d 6.0 .. .... .OE!-.05 -'J1.'2E ;0 "2,2E-05 ::
(u nfiltered)
.CTM or SGT R (below). .1 E 0. 3 .0. . . .. E.. 3.E
... ~ ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~.... ..
'$'$S.. (above) *$'SGTRS 8;0E.02 3.0E-02 24.2E03 5.5E-02
<. .:i~m;'iS' iii>MSLB (BFN): i$.;E04..i 3.OE 02 I .2E-02 2;2E.02; 4.b. CALCULATE actual/projected iodine-131 abQ66filt~~~r~ed ..... 4. release rate as follows:
(item A.5) (item 4a) (pCi/s)
THEN radiological conditions indicate a General Emergency:
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 18 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES Appendix F Page 4 of 8 MANUAL AIR Manual Method for Assessing Airborne Releases SB TEDE RATE
[C. Calculating TEDE Dose Rate'at SITE BOUNDARY (0.62 miles) l
Stability Class: (circle) A B C D E F G Release Type: QRCS []Core Damage OUser Specified (for noble gas and Tritum only)
OGap (default) 0Fuel Melt Release Path: SQN/WBN BFN EJ Filtered via CTM El filtered via stack o Unfiltered via CTM El unfiltered via stack Ea SGTR with rupture BELOW water El Turbine, Reactor Bldg
- SGTR with rupture ABOVE water El Main Steam Line Break El Turbine, Reactor, Auxiliary Building Noble Gas Release Rate: - (pICi/s)
- 2. CIRCLE the TEDE FACTOR (remfh per .LCi/m) below, based on the stability class and release level.
NOTE: USE ground level for all cases except for BFN stack.
A I B I C I D I E I F I G I Ground 6.OE-10 I 2.1E-09 I 14.6E-09 9.5E-09 1.4E-08 2.1E-08 13.5E-08 Stack 5.5E-10 1.1E-09 1.1E-09 1.2E-09 1.2E-09 1.3E-09 1.1E-09
- 3. CIRCLE the appropriate TEDE Ratio below, based on release type/path:
TEDE Ratio (at 0.62 mi)
WR PWR Core Fuel User tCS RCS GAP Damage Melt Spec Stack (unfiltered) 2.0 N/A 1.8 1.3 2.0 1.0 Stack (filtered) _ 1.9 N/A 1.0 1.0 1.0 1.0 CTM (unfiltered) or SGTR (below) Iq/A 7.4 9 5.3 - 11 1.0 CTM (filtered) Iq/A 3.7 1.0 0.9 1.0 1.0 SGTR (above water) Iq/A 95 221 111 263 1.0 MSLB (BFN) 7.4 N/A 84 44 100 1.0 TB, RxB, AB 4.4 17 32 16 37 1.0
- 4. CALCULATE the TEDE Dose as follows:
X X I =
NG release rate (gCi/s) TEDE FACTOR TEDE Ratio wind sp. (m/s) TEDE (rem/h)
(item A-5) (item 2) (item 3) (item 1) 0.62 mile For Tritium Accidents (e.g., TPBAR handling or WGDT rupture),
I A I l C_ I l E I F I I 2.5E-10 l 1.2E-09 I 3.5E-09 I 1.0E-08 1.7E-08 I 3.3E-08 I 7.OE-08
Appendix F Page 5 of 8 Manual Method for Assessing Airborne Releases MANUAL AIR 5 mi TEDE RATE
______X I .__=
Tritium Release Rate* Tritium TEDE FACTOR wind speed Tritium TEDE (PCi/s) (item 5) (mWs) (rem/h)
(item 1)
NOTE:
- For a TPBAR handling accident, the H-3 release can be estimated as:
H-3 Release = uCicc H-3 x cfm x 28320 cc/cf Rate 60 min/sec
{H-3 release (,uCi~s) = #1iCi/cc H-3 x building exhaust flow rate (cfm) x 28320 cc/cf x 1/60 min/s }
- For a WGDT Rupture accident, the default H-3 release is 2500 Ci over one hr or 6.94E+05 +/-CiVs for 1 hr
+
TEDE (rem/h) Tritium TEDE (rem/h) l D. Calculating SB THYROID CDE Dose Rate
- 1. CIRCLE the Thyroid CDE FACTOR (rem/h per g.Ci/m), based on the stability class and release level.
NOTE: USE ground level for all cases except for BFN stack.
A j B C D -E FG Ground 1.2E-05 5.8E-05 l 1.7E-04 I 4.8E-04 l 8.3E l 1.6E-03 l 3.5E-03 l Stack 1.2E-05 7 2.2E-05 1A.4E-05 7.7E-06 3.5E-06 2.3E-07 1.OE-1 l 2 a. If known, RECORD the 1-131 release rate' -________ .Ci/s and go to Step 3.
If unknown, CIRCLE the 1-131 to NG ratio below, based on release type and path and continue with step 2b.
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~.............
RCS ao ............ {%%2%{..
.ore......uelMe.
^..
......... .. .ter C d 7, 06 3.OE'05 or't2E-05 2.2E-05'
' ..... Stack fil ered' i.6Eo7 *3.E'05' i 2E-05; 2.2E-05 CTM (unfilte.red).or.SGTR (below) I....0. 30.E 03 .....
1 3 .......
',,, ,,,:,,,r', ,S ack (unfiltered) 4.6E-05 3.OE-03 .:. 1.2E-03 ' 2,2E-03 TB.Aux, iB . 5..E-4 iOE-02 4ii-03 7E-03
..... ... GTR (abo e). ' 2E 03 OE02 30E.02 5.5E-02 i
......SLB (F) .,6E
.2 . ..E 2E.0. .2E-02
"~...-i.2b. CALCULATE actual/projected iodine-131 release rate as follows:
X =
NG release rate 1-131 to NG ratio 1-131 release rate ( 1iCi/s)
(item A.5) (item 2a)
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 20 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES Appendix F Page 6 of 8 MANUAL AIR Manual Method for Assessing Airborne Releases 5 mi TEDE DOSE
- 3. CALCULATE Thyroid CDE Dose Rate as follows:
X I_
1-131 release rate (p.Ciis) Thyroid CDE FACTOR wind speed (item 2) (item 1) (m/s)
IE. Calculatinq 5 mile TEDE I USE the data from section A.1, THEN
- 1. OBTAIN an estimate of the release duration (t) hours. Use 4 (four) hours unless known otherwise.
- 2. CIRCLE the TEDE FACTOR (rem/h per per +/-Ci/m) below, based on the stability class and release level.
NOTE: USE ground level for all cases except for BFN stack.
A B C D E F G Ground 9.5E-11 1.5E-10 2.8E-10 9.5E-10 1.8E-09 I3.5E-09 16.5E-09 Stack 9.OE-11 1.5E-10 2.6E-10 7.5E-10 1.1E-09 1.3E-09 1.1E-09
- 3. CIRCLE the appropriate TEDE Ratio below, based on release type/path:
TEDE Ratio (at 5 mi)
,CS RCS GAP Damage Melt Spec Stack (unfiltered) 2.1 NIA 2.8 1.9 3.1 1.0 Stack (filtered) _ 2.1 N/A 1.0 0.9 1.0 1.0 CTM (unfiltered) or SGTR (below) I /A 3.5 4.9 2.9 5.8 1.0 CTM (filtered) _ /A 1.8 1.0 1.0 1.0 1.0 SGTR (above water) t/A 43 100 51 116 1.0 MSLB (BFN) 4.5 N/A 40 21 47 1.0 TB, RxB, AB 3.1 7.4 15 7.9 17 1.0
- 4. CALCULATE the TEDE Dose as follows:
X_ X X NG release rate (.+/-Ci/s) TEDE FACTOR TEDE Ratio Duration (hrs) wind sp. (m/s)
(item A.5) (item 2) (item 3) (item 1) (item 1)
For Tritium Accidents (e.g., TPBAR handling or WGDT rupture),
I.A- I5 I 1-I D I.E IF I _GE-I4.OE-1 11 5.OE-1 11 1.1 E-1 0 14A4E-1 0 9.5E-1 0 12A4E-09 15. 5E-0~9
Appendix F Page 7 of 8 MANUAL AIR Manual Method for Assessing Airborne Releases 5 mi TEDE DOSE
_ _ _ _ _ _ _ _ __- - - Xx __X =
Tritium Release Rate Tritium TEDE FACTOR Duration wind speed Tritium TEDE (PCils) (item 5) (hrs) (m/s) (rem)
(item A.1) (item A.1)
NOTE:
- For a TPBAR handling accident, the H-3 release can be estimated as:
H-3 Release = uCi/cc H-3 x cfm x 28320 cc/cf Rate 60 min/sec
{ H-3 release (tCi/s) = #gCi/cc H-3 x building exhaust flow rate (cfm) x 28320 cc/cf x 1/60 min/s }
. For a WGDT Rupture accident, the default H-3 release is 2500 Ci over one hr or 6.94E+05 IiCi/s for 1 hr
_ __ _ _ + _ = ,__ _ _ _ _
TEDE (rem) Tritium TEDE (rem)-. -Total TEDE(rem) 5 mile IF. Calculating 5 mi THYROID CDE Doses I
- 1. - CIRCLE the Thyroid CDE FACTOR (rem/h per piCi/m), based on the stability class and release level.
NOTE: USE ground level for all cases except for BFN stack.
A I B I C eD E F ' G Ground l 2.OE-06 l 2.5E-06 l 5.OE-06 l 2.2E-05 l 4.7E-05 7 1.2E-04 l 2.7E-04 Stack 2.OE-06 I 2.5E-06 4.5E-06 7.7E-06 3.5E-06 2.3E-07 l 1.OE-11
- 2. OBTAIN the 1-131 release rate from B.4 (gCi/s).
- 3. CALCULATE Thyroid CDE Dose as follows:
- - - X X ____ /__
1-131 release rate (iCil/s) Thyroid CDE FACTOR duration (hrs) wind speed (item 2) (item 1) - (item C.1) (m/s) -
(item A.1) i
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 22 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES Appendix F Page 8 of 8 Manual Method for Assessing Airborne Releases Summary G. Summary of Results Site Boundary TEDE Rates
- 1. Total TEDE Rate (item C.7) rem/h
For 0.62 mi TEDE dose rate 2 REP Emergency Class I E-04 rem/h NOUE I E-02 rem/h ALERT 1E-01 rem/h SAE 1E+00 rem/h GE Site Boundary Thyroid CDE Dose Rate
- 3. CDE Dose Rate (section D.3) - rem/h
For 0.62 ml CDE dose rate 2 REP Emergency Class NA NA 0.5 rem/h SAE 5 rem/h GE 5 Mile TEDE
[5 Mile Thyroid CDE
Emergency Class
- 8. Circle the most restrictive REP class from items 2 and 4: NOUE Alert SAE GE END OF MANUAL Calculated by: (initial / date) I ASSESSMENT DATA VERIFICATION Verified by: (initial / date) /
APPENDIX G tAM'lDADRIQrNK n MRAqI IoFln FIF n nATA Tn nf = Dori irSTIAni Mrnci c Ratio = PROJECTED centerline dose rate MEASURED centerline dose rate id 40.-~~I.
Unlikely - Field Team Plant but release possible not on unidentified?
NOBLE GAS RATIO I Not unusual l centerline?
I I I I I I I I I 0.001 0.01 0.1 0.2 0.5 1 10 50 100 1000
. I 6 Base actions on Base Attempt to verify projections by verified field actions traversing the plume. Ask for measurements on reevaluation and level of projections confidence on plant release data. Must be very confident that field data is correct to override projections based on measured release data.
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 24 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES APPENDIX H WATERDOSE WATERDOSE Evaluation of Liquid Release to the River Code Run
- 1. Log on to WATERDOSE. DOUBLE CLICK on the 'CECC VAX" icon. PRESS return until prompted for usemame. ENTER usemame (WATERDOSE) and password (CECC).
- 2. OBTAIN the following information for input to WATERDOSE and FOLLOW code prompts.
NOTE: TYPE CTRL Z any time to exit or re-start program.
- a. Determine Release Point:: El Diffuser El Shoreline
- b. Length of release: -- Hours-- -
- c. Volume of release: (ft3)
- d. Release Mix -(nuclides and concentrations)
Nuclide Concentration (gCi/ml)
- 3. RUN the WATERDOSE code using the available (or default below) information to obtain an estimate of the dose impact. (If the computer code is not operational, the dose calculation methodology contained in Appendix I can be used.)
BFN-33000 cfs SQN - 29000 cfs *WBN - 27000 cfs NOTE: TYPE CTRL Z any time to exit or re-start program.
- 4. OBTAIN the State Update Form (SUF). The Preparer and Verifier shall initial and date the results.
- 5. TRANSMIT (by spooling through the computer) the SUF to the TSC and State if approval to do so has been given by the RAC/RAM.
- 6. TYPE CTRL Z any time to exit or re-start program.
- Revision
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 25 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES APPENDIX I 'Page 1 of 5 MANUAL Manual Evaluation of Liquid Releases to the River RIVER
- 2. Release Point: EDDiffuser EShoreline
- 3. Release Time: Start End OEastem - OCentral
- 4. Release Volume (V) . ft 3 (1gal = 0.134 ft3)
- 5. Calculation of Hazard Index (HI):
Nuclide Concentration Dose - Hazard (uCi/ml) (rem/day per gCi/ml) Index (rem/day)
C DF- Table 3 HI=C *DF
=__________._______________ Total Hazard Index -
- 6. Riverflow at the plant ;-O__ ft3/s (cfs). This can be obtained from the ICS (for SQN and WBN) or River Operations. If flow data is not available use the following default values:
BFN-33000 cfs SQN - 29000 cfs *WBN - 27000 cfs 7.' Calculate the downstream dose rate to hypothetical individual at first downstream Public Water Supply and then other locations of interest. Refer to Appendix J.
(table 2) (table 1) (item 5) (item 4A Location Arrival Time Dilution Factor Hazard Index Release Dose Rate TRM Hours (1ift3) (rem/day) Volume (ft3) (rem/day)
D HI V D*H*V
- 8. Record the applicable data on the State Update Form in CECC EPIP-1 and distribute.
Comments:
END OF MANUAL Calculated by: (initial I date) /
ASSESSMENT DATA VERIFICATION Calculated by: (initial I date) /
- Revision
APPENDIX I Page 2 of 5 TABLE 1 Manual Evaluation of Liquid Releases to the River DILUTION FACTOR RELATIVE CONCENTRATION FACTORS-PER CUBIC FOOT RELEASED (D )
BROWNS FERRY NUCLEAR PLANT RHC)RFI IMF PFI F=AI;F= nl!FF~i5,;FP PIP;= RF FA!RF Tennessee Plant Side Opposite River Shoreline Shoreline Centerline Shoreline Mile (TRM) D D D D 294.00 Plant _
293.00 2.8E-08 .OOE+00 1.4E-08 .OOE+00 292.00 1.4E-08 .OOE+00 6.9E-09 .OOE+00 291.00 9.2E-09 .OOE+00 4.6E-09 1.2E-36 290.00 6.9E-09 .OOE+00 3.4E-09 8.2E-30 289.00 5.5E-09 .OOE+00 2.8E-09 1.0E-25 288.00 4.6E-09 .OOE+00 2.3E-09 5.1 E-23 287.00 3.9E-09 .OOE+00 2.OE-09 4.3E-21 286.00 3.4E-09 .OOE+00 1.7E-09 1.2E-19 285.00 3.1 E-09 .OOE+00 1.5E-09 1.52-18 284.00 2.8E-09 1.8E-42 1.4E-09 1.2E-17 283.00 2.5E-09 1.8E-39 1.3E-09 6.2E-17 282.00 2.3E-09 5.8E-37 1.1 E-09 2.4E-16 281.00 2.1 E-09 7.4E-35 1.1 E-09 7.7E-16 280.00 2.0E-09 4.8E-33 9.8E-10 2.1 E-15 279.00 1.8E-09 1.8E-31 9.2E-10 4.8E-15 278.00 1.7E-09 4.1 E-30 8.6E-10 1.02-14 274.90 Downstream Dam SEQUOYAH NUCLEAR PLANT SQwRlpFI IMP REI FASE; ni;:;:i I-q;=p pip;: PPI F=Aq;=
Plant Side Opposite Shoreline Shoreline Centerline Shoreline TRM D D D D 484.50 Plant 484.00 3.5E-08 5.9E-34 1.8E-08 1.1E-14 483.00 1.4E-08 5.3E-19 7.2E-09 3.0E-11 482.00 9.1 E-09 3.2E-15 4.6E-09 1.9E-10 481.00 6.6E-09 1.5E-13 3.3E-09 3.9E-10 480.00 5.2E-09 1.4E-12 2.6E-09 5.6E-10 479.00 4.3E-09 5.4E-12 2.2E-09 6.8E-10 478.00 3.7E-09 1.4E-11 1.8E-09 7.6E-10 477.00 3.2E-09 2.7E-11 1.6E-09 8.2E-10 476.00 2.8E-09 4.5E-11 1.4E-09 8.4E-10 475.00 2.5E-09 6.6E-11 1.3E-09 8.6E-10 474.00 2.3E-09 9.0E-11 1.2E-09 8.6E-10 473.00 2.1E-09 1.2E-10 1.1E-09 8.6E-10 472.00 1.9E-09 1.4E-10 1.OE-09 8.5E-10 471.00 1.8E-09 1.7E-10 9.8E-10 8.3E-10 471.00 Downstream Dam
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 27 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES APPENDIX I Page 3 of 5 TABLE I Manual Evaluation of Liquid Releases to the River DILUTION FACTOR RELATIVE CONCENTRATION FACTORS-PER CUBIC FOOT RELEASED (D)
WATTS BAR NUCLEAR PLANT SHORELINE RELEASE __I DIFFUSER PIPE RELEASE Plant Side Opposite Shoreline Shoreline Centerline Shoreline TRM D D D D 528.00 Plant _
527.00 3.7E-08 1.2E-20 1.8E-08 2.3E-11 526.00 1.8E-08 1.5E-14 9.1 E-09 4.1 E-09 525.00 1.2E-08 1.3E-12 6.1E-09 1.OE-09 524.00 9.1 E-09 1.2E-11 4.6E-09 1.4E-09 523.00 7.3E-09 4.OE-11 3.7E-09 1.7E-09
'522.00 6.1 E-09 9.OE-11 3.1 E-09 1.8E-09 521.00 5.2E-09 1.6E-10 2.7E-09 1.8E-09 520.00 4.6E-09 2.3E-10 2.4E-09 1.8E-09 519.00 4.1 E-09 3.1 E-10 2.2E-09 1.8E-09 518.00 3.7E-09 3.8E-10 2.OE-09 1.8E-09 517.00 3.3E-09 4.6E-10 .1.9E-09 1.7E-09 516.00 3.OE-09 5.2E-10 1.8E-09 1.7E-09 515.00 2.8E-09 5.8E-10 1.7E-09 1.6E-09 514.00 2.6E-09 6.4E-10 1.6E-09 - 1.6E-09 513.00 2.4E-09 6.8E-10 - 1.6E-09 1.5E-09 512.00 -- 2.3E-09 7.2E 1.5E-09 1.5E-09 511.00 2.2E-09 7.6E-10 1.5E-09 1.4E-09 510.00 -2.OE-09 7.9E-10 1.4E-09 1.4E-09 510.00 1.9E-09 8.2E-1 0 1.4E-09 1.4E-09 508.00 1.8E-09 8.4E-10 1.3E-09 1.3E-09 507.00 1.8E-09 8.6E-10 1.3E-09 -1.3E-09 506.00 1.7E-09 8.7E-10 1.3E-09 1.3E-09 505.00 1.6E-09 8.8E-10 1.2E-09 1.2E-09 504.00 1.5E-09 8.9E-10 1.2E-09 1.2E-09 503.00 1.5E-09 9.OE-10 - 1.2E-09 - 1.2E-09 502.00 1.4E-09 9.1 E-10 - -- 1.2E-09 1.2E-09
.501.00 1.4E-09 - 9.1 E-10_- - 1.1E-09 1.1 E-09 500.00 1.3E-09 9.1 E-10 1.1 E-09 1.1 E-09 471.00 Downstream Dam -
I-DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 28 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES APPENDIX I Page 4 of 5 TABLE 2 Manual Evaluation of Liquid Releases to the River ARRIVAL TIME APPROXIMATE TRAVEL TIME TO MAXIMUM CONCENTRATION - HOURS (HRS)
BROWNS FERRY NUCLEAR PLANT TRM RIVER FLOW IN CUBIC FEET/SECOND 25000 30000 33000 35000 37000 39000 294.00 Plant _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
292.00 25 21 19 18 17 16 290.00 49 41 37 35 33 31 288.00 74 62 56 53 50 47 286.00 99 82 75 71 67 63 284.00 124 103 92 88 84 80 282.00 148 124 112 106 100 94 280.00 173 144 131 124 117 110 278.00 198 165 150 141 134 128 276.00 222 185 169 159 150 142 274.90 Downstream Dam SEQUOYAH NUCLEAR PLANT 21000 25000 29000 30000 33000 484.50 Plant _
483.00 5 4 4 3 3 10 8 8 7 ' /;
481.00 12 479.00 18 15 13 13 12 477.00 25 21 18 17 16 475.00 32 26 23- 22 20 473.00 38 32 28 27 24 471.00 45 38 32 31 28 471.00 Downstream Dam WATTS BAR NUCLEAR PLANT 19000 20000 25000 30000 35000 528.00 Plant 526.00 5 4 3 3 3 524.00 10 9 7 6 6 522.00 15 - 14 11 9 9 520.00 20 19 15 12 12 518.00 25 24 19 16 15 516.00 30 29 23 19 18 514.00 35 33 27 22 21 512.00 40 38 30 25 24 510.00 45 43 34 29 28 508.00 50 48 38 32 31 506.00 56 53 42 35 34 504.00 61 58 46 38 37 502.00 66 62 50 41 40 500.00 71 67 54 45 43 471.00 Downstream Dam
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 29 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES TABLE 3 APPENDIX I Page 5 of 5 DOSE Manual Evaluation of Liquid Releases to the River FACTORS Critical Ingestion Dose Rate Factors ( DF _
(Derived from Regulatory Guide 1.109)
Rem/day per gCi/ml Nuclide Dose Factor Organ 1 Age2 Nuclide Dose Factor Organ, Age2 H-3 0.28 TB Ru-1 03 43.2 GIT A C-14 16.9 B Ru-1 05 58.9 GIT C Na-24. 8.12 TB Ru-106 356 GIT A P-32 1155 B Ag-110m 121 GIT A Cr-51 1.34 GIT Te-125m 21.8 K A Mn-54 28 GIT Te-127m 55 K A Mn-56 67.8 GIT Te-127 25.8 GIT C Fe-55 16.1 B Te-129m 96 K C Fe-59 68 GIT Te-129 20.4 GIT A Co-58 30 GIT Te-131 168 GIT A Co-60 80.4 GIT Te-131 6.4 GIT Ni-63 753 B Te-132 154 GIT A Ni-65 35.8 GIT 1-130 1332 THY Cu-64 14.2 GIT 1-131 12500 THY Zn-65 51.1 L 1-132 142 THY. C C
Zn-69 12.33 GIT 1-133 2980 THY Br-83 0.24 TB 1-134 37.4 THY Br-84 0.28 TB 1-135 584 THY Br-85 0.013 TB Cs-1 34 538 L C Rb-86 153 L Cs-1 36 90.4 L C Rb-88 0.45 L Cs-1 37 438 B C A
Rb-89 0.26 L Cs-1 38 1.13 GIT I A
Sr-89 1850 B Ba-139 50.2 GIT C Sr-90 23800 B Ba-140 116 B IA Sr-91 74.2 GIT Ba-141 7.27 GIT C A
Sr-92 239 GIT Ba-1 42 1.06 GIT A
Y-90 204 GIT La-140 185 GIT A Y-91m 2.43 GIT La-142 46.3 GIT C Y-91 155 GIT Ce-1 41 48.4 GIT A Y-92 146 GIT Ce-1 43 91.2 GIT A Y-93 238 GIT Ce-1 44 330 GIT A-Zr-95 61.8 GIT Pr-143 80.6 GIT A Zr-97 210 GIT Pr-144 4.44 GIT I Nb-95 42 GIT Nd-147 69.8 GIT A Mo-99 39.8 K W-187 56.4 GIT A Tc-99m 1.44 GIT Np-239 48 GIT A
- 1. THY = thyroid, GIT = Gastrointestinal Tract, K = Kidney, L = Liver, TB = Total Body, B = Bone
- 2. A = Adult, C = Child, I = Infant
DOSE (SESSMENT K (
-LI,-
STAFF ACTIVITIES DURING NUCLEAR Page 30 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES APPENDIX J Page 1 of 3 BFN - PUBLIC AND INDUSTRIAL SURFACE WATER SUPPLIES Type of County-State Plant Name Water Source Water SuppIy Notification Advise State or Local Authorities 10-Mile Radius listed in the REND Limestone-Alabama Browns Ferry Nuclear Plant Tennessee River Industrial Lawrence-Alabama W. Morgan, E. Lawrence Tennessee River Municipal Lawrence-Alabama Water Authority Champion International Tennessee River Industrial &
25-Mile Radius (Courtland Plant) Potable State of Alabama Joe Wheeler State Park Tennessee River Municipal Lawrence-Alabama TVA-Wheeler Dam' Tennessee River Industrial 50-Mile Radius Lauderdale-Alabama Florence City-Wilson Plant Tennessee River Municipal Colbert-Alabama Reynolds Metals Company Tennessee River Industrial Colbert-Alabama Muscle Shoals - Tennessee River Municipal Fleet Hollow Embayment Colbert-Alabama TVA ERL Fleet Hollow Embayment Industrial &
Potable Colbert-Alabama TVA-Wilson Dam Tennessee River Industrial Colbert-Alabama Occidental Chemical Company Tennessee River Industrial Colbert-Alabama Sheffield Tennessee River Municipal Colbert-Alabama Sheffield Police Colbert-Alabama TVA Colbert Fossil Plant Tennessee River Industrial Colbert-Alabama Cherokee Water Works & Gas Tennessee River Municipal Colbert-Alabama Cherokee Police (Day)
Colbert-Alabama Cherokee Police (Night)
Colbert-Alabama Laroche Industries Tennessee River Industrial
'Potable water obtained from East Lauderdale County Water District.
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 31 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES APPENDIX J Page 2 of 3 SQN - PUBLIC AND INDUSTRIAL SURFACE WATER SUPPLIES Type of County-State Plant Name Water Source Water Supply Notification Advise State or Local Authorities 10-Mile Radius listed in the REND Hamilton-Tennessee Sequoyah Nuclear Plant Tennessee River Industrial Gold Point Marina Tennessee River East Side Utility Tennessee River Industrial Tennessee River Industrial Chickamauga Dam (Power Service Center) Tennessee River Industrial Chickamauga Dam Tennessee River 25-Mile Radius E. I. Dupont Co. Tennessee River Industrial and Potable Tennessee American Water Co. Tennessee River Municipal Rock-Tennessee Mill' Tennessee River Industrial Vulcan Sand & Gravel' Tennessee River Industrial Signal Mountain Cement' Tennessee River Industrial Medusa Cement Co. Tennessee River Industrial 50-Mile Radius Signal Mountain Cement (Plant) Tennessee River Industrial Marion-Tennessee Signal Mountain Cement (Quarry) Tennessee River Industrial South Pittsburg Tennessee River Municipal Nickajack Dam Tennessee River Industrial Jackson-Alabama Bridgeport Tennessee River Municipal and Spring Jackson-Alabama Bridgeport Police Tennessee River and Spring Widows Creek Fossil Plant2 Tennessee River Industrial Mead Corporation . Tennessee River Industrial
- Obtains potable water from Tennessee-American Water Company.
2 Obtains potable water supply from Bridgeport - physically removed potable water intake in November 1986.
( c c
. (17
-7 DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 32 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 27 EMERGENCIES APPENDIX J Page 3 of 3 WBN - PUBLIC AND INDUSTRIAL SURFACE WATER SUPPLIES ON THE TENNESSEE RIVER Type of County-State Plant Name Water Source Water Supply Notification Advise State or Local Authorities listed in 10-Mile Radius the REND Rhea-Tennessee Watts Bar Fossil &Hydro Plant' Tennessee River Industrial2 ,3 Watts Bar Nuclear Plant Tennessee River 'Industrial1 4 25-Mile Radius Rhea-Tennessee City of Dayton Tennessee River Municipal Dayton Police 50-Mile Radius Hamilton-Tennessee TVA Sequoyah Nuclear Plant Tennessee River Industrial East Side Utility Tennessee River Industrial E. I. Dupont Tennessee River Industrial and Potable Chickamauga Dam Tennessee River Industrial Tennessee American Water Co. Tennessee River Municipal Rock-Tennessee Mills Tennessee River Industrial Vulcan Sand and Gravels Tennessee River Industrial Signal Mountain Cements Tennessee River Industrial iOn layby status - water use when activated is about 445 MGD.
2 Cooling water.
3 Potable water to nuclear plant, steam plant, hydro plant, and resort area, provided through Watts Bar Reservation System (wells).
4Cooling water and cooling tower makeup.
5 Obtains potable water supply from Tennessee-American Water Company.
CECCEPtPCoversheet : =
Title CECC EPIP-23 Tennessee REV. 19 Valley Authority CENTRAL EMERGENCY RADIOACTIVE MATERIAL CONTROL CENTER TRANSPORTATION INCIDENTS EMERGENCY PLAN IMPLEMENTING Effective Date:
PROCEDURES WRITTEN BY: c C-. vv REVIEWED BY: _2_ 7__
Signature Signature Date PLAN EFFECTIVENESS DETERMINATION: 191//62, Signature Date CONCURRENCES Concurrence Signature Date 0 Mar er, EP ProgramPfan ing and Implementation 03 lnager, Emqgency Preparedness - -
0 Manager, Radiologidif and Chemistry Services 1103 APPROVAL APPROVED BY: Engineering & Technical Services /7'03 Signature - - Ttle Organization 'Date
CECC-EPIP-23 RADIOACTIVE MATERIAL TRANSPORTATION INCIDENTS REVISION LOG Rev. No. Date Revised Pages 0 12/12/88 All 1 4/26/89 3 2 10/26/89 App. A 3 6/20/90 All (formerly EPIP-21) (Former EPIP-23 transferred to EPIP-13) 4 9/14/90 Pg. 4 (only) 5 5/21/91 Pages 1 - 19 6 02122/93- Pgs. 1-17 revised. Pages 20-23 added. All pages issued.
7 11/30/93 Pages 3, 15, and 20; all pages issued.
8 06/23/94 Pgs. 5-7: All pages issued.
9 6/27/95 Pgs. 3-6, 11-15, 17, and 18 10 1/3/96 Procedure issued in new format which includes, in some cases, altering of the order of statements, editorial changes, and adding boxes and shading to highlight statements. Changed accident to incident in title and through the EPIP. Added definition of transportation incident, revised references section, updated EDO checklist. Added notification of the Senior Nuclear Executive and affected site VP to the CECC Dir. checklist, added WBN phone numbers, changed Appendices to Attachments. All pages issued.
11 5/30/96 Pgs. 2, 4, 6, 8, Att. E; Att. F: annual review, minor changes for clarification, revised to provide flexibility for selection of optional equipment needed by field teams; all pages issued.
12 4/7/97 Annual review, editorial and organizational updates. All pages issued.
13 5/8/97 Page 18 revised to support new air sampling equipment. All pages issued.
14 3/11/98 Annual review. Pages 2, 4; and 5 revised to add instructions to get equipment from plants and consideration for use of still camera and satellite phone, update Corporate Communications titles.
Page 15 revised to remove full-face respirators w/HEPA-charcoal filters from equipment list. All pages issued.
15 7/7/98 Update Transportation Equipment list, pages 14 & 15. All pages issued.
16 6/15/00 Annual review. Editorial changes, update area codes, new packaging for KI, add flash lights to inventory list.
17 8/23/01 Update EDO checklist and SQN SM telephone number. All pages issued.
CECC-EPIP-23 RADIOACTIVE MATERIAL TRANSPORTATION INCIDENTS REVISION LOG I> -Rev. No. Date Revised Pages 18 6/13/02 Annual review. Add references to REPTRACK, update telephone numbers, editorial changes. All pages issued.
19 10/09/03 Annual review. Add equipment inventory retention criteria, editorial changes. All pages issued.
l Radioactive Material CECC EPIP-23 . . Page 1 of 24 Transportation Incidents C E Revisiono219 RADIOACTIVE MATERIAL TRANSPORTATION INCIDENTS 1.0 PURPOSE This procedure provides guidance to TVA personnel under the control of the CECC for response to transportation incidents involving radioactive materials. A transportation incident includes vehicle incidents, leaking containers, or other abnormal situations that could attract attention or require assistance.
2.0 SCOPE This procedure is applicable to transportation incidents involving radioactive materials to which TVA is requested to respond, including those situations which do not include shipments involving TVA materials or facilities.
3.0 REFERENCES
3.1 "Carrier and Shipper Responsibilities and Emergency Response Procedures for Highway Transportation Accidents Involving Truckload Quantities of Radioactive Materials," ANSI N14.27, 1986.
3.2 "Emergency Response Guidebook," Department of Transportation.
4.0 RESPONSIBILITIES 4.1 CECC Director Upon notification of a transportation incident, evaluate the need to staff the CECC and provide overall coordination of the response to the incident. Perform actions per Attachment B and review section 6.0.
NOTE:. If an ones ' ,resPfonder:ieqtuests irmmediate information concerning the shipment or' how to to' theiincident, teh'forin
respond :::.........................:.:.
ation must be providedvii15mis frm the time the
-:Ycall
- .- is received.;. Additional iformation is contained in Attachment B of this procedure.
4.2 CECC Emergency Preparedness Staff 4.2.1 The Manager, EP Program Planning and Implementation Section, or designee, ensures equipment and materials are available and maintained in accordance with section 5.0.
4.2.2 Upon notification, the EP Emergency Duty Officer (EDO) shall perform actions per Attachment A.
Radioactive MaterialECC EPIP-23 Page 2 of 24 Transportation Incidents Revision 19 4.3 Radiological Assessment Manager (RAM)
Upon notification, perform actions per Attachment C and review section 6.0.
4.4 Environs Assessor (EA)
Upon activation, perform actions per Attachment D and review section 6.0.
4.5 Field Coordinator (FC)
Upon activation, perform actions per Attachment D and review section 6.0.
[:NOTE:: Th-e may assume thefnctio of the FC. .. . :::
4.6 Monitoring Team 4.6.1 If using a site sampling team vehicle for response to the incident scene, the inventory per CECC EPIP-9 should be sufficient. Obtain additional dosimetry for any persons in addition to the standard 2-person sampling team crew.
If not using a sampling team vehicle for response to the incident scene, gather equipment per Attachment E. Consider Health Physics equipment needs applicable to the emergency and obtain those items from plant inventory (i.e., hand held and extended reach survey instruments, air samplers, and respirators).
4.6.2 Consider the need for video camera, still camera, and portable communications (radio, cellular phone or satellite phone).
4.6.3 Prior to arrival at the incident scene, review expected actions per Attachment F and review section 6.0.
4.6.4 Upon arrival at the incident scene, perform actions per Attachment F and CECC instructions.
Utilize applicable CECC EPIP-9 instructions and data forms for radiological monitoring.
Complete Attachment G as an incident area survey map.
4.7 Dose Assessment Upon activation for a transportation incident response, perform actions per instructions of the Radiological Assessment Manager.
4.8 Corporate Communications 4.8.1 Upon notification of a transportation incident, the Nuclear Information Duty Officer shall inform the Site Communications Consultant or the Media Relations Duty Officer of the incident.
4.8.2 The Site Communications Consultant or Media Relations Duty Officer has the responsibility to establish contact with the CECC Director for coordination and to open a conduit to obtain information concerning the incident.
Radioactive Material CECC EPIP-23 'Tage3 of 24 Transportation Incidents C EP-PR23iPage of 19 24 5.0 OPERATIONAL READINESS OF ENVIRONMENTAL MONITORING EQUIPMENT 5.1 Emergency Environmental Monitoring Vehicles Emergency Preparedness has vehicles and equipment available for response to a transportation incident. Inspections, inventories, and locations are provided in CECC EPIP-9 and -23.
5.2 Transportation Incident Kit 5.2.1 A response kit for situations requiring the use of transportation other than the vehicles referenced in section 5.1, is located at the Central Emergency Control Center (CECC).
5.2.2 The contents of the kit are listed in Attachment E. As a minimum, inspections shall be performed by the assigned organization each calendar quarter or after use to ensure operational readiness is maintained.
- 5.2.3 Completed checklists shall receive a supervisory review prior to placement in the EP test file.
- 5.2.4 Inspection checklists shall be retained for a minimum period of three years.
6.0 GENERAL OPERATIONS FOR ENVIRONMENTAL MONITORING TEAMS 6.1 Radiological and Physical Hazard Precautions 6.1.1 Perform applicable radiological monitoring practices upon the approach to an incident area, during on-scene operations, and prior t6leaving controlled areas.
6.1.2 Be attentive to potential changing conditions (i.e., onset of release'due'to fire, addition of runoff due to fire-prevention measures, movement of vehicle or container, deterioration of containers due to contact with spilled chemicals, or meteorological conditions). -'
6.1.3 Remain cognizant of individual doses and take action to limit doses ALARA, below individual routine exposure limits. Any decisions to embark on emergency operations which would result in exposures in excess of limits in 10 CFR 20 should be done in consultation with the CECC Radiological Assessment Manager.
6.1.4 Assume airborne radioactivity exists until there is direct evidence to the contrarv and use appropriate respiratory protection equipment, based on known or suspected airborne hazards.
CAUTION!: Because some shipments may contain materials that present toxic hazards that exceed radiological hazards, the team shall not enter a plume from a fire.:
Shipments of radioiodinfes with significant activity are common for medical
--purposes. Consider the use of KI if airborne radioiodine is suspected (and actual levels'are'uiiknown)'and exposure' rates greater of 25 mremlhr are'encountered.
- Revision
Radioactive Material CEC EPIP-23 Page 4 of 24 l Transportation Incidents C2 Pa 4 of 19 6.1.5 Shipments may also involve other hazardous materials (toxics, corrosives, flammables or reactives). Be attentive to contact with materials (either directly or from residues on radiological samples) and to the limitations of your personal protective clothing and equipment.
..NOTE: Material infor ation mayb'e listed on. shipping pers.. . Refer.to. te DOTEEergency-Response' Manual fo specific p rotective action recomme n's if placard 'orchemical ID
information is know\'n. Otherwise, t~ii
...... .. . osr r i e actionsdescribedinCECC. EPIP-9 asnoted on te bottom ofexposurerate and ...... nd
- .: ' ':,:activity dataform's,: :':: ' ::: : -
6.2 Communications for Environmental Monitoring Teams 6.2.1 If available, the Emergency Environs Monitoring radio is the primary means of communication if the incident location is within the system coverage.
6.2.2 If the radio system is not available, utilize best available alternate means (cellular or satellite telephone).
NOTE:
- .'..NOTEEPIP-9 ~~~~~:fi
Addtio'nl rado sy'te'minfo'rm'tion ad (dCECC.telepo6n~e n-u-mb'e-rs~a'ar rvddi. IEC C...I~Ji
. ...-cr-,....:. ... . - :.
6.3 Incident Scene Activities The monitoring team shall follow instructions from the CECC and in accordance with Attachment F. Deviations from exact compliance may be necessary in consideration of specific circumstances of the incident; however, personnel safety shall not be compromised.
7.0 LIST OF ATTACHMENTS Attachment A: EP Emergency Duty Officer (EDO) Checklist Attachment B: CECC Director Checklist Attachment C: CECC RAM Checklist Attachment D: CECC Environs Assessor and Field Coordinator Checklist Attachment E: Transportation Incident Equipment Attachment F: Incident Scene Activities (Environmental Monitoring Team)
Attachment G: Incident Area Survey Form Attachment H: On Scene Incident Report Attachment l: Fitness for Duty Program Administration - TVAN Call-In Sheet
Radioactive Material CECC EPIP-23 . Page5 of 24 Transportation Incidents Revision 19 Attachment A Page 1 of I EP Emergencv Duty Officer Checklist
- 1. Perform the following notifications:
Time/mnit.
'/ ' -' Confifin the CECC7DiiEcft6ihas been notified by the Operation-s'DDuItSpecialist.
Specialist (Name: _ Number: )
Notify the Manager, EP Program Planning and Implementation Section or designee. .. . _
I Notify the EP Program Manager responsible for EP emergency radiological monitoring equipment and vehicles or designee.
I Notify the Manager, EP State and Local Programs Section or designee.
I Notify the Nuclear Information
.... a.e.. ...... . Duty Officer.
(Name: ~Number: I
- 2. Establish initial operation of the CECC if it is to be utilized.
- 3. Assist any response team members in obtaining EP equipment and vehicles.
- NO.'nt kitassigneddto the CECC:ma' be located int CECC.
.'Ifavehicleis not cu.rre'ntly!available in Chat-taog :refer to EPIP9 ;forothervehicle
- .:-.:': .locations..A Portable.radio, cainera, film, an'd 'cameorders' may :also be available in the EP:'
..- Staff storageoarea.
Radiological
- :- monitoring equipment, supplies, and Potassium Iodide tablets may als'o be ' . '. ' ::::
available:inthe'CECC area...
- 4. The issuance of a cellular or satellite phone to the CECC management team should be considered.
Radioactive Material l CECC EPIP-23 lPage 6of24 Transportation Incidents C E Revision 1924 Attachment B Page 1 of 6 CECC DIRECTOR CHECKLIST
- 1. Obtain a completed:
'* '"Transportation Incident Checklist" (CECC EPIP-22, Attachment A)
- ODS Radioactive Material Shipment Notification form (from the Operations Duty Specialist if it was faxed by the shipper.) '
- -'NOTE:.'..Ifan"'on scene responder reque s im mdiate inor atin cnc'e.rnig8the shipment' o how...to res pond
.t th iide, i , t 're fer to p 'age'3 4, ' and.6' e':oK o this
... -::.:ttachment. Requeste inforation shallbe provided within 15 minutes ifom:..e':..
ti e that it is initia ly re q ested. ' ' "'on' - I ' ' ' ' : ' " ' ' '
- 2. Consult with the on duty CECC Radiological Assessment Manager and Nuclear Information Duty Officer to determine the necessary levels of staffing for the CECC.
Inform the ODS to notify selected staff and utilize Attachment I, "Fitness for Duty Program Administration" for documentation.
- 3. If determined necessary, begin preparations to dispatch a CECC Management team from the CECC consisting of management representatives from Emergency Preparedness, Radiological Control, and Communications to the incident site.
- 4. Consult with the on duty CECC Radiological Assessment Manager and determine if an environmental monitoring team should be dispatched.
.. ~~~~~~~~~~~~~~~~~~i rs.. . v .-. .... ..
- NOTE: The Radiological repnetmmembn. . . .Assessment .r.Manager
. . ... .. ..-r. ;.. gn is responsible o. for providing input, selecting
.: .-... :: -e spbnse't ea nmmem berts,; aihd-a:rrainig in'..g 'ra:n~s"p~ort'atio:n " -.. I
- 5. 'Consult with the on duty Radiological Assessment Manager and Nuclear Information Duty Officer to determine if the CECC Management Team should be released to proceed to the incident location.
- 6. Notify the Senior Nuclear Executive' of the incident.
- 7. Notify' the affected site Vice President of the incident I
I-Radioactive Material CECC EPIP-23 l Page 7 of 24 ITransportation Incidents Revision 19 Attachment B Page 2 of 6 CECC DIRECTOR CHECKLIST
- 8. Notify the following: (These notifications may be delegated.)
These'notification
.-. NOTE:. shall be made for all vehicle accident: situations and are optional .
- -NOTE: for other'minortincidents asdeemedapproprIate. :
Time/Init. (Refer to the TVA REND)
- / NRC Office of Inspection and Enforcement-Atlanta (consider notification of Rockville, Maryland if the incident is in a state outside of Region II)
MRC reporting requirements in 10 CFR 2202 do not require an accident to be repaired.
- / U.S. Department of Transportation. All accidents are not required to be reported to DOT, only those meeting 49 CFR 171.15)
/ State contact for incident location
/ Department of Energy (for information only)
/ American Nuclear Insurers (ANI)
- (Refer to the current CECC Reptrack Roster.)
- / Nuclear Information Duty Officer (Reptrack Roster)
- 9. Evaluate the appropriate level of TVA resources to commit and provide overall coordination of those resources.
- 10. Ensure that Federal, State, and local agencies are kept informed, as appropriate, of TVA activities and coordinate TVA's efforts with those agencies.
- 11. Review with the Radiological Assessment Manager any on site and offsite consequences and assess the adequacy and need for measures for the protection of the public.
- 12. Make recommendations to State and local agencies on protective measures for the public.
- 13. Maintain accurate records of decisions made and actions started and completed.
- Revision
Radioactive Material CECC EPIP-23 Page8 of 24 Transportation Incidents Revision 19 Attachment B Page 3 of 6 CECC DIRECTOR CHECKLIST INFORMATION FOR ON SCENE RESPONDERS
- 14. Ensure Public Information needs are addressed:
- 15. Ensure appropriate recovery actions are taken.
.:NOTE: 'Infor ation requested by.authorities forimmediate' action shall be provided withi 15minutes;:.
Information About Shipments
- a. If you are requested to provide information concerning the shipment, refer to the ODS RADIOACTIVE MATERIALHlMMENTE.QRM-which was telecopiedjo the.ODS when the shipment left the TVA facility. Provide any information on the form which may be requested by the on scene responder and tell this individual of any precautions
-that may be indicated on the form.
Information About Emereency Response
- b. If you are requested to provide information concerning Emergency Response, then provide any pertinent information contained in pages 4, Sand 6 of this Attachment.
Where To Get Assistance
- c. If you are requested to provide information which you have no knowledge of or is not -
available to you, contact the Shift Manager or the RADCON Lab at the affected plant for assistance at the telephone numbers listed below. If the shipment does not originate at a nuclear plant, the Shift Manager or Site RADCON Staff at a TVA nuclear plant may be able to provide information' concerning the radioactive material being shipped.
BFN RADCON Lab 256-729-7865 WBN SM 423-365-7860 WBN RADCON Lab 423-365-7865 If you are unable to contact the Shift Manager or RADCON Lab, then contact the
- Radiological Assessment Manager listed on the CECC Reptrack Roster or one of the Radioactive Materials Specialists listed in the REND.
- Revision
lRadioactive Material M CECC EPIP-23 } Page 9of 24 11 Transportation Incidents C 2 Revision 19 Attachment B Page 4 of 6 CECC DIRECTOR CHECKLIST INFORMATION FOR ON SCENE RESPONDERS EMERGENCY RESPONSE INFORMATION
.:NOTE:- '::'A copy.of this' information is' included with the shipping papers NOTE:...: .:.sent with the shipment.:
Immediate Hazards to Health
- a. External radiation from unshielded radioactive material.
- b. Internal radiation from inhalation, ingestion, or skin absorption.
- c. Radioactive material; degree of hazard will vary greatly, depending on type and quantity of radioactive material.
- d. Runoff from fire control or dilution water may cause the spread of radioactive contamination.
Risks of Fire and Explosion
- a. The primary potential for fire or explosion is from leaking fuel from the motor vehicle.
- b. Some of the packaged materials may bum, but none of them readily ignites.
- c. Radioactive oil (if present in a package) has a potential for fire.
Immediate Precautions To Be Taken
- a. Keep unnecessary people as far from the transport vehicle as practicable.
- b. Notify State or local police that an incident has occurred involving radioactive material.
- c. Isolate hazard area and deny entry.
- d. Detain uninjured persons and equipment exposed to radioactive material until arrival or instruction of Radiation Authority.
- e. Delay clean-up until arrival or instruction of the Radiological Authority with jurisdiction.
- f. Do not move damaged containers.
Radioactive Material I CECC EPIP-23 Page 10 of 24 Transportation Incidents l l Revision 19 -
Attachment B Page 5 of 6 CECC DIRECTOR CHECKLIST INFORMATION FOR ON SCENE RESPONDERS EMERGENCY RESPONSE INFORMATION Immediate Methods of Handling Fires
- a. Keep everyone at least 150 feet upwind and minimize breathing any of the smoke or fumes from the fire. Greater distances may be necessary if advised by Radiation Authority.
- b. Notify the fire department of the fire and inform them that the transport vehicle is carrying radioactive material.
c.,. Self-contained breathing apparatus (SCBA) and structural firefighter's protective clothing will provide limited protection.
- d. If advised by the Radiation Authority, move undamaged containers out of fire zone.
- e. Small Fires: Dry chemical, C02, Halon, wvater spray, or standard foam.
- f. Large Fires: Water spray, fog (flooding amounts).
- g. For massive fire in cargo area, use unmanned hose holder or monitor nozzles.
- h. Fight fire from maximum distance. Stay away from ends of tanks.
- i. If water pollution occurs, notify the appropriate authorities.
Immediate Methods for Handling Spills or Leaks in the Absence of Fire
- a. Establish the restricted area and keep people outside of the area and on the upwind side (if possible).
- b. Enter the spill area only to aid injured persons; limit entry to the shortest possible time.
- c. Unless authorized by the Radiation Authority, do not touch damaged containers or spilled material.
- d. Damage to outer container may not affect primary inner container.
- e. Small Liquid Spills: Take up faith sand, earth or other noncombustible absorbent material.
- f. Large Spills: Dike far ahead of liquid spill for later disposal.
- ~~~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
Radioactive Material CECC EPIP-23 Page 1l of 24~
Transportation Incidents RaIocieMtraPae1of2 Revision 19 Attachment B Page 6 of 6 CECC DIRECTOR CHECKLIST INFORMATION FOR ON SCENE RESPONDERS EMERGENCY RESPONSE INFORMATION Preliminary First Aid Measures
- a. Call emergency medical care if there are any suspected injuries.
- b. Advise medical care personnel that injured persons may be contaminated with radioactive material.
- c. Remove injured persons from any possible contaminated areas (unless the injuries are of a severe nature that would make movement inadvisable).
- d. If not affecting injury, remove and isolate contaminated clothing and shoes; wrap victim in blanket before transporting.
- e. If not injured, detain persons and equipment exposed to radioactive material until arrival or instruction of Radiation Authority.
Radioactive Material CECC EPIP-23 Page 12 of 24 Transportation Incidents Revision 19 Attachment C Page 1 of 1 CECC RAM CHECKLIST
- 1. Review incident information. (Refer to CECC EPIP-22, Attachment A completed by the Operations Duty Specialist and an) radioactive material shipping papers that may have been telecopied to the ODS.)
- 3. Select and activate appropriate CECC Radiological staff and Response Team members.
Refer to REND for notification listings. Ensure Attachment I is utilized for any call outs
.NOTE '.'A' es'on. TseT should be dis patchedifr d i at'ria.s..requir'.
. .. ack.in g:..In...
.' 'hese eVents ' oraioacti'-a enia sp~e i utuld accm pn' -he Rspon sT i te...
chnical' assistance.'Personnel
' ' ' i selectedifor :entr into:radiolog.ical. ncidentres
.for.fi ld'
,.:,m
onitoring
... ;:..';.': ~~~~~~~~~~~~~~~.
duties shall b.e Emergen...i......P ..... ..... ............ ....
l ;....
in .. ...
qu.fe........... ...... ....... ..... .;;.;.
The following is provided to -assisttilrnctifications-fuse as appropriate)
Environs Assessor: -contacted:---
Field Coordinator: -- --- - - Contacted-Radioactive Material Specialist: Contacted:-
Response Team Member: Contacted:_
Response Team Member: Contacted:_
Dose Assessor: Contacted:_
Meteorologist:_ Contacted:-
Mode of Transportation: Means of
Contact:
- 4. Coordinate TVA's radiological assessment activities and keep the CECC Director advised of the status of the TVA response efforts and of radiological assessments.
- 5. Ensure personnel are briefed on known or anticipated conditions and that they, are informed of the agency requesting TVA assistance.
- 6. Ensure that all immediate notifications are made as required in the TVAN Radioactive Material Shipment Manual.
- 7. Ensure recovery actions are completed, equipment is returned to an in-service status, and that personnel dosimetry/dose assessment needs are performed.
Radioactive Material CECC EPIP-23 l Page 13 of 24 Transportation Incidents C E Revision 19 AttachmentD Page I of I CECC ENVIRONS ASSESSOR AND FIELD COORDINATOR CHECKLIST Environs Assessor
- 1. If the shipment originated from a TVA nuclear site, obtain a copy of the shipping papers that would have been telecopied to the ODS.
- 2. Provide support for field team preparation and dispatch. Ensure equipment and staff needs are completed.
- 3. In coordination with the RAM, determine response-specific exposure limits and Remaining Allow.able-Doses for field team personnel and inform them of same.
l NOTE: Crosseference exposure control, protective action levels ad dose logs with CECC EPIP-9.:
- 4. Confirm Response Team personnel eligibility for expected actions in field response (refer to personnel requirements in CECC EPIP-9).
- 5. Determine means of communication to be used by the Response Team (operate CECC base radio console as applicable).
- 6. Review field monitoring instructions per CECC EPIP-9 which apply to the response.
- 7. Maintain a log of Response Team actions and incoming information reported by the Response Team.
Field Coordinator
- 1. Ensure that departure preparations are complete and in accordance with any special instructions from the RAM.
- 2. Accompany Response Team members to the incident location and supervise TVA personnel at the incident scene per section 6.0 and Attachment F.
- 3. Track TVA personnel exposures on scene.
- 4. Unless instructed othervise by the RAM, serve as the primary TVA interface with on scene authorities and ensure the CECC is kept informed of operations.
- 5. Ensure necessary surveys are performed and documented.
- 6. Ensure recovery actions are completed and any TVA equipment used is returned to service following operations.
Radioactive Material CECC EPIP-23 Page 14 of 24 lTransportation Incidents - -Revision 19 --
Attachment E Page 1 of2 TRANSPORTATION INCIDENT EOUIPMENT
.... :.~~~
- .. .- .1 ......... T r..... ir. it. 7 .-:-2SI. .hi.... i
.-~~~~~~~ .: . ':' :i.: :: ', m:'ar' ' k.:'
te
- :'-'Re s:
I CECC EPIP-23 (Controlled copy) Rev:
5 CECC EPIP-23 Attachment G'(working copy) i Rev:
I CECC EPIP-9 (Controlled copy) Rev:
- 5 CECC EPIP-9, Shift Information Sheet and Team Dose Rev:
Tracking Log (working copy)
- 5: CECC EPIP-9 Emergency Authorization ( vorking copy) Rev:
. 10 CECC EPIP-9 Field Team Measurement Log (working Rev:
. copv)
W. -*'
Conent Kit
'&enera
'£r 3_ TLDs (list expiration date) :Date:
3 Direct reading dosimeters (0-200 mrem range) .
I Dosimeter charger with batterv 0
- Package I1(list expiration) Date:
I_ Calculator' -- -
3 Mlechanical pencils and pens (each)
I1 US Atlas-:
I Logbook .
I DOT Emergency Response Guidebook . Year:
- Revision
Radioactive Material ECCEPIP- 23 Page 15 of 24 Transportation Incidents Revision 19 Attachment E Page 2 of 2 TRANSPORTATION INCIDENT EOUIPMENT
- .. ... ...... ...... : General Kit Contents: .. ..... .:, :...
Item
~~~~~~~~~... Remark.....s..
1 Roll 2-inch Radiation Symbol warning tape 12 Radioactive Material ID tags 6 Radiation/Contamination Area warning signs 400 ft. Yellow and magenta ribbon or rope -
10 Large yellow plastic bags 10 Small vellow plastic bags .
10 Zip-lock sample bags (approx. 6" and 10") ,
20 Adhesive sample bag labels 5 Plastic liquid sample containers (min. 500 ml) 5 Charcoal air sampler cartridges 5 Silver Zeolite air sampler cartridges I Air sampler head (for Radeco H 809V) 10 Air sampler prefilters 10 Plastic petri dishes 1 Pair tweezers 100 Smears with folders 6 Disposable coveralls (anti-contamination) 6 Canvas hoods (anti-contamination) 6 Skull caps 6 pr. Pair of rubber overshoes 6 pr. Yellow plastic booties 12 pr. Rubber gloves (anti-contamination) 12 pr. Glove liners I pr. Work gloves (leather/canvas) 12 pr. Latex gloves (surgeon's type)_
I Roll of 2-inch duct tape I Can spray paint (for area marking) 2 Flash lights xv/batteries '
-i-i I Stored location of kit and equipment:
Additional comments:
Inspected by: Date:
Supervisory Review: Date:_
- Revision
Radioactive Material CECC EPIP.-23 Page 16 of 24 Transportation Incidents Revision 19 Attachment F Page I of 5 INCIDENT SCENE ACTIVITIES (Environmental Monitoring Team) 1.0 Actions Immediately Upon Arrival 1.1 Each TVA person entering radiation exposure fields shall wear a TLD badge, and a 200 mrem direct reading dosimeter. Record data on CECC EPIP-9 Dose Log.
1.2 Place a radiation survey meter in the ON position on a lower range scale to monitor any increase in background as you approach the area.
1.3 Locate the senior authority at the incident site, identify yourself, and indicate that you are responding at the request of (i.e., the State Division of Radiological Health, Emergency Management Agency, -etc.).
1.4 Obtain a briefing from the senior authority on the physical hazards present (chemical, fire, electrical, etc.).
1.5 As necessary, report Attachment H information to the CECC as soon as possible, preferable before proceeding to the followving steps.
1.6 If requested by the on scene authority, proceed with the remainder of guidance in this attachment.
. ~~
~ ........
~ ~ ..... ~.. .. ~.--.. ~ ~ .
- NOTE: T'A t sobligation is to proide radiological su p ' scen local h
'i 'loc andn ateauthorities have jurs icti i the r. e..pons.
...... effort ev'nifa:TA
- "v' ehicle
' :' ' or
::shipment' is inVolved in'th'e'incidefnt., .......... ..' ' ' :
2.0 Establishment of Area Control 2.1 Request the on scene authority to have people move back from the incident. Nonessential persons and onlookers should be'm6ved a safe distance awvay, but be aware that some may already be contaminated if the source has been breached. -
Recommend an attempt to identify these persons (i.e., obtain name, address, phone numbers, etc.)
and as necessary, isolate these persons for the purpose of performing a contamination survey prior to release. (This may also apply to first responders.)
l NOTE: Persons suspected of contamination con'ccr'ms should'immrediately bc'adv;ised not to cat, drink,l I: -: : or smoke'u'ntil surveyed. ':I-: '
Radioactive Material CECC EPIP-23 Page 17 of 24 ITransportation Incidents Revision 19 Attachment F Page 2 of 5 INCIDENT SCENE ACTIVITIES (Environmental Monitoring Team) 2.2 Advise fire and rescue personnel to stay upwind or crosswind from the location of the source, if possible. Firefighting and rescue efforts should not be interrupted.
CAUTION!.: :.' ':The life-threatening hazards"associated-with a vehicle fireandthe potential for :
- .:exp losions faroutweig the radioloic haardsinalmost' n se .
..:.:.......... :' DO.NO EN R A LUME FROM F R !: .
2.3 If fire fighting efforts are in progress, determine the path of the water runoff and, if possible, advise on the containment and control of runoff.
- NOTE: Thisappliesduring ainfallfas. well. Always assume ht the source container has fuleduntil l" : .: ' .' .:: confirmed intact. ... .. ..:.'.... .. ..
2.4 If rescue of injured persons is still in progress, offer to survey the patient to assist in any notifications to receiving hospitals.
2.5 Establish a control area using radiation warning rope and signs using guidance from the DOT Emergency Response Guidebook and from best available information. (The initial posted area may be reduced in size as later survey results indicate.)
2.6 If radioactive material has spilled, consider plans to cover/contain the material to reduce its spread. The use of plastic sheeting, plastic bags, or fire department salvage or rescue covers may be used to prevent dispersion by wind, etc.
3.0 Survey of the Incident Scene 3.1 Don appropriate personal protective clothing or equipment in preparation for entry into the incident area. Remember to assume that the area may already have been contaminated and that airborne hazards exist, UNTIL INFORMATION IS KNOWN TO THE CONTRARY.
3.2 If a fire prevents surveying the area for the foreseeable future, analysis of a sample of the runoff water may indicate whether the source container has been breached. After best available analysis, double bag the sample to prevent leakage until a more detailed analysis can be obtained.
CAUTION!: Be attentive to the possibilitv of chemical contaminates in the runoff. Collect samples
- .: . :. only if safe to do so and if the container is able to withstand contact with the liquid.
Radioactive Material Page 18 of 24 Transportation Incidents CECC EPIP-23 Revision 19 -
Attachment F Page 3 of 5 INCIDENT SCENE ACTIVITIES (Environmental Monitoring Team) 3.3 If fire and/or smoke is present, and an elecfrical source is available, attempt to obtain an air sample using the following procedure:
3.3.1 Prepare the air sampler cartridge using a charcoal cartridge (use silver zeolite if Iodine 131 is suspected) and particulate prefilter.
3.3.2 Secure (tape) the extension cord connection with'the air sampler plug. While still in a safe area, briefly start the air sampler to adjust the'flowv rate to 60 liters per minute (2 cfin), then terminate the sample by depressing the STOP key and prepare the sampler to start with the next depression of the START key.
3;3.3 Request that a firefighter in appropriate protective clothing and respiratory protection place the sampler in the plume and depress the START key.
l `CAUTION!: ". ':Be attentiveto electrical hazard s frm ' ater runoff-:-:
3.3.4 Run the sample for 5 minutes unless instructed otheriise. Stop the air sampler by disconnection of the extension cord with the power source.
3.3.5 If a sampling van is present, analyze the cartridge and prefilter according to EPIP-9.
If the sampling van'is not available, survey the sample using the Bicron Surveyor 50 for a gross indication of the presence oi absence'of radioactivity.
l':CAUTIO l!CAUTION!'.'
'Consider the po'ssibility:of
-hadlete esamlesY'Al the pen sin eers ofndRaon' loves. recount After 30 3.4 . If the on scene authority has declared the area to be free of other physical hazards (fire, chemical, electrical, etc.), one person should prepare to make an entry to the control area to perform radiological monitoring. This should be done only with the permission of the on-scene authority.
The other person should remain in the clean area to coordinate communications Xwith the on scene incident command and CECC. , ' - -
3.5 Establish some means of communications with the person performing the entry into the controlled area. Approach the vehicle (or source) from an upwind direction. The Gieger-Mueller Survey Meter (GMSM) should be adequate to obtain exposure rates.
I -
Radioactive Material CEC EPI- Pae 19 of 24 Transportation Incidents C C E 2 Revision 19 Attachment F Page 4 of 5 INCIDENT SCENE ACTIVITIES (Environmental Monitoring Team)
.:NOTE: ,Allo'a'bleDOT'radiatio'n limnits .ra on a package ranges from';les t '1'emr I up to'
: ' 1000 mrerhr' dep'endinggon p.packagey'p' and. methdo f trnspr t t. Conuil tthe shipping:
- . papers (if available) for the expected'do.se ates on the package and ehicle exterio.r.
'.'i..... Additional advicemay be available froma TVA Radioactive Materialspecialist:
3.6 After exposure rates have been determined and recorded, perform a contamination survey. All radioactive material outside its container should be considered transferable contamination, and smear surveys will also be made. Any object that show's detectable contamination above background shall be considered contaminated no matter how small the amount of activity.
- .,NOTE.,: Consider tfie' tpe: f isotope emisioii wh :electingth gty -e of detetioninstrument.' DOT:
contaminaio'n't .limi a*u.p' to 2200 dpmi I100c. ' b' 'tagamaand'220;dp/100 cm2 :
alpha (transferable) on a package. Consult the shipping 'papers (if available) for. vehicle and package contanation.measurements..:: ::'
3.7 The person outside the area should attempt to draw and complete a survey map (Attachment G).
3.8 Keep the CECC informed of the survey results.
3.9 If the source container has failed, or if its condition is not known, frisk personnel at the site.
Recommend that anyone found to be contaminated above BG levels be evaluated by local RAD Health Authorities. Because TVA has no legal authority at the site, TVA personnel cannot make decisions on releasing contaminated persons.
3.10 Advise the on scene authority on the packaging or control of equipment until surveys can be performed (after personnel needs have been addressed).
3.11 Consult with emergency responders to determine the priority of equipment which need to be surveyed for return to service.
4.0 Additional Services for Transportation Incidents 4.1 Decontamination of persons and equipment (even TVA equipment) is the responsibility of State authorities. If requested to assist, contact the CECC for authorization. It may be possible to provide coveralls for contaminated persons, but keep enough to be able to perform your field monitoring duties.
I
Radioactive Material CECC EPIP-23 Page 20 of 24 Transportation Incidents Revision 19 Attachment F Page 5 of 5 INCIDENT SCENE ACTIVITIES (Environmental Monitoring Team) 4.2 As applicable, inform the on scene authority at the scene that persons injured and sent to hospitals in the area may be contaminated. If requested by State officials, assistance may be provided at a medical facility if authorization is provided by the CECC.
4.3 Support the coordination of arrangements for the disposal of radwaste.
4.4 The team may support clean-up efforts at the scene as requested by the State until no longer needed or until instructed to depart by the CECC. Consult with the CECC before departing the area.
Radioactive Material CECC EPIP-23 . Page 21 of 24 - ll Transportation Incidents l I -Revision 19 Attachment G Page 1 of 2 INCIDENT SURVEY FORM All exposure rate readings in mrem/hr; (contact/30 cm/I meter).
All contamination levels in dpm/100 cm 2 .
._-_-_::::_.-_:_:_._ .SMEAR SURVEYS
- 1. l 8. 15.
- 2. 9. 16.
- 3. 10. 17.
- 4. 11. 18.
_._ 12. 19
- 6. 13. 20.
- 7. 14. 21.
CONTINUED ON BACK
.1I Radioactive Material CECC EPIP-23 l Page 22 of 24 I Transportation Incidents C E Revision 19 Attachment G Page 2 of 2 INCIDENT SURVEY FORM Date Time Location Survev Meter Type: __Serial #
Survev Meter Type: Serial_#
Survey Meter Type: Serial #_l ISurvey Meter Type: I _ISerial #_I Additional Comments: Description of incident area, personal protective clothing or protective measures taken during survey, etc.
Signature: Date:
Supervisor: Date:
' ! I I Radioactive Material CECC EPIP-23 l Page23 of 24 Transportation Incidents C 2 Revision 19 Attachment H Page 1 of l ONSCENE INCIDENT REPORT
- 1. Location of incident
- 2. Radioisotopes involved
- 3. Activity of isotopes
- 4. Markings: LSA SCO Radioactive
- 5. Description of packages:
- 6. Physical and chemical forms:
- 7. Package identification (specify type A or B, etc.)
- 8. Shipper, carrier, and destination:
- 9. Injuries and receiving hospitals.
- 10. Release(s) of shipment contents to environment:
- 11. Other hazardous materials present (ID numbers, etc):
- 12. Incident description and present status, terrain (including dowvnwind and do%%mslope farms and residential areas).
- 13. WVeather conditions.
- 14. Authorities at the scene.
- 15. Phone number (if not using van radio).
- 16. Results of sunreys. (Report using CECC EPIP-9 data forms)
NOTE: Much of this information can be found on the shipping papers. If lost or destroyed in the incident, the driver may be able to help. If all else fails, markings on the vehicle may enable CECC personnel to contact the carrier for information.
Radioactive Material CECC EPIP-23 Page 24 of 24 Transportation Incidents Revision 19 ATTACHMENT I Page 1 of I FITNESS FOR DUTY PROGRAM ADMINISTRATION TVA NUCLEAR CALL-IN SHEET Person Calling: Date:
- :Alcohol 5 -- ....... ... ..-.....
Name., ': :.'.':::: 'Hrs;Prior~to
- ' ' Fit :: ...for ......... ':DutyOfficialC,'. : :.Time"':
T e N d.,o . , ..... . .. .C T...... ' . men
- d. .. s
_-_- _::_________.:_.:_- _.:_::_--_ Called Reo: -' )-.::
- YN ': (Y IN)::: .. ...
.'ald=..
t 1 t 4 1 4 I .1
- 4. I 4- I 4
.1. 1 1. 1 4.
- 4. .4 4- 4 4~~~~~~~~~~~~
- 4. 4 4 .4 4
- 4. 4. 1 4. 4.
4- 4 I .1. 4.
4.. .