ML023450103
| ML023450103 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Watts Bar, Sequoyah  |
| Issue date: | 12/06/2002 |
| From: | Burzynski M Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML023450103 (44) | |
Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801 December 6, 2002 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 Tennessee Valley Authority Docket Nos.
50-259 50-260 50-296 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 EPIP EPIP-8 EPL Rev.
23 EFFECTIVE DATE 11/22/02 11/22/02 If you have any questions, please contact Terry Knuettel at (423) 751-6673.
Sincerely,
-Mo44k.Burzyn'ski Manager Nuclear Licensing Enclosures cc:
See page 2 Pr"r. ',
-e, j PapF 50-390 50-391 50-327 50-328
) )
U.S. Nuclear Regulatory Commission Page 2 December 6,
2002 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 37379-3624 NRC Senior Resident Inspector
[No enclosures, by request Watts Bar Nuclear Plant of site resident]
1260 Nuclear Plant Road Spring City, Tennessee 37381
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u _________________________ a Date Ext.
Acceptance:
Signature Date TVA 400748 (8-97) [08-97]
Page 1 of 1 SPP-2.3-3 [08-29-97]
Contact:
DOCUMENT RELEASE AND FILING INSTRUCTIONS Page 1
of 1
Release No.
To:
Management Services/RIM/EDM Prepared By:
Gail White Other Address:
Extension:
751-2108 Date Submitted to Management Organization:
AS&P Services/RIM/EDM:
Address:
Attached are: (select one)
Release and Submitted for:
Z QA Records/Documents
[
Distribution LI Non-QA Records/Documents
[
Retention REC NO.
ACCPT REMOVE INSERT DOCUMENT NUMBER REV PAGES Y
N DATE PAGES PAGES CECC-EPIP List of Effective Pages 8
11/22/02 1 - 8 1 - 8 CECC EPIP-8, cover sheet 23 1
cover sheet cover sheet CECC EPIP-8, rev. log 23 y
Page 1 of 1 SPP-2.3-3 [08-29-97]
CECC-EPIP EPL Page 1 of 8 11/22/02 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.
Table of Contents Subdivision List of Effective Pages Page No.
1 of 8 2 of 8 3 of 8 4 of 8 5of 8 6 of 8 7 of 8 8 of 8 1 of 2 2 of 2 EPIP-1 Appendix A Appendix B Appendix C Appendix D Appendix E Appendix F Appendix G Appendix H Cover Sheet Rev. Log 1 of 30 2 of 30 3 of 30 4 of 30 5 of 30 6 of 30 7 of 30 8 of 30 9 of 30 10 of 30 11 of 30 12 of 30 13 of 30 14 of 30 15 of 30 16 of 30 17 of 30 18 of 30 19 of 30 20 of 30 21 of 30 22 of 30 23 of 30 24 of 30 25 of 30 26 of 30 27 of 30 28 of 30 29 of 30 30 of 30 Rev. No.
11/22/02 11/22/02 11/22/02 11/22/02 11/22/02 11/22/02 11/22/02 11/22/02 10/17/02 10/17/02 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36 36
CECC-EPIP EPL Page 2 of 8 11/22/02 List of Effective Pages (Continued)
Procedure No.
EPI P-2 Subdivision Appendix A Appendix B EPIP-3 Appendix A Appendix B Appendix C EPIP-4 Appendix A Appendix B Appendix C EPIP-5 Appendix A Appendix B Appendix C EPIP-6 Appendix A Appendix B Appendix C Cover Sheet Rev. Log 1 of 23 2 of 23 3 of 23 4 of 23 5 of 23 6 of 23 7 of 23 8 of 23 9 of 23 Rev. No.
29 29 29 29 29 29 29 30 30 30 30 30 30 30 30 30 30 Page No.
Cover Sheet Rev. Log I of 5 2 of 5 3 of 5 4 of 5 5 of 5 Cover Sheet Rev. Log 1 of 8 2 of 8 3 of 8 4 of 8 5 of 8 6 of 8 7 of 8 8 of 8 Cover Sheet Rev. Log 1 of 8 2 of 8 3 of 8 4 of 8 5 of 8 6 of 8 7 of 8 8 of 8 Cover Sheet Rev. Log 1 of 8 2 of 8 3 of 8 4 of 8 5 of 8 6 of 8 7 of 8 8 of 8 31 31 31 31 31 31 31 31 31 31 33 33 33 33 33 33 33 33 33 33 23 23 23 23 23 23 23 23 23 23 23
Procedure No.
EPIP-6 (Continued)
Appendix E Appendix F Appendix G Appendix H Appendix I Appendix J Appendix K EPIP-7 Appendix A Appendix B Appendix C Appendix D Appendix E Appendix F EPIP-8 Appendix A Appendix B Appendix C Appendix D Appendix E CECC-EPIP EPL Page 3 of 8 11/22/02 List of Effective Pages (Continued)
Page No.
10 of 23
.11 of 23 12 of 23 13 of 23 14 of 23 15 of 23 16 of 23 17 of 23 18 of 23 19 of 23 20 of 23 21 of 23 22 of 23 23 of 23 Cover Sheet Rev. Log 1 of 15 2 of 15 3 of 15 4 of 15 5 of 15 6 of 15 7 of 15 8 of 15 9 of 15 10 of 15 11 of 15 12 of 15 13 of 15 14 of 15 15 of 15 Cover Sheet Rev. Log 1 of 30 2 of 30 3 of 30 4 of 30 5 of 30 6 of 30 7 of 30 8 of 30 9 of 30 10 of 30 11 of 30 12 of 30 13 of 30 14 of 30 Subdivision Appendix D Rev. No.
23 23 23 23 23 23 23 23 23 23 23 23 23 23 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23
CECC-EPIP EPL Page 4 of 8 11/22/02 List of Effective Pages (Continued)
Procedure No.
Subdivision Page No.
Rev. No.
EPIP-8 (Continued)
Appendix F 15 of 30 23 16 of 30 17 of 30 18 of 30 19 of 30 20 of 30 21 of 30 22 of 30 23 of 30 24 of 30 25 of 30 26 of 30 27 of 30 28 of 30 29 of 30 30 of 30 Cover Sheet Rev. Log 1 of 46 2 of 46 3 of 46 4 of 46 5 of 46 6 of 46 7 of 46 8 of 46 9 of 46 10 of 46 11 of 46 12 of 46 13 of 46 14 of 46 15 of 46 16 of 46 17 of 46 18 of 46 19 of 46 20 of 46 21 of 46 22 of 46 23 of 46 24 of 46 25 of 46 26 of 46 27 of 46 28 of 46 29 of 46 23 23 23 23 23 23 23 23 23 23 23 23 23 23 23 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 Appendix G Appendix H Appendix I Appendix J EPIP-9 Appendix A Appendix B Appendix C Appendix D Appendix E Appendix F Appendix G
CECC-EPIP EPL Page 5 of 8 11/22/02 List of Effective Pages (Continued)
Procedure No.
EPIP-9 (Continued)
Subdivision Appendix H Appendix I Appendix J Appendix K Appendix L Appendix M Appendix N Page No.
30 of 46 31 of 46 32 of 46 33 of 46 34 of 46 35 of 46 36 of 46 37 of 46 38 of 46 39 of 46 40 of 46 41 of 46 42 of 46 43 of 46 44 of 46 45 of 46 46 of 46 Rev. No.
25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 EPIP-11 Appendix A Appendix B Appendix C Appendix D Appendix E Appendix F Appendix G Appendix H Appendix I Appendix J EPIP-12 Cover Sheet Rev. Log 1 of 17 2 of 17 3 of 17 4 of 17 5 of 17 6 of 17 7 of 17 8 of 17 9 of 17 10 of 17 11 of 17 12 of 17 13 of 17 14 of 17 15 of 17 16 of 17 17 of 17 Cover Sheet Rev. Log 1 of 19 2 of 19 3 of 19 4 of 19 5 of 19 6 of 19 7 of 19 8 of 19 9 of 19 10 of 19 11 of 19 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 18 18 18 18 18 18 18 18 18 18 18 18 18
CECC-EPIP EPL Page 6 of 8 11/22/02 List of Effective Pages (Continued)
Procedure No.
EPIP-12 (Continued)
Subdivision 0 0 EPIP-13 Appendix A Appendix B EPIP-14 Appendix A Appendix B Appendix C Appendix D Appendix E Appendix F Appendix G Appendix H Page No.
12 of 19 13 of 19 14 of 19 15 of 19 16 of 19 17 of 19 18 of 19 19 of 19 Cover Sheet Rev. Log 1 of 6 2 of 6 3 of 6 4 of 6 5 of 6 6 of 6 Cover Sheet Rev. Log 1 of 25 2 of 25 3 of 25 4 of 25 5 of 25 6 of 25 7 of 25 8 of 25 9 of 25 10 of 25 11 of 25 12 of 25 13 of 25 14 of 25 15 of 25 16 of 25 17 of 25 18 of 25 19 of 25 20 of 25 21 of 25 22 of 25 23 of 25 24 of 25 25 of 25 EPIP-15 Cover Sheet Rev. Log 1 of 5 2 of 5 3 of 5 Rev. No.
18 18 18 18 18 18 18 18 8
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CECC-EPIP EPL Page 7 of 8 11/22/02 List of Effective Pages (Continued)
Procedure No.
EPIP-15 (Continued)
Subdivision Appendix A Appendix B EPIP-17 Appendix A Appendix B Appendix C Appendix D Appendix E Appendix F Appendix G Appendix H Appendix I Appendix J Appendix K Appendix L Appendix M Appendix N EPIP-18 Appendix A Appendix B EPIP-1 9 Appendix A Cover Sheet Rev. Log 1 of 27 2 of 27 3 of 27 4 of 27 5 of 27 6 of 27 7 of 27 8 of 27 9 of 27 10 of 27 11 of 27 12 of 27 13 of 27 14 of 27 15 of 27 16 of 27 17 of 27 18 of 27 19 of 27 20 of 27 21 of 27 22 of 27 23 of 27 24 of 27 25 of 27 26 of 27 27 of 27 Cover Sheet Rev. Log 1 of 6 2 of 6 3 of 6 4 of 6 5 of 6 6 of 6 Cover Sheet Rev. Log 1 of 11 2 of 11 3 of 11 4 of 11 5 of 11 6 of 11 7 of 11 Page No.
4 of 5 5 of 5 Rev. No.
0 0
17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 17 8
8 8
8 8
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8 12 12 12 12 12 12 12 12 12
Proceaure No.
CECC-EPIP EPL Page 8 of 8 11/22/02 List of Effective Pages (Continued)
,sUDalivSiOn EPIP-19 (Continued)
SPane No Revx No Appendix B 8 of 11 9 of 11 10 of 11 11 of 11 EPIP-21 Appendix A Appendix B EPIP-22 Attachment A Attachment B EPIP-23 Attachment A Attachment B Attachment C Attachment D Attachment E Attachment F Attachment G Attachment H Attachment I Cover Sheet Rev. Log 1 of 4 2 of 4 3 of 4 4 of 4 Cover Sheet Rev. Log 1 of 7 2 of 7 3 of 7 4 of 7 5 of 7 6 of 7 7 of 7 Cover Sheet Rev. Log 1 of 24 2 of 24 3 of 24 4 of 24 5 of 24 6 of 24 7 of 24 8 of 24 9 of 24 10 of 24 11 of 24 12 of 24 13 of 24 14 of 24 15 of 24 16 of 24 17 of 24 18 of 24 19 of 24 20 of 24 21 of 24 22 of 24 23 of 24 24 of 24 12 12 12 12 13 13 13 13 13 13 19 19 19 19 19 19 19 19 19 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 Paae No_
RAy Nn
CECC EPIP Coversheet APPROVAL Entire Page Revised
CECC-EPIP-8 DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR PLANT RADIOLOGICAL EMERGENCIES REVISION LOG Rev. No.
0 1
2 3
4 5
6 7
8 9
Entire Page Revised Date 3/22/88 11/18/88 12/12/88 4/26/89 9/19/89 10/26/89 5/21/91 10/17/91 05/13/93 11/22/93 11/30/93 06/24/94 6/27/95 1/17/96 10 11 12 13 Revised Pages All (Changed from IPD to EPIP) 2-7, Apps. A, B, C, & D Appendix A All App. C All App. B, pgs. 1-4; Appendix C, pgs. 1-2; App. D, pg. 1 App. B, pgs. 2-4; App. C, pg. 1.
1-4; App. A; App. B, pg. 1, 3, & 4; and App. G; App. C deleted. All pages issued.
Pg. 4; App. B, pgs. 1&4; App. D changed to App. C; App. E changed to App. D; App. F changed to App. E; and App. G changed to App. F.
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.
App. B, pg. 1; App. D, pgs. 2-5; App. F; App. J added. All pages issued.
Pg. 1; App. A; App. B, p.3; App. C, p. 5; App. D, p. 2; App. G, pgs. 4 and 6 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 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.
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.
Editorial changes, update manual dose assessment methodology, update preliminary assessment table, revise river miles on tables in Appendix G, annual review. All pages issued.
Revise default river flow rate for BFN, revise responsibilities of Norris Lab, add water intake tables. All pages issued.
14 5/30/96 15 10/30/96 16 5/30/97 17 8/8/97
CECC-EPIP-8 DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR PLANT RADIOLOGICAL EMERGENCIES REVISION LOG (Continued)
Rev. No.
18 19 20 21 22 23 Entire Page Revised Date 6/9/98
-6/4W98 RR 10/27/98 5/20/99 9/8/00 3/30/01 11/22/02 Revised Pages Annual review. Organization title changes. In Appendix D clarify Type I and Type II formulas. Remove Tennessee River miles from tables. All pages issued.
Correct reference to CECC EPIP-1 Appendix on Appendix J.
Annual review. Editorial and clarification changes, revise public water use tables. All pages issued.
Annual review. Editorial changes. All pages issued.
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 project.
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 1 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES Table of Contents 1.0 P U R P O S E................................................................................................................
2 2.0 S C O P E.....................................................................................................................
2 3.0 STAFFING 3.1 Activation and Notification..........................................................................
2 3.2 S hift C hange.............................................................................................
2 3.3 T erm ination.............................................................................................
.. 2 4.0 DOSE ASSESSOR INTERFACES 4.1 Radiological Assessment Manager/ Coordinator.................................... 3 4.2 M eteorologist...........................................................................................
3 4.3 Environs Assessor / Field Coordinator....................................................
3 4.4 Core Damage Assessor............................................................................
4 4.5 Technical Support Center.......................................................................
4 4.6 R iver O perations......................................................................................
4 4.7 State (R adiological)..................................................................................
4 5.0 PERFORMING DOSE ASSESSEMENTS 5.1 D ata V erification.......................................................................................
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 R E FE R E N C E S.....................................................................................................
6 7.0 A B B R EV IA TIO NS................................................................................................
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........... 20 H
WATER DOSE Data Inputs...................................................................
21
- 1.
Manual Methodology for Assessing Liquid Releases to the River.......... 22 J.
Public and Industrial Surface Water Supplies........................................
28 Entire Page Revised
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 2 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES 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 is a 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).
Entire Page Revised
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 3 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES 4.0 DOSE ASSESSOR INTERFACES 4.1 Radiological Assessment Manager I Coordinator (RAM/RAC)
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 is not 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 is also 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.
Entire Page Revised
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 4 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES 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 verifier will 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.
Entire Page Revised
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 5 of 30 PLANT RADIOLOGICAL CECC EPIPP-8 Revision 23 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 / 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).
Entire Page Revised
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 6 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES 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 Users 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 Entire Page Revised
APPENDIX A Dose Assessor Initial Reporting Checklist (steps do not need to be performed in sequential order)
- 1.
SIGN IN on the CECC staffing board and don your CECC position tag.
- 2.
START Iogkeeping 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.
Entire Page Revised 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)
If 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).
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 8 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES APPENDIX B Dose Assessor Shift Change 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.
Dose methodologies being used.
Identification of problems in response capability.
Identification of contacts at the TSC, State, Core Damage staff and RO 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/turn 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 Entire Page Revised
FRED Appendix C Page 1 of 2 RED Data Inputs FRED / RED Data Inputs NOTE:
The source for this information may be the site Technical Support Center or from ICS.
- 1.
Plant:
- 2.
Meteorological data will be: Fl ACTUAL or Fl EXERCISE (confirm with drill controller).
- 3.
Release start time:
Eastern F-] 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):
SQN/WBN BFN El Shield Bldg LI Stack El Near ground F1 Radwaste Zone (of Rx Bldg)
El Refueling Bldg zone (of Rx Bldg)
El Reactor Bldg zone (of Rx Bldg)
El 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 data is unavailable.
- 7.
Release Type:
ElRCS ElCore Damage El-User Specified E]Gap (default)
E]Fuel 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 Iodine131 microCi/cc Ratio = Release Type:
Gap Core Damage Fuel Melt
> 0.18
> 2.0
> 3.5 Entire Page Revised
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 10 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES
- 8.
Release Path:
SQN/WBN II Filtered via containment (CTM)
El Unfiltered via containment (CTM)
E] SGTR with rupture located BELOW water level n] Steam Generator Tube Rupture with rupture located ABOVE water level El Turbine Bldg El Reactor Bldg El Auxiliary Bldg.
Appendix C Page 2 of 2 BFN El Stack (filtered)
El Stack (unfiltered)
EL Turbine Bldg, Reactor Bldg EL Main Steam Line Break (MSLB)
- 9.
Release rates:
Basis for rates:
El Monitor reading E] Plant personnel E] BRED estimate Ci/s Noble Gas
_Ci/s 1-131 (pre-treatment value only, if available) laCi/s Total Particulate (pre-treatment value only, if available)
__pCi/s H-3 (if applicable see note below)
Entire Page Revised FRED / RED Data Inputs FRED RED Data Inputs NOTE:
"* For a TPBAR handling accident, the H-3 release can be estimated as:
H-3 Release
=
4Ci/cc H-3 x
cfm x 28320 cc/cf Rate 60 min/sec
{ H-3 release (l.Ci/s) = #jtCi/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 ptCi/s for 1 hr
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 11 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES FRED Appendix D Page 1 of 2 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.
- 2.
ENTER user name and password:
F-1 RED and CECC or LI FRED and CECC
- 3.
FOLLOW computer 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-131M 6
KR-85 29 XE-1 33 7
KR-85M 30 XE-1 33M 8
KR-87 31 XE-1 35 9
KR-88 32 XE-1 38
- 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:
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.
Entire Page Revised
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 12 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES FRED Appendix D Page 2 of 2 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:
[1] for 10 mile,
[2] 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 actual/projected release rates from the State Update Form.
- 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.
Entire Page Revised
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 13 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES Appendix E Page I of 2 BRED Evaluation of Airborne Field Data BRED Code Run
- 1. Log on to BRED. DOUBLE CLICK on the "CECC VAX" icon. PRESS return until prompted for usemame. ENTER username (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 Iodine-131 OR Tritium (H-3)
SDistance (miles)
Direction (sector)
Time Taken I Dose Rate mrem/hr (1 meter w/c)
IIodine-131 ACi/cc 3H Concentration ptCi/cc
- 3. Elapsed Time from reactor shutdown to time of field measurement:
(hours) (enter 0 if Rx under power)
- 4.
DETERMINE the Release Path:
SQN/WBN D] Filtered via containment (CTM)
LI Unfiltered via containment (CTM)
MI SGTR with rupture located BELOW water level M] Steam Generator Tube Rupture with rupture located ABOVE water level F] Turbine Bldg El Reactor Bldg E] Auxiliary Bldg.
LI Stack (unfiltered)
[] Turbine Bldg, Reactor Bldg El Main Steam Line Break (MSLB)
- 5.
DETERMINE the Release Type:
[EIRCS ElGap (default)
[]Core Damage
-IFuel Melt Entire Page Revised 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 Iodine"" microCi/cc Gap Core Damage Fuel Melt Ratio = Release Type:
Ž 0.18
>_ 2.0
>_ 3.5
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 14 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 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) gCils Tritium (3H) tCils
- 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 divided by the FIELD DATA Centerline Dose Rate divided by
=
RATIO NOBLE GAS RATIO Plant release unidentified?
1 1
Unlikely but possible Not unusual 0.001 0.01 0.1 0.2 0.5 Base actions on verified field measurements 1
10 50 100 Base actions on projections 1000 Attempt to verify projections by traversing the plume. Ask for reevaluation and level of 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.
Entire Page Revised Field Team not on centerline?
I
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 15 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES MANUAL AIR Appendix F Page 1 of 6 SB TEDE PAG Manual Method for Assessinq Airborne Releases A.
Calculating TEDE PAG Release Rate at SITE BOUNDARY (0.62 miles)
- 1.
DETERMINE:
Plant:
E] BFN
(m/s)
Stability Class: (circle)
A B
C D
E F
G Release Type:
F-RCS E]Gap (default)
E]Core Damage E-]Fuel Melt LiUser Specified (for noble gas and Tritium only)
Release Path:
SQN/WBN El Filtered via CTM
[] Unfiltered via CTM
[] SGTR with rupture BELOW water
[] SGTR with rupture ABOVE water E] Turbine, Reactor, Auxiliary Building BFN El filtered via stack El unfiltered via stack El Turbine, Reactor Bldg El Main Steam Line Break
- 2.
CIRCLE the TEDE PAG FACTOR (IiCi/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 1.7E+09 4.8E+08 2.2E+08 1.1E+08 7.4E+07 4.9E+07 2.9E+07 Stack 1.8E+09 9.1E+08 9.1E+08 8.3E+08 8.3E+08 8.OE+08 9.1E+08
- 3.
CIRCLE the appropriate TEDE Ratio below, based on release type/path:
TEDE Ratio (for 0.62 mi)
Stack (unfiltered Stack (filtered)
CTM (unfiltered) or SGTR (below)
CTM (filtered)
SGTR (above water)
Turbine, Reactor or Aux Bldg BWR RCS 2.0 1.9 N/A N/A N/A 8.1 4.8 PWR RCS N/A N/A 7.4 3.7 95 N/A 17 Gap 1.8 1.0 9.5 1.0 221 84 32 Core Damage 1.3 1.0 5.3 0.9 111 44 16
- 4.
CALCULATE the TEDE PAG Release Rate (0.62 mi) as follows:
TEDE PAG FACTOR (jiCi/m, item 2)
X wind speed (m/s, item 1)
/
TEDE Ratio (item 3)
Fuel Melt 2.0 1.0 11 1.0 263 100 37 User Spec 1.0 1.0 1.0 1.0 1.0 1.0 1.0 Entire Page Revised TEDE NGPAG Release Rate SB 0.62 mi (gCi/s)
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 16 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES MANUAL AIR Appendix F Page 2 of 6 SB TEDE PAG Manual Method for Assessing Airborne Releases
- 5.
OBTAIN the actual/projected Noble Gas Release Rate
_PCi/s.
- 6.
IF noble gas release rate (item 5) _> TEDE PAG Release Rate (item 4),
THEN radiological conditions indicate a General Emergency.
For Tritium Accidents (e.g., TPBAR handling or WGDT rupture),
- 7.
CIRCLE the Tritium PAG FACTOR (ýCi/m) below, based on the stability class.
A BI C
I F
I 4.OE+09 I 8.7E+08 12.9E+081 1.0E+08 5.9E+07 3.1 E+07 11.+07
- 8.
CALCULATE the Tritium PAG Release Rate as follows:
X=
Tritium PAG FACTOR wind speed TEDE Tritium PAG Release Rate (laCi/m, item 7)
(m/s item 1)
SB 0.62 MI (4Ci/s)
- 9.
OBTAIN the actual/projected Tritium Release Rate (see below)
Ci/s.
NOTE:
"* For a TPBAR handling accident, the H-3 release can be estimated as:
H-3 Release
=_
iCi/cc H-3 x
cfm x 28320 cc/cf Rate 60 min/sec
{ H-3 release (1.Ci/s) = #pCi/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 4Ci/s for 1 hr
- 10.
IF tritium release rate (item 9) __ TEDE PAG Release Rate (item 8),
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 _Ž 1.0, THEN radiological conditions indicate a General Emergency.
Entire Page Revised
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 17 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES MANUAL AIR Appendix F Page 3 of 6 SB THYROID Manual Method for Assessing Airborne Releases CDE PAG B.
Calculating THYROID CDE PAG Release Rate at SITE BOUNDARY (0.62 MILES)
- 1.
USE the data from section A.1
- 2.
CIRCLE the CDE PAG FACTOR (ýtCi/m), 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 4.1E+05 8.6E+04 3.OE+04 1.0E+04 6.OE+03 3.1E+03 1.4E+03 Stack 4.1E+05 2.3E+05 3.7E+05 6.5E+05 1.4E+06 2.1E+07 4.9E+11
- 3.
CALCULATE the CDE PAG Release Rate as follows:
CDE PAG FACTOR (tpCi/m, item 2)
X wind speed (m/s)
CDE PAG Release Rate SB 0.62 mi (4Ci/s)
- 4. a.
If known, RECORD the actual/projected 1-131 release rate p.Ci/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.
1-131 to Noble Gas Ratio CTM filtered Stack filtered CTM (unfiltered) or SGTR (below)
Stack (unfiltered)
RCS 1.7E-06 4.6E-07 1.7E-04 4.6E-05 5.8E-04 4.2E-03 4.6E-04 Gap 3.OE-05 3.OE-05 3.OE-03 3.OE-03 1.OE-02 8.0E-02 3.OE-02 Core Damage 1.2E-05 1.2E-05 1.2E-03 1.2E-03 4.1 E-03 3.OE-02 1.2E-02 4.b.
CALCULATE actual/projected iodine-131 release rate as follows:
Actual/Projected NG release rate (item A.5)
X 1-131 to NG ratio Actual/proj. 1-131 release rate (item 4a)
(LCi/s)
- 5.
IF 1-131 release rate (item 4a orb) > CDE PAG Release Rate (item 3),
THEN radiological conditions indicate a General Emergency.
Entire Page Revised Fuel Melt 2.2E-05 2.2E-05 2.2E-03 2.2E-03 7.7E-03 5.5E-02 2.2E-02
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 18 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES Appendix F Page 4 of 6 Manual Method for Assessing Airborne Releases MANUAL AIR 5 mi TEDE DOSE I C.
Calculating 5 mile TEDE USE the data from section A.1, THEN
- 1.
OBTAIN an estimate of the release duration (t) known otherwise.
hours. Use 4 (four) hours unless
- 2.
CIRCLE the TEDE FACTOR (rem/h per m/4Ci) 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 3.5E-09 6.5E-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:
Stack (unfiltered)
Stack (filtered)
CTM (unfiltered) or SGTR (below)
CTM (filtered)
SGTR (above water)
TB, RxB, AB TEDE Ratio* at 5 mi BWR PWR Core Fuel User RCS RCS GAP Damage Melt Spec 2.1 N/A 2.8 1.9 3.1 1.0 2.1 N/A 1.0 0.9 1.0 1.0 N/A 3.5 4.9 2.9 5.8 1.0 N/A 1.8 1.0 1.0 1.0 1.0 N/A 43 100 51 116 1.0 4.5 N/A 40 21 47 1.0 3.1 7.4 15 7.9 17 1.0
- 4.
CALCULATE the TEDE Dose as follows:
NG release rate (ýLCi/s)
(item A.5)
X TEDE FACTOR (item 2)
X TEDE Ratio (item 3)
X
/
Duration (hrs) wind sp.
(item 1)
(m/s item A.1) 5 mile For Tritium Accidents (e.g., TPBAR handling or WGDT rupture),
- 5.
CIRCLE the Tritium TEDE FACTOR (rem/h per 4Ci/m) below, based on the stability class.
IE a
.IE-11 41 0 91 E
T I4.OE-11 I5.OE-11 I1.1E-10 4.4E-1.0 I9.5E-10 I2.4E-09+5.5E-0ý9 Entire Page Revised
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 19 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES MANUAL AIR Appendix F Page 5 of 6 5 mi TEDE DOSE Manual Method for Assessing Airborne Releases 5 mi THY CDE DOSE
- 6.
CALCULATE the Tritium TEDE as follows:
XX
/
=
Tritium Release Rate*
Tritium TEDE FACTOR Duration wind speed Tritium TEDE (LCi/s)
(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 (tPCi/s) = #1LCi/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 ýtCi/s for 1 hr
- 7)
IF tritium accident also involves noble gases, THEN CALCULATE Total TEDE as follows:
D.
calculating 5 mi THYROID CDE Doses
- 1.
CIRCLE the Thyroid CDE FACTOR (1.Ci/m), 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 2.OE-06 2.5E-06 5.OE-06 2.2E-05 4.7E-05 1.2E-04 2.7E-04 Stack 2.OE-06 2.5E-06 4.5E-06 7.7E-06 3.5E-06 2.3E-07 1.OE-1 1
- 2.
OBTAIN the actual/projected 1-131 release rate from B.4 (4Ci/s).
- 3.
CALCULATE Thyroid CDE Dose as follows:
X X
/
1-131 release rate (ECi/s)
Thyroid CDE FACTOR duration (hrs) wind speed (item 2)
(item 1)
(item C.1)
(m/s)
Entire Page Revised
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 20 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES Appendix F Page 6 of 6 Summary Manual Method for Assessinq Airborne Releases E.
Summary of Results Site Boundary Thyroid CDE PAGs
- 8.
CDE PAG Release Rate (section B.3)
__Ci/s.
- 9.
Actual/projected 1-131 Release Rate (section B.4a/B.4b)
__Ci/s.
- 10. IF item 9 is > than item 8, THEN check yes for General Emergency below (item 14) 5 Mile TEDE
- 11.
TEDE without Tritium (section C.4) rem.
5 Mile Thyroid CDE
- 14. CHECK the appropriate box based "yes" if any of items 3, 6, 7, or 10 are "yes" GENERAL EMERGENCY?
[-] yes F-- no END OF MANUAL ASSESSMENT DATA VERIFICATION Calculated by: (initial / date)
Verified by: (initial / date)
Entire Page Revised Site Boundary TEDE PAGs
- 1.
TEDE NGPAG Release Rate (section A.4)
_Ci/s.
- 2.
Actual/projected Noble Gas Release Rate (section A.5)
_iCi/s.
- 3.
IF item 2 is > than item 1, THEN check yes for General Emergency below (item 14)
- 4.
TEDE Tritium PAG Release Rate (section A.8)
__Ci/s.
- 5.
Actual/projected Tritium Release Rate (section A.9)
__Ci/s.
- 6.
IF item 5 is > than item 4, THEN check yes for General Emergency below (item 14)
- 7.
Noble gas plus tritium TEDE factor (section A.1 1).
ratio IF factor > 1.0, THEN check ves for General Emernfencv hbelow (item 1 A
/
/ /
/
END OF MANUAL I ASSESSMENT j DATA VERIFICATION
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 21 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES APPENDIX G COMPARISON OF MEASURED FIELD DATA TO DOSE PROJECTION MODELS Ratio =
PROJECTED centerline dose rate MEASURED centerline dose rate NOBLE GAS RATIO Plant release unidentified?
Unlikely but possible Not unusual Field Team not on centerline?
0.001 0.01 0.1 0.2 0.5 1
Base actions on verified field measurements 10 50 100 Base actions on projections I
1000 Attempt to verify projections by traversing the plume. Ask for reevaluation and level of confidence on plant release data. Must be very confident that field data is correct to override projections based on measured release data.
Entire Page Revised
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 22 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES WATERDOSE APPENDIX H Code Run WATERDOSE Evaluation of Liquid Release to the River
- 1. Log on to WATERDOSE. DOUBLE CLICK on the "CECC VAX" icon. PRESS return until prompted for usemame. ENTER username (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.
Plant:
- a.
Determine Release Point::
El Diffuser LD Shoreline
- b.
Length of release:
Hours
- c.
Volume of release:
(ft3)
- d.
Release Mix (nuclides and concentrations)
Nuclide Concentration (tCi/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 - 2700 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.
Entire Page Revised
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 23 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES APPENDIX I Page 1 of 5 Manual Evaluation of Liquid Releases to the River
- 1.
Plant:
El BFN El SQN MANUAL RIVER LI WBN
- 2.
Release Point:
-]Diffuser
- 3.
Release Time:
Start E-iShoreline End
[--]Eastem ElCentral
- 4.
Release Volume (V) __
ft3 (1 gal = 0.134 ft3)
- 5.
Calculation of Hazard Index (HI):
Nuclide Concentration Dose Hazard (4Ci/ml)
(rem/day per l.Ci/ml)
Index (rem/day)
C DF-Table 3 HI=C
- DF Total Hazard Index
- 6.
Riverflow at the plant 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 - 2700 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 4)
Location Arrival Time Dilution Factor Hazard Index Release Dose Rate TRM Hours (l/ft3)
(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 / date)
/
ASSESSMENT DATA VERIFICATION Calculated by: (initial / date)
/
Entire Page Revised
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 24 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES APPENDIX I Page 2 of 5 Manual Evaluation of Liquid Releases to the River RELATIVE CONCENTRATION FACTORS-PER CUBIC FOOT RELEASED BROWNS FERRY NUCLEAR PLANT 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
.00E+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 3.1E-09
.00E+00 1.5E-09 1.5E-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 1.1E-09 2.4E-16 281.00 2.1E-09 7.4E-35 1.1E-09 7.7E-16 280.00 2.OE-09 4.8E-33 9.8E-10 2.1E-15 279.00 1.8E-09 1.8E-31 9.2E-10 4.8E-15 278.00 1.7E-09 4.1E-30 8.6E-10 1.OE-14 274.90 Downstream Dam SEQUOYAH NUCLEAR PLANT SHORELINE RELEASE DIFFUSER PIPE RELFASF 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.OE-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-1 1 1.6E-09 8.2E-1 0 476.00 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.OE-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 Entire Page Revised TABLE 1 DILUTION FACTOR (D)
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 25 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES TABLE 1 APPENDIX I Page 3 of 5 DILUTION Manual Evaluation of Liquid Releases to the River FACTOR RELATIVE CONCENTRATION FACTORS-PER CUBIC FOOT RELEASED (D)
WATTS BAR NUCLEAR PLANT
- fl'-l.Jr\\r-LilaE *r-~LL.,,.JIr LIIl I *Jfl-I X
- S=-
.lL=_*
=
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-1 1 526.00 1.8E-08 1.5E-14 9.1E-09 4.1E-09 525.00 1.2E-08 1.3E-12 6.1E-09 1.0E-09 524.00 9.1 E-09 1.2E-1 1 4.6E-09 1.4E-09 523.00 7.3E-09 4.0E-1 1 3.7E-09 1.7E-09 522.00 6.1 E-09 9.OE-11 3.1E-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 4.1E-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-10 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-10 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 9.1E-10 1.2E-09 1.2E-09 501.00 1.4E-09 9.1E-10 1.1E-09 1.1E-09 500.00 1.3E-09 9.1E-10 1.1E-09 1.1E-09 471.00 Downstream Dam Entire Page Revised
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 26 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES TABLE 2 APPENDIX I Page 4 of 5 ARRIVAL Manual Evaluation of Liquid Releases to the River 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
481.00 12 10 8
8 7
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 Entire Page Revised
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 27 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES Nuclide Dose Factor H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m 0.28 16.9 8.12 1155 1.34 28 67.8 16.1 68 30 80.4 753 35.8 14.2 51.1 12.33 0.24 0.28 0.013 153 0.45 0.26 1850 23800 74.2 239 204 2.43 155 146 238 61.8 210 42 39.8 1.44 APPENDIX I Page 5 of 5 Manual Evaluation of Liquid Releases to the River Critical In-gestion Dose Rate Factors (Derived from Regulatory Guide 1.109)
Rem/day per p.Ci/ml Organ1 Age 2 Nuclide Dose Factor TB B
TB B
GIT GIT GIT B
GIT GIT GIT B
GIT GIT L
L L
B B
GIT GIT GIT GIT GIT GIT GIT GIT GIT GIT K
GIT Ru-1 03 Ru-1 05 Ru-1 06 Ag-110m Te-125m Te-1 27m Te-127 Te-1 29m Te-129 Te-131 Te-131 Te-132 1-130 1-131 1-132 1-133 1-134 1-135 Cs-1 34 Cs-136 Cs-1 37 Cs-138 Ba-1 39 Ba-140 Ba-141 Ba-142 La-1 40 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 43.2 58.9 356 121 21.8 55 25.8 96 20.4 168 6.4 154 1332 12500 142 2980 37.4 584 538 90.4 438 1.13 50.2 116 7.27 1.06 185 46.3 48.4 91.2 330 80.6 4.44 69.8 56.4 48 TABLE3 DOSE FACTORS (DF)
Organ1 Age 2 GIT GIT GIT GIT K
K GIT K
GIT GIT GIT GIT THY THY THY THY THY THY L
L B
GIT GIT B
GIT GIT GIT GIT GIT GIT GIT GIT GIT GIT GIT GIT
- 1. THY = thyroid, GIT = Gastrointestinal Tract, K =
TB = Total Body, B = Bone Kidney, L = Liver,
- 2. A = Adult, C = Child, I = Infant Entire Page Revised
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 28 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES APPENDIX J Page 1 of 3 BFN - PUBLIC AND INDUSTRIAL SURFACE WATER SUPPLIES County-State 10-Mile Radius Limestone-Alabama Lawrence-Alabama Lawrence-Alabama 25-Mile Radius State of Alabama Lawrence-Alabama 50-Mile Radius Lauderdale-Alabama Colbert-Alabama Colbert-Alabama Colbert-Alabama Colbert-Alabama Colbert-Alabama Colbert-Alabama Colbert-Alabama Colbert-Alabama Colbert-Alabama Colbert-Alabama Colbert-Alabama Colbert-Alabama Plant Name Water Source Browns Ferry Nuclear Plant W. Morgan, E. Lawrence Water Authority Champion International (Courtland Plant)
Joe Wheeler State Park TVA-Wheeler Dam1 Florence City-Wilson Plant Reynolds Metals Company Muscle Shoals TVA ERL TVA-Wilson Dam Occidental Chemical Company Sheffield Sheffield Police TVA Colbert Fossil Plant Cherokee Water Works & Gas Cherokee Police (Day)
Cherokee Police (Night)
Laroche Industries Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Fleet Hollow Embayment Fleet Hollow Embayment Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Type of Water SuppIly Notification Advise State or Local Authorities listed in the REND Industrial Municipal Industrial &
Potable Municipal Industrial Municipal Industrial Municipal Industrial &
Potable Industrial Industrial Municipal Industrial Municipal Industrial IPotable water obtained from East Lauderdale County Water District.
Entire Page Rebsed t, \\,
(
(
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR PLANT RADIOLOGICAL EMERGENCIES CECC EPIP-8 Page 29 of 30 Revision 23 APPENDIX J Page 2 of 3 SQN - PUBLIC AND INDUSTRIAL SURFACE WATER SUPPLIES County-State 10-Mile Radius Plant Name Water Source Type of Water Supply Notification Advise State or Local Authorities listed in the REND Sequoyah Nuclear Plant Gold Point Marina East Side Utility Chickamauga Dam (Power Service Center)
Chickamauga Dam 25-Mile Radius E. I. Dupont Co.
50-Mile Radius Marion-Tennessee Jackson-Alabama Jackson-Alabama Tennessee American Water Co.
Rock-Tennessee Mill' Vulcan Sand & Gravel' Signal Mountain Cement' Medusa Cement Co.
Signal Mountain Cement (Plant)
Signal Mountain Cement (Quarry)
South Pittsburg Nickajack Dam Bridgeport Bridgeport Police
- Widows Creek Fossil Plant2 Mead Corporation Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River and Spring Tennessee River and Spring Tennessee River Tennessee River 1Obtains potable water from Tennessee-American Water Company.
- 2Obtains potable water supply from Bridgeport - physically removed potable water intake in November 1986.
Entire Page Revised Hamilton-Tennessee Industrial Industrial Industrial Industrial Industrial and Potable Municipal Industrial Industrial Industrial Industrial Industrial Industrial Municipal Industrial Municipal Industrial Industrial C
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 30 of 30 PLANT RADIOLOGICAL CECC EPIP-8 Revision 23 EMERGENCIES County-State 10-Mile Radius Rhea-Tennessee 25-Mile Radius Rhea-Tennessee 50-Mile Radius Hamilton-Tennessee APPENDIX J Page 3 of 3 WBN - PUBLIC AND INDUSTRIAL SURFACE WATER SUPPLIES ON THE TENNESSEE RIVER Type of Plant Name Water Source Water Supply Watts Bar Fossil & Hydro Plant1 Watts Bar Nuclear Plant City of Dayton Dayton Police TVA Sequoyah Nuclear Plant East Side Utility E. I. Dupont Chickamauga Dam Tennessee American Water Co.
Rock-Tennessee Mill 5 Vulcan Sand and Gravel5 Signal Mountain Cement5 Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Industrial 2,3
- Industrial3-4 Municipal Notification Advise State or Local Authorities listed in the REND Industrial Industrial Industrial and Potable Industrial Municipal Industrial Industrial Industrial 1On layby status - water use when activated is about 445 MGD.
2Cooling water.
3Potable water to nuclear plant, steam plant, hydro plant, and resort area, provided through Watts Bar Reservation System (wells).
4Cooling water and cooling tower makeup.
SObtains potable water supply from Tennessee-American Water Company.
Entire Page Rised
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