ML031820262
| ML031820262 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Watts Bar, Sequoyah  |
| Issue date: | 06/25/2003 |
| From: | Burzynski M Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| -RFPFR EPIP-8, Rev 25, EPIP-9, Rev 25 | |
| Download: ML031820262 (99) | |
Text
Tennessee Valley Authority, 1 101 Market Street, Chattanooga, Tennessee 37402-2801 June 25, 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 Tennessee Valley Authority
)
Docket Nos.
50-259 50-260 50-296 50-390 50-391 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 EPIP EPIP-8 EPIP-9 EPL Rev. 25 Rev. 25 EFFECTIVE DATE 6/16/03 6/16/03 6/16/03 If you have any questions, please contact Terry Knuettel at (423) 751-6673.
Sincerely, H
Mark J.
Burzynski Manager Nuclear Licensing Enclosures cc:
See page 2 Am
7---;, -
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U.S. Nuclear Regulatory Commission Page 2 June 25, 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 Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379-36 NRC Senior Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381
[Enclosures provided by site DCRM]
2-4
[No enclosures, by request of site resident]
DOCUMENT RELEASE AND FILING INSTRUCTIONS Page 1
of I
Release No.
To:
Management Services/RlIWEDM Prepared By:
Gail Mhite Other Address:
Extension:
751-2108 Date Submitted to Management Organization:
AS&P Services/RIM/EDM:
Address:
Attached are: (seled one)
Release and Submitted for la QA Records/Documents 0
Distribution o
Non-OA Records/Documents 0
Retention REC NO.
ACCPT REMOVE INSERT DOCUMENT NUMBER REV PAGES Y
N DATE PAGES PAGES CECC-EPIP List of Effective Pages 9
v 06/16/03 1 - 9 1 - 9 CECC EPIP-8, cover sheet 25 1
VI'
,-16-o3 cover sheet cover sheet CECC EPIP-8, rev. log 25 rev, log rev. log CECC EPIP-8 25 32 1_
All I - 32 CECC EPIP-9, cover sheet 27 1
lo -b 3 cover sheet cover sheet CECC EPIP-9, rev. log 27 rev. log rev. log CECC EPIP-9 27 All I
Acceptance:
Date S~'.
41 o
Signature Date Contact Et._
'NA
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=7B(-7 0-7 ae1 fISP233[82-7 TVA 4W74B (8-9-1) [08-9-n Page I of 1 SPP-2.3-3108-29-971
4 CECC-EPIP EPL Page 1 of 9 06/16/03 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 List of Effective Pages Page No.
1 of 9 2 of 9 3 of9 4 of 9 5 of 9 6 of 9 7 of 9 8 of 9 9 of 9 Rev. No.
06/16/03 06/16/03 06/16/03 06/16/03 06/16/03 06/16/03 06/16/03 06/16/03 06/16/03 Table of Contents 1 of2 2 of 2 10/17/02 10/17/02 EPIP-1 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 Cover Sheet Rev. Log 1 of33 2 of 33 3 of 33 4 of 33 5 of 33 6 of 33 7 of 33 8 of 33 9 of 33 10 of 33 11 of33 12 of 33 13 of 33 14 of 33 15 of 33 16 of 33 17 of 33 18 of 33 19 of 33 20 of 33 21 of33 22 of 33 23 of33 24 of 33 25 of33 26 of33 27 of33 28 of 33 29 of 33 30 of 33 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37 37
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CECC-EPIP EPL Page 2 of 9 06/16/03 List of Effective Pages (Continued)
Dmeg..ra Mt n Sutbdhrivinn Pane NO.
Rev. No.
EPIP-1 (Continued) 31 of 33 32 of 33 33 of 33 37 37 37 EPIP-2 Apper di;: A Appendix B EPIP-3 Cover Sheet Rev. Log 1 of 5 2 0f5 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 of8 6 of 8 7 of 8 8 of 8 30 30 30 30 30 30 30 31 31 31 31 31 31 31 31 31 31 Appendix A Appendix B Appendix C EPIP-4 Appendix A Appendix B Appendix C EPIP-5 Cover Sheet Rev. Log 1 of8 2 0f8 3 0f8 4 0f8 5 of8 6 0f8 7 0f8 8 of 8 Cover Sheet Rev. Log 1 of 10 2 of 10 3 of 10 4 0f10 5 of 10 6 of 10 7 0f10 8 of 10 9 of10 10 of 10 32 32 32 32 32 32 32 32 32 32 34 34 34 34 34 34 34 34 34 34 34 34 Appendix A Appendx B Appendix C EPIP-6 Cover Sheet Rev. Log I of 23 2 of 23 3 of 23 4 of 23 24 24 24 24 24 24
CECC-EPIP EPL Page 3 of 9 06/16103 List of Effective Pages (Continued)
- Procedure No.
EPIP-6 (Continued)
Subdivision Appendix A Appendix B Appendix C Appendix D Appendix E Appendix F Appendix G Appendix H Appendix I Appendix J Appendix K Page No.
5 of 23 6 of 23 7 of 23 8 of 23 9 of 23 10 of 23 11 of 23 12 of 23 I oi 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 Rev. No.
24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 24 EPIP-7 Appendix A Appendix B Appendix C Appendix D Appendix E Appendix F Cover Sheet Rev. Log I 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 I of 32 2 of 32 3 of 32 4 of 32 5 of 32 6 of 32 7 of 32 8 of 32 9 of 32 10 of 32 11 of 32 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 28 25 25 25 25 25 25 25 25 25 25 25 25 25 EPIP-8 Appendix A Appendix B Appendix C Appendix D
CECC-EPIP EPL Page 4 of 9 06/16/03 List of Effective Pages (Continued)
- Procedure No.
EPIP-8 (Continued)
Subdivision Appendix E Appendix F Appendix G Appendix H Appendix I Appendix J Page No.
12 of 32 13 of 32 14 of 32 15 of 32 16 of 32 17 of 32 18 of 32 19 of 32 0 of ci 2 21 of 32 22 of 32 23 of 32 24 of 32 25 of 32 26 of 32 27 of 32 28 of 32 29 of 32 30 of 32 31 of 32 32 of 32 Rev. No.
25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 EPIP-9 Cover Sheet Rev. Log I of 48 2 of 48 3 of 48 4 of 48 5 of 48 6 of 48 7 of 48 8 of 48 9 of 48 10 of 48 11 of48 12 of 48 13 of 48 14 of 48 15 of 48 16 of 48 17 of 48 18 of 48 19 of 48 20 of 48 21 of 48 22 of 48 23 of 48 24 of 48 25 of 48 26 of 48 27 of 48 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 Appendix A Appendix B Appendix C
UI CECC-EPIP EPL Page 5 of 9 06/16/03 List of Effective Pages (Continued)
- Procedure No.
EPIP-9 (Continued)
Subdivision Appendix D Appendix E Appendix F Appendix G Appendix H Appendix I Appendix J Appendix K Appendix L Page No.
28 of 48 29 of48 30 of 48 31 of48 32 of 48 33 of 48 34 of 48 35 of 48
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37 oF 48 38 of48 39 of 48 40 of48 41 of48 42 of 48 43 of 48 44 of 48 45 of 48 46 of 48 47 of 48 48 of 48 Rev. No.
27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 27 EPIP-1 I Appendix A Appendix B Appendix C Appendix D Appendix E Appendix F Appendix G Appendix H Appendix I Appendix J Cover Sheet Rev. Log I 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 I of 19 2 of 19 3 of 19 4 of 19 5 of 19 6 of 19 7 of 19 8 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 EPIP-12
CECC-EPIP EPL Page 6 of 9 06/16/03 List of Effective Pages (Continued)
- Procedure No.
EPIP-12 (Continued)
Subdivision A 1. cz a.
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18 18 18 18 18 18 18 18 18 18 EPIP-13 Appendix A Appendix B Appendix C EPIP-14 Cover Sheet Rev. Log I of 10 2 of 10 3 of 10 4 of 10 5 of 10 6 of 10 7 of 10 8 of 10 9 of 10 10 of 10 Cover Sheet Rev. Log I of 21 2 of 21 3 of 21 4 of 21 5 of 21 6 of 21 7 of 21 8 of 21 9 of 21 10 of 21 11 of 21 12 of 21 13 of 21 14 of 21 15 of 21 16 of 21 17 of 21 18 of 21 19 of 21 20 of 21 21 of 21 9
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9 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 25 Appendix A Appendix B Appendix C Appendix D
CECC-EPIP EPL Page 7 of 9 06/16/03 List of Effective Pages (Continued) mrndoreiir Wn Subdicivision EPIP-15 Appendix A Appendix B 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 Page No.
Cover Sheet Rev. Log I of 5 2 of 5 3 of 5 4 of 5 5 of 5 Cover Sheer 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 I of6 2 of 6 3 of 6 4 of6 5of6 6 of 6 Rev. No.
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CECC-EPIP EPL Page 8 of 9 06/16/03 List of Effective Pages (Continued)
Procedure No.
Subdivision Page No.
Rev. No.
EPIP-19 (Continued)
Appendix A Appendix B 1 of 11 2 of 11 3 of 11 4 of 11 5 of 11 6 of 11 7 of 11 8 of 11 4 A 10 of 11 11 of 11 12 12 12 12 12 12 12 12 12 12 12 EPIP-21 Appendix A Appendix B EPIP-22 Cover Sheet Rev. Log 1 of 4 2 of 4 3 of 4 4 of 4 Cover Sheet Rev. Log 1 of 7 2of7 3of7 4of7 5of7 6 of 7 7 of 7 13 13 13 13 13 13 19 19 19 19 19 19 19 19 19 Attachment A Attachment B EPIP-23 Attachment A Attachment B Attachment C Attachment D Attachment E Attachment F 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 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18
CECC-EPIP EPL Page 9 of 9 06/16/03 List of Effective Pages (Continued)
- Procedure No.
EPIP-23 (Continued)
Subdivision Page No.
Rev. No.
Attachment G 21 of 24 22 of 24 23 of 24 24 of 24 18 18 18 18 Attachment H Attachment I
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CECC EPIP Coversheet Title CECC EPIP-8 Tennessee REV. 25 Valley Authority CENTRAL EMERGENCY DOSE ASSESSMENT STAFF ACTIVITIES CONTROL CENTER DURING NUCLEAR PLANT EMERGENCY PLAN RADIOLOGICAL EMERGENCIES IMPLEMENTING Effective Date:
PROCEDURES WRITTEN BY:
REVIEWED BY:
5'iK c
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-503 Signature Signature Date PLAN EFFECTIVENESS DETERMINATION:RI4..
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6z°4 s G ° 3
Signature Date CONCURRENCES Concurrence Signature Date 0
Maager, EP Pro!7m Planning and Implementation 0 Manager, Emergency Preparedness 6A702 A
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0Mna r adiological and Chemistry Services p
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I CECC-EPIP-8 DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR PLANT RADIOLOGICAL EMERGENCIES Rev. No.
Date REVISION LOG Revised Pages 0
3122/88 All (Changed from IPD to EPIP)
I 11/18/88 2-7, Apps. A, B, C, & D 2
12/12/88 Appendix A 3
4 5
4/26/89 9/19/89 10/26/89 All App. C 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 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. I & 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.
Rev. No.
18 19 20 21 22 23 24 CECC-EPIP-8 DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR PLANT RADIOLOGICAL EMERGENCIES REVISION LOG (Continued)
Date Revised Pages 6/9/98
-&L4)9=
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.
10)27/98 Correct reference to CECC EPIP-1 Appendix on Appendix J.
5/20/99 Annual review. Editorial and clarification changes, revise public water use tables. All pages issued.
9/8/00 Annual review. Editorial changes. All pages issued.
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 11/22/02 project.
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.
6/16/03 Make corrections to Anpendix F. All oaaes issued.
25
-A DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 1 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 EMERGENCIES Table of Contents 1.0 PURPOSE..
2...................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 I Field Coordinator............
....................... 3 4.4 Core Damage Assessor....................................
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 Verificatiqn...................................
4 5.2 Preliminary Assessments..................................
4 5.3 Criteria for Significant Change in Conditions..................
5................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.
B.
C.
D.
E.
F.
- G.
OH
- l.
- J.
- Revision Dose Assessor Initial Reporting Checklist............................................... 7 Shift Change and Termination Checklist............................................... 8 FRED / RED Data Inputs.............................................. 9 FRED / RED Assessment of Airborne Releases........................................ 11 BRED Assessment of Airborne Release Field Data................................... 13 Manual Methodology for Assessing Airborne Releases.................
............ 15 Comparison of Measured Field Data to Dose Projection Models..........
..... 23 WATER DOSE Data Inputs.............................................. 24 Manual Methodology for Assessing Liquid Releases to the River.........
..... 25 Public and Industrial Surface Water Supplies............................................ 30
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 2 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 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.
lUpon reporting to the CECC, perform initial activities in accordance with the checklist provided l 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).
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 3 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 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 assessmentsand 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 pbts 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. Thisdata 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 EAIFC 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.
DOSE.ASSESSMENT STAFF ACTIVITES DURING NUCLEAR Page 4 of 32 PLANT RADIOLOGICAL CEGC EPIP-8 Revision 25 EMERGENCIES o a u 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.
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 5 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25
_ 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 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.
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 RACIRAM 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, orthe 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 1-131/1-1-3 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 detemnine 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).
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 Users 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)
RAMWRAC -Radiological Assessment Manager or Radiological Assessment Coordinator
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 7 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 EMERGENCIES__
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 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 occuring. 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. Reporttrequest 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)
If comouterproblems are encountered, Immediately contact ComputerSupport.
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 ASSESSMENTSTAFF ACTIVITIES DURING NUCLEAR Page 8 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 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 nexd 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 systemtturn 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
Appendix C Page 1 of 2 FRED RED FRED I RED Data Inputs 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: n 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):
I SQONW FN E] Shield Bldg El Stack El Near ground 0 Radwaste Zone (of Rx Bldg)
El Refueling Bldg zone (of Rx Bldg)
Cl 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:
ORCS E[Core Damage OUser Specified OGap (default)
EFuel 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. Aitemately, particulate-to-113' field team air concentration data can be used as follows:
Field Team Data Particulate microCi/cc =
Ratio Field Team Data lodine'31 microCi/cc Ratio = Release Type:
GaD Core Damaae Fuel Melt 20.18
Ž2.0 23.5
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 1O of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 EMERGENCIES I
Appendix C Page 2 of 2 FRED RED Data Inputs FRED I RED Data Inputs
- 8.
Release Path:
SQN/WBN o Filtered via containment (CTM) o Unfiltered via containment (CTM)
Cl SGTR with rupture located BELOW water level El Steam Generator Tube Rupture with rupture located ABOVE water level o Turbine Bldg o] Reactor Bldg O Auxiliary Bldg.
BFN El Stack (filtered)
El Stack (unfiltered)
El Turbine Bldg, Reactor Bldg El Main Steam Line Break (MSLB)
- 9.
Release rates:
Basis for rates:
E Monitor reading a
Plant personnel
[] BRED estimate
_iCi/s Noble Gas
_Ci/s 1-131 (pre-treatment value only, if available) pCi/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 Rate II/cc1ri "--'
x rfm x 28320 crr/f 60 min/sec
{ H-3 release (jCVs) = #pCicc H-3 x building exhaust flow rate (cfrn) 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 pCiis for 1 hr
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 11 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 EMERGENCIES Appendix D Page l of 2 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.
- 2.
ENTER user name and password:
C RED and CECC or 0 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-131 M 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, (YIN). Edit as necessary.
6 CONFIRM whether the calculated release rate data is correct, (YIN). 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.
I I 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 uPrint 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.
COMPAREthe 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.
Appendix E Page 1 of 2 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 username. 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 lodine-131 OR Tritium (H-3)
I.:Distance (miles) l:
D.irection (setor)t
- TimeTaken :-:l Dose Rate mm/hr (1 neterw/c4l liodine Jo iii
-1H
- Concentration c --
- 3. Elapsed Time from reactor shutdown to time of field measurement (hours) (enter 0 if Rx under power)
- 4.
DETERMINE the Release Path:
SQNIWBN El Filtered via containment (CTM)
O Unfiltered via containment (CTM) o SGTR with rupture located BELOW water level E Steam Generator Tube Rupture with rupture located ABOVE water level a Turbine Bldg Cl Reactor Bldg a Auxiliary Bldg.
[I Stack (filtered) a Stack (unfiltered)
[] Turbine Bldg, Reactor Bldg El Main Steam Line Break (MSLB)
- 5. DETERMINE the Release Type:
ORCS
[]Gap (default)
ECore Damage E]Fuel Melt NOTE: Initially, a GAP Release Type should be used unless otherwise specified by the Core Damage Assessment team. Altemately, particulate-to-I1 31field team air concentration data can be used as follows:
Field Team Data Particulate microCVcc = Ratio Field Team Data Iodine"" microCicc Gag Core Damaae Fuel Melt Ratio = Release Type:
2 0.18
Ž 2.0
Ž 3.5
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 14 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 EMERGENCIES_
I Appendix E Page 2 of 2 CoBRED R
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 Cils)
I Iodine 131 (pre-treatment) Cis Tritium eH) pCi/s I~~
- 1.
1
- 8.
COMPARE the new FRED run dose rate output to the previous RED/FRED computer model by CALCULATINGa data ratio as follows:
FRED or RED Centerline Dose Rate divided by the FIELD DATA Centerline Dose Rate divided by
=
RATIO Plant release unidentified?
Unlikely -
but possible I Not unusual I
Field Team not on centerline?
NOBLE GAS RATIO I
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
I Base actions on verified field measurements Base actions on projections 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.
Appendix F Page 1 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)
- 1.
DETERMINE:
Plant: 0 BFN Q SQN E VWBN Wind Speed:
(m/s)
Stability Class: (circle)
A B
C D
E F
G Release Type:
ORCS OGap (default)
EiCore Damage ElFuel Melt EjUser Specified (for noble gas and Tritium only)
Release Path:
SQN/WBN O Filtered via CTM o Unfiltered via CTM El SGTR with rupture BELOW water El SGTR with rupture ABOVE water O Turbine, Reactor, Auxiliary Building 1BFN
[l filtered via stack 0 unfiltered via stack O Turbine, Reactor Bldg EO Main Steam Line Break
- 2.
CIRCLE the TEDE PAG FACTOR (uCi/m) below, based on the stability class and release level.
NOTE: USE ground level for all cases except for BFN stack.
l A I
B I
C I
D I
E I
F I
G -l Ground 1.7E+09 I 4.8E+08 12.2E+08 11.1 E+08 7.4E+07 4.9E+07 12.9E+07 1 Stack 1.8E+09 9.1 E+08 19.1 E+08 8.3E+08 8.3E+08 8.0E+08 9.1 E+08
- 3.
CIRCLE the appropriate TEDE Ratio below, based on release type/path:
TEDE Ratio (for 0.62 mil BWR PWR Core Stack (unfiltered Stack (filtered)
- CTM (unfiltered) or SGTR (below)
CTM (filtered)
SGTR (above water)
- MSLB (BFN)
- Turbine, Reactor or Aux Bldg RCS 2.0 1.9 N/A N/A N/A 7.4 4.4 RCS N/A N/A 7.4 3.7 95 N/A 17 GaP 1.8 1.0 9.0 1.0 221 84 32 Damage 1.3 1.0 5.3 0.9 111 44 16 Fuel Melt 2.0 1.0 11 1.0 263 100 37 User Snec 1.0 1.0 1.0 1.0 1.0 1.0 1.0
- 4.
CALCULATE the TEDE PAG Release Rate (0.62 mi) as follows:
X wind speed (m/s, iem 1)
TEDE Ratio (item 3)
TEDE NGPAG Release Rate SB 0.62 mi (pCUs)
- Revision JiIIR liil I1 j 1 1 till i NiW I! q!
lithN I III 4iii I I I.1jHi l 11N]L 11 Mi 4021739564 CHAT CECC EPIP CECC-EPIP-8 061603 25 CORR.TYPO'S PG.15 6-23-03
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 16 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 EMERGENCIES Appendix F Page 2of 8 MANUAL AIR Manual Method for Assessing Airborne Releases SB TEDE PAG
- 5.
OBTAIN the actual/projected Noble Gas Release Rate
__Cis.
- 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 &tCi/m) below, bascd cn the stability class.
A B
C D
E F
lG l
4.OE+09 8.7E+08 2.9E+08 1.OE+08 5.9E+07 3.1 E+0711.4E+07
- 8.
CALCULATE the Tritium PAG Release Rate as follows:
X Tritium PAG FACTOR wind speed TEDE Tritium PAG Release Rate (iCi/m, Rem 7)
(m/s Rem 1)
SB 0.62 Ml (j+/-Ci/s)
- 9.
OBTAIN the actual/projected Tritium Release Rate (see below)
_CVs.
NOTE:
- For a TPBAR handling accident, the H-3 release can be estimated as:
cfm x 28320 cc/cf Rate 60 min/sec
{ H-3 release (uCi/s) = #jiCi/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
- 10.
IF tritium release rate (item 9) 2 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 2 1.0, THEN radiological conditions indicate a General Emergency.
- Revision
.3.
DOSE ASSESSMENT STAFF ACIlVIllES DURING NUCLEAR Page 17 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 EMERGENCIES Appendix F Page 3 of MANUAL AIRO 1 Manual Method for Assessing Airborne Releases SB THYROID B.
Calculating THYROID CDE PAG Release Rate at SITE BOUNDARY (0.62 MILES) l
- 1.
USE the data from section A.1
- 2.
CIRCLE the CDE PAG FACTOR (FLCilm), 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
I G
Ground 4.IE+05 I 8.6E+04 I 3.OE+04 I 1.OE+04 I 6.OE+03 I 3.1E+03 I 1.4E+03 Stack 4.1 E+05 2.3E+05 3.7E+05 6.5E+05 I 1.4E+06 2.1 E+07 4.9E+11
- 3.
CALCULATE the CDE PAG Release Rate as follows CDE PAG FACTOR (sCam, item 2)
X wind speed (mls)
CDE PAG Release Rate SB 0.62 mi (;LCI/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.
4.b.
CALCULATE actual/projected iodine-131 release rate as follows:
X Actual/Projected NG release rate (item A.5) 1-131 to NG ratio Actual/proj. 1-131 release rate (item 4a)
(ACiVs)
S.
IF 1-131 release rate (item 4a or b) 2 CDE PAG Release Rate (item 3),
THEN radiological conditions indicate a General Emergency.
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 18 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 EMERGENCIES I
Appendix F Page 4 of 8 MANUAL AIR Manual Method for Assessing Airborne Releases SB TEDE RATE lC.
Calculating TEDE Dose Rate at SITE BOUNDARY (0.62 miles)
- 1.
DETERMINE:
Plant: [3 BFN O SQN O WBN Wind Speed:
(mIs)
Stability Class: (circle)
A B
C D
E F
G Release Type:
ORCS OCore Damage OGap (default)
OFuel Melt EjUser Specified (for noble gas and Tritum only)
Release Path:
SQNIWBN BFN O Filtered via CTM El filtered via stack O Unfiltered via CTM 0 unfiltered via stack o SGTR with rupture BELOW water El Turbine, Reactor Bldg E SGTR with rupture ABOVE water[ Main Steam Line Break O Turbine, Reactor, Auxiliary Building Noble Gas Release Rate: __Ci/s)
- 2.
CIRCLE the TEDE FACTOR (rem/h per p&Cim) 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 I 6.0E-10 I 2.1E-09 14.6E-09 19.5E-09 11.4E-08 2.1 E-08 13.5E-08 Stack 5.5E-10 1.I E-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 mil Stack (unfiltered) _
Stack (filtered) _
CTM (unfiltered) or SGTR (below)
I CTM (filtered) r SGTR (above water)
- 4.
CALCULATE the TEDE Dose as follows:
,CS RCS GAP Damage Melt Spec 2.0 N/A 1.8 1.3 2.0 1.0 1.9 N/A 1.0 1.0 1.0 1.0 V/A 7.4 9
5.3 11 1.0 NIA 3.7 1.0 0.9 1.0 1.0 V/A 95 221 111 263 1.0 7.4 N/A 84 44 100 1.0 4.4 17 32 16 37 1.0 X
X I
NG release rate (Cis)
TEDE FACTOR TEDE Ratio wind sp. (m/s)
(item 1)
(item 2)
(item 3)
(item 1)
For Tritium Accidents (e.g., TPBAR handling or WGDT rupture),
TEDE (rem/h) 0.62 mile S.
CIRCLE the Tritium TEDE FACTOR (rem/h per Ci/m) below, based on the stability class.
I A
I B
I C
I D
I E
I F
I I 2.5E-10 I 1.2E-09 I 3.5E-09l 1.OE-08 I 1.7E-08 13.3E-08 17.OE-08
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 19 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 I
EMERGENCIESl Appendix F Page 5 of 8 Manual Method for Assessing Airborne Releases MANUAL AIR 5 ml TEDE RATE
- 6.
CALCULATE the Tritium TEDE as follows:
5 mi THY CDE RATE X
I
=
Tritium Release Rate*
Tritium TEDE FACTOR wind speed Tritium TEDE (pCi/s)
(item 5)
(MIs)
(rernh)
(item 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 (pCi/s) = #+/-Ci/cc H-3 x building exhaust flow rate (cfm) x 28320 cc/cf x 1160 minis}
^ For a WGDT Rupture accident, the default H-3 release is 2500 Ci over one hr or 6.94E+05 +/-Ci/s for 1 hr
- 7.
IF tritium accident also involves noble gases, THEN CALCULATE Total TEDE rate as follows:
TEDE (rem/h)
Total TEDE (rem/h) 0.62 mile D.
Calculating SB THYROID CDE Dose Rate
- 1.
CIRCLE the Thyroid CDE FACTOR (remht per pCi/m), based on the stability class and release level.
NOTE: USE ground level for all cases except for BFN stack.
EZZ)~
A I
B C Z I
D I
E lGround 1.2E-05 I 5.8E-05 I 1.7E-04 I 4.8E-04 I 8.3E-04 I 1.6E-03 I 3.5E-03l Stack I 1.2E-05 I - 2.2E-05 I 1.4E-05 7.7E-06 I 3.5E-06 I 2.3E-07 I 1.0E-1j I 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.
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~......................................
NG releae rate
-31 10~l NGs Ratio 111rlaert (Tem filtered I.7em06 2a 1.E2E-bve... 2........
3QE O
....... FN
-4
~ O-2 1,E(
~
2E 2b. CALCULATE actual/projected iodine-13I release rate as follows:...
_ x _ _ _ _
NG release rate 1-131 to NG ratio 1-131 release rate~~~~~~~~~~~~~............
item...
A.........
(..e
.(...
C.........
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 20 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 EMERGENCIES Appendix F Page 6 of 8 Manual Method for Assessing Airborne Releases
- 3.
CALCULATE Thyroid CDE Dose Rate as follows:
X I
1-131 release rate ECius)
Thyroid CDE FACTOR wind speed (item 2)
(item 1)
(mIs)
MANUAL AIR I5miTEDE DOSE E.
Calculatinc 5 mile TEDE 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 (rerr/h per per,uCi/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
l G
Ground 9.5E-11 I 1.5E-10 12.8E-10 9.5E-10 1.8E-09 I13.5E-09 16.5E-09 Stack 9.0E-11 1.5E-10 2.6E-10 7.5E-10 1.I E-09 1.3E-09 I1.1E-09
- 3.
CIRCLE the appropriate TEDE Ratio below, based on release type/path:
Stack (unfilterec Stack (filterec CTM (unfiltered) or SGTR (belom CTM (fifferec SGTR (above water MSLB (BFA TB, RxB, Ai
- 4.
CALCULATE the TEDE Dose as foil X
NG release rate (rCiVs)
(item TEDE Ratio (at 5 ml)
BWR PWR Core Fuel User RCS RCS GAP Damage Mel Spec d) 2.1 N/A 2.8 1.9 3.1' 1.0 d) 2.1 N/A 1.0 0.9 1.0 1.0 v) N/A 3.5 4.9 2.9 5.8 1.0 f)
N/A 1.8 1.0 1.0 1.0 1.0
)
N/A 43 100 51 116 1.0
- 1) 4.5 N/A 40 21 47 1.0 B
3.1 7.4 15 7.9 17 1.0 ows:
CTOR 2) x TEDE Ratio (Hem 3)
X Duration (hrs)
(item 1) wind sp. (m/s)
(item 1) 5 mile For Tritium Accidents (e.g., TPBAR handling or WGDT rupture),
- 5.
CIRCLE the Tritium TEDE FACTOR (remlh per pCi/m) below, based on the stability class.
I A I
4.OE-11 I 5.OE-11 I 1.1E-10 4.4E-10 I 9.5E-10 I 2.4E-09 l5.5E-09
- Revision
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 21 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 EMERGENCIES Appendix F Page 7 of 8 MANUAL AIR Manual Method for Assessing Airborne Releases 5 ml TEDE DOSE
- 6.
CALCULATE the Tritium TEDE as follows:
________~X____ X__
I
=_____
Tritium Release Rate Tritium TEDE FACTOR Duration wind speed Tritium TEDE
-(1.Cis)
(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 (iCi/s) = #IiCi/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 pCi/s for 1 hr
- 7)
IF tritium accident also involves noble gases, THEN CALCULATE Total TEDE as follows:
F.
Calculating 5 mi THYROID CDE Doses I
- 1.
CIRCLE the Thyroid CDE FACTOR (rem/h per gCi/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 I
D I
E I
F I
G I
Ground l 2.OE-06 I 2.5E-06 I 5.OE-06 I 2.2E-05 I 4.7E-05 I 1.2E-04 I 2.7E-04 Stack 2.OE-06 I 2.5E-06 I 4.5E-06 I 7.7E-06 I 3.5E-06 I 2.3E-07 I 1.OE-1 1
- 2.
OBTAIN the 1-131 release rate from B.4 CUs).
- 3.
CALCULATE Thyroid CDE Dose as follows:
X 1-131 release rate uCi/s)
(item 2)
Thyroid CDE FACTOR (item 1)
X duration (hrs)
(item C.1) wind speed (mls)
(item A.1)
- Revision
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 22 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 EMERGENCIES Appendix F Page a of 8 Manual Method for Assessing Airborne Releases S3 mar
- G.
Summary of Results Site Boundary TEDE Rates
- 1. Total TEDE Rate (item C.7) rem/h
For 0.62 ml TEDE dose rate 2 REP Emergencv Class 1E-04 rem/h NOUE 1 E-02 rem/h ALEFIT 1 E-01 rem/h SAE I E+00 rem/h GE Site Boundary Thyroid CDE Dose Rate
- 3.
CDE Dose Rate (section D.3) rem/h
- 4.
Cirlce REP Emergency class based on CDE rate above:
For 0.62 mi CDE dose rate 2 REP Emergencv Class NA NA 0.5 rem/h SAE 5 rem/h GE 5 Mile TEDE
- 5.
TEDE without Tritium (section E.4) rem.
- 6.
Total TEDE with Tritium (section E.7) rem.
5 Mile Thyroid CDE
- 7.
ThyroidCDE (section F.3) rem.
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)
/
ASSESSMENT DATA VERIFICATION Verified by: (initial / date)
/
DOSE ASSESSMENT STAFF ACTlIVES DURING NUCLEAR Page 23 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 EMERGENCIES.
APPENDIX G COMPARISON OF MEASURED FIELD DATA TO DOSE PROJECTION MODELS Ratio =
PROJECTED centerline dose rate MEASURED centerline dose rate
~~~~1*I Plant release unidentified?
Unlikely -
but possible I Nt uusual Field Team not on centerline?
NOBLE GAS RATIO I
I I
I I
I I
I I
0.001 0.01 0.1 0.2 0.5 1
10 50 100 1000 A
I Base actions on verified field measurements Base actions on projections 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.
I DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 24 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 EMERGENCIES APPENDIX H lWATERDOSE 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 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:
E BFN 5
- a.
Determine Release Point::
El Diffuser D Shoreline
- b.
Length of release:
Hours
- c.
Volume of release:
(ft3)
- d.
Release Mix (nuclides and concentrations)
Nuclide lConcentration (4Cilm1)
I l
~~~~~~~~~~~~~~~~~~~~~~~
l
~~~~~~~~~~~~~~~~~~~~~~~
I I
I I~~~~~~~~~~~~~~~~~~
- 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.
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 26 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 EMERGENCIES APPENDIX I Page 1 of 5 Manual Evaluation of Licuid Releases to the River MANUAL RIVER
- 1.
Plant:
- 2.
Release Point:
ODiffuser L]Shoreline
- 3.
Release Time:
Start End OEastem Ocentral
- 4.
Release Volume (V) ft3 (1 gal = 0.134 ft3)
S. Calculation of Hazard Index (HI):
Nuclide Concentration Dose Hazard 1Ci/rn)
(remnday per Ci/ml)
Index (rern/day)
C DF-Table 3 Hl=C
- DF Total Hazard Index
- 6.
Riverflow at the plant ft3ls (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 (1m)
(rem/day)
Volume (ft)
(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)
APPENDIX I Page 2 of 5 TABLE I Manual Evaluation of Liouid Releases to the River DILUTION FACTOR RELATIVE CONCENTRATION FACTORS-PER CUBIC FOOT RELEASED (D)
BROWNS FERRY NUCLEAR PLANT SHORELINE RELEASE DIFFUSER PIPE RELEASE 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.OE-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-1 9 285.00 3.1 E-09
.OOE+00 1.5E-09 1.5E-1 8 284.00 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 2.1 E-09 7.4E-35 1.1 E-09 7.7E-16 280.00 2.OE-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.OE-14 274.90 Downstream Dam SEQUOYAH NUCLEAR PLANT SHORELINE RELEASE DIFFUSER PIPE RELEASE 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 1.1 E-14 483.00 1.4E-08 5.3E-1 9 7.2E-09 3.OE-1 1 482.00 9.1 E-09 3.2E-15 4.6E-09 1.9E-10 481.00 6.8E-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-1 1 1.3E-09 8.8E-1 0 474.00 2.3E-09 9.OE-11 1.2E-09 8.6E-10 473.00 2.1 E-09 1.2E-10 1.1 E-09 8.6E-10 472.00 1.9E-09 1.4E-10 1.0E-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 ACTIVIllES DURING NUCLEAR Page 27 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 EMERGENCIES APPENDIX I Page 3 of 6 TABLE I Manual Evaluation of Liauid Releases to the River DILUTION FACTOR RELATIVE CONCENTRATION FACTORS-PER CUBIC FOOT RELEASED (D)
WATTS BAR NUCLEAR PLANT SHORELINE RELEASE 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-1 1 526.00 1.8E-08 1.5E-14 9.1 E-09 4.1 E-09 525.00 1.2E-08 1.3E-12 6.1 E-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 9.0E-11 3.1 E-09 1.8E-09 521.00 5.2E-09 1.6E-1 0 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-10 1.5E-09 1.5E-09 511.00 2.2E-09 7.6E-10 1.5E-09 1.4E-09 510.00 2.0E-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 9.1 E-10 1.2E-09 1.2E-09 501.00 1.4E-09 9.1E-10 1.1 E-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
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 28 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 EMERGENCIES I
APPENDIX I Page 4 of 5 Manual Evaluation of Liquid Releases to the River TABLE 2 I
ARRIVAL TIME (HRS)
APPROXIMATE TRAVEL TIME TO MAXIMUM CONCENTRATION-HOURS BROWNS FERRY NUCLEAR PLANT
.I.^ I E211k 101M 01 r%%A1 MI ^1 101f%
0MM'rJ0=?%^K1r'%
I MM FMGIVr% F LYVV aif DIo Q II'.1C.%IW
_N_
25000 30000 33000 35000 37000 39000 294.00 Plant 292.00 25 21 19 18 17 18 290.00 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 WAiTS BAR NUCLEAR PLANT
_ 19000 20000 25000 30000 35000 528.00 Plant I
l
_II 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
APPENDIX I Page 5 of 5 TABLE 3 Manual Evaluation of Liquid Releases to the River DOSE FACTORS Critical Inoestion Dose Rate Factors (DF)
(Derived from Regulatory Guide 1.109)
Rem/day per gCi/ml Nuclide Dose Factor Organ1 Age2 Nuclide Dose Factor
Ru-103 43.2 GIT A
C-14 16.9 B
C Ru-105 58.9 GIT C
Na-24 8.12 TB C
Ru-1 06 356 GIT A
P-32 1155 B
C Ag-110m 121 GIT A
Cr-51 1.34 GIT A
Te-125m 21.8 K
A Mn-54 28 GIT A
Te-127m 55 K
A Mn-56 67.8 GIT C
Te-127 25.8 GIT C
Fe-55 16.1 B
C Te-129m 96 K
C Fe-59 68 GIT A
Te-129 20.4 GIT I
Co-58 30 GIT A
Te-131 168 GIT A
Co-60 80.4 GIT A
Te-131 6.4 GIT I
Ni-63 753 B
C Te-132 154 GIT A
Ni-65 35.8 GIT C
1-130 1332 THY I
Cu-64 14.2 GIT A
1-131 12500 THY I
Zn-65 51.1 L
C 1-132 142 THY I
Zn-69 12.33 GIT I
1-133 2980 THY I
Br-83 0.24 TB C
1-134 37.4 THY I
Br-84 0.28 TB C
1-135 584 THY I
Br-85 0.013 TB C
Cs-134 538 L
C Rb-86 153 L
I Cs-136 90.4 L
C Rb-88 0.45 L
I Cs-1 37 438 B
I Rb-89 0.26 L
I Cs-138 1.13 GIT I
Sr-89 1850 B
C Ba-139 50.2 GIT I
Sr-90 23800 B
C Ba-140 116 B
C Sr-91 74.2 GIT C
Ba-141 7.27 GIT I
Sr-92 239 GIT C
Ba-142 1.06 GIT I
Y-90 204 GIT A
La-140 185 GIT A
Y-91m 2.43 GIT I
La-142 46.3 GIT C
Y-91 155 GIT A
Ce-141 48.4 GIT A
Y-92 146 GIT C
Ce-143 91.2 GIT A
Y-93 238 GIT C
Ce-144 330 GIT A
Zr-95 61.8 GIT A
Pr-143 80.6 GIT A
Zr-97 210 GIT A
Pr-144 4.44 GIT I
Nb-95 42 GIT A
Nd-147 69.8 GIT A
Mo-99 39.8 K
C W-187 56.4 GIT A
Tc-99m 1.44 GIT C
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
(
C
(
DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR Page 30 of 32 PLANT RADIOLOGICAL CECC EPIP-8 Revision 25 EMERGENCIES 4
APPENDIX J Page 1 of 3 BFN - PUBLIC AND INDUSTRIAL SURFACE WATER SUPPLIES Type of Water Source Water Supply County-State Plant Name Notification Advise State or Local Authorities listed in the REND 10-Mile Radius Limestone-Alabama Lawrence-Alabama Lawrence-Alabama 25-Mile Radius State of Alabama Lawrence-Alabama Browns Ferry Nuclear Plant W. Morgan, E. Lawrence Water Authority Champion International (Courtland Plant)
Joe Wheeler State Park TVA-Wheeler Dam' Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Industrial Municipal Industrial &
Potable Municipal Industrial 50-Mile Radius Lauderdale-Alabama Colbert-Alabama Colbert-Alabama Florence City-Wilson Plant Reynolds Metals Company Muscle Shoals Tennessee River Tennessee River Tennessee River Fleet Hollow Embayment Municipal Industrial Municipal Colbert-Alabama Colbert-Alabama Colbert-Alabama Colbert-Alabama Colbert-Alabama Colbert-Alabama Colbert-Alabama Colbert-Alabama Colbert-Alabama Colbert-Alabama TVA ERL Fleet Hollow Embayment 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 Industrial &
Potable Industrial Industrial Municipal Industrial Municipal 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 25 EMERGENCIES APPENDIX J Page 2 of 3 SQN - PUBLIC AND INDUSTRIAL SURFACE WATER SUPPLIES Type of Water SuoolV County-State Plant Name Water Source Notification Advise State or Local Authorities listed in the REND 10-Mile Radius Hamilton-Tennessee Sequoyah Nuclear Plant Gold Point Marina East Side Utility Tennessee River Tennessee River Tennessee River Industrial Industrial Chickamauga Dam (Power Service Center)
Chickamauga Dam Tennessee River Tennessee River Tennessee River Industrial Industrial 25-Mile Radius E. I. Dupont Co.
Tennessee American Water Co.
Rock-Tennessee Mill1 Vulcan Sand & Gravel' Signal Mountain Cement' Medusa Cement Co.
Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Industrial and Potable Municipal Industrial Industrial Industrial Industrial 50-Mile Radius Marion-Tennessee Jackson-Alabama Jackson-Alabama 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 and Spring Tennessee River and Spring Tennessee River Tennessee River Industrial Industrial Municipal Industrial Municipal Industrial Industrial
'Obtains potable water from Tennessee-American Water Company.
- 2Obtains potable water supply from Bridgeport - physically removed potable water intake in November 1986.
I
(
(
(
EN'h..
L DOSE ASSESSMENT STAFF ACTIVITIES DURING NUCLEAR PLANT RADIOLOGICAL EMERGENCIES CECC EPIP-8 Page 32 of 32 Revision 25 APPENDIX J Page 3 of 3 WBN - PUBLIC AND INDUSTRIAL SURFACE WATER SUPPLIES ON THE TENNESSEE RIVER Type of Plant Name Water Source Water SuDply County-State Notification Advise State or Local Authorities listed in the REND 10-Mile Radius Rhea-Tennessee Watts Bar Fossil & Hydro Plant' Watts Bar Nuclear Plant Tennessee River Tennessee River Industrial 2,3
- Industrial3 4 25-Mile Radius Rhea-Tennessee 50-Mile Radius City of Dayton Dayton Police Tennessee River Municipal Hamilton-Tennessee TVA Sequoyah Nuclear Plant East Side Utility Tennessee River Tennessee River Industrial Industrial E. I. Dupont Chickamauga Dam Tennessee American Water Co.
Rock-Tennessee Milf Vulcan Sand and Gravel5 Signal Mountain Cement 5 Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Tennessee River Industrial and Potable Industrial Municipal Industrial Industrial Industrial IOn 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).
'Cooling water and cooling tower makeup.
5Obtains potable water supply from Tennessee-American Water Company.
CECC EPIP Coversheet Title CECC EPIP-9 Tennessee REV. 27 Valley Authority CENTRAL EMERGENCY ENVIRONMENTAL EMERGENCY CONTROL CENTER RADIOLOGICAL MONITORING PROCEDURES EMERGENCY PLAN IMPLEMENTING Effective Date:
PROCEDURES WRITTEN BY:
A. J. Salatka RD BY:
5' S
/_
Signature /
Signature Date PLAN EFFECTIVENESS DETERMINATION:
6iLZ.
_ _/___
Signature Date CONCURRENCES Concurrence Signature Date 101 Man3^r, EP Progra~lanning and Implementation 0 Manager, Emergency Preparedness 0 Manager, Radiological and Chemistry Services OL$24~7 ct -
7<
APPROVAL APPROVED Br7
.P. En ineegn
& Technical Services
__3___-
/ /
ignature
/
Ttle Organization Date I
U
1 epip9r27.w95
CECC l
Emergency Environmental Radiological EPIiP 9 CECC Monitoring Procedures I
CECC-EPIP-9 EMERGENCY ENVIRONMENTAL RADIOLOGICAL MONITORING PROCEDURES REVISION LOG Rev. No.
Date Revised Pages 0
3/22188 All (Changed from IPD to EPIP) 1 07/08/88 Pages 1 & 2, Page 3 of App. E, Page 4 of App. G Page 3 of App. l 2
4/26/89 All 3
5/15/90 All 4
07/02/90 1, 2, 5, Att. A, pg. 1; Added At. R (pgs. 1-4) 5 11/09/90 Paqes 4 & 5 6
7 8
9 10 12/11/90 03/25/91 10/25/91 5/15/92 11/25/92 Page 4 (only)
All (*Title changed)
All All All pages revised to issue instructions for use of new scalers which are beina Dlaced in the environmental monitorina vans.
11 06/15/93 Pages 4, 5, 9; Att. I, pg. 1; Att. J. pg. 1; Att. K; pg. 1; Aft. M, pg. 1, Aft. Q, pg. 1; Aft. R, pg. 2; all other pages reissued.
12 11/09/93 2-8; 10-11; Att.A, pg. 1-4; Aft. B, pgs. 1-5; Aft. C, pg. 1; Att.
D, pg. 1; Aft. E, pg. 1; Aft. F, pg. 1, 3; Aft. G. pg. 1; Aft. I, pg.
1; Aft. L, pgs. 1-4; Aft. M, pg. 1; Aft. N, pg. 2; Aft. 0, pg. 1; Aft. Q, pg. 1; Aft. R, pgs. 1-2, 5.
13 11/30/93 Pgs. 1, 4-8, 10-13; Aft. A, pg. 4; Aft. G. pg. 1; Aft. H, pgs. 1-2; Att. I, pg. 1; Aft. J, pg. 1; Aft. K, pg. 1; Aft. L, pg. 4; Aft. M, pg. 1; Aft. 0, pg. 1; Aft. S, pgs. 1-2.
14 11/22/94 All 15 05/23/95 All
CECC Emergency Environmental Radiological EPIP 9 t
§
~
~
~
Monitoring Procedures lIX CECC-EPIP-9 EMERGENCY ENVIRONMENTAL RADIOLOGICAL MONITORING PROCEDURES REVISION LOG Rev. No.
Date Revised Pages 16 01/04/96 Procedure issued in new format which included in some cases altering the order of statements, editorial changes, and addition of boxes and shading to high light of statements.
Additional updating was performed on pages 3, 4, 5, 7, 12, 14, 16, 17, 19, 21, 22, 23, 36. All pages issued.
17 12/9/96 1-4, 6-11, 13-19, 21-25, 28-30, 32-39. Changes per annual review.
All pages issued.
18 12/23/97 7, 12, 15, 23, 25, 30, 34, 35 and 36. Update map rev. level, update telephone number, update air sampler instructions, update Barium source chart, change field team form so social security numbers are not read over the radio, update inventory checklists. All pages issued.
19 10/27/98 Delete references to TAC backup radios, area code changes, delete reference to BLN HP radio transmitters, revise air sampler operation instructions, add reference for Iodine concentration, revise sample parameters for soil and snow samples, revise air sampling instructions, add statement for van crew to take any attendant respirator eye ware, update Ba-133 check source table, clarify items for RMCC and courier kits. Al pages issued.
20 12/21/99 Change uAttachments" to "Appendix". Update Ba-133 check source decay charts. Editorial changes. All pages issued.
21 6/15/00 Annual review, editorial changes, remove reference to BLN repeaters, remove requirement to keep copy of latest inventory check in vans, indicate new packaging for KI remove reference to second Bicron AnalystINal set.
22 12/27/00 Update Barium Source Activity Chart on page 23. All pages issued.
23 11/09/01 Clarify SRMAC definition, clarify courier instructions, provide information concerning how sampling points are to be used, indicate dates of interim map changes, update BFN Stack release table per CECC-EPIP-8 changes, update Barium Source Activity Chart, update field team forms based on training feedback comments, add fire extinguisher information to inventory forms and other minor equipment or supply additions, minor editorial changes. All pages issued.
I CECC l
Emergency Environmental Radiological I
E D 1 i9 l
Monitoring Procedures I
IP~9 CECC-EPIP-9 EMERGENCY ENVIRONMENTAL RADIOLOGICAL MONITORING PROCEDURES REVISION LOG Rev. No.
Date Revised Pages 24 11/30/01 Clarify initial site boundary survey, pp. 6, and App. B. Added information on GPS units page 7 and added Appendix N.
Revised data forms to include data column for GPS Bearing degrees on Appendix F, G. H, I. Added GPS as line item on van inventory, page 33, Appendix J.
25 3/4/02 Update map revision status, revise WARL Screening Van Inventory list. Minor editorial changes. All pages issued.
26 12/05/02 Procedure issued in new format which included, in some cases altering the order of statements and editorial changes; Added new Step 2 to Appendix A to notify Site Security that van is being deployed for site boundary surveys; Updated Appendix C, Table 1 - Barium Source Activity Chart; Changed references for CECC EPIP-12 to CECC EPIP-15 (superceded CECC EPIP-12); Removed blank spaces from inventory appendices.
27 6/16/03 Implementation of Tritium Monitoring; removed reference to Data Systems Radiological Emergency Procedures, CECC EPIP-12; Deleted Barium Source Ba'33 Pt84 and added Barium Sources BaI33 Pt84 and Ba'33 Pt84 to Appendix C; Updated Barium Source Activity chart in Appendix C;
I CECC Emergency Environmental Radiological EPIP-9 l
I Monitoring Procedures Table of Contents 1.0 Purpose............................
3 2.0 Scope............................
3 3.0 Activation 3.1 Command and Control
.3 3.2 Site RADCON Staff (Field Control
.3 3.3 Environs Assessor & Field Coordinator
.4 3.4 Environs Monitoring Teams
.4 3.5 Screening Van Team
.5 3.6 Courier
.5 3.7 Fixed Monitor Retrievers
.5 4.0 Field Operations 4.1 Priorities
.6 4.2 Plume Tracking and Survey
.6 4.3 Sample Point Maps
.8 4.4 Radio Protocol
.8 4.5 Routine Dose Control
.9 4.6 Emergency Dose Limits.10 4.7 Potassium Iodide (KI).11 4.8 Contamination Control.11 5.0 Communications 5.1 Primary Motorola Radio...........................
11 5.2 Cellular Telephones...........................
12 5.3 Important Phone Numbers............................
13 5.4 HP Radio System Phone Patch...........................
14 6.0 Electrical Power Supplies 6.1 Vehicle-installed Generator...........................
14 6.2 DC toAC Power Inverter...........................
15 6.3 TVA Siren...........................
15 6.4 Honda Generator...........................
15 7.0 Air Sampling 7.1 Preparation of Plume Air Sample.16 7.2 Radeco H810 Totalizer - Grab Sampler.16 7.3 Radeco H810 Totalizer - Continuous Run Sampler.17 7.4 Analysis of Air Samples.17 7.5 Scintrex, Model 309A Tritium-in-Air Monitor.18 7.6 MSA Escorts ELF Pump.19 PAGE 1 OF 48 REVISION 27
I CECC Emergency Environmental Radiological E P P I 91 l
I Monitoring Procedures l
P Table of Contents (continued) 8.0 Terrestrial Samples 8.1 Vegetation Sample........................
21 8.2 Soil Sample........................
21 8.3 Snow / Ice Sample........................
22 8.4 Other Samples........................
22 8.5 Sample Identification and Labeling........................
23 8.6 Isotopic Analysis of Samples........................
23 9.0 Operational Readiness 9.1 Monitoring Team Vehicles..................................
23 9.2 Screening Van Equipment..................................
23 9.3 Field Coordinator Equipment..................................
24 9.4 Courier Equipment..................................
24 10.0 References...................................
24 Appendixes I
I I
I I
I Appendix A:
Appendix B:
Appendix C:
Appendix D:
Appendix E:
Appendix F:
Appendix G:
Appendix H:
Appendix l:
Appendix J:
Appendix K-Appendix L Plant Lab Dispatch Monitoring Team Activation / Shift Turnover Scaler Set-Up Shift Information Sheet and Team Dose Tracking Log Emergency Authorizations Field Team Measurement Log TVA Field Team Control Monitoring Record Monitoring Team Vehicle Inventory WARL Screening Van Inventory Field Coordinator Kit Inventory Courier Kit Inventory Global Positioning Satellite Unit Operation 25 26 27 29 31 33 34 35 39 43 44 45 I
I I
I I
I 1
PAGE 2 OF 48 REVISION 27
CECC Emergency Environmental Radiological I
E IiP 9 I I Monitoring Procedures 1.0 PURPOSE This procedure describes environmental radiological monitoring during or after an emergency at a TVA nuclear facility.
2.0 SCOPE This procedure provides instruction for environmental monitoring under the direction of the plant Radiological Control (RADCON) staff, the Central Emergency Control Center (CECC) or the Radiological Monitoring Control Center (RMCC).
The location term SRMAC (State Radiological Monitoring Assessment Center) is referenced in the Alabama Radiological Emergency Response Plans for Nuclear Plants.
For the purpose of this procedure, it is considered synonymous with the term RMCC.
Checklists and instructions for the inspection, inventory and use of field equipment are also included within this procedure. Several sequences or options may be used to obtain the same results with equipment operation or sampling techniques. Only one method will be discussed in this procedure.
3.0 ACTIVATION OPTIONAL:
At an Alert or Unusual Event classification.
MANDATORY:
At a Site Area Emergency or General Emergency unless directed otherwise by the Site Emergency Director.
3.1 Command and Control As emergency response facilities become operational, command and control shall progress from the Site RADCON staff to the CECC and RMCC. The CECC Environs Assessor has responsibility for control of environmental monitoring efforts.
Since the time of operational status of facilities may vary, instructions may generically refer to "Field Control".
l 3.2 Site RADCON staff (Field Control)
A quick reference Table of Contents is provided at the front of this procedure for detailed instruction on emergency authorizations, dose control and field monitoring strategies and priorities.
Ensure that any DOSE RATE or AIR ACTIVITY survey results are PROMPTLY reported to assist in determining emergency classification levels by the Site Emergency Director.
Report survey locations as a distance and direction.
PAGE 3 OF 48 REVISION 27
CECC l
Emergency Environmental Radiological I E P1 P 9 Monitoring Procedures I
E Anticipate contact by the CECC Environs Assessor to coordinate a turnover of field control. The transfer of control should be announced on the radio. Thereafter, contact with all field team personnel should be routed through Field Control to avoid conflict of assignments.
3.3.
Environs Assessor (EA) & Field Coordinator (FC)
,v,. A d A....................
,. I~~~~~.
instruction on emergency authorizations, dose control and field monitoring strategy and priorities.
IEnsure that any DOSE RATE or AIR ACTIVITY survey results are PROMPTLY reported for considerations on dedaration of emergency classification levels by the Site Emergency Director. Report survey locations as a distance and direction.
If reporting to a RMCC obtain a FC kit from the CECC. Ask CECC Emergency Preparedness staff if other equipment needs to be taken to the RMCC (fax, etc.).
BFN RMCC Morgan County Courthouse basement, Decatur, AL SQN RMCC Air National Guard Armory, Lovell Field, Chaff., TN WBN RMCC TEMA Operations Center, Alcoa, TN Coordinate the deployment of the Scintrex Tritium 309A instruments to State field teams.
Upon arrival at the RMCC, establish TVA phone, radio and fax machine communication.
Ensure other field monitoring support staff are adequately briefed on their expected roles (Courier, Fixed Monitor Retrievers, Field Support).
Direction and control of all field operations shall be limited to one individual on the radio.
3.4 Environs Monitorina Teams
..E I> f
-E -;
- - h a.
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HE
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i ;;. -tnf~~~onr.
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per Appendix B,...
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A a j, A
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I: eodfel aao Apt~
pendix F (s rats Airand terr-estn ial)
Use column heading numbers for communication of data. Report survey locations as a distance and direction, and if applicable, the sample point. Command centers need distance and direction for decision logic.
A quick reference Table of Contents is provided at the front of this procedure for detailed instruction on radiological protection, equipment operation and sampling techniques.
PAGE 4 OF 48 REVISION 27
CECC Emergency Environmental Radiological r PIP-D l
I Monitoring Procedures I
3.5 Screening Van team Obtain dosimeters (TLD and 200 mrem self-reading dosimeter). Prepare the vehicle for departure according to WARL procedures. Establish radio contact with the field team control to ascertain team member dose information and obtain assignment.
3.6 Courier Couriers transport radioactive samples or deliver personnel, supplies and equipment.
Courier personnel shall be familiar with concepts for basic radiation protection. The Courier should avoid plumes or radioactivity contaminated areas due to interface requirements outside the affected area, but may do so at the discretion of Field Control.
Obtain a radio equipped vehicle. If needed, a Courier Kit and sample transport containers can be provided by Corporate Emergency Preparedness.
Obtain briefing from the Environs Assessor or Field Coordinator.
Prior to deployment into the EPZ or receiving samples, don dosimeters (TLD and 200 mrem self-reading dosimeter). Re-zero as necessary.
A quick reference Table of Contents is provided at the front of this procedure for detailed instructions (emergency phone numbers, inventory lists and operation of equipment).
Upon arrival at the vehicle, establish radio contact with the CECC Environs Assessor or RMCC Field Coordinator.
Obtain the appropriate maps and sample point description book from the Courier Kit for ready reference.
3.7 Fixed Monitor Retrievers Fixed Monitor Retrievers collect specific samples and environmental TLDs as requested by Field Control. Their duties are similar to non-emergency responsibilities.
Obtain job-specific supplies and equipment and establish communication with the Environs Assessor/Field Coordinator.
Refer to Table of Contents (front of procedure) for detailed instruction on emergency authorizations, dose control and field monitoring techniques and equipment operation.
PAGES OF48 REVISION 27
CECC Emergency Environmental Radiological I
E I DP C I
I Monitoring Procedures I
l 4.0 FIELD OPERATIONS 4.1 Priorities During the early phases of a radiological emergency when protective actions must be initiated quickly to be effective, environmental measurements used to calculate the inhalation dose commitment rate to the thyroid and the total body external gamma dose rates to the general public are the most important.
Knowledge of radiological conditions at the site boundary and at a distance of 5 miles out from the plant are critical for decisions on emergency classifications and for Protective Action Recommendations to the State.
Environs Monitoring Teams shall perform their tasks according to the following priorities unless directed otherwise by Field Control:
- 1.
The first team to activate shall promptly obtain dose rate measurements along the designated site boundary at the down wind areas (see 2 mile map) to obtain site boundary survey prior to scaler set-up.
- 2.
Upon detection of plume immersion, collect and analyze an air sample for radioiodine and particulates at estimated plume centerline.
- 3.
Upon detection of plume immersion, collect and analyze an air sample for tritium at estimated plume centerline. [ONLY PLANTS THAT CURRENTLY CONTAIN IRRADIATED TPBARS ONSITE]
- 4.
The second team to activate shall focus on locating the (offsite) touchdown point of the plume and collect air samples for analyses.
- 5.
As additional teams become available, dispatch to the opposite side of the river should be considered for the contingency of (near plant) wind shifts and the travel time required.
- 6.
Send air filter media to the screening van or WARL for further analyses as directed by Field Control.
4.2 Plume Tracking and Survev When directed by Field Control, Environs Monitoring Teams shall traverse along the assigned route to locate the plume. Travel at approximately 20 mph (during drills, simulate reduced speed as necessary to avoid traffic hazards). Practice safe vehicle operation with attention to height limitations, safe roadside pull-offs and parking, accessing private property and use of the warning strobe lights. Secure cabinets, lead shields, and personnel seat belts prior to vehicle movement.
PAGE 6 OF 48 REVISION 27
CECC Emergency Environmental Radiological l
1D I,
I I
Monitoring Procedures 9
P Sample Points (clarification for PER CRP 01-000161-000)
The intent and use of sample points has evolved in consideration of REP van upgrades and dose assessment methods. Prior to the Installation of onboard gas generators in the vans, sample points with sirens were of greater value as a source of AC power. With improvements of equipment and dose assessment capability, field data is now used for comparisons with computer dose assessments, with the desired data being the actual plume centerline location, which may or may not be at a sample point. Therefore, although sample locations are described as a particular point, sample points should be used as a reference to a vicinity where plume search and traverse is begun (pin-point accuracy is not essential). This is why our ability to communicate survey locations using distance and direction is more important. Global Positioning Satellite (GPS) units are an available tool to supplement our field navigation using the sampling point maps. GPS instructions are provided in Appendix L. Column 2 on Appendices F and G may be N/A'd when sampling is performed at a sample location that does not have a specific sample point address.
In regard to timeliness during plume monitoring the expectation is for monitoring without delay when requested. However, the need to backtrack your travel path to confirm a location is not considered a delay. Examples include backtracking to confirm a peak radiation (centerline) level, or to continue down the road to locate a crossroad or reference point. And as always, road safety should never be compromised.
Monitor the survey meters (open and closed beta shields) to determine plume immersion versus shine.
... :. naaEe$aSE-.p i HHl H :
- H
- : :
Report "Plume Traverse" readings at the estimated PLUME CENTERUNE. If instructed to survey plume edge, report EDGE. If the centerline cannot be determined (i.e., if required to turn back with rates still increasing), report plume location as UNKNOWN.
NOTE: If less than 2 mrem/hr, report Geiger-Mueller Survey Meter (GMSM) measurements. If greater than or equal to 2 mrem/hr, use measurements from the Ion Chamber Survey Meters (ISM).
If plume immersion is suspected, the following ALARA practices are recommended when surveys are requested:
- 1. consider the use of the air sampling portal to obtain 1-meter ISM measurements.
- 2. use of the rear air lock exit to obtain "Near Ground" surveys.
Assessment of ground deposition coud be requested in support of public dose assessment.
PAGE 7 OF 48 REVISION 27
CECC l
Emergency Environmental Radiological I
EP D I
9 I
Monitoring Procedures 4.3 Sample Point Mans (latest revision levels)
Map Rev.
Date BFN 2-mile 3
February 2002 BFN 10-mile 3
February 2002 BFN 50-mile 2
1 July 1994 SQN 2-mile 2
February 2002 SQN 10-mile 2
February 2002 SQN 50-mile 1
30 June 1991 WBN 2-mile 3
February 2002 WBN 10-mile 2
February 2002 WBN 50-mile 2
30 August 1993 4.4 Radio Protocol NOTE: During drills or exercises, all personnel should state "THIS IS A DRILL' when transmitting simulated radiological or plant accident conditions, or other information which may cause public concern if it were monitored. Use of urepeat-back's" and phonetic is the expectation..
I Maintain communication with field team control according to the following sequence. Use the vehicle's external speaker during exits.
1.
2.
3.
Motorola mobile radio (with repeater activated frequencies)
Cellular phone Leave area of hazard and contact by public phone I
The following call signs are designated for field operations:
Base Stations CECC Site TSC Site Plant Lab RMCC Mobile Units Truck # (monitoring vehicle)
Screening Van Courier Portable # (misc.)
I-PAGE 8 OF 48 REVISION 27
I I
CECC Emergency Environmental Radiological I
E D I D 9 I
I Monitoring Procedures I
PIP 4.5 Routine Dose Control The dose of personnel during emergency operations shall be maintained As Low As Reasonably Achievable (ALARA).
.CAW1]
Personel s.o.u.. e awareof otenti-apid chagin conditi n..
For purposes of this implementing procedure, radiation exposure as expressed in units of R and subunits, thereof, is equivalent to dose (rad) and dose equivalent (rem) based on ANSI N 13.11 development and terminology. Any acute dose greater than 10 rem is generally denoted in units of rad, since that level is considered as the accident range of personnel exposure. Any dose less than that level is considered the protective range of personnel exposure. For purposes of this procedure the assumption of 1 rad = 1 rem is assumed for all levels of exposure.
Field personnel shall report their self-reading dosimeter readings to Field Control at approximately every 100 mrem increment and record doses on Appendix D.
Until isotopic assessments of airborne radioactivity are available, the CECC Environs Assessor shall apply an administrative correction factor of 2 to estimate TEDE doses in airborne radioactivity areas:
Estimated TEDE = dosimeter reading x 2 When accident specific radionuclide assessments are available, dose assessment activities should be performed to adjust the correction factors.
Personnel shall advise Field Control when TEDE doses (including pre-emergency doses) approach their individual dose limits. Limits used for declared REP emergency events are based on 10 CFR 20, versus TVA administrative levels. Perform this notification early enough to allow exit from the area prior to exceeding any limits, if higher doses are not authorized.
................... N e m n A Jk--:--.D.
I S.e p t
i.e,n A. pped.
The Environs Assessor shall coordinate appropriate post exposure dose assessments for field personnel.
PAGE 9 OF 48 REVISION 27
CECC Emergency Environmental Radiological I
E P
Monitoring Procedures l
4.6 Emergency Dose Limits The dose of personnel during emergency operations shall be maintained As Low As Reasonably Achievable (ALARA). If circumstances require field personnel to remain in a radiologically hazardous area, higher whole body dose limits may be authorized. Any decisions to embark on emergency operations which would result in doses in excess of 10 CFR 20 should be done in consultation with the most senior member of RADCON who is available on a timely basis.
~~~~~~~~~~~~~~~~~~~~............................. -......
Receipt of emergency dose above normal limits shall be on a voluntary basis Other factors being equal, older volunteers should be selected first. In addition, selection of female volunteers capable of reproduction should be avoided if other volunteers are available.
The use of respiratory protection equipment and protective clothing should be considered to minimize personnel contamination. Personnel shall not enter any area where dose rates are unmeasureable with instruments and dosimetry (i.e., offscale high reading).
Personnel receiving emergency doses shall be informed of the risks involved, including the numerical levels of dose at which acute effects of radiation will be incurred, and numerical estimates of the risk of delayed effects. Recipients shall acknowledge review of this information (located on Appendix E, page 2 of 2) by signature on Appendix E. Dose under these conditions shall be limited to once in a lifetime.
For Lifesaving or Protection of Larae Pooulations the limit is 25 rad TEDE, (when lower dose is not practicable). In this situation, the limit for lens of eye is 75 rad, or three (3) times the TEDE value. The limit for any other organ (including skin and body extremities) is 250 rad, or ten (10) times the TEDE value.
.. ~~~~~~~~~~~~~~~~~~~~~~.....
....t.,..............
..... i-. -.
.s.7
.NOT Situation may occr inwhiha dose i excess; of 2 ad would be r~equired for lifesaving, takep tof sarec ds bve thnieo aohj ormal perisshlbeons nra volnt~anmryec bass. Other femhliev the d ese ld exeed 25 rpd thc whood should Md si othnr volu nt are basis and with full0. awarns Aof thisks inoWd For Protection of Valuable ProDertv the limit is 10 rem TEDE (when lower dose is not practicable). In this situation the limit for lens of eye is 30 rad, or three (3) times the TEDE value. The limit for any other organ (including skin and body extremities) is 100 rad, or ten (10) tmes the TEDE value.
PAGE 10 OF 48 REVISION 27
CECC Emergency Environmental Radiological EP I D C]
I Monitoring ProceduresAdEE s
4.7 Potassium Iodide (KI)
If field personnel are expected to receive a cumulative dose to the thyroid (from inhalation of radioactive iodine) which might exceed 10 rem, then a dose regimen of Potassium Iodide (KI) should be considered. Since Environs Monitoring teams have the greatest potential need for thyroid blocking, KI should be administered at the time of initial dispatch.
This action would allow absorption of the KI prior to the exposure. Authorization shall be provided by the most senior member of RADCON who is available on a timely basis.
Otherwise, teams are granted authorization by this procedure to self-administer KI in accordance with the TVA Protective Action Levels on Appendix D. Field Control is to be immediately informed of such action.
The decision of KI for field team members other than Environs Monitoring Teams shall be based upon their needs. The CECC Environs Assessor has the responsibility to authorize the administration of KI for field staff under CECC control. The Environs Assessor shall inform the CECC RAM of that action. The person authorizing the issuance of KI shall be familiar with the Food and Drug Administration's approved package insert and ensure each recipient is similarly informed.
Document the authorization and.accet.ane-of 1(1 4n Appencfix E.
4.8 Contamination Control Minimize opening and exiting of the van in plume conditions. Use equipment and materials to identify contamination and minimize its spread to personnel and the vehicle interior. Interior air-lock door should remain closed. Exercise precautions with use of personal protective equipment, such as respirators against adverse impacts to safe vehicle operation. Place contaminated clothing and waste in plastic bags and store in the van until arrangements can be made for final disposal. Contact Field Control for arrangements with personnel and vehicle decontamination.
5.0 COMMUNICATIONS 5.1 Primary Motorola Radio The POWER switch is on the bottom right side of the front control unit.
Select transmitters with MODE switch. Selections are programmed in the following order:
- 1. WILSON - BFN
- 4. deleted
- 7. MONTLKE - SQN
- 2. BRINLEY - BFN
- 5. deleted
- 8. OSWALD - WBN
- 3. MONTE S - BFN
- 6. SIGMTN - SQN
- 9. RSVLT - WBN VOL adjusts the volume, (range 1-15 with normal volume around 10).
SQL button on keypad unsquelches radio. Press SQL momentarily to display "MONITOR ON" to allow channel monitoring. Display alternates between "MONITOR ON" and "MONITOR OFF".
PAGE 11 OF 48 REVISION 27
I
~~~~~~
II CECC Emergency Environmental Radiological I
E D
IP9 I
Monitoring Procedures
. P SQL also used to set the squelch level (0-4). Depress SQL and hold until the beep, then adjust up or down using the MODE switch. Then press HOME to return to normal operation. Repeat adjustment to the minimal level at which continuous static is eliminated.
HOME button returns the unit to normal operation after adjustment of squelch. HOME button also returns the unit to the first transmitter in the programming sequence.
DIM adjusts brightness of the display (four levels with one oft).
The primary position for the DIR button should be with the red light OFF (unit will now automatically activate the repeater).
FIR switch is for activation of either the fronttrear control. "REMOTE" or UREAR" display indicates the other control head is operational. Depressing the FIR button repeatedly alternates the front and rear control function.
The SCAN, EMER and keypad keys are not operational.
Use Microphone keypad for entry of radio-phone patch numbers.
NOTE: Ensure the active repeater is displayed (versus "REMOTE" or 'REAR") prior to attempting data transmission.
5.2 Cellular Telephones Depress PWR [power]. If unit reads "Loc'cF', enter the unlock code of "REP" or 737.
To use unit as a speaker phone (hands-free operation) leave unit in the cradle. The microphone is mounted above the driver's window.
To answer a call, press SND.
To hang-up, or clear a number, press CLRIEND.
To place a call, enter number then press SND [send]. If calling long distance, dial the area code with the number (use of "0-" or "1-" may vary with location).
24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> assistance:
Public telephone 1-800-922-0204, From vehicle 611 PAGE 12 OF 48 REVISION 27
CECC Emergency Environmental Radiological EP I P-9 Monitoring Procedures 5.3 Important Phone Numbers I
o ato
\\,-,
R,>Pho c.....................
CECC Environs Assessor 423-751-1623 423-751-1624 423-751-1681 BFN RMCC 423-751-1672 256-351-0441 256-355-1680 SQN RMCC 423-899-9858 423-751-1676 423-855-0190 WBN RMCC 865-981-5608 865-981-5632 BFN TSC RADCON 256-729-3767 256-729-3763 256-729-3742 SQN TSC RADCON 423-843-6472 423-843-6461 WBN TSC RADCON 423-365-8606 423-365-8608 423-365-8365 CECC Operations Duty 423-751-1700 800-237-2322 Specialist (24 hr) 40A a
a..
't c
1 ' >'.
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.., aa a
.a' 'a a......
,0 CECC_____________________________________IdWarP............
TV44062 423-CECC Truck 2 TV-44062 423-240-6267 SQN Truck 2 TV-44063 423-240-6268 SQN Truck 3 TV-44053 423-667-4921 WBN Truck 4 TV-44054 423-667-4918 BFN Truck 5 TV-44084 256-508-4872 BFN Truck 6 TV-44052 256-656-9623 Screening van TV-44019 256-740-1566 (voice & fax)
PAGE 13 OF 48 REVISION 27
I CECC Emergency Environmental Radiological I
EPIP D9 I
Monitoring Procedures l
5.4 HP Radio System Phone Patch To place a telephone call from a mobile radio:
Enter proper access code and wait for a dial tone (if no tone, depress # to clear command and restart).
Access Code 1*1 01
'9*11 02
"*1* 03 Transmitter Locations Wilson Hydro Plant Brinley Mountain Monte Sano Plant Site/Local Area BFN/Muscle Shoals BFN/Decatur BFN/Huntsville a*9 06
"*yI 07
"*I 08 1*n 09 Signal Mountain Montlake Oswald Dome Roosevelt Mountain SQN/Chattanooga SQN/Soddy-Daisy, Dayton WBN/Cleveland, Athens WBN/Spring City, Rockwood After the dial tone, dial "9" for a second dial tone.
Depress "1" + (Area Code) + 7 digit number + "".
(Chattanooga calls may not require long distance area code.)
Depress "'" to disconnect (hang up).
6.0 ELECTRICAL POWER SUPPLIES
...........ofteft..........
Ile M-
) ZQ -, COM P JK IA ""'M........................... W ift.
b."O "INA.
4......i.......
Circuit breakers for the vehicle's electrical system are located in a gray breaker box inside the cabinet 8. Additional circuit breakers for the onboard generator are located on the rear facing side of the generator housing.
I 6.1 Vehicle-installed Generator Place GENERATOR-SHORE POWER switch to the neutral position to avoid attempted starts under load.
Depress generator STARTISTOP button, and hold until the engine is running.
Place GENERATOR-SHORE POWER switch to the generator position.
Primary vehicle outlets are now supplied power.
The onboard generator may be run continuously during vehicle operation, using the vehicle tank for fuel. If the generator is no longer needed, depress the STARTISTOP button and hold until the engine stops completely. For vehicles equipped with dual fuel tanks, generator is fueled from front tank; therefore, utilize the rear fuel tank as the primary fuel source for vehicle operation.
PAGE 14 OF 48 REVISION 27
CECC l
Emergency Environmental Radiological l
EPIP ll I
Monitoring Procedures I
6.2 DC to AC Power Inverter (back up use only)
Ensure vehicle engine is running and MASTER switch on the front console is ON.
Place the INVERTER switch, located on the cabinet door panel, to the ON position.
sw6th ontheinverte
"'eel fad e is an the
'O p'ito an
ue h~
swit @is inz Ath m
OF moito (uit tu on reot ho pset switch is.i.:te ON positioK~w.S,,^Qa.,n.'
(
,oes s.nt runWa onrem....te~e°.
hooup settinZ g).
6.3 1WA Siren j;
haza;-2
- > 2 rds such 2as wetx mgrou-nd
-<gj>:: :>->-
Unlock outlet box using key # 0896. Check Ground Fault Interrupter breaker status.
64 Honda Generator Remove generator from vehicle, add fuel as necessary and attach Ground Fault Interrupter (GFI) cord to generator socket.
Ensure Reset button on GFI is depressed.
Slide ENGINE switch, on front of unit, upward to ON.
Push CHOKE lever in direction of arrow to CLOSED.
Pull start cord and prevent it from snapping back against unit.
Turn the CHOKE lever to OPEN as the engine warms up.
I.T......
....... lft-s If power to the outlets is ~~~~ot available, ensure the AC Circuit....is.....the.CLOSE.
I position (ON).~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~.....
PAGE 15 OF 48 REVISION 27
l CECC l
Emergency Environmental Radiological l
EPIP-9 I l Monitoring Procedures I
7.0 AIR SAMPLING 7.1 Preparation for Plume Air Sample S........
e....
e..pe........n~a a d a r qu re d sp sa as~~mlxedv~~~~ast~~..
Do Load head with a Silver Zeolite cartridge, marked to indicate direction of the air flow.
Install a prefilter (rough side out).
Position the vehicle so that the air sample port is toward the plant or upwind direction.
Record 1-meter dose rates for the area on Appendix F. Use ISM if above 2 mrem/hr.
Do not obtain near ground dose rates unless instructed.
Note: Onboard generator power fluctuations affecting flow rate may occur during simultaneous use of the roof top air conditioner unit. It may be necessary to cut the air conditioner off during sampling; or to use the ACIDC inverter as the power source. If power is interrupted during a sample collection, the unit will display the collected sample data upon restoration of power.
7.2 Radeco H81 0 Air Sampler - GRAB SAMPLE
[Grab Sample:0 5 mi-inute Aun at SOLp 2 CFM) flow rate
- ~~~~~~~~.
i.........
Turn power ON using rocker switch on side of unit.
After display stops scrolling, depress the CLEAR key to reset the unit. Display should now read 'TARGET VOLUME: 300 LITERS'.
Depress green START key to begin sample collection, then following the message "WARM UP DELAY IN PROGRESS", observe the display to confirm the desired flow rate of 60 LPM. Adjust as necessary using the recessed slotted screw head above the on-off switch. To perform adjustments, turn the slotted screw head clockwise to increase flow rate and counter-clockwise to decrease flow rate. Since the digital display is very accurate, a flow rate +/- 6 LPM (10%) is satisfactory. Close cabinet door during sampling.
Sampler will automatically shut off upon collection of pre-set volume (300 Liters).
PAGE 16 OF 48 REVISION 27
CECC Emergency Environmental Radiological EP D I D-9 1
~~~~Monitoring Procedures lsl-7.3 Radeco H81 0 Air Sampler - CONTINUOUS RUN Coinuous00 Rgn 0
M (1 &C't-f' Si F...."-:.E.: W : n zai E :.............
.....ifo:
Ia-E :
t;a ai Turn power ON using rocker switch on side of unit.
After display stops scrolling, depress the CLEAR key to reset the unit. Display should now read 'TARGET TIME X)OOX or "TARGET VOLUME X0(X".
Depress green START key to begin sample collection, then following the message WARM UP DELAY IN PROGRESS". observe the display to confirm the desired flow rate of 30 LPM. Adjust as necessary using the recessed slotted screw head above the on-off switch. To perform adjustments, turn the slotted screw head clockwise to increase flow rate and counter-clockwise to decrease flow rate. Since the digital display is very accurate, a flow rate +/- 3 LPM (10%) is satisfactory.
Depress STOP key to end sample.
7.4 Analysis of Air Sample Close sampling portal and cabinet door at end of sampling. If using a power inverter, turn it OFF when not in use.
Relocate as necessary for ALARA purposes prior to continuing.
Remove the cartridge and seal it in plastic wrap. Be cautious of cartridge heat up and the effect on the plastic wrapping. Survey the cartridge with a GMSM (beta shield dosed).
If <1 mrem/hr, analyze with the Nal detector, record data on Appendix F column 16.
If >1 mrem/hr, do NOT analyze with the Nal detector. Advise Field Control and approximate iodine concentration using the formula below:
ji Ci/cc = Average Front & Back contact rate (mrem/hr) x 5.1 x 1 03 Sample Volume in Liters Note:
Formula referenced in RIMS L91 880217 801 DO NOT DELETE I Remove the prefilter with tweezers, and survey using the Bicron Surveyor 50.
If s50,000 CPM, analyze in GM detector, record data on Appendix F, column 17.
If >50,000 CPM, do NOT analyze in the GM detector. Record frisker reading minus background on Appendix F (net CPM or if uoffscaler). Contact Field Control for instructions.
Place the prefilter in a petri dish. Label and package all for transfer to the Courier. (Refer to section 8.5).
PAGE 17 OF 48 REVISION 27
I CECC Emergency Environmental Radiological EPID P9 l
l Monitoring Procedures I
Report data per Appendix F. Report results as "Less than MDA" if below values and I
background rates listed on Appendix F.
lNote: Minimum Detectable Activities for Bicron Analysts per memorandum to C. D.Pondl I
from J. L Lobdell, dated March 28, 1995 (RIMS L91 950328 800). Do not delete l
7.5 Scintrex. Model 309A Tritium-in-Air Monitor Precautions and Limitations Note: This instrument should only be used if GM instruments indicate background levels.
Otherwise, the Tribum results will be invalid due to interference from noble gas.
The electrometer in the Scintrex Model 309A requires a warm-up period of 15 to 30 minutes when all power is lost (i.e., dead batteries). For continuos monitoring or long-duration jobs, consideration should be given to the use of the AC adapter for an uninterrupted power supply.
The Scintrex monitor takes 2 to 5 minutes to settle when turned on. Accommodations for the settling time must be considered by the user when the sampling time is short or quick measurements are required.
PERFORM battery check of the instrument.
Turn function switch to the BAT. /ALARM CHECK position to activate the pump. The alarm will sound once and the alarm light will be activated. Read the battery voltage on the display.
The batteries should be replaced if the voltage is below 3.0 V and if the instrument will be in service for more than four hours. Return the instrument to the Instrumentation group if the batteries need replacement.
PERFORM zero set adjustment of the instrument.
Place the instrument in a low-gamma location (<0.1 mR/hr.).
Turn the function switch to DISPLAY ON and press the ZERO SET push-button. A numerical value followed by the function description will be displayed (i.e., 2 ZERO-SET).
If the ZERO reading is outside the -5 to 5 range, then unlock the external lock-ring, and adjust he ZERO ADJUST potentiometer so the display reads "0n ZERO SET".
Wait at least five seconds and then press the ZERO SET button to return to the display reading. Allow two to five minuets for the reading to stabilize. The display reading should stabilize between -10 to 10 PCiM 3 with minor excursions of up to plus or minus 2 uCi/m3.
If the instrument fails to stabilize, obtain a replacement unit PREPARE the instrument for sampling and OBTAIN measurements.
PAGE 18 OF 48 REVISION 27
I CECC Emergency Environmental Radiological I
ED I
~
~~I Monitoring Proceddires
IP I
Connect air line tubing (no greater than 3 ft ) WITHOUT A MOLECULAR SIEVE to the instrument inlet. Route the tubing to the exterior of the vehicle.
NOTE: Identify the Instrument reading before the pump is turned ON. The reading can be considered as background and subtracted from the sample measurement
[i.e., settled reading _6 RCiUM3, measured reading 1 0 PCiUM3, actual measurement is 10 - (-6) = 16 pLCi/m8J.
(1 pCi~m3 is equal to I1x10 4 pCi~cc)
Turn the function switch to PUMP ON. The message "LOW FLOW" will be displayed and the alarm will sound. The alarm will reset after the necessary flow is achieved. The reading on the display may show fluctuations of a few increments for a few seconds after you turn the pump ON or OFF.
Perform the survey. Read the instrument display and report results in correct range and units.
Gamma dose rates cause fluctuations in the instrument readings. Collect samples only in an area with background gamma dose rates.
MSA Escort ELF Pump I
I 1 7.6 G r a b a m p l e 5 m i u t :r u n a 2 L P f o w raZ CAUTION
- DO NOT charge the battery pack in areas that may contain a flammable mixture of combustible gases, vapors, or dust and air, otherwise, an explosion may occur because a source of ignition exists during charging.
- DO NOT operate the pump in oxygen-enriched atmospheres (more than 21 %
oxygen) containing combustible gases, vapors, or other materials. Fire or explosion can result from operating in these atmospheres.
PAGE 19 OF 48R VI ON2 REVISION 27
IL-i CECC l
Emergency Environmental Radiological I
E PI P-9 ll I Monitoring Procedures I
I l
PREPARE the instrument for sampling and OBTAIN measurements.
l Connect tubing to the inlet (red) side of molecular sieve using a male leur adapter.
l Connect the tubing and molecular sieve to the inlet fitting.
If installed, loosen front cover screw l
and rotate cover to expose OFF/O N OFF/l and RUN/HOLD pushbuttons.
ON HL l
Press ON/OFF button until the I
RUN/HOLD L.E.D. illuminates.
IEli l
The Flow Fault and Low Bat L.E.D.'s will then illuminate.
During the time these L.E.D.'s are being lighted, a number from 0 to 999 will be displayed. This is the total of the pump's operating hours since its last calibration.
l When all three L.E.D.'s are illuminated, the display changes to 8.88 LPMIMINS, to indicate they are functional.
l The pump will then begin operation. The LOW BAT L.E.D. will be dark if the battery voltage is above 4.1 volts. The FLOW FAULT L.E.D. will be dark if the rate is within 0.1 LPM of the setpoint.
The RUN/HOLD button may be pressed to interrupt sampling without causing the timer to reset to zero.
l Press the ON/OFF button at the end of sampling.
Total sample minutes will be on the display and will remain until the pump is turned ON l
again.
Label and package the sample media (zip lock bag) for transfer to the Courier. (Refer to section 8.5).
PAGE 20 OF 48 REVISION 27
CECC Emergency Environmental Radiological I EPIP 9 I I Monitoring Procedures E
II 8.0 TERRESTRIAL SAMPLES 8.1 Vegetation Sample If possible, avoid sampling an area sheltered by trees and obtain samples which are representative of the pasturage where the grass depth is as close to uniform as practical.
RECORD a one-meter GMSM window-closed measurement on a sample label.
Using grass cutters, cut grass near the ground. Avoid pulling up grass since roots are not desired. Pack a marinelli beaker to obtain as large a mass as practical. The sample parameter is activity per kilogram.
Seal the beaker cover with electrical tape, keeping the tape slightly stretched while wrapping.
Affix a sample label with the date, time, location, sample type, exposure rate at one meter above ground and the initials of the collector.
Repeat the sampling process, placing the second sample in a zip-lock plastic bag instead of a beaker. Label in the same manner, using a separate sample number.
8.2 Soil Sample Soil samples should be collected from areas that are relatively free of vegetation, rocks and roots. If vegetation cover can not be avoided, it should be sampled with the soil and the analytical results combined to measure the total deposition per surface area.
RECORD a one-meter GMSM window-closed measurement on a sample label.
Prepare the hole cutting tool (approx. 4.25 inches in diameter) to obtain the soil sample by adjusting the collar above the cutting tube for a 2 or more inch cutting depth.
Collect 5 core samples from a square meter area (4 comers and 1 center). The desired sample parameter is square meters, do not obtain more or less core samples.
lNote: 5 core diameters equals 0.046 square meters. Screening van/fixed lab may multiply l
Note: activity/sample results by 22 to obtain activity/square meter).
I The correct sample depth is obtained by pushing the core tool fully into the ground, and removing the top one centimeter (about one-half inch) from the top of the core (using the putty knife) as the sample retained.
If the soil is too dry or sandy to allow coring, use the shovel or putty knife to collect material about one centimeter deep (approx. 1/2 inch) in the pattern described above.
PAGE 21 OF 48 REVISION 27
CECC l
Emergency Environmental Radiological I EPI P-9 I l Monitoring Procedures l
Place the sample in a marinelli beaker and seal with electrical tape. Affix a sample label with the date, time, location, sample type, sample area, dose rate at one meter above ground and the initials of the collector.
Repeat the sampling process, placing the second soil sample in a large zip-lock plastic bag instead of a beaker. Label in the same manner, using a separate sample number.
8.3 Snow/Ice Sample RECORD a one-meter GMSM window-closed measurement on a sample label.
Set the core tool for a 4 inch depth. Collect 5 core samples from a square meter area (4 comers and I center). The sample parameter is surface area, do not obtain more or less core samples. Ascertain the desired sampling depth from the Environs Assessor, based upon meteorological history.
Note: 5 core diameters equals 0.046 square meters. Screening van/fixed lab may multiply Note activity/sample results by 22 to obtain activity/square meter).
I Place the snow/ice in double plastic bags. Check bags for leakage.
Take a second sample (new sample number) approximately 3 meters from the first by repeating the above steps.
Affix a sample label to both samples.
After the snow/ice melts, pour each sample into separate sample jugs and transfer the sample labels to the jug(s). The funnel in cabinet 10 may be useful for filling the jug.
it NOE GenraoirEb Rutrs" recmedto ii W
TOti iD NOSE 302 August22, 1994...
Do.
g not Xelete this reerece.
8.4 Other Samples RECORD a one-meter GMSM window-closed measurement on a sample label.
Any liquid sample container shall be placed in double poly bags with absorbent material.
Outside bags/container of samples should be dry, non-contaminated, labeled and if necessary display a caution radioactive material tag.
Certain types of environmental samples (i.e., rainwater, milk, food crop, fodder and feed, well water) may be requested by Field Control to assist State activities. The minimum sample quantity, type of container and any special controls will be defined dependent on the needs of the situation.I PAGE 22 OF 48 REVISION 27
CECC I
Emergency Environmental Radiological I
E I P D i9 I
I Monitoring Procedures l
8.5 Sample Identification and Labelinq Each sample shall be tagged with an identification label containing the following appropriate data:
Sample Number 1-meter dose rate Time taken Sample Type Date taken Sampling Flow Rate Location sampled Sample Area (if applicable)
Name of the Collector The sample number is composed of the abbreviation of the Truck number (T2-xx),
assigned to the vehicle followed by a dash and the consecutive number of the sample and type of sample (i.e., T2-11, T2-1P).
8.6 Isotopic Analysis of Samples Isotopic analysis of samples may be provided by the screening van or by WARL. Analysis results are to be reported to the Environs Assessor and Field Coordinator.
9.0 OPERATIONAL READINESS - (Equipment and vehicles)
As a minimum, inspections/inventory checks shall be completed each calendar quarter.
Additional inspection guidelines may be contained in location-specific procedures.
9.1 Monitoring Team Vehicles nscon h
ist s.,
b,, o d
to t ap...cabe. site I Prepardriess EP) Manger te.e........lndrqarer A site-specific method of providing accountability control of equipment and materials between inspections shall be practiced. Inventories shall be completed after drills, training, or emergency use. The training instructor is responsible for inventories following training activities and the RADCON organization is responsible for inventories following drills or emergency response. In either case, a signed inventory form with comment confirming the vehicle was returned in the "as found" condition is sufficient. These inventories shall be forwarded to the Site EP Manager prior to the end of the calendar quarter.
9.2 Screening Van Equipment A screening van is stationed at the Westem Area Radiological Laboratory (WARL).
Inventories and inspections shall be performed in accordance with Appendix I PAGE 23 OF 48 REVISION 27
CECC Emergency Environmental Radiological EPIDP Monitoring Procedures I
9.3 Field Coordinator Equipment A Field Coordinator Kit is available at BFN and the CECC. Inventories and inspections shall be performed in accordance with Appendix J.
9.4 Courier Equipment A Courier Kit is available at BFN and the CECC. Inventories and inspections shall be performed in accordance with Appendix K.
10.0 REFERENCES
10.1 Radiological Emergency Plan.
10.2 Collection of Environmental Monitoring Samples, SC-01, Radiological Laboratory Procedures Manual.
10.3 "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," NUREG-0654 FEMA-REP-1, Rev. 1 (1980).
10.4 "Emergency Dose Assessment Procedures for Atmospheric Releases of Radioactivity from TVA Nuclear Plants," TVA Publication RH-82-1-RA1 (1984).
10.5 "Evaluation of Radiation Emergencies and Accidents Selected Criteria and Data,"
International Atomic Energy Agency, Vienna (1974).
10.6 "Manual of Protective Action Guide and Protective Actions for Nuclear Accidents' EPA-400, October 15, 1991.
10.7 "Domestic licensing of Production and Utilization Facilities," 10 CFR 50.
10.8 TVA CECC EPIP-7, CECC RADIOLOGICAL ASSESSMENT STAFF PROCEDURE FOR ALERT. SITE AREA EMERGENCY AND GENERAL EMERGENCY 10.9 INPO SOER 83-002, "Steam Generator Tube Ruptures", recommendation WBN TROI ID:
INPO SOER 83-002, August 22, 1994.
10.10 "Standards for Protection Against Radiation", 10 CFR 20.
PAGE 24 OF 48 REVISION 27
CECC Emergency EnvironmentaRd ll I
EDI D Monitoring Procedures I
Appendix A Page 1 of I Plant Lab Dispatch
- 1.
Select two qualified persons per team and instruct them to complete Appendix B.
Qualifications I Environs Monitoring Van training I Radiation Worker Training (or equivalent) l I Use of full face respiratory protection I Valid Driver's License Jimmy Wp
- 0 M IS -
QTE
6'. Mole-,...........
an a t
t d'
...... ift"
- 2.
Contact Site Security and advise that a REP Van is being deployed for site boundary surveys (for expediting access into areas controlled for security reasons).
- 3.
For WBN emergencies immediately request a second team from SQN. Instruct SQN staff to establish radio contact with WBN upon arrival at the van (attempt both WBN repeaters, use cell phone for back up), for instructions related to the recommended travel approach to the WBN EPZ and for a recommendation on the need of KI.
- 4.
If the response Is for a plant release with known or potential radioiodine exposure, request authorization for teams to take KI prior to leaving the building (refer to section 4.7) Simulate for drills and do not take if known allergy exists.
S.
Complete the following on field personnel: (Provide to CECC for transfer of control.)
A.
6.
B C._
D.
Obtain the following from the Control Room or ICS and advise teams for deployment:
Suspected Release i progress?
Yes / No I Time:
Wind Direction (from)
(degrees)
(compass direction)
Wind Speed (m.p.h)
(Note: meters/sec. x 2.2 = m.p.h)
Stability Class I
- 7.
As teams establish radio contact, test available transmitters to determine the best reception and advise teams of same. If a Zetron console is installed (BFN and WBN) and reception is poor, depress wMUTE" for transmitters not selected.
I 8.
Report field team data to the TSC per Appendix F.
- 9.
Update wind direction periodically to adjust field team deployments.
PAGE 25 OF 48 REVISION 27
I CECC Emergency Environmental Radiological I
EPDI i
I ~--
I Monitoring ProceduresL.P1~
Appendix B Page 1 of I Monitoring Team Activation I Shift Turnover Complete PROMPTLY! Emergency classifications may depend on field data.
W m.
- 0.
ENT" El El El 01 Identify which radio transmitter to use for initial contact.
Collect keys, instruments, sources, Kl and any personal respirator spider glasses.
Request/administer KI if authorized. Simulate for drills and do not take if known allergy exists.
Monitor dose rates with GMSM while enroute to truck
......................U..............................
0 I..........
-T R U W
............. -A A L.:.A A
01 01 El 01 01 Don TLD, 200 mrem and 5 rem DRD, note initial reading. (complete Appendix D later).
Wrap one GM probe in plastic and secure outside window with beta window open & facing up.
Place second GM and ISM (window dlosed) inside vehicle.
Establish contact with Field Control and synchronize watches.
Prepare GPS unit for operations in accordance with Appendix L.
..,,,....~~~~~~~~~~~~~~~~
TO AI~~~~~~~~~~~Ta~~~~~SA~~~~~<~...........
I.
- *--..-.~~~~~~~~*..........
T EM......
I El DELAY scaler set-up. Obtain updated wind direction and plant release status.
o Unless directed otherwise, immediately obtain dose rates at the down wind site boundary route.
NOTE: Wind direction may fluctuate from the reported direction, therefore, actively search for the plume and report survey results per Appendix F ol Upon arrival at downwind area, COLLECT a GRAB air sample, (I & P & T) even if survey meters indicate background levels. If necessary, go to a low background area to complete the items below and report air sample results per Appendix F
...READ
_10
.........................I
[""""i.-M-100 -P.-L.-ETE.-
0 A
- n. ;
... P M..
--- OG-N r-_j':6ft ibi..... learn'W ad, Iva......,......
El Complete scaler set up per Appendix C.
ElComplete Appendix D. Complete Appendix E if KI was authorized and administered.
El Confirm the truck has at least three-quarters capacity of gas. If equipped, operate on rear tank first (generator runs off front tank).
[3 Contact field team control to report/confirm dose and limits, report operational status and request assignment. Note key events in logbook. If you are a van responding to another site, contact that site for instructions on the recommended travel approach and if KI is recommended.
Unless iec ~ ~~ted h.. w ise~t h.........o.ndtea.......It... d tivule std~tut d""btai yts ~t n i t'~""WeW's diwn tl Q k99ns d
Re vttea beiow rE N eta s.-
I....t......
ume maximum fo BF e.e...e........
Stability Class A
B j C
D I
E F____
Downwind (miles) j0.62 0.62 j0.62 2.0 2.0
~F~
Coordinate inventory requirements per section 9.1 at the end of shift or event termination.
PAGE 26 OF 48RE SON2 REVISION 27
CECC l
Emergency Environmental Radiological E P I P-9 Monitoring Procedures I
Appendix C Page 1 of 2 Name:
t..., :
cron I
i Name:
Analyst Serial #:
Date:
Calibration due date:
- 1.
Perform battery check and position Nal detector in shielded pig.
- 2.
Install cables; Set unit to: Range x 1 000 Channel: 1 Response: S Audio: OFF I
NOTE: To achieve listed MDA, background must be < 255 counts per minute
- 3.
Enter a 1 minute background count:
counts
- 4.
Enter a 1 minute Ba'33 contact count counts
- 5.
Enter net counts: (Step 4 minus Step 3) counts
- 6.
Enter Ba'33 activity from Table I below:
- 7.
Enter Step 5 divided by Step 6:
- 8.
Enter acceptance range from instr. label:
Rci counts tco to It.....
0 A on:
torn eco.. 4
_.0r-AN':::
U.4, _RnQM
- 9.
If unit fails, check source position. Nal probe, cable, and Bicron Analyst are paired, DO NOT SWITCH. Contact Field Control if replacement scalers are necessary.
~~~~~~~~~~..........
Half-life 10.5 yr 2003 2004 Source ID May-Jun Jul-Aug Sep-Oct Nov-Dec Jan-Feb Mar-Apr MayJun Ba" Pt84 0.057 0.056 0.056 0.055 0.055 0.054 0.053 Ba' Pt84 0.056 0.055 0.055 0.054 0.054 0.053 0.052 Ba'-3 Pt84 0.058 0.057 0.056 0.056 0.055 0.055 0.054 Ba" Pt84 0.057 0.056 0.055 0.054 0.054 0.053 0.053 Balm Pt84 0.057 0.056 0.056 0.055 0.055 0.054 0.053 Bal3 Pt84 0.055 0.055 0.054 0.054 0.053 0.052 0.052 Ba
-1 1-Pt84 0.058 0.057 0.056 0.056 0.055 0.055 0.054 Bala Pt84 0.057 0.056 0.056 0.055 0.054 0.054 0.053 PAGE 27 OF 48 REVISION 27
CECC Emergency Environmental Radiological l
i D
I l
I Monitoring Procedures I
I I
Appendix C Page 2 of 2 Sc.-.afer Set-Up: Bcrn Ana...M.Detec Name:
Analyst Serial #:
Date:
Calibration due date:
- 1.
Connect cable to shielded detector and perform a battery check.
- 2.
Set unit range to: Range X 1000 Channel: OUT Response: to S Audio: OFF NOTE: To achieve listed MDA, background must be < 276 counts per minute
- 3.
Enter a 1 minute background count:
counts
.......... :..,:L::..:.::::::.'-..V.-:...'....'..:':'.................................
°otefI count time~t 1,s, n ot I tewset he.11110 2selectorinside the instrumen I
cbinet I
See.'0 i:lustJ ahi on g in~m e~.
.,5.............t...
- 4.
Place Tc99 source on planchet shelf closest to GM tube.
- 5.
Enter a 1 minute lTc99 count:
__________counts
- 6.
Enter net counts: (Step 5 minus Step 3)
__________counts
- 7.
Enter Tc99 activity from source box label:
__________dpm
- 8.
Enter Step 6 divided by Step 7: (efficiency)
__counts
-L dpm i itStep8reult is wirthint acceptanc range of 0.06 to QAinsrueis :iready for use.
Rco
.M ffcinc..t.Apeni.F l.'..'..:'-". ' '
- 9.
If unit fails, check source position. If necessary, the GM tube height can be adjusted slightly. Contact Field Control if replacement scalers are necessary.
PAGE 28 OF 48 REVISION 27
I CECC Emergency Environmental Radiological I
Di I
~ ~~I Monitoring Procedures EPIP-9 1 I APPENDIX D PAGE I OF 2 SHIFT INFORMATION SHEET AND TEAM DOSE TRACKING LOG I Date:
Truck No.:
Time:
Team Members:
I10 CFR 20 Limit = 6000 mirem I
YTD Dose mirem (prior to incident) 1 A 11IB.
1k:C.
IInstrument Data:
IGMSM#
ISM#
Surveyor5O0#
IGMSM#
ISM#
Surveyor 50#
Scintrex 309A Tritium Instrument#~
IMSA ELF Pump Instrument~
IGrab Air Sampler #
Continuous Run Sampler#
TIT
-11W PR 7-Sn
______________CONDITIONACTON 1A.
Any exposure rate> 25 mrem/hr. And 1A.
Potassium Iodide (KI) recommended, radiolodine 1-131) air activit Is not known
___notify Field Control l B.
Any measured dose rate >200 mremlhr.
l B.
Evacuation recommended, notify Field
_ _C o ntro l I C.
Any measured dose rate >1 0 rem/hr.
I C.
Evacuation mandatory, notify Field Control 2A.
2A.
Evacuate unless higher dose is authorized, notify Field Control 2B.
TEDE dose of 25 rad.
__2B.
Evacuation mandatory, notify Field Control 3A.
Radiolodine (1131) air activity 3A.
Potassium Iodide (KI) recommended,
> 8.0 E-7p.il/cc (40 DAC).
___notify Field Control 4A.
Particulate air activity > 1.2 E-7 pCi/cc 4A.
Respiratory protection recommended, (40 DAC).
___notify Field Control 4B3.
Particulate air activity > 6.0 E-7 pCi/cc 4B.
Respiratory protection mandatory, notify (20DC).
Field Control 4C.
Particulate air activity > 6.0 E-6 pCi/cc 4C.
Evacuation mandatory, notify Field Control (2000 DAC).
One radiolodine DAC = 2.0 E-8 pCI/cc One particulate DAC =3.0 E-9 zCL'cc I DAC = 2.5 millirem One HTO DAC =21.6 pCi/rn = 2.16 E-5 pCi/cc I
I I
PAGE 29 OF 48RE SIN2 REVISION 27
I I
CECC Emergency Environmental Radiological I
P IP91 I
Monitoring Procedures l
APPENDIX D PAGE 2 OF 2 SHIFT INFORMATION SHEET AND TEAM DOSE TRACKING LOG ESTIMATED TEDE = DOSIMETER READING x 2 (Section 4.5)
FOR HTO-ONLY EXPOSURES, DETERMINE DOSE BASED ON DAC HOURS I
I.
Dose Trackin Log:
21 22 22 24 25 TEDE Estimate "As Team PC "A2 Read" Total "As Read" Corrected" KI Taken Mem.
Time (mrem)
Incident Dose per Field Control Yes/No (mrem)
(mrem)
IA.
lA.I A.
I DOSE Trackin _ Log:
21 22 23 24 25 TEDE Estimate "As Team PC "As Read" Total "As Read" Corrected" KI Taken Mem.
lime (mrem)
Incident Dose per Field Control YesINo lB.
(mrem)
(mrem) l B.
B.
l B. _
Dose Trackin 3Log 21 22 23 24 25 TEDE Estimate "As Team PC "As Read" Total UAs Read" Corrected" KI Taken Mem.
Time (mrem)
Incident Dose per Field Control Yes/No (mrem)
(mrem)
I C.
C.
C.
=
C.
C.
BE ATTENTIVE TO PROTECTIVE ACTION LEVELS ON PAGE 1 OF 2 I
PAGE 30 OF 48 REVISION 27
CECC l
Emergency Environmental Radiological E PIP 9 ]
Monitoring Proceddres EP Appendix E Page 1 of 2 Emergency Authorizations
- 1.
Emergency Dose Limits The persons listed below acknowledge they have volunteered to receive an emergency dose, have been briefed on the emergency situation, and are aware of possible consequences of being exposed to a radiation dose up to the authorized limits (see page 2 of 2).
Signature SocVa..S..
e it.
Liit
....... Daie Authorized by:
Name & Title Date Time
- 2.
Issuance of Potassium Iodide KI The persons listed below acknowledge they have been authorized to take KI on a voluntary basis and have read and understand the information provided on the Food and Drug Administration approved package insert.
Approved Dose: I tablet (130 mg) per day i
i So I.Date
.r......
7-
..... 7~ n
........D '..
tan1 1k.......
Authorized by:
Name & Title Date Time PAGE 31 OF 48 REVISION 27
CECC Emergency Environmental Radiological PI P 9 I
-- Monitoring Procedures I
Appendix E Page 2 of 2 Emergency Authorizations EPA EMERGENCY DOSE RISK INFORMATION I.
...a.
.............Efe t A.s..ath
- l. Bo.dy o
E__________ Hi~e- --
h Receiv hi:..
a FEw u:s:.
Whole Body Early.-.
Whole Body Prodromal Absorbed Fatalities2 Absorbed Dose Effects3 Dose (percent)
(rad)
(percent)
(rad) 140 5
50 2
200 15 100 15 300 50 150 50 400 85 200 85 460 95 250 98
'Risks will be lower for protracted exposure periods.
2 Supportive medical treatment may increase the dose at which these frequencies occur by approximately 50 percent.
3 Forewarning symptoms of more serious health effects associated with large doses of radiation.
II.
~~~~~~~~~~............
1, S5
-Apx.mmc..rf.s~k
........... E.............. D.............v o X
e n i U e b v e r e d X r o m
u :
Age at Dose Risk of Premature Death Average years of life lost (years)
(deaths per 1,000 persons if premature death occurs exposed)
~~~~(years) 20to30__
9.1__
24
.........4 1 9
_5
.3_
1 5 7
50to60 3.5 11 Note: Tables referenced from the Environmental Protection Agency's "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents", (EPA-400), May 1992, tables 2-3 and 2-4, page 2-12.
PAGE 32 OF 48 REVISION 27
CECC Emergency Environmental Radiological E E P IP-I l
Monitoring Procedures II APPENDIX F PAGE 1 OF I FIELD TEAM MEASUREMENT LOG NA I Correction Factor:
GM Efficiency:
o'31dine MDA = 2.0 E-9 (if BKG < 265)
Particulate MDA = 2.0 E-9 (if BKG c 276)
'lodine 11CI/cc = (CPM) (Correction Factor)
Particulate pC/cc =
(CPM) (4.505 E-10)
Volume in Liters (Efficiency) (Volume in Uters) 1 Tritium pCi/cc = (NET Scintrex Tritium monitor reading pCi/m") (1 E -6)
REPORT BY COLUMN NUMBER ONLY 1 -
I q~~~~~~.........
W I
.~~~~.
~~~~ ~.......
A %
7~t I
1 2
3 4
5 6
TRUCK SAMPLE DISTANCE DIRECTION FROM TIME RELATIVE PLUME POINT (Miles)
PLANT (Degrees)
TAKEN POSITION (CIRCLE)
EXPQ$URE RATE E)ATAE Repor Coun 1-9=
fat Plu.me 0
Taese Re Sr Cofumns 143 fo Stati ona$j S 22 Sre 7
8 9
11 12 13 INST.
1 Meter WIC
. 1 Meter INST.
NEAR NEAR TYPE mR/hr WIO mR/hr TYPE CONTACT WIC mR/hr CONTACT W/O mR/hr I
I Run rime Flow LPM SAMPLE VOL (L)
BKG GROSS NET LP GRS NET__
1-131 I
I Pnrn
-[ I I
Legend Column 6 Column 20 C - Center HP - Heavy Particulate P - Particulate Filter T - Tritium E - Edge ICE - Ice RW - Rain water TLD - Environ. TLD U - Unknown I - Iodine Filter SDW-Surface Drink Water VG - Vegetation Column 7 MK - Milk SL - Soil WW - Well water GMSM or ISM OTH - Other SN - Snow BE ATTENTIVE TO PROTECTIVE ACTION LEVELS IN APPENDIX D, PAGE 1 OF I PAGE 33 OF 48 REVISION 27
CECC Emergency Environmental Radiological I
E D
IP Monitoring Procedures E P
-J APPENDIX G PAGE I OF I WTA FIELD CONTROL MONITORING RECORD E
E RMCC El SON SITE El WBN Recorded by Date Time Distribute Promptlyl l ::i nf 2.: *sf fgf992:f-af:$oR::S~t-v2; 9 g 2--;
....-.'.a.2...'....
1 ~
2 3
4 6
TRUCK SAMPLE DISTANCE DIRECTION FROM TIME RELATIVE PLUME POINT (Miles)
PLANT (Deqrees)
TAKEN POSITION (CIRCLE)
C E
U a
a a
m Z A FA RE 7
8 9
11 12 13 INST.
1 Meter WIC 11 Meter W/O INST.
NEAR NEAR TYPE mR/hr mRlhr TYPE CONTACT W/C mR/hr CONTACT W/O mR/hr I
Flow LPM 1431
.pCi/cc PART.
MCCifcc Tritium
-PC!/CC I
S SAMPLE TYF
& NUMBER BE ATTENTIVE TO PROTECTIV E ACTION LEVELS ON APPENDIX D, PAGE 1 of I ENSURE DATA SHARING WITH THE SITE TSC AND RMCC a
I' Column 6 C - Center E - Edge U - Unknown Column 7 GMSM or ISM Legend C olum n 20 HP - Heavy Particulate P - Particulate Filter T - Tritium ICE - Ice RW - Rain water TLD - Environ. TLD I - Iodine Filter SDW-Surface Drink Water VG - Vegetation MK - Milk SL - Soil l WWV-Well water OTH - Other l SN - Snow I
I I
PAGE 34 OF 48 REVISION 27
CECC l
Emergency Environmental Radiological I EPI P -9 l
l Monitoring Procedures I
Appendix H Page 1 of 4 MonitorinQ Team Vehicle Inventory Note: During quarterly checks, perform Operability Checks (OC) and check battery status with Iometer. Change out tape as needed.
1.0 The following items may need to be taken to the vehicle upon activation.
I g.0 W.. l0.
tm em a ks" 1
Bicron Analyst with Nal detector and cable
_C I
Bicron Analyst for GM use with cable OC 2
Ion Survey Meters (range to 10 R/hour) 0C 2
Geiger Mueller Survey Meters (14C or E-530)
_C 2
Bicron Surveyor 50s 0C 2
MSA ELF Pumps (effective 10101/2003)
_C 2
Scintrex 309A Tritium-in-Air Monitor (effective 10/01/2003) oc I
Package of Potassium Iodide Expiration:
I Ba ' check source ID#
i Tc-w check source ID #
2.0 The following are minimum quantities stored in the vehicle.
Environs Monitoring Vehicle Booklet 1
CECC EPIP-9 (controlled copy) 1_Rev.
4 Appendix B, CECC EPIP-9 (photocopies)
Rev.
4 Appendix C, CECC EPIP-9 (photocopies)
Rev.
4 Appendix D, CECC EPIP-9 (photocopies)
Rev.
4 Appendix E, CECC EPIP-9 (photocopies)
Rev.
50 Appendix F, CECC EPIP-9 (photocopies)
Rev.
4 Appendix H, CECC EPIP-9 (photocopies)
Rev.
I CECC EPIP-23 (controlled copy)
Rev.
5 Attachment G, CECC EPIP-23 (photocopies)
Rev.
I Site-specific EPIP-10 (controlled copy)
Rev.
I Georgia Public Service Commission Letter of Intent Date:
1 Laminated GPS conversion tables Miscellaneous Locations 1
GM detector in lead shield 0C 1
Fire extinguisher (check pressure within green band)
Note: Replace extinguisher 5-years from manufacture Mfg. Date:
date.
1 Primary Motorola radio 0C 1
Hand held spotlight
_C 1
First-aid kit I
GPS unit with 12 volt power cord and windshield bracket 0C PAGE 35 OF 48 REVISION 27
I CECO~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
ll CECC l
Emergency Environmental Radiological l
EPI P-9 I1 [
Monitoring Procedures I
Appendix H Page 2 of 4 Monitorinq Team Vehicle Inventory Work Desk I
.R a.....
.R. rn......
Battery level tester OC 2
Flashlights (check battery status)
OC 2
Spare batteries size 9 volt 4
Spare batteries, size D cell 2
Spare batteries, size AA 1
Scientific calculator CC 2
200 mrem Direct Reading Dosimeters re-zero 2
5 rem Direct Reading Dosimeters re-zero 2
TLDs (list expiration date)
Date:
I Scissors I
Allen wrench to fit lead shield top cap bolts 1
Tweezers 2
Pens or pencils 6
Planchets 20 Radioactive Material tags 40 Sample labels Cabinet 1 4
Full-face respirators w/cartridges l
8 Spare respirator cartridges (hepa)
I Spray cleaner for decontamination 15 Massilin cloths 15 Paper towels I
Water-less hand cleaner Cabinet 2 l
[ Air Sampling Portal vents and electrical outlets CC Cabinet 3 14 Marinelli beakers (500 mr L.10 Liquid Sample containers) 1 Sample Transport bag Cabinet 4 l
Cabinet 5 S
(space reserved for air samplers)
Cabinet 6 20 Large plastic radwaste bags 20 Medium plastic radwaste bags
.1, PAGE 36 OF 48 REVISION 27
i CECC l
Emergency Environmental Radiological l
E P I P 9
I l Monitoring Procedures I
I Appendix H Page 3 of 4 Monitorinq Team Vehicle Inventory Cabinet 7, Hi, i~~~~~~~~~~~~~~~~~~~~~.......................
r.k;kS*
5 Screw on air sampler heads I
Box 2 inch prefilters (minimum of 30 each) 30 Silver Zeolite air sampler cartridges (list manufacture Date:
date) NOTE: 10 year shelf life if packaging is unopened.
30 Molecular sieves 2
Lengths of sampling tubing and male leur connectors 30 Petri dishes 30 Small zip-lock bags 30 Large zip-lock bags
. Roll of plastic wrap (Saran type) 1 Box gloves - sample handling (min. 20 pair)
I Box smears (minimum of approx. 200)
X X
X 1
Roll 2 inch duct tape 1
Roll Radiation Waming Symbol tape 1
Roll electrical tape I
Dosimeter charger OC Cabinet 8 l Electrical switch panel a
C Onboard generator (record run time displayed)
OC hrs.
Cabinet 9 1
Logbook I
DOT Emergency Response Guidebook Year:
1 TN AL and GA State road maps 1
Sample Point Description book for BFN, SON, WBN 6
Area posting signs (Radiation and Contamination Area insert) 6 Radioactive placards 1
Trash can 2
Rain Suits 2
Insulated coveralls
.:...z.
z 2
BFN 2-, 10-, 50- mile sampling point maps 2
SQN 2-, 10-, 50- mile sampling point maps 2
WBN 2-, 10-, 50- mile sampling point maps Cabinet 10 I
Set Jumper cables 1 Funnel i
1 Siphon pump/hose 1
Set of wrenches 1
Set of screwdrivers 1
Pair of Pliers X
_X I
Hammer 1
Box of 3 reflective triangles PAGE 37 OF 48 REVISION 27
CECC I
Emergency Environmental Radiological EPIP91 l
l Monitoring Procedures I
I Appendix H Page 4of4 Monitorinq Team Vehicle Inventory Cabinet 1 1 24 Pair booties 24 Pair cotton inserts 12 Pair Anti-C gloves 12 Pair rubber shoe covers 12 Pair coveralls (disposable) 12 Dressout caps 12 Hoods 1
Roll dress-out tape Cabinet 12 I...,.,,;,.,.,,,,,,,,,,,
em................................................
.R em ar.....k................._._
2 Air samplers for Grab Samples (H810)
OC 2
Air samplers for Continuous Run (11810)
OC Outside Compartments 1 ea.
110 volt extension cord (25-, 50-, 100 ft) 1 External vehicle power supply cord (shore power) 8 Wooden stakes I
Soil sampling tool I
Shovel 400 Feet of radiological warning bamer rope/ribbon 1
Box plastic sheeting 1
Putty knife (4 inch)
I Grass cutters 8
Traffic cones I
Can of spray paint for marking of areas (i.e., roadway)
I Pair of work gloves I
Fire extinguisher (check pressure within green band)
Note: Replace extinguisher 5-years from manufacture Mfg. Date:
date.
1 Ground Fault Interrupter OC 1
Honda gas generator OC Vehicle Location:
Vehicle tag #:
Forward for signatures below. EP Manager to receive by end of calendar quarter.
Purpose of Inspection:
0 Monthly 0
Quarterly 0
Post training/drillresponse Additional Comments:
.....~~~........
Inpecb~i5~lw gte!
by i;
.re
!! At r c.............
- I
. l.
......................~~~~~~~~~~~~~~~~~~~
.I.
d, PAGE 38 OF 48 REVISION 27
CECC Emergency Environmental Radiological I
D I P I
I Monitoring Procedures l
'r Ir-I I
Appendix I Page 1 of 4 WARL Screening Vehicle Inventory Note: During quarterly checks, perform Operability Checks (OC) and check I
battery status with meter. Change out tape as needed.
I 1.0 Items stored in WARL.
11-1-11 I I'i...............
....... 'l:.'
- 'ii;I'Sft
- ..E..;
1 Geiger Mueller Survey Meter with pancake probe oC
- 1.
Geiger Mueller Survey Meter 0C I
Package of Potassium Iodide Expiration:
2 Calibration sources for Germanium detectors 1
Radioanalytical Laboratory Procedures Manual I
Sample Transport case 2.0 The following are minimum quantities stored in the vehicle.
Miscellaneous Locations 2
Germanium detector systems 1
Liquid nitrogen dewar 2
Fire extinguisher (check pressure within green band)
Note: Replace extinguisher 5-years from Mfg. Date:
manufacture date 1
Uninterruptible Power Supply 1
Gamma analysis system Cabinet A 1
Set of wrenches 1
Set of screwdrivers I
Pair of pliers 1
Set of alien wrenches 1 _
Pair insulated gloves (nitrogen handling) 2 Pair leather or canvas work gloves 2
Pair cloth glove inserts Cabinet B I
Tape dispenser I
Roll of Radioactive Materiar tape 1
Roll 3/4 inch fiber tape 1
Roll 2 inch Scotch tape 1
Roll 2 inch masking tape PAGE 39 OF 48 REVISION 27
- CECC T
Emergency Environmental Radiological EPIP-9 l
Monitoring Procedures I
I Appendix I Page 2 of 4 WARL Screening Vehicle Inventory Cabinet B (continued) l Roll 3/4 inch masking tape 3
Rolls electrical tape 1
Calculator OC I
Box 2 inch filter papers 10 Tags (with string) 25
'Radioactive Material' tags I
Pack cotton swabs 10 Pair rubber or plastic gloves 1
Direct Reading Dosimeter charger (AC or battery OC powered)
Cabinet C 10 Shallow planchets 5
Deep planchets 2
Boxes smears 50 Small Ziplock bags 20 Large Ziplock bags 1
Roll clear plastic wrapping (Saran type) 5 Yellow 'Radioactive Material" plastic bags Cabinet D 10 Marinelli beakers (500 ml) 20 Petrl dishes 1
500 ml graduated cylinder Cabinet E 4
D-cell batteries 2
9-volt batteries 4
AA batteries 1
Box of replacement fuses for equipment I
Spotlight C
I Flashlight with batteries 0C I
Balance (3000 gram capacity) with check wts.
Cabinet F 1 2 1 Rainsuits Cabinet G l
6 I Pairs disposable coveralls PAGE 40 OF 48 REVISION 27
t CECC Emergency Environmental Radiological I
EP I P-9 Monitoring Procedures I
Appendix I Page 3 of 4 WARL Screening Vehicle Inventorv Cabinet H I ~~iW1 1ta~m I
~t'~~ t Rp.............
2 Orange safety vest 4
Pairs rubber shoe covers Cabinet I 1
Radiological Health Handbook 1
DOT Emergency Response Guidebook Year 1
Sample Point Description Booklet (each site)
Environs Monitoring Vehicle Booklet 1
CECC EPIP-9 (controlled copy)
Rev.
2 EPIP-9, Screening Vehicle Inventory (photocopies) l_
l_Rev.
2 EPIP-9, Dose Logs (photocopies)
Rev.
2 EPIP-9, Emergency Authorizations (photocopies)
Rev.
20 Isotopic Analysis forms 1
Georgia Public Service Commission Letter of Intent Date:
Cabinet J l
I Miscellaneous spare cables for gamma systems Cabinet K 1
Can insect repellent I
Can de-icing fluid 1
Can wasp insecticide I
First-Aid kit 1
Can decontamination spray or foam E
Drawer I Sa ~Pin ax, la~tetrevisIo EPIPlseton43 2
BFN 2-, 10-, 50- mile sampling point maps l_
l 2
SQN 2-, 10-, 50- mile sampling point maps 2
WBN 2-, 10-, 50- mile sampling point maps 1
State Highway map for Georgia, Tennessee and Alabama 2
Germanium detector logbooks 1
Germanium detector control charts folder 1
Germanium detector efficiency table folder PAGE 41 OF 48 REVISION 27
0 CECC I
Emergency Environmental Radiological E P I P-9 I g Monitoring Procedures l
I Appendix I Page 4of4 WARL Screening Vehicle Inventory Drawer 2 If:;
... g.
.temii
"..'.ia t"-
-i.......... tgi-.
Remarks 2
TLDs (list expiration date)
Date 2
200 mrem Direct Reading Dosimeters I
Control TLD (list expiration date)
Date 2
Lab markers 2
Pens 4
Mechanical pencils 1
Steno pad I
Set of jeweler's screwdrivers Vehicle Location:
Vehicle tag #:
Purpose of Inspection: El QuarterlyOj Post Training 0l Post Drill I Response Additional Comments:
Place completed copy of quarterly inventory in front of vehicle booklet.
- Forward for signatures below.
l pecte, M.....
D.
I PAGE 42 OF 48 REVISION 27
CECC Emergency Environmental Radiological I
EPIP 91 I
Monitoring Procedures l
P Appendix J Page 1 of 1 Field Coordinator Kit Inventory Emergency Preparedness Implementing Procedures I
_~~~~~~~~~~~~~~~~~~~~~.
......;lUsdl U
I CECC EPIP-7 (controlled copy)
Rev.
1 CECC EPIP-9 (controlled copy)
Rev.
1 CECC EPIP-15 (controlled copy)
Rev.
1 CECC EPIP-23 (controlled copy)
Rev.
1 REND (controlled copy)
Rev.
Mliscellaneous Items s M
E i::....Item.. t R..a.ks I
Radiological Health Handbook 12 TLDs (list expiration date)
Date I
Scientific calculator 50 Copies of Environs Monitoring forms (TV 7918A)
Date 10 Copies of Clerical Logsheets Logbook 1
Package of Potassium Iodide (list expiration)
Date 1
Flashlight & batteries 1
DOT Emergency Response Guidebook Year 1
Tennessee Highway road map I
Alabama Highway road map 1
Georgia Highway road map 1
Sample Point Description booklet for BFN I
Sample Point Description booklet for SQN 1
Sample Point Description booklet for WBN
$a----e-
- -t i -ii ites-t i
H i rEPIN ection4,33/4w.:..:...:.:...:....::....
2 BFN 2-, 1 0-, 50- mile sampling point maps S2 QN 2-, 10-, 50- mile sampling point maps 2
WBN 2-, 10-, 50- mile sampling point maps s Miscellaneous office supplies may also be contained in the kit for convenience purposes.
Kit Location:
El CECC E BFN Purpose of Inspection: El Quarterly[
Post Training E Post Drill I Response Additional Comments:
- Inspectd b:
Dte Manager. Revie :
l-t...e..............el l ReV~~~~~~~~...
- 11.
a11 PAGE 43 OF 48 REVISION 27
{ CECC Emergency Environmental Radiological I
E P i P-9D Monitoring Procedures Appendix K Page 1 of 1 Courier Kit Inventory 0, ; xfig; -;-
0t l Aft t ri i *
^
R e v......
1 CECC EPIP-9 (controlled copy)
Rev.
1 200 mrem Direct Reading Dosimeter I
TLD (list expiration date)
Date I
Dosimeter charger with battery I
Flashlight & batteries I
First-aid kit 1
Scientific calculator I
Pair Disposable coveralls 4
Pair booties 10 Pair sample handling gloves and cotton liners 1
Pair work gloves I
Package of Potassium Iodide (list expiration)
Date 12 Radioactive Material tags 12 Sample labels 12 Yellow "radioactive material bags I
Roll of duct tape I
Roll of electrical tape 1
Rain coat 1
Logbook_
3 Pens 1
Sample transport container I
DOT Emergency Response Guidebook Year I
Highway road map including TN, AL and GA.
I Sample Point Description booklet for BFN I
Sample Point Description booklet for SQN 1
Sample Point Description booklet for WBN
.... >....,.,., i,,..,.,......
i 1
BFN 2-, 10-, 50- mile sampling point maps 1
SQN 2-, 10-, 50- mile sampling point maps 1
7 WBN 2-, 10-, 50- mile sampling point maps Miscellaneous office supplies may also be contained in the kit for convenience purposes.
Kit Location:
El CECC El BFN Purpose of Inspection:
El Quarterlyn Post Training El Post Drill / Response Additional Comments:
.s gDate:-
PAGE 44 OF 48 REVISION 27
I CECC Emergency Environmental Radiological I
E=P D
D 9 Il l
Monitoring Procedures l
Appendix L Page 1 of 4 Global Positionina Satellite Unit Operation Keep unit mounted on windshield bracket with power plug installed.
During night time, depress the light symbol for on, low and high screen illumination.
Remember to turn the unit off by the PWR button when leaving the vehicle.
DO NOT ATTEMPT TO ALTER MENU. Depressing the QUIT button is acceptable to "step back" or to start over on the sequence below.
- 1. Depress the red PWR button.
- 2. Depress the ENTER button.
- 3. Depress the NAV button 2 TIMES to bring up the screen with DST and BRG displayed.
- 4. Depress the GOTO button.
- 5. Use the 4 arrow button and depress the down arrow to highlight USER, then depress the ENTER button.
- 6. Use the 4 arrow round button to highlight the desired plant.
- 7. Once the desired plant is highlighted, depress ENTER.
- 8. The unit should now display the Bearing in degrees (BRG) and Distance (DST) in miles from the selected nuclear site.
- 9. No further actions are needed. Simply drive and view the screen for continuous updates of your bearing and distance from the selected nuclear site.
- 10. To turn the unit off when leaving the vehicle, depress the PWR button to turn the unit off.
Remove bracket from windshield, store GPS screen out of direct sunlight.
Note:
l A_
Bearing (BRG) indicates the compass direction back TO the nuclear site. The Bearing (BRG) value is 180 degrees off from our method of communication to dose assessors and decision makers. Therefore, when reporting data locations, field team members should reportthe DISTANCEand DIRECTION. Field teams will determine the adjusted value using the conversion tables such as pages 2 through 4 of this appendix. An example radio report for the above illustration would be a "Distance of 17.7 miles, Direction 224 degrees".
PAGE 45 OF 48 REVISION 27
I I I
Appendix L Page 2of4 Global Positioning Satellite Unit Operation BRG FROM displayed adjusted 1
181 2
182 3
183 4
184 5
185 6
186 7
187 8
188 9
189 10 190 11 191 12 192 13 193 14 194 15 195 16 196 17 197 18 198 19 199 20 200 21 201 22 202 23 203 24 204 25 205 26 206 27 207 28 208 29 209 30 210 BRG displayed 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FROM adjusted 211 212 213 214 215 216 217 218 219 220 221 222 223 224 225 226 227 228 229 230 231 232
[233 234 235 236 237 238 239 240 BRG FROM displayed adjusted 61 241 62 242 63 243 64 244 65 245 66 246 67 247 68 248 69 249 70 250 71 251 72 252 73 253 74 254 75 255 76 256 77 257 78 258 79 250 80 260 81 261 82 262 83 263 84 264 85 265 86 266 87 267 88 268 89 269 90 270 BRG FROM displayed adjusted 91 271 92 272 93 273 94 274 95 275 96 276 97 277 98 278 99 279 100 280 101 281 102 282 103 283 104 284 105 285 106 286 107 287 108 288 109 289 110 290 111 291 112 292 113 293 114 115 116 117 118 119 120 294 295 296 297 298 299 300 PAGE 46 OF 48 REVISION 27
. i CECC Emergency Environmental Radiological I
DIDO I
Monitoring Procedures L..I I I-9 I
Appendix L Page 3 of 4 Global Positioninq Satellite Unit Operation BRG FROM displayed adjusted 121 301 122 302 123 303 124 304 125 305 126 306 127 307 128 308 129 309 130 310 131 311 132 312 133 313 134 314 135 315 136 316 137 317 138 318 139 319 140 320 141 321 142 322 143 323 144 324 145 325 146 326 147 327 148 328 149 329 150 330 BRG displayed 151 152 153 154 155 156 157 158 159 160 161 162 163 164 165 166 167 168 169 170 171 172 173 174 175 176 177 178 179 180 FROM adjusted 331 332 333 334 335 336 337 338 339 340 341 342 343 344 345 346 347 348 349 350 351 352 353 354 355 356 357 358 359 0
BRG FROM displayed adjusted 181 1
182 2
183 3
184 4
185 5
186 6
187 7
188 8
189 9
190 10 191 11 192 12 193 13 194 14 195 15 196 16 197 17 198 18 199 19 200 20 201 21 202 22 203 23 204 24 205 25 206 26 207 27 208 28 209 29 210 30 BRG FROM displayed adjusted 211 31 212 32 213 33 214 34 215 35 216 36 217 -37 218 38 219 39 220 40 221 41 222 42 223 43 224 44 225 45 226 46 227 47 228 48 229 49 -
230 50 231 51 232 233 234 235 236 237 238 239 240 52 53 54 55 56 57 58 59 60 PAGE 47 OF 48 REVISION 27
CECC Emergency Environmental Radiological
{
DO 9 I I Monitoring Procedures l
I Appendix L Page 4 of 4 Global Positioning Satellite Unit Operation BRG FROM displayed adjusted 241 61 242 62 243 63 244 64 245 65 246 66 247 67 248 68 249 69 250 70 251 71 252 72 253 73 254 74 255 75 256 76 257 77 258 78 259 79 260 80 261 81 262 82 263 83 264 84 265 85 266 86 267 87 268 88 269 89 270 90 BRG displayed 271 272 273 274 275 276 277 278 279 280 281; 282 283 284 285 286 287 288 289 290 291 292 293 294 295 296 297 298 299 300 FROM adjusted 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 116 117 118 119 120 BRG FROM displayed adjusted 301 121 302 122 303 123 304 124 305 125 306 126 307 127 308 128 309 129 310 130 311 131 312 132 313 133 314 134 315 135 316 136 317 137 318 138 319 139 320 140 321 141 322 142 323 143 324 144 325 145 326 146 327 147 328 148 329 149 330 150 BRG FROM displayed adjusted 331 151 332 152 333 153 334 154 335 155 336 156 337 157 338 158 339 159 340 160 341 161 342 162 343 163 344 164 345 165 346 166 347 167 348 168 349 169 350 170 351 171 352 172 353 173 354 174 355 175 356 176 357 177 358 178 359 179 0
180 PAGE 48 OF 48 REVISION 27