ML14311A612
| ML14311A612 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/03/2005 |
| From: | Grissette D Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Information Services |
| Shared Package | |
| ML14311A546 | List: |
| References | |
| EP-04-2154, FOIA/PA-2014-0472 | |
| Download: ML14311A612 (112) | |
Text
TREAT AkS INFSATIVE II
œN~oRA~rlo
Don E. Grissette Southern Nuclear Vice President Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.6474 Fax 205.992.0341 A
SOUTHERNNA January 3, 2005 COMPANY Energy to Serve Your Worid'>
Docket Nos.: 50-424 EP-04-2154 50-425 US Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Vogtle Electric Generating Plant Emergency Plan Revision 39 Ladies and Gentlemen:
In accordance with I OCFR50.54(q) and I OCFR50.4(b)(5), Southern Nuclear Operating Company hereby submits Revision 39 to the Vogtle Electric Generating Plant (VEGP)
Units I and 2 Emergency Plan (the Plan).
Revision 39 incorporates a transfer of responsibility to monitor and decontaminate non-involved VEGP personnel from VEGP to Burke County EMA, a change to the present designated location (TSC) for the Backup OSC and an update to Appendix 2, letters of agreement. Additionally, minor editorial comments and title changes were incorporated.
Justifications for the changes are located within Enclosure 1. Enclosure 2 provides the insertion instructions, and Enclosure 3 identifies the revised pages. These plan changes do not decrease the effectiveness of the Plan.
If you have any questions regarding this submittal, please contact this office or Mr. C. E.
Boone, Emergency Planning Coordinator, at (205) 992-6635.
Sincerely, Don E. Grissette DEG/CEB/daj
Enclosures:
- 1. Justification For Revision 39 to the VEGP Emergency Plan
- 2. Insertion Instructions
- 3.
Revised Plan Pages
U. S. Nuclear Regulatory Commission EP-04-2 154 Page 2 cc:
Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. W. F. Kitchens, General Manager - Plant Vogtle Mr. L. E. Mayo, Emergency Planning Coordinator - Plant Vogtle Mr. K. Holmes, Performance Analysis Mr. C. E. Boone, Emergency Planning Coordinator R Type: CVC7000 U. S. Nuclear Regulatorv Commission Dr. W. D. Travers, Regional Administrator Mr. C. Gratton, NRR Project Manager-Vogtle Mr. G. J. McCoy, Senior Resident Inspector - Vogtle
ENCLOSURE 1 Justification For Revision 39 To The VEGP Emergency Plan
JUSTIFICATION FOR REVISION 39 TO TIHE VEGP EMERGENCY PLAN Sheet I of 3 LDCR 2004023, Attachment I
- 1. Preface Page xix Paragraph I - Delete "and relocation centers are also." Add word "are."
Justification: The responsibility to monitor and decontaminate VEGP personnel, once dismissed from the site, has been accepted by Burke County EMA. Burke County has trained personnel to staff reception centers and operate the portal monitors which are designed for persons and vehicles. Therefore the reference to onsite relocation centers has been removed.
- 2. Table of Content Page ix List Of Figures - Delete figures J-I and J-2 from list.
Justification: Same as change I above.
- 3. Page B-4 Section B.2.1.1, 6th bullet - change reference from "early dismissal of nonessential" to "site dismissal of non-involved."
Justification: Editorial change to maintain consistency throughout emergency plan. Function has not changed.
- 4. Page B-4 Section B.2. 1.1, 7'h bullet - change reference from "relocation" to "reception." Delete "prior to dismissal."
Justification: Same as change I above.
- 5. Page H-5 Section H. 1.2, 3rd paragraph - Change "TSC" reference to "Outage Control Center (OCC) and Clearance and Tagging (C&T)" as the location of the back-up OSC.
Justification:
The TSC is limited in the floor space, communications, printed resources, electronic resources, and seating if the OSC relocates to the TSC. The OCC and C&T are located in the control building one level above the control room. The floor space, communications, printed resources, electronic resources, and seating are available.
- 6. Page H-18 Section H.6, 1" paragraph - Delete wording ", and relocation centers."
Justification: Same as change 1 above.
JUSTIFICATION FOR REVISION 39 TO T1HE VEGP EMERGENCY PLAN Sheet 2 of 3 LDCR 2004023, Attachment I
- 7. Pages J-2, J-3 and J-4 Section J.1.4 - Entire section rewritten to accommodate the change of responsibility of the offsite reception center.
Burke County EMA will receive VEGP non-involved personnel, monitor for contamination, and decontaminate as necessary. This will be accomplished in accordance with their approved plan and procedures.
Justification:
Same as change I above.
- 8. Table J-5, item I Deleted references to "Burke County Middle School and Blakeney Elementary School" as additional reception centers for Burke County Georgia.
Justification: State of Georgia and Burke County eliminated these centers from their respective emergency plans.
- 9. Figures J-l and J-2 Deleted Figures J-1 and J-2.
Justification: Same as change I above.
- 10. Page K-3 Section K.3, 1 't paragraph - Delete word "offsite" as it pertains to decontamination emergency kit.
Justification: Editorial change. Decontamination kits are still available at the EOF and Health Physics Control Point.
The offsite reference is no longer applicable.
- 11. Page K-3 Section K.3, 3rd paragraph - Deleted all references to the relocation centers.
Justification: Same as change I above.
- 12. Page K-3 Section K.3, 3rd paragraph - Change "Burke County Hospital" to "Burke Medical Center."
Justification: Editorial change to correct hospital name.
- 13. Table 0- I Delete reference to "site relocation centers" in Sheet 3 of 3, Radiological Emergency Team In-Plant course.
Justification: Editorial change to correct reference to "relocation centers."
JUSTIFICATION FOR REVISION 39 TO TIlE VEGP EMERGENCY PLAN Sheet 3 of 3 LDCR 2004023, Attachment I
- 14. Appendix I GLOSSARY - Correct the following:
- EBS changed to EAS - Emergency Alerting System
- EPD changed to EMD - Emergency Management Division of South Carolina Justification: Editorial changes.
- 15. Appendix 2 Change "Table Of Contents" to "List of Letters Of Agreement On File" Justification: The information contained in the letters of agreement is not needed to implement any action. Other sections of the emergency plan (i.e., sections A and L) contain the specific actions that these authorities have agreed to perform if called upon by VEGP. These letters will-remain on file and will continue to be confirmed viable on an annual basis.
- 16. Appendix 2 Delete letters of agreement with Frank L. Carter, M.D. and Framatome Technologies.
Justification: Dr. Carter has joined practice w ith Medical Specialist which is listed as current. Framatome Technologies no longer provides post accident sampling services.
- 17. Appendix 4 Table 4-4, OSC Emergency Equipment (Typical), Item 30 -
Delete references to tools.
Justification: OSC tools are stored in the tool room located on the first floor of the maintenance building. There are also tools stored in the hot machine shop within the Auxiliary Building.
- 18. Appendix 4 Table 4-6, Offsite Decontamination Emergency Equipment Kit (Typical) - Delete "Offsite" in title of table and delete item 18, bags.
Justification: Title change for consistency with item 9 above and deleted redundant "bag" reference which is listed in item 4 of table 4-6.
ENCLOSURE 2 Insertion Instructions
VEGP UNIT 1 AND UNIT 2 EMERGENCY PLAN REVISION 39 11/04 INSERTION INSTRUCTIONS Is I
I Section Instructions Remove Justification for Revision 37 to Replace with the VEGP Emergency Plan, Enclosure #1 Justification for (Sheets 1 and 2).
Revision 39 (Sheets 1 through 3).
Remove Table of Contents.
Replace entire Table of Contents.
Remove Preface.
Replace entire section.
Remove Section B.
Replace entire section.
Remove Section H.
Replace entire section.
Remove Section J.
Replace entire section.
Remove Section K.
Replace entire section.
Remove Section 0.
Replace entire section.
-X Appndi Rltp Remove Appendix 1.
Replace entire appendix.
Remove Appendix 2.
Replace entire appendix.
Remove Appendix 4.
Replace entire appendix.
Acknowledgment Receipt Sign and return.
ENCLOSURE 3 Revised Plan Pages
TABLE OF CONTENTS Section Title Page PREFACE xix A
ASSIGNMENT OF RESPONSIBILITIES A-1 A.1 Vogtle Electric Generating Plant A-1 A.2 State of Georgia A-2 A.3 Burke County, Georgia A-8 A.4 State of South Carolina A-9 A.5 Aiken, Barnwell, and Allendale Counties, South Carolina A-14 A.6 Department of Energy -
Savannah River Site A-16 A.7 Medical Support A-16 A.8 Private Sector Organizations A-16 A.9 Federal Government Support A-17 A.10 Concept of Operations A-17 B
ONSITE EMERGENCY ORGANIZATION B-1 B.1 Normal Plant Organization B-1 B.2 Emergency Organization B-1 C
EMERGENCY RESPONSE SUPPORT AND RESOURCES C-1 C.1 State and Local Governmental Support C-1 C.2 Federal Governmental Support C-1 C.3 VEGP Support C-3 C.4 Other Support C-4 D
EMERGENCY CLASSIFICATION SYSTEM D-1 D.1 Summary of Emergency Classification Logic D-1 D.2 Emergency Class Description and Response D-1 D.3 Classification Process D-5 i
REV 21 10/94
TABLE OF CONTENTS (Continued)
Section Title Page E
NOTIFICATION METHODS AND PROCEDURES E-1 E.1 Notification of VEGP Personnel E-1 E.2 Notification of State and Local Response Personnel E-2 E.3 Notification of Federal Agencies E-3 E.4 Notification of the Public E-3 E.5 Followup Emergency Messages E-4 E.6 Verification of Notification Messages E-4 F
EMERGENCY COMMUNICATIONS F-1 F.1 Communications With the State of Georgia and Burke County F-1 F.2 Communications With the State of South Carolina and Aiken, Barnwell, and Allendale Counties F-2 F.3 Communications With the Savannah River Site F-2 F.4 Communications With Nuclear Regulatory Commission and Other Federal Agencies F-3 F.5 Communications Among VEGP Emergency Response Facilities F-3 F.6 Medical Support Facility Communications F-6 F.7 Alerting Emergency Response Personnel F-7 F.8 Communications System Tests F-7 F.9 VEGP Radiological Monitoring Teams F-7 G
PUBLIC EDUCATION AND INFORMATION G-1 G.1 Information for Transients G-2 ii REV 21 10/94
TABLE OF CONTENTS (Continued)
Section Title G.2 Emergency News Center Operations G.3 Offsite Agency Coordination G.4 Rumor Control G.5 Media Education H
EMERGENCY FACILITIES AND EQUIPMENT H.1 Emergency Facilities H.2 Corporate and News Center Facilities H.3 Activation and Staffing of Emergency Facilities H.4 Plant Monitoring and Data Handling Systems H.5 Out-of-Plant Monitoring H.6 Emergency Kits I
ACCIDENT ASSESSMENT I.1 Plant Parameters I.2 Radiological Monitors 1.3 Determination of Release Rate I.4 Dose Assessment System I.5 Field Monitoring I.6 Environmental Samples I.7 Use of Field Monitoring Data J
PROTECTIVE RESPONSE J.1 Protective Response for Onsite Personnel J.2 Protective Response for the Public K
RADIOLOGICAL EXPOSURE CONTROL K.1 Emergency Exposure Guidelines Page G-3 G-4 G-4 G-4 H-1 H-1 H-8 H-8 H-9 H-17 H-18 I-1 I-i I-i I-3 I-3 I-5 I-8 I-9 J-1 J-1 J-4 K-1 K-1 iii REV 27 02/98
TABLE OF CONTENTS (Continued)
Section Title K.2 Onsite Radiation Protection Program K.3 Decontamination K.4 Onsite Radiological Contamination Control L
MEDICAL AND PUBLIC HEALTH SUPPORT L.1 Onsite Capability L.2 Medical Transportation L.3 Offsite Support Services L.4 Training of Medical Support Personnel M
RECOVERY AND REENTRY PLANNING AND POST-ACCIDENT OPERATIONS M.1 Commencement of Recovery Phase M.2 Recovery Organization M.3 Reentry Planning M.4 Exposure Monitoring N
EXERCISES AND DRILLS N.1 Exercises N.2 Drills N.3 Scenarios N.4 Evaluations and Corrective Actions 0
RADIOLOGICAL EMERGENCY RESPONSE TRAINING 0.1 Training 0.2 Qualification 0.3 Summary P
RESPONSIBILITY FOR THE PLANNING EFFORT Page K-2 K-3 K-4 L-1 L-1 L-1 L-2 L-4 M-1 M-1 M-2 M-4 M-4 N-1 N-1 N-1 N-4 N-5 0-1 0-1 0-2 0-2 P-1 iv REV 21 10/94
TABLE OF CONTENTS (Continued)
Appendix Title 1
GLOSSARY 2
LETTERS OF AGREEMENT 3
MEANS FOR PROVIDING PROMPT ALERTING AND NOTIFICATION OF THE PUBLIC 4
EMERGENCY EQUIPMENT LIST 5
MEMORANDUM OF AGREEMENT WITH DEPARTMENT OF ENERGY -
SAVANNAH RIVER 6
EVACUATION TIME ESTIMATES FOR THE VOGTLE ELECTRIC GENERATING PLANT PLUME EXPOSURE PATHWAY EMERGENCY PLANNING ZONE 7
CORPORATE EMERGENCY PLAN FOR VOGTLE ELECTRIC GENERATING PLANT 8
VOGTLE ELECTRIC GENERATING PLANT EMERGENCY COMMUNICATIONS PLAN 9
INDEX OF VEGP ADMINISTRATIVE, HEALTH PHYSICS AND EMERGENCY PLAN IMPLEMENTING PROCEDURES CROSS-REFERENCED TO SECTIONS OF THE VEGP EMERGENCY PLAN 10 FSAR-POSTULATED TRANSIENTS 11 LETTER FROM THE STATE OF GEORGIA I
I v
REV 27 02/98
LIST OF TABLES Table Title A-1 Responsible Individuals of Primary Response Organizations B-1 Minimum Staffing for Power Operation B-2 Emergency Organization Assignments C-1 Airport Characteristics C-2 State and County Emergency Operation Centers (EOC)
D-1 Hazards and Other Conditions Affecting Plant Safety for All Modes D-2 System Malfunction Emergency Action Levels D-3 Abnormal Rad Levels/Radiological Effluent D-4 Fission Product Barriers Status E-1 Initial Notification System (Normal Working Hours)
E-2 Initial Notification System (Backshift Hours)
F-1 Emergency Response Communications Summary H-1 Integrated Plant Computer Inputs l
vi REV 27 02/98
LIST OF TABLES (Continued)
Table Title J-1 Use of Protective Equipment and Supplies J-2 Recommended Protective Actions To Reduce Total Effective Dose Equivalent and Thyroid Committed Dose Equivalent From Exposure to Airborne Radioactivity J-3 Sheltering Guidance Reduction in External Gamma Dose From Passing Cloud J-4 Evacuation Time Estimate Summary J-5 Reception Centers/Shelters for Counties Within the Plume Exposure Pathway EPZ of VEGP K-1 Emergency Exposure Limits Per Person Per Response 0-1 Training Course Descriptions 0-2 Training Requirements for VEGP ERO Personnel vii REV 27 02/98
LIST OF FIGURES Figure Title i
General Vicinity Map ii Vogtle Electric Generating Plant Site Plan iii Vogtle Electric Generating Plant 10-Mile EPZ (Plume Exposure Pathway) iv Vogtle Electric Generating Plant & Savannah River Site 50-Mile EPZ (Ingestion Pathway) v 1987 Permanent Population Within the Vogtle Electric Generating Plant Plume Exposure EP2 vi Transient and Special Facility Population (Employees, Visitors to Recreational Areas and Schools) Within the Vogtle Electric Generating Plant Plume Exposure EP2 A-1 Formal Interfaces Among Emergency Organizations A-2 State of Georgia Operating in a Declared Radiological Emergency A-3 Operational Relationships Among Burke County Response Organizations A-4 State of South Carolina Operating in a Declared Radiological Emergency A-S Aiken County, S.C., Emergency Response Organization A-6 Barnwell County, S.C., Emergency Respon'se Organization A-7 Allendale County, S.C., Emergency Response Organization B-1 VEGP Organization Chart B-2 Response Organization for Alert B-3 Site Area or General Emergency Response Organization B-4 Corporate Emergency Organization viii REV 27 02/98
LIST OF FIGURES (Continued)
FiQure Title E-1 Example of Initial Emergency Message For State and Local Response Agencies E-2 Example of NRC Operations Center Event Notification Worksheet H-1 TSC Layout Plan H-2 OSC Layout Plan H-3 EOF Layout Plan H-4 Backup EOF Floor Plan M-1 Recovery Organization P-1 Emergency Preparedness Organizations ix REV 39 11/04
VEGP EMERGENCY PLAN LIST OF EFFECTIVE PAGES WITH REVISIONS PAGE REV.
Table of Contents (i) 21 ii 21 iii 27 iv 21 v
27 vi 27 vii 27 viii 27 ix -xv 39 xvi -
xvii 37 xviii 35 Preface xix 39 xx 12 Figure i 5
Figure ii 27 Figure iii 14 Figure iv 23 Figure v NONE Figure vi 12 A-1 19 A-2 30 A-3 23 A-4 30 A-5 30 A-6 30 A-7 23 A-8 18 A-9 35 A-10 35 A-11 35 A-12 35 A-13 31 A-14 23 A-15 35 A-16 30 A-17 24 A-18 23 A-19 35 A-20 35 A-21 24 Table A-1 (1 of 2) 35 Table A-1 (2 of 2) 14 Figure A-1 35 Figure A-2 22 Figure A-3 2
Figure A-4 35 Figure A-5 35 Figure A-6 35 Figure A-7 35 x
REV 39 11/04
VEGP EMERGENCY PLAN LIST OF EFFECTIVE PAGES WITH REVISIONS PAGE REV.
B-1 B-2 B-3 B-4 B-5 B-6 B-7 B-8 B-9 B-10 Table B-1 Table B-1 Table B-2 Table B-2 Figure B-1 Figure B-2 Figure B-3 Figure B-4 C-1 C-2 C-3 C-4 C-5 Table C-1 Table C-1 Table C-2 D-1 D-2 D-3 D-4 D-5 D-6 Table D-1 Table D-1 Table D-1 Table D-1 Table D-2 Table D-2 Table D-2 Table D-2 Table D-2 Table D-3 Table D-3 Table D-3 Table D-3 Table D-4 Table D-4 Table D-4 Table D-4 (1 of 2)
(2 of 2)
(1 of 2)
(2 of 2)
(1 of 2)
(2 of 2) 31 35 24 39 37 37 31 37 35 19 30 26 37 35 35 37 37 37 36 19 19 36 36 2
28 31 21 27 33 33 33 33 23 15 15 15 15 15 25 25 15 15 15 21 15 15 15 15 15 (1
(2 (3
(4 (I
(2 (3
(4 (5
(1 (2
(3 (4
(1 (2
(3 (4
of 4) of 4) of 4) of 4) of 5) of 5) of 5) of 5) of 5) of 4) of 4) of 4) of 4) of 4) of 4) of 4) of 4) xi REV 39 11/04
VEGP EMERGENCY PLAN LIST OF EFFECTIVE PAGES WITH REVISIONS PAGE REV.
E-1 E-2 E-3 E-4 Table E-1 Table E-1 Table E-2 Table E-2 Figure E-1 Figure E-2 Figure E-2 Figure E-2 F-1 F-2 F-3 F-4 F-5 F-6 F-7 Table F-1 G-1 G-2 G-3 G-4 H-1 H-2 H-3 H-4 H-5 H-6 H-7 H-8 H-9 H-10 H-11 H-12 H-13 H-14 H-15 H-16 H-17 H-18 Table H-1 (1
(2 (I
(2 of 2) of 2) of 2) of 2)
(1 (1
(2 of 3) of 2) of 2)
DELETED 35 35 25 19 35 25 33 33 35 21 35 35 31 31 30 28 31 31 31 31 24 31 31 24 21 23 30 30 39 22 37 33 19 35 35 28 21 29 22 22 34 39 34 Figure H-1 Figure H-2 Figure H-3 Figure H-4 34 19 37 37 xii REV 39 11/04
VEGP EMERGENCY PLAN LIST OF EFFECTIVE PAGES WITH REVISIONS PAGE REV.
I-1 I-2 I-3 I-4 I-5 I-6 I-7 I-8 I-9 I-10 J-1 J-2 J-3 J-4 J-5 J-6 Table J-1 Table J-2 Table J-3 Table J-4 Table J-5 Table J-5 K-1 K-2 K-3 K-4 Table K-1 Table K-2(I L-1 L-2 L-3 L-4 M-1 M-2 M-3 M-4 Figure M-1 N-1 N-2 N-3 (1 of 2)
(2 of 2) 34 34 34 25 30 30 21 18 21 21 35 39 39 39 35 11 22 21 0
12 39 21 34 21 39 23 19 23 30 30 30 19 37 19 16 28 16 31 25 25 34 25 31 35 35 35 35 39 37 37 DELETED)
N-4 N-5 N-6 0-1 0-2 Table Table Table Table Table 0-1 0-1 0-1 0-2 0-2 (1 of 3)
(2 of 3)
(3 of 3)
(1 of 2)
(2 of 2)
..i.
REV 39 11/04
VEGP EMERGENCY PLAN LIST OF EFFECTIVE PAGES WITH REVISIONS PAGE REV.
P-1 P-2 P-3 P-4 Figure P-1 Appendix 1 1-1 1-2 1-3 36 36 30 30 36 0
39 39 34 1-4 3(
1-5 2;
Appendix 2 0
Letters of Agreement on File 3'
LETTERS OF AGREEMENT 35
- Burke Co. EMA
- WBRO Radio Station
- WYFA Radio Station
- WJBF-TV Channel 6
- WRDW-TV Channel 12(2 pages)
- WAGT-TV Channel 26
- RMC (2 pages)
- Columbia Augusta Medical Center
- Physicians' Multispecialty Group, P.C. (2 pages)
- Burke Co. Hospital
- Medical Specialists, Inc.
- Westinghouse (6 pages)
- Bechtel (2 pages)
- Cumulus Broadcasting
- Vacant
- WBAW Radio Station
- National Weather Service (7 pages)
- WDOG Radio Station
- WKXC/KICKS 99 Radio Station
- Burke County Sheriff's Dept.
- B. Lamar Murray, M.D.
- WFXG-TV 02/08/93 04/13/98 12/14/94 02/05/93 12/15/98 02/04/93 01/18/99 03/18/97 01/07/98 12/31/97 12/21/94 10/22/98 11/12/92 12/15/98 03/01/93 01/09/95 02/10/93 02/04/93 06/24/94 01/23/98 12/29/97 09/25/96 Appendix 3 3-1 3-2 3-3 3-4 3-5 3-6 3-7 3-8 3-9 3-10 Figure 3-1 0
28 19 5
28 28 31 31 25 28 31 7
xiv REV 39 11/04
VEGP EMERGENCY PLAN LIST OF EFFECTIVE PAGES WITH REVISIONS PAGE REV.
Appendix 4 0
4-1 21 4-2 21 4-3 25 4-4 39 4-5 21 4-6 39 4-7 21 Appendix 5 0
Department of Energy -
Savannah River 07/28/93 Site Memorandum of Agreement (3 pages) 5 Appendix 6 0
Table of Contents (i) 1 ii 12 iii 1
iv 1
v 1
1-1 1
1-2 18 1-3 1
1-4 18 1-5 14 1-6 14 1-7 14 1-8 1
2-1 thru 2-7 1
3-1 thru 3-11 1
4-1 1
4-2 14 4-3 14 4-4 thru 4-7 1
5-1 28 5-2 1
5-3 1
5-4 1
5-5 1
5-6 1
5-7 1
5-8 1
5-9 1
5-10 1
6-1 thru 6-17 1
7-1 1
7-2 1
7-3 14 7-4 14 8-1 11 8-2 11 8-3 28 8-4 11 xv REV 39 11/04
VEGP EMERGENCY PLAN LIST OF EFFECTIVE PAGES WITH REVISIONS PAGE REV.
8-5 11 Figure 8-1 11 R-1 (References)
NONE Al-1 12 Letter dated 3-25-80 (2 pages) 0 A2-1 1
A2-2 1
A2-3 1
A3-1 1
A3-2 2
A4-1 1
A4-2 1
A4-3 1
A4-4 1
Addendum to Evac. Time...
5 Table of Contents (i) 5 ii 5
Page 1 5
Page 2 14 Page 3 5
Page 4 5
Page 5 28 Pages 6-17 5
Page 18 14 Pages 19-23 5
Page 24 12 Pgs. 25 & 26 (Letter dated 3-25-80)
Table 1 (Page 27)
NONE Appendix 2 (28) 5 Appendix 2 (29) 5 Appendix 7 (Corporate E-Plan) 12 Table of Contents (Page 1) 37 Table of Contents (Page 2) 28 List of Figures (Page 3) 28 List of Tables (Page 4) 28 5
36 6
36 7
37 8
37 9
36 10 37 11 31 12 -
Table B-1 37 Table B-1 (2 of 2)- DELETED 22 13 -
Figure B-1 37 14 37 15 -
Figure C-1 37 16 31 17 25 xvi REV 37 4/03
VEGP EMERGENCY PLAN LIST OF EFFECTIVE PAGES WITH REVISIONS PAGE REV.
18 22 19 36 20 22 21 37 22 -
Table G-1 37 23 - Table G-2 35 24 36 25 -
Attachment A -
References 37 26 -
Index of Corporate EPIPS 25 Attachment B (Mutual Assistance)
Agreements) DELETED 21
- 1) Nuclear Power Plant Assistance Agree. (16 pgs.)DELETED 21
- 2) Electric Utilities Assist Agreement (15 pages) DELETED 21 Appendix 8 (Emergency Commun. Plan) 23 Table of Contents (i) 27 ii 32 iii 27 1
31 2
30 3
32 4
32 5 - Figure A 32 6 - Figure B 32 7 - Figure C 32 8 - Figure D 30 9 - Figure E 32 10 32 11 32 12 32 13 32 14 32 15 32 16 32 17 32 18 31 19 31 20 30 21 32 22 30 23 32 24 19 25(TABLE 1) 32 26 27 27 27 28
.28 29 -
Table 2 (1 of 2) 32 30 - Table 2 (2 of 2) 32 xvii REV 37 4/03
VEGP EMERGENCY PLAN LIST OF EFFECTIVE PAGES WITH REVISIONS PAGE REV.
Appendix 9 5
9-1 21 9-2 35 Appendix 10 1
Sheet 1 of 2 21 Sheet 2 of 2 21 Appendix 11 6
GEMA Letter dated 9-7-84 0
..i.
REV 35 6/02
PREFACE The Vogtle Electric Generating Plant (VEGP) is a two-unit pressurized water reactor operated by Southern Nuclear Operating Company (SNC).
The plant is on a 3169-acre site located in the eastern portion of Burke County, Georgia, approximately 23 river mi upstream from the intersection of the Savannah River with U.S. Highway 301, as shown on figure i.
Figure ii shows the site and the locations of the buildings on the site.
The locations of the VEGP emergency facilities are shown on figure ii.
This Emergency Plan is applicable to VEGP, Units 1 and 2, and to its environs as specified by the emergency planning zones (EPZs): a plume exposure pathway EPZ, which nominally consists of the area within approximately 10 mi of the plant, and an ingestion exposure pathway EPZ, which extends to 50 mi. These distances are reckoned from a point midway between the centers of the Unit 1 and Unit 2 containment buildings for the 10 mile EPZ map.
The two EPZs are shown in figures iii and iv.
Because of the location of VEGP, the emergency planning and/or protective action responsibilities at the state level involves two states, Georgia and South Carolina.
Both Georgia and South Carolina, as well as the counties (Burke County in Georgia and Aiken, Barnwell, and Allendale Counties in South Carolina) within the plume exposure pathway EPZ, have prepared plans for a response to an emergency at VEGP.
These plans describe their respective responsibilities, authorities, capabilities, and emergency functions.
The major portion of the plume exposure pathway EPZ in South Carolina is within the Department of Energy's Savannah River Site (SRS).
The Department of Energy, Savannah River Operations Office (DOE-SR), pursuant to a memorandum of agreement between Georgia Power Company (GPC),as assigned to SNC, and DOE-SR provided in appendix 5, will be responsible for all emergency response actions on the SRS whenever an emergency occurs at VEGP.
Small areas of Georgia within a 10-mi radius of the plant have been excluded from the detailed state and local planning. The area in Richmond County has been excluded because it is a low-lying swampland with no residences, no access routes, and limited recreational use.
A letter documenting this provision is included in appendix 11.
Within the plume exposure pathway EPZ, Burke County in the State of Georgia has the largest resident population.
- However, even here the population is small and dispersed.
The areas in South Carolina that are not federally owned or controlled are along the Savannah River lowlands in Aiken, Allendale, and Barnwell Counties.
The segment in Aiken County, approximately 8 to 10 mi NNW from VEGP, is part of the Cowden Plantation xix REV 39 11/04
and has no resident population.
The segments to the ESE, Barnwell and Allendale Counties (approximately 9 to 10 mi from VEGP), are largely comprised of portions of the Creek Plantation, a horse farm.
Within the South Carolina portion of the plume exposure pathway EPZ, the only housing occurs within the Creek Plantation in Barnwell County, where there are only a limited number of permanent residences.
Figure v presents the permanent population within the plume exposure pathway EPZ.
The transient population within the plume exposure pathway EPZ includes persons in the work force at the VEGP and at recreational areas, mainly hunters and fishermen (see figure vi).
This transient population is generally along the Savannah River; around the Cowden Plantation and Gray's Landing in Aiken County; around Creek Plantation in Barnwell and Allendale Counties; and at St. Mary's Baptist Church in Barnwell County.
The EPZ for ingestion exposure includes an area within 50 mi of VEGP.
Planning for the ingestion exposure pathway is a responsibility of the States of Georgia and South Carolina.
More information about the ingestion exposure pathway EPZ can be obtained from the States' Radiological Emergency Plans.
The order of the presentation provided herein follows that of the 16 standards delineated in 10 CFR 50, Section 50.47 (b).
Appropriate criteria from NUREG-0654, Revision 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, are addressed approximately in the sequence presented in that document.
Although this Plan is designed to stand on its own, two additional plans expand on matters mentioned here:
the Corporate Emergency Plan (appendix 7) and the Emergency Communication Plan (appendix 8).
It is to be recognized that this is only a plan and not a prescriptive document.
Each incident is a unique event; therefore this Plan is designed to incorporate the flexibility to tailor the response and meet the emergency.
This Plan is supported by a set of implementing procedures.
A listing of these procedures is included as appendix 9.
xx REV 12 4/90
B. ONSITE EMERGENCY ORGANIZATION Initial staffing of the onsite emergency organization will be provided from personnel normally employed at the site.
For reference throughout this section, the organizational chart for the Vogtle Electric Generating Plant (VEGP) staff is presented in figure B-1.
If the need arises, this staff will be augmented substantially by the addition of Southern Nuclear Operating Company (SNC) personnel and by personnel from other organizations.
This section includes a description of the emergency duties of the normal shift complement, a discussion of the manner in which emergency assignments are to be made, a listing of additional support personnel on whom VEGP can rely, and a description of the relationships between onsite and offsite response activities.
B.1 NORMAL PLANT ORGANIZATION The organizational structure shown on figure B-1 represents the pool of personnel available on site during normal working hours. Approximately 700 people are stationed at the site during the standard workday.
The normal operating crew for two units includes a shift supervisor, licensed plant operators, and non-licensed plant operators.
A shift superintendent is also on shift during operation (as defined in the Technical Specifications).
Personnel from the Chemistry and Health Physics, Maintenance, and Security Departments are also on site continuously.
Refer to table B-1 of this section for minimum staffing requirements.
B.2 EMERGENCY ORGANIZATION The emergency director has the responsibility to classify an event in accordance with the emergency classification system (described in section D).
Classification of an event into one of the four emergency categories (Notification of Unusual Event (NUE), Alert, Site Area Emergency, or General Emergency) activates the VEGP emergency organization.
The extent to which the emergency organization is activated depends on the severity of the situation.
Table B-1 provides a summary of personnel available on shift and those who would be available within 60 min of notification.
For an NUE, the emergency director assigns responsibility for making the appropriate notifications and directing the proper response; but no further activation of the emergency organization is required.
If the event is classified as an Alert, the technical support center (TSC), operations support center (OSC), and Corporate Emergency Operations Center (CEOC) will be activated.
B-1 REV 31 12/00
For this classification, the emergency organization is structured as shown on figure B-2.
The corporate emergency organization will also be activated.
The organization for corporate response is shown on figure B-4, and further information about the corporate resources and operations is presented in the SNC Corporate Emergency Plan (appendix 7).
Corporate personnel who report to the plant site will be integrated into the VEGP emergency organization.
In addition, the emergency operations facility (EOF) will be brought to a standby status.
For a Site Area Emergency or General Emergency, the emergency organization and EOF will be fully activated.
The organization will be as shown in figure B-3.
A security related emergency may delay the ordering of facility activation in order to protect plant personnel from the security threat.
The decision to delay activation of the facilities will be made by the Emergency Director.
Relationships among the VEGP emergency organization and other elements of emergency response are shown on figure A-1.
B.2.1 Emergency Organization Responsibilities Following an Alert or higher emergency declaration, the positions shown on figures B-2 and B-3 will be filled by VEGP or SNC personnel as discussed below.
- 1. EMERGENCY DIRECTOR Plant and corporate personnel that may be designated as emergency directors are listed in table B-2 of this plan.
They will receive training as specified in table 0-2 of this plan prior to becoming qualified to fill this position.
Their nonemergency positions as vice president, general manager, assistant general managers, managers, superintendents, and supervisors provide them plant knowledge and supervisory skills necessary to fill the emergency director position.
The emergency director has the authority, management ability, and knowledge to assume the overall responsibility for directing VEGP staff in an emergency situation.
Initially this position will be filled by the shift superintendent or the shift supervisor if the shift superintendent can not be located expeditiously.
The responsibility for emergency direction will be transferred to the nuclear plant general manager, or an alternate after receiving an appropriate briefing and becoming familiar with the current status of events.
Turnover with the accompanying briefing will include, but is not limited to, the following:
B-2 REV 35 6/02
- 1. Review of logs and status boards.
- 2. Discussion with the incumbent including emergency classification, summary of events, offsite notifications, plant status, equipment status, outstanding orders, any noted deficiencies and completed checklist items.
- 3. Discussion with staff, as needed.
Following relief, announcement will be made to staff of the transfer of responsibility.
(See Procedure 91102-C for specifics.)
The primary and alternates for the position of emergency director are shown on table B-2.
The emergency director manages the following activities for the duration of the emergency:
Notification and communication: directs the notification of VEGP, SNC and GPC personnel and notifies and maintains open communications with offsite authorities regarding all aspects of emergency response.
Emergency response facilities:
oversees the activation and staffing and requests additional assistance, as needed.
Emergencv operations:
has authority over those actions taken to mitigate the emergency condition or reduce the threat to the safety of plant personnel or the public, including the recommendation of protective actions to offsite authorities.
Emergency services:
provides overall direction for management of procurement of site needed materials, equipment, and supplies; documentation; accountability; and security functions.
Emergency operations planning provides overall direction for the management of planning for procedure, equipment, and system development to support emergency operations.
Discretionary authority:
can modify emergency implementing procedures; may tailor the emergency organization to fit the specific staffing needs on a case by case basis.
The emergency director may not delegate the following responsibilities:
- The decision to notify offsite emergency response agencies.
B-3 REV 24 03/97
- The decision to recommend protective actions to offsite authorities.
- Declaration of emergency classifications.
- Authorization for plant personnel to exceed 10 CFR 20 radiation exposure limits.
- The decision to downgrade the emergency classification or terminate the emergency.
- Request for Federal assistance.
- The decision to order site dismissal of non-involved personnel from the site at an Alert classification level.
- The decision to order non-involved personnel to proceed to a reception center and receive radiological monitoring.
The emergency director may operate from the control room, TSC, or EOF at his discretion.
He may act as the TSC manager during the early phases of emergency response until the EOF is activated.
- 2. TSC STAFF
- Coordination of inputs and recommendations from technical and corrective action advisors.
- Direction of onsite emergency personnel involved in restoration of the plant to a safe condition.
- Technical assistance and operations guidance to control room personnel.
- Direction of TSC staff in analysis of problems, design and planning for temporary modifications, and development of temporary emergency operating procedures.
- Recommendation of protective actions to the emergency director based on plant conditions.
- Providing recommendations on emergency classifications to the emergency director.
B-4 REV 39 11/04
- b. TSC Support Coordinator The TSC support coordinator directs the clerical and logistic activities in the TSC.
He ensures that support staff, including clerks, status board keepers, and communicators, are available in sufficient numbers and that office supplies, drawings, and other documents are available to TSC and OSC personnel.
He is responsible for timely completion of offsite notification.
He ensures that transportation and communication needs are satisfied.
He arranges for additional offsite support personnel and equipment working in conjunction with the EOF support coordinator.
(Designees are identified on table B-2).
- c. Engineering Supervisor The engineering supervisor directs a staff of engineers with expertise in reactor engineering, thermal and hydraulic analysis, instrumentation and control, and mechanical and electrical systems.
He directs the analysis of plant problems, core damage, and provides recommendations for plant modifications to mitigate the effects of the accident.
- d. Maintenance Supervisor The maintenance supervisor manages the planning and coordination of repair, damage control, and plant modification activities.
He works closely with the engineering supervisor in planning for plant modifications and repairs.
- e. Operations Supervisor The operations supervisor analyzes problems associated with systems operations and provides recommendations for procedures for mitigating the emergency situation.
- f. Health Physics Supervisor The health physics supervisor is responsible for onsite and in-plant radiological controls.
He provides guidance to the maintenance supervisor related to radiological considerations associated with plant modification and repair and provides direction to the OSC manager related to the health physics controls for emergency teams.
He performs offsite dose assessment prior to EOF activation and keeps the dose assessment supervisor in the EOF informed of the radiological status of the plant.
B-5 REV 37 4/03
- g. Chemistry Supervisor The chemistry supervisor is responsible for directing and evaluating in-plant chemistry and analyses, directing and evaluating post accident sampling, and assisting in core damage assessment.
- h. TSC Security Supervisor The TSC security supervisor coordinates the security functions including accountability and site access control. He coordinates the processing of offsite personnel who require authorization to enter the site.
When directed by the emergency director, will request assistance from civil law enforcement authorities, as required.
- 3. OSC STAFF
- a. OSC Manager The OSC manager receives direction from the TSC personnel to dispatch emergency teams (e.g.,
firefighting, search and rescue, first aid, repair, etc.) to prescribed areas of the plant or site.
The OSC manager directs composition of the teams to ensure that appropriately qualified personnel are assigned.
In particular, he will ensure that proper health physics coverage is provided.
The OSC manager will provide specific instructions to the team leaders.
He will also maintain communications with the teams that remain assigned to the OSC and monitor the status of their activities.
- b. OSC Personnel Selected emergency response personnel will report to the OSC as directed. Depending on the nature of the emergency, personnel from the Maintenance, Operations, Chemistry and Health Physics Departments will be directed to report to the OSC. The following emergency teams will be formed as necessary:
- Backup fire brigade.
- Search and rescue.
- First aid.
- Damage assessment.
- Damage control.
B-6 REV 37 4/03
- Repair and modification.
- Field monitoring.
Each team will be headed by a designated team leader, who will maintain communications with the OSC, TSC, or EOF.
- 4. EOF STAFF The emergency director will normally manage the VEGP emergency organization from the EOF when activated.
In addition to serving as the overall command center, the EOF is the location where offsite response activities are coordinated and initial reentry and recovery actions are planned.
- Overall direction and control of offsite VEGP response.
- Communication of radiological information to State and local emergency response agencies.
- After consultation with the emergency director, provides support for initial activities associated with planning for recovery operations.
B-7 REV 31 12/00
- Ensures timely completion of offsite notifications in coordination with the TSC support coordinator.
- Ensures the availability of an adequate number of administrative personnel for EOF and TSC operations.
- Develops a duty roster for extended emergency operations, if necessary.
- Obtains and distributes office supplies, office equipment, drawings, and documents, as necessary.
- Provides temporary quarters, food, and water as necessary for emergency workers.
- At the request of the EOF manager or emergency director, makes contact with private organizations to provide support services.
- Expedites procurement of necessary materials or equipment.
- Arranges for offsite support personnel and equipment.
- Access control for the EOF
- c. Dose Assessment Supervisor The dose assessment supervisor is responsible for the evaluation of offsite radiological conditions; specific responsibilities include:
- Performance of offsite dose calculations in accordance with plant procedures.
- Direction of VEGP field monitoring teams.
- Comparison of calculations and measurements with State and Federal groups performing radiological assessment.
B-8 REV 37 04/03
- Projection of radiological consequences offsite, based on anticipated or predicted plant conditions.
- Recommending protective actions to the EOF manager, based on actual or projected offsite radiological consequences.
- 5. OTHER CORPORATE PERSONNEL The Corporate Emergency Plan (appendix 7) describes the actions to be taken by Southern Nuclear Operating Company (SNC) in the event of an emergency.
The vice president, project, may supplement the VEGP emergency organization with additional resources and personnel from Hatch or Farley Nuclear Plant.
B.2.2 Emergency Organization Assignments Table B-2 identifies by title the individuals who will fill the key emergency positions.
A sufficient number of people are identified to ensure that all emergency positions on table B-2 will be filled.
B.2.3 Other Support Services
- 1. CONTRACTOR SUPPORT Arrangements have been made to obtain support services from Bechtel Power Corporation and Westinghouse, if required.
These organizations will initially be contacted by the EOF support coordinator or Corporate Emergency Operations Center to arrange for the required assistance.
- 2. MEDICAL ASSISTANCE Agreements are in place with Radiation Management Consultants, Burke County Hospital, Doctors Hospital, and Burke County Emergency Management Agency (see appendix 2) to provide assistance for injured personnel, including cases involving radioactive contamination.
This assistance will be requested whenever necessary in accordance with plant procedures.
B-9 REV 35 6/02
- 3. AGENCY SUPPORT Assistance may be requested from Burke County, the State of Georgia, or Federal agencies.
Section A of this Plan describes the assistance that may be requested.
Any requests for aid will be made by the emergency director.
B.2.4 Interfaces Among Response Groups Section A, figure A-1, illustrates the integrated organization for response to an emergency at VEGP.
B-1 0 REV 19 1/94
TABLE B-i (SHEET 1 OF 2)
MINIMUM STAFFING FOR POWER OPERATION Augmen-Major Functional Area Major Tasks:.
Position Title or Expertise On.
tation in
.__.__._:_:_.________:: __._:.- _-_. Shift 60 m in Plant operations and assessment Shift superintendent (SRO) 1(a) of operational aspects Shift supervisor (SRO) 1(a)
Plant operator (RO) 3(a)
Plant equipment operator 3(a) (e)
Emergency direction and control Overall management of Shift supervisor; 1(b)
(emergency director) emergency organization shift superintendent Notification/communication Notification of VEGP, State, Shift administrative assistant 2
2 local, and Federal personnel or other trained personnel Radiological accident assessment EOF direction Manager or superintendent; 1
and support of operational Offsite dose assessment HP/Chemistry Shared foreman 1
accident assessment Offsite surveys Chemistry technicians and 3
3 onsite (out of plant) other trained personnel Chemistry/radiochemistry Chemistry technicians or 1
1
- :equivalent Plant system engineering, repair Technical support (including Shift technical advisor or 1(c) and corrective actions core/thermal hydraulics) engineer Electrical 1
Mechanical 1
Repair and corrective actions Mechanical maintenance 1
1 System operator 1
Electrical maintenance 1
1 Instrumentation and control 1
technician Protective actions (in plant)
Radiation protection:
Health Physics technicians or 2
2
- Access control other trained personnel
- HP coverage for repair, corrective actions, search and rescue, first aid and fire fighting
- Personnel monitoring
- Dosimetry
- Decontamination
- In-plant Survey REV 30 07/00
TABLE B-1 (SHEET 2 OF 2)
MINIMUM STAFFING FOR POWER OPERATION Major Functional Area Major Tasks osition Title or On Shi Augent xpertise in 60 min-Firefighting Fire brigade per FSAR Local support Rescue operations and 2(b)
Local support first aid Site access control and Security, firefighting Security personnel Per Security Plan personnel accountability communications, personnel accountability Totals 20(d) 14 a.
b.
c.
d.
e.
Refer to technical specifications for nonpower operation.
May be provided by shift personnel assigned other functions.
Required unless shift superintendent or the individual with a senior operator license meets the qualification for the STA as required by the NRC.
Does not include positions footnoted with a (b) or (c).
One of the three plant equipment operators may be assigned to the Fire Brigade.
REV 26 4/97
TABLE B-2 (SHEET 1 OF 2)
EMERGENCY ORGANIZATION ASSIGNMENTS
- Emergency
- Position Primary Alternate (B)
Emergency director Nuclear plant general manager Plant operations AGM*; manager operations; operations superintendent; plant support AGM; shift superintendent; shift supervisor Desi gnees EOF manager Supervision from onsite staff as designated in procedure 91101-C EOF support coordinator Supervision from onsite staff as designated in procedure 91101-C Dose assessment supervisor Health Physics/Chemistry supervision from on-site staff as designated in procedure 91101-C Dose analyst Onsite staff as designated in procedure 91101-C TSC manager Supervision from onsite staff as designated in procedure 91101-C TSC support coordinator Onsite staff as designated in procedure 91101-C Engineering supervisor Supervision from onsite staff as designated in procedure 91101-C Maintenance supervisor Supervision from onsite staff as designated in procedure 91101-C operations supervisor Supervision from onsite staff as designated in procedure 91101-C Health physics supervisor Supervision from onsite staff as designated in procedure 91101-C Chemistry supervisor Supervision from onsite staff as designated in procedure 91101-C Engineers Plant engineers TSC security supervisor Supervision from onsite staff as designated in procedure 91101-C
- AGM - Assistant General Manager REV 37 04/03
TABLE B-2 (SHEET 2 OF 2)
Emergency Position, Designees OSC manager Supervision from on-site staff as designated in procedure 91101-C Dosimetry team Qualified health physics personnel Communicators (Offsite for Plant engineers; nuclear specialist; administrative assistants; operations Control Room, TSC and EOF) personnel Clerks Administrative assistants In-plant radiation monitoring Selected emergency response personnel team Post accident sampling team Selected emergency response personnel Damage control/assessment/
Selected emergency response personnel repair team Search and rescue team Selected emergency response personnel Backup fire brigade Selected emergency response personnel First aid team Selected emergency response personnel Field monitoring team Selected emergency response personnel Shift supervisor Normal operating shift personnel Plant operators Plant equipment operators REV 35 06/02
GENERAL MANAGER PLANTOPERATIONS PLANTSUPPORT ASST.GENFRAL ASST.GEKERAL MANAGER MANAGER F.
I MAINTENANCE OUTAGE&
HEALTH P11YSICS TRAINING &
ENGMEE IING MANAGER MODIFICATIONS
& CHEMISTRY ADMINISTRATION ENIERGFNCY SUPPORT MANAGER MANAGER MANAGER PREPAREDNESS MANAGER MANAGER E',%tERCE.%CY PLANT IONS NtAtNTFNANCE SUPERIVrENnENT ADMINISTRATIVE PREPAREDNESS ENGINEERING INDENTS RINTENDEINT HEALTH SUPERVISORS SUPERVISOR PHYSICS COORDINATOR DOCUMENT TEAM 11FALTUPHYSICS CONTROL LEADER SUPERVISOR SUPERVISOR ASSISTANT SUPERINTENDENT TEAM SECURITY LEADER CHEMISTRY MANAGER CHEMISTRY SUPERVISOR Vogtle Electric Generating Plant AL VEGP ORGANIZATION Cn FIGURE B-1
EOF STAFF (STANDBY)
EMERGENCY DIRECTOR TSC MANAGER
-TSC SUPPORT COORDINATOR
-TSC SECURITY SUPERVISOR
-HEALTH PHYSICS SUPERVISOR
-CHEMISTRY SUPERVISOR
-MAINTENANCE SUPERVISOR
-OPERATIONS SUPERVISOR
-ENGINEERING SUPERVISOR IS SHIFT SUPERINTENDENT (CONTROL ROOM)
SHIFT SUPERVISOR I
I PLANT EQUIPMENT OPERATORS PLANT OPERATORS REV 37 4/03 RESPONSE ORGANIZATION FOR ALERT Vogtle Electric Generating Plant R
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SITE EMERGENCY
RESPONSE
ORGANIZATION Reports to the ENC when that facility is activated.
Coordination REV 37 4/03
H. EMERGENCY FACILITIES AND EQUIPMENT Following the declaration of an emergency, response activities will be coordinated at a number of facilities.
These Emergency Response Facilities (ERF) and the equipment which will be used for accident assessment and monitoring functions are described in this section.
H.1 EMERGENCY FACILITIES
The TSC has been established consistent with NUREG 0696, as described below.
The TSC is shared by both units and is located adjacent to the Unit 1 control room at el 220 ft.
The layout of the TSC and location of key personnel are shown in figure H-1.
Walking time from the TSC to the control room is less than 2 min. The TSC covers about 5900 ft2 and can accommodate 25 people.
It is an integral part of the Seismic Category I control building structure.
The TSC provides plant management and technical support personnel (including five Nuclear Regulatory Commission (NRC) personnel) with a facility from which they can assist plant operating personnel located in the control room during an emergency.
The emergency director and NRC director will be located next to each other to ensure proper communications. The TSC is equipped with a computer system, which provides source term and meteorological data and technical data displays to allow TSC personnel to perform detailed analysis and diagnosis of abnormal plant conditions, including assessment of any significant release of radioactivity to the environment.
In addition, the TSC has ready access to plant records, some of which are stored in the TSC and some in the control room.
The TSC structure and ventilation system are designed to ensure that the TSC personnel are protected from radiological hazards.
The TSC ventilation is a separate system and not a part of the control room ventilation system.
The air supply is filtered by high efficiency particulate air (HEPA) and charcoal filters.
During accident conditions the filtration system provides filtered cooling air meeting the following exposure design criteria:
5 rem -
whole body; 30 rem -
thyroid; and 75 rem - skin dose for a 30 day occupancy.
H-1 REV 21 10/94
The air filtration system will be placed in service when required by Procedure 91110-C, Duties of the Health Physics Supervisor (TSC). The ventilation system can be manually controlled from the TSC.
The air filtration system will also be placed in the filtration mode automatically whenever the control room HVAC is isolated.
The air filtration system, when activated, automatically processes all of the outdoor air together with approximately 25 percent of the recirculated air through the filtration unit.
In the initial actuation of the air filtration system, a parallel signal is initiated to deenergize the onsite technical support center battery room and toilet exhaust fans and dampers.
The continuous influx of outdoor air with no positive exhaust is designed to pressurize the area to 0.125 in. WG.
After the filtration process, the filtered air is mixed with the balance of recirculated air for further conditioning by the normal supply system.
When the TSC is activated, there will be a portable radiation monitor placed in the TSC to alert personnel of the presence of high radiation levels.
In addition, portable radiation monitors are available for personnel in transit from the TSC to other areas.
Portable air breathing apparatus and anti-contamination clothing are provided in the TSC.
The TSC normal lighting is supplied from normal offsite power through a motor control center backed up by the security diesel generator.
The TSC essential lighting is supplied from the essential lighting system. Self-contained, battery-operated emergency lighting is provided as a backup to the normal lighting for ingress and egress only and is located in the TSC hallway.
Power for TSC vital equipment is provided from either the motor control center backed up by the security diesel generator or from a battery-backed uninterruptible power supply system.
Power to the dc system is provided via battery chargers, one of which is powered from this same motor control center.
The records storage is shared by the control room and the TSC.
Separate copies of the following documents will be stored in the control room complex and in the TSC:
- Technical Specifications.
- Plant Operating Procedures.
- Final Safety Analysis Report.
H-2 REV 23 4/96
- Emergency Plan Implementing Procedures.
- Records needed to perform the functions of the emergency operating facility (EOF) when it is not operational.
In addition, copies of the above-listed documents and the following documents are available in Vogtle Electric Generating Plant (VEGP) Document Control:
- Plant operating records.
- Plant Review Board records and reports.
- System piping and instrumentation diagrams and heating, ventilation, and air-conditioning (HVAC) flow diagrams.
- Piping area drawings.
- Electrical one-line, elementary, and wiring diagrams.
- Control logic and loop diagrams.
The above records are available in current form and are updated as necessary to ensure currency and completeness.
Operations at this facility are directed by the TSC manager.
- 2. OPERATIONS SUPPORT CENTER (OSC)
The OSC has been established to be consistent with NUREG 0696 as described below.
The OSC is located on the second floor of the maintenance building in the lunch room.
The lunch room is located in the southeast corner of the second floor and is accessed via the south stairwell or the east stairwell.
Figure H-2 defines the OSC layout and shows access stairwells. The OSC is where operational support personnel (such as instrument technicians, engineers, mechanics, electricians, chemical/radiation technicians, equipment operators, incoming shift personnel, etc.) assemble to aid in the response to an emergency.
H-3 REV 30 07/00
Preparations for dispatching maintenance teams to the plant will include the following steps as described in Procedure 91104, Duties of the OSC Manager, and Procedure 91202, Activation and Operation of the OSC.
A. Members of the team will be selected by the OSC manager based on the type of work to be conducted.
B. The work will be preplanned by the maintenance personnel.
C. Drawings, manuals, and other procedures will be obtained from the document control room or maintenance building.
If the equipment manuals are not available in either facility, a complete set of manuals is available in the service building.
D. Dosimetry will be obtained from the OSC emergency kit or at the HP control point.
E. Protective clothing and equipment, radios, and other supplies will be obtained from the emergency kit stored in the OSC or the health physics control point.
All equipment will be checked before leaving the OSC or health physics control point.
F. A radiation work permit (RWP) will be completed in accordance with standard practices at the health physics control point, TSC, or OSC.
Standard procedures include emergency RWPs.
Procedure 91301-C, Emergency Exposure Guidelines, provides instruction for emergency exposures.
G. The tools and equipment needed to conduct repairs and take corrective actions will be determined. This equipment may be available in the auxiliary building tool crib or in the maintenance building.
Arrangements for tools and equipment not located onsite will be made in coordination with the support coordinator.
H. ALARA and job briefings will be held with each team in the OSC, the TSC, or at the health physics control point, as appropriate.
Work to be performed, special precautions, plant conditions, and radiological information will be included in the briefings.
I. Upon completion of the job, the team members will be debriefed and their exposures recorded.
H-4 REV 30 07/00
Status boards containing plant conditions and emergency classification will be available in the OSC.
Emergency kits containing radiation monitoring equipment, first aid supplies, decontamination supplies, breathing apparatus, portable lighting, and hand-held radios are stored in the OSC.
Emergency kit contents are listed in appendix 4.
In the event that this facility becomes uninhabitable, the functions of the OSC will be conducted from the Outage Control Center (OCC) and Clearance and Tagging (C&T) located in the control building.
Evacuation of the OSC will be conducted according to Procedure 91202-C, Activation and Operation of the OSC. This Procedure describes the method by which the OSC is evacuated and the movement of personnel to other facilities in an orderly manner.
The OSC manager will keep the TSC manager informed of the initiation, progress, and completion of the evacuation and relocation of the OSC personnel.
Operations at this facility are directed by the OSC manager.
- 3. EMERGENCY OPERATIONS FACILITY The EOF has been established consistent with NUREG 0696, as described below.
It is located in the lower south wing of the training center, approximately 1.5 mi. southeast of the plant.
The EOF is a command post for the overall management of the emergency response, the coordination of radiological assessment, and the management of initial recovery operations.
The EOF will be activated as prescribed in the Vogtle Electric Generating Plant Emergency Plan implementing procedures.
From the EOF, VEGP management personnel assist the states and other governmental bodies by recommending protective actions to ensure public health and safety.
Plant systems information, radiological data, and meteorological data are provided via the Integrated Plant Computer (IPC) system to EOF personnel.
IPC terminals may be located in the dose assessment area and others may be located in the command center area.
The EOF is the control point for the assessment of all field data and sample analyses.
This information will be available to county, State, and Federal representatives.
The EOF is sized to accommodate 35 persons, including 25 predesignated persons, 9 persons from the NRC, and 1 person from the Federal Emergency Management Agency H-5 REV 39 11/04
(FEMA).
The emergency director and NRC director of site operations will have designated seating adjacent to each other to facilitate proper communications.
It is anticipated that representatives from the states of Georgia and South Carolina will be sent to the EOF.
The EOF consists of several rooms, as shown, together with the location of key personnel, in figure H-3.
Three of these rooms are equipped with IPC terminals.
These rooms are normally used as classrooms.
The walls of these classrooms consist of panels that fold back to form one large room that can accommodate at least 35 people.
The stored IPC terminals will be placed in this area for EOF personnel use.
The remaining EOF rooms are designated for equipment and records storage, and NRC and VEGP conference rooms.
The EOF ventilation system is functionally similar to the system used in the TSC.
The EOF is sealed and maintained at a positive pressure with respect to atmospheric pressure.
The ventilation system has recirculation capability through high-efficiency particulate air filters.
The EOF protection factor has been calculated to be at least 5.7 for photons of 0.7 MeV.
Dedicated portable radiation monitors are available at the EOF for surveillance.
Normal power to the training center, including the EOF, is from a reliable offsite source.
Emergency lighting is provided by battery operated lights.
The following records or information are available at the EOF:
- Technical Specifications.
- Selected plant operating procedures.
- Emergency Plan Implementing Procedures.
- FSAR.
- State and local emergency response plans.
- Offsite population distribution data.
H-6 REV 22 5/95
- Evacuation plans.
- Savannah River Site Emergency Plan.
The following records or information can be transmitted to the EOF by hand or facsimile:
- Environs radiological monitoring records.
- System piping and instrumentation diagrams and EVAC flow diagrams.
- Piping area diagrams.
- Electrical one-line, elementary, and wiring diagrams.
The above records or information are available in current form and updated as necessary to ensure currency and completeness.
Operations at this facility are directed by the EOF manager.
- 4. BACKUP EOF In the unlikely event that the EOF becomes uninhabitable, resources and personnel will be transferred to the backup EOF, located in the Georgia Power Company (GPC) operating headquarters on Woodlands Road in Waynesboro, Georgia.
The location of Woodlands Road is shown on preface Figure iv, 50-Mile Emergency Planning Zone (Waynesboro insert).
The backup EOF is approximately 16 miles west-southwest of VEGP.
The dose assessment supervisor will assign a person to periodically complete a habitability survey of the EOF. If the dose rate exceeds 100 mrem/h or the airborne iodine activity exceeds 2.7 E-7 pCi/cc, the dose assessment supervisor may recommend to the EOF manager that the EOF be evacuated. Following the decision to evacuate, the EOF manager will manage the transfer to and setup of the backup EOF.
H-7 REV 37 4/03
The transfer of EOF activities will be conducted in such a manner that the continuity of the dose assessment and decision-making functions are maintained.
The transfer will be conducted as described below in accordance with Procedure 91203-C, Activation and Operation of the EOF.
A. The EOF manager will direct the relocation activities.
B. The control room, TSC, OSC, corporate office, Federal, State, and local officials will be notified of the decision to relocate the EOF.
C. The EOF support coordinator will direct the collection of all equipment identified in Procedure 91203-C and will arrange for the transportation of personnel and equipment.
The equipment transferred will include a dose projection computer, a facsimile machine, overhead projectors, and reference materials.
D. The dose assessment and field monitoring team direction functions will be transferred to the TSC initially.
The dose assessment function may be transferred to the backup EOF when the relocation is complete.
E. The emergency director function will be transferred to the TSC during the relocation.
The emergency director may choose to go to the TSC or direct the TSC manager to assume the emergency director function.
F. The EOF manager will inform the TSC when the backup EOF is capable of performing the EOF function.
The total time to complete the relocation to the backup EOF is approximately 75 minutes.
H.2 CORPORATE AND NEWS CENTER FACILITIES Descriptions of the corporate facilities used during emergencies and the Emergency News Center are described in appendix 7 and appendix 8, respectively.
H.3 ACTIVATION AND STAFFING OF EMERGENCY FACILITIES During the initial stages of an emergency situation, emergency activities at VEGP are directed from the control room.
For a Notification of Unusual Event, no other facilities need be activated.
For security related events, the activation of emergency facilities may be delayed as described in section B.
H-8 REV 33 12/01
Upon declaration of an Alert or higher level classification, the TSC will be activated and will be operational within about an hour of the initial notification.
Overall direction and control will be exercised from the TSC for an Alert situation.
For Site Area and General Emergency categories, the TSC will be the command center if the emergency director chooses, at least until the EOF is activated.
Activation of the OSC will be initiated at an Alert or higher level classification.
Support personnel will be directed to report to that facility as appropriate for the specific situation.
The OSC will be operational within about an hour of initial notification.
The EOF will be brought to a standby status for an Alert and will be activated for a Site Area or General Emergency classification.
This facility will be operational'within about an hour of the initial notification. VEGP security personnel will establish access control to the EOF, since it is outside the plant security area.
The emergency director may establish himself either at the TSC or EOF at his option.
H.4 PLANT MONITORING AND DATA HANDLING SYSTEMS
- 1. GEOPHYSICAL PHENOMENA MONITORS
- a. Meteorological A meteorological monitoring program is in place at VEGP.
Instruments are mounted on a 60-m tower located to the south-southwest of the power block. Parameters measured and transmitted to the control room include:
- Windspeed (10 m and 60 m).
- Wind direction (10 m and 60 m).
- Standard deviation of horizontal wind direction (10 m).
- Vertical temperature difference (10 m and 60 m).
- Ambient temperature (10 m).
- Dewpoint temperature (10 m).
- Precipitation (base).
H-9 REV 19 1/94
An equipment building which houses the recording, calibration, and amplification equipment is located near the base of the tower.
The system is powered by an uninterruptible power supply consisting of wet cell batteries, charger, and inverter for high availability.
The important parameters for characterizing the transport of airborne radioactivity are windspeed, wind direction, and atmospheric stability (derived from the standard deviation of the horizontal wind direction or vertical temperature difference). These meteorological parameters are used in a calculational methodology to assess the offsite radiological consequences of accidental releases of airborne radioactivity.
The methodology is described in section I, Accident Assessment.
- b. Hydrologic The normal source of plant cooling water is the Savannah River, which provides makeup to the cooling towers.
The probable maximum flood level has been determined to be about 140 ft mean sea level (MSL).
However, since the access elevations to safety-related structures are at 220 ft MSL, high river level is not relevant to plant safety. The ultimate heat sink for VEGP is the nuclear service cooling water towers.
Two 100-percent towers are provided for each unit, and the system will provide sufficient shutdown cooling for approximately 30 days with no makeup.
Because of these design features, hydrologic monitors will not be required for initiation of emergency actions; therefore, there will be no emergency levels based on hydrologic monitors.
- c. Seismic Seismic monitoring instrumentation for VEGP consists of time-history accelerographs, central control unit, and free-field ETNA.
A strong-motion accelerometer (SMA) is installed in the containment tendon gallery on the basemat.
The second SMA is located on the containment operating floor at elevation 220 feet.
H-10 REV 35 6/02
Activation of the time history accelerographs causes visual and audible annunciation in the control room to alert the plant operator that an earthquake has occurred.
- d. Fire Detection The fire-detection system at VEGP includes smoke, flame, and temperature detectors and manual fire alarms.
Fire-detection systems are provided in all areas with safe shutdown equipment, as well as other locations throughout the plant.
In addition to initiating fire-suppression systems, indications from the fire-detection system are transmitted to the control room.
- 2. PROCESS AND EFFLUENT RADIATION MONITORING SYSTEM (PERMS)
PERMS receives and processes radiological input readings during normal and abnormal operating and accident conditions; measures, evaluates, and reports radioactivity in designated areas; and monitors releases of radioactive materials in liquid and gaseous effluents.
Data from PERMS are obtained for the IPC. A more detailed description of PERMS is provided in FSAR section 11.5.
PERMS consists of the following components:
- PERMS Display Computer: capable of nonvolatile mass data storage and provided with all necessary programming, communication, display, and hardware to serve as information manager for the PERMS.
- Communications Display Computer:
in the control room, polls individual data modules and updates alarm status and system radiation levels throughout the plant.
Communicates with the IPC to provide data to general plant areas.
- Safety-related display console:
in the control room, provides remote control and status display of the safety-related channels from the safety data modules.
H-11 REV 35 6/02
- Data processing modules (DPMs): microprocessor-based data acquisition processors for local control and data processing; have two-way digital communication with the communication display computer except safety related DPMs which have one way communications.
- Radiation monitors:
along with their associated DPMs, detect, compute, and indicate the radiation levels at selected plant locations and actuate alarms if these levels exceed predetermined values; include area, airborne, and liquid monitors.
- Displays:
PERMS Display Computer.
Communications Display Computer.
- Printers:
Radiochemistry Lab.
There are four types of radiation monitors in PERMS:
area radiation monitors, airborne and air particulate radiation monitors, liquid radiation monitors, and post-accident radiation monitors.
The post-accident radiation monitors provide radiation monitoring after an accident.
The monitors are comprised of area, airborne, and air particulate monitors. Area monitors respond to gamma radiation photons within any energy range from 60 keV to 3 MeV. Airborne monitors are capable of detecting and measuring radioactive gaseous effluent concentrations with compositions ranging from fresh equilibrium noble gas fission product mixtures to 10-day old mixtures.
Power to post-accident monitors is diesel generator backed to ensure against interruption of monitor operation and loss of data.
- 3. Integrated Plant Computer (IPC)
The Integrated Plant Computer gathers, stores, and displays data used by TSC and EOF personnel to analyze plant conditions.
The IPC performs this function independently of actions in the control room and without degrading or interfering with control room and plant functions.
The IPC consists of workstations, printers, video copiers, and associated computer hardware and software.
H-12 REV 28 3/99
The IPC serves as the primary data acquisition system for emergency response, acquiring, processing, and feeding data to the TSC, EOF, and SPDS.
In addition, data links are provided to other locations.
Overall system unavailability is 0.01 or less.
All inputs originating from safety systems are individually isolated at specific locations before entering the IPC system.
The IPC has the required data storage capability to meet the guidelines of NUREG-0696, which specifies 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of pre-events data, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of post event data, and 2 weeks of additional post-event data within reduced-time resolution.
The emergency response parameters provided to the IPC are listed in table H-1. All the parameters in the IPC are available to all IPC workstations.
The IPC hardware and software are protected against unauthorized manipulation of, or interference with, input signals, data processing, data storage, and data output. This security is provided by way of key lock devices, integral program write protection, restricted authorized personnel access, and other administrative controls.
The required IPC equipment (processor, workstations, printer, video copiers, and network devices) are powered by a battery system (uninterruptible power).
Meteorological information is collected by a data recorder at the meteorological tower.
The information is transmitted via microwave to the plant.
In the plant, the data is provided to the IPC computer.
The meteorological system power is provided with a wet cell battery backup.
In the event the data transmission system fails, data will be obtained by sending a person to the meteorological shack to collect the information and phone it back to the plant.
Fire detection information is provided via visual observation of the fire alarm panel by the control room personnel and an audible alarm.
The fire alarm panels are discussed in the Vogtle Electric Generating Plant (VEGP) Final Safety Analysis Report (FSAR) subsection 9.5.1.
Information of fire detection will be verbally transmitted to the other ERFs by control room personnel.
Fire main header pressure is provided by direct input to the IPC.
Seismic panels are discussed in the VEGP FSAR subsection 3.7.4.
Information on seismic motion will be verbally transmitted to other ERFs by control room personnel.
H-13 REV 21 10/94
The following discussion summarizes the IPC system hardware for emergency response at various locations.
- a. Computer Room Hardware The computer is located next to the lower cable spreading room.
This room house the main computer for processing information. Also located in this room is the Input/Output equipment, printing, off-line storage, and computer network equipment.
- b. EOF Hardware The EOF is located in the training center approximately 8000 feet from the power block.
It contains workstation and computer network equipment required for communicating with the main IPC processors.
This room houses workstations, computer network equipment and data link equipment.
- d. Control Room Hardware The control room contains SPDS workstations and other general operator use workstations.
- e. System Input Room Hardware This room is used for signal tie point to the IPC equipment when required.
- f. Remote Processing Units In addition to the input configuration described above, many input signals come from remote processing units (RPUs).
Field data will be scanned, converted to engineering units, and transmitted to the IPC system via seven data links from three remote processing units.
Data from train A will be transmitted via three data links by RPUA.
Data from train B will be transmitted via three data links by RPUB.
Nonnuclear safety data will be transmitted via a single data link by RPUN.
H-14 REV 29 6/99
- g. Process Effluent Radiation Monitoring System Radiation inputs are scanned and transmitted to the IPC system via data links by PERMS.
In accordance with the requirements of 10 CFR 50, Appendix E, Section VI and NUREG 1394, Revision 1, means are provided to transmit critical plant variables from the onsite computer system to the Nuclear Regulatory Commission Operations Center via a dedicated communications link. The installed system consists of a computer which polls the Integrated Plant Computer (IPC)for the required data, assigns the appropriate data quality value, formats the data stream, and periodically transmits the data stream over the dedicated telecommunications circuit to the NRC.
NUREG 1394, Revision 1, required submittal of a Plant Attribute Library (PAL) and Data Point Library (DPL) to the NRC.
Vogtle Electric Generating Plant submitted the original PAL and DPL information to the NRC under a letter from C. K. McCoy to the USNRC (letter number ELV-03500).
Changes to the computer configuration or data protocols (contained in the PAL) must be reported to the USNRC at least 30 days prior to installing the change.
Changes to the information describing the specific computer data points transmitted must be reported to the USNRC within 30 days following the change.
The specific plant parameters which are designated as ERDS points are shown in the FSAR in table 7.5.2-1.
Typical plant modifications which might affect the DPL include:
- 1. Software changes which affect calculated points on the IPC.
- 2. Rescaling or replacement of transmitters that are scanned by the IPC, PSMS, or PERMS and are associated with ERDS.
- 5. SAFETY PARAMETER DISPLAY SYSTEM The SPDS provides a display of plant parameters from which the status of operation can be assessed, in the control room, TSC, and EOF.
The SPDS has the following functions:
- Aids the control room operators in the rapid detection and identification of abnormal operating conditions.
H-15 REV 22 5/95
- Provides additional specific information to analyze and diagnose the cause of abnormal operating conditions.
- Monitors plant response to corrective actions.
- Provides grouping of parameters to enhance the operators' capability to assess plant status quickly without surveying all control room displays concurrently.
- Directs the operators' attention to other specific confirmatory non-SPDS control room displays.
- Provides human factors engineered display formats in simple and consistent display patterns and codings.
- Provides display information on a real-time basis, along with validation of data.
- Provides generated selectable trend displays on a real-time basis for monitoring reactivity control, reactor core cooling and heat removal from the primary system, reactor coolant system integrity, radioactivity control, containment integrity, and other selected parameters.
The SPDS in the control room consists of displays of sets of concentrated parameters from which plant safety status can be rapidly assessed.
Duplicate SPDS displays are located in the TSC and EOF to maximize the exchange of information between these facilities and the control room.
The SPDS in each facility is a peripheral of the IPC system. The SPDS is in operation during normal and abnormal operating conditions.
The selection of parameters to be displayed on the SPDS is based on the parameters required to monitor the critical safety functions identified by the Westinghouse Owners Group (WOG).
These parameters will aid control room operators in determining the safety status of the plant.
The justification for selecting these parameters is contained in the analyses and background information generated by the WOG to support the critical safety function restoration guidelines.
The emergency response guidelines, which contain the critical safety function restoration guidelines and identify the parameters used to monitor the critical safety functions, have been submitted to the NRC by the WOG.
H-16 REV 22 5195
- 6. POST ACCIDENT SAMPLING Liquid samples from the reactor coolant system and the containment sumps, and air samples from the containment atmosphere may be taken during accident conditions.Section I of this plan contains a more detailed description of these capabilities.
- 7. OTHER PROCESS PARAMETERS Several other process parameters, including reactor coolant system pressure and temperature, containment pressure and temperature, liquid levels and other system indications, are useful both for the initiation phase and continued assessment.
The specific parameters monitored by the IPC are listed in table H-1.
Several of these are used in the classification process as discussed in section D, Emergency Classification System.
H.5 OUT OF PLANT MONITORING
- 1. GEOPHYSICAL MONITORING A source of meteorological data is Bush Field in Augusta. The National Weather Service (NWS) maintains an automated observation station at the airport; and windspeed, wind direction, cloud cover, and ceiling height can be obtained. Information from this automated observation station as well as forecast information can be obtained from the NWS in Columbia, S. C.
- 2. RADIOLOGICAL MONITORING VEGP will have sufficient portable equipment and trained personnel to field three field monitoring teams. Each team will include two people who will obtain an emergency monitoring kit. The kits will include dosimeters, a two-way radio, meters for measuring gamma and beta/gamma dose rates, and air samplers for collecting particulates and iodines.
The particulate filter is used in the field primarily to clean the sample so that any activity on the cartridge (silver zeolite or equivalent) will be iodine.
The cartridge is then counted in the field to provide an estimate of airborne iodine concentration. VEGP monitoring teams will remain on the Georgia side of the Savannah River.
H-17 REV 34 04/02
Radiological monitoring on the South Carolina side of the Savannah River will be conducted by personnel from the SRS, or the State of South Carolina.
These field monitoring teams will be equipped with equipment similar to that used by the VEGP teams.
Results of the SRS monitoring activities will be provided to the EOF.
- 3. LABORATORY FACILITIES VEGP has laboratory facilities for analysis of radioactive samples.
The major pieces of equipment include a solid-state gamma spectrometer and a beta/gamma gas proportional counter.
The GPC environmental laboratory located in Smyrna, GA has the capability to perform isotopic analyses of drinking water, river water, milk, vegetation, sediment, and biological samples, as well as tritium and gross-beta analysis.
In addition, processing of environmental TLDs will be handled by this laboratory.
Backup laboratory facilities are available at Plant Hatch. This backup capability could be used if facilities in VEGP were not available.
H.6 EMERGENCY KITS Emergency kits are located in the TSC (for control room also), the OSC, the health physics control point and the EOF.
An ambulance kit will be carried by the VEGP health physics technician who accompanies the ambulance.
Procedures require an inspection and operational check of equipment in these kits on a quarterly basis and after each use.
Equipment in these kits is calibrated in accordance with the suppliers' recommendations.
A set of spares of certain equipment is also maintained to replace inoperative or out-of-calibration equipment.
A listing of the typical contents of each kit and the spares is included in appendix 4.
H-18 REV 39 11/04
TABLE H-1 INTEGRATED PLANT COMPUTER INPUTS
- Neutron flux
- Pressurizer (pressure, level, temperature, valve position).
- Reactor coolant system (pressure, temperature, flow)
- Reactor coolant pump status
- Containment (pressure, temperature, H2 concentration, water level)
- Containment spray system status
- Safety injection system status
- Residual heat removal (RHR) system status
- Chemical and volume control system (CVCS) status
- Nuclear service cooling water (NSCW) system status
- Component cooling water (CCW) system status
- Auxiliary component cooling water (ACCW) system status
- Steam generator (pressure, level, flow)
- Auxiliary feedwater system status
- Turbine status
- Generator status
- Condensate system status
- Feedwater system status
- Circulating water system status
- HVAC systems status
- Radiation monitoring systems (effluent, area, and process monitors)
- Meteorological system (primary and backup tower, wind speed, wind direction, indication of stability class, temperature) {Unit One IPC only}
REV 34 4/02
TECHNICAL SUPPORT CENTER AIR LOCK 65' COMPUTER ROOM AIR VESTIBULE LOCK OPERATION ROOM
- EMERGENCY DIRECTOR
- TSC MANAGER
- ENGINEERING SUPERVISOR
- OPERATIONS SUPERVISOR
. MAINTENANCE SUPERVISOR
- HEALTH PHYSICS SUPERVISOR
- CHEMISTRY SUPERVISOR
. NRC DIRECTOR (IPC TERMINALS)
MECHANICAL (ERDS COMPUTER)
OPC TERMINAL)
EQUIPMENT ROOM (HVAC)
COMMUNICATIONS HPXCHEM STATT OPC TERMINAL)
CONFERENCE ROOM
- NRC STAFF
- VEGP STAFF TO CONTROL ROOM Id AIR LOCK LEVEL 1 CONTROL BUILDING ELECTRIC EQUIPMENT ROOM BATTERY ROOM RESTROOMS
& SHOWERS WORK AREA m
AIR LOCK 84' 0A
WOMEN'S RESTROOM STAIRWELLI rI iL 0
I HP AREA KITCHEN OSC STAFF WAITING AREA MAINTENANCE ENGINEERING OFFICES OPERATIONS SUPPORT CENTER 7
t,;---
OSC MANAGER'S OFFICE cn 0m OSC STAFF CONFERENCE AREA F
I STAIRWELL Il MAINTENANCE BUILDING SECOND FLOOR REV 19 1/94
EMERGENCY OPERATIONS FACILITY COMMAND
. UIPMENT CONFERENCE STORAGE ASSESSMENT ROOM EMERGENCY DIRECTOR EOF E3 17 RECORDS SITEOPERATIONS FEMA OFFICE STATEfCOUNTY REPRESENTATIVES STAIRS UP WOMENS ENCY RESTROOM IRAGE MENS RESTROOM NRC CONFERENCE ROOM MECHANICAL OFFICE OFFICE ROOM KITCHEN Vogtfe Electric Generating Plant EOF LAYOUT PLAN FIGURE H 3
Reception Desk Entrance Parking Lot 0
C, 00 E
0 0cc I
Support Staff ENN Security Assembly Room NRC Staff Georgia South Carolina NRC Staff Emergency Director NRC Director Site Operations EOF Manager
-o en
-60 00
(:C3 U) -
SRS FEMA VEGP and DNR Dose Assessment Dose Assessment I
Status I
REV 37 4/03 i
BACKUP EOF FLOOR PLAN Vogtle Electric Generating Plant A
FIGURE H-4
J. PROTECTIVE RESPONSE This section describes the protective actions that have been developed to limit radiation exposure of plant personnel and the public following an accident at the plant.
This section addresses conditions at the Alert, Site Area, or General Emergency classification.
Protective response at the Notification of Unusual Event (NUE) level would be taken at the discretion of the emergency director.
J.1 PROTECTIVE RESPONSE FOR ONSITE PERSONNEL Protective response for onsite personnel (including visitors and contractor personnel) depends upon alerting, assembly and accountability, site dismissal, monitoring, and decontamination.
- 1. ALERTING Section E of this Plan, Notification Methods and Procedures, describes the methods to be used to alert onsite personnel of emergency conditions.
- 2. ASSEMBLY AND ACCOUNTABILITY A security related emergency may preclude the ordering of assembly and accountability in order to protect plant personnel from the security threat.
The decision not to order assembly and accountability will be made by the Emergency Director.
Upon activation of the plant emergency alarm, plant personnel assigned specific emergency responsibilities proceed to their designated emergency response location. Emergency response personnel in the protected area badge into their emergency response facility (TSC, OSC, or control room) using their ACAD badge and also sign in on a personnel roster (TSC and OSC only).
The security computer system performs an initial accountability of all persons in the protected area.
Thereafter, the emergency response facility managers of the control room, TSC, and operations support center shall be responsible for periodically assuring that accountabilities in their facilities are being maintained. Assignment logs and required periodic communications between emergency response teams maintain accountability.
Non-involved plant personnel, visitors, and contractors located within the protected area leave the protected area upon hearing the emergency alarm and report to their designated assembly areas. As these individuals exit the protected area, they badge out.
The Security Department accounts for each person inside the protected area at the start of an emergency by using the security computer system.
J-1 REV 35 6/02
This method provides for accountability of all individuals inside the protected area within about 30 min. of the emergency declaration page announcement. Accountability reports are made periodically to the emergency director by the Security Department.
- 3. SEARCH AND RESCUE If protected area accountability reveals a missing person, the emergency director assembles a search and rescue team per emergency response procedures (Procedure 91401-C, Assembly and Accountability).
The search and rescue team obtains information on last known location from the computer system or reports from other personnel.
A search of likely areas is conducted until the missing individual is located.
- 4. SITE DISMISSAL Site dismissal, with or without monitoring, of non-involved personnel on-site (if feasible) is ordered by the emergency director whenever a Site Area or General Emergency is declared.
If there has been no radioactive release and a release is not projected, the emergency director may elect to order a "site dismissal with no monitoring" rather than with monitoring.
For a site dismissal with no monitoring, non-involved personnel are sent home without going to reception centers.
If site dismissal with monitoring is necessary, the emergency director will notify Burke County EMA and request setup of a reception center to receive VEGP non-involved personnel.
The route selected to the reception center is based on meteorological and/or radiological conditions.
The location of the reception center is shown in figure iv in the Preface.
Personnel on site will be notified by public address, site siren, or other communication that dismissal of non-involved personnel to the applicable reception center will take place and specify the route.
The site dismissal will be conducted and controlled per Procedure 91403-C, Site Dismissal.
Security will dispatch security officers to work areas outside the protected area to ensure all non-involved personnel have left the owner-controlled area.
REV 39 11/04
Upon site dismissal to a reception center, non-involved personnel will be monitored for contamination to determine gross contamination as per the Burke County Emergency Operations Plan.
Those personnel who are contaminated will undergo a decontamination process in accordance with standard health physics procedures.
Those personnel who are not contaminated will be released upon clearance of the vehicle.
Vehicles will be monitored by gamma instruments for contamination in the designated parking areas.
Those vehicles which indicate contamination will be marked or identified for decontamination.
Uncontaminated vehicles will be allowed to exit the area upon authorization of the reception center emergency workers.
Contaminated vehicles will be decontaminated as per the Burke County Emergency Operations Plan.
Contaminated articles and clothing and waste material will be collected and placed in containers or bags for disposal and/or processing at the site.
- 5. MONITORING AND DECONTAMINATION When an Alert is declared and site dismissal with no monitoring is anticipated, personnel who have left the protected area are monitored by portal monitors.
If necessary, decontamination is completed using the plant decontamination facilities located in the control building or other appropriate location.
When site dismissal with monitoring is expected and release of radioactivity has occurred, monitoring is performed by Burke County EMA emergency workers at an established reception center.
J-3 REV 39 11/04
Should decontamination be necessary, the reception center establishes a field decontamination area, using materials from emergency kits located in the vicinity of the reception center.
Decontamination and waste disposal are completed in accordance with the Burke County Emergency Operations Plan.
- 6. USE OF ONSITE PROTECTIVE EQUIPMENT AND SUPPLIES A supply of potassium iodide is stored in the TSC for TSC and control room use, OSC, EOF, main control point, or health physics room.
The health physics supervisor will direct the issuance of potassium iodide when the projected thyroid exposure is greater than 25 rem.
The health physics supervisor will direct radiological survey personnel to distribute potassium iodide and record the name and social security number of those individuals who are issued potassium iodide.
Potassium iodide will be issued in 130-mg doses daily for at least 3 days, but not more than 10 days.
Issuance will be performed immediately prior to exposure or not longer than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after exposure.
At the time potassium iodide is distributed, an iodine sensitivity check will be made by querying each individual concerning known reactions to iodine.
Individuals who have experienced reactions to iodine will be excused from duties requiring issuance of KI.
J.2 PROTECTIVE RESPONSE FOR THE PUBLIC VEGP is responsible for ensuring that timely recommendations for protective actions reach appropriate State and local officials. These officials (as described in section A) are then responsible for alerting the public and ordering shelter and/or evacuation, if necessary.
- 1. ALERTING The means used by VEGP to alert local and State agencies and the means used by local and State agencies to alert the public are described in section E and appendix 3 of this Plan.
J-4 REV 39 11/04
2: PROTECTIVE ACTION RECOMMENDATIONS The emergency director is responsible for providing protective action recommendations to State and local officials as part of initial notifications and follow-up communications.
These recommendations are based upon assessment actions as described in section I of this Plan.
Using available information on plant conditions, projected dose estimates, and any available monitoring data, the emergency director recommends whether the public should be advised to seek shelter or evacuate.
Other factors which influence protective actions will be evaluated by State and local officials.
The mechanism for communicating these recommendations is described in section E of this Plan.
These recommendations are based on the Environmental Protection Agency (EPA)
Protective Action Guidelines, as shown in Table J-2.
Table J-3 provides guidance to the emergency director on the expected protection afforded by residential units.
In addition, Procedure 91305, Protective Action Guidelines, provides guidance on protective action recommendations in the absence of any release of radioactivity.
Site dismissal of non-involved station personnel and evacuation and/or sheltering the general public is recommended for a General Emergency even though there has not been a release of radioactivity from the plant.
- 3. EVACUATION AND SHELTERING The Georgia Emergency Management Agency (in coordination with Georgia Department of Natural Resources) and South Carolina Emergency Management Division (in coordination with South Carolina Department of Health and Environmental Control) are responsible for deciding protective measures for affected offsite areas within their jurisdictions.
State officials will consider the potential risks of implementing protective actions against the reduction of radiological risk achieved by the protective action.
Determination of the benefit of evacuation must take into account the time needed to complete the evacuation.
Table J-4 presents a summary of evacuation time estimates. Appendix 6 includes more detail on how these estimates were developed and presents information on evacuation routes, evacuation areas, relocation centers, shelter areas, and the population distribution by evacuation areas and sectors.
J-5 REV 35 6/02
If a decision is made to evacuate any part or all of the plume exposure pathway EPZ, the evacuation will be carried out in accordance with the emergency response plan of each affected county.
In the event of an evacuation, the populace will be instructed to proceed by the appropriate evacuation route to predesignated reception centers/shelters.
Reception centers/shelters for Georgia and South Carolina counties within the plume exposure pathway EPZ are listed in Table J-5.
The services to be provided in the reception centers include:
- Registration
- Screening for contamination
- Decontamination as needed
- Information and assistance for family unification
- Food and lodging
- First aid Privately owned vehicles will be the primary mode of transportation if evacuation is directed.
Individuals who do not have their own means of transportation have been advised in the public information calendar, to arrange their own transportation, if possible.
If this is not possible, individuals are instructed to stay tuned to the radio or television and listen for the phone number to call to be picked up.
Specially equipped vehicles will be dispatched directly to the homes of handicapped and/or nonambulatory individuals requiring special transportation means.
Under certain conditions, sheltering inside the home may be the preferred recommended action.
Area radio and television stations or tone alert radios will advise the public on taking this action, will provide instructions to the public, and will give the "all clear signal" when appropriate.
J-6 REV 11 1/89
TABLE J-1 USE OF PROTECTIVE EQUIPMENT AND SUPPLIES Equipment..
Criteria for-Issuance Location..
.Means of Distribution Full face canister As needed by onsite
- a. Emergency kits
- a. Issued at OSC or respirator emergency teams in
- b. Health physics control point areas of high airborne (HP) supply room
- b. Issued as needed by radioactivity HP personnel Self contained
- a. Firefighting
- a. Control room
- a. Used as needed by breathing apparatus
- b. Toxic Gas
- b. Emergency kits operators
- c. Highly radioactive airborne activity
- d. Lack of oxygen Protective clothing As needed in areas of
- a. Various areas of
- a. Issued as needed by (coveralls, hoods, known contamination the station HP personnel boots, gloves)
- b. Emergency kits
- b. Issued'at OSC or
- c. HP supply room control point for emergency teams REV 22 5/95
TABLE J-2 RECOMMENDED PROTECTIVE ACTIONS TO REDUCE TOTAL EFFECTIVE DOSE EQUIVALENT AND THYROID COMMITTED DOSE EQUIVALENT FROM EXPOSURE TO AIRBORNE RADIOACTIVITY Projected Dose (rem) to the Recommended Actions Comments Population Total Effective Dose Equivalent No planned protective Previously recommended (TEDE) less than 1 actions.
protective actions may be reconsidered or terminated.
State may issue an advisory to seek shelter and await further instruction.
Thyroid Committed Dose Monitor environmental Equivalent (CDE) less than S radiation levels.
TEDE 1 to less than 5 Evacuate unless constraints The State and/or County make it impractical.
may shelter if evacuation Thyroid CDE 5 to less than 25 Monitor environmental poses a higher risk to radiation levels.
Control some special groups of access.
the population.
TEDE 5 and above Conduct evacuation.
Monitor environmental radiation levels and Thyroid CDE 25 and above adjust evacuation based on these levels.
Control access.
REV 21 10/94
TABLE J-3 SHELTERING GUIDANCE REDUCTION IN EXTERNAL GAMMA DOSE FROM PASSING CLOUD tructure Shielding Factor(a)
- or Location i
Average Range Outside 1.0 Vehicles 1.0 Wood frame house (no basement)(b) 0.9 Basement of wood house 0.6 0.1 to 0.7(c)
Masonry house (no basement) 0.6 0.4 to 0.7(c)
Basement of masonry house 0.4 0.1 to 0.5(c)
Large office or industrial building 0.2 0.1 to 0.3(c)(d)
- a.
The ratio of the interior dose to the exterior dose.
- b.
A wood frame house with brick or stone veneer is approximately equivalent to a masonry house for shielding purposes.
- c.
This range is mainly due to different wall materials and different geometries.
- d.
The reduction factor depends on where personnel are located within the building (e.g., the basement or an inside room).
REV 0 11/30/84
TABLE J-4 EVACUATION TIME ESTIMATE
SUMMARY
.'Evacuation'
- -Total :Evacuation
- __Area(a)
Time(b) (Minute's)
-...,Local'-:
Fair' Adverse(c)
Analysis.:
P lanning.
.Weather Weather..
Area Zone Winter-Day Winter Day 0-2 miles A
150 155 (160) 0-5 miles A, B-5, and C-5 150 155 (160) 90° S 0-5 miles A, D-5, E-5, and F-5 150 155 (160) 900 NW 0-5 miles A, B-5, C-5, D-5, E-5, 150 155 (160)
Except (SRS) and F-5 0-10 miles A, B-5, C-5, B-10, C-10, 155 160 (165) 900 S and D-10 0-10 miles A, D-5, E-5, F-5, E-10, 155 160 (165) 900 NW and F-10 0-10 miles G-10 115 120 (120) 900 N 0-10 miles H-10 155 160 (160) 900 E Full EPZ 13 Evacuation Planning 155 160 (165)
Zones
- a.
Analysis area does not include the EPZ that lies within the Savannah River Site (SRS) operated by the U.S.
Department of Energy (DOE).
If required, evacuation of the portion of the SRS within the VEGP EPZ will be accomplished by relocating the potential population at risk to areas outside of the EPZ, but still within the SRS boundaries, with evacuation route not coinciding with routes designated for the population of the other evacuation planning zones.
- b.
All residents, transients, and special facilities within the analysis area would be evacuated.
Evacuation time estimates include the times associated with notification, preparation, and mobilization events, as well as travel time out of the EPZ.
- c.
Moderate rainstorm represented by a reduction in roadway capacities and travel speeds of 20 percent. Number in parentheses indicate estimated evacuation times during a heavy rainstorm represented by a reduction in roadway capacities and travel speeds of 30 percent.
I I
I REV 12 4/90
TABLE J-5 (SHEET 1 OF 2)
RECEPTION CENTERS/SHELTERS FOR COUNTIES WITHIN PLUME EXPOSURE PATHWAY EPZ OF VEGP COUNTY
-RECEPTION CENTER/SHELTER CAPACITY:
- 1.
Georgia Burke County Burke County Comprehensive 4,675, school High School in session 1057 Perimeter Road Waynesboro 5,980, school not in session
- 2.
South Carolina Aiken County PRIMARY South Aiken High School 1200 701 Pine Road Aiken, SC 29801 (803) 641-2600 ADDITIONAL CENTER Kennedy Middle School 1200 659 Pine Log Road Aiken, SC 29801 (803) 641-2470 Middlebrook Elementary School
- 255 East Pine Log Road Aiken, SC 29801 (803) 641-2580 I
REV 39 11/04
TABLE J-5 (SHEET 2 OF 2)
COUNTY RECEPTION CENTER/SHELTER CAPACITY Allendale PRIMARY County(a)
Allendale Elementary School 675 Route 278 East Allendale, SC 29810 (803) 584-3476 ADDITIONAL CENTER Fairfax Elementary School 265 14th & Byrd Streets Fairfax, SC 29827 (803) 632-2536 Barnwell See Allendale County County Shelters listed above
- a.
To accommodate residents of Barnwell County within the Vogtle EPZ.
REV 21 10/04
K.
RADIOLOGICAL EXPOSURE CONTROL K.1 EMERGENCY EXPOSURE GUIDELINES During an emergency, it may be necessary to authorize radiation exposures above 10 CFR 20 limits.
These higher exposures may be necessary to complete protective, corrective, or lifesaving actions.
Table K-1 presents the emergency exposure limits for emergency workers involved in protecting valuable property, protection of large populations, or lifesaving actions.
Under all such situations, every reasonable effort will be made to minimize exposures. Decisions as to appropriate exposures, considering the action required and relative risks, will be made by the emergency director in consultation with health physics personnel.
Equipment and facilities have been designed in accordance with Title 10, Code of Federal Regulations, Part 50 (10 CFR 50), Appendix A, General Design Criteria for Nuclear Power Plants. Criterion 61, "Fuel Storage and Handling and Radioactivity Control," requires systems which may contain radioactivity to be designed to assure adequate safety under normal and postulated accident conditions.
Plant design has undergone an extensive As Low As Reasonably Achievable (ALARA) review.
The ALARA reviews ensured that the design philosophies established in Regulatory Guide 8.8 were considered at the design stage.
Design features are considered for potential exposure and changes are recommended to reduce potentially high doses.
The post-accident sampling procedures have been designed to provide adequate protection to personnel during the collection of grab samples. Designated sample points are specified in plant procedures.
A plant shielding design review was conducted in accordance with the criteria for infrequently occupied areas in NUREG 0737, Item II.B.2.
The projected dose rates in the facility are presented in table 12.3.1-5 of the VEGP FSAR.
The effluent sampling procedures have been written to assure that no individual receives a dose in excess of regulatory criteria (5 rem wholebody, 25 rem thyroid, 75 rem extremities). A time and dose rate study has been conducted to assure that the exposure criteria can be achieved under accident conditions.
K-1 REV 34 4/02
K.2 ONSITE RADIATION PROTECTION PROGRAM When necessary, the emergency director can authorize emergency exposures in excess of 10 CFR 20 limits but within the limits in table K-1.
Where possible, the normal radiation work permit (RWP) procedure will be used to control exposures.
This procedure requires signature approval, prior knowledge of worker past exposures, and guidance on protective actions to be used in the course of the emergency work.
If time and urgency do not allow this procedure to be followed, the health physics supervisor may approve emergency RWP controls.
In all cases, a briefing is given to the emergency team by health physics staff, and each team is accompanied by a qualified health physics technician who meets the qualifications of ANSI 18.1 criteria set out in the VEGP Technical Specifications.
This briefing includes a discussion of the hazards involved in the planned action, as well as protective actions to be taken.
A record of individual and collective exposure received during the emergency will be maintained by the dosimetry team. Exposure records at the control point or the OSC will be updated after each entry into a radiologically controlled area.
This may be accomplished through the dosimetry records computer system or manually.
An individual's dose margin will be assessed by determining the difference between the updated exposure and current administrative limit; these margins are used to determine emergency assignments.
Operation of the manual system and activation of the dosimetry team are described in Procedure 91110, Duties of the Health Physics Supervisor (TSC).
In situations where exposures in excess of 10 CFR 20 limits are authorized, the following considerations will be made prior to emergency team selection:
- 1. Declared pregnant female employees shall not be allowed to participate.
- 2. For doses greater than 25 rem, personnel shall be volunteers and be fully aware of the risks involved.
All emergency exposures will be included in personnel radiation exposure records.
Emergency dosimetry is provided to each member of the emergency response organization for both onsite and offsite organizations as required by the radiological conditions existing at the time. Appendix 4 presents information on the types of dosimetry available in each emergency response facility and other locations.
K-2 REV 21 10/94
Emergency response personnel will be made aware that self reading dosimeters should be checked every 15 to 30 min. during the emergency.
There is the capability to read TLDs within 24 h. They will also be read if the individual has received greater than a previously established value as determined by health physics procedures on their direct reading dosimeter.
Radiation dose will normally be controlled by the health physics supervisor within the limits authorized by routine station health physics procedures.
The 10 CFR 20 limits will not be exceeded without the prior approval of the emergency director.
TLDs are processed on a routine basis as delineated in chapter 12 of the FSAR.
K.3 DECONTAMINATION The action levels for determining the need for decontamination of personnel, equipment, and areas are delineated in plant admin. and health physics procedures.
Personnel decontamination facilities are located on Level 1 of the control building in room R-l10.
The decontamination facility is located adjacent to the health physics station.
Instrumentation to survey personnel during and after decontamination is located at the health physics station.
The facility has vertical showering and normal wash sinks.
Decontamination equipment for personnel is similar to that available in the Decontamination Emergency Equipment Kit (Appendix 4), except that the available supply is greater and stronger cleaning solutions are available.
Waste generated through the use of the decontamination facilities is collected and processed by the plant liquid radwaste system.
Decontamination of personnel will be conducted in accordance with standard health physics practices.
If decontamination activities are required, a controlled access area will be established by roping off the area.
Procedure 91306, Contamination Monitoring and Decontamination, addresses field decontamination and waste control.
Supplies of clean clothing will be made available.
Personnel decontamination will be accomplished using water washes or other methods for extreme cases as described in plant health physics procedures.
These procedures will be applicable to removal of radioiodine from the skin.
Decontamination of serious wounds will be accomplished at Doctors Hospital or the Burke Medical Center as described in section L of this Plan.
K-3 REV 39 11/04
Equipment and area decontamination will be conducted as determined by the TSC manager, maintenance supervisor, operations supervisor, or health physics supervisor.
It is accomplished as described in plant health physics procedures and ranges from vacuum cleaning to wash downs with water and acid or caustic solutions.
Personnel exiting the radiation-controlled area will be monitored for contamination by stand-up monitoring booths or by a whole-body scan with a hand-held probe. The standard health physics contamination limits will be used for release of personnel.
The decontamination facilities described above can accommodate both men and women who indicate low and high levels of contamination.
Plant areas that require access to facilitate recovery operations will be surveyed with portable instruments equipped with Beta/Gamma detectors.
Appropriate protective clothing will be worn, as determined by this survey, to perform activities in these areas.
Recovery operations will necessitate more detailed surveys on an as-needed basis.
K.4 ONSITE RADIOLOGICAL CONTAMINATION CONTROL Access control is provided by the Security Department during emergency conditions.
Only authorized emergency response personnel are allowed to enter the protected area.
Such personnel report to the appropriate emergency response facility for accountability prior to completing any emergency assignments.
Access to in-plant areas that are contaminated is controlled by barriers, signs, locked doors, or personnel stationed for that purpose.
Emergency monitoring teams are responsible for determining the need for onsite access control and establishing the proper method through discussions with technical support center (TSC) personnel.
Plant procedures used for determining contaminated areas will be used for determining the need for access control.
Any food, tobacco, or potable liquids that are inside a radiation or contamination controlled area, regardless of the packaging, will be considered to be contaminated until surveyed or otherwise determined to be free of contamination.
These areas will be controlled by plant health physics procedures and no eating, smoking, or drinking will be allowed.
The emergency director or designee will make arrangements for supplies to be brought in.
The emergency health physics supervisor is responsible for permitting return of onsite areas and equipment to normal use once monitoring and decontamination are completed.
K-4 REV 23 4/96
TABLE K-1 EMERGENCY EXPOSURE LIMITS FOR WORKERS PERFORMING EMERGENCY SERVICES
- Dose-Limit (rem) (a)-
Total Effective Dose Activity Condition
- Equivalent (TEDE) ;-;
5 All 10 Protecting valuable Lower dose not property.
practicable.
25 Life saving or Lower dose not protection of large practicable.
populations.
>25 Life saving or Only on a voluntary protection of large basis to persons populations.
fully aware of the risks involved.
- a.
Limit dose to the lens of the eye to three times the listed value and doses to any other organ (including skin and extremities) to ten times the listed value.
REV 19 1/94
- 0. RADIOLOGICAL EMERGENCY RESPONSE TRAINING Emergency response training is provided at four levels:
- 1. All VEGP badged personnel will receive General Employee Training at inception of onsite duties.
GET will include emergency classification, individual response, signals, accountability, and site dismissal procedures.
- 2. All VEGP emergency response organization personnel will receive specialized training per Table 0-2.
- 3. Offsite response groups who may support onsite situations, such as fire or personnel injury, will be offered annual training in notification, expected roles, site orientation, security procedures, and basic radiation protection.
- 4. Selected state and local emergency response management personnel with offsite emergency response roles will be offered a seminar/training course in specific areas; (1) the VEGP emergency classification system; (2) the VEGP protective action recommendation criteria and their relationship to plant conditions; and (3) the VEGP emergency response organization.
These offsite management personnel will be offered initial training and annual retraining.
Coordination with offsite authorities will include planning for and participation in VEGP exercises.
0.1 TRAINING As a minimum, training will be provided in the subject areas shown in table 0-1 to various personnel according to their emergency response position as shown on table 0-2.
It should be noted that these subject areas do not necessarily represent specific course titles, since several individual courses may be used to implement the training in each area.
Also, both the content and depth of training may be varied slightly, depending upon the particular audience, in order to tailor the presentation to the specific needs of the group.
The training will be conducted in accordance with lesson plans. Classroom lectures, demonstration and use of equipment, and walk throughs of facilities will be incorporated into the lesson plans as appropriate.
A written examination or practical exercise may be administered at the conclusion of a lesson. Records of the attendance and examination scores will be retained in the training files.
Those designated to receive training in each subject area are indicated in table 0-2.
0-1 REV 35 6/02
Radiological emergency response training is offered throughout the year, with each training course being covered at least once per calendar year or as often as necessary to ensure that ERO personnel remain qualified per training requirements in section 0.2.
Annual retraining consists of initial training material reinforcement and appropriate lessons learned from the previous year's operating experience.
Lessons learned that are distributed by other methods may not be included in annual retraining.
The general manager-nuclear plant may receive credit for Management of Radiological Emergencies (MRE) requalification by participating in an integrated drill or annual exercise.
In addition, drills and exercises are an integral part of the training program-and are conducted as specified in section N of this Plan.
During practical drills, on the spot corrections will be made if the situation and time allow.
If not, the corrections will be pointed out in the critique.
Upon completion of each training session or drill, the participants will be asked to critique the training in order to ensure continued improvement.
0.2 QUALIFICATION Emergency response personnel at VEGP are qualified by the following criteria:
Normal duties Positions in the emergency organization are assigned commensurate with normal managerial, supervisory, and/or technical skills, as shown in table B-2.
Mandatory training for emergency positions held Drills/exercise performance All ERO personnel shall be trained per table 0-2 within the last 15 months, except for post accident sampling and first aid training, which is to be within 36 months.
I Individual performance is evaluated and corrective actions taken as necessary.
0.3
SUMMARY
All badged VEGP workers will receive general training in emergency preparedness.
Selected individuals on site and off site will annually receive specialized training in order to implement the VEGP Emergency Plan.
0-2 REV 35 5/02
TABLE 0-1 (SHEET 1 OF 3)
TRAINING COURSE DESCRIPTIONS Training Course Core Damage Assessment Offsite Communications Emergency Plan Overview(a)
(EPO)
Description This course covers the calculational methodology for assessing core damage and estimating potential source terms. It includes retrieval of pertinent plant parameter data from the control room; making core inventory determinations based on reactor power history; estimating cladding and/or fuel damage; and estimating resultant activity released to containment atmosphere.
This course covers operation of communications equipment in the ERFs; communications methods, and procedures for notification of off-site emergency response agencies.
This course covers an overview of the Emergency Plan with special attention to emergency planning zones (EPZs); emergency classification system; onsite emergency response organizations; responsibilities of emergency response personnel; and site accountability and site dismissal.
I First Aid This course covers standard Red Cross Multimedia First Aid or equivalent.
Management of Radiological Emergencies (MRE)
This course covers classification of emergencies; emergency notification of on and offsite emergency response personnel and agencies; activation and staffing of emergency response facilities; protective action recommendation decision-making based on EPA PAG; retrieval of available plant computer data; reentry and repair operations; and communications and information management; and recovery.
- a.
EPO is included in G.E.T. badge training for all unescorted personnel.
REV 35 6/02
TABLE 0-1 (SHEET 2 OF 3)
Training Course Offsite Dose Assessment Post-Accident Sampling (TSC Chemistry Supervisors Only)
Repair and Corrective Actions Field Monitoring Team Description This course covers dose projection methodology including computerized methods; retrieval of plant computer data; methods for obtaining meteorological data; operation of the dose assessment computer; and interpretation of offsite dose calculation results.
This course covers collection of samples from plant process and effluent streams under emergency conditions; measuring radionuclide and selected chemical concentrations in those samples; interpretation of sample results. Training requirement for the TSC chemistry supervisor is triennial.
This course covers As Low As Reasonably Achievable (ALARA) principles as they apply to planning and implementing repair and corrective action; emergency exposure guidelines; and communications during repair and corrective actions.
This course covers field measurement of airborne radioactivity, radiation levels and contamination in the EPZ; collecting environmental samples; map reading; record keeping; and radio communications.
I REV 35 6/02
TABLE 0-1 (SHEET 3 OF 3)
Training Course Radiological Emergency Team In Plant Description This course covers methods for performing in-plant radiation, contamination, and airborne radioactivity surveys under emergency conditions; search and rescue of missing personnel; managing health physics activities and communications for the above activities.
I Security This course covers emergency response activities of the security department including personnel accountability; traffic control; communications; and access control to emergency response facilities.
Medical Support of Radiation Emergencies This course covers the responsibilities and methods for handling exposed and/or contaminated injuries.
It includes interfacing with ambulance crews; health physics activities for transporting a contaminated injured patient to the hospital; monitoring and decontamination while at the hospital; and final disposition of the ambulance, ambulance crew, hospital staff, and radiation emergency area (REA) at the hospital.
SCBA This course covers the use of self-contained breathing apparatus including equipment description; proper donning and use; and inspection and actions in case of equipment failure.
REV 39 11/04
TABLE 0-2 (Sheet 1 of 2)
Training Requirements For VEGP ERO Personnel N
04 0
U N
M0 E
I U
I..
0 z
a 3
t 01 w1 14 5
0 9
d 0t IN x3 Ix w E
x 14W N
W O
N4 1..
0 0z N
.4E0, 0
U 98 14 z N O
.4N 14.
0 O
1, 0
z 0
°x R1 N
0 14 W3 0I14 o o:
a:W DO,4 N N xd0 a
.4 N.
14 f.
w4 N)
.4 N4 U
En Emergency Director x
x X(b)
EOF Manager x
x EOF Support Coordinator x
x Dose Assessment x
_x___
Supervisor Dose Analyst x
x TSC Security Supervisor x
x TSC Manager x
x TSC Support Coordinator x
x Engineering Supervisor x
x Maintenance Supervisor x
x Operations Supervisor x
x Health Physics Supervisor x
x x
x Chemistry Supervisor x
x TSC Engineering Staff x
OSC Manager x
x x
Communicators x
x Clerks X(a) x Teams In-Plant Monitoring x
x x
Damage Control/Assessment x
x x
Repair And Modification x
x x
Search And Rescue x
x x
Fire Brigade x
x First Aid x
x x
I REV 37 04/03
TABLE 0-2 (Sheet 2 of 2)
Training Requirements For VEGP ERO Personnel 00 0
H I-12 0
z u
b cc 0
R D
M H
En N
1.4 5
H R
04 0VI I I IOPE I
H 14 (A
8 C..n 1..
0 0z H
1.
0 uI O
82 ix Ht0 1.40 I"
N 0
H 0
z 94-N N
b 0:
'4 a
0N ON 0
3 u0 20 Ca H
M.
A:
1.
6 In Field Monitoring Team x
x I
Health Physics Technicians x
x xx Monitoring Team Communicator x
x
_i I
(a) For Control Room Clerks Only (b) Except General Office Staff (c) Included in General Employee Training (GET)
REV 37 04/03
APPENDIX 1 GLOSSARY REV 0 11/30/84
GLOSSARY Term AIM ALARA Definition analog input module As Low as Reasonably Achievable CRT CSC CSF CSFST CVCS DEFACS DHEC DMA DNR DOD DOE DOE SR DOE SRS DPM EAS ED EMA ENC ENN ENS EOC EOF cathode ray tube Customer Service Center critical safety function critical safety function status tree chemical and volume control system Department of Family and Children Services Department of Health and Environmental Control of South Carolina direct memory access Department of Natural Resources Department of Defense Department of Energy Department of Energy -
Savannah River Operations Office Department of Energy -
Savannah River Site data processing module Emergency Alerting System emergency director Emergency Management Agency Emergency News Center Emergency Notification Network Emergency Notification System emergency operations center emergency operations facility I
1-1 REV 39 11/04
GLOSSARY (Continued)
Term Definition EOP emergency operating procedure EPA Environmental Protection Agency EPC emergency preparedness coordinator EPD Environmental Protection Division of Georgia EMD Emergency Management Division of South Carolina EPO Emergency Plan Overview EPZ emergency planning zone ERF emergency response facilities FEMA Federal Emergency Management Agency FEOC forward emergency operations center FRERP Federal Radiological Emergency Response Plan FSAR Final Safety Analysis Report FT fire training GEMA Georgia Emergency Management Agency GET general employee training GPC Georgia Power Company HP health physics HPN Health Physics Network HVAC heating, ventilation, and air conditioning I&C instrumentation and control INPO Institute of Nuclear Power Operations IPC Integrated Plant Computer MSIV main steam isolation valve MSL mean sea level 1-2 REV 39 11/04
GLOSSARY (Continued)
Term Definition MSRE medical support of radiological emergencies NACOM National Communication NAWAS National Warning System NCHPD Nuclear Chemistry and Health Physics Department NEI Nuclear Energy Institute NDOP Natural Disaster Operations Plan NOAA National Oceanic and Atmospheric Administration NRC Nuclear Regulatory Commission NSCW nuclear service cooling water NSSS nuclear steam supply system NWS National Weather Service NUE Notification of Unusual Event ODA offsite dose assessment OPS operational protection system OS operations supervisor OSC operations support center PA public address PAG Protective Action Guideline PBX private branch exchange PEO plant equipment operator PERMS process and effluent radiation monitoring system PO plant operator PRA peak recording accelerograph R&CA repair and corrective action 1-3 REV 34 4/02
GLOSSARY (Continued)
Term RCP RCS REC RERP RET RET/E RET/I RMC RO RPU RTD RVLIS RWP SAT SC SCORERP SEC SG SLED SMA SNC SOE SPDS SRO SRS Definition reactor coolant pump reactor coolant system radiation emergency coordinator Radiological Emergency Response Plan radiological emergency team radiological emergency team/environmental radiological emergency team/in plant Radiation Management Consultants reactor operator remote processing unit resistance temperature detector reactor vessel level instrumentation system radiation work permit satisfied South Carolina South Carolina Operational Radiological Emergency Response Plan security steam generator State Law Enforcement Division of South Carolina strong motion accelerometer Southern Nuclear Operating Company sequence of events safety parameter display system senior reactor operator Savannah River Site I
1-4 REV 30 07/00
GLOSSARY (Continued)
Term Definition STA shift technical advisor SUR startup rate TC thermocouple TLD thermoluminescent dosimeter TMI Three Mile Island TSC technical support center UFM universal field multiplexer USDA United States Department of Agriculture VEGP Vogtle Electric Generating Plant WOG Westinghouse Owners Group 1-5 REV 22 5/95
APPENDIX 2 LETTERS OF AGREEMENT REV 0 11/30/84
Letters of Agreement on File The following letters of agreement are maintained on file with the Site Emergency Preparedness Coordinator.
- Burke County Emergency Management Agency
- WJBF-TV Channel 6
- WRDW-TV Channel 12
- WAGT-TV Channel 26
- RMC -
Radiation Management Consultants
- Doctors Hospital
- Physicians' Multispecialty Group, P.C. and Augusta Cosmetic Survey
- Burke Medical Center
- Medical Specialists, Inc.
- Bechtel Power Corporation
- Clear Channel (WGUS-AM, WINZ-AM, WEKL-FM, WBBQ-FM, WPRW-FM, WKSP-FM, and WZNY-FM)
- WBAW Radio Station
- National Weather Service (NWS)
- WDOG Radio Station
- WKXC/KICKS 99 Radio Station
- Burke County Sheriff's Department
- B. Lamar Murray, M.D.
- WFXG -
TV Channel 54 2-1 REV 39 11/04
- Aiken County South Carolina
- Allendale County South Carolina
- Barnwell County South Carolina
- Georgia Emergency Management Agency
- South Carolina Emergency Management Division 2-2 REV 39 11/04
APPENDIX 4 EMERGENCY EQUIPMENT LISTS REV 0 11/30/84
TABLE 4-1 CONTROL ROOM/TSC EMERGENCY EQUIPMENT (TYPICAL)
- 1.
Survey meters:
Ion chamber, minimum range 0-50 R/h; Frisker, minimum range 0-50 k cpm
- 2.
Dosimeters (0-99.99 Rem)
- 3.
- 4.
Air sampler
- 5.
Silver zeolite cartridges for air sampler
- 6.
Particulate filter papers for air sampler
- 7.
Survey logs
- 8.
Smears
- 9.
Plastic bags
- 10.
Radiological signs
- 11.
Barrier ropes or ribbon
- 12.
Tape
- 13.
Plastic sheeting
- 14.
Absorbent material
- 15.
Coveralls
- 16.
Shoe covers
- 17.
Rubber gloves
- 18.
Cotton gloves
- 19.
Hoods
- 20.
Respirators
- 21.
Respirator filters
- 22.
- 23.
First aid kit
- 24.
Portable lanterns
- 25.
Flashlights
- 26.
- 27.
Clipboards, writing materials, and secretarial supplies
- 28.
Area maps
- 29.
Check sources 4-1 REV 21 10/94
TABLE 4-2 EOF EMERGENCY EQUIPMENT (TYPICAL)
EOF Supplies
- 1.
Survey meters:
Ion chamber, minimum range 0-50 R/h; Frisker, minimum range 0-50 k cpm
- 2.
Dosimeters (0-99.99 Rem)
- 3.
- 4.
Air sampler
- 5.
Silver zeolite cartridges for air sampler
- 6.
Particulate filter papers for air sampler
- 7.
Survey logs
- 8.
Smears
- 9.
Plastic bags
- 10.
Radiological signs
- 11.
Barrier ropes or ribbons
- 12.
Tape
- 13.
Plastic sheeting
- 14.
Absorbent material
- 15.
Coveralls
- 16.
Shoe covers
- 17.
Rubber gloves
- 18.
Cotton gloves
- 19.
Hoods
- 20.
Respirators
- 21.
Respirator filters
- 22.
First aid kit
- 23.
Portable lanterns
- 24.
Flashlights
- 25.
Check sources
- 26.
- 27.
Disposable plastic gloves
- 28.
Clipboards, writing materials, and secretarial supplies
- 29.
Area maps 4-2 REV 21 10/94
TABLE 4-3 EMERGENCY FIELD MONITORING KITS (3) (TYPICAL)
- 1.
Ion chamber survey meter minimum range 0-5 R/h
- 2.
Frisker minimum range 0-5 k cpm
- 3.
Dosimeters (0-99.99 Rem)
- 4.
Air sampler
- 5.
Silver zeolite cartridges for air sampler
- 6.
Particulate filter papers for air sampler
- 7.
Sample counting equipment
- 8.
Field monitoring log forms
- 9.
Area and road maps
- 10.
Clipboard and writing materials
- 11.
Radios
- 12.
Smears
- 13.
Plastic bags
- 14.
Soil scoop
- 15.
Knife
- 16.
1-liter bottles
- 17.
Tape
- 18.
Cotton gloves and rubber gloves
- 19.
Protective clothing
- 20.
First aid kit
- 21.
Flashlight
- 22.
Calculator
- 23.
Tape measure
- 24.
Stop watch
- 25.
Respirators 4 -3 REV 25 4/97
TABLE 4-4 OSC EMERGENCY EQUIPMENT (TYPICAL)
- 1.
Survey meters:
Ion chamber, minimum range 0-50 R/h; Frisker, minimum range 0-50 k cpm
- 2.
Dosimeters (0-99.99 Rem)
- 3.
- 4.
Air sampler
- 5.
Silver zeolite cartridges for air sampler
- 6.
Particulate filter papers for air sampler
- 7.
Survey logs
- 8.
Smears
- 9.
Plastic bags
- 10.
Radiological signs
- 11.
Barrier ropes or ribbons
- 12.
Tape
- 13.
Plastic sheeting
- 14.
Absorbent material
- 15.
Coveralls
- 16.
Shoe covers
- 17.
Rubber gloves
- 18.
Cotton gloves
- 19.
Hoods
- 20.
Respirators
- 21.
Respirator filters
- 22.
- 23.
First Aid kit
- 24.
Flashlights
- 25.
Batteries
- 26.
Check source
- 27.
- 28.
Data forms
- 29.
Clipboards, writing materials, and secretarial supplies 4-4 REV 39 11/04
TABLE 4-5 I
MAIN CONTROL POINT OR HP ROOM EMERGENCY EQUIPMENT (TYPICAL)
- 1.
Survey meters:
Ionization chamber, minimum range 0-50 R/h; Frisker, minimum range 0-50 k cpm
- 2.
Dosimeters (0-99.99 Rem)
- 3.
- 4.
Air sampler
- 5.
Silver zeolite cartridges for air sampler
- 6.
Particulate filter papers for air sampler
- 7.
Survey logs
- 8.
Smears
- 9.
Plastic bags
- 10.
Radiological signs
- 11.
Barrier ropes or ribbons
- 12.
Tape
- 13.
Plastic sheeting
- 14.
Absorbent material
- 15.
Coveralls
- 16.
Shoe covers
- 17.
Rubber gloves
- 18.
Cotton gloves
- 19.
Hoods
- 20.
Respirators
- 21.
Respirator filters
- 22.
- 23.
First Aid kit
- 24.
Flashlights
- 25.
Batteries
- 26.
Radiation protection and monitoring procedures
- 27.
- 28.
Clipboards, writing materials, and secretarial supplies 4 -5 REV 21 10/94
TABLE 4-6 DECONTAMINATION EMERGENCY EQUIPMENT KIT (TYPICAL)
- 1.
Ion chamber, minimum range 0-5 R/h
- 2.
Frisker with probe, minimum range 0-50 k cpm
- 3.
Smears
- 4.
Plastic bags
- 5.
Radiological signs
- 6.
Barrier ropes or ribbons
- 7.
Tape
- 8.
Plastic sheeting
- 9.
Absorbent material
- 10.
Coveralls
- 11.
Shoe covers
- 12.
Rubber gloves
- 13.
Cotton gloves
- 14.
Hoods
- 15.
Soap
- 16.
Shampoo
- 17.
Towels
- 18.
Razors
- 19.
Shaving cream
- 20.
Dosimeters (0-99 rem)
- 21.
Hand brushes
- 22.
Body maps
- 23.
- 24.
- 25.
Respirators with/filter cartridges
- 26.
Cotton swabs 4-6 REV 39 11/04
TABLE 4-7 OFFSITE AMBULANCE EMERGENCY EOUIPMENT
- 1.
Coveralls
- 2.
Shoe covers
- 3.
Cotton gloves
- 4.
Plastic bags
- 5.
Tape
- 6.
Plastic sheeting
- 7.
Absorbent material
- 8.
Rubber gloves
- 9.
Frisker with/probe, minimum range 0-50 k cpm
- 10.
TLDs(a)
- 11.
Dosimeters (0-99.99 Rem)(a)
- 12.
Radiation tape and tags
- a.
Equipment supplied by personnel at Plant Entry and Security Building (PESB).
I I
I 4 -7 REV 21 10/94 l