BSEP-99-0085, Forwards Proprietary Rev 67 to EPIP OPEP-App a, Emergency Response Resources & non-proprietary Rev 53 to Radiological Emergency Response Plan, Rev 15 to EPIP OPEP- 03.8.2 & Rev 17 to EPIP OPEP-04.2.Proprietary Info Withheld
| ML20207E138 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/27/1999 |
| From: | Jury K CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20137S371 | List: |
| References | |
| BSEP-99-0085, BSEP-99-85, NUDOCS 9906040172 | |
| Download: ML20207E138 (5) | |
Text
{{#Wiki_filter:< q CP&L Carolina Power & Light Company P.O. Box 10429 Southport, NC 28461 4429 MAY 2 71999 , SERIAL: BSEP99-0085- 10 CFR 50.54(q) U. S. Nuclear Regulatory Commission ATTN: Document Control Desk l Washington, DC 20555-0001
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BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 REVISION TO PLANT EMERGENCY PROCEDURES Gentlemen: In accordance with 10 CFR 50.54(q) and 10 CFR 50, Appendix E, Carolina Power & Light (CP&L) Company is submitting revisions to Brunswick Steam Electric Plant, Unit Nos. I and 2,
' Plant Emergency Procedures. CP&L has evaluated these changes in accordance with 10 CFR 50.54(q) and has determined that the changes do not decrease the effectiveness of the Radiological Emergency Response Plan. A list of the revised procedures is provided in Enclosure 1. A summary of the changes is provided in Enclosure 2. Enclosures 3,4,5, and 6 contain copies of the revised procedures. CP&L requests that the information contained in Enclosure 6 be withheld from public disclosure in accordance with 10 CFR 2.790(a)(6) since disclosure of this information would constitute a clearly unwarranted invasion of personal privacy.
There are no regulatory commitments being made in this submittal. Please refer any questions regarding this submittal to Mr. Warren J. Dorman, Supervisor - Emergency Preparedness, at (910)457-2068. Sincerely, I 0L t. Keith R. Jury Manager- Regulatory Affairs Brunswick Steam Electric Plant 9906040172 990527 PDR ADOCK 05000324 p )( F PDR _ {g
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Enclosures:
- 1. Listing of Revised Plant Emergency Procedures
- 2. Revision Summary .
- 3. OERP, " Radiological Emergency Response Plan (ERP)," Revision 53 -.
- 4. OPEP-03.8.2, " Personnel Accountability and Evacuation," Revision 15
- 5. OPEP-04.2,." Emergency Facilities and Equipment," Revision 17
- 6. OPEP-Appendix A, " Emergency Response Resources," Revision 67 cc (with enclosures):
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr.Luis A.Reyes, Regional Administrator Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 , Atlanta, GA 30303-3415 ' U. S. Nuclear Regulatory Commission ATTN: Mr. Theodore A. Eastick, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission A'ITN: Mr. Allen G. Hansen (Mail Stop OWFN 8G9) 11555 Rockville Pike Rockville, MD 20852-2738-cc (without Enclosure'6): Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 - Raleigh, NC 27626-0510 l
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ENCLOSURE 1- l l BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 1 DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 REVISION TO PLANT EMERGENCY PROCEDURES < Listing of Revised Plant Emereency Procedures Effective Pmcedum - Revision Date' - 11tle-0ERP 53 05/14/99 Radiological Emergency Response Plan (ERP) OPEP-03.8.2 15 04/29/99 Personnel Accountability and Evacuation OPEP-04.2 17 05/14/99 Emergency Facilities and Equipment OPEP-Appendix A 67 05/14/99 Emergency Response Resources i l l El-1 c.
P ENCLOSURE 2-BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR.-62 REVISION TO PLANT EMERGENCY PROCEDURES Revision Summary A. OERP, " Radiological Emergency Response Plan (ERP)" Revision 53 of OERP consists of the following changes:
- 1. Incorporated new accident source tenn values in Appendix F, " Technical Basis for Source Term Mixes," to reflect the new fuel configuration following refueling outages BICl2 and B2C14; and
- 2. Revised Figures 1.1-3 and 5.0-1 to reflect the site reconfiguration and inclusion of the Administration Building and Office Building inside the Protected Area.
B. OPEP-03.8.2, " Personnel Accountability and Evacuation" Revision 15 of OPEP-03.8.2 consists of a change which added Step 6.1.5 to defm' e the l duties of the Emergency Preparedness Representative during a precautionary relocation of personnel. j C. OPEP-04.2, " Emergency Facilities and Equipment" Revision 17 of OPEP-04.2 consists of the following changes:
- 1. Added information to Section 1.0 regarding the use of Attachment 2, " Equipment Repair Form," to document deficiencies noted during prescribed testing or during I normal operation;
- 2. Added OPT-96.0, "ERDS Quarterly Test With NRC," and 101-03.4.1, " Unit 1 Control Operator Daily Check Sheets," as references in Section 2.0;
- 3. Added testing requirements for the FTS-2000 phone system in Sections 5.1.6, 5.1.8,5.1.9,5.1.10,5.10.6,5.10.7, and Attachment 1, "BNP Communications Test;"
- 4. Reworded Step 5.10.1 to allow the use of alternative scheduling tools;
- 5. Revised Attachment I by moving references to the Emergency Notification System (ENS) and Health Physics Network (HPN) phones from page I to new pages 2 and 3; E2-1 o
- 6. Revised Attachment 3, "OSC/TSC/ EOF /JIC Quarterly Checklist," by adding testing of the site Environmental Monitoring Team radio and cellular phone communications equipment;
- 7. Added initial /date blocks to Sections 5 and 8 of Attachment 3; and I
- 8. Added testing of the Automatic Ring Down (ARD) phones located at the remote shutdown panels in Attachment 3.
D. ' OPEP-Appendix A, " Emergency Response Resources" i Revision 67 of OPEP-Appendix A consists of the following changes:
- 1. Updated personnel phone numbers;
- 2. Deleted Emergency Response Organization (ERO) personnel with lapsed qualifications; and
- 3. Added new ERO members.
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ENCLOSURE 3 BRUNSWJCK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 REVISION TO PLANT EMERGENCY PROCEDURES OERP.
- Radiological Emergency Response Plan (ERP)." Revision 53 i
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l l w' OERP Rev.53 f Q90 W 'G & l10ff
g, , i L i LIST OF EFFECTIVE PAGES RADIOLOGICAL EMERGENCY PLAN. Paae(s) Revision 1-10 53 1-1 20' 53 - 2 2-6 53 3 3 53 4-1 '4-29 53 I 5 5-22 -53 6 6-11 53 7 7-8 53 8 8-2 53 l-A A-4 , 53 B B-13 53 C C-3 53 D-1 53 E E-3 53 F F-7 53 ! G G-3 53 H H-10 53 p-l Attachments EAL-1 OPEP-02.1 Rev. 43 '! EAL-2 OPEP-02.1 Rev. 43 J l l OERP. Rev.53 2 ! l-
y REVISION
SUMMARY
l ^ . Revision 53 of the OERP consists of the following changes: 1 e incorporated new accident source term values in Appendix F to reflect the new fuel ' configuration following refueling outage B1C12 and B2C14. 1
. Changed Figures 1.1-3 and 5.0-1 to reflect site reconfiguration and inclusion of the j Admin Building and Office Building inside the Protected Area.
l l l l l 1 i l l l l l i OERP Rev. 53 1
r BRUNSWlCK NUCLEAR PLANT RADIOLOGICAL EMERGENCY PLAN m TABLE OF CONTENTS Section Pace
1.0 INTRODUCTION
. . . . . . . . . . . ... .. .. . . 1-1 1.1 GENERAL INFORMATION. .. . ......... . .. .. .. . . . . . . . . 1-2 1.1.1 Plant Site Description. .. . . .. ... . :-2 1.1.2 Plume Exposure Emergency Planning Zone. . . 1-2 1.1.3 Ingestion Exposure Emergency Planning Zone.. .. . 1-3 1.1.4 Demographic Information. . . . . . . . . . . 1-3 1.2 SCOPE AND APPLICABILITY.. . .. . . . . . ... .. . . . 1-4 1.3
SUMMARY
OF EMERGENCY PROGRAM . . . ... . . . 1-5 1.3.1 Concept of Operations ... . ... . . . . . . . . . . . . . .. 1-5 1.3.1.1 Emergency Response Activities .. . .. . . . . . . 1-5 1.3.1.2 Emergency Response Resources . . . . . . . . . . . . . . 1-7 1.3.1.3 Emergency Response Facilities. . . . .. ... .. . . . . 1-9 1.3.1.4 Emergency Response Plan Maintenance.. .. . 1-9 1.4 BRUNSWICK PLANT EMERGENCY PROCEDURES . .. . . .. . . 1-10 1.5 DEFINITIONS... . .. . . . . . . . . . . .. . . . . .. . 1-10 2.0 EMERGENCY CLASSIFICATIONS. . .. . . . . . . . . . 2-1 2.1 GENERAL CLASSIFICATION SYSTEM . . . . .. ...... . . . . 2-1 2.2 UNUSUAL EVENT. . . . ... . . ... ... .. 2-3 2.3 ALERT. . ..... .. . . . . . . . . . . . . . . . . . . 2-3 2.4 SITE AREA EMERGENCY... . . . . . . . . .. . . . . . . . . . 2-4 2.5 GENERAL EMERGENCY.. .. . . . . . . . . . . . . . . . . ....... 2-5 3.0 EMERGENCY RESPONSE ORGANIZATION., . . . . . . . . . . . . . .. 3-1 3.1 NORMAL OPERATING ORGANIZATION. . .. . . 3-3 3.2 ON-SITE EMERGENCY ORGANIZATION.. . . . . . . . . . . . . . . . . . . . . 3-4 3.2.1 Site Emergency Coordinator.. . .. .... .. . . . . . . . . 3-5 3.2.2 Plant Operators .. . ... . . . . . . . . .. .. 3-7 3.3 Technical Support Center . .. . .. .... . . . . .. . 3-7 3.3.1 Plant Operations Director. . . . . . 3-8 3.3.2 Radiological Control Director.. ... .. . . . . . . . . 3-8 3.3.3 Technical Assessment Director... .. . . . . . . 3-9 3.3.4 Security Director. . . . . . . . . . . . . . .. .. 3-9 3.3.5 Communications Director.. ..... . ... .. . . . . . . . . 3-9 3.3.6 Radiological Control Communicator.. . .. .. . . 3-9 3.3.7 Accident Assessment Team Leader.. . .. . . . . . 3-10 . a OERP Rev.53 3 L - _ - - - - - - - - - -
TABLE OF CONTENTS (Cont'd) m Section - Paae 3.4 . Operational Support Center....... ... ....... .........................3-10 3.4.1 Emergency Repair Director........... . ... ...... ..... ... ..... ....... .. 3-10 3.4.2 - Operational Support Center Mission Coordinator. . . . . . . . . 3-1 1 3.4.3 Operations Coordinator..... .. ..... ..........................3-11 3.4.4 Environmental & RadiologicLI Control (E&RC) C oo rd i n ato r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . 3-11 3.4.5 Radiological Emergency Teams ..... ..... .. ..... . . . . ... . . . . 3-12
'3.4.6 Fire B rig ad e . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-13 3.5 Emergency Operations Facility. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3- 13 3.5.1 Emergency Response Manager. .. . .. . . . . . . . . . . . . . . . 3-13 3.5.2 Administrative and Logistics Manager ..-........ . . ........ . .. 3-14 3.5.3- Technical Analysis Manager ..... ..... ......... . .......... .... .. ...... 3-14 3.5.4 Radiological Control Manager...... . . . . . . . . . . . . . . . . .. . . . . . 3-14 E.5.5 Environmental Monitoring Team Leader.. . . . . . . . . . . . . . . . . 3- 15 3.5.6 Dose Projection Coordinator... .......... ... .. . ..... ... . . . . 3-15 3.5.7 Communications Manager .. ... . . . ..... .. .. ... ........ .............. 3-15 3.5.8 Assistant to the Emergency Response Manager (AERM)... . 3-16 3.6 Joint Information Center...... .... . . .. . ... ... ... . . . . . . . . . . . . . . . . . . . . . 3-16 3.6.1 Company Spokesperson.... ..... ... ... .... . . .. . . . . . . . . . . . 3- 16
. 3.6.2 J l C D i re cto r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . 3-16 3.6.3 Company Technical Spokesperson ...... .. ... .. ..... . ... . ... . 3-17 s 3.6.4 Administrative Coordinator... . .. .... .. .. . . . . . . . . . . . . . . . . . 3-17 3.6.5 Public information Director.. ....... . .. .. . .. . .... .. . . . .. . . 3-17 3.7 OFFSITE ORGANIZATION ASSISTANCE ... .. . ..... . . . . . . . . 3-18 3.7.1 Contracted Services ...... . . . . ... .... .... . ... .. ...... . .. .. . 3-18 3.7.2 Local Services Support . .......... ...... . .. .... .. . ....... . . . .. 3-19 3.7.2.1 Medical Assistance. . .. . . .. . . . . . . . .. .. . . . . .. . . . . . . . .. .. .. ... 3-19 3.7.2.2 Ambulance Service . . . ... .... .. ..... . . . . . . . . . . . . . . ... 3-19 3.7.2.3 Fire Assista n ce .. .. .. . .. . . .. . . . . . . .. . . . .. ... . . . . . . . . . . . . 3-2 0 3.8 COORDINATION WITH PARTICIPATING GOVERNMENTAL AG E N C lE S ... . .. . . . . . .. . . . . . . .. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-21 3.8.1 State of North Carolina... .... ... . .... .. . . . . . .. . . . . . . . . 3-21 3.8.1.1 G ove rno r's Office . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-21 3.8.1.2 Department of Crime Control and Public Safety.. .. .. . 3-21 3.8.1.3 Department of Environmental Health and Natural Resources, Division of Radiation Protection.. . . . . 3-22 l 3.8.2 B ru n swick Cou nty... . . . ... .. . . .. . ... . . .. . . .. . . . . . . . . . .. . . . . .. . . . 3-2 2 3.8.2.1 Emergency Management Agency.. .. .. . .... . . ........... 3-22 3.8.2.2 Brunswick County Sheriffs Department.. .. . ..... .... .... 3-22 g
OERP Rev.53 4
TABLE OF CONTENTS (Cont'd) m Section Paae 3.8.3' New Hanover County.. . . . . . . . . . . . . . .. .. 3-23 3.8.3.1 Emergency Management Agency.. .... . . . . . . . 3-23 3.8.3.2 New Hanover County Shariffs Department. . . . . 3-23 3.8.4 Federal Agencies . .. ...... .. .. . . . . . . . . . .. . . . . . 3-24 3.8.4.1 Department of Energy, Savannah River Operations Office . ... . . . . . . . . . . . .. 3-24 3.8.4.2 Federal Emergency Management Agency (FEMA). . 3-25 3.8.4.3 Nuc: ear Regulatory Commission (NRC) . ... .. . . 3-25 3.8.4.4 U. S. Coast Guard (USCG). .. . . . .. .. 3-25 3.8.4.5 Murray and Trettle.. . . ....... .. .. . 3-25 3.8.4.6 Weather Service........ . . . . . . . . . . . . . 3-26 3.8.5 Ag reements ... ... . .... .. .... .. . . . . . . . . . . . . . . 3-26 3.9 NOTIFICATION AND ACTIVATION ........ . ..... . . .. . . . . . 3-26 4.0 EMERGENCY MEASURES. ... . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 4.1 ACTIVATION OF EMERGENCY ORGANIZATIONS.. . . . . . . 4-1 4.1.1 General. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 4-1 4.1.2 Unusual Event.. . . ..... . . . . . . . . . .. . . . 4-2 4.1.3 Alert . . - .. . . . . . . . .. .. .. .. . . . . . 4-2 4.1.4 Site Area Emergency. . . . . . . . . . . . . . . . . . . . . . . . . . . 4-3 4.1.5 General Emergency .. ... . .. . . . . . . . . . . . . . . . . . . . . 4-4
, 4.2 ACCIDENT ASSESSMENT ACTIONS. . ..... . . . . . . . . 4-4 4.2.1 General .. . . ... . . .... . . . . . . . . . . . . . . . . . . ... . 4-4 4.2.2 Source Term Assessment.. . ... ' . . . . . . . . . . . . . . . 4-5 4.2.2.1 Effluent and Radiation Readings . .. . . . . .. . .. . . . . 4-5 j 4.2.2.2 Potential Consequences Based on in-Plant C o n d itio n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-6 4.2.2.3 Post Accident Sampling and Analysis of Reactor and Containment. . . . . . . . . . . . . . . . . . . 4-7 4.2.3 Dose Projection and Meteorological Systems .... . . ... 4-8 4.2.4 Emergency Environmental Monitoring .. . .. .. 4-9 4.2.5 Emergency Response Data System (ERDS) ... . 4-10 4.3 CORRECTIVE ACTIONS . . . . . ... . . . . . ... . . 4-10 4.4 PROTECTIVE ACTIONS. .. .. . . . . . . . . . . . . . . . . . 4 -10 4.4.1 Protective Action - Off Site. .. . . . ... 4-11 4.4.2 Protective Action - On Site . . ... . . . . .. . . . . . . . 4-11 4.4.2.1 Warning and Notification. . . . . . . 4-11 4.4.2.2 Evacuation & Personnel Accountability . . . . . 4-12 l
w l OERP Rev.53 5 i L
g 1 . TABLE OF CONTENTS (Cont'd) m Section Paae 4.4.3 . Control of Personnel Radiation Exposures . ........ .. . . . . . 4-13 4.4.3.1 Exposure Control Under Emergency Conditions........ . 4-14 4.4.3.2 Exposures During Repair / Reentry Efforts..................... 4-15 4.4.4 Radioactive Contamination ... . .... ... .. . .... .... ........... . ... . 4-16 4.4.4.1 O n-Site Person nel . . .. . . .... .. . . . ... . .. . .... .. . ... ..... . . .. .. . .. . 4-16 l 4.4.4.2 Equipment and Vehicles .... ..... .... . .... .. . . ..... ..... 4-16 4.4.5 _ Treatment of injured and Contaminated Persons... . ... . .. . . 4-17 4.4.6 Public Warning and Notification ..... .... ... . .. .......:... . ..... .. 4-18 4.4.7 Protective Actions - Off Site /Public .. ...... . .... .. .. ........ . 4-19
-4.4.7.1 Public Education and information ........... . .... ..... . ...... 4-19 4.4.7.2 G e n e ra l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 -2 0 4.4.7.3 Eva cu a tio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4. .-21 ....
4.4.7.4 S h e lte r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . 4 -21
-4.4.7.5- . Respiratory Protection ......... . . ... ... .. ................ ..... .... 4-22 5.0 EMERGENCY FACILITIES AND EQUIPMENT ... ... ..... ..... . .. ........... . . ....... 5-1 5.1 C O NTR O L ROO M . .. . . . .. .... . . ..... . . ... .. .... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-2 5.2 TECH NICAL SUPPORT CENTER .. ... ...... ... ....... .. . . .. ......... ..... . 5-2 5.2.1 TSC/ EOF EMERGENCY VENTILATION SYSTEM .. ...... ... 5-3 5.2.2 TSC/ EOF EMERGENCY CONTAMINATED DRAIN SYSTEM 5-3 5.3 OPERATIONAL SUPPORT CENTER .. . ... ......... .. ...... ... . ..... ..... . 5-4
_. 5.4 ' EMERGENCY OPERATIONS FACILITY ........... .. ... .. ......... . ..... . 5-4 5.5- JOINT INFORMATION CENTER..... . .....................................5-5 5.6 OFF-SITE EMERGENCY FACILITIES .. ..:... ..... .... .. .. ... .... .. .... . 5-5 5.6.1 North Carolina Emergency Operations Center........... .... ..... 5-5 5.6.2 Brunswick County Emergency Operations Center ....... .. .. .. 5-5 5.6.3 New Hanover County Emergency Operations Center. ......... . 5-6 5.7 ASS ESSM ENT CAPABILITIES . .. . .. .. .. . . . . .... . . . . ... ... .. . . . . ... . . .. ... . . . 5-6 5.7.1 G e n e ra l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-6 5.7.2 Meteorological Instrumentation and Procedures ...... ...... ....... 5-6 5.7 3 Seismic Monitoring .... . ........ ... . . . ... .. .. . .. . . . . . . . . . . 5-8 5.7.4 Radiological Monitors ... .... ... .. ... . . . . . . . .................5-9 l 5.7.5 Process Monitors..... .. . .............. . .... .. . . . . . . . . 5-10 5.7.6 Laboratory Facilities .. .. . ... ........ . . .. .. .. . .... .. ..... . . 5-10 5.7.7 Dose Projection ...... .... . . . . . . . . . . . . . . . . . . . . . . ...............5-11 l l l 1 OERP Rev.53 6 m
TABLE OF CONTENTS (Cont'd) l i m Section Paae l l 5.8 FIRE DETECTION ... .... . . .. .. . . . . . . . . . . . . . . . 5-11 5.9 PROTECTIVE FACILITIES AND EQUIPMENT ... . .... . .. . . . . . 5-12 5.10 FIRST AlD AND MEDICAL FACILITIES... .. .. . . ....... . . .. ... . .. 5-12 5.11 DAMAGE CONTROL EQUIPMENT AND SUPPLIES., . . . . ... .... 5-12 . 1 5.12 OFF-SITE ENVIRONMENTAL MONITORING EQUIPMENT AND SUPPLIES.... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-13 6.0 - MAINTAINING EMERGENCY PREPAREDNESS .. .. . ..... . ... .. . . . . . 6-1 6.1 ORGANIZATIONAL PREPAREDNESS .. . .. . . . . . ... ... ...... 6-2 6.1.1 Tra in i n g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... 6-2 l 6.1.2 Drills and Exercises.. ... .. .. . . ...... . . . . . . . .. . ... . 6-4 ! 6.1.2.1 D rills . . . . . . .. . . . . . . . . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-4 6.1.2.2 Exe rcises . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-8 6.1.3 Emergency Planning Coordinator. . . . . . . . . .... ..... 6-8 6.1.4 Public Education.. .. .. .. .. .. . .... . . ....... .. .. . .... . . . 6-9 6.2 REVIEW AND UPDATE OF THE PLAN AND IMPLEMENTATION PROCEDURES... . ..... . . . . . . . . . . . . . . . . . . . . . . . . . .. 6-9 6.2.1 Plan Updates. . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-10 6.2.2 Independent Audit and Review. .. ..... . . . . . . . . . . . . .... . 6-10 6.2.3 Off-Site Agreements and Plans.. . . . . . . . . . . . . . . . . . . . . . . . . . 6-10 6.3 MAINTENANCE AND INVENTORY OF EMERGENCY EQUIPMENT AND SUPPLIES ........ .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-10 6.3.1 Emergency Equipment and Supplies.... . . . . . . . . . . . . . . . . . . 6- 1 1 6.3.2 Medical Equipment and Supplies *.. . .. . .. .... .. ....... ........ 6-11 6.4 PLANT NUCLEAR SAFETY COMMITTEE .. ........ ....... .. . .. . . 6-11 7.0 R ECOVE RY . ..... ...... .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. ...... 7-1 7.1 . G E N E RA L . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... ......... ..... ... .... .. 7-1 7.2 RECOVERY ORGANIZATION ....... ...... . . . . . . . . . . . . . . . . . . . . . . . . ... 7-1 7.2.1 Recovery Manager.... ..... .......... ... .. . . . . . . . . . . . . . . . . . .. .... 7-2 7.2.2 Plant General Manager. . . . . . . . . . . . . . . . . . . . . . . . . . 7-2 7.2.3 Technical Analysis Manager.... . .. . ... .. .... . . . .. .... 7-2 7.2.4 Engineering Manager.. . ...... . .... .. . . . . . . ..... 7-3 7.2.5 Administrative and Logistics Manager. . . . . . . . . . . . . 7-3 l 7.2.6 Radiological Control Manager. . .. . . . . . . . . . . . . . . . . . 7-3 l 7.3 RECOVERY PLAN NIN G ......... ...... ......... . . . . . . . . . . . . . . . . 7-3 l 7.4 ON-SITE RECOVERY ACTIVITIES . . .. . . . . .. . .. . .. . . .... .. ...... 7-3 ) 1 1 v OERP Rev.53 7 i l
TABLE OF CONTENTA (Cont'd) lm Section Paae 7.5 OFF-SITE RECOVERY ACTIVITIES.. . . . . . . . . . . . . . . . . 7-4 7.5.1 General. . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . 7-4 7.5.2 Emergency Cleanup Operations. ... . . . . . . . . . . . . . . . . 7-4 7.5.3 Countermeasures.. . . .. .. ... . ..... . ... . 7-5 7.5.4 Monitoring and Dose Assessment . . . . . . . . . . . . . . . . . .. 7-6
8.0 REFERENCES
. . . . . . ... ... .. . .. .. . . . . .. . . . . . . 8-1 l V OERP Rev.53 8
n 1 I r TABLE OF CONTENTS (Cont'd) N Section Paae LIST OF APPENDICES 1 Number- . . Title APP A. ' Brunswick Communications System...... ...................... .... ............... .... A .
- APP B Ag re e m e n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B- 1 APPC. Brunswick, Nuclear Plant (BNP) Off-Site Agency Support Summary.. .... C-1 APP D S u p e rs e d e d . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . D- 1 APP E . Medical Treatment and Assistance...................... .. ..... . . . .... . ............ - E-1 APP F Technical Basis for Source Term Mixes .......... . ... .......... . ..... . ........... F-1 APP G Minimum Procedures Required to implement the Sections of the Plan............................................................................................G-1 l' APP H Cross-Reference Between NUREG-0654 Evaluation Criteria and Brunswick Radiological Emergency Response Plan .................... ... .. ... H-1
.-LIST OF TABLES
' Number Title -
3.5-1 Notification and Activation of Principal Emergency Response O rg a n iz a ti o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 - 31 4.4-1 Factors Related to Warning / Evacuation Time ................... . ........... ... 4-23 4.4-2 Representative Shielding Factors for Surface Deposited R a d io n u clid e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-2 4 4.4-3 Representative Shielding Factors from Gamma Cloud Source .. ... ... . 4-25 4.4-4 PF of Various Vehicles and Structures ........... . ... .... ........ ............... . 4-26 5.0-2 Functional Objectives of Emergency Facilities . ................. ..... ... ..... .. 5-15 5.7-1 On-site Meteoroiogical Instrumentation .................................. ........ . ... 5-16
,5.7-2 Area Radiation Monitoring System Channel Identification & Meter _
i Ranges...........................................................................5-17 5.7-3 Process Radiation Monitoring System Channelidentification & ; Mete r R a n g e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-21
.5.7-4 Typical Portable Survey Equipment................. . .. . . . . . . . . . . . . . .. 5-2 2 l 7.2-1 ' Designation of Key Recovery Organization Personnel............................ 7-7 1
1 1 I i w i l OERP.:. Rev.53 9
t w a, ; o l TABLE OF CONTENTS (Cont'd) . H . Section : Paae LIST OF FIGURES
. Number Title 1.1-1 B ru n swick S ite P la n . . .. . . . . . . . . . .-. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 - 14
" !1.1 10-Mile Plume Exposure EPZ..... . . . . . .. . . ...... .. . . . . . . . . ... . . . . . .. ... .. .. .. . . . ... . 1 -15 1.1-3= Brunswick Site Building Locations ... .. ..................... ..... ... ... . .. ... ... . 1-16
'1.1-4 Wi n d R o s e s . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-17
.1.1-5 50-Mile Ingestion Exposure EPZ ... ......... ............... ...... .... ........ . . .. 1-18 j 1.1-6; P op ula tio n Tota ls . . . . .. . .. . . . . . . . . . . . . . . . . . .. . .. . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 - 19 j 1.-1-7! Concept. of Emergency Planning Zones .... . .... .... .. ..... ......... ........ . 1-20 '
2.0-1~ ' Response Sequence to Off-Normal Conditions.. .............................. ... . 2-6
~3.1 B ru n swick S hift O rg a n izatio n .. . . . . . . . . . .. . . . . .. .. . . .. . . . .. . . . . .. . . . . .. . . . . .. . . . .. . . . . . . . 3-2 8
'3.2 Brunswick Emerger.cy Organization ............ ..... .. ..... ...... ...... . . ..... 3 3.4-1 Operational Support Center (OSC)........... ...... . ......... .... . .... ..... . . 3-30 3.6-1 Joint Information Center (JIC). .... . .... ....... ...... ... .. ............... .......... 3-32 4.4-1' BNP Evacuation Schedule and Warning .............. . ................. .... ...... 4-27 4.4-2 - Evacuation Times - Brunswick EPZ .......... .. ........ .... .......... ........ .... 4-28
-s 4.4-3 Protection Factors of Shielding Materials .. ..... . . .... .... .. ................. 4-29 5.0-1 Brunswick On-Site Emergency Facilities .....'.. . . . ......... ................... .. 5-14 i l
l 7.2-1 C P& L Recove ry O rg a nizatio n . . . . . . . . .. . . . . . .. . .. . . . . . .. .. . . . . . . . . .. .. .. . .. . . ... . . . . . 7-8 i L f.
. .Q ..
OERP Rev.53 10 m n
n j CAROLINA POWER & LIGHT COMPANY BRUNSWICK NUCLEAR PLANT (BNP) ; im = RADIOLOGICAL EMERGENCY PLAN (ERP)
1.0 INTRODUCTION
~The Emergency Program for the Brunswick Nuclear Plant consists of the Brunswick Radiological Emergency Plan and its implementing Plant Emergency Procedures. The Radiological Emergency Plan may also be referred to as the
- Emergency Response Plan (ERP)in other plant documents. Also included are the related radiological emergency plans and procedures of state and local organizations. The purpose of these programs is to provide for the protection of
. plant personnel and the general'public and to prevent or mitigate property damage that could result from~an emergency at the Brunswick Nuclear Plant. The -
combined emergency preparedness programs have the following objectives:
- 1. Effective coordination of emergency activities among all organizations having a response role. l
- 2. Early warning and clear instructions to the population-at-risk in the event of '
a seri_ous radiological emergency.
- 3. Continued assessment of actual or potential consequences both on site and off site.
.4. - Effective and timely implementation of emergency measures.
' 5. Continued maintenance of an adequate state of emergency preparedness.
The Supervisor - Emergency Preparedness is the BNP Emergency Planning Coordinator. The BNP Emergency Plan and Procedures are contained in the Plant Operating Manual (POM), Volume 13, which consists of the following parts: Book 1 Radiological Emergency Plan (ERP) Book 2, Plant Emergency Procedures (PEP)
)
L i
- I s
OERP Rev.53 1-1 Li j
A list of procedurcs required to implem:nt the plan can be found in Book 2. m 1.1 GENERAL INFORMATION 1.1.1 Plant Site Description The Brunswick plant site is located in the southeastern portion of Nodh Carolina 21/2 miles north of Southport in Brunswick County, and 16 miles south of Wilmington, North Carolina, in adjacent New Hanover County. (See Fig.1.1-1 and Fig.1.1-2.) Approximate coordinates of the reactor buildings are latitude 33* 57'30" N and longitude 78* 00'30" W. The Brunswick Plant utilizes two General Electric Company boiling water reactors. Each unit is licensed to operate at 2558 megawatts-thermal with an associated gross electrical output of approximately 862 megawatts. The major structures of the Brunswick plant which contain radioactive materials are the Units 1 and 2 reactor buildings, the turbine building and radwaste building. Figure 1.1-1 shows a site plan for the Brunswick plant and Figure 1.1-3 shows the location of the buildings at the site. 1.1.2 Plume Exposure Emergency Planning Zone The plume exposure Emergency Planning Zone (EPZ) is defined to be the area within an approximate ten-mile radius of the Brunswick plant. , Principal exposure sources from plume exposure pathways are: (a) external exposure to gamma and beta radiation from the plume and deposited material and (b) exposure of internal organs to gamma and beta radiation from inhaled radioactive gases and/or radioactive particulates. Figure 1.1-2 shows the ten-mile plume exposure EPZ in relation to the location of the Brunswick plant. The plume exposure EPZ includes portions of the North Carolina counties of Brunswick and New Hanover. The prevailing winds around the Brunswick plant are from the southwest. Figure 1.1-4 presents wind roses for the Brunswick plant site. v OERP Rev.53 1-2
1.1.3 Ingestion Exposure Em@rgency Planning Zone m The ingestion exposure EPZ is defined to be the area within a 50-mile radius of the Brunswick plant. The principal exposure sources from ingestion pathways are contaminated water or food, such as milk or fresh vegetables. The time of potential exposure can range in length from hours to months. Figure 1.1-5 shows the 50-mile ingestion exposure EPZ in relation to the location of the Brunswick plant. The ingestion exposure EPZ includes the North Carolina Counties of Bladen, Brunswick, Columbus, New Hanover, Onslow. Pender, and Sampson, and the South Carolina County of Horry. The region within a 50-mile radius of the Brunswick plant site is predominantly rural, with less than one-half the land devoted to farming. The remainder of the region consists of undeveloped, non-utilized marshes and wooalands. 1.1.4 Demographic Information Demographic information for the 10-mile Emergency Planning Zone is presented in Figure 1.1-6. The information is presented by (1) local planning zones and (2) distance from plant at 0-2 miles,'2-5 miles, and 5-10 miles, based on the longitude and latitude of the plant site. Since some of the local planning zones extend beyond the 10-mile radius, the total population for the local planning zones is greater than the total population for the 0-10 mile radius. v OERP Rev.53 1-3
1.2 SCOPE AND APPLICABILITY m This document describes the Brunswick Radiological Emergency Plan %) which has been prepared in accordance with Section 50.47 and Appena.. , of Title 10, Part 50, of the Code of Federal Regulations. The Plan shall be implemented whenever an emergency situation is indicated as defined in Section 2.0 Emergency Classifications. Radiological emergencies can vary in severity from the occurrence of an abnormal event, such as a minor fire with no radiological health consequences, to nuclear accidents having substantial on-site and/or off-site consequences. j in addition to emergencies involving a release of radioactive materials, events such as security threats or breaches, fires, electrical system disturbances, and natural phenomena that have the potential for involving radioactive materials are included in the Plan. Other types of emergencies that do not have a potential for involving radioactive materials are not included in the Plan. The activities and responsibilities of outside agencies providing an emergency response role at the Brunswick plant are summarized in Appendix C and in the state's Emergency Plan. i 1 1 v OERP Rev.53 1-4 l l' L
1.3
SUMMARY
OF EMERGENCY PROGRAM m The Brunswick radiological emergency program consists of the Brunswick
. Radiological Emergency Plan and its implementing procedures. The Plan provides the basis for performing advance planning and for defining specific requirements and commitments to be implemented by other documents and procedures. The Brunswick plant procedures provide the detailed actions and instructions that will be required to implement the Plan in the event of an emergency. The Plan and its implementing procedures are briefly described below.
1.3.1 Concept of Operations The Brunswick Radiological Emergency Plan describes the general nature of emergency response activities, the available emergency response resources and facilities, and the means for maintaining emergency preparedness. Specific plant implementing procedures have been developed (or existing ones modified) to describe in detail how involved plant and corporate personnel carry out their specific responsibilities as identified in the Plan. 1.3.1.1 Emergency Response Activities The first step in responding to an emergency is recognizing and classifying the naturc of the emergency. In order to standardize this process, the four emergency classifications described in NUREG-0654' a e adopted for use in this plan. Each class of emergency (U.1 usual Event, Alert, Site Area Emergency, and General Emergency) encompasses a predefined set of increasingly severe circumstances, including plant conditions, instrument readings, and effectiveness of in-plant corrective actions, known as Emergency Action Levels. The process of properly classifying an emergency is important because the subsequent response activities are dependent on the severity of the emergency. l V ) OERP- Rev.53 1-5 L
g The next st p is to notify (and activate as conditions warrant) the proper emergency organizations, both inside !m and outside CP&L. Proper integration of the efforts of the various response organizations is important to prevent omission or unnecessary duplication of key activities. Therefore, the emergency plan identifies in terms of information flow and commun'ications links the interfaces between pertinent organizations, and identifies the role each is to perform. The emergency response measures to be taken by CP&L are discussed in detail in ths Plan, while those taken by the state and local governments are
.{
summarized herein with details provided in the North Carolina State Emergency Plan. Beyond the process of notification and activation of support 3 groups, a variety of efforts must be made to assess and minimize the consequences of an emergency condition. These efforts include estimates of the radiation exposures that may occur to plant and off-site personnelif the emergency is not brought quickly under control. Such
- estimates can be used to initiate preplanned protective actions. The decisions on protective actions off site, such as taking shelter or evacuation, are the responsibility of state and local authorities. The Plan provides for technical l-assessments of the course and consequences of the s emergency and the means for providing state and local
- agencies with adequate information upon which to make their decisions. Emergency response activities also include personnel accountability, search and rescue, first aid, personnel decontamination, fire fighting, and damage control.
The final step is to declare the emergency over and l l perform any necessary post-accident recovery activities. The Plan describes post-accident recovery provisions and identifies the transition from the emergency phase to the recovery phase. l i { l
.a OERP Rev.53 1-6 L
p p 1.3.1.2 Emergsncy Responso Resources 1 Ln The emergency response resources available to respond to j an emergency consist of the personnel at Corporate j Headquarters, at other CP&L facilities, and, in the longer term, at organizations involved in the nuclear industry. The first line of defense in responding to an emergency lies with the normal operating shift on duty when the emergency begins. Therefore, members of the Brunswick staff are assigned defined emergency response roles that are to be assumed whenever an emergency is declared. The overall management of the emergency is normally performed by the Shift Superintendent until relieved by the on-call Site Emergency Coordinator. Because of his overall knowledge, he is best able to bring the full resources of the plant to bear on controlling the emergency. On-site i personnel have preassigned roles to support the Site Emergency Coordinator and to implement his directives. These roles, for the purpose of emergency planning, are cast in terms of emergency teams and assignments, each having a designated leader or primary person and alternate (s) assigned to it. Each team and individual assignment carries with it specific emergency response duties and, where practical, each is
- provided with an on-shift person to perform those duties on an interim basis. This approach ensures under most conditions that an emergency response duty falls under some predesignated position and provides a smooth transition as additional people are called to the plant, since each one knows ahead of time what his area of responsibilities will be. The Site Emergency Coordinator will also have ready access to the Technical Support Center. This Emergency Facility is comprised of personnel who are knowledgeable of and responsible for engineering )
~
and management support. It will assemble shortly after an Alert, Site Area Emergency, or General Emergency is declared in order to assist the Site Emergency Coordinator and to carry out his directives. I-O OERP Rev 53 1-7 { u.
y I f Upon d:claration of an Alert, Sita Area Emergency, General Emergency, or at the discretion of the Site ,m Emergency Coordinator, the Emergency Operations Facility will be activated and staffed by personnel under the direction of the Emergency Response Manager. The position of Emergency Response Manager is staffed by qualified senior plant management personnel. Once the Emergency Operations Facility has been fully activated, the Emergency Response Manager will be responsible for all i off-site emergency response including radiological and environmental assessment, determination of recommended l public protective actions, and coordination of emergency response activities with federal, state, and local agencies. The Emergency Response Manager will manage the corporate response activities, to relieve the Brunswick plant personnel of any activities that could hamper their response efforts, and to marshall the corporate resources needed to properly respond to the emergency. ' CP&L has a staff of well-trained and experienced engineers, scientists, and technicians. These personnel represent a pool of technical expertise which can be called upon to provide additional support to the emergency response and recovery organizations. CP&L personnel will staff a near-site Joint Information Center to interface with the media and general public in order to effectively communicate to the public the nature of an emergency in progress. Available to assist the Brunswick plant in responding to an emergency are CP&L personnel assigned to the Shearon Harris and Robinson nuclear plants and the Corporate Offices. In addition as outlined in Appendix C, CP&L has arranged for support from outside CP&L in the areas of fire fighting, rescue and medical assistance, as well as that support delineated in the state and local emergency plans. Assistance may also be available from the Nuclear Regulatory Commission, Federal Emergency Management Agency, Department of Energy, and General Electric. The , industry resources identified by INPO are also available. l CP&L is a signatory to the mutual assistance agreement developed by INPO for utilities in the nuclear power industry. l l l 1 0ERP Rev.53 1-8 i
1.3.1.3 Em:rg:ncy Responsa Faciliti:s m Special provisions have been made to assure that ample space and proper equipment are available to effectively respond to the full range of possible emergencies. The emergency facilities available include the Brunswick plant Control Room, Operational Support Center, Technical Support Center, Emergency Operations Facility, and Joint Information Center. Each of these facilities, as we'! as the North Carolina Emergency Operations Center, the Brunswick County Emergency Operations Center, and the New Hanover County Emergency Operations Center, are described in Section 5, Emergency Facilities and Equipment. 1.3.1.4 Emergency Response Plan Maintenance The Plan, as described in Section 6, provides for maintenance of emergency preparedness by establishing the framework and requirements for training, drills and exercises, and periodic updating. Each Brunswick employee having an emergency response role is trained, and annually retrained, in his area of responsibility and also how his duties fit in with those of others. Each individual must know what is expected of him and what he should expect of others while responding to an emergency. A basic description of the recjuired training for e'mergency assignment is provided in the Plan. The effectiveness of such training is gauged by the use of drills and exercises. Drills are supervised instruction periods aimed at developing, maintaining, and testing skills in a specific operation such as communications or radiation monitoring. An exercise tests the overall capability of the integrated plant, state, and local emergency organizations to properly respond to an emergency. The Plan sets forth the i frequency and content of such drills and exercises and also establishes how lessons learned will be used to improve I the Plan. j l l l 1 i OERP Rev.53 1-9l l 1 4
Tha Pl n clso delin:ct:s tha requirem:nts for revi: wing, updating, and auditing the Plan and for performing m maintenance on and taking inventories of emergency equipment and supplies. An Emergency Planning Coordinator is designated to be responsible for overseeing this process as outlined in Section 6.2. 1.4 BRUNSWICK PLANT EMERGENCY PROCEDURES Plant Emergency Procedures (PEP's) are implementing procedures which define the specific (i.e., step-by-step) actions to be followed in order to recognize, assess, and correct an emergency condition and to mitigate its consequences. Procedures to implement the Plan have been developed or existing procedures modified to provide the following information:
- 1. Specific instructions to the plant operating staff for the implementation of the Plan.
- 2. Specific authorities and responsibilities of p,lant operating personnel.
- 3. A source of pertinent information, forms, and data to ensure prompt actiorrs are taken and that proper notifications and communications are carried out.
-- 4. A record of the completed actions.
- 5. The mechanism by which emergency' preparedness will be maintained at all times.
1.5 DEFINITIONS Accident - Any unforeseen, or unintentional occurrence or mishap resulting in, or potentially resulting in, physical injury or injury due to radiation exposure or excessive exposure to radioactive materials. Activated - To formally put on active duty with the necessary personnel and equipment to carry out the function required. l l l 1 v I OERP Rev.53 1-10
' Activatina - Key personnel are responding as a mandatory step to make the facility operational within the required time.
Corrective Actions - Those emergency measures taken to lessen or terminate an emergency situation at or near the source of the problem, to prevent an uncontrolled release of radioactive material, or to reduce the magnitude of a release (e.g., equipment shutdown, fire fighting, repair, and damage control.) Emeraency Action Levels - Plant conditions used to determine the existence of an emergency and to classify its severity. The conditions include specific instrument readings (e.g., radiation release rates out of a building vent) that may be used as thresholds for initiating emergency measures such as ) initiating a notification procedure. Emeraency Classification - The characterization of emergency situations consisting of several groupings including the entire spectrum of possible radiological emergencies. The four classes of emergencies, listed in order of increasing severity (and decreasing probability), are (1) Unusual Event, (2) Alert, (3) Site Area Emergency, and (4) General Emergency. Emeraency Instructions - Specific procedures that provide step-by-step i instructions to guide plant operations during potential or actual emergency situations. j
-- Emeraency Operations Centers - Designated facilities designed and
, equipped for effective coordination and control of emergency operations carried out within an organization's jurisdicti'on. Emeraency Operations Facility (EOF) - An on-site support facility for the management of overall licensee emergency response including coordination with federal, state, and local officials, coordination of off-site radiological and environmental assessment, and determination of recommended public protective actions. The EOF is located in the TSC/ EOF / Training Building. Emeraency Plannina Zones (EPZ)- A generic area defined about a nuclear plant to facilitate emergency planning off site. The plume exposure EPZ is described as an area with a 10-mile radius and the ingestion exposure EPZ l is described as an area with a 50-mile radius in NUREG-0654. (See j l Figure 1.1-7) ) l v OERP Rev.53 1-11 ! l
Exclusion Arna - Carolina Powcr & Light Company-own:d property that surrounds the reactor plants as defined in 10CFR100. The area is of such m size that an individual located at any point on its boundary for two hours immediately following onset of the postulated fission product release would not exceed 25 rem whole body dose or 300 rem thyroid d ase. This is the property boundary used for off-site dose projections. (See Figure 1.1-1) Joint Information Center (JIC)- A nearsite facility equipped and staffed by CP&L, State, County, and Federal Agencies to coordinate the dissemination of information to the news media and general public during an emergency. Inaestion Exoosure Pathway - The potential exposure pathway to the public through consumption of radiologically contaminated water and foods such as milk or fresh vegetables. The basis for planning within the 50-mile EPZ. Mannina - A person is in the facility to respond to incoming calls. Nuclear Incident - An event or series of events, either deliberate er accidental, leading to the release or potential release into the environment of radioactive materials in sufficient quantity to warrant consideration of protective actions. Operational- The facility is executing its designed func* ions and tasks. Operational Support Center (OSC) - The place to which emergency response support personnel report and standby in an emergency situation. The OSC is located in the Operations and Maintenance (O&M) Building. Plume Exposure Pathway - The potential exposure pathway to the public through (a) whole body external exposure from the plume and from deposited materials, and (b) inhalation of radioactive materials. The basis for planning within the 10-mile EPZ. Population-at-Risk - Those persons for whom protective actions are being or would be taken. Projected Dose - An estimate of the potential radiation dose which affected population groups could receive. l l J OERP Rev.53 1-12 l 1 J
r ) Protectid Area - Tha doubla-fsnc d security area with intrusion detection devices immediately surrounding the plant structures. (See Figure 1.1-3.) ! m ^ Protective Action - An activity conducted in response to an incident or potential incident to avoid or reduce radiation dose to members of the public , (sometimes referred to as protective measure). ! Protective Action Guide (PAG) - The projected dose to reference man, or other identified individual, from an accidental release of radioactive material , at which a specific protective action to reduce or avoid that dose is warranted. Radioloaical Emeraency - An off-normal situation that has or may have a radiological impact on the public health and safety. I Recoverv Actions - Those actions taken after an emergency to restore the i Brunswick plant and the surrounding environment as nearly as possible to I its pre-emergency radiological condition. Restricted Area - Any area, access to which is controlled by Carolina Power
& Light Company for purposes of protection of individuals from exposure to i radiation and radioactive materials.
Severe Accident Manaaement Guidelines (SAMGs)- Severe Accident Management Guidelines are entered when Emergency Operating
- Procedures (EOPs) are not able to maintain adequate core cooling.
Staffina - Key personnel are responding to the facilities as a proactive step to prepare for potential operational status. State - The State of North Carolina. Technical Support Center (TSC)- A center outside of the Control Room that supplies information on the status of the plant to those individuals who are knowledgeable or responsible for engineering and management support of reactor operations in the event of an emergency, and to those persons who l are responsible for management of the emergency response. The TSC is located in the TSC/ EOF / Training Building. Unrestricted Area - Any area to which access is not controlled by the licensee for protecting individuals from exposure to radiation and radioactive l materials, and any area used for residential quarters.
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ESE-i4348I l 2 l SW SE l1221 1 SSW I 2 I S I1716I ' I1175 I POPULATION TOTALS e$$a M PE^K POP RlN u RING MILES POPUtA ION TOTAL MILES hhglTf A 2078 5406 B 1254 3006 0-2 1362 0-2 1362 25- 3813 0-5 5175 D 5099 35851 5-10 14170 0 10 19345 E 1267 1614 F 1520 2140 Total S m ent opulation G 525 774 19345 H 154 1134 K 6471 78513 TOTALS 19345 132367 BRUNSWICK SITE 3,,y,,,,,,,,., PLUME EXPOSURE PATHWAY I 10 Mile Emergency Planning Zone j
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.. .i
e Nr - BRUNSWICK NUCLEAR PLANT
$; RADIOLOGICAL EMERGENCY PLANI A
'2.0 ' EMERGENCY CLASSIFICATIONS l ~ A key element'of this Plan is a preplanned system of notifying and activating' -
various emergency response organizations. This system, in accordance with '
' NRC recommendations, uses graded levels of emergency response where the
~
actions specified are organized according to the general severity of the emergency condition. This section discusses the criteria for determining the level of the emergency i
- condition.!It also illustrates how a decision is made to declare that an emergency exists by providing example initiating conditions that could correspond to each' emergency class. Section 3 in turn will discuss the plans for notification of off-site
' agencies and mobilization of emergency teams and how they may vary with the .
~
level of the emergency. 2.1 GENERAL CLASSIFICATION SYSTEM L The operating staff is provided formal training to recognize and respond in a - logical manner to off-normal plant conditions. Plant abnormal and emergency instructions are designed to allow plant personnel to mitigate the consequences of and correct an off-normal condition as quickly as possible.
; following its occurrence. The procedures identify the conditions requiring
-_. implementation of this Plan._ Figure 2.0-1 shows the basic response
- sequence that is followed during any off-normal condition.
The types of potential emergencies vary in probability and consequences. Accordingly, any system that categorizes emergencies must be both wide-ranged and flexible. This Plan adopts the NRC recommended -
. standard of four general classes of emergencies and, as described below, l includes the methods for determining the class in which a specific type of event should be placed.
I l l a
, OERP Rev.53 2-1
i Thara cro three basic t:sts or crit:ris that must be considered in daciding ! which emergency class exists. These are: l m 1
- 1. Radioactivity release: Is a release occurring; and if so, what is its magnitude?
)
2, Core damaae: If no release to the environment is occurring, has there been a release of fission products from the fuel? Do the radiation levels in the coolant system or primary containment pose a potential danger to the public? '
- 3. Plant dearadation: Has the plant responded to equipment failures or external events as designed? If the plant has not j responded as expected, what is the prognosis for a safe recovery, or alternately that further degradation will occur (e.g., corrective action is ,
not likely to be successful or cannot be accomplished before a major l release occurs)? i 1 l The categorization of events and combinations of events according to one of the four emergency classes is implemented through Emergency Action Levels (EALs). These are specific sets of plant conditions, instrument readings, and events which, unless promptly corrected, coincide with the conditions associated with one of the four emergency classes. i EALs for the Brunswick Nuclear Plant are included as an attachment to the s Radiological Emergency Response Plan and are provided in OPEP-02.1, Initial Emergency Actions. The EALs have been selected with a view towards ensuring that a reasonable time is available'to diagnose the specific cause of the emergency and attempt immediate corrective actions. Once an emergency is declared, assessments of core and containment conditions, projected releases, and resultant exposures are performed. The results, along with other plant status assessments, are reported to off-site agency officials who decide, based on these inputs, whether or not I protective actions for the public are to be implemented. The relationship of dose assessment values to the Environmental Protection Agency (EPA) Protective Action Guides (PAGs), and the possibility of approaching or exceeding the PAGs, will specifically be reported. Section 4 describes the relationships between emergency classes, PAGs, and various emergency measures. Each of the four emergency classes are discussed below. l a OERP Rev.53 2-2
2.2 UNUSUAL EVENT 1 m Unusual events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant. ; Determination of an Unusual Event (or any emergency condition) may be accomplished in one or more of the following ways:
. Observations / inspections
. Automatic alarms (e.g., Radiation and Process Monitoring Systems)
I
. Communications from others (e.g., warnings of severe natural i phenomena by the National Weather Service) i l
As in all cases, the Site Emergency Coordinator will declare an Unusual j Event in any circumstance where, in his judgment, the status of the plant l warrants it. Initiating conditions are established as EALs for the determination of this class. Specific EALs for an Unusual Event are listed in i OPEP-02.1, Initial Emergency Actions. An Unusual Event does not require the activation of the entire on-site I emergency organization, but the Site Emergency Coordinator can direct that additional personnel come to the site to support shift workers. Off-site emergency organizations shall be notified as necessary for informational purposes and aid from off-site fire fighting, medical services, and security , organizations can be requested. Notificatichs are discussed in Section 3.9, j and emergency measures to be taken are described in Section 4. Specific emergency actions to be followed during an Unusual Event are contained in OPEP-02.1.1, Emergency Control- Notification of Unusual Event, Alert Site Area Emergency, General Emergency. 2.3 ALERT Events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Initiating conditions are established as EALs for determination of an Alert and are listed in OPEP-02.1, Initial Emergency Actions. Additionally, the Site Emergency Coordinator will declare an Alert whenever he concludes that plant conditions so warrant. l l OERP Rev. 53 2-3
Ev:nts in this class may rafl:ct a significant d: gradation in the safety of the . reactor. However, releases from such events will be small. Off-site I m mobilization and assessment actions will be initiated to ensure that emergency personnel are readily available to respond if situations become more serious and confirm that radiation levels in the environment do not require protective actions off-site. Notifications and activation of emergency i organizations are discussed in Section 3.9, and the emergency measures to I be taken are described in Section 4. Specific emergency actions to be i followed during an Alert are contained in OPEP-02.1.1, Emergency Control- j Notification of Unusual Event, Alert, Site Area Emergency, General i Emergency. 2.4 SITE AREA EMERGENCY Events are in progress or have occurred which involve actual or likely major j failures of plant functions needed for protection of the public. I initiating conditions are established as EALs for determination of the Site ! Area Emergency class and are listed in OPEP-02.1, Initial Emergency Actions. Additionally, the Site Emergency Coordinator will declare a Site ! Area Emergency whenever he concludes that plant conditions so warrant. The Site Area Emergency class includes Alert conditions where the plant personnel have been initially unsuccessful in restoring the facility to a safe shutdown condition. It also includes Alert conditions where subsequent ; additional malfunctions have occurred. The Site Area Emergency class is more severe than the Alert class because significant radiation releases may occur. However, most of the initiating conditions associated with the Site Area Emergency class do not result in an immediate release and may never result in a significant release if emergency repairs are successful. Although immediate protective actions are not automatically required, declaration of a Site Area Emergency will set into motion all personnel on site and off site that would be required to perform actions up to and including the evacuation of a near-site area. If circumstances warrant, the process of public notification may begin as directed by the state plan. Section 3.9 discusses the planned process of notification and activation of emergency organizations. Emergency measures to be taken are described in Section 4. Specific emergency actions to be followed during a Site Area 1 Emergency are contained in OPEP-02.1.1, Emergency Control- Notification of Unusual Event, Alert, Site Area Emergency, General Emergency.
}
l l 1 a ! i OERP Rev.53 2-4 l I
l 2.5 GENERAL EMERGENCY m' Events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. L Initiating conditions predictive of a major radiological release are established i as Emergency Action Levels for determination of the General Emergency class and are listed in OPEP-02.1, Initial Emergency Actions. Additionally,- I j the Site Emergency Coordinator will declare a General Emergency l whenever, in his judgment, conditions exist that warrant activation of l emergency response efforts including off-site monitoring and prompt public notification. l The General Emergency class includes accident conditions that involve I severe core damage or melting. Such conditions will result in major releases to the primary containment and extremely high levels of contamination in the reactor coolant. Releases to the environment may be kept low unless leak paths in the primary containment develop (as from containment failure or failures in pumps, valves and other equipment which circulate reactor coolant outside primary containment). If major releases do occur, it is probable that they will occur hours to days after the onset of the emergency and that off-site exposures will approach or exceed EPA recommended protective action guides unless protective measures are instituted. ; l Notifications and activation of emergency organizations are discussed in l . Section 3.9. The emergency measures to be taken are described in l Section 4. Specific emergency actions to be followed during a General Emergency are contained in OPEP-02.1.1, Emergency Control - Notification of Unusual Event, Alert, Site Area Emergency, General Emergency. I t i i l f a OERP Rev.53 2-5 i
)
b THE SHIFT SUPERINTENDENT Event I /). LEARNS OF AN OFF. NORMAL Occurs - W,m CONDITION. DETERMINED BY li4 INSTRUMENT READINGS OR
- OBSERVATION. SHIFT r SUPERINTENDENT IMPLEMENTS l OPEP-02.1, WHICH FLOWS AS Venfy proper procedures are being followed i ak Personnel i Injunes or NO Contamination YES Implement OPEP-03 9 2 and OPEP-03 9 3 as necessary Fire?
NO YES Notify the Fire Bngade m NO EAL Exceeded?. YES Implem&nt Appropriate Plant Emergency Procedure PEP-o211 ,, ir Event NO Over? YES ) Terminate OPEP-02.1 Figure 2.0-1 l Response Sequence to Off-Normal Conditions v OERP Rev.53 2-6 1 p.
y l BRUNSWICK NUCLEAR' PLANT ' l RADIOLOGICAL EMERGENCY PLAN In , 3.0 EMERGENCY RESPONSE ORGANIZATION l l There are requirements for action in an emergency that go beyond those encountered during routine operations.' To meet these extra demands and provide an effective response to the emergency, the Brunswick Radiological Emergency Plan employs an organizational concept that has four features.
- 1. ' Whenever the Plan is activated (i.e., an EAL is exceeded), a single individual is charged with the responsibility for and authority to direct all actions necessary to respond to the emergency.
- 2. The primary responsibility of the individual in charge is to assure that all critical actions (emergency response functions) are carried out. Upon activation of the Plan, he is freed of all other responsibilities and thus able to devote his entire effort to managing the emergency response.
- 3. Specific individuals are assigned the responsibility of carrying out predefined critical actions.
- 4. There is a mechanism established to provide additional resources as necessary to respond to the emerge v vihich provides continuity of response on each critical action.
This concept of organization is compatible with and integrated into the normal I mode of operation. There are a number of procedures to guide operators in responding to equipment malfunctions and instrument alarms. There are also procedures to maintain effective control over contamination and radiation exposures. Emergency procedures basically involve an extension of these existing plant procedures. Organizational control of emergencies is accomplished in several steps. First, as is discussed in Section 2, conditions associated with the various emergency. classes are clearly defined. Second, emergency response functions are specified
.with levels of action appropriate to each emergency class (e.g., notification, off-site radiation monitoring, etc.). Third, individuals are assigned to be responsible for carrying out each emergency response function, with the assignments to cover all phases of the emergency-from its initial declaration to the final recovery operations.
I OERP Rev.53 3-1
m, Finally, tha position of Sits Em:rg:ncy Coordinator is established to b3 activatnd immediately on declaration of an emergency. ' To that individual is delegated the m immediate and unilateral authority to act on behalf of the Company to manage and direct all emergency operations involving the facility, Upon activation of the EOF, the Emergency Response Manager assumes responsibility of overall emergency response and performs those requirements for all off-site related
- activities. The Site Emergency Coordinator maintains overall on-site emergency response responsibilities and reports to the Emergency Response Manager.
Initially the Site Emergency Coordinator would be the Operations Shift Superintendent.' He would act in that capacity until formally relieved by the designated On-Call Site Emergency Coordinator or his alternate (qualified SECS are listed in OPEP-Appendix-A) in the Technical Support Center. In this manner, the individual usually in charge of activities in the Control Room is responsible for initiating the necessary emergency response, but the emergency response organization On-Call SEC is expected to assume management of the emergency response as soon as he is available to do so--in anticipation of the possible wide-ranging responsibilities associated with managing a major emergency. This section of the plan delineates the various emergency actions and separates them into groups of related functions. These functions are then assigned to designated emergency response personnel who are responsible to the Site Emergency Coordinator for the performance of the activities required to fulfill those functions.
-- Upon the declaration of an emergency, specified on-shift personnel assume the responsibility for performing the required emergency response actions until properly relieved by another emergency responss organization member qualified for the position. All emergency response organization members are trained as ;
. described in Section 6.1.1.
If necessary, the Site Emergency Coordinator will allocate available resources l based on existing plant conditions. Where necessary, additional personnel will be notified and requested to augment on-site personnel. v OERP Rev.53 3-2 l
A curr:nt call list of em:rg:ncy r:sponsa org:nization m::mb:rs_is m:intained in the Control Room and procedures are available to make this notification. Since ; n many of the Brunswick plant management staff and substantial numbers ofits support personnellive in the site vicinity (i.e., Southport and surrounding areas) additional assistance can be quickly provided. 3.1 NORMAL OPERATING ORGANIZATION The greatest number of people on site occurs during day shift operations. The plant crew available to respond to an emergency provides a broad spectrum of specialties including operations, maintenance, engineering, radiochemistry, health physics, fire protection and security. The Plan, as will i be discussed, utilizes the basic plant organizational structure and cadre of available manpower as the principal means of responding to an emergency condition. This is accomplished by assigning the management of various emergency response functions to individuals in accordance with their routine operational responsibilities. To illustrate, Radiological Emergency Teams will be directed by Environmental & Radiation Control, management personnel, who are the individuals responsible for directing day-to-day radiation control programs. In the event of an emergency, they report directly to the Site Emergency Coordinator and continue to be responsible for radiological matters.- There are, of course, times when the full complement of staff is unavailable, just as there are times when one or a few key supervisory officials are away
- from the plant. Therefore, the shift organization as described in the Administrative Controls section of the BNP Technical Specifications must be prepared to provide the initial response to a'n emergency. The following on-shift expertise will be maintained 24 hours per day:
Each operating shift will normally consist of a Shift Superintendent, two Senior Control Operators, four Control Operators, seven Auxiliary i Operators, three Health Physics Technicians, one Chemistry Technician, and one Shift Technical Advisor (STA). Deviation from the normal shift complement is allowed as long as the minimum shift complement, as ; described in Technical Specification 5.2.2.c and UFSAR Table 13.1.2-1, is maintained and appropriate action is taken (see Figure 3.1-1). l 1 i
,s OEPP Rev.53 3-3 i
l
r l l As will b3 d scrib:d bslow, tha general approach is to assign all necessary l emergency response functions to the individuals on site. Each individual, on o declaration of an emergency, would be responsible for carrying out one or more emergency actions until additional personnel arrive on site. It should be noted that they are initially responsible under all circumstances, and remain so until relieved. This arrangement provides for a clear and uniform assignment of responsibility and provides a mechanism to assure that all I important emergency response functions are dealt with from the very beginning of the accident. 3.2 - ON-SITE EMERGENCY ORGANIZATION The minimum on-site emergency organization for non-normal working hours, backshifts, and holidays for the Brunswick Plant is described above in Section 3.1. Compliance with the requirements of NUREG 0654 Table B-1 has been assured. Guidance for augmenting the emergency organization is found in the notification checklists of the plant emergency procedures. Individuals' names and roles in the emergency organization, phone numbers, and alternates are also described in the plant emergency procedures. OPEP-Appendix A lists the individuals and alternates qualified to fill the positions described for the TSC, OSC, and EOF. The Company is committed to provide staffing to effectively contain any emergency which might occur at its nuclear facilities. Depending on the emergency at hand, personnel will be contacted with required expertise on a priority basis. Since a large portion of the Brunswick staff lives in the vicinity of the plant, additional personnel will be available for communications, on-site and off-site Radiological assessment, repair and corrective actions and technical support within a short period of time. Depending on weather conditions,30-45 minutes should provide enough time to make the ! appropriate staff available to augment the on-site organization. The on-site organization will continue to be augmented such that within 60-75 minutes after notification, additional personnel will be added to provide the necessary support and will meet the intent of Table B-1 of NUREG 0654. Additional personnel will continue to supplement the plant emergency organization as necessary to meet the requirements of this Plan. Periodic drills will be conducted to determine that this augmentation schedule can be maintained. 1 l s-OERP Rev.53 3-4 l
p l
'As an aid toward assuring that critical emnrgency actions are given propar attention, the plant's emergency procedures provide for emergency m response personnel established to carry out specific types of functions such I as accident assessment and off-site notification. As discussed below, emergency response organization personnel have been selected with an aim toward making a smooth and rapid transition to the emergency mode of operation. The Emergency Response Organization is shown in Figures 3.2-1 and 3.4-1.
The functions specifically assigned to each element of the Emergency Response Organization are intended to encompass all critical response functions, from command and control to communications. One function assigned to each is that of record keeping. Typical of the records to be maintained are the emergency communications, the radiation records, (i.e., surveys, projected dose calculations, personnel / population-at-risk evacuations, etc.), the sequence of events (i.e., the managerial decisions and essential occurrences that evolve throughout the emergency), and the security / accountability records (i.e., who is presently on each team or at each center and any security threats). The following sections describe the specific emergency assignments, which are in the Plan's implementing procedures. The Emergency Response Organization personnel telephone numbers are available in the Control Room. In all emergencies, the on-duty Shift Superintendent is authorized and qualified to implement the Plan and to classify the emergency condition. m ..- 3.2.1 Site Emergency Coordinator As discussed in Section 3.1, direction and coordination of emergency actions on-site (and off-site until relieved by the Emergency Response Manager) are prime responsibilities of the Site Emergency Coordinator. The initial determination that an emergency exists will be made in the Control Room, based on measured plant parameters. Therefore, the Shift Superintendent is initially the Site Emergency Coordinator. If the Shift Superintendent becomes incapacitated for any reason, the , Senior Control Operator of the unaffected unit will assume the I responsibilities of the SEC. He will be in command of the on-site emergency organization until relieved by the designated On-Call Site Emergency Coordinator. The Shift Superintendent will be relieved by the first qualified SEC to arrive on site so that he may j devote his attention to plant operations. The Shift Superintendent remains responsible for the decision making of Severe Accident Management Guidelines strategies. Names 4 a OERP Rev 53 3-5 1 L
o and phon 3 numbers of qunlifi:d Sito Em:rgency Coordinators are available in OPEP-Appendix A. He will also appoint an m Emergency Communicator who will relay messages and maintain notification records throughout the emergency. Any individual who may be required to serve, even temporarily, in the capacity of a Site Emergency Coordinator must be qualified and trained in accordance with the training program described in Section 6.1.1. The primary responsibilities of the Site Emergency Coordinator include the following:
- 1. Coordinating and directing the combined activities of Brunswick personnel in the Control Room, Technical Support Center, Operational Support Center, and elsewhere on the site.
- 2. Classifying the emergency.
- 3. Notifying off-site plant, corporate, and local agency personnel, as well as on-site personnel, as delineated in the procedures which implement the Plan. (Upon actuation of the Emergency Operations Facility, the Emergency Response Manager provides liaison between the Site Emergency Coordinator and all off-site agencies.)
- 4. Issuing instructions to eme'rgency response personnel and assuring that the appropriate procedures are being followed.
- 5. Initiating protective actions to be taken on site, if required.
- 6. Determining the advisability of re-entry operations during or immediately following an emergency situation.
- 7. Directing health physics activities until the arrival at the site of the Radiological Control Director.
- 8. Assuring continuity of on-site resources.
- 9. Declaring the emergency over. i l
l 0ERP Rev.53 3-6 1 1
p l' q L - Until relieved by tha Em rgbncy Response Manager, the Site l' Emergency Coordinator may not delegate the responsibility to Lw make the decision to notify and make recommendations to authorities responsible for off-site emergency measures. L Further, while he may consult with others, he may not delegate i_
- the responsibility to upgrade or downgrade the emergency classification or to declare that the emergency has been terminated. He may delegate the responsibility to announce that the emergency has been terminated. . He may delegate the responsibility and authority for mobilization of recovery efforts while that emergency still exists provided that such efforts in no way interfere with or detract from the response to the emergency. (Responsibility for mobilization of recovery efforts transfers to the Emergency Response Manager upon activation of the EOF.)-
Other responsibilities may be delegated to other emergency organizational units as necessary for expeditiously carrying out the requirements of the Plan and procedures which implement the Plan. 3.2.2 Plant Operators During an emergency, the Plant Operators (including the Shift Superintendent) are the nucleus of the initial effort to control the
- plant and take steps to protect the public.
The Plant Operators' primary responsibility is to carry out assigned actions necessary during an emergency to provide initial emergency response per established emergency instructions and perform initial calculations of projected off-site consequences. The Operators are responsible for implementing actions (including Severe Accident Management Guidelines) as directed by the Shift Superintendent. Specific emergency , response duties of the Plant Operators are found in the Plant Emergency Procedures which implement the Plan and in other Operations procedures. 3.3 Technical Support Center The Site Emergency Coordinator, as discussed above, is responsible for 3 managing a wide range of activities at the plant. To assist the Site j Emergency Coordinator in this effort and to implement his directives, a ! Technical Support Center has been established. The Technical Support j Center consists of management-level personnel. Upon declaration of an . L Alert, Site Area Emergency, or General Emergency, the Technical Support i Center will be notified to immediately assemble. The SEC and other TSC l 0ERP Rev.53 3-7
staff m:mb:rs p;rform monitoring and evaluttions required for Severe Accident Management Guidelines, and provide advice and m recommendations to the Shift Superintendent and Control Room Operators. The various technical and administrative functions to be performed at the plant have been grouped into five categories similar to the organization for routine operations. These are as follows: Plant Operations NRC Communications Radiological Control Technical Assessment Security-Directors are assigned to be responsible for activities within each category.
-The Directors within the Tecanical Support Center rnay be relieved by designated qualified plant peisonnel (phone numbers are listed in GPEP-Appendix A).
3.3.1 Plant Operations Director The Plant Operations Director is responsible to the Site Emergency Coordinator for providing liaison with the Control Operators, Shift Superintendent, and Technical Support Center.
- He is responsible for providing technical and administrative j assistance to the Control Operators. This position also performs ;
monitoring and evaluations required for Severe Accident ) Management Guidelines. Responsibilities of this position are ! contained in OPEP-02.6.26, Activation and Operation of the l Technical Support Center. ! 3.3.2 Radiological Control Director ; The Radiological Control Director is responsible to the Site Emergency Coordinator for managing the radiological monitoring and assessment aspects of the plant during an emergency; managing activities to control radiation exposure; providing technical and administrative direction to the Radiological Emergency Teams; and providing liaison with the Emergency l Operations Facility and with the Radiological Control Manager. Responsibilities of this position are contained in OPEP-02.6.26, ActivMion and Operation of the Technical Support Center. l J OERP Rev. 53 3-8
r 3.3.3 Technical Assessm:nt Director N The Technical Assessment Director is responsible to the Site Emergency Coordinator for providing technical and administrative direction to the Accident Assessment Team and for providing liaison with the Technical Analysis Manager after the EOF is activated. The Technical Assessment Director is responsible for performing the monitoring and evaluations required for Severe Accident Management Guidelines. Responsibilities of this position are contained in OPEP-02.6.26, Activation and Operation of the Technical Support Center. 3.3.4 Security Director The Security Force is composed of personnel qualified in security, personnel accountability, and evacuation procedures and practices. The Security Director is responsible to the SEC for providing direction to the Security Force during a declared emergency and providing liaison with the state and local law enforcement agencies. Responsibilities of this position are contained in OPEP-02.6.26, Activation and Operation of the Technical Support Center. 3.3.5 Communications Director The Communications Director in'the TSC reports to the Site Emergency Coordinator. He is responsible to make plant-wide announcements over the Public Address System, ensure NRC notifications are performed, and supervise the administrative staff. Responsibilities of this position are contained in OPEP-02.6.26, Activation and Operation of the Technical Support Center and OPEP-02.6.21, Emergency Communicator. 3.3.6 Radiological Control Communicator The Radiological Control Communicator is responsible to the Radiological Control Director for expediting communications between the director and the Radiological Emergency Teams. The responsibilities and objectives of the Radiological Control Communicator are contained in OPEP-02.6.26, Activation and l Operation of the Technical Support Center. v OERP Rev.53 3-9 l
\
a
1 3.3.7 Accid:nt Ass:ssment Team Lead:r )
^ One of the principal groups housed within the Technical Support q Center is the Accident Assessment Team. The specific responsibilities of the Accident Assessment Team are as follows: ,
A. Analyze mechanical, electrical, instrument and control problems and determine alternate solutions. B. Analyze thermohydraulic and thermohydrodynamic problems and develop alternate courses of action to resolve them. C. Analyze and evaluate accident conditions and develop guidance for the Site Emergency Coordinator and Operations personnel on protection of the core. D. Perform monitoring and evaluations to support Severe I Accident Management Guidelines. The Accident Assessment Team Leader is responsible to the Technical Assessment Director and provides technical and administrative direction to the Accident Assessment Team. 3.4 Opyational Support Center l 3.4.1 Emergency Repair Director The Emergency Repair Director is responsible to the Site Emergency Coordinator for the management of efforts to repair I and maintain equipment during an emergency, install emergency structures, systems and components, and perform mitigation and cleanup activities during an emergency. These responsibilities l include providing technical and administrative direction to any emergency repair team that may be formed during the ! emergency and to the Operational Support Center Mission Coordinator. Responsibilities of this position are contained in OPEP-02.6.12, Activation and Operation of the Operational Support Center. w OERP Rev.53 3-10 l l
m l 3.4.2 Op:: rational Support Cent::r Mission Coordinator m Upon the decision of the Site Emergency Coordinator to activate the Operational Support Center, an OSC Mission Coordinator will report to the Emergency Repair Director. This individual will-direct the activities of the mechtinical, electrical, and I&C personnel requested to report to the OSC. His responsibilities and objectives are contained in OPEP-02.6.12, Activation and Operation of the Operational Support Center. He will coordinate OSC response activities with the E&RC and Operations Coordinators. 3.4.3 - Operations Coordinator Upon the decision of the Site Emergency Coordinator to activate the Operational Support Center, an Operations Coordinator will report to the Emergency Repair Director. This individual will coordinate the activities of operations and Fire Brigade personnel with the OSC Mission Coordinator and E&RC Coordinator. His responsibilities and objectives are contained in OPEP-02.6.12, Activation and Operation of the Operational Support Center. 3.4.4 Environmental & Radiological Control (E&RC) Coordinator Upon the decision of the Site Emergency Coordinator to activate the Operational Support Center, an E&RC Coordinator will report to the Emergency Repair Director. This individual will direct the activities of the radiological controls (HPs) and chemistry personnel requested to report to the OSC. He will coordinate OSC response activities with OSC Mission Coordinator and Operations Coordinator. His responsibilities and objectives are contained in OPEP-02.6.12, Activation and Operation of the Operational Support Center. l ! 1 l l M l OERP Rev. 53 3-11
1 I 3.4.5 Radiological Emtrgency Terms m The Radiological Emergency Teams consist of members of the ! Environmental & Radiation Control organization and of other plant or off-site personnel who have received necessary training. Members of the teams who have not completed such training , may be assigned to tasks in which they assist a qualified team
- l. ' member under his direct guidance.
The general functions of the various Radiological Emergency
- Teams include:
l l 1. Determine and report on-site radiological conditions.
- 2. Determine and report off-site radiological conditions.
- 3. Establish areas to which access should be controlled for the purpose of minimizing personnel exposures.
- 4. Issue protective equipment and personnel gear.
- 5. Personnel decontamination services.
- 6. Determine and maintain records of personnel exposure.
Radiological emergency teams are formed from the pool of I available personnel who assemble in the Operational Support l Center. These teams are in addition to the emergency repair i teams that are formed from the pool of mechanics, electricians,
^
l l' l .-..- and instrument technicians to perform repair missions in the l- plant. 1 - The radiological emergency teams formed are determined by the radiological conditions that require their services. The following teams may be necessary: !
- 1. Plant Monitoring - responsible for conducting i in-plant and inside the protected area monitoring to include ;
air sampling, direct radiation monitoring, and smear surveys to determine radiological conditions. l l l ly OERP Rev.53 3-12 l
^
- 2. Post Accident Sampla - rcsponsibla for obtaining
.. and analyzing highly radioactive gas and/or liquid samples m ' necessary for source term determination and core damage assessment. 3.' Personnel Protection and Decontamination - responsible for monitoring and verifying that personnel and vehicles exiting the protected area and the site are free of radioactive contamination. 3.4.6 Fire Brigade When conditions require activation of the emergency facilities, the on-shift Fire Brigade is incorporated into the Operational Support Center. The Fire Brigade consists of a Shift incident Commander and a minimum of four fire brigade members who provide fire brigade, first aid, search and rescue, chemical / hazardous materials response, and confined space entry services. Fire Brigade members will be the on-shift operators, E&RC, or maintenance personnel qualified as Fire Brigade members, The Fire Brigade, when incorporated into the OSC, functions as a team under the ! direction of the Operations Coordinator. The Fire Brigade is ! staffed on a 24-hour basis. I j 3.5 Emergency Operations Facility ' The Emergency Operations Facility is activated by the On-Call Emergency Response Manager when he is notified by the Site Emergency Coordinator that an Alert or higher emergency condition exists at Brunswick. Guidance ; for activation and operation of the EOF is contained in OPEP-02.6.27, { Activation and Operation of the Emergency Operations Facility. ! l i 3.5.1 Emergency Response Manager l The Emergency Response Manager is responsible for providing I liaison between the Site Emergency Coordinator and off-site support personnel (Corporate Headquarters, Joint Information
- Center, state and federal agencies) and marshalling off-site l l support as required to support the Site Emergency Coordinator.
L The responsibilities and ~ objectives of this position are contained ! in OPEP-02.6.27, Activation and Operation of the Emergency Operations Facility.
.u OERP Rev.53 3-13 h:
i
7 3.5.2 Administrativa and Logistics Man::gsr !A The Administrative and Logistics Manager is responsible to the Emergency Response Manager for providing assistance to the Emergency Response Manager and site personnel in administrative, logistics, communications, and personnel support, , as requested. The responsibilities and objectives of this position are contained in OPEP-02.6.27, Activation and Operation of the Emergency Operations Facility. 3.5.3 Technical Analysis Manager The Technical Analysis Manager is responsible to the Emergency Response Manager for coordinating technical information coming from the Technical Support Center, supplying the Emergency Response Manager with an assessment of the emergency, and providing interface for the Emergency Response Manager to consultants, regulatory agencies, architect-engineers, and General Electric. The responsibilities and objectives of this position are contained in OPEP-02.6.27, Activation and Operation of the Emergency Operations Facility. 3.5.4 Radiological Control Manager The Radiological Control Manager is responsible to the Emergency Response Manager for coordinating off-site radiological and environmental assessment and recommending to the Emergency Response Ma' nager protective actions necessary to protect the public health and safety. The responsibilities and objectives of this position are contained in OPEP-02.6.27,' Activation and Operation of the Emergency Operations Facility. i i i a OERP Rev.53 3-14
I l i i l 3.5.5 Environm::ntal Monitoring Team Leader m The Environmental Monitoring Team Leader is responsible to the Radiological Control Manager when the EOF is activated, for j providing technical and administrative direction to the ' Environmental Monitoring Team. Two Environmental Monitoring Teams will be made available for deployment, if additional monitoring teams are needed, they may be requested from the Shearon Harris Plant or the H. B. Robinson Plant. The responsibilities and objectives of the environmental monitoring team are contained in OPEP-02.6.6, Environmental Monitoring i Team Leader. 1 3.5.6 Dose Projection Coordinator 1 The Dose Projection Coordinator is responsible to the l Radiological Control Manager and provides technical and I administrative direction to the Dose Projection Team when the EOF is activated. Responsibilities of the Dose Projection Team include radiological dose projections and source term j determination, contained in OPEP-03.4.7, Automation of Off-Site Dose Projection Procedures, and acquisition and distribution of meteorological data for dose assessment and environmental monitoring purposes. The responsibilities and objectives of the Dose Projection Team are contained in OPEP-02.6.20, Dose Projection Coordinator. 3.5.7 Communications Manager l The Communications Manager reports to the Emergency Response Manager. He functions as liaison between the off-site organizations and agencies and the on-site emergency organization. Specifically, he relays messages between the ERM in the EOF, Technical Support Center, and the State Emergency Response Team, using the communication equipment discussed in Appendix A of this plan. The responsibilities of this position are contained in OPEP-02.6.21, 1 Emergency Communicator. 1 w OERP Rev.53 3-15 l 1
p l 3.5.8 ' Assistant to tha Em:rgency Responso Managar (AERM) lA The Assistant to the Emergency Response Manager is j responsible to the Emergency Response Manager for L coordination of information within the Emergency Operations Facility. Reporting to the Assistant AERM are County EOC Representatives (utility representative) that respond to the New Hanover and Brunswick County EOCs. The responsibilities of this position are contained in OPEP-02.6.27, Activation and l Operation of the Emergency Operations Facility. 3.6 Joint Information Center ! The Joint Information Center is activated by the Emergency Response Manager when he is notified that a Site Area Emergency or General Emergency condition exists at Brunswick. Activation is discretionary for lesser emergency classifications. (Fig. 3.6.1) 3.6.1 Company Spokesperson The Company Spokesperson is responsible to the Emergency Response Manager for the coordination of plant information with County, State, and Federal representatives for dissemination to the news media and general public. The responsibilities of this position are contained in OPEP-02.6.29, Activation and Operation of the Joint Information Center (JIC). 3.6.2 JIC Director The JIC Director is responsible to the Company Spokesperson as the primary interface with State, County, and Federal Public information Coordinators and for the preparation and coordination of all news releases. The responsibilities of this position are contained in OPEP-02.6.29, Activation and Operation of the Joint Information Center (JIC). I i OERP Rev. 53 3-16 l L_.
3.6.3 Company Technical Spokesp:rson m ~ The Company Tecnnical Spokesperson is responsible to the JIC Director for the acquisition, coordination, and interpretation of plant technical information disseminated to the news media and
' general public. The responsibilities of this position are contained in OPEP-02.6.29, Activation and Operation of the Joint information Center (JIC).
3.6.4 - Administrative Coordinator Administrative Coordinators are responsible to the JIC Director for initial JIC facility setup, and the coordination of logistical, security, and administrative duties. The responsibilities of this position are contained in OPEP-02.6.29, Activation and Operation of the Joint Information Center (JIC). 3.6.5 Public Information Director Public Information Directors are responsible to the JIC Director for monitoring and coordinating the flow of media and general public information in the Joint Information Center. The responsibilities of this position are contained in OPEP-02.6.29, Activation and Operation of the Joint Information Center (JIC). l l l l 1 l l -v i OERP- Rev.53 3-17
.- ) . ,
i
- 3.7 OFFSITE ORGANIZATION ASSISTANCE
- A Should conditions at the plant degrade to the extent that further on-site
- assistance is needed, assistance is available from Corporate personnel, contracted services, and certain locally available service groups, as described in the following subsections.
q 3.7.1 Contracted Services A number of active outside contracts are rnaintained in order to ensure continuing access to qualified personnel when and if they are needed to supplement CP&L resources. These contracts provide the capability of obtaining, on an expedited basis, additional maintenance support personnel (such as mechai 1, electricians, and l&C Technicians), other technical personnel i
'(such as E&RC Technicians), and engineering and consulting services. For example, contracts are maintained with General Electric (the NSSS vendor and architect-engineer for the Brunswick plant).
General Electric will form a Technical Support Team upon request. The team will be composed of personnel with the appropriate technical disciplines, that can be dispatched to the ! plant site. General Electric will also establish dedicated telephone communications for data transmission until the arrival
. of the team.
Babcock and Wilcox (B&W) will (naintain its Radiochemistry q Laboratory and Nuclear Counting Room in a state of availability j that will permit the analysis of post accident samples. ) The Institute of Nuclear Power Operations (INPO) serves as a clearinghouse for industry wide support during an emergency. When notified of an emergency situation at a nuclear plant, INPO will provide emergency response as requested. INPO will be able to provide the following emergency support functions:
- a. Assistance to the affected utility in locating sources of emergency manpower and equipment. j 1
I-v OERP Rev.53 3-18
- b. Analysis of tha op: rational asp:: cts of tha incident.
tm c. Dissemination to member utilities of information concerning the incident.
- d. Organization of industry experts who could advise on technical matters.
If requested, one or more suitably qualified members of the INPO staff will report to the Emergency Response Manager and will assist in coordinating INPO's response to the emergency. 3.7.2 Local Services Support The Brunswick Plant is equipped and staffed to cope with many types of emergency situations. However, if a fire or other type of incident occurs that requires outside assistance, such assistance is available as described in the following subsections. 3.7.2.1 Medical Assistance Dosher Memorial Hospital has medical facilities immediately available for the treatment of contaminated and non-contaminated injured personnel.
- New Hanover Regional Medical Center will serve as a backup for Dosher Memorialif necessary.
In addition, medical assistance is available on or off site from physicians in the Southport area, all of whom are on the staff of Dosher Memorial Hospital and who slave agreed to provide medical assistance to contaminated patients. (See Appendix E, Medical Treatment and Assistance, for more details.) 3.7.2.2 Ambulance Service The C!!y of Southport Volunteer Rescue Squad has agreed to respond to all emergency calls from the plant, just as they respond to other calls from the Southport area. A copy of the response agreement with the City of Southport Rescue Squad is included in Appendix B. I t v OERP Rev.53 3-19 I I i
c i 3.7.2.3 Firo Assist nco
.m ' Agencies with fire protection resources in the vicinity of Brunswick are as follows:
Southport Fire Department Boiling Spring Lakes Fire Department , Yaupon Beach Volunteer Fire Department Long Beach Volunteer Fire Department Sunny Point Fire Department The Southport Fire Department is the primary fire protection response agency for the Brunswick Plant and will coordinate assistance activities, if required, of the other above agencies. Copies of agreements with local fire departments are contained in Appendix B. In addition, the North Carolina Fire Protection Law makes provisions for volunteer fire departments to furnish fire protection in rural areas. u r" a OERP Rev.53 3-20
m 3.8 COORDINATION WITH PARTICIPATING GOVERNMENTAL AGENCIES m A summary of each governmental organization having major responsibilities for the planning and response to Brunswick Plant radiological emergencies is described below; comprehensive summary tables of emergency response organizations are included in Appendix C; and a detailed description of the authority, responsibilities, and duties of each organization is presented in their respective emergency plans. Each of these organizations having response duties is capable of providing such on a 24-hour-per-day basis. 3.8.1 State of North Carolina 3.8.1.1 Governor's Office The Governor has the authority to direct and control the State Emergency Management Program. During a declared State of Disaster, he has the authority to utilize all available state resources reasonably necessary to cope with emergencies. His representatives coordinate as necessary with the Carolina Power and Light Company, the ) Governor of South Carolina, and with local government officials. 3.8.1.2 Department of Crime Control and Public Safety
~-
The Department of Crime Control and Public Safety functions as the State of North Carolina Emergency Planning Coordinator. In that capacity the Department has overall management responsibility for North Carolina's , radiological emergency response planning, development, j and updating of North Carolina's emergency response plan, and coordination with Carolina Power & Light Company. The Department coordinates emergency response activities for the State of North Carolina and other government response agencies. v OERP Rev.53 3-21
3.8.1.3 D:partm:nt of Environm:ntal H:alth and Natural Resources, Division of Radiation Protection % 1 The Radiation Protection Division, performs radological l field monitoring and laboratory analysis of field samples. This section is responsible for dose assessments and projections and personnel radiological monitoring outside the Brunswick site, and other functions as described in the State Emergency Plan. 3.8.2 Brunswick County l 3.8.2.1 Emergency Management Agency The Brunswick County Emergency Management Agency has overall responsibility for Brunswick County's radiological emergency response planning, development, and updating of Brunswick County's emergency response plan, and coordination between the county and Carolina Power & Light Company and other local government response agencies. It functions as the lead county agency for radiological monitoring and decontamination activities as directed by the State of North Carolina's Division of Radiation Protection. 3.8.2.2 Brunswick County Sheriff's Department The Sheriff's Department e'mergency response functions are: A. Coordinate all local law enforcement and traffic control. B. Operate the county warning point on a 24-hour basis. C. Provide immediate assistance to facility management and local authorities during initial onset of the emergency. a OERP Rev.53 3-22
D. Provido traffic control in support of evacuation. m E. Establish road blocks, re-route traffic around contaminated areas and report traffic problems to the County Emergency Operations Center. F. Provide traffic control in the vicinity of shelter areas. G. Provide assistance to municipal law enforcement agencies in warning and evacuating persons in designated zones. H. Provide security for county property. 3.8.3 New Hanover County 3.8.3.1 Emergency Management Agency
)
The New Hanover County Emergency Management Agency has overall responsibility for New Hanover County's radiological emergency response planning, development, and updating of New Hanover County's emergency response plan, and coordination between the County, Carolina Power & Light Company, and other local government response agencies. It functions as the lead county radiological response agency and provides any required radiological monitoring and decontamination activities as directed by the State of North Carolina's Division of Radiation Prote'ction. 3.8.3.2 New Hanover County Sheriffs Department The Sheriff's Department emergency response functions are: A. Coordinate all local law enforcement and traffic control. B. Operate the county warning point on a 24-hour basis. C. Provide immediate assistance to facility management end local authorities during initial onset of the emergency. OERP Rev.53 3-23
e ! D. Provids traffic control in support of evacuation, m E. Establish road blocks, re-route traffic around contaminated areas, and report traffic problems to the County Emergency ' Operations Center. F. Provide traffic control in the vicinity of shelter areas. G. Provide assistance to municipal law enforcement agencies in warning and evacuating persons in designated zones. H. Provide security for county property. 3.8.4 Federal Agencies 3.8.4.1 Department of Energy, Savannah River Operations Office The Savannah River Operations Office coordinates, under the Interagency Radiological Assistance Plan (IRAP), federal resources as required to: minimize accidental radiation exposure; minimize the spread of radioactive materials into the environment; and carry out countermeasures to control and eliminate radiation hazards. Upon request of the State of North Carolina, Department of Environmental Health and ! Natural Resources, Division of Radiation Protection, or the Nuclear Regulatory Commission (NRC); the Department of Energy will: provide equipment, supplies, and personnel to evaluate radiological hazards and to minimize radiation exposures; assist in carrying out emergency response operations and implementing prMeetive actions; and provide an aerial radiological rv easuring system for mapping radioactive plumes. The Site Emergency Coordinator or Emergency Response Manager after activation of the Emergency Operations Facility may request this assistance via the NRC or the State. Resources available in the area to facilitate federal assistance include the New Hanover International Airport, 1 i i v OERP Rev.53 3-24
y locat d cpproximately tw nty miiss from the Brunswick i Plant near Wilmington, North Carolina, which has two lW runways capable of supporting large commercial aircraft. L Also located at the New Hanover International Airport is a National Guard Armory. This area could be used as a Federal Command Post meeting the requirements of IRAP. 3.8.4.2 Federal Emergency Management Agency (FEMA) The Federal Emergency Management Agency coordinates, through the Atlanta, Georgia Regional IV Office, federal response as required to supplement that provided by IRAP. A representative from FEMA Region IV will be present at the SERT to coordinate any federal response requested by the state. 3.8.4.3 Nuclear Regulatory Commission (NRC) The Nuclear Regulatory Commission provides resident inspectors at Brunswick. At the request of Carolina Power & Light Company, NRC provides additional technical advice, technical assistance, and personnel during and foHowing a radiological emergency. The Director of Regulatory Operations will be notified of radiation incidents in accordance with 10CFR20.2202 and will conduct
- appropriate investigative activities.
3.8.4.4 U. S. Coast Guard (USCG) The Coast Guard controls access of navigable waterways in the vicinity of the Brunswick Plant and provides public warning and notification as described in the State Emergency Plan. 3.8.4.5 Murray and Trettle Murray and Trettle is under contract with CP&L to provide meteorological services during day to day and/or emergency operations. i l l J OERP Rev.53 3-25 a
r-I 3.8.4.6 Wrth:r S::rvica m The National Weather Service in Wilmington, North Carolina will provide meteorologica1 information during - emergency situations, if required. Data available will include existing and forecasted surface wind directions, j wind speed with azimuth variability, and ambient surface air temperature. I 3.8.5 Agreements ! Appendix B presents copies of letters of agreement with ; agencies that would not normally be available for assistance ' through existing state or federal plans but will make certain services available. l 3.9 NOTIFICATION AND ACTIVATION Notification and activation of the on-site and off-site emergency response I organizations is dependent upon the emergency classification and is listed in Table 3.5-1. Details of notification responsibilities, communications systems utilized to make the notifications, information require ,,, be transferred to off-site agencies, and notification verificatici. . @n4 Jes are specifically described in the Plant Emergency Procedures (PEPS) and Appendix A of this Plan. Additionalindividuals and organizations who might be required to activate are contained in OPEP Appendix A. Any time that an emergency is reclassified, the initial notification scheme will apply. The State of North Carolina and the Counties of Brunswick and New Hanover are responsible for the process of notification of the public. The initial instructions to the public will consist of preestablished emergency messages which will be tailored to reflect whether the event is a Site Area Emergency or General Emergency classification. The following information is typical of that which would be provided in the initial message:
- 1. Identification of the agency issuing the information.
- 2. A statement that an emergency condition exists at the Brunswick Nuclear Plant.
l 0ERP Rev.53 3-26 l
- 3. Britf description of tho typ3 of emnrgency and the natura of the hazard, m
, 4. Identification of the communities or geographical areas affected by the emergency.
- 5. Recommendations with regard to specific protective measures to be taken by residents of the affected areas.
- 6. A statement concerning how the public will receive further emergency information.
Prewritten emergency messages to be used for public notification are contained in the procedures of the State of North Carolina, and Brunswick and New Hanover Counties. e-4 i l V l- 0ERP Rev.53 3-27
7-l
$N'F T SUPERAft'NOANT be s*gese
' = " - -
, Y, g , --- SECURITY
,,. ,,,, I swF w . a, FIELD
$RO l
6L NtoM $L N;OM CONTR04 i CONTROL 3PERATOR ($RO1 _ STA I PERATOR ($RO) IUNIT 1) (UNIT h i I I I i i CONTROL CONTROL C C*dTR OL CONTROL OPERATON Or'E RATOR OPERATOR OPE RATOR 1RO) (RO) (RO: LRO) AUNlt tA RY AUxttiARY AUr pt ia Ry Aijxit aARY AuxiLlARv AuxitlARv A uxitiARy OPERATOR OPERATOR OPE RATOR OPERATOR *EqaTOR OPE RATOR OPERATOR l I
; _ _ _L _ _ _,
t CHEMISTRY W ALI" TECHNICIAN T @ l Figure 3.1-1 Brunswick Shift Organization l v OERP Rev.53 3-28
fS[ EUF 4GE Nr,Y CEWOtesE StANAGE R I I I I 1 l O' AA kS bNY YgCHMCA;, AreAtyn appygygeggf CCMdtpeaCA 60*t%f g gg h, R LOCitTCS waseAGER 'EAI C,Ty'[fM CCseikUL LR
....l.... _ sw.
f RE LM TA Vf 8 e ~ gy pg ~ gos gTatug
*.......*. R(ACTOR opt R ATOR O PLuf fLR 1ALnLRS COMMNTOR
- . 0,e
.-. mof w ,,Cu,,, ,,,o M - m ,-- _ - -> w . - - ,
OPLRMQN COUNDs*eATOR EOC _ , . . . . %.uC -0..mo. _ . O, .Nw CLERK,AL nfAsp - (LWMUNICAf0R pgN3 f;,mlNG )[,AM L E ALW N L......... _ NEWmMnav,.WER MQte CA f 3
. . emcR . . ccmo.
0,~....a , TERM,AAN
.,f. -Rme COOHLfNAtOH I
I I I I I u~, ,,- -mo OPPAAfDs A35t S5vt NT (f pa.orr NL*nCATKlN$ SE CV8P TV " DIRECTOR e DRECTOR DRECTOR PRECTUN DHECTCA E NS 19C 5Fre0R " Actioff f5C _.= RI. AC104 AS$l66WENT TEAM = NADTAaHUTV (FE MA'OR LE ALA R TECHfeCAN gy g,y 1 - A0ery CLE8eKA sfA** g ASSE66ulNT TEAW COMWVNCATON
...n.e OSC ' __ =i*mi Nt +4 l 90A40 P'LOTTER DREC10N I
8 _ Eros OceR4*oR i Figure 3.2-1 Brunswick Emergency Organization u OERP Rev.53 3-29
m EMERGENCY REPAIR DIRECTOR AERD AAT MEMBER (ERD) LIAISON
-~~~l l l -l l O C
{ ) CONTR L E&RC OPERATIONS (MECH) LOG KEEPER COORDINATOR
-~~
WORK PLANNER l l HP LEAD CHEM LEAD FIRE t ^IO*o*caI fr TSCIEOFa BRIGADE ~ E',',7jg,'"7 D/G -. - Fa boso. g (MISSION) l Z l I 9 W I&C TO. PLANT SPA
- PASS CHEM CONTROL MONITORING -
HP TEAM TEAM LAB ROOM (MISSION) (MISSION) 2 (MISSION) (MISSION) REPAIR P N L _ OSC POOL E TEAM - AND DECO'N - Mechanics (MISSION) . Electricians
- l&C Techs b PASS TEAM - Aux Operators (SAMPLE AND _
- HPs ANALYSIS) - Chemists
- AUTOMATIC Figure 3.4-1 Operational Support Center (OSC) v OERP Rev.53 3-30 1
p BRUNSWICK TABLE 3.5-1 NOTIFICATION AND ACTIVATION OF PRINCIPAL EMERGENCY RESPONSE ORGANIZATIONS 1 Unusual Site General L Acency Event Alert Emeraency Emeraency On site: Carolina Power & Light i Plant Operators Activate Activate Activate Activate Radiological Emergency Teams (a),(c) . (a) Activate Activate Technical Support Center (a),(c) Activate Activate Activate Operational Support Center (a),(c) Activate Activate Activate Emergency Operations Facility (a),(c) Activate Activate Activate Corporate Headquarters Notify (a) Notify (a) Activate Activate Fire Brigade . (a) (a) (a) (a) Off site:
. State of North Carolina Notify Notify (a) Activate Activate Brunswick County Notify Notify (a) Activate Activate New Hanover County Notify Notify (a) Activate Activate
.USNRC Notify Notify Activate Activate American Nuclear Insurers Notify Notify (a) Activate U. S. Coast Guard (c) (c) Notify (a) Activate Dosher Memorial Hospital (b) (b) (b) (b)
- Southport Volunteer Fire Department (b) (b) (b) (b)
Southport Volunteer Rescue Squad- (b) (b) (b) (b) General Electric (c) Notify (a) Activate Activate INPO (c) Notify Notify Notify 1 (a) Mobilize,if deemed necessary. (b) Request assistance,if required.
. (c) Notify if deemed necessary.
OERP Rev.53 3 31
(.. COMPANY SPOKESPERSON JIC DIRECTOR COMPANY TECH ADMIN. PUBLIC INFO SPOKESPERSON . COORDINATORS DIRECTOR Figure 3.6-1 Joint Information Center (JIC) OERP Rev.53 3-32 l 1
7 BRUNSWICK NUCLEAR PLANT RADIOLOGICAL EMERGENCY PLAN m 4.0 EMERGENCY MEASURES This section identifies the measures to be taken for each class of emergency described in Section 2. The measures presented in this section are used as the basis for the detailed Plant Emergency Procedures which define the specific actions to be taken for each emergency class. Emergency measures begin with the recognition and declaration of an emergency class, notification of the applicable agencies for that emergency class, and mobilization of the appropriate portions of the emergency organization. Subsequent measures include damage assessment, corrective actions, protective actions, and aid to affected personnel. Recovery activities are discussed in Section 7. 4.1 ACTIVATION OF EMERGENCY ORGANIZATIONS 4.1.1 General The Plant Operating Manual contains Emergency Operating Procedures (EOPs). These are intended to aid the plant operators in responding to an accident. The EOPs identify actions which should automatically occur to safely terminate the accident and manual actions which should be taken to verify that the automatic actions have produced the desired results. The EOPs also provide, for the operator's use, guidelines which alert the operators to conditions where inadequate cooling of the core ! exists or where radioactivity releases may occur. Accordingly, if it should appear that any of the Emergency Action Levels are exceeded, as described in OPEP-02.1, initial Emergency Actions, the operators are instructed to activate the Emergency Plan. The Shift Superintendent activates the Plan, assumes the Site ' Emergency Coordinator's responsibilities, initially classifies the emergency, and ensures that the required notifications are made. The Site Emergency Coordinator will activate portions of, or the entire emergency organization, as warranted for the emergency situation. A more detailed discussion of the methodology that is used in activating the emergency organizations during each class of emergency is provided below and in the Plant Emergency Procedures. Additional detail of the communications networks to be used for notification v OERP Rev.53 4-1 e
o ; requirements, for information reporting, and for decision-making with respect to taking protective action on site and for the general n public is contained in Appendix A of this plan and OPEP-03.1.3, Use of Communication Equipmen.
.j-
'4.1.2 Unusual Event The Shift Superintendent, when informed of conditions that meet emergencies that are classified as an Unusual Event, confirms that an Emergency Action Level has been exceeded and implements OPEP-02.1.1, Emergency Control- Notification of Unusual Event, Alert, Site Area Emergency, General Emergency.
- He then is responsible for assuming the role of the Site Emergency Coordinator and for notifying and activating those portions of the emergency. organization as appropriate to the emergency class which then exists. The Site Emergency Coordinator can augment the on-site shift personnel by activating addit _ional emergency personnel described in Section 3. Typical of the personnel that may be notified are E&RC, the Fire Brigade, and the Security Force.
4.1.3 Alert Section 2 and OPEP-02.1, Initial Emergency Actions, describe the types of emergencies that are classified as an Alert. Since
- the conditions in this emergency class indicate an actual or j potential substantial degradation of the level of safety of the plant '
and has the potential for limited releases of radioactive material . to the environment, off-site groups will be notified to standby so l that if the emergency level is escalated, the essential off-site l emergency organizational groups can be notified and readily i mobilized to augment the on-site emergency groups. i Upon declaration of an Alert emergency classification the Shift , Superintendent assumes the role of the Site Emergency ! Coordinator until relieved by a designated, qualified emergency response organization member. The transfer of Site Emergency Coordinator responsibilities from the Shift Superintendent occurs simultaneously with the activation of the Technical Support Center (TSC). The Site Emergency Coordinator implements OPEP-02.1,1, Emergency Control- Notification of Unusual Event, Alert, Site [ Area Emergency, General Emergency, and notifies the l appropriate individuals or groups. 0ERP Rev.53 4-2
l The Sito Em:rgency Coordinator initiates the activation of the Technical Support Center, Operational Support Center, and the m Emergency Operations Facility (EOF). The radiological emergency teams will be activated, as appropriate. The appropriate county and state emergency groun leaders will be requested to remain in a readiness condition in case additional augmente. tion of support personnelis needed and alerting the population-at-risk is warranted. A decision to go beyond the initial response associated with an Alert class would be based on further degradation of plant parameters, operational experience, or radiation releases that are projected to escalate beyond the Emergency Action Levels for an Alert. 4.1.4 Site Area Emergency Section 2 and OPEP-02.1, Initial Emergency Actions, describe the types of emergencies classified as a Site Area Emergency. The Site Emergency Coordinator, when classifying the emergency, takes appropriate predefined steps to correct the situation as described in OPEP-02.1.1, Emergency Control-Notification of Unusual Event, Alert, Site Area Emergency, General Emergency. if he has not done so earlier, the Shift Superintendent assumes the role of the Site Emergency Coordinator until he is formally relieved. He activates the necessary emergency organizations and directs that the essential emergency personnel be notified. If they have not been previously requested to do so, the off-site groups will be mobilized as soon as possible; the Technical Support Center, Operational Support Center, and the Emergency Operations Facility will be activated. Radiation monitoring teams may be augmented to permit an expanded on-site and near site monitoring program. The Joint Information Center will be activated for the purpose of providing information to the public. If the plant parameters indicate possible further degradation of plant safety or projected radiation levels which exceed the recommended values, the emergency will be escalated to the General Emergency level. OERP Rev 53 4-3 J
E 4.1.5 G:n:ral Em rg:ncy ,m Section 2 and OPEP-02.1, initial Emergency Actions, describe the types of emergencies classified as a General Emergency. The Site Emergency Coordinator upon classifying the situation as a General Emergency takes appropriate, predefined steps to respond to and correct the situation as described OPEP-02.1.1, Emergency Control- Notification of Unusual Event, Alert, Site Area Emergency, General Emergency. This includes arranging for personnel to be available, both on site and off site, to perform actions up to and including evacuation of the affected sectors of the 10-mile EPZ. If he has not done so earlier, the Shift Superintendent assumes the role of the Site Emergency Coordinator until he is formally relieved. He activates the necessary emergency organizations and directs that the essential emergency personnel be notified. The activation and notification process should have begun well before a General Emergency is declared. Recommendations will be made for sheltering and/or evacuation in accordance with the guidelines in OPEP-02.6.28, Off-Site Protective Action Recommendations. 4.2 ACCIDENT ASSESSMENT ACTIONS 4.2.1 General Effective coordination and direction of all elements of the emergency organization require continuing accident assessment throughout an emergency situation. The process of accident assessment involves several different types of activities, in-plant and off-site, depending on the nature and severity of the emergency. l l l l l 1 a OERP Rev. 53 4-4 . . J 1 l I
The magnitudo of ral:as:s of radioactive matnrial can be determined using effluent and process monitors, meteorological im data and other sources of information. Additionally, an independent confirmation of the magnitude of the release can be obtained based on the measured dose rates in the environment. Given these measured releases or environmental levels and estimates of the amount of dispersion between the plant and the various points of interest, projected doses can be estimated for other locations. These doses can then be compared to Protective Action Guides. The various steps in this process are discussed in the following sections and in the Plant Emergency Procedures. In the absence of measurable off-site dose rates, protective action recommendations will be made based on the guidelines OPEP-02.1.1, Emergency Control - Notification of Unusual Event, Alert, Site Area Emergency, General Emergency. 4.2.2 Source Term Assessment Source terms for assessment of off-site dose consequences to the public can be determined by using effluent and radiation monitor readings, evaluating plant conditions against predetermined scenarios, using analysis results of plant effluent samples, and by manually estimating curie inventories. A thorough discussion of source term development is provided in Appendix F. 4.2.2.1 Effluent and Radiation Readings ! The most direct indication of a radiological emergency is a high reading in the effluent radiation monitors. The Radiation Monitoring System (RMS) monitors the airborne gaseous and particulate activity released from the Reactor ! Building and Turbine Building. Additional channels of the j Radiation Monitoring System also monitor the gaseous i activity in the air ejectors, primary containment (drywell atmosphere) ventilation system, and main steam line i monitors. These channels indicate, record, and alarm in the main control room. The RMS gives early warning of a plant malfunction and warns plant personnel of increasing radiation activity which might result in a radiation health hazard. (See OPEP-03.6.3 for procedures on source term assessments and estimates of core damage.) \ v i OERP Rev.53 4-5 i
Thnse monitors era also the primary m:ans of determining that an emergency exists for accidents involving spills or N leaks of contaminated liquids or gases from tanks housing radioactive materials. Such leaks could lead to a release to l the environment. In such instances, the following types of emergency actions would take place:
- 1. The Shift Superintendent on duty would be notified.
- 2. Personnel from the affected plant area would be evacuated,if required.
- 3. Access to the plant area involved would be restricted.
4.- All plant personnel directly involved would be monitored for contamination.
- 5. A determination would be made of the potential for an off-site release.
6.- The Plant Emergency Procedures would be activated if an emergency is declared. 4.2.2.2 Potential Consequences Based on in-Plant Conditions The source term can be es'timated by evaluating the plant condition against a number of preselected scenarios that best describes the effectiveness of containment, cleanup systems, subcooled, or saturated conditions in the torus, and other relevant parameters. A more thorough discussion of the determination of source terms from plant conditions is described in Appendix F. OERP Rev.53 4-6 ! l a
{ l f i 4.2.2.3 Post Accident Sampling and Analysis of Reactor and Containment m I To aid in the assessment of core damage, capabilities have been provided to permit sampling for chemical and radioanalysis under a wide range of accident conditions. , Samples can be taken from effluent streams such as the plant stack to determine total release quantity and , radionuclide mix, or they can be taken from the RCS, ! drywell, and torus to determine radionuclide mix. The collection and analysis of samples can be performed without incurring radiation exposures to individuals in . excess of 10CFR20.1201 limits. ! The procedures for obtaining samples of gases and liquids l during normal operation (such as a sample of primary coolant) can also be safely used during a wide spectrum of accident conditions. However, there are situations involving gross damage to the core where access to the sampling stations and handling of samples may be limited due to high radiation levels. Procedures have been developed and equipment has been installed at the sample panels to minimize the time required to obtain samples and to reduce the radiation levels during transport and analysis of samples. Beyond these measures, post accident
-- sampling stations are located in the breezeway on the 20-foot level. This permits the collection of samples even if access to the Reactor Building is lost. This station can be used to safely withdraw samples of reactor coolant from the recirculation instrument racks in parallel with the jet pump flow indicator and to withdraw samples of water in the torus.
In addition to the liquid samples, area-type monitors ; utilizing ion chamber detectors are available to monitor radiation levels in the drywell. These monitors have a range of up to 10' Rem /hr. The range of monitoring equipment in various locations of the plant has also been extended (e.g., high range noble gas vent monitor and improved procedures for iodine analyses). This information can be used, together with the analyses of primary coolant system contamination levels, to develop an assessment of i the types and quantities of various materials that have ; been released. i DERP Rev.53 4-7
E 1 4.2.3 Doso Proj:ction and M:teorological Syst:ms { m Once the source term is estimated, exposures to on-site and off-site individuals can be estimated as described in OPEP-03.4.7, Automation of Off-Site Dose Projection Procedures. The technical basis for the methodology for performing dose projection is described in Appendix F. Prior to receipt of information from the emergency radiation monitoring I teams, exposure rates at various locations on site and off site will l be estimated from the airborne concentrations of radioactive material as calculated from plant radiation monitors and the atmospheric dispersion characteristics. Meteorological measurements, specifically the change in temperature with height, wind velocity, and wind direction, are used to determine the atmospheric dispersion conditions. Normally, the plant computer will provide a readout of the stability condition, but alternate methods are available. Rapid evaluation of potential radiation levels of any downwind area can be made through the use of precalculated dispersion factors and the calculated release rate of airborne radioactive material from the plant.
. i The Brunswick Nuclear Plant has an on-site meteorological station with a backup source of additional meteorological data to provide sufficient information for utilization in a dose assessment capability. This system is further described in Section 5.7.2.
Currently, the BNP staff has an automated dose projection capability as described in OPEP-03.4.7, Automation of Dose Projection Procedures. By entering critical plant data and meteorological information obtained from the on-site meteorological station, dose projections can be made for various locations using the plant computer systems. This function has been designed and implemented to allow for the rapid determination of dose isopleths for immediate use by plant personnel. Additionally, contract meteorologists are to be contacted by plant personnel. Meteorological data display is available for remote interrogation as part of the Emergency Response Facility information System (ERFIS). This satisfies the NUREG 0654, Rev.1 criteria for meteorological evaluation and remote interrogation. 0ERP Rev.53 4-8
4.2.4 Emerg:mcy Environm:ntal Monitoring '~ The Site Emergency Coordinator is responsible for quickly evaluating meteorological conditions existing at the time of the I incident and, where releases are or soon will be occurring, for ; dispatching monitoring teams to specified, predetermined I downwind locations. The prime objective of the initial emergency off-site monitoring is to confirm or modify the initial projections of the consequences of any release of radioactive materialinto the environment. l The Environmental Monitoring Teams collect samples and survey data and transmit information to and/or receive I instructions from the Radiological Control Manager of the EOF staff (or Radiological Control Director, if the EOF is not i activated). Calculational aids, site maps, and actual radiation survey data collected by off-site survey teams define'affected areas and assess the extent and significance of the release. Information is required for decision making with as little delay as possible; therefore, the initial environmental surveys involve simple-to-perform measurements so that the dose assessments based on plant parameters can be quickly confirmed or modified. l Subsequent environmental monitoring efforts will be aimed at ; further defining the off-site consequences including estimates of l total population exposure and instituting an expanded program to enable prompt assessments of Gny subsequent releases from the plant. CP&L Environmental Monitoring Teams will coordinate expanded environmental monitoring efforts to assist the agencies identified in Section 3.8. Field monitoring equipment will have at least the capability to detect and measure radiciodine in the vicinity of the plant site as low as 5 x 10~' Ci/cm*. The collected air sample can easily be measured by hand held survey meters, a simple test that can serve as an initial check of projected releases based on plant data and can confirm that significant quantities of elementaliodine have been released (the chemical form that would pose a health hazard). More detailed measurements (e.g., Sodium lodide scintillation counters) can be quickly brought into service to provide the longer term higher capabilities to detect and measure very low levels of contamination in the environment, as would be planned for subsequent radiation monitoring efforts. l v OERP Rev.53 4-9 L
L \ l At Inst two environm:ntal monitoring trams will initially b3 activated from the plant staff upon activation of the EOF by the m Emergency Response Manager, if conditions warrant their deployment. Additional teams from the Harris Nuclear Plant and l the Robinson Nuclear Plant may be requested, if needed. l 4.2.5 Emergency Response Data System (ERDS) The Emergency Response Data System will supply the NRC with l selected ERFIS data points on a near real time basis. This function will be activated by the Control Room staff within an hour of the declaration of an Alert. The selected data points are transmitted via modem to the NRC at approximately 1-minute intervals. If the primary ERFIS system fails (failover) the backup j ERFIS system will re-establish the ERDS ank automatically l through the communication port for ERDS. ! 4.3 CORRECTIVE ACTIONS Corrective actions that may be taken to mitigate the circumstances of various levels and types of emergencies identified in this plan are given in the Plant Operating Manual. Generally, corrective actions include any ; actions that are taken to repair damaged equipment, to install emergency l structures, systems, and components, or to reduce the releases of 1 radioactivity. l In order to maintain proficiency in implementing the various procedures and plans, there are training and retraining programs which in some cases are augmented by periodic drills and exercises. A description of this specialized training is given in Section 6.1.1. ; 4.4 PROTECTIVE ACTIONS 1 Protective actions are defined for each emergency class. Protective actions must take into consideration the potential risks of implementing such measures versus the reduction of the radiological risk achieved by their use. Analyses of the spectrum of emergencies show that only those in the General Emergency class are expected to have consequences in excess of one Rem whole body (TEDE). 0ERP Rev.53 4-10 l l
r; Prot:ctiva cction recommendation guid:: lines for the general public are described in OPEP-02.6.28, Off-Site Protective Action Recommendations. m- Protective actions planned for on-site personnel are described in Section 4.4.2. Protective actions for the off-site population-at-risk are the responsibility of state and local agencies; however, representative actions at various dose levels are described in Section 4.4.7. The evaluation of Protective Action Guidelines for the intermediate phase and for ingestion pathways are the responsibility of the state. 4.4.1 Protective Action - Off Site Notification of off-site agencies will take place when EALs are exceeded (see Section 3.9). Any incident that is projected to result in radiation doses to the general public in excess of the Protective Action Guidelines listed in OPEP-02.6.28, Off-Site Protective Action Recommendations, requires the Site Emergency Coordinator to declare a General Emergency. The Emergency Response Manager will recommend to the state and counties protective measures for the public. 4 4.4.2 Protective Action - On Site 4.4.2.1 Warning and Notification The on-site PA system and appropriate alarms will be used to alert / warn and notify on-site personnel of an emergency and necessary protective actions as described ~in OPEP-02.1.1, Emergency Control- Notification of Unusual Event, Alert, Site Area Emergency, and General Emergency. In addition to the alarms, PEPS and security , instructions provide guidance for on-site warning and notification. Such warning and notification willinclude persons at the Visitors Center and the recreation area. Outside the plant protected area, warning will be accomplished as described in Section 4.4.6 for the public. i i l l I l l l: v OERP- Rev.53 4 11 i i
p i l 4.4.2.2 Evacu: tion & Personn:1 Accountability j !m For emergencies requiring protective actions in accordance with OPEP-03.8.2, Personnel Accountability and Evacuation, personnel will proceed by the safest, most direct route to the designated assembly locations or as l directed by the Site Emergency Coordinator.
- a. Shift operating personnel will assemble in the Control Room.
- b. All personnel not specifically involved in responding to the emergency (non-essential) will assemble as directed.
- c. All visitors will report to the Security Office at the protected area central access control point.
A personnel accountability check will be carried out in accordance with OPEP-03.8.2, Personnel Accountability and Evacuation, and all personnel will return dosimeters and be checked for radioactive contamination. Contaminated and/or injured individuals will be directed to an area set aside for decontamination and/or medical aid as described in OPEP-03.9.2, First Aid and Medical Care, and OPEP-03.9.3, Transport of Contaminated injured Personnel. Search for missing persons and rescue will be performed l as described in OPEP-03.9.6, Search and Rescue. On-site personnel will evacuate the area when directed using transportation that was employed to arrive at the site. Personnel without transportation will be identified during the assembly phase and provided transportation. The secondary access road and the main plant access ; road will be used to depart from the site as advised, and evacuation from the 10-mile EPZ will be by way of evacuation routes identified in Figures 1.1 -1, 1.1 -2, and 4.4-1. i v l 0ERP Rev. 53 4-12
L '4.4.3 Control of Parsonnti Radiation Exposures
% Although an emergency situation transcends the normal
, requirements for limiting exposures to ionizing radiation, l g'uideline levels are established in OPEP-03.7.7, Onsite Radiological Controls, for exposures that may be acceptable in emergencies. The maximum whole body (TEDE) dose received by any worker should not exceed established regulatory limits. Every reasonable effort will be used to ensure that an emergency _ is handled in such a manner that no worker exceeds these limits. The administration of radioprotective drugs such as potassium iodide (KI) to CP&L personnel may also be useful in mitigating the consequences of inhalation of radioactive materials such as radiciodines during an emergency.
. Procedures for the administration of radioprotective drugs to i CP&L and vendor employees are described in OPEP-03.7.6, Emergency Exposure Controls.
Decision making is based on conditions at the time of an emergency and should always consider the probable effects of an exposure prior to allowing any individual to be exposed to radiation levels exceeding the established occupational limits. The probable high radiation exposure effects are:
- 1. Up to 50 Rem EDE in 1 d' av - no physiological changes are likely to be observed.
- 2. 50 to 100 Rem EDE - no impairment li'Kely but some physiological changes, including possible temporary blood changes, may occur. Medical observations would be required after exposure.
- 3. 100 to 300 Rem EDE - some physical impairment possible.- Some lethal exposures possible.
l I l l I
'J OERP Rev.53 4-13 !
i Th3 following subsect!ons describe the critaria to ba considered for life-saving and facility protection actions. m 4.4.3.1 Exposure Control Under Emergency Conditions Dose limit guidelines for workers in an emergency are taken from EPA 400-R-92-001, Manual of Protective Actions and Protective Action Guidelines for Nuclear incidents, U. S. Environmental Protection Agency, May 1992. Much of the discussion in this section is taken in whole from that document. In emergency situations, workers may receive exposure under a variety of circumstances in order to assure protection of others and of valuable property. These exposures will be justified if the maximum risks or costs to others that are avoided by their actions outweigh the risks to which the workers are subjected. The Emergency Worker Dose Limit Guidelines are as follows: Ddse Limit (Rem TEDE)8 Actlylty Condition
- 5 All 10 Protecting valuable Lower dose not practicable property .
25 Ufesaving or protection of Lower dose not practicable large populations
>25 Ufesaving or protection of only on a voluntary basis to large populations personsfullyawareof the risks involved Routine dose limits shall not be extended to emergency dose limits for declared pregnant individuals. As in the case of normal occupational exposure, doses received j under emergency conditions should be maintained as low y as reasonably achievable. ' Doses to the lens of the eye should be limited to three times the stated TEDE value and doses to any other organ (including skin and body extremities) should be limited to 1 ten times the stated TEDE value. l l,
- g l OERP Rev.53 4 14 I
7 1' l In thm context of th:s3 guid linas, exposure of workers that is incurred for the protection of large populations may be ea considered justified for situations in which the collective dose avoided by the emergency operation is significantly larger than that incurred by the workers involved. Persons undertaking any emergency operation in which the dose will exceed 25 Rem TEDE should do so only on a voluntary basis and with full awareness of the risks involved, including the numerical levels of dose at which acute effects of radiation will be incurred and numerical estimates of the risk of delayed effect. 4.4.3.2 Exposures During Repair / Reentry Efforts
+y Each emergency worker entering a high radiation area shall !
wear dosimetry capable of measuring the expected exposure to be received. Emergency teams that must enter areas where they might be expected to receive higher than normal doses will be fully briefed regarding their duties and actions and what they are to do while in the area. They will also be fully briefed as to expected dose rates, stay time, and other hazards. All such entries willinclude one Health Physics
- Technician, or other person adequately trained in health >
physics. All team members will use protective devices as specified by the Radiological Control Director. The team members will be instructed not to deviate from the planned route unless required by unanticipated conditions, such as rescue or performance of an operation that would minimize the emergency condition. If the monitored dose rates or stay times encountered during the entry exceed the limits set for the operation, the team will communicate with the OSC Mission Coordinator or will return to the area from where they were dispatched. Once their operation has been completed, the team personnel will follow established monitoring and personnel decontamination procedures as specified by the Radiological Control Director. a OERP Rev.53 4-15 < J l l
E l l 4.4.4- Rrdio:ctivo Cont minttion l m 4.4.4.1 On-Site Personnel Radiation safety controls are established to contain the spread of loose surface radioactive contamination. Personnelleaving the contaminated areas are monitored to ensure that they or their clothing are not radioactively-contaminated. Additionally, in the event of a site evacuation, no personnel will be allowed to leave the plant site until they have been checked for contamination. In addition to the decontamination area of the Service
. Building, additional areas can be set up inside the entrance to the TSC and the entrance to the EOF.
Contaminated clothing or personal articles will be decontaminated. Drinking water and food supplies will be monitored and, during an emergency, permitted only in specified clean areas. Contamination on personnel will be removed in accordance with established E&RC procedures. { if normal decontamination procedures do not reduce contamination to acceptable levels, the case will be referred to a competent medical authority. 4.4.4.2 Equipment and Vehicles Equipment and tools will be released for use outside of the contaminated areas only if' loose surface radioactive contamination is within acceptable limits. All tools and items of equipment must be checked for contamination before being taken from a known contaminated area. If the item is found to be contaminated and decontamination is i not practical, the item must remain in that area. In the event of a site evacuation, vehicles will be surveyed for contamination before they are allowed to leave the plant site. Contaminated vehicles will be decontaminated before being released. If the Low Level Radwaste Warehouse is not a suitable decontamination site due to radiological concerns, vehicles will be directed to an alternate area for decontamination. Brunswick County Emergency Management may provide assistance in this area. 0ERP Rev.53 4-16
r 1 4.4.5 Tr:atm::nt of injur d end Contaminat:d Persons j m Personnel showers and chemical decontamination agents are available on site and, except in cases of life-threatening / serious injury, established decontamination procedures will be employed on site prior to medical treatment. Decontamination showers and supplies are provided in the Service Building. Shower and sink drains in the Service Building are routed to the miscellaneous waste processing system where the liquid is processed and monitored prior to discharge. Arrangements and facilities for medical treatment of injured plant personnel are described in detail in Appendix E - Medical Treatment and Assistance and in OPEP-03.9.2, First Aid and Medical Care. Depending on the nature and severity of injury, I injured personnel may be treated in-plant by individuals trained in first aid, treated in-plant by a physician, or transported to the hospital for treatment (see OPEP-03.9.3, Transport of Contaminated injured Personnel), in cases of severe injury, lifesaving first aid or medical treatment will take precedence over personnel decontamination. In general lthe order of medical treatment will be: 1, Care of severe physicalinjuries.
- 2. Personnel decontamination. )
- 3. First aid to other injuries. )
- 4. Definitive medical treatment and subsequent therapy as required.
Definitive medical treatment, therapy, and evaluation may include radioprotective drugs, urinary bio-assays or whole body counts on persons suspected of inhaling or ingesting a significant i amount of radioactive material or may include surveillance and j therapy for persons receiving a large whole body dose. J i q OERP Rev.53 4-17
r 4.4.6 Public W rning and Notification m in the event of an emergency, the plant will notify designated emergency officials in Brunswick and New Hanover counties as well as state and federal officials in accordance with OPEP-02.6.21, Emergency Communicator. During the ALERT phase of an emergency, the appropriate county and state emergency group leaders will be requested to remain in a readiness condition to alert the population at risk if needed. The plant will recommend protective actions for the public upon declaration of a General Emergency. Public warning when deemed necessary will be accomplished as described in the North Carolina Emeraency Response Plan In Support of the BNP. Warning will be given by such methods as sirens supplemented by radio, television, sound trucks, bullhorns, and knocking on doors. The Coast Guard will be used in notifying people along the coast and other large bodies of water where appropriate and necessary. Sirens mounted on 50-foot utility poles have been installed by Carolina Power & Light Company at 35 locations within a 10-mile radius of the Brunswick Nuclear Power Plant. Since the average ambient noise level throughout the EPZ is about 49dBA, the siren system is planned to provide a 59dBA minimum signal. l The warning signal will be a 3-to-5-minute steady tone on the sirens. ! Sirens will not be sited in the Sunny Point Army Terminal. Brunswick County will notify the terminal which will alert its personnel using on-site warning methods. Sirens will not be sited in areas of no population. Large areas of Brunswick County consist of swamps and forests with no population. These areas include such tracks as the Orton Plantation, the western section of Boiling Springs Lakes, and some areas south of Route 211. These tracts are often owned by a few local individuals or lumber companies. Based on land use history, they show little promise of development. However, the warning system will be reviewed annually and upgraded when conditions warrant. v OERP Rev.53 4-18
r Activ tion of tha sir:ns will b3 accomplished from ths Brunswick and New Hanover Counties Emergency Operation Centers. The , -., sirens in each county are independently controlled, but may be activated by CP&L with permission from the counties. A feedback system immediately alerts CP&L and both counties of any siren failure. The U.S. Coast Guard will perform the warning of people on bodies of water under their jurisdiction. The population at risk in the 10-mile Emergency Planning Zone (EPZ) is subdivided into three general categories: resident (permanent) population, transient population, and special facility population as described in Evacuation Time Estimates for the Brunswick Nuclear Plant Plume Exposure Pathway Emergency Planning Zone, prepared by HMM Associates, November 1993. The total resident population within the 10-mile EPZ is approximately 19,345. During the summer months, June through August, the daytime population of the EPZ is approximately 132,367 (see Figure 1.1-6). The population is concentrated along the coast and a relatively few inland roads. 4.4.7 Protective Actions - Off Site /Public 4.4.7.1 Public Education and Information
^
Occupants in the plume exposure pathway Emergency Planning Zone (EPZ) will be provided information prepared by CP&L in conjunction with the state and county agencies. This public education and it1 formation program is intended to ensure that members of the public are: (a) aware of the potential for an occurrence of a radiological emergency; (b) able to recognize a radiological emergency notification; and I (c) knowledgeable of the proper, immediate actions to be taken upon notification. i This will be accomplished by: (1) distribution of the annual safety information calendar which contains educational l information on emergency preparedness, sheltering, sirens, radiation, and telephone numbers of agencies to contact for more information; (2) availability of qualified personnel to address civic, religious, social and occupational organizations; and (3) distribution of news material to the media and numerous community and business newsletters. v OERP Rev.53 4 19
y Em:;rgency inform: tion will be m:d3 available to transi:nt populations through the distribution of safety information
'm calendars to commercial establishments in the 10-mile EPZ.
During an actual emergency, provisions will be established through the Joint Information Center to make available and distribute information to the news media. The Joint Information Center will also implement provisions for a i number of telephones which members of the public, who hear rumors, can call for factual information. 1 The public education and information program is further described in Section 6.1.4. 4.4.7.2 General For emergencies requiring protective actions for the general public in designated off-site areas, state agencies will determine the advisability of any necessary evacuation or sheltering. Local agencies will conduct the protective actions as warranted. Assembly points would vary depending on the severity of the incident and on the prevailing weather conditions. To assist in this effort, CP&L will provide up-to-date assessments of the condition of the plant and of the quantity and rate of release of radioactivity. CP&L will also assist by performing dose assessments which will be compared to the protective action guidelines. The protective actions that CP&L recommend to the state I will be based upon current meteorological data such as wind direction, speed and stability class, and other factors. Releases affecting off-site areas may not be of the 4 magnitude requiring evacuation, areas within the 10-mile ) EPZ that do not evacuate will be recommended to shelter. l I Detailed procedures for public protective actions are l contained in the North Carolina Emeroency Response Plan in Support of BNP. I l 1 a , OERP Rev.53 4-20 l
p 4.4.7.3- Evncurtion m In the event that evacuation of the 10-mile EPZ is required, l the evacuation routes shown in Figure 1.1-2 and Figure 4.4-1 will be used by on-site and off-site personnel. The time required to evacuate personnel from the 10-mile EPZ varies depending on whether a part of the EPZ is to be evacuated or all of it, on the time of year such as winter or summer, etc., as illustrated in Figure 4.4-1 and on other factors as shown in Table 4.4-1. It should be noted that the evacuation process in itself involves risk to the public. Risks resulting from evacuation are discussed in US EPA Report, EPA 400-R-92-00, Appendix C. 4.4.7.4 Shelter All sectors that are not recommended to evacuate will be recommended to shelter. The state may consider
--. sheltering for doses up to 5 Rem TEDE for special populations or hazardous environmental conditions, and for doses up to 10 Rem TEDE for special populations and hazardous environmental conditions. Special populations - may include institutionalized or infirm persons. Hazardous environmental conditions may include the presence of severe weather or competing disasters.
The local housing consists primarily of wood framed dwellings,1 and 2 stories, that are over 10 years old. Very few houses have basements. There are a number of brick veneer dwellings of later construction and a fairly small even distribution of house trailers. The term Protection Factor (PF) refers to a number used to express the relationship between the amount of gamma radiation that would be received by an unprotected person and the amount that would be received by a person in shelter. An occupant of a shelter with a PF of 40 would be exposed to 1/40 (2.5 percent) of the dose or dose rate to which he would be exposed if his location were unprotected (Sheltered Dose = Unsheltered Dose + PF). w OERP Rev. 53 4-21 1
i Protection f:ctors for various shielding materials are givsn in Figure'4.4-3 and for various structures and vehicles in a . Tables 4.4-2, 4.4-3, and 4.4-4. 4.4.7.5 Respiratory Protection it is unlikely that effective public respiratory protection can
' be provided by improvised devices.~ This problem will be studied and provisions incorporated in this plan in the event
. satisfactory systems are found.
1 k 1
.s 0ERP Rev.53 4-22 I 1
b TABLE 4.4-1 1 ,.. FACTORS RELATED TO WARNING / EVACUATION TIME l 1: Facility to Off-site Aoencies Alert Phase l l a- Decision-making time
. b. : Physical actions / calling time
- 2. Governmental Aaencies to Public Alert Phase l a. . Decision-making time
. b. Physical actions / calling-alerting time
- 3. Public Alert and Notification Phase .
l a. Hear signal l
- b. Recognize signal
- c. Seek confirmation of signal meaning and validity . .j
- d. Find confirmation of signal meaning
- e. Relate signal meaning to self
- f. Decide to act.
- 4. Movement Preoaration Phase
- a. Time between deciding to act and departing location
- b. Shutting off utilities-
- c. ' Packing bags .
- d. Deciding on destination and routes
' e.' - Taking care of livestock, etc.
- f. Collecting other family members. *
- g. _ Loading the automobile and departing -
- 5. Movement / Travel Phase
- a. Movement time is a function of road distance to the boun'dary of the evacuation area, vehicle used for evacuation, and auto traffic conditions (traffic volumes, road capacity, weather conditions, etc.).-
. b. Road capacity under emergency conditions per FEMA CPG-2-8-C are assumed to be 850 vehicles per hour (vph) per lane; under foul weather conditions 450-500 vph.
- c. Traffic volume is determined by: (1) dividing the EPZ population by the average number of persons per dwelling unit; or (2) obtaining statistical data on number of vehicles registered in the EPZ, or; (3) other.
I
- 6. Eyacuation Verification Ph'ase
- a. Marker Technique (NRC NUREG-0654)
Auto check - Total road distances + Ave.15 mph Aircraft check
- b. ' Telephone poll: 0.5 min. per residence i
j w#. OERP' . Rev.53 4-23
F ' TABLE 4.4-2 '
. REPRESENTATIVE SHIELD'NG I FACTORS FOR SURFACE DEPOSITED g RADIONUCLIDES *
. .. , Representative Representative
' Structure or Location Shieldina Factor Ranoe 1 m above ordinary ground 0.70 0.47-0.85 Cars on 50-ft. road:
Road fully contaminated . 0.5 0.4-0.7 Road 50% decontaminated 0.5 0.4-0.6 Road fully decontaminated 0.25 0.2-0.5 Trains 0.40 0.3-0.5
' One and two-story wood-frame house ' 0,4* 0.2-0.5 (no basement)
One- and two-story block and brick 0.2* 0.04-0.40
. house (no basement)
House basement, one or two walls 0.1
- 0.03-0.15 fully exposed:
One story, less than 2 ft of . 0.05* 0.03-0.07 basement, walls exposed Two stories, less than 2 ft. 0.035 0.02-0.05 s of basement, walls exposed Three- or four-story structures, . 5000 to 10,000 ft2 per floor: First and second floors 0.055 0.01-0.08 Basement O.01
- 0.001 0.07 Multistory structures, > 10,000
. ft2 per floor:
Upper floors 0.01* 0,001-0.02 Basement 0.005" 0.001-0.015 (a). The ratio of dose received inside the structure to the dose that would be received outside the structure. (b) Away from doors and windows. (c). . Shielding Factor =. Shielded Dose Rate / Unshielded Dose Rate
*From: SAND 771725, Public Protection Strategies for Potential Nuclear Accidents, Sandia Laboratory J
OERP- Rev.53 4-24
l TABLE 4.4-3 REPRESENTATIVE SHIELDING FACTORS FROM GAMMA CLOUD SOURCE m Shielding Representative Structure or Location Shieldina Factor (') Ranae i Outside 1.0 - l Vehicles 1.0 -- Wood-frame house" 0.9 -- 1 (no basement) ! Basement of wood house 0.6 0.1 to 0.7W l l Masonry house (no basement) 0.6 0.4 to 0.75 Basement of masonry house 0.4 0.1 to 0.5* Large office or industrial 0.2 0.1 to 0.3k* building (a) The ratio of the dose received inside the structure to the dose that would be received outside the structure. (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. (c) The shielding factor depends on where the personnel are located within the building (e.g., the basement or an inside room). (d) Shielding Factor = Shielded Dose Rate / Unshielded Dose Rate
*From: SAND 77-1725, Public Protection Strategies For Potential Nuclear Reactor Accidents, Sandia Laboratory l
i I l 1 l v OERP Rev.53 4-25 l
{ l TABLE 4.4 4 PF OF VARIOUS VEHICLES AND STRUCTURES i O Averaae PF ! Aircraft Light (Cessna 172 type) . ,
. .. . 1.25 Dus - Scenic Cruiser. . .
7
- Commercial Type . l.7 School.. .
l.6 i Ca,2 - Passenger.. , 1.6 Foxhole (3 ft. diameter x 4 ft. deep) . 10.0 if an area 3 or 4 feet wide around the foxhole is kept free of fallout material, a protection factor of 100 or more is possible.
)
House. Wood Frame (Cape Cod / Colonial Types) First Floor Center of House .
. 2.0 Basement . . .
'10.0 j Corner of Basement, Under Table with 8" 100.0 l Concrete on top .
. 100.0 House. Brick (Cape Cod / Colonial Type)
First Floor Center of House
. . 10.0 Basement . .
30.0 i Locomotive, Heavy, Engineers Seat . ..,.. . . 3.3 Normal Livina. Home and Work as Usual 2.0 Trucks 1/4 Ton . .. . 1.3 3/4 Ton . . . l.4 21/2 " Ion I.7 . 4 to 7 Ton 2.0 i Fire Truck, Drivers Side . 2.9 Fire Truck. Standing Area in Back 1.7 l Roadway Underpass , 2 to 5 ; Urban Areas (In Open) 1.4 Woods 1.25 i NOTE: Protection Factor (PF) = Unshielded Dose Rate + Shielded Dose Rate. Above data pertains to deposited particulate radioactive material with gamma energy approx. 0.7 mev. v OERP Rev.53 4-26
e - t l na . ) N k en aios en as 6 0 4, 6 0 0, 9 2 9, 1 5 8 4 1 6, 0 4 1, 4 ~ 7 4 3 1, 5, 3 1 7 2-O Pa r e 5 3 3 5 3 1 2 7 1 8 7 I T TS . 4 A h t L r U t .o
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/ e e
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7 EVACUATION TIMES - BRUNSWICK EPZ l6 Analysis ~ ~ Area Local Planning Evacuation Time
.< Zones Evacuated (minutes)**
l
.1 B- 175-480 ~
2 A,B,C . 175-480 i i 3 A,B,C,D 185-480 4 A,B,C',D,E 185-490 5 A,B.C,D,E,F,G,H 185-500 6 A,B,C E,F,G,H,K 185-685 7 A,B,C,G,H,K 175-685 8 A,B,C,H,K 175-685 9 A,B,C,K 175-685
~
10- A,B,C,D,E,F,G,H,K 190-695 l I a This range of evacuation times covers four conditions: Fair Weather - winter weekday, winter weeknight, summer weekday and summer weekend; and Adverse Weather - winter weekday and summer weekend, i b Evacuation time includes public alerting and notification (15 minutes), i l preparation for movement (15 minutes), and time to travel out of the local planning zone (s) .being evacuated, , i l l l l l Figure 4.4-2 Evacuation Times v OERP Rev.53 4-28
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w BRUNSWICK NUCLEAR PLANT RADIOLOGICAL EMERGENCY PLAN ! ;m 5.0 EMERGENCY FACILITIES AND EQUIPMENT To facilitate efficient and effective control and coordination of the numerous actions required during emergency situations, several facilities have been 4 - designated as emergency centers for Brunswick. These facilities are linked by a comprehensive communications network to allow accurate and timely communications between the facilities, outside agencies, and the public. The communications network uses Bell systems, fiber optic, Carolina Power & Light microwave net, data links, and radio to provide: (a) voice communication through normal telephone use, automatic ringdown between selected facilities, conference call capability, speaker phones and operator assistance where required; (b) radio ' communications between selected Carolina Power & Light vehicles and - appropriate fixed locations, as well as with state mobile units and fixed locations;
. (c) facsimile and Telex transmission. (A detailed listing of the Brunswick emergency communications systems is presented as Appendix A.)
l The purpose of emergency response facilities is to provide centralized locations { for organized coordination and control of on-site and off-site activities during an emergency, Each emergency response organization must assure that a location is provided from where they may direct the activities for which they are responsible, while providing for coordination of activities with other organizations. Facilities are needed to function as a center for the licensee's command and control functions of on-site operations, including coordination of all licensee , i activities, on site and off site Also needed is a center for the analysis of plant effluent monitors, riieteoruiogical conditions, and off-site radiation measurements, and for off-site dose projections. As discussed in Section 3 additional facilities are
- needed where information regarding current and projected plant status needed by -
federal, state, and local authorities for implementation of off-site emergency plans 1 l can be transmitted, where key representatives of the agencies can meet and 'f where the press can operate. The above functions are carried out by the interaction of the Control Room, the l Operational Support Center, the Technical Support Center, the Emergency Operations Facility, the Joint information Center, and the State and Local Emergency Operations Centers. These centers are connected with a comprehensive, redundant communications network. a
]
- v. j i
OERP Rev.53 5-1 i
b 1 in the emargency facilities, d:cisions and responses are based upon approved procedures and controlled drawings. Uncontrolled drawings and other documents 4 ._ may be used for reference if identified with "FOR INFORMATION ONLY" or "FOR TRAINING USE ONLY." Materialidentified as "FOR INFORMATION ONLY" or "FOR TRAINING USE ONLY" will not be used in place of approved procedures or l~ controlled drawings. The functional capabilities of the Brunswick emergency facilities are presented in Table 5.0-2, and the physical locations of on-site emergency facilities are shown on Figure 5.0-1. Specific information about the facilities and equipment available for dealing with emergencies at Brunswick is presented in the following sections. 5.1 CONTROL ROOM The function of the Control Room is ' plant control. All plant-related operations are directed from the Control Room. The Control Room is designed to meet habitability standards as described in the Brunswick FSAR. Nuclear plant instrumentation, including area and process radiation monitoring system instrumentation, is provided in the Control Room to give early warning of a potential emergency and provides for a continuing evaluation of the emergency situation. The Control Room contains the controls and instrumentation necessary for operation of the reactors and turbine generators under normal and emergency situations. Additional equipment such as portable radiation survey instruments, readout of meteorologicalinstrumentation and comrhunication equipment is available in the Control Room. A supply of protective clothing, respiratory equipment, and self-contained breathing apparatus will also be maintained in the Control Room. 5.2 TECHNICAL SUPPORT CENTER The Technical Support Center (TSC) provides a location to house personnel who are responsible for management and technical support of plant operations during emergency conditions. The TSC also functions to relieve i the Control Operators of peripheral duties and communications not directly j related to reactor system manipulations and preventing congestion in the Control Room. In the event of a loss of power, an auxiliary diesel generator is located near the building to supply an alternate source of power. ; I l OERP Rev.53 5-2
[ 1 i Th3 TSC will b3 cctivat:d for an alsrt or higher classification. Activation for j an unusual event is optional.- n. When readied for functional operation by Security, the TSC will be incorporated into the protected area. The only major security barrier between the Control Room and the TSC will be the security controlled door for the Control Room. The TSC and EOF share a common building which has been designed to havq the same habitability as the Control Room. The north wallis 18 inches thick and the other walls and roof are 14 inches thick. The ventilation i system is described in Section 5.2.1. 5.2.1 TSC/ EOF EMERGENCY VENTILATION SYSTEM 1 The EOF /TSC Building Ventilation System is equipped with two (2) filter systems (containing both HEPA and charcoal filters), , one for each of the two ventilation intake locations (Mechanical I Rooms 134 and 165). As soon as practical following an Alert l declaration, the systems are manually started. The TSC/ EOF l Building Ventilation System is equipped with two intake air l monitors which are Eberline SRM-100 monitors with SPA-8 probes. The probes are installed in the intake air ducts where detection of a high level of radiation can automatically trigger the HVAC system to actuate emergency fans to direct intake air through the filter trains. The intake air radiation monitors'are provided with an audible local alarm that is located on the radiation monitor. When the alarm setpoint is reached, the monitor will energize its associated radiation monitor relay, which will automatically activate an emergency fan to redirect the intake air through the associated filtering system. 5.2.2 TSC/ EOF EMERGENCY CONTAMINATED DRAIN SYSTEM During an emergency, contaminated drainage could occur at the decontamination shower. An emergency drain system is provided to isolate potential contaminated drainage which can be collected in a 1,000 gallon holding tank. For normal operating conditions, all drainage would be collected by the sanitary drain lines. The holding tank is located underground on the west side of the building. Manually operated valves allow the rerouting of potentially contaminated liquid to the 1,000 gallon holding tank. OERP Rev. 53 5-3 I i
i I l 5.3 OPERATIONAL SUPPORT CENTER )
^
The purpose of the Operational Support Center (OSC) is to minimize congestion in the Control Room during emergencies by providing a location, separate from the Control Room, where plant maintenance, operations, E&RC, and other plant emergency support personnel will assemble and stand by to assist as needed. The Operational Support Center is located in the O&M Building. When the OSC is activated, dosimetry, respiratory protection, radiation survey equipment, and RWPs will be provided. In the event of a personnel contamination, decontamination will be performed in the area normally designated for this purpose. In the event the OSC is evacuated, a backup can also be provided in the Simulator. The Simulator is within the habitability envelope of the TSC/ EOF. 5.4 EMERGENCY OPERATIONS FACILITY The Emergency Operations Facility (EOF), located on site provides space for management of overall emergency response including coordination with federal, state, and local officials, coordination of off-site radiological and environmental assessment, and determination of recommended public protective actions. *The EOF is activated at an alert or higher level. The EOF is in the same habitability envelope as the TSC. l If radiological conditions prevent EOF personnel from traveling to the EOF for activation, the Brunswick County Complex in Bolivia, N.C. will serve as a meeting place for personnel-until radiologichi conditions permit travel to the ! facility. l l l v OERP Rev.53 5-4
F 5.5 JOINT INFORMATION CENTER m The Joint Information Center (JIC), located in the Brunswick Community College Complex near Bolivia, N.C., will serve as the primary location for the accumulation of accurate and current information regarding emergency conditions, and dissemination of information to news media and the general public. The JIC Communications Network has back-up capability for telephone and radio functions. Work stations are provided for Company , personnel and a media briefing room is available. Telephones are provided j for use by news media personnel. The center also contains work space and j phones for public information personnel from the state, counties, NRC and industry-related organizations. Additionalinformation can be found in OPEP-02.6.29, Activation and Operation of the Joint Information Center 1 (JIC). j 5.6 OFF-SITE EMERGENCY FACILITIES l q 5.6.1 North Carolina Emergency Operations Center The North Carolina Emergency Operations Center (EOC) is located in Raleigh, North Carolina. When necessary, it will be activated and staffed to assist in coordinating emergency ) operations in support of the Brunswick Nuclear Plant. l i 5.6.2 Brunswick County Emergency Operations Center The Brunswick County Emergency Operations Center is located in the Brunswick County Administration Complex in Bolivia, North Carolina, about fifteen miles from the Brunswick site. It , provides a location where Brunswick County authorities can { direct off-site activities in Brunswick County. If radiological conditions prevent EOF personnel from traveling to the EOF for activation, the Brunswick County Complex in Bolivia, N.C. will serve as a meeting place for personnel until radiological ! conditions permit travel to the facility. This facility presently has l direct communications links with the Brunswick Nuclear Plant l TSC and EOF, and will allow free interchange of information between government officials and those persons located in the TSC and EOF responsible for dose projection and management decision making. I l- } OERP Rev.53 5-5
L 5.6 3 New Hanovar County Em rg:ncy Op: rations Center m The New Hanover County Emergency Operations Center is located in the New Hanover County Law Enforcement Center in Wilmington, North Carolina, about 20 miles from the Brunswick site. It provides a location where New Hanover County authorities can direct off-site activities in New Hanover County. This facility presently has direct communications links with the Brunswick Nuclear Plant TSC and EOF, and will allow free interchange of information between government officials and those persons located in the TSC and EOF responsible for dose projection and management decision making. 5.7 ASSESSMENT CAPABILITIES 5.7.1 General The instrumentation and control systems monitor, provide indication and recording, and automatically regulate the variables necessary for safe and orderly operation of the plant. These systems provide the operators with the information and controls needed to start up, operate at power, and shut down the plant. They further provide means to cope with all abnormal operating conditions.- Plant control and display of information from these various systems are centralized in the Control Room at locations
- convenient to the operator. This instrumentation, in conjunction with projected off-site doses, provides the basis for initiation of protective actions.
5,7.2 MeteorologicalInstrumentation and Procedures The Brunswick Nuclear Plant has a permanent meteorological monitoring station located on-site for display and recording of wind speed, wind direction, and temperature differences for use in making off-site dose projections, etc. Meteorological l information is presented in the Control Room by means of the plant computer system. The meteorological parameters , measured on the tower at the 10-meter and 100-meter levels 1 l' above ground are listed in Table 5.7-1. In addition, barometric L pressure, solar radiation, precipitation and dew point temperature data are recorded at the station to provide supplemental information on local meteorological conditions. This information is remotely interrogatable using a computer or other data access
- i. terminal.
v OERP Rev.53 5-6 L
Th3 met:orological sensors ustd ct th BNP metrorological monitoring station are calibrated at least twice during an annual >m calendar year (approximately six months between calibrations). Meteorological sensors which are removed from service are replaced with a recalibrated unit having met original equipment manufacturer specifications. Between calibrations, an electronic verification of system performance will be made and, if necessary, adjustments to the system will be performed. This electronic verification shall be performed at least once between calibrations. BNP personnel will make periodic visits to the monitoring station to assure that components are functioning as anticipated. Further checks of the data are made by remote , interrogation of the monitoring station by the staff of Murray and i Trettle, where the data is reviewed by the meteorological staff to f
^
determine system performance and the acceptability of the reported information. Historical records and data will be maintained with the Environmental Unit for effluent reporting. The meteorological instrumentation which Carolina Power & Light Company uses at the BNP meteorological monitoring i station meets the requirements of NRC Regulatory Guide 1.23 i (Rev. 0) and provides the meteorological parameters to the locations specified within NRC Regulatory Guide 1.97 (Rev. 2), Table 1 and Table 2. As specified within Section 8.2 of the Supplement Number 1 to NUREG-0737, CP&L maintains I telephone numbers for voice communications to the nearest National Weather Service, first order observation station I (Wilmington, NC) for twenty-four' hour per day access to this backup meteorological information should the on-site system fail. l This backup source of meteorological data is the closest location which can provide reliable representative meteorological information for the BNP site. Should the on-site meteorological data collection system exhibit suspect information, loss of data due to computer or instrument failure, or plant personnel require additional technical assistance, meteorologists are available to provide needed expertise. Meteorologists can independently access on-site meteorological data, contact the National Weather Service to obtain additional synoptic scale weather data and compile a site specific atmospheric diffusion assessment for BNP site. 1 I 0ERP Rev.53 5-7 l t
5.7.3 S@ismic Monitoring m The Brunswick Seismic Monitoring System senses and records earthquake ground motion received in two areas of the Reactor Building. The system is comprised of the following components:
- 1. Two peak shock recorders - remote sensing devices.
- 2. One multichannel accelograph - Model SMA-3.
- 3. One magnetic tape play-back unit - Model SMP-1.
The peak shock recorders measure and record the acceleration of the structure, primarily the concrete floors adjacent to the Reactor Building equipment drain tank and at the refueling elevation. Earthquakes produce low frequency accelerations which, when detected by the remote sensing devices, will be recorded at the remote location as well as by the accelograph located in the electronic equipment room. The Seismic Monitoring System remains in a standby condition until an earthquake causes the remote unit (s) to activate the recording circuits and tape transports. The peak shock recorder senses and permanently records the information defining a response spectrum, it also provides signals for immediate remote indication that specific preset response accelerations have been exceeded. A considerable array of seismomM . is located in the region. A central point of contact t vu.ain information about a seismic event is the Nationes Earthquake Information Center in Golden, Colorado. OERP Rev.53 5-8
7 5.7.4 RSdiological Monitors - l m .The Radiation Monitoring System is available to give early warning of a possible emergency and provides for a continuing evaluation of the emergency situation in the Control Room. L Radiation monitoring instruments are located at selected areas within the facility to detect, measure, and record radiation levels. In the event the radiation level should increase above a preset level, an alarm is initiated in the Control Room. Certain radiation monitoring instruments also alarm locally in selected areas of the facility. The Radiation Monitoring System is divided into four l subsystems:
- 1. Process Radiation Monitoring System monitors various fluid streams in operating systems. l
- 2. Area Radiation Monitoring System monitors radiation levels at various locations within the operating area that can be read in the Control Room.
- 3. Continuous air monitors measure airborne particulate and airborne iodine activities at various locations within the operating areas.
- 4. Radiation monitoring equipment with readouts in various
- plant locations and the HP office.
The types, ranges, and locations of monitors are listed in Tables 5.7-2 to 5.7-4. Typical portable radiation monitors are listed in Table 5.7-4.' The radiation monitors are designed to permit monitoring of activity releases during a broad spectrum of postulated emergency situations. The locations of the off-site and on-site environmental monitoring stations, and the location of the emergency TLD monitoring l stations are contained in plant Environmental and Radiation Control Procedures. v OERP Rev.53 5-9
$. i
L 5.7.5 ' Process Monitors ! m Instrumentation used to monitor vital plant parameters is described in Section 7 of the Brunswick FSAR. This I instrumentation is continuously monitored in the Control Room. Essential process monitoring (Critical Plant Variables) will also be available in the Technical Support Center. 5.7.6 Laboratory Facilities Support of the radiation monitoring and analysis effort is provided by an on-site laboratory. The on-site laboratory includes equipment for chemical analyses and for analysis of radioactivity. The wet chemistry equipment is used to perform a variety of analyses (pH, conductivity, boron content of reactor coolant, ] etc.). It is also used to perform radiochemical analyses (preparation of samples to permit analysis of the radioactivity content). Equipment used to analyze the type and amount of radioactivity in filters, smears, etc., is located adjacent to the chemistry lab. This includes a multichannel analyzer (Ge-Li) used to determine the isotopic content in a sample, a liquid scintillation counter for tritium analyses, and gas proportional counter for gross alpha, and gross beta activity. Much of this equipment is rack rhounted; some is readily I portable. Additional facilities for counting and analyses of Brunswick samples can be provided by laboratory facilities at the j Shearon Harris Energy and Environmental Center (SHEEC) j located near New Hill, North Carolina, by the Robinson Nuclear ! Plant, and by Babcock and Wilcox at the Lynchburg Research Center. As described in the State of North Carolina Radiological i Emergency Response Plan, the Division of Radiation Protection maintains a mobile radiologicallaboratory. OERP Rev. 53 5-10
I I Th3 NRC mobile I:boratory m y ba mada availabla for site and general emergencies. Parking space for the mobile laboratory is m reserved on the southeast corner of the fabrication shop (old ! firehouse). The building is located on the north side of the plant, west of the Rad Material Container Storage Building. A 120 VAC receptacle box is mounted on the east exterior wall and is reserved for the mobile laboratory. The Radiological Control Director shall coordinate setting up of the mobile laboratory. 5.7.7 Dose Projection The magnitude of releases of radioactive material can be determined from effluent and process monitors based on OPEP-03.4.7, Automation of Off-Site Dose Projection Procedures. Additionally, an independent confirmation of the i magnitude of a release can be obtained by environmental ' monitoring as described in OPEP-02.6.6, Environmental l Monitoring Team Leader and OPEP-03.5.5, Environmental ' Monitoring and Plume Tracking. Given a source term, or the duration and rate of release to the environment, and meteorological data previously described, the Control Room can ; make the initial dose projections and is capable of performing ! this function on a 24-hour-per-day basis. After activation of the ' EOF, the Radiological Control Manager described in l Section 3.5.4 is responsible to the Emergency Response '
~
Manager for determining dose projections from readily available j data. OPEP-03.4.7, Automation of Dose Projection Procedures, i describe computer programs which automate dose projection calculations when used in conjunction with the BNP ! meteorological systems. 5.8 FIRE DETECTION The Fire Detection System is designed to quickly detect visible or invisible smoke (or other products of combustion) and/or heat in designated areas of the plant. The Fire Detection System consists primarily of fire detectors, control panel units, and annunciator panels. A fire signalinitiated by a detector flows through a control panel unit to an annunciator panel. The control panel unit is located in the same building as the detector. The annunciator panelis located in the Control Room. l 0ERP Rev.53 5-11
h Tha types and numb:r of d;t:ctors hav3 b:en s l:cted in accordance with the combustible materials and electrical equipment present in the area and m the physical surroundings of each area. lonization detectors sense the presence of products of combustion before they are visible in the form of smoke. Thermal detectors are sensitive to both temperature and the rate of rise of increasing temperature. SD-42 provides a description of detector types, numbers, and locations. 5.9 PROTECTIVE FACILITIES AND EQUIPMENT OPEP-04.6, Radiological Emergency Kit inventories, lists emergency equipment that is available for the various Brunswick emergency facilities. j Complete personnel decontamination facilities are included in the Service Building. These facilities include two decontamination showers. Alternate i means for decontamination are also available. 5.10 FIRST AlD AND MEDICAL FACILITIES First Aid is located on the first floor of the O&M Building. First aid kits and i supplies are also placed at various locations throughout the plant. Off-site medical facilities which have agreed to accept personnel are described in Appendix E, Medical Treatment and Assistance. 5.11 DAMAGE CONTROL EQUIPMENT AND SUPPLIES in the event of an emergency, certain immediate repairs may be necessary ! to minimize the further release of radioactivity and also insure the protection of plant equipment. Damage control equipment and supplies that would be used to effect repair would depend on the nature of the repairs to be performed. Damage control equipment and supplies are located in the stockroom and the maintenance shops. i i v OERP Rev.53 i 5-12 l
5.12 OFF-SITE ENVIRONMENTAL MONITORING EQUIPMENT AND SUPPLIES s l . In the event of an emergency, the plant has the capability to deploy two 3 off-site environmental monitoring teams as described in OPEP-02.6.6, Environmental Monitoring. Team Leader. Two environmental monitoring kits i with the necessary equipment and supplies for off-site radiological monitoring are designated for use in the event of an emergency. . Transportation for off-site environmental monitoring teams will be supplied I by plant vehicles and other Company trucks as available or private autos at J the site. l I l 1 OERP Rev.53 5-13
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TABLE 5.7-1 n ON-SITE METEOROLOGICAL INSTRUMENTATION l Approximate Height . Recorded Above Tower Bas ~ e (ft) : Parameter Instrument 344 Windspeed, direction . Threshold less than and direction variance 1 mph. 35 Windspeed, direction, Threshold less than
- and direction variance' 1 mph.
344 Temperature difference Resistance thermobulb relative to 35 ft in aspirated radiation elevation shield at 344 and 35 ft elevation. 35 Ambient temperature Resistance thermobulb in aspirated radiation shield at 35 ft elevation. I
-s.
OERP-- Rev.53 5-16
r TABLE 5.7-2 AREA RADIATION MONITORING SYSTEM
^ CHANNEL IDENTIFICATION & METER RANGES Range Detector Channel (mrem /hr) Desianation Location (Blda.)
1-1 0.01 -100 Control Room Operating Area Control 1-2 0.01 -100 U-2 Electronic Equipment Room
- Control 1-3 0.01 .100 U-1 Electronic Equipment Room
- Control 1-4 0.01 - 100 Stack Filter House Stack
.1-5 0.01 -100 Service Bldg. Radiochemical Lab. Service 1-6 0.01 -100 Service Bldg. Locker Room Service 1-7 0.1 -10 Hot Machine Shop Service 1-8 0.01 -100 Service Bldg. Laundry Service 1-9 0.01 -100 U-1 Turb. Hall Control Access Turbine Corridor 1-10 0.01 - 100 U-1 FW Heater Bay Access Corridor Turbine 1-11 0.01 -100 U-1 Turb. Bldg. Sampling Station Turbine 1-12 0.1 -10 U-1 Turb. W Moist Sep. Drain Tanks Turbine I 1-13 0.1 -10' U-1 Turb. E Moist Sep. Drain Tanks Turbine l 1-14 0.1 -10 U-1 Turb. Rotor Washdown Area Turbine ;
1 1-15 0.1 -10 1 A Core Spray Pump Room ESS 1 Reactor 1-16 0.1 -10 1B Core Spray Pump Room ESS 11 Reactor
- Detectors are located in mechanical equipment room (Control Building ventilation air intake plenum)
R OERP Rev.53 5-17 l
l. TABLE 5.7-2 (Cont'd) AREA RADIATION MONITORING SYSTEM n CHANNEL IDENTIFICATION & METER RANGES Range Detector Channel -(mrem /hr) Desianation Location (Blda.) i 1-17 0.1 -10' 1 A RHR System Hx and Pump Room Reactor ESSl 1-18 0.1 -10 1B RHR System HX and Pump Room ' Reactor l ESSil 1-19 0.01 -100 U-1 Rx Bldg. Airlock Area EL 20 ft. Reactor 1-20 0.01 - 100 U-1 Drywell Entrance Reactor - l 1-21 1.0 -10? ' U-1 TIP Room Reactor L 1-22 0.01 - 100 U-1 Decontam. Room EL 20 ft. Reactor 1-23 0.01 -100 U-1 Equipment Entry EL 20 ft. Reactor 1-24 0.01 - 100- . U-1 Rx Bldg. Sampling Station Reactor
~- 1-25 0.01 -100 U-1 Rx Bldg. Air Lock EL 50',8" Reactor 26 0.01 -100 U-1 New Fuel Vault EL 98'; 9" Reactor 1 0.01 -100 - U-1 North of Fuel Storage Pool Reactor
.1-28 102 -10' U-1 Between Rx and Fuel Pool Reactor EL 117- ft.,4 in.
1-29 0.01 -100 U-1 Cask Wash Area Refuel Floor- Reactor l
.1-30 0.01 - 100 U-1 Spent Fuel Pool Cooling Reactor System l
I J l OERP Rev.53 5-18 ! I i l
TABLE 5.7-2 (Cont'd) l AREA RADIATION MONITORING SYSTEM Lm CHANNEL IDENTIFICATION & METER RANGES
. Range Detector Channel (mrem /hr) Desianation Location (Blda.)
2-1 0.1.-10 2 Radwaste Bldg. EL 3 ft. Radwaste N MCC and Sump Area 2-2 0.1 -10' .Radwaste Bldg. EL 3 ft. Radwaste S MCC and Sump Area 2-3 0.1 -10' U-2 Cond Filter - Demin Aisle - Radwaste 2-4 0.1 $ U-1 Cond Filter- Demin Aisle Radwaste 2-S 0.01 -100 Radwaste Control Room Radwaste 2-6 0.01 -100 Radwaste Sampling Station Radwaste d 2-7 0.01 -100 Radwaste Drum Capping Station Radwaste 2-8 1.0 -10" Radwaste Drum Storage Radwaste 9 0.01 -100 U-2 Turb. Hall Access Corridor Turbine - 2-10 0.01 -100 U-2 FW Heater Bay Access Corridor Turbine 2-11 0.01 -100 U-2 Turb. Bldg. Sampling Station Turbine 2 12 0.1 - 1 08 U-2 Turb. W Moist Sep Drain Tanks Turbine i 2-13 0.1 - 1 08 U-2 Turb. E Moist Sep Drain Tanks Turbine 2-14 0.1 -10 U-2 Turb. Rotor Washdown Area Turbine 2 0.1 -10 5 2A Core Spray Pump Room ESS I Reactor 2-16 0.1 -10 2B Core Spray Pump Room ESS ll Reactor v j OERP Rev.53 5-19
m TABLE 5.7-2 (Cont'd)
/ AREA RADIATION MONITORING SYSTEM l
i m CHANNEL IDENTIFICATION & METER RANGES 7 Range Detector l- Channel (mrem /hr) Desianation Location (Blda.) 17 0.1 - 1 02' 2A RHR System Hx and Pump Room Reactor ESSI 2-18 0.1 10 e 2B RHR System Hx and Pump Room Reactor ESS11 2-19 0.01 -100 - U-2 Rx Bldg. Airlock Area EL 20 ft. Reactor 2-201 0.01 -100 U-2 Drywell Entrance - Reactor 2-21 1.0 -10' U-2 TIP Room - Reactor l 2-22 0.01 -100 U-2 Decontam. Room EL 20 ft. Reactor 2 0.01 -100 - U-2 Equipment Entry EL 20 ft. Reactor 2 0.01 -100' U-2 Rx Bldg. Sampling Station Reactor s 2-25 0.01 -100 U-2 Rx Bldg. Airlock EL 50 ft. Reactor i 2-26' O.01'-100 U-2 Inside New Fuel Vault
- Reactor EL 98 ft. 8 in.
2 0.01 -100 U-2 North of Fuel Storage Pool Reactor 2-28 1 02 - 10' - U-2 Between Rx and Fuel Pool Reactor i EL 117 ft. 4 in. I 2-29 0.01 -100 U-2 Cask Wash Area Refuel Floor Reactor l
' 2-30 '- 0.01'-100. U-2 Spent Fuel Pool Cooling System- Reactor 'J i
OERP Rev, 53 5-20
[, TABLE 5.7-3 M PROCESS RADIATION MONITORING SYSTEM CHANNEL IDENTIFICATION & METER RANGES
' Channel Supplier Ranae Main Steam Line Radiation Monitors GE- 1-10' mrem /hr Channel A (D12-RM-K603A) i L Channel B (D12-RM-K603B)
L Channel C (D12-RM-K603C) Channel D (D12-RM-K603D) Condenser Off-Gas Radiation Monitors _ GE ' Log Channel A (D12-RM-K601 A) 1-10' mrem /hr Log Channel B (D12-RM-K601B) Linear _ Channel (D12-RM-K602)
- Main Stack Radiation Monitors General 10~7-1 05 pCi/cc l~ Atomics (Xe equivalent) l Liquid Process Radiation Monitors GE Radwaste Effluent (D12-RM-K604) 10410' cps Service Water Discharge (D12-RM-K605) !
Reactor Bldg Closed Cooling Water (D12-RM-K606) Reactor Bldg Ventilation Radiation Monitors Channel A (D12-RM-K609A) GE 0.01-100 mrem /hr l Channel B (D12-RM-K609B) GE Gaseous Analyzer Radiation Monitors Reactor Building Roof Vent (CAC-AQH-1264) NMC 10-105 cpm i Turbine Building Vent General , 5 (D12-RM-23) Atomics 10-7-10 Ci/cc l l (Xe equivalent) I L( Drywell Primary Containment Atmosphere l' (CAC-AQH-1260,1262) NMC !
)
OERP Rev.53 5-21 l L
W ! TABLE 5.7-4 L ^- ~. TYPICAL PORTABLE SURVEY EQUlPMENT l l Type Of . l , Radiation Tyce. Ranae Measured Teletector 0.1 mrem /hr-1000 Rem /hr y Eberline RM-14 Radiation 0 - 50,000 cpm p,y Monitor - R07 1 mr/hr - 20,000 r/hr p,y R02 0 - 5000 mr/hr p,y R02A 0 mr/hr - 50 r/hr p,y R020 0 mr/hr - 50 r/hr p,y BICRON Micro Rem O - 200,000 pr/hr y ASP-1 With Neutron Ball 0 - 100 Rem /hr n E530N 0 mrem /hr - 20 R/hr y v 1 OERP Rev.53 5-22 t l L
BRUNSWICK NUCLEAR PLANT RADIOLOGICAL EMERGENCY PLAN m 6.0 MAINTAINING EMERGENCY PREPAREDNESS Emergency preparedness at Brunswick will be maintained by (a) preparing the emergency organization members and the public for proper emergency response actions through training, drills and exercises, and public education programs (Section 6.1); (b) periodic review and update of the Brunswick Radiological Emergency Plan and its implementation procedures (Section 6.2); (c) periodic inventory and calibration of emergency equipment and instrumentation (Section 6.3); and (d) cognizance of the Plant Nuclear Safety Committee over safety-related issues (Section 6.4). The Supervisor- Emergency Preparedness is the Emergency Planning Coordinator and is responsible for maintaining Emergency Preparedness at the Brunswick Nuclear Plant, as outlined in Section 6.1.3. Each periodic requirement in this section and elsewhere in the plan and plant emergency procedures shall be performed within the specified time below:
- a. Annually - At least once per 366 days
- b. Monthly - At least once per 31 days
- c. Quarterly - At least once per 92 days
- d. Semiannually - At least once per 184 days For the above intervals, a maximum allowable extension is permitted subject to the following restrictions:
- The maximum allowable extension shall not exceed 25% of the specified interval.
- The combined time interval for any three consecutive intervals shall not exceed 3.25 times the specified interval.
l 1 l 1 OERP Rev.53 6-1
p This d:finition for p:;riodic r.:quirem:nts appli;s to all int:rv::Is in tha cmarg:ncy plan and plant emergency procedures except for the evaluated exercise which is m conducted once every two calendar years, and off-site training which is conducted once per calendar year. 6.1 ORGANIZATIONAL PREPAREDNESS Organizational preparedness is maintained through an integrated training program that includes general orientation of all persons at the site and detailed training of individuals and groups required to perform specific functions and actions during an emergency condition. The training program ; provides initial training and annual retraining of the emergency response organization. Significant changes in the content of this Plan and procedures which implement this Plan are distributed by memorandum to the ' appropriate plant groups, 6.1.1 Training ! The primary objectives of the training program are to:
- 1. Familiarize appropriate individuals with the Plan and the procedures that implement the Plan. ;
- 2. Instruct assigned individuals and their alternates in their duties and responsibilities.
- 3. When appropriate, train on significant changes in the scope or contents of the Plan or procedures which implement the Plan.
- 4. Provide annual refresher training and retesting to ensure that Emergency Plan personnel are familiar with their duties and responsibilities assigned by the Plan and procedures which implement the Plan.
Each individual, other than escorted personnel, is provided with initial orientation training on the notification and instruction methods used at the Brunswick plant in the event of an emergency. Each badged individual, other than escorted personnel, also receives initial orientation on the basic principles of radiological safety including the effects of radiation and the theory and use of radiation detection devices. Appropriate actions for escorted l individuals shall be the responsibility of the escort. I a OERP Rev.53 6-2
p 1 Th3 Em:rgancy Plan Training Program described in OPEP-04.3 L assures training of those individuals who may be called to !m respond to an emergency at the Brunswick plant by providing ) initial training and annual refresher training and retesting on the scope and content of the Plan and procedures which implement the Plan. l The Emergency Plan Training Program provides training for the following groups of personnel to perform the specific tasks ! assigned to them in the emergency organization. Site Emergency Coordinator TSC Staff Personnel Security Personnel Fire Brigade Personnel L Dose Projection Personnel
- Radiological Emergency Teams Emergency Communicators EOF Personnel' OSC Personnel 1 JIC Personnel Plant Operators Off-site groups who may be requested to assist in an emergency.
Training of off-site organizations is described in their radiological ls emergency plans. Training by CP&L for hospital, ambulance, rescue, police, and fire personnel will include the procedures for notification, basic radiation prote'ction, and their expected roles. For those local services support organizations who may enter the i site, training by CP&L will also include site access procedures and the identity (by position and title) of the individual in the Brunswick organization who will control the organization's l support activities. Carolina Power & Light Company will assist these off-site organizations in performing their radiological emergency response training as related to the Brunswick plant. Carolina Power & Light Company, and the public information officials from the state and local governments willjointly make available an annual program to acquaint the news media with the company, state and county emergency plans and procedures. The program also includes information concerning radiation, nuclear plant operations and official points of contact for release of public information. i Severe Accident Management training and drills will be conducted in accordance with Severe Accident Management Program and Training Procedures. OERP Rev 53 6-3
6.1.2 Drills and Excrcises m This section describes provisions for conducting periodic drills
.. and exercises to test the adequacy of the Plan and implementing procedures, emergency equipment, and the preparation and training of emergency personnel.
Each exercise scenario will include the following:
- 1. The basic objective (s) of the exercise.
- 2. .The date(s), time period, place (s), and participating organizations.
- 3. The simulated events.
- 4. A time schedule of real and simulated initiating
- events.
- 5. A narrative summary describing the conc :t of the exercises to include such things as simulated casualties, off-site fire or police department assistance, rescue of personnel, use of protective clothing, deployment of radiological monitoring teams, and public information activities.
- 6. Arrangements for qualified observers.
6.1.2.1 Drills Emergency drills are supervised instruction periods aimed at testing, developing and maintaining skills, and to ensure that adequate emergency response capabilities are maintained during the interval between evaluated exercises. Periodic drills will be conducted, in addition to the evaluated exercise as follows:
- 1. General: At least one drill shall be conducted during the interval between evaluated exercises involving a combination of some of the principal functional areas of the organization's onsite ernergency response capabilities. The principal functional areas of emergency response include activities such as J
OERP Rev.53 6-4
manag:m:nt cnd coordination of em::rg:ncy response, accident assessment, protective action m decision making, and plant system repair and corrective actions. During these drills, activation of all of the emergency response facilities (Technical Support Center (TSC), Operations Support Center (OSC), and the Emergency Operations Facility (EOF))is not necessary. Participants have the opportunity to consider accident management ! strategies, supervised instruction is permitted, and participants have the opportunity to resolve problems (success paths) rather than have controllers intervene. The drills focus on onsite training l objectives. 1
- 2. Communications Drills: A system to test the '
readiness of the communications network between the plant and state and county governments within I the ten-mile EPZ and the NRC will be conducted monthlv. Communications between the plant, federal emergency response organizations, and states within the 50-mile EPZ will be tested auarteriv. ] Communications between the plant and state and local emergency operation centers and field assessment teams shall be conducted annually.
- 3. Fire Drills: Fire drills will be conducted in accordance with the Fire Protecti6n Program.
- 4. Medical Emeraency Drills: Medical emergency drills involving a simulated contaminated individual will be ;
conducted annually. The actual off-site portions of these drills may be conducted once per calendar year.
- 5. Radioloaical Monitorina Drills: Radiological monitoring drills will be conducted annually. These drills will include collection of the appropriate sample media both on site and off site as the drill scenario requires.
OERP Rev.53 6-5
F 1 i ! 6. In-Plant Radiation Prot *ction Drills: Radiation
- protection drills, including response to and analysis of
!m simulated elevated airborne and liquid samples and j direct radiation measurements will be conducted semiannually. This may be held in conjunction with the Radiological Monitoring Drills.
- 7. Auamentation drills: Augmentation drills requiring travel to the site shall be conducted once every 24 months.
- 8. SAMG drills: Severe Accident Management Guideline table-top and/or inter-facility mini-drills will be conducted periodically and will involve a combination of some of the principal functional areas of the organization's onsite emergency response l capabilities similar to that desenbed in General drills (6.1.2.1.1) above.
The above drills will be evaluated by a drill observer (communication drills will not require an observer). The degree of participation by outside agencies in conducting these drills may vary and their action may actually be simulated. Any state or local government located within the plume exposure pathway EPZ will be allowed to participate in the drills when requested by such State or local government. 6.1.2.2 Exercises An exercise is an event that tests the integrated capability of major response organizations. An emergency exercise will be conducted once every two calendar years and will I be based on a scenario which is ultimately declared at least as a Site Area Emergency. The scenario will be varied from exercise to exercise such that all elements of the j plant, county, and state plans and emergency i organizations are tested within a 6-year period. One ) exercise shall start between midnight and 6:00 a.m. and another between 6:00 p.m. and midnight once every six years. Every sixth year, the exercise will be expanded to allow involvement of the federal response organizations in addition to the state and local organizations. Advance , knowledge of the scenarios and the times of the exercises l will be kept to a minimum to ensure a realistic participation i i by those involved. ! 0ERP Rev.53 6-6
i Each ex:rcise sc:nario will includo a list of performance objectives and a description of the expected responses.
- Specific tasks to be evaluated are:
- 1. Condition recognition and reporting
- 2. Assessment i
- 3. Off-site notification, including CP&L off-site personnel l and protective action recommendations
- 4. Off-site response .
1
- 5. Site response coordination, including logistics, center manning, information gathering and j analysis, and coordination with off-site agencies
- 6. Corrective actions
- 7. Protective actions
- 8. Record keeping
- 9. Monitoring
- 10. Plant operation Qualified observers from C'P&L, federal, state, or local governments will observe and critique each exercise. A critique will be scheduled at the conclusion of each exercise to evaluate the ability of all participating organizations to respond. The critique will be held as soon as possible after the exercise. A formal written evaluation of the exercise will be prepared by the Emergency Planning Coordinator, or his designee, following the critique.
Exercise controllers, observers, and participants (if appropriate) will prepare written descriptione of the actions they observed and will comment as to how the part of the exercise they observed matched the performance criteria. The Emergency Planning Coordinator or his designee will determine the corrective actions necessary and the schedules for performing them and will evaluate the corrective actions taken. l OERP Rev.53 6-7
o Ram: dial exarcisas will ba required if the emnrgency plan i is not satisfactorily tested during the biennial exercise, such I^- that NRC, in consultation with FEMA, cannot find l reasonable assurance that adequate protective measures i can be taken in the event of a radiological emergency. The extent of State and local participation in remedial exercises j must be sufficient to show that appropriate corrective measures have been taken regarding the elements of the plan not properly tested in the previous exercises. , 6.1.3 Emergency Planning Coordinator The Supervisor - Emergency Preparedness is the Brunswick Emergency Planning Coordinator. He is responsible for coordinating on-site and off-site radiological emergency response planning. Specific responsibilities include the following:
- 1. Interfacing with federal, state, county, and local planners.
- 2. Revising and updating the Plan in response to I new federal regulations, modifications identified during exercises and drills, and changes in hardware and personnel.
- 3. Coordinating the evaluated exercise and the periodic drills.
- 4. Identifying off-site training needs of state and local emergency support personnel and arranging for training to meet the identified needs.
- 5. Identifying corrective actions needed following an exercise, assigning responsibility for implementing these actions, specifying a schedule for completion of these actions, and evaluating the adequacy of the actions taken. These corrective actions can be tracked by means of the Corrective Action Program.
I
- 6. Maintaining and negotiating agreements with state and county response agencies, federal assistance agencies, and medical and fire support agencies.
l v OERP Rev.53 6-8
L
- 6.1.4 Public Education !
l~ m The North Carolina Department of Crime Control and Public Safety has overall responsibility for maintaining a continuing ! disaster preparedness public education program. Such a l program, prepared by the State of North Carolina, with the l cooperation of local governments and CP&L, is intended to ensure that members of the public are: , (1) Aware of the potential threat of a radiological emergency; (2) Able to recognize radiological emergency notification; and (3) Knowledgeable of the proper, immediate actions (e.g., return to home, close windows, and tune to an Emergency Broadcast System station) to be taken. A program of this type includes education on protective actions to be taken if shelter is prescribed, and the general procedures to follow if an evacuation is required. It also includes general educational information on radiation and how to learn more about emergency preparedness. Additionalinformation concerning public education can be found in Section 4.4.7. 6.2 REVIEW AND UPDATE OF THE PLAN AND IMPLEMENTATION PROCEDURES The Plan and its implementation procedures are intended to provide for continuous emergency preparedness. In addition to the training, drills, and exercises, regular reviews and audits are performed. The reviews and audits are described in the following sections. l 1 l 1 OERP Rev.53 6-9
6.2.1 Plan Updates m The Emergency Planning Coordinator is responsible for coordinating the updating of the Plan and implementing
- procedures. He schedules an annual review of the Plan by the l
Plant Nuclear Safety Committee (see Section 6.4). Any proposed changes to the Plan due to regulatory revisions, experiences of drills and exercises, or other requirements are approved by the Supervisor - Emergency Preparedness. Approved changes to the Plan will be distributed to organizations and individuals with responsibility for implementation of the Plan. Revised pages will be marked to show revision numbers and where changes have been made. Phone listings in emergency procedures shall be updated quarterly, if required. 6.2.2 Independent Audit and Review In addition to the reviews conducted at the plant, an independent audit of the Plan will be conducted every year by the Nuclear l Assessment Section. Written reports of the findings of these audits and reviews will be provided to Corporate Management. Each report will specifically address the adequacy of interfaces with state and local governments, of drills and exercises, and of emergency response capabilities and procedures. The reports will be retained for five years. Corrective actions deemed necessary from the audit will be implemented similarly to those l required by the annual review (see Section 6.2.1). 6.2.3 Off-Site Agreements and Plans l Emergency response plans and agreements with supporting i organizations are reviewed and updated by the cognizant organization at least every two years and incorporated in the annual revision. 6.3 MAINTENANCE AND INVENTORY OF EMERGENCY EQUIPMENT AND l SUPPLIES 1 l To ensure that equipment and supplies are maintained in a readiness state, periodic maintenance and inventories are performed as described in the following sections. l 1 a OERP Rev.53 6-10 L
6.3.1 Emargency Equipment and Supplies l m A listing of emergency equipment and supplies to be inventoried i is included in OPEP-04.6. This listing provides information on l location and availability of emergency equipment and supplies. b An inventory of emergency equipment and supplies is held in accordance with OPEP-04.6. During this inventory, radiation monitoring equipment is checked to verify that required calibration and location are in accordance with the inventory lists. Respiratory protection equipment, maintained for emergency purposes, is also inspected and inventoried. 6.3.2 Medical Equipment and Supplies l At least twice each year and after use in an emergency, the l contents of emergency medical equipment and supplies located in the First Aid Office is to be inventoried, inspected, replaced, replenished and/or resterilized as necessary. Company personnel inspect and inventory emergency medical supplies required to support a medical emergency at the plant. 6.4 PLANT NUCLEAR' SAFETY COMMITTEE The Plant Nuclear Safety Committee (PNSC) is a standing committee comprised of Brunswick plant personnel that provides timely and continuing review of plant operations to assist the Plant General Manager in maintaining cognizance of plant activities, with particular emphasis on j safety-related matters. l l The PNSC reviews all changes to the plant, or its documentation, that involve unreviewed safety questions. In addition, the PNSC reviews plant operations to detect any potential safety hazards. Each plant supervisor will ! monitor the activities within his areas of responsibility to detect unsafe practices, trends, or hazards. Also, the PNSC investigates and reports on Technical Specification violations or other situations involving safety. l l \" l OERP Rev.53 6-11
BRUNSWICK NUCLEAR PLANT RADIOLOGICAL EMERGENCY PLAN LA 7.0 ; RECOVERY l~ I
- 7.1 . GENERAL -
Once the Site Emergency Coordinator has declared that the emergency-condition has passed, steps will be taken to recover from the incident. The L Emergency Response Manager will advise appropriate organizations that l- recovery activities are initiated and that the Recovery Organization as l shown in Figure 7.2.1 will be assembled in the EOF. All recovery actions l will be preplanned in order to minimize radiation exposure or other hazards l to recovery personnel. Recovery activities are classified as described in i Sectio'n 7.3. The overall goals of the recovery effort are to assess the radiological consequences of the emergency and perform cleanup and repair operations , necessary to restore normal access to the affected areas or identify and restrict access to those areas that must be controlled. This effort includes l marshaling of the Corporate resources and interfacing with outside agencies. 7.2 ' RECOVERY ORGANIZATION l
- The recovery organization consists of the Recovery Manager, managers of support functions who are responsible to the Recovery Manager, and supporting personnel. This organization mdy be modified during the recovery process to better respond to the conditions at the plant. Recovery activities will be directed from the Recovery Center.
The Recovery Center at Brunswick will be established in the existing , l TSC/ EOF / Training Building. Provisions have been made for expansion into : I the BNP Technical and Administration Center (TAC Building), if required to support an extensive recovery effort. l l l . l l l 1 i l v ; OERP Rev.53 7-1 i
Activation of tha recovery organization will be initiated by the Vice President
- Brunswick Nuclear Plant (or his alternate) after consultation with the Plant ^ General Manager (or his alternate). The recovery organization will then be established at Brunswick to provide for recovery of the facility. The recovery organization may begin to develop plans for recovery of the facility while the emergency is still in progress. However, these efforts will not be permitted to interfere with or detract from the efforts to control the emergency situation. During the emergency phases of the incident, the recovery organization resources will be available to assist and provide support for the Site Emergency Coordinator. A block diagram of the typical recovery organization is presented in Figure 7.2-1.
Table 7.2-1 indicates the personnel designated to assume responsibility of-each of the activities shown in the block diagram. 7.2.1 Recovery Manager The Recovery Manager is the senior position responsible for all on-site activities during'the recovery phase following a radiological emergency. He is also responsible for providing the primary interface with State, local and Federal agencies including the coordination of CP&L resources during off-site recovery efforts. 'The specific responsibilities of this position are contained in OPEP-02.7, Recovery. 7.2.2 Plant General Manager The Plant General Manager is rssponsible to the Recovery Manager for implementation of in-plant activities during the Recovery phase with the objective of maintaining a safe shutdown condition and controlling sources of radioactivity in the plant. The specific responsibilities of this position are contained in OPEP-02.7, Recovery. 7.2.3 Technical Analysis Manager The Technical Analysis Manager, is responsible to the Recovery Manager for technical support, specifically in the analysis and development of plans and procedures to support recovery activities and to maintain the affected unit in a safe shutdown condition in a manner which minimizes the effect on the health and safety of the public. The specific responsibilities of this position are contained in OPEP-02.7, Recovery. w OERP Rev.53 7-2
'7.2.4 Engineering Manager m The Engineering Manager, is responsible to the Recovery Manager for directing and administratively controlling the CP&L recovery organization engineering staff while providing engineering, including civil, and design support to meet requirements of the recovery activities. The specific responsibilities of this position are contained in OPEP-02.7, Recovery.
7.2.5 Administrative and Logistics Manager The Administrative and Logistics Manager, is responsible to the Recovery Manager for providing administrative, logistic, communications, and personnel support for recovery activities. The specific responsibilities of this position are contained in OPEP-02.7, Recovery. 7.2.6 Radiological Control Manager The Radiological Control Manager, is responsible to the Recovery Manager for providing radiation protection and waste disposai plans to support recovery activities. The specific responsibilities of this position are contained in OPEP-02.7, Recovery. 7.3 RECOVERY PLANNING l For convenience in planning, the recovery activities can be classified as. l follows: 1
- 1. On-site recovery )
- 2. Off-site recovery 7.4 ON-SITE RECOVERY ACTIVITIES ,
On-site recovery activities are performed in accordance with existing plant procedures. Radiation and contamination levels for determining the need for decontamination and for returning areas or items to normal use are l l included in these procedures. Additional procedures will be developed as appropriate on a case-by-case basis. l l OERP Rev.53 7-3 l-1 1
7.5 OFF-SITE RECOVERY ACTIVITIES 1 m .7.5.1 General The CP&L Recovery Manager will coordinate with and assist i off-site agencies in the recovery activities. 1 1 ! The State will be the lead organization for off-site recovery activities and put emergency regulations into effect to ensure that no food items in the contaminated area are consumed or put on , I the mnrket without the required health physics monitoring, and to control access into contaminated areas. Authorization for reentry to off-site areas will be made by the senior elected official of the area concerned after consultation with the North Carolina Division of Radiation Protection. 7.5.2 Emergency Cleanup Operations The most urgent tasks will be to clear (i.e., partially l decontaminate) emergency paths to allow access to critical facilities and inhabited areas. These clearing operations will be necessary particularly to:
- a. Allow health physics teams to survey the contaminated areas, t
- b. Allow farmers to provide emergency care for livestock that had tobe left in contaminated areas or i to assist them in moving the stock to uncontaminated areas.
- c. Allow emergency operations of utilities and j services (power, water, telephone, sewage treatment, etc.) during the cleanup operation, and ;
l d. Allow decontamination teams to perform the l emergency and priority decontamination tasks (these emergency tasks will consist primarily of fire-hosing i pavements, plowing or scraping unpaved areas adjacent to roads, and spraying paint or asphalt to fix loose contamination in place). 0ERP Rev.53 74 1
0 1 l- e. Stabiliza the contaminated arcas so that the I- radioactive materials are not spread to other areas or
^ leached into streams. In particular, if public roads run through the area, cleanup of the road will be required, and cleanup of the area to some distance from the road will be needed to minimize exposure to travelers.
After the main roads and utilities have been put back into service, the urgency of the cleanup tasks will drop. However, the population that was evacuated will be eager to return, and industrial operations that had to be shut down need to start up as soon as possible, and business operations need to be resumed. i Some farmland may have to be removed from use, which would ! cause hardship primarily to the occupants. Thus, it may be i feasible to permanently evacuate such areas and pay the owner ; the market value. Such a step would probably occur at ! contamination levels where future crops would not be marketable due to the uptake of long-lived isotopes (primarily strontium).
' Some of the buildings and houses may be contaminated to such a high level that it is more economical to demolish them than to decontatninate them. Areas where this occurs can be kept ,
vacated; in such cases, demolition and burial can be a routine l task, and the work can be scheduled over a longer period of ! time. Decontamination of the agriculturalland may or may not j be feasible. Where it is feasible, the changes in agricultural operations that are required can'be made on a routine basis. 7.5.3 Countermeasures * ; Countermeasures will have serious impact on the economy of contaminated areas, so they must be applied judiciousiy. They must be no more restrictive than necessary; however, once determined, they will be applied quickly and equitably, and may consist of:
- a. Reducing contamination on the surface of any fruits and vegetables that were in the field at the time of the accident by ensuring that the surfaces are washed, that the outer leaves of leafy vegetables are removed, and that more than normal preference is given to peeling.
l
- J. A. Auxier and R. O. Chester, eds., Report of the Clinch Valley Study, ORNL-4835
- _(January 1973).
OERP Rev.53 7-5 l
F l
- b. . Alt:: ring production, proc:ssing, or distribution
- l. practices that affect the movement of radioactive
! m, contamination through food chain and into the human , body. This willinclude storage of some food , (primarily milk products) and animal feed supplies to allow radioactive decay--particularly of lodine 131.
- c. Diverting affected products to uses other than human consumption.
- d. Condemning food.
- e. Decontaminating farmland where practical.
- f. Converting farmland to other uses for extended periods of time when decontamination is not practical.
- g. Decontaminating industrial buildings, stores and shops, and residences and removing milk-producing cattle from the contaminated pastures should be priority items. The longer these activities are delayed, the greater will be the costs and consequently the claims 7.5.4 Monitoring and Dose Assessment
, The North Carolina Division of Radiation Protection (DRP), 1 Department of Environment Health and Natural Resources, will be the lead agency in the collection and analysis of radiation monitoring reports and of environmental air, foliage, food, and water samples._ The DRP will be assisted by qualified personnel
- from the BNP, and the General Electric Company Wilmington
! Manufacturing Division. Total population exposure will be periodically determined through a variety of procedures including:
- a. Examination of prepositioned TLDs,
- b. Bioassy.
L c. Estimates based on release rates and I meteorology.
- d. Estimates based on environmental monitoring of l food, water, and ambient dose rates.
I l
. J OERP Rev.53 7-6
TABLE 7.2-1 , DESIGNATION OF KEY RECOVERY ORGANIZATION PERSONNEL m , Recovery Manager. -
.1. Vice President - Brunswick Nuclear Plant
- 2. Director- Site Operations Plant General Manager:
- 1. Brunswick Plant General Manager Technical Analysis Manager:
- 1. Manager- Regulatory Affairs Engineering Manager:
~1. - Manager - Brunswick Engineering Support l Manager.- Administrative and Logistics: !
i
- 1. - Manager - Site Support Services
. Radiological Control Manager:
- 1. Manager - E&RC -
l l [. h O l- OERP- Rev.53 7-7 L:
1 CORPORATE
- % MANAGEMENT REGULATORY -
AGENCIES l i j RECOVERY CORPORATE
' MANAGER. SPOKESMAN 1 l
- l. .: .
l l
; 1
., i.
STATE CP&L_ !
-{ l ';
-I. I-l JOINT j _ INFORMATION
. . . . . . . . ... CENTER I
~
-! PLANT- TECHNICAL - ADMINISTRATIVE RADIOLOGICAL
- l. GENERAL- ANALYSIS AND LOGISTICS ENGINEERING CONTROL i MANAGER MANAGER MANAGER MANAGER MANAGER'
.{-
FIGURE 7.2.1 CP&L Recovery Organization i l I i a OERP Rev.53 7-8
r-
]!
BRUNSWICK NUCLEAR PLANT RADIOLOGICAL EMERGENCY PLAN r
8.0 REFERENCES
1, Brunswick Steam Electric Plant Operating Manual, Carolina Power & Light Company, (date varies by volume and by entry).
- 2. - NGGM-PM-0002, CP&L Radiation Control and Protection Manual.
- 3. Updated Final Safety Analysis Report (FSAR), Carolina Power & Light Company, Brunswick Steam Electric Plant Units 1 and 2.
- 4. Environmental and Fallout Gamma Radiation Protection Factors Provided By Vehicles, Health Physics,26, Pg. 41-44,1974.
- 5. EPA-400-R-92-001, Manual of Protective Action Guides and Protective 3
Actions for Nuclear incidents, U. S. Environmental Protection Agency, May J' l 1992.
- 6. Evacuation Time Estimates - Brunswick Steam Electric Plant, November 1993. CP&L and HMM Associates.
- 7. North Carolina Emergency Response Plan in support of the Brunswick Steam Electric Plant.
- 8. NUREG-0654/ FEMA-REP-l, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
- 9. 1990 Census data as reported by the State of North Carolina, Office of State Planning, Center for Geographic Information and Analysis.
- 10. NUREG-0737, Supplement 1, Clarification of TMI Action Plan Requirements.
- 11. NUREGICR-1433, Examination of the Use of Potassium lodide (KI) as an Emergency Protective Measure for Nuclear Reactor Accidents, March 1990.
l l OERP Rev.53 8-1 l' ! L L
R-
.12. Titla 10, Code of Fed:ral Regulations; ^
- a. Part 20, Standards for Protection Against Radiation
- b. Part 50, Licensing of Production and Utilization Facilities
- c. Part 50, Appendix E, Emergency Plans for Production and Utilization Facilities
- d. Part 100, Reactor Site Criteria -
t
- 13. ~ NEl 91-04, Rev.~ 1, Severe Accident Issue Closure Guidelines e
L-l l l v OERP Rev.53 8-2 o
APPENDIX A j m BRUNSWICK COMMUNICATIONS SYSTEM I 4 A.0 INTRODUCTION Communications systems are designed to facilitate emergency communications within j the Brunswick Plant and between Brunswick and emergency facilities. Redundant ! means of communication are provided to locations which provide a vital emergency response role. A.1 PLANT COMMUNICATION SYSTEMS A.1.1 Public Address System l The Brunswick Plant public address system provides paging and party line communications between stations located throughout the plant. Inside and outside type wall and desk-mounted stations are used to communicate between roaming personnel and fixed work locations. Plant-wide instructions are issued using the paging feature. This system is powered from the plant uninterruptible power supply which employs battery reserve as well as diesel generator emergency supply. J A.1.2 PBX Telephone System The Brunswick Site PBX telephone system provides communication capability between ; telephone stations located within the plant by dialing the four-digit telephone station ! code. The PBX telephone system also provides for outside communications as j discussed in Sections A.2.1 and A.2.2. ' A.1.3 Sound Powered Telephone System i The sound powered telephone system is a communications system which uses the mechanical energy in the human voice to generate electrical pulses to power the system. It requires no outside source of power and is therefore very reliable. The system consists of phone jacks, wiring, and the sound-powered handsets. There is no separation in the circuits. A handset plugged into a jack is connected to all other handsets plugged into that circuit. Additional temporary circuits may be easily set up by attaching phone jacks to any unused cable between any points requiring sound-powered communications. Sound powered phone jacks are provided on selected instrument racks. Switch panels are provided in the control room to cross-tie any circuit with any other circuit providing sound-powered phone communications between several plant areas. OERP Rev. 53 A-1
rg A.1.4 Radio Tr:nsceiv;rs for Brunswick and Vicinity
^ VHF transceivers are used for point-to-point communications in the plant vicinity using state frequencies. ' Control stations are located in the TSC and EOF to talk with mobile and portable units. A primary and secondary source of power is provided for fixed base Lredio, with portable and mobile units powered by battery.
'A'1.5 Brunswick Emergency Telephone and Radio System The Brunswick Site emergency telephone system consists of dedicated telephone lines between emergency facilities at the Brunswick Plant through a switch which is provided with a primary and secondary source of power (ROLM 4000 series). Communications with mobile and portable units reserved for an emergency is possible through a l repeater on a CP&L-assigned frequency as well as a local (UHF) short-distance frequency. A primary and secondary source of power is provided for fixed radio equipment, with mobiles and portables powered by battery.
A.1 6 Plant Security Communications l A portable radio communication system for plant use is available. Specific channel assignments are designated door security force use. , l A.1.7 Emergency Responsd Facility information System (ERFIS) I During an emergency, this system provides information on a Video Display Terminal simultaneously in the control room, the Technical Support Center, and the Emergency Operations Facility. The data may also be printed out in hard- copy form. Primary and secondary power sources are supplied to this system.
- A.1.8 Satellite Telephone Communications This system consists of a briefcase enclosed portable, AC, DC, or battery powered !
satellite link telephone. This telephone has the capability to be connected with a fixed remote antenna or use the briefcase portable antenna with access to either of two ; geosynchrorious communication satel!nes. A.2 OFF-SITE COMMUNICATIONS SYSTEMS A.2.1 Corporate Telephone Communications System (Caronet)
. Interconnected through the site PBX and the emergency telephone system, the corporate telephone system provides a means to communicate with other corporate locations with which the plant has a need to communicate. Corporate transmission facilities provide fiber eptic, copper-wire, and microwave radio to ensure a high degree of system reliability. In addition to the redundancy provided by the three system options, backup power is provided for the systems, iw OERP Rev.53 A-2
f. A.2.2 Comm:rci:1 Phons Lin s m' Commercial telephone lines,' which supply public telephone communications, are ernployed by CP&L in three ways: (1) tie-ins through the PBX to any other plant location, (2) lines to plant emergency facilities, and (3) lines to the Joint Information Center for public information purposes. Bell South provides primary and secondary power for their lines at the Central Office. A.2.3 Dedicated Telephone System to Load Dispatcher f l This system provides direct links between the Control Room and the load dispatcher. I Transmission facilities are microwave radio. These lines appear on several phones in ! the Control Room and are selected by pushing the appropriate button on a multibutton { phone. The lines are automatically rung at the load dispatcher identifying Brunswick as j the caller. Primary and secondary power is supplied at both ends. I A.2.4 Emergency Communications Network The Emergency Communications Network is a system, separate from other communications systems, which provides back-up dedicated telephone and radio facilities between emergency response centers. The purpose of these facilities is to ensure priority communications at any time from Brunswick Plant to emergency response personnel at the federal, state, local governments, and other Carolina l Power & Light facilities, and General Electric Company. A.2.5 Plant Security A plant security radio control station provides for radio communications to local law enforcement agencies (LLEA). Primary and secondary power is supplied. A.2.6 Corporate Informational Data Communications Large central computers are located at the Corporate headquarters. Smaller special purpose computers are located at other Corporate facilities, including the Brunswick Plant. The communications link between the Brunswick Plant and Corporate headquarters allows the interchange, storage, and processing of information. A.2.7 NRC Emergency Notification System The NRC operates a dedicated telephone system which allows direct telephone communications from all nuclear power plants to NRC regional and national offices. Telephones connected to this network are located in the Brunswick Control Room, Technical Support Center, and Emergency Operations Facility. Primary and secondary sources of power are supplied. s OERP Rev.53 A-3
p .c . ; 3 (l1, A.2.8 ' NRC H=lth Physics N;twork i m- The NRC also' operates a second dedicated telephone system which allows telephone - l communications from all nuclear plants to NRC regional and national offices. Telephones connected to this system are located for access by Health Physics ; personnel. Primary and secondary power is supplied. I I 1 1 I 1 i l
\
0ERP Rev.53 A-4
Accendix B AGREEMENTS NOTE: . Existing agreements are included for this submittal. These
' agreements will be revised as required to be consistent with this revision of the o Plan'.
)
i
'i
)
I l 0ERP Rev.53 B-1
I l l l L City of Southport
N 201 East Koore Street
'Southport, North Carolina 28461 May 6, 1998 l
JMs. Cynthin Cachwell.
' Manager, Emergency Preparedness Brunswick Plant PO Box 10429 l Southport, North Carolina 28461-C429 l-
Dear Madam:
This letter acknowledges the City of Southport and Southport Fire l ' Department's (hcroafter identified as Fire Department) understanding and agrocmcat to provide assistance in the event of an accident or emergency at the Brunswick Nuclear Plant. Specifically, we agree to be familiar with the Brunswick Emergency Plan and understand that:
- 1. This agreement shall take effect on July 1, 1987 and shall continue through December 31, 2001, except that either party may terminate this agreement at any timo, prior to December 31, 2001, upon six months written notice to the other party. !
I
- 2. .The Fire Department shall be available to fight fires at the Brunswick Plant upon request by CP&L, including fires where radioactivity may be present. However, in any situation where radioactivity nay be present, I the BNP Shift Incident Commander shall first concult with the Chief officer of the Southport Fire Department cencerning the situation befo:.?i sending any of the Fire Department into an area where radioactivity may be present.-After consultation the Chief Officer of the Fire Department 1
-will comply with the Brunswick shift Incident Ccmmander's request and shall locue the command to his personnel.
l 3. In the event that the Fire Department is unavailabic to respond to ! j- CP&L's request d;e to other calls or fire fighting activities, it will ! !. incur no liability to CPLL for failure to respond to said call. l i
- 4. The Fire Department will be under the direction of the BNP Shift Incident Commander who chall issue contands to the personnel of the Fire Department through its Chief Officer. Should it be necessary for more than one fire company to assist in the fighting of a fire at HNP, the Fire Department will assume recponsibility as the lead fire company.
.5. In the event of possible radioactive centamination of the Fire Department personnel and/or equipment, qualified CP&L personnel will provide' Fire Department personnel with appropriate monitoring or protective devices prior- to engaging said personnel in a radioactive situation to ensure that the~ radiation level is not unreasonably ,
dangerous. ! OERP_ Rev.53 B-2
m- 7
'l f
M , ,
- 6. ,In the event of'a'caemical fire at'BNPi proper clothing will be
' ~
provided by CP&L to Fire Department personnel prior to engagement in Lftre fighting.
- 1. CP&L shall provide the Fire Department personnel with all necessary
~ instructions and training to enable the Fire Department personnel to' engage in fire fighting at BNP. Fire Department personnel agree to participate in said training and in all training exercises ~and
,drilla...In addition. CP&L'sha".1 not request Fire department personnel to engage in the-fighting of a chenical fire or in a fire where-radioactivity may be present prior to any' additional instruction or training of Fire Department personnel necessary to qualify them to engage'in such activities. Both CP&L and the Fire Department
,- -personnel shall cooperate with each other-in arranging for the instruction and training of the Fire Department personnel necessary.
to qualify them'to engage in such activities. Both CP&L and the Fire Department personnel shall' cooperate with each othor in arranging for
' instruction and training exercises.
- 8. 'Any contaminated articles belonging to the Fire Department?or its
' personnel, including fire trucks, will be adequately decontaminated -*
or replaced by CP&L at its own expense as expeditiously as possible.
- 9. CP&L shall be liable to the Fire Department personnel for~any radiation injury sustained by said personnel at BNP and shall provide nuclear insurance to cover the Fire Department personnel while engaged in. fire fighting at BNP.
- 10. CP&L shall retain the right to periodically inspect, calibrate, and
. ansure operability of any equipment that may be furnished the Fire Department in. order to enhance the performance of the' support
- functions,
- 11. The Fire Department 'shall furnish and make available to the Fire Department personnel a procedure manual for assisting the BNP Fire Brigade.
- 12. As compensation for services Provided herein by the Fire Department.
-CP&L shall pay to the City of Southport the sum of $12.000 per year-payable on or before December 31, 1987.and each year thereafter.-
I l Sincerely, V l
/ /N, flok City of Sout(port City o fSouthport I Mayor . Fire Chief i
.i l
MDV/cdv
- SPFD LOA 5-99 y
a i OERP- - Rev. 53 B-3 L
r=- James R. Forstner, M.D.
,s' 250 E. lith Street Southport, North Carclina 20461 Eay 6, 1998 Ms. Cynthia Cashwell
" Supervisor, Emergency Preparedness 'j Brunswick Nuclear ?lant )
PO Box 10429- . / Southport, North Carolina 204613
-)
Dear Madam,
This letter acknowledges.that I, James R. Forstner, M.D., understand and agree to provido medical-supervision and care for employees of-the' Brunswick Nuclear Plant as requested by responsible plant management personnel. I am familiar with the Drunswick Emergency Plan and'appropriato. implementing procedures and understand that injuries might involve ionizing radiation. I will' provide said medical supervision and treatment within the limitations of my training. 1 Sincerely, . i
'J es R. Forstnera'M.D.
MDV/mdv I JR Forstner M3 LOA 5-98 I i i i I i
;~ . '
OERP Rev.53 B-4 F ; l l
r l l Peter D Almirall, M.D. l
.s 307 Yaupon Drive Yaupon Dea:h, North Carolina 20465 May 6, 1998 i
l Ms. Cynthia Cashwell. j Supervisor, Emergency Preparedness l Brunswick Nuclear Plant l PO Box 13429 ! Southport, North Carolina 28461
Dear Madam,
I This letter acknowledges that I, Peter D. Almirall, M.D., understand and agree j to provide nedical supervision and care for employees of the Brunswick Nuclear Plant as requested by responsible plant management personnel. I an familiar with the Brunswick Emergency Plan and appropriate implementing procedures and understand that injuries might involve ionizing radiation. I will provide said medical supervisien and treatment within the limitations of my training. I l I Sincerely, 1 1
~
l ' _ jo fl v Peter D. Almirall, M.D. MDV/mdv PD Amirall MD LOA 5-98 0ERP Rev.53 B-5
J. Arthur Dosher Memorial Hospital 924 Howe Stzwet O Southport, North Carolina 28461 May 6, 1998 Ms. Cynthia Cashwell Supervisor, Emergency Preparedness Brunswick Nuclear Project ' PO Box 13429 ' southport, North Carolina 28461-C429
Dear Madam,
This letter acknowledges the J. Arthur Dosher Memorial Hospital's understanding of, and agreement with, actions to be taken in the event of an accident or emergency at the Brunswick Kuclear Project (*HP). Specifica'ly, we are familiar with the BNP Emergency Plan and understand that:
- 1. A specially designed radiological e:necqcncy area will be maintained in state of readiness for.use in the event that an accident or injury complicated by p ssible radiation exposure occura to your employees.
'"he Dosher Mumarial Hospital will admit a patie .t from the specially designated area for further care if recommended by the sup6rvising physician.
- 2. In the event of a serious radiation action, the Hospital will assist in the transfer of patients to the New Har.over Regional Medical center in silmington for further treatment.
- 3. A CP&L representative will be responsible for decontamination of the area, equipmont, etc., following its use. CP&L will i
'- expediticurly replace any facilities, equipment, etc., which .!
cannot be decontaminated.
- 4. Adequate instruction of the Medical staff to maintain familiarity with the procedure will be provided by CP&L. l
- 5. Disposable articles, such as hats, mask, gowns, and floor i coverings, will be provided by and disposed of by CP&L.
Copies of the Hospital's Plan and Procedures for the care and treatment et radiologically injured or contaminated pattents are kept readily available for use by Hospital employees who will direct the necessary acticns. Sincerely, Wm % inistrat J. Arthur Dosher Memorial Eospital M3V/ttdv i JADMH LOA 5-98 I I OERP Rev.53 B-6
City of Southport Rescue Squad !. - Southport. North Carolina 28461 l:- e .' May 6, 1998 Ms. Cynthia Cashwell Supervisor,, Emergency Preparedness Brunswick Nuclear Plant PO Box 10429 Southport, North Carolina.28461 , 1
Dear Madam,
.This letter acknowledges the Southport Rescue Squad understands and agrees to provide medical. assistance in the event of an emergency at the Brunswick Nuclear-Plant. Specifically, we are familiar with the Brunswick
-Emergency Plan and understand thatt
, 1.'We may be required to transport a patient who is !. radioactively contaminated. 1
'2. In the event of possible radioactive contamination, qualified CP&L personnel will provide Southport Rescue Squad personnel with '
appropriate monitoring or protective devices.
- 3. Adequate instructions will be provided by CP&L of the Southport Rescue Squad staff to maintain familiarity with the necessary procedures.
4 Any contaminated articles belonging to the Southport Rescue
-squad, including the ambulance, will be adequately decontaminated or replaced by CP&L as expeditiously as possible.
V a copies of the Southport Rescue Squad's procedures for assisting CP&L personnel are kept readily available for use by the Southport Rescue Squad personnel. ' Sincerely, Chief x w -- "'o , id ( [ y , City Manager Southport Rescue Squad City of Southport , MDV/mdv l SRS LOA 5 l t v. l OERP Rev.53 B-7 I. l
I: , Yaupon Beach Volunteer Fire DepartmentL L51a Yaupon Drivo
,-%s .
-Yaupon' Beach, North Carolina 28461-0429
~ May 6,~ 1998 l- I
, Ms. Cynthia Cashwell .
g Supervisor,' Emergency Preparedness Brunswick Nuclear Plant PO Box 10429
?Southport, North Carolina 28461 i
l
Dear Madam,
l This lotter-acknowledges the Yaupon Beach Volunteer Fire Department's 'j i understanding and agreement to' provide assistance in the event of an l ecorgency at the Brunswick' Nuclear Plant'. Specifically, we agree to be
-familiar with the Brunswick Emergency Plan and understand that:
- l. Yaupon Beach Volunteer Fire departe.ent will be available to fight fires where radioactivity may be present.
- 2. Should it be necessary for more than one fire department to assist in the fighting of a fire at Brunswick, the Southport Fire department will assume responsibility as lead fire company under l the direction of the Ilrunswick Shift Incident Commander.
- 3. In the. event of possible radioactive' contamination, qualified CP&L personnel will Provide Yaupon Beach Volunteer Fire department
. personnel with appropriate monitoring or protective devices. 1
. u. l l 4. Adequate instruction of the Yaupon Beach Volunteer Fire Department ; !,. staff to maintain familiarity with the necessary procedures will be l
'provided by CP&L. .
-5. Any contaminated articles belonging to the Yaupon Beach Volunteer Fire Department, including the fire truck, will be adequately decontaminsted or replaced by CP&L as expeditiously as possible.
l l l-Sincerely, i l 1 l .. , I 1
-Ax " - A, ;
pr 4 Fire Chief . . Yaupon Beach Volunteer Fire Departz.ent l 1 MDV/mdv l, YBVfD leOA 5-90 l s.-. 1 p OERP Rev.53 B-8
?s l Boiling Springs Lakes Fire Department Boiling Springs Lakes - Southport, North Carolina 28461-0429 November 18, 1997 Ms. Cynthia Cashwell Supervisor, Emergency Preparedness I Brunswick Nuclear Plant f PO Box 10429 Southport, North Carolina 28461 l
Dear Madam,
This letter acknowledges the Boiling Springs Lakes Fire Department's understanding and agreement to provide assistance in the event of an emergency at the Brunswick Nuclear Plant. Specifically, we agree to be familiar with the Brunswick Emergency Plan and understand that:
- 1. Boiling Springs Lakes Fire department will be available to fight fires where radioactivity may be present.
- 2. Should it be necessary for more than one fire department to assist in the fighting of a fire at Brunswick, the Southport Fire department will assume responsibility as lead fire company under the direction of the Brunswick Shift Incident Commander.
- 3. In the event of possible radioactive contamination, qualified CAL personnel will provide Boiling Springs Lakes Fire department personnel
~~ with appropriate monitoring or protective devices.
- 4. Adequate instruction of the Boiling Springs Lakes Fire Department staff to maintain familiarity with the necessary procedures will be provided by CP&L.
- 5. Any contaminated articles belonging to the Boiling Springs Lakes Fire ,
Department, including the fire truck, will be adequately decontaminated i or replaced by CP&L as expeditiously as possible, f Sincorely, b m k bu
- /
ST Fire M f Boiling Springs Lakes Fire Dopartment l BSLFDLTR.97 OERP Rev.53 B-9 I L L j
V l New flanover Regional Medical Center-
' , s' 2131 South 17th Street -
'Wilmington, North Carolina 28402-9000 4
6 May 6, 1998 Ms. Cynthia Cashwell Supervisor, Emergency Preparedness Brunswick Nuclear Plant PO Box 10429 Southport, North, Carolina 28461
Dear Madam,
This letter acknowledges Now Hanover Regional Medical Center's-understanding of, and agreement with, actions to be taken-in.the event of an emergency at the Brunswics Nuclear Flant (BNP) . Specifically, we are familiar with the BNP Plan and agree that:
- 1. J. Arthur Dosher Memorial Hospital is the primary hospital to assist BNP in the event of an accident or emergency causing injuries to personnel working at BNP. New Hanover Regional-Medical Center is the backup facility for serious injuries which can not be handled by Dosher Hospital.
- 2. A specially designated radiological emergency area will be maintained in sthte of readiness for use in the event that an accident or injury complicated by possible radiation exposure occurs to one of your employees. New Hanover Regional Medical Center (Ni4RNC) will admit a patient from the specia'ly.
designated area for further care if recommended by the supervising physician. ) 1
- 3. A CP&L representative will be responsible for de:ontaminatien of j the area equipment, etc. , following its use. CP&L will - l expeditiously replace any facilities, equipment, etc., which cannot be decontaminated.
Copies of the NHRMC's plan and procedures for the care and. treatment of j radiologically injured or contaminated patients are kept readily available for use by NHRMC employees who will direct the necessary
~
actions. Sincerely, _ j#
)f ~
Director of Emergency Services, , New Hanover Rsgional Medical Center j l MDV/mdv ! NHRMC LOA S-98 v OERP Rev.53 B-10 i
f 1 I I
'^ Long Beach Volunteer Fire Department P.O. Box 217 Long Beacn, North Carolina 28461 t;cvemoer 18, 1997 Hs. Cynthia Cashwell Supervisor, Emerger.cy Preparedness Brunswick Nuclear Plant PO Bop. 10429 Southport, North Carolina 28461-0429
Dear Madam,
This letter acknowledges the Long Beach Volunteer Fire Departmen-'s understanding and agreement to provide essistance in the event of an emergency at the Brunswick Nuclear Plant. Specifically, we agree to be familiar with the Brunswick Emergency Plan and understand that:
- 1. Iong Beach Volunteer Fire department will be available to fight fires where radioactivity may be present.
{
- 2. Should it be necessary for more than er.e fire department to assist in the fighting of a fire at Brunswick, the Scuthport Fire department will assume responsibility as lead fire company under the direction of the Brunswick Shift incident Commander.
- 3. In the event of possible radioactive contamination, qualified CP&L personnel will provide Long Beach Voluntoor Fire department i personnel with appropriate monitoring or protective devices.
- 4. Adequate instruction of the Long Beach Volunteer Fire Department =
staff to maintain f andliarity with the necessary procedures will be provided by CP&L.
- 5. Any contaminated articles belonging to the Long Beach Volunteer Firo l Department, including the tire tru::k, will be adequately j decontaminated or replaced by CP&L as expeditiously as possibic. j sincerely f/ low lL /
,j >> --
IVFire'//kl% Chief Long.7Jeach Volunteer Fire Department i LDVFDLTR.97 l v OERP- Rev.53 B-11
F 1 l Brunswick County EMS l~ P. O. Box 249 ' '~* Doliva, North Carolina 28422 July 6, 1998 , l 1 Ms. Cynthia cashwell Supervisor, Emergency Preparedoass Brunswick Nuclear Plant PO Box 13429 Southport, North Carolina 28451
Dear Madam,
! l I l This letter acknowledges the Brunswick Coanty Emergency Medical Service understands and agrees to provide medical assistance in the event of an emergency at the Brunswick Nuclear Plant. Specifically, we are f mmiliar with the Brunswick Emergency Plan and understand that:
- 1. We may be required to transport a patient who is j radioactively contaminated. !
- 2. In the event of possible radioactive contamination, qualified l CP&L personnel will provide Brunswick County EMS personnel with 1 1
appropriate monitoring or protectivo devices.
- 3. Adequate instructions of the Brunswick County EMS staf f to l maintain familiarity with the necessary procedures will be provided by CP&L.
- 4. Any contaminated articles belonging to the Brunswick County EMS, ,
including the ambulanco, will be acequately decontaminated or l replaced by CP&L as expeditiously as possible. ) l l Sincerely, M r" ot 3ranswick County Director Emergency Services l l MDV/mdv 3CEMS LOA 7-98 l 1 w i OERP Rev 53 B-12 l
{__ p l Sunny Point Fire Department
N Military Ocean Terminal i
Sunny Point Southport, North Carolina 28461 July 15, 1998 Ms. Cynthia cashwell Supervisor, Emergency Preparedness Brunswick Nuclear Plant PO Box 10429 Southport, North Carolina 28461
Dear Madam,
This letter acknowledges the Sunny Point Fire Department / EMS's understanding and agreement to provide assistance in the event of an emergency at the Brunswick Nuclear Plant. Specifically, we agree to be f amiliar with the Brunswick Emergency Plan and understand that:
- 1. Sunny Point Fire Department will be available to fight fires where radioactivity may be present, as requested by the Southport Fire Department for assistance.
- 2. Should it be necessary for more than one fire department to assist in the fighting of a fire at Brunswick, the Southport Fire department will assume responsibility as lead fire company under the direction of the Brunswick Shift Incident Commander.
- 3. We may be required to transport a patient who is radioactively contmninated.
]
1
- 4. In the event of possible radioactive contamination, qualified CP&L personnel will provide Sunny Point Fire Department / EMS personnel with appropriate monitoring or protective devices. i 1
- 5. Adequate instruction of the Sunny Point Fire Department / EMS staff to maintain familiarity with the necessary procedures will be i provided by CP&L.
- 6. Any contaminated articles belonging to the Sunny Point Fire Department, including the fire truck and ambulance, will be adequately decontaminated or replaced by CP&L as expeditiously as possible.
Sincerely, l AL~- ' AAA ChYef J Sunny Point Fire D@artment l MDV/mdv l SPEMS LOA 7-98 J OERP Rev.53 B-13 l [
i ( ' APPENDIX C' ! L BRUNSWICK NUCLEAR PLANT (BNP) I
^ 'OFF-SITE AGENCY-SUPPORT
SUMMARY
Function (NUREG-0654. II.A) Primary Responsibility Support Responsibility L !- 1 ' Command and Control
- a. Onsite- BNP NRC
- b. Offsite State, County FEMA, CP&L Corp.
L L2. Accident Classification ! a. Onsite BNP- NRC
- b. Offsite. . N/A N/A ,
- 3. Warnina
- a. s Onsite BNP Local
- b. Offsite' County State, USCG
- 4. Notification - i
- a. Onsite BNP Local
- b. Offsite BNP State, Local, Media 5.. Q nmunications e ' Onsite -
BNP- NRC, CP&L Corp. L Offsite State, County Commercial Phone Co., CP&L
- 6. T_ransoortation
- a. Onsite BNP/ Employees Local
- b. Offsite Local / Residents FEMA, State, County ?
- 7. - Traffic Control Security
- a. Onsite BNP Security County
~ b. Offsite County State
- 8. Accident Assessment a .- Onsite BNP HEEC, HNP, RNP, b, Offsite State NRC, GE, County, CP&L Corp., FEMA, EPA, DOE, CAP
- 9. Public Information Education
- a. Onsite BNP, Corp, Comm. NRC, County, ;
- b. ' Offsite State CP&L Corp.,
Media, FEMA i !'m. ! OERP Rev.53 C-1
I I APPENDIX C - BRUNSWICK NUCLEAR PLANT (BNP) l-OFF-SITE AGENCY SUPPORT
SUMMARY
Function (NUREG-0654. II.A) Primary Responsibility Support Responsibility
' 10. Protective Response
- a. Onsite BNP County, CP&L-Corp.
- b. Offsite - County, State CP&L Corp., FEMA, EPA USDA
- 11. Radioloaical Exposure Control
- a. Onsite BNP CP&L Corp.
- b. Offsite State County, FEMA, EPA, CP&L Corp.-
- 12. Fire and Rescue
- a. Onsite BNP County / Local Organ.
- b. Offsite County State
' 13. Medical a .- Onsite BNP County / Local Organ.
- b. Offsite ,
Local State, U.S. DHHS
'14. Public Health & Sanitation
- a. Onsite BNP State, Local, CP&L Corp.
- b. Offsite County- State, FEMA, U.S. DHHS
- 15. Social Services
- a. Onsite - N/A N/A b.- Offsite State County, Red Cross, Salvation Army
- 16. Trainina -
- a. Onsite - BNP NRC,
- b. Offsite County State, CP&L Corp.,
BNP
-17. Exercises
- a. Onsite BNP CP&L Corp., NRC
- b. ' Offsite State State, County, CP&L Corp., BNP 0ERP- Rev. 53 C-2
g r-APPENDIX C l :E BRUNSWICK NUCLEAR PLANT (BNP) !-W OFF-SITE AGENCY SUPPORT
SUMMARY
18.' Recoverv/ Reentry l a. Onsite BNP BNP,RNP,HNP,CP&L l Corp., NRC, GE, FEMA, b.' Offsite State Local, CP&L, DOE, EPA, U.S. DHHS, USDA Note: BSEP Brunswick Steam Electric Plant l CAP Civil Air Patrol CP&L > Carolina Power & Light Company DOE- U.S. Department of Energy EPA U.S. Environmental Protection Agency l FEMA ~ U.S. Federal Energy Management Agency
'GE General Electric
'RNP Robinson Nuclear Plant HEEC Harris Energy & Environmental Center
-NRC. , U.S. Nuclear Regulatory Commission l USCG United States. Coast Guard USDA U.S. Department of Agriculture US DHHS U.S. Department of Health & Human Services
.HNP Harris Nuclear Plant i
i i' l
)
OERP Rev.53 C-3
R . 1 g
. APPENDIX D 1^
l This Appendix has been superseded by the BNP Emergency Procedures.- 1 e 1 I*
..s k .
N l s.- ; DERP Rev.53 D-1
m I APPENDIX E j l MEDICAL TREATMENT AND ASSISTANCE ! i E.1. INTRODUCTION The Medical Treatment and Assistance Plan provides for several levels of treatment based on the severity of injury and degree of radioactive contamination involved,if any. The first level of assistance will be given on site in the plant First Aid Office, if possible, in this facility, initial evaluation of the severity of the injury will be made by first-aid and medical personnel, and emergency treatment started. In many cases, it may be possible to provide complete treatment at this location. l Concurrently the degree of radiation exposure and/or contamination will be assessed by radiation safety personnel and decontamination begun. Allinjuries occurring in a contaminated area will be considered as contaminated until monitored and cleared. If the severity of the injury requires more extensive or prolonged treatment, the patient can be transported to the second level of assistance located at the Dosher Memorial Hospital where special facilities for treatment of contaminated patients ! have been provided (see*Section E.2.2). ! l Transfer from any level of assistance to the next higher level will be effected only ( after medical evaluation (unless the urgency of the patient's condition requires ; immediate action) and will be under the control of the attending physician or his I alternate senior physician. E.2. MEDICAL EMERGENCIES 1 E.2.1 ON-SITE FIRST AlD FACILITIES lt is anticipated that contaminated personnel will not leave the facility for medical treatment except for cases thought to require immediate hospitalization. Emergency medical treatment of contaminated personnel will be handled at the Plant First Aid Office located in the O&M Building (if possible) by site medical personnel. This includes all injuries thought not to require immediate hospitalization.
%,i OERP Rev.53 E-1
r l E.2.2 HOSPITALIZATION
- If emergency medical treatment can best be given at Dosher Memorial Hospitalin Southport (or another facility as may be advised by a competent medical authority), the injured person may be transported i
to Dosher Memorial Hospital. Dosher Memorial Hospitalis the primary hospital for treating medical emergencies occurring at the Brunswick Plant, with New Hanover Regional Medical Center being the backup. OPEP-03.9.3, Transport of Contaminated injured Personnel, will be followed to prevent the spread of radioactive contamination to off-site areas and facilities. If possible, contaminated clothing and equipment should be removed from the patient, or he should be wrapped in clean sheets or clothing to prevent contamination of the transporting personnel and vehicle. Medical assistance is immediately available at the Southport area from two general practitioners, both of whom are on the staff of Dosher Memorial Hospital, and who have agreed to provide medical assistance for contaminated patients. Also, the U. S. Department of Energy Radiological Assistance Team will provide medical assistance, if required. E.2.3 TREATMENT FACILITY A specially designated emergency area is maintained in readiness at Dosher Memorial Hospital for CP&L's use for the treatment of contaminated patients. Although this area will be utilized by the hospital when not required by CP&L, it will be made immediately available to CP&L when required. Equipment is available in the hospital for the emergency treatment of patients. With the facilities and equipment available, extensive decontamination and treatment of an injured patient could be performed, including surgical treatment that may be required. E.2.4 ON-SITE MEDICAL SERVICES i Agreement has been reached with doctors in Southport who vci': . provide medical services at the plant site when required. Personnel who are contaminated and who require medical treatment may be treated by a doctor in the Plant's First Aid Office. ! l W OERP Rev.53 E-2 m
I E.2.5 EMERGENCY EQUIPMENT l^ An emergency kit is maintained at Dosher Memorial Hospital l containing supplies and equipment for personnel monitoring and the control of radioactive contamination. This kit contains the following:
- a. Radiation monitoring instruments, one low-level instrument for determining contamination levels, and one intermediate-range instrument for determining dose rates.
l b. Personnel monitoring equipment such as TLDs and , I self-reading dosimeters. I l c. Decontamination equipment and supplies for both personnel and facility.
- d. Contamination control equipment and supplies such as protective clothing, signs, ropes, tags, plastic bags, etc. ,
E.2.6 AMBULANCE SERVICE The City of Southport Rescue Squad has agreed to respond to all emergency estis from the plant, just as they respond to other calls from the Southport area. l l
^
OERP Rev. 53 E-3
APPENDIX F ~ TECHNICAL BASIS FOR SOURCE TERM MIXES Backaround Since.1962, source term mixes for nuclear power plants have been derived from TID-14844 (Reference 1), as referenced in Regulatory Guides 1.3 and 1.4 (Reference 2). This report established what was believed to be a bounding case for release of radionuclides in a severe core damage accident. The release consisted of 100% of the core inventory of noble gases,50% of the core inventory of iodines, and
- 1% of the core inventory of particulates. Since that time the use of probabilistic risk assessments in examining accident consequences has been developed and documented in the NRC Report NUREG-1465, Accident Source Terms for Light Water Nuclear Power Plants (Reference 3). In this document, new source terms were proposed that utilized the risk assessments of five typical PWRs and five BWRs to develop a mean in-containment isotopic release fraction for various core damage events.
In any risk assessment study, a large number of accident sequences and their
. probabilities of occurrence are analyzed. A separate isotopic release fraction is developed for each accident sequence. The major isotopic release fractions are those fractions of core inventory that'are released either through failure of the fuel cladding, melting of the core within the reactor vessel, or release of melted core materials through a breach of the reactor vessel. These fractions are values that when multiplied by the core inventory in curies of the particular isotopes, give curie amounts of isotopes immediately available for release from the containment. The effects of cleanup and engineered safety features are taken into account to th'e extent consistent with the failures that led to the particular accident sequence. To make the results manageable, the accident sequence and the accident isotopic release are grouped. NUREG-1465 then uses the accident sequence probabilities as a means to weigh the release fractions for that sequence category. The weighted release fractions are added up to determine a "mean" in-containment release fraction.
Source Term Cateaories The traditional source term categories used in the industry were based on TID-14844 i and utilized the major accidents analyzed in the FSAR, i.e., LOCA, Steam Generator Tube Rupture, etc. The source term based on TID-14844 was in fact a default mix of isotopes that was acted upon by the available engineering safety features and natural l' phenomeria associated with each analyzed accident. 1
- \
l i I
. l f J
! OERP Rev.53 F-1 l l
Th9 n:w tourca t:rms cro bas:d upon the cora m:lt s:quenc s d vsloped by tha methodologies used by NUREG-1465. These sequences look at four categories of
^
core damage: 1) fuel clad failure,2) in-vessel melting, 3) ex-vessel release through a breach of the vessel by melted fuel, and 4) a late in-vessel melting category. These categories have an associated release duration based upon the length of time that the core is uncovered. As a result, it is possible to construct a source term mix matrix that ! is dependent on two parameters, whether or not the fuel is uncovered, and the length of , - time that the fuelis uncovered. In order to have a dose assessment capability that can be utilized under many l circumstances, the vast majority of which are less consequential than a total melt of the core with no removal mechanisms, the effect of engineered safety features and removal phenomena must be included in the source term mix. A review of all the removal effects as listed in RTM-92 (Reference 4) was performed and the results are l summarized in Table 1 below. The column," Fraction Used"is the removal fraction used in developing the source term categories that account for removal process. The fraction used was selected to be the highest value of all of the accident categories regardless of how many mitigating processes are in effect. This was done to develop a single removal fraction to cover all cases where removal processes are in effect. The " default" condition for selecting a source term mix is to use a mix that takes into account removal mechanisms for particulates and iodines. Only if no removal process, e.g., sprays, filtration, partitioning, is available will the unmitigated source terms be used. In order to select the proper mix, the release pathway and estimated time duration of core uncovery will have to be determined. The release pathway questions should be very specific, with the user allowed to view all possible
- choices and then select the one that best fits the plant conditions. The response to the release pathway questions and core uncovery time should result in the selection of one of eight possible accident source term mixes as shown in Table 2. The late in-vessel melt release fractions in NUREG-1465 are approximately one order of magnitude below the early in-vessel values, so no separate category of source terms were developed for that cause. j 1
There remain two special cases of accident mixes which can be handled separately in l the dose assessment process. Aged spent fue! involved in shipments and storage from l the Brunswick plant have a single isotopic inventory for the gap which consists of long lived isotopes. This inventory will be used as a single case (without consideration for decay when determining detector sensitivities) for determination of a source term for dose assessment purposes. Similarly, the maximum expected inventory of waste gas ! I decay tank will be used as a single mix category (with no decay) for the PWRs. l I l 1 l l i OERP Rev.53 F-2 l L
I Radioisotope Inventorbs m The radionuclides included in the mixes were taken from RTM-92. Additional i radioisotopes were taken from the plant's core damage assessment procedure if not i already included. Isotopes that had no in-containment release fractions given in the reference documents were removed from the list. The core inventories for Brunswick were developed using the ORIGEN code assuming an average end of life burnup of 32.5 GWD/MTU. The fuel used in the analysis was i GE 13 with 3.90% enriched U 25 with Power Uprate. i l r The resulting source terms for Brunswick are presented in Table 3. 85 The sp8ent fuel assembly source term was developed by taking the values for Kr andl' from the ORIGEN code runs, decaying the values for 5 years, and then taking release fractions as stated in Regulatory Guide 1.25 (30%). The resulting isotopic inventory is presented in Table 4. References i
- 1. Technical Information Document (TID)-14844, Calculation of Distance Factors for
. Power and Test Reactor Sites, J. J. DiNunno et al, U.S. Nuclear Regulatory 1 Commission, Washington, D.C.,1962 i
~
- 2. Regulatory Guide 1.3, Revision 2, Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors, U.S. Nuclear Regulatory Commission, Washington, D.C., June 1974 ,
- 3. NUREG-1465, Accident Source Terms for Light Water Nuclear Power Plants, Draft Report for Comment, U.S. Nuclear Regulatory Commission, Washington, ;
D.C., June 1992 '
- 4. RTM-92, Response Technical Manual, Vol.1, Rev. 2, U.S. Nuclear Regulatory Commission, Washington, D.C., Octo' Der 1992
- 5. CP&L Design Calculation 0B21-0556, CRiGEN2 Execution for Use in Specifying CPLDOSE Inputs for B1C12 and B2C14
'6. ESR 98-00345, Revision 0 l
m OERP Rev.53 F-3
[. Table 1 Brunswick Source Term Removal Groupings I No Not Total Fraction l Accident Category Sprays Sprays Filtered Filtered Fraction Used l Drywell Release .03 .01 .0003 .01 i .75 1 .75 .75 1 1 Torus Release' .01 .01 .01 - l .75 .75 .75 1 l Cont. Bypass .01 .01 .01
.75 .75 .75 l l l
l l l l l
'The effects of torus scrubbing are not fully included. which would multiply the result by another 0.01 to 0.05. to make the categories consistent. the unfiltered release fraction was very conservatively aken to be 0.75.
OERP Rev.53 F-4 l I L
n ! ^~ Table 2 Brunswick Source Term Categories Source Term Cateaory Description Normal RCS Accidents that do not result in core uncovery. Filtration and/or containment sprays are considered to be effective. Gap Release w/f-s Any accident sequence that results in core uncovery
<60 minutes, or mechanical fuel damage has occurred.
Filtration and/or containment sprays are considered to be effective. Gap Release No f-s Any accident sequence that results in core uncovery
<60 minutes or mechanical fuel damage has occurred.
Filtration and/or containment sprays are considered to be NOT effective. Early IV w/f-s Any accident sequence that results in core uncovery from 1 to 2.5 hours. Filtration and/or containment sprays are considered to be effective. Early IV No f-s Any accident sequence that results in core uncovery from 1 to 2.5 hours. Filtration and/or containment sprays are considered to be NOT effective. Ex-Vessel w/f-s Any accident sequence that results in core uncovery
>2.5 hours. Filtration and/or containment sprays are considered to be effective.
Ex-Vessel No f-s Any accident sequence that results in core uncovery
>2.5 hours. Filtration and/or containment sprays are considered to be NOT effective.
Spent Fuel An accident involving the damage of a freshly unloaded spent , fuel assembly. Filtration is considered to be effective. For spent fuel assembly accidents with no filtration, use " Gap Release No f-s." v i OERP Rev.53 F-5
i l I Table 3 Brunswick Plant Dose Assassm:nt Source Terms
.m iso- Normal Gap Rel Gap Rel EarlyIV EarlyIV Ex V Ex V Spent Fuel tope RCS wlf s Nofs w/f-s No f-s w!f-s Nofs Assy(GAP)
(Cl) (Cl) (C!) (Cl) (Cl) (Cl) (Cl) (Cl) H-3 2.7E+01 2.7E+01 2.7E+01 2.7E+01 2.7E+01 2.7E+01 2.7E+01 0.0E+00 l Mn-54 1.9E 03 1.9E-03 1.4E-01 2.1 E+03 1.6E+05 2.1 E+03 1.6E+05 0.0E+00 I Co-58 5.4E 03 5.4E-03 4.0E-01 5.9E+03 4.4E+05 5.9E+03 4.4E+05 0.0E+00 i Co-60 1.1 E-02 1.1 E-02 8.1E-01 1.1 E+04 8.6E+05 1.1E+04 8.6E+05 0.0E+00 l Kr-85 0.0E+00 4.5E+04 4.5E+04 9.1E+05 9.1 E+05 9.1E+05 9.1E+05 8.1 E+01 Kr 85m 0.0E+00 8.9E+05 8.9E+05 1.8E+07 1.8E+07 1.8E+07 1.8E+07 1.6E+03 Kr 87 0.0E+00 1.7E+06 1.7E+06 3.4E+07 3.4E+07 3.4E+07 3.4E+07 3.0E+03 Kr 88 0.0E+00 2.4E+06 2.4E+06 4.8E+07 4.8E+07 4.8E+07 4.8E+07 4.3E+03 l Sr-89 2.7E-03 2.7E-03 2.0E-01 1.9E+04 1.4E+06 1.7E+05 1.3E+07 0.0E+00 l Sr-90 1.9E-04 1.9E-04 1.4E-02 2.2E+03 1.6E+05 1.9E+04 1.5E+06 0.0E+00 St91 1.1E 01 1.1 E-01 8.1 E+00 2.4E+04 1.8E+06 2.2E+05 1.6E+07 0.0E+00 l Y-91 1.1E-03 1.1E-03 8.1 E-02 1.7E+03 1.2E+05 1.0E+04 7.5E+05 0.0E+00 l l Y-91m 0.0E+00 0.0E+00 0.0E+00 9.4E+02 7.1 E+04 5.6E+03 4.2E+05 0.0E+00 Mo-99 S.4E 02 5 4E-02 4.0E+00 9.2E+03 6.9E65 1.4E+04 1.1E+06 0.0E+00 Ru 103 5.4E 02 5.4E-02 4.0E+00 7.5E+03 5.7E+05 1.2E+04 8.9E+05 0.0E+00 Ru 106 5.4E 04 5.4E 04 4.0E-02 2.9E+03 2.2E+05 4.6E+03 3.4E+05 0.0E+00 Te-129m 1.1 E-03 1.1 E-03 8.1E-02 3.6E+03 2.7E+05 1.6E+04 1.2E+06 0.0E+00 Te 131m 2.7E-03 2.7E-03 2.0E-01 1.1E+04 8.3E+05 4.9E+04 3.7E+06 0.0E+00 Te 132 2.7E-04 2.7E-04 2.0E-02 1.1 E+05 8.1E+06 4.8E+05 3.6E+07 0.0E+00 1131 5.9E-02 3.5E+04 2.6E+06 1.9E+05 1.4E+07 4.4E+05 3.3E+07 6.2E+03 1132 5.9E-01 5.0E+04 3.BE+06 2.7E+05 2.0E+07 6.4E+05 4.8E+07 8.9E+03 1-133 4.0E 01 7.1 E+04 5.3E+06 3.8E+05 2.8E+07 , 9.0E+05 6.8E+07 1.3E+04 1134 1.2E+00 7.8E+04 5.8E+06 4.2E+05 3.1 E+07 9.9E+05 7.4E+07 1.4E+04 l135 5.9E-01 6.6E+04 5.0E+06 3.6E+05 2.7E+07 8.4E+05 6.3E+07 1.2E+04 i Xe-131m 0.0E+00 3.9E+04 3.9E+04 7.7E+05 7.7E+05 7.7E+05 7.7E+05 6.9E+01 {i j Xe 133 0.0E+00 6.8E+06 6.BE+06 1.4 E+08 1.4E+08 1.4E+08 1.4E+08 1.2E+04 Xe-133m 0.0E+00 2.2E+05 2.2E+05 4.4E+06 4.4E+06 4.4E+06 4.4E+06 3.9E+02 Xe 135 0.0E+00 2.5E+06 2.5E+06 5.1 E+07 5.1E+07 5.1 E+07 5.1 E+07 4.5E+03 Xe 138 0.0E+00 5.8E+06 5.8E+06 1.2E+08 1.2E+08 1.2E+08 1.2E+08 1.0E+04 Cs-134 8.1 E-04 7.5E+03 5.6E+05 3.0E+04 2.2E+06 9.7E+04 7.3E+06 1.3E+03 Cs 136 5.4E-04 2.5E+03 1.9E+05 1.0E+04 7.5E+05 3.2E+04 2.4E+06 4.4E+02 Cs-137 2.2E-03 4.9E+03 3.7E,-05 2.0E+04 1.5E+06 6.4E+04 4.8E+06 2.8E+02 l Cs 138 0.0E+00 6 4E+04 4.8E + 06 2.6E+05 1.9E+07 8.3E+05 6.2E+07 1.1 E+04 l Ba-140 1.1 E-03 1.1E 03 8.1E 02 3.6E+04 2.7E+06 2.9E+05 2 2E+07 0.0E+00 j 8.1E 01 I La 140 1.1E-02 1.1 E-02 2.5E+03 1.9E+05 1.5E+04 1.1 E+06 0.0E+00 Ce-144 8.1E 05 8.1E 05 6.1E-03 8.4E+03 6.3E+05 1.8E+04 1.Fd+06 0.0E+00 Total i 2.8E+00 3.0E+05 2.2E+07 1.6E+06 1.2E+08 3.8E+% 2.9+08 5.3+04 Total P 2.6E-01 7.9E+04 5.9E+06 5.7E+05 4.3E+07 2.4+06 1.8E+08 1.4E+04 Total NG 2.7E+01 2.0E+07 2.0E+07 4.1 E+08 4.1 E+08 4.1 E+08 4.1 E+08 3.7E+04 v Grand Total 3.0E+01 2.1 E+07 4.9E+07 4.1 E+08 5.7E+08 4.2E+0B 8.7E+08 1.0E+05 OERP Rev. 53 F-6
Tabla 4 Old Sp::nt Fue; 1sssmbly Inventories H: Brunswick Spent Fuel: Inventory Initial Core Five Year Available isotope - Inventory Decay Constant inventory For Release (Cl) (HOUR-1) (Cl) - (Cl)
- Kr-85 - 1.49E+03 7.37E-06 1.08E+03 3.24E+02 1-129 4.75E-03 . 4.97E-12 4.75E-03 1.43E-03
.- 1
,,+
I i i j i l l 1
+
a OERP Rev.53 F-7
D APPENDIX G
^
MINIMUM PROCEDURES REQUIRED TO IMPLEMENT THE SECTIONS OF THE PLAN l PLAN- -PROCEDURES 1. L Section 1: Introduction N/A
'Section 2: Emergency OPEP-02.1 Initial Emergency Actions Classifications OPEP-02.1.1 Emergency Control- Notification
- ' of Unusual Event, Alert, Site Area Emergency, General Emergency l Section 3
- Emergency OPEP-02.6.6 Environmental Monitoring Response Team Leader Organization OPEP-02.6.12 Activation and Operation of the l Operational Support Center OPEP-04.7 Brunswick Emergency Notification (Automated Telephone) System 0 PEP-02.6.26 Activation and Operation of the i
Technical Support Center (TSC) i OPEP-02.6.27 Activation and Operation of l Emergency Operations Facility (EOF) 1 OPEP-02.6.28 Off-Site Protective Action Recommendations ' OPEP-02.6.20 Dose Projection Coordinator ; OPEP-02.6.21 Emergency Communicator OPEP-02.1.1 Emergency Control- Notification of i Unusual Event, Alert, Site Area Emergency, General Emergency 0 PEP-02.0.29 Activation and Operation of the Joint Information Center (JIC) 1 OERP - Rev.53 G-1
I APPENDIX G (cont'd)
^
PLAN PROCEDURE _S ' Section 4: Emergency OPEP-02.1 Initial Emergency Actions Measures j OPEP-02.1.1 Emergency Control- Notification of Unusual Event, Alert, Site Area Emergency, General Emergency 0 PEP-03.1.3 Use of Communication Equipment OPEP-03.4.7 Automation of Off-Site Dose Projection Procedure OPEP-03.8.2 Personnel Accountability and-Evacuation OPEP-03.9.2 First Aid and Medical Care OPEP-03.9.3 Transport of Contaminated injured Personnel 0 PEP-03.9.6 Search and Rescue OPEP-04.5 Public Education and information OPEP-03.7.6 Emdrgency Exposure Controls 1 OPEP-03.7.7 Onsite Radiological Controls i i I 0ERP. -Rev.53 G-2
APPENDIX G (cont'd)
^
PLAN PROCEDURES l Section 5: Emergency 0 PEP-03.4.7 Automation of Off-site Dose Facilities and Projection Procedure Equipment OPEP-03.5.5 Environmental Monitoring and Plume ! Tracking OPEP-04.7 Brunswick Emergency Notification (Automated Telephone) System j OPEP-04.2 Emergency Facilities and Equipment Section 6: Maintaining 0 PEP-04.1 Record Keeping and Documentation Emergency - Preparedness OPEP-04.2 Emergency Facilities and Equipment OPEP-04.3 Performance of Training, Exercises, and Drills OPEP-04.5 Public Education and Information OPEP-04.6 Radiological Emergency Kit inventories Section 7: Recovery 0 PEP-02.7 Recovery l l I 0ERP Rev.53 G-3 o
p l-APPENDIX H
=^ ~
CROSS-REFERENCE BETWEEN NUREG-0654 EVALUATION CRITERIA AND BRUNSWICK RADIOLOGICAL EMERGENCY RESPONSE PLAN i / NUREG-0654 Brunswick
, Criterion Section(s)
A.1.a - 3.1, 3.2, 3.3, 3.4, 3.5, 3.6, 3.7, 3.8 Appendix C L A.1.b 3.0, 3.1, 3.2, 3.3, 3.4, I 3.5, 3.6, 3.7, 3.8 A.1.c - Figures 3.1 -1, 3.2-1, 3.4-1 A.1.d 3.0, 3.2.1 1 A.1.e 3.2,3.9 A.2.a N/A I A.2.b N/A A.3 Appendix B A.4 ' ' 3.0, 3.2,' 3.3, 3.4, 3.5 i i B.1 3.0, 3.1, 3.2 i B.2- 3.0, 3.2.1 B.3 3.0, 3.2.1 i B.4 3.0, 3.2.1 B.5 3.2, 3.3, 3.4, 3.5, 3.6, 3.7., 3.8 B.6 Section 3 Appendices A, B, C, E Figure 3.2-1 OERP Rev. 53 H-1 L p .
APPENDIX H (Cont'd)' NUREG-0654 - Brunswick Criterion Section(s) l B.7 Section 3 B.7.a ~ 3.3.5, 3.5.2 - l .B.7.b 3.3.1, 3.3.3, l Section 7.0 l~ B.7.c 3.2.1, 3.5 B.7.d .3.6 B.8 3.7.1, Table 3.5-1 B.9 - 3.7.2, Appendix B, Appendix C, Appendix E. L I- C.1.a 3.8.4.1 C.1.b 3.8.4 C.1.c 3.8 C.2.a ' N/A C.2.b 3.3.1.1, 3.5.8, Figure 3.2-1 C.3 5.7.6, 3.7.1, 3.8 C.4 3.7,3.8, Appendix B, Appendix C, Table 3.5-1
. D.1 Section 2.0 l D.2 Section 2.0 D.3 N/A D.4 N/A
'0ERP Rev.53 H-2
APPENDIX H (Cont'd)
~
NUREG-0654 Brunswick Criterion Section(s) , E.1 3.9, 4.1, 4.4.1 E.2 3.2, 3.5, 3.9 E.3 3.9 E.4.a-n OPEP-02.6.21 E.5 N/A E.6 3.9,4.4.6, OPEP-02.6.21 E.7 3.9, 4.4.7 F.1.a 3.9, OPEP-02.6.21 F.1.b 3.9, Appendix A, OPEP-02.6.21 ! l F.1.c 3.9, Appendix A, l OPEP-02.6.21 F.1.d ' 3.9, Appendix A, OPEP-02.6.21, OPEP-03.1.3 F.1.e 3.2,3.9, Appendix A OPEP-02.6.21, OPEP-04.7 F.1.f 3.9, Appendix A, OPEP-02.6.21 j F.2 Appendix A, Table 3.5-1 l a F.3 6.1.2.1 0ERP Rev.53 H-3
n> APPENDIX H (Cont'd)
. NUREG-0654 Brunswick Criterion Section(s)
G.1 4.4.7.1, 6.1.4 G.2 4.4.7.1, 6.1.4 TG.3.a 3.6, 5.5 > G.3.b 5.4, 5.5 G.4.a 3.6 G.4.b 3.6 G.4.c 3.6, 4 A.7.1 G.5 6.1.4 H.1 5.2, 5.3 l' ._ H.2 5.4 l
-~~
H.3 N/A H.4 ' 3.0, 3.1, 3.2, 3.3, 3.4, 3.5, 3.6, 3.9 Table 3.5-1 H.5 5.7 H.5.a 5.7 H.5.b 5.7.4 H.5.c 5.7.5 H.S.d ' 5.8 v OERP' -Rev.53 H-4 t :.
j-; APPENDIX H (Cont'd)
^- NUREG-0654 Brunswick Criterion Section(s)
H.6.a - 5.7 H.6.b 5.7 l H.6.c 5.7.6 - H.7 - 5.7.4,5.12 l- H.8 5.7.2 H.9 5.3, Table 5.0-2 H.10 Procedure OPEP-04.6 H.11 Procedure OPEP-04.6 Appendix A H.'12 5.0, 5.7.6 1.1 - Section 2, OPEP-02.1, Section 5.0 1.2
- 4.2, Section 5.0
.l.3.a 4.2.2, PEP-03.6.1, PEP 03.6.3, Appendix F l.3.b - 4.2.2,4.2.3, OPEP-03.4.7, PEP-03.5.5 l l
l.4 4.2.2, OPEP-03.4.7,
. OP EP-03.6.1 ,
l.5 5.7.2 1.6 - 4.2.2.3 l l l
%.ame*'
OERP Rev.53 H-5
o APPENDIX H (Cont'd) NUREG-0654 Brunswick Criterion Section(s) t' l.7 ~4.2.4 i 1.8 4.2.1, 4.2.2, 4.2.3, 4.2.4 l.9 4.2 t 1.10 4.2 J.1.a '- 4.4.2, 6.1.1, Appendix A
- J.1.b' 4.4.2,6.1.1,' Appendix A
.J.1,c ~ 4.4.2, 6.1.1 J.1.d 4.4.2, 4.4.6 J.2 4.4.2 J.3 4.4.2.2, 4.4.4.1, 4.4.4.2 J.4 4.4.2.2 J.5 ' 4.4.2.2 J.6.a 4.4.3, 5.9 '
J.6.b 4.4.3, 5.9 J.6.c ~ 4.4.3 , l J.7 4.1.5, 4.4.7 i J.8 4.4.7.3 J.9 N/A v l OERP Rev.53 H-6
g APPENDIX H (Cont'd)
^' NUREG-0654 - - Brunswick Criterion Section(s)
J.10.a 4.4.7.3, Figures 1.1-1, 4.4-1, Figure 1.1-2 J.10.b' Figures 1.1-1,1.1-2,1.1 -6 J.10.c - 3.9, 4.4.6 J.10.d N/A J.10.e - N/A J.10.f N/A-J.10.g - N/A J.10.h N/A J.10.1 N/A J.10.] N/A J.10.k , N/A J.10.1 N/A J.10.m : See item J.7
. J.11 N/A J.12 N/A K.1.a-g 4.4.3 K.2 ~ 4.4.3
.K.3.a 4.4 K.3.b' 4.4 K.4 N/A l
OERP Rev.53- H-7 I. ~ 2-
r-APPENDIX H (Cont'd)
" NUREG-0654 Brunswick Criterion Section(s)
K.5.a 4.4.4 K.S.b 4.4.4.1, 4.4.4.2, 4.4.5 K.6.a 4.4.4 K.6.b 4.4.4 K.6.c 4.4.4 K.7 4.4.4, 4.4.5 L.1' Appendix B, Appendix E, 5.10 L.2 4.4.5,5.10, Appendix B, Appendix E 4 L.3 N/A L.4 3.7.2.1, 3.7.2.2, 4.4.5, Appendix B, Appendix E M.1 OPEP-02.7, Section 7.0 i M.2 7.2, Figure 7.2.1, l Table 7.2 ~1, OPEP-02 7 j M.3 7.2, OPEP-02.7 M.4 Figure 1.1-6 N.1.a 6.1.2.2 l N.1.b 6.1.2.2-N.2.a 6.1.2.1 N.2.b 6.1.2.1 0ERP Rev.53 H-8
r I APPENDIX H (Cont'd)
^' NUREG-0654 Brunswick Criterion Section(s)
N.2.c 6.1.2.1 N.2.d 6.1.2.1 N.2.e 6.1.2.1 N.3.a-f 6.1.2 N.4 6.1.2.2 N.5 6.1.2.2 0.1 6.1.1 0.1.a 6.1.1 0.1.b- , N/A O.2 6.1.1 O.3 6.1.1 0.4.a-j ' 6.1.1 0.5 6.0, 6.1, 6.1.1 ; P.1 6.1.3-i P.2 6.1.3 P.3 6.1.3 P.4 6.2.1 P.5 6.2.1 P.6 6.2.3 OERP Rev.53 H-9 L_.
I i APPENDIX H (Cont'd) i m NUREG-0654 Brunswick Criterion Section(s) P.7 Appendix G P.8 Table of Contents ! P.9 6.2, 6.2.1, 6.2.2 P.106 6.2.1 1 I w l l OERP Rev.53 i H-10 i
ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS 1 AND 2 DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 REVISION TO PLANT EMERGENCY PROCEDURES OPEP-03.8.2. " Personnel Accountability and Evacuation," Revision 15
- - CP&L,- CAROLINA POWER & LIGHT COMPANY I
information ummm m mm m mmu BRUNSWICK NUCLEAR PLANT use
)
PLANT OPERATING MANUAL VOLUME Xlli PLANT EMERGENCY PROCEDURE l UNIT 0 pei r w D:L , c .- i m. lllllllll ll llllll llllllllll OPEP-03.8.2 PERSONNEL ACCOUNTABILITY AND EVACUATION REVISION 15 tretsnw EFFECTIVE DATE y /2 7/'P/ APR 2 81999 manoocamcum Sponsor JAlaa ddt x- h J:x>o s- i '27 91 Date Approval \ , hm 4 g3 Sq Supervisor - Emergency Preparedness Date OPEP-03.8.2 Rev.15 Page 1 of 22
&Qb00S I l b S S fb3
r l
' REVISION
SUMMARY
- n .
i As a result of action items from CR 98-02901, Revision.15 of OPEP-03.8.2 reflects the following change: Added Step 6.1.5 to define the duties of the Emergency Preparedness Representative during a Precautionary Relocation of personnel. LIST OF EFFECTIVE PAGES Paae(s) Revision l l 1-22 15 1 i I l l l ,.s l OPEP-03.8.2 Rev.15 Page 2 of 22
c 1 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE...............................................................................................4 1 I 2.0 ~ R E F E R E N C E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 ............. 3.0 D E F I N IT I O N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.0 R E S P O N S I B I LITI E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.0 GENERAL........................................................................................................8 6.0 I N S T R U C TI O N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.1 P recautio na ry Relocation . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . 9 6.2 S it e Evac u at io n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6.3 B uilding o r Are a Evacu ation .. ... . ... .. . .... .. . . .. . ... .. . . . . . .... .. . . .. . .. . .. ... .. ... ... ........ . 13 6.4 Ac c e s s C o n t ro l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . l - 1 1 ATTACHMENTS . 1 M is si n g P e rs on n e l Fo rm . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 2 E RO Additio n al S u ppo rt Ro ste r. . . . .. .. . . . . . . .. .. . .. . .. .. .. . . .. . . . . .. . ... . . . .. . . ... . .. . . . . ... ... .. . 17 3 P rim a ry Ass e mbly Are a I n st ruction s. . . .. .. . . . .. . . . . . . . ... . .. ... . . ... . . . . . . . ..... .. . . . . . .. . . . .. .. . . . 21 4 Alte rnate Asse mbly Area instructions . ... ......... .. .... ..... ......... ......... ... ................ 22 a OPEP-03.8.2 Rev.15 Page 3 of 22
p I 1c0 PURPOSE
^
This procedure provides guidance and instructions to ensure the prompt and orderly relocation or evacuation and assembly of personnel at the Brunswick Nuclear Plant including control of vehicle traffic entering the site. 2.0- REFERENCES 2.1 OSI-05, Security Post Duties, Responsibilities and Patrol Procedures 2.2 OPEP-03.9.6, Search and Rescue 2.3 0 PEP-02.1.1, Emergency Control- Notification of Unusual Event, Alert, Site Area Emergency, and General Emergency 2.4 OPEP-Appendix A, Emergency Response Resources 3.0 DEFINITIONS 3.1 Accountability - The process by which all personnel within the Protected Area are identified and either accounted for or determined to be missing. Accountability must,be established: 3.1.1 Within 30 minutes of the declaration of a Site Area Emergency or higher. 3.1.2 Within 30 minutes of the time the decision is made to conduct a Site Evacuation (when performed prior to a Site Area Emergency). 3.2 Assembly Area - The designated location where non-essential personnel are directed to report and await further instructions following an evacuation or relocation. The primary and alternate Assembly Areas are illustrated in Attachments 3 and 4 and are described as follows: 3.2.1 Primary Personnel Assembly Areas are: I
- TAC Parking Lot for all non-essential personnel whose normal work location is inside the protected area.
NOTE: The Control Room may direct these personnel to the Technical-Training Center (TTC) Mechanical Lab (shop area) due to inclement weather
- TAC Building Lobby for non-essential personnel whose normal work i- location is in the EOF /TSC Training Building.
0 PEP-03.8.2 Rev.15 Page 4 of 22 i
m 3o0 DEFINITIONS
~
*- Primary work location for non-essential personnel whose normal work location is outside the protected area:
. TAC Building
. Technical Training Center (TTC)
. The Media Center / Visitor's Center
! . The Document Control Building l l . The Low Level Warehouse
. The Clean Material Monitoring Facility (Clean Waste) l
. The Incinerator Building
. The Garage
. Warehouse W 3.2.2 Alternate Personnel Assembly Areas
- The north end of the Document Control parking lot (across from the Administration Annex) for all personnel whose normal work location is inside the Protected Area.
- The south end of the Document Control parking lot (across from the EOF /TSC/ Training Building) for all personnel whose normal work location is outside the Protected Area.
3.2.3 Remote Personnel Assembly Areas
- Personnel may be instructed to proceed directly to an offsite relocation center or other designated location due to inclement weather or undesirable plant or radiological conditions, s
OPEP-03.8.2 Rev.15 Page 5 of 22 L:
1 3.0 ' DEFINITIONS
^
3.3 Building or Area Evacuation - The safe and orderly evacuation of
- personnel from an identified building or location when deemed necessary by the Site Emergency Coordinator due to habitability hazards, such as radiological, toxic gases, fire, or natural phenomenon.
3.4 Essential Personnel - Personnel assigned to fill an emergency position in an emergency response facility (such as, the on-call ERO Team, Duty Maintenance /l&C personnel, Security Force, etc.). In a declared emergency of an Alert or higher, these individuals report immediately to the TSC, EOF, OSC, Security Post or Control Room as assigned. 3.5 Non-Essential Personnel - Personnel who do not have pre-assigned duties i in an emergency facility. This includes qualified Emergency Response i personnel which are not currently required to fill an ERO position, as well as < contractors and visitors. 3.6 Precautionary Relocation - Relocation of non-essential personnel from l the Protected Area, to limit the number of onsite individuals potentially exposed to a hazardous condition and to minimize the impact on emergency response functions,and logistics, as a precautionary measure. l 3.7 Site Evacuation - The safe and orderly evacuation of non-essential { personnel from the Protected Area at the declaration of a Site Area
~
Emergency or when deemed necessary by the Site Emergency Coordinator. i 3.8 TTC - Technical Training Center 4.0 RESPONSIBILITIES 4.1 Operations Shift Superintendent - In all situations when emergency response facilities are not activated, the Shift Superintendent is responsible for implementation of this procedure. L L OPEP-03.8.2 Rev.15 Page 6 of 22
r 4.0 RESPONSIBILITIES
^
4.2 The Site Emergency Coordinator is responsible for the overall safety and we;!-being of personnel on site. Specific responsibilities include: 4.2.1 Determining the need for and directing a precautionary relocation of non-essential personnelinside the Protected Area. l 4.2.2 Determining the need for and directing a Site, Building, or Area Evacuation. 4.2.3 Dispatching Fire Brigade personnel to evacuated areas to ensure all personnel have exited the location. 1 4.3 The Radiological Controls Director, in cooperation with the Radiological ! Controls Manager, is responsible for determining the appropriate Assembly I Area based on radiological conditions and recommending the location to the Site Emergency Coordinator. 4.4 The Security Director (or Security Lieutenant if TSC is not yet activated) is ' l responsible for: 4.4.1 Establishing' accountability of all personnel within the Protected Area, identifying any missing individuals and communicating this information to the Site Emergency Coordinator. l 4.4.2 Providing information and coordinating activities with the OSC OPS , Coordinator for search and rescue operations. ! 1 4.4.3 Ensuring a roster of Emergency Response Organization personnelin j each of the emergency response facilities is generated and maintained whenever the facilities are activated. 4.4.4 Providing notification to personnel on CP&L property outside the Protected Area of the need to evacuate or relocate, as directed by the Site Emergency Coordinator. 4.4.5 Providing security, access and traffic control for the site and providing security support to the Emergency Response Facilities. 4.5 OSC OPS Coordinator is responsible for: Coordinating activities with Security for the dispatch of Fire Brigade personnel for search and rescue operations. OPEP-03.8.2 - Rev.15 Page 7 of 22
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4.0 ' RESPONSIBILITIES
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4.6 Work Group Supervisors for personnel who exited from the Protected Area are responsible for: 4.6.1 The assembly and muster of personnel associated within a work group at the designated Assembly Area. 4.6.2 Coordinating the disposition of personnelin the Assembly Area with Security. 4.6.3 Contacting the Security Lieutenant (Ext. 2257) with a list of personnel thought to be missing. Attachment 1 should be used to document missing personnel. 4.7 The Emergency Preparedness Representative will coordinate activities of
. personnel arriving at the Technical Training Center following a site evacuation.
5.0 GENERAL 5.1 The primary method for accountability of personnel within the Protected Area is the electronic security computer roll call. A manual back-up method is also coordinated by the Security Director should the security computer fail. 5.2 The Site Emergency Coordinator shall be notified upon the completion of accountability and the identification of personnel determined to be missing, if any. Accountability must be completed within 30 minutes of the declaration of a Site Area Emergency or higher (or within 30 minutes of the decision to conduct a Site Evacuation when performed prior to a Site Area Emergency). 5.3 Radiological monitoring of each individual exiting the Protected Area is conducted while personnel are processed through the central access control point. Personnel identified as contaminated are taken to the Service Building or TSC decontamination areas. Health Physics personnel are dispatched to the designated Assembly Area to provide additional radiological support as necessary, i OPEP-03.8.2 Rev.15 - Page 8 of 22
O~ 6.0
- INSTRUCTIONS S.1 Precautionary Relocation Th'eSite Emergency Coordinator may elect to conduct a precautionary relocation of non-essential personnel from the Protected Area as follows:
6.1.1 An announcement is made, from the Control Room over the public
. address system, of the precautionary relocation of non-essential pers'annel. The Site Evacuation Alarm should NOT be used.
" Attention All Personnelc All Non-Essential Personnel Are To Exit -
The Protected Area And Report To Your Primary / Alternate Assembly, Location". -(pick one) Repeat Announcement 6.1.2 - Non-essential personnel are to exit the Protected Area through the Central Access Point (CAP) using Radiological and Security Procedures and report to the designated Assembly Area for further instructions. , 6.1.3 The Security Director will perform the following:
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- 1. Direct the distribution of Assembly Area instructions to personnel exiting the Protected Area'at the central access control point.
~ 2. Direct Security personnel to make announcements to assembled
- personnel using Plant PA and TAC Building PA systems in coordination with the Control Room.
- 3. Dispatch personnel to the parking lots to direct the flow of traffic leaving the site, 6.1.4 The Work Group Supervisors will perform the following:
- 1. Assemble personnel and designate individuals, as necessary, to assist with the Assembly Area briefings.
- 2. Direct ERO qualified personnel to the TTC Auditorium for further instructions and assignments.
i OPEP-03.8.2 Rev.15 Page 9 of 22
=
g - l 6.1 Prccrutinn:rymi cati:n
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- 3. Discuss instructions for release of non essential personnel as directed by the Control room, Security, or PA announcements.
- 4. Verify that personnel have transportation and have been provided l instructions prior to release from the Assembly Area.
6.1.5 The Emergency Preparedness Representative will perform the ! following:
- 1. Direct ERO personnel arriving in the Technical Training Center to sign in on appropriate sections of Attachment 2, ERO Additional Support Roster, ,
- 2. Transmit completed copies of Attachment 2, ERO Additional Support Roster to the Control Room. Referio OPEP-Appendix A, Emergency I Response Resources for Control Room fax numbers.
l
- 3. Provide other assistance in support of the Precautionary Relocation of person ,el as directed. i 6.2 Site Evacuation '
- Upon the declaration of a Site Area Emergency or higher, or when directed Fj (ne Site Emergency Coordinator, an evacuation of non-essential personnel from the Prclected Area is conducted and accountability of the remaining essential personnel is established and continuously maintained as follows:
i 6.2.1 The Site Evacuation Alarm is sounded, from the Control Room over the public address system, and an announcement of the evacuation of non-essential personnel from the Protected Area is made. NOTE: All escorts shall accompany their visitors to the Protected Area's central access point and direct the visitors to leave the site. The escort will then report to their Emergency Response Facility or the designated Assembly Area. 6.2.2 Non-essential personnel within the Protected Area are to exit the Protected Area through the central access control point and re' port to ) their Wo-k Group Supervisor in their designated Assembly Area, for 1 accountability and further instructions. 6.2.3 All non-essential personnel outside of the Protected Area are to remain in or return to their normal work location aled await PA
,, announcements or instructions from Security.
OPEP-03.8 2. Rev.15 Page 10 of 22 %_ o
n . 6,2 SitD Ev:cu;ti:n ' i^ -6.2.4 Essential Personnelin the Emergency Response Organization shall l report to their designated emergency response facility for l accountability and further instructions and assignments. L 6.2.5 All ERO qualified individuals not currently assigned (on duty) to the Emergency Facilities will report to their Work Group Supervisor and then to the Technical Training Center. Jditorium. After reporting to the auditorium, they are to immediately sign Attachment 2, ERO Additional Support Roster, and receive further instructions and assignments, as directed by the Emergency Preparedness Representative. 6.2.6 The Security Director will perform the following: 1
- 1. Direct the distribution of Assembly Area instructions to personnel {
exiting the Protected Area at the access control point (see Attachment 3 or 4). , 2, Direct Security personnel to coordinate with the Control Room for announcements to the designated Assembly Area (s). NOTE: The TAC and O&M Building PA system can be used to notify personnel in those buildings by using any plant phone. (see OPEP-Appendix A).
- 3. Notify personnelin Assembly Areas of instructions for the release of non-essential personnel.
- 4. Obtain and maintain personnel accountability in accordance with this procedure and SI-05.
- 5. Notify the Site Emergency Coordinator of the completion of Accountability and the number of personnel determined to be missing,if any.
- 6. Following the establishment of accountability, direct the survey of locations outside the Protected Area within the owner controlled area to warn and advise individuals,
- a. Obtain the name and address of any persons found within the owner controlled area not mustered in an Assembly Area.
- b. Recommend evacuation routes or provide further instructions as necessary.
1 OPEP-03.8.2 Rev.15 Page 11 of 22 i
V : L . 6.2 Sita Ev:cuition l: ' ^
- 7. Dispatch personnel to the parking lots to direct the flow of traffic leaving the site.
- 8. Maintain accountability of personnel within the TSC and EOF.
6.2.7 The Operations Shift Superintendent shall ensure the following:
- 1. Shift Operating personnel not otherwise assigned are assembled in the Control Room.
- 2. Shift Operations personnel assigned to tasks outside of the Control Room are contacted to verify their location and saioty. j
- 3. Generate a roster by name, badge number and location of all Operations personnelinside the Protected Area that are not inside the Control Room, or will not remain inside the Control Room during the accountability process, and provide this information to the i Security Shift Lieutenant within approximately fifteen (15) minutes of the evacuatica alarm.
6.2.8 The Emergency Repair Director shall ensure that a roster is generated which includes names and locations of each OSC individual and the information is forwarded to the Security Lieutenant as soon as possible. 6.2.9 The Work Group Supeivisor will perform the following:
- 1. Assemble personnel and designate individ'.!als, as necessary, to assist with the Assembly Area briefings.
- 2. Generate a list of known or suspected missing personnel remaining within the Protected Area and forward the information to the Security Lieutenant as soon as possible (see Attachment 1).
- 3. Segregate personnel known or suspected of being contamir'ated until they can be attended to by Health Physics personnel, if necessary.
- 4. Direct ERO qualified personnel to the TTC Auditorium for further instructions and assignments.
- 5. Discuss instructions for the release of non-essential personnel as directed by the Control Room, Security or PA announcements.
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OPEP-03.8.2 l Rev.15 Page 12 of 22 l
r 6.2 Sit 3 Ev curti::n
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- 6. . Verify personnel have transportation and have been provided any further instructions prior to release from the Assembly Area.
6.2.10 Health Physics Technicians shall be dispatched to the designated Assernbly Areas to perform radiological monitoring and direct decontamination of personnel as necessary. 6.2.11 The Emergency Preparedness Representative will perform the following:
- 1. Direct ERO personnel arriving in the Technical Training Center to sign in on appropriate sections of Attachment 2, ERO Additional Support Roster.
2.' Transmit completed copies of Attachment 2, ERO Additional Support Roster to the.TSC, OSC and EOF. Refer to OPEP-Appendix A, Emergency Response Resources for facility fax numbers.
- 3. Coordinate shift relief activities with the Administrative and Logistics Manager in t,he EOF.
'4. Provide other assistance in support of site evacuation as directed.
6.3 Building or Area Evacuation Upon the announcement of a local evacuation, persorinel will exit the area and report to their Work Group Supervisor to be accounted for and receive information. This location should normally be the Supervisor's office. if the Supervisor's office is within the evacuation zone, an Alternate Assembly Area will be designated by a PA announcement. 6.3.1 The Building / Area Evacuation Alarm is sounded, from the Con' al Room over the public address system, and an announcement for the local evacuation of all personnel within the affected location is made. 6.3.2 All individuals at the affected location shall evacuate as directed via prescribed routes using radiological and security procedures and report to their Work Group Supervisor or an alternate Assembly Area as directed by PA ar'ncuncements for accountability and further information. OPEP-03.8.2 Rev.15 Page 13 of 22 i i
6.3 Building er Ara Ev cu;ticn 6.3.3 The Security Director will perform the following: l
- 1. Where Card Reader capability is available, accountability should be performed.
1 NOTE: The TAC and O&M Building PA system can be used to notify personnel in those buildings by using any plant phone. (see OPEP-Appendix A).
- 2. Access Control Dispatch Security personne:, equipped with hand-held loudspeakers, to ensure personnel in dead areas have been notified,if required.
]
NOTE: Prior to sending personnel into a building or area that is being evacuated, ensure that there are no radiological, fire, or other hazardous conditions present that might make such entry inadvisable. 6.3.4 The Control Room SEC or OSC OPS Coordinator will perform the following: . Dispatch Fire Brigade personnel to the evacuated building or area to _ ensure all personnel have exited the location. 6.3.5 Work Group Supervisor or Alternate will perform the following:
- 1. Generate a list of known or suspected missing personnel and fonuard the information to the Security Lieutenant as soon as possible (see Attachment 1).
- 2. Segregate personnel known or suspected of being contaminated until they can be attended to by Health Physics personnel, if necessary.
- 3. Await instructions for and the disposition of the assembled personnel.
6.4 Access Control The Security Director shall control access to the site and remote emergency l facilities as follows: 6.4.1 Brief roving patrols and stationary personnel on environmental conditions, hazardous areas and security instructions and ensure Security personnel are provided dosimetry. OPEP-03.8.2 Rev.15 Page 14 of 22 j
j 6.4 Accrs Centrol !
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6.4.2 Establish security control points on the plant access roads as
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conditions allow. .
- 1. . Allow CP&L personnel unrestricted passage onto and off of the site.
Employee identification can be verified by company ID card. ;
- 2. Allow CP&L personnel without their CP&L ID, but who are listed in OPEP-Appendix A and have a photo ID, access to the site. l l
- 3. Allow non-CP&L personnel, Federal, State, and Local officials
. unrestricted passage when authorized by the Security Director and presented with an acceptable photo ID.
- 4. Provide verbal directions or maps of specific destinations to personnel unfamiliar with the site.
- 5. Direct individuals without current site access authorization to proceed to the Media Center to await approval.
6.4.3 If requested,. dispatch a guard to the Joint Information Center to assist in security and access control functions. Instruct the guard to report to the Administrative Coordinator. i v. OPEP-03.8.2 - Rev.15 Page 15 of 22
r, j .: , ATTACHMENT 1 Page~ 1 of 1 l Missing Personnel Form Work Group - INSTRUCTIONS:
- 1. This information must be given to Security within 25 minutes following the order to evacuate.
- 2. . When complete, give this sheet to Security at the access point or call the Security Lieutenant's Office, at 2257, with the information.
- 3. This form should be completed by the Work Group Supervisor or Alternate.
NAMES OF MISSING PERSONNEL LAST S5EN OR POSSIBLE LOCATION BADGE # (if unknown, write UK) ' (If known) 1. 2. 3. 4. s. 6. 7.- 6. 9..
.10. _
Print Name Date/ Time l OPEP-03.8.2 Rev.15 Page 16 of'22
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,_. ATTACHMENT 3 .
Page 1 of 1 Primary Assembly Area Instructions
; ASSEMBLY LOCATIONS O d' , A. All contractors.
l B. Maint. Il&C,
, ,,,,,,,,j Outage Mgmt.
l ctras . l C. E&RC / Chemistry, W,yJr i TO $= i Engineering. i i
------- ' A B D. Ops'. / Work Control Center, T^c Work M mt. Centers, Admin, ervices, eomse '"*"** I All other CP&L
=== lm..vl C D personnel not "C
TENiffo? tac otherwise listed. PARKNG LOT PAR NG i m,M.m" l INSTRUCTIONS: { \ i
- 1. Upon exiting Protected Area report to Work Group Supervisor in assigned TAC Building Parking Lot Assembly Arealocation.
I
- 2. Standby for further instructions.
- 3. All ERO qualified individuals not currently assigned (on duty) to the Emergency Facilities will report to their Work Group Supervisor and then report to the !
Technical Training Center Auditorium. After reporting to the auditorium, they are to immediately sign Attachment 2, ERO Additional Support Roster, and receive further instructions and assignments. NOTE: Non-essential personnellocated outside the Protected Area will i remain in their normal work location. (Except TSC/ EOF / Training Building personnel.) OPEP-03.8.2 Rev.15 Page 21 of 22
i~s . ATTACHMENT 4 . Page 1 of 1 Alternate Assembly Area instructions
. ASSEMBLY LOCATIONS
, , , semace A B l
?Ji , A. All contractors.
I n[f.f,I."o.*in. Proi ci area '. __, l i B. Maint. Il&C, Outage Mgmt. C. D. c<, ,, l C. E&RC / C,hemistry, lgyg l, ",J" auem i Engineenng 1 i I l ------- 4 D. Ops. / Work Control Center, Tac Work Mgmt. Centers, Tf0"!!t' Admin. Services, PA W LOT t&mc pl[ho I a " l All other CP&L t**c
"* he..,l Lor personnel not "C
. otherwise listed.
E l F E. Personneirrom outside the 1 tu Personnel Protected Area. 4 "e*:,' ::: '
'm;*'
--a
- INSTRUCTIONS:
- 1. Upon exiting Protected Area report to Work Group Supervisor in assigned Document Control Building Parking Lot Assembly Area location. l f
1
- 2. Standby for further instructions, i
i i I OPEP-03.8.2 . Rev.15 Page 22 of 22 L
o q t ENCLOSURE 5 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 REVISION TO PLANT EMERGENCY PROCEDURES OPEP-04.2. "Emercency Facilities and Eauipment." Revision 17 i I i
CP&L CAROLINA POWER & LIGHT COMPANY BRUNSWICK NUCLEAR PLANT infor ation use PLANT OPERATING MANUAL VOLUME XIll PLANT EMERGENCY PROCEDURE RECElVED 57 BNP UNIT MAY I 21999 0 NUCLEAR DOCUMENT C0NT 11llllllIl 11llIlll!!!I11 OPEP-04.2 EMERGENCY FACILITIES AND EQUIPMENT 1 REVISION 17 SEkE9.,ou EFFECTIVE DATE g
}hQd* l 5 fMf99 Sponcor 3/uo ct x- m E 4 99 I
Date Approval \ f!4Nh, Supervisor - Emergency Preparedness Date q i OPEP-04.2 Rev.17 Page 1 of 28 Q(($i OWQ'] cNfff)
rt REVISION
SUMMARY
OPEP-04.2 revision 17 consists of the following changes > m
. . Added information regarding the use of Attachment 2 following
' deficiencies identified during testing and those found during operation in Section 1.0.
. Added testing of the FTS-2000 phone system in Sections 5.1.6,5.1.8, 5.1.9,5.1.10,5.10.6,5.10.7, and Attachment 1.
Added OPT-96.0 and 101-03.4.1 as references in Section 2.0. and as Other Tests in Sections 5.10.6 and 5.10.7.
. Reworded Section 5.10.1 to allow different scheduling tools.
. Moved testing of ENS and HPN phones from page 1 of Attachment 1 to new pages 2 and 3 of Attachment 1.
. Added testing of the site Environmental Monitoring Team radio and cellular phone communications equipment in Attachment 3.
. Added signoffs to Sections 5 and 8 of Attachment 3.
. Added testing of the ARD phones located at the remote shutdown panels in Attachment 3.
LIST OF EFFECTIVE PAGES Paae(s) Revision 1-28 17 l l t OPEP-04.2 Rev.17 Page 2 of 2B
.[
T TABLE OF CONTENTS
- SECTION : PAGE 41.0 1 :
PU'RPOSE.?.............................................................................................................4
. 2. 0 .
R E F E R E N C E S . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
, 3 . 0 - D E F I N ITI O N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .l
' . 4.0 - R E S P ON S I B I LITI E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
5.0 i N ST R U CTI O N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .6
~ 5.1 Monthly Comm unications Test . ...... ... ....... ...... .. .......... ................................ .... 6 -
5.2 S i ren S ile nt Test . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.3 ~ S i ren G rowl Test . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.4 - Siren Fu ll Volu m e Test . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.5. .M onthly P a ge r Te st . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 3 5.6 - Q ua rte rly C h ecklist '. . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 3 5.7. Dose Projection / Environmental Monitoring Cabinet Inventory List.............. 13 5.8 ~ Miscellaneou s Supplies G uide ............. . . ......... ................... ...... ..... . .............. 14 i 5.9' OPE P-APP E N DIX A Review. . . .. .... ... . . . .. .. . . . . ... .. . .. . .. . .. . . .. . . ... .. . . . .. . . . . . . .. . . . .. . .. .. . . 14 5.10 Oth e r Te st s .'. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
~ ATTACHMENTS 1- 1 B N P Comm unications Test . .. . . . .. .. . . . . . .. . .. . . . . . . . . . . . . .. . . . . . . . . . .. . . . . . . . . .. . . . . . . .. . . . . . . . . .
2 E q uipment Repai r Fo rm . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .1. 8 3 : O SC/TSC/ EOF /J IC. Q u arterly Ch ecklist '.. .. ... .. . .. . ..... . ...... .. . ... ... .... .. . .. . .. .. .... ...... . 19 q [4 .- Miseeilaneous' S upplie s G uide .,............ ...... ... . . ........... . .. ... .. . .. .. ....... ... .. ... . .... ... 21 i 5- B N P Fax Te st Lett e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16' . Dose Projection / Environmental Monitoring Cebinet Inventory List.................. 26 l 1
- 17. Selective Signalling Individual Location Telephone Numbers ......................... 28 i
r s u m OPEP-04.2 Rev.17 L Page 3 of 28 .;
1.0 PURPOSE This procedure provides guidance for the maintenance of on-site emergency facilities and equipment. This procedure does not address those areas cov'.sred under existing programs such as Fire Protection and Diesel / Ventilation maintenance procedures. The facilities willinclude the equipment / material needed for the BNP Emergency Response Organization to adequately respond to an emergency. This procedure is intended to be performed at a frequency specified for the particular equipment / facility or as needed following an emergency drill, exercise, or event. Although equipment testing is specific, items such as office supplies will be checked to ensure an adequate supply and the numbers listed are suggested quantities. This procedure describes when county / state and NRC should be notified of equipment problems. In order to provide accurate status of EP equipment included in this procedure, Attachment 2 is to be completed for deficiencies that are noted during prescribed testing or those identified in operation.
2.0 REFERENCES
2.1 OPEP-Appendix A, Emergency Response Resources 2.2 OPEP-04.6, Radiological Emergency Kit Inventories l 2.3 IActorola - CP&L MOSCAD Siren System Operators Manual 2.4 OPEP-03.1.3, Use of Communications Equipment 2.5 OPT-48.1, Public Address System Speaker Test 2.6 OPT-93.0, EOF /TSC Building Emergency System Test 2.7 OPT-94.0, EOF /TSC Emergency Ventilation System Lineup Verification 2.8 OPM-ENG505, Covington Diesel Generator, Model 7123-7305 2.9 OPM-GEN 008, Covington Diesel Generator Electrical inspections 2.10 001-01.07, Notifications 2.11 OPT-96.0, ERDS Quarterly Test with NRC 2.12 101-03.4.1, Unit 1 Control Operator Daily Check Sheets OPEP-04.2 Rev.17 Page 4 of 28
3.0 - DEFINITIONS i 3.1 Annually At least once per 366 days. 3.2 Biweekly
. At least once every other week. <
3.3 EOF Emergency Operations Facility - 3.4 Monthly
- At least once per 31 days.
3.5 Once per Calendar Year , 1 Once anytime between January 1 and December 31. ! I 3.6 Quarterly - ' At least once per 92 days. 3.7 TSC Technical Support Center 3.8 JIC Joint Information Center 3.9 OSC Operational Support Center OPEP-04.2. Rev.17 Page 5 of 28
4c0 RESPONSIBILITIES l 4.1 Supervisor - Emergency Preparedness l Emergency Preparedness is responsible to ensure adequate and timely maintenance of the Emergency Facilities and equipment.
' 4.2 CP&L Telecommunications (Interpath) is responsible to maintain on-site equ'ipment, including selective signaling, decision line and siren equipment, at the off-site locations.
4.3 State / County /NRC Agencies Are responsible to maintain their radio equipment. l 4.4 North Carolina Emergency Management (NCEM) Operations Center The NCEM Operations Center is responsible to initiate the Decision Line test monthly. i 5.0 INSTRUCTIONS l NOTE: Due to the coordination requirements with State and County agencies that are necessary in Emergency Preparedness Programs, some test /surveillances may not occur within the strict periodicity definitions included in this procedure. Scheduling will be done to minimize this occurrence and any surveillance / test performed that exceeds the procedural definition should be noted with information identifying the reason for the deviation. In any case, the tests / surveillance deviations that occur due to coordination problems should not prevent satisfaction of the 3.25 periodicity requirement. 5.1 Monthly Communications Test Communications testing with off-site agencies will be conducted on a monthly basis to coincide with the State Procedures. This will normally be the first Tuesday of each month but may be adjusted (adjusted annually for holiday conflicts). 5.1.1 Transmit a test facsimile message (Attachment 5, BNP Fax Test Letter) to all EOCs and warning points and document on Attachment 1. The " Time" should be recorded as time the fax was sent; signature at the completion of the test documents all points acknowledge receipt. OPEP-04.2 Rev.17 Page 6 of 28 r s
r ! 5.1 M:nthly C:mmunic tirn3Tcct 5.1.2 Utilize the Selective Signalling System to simultaneously activate all warning points (Code 10-22). Conduct a roll call to validate
)
operability and document on Attachment 1. 5.1.3 Utilize the Selective Signalling System to simultaneously activate all
}
EOCs (Code 10-33). Conduct a roll call to validate operability and j document on Attachment 1. ' 5.1.4 Proceed to the EOF for a test of the State Decision Line Phone. This will be initiated by the NCEM Operations Office. Answer the phone to support the test. Verify operability and document on Attachment 1. 5.1.5 Conduct a test of the VHF radio (s) from t!. TSC to the counties. , Conduct a VHF radio test from the Control Room to a County. Verify ^ l operability and document on Attachment 1. (See OPEP-03.1.3 for use of VHF radios.) 5.1.6 Contact the NRC Region ll office from both the EOF and the TSC using the telephone number listed in OPEP-Appendix A. This call must not be made from FTS 2000 telephones. 5.1.7 Contact South Carolina Bureau of Radiological Health using the telephone number listed in OPEP-Appendix A. 5.1.8 Notify the Control Room and inform them that testing of the FTS-2000 Telephone System is in progress and request that Control Room personnel disregard the Emergency Notification System (ENS) phone in the Control Room until notified testing is complete or the ENS tolephone rings more than twice. , I 5.1.9 Conduct testing of the FTS-2000 Telephone System in the EOF and j TSC. Document results of testing on Attachment 1. Telephone l numbers for ENS and HPN c~ alls to the NRC are posted on the phones and in OPEP-Appendix A. On-Site numbers for calling the FTS-2000 telephones are found in Attachment 1. l OPEP-04.2 Rev.17 Page 7 of 28
5.1 Menthly C mmunicationn Test 1 i NOTE: On occasion, it may be necessary for the NRC Operations Center Duty l Officer to delay calling back on the ENS and Health Physics Network (HPN) telephones due to a heavy volume of communications traffic. If the Duty Office cannot call back in a reasonable time, this section of Attachment 1 must be repeated at a later time, i 5.1.10 Notify the Control Room that testing of the FTS-2000 Telephone System is complete and to no longer disregard rings on the ENS telephone. 5.1.11 Report any failures to the Telecommunications (Interpath) Help Desk (see OPEP-APPENDIX A for telephone number). Document each identified equipment problem on a separate Attachment 2. 5.1.12 Prior to returning equipment to service, verify operability by testing and document on Attachment 2. Individual telephones in the Selective Signaling System may be tested to determine operability. See Attachment 7, Selective Signalling Individual Location Telephone I Numbers, for specific selective signal location numbers. 5.1.13 Forward completed documentation to Document Control with l "0 PEP-04.2" clearly identified on the transmittal form. 5.2 Siren Silent Test A silent test of the Early Waming Siren System shall be completed on a biweekly freauency (26 times per year). 5.2.1 Log on to the siren computer and conduct a silent test by:
- 1. Access the " REPORTS" Screen (PF2).
- 2. With the mouse, interrogate "All Sites".
- 3. Verify siren polling by printout on the alarm printer (5 groups will be j polled taking about 3 minutes).
i OPEP-04.2 Rev.17 Page 8 of[8
[ 5.2 SirIn Silsnt Tut i
- 4. When " Polling Complete" is indicated, select, using the mouse,
" Silent Report".
l S. Obtain the Silent Report printout and evaluate for failures. " Normal" ! on the printout for "Communiication Test" indicates that the siren l l passes the silent test. NOTE: Refer to 001-01.07, Notifications, to determine if test results should be l l reported to the Control Room for reportability to the NRC. l- 5.2.2 Report any failures to the Telecommunication (Interpath) Help Desk l (see OPEP-APPENDIX A for telephone number) and notify the i appropriate county. Document each identified equipment problem on a separate Attachment 2, Equipment Repair Form.
- 1. Notify counties when siren (s) are placed back in service and complete Attachment 2.
i 5.2.3 Forward the Silent Report printout and copies of Attachment 2 for any failures to Document Control for retention. Clearly identify "0 PEP-04.2" on the transmittal form. l l l 5.3 Siren Growl Test l A growl test of the Early Waming Siren System shall be completed auarterly L (2nd Mondav of January. April Julv & October). Variation in test days may l occur due to holidays or state / county request. 5.3.1 Coordinate with counties on an agreed-to test date; and ensure that a news release has been issued by Site Communications, in advance, announcing the date and time of test. 5.3.2 Coordinate with the Telecommunications (Interpath) Unit to have a representative present during the test to ensure any siren failing the test can be quickly diagnosed and scheduled for repair; and notify Wilmington South Office of date and time of test. e\y r OPEP-04.2 - Rev.17 Page 9 of 28 E
; 53 Siren Crowl To:t 5.3.3 Ensure that each of the following locations have been notified on the day of the test of the test time prior to performing the test.
- 1. Control Room
- 2. NRC Resident'e Office f
- 3. Telecommunications (Interpath) Help Desk
- 4. Visitors' Center
- 5. Switchboard Operator
- 6. Site Communications Office
- 7. Wilmington South Office 5.3.4 On the test date have both counties select and perform a growl test from their console.
5.3.5 Following the test, log cn to the siren computer and conduct a growl test by:
- 1. Access the " REPORTS" Screen (PF2).
- 2. With the mouse, interrogate "All Sites".
- 3. Verify siren polling by printout on the alarm printer (5 groups will be polled taking about 3 minutes).
- 4. When " Polling Complete" is indicated, select, using the mouse,
" Growl Report".
- 5. Obtain the Growl Report printout and evaluate for failures. " Pass" on the printout for " Growl Status" indicates that the siren passes the Growl Test, or an observer at the siren site may verify that the siren sounded.
OPEP-04.2 Rev.17 Page 10 of 28
(" 5,3 Siren GrowlTc t L NOTE:- Refer to 001-01.07, Notifications, to determine if test results should be reported to the Control Room for reportability to the NRC. 5.3.6 Report any failures to the Telecommunications (Interpath) Help Desk (see OPEP-APPENDIX A for telephone number) and the appropriate county. Document each identified equipment problem on a separate Attachment 2, Equipment Repair Form.
- 1. Notify counties when siren (s) are placed back in service and complete Attachment 2.
5.3.7 Forward the Growl Report printout and copies of Attachment 2 for any j failures to Document Control for retention. Clearly identify "0 PEP-04.2" on the transmittal form. 5.4 Siren Full Volume Test A full volume test will be conducted on a once per calendar year basis. 5.4.1 Coordinate with counties / state to establish an agreed test date. This may be required during the emergency preparedness exercise with the state agencies. 5.4.2 Ensure that a news release has been issued by Site , Communications, in advance, announcing the date and time. l 5.4.3 Coordinate with the Telecommunications (Interpath) Unit to have a representative present during the test to ensure any siren failing the test can be quickly diagnosed and scheduled for repair; and notify , Wilmington South Office of date and time of test. i 5.4.4 Ensure that on the day of the test each of the following locations have j been notified of the test time prior to performing the test, j
- 1. Control Room
- 2. NRC Resident's Office
- 3. Telecommunications (Interpath) Help Desk i
OPEP-04.2 Rev.17 Page 11 of 28
r- 1 l 1 5.4 . Sir;n Full Voluma Tcct i
- 4. Visitors' Center
- 5. Switchboard Operator
- 6. Site Communications Office
- 7. Wilmington South Office 5.4.5 On the test date, have both counties select and perform one separate l full volume test or siren " Alert."
5.4.6 Following the test, log on to the siren computer and conduct a full volume test by:
- 1. Access the " REPORTS" Screen (PF2).
- 2. With the mouse, interrogate "All Sites".
- 3. Verify siren polling by printout on the alarm printer (5 groups will be polled taking about 3 minutes).
- 4. When " Polling Complete" is indicated, select, using the mouse, " Alert Report".
- 5. Obtain the Alert Report printout and evaluate for failures. " Pass" on the printout for " Siren Alert" indicates that the siren passes the Full Voltime Test, or an observer at the siren site may verify that the siren rotated at least twice and sounded at full volume for approximately three minutes.
NOTE: Refer to 001-01.07, Notifications, to determine if test results should be reported to the Control Room for reportability to the NRC. 5.4.7 Report any failures to the Telecommunications (Interpath) Help Desk (see OPEP-APPENDIX A for telephone number) and the appropriate county. Document each identified equipment problem on Attachment 2, Equipment Repair Form. l i I OPEP-04.2 Rev.17 Page 12 of 28 i i i l l
i 5.4 Sircn Full Vcluma Tcst
.5.4.8 Notify counties when siren (s) are placed back in service and complete Attachment 2.'
5.4.9 Forward the Alert Report printout and copies of Attachment 2 for any failures to Document Control for retention. Clearly identify "0 PEP-04.2" on the transmittal form.
~ 5.4.10 In January prepare and forward to the state of North Carolina and FEMA, a report certifying the successful testing of the Early Warning System sirens in the 10 mile EPZ. The report should state whether or not 90% operability of the system was attained.
5.5 Monthly Pager Test l Perform a pager test monthly. Forward documentation of the Pager Test to Document Control for retention. Clearly identify "0 PEP-04.2" on the transmittal form. 5.6 Quarterly Checklist Complete Attachment 3, OSC/TSC/ EOF /JIC Quarterly Checklist, on a auarterly basis to verify operability and availability of equipment and materials. Administrative supplies will be supplemented as necessary. Forward documentation to Document Control with "0 PEP-04,2" clearly identified on the transmittal form. 5.7 Dose Projection / Environmental Monitoring Cabinet inventory List Complete Attachment 6, Dose Projection / Environmental Monitoring Cabinet Inventory List, on at least a auarterly basis. A " spot check" should be conducted following each drill or event to ensure adequate supplies. Forward documentation to Document Control with "0 PEP-04.2" clearly identified on the transmittal form. i 1 I l l l OPEP 04.2 Rev.17 Page 13 of 28 l 1
1 1
)
5.8 Miscellaneous Supplies Guide Complete Attachment'4, Miscellaneous Supplies Guide (OSC/TSC/ EOF /JIC) on at least a cuarterly basis to verify necessary i supplies are in place. A " spot check" should be conducted following each l drill or event to ensure adequate supplies. Forward documentation to l Document Control with "0 PEP-04.2" clearly identified on the transmittal form. l: 5.9 OPEP-APPENDIX A Review I A review of OPEP-APPENDIX A will be conducted on a auarteryl basis to ; verify names, phones, and qualification status of individuals listed. Appendix A should be compared to the current ERO Team List. Individuals l should be notified to verify office, home, and pager phone numbers. Appendix A will be revised if needed by Emergency Preparedness. 5.10 Other Tests 5.10.1 Schedules for testing at prescribed frequencies defined in this procedure will be maintained by Emergency Preparedness. 5.10.2 Public Address units in the TSC and EOF are tested per OPT-48.1 on l a auarterly basis by Operations. 5.10.3 TSC/ EOF emergency diesel generator is tested per PMs, ENG505, and GEN 008 at prescribed frequencies by Maintenance. I 5.10.4 TSC/ EOF ventilation is tested per OPT-93.0 and OPT-94.0 by i Maintenance at prescribed frequencies. OPT-93.0 is coordinated by l the System Engineer. OPT-94.0 is coordinated by Operations. 5.10.5 Radiological Emergency Kits are inventoried by E&RC and Operations at prescribed frequencies per OPEP-04.6. 5.10.6 FTS-2000 ERDS telephone lines are tested on a quarterly basis per OPT-96.0 by Information Technology. 5.10.7 Control Room FTS-2000 ENS phones are tested monthly per 101-03.4.1 by Operations. 5.10,8 Test the satellite phone on at least a _ quarterly basis, i OPEP-04.2 Rev.17 Page 14 of 28
ATTACHMENT 1 Page 1 of 3 BNP Communications Test AGENCY' METHOD OF PERSON TIME i CONTACT CONTACTED Fax test to all WPs & EOCs Fax N/A Brunswick County WP Selective Signalling New Hanover County WP Selective Signalling State Warning Point Selective Signalling Brunswick County EOC Selective Signalling New Hanover County EOC Selective Signalling NCEM Operations Center Selective Signalling Coast Guard MSO "EOC"
- Selective Signalling Coast Guard Ft. Macon "EOC" Selective Signalling State / County Decision Line TSC to Brunswick County VHF Radio TSC to New Hanover County VHF Radio Control Room to either County VHF Radio NRC (Region 11 office) from Bell System EOF NRC (Region ll office) from Bell System .
TSC South Carolina Bureau of Bell System Radiological Health Comments: s l t
- Signature Date OPEP-04.2 Rev.17 Page 15 of 28 I
.. j I l ATTACHMENT 1 Page 2 of 3
~ BNP Communications Test
!- Technical Suonort Cente; (TSC)- Initials / Time - Notified Control Room of start of FTS 2000 testing' / ENS (Room 144) call to the NRC completed successfully . / Person contacted: Call from NRC to ENS (Room 144) received successfully / ENS (Room 144) call to PMCL (Room 144) completed successfully - / PMCL (Room 144) call to HPN (Room 143) completed successfully / HPN (Room 143) call to ENS * (Room 149) completed successfully / ENS * (Room 149) to HPN* (Room 149) completed successfully /
, HPN*(Room 149) to OCL *(Room 149) completed successfully /
l
. OCL*(Room 149) to RSCL *(Room 150) completed successfully /
RSCL*(Room 150) to ENS (Room 144) completed successfully / l , Notified Control Room that FTS 2000 testing is complete / !
- Phone may not be plugged into Jack. Phone must be plugged into Jack prior to test
- FTS 2000 On-Site Phone Numbers:
Emergency Notification System (ENS) 700-256-0202 Health Physics Network (HPN) 700-256-0206 Management Counterpart Link (MCL) 700-256-0204 Operation Center LAN (OCL) 700-256-0203 ; Protective Measure Counterpart Link (PMCL) 700-256-0200 J Reactor Safety Counterpart Link (RSCL) 700-256-0205 l ENS and HPN numbers for contacting the NRC are found in OPEP Appendix A or posted on the telephones. l ' Comments: i i l Completed by: Date: ! i- OPEP-04.2 Rev.17 Page 16 of 28 l. u
l 1 l ATTACHMENT 1 I l < -- Page 3 of 3 ) BNP Communications Test Emeroency Operations Facility (EOF) Initials / Time Notified Control Room of start of FTS 2000 testing / ENS (EOF NRC Room) call to the NRC completed successfully / 1 l Person contacted: Call from NRC to ENS (EOF NRC Room) received successfully / ENS (EOF NRC Room) call to RSCL (EOF NRC Room) completed successfully / RSCL (EOF NRC Room) call to ENS (in Simulator) call completed successfully I ; ENS (in Simulator) ca!! to EOF HPN (Room 123) completed successfully / HPN (Room 123) call to PMCL' (Room 128) completed successfully / PMCL* (Room 128) call to HPN* (Room 128) completed successfully / HPN* (Room 128) call to ENS * (Room 131) completed successfully / l ENS * (Room 131) call to OCL* (Room 131) completed successfully / OCL* (Room 131) call to MCL* (Room 131) completed successfully / MCL* (Room 131) call to EOF ENS (EOF NRC Room) completed successfully / Notified Control Room that FTS 2000 testing is complete /
- Phone may not be plugged into Jack. Phone must be plugged into Jack prior to test FTS 2000 On-Site Phone Numbers:
Emergency Notification System (ENS) 700-256-0202 Health Physics Network (HPN) 700-256-0206 Management Counterpart Link (MCL) 700-256-0204 Operation Center LAN (OCL) 700-256-0203 Protective Measure Counterpart Link (PMCL) 700-256-0200 Reactor Safety Counterpar1 Link (RSCL) 700-256-0205 ENS and HPN numbers for contacting the NRC are found in OPEP-Appendix A or posted on the telephones. Comments: Completed by: Date: OPEP-04.2 Rev.17 Page 17 of 28 L
~ ATTACHMENT 2 Page 1 of 1 Equipment Repair Form Person Identifying Problem: Equipment Out of Service: Description of Problem: Problem Reported To For Action: Date/ Time EFFECTED AGENCIES CONTACTED: Name of Contact / Agency: Date/ Time Name of Contact / Agency: Date/ Time Name of Contact / Agency: Date/ Time Name of Contact / Agency: Date/ Time Explanation of Repair: Equipment Retested and Restored to Service: / Signature Date Previously Contacted Agencies Notified: / Signature Date OPEP-04.2 Rev.17 Page 18 of 28
1 i ATTACHMENT 3 Page 1 of 2 , OSC/TSC/ EOF /JIC Quarterly Checklist i 1
. CORRECT DISCREPANCIES WHICH CAN BE CORRECTED AS THIS CHECKLIST IS BEING COMPLETE. DOCUMENT ALL OTHERS.
- 1. : Emergency Lighting Test operation of emergency lights by depressing the " Test" button and verifying both lamps illuminate: (See Note)
Initial /Date
-EOF Command Room /
-Room 128 (EOF) /
-TSC Command Room /
-TSC ERFIS Area /
-Room 138 (TSC) /
-Room 139 (TSC) /
-Room 149 (TSC) /
-Room 150 (TSC)
/
- 2. Clocks Verify the correct time is displayed and check battery (replace if needed)
-EOF Command Room /
-Room 128 (EOF) /
-TSC Command Room /
-TSC ERFIS Area / !
-Room 138 (TSC) -/
-Room 139 (TSC) /
-Room 149 (TSC) /
-Room 150 (TSC) /
- 3. Copiers
- l l Fill paper trays and verify copy quality 1
-EOF /
-TSC /
-JIC (CP&L supplied copiers) /
OPEP-04.2 Rev.17 Page 19 of 28 [ L
+ , i l
- ATTACHMENT 3 !
Page 2 of 2 OSC/TSC/ EOF /JIC Quarterly Checklist
- 4. Facsimile /Telecopiers I Fill paper trays and verify correct date and time is displayed
-EOF Outgoing / !
-EOF Incoming / !
-TSC /
-JIC (All) /
- 5. Public Address / Intercom System l Verify operability including volume levels in each room. (Replace batteries, if necessary) )
-EOF /
-TSC /
-OSC /
-JIC /
- 6. Communications Equipment Verify operability of automatic ring down phones ERM to SEC / .
CM to CD / SEC to Control Room / Conduct quarterly test of Satellite Telephone / Conduct test of state Environmental Monitoring Team / j remote radio in the EOF l Conduct test of the Site Environmental Monitoring Team / radio and cellular telephone in the EOF i Conduct test of ARD to TSC phones located at the U1 and / U2 remote shutdown panels
- 7. Equipment !
-Check the material condition of all communications headsets '
-/
-Replace batteries in Pl Specialist headsets (JIC) /
-Check the material condition and readiness of all facility rooms / ,
-Verify 10 copies of SPDS large sheets are available (TSC and /
EOF)
- 8. Discrepancies that are not easily corrected have been /
documented and appropriate notifications made NOTE: Emergency lighting batteries have a 5-year expected lifetime. Replace with "Sure-Lite", Part #026-117 SP, from Cameron & Barkley. Signature Date ! OPEP-04.2 Rev.17 Page 20 of 28 l r
p
,l'
(, ATTACHMENT 4 h Page 1 of 4' Miscellaneous Supplies Guide (TSC Room 143) Minimu'm Quantity ; Item Amount on ' N' umber .. Hand Needed 24 EXPO dry erase markers (various colors) 12 Black " Flair Type" markers 12 Red ' Flair Type" markers 15 Highlighters 2 Stapfers 2 bx Staples 3 - Staple Removers 3 bx Thumb tacks 1 Tape dispenser 4 ris Scotch tape 1 rl Masking tape 1 rl Duct tape - 2 bx Small binder clips 2 bx Medium binder clips l 2 bx Large binder clips 2 bx Regular paper clips 1 Paper clip caddy 2 bot Liquid paper 2 bot Liquid paper thinner 1 bx Rubber bands (Various sizes) 1 pair Scissors 75 Black ballpoint pens ! 1 Portable first aid kit 2- Stenographer pads 12 Lined pads 10 Telephone message pads 1 pk Speed SNAP-A-WAY memos 10 Logbooks 15 CP&L telephone directories 15 ROLM operating instructions 15- Local telephone directories 1 ream Copier paper - 12- Flashlights with batteries 24 D-cell batteries l 5 Radar lights with batteries 8 AA batteries for microphones 4 Signature Date
- c L OPEP-04.2 ' Rev.17 Page 21 of 28 i.
l._
o l I l ATTACHMENT 4 Page 2 of 4 Miscellaneous Supplies Guide (EOF Room 122) l Minimum item Amount on Number Needed Quantity Hand 24 EXPO dry erase markers (various colors) 12 Black " Flair Type" markers - l 12 Red " Flair Type" markers 15 Highlighters 2 Staplers 2 bx Staples 3 Staple Removers 3 bx Thumb tacks 1 Tape dispenser 4 ris Scotch tape 1 rl Masking tape I 1 rl Duct tape 2 bx Small binder clips 2 bx Medium binder clips 2 bx Large binder clips 2 bx Regular paper clips 1 Paper clip caddy 2 bot Liquid paper 2 bot Liquid paper thinner 1 bx Rubber bands (Various sizes) 1 pair Scissors 75 Black ballpoint pens 1 Portable first aid kit 2 Stenographer pads 12 Lined pads 10 Telephone message pads 1 pk Speed SNAP-A-WAY memos l 10 Logbooks 15 CP&L telephone directories 15 ROLM operating instructions 15 Local telephone directories 1 ream Copier paper l 12 Flashlights with batteries ! 24 D-cell batteries 5 Radar lights with batteries 8 AA batteries for microphones Signature Date OPEP-04.2 Rev.17 Page 22 of 28 L
F
\
ATTACHMENT 4 Page 3 of 4 Miscellaneous Supplies Guide (JIC Command Room) Minimum item Amount on Number Needed Quantity Hand 24 EXPO dry erase markers (various colors) 20 Highlighters 3 Staplers 2 bx Staples 2 Staple Removers 2 bx Pins 1 Tape dispensers . 2 ris Scotch tape 1 rl Masking tape 1 rl Duct tape 2 bx Small binder clips 2 bx Medium binder clips 2 bx Large binder clips 2 bx Regular paper clips, 2 pk Correction tape 1 bx Rubber bands (Various sizes) 2 pairs Scissors 3 bx Black pens 1 Portable first aid kit 1pkg Lined pads 2 Telephone message pads 1each Logbooks ERO position 4 CP&L Directory 1 Local Directory 5 reams Copier paper 12 AA batteries 1 box News release paper 10 Media Handbooks 1 box Media Badges 100 Public Information Brochures 5 pks Post-it notes Signature Date OPEP-04.2 Rev.17 Page 23 of 28
ATTACHMENT 4 Page 4 of 4 Miscellaneous Supplies Guide (OSC Locker) Minimum item Amount on Number Needed Quantity Hand 1 Telephone monitor 11 Rolm phones 2 Pushbunon phones 1 Dry erase marker cleaner solution 1 box Kim Wipes 1 can All Purpose Cleaner 12 Note pads 6 Logbooks 6 CP&L Directory / phone books 12 Pens 12 Pencils 1 Stapler 1 Procedures Set of Controlled PEPS 2 (each Event Classification signs classification) 2 No Eating / Drinking / Smoking signs 1 bag Disposable shavers 2 cans Shaving cream Signature Date OPEP-04.2 Rev.17 Page 24 of 28
7
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ATTACHMENT 5 f~ Page 1 of 1 BNP Fax Test Leuer DATE TO: Brunswick County Warning Point New Hanover County Warning Point N. C. State Warning Point (NC Highway Patrol Communications Center) Brunswick County EOC
- New Hanover County EOC NCEM Operations Center, Raleigh EOC ,
Coast Guard Fort Macon Station EOC. Coast Guard MSO, Wilmington EOC ' FROM: CP&L Brunswick Nuclear Plant This is a test of the BNP emergency facility telecopier function to off-site agencies. Upon receiving this message, please call and leave a voice mail message confirming you received this fax. Thank you CP&L Brunswick Plant Emergency Preparedness Unit ! 1 !. l i t OPEP-04.2 Rev.17 Page 25 of 28 { L
ATTACHMENT 6 Page 1 of 2 Dose Projection / Environmental Monitoring Cabinet inventory List ITEM QUANTITY AMOUNT ON (Approx.) HAND ~
"Texwipe" Terminal Wipes 1 box invisible Tape 1 box Staplers 2 Staple Removers 2 Staples - 1 box Scientific Calculator 1 Plastic Compass 1 Pens 1 box Pencils 1 box Dry-Erase Markers 4 Fine-lins Markers 4 Laser Printer Paper 1 ream I Writing Tablets 6 Transparencies for Laser Printer 1 box Carbon Paper 1 box Rulers (long/ regular size) 3 Scotch Tape . 4 rolls Binders 2 Paper Clips 1 box Highlighters 6
' Erasers 6 Correction Tape 1 box Flashlights 2 Extension Cords 1 Multi-Outlet Strips 3 Logbooks (Dose Proj. Coord/EMTL) 2 Computer Mouse 1 CPLDOSE Program Diskette 1 Person Performing Test Date REFERENCE MATERIALS:
Reg. Guide 1.109 (October 1977) Binder containing the following:
*NUREG / CR-3011, " Dose Projection Considerations for Emergency Conditions at Nuclear Power Plants" (1983)
- Stone and Webster Radiological Conseq.
"NRC Accident Source Term l Technical Basis for CPL Dose (March 1995) l OPEP-04.2 Rev.17 Page 26 of 28 L:
f ATTACHMENT 6 Page 2 of 2 Dose Projection / Environmental Monitoring Cabinet inventory List Meteorology and Atomic Energy (1968) Radiological Health Handbook (1970) l NUREG / CR-2298, USDOE, " Measurement of Release of Rad. Xenon, Krypton, and lodine from UO2 at Typical Light Water Reactor Conditions and Comparison with Release Models", November 1981 Rad. Decay Data Tables (2 copies),1981 NUREG / CR-2260, NUS 3854, " Technical Basis for Reg. Guide 1.145, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants",1981 NUREG / CR-2227, " Rad. Material Release from Nuclear Power Plants (1979) NUREG 0771, " Regulatory impact of Nuclear Accident Source Term Assumptions" (1981) NTIS Workbook of Atmospheric Dispersion Estimates (1970) Manual of Protective Action Guides and Protective Actions for Nuclear Incidents - EPA (1992) NUREG / CR-1918-ORNUNUREG-79, " Dose' Rate Conversion Factors for External Exposure to Photons and Electrons (August 1981) Reactor Shielding Design Manual (1956) l "Microshield" Version #3 (October 1987); Information to evaluate dose from shielded / unshielded radioactive sources. i United Engineers," Post-Accident Dose Analysis"(February 1980) l Post-Accident Sample Station Update Memo (12/2/81)/ Extent of Core Damage Under Accident Conditions ." Draft" (September 1981) Plant Emergency Procedures (PEPS) l Hurrevac Manual 1 Surrogate Tour Diskette l-l OPEP-04.2 Rev.17 Page 27 of 28 L t i
ATTACHMENT 7 Page 1 of 1 Selective Signalling individual Location Telephone Numbers
- 1. Warning Points (WPs)
Brunswick County 10-87 New Hanover County 10-89 State- 10-86
- 2. Emergency Operations Centers (EOCs)
Brunswick County 10-95 New Hanover County 10-96 State Operations Center 10-93
- Coast Guard MSO (Wilmington) 10-97 Coast Guard T. Macon 10-92
- 3. BNP Locations Control Room 10-82 EOF 10-84 TSC 10-83 PBX Room (Rm 136) 10-85
- 4. Group Numbers All Warning Points 10-22 All EOCs 10-33 All Warning Points & EOCs 10-44 All BNP Locations 10-55 OPEP-04.2 Rev.17 Page 28 of 28 i}}