NRC-89-0217, Forwards Rev 1 to Radiological Emergency Response Preparedness Plan.
| ML19325D688 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 10/20/1989 |
| From: | Sylvia B DETROIT EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-89-0217, CON-NRC-89-217 NUDOCS 8910250320 | |
| Download: ML19325D688 (1) | |
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W'a B. Ralph SylvD ' ,
. sen.or vice Peesioent p.
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October 20, 1989 NPC-89-0217 l [ U. S. thelear Regulatory Conunission
, -Attn Docunant Control Desk '
4 Washington, D. C. 20555
Reference:
Fermi 2 g NJC Docket No. 50-341 NIC License No. NPF-43
Subject:
Submittal of Fermi 2 Annual Radiological l Bnaroancy Response Preparadnama Plan Update t In accordance with 10 CPR 50.54(q) Detroit R5ison is submitting Revision 1 of the Fermi 2 Radiological Bnergency Response Preparedness {. ) . J Plan. . The changes. in this revision were primarily administrative in ff , ,, nature and were made to reflect current plant operation. All the changes to the Fermi 2 Radiological Bnergency Response Preparedness Plen were reviewed and it was determined that they do not decrease the effectiveness of the emergency plan and so are consistent ti with the requirements of 10 CPR 50.54(q) . A copy of the effectiveness , review is attached for your information.
. j Should you have any questions regarding the changes, the effectiveness
, review, or the Radiological Bnergency Response Preparedness Plan, please contact Ms. Joan Malvehill at (313) 586-4326.
l l Sincerely, l Enclosure fl i j 4 cc A. B. Davis R. C. Knop W. G. Rogers J. F. Stang 4 h02gCK05000343 20 892020 l-F { \\ , PNU \
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EFFECTITEMSS REVERV D0ctBIEWt& TION i 1
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'Emetion/ Pane chanee _
Rmala A,1/A-1 Requirement added for initial Per Letter of Agreement ;
'E.3/E-2 notification of Unusual Event between Fermi 2 and Province a to the Province of Ontario. of Ontarie. Notification to 1 Canada not addressed in State or Federal requiremento.
A.2/A-2 All references to the State State of Michigan determined 1 A.3/A-3 On-scene E00 deleted. this facility to be unneces-C.1/C-1, C-2' sary and has removed it from Fig. F-2/F-7 MEPP. No Federal requirement for this facility. Duties will be carried out in the State EOC. A.3/A-3 Initiation of emergency No change, clarification only ' notification procedures in Wayne County specified to be . performed by the Wayne County Central Communication office of the Sherrif f's department. . A.4/A-4 U.S.- Coast Guard assistance to Per Letter of Agreement be requested by State only, not between State Emergency by the State or Monroe County. Management Division and Coast Guard District Commander.
- l. A.5/A-4 All Health Physics personnel Recent job title change "D.1/B-1 titles changed to " Radiation in the organization.
Table B-1/B-4 Protection". No change in job tunctions. ( Table D-1/D-10 l- /D-34 l' /D-35 J.1/J-2 K.1/K-1 i K.2/K-2 K.3/K-3 ; K.4/K-3 B.2/B-2 JPIC Manager position deleted. Position determined to be unnecessary. Responsibilities transferred to JPIC Corporate j e Spokesperson or JPIC Administrator. No change, specification only l l B.3/B-3 Monroe Cuctomer Office replaced "an Edison General Of fice" in Facility is used to stage the list of of fsite ERF. offsite RETs.
n =~ - - - Raet{an/Pasa Phanom Ramin Tchie B-2/B-5 Job Titles revised. Recent job title changes l /B-7 in the organisation.
/B-8 Responsibilities of ERO l> positions maintained.
/B-11
/B-12 l .
Tcble B-2/B-10 Responsibility added for TSC SPDS upgrade program enhanced' Support Engineers to trend ' system capabilities and thus plant' parameter on ERIS SPDS. enhanced the support that engineers can provide to the ERO. Tcble B-2/B-10 Reportability of TSC Status It has been determined from l- Fig'. B-4/B-17 Board Clerks changed from TSC experience in drills and Administrator to Technical exercises that this will Communic a tor. provide more ef ficient supe rvis ion. l Fig. B-5/B-18 Reportability of Offsite It has been detertined from j l Liaisons changed from Nuc. experience in drills and ] Ops. Advisor to EOF Administrator. exercises that this will ; provide more ef ficient j supe rvis ion. l= Fig. B-1/B-14 Outage Manager replaced Recent changes in j Supervisor, Planning & Scheduling. organizational stn cturc ' of Nuclear Production Supervisor RERP repisced and Nuclear Generation. Director. Regulatory Af fairs. Responsibilities of ERO positions maintained. Supervisor. Surveillance Programs repisced Startup Engineer. Test Phase. i 1 D.2/D-2 Activation of EOF and JPIC at NUREC 001. r equires l Alert level removed. acte . s:- 3f these l facility- 't Site Area I and Gene r.1 levels only. D.2/D-3 " Reduction of emergency class" No change in intent. D.3/D-4 changed to "de-escalation". Clarification only. D.4/D-5
/D-6 Table D-1/D-10 Greater than ( > ) revised to Correction of typographical :
/D-11 greater than or equal to ( 2t ). error.
Table D-1/D-34 Inserted " unexpected" ARM alarm To allow for expected condition required for declaration alarm condition, e.g. of Alert. TIP Room ARM alarm.
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n.eetan/Pama r*kanes Rmala
- Telecommunication System. Recent change in Corporate
- F.1/F-3 Information System Organisation" organisational structure.
replaced " Communication System Responsibilities of ERO Divison. Electrical System". maintained . R.3/H-8 Number of TLD offsite monitoring Updated information. stations changed from 30 to 39. Definition of dose assessment No change in i$ tent.
- I.3/I-2 Enhancement and
/I-4 added. Descriptions of dose .
clarification only.
/I assessment methods clarified.
/I-7 No reference or technical Incorrect Ground Contamination l Table J-1/J-6 Action Level of 2000 Ci/sq. meter basis available to support removed. this PAG. Ingestion PAGs is a requirement for the i State, not the licensee. !
per NUREG 0654/ FEMA REP-1. ! Supervisor. Nuclear Information Detriot Edison position l M.2/M'6. Fig.M-1/M-7 repisced Director. Public has been deleted . Infoma tion. ERO responsibilities have been assumed by Supervisor, ,
- Nuclear Information. l Table 0-1-B/0-5 Training requirement of Modules From experience in drills and l 11 & 13 for Chemistry Technicians axercises, this training has removed. been determined to be not applicable to the duties and l responsibilities of Chemistry !
Technicians. App. 1-27 MCCC Agreement - change in the Relocation due to areas designated for use by construction modifications < Detroit Edison as the operating at MCCC. The operation of location for the JPIC. JPIC is not af fected. i H.5/H-9 Procedure references updated Recent upgrade of Fermi l 8 thoughout text and appendixes. Procedure program. J.2/J-3 All procedural requirements J.3/J-4 of the Plan maintained. K.1/K-1 K.2/K-2 App 3-2 App 3-3 App. 3-5 App. 4-3 0
' " ~ ' " ' ' " ' "' - - ~ - _ - - _ _ , _ _ _ _ _ _ _ _ _ _
' D'etr:lt Edisin - F;rmi 2 RERP PLAN
' R;vislin 1 c
RERP PLAN
- Revision Summary:
- 1) Added requirement for initial notification of Unusual Evet to the Province of Ontario.
- 2) Deleted all references to the State of Michigan On-Scene Emergency Operations ,
l Center.
- 3) Clarified title.of Wayne County Sheriff's Department receiving emergency [
notification in Section A.3. i
- 4) Revised Section A.4 to state that U S. Coast Guard assistance would be requested j only by the State of Michigan,
- 5) Updated all Health Physics personnel titles to Radiation Protection.
- 6) Deleted JPIC Manager position in Section B.2. Responsibilities transferred to JPIC Corporute Spokesperson or JPIC Administrator.
7)' Listed Monroe Customer Office as Offsite ERF in Section B.3. ,
- 8) Revised job titles and clarified responsibilities of Emergency Response Organization l personnel in Table B-2. >
- 9) Revised Figure B-1 to reflect current Nuclear Organization titles. ,
- 10) Modified reportability of Status Board Clerks in Figure B-4 and Offsite Liaisons Figure B-5.
- 11) Updated Reference to Seaway Hospital (Peoples Community Hospital Authority) to '
Seaway Hospital (United Care, Inc.) in Section C.2. and Letter of Agreement.
- 12) Deleted activation of EOF and JPIC at Alert level in Section D.2.
- 13) Clarified reduction of emergency classification to be de-escalation in Section D. .
- 14) Corrected Table D-1 data to read > values and clarified unexpected increhse in radiation level on Page D-34. ,
- 15) Revised Section F.1.7 to reflect current corporate structure.
- 16) Updated number of TLD station locations in the Offsite Monitoring Program (Section H.3).
- 17) Defined Dose Assessment and clarified description of Dose Assessment methods in .i Section 1.
!! 18) Deleted incorrect Ground Contamination Action Level from Table J-1. l 19) Updated Section M to reflect current organization titles. l 20) Revised training requirements for Chemistry Technicians in Section O.
- 21) Updated Letters of Agreement with Monroe County Community College.
- 22) Updated procedure references throughout text.
- 23) Updated Index of RERP Implementing Procedures (Appendix 3).
- 24) Updated index of Supporting Procedures and Documents (Appendix 4).
L Implementation Plan ' j 1) This plan will be in effect upon approval.
- 2) No unique implementation plan is required.
l Attachments - None Enclosures - None ARMS - INFORMATION SERVICES Date approved: Release authorized by: Change numbers incorporated: DTC TMPLAN DSN Rev 1 Date PlS PIS File 1715.03 Recipient l l<
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LIST OF ABBREVIATIONS vill
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, PREFACE 'x .
a A. . ASSIGNMENT OF RESPONSIBILITY (ORGANIZATION CONTROL) A-1. A.1 Octroit Edison A-1 c.- A.2 - State of Michigan A- 1 ' A.3 Local Governments A-3
', " A.4 ( Federal Agencles A-4 A.5 Emergency Response Services A-4 A.S.1 Medical Gervices A-4 4- A.S.2 Ambulance Service A-4 A.5.3 Firefighting Assistance A-5 A.5.4 Law Enforcement Services A-5 A.S.5 Technical Assistance A-5 A.6 Continuity of Resources A-5 SECTION -A- Figures j Figure A-1: Fermi 210-Mile Emergency Planning Zone A-6 'l
. Figure A-2: Fermi 2 50-Mile Emergency Planning Zone A-7 l-Figure A-3: State of Michigan Nuclear incident Response Organization A-8 Figure A-4: Monroe County Emergency Function and Agency l Assignment Chart A-g l Figure A-5: Wayne County Emergency Function and Agency ,
Assignment Chart A-10 ; Figure A-6: Emergency Operation Center interrelationships A-11
; B. EMERGENCY RESPONSE ORGANIZATION B-1 B.1 ' Nuclear Organization B-1 B.1.1 Normal Organization B-1 D.1.2 Emergency Response Organization B-1
, B.2 Emergency Assignments B-1 B.2.1 Responsibilities B-1 B.2.2 Offsite Emergency Response Organization B-2 B.3 Emergency Response Organization Interfaces B-3 i
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Pege l i SECTION-B- Tobles and Figures i J Table B-1:. Staffing for Fermi 2 Emergency Response
, Organization B-4' l . Table B-2: Emergency Response Organization Functional u Responsibilites B-5 l Figure B-1: Nuclect Operations Organizations B-14 l Figure B-2: Emergency Response Organization: Control l Room (Unusual Event) B-15 Figure B-3: Emergency Response Organization: Control l Room & Operational Support Center (Alert - Site Area Emergency - General l Emergency) B-16 Figure B-4: Emergency Response Organization:
- - Technical Support Center (Alert) B-17 l Figure B-5
- Emergency Response Organization: Emergency l Operations Facility (Site Area Emergency -
General Emergency) B-18 5 C. EMERGENCY RESPONSti: SUPPORT AND RESOURCES - C-1 C.1 Government Support C-1 1 C.2 Industry Support C-2 1 D. EMERGENCY CLASSIFICATION SYSTEM D-1 J D.1 Unusual Event D-1 D.1.1 Definition D-1 , L < D.1.2 Purpose D-1 l L D.1.3 Licensee Actions D-2 ; D.1.4 State and/or Local Offsite Authority Actions D-2 D.2 Alert D-2 I D.2.1 Definition D-2 D.2.2 Purpose D-2 D.2.3 Licensee Actions D-2 D.2.4 State and/or Local Offsite Authority Actions D-3 D.3 Site Area Emergency D-3 l D.3.1 Definition D-3 l D.3.2 Purpose D-3 l- D.3.3 Licensee Actions D-3 L D.3.4 State and/or Local Offsite Authority Actions D-4 D.4 General Emergency D-5 D.4.1 Definition D-5 D.4.2 Purpose D-5 D.4.3 Licensee Actions D-5 D.4.4 State and/or Local Offsite Authority Actions D-5 SECTION -D - Tables Table D-1: Classification of Emergencies D-7 il I )
T A B. RERP Plan Revision 1 TABLE OF CONTENTS (Con't) Page E. NOTIFICATION METHODS AND PROCEDURES E-1 E.1 Notification of Onsite Emergency Response Organizations E-1 E.2 . Notification of Offsite Emergency Response Organizations E-1 E.3 Notification of the General Public E-2 SECTION -E - Tables and Figures , i Table E-1: Prompt Notification System Siren Locations . E-3 Figure E-1: Siren Locations E-6 l F. EMERGENCY COMMUNICATIONS ,
- . F.1 Telephone Communications F-1 i F.1.1 CBX Lines F-1 l~ F.1.2 Direct-Ring Lines F-1 f
- F.1.3 - NRC Telephones F-2 l
- F.1.4 . Microwave System F-3 ,
L F.1.5 Medical Support Facilities F-3 L F.1.6 Joint Public Information Center (JPIC) F-3 l F.1.7 Telephone Equipment Maintenance F-3 F.1.8 General Information F-3 F.2 Radio Communications F-4 F.2.1 Operations and Maintenance System F-4 1 F.2.2 Offsite Radiological Emergency Teams F-5 F.2.3 Nuclear Security System F-5 F.3 Facsimile Transmission F-5 F.4 Public Address System F-5 F.5 Plant Intercom System F-5 SECTION-F - Figures Figure F-1: Emergency Communications Telephone Network F-6 Figure F-2: Emergency Response Direct-Ring Lines F-7 l G. PUBLIC EDUCATION AND INFORMATION G-1 G.1 Education and information Program G-1 G.2 Public Awareness G-1 G.3 News Centers G-2 G.4 Information Sources During an Emergency G-2 G.5 News Media Acquaintance Program G-3 l 1 ill
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( TABLE OF CONTENTS (Con't) Page b H. EMERGENCY FACILITIES AND EQUIPMENT H.1 ' Emergency Response Facilities H-1
, H.1.1 Control Roorn H-2 H.1.2 Technical Support Center H-2 H.1.3 Operational Support Center H-3 i H.1.4 Emergency Operations Facility H-4 H.2 Onsite Monitoring Systerns H-5 i
.H.2.1 Geophysical Phenomena H-5 i H.2.1.1 Meteorological Monitoring H-5 l H.2.1.2 Hydrological Monitoring H-6 I
.H.2.1.3 Seismic Monitoring H-6 l H.2.2 Radiological Monitoring H-6 i H.2.3 Process Monitors H-6 H.2.4 Fire and Combustion Product Detectors H-6 H.3 Offsite Monitoring Systems H-7 4 i '
H.3.1 Geophysical Phenomena H-7 H.3.1.1 Meteorological Monitoring H-7 H.3.1.2 Hydrological Monitoring H-7 ll .H.3.1.3 Seismic Monitoring H-7 l H.3.2 Radiological Monitoring H-7 l H.3.2.1 Offsite Monitoring H-7 l H.3.2.2 Laboratory Facilities H-8 l H.4 Emergency Response information System (ERIS) H-8 J l' H .S Emergency Equipment and Supplies H-9 SECTION-H - Tables and Figures
':, Table H-1: Meteorological Parameters H-10 Table H-2: Typical Area Radiation Monitors H-11 1' H-12 Table H-3: Radiological Effluent Monitors Table H-4: Typical Portable Monitors H-13 Table H-5: Post-Accident Process and Effluent l Radiation Monitors H-14 Table H-6: Process Radiation Monitors H-15 Table H-7: Radiological Environmental l
Monitoring Program 1988-1989 H-16 , Table H-8: Supplemental TLD Stations H-19 Table H-9: Typical Laboratory Equipment H-22 Figure H-1: Block Diagram of Detroit Edison ; Meteorological Data Acquisition System H-23 , Figure H-2: Sampling Locations by Station Number (Site Area) H-24 Figure H-3: Sampling Locations by Station Number (Site Area - Lake Erle) H-25 Figure H-4: Sampling Locations by Station Number , (Greater than 5 Miles) H-26 Figure H-5: Sampling Locations by Station Number (Less than 10 Miles) H-27 IV l 1
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- l. ACCIDENT ASSESSMENT 11 in-Plant Monitoring Capability 1-1 1.2 Source Terms 1-1 1.2.1 Monitoring instruments Operable 1-1 1.2.2 Monitoring instruments inoperable 1-1 1.3 Dose Assessment 1-2 1.3.1 Airborne Releases 1-2 1.3.1.1 Methodology 1-2 1.3.1.1.1 Manual Method I-3 1.3.1.1.2 Microcomputer Model 1-4 1 1.3.1.1.3 ERIS Model 1 !
l.3.2 - Liquid Releases . 1-8 f.3.3 Long-Term Dose Assessment l-8 I 1.4 Field Monitoring I-8 j
-l J. PROTECTIVE RESPONSE J-1 !
J.1 Onsite Notification J-1 ) J.2 Evacuation J-3 J.2.1 Monitoring and Decontamination J-3 J.2.2 Accountability J-3 J.3 Radiation Protection Equipment J-4 l J.4 Protective ' Actions J-4 i J.4.1 Basis for Recommending Protective Actions J-5 J.4.2 Evacuation Time Estimates J-5 J.4.3 ' Population Distribution J-5 J.4.4 Offsite Monitoring J-5 SECTION-J - Tables and Figures 1 Table J-1: Guidelines for Protection Against ingestion of Contamination for the Public J-6 Table J-2: Summary of Possible Offsite Protective l L Actions to be Recommended or Implemented l During an Emergency J-7 , Table J-3: Representative Shielding Factors from Gamma 1 Cloud Source J-8 ) Table J-4: Representative Shielding Factors for Surface Deposited Radionuclides J-9 i Table J-5: Distribution of 1980 Population in Emergency Planning Zone Rings and Sectors, J-10 Monroe and Wayne Counties, Michigan Figure J-1: Owner-Controlled Area J-11 Figure J-2: Evacuation Routes and Assembly Areac J-12 Figure J-3: Population Map J-13 v l
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a' i RERP Plan - Revision 1 TABLE OF CONTENTS (Con't) j Page l K. RADIOLOGICAL EXPOSURE CONTROL K-1 l K.1 Exposure Ouldelines . K-1
.K.1.1 Control of Personnel Radiation Exposure K-1 [
K.2 Dosimetry .K-2 K.3 Decontamination Criteria K-3 r K.4 Contamination Control K-3 SECTION -K - TABLES Table K-1: Emergency Exposure Criteria K-5 L MEDICAL SUPPORT L-1 L1 OMsite Support L-1 L1.1 Hospitals L-1 L1.2 Services L-1 L2 <Onsite First Aid Capability L-2 L3 Transportation Arrangements L-2 M. ' REENTRY AND RECOVERY PLANNING AND ' POST-ACCIDENT PLANNING M-1 M.1 Reentry and Recovery M-1 M.2 Recovery Organization M-3 M.3 Recovery Operations Notification M-6
' M.4 Population Exposure Evaluation M-6 M.5 Recovery Organization Composition M-6 SECTION -M- Figures Figure M-1: Recovery Organization M-7 N. EXERCISES AND DRILLS N-1 N.1 Exercise Requirements N-1 N.2 Drill Requirements N-1 N.2.1 Communications N-1 ,
N.2.2 Fire N-2 N.2.3 Medical Emergency N-2 N.2.4 Radiological Monitoring N-2 , N.2.5 Radiation Protection N-2 N.2.6 Additional Drills N-2 N.3 Drill and Exercise Scenarios N-2 N.4 Conducting Drills and Exercises N-3 >
- 0. RADIOLOGICAL EMERGENCY RESPONSE PREPAREDNESS TRAINING O-1 0.1 Qualification Requirements for Onsite Emergency Response Personnel 0-1 0.2 Training Requirements for Offsite Organizations 0-2 vi
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RERP Plan Revision 1 TABLE OF CONTENTS (Con't) Page SECTION - O - TABLES l Table 0-1: RERP Training Courses and Training Matrix O-3 ; 1 P. RESPONSIBILITY FOR THE PLANNING EFFORT: DEVELOPMENT, PERIODIC REVIEW, AND DISTRIBUTION OF RERP PLANS P-1 i P.1 Responsibilities P-1 P.2 Format of the RERP Plan P-1 - P.3 Review and Revision of the RERP Plan P-2 P.4 Review and Revision of RERP Program P-3
- APPENDIX 1 App.1-1 Letters of Agreement EMTS Ambulance Service App.1-3 Frenchtown Fire Department App.1-7 General Electric Company
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App.1-10 lnstitute of Nuclear Power Operations l (* Nuclear Power Plant Emergency Response Voluntary Assistance Agreement") App.1-13 Mercy Memorial Hospital Corporation App.1-23 ' Monroe County Community College App.1-27 Mutual Assistance Agreement between: App.1-33 Consumers Power Company l Detroit Edison App.1-33 The Toledo Edison Company App.1-33 I Indiana Michigan Power Illuminating Company App.1-33 The Cleveland Electric illuminating Company App.1-33 Seaway Hospital (United Care incorporation) App.1-44 l U.S. Department of Energy (Chicago Operations Office) App.1-49 i APPENDIX 2 l Emergency Broadcast Syr. tem Plan App.2-1 I
' APPENDlX 3 List of RERP Implementing and Administrative Procedures App.3-1 APPENDIX 4 l
List of Supporting Procedures end Documents identified in the Plan App.4-1 l L APPENDIX 5 l RERP Plan Cross-Reference with NUREO-0654 App.5-1 vil
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o < o if ' - ' RERP Plan i, a Revision 1 [ '-[ LIST OF ABBREVIATIONS AB - Auxiliary Building - .,
'APRM: -
Average Power Range Monitor < ) ARM ' Area Radiation Monitor 1
- BWR - -
Boiling-Water Reactors
.CAS '
Central Alarm Station CBX. - Computerized Branch Exchange '
]'
Closed Circuit Television CCTV- -
.CHRRM -
Containment High. Range Radiation Monitor 1 CR '- Control Room i CWH - Circulating Water Pump House , DID - Direct inward Dialing . EBS- - Emergency Broadcast System - l
, ECCS -
Emergency Core Cooling Systems l NEDG -
. Emergency Diesel Generator l EECC .
Employe Emergency Communications Center )
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EECW - Emergency Equipment Cooling Water EMD - Emergency Management Division
, ENS -
. Emergency Notifications System (NRC)-
EOC . Emergency Operations' Center 1 i' EOF- -' Emergency Operations Facility .,i Environmental Protection Agency EPA" . Radiological Emergency Response Preparedness Administrative Procedures EPAs - EPs '- Radiological Emergency Response Preparedness implementing Procedures i f EPZ - Emergency Planning Zone ERF- - . Emergency Response Facility l !< ERIS - Emergency Response Information System , l' FEMA - Federal Emergency Management Agency l= FRERP. - Federal Radiological Emergency Response Plan L .FSAR - Final Safety Analysis Report L; GE - General Electric a GMJ, - General Maintenance Journeyman GPM
- Gallons per minute b, GSW -
General Service Wcter } ( .- GTOC - General Training and Orientation Center . HPCI - High Pressure Coolant injection 2 HVAC - Heating, Ventilation, and Air Conditioning l&C - Instrument & Controls INPO - Institute of Nuclear Power Operations IRM - Intermediate Range Monitor l> ', vill l l. E i-L L
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- LIST OF ABBREVIATIONS (Con't)
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JPIC ' -
' ' Joint Public information Center
, < JPIT -
' Joint Public information Team
'LOCA -
Loss of Coolant Accident LPCI -~ _- Low Pressure Coolant injection MBT' - Michigan Bell Telephone Company
- j. MEPP -
. Michigan Emergency Preparedness Plan MREM . -
Millirem' , Main Stream Isolation Valve: MSIV - uCl/cc - - Microcuries per cubic centimeter uCi/g . - Microcuries per gram uCi/kg ' - Microcuries per Kilogram
. uCl/l - Microcuries per Liter uCi/sec -
' Microcuries per second {
NASS- - : Nuclear Assistant Shift Supervisor o
.,, NOAA -
National Oceanic and Atmospheric Administration Nuclear Operations Center
'NOC .
a NRC .- Nuclear Regulatory Commission 1
-NSO. -
Nuclear Supervising Operator NSRG - Nuclear Safety Review Group NSS :- Nuclear Shift Supervisor
.OSC '- Operational Support Center .
OSRO - Onsite Review Organization , L' PAG -- Protective Action Guideline PRM - Process Radiation Monitor J PRMS. -1 < Process Radiation Monitoring System j L 'RB - Reactor Building - j l
- l. RBCCW ' - Reactor Building Closed Cooling Water RCIC - Reactor Core isolation Cooling q
', RERP -
Radiological Emergency Response Preparedness
- RET -
Radiological Emergency Team RHR - Residual Heat Removal RWB - Radweste Building i SAS - Secondary Alarm Station ; SOTS - Stand-by Oas Treatment System SRV - Safety Rollef Valve i SSE - Safe Shutdown Earthquake ; STA - Shift Technical Advisor ; l< -TAC- - Technical Assistance Center l TB - Turbine Building < p TLD - Thermoluminescent Dosimeter 'j TSC - Technical Support Center ; ix
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' A. ASSIGNMENT OF RESPONSIBILITY (ORGANIZATION CONTROL) 3 RERP planning for an incident at Fermi 2 is a cooperative effort involving Detroit Edison, the State of Michigan, local government agencies, federal government agencies, ;
provincial agencies in Ontario, Canada, and various organizations that provide support ' for these agencies. Each organization has the responsibility to assure, through' ! i coordinated planning and regularly scheduled ' exercises, that it can provide an effective l emergency response 24 hours a day. The responsibilities of the state and local . ;
. government Emergency Response Organizations are summarized in Figures A-3 through i A-5. The interrelationships of the organizations supporting the Fermi 2 emergency response are shown in Figure A-6, A.1 Detroit Edison l' ,
E in the event of a radiological emergency at Fermi 2, Edison's Onsite Emergency Response Organization will initiate corrective and protective actions to control the g incident and mitigate its effects. The incident will be clast.ified as an Unusual Event, an Alert, a Site Area Emergency, or a General Emergency based upon the criteria in Section , D. Detroit Edison provides initial emergency notification to the State of Michigan via the Michigan State Police and to Monroe and Wayne Counties via the Monroe County Sheriff's Office, and Wayne County Emergency Management. These offices have communication centers staffed 24 hours a day. l Notifications and required Protective Action Recommendations to Canada will be made ; I by Detroit Edison to the Province of Ontario, Provincial Police Headquarters once at the initial classification of an Unusual Event, Alert, Site Area Emergency, and General t l- Emergency. All subsequent information updates will be coordinated by me Michigan Department of State Police. Throughout an emergency situation, Detroit Edison maintains control over onsite perscnnel, equipment, and activities. The Vice President, Nuclear Engineering and Services / alternate, acting as the Emergency Officer, has ultimate responsibility for the Edison emergency response. The Fermi 2 Emergency Response Organization evaluates plant, meteorological, and radiological conditions to provide timely protective action recommendations to State and local Emergency Response Organizations. A.2 State Of Michigan The Governor of the State of Michigan has complete authority over offsite emergency operations and decision making when a radiological emergency occurs at Fermi 2 and a
" State of Disaster" is declared under the provisions of Act 390 of the Public Acts of 1976. The State Director of Emergency Services (Director, Department of State Police),
under the direction and auspices of the Governor, has the responsibility for coordinating the state's emergency response. The State Director of Emergency Services heads the 1 State Emergency Management Division (EMD), which directs and coordinates various State agency responsibilities.
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RERP Plan Revision 1 Page A-2 State responsibilities include, but are not limited to, radiological assessment via t-environmental sampling and monitoring, implementation of protective actions .. 3 IL :(evacuation or shelter), control of food and water supplies, damage assessment, medical uervices, sanitation, environmental protection, dissemination of warning and notification : L l- Information, security, traffic control and maintenance, public information, and crisis f counseling. The Michigan Emergency Preparedness Plen'(MEPP) details the specific duties of each State agency or department,
- ' The MEPP is activated when the Governor, as a rssult of availaDie information or at the !
I l request of a county, declares a State of Disaster. When a disaster has been declarod, p, available State resources age mobilized for the response, and state authority supersedes
+ local authority. ' t.ocal plans are also activated at this time, if not previously activated, l The State Emergency Operations Center (EOC) in Lansing is activated for coordination of L state emergency activities. The EOC is staffed by State personnel in accordance with j l the MEPP as summarized in Figure A-6 to provide the executive liaison and data ,
verification purposes. Communications with the State from Detroit Edison are j l transmitted via direct ring or CBX telephone lines. The state has provided for, and is 1 capable of,24-hour-per-day operation for a protracted period of time during an ! eme<gency situation at fermi 2. The Department of State Police and the Department of Public Health (Division of ; Radiological Health) are the primary State Response Agencies during a radiological .j emergency. The Department of State Police is responsible for general planning, , command and control, and overall direction and coordination including: ]
- Receiving initial notification of the emergency and notifying other state agencies
- Providing periodic information updates to affected local governments, adjacent !
states, and the Joint Public Information Center (JPIC)
- Notifying and providing periodic information updates to the Province of Ontario, ,
Canada through the Ministry of the Solicitor General in Toronto, Canada f Operating the State EOC
- Coordinating with local organizations to implement protective actions based on technical advice by the Divlsion of Radiological Health to evacuate and/or shelter l
l-the general population ; l - Notifying the Federal Emergency Management Agency (FEMA) and other Federal agencies as required and providing liaisons to these agencies a i l i l.
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RERP Plan Revision 1 Page A-3 l The Department of Public Health, Division of Radiological Health, is responsible for environmental monitoring, meteorology, offsite dose assessment and dose projections, and formulating protective action recommendations for the general public. A.3 Local Governments Wayne and Monroe County governments have established emergency response facilities in accordance with their individual emergency preparedness plans. Upon notification of r a radiclogical emergency at Fermi 2, the Monroe City / County Joint Communications
>' Center initiates notification procedures in Monroe County.
l When notified of an emergency at Fermi 2, the Wayne County Central Communication L initiates notification procedures in Wayne County, includ(ng calling the Gibraltar, Flat
- j. Rock, and Rockwood Police Departments and the Brownstown Township Fire Department.
Detroit Edison maintains communications with Wayne and Monroe Counties until the State EOC in Lansing is activated, at which time all communications with the counties I, are channeled through the State EOC. i The Chairperson of tlw Monroe County Board of Commissioners la responsible for Monroe County emergency preparedness and has the authority to declare a " State of . Emergency" within the county in the event of a radiological emergency at Fermi 2. If a l
- State of Emergency
- is declared, the Monroe County Emergency Operations Plan is .
l implemented and the Monroe County EOC is activated at the Office of Civil l Preparedness. The EOC is staffed with personnel from county agencies as shown in l Figure A-4. The Wayne County Executive is responsible for Wayne County emergency preparedness and the implementation of the Wayne County Emergency Operations Plan. The Wayne County EOC is located at the Wayne County Criminal Justice Center and is activated upon notification of a radiological emergency at Fermi 2. The Wayne County EOC is staffed with personnel from county agencies as shown in Figure A-5. In addition, l personnel from Brownstown Township will occupy the Wayne County EOC. County responsibilities include, but are not limited to, access and traffic control, firefighting and rescue, public warning and information, sheltering (Involving food, ! clothing, sanitation, medical services, and counseling), decontamination centers, transportation of persons and supplies, and evacuation of the general population. These actions are directed and coordinated from the respective county EOCs. These local emergency response activities are coordinated with the state through the State EOC. Both Monroe and Wayne Counties have made provisions for and are capable of 24-hour 4 operation for extended periods of time during an emergency situation at Fermi 2. ________-_--___________A
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RERP Plan ! s Rovision 1 Page A-4 l A.4 Federal Agencies j Federal Agencies will be activated according to the Federal Radiological Emergency ; Response Plan to provide support to ut%ty, state, or Iccal authorities upon notification from the utility er state of an emergency that may affect public health and safety. The U.S. Nuclear Regulatory Commission (NRC) is responsible for conducting investigative activities associated with an emergency and verifying that emergency plans have been - Implemented and the appropriate agencies have been notified. The NRC is also responsible for the notification of other Federal agencies.' The NRC response is described in NUREG-0723. Rev.1. Further actions of Federal Emergency Management Agency ,. (FEMA) and the NRC are outlined in NUREG-0981/ FEMA-51. I i The U.S. Coast Guard will provide assistance through the Federal Radiological Emergency Response Plan upon rec;uest from the State of Michigan in the event that an ; emergency at Fermi 2 may affect act!vities on I.ake Erie, including Canadien waters. l FEMA is responsible for ensuring that offsite protective actions are carried out , appropriately and expeditiously by the state. FEMA also provides coordination of other federal emergency response agencies and provides back-up provisions to support state j l and local emergency response organizations. 1 A.5 Emergency Response Services The nature of an emergency may require augmenting onsite response groups wita l I l offsite services, personnel, and equipment. Support from offsite organizations, such as those listed in Appendix 1, may be obtained by direct notification to the individual l organization by the Emergency Director or Emergency Officer. Types of services that I may be required are briefly outlined below. q L A.5.1 p.edical Services - In the event of en emergency involving an injury to onsite
- personnel, Seaway Hospital (Trenton) or Mercy-Memorial Hospital (Monroe) is' called I
upon to provide medical aid. Detroit Edison also has a corporate medical staff of
- l. doctors and nurses for assistance.
l The Control Room ensures notification of the appropriate hospital and provision of L pertinent information if the injury involves radiological contamination. Radiation i p Protection personnel are dispatched to perform contamination surveys for the l ambulance service and at the hospital. l l Ambulance Service - Contractual arrangements have been made with an ambulance I A.S.2 service for the transportation of patients from Fermi 2. This includes individuals who f may have injuries complicated by the presence of radioactive contamination or who may ) have exceeded personnel exposure limits. They will be transported to either Seaway Hospital or Mercy-Memorial depending on the medical needs of the injured person. I n.,,,,,n---
[, [ t ' HERP Plan Revision 1 Page A-5 1 A.S.3 Firefighting Assistance - In the event the Fermi 2 Fire Brigade requires assistance with an onsite fire, the Frenchtown Volunteer Fire Department will be called. All firefighting l- , . personnel periodically receive training for fighting fires involving radiological hazards. A.S.4 Law Enforcement Services - Civil disorder or other plant security threats may require prompt augmentation of the onsite security force. in the event law enforcement L services are required, the Monroe County Sheriff's Department or the local Michigan State Police barracks (Flat Rock Post #25) are notified. A.5.5 Technical Assistance - Detroit Edison has entered a mutual emergency assistance l agreement with Cleveland Electric illuminating Company, Consumers Power Company, l Indiana and Michigan Electric Company, and Toledo Edison Company. This agreement
- l. provides personnel and equipment for offr,ite radiation monitoring activities.
l In addition, the Institute of Nuclear Power Operations (INPO) may be callod upon for
- l. technical support. A dedicated emergr; icy call number is capable of activating the INPO support function on a 24-hour basis. INPO will be able to provide the following support ~
functions:
- Assistance in locating sources of emergency staff with nuclear and health physics !
I experience l Analysis of the operational aspects of the incident , 1 l
- Cbtaining nuclear operations experts for assistance and advice in technical matters {
- Assistance in locating sources of specialized equipment i i
i Technical / engineering assistance is also available from the following organizations: l j Babcock 8 Wilcox
- General Electric Company
- Sargent and Lundy Engineers
- NUS Corporation Stone and Webster 1 Assistance in the analysis of environmental samples will be performed by the contractor ;
l or vendor who conducts the routine Radiological Environmental Monitoring Program. I A.6 Continuity Of Resources Sufficient staffing is provided to ensure that the Fermi 2 Emergency Response 1 Organization can operate on a continuous,24-hour basis for extended periods of time. Communications systems between Detroit Edison and offsite authorities are available I and are staffed 24 hours a day. These systems are discussed in detail in Section F of this plan. Detroit Edison's Senior Vice President, Nuclear Generation, the Vice President, Nuclear I L Engineering and Services, and the Vice President, Nuclear Operations are reponsible for I ensuring continuity of technical, administrative, and material resources. l l
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RERP Plan . Revision 1 - 4 Page B-1 S. EMERGENCY RESPONSE ORGANIZATION B.1 Nuclear Organlaation B.1.1 Normal Organlaation - The Nuclear Organization includes operating, technical and administrative support, engineering, and management personnel. Figure B-1 is a chart showing the functional levels and detailing the plant and technical support organizations. The Nuclear Organization is onsite during normal working hours Monday through Friday, excluding holidays. Plant Operations, Radiation Protection, Chemistry, and Security personnel are onsite on a 24-hour basis including holidays. The minimurn shift complement is specified in Technical Specifications Section 6.2, Table 6.2.2.1. l . B.1.2 Emergency'Hosponse Organlaation - In the event of an emergency at Fermi 2, the Emergency Response Organization shown in Figures B-2 through B-5 is activated. As l shown in the figures, the normal complement of shift personnel is augurnented h according to the emergency classification. The Nuclear Organization provides the fH majority of the personnel required to staff the organization. Additional Detroit Edison personnel are called upon to provide specific expertise as required. During an emergency, the Emergency Response Organization is located in the Control 4 Room and the three Emergency Response Facilities (ERFs) described in Section H of this l plan: Operational Support Center (OSC); Technical Support Center (TSC); and Emergency Operations Facility (EOF). It is Detroit Edison's intent to activate the ERFs based on the emergency classification. I The Emergency Response Organization is predefined by the Supervisor, RERP. Alternate I assignments to various positions are speufid to provide timely, unambiguous staffing. ! L Taole B-1 shows the minimum staffing for tla Fermi 2 Emergency Response l Organization according to functional area, ERF, and emergency classifiation. Table B-1 I reflects Detroit Edison's intent to achieve the 30-minute and 60-minute augmentation times indicated in Table B-1 of NUREG-0654/ FEMA-REP-1 and in Supploment 1 to l' NUREG-0737 as a dostrable goal for staffing the ERFs. i It is the goal of Detroit Edison to augment Control Room staff hy the Emergency l l 1 Response Organization (Table B-1)in two groups of key personnel. The first group of key personnel should be in their Emergency Response Facility within 30 minutes of an Alert being declared. The second group of key persoarsi should be in place within 60 ! minutes of a Site Area Emergency being declared. The emergency c111-out list it l arranged such that personnel living closest to the plant would be called first to meet the intent of the augmentation goals of NUREG-0654. B.2 Emergency Assignments B.2.1 Responsibilities - The organization and functional responsibilities of the Emergency Response Organization personnel are outlined in Table B-2 for the key functional positions.
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i RERP Plan I Revisloa 1 Page B-2 i When the EOF is activated, the Emergency Officer assumes overall management ! responsibility for the Emergency Responso Organization and for all assignments in the l organization. The Emergency Officer also assumes full responsibility for all coordination I and interaction with offsite response organizations, with the exception of the local fire I department, the ambulance service, and the hospital for contaminated injured personnel. l Tt:ese organizations are, and will continue to be, contacted through the Control Room, ) The EOF will be the focal point for meteorological data, dose assessment and projection, i offsite redhMical field surveys, and recommendations for protective action for the i general public within the 10-mile EPI. The Emergency Officer will approve all protective l action recommendations made to the State, when the EOF is activated. The Emergency Director, EOF Staff, and Joint Public Information Center (JPIC) Corporate Spokesperson report to the Emergency Officer. The Emergency Officer: (1) ensures that the full resources of Detroit Edison are made available as required to secure the plant systems and to minimize the effects of the incider,t on plant personnel and the public, including the availability of other utilities, vendors, and consultants,(2) ensures that information , released to the public is accurate and directed through proper channels, (3) i communicates with Corporate Headquarters, and (4) ensures that too long-term 1 emergency and recovery organizations are established. ] The Emergency Director assumes full responsibility for the emergency response , measures and implementation of the RERP Plan prior to activat6on of the EOF At the onset of an emergency, the Nuclear Shift Supervisor (NSS) assumes the role of the ' Emergency Director and retains this role until rolleved of the responsibility by the Plant Manager / alternate. ] The Emergency Director operates from the Control Room initially, and then from the TSC should the situation progress beyond the Unusual Event classification. Certain . responsibilities may be delegated to other individuals or groups, with the exmtion of f i decisions to: (1) classify the emergency; (2) authorire radiation exposures over 10 CFR ; 20 limits for emergency workers; and (3) make protective action recommendations to , offsite response organizations (prior to EOF nctivation). ! Operations, techrdcal, and administrative support personnel will be assigned according to f the needs of each ERF Table B-2 describes the functional duties and responsibilities of the personnel who may be present in each of the facilities. ! B.2.2 Offsite Emorgency Response Organlaation - Detroit Eoison corporate management personnel listed below villl be available via the Divisional Organization Emergency Headquarters located in the corporate offices in Detroit.
- Chief Executive Officer - Respons ble for corporate support from the Corporate Headquarters President - Alternate for the Chief Executive Officer l
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< l i RERP Plan Revision 1 :
Page U-3 l 1 B.3 Emergency Response Orgenlaation interfaces The onsite ERFs are discussed in Section H. The offsite centers are, at a minimum, ! Monroe Customer Office, Wayne-Monroe Division Headquarters, and the emergency j centers of the federal, state, and local response organizations. The interface among all ; these centers provides a logical flow of information in a direct and unambiguous manner and is based on the functional responsibilities of each center. Communications systems, as discussed in Section F, are provided to maintain these primary interfaces. I 3
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o I RERP Plan , Revision 1 : Page B-5 i TABLE t-2: EMERGENCY RESPONSE ORGANIZATION FUNCTIONAL RESPONSl81LITIES ! f
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Position Location Reports To Responsibilities ' t Emergency Emergency Chief Overall emergency ; Officer Operations Executive management. , Facility Officer, , Vice President Detroit Approve all protective action Nuclear Operations Edison recommendations. Vice President Ensure that the full resources of Nuclear Engineering Detroit Edison are maos available : and Services to secure the plant systems and to minimize ' the eNects of the General Director, incident on plant personnel and Nuclear Engineering public. This includes availability of other ! utilities and vendor resources, i Assistant to Vice President - Nuclear Engineering and Interface with govemmental . authorities as required. Services Ensure information released to the public is l prompt and accurate and roles:ad through proper channels. ; Establish long-term emergency and recovery organizations.
- Communicate with Corporate Headquarters. :
I i Emergency Control Emergency implement the immediate , Director Room Officer onsite corrective and protective actlons to bring the incident . Nuclear Shift under control and mitigate its l Supervisor effects. , Classify the emergency. ! Plant Manager Technical Emergency Initiate offsite notifications and . l Superintend- Support Officer protective action recommendations. ent, Center Operations Interface with governmental authorities as : required. Director, Nuclear Training Ensure Detroit Edison personnel are l l l Supervisor, Quality called in as conditions warrant. L Propram Assurance 1
1 t, .se 4 l CERP Plan )j n Revision 1 Section B-6 . TADLE B-2 (Con't) ! Functional I
, Position Location Reports to Responsibilities l
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Emergency Director Ensure that Information to ! (Continued) be released to the public be released to the l public is prompt, accurate, and released ! through proper channels. l l Coordinate and direct the combined activities l of Detroit Edison personnel In the Control ! Room, TSC, OSC, and elsewhere on j owner-controlled property. ' Authorize plant and emergency workers to , receive radiation doses in excess of 10 CFR 20 j l' limits. Obtain assistance of offsite support organizations as necessary. I 1 . l' Shift Control Emergency Advise the Emergency i Technical Room Director Director on plant technical l Adviser matters. ! Shift Technical Access meteorological data. ) Advisor Perform dose assessment based on potential or actual radiological releases. l i Reacter Control Emergency Analyze conditions I' Eng6neer Room Director affecting core safety. Shift Nuclear Advise the Emergency Engineer Director / Nuclear Shift Supervisor on all ; matters relating to reactor core safety, , P
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o t l RERP Plan - Revision 1. Section B-7 TABLE E-2 (Con't) Functional Pos6 tion iocation Reports to Responslbilities OSC Operational Emergency Direct maintenance operations. Coordinator Support Director ! Center Dispatch onsite emergency teams. j Supeiintendent, Maintenance and Advise the Emergency Director on t Modifications repair activities. : i General Supervisor, Recommend maintenance actions to l Maintenance Electrical mitigate the emergency, I Provide work assignments for maintenance personnel. l
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Technical Technical Emergency Provide recommendations to the Engineer Support Director Emergency Director on plant ! Center , technical matters, ! Operations Engineer Request technical and engineering analyses ; from the Nuclear Safety Technical Engineer Advisor. [ Director, Plant ! Safety Nuclear Technical Emergency Advise the Emergency Director i i Safety Support Director on plant engineering matters. l l- Advisor Center l Provide work assignments for f
- Assistant to Nuclear Engineering Support General Director, groups. ;
Nuclear Engineering ; General Supervisor, ; Engineering Design : end Services ; i General Supervisor, ; Special Projects l l General Supervisor, Plant Engineering l 1
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m 1 RERP Piers l Revision 1 ; Page B-8 j 1 I TABLE B-2 (Con't) : I Functional { Position Location Reports to Responsit.'.lities ; Rad 6ation Technical Emergency Advise the Emergency Director j Protection Support Director concerning offsite protective ! Adviser Center action recommendations. ) i General Provide work direction for radiation i Supervisor, protection and dose assessors. ) Radiation Protection Ensure personnel e.:posure records are ] i maintained. Radiological ) Engineer Ensure TSC habitability surveys are performed. ; Supervisor Authorire the Dispatch of Onsite Radiation RETs. ! Protection l Authorizes the Dispatch of Offsite RETs until the EOF is activated, j Evaluate results of offsite environmental surveys ! until the EOF is activated. l Ensure that radiation protection equipment, such as dosimetry devices, respiratory protection gear, , and protective clothing, is issued and controlled, f as required. + Direct onsite decontamination activites. . Dese Technical Radiation Perform onsite and offsite dose Assessor Support Protection assessment and projections. . Center Advisor Engineer Assess meteorological conditions and projections. Nuclear Training Specialist Specialist Radiation Protection s .
RERP Plan Revision 1
! Section B-g TABLE D-2 (Con't) l t
Functional Position Location Reports to Responsibilities i Radchem Technical Emergency Direct in-plant Chemistry sampling l Adviser Support Director activities, i I Center Direct Radicchemistry Laboratory activ!tl*4 : r Chemist Advise Emergency Director on l Engineer red-waste processing / storage / disposal, i Security Technical Emergency Ensure that site security is Advisor 9upport Director maintained and appropriate r Center contingency measures are implemented. - General Super-Visor Security Ensure that security and traffic Operations control measures are in effect, including traffic direction during , evacuation Security Shift . , Supervisor Ensure personnel accountability procedures are implemented in the event of a radiological i emergency or the need for plant / site evacuation. , Maintain security of the TSC. l 4 - Advise the Director, Nuclear Security and l Emergency Director on matters related to , f security,
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i i l RERP Plan j Revision 1 l Page B-10 i TABLE B-2 (Con't) Functional l Position , Location Reports to Responsibilities TSC Technical Emergency Ensure that all notifications and ! Administrutor Support Director communications to ONsite ! Center organtiations are accomplished ; Statt within time requirements, i Assistant Maintain and control documentation concerning l the emergency. l Business l Analyst - Supervise TSC communicators, and clerical ' support. i Coordinate logistical support for onsite ; emergency personnel. Advise the Emergency Director on matters ! relating to personnel and equipment. j Provide for replacement or addition of TSC personnel or equipment as conditions warrant, Support Technical Nuclear Use ERIS SPDS to trend key plant Engincors Support Safety parameters. Center Advisor Engineer Advise Nuclear Safety Advisor on plant i engineering matters as required. { l l 1 1 l-
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REC'P PCn i Revision 1 ! P6pe B-11 } TABLE B-2 (Con't) Functional Posillen Location Reports to Responsibilities ; Radiation Emergency Emergency Direct and coordinate offsite , Protection Operations Officer environmentcl assessment activities. ! Coordinator Facility t Direct Radiological Emergency Team ; Coordinator, Dose Assessors, 4 ! Superintendent Meteorologists, and Laboratory l Radiation Tech l Protection ! Determine survay areas for offsite RETs. Supervisor, i Radiological Determine environmental i Engineering samples / surveys, j Supervisor, Advise Emergency Officer on offsite Radiological protective action recommendations. Health
- Evaluate results of offsite environmental surveys. l Direct activities in EOF Emergency Laboratory.
Ensure personnel exposure records are t maintained. Ensure EOF habitability surveys are performed. Ensure that radiation protection equipment, such as dosimetry devices, respiratory protection gear, , and protective clothing, is issued and controlled. Implement a vehicle monitoring / decontamination program. i Dese Emergency Radiation Perform dose assessment and Assessor Operations Protection projections. Facility Coordinator Engineer Assess meteorological conditions as rcquired. Nuclear Training ; Specialist , Meteorologist Emergency Radiation Assess meteorological conditions and Operations Protection projections. Facility Coordinator Engineer
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- . ;A i CEMP Plan l Revision 1 i Page B-12 ,
l !' TABLE S-2 (Con't) . ! 1 i Functional ' Polition - Location Reports to Responsibilities Red 6eleg6 cal Emergency Radiation Update RET status, i Emergency Team Operations Protection Coord6nator Facility Coordinator Coordinate efforts of the 1 Offsite RETS. ; Nuclear Training Specialist l 1 l Nuclear Emergency Emergency Advise Emergency Officer on plant Operat6ons Operations Officer status. Advisor Facility Provide updated information to the l Supervisor, Detroit Edison liaisons to the ISEO State of Michigan, Monroe County, and Wayne l County. 1 Nuclear Training .,. j Operations Supervisor Senior Nuclear l Training Specialist ; j 1 Public Emergency Emergency Prepare information under the j lnformation Operations Officer direction of the Emergency J Coordinator Facility Officer for prompt release to the j Joint Public Information Center i Supervisor, (JPIC). Nuclear information I
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Media Relations Specialist ; GOF Emergency Emergency Ensure that all notificat'ons and I
- Administrator Operations Officer communications to otsite J Facility organizations ::e accomplished 1 Senior Nuclear within timo requirements. l Training Specialist -
Ensure communications with offsite 1 Supervisor, emergen;y response organizations ! Planning Services are er,testished. Maintain and control documentation concerning ; the emergency.
m.. l l t j RERP Plan i Revision 1 Page B-13 i TABLE 3 2 (Cen't) ; i
I Functional P064 tion . Location Repotisto Responsibilities EOF Administrator Maintain and control documentation l (Continued) concerning the emergency. ;
Suparvise EOF status board clerks, communicators, and cierical support. ; 6 Coordinate logistical support for onsite , emergency personnel. j i Advise the Emergency Officer on matters relating to personnel and equipment. ; Provide for replacement or addition of EOF i personnel or equipment as conditions warrant. j f Security Emergency Emergency Coordinate access and egress of } Advisor Operations Officer offsite personnel to owner- t Facility controlled area. [ Director, Advise the Emergency Officer Nuclear Security on security matters, j l l Supervisor, Maintain security of the EOF. ! Background ; investigations ! l ! l l
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, j newe54- man i EMERGENCYRESPONSE ORGANIZATION: Wn 11s
{ CONTROL ROOM (UNUSUAL EVENT)* i t EMERGENCY DIRECTOR (Nuolear Shift Supervisor) { i SHIFT TECHNICAL COMMUNICATOR , ADVISOR : i i l 1 NUCLEAR ASSISTANT ! SHIFT SUPERVISOR f I NUCLEAR SUPERVISING - OPERATOR c !
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%M RERP Plan EMERGENCY RESPONSE ORGANIZATION: P 5-CONTROL ROOM & OPERATIONAL SUPPORT CENTER (ALERT SITE AREA EMERGENCY + GENERAL EMERGENCY)
EMERGENCY DIRECTOR (Nuolear Shm Superymor) M I ! STA SHIFT NUCLEAR OSC ENGINEER COORDINATOR r i NUCLEAR ASSISTANT SHIFT SUPERVISOR l j NON UCENSE NUCLEAR SUPERVISING . ONM OPERATOR I (Assigned to Rounds) FIRE i NON UCENSED OPERATORS SRIGADE (Not Assigned to Rounds) ' RP/ CHEM TECHS ALERT i CONTROL ROOM . l' l l
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*" RERP PLAN i
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EMERGENCY REPONSE ORGANIZATION:' ",$"q'y p -- TECHNICAL SUPPORT CENTER (ALERT) l EMERGENCY DIRECTOR j 5 f f TYPIST ! f t RADIAT10N ) TECHNICAL RADCHEM TSC- SECURITY !. ADVISOR PROTECTION , ENGINEER ADVIDOR ADMINISTRATOR ADVISOR ADVISOR : i 1 1 TECHNICAL - SUPPORT DOSE COMMUNICATORS COMLUNICATOR ENGINEERS ASSESSORS CLERICAL SUPPORT 1 s
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STATUS ; SOARD CLERKS ALERT TECHNICAL SUPPORT CENTER
I i Flows B-S RERP Plan l EMERGENCY RESPONSE ORGANIZATION: ImpIN1b l 1 EMERGENCY OPERATIONS FACluTY i (SITE AREA EMERGENCY GENERAL EMERGENCY) l i EMERGENCY OFFICER l
- l TYPIST t
RADIATION i NUCLEAR EOF SECURITY PUBUC OPERATIONS PROTECTION INFO ! ADMINiSTMTOR ADVISOR ADVISOR COORD MTOR COORDINATOR I i l I ; i UAISONS TO ' COMMUNICATORS STATE OF Ml. STATUS BOARDS , WAYNE AND CLERICAL SUPPORT a MONROE COUNTIES l DOSE ASSESSORS . l- RADIOLOGICAL EMERGENCYTEAM COORDINATOR METEOROLO3IST SITE AREA EMERGENCY OFFSITE RETs EOF EMERGENCY ! LABORATORY TECH l OPERATIONS ! FACILITY 1
l RERP Plan Revision 1 Page C-1 C. EMERGENCY RESPONSE SUPPORT AND RESOURCES , This Plan Section describes arrangements for requesting and effectively using ; government or other industry support to augment the onsite emergency response capability. 2 C.1 ' Government Support Federal assistance can be requested as needed by the Emergency Officer or the Emergency Director. Federal assistance is available through the Federal Radiological Emergency Response Plan (FRERP). Requests can also be initisted by the Michigan . Department of Public Health as stated in Annex Q, Section F to the Michigan Emergency ; Preparedness Plan (MEPP). In addition, the Nuclear Regulatory Commission (NRC) dispatches representatives to the EOF and to the TSC in accordance with l NUREG-0981/ FEMA-51 and NUREG-0728, Revision 1, Federal representatives are ! l expected to be dispatched to the Joint Public Information Center to participate in the . coordinated dissemination of information to the media. Airfields in the vicinity of the ptsnt that may be used by emergency suppon groups l l
' include commercial airports and small municipal airports that can only accommodate l small aircraft. The approximate distances in miles and directions to these airfields from j Fermi 2 follow. Three helicopter landing pads are located in the Fermi 2 l Owner-Controlled Area. )
Airport teistance, Mi Direction i Commercial l l \ Detroit Metropolitan 19 NNW Detroit City 34 NNE Toledo Express 39 SW i NW J Willow Run 24 Municipal i Marshall 2 W Carl 6 NNW Custer 10 W i Grosse lie 11 NNE State and local command centers that may be available to support federal response include the State EOC located at the Department of State Police (Emergency L Management Division) in Lansing, Michigan, the alternate State EOC for Fermi 2 located at the Northville State Police District Headquarters, Northville, Michigan. The State Emergency Operations Centers (EOCs) are described in the MEPP. l
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i I RERP Plan Revision 1 ) l Page C-2 1 The local EOCs are described in detail in the Monroe County and Wayne County, Emergency Operations Plans. The Monroe County EOC is located in the Monroe City-County Ctfice of Civil Proparedness, Monroe, Michigan and the Wayne County EOC i
,. Is located at 5.he Emergency Management Division, Romulus, Michigan. ;
i Detroit Edist,n will provide liaison personnel to the State and county EOCs. These l llelsons are knowledgeable in the integrated aspects of the Fermi 2 RERP Plan. ; The state rosy have a Liaison Officer from the Department of State Police or the .; Departmer,t of Public Health in the EOF; the counties may dispatch liaisons as they j deem necessary. In addition, the Division of Radiological Health, Michigan Depanment i of Public Health has a mobile laboratory capable of analy:Ing radiological and environrnental samples. a C.2 Industry Support Detreit Edison, a member of the Institute of Nuclear Power Operations (INPO),is provided with the INPO Emergency Resources Manual, which identifies a number of personnel that various organlaations utilities, service companies, Architect / Engineers ; (A/Es), and reactor vendors could reasonably be expected to make available in response : to a request for. emergency support. Personnel are listed by three categories: 1) ; operations and maintenance support,2) technical support, and 3) technical expens, ; Operations and maintenance personnel will provide direct operations or maintenance support and will normally come from a utility; technical support personnel will provide general engineering assistance. The technical experts will be nationally recognized i experts in their field who might be called upon by the Recovery Manager to provide , consultation in the analysis of a unique or complex problem. j The INPO Emergency Resources Manual provides the licensee with the option of either ! communicat'ng directly with the organization that is providing the support or ushg INPO ; as an agent to arrange for and coordinate the required support. The individuals to be l contacted in the various organizations along with their telephonc numbers are listed in j l' the manual, which is updated annually. ; in addition, a separate mutual assistance agreement exists among Cleveland Electric liluminatmg Company, Consumers Power Company, Toledo Edison Company, Indiana and , Michigan Electric, and Detroit Edison. Such requests for assistance can be in tne form j of personnel or equipment. This agreement is limited to for assistance in environmental i monitoring. ! [
h I CERP Plan { t Revision 1 ! Page C-3 ; I
, General Electric (GE) has a support program in place which utillros the full resources of !
L the Nuclear Energy Group in San Jose and the installation and Services Engineering ,
' personnel in the local districts to support utilities during emergency situations. This i program has provided assistance for boll!ng-water reactors (BWRs) during major i component fe!!ures and plant transients to minimize the impact of the event and to :
assure rapid return to operation. To assist BWR owners / operators more expeditiously . during emergency situations that could potentially endanger the health ano safety of the ! public or plant personnel, or that under certain circumstances could have a major impact i on continued plant operations, a special Emergency Support Program hss been ! established by GE's Nuclear Services Department. Fermi 2 has access to this GE l support program 24 hours a day. The support program is described in detall in , Appendix 1. r i in addition to that provided by government emergency plans, Detroit Edison has } arranged for emergency assistance from local and other private organizations through , signed letters of agreement with each of these organizations. The letters of agreement - containing concepts of operation, specific support commitments, authorities, responsibilities, and limits of these organizations are included in their entirety in ! Appendix 1. The following is a complete list of these organizations: } EMTS Ambulance Service I ~
- Frenchtown Fire Department }
j GE Company (BWR Emergency Support Program) - not a 1.etter of Agreement l l - INPO (Nuclear Power Plant Emergency Response Voluntary Assistance Agreement) ; Mercy-Memorial Hospital , Monroe County Community College l
- Mutual Assistance Agreement ,
- Cleveland Electric illuminating Company ,
- Consumers Power Company 3
- Detroit Edison Company
- Indiana and Michigan E'ectric Company 1
- Toledo Edison Company f
- Seawey Hospiisi (united Car., inc.) :
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y; - -- . . -- - [> I RERP Plan Revision 1 : Page D-1 [ i D. EMERGENCY CLASSIFICATION SYSTEM A standard emergency classification and action level scheme, the basis of which ! includes facility system and effluent parameters, has been established. State and local
- response organizations will rely on information provided by the facility licensee for the ;
classification of an emergency and related appropriate offsite protective actions y recommendations. l The emergency classifications are as follows: l o Unusual Event o Alert , i o Site Area Emergency j o General Emergency A general description and the purpose of each classification level 16 provid6d in Sections D-1 through D-4. The actions required by the licensee arid by the state and/or local offsite authorities are also given for each class. Emergency Action Levels are provided in Table D-1. Included in this table are the FSAR i postulated accidents that are considered to be of sufficient severity to establish an l emergency condition. Specific information on instruments, parameter values, and/or i equipment status for establishing the emergency class is provided in RERP Implementing ! Procedures. The initiating conditions are classified to provide consistency with ;
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established plant Technical Specifications and abnortrAl and emergency operating ' procedures. The classification is then further related to the four emergency classification levels. . r Table D-1 is a guide for classifying emergency conditions. In any situation not covered i in the Table, the Nuclear Shift Supervisor / Emergency Director must make a judgement in . determining the appropriate emergency classification in consultation with the Control , Room and/or other knowledgable individuals in the TSC. j D.1 Unusual Event {' Definition - Events are in progress or have occurred that Indicate a potential D.1.1 degradation of the level of safety of the plant. No releases of radioactive material
- requiring offsite response or monitoring are expected unless further degradation of i safety systems occurs.
I l D.1.2 Purpose - The purpose of the offsite notification is to assure the first step in any r l response later found to be necessary has been carried out, it is also to bring the operating staff to a state of readiness and to provide systematic handling of unusual events information and decision making. L - - - - _ _ _ _ _ _ _
[ RERP Plan j Revislan 1 . Pope D-2 ! D.1.3 Licensee Actions 1, Inform state and local offsite authorities of the nature of the unusual condition , within 15 minutes following classification and notify the Nuclear Regulatory Commission (NRC) as soon as possible but within 1 hour.
- 2. Augment onshift resources as needed
- 3. Assess and respond.
- 4. Escalate to a more severe class,if appropriate, or ,
- 5. Close out with verbal summary to ottsite authorities, followed by written summary ;
within 24 hours. l D.1.4 State end/or Local Offsite Authority Actions !
- 1. Provide fire, ambulance, or security assistance, if requested.
- 2. Escalate to a more severe clacs,if appropriate. ,
- 3. Stand by until verbal closeout. .
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.D2 Alert !
D 2.1 Definition - Events are in progress or have occurred that involve en actual or l potentially substantial degradation of the level of safety of the plant. Any releases of radioactive material are expected to be limited to small fractions of the Environmental Protection Agency (EPA) Protective Action Guideline (PAG) exposure levels. , D.2.2 Purpose - Purpose of Alert is to (1) assure that emergency personnel are readily , available to respond if tht> r,ituation becomes more serious or to perform confirmatory '3 i radiation monitoring if required, and (2) provide offsite authorities with current status information. l D.2.3 Licensee Actions
- 1. Inform state and local authorities of Alert status and reason for Alert within 15 l minutes following classification and to the NRC as soon as possible but within 1 ,
j hour.
- 2. Augment resources by activating the TSC and OSC.
- 3. Assess and respond.
- 4. Mobilize and dispatch onsite monitoring teams with associated communication equipment if required.
Provide periodic plant status updates to offsite authorities. 5. I l ( . . _ - _ . - - . _ _ _ . - _ . - _ _ . . - - . _ , - . . -_.
7 i 1 RERP Plan l Revision 1 j Page D-3 i i
- 6. Provide periodic meteorological assessments to offsite authorities and, if any ;
releases of radioactive material as specified for en Alert in Table D-1 are i occurring, provide dose estimates for those releases.
- 7. Escalate to a more severe class, if appropriate, or I
- 8. Close out emergency class by verbal summary to offsite authorities followed by l written summary within 8 hours of closecut or class de-escalation. l D.2.4 State end/or Local Offsite Authority Actions j
- 1. Provide fire, ambulance, or security assistance, if required.
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- 2. Augment resources and bring Emergency Operations Centers (EOCs) to standby. !
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- 3. Place key emergency personnel on standby status, including monitoring teams with l associated communication equipment. ]
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- 4. Provide confirmatory offsite radiation monitoring and Ingestion pathway dose '
projections if actual releases substantially exceed Technical Specifications limits. j i
- 5. Escalate to' a more severe class, if appropriate, j
- 6. Maintain Alert status until verbal closeout or de-escalation of emergency class.
D.3 Site Area Emergsney D.3.1 Definition - Events are in progress or have occurred that involve actual or likely major failures of plant functions needed for protection of the public. Any releases of radioactive material are not expected to exceed PAG exposure levels, except within the ; site boundary. D.3.2 Purpose - Purpose of the Site Area Emergency declaration is to (1) assure that l response centers are staffed,(2) assure that monitoring teams are dispatched, (3) . t provida consultation with offsite authorities, and (4) provide updates for the public l through offsite authorities. l D.3.3 Licensee Actions i 1, inform state and local offsite authorities of Site Area Emergency status and : reasons for emergency within 15 minutes following classification and to the NRC ! as soon as possible, but within 1 hour.
- 2. Augment resources by activating the TSC, the OSC, EOF and JPIC. ,
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- 3. Assess and respond.
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i RERP Plan i Revision 1 i Page D-4 l
- 4. Dispatch onsite and offsite monitoring teams with associated communication ,
equipment if required.
- 5. Provide regular plant status updates to offsite authorities and periodic press !
briefings with offsite authorities. 6 Make onsite senior technical and management staff available for consultation with ; NRC and state authorities on a periodic basis. !
- 7. Provide meteorological data and dose estimates to offsite authorities for :
potential / actual releases as appropriate, f
- 8. Provide release data and dose projections based on available plant condition information and foreseeable contingencies. I
- 9. Escalate to General Emergency classification, if appropriate, or !
- 10. Close out emergency classification or reduce by briefing offsite authorities {
followed by written summary within 8 hours of closeout or classification ! oe-escalation. I D.3.4 State and/or Lo' cal Offsite Authority Actions
- 1. Provide any assistance requested.
- 2. Provide public within 10-mile radius with periodic updates on emergency status. ;
l l 3. Augment resources by activating EOCs. ; i
- 4. Dispatch key emergency personnel, including monitoring teams with associated {
communications. , I l 5. Alert other emergency personnel to standby status (for example, those needed for ; evacuation) and dispatch personnel to assigned near-site locations, j
- 6. Provide offsite monitoring results to licensee and others, and jointly assess them. l l
- 7. Continuously assess information from licensee and offs!te monitoring teams I ;
regarding changes to protective actions already initiated for public and mobilitng evacuation resources. j I
- 8. Consider placing milk animals within 2-mile radius on stored feed and assess need to extend distance.
l g. Provide press briefings with licensee. !
- 10. Escalate to General Emergency classification, if appropriate.
- 11. Maintain Site Area Emergency status until closeout or de-escalate of emergency class.
l l l
p q l RERP Plan i Revision 1 ( Page D-5 { D.4 General Emergency D.4.1 Def6nition - Events are in progress or have occurred that involve actual or imminent substantial core degradation or molting with potential for loss of containment integrity. Release of rddioactive material can be reasonably expected to exceed PAO exposure ! levels offsite. 'l D.4.2 Purpose - Purposes of the General Emergency declaration are to (1) initiate f predetermined protective actions for the public, (2) provide continuous assessment of ! Information from licensee and offsite organization measurements,(3) initiate additional ! measures as indicated by actual or potential releases. (4) provide consultation with . offsite authorities, and (5) provide updates for the public through offsite authorities. D.4.3 Licensee Actions l
- 1. Inform state and offsite authorities of the General Emergency status, reason for emergency, and a minimum protective action recommendation within 15 minutes following classification and to the NRC as soon as possible, but within 1 hour. l
- 2. Augment resources by activating the TSC, OSC, EOF, and JPIC, if not already activated.
- 3. Assess and respond.
- 4. Dispatch onsite and offsite monitoring teams with associated communications,if required. ;
i l 5, Provide regular plant status updates tv offsite authorities and periodic press ' briefings with offsite authorities.
- 6. Make senior technical and management staff available onsite for consultation with 1 NRC and State authorities on a periodic basis.
- 7. Provide meteorological data and dose estimates to offsite authorities for l potential / actual releases. ;
- 8. Provide release data and dose projections based on available plant condition information and foreseeable contingencies. ,
- 9. Close out or de-escalate emergency class by briefing offsite authorities followed by written summary within 8 hours of closeout or de-escalation.
D.4.4 State and/or Local Offsite Authority Actions , i
- 1. Provide any assistance requested.
- 2. Activate public notification system promptly, inform public of emergency status, and provide updates periodically.
- 3. Order protective actions based on actual or potential plant conditions, licensee recommendations, and field surveys.
- 4. Augment resources by activating EOCs.
l
RERP Plan L Revision 1 Page D-6
- 5. Dispatch key emergency personnel including monitoring teams with associated communications.
- 6. Dispatch other emergency personnel to duty stationt. within 5-mile radius and alert all others to standby status.
- 7. Provide offsite monitoring results to licensee and others, and jointly assess them.
- 8. Continuously assess information from licensee and offsite monitoring teams regarding changes to protective actions already initiated for public and mobilizing evacuation resources.
- g. Consider placing milk animals within 10-mile radius on stored feed and assess need to extend distance.
- 10. Provide press briefings with licensee.
- 11. Maintain General Emergency status until closeout or de-escalation of emergency class.
l [
F? l i l RERP Plan Revision 1 Page D-7 Table D-1: CLAS$1FICATION OF EMERGENCIES Emergency ) Condition Indication (s) Classification H10H RADIOLOGICAL EFFLUENT Oaseous Effluent Annunciator EFFLUENT PROCESS Unusual Event release > Instantaneous RADIATION MONITOR TROUBLE: and limits allowed by ' Technical Specification Verification of High Alarm status 3.11.2.1 on Channel 05 on CT2B recorder and confirmed analysis by Radiation Protcction that gaseous release exceeds Technical Specification Umit j Liquid Effluent Annunciators CIRCULATING Unusual Event release > limits H2O SYSTEM DECANT LINE allowed by Technical RADIATION MONITOR TROUBLE: or Specification 3.11.1.1 CIRCULATING H2O SYSTEM DECANT LEE RADIATION MONITOR UPSCALE: AND Confirmed analysis by Rad Protection that liquid release exceeds 10 CFR 20, Appendix 3 Gaseous EMiuent Annunciator EFFLUENT PROCESS Alert ' release > 10 times RADIATION MONITOR TROUBLh and instantaneous limits allowed by Techrilcal Verification of high alarm status on Specification 3.11.2.1 Channel 05 of Standby Oss Treatment system units on CT2B recorder; and Confirmed analysis by Rad Protection i that gaseous release exceeds 10 times Technical Specification limit Liquid Effluent release Annunciator CIRCULATING H2O Alert
> 10 times limits SYSTEM DECANT LINE RADIATION - allowed by Technical MONITOR TROUBLE; or Specifications 3.11.1.1 CIRCULATING H2O SYSTEM DECANT 4.INE RADIATION MONITOR UPSCALE AND Confirmed analysis by Red Protection that liquid release exceeds 10 times 10 CFR 20. Appendix B
. _ t
- ,i o
RERP Plan l Revision 1 i Page D-8 l Table D-1: CLASSIFICATION OF EMERGENCIES (Continued) Emergency Condition Indication (s) Classification i HIGH RADIOLOGICAL EFFLUENT (Continued) } i Radiation monitor Annunciator EFFLUENT PROCESS Site Area readings indicate sa RADIATION MONITOR TROUBLE; Emergency i actual or potential and dose rate at the Site t Boundary of >50 mRom/hr Verification of Alert alarm i Whole Body or >250 status on Channel 07 for a mrem /hr Child Thryoid Standby Gas Treatment System i for 30 minutes using units on CT2B recorder, or actual meteorology Failure of Turbine and/or , (or worst case if Radweste Building (s) to actual is not known) isolate with verification of high alarm status on Channel ' 05 on CT2B recorder; and Dose rate calculations at the site boundary (0.57 mile); OR Annunciator DIV I/DIV 11 CONTAINMENT AREA RADIATION MONITOR TROUBlii; and - i Verification of alarm status (> 1000 R/hr) on CHRRM recorder; and i Dose rate calculations at the site boundary (0.57 mile); [ i OR j Field team measurements at site i boundary indicate 100 mrem /hr V
+ - - -. ,
7
- s ,
i RERP Plan : u Revision 1 Page D-g Table D-1: CLAS$1FICATION OF EMERGENCIES (Continued) Emergency Condition Indication (s) Classification HIGH MADIOLOGICAL EFFLUENT (Continued) Radiation monitor Annunciator EFFLUENT PROCESS General readings indicate an RADIATION MONITOR TROUBLE: Emergency actual or potential and dose rate at the Site Boundary of > 1 Rem /hr Verification of High Alarm on AXM Whole Body or> 5 Rem /hr Channel 03 or SPINO Channel Og on Child Thyrold using CT2B recorder; and actual motorology (or worst case if Dose rate calculations at the site l actual is not known) boundary (0.57 mile); OR Annunciator DIV I/DIV 11 ,
. CONTAINMENT AREA RADIATION MONITOR TROUBLE: and ,
Verification of alarm status (> 1000 R/hr) on CHRRM recorder; and Dose rate cf.lculations at the site boundary (0.57 mile); OR , Field team measurements at offsite boundary indicate 1 Rem /hr. FUEL HANDLING AND SPENT FUEL POOL ACCIDENTS Fuel Handling Accident Fuel Handling or handling of Alert which results in the incore materials in progress release of radio- and activity to ttee Reactor Alarms on operable Building Area Radiation Monitor Channels 15 and 17; and Annunciator DIV l/11 FUEL POOL VENT EXHAUST RADIATION MONITOR UPSCALE TRIP; and I Confirmation by Radiation Protection that I
. higher than normal background radiation )
levels exist in the Reactor Building.
a' 4<
, l RERP Plan o Revision 1 Page D-10 i
3 Table D-1: CLASSIFICATION OF EMERGENCIES (Continued) _ m e- Emergency
; Condition Indication (s) Classification l; i 11 . FUEL HANDLING AND SPENT FUEL POOL ACCIDENTS (Continued) i Major damage to spent Alarms on operable !
fuel in Reactor Area Radiation Monitor Site Area L Building Channels 15,17, and 18; and Emergency , 1 Annunciator DIV I/II FUEL
, POOL VENT EXHAUST R/.9tATION '
- i. MONITOR UPSCALE TRIP-1 OR Observation that fuel pool water level is below top of irradiated ,
J fuel; l l' ' . OR 1 Observation of spent fuel damage resulting in rupture of the fuel cladding; and i l l} Actual trdiation survey by Radiation ) l Protection Indicate > 1 Rem /hr on j lq Reactor Building fifth floor. j DEGRADED SAFETY SYSTEMS AND SAFETY LIMITS Any unplanned event HPCI is operating and Unusual Event- ) that results in ECCS HPCl Pump discharge inboard I ! discharge into the isolation valve open and l L reactor coolant system HPCI Pump discharge flow I l es a result of a valid indicated; or !A signal ; Core Spray Pump (s) running and ) l Core Spray injection check valves , open and Core Spray Pump discharge J flow to vessel; or l RHR Pump (s) running and i l' LPCI Injection valves open and LPCI flow to vessel and LPCI injection check valves open. l l e
($ '.,. l ( c, i q . RERP Plan i (! Revision 1 ; Page D-11 i M: Table D-1: CLASSIFICATION OF EMERGENCIES (Continued) l Emergency i Condition Indication (s) Classification 1 DEGRADED SAFETY SYSTEMS AND SAFETY LIMITS (Continued) : Failure of Safety SRV valve position indicates Unusual Event Relief Valve to reset open;and i A reactor shutdown is initiated l l
. in aLccordance Technical Specificattt,n . 5 A.2.1.
- 4. ,. ,
OR I 1
, Annunciator SAFETY RELIEF VALVE t OPEN and verification that .
tallpipe temperature ' * >265 0F; and l
' Failure of SRV tail pipe ,
' temperature to decrease; and i Supression Pool water coverage tempgrature increases to
> 105 F 3 I
's
.j k
( ,
}
i RERP Plan 1 Revision 1 Page D-12 Table D-1: CLASSIFICATION OF EMERGENCIES (Continued) Emergency Condition , Indication (s) Classification
' DEGRADED' SAFETY SYSTEMS AND SAFETY LIMITS (Continued)
Loss of any Engine'ered Emergency Core Cooling Unusual Event Sa'ety Features Systems inoperable and a System (b) function reactor shutdown is initiated requiring shutdown in by Technical Specifications; or accordance with Technica! Specifications Suppression pool inoperable and a reactor shutdown is initisted. by Technical Specifications; or One Main Steam isolation Valve , inoperable and inability to isolate the affected main steam line and a ; reactor shutdown is initiated by Technical Specifications; or Isolation Actuation Instrumentation channelb inoperable and a reactor shutdown is initiated by Technical Specifications; or , i l Emergency Equipment Cooling Water E System inoperable and a reactor ' j' shutdown is initiated by Technical ' Specifications; or I Emergency Equipment Service Water L System inoperable and a reactor l shutdown is initiated by Technical l Specifications; or RHR reservoirs inoperable 6nd a reactor shutdown is initiated l by Technical Specifications; or l, RHR Service Water System inoperable and a reactor shutdown is initiated by Technical Specifications; or Diesel generator cooling water i 1, subsystem associated with each diesel generator inoperable and a reactor shutdown is initiated by l Technical Specification 3.7.1.4 l l l
. . ~.
l RERP Plan 1 Revision 1 Page D-13 Toble D-1: CLASSIFICATION OF EMERGENCIES (Continued)
.i.
Emergency ; Classification Condition Indication (s)
' DEGRADED SAFETY SYSTEMS and SAFETY LIMITS (Continued)
Safety limits exceeded Thermal power, low pressure, Unusual Event requiring shutdown or low flow limits exceeded and according to Technical a reactor shutdown is initiated by Specifications Technical Specification 2.1.1; or Thermal power, high pressure, and
~high flow limits exceeded (MCPR < 1.06) ,
and a reactor shutdown is initiated by ; Technical Specification 2.1.2; or Reactor Coolant System pressure ! measured in the steam dome, >1325 i psig, and a reactor shutdown is initiated by Technical Specification 2.1.3. Abnormal Reactor' dome' Reactor pressure ,> 1040 psig, _ Unusual Event pressure outside of as indicated by Reactor Vessel Steam Technical Specification Dome Pressure and pressure not l operational limits reduced to <1040 psig in 15 minutes ( l r Reactor cooldown Reactor cooldown rate Unusual Event rate exceeding exceeding 1000 F in any 1-hour , i Technical period and temperature / pressure Specifications not restored within 30 minutes l Complete loss of any RHR - The Limiting Condition Alert J for Operation and tne action l functions essential to achieve plant cold statements of Technical Specification , , shutdown 3.4.9.2 are not met within the l specified time interval. Complete loss of any RHR - The Limiting Condition Site Area functions essential for Operation and the action Emergency to achieve plant hot statements of Technical Specification shutdown 3.4.9.1 are not met within the specified time Intental. Small or large LOCA Reactor Water Level < Level 1 General with failure of low as Indicated by Reactor Water Emergency pressure ECCS to Level indicators; and perform Failure of all low pressure ECCS to inject water into the reactor vessel
fi, . h (, ,t REftP Plan Revision 1 Page D-14 Table D-1: CLASSIFICATION OF EMERGENCIES (Continued) Emergency ! Condition , Indication (s) Classification REACTOR CONTROL' SYSTEM FAILURES Reactivity Control Any condition that exceeds Unusual Event limits exceeded Technical Specifications in . j requiring shutdown Section 3/4.1 and a reactor according to shutdown is initiated in Technical Speci- accordance with action statements fications , Failure of Reactor Valid initiating SCRAM signal Alert Protection System to as indicated by Annunciators TRIP initiate and complete a ACTUATORS A1 A2 TRIPPED and Scram and/or failure of TRIP ACTUATORS B1/B2 TRIPPED, or a manual Scram to bring the reactor subcritical MANUAL TRIP ACTUATOR
. A SYSTEM TRIPPED, and MANUAL ;
TRIP ACTUATOR B SYSTEM TRIPPED l AND j ! All rods are not fully inserted, as indicated by control rod position Indicators; i AND Reactor is critical, as indicated l by Neutron Flux monitors l Transient requiring Fallure to bring the teactor Site Area L operation of shutdown subcritical with the control Emergency l~ systems with failure rods, as shown by IRM/APRM l to Scram and no core indicators; and damage immediately l evident Failure of the Standby Liquid
- Control System to bring the reactor subcritical; and l
No core damage as indicted by i CHRRM, main steam line radiation ! monitors, SJAE radiation monitors, or high reactor coolant activity 1
p , H
! I RERP Plan by .
Revision 1 l' Page D-15 Table D-1: CLAS$1FICATION OF EMERGENCIES (Continued) i. Emergency Condition L Indication (s) Classification LOSS OF ELECTRICAL POWER p Loss of offsite power Operating - AC electrical Unusual Event or loss of onsite AC power sources inoperable and a power capability reactor shutdown is initiated by Technical Specification 3.8.1.1; or Shutdown - Loss of DIV l and OlV li offsite power sources or inability to start and load EDGs 11,12,13, and 14 l 1' Loss of vital DC DC electrical power sources Unusual Event electrical power inoperable and a reactor shutdown sources requiring is initiated by Technical L shutdown in accord- Specification 3.8.2.1 ance with Technical - l Specifications ' { 1 Loss of primary Primary containment penetra- Unusual Event
]
containment penetration tion overcurrent protective .i l-conductor overcurrent devices inoperable and a reactor protective devices shutdown is initiated by Technical l requiring shutdown in Specification 3.8.4.2 l accordance with Technical - Specifications I Loss of power distribu- Power distribution system Unusual Event tion systems requiring divisions not energized and L l shutdown according to a reactor shutdown is initiated l Technical Specifica- by Technical Specificttion 3.8.3.1 l tions j i l Loss of offsite power Loss of offsite power supply- Alert I and all onsite AC power ing Div i and Div II; and for less than 15 minutes Inability to start and load EDGs 11,12,13 and 14 Loss of all onsite Loss of DIV I and DIV 11 Alert vital DC power for 130V-DC Busses: and less than 15 minutes Local verification of loss of charger voltage and battery voltage on Div i and Div 11 batteries l 1
- - , - _ - . - - - _ . _- -- _ _ _ _ _ _ - _ _ _ _ _ _ _ - - _ _ _ _l
t t ll RERP Plan
'- . 0 '
Revision 1 ! Page D-16 J Table D-1: CLASSIFICATION OF EMERGENCIES (Continued) 4 1 Emergency Condition - Indication (s) Classification LOSS OF ELECTRICAL POWER (Continued) i i Loss of offsite power Loss of offsite power supply- Site Area and all onsite AC power . Ing Div i and Div 11; and Emergency for more than 15 minutes inability to start and load EDGs 11,12,13 and 14 Loss of all onsite Loss of Div i and Div 11 Site Area vital DC power for 130V-DC Busses; and Emergency j" more than 15 minutes Local verification of loss of charger voltage and battery l voltage on Div i and Div 11 batteries LOSS OF ANNUNCIATORS, ALARMS, OR INDICATORS Significant loss of Loss of all communications Unusual Event com munications capability offsite except radio capability Most or all Observation that most or all Alert annunciator alarms annunciator alarms are Inoperable [ inoperable for greater i than 15 minutes (operational t condition 1,2, or 3) Most or all Most or all annunciator Site Area H annunciator alarms alarms inoperable; and Emergency inoperable, plant transient initiated or in Plant transient is in progress or progress (operational is initiated condition 1,2, or 3) l I 1 j 1 l l
l l RERP Plan Revision 1 ;
- Page D-17 i ,3 Table D-1: CLASSIFICATION OF EMERGENCIES (Continued) l Emergency l'
s ' Condition ' Indication (s) , Classification NATURAL DISASTER, ACCIDENT, OR FIRE ; Natural Phenomenon Earthquake < 0.08g (OBE) Unusual Event (; being experienced or > 1: projected beyond normal Control Room Informed by values ' Site personnel who have ; experienced tremor, and 3 Indication of earthquake ! j' magnitude seismic <0.08g on L recorder i Flood Werning Unusual Event ] Control Room informed by site l personnel who have made a visual sighting of high water approaching : top of shore barrier I Tornado Onsite Unusual Event l
\
Control Room infcrmed by site ; personnel who have made a , visual sighting of a tornado j crossing the site boundary l l Suttained Winds Unusual Event l L l l Average wind velocity > 75 mph ) for > 15 minutes on 60-meter or 10-meter wind speed indicators ' on the Meteorological Tower onsite l' l 5 l o i l
RERP Plan . l'i i Revision 1 ! Page D '
.i l
m 3 Table D-1: CLAS$1FICATION OF EMEROENCIES (Continued) , 4 Emergency.
' Condition Indication (s) Classification t
NATURAL DISASTERS, ACCIDENT, OR FIRE (Continued) Severs Natural Earthquake > Operating Basis Alert ; Phenomenon being Earthquake (OBE) level of 0.08g ; j
, experienced or ;
projected i Indication of earthquake ; magnitude >0.00g on ' seismic recorder ') Flood Approaching Design Alert Level of 586.9 feet Control Room informed by i site personnel who have made j
. a visual sighting of high :l water levels intermittently .I breaking over shore barrier l
Tornado Striking Facillity. Alert Tornado observed striking .j Reactor Building, RHR Complex, Turbine Building, Redwaste Building, or a Auxilla,ry Building Storm Winds Approaching Alert ~! Design Basis Level of 90 mph Average wind velocity > 85 , l- mph for > 15 minutes on ! l 60-meter or 10-meter wind i speed indicators on the ! Meteorological Tower onsite l
't
{
4 , 1 1 i I RERP Plan Revision 1 Page D-19 l Table D-1: CLASSIFICATION OF EMERGENCIES (Continued) Emergency Condition Indication (s) Classification [ NATURAL DISASTERS, ACCIDENTS, OR FIRE (Continued) Severe Natural Earthquake > Safe Shutdown Site Area ; Phenomenon being Earthquake (SSE) Level of Emergency
- experienced or 0.15g projected with plant - ,
not in cold shutdown ~ Indication of earthquake ? magnitude >.159 seismic on recorder r Flood > Design Level Site Area ' Emergency Control Room informed by plant personnel who have made a visual sighting of flood waters continuously overflowing the shore barrier Tornado Striking / Damaging Site Area
- Facility Emergency ,
t Tornado striking Reactor Building, Auxillary Building, Turbine Building, Redwaste Building, RHR Complex, affecting operation of Reactor Safety . Systems Storm Winds > Design Basis Site Area Level Emergency Sustained wind velocity > 90 mph for > 15 minutes on 60-meter or 10-meter wind speed indicators on the Meteorological Tower onsite 4 s .. - - , - - - _ . . . - , . . - . . ,- - - - , . , . , ,r- , .-,.- r
"' RERP Plan a'
i. Revision 1 Page D-20 4 Table D-1: CLAS$1FICATION OF EMERGENCIES (Continued) Emergency Condition Indication (s) Classification '
'l NATURAL DISASTERS, ACCIDENTS, OR FIRE (Continued) l Other hazards being Aircraft crash onsite or un- Unusual Event experienced or usual aircraft activity over projected facility Control Room informed by ;
site personnel who have made 3 a visual sighting Explosion near or onsite Unusual Event Control Room informed by site personnel who have confirmed the,6cebrrence Toxic or flammable gas re- Unusual Event lease from its container to ! atmosphere near or onsite Control Room informed by site l l personnel who have confirmed L the release onsite or within 500 feet of the perimeter fence; and The quantity released is sufficient i to affect the cafety of personnel j i outside a 50 foot radius from the i source of the release. ( ( ' 1 I 1 Turbine rotating component Unusual Event ; failure causing a reactor scram Control Room instrumentation indicates turbine rotating component failure resulting in q a reactor scram l i Train derailment near or Unusual Event onsite ! Control Room informed by site l personnel who have confirmed a I tra!n detallment onsite or within 500 feet of the perimeter fence
w RERP Plan i Revision 1 Page D-21 Table D-1: CLAS$lFICATION OF EMERGENCIES (Continued)- Emergency i' Condition Indication (s) Classification , s J NATURAL DISASTERS, ACCIDENTS, OR FIRES (Continued) Other hazards being Aircraft crash or missile Alert experienced or impact into Reactor Building, projected Auxiliary Building, Radweste Building, 1 RHR Complex, Emergency Operations l l;
- Facility or the Technical Support 1 Center 1
Control Room informed by site personnel I l who have made a visual sighting Onsite explosion affecting Alert plant operations Control Room informed by site personnel who have confirmed the occurrence 7 and instrument readings on plant ; systems indicate equipment problems Uncontrolled flammable or Alert toxic gas release at life-threatening levels into the Reactor Building, Turbine Building, Auxiliary Building, RHR Complex, Emergency Operations Facility or the Technical Support Center Annunciators OlV I NORMAL AIR INTAKE CHLORINE DETECTED and/or DIV 11 NORMAL AIR INTAKE CHLORINE DETECTED; or - Annunciators CIRCULATING WATER PUMP-HOUSE CHLORINE SYSTEM TROUBLE or FERMI 1/11 OSW CHLORINE SYSTEM LEAK; or Evacuation of Control Room with control established at Remote Shutdown Panels within 15 minutes. AND Control Room informed by plant personnel who have confirmed life-threatening levels;
.e -
RERP Plan I Revision 1 j Page D-22 Table D-1: CLASSIFICATION OF EMERGENCIES (Continued) Emergency
' Condition Indication (s) Classification NATURAL DISASTERS, ACCIDENTS, OR FIRES (Continued)
Turbine failure causing Alert casing penetration r Excessive noise in vicinity of turbine, turbine vibration, turbine trip, or Turbine Building area radiation monitors high, and/or visual observation of i turbine failure Other hazards being Damage from aircraft crash, Site Area experienced or missile impact, or explosion Emergency. projected with affecting safety systems or plant not in functions cold shutdown Control room informed by site personnel of any aircraft / missile impact or explosion affecting safety system equipment; and instrument readings on vital systems indicate equipment status; or Inspection of safety system equipment verifies damage to equipment + t-1 l Uncontrolled toxic gas Site Area release at life-threatening Emergency levels into areas containing nuclear safety systems or engineered safeqr features l Control Room informed by site personnel who have confirmed life-threatening levels in areas containing nuclear safety systems or engineered safety features; or Annunciator DIV i NORMAL AIR INTAKE CHLORINE DETECTED and/or DIV ll NORMAL AIR INTAKE CHLORINE DETECTED and Annunciator CIRCULATING WATER PUMP-HOUSE CHLORINE SYSTEM TROUBLE or FERMI 1/11 GSW l CHLORINE SYSTEM LEAK and Control Room l HVAC System Chlorine mode inoperable
N '.y
.t ,
RERP Plan Revision 1 Page D-23 l Table D-1: CLASSIFICATION OF EMERGENCIES (Continued) Emergency Condition Indication (s)' Classification
, NATURAL DISASTERS, ACCIDENTS, OR FIRES (Continued)
Uncontrolled plant Working fire within the plant fire Unusual Event not brought under control by
- i. automatic fire suppression systems or plant personnel within 10 lc minutes; or Any fire within the plant or 3 outbuildings containing plant l~ equipment that requires offsite support
- j. Fire potentially Working fire within the plant L affecting safety with potential to affect nuclear
. systems .
safety systems or engineered safety features; OR 1 i l Plant fire requiring the evacuation of Control Room; and Control of shutdown systems established from Remote Control l Shutdown Panels within 15 minutes. . l Fire affecting Working fire within the plant Site Area j functions of safety affecting the functions of Emerg6ncy : systems nuclear safety systems or ! i engineered safety features; I l OR Plant fire requiring the evacuation of Control Room; and Control of shutdown systems not t established from Remote Shutdown ) Panels within 15 minutes 1 l' i
i{ ^ f , 0.1 , q I RERP Plan .i Revision 1 ) Page D-24 1 Table D-1: CLASSIFICATION OF EMERGENCIES (Continued) 1 a Emergency l .Co,ndition_ Indication (s) Classification LOSS OF FISSION PRODUCT BARRIERS I Loss of one High off gas activity at SJAE Unusual Fission Product (> 500,000 uCi/Sec) and Event Berrier verified by Off Gas PRMS - l.. recorder reading; or i i Fuel Clad ; Failure An increase in off gas activity L at the SJAE (100,00 uCl/Sec in t 1 30 minutes) and verified by OFF Gas PRMS recorder reading; or l Reactor water sample analysis results indicate high reactor i , coolant activity of > 4.0 uCi/ gram l-dose equivalent 1-131; or 100/E uCi/ gram specific activity - 1: Severe Fuel High Main Steam Line radia- Alert Clad tion > 3.0 times fall power background Failure and verified on the Main Steam Line PRMS recorder; or b Very high off gas activity at SJAE, (> 5 Cl/Sec) and verified by Off p Gas PRMS recorder reading; or Reactor water sample analysis results indicate very high reactor ; coolant activity of .>_300 uCl/ gram dose equivalent 1-131; or l' Fuel clad gap release > 20% as verified by reading on Containment p, High Range Radiation Monitor recorder of >7.5E04 Rad /hr
1 i t., RERP Plan .1 Revision 1' Page D , 3 i,'- Table D-1: CLASSIFICATION OF EMERGENCIES (Continued)
- t. Emergency
- Condition Indication (s) Classification - l LOSS OF FISSION PRODUCT BARRIERS (Continued) ,
Loss of one Degraded core as indicated Site Area Fission Product by any of the fellowing: Emergency Barrier (Continued) Main Steam Line radiation >-3.0 Degraded core with times full power background and ; possible loss of verified on the Main Steam Line , Reactor Vessel PRMS recorder or ' i' water level (cool-able geometry) Very high off gas activity at SJAE (> 5 Cl/Sec) verified by Off Gas PRMS ' recorder reading > 14.5E03 mR/hr; or Reactor water sample analysis results indicate very high reactor l coolant activity of > 300 uCi/ gram dose equivalent 1-131; or l. i > 20% fuel clad gap release as verified by reading on Containment High Range Radiation Monitor i recorders; and Possible loss of coolable geometry ' L as indicated by reactor water level
- l. < TAF, as shown by Reactor Water level indiceters.
Reactor Water Reactor water level < TAF Unusual Event Level Safety Limit in operational condition l exceeded according 3, 4, or 5 l- to Technical Specification 2.1.4 , L 1 1 1 1 i. l l l
, . . - . _ _ - _ . _ . . ., . . . _ _ _ . . . . . . . . _ _ . . . _ . . - _ _ _ ~. _ _ _ _ . _ _
t j)i.
'l RERP Plon 'l '
Revision 1 Page D-26 Table D-1: CLASSIFICATION OF EMERGENCIES (Continued) Emergency j Condition , Indication (s) Classification LOSS OF FISSION PRODUCT BARRIER (Continued) Loss of one Pressure boundary leakage Unusual Event Fission Product ' exceeding the specified limits
- Barrier (Continued) and a reactor shutdown is initiated by Technical Reactor Coolant Specification 3.4.3.2 ;
System leak rates
! greater than those specified in Technical
, Specification 3.4.3.2 Reactor Coolant Annunciator REACTOR BUILDING Alert l Leak Rate greater DRYWELL FLOOR DRAIN SUMP LEVEL
'than 50 gpm HIGH and both Drywell Floor Drain-Sump Pumps running; or Annunciator DRYWELL EQUIP DRAIN LKGE HIGH and both Drywell !
j Equipment Drain Pumps running or Drywell floor drain or drywell I equipment drain sumps indicate i > 50 gpm increase in level , l l. , Steam Line Break Verification that Drywell Alert I inside Primary average temperature > 1450F 1 Containment and increasing; and ) l Verification that Drywell pressure j is > 1,68 psig and increasing l l Steam Line Break Verification that Steam Alert 0 outside Primary Tunnel temperature is > 200 F l and increasing; or 1 Containment with ! MSIV isolation and l continued steam Area Radiation Monitor Recorder leak Channels in the Turbine Building show rapid increase in radiation level l -
[L F , E RERP Plan l b , Revision 1 L Page D-27 ! l , I I' Table D-1: CLASStrlCATION OF EMERGENCIES (Continued) l Emergency
- Condition - Indication (s) Classification ,
LOSS OF FISSION PRODUCT BARRIERS (Continued) i Loss of one Reactor Water Level low at Site Area Fiesion Product < TAF, as shown by Reactor Emergency < I Barrier (Continued) Water Level indicators; and Reactor Coolant Containment pressure > 1.68 psig
. System Leakage and increasing, as shown by I (LOCA) greater recorders; and than makeup pump capacity Primary Containment average temperature > 145 0F and increasing, as thown by recorders
- p Loss of Primary Any one of the following for Unusual Event Containment Primary Containment:
Integrity requiring , ! plant shutdown in Primary containment air lock accordance with inoperable and a reactor shutdown L Technical is initiated by Technical
. Specifications Specification 3.6.1.3; or 1
Inability to restore structural , integrity of the primary containment and a reactor shutdown is in!tlated l in accordance with Technical Specification 3.6.1.5; or , Any primary Containment Isolation Valve or Reactor Line Excess Flow Check Valve inoperable and a resctor shutdown is initiated by Technical
, Specification 3.6.3; or One Suppression Chamber Drywell Vacuum Breaker open and a reactor l;
shutdown is initiated by Technical l' Specification 3.6.4.1; or L , L One Reactor Building Suppression Chamber Vacuum Breaker open and l- a reactor shutdown is initiated i- 1 l' by Technical Specification 3.6.4.2; or Primary containment integrity lost I and a reactor shutdown is initiated by Technical Specification 3.6.1.1 l
s RERP Plan
> Revision 1 .
Page D-28 Table D-1: CLAS$1FICATION OF EMERGENCIES (Continued) Emergency Condition Indication (s) Classification , LOSS OF FISSION PRODUCT SARRIER (Continued) . Loss of one Any one of the following for Unusual Event Fission Product Secondary Containment:
. Barrier (Continued)
Secondary Containment pressure 1 Loss of Secondary > - 0.125 inches of water Containment and a reactor shutdown is requiring shutdown initiated by Technical Specification in accordance with 3.6.5.1; or Technical Specifications Any Secondary Containment Automatic isolation Damper inoperable and a reactor shutdown is initiated by , Technical Specification 3.6.5.2; or Divisions I and 11 Standby Gas Treatment Systems anoperable and a i reactor shutdown is initiated in accordance with Technical Specification 3.6.5.3 L l Loss of two Main Steam Line Site Area ' Fission Product Emergency Barriers One or more of the following main steam line isolation set . Steam Line Break points are exceeded: outside Primary Containment without o High steam line flow isolation > 137.9% of rated o Low main steam pressure
< 756 psig with mode switch L in run o High sgam tunne! temperature
> 200 F o High Tgrbine Building temperature;
> 200 F AND One or more main steam lines do not isolate;
L'
' u .; . RERP Plan l ltevision 1 I Page D-2g j i
Table D-1: CLASSIFICATION OF, EMFRGENCIES (Continued) ; Emergency i Condition - Indication (s) Classification < ( LOSS OF FISSION PRODUCT SARRIER (Continued) ~; Loss of two - Fission Product i Berriers (Continued) i i Steam Line Break HPCI Steam Line Site Area outside Primary Emergency Containment without HPCI does not isolate when one or isolation more of the following setpoints are (Continued) exceeded o High Steam line flow .j
- j>_536,625 lbm/hr o Steam supply low pressure
< 100 psig
~
o HPCI Equipment roop high temperature > 150 F ; l o High HPCI exhaust diaphragm l pressure > 10 psig AND Annunciator REACTOR AND AUXILIARY !
, BUILDING SUB BASEMENT AND BASEMENT HIGH RADIATION and Area Radiation .
Monitor Recorders indicate high;
!I ..
4.. ;. b ( I
RERP Plan !: Revision 1 Page D-30 Table D-1: CLASSIFICATION OF EMERGENCIES (Continued) ' it Emergency L' Condition Indication (s) Classification LOSS OF FISSION PRODUCT BARRIER (Continued) RCIC Steam Line Site Area ~ Emergency RCIC does not isolate when one or more of the following setpoints are exceeded: o High Steam line flow > g0,875 lbm/hr o Steam supply low pressure < 62 psig .; o RCIC equipment, room high pressure > 150 F o High RCIC exhaust diaphragm . pressure > 10 psig AND Annunciator REACTOR AND AUXILIARY i BUILDING SUB BASEMENT AND BASEMENT I HIGH RADIATION and Area Radiation i Monitor Recorders indicate high. L L Loss of two Fission Product Barriers (Continued) i Loss of Fuel clad failure; and S!te Area i
- 1. Fuel Cladding Emergency i
- 2. Reactor Coolant Loss of reactor Coolant Boundary as l Boundary indicated by any of the following: l I
Reactor Coolant System Leak Rates i greater than those specified in Technical Specification 3A.3.2: or Steam Line Break inside Frimary Containment Loss of Fuel clad failure and Site Aree l
- 1. Fuel Cladding .
Emergency l
- 2. Primary Loss of Primary Containment integrity Containment in accordance with Technical Specifications l
l l l M . - - _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
d , i RERP Plan i Revision 1 Page D-31 l Table D-1: CLASSIFICATION OF EMERGENCIES (Continued) Emergency u Condition Indication (s) Classification
, LOSS OF FISSION PRODUCT BARRIER (Continued)
Loss of Loss of Reactor Coolant Site Area
- 1. Reactor Coolant Boundary indicated by any of Emergency -
Boundary the follow!ng: ,
- 2. Primary Containment Reactor Coolant System Leak Rates greater than those specified in Technical Specifications 3.4.3.2; or Steam Line Break inside Primary >
l Containment; , l and Loss of Primary Containment as indicated by loss of Primery Containment integrity in
. accordance with Technical Specifications; ,
OR Steam Line Break outside Primary Containment without isolation and continued steam leakage; or l Reactor Coolant System Instrument Line Break without isolation; or Reactor Water Cleanup System leakage, and l failure of both RWCU isolation valves to close i' l
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RERP Plan .i l Revision 1 1 Page D-32 , C Table D-1: CLASSIFICATION OF EMERGENCIES (Continued)' ! Emergency i Condition indication (s) ~ Classification i
~ LOSS OF FISSION PRODUCT BARRIERS (Continued) l '
Loss of two . Fuel clad failure General Fission Product Emergency ,
' Barriers with AND
. Potential Loss of the , ;
third Barrier Loss of reactor Coolant Boundary ' L'" l as indicated by any of , the following: , Reactor Coolart System Leak
- i. .
Rates greater than those specified Loss of I
- 1. Fuel Clad in Technical Specification
! , 2. Reactor Coolant 3.4.3.2; or , Boundary St6am Line Break inside Primary l Contamment; . I r' Potential loss of L
- 3. ' Primary - AND Containment 3 Potential loss of Primary .;
Containment Integrity as indicated ! by any of the following: ' Drywell pressure > 56.5 psig on : Drywell pressure indicator; or . Drywell temperature > 3400F; or Annunciators DIV l/DIV ll H 2/02 l .. VERY HI CHECK COMBUSTIBILITY and confirmation that containment atmosphere H2 > 4% and O2 > 4% , Loss of Fuel clad failure Gen rTa'i l' 1. - Fuel Clad , Ems?gency ~! ( 2. Primary AND i l Containment Loss of Primary Containment ' Potential loss of integrity in accordance with
- 3. Reactor Coolant Technical Specifications Boundary AND Potential loss of Reactor Coolant >
Boundary as Indicated by Reactor Coolant System pressure measured in the Reactor Vessel Steam Dome s
> 1325 psig
y .) t-
- gr RERP Plan Revision 1 ;
Page D-33 j ' Table D-1: CLASSIFICATION OF EMERGENCIES (Continued)
. Emergency Condition Indication (s) Classification LOSS OF FISSION PRODUCT BARRIERS (Continued)
Loss of two Loss of Reactor Coolant General
<. Fission Product Boundary indicated by any of Emergency 1 Barriers with - the following:
- Potential Loss of the third Berrier Reactor Coolant System Leak (Continued) Rates greater than those specified in Technical Specification 1 Loss of 3.4.3.2; or i
- 1. Reactor Coolant Steam Line Break inside Primary i: Boundary Containment;
- 2. Primary q Containment AND l I
Loss of Primary Containment as l i Potential loss of , indicated by loss of Containment j L 3. ' Fuel Clad Integrity in accordance with l j- . Technical Specifications; or Loss of Reactor Coolant Boundary i and Primary Containment Integrity I as indicated by Steam Line Break l l outside Primary Containment without ) isolation; AND ; Potential loss of Fuel Clad i l- indicated by possible loss of coolable geometry as indicated L ' i l by Reactor water level < TAF Loss of three Any combination of conditions General Fission Product that Indicate the integrity Emergency Barriers of all three fission product ! barriers are lost; Loss of Example:
- 1. Fuel Clad Fuel clad failure and an
- 2. Reactor Coolant unisolated leak outside Boundary Primary Containment from l 3. Primary the Reactor Coolant Boundary i Containment l
1 l l
t f ,' RERP Plan Revision 1 Page D-34 Table 0-1: CLASSIFICATION OF EMERGENCIES (Continued) Emergency Condition Indication (s) Classification SECURITY COMPROMISE 4
' 6ecurity Threat, Report by a senior member of Unusual Event Attempted Entry, or the Security Force of a security Sabotage' contingency event Ongoing Security Report by a senior member of Alert Compromise the Security Force that adversaries are commandeering an area of the plant, but not controlling shutdown capability, or any areas containing nuclear safety systems or engineered safety features Imminent loss of Physical attack on the plant Site Area physical control of -
Involving imminent occupancy Emergency the plant of the Control Room, Remote ! Shutdown Panels, or other areas containing nuclear safety systems or engineered safety features f I Loss of physical Physical attack on the plant General control of the plant that has resulted in unautno- Emergency rized personnel occupying the Control Room, Remote Shutdown Panels, or any other areas containing nuclear safety systems or engineered safety features 1- HIGH RADIATION OR CONTAMINATION LEVELS WITHIN FACILITY Significant unexpected Any area radiation monitor A'ert increase in radiation channels offscale high, and i or airborne verified by survey or sampling activity levels analysis by nadiation Protection , personnel; or 1 An increase in airborne radioactivity levels in occupied plant areas of 1000 times normal levels, as t indicated by continuous air monitors, l- or sampling and analysis by Radiation Protection personnel 1 L c
. - - . _~ .
RERP Plan Revision 1 ; Page D-35 1 Table D-1: CLASSIFICATION OF EMERGENCIES (Continued) ] Emergency l- ' Condition Indication (s) Classification HIGH RADIATION OR CONTAMINATION LEVELS WITHIN FACILITY (Continued) Evacuation of Control . Any evacuation of the Control Alert Room Room due to high radiation with control of shutdown systems established within 15 minutes at ' Remote Shutdown Panels
?
Dose rates onsite- Any area radiation monitor Site Area I' > 1 Rem /hr Whole Body channels or airborne monitor Emergency ' !,_ or > 5 Rem /hr Thyroid alarms offscale high; and l- in normally occupied areas of the plant Radiation surveys by Radiation
. Protection personnel indicate a dose rate of >1 Rem /hr Whole Body or
~
> 5 Rem /hr Thyroid in normally
- occupied areas of the plant Evacuation of Control Any evacuation of the Control Site Area
! Room and control not Room due to high radiation Emergency established locally with control of shutdown systems within 15 minutes not established within 15 minutes at Remote Shutdown Panels. PERSONNEL INJURY Transportation of Information from Radiation Unusual Event contaminated injured Protection survey indicates individual (s) from the detectable levels of external i facility to an offsite contamination on skin or hair i medical facility of injured person above background on a frisker with an efficiency of 10%; and injury requiring offsite medical treatment prior to decontamination;
- . and Transportation of contaminated injured individual (s) from the facility to an offsite medical facility.
l
( s e RERP Plan Revision 1 Page E-1 ' i E. NOTIFICATION METHODS AND PROCEDURES l [ - This Plan Section describes the methods for notification of Emergency Response - l Organizations and the means used to notify and provide instruction to members of the I public within the plume exposure pathway 10-mile Emergency Planning Zone (EPZ). 7 l E.1 Notification of Onsite Emergency Response Organizations ]
'E.1.1 Initial notification of Onsite Emergency Response Organizations is made by the Control Room on the plant Hi Com system. Personnel with emergency essignments are ordered to report to their assigned emergency facility. Notification of other plant personnel who l
are offsite is performed by the On-Call Plant Supervisor and Detroit Division Dispatch and Report Center. , L E.2 - Notification of Offsite Emergency Response Organizations E.2.1 The basis for notification of all Offsite Emergency Response Organizations is consistent . with the emergency classification action level scheme delineated in Section D. - Procedures are established for the notification of appilcable State and local response organizations. These procedures include provisions for message verification by plant emergency response personnel. The notification message to the eppropriate state and local Emergency Response ' Organizations has been standardized and was developed in cooperation with the state and other utilities in Michigan. It contains infor:Y.ation concerning the emergency ; classification, the radioactive releases, potentially affected populations, and protective action recommendations (as necessary). Provisions for initial and follow-up messages contalri the following information (if known and if appropriate): Emergency classification
- Location of incident and name and telephone number (or communications channel identification) of caller j Date and time of incident Type of actual or projected release (alrborne, waterborne, surface spill) and estimated duration time
- Estimate of quantity of radioactive material potentially released or being released and the points and height of releases
- Chemical and physical form of released material, including estimates of the relative quantitles and concentration of noble gases, lodines, and particulates, as applicable
-- e-r--w,
I RERP Plan Revision 1 . Page E-2 1, i - Meteorological conditions at en appropriate elevation, including wind speed, l' direction (to and from), stability class, and precipitation l i
- Actual or projected dose rates at site boundary and projected integrated dose at site boundary including sector (s) affected '
- Projected dose rates and integrated dose at 2,5, and 10 miles downwind including sortor(s) affected ]
- Estimate of any suriace radioactive containination inplant, onsite, or offsite I
- t.lconsee emergency resoonse actions underway {
1 Protective action recommendations Requests made for onsite support from offsite organizations
~
- Prognosis for escalation or termination of event based on plant information s
i E.3 - Notif6 cation of the General Public Both physical and administrative means have been established for notifying and instructing the population within the plume exposure pathway (10-mile EPZ). ; Notification will be made by a primary system of 31 and a supplementary system of 28 ' fixed electronic strens situated throughout the 10-mile EPZ (Table E-1 and Figure E-1). The siren signals alert the population to tune to a local radio or television station j affiliated with the Emergency Broadcast System (EBS) (Appendix 2). The state is } responsible for activating the EBS, County officials are responsible for activating the ! stren notification system. Activation of this system is based on the emergency [ classification declared by the licensee. I F The licenses will provide offsite suthorities with supporting information for their ! messages to the public. Such messages, consistent with the emergency classification ' scheme and with the American industrial Hyglene Association Respiratory Protection Devices Manual, will provide the public with instructions regarding protective actions to be taken by occupants of affected areas. Initial information to the public will state, at a minimum, that an emerge .ay has occurred at Fermi 2 and further instructions will be : provided. Detroit Edison c'1 continue to coordinate planning with the responsible . offsite authorities to assu e that administrative means exist to promptly notify the public during rapidly developing ' norgency situations. i A small (224 acres) section of the 10-mile EPZ includes Canada and is sparsely populated. The Province of Ontario (Canada) is notified only once at each initial , classification of an Unusual Event, Alert, Site Area Emergency, or General Emergency. , The Michigan State Police will provide all subsequent communications and information. m __ .
I s i ( RERP Plan l Revision 1 l Page E-3
,. TABLE E-1: PROMPT NOTINCATION SYSTEM SIREN LOCAT60NS i
MON 8 TOE COUNTY l Frenchtown Township ( f r
- 1. Avenue B and Lakeview in Stoney Point Beach ;
t 2. Northeast Corner Post Road and Dixie Highway ' E 3. North Dixie and Nadeau behind Fire Station l
- 4. Northeast Corner State Park Reid and Waterworks (Sterling State Park) I
- 5. North Monroe and Nadeau ;
- 6. Heiss Road, West of Exeter j
- 7. Bluebush and Stewart i
- 33. Montel Road, South of Nadeau Rd !
- 34 Newport Road, West of Telegraph at Nike Park ;
- 40 Buhl, between Grafton and Telegraph !
- 43. Toll Road,1/4 mile South of Leroux i
- 44. Williams, South of Post at the railroad crossing
- 45. North Dixis, East of Hurd at the Jefferson Schools Administration Building
~
- 46. Vivian, North of Fix Road at the Frenct1 town Township Hall
- 50. Stewart, West of Bates Lane City of Monroe l
- 6. Lorain, West of Dane Drive - at Manor School
- 9. East Fro'it and Port Street l
- 10. North Macomb at Monroe Public Schools Administration Building '
- 23. Southwest Corner East Fifth and South Macomb
- 3 5. 600 fDet West of Lorain behind St. Mary's Academy
- 37. North Dixie, West of 1-75 at Heck Park -
- 38. f ront, east of Link Street !
- 47. Lorain and Maple
- 48. Second and Cass ;
Ash Township I
- 11. Grafton, North of Sigler
! 12. Sigler Road, East of Telegraph
- 13. Exeter, South of South Stony Creek
- 14. North Stony Creek and Newport Road at C 8i O Railroad t
- 15. Romine Road, North of Newburg ,
- 16. Carleton South Rockwood Rd, West of Berlin Road
- 52. Northeast corner of Labo and Swan Creek Road '
- 56. Newburg, West of Telegraph (Wilson Substation)
- 57. Carleton-South Rockwood Road, East of Briar Hill (Eyler School) ;
- Supplementary Siren System l
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l RERP Plan I s Revision 1 Page E-4 -l 1 1 Village of Carleton I
- 17. Horan, North of Ash at Ash Carleton Park i V6llage of South Rockwood
- 18. North Dixie Highway, North of South Huron River Drive j
- 55. Park and Edwards (South Rockwood) j Berlin Township l
)
- 19. U.S. Turnpike, North of Roelant Road
- 20. Armstrong, South of Labo ;
- 21. Ruhl Road, West of I-75 )
- 32. Newport South Road at Niedermeier Elementary School ;
- 41. Strong Road and U. S. Turnpike >
- 42. Northeast Corner North Dixie Hwy. and Swan Creek Road l
- 53. Southeast corner, Armstrong and Mattison i
- 54. Sigler Road, West of Hagerman ]
Village of Estral Beach
- 22. Lakeview and' Superior near Fire Station I
Monroe Township , l
- 24. South Telegraph and Albain at Monroe Public Schools Garage ]
- 25. Albain Road, West of LaPlaisance '
- 36. West Seventh and Telegraph at the Road Commission Garage )
- 39. Dunbar. West of South Monroe
- 49. Western and Erle (Waterloo School) l Exeter Township !
- 51. Northeast corner, Helss Road and Finzel WAYNE COUNTY !
Brownstown Township
- 26. Lee Road, East of West Jefferson
- 28. Gibraltar Road, West of Fort Street near fire station
- 58. 32355 West Jefferson (Brownstown Fire Station #2)
- Supplementary Siren System 1
l 1 L
T. r RERP Plan I. Revision 1 Page E-5 City of S6brahar
- 27. Munro and Bayview near fire station City of Flat Rock
- 29. Peters and Vreeland in Railroad yard
- 30. Arsenal Road, North of Huron River Drive 31, Alders and Woodruff in Elementary School yard City of Rockwood
- 59. Fon Street, North of Huron River Drive at the Rockwood Depanment of Public Works
- Supplementary Siren System
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) !' RERP Plan j Revision 1 ;
Page F-1
, e F. EMERGENCY COMMUNICATIONS L I i
F.1 Telephone Communicetions The emergency telephone communications network (Figures F-1 and F-2) established for " the Emergency Response Facilities combines Direct-inward-Dialing (DID) lines provided by Century Telephone with dedicated lines on a separate Ed! son-owned Competerized - Branch Exchange (CBX) telephone system (ROLM). An Edison-owned microwave system i is also installed to provide back-up emergency communications from the Fermi 2 site. Figures F-1 and F-2 lilustrate the interface of these systems betwetn the various Emergency Response Facilities. l F.1.1 CSX Lines - Extensions on the ROLM system are divided into two series. One series allows communication between the Emergency Response Facilities and features DID ! capability, which allows an outside caller to be connected directly to an extension by ! prefixing the four-digit extension number with a three-digit number. The second series is unrestricted for outgoing cells; however, these extensions do accept direct incoming calls, Sufficient CBX lines are distributed among the Emergency Response Facilities to ! provide adequate communications both internal and external to the site. F.1.2 Direct-Ring Lines - Direct ring lines are provided between the Emergency Response l Fscilities and Offsite Emergency Response Organizations. These extensions are programmed for automatic ring. The location of direct ring instruments and associated , extensions are listed below and diagrammed in Figure F-2: Facility Position Facility Accessed . t Control Room Communicator Technical Support Center i Technical Support Center 2 , (second line) , Operational Support Center i Monroe County Sheriff [ Wayne County Sheriff , Nuclear Security - Central ' Alarm Station / Secondary i Alarm Station i Emergency Notification System (ENS) ; t Technical Emergency Control Room 2 - Support Director Emergency Operations Center Facility Emergency Officer Hotline Monroe County Sheriff Wayne County Sheriff Operational Support Center , ENS .
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I RERP Plan l i Revision 1 Page F-2 j Facility Position Feellity Accessed l Technical Nuclear Safety Control Room I Support Advisor i Center (Con't) i Communicator Monroe County Sheriff [ Wayne County Sheriff - Red / Chem Control Room 2 (second Advisor line) , Radiation Protection Control Room 2 (s9cond i Advisor line) l I NRC Conference ENS Room - Technical Operational Support Center l Communicator Control Room ; Control Room'2 (second i line) Emergency Operations Facility Technical Engineer Control Room 2 (second ! line) i Emergency Emergency Officer Technical Support Center Operations Emergency Director Hotline i Facility Joint Public Information : Center ENS Nuclear Operations Technical Support Center f Advisor ENS , f Public Information General Offices Coordinator Joint Public Information Center Communicator ENS l F.1.3 NRC Telephones - Telephone communications in the NRC conference room in the - Technical Support Center (TSC) consist of a hot line on the ENS and a minimum of two general access telephones. The NRC office / conference room in the Emergency Operations Facility (EOF) has an ENS hotline and a minimum of two general access telephones. e L
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RERP Plan Revision 1 Page F-3 F.1.4 Microwave System - An Edison-owned microwave system is installed at Fermi 2 to provide back-up emergency telephone communications. Through use of the microwave system, telephone communications are routed from the Fermi site to the General Offices in Detroit and transferred by land lines through the Michigan Bell Telephone (MBT) central office system to any desired location. The microwave system may be accessed from the ROLM system extensions. Offsite or remote locations may be accessed via the microwave system from all16taphone locations. F.1.5 Medical Support Facilities - The Control Room maintains responsibility throughout an emergency for all communications to hospitals. Ambulance / hospital communication 4 Aystem maintenance is the responsibility of the ambulance and hospital services. F.1.6 Joint Public Information Center (JPIC) - The telephone network for the JPIC, located in Monroe, is served by MBT as the local telephone company. The interface between the JPIC and the Onsite Emergency Response Facilities is provided through foreign exchange lines that are switched at MBT Monroe end passed through Century Telephone i switchgear at Newport. These fqreign exchange lines provide 13 site extensions from the < Onsite Emergency Response Facilities, in addition, over 50 general business lines on the MBT system have been installed,10 (credit card only) of which are for use by media representatives. Provisions have been made at the JPIC to expand the number of lines i. for media representatives within 48 to 120 hours of notifying MBT of additional emergency needs. l Direct dial lines are also available from the JPlc Communicator to the EOF and the Edison General Offices. F.1.7 Telephone Equipment Maintenance - If an emergency occurs at Fermi 2, the emergency response staff can be augmented by Detroit Edison personnel from Telecommunications Systems, Information Systems Organization, a representative from Century Telephone; and a representative of ROLM of Michigan to serve as technical advisors to effect repairs or open additional lines for use Dy the Emergency Response Organization. F.1.8 General Information All single-line instruments in the Emergency Response Facilities have muted rings to reduce ambient noise levels. i Headsets are provided for positions where heavy telephone use is anticipated. l
i RERP PLOn Revision 1 Page F-4 l i The ROLM system has many special teatures available to users that include, but are not limited to, the following: Conferencing capability for up to eight parties, two of whom may be offsite
- Stetlon call forwarding, which allows a party to direct incoming calls to another
; work area Consultation hold, whereby a user can temporarily place a person on hold, consult with a third party, then return to the original call The entire emergency communication system is tested on a periodic basis, consistent with communications drill requirements.
s F.2 Radio Communications The communications network at Fermi 2 also involves several radio systems to effect communications within the plant with radiological monitoring teams, maintenance teams, and Nuclear Security personnel, as well as provide backup communication modes to essential Offsite Emergency Response Organizations in the event of telephone equipment malfunctions or traffic congestion. F.2.1 Operations end Maintenance System - There are two radio consoles normally used in the Control Room. One is installed in the operator's desk while the other is installed in ths Nuclear Shift Supervisor's office. These consoles allow for direct communication to VHF hand-held portable radios on Channel 3 (Operations Channel) via the plant's radio l repeater system. In addition to its local microphone, the radio console at the operator's l desk has provisions to allow radio dispatching from any one of 15 remote microphone , positions located at the base of each control room panel. i l An additional radio console is stored in the Control Room operator's desk which can be l placed into service to allow for direct communication to VHF hand-held portable radios ; on Channel 1 (Maintenance Channel) via the plant's radio repeater system, should this { alternative become necessary. l l In addition to communications with Operations and Maintenance personnel as noted i f above, hand-held portable radio units with four-channel capability are used by the Damage Control and Rescue Teams, Fire Brigade, or Onsite Radiological Emergency Teams (RETS) to communicate with the Control Room and/or Radiation Protection ,. personnel in the OSC and other remote parts of the plant via the radio repeater system on Channels 1 or 3. Channels 2 or 4 are utilized where direct communication between portable units is desired and the repeater system is inoperative.
b RERP Plan Revlalon 1 Papa F-5 F.2.2 Offsite Radiological Emergency Teams - The radio control console for directing the actions of Offsite RETs is located in the EOF / RET Dispatch Room. Each RET vehicle is ; equipped with a radio to provide mobile communications within a range of 20 miles. I Radio communications with Offsite RETs are carried over customer service UHF . frequencies assigned to Wayne-Monroe Division. ) l F.2.3 Nuclear Security System - The Nuclear Security System provides communications with : Nuclear Security personnel within the Owner-Controlled Area through the use of l 2-channel hand-held portable radios operating through UHF frequencies .and two ! associated repeater systems. The primary location of the radio console is the Security Bullding Secondary Alarm Station (SAS); however, this console is also duplicated at the ) Office Services Building Security annex Central Alarm Station (CAS). i Communications with the Monroe County and Wayne County Sheriff departments from the Emergency Response Facilities are through the installation of direct ring lines as i described in Section F.1.2. In addition to using gen 6ral business phones as a backup, l the EOF Security Advisor has direct radio contact with the Michigan State Police or the ' Monroe County Sheriff when telephones are Inoperative. The CAS and SAS have telephone-to-radio patching capability which also allows a telephone caller to be relayed to the Monroe County Sheriff or the Michigan State Police via radio. l {, F.3 Facsimile Transmission , Facsimile machines are provided in the Control Room, the TSC, the EOF, the JPIC and at ! the General Offims in Detroit for use by emergency response and NRC personnel. l F.4 Public Address System Public address systems are evallable in the TSC and the EOF to allow dissemination of information to emergency response personnel within these facilities. 9 F.5 Plant intercom System l Extensions of the plant intercom (HiCom) system from the Control Room used for general plant operations are located in the TSC, the EOF, the OSC, and the Control Room ; to disseminate information that may affect onsite personnel. e l
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RERP Plan ( r Revision 1 Page 0-1 G. PUBLIC EDUCATION AND INFORMATION l 1 i This Plan Section describes Detroit Edison's Public Education and informatlon Program, the type of information that will be distributed, and the procedures for roordinated dissemination of information to the public concerning Radiological Emergency Responso Preparedness (RERP) in the Fermi 210-mile EPI. l i G.1 Educat6on end information Program Detroit Edison provides information to the public at least annually regarding how they will be notified in the event of an emergency and what their actions should be in such ! an emergency. This information includes, but is not limited to, the following: Educational information on radiation
- Phone numbers to call for additional infortnation
- Protective measures (sheltering information, evacuation route maps, f reception / congregate care center locations, and respiratory protection Information) !
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- Any special instructions for the handicapped - This information is propdred by Detroit Edison and is jointly reviewed and approved by !
i the state, the counties, and Edison, it is mailed at least annually to each occupiable and addressable dwelling within the 10-mile EPZ. This same information is published -! j snnually in telephone directories issued in communities w! thin the EPI Other forms of information may include, but are not limited to, such activities as school program i presentations, speeches at meetings of community groups, booth displays at the Monroe [ County Fair and tours of Fermi 2. The tour programs include exhibits, lectures, and the , opportunity to ask questions about all aspects of plant operations. I G.2 Public Awareness Detroit Edison's Public Information Program provides the permanwnt, as well as the , transient, adult population with an adequate opportunity to become aware of the Information that is available. Notices refer the translent to the appropriate radio and/or , television stations for information in the event of an emergency. These notices are l prepared from approved material contalt.ed in the informational malling to parmanent l residents. Copies of this information are made available annually to hotels, highway rest areas, and state recreation areas with the 10-mile EPZ.
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RERP Plan Revision 1 Page 0-2 0.3 News Centers The Joint Public Information Center (JPIC)is activated to coordinate the dissemination of information to the public during ari emergency. The JPIC is located at Monroe County Community College and can accommodate approximately 500 members of the news media. A multichannel telephone trunk is available near the cafeteria to provide a means for the local telephone company to prepare adequate communications on short notice as described in Section F. The college is located outside the EPZ approximately 12 miles west southwest of Fermi 2. The JPIC will be staffed by represe'itatives from Detroit Edison, Monroe County, Wayne County, the Province of Ontario, and the State of Michigan. This team reviews information, coordinates all news releases, and holds press conferences. Detroit Edison also has an Onsite News Center that can accommodate 20 to 60 news media personnel at the Nuclear Operations Center (NOC). The Onsite News Center serves as a briefing area for the media when appropriate. The NOC is approximately one mile southwest of the plant and is within the Owner-Controlled Area. O.4 information Sources During an Emergency Plant operations'and technical staff must remain isolated from tasks that distract them from their immediate responsibility of mitigating the emergency and restoring the plant to normal operating conditions. For this reason, additional Detroit Edison personnel are assigned to organtre and implement all communication measures that serve the news media, the public, company employes, and public officials from Federal, State, and local levels. Designated public telephone lines are reserved at the JPIC for use by the public wishing to obtain specific information about the emergency. These telephone numbers will be widely publicLted at the time of the emergency. The lines usually will be staffed by representatives from local government. Rumors should be kept to a minimum through the use of this one authenticated stource of information. The rumor control center is described in the Public information Annex of the Monroe County Emergency Operations Plan. A Company officer has been designated as the spokesperson for Detroit Edison on the Joint Public Information Team (JPIT) in the event of an emergency at Fermi 2. This spokesperson and his/her staff have communications capability to Edison's EOF and the Employe Emergency Communications Center located in the corporate General Offices (GOECC), in addition, this spokesperson or alternate is responsible for the briefing of news media members who are present at the Onsite News Center when it is activated to serve for media briefings in emergencies involving nonradioactive releases.
i RERP Plan l Revision 1 ! Page G-3 l O.5 News Media Acquaintance Program j l Detroit Edison, with the assistance of State and local authorities, conducts an annual i program to acquaint the news media with emergency planning and procedures. These ; programs cover redl]) tion and radiological effects of nuclear plants, as well as offer ' information to enhance the media's ability to communicate radiological events to the ; public. P i i i t i 6 t l l i 1
i RERP Plan ! Revision 1 Page H-1 i i M. EMERGENCY FACILITIES AND EOulPMENT l l This Plan Section identifies and briefly describes the functions and location of the Emergency '.esponse Facilities (ERFs) and equipment that will be used and maintained ; by Fdison in coordinating and performing emergency response activities, j r I H.1 Emerger>cy Response Facilities ! The ERFc that have been established at Fermi 2 to assist Control Room personnel in ! t mitigating the consequences of accidents and responding to abnormal operating conditions are the Technical Support Center (TSC), the Operational Support Center (OSC), and the Emergency Operations Facility (EOF). i The ERFs are staffed by the emergency organization as described in Section B. The minimum staffing for the ERFs varies, as described in Section B, depending upon the class of emergency as determined by the emergency action levels discussed in Section D. The ERFs are activated as soon as possible after an emergency is declared. The ERFs are linked by a comprehensive communications network to provide reliable and ! timely communications between the Control Room, the ERFs and offsite Emergency Response Organlaations. The communications network provides dedicated telephone ; lines, general business lines, intercoms, public address speakers, microwave communications, data transmission, and radio link capabilities. Detailed information on - the communication capabilities is provided in Section F. ; i Emergency Response Information System (ERIS) equipment is provided to gather, store, and display data in the Control Room, the TSC, and the EOF. This enables personnel to analyze plant conditions and to make appropriate recommendations regarding protective actions for emergency personnel and the public. The ERIS is described in Section H.4 , and in greater detail in the Fermi 2 Updated Final Safety Analysis Report (UFSAR).
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The TSC and the EOF have information centers containing the necessary up-to-date plant records, procedures, Technical Specifications, and as-built drawings to aid emergency personnelin their technical analysis and evaluation of emergency conditions. Procedures have been developed for ensuring that the most cu/ rent g revisions of these controlled documents are being maintained. i The ERFs provide adequate space to accommodate assigned emergency response personnel. There is sufficient space for the operation and maintenance of communications and data transmission equipment, data acquisition and display equipment, and other instrumentation required at the respective facliltles. Storage space is provided for the necessery emergency supplies, protective equipment, plant documentation, and administrative materials. f
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h 1: ; RERP Plan Revision 1 j Page H-2 ) I The TSC and EOF each provide a consultation room and provisions for a small staff of , Nuclear Regulatory Commission (NRC) personnel. Provisions include desks, chairs, and l telephone lines. j l
- The following sections describe the individual ERFs and their corresponding specific i functions. Additional detailed information regarding the design, construction, and !
habitability of the ERFs is provided in of the UFSAR. H,1.1 Control Room - The Control Room is located on the third floor of the Auxillary Building j and is designed to meet 10 CFR 30, Appendix A, Criterion 19. The habitability standards i ard described in Chapter 6 of the UFSAR. The Control Room contains instrumentation, l controls, and displays for monitoring and controlling the plant operating and safety I systems during emergency events and for mitigating the consequences of an f emergency. Safe operation of the reactor and plant manipulations are performed by j licensed Control Room personnel under the supervision of the Nuclear Shift Supervisor, j Initial emergency response measures, as shown below, are exercised from the Control Room under the direction of the Emergency Director (Nuclear Shift Supervisor). J Plant operations i Direction and control '
- Accident assessment / meteorology l Ra o gica a sessment Protective actions (Inplant; offsite until EOF is activated) '
Communications (licensee /offsite response organizations) ; [ i l The Control Room is the initial onsite communications center during an emergency, it has a reliable communications system providing communication capabilities to the NRC, 4 Offsite Emergency Response Organizations, OSC, TSC, EOF, and all areas of the plant. I H.1.2 Technical Support Conter - When emergency conditions escalate to en Alert status, coordination of the emergency response measures shifts from the Control Room to the . Technical Support Center under the direction of the Emergency Director (Plant Manager /alternata). The Emergency Director coordinates activities in the TSC and ; interfaces with the Control Room, the OSC, and the EOF. j i I a . - - , - , , - - - - - - -,- -
i r l RERP Plan i Revision 1 l Page H-3 j l The TSC is the emergency operations work area for senior technical, engineering, and management personnel; other licensee designated technical and administrative support ! l personnel; and a small staff of NRC personnel. Closed circuit television is installed in ! i the TSC for observation of Control Room displays. The TSC provides plant management l l and technical support to Control Room personnel and rolleves the reactor ?c 9 tors of i peripheral duties not directly related to reactor system manipulations during an ! emergency. The TSC may also be used to provide technical support during recovery 1 operations following an emergency. TSC personnel perform tne functions listed below for an Alert, Site Area Emergency, and Oeneral Emergency as listed below until the EOF is functional. j l i Direction and control Accident assessment o - Corrective actions
- Plant system engineering ]
- Radiological assessment 1
- Protective actions (inplant; offsite until EOF 16 activated) !
Site access control
- Communications (licenses /offsite response organizations) !
When functional, the TSC becomes the primary onsite communications center during an j emergency. It has a reliable communications system providing communication i capabilities with the Control Room, the OSC, the EOF, the NRC, and other offsite agencies. The system provides for the immediate exchange of information on plant j status and operations, notifications to Federal, State, and local agencies, and l Inter-communications within the TSC. The communications system consists of ! dedicated and general business telephor's lines, a microwave system, the plant intercom, i a public address system, and data transmission equipment. The TSC is located at the southeeft end of the plant within the Protected Area on the t ground floor of a two-story Office Building Annex. The TSC is habitable during postulated radiological 6...orgencies to the same degree as the Control Room (Design l Criteria Ig), with the exception of redundant filter systerns. TSC construction provides special shleiding and an HVAC system designed to facilitate the occupation of all , necessary personnel for winter and summer environmental radiological accident i conditions. Portable airborne and area radiation monitors that alarm locally are , provided. In the event that the TSC becomes uninhabitable. TSC functions are divided < between the Control Room and an alternate facility such as the EOF as directed by the ! Emergency Director. , H.1.3 Operational Support Center - The OSC is a designated assembly point nobr the Control , Room. it is located at the north end of the third floor of the Turbine Building. The OSC provides an area for the coordination of shift personnel to support emergency response i operations without causing congestion in the Control Room. Personnel reporting to the ' OSC may include the Fire Brigade, the Damage Control and Rescue Team, the Onsite ' Radiological Emergency Teams, instrument technicians, and general mainterance 3 personnel.
b CERP Plan Revision 1 Page H-4 i The OSC is activated for en Alert, Site Area Emergency, or General Emergency. The OSC ! Coordinator integrates OSC activities and dispatches emergency personnel on !
. assignments as cirected by the Emergency Director, i The OSC has dedicated telephone lines to both the Control Room and the TSC and a i dial telephone for communications with other onsite and offsite locations. Portable i radios are also available to complement er serve as backup to the telephones and for !
onsite emergency teams. l t in the event that the OSC becomes uninhabitable, an eres at the rear of the machine f shop is designated as the alternate OSC. The machine shop is located on the first floor ! of the Office Services Building. i H.1.4 Emergency Operations Facility - The EOF is a command post for the overall management of the offsite emergency response including the coordination of l radiological and environmental assessments, the determination of protective actions for ! the public, and the management of the recovery operations stated below: i i Radiological assessment
- Offsite protective actions ;
- Ottsite radiological monitoring Environmental sample analysis j Public information Communications (licenses /otfsite response agencies) l The EOF is on the first floor of the Nuclear Operations Center (NOC) and is .
! approximately 6000 feet southwest of the Fermi 2 Plant on owner-controlled property. ! Supporting facilities at the NOC include the plant simulator, plant training offices, training classrooms, space for news reporters, etc. Access is available to the facility [ from two directions via roads under the control of Edison. ! The EOF has been designed for habitability in the event of a postulated accidental radioactive release from Fermi 2. The design includes shielding (protection factor of 20), l an HVAC system with HEPA filters, and portable airborne radioactivity and area radiation ! monitors that alarm locally to assure that personnel exposures to radiological hazards do not exceed 10 CFR 20 limits. ; The EOF is activat6d for a Site Area Emergency or Oeneral Emergency. The Emergency . l Officer is responsible for the integration of EOF activities and the offsite emergency ' response. l t The Radiological Emergency Team (RET) Coordinator coordinates the Offsite RET field surveys by radio, as directed by the Radiation Protection Coordinator, from the RET Dispatch Room in the EOF. i i T w--wv ----+ __
4 RERP Plan Revision 1 Page H-6 The EOF counting laboratory is available for the qualitative analysis of environmental samples collected by the RET, as well as a backup facility to the inplant laboratories. Laboratory facil6 ties are described in Section H.3.2.2. An extensive communications system is provided in the EOF, which includes communications to the TSC, the Offsite RETs, the NRC, the State Emergency Operatious Center (EOC), and intercommunications within the EOF. The system consists of dedicated and general business telephone lines, a microwave systern, radios, the plant HICom, a public eddress system, and data transmission equipment. The State of Michigan and the Province of Ontario may dispatch representatives to the EOF as they deem necessary to support emergency response activities. The EOF contelns provisions such as desks, chairs, telephones, and data transmission equipment to support these representatives. The EOF provides a consultation room and provisions for a small staff of NRC personnel. An alternate EOF is located at the Wayne-Monros Division Headquarters, approximately 22 miles northwest of Fermi 2. The facility has adequate communications equipment and sufficient space to accommodate the additional personnel required for continuity of.
' dose projection and decision making capability, including coordination of the offs!te teams. Portshle equipment is provided for the personnel to leerform their assigned functions. Procedures are in place which describe the activation and support functions.
H.2 Onst'.e Monitoring Systems Onsite monitoring systems used to initiate emergency measures in accordance with Section D, as v4 ell as those for conducting ongoing assessment, include geophysical phenomena monitors, radiological monitors, process monitors, and fire and combustion product detectors. H.2.1 Geophysical Phenomena H.2.1.1 Meteorological Monitoring - The meteorological monitormg system at FormI 2 presently meets the requirements of Regulatory Guide 1.23. The onsite 60-meter meteorological tower has meteorological sensors that include a temperature differential network, a sigma theta signal conditioner, and a precipitation gauge capacle of real-time data acquisition. A secondary meteorological system consists of redundant sensors mounted on the 60-meter tower that are independent of the primary system and require redundant signal conditioners, digital data acquisition systems, and power supplies. A block diagram of the modified system is shown in Figure H-1, Block Diagram of Detroit Edison Meteorological Data Aquisition System, and Table 1, Meteorological Parameters, indicate.s the parameters measured.
I l f1ERP Plan ,l Revisien 1 ! Page H-6 i The meteorological system is capable of providing the following types of data upon request from dial-up terminals in the Control Room, TSC, and EOF: Instantaneous values ;
- One-minute blocked averages Fifteen-minute blocked averages )
Fifteen-minute running everage 2 One-hour blocked everage !
- Twelve-hour, fifteen-minute blocked historical file l
1 in addition, the system has the capability of being remotely interrogated on a i simultaneous basis by multiple users, j For accident assessment, the ERIS gathers real-time data and performs the ! required meteorological calculation as stated in Section 1. i H.2.1.2 Hydrological Monitoring - The National Oceanic and Atmospheric ;
- Administration (NOAA) has an official gauging station in the Fermi 2 Intake j l'
canal that records Lake Erie water levels. L . j H.2.1.3 Seismic Monitoring- Strong motion triaxial accelerographs are installed in [ different locations of the reactor / auxiliary building to measure the basic j l ground motion / time history acceleration, as well as the seismic motion. : Passive earthquake recording instrumentation has been provided to measure 'l various ground motion and in structure response spectra. The passive ' instruments serve as backup for the active sensors. ' l' l H.2.2 Reelological Monitoring - The area, effluent, portable, and post-accident radiation monitors are listed in Table H-2 through Table H-5: e o Table H-2, Typical Area Radiation Monitors ' o Table H-3, Radiological Effluent Monitors ! o Table H-4, Typical Portable Monitors o Table H-5, Post-Accident Process and Effluent Radiation Monitors j H.2.3 Process Monitors - The process monitors are listed in Table H-6, Process Radiation Monitors. , H.2.4 Fire and Combustion Product Detectors - Fire and combustion product detectors are i installed throughout the plant to monitor various vital areas. These are classified as ' ionization, phc,toelectric, thermal fixed-temperature, and thermal rate-of-rise detectors. 1, t l l l l l l
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RERP Plan i j Revision 1 { Page H-7 l H.3 Offsite Monitoring Systems ' ! i H.3.1 Geophysical Phenomena { H.3.1.1 Meteorological Monitoring - The meteorological monitoring system at ; Fermi 2 is operated to NRC standards. Sufficient redundancy is built into the , system so only under the most unusual circumstances would site data be unavailable. Should any of the parameters required for dose assessment be i unavailable from Formi 2, worst case meteorology can be assumed. l l Additional supplementary wind direction and wind speed data is available via $ a dial-up line from the 10-meter towers located in various directions from the site. This system is operated and maintained by Edison's Engineering ' Research Department as a portion of the southern air quality network. This system is not maintained to NRC standards and may be subject to change. ; Also, National Weather Service data are available by telephone from Ann l Arbor, Michigan and a contract is in place with Weather Services international ! for forecast data, i H.3.1.2 Hydrological Monitoring - NOAA has gauging stations at Gibraltar, Michigan, : about 10 miles north-northeast of the plant on the Detroit River, and Toledo ! Ohio, about 22 miles south-southwest of the plant on Lake Erie. Data will be l obtained from the Toledo station by calling the Toledo Coast Guard should the gauge at Fermi 2 become inoperable. l H.3.1.3 Seismic Monitoring - Selsmic data will be obtained from the University of Michigan at Ann Arbor, Michigan as a backup resource. ~ H.3.2 Radiological Monitoring I H.3.2.1 Offsite Monitoring - An ongoing Radiological Environmental Monitoring , Program (REMP) is consistent with the Formi 2 Technical Specifications. The following media are evaluated: Direct radiation (TLDs)
- Airborne particulates .
~ Airborne lodine >
Surface water '
- Drinking water Ground Water Shoreline sediments i
Fish l - Milk Vegetation i
t i RERP Plan Revision 1 i Page H-8 l i ! j in addition to the original seven Thermoluminescent Dosimetry devices (TLDs) i- placed in the area of the highest ranking D/Q 3g stations are located at the 2,5, and 10-mile redli. Table H-7, Radiological Environmental Monitoring l Program 1988-198g, describes the routine environmental sampling program. l l Figures H-2 through H-4 show the location of the sampling stations relative : i to the plant: l t o Figure H-2, Sampling Locations by Station Number (Site Area)
- h. o Figure H-3, Sampling Locations by Station Number (Site Area - Lake Erie) !
o Figure H-4, Sampling Locations by Station Number (Greater than 5 Miles) ! o Figure H-5. Sampling Locations by Station Number (Less than 10 Miles) : Duplicate Thermoluminescent dosimeters (TLDs) and air samples for collection of radioactive for particulates and radiolodines are in place at i various sample locations in case of an emergency. Other environmental , media, including surfaca and drinking water samples, can be readily obtained j should they be required. H.3.2.2 Laboratory Facilities - The EOF laboratory is the designated facility for the ' receipt and analysis of environmental samples during emergencies. The inplant Chemistry and Red Protection laboratories are also available for the snelysis of environm6ntal samples. The calibration and operational readiness of alllaboratory equipment is assured in accordance with plant procedures. Typical equipment for all l laboratory facilities is listed in Table H-9. Typical Laboratory Equipment. ! In addition to the above, the State of Michigan has a mobile laboratory with , various radiological and radiochemical analysis equipment. In the event of an ' emergency, the State will arrange for this laboratory to be moved to the plant vicinity. Provisions for analyses of environmental samples have also ; been established with the contractor or vendor who conducts the routine REMP program. ; i H.4 Emergency Response Information System (ERIS) .l The function of ERIS is to scan plant instrumentation and gather, display, and store data , needed to analyze and exchange information on plant conditions between emergency i response facilities. ERIS equipment is located in the Control Room, the TSC, and the EOF. The ERIS is described in detall in the UFSAR. " 1
L 4 RERP Plan Revision 1 Pope H-9 I The ERIS computer interfaces with the meteorological computer to provide and retain the data needed to project offsite doses. The following information can be acquired or determined through the ERIS:
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l . 1 Plant status and dynamics prior to and during the accident Safety parameter display system . Trending of the accident Status of the operation , 1 Quantity of radioactive gases released to the environment I Prevailing meteorological status ] Radiological accident assessment (impact of dose on public health and safety) j Record of monitored parameters for the duration of an emergency ' H.5 Emergency Equipment and Supplies : Equipment and supplies needed to support the emergency response effort fall in general categories: # Communications equipment I Protective clothing Raspiratory protection equipment , Realological monitoring equipment Environmental sampling equipment ' Decontamination supplies
- Miscellaneous tools and equipment '
Data and reference material Radiation Protection emergency equipment and supplies are listed in POM Proc.edure l 67.000.405. Backup equipment and supplies are evallable at designated plant storage I locations. The operational readiness of emergency equipment and supplies is ensured by conducting frequent inventories (at least quarterly) in accordance with POM Procedure 67.000.405. Equipment / instruments will be operationally checked at the time of the r inventory and those instruments that require calibration prior to the next inspection are replaced with calibrated ones. Calibration intervals are based on the recommendations
'of the manufacturer and previous operational history. Perishable supplies, such as batteries, are replaced as required at the time of the inventory. -- - y-,--,,a.- w-,--, --
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RERP Plan ; Revision 1 i Page H-10 TABLE H-1: METEOROLOGICAL PARAMETERS > 10-Meter Level Wind Speed ; Wind Direction l Air Tempegture j Dow Point ? Sigma Theta , i 60-Meter Level ! t Wind Speed , Wind Directior) L , e 'I Miscellaneous ! Temperature Difference (60-1g) !
- Precipitation at Ground Level Pasquill Stability Class !
- a. Available from the primary system only.
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1 (H RERP Plan l Revision 1 l n Page H-11 ; TABLE H-2: TYPlCAL AREA RADIATION MONITORS (a) j J l.O. Numbor@) Location (') Range Function j Main Control Room i D21-N106 G-13-3-AB 10-2-102mR/hr Monitor ) SE Corner I 3 D21-N107 F-9-SB-RB 10-1-10 mR/hr Monitor SW Corner Room D21-N108 B-10-SB-RB 10"I-10 3mR/hr Monitor { NW Corner Room i 3 D21-N109 B-15-SB-RB 10-l-10 mR/hr Monitor ; r NE Corner Room i D21-N110 0-17-SB-RB 10~1-103mR/hr Monitor j D21-N111 G-11-SB-RB 10~l-103mR/hr HPCI Room Monitor D21-N115 F-15-5-RB 10-2.go2mR/hr Water Act'vity & Criticality Monitor i D21-N123 M-17-1-RWB 10-2-102mR/hr Radweste Control Room , D21-N128 G-11-4-AB 10-2-102mR/hr Personnel Protection-
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Stand-by Gas Treatment System ' (SGTS) D21-N132 G-13-1-AB 100 -104mR/hr Operating information ! D21-H145 C-12-1-RB 10~l-103mR/hr Drywati Maintenance Monitor . l (a) Table H-2 does not include all the Area Radiation Monitors (ARM) in the plant, but is typical f of those available. r (b) Detector and/or channel number i (c) Locations by column-row-floor-building RB = Reactor Building; AB = Auxiliary Building: RWB = Radweste Building; SB = Service Building t t
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, TADLE H-3: RADIOLOGICAL EFFLUENT MONITORS I? I.D.-
e n o i,. ,(e) t.ee .n*> T. F.meu.o l D11-N402 F-3-1-CWPH Liquid Monitor Liquid l Effluent Discharges to Lake Erie ; D11-N403' NP-16-3-RWB Gaseous Monitor Geseous ! Effluent Discharges from RW Building l D11-N404 N-3-3-TB Gaseous Monitor Gaseous - Effluent Discharges from Turbine i Building i i D11-N405 TU-8a-1-SB Gaseous Monitor Gaseous Effluent Discharges from SOTS t D11-N406A F-15-5-AB Gaseous Monitor Gaseous Effluent Dischages from SGTS ! i D11-N406B F-13-5-AB Gaseous Monitor Gaseous l Effluent Discharges from SGTS i D11-N407 F-g-56-AB Gaseous Monitor Gaseous !' Effluent Discharges from Reactor Building l I. l (a) Detector and/or channel number ; (b) Locations by column-row-floor-building ;
- i. Buildings are CWPH = Circulating Water Pump House; AB = Auxillary Building; TB = Turbine Building; RWB = Redweste Building; SB = Service Building j t
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RERP Plan i Revision 1 : Page H-13 TABLE H-4: TYPICAL PORTABLE MONITOR 8(a) Contamination (personnel, wounds, equipment, areas) - [ Friskers (hand-held and PCM-1a) OM detectors / Gas flow proportional Radiation detection and measuremwnt - OM survey meter /lon chamber survey meters High range radiation -
, GM survey meter with range to 1000 R/hr Airborne Radioactivity (particulates, radiolodine gaseous)
Continuous Air Monitors Long Term Air Samplers (>24 hrs) Short Term Air Samplers (<24 hrs) (a) The Fermi 2 Updated Final Safety Analysis Report provides a description of portable monitors in Chapter 12. . l v o
+
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j [ lf ' RERP Plan
- b. Revision 1 Page H-14 TABLE H-5: POST-ACCIDENT PROCESS AND EFFLUENT l RADIATION MONITORS i
, 1 1.D. . f . Number (a) Location Type Function 1 , F ~ D11-443A Drywell Post-Accident Monitor Post-Accident J H ARM Radiation Level in Containment D11-4438 Druell Post-Accident Monitor Post-Accident t Radiation Level in ARM , Containment D11-300A. 5th Floor Post-Accident Monitor Post-Accident . Aux. Bldg Effluent PRM SGTS Effluent : 011-3000 5th Floot Post-Accident Monitor Post-Accident Aux. Bldg. Effluent PRM SGTS Effluent 6 . .. l 1
- i. 3
- (a) . Detector and/or channel nurgher .
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w...- ~. --. - - . . - - - - - l RERP Plan Revision 1 Page H-15 TABLE H-6: PROCESS RADIATION MONITORS (e) , T 1.D. Number (b) LocasionI ') Type Range Function D11-N004A,0 M-0-3-TB PRM 100 -100mR/hr Monitor Off-Oes-Advisory Info i D11-N006A,B 0 6 Limit Fist,lon G-12-1-RB PRM 10 -10 mR/nr D11-N006C,D G-11-1-RB PRM 10 -10 mR/hr Product Carrycver D11-N008 J-6-1-TB PRM 10-I-10 6cps Detect in-leakage to GSW , D11-N009 H-13-1-AB PRM 10-1-106cps Detect In-Leakage , to RBCCW , 10*2-102mR/hr D11-N-010A,B F-13-3-RB PRM Monitor Fuel Pool D11-N-0100,0 B-13-4-RB PRM 10 -10 mR/hr Exchange & Initiate SGTS
- D11-N400A A-12-2-RB PRM 10 -107cpm Monitor in-leakage D11-N4008 D-10-2-RB PRM 10 -10 cpm to EECW t ;
D11-N401A B-15-2-RB PRM 10 1
-107cpm Monitor to In-leakage
.D11-N401B B-10-2-RB PRM 10 -10 cpm to RHR Service water D11-N408 F-10-4-RB PRM 101 -107cpm Monitor Reactor Building Vent '
for Fission Products 1 . D11-N410 G-10-4-RB PRM 10 -107 cpm 1 Monitor Reactor Building Vent for Fission Products l' l l (a) The Fermi 2 Updated Final Safety Analysis Report provides a detalled description of the Process Radiation Monitoring System in Chapter 11. (b) Detector and/or channel number (c) Locations by column-row-floor-bullding Buildings are: RB = Reactor Building; AB = Auxillary Building: TB = Turbine Building (d) Data extracted from Central Component Database (CECO) July 1988.
4 : RERP Plan r Revision 1 ; u-Page H-16 ; i TAttE H-7: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1988-1989
~~
Type of Samples 8: Sampiing Analysis . Sample Location Devics Frequency Type Frequency Direct See Table Two Continuous Gamma Quarterly ;
, Radiation H-8 TLDsat sampling- dose each TLDs location changed quarterly ,
- Fish - Fermi 2 - Nets Semlannually Gamma Semi-Yellow vicinity of or Spring end isotopic annually ,
Perch discharge. equivalent Fall an (edible .
. Walleye Control - weather portion) i Bass vicinity permits.
of Celeron Island. Brest Bay Marina Area Remarks: Yellow perch selected on the basis of being a relatively abundant species that is a sport fish in Lake Erie. Shoreline S - Pointe Grab Semi- Gamma Semi-Sediments Aux Peaux; sample annually isotopic annually NE - Estral Spring and Beach; Fall as , l E - Fermi 2 weather permits. I discharge, s p NNE - Trenton ' I Channel Control WWS - Indian Trails Community Beach . l Airborne NE '- Estral 1. Filters la, Gross Weekly Particu- Beach; NW - Continuous Changed beta (a) following ' lates (a) Site particu- weekly f;lter change. Boundary; late sampler Quaterly NNW - Site composite by Boundary; SSW - location. Site Boundary l E- 2. Radio- Changed 1b. Gamma Community iodine weekly isotopic (same as canister above NE - l Estral Beach) Control - 2.1-131 Weekly Farm 15 miles W (a) If gross beta in air or water is greater than 10 times the mean of control samples gamma, l Isotopic performed on individual samples.
h 1 RERP Plan Revision 1 Page H-17 ; TABLE H-7 (Continued) Type of Samples & Sampling Analysis , Sample Location Device Frequency Type Frequency l Surface Fermi 1 Composite Monthly 1. Osmma Monthly Water potable sampler Isotopic 'I water intake. ! Control - Trenton 2. Quarterly Channel Power Tritium composite by Plant intake, location. Remarks: Composite sampler collects an aliquot at hourly time intervals relative to monthly composting period. Drinking City of Composite Monthly 1. Gross Monthly l Water (b) Monroe sampler .. beta (a) f water intake.
- 2. Garama Monthly Control - . Isotopic composite by Detroit water location intake at 3. Tritium Quarterly Fighting Island composite by (Allen Park) location .
j Romerks: Composite sampler collects an aliquot at hourly time intervals relative to monthly t composting period. Ground Ground-water Gauge Quarterly 1. Gamma Quarterly ( l Water elevation from l l- 4 wells onsite. 2. Tritium ? Romerks: Gamma isotopic and tritium quarterly is noted and a release is
- suspect" from radwaste.
Food- Farms within -- Monthly as 1. Gamma Monthly as , Products 10-mile radius - available isotopic available preferably during growing during growing l those having season 2.1-131 season I the highest annual , l X/O.D/O 1 y Remarks: When milk samples not available, or as necessary as determined by licensee. l
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ct s , r RERP Plan ; Revision 1 -' Page H-18 p ' L TABLE H-7 (Coitinued) 3 Type of Samples & Sampling Analysis Sample Location Device Frequency Type Frequency n Milk WNW - 2.1 mi Goat, cow 1. Monthly 1 Gamma Monthly
- NW - 4.5 ml isotopic NW - 5.7 ml :
Control - 2. Semi-monthly 2,1-131 Semi-monthly Cow,14.2 when animals when animals ml. W on pasture on pasture-Y , r e b k 4 l b l l l
y 9 1
/
RERP Plan
'+. Revision 1 Page H-19 TABLE H-8: SUPPLEMENTAL TLD STAT,0NS j Direction / Sector /Stetion No. Location (approximate rilles)
NE C .T1 Estral Beach (community) Pole on Lak) shore,18 poles South of j Lakeview (1.4 miles) 4 NNE B T2 Tree at termination of Brancheau Street (privato residence) (1.1 miles) j N A T3 Pole at Northwest corner of Swan Creek Boat Club Fence (Community) 7' (1.1 miles) NNW +R T4 Site Boundary and Toll Road, on site Fence by APS #2 (0.6 miles) NW O T5 Site Boundary and Toll Road, on site Fence by APS #3 (0.6 miles) i WNW P T6 Polo Northeast corner of bridge over Toll Road (0.6 miles) W N T7 Pole, behind Doty Farm,7512 North Custer Road (control) (14.2 miles) NW O T8 Pole northeast corner Dixie Highway and Post Road (1.9 miles) Pole northwest corner Swanview and Trombly (1.5 miles) ; NNW R T9 . N A T10 Pole on South side Masseront 2 poles West of Chinavare (2.2 miles) . p NNE B T11 Pointe Mouille - West Jefferson and Campau Road, Pole on southeast corner of bridge (6.3 miles) . NNE B T12 Pointe Mouillee Game Area - Field Office, pole near tree north area of parking lot (6.1 miles) ./ N A T13 Labo and Dixie Highway - Pole on southwest corner with light (4.1 miles) NNW R T14 Labo and Brandon - Pole on southeast corner near RR (4.4 miles) NW Q T15 Pole Northwest corner Newport and Brandon Roads (3.9 miles) WNW P T16 Pole on southeast corner of War and Post Roads (4.8 miles) W N T17 Pole on northeast corner Nadeau and Laprad -near mobile home park (5.2 miles) WSW M T18 Pole on northeast corner Mentel and Hurd (4.8 miles) l
i f, . 1
'q RERP Plan "
Revision 1 j Page H-20 J TABLE H-8 (Continued) '
)
Direction / Sector / Station No. Location (approximate miles) J SW- L T19- First pole east of Fermi siren on Waterworks Road on Northeast corner of intersection of Sterling State Park Road stitrance drive and ; Waterworks (in Sterling State Park) (5.0 miles) i WSW M T20 Pole South side Williams,8 Poles West of Dixie Hwy (Special Area) (2.6 miles) WSW M T21 Pole North side of Pearl at Parkview -Woodland Beach (2.7 miles) ! SSE J .T22 Pole North side Point Aux Peaux 2 Poles West of Long (Site Boundary) i (1.2 miles) SSW K T23 Pole South side of Point Aux Peaux 1 Pole West of Huron (1.1 mile) SW L T24 Fermi gate e'lonip Point Aux Peaux Road - on fence post west of gate : (1.2 mile , , , ll NW Q T25 Pole on oil., .Ro,ad,13 Poles South of Fermi Drive (1.4 miles) , s WSW M T26 ' Pole ofi Toll Road,6 Poles South of Fermi Drive (1.1 mile) ; SW L T27 Pole Northeast corner MacMillan and East Front (7.0 miles) [ SW L T28 Pole Southeast corner of Mortar Creek and Laplaisance (10.6 miles) i l , l- SW L T29 Pole East side of South Dixie,1 Pole South of Albaln- (10.3 miles) t i ' 1 WSW M T30 Pole Custer (St. Mary's) Park corner of North Custer and Dixie (Monroe St.) (north side, next to river) (7.8 miles) WSW M T31 First pole West of entrance drive, Milton " Pat" Munson Recreation I Reserve - North Custer Road (8.9 miles) WNW P T32 Pole corner Stoney Creek and Finzel Roads (10.3 miles.) NW Q T33 Pole West side of Grafton Road,1 Pole West of Ash /Grafton, on Ash l E. Road (0.3 miles) l NNW R T34 Pole East side of Port Creek,1 Pole South of Will-Carleton (9.7 miles) , Pole on South side South Huron River Dr. across from Pace St (7.0
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N A T35 miles) l N A T36 Pole Northeast corner Gibraltar and Cahill Rds (9.2 miles) NNE B T37 Pole South corner of Adams and Gibraltar (across from Humbug l Marina) (9.9 miles) l
;i' RERP Plan Revision 1 l
- c. > Page H-21 TABLE H-8 (Continued) -s Direction / Sector /Statior. No. Location (approximate miles)
WNW R T38 6494 North Dixie Hwy. (private residence) (1.7 miles) > SSE 'O T39 SE corner Protected Area Fence (PAF) SE G T40 Midway along OBA, PAF SE G T41 Midway between OBA and shield wall, PAF SE G T42 Midway along shield wall, PAF ESE F T43 Midway between shield wall and auxillary boilers, PAF ; E E T44 Opposite Onsite Storage Facility door, PAF E E T45 NE corner, PAF 1 ENE D T46 , NE side of barge slip, on fence t s 9 5 g v 1 1 ! 1
n RERP Plan , flevision 1 j Page H-22 l TABLE H-9: TYPICAL L.ABORATORY EQUIPMENT inplant Radiochemistry Two Ge(LI) intrinsic detectors, associated electronics with an M.C.A. and computer bottware for Liamma emitting isotope identification and quantification One low background gross alpha / beta counters - One Beta / Gamma Counter One Nal(TL) detectors and associated electronics for support work One direct-coupled plasma spectrometer for trace metals determination One gas chromatograph for gas and hydrocarbon analysis
- One liquid scintillation counter for low energy beta emitting Isotope counting
- One Infrared spectrometer for organic work
- Miscellaneous: pH, specific lon, conductivity work [
Radiation Protection , e - Two Ge(LI) Intrinsic detector, essociated electronics, with an M.C.A. and computer I r software for gamma emitting isotope identification and quantification Two alpha / beta counters l Two " smear
- counters EOF Analytical Facility l j
Ge (LI) intrinsic detector and associated electronics
" Smear" counter (s) l
- Gas chromatograph and associated equipment
- pH meter with specific lon capability l
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l l. ACCIDENT ASSESSMENT l This Plan Section Indicates the methods, systems, and equipment for assessing and monitoring actual or potential offsite radiological consequences resulting from an
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i emergency event, j l.1 In-Plant Monitoring Capability Fermi 2 has appropriate equipment, systems, and plant designs to provido'the capability to monitor and sample releases from the plant or radioactivity contained in key areas of the plant. These include post-accident sampling capability, radiation effluent monitors, in-plant iodine instrumentation, and containment radiation monitors in accordance with NUREG-0737. These monitors are listed in Tables H-4 through H-8. In all cases where ; monitoring instrumentation Indicates that an actual or potential emergency event exists, 1 steps shall be immediately taken to assess and confirm the validity of the indications. , Section D includes vital plant parameters and correlation to emergency action levels, as appropriate. 1.2 Source Terms 1.2.1 Monitoring instruments Operable - Accident assessment methodology has been
- developed that incorporates the calibration of the monitor with a known radionuclide, if possible during an emergency event, the mix of radionuclides will be determined by isotopic analysis. If this information is not available, a conservative radionuclide ,
spectrum is assumed. In the case of effluent source term determinations, the conservative (in termt of offsite dose per quantity of radioactivity released) postulated ; accident radionuclide spectra is stated in the Fermi 2 Updated Final Safety Analysis , Report (UFSAR), Chapter 15. Both the spectrum of radionuclides and magnitude of ! accident source terms can be correlated to actual monitor readings in b conservative i manner. Based upon readings from accident assessment instrumentation (such as the containment high range radiation monitors), estimates of the magnitude of potential releases are developed. Post-accident sampling can provide the isotopic analysis for these release values. 1.2.2 Monitoring instruments inoperable - In the unlikely event that mstrumentation used 9 for accident assessment is offscale or inoperable, methods and supporting procedures have been established to provide estimates of radioactive releases. The normal operating release paths (turbine building ventilation stack and radwaste building ventilation stack) are designed to isolate at setpoints associated with 10 CFR 20 and 10 CFR 50, Appendix l design objectives. If the isolation falls, either a default accident radionuclide spectrum or the most recent analysis of the isotopic mix of radionuclides is used with design air flow rates. If possible, samples will be obtained and analyzed. The reactor building ventilation stack monitor alarms at predetermined setpoints, but does not isolate.
4
/ \.
RERP Plan . I Revision 1 l Page1-2 I The accident range containment high range radiation monitors (CHRRM) in the drywell and the Accident Range Monitoring System (AXMS) in the standby gas treatment system have redundant systems, it is not postulated that these monitors would all become 4
'! Inoperable or offscale at any one given time. However, specific methods for handling ;
the above occurrences, or combinations thereof, are established in procedures to correlate survey meter readings with monitor readings. In all cases, where end.when available, field monitoring data will be used in conjunction with dose projection data, i ' l.3 Dose Assessment . t Dose Assessment is the process that enables Fermi 2 emergency workers to predict the ; l level and location of radiation exposure in the event of a release or potential release of radioactivity to the environment. l.3.1 Airborne Releases - Three methods for assessing potential and actual offsite dose and ' dose rate projections are available in the Control Room, TSC, and EOF based on the methodology described below. These consist of a manual procedure that uses a series
- /, of tables and curves, a microcomputer model, and on the Emergency Response '
Information System (ERIS). The microcomputer and ERIS models differ in that ERIS uses real time data;
./ ;
./ 7 l.3.1.1 Methodolog'y - The basic methodology used to calculate the offsite radiological dose and dose rates was developed by and agreed upon by l Edison (Fermi 2), Consumers Power (Big Rock Point and Palisades), and f Michigan & Indiana Electric (Cook) for use in emergency planning. This methodology was presented to and accepted by the State of Michigan's Division of Radiological Health. The model determines the whole-body dose and dose rate due to noble gases and the thyroid dose (and dose rate) to a ' child and adult due to airborne radiolodine. The dose calculations are proportional to the relative downwind concentration of a radioactive release. Dose calculations are a function of l atmospheric stability class, wind speed, and downwind distance from the plant. The present model assumes the plume to be a straight-line Gaussian model. This conservatively assumes that all releases are at ground level and downwind building wake (turbulent mixing) effects have been incorporated. Finite cloud correction factors are also applied. A lake breeze study was conducted at Fermi 2 which resulted in n site specific lake breeze equation. A dose adjustment factor can be calculated and applied to doses and dose rates during lake breeze conditions. The possible existence of a lake breeze is based on the following criteria:
- Date - April 1 to October 31
,t-Time - One hour after sunrise to one hour before
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. . _ -- . . ._ . , _. . , _ . _ - - ~ _ ._.. -_ _ ., ._,
p.; ; , il 2 1 i- ' RERP Plan -l U Revision 1 1 Page1-3 f y .- Wind Direction - Between 570 and 168 0 Stability Class - A, B, or C 1 , l.3.1.1.1 Manual Method - Procedure EP-540 is used when there is a ! j .. potential for a radioactive release to occur or a radioactive : release has occurred. This method is in place for performing l l dose assessment calculations when the computerized models , are unavailable. 1 The options considered are as follows: I-
- t. , 1. Loss-of-coolant (LOCA) Accident based on Containment
[ High Range Radiation Monitor (CHRRM) in Drywell. This option calculates releases to the environment with the standby gas treatment system (SGTS) monitor essentially unavailable. The estimated release to the environment can also be calculated when primary containment integrity is threatened." The model assumes a release to the drywell resulting in a reading on the CHRRM sufficiently above ambient background to warrant action. The CHRRM is located on the outer wsll of the bulbous section of the drywell at elevation 605 feet. It views a portion of a cylindrical annulus cloud of gamma emitters and is not affected by beta radiation. The CHRRM reads in Rad /hr. l l The course of the accident is that of the design basis I. LOCA as described in Regulatory Guide 1.3 and the Fermi 2 UFSAR, Chapter 15. The release to the reactor building t L from the drywell is assumed to be at the technical l specification leak rate (0.5% by weight per day) and I. pressure. The airborne activity is then exhausted ? Immediately through SGTS at 99% filter efficiency for ! l' lodine removal. For the purpose of determining the actual amount of noble gas released to the primary containment,100% of the core inventory of noble gases is instantaneously released to the entire primary containment at reactor shutdown with perfect mixing. For the purpose of determining the actual amount of lodines airborne in the primary containment,2% of the core Inventory of lodines are instantaneously released to the entire primary containment at reactor shutdown with perfect mixing. l ,
~
m; , o, , cn n .I e , 4;; j RERP Plan Revision 1 Page1-4 2.' LOCA based on SGTS Monitor Readingsi ,
~
This option calculates actual releases to the environment based on SGTS monitor readings assuming a design basis ;
.LOCA. The SOTS monitor is located in the standby gas ~ j treatment effluent stream downstream of the lodine filter. )
- 3. Monitored Release Through Building Vent Stacks '
(non-LOCA). Actual releases to the environment are based on the monitor readings SGTS, Reactor building stack Turbine ,, building stack or from the Redweste building stack.- ; Hettever, the accident scenario is not an LOCA, but of some other source.
- 4. Unmonitored Releases Through Building Vent Stacks.
This option assumes that grab sample data, stack flow :) rates, or other information is available to permit one to provide the total radioactivity release rate of noble ces ; (curies /sec) and its corresponding average energy for assessment, S. Anticipated Transient Without Scram (ATWS) (Reactor - Operating). This option assumes a LOCA with the reactor ; operating. 1.3.1.1.2 Microcomputer Model - A software package has been developed.for a microcomputer that is designed to automatically model the more significant accident release scenarios based on manual input to the system. The software ; package was designed to incorporate as many of the features of ERIS as practicable, l; The software package allows the user to determine whole-body i gamma and offslte thyrold doses and dose rates that can result from the altborne release of mixes of noble gases and lodine [ fission products using the following scenarios: L LOCA Fuel Handling Accident Reactor Building Release L - Radwaste Building Release b - Turbine Building Release L Unmonitored Release l' Reactor Operating (ATWS) l L l '. 1 l u
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s RERP Plan Revision .1 - PageI l; , _ lt also provides flexibility in user control over source terms, j release models,' accident parameters, physical data, and . l
, transport and dose parameters. .(
For the above reasons. The microcomputer-based model will be ' used as the " manual" back up for ERIS. This model performs the same calculations as ERIS, but does not have the automatic data acquisition and storage capability or the ability to maintain l a historical record of the dose distribution.
- 1. Software Description -
u4 ., ., in brief, the software package determines a radionuclide i release rate based on the following: E ' LL[ The age of the radionuclide mix f, - Monitor readings The plant parameters pertinent to airborne transport of $n - radionuclides . r, 4 From this, a projection of continued releases is developed
. over the specified dose integration period.
Determination of Radionuclide Release In general, the radionuclide release is based on three .i pieces of in'ormation: (1) an assumed original nuclide mix, (2) a monitor reading, arid (3) knowledge of the decay ,! characteristics of the radionuclides. I
- a. Release Based on the CHRRM Monitor 1
LOCA-type releases can be evaluated on the basis of the CHRRMs. Such modeling assumes a release of , noble gases and lodines to the drywell atmosphere in a release fraction ratio of 50 to 1 (100% to 2%), respectively (based on an equilibrium core). Using this
)
i ratio to represent the potential drywell alrbome mix at l the time of shutdown, the software package calculates l a time decay of the mix to determine the mix of i nuclides at the time of the monitor reading. This, I combined with the monitor reading and the monitor response characteristics, is then used to determine the actual radionuclide inventory of the drywell atmosphere 1 at the time of the monitor reading. ! l
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[, l! M , RERP Plan - Revision '1 . PageI-6 1 The release of these radionuclides to the reactor l c building from the drywell is assumed to be at the ; Technical Specifications leak rate-(0.5% by weight per , day) and pressure, As such, this is a potential release. H The actual leak rate could be higher or lower J depending on containment pressure, integrity of J penetration seals, or any number of other conditions. I l Releases from the primary containment are next assumed to be mixed in the reactor building volume (in l accordance with the specified mixing fraction) and then . , processed through the SGTS. The SGTS has no effect
' on nobles, but is assumed to have a 99% remoal- ,
efficiency for lodines. Those radionuclides passed through to the the environment represent the potential - radionuclide release. i
- b. Releases Based on Effluent Monitor Readings 1
-l Releases that are measured by effluent monitors can be handled much more directly.than those based on <
, CHRRM monitor readings. The type of accident j determines the noble / iodine mix ratio at the time of ;
shutdown. (Source mixes representing LOCA, gap C activity, and primary coolant releases are built in and , available to the user.) Just as in the case of the CHRRM monitor, the chosen redlonuclide mix is ' corrected for decay between the time of shutdown and the time of the monitor reading. This information, . l combined with knowledge of the monitor response characteristics and the release path flow, allows the < radionuclide release rate to be determined.
- c. User input of the Nuclide Mix >
if knowledge of the radionuclide mix and release rates is available from post-accident sample analyses or any other source, it can be entered manually by the user.
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- RERP Plan :
lf " [~ ,( . Revision 1 Paget-7
. 2. User Modification Parameters e
Most model parameters are provided with default. values
- that, in most ct:ses, may be modified by the user.
Among those that can be modified include the following: Meteorology f
- Monitor readings Nuclide analysis e Gamma Shielding Factor Drywell leak rate Bypass leakage fractions -
Reactor building mixing fraction SGTS filter efficiencies , Release path flow rates . ; Monitor range L Monitor response characteristics :i Monitor calibration constants .; Breathing rates Accident duration i Dose Integration times I Distances at which analyses are performed , l.3.1.1.3 ERIS Model - The automated capability of ERIS enhances the flexibility of the dose assessment model. The basic model is described previously in Section 1.3.1.1.2 for the microcomputer, f The stack effluent monitors, the containment high range radiation monitors, and the meteorological computer are >
, ,g hard-wired into the system and, once the basic parameters are selected from the menu, dose projections are automatically updated at 10-minute intervals, stored, and printed on command. Additional features of ERIS include the capability to:
l_ ; l- i L 1. Vary, at a minimum, the parameters listed for the ' microcomputer.
- 2. Enter nuclide analysis from actual sample data, recalculate the previous dose projections based on default values.
( enter the nuclide analysis into the system, and calculate future 10-minute projection using the new analysis. t I 3. Accumulate dose projections from actual releases by sector j , to maintain a record, should the wind direction shift. 1 e
- 4. Display quality codes for hard-wired data.
- 5. Track a segmented meteorological plume.
y, ' * (: y:, RERP Plan i Revision 1 .
.c PageI-8 -
1.3.2 Liquid Releases - The primary method for determining doses from the liquid pathway involves the analysis of a sample for Isotopic content and a calculation using the Offsite - Dose Calculational Manual. l.3.3 Long Term Dose Assessement - For long term analysis, field monitoring data can be , used to calculate the dose to the population. l.4 Field Monitoring Field monitoring within the plume exposure pathway is performed by the Radiological Emergency Teams (RETs). These teams are trained to conduct field surveys, obtain air samples, and collect environmental samples. At the onset of an emergency with
- potential for actual redlological releases in excess of Technical Specifications, RET members can be dispatched to field positions. Each team is provided with air-templing ,
equipment, personnel dosimetry, radiological survey instruments, procedures, and radios * (see Section H). From one to three teams are available and can be dispatched within 30 to 60 minutes of the emergency declaration. i The RETs are deployed in a manner that provides preliminary estimates of plume location and exposure rates. Established sampling and monitoring locations, based on prevailing wind directions, may be utilized. The information collected Is forwarded to the Control Room or to the TSC when it is activated. When activated, the EOF assumes - responsibility for the direction of environmental assessment activities. The EOF laboratory may be used for the receipt and qualitative analysis of all environmental sample media. 'L if necessary, supplemental teams trained in field survey and monitoring techniques can be called out or may be requested through the mutual assistance agreements. They are , also equipped with appropriate monitoring and sampling equipment. The Radiation Protection Coordinator directs the activities of the offsite RETs. Data from , the supplemental field monitoring force is reported to the EOF. ! L : I - l l l l
I t; i a l RERP Plan Revision 1
,," Page J-1 J. PROTECTIVE RESPONSE I l
This Plan Section describes the range of protective actions developed for plant workers I y and the general public within the plume exposure pathway, the 10-mile Emergency l 3 Planning Zone, J.1 Onsite Notification 1 The Protected Area is the zone within the Owner-Controlled Area bounded by the ! Protected Area security fence. The plant itself is located within this zone, in the event j of an emergency situation at Fermi 2, methods are established for notifying personnel J within the Protected Area. These people include the following: )
- Employes not having emergency assignments !
Visitors
- Contractor and construction personnel i Methods are also established for notifying personnel outside the Protected Area yet still In facilities within the Owner-Controlled Area (site boundary). These facilities include ,
the following: ; Visitors' Cer)ter [
- General Training and Orientation Center (GTOC) !
Technical Assistance Center (TAC)
- Nuclear Operations Center (NOC)
Enrico Fermi Unit 1 (Formi 1) l The primary means of notification within the Protected Area is the emergency alarm i system. This systern provides an audible signal that alerts personnel to the existence of [ an emergency event. The following emergency events have specific audible alarm signals: j ,1 - Control Room evacuation - pulse ! Site evacuation - stron [ Fire - yelp ! Tornado - warble
- Plant area - steady i Following the alarm, personnel are advised of the nature of the emergency via the plant intercorn (HICom) system. i Activation of the emergency alarm system and the subsequent announcement is the responsibiluy of the Emergency Director. The activation and the appropriate announcement are performed immediately upon classification of an Alert, Site Area I
Emergency, or General Emergency, if an Unusual Event occurs, notification announcements are performed on a timely basis consistent with the nature of the event. Following activation of the emergen'c y alarm system, all personnel within the ; Protected and Owner-Controlled Areas are notified and advised within 15 minutes of an emergency situation.
i . [
! RERP Plan !
L Revision 1 - l t Page J-2
?- f t
l-All personnel working within the Protected Area (including contractors, vendols, and F. visitors) are either trained in emergency procedures or escorted at all times by an authorized individual. Authorised escorts are trained in emergency procedures and in ; the appropriate steps to be taken by visitors in an emergency, l t An escort is assigned to meet the visitol at the Security Building. Within the Owner-Controlled Area, a visitor is defined as anyone whose work location is not t Fermi 2 Within the Protected Area, a visitor is alyone who has not been issued an ! unescorted access keycard for the Protected Area. l i The Visitors' Center, OTOC, TAC, NOC, and Fermi 1 will be notified by telephone or patrol ! officers of an emergency by Nuclear Security, ; All onsite personnel are classified according to their assigned duties in the event of an f emergency event at Fermi 2. This classification is also used for evacuation, t,hould [ evacuation become necessary Personnel classifications are defined as follows: ! Class 1 ,
- Operations personnel onshift .
- All Radiatior Protection, Chemistry and Medical personnel onsite
- All personnel assigned to an emergency team or emergency facility as defined by l Section B of this plan ;
i
- Nuclear Security personnel on shift l Class 2
- Instrument and Controls (160) Technicians and their Supervisors
- General Maintenance Journeymen (GMJ) and their Supervisors i
Redwaste Personnel Class 3 I
- All other personnel at Forml 2 at the time an emergency is declared or an accountability is initiated; this category includes contractors and visitors, ,
)
9 l
I RERP Plan Revision 1 Page J-3 .! J.2 Evetuation l l A Plant Area Evacuation is defined as the supervised evacuation of all nonessential j personnel from a specific area of the plant to another designated safe area. A Protected 1 Area Evacuation is defined as the supervised evacuation of all nonossential personnel j from the Protected Area. A Site Area Evacuation is defined as the supervised evacuation I of all nonessential personnel from all Owner-Controlled Areas of the site, including but l not limited to the Protected Area, the Visitors' Center, the GTOC, the TAC, Forml 1, and ! the NOC. Evacuated personnel will be directed to assemble at the Newport Service l Center, Monroe Power Plant, Trenton Channel Power Plant or will be sent home. I Figure J-1 identifies the Owner-Controlled Area. The evacuation routes and the relocation and monitoring centers for persons leaving Fermi 2 are shown in Flpure J-2. j The directions of travel and the off-site assembly area (s) (Edl6on's Newport Service ! Center, Monroe Power Plant, and Trenton Channel Power Plant) are determined by the Emergency Director based on the current meteorological and emergency conditions. An announcement will be made over the HiCom system in the Protected Area. The same information will be conveyed by telephone to the Visitors' Center, OTOC, TAC, NOC, and i Fermi 1. Nuclear Security is responsible for traffic direction and control of persons i leaving Fermi 2, including special provisions for a coordinated evacuation under severe ] conditions such as inclement weather, large groups of personnel to be evacuated, or e i high level redloactive release. Assembly, accountability, and evacuation are conducted , in accordance With established procedures. J.2.1 Monitorino end Decontamination - in the event of a Sits Area Evacuation, all ; nonessential personnel exiting the Protected Area are monitored for contamination by passing through passive portal radiation monitors. Personnel in the Visitors' Center, the i j, GTOC, the TAC, the NOC, and Fermi 1 are directed to offsite assembly areas and r monitored,if emergency conditions warrant, by Individuals trained in the operation of l personnel monitoring equipment. Vehicles are monitored, as necessary, depending on the amount and direction of the radioactivity released. Facilities will be available at the offsite assembly areas should it be necessa 'y to i decontaminate Individuals and/or vehicles. Decontamination equipment is listed in POM j Procedure 67.000.405. Personnel monitoring and decontamination is perforn ed in ; I accordance with POM Procedure 67.000.400. Vehicle monitoring and decontamination is performed in accordar.cc with EP-220. J.2.2 Accountability - As individuals exit the Protected Area, they leave their identification i padges with the Nuclear Security personnel. Nuclear Security will account for each l l person inside the Protected Area, using either the security computer system or by visual ; I inspection using the badge exchange system. Eithcr method provides for accountability ' I of all individuals within 30 minutes of the start of an asc3mbly and accountability and , continuously thereafter for all individuals remaining within the protected area, i t I o _ _ _ . _ . . _ _ _ . - _ , . _ _ .._ _ _ . . . _ _ _ _ . _ . _ . _ ~ . _ _ _ - . . _ . . . - . . - - . _ _ . , . -
i RERP Plan ! Revision 1 l Page J-4 ; i The accountability of tour groups is the responsibility of the guides who are escorting i each group. Persons leaving the NOC, TAC, and Fermi 1 are eccounted for by their work ! supervisors. Assembled groups report to the senior person at ear.h assembly area. ! t i J.3 Reallation Protection Equipment Adequate supplies of radiation protection equipment including protective clothing are i maintained for persons remaining in or entering the Protected A.rea or the Eme#gency : Response Facil! ties. This emergency equipment is listed, maintained, and inspected in ! occordance with with POM Procedure 67.000.405. l The Medical Department maintains adequate amounts of potassium lodido (KI) to support : the Onsite Emergency Response Organization for emergency situations at Fermi 2. The ' Emergency Director is responsible for requesting authortration for the distribution and i use of Kl from the Edison Medical Director. Protective clothing and respiratory l protection equipment are used as directed by the Emergency Director (or delegate). J.4 Protective Actions . In a radiological emergency, an estimate must be made of the radiation dose that effected population groups may potentially receive. A protective action is taken to avoid or reduce the effects of this projected radiation dose. The Protective Action Guideline , (PAO) is a predetermined level of projected dose to individuals in the population at ; which protective actions are warranted. Procedures are in place for use in recommending protective actions to State and local 5 offsite emergency response agencies. Prompt notification of protective action - recommendations at Fermi 2 is made to State and local agencies. The Nuclear Regulatory Commission is informed of these recommendations. ; The implementation of any protective action recommendation taken offsite to protect the health and safety of the general public Is the responsil;ility of the State of Michigan in conjunction with local emergency response agencies. The Michigan Emergency Preparedness Plan, the Monroe and Wayne Counties Emergency Operations Plans describe the provisions to implement protective measures for the plume exposure pathway EPZ for State and local emergency i response personnel and the public. Provisions include the following: Maps showing evacuation routes, evacuation areas, congregate care centers, and shelter areas j - Maps showing the population distribution around the nuclear facility , l l
-l REP.P Plan I 'i Revision 1 !
Page J-5 l Methods for notifying all segments of the transient and resident population l Means for protecting handicapped, institutionallred, or confined individuals whoto mobility may be impaired Methods for registering and monitoring evacuees at reception centers ! Means of relocation, including reception centers, access control, and evacuation routes and methods l Methods for protecting the public from consumption of contaminated foodstuffs ' l l J.4.1 Basis for Recommending Protective Actions - The Manuel of Protective Action Guides j and Protective Actions for Nuclear incidents (EPA 520/1-75-001) and NUREG-0654 are
=
used as the basis for recommendations for protective actions for the offsite public. ; Protective action recommandations are also consistent with the guidance of the U.S. Food and Drug Administration concerning accidental contamination of human food and : animal feed, published in the Federal Register, Volume 43, Number 242 December 15, ! 1978. . l Tables J-1 and J-2 provide the technical basis for protective action recommendations to i State and local egencies during an emergency. As a further aid in determining l appropriate protective actions, Tables J-3 and J-4 contain representative shielding factors provided by typical structures against direct exposure from the plume. J.4.2 Evacuation Time Estimates - When evacuation is being considered, the time required to implement the evacuation is an important factor in reaching a protective action recommendation. Evacuation time estimates in the plume exposure EPZ are contained in a separate study
- Estimate of Evacuation Times,' revised May,1985. This study was performed for Edison by PRC Engineering, McLean, Virginia. The evacuation time estimate study includes considerations for periods of peak traffic congestion, adverse weather conditions, and the evacuation of institutionallred population.
J.4.3 Population Distribution - The 10-mile and 50-mile EPZs are shown in Figures A-1 and A-2. The population distribution around Fermi 2 is given in Table J-5 and identified by sector in Figure J-3. J.4.4 Offsite Monitoring - The locations of the offsite environmental monitoring stations are shown in Table H-8.
hr(- RERP Plan Revision 1 Page J-6 TABLE J-1: OUlDELINES FOR PROTECTION AGAINST INOESTION OF (a) <: CONTAMINATION FOR THE PUBLIC
- l. Oreund Contemination A. Action Levels
- 1. Projected whole-body dose above the ground 11 rom.
- 2. Exposure rate 112 mR/hr at 1 meter above ground at t = 1 hour post-accident,
, B. Recommended Protective Actions
- 1. Evacuathn of affected areas.
- 2. Restriction of entry to contaminated offsite areas until radiation level has decreased to state-approved levels.
II. Food and Water Contamination A. Action Levels Concentration in Milk or Water 0.5 rom 5 rem Whole body Whole body or bone; or bone; Total intake via 1.5 rem . 15 rom all Food and Pasture Grass thyroid thyroid Water Pathways (Fresh Wolght) Preventive Emergency Preventive Emergency Preventive Emergency Level Level Level Level Level Level Nuclide (b) (uCl/1) (uCl/1) (uCl) (uCl) (uCl/kg) (uCl/kg) i 1-131 (thyroid) 0.012 0.12 0.09 0.9 0.27 2.7 Cs-137 (whole body) 0.34 3.4 7.0 70.0 3.5 35.0 Sr-90 (bone) 0.007 0.08 0.2 2.0 0.7 7.0 l Sr-89 (bone) 0.13 1.3 2.6 26.0 13.0 130.0 B. Recommended Protective Actions Preventive Emergency
- Removal of lactating dairy isolate food and water from its cows from contaminated introduction into commerce after pasture and substitution of considering:
uncontaminated stored feed, s. Availability of other possible Substitute source of actions; uncontaminated water. b. Importance of particular food Withhold contaminated milk in water, nutrition; , from market to allow c. Time and effort to take action; I radioactive decay, d. Availability of other foods.
- Divert fluid milk to production l of dry whole milk, butter, etc.
(a)
Reference:
U.S. Food and Drug Administration, Federal Register, Vol 43, No. 242, December 15,1978. (b) If other nuclides are present, use Regulatory Guide 1.109 to calculate the dose to the critical organ (s). Infants are the critical segment of the population. 1 i
l RERP Plan Revision 1 l Page J-7 i TABLE J-2:
SUMMARY
OF POSSIBLE OFFSITE PROTECTIVE ACTIONS TO BE RECOMMENDED OR IMPLEMENTED DURING AN EMERGENCY (a) i Accident Exposure Examples of Actions Phase Pathway . to be Recommended i inhalation of gas ,s, Evacuation, shelter, access control, EMERGENCY radiolodine, or respiratory protection, prophylaxis l PHASE (b) paniculate. (thyroid protection). (0.5 to 30 hours) (c) ! Direct whole-body Evacuation, shelter, access control, l exposure. ; l Ingestion of milk. Taks cows off pasture, provsnt cown from drinking surface water, discord contaminated milk, or divert to stored products such as cheese. l Ingestion of fruits Wash att produce, or impound produce, INTERMEDIATE and vegetables. dolay harvest until approved, J PHASE (d) substitute uncontaminated produce. (30 hours ; to 30 days)(c) ingestion of water. Cut off contaminated supplies, substitute from other sources, filter, domineralize. Whole-body expost?:a Relocation, decontamination, and inhalation. access control. Ingestion of food and Decontamination, condemnation, or LONG-TERM water contaminated destruction of food; deep plowing, PHASE (e) from the soit either condemnation, or alternate use of land. (over 30 by resuspension or days) (c) uptake through roots. Whole-body exposure Relocation, access control, from deposition of decontamination, fixing of material or Inhalation contamination, deep plowing. or resuspended material. (a)
Reference:
U.S. Environmental Protection Agency,
- Manual of Protective Action Guides and i Protective Actions for Nuclear incidents,* 1975.
(b) Emergency Phase - Time period of major release and subsequent plume exposure. (c) " Typical" post-accident time periods. (d) Intermediate Phase - Time period of moderate continuous releases with plume evnosure and contamination of environment. (e) Long-Terrn Phase - Recovery period.
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i, 1 RERP Plan l Revision 1 ! Page J-8 l TABLE J-3: REPRESENTATIVE SHIELOlNG FACTORS FROM GAMMA CLOUD SOURCE (a) ; l Representative i Structure or Location $hleidine Factor (b) Representative Ran00 _ { Outside 1.0 -- Vehicles 1.0 -- l Woodframe house (c) 0.0 -- i
,. (no basement) '
l Basement of wood house 0.6 0.1 to 0.7 (d) j Masonry house (no basement) 0.6 0.4 to 0.7 (d) Basement of masonry hour.o 0.4 0.1 to 0.5 (d) l t Large office or industrial 0.2 0.1 to 0.3 (d.e) building ', (a) Taken from SAND 77-1725 (Unlimited Release) [ (b) The ratio of the dose received inside the structure to the dose that would he received outside ! the structure. ! (c) A Wood-frame house with brick or stone veneer is approximately equivalent to a masonry I house for shielding purposes. (d) This range is mainly due to different wall materials and different geometries. (e) The shielding factor depends on where the personnel are located within the building (for ! example, the basement or an inside room). ! e r { i
y RER) Plan t Revision 1 Page J-9 TABLE J-4: REPRESENTATfVE SHIELDING FACTORS FOR GURFACE DEPOSITED RADIONUCLlDES (a) Representative Structure or Location Shielding Factor (b) Representative RanDe 1 m above an infin6te smooth 1.00 -- surface 4 1 m above ordinary ground 0.70 0.47-0.85 1 m above conter of 50 ft roadways, 0.55 0.4-0.6 50% decontaminated Cars on 50 ft roed: Road fully contaminated 0.5 0.4-0.7 Road 50% decontaminated 0.5 0.4-0.6 i Road fully decontaminated 0.25 0.2-0.5 ;
, Trains 0.40 0.3-0.5 I L
One and two story wood frame house 0.4(c) 0.2-0.5 l' (no basement) - One and two story b!cck and brick 0.2(c) 0.40-0.40 , house (no basement) ; i House basement, one or two walls 0.1(c) 0.03-0.15 l fully axposed: ! One story, less than 2 ft of 0.05 (c) 0.03-0.07 l basement, walls exposed Two stories,less than 2 ft of 0.03 (c) 0.02-0.05 basement, walls exposed i Three or four story structures, ' 5000 to 10,000 ft2 par floor: 0.01-0.08 d First and second floors 0.05 (c) Basement 0.01 (c) 0.001-0.07 Muglstory structures, >10,000 ft per floor: , Upper floors 0.001-0.02 0.01 (c) Basement 0.005 (c) 0.001-0.015 (a) Tanen from SAND 77-1725 (Unlimited Release) (b) The ratio of dose received inside the structure to the dose that would be received outside the
. structure (c) Away from doors and windows l
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I CERP Plan Revision 1 Ps9e J-10 TABLE J-5: DISTRIBUTION OF 1980 POPULATION IN EMEROENCY PLANNING 20NE RINGS AND SECTORS, MONROE AND WAYNE COUNTIES, M6CHIGAN ! Cir Rino tone-mile) l 1 2 3 4 5 6 7 8 9 10 Total l N 29 286 179 80 199 233 884 4,341 4,350 5,288 15.849 i NNE O 103 12 92 82 382 1,205 1,322 956 3.845 7,999 ( NE O 264 134 12 0 0 0 -- -- -- 410 l ENE O -- -- -- -- -- -- -- -- -- 0 E O -- -- -- -- -- -- -- -- -- 0 ! ESE O -- -- -- -- -- -- -- -- -- 0 SE 0 -- -- -- -- -- -- -- -- -- 0 SSE O -- -- -- -- -- -- -- -- -- 0 8 42 586 52 -- -- -- -- -- -- -- 680 l SSW 0 723 21 -- -- -- -- -- -- -- 744 f SW 0 212 9 -- 119 0 0 0 66 887 1,293 WSW 0 25 861 2,276 1,811 997 4,483 9,444 13 971 6,198 40,066 : W 0 59 30 168 611 992 990 1,197 690 696 5,439 i WNW0 18 32 53 111 1,958 482 191 610 623 4,087 f NW 3 77 359 651 324 259 505 371 601 3,295 6.445 r NNW 0 143 247 65 78 224 653 596 681 515 3,202 f Total 74 2,476 1,936 3,397 3,335 5,045 9,208 17.462 21,934 21,347 86,214 t t t t 6 s 1 j
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t RERP Plan Revision 1 f Page K-1 i i K. RAD 60 LOGICAL EXPOSURE CONTROL ; This Plan Section describes the means for controlling radiation exposure for emergency workers at Fermi 2. l K.i Exposure ouw.iines l in an emergency situation, all reasonable measures will be taken to maintain the i radiation exposure of emergency personnel providing rescue, first ald, decontamination, i ambulance, medical treatment services, or performing corrective or assessment actions l within oppilcable limits specified in 10 CFR 20. ! The Emergency Director will evaluate any emergency response exposures in excess of f 10 CFR 20 limits. The Emergency Director is responsible for authorizing voluntary j emergency perbonnel to exceed the 10 CFR 20 dose limits, if deemed necessary. The ; Emergency Director will consult with Radiation Protection personnel to the greatest , extent possible before granting thib authorization. Table K-1 contains the basis for emergency exposure criteria. The guldelines for these exposures are consistent with EPA Emergency V<orker and Life Saving Activity Protective Action Guides (EPA 520/1-75/001).
.j K.1.1 Control of Personnel Radiation Exposure - Every reasonable effort will be made to T ensure that during an emergency no worker exceeds the exposure limits stater in Table :
K-1. Emergency response personnel who must enter radiation areas where they might be ; expected to receive higher than normal doses will be fully briefed regarding their duties ! and expncted actions, expected dose rates, stay time and other harards, All such individusts will be adequately trained in appropriate Radiation Protection procedures. ! Personnel will use respiratory protective devices (if required) in accordance with RPC-05. _ i When recommended by the Detroit Edison Medical Director or delegate, the l administration of radioprotective drugs such as potassium lodido (KI) may mitigate the 1 consequences of the inhalation of radiolodines. Section J discusses the authorization and administration of Kl to Edison end contract personnel. e I t e
- , - - - , , - ,,----.,.,nn, , , _.-. ,,, , ,- - - - - , - - - , , ,,, -,. , - - ,,--n- , , --~ - , y - ---,,-.,-e-- -- ,, , - - , - ,
{ i RERP Plan i Revision 1 [ Page K-2 I K.2 Dee6 metry j in an emergency, dosimetry service for all emergency personnel will be provided on a [; 24-hour basis. As a minimum, personnel are issued a self-reading pocket dosimeter
- and a thermoluminescent dosimeter (TLD) badge. These personnel monitoring devices are issued at the Radiation P'.otection access coritrol station, or en alternate designated !
area. Dosimetry records consisting of each person's (1) name,(2) social security I number, (3) dosimetry number, (4) time entering redletion area, (6) time leaving area, (6) total time spent in the area, (7) initial dosimeter reading, (8) final dosimeter reading, and l (9) total exposure are maintained in accordance with FlP-RCI-01 The recorded ! exposures are e.raluated and maintained by the site Radiation Protection group to assure t that personnel de not exceed the dose limits of 10 CFR 20, except as authorised by the Emergency Director, ; i Offsite emergency response groups who enter the Protected Area (that is ambulance j teams, medical support personnel, local fire department personnel, Offsite RET, etc) will ! be issued dosimeters. ! The type and number of self-reading dosimeters issued (that is 0-200 mR range,0-1 R range, etc) will depend upon the anticipated dose rate levels and the approximate time ; needed to complete specific activities. The distributio'h use, and reading of TLDs and pocket dosimeters in both routine and I emergency ci.reditions are described in POM Procedure 67.000.403 and 65.000.200, j t Pocket dosinnters are zerood prior to use and monitored at established intervals as required by toe above procedure or as directed by Radiation Protection personnel. Each l l individual is responsible for reading his/her own pocket dosimeter and recording the ! dose. Dosimeter readings are recorded upon entering and leaving high radiation areas, i as well as at the Radiation Protection access control point or a designated alternate ! area. j Personnel exp isuros, as determined from pocket dosimeters, are totaled and evaluated at least daily by Radiation Protection personnel. Radiation Protection personnel will also ! predetermine, as necessary, exposure values at which personnel should leave redletion l areas and have their TI.D processed to prevent personnel from exceeding emergency ; exposure limits. , in instances where the extremity dose may pose a greater hatard than the whole-body l exposure, personnel are issued extremity dosimetsrs, such as TLD ring badges. A permanent record of radiation exposure is provided by the TLD. The TLDs are read I promptly by quellflod Radiation Protection personncl using equipment located in the l l Radiation Protection offices. j l 1 I I l
f l RERP Plan Revision 1 ! Page K-3 ! L K.3 Decentamination Criteria l { Personnel contamlaation is minimlred to the greatest extent feasible by following j established Radiation Protection practices and procedures. These include the proper use l t and removal of protective equipment and clothing, followed by personnel contamination f surveys. Any transferable contamination that is above background requires t decontamination. Facilities for onsite personnel decontamination are available in the ; Radweste Building and include provisions such as decontamination supplies, spare i clothing, and contamination survey instrumentation. ; i K.4 Contamination Control Contaminated areas will be designated and clearly identified to minimize personnel ; contamination or the spread of contamination in the plant. Accobs to these areas is controlled and personnel will take the required precautionary measures and use the tppropriate protective clothing and equipment. Prior to being released for general uss, ' contaminated areas are decontaminated in accordance with Redweste Decontamination Procedures. Personnellaeving contaminated areas are monitored to ensure that they or their clothing are not contaminated. The Radiation Protection access contrc,1 point and l : the primary and alternate access portals are provided with portal monitors and l l personnel friskers to prevent the spread of loose surface contamination outside the j protected area. q in the event that personnel become contaminated, they are decontaminated in ! l accordance with established procedures, if normal decontamination procedures do not [ [ reduce contamination to acceptable levels, the case will be referred to a Medical ; Depertment representative. Extra clothing is available for the toplacement of . contaminated personal clothing at the decontamination facilities. ; i
- Because of the possibility of the presence of radiolodine during emergency situations, '
particular attention is focused on searching for skin contamination when monitoring '- personnel during evacuation. Personnel found to be contaminated are directed to the onsite or offsite decontamination facility as appropriate. i Depending on the nature of an injury and the amount and location of contamination, contaminated injured personnel are either treated at Fermi 2 or transported to Seaway ; or Mercy-Memorial Hospital for treatment. The treatment of contaminated injured t personnel is described in Section L All equipment and tools are checked for contamination before being removed from a . known contaminated area. If tools or equipment are contaminated, they will be ' decontaminated in accordance with Redweste Decontamination Procedures. , l l
l ' i : i ! I RI:RP Plan Revision 1 , f Page K-A ! Contaminated waste resulting from pctsonnel decontamination and contaminated I material that cannot be decontaminated or Ut;lited as controlled contaminated equipment are handled in accordance with Redweste Decontamination Procedures. l Drinking water and food supplies are not allowed into contaminatud or potentially ! contaminated areas, if a potential for contamination or contamination is discovered in , an area already containing drinking water or food, the food and water are surveyed to . ensure that they are not contaminated if contamination is discovered, appropriate ! actions will be taken based on the level and location of the contamination. la general, contaminated areas and materials are permitted to be returned to normal vse [ when there is no detectable radiation above the normal background levels. However, : some areas and equipment may have to be returned to use above these limits in such cases, special precautions and measures are taken to prevent personnel contamination , and to limit the spread of contamination. These precautions, which rney include using ; protective clothing or covering the contaminated items or area, f i 6 h
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, . . . . . _ _ . _ , _ _ .-c .-
RERP Plan
. Revision 1 Page K-5 TABLE K-1: EMERGENCY EXPOSUNE CRITERIA 1
Planned exposure to the whole body and/or specific organs shall not exceed the following: j Protective or Lifesevin, ! Corrective Actions Actions ! I o,.an Eme,.eney wo,be,a Eme,,ency wo,be,. ; Whole Body (I) 25 rem 75 rem I Hands Si Forearms (2) 100 rem 300 rem (including whole- l body exposures) ThyroldIII 125 rem (3) (1) Limits are based on the recommendations of the Environmental Protection Agency in ! EPA-520/1-75-001. (2) Limits are based on the recommendations of the National Council on Radiation Protection 3 and Measurements in NCRP-39. ; (3) No limit is specifle'd for lifesaving actions since the complete loss of the thyroid may be ! considered an acceptable risk for saving a life. llowever, thyrold exposure should be i minimized by the use of protective agents or respirators if available, j Additional General Criteria j
- All reasonable means for keeping personnel emergency exposures as low as reasonably f achievable within 10 CFR 20 limits shall be expended before exposures exceeding 10 CFR 20 limits are permitted.
- All reesc,nable measures shall be taken to minimize skin contamination and the intake of radioactive materials. [
t
- All personnel performing emergency activities involving exposures which may exceed 10 CFR 20 limits shall be volunteers and shall be briefed on potential exposure '
consequences prior to receiving suct. exposure.
- Previous exposure history shall be evaluated on an Individual case basis.
( l l I l l
t D i RERP Plan ! Revision 1 l Page I.-1 l, L h4EDICAL SUPPORT l This Plan Section describes the arrangements made for medical ssrvices for ; contaminated injured personnel. j i L1 Offsite Support i L1.1 Hospitels - Arrangementh have been made for medical treatment of Fermi 2 personnel ! who may have injuries complicated by the presence of radioective contamination and/or :' overexposure to radiation. The primary treatment facility is the Seaway Hospital, Trenton, Michigan, located approximately 12 miles from the plant, A back-up medical ! facility is established at Mercy-Memorial Hospital in Monroe, Michigan. l Seaway and Mercy-Memorial Hospital are adequately supplied and equipped to receive l and treat contaminated patients. Detroit Edison maintains emergency cabinets j i containing contamination control supplies and dosimeters at both hospitals. ; L1.2 Serv 6ces - In addition, Detroit Edison will co-ordinate medical amorgency activities and l ensure that the following are provided; ; Immediate telephone consultation for the hospital staff and/or Fermi 2 personnel j with respect to evaluation and treatment of Individuals involved in a redlological medical emergency A radiation emergency medical team to assist in the implementation of the , emergency medical plan, it required Written procedures that implement an emergency medical plan for the treatment of radiation-related injuries ! I Written procedures regarding radiological medical emergencies detalling actions to be taken onsite {
- Written procedures regarding radiological medical emergencies detalling actions to be taken onsite for offsite transportation of injured / contaminated Individuals and :
l hospital notifications i .
- Recommendations regarding facilities, equipment, and supplies required for effective implementation of the emergency medical plan 1
- Annual training of plant, ambulance, and hospital personnel who have emergency
, medical responsibilities ; l - An annual emergency medical drill providing immediate evaluation ind critique of the results
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a p e-f RERP Plan l
, Revision 1 '
Page L-2 ] l I Backup radio-bloessay laboratory services for the evaluation of body burdens and j exposure consequence ,
- Arrangements, as required, for the medical evaluation and/or treatment of l radiological casualties at a definitive care center for speciallred treatment I
L2 Onsite First Aid Cepobility j A Reglstered Nurse is usually onsite during normal working hours 5 days a week. In l addition, et least two persons quellflod in first aid methods equivalent to Red Cross i t multi-media training will be onsite at all times. First aid to injured personnel can ! normally be performed in conjunction with any needed decontamination. However, if ! Immediate treatment of the injury is vital, medical treatment takes precedence over [ decontamination ettorts, This philosophy also extends to offsite emergency care ; involving radioactive contamination. L3 Transportation Arrangements , i Contractual arrangements have been made with EMTS Ambulance Service for the t transportation of patients from Fermi 2 who may have injuries complicated by the ; presence of radioactive contamination or who niay have exceeded personnel exposure y limits. ; l i i e [ i l l l l l s
l RERP Plan ! Revision 1 l Page M-1 l i M. REENTRY AND RECOVERY PLANNING AND POST-ACCIDENT OPERATIONS PLANNING During an emergency,immediate action is directed toward limiting the consequences of the incident in a manner that gives maximum protection to the plant personnel and the i general public. Once the situation is under control, the emergency actions shift into the ; Recovery phase. Recovery Actions shall be planned and deliberate. ; i M1 Reentry and Recovery ! t The actual magnitude of an emergency event will dictate the extent of personnel ! Involvement in the recovery operations. i a a. For events of a minor nature, the normal on-shift organization should be adequate ; to perform recovery actions (Unusual Event classifications), !
- b. For events involving significant damage to plant systems required to maintain operation of the plant, the onsite emergency organization should be adequate to ,
coordinate the necessary recovery actions (Alert classifications). *
- c. For events involving damage to plant systems required to maintain safe shutdown '
of the reactor, the complete recovery orgenlration should be adequate to manage . the necessary recovery actions (Site Area or General Emergency classifications). 'a The Emergency Director has the responsibility for implementing this procedure if the emer06ncy classificatioiis at the Unusual Event or Alert level. The Emergency Officer has the responsibility for authorizing recovery operations for : events classified as a Site Area or General Emergency. The Vice President, Nuclear Operations has the overall responsibility as Recovery Manager to coordinate and manage all recovery operations. t
I RERP Plen , r Revision 1 1 Page M-2 j Once the Emergency Officer has determineI that the site area or general emergency j event has terminated or is stable, the Vice President, Nuclear Operations (or alternate) becomes the Recovery Manager and activres the Recovery Organization. The Recovery Manager will order a meeting of the Recovery Organlaation. All recovery actions are ; developed via evaluation of plant conditions and data acquired throughout the emergency. All planned actions and recommendations to reduce protectivw action , measures will be thoroughly reviewed to minimlre radiation exposure or other hazards ; to recovery personnel and the public. The Recovery Organization will develop, coordinate, and expedite plans and schedules for the recovery operations. The Nuclear ' Safety Review Group (NSRG) will oversee the activities of this team to ensure that all nuclear safety aspects of the recovery operations are satisfied. 4 The following are typical criteria for declaring an emergency event terminated:
- Radiation levels in all inplant areas are stable and are decreasing with time. - The reactor is in a shutdown condition with adequate core cooling available.
The release of radioactive materials to the environment is within Technical Specifications and the potential for additional uncontrolled releases is minimal. Fire, flooding, or similar emergency conditions which do not effect reactor operation
.are under control or have ceased.
The Recovery plans, from a practical standpoint, must be flexible enough to meet the needs of the existing event, rather than thecretical conditions, it is not possible to anticipate in advance all the conditions that may be encountered in an emergency situation. The Recovery plans will be developed by Detroit Edison and coordinated with federal and local governmental officials. The following actions will be taken, as required, prior to authorizing reentry into the plant:
- Review available radiation surveillance data and determine plant areas potentially affected by radiation and/or contamination. - Review radiation exposures of personnel required to participate in the recovery operations and determine the need for additional personnel as well as the source of these additional personnel. - Review the adequacy of radiation survey Instrumentation and equipment (for example, types, ranges, number, calibration, etc.)
l 1 i 1
'l RERP Plan l Revision 1 !
Page M-3
- - Plan survey team activities to include: 3
- Areas to be surveyed I
- Radiation and contamination levels anticipated i Radiation survey equipment required J Shielding requirements and availability Protective clothing and equipment required ?
Access control procedures l Issuance of riew Radiation Work Permit ! Exposure control limits and personnel dosimetry required I
- Decontamination requirements j
- Communication equipment required j The initial reentry into the plant areas should encompass the following activities with task priority determined by the Recovery Manager:
- Determine the initial required recovery operations.
- Observe (visual) hazards or potential hazards associated with the recovery operations.
Make a comprehensive radiation surveillance of plant facilities and define l radiological problem areas. .
- Isolate hazardous areas of the plant by using appropriate warning signs and rope i barriers.
Revise security access lists to prevent unauthorized or inadvertent entry into i hazardous areas. , The Recovery Operation, as defined herein, involves assessing equipment damage; , Installing shielding, rope barriers and signs and tags; and decontaminating and cleaning ; as necessary to place the plant in acceptable, long-term stable condition. Recovery : operations will not be initiated until the eres(s) affected by the emergency has been defined. Particular attention will be directed toward isolating components and systems as required to control or minimize the hazards. A systematic investigation will bs conducted to determine what equipment has been damaged and the extent of the ' damage. Recovery operations can be terminated when the plant has been returned to . l pre-accident levels of radiation and contamination, a condition which is acceptable and controllable for an extended period of time or to normal operating condition. l l M.2 Recovery Organlaation i i The Recovery Organization is shown in Figure M-1. The organization is based on the orgsnization and functions recommended by the Atomic Industrial Forum Nuclear Power
- Plant Emergency Response Plan. Recovery Organization functions are briefly described l
below:
J i
> '> RERP Plan j Revision 1 Page M-4 l l
l
. Recovery Manager (Vice President, Nuclear Operations or Alternate) j l
- ' Determines and declares when a stable condition exists and when the plant is ready !
to begin reentry and recovery.
- Authorizes funds and the utillration of manpower and equipment necessary to )
accomplish the recovery operation. l t Notifies offsite authorities, in a timely manner, that a recovery operation will be i initiated and indicates any expected or potential offsite impact.
- Authorizes offsite notification whenever recovery operations have potential offsite i effects. j Nuclear Product;on Curdinator (Plant Manager or Alternate) 1
- Authorizes the start of plant reentry activities.
- Prepares an af.d,T.. >f the circumstances leading up to and resulting from the f emergt:ncy, together with recommendations to prevent a recurrence, j
- Ensures that As Low As Reasonably Achievable (ALARA) concerns are addressed in i Recovery-related operations activities. ;
i
- !Asintains the plant during the recovery operation.
- Develops implementing and operating procedures to support recovery efforts, t
i
- Assures that plant personnel are trained in recovery-related operating and maintenance procedures.
- Develops post-accident plans and procedures for obtaining solid, liquid, and gaseous !
samples as required.
- Implements recovery plans and schedules. !
Implements offsite and onsite radiation monitoring programs.
- Authorizes the return to normal operations when approved by the NRC. l Offsite Activities Coordinator (Manager, Wayne-Monroe Division or Alternate)
- Provides recovery information to offsite officials, s
Coordinates offsite activities with onsite activities. _ . . , , , _ . , . . ~ . _ . , ._m. , . _ _. . .. _.. ,. _ .,, _ . ,. .., ,, _ _ . , -m. ... . , , , < - . - . . . _ . ,
r ' E l RERP Plan l Revision 1 1 Page M-5 ) l Nuclear Safety Review Group Coordinator (f6SRG Chaltperson or Alternate)
- Ensures that all nuclear safety aspects of the reentry and recovery operation are 'i
, satisf6ed by calling upon the NSRO to review the various recovery organlaation activities. ! i
- Analyres at d develops input pertinent to plant licensing issues. ;
t
- Provides expsrtise to support offsite radiation monitoring programs and activities. !
I Technical and Engineering Support Coordinator (General Director, Nuclear . Engineering or Alternate) : i
- Develops post-accident engineering procedures necessary to maintain a safe reactor l shutdown. j Coordinates activities with Plant Operations group. ,
- Assures that ALARA concerns are addressed in Recovery-related engineering i activities, ,
l
- Coordinates A/E or consultant activities if required. >
- Advises on plant and engineering technical matters, j
- Coordinates the design activities that support recovery activities. l Analyzes and develops solutions for instrumentation difficulties and the functions l controlled by those instruments. ;
I Quality Assurance Coordinator (General Director Nuclear Quality Assurance and Plant > Safety) ;
- Ensures that quality assurance requirements are met in all aspects of the recovery operations.
Administration and Planning Support Coordinator (Director, Nuclear Services or : Alternate)
- Provices administrative and clerical support for the recovery operation, t
- Establishes schedules and priorities that ensure an orderly and progressive work flow. ,
Tracks and expedites vendor contracts, corporate and govermental commitments. ! i _ - ,- , . _ . . , , . . . . _ _ . _ - m.__ .. , __ _ , , - , . ,_ ___ -
_ - ~ _ ._ . . _ _ __ it RERP Plan , I' Revision 1 Pace M-6 i I Public information Coordinator (Director, Public Information er Altenate) i i Disseminates information about the recovery operation to the media. J l Outage Management Coordinator-(Superintendent, Maintenance and Modif! cation or l Alternate) I 1 Coordinates outage act!vities with Engineering, Production, and construction activities. l Provides input in determining outage activity priorities. ? Nuclear Security Coordinator (Director, Nuclear Security or Alternate) l Coordinates security activities such as personnel accountability and site access control ~ Secretary Documents Recovery meetings including list of meeting (s), participants, action items, i status reports, etc. Coordinates all information for dissemination to the appropriate recipients. M.3 Recovery Operations Notification it is the responsibility of the Recovery Manager to notify corporate and offsite authorities, in a timely manner, that a recovery operation is initiated. Additional , notifications will be made whenev6r the operation may have potential offsite effects. l. l- M.4 - Population Exousura F tatuation l' . . Dose Assessment personnel in the EOF will continue to cooperete with state and federal ; agencies and periodically update total population exposure estimates. In the event a E release of radiosctive material is planned, the anticipated offsite dose will be calculated, j including an estirr. ate of the total population dose. p M.S Recovery Organization Composition it is not intended that the Recovery Organization be limited to only those persons / functions identified in Figure M-1. As specific emergency circumstances l' dictate, additional expertise will be called upon to participate in the Recovery ll ' Organization. l L 1 L m
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, Revision 1 i FERMI 2 Pg M4 ,
p RECOVERY ORGANIZATION l R% u.n.g.r
- NSRG or Alternate i m m e . .. e ,
t Secstary i Technical and Nuclear Production 7netor ouaW Assumnos Public Information Nuclear Safety coordinaw coordinaw coordinator Roew Group General Director Director, Nuclear - Plant Manager Nuclear Supervisor ' QualW Nuclear Safety Engineering & Nuclear g ,,,, Review Group Services information Chairperson
' offsite Activities PNi$nuYph Management Nuclear Securtty coordinator coordinaw inaw coordinaw '
Manager Wayne /Mortroe Director, Superintendent, Director, Division Nuclear Maintenance and Nuclear Services Modifications Security l; p Figure M 1 RECOVERY ORGANIZATION 1 . i: 1 1' l l l
i. T ' j , 1 i l RERP Plan is 4 Revision 1 [lpr Page N-1
. N. EXERCISES AND DRILLS l This Plan Section describes the program of exercises and drills conducted to develop 1 L. and maintain emergency response preparedness skills and to evaluate emergency I response preparedness capabilities, l l
N.1 Exercise Requirements 1 An exercise is an event that tests the integrated capability of a maior portion of the l basic elements existing within emergency response preparedness plans and organizations. An exercise simulates an emergency that results in offsite radiological , releases and would require response by offsite authorities. Exercises mobilize personnel and resources enough to adequately verify the capability to r6spond to an accident 4 scenario. ; The utility is required to exercise the emergency plan annually according to 10 CFR 50, Appendix E. Section F. State and local agencies will participate at the frequency ' specified by 44 CFR 350, unless they choose to participate more often. Exercises are critiqued annually by Federal and/or State observers and licensee evaluators. I N.2 Drill Requirements A drill is a supervised event aimed at evaluating, developing, and maintaining skills in a , particular operation. Drills are supervised and evaluated by evaluators / controllers who are knowledgeable in their area of observation and/or have attended a pre-drill briefing. ' As a minimum, the following drills will be conducted. , N.2.1 Communications ;
- Communication equipment between the Fermi 2 Emergency Response Facilities (Control Room, Technical Support Center and Emergency Operations Facility),
Michigan State Police, the Monroe County Sheriff and Wayne County Sheriff offices
- are tested monthly.
Communication equipment to the NRC's Emergency Response Organizations is tested monthly.
- Communications between the Fermi 2 Emergency Response Facilities and the appropriate offsite response organizations are tested during an annual exercise.
- Communications between the EOF and the Offsite Radiological Emergency Teams (RETs) are tested annually. Annual drills shall also test the ability to understand the content of messages. ,
Emergency Telephone Directories are updated quarterly.
y ,- _ . _ _ _ _ _ __ ._ ._ s-RERP Plan l Revision 1 l Page N-2 ! N.2.2 Fire - Fire drills are conducted quarterly. A fire drill involving the Frenchtown Township Volunteer Fire Department is conducted annually. l N.2.3 Medical Emergency - Medical emergency drills, which involve a simulated contaminated individual and participation by local support agencies (for example, EMTS emb9tance
- service, Seaway or Mercy-Memorial Hospital), are conducted annually.
N.2.4 Radiologicel Monitoring - RET drills are conducted annually. These drills will include the collection and analysis of air samples and shall include sample media such as water, grass, and soil from the Owner-Controlled Area or nearby offsite areas. In addition, i l these drills provide the opportunity for the assessment of communication and record keeping capabilities,
~N.2.5 Health Physics - Health Physics drills involving response to and analysis of simulated elevated airborne and liquid samples as well as direct radiation measurements in the .
environment are conducted semlannually. Analysis of inplant liquid samples with - simulated elevated radiation levels will be conducted annually.- These drills may be I conducted in conjunction with the annual exercise. N.2.6 Additional Drills - Additional drills will be scheduled as necessary to provide adequate training of personnel, provide emphasis on weak areas, and ensure an adequate level of emergency prop,aredness. N.3 Drill and Exercise Scenarios Drill and exercise scenarios will contain, as a minimum, the following: Basic objective (s) of the drill or exert.se and appropriate evaluation criteria Date, time period, place (s) of the drill or exercise, and participating organizations Simulated events " Time schedule of real and simulated initiating events Narrative summary that describes the conduct of the exercise or drill and I includes such items as simulated casuattles, offsite fire department , l assistance, rescue of perconnel, use of protective clothing, deployment of I. emergency teams and public Information activities l Detailed data sheets (as required) Assignments for qualified controllers / evaluators and provisions for observers from Federal, State, and local organizations as appropriate l l
. . _ . .A._______. _ . . _ _ _ , . . _ , . . . . _ _ _ _ . . , _ . _ _ _ . _..._ _..._____._ ...,. _ _ _ ._.
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i' RERP Plan Revision 1 l Page N-3 N.4 Conductir4e Drills Gnd Exercises i
Official Federal, State, or local observers are provided advance exercise scenario l materials as appropr:ste: The NRC will be provided with advance materials in accordance with FEMA and NRC ,1 guidance documents. i
- State and local observers will be providad advance materials on an as-needed basis.
All drills and exercises (except communications drills) are preceded by a conference at which personnel conducting or monitoring the drill or exercise obtain instructions and j" guidance. As soon at practicable following the drill or exercise, a critique is held. A formal evaluation based on the results of the critique is prepared. The Supervisor, RERP is responsible for management review of observer and participant comments and the (, implementation of appropriate correctivo actions. ; l' k b Y
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RERP Plan l Revision 1 Page O-1 O. RADIOLOGICAL EMEROENCY RESPONSE PREPAREDNESS TRAINING Radiological Emergency Response Training is provided to all individeals in the . emergency response organizations. The Integrated Training Program includes General Employe Trsining for all persons at Formi 2 and detailed training for individuals and groups with responsibilities during an emergency. The Training Program provides initial . , training and periodic retraining. Drills and exercises constitute a portion of the s intearated Training Program and are discussed separately in Section N. ; O.1 Guelification Requirements for Onsite Emergency Response Personnel Specific training requirements are established for the following functional roles la the c Onsite Emergency Response Organization: Emergency Officer Emergency Director Control Room Personnel TSC Support Personnel ; EOF Support Personnel Communicators Edison Liaison to State and County Emergency Operations Centers ' Operational Support Center Coordinator Onsite and Offsite Radiological Emergency Teams Personnel Monitoring Teams Damage Control and Rescue Teams Fire Brigade Nuclear Security Force Dose Assessors and Meteorologists Corporate Officer Radiation Protection Advisors and Coordinators All emergency response personnel are initially trained and some must requalify annually. Furthermore, key emergency response personnel must participate in a drill or exercise at least annually. Table O-1 shows a matrix of the training modules available and the initial and requalification training requirements for emergency response organization pvsitions. Completion of specialized training for each position can include attending lectures and seminars, participating in practical drills and exercises, ' familiarization with specified reference material, and taking periodic' examinations. This training is documented in the Personnel Training History System. Documentation is completed in accordance with Nuclear Training Procedures.
- t During practical drills, on the spot correction of erroneous performance will be made and demonstration of the proper performance will be offered by the instructor / controller.
0 I RERP Plan Revision 1 Page 0-2 1 J l Personnel assigned to emergency teams that provide first aid will complete a training l course equivalent to Red Cross Multi-Media on a schedule compatible with the Red i Cross requirements. ' O.2 ' Training Requirements for Offsite Organlaations ) Detroit Edison provides specialized training for the EMTS ambulance service, the Frenchtown Township Volunteer Fire Department and Seaway and Mercy-Memorial i Hospitals. This training may include topics from the following areas: l RERP Plan orientation
- ' Communications and emergency notifications '
Transporting and treating contaminated patients Radiation fundamentals Protection against radiological hazards j- , Emergency equipment - ' Site access procedures Identification of Individuals onsite in control of offsite support activities e in addition to the specifip offelte training stated above, Edison, the Emergency Management Division of tho' Michigan State Police, and the local counties have , developed a four part training program that is presented to the local offsite Emergency Response Organizations annually. The program consists of the four parts listed below: " Part 1: Plant Operations and Emergency Planning
- i. Part 2: The Basics of Radiation Part 3: Radiological Emergency Response Plans, Organization, and Procedures for the
.' State of Michigan y Part 4: Emergency Worker Orientation to the County Radiological Emergency Response Plan 1 Detroit Edison also conducts an annual seminar for offsite State and loaf government personnel who will be involved with the onsite/offsite Emergency Rebponse faclltt.es, emergency action levels, emergency classification, meteorology, dose assessment, field surveys, and protective action recommendations. This seminar provides a basis for 7 understanding the application, process, and interfaces among Fermi 2 and offsite response organizations. The presentation is made available to the following: Michigan State Police Emergency Management Division Michigan Department of Public Health. Division of Radiological Health
- Province of Ontario, Canada L Ministry of Solicitor General Ministry of Labor Monroe County Wayne County p
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' TABLE O-1: RF.RP TRAINING COURSES AND TRAINING MATRIX. ;
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- >- A., RERP Training Courses .. y l
- 1. Emergency Plan Orientation < - l t
' 2. Emergency Radiological Exposure Control i '
- 3. Communications
- 4. ' Notification Procedures
- 6. Emergency Classification o.
' 6. Reentry & Recovery
- 7. Emergency Response Organization & Facilities .
- 8. Variances From Routine Radiological Practices and Procedures !
- g. '
' Radiological Assessment & Protective Action Recommendations !
.10. A.' Offsite Dose Assessment Methodology - Manual !
B. Offsite Dose Assessment Methodology - IBM Microcomputer > C. Meteorology 1 . >
.: 11. On-Site Radiological Emergency Team (RET) ;
- 12. A.' . ERIS - Safety Parameter Display System (SPDS)
~ B. ERIS - Dose Assessment & Meteorology .
n 13. Damage Control & Rescue I i
- 14. Off-Site Radiological Emergency Team (RET) I
- 15. Emergency Classification & Protective Action Recommendations l (Combined Courses 5 & 9) r
- 16. Personnel Monitoring Team
- 17. Drills / Exercises I
1* 1-
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RERP Plan Revision 1 ., Page O-4 j I
- 3. . RERP Training Matrix l
, I CONTROL ROOM (CR) l
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!'~4- i TRAINING COURSE NUMBER !
Position Title 1 2 3 4 5 7 8 9 10A 108 12A 128 13 17 , l NSS ***XX* XX X X X X X
]
NASS * *
- XX* XX X X X X X
~
STA * *
- XX* X X X X X X NSO-SRO Licensed * *
- XX*XX X X X X X X NSO-RO Licensed * * *X
- X X X X Admin. Support * * *
- X ,
NSO-Not Licensed * * *
- X X.
- I.
* * *
- X X Shift Nuc. EnDineer Non-Licensed Operator' * * *
- X X *
* = No Requalification Required L
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RERP Plan - i Revision 1 l Page 0-5 4 t
.B. RERP Training Matrix (Continued) ' ,
OPERATIONAL SUPPORT CENTER (OSC) ; TRAINING COURSE NUMBER Position Title 1 237811 13 17 OSC Coordinator * * *
- XX X X ,
' Asst. OSC Coordinator * * *
- XX X X ,
Rad Protection Tech * * *
- X * !
l ) Chem. Tech. '
* * *
- X '
Damege/ Rescue (GMJ, I&C) * *
- X X *
(See NSO, Non-Ucensed Fire Brigade . Operator, l&C) ,i Security * * * *
- r
* = No Requalification Required r
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RERP Plan ' Revision 1 Page O-6 , p B. MERP Training Metrix (Continued) l TECHNICAL SUPPORT CENTER (TSC) TRAINING COURSE NUMBER Pobition Title 1 2 3 4 5 7 8 9 10A 108 10C 11 12A 125 13 16 17
, Emergency Director * *
- X*XX 0 X ,
'S
( Technical Engineer * *
- X* X X X Technicel
\
Communicator * * *
- X X Nuclear Safety Advisor * *
- X* X X l Engineering Staff '* * *
- X X Red. Protection,Adv. * *
- X*XX X X X X X X X ,
Dose Assessor .
* * *
- X X X X X X Radchem Advisor * * * *X X a
Security Advisor * * *
- X ,
I~ TSC Administrator * *
- X
- x l
- X Communicator * *
- X l Status Board Clerk * * *
- X
* * *
- X L Typist _
I s Clerical Support * * *
- X Info. Center Spec. * * *
- X l.
?- I' O = Optional
* = No Requalification Required 1
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n 1 ) e RERP Plan J a Revision 1 Page O-7 , B. RERP Training Matrix (Continued) s a
$ EMEROENCY OPERATIONS FACILITY (EOF) l TRAINING COURSE NUMBER '
Position Title 1 2 3 4 5 7 8 9 10A 108 10C 12A 12B 14 15 16 17 [ l Emergency Officer * *
- X* XX O X ,
i Nuclear Ops. Advisor * *
- X* X X X [
Red. Protection Coord. * *
- X* XX X X X X X X X Asst. Red.
Protection Coord. * *
- X* XX X X X X X X X Met / Dose Assessor * * *
- X X X X X X .i
' Emero. Lab. Tech.
- t (See OSC - Chem. Tech) -
\. , .
Security Advisor * * *
- X Public Infor. Coord. * * *
- X X i EOF Administrator * * *X
- X Communicator * *
- X
- X Status Board Clerk * * *
- X
; HET Coordinator * * *
- X X Typist * * *
- X Clerical Support * * *
- X !
Info. Center Spec. * * *
- X 0 = Optional
* = No Requalification Required
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4 RERP Plan pe Revision 1 L 4 Page 0-8
' O. RERP Training Matrix (Continued)
OFF-SITE i,\1
- j. TRAINING COURSE NUMBER Position Title 1 2346714 15 16 17 Offsite RET AAA X X PMT * *
- X
- RET Supervisor A A'A X X JPIC Spokespersoi * * *
- X *
.JPIC Staff * * * *
.1
- Corporate Officer A A A' O
- l
- On-Call .
Plant Supervisor * *
- X * -*
State Liaison ** *
- X
- 1 County Liaison * * *
- X
- l l !
l- + Recovery Org. * *
- X
- i l ~. -
l- State / Local Officials Annual PAG /EAL Seminar , Annual County Volunteer ' Ambulance Training Program l- Annual County Volunteer j Medical ' Training Program I Annual County Volunteer Fira Dept. Training Program Annual County Volunteer , i4 Volunteers Training Program ! l~ . i A = Attendance Required. No Exam l- m - O = Optional A l? * = No Requalification Required.
+ = See EP-402 for specific position titles I
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t {' i RERP Plan Revision 1 Page P-1 P. RESPONSIBILITY FOR THE PLANNING EFFORT: DEVELOPMENT, PERIODIC REVIEW, AND ' DISTRIBUTION OF RERP PLANS , This Plan Section identifies key personnel who are responsible for developing, reviewing, and updating the RERP Plan, discusses the RERP format, and describes the review process. P.1 Responsibilities ; The Vice President Nuclear Engineering and Services has overall authority and responsibility for RERP planning for Detroit Edison. The Supervisor, RERP is responsible for developing and updating the RERP Plan and its Implementing and administrative , procedures. The Supervisor, RERP coordinates the development and revision af the plan and procedures with other response organizations. The Supervisor, RERP will identify the supporting procedures required.by other groups. The Supervisor, RERP in conjunction with Nuclear Training, is responsible for ensuring that all Emergency Response Organization personnel complete training in emergency preparedness. The Supervisor, RERP is responsible for the training"of individuals responsible for the planning effort. P.2 Format of the RERP Plan l The RERP Plan is written in the following format: Each Plan section corresponds to a similarly titled section in NUREG-0654/ FEMA-REP-1, Revision 1, November 1980, Criteria for Preparation and ! Evaluation of Radiological Emergency Response Plans and Preparedness in Support ; l. of Nuclear Power Plants (see Appendix 5). , A specific table of contents is provided. 1
- A list of implementing and administrative procedures is found in Appendix 3. A list of supporting procedures and documents is found in Append!x 4.
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i E , 4 g < l 4 # RERP Plan 1 s a Revision 1 I Page P i p P.3 Review and Revision of the RERP Plan c l The Supervisor, RERP is responsible for enwuring that an annual review of the Plan is
. conducted ~ The Letters of Agreement (Appendix 1) between the Fermi 2 Emergency Response Organization and offsite agencies will also be reviewed and updated as required at that time. Changes are recommended based on the following considerations:
Written critiques and evaluations of drills and exercises, especially recommended corrective actions , Changes in company or plant organization Changes in function or organization of support agencies, including necessary r ' revisions to letters of agreement Changes in state or federal regulations or regulatory guidance - Changos in state or local emergency plans
. Modifications to the plant or site that could affect emergency planning, including modifications to plant systems, emergency equipment, or emergency facilities, etc Changes to Technical Specifications Recommendations from other organizations, such as state and federal agenc!* and other utilities !
Significant changes in the areas surrounding tho site, such as changes in population density or land ushge Changes in capabilities of supporting organizations, including local hospitals, l ambulance services, fire departments, etc. p Changes in other plant operating or administrative procedures Revisions to the RERP Plan are reviewed by affected organizations and approved by the Onsite Review Organization (OSRO). Revised pages indicate where revisions were made E and controlled copies are distributed. Documents concerned with review of the RERP l Program are retained for at least 5 years. l The Plan shall contain an appendix listing, by m.mber and title those procedures required to implement the Plan. This listing shall crost.-reference the RERP Plan Section implemented by each implementing or administrative RERP procedure. The Plan also i contains a cross-reference to each section of NUREG-0654 required to be implemented in the Fermi 2 RERP Program in Appendix 5 l 1
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RERP PI n Revision 1 Page P-3 i
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1 P.4 - Review and Revision of RERP Program 1 P.4.1 Independent Review - An independent audit of the RERP Program is to be conducted in l accordance with 10 CFR 50.54 (t). The review will address all aspects of the RERP i Program, including the Plan, implementing and administrative procedures, training, I ret diness, testing, equipment, and interfaces with the state and local government ; agencies. .This independent review may be conducted in conjunction with the annual exerciss. Recommended correction actions and any proposed revisions to the RERP Plan' ' are documented and reviewed. The Supervisor, RERP, is responsible for recommending revisions to be made to the RERP Plan or other corrective actions as appropriate, o > END OF RERP PLAN TEXT t I l~ l, ) u 1 1 l l
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l App.,1-1. i 1 I 45 1 t a ( ,' , , b f , APPENDIX 1: : LETTEF.S OF AGREEMENT -
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y h' RERP Plan n Revision 1 App.1-2 i , LETTERS OF AGREEMENT !. Ir, Letters of agreement have been obtained from both government agencies and private industry
> that have agreed to support the Fermi 2 Emergency Response Organization during an -
emergency. The. Letters of Agreement listed below are included in this Appendix: I EMTS Ambulance Service Frenchtown Fire Department I General Electric Company. BWR Emergency Support Program (not a Letter of Agreement) institute of Nuclear Power. Operations (Nuclear Power Plant Emergency' Rosponse Voluntary Assistance Agreement) j Mercy-Memorial Hospital Corporation Monroe County Community College
. Mutual Assistance Agreement among
.1
' Consumers Power Company
' Detroit Edison
- , The Toledo Edison Company l.
Indiana Michigan Power Illuminating Company j I p The Cleveland Electric illuminating Company .i l .1 1 . Seaway' Hospital (United Care incorporation) l U.S. Department of Energy (Chicago Operations Office) l 1 n le
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R , ! k4 l . RERP Plan Revision 1 i- App.1-3 ; r RADIOLOGICAL EMERGENCY RESPONSE PLAN y LETTER OF AGREEMENT H : This Agreement, made between E.M.T.S., Inc. Ambulance Service, hereinafter called "EMTS", and LDetront Edisoni WITNESSETH: l Whereas, EMTS provides ambulance transport services to injured persons in the city of Monroe, Michigan and surrounding localities to local hospital facilities, and k Whereas, Detroit Edison owns electric facilities, including the Fermi 2 nuclear generating station, , and' ( h Whereas, the parties desire to help assure the availability of adequately trained and experienced [ emergency personnel in the event of a medical emergency at Fermi 2. .l
' Now, Therefore, it is Agreed between the parties as follows:
ARTICLE I l REQUESTS FOR EMERGENCY ASSISTANCE 1.1 in the event of injury to any person (s) on property owned or utilized by Detroit Edison, EMTS will be notified by an authorized Detroit Edison representative that ambulance service - is required. 1
' 1.2 Notification to EMTS will be made via telephone communication by calling (313) 241-1111 or through radio communication routed through the Monroe County Sheriff's department.
1.3 At the time of the request for ambulance assistance, EMTS will be provided with the location of the injured person (s), a description of the nature of the injury. the extent of - radioactive contamination and a status report of the injured person (s) condition as can best , be determined. ARTICLE ll TRANSPORTING INJURED PERSONNEL [ : 2.1 in the event of a non-radiological related injury, EMTS personnel will be responsible for transporting the injured person (s) to the emergency medical facility. A health-physics technician will not accompany the injured person (s) in the ambulance. i; e
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!' RERP Plan Revision i l App.1-4 2.2 If the injury has radiological Im' plications, the injured party will normally unaergo ;- decontamination at the Fermi 2 site prior to transport to the hospital by EMTS personnel.
However, If immediate medical treatment of the injury is vital, that treatment will take l precedence over decontamination. A radiologically contaminated person (s) will be transported to either Seaway Hospital or Mercy-Memorial Hospital where facilities are ; available to handle a radiologically contaminated injury. In this event, a person trained in health-physics monitoring techniques will accompany the injured person (s) in the i ambulance. 2.3 If an injured person (s) is in an area which has been determined to be unsafe due to the presence of high radiation levels, it will be the responsibility of Detroit Edison to transport the hjured person (s) to an area which is determined safe, at which point EMTS will . continue transport of the injured party as outlined in paragraph 2.2 preceding, j l ARTICLE lil SCOPE OF ASSISTANCE 3.1 ' Emergency ambulance service shall be made available to Detroit Edison on a 24-hour per day, seven days a week basis. 3.2 El'ATS will staff each ambulance with a Michigan Departmont of Public Health licensed emergency medical technician and/or paramedic. 3.3 EMTS will be responsible for communicating all necessary medical information to the l Individual medical facility through EMTS radio equipment once the EMTS ambulance team L has arrived on the scene. 1. l 3.4 Detroit Edison will provide EMTS response personnel with four ambulance supply kits which contain direct reading dosimeters and dosimeter chargers for use in radiological related p emergencies. Detroit Edison shall be responsible for maintaining the contents of these I emergency-supply kits. 3.5 Detroit Edison will make available annual training for EMTS personnel in the handling of l radiologically related injuries. 3.6 Detroit Edison will conduct annual emergency medical drills and wlll provide EMTS with a copy of the written evaluation. 3.7 Precaution will be exercised by Detroit Edison personnel to prevent contaminating the ambulance interior in the event of transport of a contaminated person (s). Detroit Edison will be responsible for the radiological monitoring and decontamination of equipment owned by EMTS.
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t .. RF.RP Plan Hovision 1 App.1-5
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ARTICLE IV RElMBURSEMENT FOR EMERGENCY ASSISTAhCE RENDERED
; 4.1 Pursuant to this agreement, t,etroit Edison will call upon EMTS to participate in training i non-emergency drills and exercises and EMTS agrees to participats 'u such training, drills and exercises.
4.2 To reimburse EMTS for expenses Incurred for participation in such non-emergency events Detroit Edison agrees to pay not more than Two Thousand Eight Hundred Dollars ($2,800). annually. ARTICLE V MODIFICATION 5.1 At any time after,the date of this Agreement either party, by giving not less than thirty days written notice to the other party, may call for reconsideration of the terms and conditions of this Agreement. If such reconsideration is called for, the authorized representatives of the parties shall meet as promptly as convenient and discuss any of the terms and conditions of this Agreement. No party shall be under any obligation to agree , to any modification or supplement not satisfactory to it. Any agreement modifying or j supplementing such terms and conditions shall be in writing, signed by both parties, and i shall specify the dato such modification or supplement shall become effective. . h ! ARTICLE V TERM OF AGREEMENT l 6.1 This agreement shall continue for a term of two (2) years from the date of signing and ! bi-annually thereafter unless and until terminated as provided for in Section 6.2 following, i 6.2 Elther party to this agreement may, upon sixty (60) days written notification to the other party, terminate this Agreement at the expiration of any successive two (2) year term. l i
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, RERP Plan ,
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n- IN WITNESS WHEREOF, the parties hereto cause this Agreement to be executed by their duly ' authorized representatives. , kq
- i THE DETROIT EDISON COMPANY EMTS, INC. AMBULANCE SERVICE By: .
D. C. Metcalf /s/ By: Bernard G. Sieg /s/ .
Title:
B. Contracting Specialist
Title:
President
' Date: 1-12-88 Date: 11-20-87 -
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l h, RERP Pir,n [ , Revision 1 f t App.1-7 t' I C RADIOLOGICAL EMERGENCY RESPONSE PRFPAREDNESS
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L LETTER OF AGREEMENT v This Agreement, made b'etween Frenchtown Fire Department and The Detroit Edison Company (hereinaf ter called ." Detroit Edison"): b WITNESSETH: E Whereas, Frenchtown Fire Department is a paid on-call organizetion providing fire protection and 1 il emergency rescue services Whereas, the par.les desire to help assure the availability of adequately trained and experienced emergency personnel in the event of an emergency situation at the Fermi 2 plant site, J. Now, Therefore, it is Agreed between the Parties as follows: ARTICLE I Request for Emergency Assistance f 1.1 In the event of a fire occurring at the Fermi 2 site owned and utilized by Detroit Edison, Frenchtown Fire Department will be notified by an authorized employe of Detroit Edison at Fermi 2 that fire fighting assistance is required. 1.2 - In the event of a Radiological Medical Emergency at the Fermi 2 site owned and utilized by Detroit Edison, Frenchtown Fire Department will be notified by Central Dispatch at the , Monroe County Sheriff Department or by an authorized employe of Detroit Edison that an i emergency vehicle (ambulance) is required. 1.3 The Fermi 2 Control Room will request fire fightin'; assistance by calling (313) 241-0600. Control Room will designated proper gate. L 1.4 At the time of the request for fire fighting assistance, Frenchtown Fire Department will be l provided with necessary information relative to the location and nature of the fire and the l designated gate for access to owner-controlled property. 1.5 Detroit Edison will provide Frenchtown Fire Department with a map identifying the location of access gates, hydrants, drafting locations, hose houses and similar connections. l l L 1 l
w , 0, F RERP Plan Revision 1 App.1-8 l [ i ARTICLE 11 Scope of Assistance ! 2.1 Frenchtown Fire Department will provide fire fighting assistance on a 24-hours per day,
!. seven days per week basis and wi!! draw upon personnel and equipment resources from any of the four fire stations in the area.
2.2 Frenchtown Fire Departmerit will ensure that adequate fire fighting equipment is properly maintained and readily available.
; , 2.3 Frenchtown Fire Department will equip its fire fighting personnel with portable breathing l apperatuses Detroit Edison will ensure that compressed air and adapter fittings, if '
necessary, are available on site for recharging breathing tanks. Frenchtown Fire I Department will immediately nofify Detroit Edison in writing if a change is made in its type of threaded hose connections. 2.4 Training in fire fighting techniques will be the responsibility of Frenchtown Fire Department. Detroit Edison will make available training to members of the Frenchtown Fire j j. Department in site access procedures, overview of the plant fire protection systems, review ! of hazardous materials located onsite, and radiation emergency medical training. 2.5 Periodic, at least annually, drills will be held in cooperation with Frenchtown Fire Department to exercise emergency response procedures and effectiveness. l i l ARTICLE lil i Security Procedures j 3.1 A security guard will be stationed at the designated access gate to provide access for fire department personnel and vehicles to the owner-controlled property. l 3.2 A Secunty guard will escort fire department response personnel and vehicles directly to -l ( the location of the fire if it is outside the protected area. I \ 3.3 If the fire is located within the protected area, the Secunty guard will escort fire ' department personnel and vehicles to the truck lock gate at the perimeter of the protected area. Personnel will be provided with an identification badge, thermoluminescent dosimeter and/or pocket dosimeter and will proceed under Security escort to the site of the fire, j y Only emergency vehicles wnl be allowed to enter the protected area. i o .
~
[ RERP Plan r Revision 1 App.1-9 3.4 ' To facilitate Security clearance, Frenchtown Fire Department will provide Fermi 2 Security f
! Department with a master list of all personnel who may be anticipated to respond to a request for fire fighting assistance. Updating this list and informing Detroit Edison will be the responsibility of Frenchtown Fire Department.
3.5 Both parties agree that Frenchtown Fire Department is trained in proper fire fighting
'1 techniques and Detroit Edison personnel are trained in the unique operating and safety characteristics at a nuclear power plant. Therefore firefighting at Fermi 2 is a cooperative ' effort between Frenchtown Fire Department personnel and Fermi 2 personnel. Prior to activation'of any fire extinguishing systems by Frenchtown Fire Department personnel, the Detroit Edison Fire Brigade leader (or delegate)'will authorize such activation to assure that the safety of plant and personnel will not be jeopardized. 1 ARTICLE IV Reimbursement for Expenses i i
4.1 Pursuant to this Agreement, Detroit Edison will call upon the Frenchtown Fire Department to participate in a variety of drills, training and exercises which are non-emergency situations and Frenchtown Fire Department agrees to participate in such drills, training and exercises. 1 I ARTICLE V Term of Agreement 5.1 This agreement shall continue for a term of two (2) years from the date of sigrung and { j, bi-annually thereaf ter unless and until terminated as provided for In Section 5.2 following: l 5.2 Elther party to this agreement may, upon sixty (60) days written notification to the other , party, terminate this Agreement at the expiration of any successive two (2) year term.
'i IN WITNESS WHEREOF, the parties hereto cause this Agreement to be executed by their duly authorized officers.
i l THE DETROIT EDISON COMPANY FRENCHTOWN VOLUNTEER FIRE DEPARTMEN I' By: D. C. Metcalf /s/ By: Edward Thoma /s/
Title:
Sr. Contracting Speciellst
Title:
Chief _ Date: 3/7/88 Date: Feb.22,1988
m L RERP Plan Revision 1 i App.1-10 t April 14,1980 SIL No.324 File Tab A Category 1 1 BWR EMERGENCY SUPPORT PROGRAM For some time, General Electric (GE) has had in place a support program, which utilized the full , resources of the Nu' clear Energy Group in San Jose and the Installation and Services Engineering l personnel in the local districts, to support utilities during emergency situations. This program . has provided assistance for BWRs during major component failures and plant transients to minimize the impact of the event and assure BWR owners / operators during emergency situations which could potentially endanger the health and safety of the public or plant personnel, or which under certain circumstances could have a major impact on continued plant operations, a special Emergency Support Program has been established by GE's Nuclear Services Department. The purpose of this Service Information Letter is to provide BWR owners / operators the essential details of this Emergency Support Program and to identify how emergency assistance can be j expeditiously requested from GE. l NOTE: This support prontam is directed at emergency situations and is not intended to replace normal tarvices requests / communications through the local GE service representatives or Nuclear Services Managers. EMERGENCY SUPPORT PROGRAM
- l. 24 HOUR DEDICATED COMMUNICATIONS COVERAGE i
General Electric has established 24-hour dedicated communications coverage to be used to request emergency assistance. The telephone number to be used for the initial contact is: Area Code - 971-1038 l E During normal working hours this number will be connected to the office of the Manager of BWR Product Service. During non-working hours, this number will be monitored by an answering service which will contact a designated GE manager. Upon reaching the answering service, the BWR owner / operator should leave a number, name and BWR site name for immediate call back.
- 11. SITUATION ASSESSMENT The Manager, BWR Product Service, os designated GE Manager, will make an assessment of the emergency situation during the Initial contact discussion with the l BWR owner / operator and determine the scope of the assistance being requested by the utility.
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; RERP Plan l Revision 1 App.1-11 1
3 Ill. SUPPORT i Upon activation of the Emergency Support Program GE will:
- 1. Form and dispatch to the affected site (if requested) an Emergency Response Team composed of appropriate technical disciplines. The program is set up to accomplish team arrival on the affected BWR site within 24 hours of the request.
The team will be equipped with film badges, mobile telephone and a portable telecopy machine. ,
- 2. Form a Technical Support Team in San Jose composed of appropriate technical disciplines and establish dedicated telephone communications with the affected ,
a BWR site, the GE Operations Site Engineer and/or local General Electric service l; representatives, and the Emergency Response Team. y
- 3. ' Contact the BWR Operations Engineer and/or the local General Electric service representative and direct him to proceed immediately to the BWR site to establish communications and data collection as necessary until the arrival of the Emergency Response Team or as the Technical Support Team directs.
- 4. Cuatinue to provide assistance to the utility in recovery from the emergency to insure timely return to service.
t ! IV. ARRANGEMENTS ' GE will maintain the Emergency Support Program in a standby mode at no cost to the BWR owner / operator. Once the Emergency Support Program is activated, however, services provided will be governed by the terms and conditions of the nuclear services contract in place between the BWR owner / operator and GE, or if such contract is unsigned, as currently proposed by GE to the BWR owner / operator. To facilitate initiation of the program prior written agreement with this approach will be needed. T RECOMMENDATIONS To accomplish a rapid initiation of emergency support and to insure a coordinated i effort at combating and recovering from emergency conditions it is recommended that the following be done by the BWR owner / operator:
- 1. Incorporate the GE 24-hour dedicated communications number into site emergency procedures.
- 2. Provide site administrative support for the Emergency Response Team when such a team is activated. This should include communication facilities, health physics control and document access.
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'l- Revision 1 1 App.1-12
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[ 3. Provide General Electric with emergency situation instructions governing site ' admission and specifyinD conduct for the BWR Operations Site Engineer, the local General Electric service representative, and the Emergency Response Team. t
- 4. Provide a written agreement to GE that Emergency Support services may be desired and that such services, when activated, will be governed by the terms and l condit as of the nuclear services contract in place between th9 BWR
[ owner,uperator and GE, or if such contract is unsigned, as currently proposed by
! GE to the BWR owner / operator.
For additional information contact your local General Electric service representative. r Prepared by: D. L. Layton/R. E. Bates . . Approved by: D. K. Willett /s/ Issued by: D. L. Allred /s/ D. K. Willett, Manager D. L. Allred, Manager BWR Product Service Utility Support, Serv. Product
Reference:
i A71 - Plant Recommendations l l l
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r; , v 3 RERP Plan Revision 1
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App.1-13 ,
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t Nuclear Power Plant Emergency Response Voluntary Assistance Agreement l o. i
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P Dated: July 1,1982 l t l i i 1 l I l l w I
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RERP Plan Revision 1 App.1-14 ' Nuclear Power Plant Emergency Responso Voluntary Assistance Agreement I This Nuclear Power Plant Cmergency Re6ponse Voluntary Assistance Agreement (hereinatter i
- Agreement *) has been entered into by and among slectric utilitics which have responsibility for the construction or operation of commercial nuclear power plants under a license issued by the '
i U.S. Nuclear Regulatory Commission pursuant to Title 10 of the Code of federal Regulations (hereinatter ' nuclear power plants *) and which have subscribed counterpart signature pages in ' the form attached hereto (hereinafter
- Parties").
The Parties wish to set forth herein their understanding and agreement with respect to their rnutual undertaking to each other iri the situation wherein an emergency occurs at a nuclear L power plant under the control of or operated on behalf of a Party and a request for assistance is issued to another Party hereto in respect to such emergency and such assistance is providad. This Agreement is intended only to define the terms and conditions under which such assistance, if volunteered. will be rendered and received. It is understood that this Agreement does not impose any obligation on any Party to render or continue to render any such assistance but this Agreement does record the understanding of the Parties with respect to the riDhts and obligations which will be incurred in responding to requests for assistance. i NOW, THEREFORE, it is eDreed, that:
- 1. Assistance rendered by a Party as described hereunder shall be entirely voluntary and, when given in response to a request by any Party for help following an emergency arising at a nuclear power plant shall be rendered in accordance with the terms and conditions herein.
- 2. The Party that requests assistance shall be known as the
- Requesting Company" and the Party furnishing assistance shall be known as the
- Responding Company.* Attachment A is a suggested letter confirming an agreement whereby assistance will be furnisher.1 pursuant to this Agreement.
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7 I- , m ; i RERP Plan ! Revision 1
! App.1-15 l o 3. (a) Requesting Company shall notify Responding Company of the type of assistance !
requested and the anticipated duration during which such assistance is desired. Responding Company shall furnish such assistance as it may decide. Except as ; such companies may agree otherwise, Requesting Company sh611 be responsible l for determining the procedures to be followed relative to the furnishing of such f assistance, directing the work and making any reports to governmental authorlW8 ; and the news media regarding the emergency or the furnishing of assistance F pursuant to this Agreement. Regeesting Company shall rMy Responding i Company when its assistance is no longer needed. l
.i (b) The furnishing of assistance hereunder shall be deemed to have commenced when ;
personnel of the Responding Company are assigned to other than normal duties or ! transportat!on of equipment commences pursuant to a determination by the Responding Company to provide assistance to a Requesting Company under this a Agreement and shali be deemed to have terminated when the transportation of [ such personnel or equipment back to their working bass, or home (for personnel returning at other than regular working hours), is completed. [ (c) The Responding Company shall make all arrangements for the transportation of its ! ! personnel and equipment from and to their working base or home. [
- 4. (a) Employees of Responding Company shall at all times continue to be employees of the Responding Company and shall at no time and for no purpose be deemed to i be servants, egents, employees, or representatives of the Requesting Company, j (b) Wages, hours and other terms and conditions of employment applicable to !
personnel of the Responding Company shall be those of the Responding Company. Work procedures, security and safety rules for such personnel shall be i those of the Requesting Company. (c) Unless otherwise agreed, all personnel of the Responding Company shall be l equipped by the Responding Company with such normal working and protective ! equipment as shah oe compatible with the circumstances under which said 1 personnel shall function hersunder; Requesting Company shall inform Responding Company of any specific equipment which may be required in a particular situation. T 4 l i
s RERP Plan Revision 1 i App.1-16 l l l i
- 5. (a) Responding Company shall furnish the requested personnel and equipment to the !
extent that the Responding Company may determine to do so in its sole judgment ! and discretion. l (b) Any information which I;esponding Company may provide to Requesting Company I (including drawings, reports and analyses), or which Requesting Company provides 1 to Responding Company, which either the Responding Company or the Requesting j Company considers proprietary or confidential, shall be so designated. Such , proprietary information shall be held in confidence and shall be used exclusively in j connection with the emergency at the nuclear power plant at which the emergency j has occurred (including necessary disclosures on a proprietary basis to others in i that connection) and shall not be published or otherwlte disclosed to others, i except as may be required by law. 1 (c) Responding Company shall have the right, at any time and in its sole judgment and { discretion, to withdraw personnel and equipment furnished to the Requesting i Company and return such personnel and equipment to its working base. Without I limiting Responding Company's rights under the preceding sentence, Responding l Company shall attempt to schedule any such withdrawal of its personnel or : equipment to accommodate the needs of Requesting Company. Responding l Company shall give written notice at least 24 hours in advance to Requesting J Company of the permanent withdrawal of personnel or equipment furnished. , Respondino Company's withdrawal of personnel or equipment shall not affect any obligations which may have been incurred hereunder prior to such withdrawal or which may arise out of events occurring prior to such withdrawal. ,
- 6. All time sheets and work records pertaining to Responding Company personnel and ;
equipment shall be kept by the Responding Company. The Responding Company shall - furnish the Requesting Company with a detailed statement of all costs and expenses paid I or incurred by the Responding Company in connection with the furnishing of assistance to the Requesting Company, which statement shall be paid by Requesting Company within thrity (30) days after reesipt. i The Requesting Company shall reimburse Responding Company for all direct and indirect- I 7. costs and expenses, not including a profit, incurred by Responding Company in giving r assistance pursuant to this Agreement, including but not limited to costs and expenses , related to or resulting from compliance with governmental requirements such as Title 10 of the Cods of Federal Regulations Part 20. Such costs and expenses shall be computed in accordance with Responding Company's standard rates and accounting practi:es including such overheads as are determined by Responding Company to be appIlcable to such direct I and indirect costs and expenses incurred by Responding Company. Requesting Company l Shall have the right to audit the records of Responding Company relative to work performed pursuant to this agreement. l l
I i RERP Plan
.. Rev!sion 1 I App.1-17
[ 8. '(a) In addition, and subject to the provisions of paragraph 8 (b) hereof, Requesting Company shall indemnify and hold Responding Company, its officers, directors and employees, jointly and severally, harmless from and against any and all liability or lors, damage, cost or expense which any of thorn may incur by reason of bodily injury, including but not limited to death, to any person or persons, or by reason of damage to or destruction of any property, including but not limited to any property located at the site of the Requesting Company's nuclear power plant or the loss of use of any property, which results from furnishing assistance pursuant to this Agreement, whether due in whole or in part to any act, omission, or negligence of Responding Company, its officers, directors or employees, (b) Where payments are made by Responding Company or its insurers to Responding Company's officers, directors, or employees or their beneficiaries for bodily inj'u ry or death resulting from furnishing assistance pursuant to this Agreement, including but not limited to workers' compensation, disability, pension plan, medical and hotpitallration, or other such payments, Requesting Company shall make reimbursement to Responding Cornpany to the extent such payments increase the Responding Company's employee-related costs, whether such increase in costs occurs in the form of an increase in premiums or contributions, a reduction in dividends or premium refunds, or otherwise. Requesting Company shall also reimburse Responding Company for any deductible amounts or for any amounts paid by Responding Company as a self-insurer Responding Company will request its insurer to waive any right of subrogation it may have against Requesting Company as a result of any payment described in paragraph 8 (b) which such insurer may make on b6 half of Responding Company because of Responding Company's furnishing of assistance pursuant to this Agreement. (c) Responding Coropony makes no warranty with respect to any goods or services provided to Requesting Company and NO WARRANTY, EITHER EXPRESS OR IMPLIED, ORAL OR WRITTEN, SHALL APPLY TO THE GOODS OR SERVICES PROVIDED, INCLUDING, WITHOUT LIMITATION, THE WARRANTIES OF MERCHANTABILITY AND OF FITNESS FOR SPECIFIFD OR INTENDED PURPOSE. All equipment and services furnished pursuant to this Agreement are furnished as is. (d) In the event any claim or demand is made or suit, action or proceeding is filed against Responding Company, its officers, directors or employees, jointly or
- severally, alleg!ng liability for which Requesting Comparty shall indemnify and hold l , harmless Responding Company, its officers, directors and employees under this t
paragraph 8 hereof, Responding Company shall promptly notify Requesting L Company thereof, and Requesting Comptny, at its sole cost and expense, shall settle, compromise or defend the same in such manner as it in its sole discretion deems necessary or prudent. Responding Company shall cooperate with Requesting Company in the resolution of any such matter. l l l l
! I RERP Plan i l
Revision 1 App.1-18 ! l' (e) Each party to this Agreement agrees to carry the amount of financial protection ! required by the Atomic Energy Act of 1954, as amended, and self-insurance or l comprchensive liability insurance, including contractual liability coverage, covering j , ,t the indemnification and defense obligations set forth herein, subject to such types ) and amounts of self-insurance, retentions or deductibles as are consistent with l good business practice in the industry. ! i (f) in the event a Responding Company provides assistance pursuant to this I Agreement through an affiliate or subsidiary, the indemnification provided in this paragraph 8 to the officers, directors and employees of that Responding Company ; shall apply with equal force to the officers, directors and employees of that ! affiliate or subsidiary. ) i
- 9. Each Party shall provide the Institute of Nuclear Power Operations (*hereinatter INPO*) with ;
an executed counterpart signature page to this Agreement and to any amendments hereto. This Agreement shall become effective when counterpart signature pages executed by at least two Parties shall have been received by INPO. This Agresment shall remain in effect as to any Party until such Party has withdrawn from the Agreement as provided below. : Any electric utility with responsibilities for the construction or operation of a nuclear power ! plant may become a Party upon execution of the Agreement.
- 10. (a) INPO may provide certain administrative and emergency response support services in furtherance of this Agreement, such as maintaining and distributing to the i Parties a roster of the signatories to this Agreement; providing copies of the {
Agreement and any amendments thereto to all Parties; and preparing and i distributing to the Parties other documents, such as a list of sources of emergency i manpower and equipment. INPO may provide such other services as may be i requested of INPO from time to time by the Parties. The Parties recognize that INPO shall not be responsible for implementing, enforcing or interpreting this ; Agreement. ; (b) The Parties shall defend, indemni.'y and hold harmless INPO, its officers, directors ! and employees, jointly and severally, from and against any and all liability or loss, damage, cost, or expense which results from performance of INPO's functions described in paragraph 10(a) of this Agreement, except as may result from the sole - negligence or willful misconduct of INPO, its officers, directors or employees. Each Party hereby expressly walves any right it mey have to assert any claim against . I
.lNPO, its officers, directors, or employees arising out of its or their performance of INPO's functions described in paragraph 10(a), except as may result from the sole negligence or willful misconduct of INPO, Its officers, directors or employees. !
,- ,e - = ,. -
y - G, RERP Plan Revision 't s App.1-1g p t (c) Following an emergency at a nuclear power plant,INPO may,11 asked to do so by
- a Requesting Company, help to locate sources of emergency manpower and equipment which the Requesting Company may contract for assistance. The Requesting Company may ask iNPO to furnish personnel or equipment following an emergency arising at a nuclear power plant, if INPO does furnish such assistance and unless otherwise agreed by INPO and the Requesting Company, the Requesting Company and INPO shall have the same rights cnd obligations as if INPO were a Responding Company (including but not limited to the Reciuesting Company's obligations to INPO, its officers, directors and employees under paragraph 8 hereof), except that paragrgphs 6 and 7 shall not apply either to Requesting Company er INPO and paragraph 8(e) shall not apply to INPO.
- 11. This Agreement will not create any rights or defenses in favor of any entity or person not a signatory to this Agreement except to the extent provided in paragraphs 8 and 10 of this Agreement, This agreement shat! be binding upon and inure to the benefit of each signatory to this Agreement and the subsidiaries and affiliates of each such signatory,
- 12. Except as otherwise provided in paragraph 13, any Party may withdraw from this Agreement upon at least thirty (30) days prior written notice to INPO with a copy to all of the other Parties. Notice of withdrawal shall not affect any obligations which may have been incurred hereunder prior to the effective date of such notice or which may arise out of events occurring prior to that date. No Party may withdraw from this Agreement while it is receiving assistance pursuant to this Agreement.
- 13. This Agreement may be amended by the agreement of a majority of the Parties hereto.
Such amendment shall be effective and binding upon all Parties thirty (30) days after INPO has received counterpart signature pages for the amendment executed by at leart a majorit/ of the Parties to the Agreement. INPO shall notify all Parties when at least a majority of the Parties have executed an amendment to the Agreement. No amendment shall affect any obligation which may have been incurred hereunder prior to the effective date of such amendment or which may arise out of events occurring prior to that date. Notwithstanding the first sentence of paragraph 12, any Party may withdraw from this Agreement by submitting written notice to INPO at any time during the thirty (30) day period prior to the effective date of such amendment with a copy to all of the other Parties. I
RERP Plan ! Revision 1 ! App.1-20
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- 14. If any provision of this Agreement is determined to be invalid or unenforceable as to any Party or otherwise, such determination shall not affect the validity or enforceability of the '
other provisions of this Agreement as to that Party or otherwise. -
- 15. In the event (i) an emergency occurs at a nuclear power plant under the control of or f
( '
; operated on behalf of a Party; (ii) a request for assistance is issued to another Party hereto in respect to such emergency; and (iii) such assistance is provided, this Agreement shall be -
construed in accordance with the law of the State in which the nuclear power plant is located with respect to all rights and obligations arising out of such emergency, p. i l l l i
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- i. Revision 1- ;
L. s. . App.1-21 [ t i ! ! N'- ' COUNTERPART SIGNATURE PAGE 'l l': - i > I The undersigned company hereby agrees to become a Party to the Fixed Facility Emergency , Responso Voluntary Assistance Agreement dated July 1,1982. ! Date May 15,1986 Company The1)etroit Edslon Co. j r i t By Frank E. Agostl /s/ f Corporate Officer Signature 'l Y
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i RERP Plan
; ', s' Revision 1
- j. App.1-22 f
t ATTACHMENT A r Requesting Company Letterhead Date , 19 (Name and Address of responding organization) This letter confirms the telephone conversation on insert date and time betw6en out.
, and your _ in which our company requested assistance pursuant to the terms of the Nucitar Power Plant Emergency Response Voluntary Assistance Agreement dated and your organization agreed to provide assistance pursuant to that Agreement, t
Please acknowledge your agreement to the foregoint) by signing and returning to me the enclosed copy of this letter. Requesting Company Name and Address Corporate Officer Signature Respondind Organization Name and Address Corporate Officer Signature and Date
N e P.ERP Plan I Revision 1 , App.1-23 ) { LETTER OF AGREEMENT ! between MERCY MEMORIAL HOSPITAL CORPORATION ! I and !
< i THE DETROIT EDISON COMPANY i f*
for EMERGENCY MEDICAL ASSISTANCE ! THIS AGREEMENT made and entered imo as of the _20th day of _ January 1980, by and between Mercy Memorial Hospital Corporation, (the
- Hospital *) and Detroit Edison, a ,
Michigan Corporation. WITNESSETH: WHEREAS, the Hospital is the owner and operator of Mercy Memorial Hospital (the !
- Hospital") located in the County of Monroe, Michigan; that maintains JCAH accrediation .l and provides emergency medical service including fecilities for the treatment of !
radiologically contaminated patients and, f WHEREAS, Detroit Edison owns elStric f acilities, including Fermi 2, a Nuclear Generating ! Station, and ; WHEREAS, the panies desire to have available adequately trained and experienced [ personnel in the event of a medical emergency at the Fermi 2 power plant. , NOW, THEREFORE, it is agreed between the parties as follows: *
- 1. REQUESTS FOR EMERGENCY AS$1 STANCE, 1.1 In the event of injury to any person (s) on property owned or utilized by Detroit l
Edison, the Hospital will be notified by an authorized person ot Detroit Edison or l EMTS, Inc. Ambulance Service, or any authorized emergency transport carrier, t that an injured person (s) is (are) being transported to the Hospital receding ! emergency medical attention.
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l, g RERP Plan i Revision 1 l [ App.1-24 !i 1.2 If the injury is non-radiologically related, notification to the Hospital will be ; made through procedutos established for responding to any normal request for : emergency medical service by Detroit Edison at 241-1700 or EMTS on their J hospital compatible radio frequency, I
% 1.3 If the injured person (s) is radiologically contammated, the request for medical f
- attention will be made by calling 241-1700 for Detroit Edison, or EMTS can call ;
on their hospital compatible radio frequency. This notification will provide for ; implementation of the Hospital's radiological contilegency emergency plan. The injured person (s) will normally undergo decontamination procedures on the l Fermi 2 site prior to transport to the hospital. However, if immediate treatment . i i of the injury is vital, that treatment will take precedence over decontamination. ! A person trained in health physics monitoring techniques will accompany a f radiologically contaminated individual in the ambulance enroute to the hospital ) and remain at the Hospital as needed to continue health physics monitoring. ! 1.4 At the time of the request for emergency medical services, the Hospital will be provided with necest.ary information relative to the injured person (s) status as ! defined in mutually agreed upon operating procedures, it, SCOPE OF ASSISTANCE: i 2.1 Emergency medical service should be made available to Detroit Edison on a [' 24-hour, per day, seven days a week basis. l 2.2 The Hospital will have at least one physician and one nurse evallable within i about 2 hours who can supervise the evaluation and treatment of radiologically contaminated injured members of the general public, resulting from an i emergency event at Fermi 2. , 2.3 The Hospital, as part of their qualifications for treating radiologically [ contaminated injured persons, will ensure that emergency equipment for ('. s treatment of a radiological contamineted person (s)is continuously available at I' the hospital emergency f acility. ; 2.4 Detroit Edison will provide the Hospital with an embrgency supply cabinet which will contain the items listed in mutually agreed upon operating procedures. This i cabinet will be located on the Hospital's premises gnd should be locked when ; not in use. A master key to this cabinet will be retained by the Hospital. ; i l , 1
RERP Plan . Revision 1 i g App.1-25 , k ! i t 2.5 Detroit Edison will be responsible for disposal of all radiologically contaminated waste material (for example, cleansing liquids) on the Hospital's promises ' resulting from treatment of a contaminated person (s) from Fermi 2. ; r 2.6 Detron Edibon or its contractor will conduct annual training sessions for l l personnel who have emergency medical responsibilities defined in the - emergency medical plan. 2.7 Detroit Edison will make availabic technical Information and treatment protocols - for contaminated injured personnel 2.8 Detroit Edison or its contractor will conduct annual emergency medical drills and will provide the Hospital with a copy of the written drill evaluations. . 2.9 Detroit Edison will be responsib'd i er maintenance of the supply cabinet, f 2.10 Detroit Edison will be responsible for payment of services rendered to its j employees. , Ill. MODIFICATION 3.1 At any time after the date of this Agreement either party, by giving not less than thirty days written notice to the other party, may call for reconsideration of j the terms and conditions of this Agreement. if such reconsideration is called i for, the authorited respresentatives of the parties shall meet as promptly as ! convenient and discuss any of the terms and conditions of this Agreement. No i party shall be under any obligation to agree to any modification or supplement not satisf actory to it. Any agreement modifying or supplementing such terms [ and conditions shall be in writing, signed by both parties, and shall specify the date such modification or supplement shall become effective. t IV TERM OF AGREEMENT
- i 4.1 This eDreement shall continue for a term of two (2) years from the date of
- signing and bi-annually thereafter unless and until te'minated as provided for in ,
Section 4 2 followinD: ; i I I v
0] l i- t RERP Plan l
, Revision 1 l t App.1-26 '
4.2 Either party to this agreement may, upon sixty (60) days written notification to the other party, terminate this Agreement at the expiration of any successive two (2) year term. l l' IN WITNESS WHEREOF, the parties hereto cause this Agreement to be executed by their ; duly authorized representatives. THE DCTROIT EDISON COMPANY MERCY MEMORIAL HOSPITAL CORPORATION ! BY Donald C. Metcalf /s/ BY, Paul Levy /s/ ; t TITLE Sr. Contracting Specialist TITLE Executive Vice President i
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*l RERP Plan IW Revision 1 App.1-27 l.
f. EMERGENCY RESPONbE PREPAREDNESS PLAN i Letter of Agreement This Agreement, made between the Community College District of Monroe County, Michigan, hereinatter called
- Monroe County Community College *, and The Detroit Edison Company, hereinatter called
- Detroit Edison *:
WITNESSETH:
! Whereas, Monroe Cotinty Community College, is an educational institution located in the cuanty of Monroe, Michigan, and .
Whereas, Detroit Ecison, owns electric facilities, including the Fermi 2 Nuclear Power Plant, and Whereas, the parties desire to help assure the provision of adequate emergency preparedness for the residents of Monroe County in the event of an emergency situation at Fermi 2. Now, Therefore, it is Agreed between the parties as follows: ARTICLE I Use of Physical Facilities 1.1 Monroe County Community College will make available to Detroit Edison the use of designated rooms in the Student Services-Administration Building as the operating location for the Joint Public Information Center on a 24-hours per day, seven days per l week basis upon notification to authorities at Monroe County Community College that an ! cmergency has been declared at Fermi 2 and for use in periodic drills of the Joint Public Information Center. 1.2 Designated rooms in the Student Services-Administration Building will include the cafeteria dining area and conference rooms 1,2,3, and 4. The hallway corridor outside of ' these rooms will be shared by Detroit Edison and Monroe County Community College ! unless other arrangements are agreed upon by both parties. See Attachment A for building diagram. Parking lot A (north end of campus) will be available for parking. 1 l l I i l
r [ RERP Plan I Revision 1 , App.1-28 i t ARTICLE 1 Use of Physical Facilities (con't.) 1.3 If the volume of media representatives exceed the capacity of the designated area or if the scope of the emergency warrants additional facilities, officials of Monroe County Community College may designate additional facilities for the Joint Public Information Center. 1.4 In the case of an announced drill, Detroit Edison will notify the Administrator in the Continuing Education / Community Services Department to arrange for room reservations. 1.5 in the case of an unannounced drill or actual emergency, Detroit Edison will notify Monroe County Community College as per Attachraent B. ! ARTICLE 11 ; Security 2.1 During operation of the Joint Public information Center, Detroit Edison security personnel ! will control access to and within all rooms as designated in paragraph 1.2 and other i rooms and/or buildings as designated in paragraph 1.3. 2.2 Authorized entrants to any Monroe County Community College facility utilized for f emergency purposes by Detroit Edison will be identified by a badge issued by Detroit , Edison Security personnel stationed at the Monroe County Community College campus. : t ARTICLE lit Services 3.1 Food Services - Provision of food services for emergency response personnel and media ; i representatives will be the responsibility of Detroit Edison. A separate contractual agreement between A.R.A. and Detroit Edison may be arranged if the kitchen facilities of Monroe County Community College are to be utillred. If kitchen facilities are not utilized, t provision of food services will be contracted by Detroit Edison through an outside 4 organization, l 3.2 C_.u,stodial Services - Detroit Edison will be responsible for providing custodial services , I and supplies at Monroe County Community College for the duration of any declared emergency which activates the Joint Public information Center. At the close of the emergency, the facilities will be cleaned and furniture returned to its original position. l Also, Detroit Edison will provide for custodial services and supplies for any drills. l . l l ' L l
y n i RERP Plan , Revision 1 App.1-29 ! ARTICLE IV j Communications and Equipment 4.1 Telephone service for use by personnel in the Joint Public Information Center will be provided by Detroit Edison through a system installod by Michigan Bell Telephone which is separate from Monroe County Community College's telephone system. 4.2 Monroe County Community College will be responsible for deactivating the college telephone system if college personnel vacate the premises. Deactivating will mean either shutting off the system completely or setting the system in either a night mode or a special message mode.
, 4.3 Public pay telephones and credit card phones located in tho hallway of the Student Services-Administration Building will be available for use by Joint Public Information Center personnel.
4.4 Detroit Edison will provide all audio-visual and copying equipment to be utilized by Joint Public Information Center personnel, with the exception of the projection screen and lectern located in the cafeteria. 4.5 Locked cabinets for stora0e of Detroit Edison telephone instruments and audio-visual equipment will be located in the telephore equipment room and room B-15 in the basement of the Student Services-Administration Building. Keys to these cabinets will be retained by Detroit Edison. ARTICLE V Charges 5.1 in an effort to promote and ensure public safety, Monroe County Community College agrees that it will not charge Detroit Edison for any of the aforementioned services. 5.2 At its option, however, Monroe County Community College may elect to charge Detroit Edison for any, or all, of the following: 5.2.1 Property or equipment damage resulting from Joint Public information Center's activities. 5.2.2 Any services or costs incurred by Monroe County Community College beyond the scope of this Agreement incurred as a result of the Joint Public Information Center's activities. 5.2.3 Any loss of revenue due to the cancellation of scheduled luncheons, dinners, or other programs that Monroe County Community College may incur or be responsible for as a result of the Joint Public Information Center's activities.
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l RERP Plan i Revision 1 App.1-30 1 i , ART 6CLE VI
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Term of Agreement t
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6.1 This agreement shall continue for a term of two (2) years from the date of signing and bi-annually thereafter unless and until terminated as provided for in Section 6.2 or 6.3. , i 6.2 Either party to this agreement may, upon sixty (60) days written notification to the other : party, terminate this Agreement et the expiration of any successive two (2) year term.
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6.3 In the event that fAonroe County Community College begins any facility construction or , , renovation of any of the rooms or areas that are used for or affected by the Joint Public i information Center, alternative arrangements will have to be made based on the availability of f acilities. IN WITNESS WHEREOF, the parties hereto cause this Agreement to be executed by their duly authorized officers. DETROIT EDISON COfAPANY MONROE COUNTY COfAfAUNITY COLLEOE By D. C. Metcalf /s/ By Timothy S. Bennett /s/ Senior Dean of Business Title Contracting Specialist Title Affairs & Treasurer Date June 23.1989 Date June 19,1989 I l l l l
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.] Revision 1 l App.1-31 l o
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(,=, ._ REF'P Plan Revision 1 App.1-32 ATTACHMENT S Monroe County Community College Joint Public Inforn ation Center Agreement l COLLEGE CONTACTS FOR UNANNOUNCED DRILL OR ACTUAL EMERGENCY This attachment contains confidential phone numbers which will not be published. The information contained in Attachment B is available in the original letter of Agreement which is on file,
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' App.1-33 i
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l i MUTUAL ASSISTANCE AOREEMENT BETWEEN DETROIT EDISON CONSUMERS POWER COMPANY, THE TOLEDO EDISON COMPANY, INDIANA MICHIGAN POWER COMPANY AND
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THE CLEVELAND ELECTRIC ILLUMINATING COMPANY ? l I l I' N
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) .l RERP Plan l' Revision 1 App.1-34 0.1 The Consumers Power Company, a Michigan corporation; Detroit Edison, e Michigan and New York corporation; The Toledo Edison Company, an Ohio corporation; Indiana Michigan Power Company, an Indiana corporation; and The Cleveland Electric illuminating Company, an Ohio corporation, WITNESSETH I
0.2 WHEREAS, Consumers Power Company, Detroit Edison, and indiana Michigan Power Company own electric facilities, including nuclear generation stations, and are engaged in the geneistion, transmission, distribution and sale of electric power and energy in Michigan; and 0.3 WHEREAS The Toledo Edison Company and the Cleveland Electric liluminating Company own electric facihties, including nuclear generating stations, and are engaged in the generation, transmission, distribution, and sale of electric power and energy in Ohio; and 0.4 WHEREAS, the parties desire to help assure the av6l lability of adequately trained and experienced emergency personnel in the event of an emergency situation at any of their nuclear generating stations; 0.5 NOW, THEREFORE,in consideration of the promises and mutual covenants herein set forth, the parties agreo as follows: ARTICLE 1 OErlNITIONS 1,1
- Alert" shall be defined as a situation in which events are in process or have occurred which involve an actual or potential substanties degradation of the level of safety of the plant.
1.2 Emergency
- shall be defined consistent with the definition of
- site area emergency
- as set forth in NUREO 0654 as a situation in which events are in process or have occurred which involve actual or likely rnajor failures of plant functions needed for protection of the public.
- 1.3
- Requesting party
- shall be defined as any party to this Agreement who, upon the occurrence of an emergency at one of its nuclear generating stations, seeks emergency assistance, pursuant to this Agreement, from one or more of the parties hereto, l
l 1.4
- Responding party" or
- responding parties" shall be defined as any party or parties to this l Agreement who are presented with a request for emergency assistance pursuant to this l" Agreement.
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I l f 4 RERP Plan ! Revision 1 i App.1-35 ! ARTICLE 11 ; REQUESTS FOR EMERGENCY ASSISTANCE 2.1 in the event of an alert at one of its nuclear generating stations, any party to this Agreement may notify any or all of the other parties that an alert exists and that thalt emergency assistance may be required. j.i i 2.2 In the event of an emergency at one of its nuclear generating stations, any party to this ! Agreement may request emergency assistance from any or all of the other parties, i 2.3 Requests for emergency assistance shall be made between and among the following party i personnel: Consumers Power Company -Vice President ; Nuclear Operations Detroit Edison -Vice President . Nuclear Operations The Toledo Edison Company -Vice President - Nuclear l Indiana Michigan Power -Vice President Company Nuclear Operations e The Cleveland Electric -Vice President - Nuclear Illuminating Company ARTICLE 111 ' EXCUSED FAILURE TO RESPOND 3.1 Failure to respond to a request for emergency assistance pursuant to this Agreement shall be excused if, in order to respond, the requested party or parties would be forced in its or their sole judgment or judgments to: 3.1.1 Violate its duties relating to the care and staffing at its own nuclear generating stations; or 3.1.2 Jeopardize the public health or safety at a location other than the location of the , requesting party's emergency.
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Revision 1 i App.1-36 l 1 I 1 ARTICLE IV SCOPE OF AS$1 STANCE 4.1 It requested under this Agreement, the responding party or parties will provide tralned and ; experienced personnel to perform off-site radiation protection activities to the requesting party as those persons may be available to th6 responding party up to a maximum of six (6) such persons. All equipment intended for use by the responding personnel except
; personal dotimeters and certification documents (such as certifications of Health Physics training, instrument training and dose exposure records), shall be the responsibility of the requesting party to provide. The responding party or parties may use their own equipment if agreeable to the requesting party. However, use by the responding party or parties of their own eaulpment shall in no way alter the duties and obligations imposed upon the parties by this Agreement.
4.2 Emergency assistance provided by the responding party or parties shall continue until their personnel are relieved by the requesting party, the Federal or St6te emergency teams, or by the need of the responding party to answer an emergency at its own facilities, in no event shall such assistance be required for a period in excess of two (2) weeks for any one emergency including transportation time to and from the location of the emergency. 4.3 Exposure to personnel provided by the responding party or parties shall be limited to off-site radiation, and such exposure shall be kept as low as practicable. 4.4 Wages. hours and other terms and conditions of employment applicable to loaned personnel shall be those of the party providing such personnel. t 4.5 Personnel provided by the responding party or parties shall, at all times during the period l In which emergency assistence is being provided, continue to be employees of the responding party or parties and shall at no time and for no purpose be deemed employees of the requesting party. ARTICLE V REIMBURSEMENT FOR EMERGENCY ASSISTANCE RENDERED 5.1 The requesting party shall reimburse each responding party for all costs and expenses incurred by each responding party in providing emergency assistance hereunder. Such CCsts and expenses shall include. 5.1.1 Salaries and wages paid to loaned personnel (including supervisors) for paid tima j spent in the requesting party's service area, and paid time for travel to and from I such service area; l l l l l
y - ( ! !,, RERP Plan
- Revision 1 App.1-37 I 5.1.2 A percentage of the total of such wages and salaries, as determined by the responding party, reflecting expenses incurred for; l 5.1.2.1 Compliance with Worker's Compensation laws; 5.1.2.2 Payroll taxes; 5.1.2.3 Hospitalization, surgical and medical coverage
5.1.2.4 Pensions and life insurance; f 5.1.2.5 Vacation, holiday and sick pay; 5.1.2.6 Travel accident insurance: 5.1.3 Transportation to and from the requesting party's service area, including the cost of travel accident insurance purchased expressly for coverage during such transportation: 5.1.4 Food and lodging: 5.1.5 Personal expenses specifically etireed to between the requesting and responding parties; 5.1.6 Charges, at the rates internally used by the responding party, for the use of transportation equipment and other equipment requested; and 5.1.7 Any further costs specifically agreed to between the requesting and responding parties, s 5.2 All time sheets and work records pertaining to loaned personnel shall be maintained by the responding party. 5.3 All charges shall be psid by the requesting party to each responding party within ten (10) days after receipt of an invoice, itemized to the satisfaction of the requesting party. l i
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RERP Plan Revision 1 ; App.1-38 l l ARTICLE VI I INDEMNIFICATION i 6.1 The requesting party shallindemnify and hold harmless each responding party from and , against any and all liability for loss, damage, cost or expense which the responding party ; shall incur by reason of bodily injury, including death, to any person or persons. or by ' f reason of damage to or destruction of any property, including the loss of use thereof, , arising out of or in any manner connected with the giving of emergency assistance to the t requesting party. l 6.2 in the event of bodily injury, including death, to any employee of the responding party, or ! in the event of damage to or destruction of any property of the responding party, the i requesting party shall indemnify the responding party for such loss in the following manner; t f' 6.2.1 If such loss is covered by an insurance policy purchased by the responding party from a third party carrier, the requesting party shall make reimbursement to the ; extent such losses increase the responding party's insurance costs, whether such increase in premium refunds, or both; , 6.2.2 If such loss is not covered by an insurance policy purchased by the responding party or exceeds such coverage, the ret uesting party shall make reimbursement to the extent of the claims or benefits actually paid or the losses sustained by the responding party. ARTICLE VL t MODIFICATION 7.1 At any time after the date of this Agreement any party by giving not less than thirty days written notice to the other parties, may from time to time call for reconsideration of the ; terms and conditions of this Agreement. If such reconsideration is called for, the ! authorized representatives of the parties shall meet as promptly as convenient and discuss any of the terms and conditions of this Agreerr ant. No party shall be under any obligation to agree to any rnodification for supplement not satisfactory to it. Any agreement modifying or supplementing such terms and conditions shall be in writing, signed by all parties, and shall specify the date such modification or supplement shall become effective. ARTICLE Vill PLAN EXERCISING 8.1 The parties agree to provide, at their own expense, personnel to observe or assist in demonstrating the effectiveness of a nuclear generating station's emergency plan as may be required by that nuclear generating station's NRC approved emergency plan.
a. RERP Plan Revision 1 ; App.1-39 i J ARTICLE IX TERM OF AGREEMENT j i 9.1 This Agreement shall oe for a term of one (1) year and from year to year thereafter j unless and until terminated as provided for in Section 9.2 below. l 1 9.2 Any party, upon sixty (60) days prior written notice to all other parties, may terminate I this Agreement at the expiration of any successive one (1) year term, i IN WITNESS WHEREOF, the parties hereto cause this Agreement to be executed by their duly authorized officers on duplicate original pages attached hereto and made a part hereof. CONSUMERS POWER COMPANY INDIANA MICHIGAN POWER COMPANY By: D. P. Hoffman /s/ By: Title. _ VP - Nuclear Operations
Title:
Date: July 10,1988 D6to: DETROIT EDISON THE CLEVELAND ELECTRIC ILLUMNIATING COMPANY By: By:
Title:
Title: Date: Date: THE TOLEDO EDISON COMPANY By: By:
Title:
Title: Date: Date: i I
E < r r. CERP Plan [- ,, Revision 1
, App.1-40 IN WITNESS WHEREOF, the parties hereto cause 17:13 Agreement to be executed by their duly authorized officers on duplicate original pages attached hereto and made a part hereof.
CONSUMERS POWER COMPANY INDIANA V,1CHIGAN POWER COMPANY Sy: By:
Title:
Title: Date: Date: DETROIT EDISON THE CLEVELAND ELECTRIC ILLUMNIATING COMPANY By: _W. S. Orser /s/ By:
Title:
VP - Nuclear Operation
Title:
Date: August 4,1988 Date: THE TOLEDO EDISON COMPANY By:
Title:
Date: i
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il' ' RERP Plan i < Revision 1 l
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App,1-41
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'j- . IN WITNESS WHEREOF, the par.!ss hereto cause this Agreement to be executed by their duly l authorized officers on duplicate original pages attached hereto and mhde 'a part hereof. ;
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, , CONSUMERS POWER COMPANY INDIANA MICHIGAN POWER COMPANY
. By: By: ;
Title:
Title: ,_
, Date: . Date:
O I DETROIT EDlSON THE CLEVELAND ELECTRIC ILLUMNIATING COMPANY j i, i By: By:
Title:
Title: , I
,-. , Date: Date: _
l: 1 ( THE TOLEDO EDISON COMPANY a By: D. Shelton /s/
Title:
VP - Nuclear 3 Dato: July ' 22,1988 -
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Revision 1 [ ;r' App.1-42 r ll lN WITNESS WHEREOF, the parties hereto cause this Agreement to be executed by their duly authorized officers on duplicate original pages attached hereto and made a part hereof. h: 7- [ . CONSUMERS POWER COMPANY INDIANA MICHIGAN POWER COMPANY l [, [- By: , By: 1 P. Alexich /s/ ik
Title:
Title: Vice President Date: Date: August 12,1988-DETROIT EDISON THE CLEVEf.AND ELECTRIC ILLUMNIATING COMPANY By: By: j
Title:
Title: l I Date: Date: ! A i
- THE TOLEDO EDISON COMPANY !
I By: l
Title:
Date: l (- g L , 1.- i 1 l l l
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, RERP Plan '
b' > Revision 1 r App.1-43 F. r (' IN WITNESS WHEREOF, the perties hereto cause this Agreement to be executed by their duly + authorized officers on duplica:. original pages attached hereto and made a part hereof. l f-
!' CONSUMERS POWER COMPANY INDIANA MICHIGAN b POWER COMPANY ., i By: _
By:
Title:
Title: I Date: Date: , E - DETROIT EDISON' THE CLEVELAND ELECTRIC ILLUMINATING COMPANY 4 By: By: A. Kaplan /s/
Title:
Title:
VP - Nuclear Group Date: Date: July 15,1988 I THE TOLEDO EDISON COMPANY ls , By: 1
Title:
1, L Date: j i 1 )' l,< l - 4 1 i
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App.1-44 h . [g ' l 1 MEMORANDUM OF AGREEMENT p > i- between i f PEOPLES COMMUNITY HOSPITAL AUTHORITY ' t and DETROIT EDISON COMPANY L for
' RADIOLOGICAL EMERGENCY RESPONSE PLAN L
THIS AGREEMENT made and entered into as of the 1st _ day of January ._ 1988,' by and - between Peoples Communit/ Hospital Authority, a State Agency, ("the Authority") and Detroit .! Edison, a Michigan and New York Corporation. j
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WITNESSETH: WHEREAS, the Authority is the owner and operator of Seaway Hospital (the " Hospital") and maintains JCAH accreditation located in the County of Wayne, Michigan; provides emergency-medical service including facilities for the treatment of radiologically contaminated patients and, 1 WHEREAS, Detroit Edison, owns electric facilities, including Fermi 2 Nuclear Generating Station, and . I WHEREAS, the parties desire to have aval'able adequately trained and experienced emergency . personnel in the event of a medical emergency at the Fermi 2 Power Plant, j 1: NOW, THEREFORE, it is agreed between the parties as follows: ) 1
- 1. REQUESTS FOR EMERGENCY ASSISTANCE: f j
1.1 in the event of injury to any person (s) on property owned or utilized by Detroit ' Edison as part of an emergency response, the Hospital will be notified by an j authorized person of Detroit Edison or EMTS, Inc. Ambulance Service as an ' authorized emergency transport carrier, that an injured person (s) is (are) being transported to the Hospital needing emergency medical attention. 1.2 If the injury is non-radiologically related, notification to the Hospital will be made h through procedures established for responding to any normal request for emergency medical service by calling Detroit Edison at 671-3883 or 671-3884, or EMTS can call on their hospital compatible radio frequency. , l a
l {o s. S RERP Plan i k"< Revision 1 App.1-45 ; 1.3 if the injured person (s) is radiologically contaminated, the request for medical attention will be made by calling 671-3883 or 671-3884 for Detroit Edison, or ;
". EMTS can call on.their hospital compatible radio frequency. This notification will .
provide for implementation of the Hospital's radiological contingency emergency l plan. The injured person (s) will normally undergo decontamination procedures on. the Fermt 2 site prior to transport to the Hospital. However, if immediate treatment of the injury is vital, that treatment will take precedence over decontamination. A person trained in health physics monitoring techniques will,
- A accompany any radiologically contaminated individual in the ambulance enroute to 'j
'- the hospital and remain at the Hospital as needed to continue health physics i monitoring.
1.4 At the time of the request for emergency medical services, the Hospital will be , provided with necessary information relative to the injured person (s) status as l defined in mutually agreed upon operating procedues. ; i'
- 11. SCOPE OF ASSISTANCE: P i
?1 Emergency medical service should be made available to Detroit Edison on a 24-hour per day, seven day per week basis.
2.2 If personnel are not in-house, the Hospital will have at least one physician and one ' nurse available within about 2 hours who can supervise the evaluation and treatment of a radiologically contaminated injured member of the general public, resulting from an emergency event at Fermi 2, 2.3 The Hospital, as part of their qualifications for treating radiologically contaminated injured persons, will use its best efforts to provide emergency equipment for treatment of a radiologically contaminated person (s) at the hospital emergency facility. 2.4 Detroit Edison will provide the Hospital with an emergency supply cabinet which will contain the items listed on the attachment to this agreement. This cabinet will be located on the Hospital's prensises and should be locked when not in use. A master key to this cabinet will be retained by the Hospital 2.5 Detroit Edison will be responsible for disposal of all radiologically contaminated waste material (for example. cleansing liquids) on the Hospital's premises resulting from treatment of a contaminated person (s) from the Fermt 2 site. , 2.6 Detroit Edison or its contractor will conduct annual training sessions for the Hospital personnel who have emergency medical responsibilities defined in the emergency medical plan. 2.7 Detroit Edison will make available technical information and treatment protocols for contaminated injured personnel. 2.8 Detroit Edison or its contractor will conduct annual emergency medical drills and will provide the Hospital with a copy of the written drill evaluations.
w $ RERP Plan Revision 1 App.1-46 2.9 Detroit Edison will be responsible for maintenance of the supply cabinet. 2.10 Detroit Edison will be responsible for payment of services rendered to its employees. { 111. MODIFICATION 3.1 At any time after the date of this Agreement either party, by giving not less than thirty days written notice to the other party, may call for reconsideration of the terms and conditions of this Agreement. If such reconsideration is called for, the ' authorized representatives of the parties shall meet as promptly as convenient and l' discuss any of the terms and conditions of this Agreement. No party shall be under any obilgation to agree to any modification or supplement not satisfactory to it. Any agreement modi'ying or supplementing such terms and conditions shall in writing, signed by both parties, and shall specify the date such modification or - supplement shall become effective. IV. TERM OF AGREEMENT 4.1 This agreement shall continue for a term of two (2) years from the date of signing and bi-annually thereafter unless and untlI terminated as provided for in Soction ,
4.2 following
]
1 4.2 . Either party to this a0reement may, upon sixty (60) days written notification to the other party, terminate this Agreement at the expriation of any successive two (2) year term. IN WITNESS WHEREOF, the parties hereto cause this Agreement to be executed by their duly authorized officers.
. DETROIT EDISON COMPANY PEOPLES COMMUNITY HOSPITAL AUTHORITY BY D.C. Metcalf /s/ BY J. F. Melling /s/
TITLE Sr. Contracting Specialist TITLE Secretary BY D. J. Pizzimenti /s/ Chairman, Board TITLE of Directors DATE 3/8/88 DATE 2/25/88 l 1 /
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k e , [" RERP Plan 1 Revision 1 .l App.1-47 ; k.. ATTACHMENT L-4 l EF-2-FSAR TABLE'L-1 TYPICAL EMERGENCY SUPPLIES FOR HOSPITALS ' ) Set of hospital emergency procedures Eight pair of coveralls Four pair of lab coats , Eight pair. of rubber overshoes , 100 pair of plastic choe covers ! 50 pair of surgeon's gloves i < Twelve surgeon's caps Six hoods 3 Plastic sheeting Assorted plastic bags y 1' , . Five 50-lites plastic bottles Ten feet of 1/2" Tygon tubing Two sets of nasal irrigation equipment , Six bottles of saline solution i Two boxes of detergent Two cans Septisol 1000 swahs , Two handbrushes Decontamination chemicais (proper quantity in bottles with water addition line marked):
- 1. Four bottles Titanium dioxide
- 2. Four bottles Potassium permanganate
- 3. Four bottles Sodium bisulfite i L I
T - r , RERP Plan Revision 1 App.1-43 Twelve plastic beskers 24.vlais for collecting excised tissue Labels for bottles and vials Ten rolls of masking tape - 2" wide 50 feet of yellow and magenta tape Assorted radiation / contamination signs ; Box of swipes Dosimeter charger ,
-15 pocket dosimeters 15 Thermoluminescent dosimeters Frisker (RM-14 or L-177 with HP-210 probe or equivalent)
Dose Rate Meter Portable Air Sampler , Alkaline Batteries (spare) f 4 i l' 1 l '. l i; l 1 1
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RERP Plan Revision 1 App.1-19 + s A Department of Energy . '(, ~
- Chicago Operations Office 9800 South Cass Avenue Argonne, Illinois 60439 L
February 10,.1987 Mr, Thomas Randazzo, Director
-,- Regulatory Affairs Detroit Edison K '
- 6400 North Dixie Highway
, Newport, Michigan 48166
Dear Mr. Randazzo:
1
- The U. S. Department of Energy (DOE) will respond to requests for radiological assistance from ;
licensees, Federal, State, and local agencies, private organizations, or individuals involved in or i cognizant of.an incident believed to involve. source, byproduct, or special nuclear material as - defined by the Atomic Energy Act'of;1954, as amended, or other lonizing radletion sources. i Unless DOE or a DOE contractor is responsible for the activity, ionizing radiation source,'or radioactive material involved in an incident, DOE radiological assistance will be limited to advice and emergency action essential for the control of the immediate hazards to health and s6fety. Radiological emergency assistance will be terminated as soon as the emergency situation is under control. Therefore, responsibility for postincident recovery, including further action for the i protection of individuals and public health and safety, should be assumed tiy the appropriate responsible Federal, State, or local government, or private authority as soon as the emergency conditions are stabilized. l t if we can be of further assistance, please feel free to contact us. 1 Sincerely, 1 Hilary J. Rauch /s/ l Manager ; cc: Director, Office of Nuclear Safety, HQ (EH-13/GTN) i U.S. Nuclear Regulatory Commission, Office of ) Inspection and Enf reement, Region 111 ; 4 9
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App.2-1 ; i j I
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i l APPENDIX 2: J EMERGENCY BROADCAST SYSTEM PLAN 5 l l 1 t 1 l l~ I l l< \ l l l I
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rc 9' j .' o RERP Plan Revision 1
!; App.2-2 l'
; EBS CHECK SHEET FOR BROADCAST STATIONS
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Operational Area Monitoring Assignment (Call /Freq)
- 1. All personnel trained in EBS procedures and in the use of EBS squipment. I
- 2. EBS tone encoder / decoder. installed and operating. ,
- 3. Correct station monitored, according to state or local EBS Plan.
- 4. Weekly EBS test received and lo0ged.
- 5. Weekly EBS test transmission made and logged, i
- 6. Orange.EBS Checklist immediately available.
, _,_,7 . Red Authenticator envelope immediately availablo.
- 8. Copies of state and local EBS Plans immediately available.
- 9. Copy of FCC Rules and Regulations (Subpart G and Part 73.1250) available. l I
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9 d k-t MICHIGAN EMERGENCY BROADCAST SYSTEM FOR SOUTHEASTERN MICHIGAN l ' l[ Standard Operating Procedure (; c. a [ , The followinD plan has been reviewed and ar. proved by the undersigned. John P. Begin /s/ 5/2'{/84 _ r
.c Chairman, Michigan State Date Emergency Communications Committe Rod Hansen /s/ 5/22/84i ,}
Chairman, Southeast Michigan Date , Emergency Communications Committee Sgt. James N. Hostutler /s/ _ 5/24/84 [ Second District Emergency Management Date Coordinator ' l' 1 . 1 1 i i I
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{ 1 RERP Plan ~ l Revision 1 l App.2-4 EMERGENCY BROADCAST SYSTEM PROCEDURES FOR SECOND DISTRICT (SOUTHEASTERN MICHIGAN) OPERATIONAL AREA INCL.UDING ; MONROE, WAYNE, OAKLAND, MACOMB AND ST. CLAIR COUNTIES PURPOSE The purpose of this document is to provide procedures agreed upon by the broadcast industry, the Michigan Department of State Police, the National Weather Service, the Federal Emergency Management Agency, the Federal Communications Commission and appropriate local civil ; defense and emergency preparedness officials that will permit the issuance of emergency ' information and instructions during threatened or actual danger to life and property. AUTHORITY Title 47 U.S.C.151,154 (1) and (o), and 303 (r); Chapter I, Part 73, Subpart G. Federal Communications Commitsion Rules and Regulations, Radio Broadcast Services, Emergency
- Broadcast System (EBS) and Emergency Action Notification System (EANS) as pertain to day-to-day emergency operation.
INTRODUCTION , These procedures, designed to complement present and future National and State Emergency Broadcast System programs,'were developed by the Second District (Southeastern Michigan) L Operational Area Emergency Communications Committee. Contributing to the development were i the Emergency Management Division, Michigan Department of State Police; the National Weather Service and civil defense and emergency preparedness officials in Monroe, Wayne, Oakland, Macomb and St. Clair Counties. This document provides background information and prescribes specific procedures for the L broadcast media to use in disseminating emergency information and warnings to the general I public in the operational area, or any portion thereof, within the stationc' broadcast coverage > capability. The plan is designed to encourage development of relationships between local authorities and statione serving counties and communities within the operational area. It also encourages establishment of county or bi-county emergency communications subcommittees to arrange for , EBS activation during times of emergency affecting only portions of the operational area.
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l And15 snvisions involvement or the broadcast media, as may be appropriate, in mutual aid arrangemems with media and public officials in Michigan and Ohio counties and in the Province of Ontario, Canada, contit,uous or adjacent to the operational area. [ 1 l l
'""9-' +- w - _ - - n _ ,_--_ _ - - _ _ _ - _ - - - _ - - - - , - , , - _ _ - - - - , - - _
5
% 6 RERP Plan Revision 1 l App.2-5 ;
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. Acceptance of this plan, and participation in it, shall not be deemed as a relinquishment of H program control and shall not be construed to prohibit a licensee from exercising Independent discretion and responsibility in any situation, Stations originating emergency communications ;
shall be deemed to have been conferred rebroadcast authority (FCC Rules 73, 935 (6). The role of management of each broadcast station exercising discretion regarding the broadcast of emergency information and instructions to the general public Is provided by Federal Communications Commission Rules and Regulations, Part 73, Subpart G. 4 DEFINITIONS Emergency: A situation posing an extraordinary threat to the safety of life and property. Examples include: tornadoes, floods, earthquakes, icing conditlor.s, bilzzards, heavy snows, , widespread electric power failures, widespread heating energy shortages, major explosions and fires,' nuclear hazards, transportation accidents involving hazardous materit,Is, Industrial accidents ' with severe environmental pollution potential and massive civil strife. Activating Officials: The person (s) designated by state and local governments participating in this plan to make emergency announcements / broadcasts. Participating Broadcasters: Management and/or staff personnel designated to activate EBS , operations in behalf of radio, television or cable licensees subscribing to this plan. GENERAL PROCEDURES FOR USE OF BROADCASTING FACIL! TIES A. Weather Emergencies l ' L 1. When a tornado watch or severe weather watch is issued by the National Weather ' Service (NWS), all radio and television stations in the operational area will receive hard copy via Associated Press (AP), United Press International (UPI) or the NOAA Weather l Wire, NOAA Weather Radio also will disseminate watch information.
- 2. When a tornado warning is issued by the National Weather Service, the same means of dissemination will be used. Additionally, the warning will be telephoned by NWS to j the Primary Common Program Control Station -1 (CPCS-1), WJR, WHYT(FM).
WJR, WHYT(FM) will activate the Operational Area EBS and issue appropriate warning information (see IMPLEMENTATION section).
- 3. Operational Area EBS will be activated only under extreme circumstances for other weather warnings, although participating stations are encouraged to broadcast them promptly.
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B. Non-Weather Emergencies
- 1. County or murilcipal police, fire, civil defense or emergency preparedness officials will .
contact Michigan State Police (MSP) Emergency Management Division, Second District t Headquarters, by means prescribed in their state-approved plans and annexes. v 2. After conferring with the district coordinator, the chief executive officer of the affected community of his designee will make a determination whether to request activation of operational area EBS through the CPCS-1, WJR, WHYT(FM). 7 C. Emergencies Affecting Only a Portion of the Operational Area
, 1. Police, fire, civil defense or emergency preparedness official in the erfected community will contact radio and/or television station (s) serving that community to request i
local-level EBS activation, utilizing call-back authentication. l L' 2. Police, fire, civil defense or emergency preparedness official in the affected commualt)
-{
1 t will contact the chief executive officer or his designee for communication of j information to WJR, which will determine potential need for operational area EBS activation. 3, Participating broadcasters are urged to direct viewers and listeners in the affected community to tune to the station (s) that have specific local-level information useful only to residents of that community. l i D. If, for any reason, WJR, WHYT(FM) is incapacitated, CPCS-2 stations are to be notified by I activating officials (see IMPLEMENTATION section). l l E. In National or State emergencies, time allotted for local emergency programming will be j l originated under procedures in (B) above and where practicable under procedures in (C)
- above.
1 IMPLEMENTATION i
'l
, A. Procedures for Activating Officials ! l' l l 1. Weather Emergencies i l-
- a. National Weather Service, Metropolitan Airport, requests activation of EBS via l' NOAA Weather Wire, Weather Radio and direct telephone contact with WJR at 873-9840, 875-0709, 875-4480, 873-2370 or 875-4440. i, 1
1
\l RERP Plan
[! , Revision 1 1 App.2-7 ,
- b. City or county c!vil defense'or emergency preparedness official or law enforcement ;
officials, while contacting National Weather Service, may make direct request for EBS activation by telephoning WJR at above-listed numbers, fully identifying self, i location and source of. warning information. , i
- c. Michigan State Police, Northville Headquarters, may request activation by telephone
' call to WJR at above numbers or via Remote Pickup Unit.
- 2. Non-Weather Emergencies
- a. Aftet conferring with the district coordinator, the chief executive officer of the affected community or his designee'will make e determination whether to request
. activation of operational area EBS through the CPCS-1, WJR, WHYT(FM).
l b. County or municipal civil defense or emergency preparedness official, law i< enforcement official or ch;ef executive officer or his designee contacts CPCS-2, L CPCS-3, or other participating radio and/or television station (s) to request EBS I activation of affected portion of operational area.
- 3. In the event WJR, WHYT(FM) is incapacitated, activating officials will establish direct
. contact with all of ttio following CPCS-2 stations:
l i WCXI, Detroit, telephone: 341-7535,676-2482 l lj WWJ, Detroit, telephone: 222-2695,222-2134 WPHM, Port Huron, telephone: 987-4100,989-8770 t I B. Procedures for Participating Broadcasters i
- 1. Upon receipt of request to activate EBS at operational area level, senior employee of I
news, program or engineering department at WJR will evaluate information and, upon deciding to honor request, will proceed as follows: ;
- a. Broadcast program interruption announcement, to be furnished.
- b. Transmit EBS tones signal for twenty-two seconds. .
- c. Broadcast EBS activation announcement, including name of agency requesting <
activation and time of activation. l 1
- d. Broadcast emergency information, repeating as necessary, citing authority for information and stressing any time frame.
1' f
't t
7- ,
, 3 bo ' J. - .
o. l 1- c. RERP Plan Revision 1 f App.2-8 l 9 2. . At its discretion, each primery station, having monitored the WJR activation, will follow ,\- procedures,' a, b, c, and d above.
- 3. Upon receipt of request to a.ctivate EBS in only its portion of the operational area, participating broadcaster will authenticate the request by telephone call-back and, if request is honorek y Mw procedures a, b, c, and d abeve aN/ telephone to WJR for potentia! use througnuut operational area.
- 4. If EBS activation does not expire at a previously-specified time, information on termination ib to be secured by WJR or other originating station from authorizing officer of Michigan State Police or other agency and broadcast as follows:
- a. Broadcast program interruption announcement, to be furnished,
- b. Transmit EBS tones signal for twenty-two seconds.
- c. Broadcast EBS termination announcement, including name of agency adhorizing termination and time of retention.
s
- d. Resume normal programming.
- 5. Upon completion of above procedures, make appropriate notations of activity in station - 4
, records. (Refer to FCC Regulations, Part 73, Subpert G,73.937). ,
IMPORTANT NOTE: To avoid unnecessary public confusion, alarm and possible panic, personnel of all broadcast stations involved in EBS activation must be cautious in i providing information and news pertaining to the emergency. All messages are to be based on confirmed, factual Information. MONITORING ASSIGNMENTS , All participating radio and television stations and cable relay operations in the operational area are to monitor WJR-AM (760 KHZ) WHYT(FM) (96.3 MHZ) which are designated Primary CPCS-1. , As a secondary assignment, participating broadcasters in Wayne and Monroe Count'es are urged to monitor WCXI-AM (1130) or WCXI-FM (92.3 MHZ). In Oakland and Macomb Counties, the , secondary assignment is WWJ-AM (950 KHZ) or WJOl-FM (97.1 MHZ). And those in St. Clair j County should monitor WPHM (1380 KHZ). These are Primary CPCS-2 stations. Further, it is strongly suggested by the Operational Area Emergency Communications Committee that all participating broodcasters maintain the capability of monitoring either the NOAA Weather Wire or Weather Radio. i
p
'i; V. ' , ; l '
k..t .[fb Ije RERP Plan j I' ; ,'l x Revision 1 n , App.2-9 '
.$[
' CONCLUSION ,
f
.y a, .
.f . Acceptance.of this plan by the participating stations, the Michigan Department of State Police,
' r the National Weather Service, the Federal Emergency Management Agency, and the Federal
-) ' Communications Commission shall constitute full authority for its implementation and use, sf pursuant to FCC rules cited above.
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E , bw RERP Plan Revision 1 ' App.2-11 ' c-I
- j. MACOMB (469-5270)
Official-In-Charge (941-3721) Mr. John P. Perry, Coordinator National Weather Service Office Macomb County Emergency Services Metropolitan Airport o 43565 Elizabeth Road . Building 348 Mt. Clemens, MI 48043 Detroit, MI 48242
- 1. -
l MONROE (241-6400) Mr. C. R. Snider (668-2220) State Area Manager Mr. Jon R. Eckert, Director / National Weather Service Coordinator Forecast Office [' ' Monroe. County Civil Preparedness 200 East Liberty Street 106 East First Street Ann Arbor, MI 48107 ! Monroe, MI 48161 OAKLAND (858-5300) Mr. Paul Phelps, Director Oakland County Disaster Control 1200 North Telegraph Road Pontiac, MI 48053 ST. CLAIR (985-8115, Ext. 30) Mr, James VanConant, Coordinator 1 L St. Clair County Emergency Services 204 Bard Street Port Huron, MI 48060 WAYNE (326-0811) , Mr. Mitchell Kozak, Director l- Wayne County Emergency Preparedness i' Building A, Wayne County Complex ' L Westland, MI 48185 l l STATE POLICE (346-9550) Sgt. James Hostutter l Second District Coordinator
- 1. Secon:! District Headquarters i Michigan Department of State Police .
i-42145 West Seven Mile Road Northville, MI 48167 l l l l. l' 1 . . . -. _ _ _ . . _____________________ _ _ _ _ - _ __.
, u
{; RERP Plan lj- , j ' Revision 1 , T App.2-12 L, l.
.SECOND DISTRICT (SOUTHEASTERN MICHIGAN) OPERATIONAL AREA l L. s EMERGENCY COMMUNICATIONS COMMITTEE e
P Chairman Vice-Chairman 1 Ar. Rodney Hansen Mr. Gregory Urbiel 4.adio Station WJR Radio Station WWJ 2200 Fisher Building P.O. Box 5005 , Dctroit, Michigan 48202 - Southfield, Michigan 48086 (Business: (313) 875-4440). (Business: (313) 423-3300) 1 Members are management-level representatives of all participating broadcasters. t i: h , l I l l l l l' l
p) '"~ J e p n ; n RERP Plan f.f Revision 1 l
? ;3 ,
App.2-13 .; f'r ' l
~ BROADCAST STATIONS - SOUTHEASTERN MICHIGAN OPERATIONAL AREA b .
, Ca.11. Sign -
' .g
' City
. Frequency Facilities -
ESS Designation WAHS (FM) WCXI' WGPR (FM) .
- AUBURN HEIGHTS , DETROIT DETROIT C 89.5 ~ 1130' 107.5 0.1 KW 140 FT 10/50 KW DA-2 U 50 KW 360 FT PRIMARY - PRI CPCS-2 PRIMARY WMJC (FM) WCXI-FM WGPR 'N l
' BIRMINGHAM DETROIT DETROIT 94.7 92.3 CH 62 10 KW 950 FT 21.5 KW 700 FT 1000 KW 970 FT PRIMARY PRICPCS-2 PRIMARY 1; WBFH (FM) .
WCZY (FM) WHYT (FM) BLOOMFIELD HILLS' DETROIT DETROIT 88.1 95.5 96.3 0.01 KW 100 KW 430 FT 50 KW 480 FT PRIMARY PRICPCS-3 PRI CPCS-1 !
- p. 1
- l. WHFR (FM) WDET-(FM) WJBK-TV !
DEARBORN- DETROIT DETROIT l l 89.3 101.9 CH 2 ! 0 0.018 KW 60 FT 79 KW 450 FT 100 KW 1000 FT l
. ).I- PRIMARY PRI CPCS-3 . PRIMAHY WNIC WDIV (TV) WJLB (FM) l DEARBORN DETROIT DETROIT )
L. 1310 CH 4 97.9 ! 5 KW DA-2 U 97.7 KW 1010 FT 50 KW 490 FT $ p PRICPCS-3 PRIMARY PRIMARY i n WNIC-FM WDRO (FM) WJOI (FM) DEARBORN DETROIT DETROIT < l 100.3 93.1 97.1 , 50 KW 400 FT 20 KW 500 fT 12 KW 890 FT ,. , PRI CPCS-3 PRICPCS-4 PRI CPCS-2 WCLS (FM) WDTR (FM)
- 1) DETROIT DETROIT l 99.5 90.9 L 6.5 KW 870 FT 42 KW 540 FT PRIMARY PRIMARY i
u \ l1 l
RERP Plan Revision 1 App.2-14 4
- BROADCAST STATIONS - SOUTHEASTERN MICHIGAN OPERATIONAL AREA Con't WJR WORS (FM) WORB (FM) WBRB DETROIT DETRO'T FARMINGTON HILLS MT. CLEMENS 760 105.1 90.3 1430 50 KW U 50 KW 480 FT 0.01 KW 120 FT 0.5 KW DA-2 U PRICPCS-1 NON-EBS PRIMARY PRICPCS-4 WJZZ (FM) WRIF (FM) WHPR (FM) WLRS (FM)
DETROIT DETHOIT HIGHLAND PARK MT. CLEMENS , 105.9 101.1 88.1 102.7 34 KW 300 FT 27 KW 880 FT 0.01 KW 50 KW 410 FT
' PRIMARY PRI RELAY PRIMARY PRICPCS-4 i
WKBD (TV)- WTVS (TV) WCHB WOVI (FM) DETROIT DETROIT INKSTER NOVI l CH50 CH 56 1440 89.5 l- 2340 KW 960 FT 2090 KW 960 FT 1 KW DA-2 U 0.01 KW 64 FT PRIMARY PRIMARY PRIMARY PRIMARY / i l WLL2 (FM) WWJ WCAR WOPR (FM) l=, DETROIT DETROIT LIVONIA OAK PARK l- 98.7 950 1090 90.3 ! l 50 KW 480 FT 5 KW DA-N U - 0.25/0.5 KW DA-2 U 0.01 KW 101 FT ! 1: PRI CPCS-3 PRI CPCS-2 PRIMARY NON-EBS WLOV WWWW (FM) WSMA WBLD (FM) DETROIT DETROIT MARINE CITY ORCHARD LAKE l 1500 106.7 1590 89.3 5/500 KW DA-2 U 61 KW 510 FT 1 KW DA-D 0.01 KW 110 FT ; PRI CPCS-3 PRIMARY PRIMARY PRIMARY. l
. WMUZ (FM) WXON (TV) WEJY (FM) WSDP (FM) ,
DETROIT DETROIT MONROE PLYMOUTH ; l 103.5 CH 20 89.5 88.1 ! 115 KW 295 FT 2190 KW 960 FT 0.01 KW .150 FT 0.2 KW 73 FT NON-EBS PRIMARY PRIMARY NON-EBS ; WMOC (FM) WXYZ WHND WPON j DETROIT DETROIT MONROE PONTIAC - 104.3 1270 560 1460 190 KW 360 FT 5 KW DA-N U 0.5 KW DA-D 0.5/1 DA-N U PRIMARY PRICPCS-3 PRIMARY PRIMARY WOBH WXYZ-TV WTWR (FM) WHLS DETROIT DETROIT MONROE PORT HURON 1400 CH 7 98.3 1450 0.25/1 KW U 316 KW 1000 FT 3 KW 3000 FT 0.25/1 KW U PRI CPCS-4 PRIMARY PRIMARY PRI CPCS-3 s
p.. ; 70= i , 4 i RERP Plan j p Revision 1 i App.2-15 1 C' , E BROADCAST STATIONS - SOUTHEASTERN MICHIGAN OPERATIONAL AREA Con't c. WORW (FM) - PORT HURON U i: ' 91.9 ' s 0.18 KW 21 FT - p . PRIMARY '
.WPHM
' PORT HURON r 1380 5 KW DA-2 U -
~ PRI CPCS-2 l: .
- l. WSAO (FM)
PORT HURON . 107.1 3 KW 300 FT , PRI CPCS-4 'I WSGR (FM)
. PORT HURON .
91.3 _ >} i.. 0.01 KW 87 FT NON-EBS l WEXL ROYAL OAK 1340 , 0.25/1 KW DA-D U PRI CPCS-4 WSHJ (FM) SOUTHFIELD 99.3 , L-0.125 KW 43 FT PRIMARY e' WPHS (FM) WARREN
- 1. 91.5
'O.01 KW
~
PRIMARY l - I
c- , f.-. :
- p. RERP Plan P Revision 1 l ,
s App.3-1
- t r
APPENDIX 3: a.- LIST OF RERP IMPLEMENTING AND ADMINISTRATIVE PROCEDURES i: r 1.
, 'i l'
1 l ! 1' i b k l lb ., 1
- l. :
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._-- _.) s'_ _ _ _ - __ _._________. _ ___
P .' .,> j I, . f ... , ,
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'i C RERP Plan j 9 Revision 1 App.3-2 .
t FERMI 2 l ' RERP IMPLEMENTING PROCEDURES p INDEX ,. m . , , RERP PLAN SECTION ; i EP NO. TITLE IMPLEMENTED
). , ; 101 Classification of Emergencies D !
L , (; 102- Unusual Event D l ' 103 Alert D 104, Site Area Emergency D 105- General Emergency D h .110 Organization and Responsibilities B .
'201-03 Variances from Routine Radiological J,K Practice and Procedures During an '
Emergency 1 204-01 Damage Control and Rescue Team B,K,L ', l' 205-01 Security Force B,J l 220 Personnel Monitoring and Radiological B,H,1,J,K,L, l . Emergency Teams , L-1 i LN -
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i p i p' , > ; RERP Plan - i re
' Revision 1 2 App.3-3 .l .. \
r L RERP IMPLEMENTING PROCEDURES 1
- s. .
3 INDEX (Continued). l' RERP PLAN 6 SECTION h,. EP NO. TITLE IMPLEMENTED l' '225 Radiological Medical Emergencies L e 226 Potassium lodide J 290 Emergency Notifications J ; 292 Detroit Division Dispatch and Report B,EF Center: Emergency Notifications !
^
301-01 Technical Support Center . B,F H,1,J,K,M '. 302-01' Operational Support Center B,F,H / , . s 303-01 Emergency Operations Facility B,F,H,1,J,K,M j.; 304-01 Alternate Emergency Operations H l> Facility 402 ' Responsibilities of the Recovery B,M '! l Organization l l> : i L I
Is. r RERP Plan !J Revision 1 App.3-4
- . ,. j RERP IMPLEMENTING PROCEDURES INDEX (Continued)
RERP PLAN SECTION EP NO. TITLE IMPLEMENTED 530 Assembly and Accountability of J Personnel Within the Protected Area and Evacuation of the Owner-Controlled Area 540 Manual Off-Site Radiological Dose l Assessment Calculational Procedure - i Airborne Releases - Overview 541 Assessment of Abnormal'or Unplanned I Liquid Releases . ; 542 Radiological Doso Assessment 1 4 Calculational Procedure Using a Computer-Based Program - Airborne ; Releases a 545 Protective Action Recommendations 1,J 546 Calculation of Estimated Containment i High Range Radiation Monitor or i SGTS/AXM Monitor Readings if Instruments I are Inoperable or Offscale 547 Rapid Estimate of. Core / Fuel Damage l Based on Containment High Range ; Radiation Monitor f 548 Manual Calculations of Dose Adjustment i Factor for Lake Breeze Conditions 601 Public Affairs: Public Education and O i information 607 Public Affairs: Media Pool Operation G j 608 Joint Public Information Center G Operation
A t
!- l L i L RERP Plan j l
Revision 1 1 App.3-5 { [
! \
L RERP ADMINISTP.ATIVE PROCEDURES ! l INDEX l l RERP PLAN < l- PROCEDURE SECTION l NO, TITLE IMPLEMENTED I RAP-PR1-01 Radiological Emergency Response P ! Preparedness Procedstres RAP-EM1-02 Maintenar.co of Emergency H i Response Facilities j i RAP-EM1-04 Drills and Exercises N,0 ]
)'
RAP-EM1-06 RERP Emergency Telephone B,E,H Directory and Emergency Call-Out ! List: Review and Update 1 l END i
)
, 5 i
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l I t l i i J
l !\r RERP Plan Revision 1 App.4-1 l t i t t i I t t I i APPENDIX 4 i LIST OF SUPPORTING PROCEDURES AND l DOCUMENTS IDENTIFIED IN THE PLAN ! i I i 8 l 4 f I i [ i-l h t I i L [ I t
,-- , =<,-r--, , a----g - - - t
P 7 r I 5 'i ; RCRP Plan Revision 1
- App.4-2 I
l SUPPORTING PROCEDURES AND l DOCUMENTS IDENTIFIED IN PLAN j INDEX - n I. i 1, 10 CFR 20 (Sections B,H,1,K)
- 2. 10 CFR 20, Appendix B Table 11, Column 2 (Section D) 3 i
- 3. 10 CFR 50.47 (Preface) l i, 4. 10 CFR 50.54(t) (Section P) !
- 5. 10 CFR 50, Appendix E, Section F (Section N)
- 6. 10 CFR 50, Appendix l (Section 1) ,
7, 44 CFR 350 (Section N)
- 8. NUREG-0654/ FEMA-REP-1, Revision 1, Criteria for Preparation and Evaluation of l Radiological Emargency Response Plans and Preparedness in Support of Nuclear Power i Plants (Preface, Sections B,J,P)
- 9. ' NUREG-0728, Revision 1, Report to Congress: NRC incident Response Plan (Sections A,C)
- 10. NUREG-0737, Clarification of TMl Action Plan R9quirements (Sections B,1) '
- 11. NUREG-0981/ FEMA-51, NRC/ FEMA Operational Rerponse Procedures for Response to a !
Commercial Nuclear Reactor Accident (Sections A.C) { i
- 12. U.S. NRC Regulatory Guide 1.23. Onsite M6:eorological Programs (Safety Guide 23) l (Section H)
- 13. U.S. NRC Regulatory Guide 1.3, Assumptions Used for Evaluating the Potential Radiological ,
Consequences of a Loss-of-Coolant Accident for Bolling Water Reactors (Section I) l
- 14. U.S. NRC Regulatory Guide 1.109. Calculation of Annual Doses to Man from Routirse
- Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1 (Section J)
- 15. Act 390 of the Public Acts of 1976 (Section A) ;
- 16. Fermi 2 Updated Final Safety Analysis Report (Sections H,1)
- 17. Fermi 2 Technical Specifications (Sections B,D,1) ;
3
,n. ---- -. - .-
m . i RERP Plan Revision 1 App.4-3
?~
t SUPPORTING PROCEDURES AND l DOCUMENTS IDENTIFIED IN PLAN . t INDEX (continued) , i
- 18. EPA 520/1-75-031, Manual for Protective Action Guides and Protective Actions for Nuclear
; incidents (Sections J.K) ! 19. Federal Radiological Emergency Response Plan (Sections A,C)
- 20. Michigan Emergency Preparedness Plan (Preface, Sections A,C)
- 21. Monroe County Emergency Operations Plan (Preface, Section A) ,
f r
, 22. Wayne County Emergency Operations Plan (Preface, Section A) l
- 23. Brownstown Township Emergency Operations Plan (Preface)
- 24. F6deral Register, Volume 43, Number 242, December 15,1978 (Section J) l
- 25. Sandla Report, SAND 77-1726, Public Protection Strategies for Potential Nuclear Reactor ;
Accidents: Sheltering Concepts with Existing Public and Private Structures (Section J)
- 26. PRC Engineeiing Study, revised May 1985, Estimate of Evacuation Times (Section J) l
- 27. POM Procedure 67.000.403, Inplant Dosimetry issuance (Section K) '
- 28. RPC-05, Respiratory Protection / internal Dosimetry (Section K)
- 29. POM Procedure 67.000.400, Personnel Decontamination (Section J) l
- 30. POM Procedure 67.000.405 Maintenance and Inventory of Radiation Protection Emergency <
Kits (Sections H,J)
- 31. FIP-RC1-01 Accessing and Working in Radiologically Controlled Areas (Section K) l 32. POM Procedure 65.000.200, issuance of Routine Thermoluminescent Dosimetry (Section K) .
l END l l l l l t
RERP Plan : Revision 1 i' App.5-1
)
I i APPENDIX 5: i l RERP PLAN CROSS-REFERENCE WITH NUREG-0654 j i I, 6 [ b b 4 D i s h t t l t i I
p . l L ! l l ji RERP Plan ! Revision 1 l App.5-2 RERP PLAN CROSS-REFERENCE WITH NUREG-0654 l NUREG-0654 RERP Plan j Requirement Description of Requirement Section ! I A.1.a identify State, local ard Federal emergency A . organizations intended to be part of overall { response organization, j A.1.b Specify concept of operation for each emergency A j organization. ' A.1.c illustrate interrelationships in a block diagram. A A.1.d Identify a specific individual by title in charge A.1, A.2, et all times of the emergency response. A.3 i I A.1.e Provide for 24-hour per day emergency response A6 and communications. ; A.3 Establish written agreements with support Appendix 1 organizations and/or governments. A.4 Ensure capability for 24 hour coverage for A.6,8.2 l protracted time and identify individual, by title, who is responsible for ensuring continuity of resources. B.1 Specify plant staff and responsibilities for all B (tB-1) { shifts and its relation to the retponsibilities : and duties of normal staff complement. l 1 B.2 Designate an Emergency Coordinator on shift. B.2.1 l B.3 Designate line of succession for Emergency B.2.1 Coordinator and identify specific conditions for higher level utility officials assuming this function. ; B.4 Establish Emergency Coordinator's functional B.2.1 responsihihties and clearly specify which ' responsiollities may not be delegated. B.5 Identify shift augmentation / minimum staffing as B (tB-1) iderstified in NUREG-0654, Table B-1. B.6 Include block diagram of interfaces established B (f B-2, between onsite organizations, State, and local fB-3,fB-4) organizations. ' B.7 Specify corporate, administrative, and technical B (tB-2) support personnel who will augment Table B-1 staff. Note: "t* indicates a Table; "f" indicates a Figure (tB-1 = Table B-1)
f \ L i RERP Plan ) Revision 1 App.5-3 j t RERP PLAN CROSS-REFERENCE WITH NUREG-0654 NUREG-0654 RERP Plan i Requirement Description of Requirement Section l B.7.a identify the individual responsible for logistical B (tB-2) i support. ) B.7.b Identify the individual responsible for technical B (tB-2) l support for planning and reentry / recovery operations. B.7.c Identify management interface with government B (tB-2) authorities, i B.7.d Identify the individual responsible for information B (tB-2) ' release to the media. l l B.8 Specify contractor or private organizations who may Appendix 1 i be required to provide technical support. B.9 Identify services to be provided by local agencies. Appendix 1 Col.a Specify those persons, by title, who are authorized C.1 i to request Federal assistance. C.1.b Specify what Federal resources are expected, C.1 , including estimated times of arrival. l C.1.c Specify what utility, local, and State resources C.1 are available to support Federal response. , C.2.b identify are individual to be dispatched to C.1 l governmental Emergency Operations Centers. ' C.3 Identify radiological laboratories and their H.1.4 general capabilities and expected availability H.3.2.2 ; for emergency use. l C.4 Identify nuclear and other facilities, individuals, C.2 or organizations providing assistance. Appendix 1 ; D.' identify emergency classification / action levels. D D.2 Include all initiating conditions from NUREG-0654 D ' Appendix 1 and all postulated accidents found in the Fermi 2 Final Safety Analysis Report. E.1 Esthblish procedures which prescribe methods of E.2 notification / verification. E.2 Establish procedures for alerting, notifying, and E.1.1 mobilizing Emergency Response Organization.
g >- I'k : l , RERP Plan
, Revision 1 App.5-4 l
! RERP PLAN CROSS-REFERENCE WITH NUREG-0654 NUREG-0654 RERP Plan Requirement Description of Requirement Section E.3 Establish contents of initial emergency messages. E.2.1
. E.4 Provide for follow-up messages from Fermi 2 to E.2.1 Offsite Authot;tles.
E.4.a Follow-up messages shall contain location, s.same, E.2.1 and telephone number of caller. E.4.b Follow-up messages shall contain date and time of E.2.1 incident. E.4.c Follow-up messages shall contain the class of E.2.1 emergency. E.4.d Follow-up messages shall contain type of actual or E.2.1 projected release and duration. E.4.e Follow-up messages shall contain quantity and E.2.1 height of release. E.4.f Follow-up messages shall contain chemical and E.2.1 physical form and estimates of relative quantitles and concentrations (noble gases, lodines, particulates) released. E.4.g Follow-up messages shall contain meteorological E.2.1 conditions (wind speed, directions, stability class, etc.) E.4.h Follow-up messages shall contain actual or E.2.1 projected dose and dose rate at site boundary. E.4.1 Follow-up messages shall contain projected dose E.2.1 and dose rate at 2,5, and 10 miles, including affected sectors. E.4.] Follow-up messag6) shall contain estimate of E.2.1 surface contamination. E.4.k Follow-up messages shall contah Fermi 2 emsrgency E.2.1 response actions underway. E.4.1 Follow-up messages shall contain protective action E.2.1 recommendations.
RERP Plan j Revision 1 j App.5-5 i RERP PLAN CROSS-REFERENCE WITH NURF.G-0654 i NUREG-0654 RERP Plan l Requirement Description of Requirement Section 1 E.4.m Follow-up messages shall contain request for E.2.1 , offsite support needed onsite. 1 i E.4.n Follow-up messages shall contain prognosis for E.2.1 l the event. { E.6 Establish administrative and physical means for E.3 notifying the public and define time needed to provide notifications and instructions to public within the 10-mile EPZ. E.7 Provide supporting information for public E.3 protective actions. - F.1.a Provide for 24-hour per day notifications to State A.6 and local governments. F.1.b Provide for communications with State and local H.1.4 governments. F.1.c Provide for communications with Federal emergency F (fF-2) recponse organizations. F.1.d Provide for communications between the nearsite H.1.4 Emergency Operations Facility and State / local Emergency Operations Centers, and offsite Radiological Emergency Teams. F.1.e Provide for alerting personnel in each response E.1.1 organization. F.1.f Provide for communications between Fermi 2 and H.1.4 NRC Headquarters and NRC Region 3, the nearsite Emergency Operations Facility, and offsite Radiological Emergency Teams. F.2 Ensure that a coordinated communications link L1.1 exists between Fermi 2 and mobile medical support L.3 facilities. F.3 Conduct periodic testing of emergency communicatiort N.2.1 systems.
- RERP Plan !
Revision 1 App.5-6 RERP PLAN CROSS-REFERENCE WITH NUREG-0654 NUREG-0654 RERP Plan f Roguirement Description of Requirement Section t t 0.1 Provide, at least annually, dissemination of 0.1 information to the public regarding notification procedures, protective measures, and general information on radiation, e i O.2 Provide information for the permanent and transient 0.2 population, and update such information at least annually. , i O.3.a Designate points of contact and physical locations G.3 + for news media use in an emergency. 0.3.b Provide space for the media at the nearsite 0.3 Emergency Operations Facility. . O.4.a Designuta a spokesperson having access to all O.4 ' necessary information. O.4.b Establish arrangements for timely exchange of 0.4 information among designated spokespersons, j G.4.c Establish coordinated arrangements for dealing with G.4 rumors. ' O.5 Conduct coordinated programs at least annually to 0.5 acquaint news media with emergency plans, information concerning radiation, and points of contact for , the release of information in en emergency, [ t H.1 Establish a Technical Support Center in accordance H.1.2 , with NUREG-0696, Revision 1. H.2 Establish an Emergency Operations Facility In H.1.4 l accordance with NUREG-0696, Revision 1. H.4 Provide for the timely activation and staffing of H.1
, facilities.
l H.5 Identify and establish onsite rnonitoring systems H.2.1 l that are to be used to initiate emergency measures H.2.4 l l as well as those to be used for conducting assessmant. 1 i l l l
RERP Plan l Revision 1 l App,5-7 ; RERP PLAN CROSS-REFERENCE WITH NUREG-0654
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l NUREG-0654 RERP Plan Heeuirement Description of Requirement Section H.S.a Onsite equipment includes geophysical phenomena H.2.1 j monitors. 4 H.5.b Onsite equipment includes radiological monitors. H.2.2 W H.S.c Onsite equipment includes process monitors. H.2.3 H.S.d Onsite equipment includes fire and combustion H.2.4 productri detectors. , i H.6.a Acquire dets for offsite geophysical phenomena H.3.1 monitors. l H.6.b Provide for offsite radiological monitoring and H.3.2.1 sampling. l 1 H.6.c Provide for fixed or mobile laboratory facilities H.3.2.2 l for analyzing offsite samples, j H.7 Provide for offsite radiologicol monitors near the H.3.2.1 ) plant. : l H8 Provide meteorological instrumentation and H.3.1,1 J procedures and ensure ability to obtain representative ; current meteorological information from other tources. l j H.g Provide for en onsite Operational Support Center. H.1.3 )
- 1 l H.10 laspect, inventory, and check all emergency H.5 j equipment at least quarterly, and after each usu. 1 H.11 Identify emergency kits by general category. H.5 H,12 Establish a central point for receipt and analysis H.3.2.2 l of field data and cooMination of sample media.
1 l 1.1 Identify plant system and effluent parameter values D I for off-normal conditions and the corresponding emergency classification. l.2 include onsite capability and resources to provide H (tH-2, j initial values and continuing assessment, including tH-3,tH-4, 1 post-accident sampling, radiation and effluent tH-5) I monitors, in-plant lodine instrumentation, and containment radiation monitoring in accordance with NUREG-0578. ] 1 l l l 1
P ,. 1 i O RERP Plan
. 3 Revision 1 App.5-8 i' l i
l i i RERP PLAN CROSS-REFERENCE WITH NUREG-0454 l NUREG-0654 RERP Plen , Requirement Description of Requirement Section i 1.3.s Estab!Ish methods and techniques to determine the 1 source term of releases within plant systems. 1.3.b Establish methods and techniques to determine the l l magnitude of release cased on effluent monitors and j plant system parameters. I l.4 Establish 'the relationship between effluent monitor I readings and onsite and. offsite upon.rus for various i meteorological conditions. l.5 Acquire and evaluate meteorological infor nation. H.3.1.1 1.6 Establish the methodology for determining release I i rat 6 and projected doses with dose assessn.ent i lustrumentation inoperable. l 1.7 Describe the capability and resources for field 1.4 ; monitoring within the plume exposure EPZ. l.8 Provide method for making rapid field estimates of I.4 1 liquid and gaseous releases. l 1.9 Ensure espability to detect airborne radiolodine as H.3.2.1 low as 10E-7uc/cc in the field, j i 1.10 Establish means to conduct Nuclide Analysis / 1.3 l Integrated dose and make provisions for comparing such I estimates with protective action guides. J.1.a Establish means to warn non-Emergency Response J.1 l Organization employes onsite. 1 J.1.b Establish means to warn Visitors onsite. J.1 a 1 J 1.c Establish means to warn Contract / Construction J1 personnel onsite. J.1.d Establish means to warn other personnel in the J.1 Owner-Controlled Area, J2 Provide for evacuation routes and transport to J.2 i offsite assembly areas. J.3 Provide for radiological monitoring of evacuees. J.2.1 l I X-
V k RERP Plan
'C Revision 1 )
. App.5-9 !
j RERP PLAN CROSS-REFERENCE WITH NUREG-0654 l NUREG-0654 RERP Plan 1 Requiremn,nt Description of Requirement , Section . I J.4 Provide for evacuation of non-essential personnel J.2.1 1 at Site Area Emergency or General Emergency and provide ; decontamination. J5 Provide for capability to account for all onsite J.2.2 cy personnel and report n6mes of missing within 30 minutes. J.6.a Provide for respiratory protection during an J.3 emergency. ! J.6.b Provide for use of protective clothing during an J.3 emergency. s J.6.c Provide for the use of radioprotective drugs. J.3 X J.7 Provide for protective action recommendations to J4 State and local authorities. Recommendations shsil Include Emergency Action Levels corresponding to
.S projected dose to the population-at-risk.
J.8 Provide for evacuation time estimates within the J.4.2 plume exposure EPZ. J.10.a Develop maps for evacuation routes and sampling J (fJ-2) sites, relocation centers, and shelter areas. J.10.b include maps showing population around Fermi 2. J (fJ-3) J.10.c Provide for means of notifying transients and J.4 riuldents. J.10.m Describe the basis for choice of recommended J.4.1 + protective actions from plume exposure pathway during an emergency. K.1.a Establish onsite exposure guidelines for removal K (tK-1) of injured personnal. K.1.b Establish onsite exposure guidelines for taking K (tK-1) correctivo actions. t K.1.c Establish onsite cxposure guidelines for performing K (tK-1) assessment actions. Y K.1.d Establish onsite exposure guidelines for providing K (tK-1) first aid.
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[. H l RERP Plan I Revision 1 App.5-10 RERP PLAN CROSS-REFERENCE WITH hUREG-0654 NUREG-0654 RERP Plan Requirement Description of Requirement Section K.1.e Establish onsite exposure guidelines for performing K (tK-5) personnel decontamination. K.1.f Establish onsite exposure guidelines for providing K (tK-1) ambulance service. K.1.g Establish onsite exposure guidelines for providing K (tK-1) medical treatment services. K.2 Provide an onsite radiation protection program to K.1.1 be implemented during an emergency. Identify individual, by title or position, who can authorize emergency workers to exceed 10 CFR 20 Ilmits. K.3.a Provide for self-reading / permanent record doelmetry K.2 and for capability to determine doses received by emergency workers on a 24-hour-per-day basis. K.3.b Maintain dose records of emergency workers and read K.2 dosimetry at appropriate (time) frequencies. ! K.5.a Specify action level for determining the need for K.3 l decontamination. l K.S.b Establish means for decontamination of wounds, K4 supplies, instruments and equipment, and waste d'.sposal. K.6.a Provide for area access contamination control. K.4 K.6.b Provide for drinking water and food supply K.4 l contamination control. ( - K.6.c Provide criteria for return of areas and items to K.4 normal use. K.7 Provide for the decontam! nation of relocated J.2.1 onsite personnel with special attention given to raololodine contamination of toe skin. L.1 Provide for local and backup hospital and medical L.1.1 services to evaluate radiation exposure and uptake. L.2 Provide for onsite first aid capability. L.2 ; L4 Arrange for transport of victims of radiation L3 accidents to medical fac!!ities.
l RERP Plan l Revision 1 ! App.5-11
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i RERP PLAN CROSS-REFERENCE WITH NUREG-0654 l i NUREG-0654 RERP Plan ; Requirement Description of Requirement Section l M.1 Develop general plans and procedures for Reentry / M.1 Recovery operations. M.2 Identify by position and title key members of the M.2 Recovery Organization, including their authority and j responsibilities. M.3 Specify means for informing organizations that M.3 i Recovery operations are to be initiated, and what i organizational changes might occur. ; i M.4 Establish a method to periodically estimate total M.4 ) population exposure. N.1.a Define and conduct exercises per NRC/ FEMA rules. N.1 N.1.b Conduct announced and unannounced exercises under N.2 ) various weather conditions and times, and with various , scenarios. N.2.a Cornmunications with the State, local authorities, N.2.1 ; and the NRC shall be tested monthly Communications between Fermi 2 State and local emergency operations centers, and field teams, shall be conducted annually. ) N.2.b Fire drills shall be conducted in accordance with N.2.2 Technical Specifications. N.2.c A medical emergency drill which contains provisions N.2.3 : for participation by local support services agencies shall be conducted annually. , N.2.d Plant environs and radiological monitoring drills N.2.4 shall be conducted annually, and shell include collection and analysis of all sample media. N.2.e.1 Conduct Health Physics drills semi-annually that N.2.5 involve response to, and analysis of, simulated elevated airborne and liquid samples, and direct radiation measurements in the environment. N.2.e.2 Conduct analysis of in-plant liquid samples with N.2.5 actual elevated radiation levels, including use of post-accident sampling system, annuall e.
i l 1 i RERP Plan i Revision 1 1 App.5-12 ! I l RERP PLAN CROSS-REFERENCE WITH NUREG-0654 j l NUREG-0654 RERP Plan l Requirement Description of Requirement Section l
< N.3.a Scenarios shall contain basic objectives and N.3 evaluation criteria. ;
N.3.b Scenarios shall contain dates, time periods, N.3 l places, and participating organizations. N.3.c Scenarios shall contain a list of simulated ovents. N.3 l l N.3.d Scenarios shall contain a time schedule o' real N.3 ) and simulated events, j N.3.e Scenarios shall contain a narrative sumtrary of N.3 l events. l N.3.f Scenarios shall describe arrangements for, and N.4 advance materials previded to, official observers. i r N.4 Conduct a critique as soon as possible following N.4 completion of the drill / exercise, and produce a formal ; evaluation as a result of the critique. ; l N.5 Establish management controls for assigning and N.4 implementing corrective actions. O.1 Conduct training for appropriate individuals. O.1 f 0.1;a Provide site specific training to offsite emergency 0.2 ! response organizations, j O.2 Emercency Response Organization training shall, 0.1 l besides classroom training, include participation l in drills / exercises. O.3 First Aid training shall be equivalent to Red Cross 0.1 i Multi-Media. l 1 f
p l l RERP Plan L Revision 1 App.5-13 RERP PLAN CROSS-REFERENCE WITH NUREG-0654 NUREG-0454 RERP Plan Requirement Description of,, Requirement Section O.4.a Provide training for Emergency Response 0.1 Organization Director / Coordinators. I O.4.b Provide training for accident assessment personnel. O.1 j 0.4.c Provide training for radiological monitoring teams 0.1 and radiological analysis personnel. ! O.4.d Provide training for police, security, and fire 0.1 fighting personnel O.4.e Provide training for Damage Control and Rer. cue 0.1 Teams. O.4.f Provide training for First Aid and rescue 0.1 j personnel. O.4.g Provide training for local support services 0.2 personnel, including Civil Defense / Emergency Services. t 0.4.h Provide training for medical support personnel. O.2 0.4.1 Provide training for headquarters support 0.1 personnel. O.4.J Provide training for Communicators. O.1 0.5 Provide for initial and annual retraining of 0.1 personnel with emergency response responsibilities, l
- P.1 Provide for the training of those responsible for P.1 l.
pit.nning. L P.2 Identify the individual, by title, who has overall P.1 authority and responsibility for planning. l L P.3 Designate an Emergency Planning Coordinator with P.1 L responsibility for development and update of emergency I plans. P.4 Annually, or as needed, review and update the RERP P.3 Plan and agreemonts, taking into account changes identified by drills / exercises. P.5 The RERP Plan and approved changes shall be dated P.3 and marked to show revisions, anct shall be sent to all organizations and individuals with implementation responsibilies.
t ;> 1 L RERP Plan !
,;1 Revision 1 :
App.5-14 L r . l RERP PLAN CROSS-REFERENCE WITH NUREG-0654 NUREG-0654 RERP Plan , i-Requirement Description of Requirement Section i P.6 The RERP Plan shall contain a detailed list of Appendix 4 ; supporting plans and their sources, j P.7 The RERP Plan shall contain an appendix listing of Appendix 3 implementing procedures. This list shall include ! the sections of the Plan to be implemented by each procedure. P.8 The RERP Plan shall contain a specific Table of Table of l Contents. Plans submitted for review should be Contents i k cross-referenced to these criteria. P.9 Conduct independent reviews of the Emergency P.4.1 Preparedness program every 12 months. Review i shall include the RERP Plan, implementing p procedures, training, readiness testing, equipment, [ and interfaces with State and local governments. k Review results shall be formally documented, i reported to appropriate organizations, and retained for l 5 years. i P.10 Update emergency telephone numbers in procedures at N.2.1 l L least quarterly. ; l i l l l l l l l l ' ______ _ _. _ _.}}