ML20079S421

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures PEP-02.1 Re Initial Emergency Actions & PEP-02.6.4 Re Radiological Control Director

ML20079S421
Person / Time
Site:	Brunswick
Issue date:	05/04/1983
From:	Boyer L CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20079S396	List: ML20079S411 ML20079S421
References
PROC-830504-01, NUDOCS 8307110586
Download: ML20079S421 (23)

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N i BSEP PLANT OPERATING MANUAL VOLUME XIII, BOOK 2 PLANT EMERGENCY PROCEDURES (PEP) l.

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i PLANT OPERATING MANUAL VOLUME 13, BOOK 2 TABLE OF CONTENTS PLANT EMERGENCY PROCEDURES (PEP) 1.0 PLANT EMERGENCY PROCEDURES INTRODUCTION 1.1 Manual Purpose and Use 1.2 Emergency Response Organization 2.0 EMERGENCY CLASSIFICATIONS AND CONTROL PROCEDURES 2.1 Initial Emergency Actions 2.2 Emergency Control - Unusual Event 2.3 Emergency Control - Alert

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2.4 Emergency Control - Site Emergency 2.5 Emergency Control - General Emergency 2.6 Emergency Management Guides 2.6.1 Plant Operations Director l c

i 2.6.2 Emergency Repair Director 3 2.6.3 Logistics Support Director

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2.6.4 Radiological Control Director I

2.6.5 Representative to the State Emergency Response Team 2.6.6 Environmental Monitoring Team Leader 2.6.7 Plant Monitoring Team Leader 2.6.8 Personnel Protection and Decontamination Team Leader 2.6.9 Fire Brigade Leader 2.6.10 Emergency Security Team Leader 2.6.11 Damage Control Team Leader 2.6.12 Operational Support Center / Evacuation Assembly Area Leader l 2.6.13 Site Public Information Coordinator l l 2.6.14 Site Systems Communications Coordinator 2.6. 15 Support Services Coordinator 2.6.16 Emergency Response Mainager 2.6.17 Administrative and Logistics Manager  !

2.6.18 Technical Analysis Manager 2.6.19 Radiological Control Manager 2.6.20 Dose Projection Coordinator l

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, a 3.0 EMERGENCY ACTION PROCEDURES 1

3.1 Communications Procedures 3.1.1 Follow-up Notification and Communications 3.1.2 Communications Activities 3.1.3 Use of Communications Equipment

! . 3.2 Augmentation and Mobilization Procedures 3.2.1 Notification of Off-duty PersonneI

3.2.2 Mobilization of Outside Agencies 3.3 Plant Monitoring Procedures i

3.3.1 In-plant Monitoring and Surveys 3.3.2 On-site Monitoring and Surveys 3.3.3 Collection of Very High Level Samples 3.3.4 Analysis of Very High Level Samples ,

i 3.4 Radiological Consequences f

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) 3.4.1 Initial Dose Projections

! 3.4.2 Whole Body Dose Projections  !

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! 3.4.3 Thyroid Dose Projections 3.4.4 (Reserved)

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3.4.5 Automation of Dose Projection Procedures l 3.4.6 (Reserved)

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3.5 Environmental Monitoring Procedures i

i 3.5.1 Confirmation of Initial Off-Site Dose Projections 3.5.2 Expanded Environmental Monitoring 3.5.3 Plume Tracking by Actual Measurement

3.5.4 Coordination with State Monitoring

! 3.6 Source Term Assessments and Estimates of Core Damage 3.6.1 Release Estimates Based Upon Stack / Vent Readings l 3.6.2 (Reserved) 3.6.3 Interpretation of Liquid and Gaseous Samples

3.6.4 Consequences of Leakage and Spills 3.7 Radiation Control Procedures j i 3.7.1 Radiation Work Permits and Exposure Control i 3.7.2 Emergency Personnel Monitoring and Dosimetry

! . 3.7.3 Issuance and Use of Protective Gear f

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3.8 Protective Action Procedures 3.8.1 Evacuation 3.8.2 Personnel Accountability 3.8.3 Administration of Radioprotective Drugs 3.8.4 Access Control 3.9 Aid to Affected Personnel 3.9.1 (Reserved) ,

3.9.2 First Aid and Medical Care 3.9.3 Transporting of Contaminated Injured Personnel 3.9.4 (Reserved) 3.9.5 Personnel Decontamination 3.9.6 Search and Rescue 4.0 SUPPLEMENTAL PROCEDURES 4.1 Record Keeping and Documentation 4.2 Emergency Facilities and Equipment i

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4.3 Performance of Training, Exercises and Drills 4.4 (Reserved) 4.3 Public Education and Information APPENDIX A EMERGENCY RESPONSE RESOURCES

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A.1 BSEP Personnel

• A.2 Federal, State and County Agencies A.3 Fire and Medical Assistance A.4 Other Emergency Response Contacts

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CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLA.T V UNIT 0 INITIAL EMERGENCY ACTIONS PLANT EMERGENCY PROCEDURE: PEP-02.1 VOLUME XIII Rev. 008 Recomended By: "

.A Date: 5!3fy3

AssistantgGeneralManager Approved By

F S: + Date: f/9/F3

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General Managht shb i .J 3 /; i h y, - -

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s LIST OF EFFECTIVE PAGES PEP-02.1 Page(s) Revision 1-3 5 4-7 ,

8 8 7 9 8 10 - 25 7 i

l BSEP/Vol. XIII/. PEP-02.1' i Rev. 8 l

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EXHIBIT 2.1-2 EMERGENCY ACTION LEVELS Section Event Category Page No.

1 Abnormal Primary Leak Rate 8 2 Steam Line Break or Safety / Relief 9 Valve Failure 3 Abnormal Core Conditions and Fuel Damage 10 4 Abnormal Radiological Effluent or 12 Radiation Levels 5 Loss of Shutdown Functions: Decay Heat 14 and Reactivity 6 Electrical or Power Failures 15 7 Fire 16 8 Control Room Evacuation 17 9 Loss of Monitors or Alarms 18 10 Fuel Handling Accident 19 11 Security Threats 20 12 Injury or Specific LCOs 21 13 Hazards to Plant Operations 22 14 Natural Events 23 13 Shift Operating Supervisor / Site Emergency 24 Coordinator Judgments CAUTION

. The following flow charts (pages 5, 6, and 7) should be used as an initial check that an emergency action level has been met or exceeded.

The specific indications for classifying an emergency begin on page 8.

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BSEP/Vol. XIII/ PEP-02.I 4 Rev. 8

EMERCENCY Cf.ASSIFICATI0ll CUIDE FIAWCHART

@SECTION ALERT SITE AREA EHERCENCY CENERAL EHERGENCY t:1 No. EVENT CATECORY UNUSUAt. EVENT

• t1 Primary Coolant Leak Known loss of Coolant Small or I.arge Break LOCA

<: 1 Abnormal Primary Leak Rate - Exceeding Primary System Rate Creater Than 50 Accident (IACA) Creater Occurs and Containment Per-f.

(rege 8) Leak Rate Technical Spect-fication CFH Than Make-up Capacity formance is Unsuccessful Affecting longer Tere p;

Success of the ECCS: Could.

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H Lead to Core Degradation or

[ Helt in several Hours With-out Containment Soundary y ,

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2 Steam Line Break or Failure of a Safety or Relief-Steam Line Break With-Steam I.ine Break outside

'." Safety / Relief Valve Valve in a Safety-Related itSIV Halfunction Containment Without Isolation

~ , Failure (Fage 9) System to Close or Open if Causing Leakage

• Challenged 3 Abnormal Core Conditions M uel Damage Indication Severe Loss of Fue! Degraded Core with Fossible- 1 Loss of 2 of 3 Fission and Fuel Damage (Fase 10)q-Cladding Loss of Coolable Geometry Product Barriers With Fo-tential less of the Third bHighCondenserOff-Cas d ndenser Off-Cas 10 Barrier Times Unusual Event Levels Weall or Large IACAs With Failure of ECCS to Perform Leading to Core Melt Degra-dation or Helt in Hinutes to Hours. Loss of Contain-u ment Integrity Hay Be Isminent l 4 Abnormal Radiological :adiological Effluent Tech-1---Radiation Levels or , 1 Any Release to the Environ- Effluent Honitors Detect Effluent or Radiation nical Specification Limits Airborne Contamination ment Resulting in an Off-Site Levels Corresponding to Enceeded Which Indicates Severe Dose Rate in Escess of I res/hr Whole Body or t.evels (Fase 12) 5 ree/hr Thyroid at the j

Degradation in control 0.1 res/hr (Whole Body) or i

of Radioactive Haterial 0.5 res/hr (Thyrois e) site soundary Under Actual Meteorological Conditions badiological Effluents -These Dose Rates are L-These pose Rates are Creater Than 10 Times Projected Based on Other Projected Based on other Technical Specifica- Plant Parameters or are Plant Parameters or are tions' instantaneous Hessured in the Environs Heasured in the Environe Limits LEFA Frotective Action Guide-lines are Projected to be Enceeded Outside the Site 1 :o Boundary 69 4

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• 5 t.oss of Shutdown Failure of teactor Transient Requirina operation 7T ransient (e.g., t.oss of j Functions: Decay Heat Protection System to of Slastdown Systems With Off-Site Power) Flus m Initiate and Complete Failure to Scram (Continued Failure of Requisite Core seul Reactivity (Fage 14) a Scram Whic! Brings Power Ceneration With No Shutdown Systems (e.g.,

j the Reactor dubcritical Core Damage immediately Scram). Could Lead to Core j Evident Helt in Several Hours With

• Containment Failure Likely.

-  % lete loss of Any A ss of Any Function Needed Hore Severe Consequences if Function Needed for for Flant Hot Slastdown Fump Trip Does Not Function.

Plant Cold Slaatdown ,

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EMEltCENCY Cl.ASSIFICATION CUIDE FtJDWCHART (Continued) . . ,

37g g SITE AREA EMERGENCY CENFRA1. EHERCENCY ALERT ,

p1 NO. EVENT CATEGORY UNUSUAL. EVENT l

L--Shastdown Occurs But 2 5 Continued Requisite Decay Heat g Removal System (e.g., RHR) p.

or Nonsafety Systems Heat Removat Means are pendered

>4 Unavailable. Core Degrad- .

N ation or Melt Could occur in f Qm About Ten Hours With Subse-quent Containment Failure l

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i  :.oss of Of f-Site Power--Loss of Of f-Site Power and Loss O 6 Electrical or Power imse of Of f-Site Power P Failures (Fase 15) or Loss of On-Site AC Fower and Imse of All On-Site of All On-Site AC Power for

• Capability AC Fower More Than 15 Minutes LLoss of All vital on. -Loss of All Vital On-Site l

Site DC Fower DC Power For More Than 15 Minutes Fire Within the Plant ' Fire Potentially Af fect- Fire Compromising the Any Major Internal or 7 Fire (Page 16 ) External Events (e.g..

t.asting Mure Than 10 ing Safety Systems Functions of Safety Systems Minutes Fires, Earthquakes Sub-stantially Seyond Design Basis) Which Could Cause Massive Common Damage to Flant Systems m

8 Control Room Evacuation Evacuation of Control-Evacuation of Control Room (Page 17) Room Anticipated or and Control of Shutdown Systems Required With Control of Not Established f rom I.ocal Shutdown Systems Estab- Stations in 15 Minutes 11shed from Local Stations 9 Loss of Honitors or Indications or Alarms on Most or All Alarms Most or all Alarms (Annunciators Alarms (Fase 18) Procesa or Effluent Parameters (Annunciators) Lost lost and Flant Transient Intiated Not Functioning in Control or in Progress Room to an Estent Requiring Plant Shutdown or Other Significant Loss of Assessment of Communication capability 10 Fuel Handling Accident Fuel Damage Accident Major Damage to Spent Fuel in (Page 19 ) With Release of Containment or Fuel Handling Radioactivity to Con- Building tainment or Fuel Handling Building

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4 Security Threat. Attempted ongoing Security imminent loss of Physical Imes of Physical Control 11 Security Threats Entry or Attempted Sabotage Comproutse Control of Plant of the Facility OD (Page 20)

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bJ un V8 d EHERGENCY Cl.ASSIFICATION CUIDE FIXniCliART (Continued)

<1 SECT!DN SITE AREA ENERGENCY CENERAI. EMERCENCY Al.ERT

f. No. EVENT CATEcostY UNUSUAI. EVENT g 12 Injury or Specific LCOs 1 Lous of Containment Integrity jj (Page 21) Resulting in Immediate Shutdown By Tech. Spec.

F4 Yo ---Loss of Engineered Safety tg -

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• d Feature or Fire Protection c) 8 Function Requiring Shut-down by Tech. Spec.

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- --Emergency Core Cooling System (ECCS) Initiated and Dis-charged to Vessel 6-Transportation of Contam-

' insted Injured Individual from Site to Off-Site tiospital Itazarde Being Emperienced or----Severe Hasards Being Severe Hazards Being Emper-11 Hazards to Plant Experienced or Projected fenced or Projected That i operations (Page 22) Projected That Affect Fiant Compromise tLe Functions of operations rotentially Affecting 1 ,

Safety Systens Safety Systems. Reactor Not in Cold Shutdown.

Natural Phenomena Seing Severe Natural Phenomena Severe Natural Phenomens Being - Any Major Internal or 14 Natural Events Being Experienced or Experienced or Projected That External Events (e.g.,

(rege 23) Emperienced or Projected Fires. Earthquakes Beyond Usual Levels Projected Compromise the Functions of

- Safety Systems. Reactor Substantially Beyond Not in Cold Shutdown Design Basis) Which Could Cause Massive 1 Common Damage to Flant Systems i

shif t operating Surervisor/--other Plant conditione Entst-Other Flent conditione-Other Flaat Activation Conditions Other Fiant Conditions 15 That Warrant lucreased Aware- Exist Warranting Fre- Warranting of Esist EOF. Entst, from Whatever Site Emergency coordinator Emergency Centers and Monitoring Source, That Make Release Judgments (Page 24) neus on the Part of a Plant cautionary Activation Tenne, or Issuance of a of Large Amounts of 1

Dperating Staff or State of the TSC

, Frecautionary Notification to Radioactivity in a Short l and/or Local Off-Site Author- the Public Near the Site Time Feriod Possible ( e.g., '

Atles or Require Fiant

, Any Core Melt Situation).

• Shutdown Under Technical Specification Requirements or DJ Involve Other Than Normal Con-trolled Shutdown t

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3 Section 2 - Steam Line Break or Safety / Relief Valve Failure 2.1 Unusual Event 2.1.1 Failure of a primary system safety / relief valve, including ADS, to open if challenged as indicated on annunciator panel C32-LPR-R608 or R609.

9B 2.1.2 Failure to close following reduction from applicable pressure as indicated on annunciator panel A-3,'l-1,1-10.

CAUTION Failure is due to an overpressure event, not a test.

2.2 Alert 2.2.1 Steam line break downstream of MSIVs or upstream of feedwater isolation valves as indicated by either A and C or B and C:

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a. Reactor trip with:

(1) Low RCS pressure (C32-LPR-R608) 9E (2) Low steam pressure (C32-LPR-R609)

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93 (3) Low reactor vessel water level (C33-LPR-R608) 9E (4) High steam flow (P603)

b. Anytime EI-01.3 is implemented.

AND

c. Shift Operating Supervisor's opinion or evidence on P601 and P603 of continuing steam flow with steam line break

. outside of primary containment.

2.3 Site Emergency 2.3.1 Alert indicated above AND inability to close MSIVs within 15 minutes.

2.4 General Emergency N/A BSEP/Vol. XIII/ PEP-02.1 9 Rev. 8

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CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM EIICTRIC PLAhT UNIT 0 RADIOLOGICAL CONTROL DIRECTOR PLAST EMERGENCY PROCEDURE: PEP-02.6.4 VOLUME XIII

. Rev. 003 Recommended By: Me -

Date: 5'/J!F7 '

Assi5itanttothpeneralManager Approved By: C D . ** Date: f/9 / T3 General Manager ' /

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LIST OF EFFECTIVE PAGES PEP-02.6.4 PAGE(S) REVISION 1-3 2 i

'4-6 3 7-8 '2 BSEP/Vol. XIII/ PEP-02.6.4 i Rev. 3

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l 3.4.2 If estimates of reactor coolant system activity (containment atmosphere activity) or fuel damage are required, implement PEP-3.6.3, " Interpretation of Liquid and Gaseous Samples."

3.4.3 To evaluate potential radiological consequences from leaks i or spills, implement PEP-3.6.4, " Consequences of Leakage l and Spills." '

3.5 ENVIRONMESTAL MONITORING ACTIVITIES

• 3.5.1 Assist the Environmental Monitoring Team Leader in selecting proper monitoring locations and assessing radiological conditions expected in the field.

NOTE: The Environmental Monitoring Team Leader will'be responsible to the Radiological Control Director j

prior to Emergency Operations Facility activation and to the Radiological Control 1 Manager after Emergency Operations Facility activation.

• 3.5.2 Advise appropriate State and county officials of the initial monitoring efforts underway prior to activation of the Emergency Operations Facility. (This may be carried out via the Representative at the State Emergency Response Team Headquarters).

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3.3.3 Make the results of monitoring efforts and analysis of samples available to the State Emergency Response Team Headquarters (prior to activation of the Emergency Operations Facility).

3.5.4 Where requested by responsible State officials, arrange for analysis of environmental samples by the Harris Energy &

Environmental Center and for whole body counting and bioassay of affected off-site individuials.

NOTE: This function will be the responsibility of the Radiological Control Manager after activation of the Emergency Operations

! Facility.

3.5.5 Upon declaration of a Site Emergency where a radioactivity release occurred or declaration of General Emergency, the l Radiological Control Director shall request immediate monitoring support. The NRC may make available its mobile laboratory. Parking space and 120 Vac power receptacles are reserved for the NRC mobile laboratory (see Brunswick REP, Section 5.7.6 and Figure 5.0-1).

BSEP/Vol. XIII/ PEP-02.6'.4 4 Rev. 3 l I

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l 3.6 PLUME TRACKING ACTIVITIES NOTE: This function will be the responsibility of the Radiological Control Manager after activation of the Emergency Operations Facility.  ;

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• 3.6.1 Upon declaration of any Site or General Emergency arrange for the Environmental Monitoring Team to monitor the location and radiation levels in the plume.

l 3.6.2 Direct the Envircnmental Monitoring Team Leader to obtain the survey gear and prepare for the plume measurements.

I 3.6.3 Direct the Dose Projection Coordinator to maintain com-munications with the Environmental Monitoring Team and compare reported readings with these projected.

l 3.6.4 If deemed necessary and if not already done by the State, request assistance from the Department of Energy for special plume surveys.

4 Note: All off-site assistance will be requested

! and coordinated by the Radiological Control Manager after activation of the Emergency Operations Facility.

Note: This cannot be made available for a number of f hours, but can be extremely useful in measuring

1. b low levels of radioactivity. Such requests shall be made through the North Carolina State Radiation Protection Section.

3.6.5 If assessments of the plume trajectory are uncertain and if not already done so by the State, request assistance from NOAA and/or the NWS.

Note: These groups may be able to provida expert advise on regional meteorological conditions.

Depending on the existing conditions, they may be able to provide devices to measure existing wind patterns (sounding balloons, theodolites) and thus plume trajectories. Such requests shall be made through the North Carolina Bureau

! of Radiological Health.

I 3.7 PLANT MONITORING ACTIVITIES

• 3.7.1 Assist Plant Monitoring Team Leader in selecting proper monitoring and sample collection points and data required, and in assessing radiological conditions at those points.

BSEP/Vol. XIII/ PEP-02.6.4 5 Rev. 3 l

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3.7.2 Assist Plant Monitoring Team Leader in determining proper protective gear and dosimetry and in developing any pre-cautions that should be included in the Plant Monitoring Team's briefing.

3.8 PERSONNEL PROTECTION

• 3.8.1 Determine need for special protective gear and for deviation from^" fill" set of Anti C's. Automatic " full" gear with Anti C's and respiratory equipment required for:

a. Sampling RCS or waste fluid

b. Cleanup

t. Entry to rad area of >10 x MPC i

d. Entry to rad area of unknown intensity

e. Entry to containment.

3.8.2 Require air samples to remove requirement for respiratory equipment when possible to better facilitate emergency communications.

• 3.8.3 Inform medical facility to set up for receipt of a con-taminated injured person (s) prior to allowing the trans-portation vehicle to leave the site.

Note: Patients are not to be transported to the hospital for treatment if medical attention by the physician can be accomplished at the plant site.

1 BSEP/Vol. XIII/ PEP-02.6.4 6 Rev. 3 i

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I CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIT 0 ON-SITE MONITORING AND SURVEYS PLANT EMERGENCY PROCEDURE: PEP-03.3.2 VOLUME XIII Rev. 003 Recommended By: x" "

Date: f!3!PJ assistanttothfdeneral Manager Approved By: ( b. ' _ -k- - Date: f/N /77 General Managed '

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i LIST OF EFFECTIVE PAGES PEP-03.3.2 PAGE(S) REVISION 1-2 3 e

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BSEP/Vol. XIII/-PEP-03.3'.2 -i- Rev. 3

PEP-03.3.2 ON-SITE MONITORING AND SURVEYS

1.0 Resoonsible Individuals and Objectives 1 l

The Personnel Protection and Decontamination and Plant Monitoring Team are responsible to the Radiological Control Director for assuring on-site monitoring and surveys are conducted at locations on-site (including those outside the protected area), documented and reported to appropriate personnel.

Releases of radioactivity may lead to excessively'high radiation levels in or near the Operational Support Center, the Technical Support Center, Emergency Operations Facility, the machine shops, the counting areas, or other areas within the site boundary, but removed from the reactor.

Periodic surveys of such areas are necessary to assure their continued use.

2.0 Scone and Aeolicability This procedure shall be implemented if a Site Emergency or General Emergency is declared during which radioactivity is directly released or suspected to be released into the atmosphere, and as directed by the Radiological Control Director or Site Emergency Coordinator.

NOTE: Where this procedure does not address specific monitoring details refer to existing plant procedures.

3.0 Actions and Limitations

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NOTE: For conditions where off-site doses have exceeded or are projected to exceed 0.1 rem whole body, and resources are limited, confirmatory off-site monitoring at the site boundary takes precedence.

3.1 Unless otherwise directed by the Radiological Control Director the general criteria for determining that radiation levels are acceptably low for continued habitability are:

1 3.1.1 < 3 mr/hr direct; 8

3.1.2 < 1000 dpe/100 cm S.T contamination; and 3.1.3 < 0.25 MPC airborne.

l 3.2 Obtain calibrated monitoring equipment and amargency kits.

3.3 Perform an instrument check including:

3.3.1 Battery Check.

3.3.2 Current calibration sticker.

3.3.3 Modifications or limitations (per sticker).

BSEP/Vol. XIII/ PEP-03.7.2 Rev. 3 y- -y --- - , ,w ,

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1 3.4 Conduct on-site monitoring and surveys (airborne contamination, dose rate, and smear surveys) as directed in E&RC-0100 " Routine /Special Dose Rate Survey," E&RC-0120 " Routine /Special Airborne Radioactivity Survey;" E&RC-0111 " Routine /Special Surveys for Removable Surface Contamination."

3.5 Operate direct radiation monitors continuously while proceeding to requested locations and note any unanticipated high radiation

. levels, their location, and time and date of reading.

3.6 Record (or communicate to one who is recording) pertinent data at each location requested to be wonitored:

3.9.1 For dose rate surveys, use forms in E&RC Procedure 0100.

3.9.2 For airborne surveys, use forms in E&RC Procedure 0120.

3.9.3 For contamination smear surveys, use forms in E&RC Procedure 0111.

3.7 For general radiation measurement of areas that should remain habitable take portable air samples and direct radiation surveys in the following areas and in other areas, as directed by the Radiological Control Director:

3.7.1 Machine shops 3.7.2 Administration Building a

3.7.3 Operational Support Center 3.7.4 Technical Support Center 3.7.5 Counting areas 3.7.6 Emergency Operations Facility 3.7.7 Assembly areas 3.8 For specific locations of personnel ingress and egress, personnel

, monitoring devices (e.g., RM-14) should be set up (PEP-03.8.4,

" Access Control").

l 3.8.1 Main entrance i

3.8.2 Visitors center

. 3.8.3 Construction entrance 3.8.4 Any other area (s) specified by the Radiological Control Director or Site Emergency Coordinator.

! BSEP/Vol. XIII/ PEP-03.3.2 Rev. 3 l l I l

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A J P:go 1 of 3 BRUNSWICK STEAM ELECTRIC PLAST RADIOLOGICAL EMERGENCY PLAN EFFECTIVE PAGE LISTING APRIL 1983 Page Revision Page Revision i 8 3-15 8 11 8 3-16 8 iii 8 3-17 8 iv 8 3-18 8 v 8 3-19 8 vi 7 3-20 8 vii 3 3-21 8 1-1 8 3-22 8 1-2 8 3-23 8 1-3 8 T3.5-1 5 1-4 8 F3.1-1 7 1-5 8 F3.2-1 8 1-6 8 F3.5-1 2 1-7 8 - F3.5-2 2 1-8 8 F3.5-3 2 1-9 8 F3.5-4 2 1-10 8 F3.5-5 2 1-11 8 F3.5*6 2 F1.1-1 2 4-1 2 F1.1-2 2 4-2 2 F1.1-3 2 4-3 2 F1.1-4 2 4-4 2 F1.1-5 2 4-5 2

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F1.1-6 2 4-6 7 F1.1-7 2 4-7 7 2-1 8 4-8 7 2-2 8 4-9 7 2-3 8 4-10 7 2-4 8 4-11 7 2-5 8 4-12 7 2-6 8 4-13 7 F2.0-1 7 4-14 7 3-1 8 4-15 7 3-2 8 4-16 7 3-3 8 4-17 7 3-4 8 4-18 7 3-5 8 4-19 2 3-6 8 4-20 2 3-7 8 4-21 2 3-8 8 4-22 2 3-9 8 T4.4-1 2 l 3-10 8 T4.4-2 2 l 3-11 8 T4.4-3 2 i 3-12 8 T4.4-4 2 3-13 8 F4.4-1 2 3-14 8 F4.4-2 2 74.4-3 2

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Peg 2 2 of 3 BRtlNSWICK STEA.4 ELECTRIC PLAST RADIOLOGICAL EMERGENCY PLAN l EFFECTIVE PAGE LISTING APRIL 1983 h Revisien Pm Revision 5-1 8 7-11 2 5-2 '8 F7.2-1 2 5-3 8 8-1 2 5-4 8 8-2 2 5-5 8 A-1 2 5-6 8 A-2 2 5-7 8 A-3 2 5-8 8 A-4 2 5-9 8 B-1 2 T5.0-1(1), 3 B-2 2 T5.0-1(2) 3 B-3 2 T5.0-1(3) 3 B-4 2 T5.7-1 3 B-5 2

. T3.7-2(1) 3 B-6 2 T5.7-2(2) 3 B-7 7 T5.7-2(3) 3 B-8 2 T5.7-2(4) 3 B-9 2 T5.7-3 8 B-10 2 T5.7-4 3 B-11 2 T5.7-5 3 B-12 2

- T5.8-1 3 B-13 2 T5.9-1 3 B-14 2 F5.0-1 3 B-15 2 6-1 8 B-16 2 6-2 8 B-17 2 6-3 8 B-18 2 6-4 8 B-19 2 6-5 8 B-20 2 6-6 8 B-21 7 6-7 8 B-22 7 6-8 8 B-23 7 6-9 8 B-24 7 6-10 8 B-25 7 6-11 8 B-26 7 6-12 8 C-1 2 6-13 8 C-2 2 6-14 8 D-1 2 7-1 2 E-1 2 7-2 2 E-2 7 7-3 2 E-3 2 7-4 2 F-1 8 7-5 2 F-2 8 7-6 2 F-3 ,

8 7-7 2 F-4 8 7-8 2 F-5 8 7-9 2 F-6 8 j 7-10 2 '

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Pogs 3 cf 3 BRUNSWICK STEAM ELECTRIC PLANT RADIOLOGICAL EMERGENCY PLAN EFFECTIVE PAGE LISTING APRIL 1983 Page Revision G-1 7 G-2 '7 G-3 7 H-1 7 H-2 7 H-3 7 H-4 7 H-5 7 H-6 7 H-7 7 H-8 7 e

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