Text

Rev 1 to Browns Ferry Nuclear Plant Torus Integrity Long- Term Program Plant-Unique Analysis Rept.
	ML18026B218
Person / Time
Site:	Browns Ferry
Issue date:	07/12/1984
From:	Drake S, Rochelle J, Williams J; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML18026B217	List: ML18026B216; ML18026B218;
References
	CEB-83-34, CEB-83-34-R01, CEB-83-34-R1, NUDOCS 8409180350
	Download: ML18026B218 (258)
	v • d • e

~ ~

CEB REPORT TVA 10752 {EN OES.2.83)

REPORT NO.

ant CEB-83-34 Torus Integrity Long-Term Program PLANT/UNI T Plant Unique Analysis Report BFN Units 1 SAR SECTION{5)

VENO R ONTRAC No.

ontainment N/A APPLICABLE OESIQN N/A Torus Inte rit stems REV {FOR MEOS USE) MEOS ACC SION NUMBER OOCUMENTS BFN-50-D706$ RO

~-." b3'LI 0018

') CEB'8 1221 008 BFN-50-D711 REFERENCES Rl 12 004 NUREG-0661, CEB-76-23 R2 0% l TENNESS VALLEYAUTHORITY DIVISI N OF ENGINEERING DESIGN CIV ENGINEERING SUPPORT BRANCH Revision 0 Rl R2 te December 21, 1983 7-12-84 Prepared g~wa 16fN:cAD Cliecked z 8-/~

Submitted Reviewed Recommended Approved

>>Prepared by CEB, NEB, and BMP representatives, J. K. Rochelle, Lead Engineer',

See Acknowledgment. 8409180350 84Q911 PDR ADDCK 05000259 I I P PDR

~ E I

II 0 ~

COORDINATION LOG Document No.

'ROLPilS FERRY NUCLEAR PLANT TORUS INTEGRITY LONG-TERM PROGRAM PLANT UNIQUE ANALYSIS REPORT Revision: R-Denotes review A-Denotes approval ENGINEERING SUPPORT BRANCHES CEB EEB MEB QEB A R R A R A R A R A R A R A

/C7 NUCLEAR PROJECTS DESIGN BLP BWP DNP IRP PWP WBP R A R A R A R A R A R A R A R A FOSSIL, IIYDRO, 5 SPECIAL PROJECTS DESIGN AND ARCHITECTURALSUPPORT BRANCH CBP COP FDP HDP SDP ASB A R A R A R A R A A R ESB MEDS PBB OQA R A A A A A A A

I 1

,l I,

0 I,

0

BFN-PUAR TABLE OF CONTENTS

~Pa e AB S TRACT ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

TABLE OF CONTENTS LIST OF ILLUSTRATIONS LIST OF TABLES LIST OF ABBREVIATIONS

1.0 INTRODUCTION

1.1 0 1.2 Ori inal Desi n of Browns Ferr Containment S stems l-l 1-2 1.3 Formation o he Mar I Owners G rou ~ ~ ~ I ~ ~ ~

1.4 Short-Term Pro ram Activities ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1-2 1.5 Generic Lon -Term Pro ram Activi tie 1-3 1.6 The Browns Ferr Torus Inte rit Lon -Term Pro ram ............... ~ ~ ~ ~ ~ ~ ~ ~ ~

1.6.1 H drod namic Load Miti ation 1-4 1.6.2 Com osi ion o the BFN-PUAR 1-5 1.6.2.,1 Contents 1-5 1-6 2.0 GENERAL DESCRIPTION OF STRUCTURES AFTER'MODIFICATION 2-1 2.1 Dr well 2-1 2.2 -W etwell 2-2 2.3 2.4 Vent S stem Torus In ernal Structures

.................... and Pi

~ ~

in

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 2-2 2-2 2.4.1 Submer ed Structures 2-2 2.4.1.1 ECCS Suction Nozzle Strainers 2-2 2.4.1.2 HP I R I and RHR u orts ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 2-3 2.4.1.3 uenchers and Quencher Su o rt S true ures 2-3 PUAR.TC

BFN-PUAR TABLE OF CONTENTS (Continued)

~Pa e 2.4.2 Partiall Submei'd Structures 2-3 2.4.2.1 S/RV Dischar e Lines 2-3 2.4.2.2 Turbine Exhaust and Return Lines 2-3 2.4.3 Above-Pool Structures 2-4 2.4.3.1 Catwalk and Vacuum Breaker Platforms 2-4 2.4.3.2 RHR S ra Header 2-4 2.4.3.3 Monorail 2-4 2.4.3.4 ~rwel l Wetwel 1 Vacuum Breaker Valves 2-4 2.5 S/RV Dischar e Lines in the Dr well 2-4 2e6 Torus Attached Pi in 2-5 2e7 Active Com onents 2-5 2.8 Torus Pene rat ons 2-5 3.0 LOADS FOR STRUCTURAL ANALYSES 3-1 3.1 Ori inal Desi n Loads 3-1 3.2 Newl Defined LOCA-Induced Loads 3-1 3.2.1 Desi n Basis Accident ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3-1 3.2.2 Intermediate Break Acciden t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3-4

3. 2.' Small Break Accident 3-5 3.3 Safet /Relief Valve Dischar e-Induced Loads 3-5 4.0 GENERAL DESIGN CRITERIA 4.1 Introduction 4-1 4.2 Load Definitions 4-1 4.2.1 General 4-1 4.2.2 ~SRV H dred namlc Loads 4-1 4.2.2.1 Inter retation 4-1 4.2.2.2 Justi ication 4-2 4.2.3 DBA Condensation Osc ill'ation H drod nam c pads 4-3 4.2.3.1 Inter retation 4-3 4.2.3.2 Justification 4-4 PUAR.TC

~ ~

BFN-PUAR TABLE OF CONTENTS (Continued)

~Pa e 4.2.4 Post-Chu H drod namic Loads 4-4 4.2.4.1 Inter retation 4-4 4.2.4.2 Justification 4-5 4.2.5 DBA Pool* Swell H drod namic Loads 4-5 4.2.5.1 Inter retation 4-5 4.2.5.2 Justification 4-6 4.3 Structural Acce tance Criteria 4-7 4.3.1 G eneral 4-7 4.3.2 Torus Dr well and Vent S stem Pressure Boundar Com onents 4-7 4.3.3 Pi in S stem Com onents Excluding Supports 4-7RI 4.3.4 Linear Su orts and Snubbers 4-8 4.3.4.1 Allowable Stress Criter ia 4-8 4.3.4.2 Justification 4-12 4.3.5 Variable S rin Su orts 4-12 4-12Rl 4.3.5.2 Minimum Re uirements 4-13 4.3.5.3 Justification 4-15 4.3.6 0 erabilit and Functionalit of 4-15 4.3.7 Nonsafet -Related Internal Stl uctures ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ 4-16 4.3. Reinforced Concrete Structures 4-16 4.3. 9 Fati ue Evaluation 4-16 4.4 Anal sis Procedures 4-17 4.4.1 General 4-17 4.4.2 Load Combination Techni ues 4-17 4 ~ 4 ~ 2.1 Torus and Vent S stem ...." 4-17 4.4. 2.2 Torus Attached Pi in S st em S/RV Pi in S stems Inside th e Torus and Other Nonsafet -Rela ted Internal Structures 4-17 PUAR.TC

BFN-PUAR TABLE OF CONTENTS (Continued)

~Pa e 4.4.2.3 S/RV Pi in S stems Inside the Dr well and Vent S stem .......... 4-17 4.4.2.4 Justi ication 4-18 4.4.3 S/RY Load Reduction Factors 4-18 4.4.4 Torus Anal sis Procedure 4-18 4.4.5 Vent S stem Anal sis Procedure 4-19 4.4.6 Torus Attached Pi in S stems Anal sis Procedure ~ ~ 4-20 4.4.7 S/RV Pi in S stems Anal sis Procedu re 4-22 4.4.8 Com onent 0 erabilit Procedure 4-23 4.4.9 Other Internal Structures Anal sis Procedure 4-24R1 4.5 Construction Code for Modificat ons 1 ~ ~ ~ ~ ~ 0 ~ ~ 4-25 4.6 S RV Confirmator Test 4-25 4.6.1 Test Ob'ective 4-25 4.6.2 Basic Test Re uirements 4-25 4.6.3 Test Re ort ~ ~ ~ ~ ~ ~ ~ ~ ~ 4-26 4.6.4 orrelatlon of Test Data With Anal sis 4-26 4.7 Permanent Anal sis and Desi n Documentation 4-26 4.7.1 Desi n CIiteria 4-26 4.7.2 Anal sis Calculations ~ t ~ ~ ~ ~ 4-26 4.7.3 Desi n Re uirements 4-26 4.7.4 References 4-27 4.7.5 Des 1 n Calculations and Drawi n s oI Modi cations 4-27 4.7.6 Surmar Re ort 4-27 5.0 TORUS CONTAINMENT STRUCTURE - ANALYSI S AND MODIFICATIONS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ 5-1 5.1 General Descri tion ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ 5-1 5.2 Torus Modi ications ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5-1 5.2.1 D namic Rin Girder Restraints Snubbers ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5-2 5.2.2 External Rin Girder Reinforc enlen t 0 ~ ~ ~ ~ ~ ~ 5-3 5.2.3 Tiedowns 5-3 5.2.4 Local Stiffenin 5-4 PUAR.TC

BFN-PUAR TABLE OF CONTENTS (Continued)

~Pa e 6.4 Vacuum Breaker/Main Vent End Ca Intersection 6.4.1 Anal tical Procedure 6-7 6.4.1.1 Anal tical Model 6-7 6.4.1.2 Static and D namic Loads 6-7 6.4.2 Controllin Load Combinations 6-7 6.4.3 ASME Code Allowables 6-7 6.4.4 Results and om arisons 6-8 6.5 Vent Header/Downcomer Intersection 6-8 6.5.1 Anal tical Procedure 6-8 6.5.1.1 Anal tical Models 6-8 6.5.1.,2 tat c and D nam c Loads 6-8 6.5.2 Controllin Load Combinations 6-8 6.5.3 ASME Code Allowables 6-8 6.5.4 Results And om arisons 6-9 6.5.4.1 Stress Evaluation 6"9 6.5.4.2 Fati ue Evaluation 6-9 6.6 Vent Pi e Drain 6-10 6.6.1 Anal tical Procedure 6-10 6.6.2 Controllin Load Combinations 6-10 6.6.3 Allowable Stress ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-10 6.6.4 Stress Resul s And Com arison S ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-10 6.6.5 Descri tion o Modi f ications 6-10 6;7 Downcomer/Tiebar Intersection 6-11 6.7.1 Anal tical Procedure 6-11 6.7.1.1 Anal tical Models 6-11 6.7.1.2 Static and D nam>c Loads 6-12 PUAR.TC

BFN-PUAR TABLE OF CONTENTS (Continued)

~Pa e 6.7.2 Desi n Load Combinations 6-12 6.7.3 owab e resses 6-13 6.7.4 esu s an om arisons 6-13 6.7.4.1 Stress Evaluation 6-.13 6.7.4.2 Fat ue Eva uation 6-13 6.7.5 Descri tion of Modifications 6-13 6.8 'ent Column Su ort Columns 6-14 6.8.1 Anal tical Procedure 6-14 6-14 6.8.2 Controll n Loa ombinations 6.8.3 A owable Stresses 6-14 6.8.4 Stress Results and Com arisons 6-15 6.9 Vent S stem Miter Bends 6>>15 6.9.1 Anal tical Procedure 6-15 6<<15 6.9.2 ontro 1 n Load ombinations 6.9.3 ASME ode Al owab es 6-15 6.9.4 tress Resul s and Com arisons 6-16 6.10 Torus Bellows 6-16 6.10.1 Anal tical Procedure 6-16

6. 10. 1. 1 Anal t i ca 1 Model 6-16 6.10.1.2 at c and D namic Loads 6-16

6. 10. 2 Desi n Loadin Conditions 6-17

6. 10. 3 A ME Code Al owables 6-17

6. 10. 4 Results and om ar sons 6-17 6.11 Vent Header Shell 6-17 6.11.1 Anal tical Procedure 6-17 6.11.1.1 Anal tical Model 6-17 6-18 6.11.2 Results and Com arisons ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-18 6.11.3 Descri tion o Mod ication s ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6-18 PUAR.TC

~ ~

BFN-PUAR TABLE OF CONTENTS (Continued)

~Pa e 10.4 Results and Conclusions 10-4 10.5 Descri tion of Tem erature Monitor ln S stem e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 10-5 11.0

SUMMARY

AND CONCLUSIONS ll-l 11.1 G eneral 11-1 11.2 Browns Ferr Desi n Criteria 11.3 Structural Anal ses and Desi of Re u i red Mod i f i ca t ions n

ll-l 11-2 11.4 S/RV Confirmator Test

11. 5 Installation of Modifications and Final Conclusions 11-2

12.0 REFERENCES

12-1RI APPENDIX A.O TORUS ATTACHED PIPING ANALYSIS PROCEDURES AND CRITERIA A-1 A.i Introduction e ~ ~ . ee

~ ~ ~ e ~ eeee A-I A.2 Sco e A-I A.3 Definitions A-2 A.3.1 Essential Pi in ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ A-2 A.3.2 Nonessential Pi in ~ ~ A-2 A.3.3 Active Com onent A-2 P

A.4 Anal tical Models A-2 A.4.1 Pi in Model Boundar res A-3 A.4.2 Torus Interface ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ A-3 A.4.2.1 Coordinate S s tern A-3RI A-3 A.4. 3 Process Pi in A-4 A.4. 4 Branch Lines ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ A-4 A.4. 5 Va ves1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ A-5 A.4. 6 F~lan es A-5 A.4. 7 Reducers A-5 A.4. 8 ~Sn or ts ~ ~ ~ ~ A-5 A.4. 9 S ecial Consider atio ns ~ ~ ~ A-6 A.4. 10 Com onent Nozzle At tac hm en ts A-6 xiv PUAR.TC

BFN-PUAR TABLE OF CONTENTS (Continued)

~Pa e A.S Load Sources A-6 A.5.1 General A-6 A.5.2 Seismic L oads ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ A-7 A.5.2.1 0 erative Basis Earth ua ke A-7 A.5.2.2 Safe Shutdown Earth uake A-7 A.5.3 Thermal Loads A-7R1 A.5.4 Torus Motion and Dra Load A-8 A.6 Anal sis Procedures A-8 A.6.1 Introduction 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ A-8 A.6.2 Modelin Assum tions A-8 A.6.3 Deadwei ht Anal sis A-9 A.6.4 Thermal Load Case Anal sis ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ A-9 A.6.5 Seismic Anal sis A-9 A.6.6 LOCA and S RV Anal sis A-10 A.6.6.1 D namic Inertial Efforts A-10 A.6.6.2 D namic Dis lacements ~ ~ ~ ~ ~ ~ ~ A-11 A.6.6.3 Thermal and Pressure Dis lac erne nts A-11 A.6.6.4 Fluid Motion A-11 A.6.7 Anal sis Results A-11 A.7 Load Case Combinations A-11 A.7.1 Introduction 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ A-11 A.7.2 Combinations Used for Pi in Su or ts and Act i ve Com onent Eva luations A-12 A.7.3 Combinat ions Used for Eval uation of Pi in S stem Reactions on Torus Penetrations A-12 A.7.4 Combinations Used for Evaluation of Valve Accelerations A-12 A.8 Process Line Evaluations A-12 A.8.1 Code Jurisdiction A-12 A.8.2 Pi in Evaluation Procedur e A-12 XV PUAR.TC

BFN-PUAR TABLE OF CONTENTS (Con t i nued )

~Pa e D.l.l.l Bubble-Induced Pool Swell Dra Load s ~ ~ ~ D-1 D.l.l.2 Downcomer Water Jet Loads D-1 D-2 D.1.1.3 Bulk Pool Mo on Loa s D.1.2 Condensation Oscillation and Chu in D D>>2 D.1.2.1 Pseudo Res onse S ectrum Method D-2 D.l.2.2 E uivalent Static Load Method D-16 D.l.2.3 DBA Condensation Oscillation Dra L Oads D-17 D.l.2a4 Chu iu Dra Loads D-17 D.1.3 S/RV Dra Loads D-19

=

D.l.3.1 T- uencher Bubble-Induced Dra Loads ~ ~ ~ ~ ~ ~ ~ ~ ~ D-19 D.l.3.2 T- uencher Water Jet Loads ~ ~ ~ ~ ~ ~ ~ ~ ~ D-21 D.2 -

Above-Pool Fluid-Induced Loads D-21 D.2;1 Pool Swell- Im act and Dra Loads D-21 D.2.2 Froth Im n ement Loa s D-21 D.2.3 Fallback Loads D-22 APPENDIX E.O IMPLEMENTATION OF CONSISTENT FLU ID MASS MATRIX FOR TORUS MODEL E-1 IL E-1 E.2 Im lementation E-1 APPENDIX F.O MAJOR COMPUTER CODES F-1 APPENDIX G.O PHOTOGRAPHS G-1 xviii PUAR.TC

I I

BFN-PUAR LIST OF ILLUSTRATIONS

~Ft u re Tt tie 2-1 Browns Ferry Containment Configuration 2-2 Plan of Torus 2-3 Cross Section of the Torus 2-4 Plan of Vent System 5-1 Snubber, Base Plate, and Local Stiffening 5-2 External Ring Girder Reinforcement 5-3 Nozzle Reinforcement 5-4 22-1/2o Model Ring Girder, Cradle Section 5-5 22-1/2o Model 5-6 180o Model - Lower Half 5-7 Mid-Bay, 10.1 Hz Shell Mode 80 Percent Water 5-8 Tangential Shell Motions at X-214 Due to hP Pool Swell 5-9 Tangential Respons'e Spectrum at X-214 Due to hP Pool Swel 1 6-1 Drywell/Main Vent Intersection 6-2 45o Model - Vent Header, Main Vent, Downcomers, Tiebars 6-3 180o Model Vent System 6-4 Bechtel Finite Element Model of Vent System 6-5 Main Vent/Vent Header Intersection - Finite Element Model 6-6 Vacuum Breaker/Main Vent End Cap Intersection 6-7 Vent Header/Downcomer Intersection Finite Element Model 6-8 Vent Pipe Drain 6-9 Final Design of Downcomer/Tiebar. Configuration 6-10 Downcomer/Tiebar Intersection Finite Element Model 6-11 Revised Mesh for Downcomer/Tiebar Attachment Region 6-12 Downcomer Condensation Oscillation Load Application 6-13 Probability of Exceeding a Given Force per Downcomer for Different Numbers of Downcomers 6-14 Typical Pressure Pulse Experienced by Vent Header 6-15 Thrust Loads xix PUAR.IV

BFN-PUAR LIST OF ILLUSTRATIONS (Continued)

F~t'u r e Tt tie 7-1 Typical Quencher/Quencher Support Structure 7-2 Typical Installation of Additonal Vacuum Breaker 7-3 S/RV Discharge Layout in the. Torus 7-4 Vent Penetration Reaction Box 7-5 Vent Penetration Reinforcement for S/RV Discharge Lines M and N

~

7-6 S/RV Discharge Line Routing and Supports in the Main Vent 7-7 Typical S/RV Discharge Line Model 7-8 Analysis Model Typical Short Line 7-9 Analysis Model - Typical Long Line 7-10 Typical Node Location - Quencher and Box Beam 7-,11 Typical S/RV Blowdown Forcing Function for Horizontal Segment of Typical Long Line Showing Water Clearing Loading "7-12 Typical Pool Swell Force-Time History 8-1 Plan View of Torus Spray Header Supports 8-2 Core Spray Test Return Line Internal Piping Modifications 8-3 Orientation of RHR Discharges 8-4 Strainer Basket Modifications 8-5 Typical Modification of Attached Piping, Vents, Drains and Test Connections 8-6 Typical Flexible Hose Application Torus Instrumentation Piping 8-7 RCIC Turbine Exhause Upper and Lower Supports 8-8 RCIC Turbine Exhaust Upper Support 9-1 Catwalk Plan View 9-2 Catwalk Knee Brace 9-3 Catwalk - Vacuum Breaker Valve Platform 10-1 Coupled Reactor and Suppression Pool Model 16-2 Plan View of Browns Ferry Suppression Pool with T-Quenchers and RHR Discharge Locations 10-3 Bulk Pool Temperature and Vessel Pressure Response, Case lAX 10-4 Local Pool Temperature Response, Case lAX 10-5 Bulk Pool Temperature and Vessel Pressure Response, Case 2AX PUAR.IV

BFN<<PUAR LIST OF ILLUSTRATIONS (Continued)

~Fl ere Title 10-6 Local Pool Temperature Response, Case 2AX 80 Percent Water Fluid Mesh 10-7 Thermowell Orientation Inside Torus 10-8 Schematic of BFN Torus Showing Bulk Temperature Sensor Locations 10-9 Suppression Pool Temperature Monitoring System Block Diagram A-1 Global Coordinate Definition A-2 Local Coordinate Definition for Torus Nozzles A-3 Local Coordinate Definition Detail A-4 Directions for Torus Penetration Spring Constants A-5 Differential Fluid Temperature Between Torus and ECCS Ring Header During DBA, IBA, and SBA B-1 Typical Concrete Anchors C-1 Strain Gage Rosette Locations - Torus Shell C-2 Pressure Transducer Locat.ions C-3 Acceleration and Displacement Transdu'cer Locations - Outer Shell C-4 Saddle Gage Locations C-5 RCIC Turbine Exhaust Gage Locations C-6 RCIC Vacuum Relief and Test Line Transducer Locations C-7 ECCS Header and Associated Gage Locations C-8 RHR Test and Restraint Gage Locations C-9 Downcomer Gage Locations C-10 Quencher Support and S/RV Gage Locations E-1 80 Percent Water Fluid Mesh

"- PUAR. IV

BFN-PUAR LIST OF ILLUSTRATIONS (Cont i nued) e Plate Ti tie 1 Torus Snubber and Base Plate; ECCS Header Suppor t 2 External Ring Girder Reinforcement 3 Torus Tiedown System 4 Vent Header Column Support Extension 5 Cradle Reinforcement 6 ECCS Header Penetration Shell Reinforcement 7 Reinforcement of Vent Header and Downcomer 8 Reinforcement of Vent Header 9 Downcomer Tiebar and V-Bracing 10 Typical Overhead View of, Ramshead/Quencher/Boxbeam Arrangement Typical Quencher/Boxbeam Installation Showing Quencher Midspan Clamp and End Point Lateral Lug 12 Typical Boxbeam to Ramshead Support Connection 13 Typical Perspective of S/RV Pipe/Quencher/Boxbeam i'n Torus Showing Overhead Reroute of S/RV Lines E and M 14 Typical S/RV Long Line Showing Vertical and Horizontal Struts with Ring Girder Re in forcement 15 Main Vent Reaction Box for Typical Two S/RV Line Penetration e 16 Main Vent Reaction Box for Typical Three S/RV L'ine Penetration 17 Torus Spray Header Support 18 RHR Vertical and Horizontal Bracing 19 RHR Support Collar 20 HPCI Support Collar 21 HPCI Vertical'nd Horizontal Bracing 22 X-204 A Thru D Penetration Support for ECCS Header 23 Process Suction Line "TEE" Support and ECCS Header 24 RCIC Turbine Exhaust First Axial Restraint 25 Catwalk From Below 26 Catwalk Knee Brace and Longitudinal Pipe Connection 27 Catwalk, Handrails, Vacuum Breaker, Valve Platform, and Monorail 28 Typical S/RV Pipe Support Inside Main Vent 29 Triple S/RV Line Routing Inside Main Vent; Replacement of 70o Miters with Elbows 30 General View of Work Including V-Brace, RHR Return Line, Quencher and Quencher Support, and S/RV Strut Modification XXX'UAR.IV

BFN-PUAR LIST OF TABLES Tab 1 e Tf tie 2-1 Principal Design Parameters and Characteristics of Primary Containment 2-2 Torus Attached Piping Penetrations 2-3 Active Components for Operabil'ity Evaluation 3-1 Event and Load Combinations 5-1 Allowable Stresses - Torus Shell and Ring Girder 5-2 Maximum Torus Reactions

'-1 Load Combinations and Service Levels for Drywell/Main Yent Intersection 6-2 Maximum Stress Intensities on Drywell/Main Vent Intersection 6-3 Vent System Analysis Temperature and Pressure (Wetwell) 6-4 Vent System Analysis Temperature and Pressure (Drywell) 6-5 Controlling Load Combinations and Service Levels of Main Vent/Yent Header Intersection 6-6 Maximum Stress Intensities on Main Vent/Vent Header Intersection 6-7 Controlling Load Combinations and Service Level of Yacuum Breaker/Main Vent End Cap Intersection 6-8 Maximum Stress Intensities on Vacuum Breaker/

Main Vent Intersection 6-9 Controlli,ng Load Combinations and Service Levels of Downcomer/Yent Header Intersection 6-10 Maximum Stress Intensities on Downcomer/Vent Header Intersection 6-11 Fatigue Usage Factors for Containment Vent System 6-12 Controlling Load Combinations and Service Levels of Downcomer/Tiebar Intersection 6-13 Maximum Stress Intensities on Downcomer/Tiebar Intersection 6-14 Stress Evaluation of Tiebar 6-15 Controlling Load Combinations and Service Levels of the Vent Column Supports 6-16 Stress and Buckling Evaluation on Vent Column Supports 6-17 Maximum Stress Intensities on Main Vent Miter Bends 6-18 Maximum Stress Intensities on Vent Header Miter Bends 6-19 Maximum Stress Intensities on Downcomer Miter Bends 6-20 Stress Evaluation at Key Locations for Zero B,P XXX'.i PUAR.TB

BFN-PUAR LI ST OF TABLES (Con t i nued)

Table Title 7-1 Drywell Load Combinations 7-2 NOC Service Levels B and C Load Combinations 7 "3 SBA/IBA Service Levels C and D Load Combinations 7-4 DBA Service Level D Load Combinations 8-1 Torus Attached Piping Systems 8-2 Limiting Case Event Combinations and Service Levels for Torus Attached Piping, Piping Supports, and Equipment Nozzle Loads 8-3 Limiting Case Event Combinations and Service Levels for Piping Loads on Torus Shell and Nozzles 8-4 Number of Supports Removed, Modified, and Added to Unit 1 RHR System Torus Attached Piping 10-1 Sumnary of Results Browns Ferry Suppression Pool Temperature Response of Results -

10-,2 Sumnary RHR Heat Heat Exchanger Flow Rate 10-3 Suppression Pool Temperature Monitoring System Environmental Requirements ll-l Sunmary of BFN LTP Modifications A-1 Spring Constant Sumnary A-2 Load Cases for Torus Attached Piping Systems A-,3 Expected Piping Segment Temperatures for BFN A-4 Analysis Criteria for Torus Attached Piping-LOCA Effects A-5 Limiting Case Event Combinations for Valve Accelerations C-1 Torus Shell Stress Comparison C-2 Torus Shell Pressure Comparison C-3 Torus Acceleration and Displacement Comparison XX'UAR.TB

BFN-PUAR LIST OF ABBREVIATIONS ABBREV I AT ION ABS Absolute Suranat ion AC I Amer i can Conc re te I ns t i tu te ADS Automatic Depressurization System Architect/Engineer AI SC American Institute of Steel Construction ANSI American National Standards Institute

'SME American Society of Mechanical Engineers AS'IM American Society of Testing Materials BDC Bottom Dead Center BFN Browns Ferry Nuclear Plant BWR Boiling Water Reactor CFR - Code of Federal Regulations CH Chugging CAN Consistent Mass Matrix CO Condensation Oscillation DBA Design Basis Accident DLF Dynamic Load Factor ECCS Emergency Core Cooling System EN DES Engineering Design EP Engineering Procedure EPRI Electric Power Research Institute EQ Earthquake F Fahrenheit F SAR Final Safety Analysis Report FS I Fluid Structure Iteration FSTF Full Scale Test Facility g Acceleration due to gravity (32.2 ft/sec2)

GE General Electric Company gpm -

Gallons per minute HPCI High Pressure "Coolant Injection Hz Hertz IBA Intermediate Break Accident ksi Kips per square 'inch LDR Load Definition ReportCondition LOCA Loss-of-Coolant Accident LTP Long-Term Program

,'MCR Main Control Room MS Main Steam MSIV Main Steam Isolation Valve NOC Normal Operating .

NRC Nuclear Regulatory Conmission PUAR.BV

BFN-PUAR ABBREVIATION (Con t i nued)

OBE Operating Basis Earthquake Pb Primary bending stress PL Local primary membrane stress Pm General primary membrane stress PIM Pittsburgh Des Moines psi Pounds per square inch psia Pounds per square inch absolute .

psid Pounds per square inch differential psig Pounds per square inch gage PUAAG Plant Unique Analysis Application Guide PUAR Plant Unique Analysis Report PULD Plant Unique Load Definition Q Secondary stress due to primary plus bending QSTF Quarter Scale Test Facility RC I C Reactor Core Isolation Cooling RHR Residual Heat Removal RPS Reactor Primary System RPV Reactor Pressure Vessel RTD Resistance Temperature Detectors Sy Yield Stress Sa Alternating Stress Intensity San Spectral Acceleration SAC Structural Acceptance Criteria SBA Small Break Accident SER Safety Evaluation Report SORV Stuck Open Relief Valve SRSS Square Root of the Sum of the Squares S/RV Safety/Relief Valve

'SSE Safe Shutdown Ear thquake STP Short-Term Program TES Teledyne Engineering Services TKM Tributary Mass Matrix TVA Tennessee Valley Authority WRC Welding Research Council ZPA Zero Period Acceleration PUAR.'BV

BFN-PUAR Truncation of the downcomers reduces pool swell -loads.

Addition of S/RV quenchers and RHR return elbow discharge devices ensures stable steam condensation during S/RV blowdowns for all postulated accident conditions. The quenchers also mitigate S/RV discharge loads on the tori for all normal and postulated LOCA events. Finally, addition of the 10-inch S/RV vacuum breakers reduces water clearing loads on the S/RV piping systems for rapid second actuation conditions.

-The basic functional requirements for these modifications

'ere defined from generic and plant unique information provided by the Mark I Owners Group and GE and approved by NRC. The other generically approved load mitigation methods were inappropriate or unnecessary for BFN.

1.6.2 Com osition of the BFN-PUAR 1.6.2.1 Contents BFN containment systems are described in Section 2. The new hydrodynamic loads for structural analysis of those systems are suranarized in Section 3. Structural analysis of the BFN. containment systems and structural design of the necessary plant modifications were performed according to the BFN LTP general design criteria described in Section 4.

The five basic categories of structural analysis and design activity ar'e described in Sections 5 through 9.

An evaluation of the bulk and *local pool temperatures for various postulated accident conditions was conducted as required by NUREG 0661. Section 10 surrrnarizes the results of that evaluation and describes the new pool temperature monitoring system for each BFN unit.

Section ll gives a general sunmary and status of BFN LTP and related modification activities upon submittal of this report for NRC review (on approximately December 31, 1983).

It also draws basic conclusions regarding completion of BFN LTP activities for all three BFN units.

Additional information on structural analysis and design methods, as well as confirmatory postmodification S/RV test results, are given in Appendices A through F. Appendix G contains construction photographs of some major BFN LTP modifications.

1-5 PUAR. 1

BFN-PUAR The Table of Contents,.beginning on page ii, lists the headings and subheadings of each sect ion and appendix. It locates .the List of Tables, List of Illustrations, and List of Abbreviations, as well as References.

The title page of each section and appendix is brown, to provide easy access. The text of each section and appendix is numbered separately. For example, page 2-9 is the ninth page in Section 2.

Illustrations include both figures and plates (photographs).

All figures and tables are located at the end of each section and appendix. For example, Figure 2-1 is the first figure in Section 2 and Table A-2 is the second table in Appendix A. Plates are located in Appendix G.

1-6 'PUAR. 1

BF¹ PUAR The QBUBS02 code predicts shell pressures which envelop both rigid-wall and flexible-wall test data. It also predicts conservative attenuation rates with time which produce conservative dynamic amplification of torus motion inputs to piping systems and other components attached to the torus.

The first mode frequencies of the vent system downcomers in both the longitudinal and transverse directions were within the frequency range of S/RV discharge air bubbles.

Therefore, use of the conservative load attenuation with time according to computer code TQFORBF would result in excessively conservative predictions of downcomer responses. The more realistic attenuation rates of TQFOR03 provided a reasonable drag load definition for combination with other downcomer loads and design of downcomer bracing modifications.

SRSS of multiple valve effects in combination with the conservative aspects of this load definition produced a reasonable analysis and design approach. Absolute suranation of multiple valve effects would be excessively conservative because there are 13 S/RV lines discharging into 16 bays of each BFN torus (see Figure 7-3).

Both single and multiple valve tests were run in the S/RV confirmatory test, thereby verifying the overall load interpreta tion and analytical approach. Load reduction factors were conservatively defined based upon correlation of both single and multiple valve test result's (Appendix C).

4.2.3 DBA Condensation Oscillation H drod namic Loads 4.2.3.1 Inter retation The torus was analyzed for shell pressure harmonic forcing functions at 1-Hz intervals from to 30 Hz. Forcing 1

functions above 30 Hz were neglected.

Referring to Table 4.4.1-2 and Figure 4.4.1-1 of the LDR (Reference 14 ), the largest input pressure coefficient for each 1-Hz interval was selected from the three alternatives.

The response for each interval was determined on the basis of maximum r'esponse for any frequency within the 1-Hz band.

Then the responses was combined by the following procedure:

1) The responses for four forcing functions (at 4-5 Hz, 5-6 Hz, 10-11 Hz, and 15-16 Hz) were added absolutely.

PUAR. 4

BFN-PUAR

2) The responses for the other 26 forcing functions we r e combined by SRSS.

3) The results of I) and 2) were added absolutely.

DBA condensa t ion osc i liat ion (CO) drag load responses for each structural mode were determined by the same procedure.

4.2.3.2 Justification This interpre(ation was developed early in 1980 on the basis of Full Scale Test Facility (FSTF) data analysis by GE and Mark I LTP consult'ants. That data analysis indicated that input above 30 Hz is of such low energy content as to be negligible in determining torus response. Further, the forcing functions were found to have little or no phase relationship to each other. Very loose phase relationships were seen by one study for forcing functions at 5-6, 10-11, and 15-16 Hz, whereas a more definitive study, Reference 19, showed essentially random phasing of all fo'rcing functions.

The procedure outlined above recognized the remote possibility of constant phase 15-16 relationships between forcing functions at 5-6, 10-11, and Hz. It also recognized the random phasing between all other forcing functions and assured that the desired 84 percent nonexceedance probability was achieved.

Additional conservatisms which were inherent to the BFN DBA CO analysis methods are described in Section 5.4.2.9 and Appendix D.

This interpretation reduced the total calculated response by a factor of 2 or more relative to absolute summat ion of maximum responses for a I 1 50 forc ing functions defined in the LDR. Therefore it eliminated excessive conservatism but ensured a satisfactory nonexceedance probability of the pr edic ted dynamic responses.

4.2.4 Post-Chu H drod namic Loads 4.2.4.1 Inter retation The torus was analyzed for shell pressure harmon ic functions at I-Hz intervals from I to 30 Hz. Forcing functions above 30 Hz were neglected. The dynamic response for each of the 30 forcing functions was calculated separately on the basis of maximum response for any frequency within the I-Hz band.

Then the responses were combined by 'absolute summation.

4-4 PUAR. 4

BFN-PUAR Post-chug drag loads were defined and analyzed for harmonic forcing functions at I-Hz intervals from 1 to 50 Hz. The dynamic responses for each interval were determined on the basis of maximum response for any frequency within the 1-Hz band. Then the combined response for each structural mode was determined by absolute sumna tion of th'e response for the five largest input coefficients plus SRSS of the other 45 responses.

4.,2.4.2 Justification This interpretation was justified by analysis of FSTF data as documented by Reference 20. The procedure for torus analysis was established and the analysis was performed before completion of Reference 20. By relating Reference 20 results to those obtained by this procedure it was clear that the desired 84 percent nonexceedance probability response was attained. (See Section 5.4.2.11- for a more detailed discussion of this topic.)

The procedure for post-chug drag load on submerged struc-tures is in compliance with the recommendation of Reference 20 for 84 percent nonexceedance probability loading.

Appendix D gives a detailed discussion of the BFN fluid drag load analytical method and identified conservatisms inherent to that method.

.This interpretation reduced the analytically predicted responses by a factor of 2 or more relative to the absolute surrmation of responses for all 50 inputs . Therefore, it eliminated significant excess conservatism from the load definition, but preserved the desired nonexceedance probability.

4.2.5 DBA Pool Swell H drod namic Loads 4.2.5.1 Inter retation The torus was analyzed for average hydrodynamic pressure loads as def ined by the PULD and LDR Sect ion 4.3.2. A 6.5 percent margin was added to predicted responses to account for uncertainties in the test data for both operating and zero b,P cases.

The vent system and S/RV piping systems in each torus were analyzed for pool swell impact and drag loads at operat ing and zero hP cond it ions, as defined by the PULD and LDR.

Zero bP ve 1oc i ty, d i splacement, and c i r cumferent ia1 t ime 4-5 PUAR. 4

BFN-PUAR delay curves were defined from the 1/4 scale BFN test results. Resulting vent support column reaction time histories for each condition were applied to the torus model in combination with the corresponding pool swell average pressure loads, prior to addition of the 6.5 percent uncertainty margin described above.

Pool swell impact and drag loads for other internal structures were analyzed for one enveloping load case in accordance with LDR Section 4.3.4 and the PULD.

4.2.5.2 Justification This interpretation was based upon the fact that the 1/12 scale Electric Power Research Institute (EPRI) 3-dimensional test model was a prototypical model of BFN in every significant detail and it was consistent with the BFN 1/4 scale model. This fact eliminated the majority of NRC's concerns expressed in NUREG 0661, which led to specification of an additional 15 percent upload margin and definition of an, enveloping longitudinal time delay and velocity distribution 'for the vent system and other above-pool structures.

The'FN torus was analyzed with a constant effective added fluid mass equal to 80 percent of the total contained fluid mass. The 6.5 percent margin exceeded one standard deviation of the BFN 1/4 scale test "data. These considerations ensured an upper bound prediction of torus response, pal ticularly during the upload phase. (See Section 5.4.2.7 for a more detailed discussion in this regard.)

The vent system and S/RV piping systems pool swell. impact analysis in the unmodified and modified conditions was completed well before release of NUREG 0661 and subsequent revision of the BFN PULD. The interpretation defined above was more accurate for BFN than that identified by NUREG 0661 Appendix A and it predicted higher impact velocities for the critical regions of the vent header and S/RV piping.

Therefore, reanalysis of the BFN vent system and S/RV piping for revised longitudinal variations was not necessary or appropriate. (See Sections 6 and 7 for more discussion of the vent system and S/RY piping analyses.)

Other above-pool structures were conservatively analyzed for one enveloping pool swell impact and drag load case in accordance with NUREG 0661. (Appendix D describes the specific analytical method which was applied.)

4-6 PUAR. 4

BFN-PUAR 6.4 Vacuum Breaker/Main Vent End Ca Intersection The vacuum breaker valves located on the end cap of the main vent pipes are evaluated in the following paragraphs.

Figure 6-6 shows the vacuum breaker/main vent intersection.

6.4.1 Anal tical Procedure 6.4.1.1 Anal tical Model The vacuum breaker intersection was modeled using the TPIPE computer program (see Appendix F) for consideration of reactions induced by pool swell vent response and coincident loads. A set'f shell pipe intersection spring rates was calculated using Bijlaard procedures from Reference 64.

Using the output reactions from the'TPIPE model, the shell stresses at the vacuum breaker penetration were dete.rmined using the WERCO computer program.

6.4.1.2 Static and D namic Loads Due to location, the load 'experienced by the vacuum breaker valve varies from the loading imposed on structures previously discussed. The vacuum breaker elevation is such, that it is above the water level inside the torus. This significantly reduces the number of phenomena that will act upon the valves. S/RV loads, CO loads, and chugging loads

'are i'nsignificant at this location, leaving only the effects from pool swell, deadweight, and seismic. Time history data generated by Bechtel Corporation (Reference 17) for the pool swell impact loading analysis was input into the TPIPE model.

6.4.2 Controllin Load Combinations The number of controlling load combinations required to evaluate this component was reduced to one. Table 6-7 identifies that combination.

6.4.3 ASME Code Allowables The allowable stress intensities for SA-516 GR 70 carbon steel are shown in Table 6-8. This is consistent with the material composition at the temperature provided in Table 6-3.

~ L 6-7 PUAR. 6

BFN-PUAR 6.4.4 Results and Com ar isons The stress experienced by the vacuum breaker/main vent intersection was in large part due to the pool swell impact load. Thus, only combination event 18 from Table 3-1 was required for analysis as seen, in Tables 6-7 and 6-8. The calculated stress intensity of 16.7'ksi was well below the Service Level B allowable of 28.95 ksi.

6.5 Vent Header/Downcomer Intersection The vent header and downcomer pairs typically intersect as shown in the finite element representation which simulated this intersection (Figure 6.6).

6.5.1 Anal tical Procedure 6.5.1.1 Anal tical Models The vent header/downcomer intersection was modeled into 45o and 180 beam models for the purpose of evaluating loads described in Section 6.5.2. Flexibility constants were input at adjacent nodes which, when connected, formed a short beam portraying the spring rate of the intersection.

Analysis output forces and moments from the beam models were input to a STARDYNE computer code finite element plate and shell model as shown in Figure 6-6. The fine mesh of elements ext'ending around the intersection serv'ed to obtain accurate stress output.

6.5.1.2 Static and D namic Loads The loading conditions to which the vent header/downcomer intersection.-was subjected are identical to those outlined in Section 6.2.1.2.

6.5.2 Controllin Load Combinations The 27 load combinati ons were reduced to three controlling combinations as .shown in Table 6-9.

6.5.3 ASME Code Allowables The material composition of the vent header/downcomer intersection is SA-516 GR 70 carbon steel. Stress intensity allowable values are listed in 'Tables 6-10.

6-8 PUAR. 6

BFN-PUAR 6.5.4 Results and Com arisons The results and comparisons presented in this section ar' products of stress and fatigue evaluations. The fatigue analysis provides information for DBA, SBA, and IBA

=conditions.

6.5.4.1 Stress Evaluation The downcomer/vent header stress evaluation was completed using the controlling combinations in Table 6-9. The intersection was most affected by the PL + Q stress category during the DBA condensation oscillation event from Case 27.

The calculated stress intensity of 57.6 ksi, compared to an allowable of 57.9 ksi, could be further reduced by removing thermal expansion since it is a one-time occurrence. The most critical pool swell event combination resulted a stress intensity of 44.4 ksi as compared to a 45.2'a ksi allowable.

The SBA chugging combination 15, realizing PL + Q stress intensity of 53.3 ksi, could also be reduced by removing the thermal loads as previously mentioned.

6.5.4.2 =.

Fati ue'Evaluation The ASME Code for Class MC 'requires that a component or structure be evaluated to demonstrate adequate margin, against fatigue damage in a cyclic load environment. The approach for this evaluation is to compare maximum stress cycle histogram components with conservative strain cycling

,fatigue data. The strain cycling data is defined by the fatigue curve in Figure I-9 of the Appendices to the ASME Code. This figure plots the alternating stress intensity (Sa) against the number of allowable cycles which may occur for that particular stress intensity. An analysis for cyclic service is not required for a vessel, component, or structure, provided that Paragraph NE-3221.5d is satisfied for all conditions. The only components of the vent system requiring further evaluation were the downcomer/vent header and downcomer/tiebar intersections and the torus bellows/

main vent connection. These three portions of the vent system were critical because of their discontinuity and stress concentration characteristics which resulted in high localized stresses.

Since the occurrence of one accident condition (DBA, SBA, or IBA) and cumulative normal load occurrences was postulated in the fatigue life of the vent system, all three LOCA 6-9 PUAR. 6

BFN-PUAR events were examined. Table 6-11 presents the usage factors compared with the allowable fatigue usage. Note that thermal transient through-wall stresses were not included in the fatigue evaluation since that stress profile would occur only one tim'e in the design life.

6.6 Ven't Pi e Drain r1 The vent drain is located at the lowest elevation of the head at the end of the main vent inside the wetwell. The drain extends into the water and must be able to withstand the hydrodynamic and accident related loads resulting from a LOCA. The following sections confirm the fact that the drain and modified support configuration shown in Figure 6-8 and described in Section 6.6.5 are qualified.

6.6.1 Anal tical Procedure The vent drain and support were modeled into STARDYNE and a modal analysis was performed. It was determined that the dominant frequency (35.1 Hz) was in a key range for chugging; The resulting loads were evaluated by simple hand calculations.

6.6.2 Controllin Load Combinations Since the frequency of the vent drain and support is out of the range of the condensation oscillation event, it was determined by inspection that either combinations 11, 16, 18, or 25 would control. Because the structure would be in resonance with key post-chug frequencies, combination ll (SBA + S/RV + CH) actually, controls.

6.6.3 Allowable Stress The allowable stress for SA-333 GR B carbon steel is 0.66 times the yield stress, or 23.1 ksi, in accordance with Se'ction 4.3.4.

6.6.4 Stress Results and Com arisons The calculated stress in the new support structure is 21.1 ksi. This is less than the allowable value of 23.1 ksi.

6.6.5 Descri tion of Modifications t

The vent pipe drains were truncated to the same elevation as the vent header downcomers, i.e., three feet below minimum pool level. The existing support for each drain was removed 6-10 PUAR. 6

BFN-PUAR 6.?.3 Allowable Stresses The downcomer/tiebar intersection is made of SA-516 Grade 70 carbon steel. Table 6-13 compares actual stresses derived from the analyses with the ASME and AISC Code allowable stresses per Section 4.3.2 and Section 4.3.4.

E 6.?.4 Results and Com arisons 6.7.4.1 Stress Evaluation The downcomer/ ti ebar intersection was analyzed to Service Level B for Cases '15, 25, and 27. From Tables 6-12 and 6-13, the greatest primary plus secondary stress occurs during the SBA event. The maximum calculated stress intensity was 53.8 ksi, compared to the stress allowable of 57.9 ksi. The largest primary local membrane stress intensity of 27.9 ksi also occurred 'during the SBA event for Case 15, as compared to a 28.95 ksi allowable stress.

The ti char itself was further analyzed as a linear support for the loads described in Tables 6-12 and 6-13. As seen from Table 6-14, the most severe stress occurred during the CO event combination at a level of 20.1 ksi. This is below the allowable of 0.66 times the yield stress, or 23 ksi.

6.7.4.2 Fati ue Evaluation The fatigue evalu'ation of the downcomer/tiebar intersection is comparable to the evaluation discussed in Section 6.5.4.2. It can be seen from Table 6-11 that the usage factors are well below 1.0, as required.

6.7.5 Descri tion of Modifications A new tiebar with V-bracing members was required between each downcomer pair to minimize downcomer lateral response induced by condensation oscillation effects. As a result, bending stresses in-the vent hea'de'r/downcomer intersection are reduced and no further reinforcement of that area was required, except as described in Section 6.11.

The tiebar was installed at elevation 534'-0" and the V-bracing members intersect the tiebar at midspan.

Fabrication consisted of 3- and 4-inch schedule 40 pipe for the tiebars with short sections of 3-1/2-inch schedule 40 pipe for the bracing at .the downcomer end to facilitate field adjustability. All pipe material is ASTM A 53 Grade B or A 106 Grade B.

6-13 PUAR. 6

BFN-PUAR'he connections to the downcomer shell were reinforced using pad plates rolled to match contour and wrapped 120o. The plates were 1/2-inch thick by .7 inches wide'or the tiebar connection and 5/8-inch thick by 7 inches wide for the bracing connection. Additional 3/8-inch gussets and small pad plates were provided at the tiebar ends to distribute the loads for adequate structural integrity. A 3/8-inch thick saddle plate was provided at the bracing to tiebar intersection to distribute stresses. All plate material is ASME SA-516 Grade 70. For the configuration, see Figure 6-9 and Plate 9.

I 6.8 Vent Header Su ort Columns 6.8.1 Anal tical Procedure The vent header support columns are 8-inch diameter double extra strong pipes attached to the vent header miter bends via pipe collars. Figure 6-2 shows the support columns as they are represented in the computer model; The beams extending from the straight portion of the columns to-the vent header are rigid, representing the minimal flexibility of the collars.

6.8.2 Controllin Load Combinations The'7 design load combinations were reduced to three controlling cases given in Tables 6-'15 and 6-16.

6.8.3 Allowable Stresses The vent column supports are constructed of 8-inch double extra strong A 53 Grade B piping. Table 6-16 compares actual st,resses derived from the analysis with AISC stress allowables per Section 4.3.4..

6.8.4 Stress Results and Com arisons I

The calculated stresses indicated by Table 6-16 are less than the allowable stress of 16.6 ksi. The combination of events in Table 6-15 are composed of Service Level C loads and compared against Service Level B allowables. The most severe case is due to pool swell impact which imposes a stress of 10.4 ksi. The buckling check evaluates the maximum axial load plus bending moment and shows the highest combined effect occurring for pool swell as expected. The maximum buckling factor is 0.63 compared to a Service Level B allowable of 1.0.

6-14 PUAR. 6

BFN-PUAR 6.9 Vent S stem Miter Bends There are three structural areas in the vent system at which miter bends are located. The main vent, vent header, and downcomer miter bends are all Class MC components. However, for analysis purposes these items lend themselves more to treatment as piping components. Paragraph NB-3680 was introduced for stress evaluation while retaining the Class MC allowables. The following subsections surrrnarize the analysis of these three types of miter bends.

6.9.1 Anal tical Procedure As mentioned above, the ASME Code provides a guide for the evaluation of miter bends. The modeling of the bends is indicated in Figure 6-2. Stress intensification factors are presented in Table 6-17. These stress intensification factors were calculated using the vent system beam model in conjunction with results from the Bechtel analysis, which provided detailed modeling of the miters in question.

Maximum primary plus secondary stresses were ratioed to the nominal section stresses generated from the beam model thereby defining the stress intensification factors.

6.9.2 Controllin Load Combinations The three controlling load combinations are shown in Tables 6-.17, 6-18, and 6-19.

6.9.3 ASME Code Allowables The ASME Code allowable stresses are presented in Tables 6-17, 6-18, and 6-19.

6.9.4 Stress Results and Com arisons The main vent miter bend was evaluated for three load cases using Service Level C loads and Service Level B allowables.

As seen from Table=.6-17, these stresses are considerably

'below the allowables, showi'ng a maximum value of 3.9 ksi, compared with a 28.95 ksi allowable for the condensation oscillation event combination.

In the same manner, the vent header miter bend and the downcomer miter bend were evaluated for three cases, each involving CO, chugging, and pool swell (Tables 6-1 8 and 6-19). The maximum local membrane stresses for the Service PUAR. 6 6-15

BFN-PUAR Level C load,ing on the miter bends were found to be 18.6 ksi and 20.7 ksi, respectively. When compared with the Service Level B allowable of 28.95 ksi, these areas are qualified.

6.10 Torus Bellows The torus bellows are flexible expansion joints allowing movement of the main vent pipes through the torus wall while maintaining the required pressure boundary. The analysis performed on this structure was done in accordance with Standards of the Expansion Joint Manufacturer's Association, Inc,, (Reference h4). Fatigue life is the dominant concern.

6.10.1 Anal tical Procedure 6.10.1.1 Anal tical Model The flexibility of the bellows was the concern in R

accurately representing the bellows in the 45 and 180 beam models.'n Figure 6-2, local springs were inserted.

Output from the 45o and 180 models in the form of displacements was extracted from the various loading events.

The combination of these cases as .described in Section 6.10.2 was then used to calculate stresses in the bellows.

6.10.1.2 Static and D namic Loads II The loading "events to which the torus bellows are subjected are explained in Section 6.2.1.2.

6..10.2 Desi" n Loadin Conditions The controlling loading conditions were provided by Reference 21 for SBA, IBA, and DBA events.

6.10.3 ASME Code Allowables The ASME Code makes reference to bellows in Paragraph NE-3365. Standards of the Expansion Joint Manufacturer's Association, Inc., offers a more straightforward and acceptable approach for fatigue evaluation of bellows.

6.10.'4 Results and Com arisons Results of the fati gue evaluation are shown in Table 6-1 2 of Section 6.5.4. No significant usage factor is observed.

Therefore, the fatigue failure of these components does not present a significant concern.

6-16 PUAR. 6

TABLE 8-8 CONTROLLINQ LORD COMBINRTIONS AND SERVICE LEVELS OF DOWNCOMER/VENT HERDER INTERSECTION EVENT COMBINATION SERVICE LEVEL 27 DBA + SSE EQ + S/RV + CO 27 DBA + SSE EQ + S/RV + CO 25 DBA + SSE EQ + S/RV + PS 18 DBA + OBE EQ + PS 15 SBA + SSE EQ + S/RV + CH 15 SBA + SSE EQ + S/RV + CH TABLE 8-iO MAXIMUM STRESS INTENSITIES ON DOWNCOMER/VENT HEADER INTERSECTION EVENT STRESS CATEGORY STRESS ALLOHABLE 27 PL+ Q 57.60 KSI 57.9 KSI 27 14.6 37.6 25 44.4 45.2 18 PL 31.4 37.6 15 PL+ Q 53.3 57.9 15 21.6 37.6

TRBLF 6-i'1 FATIGUE USAGE FACTORS FOR. CONTAINMENT VENT SYSTEM ALLOHABLE COMPONENT FATIGUE DBA SBA/IBA USAGE USAGE USAGE DOHNCOMER / VENT HEADER INTERSECTION 1.0 .559 .610 DOHNCOMER / TIEBAR INTERSECTION 1.0 . 107 .353 TORUS BELLOHS 1.0 .000 .000 INTERSECTION

TRBLE 8-12 CONTROLLINt'OAD COMBINATIONS AND SERVICE LEVELS OF DOHNCOMER/TIEBAR INTERSECTION EVENT COMBINATION SERVICE LEVEL 27 (CASE 1) 'BA + SSE EQ + S/RV + CO 27 (CASE 2t DBA + SSE EQ + S/RV + CO 27 DBA + SSE EQ + CO 25 DBA + SSE EQ + S/RV + PS 15 SBA + OBE EQ + S/RV + CH 15 SBA + SSE EQ + S/RV + CH TRBLE 8-13 MAXIMUM STRESS INTENSITIES ON DONNCOMER/TIEBAR INTERSECTION EVENT STRESS CATEGORY STRESS ALLOWABLE 27 (CASE 27 (CASE 2) 27

'LPL PL+ Q 21.7 KSI 30.8 30.9 28.95 KSI 34.74 57.9 25 28.4 28.95 15 PL+ Q 53.4 57.9 15 27.97 28.95

TRBLE 8-14 STRESS EVALUATION ON TIEBAR 27 PL 20.7 KSI 23 KSI 25 PL 8.7 23 15 PL 18.0 23

TABLE 6-1'5 CONTROLLING LOAD COMBINATIONS AND SERVICE LEVELS OF THE VENT COLUMN SUPPORTS EVENT COMBINATION SERVICE LEVEL 27- DBA + SSE EQ + S/RV + CO 25 DBA + SSE EQ + S/RV + PS 15 DBA +, SSE EQ + S/RV + CH TABLE 6-16 STRESS AND BUCKLING EVALUATION ON VENT COLUMN SUPPORTS STRESS BUCKLING EVENT CATEGORY STRESS AL'LONABLE FACTOR 27 7.1 KSI 16.6 KSI .43 25 10.4 16.6 .63

15. PL 7.6 16.6 .46

TRBLE 6-17 MAXIMUM STRESS INTENSITIES ON MAIN VENT MITER BEND STRESS SERVICE MICKEY. LEVEL 27 PL 3.9 KSI 28.95 KSI 25 PL 1.8 28.95 15 PL 2.4 28.95 TRBLE S-ie MAXIMUM STRESS INTENSITIES ON VENT HEADER MITER BEND STRESS SERVICE XSJQ CEIHkQRY. RISHI LEVEL 27 PL 18.0 KSI 28.95 KSI 25 PL 15.5 28.95 15 PL 18.7 28.95 TRBLE 8-iS MAXIMUM STRESS INTENSITIES ON DONNCOMER MITER BENDS STRESS SERVICE EVEIVT C8IEBQBY ~LEV L 27 PL 16.5 KSI 28.95 KSI

-25 13.8 28.95 15 PL 20.6 28.95

TRBLE 6-20 STRESS EVALUATION AT KEY LOCATIONS FOR ZERO h,P (LOAD COMBINATION P + N + T + PS ZERO b,P)

HID BAY iiST DOHNXNER 2M) ~ 3RD 0$ 44XHER PAIR IR PAIR A C D F STRESS CIRXKlGED ALLOHRRE RKKLIhG LOCATION INTENSITY STRESS TKSI) STRESS (KSI) INTE)PACTION MIDBAY BOTTOH 12+0 41.6 ~L + ~H < 1.0 ELE)%NT 13 "PL+ Pb 29.1 62.5 12.0 25.5 QA 3.1 16.9 0.7 HIDBAY TOP eeo 41.6 ELE)KNT 1 PL+ Pb 17.6 82~5 oL ae6 25.5 0.2 Qe 0.5 16+9 BOTTOH BETHEEN 9.0 41.8 1ST D/C PAIR ELB%M 1062 PL+ Pb 41 e2 62.5 oL 11.0 25.5 0.7 16.9 0.5 BOTTOH BETHEEN 15.5 41.6 TWO PAIRS (F WC +Pb 24.1 62e5 ELEHENT 1439 P(

oL 13.9 22.5 0.7 07 san Qo e~

ZM3 WC PAIR PL+ P 17.4 41.6 13+6 41.6 62.5 ELEMENT 2062 17e2 22.5 3ea 13.6 1.0 BOTTOH BETNEEN 5.3 41.6 3RD WC PAIR ELB%Nf 3062 ieoa 82.5 5.0 22+5 1.7 13e6 0.3

J TRBLE 7-1 DRYNELL LORD COMBINATIONS Z

CU DU I- UJ S C>-

~ I-0 Ul I- N P) Z UJZ UJ QM C3 UJ 2cC 0 )Q UJ UJ X

CI

')K W

V)

E 0

K CO EUJE

~ CONC Mm UJ DI-(O' J0 UJ M

cC UJ UJ K

UJ K

00 cCMV) m- UJ m 0 lL UJ LOADS 0 0 I- Z 0 0 V)

CASE 1 X X' X CASE 2 X X CASE 3 X X CASE 4 X X X X D

i. WORST CASE THERMAL EXPANSION

2. WORST 'CASE FIRST ACTUATION VS. SUBSEQUENT ACTUATION.

3 IBA S/RV SUBSEQUENT ACTUATIONrSTEAM IN DRYWELL

4. SEISMIC EVENTS INCLUDE ANCHOR MOVEMENTS.

5. POOL SWELL INCLUDES VENT RESPONSE AND DISPLACEMENT.

6. EVALUATION OF PRELIMINARY ANALYSIS INDICATED SBA/IBA FIRST AND SECOND ACTUATIONS WITH AIR IN THE DRYWELL TO BE LESS SEVERE THAN NOC BLOWDOWNS. WITH THE EXCEPTION OF SUBSEQUENT ACTUATION'TEAM IN THE DRYWELLi THE NOC BLOWDOWNS ENVELOPE SBA/IBA BLOWDOWNS. BECAUSE

., OF THE LOW PROBABILITY OF STEAM IN THE DRYWELL COINCIDENT WITH MAX REFLOODi ACTUATION UNDER THESE CONDITIONS IS ASSUMED TO BE SERVICE LEVEL D.

TRBLE 7-2 NOC SERVICE LEVELS B AND .C LOAD COMBINATIONS X

M O Lll I- M LOADS ~ I-CC CC UJ C9 Ld >D lV I- lKI- LLI LLI M

WACO V) cL I- X 0Vi McCl-C3 ncC m One X X LLI K OZ> V nLLJ LLJ !L Ld n X NLLI OZO M LLI o X Nld Co M CASE 1 x x CASE 2 x x B CASE 3 x x X C CASE 4 x x X C

i. S/RV ACTUATION EVENTS INCLUDE TORUS RESPONSEi FLUID DRAG ON SUBMERGED STRUCTURES'LOHDOHN FORCE IN PIPE AND QUENCHER HATER CLEARING THRUST

CONDENSATE STORAQE TANK TCV HISV TURBINE FEED-FUEL WATER TBV decay LPCS HAIN HPCI CONDENSER LPCI S/RV RHR SHUTDOWN HPCI COOLINQ LPCI HGDE CRD DRYWELL DOXNCOHER SYSTEH I

WETWELL AIR SPACE SERVICE SUPPRESSION POOL WATER RHR POOL COOLINQ NMK FIGURE 10-1 COUPLED REACTOR AND SUPPRESSION POOL MODEL

I g I 8 l0

//

6 SORY BULK POOL VELOCITY RHR DISCHARGE RHR DISCHARGE T-QUENCHER l4 l5 I

I6 l

I FIGURE i0-2 PLAN VIEW OF BROWNS FERRY SUPPRESSION POOL WITH T-QUENCHERS AND RHR DISCHARGE LOCATIONS USED IN THE LOCAL POOL TEMPERATURE MODEL

BFN-PUAR 11.0

SUMMARY

AND CONCLUSIONS 11.1 General The BFN Torus Integrity LTP has been underway since 1977.

The program objective was to upgrade the containment systems of each BFN unit for suppression pool hydrodynamic loads which were not explicitly included in the original design specification.

Mark I Owners Group and NRC activities resulted in generic load definitions and corresponding structural acceptance cri.teria to be applied for each domestic Mark I plant. NRC's generic safety evaluation report for the Mark I containment system long-term program, NUREG 0661 (Reference 1), was published in July 19SO.

The current orders for completion of BFN LTP modifications were issued on January 19, 1982. Those orders require installation of all modifications necessary for compliance with NUREG 0661 before the start of Cycle 6 operations of each BFN unit.

11.2 Browns Ferr Desi n Criteria The BFN LTP general design criteria (Section 4.0) defined the basis for structural analysis of BFN containment system components as well as structural design of required modifications. It also ensured compliance with the intent of NUREG 0661.

The detailed design criteria for analysis of torus attached piping systems (Appendix A) supplemented the general design criteria and defined specific requirements and procedures for analysis of torus attached piping systems.

11.3 Structural Anal ses and Desi n of Re uired Modifications Structural analysis and design of required modifications for each basic category of BFN containment system components were performed as described in Sections 5.0 through 9.0.

The analyses addressed containment systems as configured for the start of Cycle 6 operations of each unit, including plant modifications installed for NUREG 0661 compliance and for other reasons. Modifications related to suppression pool local and bulk temperature requirements in NUREG 0661 were designed as described in Section 10.0. All modification designs complied with the Browns Ferry LTP design criteria and NUREG 0661.

ll-l PUAR.ll

BFN-PUAR Analysis and design of associated modifications to the 10-inch S/RV discharge line vacuum breakers and the drywell/wetwell vacuum breakers have also been completed.

Permanent documentation of all analysis and design activities associated with the BFN LTP was accomplished, in compliance with Section 4.6.

Future modifications to BFN containment system components will be designed in accordance with the BFN LTP design criteria, when the modifications are w'ithin the region of influence of .torus hydrodynamic loads.

11.4 S/RV Confirmator Test An in-plant S/RV confirmatory test was successfully completed in BFN Unit 2 during April 1983 in accordance with Section 4.6. The test results were documented by Reference

41. Correlation of analysis and test results, including definition of selected load reduction factors, was accomplished as described in Appendix C.

11.5 Installation of Modifications and Final Conclusions At this time (December 1983), all LTP modifications and 10-inch S/RV vacuum breaker modifications have been installed in BFN Unit 1. Major LTP modifications have been installed in Units 2 and 3, and 10-inch S/RV vacuum breaker modifications have been installed in Unit 2. Unit 3 is in its cycle 5 refueling outage.

All BFN containment system modifications for compliance with NUREG 0661 will be completed before restart for Cycle 6 operations of each unit, in accordance with NRC's orders (Reference 12). Other modifications will be installed according to a NRC-approved integrated schedule.

BFN LTP total costs are currently estimated at $ 105,000,000 excluding interest payments and lost power revenues while installing modifications. The extent and scope of those modifications are sunmarized by Table ll-l and the construction photographs in Appendix G.

This PUAR provides an accurate and sufficient surrmary of LTP activities for all three BFN units.

11-2 PUAR. 11

TABLE R- 4 (CONTINUED) iSHEET 8 ANALYSIS CRITERIA FOR TORUS ATTACHED P IP INQ LOCA EFFECTS (1 r 2 r. 5)

PLANT CONDITION MOMENT CONSTITUENTS (L CE T F LOA SOU CES QfK (CONTINUED)

POSTPROCESSOR 8 PUAAG COMB. 16 0.0 POOL SHELL PRIMARY (PRESSURE + '

SUSTAINED + DBA ) HA = H (DH + PL)

+ ~t~(MA+ MBFW 2 4 SI, ESSENTIAL

" 4 NONESS.

(P d ) Z HBF = H [( + (APID 1.2 OR PSF) + FI SI, ACT.COMP.

NONESS.-SVC LEVEL D + PSDL + PSFB PRax 2.0 P NONESS.

ESS. SVC LEVEL B + DHJDL]

= 1.1 P ESS.

SECONDARY (PRESSURE + SUSTAINED HC =,H(Ti + PS2 + 7 + = SA + SI

+EXPANSION + DBA) + PQ2) -d (DD )

OR

= .ii2 r~c = SA Z

OR MC = M[Ti)

ANP Hp H[PS2 + PQ2 l EHp

~ 3Sc Z

1 TRBt E Pl 4 (CONTINUED) r SHEET 9 NOTES:

1. THESE EQUATIONS REPRESENT THE WORST CASES FROM PUAGG TABLE 5-2 AND MARK I CONTAINMENT PROGRAM LOAD DEFINITION REPORT NEDO 21888iSECTION 3i TABLE 3 ~ 0 3s FIGURES 3 ~ 0 is 2s 3s 4s AND 5 ~

I

2. ALL DYNAMIC ANCHOR POINT MOVEMENTS ARE INCLUDED IN EQUATIONS Si 10'ND 11. FATIGUE ANALYSIS REQUIREMENTS WILL BE SATISFIED BY DEMONSTRATION OF COMPLIANCE WITH ASME CODE SECTION I I I NC 3600'QUATIONS Ss 10> AND 11

3. THE PUAGG (REFERENCE 13) PERMITS THE PIPING STRESS ALLOWABLESr PIPING DAMPING VALUES'ND PIPING SUPPORT ALLOWABLES TO MEET THE REQUIREMENTS OF SERVICE LEVEL C.

THIS DOES NOT APPLY TO ACTIVE COMPONENTS.

4. THE PUAGG (REFERENCE 13) PERMITS THE PIPING STRESS ALLOWABLESa PIPING DAMPING VALUES'ND PIPING SUPPORT ALLOWABLES TO MEET THE REQUIREMENTS OF SERVICE LEVEL D.

THIS DOES NOT APPLY TO ACTIVE COMPONENTS.

5. A STRESS RANGE EVALUATION MUST BE PERFORMED FOR ALL THERMAL CYCLIC CONDITIONS AND ALL DYNAMIC DISPLACEMENT CYCLIC CONDITIONS THAT ARE QUALIFIED BY CODE EQUATIONS 10 OR 11.

I 8 ~

Page 1 of 3 BFN"REP List of Effec ve Pages Rev., 23 TENNESSEE VALLEY AUTNORITY r

Browns Ferry Nuclear Plant - Radiological Emergency la'n List of Effective Pa es f 'ages must be retained with th rown Ferry Nuclear Plant Radiological Emergency Plan.

Page Number Date art Page Number Date List of Effective Pages 1of3 Rev. 23 BFN- P (cont'd) 9 Rev. 6 2of3 Rev. 23 10' Rev. 4 3of3 Rev. 22 11 Rev. 4 able of 12 Rev. 4 Contents 1 Rev. 13 13 Rev. 4 2 "

Rev. 23 14 Rev. 4 3 Rev. 4 15 Rev. 4 4 Rev. 19 16 Rev. 4 5 Rev. 7 17 Rev. 7 6 Rev. 7 18 Rev. 23

.7 Rev. 4 19 Rev. 23 8 Rev. 19a Rev. 23 9 Rev. 11 20 Rev. 7 10 Rev. 19 Rev. 13 ll R . 7 22 Rev. 23 12 ev. 7 22a Rev. 23 13 Rev. 19 23 Rev. 7 List 24 Rev. 7 Appen Mes Rev. 13 25 Rev. 4

/ 26 Rev. 4 I'ist of 27 Rev. 4 Figures Rev. 13 28 Rev. 4 Rev. 21 29 Rev. 4 st of 30 Rev. 4 T,a s Rev. 13 31 Rev. 4 32 Rev. 4 BFN-REP 1 Rev. 4 33 Rev. 4 2 Rev. 4 34 Rev. 4 3 Rev. 35 " Rev. 13 4 Rev. 4 36 Rev. 13 5 Rev. 4 37 Rev. 13 6 Rev. 4 38 Rev. 13 7 Rev. 4 39 Rev. 13 8 Rev. 4 40 Rev. 1.3 41 Rev. 17 42 Rev. 17 43 Rev. 4 44 Rev. 4 45 Rev. 4 REP-BFN-EPL

I

'I V

k

~, C Page 3 of 3 BFN-REP List of Effective Pages Rev. 22 List of Effective Pa es (con't)

Part Page Number Date Part Page Number Date Appendix B 1 Rev. ll Appendix E 17 Rev. 19 2 Rev. ll 18 Rev. 19 3 Rev. ll 19 Rev. 19 4 Rev. ll 20 Rev. 19 5 Rev. ll 21 Rev.

Rev.

19 6 Rev. 11 ,22 19 7 Rev. 22 23 Rev. 19 24 Rev. 19 Appendix C 1 Rev. 4 25 Rev. 19 2 Rev. 4 26 Rev. 19 3 Rev. 4 27 Rev. 19 4 Rev. 4 28 Rev. 19 5 Rev. 4 29 Rev., 19 6 Rev. 4 30 . Rev. 19 Appendix D 1 Rev.

2 Rev.

3 Rev. Appendix F 02/23/81 4 Rev.

5 Rev.

6 Rev.

7 Rev.

8 Rev.

9 Rev.

10 Rev.

11 Rev.

12 Rev.

13 Rev.

14 Rev.

Appendix E 1 Rev. 19 2 Rev. 19 3 Rev. 19 4 Rev. 19 5 Rev. 19 Rev. 19 Rev. 19 Rev. 19 9 Rev. 19 10 Rev. 19 11 Rev. 19 12 Rev. 19 13 Rev. 19 14 Rev. 19 15 Rev. 19 16 Rev. 19 REP-BFN-EPL

l 0

Pege 18 HFN-REP Agreement I.etters 3- / 8'" Appendix Rev. 19 E

date Robe'rt L. Craig, M.D.

.'edical Director

'Tennessee Valley Authority 320 Edney Building Chattanooga, Tennessee 37401

Dear Dr. Craig:

RADIOLOGICAL EMERGENCY PLA FOR / /8 <'- 'cm 't'> < NUCLEAR PLANT ~

This is to certify tha5-~~r~C<i'r . r>".:"'* '~e. e will respond (name of ambulance.service}

and provide ambulance transportation for ~>,~i<r~ ~'7->>y i'>

Nuclear Plant at the request of TVA. Our se'rvice's available 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months a day for transportation of patients, including those who may have been exposed to or may be contaminated with radioactive material. We have number fully equipped ambulances which are staffed by personnel trained and certified as Emergency Medical JA'I ~"" C6.(. C'., i Technicians.

r7;;

We

,,are located at J 6'far.'..

which is approximately ~7 'inutes response time from the plant. We may be reached by emergency telephone number cW.')

l

-5.~) ') '5,) /

~,

Sincerely, (name and title) h '. 4A Z iver, name of a u ance service "i: i '8: i7'8

~ ~ ~ I

~/~

Revi8ien

BFN-IPD List of Effective Pages Page 1 of 9 12/20/84 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT IMPLEMENTING PROCEDURES DOCUMENT LIST OF EFFECTIVE PAGES This List of E'ffective Pages must be retained with the Browns Ferry Nuclear Plant Implementing Procedures Documents.

Procedure Page Part Number Subdivision Number Date/Rev. No.

4 BFN List of Effective E Pages lof9 12/20/84 2of 9 10/29/84 3of9 11/28/84 4of9 12/20/84 5of9 12/20/84 6of9 10/29/84 7of 10/02/84 10/29/84 9'of9 9of9 05/14/84

'Table of Contents ,1 of 1 05/04/84 IP-1 Coversheet 09/05/84 Preface lof 1 10/12/83 1 of 11 03/14/84 2 of ll 03/14/84 3of ll 10/19/82 4of ll 04/06/84 5 of ll 10/19/82" 6 of ll 04/06/84 7 of ll 10/19/82 8 of ll 10/19/82 9 of ll 05/30/84 10 of ll 05/30/84 ll of ll 09/05/84 IP-2 Coversheet 09/21/84 Revision Log 09/21/84 lof3 09/21/84 2of3 09/21/84 3of3 02/04/83 IP-3. Coversheet 09/21/84 Revision Log 09/21/84 lof3 09/21/84 2of3 09/21/84 3of3 04/17/84

P BFN-IPD List of Effective Pages Page 2 of 9 10/29/84 LIST OF EFFECTIVE PAGES (Con't)

Procedure Page Part Number Subdivision Number Date/Rev. No.

BFN IP-3 Table 1 lof 1 10/12/83 (Cont'd) Table 2 iof 1 10/12/83 IP-4 Coversheet . io/i9/84 Revision Iog 10/19/84 lof3 09/21/84 2of 10/19/84 3 03/20/84 3',of Table 1 lof 1 10/12/83 Table 2 lof 1 10/12/83 IP-5 Coversheet 10/23/84 Revision Log 10/23/84 lof3 09/21/84 2of 3 10/23/84 3of3 10/23/84 Table 1 lof1 10/12/83 Table 2 lof 1 10/12/83 Figure 1 l.of 1 1O/23/84 IP-6 Coversheet 10/19/84 Revision Log 10/19/84 lof 1 03/08/84 Attachment lof2 09/21/84 2of2 10/19/84 Attachment 2"- 1 of 2 09/21/84 2of2 10/19/84 Attachment 3-" lof2 10/19/84 2of2 09/21/84 IP-7 Coversheet 09/21/84 Revision Log 09/21/84 lof 1 12/21/81 Attachment 1 lof2 02/15/84 2of2 04/17/84 IP-8 Coversheet 04/17/84 lof 4 04/17/84 2of4 O3/14/84 3of4 O3/i4/84 4of4 01/12/84 Attachment 1 (de'leted) 1 of 1 03/i4/84

-Filed in plant site manuals only.

0 BFN-IPD List of Effective Pages Page 4 of 9 12/20/84 LIST OF:EFFECTIVE'PAGES (Con't)

Procedure Page Part Number Subdivision Number Date/Rev. No.

BFN IP-14 Coversheet 09/21/84 Revision Log 09/21/84 lof5 10/12/83 2of5 05/30/84 3of5 05/30/84 4of5 01/19/84 5 of 5 09/21/84 Attachment 1 1 of.1 01/19/84 Attachment 2 lof1 01/19/84 Attachment 3 lof 1 'Rev. 0 Attachment 4 lof 1 Rev. 0 Attachment 5 1 of 1 Rev. 0 IP-15 Coversheet 06/15/82 lof 4 Rev. 0 2of4 Rev. 0 3of4 Rev. 0 4of4 03/30/82 IP-16 Coversheet 06/15/82 lof2 04/22/82 2of 2 Rev. 0 IP-17 Coversheet 12/ll/84 Revision Log "12/11/84 1 of 18 12/11/84 2of 18 12/11/84 3of 18 12/11/84 4 of 18 12/ll/84 5 of 18 12/11/84 6 of 18 12/11/&4

. 7 of 18= 12/11/84 8 of 18 12/11/84 9 of 18 12/11/84 10 of 18 12/11/84 ll of 18 12/ll/84 12 of 18 12/11/84 13 of 18 12/11/84 14 of 18 12/11/84 15 of 18 12/11/84 16 of 18 12/11/84 17 of 18 12/11/84 18 of '18 12/11/84

f

~ 'I Tennessee Ualley Authority <Page 1 of 2 Browns Ferry Nuclear Plan= Form BF-5 BF 1.2, 2.1, 6 2.3 STANDARD PRACTiCE/PEM1ANEtNT INSTRUCTION CHANGE INFORMATION AVG P. 8 tg8y Standard Practice/

Instrudtion Number ~C M . Unit /RH Pages Affected I P Title Ao~ c< rg o (ti: ..'.d.s,r =)v.

.STANDARD PRACTICE C)iANGE Does this standard practice refer'ence <<echnical specifications or Regulatory Guide 1.33? If yes, PORC review is required prior 'to issuance. Yes No Is this standard practice listed on Attachment 3 of Standard Practice BF 1.2?

C If yes; PORC review is required 'p'ri'or 'to issuance. Yes No Was.t11is'ha'nge made to meet an NRC "co'mmitment? Yes No (If yes, refer to BF-2.3 for prbper identification of the change.)

Does this revision implement a source document? If yes, attach form. BF-4.

Due date of form BF-4 is Yes No PERMANENT ..'sSTRUCTION CHANGE Is this change in response to an LER,s IE bulletin, NRC inspection report, Management/Supervisor inspection, OQAB audit, etc?~ If yes, specify document under reas;n for revi'sion. Yes No Change New in procedural detail of FSAR or'ther licens'ing document'? Yes instruction?, Yes No ~ Intent change to instruction? Yes (If yes to a'y of these questions, a'SQD is "req'uired.)

No No ~

Is 'this a workplan-initiated. change? Yes (Workplan No. ) No~

Was this change made to meet an NRC co'msmitment? . Yes No (If Yes~. refer to'" BF-2.3 for eroperidentification of .the change.)

Fire Protection System involved?

Yes No /

Fire Protectio'n Engineer Date If yes, 'Fire Protection Engineer signaturoeis required.

Yes 'o ~W Security System involved?

Public Safety Supervisor Date If yes, Public Safety Supeivisor signature is required.

opc-Submitted by / / 9/g+J + /

Date Phoae Number Reviewed by / gJc( yC (See BF-2.14 for Standard Pracii.ces) Responsi le Section Supv.. Date Qual'ity Assurance progr'am requ'irem'ents have been properly included.

8'-

(For standard practices "only.) Quality Engine'ering Supv. Date The requirements herein are consisten't with safe, efficient plant op'eration.

ORC Chairman Date Admin. Svcs: Uerification of Document Accuracy Total Number of Pages in Procedure:

~6 Pl'ant Manager Disk Update

Job No. 6 r

- 0 I~m Date Initials Retention Period: Lifetime Responsibility.: "

Document Control Supervisor

>Revision s

<<Page 2 ot'? 3 Tennessee Valley Authority Form BF-5 Browns Ferry Nuclear Plant BF-1.2, 2.1~, & 2.3 August 28> 1984 STANDARD PRACTICE/PERMANENT INSTRUCTION CHANGE INFORMATION (cont'd)

IP-2 S ON 07/06/83 09/30/83 10/12/83 01/19/84 1 g2 04/17/84 112 09/21/84 1!2 Telephone number change due to new telephone system actiyation.

<<Addendum

Page 1 of 3 BFN - 'IPD BFNE IP-2 SEP 2 1 p8y CAUSE:

NOTIFICATION OF UNUSUAL EVENT 1 0 JJJP~S~

1.1 Provide for timely notification of appropriate individuals and organizations of a NOTIFICATION OF UNUSUAL EVENT.

1.2 Provide for periodic reanalysis to determine whether the NOTIFICATION OF UNUSUAL EVENT should be cancelled, continued, or upgraded to a more serious classification.

Date . 'Date INITIATED' CANCELLED uueme 2' Shift Engineer notify Operations Duty Specialist 7-200 or 8-0200} within 5 minutes of declaration of NOTIFICATION "OF UNUSUAL EVENT.

Give, the following:

a. .Your name.

b. 'Browns Ferry Nuclear Plant

c. NOTIFICATION OF UNUSUAL EVENT

d. Time incident declared.

'e. Brief 4pscri'ption of incident.

Plant condition (whether stable or deteriorating..

,g.:Reactor,(ddid/died not') shut down at (time).

>h. Unusual release of radioactivity (yes, no, or not known).

If radiation release: (a) .Ground Level, (b} Elevated

,<<Airbor ne,,(c) Mat'ei borne, '(d) Other.

Release oT XP-3.

rate if .unusual Release:rate releas'e from Tables uCA/seo.

1 and 2

k. Di'rection wind is coming from (degrees) and

'speed (milesltour). (Dse 91m Aero, Af ava1t able. )

1. No protective action recommended.

m. Any emergency actions underway onsite.

n., Any offsite support that has been requested.

<<Revision

Page 2 of:.

BFN -. IPD INITIATED CANCELLED BFN, IP-2 S~P2 I 2.2 Oper ations Duty Specialist wQ.1 return call to v authentici ty.

2.3 Shift Engineer will notify the following of the event:

a. Other Shift Engineer (when assigned);

b. STA (Code Call 544)

c. Operations Section Supervisor R. HunkapQ.ler 2214/$ 205 355-5667 Oper'ations Supervisor Tommy Jordan Muscle Shoals 2205/2214 383-5868 Operations Supervisor A. Burnette 2430/2429 766-1929

d. Plant Manager G; T. Jones Decatur 2212/2221 350-7444 Plant Superintendent J. E. Swindell Decatur 2221/221 2 355-'7277 Plant Superintendent J. R. Pittman 2221/2212 355-0230

e. Public Information Officer Mike Harris Athens 2413 (205)233-1125 2.4 I Shift Engineer will notify the NRC of NOTIFICATION OF I UNUSUAL EVENT by red phone. Give a brief description, NRC/C l Maintain an open line upon request by NRC.

I

~ Revision

Page 2 of 3 BFN - IPD INITIATED CANCELLED n e n e %Pa B)os~

Operations Duty Specialist will return call to verify authenticity.

2.3 Shift Engineer will notify the following of the event:

a. Other Shift Engineer. (When assigned)

b. STA (Code Call 544)

.I C~ Operations Section Supervisor R. Hunkapiller 214/205 355-5667 Operations Supervisor Tommy Jordan Muscle Shoals 205/214 383-5868 Operations Supervisor A-. Burnette 430/429 766-1929

d. Plant Manager G. T. Jones Decatur 212/221 350-7444 Plant Superintendent J. E. Swindell Decatur 221/212 355-7277 Plant Superintendent J. R. Pittman 221/212 355-0230 Frank Cason Decatur 413 355-3520 (Decatur Inn)

+ 2.4 Shift Engineer will notify the NRC of NOTIFICATION OF UNUSUAL EVENT by red phone. Give a brief description.

NRC/C Maintain an open line upon request by NRC.

~ Revision

J t (

r'

Page 3 of 3 BFN-IPD FE 04 1983 2.5 At least every two hours, e the Shift Engineer will reevaluate the event using IP-1. The Shift Engineer on the unaffected unit(s) will (if assigned) handle additional communications.

II

+ a. If the situation no longer exist, inform the personnel notified in step 2.1 thru 2.4.

b. If the condition warrants upgrading to a higher classification, initiate the appropriate procedure.

+Revisio

Tennessee Valley Authority +Page 1 of 2 Browns Ferry Nuclear Plant Form BF-5 BF 1.2P 2.1P Sr 2.3 STANDARD PRACT ICE/PERt1ANENT INSTRUCTION CHANGE INFORMATION AUG 2 8 )984 Standard Practice/ Pages / -P Unit > ~ ~ Affected Title STANDARD PRACTICE CRANGE Does this standard practice reference technical specifications or Regulatory Guide 1.33? If yes, PORC review is required prior to issuance. Ycs No Is this standard practice listed on Attachment 3 of Standard Practice BF 1.2?

If yes, PORC review is required prior to issuance. Yes No Was this change made to meet an NRC commitment? Yes No (If yes, refer to BF-2.3 for proper identification of the change.)

Does this revision implement a source document? If yes, attach form BF-4.

Due data of form BF-4 is Ycs No PER?fANENT .NSTRUCTION CEQfGE Is this change in response to an LER., IE bulletin, NRC inspection report, Management/Supervisor inspection, OQAB audit, ctc'? Xf yes, specify document under rcas:;.. for revision. Yes No Change in procedural detail of FSAR or other licensing document? Yes New instruction? Yes No ~X Intent change to instruction?

(If yes to any of these questio'ns, a USQD is required.)

Yes 'o No Is this a workplan-initiated change? Yes (Workplan No. ) No Was. this change made to meet an NRC commitment? Yes No (If yes refer to BF-2.3 for proper identification of thc change.)

Fire Protection System involved?

Yee No /

Fire Protection Engineer Date If yes, 'Fire .Protection Engineer signature~ is required.

Security System invojvcd?

/

Public Safety Superviscr Date If yes, Public Safety Supervisor signature is required.

/~mZ~rg~ /

Submitted by cor'hone Dat,e humber Rcvic'wed by -- IA~~~J~

(S<< BF-2 '4 for Standard Pract.iccs) Responsibl Section Supv. Date Quality Assurance program requirements have been properly included. ~ ~

e (For standard practices only.) Quality Engineering Supv Date Thc requirements herein arc consistent with safe, efficient plan't operation. ~

Admtn. Svcs. Verification of Document Accurac 6 PORC P

Lhaxrman Plant "Manager Disk Update g d

/~a-

/~2i Date t/P' C5'ate

.Tor.ci Numtcr of potce in Procedure: Job No. 6 Initials Retention Period: Lifet.ime Responsibility: Document Control Supervisor

Revision

I ~ ~

<<Page 2 of 2 L Tennessee Yalley Authority Form BF-5 Br owns Ferry Nuclear Plant BF<<1.2g 2.1g 5 2.3 August 28, 1984 STANDARD PRACTICE/PERMANENT INSTRUCTION CHANGE INFORMATION (cont'd) 1P-3 10/12/83 2;1 of Table 1;1 of Table 2

, 01/19/84 1,2 03/20/84 1,2; add 3 04/17/84 1 t2t3 09/21/84 .

102 Telephone number change due to new telephone system activation.

<<Addendum

m ~ Page 1 of 3 CAUSE: BFN - IPD BFN, IP-3 SEt'~ I ts84 ALERT 1.0 ~~e ie 1.1 Provide for timely notification of appropriate individual:

C and organizations of an ALERT.

Date Date 1.2 Provide for periodic reanalysis to determine whether the

" INITIATED CANCELLED ALERT should be cancelled, continued, or upgraded to a more serious classification.

2.0 2.1 Shift Engineer notify Operations Duty Specialist (7-200 or 8-0200) within 5 minutes of declaration of ALERT.

Give the following:

a. Your name.

b. Browns Ferry Nuclear Plant.

o. ALERT.

d. Time incident declared.

e. Brief description of incident..

f. Plant condition (whether stable or deteriorating).

g. Reactor (didldid not) shut down at (time).

~%

h. Unusual release of radioactivity (yes, no, or not known) .

~

v If a radiation release:

a. Ground level <<,airborne.

b. Elevated airborne.

c. Mater borne.

d. Other.

Zf yes, oaloulate release r ate(s) in uci/seo i'rom Tables 1 and 2. Release rate uC1/seo.

ks Direotion wind is earning from (degrees) and speed (miles/hour). (Use Rlm info, if available).

1. No protective action recommended.

m. Any emergency actions underway onsite.

n. Any offsite support that has been requested.

<<Revision

I ~

Page 2 of BFN - IPD BFN, IP-3 INITIATED CANCELLED SEP3 l ma4

~Mhm. Ln~Xizm 202 Operations Duty Specialist will return call to verify authe nti ci ty.

2.3 Shift Engineer will evaluate conditions. If required, initiate area (by public address) or total plant (by siren) evacuation. Refer to IP-8.

2.4 Shift Engineer's clerk will:

a. Notify other Shift Engineer (when assigned) of ALERT.

b. Notify STA (Code Call 544) of the ALERT.

I

c. Notify Chem Lab Supervisor (PAX 2367/2368) of ALERT.

Direct them to activate IP-25.

d. Notify HP Shift Supervisor (PAX 2300) of ALERT. Direct them to activate IF=14.

e. Notify Public Safety Supervisor (PAX 2273) of ALERT.

Direct them to activate IP-11 (Control Rooms only) and IP-7 ~

f. Verify Power Stores manned (PAX 2217/2104). If,not manned, contact B. H. Weeks (757-3379) or Ruddie P (233-0039) and request manning "

I 2.5 Shift Engineer's clerk will:

a. Initiate IP-6.

2.6 r Shift Engineer will notify NRC of ALERT by red phone. Give l brief description. Maintain an open line upon reques. by

,NRC/C l NRC.

NOTE:

site.

NRC ~ send a response team to tne 2.7 Time permitting, the Shift Engineer will implement operation of the TSC (IP-20), to include activation of Dimension telephones and placing required'desks in hall in front of TSC.

~Revision 0

> Page g of 3 BFN - IPD APR 17 1/84 2.8 At least every two hours, r o e e uen condit on p~arr.i~n the Shift Engineer/Site Emergency Director will reevaluate the event using IP-1.

a. If the situation no longer exists or should be downgraded, inform all personnel previously notified.

b. If the condition warrants upgrading to a higher classification, initiate the appropriate procedure.

of the s e oundar d se for bu d n e e se 2.10 If necessary to deviate from license conditions (Technical Speoifications and/or plant instructions) to protect public health and safety, refer to Standard Practice BF 12.22.

+Revision

I~

I ~,

0

Tennessee Ualley Authority *Page l. of 2 Browns Ferry Nuclear Plant Form BF-5 BF 1 ~ 2s 2.ls Sc 2.3 STANDARD PRACTICE/PERMANENT INSTRUCTION CHANGE INFORMATION AUG 28 ~g8g Standard Practice/ Pages Instruction Number XP-4 Unit 0 Title SITE AREA EMERGENCY STANDARD PRACTICE CHANGE Does this standard practice reference technical specifications or Regulatory Guide 1.33? If yes, PORC review is required prior to issuance. Yes No Is this standard practice listed on Attachment 3 of Standard Practice BF 1.2'?

If yes, PORC review is required prior to issuance. Yes No Was this change made to meat an NRC commitment' Ycs No (If yes, refer to BF-2.3 for proper identification of the change.)

Does this revision implement a source document?

Due date of form BF-4 is If yes, attach form BF"4.

Yes No PERMANENT INSTRUCTION CHANGE Is this change in response to an LER, IE bulletin, NRC inspection report, Management/Supervisor inspection, OQAB audit, etc?

under reason for revision.

If yes, specify document Yes No X Change in procedural detail oE FSAR or other licensing document? Yes No X New instruction? Yes No K Intent change to instruction? Yes No X (If yes to any of these questions, a'SQD is required.)

Is this a workplan-initiated change? Yes (Workplan No. ) No~

Was this change made to meet an NRC commitment?

(If VVes g refer to BF-2.3 for Doropcr a D identification of thc chanpc.)

a R Ycs

~ )

No ~

Fire Protection System involved?

X /

Fire Protection Engineer Date If yes,'Fire Protection Eng'ineer signature is required.

Security System involved?

K /

Public Safety Supervisor Date If yes, Public Safety Supervisor signature is required.

R. T. Smi / 10-10-84/ 3697 Submitted by D Phone Number Reviewed by (Sce BF-2.14 for Standard Practices) Responsible Section Supv. 'te Quality Assurance program requirements

, hav'c been properly. included.

(For standard practices only.) Quality Engineering Supv. Date The requirements herein are consistent with safe, efficient plant operation. //date 0 PO C Chairman 6!m-Plant Manager Admin. Svcs. Vcrification of Document Accuracy 6 Disk Update 84l,01 g 4/te/6g,::.:

Date Total Number of Pages in Procedure: Job No. 6 Initials

. Retention Period: Lifetime Responsibility: Document Control Supervisor .'s.".

Revision.

<<Page 2 of. 2 T~nn~~aee Yalley Authority Form BF-5 B: vins Ferry NucXear Plant BF-1.2, 2.1, Ec 2.3 August 28, 1984 STANDARD PRACTICE/PERMANENT INSTRUCTION CHANGE INFORMATION (cont'd)

IP-4 10/12/83 2, 1 of Table 1; 1 of Table 2 01/19/84 '1,2~3 O3/2O/84 04/17/84.

09/21/84 1,2 Telephone number change due to new telephone system activation.

Due to reorganization OCT 19 1984

<<Addendum

CAUSE: Page 1 of 3 BFN >> IPD BFN, IP-0 SITE EMERGENCY EMERGENCY SEP 8 I 1984 1.0 Rumba 1.1 Provide for timely notification of appropriate indiv" duals and organizations of a SITE AREA EMERGENCY.

1.2 Provide for periodic reanalysis of the situation to determine whether the SITE AREA EMERGENCY should be Date cancelled, continued, or upgraded to a more serious cl assifi cation.

INITIATED CANCELLED

~~m. LaQ~m, 2.0 2.1 Shift Engineer notify Operations Duty Specialist or 8-0200) within 5 minutes of declaration of (7-'00 SITE AREA EMERGENCY.

Give the following:

a. Your name,

b. Browns Ferry Nuclear Plant.

c. SITE AREA EMERGENCY.

0 d.

e.

Time incident declared.

Brief description of incident.

f. Plant condition (whether stable or deteriorating).

g. Reactor (did/did not) shut down at (time).

h. Unusual release of radioactivity (yes, no, or no known).'f a radiation release:

a. Ground level - airborne.

b. Elevated airborne.

c. Waterborne.

d. Other.

If yes, calculate release rate(s) in uCi/se<

from Tables 1 and 2. Release rate uCi/sec.

<<Revision

~IrgfPUIf vmlegmmIPUÃgggregg~M~w~e~~~M55KKL, e e ~4M ae Pbgd 2 Of 3 QFN ~ IPD"

'BFN 9 IP-4 INITIATED CANCELLED OCT 1 9 1984

~~ma Ln~Xma v

k. Direcbion mind is coming from (degrees) and speed (miles/hour). (Use 91m info, if available. )

1. No protective action recommended.

m. Any emergency actions underway onsite.

n. Any offsite support that has been requested.

2e2 Operations Duty Specialist wQ.1 return call to verify authenticity 2 ~3 Shift Engineer wQ.1 evaluate conditions. If required, initiate area (by public address) or total plant (by siren) evacuation. Refer to 'IP-8.

NOTE: Precautionary site evacuation should be considered.

2.4 Shift Engineer's cler k will:

a. Notify other Shift Engineer (when assigned) of SITE AREA EMERGENCY.

b. Notify STA (Code Call 544) of SITE AREA EMERGENCY.

c. Notify Chem Lab Supervisor (PAX 2367/2368 of SITE AREA EMERGENCY. Direct them to activate IP-25.

d. Notify HP Shift Supervisor (PAX 2300) of SITE AREA EMERGENCY. Direct them to activate IP-14.

e. Notify Public Safety Supervisor (PAX 2273) of SITE AREA EMERGENCY. Direct them to activiate IP-11 and IP-7.

f. Verify Power Stores manned (PAX 2217/2104). If not manned, contact B. H. Weeks (757-3379) or Ruddie Putman (233-0039) and request manning.

2,5 Shift Engineer's clerk will:

a. Initiate IP-6.

b. Notify Jim Coffey (Dim 3675, PAX 2476, (205) 350-1313, (205) 747-1833) or Herb Abercrombie (6907 Chatt.,(615) 886-6339) of site area emergency and to report to TSC as senior advisor.

2.6 I Shift Engineer will notify NRC of SITE AREA EMERGENCY by red phone. Give a brief description. Maintain a I open line upon request by NRC.

NRC/C I NOTE: NRC will probably send a response team to the site.

+Revision

Page 3 of 3 BFN - IPD BFN, IP-4 MAR 80 1984 INITIATED CANCELLED Init. Time Init. Time 2.7 Time permitting, the Shift Engineer will implement operation of the TSC (IP-20), to include actiVhticn of dimension telephones and placing required desks in front of TSC.

2.8 At least every two hours, 'e e et The'hift Engineer/Site Emergenc Director will reevaluate the event using IP-

a. If the situation no longer exists or should be downgraded, inform all personnel previously notified.

b. If the condition warrants upgrading to a higher classification, initiate the appropriate procedure 2.9 Refer to Table 1 for a quick estimate of gm~gm quick estimate of u d for Jaii14ing.

~ee s~s

2. 10 If necessary to deviate from license conditions (Technical Specifications and/or plant instructions) to protect public health and safety, refer to Standard Practice BF 12.22.

<<Revision

I ~

'E

hh ~ ~

~ ~

Tennessee Valley Authority *Page 1 of 2 Browns Ferry Nuclear Plant Form BF-5 BF 1.2, 2.1, 6 2.3 STANDARD PRACTICE/PERNQKNT INSTRUCTION CHANGE INFORHATION AUG 2 8 ]984 Standard Practice/ Pages Instruction Number Zp-5 Unit 0 Affected Nae page 2 Title GENERAL EHERGENCY STANDARD PRACTICE CHANGE Does this standard practice reference technical specifications or Regulatory Guide 1.33? If yes, PORC review is required prior to issuance. Yes No Is this standard practice listed on Attachment 3 of Standard Practice BF 1.2?

If yes, PORC review is required prior to issuance. Ycs No Was this change made to mcct an NRC commitmcnt? Yes No (If yes, refer to BF-2.3 for proper idc>>tification of thc change.)

Does this revision ihplcmcnt a source document? If yes, attach form BF-,4.

Duc date of form BF-4 is Ycs No PERHh%.'NT INSTRUCTION CHANGE Is this change in response to an LFR, IE bullet. in, NRC inspection rcport, Hanagcmcnt/Supervisor inspection, OQAB audit, ctc? If yes, specify document under reason for revision. Yes ~ No Change Ncw in procedural detail of I'SAR or other licensing document'? Yes instruction? Ycs No X Intent change to instruction? Yes (If ycs to any of these questions, a USQD is rcquircd.) ~ ~ No No Is this a workplan-initiated chang<<? Ycs (Workplan No. ) No X As this change made to meat an NRC commitmcnt? ~

~

Ycs No (If yes V i refer to BF-2.3 . for nro>>cr n > ..

identificationn of thc change.) R ~ )

Fire Protection System involved.

Yas No /~ah -rd Fire Protecti,on Engineer Date If yes, No ~

If yes, Fire Protection Fngineer signature is required.

'Security System involved' Yes Public Safety Supervisor signature is rc ired.

Public Safety Supervisor

/ g-g sf Date

/ 0 at,/ 3697 Submitted by t Phone Number Reviewed by (Sec BF-2.14 for Standard Practices) Responsible Section Supv. ate Quality Assurance program requirements have been properly included. </ io (For standard practices only.) Engineering Supv. Date <.A'uality The requirements herein are consi tent with safcp efficient plant operation. Y~4'

>airman

/rDat" k4 Plan anager Admin. Svcs. Verification of Document Accuz'acy 6 Disk Update 841010-06 Total Number of Pages in Procedure; Job No. 8 Initials Retention Period: Lifetime Responsibility: Document Control Supervisor , 'd<, ~

s h

Revision.

huh s

~ 4J4t m'h ~

<<Page 2 of 2 Tennessee Val3,ey Authority Form BF-5 Browne Ferry Nuclear Plant BF-1.2, 2.1, 4 2'.3 August 28, 1984 STANDARD PRACTICE/PERMANENT INSTRUCTION CHANGE INFORMATION (cont'd)

IP-5 10/12/83 2, 1 ofTable 1, 1 of Table 2 01/19/84 1 F2 03/12/ 84 1,2, 1 of figure 1 03/20/84 3 04/17/84 0 9/21/ 84 1,2 Telephone number change due to new telephone system activation.

()gy pg )984 Due to reorganization. Modify figure 1 to ensure compliance with NRC IN 83/28 and NRC IR 83/40 .

<<Addendum

CAUSE; Page of 1 3 BFN - IPD BFN) IP-5 SEP 8 l >g8y 1.0 1.1 Provide for timely notification of appropriate individuals and organizations of a GENERAL EMERGENCY.

1.2 Provide for periodic reanalysis of the situation to Date Date determine whether the GENERAL EMERGENCY should be cancelled or continued.

INITIATED CANCELLED LlLQ~N Jim'. 2.0 2.1 Shift Engineer notify Operations Duty Specialist (7-200 or 8-0200) within 5 minutes of declaration of GENERAL EMERGENCY.

Give the following

a. Your name.

b. Browns Ferry Nuclear Plant.

c. GENERAL EMERGENCY.

d. Time inoident declared.

e. Brief description of incident.

f. Plant condition (whether stable or deteriorating).

g. Reactor (did/did not) shut down at (time),

h, Unusual release of radioactivity (yes, no, or not known).

i. If a radiation release:

a. Ground level - airborne.

b. Elevated airborne.

c. Waterborne.

d. Other.

If yes, calculate release rate(s) in uCi/sec from fables 1 and 2. Releases rate uni/sec.

kk Direction wind is coming from 'degrees) and speed available.)

(milne per hour). (Dse 91 m info, if IRevision

Page 2 of 3 BFN IP-5 IPD'FN, OGT33 584 INITIATED CANCELLED Lait~m.

I l. "Recommend protective actions for the public from using I logic of Figur e 1.

Recommendation 1 NRC/C I I (Initial Recommendation Recocacendation 2 Rpt 83-48 t given. ) Recommendation 3 f Recommendation I I

t m. Any emergency actions underway onsite.

I I

I I n. Any offsite support that has been requested.

2.2 '

Operations Duty Specialist will return call to verify authenticity.

2 ~3 Shift Engineer will evaluate conditions. If required, initiate area (by public address) or total plant (by siren) evacuation. Refer to IP-8.

NOTE: Site evacuation is probable under these conditions.

2.4 Shift Engineer's clerk will:

a. Notify other Shift Engineer (when assigned) of GENERAL EMERGENCY.

b. Notify STA (Code Call 544) of GENERAL EMERGENCY.

Ce Notify Chem Lab Supervisor (PAX 2367/2368) of GENERAL EMERGENCY. Direct them to activate IP-25.

d~ Notify HP Shift Supervisor (PAX 2300) of GENERAL EYZRGENCY. Direct them to activate IP-14.

e>> Notify Public Safety Supervisor (PAX 2273) of GENERAL EMERGENCY. Direct them to activate IP-11 and IP-7.

Verify Power Stores manned (PAX 2217/2104). If not manned, contact B. H. Weeks (757-3379) or Ruddie Putman (233-0039) and request manning.

2.5 Shif t Engineer's clerk will:

a. Initiate IP-6.

I b, Notify Jim Coffey (Dim 3675, PAX 2476, (205) 350-13'l32 (205) 747-1833) or Herb Abercrombie (6907 Chatt.,

(615) 886-6339) of general emergency and to repor t to I TSC as senior advisor.

ORevision

<<Page3of 3 BFN XPD BFN ~ IP-5 IATED CANCELLED OCT38 ig Eadem 2.6 I Shift Engineer will notify NRC of GENERAL EMERGENCY by red NRC/C,'hone. Give a brief description. Haintain an open line Rpt 81-19 l upon request by NRC.

2 7. Time permitting, the Shift Engineer will implement operation of the TSC (XF-20), to include activation of Dimension telephones and placing required desks in hall in front of TSC.

2.8 At least every two hours, ggLrZRCL4. the Shift Engineer/Site Emergency Director will

., reevaluate the event using IP-1.

a. If the situation no longer exists or should be downgraded, inform all personnel previously notified.

2.9 of the for 2.10 If necessary to deviate from license conditions (Technical Specifications and/or plant instructions) to proteot public health and safety, refer to Standard Practice BF 12.22

<Revision for pagination

~ ~

L

RADIOLOGICAL EMERGENCY PLAN Transmittal Date: MAY 02 398 This log sheet must be retained as the last page of the Division of Nuclear Power Emergency Center Implementing Procedures Document.

Reason for revision: Organization, change f om HSRC Director to RAN (Ip-1);

" add critical drawin s and ties of the Resource Su ort Co dinator (IP-6).

Inserted by: Date Inserted:

es to be Remove New Pa es to be Inserted Pa Pa e Numb Revision Part Pa e Number Revision 1 3 16 EPL lof 3 17 2of 3 15 2of 3 16 Cov rsheet 7 IP-1 Coversheet 8 2 of 2 7 2 of 2 8 Coversheet 17 IP-2 Coversheet 18 At chment lof37 2 of 3 15 Attachment 1 2of

.1 of 3

3 18 18 Attachm t 2 lof 3 Attachment 2 1 of 3 18 IP-3 Coversheet 20 IP-3 Coversheet 21 2of3 18 2of 3 21 At achment 1 1 of 3 9 Attachment 1 lof 3 21 Attachment 2 lof 3 Attachment2 1 of'3 21 IP-5 Coversheet 21 IP-5 Coversgeet 22 3of 4 21 3of 4 22 Attachment 1 lof 3 10 Attachment 1 lof 3 22 Attachment 2 lof 3 10 Attachment 2 lof 3 22

RADIOLOGICAL EMERGENCY PLAN Revision Log Sheet (continued)

Manual: DNPEC-IPD Revision Date:

NY 02 1985 Pa es to be Removed New Pa es to be Inserted Part Part Page Number Revision IP-6 Coversheet 13 IP-6 Coversheet 14 Attachment 1 2 of 4 13 Attachment 1 2 << 4 14 Attachment 5 1 of 1 13 Attachment 5 1 of 1 14 N/A N/A Attachment 6 1 of 3 14 2of3 14 3of 3 14

, DNPEC-IPD List of Effective Pages Page 1 of 3 Rev. 17 TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER EMERGENCY CENTER IMPLEMENTING PROCEDURES DOCUMENT LIST OF EFFECTIVE PAGES This list of effective pages must be retained with the Division of Nuclear Power Emergency Center Implementing Procedures Document.

Procedure No. Subdivision Pa e No. Rev. No.

List of Effective Pages 1 of 3 17 2 of 3 16 3of3 3 .

Table of Contents 1 of 1 IP-1 Cover Sheet 8 1 of 2 1 2of2 8 Attachment 1 1 of,l 2 IP-2 Cover Sheet 18 lof3 15 2of3 18 3of3 17 Attachment 1 lof 3 18 2of3 12 3of3 12 Attachment 2 lof3 18 2 of 3 12 3of3 12 IP-3 Cover Sheet 2]

1 of 3 18

,2of 3 21 3of3 20 Attachment 1 lof3 21 2of3 15 3of3 15 Attachment 2 lof3 21 2of3 15 3 of,3 15 IPD-DNPEC"EPL

J S

0

VVi ed <OS.O Oo>

UNITED STATES GOVERNMENT Memorandum TENNESSEE VALLEY AUTHORITY TO Holders of the Division of Nuclear Power Emergency Center Implementing Procedures Document FROiH B. K. Marks, Supervisor, Radiological Emergency Preparedness Section, 1640 CST2-C DATE SUIIJECT:

III'I<l Division of Nuclear Power Emergency Center Implementing Procedures Document The attached revision is for inclusion in your copy of the subject manual.

>>ecti<rrr JO.1.5.3 <>I' lrc II<k<IioloIric<rl I'<r<<:r'rr< rr< y I'Irur<<I<< i re, <riual.

rrr holder:; no ccknovlcdnc ~rccciri oi'cvi:::ion::. I'lenin::it'.n ihe receipt, on the back of the distribution list and return to the Accords/Manual Control Unit, 1570 CST2-C, within 2 weeks of transmittal date. If you have any questions, call Chuck Mull, 7718-C.

If responsibility for this manual is transferred to another individual, please note this on your acknowledgme'nt receipt.

D. K. Marks=-

IIJS:CSM Attachments Buy U.S. Savings Bonds Regularly on the Payroll Savings Plan r

r

DNPEC-IPD List of Effective Pages Page 2 of 3 Rev. 16 List of Effective Pages (Continued)

Procedure No. Subdivision Pa e Rev. No.

No.'over IP-4 (deleted) Sheet 10 IP-5 Cover Sheet 22 lof 4 19 2of4 11 3of4 22 4of4 18 Attachment 1 lof3 22 20f 3 16 3of3 16 Attachment 2 1 of 3 22 2of3 16 3of3 16 IP-6 Cover Sheet 14 lof4 13 2of4 13 3of4 13 4of4 13 Attachment 1 lof4 13 2of4 14 3of44' 13 4of 13 Attachment 2 of 1 13

, Attachment 3 lof1 13 Attachment 4 1 of 1 13 Attachment 5 lof1 14 Attachment 6 lof3 14 2of3 14 3of3 14

, IPD-DNPEC-EPL

0 REP- IPD DNPEC IP-1

?

OPERATIONS DUTY SPECIALIST-TRANSPORTATION ACCIDENT INVOLVING SHIPMENT OF RADIOACTIVE WASTE FROM A TVA FACILITY Prepared By: W. E. Webb, r.

Approved By:

Date:

~t 0 2

0?

9/~y

?JLI9?tt 2/24/83 Al 1 2, 3 3

5 4PR 6 SEP 07 NOV" f 3

$ 8%over Sheet 1984covetsheet Q Coversheet, 2 2

2 6

MAR 04% Coversheet, 2

> APR 0 t? lgg Covetsheet, 2 8 4PR 2 $ )985 Coversheet, 2 se

j 'C 4

I

,c f

'L C,

\

0

DNPEC-IPD IP-1 Page 2 of 2

'Rev. 8 (Time/Initials) 6.2 Notify the following:

If the accident occurs in either Alabama or Tennessee, notify the appropriate State agency by direct line.

After hours, the Alabama phone will be answered by the Department of Public Safety. Ask the officer to contact the Radiological Health Staff by phone or pager (No. 215) and relay the accident information. Alternate telephone numbers for these agencies are listed in the TVA Radiological Emergency Notification Directory.

6.2 ~ 2 The NUC PR Emergency Duty Officer (See the CECC Notification Board.) ~

6.2.3 Notify the Shift Engineer of the plant where the

'hipment originated. Alternate numbers are listed

~

in the TVA Radiological Emergency Notification Directory.

Notify the CECC staff, Mechanical Branch representative.

(See the CECC Notification Board.)

6:2.5 Notify the Radwaste Technical Support representative. (See the CECC Notification Board.)

6.2.6 Notify the following (See the CECC Notification Board):

J. P. Darling

/ John Hutton

/ R. J. Kitts

/ B. K. Marks

/ E. K. Sliger 6.2.7 -Notify the Radiological Assessment Manager.

(See the CECC Notification Board.)

-"Revision I

IPD"DNPEC-IP-1

REP-IPD DNPEC - IP-2 OPERATIONS DUTY SPECIALIST PROCEDURE FOR NOTIFI'CATION OF UNUSUAL EVENT Prepared By; W. E. Webb, Jr.

Approved By:

Date:

4. ~id 0 9/~1 Al 1 3 2/~383, 2 1 3/10/82 2 MAR 1'I 1983

~OCT ~6 $ 82 Au. JURY 03 1983 r, 7 Rev. No. Date Revised Pa es JUL 0.71983tt 2 . 1 AVG1 0 td184 p

44 ILJ98~ Cover Sheet; At t. 2 p. 1-3 13 AUG 5'1 19A4'Att. 2-p.

. Coversheet, 2 & 3 Cover Sheet, 3'OV 2 6 W 8 MAR 29 t984 2, 3 14 Coversheet, 3 15 JAN P g 1985 Coversheet, 1, 2, & 3 NN 16 MAR 0 4% Coversheet, 3 i7 APR 02 1985 covezsheht 3 gs APR 2 1985 ARR. i i. Ahh. ~

0 DNPEC-IPD IP-2 Page 2 of 3 Rev. 18 Note: When making notifications of an emergency situation, provide only the information contained on the appropriate attachment.

Avoid any unnecessary explanation or elaboration of the information. Timeliness and accuracy is of the utmost impor-tance. If additional information/explanation is required by any party, provide the name and phone number of the DNP EDO and request they contact him or patch them through to him.

(Time/Initials)

/ 6.1.1 Upon receiving a call from the Site Emergency Director:

1. Turn on 'recording equipment.

2. Receive information from the Site Emergency Director.

3. Log information on the appropriate attachment.

4. Conduct verification call to originating plant.

/ 6.1.2 Notify the appropriate State agency by diiect line. For initial notification, provide only the, basic information 'he as indicated on the appropriate attachment. Request that the State make a verification callback, and at that time provide them the remainder of the attachment information.'fter hours, the Alabama phone will be. answered by the Department of Public Safety. Provide the officer with the basic information as indicated on'attachment 1. Request that he contact the Radiological Health Staff and have them call the ODS for additional information. Provide the remainder of the attachment 1 information when the call is returned.

Alternate telephone numbers for these agencies are listed in the TVA Radiological Emergency Notification Directory.

Note'otification to the State shall be made as soon as possible such that in .all cases it is made within five minutes from when call is first received from the plant. Under this emergency classification, the ODS is the "primary contact" with the State and is relieved of this function only if the CECC is activated.

6.1 ~ 3 Notify the CECC EDO. He will specify'hether to notify the MSEC Director. (See the CECC Notification Board.)

6.1 ~ 4 *Notify the Radiological Assessment Manager if specified by the EDO.

(See the CECC Notification Board.)

+Revision IPD-DNPEC"IP-2

0 DNPEC-IPD IP"2 Attachment 1 Page 1 of 3 Rev. 18 Attachment 1 BROWNS FERRY/BELLEFONTE NUCLEAR'LANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM Turn on recording equipment Date Time Initials Call verified Site Emergency Director NOTIFICATION TO STATE OF ALABAMA/TVAEMERGENCY CENTER, My name is. , TVA; Operations Duty Specialist.

The Browne Ferry Bellefonte Nuclear Plant, Unit declared a: Notification of Unusual Event Alert Site Area'mergency General Emergency

"at CST (time event declared) on (date) ~

(Initially, provide the above information. Request State Radiological

'Health Staff duty officer to call you back for detailed information.)

-'rief description of the incident is:

e

- e The plant condition is: Stable Deteriorating The reactor (did/did not) shut down at CST on (date)

Revision IPD-DNPEC-IP-2

e. I ere . w F wee, ~

DNPEC"IPD IP-2 Attachment 2 Page 1 of 3 Rev. 18 Attachment 2 SEQUOYAH/WATTS BAR NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM Turn on recording equipment Date I

Time Initials

'Call verified Site Emergency Director NOTIFICATION TO STATE OF TENNESSEE/TVA EMERGENCY CENTER My name is , TVA, Operations Duty Specialist.

Watts Bar Nuclear Plant, Unit

'lert The -

Sequoyah declared a: Notification of Unusual Event Site Area Emergency General Emergency CST (time event declared) on '(date).

(Initially, provide the above information. Request State duty officer to call you back for detailed information.)

Brief description of the incident is:

>Revision IPD-DNPEC-IP-2 l

dr REP-IPD DNPEC - IP-3 OPERATIONS DUTY SPECIALIST PROCEDURE FOR. AT,EPT'ND SITE AREA EMERGENCY

~, 5 't Prepared By: W. E. Webb, Jr.

Approved By:

Date:

d Rev. Ro. Date Revise~dPa es 0 9/~25 81 Al l 3 2/3/83 2 1 3/10/82 2 3 4 2~24 83 2 OCT ~gg All 5 MAR 17 1983 Rev. No. Date Revised Pa es JUN 03 1983 JUL OV 1983 3 e SEP 16 198~3 MAR 8 $ 84 Cover Sheet; Att. 1 p. I-3; Att. 2 p. 1-3 aRan nn

~~~ + > 584 Cover Sheet, 1O 1-3, delete Att. 3 11 APR 6 $ 84 Cover Sheet, 1

~12 lY 1 8 %4 Cddver Sheet Att. 1 . 2 13 ~ ~ 8" Cover Sheet 14 AUG 1 0'1984 Cover Sheet 15 AUG 5 1 N.I4 Coversheet'tt. 1- . 2 & 3'tt. 2- . 2 & 3 (OVER) .ado io,.

d

<<d ..= wovwv .a 'oo e.h ..:, a. o'

REP-IPD DNPEC IP-3 Rev. No. 'Date Revised Pa es 16 NOVg g~ Coversheet 3 IfOV'2 8 ~. . Coversheet, 3, 18 JAN.25 1985 Coversheet 2 & 3 19 MAR 04%6 Coversheet, 3 20 APR 02 )985 Coversheet, 3 21'PR 23 )985 Coversheet, 2, Att. 1 & Att. 2

DNPEC-IPD IP-3 Page 2 of 3 Rev. 21 Note: When making notifications of an emergency situation, provide only the information contained on the appropria'te attachment.

Avoid any unnecessary explanation, interpretation, or elabora-tion of the information. Timeliness and accuracy is of the utmost importance.

(Time/Initials) 6.1.1 Upon receiving a call from the Site Emergency Director:

Turn on recording equipment.

2. Receive information from the Site Emergency Director.

3. Iog information on the appropriate attachment.

4. Conduct verification call to originating plant.

6.1.2 Notify the appropriate State agency by direct line. For the initial notification, provide only the basic informa-tion as indicated on the appropriate attachment. Request that the State make a verification callback, and at that time provide them the remainder of the attachment information.'fter hours, the Alabama phone will be answered by the Department of Public Safety. Provide the officer with the basic information as indicated on attachment 1.

Request that he contact the Radiological Health Staff and have them call the ODS for additional information.

Provide the remainder of the attachment 1 information when the call is returned.

Alternate telephone numbers for these agencies are listed in the TVA Radiological Emergency Notification Directory.

Note: Notification to the State shall be made as soon as possible such that in all cases it is made within five minutes from when call is first received from the plant. Under this emergency classification, the ODS is the "primary contact" with the State. The ODS is relieved of this function by the CECC State

'ommunicator once the CECC is staffed.

6.1.3 Notify the CECC EDO. (See the CECC Notification Board.)

6.1.4 *Notify the Radiological Assessment Manager.

(See the CECC Notification Board.)

IPD-DNPEC-IP-3

DNPEC-IPD IP-3 Attachment 2

="Page 1 of 3

. Rev. 9 Attachment 2 SEQUOYAH/WATTS BAR NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM Turn on recording equipment Date Time Initials Call verified Site Emergency Director NOTIFICATION TO STATE OF TENNESSEE/TVA EMERGENCY CENTER My name is , TVA, Operations Duty Specialist.

The Sequoyah Watts Bar Nuclear Plant, Unit declared a: Notification of Unusual Event Alert Site Area Emergency General Emergency at CST (time of incident) on (date).

(Initially, provide the above information. Request State duty officer to call you back for detailed information.)

Brief description of the incident is:

"Revision

REP-, IPD DNPEC - IP-5 OPERATIONS DUTY SPECIALIST PROCEDURE FOR GENERAL EMERGENCY d

Prepared By: W. E. Web ~Jr.

Approved By:

Date: 9/25/81 d

9/25/81 All 3 2/3/83 2 3/10/82 2, 3 ddee

~CT 28296 MAR 1~ >9P)3 Rev. No. Date Revised Pa es JUN 03 1983 JUN 07 1903Att 8 JUL OV 1983 3

$ EP 1 61963 2-4 Attachment 3 1-3 10 MAR8~~ 2 &. ' -- 13 ll MAR ~9 ~984 Cover Sheet'-4 Att. 2 . 3 delete Att. 3 12 MiY i 4 ~+ Cover sheet 3 13 MAY 1 8 SL4 Cover Sheet'tt. 1 . 2 5)AY 2~ 1984 15 AQt2 f p Qg Cover Sheet; pg. 3 16 AUG 5 1 %4 Coversheet'tt. 1- . 2 & 3 Att. 2- . 2 & 3 (OVER)

REP-IPD DNPEC IP-5 Rev. No. Date Revised Pa es NOV f 3%4 17 Coversheet 3 NOV26~

18 Coversheet, 3, 4 19 JAN 2 5 1985 Coversheet 1 a 3 20 NR 0,4% Coversheet, 3 21 APR 02 )985 Coversheet, 3

DNPEC-1PD IP-5 Page 3 of 4 (Time/Initials) Rev. 21

/ 6.1.3 Notify the appropriate local Civil Defense Agencies. (See the TVA Radiological Emergency Notification Directory.)

Give the following message. "This is the TVA Operations Duty Specialist. We have a General Emergency existing at nuclear plant. Please activate your emergency organization. You will receive further instructions from the appropriate State agency."

Ensure the Attachment 1 or 2 recommended protective action given by the shift engineer is relayed to the contact.

Iocal Civil Defense agencies (Provide appropriate message and recommendation.)

BFNP

,. Pzmestone Co.

~

Morgan Co.

Lawrence Co.

Lauderdale Co.

SQNP Hamilton Co.

Bradley Co.

h

~ WBNP

/ Meigs Co.

i/ Rhea Co.

i,/ McMinn Co.

I/ 6.1.4 ~ Notify the CECC EDO. (See the CECC Notification Board.)

,/ 6.1.5 Notify the MSEC Director and have him activate the MSEC.

(Contact the Muscle Shoals operator and have he/she page.)

6.1.6 Notify the following and have them report to the center.

(See the CECC Notification Board.)

i/ CECC Director: J. P. Darling l/ John Hutton

'/ R. J. Kitts

/ B. K. Marks

/ >E. K. Sliger

/ Plant Assessment Manager

/ Management Services (Request he provide clerical support for the CECC)

Mechanical Branch Electrical and Instrument and Controls Branch Fuels Branch Plant Communicator Assessment'Team Leader (BWR - Browns Ferry, PWR-Sequoyah or Watts Bar)

Plant Radiological Communicato'r

>Revision IPD-DNPEC-IP"5

DNPEC-IPD IP-5 Attachment 1 Page 1 of 3 Rev. 10 Attachment 1 BROWNS FERRY/BELLEFONTE NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM Turn on recording equipment Date Time Initials Call verified Site Emergency Director NOTIFICATION TO STATE OF ALABAMA/TVAEMERGENCY CENTER My name is , TVA, Operations Duty Specialist.

The Browns Ferry Bellefonte Nuclear Plant, Unit declared a: Notification of Unusual Event Alert Site Area Emergency General Emergency e

at CST (time of incident) on (date).

(Initially, provide the above information. Request State Radiological Health Staff duty officer to call you back for detailed information.)

Brief description of the incident is:

The plant condition is: Stable Deteriorating t The reactor (did/did not) shut

"Revision down at CST on (date)

DNPEC-IPD IP-5 Attachment 2

':Page 1 of 3 Rev. yp Attachment 2 SE(UOYAH/WATTS BAR NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM Turn on recording equipment Date Time Initials Call verified Site Emergency Director NOTIFICATION TO STATE OF TENNESSEE/TVA EMERGENCY CENTER My name is , TVA, Operations Duty Specialist.

The Seqeoyah Watts Bar Nuclear Plant, Unit declared a: Notification of Unusual Event Alert Site Area Emergency, General Emergency at CST (time of incident) on (date).

(Initially, provide the above information. Request State duty officer to call you back for detailed information.)

Brief description of the incident is:

"Revision q

REP- IPD DNPEC - IP-6 CECC Plant Assessment Staff

.,Ptryj edure for Alert, Site Area Emergency; anh General Emergency Prepared By: W. E. Webb, Jr.

Approved By:

Date: /25/81 0 9/25/8y All MAR 8 4 1983 1 3/10/82 2, 3, 4 JUN 03 1983 All JUL 0719833 Att ]

AA1e2 2 4 CT Att. 5 p.

1'ev.

No. Date 2, 3, 4, 5; Cover sheet;

, NOVOO 1983 Att. 1>>- .1-6; 10 thAY 25 t884 ~ 2 Att. 3 p.l;

"'--e.

Att. 5 Deleted

>> ge 3AAI8<

, MAR i41984 ove 's ee ; pp. . . , 6 6; Att. 1, pp. 1-2, Att. 6 . 1 4 53 Att 23 pe 13 3 o

~

l l3 JAN 25 1985 All Att. 4 deleted.

~8P +~8 cover Sheet 13 2 9 M4~ ~ 4 ~ Cover Sheet; Att. 1, p.5; Att. 3, p. 1.

I DNPEC-IPD IP-6 Attachment 1 Pa.ge 2 of 4 Rev. 13 1.3.5 Maintains communications with other NUC FR technical staff representatives to keep them briefed on 'the emergency conditions and coordinates obtaining support from them as necessary.

Assists the Plant Assessment Coordinator in other communications needs as necessary.

1.4 Plant Assessment Team - Provides periodic evaluation of plant status information and protective action recommendations (when applicable) to the Plant Assessment Manager. Serves as a technical reference.

The assessment team shall be made up of the following: team leader, engineers, SROs, STAs, nuclear fuels engineers (core damage assessment), etc. (two mini'mum). Exact makeup of "the team wi:ll be determined by th'e team leader.

Duties 1.4.1 The assessment team leader will be activated automatically.

He is responsible for activating the remainder of the required team members.

1.4.2 The assessment team shall provide a periodic evaluation of the situation..and input back to the site and the CECC as appropriate via the Plant. Assessment Coordinator.

1.4.3 The assessment team shall evaluate all previous telecopied information and discuss the key plant events with the Plant Communicator, EDO, or Plant Assessment Manager to ensure they have received all the information necessary to begin an evaluation of plant conditions. Attachment 3 provides a methodology to be used as guidance in provi'ding a recommended protective action for the public to the CECC Director.

1.4.4 The assessment team will draw on their knowledge of FSAR, EOIs, owners'roup work, analytical basis for accident analyses, and communications between the TSC and plant communicator in evaluating the assessments provided by the site (att'achment 4) in terms of current and long-range plant conditions and in applying their evaluation to the protective action logic diagram (attachment 3).

Attachment 5 provides a list of reference material/

equipment which is maintained in the Plant Assessment Team area. A TSC communicator shall be available to answer all the assessment team's questions at all times.

The overall accident assessment serves to inform the Plant Assessment Manager of the general plant status.

It also enables the Plant Assessment Manager to communicate with the CECC Director in planning offsite General Revision

4 CECC-IPD Table of ntents Page 1 1 Rev.

CENTRAL EMERGENCY CONTROL CENTER PRO EDURES IP-1 CECC - Transpor 'on Accident Involvi a Ship ent of Radioactive Materials a TVA xlity IP-2 DNP Emergency Duty Officer/CECC Director/D EC Director-Notification of Unusual Event IP-3 CECC - Alert, Site Area Emergency, an General Emergency IP-4 CECC - Site Emergency--procedure de eted October 1982 (see IP-3)

IP-5 CECC - General Emergency--proced e deleted October 1982 (see IP-3)

IP-6 Division of Purchasing Radio gical Emergency Procedure IP-7 Division of Medical Servic s Radiological Emergency Procedure IP-8 Office of the General C nsel Radiological Emergency Procedure IP-9 :>(Deleted June 1983--I formation Office Procedures for Abnormal Occurrences at Nucle r Power Plants)

IP-10 Emergency Financi Support Procedures IP-ll CECC Training R uirements IP-12 CECC/DNPEC Se rity IP-13 Inclement W ather Procedure IP-14 TVA Board and General Manager Notification Procedure for All Classes f Radiological Emergencies

<~'~IP-15 Infor tion Office Procedures for Abnormal Events at Nuclear Plants

'"Revision

~'< "Addendum

CECC-IPD List of Effective Pages Page 1 of 4 Rev. 13 TENNESSEE VALLEY AUTHORITY CENTRAL EMERGENCY CONTROL CENTER IMPLEMENTING PROCEDURES DOCUMENT LIST OF EFFECTIVE PAGES This list of effective pages must be retained with the Central Emergency Control Center Implementing Procedures Document.

Procedure No. Subdivision Pa e No. Rev. No.

List of Effective Pages lof4 13 2of4 0 3of4 0 4of4 4 Table of Contents 1 of IP-1 Cover Sheet lof2 2of2 'P-2 Cover Sheet lof2'of2 IP-3 Cover Sheet 16 1 of 6 14 2of6 14 3 of'6 14 4of 6 14 5of6 14 6of6 14 Attachment 1 1 of 1 16 Attachment 2 1 of 1 14 Attachment 3 1 of 1 14 Attachment 4 1 of 5 14 2of5 14 3of5 14 4of5 14 5 of 5 14 Attachment 5 lof 1 14 Attachment 6 lof3 14 2of3 14 3of3 14 Attachment 7 lof3 14 2of 3 14 3of3 14 Attachment 8 1 of 2 14 2of2 14 Attachment 9 lof2 14 2of2 14 IPD-CECC-EPL

CECC-IPD List of Effective Pages Page 2 of 4 Rev. 0 List of Effective Pages (Continued)

Procedure No. Subdivision Pa e No. Rev. No.

IP-4 (Deleted) Cover Sheet IP-5 (Deleted) Cover Sheet IP-6 Cover Sheet 0 1 of 2 0 2of2 0 IP-7 Cover Sheet .0 lof4 0 2of4 0 3of4 0 4of 4 0 IP-8 Cover Sheet lof2 2of2 IP-9 (Deleted) Cover Sheet IP.-10 Cover Sheet 0 lof4 0 2of4 3of4 0 4of4 0 IP-11 Cover. Sheet-lof3 2of3 3of3 IP-12 Cover Sheet 1 lof2 1 2of2 0 Attachment 1 1 of 1 0

'Attachment 2 lof2 1 2of2 1 Attachment 3 lof 1 0 IP-13 Cover Sheet 1 lof3 1 2of3 0 3of3 1

CECC-IPD List of=Effective Pages Page 3 of 4 Rev. 0 List of Effective Pages (Continued)

Procedure No. Subdivision Pa e No. Rev. No.

IP-14 Cover Sheet 0 lof2 -

0 2of2 0 IP-15 Cover Sheet 1

'Index 1 of 1 1 I of I5 I 2of 15 1 3of 15 1 4of 15 1 5 of 15 1 6of 15 1 7of 15 1 8of 15 1 9of15 1 10 of 15 ll of 15 1

1 12 of 15 1 13 of 15 1 14 of 15 1 15 of 15 Appendix A 1 of 27 1 2 of 27 1 3 of'7 1 4 of 27 1 5 of 27 1 6 of 27 1 7 of 27 1 8of 27 1 9of 27 1 10 of 27 1 ll of 27 1 12 of 27 1 13 of 27 1 14 of 27 1 15 of 27 1 16 of 27 1 17 of 27 1 18 of 27 1 19 of 27 1 20 of 27 1 21 of 27 1 22 of 27 1 23 of 27 . 1 24'f 27 1

W CECC-IPD List of Effective Pages Page 4 of 4 Rev. 4 List of Effective Pages (Continued)

Procedure No. Subdivision Pa e No. Rev. No.

IP-15 (Cont'd) 25 of 27 1 26 of 27 1 27 of 27 1 Appendix B lof2 1 2of2 1:

Appendix C lof2 1 2of2 1 Appendix D 1 of 2 1 2of 2 1 Appendix E lof 1 1 Appendix F 1 of 5 1 2of 5. 1 3of5 1 4of5 1 5 of 5 1 IP-16 Cover Sheet 2 lof2 0 2of 2 2

REP- IPD CECC - IP-1 CECC-TRANSPORTATION ACCIDENT INVOLVING A SHIPMENT OF RADIOACTIVE WASTE FROM A TVA FACILITY Prepared By. W. E. Webb, Jr .

Approved By:

Date:

Rev. No.

All Cover Shee~;

9~1 84

~~>

~OCT 26 1982 A11 < ocr o<<sr<".",","","'he

~2P 6~$ Cover Sheet 1-2 last page of'his procedure is Number

CECC-IPD CECC - TRANSPORTATION IP-1 Page 1 of 2 ACCIDENT INVOLVING A SHIPMENT OF Rev. 4 RADIOACTIVE WASTE FROM' TVA FACILITY 1.0 PURPOSE

,This procedure is design'ed to direct the CECC Director in implementing TVA's response to a transportation accident involving a shipment of radioactive waste from a TVA facility.

It is also designed to direct the appropriate notifications outside TVA.

2 ..0 SCOPE This procedure covers anticipated actions of the CECC Director following the notification of a transportation accident involving a shipment of radioactive waste from a TVA facility.

3.0 REFERENCES

Radiological Emergency Plan.

4.'0 ABBREVIATIONS AND DEFINITIONS None.

5.0 RESPONSIBILITIES In the event of a transportation accident involving a shipment of TVA's radioactive waste, the Operations Duty Specialist (ODS) notifies the Emergency Duty -Officer (FDO) and the CFCC Director.

The,EDO is responsible for establishing initial operation of the CECC.

The CECC Director shall be responsible for notifying the Nuclear Regulatory Commission (NRC), Department of Transportation (DOT),

"""'-appr'opriate, State authorities, American Nuclea'r Insurers

'(liability insurance carrier), and De'partment of Energy (DOE)

(information only). The CECC Director, after consultation with the Muscle Shoals Emergency Center (MSEC) Director and the Reactor Engineering Branch representative and others, as necessary, decides whether conditions warrant the activation of the CECC staff and the dispatch of a TVA response team to the accident site.

"--Addendum

CECC-IPD IP-1 Page 2 of 2 Rev. 4 6.0 PROCEDURE RE UIREMENTS 6.1 Receive "Transportation Emergency Checklist" information from the ODS.

6.2 Notify the following:

(Time/Initials)

/ 6.2.1 Power Information Dut Officer. (See the.DNP Notification Board.)

6.2.2 NRC - Office of Inspection and Enforcement (Atlanta).

(See the TVA Radiological Emergency Notification Directory.)

6.2.3 DOT (See the TVA Radiological Emergency Notification Directory.)

6.2 ' State Authorities (State where accident has occurred.)

(See the TVA Radiological Emergency Notification Directory.)

6.2.5 DOE (for information onl ) (See the TVA Radiological

~ ~ ~

Emergency Notification Directory.)

N\ A 41 6.2.6 American Nuclear Insurers (liability insurance carrier)

(See the TVA Radiological Emergency Notification Directory, Insurance Support Directory.) Activate the Fire Protection Section Representative (DNP Notification Board) to provide follow-up reports/notifications to ANI during the event and at the conclusion of the event.

staff

/. 6.3 If't Determi.ne whether key the is necessary ODS.

CECC should be activated.

to activate the key staff, notify 6.4 Consult. with the NSEC Director and 'the Reactor Engineering Branch representative to determine whether a TVA response team should be dispatched to the accident site. If the response team is di'spatched, the HSEC Director is responsible for designating the response team members and arranging transportation.

- "Addendum

REP-IPD CECC - IP=2 DNP EMERGENCY DUTY OFFICER CECC DIRECTOR DNPEC DIRECTOR NOTIFICATION OF UNUSUAL EVENT Prepared By: W. E. Webb, Jr.

Approved By:

Date:

R .R. Rt ~R R .. 6 ~id 0 9~1 Al 1 3 2/14/83 2 3 4 2L18/82

~OCT 2 6 1262~

The last page of this procedure is Number

~ 0 CECC-IPD IP-2 Page 1 of 4 Rev. 2 NUC PR EHERGENCY DUTY OFFICER/CECC DIRECTOR/DNPEC DIRECTOR NOTIFICATION OF UNUSUAL EVENT 1.0 PURPOSE This procedure is designed to direct the Division of Nuclear Power (NUC PR) Emergency Duty Offic'er (EDO) in assuming the responsibilities for the positions of Central Emergency Contxol Center (CECC) Director and Division of Nuclear Power Emergency Center (DNPEC)

Director during an emergency in order to ensure consistent, accurate, and timely response in the event of an accident.

2.0 SCOPE This procedure covers anticipated requirements of the CECC Director and DNPEC Director during a Notification of Unusual Event. This procedure does not cover additional actions that may be required under more severe classifications.

3.0 REFERENCES

Radiological Emergency Plan.

4.0 ABBREVIAT10NS AND DEFINITIONS None.

5.0 RESPONSIBILITIES 5.1 Upon notification by the Operations Duty Specialist (ODS) that an emergency condition exists, the EDO is responsible for establishing initial operation of the CECC and the DNPEC. The EDO may elect to remain at home or at his office to make the required notifications if the incident has already terminated or will be terminated within the length of time it would take for him to arrive at the Emergency Control Center. The EDO, at any time, may request the CECC and/or the DNPEC Director to report to the Chatt-anooga emergency centers. However, if the plant is capable of adequately rectifying the condition which initiated the emergency, and plant safety systems are not in jeopardy, then the EDO may retain responsibility -"

for the position of CECC and DNPEC Directors. Should the situation degrade into an Alert or greater, the EDO notifies the CECC and DNPEC Directors to immediately<

report to the,CECC and DNPEC.

Revision

CECC-IPD IP-2 Page 2 of 4 Rev. 3 (Time/Initials) 6.0 PROCEDURE RE UIREMENTS Notify the ODS immediately upon arrival at the CECC/DNPEC.

/ 6.2 Notify the Manager of Power Information Duty Officer. (See the DNP Notification Board.)

/ 6.3 Contact the Site Emergency Director and obtain a current status report.

The principal means of contacting the plant emergency organizations is by use of the direct line in the DNPEC.

Alternatives to the direct line are listed in the TVA Radiological Emergency Notification Directory.

6.4 Notify the following for information only: (See the DNP Notification Board.)

/ 6.4.1 H, J. Green

/ 6.4.2 H. I. Abercrombie

/ 6.4.3 Hugh Parris

/ 6.4.4 J. A. Coffey

/ 6.5 >>Notify the NSRS Duty Engineer. (Contact the Knoxville TVA operator, identify yourself, and provide your telephone number. Request the operator to page the NSRS Duty Officer and to have him return your call.)

/ 6.6 ~ -Notify the Power Nuclear Safety Staff Duty Officer.

(See the DNP Notification Board).

/ >>6.7 Notify the appropriate Department of Energy (DOE)

Operations Office regarding the existence of an emergency condition at a TVA facility if their assistance will be required. (See the TVA Radiological Emergency Notification Directory.)

"6 8 Periodic U datin of TVA and Other Emer enc Or anizations/Personnel

>>'~'<Addendum

>>Revision "2-

CECC-IPD IP-2 Page 3 of 4 Rev. 3 Obtain an update on plant status from the Site Emergency Director or DNPEC Director approximately every hour (or as often as provided by the Site Emergency Director or DNPEC Director than once per hour).

if more frequent

"-6.8.2 Maintain periodic contact with other organizations that have been notified.

-"6.8.3 Provide the personnel contacted as permanent CECC Director and DNPEC Director with periodic updates of the accident.

Actions to be Taken Should the Accident De rade Into a More Serious Condition

~6.9.1 Notification

'"6.9.1.1 Notify the appropriate State agency as to the nature of the degraded condition.

6.9.1.2 Contact the CECC Director and inform him that he should report to the CECC. Review the new emergency situation with the CECC Director.

~'.6.9.1.3 Contact the DNPEC Director and inform him that he should report to the DNPEC. Review the new emergency situation with the DNPEC Director.

< 6. 9.-1. 4 Contact the MSEC Director and review the new emergency situation. If radioactive releases are occurring at the plant, request estimated dose rates.

>6.9.2 Assessment

"'6.9.2.1 Should the emergency degrade to an Alert, Site Area Emergency, or General Emergency, continue to obtain periodic updates of conditions from the Site Emergency or DNPEC Director.

'~6.9.2.2 Establish contact with the MSEC Director immediately after determining plant status, review the status with him, and include the data he can supply regarding offsite doses and environmental sampling to other organizations as appropriate.

"6.9.2 ' Request support from outside organizations as needed to cope with the emergency.

~'6,9.3 Relief of Duties'as CECC or DNPEC Director Revision

CECC-IPD XP-2 Page 4 of 4 Rev. 3

6.9.3.1 The EDO turns over the responsibilities of CECC and DNPEC Director upon the arrival of the permanent CECC and DNPEC Directors.

6.9.3.2 The EDO will brief the permanent CECC and DNPEC Directors on events which may have developed during their travel.

<6.10 Actions to be Taken When the Accident Terminates

'<6.10.1 Should the accident be of a nature such that terminated almost immediately after it it is is declared, inform all parties that the notification is for information purposes only and the incident has already been terminated.

<6.10.2 Upon notification of the termination of a Notification of Unusual Event, the EDO is responsible for notifying all parties and individuals informed of the emergency in sections 6.3 through 6.6 of this procedure.

"c6.10.3 The EDO makes himself available for review of the accident events at the convenience of TVA management.

+Revision r>>

REP-IPD CECC - IP-3 CECC ALERT SITE AREA EMERGENCY AND GENERAL EMERGENCY Prepared By: W. E. Webb Jr.

Approved By:

Date:

R . N 0 9/~25 81 Al 1 3 MAR 1 "! 1983 All IJlllÃ JUL 073983 Att. 1-"p. 1

~2CT ~18 All set a sess HOII ee 0 II (N3 t~~

$ A; Att.

added 5 p.

Att.

1-2.

2B; ll 'ttAUG 1 0 1984 Coversheet, 1

Att. I P. 1 JAN 24 >985A>>

~alR 2~1g8htevetAtt. 2; Sheet 1 p. 1,1 ts MAR 0 I 1985 ",",";"""

v MAY~51984Cover Sheet; 1; APR 0 1 1985 Att.

Att.lp.l 10 'JQN Q 5 1984 A

0 CECC-IPD IP-3 Page 1 of 6 Rev. 14 CENTRAL EMERGENCY CONTROL CENTER ALERT SITE AREA EMERGENCY AND GENERAL EMERGENCY 1.0 PURPOSE This procedure is designed to direct the CECC Director and staff to ensure consistent, accurate, and timely response to the events of an accident.

This procedure further serves to identify the necessary information.to

,provide for prompt, accurate, public protective action recommendations to appropriate State authorities.

2.0 .SCOPE This procedure covers anticipated requirements of the CECC Director and staff during an emergency classification of Alert, Site Area Emergency, or General Emergency.

3.0 REFERENCES

Radiological Emergency Plan.

4.0 ABBREVIATIONS AND DEFINITIONS CECC - Central Emergency Control Center EDO - Emergency Duty Officer KEC - Knoxville Emergency Center ODS - Operations Duty Specialist NCO - Nuclear Central Office NSMC - Nearsite Media Center NRC - Nuclear Regulatory Commission TSC - Technical Support Center 5.0 RESPONSIBILITIES 5.1 Upon notification by the TVA Operations Duty Specialist (ODS) that an emergency condition exists, the Emergency Duty Officer (EDO) is responsible for establishing initial operation of the CECC. The ODS is responsible for contacting the CECC staff and having them report to the CECC. The CECC Director has general responsibility for verification of notification and overall accident assessment during an emergency condition.

5' To assist the CECC Director in carrying out the responsibilities of the Director's position, a CECC staff is available. An assignment of positions and duties of this staff is described in attachment 4.

'6.0 PROCEDURE RE UIREMENTS 6.1 Notifications General Revision

CECC-IPD IP-3 Page 2 of 6 Rev. 14 6.1.1 Upon reporting to the CECC, the Director will verify that communications have been established with the State and that the nature of the accident has been reviewed with them.

6.1.2 The CECC Director shall ensure that notification of the event is made to all those listed on the Notification Check Sheet (attachment 1) as appropriate. Priority is noted on the attachment.

6.1.3 The CECC Director shall ensure that those listed on attach-ment 1 are kept briefed periodically, as appropriate, on the progression of events and in particular when the accident classification is either upgraded or downgraded.

6.1.4 Upon termination of the emergency, the CECC Director shall ensure that all attachment 1 notifications are made as appropriate.

6.2 Accident Assessment 6.2.1 The CECC Director is responsible for directing TVA's overall response to the emergency.

6.2.2 The CECC Director shall ensure that all information required by State authorities to perform their assessment function and carry out necessary protective actions is being provided to them in a timely and accurate manner (see attachment 6).

6.2.3 The CECC Director is responsible for making appropriate public protective action recommendations to State authorities. Attachment 2 provides an overview of the necessary information required by the CECC Director to make appropriate protective action recommendations. Attachment 3 provides a logic diagram to assist the CECC Director in making protective action recommendations to the State.

6.2.4 The CECC Director shall schedule periodic briefings (at a minimum, hourly) with the Plant Assessment and Radiological Assessment Managers, Power Information Manager, and others as necessary to review all appropriate information as identified in attachments 2 and 3.

6.2.5 The CECC Director shall ensure that the accident information collected is posted appropriately on the status boards. The information on the status boards must be kept current for the benefit of the CECC Director and staff.

General Revision

CECC-IPD IP-3 Page 3 of 6 Rev. 14 6.2.6 The CECC Director shall ensure that a chronology of key offsite activities is being kept and distributed'o other emergency centers as appropriate. This responsibility is assigned to the State Communicator.

6.2.7 The CECC Director shall ensure that appropriate offsite assessment information is transmitted to the site (attachment 8).

6.2.8 The CECC Director shall utilize the Plant Assessment and Radiological Assessment Managers and staff to continuously review the onsite and offsite accident information. These reviews should attempt to identify trends in key 2 and 3) and emphasize display and analysis information'attachments of data for predictive purposes. Assessments in these areas shall be updated, at a minimum, on an hourly basis and all TVA and State personnel briefed appropriately.

6.2.9 The CECC Director shall ensure that any discrepancies between TVA and State information/assessment are resolved and clarified appropriately.

6.2.10 Potential Release Evaluation 6.2.10.1 A potential release evaluation may be performed at any time by the KEC to assess the impact of plant conditions on the environment. This evaluation is based on the present or projected plant conditions.

6.2.10.2 The Plant Assessment and Radiological Assessment Managers shall determine the need for a potential release and associated dose evaluation based on a potential change in plant conditions. The need for such an evaluation shall be based on the continuing assessments being made by the CECC staff and the information obtained from trending key plant and offsite parameters.

6.2.10.3 If this evaluation is needed, the KEC will perform the necessary calculation to predict the potential release. The Plant Assessment Staff shall also provide the KEC with the assumptions and postulated plant status that should be considered when performing the calculation.

6.2.10.4 The KEC will calculate the predicted release and provide it to the Radiological Assessment Staff who will calculate an associated offsite dose. The results of the dose assessment will then be provided to the Radiological Assessment Manager and CECC Director.

Genera1 Revision

CECC-IPD IP-3 Page 4 of 6 Rev. 14 6.3 General 0 eration 6.3.1 Ph sical Securit Re uirements for CECC The CECC Director has responsibility for physical security of the CECC and ODS work area. The CECC Director or his representative will inform the Public Safety Officer (stationed at the entryway to the CECC) if visitors requesting admittance to the emergency center should be allowed to enter. Permanent members of the ODS and CECC staffs will have identification badges.

6.3.2 Power Information Liaison The CECC Director will coordinate with the Plant Assessment Manager the selection of one person to serve as a technical advisor to the Power Information Manager in the CECC. The person will be responsible for providing a nontechnical interpretation of the event for the CECC Information Office staff.

If the NSMC is to be staffed, the CECC Director will coordinate with the Plant Assessment and Radiological Assessment Managers the selection of two people to serve as technical advisors to the TVA spokesperson located there. One will serve as a Radiological Health Advisor and the other as a Plant Operations Advisor. These people will be responsible for assisting the TVA spokesperson in interpreting the*approved releases and events taking place. 'ress 6.3.3 Discussion with Other TVA Or anizations The CECC Director will discuss the efforts being taken by TVA to mitigate the consequences of an accident with representatives of other TVA organizations as needed.

Representatives are identified for the Division of Medical Services, Division of Water Resources, the Nuclear Licensing Staff, Division of guality Assurance, and the Office of the General Counsel. These representatives may report to the CECC if necessary or desirable. Notification information is provided in the TVA Radiological Emergency Notification Directory.

The CECC Director shall conduct periodic briefings for the entire CECC staff to update the emergency situation for them.

General Revision

CECC-IPD IP-3 Page 5 of 6 Rev. 14 6.3.5 State'Advisors For a classification of SITE AREA EMERGENCY OR GENERAL EMERGENCY, the CECC Director will coordinate with the Plant Assessment Manager the selection of two people to serve as technical advisors to the State Emergency Operations Center.

The CECC Director will authorize travel to the State Emergency Operations Center for the purpose of providing technical information, advice, and interpretation to state personnel. Those personnel will set up a 12-hour shift rotation upon arrival to provide 24-hour coverage for the State. The CECC Director may provide additional personnel as needed.

Primar'y duties of the State advisors are as follows:

A. Technical explanations and clarification on plant status.

B. Assist the State by keeping them informed of available TVA resources.

C. Assist the State in describing/clarifying TVA's response to the emergency, understanding TVA's emergency organi- "

zation, key TVA staff positions, etc.

6.3.6 Senior Cor orate Su ort at the Site The Site Director will serve as the Senior Corporate repre-sentative onsite. He will advise the Site Emergency Director on,TVA policy matters and act as an additional interface with, NRC and others as necessary. He also serves as a direct interface with the CECC Director.

6.3.7 Relief of Duties Should the accident be expected to last for an extended period, the CECC Director originates a schedule for relief.

The duties of CECC Director should only pass to individuals identified as alternates for the CECC Director's position.

However, for a short period of time, the CECC Director may delegate the authority of CECC Director to a member of the CECC staff until an alternate CECC Director can arrive. The CECC Director also directs his staff and the CECC repre-sentatives to prepare a schedule for their relic'f to ensure the necessary staff and representatives of the CECC are available for the duration of the emergency. The CECC Director gives the Management Services representative a copy of the schedule, and he notifies the individuals of the time they are to report.

General Revision

CECC-IPD IP-3 Page 6 of 6 Rev. 14 6.3.8 Coordination of Recover Efforts Appropriate recovery efforts shall be initiated upon termi-nation of the emergency. The CECC Director is responsible for assessing and coordinating the recovery efforts for response to an emergency in accordance with the general guidelines provided in the Radiological Emergency Plan. The CECC,Director will inform each emergency center when the emergency is terminated and the recovery phase begins. As judgement and events determine, additional resources outside of TVA may be required to mitigate the consequences of an emergency. The CECC Director contacts these offsite agencies as needed. Some of the groups from whom support can be obtained include: NRC, DOE (Oak Ridge), DOE (Savannah River),

INPO, MAELU, NSSS vendors, and other nuclear utilities.

6.3.9 Termination of the Emer enc Upon termination of the emergency, the CECC Director and staff will make themselves available for review of the accident.

General Revision

CECC-IPD IP-3 Attachment 1 Page 1 of 1 Rev. 16

'ttachment 1 Notification'heck Sheet

1. Power Information, Duty Officer (CECC) 2'. Public Safety (If physical security of the facility is required)(REND)

3. J. P. Darling

4. John Hutton

5. R. J. Kitts

6. B. K. Marks

%7, E. K. Sliger Manager, Office of Power and Engineering

%9. NSRS Duty Engineer

10. Power Nuclear Safety Staff (CECC)~

11. NSSS Vendor (REND)~

INPO (REND)~

13. DOE (REND)~

14. South Central Bell (REND)~

+15. Appropriate insurance carrier per Attachment 9. (REND)~

NOTE: CECC--Indicates appropriate contact and number are located on the CECC Notification Board.

REND--Indicates appropriate contact and number are located in the TVA Radiological Emergency Notification Directory.

Response to the emergency takes top priority. These notifications shall be made when there is time and staff to do so.

~Contact the Knoxville TVA operator, identify yourself, and provide telephone number. Request that the operator page the NSRS duty officer and have him return your call.

+Revision IPD-CECC-IP-3

J h

0 0

CECC-IPD IP"3 Attachment 2 Page 1 of 1 Rev. 14 Attachment 2 INPUT FOR CECC ACCIDENT ASSESSMENT HEAT REMOVAL CAPABILITY FUEL INTEGRITY SOURCE TERMS CONTAINMENT INTEGRITY MET DATA RADIOACTIVITY IN CONTAINMENT FIELD SURVEY DATA PLANT ASSESSMENT DOSE ASSESSMENT KEC TSC IP-6 PLANT ASSESSMENT RADIOLOGICAL ASSESSMENT MANAGER M NAGER E EMERGENCY CECC DIRECTOR DIRECTOR PROTECTIVE ACTION RECOMMENDATIONS General Revision

REP-IPD CECC - IP+4 CECC SITE EMERGENCY Prepared By: W. E. W b J Approved By:

Date:

Rev. No. Date Revise~d Pa es Rev. No. Date Revise~d Pa es 9~1 1 2/18/82 2 3 4

~~ PRO~RE WAS DELETED EFFECTIVE OCTOBER 1982 The last page of this procedure is Number

Page 1 of 6 CECC-IPD IP-4 Rev. 0 CECC SITE EMERGENCY 1.0 PURPOSE This procedure is designed to direct the Central Emergency Control Center (CECC) Director and staff to ensure consis-tent, accurate, and timely response to the events of an accident.

2.0 SCOPE This procedure covers anticipated requirements of the CECC Director during an emergency classification of Site Emer-gency. This procedure does not address actions of the CECC Director during a Notification of Unusual Event, Alert, or General Emergency.

3.0 REFERENCES

Radiological Emergency Plan 4;0 ABBREVIATIONS AND DEFINITIONS None 5.0 RESPONSIBII.ITIES 5.1 Upon notification by the TVA Operations Duty Specialist that an emergency condition exists, the Division of Nuclear Power Emergency Duty Officer (Emergency Duty Officer) is respon-sible for establishing initial operation of the CECC. The Emergency Duty Officer is relieved by the designated CECC Director upon arrival. The CECC Director has general res-ponsiblity for verification of notification and assessment during an emergency condition.

5.2 To assist the CECC Director in carrying out the responsi-bilities of the Director's position, a CECC staff is available.

Page 2 of 6 CECC-IPD

'KP-4 Rev. 1 6.0 PROCEDURE RE UIREMENTS NOTE: The Emergency Duty Officer will follow this procedure until relieved by the permanent CECC Director. The permanent CECC Director debriefs the Emergency Duty Officer and continues with the procedure where the Emergency Duty Officer left off.

6.i Notify the Power Information Duty Officer (See the DNP Notification Board).

6.2 Notify Nuclear Security (See the DNP Notification Board).

6.3 Discuss the current status of the emergency with the DNPEC Director as soon as possible.

6.4 Establish communication with the MSECC and review the nature of the accident. The primary means of communication wi:th the MSECC is a dedicated ring-down line from the CECC.

Alternate numbers are listed in the TVA Radiological Emer-gency Notification Directory.

6.5 Establish communication with the appropriate State agencies by direct ring-down line and review the nature of the accident.

Alternate phone numbers for these agencies are listed in the TVA Radiological Emergency Notification Directory.

6.6 Confirm notification of the KECC and review the status of the accident by contacting the KECC by direct ring-down line.

Alternate numbers are listed in the TVA Radiological Emer-gency Notification Directory.

/ 6.7 Notify the'SRS Duty Engineer (See the DNP Notification Board).

/ 6.8 Notify the following for information only (See the DNP Notification Board).

6.8.1 H. J. Green 6.8.2 E. F. Thomas 6.8.3 Hugh Parris 6.8.4 J. A. Coffey

Page 3 of 6 CECC-IPD IP-4

,Rev. 1 Notify the NSSS Vendor (See the TVA Radiological Emergency Notification Directory)

Browns Ferry - General Electric Sequoyah, Watts Bar - Westinghouse Notify INPO (See the TVA Radiological Emergency Notification Directory).

Notify the appropriate DOE Operations Office regarding the existence of an emergency condition at a TVA facility. (See the TVA Radiological Emergency Notification Directory.)

Initiate notification of the Insurance Underwriters by calling the Division of Purchasing (See the TVA Radiological Emergency Notification Directory).

Notify South Central Bell. (See the TVA Radiological Emer- .

gency Notification Directory.)

The CECC Director will coordinate with the DNPEC Director the selection of one person to serve as a technical advisor to the Power Information Officer. This person will be respon-sible for providing a non-technical interpretation of the event for the Information Office.

For a classification of site emergency or general emergency the CECC Director will coordinate with the DNPEC Director the selection of two people to serve as technical advisors to the State Emergency Operations Center. The CECC Director will authorize travel to the State Emergency Operations Center for the purpose of providing technical information, advice, and interpretation to state personnel. Those personnel will set up a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift rotation upon arrival to provide 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months coverage for the state. The CECC Director may provide addi-tional personnel as needed.

The CECC Director will dispatch a senior management repre-sentative to the site to act as Senior Advisor to the Site Emergency Director. This individual will advise the Site Emergency Director on TVA policy matters and act as an additional interface with the NRC as necessary. He will in.

no way control events or operations at the site. If 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months operation is necessary, two people should be sent.

Periodic U datin of State Federal Industr and TVA Emer enc '0 erations Personnel Obtain an update on plant status from the DNPEC Director approximately every hour (or as often as provided if more frequent than once per hour).

3

Page 4 of 6

~'ECC-IPD IP-4 Rev. 1 6.16.2 After obtaining a status update from the SE Director or DNPEC Director, contact the MSECC Director and obtain the status of environmental'onitoring, dose calculations, and health physics coverage. Provide the MSECC and KECC Director with the information supplied by the site.

6.16.3 Notify the MSECC and KECC after each update received from the plant. This should be done even significant change in the accident status.

if there is little or no 6.16.4 Maintain periodic contact with other organizations as listed in sections 6.4 through 6.13.

6.17 Assessment of Accident Data Durin an Emer enc Continuous Review of Accident Pro ression--The CECC Director will designate a member of the CECC staff to review the accident information. The review should attempt to identify trends in plant release rate dose rates.

if any, and trends in offsite The review should incorporate the use of graphs for extrapolation where possible. The review should empha-size display and analysis of data for predictive purposes.

6.17.,2 Maintenance of CECC Status Board--The CECC Director will designate a member of the CECC staff to post the accident information collected on a status board. An erasable marker board is provided in the CECC for this purpose. The infor-mation on the status board must be kept current for the benefit of the CECC Director and staff.

6.17.3 CECC Director Discussion with CECC Re resentatives from Ke TVA Grou s--The CECC Director discusses the efforts being taken by TVA to mitigate the consequences of an acci-dent with the CECC representatives of TVA organizations as needed. Representatives are identified for the Divisions of Occupational Health and Safety, Medical Services, Division of Water Resources, and the Office of the General Counsel (Law).

These representatives may report, to the CECC if desirable. Notification information is provided in the TVA necessary or Radiological Emergency Notification Directory.

6.18 Ph sical Securit Re uirements for the Chattanoo a Emer enc Center The CECC Director has responsiblity for physical security of the CECC, DNPEC, and Operations Duty specialist work area.

The CECC Director or his representative will inform the Public Safety Officer stationed at the entry way to the CECC if visitors requesting admittance to the emergency center should be allowed to enter. Permament members of the Opera-tions Duty Specialist, CECC, and DNPEC staffs will have identification badges.

Page 5 of 6 CECC-IPD IP-4 Rev. 0 General Coordination of Recover Efforts b the CECC Director The CECC Director is responsible for assessing and coor-dinating the recovery efforts for response to an emergency.

The CECC Director will inform each emergency center, when the emergency is terminated and the recovery phase begins. As judgement and events determine, additional resources outside .

of TVA may be required to mitigate the consequences of an emergency; The CECC Director contacts these offsite agencies as needed. Some of the groups from whom support can be obtained include: NRC, DOE (Oak Ridge), DOE (Savannah. River),

INPO, MAELU, NSSS vendors, and other nuclear utilities.

Relief of Duties as CECC Director Should the accident be expected to last for an extended period, the CECC Director originates a schedule for relief.

The duties of CECC Director should only be passed on to individuals identified as alternates for the CECC Director's position. However, for short periods of time, the CECC Director may delegate the authority of CECC Director to a member of the key CECC staff until an alternate CECC Director can arrive. The CECC Director also directs his staff and the CECC representatives to prepare a schedule for their relief to ensure the necessary staff and representatives of the CECC are available for the duration of the emergency. The CECC Director gives the" DNPEC Administrative Coordinator a copy of the schedule and he notifies the individuals of the time they are to report.

Actions to be Taken When the Accident Terminates Upon notification of the termination of the emergency, the CECC Director has the responsibility of notifying all parties informed in section 6.1 through 6.13 of this procedure.

Initiate recovery effort under the general guidelines of the REP, Section 11.

The CECC Director will .make himself available for review of the accident.

Actions to be Taken Should the Accident Classification be U raded or Down raded If the accident classification is upgraded to a General Emergency, notify all parties informed= in sections 6.1 through 6.13.

Page 6 of 6 CECC-IPD IP-4 Rev. 0 6.22.2 If the accident classification is downgraded to Notification of Unusual Event, notify all parties informed in sections 6.1 through 6.13.

REP-IPD

~

CECC - IP-5 CECC GENERAL EMERGENCY Prepared By: W. E. Webb, Jr.

Approved By:

Date:

9~1 Al 1 1 2/~18 82 2 3 4 lHJ'j PROQKDg3E ~Q~ELKXg~FECTIV~~QQR 19 Q The last page of this procedure is Number

0 Page 1 of 5 CECC-IPD IP-5 Rev. 0 CECC GENERAL EMERGENCY 1.0 PURPOSE This procedure is designed to direct the Central Emergency Control Center (CECC) Director and staff to ensure consis-tent, accurate, and timely response to the events of an accident.

2.0 SCOPE I

This procedure covers anticipated requirements of the CECC Director during an emergency classification of General Emer-gency. This procedure does not address actions of the CECC Director during a Notification of Unusual Event, Alert, or Site Emergency.

3,0 REFERENCES Radiological Emergency Plan 4.0 ABBREVIATIONS AND DEFINITIONS None 5.0 RESPONSIBILITIES 5.1 Upon notification by the TVA Operations Duty Specialist that an emergency condition exists, the Division of Nuclear Power Emergency Duty Officer (Emergency Duty Officer) is respon-sible for establishing initial operation of the CECC. The Emergency Duty Officer is relieved by the designated CECC Director upon arrival. The CECC Director has general respon-siblity for verification of notification and assessment during an emergency condition.

5.2 To assist the CECC Director in carrying out the responsi-bilities of the Director's position, a CECC staff is available.

Page 2 of 5 CECC-IPD IP-5 Rev. 1 6.0 PROCEDURE RE(}UIREMENTS NOTE: The Emergency Duty Officer will follow this procedure until relieved by the permanent CECC Director. The permanent CECC Director debriefs the Emergency Duty Officer and continues with the procedure where the Emergency Duty Officer left off.

6.x Notify the Power Information Duty Officer (See the DNP Notification Board).

6.2 Notify Nuclear Security (See the DNP Notification Board).

/ 6.3 Discuss the current status of the emergency with the DNFEC Director as soon as possible.

/ 6.4 Establish communication with the MSECC and review the nature of the accident. The primary means of communication with the M8ECC is a dedicated ring-down line from the CECC.

/

Alternate numbers are listed in the TVA Radiological Emer-gency Notification Directory.

/ 6.5 Establish communication with 'the appropriate State agencies by direct ring-down line and review the nature of the accident.

Alternate phone numbers for these agencies are listed in the TVA Radiological Emergency Notification Directory.

/ 6.6 Confirm notification of the KECC and review the status of the accident by contacting the KECC by direct ring-down line.

Alternate numbers are listed 'in the TVA Radiological'Emer-gency Notification Directory.

/ 6.7 Notify the NSRS Duty Engineer (See the DNP Notification Board).

/ 6.8 Notify the following for information only (See the DNP Notification Board).

6.8.Z H. J. Green 6.8.2 E. F. Thomas 6.8.3 Hugh Parris 6.8.4 J. A. Coffey 0

II Page 3 of 5 CECC-LPD IP-5 Rev. 1 6.9 Notify the NSSS Vendor (See the TVA Radiological Emergency Notification Directory)

Browns Ferry - General Electric Sequoyah, Watts Bar - Westinghouse Notify INPO (See the TVA Radiological Emergency Notification Directory).

Notify the appropriate DOE Operations Office regarding the existence of an emergency condition at a TVA facility. (See the TVA Radiological Emergency Notification Directory.)

6.12 Initiate notification of the Insurance Underwriters by calling the Division of Purchasing (See the TVA Radiological Emergency Notification Directory).

6.13 Notify South Central Bell. (See the TVA Radiological Emer-gency Notification Directory.)

The CECC Director will coordinate with the DNPEC Director the selection of one person to serve as a technical advisor to the Power Informati:on Officer. This person will be respon-sible for providing a non-technical interpretation of the event for the Information Office.

6.15.1 For a classification of site emergency or general emergency the CECC Director will coordinate with the DNPEC Director the selection of two people to serve as technical advisors to the State Emergency Operations Center. The CECC Director will authorize travel to the State Emergency Operations Center for the purpose of providing technical information, advice, and interpretation to state personnel. Those personnel will set up a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift rotation upon arrival to provide 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months coverage for the state. The CECC Director may provide addi-tional personnel as needed.

6.15.2 The CECC Director will dispatch a- senior management repre-'

sentative to the site to act as Senior Advisor to the Site Emergency Director. This individual will advise the Site Emergency Director on TVA policy matters and act as an additional interface with the NRC as necessary. He will in no way control events or operations at the site. If 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months operation is necessary, two people should be sent.

Periodic U datin of State Federal Industr and TVA Emer enc 0 erations Personnel 6.16.1 Obtain an update on plant status from the DNPEC Director approximately every hour (or as often as provided if 'more frequent than once per hour).

Page 4 of 5

CECC-IPD IP-5 Rev. 1 6.16.2 After obtaining a status update from the SE Director or DNPEC Director, contact the MSECC Director and obtain the status of environmental monitoring, dose calculations, and health physics coverage. Provide the MSECC and KECC Director with the information supplied by the site.

6.16.3 Notify the MSECC and KECC after each update received from the plant. This should be done even if there is'ittle or no significant change in the accident status.

6e16.( Maintain periodic contact with other organizations as listed in sections 6.4 through 6.13.

6.17 Assessment of Accident Data Burin an Emer enc 6.17.1 Continuous Review of Accident Pro ression--The CECC Director will designate a member of the CECC staff to review the accident information. The review should attempt to identify trends in plant release rate if any, and trends xn offsite dose rates. The review should incorporate the use of graphs for extrapolation where possible. The review should empha-size display and analysis of data for predictive purposes.

6.17.2 Maintenance of CECC Status Board--The CECC Director will designate a member of the CECC staff to post the accident information collected on a status board. An erasable marker board is provided in the CECC for this purpose. The infor-mation on the status boards must be kept current for the benefit of the CECC Director and staff.

6.17.3 CECC Director Discussion with CECC Re resentatives from Ke taken by TVA to mitigate the consequences of an accident with the CECC representatives of TVA organizations as needed.

Representatives are identified for the Divisions of Occupa-tional Health and Safety, Medical Services, Division of Water Resources, and the Office of the General Counsel (Law).

These representatives may report to the CECC if necessary or Notification information is provided in the TVA desirable.

Radiological Emergency Notification Directory.

6.18 Ph sical Securit Re uirements for the Chattanoo a Emer enc Center The CECC Director has responsiblity for physical security of the CECC, DNPEC, and Operations Duty specialist work area.

The CECC Director or his representative will inform the Public Safety Officer stationed at, the entry way to the CECC if visitors requesting admittance to the emergency center should be allowed to enter. Permament members'f the Opera-tions Duty Specialist, CECC, and DNPEC staffs will have identification badges.

Page 5 of 5'ECC-IPD IP-5 Rev. 0 General Coordination of Recover Efforts b the CECC Director The CECC Director is responsible for assessing and coor-dinating the recovery efforts for response to an emergency.

The CECC Director will inform each emergency center when the emergency is terminated and the recovery phase begins. As judgement and events determine, additional resources outside of TVA may be required to mitigate the consequences of an emergency. The CECC Director contacts these offsite agencies as needed. Some of the groups from whom support can be obtained include: NRC, DOE (Oak Ridge), DOE (Savannah River),

INPO, MAELU, NSSS vendors, and other nuclear utilities.

Relief of Duties as CECC Director Should the accident 'be expected to last for an extended period, the CECC Director originates a schedule for relief, The duties of CECC Director should only be passed on to individuals identified as alternates for the CECC Director's position. However, for short periods of time, the CECC Director may delegate the authority of CECC'irector to a member of the key CECC staff until an alternate CECC Director can arrive. The CECC Director also directs his staff and the CECC representatives to prepare a schedule for their relief to ensure the necessary staff and representatives of the CECC are available for the duration of the emergency. The CECC Director gives the DNPEC Administrative Coordinator a copy of the schedule and he notifies the individuals of the time they are to report.

Actions to'e Taken When the Accident Terminates Upon notification of the termination of the emergency, the CECC Director has the responsibility of notifying all parties informed in section 6.1 through 6.13 of this procedure.

Initiate recovery effort under the general guidelines of the REP, Section 11.

The CECC Director will make himself available for review of the accident.

Actions to be Taken Should the Accident Classification be U raded or Down raded If the accident classification is downgraded to Notification of Unusual Event, Alert, or Site Emergency, notify all parties informed in sections 6.1 through 6.13.

REP- IPD/EC-IPD Cover Page REP-IPD CECC - IP-6 DIVISION OF PURCHASING "RADIOLOGICAL EMERGENCY PROCEDURE Prepared By: W. E. Webb, Jr.

Approved By:

Date:

R .N. RR ~ll l dP R.N.R ~Pi dP 0 9~( A11 The last'age of this procedure is Number

Page 1 of' CECC-IPD IP-6 Rev. 0 P

DIVISION OF PURCHASING RADIOLOGICAL EMERGENCY PROCEDURE 1.0 PURPOSE This procedure is designed to give direction to Division, of Purchasing personnel during a TVA radiological emergency or drill; in order to ensure consistent, accurate, and timely response to the events of a real or simulated accident.

2.0 SCOPE This procedure covers anticipated requirements of the Division of Purchasing during emergency conditions. This procedure does not cover additional actions to be taken. prior and subsequent to an emergency or drill.

3.0 REFERENCES

Radiological Emergency Plan.

4.'0 ABBREVIATIONS AND DEFINITIONS None.

5.0 RESPONSIBILITIES 5' In the event of a TVA radiological emergency or drill, the CECC Director is r'esponsible for establishing the operations of the CECC. Upon arrival at the CECC and assessment of the situation, the CECC Director notifies the Division of Pur-chasing, if necessary.

6.0 PROCEDURE RE UIREMENTS 6.1 Upon assuming his responsibilities, the CECC Director noti-fies one of the Division of Purchasing Director's Office personnel listed in the TVA Radiological Emergency Notifi-cation Directory.

6,2 Upon notification by the CECC Director, the personnel con-tacted in 6.1 notifies the applicable Division of Purchasing branch chiefs, if required, for appropriate actions.

'6. 3 All branch chiefs involved are responsible for contacting their respective section supervisors and/or purchasing agents as appropriate. Accordingly, all branch chiefs maintain a list of home telephone numbers of essential personnel in their branch'n the event of an emergency.

Page 2 of 2 CECC-IPD rP-6 Rev. 0 6.4 Periodic status reports are given through the Division of Purchasing Director's Office to the CECC Director or his staff.

6.5 If it becomes necessary, Division of Purchasing personnel may be required at the CECC to augment necessary coordination and.

communications.

6.6 The Division of Purchasing representative also acts as the TVA contact with the insurance underwriters. As this 'con-tact, the Division of Purchasing representative will contact the insurance underwriters and keep them advised on the status of the emergency.

REP- IPD/EC-IPD Cover Page REP-IP0 CECC - IP-7 DIVISION OF MEDICAL SERVICES prepared By:

W. E. Webb, Jr.

Approved 'By:

Date: 25 81 II .N. Nt ~II I dP II .N. Il ~di dP 0 9/~25 81 All The last page of this procedure is Number

Page I of 4 CECC-IPD IP-7 Rev. 0 DIVISION OF MEDICAL SERVICES 1.0 'URPOSE This procedure is designed to provide Medical Services con-sultation to the CECC Director and coordinate additional medical support for the affected TVA facility as needed.

2.0" SCOPE This procedure outlines Medical Services representative activities upon activation of 'the CECC staff during a TVA nuclear emergency. 4

3.0 REFERENCES

3.1 Radiological Emergency Plan and IPD.

4.0 ABBREVIATIONS AND DEFINITIONS 4.1 The Division of Medical Services representative who serves staff.

on'he CECC 4.2 Area Medical Chief The physician who supervises all clinical (patient care)

. services in TVA facilities within a specified geographical area. This will also refer to designated alternates when the Area Medical Chief is unavailable.

4.3 Area Chief Nurse The nurse who supervises nursing services and nursing personnel in a specified geographical area. This will also refer to designated alternates when the Area Chief Nurse is unavailable.

4,4 Medical Director The Director of TVA's Division of Medical Services.

5.0 RESPONSIBILITIES AND DUTIES 5.1 Medical Services CECC Re resentatives 5.1.1 Outline of Duties

Page 2 of 4 CECC-IPD IP-7 Rev. 0 5.1.1.1 Acts as consultant to the CECC Director concerning:

1. treatment of radiation injuries among the workforce;,

2. proposed recommendations regarding protective measures for the public;

3. occupational'ealth matters, including employee health, status.

5.1.1.2 Monitor changing emergency situation by briefings from the CECC Director and other sources of reliable information.

5.1.1.3 Predict potential needs for additional medical support at the affected facility.

5.1.1.4 Convey current emergency status and projected medical support needs to the appropriate Area Medical Chief.

5.1.1.5 Receive status reports from Area Medical Chief or facility health station regarding medical response capability and projected needs.

5.1.1.6 Inventory resources available from other Medical Services areas and outside sources, e.g., REAC/TS.

5.1.2 Action Se uence and Documentation Guidelines 5.1.2.1 Receives notice of emergency from CECC director.

5.1.2.2 Get briefing of situation and instructions for participation.

5.1.2.3 Standby or report to CECC as requested.

5.1.2.4 Start time log of events, contacts, notifications, actions, etc.

5.1.2.5 Alert appropriate Area Medical Chief and instruct him to take appropriate action as outlined in 5.2 5.1.2.6 Alert the Medical Director.

5.1.2.7 Contact alternate MED SV CECC representatives, alert them, and establish a tentative duty/relief schedule.

5.1.2.8 Confirm communication channels, alert and request standby for possible assistance to:

l. Area Medical Chiefs

2. REAC/TS

Page 3 of 4 CECC-IPD IP-7 Rev. 0

3. other resources as deemed necessary 5.1.2 ' Obtain from the Area Medical Chief, proposed duty rosters and shift coverage for the affected facility.

5.1.2.10 Keep proposed staffing schedules for reference, briefing and adjustment in response to assessment of potential needs by CECC Director.

5.2 Area Medical Chief 5.2.1 Initiate and maintain time log of all notifications, actions, and other pertinent events.

5.2.2 Inventory, alert, schedule or coordinate TVA-MED SV staff to provide coverage for onsite and area medical support facilities.

5.2.3 Coordinate and provide other medical support for onsite and area medical facilities as deemed necessary.

5.2.4 Provide professional supervision for medical assessment, treatment, consultation and referral.

5.2.5 Arrange for additional consultation, referral, or medical followup as necessary.

5.2.6 Determine from health station staff and other sources, a specific summary of all patients by name, extent of injury, radiological exposure and contamination, treatment, disposi-tion and current location.

5.2.7 Coordinate and exchange pertinent evaluation, treatment, and disposition information with health physics staff.

5.2.8 Coordinate collection of all records and reports on radiologic exposure or contamination of TVA personnel.

5.2.9 Provide MED SV CECC representative with proposed scheduling rosters for onsite and area medical facilities.

5'.2. 10 Notify Medical Director and MED SV CECC representative of injury, illness, or radiological exposure and contamihation to onsite personnel.

5.2.11 Notify Medical Director and MED SV,. CECC representative promptly and periodically on status of items 5.2.2, 5.2.6, and 5.2.9 above.

Page 4 of 4 CECC-IPD

'IP-7 Rev. 0 5.3 Area Chief Nurse Arear'edical 5.3.1 Assist the Chief in alerting, scheduling, and providing nursing services as requested.

6.0 Arran ements for Additional Medical Su ort The Division of Medical Services provides additional medical supplies and equipment, and nurse and physician coverage onsite, upon request and after consultation with the Medical Director and the MED SV CECC representative.

PE'P~"KPD I

CECC -, IP-8 OFFICE OF THE'GENERAL COUNSEL REP,PROG DURES i '

I Prepared By: W. E. Web Jr.

Approved By:

Date: 9/25/81 Rev. No. Date Revi~sed Pa es O 9/25/81 Al 1 OCT 26 $ 82 Azz The last page of this procedure is Number

CECC-IPD IP-S Page 1 of 2 Rev. 1 OFFICE OF THE GENERAL COUNSEL REP PROCEDURES 1.0 'PURPOSE These procedures are designed to establish a line of responsibility within the Office of the General Counsel (OGC) to assure that requests for legal assistance during an emergency are appropriately handled in a timely manner.

2.0 SCOPE These procedures cover the assignment of OGC attorneys during emergency conditions. The procedures do not cover assignments that may be made prior or subsequent to an emergency or drill.

3.0 REFERENCES

Radiological Emergency Plan.

4.0 ABBREVlATIONS AND DEFINITIONS CECC - Central Emergency Control Center.

KEC - Knoxville Emergency Center.

OGC - Office of the General Counsel.

5.0 RESPONSlBILlTIES 5.1 Upon notification by the CECC Director that an emergency condition exists, the OGC representative to the CECC is responsible for making himself available to receive requests for legal assistance from the CECC Director or the KEC Director. The OGC representative will provide requested legal advice or coordinate the provision of such advice by OGC, as'ppropriate.

6.1 The OGC representative, as designated in the TVA Radiological Emergency Notification Directory, will advise the CECC Director of a telephone number at which he or she can be reached during the emergency, and derring the course of the emergency will provide legal assistance as requested consistent with OGC procedures. The CECC Director will attempt to contact an OGC representative by calling

"-Revision

~ "1"

0 CECC-IPD IP-8 Page 2 of 2 Rev. 1 those designated in the TVA Radiological Emergency Notification Directory in the order listed. The first person contacted shall act as the OGC representative until responsibility is transferred to another OGC representative or until the end of the emergency.

The first three OGC representatives on the list are considered the primary OGC representatives. Other OGC representatives will attempt to contact a primary OGC representative to transfer responsibility for OGC representation.

Entire Page Revised

REP-IPD CECC - IP- 9 INFORMATION OFFICE OPERATING PROCEDURES F R ABNORMAL OCCURRENCES XT NUCLEAR POWER PLANTS H

Prepared By: W. E. Web Jr.

Approved By:

Date:

0 9/~25 81 Al 1 OCT 26 1982 PROCEDURE DELETED'JULY 1983

Jl I

f

REP-IPD/EC-IPD Cover Page REP-IPD CECC - IP 1O EMERGENCY FINANCIAL SUPPORT PROCEDURES Prepared By:

Approved By:

Date: 25 81 R .N. Dt ~Ri dP R .N. D ~ti dP 9/25/81 All The last page of this procedure is Number

Page 1 of 4 CECC-IPD IP-10 Rev. 0 EMERGENCY FINANCIAL SUPPORT PROCEDURES 1.0 PURPOSE These procedures are designed to direct Division -of finance employees to insure that financial support is provided during a radiological emergency.

2.0 SCOPE These procedures apply to all financial reporting and payment activities during the period of the emergency.

3.0 REFERENCES

Ra'diological Emergency Plan.

4'. 0 ABBREVIATIONS AND DEFINITIONS 4.1

1 employee's time and delivering employee paychecks.

4.2 Emer enc Coordinator - The Division of Finance employees designated to coordinate all financial support to other TVA organizations during a radiological emergency.

4.3 Emer enc A ent Officer - A TVA employee authorized by the TVA Treasurer to receive or disburse TVA funds during a radiological emergency.

4.4 Advance Pa ent of Earnin s - A monetary amount payable to an employee in a'dvance of the date on which the employee would otherwise be entitled to be paid.

4.5 S ecial Allowance - An additional allowance payment to offset the direct added expenses incident to a radiological emergency.

5;0 RESPONSIBILITIES 5.1 Upon notification of an emergency, the Comptroller is respon-sible for implementing .the emergency financial support procedures.

6.0 PROCEDURE RE UIREMENTS

Page 2 of 4 CECC-IPD IP-10 Rev. 0 6.1 Initial Notification The Comptroller notifies the Division of Finance Emergency Coordinator after official notification of an emergency is received.

6.2 Division of Finance Emer enc Coordinator The Division of Finance Emergency Coordinator stands by in case financial services are needed at the emergency site or immediate vicinity. The Emergency Coordinator activates emergency agent officers at the Division of Finance location nearest the emergency location.

6' ADVANCE PAYMENTS The Emergency Coordinator may authorize advance payments of earnings when, in the opinion of the Emergency Agent Officer, payment is required to help an employee defray immediate expenses incident to an emergency.

6.3.1 Rate of Advance Pa eats Advance payment is based on the rate of pay to which the employee was entitled immediately prior to notification of the emergency.

6.3.2 Amount of Advance Pa ent The amount of advance payment is the monetary amount covering a period not to exceed 30 days or a lesser number of days as determined appropriate by the Emergency Coordinator.

6.3.3.1 Com utation of Advance Pa ent For full-time and regular part-time employees, the amount of advance is computed on the basis of the number of regularly scheduled workdays that will occur during the period covered by the advance.

6.3.3.2 To Whom Paid The advance payments may be paid to the employee, an adult dependent, or a designated representative. When these pay-ments are made to other than the employee, prior written authorization may have been given by the employee.

6.3.4 When Paid The advance payment may be made at any time after notifi-cation of an emergency.

Page 3 of 4'ECC-IPD IP-10 Rev. '0

=, 6.3.5 Reco~erCr After an employee's account is reviewed and it is found that the employee is indebted for any part of the advance payment, recovery of the payment will be made. Repayment may be made either in full or in partial payments as agreed upon. between the payroll officer and the employee.

6.3.6 Waiver of Recover Recovery of an advance payment is not required when determined that the recovery would be against equity and good it is conscience or against the public interest.

6.4 SPECIAL PAYMENTS Special allowances may be paid to offset any direct added expenses which are incurred as a result of an emergency.

Such allowances may be paid by authorized agent officers.

6.4.1 Travel E enses Travel expenses 'and per diem is paid in accordance with TVA travel regulations.

6.4.2. Subsistence Ex enses Subsistence payments are made when considered necessary in the opinion of the Division of Finance.

6.4.3 The Emergency Coordinator is authorized to make payments for other expenses considered necessary to insure that financial support is provided during the period of emergency. Such payments are made by agent officer checks to employees or to commercial establishments for materials, supplies, or other expenses necessary to support TVA emergency procedures.

6.5 REPORTING The Emergency Coordinator takes steps necessary'o see that all payments are adequately supported, considering the cir-cumstances.

Pa roll Time Re ortin During 'he emergency, normal reporting of employees'ime worked is made if practicable. The Emergency Coordinator

Page 4 of 4 CECC-IPD IP-10 Rev. 0 activates necessary procedures depending upon the . circum-stances, These procedures are coordinated with the local payroll office if the payroll office is still active.

6.

When the emergency condition ceases, the Emergency Coordi-nator initiates a final accounting for all payments made.

6.5.3 Financial Records The Emergency Coordinator takes necessary steps to protect all financial and accounting records and cash at the emergency location.

~s REP-IPD CECC - IP-11 CECC TRAINING- RE UIREMENTS 1

Prepared By: B. K. Mark Approved By:

Date: 2 81 Rev. No. Date Revised Pacdes 9L22581 Al 1 OCT 26 $ 82 The last page of this procedure is Number

CECC-IPD IP-11 Page 1 of 3 Rev. 1 CECC TRAINING RE UIREMENTS 1.0 PURPOSE This procedure specifies the training provided to the Director, technical assistants, and representatives of the CECC.

2.0 SCOPE This procedure covers the training of the CECC members,'defines the responsibility for providing the training and documentation, and provides for peri'odic retraining.

3.0 REFERENCES

Radiological Emergency Plan.

4.0 ABBREVIATIONS.AND DEFINITIONS None.

5.0 RESPONSIBILITIES 5.1 The Division of Nuclear Power Radiological Emergency Preparedness Section is responsible for training the CECC Director and technical assistants. Training documentation will be retained in the Radiological Emergency Preparedness Section files. Lesson plans will be prepared by the Radiological Emergency Preparedness Section.

6.0 PROCEDURE RE UIRENENTS 6.1 Trainin Lessons The lesson plans for specific training will be prepared by the Radiological Emergency Preparedness Section. A n

6.2 Trainin Records Records of individual training will be maintained on Form TVA 1453

'nd retained in the Radiological Emergency Preparedness Section

files.

6.3 S ecific Trainin Re uirements

<<Revision

0 CECC-IPD IP-11 Page 2 of 3 Rev. 1 6.3.1 CECC Director and Emer enc Dut Officer The CECC Director, his alternates, and the Emergency Duty Officers will attend a training class annually to ensure appropriate coordination and response of the CECC.

The training will .cover the following subjects:

1. TVA Radiological Emergency Plan Familiarization

2. Facility Familiarization

3. Communication System Familiarization

4. Implementing Procedure Review

5. Protective Action Options

6. Coordination of TVA Support

7. Interagency Coordination (State, Federal, and Vendor)

8. Example Scenarios (including transportation) 6.3.2 CECC Technical Assistants The CECC technical assistants will attend a training class annually to ensure appropriate coordination and response of the CECC.

The training .will cover the following subjects:

1. TVA Radiological. Emergency Plan Familiarization

2. Facility Familiarization

.3. Communication System Familiarization

4. Implementing Procedure Review 6.4 Revisions to the REP or REP-IPD Each approved revision to the REP or REP-IPD containing other than editorial or plan administration-type changes is routed, by the Radiological Emergency Parparedness Section, to each individual assigned a,responsibility in the CECC. Each individual is responsible for verifying he has read and understands the revision by signing and returning the cover letter attached to the change.

~Revision "2-

CECC-IPD IP-11 Page 3 of 3 Rev. 1 6.5 Trainin Drills Training drills are conducted periodically to ensure appropriate components of the CECC are thoroughly tested and proven effective.

On-the-spot corrections are made of participants as necessary.

Records of these training drills are maintained in the Radiological Emergency Preparedness Section files.

>Revision

REP- IPD CECC - IP- 12 Prepared By: W. E. ebb, Jr.

Approved By:

Date: 9 25 81 0 9/gg/g1 All OCT ~882 z. a 5 The last page of this procedure is Number

CECC-IPD IP"12 Page 1 of 2 Rev. 1 CECC/DNPEC SECURITY 1.0 PURPOSE This procedure defines CECC/DNPEC security requirements and specific instructions for TVA Public Safety Officers when the CECC/DNPEC is activated.

2.0 . SCOPE This procedure covers the actions required to establish and maintain access control at the CECC/DNPEC complex.

3.0 REFERENCES

TVA Radiological Emergency Plan.

4.0 ABBREVIATIONS AND DEFINITIONS None.

5.0 RESPONSIBILITIES 5.1 The Radiological Emergency Preparedness Section is responsible for ensuring that each TVA employee having a function inside the CECC/DNPEC complex has an identification card with the designation "CHATT,-RADIOLOGICAL EMERGENCY TEAM." These identification cards will be maintained in the CECC.

5.2 The Chattanooga TVA Public Safety Office is responsible for general access control within the Chestnut Street Tower II office building and for establishing restricted access control for the CECC/DNPEC area.

6.0 PROCEDURE RE UIREMENTS 6.1 Notification The Chattanooga TVA Public Safety Office will be notified by the CECC Director whenever the CECC/DNPEC is activated.

6.2 Securit Re uirements 6.2.1 When notified 'that the CECC/DNPEC has been activated, the Chattanooga TVA. Public Safety Office will immediately assign two TVA Public Safety Officers to establish a post immediately outside the CECC/DNPEC (room 140, Chestnut. Street Tower II - see attachment 1).

='Revision

CECC-IPD IP-12 Page 2 of 2 Rev. 0 6.2.2 Upon arrival at the CECC/DNPEC, the Public Safety Officers shall establish and maintain access control in accordance with CECC/

DNPEC Security Instruction given in attachment. 2.

6.2.3 Public Safety Officers assigned to the CECC/DNPEC shall report to the CECC Director or, in his absence, the DNPEC Director. Should both directors be absent, he should report to the senior REP staff member on duty.

6.2.4 Upon arrival at the CECC/DNPEC, Radiological Emergency Team members will be issued identification cards with the designation "CHATT.-RADIOLOGICALEMERGENCY TEAM." These members are authorized unlimited access to the CECC/DNPEC.

6.2.5 All other personnel requesting access to the CECC/DNPEC must be authorized by one of the following CECC/DNPEC staff personnel:

CECC Director, REP staff, DNPEC Director, Plant Communicator.

6.2.6 A roster of CECC/DNPEC access shall be maintained by the TVA Public Safety Officers. See attachment 3.

CECC-IPD IP"12 Attachment, 2 Page 1 of 2 Rev. 1 Attachment 2 CECC/DNPEC SECURITY INSTRUCTIONS D~ut Sco e A TVA Public Safety Officer shall establish a post immediately outside the CECC/DNPEC to control access to the area during a radiological emergency or drill.

Materials and E ui ment Re uired Sign-in log and pen Watch Table and chair (may be borrowed from the CECC/DNPEC area)

CECC/DNPEC Emergency Team identification cards Visitor identification cards Instructions

1. When notified that the CECC/DNPEC is to be activated, immediately report to the CECC Director, room 140, Chestnut Street Tower II.

2. If occupied for other uses, clear conference room 130.

3. Lock doors 1, 2, and 3 (see attachment 1).

Set up the Sign-in Station in the hallway outside door 1.

5. Obtain the CECC/DNPEC Emergency Team identification cards from the CECC cabinet (Operations Duty Specialist (ODS) has key).

6. Date and number the first sheet of the Sign-in Log and request all TVA CECC/DNPEC personnel already working in the area to sign the log. Issue each emergency team member their identification card.

All visitors must leave the area unless authorized to remain by the CECC Director, REP staff, DNPEC Director, or Plant Communicator.

7. CECC/DNPEC Emergency Team personnel (as identified by TVA photograph identification cards designated "CHATT.-RADIOLOGICAL EMERGENCY TEAM") are authorized unlimited access to the CECC/DNPEC.

8. All other personnel requesting access to the CECC/DNPEC must be authorized by one of the following CECC/DNPEC staff members:

CECC Director REP staff DNPEC Director Plant Communicator

Revision

CECC-IPD IP-12 Attachment 2 Page 2 of 2 Rev. 1

9. Each person entering the CECC/DNPEC area must sign the log before entering.

10. Each person leaving the CECC/DNPEC area must surrender their identification card or visitor badge and note the time on the sign-in roster."

11. Since it is not prudent for TVA to issue identification badges to all personnel within TVA and situations may arise in which other TVA, Federal, State, local, or private organizations may be r'equired in the CECC/DNPEC complex for an extended period, an access list of the personnel, signed by the CECC Director, will be provided to the Public Safety Officer as necessary. Personnel on the access,list will be issued a visitor's badge upon presenting appropriate personal identification.

12. Should the emergency situation be of a nature that significant response from the Nuclear Regulatory Commission (NRC) is expected, additional secure office areas may be required. The CECC Director will direct the Public Safety Officers to secure the area, labeled "Additional Office Area" on attachment 1, unlock door 2, and lock the door leading from the "Additional Office Area" to the stairwell. The area will then become part, of the restricted area and subject to the same access control as the CECC/DNPEC area.

>"Revision

CECC-IPD XP-13 INCLEHENT WEATHER PROCEDURE Prepared By: W. E. We b, Jr.

Approved By:

Date:

Rev. No. Date I(ev i.sed I'a~.os 0

FE8~61 4 1. 3 The last page of this procedure is number 3

~ s 0

CECC-IPD IP-13 Page 1 of 3 Rev. 1 INCLEMENT WEATHER PROCEDURE 1.0 PURPOSE

'o provide a pickup service for key emergency personnel who may be stranded because of inclement weather. and to provide lodging

"-and meals as necessary.

2.0 SCOPE

"'his procedure provides instructions for the Public Safety Service (PSS) and the Division of Nuclear Power (NUC PR),

Management Services Staff (MSS), to implement the inclement weather plan.

3.0 REFERENCES

None.

4.0 ABBREVIATIONS AND DEFINITIONS None.

5.0 RESPONSIBILITIES The CECC Director is responsible for initiating the inclement weather plan by notifying the PSS Area Chief and the MSS supervisor. The PSS Area Chief is responsible for, providing a pickup service for key emergency center personnel during the period of inclement weather. The MSS supervisor is responsible for reserving a block of rooms at a'ocal hotel/motel for use by key individuals.

6.0 PROCEDURE RE UIREMENTS 1

6.1 The Radiological Emergency Preparedness Section shall advise the CECC Director as soon as possible of impending inclement weather conditions, i.e., snow, sleet, or ice, in the immediate area.

I 6.2 The CECC Director or his representative shall contact the PSS Area Chief, the MSS supervisor, and the Operations Duty Specialist (ODS) and request that the inclement weather plan be implemented.

6.3 Public Safet Service 6.3.1 The PSS Area Chief will notify the transportation services garage and reserve two 4-wheel drive vehicles. If 4-wheel drive vehicles are not available, two cars supplied wi.th

~ tire chains will be reserved.

"-Revisi'on

CECC-IPD IP-13 Page 2 of 3 Rev. 0 6.3.2 The PSS Area Chief will assign two PSS officers to drive the vehicles.

6.3.3 The PSS officers will be authorized to drive the vehicles to their residences for official business only. They will be responsible for having the tire chains installed if the weather deteriorates where they would be required.

6.3 ' The PSS officers may remain on standby status until relieved by another officer or until the inclement weather plan has been canceled. Standby status means the officer will remain where he can be reached by phone.

6.3.5 Expenses incurred for operation of the vehicles and extra pay for the PSS officers for actual work performed will be paid by NUC PR, 6.3.6 The CECC Director shall provide the PSS Area Chief area maps and addresses of key individuals that might need a ride to the emergency center.

6.3.7 The ODS will call the PSS officers and inform them of individuals requiring transportation and their location during an emergency situation.

6.3.8 When notified, the PSS officers will pick up the emergency personnel and transport them to the CECC.

6.3.9 Upon arrival at the CECC, the PSS officers will remain until released by the CECC Director or dispatched by the ODS to pick up additional personnel.

6.3.10 The CECC Director or his representative will contact the PSS Area Chief and cancel the inclement weather plan when the vehicles are no longer required.

6.3.11 The PSS Area Chief will return the vehicles to the transportation garage and the PSS officers will be returned to regular duties.

6.4 ODS 6.4.1 The ODS should notify PSS at extension 3408 and give the PS(

dispatcher the name of the person to be picked up, his location, and a phone number where the person can be reached, if possible.

These arrangements should be made only as time permits. Prompt notification of emergency personnel remains as the first priority.

"2-

CECC-IPD IP-13 Page 3 of 3

~

~ Rev.

6.4.2 Only members of the CECC/DNPEC staff who are stranded or are unable to respond to a nuclear plant emergency because of the weather will be picked up. All other personnel requesting this service must be specifically authorized by the CECC Director.

6.5 Mana ement Services Staff The MSS shall make reservations for six rooms (double) at a

'"hotel/motel within walking distance of the CECC and provide meals as necessary.

6.5.2 The CECC Director shall authorize key personnel to occupy Lhese rooms if the individual feels it is necessary. Key personnel are those individuals who must be immediately available 'should an emergency occur.

"-Revision 0

REP-IPD CECC - IP-14 TVA BOARD AND GENERAI. MANAGER NOTIFICATION PROCEDURE FOR ALL CLASSES OF RADIOLOGICAL EMERGENCIES Prepared By: W. E. Webb Jr.

Approved By:

Date:

O OCT 96 882 The last page of this procedure is Number 2

CECC-IPD Page 1 of 2 IP-14 Rev. 0 TVA BOARD AND GENERAL MANAGER NOTIFICATION PROCEDURE FOR ALL CLASSES OF RADIOLOGICAL EMERGENCIES 1.0 . PURPOSE This purpose is designed to provide the necessary communication link within TVA for high-level government officials at the Federal and State levels during radiological emergencies. It also provides for the Board and General Manager interface with the radiological emergency organization. This procedures is not intended to cover radiological emergencies resulting from national emergencies or acts of war which require implementation of the TVA Emergency Preparedness Plan.

2.0 SCOPE This procedure designates a spokesperson for the TVA Board and provides guidance on his specific responsibilities during radio-logical emergency conditions. It also provides specific expected locations and notification procedures for the Board spokesperson.

3.0 REFERENCES

None.

4.0 ABBREVIATIONS AND DEFINITIONS Board spokesperson - Used to refer to the TVA Board spokesperson or his designated alternate.

CECC - Central Emergency Control Center.

KHC - Knoxvill.e Emergency CenLer.

5.0 RESPONSIBILITIES In the event of a serious radiological emergency invo1ving TVA facilities, the TVA radiological emergency response organization is responsible for overall management of the emergency response, for keeping the Board spokesperson or his designated alternate (hereinafter referred to as "Board spokesperson") informed of plant and environmental conditions, and, when the time permits, for consulting with them on major decisions. Communications with high-leve1 government officials (e.g., President, Governors, NRC Commissioner) on the status of the emergency will be conducted as necessary by the Board spokesperson during the emergency.

CECC-IPD Page 2 of 2 IP-14 Rev. 0 6.0 PROCEDURE RE UIREMENTS 6.1 Initial notification of the General Manager and the Board will be made by the Director of Information or his representative. Noti-fication of the Board spokesperson shall be in accordance with the order specified in the Radiological Emergency Notification Directory.

6.2 The following persons, in the order listed, are designated to speak for TVA in communications with high-level government officials relative to radiological emergency matters.

1. C. H. Dean, Jr.

2. S. David Freeman

3. Richard M. Freeman

4. William F. Willis

5. H. G. Parris

6. CECC Director The Board spokesperson is specified to be the first person listed who is present in the vicinity of Knoxville or Chattanooga. That person shall be responsible as Board spokesperson until such time as the Chairman, or a higher alternate relieves him.

When notified, the Board spokesperson will ensure that all other alternates are informed that he is acting as Board spokesperson and that all appropriate calls are referred to his number.

6.3 When notified of an emergency situation, the Board spokespqrsqn acts as follows for the specific emergency categories:

Notification of Unusual Event - The Board spokesperson is kept informed of the situation by the Director of Information. No further action is required at this point.

Alert - The Board spokesperson may choose to remain where he is or go to the KEC. If outside the KEC, the Director of Information or his representative will keep him informed of the situation. If at the KEC, the Board spokesperson will be kept apprised of the situation through the updates from the KEC Director and through periodic situation assessments by CECC, Division of Nuclear Power (NUC PR) and Division of Occupational Health and Safety (OH 8 S) representatives. Updates in all cases will take place hourly and when significant changes occur.

Site and General Emer encies - The Board spokesperson will relocate to the CECC in Chattanooga.

While at the CECC, the Board spokesperson will receive briefings on plant conditions from the CECC NUC PR representative, and on offsite environmental conditions from the CECC OHMS representative.

Communications and visits from high-level government officials will be referred to and coordinated by the Board spokesperson.

. ~

REP-IPD CECC - IP-15 ABNORMAL EVENTS AT NUCLEAR PLANTS Prepared by:

W. R. Steverson Submitted by:

C W. Crawford Manager of'ower Informa ion Approved by:

Craven Crowell Director of Information

~

Date:

Rev. No. Date Revised Pa es SH'UK83

0 CECC-IPD IP-15 Index Page 1 of 1 Rev. 1 Information Office Procedures for Abnormal Events at Nuclear Plants rmzx Section Purpose= 1.0 Scope 2.0 References 3.0 Abbreviations and Definitions 4.0 Responsibilities and Staffing 5.0 Procedures - Occurrences That Do Not Require Activation of Near Site Press Center 6.0 Procedures - Occurrences That Require Activation of Near Site Media Center 7.0 Telephone Listings 8.0 Letters of Agreement, Contracts, Supporting Documentation, and Lists of Equipment Appendix A Diagram CECC Information Staff Appendix B Diagram BFNP NSMC Appendix C Diagram SNP NSMC Appendix D Diagram WBNP NSMC Appendix E

""~Log Sheets Appendix F

---Addendum

CECC-IPD IP-15 Page 1 of 15 Rev. 1 Information Office Procedures for Abnormal Events at Nuclear Plants 1.0 PURPOSE These procedures are designed as guidance for Information Office personnel and support personnel during an abnormal event at a TVA nuclear plant to ensure timely and accurate release of information to the public.

2.0 SCOPE These procedures cover anticipated requirements for the Information Office and support personnel during abnormal conditions at TVA nuclear plants and supplement the REP and IPDs of NUC PR. Because of the character of news and of media/public interest, it is impossible to include procedures for every event that might occur.

In that respect, these procedures do not cover all actions that should be taken before, during, and after an incident, but rather are'designed to serve as a general guideline to provide consistency to Information Office practices during an abnormal"event at a TVA nuclear plant.

Much flexibility is built into these procedures. The procedures need not be followed exactly as long as the spirit and purpose are met: It is noted that media interest--not necessarily the seriousness of the event--may dictate actions by the Information Office. 4

3.0 REFERENCES

REP and all IPDs.

4.0 ABBREVIATIONS AND DEFINITIONS CECC - Central Emergency Control Center (Chattanooga)

CECC Information Staff - The staff stationed in the CECC that works, under the direction of the Director of Information during a nuclear event. It consists mostly of members of the Power Information Staff with support from employees of the Office of Power and NUC PR.

DNPEC - Division of Nuclear Power Emergency Center 1

EOC - The Emergency Operations Center for the State in which the nuclear plant is located.

'EMA - Federal Emergency Management Agency IPD - Implementing Procedures Document KEC - Knoxville Emergency Center

CECC-IPD IP-15 Page 2 of 15 Rev. 1 NSMC >> Near-Site Media Center News Desk - The office of the Knoxville Information Office that serves on a day-to-day basis as the primary contact point for the news media.

NUC PR - Division of Nuclear Power NRC - Nuclear Regulatory Commission ODS - Operations Duty Specialist Q.S A - Question and Answer REP - Radiological Emergency Plan 5.0 RESPONSlalr.lTIES AND STAFZING 5.1 The overall responsibility for handling information requirements for any nuclear event rests with the Director of Information. He may use his own discretion to determine the responsibilities for individual employees and their duties described in the REP and in the procedures in this document.

5.2 The TVA Information Office has the responsibility for providing the public and the news media with timely, accurate information on the event. The appropriate State Information Office, working with TVA, has the overall responsibility for public information regarding State activities, including such items as citizen evacuation and radiation monitoring away from the plant site.

5.3 At the= direction of the Director of Information, the Assistant Director of Information has overall supervisory responsibility over the information staffs involved in a nuclear event.

5,4 The Manager of Power serves as chief spokesman for TVA at media briefings. In his absence, the Deputy Manager of Power is the spokesman. In his absence, the Director of Information shall designate an appropriate spokesman.

5.5 When the CECC is activated, the Director of the CECC has overall responsibility for handling the nuclear emergency for TVA. He consults with the Director of Information on information matters, such as activation of the NSMC and appropriate times to conduct media briefings. He also has sole res onsibilit within the CECC for reviewin TVA news statements re ared b the CECC Information

<<Staff. However, if the situation dictates, the Director of

+Information or the Manager of Power can app'rove urgent news

~'statements.

-Revision

CECC-IPD IP-15 Page 3 of 15 Rev. 1 5.6 The Power Information Staff, with additional support provided by the Office of Power, is responsible for monitoring the situation from the Office of Power and the CECC. The staff writes all news

-statements and obtains review of the statements from the Office of Power, or when the CECC is activated, from the Director of the CECC. In addition, at the direction of the Director of Information, the Power Information Staff releases written statements to the news media and assists the Chattanooga media in covering the nuclear event.

'5.7 The Knoxville Information Office is responsible for the initial notification of the General Manager, Board of Directors, the Washington Office, the district administrator in whose area the plant is located, and other top TVA officials as required. The staff is also responsible for manning the News Desk and handling media inquiries during a nuclear incident. If the NSMC is activated, the staff will provide primary staffing for it.

5.8 The Broadcast Staff acts under the direction of the Director of Information and provides appropriate services to the news media.

If the NSMC is activated,'he staff is in charge of setting up, manning, and monitoring all audiovisual and broadcast equipment.

5.9 The Communication Services Staff provides, at the direction of the Director of Information, information to TVA employees about the event and assists the News Desk Staff.

5.10 The Citizen Action Office Staff serves as rumor control, handling nonmedia calls from the public and relaying information provided by the News Desk.

5.11 The Manager of Nuclear Information shall be responsible for reviewing and updating these procedures. Such reviews shall be made no less than annually. He is also responsible for ensuring the needed materials are available for the staffing'of the CECC Information Staff office.

5.12 The Information Office Field Spokesman for the Office of Agricultural and Chemical Development, is responsible for monitoring the situation from the MSEC, and reports to that facility if the Director of Information decides it is necessary.

5. 13 The Information Office Field Spokesman for the Office of Engineering Design and Construction, is responsible for monitoring the situation from the KEC and reports to that facility Information decides it is necessary.

if the Director of 5.14 The Plant Information Officer is responsible for providing informa-tion to the Power Information Staff and the Information Office as required. During the initial hours of an emergency, he reports to the plant if the plant's emergency response plan is activated. He is responsible for notifying the appropriate State agencies of any

+Revision

0 0

CECC"IPD IP-15 Page 4 of 15 Rev. 1 planned news release. At the direction of the Director of Informa-tion, he takes action to activate the NSMC and provides assistance to the local media until the News Desk Staff from Knoxvil,le arrives on the scene. He also is responsible for ensuring the needed materials and equipment are available for the staffing of the plant NSMC and for updating emergency media kits and other 'emergency information material at least annually.

r 5.14.1 Once the NSMC is in operation and the CECC fully activated, the Plant Information Officer reports to the following location:

5..14.1.1 The Browns Ferry Information Officer reports to the Alabama EOC to serve as a liason between the Information Office and the State officials. He works under the supervision of the Director of the NSMC. In the event of an emergency at Sequoyah or Watts Bar, he may be directed to report to the Tennessee EOC in Nashville.

5.14.1.2 The Sequoyah Information Officer reports to the CECC and joins the CECC Information Staff in preparing written news statements of the event.

5.14.1.3 The Watts Bar Information Officer reports to the NSMC and assists the Director of the NSMC.

5. 15 If the NSMC is fully activated, the Director of the CECC shall desig-nate two persons to provide technical information and advice to the Manager of Power and the Director of Information. These persons shall be designated Technical Advisor--Plant Operations and Technical Advisor--Radiological Health. They shall be stationed at the NSMC.

5.-16 If the CECC is activated, the CECC Director shall designate one person to serve as a technical advisor to the CECC Information Staff. That person shall ensure the timely flow of information from the CECC/DNPEC to the CECC Information Staff, advise the Information Staff writers, and be available for telephone consul-tations with the Manager of Power and other NSMC personnel to offer advice when requested.

5. 17 Depending on the severity of the incident; the. Information Office may have to provide coverage on a 24-hour basis for an extended period. The Director of Information, in consultation with the

-Assistant Director of Information, will designate the specific assignments for Information Office personnel and their shifts.

As a rule, during the emergency, persons will work 12-hour shifts.

5.18 Assistance from other offices and divisions will be requested as needed.

6.0 PROCEDURES - Occurrences that do not require activation of the NSMC.

+Revision

e CECC-IPD IP-15 Page 5 of 15 Rev. 1 6.1 TVA Nuclear Information Policy is to fully inform the news media and the public as soon as possible of any unusual happenings at nuclear plants. Events that may not be included in the REP could be considered newsworthy and, therefore, fall within these procedures.

6.2 Initial Notification 6.2.1 The Plant Information Officer is kept apprised by the 'Plant Super-K intendent or his designee of any unusual happenings't the plant.

In addition, NUC PR keeps the Manager of Nuclear Information and the Manager of Power Information informed on a day-to-day basis of happenings at the plant. The ODS of the Office of Power also notifies the Power Information Duty Officer of any major change in status of the plant.

6.2.2, The Plant Information Officer notifies the Manager of Nuclear Informa-tion, the Manager of Power Information, or the Power Information Duty Officer, in that order, who in turn notifies the Knoxville Information Office. The order for notifying the Knoxville Information Office is as follows:

l. Assistant Director of Information 2, Director of Information

3. Manager of Media Relations

4. Manager of News Desk

5. Information Office Duty Officer 6.2.3 Depending on the nature of the event, those notified will. decide if immediate notification of the General Manager, Board of Directors, and the news media is necessary.

6.2.4 If immediate notification of the news media is determined to be necessary, the Power Information Staff will prepare a statement that will be reviewed, if at all possible, by NUC PR and the Manager of Power. Then it will be transmitted to Knoxville for release in a manner determined appropriate by the Director of Information. If review is not possible or practical, the Manager of Power Information shall assume responsibility for approving .

the release for the Office of Power.

6.2.5 In the event of a radiological emergency away from the plant site, the Director of Information will designate an Information Office Staff member to go to the'scene, if that is deemed necessary.

6.3 CECC If the CECC is activated, the Power Information Staff will activate the CECC Information Staff and generate news statements there.

Once prepared, the news statements will be reviewed and approved by the Director of the CECC, and transmitted to Knoxville for release.

-Revision

CECC-IPD IP-15 Page 6 of 15 Rev. 1 The following staffing is recommended for full activation of the CECC Information Staff (lesser levels of staffing should be made at the determination of the CECC Information Director). Staffing for each 12-hour shift is as follows:

6.3.1 CECC information Director--Stationed in the CECC near the Director of the CECC. He has overall responsibility for public information matters in the CECC and supervises the CECC information staff. He consults with the CECC Director, the Manager of Power and the Director of Information to, make sure information is released in an accurate, objective, and timely manner.

6.3.2 Supervisor--At the direction of the CECC Information Director, he oversees activities of the CECC Information Office. Works closely with the Director of the CECC and the Director of the DNPEC to monitor the accident. In consultation with the Director of the NSMC, determines when to prepare news statements and supervises and approves their writing. Obtains clearance from the Director of the CECC of all written statements. Schedules staff assignments for around-the-clock staffing. Consults with NSMC management to schedule briefings, etc.

6.3.3 Technical Advisor--Provided by NUC PR, he acts as liaison between the CECC Information Office and the CECC managers. Provides technical assistance to writers working on news statements and keeps the CECC Information Office apprised of all developments concerning the accident.

6.3.4 Writers (2)--As assigned by the CECC Information Office Supervisor, gather information from the CECC officers and the technic'al advisor and prepare written statements based on that information. May be called upon to perform other duties as necessary.

6.3.5 NRC-State Coordinator--Once news statements have been approved by the Director of the CECC, the NRC-State Coordinator ensures their prompt transmittal to the proper State and NRC officials for review.

When questions or changes are called for, he relates that information to the writers and supervisors. He also works with the State and NRC to receive information about public information announcements

>those agencies are preparing. He also provides released news

statements to the appropriate plant Technical Support Center (TSC)

":for information. These duties may,

>:two people.

if necessary, be divided among 6.3 ' Local Media Coordinator--Before activation of the NSMC, works with local news media to keep them apprised of developments at the plant and the CECC. Also serves to answer media questions about opera-tions of the CECC once the NSMC is activated and performs other duties as necessary.

+Revision

CECC-IPD IP-15 Page 7.of 15 Rev. 1 6.3.7 Q 8 A Editor/NSMC Coordinator--Interfaces with NSMC information officers to gather any questions raised by the media about develop-ments that can't be answered at the NSMC and relays those questions back to the proper person. Monitors the flow and adequacy of information between the NSMC and the CECC Information Office.

6.3.8 Clerks/Secretaries--The number of clerks and secretaries needed in the CECC Information Office will be determined by the CECC Informa-tion Office Supervisor. At maximum levels they include:

6.3.8.1 Jacquard Clerks (2)--They type into a Jacquard all news releases and follow their transmittal to the proper sources.

6.3.8.2 Telecopier Clerk--Handles all telecopier transmittals from the office.

6.3.8.3 Telephone Clerk--Answers incoming telephone calls and performs other jobs as directed by the supervisor.

6.3.8.4 , Q 6 A Clerk--Assists the Q 6 A Editor/NSMC Coordinator in answering questions and coordinating activities with the NSMC.

6.4 For non-REP items that are being announced to the media by the Informa-tion Office, the Plant Information Officer has initial responsibility to inform the appropriate State officials, as outlined in the letters of agreement in the appendix, If the Plant Information Officer is not available, the Manager of Nuclear Information will assume that duty; in his absence, the Manager of Power Information; and in his absence, the Power Information Staff Duty Officer. Once the CECC is activated, responsibility for keeping the State Information Officer informed shifts to the CECC Information Staff State Coordinator.

6.5 -"The Assistant Director of Information or his designee on the Knoxville News Desk, has the responsibility of coordinating news releases with the NRC public affairs office until such time as the CECC is activated. Once the CECC is activated, responsibility for keeping the NRC informed shifts to the CECC Information Staff NRC Coordinator.

6.6 The News Desk shall serve as the central control center for Informa-tion Office activities. Depending on the severity of the event and the number of media calls, it will be staffed as necessary, with the determination being made by the Director of Information and the Assistant Director of Information. The News Desk shall notify at a minimum the following:

1. The TVA Board and General Manager.

2. Any senior Information Office employee not already notified.

3. The NRC public affairs office (until such time as the CECC is activated).

4. The major wire services, and media in the vicinity of the affected plant.

5. Any others deemed necessary by the Director of Information.

"-Revision

II CECC-IPD IP"15 Page 8 of 15 Rev. 1 As a general rule, the News Desk should be activated whenever an Alert or higher classification of event is declared, and when the CECC is activated. The first statement prepared by the Power Information Staff and issued by the News Desk should be brief and should be released with all possible speed. It should acknowledge that an event. has occurred, and that additional information will be forthcoming.

6.7 Neither in print nor orally will Information Office personnel speculate on the cause or consequences of the incident.

6.8 Upon notification that the News Desk has been activated, the Chief of the Broadcast Staff will begin notifying his staff. The staff will begin making preparations to transport audiovisual equipment and personnel to the NSMC in the event its activation is ordered. The staff also will provide assistance to the News Desk in handling broadcast media requests.

6.9 Based on the severity of the incident, the Director of Information may order the staffing of the KEC and the MSEC. However, such staffing is not necessary for the Information Office to perform its duties. The Director of Information may also deem it necessary to request assistance from the Employee Communications Staff and from the Citizen Action Office to provide employee information and rumor control.

6.io As calls come into the News Desk, they will be handled by News Desk personnel in the normal manner. Details will be provided from the prereleased news statements. If the caller wants additional informa-tion, efforts will be made to provide that information. The CECC Information Staff can be contacted by the News Desk for those additional details. Inquiries regarding offsite evacuation or other State matters will be referred to the appropriate State agencies.

6.11 Updated news statements shall be issued periodically as needed. At a minimum, statements should be updated at least every two hours, if only to report that "no change" has occurred since the last statement.

6.12 The nuclear plant status report tape and news line tapes should be updated by News Desk personnel each time a new statement is released.

All new statements should be given to the Citizen Action Office for rumor control purposes.

6.i3 Requests by the media for personal interviews or for tours of TVA facilities will be handled through the News Desk. The requests will be coordinated with the Director of the CECC and Plant Superintendent.

7.0 PROCEDURES - Occurrences that require activation of the NSMC.

CECC-IPD IP-15 Page 9 of 15 Rev. 1, 7.1 The procedures listed in the previous section will continue as long as necessary. However, if the condition of the plant worsens, or if media interest becomes so intense that, in the judgment of the Director of Information, it ordered cannot be properly handled from the News Desk, the NSMC will be activated.

7.2 The NSMC for Browns Ferry Nuclear Plant is the Calhoun Community College on U.S. 31 North near Decatur; the NSMC for the Sequoyah Nuclear Plant is the downtown Chattanooga YMCA; the NSMC for the Watts Bar Nuclear Plant is the Sweetwater Quality Inn on I-75.

7.3 As a general goal, the NSMC at Sequoyah and Watts Bar should be operational no less than four hours after the Director of Information orders them activated. The Browns Ferry NSMC should be operational no less than six hours after its activation is ordered.

7.4 Prior to ordering activation of the NSMC, the Director of Information will consult with the Director of the CECC and appropriate State information officers, if feasible.

7.5 Equipment for the NSMC will be preboxed and ready for shipment. It is stored in Knoxville and Chattanooga. An inventor'y is listed in the appendix.

7.6 Each State affected by the accident has agreed to participate with TVA in the NSMC, as has the NRC. Once the Director of Information orders activation of the NSMC, the Information Office person who at, that time is coordinating information releases with those agencies shall notify those agencies that the NSMC is being activated and invite them to dispatch personnel to staff it.

7.7 The Plant Information Officer shall notify the owners/operators of the building of the NSMC to make arrangements for its use. Contracts with the owners are included in the appendix. He shall also ensure that South Central Bell is notified to activate telephone lines to the NSMC.

7.8 The Assistant Director of Information will determine who will report to the NSMC. He will make arrangements to have all the equipment that is stored in Knoxville shipped immediately to the center. The following is a listing of the maximum expected staffing of the NSMC.

It is anticipated that in all but the most severe case, less staffing will be acceptable. Staffing levels will be determined by the Assistant Director of Information, who is in charge of the NSMC.

7.8.1 -Chief Spokesman--The Manager of Power or, in his absence, the Deputy

<Manager of Power or another designee. This person serves as the Chief Spokesman for TVA during all news briefings. He consults with officials in the CECC and the TVA Director of Information to coor-dinate all statements and provide correct information. He is available to'nswer specific media questions when formal briefings are not being held.

Revision

CECC-IPD IP-15 Page 10 of 15 Rev. 1 Director of Information--The Director of Information has the responsibility for all information activities involving a nuclear emergency. He provides directions to both the Director of the NSMC and the CECC Information Office. He apprises the General Manager and the Board of Directors on all information matters. He consults with the Chief Spokesman before all briefings, and participates in those briefings, when necessary, with the Chief Spokesman.

Director of the NSMC--Is in charge of all activities at the NSMC. He supervises all Information Office personnel and support personnel assigned to the center. He chairs all staff meetings at the NSMC, and ensures that the needs of the State, NRC, and FEMA are met.

He serves as the chief point of contact between the NSMC and the CECC Information Office.

Audiovisual Coordinator--The Chief of the Broadcast Staff or his designee. This person is responsible for ensuring the media briefing room is adequately equipped to accommodate the needs of broadcast media and the recording of all news briefings.

The Audiovisual Coordinator will see to it that an adequate number of personnel from the Broadcast Staff are available to perform the duties described.

Associate Director of the NSMC--Serves at the instruction of the Director of the NSMC, with primary responsibility in handling media needs and making sure proper arrangements are made for timely, comprehensive media briefings. Is in charge of building arrange-ments for the NSMC and coordinates activities of the TVA Broadcast Staff to meet media needs. Coordinates schedules of personnel assigned to NSMC and acts as NSMC "historian," keeping a log of all major events at the center.

Intergovernmental Affairs Coordinator--Serves at the instruction of the Director of the NSMC, with primary duties to coordinate NSMC operations with TEMA, NRC, and FEMA. Is responsible for ensuring that representatives from those agencies at the NSMC are kept abreast of all developments, shown copies of all written TVA news releases, and that TVA is shown copies of all written news releases of those agencies. Coordinates joint conferences of all agencies prior to,:

formal briefings.

Technical Advisor--Plant Operations--Serves at the direction of the Director of the NSMC and acts as an assistant to the Chief Spokesman.

In both staff conferences and formal briefings, advises the Chief Spokesman on technical matters dealing with the design and operation of the affected nuclear plant. At the direction of the Chief Spokesman and Director of Information, answers media questions dealing with technical matters. Is available for informal background briefing sessions with the media.

0 CECC-IPD IP-15 Page ll of 15 Rev. 1 Technical Advisor--Radiological Health--Serves at the direction of the Director of the NSMC and acts as an assistant to the Chief Spokesman. In both staff conferences and formal briefings, advises the Chief Spokesman on technical matters dealing with the health and safety aspects of radiation. Works closely with State representatives to give out information on radiation releases from the plant. At the direction of the Chief Spokesman and Director of information, answers media questions dealing with technical matters.

Is available for informal background briefings with the media.

Information Officers (4 Positions)--Serve at the direction of the NSMC Director. Handle telephone calls from the media to the NSMC.

Relay information to Knoxville and Washington. Answer questions from members of the media present. Assist in writing and distri-buting news releases; coordinating information with the Citizen Action Line, which will serve as the public "rumor control"; and assisting in other activities as instructed by the Director of the NSMC.

Q 8 A Coordinator--Coordinates questions from the media that cannot be answered by the information officers, technical advisors, or Chief Spokesman. Dispatches those questions to the CECC Information Office and makes sure answers are provided and distributed to the reporter.

Artist--Serves the Chief Spokesman and the technical advisors by providing sketches that might be needed during media briefings.

Logistics Coordinator--In charge of all logistics arrangements for the NSMC, including staff transportation and lodging, equipment movement and procurement, media shuttle service between the NSMC and the plant, supplying meals for all persons in the NSMC, getting cash advances for personnel who have to stay overnight, etc. Also works with the media to ensure that out-of-town reporters have adequate accommodations.

Receptionist--Works at the entrance to the NSMC. Registers members of the media who arrive and issues credentials. Records the telephone numbers of the reporters on printed forms so they can be located in case of an emergency. Distributes press packages.

Clerks-Secretaries--The number of clerks and secretaries needed at the NSMC will be determined by the Director of the NSMC. They will include:

l. One secretary to operate the Jacquard computer and printer.

2. One secretary to operate the fastfax telecopier machine.

3. One clerk to assist the Q 6 A Coordinator.

4. Two clerks to answer telephones, take messages, and route calls.

5. One chief clerk assigned to the Director of Information and the Director of the NSMC.

Transportation Coordinator--Works with Logistics Coordinator to provide media transportation to and from the plant. Also provides staff transportation as needed.

0 CECC-IPD IP-15 Page 12 of 15 Rev. 1 7.9 The Director of the NSMC may call upon support personnel from other TVA offices and divisions as necessary to ensure adequate staffing of the NSMC.

7.10 Throughout the activation of the NSMC, the News Desk in Knoxville will continue to be operated, as will all auxiliary operations, such as the Citizen Action Line. The Director of Information shall determine the necessary staffing levels of these operations.

7.11 The Director of Information may dispatch an Information Office representative to the plant site. That person would be stationed at or near Public Safety Service roadblocks to the plant to meet with any media that attempts to gain access to the plant area.

7. 12 The NSMC Transportation Coordinator will, at the direction of the Director of the NSMC, provide.van shuttle service for the media between the NSMC and the plant. Such service shall be under control of the Information Office and shall allow the media to make pictures and conduct live news spots from the plant area.

7.13 Briefings at the NSMC will be conducted whenever necessary, but at a minimum of 2 every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . State, NRC, and FEMA representatives shall participate fully in the briefings, if they so desire. News releases shall be distributed at the NSMC whenever necessary.

7.14 The NSMC shall operate for the duration of the emergency, or until it iswaned determined by the Director to such an extent that of Information that media interest operation of the center is no has longer necessary. It is possible that because of continuing media interest after the emergency, the NSMC could be kept open for several days after the specific emergency has ended.

8.0 TELEPHONE LISTINGS 8.1 CECC Information Office Staff.

CECC Information Director (Crawford) 751-0222'223'235 CECC Information Technical Advisor CECC Information Supervisor (Steverson)

Supervisor'.s Secretary ~

'230'233~

Writers ' Desks ~

NRC Coordinator 0236'231~

State Coordinator I,ocal Media Coordinator 0209'These are Dimension telephone numbers and can be reached from other Dimension telephones by dialing the last three digits.

CECC"IPD IP-15 Page 13 of 15 Rev. 1 QSA Coordinator Panafax 3000 telecopier Verify telecopy 0224'234'230'67-8222 Jacquard 105 computer 8.2 SNP - Near-Site Media Center (Chattanoo a YMCA)

Supervisor (Cadotte)- 751-0280*

H. G. Parris (Lee Sheppeard) 265-0527 TVA Staff =-1 265-0643 TVA Staff. 2 265-0766 TVA Staff 3 265-0919 TVA Staff 4 756-8067 TVA Staff 5 756-8056 Panafax 3000 telecopier 756-8023 Verify 756"8056 Jacquard 105 computer 756-0686 TVA Broadcast 1 756-0234 TVA Broadcast 2 265-0341 NRC Staff Room 265-0454 TEMA Staff Room (Inman) 751-0279'65-6339 TEMA Staff 1 TEMA-Staff 2 265-6348 TEMA Staff .3 265-0053 TEMA Staff 4 265-0185

~These are Dimension telephone numbers and can be reached from other Dimension telephones by dialing the last three digits.

CECC-IPD IP-15 Page 14 of 15 Rev. 1 8.3 BPNP - Near-Site Media Center (Calhoun State Communit Colle e Limestone Count Tele hone Numbers (205) 355-8055 (205) 355-8073 (205) 355-8043 (205) 355-8046 8.4 State of Tennessee TEMA Emergency Center, Nashville 615-741-5181 Public Information Officer (John Parrish) 1-800-262-3400 TEMA PIO Staff, Nashville 615-741-0001 TEMA Panafax Telecopier, Nashville 615-741-0002 8.5 State of Alabama f

Lauderdale County Civil Defense 766-4201 Lawrence County Civil Defense 974-7641 Limestone County Civil Defense 232-2631 Morgan County Civil Defense 350-.9600 Ext. 227 8.6 Other Numbers Power Information Staff, Chattanooga 751"2864 News Desk, Knoxville 6000-K or 1-800-251-9438 NRC Public Affairs, Atlanta 404-221-4503 NRC Telecopier 404-242-4449

1 I

CECC-IPD IP-15 Page 15 of 15 Rev. 1 TVA Citizen Action Line, Knoxville 1-800-251-9242 TVA Nuclear Status Tape, Knoxville 1-800-251-9427 Nuclear Regulatory Commission, Public (404) 221-4503 Affairs, Atlanta Federal Emergency Management Agency, Atlanta (404) 881-2391

0 REP-IPD CECC IP-16 NUC PR EMERGENCY DUTY OFFICER PROCEDURE FOR ALERT SITE AREA EMERGENCY 'AND GENERAL 'ETKRGENCY Prepared by: B. K. rks Approved by:

Date: Ma c 28 Rev. No. Date Revised 'Pa es 0 All B'AV 35 ~984 Cover Sheet; pg. 2 HOV ) 3 '84 Coversheet, P. 2

~ V ~ V CECC-IPD IP-16 Page 2 of 2 0 6. 0 PROCEDURE RE UIREMENTS Upon Rev. 2 the declaration of an Alert, Site Area Emergency, or General Emergency, the EDO shall perform the following:

(Initials/Time) 6.1 Contact the Alternate EDO, provide the initial information, and request that he/she contact the following and request they report to the CECC. The EDO will then proceed to the CECC/DNPEC.

Power Information Staff Duty Officer W. E. Webb B. K. Marks T. E. Adkins A. A. Schenck H. B. Williamson L. N. Haik 6.2 The Alternate EDO will proceed to the CECC/DNPEC upon completion of the above notifications.

6.3 Should the EDO be unable to contact the alternate EDO, he/she shall perform the following notifications, then proceed to the CECC/DNPEC.

Power Information Staff Duty Officer

+en Upon arrival at the center, the EDO may solicit assistance from the ODS or others as necessary to notify the remaining staff.

->Deletion

4 T ~

~>

l 0

I

ML18026B218

Text

1.0 INTRODUCTION

SUMMARY

12.0 REFERENCES

SUMMARY

Dear Dr. Craig:

3.0 REFERENCES

3.0 REFERENCES

3.0 REFERENCES

3.0 REFERENCES

3.0 REFERENCES

3.0 REFERENCES

3.0 REFERENCES

3.0 REFERENCES

3.0 REFERENCES

3.0 REFERENCES

3.0 REFERENCES

3.0 REFERENCES

3.0 REFERENCES

Navigation menu

Search