RS-16-248, Redacted Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix E - Requirements Resulting from TMI-2 Accident
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B/B-UFSAR
APPENDIX E REQUIREMENTS RESULTING FROM TMI-2 ACCIDENT
B/B-UFSAR E.0-i APPENDIX E REQUIREMENTS RESULTING FROM TMI-2 ACCIDENT TABLE OF CONTENTS
PAGE E.0 List of TMI Ac tion Plan Requirem ents Which Are Not Applicable to Byron/Braidwood Stations E.0-1 E.l Shift Technical Advisor - I.A.l.l E.l-1 E.2 Shift Supervisor Adm inistrative Duties - I.A.1.2 E.2-1 E.3 Shift Manning - I.A.1.3 E.3-1 E.4 Immediate Upgrading of RO and SRO Training and Qualifications - I.A.2.1 E.4-1 E.5 Administration of Training Programs for Licensed Operators - I.A.2.3 E.5-1 E.6 Revise Scope a nd Criteria for Licensing Examina- tions - Simulator Exams (Part 3) - I.A.3.1 E.6-1 E.7 Evaluation of Organi zation and Management Improvements of Near-T erm Operating License Applicants - I.B.1.2 E.7-1 E.8 Guidance for the Eva luation and Development of Procedures for Trans ients and Accidents - I.C.l E.8-1 E.9 Shift and Relief Turnover Procedures - I.C.2 E.9-1 E.10 Shift Supervisor Respons ibilities - I.C.3 E.10-1 E.ll Control Room A ccess - I.C.4 E.ll-1 E.12 Procedures for F eedback of Operating Experience to Plant Staff - I.C.5 E.12-1 E.13 Verify Correct Perfo rmance of Operating Activities - I.C.6 E.13-1 E.14 NSSS Vendor Review of Procedures - I.C.7 E.14-1 E.15 Pilot Monitoring of Selected Emergency Procedures for N TOL - I.C.8 E.15-1 E.16 Control Room Design Reviews - I.D.l E.16-1 E.17 Plant Safety P arameters Display Console - I.D.2 E.17-1 E.18 Training During Preoperation and Low Power Testing Pr ogram - I.G.l E.18-1 E.19 Reactor Coolant System Vents - II.B.l E.19-1 E.20 Plant Shielding - II.B.2 E.20-1 E.21 Postaccident Sam pling - II.B.3 E.21-1 E.22 Training for Mitigating Core Damage -
II.B.4 E.22-1 E.23 Relief and Safety Va lve Test Requirements -
II.D.1 E.23-1 E.24 Direct Indication of Relief and Safety Valve Position - II.D.3 E.24-1 E.25 Auxiliary Feedwater System Evaluation -
II.E.1.1 E.25-1 E.26 Auxiliary Feedwater Sy stem Automatic Initiation and Flow Indication - II.E.1.2 E.26-1
B/B-UFSAR E.0-ii REVISION 4 - DECEMBER 1992 TABLE OF CONTENTS (Cont'd)
PAGE E.27 Emergency Power Supply for P ressurizer Heaters - II.E.3.1 E.27-1 E.28 Dedicated Hydrogen Penetrations - II.E.4.1 E.28-1 E.29 Containment Isolation De pendability - II.E.4.2 E.29-1 E.30 Additional Accident-Monitoring Instrumen- tation - II.F.1 E.30-1 E.31 Instrumentation for Detection of Inadequate Core Cooling - II.F.2 E.31-1 E.32 Emergency Power for Pressurizer Equipment - II.G.l E.32-1 E.33 Assurance of Proper ESF Functioning -
II.K.1.5 E.33-1 E.34 Safety-Related Syste m Operability Status Assurance - II.K.1.10 E.34-1 E.35 Trip Pressurizer Low-Level Bistables - II.K.1.17 E.35-1 E.43 Thermal Mechan ical Report - Effect of High- Pressure Injection on Vessel Integrity for Small-Break Loss-Of-Co olant With No Auxiliary Feedwater - II.K.2.13 E.43-1 E.47 Potential for Voiding in the Reactor Coolant System During Transients - II.K.2.17 E.47-1 E.48 Benchmark Analysis of Sequential Auxiliary Feedwater Flow - II.K.2.19 E.48-1 E.49 Installation and Tes ting of Automatic Power Operated Relief Valv e Isolation System - II.K.3.1 E.49-1 E.50 Report on Overall Sa fety Effect of Power- Operated Relief Valv e Isolation System -
II.K.3.2 E.50-1 E.51 Reporting SV and RV Failures and Challenges - II.K.3.3 E.51-1 E.52 Automatic Trip of Reactor Coolant Pumps During Loss-of-Coolant Accident - II.K.3.5 E.52-1 E.54 Proportional Integra l Derivative Controller Modification -
II.K.3.9 E.54-1 E.55 Anticipatory T rip Modification - II.K.3.10 E.55-1 E.56 Justification for Us e of Certain PORV's - II.K.3.11 E.56-1 E.57 Confirm Existence of Anticipatory Reactor Trip Upon Turbine Trip - II.K.3.12 E.57-1 E.61 Report on Outages of Emergency Core Cooling Systems Licensee Report and Proposed Technical Specification Changes - II.K
.3.17 E.61-1 E.66 Effect of Loss of Alternating Current Power on Pump Seals - II.K.3.25 E.66-1 E.69 Small Break An alysis Methods - II.K.3.30 E.69-1 E.70 Plant Specific C alculations to Show Compliance With 10 CFR 50.46 - II.K.3.31 E.70-1 B/B-UFSAR E.0-iii REVISION 1 - DECEMBER 1989 TABLE OF CONTENTS (Cont'd)
PAGE E.75 Upgrade Emergency Re sponse Facilities - III.A.1.2 E.75-1 E.76 Improving Licensee Emergency Preparedness - Long Term - III.A.2 E.76-1 E.77 Primary Coolant Sources Outside Containment - III.D.l.l E.77-1 E.78 In-plant Radiation Monitoring (Iodine) - III.D.3.3 E.78-1 E.79 Control Room Hab itability Requirements III.D.3.4 E.79-1 E.80 Training and Qualifi cation of Operations Personnel - (I.A.2.2 from NUREG-0660) E.80-1 E.81 Long Term Plan for U pgrading of Procedures - (I.C.9 from NU REG-0660) E.81-1 E.82 References E.82-1
B/B-UFSAR E.0-iv REVISION 8 - DECEMBER 2000 APPENDIX E REQUIREMENTS RESULTING FROM TMI-2 ACCIDENT LIST OF TABLES
NUMBER TITLE PAGE E.1-1 STA Selection Criteria E.1-3 E.17-1 Parameters Associated with Plant Function Monitoring E.17-9 E.17-2 Iconic Display Description E.17-10 E.17-3 Comparison of SP DS Safety Functions and Parameters with NUREG-0696, NUREG-0737, Supplement 1 and Westi nghouse Critic al Safety Functions E.17-15 E.20-1 Postaccident D ose Rates from Contained Sources E.20-7 E.20-2 Postaccident Doses for Essen tial Postaccident Paths E.20-8 E.30-1 Time Motion St udy for Vent Stack Effluent Grab Sample E.30-10 E.31-1 ICC Status as Availa ble to the Operator from ICC Instrumentation Trending E.31-23 E.75-1 Technical Support Ce nter HVAC System Equipment Parameters E.75-15 E.75-2 EOF and TSC Monitored Parameters E.75-20 E.75-3 Emergency Clas sification Levels E.75-22 E.75-4 Deleted
B/B-UFSAR E.0-v REVISION 8 - DECEMBER 2000 APPENDIX E REQUIREMENTS RESULTING FROM TMI-2 ACCIDENT LIST OF FIGURES
NUMBER TITLE E.7-1 Deleted E.17-1 Basic Ic onic Display E.17-2 Narrow R ange Display E.17-3 Wide R ange Display E-19-1 Reactor Vess el Head Vent System - Containment Building E.20-1 Postaccident Vital Areas E.20-2 Postaccident R adiation Zone Map 1 Ho ur After Accident -
Major Line Break E.20-3 Postaccident R adiation Zone Map 1 Da y After Accident -
Major Line Break E.20-4 Postaccident R adiation Zone Map 1 We ek After Accident -
Major Line Break E.20-5 Postaccident R adiation Zone Map 1 Ho ur After Accident -
No Line Break E.20-6 Postaccident R adiation Zone Map 1 Da y After Accident -
No Line Break E.20-7 Postaccident R adiation Zone Map 1 We ek After Accident -
No Line Break E.30-1 High Range Conta inment Radiation Detectors E.31-1 ICC Detection Instrument ation Sensors Processing and Display E.31-2 HJTC Sensor -
HJTC/Splash Shield E.31-3 Schematic of HJTC Probe E.31-4 HJTC P robe Assembly E.31-5 Probe Holder Assembly and Sensor Locations E.31-6 HJTC Holder Assembly Locations Reactor Vessel Plan E.31-7 HJTC Sensor Re sponse for a Repre sentative 4 in. (0.09 ft 2) Cold Leg Break E.31-8 Normal Operati ng Flow Pattern With Reactor Coolant Pumps On E.31-9 Core Exit Ther mocouple Core Locations E.31-10 Electrical D iagram of HJTC E.31-11 HJTC System Pr ocessing Configuration (One Channel Shown) E.47-1 Loop Reflux Illu stration Hydrogen Bubble E.47-2 Hydrogen Bubble Pressuri zed Secondary Side % CLD RX 1 = 5%, 2 = 10%, 3 = 20%
E.47-3 Hydrogen Bubble Depressurized Secondary Side % CLD RX 1 = 5%, 2 = 10%, 3 =
20%, 4 = 30%, 5 = 50% E.47-4 Loop Reflux Illustra tion Homogeneous Mixture
B/B-UFSAR E.0-vi REVISION 9 - DECEMBER 2002 LIST OF FIGURES (Cont'd)
NUMBER TITLE E.47-5 Homogeneous Mixt ure Pressurized Second ary Side % CLD RX 1 = 5%, 2 = 10%, 3 = 20%
E.47-6 Homogeneous Mixt ure Depressurized Secondary Side - % CLD RX 1 = 5%, 2 = 10%, 3 = 20%, 4 = 30%, 5 = 50%, 6 = 75%
E.75-1 Deleted E.75-2 Deleted E.75-3 Deleted E.75-2 Deleted E.75-3 Deleted DRAWINGS CITED IN THIS APPENDIX*
- The listed drawings are included as "General Re ferences" only; i.e., refer to the drawings to obtain ad ditional detail or to obtain background info rmation. These drawin gs are not part of the UFSAR. They are controlled by the Control led Documents Program.
DRAWING* SUBJECT A-831 Technical Support Center Monitor Room Pl an El. 435'-
0" M-37 Diagram of Auxil iary Feedwater System Unit 1 M-48-6A, -6B Diagram of Waste Disposal Auxiliary Building Floor Drains Units 1 & 2 M-60 Diagram of React or Coolant Loops Unit 1 M-62 Diagram of Residual Heat Removal System Unit 1 M-68 Diagram of Process Sampl ing (Primary & Secondary)
Unit 1 M-78 Diagram of Process Radia tion Monitoring System Unit 1 & 2 M-94 Diagram of Technical Sup port Center Ventilation System Units 1 & 2 M-102 Diagram of Laborator y HVAC System (V L) Units 1 & 2 M-135 Diagram of Reactor Coola nt System Loops Unit 2 M-137 Diagram of Residual Heat Removal Unit 2 M-140 Diagram of Process Sampl ing (Primary & Secondary)
Unit 2 M-151 Diagram of Process Radia tion Monitoring System Unit 2 M-152-26,
-27, -35 Diagram of HRSS Containment Air Sampling Panel (CASP) Units 1 & 2 108D685-1 Index and Symbols Fu nctional Diagrams 108D685-2 to
-18 Systems Function al Diagrams
B/B-UFSAR REVISION 8 - DECEMBER 2000 Figure E.7-1 has been deleted intentionally.