ML20072P110
| ML20072P110 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 07/15/1983 |
| From: | Edgar G JOINT APPLICANTS - CLINCH RIVER BREEDER REACTOR, MORGAN, LEWIS & BOCKIUS |
| To: | Sherwin Turk NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| References | |
| NUDOCS 8307180266 | |
| Download: ML20072P110 (12) | |
Text
4 MORGAN, LEWIS & BOCKlUS
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3. ' PHiLAccLPHsA COUN S ELORS AT LAW i LOS ANOCLES N ew YoR K 18 o 0 M STR EET, N.W.
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July 15, '1983
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Sherwin E. Turk, Esquire Office of Executive Legal Director Nuclear Regulatory Commission 7735 Old Georgetown Road Bethesda, Maryland 20014 Re:
Clinch River Breeder Reactor Plant (Docket No. 50-537
Dear Sherwin:
I have enclosed a copy of Applicants' proposed Exhibit List for the CP hearings for your review.
Please advise as to whether you will stipulate as to authenticity and admissibility, subject to the Board's approval.
I understand that you will be sending me your counterpart list in the near future.
Very truly yours, George L Edgar GLE:rw cc:
Service List 8307180266 830715 PDR ADOCK 05000537 0
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1 LIST OF EXHIBITS Exhibit PSAR Volume 1 (Chapter 1) 59 Section 1.0 Introduction and General Description of the Plant 1.1 Introduction 1.2 General Plant Description 1.3 Comparison Tables 1.4 Identification of Project Participants 1.5 Requirements for Further Technical Information 1.6 Material Incorporated by Reference 1.A Appendix l-A Flow Diagram Symbols (through pg. l.A-39)
PSAR Volume 2 Sections (2.1-2.4) 60 2.0 Site Charactdristics l
2.1 Geography and Demography 2.2 Nearby Industrial, Transportation and Military Facilities 2.3 Meteorology 2.4 Hydrologic Engineering (through pg.
2.4-237)
PSAR Volume 3 Sections (2.5-2A) 61 2.5 Geology and Seismology 2.A Appendix 2-A Field Investigative Procedures (through Boring 33W, Coordinate M+98, 67+84)
PSAR Volume 4 Sections'(2.B-3.1) 62 l
2.B Appendix 2-B Laboratory Test Procedures l
2.C Appendix 2-C Report of Test Grouting Program
.2.D Appendix 2-D Report of Engineering Froperties l
2.E Appendix 2-E Extracts from AEC Manual 2.F Appendix 2-F Review of Geologic and Seismologic Literature (1974-1981)
I Suppl. 2 Supplement to Chapter 2 Question and Responses to NRC Questions l
3.0 Design Criteria - Structures, Components, Equipment and Systems
- 3. l' Conformance with General Design Criteria l
(through pg. 3.1-77) l e
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Exhibit PSAR Volume 5 Sections (3.2-3A) 63 Section 3.2 Classifications of Structures, Systems and Components 3.3 Wind and Tornado Loadings 3.4 Water Level (flood) Design 4
3.5 Missile Protection 3.6 Protection Againct Dynamic Effects Associated with the Postulated Rupture of Piping 3.7 Seismic Design 3.8 Design of Category 1 Structures 3.9 Mechanical Systems and Components 3.10 Seismic Design of Category 1 Instrumentation and Electrical Equipment 3.11 Environmental Design of Mechanical and Electrical Equipment 3A.0 Supplementary Information on Seismic Category Structures (through pg. 3A.9-5)
PSAR Volume 6 Sections-(4.1 through pg. 4.2-475) 64 4.0 Reactor 4.1 Summary Description 4.2 Mechanical Design (through pg. 4.2-475) i i
PSAR Volume 7 (pb. 4.2-476 through pg. 4.4-194 65 4.2 Mechanical Design (from pg. 4.2-476) 4.3
. Nuclear Design 4.4
. Thermal and Hydraulic Design (through j
pg. 4.4-194) i PSAR Volume 8 Sections (4.1-5.4) 66 5. 0.-
Heat Transport and Connected Systems 5.1 Summary. Description 5.2 Reactor Vessel, Closure Head 5.3 Primary Heat' Transport System (PHTS) 5.4 Intermediate Heat Transport System (IHTS)
(through pg. 5.4-41) l l
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.: Exhibit i-PSAR Volume 9 Sections (5.5-7.4) 67 Section 5.5 Steam Generator System (SGS) 5.6 Residual Heat Removal Systems 5.7 Overall Heat Transport System Evaluation 6.0 Engineered Safety Features 6.1 General 6.2 Containment Systems 6.3 Habitability Systems 6.4 Cell Liner System 6.5 Catch Pan 7.0 Instrumentation and Controls 7.1 Introduction 7.2 Reactor Shutdown System 7.3 Engineered Safety Feature Instrumentation and Control
.7.4 Instrumentation and Control Systems
. Required for Safe Shutdown (through i
pg. 7.4-11)
PSAR Volume 10 Sections (7.5-9.2) 68 7.5 Instrumentation and Monitoring System 7.6 Other Instrumentation and Control Systems Required for Safety 7.7 Instrumentation and Control Systems Not Required for Safety 7.8 Plant Data Handling and Display System 7.9 operating Control Stations 8.0 Electric Power 8.1 Introduction 8.2 Offsite Power System 8.3 On-Site Power Systems 9.0 Auxiliary Systems 1
9.1 Fuel Storage and. Handling 9.2 Nuclear Island General Purpose l
j Maintenance System (through pg. 9.2-5) i PSAR Volume 11 Sections (9.3-9.9) 69 l
9.3 Auxiliary Liquid Metal System 9.4-Piping and Equipment Electrical Heating 9.5 Inert Gas Receiving and Processing System 9.6 Heating, Ventilating and~ Air Conditioning System 9 '. 7 Chilled Water Systems l
9.8 Impurity Monitoring and Analysis System l
9.9 Service Water Systems (through pg. 9.9-22)
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< - Exhibit i
PSAR Volume 12 Sections (9.10-11.6) 70 9.10 Compressed Gas System
- 9.11 Communications System 9.12 Lighting Systems 9.13-Plant Fire Protection System 9.14 Diesel Generator Auxiliary System
- 9.15 Equipment and Floor Drainage System 9.16 Recirculation Gas Cooling System 9.17 Sewage Disposal System 10.0 Steam and Power Conversion System j
10.1 Summary Description 10.2 Turbine Generator.
10.3 -
Main Steam Supply System 10.4 Other Features of Steam and Power Conversion System 11.0 Radioactive Waste Management 11.1 Source Terms 11.2 Liquid Waste System 11.2A Appendix ll.2A Dose Models:
Liquid Effluents i
11.3 Gaseous Waste System ll.3A Appendix 11.3A Dose Models:
Gaseous Effluents 11.4 Process and Effluent Radiological Monitoring System 11.5 Solid Waste System l
11.6 Offsite Radiological Monitoring Program (through pg.
PSAR Volume 13 Sections (12.0-15.2) 71 12.0 Radiation Protection 12.1 Shielding 12.2 Ventilation 12.3 Health Physics Program
- 12A Appendix 12A - Information Related to ALARA'for Occupational Radiation Exposures 13.0 Conduct of Operations 13.1 Organizational Structure of the Applicant
- 13. 2 -
Training Program 13.3 _
Emergency Planning 13.3A-Appendix 13.3A 13.4 Review and Audit 13.5 Plant Procedures 13.6 Plant Records 13.7 Radiological _ Security L
14.0 Initial Tests and Operation i.
14.l' Description of Test Programs l
14.2 Augmentation of Operator's Staff for-Initial-Tests and Operation
- 15.0 Accident' Analyses
t 2.
Exhibit Section 15.1 Introduction 15.2 Reactivity Insertion Design Events (through pg. 15.2-101)
PSAR Volume 14 Sections (15.3-16.6) 72 15.3-Undercooling Design Events 15.4 Local Failure Events 15.5 Fuel Handling and Storage Events 15.6 Sodium Spills 15.7 Other Events 15.A Appendix 15.A - Radiological Source Term for Assessment of Site Suitability 16.0 Technical Specifications 16.1 Definitions 16.2 Safety Limits and Limiting Safety Systems Settings 16.3 Limiting Conditions for Operation 16.4 Surveillance Requirements 16.5 Design Features 16.6 Administrative Controls (through pg.
16.6-13)
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PSAR Volume 15 Sections (17.0-17.J) 73 17.0 Quality Assurance 17.1 Quality Assurance During Design and Construction App. 17A Owner.QA App. 17B Fuel Supplier QA Program App. 17C Balance of Plant Supply QA Program App. 17D Nuclear Steam Supply System (NSSS)
Supplier QA Program App. 17E Architect-Engineer QA' Program App. 17F Constructor QA Program App. 17G RDT Standard F2-2, 1973,. QA Program
. Requirements App. 17H Reactor Manufacturer QA Program
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App. 17I GE-ARSD-RM QA Program App. 17J
'ESG-RM QA' Program (through pg. 17J-70)
L-PSAR Volume 16 (Appendix A-Appendix J) 74 App. A-Computer Codes App..B General Plant Transient Data App. C Safety Related Reliability Program (1-7)-
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, Exhibit Section App. G Plan for Inservice and Preservice Inspections App. H Post TMI Requirements App. J PRA Program Plan (through Pg. J-27)
PSAR Volume 17 Questions (001.1-0'01.75) 75
- Question / Response Supplement (Amendments 1 through 77)
- Response to 10/6/75 NRC letter
- Response to Question Series 001 (001.1 through 001.75, pg. 001.75-1)
PSAR Volume 18 Questions (001.76-001.324) 76
- Response to Questions: Series 001 (001.76 through 001.324, pg. 001.324-2)
PSAR Volume 19 Questions (001.325-001.499) 77
- Response to Question Series 001 (001.325 through 001.499, pg. 001.499-1)
PSAR Volume 20 Questions (001.500-001.704) 78
- Response to Question Series 001 (001.500 through 001.704, pg. 001.704-1)
PSAR Volume 21 Questions (011-120) 79
- Response to Question (011.1 through 011.25)
(020.1 through 020.49)
(040.1 through 040.28)
(110.1 through 110.78-v)
(120.1 through 120.74, pg.
120.74-1)
PSAR Volume 22 Questions (130-222) 80
- Response to Questions (130.1 through 130.114)
(222.1 through-222.101, pg.
222.101-1)
Exhibit PSAR Volume 23 Questions (241.1-310.67) 81
- Response to Questions (241.1 through 241.135)
(310.1 through 310.67, pg.
310.67-1)
PSAR Volume 24 Questions (321.1-430.7) 82
- Response to Questions (321.1 through 324.13)
(331.1 through 331.28)
(411.1 through 413.8)
(421.1 through 422.3)
(430.1 through 430.7, pg.
430.7-1)
PSAR Volume 25 Questions (CS 210.1-CS 410.19) 83 i
- Response to Questions (CS210.1 through CS210.14)
(CS220.1 through CS220.45)
(CS230.1 through CS230.5)
(CS231.1 through CS231.3)
(CS241.1 through CS241.7)
(CS250.1 through CS250.9)
(CS270.1 through CS270.14)
(CS281.1 through CS281.13) 3 (CS410.1 through CS410.19, pg.
QCS410.19-1)
PSAR Volume 26 Questions (CS 421.1-CS 721.1) 84
- Response to Questions (CS421.1 through CS421.59)
(CS430.1 through CS430.104)
(CS460.1 through CS460.3)
(CS471.1 through CS471.8)
(CS490.1 through CS490.39)
(CS491.1 through CS491.22)
(CS721.1 through pg. QCS721.1-10)
PSAR Volume 27 Questions (CS 760.1-CS 810.16) 85
- Response to Questions (CS760,1 through CS760.179)
(CS810.01 through CSE10.16, pg. QCS810.16-1)
. )
Exhibit Applicants' Statement of General Information 86 Pursuant to 10 C.F.R. S 50.33 Applicants' Testimony Concerning Whether 87 HCDA's should be DBA's WARD-D-0185, " Clinch River Breeder Reactor 88 Plant Integrity of Primary and Intermediate Heat Transport System Piping in Containment,"
September 1977.
Applicants' Testimony Concerning HCDA Analysis 89 CRBRP-3, Volume 1, " Hypothetical Core 90 Distuptive Accident Considerations in CRBRP; Energetics and Structural Margin Beyond the Design Basis," Rev. 5, February 1983 CRbRP-3, Volume 2, " Hypothetical Core 91 Disruptive Accident Considerations in CRBRP, Assessment of Thermal Margin Beyond the Design Base," Rev. 6, June 1983 ANL/ RAS 83-11 92 An Assessment of the Unprotected LOF Accident at EOC-4 in the CRBRP Heterogeneous Core Design GEFR-00523 93 An Assessment of HCDA Energetics in the CRBRP Heterogeneous Reactor Core Applicants' Testimony Concerning Board Areas 94 of Interest Related to Emergency Planning Applicants' Response to Board Areas of Interest 95 5 and 6
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
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UNITED STATES DEPARTMENT OF ENERGY
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PROJECT MANAGEMENT CORPORATION
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Docket No. 50-537
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TENNESSEE VALLEY AUTHORITY
)
)
(Clinch River Breeder Reactor Plant)
)
)
CERTIFICATE OF SERVICE Service has been effected on this date by personal delivery or first-class' mail to the following:
Marshall E. Miller, Esquire Chairman Atomic Safety & Licensing Board Nuclear Regulatory Commission 4350 East-West Highway Bethesda, Maryland 20814 (2 copies by hand)
Dr. Cadet H. Hand, Jr.
Director Bodega Marine Laboratory University of California P.O. Box 247 Bodega Bay, California 94923 Mr. Gustave A. Linenberger Atomic Safety & Licensing Board Nuclear Regulatory Commissien 4350 East-West Highway Bethesda, Maryland 20814 (by hand)
Stuart Treby, Esquire Sherwin E. Turk, Esquire Elaine I. Chan, Esquire Geary S. Mizuno, Esquire Office of Executive Legal Director Nuclear Regulatory Commission 7735 Old Georgetown Road l
Bethesda, Maryland 20014 (2 copies by hand) r l
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- Atomic Safety & Licensing Appeal Board Nuclear Regulatory Commission Washington, D.C.
20555 i
- Atomic Safety & Licensing Board Panel Nuclear Regulatory Commission Washington, D.C.
20555
- Docketing & Service Section Office of the Secretary Nuclear Regulatory Commission Washington, D.C.
20555 (3 copies by hand)
William M. Leech, Jr., Esquire William B. Hubbard, Esquire Michael D. Pearigen, Esquire State of Tennessee Office of the Attorney General 450 James Robertson Parkway Nashville, T,ennessee 37219 Oak Ridge Public Library Civic Center Oak Ridge, Tennessee 37830 Herbert S. Sanger, Jr., Esquire Lewis E. Wallace, Esquire W. Walter LaRoche, Esquire James F. Burger, Esquire Edward J. Vigluicci, Esquire Office of the General Counsel Tennessee Valley Authority 400 West Summit Hill Drive Knoxville, Tennessee 37902 (2 copies)
Lawson McGhee Public Library 500 West Church Street Knoxville, Tennessee 37902 William E. Lantrip, Esquire Attorney for the City of Oak Ridge
+
P.O. Box 1 Oak Ridge, Tennessee 37830 Leon Silverstrom, Esquire William D. Luck, Esquire Department of Energy 1000 Independence Avenue, S.W.
l Room 6B-256 L
Washington, D.C.
20585 (2 copies) l
. Commissioner James Cotham Tennessee Department of Economic and Community Development Andrew Jackson Building Suite 1007 Nashville, Tennessee 37219 ey f ect Management Corporation 4
DATED:
July 15, 1983 4
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Denotes hand delivery to 1717 H Street, N.W., Washington, D.C.
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