Radiological Safety for the Design and Construction of Apparatus for Gamma Radiography. ANSI S3.6 Specifications for Audiometers 1969 NRC

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1 SDO Document Number ANSI N432 Document Title Radiological Safety for the Design and Construction of Apparatus for Gamma Radiography Edition Incorporated By ANSI S3.6 Specifications for Audiometers 1969 NRC ANSI MH5.1 ANSI N45.4 American Nuclear Society ANS 5 American Nuclear Society ANS 56.8 American Society for Testing and Materials American Society for Testing and Materials American Society for Testing and Materials ASTM E 185 ASTM E 185 ASTM E 185 CFR Location 34.20(a)(1) 73 App. B, I B b 2 Basic Requirements for Cargo 1971 NRC 73.26(l)(1) Containers Leakage Rate Testing of 50 App. J, III A Containment Structures for Nuclear1972 NRC 3 a Reactors Decay Energy Release Rates 50 App. K, I A Following Shutdown of Uranium 1971 NRC 4 Fueled Thermal Reactors Proposal Contaminate System Leakage Testing Requirements Standard Practice for Surveillance Tests for Nuclear Reactor Vessels Standard Practice for Surveillance Tests for Nuclear Reactor Vessels Standard Practice for Surveillance Tests for Nuclear Reactor Vessels Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel,, Division NRC 50 App. J, III A 3 a 1973 NRC 50 App. H, I 1979 NRC 50 App. H, I 1982 NRC 50 App. H, I 1992 NRC 50.55a(b)(1)(i) 50.55a(c)(1) 50.55a(c)(3) 50.34(f)(3)(v)(B)(1)

2 Boiler and Pressure Vessel,, Division 2 Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, 50.34(f)(3)(v)(B)(1) 50.55a(b)(1)(ii) 50.55a(b)(1)(iii) 50.55a(b)(1)(v) 50.55a(b)(1)(vi) 50.55a(b)(2)(i) 50.55a(b)(2)(vii) 50.55a(b)(2)(viii) 50.55a(b)(2)(ix) 50.55a(b)(2)(xii) 50.55a(b)(2)(xiv) 50.55a(b)(2)(xviii)(A) 50.55a(b)(2)(xviii)(B) 50.55a(b)(2)(xviii)(C) 50.55a(b)(2)(xix) 50.55a(b)(2)(xx)(B)

3 ASME OM ASME OM ASME OM ASME OM ASME OM Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, Boiler and Pressure Vessel, for Operation and for Operation and for Operation and for Operation and for Operation and 50.55a(b)(2)(xxi)(A) 50.55a(b)(2)(xxi)(B) 50.55a(b)(2)(xxii) 50.55a(b)(2)(xxiii) 50.55a(b)(2)(xxiv) 50.55a(b)(2)(xxv) 50.55a(b)(2)(xxvi) 50.55a(b)(2)(xxvii) 50.55a(b)(2)(vii) 50.55a(b)(3)(i) 50.55a(b)(3)(ii) 50.55a(b)(3)(v) 50.55a(b)(3)(vi)

4 Federal Specifications Standards and Test Methods General Electric Co. International Atomic Energy Agency International Organization for Standardization Boiler and Pressure Vessel,, Division (f)(3)(v)(A)(1) Boiler and Pressure Vessel,, Division (f)(3)(v)(A)(1) Boiler and Pressure Vessel, 50.55a(b)(1) Boiler and Pressure Vessel, 50.55a(b)(2) for Operation and ASME OM 50.55a(b)(3) FedSpec W-A Alarm Systems, Interior, Security, NDG B Components for NRC 73.50(d)(1) Loss-of-Coolant Accident and GE Report 50 App. K, I D Emergency Core Cooling Models 1971 NRC NEDO c for GE Boiling Water Reactors IEEE 279 Criteria for Protection Systems for NDG Nuclear Generating Stations NRC 50.55a(h)(2) Standard Criteria for Safety IEEE 603 Systems for Nuclear Power 1991 NRC 50.55a(h)(2) Generating Stations Standard Criteria for Safety IEEE 603 Systems for Nuclear Power 1991 NRC 50.55a(h)(3) Generating Stations IEEE 803 Recommended Practice for Unique Identification in Power and 1983 NRC 50.73(b)(2)(ii)(F)(1) Related Facilities IAEA Physical Protection of Nuclear INFCIRC/225 Material and Nuclear Facilities 1999 NRC (a) ISO 1496 General Cargo Containers 1978 NRC 73.26(l)(1)

5 International Organization for Standardization National of Standards and Technology, U.S. Department of Commerce ISO 389 NIST Handbook 136 Standard Reference Zero for the Calibration of Puretone Audiometer Radiological Safety for the Design and Construction of Apparatus for Gamma Radiography 1975 NRC 73 App. B, I B b NRC 50.48(c)(3)(i) 2001 NRC 50.48(c)(3)(ii) 2001 NRC 50.48(c)(4) 2001 NRC 50.48(c)(4)(i) 2001 NRC 50.48(f) 2001 NRC National Rifle NRA Publication NRA Target Manufacturers Index 1976 NRC National Technical Information Service Trans ANL-6548 TASME Journal of Heat Transfer Studies of Metal Water Reactions at High Temperatures Maximum Flow Rate of a Single Component, Two-Phase Mixture by F. J. Moody 50.48(c)(2)(vii)(A) 1981 NRC 34.20(a)(1) 1962 NRC 1965 NRC 73 App. B, IV C note 2 50 App. K, I A 5 50 App. K, I C 1 b

6 Westinghouse Electric Company Guide Guide Guide WCAP-7665, Revision 2007 NRC 50.55a(c)(3)(iv) 32, ASME, Revision 2007 NRC 50.55a(b)(4) 32, ASME, Revision 2007 NRC 50.55a(b)(4)(i) 32, ASME, Revision 2007 NRC 50.55a(b)(4)(ii) 32, ASME Inservice Inspection Case Acceptability, ASME Section XI, 2007 NRC 50.55a(b)(5) Division 1 Inservice Inspection Case Acceptability, ASME Section XI, 2007 NRC 50.55a(b)(5)(i) Division 1 Inservice Inspection Case Acceptability, ASME Section XI, 2007 NRC 50.55a(b)(5)(ii) Division 1 Operation and Maintenance 2003 NRC 50.55a(b)(6) Operation and Maintenance 2003 NRC 50.55a(b)(6)(i) Operation and Maintenance 2003 NRC 50.55a(b)(6)(ii) Operation and Maintenance 2003 NRC 50.55a(b)(6)(iii) PWR FLECHT (Full Length 50 App. K, I D Emergency Cooling Heat Transfer) 1971 NRC 5 Final Report

7 Westinghouse Electric Company AP 600 Tier 1, Tier 2, and Generic Technical Specifications 1999 NRC 52 App. C, III A

5.0 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS

Summary Description 5.0 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS This chapter of the U.S. EPR Final Safety Analysis Report (FSAR) is incorporated by reference with supplements as identified in the