Standard Review Plan

US Nuclear Regulatory Commission 2000. Standard Review Plan for the Review of a Reclamation... 

NRC (2007), Identification of Potential Hazards in Site Vicinity , Section 2.2.1-2.2.2 of Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, Report NUREG-0800, March. 

The major regulatory requirements for digital I C QA programs are described in Chapter 7 of Standard Review Plan and associated references. There are more than 30 documents related to QA program requirements. The general structure of these documents can be presented in a hierarchical format as shown in Fig. 1. 

Based on the country of origin concept, in performing the software V V for the Limgmen project, the USNRC Standard Review Plan (SRP) Chapter 7, BTP-14 and USNRC Regulatory Guide 1.168 are followed. Two teams-the GE independent verification and validation team (GE IWT) and the owner (the TPC) IWT (OrWT), are organized by GE and TPC respectively to carry out the IV V tasks. 

Limgmen Standard Review Plan (SRP), Chapter 7, Branch Technical Position (BTP)HICB-14, Guidance on Software Reviews for Digital Computer-Based Instmmentation Control Systems. 

The safety case documentation providing evidence that the applicable requirements of the design for safety have been met in the design and implementation of the refurbished I C systems important to safety will have the format and contents as per the US NRC Regulatory Guide 1.70 and Chapter 7 of the US NRC Standard Review Plan (year 1997 issue). 

The tornado missiles used for design of the Standard MHTGR plant are those designated as Spectrum II missiles in Section 3.5.1.4 of the Standard Review Plan (SRP) for Region I tornadoes. (Ref. 1) Table 3.5-1 summarizes these... 

NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, June 1987. 

NUREG-800, "USNRC Standard Review Plan," provides additional guidance on the evaluation of heat removaI systems. The foI lowing sections... 

CFR Part 50.2, 10 CFR Part 50.55a(c), NRC Regulatory Guide 1.26 and Standard Review Plan Section 3,2,2 provide guidance for quality group classifications that may also be useful for DOE reactors. Additionally, risk-based classifications of components and systems may be util ized to ensure that components are inspected and tested commensurate with their importance to safety. 

USNRC (1996) Standard review plan for the review of safety analysis reports for nuclear power plants , NUREG-0800. 

Compilations of national regulations, such as the technical positions, the Regulatory Guides and the Standard Review Plan used in the USA are easily available (see Appendix 14). 

A complete guide for the combination of modal values can be obtained from the NRC Standard Review Plan and from a specific USNRC Regulatory Guide 1.92. ... 

A more complete treatment of these guide criteria can be found in the NRC Standard Review Plan and in the connected Regulatory Guides. 

The Standard Review Plan, SRP (USNRC, 1996) is, instead, a document (but it could be defined as an encyclopaedia because of the amount of material it contains ) which also indicates in great detail the ways (methods and depth) by which the NRC analyst must control the various parts of the safety analysis. A copy of the list of contents, some extracts from one regulatory guide and one chapter of the SRP are in Appendix 14. The regulatory guides and the SRP are frequently updated in order to keep up with the progress of knowledge and technical standards. 

USNRC Regulatory Guides and Standard Review Plan... 

This Appendix gives an example of a USNRC Regulatory Guide and a chapter of the Standard Review Plan to provide useful reference technical information and data. The numbering system and cross-references of the original documents are retained. All illustrations in the original documents have been removed. 

NRC (2007), Branch Technical Position 5-3, Fracture Toughness Requirements, NUREG-0800, Standard Review Plan, Revision 2 - March 2007, US Nuclear Regulatory Commission, Washington, DC. 

An LTOP enable temperature is defined in Branch Technical Position RSB 5-2, "Overpressurization Protection of Pressurized Water Reactors While Operating at Low Temperatures," to Standard Review Plan Section 5.2.2, "Overpressure Protection," issued November 1988 as Revision 2. The definition is based on measuring the degree of protection provided by the low temperature overpressure protection system (LTOP System) against violations of the P-T Limits in terms of the of the reactor vessel beltline material at either the l/4t or 3/it location,... 

UPDATE STANDARD REVIEW PLAN AND DEVELOP REGULATORY GUIDE... 

The NRC and others performed a variety of studies of the consequences of an inadvertent boron dilution event. The conclusions of the NRC assessment along with other studies were (1) that the consequences of an unmitigated boron dilution event, although undesirable, are not severe enough to warrant backfit of additional protective features at operating plants and (2) Standard Review Plan (SRP) Section 15.4.6 (Reference 2) is adequate for plants presently undergoing license review. 

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