ML061520233

DG-1145 Section C.I.1 Introduction on and General Description of Plant

ML061520233
Person / Time
Issue date:	05/29/2006
From:	Office of Nuclear Reactor Regulation
To:
Eric Osterle
References
DG-1145
Download: ML061520233 (8)

Text

DG-1145, Section C.I.1, Introduction and General Description of the PlantDRAFT-WORK-IN-PROGRESSPage 1 of 85/29/2006Combined license (COL) applicants per 10 CFR 52, Subpart C, may incorporate by referencedesigns that have been certified per 10 CFR 52, Subpart B, and early site permits per 10 CFR 52, Subpart A. The guidance provided in DG-1145, Section C.I, is applicable to a combined license applicant that references neither a certified design nor an early site permit. Additional guidance for COL applicants referencing a certified design and/or early site permit is provided in Section C.III of this document. The first chapter of the FSAR should present an introduction to the report and a generaldescription of the plant. This chapter should enable the reviewer or reader to obtain a basic understanding of the overall facility without having to refer to the subsequent chapters. Reviewof the detailed chapters that follow can then be accomplished with better perspective and withrecognition of the relative safety significance of each individual item to the overall plant design. 1.1Introduction In this section, the COL applicant should present briefly the principal aspects of the overallapplication, including the type of license requested, the number of plant units, a briefdescription of the proposed location of the plant, the type of the nuclear steam supply system orcertified plant design and its designer, the type of containment structure and its designer, the core thermal power levels, both rated and design, and the corresponding net electrical outputfor each thermal power level, the scheduled completion date and anticipated commercial operation date of each unit. The COL applicant should provide a general description or summary level information on the following areas of the application:1.1.1Plant Location The COL applicant should provide plant location information such as state, county, map(s)showing site location and plant arrangement within site, including whether plant is co-located with existing operating nuclear power plants.1.1.2Containment Type The COL applicant should provide a summary level description of the containment design (i.e.,freestanding or supported, cylindrical or spherical, liner or vessel type, shield building type -

reinforced concrete, post-tensioned, etc.). 1.1.3Reactor Type The COL applicant indicate nuclear steam supply system designer and model and whetherreactor is a pressurized water reactor or boiling water reactor. 1.1.4Power Output The COL applicant should provide net electrical output and core thermal power rating.

1.1.5Schedule DG-1145, Section C.I.1, Introduction and General Description of the PlantDRAFT-WORK-IN-PROGRESSPage 2 of 85/29/2006The COL applicant should provide estimated schedules for completion of construction andcommercial operation (estimates may be in durations rather than calendar dates based onapplication submittal date)1.1.6Format and Content The COL applicant should provide information on the following aspects of the format andcontent of their application:1.1.6.1Compliance with regulatory guides on format and content of a combined licenseapplication (i.e., DG-1145).1.1.6.2Compliance with the standard review plan (NUREG-0800) for technical guidanceand acceptance criteria. Guidance on providing compliance evaluations with individual SRPs is discussed in C.I.1.9 of this regulatory guide.1.1.6.3The format, content, and numbering for text, tables, and figures included in theapplication and a discussion on their use should be provided in the application.1.1.6.4Format for numbering of pages should be discussed in the application.

1.1.6.5The method by which proprietary information is identified and referenced shouldbe discussed.1.1.6.6A list of acronyms used in the application should be provided.1.2General Plant Description In this section, the COL applicant should include a summary description of the principalcharacteristics of the site and a concise description of the facility. The facility descriptionshould include a brief discussion of the principal design criteria, operating characteristics, and safety considerations for the facility; the engineered safety features and emergency systems;the instrumentation, control, and electrical systems; the power conversion system; the fuelhandling and storage systems; the cooling water and other auxiliary systems; and theradioactive waste management system. The general arrangement of major structures andequipment should be indicated by the use of plan and elevation drawings in sufficient number and detail to provide a reasonable understanding of the general layout of the plant. Those features of the plant likely to be of special interest because of their relationship to safety should be identified. Such items as unusual site characteristics, solutions to particularly difficult engineering and/or construction problems (e.g., modular construction techniques or plans) and significant extrapolations in technology represented by the design should be highlighted.1.3Comparisons with other facilities The COL applicant should provide a comparison with other facilities of similar design andsimilar power level. 1.4Identification of Agents and Contractors In this section, the COL applicant should identify the prime agents or contractors for the design,construction and operation of the nuclear power plant. The principal consultants and outside service organizations (such as those providing audits of the quality assurance program) should DG-1145, Section C.I.1, Introduction and General Description of the PlantDRAFT-WORK-IN-PROGRESSPage 3 of 85/29/2006be identified. The division of responsibility between the reactor designer or certified plantdesigned, architect-engineer, constructor, and plant operator should be delineated.1.5Requirements for Further Technical Information COL applicants that do not reference a certified design should provide information in thissection that demonstrates the performance of new safety features for nuclear power plants thatdiffer significantly from evolutionary light-water reactors or utilize simplified, inherent, passive,or other innovative means to accomplish their safety functions. The requirement to provide this information is included in 10 CFR Part 52 and is necessary to ensure that (1) these new safety features will perform as predicted in the applicant's safety analysis report, (2) the effects ofsystem interactions are acceptable, and (3) the applicant provides sufficient data to validateanalytical codes. The design qualification testing requirements may be met with either separate effects or integral system tests; prototype tests; or a combination of tests, analyses andoperating experience. These requirements implement the Commission's policy on proof-of-performance testing for all advanced reactors (51 FR 24643, dated July 8, 1986), as well as the Commission's goal of resolving all safety issues before authorizing construction. The guidance provided to COL applicants in this regulatory guide is based on a COL applicantthat does not reference a certified design as part of the application. Instead, this guidancefocuses on a COL applicant that must provide a complete design for the entire proposed facilityand with the same level of design completeness information provided for a certified design.

Because a COL applicant that does not reference a certified design must provide sufficient design information for a complete facility, the NRC staff anticipates that there may only be minimal requirements for further technical information. That is, information in addition to that provided in accordance with the discussion. These minimal requirements may include such items as verification of unique design concepts, for example, that may require tests and/or additional verification analyses for the first plant, first three plants, etc. It is the responsibility of the COL applicant providing a complete design for their proposedfacility to identify any requirements for further technical information in their application, includingan estimated schedule for providing the additional technical information that may be necessary for issuance of a combined license. 1.6Material Referenced In this section, the COL applicant should provide a tabulation of all topical reports that areincorporated by reference as part of the application. In this context, "topical reports" are defined as reports that have been prepared by reactor designers, reactor manufacturers, architect-engineers, or other organizations and filed separately with the NRC in support of thisapplication or of other applications or product lines. This tabulation should include, for each topical report, the title, the report number, the date submitted to the NRC, and the sections ofthe COL application in which the report is referenced. For any topical reports that have beenwithheld from public disclosure pursuant to Section 2.790(b) of 10 CFR Part 2 as proprietary documents, nonproprietary summary descriptions of the general content of such reports should also be referenced. This section should also include a tabulation of any documents submitted to the Commission in other applications that are incorporated in whole or in part in the DG-1145, Section C.I.1, Introduction and General Description of the PlantDRAFT-WORK-IN-PROGRESSPage 4 of 85/29/2006application by reference. If any information submitted in connection with other applications isincorporated by reference in this application, summaries of such information should be included in appropriate sections of this application.Results of test and analyses may be submitted as separate reports. In such cases, thesereports should be referenced in this section and summarized in the appropriate section of the FSAR.1.7Drawings and Other Detailed Information The COL applicant should provide a tabulation of all instrument and control functional diagrams,electrical one-line diagrams cross-referenced to application section, including legends for electrical power, instrument and control, lighting, and communication drawings. In addition, the COL applicant should provide a tabulation of system drawings and systemdesignators that are cross-referenced to applicable section of the application. The information should include the applicable drawing legends and notes. 1.8Interfaces (with Standard Designs and Early Site Permits)

The guidance provided in this regulatory guide is for a COL applicant that does not reference acertified design as part of the application. Instead, the COL applicant that is the focus of thisguide must provide a design for a complete facility, not limited in scope such as a certifieddesign, but to the same of level of design information as provided in a certified design. By definition, there no interface between standard designs and site-specific designs for a complete facility design. All interfaces, such as those which may exist between certified designs, earlysite permits and a COL application that references these documents, are expected to be integral to a COL application that provides a complete facility design. That is, there are no interfaces from a certified design and/or early site permit for a COL applicant that does not reference these documents. Based on the focus of this guidance document, there should be no interface requirements identified for a COL applicant that does not reference a certified designand/or early site permit. Likewise, a COL application that does not reference a certified design, by definition, should not include any conceptual design information for the facility. In order tofacilitate NRC staff review of previous applicants for design certification, conceptual designswere included in their design control documents (DCDs) to provide a comprehensive designperspective. However, the conceptual design portions of the DCDs were not int ended to beand were not certified by the NRC. These conceptual designs typically included portions of thebalance-of-plant. COL applicants that do not reference a certified design are expected to provide complete designs for the facility without reliance on conceptual designs. 1.9Compliance with Regulatory Criteria 1.9.1Compliance with Regulatory Guides The requirements of proposed 10 CFR 52.79(a)(4)(i) specify that the contents of a combinedlicense application must include information on the design of the facility, including the principaldesign criteria for the facility. Appendix A to part 50 of this chapter, "General Design Criteria for DG-1145, Section C.I.1, Introduction and General Description of the PlantDRAFT-WORK-IN-PROGRESSPage 5 of 85/29/2006Nuclear Power Plants," establishes minimum requirements for the principal design criteria forwater-cooled nuclear power plants similar in design and location to plants for which construction permits have previously been issued by the Commission and provides guidance to applicants in establishing principal design criteria for other types of nuclear power units. Regulatory Guides, in general, describe methods acceptable to the NRC staff for implementing the criteriaassociated with the General Design Criteria. COL applicants should provide an evaluation of compliance with the guidance provided in the NRC's Regulatory Guides that are in effect 6months before the docket date of the application. The evaluation should also include anidentification and description of any departures from the guidance contained in NRC RegulatoryGuides and suitable justifications provided for the alternative approach proposed by the COL applicant. 1.9.2Compliance with Standard Review Plan The requirements of proposed 10 CFR 52.79(a)(41) specify that for applications for light-watercooled nuclear power plant combined licenses, COL applicants should provide an evaluation of the facility against the Standard Review Plan (SRP) in effect 6 months before the docket date ofthe application. The evaluation required by this section shall include an identification anddescription of all differences in design features, analytical techniques and procedural measures proposed for a facility and those corresponding features, techniques and measures given in theSRP acceptance criteria. Where a difference exists, the evaluation shall discuss how the proposed alternative provides an acceptable method of complying with the Commission's regulations, or portions thereof, that underlie the corresponding SRP acceptance criteria. The SRP was issued to establish criteria that the NRC staff intends to use in evaluating whether anapplicant/licensee meets the Commission's regulations. The SRP is not a substitute for the regulations, and compliance is not a requirements. 1.9.3Generic Issues The requirements of proposed 10 CFR 52.79(a)(20) specify that the contents of a combinedlicense application must include the proposed technical resolutions of those unresolved safetyissues and medium- and high- priority generic safety issues that are identified in the version ofNUREG-0933 current on the date 6 months before application and that are technically relevantto the design.Since the inception of the generic issues program in 1976, the NRC has identified andcategorized reactor safety issues. These safety issues were grouped into TMI Action PlanItems, Task Action Plan Items, New Generic Items, Human Factors Issues, and Chernobyl Issues and are collectively called Generic Safety Issues (GSIs). A listing ofthese GSIs (i.e., those unresolved safety issues and medium- and high- priority generic safetyissues that are identified in the version of NUREG-0933 that was current on the date ofissuance of DG-1145) has been provided in Section C.IV.8, Generic Issues, for use by COLapplicants. A review of these GSIs was performed to determine whether they have been closed by other NRC actions or requirements. Those issues that remain open and which aretechnically relevant to the COL applicants design should be addressed in the application.

DG-1145, Section C.I.1, Introduction and General Description of the PlantDRAFT-WORK-IN-PROGRESSPage 6 of 85/29/20061.9.4Operational Experience (Generic Communications)The requirements of proposed 10 CFR 52.79(a)(37) specify that the contents of a combinedlicense application must include the information which demonstrates how operating experienceinsights from generic letters and bulletins up to 6 months before the docket date of theapplication, or comparable international operating experience, have been incorporated into theplant design.To ensure that the operational experience from decades of nuclear power plant operation in theUnited States is incorporated in the designs for new/standardized nuclear power plants, the highlights of this operational experience as documented in generic NRC communications mustbe reviewed and assessed. The significance of limiting this review to generic letters and bulletins is that these documents pertained to issues that were considered to have risen to the level of safety significance such that they required responses and resolutions from nuclear operating plant licensees. Other forms of generic communications have included circulars, information notices, and regulatory information summaries, however these types of generic communications do not require response or action on the part of the licensee. In addition, the issues discussed in these communications were generally of a more specific nature rather than a generic nature. A listing of generic communications (i.e., generic letters and bulletins that had been issued priorto date of issuance of DG-1145) has been provided in Section C.IV.8, Generic Issues, for useby COL applicants. A review of these generic communications was performed to determine whether they have been superceded by other NRC generic communications, NRC actions orrequirements. Those generic communications that remain open and which are technically relevant to the COL applicants facility design, including operational aspects of the facility,should be addressed in the application. Comparable international operating experience Applicants for certified design and applicants for a combined license are required to addresscomparable international operating experience in accordance with proposed 10 CFR52.49(a)(19) and 10 CFR 52.79(a)(37), respectively. To the extent that the design or portionsof the design for which a combined license or a design certification is sought originates or is based on international design, the COL application or design certification application shouldaddress how international operating experience has contributed to the design process. Nuclear industry regulators or industry owners groups in countries that include nuclear reactor vendors and/or nuclear power plants (e.g., Canada, France, Germany, Japan, etc.) may track, maintain, and/or issue operating experience bulletins or reports similar to the NRCs generic letters andbulletins. The COL applicant or design certification applicant should address how this body of operating experience information has been assessed and/or incorporated into the design. In addition, international experience relative to the operational aspects of both international and domestically designed nuclear reactors should be considered and assessed by COL applicants.

Applicants for design certification and/or a combined license are responsible for procuring any international operating experience information for use in this assessment.

DG-1145, Section C.I.1, Introduction and General Description of the PlantDRAFT-WORK-IN-PROGRESSPage 7 of 85/29/20061.9.4Advanced and Evolutionary Light Water Reactor Design IssuesPart I of this guidance document is applicable to COL applicants that do not reference acertified design. Therefore, COL applicants that do not reference a certified design mustprovide sufficient information on the complete design for their proposed facility, including thoseportions of the facility design that are typically provided by reactor vendors or applicants forreactor design certification per Subpart B of the 10 CFR 52. As such, COL applicants should address the licensing and policy issues developed by the NRC for advanced and evolutionarylight water reactor designs that are applicable to their proposed facility design. The followinglist provides guidance to a COL applicant on issues that should be considered and/or addressed in a COL application that does not reference a certified design, however, it does not represent a comprehensive listing for all potential COL applicants:SECY-89-013, Design Requirements Related to the Evolutionary Advanced Light WaterReactors (ALWRs)SECY-90-016, Evolutionary Light Water Reactor (ELWR) Certification Issues and TheirRelationship to Current Regulatory RequirementsSECY-90-241, Level of Detail Required for Design Certification under Part 52 SECY-90-377, Requirements for Design Certification Under 10 CFR Part 52 SECY-91-074, Prototype Decisions for Advanced Reactor Designs SECY-91-178, ITAAC for Design Certifications and Combined Licenses SECY-91-210, ITAAC Requirements for Design Review and Issuance of FDA SECY-91-229, Severe Accident Mitigation Design Alternatives for Certified Standard Designs SECY-91-262, Resolution of Selected Technical and Severe Accident Issues for EvolutionaryLight Water Reactor (LWR) DesignsSECY-92-053, Use of Design Acceptance Criteria during the 10 CFR Part 52 DesignCertification ReviewsSECY-92-092, The Containment Performance Goal, External Events Sequences, and theDefinition of Containment Failure for Advanced LWRs SECY-93-087, Policy, Technical, and Licensing Issues Pertaining to Evolutionary andAdvanced Light-Water Reactor (ALWR) DesignsSECY-94-084, Policy and Technical Issues Associated with the Regulatory Treatment of Non-Safety Systems in Passive Plant Design (RTNSS)SECY-94-302, Source-Term Related Technical and Licensing Issues Relating to Evolutionary DG-1145, Section C.I.1, Introduction and General Description of the PlantDRAFT-WORK-IN-PROGRESSPage 8 of 85/29/2006and Passive Light-Water-Reactor DesignsSECY-95-132, Policy and Technical Issues Associated with Regulatory Treatment of Non-Safety Systems in Passive Plant Designs