ML20205E302
| ML20205E302 | |
| Person / Time | |
|---|---|
| Issue date: | 03/30/1999 |
| From: | Stewart Magruder NRC (Affiliation Not Assigned) |
| To: | Carpenter C NRC (Affiliation Not Assigned) |
| References | |
| PROJECT-689 NUDOCS 9904050132 | |
| Download: ML20205E302 (7) | |
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UNITED STATES i
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NUCLEAR REGULATORY COMMISSION f.
. WASHINGTON, D.C. 20866-4001
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March 30, 1999 MEMORANDUM TO: Cynthia A. Carpenter, Chief
- Generic issues and Environmental Projects Branch Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation FROM:
Stewart L.' Magruder, Project Manager C % -
Generic Issues and Environmental Projects Branch Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF FEBRUARY 18,1999, MEETING WITH THE NUCLEAR ENERGY INSTITUTE (NEI) REGARDING DESIGN BASIS INFORMATION On February 18,1999, representatives of the Nuclear Energy Institute (NEI) and the industry
- design bases task force met with representatives of the Nucleat Regulatory Commission (NRC) at NEl's offices in Washington, DC. The purpose of the meeting was to discuss a letter from NEl
- to the NRC dated January 27,1999, that forwarded a draft revised Appendix B of NEl 97-04,
- Design Bases Program Guidelines." The revised Appendix B contains speific examples that
. attempt to distinguish between design basis information as defined in 10 CFr ' 50.2 and supporting design information. Attachment 1 provides a list of meeting attendees.
The NRC staff opened the meeting by stating that the revised examples in Appendix B were reviewed by the staff and that they were helpful in understanding the industry position. The staff noted that the additional examples and the topical design bases were particularly helpful.
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The group next discussed the reasons for distinguishing between design basis information and
- supporting design information. There was agreement that a clear understanding of what g3 constitutes design basis information is important for license renewal, engineering inspections and for implementing NEl 98-03, " Guidelines for Updating Final Safety Analysis Reports." In response to questions from the industry task force, the staff stated that there is no expectation
' that licensees will have to change the format of their updated final safety analysis reports
- (UFSARs) to implement NEl 98-03.
NEl next presented draft guidance on design basis information that they developed with the industry task force. The handout is included as Attachment 2. The NEl staff noted that the task force used the NRC draft criteria that was presented in a letter to NEl dated January 4,1999, as
'a model for their guidance. The NEl staff stated that they were consider;ng adding some form of guidance to Appendix B of NEl 97-04.
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F' C. Carpenter March 30, 1999 The NRC staff stated that they would review the draft guidance and provide comments to NEl. It was agreed that another meeting, attended by more staff, would provide the industry with a good opportunity to present their views. The NRC staff stated that they intended to keep working with the industry to develop guidance on design bases that could be endorsed via a regulatory guide as long as it appeared to be productive to do so.
Project No. 689 Attachments: As stated cc w/att: See next page
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c C. Carpenter
-2 March 30, 1999 The NRC staff stated that they would review the draft guidance and provide comments to NEl. It was agreed that another meeting, attended by more staff, would provide tne industry with a good opportunity to present their views. The NRC staff stated that they intended to keep working with the industry to develop guidance en design bases that could be endorsed via a regulatory guide as long as it appeared to be productive to do so.
Project No. 689 Attachments: As stated i
cc w/att: See next page j
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DISTRIBUTION: See attached page Document Name: g:\\SLM1\\msum0218.wpd OFFICE PM:RGEB (A)SC:RGEB SMagruderisI TM NAME DATE 3/30/99 3/b/99 4
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NRC/NEl MEETING ON DESIGN BASIS LIST OF ATTENDEES February 18,1999 NAME ORGANIZATION Tony Pietrangelo NEl Russ Bell NEl bob Evans NEl Ben George Southern Nuclear Ken Hutko PSE&G Pat Burke -
NSP George Wrobel RG&E Dave Lewis Shaw, Pittman Donald Ferraro Winston & Strawn Frank Akstulewicz NRC/NRR Eileen McKenna NRC/NRR Tom Bergman NRC/NRR Stewart Magruder NRC/NRR Tom Bruno DOE Nancy Chapman SERCH/Bechtel Kim Green NUS-IS James Riccio Public Citizen Jenny Weil McGraw-Hill Charlie Brinkman ABB-CE l
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.i Discussion Points for 2/18/99 Meeting with NRC on 10 CFR 50.2 Design Bases 10 CFR 50.2 Definition Design bases means information that identifies the specific functions to be performed by a structure, system, or component of a facility and the specific values or ranges of values chosen for controlling parameters as reference bounds for design. These values may be (1) restraints derived from generally accepted " state-of-the-art" practices for achieving functional goals or (2) requirements derived from analysis (based on calculations and/or experiments) of the effects of a postulated accident for which a structure, system, or component must meet its functional goals.
Draft General Guidance
- 1. The 10 CFP. 50.2 desgn basis functions of a plant's structures, systems, and components (SSCs).?:e those functions required by NRC regulations or order for responding to postulated events.
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- 2. The 10 CFR 50.2 design basis values for controlling parameters (" reference bounds for design," e.g., minimum flow, peak temperature, etc.) are those values used in the design process such that SSCs meet their 10 CFR 50.2 design basis functional requirements under the most limiting conditions for which the SSC is required to function.
- Draft Specific Guidance:
a) Limiting conditions for 10 CFR 50.2 design bases functions are derived from anticipated operational occurrences, design basis accidents, external events and natural phenomena for which SSCs are required to function.
b) Although every structure and component has a design basis, structure and component design basis functions are generally implicitly bounded by 10 CFR 50.2 design bases for the system.
- Structure and component functions are considered 10 CFR 50.2 design bases only if both the following criteria are met: 1) specific structure end component functions are not bounded by 10 CFR 50.2 system design bases, and 2) the structure / component or specific functions j
thereof are explicitly required by NRC regulation or order for responding to postulated events.
j Examples of structures or components having 10 CFR 50.2 design bases are the reactor pressure vessel and the emergency diesel generator, l
c) The 10 CFR 50.2 design bases of a facility are a subset of the licensing basis and are required pursuant to 10 CFR 50.34(a)(3)(ii) and (b) and 10 CFR 50.71(e) to be included in the updated FSAR along with sufficient design description to provide an understanding of the 50.2 design bases and how they are met.
- d) Underlying 10 CFR 50.2 design bases is substantial supporting design information.
Supporting design information includes design analyses, design output documents, and detailed information regarding implementation of the design bas,es. Supporting design information may be contained in the UFSAR or other documents, some of which are docketed and some of which are retained by the licensee.
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- Nuclear Energy Institute -
Project No. 689 cc:
Mr. Ralph Beedle ~
Ms. Lynnette Hendricks, Director Senior Vice President Plant Support and Chief Nuclear Officer.
Nuclear Energy Institute Nuclear Energy institute
. Suite 400 Suite 400 1776 i Street, NW 1776 i Street, NW.
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Washington, DC; 20006-3708 Washington, DC.20006-3708:
Mr. Alex Marion, Director-
,'Mr. Charles B. Brinkman, Director Programs
' Washington Operations Nuclear Energy Institute ABB-Combustion Engineering, Inc.
Suite 400.
' 12300 Twinbrook Parkway, Suite 330 1776 i Street, NW.
Rockville, Maryland 20852 Washington, DC 20006-3708 Mr. David Modeen, Director Engineering Nuclear Energy Institute Suite 400 -
1776 i Street, NW Washington, DC 20006-3708 Mr. Anthony Pietrangelo, Director Licensing Nuclear Energy Institute Suite 400 1776 i Street, NW Washington, DC 20006-3708 Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Activities Nuclear and Advanced Technology Division j
Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. Jim Davis, Director Operations Nuclear Energy Institute Suite 400 1776 i Street, NW Washington, DC~ 20006-3708
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.,9 Distribution: Mtg. Summary w/ NEl Re Design Basis Dated March 10. 1944 Hard Coov Cemet Files PUBLIC RGEB R/F OGC ACRS-SMagruder EMail SCollins/RZimmerman BSheron WKane DMatthews SNewberry TBergman FAkstulewicz EMcKenna GTracy, EDO
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