ML20153A987

Responds to .Comments on Hamilton Rept,Role of Nongovt Standards in Dev of Mandatory Fed Standards Re Safety & Health & on NRC Draft Recommendation on Lic & Auth of Acus.W/Encl NRC Standards Personnel List & 780523 Memo

ML20153A987
Person / Time
Issue date:	10/30/1978
From:	Hendrie J NRC COMMISSION (OCM)
To:	Anthony R ADMINISTRATIVE CONFERENCE OF THE U.S.
References
NUDOCS 7811290303
Download: ML20153A987 (57)

Text

{{#Wiki_filter:. _ - _ - _ _ _ _ _ _ _ _ _ - - _ _ _ - _______ - ,[f%'s UNITED STATES / NUCLEAR REGULATORY COMMISSION g y e 6,e A. y 3 E S WASHINGTON, D. C. 20555 E,, ' j Z. % s'... / October 30, 1978 OFFICE OF THE CH AIRM AN The Honorable Robert A. Anthony Chai rman Administrative Conference of the United States Washington, D. C. 20037 Dear Mr. Ch rman Thank you for your letter of August 25, 1978 offering us the opportunity to comment on Professor Hamilton's report entitled "The Role of Non-governmental Standards in the Development of Mandatory Federal Standards Relating to Safety and Health" and on the draft recommendation under consideration by your Committee on Licenses and Authorizations. Specifically, you requested our assessment of whether the account given of NRC's interaction with nongovernmental standards-developing organi-zations accurately reflects our authority, policies, procedures, and experience. We find that Professor Hamilton has accurately described our participation in the national standards program. One point does require clarification. On page VI-31 the report states: "Other agencies, such as NRC, expect that their representatives will cast votes that reflect the agency's position." This statement correctly described the NRC practice on major committees; e.g., the so-called N-committees. However, the larger number of NRC staff participants serve as individuals on committees, subcommittees, working groups, etc., where each expresses knowledge of the interests of NRC in the area of the group's activity. This is done to make clear that NRC participation in a standard development group does not commit the Commission to endorse or utilize the standards prepared by that group. This issue is resolved by your draf t recommenda-tion.which, in discussing the agency representative, states, "He should have no authority to bind the agency to any specific proposal." The draft OMB circular on Federal Participation in the Development and Use of Voluntary Standards also makes this point. We have carefully reviewed the draft recommendation. We find it to be generally consistent with NRC policies and procedures and are in substantial agreement. We feel that it is vital that the standards setting process be as open and as accountable as possible. Referenced standards are ' available from the NRC library and we are exploring the possibility of placing them in the Washington and local public document rooms dependent upon cost and copyright restrictions. We offer the following specific comment: 7811290 36.3

s The H'norable Robert A. Anthony - Recommendation V. (page 5) states that " Agencies should adopt regulations implementing the procedures..." We suggest that the recommendation be changed to read, " Agencies should adopt written policies, published in the Federal Register, implementing the procedures..." To adopt these recommendations as mandatory regu-lations might unduly restrict the ability of agency management t.o exercise individual judgment in those borderline or special situations that all too frequently arise. I would also like to respond to certain specific items cited in your letter: - We agree with the suggestion that urges agencies that utilize voluntary consensus standards for purposes other than the regulation of health and safety to follow the recommendation to the extent appro-priate. We find the recommendation to have general applicability and see no reason to restrict it to health and safety issues. At NRC our procedures, which are generally consistent with the recommendation, apply to all our standards development activities. - We agree in many instances with footnote 1 on page 3 regarding the desirability of excluding from the concept of " regulation of health and safety" regulations relating directly to the qualifications or conduct of' individuals engaged in the performance of professional services in areas of health and safety. However, there are some cases in which qualification standards may effectively be prepared as part of the consensus standards program. For example, nongovernmental reactor inspection, examination, and testing personnel may be qualified in accordance with consensus standards ANSI N45.2.6, " Qualification of Inspection Personnel for the Construction Phase of Nuclear Power Plants" and SNi-TC-1 A, " Recommended Practice for Nondestructive Testing Personnel Qualification and Certification." NRC has endorsed both these standards in our Regulatory Guide 1.58. NRC is not involved in determining eligibility for federal funding programs. We are not, therefore, qualified to comment on the exclusion of this category from the concept of " regulation of health and safety." '- In response to your request for documentary information on the presant pattern of participation of NRC employees in standards-developing organizations, I am enclosing a copy of our computerized listing of national standards committee membership. This includes lists of NRC personnel involved in the development of national standards - alpha-betically and by office, and a list of standards committees with associated NRC personnel. l

Tile Honorable Robert A. Anthony * - The Federal Advisory Committee Act (FACA) has, as yet, not affected the participation of NRC staff in the national standards program. The question of whether NRC participation in and use of national standards cormittees is subject to the FACA was addressed by our General Counsel in a recent memorandum. He concluded that "... ANSI... Committees fall into a gray area not yet fully explored by the courts; but a case can be made that they are not covered by FACA." A copy of the entire memorandum is attached. In conclusion, we believe that Professor Hamilton and the Administrative Conference are making a significant contribution to the development of a uniform policy for federal agency participation in the national standards program and utilization of its products. SSincerely, \\W < Joseph M. Hendrie

Enclosures:

1. National Standards Committee flembership Files, Privacy Act File, NP,C-15 2. Memorandum fr. J. L. Kelley to R. B. Minogue dtd. 5/23/78

. j' D UNITED STATES y g - NUCt. EAR REGULATORY cOMMIS$10N i-- j WASHINGTON, D. C. 20955 - -~ e, \\p f May 23, 1978 MEMORANDUM FOR: . Robert B. Minogue, Director, SD FROM: ames L. Kelley, Acting General Counsel

SUBJECT:

FEDERAL ADVISORY COMMITTEES j 'This memorandum responds to your request of April 7 for a legal opinion on whether NRC participation in and use of certain national standards committees is subject to the Federal Advisory Committee Act. Since your initial request, two ot.;er organizations were suggested for review: the National Council on Radiation Protection and Measurements (NCRP) and the Interagency Committee on Dam Safety (ICODS). Our conclusions, given in detail at the end of the paper, are that the ANSI and NCRP committees fall into a gray area not yet' fully explored by the courts; but a case can be made that they are not covered by FACA. We conclude that ICODS does not present a serious FACA question. Introduction This memorandum will addre,ss the following question: Are certain committees, in whose deliberations NRC employees participate and whose results and recommendations are used-by the NRC to carry out its regulatory functions, to be considered " Advisory Committees" within the meaning of Section 3(2) of the Federal-Advisory Committee Act? The analysis will proceed in three steps: (1) the meaning of " advisory committee" in FACA, as elucidated by the express statutory language, legislative history, case law, etc., .(2) structure and nature of NRC's relationship with the various' committees at issue, (3) application of the defini-tion (and associated criteria) to the committees. I. The Meaning of " Advisory Committee" Section 3(2) of FACA defines'" advisory committee" as follows: CONTACT: William M. Shields 254-5943 7849D 3 US?

• Robert B. Minogue 2

May 23, 1978 (2) The term " advisory committee" means any committee, board, commissior, council, conference, panel, task force, or other similar group, or any subcommittee or other subgroup thereof (hereafter in this paragraph referred to as " committee"), which 'is-- (A)' established by statute or reorganiza-tion plan, or (B) established or utilized by the Presi-dent, or (C) established or utilized by one or more

agencies, in the interest of obtaining advice or recommenda-tions for the President or one or more agencies or officers of the Federal Government, except that such term excludes (1) the Advisory Commission on Intergovernmental Relations, (ii) the Commission on Government Procurement, and (iii) any committee which is composed wholly'of full-time officers or employees of the Federal Government.

Two limitations may be mentioned at the outset, which will limit the focus of our inquiry considerably. First, none of the three exceptions apply to the committees in question; second, there is no doubt that the committees to be examined fall within the enumerated categories of " committee, board, commission..." Our inquiry will therefore be limited to the center section of the FACA definition, in particular to: "(C) established or utilized by one or more agencies 1n the interest of obtaining advice or reccmmendations "77 This is, of course, an exceedingly broad definition, which on-its face would appear to cover nearly every committee giving advice in some form to the government, except those expressly excluded. The problem, as stated by Marblestone, is "to determine the type of relationship between an agency and a non-federal committee which makes the statute SI The Interagency Committee on Dam Safety, to be dis-cussed below, was established by the President, and so may fall within (3) as well as (C). None of the other. committees herein were established either by statute, the. President, or a federal agency.

a 4 +.. . Robert-B. Minogue 3 May 23, 1978 applicable."2I Unfortunately,Lthe legislative history of FACA is not.very. helpful.in providing. criteria for limiting '.the definition. Marblestone notes: If--.the statute or at'least its legislative history.were more' clear, no-lengthy discussion of these coverage questions would be necessary. Hou-ever, the Advisory Committee Act is an. example of legislation containing serious ambiguitie; with respect to matters of fundamental importance..The result of. Congress '- failure to be more explicit is .to create uncertainty regarding the obligations of. ~ federal agencies and corresponding uncertainty with' regardto'tgprightsundertheActofmembersof the public. There is some. authority in the legislative history to sug-j - gest thagj" utilized" was to be read synonymously with."estab-lished."- Basic rules of statutory interpretation, how - i ever,'would weigh heavily against such a narrow interpreta- ] tion, as would the remedial purposes - of the statute as a whole. 'A more balanced reading of_the House, Senate, and l Conference Reports suggests that " utilized" was intended to mean something more than " established" but something less than "used in any.way." Marblestone cites post-conference ~ statements to-arrive at the following criterion: " utilized" meansusedinthesgpemannerasagovernment-established advisory committee S/ Marblestone, The' Coverage of the Federal Advisory Committee Act, 35 Federal Bar Journal 119, 129 1/ Id. 4/ .The Conference Report at 10 stated in comment upon FACA Section 4 (" Applicability"): "The Act does not apply ... to advisory committees. not directly established by or for... [ federal] agencies." E! Marblestone at.130. While his direct authority for this-proposition is.semewhat thin, it does seem to bring'some order outHof the confused Congressional statementaron this section. Applied to an individual committee and agency, e g, the NRC and~an ANSI' stand-i ards committee, the cricerion would suggest comparing [ Continued' on next page] I

Robert B. Minogue 4 May 23, 1973 Case law on FACA's intended coverage is similarly divergent and less than authoritative. The five reported cases inte preting Section 3(2) are federal district court decisions;g7 as yet no Court of Appeals has examined the question except to affirm summarily. Each case has essentially been re-solved on its own facts, thus providing little basis for discerning generally applicable criteria. The cases are: Food Chemical News, Inc. v. Davis, 378 F.Supp. 1048 (D.D.C. 1974); Nader v. Barcody, 396 F.Supp. 1231 (D.D.C. 1975); Lombardo v. Handler, 397 F.Supp. 792 (D.D.C. 1975); Consumers Union of U.S., Inc. v. Deet. of REW, 409, F.Supp. 493 (D.D.C. 197o); Center for Auto Safety v. Tiemann, 414 F.Supp. 215 (D.C.C. 1976). In Food Chemical Judge Richey held that two meetings between the Bureau of Alcohol, Tobacco and Firearms and ad hoc con-sumer and liquor industry committees constituted utiliza-tion of advisory committees under Section 3(2) of FACA, and thus the meetings.had to be open to the public. On the applicability of FACA, Judge Richey stated: It is undisputed that the Defendant utilized an ad hoc committee of industry representatives in order to obtain advice. Such a relationship, like that with the consumer group, clearly comes within Section 3(2) of the Act. 378 F.Supp. at 1051. Clearly where, as here, a federal agency utilizes an advisory committee for the purpose of obtaining advice,. the agency must charter and establish the committee in compliance with all the terms of the Act. Id. 5/ [ Continued from preceding page] NRC's use of that committee to its use of government-established advisory committees such as the ACES (estab-11shed by statute) or the Risk Assessment Review Group (established by the NRC). This comparison will be made below. bI In fact, all are decisions frem the District Court for the District' of Columbia. 1

i Robert B. Minogue. 5 mar 23,1978 Although the opinion is not clear on-this point, it would appear"that the Bureau was responsible for forming the com-mittees, or at the very least, actively sought their ady_ce. and recommendations. In such a case the language'of Section-3(2) becomes directly applicable, and hence the opinion does not attempt to analyze " closer cases." Judge Richey did emphasise, however, the_importance of the public health issues to be discussed by the committees, and noted the possibility of " devastating harm" when the Government is "being.regulatedbythosewhomtheGovernmentissupposypto regulate in the public interest." 378 F.Supp. at 1052 Judge Gesell offered a detailed analysis of the Act in Nader, arriving at a conclusion that "the Act was not intended to apply to all amorphous, ad hoc group meetings," but rather contemplated groups "having some sort of established struc-ture and defined purpose as ' advisory committees' 396 F.Supp. at 1233. In holding that bi-weekly meetings held at the White House with selected groups from business organizations or the private sector were not included by Section 3(2), Judge Gesell arrived at the following criterion: [3] Examination of the Act as a whole, and the indications found there, confirms the legis-lative history, and points to the conclusion that Congress was concerned with advisory committees formally organized which the President or.an execu-tive-dapartment or official directed to make recommendations on an identified governmencal policy for which specified advice was being sought. Id. at 1234. (emphasis added) As negative factors Judge Gesell noted that "the group meet-ings are unstructured, informal and not conducted for the purpose of obtaining advice on specific subjects indicated in advance." Id. at 1234-1235 While the Nader case is therefore helpful where such ad hoc groups are involved, it is of less utility where, as in the present case, the com-mittees in question are undoubtedly structured and formal. The only portion of the Nader rationale useful for present purposes is whether the ccanittees' advice has been sought by an agency in some direct way -- rephrased, whether the 1 'The analogy to the NRC and the issues considered by ~ ANSI committees, NCRP, and the Dam Safety Ccamittee is obvious, though.perhaps not so crucial as the Food Chemical opinion seems to indicate.

5 Robert B. Minogue-6 May 23, 1978 government took the initiative in seeking advice from a structured committee. In Lombardo Judge Sirica presents a lengthy analysis of the " utilized" portion of. Section 3(2), and reviews the legis-lative history in: detail.- Although the opinion appears to accept Marblestone's thesis of. limiting " utilized"gpo "in the same manner as a Government-formed committee,"- it goes on to stress the exception implied in the legis1'ative history for persons cn? organizations which have contractual relationships with the government. 397.F upp. at 798-799 Since the committee at issue in that cas had such a relationship to the EPA'(the agency." utilizing" its ser ~ vices), Judge Sirica. held it exempt from FACA on that basis. The weight of the case for present purposes is further re-duced by. Judge Sirica's finding that the EPA was actually " utilizing"-the National Academy of Sciences itself, not its subsidiary committee at issue. Id. at 800. Nevertheless, the opinion's review of the legislative history seems to support Marblestone, and is consistent with Judge Gesell's reasoning in Nader. The factual situation in Consumers Union was different from Food Chemical' in that it was an industry proposal being con-sidered, not an agency proposal, and different frca Nader in that a 3pructured, rather than an ad hoc, group was at issue.1 Judge Smith held that the CFTA -- a cosmetics industry group seeking the advice and comments of the FDA -- was not an " advisory committee" being " utilized" by the FDA. The opinion focuses on the fact that the proposal being con-sidered was formulated by the industry: ... CFTA took the initiative... Granting that FDA had frequently expressed its concern for cosmetic ingredient testing, the Court finds that planning had evolved beyond agency control. CFTA on its own discretion was ultimately to decide whether or not to initiate a testing program. Such a relationship of agency and S/- The opinion emphasizes this phrase in several quotes from the legislative' history. 397 F.Supp. at 797, 798. 1! The Ccmmittee:en Motor Vehicle Emissions of.the National Academy of. Sciences. SS/ The Lombardo case'is' cited but not discussed. 409 F.Supp. ac 475. P + - -- - - ~ n - + + s

Robert B. Minogue 7 May 23, 1978 group does not rise to the level of a FACA " advisory" relationship. 409 F.'Supp. at 477. This language makes clear the criteria alluded to by ' Judge Gesell.in Nader, that is, who " initiated" the agency-committee relationship? This criterion, as distinguished 1 from Marblestone'sisuggested "in.the same manner" test, focuses on the origin rather than on the current. nature of-the agency-committee relationship. The final case in this line is Tiemann, decided by Judge Richey who also' wrote Food, Chemical, supra. In Tiemann Judge Richey held that AASHTO,2= an organizacion of State and federal highway officials, had been " utilized" by the Federal Highway. Administration. The opinion reviews the legislative history of " utilized," citing Nader, Lombardo, Food Chemical, and Consumers Union, and-appears to accept both criteria developed above, namely, " initiative" and Marblestone's "same manner" thesis: ... as the government readily admits, it went directly to AASHTO, cmong other groups, for specific advice on<pending draft regulations. In doing so, the government employet AASHTO much as advisory committees are frequently &nd traditionally employed. 414 F.Supp. at 224. I i I The court also rejected the government's contention that apply-ing FACA to an organization of government (State and federal) i officials did not serve the purposam of the Act, on the grounds that at least the State mer' he group were members of the " regulated" in respes the matters at issue (super-vising federally-funded State highway programs). Id. at 225 The cases, then, seem to adopt two criteria to decide whether a committee or other group has been " utilized" by a. federal agency, perhaps best phrased as questions: (1) Is the com-mittee.or group being used by the agency in much the same way as that agency would use a government-established advisory committee? (2) Who took the initiative to - establish the re-lationship between the ecmmittee or group and the agency? The first of these is consistent with Marblestone's reading of the legislative history, discussed above; the second is certainly related to, but is analytically distinguishable from-the first. -11# His article pre-dates Consumers Union, which first emphasized this factor.

l 1 Robert B..Minogue 8 May 23,'1978 i Marblestone does include'" initiative" among' a list of factors not present case authority for its inclusion.-{2phough he f does to be considered in determining " utilization,' ' Hejalso lists 'a number of other factors. which would be likely to weigh in the. balance in a given case: (a) circumstances at the committee's creation and the_ purpose for which it was formed; (b); the basis'for the. committee's furnishing'its views.to the federal official - _a_.g_., an. ~ . agency request or the committee's volunteer-ing [this really re-states the " initiative" ~ factor]; (c) the purpose of the federal official -- obtain-ing advice, or public relations; ) (d) nature and frequency of dealings between the agency and the committee; l (e) any formal. recognition by the agency that the j committee has an advisory role. ) While these factors are helpful in determining what facts are relevant to the application of Section 3(2), the only legal criteria supported so far by the cases are.the two given above. Our inquiry must therefore focus on the application-of these criteria to the NRC and the committees in question. II. Committees Used-by NRC Three groups will now be examined for their characteristics - relevant : to :the legal criteria set out above: (1) The many standards-writing committees supervised by the Nuclear Standards-Management Board; (2) Committees within the National Council on Radiation Protection and Measurements (NRCP); and (3) the Interagency Committee on Dam Safety (ICCDS). A. Standards Committees Among the organizations writing standards for the nuclear industry.are ANSI,~AS"'M, ASME, IEEE, and the American Nuclear 15/ His article pre-dates Censumers Union, which first emphasized this factor. t

~. '+ Robert B.,Minogue 9 May 23, 1978 ' S ociety. - 'Their efforts are. coordinated by t Nuclear-Standards Management _ Board, created by ANSI,ggf in 1976; NRC, DCE; and.the National Bureau of Standards are. rep-resented on this' Board. The AEC contributed financially.to . ANSI,-but it is assumed that NRC does not. 1 The'above-named organizations comprise many_ separate com-mittees working in the nuclear area...NRC employees serve on many, if not all, of these' committees. In some' cases NRC' members represent their.own views but do not speak officially for.the agency; in other. cases (mainly higher-level committees) NRC members may be authorized'to represent official NRC views.,The NRC. representative actively par-ticipates in the development of standards. In 1973 the AEC stated that it would cooperate directly with the working groups, "inc ing a full exchange _of information regarding scheduling." Once 'mdard has been developed by a committee, it is re-vie ae NRC staff'(including the individual who served ivant committee) for-possible inclusion in a Regu-le or Regulation. The final decision on whether tc 3 standard is'made by persons who did not participate in a=velopmeng # It is understood that many standardsd committees devu oped by ANSI into the NRC regulatory structure. It is NRC policy to take some action on a new ANSI standard within 90 days of its issuance. The NRC either initiates endorsement -- in whole or in part -- in a Reg Guide, cr ANSI is' informed of the reasons for not using the standard. The active participation of NRC employees on the standards committees tends to prev 9 unacceptabletotheNRC.3gythedevelopmentofstandards 11/ American National Standards Institute. SE/ Minutes of the INSI Nuclear Technical Advisory Board Executive Committee Meeting, September 5, 1973. 15/ " ANSI" is used hereafter to represent the entire class o f nuclear s t andards group s, i. e., ASME, IEEE, et c. 15/ In FY 1978, of the approximately 150 employees in the NRC Cffice of Standards Development, ab out 70. serve on the technical 1 standards committees. There are approxi-mately 2500 NRC employees in all NRC offices, of whom about 230 serve on standards committees. .~

c 4^ + Robert B. Minogue 10 May 23, 1978 B. RRCP NRC participation in-the activities of NRCP committees is -similar to the ANSI situation. NRC employees serve on the scientific committees: in. areas related to NRC 's. regulatory activities.- The major difference.is mittees. write" consensus" standards,yypatwhileANSIcom-the NRCP committees' recommendations' represent the views of the. committee as an . expert panel. NRC.does use NRCP recommendations-in its Reg-Guides or Regs in much the same way as with ANSI standards. From the standpoint of deciding FACA's applicability, there appears to be little difference between NRC's relationship with ANSI and with NRCP: NRC employees participate in the development of standards, and NRC references at least some of these standards in its regulatory issuances. J C. Dam Safety a President Carter established the Interagency Committee on Dam Safety (ICODS) by a memorandum to heads of certain. federal agencies on April 23, 1977. The purpose of this committee is "to coordinate dam safety programs" and to provide "recommen- . dations as to the ~means of improving the effectiveness of the Government-wide dam' safety effort." This memorandum also directed the Director of the Office of Science and Technology Policy to establish an " Independent Review Panel" of "recog-nized experts" in dam safety. NRC participates in ICODS because of its expertise gained through analyzing-the potential danger posed to nuclear power stations by dam failures. Several NRC employees serve on various subcommittees of ICODS, for example, the Site Investigation and Desig Subcommittee. Because ICODS is not a standards committee,2gf NRC does not "make use"~of ICODS g work. KRC's participation is basically limited to " input," rather than " output." 11/ ANSI attempts by a fairly extensive, formal process to solicit the views;of industry, consumer groups, and the government so. that its ' standards represent a " consensus" of a broad range of opinion. 1$b It is more-in the nature of a study commission, intended only.to review the' federal dam safety program and make recommendations. thereon to the President. p. ,m .m ~ s m.

c Robert B. Minogue 11 May.23, 1978 ICCDS is composed entirely of federal employees, and is hence expressly exempted from FACA coverage by Section 3(2)(C)(iii). Further. discussion of it will not be neces-sary. The " Independent Review Panel," however, is chiefly composed of non-federal employee experts in various fields related to dam; safety. At this time the Panel has not begun to take an active role in the safety review process, and it 1 is not known precisely what that role will be. It is pos-sible that.the Panel may function as an " advisory committee" within'Section 3(2) Ethere is noLquestion that it was "estab-lished...Lby the President"), but, if so., it will be the responsibility of the President to charter the committee and insure that other provisions of FACA are observed. NRC will have no part in this process, and hence further discussion of the Panel is not necessary. III. Application of Criteria A. Standards Committees It would appear that the NRC's relationship with these com-mittees is a close and continuing one, and is of major .l benefit-to the NRC in the formulation of standards. The committees are neither ad hoc nor informal, and although they do not give " advice" to the NRC in the direct sense, it is clear that the NRC relies heavily on their work in carry-ing out its regulatory duties. It is difficult to apply the " initiative" test in this con-text, because the relationship between the NRC and ANSI committees 11s a long-standing one.. It also seems that, although NRC employees serve on the committees and assist in developing standards, the connection between the NRC itself and the committees is relatively arms-length. This is clearly not a case, however, like Consumers Union: ANSI and its sister nuclear standards. groups have noe sought out NRC advice and-comment on their proposals. Rather, NRC expects the various standards committees to produce standards which it can reference or endorse in its regulatory issuances. Without the committees, the NRC would be forced to greatly expand its own standards capabilities, and even then might be unable to duplicate the work of so many ccamittees rep-resenting all parts of the nuclear industry and its many I contributing industries. It is therefore not necessary for I the NRC to take the " initiative," since the committees -- on L 1

~. o i Robert B. Minogue 12 May 23, 1978 which. NRC is represented -- may be expected to carry on their. work; nor is it' necessary. for ANSI to take the "ini-tiative," since it knows.the NRC works closely with its committees.and will give-due consideration to any standard produced by them. This criterion 1s~therefore not useful as ~ to these committees. ) i The second test is whether the standards committees are used i by,the NRC in the same way as it would use (or uses) government-l established advisory committees. The NRC currently " utilizes" three advisory committees:. (1) the Advisory Committee on Reactor Safeguards (ACRS), established by the Atomic Energy Act, (2) the Advisory Committee on~the Medical Uses of Iso-topes ( ACMI), established by the_ AEC in _1958, (3) the Risk Assessment Review Group _ (RARG), established by the NRC in June 1977. All of these are duly chartered and subject to all the provisions of FACA. NRC's relationship with the ACRS is close, with the committee or its representatives frequently meeting with the Commission itself. The Commission requests the ACED to study many matters of both short4 and long-term interest, and the committee responds to such requests with reports to the Commission. The ACRS is also required by statute to review every application for a construction permit or operating license. _ Obviously the NRC does not " utilize" ANSI stand-j ards committees to this extent or with this regularity, nor does the Commission itself receive " advice" from these committees. ANSI standards are reviewed by the NRC staff and then may or may not be incorporated into Regs or Reg Guides. On the other hand, no NRC employees serve on'the ACRS or directly participate in-its deliberations. The initial responsibilities of the ACMI have, for the most part, been. assumed by the FDA, so that the committee's activities are now largely confined to recommendations _ con-cerning the training and experience of applicants for licenses for new or complex uses of radioisotopes in medi-cine. ~The committee meets infrequently, and generally conducts its. business by mail or telephone. It therefore does.not provide a useful analogy-to the standards committees. The Risk Assessment Review Group similarly does not provide a basis for comparison with the standards committees, in that it is an ad hoc group which will' provide a single report to the Commission concerning '4ASE-1400 and the general subject

4 e g-.a.ee a Robert B. Minogue 13 May 23, 1978 of risk assessment. methodology. The group has no continuing responsibilities, and will terminate when its report is issued. In summary, then, none.of the current NRC advisory com-mittees closely parallel the standa.rds. committees, and in fact have few characteristics in common among themselves. It then might be useful to ask: If the NRC did not have the input of the ANSI committees, and established its own " standards advisory committees" composed of both federal and non-federal members, how would it " utilize" them? ' If the answer'is: "similar to the way the ANSI committees are now -I used," then there is g me reason to believe FACA applies ~ to the ANSI committees. Such a hypothetical question is, of course, difficult to answer in any detail. An NRC standards advisory committee probably would have an even closer w with the staff than ANSI committees,ggping relationship although it is un-likely that. staff members would actually participate in the committee's work. The committee would formulate standards ) in much the same way as an ANSI committee, though again the l influence of the NRC staff on what constitutes an " acceptable" standard might be greater. Once a standard was agreed by the committee, NRC action would j most likely be about the sameias with ANSI committees. That is, the staff would review the proposed standard, decide to use it in whole or in part (or reject it entirely), and inform the committee of reasons for rejection or non-use of any part of the standard. This similar treatment tends to vitiate an argument based on Section 3(2)'s "advics or recommendations" language. In both cases -- an ANSI com-mittee or an NRC-established committee ~ -- the proposed standard and ita subsequent treatment by. the NRC staff seem E "Similar" is'.used here to mean how the NRC would relate to the hypothetical committee, how it.would make use of-the committee's proposed standards, etc. Obviously, an NRC-established. committee would have a different struc-ture and modus operandi from ANSI committees, but such differences are not relevant to the present inquiry. 22/. The ACRS makes considerable use of staff input in per-forming its safety reviews. t' 4

.c 4 Robert B. Minogue 14 May 23, 1978 to fall directly within these terms.21/ It is assumed that in neither case would a proposed standard be accepted or rejected without some further study as to its intrinsic merit and usefulness with NRC's regulatory sc.keme, whatever the level of direct staff participation in the committee's work. Only a totally in-house standards group ~'.1d func-tion in such a way, and this destroys the advant-ge of having a semi-independent or independent panel responsible in the first instance for the proposed standard. It thus appears that the "similar use" criterion, applied in this hypothetical sense, indicates that ANSI standards com-mittees are covered ~by FACA. Whether such an argument would be applied by the courts is another matter, however. By the previous discussion, it is clear that the NRC does not treat ANSI committees as it treats its own advisory committees, nor does it take the " initiative" in the sense of direct requests of ANSI committees for specific " advice or recom-mendations." With the exception of NRC staff membership on the ANSI committees -- an admittedly significant excep-tion -- NRC and the ANSI standards committees operate at arms-length. These committees provide no direct advice to the Commission (as does the ACRS), nor do they write reports or studies concerning general technical matters (e.g., ) RARG). Because of how they are used by the NRC, however, the proposed standards really must be viewed as "recommenda-tions" within the meaning of Section 3(2). B. Dam Safety (See discussion above at 15). C. NCRP Because the relationship between NRC and NCRP committees is similar to the ANSI case, most of the above discussion applies here e.3 well. " Initiative" is not a useful criterion, since NCRP t lon;-standing organication whose work has been used by bot'n the AEC and the NRC. NRC staff serve on NCRP ccm-mittees, and NRC uses NCRP recommendations in its regulatory issuances. It does not appear, however, that the "90-day review" procedure applies to NCR? -- in this sense the re-lationship is somewhat more arms-length than the ANSI case. b In the sense that " advice" and "recommenda-ions" can either be fcilowed or not, or scme combination thereof. l

4 ', - Rob'ert B. Minogue 15 May 23, 1978 I As with the ANS! standards committees, no NRC-established advisory committee provides a close analogy to the-NRCP committees. The closest parallel is ACMI,.but as noted j above, that committee no longer-concerns.itself (for the most part) with. substantive scientific matters. In the hypothetical case : of NRC-established advisory committees. for the development of radiation standards, all of the above considerations applied to ANSI apply - here. - Such hypothetical committees would likely be employed by NRC much as NCRP committees are now utilized, but without direct staff participation and with a decrease in the " arms-length" distance between NRC and the committees. The proposed NCRP standards, because they are frequently referenced in NRC Reg Guides or Regs, must be considered " recommendations" within the meaning of Section 3(2). IV. Conclusions The committees 'of ANSI and NCRP in which NRC participates, and whose proposals NRC frequently adopts in regulatory issuances, fall between the so-far inexact criteria developed in the few applicable court decisions interpreting Section 3(2) of FACA. The " initiative" criterion is not helpful, and the'"similar use" criterion is difficult to apply without hypothesizing. If various other suggested factors,2gpe uses Marblestone's some weigh on one side and some.on the other: the committees furnish their recom-mended standards without a specific NRC request, but NRC's dealings with the' committees clearly have an " advisory" purpose; NRC has not formally recognized the advisory role of ANSI or NRCP committees, but NRC's dealings with the committees are relatively close and continuous. What other factors a court might find relevant cannot now be determined. It can at least be concluded that the ANSI and NRCP committees arguably are not within the meaning of Section 3(2) of FACA. Certainly a defensible case can be made that, unclear legis-lative history and inexact statutory language notwithstanding, FACA was not intended to apply to such committees. Congress was motivated by: three factors in passing FACA.: (1) The cost of advisory committees had become alarming, (2) The use of advisory committees-had proliferated to such an extent that it was not even known how many there were, (3) Advisory committee deliberations, often:on'important matters of public SS/ Supra, at-10-11.

i ~ H c, r - Robert B. Minogue 16 May 23, 1978 policy, were not open to public scrutiny. The overall intent j was to gain some measure of control over the use of advisory committees by government agencies. In the present case, the standards committees of ANSI and NRCP actually represent a cost say1ngs to the NRC. And while the technical discus-sion sessions of the committees may be conducted in private, the standards eventually proposed are made public and are open to criticism from any quarter. No useful purpose would i be served, either from a cost or public information stand-point, by subjecting these committees to the requirements of FACA. The' problem of " multiple use" should also be mentioned. In many cases a particular ANSI or NRCP committee might be " utilized" by several federal agencies, as well as by industry or State regulatory agencies. The NRC, for example, might make use of certain electrical standards developed by an IEEE committee, but such standards might also be adopted by other federal or State agencies responsible in any way for the safety of electrical systems. Even a standard particularly applicable to nuclear systems might be used by DOE or DOD, and it is conceivable that NRC might not make use of the same standard. For the NRC to insist on chartering such committees as its own " advisory committees" would result-in unnecessary interference with the work of a committee used by many other agencies or groups. In short, carrying the Section 3(2) definition too far might cause bureaucre;ic confusion and inter-agency. battles over who should charter a particular technical standards committee (recalling that the committee itself is part of an independent group such as ANSI, which certainly would be averse to such government control over its operations), the end result being injury to the regulatory process as a whole. It is reasonable to assume that Congress intended no such result in passing FACA, 1 notwithstanding the broad language of section 3(2). As has been previously stated, the Interagency Committee .on Dam Safety is exempt from FACA due to its all-federal membership. The Dam Safety Review Panel, while not exempt on this basis, was similarly. ostablished by the President, who would be responsible for chartering it under FACA if Section 3(2) applies.- 4

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03890 WICitMAN. E. A. 0209) ASME-SPVC SC 11 5657 U.S. susCLEAR REGULAIORY COMM. U.S. NUCLE AR REGUL AID :V COMN. SIEEL PLAIE5 OfflCE OF n. CLEAR afAClan MEG. OFFgCE OF STANDARD 5 DEVEL. ASME-SPVC SC III SGN ICCC W45ttltoGltwo. DC 20555 WA5HipeGTON. DC 20555 CODE CASE C0040lesagIOgg ANS -05.01 ANS -50 CWG2 ASME-SPVC 50 til 56M IGC5 DECAY Et4EAGY DELE ASE R4fE5 PWR CONDifl0N5 0F DEstGN A00ltl0NAL NATERI AL5 FOR CustruseENT futtoWI**G Situl00WN Ur C00ADINAll0N WOAntttG GA0ur SUPPORIS URANIUM-FufLED filERMAL AEACina A5ME-SPVC SC III 500 VAssiv. 5. 5. 01129' IN88.61 DE SIGag u.5. NUCLEAR REGut A10av COMM. w"LLEA. AICHARD A. Oll25 A5ME-8PVC SC III SGO IGS OfflCE OF sauCLEAa REG. RES. U.S. Nt1CtEAR REGULAIDAW COMM. APPEasolX a W45HR IIGT080 e DC 20555 offlLE OF NUCLEAR REACIOR SEG. A5ME-8PVC 50 Ill SCO WGC IEEE M42 -02 W A 5tt lNGlutt. DC 20555 00a6TAINMENI RA010 ACTIVE REFEaE80CE SIAldDAR05 At4 5 -55.01 A5ME-BPVC SC Ill SCO -WGC5 SuSCOM. PWA L BWM SOLID WA5ff SYSTEM DE5tGN COMP 00eENT 5UPPORIS IEEE M44 -02 INB988 Will. F. J. 15032 IHERAPEullC RADIOLOGV 681N2 8NGE A. E. C. 02077 U.S. seUCLE AR REGut Af 0AV COMM. IltutSEVe H. 55834 U.S. NUCLEAR REGUL&iORY COMM. OFFICE OF STANDARD 5 DEVEL. u.5. leuCLE AR REGut AIORY COMM. Ot f I C C OF SI ADtDARD5 DE VEL. WA5attleGifMs. DC 20555 REGIOtt I W A$st iteGI ON. DC 20555 AICHE 8646 -05 ISA NPP5C WitIG OF PauS5tA. PA 19406 FUEL REra0CE5588tG A51M C26 talCLEAR POWER PL ANI 5 I 81 5. IsOOLRIDGE. E. D. 15033 FUEL. Cf AOL. E MODEAAIDA 15A NPP50 ISC-4 u.5. eeuCLE AR REGut AIORY COMM. MA TE R1 % FOR leUCLEAR APPLICAIIOet$ fuNCllOrdAL MEQulSEMENis OFFICE OF SI ANDAADS DEVEL. ISA NPP50 15C-6 WA5ttlNGION. DC 20555 IN-PLANI IE5ilNG AND Mk"NTtNANCli A5'ME-SPVC SC ll lillE. L. A. 07065 Su8 COMMITTEE ON NAIERIAL u.5. Pet 1 Cit AR MEGULAIORY C08tM. SPECIFICAllGN5 UFFICE OF SIANUARDS DEVEL. W A rt itsG iuti. DC 20555 4NS -02.11 GtilDE L INE S f Ost EVAtuAll866 51IE-stet AIE D GEUlf fisNIC AL i e

ae L 0 0 4 LIST OF fEC RPSCfflEL I!MOLVED If1 IEEOROIT T NIX 1 EAR STN0AFDS BY 07IE O l

i SEP 5 Ept I u.5. NUCLEAR REGULATORY COMM. - l U.S. NUCL E AR REGut 4I03Y COMM. 8ARANOW5KY. P. W. 08866 K NO N. L. J0ttN 15064 s l E xt C. O!R. FOR orERArloN5 BELLAMV. R.R. 08867 KOPP. L.I. 15018 WASHINGlute. DC 20555 B Ellu ACCHl. L. 15059 KOVAC5 J.M. 08884 itA N AH E R.

5. St.

00805 BENNEIT. T. J. 15002 KREGER. W. E. OROSF MudRE. R. II. 038TF BLOCK. SEvMOUR 08327 KUO. P. I. 15020 U.S. MuCLE AR REGUL AIDAY COMM. 805NAK. R. J. 00188 LAINA5. G. C. 05589 NULL E AR MATERIAL 5 5AfEIY C 5AFEGuARDS 84 AMME R. it. L. 00203 LEE J.Y. 15022 WA5HINGIDN. DC 20555 8URKE. W. C. 15003 LIAW. 8. D. 15023 CouPER5tEIN R. 04707 CALVO. J. A. 02337 L I PINSK I. R. E. 04073 DE L At40 Y. J. C. 02573 CAR 0lLE. F. P. 15067 L I IION F. 8. 08874 GOkDON. 4. L. 04843 CARTER. I. J. 01325 MARCHESE. A. R. 07066 JONES. JAMES A. 01152 CitAN. 5. P. 15005 MARKEE. E. H.. JR. 08875 FE llL ACit. H. 01038 .CitENG. C. Y. 02680 MATIHEW5 P. R. 00183 Et IGF IEL O. G. 15052 CilE RMY. F. C. 08F38 MATTU. R. K. 15024 MA C DONA L D. C. E. 01212 CLARE. ROBERT A. 003F2 MC DERM 0fi. R.J. 15025 MALARo. J. C. 01224 CLEMENSDN. F. 03318 MC 00NALD D. 15026 5M i let. R. D AL E 15053 CoffMAN. F. O., JR. 00387 MC GOUGH. J. M. 08280 5tEvtN5HN. M. L. 01882 COL L INS. J. T. 02560 MC MULLEN. R. S. 02310 MADE. L. 08983 CONRAD. H. F. 06295 MEYER. J. F. 1504F U.S. NUCLEAR REGULAIORY COMM. DE5AI. K. D. 15008 MEVER. R. D. 088F6 Of f l CE OF ADMINISTRAflhN OUNNING. I. G. 15D70 MILLER. C. F. 01328 WA5HING.ON. DC 20555 ECKERMAN. K. F. 02380 MOORE. V. A. 01364 SI[EtE. M. L. 65041 ERICK5ON. PETER 08373

MURPHY, T.O.

02348 U. S. NUCL E AR NEGULAIORY COMM. FENGU50N. R. L. 00614 NEHEMIAS. V. J. 04202 ottl0F uf INSPECIlute C FNinRCfMENT F15 cater. O. C. 02479 N00 NAN. V. 15051 WASH lHGION. DC 20555 FITIPATRICK. R08ERT C. 08454 PANCIERA. V. W. 014I0 DLACKMON. R. F. 15044 GAMBLE. R. M. 0114' PAWLICKl. 5. 5. 01496 BRVAN.

5. E.

00249 GlLRAY. J.W. 15082 PillLLIPS L. E. 08878 Custf N. t. K. 01138 GRIME 5

8. K.

08871 PICKETT. D. V. OF06F CONSI Aet t. G. L. 15054 GRIME 5. C. I. 15036 POLK. tiAROLD E. 01180 HE NDE M 50H. J. B. 04159 HAA55. W. P. 15066 POIAPOV5. U. 07610-LADUAN. W. 15021

IIAFil, A.

5. 08973 RAJAN. J. R. 15028 PE R Aft l Cll. M. W. 08982 HARitMANN. M. 150t3 REIO. R. W. 15063 RElff. D. D. 01595 St AlEL ION. W. 5. 00855 RIANI. L.B. 08879 RE ltaMU lit. G. W. 08186 tt[LLER. L. W. 02840 RINALDB. F. 15029 RuteHB ACHER. u. A. 08892 stELTLMES. C. J. OF083 ROSA. F. 05t92 RU l HL M F itRD. W. R. 15030 It0FNANN. R. 8. 15049 RU8 EN STE IN. L. 5. 01185 $EvtRil. K. v. 00135 ItofMAVER. C. II. 08979 5C HA DE R. F. P. 01709 Stil W"4EI R. R. E. 01784 ltOL M AN. J. J. 08853 SCHEMEL. R. J. 01F11 SulletK. J. 08336 1800

5. N.

02451 5HAPAKER. J. W. 00129 litOMA5. Y. D. 08948 etOU550N. M. D. 06545 SlHWEll. I. 5. 08896 U.S. HUCLEAR REGULAIORY CGMM. HOLMAN. L.G. 15039 SINI5 GALLI. A. A. 08854 i Ot i-I C L OF M Afth;f Hit 4 5 C PkUGN AM AN AL Y 515 ituH. M. K. 08969 SKovet0LT O. J. 02210 WA5ilINGlun. DC 20555 IMDRO. E. V. 06864 50FFER. L. 08885 8tLt1E. n.R. 00115 treutITO. I. A. 00951 SPEls. T. P. 05532 884HIl lit o, p. A. 0833) IHELAND. R. E. 00952 SIDART. RICHARD J. 01191 U.S. NUCLEAR REGULAIORY COMM. J AC K 5f tN. R.E. 15016 StualEWICE. A. 15035 ttf t lCt Of NUCil AH MLACION PEG. JENG. D.C. 01149 IAM. P. 5. 15048 W A 5it l MG I ON. DC 20555 JulNSUN. GEORGE 15050 I AN C. P. 01928 41LI5ON. D. P. 01515 K Af tE. J. D. 15065 10KAR. M. 08880 Asett. F. 5. 15001 RIE55EL. R. J. 01033 10N01. D.. JR. 07420 A lltf R ION. Pt ILH 08132 ktBNt. J.R. 00482 UNGARO. A. R. 15058 ts a t R. R. t. 00061 KNIGHl. JAME5 P. 07078 VILLALVA. 8. 02004 bAllApp. M. 1. 03865 KNIGHION. G. W. 01052 WEISS. 5. H. 08890

1 U.S. NUCLE AR REGUL ATORY COMM. 2 SEP 5 B78 WELLER. RICHARD A. O!!25 F L E 156tM AN. MORIGN R. 02405 WHIIE. L. A. - 07065 U.S. NUCLEAR REGUL AIDRV COMM. FRANE, L. 08766 WICHMAN. K. R. 02093 i OFFICL OF NUCLEAR RLG. RES. Gott. V. 5. 05545 WITI. F. J. '15032 WASHINGION. DC 20555 GRILL. RICl8ARD 01083 WOOLRIDGE. E. O. 15033 ASSEY. R. F.. JR. OIS63 GUPTA. R. P. 08362 U.S. NUCLEAR REGULATORV COMM. bl5ALv0 R. 85009 HARMON. D. F. 08365 DFFICE OF STATE PRDGRAMS FERI. R. 150!! ItELD. E. E. 02276 WASHINGTON. DC 20555 KELBER. C. N. 02465 HILL. E. L. 07875 CDLLINS. HAROLD E. 0e978 L Y Nil. E. K. 08329 HINI2E. A. 5. 07361 U.S. NUCLE AR REGUL AIORY COMM. PICKLE 5trER. M. L. 04695 sa0PKINS. O. R. 04000 REGIDN I Riu. L. N. 08e57 JAMGOCHIAN. M. f. 08900 KING OF PRUSSIA. PA 19406 R f CllARD5DN. J. E. 08618 JONES. R. J. 00987 E8 METER. 5. D. 15055 Scit4MutRGER. R. O. 02439 KASINER. J. 15017 PADLINO. R. J. 15027 4 SERPAN. C. 7.. JR. 01754 KORNA5IEWIC2. R. A. 08872 ZlBUL5KY. H. 15034 5ttan. L. C. 08766 MARINGS. E. C. 03369 U.S. NUCLEAR REGULATORY CDMM. WE SEL Y. W. E. 01421 MC GUIRE. 5. A. 04139 ' REGIDN 11 WALKER. I. J. 15031 MIL leo AN. J. L. 02534 101 MARIETTA SIREET. SUIIE 3500 WALL. 1. 6. 08854 MILLMAN. G. C. 07479 ATLANIA. GA 30303 VAulv 5. 5. 01129 MINOGUE. R. S. 01344 CDCHRAN. R. J. 00385 U.S. NUCLE AR REGUL AIDRV COMM. MONIGOMERV. J. M. 85056 HERDI, A. R. 15014 UttlCE OF SIANDARDS DEVEL. MORRISDN. W. M. 01376 L DNG. F. J. 011ST White t NG ION. DC 20555 klCis0LSDN. T. J. 15061 OUZIS. J. E. 05574 AL i M A NDE R. R. E. 04153 NIL 5tN. C. W. 01411 U.S. NUCLE AR REGUL ATORY COMM. ANDER5ON. W. F. 0402f NORBERG. J. A. 15057 REGIDN III ANiuffo. G. 4. 00047 NOILEY. D. P., SR. 15045 GLEN ELLYN. IL 60137 AMNDI. E. G. 00049 OII. W. R. 08377 GALL AGHER. EUGENE 15065 A58 TAR. Bl. G. 07407 PDRSE. L. 01545 JASLON5KI. F. 15015 8ANKER. R. F. 00055 PRELL. J. A. 01183 MC GDNNAGLE.

k. J.

07132 BE CKil AM. D. 14. 15060 RANDALL. P. N. 06300 UE51MANN. M. J. 07607 BEHAIAN. 4. L. 15042 SHAW. it. K. 08793 RIDGWAv. K. R. 05622 BROO5KW. A. 00226 $KOPEC. F. C. 04507 U.S. NUCLEAR REGULATDRY COMM. BROWN. E. J. 08364 SMIIH. DONOWAN A. 01820 REGION IV BRuwN. WILLApp B. 03861 SutEM. L. C. 01145 &lt RVAN PLAZA DREWE CAMPDELL. W. E.. JR. 08977 STANFORD. R. E. L. 03727 AALINCIDN. IK 76012 CAPilN. J. L. 04505 SIEVER. K.G. 01845 TAPRA. J. 1. 15069 CHEN. J. I. 15006 SuttlVAN. D. F. 01911 U.S. NUCLEAR REGULATDRY CDMM. COUL. W. 5. 00405 IARGADA. A. 03366 REGION V. WALNUI CREEK PLAZA C05lE ttu. J. F. 08363 IING. P. 08889 IS90 M. CALIFORNI A BLVD. D004 R. J. 85062 IUREL. 5.P. 01331 WALNUI CREEK. CA 94%96 EISLNHLHG. N. A. 01135 WEIN5fEIN. M. 5. 03819 CURit s. J. R. 08375 E t 55 A. L. 01136 WEN 2lNGEG. E. C. 02077 IAIR. J. R. 150t0 l i.

A $fP 5 Ept i u.5. NUCLEAR REGULAIDRY COMM.

• U.S. NUCL E AR REGUL A TORY COMM. BLACEMON. R.F.

15044 IEEE PES NPEC 5C4kG4.2 EEEC. OtR. FOR OPERAll0NS A5IM E10 -10.40 AIMERION. PEIER 01132 W A SH ING itM. DC 20555 ASIM F12 IEEE PES NPEC SC2WG2.14 -A-ItA NAUC R.

5. St.

~ 00805 BRYAN. 5. E. 00249 BAER. R. L. 00063 { IEC IC45 SC45A ANS -0 3 ANS -52 IEEE N41 C DitE N. L.K. 01131 AN5 -52.01 IEEE N42 HPb M13 -09 BALLARD. R. L. 08065 550 5085 CON 5tA8LE. G. L. 15054 ANS -18.05 MOURE. R. II. 038FF AN5 -15 ANS -18.08 INMM Nt3 -03 ANs -15.14 OARANOW5KY. P. W. 08566 U.S. NUCLEAR REGULAIDMY COMM. ANS -15.18 ANS -54.03 NUCLEAR PAIERIAL5 5AFEIY C SAFEGUARDS ItENDER504. J. 8. 08F59 SELLAMY. R. R. 08867 WASHINGION. 16C 20555 A5ME-8PVC SC Kl SGWC WGAR AN5 -59.02 CouPER$iEIN. R. 0470F ASME-EPVC 50 XI IGC5 A5ME CONAGI A5IM uno -02 A5ME-NPCS COM PI SELIRACCHl. L. 15059 ASIM C26 LAUDAN. W. 15021 IEEE PES NPEC SC6WG6.4 AitM C26 -02 IEEE PE5 ADCOM SENNEII. I.J. 15002 ASIM C26 -03 PERANICH. M. W. 08982 AMS -02.01 A5fM C26 -05 A5ME-NPC5 MCQA SCMC AMS -02.14 DEtANEV. J.C. 02573 REtFF. D. O. 01595 stock. SEYMOUR 08327 p ANS -5F.01 AN5 -54.03 AN5 -06.08 GORDON. L.L. 01143 ASME KRO 80$NAK. R. J. 00188 AICitE N46 -02 -A-REINMullt. G. W. 08186 A5ME-SPvc JONES, JAME5 A. OttS2 A5ME SCC A5ME-8PVC SC III A5HI MD PRC ROItRB ACHE R. R. A. 08892 A 5ME-8 P VC 5C Ill SGG EE llt ACit. N. 01034 ACI-ASME JC SGMCE $NAME M-13 AN5 -08 ACI-A5ME JC SGMC E WGC BRAMMER. H. L. 00203 ANS -0 8. 0 3 -C- ,RulinERFORD. W. R. 15030 A5ME-8PVC SC Ill SGD WGPM ANS -08.08 A5ME-8PVC SCNC BURKE. W. C. 15003 ANS -08. 3 2 A5ME SCC -A-ASME NED RSC ANS -08.83.8 5EYFRII. K. V. 00135 CALVO. J. A. 0233F 150 1085 SCI Att AN5 -56.08 ANS -04.03 .02 i kL BGF IEL D. G. 15052 intE WM AME R. R. E. 01784 CARDILE. F.P. 15067 AICitE N46 -04.02 ACl-ASME JC SGD WGCC ANS -18.0L i MAC DHNALD. C. E. 01212 ACI 349 CARTER. T. J. 01325 ABA Nt4 5NIE2EE. J. 08936 ANS ~15 MALANO. J. C. 01224 A5ME-NPCS COM ANS -15 18 ) AN5 N48 THOMAS. V. D. 01948 CHAN. 5. P. 15005 5M l ill. H. Datf 15053 IEEE PE5 HPEC SCIWGl.2A ASME-8PVC 50 til SGO IGDA ASIM i10 SEEE PE5 NPEC 5C 8W G8.1 Cite NG. C. Y. 02680 AilM 180 sa U.S. NUCLEAR REGULAIDAY COMM. A5aE-8Pvc SC Mt SGWC WGE SilVEN504 H. L. 01882 DFFICE OF MANAGEMENI C PROGRAM ANALYSIS A5ME-8PVC SC Mt SGWC WG5 Ates tal6 WA5titNGION. DC 20555 CilERNY. F. C. 08738 WAUE. L. 08983 SLEBL. M.R. 00115 A5ME-8PVC SC til SGPR IEEE N44 -A-ANSI H5MS INF A5ME-NPC5 COM PI WG5RV t8.5. NUCtCAR REGULAIURY COMM. II AR IF IE L D e R. A. 08339 CLARK. ROBERI A. 003F2 OFFICE of ADMINISIHAllbte ANS Nt 8-20 AN5 -53 W A 50t t MG I ON. DC 20S55 ANht N5MB FIRR ANS -53.01

SILLLE, M.

L. 15048 U.S. NUCLEAR REGULATDRV COMM. CLEMENSON. F. 03318 Arts -19 DFFICE OF NUCLEAR REACIOR REG. A5ME 816 Stil TF-1 AN5 -19.02 WA51tINGION. DC 20555 C0FFMANe F. D.. JR. 0038F U.S. NUCLEAR REGULAlt)RY COMM. ALLISON. D. P. 03315 ASTM 810 -02 ut i lCE 01 IN5Pt C I luf4 L E NI GHC E ME NI IELE PL5 HPEC SC2WG2.3 COL L IN5. J. I. 02560 W 4564 t NG l utt. DL 20Ys 5 A 5t at. F. 5. 15001 ANS -55 i

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f. G.

15070 ASIM C26 -02 M85 44 3 -A-IEEE PE5 hPEC 5C2WG7.2 A5fM C26 '03 RUO. P. I. 15020 ECKERMAN. K. F. 02300 HutMAN. L.G. _15039 AISC TCitt TGO AN5 -18.02 IACWD -A-L AI NAS G. C. 05559 ERICKSON. PETER 08173 hum. M. K. 00969 AN5 -56.04 AN5 -15.80 ASME-BPVC SC XI SGLM LEE. J.V. 15022 FLHGu$hN. M. L. 00614 45ME-BPVC SC x1 5 GWC WGNE ANS -55.04 AN5 -04 IMBAO. E. V. 06064 ANS -55.06 AN5 -04.01 -C-ANS -58.10 -A-LIAW. S. D. 15023 fl5CHtn. D. C. 02479 ANS -56.02 ASME-SPVC SCO SGOA IGt Arts -58.0 5 ANS -56.09 LIPINSKI. R. E. 04073 AN5 -59.03 ANS -59.04 ACI-ASME JC SGD WGC5 fiffralklCK. ROBERI C. 08454 IPPDLIIO. 1. A. 00951 ACI 349 IEEE ped NPE C 5C4 IEEE PES NPEC LIITON F. S. 08874 .tEEE PES NPEC SC4WG4 1 IEEE PES NPEC SCtWGL.0 ASME-SPVC SC III SGET GAMELt. n. M. 04141 IRELAND. R. E. 00952 ASIM C05 ACI-A5ME JC SGMCE WGRP AN5 -54 ASTM C05 -05 ASME-8PVC SC XI 5 GWC ANS -54 01 ASTM E24 -01 GILMAY. J. W. 15012 ANS -54.02 MARCHf 5E. A. R. 0F066 IEEE PE5 NPEC SC 8 WGR.2 AN5 -54.03 AMS -54 GMIME5. 8. K. OSSFt ANS -54.06 AN5 -54.01 AN5 -02.06 "ANS -54.10 ANS -54 06 GHINES. C. 8. 15036 JACK 5DN. R.E. 15016 MARKEE. E. H., JR. 08875 AN5 -56.08 AN5 -02.0F ANS -02.05 HAA55. W. P. 15066 JENG. O. C. 01849 MAfittEWS P. R. 00113 ASME-NPC5 HCU A SCOP ACI-A5HE JC SGO ANSI SCFP -A-IsAt if. A. 5. 089F3 ACI-A5ME JC SGD WGCC -A-MATIU,R. R. 15024 A5Mt-BPVC 50 lit 560 WGC -A-ACI-A5ME JC SGO WGCV -A-ASME-SPVC 500 SCE T IGC A5MC-DPVC 50 ml SGWC WGC5 A5ME-BPVC SC til SGO IGD 4 ASME-BPVC SCD SGE T IGS HaditMANN. M. 15043 JOHN 5DN. GEORGE 15050 A5ME-SPVC SCO SGET WGF A5ME-UPVC SC Ill SGu 6GF ASME-SPVC SC XI IGI MC DERMOII. R.J. 85025 l IIA lE L ION. W. 5. 00855 KANE. J. D. 15065 A5ME-NPCS CDM PT -A-t A5Mt-3Pv0 SC XI -A-ANS -02.19 MC DONALO. p. 85026 - i I 45ME-BPVC SCP 5GI KIESSEL. R. J. 08033 IEEE PE5 NPEC SC2WG2.13 i ASME-DPVC SC P WGNA A5ME-SPVC SC !!! SCO WGWA IEEE PES NPEC SC2WG2.44 ASIM 110 A5ME 816 5084 It-3 NC GOUGH. J. M. 04280 MPC-PVRC JTG FIPM KLINE. J. R. 00482 AN5 -58.04 HPC SC 6 AN5 -48.05 -A-MC MutLEN. R. 5. 02310 MPC SC6 IGMR K NIGis t. JAMES P. OFOTS ANS -02.07 stattn. L. W. 02840 ASME-SPVC 50 til -A-MEYER. J. F. 15047 i ANS -02.11 A5ME-NPC5 ONPE ANS -54.40 HttIEML5 C. J. O F08 5 KNIGHION. G. W. 01052 MEYER, R. O. 08876 A5ML-NPC5 MCU A SCOP WGD AitM Elo ANS -05 HOfMANN. R. H. 15049 ASIM E10 -02 ANS -05.04 ANS -02.06 -A-A58M E10 -10 MILLER. C. F. 01328 ANS -02.54 -A-ASIM ELO -91 IEEE PE5 NPEC 502 Hut M A Yt u. C. II. 00979 KNOX. L. JOHN 15064 IEEE PES NPEC SC2AHSC All-A SMt JC 5s.0u

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1. 5.

68896 ASTP E24 -03

MOORE, V.

A. 0t364 AC I-A S ME JC -A-ASTM E24 -04 IEEE M41 ACI 349 WRC PWRC DO SPPV { IEEE N42 SIN 15 GALLI. A. A. 08054 F IC KLE s t ME R. M. L. 04695 IEEE 5B A5IM E10 ASIM Sie ~ NUMPIV. I.D. 02348 A5fM SCP ASTM 010 -01 AN5 -06.03 5K0VHOLI. D. J. 02210 ASTM S10 -02 NEllEMI AS. V. J. 04202 AN5 -03 ASIM 810 -03 ANS -06.0F SOFFER. L. C3885 ASIM Sto -04 IIPS Nf 3 -A-ANS -02.06 ASIM E20 -04 NHONAN. V. 15051 IEEE PES NPEC SC2WG2.12 RIS. L. N. 08357-ASTM J01 A5ME-BPVC 5C III SGO IGF -A-SPEl5 I. P. 05532 IEEE PES P5RC 50 AN5 -54.10 ANS -54 PANCIERA. V. W. 04470 StuARI. RICHARD J. 01191 ANS -56.03 ANS -51.01 ACI-ASME JC SGMCE -A-ANS -54.10 ANSI SCf P ACI-ASME JC SGMCE WGRP RICHARDSON. J. E. Ot6te IAEA WGFP-A5ME-RPVC SC XI SGWC WGC A5ME-BPVC SC 111 SCO TGEJ PAWilCKl. 5. 5. 01496 slukiEMICE. A. 15035 A5ME-SPVC SC Ill $GO WGP ASIM E10 IEEE PES NPEC SC2AN50 SCHAMSERGER. R. D. 02439 MPC SC 6 IEEE PES NPEC SC2WG2.1 ANS -54.07 Pti tL L I PS. L. E. OSSFt TAM. P. 5. 15048 SERPAN. C. 2..- JR. 01F54 15A NPP50 15C-3 ANS -56.05 ASIM E10 PICkEIT. D. V. 07067 TAN. C. P. 01928 IAEA WGRAM 445 -56.06 ACI-A5ME JC SGO WGCS$ SHAG. L. C. 01766 PHLK. IRAROLO E. 08180 10KAR. M. 08800 ACI-ASME JC AI50 10181 IGD ASIM C05 AN5 -02.02 , ASIM C05 -05 WESELY W. E. O!!21 ANS -02.80 TONDI. 0.. JR. OF420 IEEE PES NPEC M5R POIAPOV5 18. 07610 IEEE PES NPEC SCIWG1.2A IEEE PE5 NPEC SC5WG5.3 A5ME-8PVC SC NI SGLM -A-IEEE PE5 NPEC SC6 WALKER. T. J. 1503L A5ME-HPVC SC Mt SGWC -A-IEEE PES NPEC 3C6WG6.0 WRC PWRC Ei i A5Mf-BPVC SCNC -A-IEEE PE5 PGC 5C50 WALL. I. 3. 0e854 RAJAN. J. R. 1502s IEEE PE5 PGC WGCAP IEEE PES NPEC 505WG5.2 ASME-NPC 5 COM 50VM SGP5 UNGAko. A. R. 15058 VANiv. 5. 5. 01129 RElp. R. W. 15065 IELE PES NPEC SCtWGl.1 IEEE M42 -02 ANS Hlf VILL ALVA.' l. 02004 IEEE N44 -02 R I ANI. L.B. 08SF9 ASME 816 SCH U.S. NUCLEAR REGULATORY COMM., AN5 -51.10 SEEE PES NPEC SC2WG2.3 DFFICE OF STANDAR05 DEVEL. RINALDI. F. 15029 WEISS. 5. H. 05890 WASHINGION. DC 20555 ACl-A5ME JC SGD W GCC ANS -05.01 AL E X ANDE R. R. E. 04153 MHSA. f. 05492 WELLER. RICHARO A.- 01125 HPS SC WG2A REEE PE5 NPEC 50% AN5 -55.01 kCRP 5054 IEEE Pti NPEC SC5hG5.2 U.S. NUCL E AR AEGULAf 0RV COMM. ANDERSON. W. F. 04027 RuhENillIN. L. 5. 0F113 0FFICE OF NUCLEAR REG. RES. ANS -50.01 MPC SC6 W A 5811 NG ION. DC 20555 A5ME-SPVC SC Mt MPC 506 IGCP ABB[V. R. F.. JR. 07863 ASME-3PVC SC5V SCilAut R. F. P. 01F09 AN5 -02.03 t ASME-NPCS ONFE -A-ACI-ASME JC SGO WGCV Ol5ALVO. R. 13009 A5ME M45 N551 SC ASCE PD AN5 -05.01 ARLOTTO. G. A. 00047 A5CE SD SR FEli. R. 15081 ANS NPPSC SC Ht ME L. R. J. Olft1 IEEE PC5 ICC TF12-40 AN5 NtB ANS Ntt -A-KELSLR. C. N. 02465 AN5 SSC Sil A P AK L R. J. W. 0012w ANS -54 ANSI NSMS ANS -S0.00 LYNN. E. K. 01329 ANSI N5MS OMP e l

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8. 5.

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00249 SPECIAL APPLICATIONS INte.68 AN5 -19.02 REACIOR PHYSICS VERMS E SE0V HOL I. D. J. 02210 KET2LACH. M. 01031 PARANETER5 (N5228 AN5 -03.05 NUCLEAR POWER PLANT AN5 -08.12 CRITICALITY CONIROL OF U-PU STEELE. M. L. 15041 i SIMUL ATORS FOR USE IN OPERATOR TRAINING FUEL NEXTURES int 6.100 AN5 -50 CMG2 PWR COM0lTIONS OF DESIGN IN6F58 EEllLACH, M. 01031 COORDINATION WORKING GROUP i HOLMAN. J. J. 08853 AN5 -0s.13.1 SOLIO ANGLE METH00 int &.tli WICHMAN. R. R. 02093 ANS -0 3.0F STANDARD FORMAT E CONTENT OF KETIL ACH. M. 01031 ANS -51.0L NUCLEAR SAFETV CRITERIA FOR EMERGENCY PLAN 5 IN5148. EMFRGENCY AN5 -09 NUCLEAR TERMIN0 LOGY E UNIIS DEstGN OF PWR PLANTS INit.21 CONTROL CENTERS IN6049.IN6458 Ht:*. E. L. 07875 PANCIERA. W. W. 01470 Cut L INS. HARut0 E. 089F3 ANS -10 MATHEMATICS g COMPUTATION ANS -51.04 CRITERI A FOR ACCEPI ASILITY OF J An60Ce:I AN. M. 3 ALIERNAIE 08980 RDPP L.I. 15018 SAFEIV-RELATED OPERATOR ACTIONS IN660) ANS -04 REACIOR DVNAMICS E CONIROLS ANS -15 SPERATION OF RESEARCH REACTORS SECKHAM. O. H. 15060 IERGusoN. R.L. 00614 CARTER. T. J. 01325 AN5 -51.10 AURELI ARY FEEONAIER FOR PWR ANS -04.01. DESIGN OF SYSTEMS THAT C ONSI ASL E. G. L. 15054 PLANTS IN46TI PERFORM PROIECTIVE FL'4CTIONS CURits. J. R. 04375 IMSRO E. W. ALIERNAIE 06864 IERGuSON. R. 1. C el4 I R MAN 00684 ANS -15.10 OECOMMI55 BONING OF RESEARCH RIANI. L.S. OSST9 ANS -04.03 .02 CRITERIA FOR APPLICATION REACTORS IN550) ANS -52 BWR MANAGEMENT (N273) OF DIGIIAL CDMPUIERS IN PROIECTION ERICKSON. PETER 08373 $AER. R. L. 00063 5V5tEMS ANS -15 11 RADIOLOGICAL CONTROL & 5AFETY ANS -52.0L DEstGN CRITERIA FOR CAlv0 J. A. '02337 (N6209 SI4ll0 NARY SWR IN212) AN5 -05 ENERGY L FI5SION-PRODUCI AELEASE CUnits. J. R. 08375 BAER. R. L. 00065 ML yt n. R. II. 08886 ANS -15.14 PitV5ICAL SECURITY OF RESEARCH ANS -52.04 SWR FLulo SYSTEM SINGLE AN5 -05.01 DECAY ENERGY RELEASE RATES REACIORS INF001 FAILURE CRITERIA F ULLOwtNG SieUIDOWN OF UR ANluM-FUELED CONSTABLE. G. L. 45054 NOR8 ERG. J. A. 15057 IHERMAL REACiuR IN18.65 ANS -15.16 EMERGENCY PLANS FOR RESEARCH ANS -53 HIGR MANAGEMENI pl5ALVO. H. 15009 REACIOR5 CLARK. ROSERI A. 003F2 Wfl55.

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0d490 CURits. J. R. 083F5 ANS -53.0L HIGR DESIGN CRITERIA IN2131 AN5 -05.04 tutt PLENUM GA5 ACIIVIIY AMS -15.18 ADMINISTRAilVE CONIROLS CLARK. RosERT A. 003T2 (N2181 CARIER. I. J. 01325 AN5 -54 DESIGN CRITERIA FOR 5 fall 0 NARY HE YE R. R. U. 08876 CONSIABLE. G. L. 15054 LMFSR (N2158 i ANS -06.03 SillELD PEMIORM ANCE EVALUAIION ANS -16 ISOIOPES E RADIATION IRELANO A. E. 00952 int 8.9) SM t ill. DONOVAN A. 01940 KEL8ER. C. N. 02465 i MUR P81v. I.D. 02348 ANS -1s ENVIROMMENTAL IMPACT EVALUAI!GN MARCHESE. A. R. 07066 ANS -06.06 C At CUL ATION L ME ASUREMENT OF GalLL. RICalARD 01013 Rie. L. N. 08057 i DIRECI L SCAIIERED RADIAllHN IN3463 AMS -18.01 SOURCE TERM SPECIFICATION AN5 -54.01 LNFBR GENERAL DESIGN CalIERIA l MHtGtH. W. E. 0108f IN2378 (AN5/-18.01//.01. //.02. E //.03 IN2848 j CMS -06.0F R ADI AllDN 20NING FOR DESIGN HAVE SAME MEMSERSHIPl IRELAND. R. E. 00952 Of NtKLEAR POWER PLANIS IN65tl CAR 0lLE. F. P. 15067 MARCHE 5E. A. R. 07066 NlllEMIAS. V. 8. 04202 ANS -18.02 ENVIRONMENI AL NONIIORING E ANS -54.02 LNFBR GENERAL DESIGN SkHPLC. I. C. 0450F DAI A EVALUATION IN33i CONSIDERATIONS .CNS -06.08 ARE A C PROCES5 RA01 AIRON ELKERMAN. K. F. 02380 IRELAND. R. E. 00952 MONIIDRING SYSIENS AN5 -18.05 TERRE 5tR ECOLOGICAL AN5 -54.03 LMFSR COMIAINMENT DESIGN nt UC K. SE THOL R 08127 5URVEY5 EN5198 CalTERIA AN5 -08 F l55tuNABL E MATERI ALS OUISIDE B ALL ARD. R.L. 08865 BARAN0W5EY. P. W. 08066 KLINE. J. R. ALIERNAIE 00482 IREL AND. R. E. 00952 i

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02458 FOR REACTOR STANDARDS ANS -55.01 PWR C SWR SOLIO WASTE SYSIEM ANS -58.03 PHYSICAL SEPARATION ARLotto. G. A. 00047 DE5IGN IN!989 EEOUIREMENIS FOR 5AFETY SYSTEMS int 02) ANSI M5MS PC M5h4 PL ANNING COMMIIIEE WEL L ER. RICHARD A. 01425 FISCHER. D. C. 02479 ARLDITO. G. A. 00047 ANS -55.04 LWR GA5EDUS RADWA5TE ANS -58.04 TECHNICAL SPECIFICATEDNS ANSI NSFC NUCLEAR STANDAR05 POLICY PmDC ESSING SYSTEM IN200) MC GOUGH, J. M. 08200 COMdlifE5 LtE. J.Y. 15022 AN5 -59.02 SAFETY-RELATED VENitLATION MI NOGUE. 2. 8. 0134% AN5 -55.06 L10UID RADI0 ACTIVE WASIE SYSIEMS IN1895 ANSI SCFP 51EERING CONNEITEE-FIRE PRDCESSING SYSTEM 5 LWR BELLAMY. R. R. 08867 PROTECilDN COLL INS. J. I. 02560 NOIL E Y. D. P., SR. 15045 MATIHEWS. P. R. ALIERNAIE 00113 LEE. J.Y. 15022 ANS -59.03 5AFETY-RELATED CONTROL AIR PANCIERA. W. W. 01470 AN5 -5 6.02 CONTAINMENT ISOLAflDN DESIGN SY$TEMS INIS75 02479 CLASS EARIN STRUCI ASCE COS DA DESIGN E ANALYSIS OF 5 AFETY IN2Fil FISCHER. D. C. I MBR O. E. V. 06864 ANS -59.04 LWR FIRE PROTECTIDN CARIERIA CHEN. J. f. 15006 AN5 -5 6.0) 150t AllDN Of LOW PRE 55URk INis.108 A5CE C05 IC MS NOCLEAR STANDARDS TA1A SYST EM CONNECTED 10 THE MCPS IN193) IMBRO. E. V. 06864 COMMIITEE MlluuAN. J. L. 02534 AM5 ASM ADVISDRV COMMITIEE FOR NUCLEAR CO5TELLO. J. F. 08363 A4 5 -5 6.04 PRES 5URE C IEMPERAtuRE MATERIAL 5 HOSA A5CE PD POWER Olvl5EDM ANAL YSIS IN6911 GOEL. W. 5. 05545 5CHAUER. F. P. 01I09 LAINAS. G. C. 05589 AN5 NPPSC NUCLEAR POWER PLANT 5tANDARDS AECE 50 SR SAFETY AND RELIASILITY AM5 -5 6.05 PWR C SWR CGNfAIMMENT SPRAY CDMMITIEE SCH A UE R. F. P. 01709 l SYSIEN DE51GN IN58th ARLOITO. G. A. 00047 A5BS NIC NATIDNAL INVE5flGATIONS IAM. P. 5. 15D48 AN5 Nf6 NUCLEAR CRITICALITV SAFETY CONNtiiEE AN5 -56.06 PWR CONT AINMENT WENitL ATION STEVEN 5ON, R. L. 01882 MONIGUMERY. J. M. 15056 i SYSIEMS IN2Fil AN5 NIT RESEARCH REACTDRS. REACIDA A5ME 816 SCH OPERASILITY STANDARD 5 FOR PICutII. D. V. 0706F PHY5105 C RADIATION 5HIELDING NUCLEAR VALVE ASSEM0 LIES I5uBCDMMIITEE AN5 -56.08 RE ACIOR CONI AINMENI LE AE AGE REID. R. W. 15063 H8 i IESIING REQUIREMENis IN2F48 SCitLMEL. R. J. ALTERNAIE 01751 ARL0tIO. G. A. 00047 GH I ME 5. C. I. !$036 AMS Mle NUCLEAR DESIGN CRITERIA VILLOLVA. I. 02004 SEvFall. E. W. 00835 ARLollu. G. A. 00047 A5ME 816 1CH IF-3 FUNCTIONAL Ste AP Au t R. J. W. 00129 AMS Ml8-20 PROGR AM FOR COLLECTIDN OF QUALIFICATION Of VALVE ASSEMSLIES AN5.-56.09 PWR ENVIRONMENIAL ENVELOPE 5 REL I ASILITY DAT A DN NUCLE AR POWER PL ANTE CLEMENSON. F. 03318 1 IN687) ItARIFIELD. R. A. 08339 KEE55EL. R. J. 08033 IMunn. E. V. 06064 AN5 N19 NONRADIDLDGICAL ENVIRONMENIAL A5ME S16 5CN SIEEL VALVE 5 AN5 -5f.08 LWR FUEL-StANDLING SYSTEM EFFECT5 E0VAC5. J.N. 08804 DESIGN IN2C88 LRILL. RICalARD 08053 A5ME CONAGT NUCLEAR AIR & GAS TREAINENT Nil 5tN. C. W. 01411 ItEL D. L. E. ALIERNAIE 022F6 CDM. ANS -57.02 OE5IGN 08JtLilVE5 FOR LWR ANS N48 RADIDACilVE WA5tE NANAGEMENI SELLAMYe R. R. 08867 1

l ASME K10 4 SEP 5 B78 I ASME Kio HE ti IRANSFER EQUIPMENI NOONAN. W. ALIERNATE 15051 A5ME-3PVC SC El SGGC WG5E SIANDAROS E . NElFF. D. D. 08595 5 HAW. H. K. 00793 EVALUATIONS A5ME NED A5C RADWAllE SYSTEM COMMIf FEE ASME-SPVC 5C III SGO ICS $ nutters ARN0f. E. G. 00049 hunEE. W. C. 15003 SHAW. H. K. 00793 ASME-SPVC SC II SGLM LIOUID MEi&L A5ME M45 REACIOR PLANil C THEIR ASME-SPVC SC III SGS WGC CONIAthMENI COOLED SYSTEMS MAINVENANCE HAftt. A. 5. ALIERNAIE Oe973 HUM. M. K. 05969 Aktollo. G. A. 00047 WICHMAN. E. R. 02093 P0fAP0v5. u. ALIERNATE 07610 MONRISON. W. M. ALIERNATE 01376 ASME-SPVC SC III SGO WGC5 COMPONENT A5ME-SPVC SC XI SGPV TESTING OF PUMP 5 & A5ME M4S -02.4 F WELDING PROCESS CONfROL SUPPORTS V ALVE S BA80ADA. A. 03366 WICHMAN. K. R. 02093 POR5E. L. 01545 ASME N45 N551 COMMITIEE ON STANDADOS A5ME-SPVC SC III SGD WGP PIPING-ASME-SPVC SC II EGMC WAlfR COOLED 5 0R PUMP SYSTEMS RICHAROSON. J. E. Ot6ts SYSTEMS MAnthus. E. C. 03369 A5ME-SPVC SC III SGO WGPM PUMP 5 CAMetE. R. M. 01141 POR it. L. 01545 BRAMMER. H. L. 00203 POTAP015. U.. A5ME N45 N551 50 STEERING COMMITTEE ASME-BPVC SC III 5GO WG55 CORE ~ ALTERNATE 07640 A NUE N SON. W. F. 04027 5UPPORI STRUCTURES A5ME-BPVC SC Mt SGWC WGC CONI AINNENT l A5ME M45 NS51 IF-2 PUMP SEALS MILLMAN. G. C. 074T9 STUAmi. RICHARD J. 01198 IA80ADA. A. 03366 A5ME-SPVC SC III EGO WGV VES5ELS ASME-sPVC EC NI 5GMC WGC5. COMPONENT -A5ME SCC COMMiifEE FOR NUCLFAR RANDALL. P. N. 06300 SUPPORT 5: WORK GROUP IN5PECTORS AND SPECI ALI2ED ENGINEERS ASME-SPVC 5C III SGO WGWA VALVES HAFIZ. A. 5. 089F3 kEINMulH. G. W. 08886 MIE55EL. R. J. C1033 5 HAW. H. E. ALTERNAIE 08793 ku lH E RF DAD. W. R. AL T ER NA T E 15030 ASME-SPVC SC Ill 5GET ELEVATED A5ME-8PVC SC XI SGWC WGE EVALUAfl0N A5HE-8PVC MAIN COMMIffEE IEMPERATURE CONSTRUCTION C HE NG. C. V. 02600. eninan. R. J. 00188 BROWN. E. J.- ALIERNAIE 08364 ASME-SPVC SC XI SGWC WGGI STEAN ASME-BPVC SC II SUSCOMMITIEE ON MAIERI AL LIIION. F. 8. 04574 GENERATOR INSPECTION SPECIFICAllDNS ASME-8PVC SC III SGFE F,ABRICATION & FRANE. L. 08766 Wo0LRIDGE. E. D. 15013 EXAMINAllGN A5ME-BPVC EC XI SGWC WGNE A5ME-8PVC SC II SG5FC STEEL FORGINGS. CONM40 11. F. 06295 NONOESTRUCilVE EMAMINATION CASTING 5 ANO 80LilNG A5ME-BPVC SC III SGG GENERAL liUM. M. K. 08969 Wikt R I DGE. E. O. 15013 REQUIREMENIS A5ME-SPVC SC MI SGWC WGAR REPAIRS E A5ME-8PVC SC II SG5P SIEEL PLAIE5 805NAK. R. J. 00198 REPLACEMENT PARIS WOGLRIOGE. E. O. 15033 A5ME-8PVC SC III SGG WGOA GUALITY HENDERSON. J. S. 00F59 A5ME-BPVC 50 III 5C IIIs NUCLEAR POWER A5SURANCE C STAMPING A5ME-BPVC SC Mt SEWC WG5 stA40aR05 80$NAK. d. J. 00488 MILHOAN. J. L. 02534 CHENG. C. V. 02680 RHl6Hl. JAME5 P. ALTERNATE 07078 A5ME-BPVC SC III SGM MATERIALS A5ME-BPVC SC XI TGC5 CERTIFICATION AND A5ME-SPVC 50 lIl AHIGFRP A0 HOC IASK TABOADA. A. 03366 STAMPING OF REPAIRS ANO REPLACEMENIS GROUP DN F IBERGL ASS REINFORCED PL ASIIC ASNE-SPVC SC III SGM IGCC CODE CASE HENDERSON. J. d. OEI59 PIPE C00ROINATION A5ME-BPVC 5C II IGI IN5PECTION OF CLASS Pup 5E. L. 01545 WoutRIDGE. E. D. 15033 2 SYSTEM 5 l .A5ME-BPVC 50 lli 560 OLSIGN A5ME-8PVC SC III SGM IGC5 ADDITIONAL SRDWN. E. J. 08364 WICHMAN. %. R. 02093 MAIERI AL5 FOR COMPONENI SUPPORIS JDMNSON. GEORGE 15050 ASME-8PVC 50 III SGD TG8 APPENOIM 8 WOOLRIDGE. E. O. 15333 A5ME-SPVC SC XI WGC CONCREfE PRES 5URE WICHMAN. K. R. 02093 A5ME-DPVC SC Ill SGM TGT TOUGHNESS COMPONENTS A5ME-BPVC SC III SGO IGDA OYNAMIC R AND AL L. P. N. 06300 ASHAR. H. G. 0740T ANAL YS l 5 ASME-SPVC 5C III SGPR PRES 5URE RELIEF ASME-OPVC SCO SGOA TGI INELA5fl0 CHAN. 5. P. 85005 CHERNY. F. C. 08738 SEHAvlDR GuPIA. R. P. 08362 A5ME-EPVC SC V WGAE AC005fl0 EMISSION LIAWe B.D. 15023 JLNG. D. C. 08149 GOtt. W. 5 05545 ASME-SPVC SCO SEET ELEVAIED REMPERAIURE ASME-SPVC SC III 560 IGEJ IA54 GROUP ASME-3PVC SC XI SC KIs NUCLEAR INSERVICE DEstGN ON Rut ES FOR CL A55 8 EEP AN51DN JOINIS INSPECil0N SROWN. E. J. 0e364 RICHARD 50N. J. E. 01618 ANDER5UN. W. F. 04027 ASME-SPVC SCO SG2T TGC CORE SUPPORT A5HE-BPVC SC III SGD IGF FAULIED HAlELtdN. W. 5. ALIERNAIE 00855 MAITU. R. K. 15024 COH0lilON A5ME-8PVC SC XI SGGC GA5 COOLED SYSTEMS A5ME-SPVC SCO SGET TG5 SUPPORIS HAnifMANN. M. 15013 IRANK. L. OSF66 EMIERNAL ID COMPONENTS IN CREEP SERVC

4 5 A5in E10 -81 Mallu. R.' K. 35024 REQUIREMENT 5 SUSCOMMITIEE LITIDN. F. B. 04874 i l ASME-8PVC SCD SGET - WGCA ELEVAIED MORRI50N. W. M. Ot37E IDKAR. M. 04880 l TEMPERAIURE CREEP ANALVil5 A5ME-NPC5 MCOA SCGR WGA AUDIIING IN45 ASTM C05 -85 WUCLEAR APPLICATIONS 8MDWN. E. J. 0e364 -02.128 L IITON. F. S. 08874 i ( ASME-SPVC 500 SGET NGF CREEP FATIGUE LONG. F. J. Otter SIEVER. K. G.. Otte5 MAITU. R. K. 15024 A5ME-NPC5 MCOA 15C MC MANUFACTURING E IDEAR. M. 04400 ( A5ME-8PVC SCD SGD OPENINGS CDN5TRUCTID4s SusCOM. ASTM C16 INERMAL AND CRYOGENIC ill A W. II. K. 08793 PERANICH. M. W. 04982 INSULAflNG MATERIALS A5ME-SPVC 5CNC NUCLEAR CERIIFICATION ASHE-NPCS MCOA SCP0 PERSONNEL EI55. A. L. 01136 l P01APOV5. U. ALIEkNATE 07610 QUALIFICATIDNS IN45 -02.068 ASTM C16 .20 PREFDRMEO SLDCR & PIPE RulHERFORD. W. R. 85030 L DMG. F. J. 08187 INSULATION THERMAL INSULATING CEMENT ASME-BPVC SCP SGF5 FATIGUE STRENGTH A5ME-NPC5 NCGA SCPO WGA AUDIIDR Elis. A. L. 01136 Mit L MAN. G. C. 0F419 CERIIFICATION REQUIREMENTS IN45 2.25) ASTM C16 .32 INERNAL IN5ULATION GENERAL A5ME-8PVC SCP SGI SUSGRDUP DN TDuGHNE55 LDNC. F. J. 01187 IEST METH005 H AZ E L iuM. W. 5. 00855 A5ME-NPC5 MCOA SCRM SECOR05 MANAGEMENT EISS. A. L. 01336 A5ME-8PVC SCP WGNA WORKING GRour UN IN45 -02.091 AllM C26 FUEL. CONtRDL. E N00ERAIDR NUCLEAR APPLICAIIDNS CAMPBELL. W. E.. JR. 08977 MAIERIAL5 FDR NUCLEAR APPLICATIONS ll Af E l l DN. W. 5. 00855 A5ME-NPCS ONFE QUALIFICATION TESTING FOR COOPERSTEIN. R. 04707 ASME-8PVC SC5V SAFEIV VALVE REQUIREMENT 5 FuwCTIONAL ADE00ACY SIEVER. K. G. 01485 ANDER50Ne W.F. 04027 ANDERSON. W. F. ALIERNATE 0402F litutSKY. N. 15034 ASME-NPC5 NUCLEAR POWER CUDES & KNIGHT, JAMES P. 07078 ASTM C26 -02 FUEL 5PECIFICAilDNS 5tANDARD5 COM. A5NT 30 NCC NUCLEAR COMPONENTS C00PERSTEIN. R. 04F07 li ~ AntulIO. G. A. 00047 COMMITIEE IINDUSTRIAL OlV.l HOUSIDN. M. O. 06545 i A5ME-NPCS COM COMMIIIEE ON DPERATION & G DE L. W. 5. 05545 ASTM C26 -03 CohiRDL MATERI AL M AIN IF N A NC E A5NT MO PRC PENEIRATING RADI ATION SPECIFICATIDMS SHIEEEK. J. 08936 CDMMITTEE COOPERSIEIN. R. 0470F .i A5ME-NPCS COM PI Pf RFORM ANCE Test!NG: JGNES. JAMES A. 01152 H005fDN. M. O. 06545 SuSC UM. ASNT'POO PER$DNNEL QUALIFICATIDN OIV. ASTM C26 -05 IEST MEIN 005 s tENDE R 50N. J. B. 08F59 GOEL. W. 5. 05545 BROWN. WILLARD S. 03869 MC DERMoli. R.J. ALTERNAIC 15025 MC GUIRE. 5 A. ALTERNAIE 04139 CDOPERSIEIN. R. 0470F ASME-NPCS COM Pt WG5RV SAFETY RELIEF ASNT P90 PG PERSONNEL QUALIFICATIDNS ASIM C26 -06 SIAll551C AL APPLICAllDNS VAtVE5 HERDt. A. R. 15014 IUREL. 5.P. 01331 C ERHf. F. C. 00738 ASTM AOL SIEEL. SIAINLE55 STEEL. ANO AliM 019 WAIER ASME-NPCS COM 50VM VISRAlinN MONITORING RELAIED ALLOV5 EISS. A. L. Oll36 MiltMAN. G. C. OF4TS IA80ADA. A. 03366 ASIM 919 -09 MEMSRANES & IDN EECHANGE I A5ME-NPCS COM SCVM 5 GPS VISRAilDN ASTM S10 RE ACilVE & REFRACIDRV LEVELS MATERIAL 5 MONIIDAING SueGROUP DN PIPING SYSTEMS PICKLESIMER. M. L. 04695 EISS. A. L. 01136

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A. 01183 MPC SC6 IGNR MATERIAL 5 FOR NUCLEAR KASTNER. J. 150lf INMN NIS -11 CERIEFICAll0N OF NUCLEAR REACIOR$s TA5K GROUP NCRP SC41 R40IAil0N RESULTING FROM MATERIAL 5 MANAGERS INIS.2el HAZELION. W. 5. 00a55 NUCLEAR PONER GENER ATION IUREL. 5.P.- 01335 MPC-PVRC JIG FIPM JetNI IA5K GROUP DN COLL INS, J. I. 02560 85A NPPic NUCLEAR POWER PLANI STO5. FRACTURE TOUGHNESS PROPERTIES FOR NCRP 5C54 SiOASSAY FOR A55E55NENI OF-MEN 2tNGER. E. C. 020TT NUCLEAR COMPONENTS INTAKE OF R ADIONUCL ISA NPPEC I5C-2 HARDWARE IN5fALLAil0N HAfEL70N. W. 5. 00855 ALEXANDER. R. E. 04153 AND INTERFACES 455 IC5P INTERSERVICE NFPA AEC AfDMIC ENERGY COMMlifEE 00215. J. E. 05574 COMMlifEEssiANDAR05 POLICV ON NOILEY. D. P.. 58. 15045 ISA NPPSC 150-3 SY5 FENS APPLICATIONS MEIRICATION NSF 16 NATIONAL 5ANII4fl0N FOUNDATION PolLLIPS. L. E. 088T8 PORSE. L. 01545 NC GUEREe 5. A.- 0413t 154 NPP50- 15C-4 FUNCTIONAL REQUIREMENTE Ne5 N43 EQUIPMENT FOR NON-MEDICAL SNAME M-13 NUCLEAR SHIPS NENilNGER. E. C. 020TT RADIATION APPLICAtlONS 805NAKe R. J. 00100 15A NPP5C 150-6 IN-PLANT IE5flNG AND BARKER. R. F. 00085 NRC HAC ASNS NELOING SIAINLE55 STEELS M AINIEN ANC E MREGER, W. E. ALTERNATE 0108 T ADVISORY SusCOM. WENilHGER. E.C. 020TT NS5 443 -03 INDUSTRIAL RADIOGRAPHY HER0i, A. R. 55014 150 TC85 IECH. COM. ON NUCLEAR ENERGV MC GutRE. 5. A. 04139 NRC PVRC DO SCOA OYNAMIC $NALV515s 8 AMERICAN MEMBERS ONLY) NSS N43 -03.02 RADIAT10N GAUGES IN534) PRES 5URE COMPONENIS HANAuER.

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i l SOCIETY AND ORGANIZATION ACRONYMS AAPM American Association J Physicists in Medicine 4 ACGIH American Conference of Governmental Industrial Hygienists ACI American Concrete Institute ACI-ASME American Concrete Institute-American Society of Mechanical Engineers AIA American Insurance Association AICHE American Institute of Chemical Engineers AISC American Institute for Steel Construction ANS American Nuclear Society ANSI American National Standards Institute ASCE American Society of Civil Engineers ASIS American Society for Industrial Security ASME American Society of Mechanical Engineers ASNT American Society for Nondestructive Testing ASTM American Society for Testing and Materials AWS American Welding Society HPS Health Physics Society IAEA International Atomic Energy Agency IEC International Electrotechnical Connission IEEE Institute of Electrical and Electronics Engineers INMM Institute of Nuclear Materials Management ISA Instrument Society of America ISO International Organization for Standardization MPC Metals Properties Council NBS National Bureau of Standards NCRP National Council on Radiation Protection and Measurements NFPA National Fire Protection Association NSF National Sanitation Foundation WRC elding Research Council

A NOTE ABOUT SOME CONVENTIONS USED IN THE COMPUTER LISTING OF NRC FILE 15 "NRC PERSONNEL INYOLVED IN THE DEVELOPMENT OF NUCLEAR STANDARDS" 1. The file is intended to list the membership of NRC personnel in comittees that develop national standards. NRC personnel parti-cipating should have a letter signed by the Director, Office of Standards Development approving their nomination to these comittees. 2. The file lists committees by their secretariat so that all comittees manaced by a particular secretariat can be identified. Thus ANS 18-20 is an ANS comittee and it is not listed as ANSI 18-20 even though the designation "18-20" is an ANSI designation. Theoretically, virtually all the comittees listed could be identi-fied as ANSI comittees but this would make this file less useful. 3. The file identifies comittees in a format convenient for computer sorting. Where most people would write ANS 2.1 the listing prints ANS-02.01 so that the computer will list the comittees in proper secuence. 4 The file often identifies the hierarchy of the standards comittee organization, ASME-8PVC SC III SGD WGC " Containment" indicates that this is a working group on containment that reports to the subgroup on design that reports to subcomittee III that is part of the Boiler and Pressure Vessel Code of the American Society of Mechanfcal Engineers. 5. The file identifies comittees by their title. In the absence of a well known title for the comittee itself, the title of the standard (s) the comittee is develcoing may be listed, but this is only a partial list of the standards. Space limitation prohibits listing more than one or two standards. 6

[ o } Privacy Act Statement NRC-15 1 System Name:, National Standards Committee Membership Files - NRC System Location: Primary System - Office of Standards Development, NRC, 5650 Nicholson Lane, Rockville, Maryland Duplicate Systems - Duplicate systems exist in whole or in part at the National Institute of Health Computer Facility, c/o the Office of Management and Program Analysis located in the Mary. land National Bank Building, 7735 Old Georgetown Road, Bethesda,, Maryland. Categories of individuals covered by the system: NRC employees who are serving on committees, subcomittees, working groups, etc., that are _ developing nuclear standards. Categories of records in the systam: This system is a comprehensive record of NRC personnel on the nuclear standards comittees and contains members' names and the names of the committees to which they belong. Authority for maintenance of the system: Section 161(b), Atomic Energy Act of 1954, as amended, 42 U.S.C. 2201(b). Routine uses of records maintained in the system, including categories of users and the purposes of such uses: These records may be used:

a. To provide information to persons or agencies requesting this information, including but not limited to:

(1) persons using the NRC Public Document Room and (2) the Department of Energy RDT Standards Office of Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee. ORNL uses this informa-tion as part of a document titled, " Personnel Involved in the Development of Nuclear Standards in the United States" and the National Technical Information Service U.S. Dept. of Comerce, sells this document to the public.

b. For the routine use specified in paragraph number 5 of the Prefatory Statement.

Policies and practices for storing, retrieving, accessing, retaining, and disposing of records in the systam: Storage: Records are maintained on lists and computer tape and disk. Retrievability: Records are indexed by the individual's name, by individual's office or region and by the committee title. i Safeguards: Open access. Retention and disposal: Updated when inforatation is out of date. The informa-tion is retained until the person is no longer a member of the comittee or l ,,,.3 I

, no longer an NRC employee, whichever occurs. first. Systemmanager(s)andaddress: ) Director Office of Standards Development U.S. Nuclear Regulatory Comission Washington, D.C. 20555 Notification procedure: Director 1 Office of Administration U.S. Nuclear Regulatory Comission ~ Washington, D.C. 20555 Record access procedures: Same as " Notification procedure." Contesting record procedures: Same as " Notification procedure." Record source categories: Information in this system of records comes from the individual to whom it applies or from his supervisor. l}}