ML20199H978

Forwards,For Review,Draft Rule Text Re Amends to 10CFR70 Which Will Require Certain NRC-licensed Facilities to Develop & Implement Safety Program Based on Performance of Integrated Hazard Analysis

ML20199H978
Person / Time
Issue date:	01/14/1999
From:	Paperiello C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Obey C LABOR, DEPT. OF
References
NUDOCS 9901260008
Download: ML20199H978 (21)

Text

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O UNITED STATES j

j NUCLEAR REGULATORY COMMISSION

& WASHINGTON, D.C. 2006 Hoot g

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.....[ January 14, 1999 Mr. Craig Obey, Director 1

Office of Intra-Governmental Affairs Occupational Safety and Health Administration U.S. Department of Labor j Room: N3841 i 200 Constitution Avenue Washington, D.C. 20210

SUBJECT:

PENDING U.S. NUCLEAR REGULATORY COMMISSION REGULATIONS FOR DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL 4

Dear Mr. Obey:

The U.S. Nuclear Regk .cey Commission (NRC) is currently in the process of amending its  !

regulations (10 CFR Part 70) for domestic licensing of special nuclear material. The amendments will require certain NRC-licensed facilities to develop and implement a safety program based on the performance of an integrated hazard analysis. Generally, the facilities that will be affected by these amendments are nuclear reactor fuel fabrication facilities and some uranium enrichment facilities. In addition to special nuclear material, these facilities may also possess quantities of hazardous chemicals that subject them to the Occupational Safety and Health Administration's (OSHA's) process safety management regulation (i.e.,29 CFR 1910.119).

The regulatory amendments are intended to be consistent with the October 21,1988 NRC-OSHA Memorandum of Understanding (enclosed). That is, NRC regulatory purview would include radiological risk, chemical risk produced by radioactive materials, and facility hazards

, (e.g., chemical, fire, electrical and mechanical) which could affect the safety of NRC-licensed materials and thus present an increased radiological risk; however, NRC would not have regulatory purview over facility hazards that may result in occupational risks but do not affect the safety of NRC-licensed materials.

l l Since the Spring of 1998, we have been communicating with OSHA by providing, via postal service and electronically, copies of the proposed rule and all related documents, and by inviting OSHA to attend Commission and public meetings on the NRC regulatory revisions.

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l

$vb Upon its review of a previous version of the rule, the Commission directed the NRC staff to {

,. revisit the issues related to chemical safety and further discuss them with the affected

! agencies, to understand the respective authorities and the degree to which those authorities are l implemented. In addition, the Commission directed the staff to discuss the relevant documents with stakeholders and the public and submit a proposed rulemaking package in May 1G99.

(Stakeholders and the public will also have an opportunity for formal comment N d//

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C. Obey January 14, 1999 L once the Commission approves a rule for publication as a proposed rule.) Since September 1998, we have held two public meetings (which OSHA staff attended), and have established a World Wide Web site (http://techconf.lln!. gov /cgi-bin / messages? dom _lic) that contains discussion threads and a library of oocuments related to this rulemaking. As a result of discussions at those meetings and written comments received, the attached two sections of the rule text were developed. These two sections are intended to implement the NRC areas of responsibility within the context of the 1988 MOU and be consistent with the respective statutory authorities of NRC and OSHA. Accordingly, we would greatly appreciate your views on the attachment.

To facilitate submission of a proposed rule package to the Commission in May 1999, we would like to resolve in January any major issues with the draft rule language itself, particularly for the attached two rule sections. Again, your views on the attached draft rule text would be appreciated. It would be desirable if your views could be provided by January 29,1999.

Should you like to arrange a meeting or have any questions, please contact Mr. Theodore Sherr on (301) 415-7218 or Mr. Andrew Persinko on (301) 415-6522.

1 Sincerely, (Original signed by)

Carl. J. Paperiello, Director Office of Nuclear Material Safety and Safeguards

Enclosure:

Draft changes to 10 CFR 9970.60 and $70.62 NRC Memorandum of Understanding DISTRIBUTION:

NRC File Center NMSS Dir Ofc r/f NMSS r/f FCSS r/f SPB r/f FRIB Task Force r/f G:\TaskForce\shaltr.wpd (*See Previous Concurrences)

OFC FCSS E FCSS E FRIB E OGC FCSS[ NMSSn/)

NAME *RLewis:al *APersinko *TSherr *KWinsberg ETenhck CJhenello DATE 12/03/98 12/13/98 12/03/98 01/05/99 01/ // /99 01/ /N /99 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY l

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.Y C. Obey January 14, 1999 once the Commission approves a rule for publication as a proposed rule.) Since September i

1998, we have held two public meetings (which OSHA staff attended), and have established a l World Wide Web site (http://techconf. lint. gov /cgi-bin / messages? dom _lic) that contains i discussion threads and a library of documents related to this rulemaking. As a result of i

discussions at those meetings and written comments received, the attached two sections of the rule text were developed. These two sections are intended to implement the NRC areas of responsibility within the context of the 1988 MOU and be consistent with the respective l

statutory authorities of NRC and OSHA. Accordingly, we would greatly appreciate your views on the attachment.

l To facilitate submission of a proposed rule package to the Commission in May 1999, we would like to reso!,a in January any major issues with the draft rule language itself, particularly for the attached two rule sections. Again, your views on the attached draft rule text would be appreciated. It would be desirable if your views could be provided by January 29,1999.

Should you like to arrange a meeting or have any questions, please contact Mr. Theodore Sherr on (301) 415-7218 or Mr. Andrew Persinko on (301) 415-6522.

Sincerely, (Original signed by)

Carl. J. Paperiello, Director Office of Nuclear Material Safety

! and Safeguards l

Enclosure:

Draft changes to 10 CFR SS70.60 and Q70.62 NRC Memorandum of Understanding DISTRIBUTION:

NRC File Center NMSS Dir Ofc r/f NMSS r/f FCSS r/f SPB r/f FRIB Task Force r/f .M' G:\TaskForce\shaltr.wpd (*See Previous Concurrences)

OFC FCSS E FCSS E FRIB E OGC FCSS[ NMS,Sa f)

NAME *RLewis:al *APersinko *TSherr *KWinsberg ETenhck CJha e ello DATE 12/03/98 12/13/98 12/03/98 01/05/99 01/ // /99 01/ /'l/99

, C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY 4

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i l

l C. Obey formal comment once the Commission approves a rule for publication as a proposed rule.)

Since September 1998, we have held two public meetings (which OSHA staff attended), and have established a Worid Wide Web site (http://techconf.llnl. gov /cgi-bin / messages? dom _,lic) that contains discussion threads and a library of documents related to this rulemaking. As a result of discussions at those meetings and written comments received, the attached two ,

sections of the rule text were developed. These two sections are intended to implement the '

NRC areas of responsibility within the context of the 1988 MOU and be consistent with the respective statutory authorities of NRC and OSHA. Accordingly, we would greatly appreciate your views on the attachment. l To facilitate completion of a proposed rule package in May 1999, we would like to resolve any i major issues with the rule language itself, particularly for the attached two rule sections, in January. Again, your views on the attached draft rule text would be appreciated. It would be l desirable if your views could be provided by January 29,1999. Should you like to arrange a meeting or have any questions, please contact Mr. Theodore Sherr on (301) 415-7218 or l Mr. Andrew Persinko on (301) 415-6522.

Sincerely, Carl. J. Paperiello, Director Office of Nuclear Material Safety and Safeguards

Enclosure:

Draft changes to 10 CFR 6970.60 and S70.62 l l

DISTRIBUTION:

NRC File Center NMSS Dir Ofc r/f NMSS r/f FCSS r/f l SPB r/f FRIB Task Force r/f G:\TaskForce\shaltr.wpd (*See Previous ConcurrencAs') 'ld' OFC FCSS E FCSS E FRIB E OGC FCNS NMSS NAME *RLewis:al *APersinko *TSherr *KWinsberg ETenEyck CJPaperiello

_DATE 12/03/98 12/13/98 12/03/98 01/05/99 01/ /99 01/ /99 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY o/ m i  !

I i

l l

1 g(ld C. Obey formal comment once the Commis on approves a rule for publication as a proposed rule.)

Since September 1998, we have blid two public meetings (which OSHA staff attended), and have established a wer,d ..id:'..Qite (http://techconf.llnl. gov /cgi-bin / messages? dom _lic) that contains discussion threads and a library of documents related to this rulemaking. As a result of discussions at those meetings and written comments received, the attached two sections of ,

the rule text were developed. These two sections are intended to implement the NRC a<us cf mf"b' If andWhos within the context of the 1988 MOU and be consistent with the respective str.tutory authcrities of NRC and OSHA. Accordingly, we would greatly appreciate your views on the attachment.

To facilitate completion of a proposed rule package in May 1999, we would like to resolve any major issues with the rule language itself, particularly for the attached two rule sections, in January. Again, your views on the attached draft rule text would be appreciated. It would be desirable if your views could be provided by January 29,1999. Should you like to arrange a meeting or have any questions, please contact Mr. Theodore Sherr on (301) 415-7218 or Mr.

Andrew Persinko on (301) 415-6522.

Sincerely, Carl. J. Paperiello, Director Office of Nuclear Material Safety and Safeguards

Enclosure:

Draft changes to 10 CFR SS70.60 and S70.62 DISTRIBUTION:

NRC File Center NMSS Dir Ofc r/f NMSS r/f FCSS r/f SPB r/f Task Force r/f G:\TaskForce\shaltr.wpd phW. e m OFC FCSS E FCSS E FR4B E OGC&h/6 FCSS NMSS NAME RLewis:al hersinko Th e hh '

ETenEyck CJPaperiello DATE b/ 31/ % tt /31 /44 p-/3 , l o 7 i / d /N / / / /

C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY

4 I

• l C. Obey once the Commission approves a rule for publication as a proposed rule.) Since September 1998, we have held two public meetings (which OSHA staff attended), and have established a World Wide Web site (http://techconf.llnl. gov /cgi-bin / messages? dom _lic) that contains discussion threads and a library of documents related to this rulemaking. As a result of discussions at those meetings and written comments received, the attached two sections of the rule text were developed. These two sections are intended to implement the NRC areas of responsibility within the context of the 1988 MOU and be consistent with the respective statutory authorities of NRC and OSHA. Accordingly, we would greatly appreciate your views on the attachment.

To facilitate submission of a proposed rule package to the Commission in May 1999, we would like to resolve in January any major issues with the draft rule language itself, particularly for the attached two rule sections. Again, your views on the attached draft rule text would be appreciated. It would be desirable if your views could be provided by January 29,1999.

Should you like to arrange a meeting or have any questions, please contact Mr. Theodore Sherr on (301) 415-7218 or Mr. Andrew Persinko on (301) 415-6522.

Sincerely, n

& ZW Carl. J. Paperie 10, Director Office of Nuclear Material Safety and Safeguards

Enclosures:

Draft changes to 10 CFR 9970.60 and S70.62 NRC Memorandum of Understanding

p REGO For the website. December 17.1998 l

l

[ >- The views expressed in this document do not necessarily represent the 8 views of the U.S. Nuclear Regulatory Commission (NRC). The

' *g j information in this document represents NRC staff-developed draft O g language for possible inclusion in a package to be provided for

% 44 ,&

4 Commission approval for publication as a proposed rule. In accordance 6

with Commission direction, NRC staff is providing this information at this time for preliminary public comment and discussion. The public will have an opportunity also for formal comment once the Commission approves a rule for l publication as a proposed rule.

Contents:

1. Release Notes l 2. Clarifyina Modifications to 670.60

3. Clarifyina Modifications to 67032

4. Related Definitions from 670.4 l

1. Release notes A. We have attempted to provide annotations [in redlined-brackets] that identify parallels to the SECY 98-185 version of the rule or call attention to certain clarifying information or other changes. These annotations will be put on the website but removed in the proposed rule package language. (Appropriate parts of this information would reappear in the rule package's statement of considerations.) The following redrafts are revisions-in-total of sections @70.60 l and @70.62 of the SECY 98-185 version of the rule. The SECY 98-185 version of the rule may

! be viewed or downloaded from this page by clicking on the highlighted link or by setting your browser to J

http /techconf.llnl. gov /cgi-bin / library? source =% library = dom _Ilc_ lib & file =042-0035.wp and clicking on either the Wordperfect (wp) or html version of 042-0002.

l B. The purpose of the following redrafts of 70.60, @70.62, and related definitions was to clarify the apparent confusion regarding the rule being " consequence-driven" as opposed to " risk-l informed." This confusion was a major topic of discussion at the December 3-4,1998, oublic meetina on the draft rule. Another purpose was to clarify the responsibilities under NRC's 1988 memorandum of understanding (MOU) with the Occupational Safety and Health Administration l (OSHA) [see note D, below), and to incorporate, in part, the comments provided by the Nuclear

! Energy Institute (NEI), in a letter dated November 4.1998, on NRC regulation of chemical hazards. To accomplish these purposes, we combined the consequence and likelihood sections, to reflect risk, and separated the performance requirements from the descriptive l requirements for integrated safety analyses (ISAs) and safety programs, l

C. The fact that a topic does not appear in the following draft rule language does not indicate

that the topic will not be reinserted intc' the draft language that the staff will submit for Commission approval for publication as a proposed rule. For example, in the draft rule language below, the annotation after section 670.62(c)(5) mentions that the staff is currently evaluating the appropriate contents and location for the requirements for preliminary integrated safety analysis. Thus, preliminary integrated safety analysis language was not included in this Enclosure 1

2 web posting even though it was in the parallel section in SECY 98-185. However, language regarding this subject will be included in the draft rule language. As another example, the draft rule below (see 70.60(b)(5) and (c)(4)) does not reference the quantitative Emergency Response Planning Guidelines (ERPG) and Acute Exposure Guideline Limits (AEGL) chemical consequence standards, but adopts equivalent, qualitative language. We are still considering the merits of this approach.

i D. As mentioned above, we believe the redrafts of these two ruie sections provide clearer treatment of the 1988 NRC-OSHA MOU on responsibilities for hazards at NRC licensed facilities. Specifically, item (c) of the NRC-OSHA MOU states that NRC has the general purview for regulating " plant conditions which affect the safety of radioactive materials and thus present an increased radiation risk to workers." As an example, NRC's regulatory purview would include the impacts of chemical system failures or fires that cause failure of a nuclear safety system, and NRC's purview would include impacts of plant conditions on the ability of operators to perform an activity (administrative control) that is relied on for nuclear safety. The draft rule addresses these responsibilities in two ways / cases, the performance requirements (70.60) and the ISA requirements (70.62(c)(1)(iii)). Language very similar to item (c) of the NRC-OSHA MOU now appears in the ISA requirements in 670.62(c)(1)(iii). Also, through 670.60,if the failure of a "non-nuclear" system could disable a nuclear system and cause an unacceptable risk (such as the frequency of a worker dose exceeding 25 rem being greater than "unlikely"-- per 70.60(c)(1)]; then 70.60(d) would require that the non-nuclear system be designated as an " item relied on for safety" and controlled by the safety program (viz., it would be under NRC's regulatory purview). In addition,70.60(b) and (c) specify risk-based standards for " hazardous chemicals produced from licensed material," such as HF gas accidentally released from a reaction of UF. with water. Sections 70.62(c)(1)(i) and (ii) also contain statements that correspond to MOU items (a) and (b). Inclusion of this language assures that each MOU item for which NRC has general regulatory purview will be explicitly addressed by

licensees in the ISA.

E. We have added two paragraphs, 70.62(c)(2) and @70.62(c)(3), that deal with integrated l safety analysis (ISA) team qualifications and ISA revalidation, respectively. These sections are l very similar to requirements of the OSHA process safety management rule (specifically,2.9

! CFR 1910.119(e)(4) and (e)(6)). We believe that inclusion of these sections may be appropriate, not only for consistency with OSHA, but also in consideration of the further development of requirements on the submittal and contents of the ISA summary, what is "on the docket" and/or "in the license," and the process (e.g., NRC pre-approval .or not) for making changec to the plant and items relied on for safety. Revalidating the ISA will also permit an j opportunity for consideration and incorporation of recent industry and facility accidents into the l ISA, and possibly an opportunity to incorporate different experiences (e.g., if staff changed) into the updated ISA.

2. Clarifying modifications to 70.60 70.60 Performance Reauirements for Certain Licensees Authorized to Possess Special Nuclear Material in Quantities Sufficient to Form a Critical Mass.

(a) Each applicant or licensee required to establish and maintain a safety program poc.mnt to

@70.62 of this part shall demonstrate, in the integrated safety analysis, compliance with tne

1 l

3 l performance requirements in paragraphs (b) and (c) of this section. (annotation: most requirements of previous 70.60(a) and 70.60(d), dealing with the safety program and ISA I contents have been moved into 70.62 (below) for clarity] l l

(b) The risk of each credible high-consequence event must be limited, unless the event is highly )

unlikely, through the application of engineered controls, administrative controls, or both, that reduce the likelihood of occurrence of the event or (except for nuclear criticality) its consequence. Application of further controls is not required for those high-consequence events demonstrated to be highly unlikely. High-consequence events are those internally or externally initiated events that result in:

(1) a nuclear criticality; (2) an acute worker dose of 1 Sv (100 rem) or greater total effective dose equivalent; (3) an acute dose outside the controlled site boundary of 0.25 Sv (25 rem) or greater )

total effective dose equivalent; l (4) an intake outside the controlled site boundary of 30 mg or greater of uranium in soluble form; or (5) an acute chemical exposure to an individual from licensed material or hazardous chemicals produced from licensed material that: (i) could endanger the life of a worker, '

or (ii) outside the controlled site boundary, could lead to irreversible or other serious, long-lasting health effects. If an applicant possesses or plans to possess quantities of material capable of such chemical exposures, then the applicant shall propose appropriate quantitative standards for these health effects, as part of the application information submitte ~. pursuant to Section Q70.65 of this Part.

{ annotation: The ERPG and AEGL would be identified as acceptable standards in the SRP. Items (b)(5) and (c)(4) cover, for example,"HF;" and rely on a new 70.4 detinition, hazardous chemicals produced from licensed materiab)

[ annotation: " acute" is defined in section 70.4 (see below)]

(c) The risk of each credible intermediate-consequence event must be limited, unless the event is unlikely, through the application of engineered controls, administrative controls, or both, that reduce the likelihood of occurrence of the event or its consequence. Application of further controls is not required for those intermediate-consequence events demonstrated to be unlikely. Intermediate-consequence avents are those internally or externally initiated events, that are not high-consequence events, that result in:

(1) an acute worker dose of 0.25 Sv (25 rem) or greater total effective dose equivalent; (2) an acute dose outside the controlled site boundary of 0.05 Sv (5 rem) or greater total effective dose equivalent; (3) a 24-hour averaged release of radioactive material outside the restricted area in concentrations exceeding 5000 times the values in Table 2 of Appendix B to 10 CFR Part 20; or (4) an acute chemical exposure to an individual from licensed material or hazardous chemicals produced from licensed material that: (i) could lead to irreversible or other serious, long-lasting health effects to a worker, or (ii) outside the controlled site boundary, could cause mild transient health effects. If an applicant possesses or plans to possess quantities of material capable of such chemical exposures, then the applicant shall propose appropriate quantitative standards for these health effects, as

4 part of the application information submitted pursuant to Section 70.65 of this Part.

(d) Each engineered or administrative control necessary to comply with subsection (b) or (c) of this section shall be designated as an item relied on for safety. The safety program, established and maintained pursuant to 970.62 of this part, shall ensure that each item relied on for safety will perform its intended function when needed and in the context of the performance j requirements of this section.

3. Clarifying modifications to 70.62 70.62 Safety Proaram. Intearated Safety Analysis, and Filina of Intearated Safety Analysis Summarv (a) safetyprogram. (1) Each licensee engaged in enriched uranium processing, uranium fuel fabrication, uranium enrichment, enriched uranium hexafluoride conversion, plutonium processing, mixed-oxide fuel fabrication, scrap recovery, or any other activity that the Commission determines could significantly affect public health and safety, shall establish and maintain a safety program that ensures that actions taken will provide adequate protection from licensed materials, for worker and public health and safety and of the environment. The safety j program may be graded such that management measures applied are commensurate with that  !

item's reduction of the risk. Requirements for the safety program, including process safety information, integrated safety analysis, and management measures, are described in subsections (b) through (d) of this sect;on.

[ annotation: note "may be.'.." - grading of safety program is pe:mitted but not required].

l

[ annotation: by " management measures" we mean measures that assure that items used for  !

safety.will be available and perform their functions reliably.when needed.] l (2) Each licensee shall establish records that demonstrate that the requirements of this section have been met. Each licensee shall maintain these records until license termination. [ annotation: (a)(1) and (a)(2) parallels 70.60(a) and 70.60(d)(6), respectively, ,

i in SECY 98_185; note change to " license termination" instead of " lifetime of the plant"]'

(3) If the decommissioning of a facility involves potentially hazardous activities such as L chemical treatment of wastes, each licensee shall perform en ISA of the decommissioning process, demonstrate compliance with the performance requirements of section S70.60 of this part, and submit the results to NRC for approval before beginning such decommissioning activities. [ annotation: parallels 70.62(b) in SECY 98-185]

l (b) process safety lnformation. Each licensee or applicant shall compile and maintain a set of l process safety information to enable the performance of an integrated safety analysis. This process safety information must include information pertaining to the hazards of the materials

used or produced in the process, information pertaining to the technology of the process, and information pertaining to the equipment in the process. [ annotation

parallels 70.60(d)(1) in SECY 98-185) i d

5 (c) integratc 1 safety analysis. (1) Each licensee or applicant shall conduct an integrated safety i

analysis, that is of appropriate detail for the complexity of the process, that:

(i) identifies radiological hazards resulting from possessing or processing licensed material at its facility; -

(ii) identifies chemical hazards of licensed material or hazardous chemicals produced from licensed material resulting from possessing or processing licensed material at its facility; (iii) identifies facility hazards (e.g., chemical, fire, electrical and mechanical) which could affect the safety of licensed materials and thus present an increased radiological risk;

[ annotation: (i)-(iii) modified slightly from draft rule to explicitly address OSHA MOU]

(iv) identlfies and provides the basis for potential accident sequences caused by process deviations or other events internal to the plant and credible external events, including natural phenomena; (v) identifies and provides the basis for the consequence and the likelihood of occurrence of each potential accident sequence identified pursuart to paragraph '

(b)(1)(iv) of this section; and i (vi) identifies and provides the basis for each item relied on for safety identified pursuant to section 670.60(d) of this Part, and the characteristics of its preventive, mitigative, or i other safety function.

(2) integrated safety analysis team qualifications. lannotation; this paragraph added to match 29 CFR 1910.119(e)(411 in order to assure the adequacy of the integrated safety analysis, the integrated safety analysis shall be performed by a team with expertise in engineering and process operations, and the team shhllinclude at least one employee who l has experience and knowledge specific to each process being evaluated, and employees who have expetience in nuclear criticality safety, radiation safety, fire safety, and chemical process safety. Also, one member of the team must be know!edgeable in the specific j

integrated safety ana!ysis methodology being used.

(3) integrated safety analysis revalidation. The integrated safety analysis shall be periodically revalidated by a team meeting the requirements of paragraph (c)(2) of this section, to ensure that the integrated safety analysis is consistent with the current facility.

The minimum period for such revalidation shall be at each filing of an application for renewal of a license pursuant to section S70.33 of this part [ annotation: this paragraph j

added to match 29 CFR 1810.119(e)(6). The wording permits a more frequent period between revalidations, e.g., every 5 years as specified in 29 CFR 1910.119(e)(6) for the process hazards analysis].

(4) integrated safoty analysis summary. Each applicant or licensee shall submit an i integrated safety analy;!s summary to NRC for approval, as appropriate: (i) in accordance with the requirements and schedule in paragraph (c)(5) of this section, if applicable; or (ii) aa part of the license application contents, amendment application contents, or renewal 4

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l i application contents identified in G670.21, A70.22, @70.33, G70.34, and 670.65. l

[ annotation: this paragraph requires the submitted ISA-summary (which used to be i called 'results of the ISA.' This paragraph (c)(4) parallels 70.62(a)(1)-(3) that were in SECY 98-185). The contents of applications section (70.65, under development) and the definitions (70.4) will identify the contents of the ISA summary and what is to be "in the. license,""on the docket," etc. We plan to move the SECY 98-185 sentence "The process description in the integrated safety analysis summary must include information that demonstrates the licensee's compliance with the design requirements for criticality monitoring and alarms in 970.24." to G70.65 (contents of applications) since it addresses I the contents of the ISA summary and license application. Note also that the correction  !

of ' unacceptable vulnerabilities' identified by the ISA, that was in the parallel section of I SECY 98-185, is now handled by 70.60(a)]

I (5) filing by existing licensees. Individuals holding an NRC license on <the effective date of this rule > shall, with regard to existing licensed activities:

(i) within 6 months of <the effective date of this rule >, submit, for NRC approval, a compliance plan that describes the integrated safety analysis approach ths't will be used, the processes that will be analyzed, and the schedule fm completing the analysis of each process. Pending the correction of unacceptabie vulnerabilities identified by the integrated safety analysis, the licensee shall implement appropriate compensatory measures to ensure adeq~uate protection.

(ii) within 4 years of <the effective date of this rule >, unless otherwise specif:ed by the conditions of a license held on <the effective date of this rule >, complete an integrated safety analysis, correct all unacceptable vulnerabilities, and submit an integrated safety analysis summary in accordance with raragraph (c)(4) of this section or the approved complianco plan submitted under paragraph (c)(5)(i) of this section.

[ annotation: (c)(4) and (5) paralle' 70.62(a)(1)-(3) that were in SECY 98-185. We are currently reevaluating: t1) if preliminary ISA requirements should appear here (as they did in the SECY 98-185 version), or another section (e.g.,670.64); and (2) the nature and contents of the preliminary ISA requirements. After this reevaluation, we may reinsert language here that parallels the old 70.62(a)(3)]

[ annotation: unacceptable vulnerabilitie.s is defined in Section 70.4 (see below)}

(d) management measures. [ annotation: except as noted, this section parallels 70.60(d)(3) in SECY 98-185] To ensure that eac's i em relied on for safety will perform itc intended function when needed, the integrated safety analysis shall be used by licensees to establish safety program management measures. The safety program management measures shall ensure that:

(1) Engineered controls that are identified as relied on for safety pursuant to section 70.60(d) of this part are designed, constructed, inspected, calibrated, tested, and maintained, as necessary, to ensure the ability to perform their intended functions when needed. Items subject to this requirement include but are not limited to: principal structures of the plant; passive barriers relied on for safety (e.g., piping, glove boxes, containers, tanks, columns, vessels); active systems, equipment, and components relied

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on for safety; sampling and measurement systems used to convey information about the safety of plant operations; instrumentation aid control systems used to monitor and control the behavior of systems relied on for safety; and utility service systems relied on for safety.

(2) Personnel are trained, tested, and retested, as necessary, to ensure that they understand, recognize the importance of, and are qualified to perform their duties that are identified as relied on for safety pursuant to sectior 970.60(d) of this part; (3) Procedures that are identified as relied on for safety pursuant to section 970.60(d) of this part are developed, reviewed, approved, and distributed to ensure that personnel are 1 able to perform the duties relied on for safety.

(4) Human-system interfaces are designed and implemented to ensure that personnel relied on for safety are able to perform their duties that are identified as relied on for safety pursuant to section 970.60(d) of this part; (5) Configuration changes to site, structures, process, systems, equipment, components, computer programs, personnel, procedures, and documentation are managed so that such modifications are reviewed, documented, communicated, and implemented in a systematic, controlled manner.

l (6) Quality assurance that is commensurate with the item's reduction of risk is applied to each item relied on for safety identified pursuant to section 970.60(d) of this part.

(7) Periodic audits and assessments of the safety program are performed to ensure that an adequate level of protection is maintained at the facility. [ annotation: parallels 70.60(d)(4) in SECY 98-185)

(8) Abnormal events are investigated and corrective actions taken to minimize the recurrence of these events. [ annotation: parallels 70.60(d)(5) in SECY 98-185]

4. Related Definitions from 970.4 Acute as used in section 970.60 of this part means a single radiation dose or chemical exposure event or multiple radiation dose or chemical exposure events occurring within a short time (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less). [ Annotation: slightly modified]

Acute exoosure auldeline levels (AEGid [ Annotation: this term is not used in the rule l anymore]

l l Controlled site boundary means the physical barrier surrounding the facility that is used by the licensee to control access. It may or may not coincide with the property boundary.

Critical mass of SNM means special nuclear materialin a quantity exceeding 700 grams of contained uranium-235; 520 grams of uranium-233; 450 grams of plutonium; 1500 grams of contained uranium-235, if no uranium enriched to more than 4 percent by weight of uranium-

i e

i 8

235 is present; 450 grams of any combination thereof; or orehalf such quantities if massive moderators or reflectors made of graphite, heavy water, or beryllium may be present.

l Emeraency resoonse olannina auidelines (ERPG) [ Annotation: this term is not used in the rule anymore]

l Hazardous chemicals [ Annotation: this term is not used in the rule anymore] l l Hazardous chemicals oroduced from licensed materials means substances having licensed material as precursor compound (s) or substances that physically or chemically interact with Econsed materials; that are tcxic, explosive, flammable, corrosive, or reactive to the extent that i they can endanger life or health if not adequately controlled. These include substances l l

commingled with licensed material, and include substances such as hydrogen fluoride that is  !

j produced by the reaction of uranium hexafluoride and water, but do not include substances prior to process addition to licensed material or after process separation from licensed material.

[ Annotation: modified version of the NEl-proposed definition. The terms, process addition and process separation are used to indicate an intentional activity (as opposed to an accidental separation)]

j Intearated safety analysis (ISA) means a systematic analysis to identify plant and external

hazards and their potential for initiating accident sequences, the potential accident sequences, I

their likelihood and consequences, and the site, structures, systems, equipment. components, and activities of personnel tha't are relied on for safety. As used here, integrated means joint I consideration of, and protection f rom, all relevant hazards, including radiological, nuclear criticality, fire, and chemical.

Items relied on for safety means structures, systems, equipment, components, and activities of personnel that are relied on to prevent or to mitigate potential accidents at a facility.

Results of the ISA [ Annotation: this term is not used anymore -it was replaced by intearated safety analysis summarvl.

Intearated safety analysis summary means the portion of the license application, license amendment application, or license renewal application that has the purpose of informing the Commission of the nature of the facility, the plans for its use, and the evaluations that have l been performed to evaluate if the facility has been constructed and will be operated in j accordance with NRC requirements and will provide adequate protection from licensed i materials, for worker and public health and safety and of the environment. [ Annotation: new definition].

< Unacceptable vulnerabilities mean deficiencies in the items relied on for safety or the ,

i measures used to assure their availability and reliability of such items when needed, that need l l to be corrected to ensure an adequate level of protection as defined in 10 CFR 70.60(b) or (c).

[ annotation: this term is now only used in one place - 670.62(c)(5) dealing with filing of the ISA summary by existing licensees]. j l

1 4

~

9 Worker means an individual whose assigned duties in the course of employment involve exposure to radiation and/or radioactive material from licensed and unlicensed sources of radiation (i.e., an individual who is subject to an occupational dose as in 20 CFR 20.1003).

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10-31-ce Monday Vol. 53 Ho. 210 g October 31,1988

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Pages 4384M3993 ...-_z

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Bnefer on How To Use the Federal Resister-for information en a briefing in Wasbngton. DC, see t_!!L ennouncement on the inside cover of this issue.

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\ m i BEST COPY AVAILABLE ENCLOSURE L

43950 Fed ral Register / Vd !3. No. 210 / Monday. October 31, 1988 / Notices DEPARTMENT OF LABOR interagency effort can ensure spgg f Oocht No. 64-4 91 F

y Haam it Surnmer Grove Pharrnacy, Shreveport. t e sam t a id d nc LA; Hearing effort. This memorandam rep; aces an f existmg procedure for interagency Notice is hereby ghen that on Apnl NUCLEAR REGUIATORY COMid2SS40N act2vities.

• General Culdeunes fer 12,1968. the Drug Enforcement Interface Activities between the NTsC Administration. Department of hatice. Memorandum of Understandin9 Regional Offices and the OSHA."

, issued to Summer Grove Pharmacy an Between The Nuckrar Regulatory Order to Show Cause as to why the CommaaWon and the Occupadonaj flazards Anociated With Nuclear Drug Enforcement Administratien Safety arsd Hearth Administration; FsMes should net revoke your DEA CertMeate Worker Protes: tion at NRC4 censed 3.There are four kinds of hazards thu of Registration AS5413755 and deny any Faditnes may be associated with NRCicensed pendeg applications. mc ear facper De Nucjaar Regulatory Commission a. Radiation risk prodaced by I Thirty days having elapsed since the (NRC) and the Occupational Safety and radioactive materials; said Order to Show Cause was received Health Mministration (OSHA) have b. Chemical risk produced by by Respondent, and wntten request for entered into a Memorandum of radcactin matenals; a hearing having been filed with the Understanding (MOU) to provide Drug Enforcement Administration. general guide!mes for interface activities c.1 W. conditions which affect the notice is hereby given that a heanns in between the two agencies.The MOU ls safety os rs6oactive< materials and tht.s this metter will be held on Thursday. designed to ensure that there will be no present an increased ra6ation nsk to workers. For example, these might November 17.19aA commencing at 10 00 gaps la the protection of workers at a.m.. at the United States Custom NRC-Bcensed facihties where the OSHA produce a fire or an explosion, and House. 423 Canal Street, courtroom. 211, also has health and safety jurisdiction. thneby caun a release of ra6cacun New Orleans, loulsiana. At the same time the MOU is designed materials or an unsafe reactor con 6m to avoed duplication of effort on the part a nd.

• of the two agencies in those cases where d. Plant conditions which resWt tn an It is not always practical to sharply occupationa! risk, but do not affect the John C t e n.

identify boundaries between the NRC's safety oflicensed radioecti.o clatena:s.

A himsucer. Ongr En/viremcet responsibilit.es for nuclear safety and For example, there might be exposure to Ah.wsuc m.

the OSHA's responsibihties for toxic nonradioactive matenals and other la Doc. on-sor' Wed 1o-za4a a 45 ::nj industrial safety, industrial hazards in the weriplace.

" * * * ' " * * * ' The MOU. which replaces an existing Generally. NRC covers the first three procedure for interagency activities. hazanis listed in paregreph 3 (n. b. ud defines the general areas of c). and OSHA covers the fourth hatard responalbilities of both agencies, described in paragraph 3 (d), h7C a IDocaat h as-ul describes generally the effortsof each to OSHA responsibilities and actions a achieve worker protection at NRC- described more fully in paragraphs 4 Michael C. Vizcarra. Hesperta CA: bcensed facilities, and provides general and 5 below.

ce of Haq procedures for the coordination of NRC Reeponsibilities Notice is hereby given that on Aprd interface activities and exchange of int rination between the NRC and 4. NRC is responsible for licensing and

"* the OSHA.He text of the MOU is set out regulating nuclear facilities and Ad strati De et f Iustice' below. materials and for conducting research i, issued to Michael C. Vizcarra. M.D., an support of the licensing and regulatory Order to Show Cause as to why the Purpose and Backg2ound process as mandated by the Atomic Drug Enforcement Administration 1.The purpose of this Memorandum of Energy Act of1954 as amended; the should not deny your application for a Understandmg between the U.S. Nuclear Energy Reorganization Act of 1974, as DEA Certificate of Registratiert Regulatory Commission (NRC) and the amended; and the Nuclear nitry days having elapsed since the Occupational Safety and Health Nonproliferation Act of 1978: and in said Order to Show Cause was received AdmWstration (OSHA)is to delineate accordance with the National by Respondent, and written request for the genersi areas of responsibility of Environmental Policy Act of1909, as a hearing having been filed with the each agency: to describe generally the amended. ce d other applicable statutes.

Drug Enforcement Administration, efforts of the agencies to achieve worker These NRC responsibihties cover the l notice is hereby given that a hearing in protection at facilities licensed by the first three nuclear faciitty harsrds this matter will be held on Tuesdsy. NRC: and to provide guidelines for identified in parsgraph 3 (a, b. c). h7C November 15.196& commencing at 1000 coordination of interface activitie s does not have statutory authority for the between the two agencies. If NRC fourth hazard described in paragrsph 3 s.m at the Alhambra MunJcipal Court, 150 West Common Wealth Avenue, licenses observe OSHA's standards and (d).

Division One Courtroom. Second floor, regulations, this will help minimize NRC responsibilities include workplace hazards, protecting public health and safety:

Alhambra. California. protecting the environment: protecting

2. Both NRC and OSHA have Lated. October 25.19ea. furisdiction over occupatjonal safety and safeguarding materials and plants JohaC.14wn, and health at NRC-licensed facilit'n. in the interest of national secunty; and Admin /suoror. Drug Enforcement Because it is not always practical to assuring conformity with antitrust laws Adia,nisuosion. sharply identify boundaries between the for certain types of facilities, e.g4 nuclear and redlelogical safety NRC nuclear power reactors. Agency (R Doc. 802509e Lied to-34e aA5 a r.] regulates and the industrial safety functions are performed through:

• • • o coos *nem OSHA regula tes, a nacrdinated Standardsactting and rulemakig l

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t

I l

l l

l 43 % 1 Federal Register / Vcl. 53. No. 210 / Monday. October 31, 1968 / Notices materials facilities presents chemica!

' technical reviews and stud;es; condact facdities are conducted norma'Jy as a and nuclear operational safety herards of pubhc heanngs; issuance of result of accidents,fatahues, referrals, which can best be evaluated by tomt authonzauons. permits and licenses; or w orker complamts.

NRC-OSHA team a ssessments. Each inspection. investigation and Interface Procedures agency will make its best efforts to er.fortement; evaluation of operating support such assentments et about 20

6. It recognition of the egencies' experience, and confirmatory research. facihties once every five years.Of these authorities and responsibihties OSHA Responsibilities enumerated above. the fodowing facihtes, about one. third are in the

5. OSHA is responsible for procedures will be fouowed: OSHA Plan States. OSHA wiu also Although NRC does not conduct assist in promottng such participation by admimatenna the requiremens established under the Occupanonal inspections of industrial safety, in the State personnelin OSHA P!an States.

course of inspections of radiological and to. Based upon reports ofinjury or Safety and Health Act (Ostia Act)l29 U.S C. 651 et seq.). which was enacted in nuclear safety NRC personnel may compla nta at nuclear power plant sites, 1970. OSHA's authority to engage in the identify safety concerns within the ana OSHA will provide NRC with kinds of activities descnbed below does of OSHA responsibility or may receive information on those sites where not a ply to those workplace safety and complaints from an employee about increased management attent on to OSHA. covered working conditions. In worker safety is needed.The NRC wdi heal conditions for which other such trutances. NRC wdl bnng the Federal agencies emercise statutory bring such informadon k&catng authoney to presenbe and enforce matter to the attention of licensee sigmficant breakdown in worker safety atanda;ds, adee or regulations. management. NRC inepectors are not to to the attention of b,censee managemect Under the OSH Act. every employer perform the role of OSHA inspectore: and monitor corrective actions.This wdl hae a general duty to furnish eoch however, they are to elevate OSHA not interfere mth OSHA authonty and employee with a place of employment safety issues to the attention of NRC responsibility to investigate industnal that is free frem recogntzed hazards that Regional management when accidents and worker complaints.

can cause death or serious physical appropnate. If significant safety 11. Power reactor sites are inspected harm and to coc ply mth au OSHA concerna are identified or if the licensee by NRC Region-based and Resident standards. rules and regulat2ons. demonstrates a pattern of --t unresponsiveness to identified concems. Inspectors. Personnel from ST(C OSt!A standards contatn Regional Offices reutinely conduct regutrements designed to protect the NRC Reponal OfGoe wdlinform the inspections at most fuel and matenals employees against workplace hazards. appropriate OSHA Regional OfSce. In the case of cocip!aints. NRC wul licensed facilitica. In order to enhance in general. safety standarda an the ability of hTC personnel to identfy intended to protect against traumatic withhcid. fmm the bcensee, the identry of the etnployee. In addJtion. when safety matters under OSHA purview injury, while health standards are dunng nucjear and todaological safety designed to addnse potential known to NRC. NRC will cocourage s licensees to report to OSHA accidents inspections, OSHA wdl provide NRC overexposure to toxic substances and Regional personnel with basic chemical

harmful physical agents, and protect resu' ting in a fatajity or mulbple q hospitahutions. and industrial aafety training and against illnesses wiuch do not marufest indoctrinationin OSHA safety themselves for many years after imtial When such instances occur within OSHA State Plan States

• junediction, standarda, consistent mth ongoing exposure. OSHA tralmas programs.To enhance OSHA standards cover employee the OSHA Regional Office wul refer the the ability of OSHA and State Plan exposures from all radiation sources not matter to the State for appropriate regulated by NRC. Examples include x- action. personnel to effectively participate in ray equipment, accelerators. 7. OSHA Regional Offices wulinform the Operational Safety Team accelerator produced matenals. electron the appropriate NRC RegionalOf6ce of Assessments. NRC wdl provide training matters which are in the purview ef in basic radiation safety requirements.

cdcroscopes and betatrons. and naturally occurnna radioactive NRC, when these come to their anecdon consistent with ongoing NRC training metenals such ae radmm. during Federal of State safety and programa. Details of such training wdl it is estimated that the Act covers health inspections or through be as mutually agreed by the NRC nearly 6 miUinn workplaces employmg complaints.The following are examples TechnicalTraining Center and the more than 80 cullion workers. Federal of matters that would be reported to the OSHA National Trahung Institute.

OSHA covers approximately three- NRC: 12. Reachidon of po% luus fif ths. or fuur milhon. of these a. Lax security control or work concerning agency junsdiction and workplaces States which operate practices that would effect nuclear or operadonal nlanons wm be OSHA. approved job safety and health radiological health and safety. coordinated by the NRC Deputy programa cr " Plans." cover the b. Improper posting of re tiation areas. Executive Direct;r for Operations. and remainder, c.1.lcensee emp}o ee stjegetions of by the OSHA Director of Policy.

OSHA State Plan States are NRC license or regu ation violabons, . Appropriate Headquarters points of encouroped. but not required. to 8.'Ihe NRC and OSHA need not contact will be established.

delineate their authonty for normally conduct loint inspections at

13. Resolution of tesues concern!ns occupational safety and bealth at NRC- NRC-licensed fa cilities. However. under inspection and enforcement actwities licensed facdities in the same manner as certain conditions, such as involving both NRC and OSHA Investigations orinspections following Federal OSHA. accidents or resulting from reported junsdiction et NPC-licensed faclhtiee The OSHA areas of responsibibty will be handled between 57C's Of' ice desenbed in this meinorandum are activities as discussed in items 6 and 7 above. it may be mutustly agreed on a of Enforcement and OSHA's Directorate subject to all applicable requirements of Compliance Programs. Each NRC and and authorities of the OSH Act. case-by. case basis that joint OSHA RegionalOffice mil designate However, the industnal safety record at investigations are in the public int'erest.

9.The chemical processing of nuclear poirds of contact for carrvmg out NTC-licensed nuclear power plants is such that OSHA inspections at these materiale at some NRC. licensed fuel and interface activities.

[N km

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Federal Re# ster / Vol. 5A No. 210 / Monday, Oc'aber 31. 388 / Noticca _~ -

c952 _ _ _ _

- Professor of Cherr.!stry and D.rece the meeting be hem & ils dos .O laboratory for Molecdar Stracru For the Nucleas Regulatory Co==ussum. accomaaodste the ed.eduhng pnenues and Bonding. Texas A&M Uruve of the participants. College Station. Texas.

uctor n ecutae BtstioEJr D torfor operema TYPE OF MEERNG. Closed. Dr. Mary L Good (Chairman). Senior October 21.196& oc.hr 25.1m Vice President.Technoloev AUied.

For the Occupational Safety and Heshh Fidlip D.Waner SEE "*

Adnunsetts uon. Direcgx. CenerclMancgement D cs o Mordstown. New kmy.

loba A.Pedagrass. [G Doc. 86-:$o64 FNed 10-au e 45 a:r.j Dr. lohn C. Hancock. 4550 %,arwick Ass.stcr:f Secretory. __

Boulevrird. Suite 901.Kanaaa Cify, ja Doc. 66-25065 Filed 10-468. 6 45 arrJ "-

~-

Missourt

,,us a com no a Dr. James B. HoMeman MM.

= NATIONAL SCIENCE FOUNDATION University of South Carchna.

Columbf a. South Cerotina.

Na bonal Sclerxs Boertt; Nominatione Dr. James L Powell. Preaident. Recd ,

NAT10NAL AERONAUTICS AND for y _.h,44p November 1,1988 College. 3:33 Southeast Woodstoc k SPACE ADMINISTRAT10N Doulevard. Portland Ongon.

twotk>sas-921 ne National. Science Board (NSB)is T e nt Dr ra ,

gy NASA Advisory Councit; Meeting coes'ata of 24 members appointed by the Ithaca. New York.

Aorwcy: National Aeronautics and President, with the advice and consent Dr. Howard A. Schnelderman. Senior Space Administration. of tr e Senate. for six. year terms. in . Vice President. Research and Acnoec Notice of meeting. adman to the NSF Director Ex ogiew, Development and Chief Scientist.

as follows: Monsanto Company,800 N. Lindbc@

suesuARY: In accordance wnb the Tems Spim Afav 10.1990 Boulevard. St. Louis. Mas sourt.

92 e nde te a ona Dr. Perry L Adklason, Chancellor.The Terms Expire Afcy 10.19W Aeronautica and Space Admuustration Texas A&M University System. Dr, Wasnn J. Baker. President.

announces a forthcoming meetmg of the ae NASA Advisory Council (NACL. System Administration Building. f aP e Executive Offices. Room 219. College ,

Informal Execudt e Subcom:ruttee. Stat 2on. Texas. Califorru.a. ,

DATE AND Unst: November 18.1968.9 Dr. Annelise G. Anderson. Senior Dr. Arden L Bement. jr. Vice Presider.t.

a'm.' to 5 m' The Hoover Technical Resources.TRW. Inc.19m Aoontsa: National Aeronautics and Rescamh Institution. Roon Fellow $ 301-M. Stanford Richmond Road. Cleveland. Ohio.'

Space Adtnin:stration, Room 7A University. Stanford. California. Dr. D. Allan Bromley, Daector. Wng rederal Office Dwldmg e, Wa shington. Dr. Craig C. Black. Director. Los Angeles Nuclear Structure laboratory. P.

County Museum of Natural History. Box 6066. 2.72 Whitney Avenue. Y m mwan muAm conAcn 900 exposition Boulevard. I4s University New Haven.Connectic Mr. Nathaniel B. Cohen. Code ADI-1' Angeles. Cahfornia. Dr. Daniel C. Drucker. Graduate National Aeronautics and Space Dr. Rita R. Colwell. Director. Maryland Research Professor, Departnient of Administration. Washington. DC :0548. Biotechnology institute and P"fessor Aerospace Engineering. Mechanir.s 202 W 6 M . of Microbiology Microbiology and Engineering Science. University of settumTAny wrowAm:The Building. University of Mar > land, Florida,231 Acimpsce Building, NAC Informal Executive Subcommittee College Park. Maryland.

Calnesville. Florida.

was established under the N AC to assist Dr.nomas B. Day (Vice Chaltman).

President. San Diego State Urdversity. Dr. Charles L Hooler. Senior Vice the Chair in planning the activities. Presidant for Research and Dean of establishing meeting agendas. and 5300 Campanile Dnve. San Diego. Craduate School.114 Kern Buildmg.

otherwise guiding the activities of the California. ne Pennsylvania State University.

Council.The Councilis chaired by Dr- Dr. }ames J. Duderstadt. President. TheUniversity Park. Pennsylvania.

John L McLucas, and includee eight University of Michigan,2074 Fleming ArtmtnfstrationBuilding. Ann Arbor. Dr.MJguelRios ]r President. ORION other members, seven of whom chair InternationalTechnology,300 San standing committees of the Council. Michigan. Mateo. N.E., Suite *200, Albuquerque The rneettng will be closed to the Dr. K. June Lindstedt-Siva. Manager.

EnvironmentalSciences. Atlantic New Mexico.8 public.The sole agenda item m!! be Dr.Roland W. Schmitt. President.

planning for the coming year of the Richfield Company,515 South Flower Street.los Angeles.Californla. Rensselaer Polytechn'n Institute, activities of the Council, the committees. PittsburEh Building. Troy, New York and their task fortes, with emphasis Dr.Kenneth L Nordtvedt. Jr Professor throughout on prospective future of Physico. Department nf Physics, (One VacancH membership of esch of these groups and Montana State University. Bozeman.

Member & Officio theltinteractions with NASA and ' Montana.

Mr. Erich Blo'ch (Chairman NSB outside parties.Throughout the sessions, Terrns Dpire May 10.1992 C

'$* 'g {o y d on the \ushfications of these individuals will e candidly discussed and Dr. Frederick Professor of Computer Science P. Brooks.Jr. Kenan g Waehi"8 ton' DC' appraised with respect to the tasks to be accomplianed. Because the meeting will Department of Computer Science. Section 4(c) of the National Science be concerned throughout with matters University of North Caralma. Chapel Foundation Act of1950 as amended.

listed in 5 U.S.C. 552b(c)(6),it has been Hill. North Carolina.

determined that this meeting should be Dr. F. Albert Cotton. W.T. Doherry-Watch Foundation Dietinguished NSB Nominee.

closed to the public. It is imperative that e

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• ** J tA 1 N8N U.S. NUCLEAR REGULATORY COMMISSION

/

LOCAT101s SYSTESS OFFICE OF NUCLEAR g o 01/12/99 MATERIAL SAFETY AND SAFEGUARDS FCSS: R. Lewis Acncsea r i e l l o - S i gn Sugagp,T TO OBEY FROM PAPERIELLO RE: PENDING NRC REGULATIONS FOR DOMESTIC LICENSING OF SNM (No TICKET)

CONCURRENCES RECEIVED PERSON CONCURRING DATE OFFICE PERSON CONCURRING DATE OFFICE DFMDA DONM5"5 (C% - [av4  % s3 w,.bb 6 % M h, d p., m&h Me 1 - i , V 2 *d A L.L - (p.J1) Lg e p v.s A 59 b yk. ( di-c. a SlMdh h a n% - 1 DNMSS OTHER NRC FORM 414A (11W7)

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LOCATuoes SYSTES$

OFFICE OF NUCLEAR

.I uo 01/12/99 MATERIAL SAFETY AND SAFEGUARDS FCSS: R. Lewis Acnes,2 r i e l l o - d ign SuggpT TO OBEY FROM PAPERIELLO RE: PENDING NRC REGULATIONS FOR DOMESTIC LICENSING OF SNM (N0 TICKET)

CONCURRENCES RECElVED OFFICE PERSON CONCURRING DATE OFFICE PERSON CONCURRING DA'iE DPMDA DDNMSS (0.% - f(om eh w.bb SvtMb. ~

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