ML24059A207

1999 Annual Report - Review of Federal Advisory Committee

ML24059A207
Person / Time
Issue date:	12/01/1999
From:	NRC/SECY
To:
References
Download: ML24059A207 (1)

Text

SF 820 http:// 204.254. l l 2.5 / cms / RptAnnu a lReport.asp

1999 Annual Report: Review of Federal Advisory Committee 1 comm ittee Menu

12 /16 /1999 2:59:47 PM I. Department or Agency 2. Fi sca l Year N uclear Regulatory Commission 1999

3. Co111 111ittee or SubCo mmitt ee 3b. GSA Co111111itt ee No.

Advisory Committee on Nuclear Waste 1100 4. Is thi s New During Fiscal Year? 5. Current C hat1e r 6. Expected Renewal Dat e 7. Expected Tenn Date N o 5 /29 /1998 5 /29 /2000 Sa. Wa s Tcnninated During FY ? Sb. Specific Tennination Authority Sc.Ac tual Tennination Date No 42 U.S.C. 220 I 9. Agency Reco 111m e ndati o n for Next FY I0a.Legis lation Req to Tenninate ? I Ob.Legislati on Pending?

Co ntinue No 11. Estab li shm e nt Authority Agency Authority

12. Specific Estnbli s hm en t Authorit y 13. Effective Date 14. Committee Type 14c. Presidentia l?

42 u.s.c. 2201 1/6 /1988 Continuing No 15. Description of Co mmittee Scientific Technical Pro g ram Advisory Board 16a. Total Nu mber of Repo rt s 8 16b. Rcpo11 Ti tl es and Dat es Devel o pment of a Standard Review Plan for Decommissioning 1/11 /1999 Co mment s o n Regulatory Uses of Importance Measures for Waste Management & Possible Application to Prop. Hi g h-Level 1/12 /1999 Radioa c tive Waste Repositor y a t Yucca Mtn.,NV Advisory Co mmittee on N uclear Wa s te 1999 Action Plan and Priority Iss ues 1/22 /1999 ACNW Visit to German Waste Iso lation Authorities and Facilities, September 14-18, 1998, G e neral Observations and Impre ss ion s 1/27 /1999 Co mme~1ts on the Department of Energy's Viabilit y Assessment for the Proposed Hi g h-Level Radioactive Waste Repo s itor y at Yucca 41811999 Mountatn, Neva da Advisory Co mmittee on Nuclear Wa s te Metrics and Self-Assessment Evaluation for Fiscal Year 1998 4/29 /1999 Linear No Threshold H y pothesis 6/4/1999 Co mments on DOE'S Licen se Application Design Selection Pr ocess (LADS) and Recommended Repository De s ig n 8/9/1999 17a Open: 9 17b. Closed: 0 17c. Pa11iall y Closed: 0 17d. Total Meeti ngs 9 Meeting Purpo ses and Dates 104th Full Co mmittee Meeting 10 /19 /1998 10 /21 /1998 105th Full Co mmittee Meeting 12 /15 /199 8 12 /17 /1998 106th Full Co mmittee Meeting 2/23 /1999 2/25/1999 10 7t h Full Co mmitt ee Meeting 3 /16 /199 9 3/17/1999 108th Full Co mmittee Meeting 3/23 /1999 3 /25 /1999 109th F ull Co mmittee Meeting 5 /11 /1999 5 /13 /1999 1101h Full Co mmittee Meeting 6 /28 /1999 6/30 /1999 111 lh Full Co mmittee Meeting 7/19 /199 9 7/21 /1999 I 12th Full Co mmittee Meeting 9/14 /1999 9/15 /1999 CuJTent Fiscal Year Next Fisca l Year I 8a( I) Pe rso nn e l Pmts to Non - Federal Members $8 4,6 98 $88,76 4 I 8a(2) Perso nn e l P111ts to Federal Memb ers $0 $0 18a(3) Pe rso nnel Pmts to Federal Staff $47 4,966 $577,406 I 8a(4) Pe rso nn el Pmt s to No n-m ember Consultants $7,07 5 S I 9,968 18b(I) Tra ve l and Per Diem to No n-Fe dera l Memb ers $35,019 $ 47, 000 18b(2) Trave l a nd Pe r Di em to Fed era l Me111bers $0 so 18b(3) Trave l and Per Die111 to Federa l Stnff $ 16,4 76 $22,000 I 8b(4) Tra ve l a nd Per Di e 111 to No n-M embe r Consu lt ant s $ 11,716 $ 13,040 I Sc.Othe r(r ent s, use r charges,grap hi cs,printing,m ai l etc.) $57,617 $44,147 18d Tota l $687,567 $812,325 I 9. Federa l Staff Sup po,1 Years 4.0 4.0

I of2 12 /16/1999 2:57 PM SF 820 http: l/204.254. 112.5 /cms /RptAnnualReport.asp

20a. How doe s th e Co mmitt ee acco mpli s h it s purµ ose?

During FY 1999, the ACNW held nine meetings and wrote eight reports. To conduct its reviews, the ACNW meets regularly with the NRC s taff, the industry, other government agencies, and interested members of the public and public inter*cst groups. In addition, the Committee meets periodically with the NRC Commissioners to discuss issues of mutual interest. The Committee's work has impacted the NRC,*cgulatory process significantly, including the Department of Energy's (DOE's) License Application Design Selection Process (LADS) and Recommended Repository Design; linear no threshold hypothesis; a review and evaluation of the NRC Safety Research Program, NUREG-1635, Vol. 2; DO E's viability assessment for the proposed high-level radioactive waste repository at Yucca Mountain, Nevada; the regulatory uses of importance measures for waste management and possible application to the proposed high-level radioactive waste repository at Yucca Mountain, Nevada; the development of a standard review plan for decommissioning, NRC's Draft 10 CFR Part 63 and Revision O of the Total System Performance Assessment Issue Resolution Status Repm*t; issues and recommendations concerning the near-field environment, and the performance of engineered barriers at Yucca Mountain. The ACNW also provided to the NRC its 1999 action plan and priority issues and its metrics and selt~asscssment evaluation for FY 1998. The ACNW visited German Waste Isolation Authorities and Facilities on September 14-18, 1998, and prnvidcd its general observations and impressions on this visit.

20b. How does th e C o mmitte e bal a nce it s m e mber s hip ?

The NRC appoints ACl\\"V members from scientific and engineering disciplines with three prerequisites in mind: outstanding scientific and technical ability, balanced and mature judgment, and willingness to devote the time required to the demanding work involved. The pool of industry. There has been a conscious effort to obtain members with backgrounds that can address the difficult and diverse questions associated persons so qualified is limited. At the end of FY 1999, the Committee included two members from academia and two members from private

with radioactive waste disposal. This permits and fosters a concentration of scientific proficiency within the Committee, together with a diversit y of viewpoints and perspectives, that provides assurance that adequate, independent, and open discu ssion and analysis of the potential hazards of nuclear waste can take place. During FY 1999, the ACNW included engineers and scientists experienced in radioactive waste management, chemistry, nuclear engineering,.-isk assessment, environmental engineering, performance assessment, hydrology, mining engineering, research, and technical management. The diversity of viewpoints represented by current members is broadly based from the standpoint of special fields of interest, employment experience, and scientific or technical specialty. These characteristics provide the ACNW with a balance of highly qualified technical experts.

20c. How fr equ e nt and re le v ant are th e Co mmitt ee m ee tin gs?

The ACNW held nine Full Committee meetings during FY 1999. The number of meetings held is directly related to the review schedule and scope of efforts on the high-level waste geologic repository, issues involving low-level waste disposal, the number of criteria, guides, and technical positions referred for review and comment, the number of special reviews requested by the NRC, and topics of particular concern /interest to the Committee. The Full Committee plans to meet approximately eight times during FY 2000. Full Committee meetings generally run two to three days and cover a variety of topics (review of the Yucca Mountain review plan and related ' RC staff analysis,

technical positions on high-level and low-level waste issues, briefings and reviews of rulemakings, etc.). For particularly complex issues, the ACNW holds working group meetings where additional time and expertise can be brought to bear on an issue and the subject developed prior to Full Committee considerations. If the ACN\\V is to continue to meet the requirements of its charter, it needs to meet with at least a similar frequenc y in the future. There is a continuing need for the technical advice provided by the ACNW to the Commission, particularly in the followin g areas: (a) the site suitability for the Yucca Mountain repository, (b) interim surface storage facilities, to the extent that programs arc directed toward such facilities, (c) reassessment of regulatory standards for Yucca Mountain, (d) use of risk assessment communication in the regulatory process, and (e) site decommissioning. The ACNW will provide advice to the Commission on issues related to NRC's oversight of DO E facilities.

20d. Wh y cc1 11 't th e ndvi cc o r in fo rm a tio n thi s co mmittee prov id es be o bt a in ed e lsew he re'?

The mandate is to provide the Commission with independent advice in this area. The Commission necessaril y ha s its own expert s taff on whom it ACN\\V is unique in that there exists no comparable body of acknowledged experts in the field of nuclear waste management whose

relics in its day-to-day operations. However, the Commission has no other advisory committee with the current, broadly based knowledge of the ACNW that could be called upon for independent assessment of safety issues related to high-and low-level w,rste management and di s posal.

In addition, since members arc part-time advisors with other full-time interests and activities in related fields, they generate an organized synergistic approach to provide a br-cadth of experience, an independent perspective on issues, and statc-of~thc-art technical knowledge that would be difficult to duplicate with full-time government employees. A continuin g committee such as the ACNW also remains current with respect to nuclear waste issues, including related safety research, and provides a collegial judgment regarding these issues that would be impossible to duplicate by use of individual, part-time consultants on a case-by-case basis. Through the ACNW, the public is provided assurance that an independent technical review and evaluation of nuclear waste safety issues is accomplished and an opportunity for public input is assured.

20e. Wh y is it necess ary to cl ose a nd/or pm 1iall y cl ose co mmitt e e meetin gs?

During this period, the Committee held nine Full Committee meetings. All portions of these meetings were open to public attendance.

2 1. Re ma rk s NONE Des ig nated Federa l Official : Michele Kelton DFO

Co mmitt ee M e m be rs Occ upa t io n Fairhurst, Dr. Charles Professor Emeritus of Civil Engineering,Univcrsity of Minnesota and Senior Engineer /Chairman of the Board, Itasca Consulting Group, Inc.

Garrick, Dr. B. John Consultant Hornberger, Dr. George M. Professor, Dept. of Environmental Sciences, University of Virginia W y mer, Dr. Raymond G. Retired, Distinguished Scientist in the International Technology Programs Division of Martin Marietta Energy Systems, Inc.

Tota l Co unt o f Co mm illee M e mb e rs 4

2 of2 12 /16/19992:57 PM SF 820 http :1/204.254.1 12.5 /cms /RptAnnual Re port.a s p

1999 Annual Report: Review of Federal Advisory Committee Committee Menu

12 /16/1999 3:00:35 PM I. Depai1ment or Age nc y 2. Fisca l Year Nuclear Regulatory Commission 1999

3. Co mmitt ee or SubCommitt ee 3b. GSA Committ ee No.

Advisory Committee on Reactor Safeguards 207

4. Is thi s New During Fi sca l Yea r? 5. C u1Te nt Cha11er 6. Expec ted Renewa l Date 7. Ex pected Te nn Date No 12 /23 /1996 12/23 /2000 Sa. Was Te m1in ated Dur ing FY ? Sb. Speci fi c Te rmin atio n Aut ho rity Sc.Ac tu a l Tenn inat io n Date No 42 U.S. C. Sect. 2039 & 2232 9. Age ncy Reco mm e nda tion for Nex t FY I Oa. Leg islat ion Req to Te nnin ate? I Ob. Leg islati on Pe ndin g?

Continue No

11. Es tab li s hm ent Auth o rity Statutory(Congress Created)

12. Spec ifi c Es tab li s hm ent Auth or it y I 3. Effec ti ve Date 14. Committ ee Ty pe 14c. Presi de nti al?

42 U.S.C. Sect. 2039 & 2232 1/1/1957 Continuing No

15. Desc ription o f Co mmitt ee Scientific Technical Program Advisory Board

16a. To tal Numb e r o f Repor1 s 54 16b. Repo rt Titl es and Dates Risk-Informed Pilot Application for Hydrogen Monitoring at Arkansas Nuclear On e, Units l and 2 I0 /14/1998 Proposed Priorit y Rankin gs of Generic Safety Issues: Tenth Group I 0 /16/1998 The Nuclear Energy lnstitute's Petition for Rulemaking to Amend Paragraph (a) of 10 CFR 50.54, Conditions of Licenses 10 /20 /1998 Proposed Inspection Procedure 35XXX, "Graded Quality Assurance" 11/13/1998 Proposed Revision to the Enforcement Policy 11 /17/1998 Proposed Rule on Use of Alternative Source Term at Operating Reactors 11 /19 /1998 Safety Evaluation Rpt. Rel to Westinghouse Owners Grp. Application of Risk-Informed Methods to lnservice Inspection of Pipin g, I l/20/l 998 Topical Rpt. (WCAP-14572, Rev. l)

Reprioritization and Proposed Resolution of Generic Safety Issue 171, "Engineered Safety Features Failure from 11 /23 /1998 Loss-of-Offsite-Power Subsequent to a LOCA" Options for Incorporating Risk Insights Into the IO CFR 50.59 Proces s 12 /11 /1998 Proposed Commission Paper Concerning Options for Risk-Informed Revisions to 10 CFR Part 50, "Domestic Licensing of 12/14 /1998 Production and Utilization Facilities" Proposed lr_nprovcmcnts to the N RC Inspection and Assessment Program s - Interim Report I 2/16 /1998 List of Questions to be Addressed for Possible Resolution of Key Issue s A ssociated with the Proposed Revision to IO C FR 50.59 2/18/1999 (C hanges, Tests and Experiments)

N FP A 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plant s " 2/18/1999 Re s olution of Generic Safet y Issue B-61, "Allowable ECCS Equipment Outa g e Periods" 2/19/1999 SE C Y-98-244, " NRC Human Performance Plan" 2/19/1999 Proposed Improvements to the NRC Inspection and Assessment Program s 2/23/1999 SE C \\'-99-054, "Plans for Final Ruic - Revisions to 10 CFR Parts SO, 52, and 72: R equirements Concerning C hanges, Tests and 3/22 /1999 Experiments" Co re Research Capabilities 3 /22 /1999 Lessons Learned from the ACRS Review of the APG00 Design 3 /22 /1999 Propo s ed Amendment to 10 CFR 50.72, Immediate Notification and 50.73, Licensee Event Reporting S y stem 3/23 /1999 Guidance Memorandum for Implementation of the Revised Enforcement Polic y 3 /24 /1999 Application of Westinghouse Best-Estimate Loss-of-Coolant Accident Anal y sis Methodolog y to U pper Plenum Injection Plant s 3 /24 /1999 High Burnup Fuel Phenomena Identification and Ranking 3 /24 /1999 Propo s ed ASME Standard for Probabilistic Risk Assessment for N uclear Power Pinnt Applications (Phase l) 3 /25/1999 Proposed Final Revision to IO CFR 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power 4 /14/1999 Plants" SE C Y-99-017, "Proposed Amendment to IO CFR S0.55a" 4 /19/1999 Reevaluation of Generic Safety Issue Process 4 /19/1999 Status of Efforts on Revising the Commission's Safety Goal Policy Statement 4 /19 /1999 Status of Resolution of Steam Generator Tube Integrity Issues 4/22 /1999 Proposed Revisions to the NRC Generic Communications Process 4/23 /1999 M o dified Proposed Final Revision to 10 CFR 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclear 5/11 /1999 Power Plants" Proposed Resolution of Generic Safety Issue-158, "Performance of Safety-Related Power -Op erated Valves Under Design Basis 5/14/1999 C ondition s "

Us e o f Mixed Oxide Fuel in Commercial Nuclear Power Plants 5/17/1999 Propo sed Final Rule - Revisions to 10 C FR Parts SO and 72 Concerning C han g es, Te s ts, and Exp e riment s 5/17/1999 The Role of Defense in Depth in a Risk-Informed Regulatory S y stem 5/19/1999

I o f 4 12 /16 /199 9 2: 58 PM SF 820 http:1/204.254.112.5 /cms/ RptAnnualReport.asp

Interim Letter on the Safety Aspects of the Baltimore Gas and Electric Company's License Renewal Application for Calvert Cliffs 511911999 Nuclear Power Plant, Units I & 2 Modifications Proposed by the Westinghouse Owners Group to the Core Damage Assessment Guidelines and Post Accident 5/19/1999 Sampling System Requirements Proposed Resolution of Generic Safety Issue-165, "Spring-Actuated Safety and Relief Valve Reliability" 6/9/1999 Exemption Request to the Hydrogen Control Requirements for the San Onofre Nuclear Generating Station, Units 2 and 3 6/9/1999 Pilot Application of Rev. Inspection and Assmnt. Programs, Risk-Based Performance Indicators, and Performance-Based 6/10/1999 Regulatory Initiatives and Related Matters Development of a Low-Power and Shutdown Risk Assessment Program 6/11/1999 Pniposed Options for Using Averted Onsite Costs and Voluntary Initiatives in Regulatory Analyses 6/11 /1999 SECY-99-148, "Credit for Existing Programs for License Renewal" 7/19 /1999 Proposed Final Regulatory Guide 1.181, "Content of the Updated Final Safety Analysis Repo1*t in Accordance with IO CFR 7/21 /1999 50.71(e)"

Proposed Revision 3 to Regulatory Guide 1.160 (DG-1072), "Assessing and Managing Risk Before Maintenance Activities at 7/21/1999 Nuclear Power Plants" Revision of Appendix K, "ECCS Evaluation Models," to IO CFR Part 50 7/22/1999 Proposed Final Amendment to 10 CFR 50.55a, "Codes and Standards" 7/23/1999 Interim Letter-Related to the License Renewal of Oconee Nuclear Station 9/13/1999 Proposed Final Revision 3 to Regulatory Guide 1.105, "Setpoints for Safety-Related Instrumentation" 9/13 /1999 Safety Evaluation Report Rel. to Electric Power Research Institute Risk-Informed Methods to Inservice Inspection of Piping (EPRI 911511999 TR-I 12657, Rev. B, July 1999)

• Prop. Rev. I to Reg. Guide 1.78 (DG-1087), "Evaluating the Habitability of a Nuclear Power Plant Control Room During a 9/16 /1999 Postulated Hazardous Chemical Release" Proposed Resolution of Generic Safety lssue-145, "Actions to Reduce Common Cause Failures" 9/17/1999 Modifications Proposed by the Westinghouse Owners Group to the Core Damage Assessment Guidelines and Post Accident 9/17/1999 Sampling S y stem (PASS) Requirements Proposed Final Rule on Use of Alternative Source Term at Operating Reactors, Associated Draft Regulatory Guide, and Standard 911711999 Review Plan 17a Open: 42 17b. Closed: 0 17c. Part iall y Closed: 5 17d. Tota l Meet in gs 47 Mee tin g Pur poses a nd Dat es 456th Full Committee Meeting 9/30/1998 I 0/2/1998 Joint Reliability & Probabilistic Risk Assessment and Regulatory Policies I0 /29 /1998 I 0/29 /1998

& Practices 457th Full Committee Meeting 11/4/1998 11/7/1998 Planning & Procedures I 1/4/1998 I I /4/1998 Plant License Renewal 11/18/1998 11/18/1998 Thermal-Hydraulic Phenomena 11 /19 /1998 11/19/1998 Jt. Reliability & Probabilistic Risk Assessment and Plant Operations 11/19/1998 11 /20 /1998 Planning & Procedures 12 /2/1998 12 /2/1998 458th Full Committee Meeting 12 /3 /1998 12 /5/1998 Thermal-Hydraulic Phenomena 12/16/1998 12/17 /I 998 Fir*e Protection 1/20/1999 1/20 /1999 Reliability & Probabilistic Risk Asessment 1/25 /1999 1/25 /1999 JI. Reliability & Probabilistic Risk Assessment and Plant Operations 1/26 /1999 1/26/1999 Planning & Procedures 2/2/1999 2 /2/1999 459th Full Committee Meeting 2/3 /1999 2/6/1999 Thermal-Hydraulic Phenomena 2/23/1999 2/23/1999 Planning & Procedures 3 /9 /1999 3 /9/1999 460th Full Committee Meeting 3/10/1999 3 /13/1999 Thermal-Hydraulic Phenomena 3/23 /1999 3 /23 /1999 Materials & Metallurgy 3/24/1999 3/25/1999 Planning & Procedrues 4/6/1999 4/6 /1999 Jt. Reliability & Probabilistic Risk Assessment and Regulator y Policies & 4 /7/1999 4/7/1999 Practices 461st Full Committee Meeting 4/7/1999 4/10/1999 Jt. Reliability & Probabilistic Risk Assessment and Regulatory Policies & 4 /21 /1999 4 /21/1999 Practices Plant License Renewal 4 /28/1999 4 /29 /1999 Severe Accident Management 4/30 /1999 4/30/1999 Safet y Research Program 5/4 /1999 5/4 /1999 Jt. Reliabilit y & Probabilistic Risk As s essment and Materials~~ Metallurgy 5/5/1999 5/5/1999 Planning & Procedures 5/5/1999 5/5/1999 462nd Full Committee Meeting 5/5/1999 5/8/1999 Jt. Advisory Committee on Reactor Safeguards and Advisory Committee 5/11/1999 5/11/1999 on Nuclear Waste Working Grp.

Thermal-Hydraulic Phenomena 5/26 /1999 5/2711999 Severe Accident Management 5 /27/1999 5 /27 /1999

2 of 4 12/16/1999 2:58 PM SF 820 http :1/204.2 54.112.5 /cms /RptAnnu a lR epo rt.a s p

Severe Accident Management 5/27 /1999 5/27 /1999 463rd Full Committee Meeting 6/2/1999 6/4/1999 Jt. Plant Operations and Fire Protection 6/23 /1999 6 /23 /1999 Plant License Renewal 6 /30 /1999 7/1/1999 Jt. Reliability & Probabilistic Ri s k Assessment and Regulatory Policies and 7/13 /1999 7/13 /1999 Practices Planning & Procedures 7/13/1999 7/13/1999 464th Full Committee Meeting 7/14/1999 7/16 /1999 Severe Accident Management 8/9/1999 8 /10/1999 Planning & Procedures 8/31 /1999 8/31 /1999 465th Full Committee Meetin g 9/1/1999 9/3/1999 Thermal-H y draulic Phenomena 9/15/1999 9 /16/1999 Seve re Accident Manag e ment 9/16/1999 9/17/1999 Plant License Renewal 9/23 /1999 9/23 /1999 Jt. Reliabilit y & Probabilistic Ri sk Assessment and Regulator y Policies & 9/23 /1999 9 /24 /1999 Practice s Plannin g & Procedure s 9 /29 /1999 9/29 /1999

Curre nt Fiscal Year Next Fi sc al Year 18a( I ) Personnel Pmts lo Non - Federal Memb ers $ 554,082 $ 580,678 I 8a(2) Pe rso nnel Pmts to Federal Members $0 $ 0 I 8a(3) Person ne l Pmt s lo Federal Staff $ 1,880,8 25 $ 1,973, 554 I 8a(4) Personne l Pmts to Non -m e mb e r Co n s ult a nt s $14,618 $ 29, 120 I Sb( I) Travel and Per Diem to Non - Federa l Members $228,018 $ 164,900 I 8b(2) Travel a nd Per Diem to Federa l Members $ 0 $0 I 8b(3) Travel and Per Di em lo Federal Staff $22,767 $ 17,460 I 8b(4) Trave l and Pe r Di e m lo No n-M embe r Co ns ult a nt s $6, 491 $7,0 00 l 8c.Ot her(ren ts,use r charges,grap h ics,p rintin g,mai l e tc.) $94, 540 S70,60 4 18d Tota l $2,8 01,341 $2,843,316 19. Federa l Staff Support Years 21.8 20.8 20a. How does the Comm ill ee accomplish its purpose?

As required by statute, the ACRS performs independent reviews of safety issues associated with the operating nuclear power plants, adequacy of new reactor designs, license renewal applications, and safety-related technical issues associated with new designs and provides valuable and timely advice to the NRC on these matters. During FY 1999, the ACRS completed 54 reports, which included it s annual report to the Co mmission on the NRC Safety Re se arch Program (NUREG-1635, Volume 2) and held 10 Full Committee meetin gs and 37 Subcommittee meetin gs. In conducting its review s, the ACRS meets regularly with the N R C s taff, industry, other gove rnment agencies, public interest groups, which g i ves the AC RS the opportunity to review a broad range ofNRC regulatory actions. In addition, the AC R S has periodic meetings with and intere s ted members of the public. The ACRS and NRC staff interact under procedures established by a Memorandum of U nder s tandin g, th e NR C Co mmi ss ioner s and wit h indi v idual N RC office director s to di sc uss issues of mutual intere st. The AC RS was particularl y effective in pr ovid in g timel y a dvice to the Co mmi ss io n on seve ral important issues, including: sa fet y aspects of the Baltim ore Gas and Electric Co mpan y's License Renewal Application for Ca lvert Cliffs N uclear Power Plant, Unit s I a nd 2; license renewal of Oconee N ucl ear Station, U nit s 1, 2, and 3 ; credit for existing pr ogra m s for licen se renewal; proposed amendment to 10 CF R 50.SSa, "Code s and S tandards;" proposed final revision to 50.59 (Changes, Tests and Ex periments) ; propo sed options for r is k-informed revi s ions to 10 CFR Part SO, " Dome s tic Licensing of Production 10 CF R 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at N uclear Power Plant s;" prop ose d final revision to 10 CF R and Utilization Facilities;" options for incorporating risk insights into th e 10 CF R 50.59 process ; list of questions to be addressed for po ss ible resolution o f ke y issues associated with the proposed revision to 10 CF R 50.59 ; th e role of defense in d e pth in a.-i s k-informed regulator y sys tem ; status of efforts on revising the Co mmission's Safety Goal Polic y Statement; proposed ASME Standard for probabilistic risk assessment for nuclear power plant applications; use of mixed oxide fuel in commercial nuclear power plant s; high burnup fuel phenomena identification and ranking; and proposed rule on use of alternative so urce term at operating reactors. Other iss ues reviewed by the ACRS in inspection o f piping ; modification s proposed by We s tinghouse Owners Group to the Core Damage Assessment Guidelines and Post Accident FY 1999 included: a safety evaluation report related to Westin g house Owners Group application ofrisk-informed methods to inservice Sa mplin g System Requirements ; propo se d prioritization of generic sa fet y issues; re eva luation of the ge neric safety iss ue proces s; revi sion of Ap pendix K, "ECCS Evaluation Models;" proposed resolution of Generic Safe ty Iss ue-158, "Performance of Sa fet y-Related Power-Operat e d Va lve s U nder De s ign Basi s Co ndition s :" low-power and s hutdown ri s k assessment pro g rnm ; propo se d final Revi sio n 3 to R eg ulator y Guide 1.105, "Setpoints for Safety-Related In s trumentation ;" propo sed revision to NR C Generic Communications process; propo s ed re v is ion to the E nfor ce ment Policy ; proposed revision to NRC In s pection and Assessment pro g ram s; and NF PA 805, "Performance-Based Standard for Fire Prot ec tion for Li g ht Water Rea c tor Electric Generating Plant s." The Co mmittee 's work has had a s ig nificant imp ac t on the N R C re g ulator y proc ess.

20b. How does the Commillee balan ce its m e mb e rship ?

The NR C appoints ACRS membe, *s fr o m the scientific and engineering disciplines with three prerequi s ites in mind : outstanding scientific and technical ability, balanced and mature judgment, and willingness to devote the time required to the demandin g work involved. There has been a conscious effort to obtain membe, *s trained in both nuclear and nonnuclear disciplines who have had considerable experience in various field s needed to evaluate design, construction, and operation of nuclear power plants and related facilities. During FY 1999, the membership included those experienced in the areas of nuclear power plant operation s; probabilistic risk assessment; analy s is of severe reactor accident phenomena ; design of nuclear power plant structures, systems, and components; mechanical, civil, and electrical engineering; materials and metallur gy; thermal-h y draulics and computational fluid dynamics; and digital instrumentation and control systems. The diversity of viewpoints represented b y current members is broadl y based from the standpoint of special fields of intere s t, employment experience, and scientific or technical specialty. These membership characteristics provide the Committee with a balanc e of hi g hl y qualified technical experts in the nucle a r and nonnuclear field s nece ssa ry to carry out the Co mmittee 's s tatutor y requirements.

3 of 4 12 /16/1999 2:58 PM SF 820 http ://204.254.112.5/cms /RptAnnual Rcport.asp

20c. How frequent a nd releva n t are the Committee meetings?

The ACRS and its Subcommittees held 47 meetings during FY 1999 of which 10 were Full Committee meetings. The number of meetings held is directly related to the number of nuclear safety matters reviewed by the Committee that were referred to it by the NRC or required by statute; the num her of generic issues that arose during the year; the number of rules, and regulatory guidance referred to the Committee for interest /concern to the Committee. The Full Committee nor*mally meets ten times a year for three 01* four days to consider various review and comment; the number of special reviews requested by the NRC Commissioners and Congress; and areas of particular safety-related nuclear issues, generic and special reviews, rules, and regulatory guidance. ACRS Subcommittees meet as necessary with licensees, NRC staff, nuclear industry groups, other government agencies, and other interested parties to develop information for the Committee on the particular matters under review and to identify those matters warranting particular attention by the Full Committee. There is a continuing need for the technical advice provided by the ACRS to the Commission particularly in its transition from prescriptive to risk-informed and performance-based regulation and its need to review new reactor designs.

20d. Wh y can 't the advice o r infonnati on this committee provides be obtained elsewhere?

The ACRS is unique in that there exists no comparable body composed of acknowledged experts in the field of nuclear reactor safety whose Congressional mandate is to provide the Commission with independent advice in this area. Upon request, the ACRS also provides advice to the U.S. Navy, the Department of Energy, and the Nuclear Facilities Safety Board. This further demonstrates the unique qualifications of the ACRS within the Federal government. The Commission necessarily has its own expert staff on whom it relics in the day-to-day regulation of nuclear power facilities. However, no other advisor*y committee, either within the Commission or in other agencies, has the current, broadly based knowledge of the ACRS that can provide independent assessments of reactor safety issues. In addition, since ACRS members are primarily part-time advisors with other full-time interests and activities in related fields, they provide a breadth of experience, an independent perspective on issues, and state-of-the-art technical knowledge that would be difficult to duplicate with full-time government employees. A continuing Committee such as the ACRS also remains current with respect to nuclear safety issues, including those related to reactor operating experience and safety research, and provides a collegial judgment regarding these issues that part-time consultants could not provide. Through the ACRS, the public and the Congress are assured of an independent technical review and evaluation of nuclear reactor projects and safety issues and of an opportunity for public input.

20e. Why is it necessary to close and/or partially close committee meetings ?

During this period, the Committee held 10 full Committee meetings during which Committee business of the usual nature was conducted.

Portions of these meetings were closed and time spent in closed sessions occupied approximately I hour 30 minutes. This session was closed to discuss: information provided in confidence by a foreign source 15 U.S.C. 552b(c)(4)1.

21. Remark s None

De sig nat ed Federal Official: Michele S Kelton DFO Committee Members Occupati o n Apostolakis, Dr. George E. Professor, Nuclear Engineering Department, Massachusetts Institute of Technology Barton, Mr. John J. Retired Vice-President, GPU Nuclear Cor*poration Bonaca, Dr. Mario V. Retired Director, Nuclear Engineering Department, Nor*theast Ut ilities Fontana, Dr. Mario 1-1. Adjunct Professor, Nuclear Engineering Department,U niversit y ofTenncssee Kress, Dr. Thomas S. Retired Head of Applied Systems Technology Section, Oak Ridge National Laboratory Miller, Dr. Don W. Professor and Chair, Nuclear Engineering Department, Ohio State University Powers, Dr. Dana A. Senior Scientist, Nuclear Facilities Safety Department, Sandia National Laboratories Scale, Dr. Robert L. Professor Emeritus of Nuclear & Energy Engineering, University of Arizona Shack, Dr. William J. Associate Director, Energy Technology Division, Argonne National Laboratory Sieber, Mr. John D. Retired Senior Vice-President, Nuclear Power Division, Duquesne Light Company Uhrig, Dr. Robert E. Distinguished Professor, Nuclear* Engineering Department, University of Tennessee Wallis, Dr. Graham B. Professor, Thayer School of Engineering, Dartmouth College Total Co unt of Committee M e mber s 12

4 of 4 12 /16/1999 2:58 PM SF 820 http: //204.254. l l 2.5 /cms /RptAnnualReport.a sp

1999 Annual Report: Review of Federal Advisory Committee Committee Menu

12 /15/19994:06:12 PM

I. D epa 11m ent o r Agenc y 2. Fi sca l Year Nuclear Regulatory Commission 1999

3. Co mmitt ee or SubCommitt ee 3b. GSA Co mmitt ee No.

Licensing Support System Advisory Review Panel 1104

4. Is thi s New During Fi sc al Year ? 5. C u1Tent Cha11er 6. Expected Rene wal Dat e 7. Expected Tem1 Date No 12 /19/1996 12/17/2000 12 /20 /2005 8a. Was Terminated During FY ? Sb. Speci fi c Te nnin a tio n A uthority Sc.Ac tu al Te,miu atio n Date No 42 u.s.c. 2201

9. Age ncy Reco mm e ndati on for Nex t FY 1 Ga.Legis latio n Req to Te rmin ate ? I Ob. Legis lati on Pending 9 Continue 11. Es tab lis hm ent A uth ority Agency Authority

12. Specific Es tab li s hment Au thori ty 13. Effecti ve Date 14. Co mmi ttee Type 14 c. Pr cs id e nti al9 42 u.s.c. 2201 1/19 /1975 Continuing No

15. Desc ri pti on o f Committ ee Non Scientific Program Advisory Board 16a. Tota l Numb er o f Re port s No Report s for this Fiscal Year.

17d. Total Meet in gs No Meetings for thi s Fiscal Year.

C un*e,11 Fiscal Yea r Nex t Fi scal Yea r 18a( I) Perso nne l Pmt s to No n-Fede ral Me m be rs $0 $ 0 I 8a(2) Pe rso nn e l Pmt s to Fede ral Me m be rs $0 $ 0 I 8a(3) Pe rso nn e l Pmt s to Fede ral Sta ff $0 $0 18a(4) Pe rso nn el Pmt s to Non-m em be r Co ns ult ant s $0 $2, 140 I Sb( I) Travel a nd Pe r Di e m t o No n-Federa l Me m be rs $0 $0 I 8 b(2) Trave l and Per Diem to Fede ral Me mb e rs $0 $7,090 I 8b(3) Trave l and Per Di em t o Federa l Sta ff $0 $7,200 18b( 4) Trave l and Per Diem to Non-M emb er Co ns ultants $0 $0 I 8c.Oth e r(re nt s, user charges,g ra phic s, printing, ma il etc. ) $0 $1,820 18d Total $0 $18,250

19. Federa l Staff Sup po rt Years 0.0 0.0 20a. How does th e Co mm itt ee acco m plish it s purpose9 The Department of Energ y and the Nuclear Regulatory Commission continue to rel y heavil y upon the Licensin g Support Network Advisor y Re v iew Panel (LSNARP) for advice and recommendations on a searchable electronic database for documents that will be pertinent to the licensing of a geologic repositor y for the storage of high level nuclear wa s te in 2002. During this reporting period, the LSNARP ' s efforts w e r e concentrated primarily on refocu s ing technology design s to reflect change s to 10 CFR Part 2, Subpart J. The revi s ions to the Rule permit bett e r utilization of technology advances which allow use of the Internet to se arch and retrieve appropriate documents in dispersed location s rather than in a centralized database.

20b. How does th e Co mmitt ee balai,ce it s mem be rs hip?

The membership of the LSSARP is balanced by being drawn from among the full spectrum of potential parties to NRC's anticipated licensing proceeding for the burial of high level radioactive waste. Since the burial site under review is in Nevada, the membership includes the State of Nevada, local county governments of both Nevada and California, Indian tribes, represented by the National Congress of American Indians and the Nevada Nuclear Waste Task force. It also includes the nuclear industry, the potential licensee (DOE) and the licensing agency (NRC).

Input by these representatives is essential to the success of the LSS project.

20c. How freq ue nt and re leva nt are th e Co mmitt ee m ee tin gs?

The Ruic was revised in early part of FY99 (Jan.). Panel was renamed from Licensing Support System (LSS) to Licensing Support Network (LSN) to.-eflect the inherent use of the internet for accessing the relevant documents used in the discovery proce ss. The Commission reassi g ned responsibilit y to the Atomic Safet y and Licensing Board Panel (ASLBP) and staffed the LSN Administrator po s ition and reconven e d the LSNARP. Preparations were made for resuming LSNARP meetings in October 1999. The level of LSNARP activity is expected to remain at a moderate level during FYOO.in order to provide advice on the establishment of Int e rnet sites and access protocol s for each of the participants database of materials relevant to the anticipated licensing proceeding.

20 d. Wh y ca n't th e adv ice or in fo nn atio n thi s co mmitt ee prov id es be obt ai ned e lsew he re?

The advice provided by the state, county and tribal governmental units, together with other potential users of the LSS, is unique to this particular computer application. It is not available from other existing committees or from NRC itself. NRC considers it essential that such establishing an informal users group as an alternative to this committee. Since public comment favored retention of this committee, however, advice should come from these entities which will be hands-on users of LSS. The NRC sought, during this reporting period, public comment on the Commission has determined to retain it. During the next reporting period, the Commissin plans to rename the Panel as the Licensing Support Network Advisory Review Panel.

20e. Wh y is it necess aiy to cl ose and/or pa11 ia ll y c lose comm itt ee m ee tin gs?

Th e LSSARP did not hold any closed meetings in FY 1999.

21. Re m arks N O N E

Designated Federal Officia l: John C. Ho y le DFO

l of 2 12 /15 /19 99 4:04 PM SF 820 bttp ://204.254.112.5 /cms /RptAnnualReport.asp

Co mmitt ee Mem be rs Occ upa ti on Bechtel, Dennis Clark County, Nevada Bradshaw, Les Nye County, Nevada Cain, Tony Esmeralda County, Nevada Cameron, \\Vayne White Pinc County, Nevada Clark, Ray US EPA Copenlrnfcr, David U.S. Securities and Exchange Commission Culvcnvell, Eve Lincoln County, Nevada Cummings, Peter City of Los Vegas, Nevada Elquist, Bill Lander County, Nevada Fiorenzi, Leonard Eureka County, Nevada Frishman, Steve State Of Nevada Funk, Ario Mineral County, Nevada Goichoechea, Pete J Eureka County, Nevada Henkel, Christopher Nuclear Energy Institute - Energy Coalition Hoffman, Juanita Esmeralda County, Nevada Holden, Robert National Congress of American Indians Hoyle, John C US Nuclear Regulatory Commission Kall, Alan Churchill County, Nevada Kolkman, Debra White Plan County, Nevada Kraft, Steven Nuclear Energy Institute - Energy Coalition Manzini, Tammy Lander County Nevada Metoxen, Loretta National Congress of American Indians Mcttam, Brad In y o Count y, Nevada Murphy, Malachy Nye County, Nevada Newbury, Claudia US Department of Energy Regan, James Churchill County, Nevada Remus, Andrew Inyo County, Nevada Silberg, Jay Attorney - Industry Coalition Swainston, Harry State of Nevada Treichel, Judy Nevada Nuclear Waste Task Force Wallace, Jackie Mineral County, Nevada Tot a l Co unt of Co mmitt ee Memb ers 31

2 of2 12 /15 /1999 4:04 PM SF 820 http: //204.254. I l 2.5 /cms /RptAnnual ke port.asp

1999 Annual Report: Review of Federal Advisory Committee Committee Menu

12/15/1999 4:01 :45 PM I. Department or Agency 2. Fi scal Year Nuclear Regulatory Commission 1999 3. Committee or SubCommittee 3b. GSA Committee No.

Pilot Program Evaluation Panel 5287

4. Is this New During Fiscal Year? S. Current Charter 6. Expected Rene w al Date 7. Expected Tenn Date Yes 6/30/1999 6/29/2001 6/30/2001 Sa. Was Tenninated During FY? Sb. Specific Termination Authority Sc.Actual Te1111i11ation Date No 42 u.s.c. 2201

9. Agency Rec o mmendation for Next FY !0a.Legislation Req to Tenninat e? I Ob.Legislation Pending ?

Continue 11. Establishment Authority Agency Authority

12. Specific Establishment Authorit y 13. Effective Date 14. Committee T y pe 14 c. Presidential?

42 u.s.c. 2201 1/19/1975 Ad Hoc No 15. Description of Committee Scientific Technical Program Advisory Board 16a. Total Number of R epo 11 s No Reports for this Fiscal Year.

17a Open : 2 17b. Closed: 0 17c. Partially Closed: 0 17d. Tot a l Meetings 2 Meeting Purposes and Da tes Organizing Meeting and Discussion of Pilot Program Evaluation Process 7/28/1999 7/28/1999 Discussion on Initial Results of Pilot Plant Inspections and Need for 8/17/1999 8/17/1999 Data Analysis

Current Fiscal Year Next Fiscal Year

!Sa(!) Perso nnel Pmt s to Non-Federal Members $0 $0

I 8a(2) Pe rso nnel Pmt s to Federal Members $0 $0 I 8a(3) Personnel Pmt s to Federal Staff $30,000 $60,000

!8a(4) Perso nn el Pmt s to Non-member Consultants $0 $0 I Sb( I) Travel and Per Diem to Non-Federal Member s $1,712 $6,400

I 8b(2) Travel and Per Diem to Fed era l Members $0 $0

I 8b(3) Travel and Per Di em to Fede ral Staff $520 $0 18b(4) Travel and Per Diem to Non-Member Co ns ultant s $0 $0

\\ Sc.Ot her ( rent s, user charges,g raphics, printing,mail etc.) $0 $0 18d Total $32,232 $66,400 I 9. Federal Staff Support Year s 0.3 0.5 20 a. How does the Committee accomplish its purpose?

The NRC has developed a revised regulatory oversight process for commercial nuclear power plants. The new risk-informed baseline inspection program, a new streamlined assessment process, and a new enforcement policy form the basis for this oversight program. The Commission instituted a pilot program that would be performed at two sites per region to exercise these new oversight processes prior to full implementation. The PPEP functions as a management-level, cross-disciplinary oversight group to independently monitor and evaluate the results of the pilot effort. The PPEP meets periodically during the pilot program to review the implementation of the oversight processes and the results generated by the Pl reporting, baseline inspection, assessment, and enforcement activities. These meetings ar-e publically announced in advance, open to the public, and all material reviewed is placed in the public document room. A meeting summary will be prepared following each meeting to document the results of the meeting. The PPEP will evaluate the pilot program results against established success criteria. For those success criteria that are intended to measure the effectiveness of the processes, and that generally do not have a quantifiHble performance measure, the PPEP will serve as an " expert panel" to review the results and evaluate how well the success criteria were met. At the end of the pilot program, the PPEP members will provide an evaluation as to whether each of the success criteria have been met. This report will include both the consensus view of the panel, along with the dissenting views of any of the panel members. The staff will use the PPEP evaluation to determine the need for any additional process development or improvements prior to full implementation.

20b. How does the Committee balance its m embers hip ?

The PPEP is balanced by including participants from NRC headquarters and regional management, a representative from the Nuclear Energy Institute, pilot plant licensee management representatives, a representative from the Union Of Concerned Scientists, and a representative from the Illinois Department of Nuclear Safety.

20c. How frequent and relevant are the Committee meetings ?

Meetings are held bi-monthly. A Final report is expected in April 2000.

20d. Wh y can 't the advice or infonnation thi s committee provides be obtained elsewhere ?

The cross section of representatives from NRC, Licensee, and Public Interest Groups provides an excellent overview for the NRC revisions to its regulatory process.

20e. Why is it necessa ry to close and/or partially close committee meetin gs?

Not applicable.

21. R e marks None

Designated Federal Official: TBD

I of2 12 /15/1999 3:59 PM SF 820 http :1/204.254.1 12.5 /cms /RptAnnualReport.asp

Co mmittee Members Occupation Bajestani, Masoud Tennessee Valley Authority Barnes, George Commonwealth Edison Company Brockman, Kenneth USNRC Chase, James Omaha Public Power District Floyd, Steve Nuclear Energy Institute Gaarchow, David Public Service Electric and Gas Gillespie, Frank USNRC Grant, Geoffrey USNRC Hahn, Heidi Los Alamos National Laboratory Lieberman, James USNRC Lochbaum, David Union Of Concerned Scientists Mallet, Bruce USNRC Thadani, Mohan USNRC Wiggins, James USNRC Wright, Gary Illinois Department Of Nuclear Safety T o tal Co unt of Committee M e mb e rs 15

2 of2 12/15/1999 3:59 PM SF 820 http: //204.254. 112.5 /cms /RptAnnu a lR eport. as p

1999 Annual Report: Review of Federal Advisory Committee I. Committee Menu

12 /15/1999 4:35:52 PM I. Depart me nt or Agency 2. Fiscal Year Nuclear Regulatory Commission 1999

3. Co mmitt ee or SubCommittee 3b. GSA Comm ill ee No.

Advisory Committee on the Medical Uses of Isotopes 1102

4. Is thi s New During Fi sca l Year? 5. C urrent C hai1er 6. Expected Ren ewa l Date 7. Expected Te nn Date No 4/4/1998 4/4 /2000 4/5/2004 8a. Was Ten11inated During FY? Sb. Spec i11c Te1111 in ation Authority Sc.Actual Te nnin ation Dat e No 42 U.S.C. 220 I

9. Age ncy Reco 111111 e nd ati on fo r Next FY I 0a. Legislatio n Req to Te1111inate? I Ob.Legislat ion Pe nding?

Continue No 11. Establishment Authority Agency A uthority I 2. Speci11c Establishment Authority I 3. Effecti ve Date 14. Commillee Type 14c. Presidenti al?

42 u.s.c. 2201 7/1/1958 Co ntinuin g No

15. Desc ription of Co mmitt ee Scientific Technical Program Advisory Board 16a. Total ~ umb er of Report s 3 16b. Report T itl es a nd Dates SUMMA RY of DISCUSSION: Public Meeting of ACMUI Diagno s tic Subcommittee held 2/23-24 /1999 3/1/1999 S ummar y of Discussion : Public Meeting of ACMUI Th e rap y Subcommittee held 2/25-26 /1999 3/1/1999 Minutes of ACMUI Meeting h e ld 3 /24-25 /1999 4/1/1999 17a Ope n: 3 I 7b. Closed : 0 I 7c. Pa11ially Closed : 17d. Total Meetings 4 Me e tin g Purposes and Dates Dia g nosti c S ubcommittee Meeting 2/23 /1999 2/24 /1999 Meeting of Therapy Subcommittee 2 /25 /1999 2/26 /1999 Full Co mmittee Meeting 3/24 /1999 3 /25 /1999 Meetin g with NRC Commissioners to provide Advice on Medical Ruic 3/25/ 1999 3 /25 /1999 Cu1Tent Fi sca l Yea r Nex t Fi sca l Yea r I Sa( I) Personnel Pmt s to Non-Federa l Me mb e rs $ 13,382 $ 30,000 I 8a(2) Perso nn el Pmt s to Federal Memb ers $ 0 $ 0 I 8a(3) Personnel Pmts to Federal Staff $96,000 $101,000 18a(4) Perso nn e l Pmt s to Non -m emb er Co ns ult ant s $ 12,365 $ 15,000

! Sb( ! ) Travel a nd Pe r Di e m t o No n-Federal Member s $8,7 53 $ 10,000 I 8b(2) Travel and Per Diem to Federa l Member s $ 0 $0 I 8b(3) Tra vel and Per Die m to Federal Staff $0 $0 I 8b(4) Tra ve l and Per Di em to No n-M ember Co ns ultants $4,92 1 $ 5,000 18c.Other(rent s,user charges,graphics,printing,m ai l etc.) $0 $ 0 18d Total $ 135,42 1 $ 161,000

19. Federal Staff Supp011 Years 1.5 1.5 20a. How does the Co mmitte e acco111pli sh its purpose?

The N R C s taff believes that both licen sees and the general public benefit when r ecog nized experts provide advic e to the s taff on medical iss ue s in which N R C's s tandards ma y be unclear or inapplicable and when the se experts can pro v ide advice on rulcmakin g and other initiatives at critical s ta ges throughout their development. The Staff provides a summary of th e is s ues to be addressed during th e meeting. The ACMUI di s cu sses the issues and makes recommendations to the Staff. In addition, working g roups and subcommittees are formed to discus s certain issues i n more depth than can be accomplished during a regular meetin g.

20b. How does the Co mm inee bala nce its me111bers hi p?

As o f October I, 1999, the ACMUI consists of the following: a ph ys ician repre se ntin g nuclear cardiology, one ph ys ician practicin g nuclear medicine, one medical ph ys icist in dia g no s tics, one health care administrator, one patients' rights and care advocate, a food and Drug Administration representative, and a State representative. Currently five more po s itions are authorized and being selected. The se position s will represent radiation oncology (two positions), medical ph ys ics in radiation therap y, nuclear pharmac y, and a radiation safety officer.

20c. How frequent and relevant are th e Co mmitt ee meetings ?

The Co mmittee generally meets semi-annually. The Commission may request the Committee to come in annually to brief the Commission.

There also may be a need for subcommittee meetings periodically.

20d. Why can't the advice or infonnation this comminee provides be obtained e lsew here?

The Co mmittee is composed of individuals with specialized degrees and who are actively involved in the medical field, i.e., physicians, m edical ph ys ici s ts, and nuclear pharmacists. The necessary advice provided by the ACMUI cannot be obtained from other so m *ces within the N RC. To dev e lop and maintain an in-house capability to match the qualit y and quantit y of expert advice embodied in the advi so ry committee would b e difficult, if not impossible. There appear to be no other sources within the N R C or e lse where which have the individual expertise capable of providin g the in-depth advice ne eded.

20e. Why is it necessary to close and/or part ia ll y c lose com mille e me et in gs?

A nnual ethics briefings are conducted. During these meeting s, private information is available for co mmittee memb e r s, but is not available to the public. The ethics briefing porti o n of the meetin g is clo sed to the ge neral p ubli c.

I of2 12/15/19994:33 PM SF 820 http :1/204.254.112.5 /crns /RptAnnu a lReport.asp

2 1. Re m arks None

De sig nat ed Fe deral Offic ial : Betty Ann Torres DFO Co mmitt ee Me mb ers Occupation A la z raki, Dr. Naomi N uclear Medicine Physician Ce rqueira M.D., Manuel Nuclear Ca rdiol ogis t Flyn n M.D., Dr. Daniel F. Radiation Oncologi s t G raham, Mr. John Hospital Administrator Hob so n, Nekita Patient Advocate Jone s M.D., Dr. A. Eric Food and Drug Ad ministration Representativ e McBurney, Ruth State Repre sentative Ne lp M.D., Dr. Wil B. Nuclear Medicine Ph ys ician -Research Stitt M.D., Dr. Judith An ne Radiation Oncolo g ist Sw an so n M.S.,BCNP, Mr. Dennis P. Nuclear Pharmaci s t Wa g ner Ph.D., Dr. Louis K. Med ical Phy s ici s t -N uclear Medicine Walkup, Ms. Theresa Ce rtifi ed Medica l Dosimetrist T o ta l Count o f Commi ttee Member s 12

2 of2 12/15 /19994:33 PM