Source: http://www.state.nv.us/nucwaste/news/nrc/nrc990806.htm
Timestamp: 2017-10-17 09:49:16
Document Index: 274068743

Matched Legal Cases: ['art 50', 'art 2', 'art 50', 'art 41', 'art 72', 'art 70', 'art 70', 'art 70', 'art_70', 'art 35', 'art 50']

For the Week Ending August 6, 1999
The Weekly Information Report is compiled by the NRC Office of the Executive Director for Operations and includes highlights of Headquarters and Regional Office activities. For technical questions, please contact M. Tschiltz, OEDO by E-mail: mdt@nrc.gov. For administrative questions, please contact Patricia Anderson at (301) 415-1703, or by E-mail: paa@nrc.gov. If you would like to request a hard copy, you may contact the NRC Public Document Room at (202) 634-3273, or by E-mail: pdr@nrc.gov.
Public Meeting on Risk-Informed Part 50
Four topics were identified as needing further discussion for the next public Meeting: (1) how will licensees assure that SSCs out of scope of the special treatment rules (industry), specifically the meaning of 'commercial grade;' (2) what level of qualification will be required for SSCs that are currently non-safety related that become in scope of the special treatment rules as a result of their safety significance (staff); (3) a description of the pilot program (industry); and (4) extent to which licensees can make changes to the qualification of SSCs under 10 CFR 50.59 without obtaining prior NRC approval (industry). The next public Meeting has been scheduled for August 26, 1999.
Shearon Harris Nuclear Power Plant: Status of Hearing Activities on Spent Fuel Pool Expansion Amendment
On July 29, 1999, the Atomic Safety and Licensing Board (ASLB) granted Carolina Power & Light (CP&L) Company's request to hold the Hearing related to its amendment request to increase the spent fuel storage capacity at the Shearon Harris Nuclear Power Plant (HNP) in accordance with the hybrid Hearing procedures of 10 CFR Part 2, Subpart K. The ASLB also established the following timetable for the proceeding:
Discovery Begins: August 2, 1999
Discovery Ends: October 31, 1999
Written Summaries Filed: December 20, 1999
Oral Argument: January 4, 2000 (ASLB Hearing Room; TWFN)
In addition, the ASLB stated that it intends to conduct one or more sessions to receive
10 CFR 2.715(a) limited appearance statements in the vicinity of the Harris facility during the first half of December 1999.
In a previous Order dated July 12, 1999, the ASLB issued its Ruling on Standing and Contentions related to the petition to intervene filed by the Board of Commissioners of Orange County, North Carolina (BCOC). BCOC's February 12, 1999, petition challenged CP&L's December 23, 1998, amendment request to increase the spent fuel storage capacity at HNP by placing spent fuel pools 'C' and 'D' in service. In the July 12, 1999, ruling, the ASLB concluded that BCOC does have standing and has submitted two admissible contentions.
By letters dated July 16, 1999, Florida Power and Light Company notified NRC that St. Lucie, Units 1 and 2, and Turkey Point, Units 3 and 4, are Y2K ready, consistent with the estimated completion Date in the licensee's responses to Generic Letter 98-01 Supplement 1. As reported in June, the only remaining system requiring remediation at all four units was the health physics administrative computer system, which is now Y2K-ready.
The completion of Y2K activities at these 4 plants reduces the number of units with remaining Y2K readiness activities from 35 to 31.
Yankee Rowe -- Termination of Hearing
By Memorandum and Order, LBP-99-27, dated July 28, 1999, the Atomic Safety and Licensing Board terminated the Yankee Rowe License Termination Plan Hearing. There were No conditions attached to the termination order and the Hearing was terminated without prejudice.
Any party to the proceeding has the right to appeal the Board's decision within 15 days of
July 28, 1999, directly to the Commission, otherwise the Order becomes final 40 days after
July 28, 1999. The Commission has the authority to review the Order absent any appeal from the parties.
On August 2, 1999, the staff issued Amendments to the Browns Ferry Units 2 & 3 Technical Specifications. These amendments extend the Allowable Outage Time for the Emergency Diesel Generators, from 7-days to 14-days. These AOT extensions were found to be acceptable on both deterministic and probabilistic (risk) bases.
The licensee's March 12, 1997 application for the amendments was over 2 years old at the Time of issuance of the amendments The long review period is attributed to the advent and evolution, during the review period, of (a) new risk considerations and risk criteria for evaluation of licensee requests to extend Allowable Outage Times, and (b) Maintenance Rule requirements.
Presentation at the American Association of Physicists in Medicine Meeting
On July 26, 1999, a staff member from the Division of Industrial and Medical Nuclear Safety made a presentation on Nuclear Regulatory Commission regulatory issues involving intravascular brachytherapy at the annual Meeting of the American Association of Physicists in Medicine (AAPM) in Nashville, Tennessee. This presentation was one of five invited talks given as a part of the AAPM's President's Symposium on "Intravascular Brachytherapy: An Emerging Role for Medical Physicists."
Participation on ANSI Writing Group Regarding Dose Calibrators
On July 28, 1999, a staff member from the Division of Industrial and Medical Nuclear Safety convened the first Meeting of the writing group for the revision of ANSI Standard N42.13 (American National Standard Calibration and Usage of "Dose Calibrator" Ionization Chamber for the Assay of Radionuclides). The staff member was appointed as the chairman of the writing group by the chairman of the parent ANSI subcommittee. The writing group planned and organized the revision effort at this first Meeting. Specifically, a Schedule for the revision was established; individual Committee member tasks were assigned and agreed to; and the scope of the revised document was defined.
Meeting with the Naval Nuclear Propulsion Program for Naval Spent Nuclear Fuel on Quality Assurance
On July 29, 1999, Division of Waste Management (DWM) staff met with representatives of the Naval Nuclear Propulsion Program (NNPP) to discuss the NNPP Quality Assurance (QA) Program, the NNPP QA Program review jointly conducted by the Department of Energy's Office of Civilian Radioactive Waste Management (OCRWM) and NNPP in 1998, and the agreements reached between OCRWM and NNPP as a result of the 1998 review. An OCRWM representative was also present for the Meeting. The NNPP representatives provided an overview of NNPP responsibilities and summarized NNPP activities related to spent nuclear fuel disposal. The NNPP representatives and OCRWM representative briefly described the 1998 review, as well as the conclusions of the review that the NNPP QA program met the applicable QA requirements of Appendix B to 10 CFR Part 50 and was effectively implemented. NNPP and OCRWM asked that DWM agree with the NNPP's approach to QA. DWM staff agreed to review the material presented, consider the acceptability of the NNPP QA program, and determine the appropriate method to document DWM staff's findings.
External Review of Nuclear Regulatory Commission's Total-System Performance Assessment Code (TPA Version 3.2)
On July 27-29, 1999, staff from the Division of Waste Management and the Center for Nuclear Waste Regulatory Analyses (Center) held a Meeting with a group of national and international experts (external review group) on the Nuclear Regulatory Commission's (NRC's) Total-System Performance Assessment (TPA) code, Version 3.2. The TPA Version 3.2 code was jointly developed by NRC and Center staff and is designed to estimate total-system performance in terms of annual individual dose or risk from exposure to releases from the proposed repository at Yucca Mountain. TPA 3.2 simulates evolution of the site including both gradual processes (e.g., ground-water flow in the unsaturated and saturated zone, corrosion of the waste package, and dissolution and release of waste) and specific disruptive events (e.g., faulting, seismicity, and volcanism). An external review of TPA 3.2 was conducted to build confidence in the code and its results and assist staff in understanding the strengths and weaknesses of the modeling assumptions and parameters.
The external review group was comprised of eight national and international experts in a variety of fields relevant to repository performance (i.e., hydrology, geochemistry, seismicity, materials, mining engineering, volcanism, health physics, and performance assessment). Based on information provided in NRC and Center staff presentations and a review of code documentation and related reports, each expert will prepare an evaluation and critique of the code. The Center will submit a summary report to NRC that contains as an appendix each of the experts' individual reviews. During the presentations, the initial reaction from the experts was favorable to the modeling approaches in TPA 3.2. Some concern was raised regarding: (1) consideration of interactions among processes (e.g., influence of the coupling of thermal, hydrologic, and mechanical effects on rockfall with repository drifts); and (2) level of rigor necessary for defending NRC's modeling assumptions and parameters compared with requirements for the Department of Energy (DOE) in its license application. NRC and Center staff will use each expert's individual review to identify further improvements of NRC's modeling capabilities in anticipation of potential reviews of DOE's site recommendation and license application.
Nuclear Regulatory Commission and Environmental Protection Agency Meeting on Coordination of Uranium Recovery Program Changes
On August 3, 1999, staff from the Division of Waste Management (DWM) met with Environmental Protection Agency (EPA) staff from the Office of Radiation and Indoor Air (ORIA) to discuss future coordination of proposed changes to the Uranium Recovery Program. These changes are detailed in three Commission Papers (SECY 99-011, 99-012, and 99-013) and include the new 10 CFR Part 41 rulemaking, regulation of ground water at in situ leach uranium recovery facilities, alternate feed at conventional mills, and the disposal of wastes other than 11e.(2) byproduct material in mill tailings impoundments. These topics were also discussed in the June 17, 1999, Uranium Recovery Commission Meeting. EPA indicated ORIA as well as other EPA offices and regions could be impacted by the NRC's potential programmatic changes in all three Commission Papers. ORIA would function as a centralized contact point for EPA and NRC coordination. DWM staff indicated that the Commission would be issuing an SRM regarding the three Commission Papers in the near future. Another Meeting will be scheduled with EPA to discuss the directions provided in the SRM when it is publically released and future coordination activities between the two agencies.
Preliminary Certificate of Compliance and Safety Evaluation Report for Holtec HI-STORM 100 Storage Cask Completed
The Spent Fuel Project Office staff has completed its review of the topical safety analysis report submitted by Holtec International (Holtec) for the HI-STORM 100 spent fuel storage cask. The HI-STORM 100 has a concrete and metal overpack. It is compatible with Holtec's HI-STAR 100 dual-purpose storage and transportation cask system. The HI-STORM 100 can be used to store spent fuel that has been shipped in a HI-STAR 100 transportation cask or to store spent fuel before it is shipped in a HI-STAR 100. The staff's preliminary Certificate of Compliance and Safety Evaluation Report will be made available for public comment. This is the first step in the rulemaking process to include the HI-STORM 100 in the list of casks available for use by holders of general licenses pursuant to 10 CFR Part 72. The HI-STORM 100 is one of the two casks which Private Fuel Storage, LLC, plans to use at its proposed interim storage facility on the Reservation of the Skull Valley Band of Goshute Indians.
Interim Staff Guidance on Full Actinide-Only Burnup Credit
On July 29, 1999, the Spent Fuel Project Office (SFPO) issued Revision 1 of its interim staff guidance document, ISG-8. The revised ISG-8 recommends a basis for design-specific acceptance of full actinide-only burnup credit in the criticality safety analysis of casks for storing and transporting spent fuel from pressurized water reactors. SFPO will issue additional revisions to ISG-8 as further information arises from its future licensing activities and from the NRC's ongoing research program on burnup credit. This guidance supplements SFPO's three standard review plans (SRP) for cask review. Future SRP revisions will incorporate or reference the current guidance, as appropriate.
Publication of 10 CFR Part 70, Domestic Licensing of Special Nuclear Material
On July 30, 1999, the proposed revisions to 10 CFR Part 70, Domestic Licensing of Special Nuclear Material, were published in the Federal Register. The comment period ends on October 13, 1999. The associated SRP was placed in the Public Document Room at the same Time. Both the proposed rule and SRP are posted on the Part 70 website. The staff plans to conduct a stakeholder workshop on the rule and SRP in late September 1999.
Rule address:
http://ruleforum.llnl.gov/cgi-bin/library?source=*&library=PR_Rulemaking_lib &file=*
SRP address:
http://techconf.llnl.gov/cgi-bin/rulemake?source=Part_70
Purdue University License Renewal
On July 30, 1999, the Division of Fuel Cycle Safety and Safeguards renewed Special Nuclear Material License SNM-142 for Purdue University, West Lafayette, Indiana, for a 10-year term. The license authorizes Purdue University to use special nuclear material for research and educational purposes in the areas of nuclear science and engineering.
On August 9, 1999, the EDO approved a proposed rule which amends 10 CFR 72.214, "List of approved spent fuel storage casks," by adding the NAC International Multi-Purpose Canister cask system (NAC-MPC system) to the list of approved spent fuel storage casks. This amendment would allow the holders of power reactor operating licenses to store spent fuel in the approved casks under a general license.
This notice informs the Commission that, in accordance with the rulemaking authority delegated to the EDO, the EDO has signed this proposed rule and proposes to forward it on August 17, 1999, to the Office of the Federal Register for publication, unless otherwise directed by the Commission.
On August 9, 1999, the EDO approved a proposed rule which amends 10 CFR 72.214, "List of approved spent fuel storage casks," by adding the Transnuclear TN-32 cask system to the list of approved spent fuel storage casks. This amendment would allow the holders of power reactor operating licenses to store spent fuel in the approved casks under a general license.
On August 9, 1999, the EDO approved a proposed rule which amends 10 CFR 72.214, "List of approved spent fuel storage casks," by adding the Transnuclear TN-68 cask system to the list of approved spent fuel storage casks. This amendment would allow the holders of power reactor operating licenses to store spent fuel in the approved casks under a general license.
PHEBUS Fission Product Project
The PHEBUS Fission Product (FP) project is sponsored by the Commissariat A L'Energie Atomique of France (CEA) and the Commission of the European Communities. The USNRC participates in the PHEBUS-FP project through a cooperative agreement with CEA. The objective of the PHEBUS-FP project is to perform in-pile severe fuel damage experiments and study the fission product behavior and transport in the reactor system and the containment system. It is recognized that such accidents are extremely unlikely, but the integral experimental data obtained will enable the USNRC to assess its analytical models to confirm the conclusions reached from the completed NRC fission product research program, as well as to assess the revised source term delineated in NUREG-1465, "Accident Source Terms for Light-Water Nuclear Power Plants."
The third PHEBUS-FP test was successfully conducted on July 22, 1999. The objective of this test was to study the release of low-volatility fission products and transuranic elements from a fuel that is initially in a solid debris bed configuration, which then changes to a molten bed because of the continued melting of the fuel. A debris bed and molten pool represent the configuration of a core during the late phase of a severe accident. The experiment began at 9:45, and there was evidence of formation of a molten pool. When fuel from the molten pool was detected to have relocated into the passive debris bed situated below the initial debris bed, the reactor was scrammed and the test was terminated at 14:22. Radionuclides and non-radionuclides released during the experiment were collected in filters located above the test bundle. Post test examination will begin shortly and details on the test will be known in a few weeks.
While the probability of the occurrence of such releases and fuel melting is extremely low, the knowledge gained from these experiments is considered to be quite valuable for assessing analytical models and source terms and for considering preventive actions.
1. PNO-I-99-037, Corporation of St. Peter's College, MISSING NATURAL URANIUM FUEL SLUGS
2. PNO-IV-99-032, Entergy Operations, Inc. (Waterford 3), PLANT SHUTDOWN DUE TO REACTOR COOLANT PUMP SEAL FAILURE
3. PNO-IV-99-033, State of California Licensee, DELIBERATE MISUSE OF PHOSPHORUS-32
Regional Office Video Teleconference
DCPM conducted a video teleconference with all Regional Offices and TTC on August 5, 1999, to discuss overview of the recently completed property inventory and procurement reviews, lessons learned and success stories. A representative from the Administrative Service Center discussed experiences with GSA Advantage. Other concerns of Regional Office personnel were discussed and action items identified. Future video teleconferences are anticipated on a regular basis to discuss procurement and property related issues.
Freedom of Information and Privacy Act Requests received during the 5-Day Period of July 29, 1999 through August 5, 1999:
Self, security file. (FOIA/PA 99-306)
Commonwealth Cancer Institute, license # 45-25422-01. (FOIA/PA 99-307)
Jones & Laughlin Steel Corporation, Aliquippa, PA, radioactive materials use and exposure incidents, 1943 through 1983. (FOIA/PA 99-308)
FOIA/PAs, 99-214, 99-215, & 99-240, incoming and response(s). (FOIA/PA 99-309)
SECY Paper, SECY-92-198 dated 5/29/92. (FOIA/PA 99-310)
Vanadium Mill Site, Cane Valley or Monument Valley, AZ. (FOIA/PA 99-311)
MLTS database for identified program codes. (FOIA/PA 99-312)
IMPAC listing. (FOIA/PA 99-313)
White House, all correspondence between NRC and First Lady Hillary Clinton and/or her staff, 1993 to present. (FOIA/PA 99-314)
Self, all records. (FOIA/PA 99-315)
BARTELS, Ellen SECRETARY RI
DANNA, James SYSTEMS PERFORMANCE ANALYST (HYDRO) NMSS
TRIFILETTI, Sue FILE CLERK RIV
PEARSON, Marcia MATERIALS PROGRAM ASST. RIII
REARDON, Mary Lynn PROJECT SCIENTIST NRR
THOMAS, Cecil PROJECT DIRECTOR NRR
NUGUCHI, Aki SUMMER INTERN ADM
There has been heightened media interest in the Y2K status of nuclear power plants in general, and The Times Picayune (LA) is preparing a story on Y2K readiness at Waterford.
HQ and the Regions have responded to several media inquiries regarding the summer heat and drought conditions and their impact on reactor power levels.
Region II was contacted by 60 Minutes staff about depleted uranium.
99-164 NRC Posts Nuclear Power Plant Performance Data on Internet Website; Seeks Public Comment on Pilot Plant Program
99-166 NRC Advisory Committee on Reactor Safeguards to Meet in Rockville, Maryland
99-167 NRC to Hold Public Workshop on Reactor Safety Chapter of its Strategic Plan on August 20
I-99-64 NRC Proposes $55,000 Fine for Operator of Seabrook Plant for Violation Involving Discrimination; Contractor, Foreman Cited
I-99-65 Haddam Neck Decommissioning Activities to be Discussed Aug. 11
I-99-66 NRC Staff to Hold Performance Review Meeting for Peach Bottom Plant
II-99-45 NRC Staff to Conduct Licensee Performance Review With General Electric Nuclear Fuel Plant at Wilmington on August 6
Y2K Early Warning System (YEWS)
On August 4, 1994, Joe Giitter, Office of Incident Response Operations, and Clarence Breskovic, Office of International Programs (OIP), met with DOE staff to discuss DOE participation in the Y2K Early Warning System (YEWS) and possible co-funding of contract work. A DOE response is expected within the next two weeks. YEWS was developed by OIP and is being coordinated with the Nuclear Energy Agency, the International Atomic Energy Agency, various reactor owner groups, utilities, and foreign bilateral partners.
Meeting on Plutonium Disposition
On August 6, 1999, Janice Dunn Lee, Director of OIP, met with Ms. Laura Holgate, DOE Director of Materials Disposition, to discuss regulatory support for the Russian regulatory authority, Gosatomnadzor (GAN) on the MOX option. Negotiations underway to finalize an agreement with the Russian Federation on plutonium disposition include establishing a special working group on regulatory matters to ensure that regulatory and licensing perspectives and requirements are fully taken into account. DOE staff is interested in NRC participation in the special working group and also in direct support to GAN on MOX.
1. COMNJD-99-002 5/13/99 Nevada Public Meeting on Spent Fuel Transportation
SRM on 99-002 6/30/99 (same)
Chmn. Dicus comments on 99-002 6/21/99 (same)
Comm. McGaffigan comments on 99-002 5/24/99 (same)
Comm. Merrifield comments on 99-002 6/16/99 (same)
2. SECY-99-179 7/9/99 Section 274b Agreement with the State of Ohio
Correction Notice to SECY-99-179 7/15/99 (same)
SRM on SECY-99-179 8/4/99 (same)
Commission Voting Record on 99-179 8/4/99 (same)
3. SECY-99-201 8/3/99 Draft Final Rule - 10 CFR Part 35, "Medical Use of Byproduct Material"
4. SRM on SECY-99-162 8/5/99 Policy for Regulatory Actions for Licensees of Nuclear Power Plants that Have Not Completed Year 2000 Readiness Activities
Commission Voting Record on 99-162 8/5/99 (same)
5. COMSECY-99-018 6/18/99 Self Assessment of ACRS and ACNW Performance
SRM on COMSECY-99-018 8/6/99 (same)
Chmn. Dicus comments on 99-018 7/17/99 (same)
Comm. Diaz comments on 98-018 6/26/99 (same)
Comm. McGaffigan comments on 98-018 7/6/99 (same)
Comm. Merrifield comments on 98-018 6/24/99 (same)
1. SECY-99-184 7/15/99 Weekly Information Report - Week Ending July 9, 1999
2. SECY-99-185 7/16/99 Summary of Activities Related to Generic Safety Issues
3. SECY-99-186 7/16/99 Staff Plan for Clarifying How Defense-in-Depth Applies to the Regulation of a Possible Geologic Repository at Yucca Mountain, Nevada
4. SECY-99-187 7/19/99 Information paper on the Viability of Entombment as a Decommissioning Option for Power Reactors
5. SECY-99-190 7/22/99 Equal Employment Opportunity Briefing
6. SECY-99-189 7/23/99 Weekly Information Report - Week Ending July 16, 1999
1. Memo to Commissioners from K. Cyr, OGC 6/9/99 The Nuclear Regulatory Commission's Process for Adopting the Department of Energy's Environmental Impact Statement for the Geologic Repository
2. M990617 8/3/99 Staff Requirements - Briefing on Status of Uranium Recovery (SECY-99-011, SECY-99-012, SECY-99-013), Thursday, June 17,1999
3. M990715A 8/5/99 Staff Requirements - Briefing on Existing Event Procedures (Including Federal Response Plan and Coordination of Federal Agencies in Response to Terrorist Activities, Thursday, July 15, 1999
1. Letter to Congress, dated July 29, 1999, provides the final NRC Y2K contingency plan.
2. Letter to Representative John D. Dingell, dated July 29, 1999, concerns regulation of the disposal of 11e.(2) byproduct material located at several Formerly Utilized Sites Remedial Action Program sites (incoming letter dated July 12, 1999, also released).
3. Letter to Senator Conrad Burns, dated July 27, 1999, concerns Freedom of Information Act requests by the Democratic Senatorial Campaign Committee (incoming letter dated July 6, 1999, also released).
4. Letter to Congress, dated July 26, 1999, provides the June monthly report on the status of NRC licensing and regulatory duties.
1. 10 CFR Part 50; Changes to Quality Assurance Programs: Responses to Comments.
2. [NUREG-1600, Revision 1] Interim Enforcement Policy for Use During the NRC Power Reactor Oversight Process Pilot Plant Study.
3. Advisory Committee on Reactor Safeguards; Meeting Notice for September 1-3, 1999.
4. Advisory Committee on Reactor Safeguards; Subcommittee Meeting on Planning and Procedures; Notice of Meeting on August 31, 1999.
5. Pilot Program Evaluation Panel; Meeting Notice for August 17, 1999.
6. Licensing Support System Advisory Review Panel; Notice of Amendment of Charter.
7. Advisory Committee on Nuclear Waste; Meeting Notice for September 14-15, 1999.
General Electric Company - Licensee Performance Review
On August 6, 1999, the Regional Administrator and other managers from the Office of Nuclear Materials Safety and Safeguards and Region II attended a management Meeting at the General Electric Company to discuss the results of the NRC's Licensee Performance Review.
On August 4, 1999, Nuclear Fuel Services, Inc. was advised that the NRC had No objection to the introduction of high enriched uranium(HEU) into process areas 100-700 in the Building 300 complex. This NRC position was based on the results of the operational readiness review inspections conducted and the issuance of License Amendment No. 1 to SNM-124 on August 2, 1999 authorizing use of the process. Nuclear Fuel Services, Inc. was making final preparations for the introduction of HEU from August 4-9, 1999.
Army Radiation Protection Officer Seminar
On August 3, 1999, the Director, Division of Nuclear Material Safety, and a member of her staff participated in a Meeting in the Rock Island, IL, area of around 80 Radiation Protection Officers from the Army. The NRC had been invited to present information on the NRC inspection process and to participate in a question & answer session on regulatory issues affecting the Army.
Public Meeting with Entergy Operations, Inc.
The Deputy Regional Administrator and other members of the Region IV staff met with the River Bend Station General Manager - Plant Operations and other members of his staff. This Meeting was open to attendance by members of the general public. The purpose of the Meeting was to discuss recent NRC findings in the radiological controls area at River Bend Station and the licensee's activities to improve performance in the area.
PRESS RELEASE No. 99-167 DATED AUGUST 6, 1999 -- NRC TO HOLD PUBLIC WORKSHOP ON REACTOR SAFETY CHAPTER OF ITS STRATEGIC PLAN ON AUGUST 20
The Nuclear Regulatory Commission will hold a Meeting in Rockville, Maryland, on August 20 to give the public an opportunity to ask questions and comment on the nuclear reactor safety chapter of the agency's Strategic Plan. The Meeting had originally been scheduled for August 10.
The Meeting will be held from 9:00 a.m. to 1:00 p.m. in the Commissioners' Conference Room in the agency's One White Flint North Building at 11555 Rockville Pike.
The Strategic Plan contains goals to carry out NRC's mission, and strategies to meet those goals. It serves as a comprehensive blueprint for the agency's program and budget planning and a guide to daily management and decision-making. The NRC's first Strategic Plan was issued in September 1997.
Since then, the NRC has adopted processes that focus on becoming more performance-based and outcome-oriented. The nuclear reactor safety chapter reflects this approach to long-range planning as well as institutionalizing regulatory reforms initiated during the last 18 months. It contains new performance goals and measures and addresses issues raised during the NRC's July 30, 1998, Congressional Hearing; the July 17, 1998, Commission Meeting with members of the public and stakeholders who would be most affected by NRC decisions; and the Chairman's August 17, 1998 tasking memo. While the NRC recognizes that more work is needed, at this point it believes the draft nuclear reactor safety chapter will benefit from stakeholder suggestions.
The NRC is looking for comments pertaining to the following four issues:
Do goals address appropriate areas?
Are the strategies to achieve the goals adequate?
Will performance measures indicate whether we are achieving our goals?
Do goals and strategies reflect NRC's commitment to institutionalize change and become more performance-based?
Additional details will be available in an upcoming edition of the Federal Register. Those interested in participating in the Meeting should contact James Blaha at (301) 415-1703. The draft strategic plan and a forum for submitting comments electronically are available on the NRC web site at: http://www.nrc.g ov/NRC/COMMISSION/INITIATIVES/199/index.html. All written comments should be submitted by August 27 to Debra J. Corley at the U.S. Nuclear Regulatory Commission, Mail Stop: O-16E15, Washington, D.C. 20555-0001.
This page was last updated on August 11, 1999, by NRCWEB (nrcweb@nrc.gov).