United States Nuclear Power
Federal Regulations, Codes, & Standards
Users Group ©
NRC Section XI Report - December 2000
Presented By: Wally Norris, United States Nuclear Regulatory Commission
1. Amendment to 10 CFR 50.55a
The NRC staff review of the 1997 Addenda, 1998 Edition, 1999 Addenda, and 2000 Addenda of Section III, Section XI, and OM Code is proceeding but has been delayed. A portion of the effort was originally tasked to Idaho National Engineering Laboratory (INEL). Management of INEL by Bechtel, however, presents a potential conflict of interest. Hence, that task has been canceled. The staff is reallocating resources to complete this effort in-house. The proposed rule is scheduled to be published in September 2001.
2. ASME Code Cases
The NRC staff is presently reviewing Supplement 8 and Supplement 9 to the 1998 Edition. The Office of General Counsel (OGC) raised concerns relative to the Code Case endorsement process and provided several options to the staff to address these concerns. The staff is developing a Commission Paper (SECY Paper) which will discuss issues and provide a recommendation. A projected date for public review is not yet available.
3. Regulatory Information Conference (RIC)
The NRC staff is in the process of considering the responses to the on-line survey (stakeholders were invited to complete the form by November 15, 2000). The responses will be used in developing the RIC which will be held March 12, 13, and 14, 2001, at the Capital Hilton Hotel, 16th and K Streets, NW, Washington, DC. Please note that both hotel registration and on-line registration for the conference will be open after January 1, 2001.
4. Voluntary Industry Initiatives
In response to the SRM issued on May 27, 1999, to SECY-99-063, "The Use by Industry of Voluntary Initiatives in the Regulatory Process," and to stakeholders' comments, the staff, working with stakeholders, developed proposed guidelines for including industry initiatives in the regulatory process. The proposed guidelines were transmitted to the Commission on May 30, 2000 (SECY-00-0116, "Industry Initiatives in the Regulatory Process"). On June 28, 2000, the Commission approved the staff’s recommendation to issue the proposed guidelines for public comment. The guidelines were published in the Federal Register on August 31, 2000 (Volume 65, Number 170, Pages 53050-53058) for public comment (45-day). The comments are scheduled to be resolved and final guidelines issued by January 5, 2001.
5. Risk-informing Technical Requirements of 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities"
The NRC staff has released to the public a draft version of its review guidelines for the South Texas Plant (STP) Nuclear Operating Company request for exemptions from numerous special treatment requirements in 10 CFR Parts 21 and 50 (http://www.nrc.gov/NRC/REACTOR/RISK50/treatment_modifications). The purpose for releasing the draft guidelines, titled "Review Guidelines for STP Exemption Request and Baseline Acceptance Criteria for RIP50 Option 2," is to facilitate discussion of the issues at several public forums. The draft guidelines represent a "work in progress" and are subject to change on the basis of stakeholder input. These guidelines will also serve as the starting point for the development of acceptance criteria for licensees who choose to adopt the staff's risk-informed changes to the special treatment requirements published in an Advanced Notice of Proposed Rulemaking on March 3, 2000 (risk-informed Part 50, Option 2).
Note that this is a draft document which is subject to change and does not yet represent official NRC positions. For further information, you may contact Tom Bergman, NRC/NRR, by telephone at (301) 415-1021, or by email at email@example.com.
An agency policy paper SECY-98-300, "Options for Risk-informed Revisions to 10 CFR Part 50 - "Domestic Licensing of Production and Utilization Facilities," identifies three options for risk-informed modifications to 10 CFR Part 50. Option 3 from SECY-98-300, is discussed on http://nrc-part50.sandia.gov/. Option 3 involves a study of risk-informed changes to specific requirements in the body of the regulations, including general design criteria. The details of the plan for risk-informing the technical requirements of 10 CFR Part 50 are specified in policy paper SECY-99-264, "Proposed Staff Plan For Risk-informing Technical Requirements in 10 CFR Part 50." SECY 00-0086 - "Status Report on Risk-Informing the Technical Requirements of 10 CFR Part 50 (Option 3)," is also available on this website. This SECY provides the first status report on the work done to date by the staff to study risk-informing the technical requirements of 10 CFR part 50, as described in SECY-99-264 (Option 3), and informs the Commission of the staff's intent to expedite completion of its recommendations for risk-informed changes to certain parts of 10 CFR 50.44 ("Standards for Combustible Gas Control System in Light-Water-Cooled Power Reactors").
SECY-00-0198 - "Status Report on Study of Risk-Informed Changes to the Technical Requirements of 10 CFR Part 50 (Option 3) and Recommendations on Risk-Informed Changes to 10 CFR 50.44 (Combustible Gas Control)," provides the second status report on the staff's study of possible risk-informed changes to the technical requirements of 10 CFR Part 50, provides the staff's recommendations for risk-informed changes to 10 CFR 50.44 ("Standards for Combustible Gas Control System in Light-Water-Cooled Power Reactors"), and provides policy issues for Commission decision.
6. License Renewal
The draft final GALL report, SRP, and RG/NEI 95-10 will be discussed at the ACRS in February 2001. Submittal to the Commission would occur in March 2001. Information relative to license renewal can be found at http://www.nrc.gov/NRC/REACTOR/LR/index.html.
Following is the latest information available regarding plant applications for license renewal:
Calvert Cliffs, Units 1 and 2 (includes milestones, application, and safety evaluation report)
Oconee Nuclear Station, Units 1, 2 and 3 (includes milestones, application, and safety evaluation report)
Arkansas Nuclear One, Unit 1 - Application received February 1, 2000
Edwin I. Hatch, Units 1 and 2 - Application received March 1, 2000
Turkey Point, Units 3 and 4 - Application received September 11, 2000 (webpage under construction)
Catawba, Units 1 and 2 - June 2001 (earliest submittal date based on granted exemptions)
McGuire Units, 1 and 2 - June 2001 (earliest submittal date based on granted exemptions)
Peach Bottom, Units 2 and 3 - July 200
North Anna, Units 1 and 2 - August 2001
Surry, Units 1 and 2 - August 2001
Fort Calhoun 1 - March 2002
St. Lucie, Units 1 and 2 - June 2002 (Unit 2 requires exemption)
Point Beach, Units 1 and 2 - July 2002
V.C. Summer - August 2002
H. B. Robinson, Unit 2 - October 2002
Farley, Units 1 and 2 - June 2003
Arkansas Nuclear One, Unit 2 - September 2003
Browns Ferry, Units 2 and 3 - December 2003
Cooper - 2003
Brunswick, Units 1 and 2 - December 2004
Beaver Valley, Units 1 and 2 - 2004 (Unit 2 requires exemption)
Pilgrim, Unit 1 - 2004
7. Revised Reactor Oversight Process
On June 28, 2000, SECY-00-0146, "Status of Risk-based Performance Indicator Development and Related Initiatives," was transmitted to the Commission to provide the Commission with a status report on the development of risk-based performance indicators (RBPIs) and related initiatives in support of the Reactor Oversight Process (ROP). A white paper ("Development of Risk-Based Performance Indicators: Program Overview) on the development of RBPIs was issued for comment in March 2000. The purpose of this white paper was to provide an overview of the current efforts to develop RBPIs. The ACRS was briefed on the RBPI white paper on April 5, 2000. The ACRS concluded that the RBPI development is very important for the successful transition to risk-informed regulation and recommended that the agency assign a high priority and adequate resources to this program. The ACRS also recommended that the staff should work with the industry to ensure that licensee reporting of reliability data becomes an industry self-imposed requirement of the Equipment Performance and Information Exchange (EPIX) database. A public meeting with external stakeholders was held on April 28, 2000, to discuss their comments on the overall concept and technical approach outlined in the RBPI development white paper. The NRC staff is developing Phase-1 RBPIs using the overall concept described in the RBPI white paper. The staff plans to brief the Commission on study findings in December 2000 following interactions with internal and external stakeholders.