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NRC Section XI Report - May 2003

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Presented By: Mr. Wally Norris, United States Nuclear Regulatory Commission

NRC Report
Section XI
May 2003

1. Amendments to 10 CFR 50.55a

The final amendment to 10 CFR 50.55a incorporating the 1997 Addenda through 2000 Addenda by reference was published on September 26, 2002 (67 FR 60520) and is available at the Office of Federal Register website: http://www.access.gpo.gov/su_docs/fedreg/a010803c.html

The NRC staff has nearly completed its formal review of the changes to the ASME Code incorporated into the 2001 Edition/Addenda and the 2002 Addenda. A formal schedule for publication to receive public comments is not yet available, but it is anticipated that the proposed rule will be published in the last quarter of CY03.

2. ASME Code Cases - Rulemaking/Regulatory Guides

Four draft regulatory guides were published for public review on December 28, 2001: DG-1090, (Proposed Revision 32 to Regulatory Guide 1.84), "Design, Fabrication, and Materials Code Case Acceptability, ASME Section III; DG-1089, "Operation and Maintenance Code Case Acceptability," ASME OM Code; DG-1091, (Proposed Revision 13 to Regulatory Guide 1.147), "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1; and DG-1112, "ASME Code Cases Not Approved for Use." The guides address Supplement 4 to the 1992 Edition through Supplement 11 to the 1998 Edition, and OMN-1 through OMN-13. Fifteen comment letters were received on the draft guides, and eight letters were received on the proposed rule. The staff has completed its proposed responses and revised the rule and guides accordingly. The final package is being reviewed by NRC management. The Committee to Review Generic Requirements (CRGR) and Advisory Committee on Reactor Safeguards (ACRS) reviews are being scheduled. Office, CRGR, and ACRS approvals have been received. The final rule and guides should be published in late May/early June 2003. Upon publication, the guides will be available in ADAMS. The ADAMS numbers are: RG 1.184: ML030730417; RG 1.147: ML030730423; RG 1.192 (OM Guide):ML030730430; RG 1.193 (Unapproved code cases): ML030730440; and the response to public comments: ML030730448.

The NRC staff has completed its review of the Code Cases in Supplement 12 to the 1998 Edition through Supplements 1, 2, 3, 4, and 5 to the 2001 Edition. Supplement 6 was recently published by the ASME. The NRC staff is considering including supplements 4 through 6 in the upcoming revisions. This would have a minimal impact on the schedule (Proposed Revision 33 to Regulatory Guide 1.84, Proposed Revision 14 to Regulatory Guide 1.147, and Proposed Revision 1 to RG 1.193, "ASME Code Cases Not Approved for Use," are in office review. It is anticipated that these draft guides would be published for public comment in July 2003.

3. ASME PRA Standard

Draft Regulatory Guide DG-1122, "An Approach for Determining the Technical Adequacy of PRA Results for Risk-Informed Activities," which provides the NRC’s proposed positions on consensus PRA standards and industry PRA documents, has been published for public review and comment (comment period ends on February 28, 2003). The NRC staff and ASME have resolved most of the issues. The NRC staff made a presentation to the ACRS the week of April 7, 2003. There are three basic areas yet to be resolved. The first area is a requirement for the peer reviewers to assess the adequacy of the assumptions. The second area is a requirement for the peer reviewers to evaluate (at a high level) a minimum list of topics [depth of review would still be left to peer reviewer discretion]. The third area is to define the words "significant," "important," and "key." The guide is scheduled to be published in June 2003. Since most of the issues have been resolved, the ASME has indicated it will publish an addendum to the standard. This would eliminate many of the NRC staff concerns.

4. Risk-Informed Activities

The NRC website contains information at http://www.nrc.gov/what-we-do/regulatory/rulemaking/risk-informed/reactor-safety.html relative to risk-informed activities in the Reactor Safety Arena.

The staff met with NEI and other industry representatives in November 2002 to discuss "living program" guidance for risk-informed in service inspection (RI-ISI) programs. RI-ISI programs must be updated to reflect changes in the plant, and general industry experience that might impact the program. The schedule and extent of such changes is under development. NEI stated that it intends to complete guidance on this process and to provide it to the staff for review and comment by the Spring of 2003. There are currently no plans for the staff to approve the guidance.

The staff is in the process of updating the RI-ISI Regulatory Guide 1.178 and SRP Section 3.9.8 and plans to issue the updated guidelines by the summer of 2003. Minimal changes are needed or planned. A public workshop was held on March 13, 2003, and a presentation to the ACRS is scheduled for May 2003. The final guide is scheduled for publication in August 2003.

5. Generic Activities on PWR Alloy 600/182/82 PWSCC

On February 11, 2003, an Order titled, "Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors," was issued (EFFECTIVE IMMEDIATELY). Many of the licensees' responses to Bulletin 2002-02 did not describe long-term inspection plans nor a schedule to submit such descriptions. The Order requires specific inspections of the reactor pressure vessel (RPV) head and associated penetration nozzles at pressurized water reactors (PWRs). It has been determined that the current RPV head visual inspection requirements are not sufficient to reliably detect circumferential cracking of RPV head nozzles and corrosion of the RPV head. The Order establishes interim requirements to ensure that licensees implement and maintain appropriate measures to inspect and, as necessary, repair RPV heads and associated penetration nozzles. The long-term resolution of this issue is expected to involve changes to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) and will involve changes to the NRC regulations in 10 CFR 50.55a, "Codes and standards." Licensee responses to the order and other related documents are provided on the website for each operating reactor, grouped by NRC region:

On April 15, 2003, the NRC's Restart Oversight Panel held public meetings to discuss the status of the Oversight Panel activities and respond to questions and concerns from the public. The next public Restart Oversight Panel meetings are scheduled for May 6, 2003.

6. Future Reactor Licensing Activities - Advanced Reactor Infrastructure Assessment

There continues to be significant interest and activity on new reactor licensing topics. On March 28, 2002, Westinghouse Electric Company (Westinghouse) submitted its application for final design approval and standard design certification for the AP1000. The staff is currently reviewing the AP1000 design certification application and has six other designs in various stages of preapplication review (most notably the ESBWR and Gas Turbine-Modular Helium Reactor (GT-MHR) designs). General Atomics met with the staff and interested stakeholders on January 28 and 29, 2003, to discuss issues related to technology and preapplication activities. In addition, preapplication discussions are taking place in preparation for three early site permit applications expected in 2003. Proposed changes to 10 CFR Part 52 have been forwarded to the Commission. ESP pre-application public meetings, discussing key issues with NEI and the expected applicants have been initiated. The staff has also begun conducting public meetings in the vicinity of expected sites to inform the public about the ESP process and opportunities for public participation.

The staff is scheduled to issue the draft safety evaluation for the AP1000 design certification in June 2003. Pre-application review for the ESBWR and GT-MHR designs will continue, with additional pre-application reviews for the ACR-700, SWR 1000, and IRIS designs starting. Technical and regulatory infrastructure development will continue, with the goal of improving the efficiency, effectiveness, and realism of staff review, and ensuring that an appropriate level of safety is maintained for new reactor and site licenses.

7. Risk-Informing 10 CFR Part 50 (Option 2)

The NRC staff has prepared a proposed rule, 10 CFR 50.69, "Risk-Informed Treatment of Structures, Systems, and Components," under Option 2 of the NRC’s initiative to incorporate risk insights into its regulations. The Commission has sought for a number of years to find various ways to use the risk insights gained to shape the NRC’s regulatory system in new ways. Option 2 was to focus on the requirements dealing with safety-related structure systems and components (SSC's). Consistent with Commission direction, the staff made its preliminary rule language publicly available on the NRC website on November 29, 2001. The staff reviewed the comments received on the draft rule and posted a revision to the draft rule dated April 3, 2002. Comments on the revised draft rule were received from NEI in a letter dated May 15, 2002, and from ASME in letters dated June 3 and 17, 2002. A public meeting was held on June 18, 2002, to discuss the NEI and ASME comments. The NRC staff considered the comments and posted a further revised draft rule dated July 31, 2002. NEI is preparing guideline document NEI 00-04, "Option 2 Implementation Guidance."

On Thursday November 21, 2002, a Commission briefing was held on risk informing special treatment requirements (the proposed rule and Differing Professional Views [DPV]on the proposed 10 CFR 50.69 rule package are available at http://www.nrc.gov/reading-rm/doc-collections/commission/slides/2002/20021121/. The filers of the DPV believe that the treatment of RISC-3 components is not sufficient to maintain safety and protect the public health and safety. The staff has focused its review of NEI 00-04 on categorization, and did not plan to develop or endorse regulatory guidance for treatment of RISC-3 components. NEI submitted a draft of NEI 00-04 on June 28, 2002. On August 14, 2002, the NRC staff provided comments to NEI on the guidance document (ADAMS Accession No. ML022270004). The NRC staff plans to complete a regulatory guide that would endorse NEI 00-04 with clarifications and exceptions, as necessary. At the present time, there are a number of issues that need further discussion and development before NRC can complete such a document.

Pilot plant activities at Wolf Creek, Surry, Quad Cities, and Palo Verde were conducted to evaluate the proposed NEI Option 2 implementing guidance (NEI 00-04). The staff plans to use the lessons learned from these efforts to improve the NEI guidance and the Option 2 regulatory framework. There are issues that remain to be resolved in the implementation guidance.

On March 21, 2003, SECY-03-0044, "Update of The Risk-informed Regulation Implementation Plan," an updated and revised version of the Risk-Informed Regulation Implementation Plan (RIRIP) was provided to the Commission. The RIRIP discusses the agency's actions to risk-inform its regulatory activities and specifically describes each of the activities identified as supporting the goals and objectives of the agency's Strategic Plan and the Probabilistic Risk Analysis Policy Statement. Key risk-informing activities to be conducted at the agency over the next 6 months are described in the SECY.

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