ML20210H971
| ML20210H971 | |
| Person / Time | |
|---|---|
| Issue date: | 07/16/1999 |
| From: | Travers W NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| SECY-99-185, SECY-99-185-01, SECY-99-185-R, NUDOCS 9908040152 | |
| Download: ML20210H971 (9) | |
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.......................a POLICY ISSUE July 16.1999 (Information)
SECY-99-185 FOR:
The Commissioners FROM:
William D. Travers Executive Director for Operations
SUBJECT:
SUMMARY
OF ACTIVITIES RELATED TO GENERIC SAFETY ISSUES PURPOSE:
To provide the annual summary report on activities related to generic safety issues (GSis).
BACKGROUND:
It has been the practice of the staff tc, provide the Commission with an annual update of the progress made in resolving G31s. Further, in a staff requirements memorandum dated May 8,1998, in response to SECY-98-030, " Implementation of DSI-22, Research," the Commission directed the staff to provide an annual summary of activities related to open GSis.
The current structure of the Genenc issues Program was established in the 1980s and was intended to address reactor generic issues, the resolution of environmental issues, improvement in the licensing process, and the elimination of requirements that are overly conservative or unnecessarily restrictive or costly. Currently, the NRC process for addressing generic issues from all sources, operational and non-operational, is delineated in NUREG-0933, "A Prioritization of Generic Safety Issues." In addition, Management Directive 8.5, " Operational Safety Data Review," addresses the roles of each affected office in the identification of generic issues resulting from the review of operational data.
Contact-Ronald C. Emrit, RES
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99-105 R PDR
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p The Commissioners 2
In 1998, the staff conducted a self-assessment of the generic issues process and recommended changes to improve efficiency, timeliness, and clarity. The staff is developing a new Management Directive 6.4, " Generic Issue Program," to institute these changes. A draft of this directive has been prepared and is now in interoffice review. The Advisory Committee on Reactor Safeguards (ACRS) has been briefed on the revised process and the new directive, and ACRS comments have been incorporated. Consistent with the ACRS recommendation, the staff intends to implement a trial application of the new directive beginning in July 1999.
The description of the progress on the resolution of GSis which follows is based on the currently approved process delineated in NUREG-0933. The process for addressing GSis currently consists of six steps: identification, prioritization, resolution, imposition, implemsatation, and verification. Generally, safety concerns associated with operating events, research results, or risk assessments form the basis for the identification of GSis by the staff, the ACRS, industry, or the public. After a GSI is identified, it is then prioritized to determine whether resources should be expended in pursuit of a resolution. This prioritization step is generally completed with a quantitative analysis of the risk reduction potential of the issue and a priority ranking of HIGH?
MEDIUM, LOW, or DROP. Those GSis with rankings of HIGH or MEDIUM would be able to meet the " substantial increase in the overall protection of the public health and safety" requirement of 10 CFR 50.109 and are selected for resolution. No additional action is taken on GSis in the LOW-priority and DROP categories.
Resolution of a GSI requires a cost-benefit analysis of a proposed solution after consideration of the options to improve safety. Some action is taken on those for which the cost-benefit analysis shows that 'the direct and indirect costs are justified in view of this increased protection"(10 CFR 50.109). The ACRS normally reviews the prioritization and resolution of GSis associated with nuclear power plants. The schedules for resolution of GSis allow adequate time for ACRS review and resolution of ACRS coraments. In the imposition step, the staff issues requirements that may result from the resolution of the GSI, and the affected licensees are required to prepare i,chedules for implementing these requirements.
Implementation covers the step in which the affected licensees perform actions on their operating plants to satisfy the commitments made during the imposition step. Finally, verification is Eccomplished by NRC inspection of licensee actions.
GSis associated with nuclear reactor power plants are prioritized by the Office of Nuclear Regulatory Research (RES) using the methodology of NUREG-0933. Most of the reactor GSis that meet the requirement of substantialincrease in public health and safety are assigned to RES for resolution. The Office of Nuclear Reactor Regulation (NRR)is assigned those reactor GSis that require extensive interface with operating plants. RES is responsible for:
(1) resolving GSis through the conduct of research; (2) tracking the status of all generic issues though the identification, prioritization, and resolution steps in the agency-wide Generic issue Management Control System (GIMCS); and (3) documenting the prioritization and resolution results in NUREG-0933 and making it publicly available on the NRC Website. NRR its responsible for managing the imposition, implementation, and verification of those GSis that result in new requirements. Tracking GSis through these final three steps is accomplished with the Safety issues Management System (SIMS). The ACRS has contributed to the prioritization and resolution of GSis associated with nuclear power plants. Resolution of GSis will continue to
I l
The Commissioners 3
be coordinated with the ACRS and schedules for resolution will allow adequate time for ACRS l
review and resolution of ACRS concerns.
Over the years, the Generic Issues Program focused on GSis related to nuclear power plants. However, following a Commission briefing on mechanisms for addressing GSis on l
December 19,1995, the staff expanded the program to include non-reactor GSIs identified by the Office of Nuclear Material Safety and Safeguards (NMSS). For non-reactor GSis, NMSS is responsible for managing all six steps of the program described above, in accordance with the guidelines of NMSS Policy and Procedures Letter 1-57.
DISCUSSION:
Reactor GSis Since the last report to the Commission in SECY-98-166, the following two new reactor GSIs were identified for prioritization:
185 Control of Recriticality Following Small-Break LOCA in PWRs 186 Potential Risk and Consequences of Heavy Load Drops These two new GSis are scheduled to be prioritized by December 1999.
Three LOW-priority GSis were reprioritized based on new information, and three GSIs (two HIGH and one MEDIUM) were resolved with no new or revised requirements for licensees.
Reactor GSis prioritized and resolved during the past year are listed in Attachment 1. Currently, nine HIGH-priority and three MEDIUM-priority reactor GSis remain to be resolved, and the current schedules for the resolution of these twelve issues are listed in Attachment 2.
Non-Reactor GSis During the reporting period, the following four new non-reactor GSIs were identified for prioritization:
NMSS-13 Use of Different Dose Models to Demonstrate Compliance NMSS-14 Surety Estimates for Groundwater Restoration at in-Situ Leach Facilities NMSS-15 Adequacy of Part 150 Criticality Requirements i
NMSS-16 Adequacy of 0.05 Weight Percent Limit in Part 40 The above four GSis were prioritized, and five G31s (one HIGH and four MEDIUM) were resolved with no new or revised requirements forlicensees. Non-reactor GSis prioritized and resolved since the last report to the Commission are listed in Attachment 1. Six non-reactor GSis remain to be resolved, and the current schedules for the resolution of these issues are listed in Attachment 2.
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The Commissioners 4
CONCLUSION:
The staff will continue to use the processes of NUREG-0933 and NMSS Policy and Procedures Letter 1-57 as well as the procedures of Management Directive 8.5 to identify, prioritize, and resolve reactor and non-reactor GSis, until the new process is approved by the Commission.
The staff will continue to provide an annual update to the Commission and will inform the Commission of any significant results of the ongoing assessment of these areas.
i L
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xecutive Directo for Operations Attachments:
- 1. GSis Prioritized and Resolved since July 6,1998
- 2. Unresolved GSis as of June 28,1999 l
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