Source: https://www.federalregister.gov/documents/2001/08/09/01-19970/stp-nuclear-operating-company-et-al-south-texas-project-units-1-and-2-exemption
Timestamp: 2018-07-18 11:04:22
Document Index: 415073322

Matched Legal Cases: ['art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 50']

https://www.federalregister.gov/d/01-19970 https://www.federalregister.gov/d/01-19970
In the introduction to Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” of Title 10 of the Code of Federal Regulations Part 50 (10 CFR Part 50, Appendix B), it states that nuclear power plants “include structures, systems, and components [SSCs] that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public. This appendix establishes quality assurance requirements for the design, construction, and operation of those structures, systems, and components. The pertinent requirements of this appendix apply to all activities affecting the safety-related functions of those structures, systems, and components; these activities include designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, operating, maintaining, repairing, refueling, and modifying.” Under 10 CFR Part 50, Appendix B, there are 18 criteria to be met by the licensee's quality assurance program. These 18 criteria are (I) Organization, (II) Quality Assurance Program, (III) Design Control, (IV) Procurement Document Control, (V) Instructions, Procedures, and Drawings, (VI) Document Control, (VII) Control of Purchased Material, Equipment, and Services, (VIII) Identification and Control of Materials, Parts, and Components, (IX) Control of Special Processes, (X) Inspection, (XI) Test Control, (XII) Control of Measuring and Test Equipment, (XIII) Handling, Storage, and Shipping, (XIV) Inspection, Test, and Operating Status, (XV) Nonconforming Materials, Parts, or Components, (XVI) Corrective Action, (XVII) Quality Assurance Records, and (XVIII) Audits.
By letter dated July 13, 1999, as supplemented October 14 and 22, 1999, January 26 and August 31, 2000, and January 15, 18, 23, March 19, May 8 and 21, 2001, (hereinafter, the submittal), the licensee requested an exemption from the definition of scope of SSCs to be covered by the rule in the introduction of 10 CFR Part 50, Appendix B, to the extent that it imposes the requirements of 15 of the 18 criteria on SSCs categorized as low safety significant (LSS) or non-risk significant (NRS) in accordance with the licensee's categorization process. The three criteria that are not included within the scope of the licensee exemption request and that will continue to be applied to activities associated with all safety-related SSCs (including LSS and NRS SSCs) are Criterion III, “Design Control,” Criterion XV, “Nonconforming Materials, Parts, or Start Printed Page 41905Components,” and Criterion XVI, “Corrective Action.”
The NRC has completed its evaluation of STPNOC's request for an exemption from the requirements of 10 CFR Part 50, Appendix B (excluding the requirements of Criteria III, XV, and XVI). The NRC's evaluation is provided in a safety evaluation (SE) dated August 3, 2001, prepared in support of this exemption.
The staff has reviewed STPNOC's integrated SSC categorization process. The categorization process was found to use both a probabilistic and a deterministic based methodology that appropriately addressed the issues of defense-in-depth, safety margins, and aggregate risk impacts. The staff finds the proposed categorization process to be acceptable to categorize the risk significance of both functions and SSCs for use in reducing the scope of SSCs subject to special treatment. The categorization process provides an acceptable method for defining those SSCs for which exemptions from the special treatment requirements can be granted. In support of its finding on the licensee's categorization process, the staff also found that the alternative treatment practices provide the licensee with a framework that, if effectively implemented, will provide reasonable confidence that safety-related LSS and NRS SSCs remain capable of performing their safety functions under design-basis conditions. Based on these findings, the staff determined that LSS and NRS SSCs could be excluded from the scope of 10 CFR Part 50, Appendix B (the requirements of Criteria III, XV, and XVI would continue to apply), without undue risk to public health and safety.
The staff also found that granting of this exemption is in the public interest in that it enhances the effectiveness and efficiency of the NRC's oversight of the licensee's activities at STP by focusing its resources on those SSCs that are most significant to maintaining public health and safety. Likewise, the licensee's resources and attention can be focused on those SSCs that have the highest contribution to plant risk. Further, the licensee's categorization process provides a method for establishing a licensing basis for STP that is consistent with the risk-informed approach in the NRC's reactor oversight process. This enhances the regulatory framework under which STPNOC operates its facility and by which the NRC oversees the licensee's activities.
Accordingly, the Commission has determined that, pursuant to 10 CFR 50.12(a), the exemption is authorized by law, will not endanger life or property or common defense and security, and is, otherwise, in the public interest. Also, special circumstances are present. Therefore, the Commission hereby grants, subject to the conditions described below, STPNOC the exemption from the definition of the scope of SSCs to be covered by the rule in the introduction of 10 CFR Part 50, Appendix B, to the extent that it imposes the requirements of Criteria I, II, IV, V, VI, VII, VIII, IX, X, XI, XII, XIII, XIV, XVII, and XVIII for SSCs at STP categorized as LSS and NRS. The requirements imposed by Criteria III, XV, and XVI of 10 CFR Part 50, Appendix B, continue to apply to all safety-related SSCs. As conditions of this exemption:
1.The licensee described the categorization, treatment, and oversight (evaluation and assessment) processes in its submittal dated July 13, 1999, as supplemented October 14 and 22, 1999, January 26 and August 31, 2000, and January 15, 18, 23, March 19, May 8 and 21, 2001. The licensee has documented these processes in a proposed Final Safety Analysis Report (FSAR) submittal dated May 21, 2001, found acceptable by the staff as the regulatory basis for granting this exemption (see the NRC's SE dated August 3, 2001). The licensee shall incorporate this proposed FSAR submittal into the STP FSAR and shall implement the categorization, treatment, and oversight processes consistent with the STP FSAR descriptions.
2.The licensee shall implement a change control process that incorporates the following requirements:
This exemption is effective upon submittal of a FSAR update pursuant to 10 CFR 50.71(e) incorporating the FSAR Sections described in the conditions above.
Director, Division of Licensing Project Management Office of Nuclear Reactor Regulation.
[FR Doc. 01-19970 Filed 8-8-01; 8:45 am]