ML070570160
| ML070570160 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 02/23/2007 |
| From: | Hall J NRC/NMSS/SFST/LID/LB |
| To: | Connell J Maine Yankee Atomic Power Co |
| Pearson J NMSS/SFPO (301) 415-1985 | |
| References | |
| TAC L24046 | |
| Download: ML070570160 (6) | |
Text
February 23, 2007Mr. James Connell ISFSI Manager Maine Yankee Atomic Power Company 321 Old Ferry Road Wiscasset, ME 04578-4922
SUBJECT:
MAINE YANKEE - APPROVAL OF QUALITY ASSURANCE PROGRAM CHANGES (TAC NO. L24046)
Dear Mr. Connell:
By letter dated November 29, 2006, Maine Yankee Atomic Power Company (MYAPC) submitted a proposed revision to the quality assurance (QA) program description for Maine Yankee. The revision was submitted as a reduction in commitment under the provisions of 10 CFR 50.54(a)(4). The proposed revision reflects program simplifications based on the plant's decommissionedstatus. Specifically, all spent fuel has been transferred to the Independent Spent Fuel Storage Installation (ISFSI). Consequently, the primary focus of the quality program requirements for Maine Yankee has shifted to important-to-safety ISFSI structures, systems, components, and associated processes. The Nuclear Regulatory Commission staff (the staff) notes that the quality program also continues to apply to packaging and transportation of radioactive material under 10 CFR Part 71. The staff reviewed the proposed revision, as documented in the enclosed safety evaluation,and found that the revised program, with the reduction in commitment will continue to satisfy the criteria of 10 CFR Part 50, Appendix B, and 10 CFR 72.140(d). Therefore, the staff finds the proposed changes to the QA program for Maine Yankee acceptable. Please contact me at (301) 415-1336, or Jim Pearson at (301) 415-1985, for any additional information or clarification you need on this subject. Sincerely, /RA/James R. Hall, Senior Project Manager Licensing Branch Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards Docket Nos: 50-309,72-030 License No.: DPR-36
Enclosure:
Safety Evaluationcc: Maine Yankee distribution list Mr. James Connell ISFSI Manager Maine Yankee Atomic Power Company 321 Old Ferry Road Wiscasset, ME 04578-4922
SUBJECT:
MAINE YANKEE - APPROVAL OF QUALITY ASSURANCE PROGRAM CHANGES (TAC NO. L24046)
Dear Mr. Connell:
By letter dated November 29, 2006, Maine Yankee Atomic Power Company (MYAPC) submitted a proposed revision to the quality assurance (QA) program description for Maine Yankee. The revision was submitted as a reduction in commitment under the provisions of 10 CFR 50.54(a)(4). The proposed revision reflects program simplifications based on the plant's decommissionedstatus. Specifically, all spent fuel has been transferred to the Independent Spent Fuel Storage Installation (ISFSI). Consequently, the primary focus of the quality program requirements for Maine Yankee has shifted to important-to-safety ISFSI structures, systems, components, and associated processes. The Nuclear Regulatory Commission staff (the staff) notes that the quality program also continues to apply to packaging and transportation of radioactive material under 10 CFR Part 71. The staff reviewed the proposed revision, as documented in the enclosed safety evaluation,and found that the revised program, with the reduction in commitment will continue to satisfy the criteria of 10 CFR Part 50, Appendix B, and 10 CFR 72.140(d). Therefore, the staff finds the proposed changes to the QA program for Maine Yankee acceptable. Please contact me at (301) 415-1336, or Jim Pearson at (301) 415-1985, for any additional information or clarification you need on this subject. Sincerely, James R. Hall, Senior Project Manager Licensing Branch Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards Docket Nos: 50-309,72-030 License No.: DPR-36
Enclosure:
Safety Evaluationcc: Maine Yankee distribution listDISTRIBUTION
- SFST r/fNMSS r/fRaymond Lorson. RIWRulandSCrutchfield, OCFO C:\FileNet\ML070570160.wpdOFC:SFSTSFSTESFSTESFSTNAME:JPearsonMDeBoseJRHallRLewisDATE: 2/12/07 2/12/07 2/23/072/15/07 / / / /OFFICIAL RECORD COPY Maine Yankee Service List cc:
Senator Charles PrayState Nuclear Safety Advisor State Planning Office State House Station #38 Augusta, ME 04333First Selectman of Wiscasset Municipal Building U.S. Route 1 Wiscasset, ME 04578Friends of the CoastP.O. Box 98 Edgecomb, ME 04556Mr. Jonathan M. BlockAttorney at Law P.O. Box 566 Putney, VT 05346-0566Joseph Fay, EsquireMaine Yankee Atomic Power Company 321 Old Ferry Road Wiscasset, ME 04578-4922Mr. Wayne Norton, Vice President and Chief Nuclear Officer Maine Yankee Atomic Power Company 321 Old Ferry Road Wiscasset, ME 04578-4922Mr. Patrick J. Dostie State of Maine Nuclear Safety Inspector Department of Health and Human Services Maine Public Health Division of Environmental Health 286 Water St., Key Plaza - 8th Floor State House Station 11 Augusta, ME 04333Mr. Mark RobertsU.S. Nuclear Regulatory Commission
475 Allendale Road King of Prussia, PA 19406David Lewis, EsquireShaw Pittman 2300 North Street, NW Washington, DC 20037Mr. James Connell, ISFSI ManagerMaine Yankee Atomic Power Company 321 Old Ferry Road Wiscasset, ME 04578-4922W. Clough Toppan, P.E., DirectorDivision of Health Engineering Department of Human Services
- 10 State House Station Augusta, ME 04333 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS PROPOSED REVISION TO THE MAINE YANKEE QUALITY ASSURANCE PROGRAM DOCKET NUMBERS 50-309 AND 72-030
1.0 INTRODUCTION
By letter dated November 29, 2006, Maine Yankee Atomic Power Company (the licensee)submitted a proposed revision (Revision 30) to their "Quality Assurance Program Description" to be applied at the Maine Yankee Atomic Power Station. This quality assurance (QA) program revision was submitted as a reduction in commitment under the provisions of 10 CFR 50.54(a)(4). The proposed QA program revision reflects changes and program simplification based primarily on having transferred all spent fuel from the spent fuel pool to dry cask storage in the Independent Spent Fuel Storage Installation (ISFSI), and also in consideration of the plant's current extensively decommissioned status.
2.0 BACKGROUND
The licensee previously submitted certification of permanent cessation of operations andcertification of permanent fuel removal. Subsequently, the licensee has accomplished significant decommissioning of the facility including removal of many major components. All spent fuel has been transferred to the Independent Spent Fuel Storage Installation (ISFSI). As a result of the decommissioning activities, the licensee states that there are no longer any safety-related structures, systems, or components (SSCs) at the facility. The QA program, however, continues to apply to the ISFSI components identified as "Important to Safety" and to other select areas, such as radiological safety and transportation of radioactive materials. 3.0 EVALUATION 3.1 Basis of Evaluation The existing Maine Yankee QA program (MYQAP) is considered to meet the criteria inAppendix B to 10 CFR Part 50, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants." Appendix B establishes quality assurance requirements for the design, fabrication, construction, testing, and operation of nuclear power plant safety-related SSCs.
During decommissioning, the regulations require the licensee to maintain a QA program that complies with Appendix B until the Part 50 license is terminated. An acceptable way of establishing QA program compliance with the requirements of10 CFR Part 50, Appendix B, quality assurance criteria in support of ISFSI operation and maintenance is by reviewing and evaluating the licensee's commitment to the applicable ANSI Standards and corresponding NRC Regulatory Guides. The proposed changes to the MYQAP were qualitatively evaluated and judged based on changes and exceptions to previous commitments to these ANSI standards and associated regulatory guides in the context of the current decommissioning status of the facility. The changes were also evaluated to ensure continued compliance of the QA program withquality assurance regulations for ISFSIs per 10 CFR 72.140(d). Evaluation of the acceptability 2of the QA program changes relative to the ISFSI was performed in accordance with theguidance of NUREG-1567, "Standard Review Plan for Spent Fuel Dry Storage Facilities," which provides a well-defined, uniform basis for evaluating proposed changes to licensee
commitments. Therefore, this evaluation reviews the MYQAP changes for conformance with both10 CFR Part 50, Appendix B, and 10 CFR Part 72, Subpart G. 3.2 Assessment of QA Program Against 10 CFR Part 72, Subpart G The staff reviewed and evaluated the proposed changes in Revision 30 of the QA program forMaine Yankee, in order to determine whether the MYQAP, as revised, will continue to comply with the requirements of 10 CFR Part 72, "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class C Waste," Subpart G, "Quality Assurance."
(a) Areas Reviewed:The complete submittal was reviewed by the staff to confirm that the corresponding guidancefor each of the Part 50 and Part 72 quality criteria listed below were acceptably addressed in the revised program:Quality assurance organizationQuality assurance program Design control Procurement document control Instructions, procedures, and drawings Document control Control of purchased material, equipment, and services Identification and control of materials, parts, and components Control of special processes Licensee and certificate holder inspection Test control Control of measuring and test equipment Handling, storage, and shipping control Inspection, test, and operating status Nonconforming materials, parts, or components Corrective action Quality assurance records Audits NUREG-1567 provides specific guidance for evaluating the licensee's quality program changesagainst the above 18 quality criteria in regard to spent fuel dry storage facilities. Based on the staff's review of the MYQAP, the staff has determined that the proposed revision continues to meet the requirements of Subpart G of 10 CFR Part 72. While this evaluation has determined that the MYQAP is acceptable, continued proper implementation of the quality program plan will be assessed during future NRC inspections. (b) Evaluation Findings 3The MYQAP describes requirements, procedures, and controls that, when properlyimplemented, comply with requirements of both 10 CFR Part 50 and 10 CFR Part 72. The structure of the organization and assignment of responsibility for each activity ensures thatdesignated parties will perform the work to achieve and maintain specified quality requirements. Conformance to established requirements will be verified by qualified personnel and groups notdirectly responsible for the activity being performed. These personnel and groups report through a management hierarchy which grants the necessary authority and organizational freedom and provide sufficient independence from economic and scheduling influences. The quality program plan provides adequate control over activities affecting quality, as well asstructures, systems, and components important to safety, consistent with their relative importance to safety. The Quality Assurance Program for Maine Yankee, Revision 30, is found to meet therequirements of 10 CFR Part 50, Appendix B, and Part 72, Subpart G, based on the review described above.
4.0 CONCLUSION
The proposed changes to the licensee's QA program as described above will continue to satisfy the criteria of Appendix B to 10 CFR Part 50, and Subpart G of 10 CFR Part 72.Principal Contributor: J. Pearson Date: February 23, 2007