ML19296B636
| ML19296B636 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 03/31/1999 |
| From: | Meraj Rahimi NRC/NMSS/DFM/MSB |
| To: | Nicholson B Portland General Electric Co |
| Markley C | |
| Shared Package | |
| ML19221B646 | List: |
| References | |
| EPID L-2017-LNE-0009, EPID L-2017-RNW-0011 | |
| Download: ML19296B636 (2) | |
Text
NRC FORM 588 U. S. NUCLEAR REGULATORY COMMISSION (10-2000) 10 CFR 72 PAGE 1 OF 2 PAGES LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter 1, Part 72, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, and possess the power reactor spent fuel and other radioactive materials associated with spent fuel storage designated below; to use such material for the purpose(s) and at the place(s) designated below; and to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified herein.
Licensee
- 1. Portland General Electric Company, with 3. License No. SNM-2509 Eugene Water and Electric Board and Amendment No. 6 PacifiCorp
- 2. Portland General Electric Company Renewed on August 9, 2019 71760 Columbia River Highway Rainier, Oregon 97048 4. Expiration Date March 31, 2059
- 5. Docket or 72-17 Reference No.
- 6. Byproduct, Source, and/or 7. Chemical and/or Physical Form 8. Maximum Amount That Licensee Special Nuclear Material May Possess at Any One Time Under This License A. Spent fuel from Trojan A. Spent fuel assemblies and A. 344.5 MTU of intact Nuclear Plant and damaged fuel spent fuel assemblies, associated radioactive assemblies as UO2 damaged fuel materials related to receipt, clad with Zircaloy-4. assemblies, and fuel storage, and transfer of the Fuel debris as UO2 debris.
fuel assemblies contained in Failed Fuel Cans or Damaged Fuel Containers
- 9. Authorized Use: The material identified in 6.A. and 7.A above is authorized for receipt, possession, storage in the Trojan Storage System, and transfer as described in the approved Trojan ISFSI Safety Analysis Report (SAR), as supplemented and amended in accordance with 10 CFR 72.70 and 10 CFR 72.48.
- 10. Authorized Place of Use: The licensed material is to be received, possessed, transferred, and stored at the Trojan ISFSI located on the Portland General Electric Company site in Columbia County, Oregon, near Rainier, Oregon.
NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 2 OF 2 PAGES (10-2000) 10 CFR 72 License No. Amendment No.
LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR SNM-2509 6 FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No.
SUPPLEMENTARY SHEET 72-17 Renewed
- 11. The Technical Specifications contained in Appendix A attached hereto are incorporated into the license.
The licensee shall operate the installation in accordance with the Technical Specifications in Appendix A. Appendix A contains Technical Specifications related to Environmental Protection to satisfy the requirements of 10 CFR 72.44(d)(2).
- 12. The licensee shall follow the physical protection plan entitled Trojan ISFSI Security Plan, dated March 26, 1996 and Revision 1, dated January 8, 1999; and as it may be further amended under the provisions of 10 CFR Parts 72.44(e) and 72.180. The requirements of 10 CFR Part 73, Appendix B for guard training and qualification are incorporated in Appendix C of the approved security plan. The requirements of 10 CFR, Part 73, Appendix C, for contingency planning are addressed in Chapter 1.9 of the physical security plan.
- 13. Within 90 days of the issuance of renewed license, the licensee shall submit an updated Trojan ISFSI Safety Analysis Report (SAR) to the Commission and continue to update the SAR pursuant to the requirements in 10 CFR 72.70(b) and (c). The updated SAR shall include the proposed revisions as documented in Appendix G in Enclosure 2 of the January 23, 2019, response to NRCs Request for Additional Information (ADAMS Accession No. ML19028A411). The licensee may make changes to the SAR consistent with 10 CFR 72.48(c).
The SAR Update must also include the following text, to be added to the last paragraph in Section 9.7.8.4 Aging Management Programs: However, for the Transfer Cask AMP and Transfer Station AMP, consistent with the timing stated in the LRA, the first inspection will occur prior to the first use of the transfer cask and transfer station, respectively.
- 14. Within one year after the renewed license effective date, the licensee shall revise or create a document that defines the implementation of the Aging Management Program (AMP) as described in the proposed SAR update, as documented in Appendix G in Enclosure 2 of the January 23, 2019, response to NRCs Request for Additional Information. The document shall have sufficient detail to enable the development of comprehensive AMP procedures. The document shall contain a reference to the specific AMP provision(s) that the document is intended to implement. The reference shall be maintained even if the document is modified. The licensee shall maintain the document and any specific procedures for implementing the AMP throughout the term of this license.
- 15. This license is effective as of the date of issuance shown below.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Meraj Rahimi, Chief Materials and Structural Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Washington, DC 20555 Date of Issuance: March 31, 1999 Renewed License: Dated August 9, 2019.
Attachment:
Appendix - Technical Specifications