ML20065N282
| ML20065N282 | |
| Person / Time | |
|---|---|
| Site: | 07200011 |
| Issue date: | 03/09/2020 |
| From: | John Mckirgan Office of Nuclear Material Safety and Safeguards |
| To: | Sacramento Municipal Utility District (SMUD) |
| KLBanovac NMSS/DFM/STL 415.7116 | |
| Shared Package | |
| ML20065N276 | List: |
| References | |
| 000993/L-2018-LNE-0004, 001028/L-2018-RNW-0005 | |
| Download: ML20065N282 (3) | |
Text
NRC FORM 588 U. S. NUCLEAR REGULATORY COMMISSION (10-2000) 10 CFR 72 PAGE 1 OF 3 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. Sacramento Municipal Utility District 3. License No. SNM-2510 Amendment No. 4
- 2. Rancho Seco Independent Spent Fuel Renewed on March 9, 2020 Storage Installation 14440 Twin Cities Road
- 4. Expiration Date June 30, 2060 Herald, California 95638
- 5. Docket or Reference No. 72-11
- 6. Byproduct, Source, and/or Special 7. Chemical or Physical Form 8. Maximum Amount That Licensee May Nuclear Material Possess at Any One Time Under This License A. Spent fuel from Rancho Seco A. Spent fuel assemblies and A. 228.8 MTU of intact spent fuel Nuclear Generating Station and damaged fuel assemblies as assemblies and damaged fuel associated fuel assembly control UO2 clad with Zircaloy-4. assemblies.
components, and radioactive materials related to the receipt, storage, and transfer of the fuel assemblies.
B. Greater than Class C Waste, B. Greater than Class C Waste, as B. 13.61 MT (30,000 lbs) of non fuel related material activated metals comprised of Greater than Class C Waste.
generated as a result of plant miscellaneous solid waste operations and decommissioning resulting from the segmentation where radionuclide and decommissioning process.
concentration limits of 10 CFR 61.55 are exceeded.
C. Strontium-90. C. Sealed source (Eckert & Ziegler C. 200 microcuries per source Isotope Products dba Isotope and 200 microcuries total.
Products Laboratories Model PHI-XXX GFS Series [formerly GFS series]).
NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 2 OF 3 PAGES (10-2000) License No. Amendment No.
10 CFR 72 LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR SNM-2510 4 FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No.
SUPPLEMENTARY SHEET 72-11 Renewed
- 9. Authorized Use: For use in accordance with statements, representations, and the conditions of the Technical Specifications and Rancho Seco ISFSI Safety Analysis Report (SAR) dated October 4, 1991, as revised or supplemented on October 27, 1993; January 28, May 28, and November 24, 1999; and February 24, March 2, 2000, July 29, 2004, December 2, 2004, and August 11, 2009.
The material identified in 6.A, 6.B, 6.C as well as 7.A, 7.B. and 7.C above is authorized for receipt, possession, storage, and transfer. Storage of material identified in 6.A, 6.B, 7.A and 7.B is authorized only in Horizontal Storage Modules of the NUHOMS design as described in the SAR.
The material identified in 6.C and 7.C above is authorized for checking functionality of radiation detection instruments.
- 10. Authorized Place of Use: The licensed material is to be received, possessed, transferred, and stored at the Rancho Seco ISFSI located on the Rancho Seco Nuclear Generating Station site in Sacramento County, California, near Herald, California.
- 11. The Technical Specifications contained in the Appendix attached hereto are incorporated into the license.
The licensee shall operate the installation in accordance with the Technical Specifications in the Appendix.
The Appendix 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 "Sacramento Municipal Utility District Rancho Seco Independent Spent Fuel Storage Installation (ISFSI) Physical Protection Plan (PPP),"
Amendment 0, dated February 1, 2000, and the safeguards contingency plan incorporated therein as Chapter 10, Contingency Response Plan and Procedures, and as they may be further amended under the provisions of 10 CFR 72.44(e) and 72.186(b).
The licensee shall follow the security organization personnel training and qualification plan entitled "Sacramento Municipal Utility District Rancho Seco Independent Spent Fuel Storage Installation (ISFSI)
Training and Qualification Plan (T&QP)," Revision 0, dated February 1, 2000, and as it may be further amended under the provisions of 10 CFR 72.44(e) and 72.186(b).
- 13. Except as specifically authorized, the licensee shall neither open sealed sources containing licensed material nor remove sources from source holders.
- 14. The licensee shall conduct a physical inventory every 6 months, or at other intervals approved by the U.S.
Nuclear Regulatory Commission, to account for all sealed sources received and possessed under the license. Records of inventories shall be maintained for 3 years from the date of each inventory and shall include the radionuclides, quantities, manufacturers name and model number, and the date of the inventory.
- 15. A sealed source shall be tested for leakage and contamination at intervals not to exceed 6 months, or at such intervals specified in the sealed source certificate of registration, while in use. Records of test results shall be kept in units of microcuries and shall be maintained for 3 years.
- 16. A sealed source need not be tested if it is in storage and is not being used. However, when it is removed from storage, either for use or for transfer to another person, and has not been tested within the required leak test interval, it shall be tested before use or transfer. No sealed source shall be stored for a period of more than 10 years without being tested for either leakage or contamination.
NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 3 OF 3 PAGES (10-2000) License No. Amendment No.
10 CFR 72 LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR SNM-2510 4 FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No.
SUPPLEMENTARY SHEET 72-11 Renewed
- 17. Sealed source leak tests shall be capable of detecting the presence of 0.005 microcurie (185 becquerels) of radioactive material on the test sample. If the test reveals the presence of removable contamination greater than or equal to 0.005 microcurie (185 becquerels), a report shall be filed with the U.S. Nuclear Regulatory Commission in accordance with 10 CFR 30.50(c)(2), and the source shall be removed immediately from service and decontaminated, repaired, or disposed of in accordance with Commission regulations.
- 18. Tests for leakage and contamination shall be performed by the licensee or other persons specifically licensed by the U.S. Nuclear Regulatory Commission or an Agreement State to perform such services. In addition, the licensee is authorized to collect leak test samples for analysis by persons specifically licensed by the Commission or an Agreement State to perform such services.
- 19. In the absence of a certificate indicating that a leak test has been made within the intervals specified in the certificate of registration, a sealed source received from another person shall not be put into use until tested and the test results received.
- 20. Within 90 days after issuance of the renewed license, SMUD shall submit an updated final safety analysis report (FSAR) to the U.S. Nuclear Regulatory Commission (NRC), in accordance with 10 CFR 72.4 and continue to update the FSAR pursuant to the requirements in 10 CFR 72.70(b) and (c). The updated FSAR shall reflect the information provided in Appendix C of the Rancho Seco ISFSI License Renewal Application, Revision 3, dated July 12, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19204A248). The licensee may make changes to the updated FSAR, consistent with 10 CFR 72.48(c).
- 21. A program document(s) shall be revised, or a new one created, for implementing the activities in the aging management programs (AMPs) described in the updated FSAR within one year after the issuance of the renewed license. The program document(s) shall contain a reference to the specific AMP provision(s) that the program document(s) is intended to implement, and the reference shall be maintained even if the program document(s) is modified. The licensee shall maintain the program document(s) throughout the term of this license.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
/RA/
John B. McKirgan, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Washington, DC 20555 Date of Issuance: June 30, 2000 Renewed License dated: March 9, 2020