ML15218A557

License Amnd 4 for Humboldt Bay ISFSI

ML15218A557
Person / Time
Site:	Humboldt Bay
Issue date:	09/22/2015
From:	Michele Sampson Spent Fuel Licensing Branch
To:	Pacific Gas & Electric Co
John Hickman
Shared Package
ML15218A551	List: ML15148A361 ML15218A557
References
TAC J53019
Download: ML15218A557 (6)

Text

PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 72-27 HUMBOLDT BAY INDEPENDENT SPENT FUEL STORAGE INSTALLATION AMENDMENT TO MATERIALS LICENSE Amendment No. 4 License No. SNM-2514

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The amendment application dated June 30, 2014, as supplemented March 27, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions regulations set forth in 10 CFR Chapter 1; B. The Humboldt Bay Independent Spent Fuel Storage Installation will continue to operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance that (i) the activities authorized by this amendment can be conducted without endangering public health and safety, and (ii) such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to public health and safety; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by the enclosed changes to Materials License No.

SNM-2514, indicated by margin notations.

2

3. This license amendment is effective as of the date of issuance and shall be implemented within 90 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Michele Sampson, Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Enclosed: Revised License Pages Date of Issuance: September 22, 2015

NRC FORM 588 U. S. NUCLEAR REGULATORY COMMISSION (10-2000) 10 CFR 72 PAGE 1 OF 4 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. Pacific Gas and Electric Company 3. License No. SNM-2514 Amendment No. 4

2. Humboldt Bay Power Plant 1000 King Salmon Avenue Eureka, CA 95503 4. Expiration Date November 17, 2025

5. Docket or Reference No. 72-27

6. Byproduct, Source, and/or 7. Chemical or Physical Form 8. Maximum Amount That Licensee Special Nuclear Material May Possess at Any One Time Under This License A. Spent nuclear fuel from the A. Spent fuel assemblies as A. 31 MTU of intact spent fuel Humboldt Bay Power Plant, UO2, clad with zirconium assemblies, damaged fuel Unit 3, and associated alloy. Damaged fuel assemblies and fuel debris.

radioactive materials related assemblies, or fuel debris as to receipt, transfer and UO2, zirconium alloy cladding storage of the fuel or stainless steel cladding assemblies. contained in Damaged Fuel Containers.

B. Greater Than Class C Waste; B. Greater Than Class C Waste, B. 11 MT of Greater Than Class C non-fuel related radioactive as activated metals and Waste material generated as a result process wastes comprised of of reactor operation and miscellaneous solid waste decommissioning, where resulting from reactor radionuclide concentrations operation and exceed the limits of 10 CFR decommissioning.

61.55 for Class C Waste.

9. Authorized Use: The material identified in 6.A., 6.B., 7.A. and 7.B., above is authorized for receipt, possession, storage and transfer using the HI-STAR HB dry cask storage system design as described in the Humboldt Bay ISFSI Safety Analysis Report dated December 15, 2003, as revised or supplemented on October 1, 2004, October 4, 2012 and as further 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 Humboldt Bay ISFSI located on the Humboldt Bay Power Plant site in Humboldt County, California, near Eureka, California.

NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 2 OF 4 PAGES (10-2000) 10 CFR 72 License No. Amendment No.

LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR SNM-2514 4 FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No.

SUPPLEMENTARY SHEET 72-27

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, Humboldt Bay Independent Spent Fuel Storage Installation Physical Security Plan, the Humboldt Bay Independent Spent Fuel Storage Installation Safeguards Contingency Plan, and the Humboldt Bay Independent Spent Fuel Storage Installation Security Training and Qualification Plan, dated December 9, 2003, as revised July 11, 2005, and as they may be further amended under the provisions of 10 CFR 72.44(e) and 10 CFR 72.180.

13. Fuel and cask movement and handling activities that are to be performed in the Humboldt Bay Power Plant refueling building will be governed by the requirements of the Humboldt Bay Power Plant Unit 3 Facility Operating License (DPR-7) and associated Technical Specifications.

14. The Commissions finding that the Quality Assurance Program complies with the requirements of 10 CFR Part 72, Subpart G is based on the existence of a Quality Assurance Program accepted by the Commission as satisfying the requirements of 10 CFR 50, Appendix B. The portion of the Commission-approved Quality Assurance Program that is applicable to the Humboldt Bay ISFSI is contained in the Humboldt Bay Quality Assurance Plan and is under the control of the Humboldt Bay Power Plant, Unit 3 Part 50 license. Prior to the termination of the Part 50 license for the Humboldt Bay Power Plant, Unit 3, the licensee must submit, for Commission approval, a Quality Assurance Program for the Humboldt Bay ISFSI that satisfies each of the elements of Subpart G.

15. The licensee shall follow the Humboldt Bay ISFSI Emergency Plan dated December 15, 2003, as revised or supplemented on October 1, 2004, March 27, 2015 and as further supplemented and revised in accordance with 10 CFR 72.44(f).

16. Pursuant to 10 CFR 72.7 the licensee is hereby exempted from the provisions of 10 CFR 72.72(d), with respect to maintaining a duplicate set of spent fuel storage records. The licensee may maintain records of spent fuel and high level radioactive waste in storage either in duplicate, as required by 10 CFR 72.72(d), or, alternatively, a single set of records may be maintained at a records storage facility that satisfies the standards of ANSI N45.2.9-1974. All other requirements of 10 CFR 72.72(d) must be met.

17. Prior to loading spent nuclear fuel into any dry storage cask, the following testing must be successfully completed:

For all fixed neutron absorbers:

(i) Each plate of neutron absorbers shall be visually inspected for damage (e.g., scratches, cracks, burrs, peeled cladding, foreign materials embedded in the surface, voids, delamination, and surface finish) as applicable.

(ii) The required Boron-10 content (areal density) of the neutron absorber panels for the MPC-HB shall be verified to be greater than or equal to 0.01 gm/cm2.

For BORAL:

After manufacturing, a statistical sample of each lot of BORAL neutron absorber shall be tested using wet chemistry and/or neutron attenuation testing to verify the minimum Boron-10 content (areal density) in samples taken from the ends of the panel.

For METAMIC:

(i) Verification that the boron carbide (B4C) content in the METAMIC is not more than 33.0 weight percent (ii) Verification that all lots of B4C powder shall meet particle size distribution requirements

NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 3 OF 4 PAGES (10-2000) 10 CFR 72 License No. Amendment No.

LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR SNM-2514 4 FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No.

SUPPLEMENTARY SHEET 72-27 (iii) Qualification testing shall be performed on the first production run of METAMIC panels to be used in a Holtec MPC to validate the acceptability and consistency of the manufacturing process and verify the acceptability of the METAMIC panels for neutron absorbing capability.

1. The B4C powder weight percent shall be verified by testing a sample from 40 different mixed batches. (A mixed batch is defined as a single mixture of aluminum powder and B4C powder used to make one or more billets. Each billet will produce several panels.) The samples shall be drawn from the mixing containers after mixing operations have been completed. Testing shall be performed using the wet chemistry method.

2. The Boron-10 areal density shall be verified by testing a sample from one panel from each of 40 different mixed batches. The samples shall be drawn from areas contiguous to the manufactured panels of METAMIC and shall be tested using the wet chemistry method. Alternatively, neutron attenuation tests on the samples may be performed to quantify the actual Boron-10 areal density.

3. To verify the local uniformity of the boron particle dispersal, neutron attenuation measurements of random test coupons shall be performed. These test coupons may come from the production run or from pre-production trial runs.

4. To verify the macroscopic uniformity of the boron particle distribution, test samples shall be taken from the sides of one panel from five different mixed batches before the panels are cut to their final sizes. The sample locations shall be chosen to be representative of the final product. Wet chemistry or neutron attenuation shall be performed on each of the samples.

(iv) For production runs of the panels to be used in the MPC-HB canisters, the following tests shall be performed:

1. Testing of mixed batches shall be performed on a statistical basis to verify that the correct B4C weight percent is being mixed.

2. Samples from random METAMIC panels taken from areas contiguous to the manufactured panels shall be tested via wet chemistry and/or neutron attenuation testing to verify the Boron-10 areal density. This testing shall be performed to verify the continued acceptability of the manufacturing process.

NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 4 OF 4 PAGES (10-2000) 10 CFR 72 License No. Amendment No.

LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR SNM-2514 4 FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No.

SUPPLEMENTARY SHEET 72-27

18. This license is effective as of the date of issuance shown below.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION

/RA/

Michele Sampson, Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Washington, DC 20555 Date of Issuance: November 17, 2005 As amended by Amendment 1, dated: August 6, 2008 Amendment 2, dated: _August 28, 2009 Amendment 3, dated: September 17, 2013 Amendment 4, dated: September 22, 2015

Attachment:

Appendix - Technical Specifications