ML120960586
| ML120960586 | |
| Person / Time | |
|---|---|
| Site: | 05000083 |
| Issue date: | 11/17/2015 |
| From: | Alexander Adams Division of Policy and Rulemaking |
| To: | Jordan K Univ of Florida |
| Hardesty, Duane 301.415.3724 | |
| References | |
| TAC ME8131 | |
| Download: ML120960586 (16) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 17, 2015 Kelly A. Jordan, Ph.D.
Director, University of Florida Training Reactor 106 UFTR Building University of Florida Gainesville, FL 32611-6400
SUBJECT:
UNIVERSITY OF FLORIDA TRAINING REACTOR - ISSUANCE OF AMENDMENT NO. 27 TO AMENDED FACILITY OPERATING LICENSE NO. R-56 (TAC NO. ME8131)
Dear Dr. Jordan:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 27 to Amended Facility Operating License No. R-56 for the University of Florida (UF, the licensee)
Training Reactor (UFTR). The amendment changes the facility license in response to your application dated February 29, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12061A271), as supplemented by letters dated July 26 (ADAMS Accession No. ML12216A152) and August 31, 2012 (ADAMS Accession No. ML12256A957);
September 3, 2014 (ADAMS Accession No. ML14255A378); and April 7 (ADAMS Accession No. ML15112B177), and October 2, 2015 (ADAMS Accession No. ML15300A060).
The amendment deletes License Condition 2.C.(3) that required a physical security plan be maintained and reflects the requested changes to the technical specifications to reference security procedures. The NRC does not require a physical security plan for facilities, such as the UFTR, that possess special nuclear material in the amounts that are of low strategic significance. However, since the research reactor license authorizes possession of such material, security in accordance with the provisions of Title 10 of the Code of Federal Regulations, Section 73.67(f), "Fixed site requirements for special nuclear material of low strategic significance," must continue to be maintained.
The related safety evaluation supporting Amendment No. 27 is enclosed.
Sincerely,
/RA D.Hardesty for/
Alexander Adams, Jr., Chief Research and Test Reactors Licensing Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No.: 50-083
Enclosures:
- 1. Amendment No. 27
- 2. Safety Evaluation cc: See next page
University of Florida Docket No.50-083 cc:
Administrator Department of Environmental Regulation Power Plant of Siting Section State of Florida 2600 Blair Stone Road Tallahassee, FL 32301 State Planning and Development Clearinghouse Office of Planning and Budgeting Executive Office of the Governor The Capitol Building Tallahassee, FL 32301 Chief, Bureau of Radiation Control Department of Health 4052 Bald Cypress Way Tallahassee, FL 32399-1741 Test, Research and Training Reactor Newsletter P.O. Box 118300 University of Florida Gainesville, FL 32611-8300 Brian Shea, Reactor Manager University of Florida 340 Weil Hall P.O. Box 116134 Gainesville, FL 32611 Dean Cammy Abernathy University of Florida College of Engineering PO Box 116550 Gainesville, FL 32611 November 17, 2015 Kelly A. Jordan, Ph.D.
Director, University of Florida Training Reactor 106 UFTR Building
September 3, 2014 (ADAMS Accession No. ML14255A378); and April 7 (ADAMS Accession No. ML15112B177), and October 2, 2015 (ADAMS Accession No. ML15300A060).
The amendment deletes License Condition 2.C.(3) that required a physical security plan be maintained and reflects the requested changes to the technical specifications to reference security procedures. The NRC does not require a physical security plan for facilities, such as the UFTR, that possess special nuclear material in the amounts that are of low strategic significance. However, since the research reactor license authorizes possession of such material, security in accordance with the provisions of Title 10 of the Code of Federal Regulations, Section 73.67(f), "Fixed site requirements for special nuclear material of low strategic significance," must continue to be maintained.
The related safety evaluation supporting Amendment No. 27 is enclosed.
Sincerely,
/RA D.Hardesty for/
Alexander Adams, Jr., Chief Research and Test Reactors Licensing Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No.: 50-083
Enclosures:
- 1. Amendment No. 27
- 2. Safety Evaluation cc: See next page DISTRIBUTION:
Public RidsNrrDpr Resource EReed, NRR PRTA R/F RidsOgcRp Resource GHill, OIS RidsAcrsAcnw_MailCtr RidsOiOd KHsueh, NRR RidsNrrDprPrtb RidsNrrDprPrta DHardesty, NRR RecordsAmend ADAMS Accession Nos.: ML120960586, *concurred by e-mail NRR-058 OFFICE PRLB/PM* PRLB/LAit* PRLB/LA* PROB/SS OGC PRLB/BC PRLB/PM NAME DHardesty NParker ELee EReed (NLO w/comment) (D.Hardesty for) (MBalazik for)
SUttal AAdams DHardesty DATE 05/14/2015 05/13/2015 05/13/2015 05/18/2015 08/19/2015 11/17/2015 11/17/2015 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 UNIVERSITY OF FLORIDA DOCKET NO. 50-83 AMENDMENT TO AMENDED FACILITY OPERATING LICENSE Amendment No. 27 License No. R-56
- 1. The U.S. Nuclear Regulatory Commission (NRC or the Commission) has found that:
A. The application for an amendment to Amended Facility Operating License No.
R-56, filed by the University of Florida (the licensee) dated February 29, 2012, as supplemented by filings dated July 26, 2012; August 31, 2012; September 3, 2014; and April 7, 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 Chapter I of Title 10 of the Code of Federal Regulations (10 CFR);
B. The facility will operate in conformity with the application, 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 the health and safety of the public, and (ii) such activities will be conducted in compliance with the Commissions rules and regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E. The issuance of this amendment is in accordance with 10 CFR Part 51 Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions, of the regulations of the Commission and all applicable requirements have been satisfied, and; F. Prior notice of this amendment was not required by 10 CFR 2.105, Notice of Proposed Action, and publication of a notice for this amendment is not required by 10 CFR 2.106, Notice of Issuance.
Enclosure 1
- 2. Accordingly, the license is amended by deletion of paragraph 2.C.(3), Physical Security Plan of Amended Facility Operating License No. R-56.
- 3. Accordingly, the license is amended by changes to the technical specifications as indicated in the enclosure to this license amendment, and paragraph 2.C.(2) Technical Specifications, of Amended Facility Operating License No. R-56 is hereby amended as follows:
(2) Technical Specifications The technical specifications contained in Appendix A, as revised through Amendment No. 27, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the technical specifications.
- 4. This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA D.Hardesty for/
Alexander Adams, Jr., Chief Research and Test Reactors Licensing Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Attachments:
- 1. Changes to Amended Facility Operating License No. R-56
- 2. Changes to Appendix A, Technical Specifications Date of Issuance:
LICENSE AMENDMENT NO. 27 AMENDED FACILITY OPERATING LICENSE NO. R-56 DOCKET NO. 50-83 Replace the following pages of the Amended Facility Operating License No. R-56 with the attached revised pages. The revised pages are identified by amendment number and contains marginal lines indicating the areas of change.
Operating License Remove Insert Page 3 Page 3 Page 4 Page 4 Attachment 1
(2) Pursuant to the Act and 10 CFR Part 70, "Domestic Licensing of Special Nuclear Material," to receive, possess, and use (1) up to 5.0 kilograms of contained uranium-235 of enrichment of less than 20 percent in the form of material test reactor (MTR)-type reactor fuel; (2) a 1-curie sealed plutonium-beryllium neutron source; (3) a 25-curie sealed antimony-beryllium neutron source; and (4) up to 0.2 kilograms of contained uranium-235 of any enrichment in the form of fission chambers, flux foils and other forms, all used in connection with operation of the reactor.
(3) Pursuant to the Act and Title 10 CFR, Chapter I, Part 30, Rules of General Applicability to Licensing and Byproduct Material, and Part 70, to possess, but not separate, such byproduct material and special nuclear materials as may be produced by the operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I; Part 20, Section 30.34 of Part 30, Section 70.32 of Part 70, is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now, or hereafter, in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at steady-state power levels not in excess of 100 kilowatts (thermal).
(2) Technical Specifications The technical specifications contained in Appendix A, as revised through Amendment No. 27, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the technical specifications.
Amendment No. 27 November 17, 2015
(3) Deleted D. This amended license is effective as of the date of issuance and shall expire at midnight 20 years from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Cecil O. Thomas, Acting Chief Standardization & Special Projects Branch Division of Licensing
Enclosure:
Appendix A -
Technical Specifications Date of Issuance: AUG 30 1982 Amendment No. 27 November 17, 2015
LICENSE AMENDMENT NO. 27 AMENDED FACILITY OPERATING LICENSE NO. R-56 DOCKET NO. 50-83 Replace the following pages of Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Technical Specifications Remove Insert Page 27 Page 27 Page 28 Page 28 Page 34 Page 34 Page 35 Page 35 Attachment 2
generated heat to the environment. A deep well furnishes about 200 gpm of cooling water to the shell side of the heat exchanger, removing primary heat and rejecting it to the storm sewer. Weekly samples monitor the activity of this water. Flow indications in the control room are 140 gpm as a warning and 60 gpm to initiate a trip at or above 1 kW after a 10-sec warning. The city water secondary cooling system can be used for backup cooling or for specific operations requiring reactor coolant temperatures hotter than those obtained with the well cooling system. The secondary flow by the city water system is about 40 gpm, with a reactor trip set at 8 gpm (as measured by a flow switch) for power levels at or above 1 kW. A back flow preventer in the city water line ensures compliance with the requirements of the National Plumbing Code to prevent contamination of a potable water supply. The secondary coolant system inlet and outlet temperatures are monitored by thermocouples, with alarm and record functions in the control room.
- 5. 7 Radiological Safety Design Features 5.7.1 Physical Features The containment structure consists of the reactor cell, with a free air volume of about 1600 m3. This building houses the reactor, reactor control room, the primary cooling system (including the dump tank heat exchanger and purification loop), secondary coolant piping, and reactor vent system. Access to the reactor cell, which is the designated restricted and security area, is controlled by the specifications established by the security procedures of the UFTR.
Ventilation is through the independent air conditioning ventilation and reactor Vent system. The reactor vent system can be secured to prevent uncontrolled discharge of radioactivity to the environment or release in excess of permis-sible levels (per 10 CFR 20). Rough and absolute filters are used to eliminate or minimize radioactive air particulate contamination from the exhaust air.
The electrically actuated damper in the core exhaust line is fail-safe and closes upon deenergization.
5.7.2 Monitoring System Area and stack monitors are used for radioactivity monitoring, as delineated in Sections 3.3, 3.4, and 3.6 of these Technical Specifications. The cell air is monitored by an air particulate detector. Exhaust air drawing from the reactor cavity, reactor cell, or experiments is continuously monitored for gross concentrations of radioactive gases.
5.7.3 Evacuation Sequence The emergency evacuation sequence is initiated either automatically by two area monitors alarming high in coincidence or manually by the console operator. The sequence is that the reactor room air conditioning / ventilation system and the reactor vent system are shut down and the core vent damper is closed.
27 Amendment No. 27 November 17, 2015
5.8 Fuel Storage 5.8.1 New Fuel Unirradiated new fuel elements are stored in a vault-type room security area equipped with intrusion alarms in accordance with the security procedures. Elements are stored in a steel, fireproof safe in which a cadmium plate separates each layer of bundles to ensure subcriticality under optimum conditions of moderation and reflection.
5.8.2 Irradiated Fuel Irradiated fuel is stored upright in dry storage pits within the reactor build-ing in criticality-safe holes.
28 Amendment No. 27 November 17, 2015
individual immediately reponsible for the area, audit in the area. The following items shall be audited:
(a) facility operations for conformance to the technical specifications and applicable license or charter conditions, at least once per calendar year (interval between audits not to exceed 15 months)
(b) the retraining and requalification program for the operating staff, at least once every other calendar year (interval between audits not to exceed 30 months)
(c) the results of action taken to correct those deficiencies that may occur in the reactor facility equipment, systems, structures, or methods of operations that affect reactor safety, at least once per calendar year ( interval between audits not to exceed 15 months)
(d) the physical security procedures, emergency plan and implementing procedures, at least once every other calendar year (interval between audits not to exceed 30 months)
Deficiencies uncovered that affect the reactor safety shall immediately be reported to the Radiation Control Committee and the Dean of the College of Engineering. A written report of the findings of the audit shall be sub-mitted to the Dean of the College and the review and audit group members within 3 months after the audit has been completed.
6.3 Procedures The facility shall be operated and maintained in accordance with approved writ-ten procedures. All procedures and major revisions thereto shall be reviewed and approved by the Director of Nuclear Facilities before going into effect.
The following types of written procedures shall be maintained:
(1) normal startup, operation and shutdown procedures for the reactor (These procedures shall include applicable checkoff lists and instructions.)
(2) fuel loading, unloading, and movement in the reactor (3) procedures for handling irradiated and unirradiated fuel elements (4) routine maintenance of major components of the systems that could have an effect on reactor safety (5) surveillance tests and calibrations required by the required by the technical specifica-tions or those that may have an effect on reactor safety (6) personnel radiation protection, consistent with applicable regulations (7) administrative controls for operations and maintenance and for the conduct of irradiations and experiments that could affect reactor safety or core reactivity 34 Amendment No. 27 November 17, 2015
(8) implementation of the Emergency Plan and physical security procedures (9) procedures that delineate the operator action required in the event of specific malfunctions and emergencies (10) procedures for flooding conditions in the reactor facility, including guidance as to when the procedure is to be initiated and guidance on reactivity control Substantive changes to the above procedures shall be made effective only after documented review by the RSRS and approval by the facility director (Level 2) or designated alternates. Minor modifications to the original procedures which do not change their original intent may be made by the reactor manager (Level 3) or higher, but modifications must be approved by Level 2 or designated alternates within 14 days. Temporary deviations from the procedures may be made by the senior operating individual present, in order to deal with special or unusual circumstances or conditions. Such deviations shall be documented and reported to Level 2 or designated alternates.
6.4 Experiments Review and Approval (1) Experiments review and approval shall be conducted as specified under Section 3.5, Limitations on Experiments, of these Technical Specifica-tions.
(2) The experiments review and approval shall ensure compliance with the requirements of the license, Technical Specifications, and applicable regulations and shall be documented.
(3) Substantive changes to previously approved experiments with safety signi-ficance shall be made only after review by the RSRS, approval in writing by Level 2 or designated alternates. Minor changes that do not signifi-cantly alter the experiment may be approved by Level 3 or higher.
(4) Approved experiments shall be carried out in accordance with established approved procedures.
6.5 Required Actions 6.5.1 Action to be Taken in Case of Safety Limit Violation (1) The reactor shall be shut down, and reactor operations shall not be resumed until authorized by the Nuclear Regulatory Commission.
(2) The safety limit violation shall be promptly reported to Level 2 or desig-nated alternates.
(3) The safety limit violation shall be promptly reported to the Nuclear Regulatory Commission.
(4) A safety limit violation report shall be prepared. The report shall describe the following:
35 Amendment No. 27 November 17, 2015
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 27 TO FACILITY OPERATING LICENSE NO. R-56 UNIVERSITY OF FLORIDA DOCKET NO. 50-83
1.0 INTRODUCTION
By letter dated February 29, 2012, as supplemented on July 26, and August 31, 2012; September 3, 2014; April 7, and October 2, 2015, the University of Florida (the licensee) requested that the requirement to maintain and implement a physical security plan be deleted as a license condition since their possession limits for special nuclear material at the facility are less than an amount of special nuclear material considered to be of moderate strategic significance.
2.0 EVALUATION The definition of Special Nuclear Material of Low Strategic Significance (SNMLSS) is defined in Title 10 of the Code of Federal Regulations (10 CFR), Section 73.2 as:
(1) Less than an amount of special nuclear material of moderate strategic significance as defined in paragraph (1) of the definition of strategic nuclear material of moderate strategic significance in this section, but more than 15 grams of uranium-235 (contained in uranium enriched to 20 percent or more in U-235 isotope) or 15 grams of uranium-233 or 15 grams of plutonium or the combination of 15 grams when computed by the equation, grams = (grams contained U-235) + (grams plutonium) + (grams U-233); or (2) Less than 10,000 grams but more than 1,000 grams of uranium-235 (contained in uranium enriched to 10 percent or more but less than 20 percent in the U-235 isotope); or (3) 10,000 grams or more of uranium-235 (contained in uranium enriched above natural but less than 10 percent in the U-235 isotope).
This class of material is sometimes referred to as a Category III quantity of material Special nuclear material of moderate strategic significance is defined in, 10 CFR 73.2 as:
(1) Less than a formula quantity of strategic special nuclear material but more than 1,000 grams of uranium-235 (contained in uranium enriched to 20 percent or more in the U-235 isotope) or more than 500 grams of uranium-233 or plutonium, or in a combined quantity of more than 1,000 grams when computed by the equation, grams
= (grams contained U-235) + 2 (grams U-233 + grams plutonium); or Enclosure 2
(2) 10,000 grams or more of uranium-235 (contained in uranium enriched to 10 percent or more but less than 20 percent in the U-235 isotope).
This class of material is sometimes referred to as a Category II quantity of material.
The licensee is authorized to possess 0.2 kilograms of any enrichment U-235, and 5.0 kilograms of U-235 enriched to less than 20 percent. Therefore, the license possession limits for special nuclear material fall within the limits defined for SNMLSS. The physical security requirements for SNMLSS of 10 CFR 73.67(f) do not require a physical security plan. However, security procedures are required.
In the licensees response to a request for additional information (RAI) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15300A060), the licensee provided analytical evidence indicating the aggregate quantity of special nuclear material will remain well below the amount considered to be of moderate strategic significance for all times in facility life. The UFTR estimate for the aggregate special nuclear material quantities for the facility end-of-life condition were provided in the licensees depletion calculations performed using the Monte Carlo N-Particle Transport Code (MCNP).
The NRC staff reviewed the results and assumptions of the licensees response to the RAI and finds that the quantity of special nuclear material resulting from operation of the UFTR reactor to end of life will remain below the existing UFTR possession limits imposed by license condition and below the threshold for SNMLSS defined in 10 CFR Part 73 for all times in the facilitys life.
The proposed security procedures are in compliance with the applicable regulations contained in 10 CFR Part 73, Regulatory Guide 5.59, and site specific security measures committed to per a Confirmatory Action Letter dated August 30, 2004 (ADAMS Accession No. ML033250506).
The revised technical specifications (TSs) will reflect that the licensee is allowed to operate the reactor with security procedures. The four affected sections of the current specifications related to security plans and the proposed revisions to the TS to reflect security procedures are as follows:
Current TS 5.7.1 states in part:
5.7.1 Physical Features Access to the reactor cell, which is the designated restricted and security area, is controlled by the specifications established by the security plan of the UFTR.
The licensee has proposed revising this part of TS 5.7.1 to read as follows:
5.7.1 Physical Features Access to the reactor cell, which is the designated restricted and security area, is controlled by the specifications established by the security procedures of the UFTR.
Current TS 5.8.1 states in part:
5.8.1 New Fuel
Unirradiated new fuel elements are stored in a vault-type room security area equipped with intrusion alarms in accordance with the Security Plan.
The licensee has proposed revising this part of TS 5.8.1 to read as follows:
5.8.1 New Fuel Unirradiated new fuel elements are stored in a vault-type room security area equipped with intrusion alarms in accordance with the security procedures.
Current TS 6.2.5 (4)(d) states in part:
6.2.5 Review and Audit (4) Audit Functions (d) the reactor facility emergency plan, and implementing procedures at least once every other calendar year (interval between audits not to exceed 30 months)
The licensee has proposed revising this part of TS 6.2.5 to read as follows:
6.2.5 Review and Audit (4) Audit Functions (d) the physical security procedures, emergency plan and implementing procedures, at least once every other calendar year (interval between audits not to exceed 30 months)
Current TS 6.3 states in part:
6.3 Procedures (8) implementation of the Emergency Plan The licensee has proposed revising this part of TS 6.3 to read as follows:
6.3 Procedures (8) implementation of the Emergency Plan and physical security procedures The licensee acknowledged their responsibility in their amendment application that they must meet the security requirements of 10 CFR 73.67(f) to: "(1) Store or use the material only within a controlled access area, (2) Monitor with an intrusion alarm or other device or procedures the controlled access areas to detect unauthorized penetrations or activities, (3) Assure that a watchman or offsite response force will respond to all unauthorized penetrations or activities, and (4) Establish and maintain response procedures for dealing with threats of thefts or thefts of this material. The licensee shall retain a copy of the current response procedures as a record
for three years after the close of period for which the licensee possesses the special nuclear material under each license for which the procedures were established. Copies of superseded material must be retained for three years after each change."
The licensee made a change to remove a footnote in the proposed TS replacement page in their application for license amendment. However, the application did not discuss the change.
In a phone call on April 10, 2012, between D. Hardesty, the U.S. Nuclear Regulatory Commission (NRC) UFTR Project Manager and B. Shea, UFTR Reactor Manager, the licensee explained that the footnote on page 27 of the UFTR TS was an outdated reference to 10 CFR 2.790 and no longer relevant.
There was a typographical error in the initial TS replacement pages submitted by the licensee.
This was discussed during a phone conference between B.Shea, UFTR Reactor Manager, and the NRC UFTR project manager on April 10, 2012. A corrected TS page was submitted by the licensee to correct the typographical error misspelling continuously.
Two other research reactors have had the requirements for physical security plans deleted. To date, experience has shown no safety or security concerns related to this deletion of the requirement for a physical security plan. Based on the above, the NRC staff finds the licensees request to replace the security plan with security procedures acceptable.
Additionally, the footnote removal and corrected spelling proposed by the licensee was evaluated and found acceptable. Since the proposed changes to the TSs are administrative in nature and results in the TSs being consistent with the intent of Amendment No. 27 to replace the security plan with security procedures, the changes to the TSs are acceptable to the NRC staff.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves changes in recordkeeping, reporting, or administrative procedures or requirements and the amendment, relating solely to safeguards matters, is organizational and procedural and involves administrative changes. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10) and 10 CFR 51.22(c)(12), respectively. Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed activities, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or the health and safety of the public.
Principal Contributors: Duane Hardesty Elizabeth Reed Date: November 17, 2015