ML113350316
| ML113350316 | |
| Person / Time | |
|---|---|
| Site: | University of Utah |
| Issue date: | 12/12/2011 |
| From: | Wertz G A Research and Test Reactors Licensing Branch |
| To: | Jevremovic T Univ of Utah |
| Wertz, Geoffrey; NRR/DPR/434-326-1086 | |
| References | |
| TAC ME7554 | |
| Download: ML113350316 (12) | |
Text
December 12, 2011 Dr. Tatjana Jevremovic Director, Utah Nuclear Engineering Program Joseph Merrill Engineering Building 50 Central Campus Drive, Room 2298 University of Utah Salt Lake City, UT 84112
SUBJECT:
UNIVERSITY OF UTAH - ISSUANCE OF AMENDMENT NO. 9 TO FACILITY OPERATING LICENSE NO. R-126, RE: TECHNICAL SPECIFICATIONS 3.5 AND 4.4 (TAC NO. ME7554)
Dear Dr. Jevremovic:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 9 to Facility Operating License No. R-126 for the University of Utah TRIGA Reactor. The amendment consists of changes to the technical specifications (TSs) in response to your application dated November 17, 2011, as supplemented on November 29, 2011. The amendment changes the TS value of the pressure difference between the reactor room and the outside of the Merrill Engineering Building. The safety evaluation supporting Amendment No. 9 is enclosed.
Sincerely,
/RA/ Geoffrey A. Wertz, Project Manager Research and Test Reactors Licensing Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-407
Enclosures:
- 1. Amendment No. 9 2. Safety Evaluation cc w/encls: See next page University of Utah Docket No. 50-407 cc: Mayor of Salt Lake City 451 South State Room 306 Salt Lake City, UT 84111 Dr. Thomas Parks Vice President for Research 201 S. Presidents Circle, Room 210 University of Utah Salt Lake City, UT 84112 Ms. Karen Langley Director, University of Utah Radiological Health 100 OSH, University of Utah Salt Lake City, UT 84112 Dr. Cynthia Furse Associate Vice President for Research 201 President's Circle, Room 210 University of Utah Salt Lake City, UT 84112 Test, Research, and Training Reactor Newsletter Universities of Florida 202 Nuclear Sciences Center Gainesville, FL 32611 Director, Division of Radiation Control Dept. Of Environmental quality 168 North 1959 West P.O. Box 144850 Salt Lake City, UT 84114-4850 December 12, 2011 Dr. Tatjana Jevremovic Director, Utah Nuclear Engineering Program Joseph Merrill Engineering Building 50 Central Campus Drive, Room 2298 University of Utah Salt Lake City, UT 84112
SUBJECT:
UNIVERSITY OF UTAH - ISSUANCE OF AMENDMENT NO. 9 TO FACILITY OPERATING LICENSE NO. R-126, RE: TECHNICAL SPECIFICATIONS 3.5 AND 4.4 (TAC NO. ME7554)
Dear Dr. Jevremovic:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 1 to Facility Operating License No. R-126 for the University of Utah TRIGA Reactor. The amendment consists of changes to the technical specifications (TSs) in response to your application dated November 17, 2011, as supplemented on November 29, 2011. The amendment changes the TS value of the pressure difference between the reactor room and the outside of the Merrill Engineering Building. The safety evaluation supporting Amendment No. 9 is enclosed. Sincerely, /RA/ Geoffrey A. Wertz, Project Manager Research and Test Reactors Licensing Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-407
Enclosures:
1. Amendment No. 9 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION: Public RidsNrrDpr RidsNrrDprPrta CBassett, NRR RTR r/f RidsNrrDprPrtb RidsOgcRp GWertz, NRR GLappert, NRR
ADAMS Accession No: ML113350316 *concurrence via e-mail NRR-058 OFFICE PRLB:PM* PRPB:LA OGC PRLB:BC PRLB:PM NAME GWertz GLappert, CMH forBMizuno, NLOJQuichocho GWertz DATE 12/1/2011 12/1/2011 12/5/2011 12/9/2011 12/12/2011 OFFICIAL RECORD COPY UNIVERSITY OF UTAH DOCKET NO. 50-407 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9 License No. R-126 1. The U.S. Nuclear Regulatory Commission ("the Commission") has found that: A. The application for amendment to Facility Operating License No. R-126 filed by the University of Utah ("the licensee"), dated November 17, 2011, as supplemented on November 29, 2011, conforms to the standards and requirements of the Atomic Energy Act of 1954, as amended ("the Act"), and the Commission's rules and regulations set forth in Title 10, Chapter I, 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) that such activities will be conducted in compliance with the Commission's 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. This amendment is issued in accordance with the regulations of the Commission as stated in 10 CFR Part 51, and all applicable requirements have been satisfied; and; F. Prior notice of this amendment was not required by 10 CFR 2.105 and publication of a notice for this amendment is not required by 10 CFR 2.106.
2. 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) of Facility Operating License No. R-126 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised by Amendment No. 9, are hereby incorporated in the license. The licensee shall operate the reactor in accordance with these Technical Specifications. 3. This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION /RA/ Jessie F. Quichocho, Chief Research and Test Reactors Licensing Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
Enclosure:
Changes to Facility Operating License and Technical Specifications Date of Issuance: December 12, 2011 UNIVERSITY OF UTAH FACILITY OPERATING LICENSE NO. R-126 DOCKET NO. 50-407 AMENDMENT TO LICENSE OPERATING LICENSE Replace the following pages of the Facility Operating License No. R-126, and 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. Facility Operating License Remove Insert Page 3 Page 3 Technical Specifications Page 26 Page 26 Page 42 Page 42 Amendment No. 9 December 12, 2011 a. to receive, possess, and use in connection with operation of the facility, up to 240 grams of plutonium in the form of a plutonium-beryllium neutron source; and b. to receive, possess, use, but not separate, in connection with operation of the facility, such special nuclear material as may be produced by the operation of the facility. (2) Pursuant to the Act and 10 CFR Part 30, to receive, possess, and use, in connection with operation of the facility, such byproduct material as may be produced by operation of the reactor, which cannot be separated except for byproduct material produced in non-fueled experiments. B. This license shall be deemed to contain and is subject to the conditions specified in 10 CFR Parts 20, 30, 50, 51, 55, 70 and 73 of the Commission's regulations; 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 a steady-state power level not in excess of 100 kilowatts (thermal) as specified in the Technical Specifications. (2) Technical Specification The Technical Specifications contained in Appendix A, as revised through Amendment No. 9, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. (3) Physical Security Plan The licensee shall fully implement and maintain in effect all provisions of the physical security plan approved by the Commission and all amendments and changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p), respectively. The approved plan, which is exempt from public disclosure pursuant to the provisions of 10 CFR 73.21, is entitled, "University of Utah Physical Security Plan for the Protection of SNM of Low Strategic Significance under Licenses R-25 and R-126," Revision 1, dated July 28, 1980.
UUTR TECHNICAL SPECIFICATIONS AND BASES Page 26 Amendment No. 9 December 12, 2011 3.5 Ventilation System Applicability This specification applies to the operation of the reactor area ventilation system. Objective The objective is to assure that the ventilation system shall be in operation to mitigate the consequences of possible releases of radioactive materials resulting from reactor operation.
Specifications The reactor shall not be operated unless the ventilation system is fully operable which is when: 1. The pressure difference between the reactor room and outside of the Merrill Engineering Building is larger than 0.01 inches-of-water. 2. In the event of a substantial release of airborne radioactivity within the reactor area, the ventilation system will be secured or operated in the limited intake mode to prevent the release of a significant quantity of airborne radioactivity from the reactor area. Basis In the operational mode of the ventilation system, the air in the controlled access area (reactor room area) is constantly being exchanged. The air leaving the facility has a volumetric flow rate of more than 100 CFM per each of the two fume hoods. The result of this is a negative pressure of greater than 0.01 inches of water in the reactor room. The worst-case maximum total effective dose equivalent is well below the applicable annual limit for individual members of the public and building residents during the maximum hypothetical accident (MHA) (SAR 13.2.1).
UUTR TECHNICAL SPECIFICATIONS AND BASES Page 42 Amendment No. 9 December 12, 2011 4.4 Confinement Applicability This specification applies to the reactor confinement.
Objective The objective is to assure that air is swept out of confinement and exhausted through a monitored release point (two fume hood systems located at Fuel Inspection area).
Specification The ventilation system shall be verified operable in accordance with TS 4.5 monthly.
Basis Because the ventilation system is the only equipment required to achieve confinement, operability checks of the ventilation system meet the functional testing requirements for confinement. The pressure difference between the reactor room and outside of the Merrill Engineering Building should be larger than 0.01 inches-of-water. To keep this pressure difference, two fume hoods should be operated with the flow rate of 90 CFM or higher.
Current flow rate for two fume hoods are >100 CFM.
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 9 TO FACILITY OPERATING LICENSE NO. R-126 UNIVERSITY OF UTAH DOCKET NO. 50-407
1.0 INTRODUCTION
By letter dated November 17, 2011, as supplemented on November 29, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML11326A171 and ML11342A053, respectively), the University of Utah (the licensee) submitted to the U.S. Nuclear Regulatory Commission (NRC) a request for amendment to the Technical Specifications (TSs) in Appendix A, to Facility Operating License No. R-126, for the University of Utah TRIGA (Training, Research, Isotopes, General Atomics) Reactor (UUTR). The requested amendment would correct a typographical error in the TSs associated with the value for the pressure difference between the reactor facility and the Merrill Engineering Building.
2.0 EVALUATION The UUTR is a 100 kilowatt thermal power steady state operation pool-type research reactor, housed within the Merrill Engineering Building located on the University of Utah campus in Salt Lake City, Utah. The UUTR Facility Operating License, R-126, was renewed on October 31, 2011 (ADAMS Accession No. ML112500321) and the renewal license included the issuance of updated TSs (ADAMS Accession No. ML112500333). By letter dated November 17, 2011, as supplemented on November 29, 2011, the licensee indicated that UUTR TS 3.5, "Ventilation System," and the Basis in UUTR TS 4.4 "Confinement," contained a typographical error with respect to the value provided for the pressure difference between the reactor facility and the Merrill Engineering Building. The licensee indicated in their letter that the TS value of 0.1 inches-of-water was incorrectly stated and that the correct value should be 0.01 inches-of-water. The licensee has requested that the TS value of 0.1 inches-of-water be replaced with 0.01 inches-of-water in UUTR TS 3.5 and in the Basis of UUTR TS 4.4. Furthermore, the licensee stated that the UUTR Updated Safety Analysis Report (SAR) (ADAMS Accession No. ML111720666) provide a description of the UUTR Ventilation System in Section 9.1.4.1, in which the pressure difference was correctly specified as 0.01 inches-of-water.
The current UUTR TS 3.5, Specification 1, states the following: 1. The pressure difference between the reactor room and outside of the Merrill Engineering Building is larger than 0.1 inches-of-water. Similarly, the current Basis of UUTR TS 4.4, states the following: Because the ventilation system is the only equipment required to achieve confinement, operability checks of the ventilation system meet the functional testing requirements for confinement. The pressure difference between the reactor room and outside of the Merrill Engineering Building should be larger than 0.1 inches-of-water. To keep this pressure difference, two fume hoods should be operated with the flow rate of 90 CFM or higher. Current flow rate for two fume hoods are >100 CFM. In the licensee's letter dated November 17, 2011, as supplemented on November 29, 2011, the licensee has requested that the 0.1 inches-of-water pressure difference value be changed to 0.01 inches-of-water, and that the proposed UUTR TSs read as follows: UUTR TS 3.5, Specification 1: 1. The pressure difference between the reactor room and outside of the Merrill Engineering Building is larger than 0.01 inches-of-water. UUTR TS 4.4, Basis: Because the ventilation system is the only equipment required to achieve confinement, operability checks of the ventilation system meet the functional testing requirements for confinement. The pressure difference between the reactor room and outside of the Merrill Engineering Building should be larger than 0.01 inches-of-water. To keep this pressure difference, two fume hoods should be operated with the flow rate of 90 CFM or higher. Current flow rate for two fume hoods are >100 CFM. The NRC staff discussed the circumstances surrounding the amendment request with the licensee during a telephone call conducted on November 10, 2011, and reviewed the information provided in the licensee's amendment request. The NRC staff reviewed the description of the ventilation system provided in the UUTR Updated SAR and noted that the UUTR Updated SAR Section 9.1.4.1 provided the value of 0.01 inches-of-water, which was consistent with the licensee's requested TS change. The NRC staff also reviewed the results of the licensee's Maximum Hypothetical Accident (MHA) described in the UUTR SAR, Chapter 13, "Accident Analyses." The radiological doses associated with the MHA were analyzed with the ventilation system in the normal operational mode (elevated release) and with that the ventilation system shutdown (ground level release).
The MHA doses to members of the public located outside the Merrill Engineering Building met the requirements of 10 CFR Part 20 in both cases with the ventilation system operating and shutdown. Additionally, there are no specific assumptions provided in the SAR MHA analysis for the pressure difference between the reactor facility and outside the Merrill Engineering Building. The ventilation system is either operating in the normal mode, or it is shutdown. Therefore, based on the pressure difference value provided in the UUTR Updated SAR, Section 9.1.4.1, and a review of the results of the UUTR MHA analysis as provided in the UUTR Updated SAR, the NRC staff concluded that a value of 0.01 inches-of-water was the correct TS value to establish the operability of the ventilation system and should be the value specified in UUTR TSs 3.5 and the Basis for UUTR TS 4.4.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment involves changes in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or changes in inspection and surveillance requirements. The NRC staff has determined that this amendment involves no significant hazards consideration, no significant increase in the amounts, and no significant change in the types, of any effluents that may be released off site, and no significant increase in individual or cumulative occupational radiation exposure. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c) (9). 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.
5.0 CONCLUSION
The NRC staff concludes, on the basis of the considerations discussed above, that (1) the amendment does not involve a significant hazards consideration because the amendment does not involve a significant increase in the probability or consequences of accidents previously evaluated, create the possibility of a new kind of accident or a different kind of accident from any accident previously evaluated, or involve a significant reduction in a margin of safety; (2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed activities; and (3) 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 Contributor: G. Wertz, NRR Dated: December 12, 2011