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| | number = ML20204D532 | | | number = ML20204D532 |
| | issue date = 12/19/1978 | | | issue date = 12/19/1978 |
| | title = Safety Eval Supporting Amend#12 to Facil Lic#R-66.Concludes Issuance of Amend Will Not Be Inimical to Public or National Interests | | | title = Safety Eval Supporting Amend 12 to Facil Lic R-66.Concludes Issuance of Amend Will Not Be Inimical to Public or National Interests |
| | author name = | | | author name = |
| | author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20198J2431998-12-21021 December 1998 Safety Evaluation Supporting Amend 24 to License R-66 ML20236K4861998-07-0707 July 1998 Safety Evaluation Supporting Amend 8 to License R-123 ML20249A5961998-06-15015 June 1998 Safety Evaluation Supporting Amend 23 to License R-66 ML20059E8991990-08-29029 August 1990 Safety Evaluation Supporting Amends 19 & 7 to Licenses R-66 & R-123,respectively ML20247H2391989-07-20020 July 1989 Safety Evaluation Supporting Amends 18 & 6 to Licenses R-66 & R-123,respectively ML20246L8071989-03-15015 March 1989 Safety Evaluation Supporting Amend 5 to License R-123 ML20151U0821988-04-25025 April 1988 Safety Evaluation Supporting Amend 16 to License R-66 ML20204D5321978-12-19019 December 1978 Safety Eval Supporting Amend 12 to Facil Lic R-66.Concludes Issuance of Amend Will Not Be Inimical to Public or National Interests 1998-07-07
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20204G5541998-12-31031 December 1998 Univ of Virginia Reactor Facility 1998 Annual Rept ML20198J2431998-12-21021 December 1998 Safety Evaluation Supporting Amend 24 to License R-66 ML20236Y4511998-07-31031 July 1998 Revised Operator Requalification Program ML20236K4861998-07-0707 July 1998 Safety Evaluation Supporting Amend 8 to License R-123 ML20249A5961998-06-15015 June 1998 Safety Evaluation Supporting Amend 23 to License R-66 ML20217G6391997-12-31031 December 1997 Univ of Virginia Reactor Facility Annual Rept,1997 ML20137B3471996-12-31031 December 1996 Univ of VA Reactor Facility Annual Rept for 1996 ML20138H1171996-11-19019 November 1996 Univ of Virginia Nuclear Reactor Facility 1996 Emergency Preparedness Exercise Scenario for 961119 ML20101E0311995-12-31031 December 1995 Univ of VA Reactor Facility 1995 Annual Rept ML20093L1171995-10-31031 October 1995 Revised Sar,Incorporating Proposed Section 9.20.8 ML20093C7501995-10-31031 October 1995 SAR for Low-Enriched U Fueled Univ of VA Reactor ML20095F3031995-10-10010 October 1995 Univ of VA Nuclear Reactor Facility 1995 Emergency Preparedness Drill Scenario for 951108 ML20081K4961994-12-31031 December 1994 Univ of VA Reactor Facility 1994 Annual Rept ML20077C3881994-10-18018 October 1994 Univ of VA Nuclear Reactor Facility 1994 Emergency Preparedness Drill Scenario for 941122 ML20076F9091994-10-13013 October 1994 HEU to LEU Conversion Rept ML20072R0081994-08-26026 August 1994 Part 21 Rept Re Area Monitoring Sys Consisting of Model Adm 600A(V10) Readout Module & GP-100C Geiger-Muller Detector Supplied by Nuclear Research Corp.Replacement Circuit Card Assemblies Provided to Univ of VA ML20071L8551994-07-28028 July 1994 Part 21 Rept Re Defect in Basic Component Purchased from Nuclear Research Corp.Rest of Ltr Follows Listing of Required Topics as Stated in Paragraph 21.21 Section 4 ML20070B4721994-06-21021 June 1994 Ro:On 940617,during pre-start Checks for Gas Cooled Mineral Irradiation Facility Checklist,Discovered That Experiment Scram Bypass Switch Position Check Had Not Been Performed Correctly for 3 Days.Caused by Supervisor Error ML20064N4511993-12-31031 December 1993 University of VA Reactor Facility 1993 Annual Rept ML20044H0671993-05-26026 May 1993 Ro:On 930428,inadvertent Mod to Reactor Console Resulted in Operation of Reactor for Period of About Five & One Half H W/Several Protective Scrams,Per TS Not Operable.Minor & temporary,non-safety Sys Related Changes Recommended ML20044D7311993-05-12012 May 1993 Fourteen-Day Rept of Reportable Event Re Inadvertent Mod of Univ of Virginia Reactor Console. ML20101N5941992-07-0101 July 1992 Special Rept:On 920615,briefly Unidentified High Radiation Area Noted During Reactor Startup.Caused by Human Error. Self-critical Evaluation Conducted & Controls in Place to Prevent Reccurrence ML20097E0431992-06-0404 June 1992 Proposed Operator Requalification Program for Univ of Virginia Reactor Facility ML20094M4301991-12-31031 December 1991 Univ of Virginia Reactor Facility Annual Rept,1991. W/ ML20070R6011990-12-31031 December 1990 Univ of Virginia Reactor Facility 1990 Annual Rept. W/ ML20059E8991990-08-29029 August 1990 Safety Evaluation Supporting Amends 19 & 7 to Licenses R-66 & R-123,respectively ML20012B0741990-02-28028 February 1990 Decommissioning Plan for Univ of Virginia 100-Watt Cavalier Reactor & Application for Termination of Ol. ML19327C1561990-01-31031 January 1990 Effective Diffusion Theory Cross Sections for Univ of Virginia Control Rods. ML20042D7581989-12-31031 December 1989 Univ of Virginia Reactor Facility Annual Rept 1989. W/ 900307 Ltr ML19327C1531989-11-30030 November 1989 SAR for Low Enriched U Fueled,Univ of Virginia Reactor. ML19327C1551989-07-31031 July 1989 Neutronic Analysis for Univ of Virginia Reactor High Enrichment U to Low Enrichment U Conversion Project. ML20247H2391989-07-20020 July 1989 Safety Evaluation Supporting Amends 18 & 6 to Licenses R-66 & R-123,respectively ML20246L8071989-03-15015 March 1989 Safety Evaluation Supporting Amend 5 to License R-123 ML19327C1541989-01-31031 January 1989 Design Optimization of Low Enrichment,Univ of Virginia Nuclear Reactor. ML20247G8351988-12-31031 December 1988 Univ of Virginia Reactor Facility Annual Rept 1988 ML20151U0821988-04-25025 April 1988 Safety Evaluation Supporting Amend 16 to License R-66 ML20148N6491988-03-31031 March 1988 Proposal for Conversion of Univ of VA Nonpower 2 Mwt Univ of VA Research Reactor from Highly Enriched U to Low Enriched U Fuel ML20148D7991987-12-31031 December 1987 Reactor Facility Annual Rept 1987 ML20137K8611986-01-13013 January 1986 Annual Operating Rept for 1985 ML20129F2401985-05-31031 May 1985 Safety Evaluation Report Related to the Renewal of the Operating License for the CAVALIER Training Reactor at the University of Virginia.Docket No. 50-396.(University of Virginia) ML20106H0141985-01-24024 January 1985 Annual Rept of Operations of Univ of Virginia Reactor & CAVALIER Reactor During 1984 ML20137E2941984-12-31031 December 1984 Addendum to 1984 Annual Rept ML20108B8341984-11-0101 November 1984 Ro:On 841002,high Radiation Hot Spot Discovered at Ground Level Along Outside Wall of Reactor Room.Caused by Experiment.Personnel Removed Radiation Source & Relocated Shield Cask.Program Revised ML20092M2891984-06-22022 June 1984 Updated SAR in Support of License R-123 Renewal ML20086S1681984-02-16016 February 1984 Annual Operating Rept for 1983 ML20024C0461983-06-30030 June 1983 Updated RO Re 830525 Low Shutdown Margin During Criticality. Initially Reported on 830609.Caused by Change in Control Rod Reactivity Worth Curves Due to Fuel Burnup.Procedures for Shutdown Margin & Reactivity Worth Determination Rewritten ML20076F3341983-06-0909 June 1983 Ro:On 830530,reactor Shut Down When Shutdown Margin During Criticality Violated Tech Specs.Caused by Difference in Partial Fuel Element Added on 830525.Reactor Shut Down 830606.Control Rods Recalibr.Procedures Changed ML20070P0581983-01-0505 January 1983 Annual Rept of Operations,1982 ML20041F4651982-03-11011 March 1982 QA Program for Procurement,Use,Maint & Repair of Packaging Used to Transport Spent Fuel,Radioactive Matl & Pu ML20038B2591981-08-26026 August 1981 Univ of VA Reactor (Uvar). 1998-07-07
[Table view] |
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O 1 jh UNITED STATES y *g NUCLEAR REGULATORY COMMIS$10N wAsmwarow, o. c. noses
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPp0RTING AMENDMENT NO. 12 TO FACILITY LICENSE NO. R-66 UNIVERSITY OF VIRGINIA DOCKET NO. 50-62 Introduction By letter dated July 14, 1978, the University of Virginia (the Licensee) requested an amendment-to Facility License No. R-66.
The amendment would change a requirement in the Technical Specifications for the University nf Virginia . pool-type nuclear reactor relating to the surveillance of safety rods. Subsequently, through di rissions with University of Virginia personnel, they agreed to the following revision to their proposed amendment.
Discussion and Evaluation The current Technical Specifications require that the safety rods be visually inspected at intervals not to exceed 13 months, or intervals
- of 50 megawatt-days, whichever comes first. The proposed amendment would delete the requirement to visually inspect the safety rods at. ;
iqtervalt,of 50 megawatt days, and replace it with a requirement to 1 inspect the rods whenever the rod drop times exceed the limit.ing .
condition of operation specification of 700 milliseconds.
The requirement to inspect the safety rods whenever the rod drop times-tests conducted every five months exceed the 700 millisecond specification provides a more valid use inspection criteria than one based on megawatt days of operation. In addition to the rod drop and 13 month visual .
inspection surveillance requirements, the licensee's operating procedures ensure the rods are capable of proper perfonnance by conducting scram l tests of each safety rod prior to all reactor start ups. Therefore, the l 13 month visual inspection interval, the new requirement to inspect when- I ever the rod drop times are exceeded and the requirement to scram each safety rod prior to start up; provides adequate assurance that the safety rods are capable of proper perfonnance.
s.
A review by. the licensee of the surveillance records covering the last 17 years and-275 megawatt days of operation has shown from the yearly visual inspection of the safety rods, that there has been no evidence of deterior-ation, swelling, or cracking. Review of the five-monthly rod drop time tests 78122900/o s .
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, I also has shown no degradation in perfonnance. This further substantiates the premise that the aforementioned visual inspection frequency and rod drop time tests will assure safety rod performance I capability.
The visual inspection requires that each rod be physically removed from j the guide tube and lowered into the reactor pool where it is inspected i under several feet of water. During the period the rod is being removed i from the guide tube and prior to being lowered in the water, operating ,
.ersonnel are exposed to radiation from the rod. In the past, radiation l have b 150-200 REM /hr at contact. s 1evels have been from the rodlimit taken.to thkensexposureto0.01 Man-RemperkrecINbn.
nsp If a visual inspection were required at 50 megawatt days during the 70 megawatt day experiments, previous precautions of allowing short-lived activity to decay prior to inspecting would be eliminated in order to meet experiment requirements. Therefore, as the aforementioned inspection frequencies are considered adequate, it would be incongruous to conduct an inspection that does not add to the margin of safety but increases exposure to inspectors. With the inspection frequencies as proposed by this amendment, the exposure to inspectors would be maintained at or below the 0.01 Man-Rem currently experienced per inspection. In no case .
would the exposure levels exceed the maximum permissible dose prescribed by 10 CFR Part 20.
Therefore, we find that the proposed deletion of. the requirement to visually inspect safety rods at 50 megawatt intervals and replacing it with the requirement to visually inspect the rods whenever the rod drop times exceed the limiting conditions for operation would not reduce the margin of safety, would reduce the frequency of exposure to a minimum and is acceptable.
Environmental Consideration We have determined that the amendmentwill not result in any significant environmental impact and that it does not constitute a major Consnission action significantly affecting the> quality of the human environment. We have also determined that this action is not one of those covered by 10 CFR E 51.5 (a) or (b). Having made these detenninations, we have further concluded, that pursuant to 10 CFR 5 51.5 (d) (4), that an environmental impact statement, or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
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Conclusion .
We have concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's' regulations and the issuance of this amendment will not be inimical t to the common defense and security or to the health and safety of ,
the public. ~
j Dated: December 19, 1978 1
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