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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20147H3871997-03-31031 March 1997 Safety Evaluation Supporting Amend 8 to License TR-5 ML20195B3931988-06-10010 June 1988 Safety Evaluation Supporting Amend 6 to License TR-5 1997-03-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20205B0511998-12-31031 December 1998 Operations Rept 51 for Jan-Dec 1998. with ML20217H4481997-12-31031 December 1997 Operations Rept 50 for Jan-Dec 1997 ML20147H3871997-03-31031 March 1997 Safety Evaluation Supporting Amend 8 to License TR-5 ML20137F2891996-12-31031 December 1996 Operations Rept 49 for Jan-Dec 1996 ML20101K9901995-12-31031 December 1995 Operations Rept 48,for 1995 ML20082B0421994-12-31031 December 1994 NIST Reactor Operations Rept 47 for Jan-Dec 1994 ML20064L2101993-12-31031 December 1993 NIST Reactor (Nbsr) Operations Rept 46 Jan-Dec 1993. W/ ML20057C4221993-09-22022 September 1993 Ro:On 930910,noticed Fluctuations on Power Channels Due to Element 574 in Position J-7 Becoming Unlatched for Listed Reasons.Subj Element Replaced.Special Instructions Will Be Provided to Operators on Fuel Handling & Monitoring ML20114D7111992-09-0202 September 1992 Ro:On 920824,several Annunicators Re Reactor in Manual, Servo Deviation Greater than 10% & Clutch Power Off Received.Caused by Shim 3 Slipping & Clutch Current on Low Alarm.Potentiometer Wiped Clean & Current Adjusted ML20094P1721991-12-31031 December 1991 Natl Inst of Stds & Technology Reactor Operations Rept, 1991 ML20070T4301990-12-31031 December 1990 Operations Rept 43 for Natl Inst of Stds & Technology Reactor for 900101-1231 ML20059M1491990-09-25025 September 1990 Special Rept,On 900918:shim 1 Relay Failed to Release Completely Upon Manual Scram.Caused by mercury-wetted- Contact Relay in Manual Scram Circuit of Shim.Relay Replaced & Relays in Sys Checked & Found to Operate Normally ML20043A4791990-05-15015 May 1990 Ro:On 900505,leak Discovered in Cooling Water Basin Steam Lines.Caused by Increasing Tritium Levels in Hx.Permanent Plug Installed in Steam Line ML20248J1901988-12-31031 December 1988 Operations Rept 41 for 1988 ML20195B3931988-06-10010 June 1988 Safety Evaluation Supporting Amend 6 to License TR-5 ML20151U3541987-12-31031 December 1987 Corrected Operations Rept 40,1987 ML20148N6081987-12-31031 December 1987 Operations Rept 40,Jan-Dec 1987 ML20235M4711987-09-23023 September 1987 Ro:On 870911,while Performing Shim Arm Calibr Tests at Low Power,Shim 1 Would Not Drive Out But Would Drive In.Caused by Worn Thrust Bearings on Drive.Drive Reinstalled & Tested Satisfactorily ML20237J2201987-02-28028 February 1987 Penetrations in Reactor Bldg for New Hot Plug Storage,Hx Vault & Neutron Beam Tubes, Study Rept ML20206D7691986-12-31031 December 1986 Operations Rept 39,1986 ML20202D3001985-12-31031 December 1985 Operations Rept 38,1985 ML20116H5891984-12-31031 December 1984 Operations Rept 37,1984 ML20098G3611984-08-31031 August 1984 SAR on D2O Cold Neutron Source for Nbs Reactor ML20087N6121984-03-29029 March 1984 Ro:On 840319,following Shim Arm Calibr Test,Shift Arm 1 Did Not Fall.Cause Unknown.New Ball Nut & Screw Assembly Installed ML20087N5901983-12-31031 December 1983 Semiannual Operating Rept 36,Jul-Dec 1983 ML20080K4781983-09-0808 September 1983 Operations Rept,Jan-June 1983 ML20072L3421983-03-18018 March 1983 Operations Rept 34,Jul-Dec 1982 ML20067D9391982-12-0606 December 1982 Ro:On 821126,during Routine Refueling Operations,Fuel Element 345 Fell to Upper Grid in Transfer from Core Position D-1 to D-7.Caused by Operating Difficulty in E-2 Transfer Arm.Element Removed & Seated ML20063P1801982-09-30030 September 1982 Operations Rept 33,Jan-June 1982 ML20050B5401982-03-30030 March 1982 Semiannual Operating Rept,Jul-Dec,1981. ML20010G1941981-09-10010 September 1981 Semiannual Operating Rept for Jan-June 1981 ML20038B2531981-08-26026 August 1981 Natl Bureau of Stds Reactor. ML20009H0111981-07-28028 July 1981 Ro:On 810717,no Deuterium Oxide Level Indication Discovered. Caused by Substance Draining Into Storage Tank Due to Failure of Valve DWV-39 to Close.Revised Procedures Instituted to Upgrade Insp Requirements ML19343C4501981-03-20020 March 1981 Operations Rept 30 for Jul-Dec 1980. ML19347B2911980-09-26026 September 1980 Semiannual Operating Rept,Jan-June 1980. ML19340E2031980-04-0808 April 1980 Semiannual Operating Rept 28,Jul-Dec 1979. ML20125D0401979-10-26026 October 1979 Rept on Nature & Source of Radioactive Matl Found at Nbs Reactor Site ML19208D5251979-09-28028 September 1979 Operations Rept 27, Jan-June 1979 ML20214M9261966-12-16016 December 1966 Suppl B of FSAR on Nbs Reactor ML20214M9321966-10-0101 October 1966 Suppl a of FSAR on Nbs Reactor ML20214M9461961-01-0101 January 1961 Preliminary Hazards Summary Rept 1998-12-31
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3 "%}$ UNITED STATES
[ ,g NUCLEAR REGULATORY COMMISSION o '# WASHINGTON, D.C. 20555 4001 .
- SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 8 TO FACILITY OPERATING LICENSE NO. TR-5 NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY DOCKET NO. 50-184
1.0 INTRODUCTION
By letter dated January 17, 1997, the National Institute of Standards _and Technology (NIST or the licensee) formerly known as the National Bureau of Standards, proposed to amend the Technical Specifications (TS) for their 20 megawatt (mw) thermal test reactor located in Gaithersburg, Maryland. The TS changes would change the name of the organization that manages the reactor, and the resear-h associated with it, from Reactor Radiation Division to NIST Center for Neutron Research. Also, it would change the position title from Chief, Reactor. Radiation Division to Director, NIST Center for Neutron Research for the person in charge of this organization.
2.0 EVALUATION The TS change is mainly a change in the name of the organization and title of the person that manages the organization. All functions, responsibilities, and personnel remain the same, and the staff finds this administrative change will not affect the operation of the reactor, and that it is acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment changes recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). 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 Commission made a proposed determination that the amendment involves no significant hazards consideration which was published in the Federal Reaister (62 FR 8801) on February 26, 1997. No public comments were received.
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 operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and (3) the issuance of this amendment will not be inimical to the common defense and security or the health and safety or the public.
Principal contributor: Theodore S. Michaeli Date: March 31, 1997 9704030102 970331 PDR ADOCK 05000184 P PDR