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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20151Z2701998-09-17017 September 1998 Safety Evaluation Supporting Amend 45 to License R-28 ML20217K8811998-04-23023 April 1998 Corrected First Page of Safety Evaluation Supporting Amend 44 to License R-28,changing Date in First Paragraph to 970930 & Date in Second Paragraph to Oct 1996 ML20216J3501998-04-16016 April 1998 Safety Evaluation Supporting Amend 44 to License R-28 ML20245F9791989-08-0404 August 1989 Safety Evaluation Supporting Amend 33 to License R-28 ML20236U2031987-11-24024 November 1987 Safety Evaluation Supporting Amend 32 to License R-28 ML20141N1111986-02-24024 February 1986 Safety Evaluation Supporting Amend 31 to License R-28 ML20136G8911985-11-0505 November 1985 Safety Evaluation Supporting Amend 30 to License R-28 ML20148D8151978-10-13013 October 1978 Safety Evaluation Rept Supporting Amend 26 to Facil Oper Lic R-28 Concluding That an Increase from 1 Mw to 2 Mw in Maximum Allowed Pwr of Fnr w/10-plate Fuel Assemblies in E,W & Core Positions Is Acceptable ML20148C8061978-10-12012 October 1978 Safety Evaluation Supporting Amend 25 to License R-28 1998-09-17
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20210P3051999-08-0505 August 1999 Ro:On 990708,credible Single Failure in SR Temp Sys Could Result in Loss of Capability of Temp Sys to Protect Limiting Safety Sys Settings.Single Failure Is Loss of 15 V DC Power Supply.Mod Request 134 to Temp Sys Was Submitted ML20209E9771999-07-0808 July 1999 Preliminary Rept of non-routine Occurence Re Identification of Possible Single Failure for Safety Related Temperature Sys on 990706.Low Temperature Auto Rundown Proposed & Problem Rept Initiated to Document Review of Event ML20205B0631998-12-31031 December 1998 Rept of Reactor Operations for Jan-Dec 1998 for Ford Nuclear Reactor Michigan Memorial - Phoenix Project Univ of Michigan,Ann Arbor. with ML20206P3021998-12-31031 December 1998 Revised Rept of Reactor Operations for Jan-Dec 1998 for Ford Nuclear Reactor Michigan Memorial - Phoenix Project Univ of Mi,Ann Arbor ML20196B2091998-11-25025 November 1998 RO Update:On 981028,reactor Was Shutdown Upon Discovery That RB Ventilation Dampers Would Not Automatically Close.Damper Cylinder Was Repaired on 981102 & Reactor Operation Resumed on 981103 ML20155J1131998-10-29029 October 1998 Part 21 Rept Re Failure of EDs to Automatically Close.Cause Due to Discovery That Air Cylinder That Operates RB Ventilation Supply & EDs Was Hanging Up.Reactor Will Remain Shut Down Until Damper Cylinder Is Repaired ML20154J6761998-10-0909 October 1998 RO 20:on 980925,Reactor Operators Made Error at Ford Nuclear Reactor in Implementing Calorimetry Procedures to Raise Power Level.Upon Discovery of Error Made in Linear Level Setpoint Reactor Power Was Reduced by 1% to Compensate ML20153H0841998-09-28028 September 1998 Special Rept:On 980925,inadequate Procedure Implementation Resulted in Possible steady-state Reactor Operation at 2.02 MW Thermal Power.Interim Reactor Manager Reviewed Calorimeter Data & Did Not See Any Obvious Errors ML20151Z2701998-09-17017 September 1998 Safety Evaluation Supporting Amend 45 to License R-28 ML20151Z1571998-09-17017 September 1998 Revised Ro:On 980817,980811 Event Re Slow Inward Drift of CR Reoccurred.Caused by Worn Worm Gear & Missing Full Turn of Worm Thread.Installed & Tested Drive Gear Coupling. Previously Submitted Ltr Rept Dtd 980911,deleted Text ML20151W6391998-09-11011 September 1998 Special Rept:On 980811,swing Shift Operators Noted That CR Would Slowly Drift Inwards When in Manual Control with CR low-raise Switch in Neutral.Cr lower-raise Switch Was Removed,Inspected & Cleaned,Then Reinstalled & Tested ML20236W0781998-07-30030 July 1998 RO 19:on 980720,determined That Reactor Was Operating W/ Inoperable Alarm Circuit on Bridge Radiation Monitor.Caused by Spurious Alarms Due to Temp & Humidity Sensitivity. Maint Procedures CP-216 & CP-219 Were Modified ML20236T0741998-07-23023 July 1998 Non-routine Rept:On 971112,reactor Operators Shut Down Ford Nuclear Reactor to Remove Piece of Polyethylene Irradiation Container.Caused by Lack of Oversight.Method Will Be Adopted to Track Quartz & Polyethylene Samples ML20236T0801998-07-23023 July 1998 Development of Model Characterizing Heat Transfer in MTR Fueled Ford Nuclear Reactor ML20236S2921998-07-20020 July 1998 RO-19:on 980720,reactor Operation w/in-operable Alarm Circuit on Bridge Radiation Monitor,Was Disabled.Caused by Spurious Alarms Due to Temperature & Humidity Sensitivity. Reactor Shutdown Pending Further Investigation ML20248L5931998-06-0303 June 1998 Ro:On 980510,discovered 75 Gallon Loss of Pool Water to Radioactive Liquid Retention Tank Sys.Caused by Leak in One of Two Resin Columns Comprising B Hot Demineralizer (Hot Di) Sys.Modified Operating Procedure OP-211 Encl ML20217K8811998-04-23023 April 1998 Corrected First Page of Safety Evaluation Supporting Amend 44 to License R-28,changing Date in First Paragraph to 970930 & Date in Second Paragraph to Oct 1996 ML20216J3501998-04-16016 April 1998 Safety Evaluation Supporting Amend 44 to License R-28 ML20217H1891997-12-31031 December 1997 Rept of Reactor Operations Jan-Dec 1997 for Ford Michigan Memorial - Phoenix Project Univ of Mi Ann Arbor ML20137F2251996-12-31031 December 1996 Rept of Reactor Operation Jan-Dec 1996 for Ford Nuclear Reactor Mi Memorial - Phoenix Project Univ of Mi Ann Arbor ML20137K7671996-12-31031 December 1996 Annual Rept of Reactor Operations for Period 960101-1231 ML20057F4521993-10-0606 October 1993 Follow-up on RO 18,dtd 930805 Re Release of low-level Radioactive Water from RB to Drain Tiles Around Foundation of Bldg.Line from Foundation Tiles Drains to Reactor Cold Sump,Through Which Water Released Permanently Sealed ML20059M3161993-08-0101 August 1993 Rev 2 to Safety Analysis ML20128D4641992-11-25025 November 1992 Ro:On 921124,control Rod Interlock Sys Removed from Reactor Control Sys.Caused by Wiring Error Made During Mod That Disabled Interlock That Drops Reactor Out of Automatic Control.Control Rod Withdrawn to 23 Inches ML20058N7841990-08-0606 August 1990 RO 13:on 900721,tritium Content in Heavy Water Tank in Excess of 50 Ci.Samples Sent to Kms Fusion.Health Physics Procedure 107 Corrected to Reflect Correct Density of Heavy Water ML20055H1141990-07-18018 July 1990 Requalification Program Ford Nuclear Reactor ML20245F9791989-08-0404 August 1989 Safety Evaluation Supporting Amend 33 to License R-28 ML20246F3881989-05-0303 May 1989 RO 12:on 881227,concentrations of I-131 & Xe-133 Discovered in Reactor Pool Water.Caused by B&W Element 204 Releasing Fission Products.B&W Contacted to Review Mfg Process.Air Samples Will Be Taken Above Pool on Monthly Basis ML20150C6951987-12-31031 December 1987 Rept of Reactor Operations,1987 ML20236U2031987-11-24024 November 1987 Safety Evaluation Supporting Amend 32 to License R-28 ML20141N1111986-02-24024 February 1986 Safety Evaluation Supporting Amend 31 to License R-28 ML20136G8911985-11-0505 November 1985 Safety Evaluation Supporting Amend 30 to License R-28 ML20126M2631985-07-31031 July 1985 Safety Evaluation Report Related to the Renewal of the Operating License for the Training and Research Reactor at the University of Michigan.Docket No. 50-2.(University of Michigan) ML20138L5791984-06-30030 June 1984 Low Enrichment Fuel Evaluation & Analysis Program Summary Rept for Jan 1983 - June 1984 ML20138L5731982-12-31031 December 1982 Low Enrichment Fuel Evaluation & Analysis Program Summary Rept for CY81 & CY82 ML20138L5621980-12-31031 December 1980 Low Enrichment Fuel Evaluation & Analysis Program Summary Rept for CY80 ML20138L5491980-03-10010 March 1980 Cycle 184 Reactor Operations Summary Rept for 800226-0310 ML20138L5241979-12-31031 December 1979 Low Enrichment Fuel Evaluation & Analysis Program Summary Rept for CY79 ML20148D8151978-10-13013 October 1978 Safety Evaluation Rept Supporting Amend 26 to Facil Oper Lic R-28 Concluding That an Increase from 1 Mw to 2 Mw in Maximum Allowed Pwr of Fnr w/10-plate Fuel Assemblies in E,W & Core Positions Is Acceptable ML20148C8061978-10-12012 October 1978 Safety Evaluation Supporting Amend 25 to License R-28 ML20138L5181978-04-20020 April 1978 Revised Safety Analysis:Utilization of Intermetallic U Aluminide (UAI3,UAI4,UAI2) & U Oxide (U308) Cermet Fuel Cores in Ford Nuclear Reactor 1999-08-05
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& pnrstoq[*- g UNITED STATES ;
[ g NUCLEAR REGULATORY COMMISSION !
- 7. j- WASHINGTON, D. C. 20555 l
\...../ SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
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i SUPPORTING AMENDMENT NO. 32 TO FACILITY OPERATING LICENSE N0. R-28 )
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UNIVERSITY 0F MICHIGAN l
- DOCKET NO.50-002 I i l
1.0 INTRODUCTION
By letter dated July 15, 1986, the University of Michigan submitted to l the United States Nuclear Regulatory Comission (NRC) an amended Ford J Nuclear Reactor Security Plan (FNRSP) dated May 27, 1986. The FNRSP was submitted as a 10 CFR 50.90 amendment to the University's reactor l operating license because of revisions that were made which decreased security effectiveness. . The revisions resulted from the conversion from high enriched uranium (HEU) to low enriched uranium (LEU) and changes in i
the University's organization. Based on an initial review by the NRC staff, it was found that additional information and clarifications were ,
i needed in order to find the amended FNRSP acceptable. Consequently, by 'l letter dated October 2,1986, the NRC's Office of Nuclear Reactor i
l Regulation transmitted to the University the staff's findings. . By
- letter dated October 13, 1986, the University responded to the staff's l findings by submitting a revised copy of the FNRSP with all. modifications i clearly delineated by underlines. The FNRSP is exempt from public disclosurepursuanttotheprovisionsof10CFR2.790(d). By letter 1 dated October 13, 1987, the University of Michigan informed the NRC that 1 all HEU fuel was shipped from their site to Savannah River, South i
- Carolint.
! 2.0 EVALUATION. .
- a. .
} The staff evaluated the FNRSP and found that the security plan: j Describes the controlled access area (CAA)'where unirradiated j special nuclear material (SNM) is stored, including its features
- relative to other facility features, its physical barriers, and the
- means and criteria for. controlling access; .j a
Describes access controls for the reactor security area where fuel, j which is exempt pursuant to 10 CFR 73.67(b)(1), is used; '
? Describes intrusion alarms and procedures used for detecting 4 unauthorized entry into the CAA and security area; l
Describes the security organization; j l
B712O20355 871124 2; DR ADOCK 0500 V !
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Establishes response procedures for attempted theft and theft of SNM; ar.d
- Describes the measures used for in-transit physicai protection.
Based on. review of the subject document. identified in Section 1.0, the staff has concluded that the protection measures identified in the physical- security plan . meet the requirements of'10 CFR' Part 73.67(f) and (g) for special nuclear material of low strategic significance.
3.0 ENVIRONMENTAL CONSIDERATION
The staff has determined that this amendment involves m significant increase in the amounts, and no significant change in- 0.4 types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
Accordingly, this amendment meets the~eligibilit criteria for categorical exclusion set forth in 10 CFR 51.22(y)(9)..
c 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, l that: (1) because the amendment does not' involve a significant increase l in the probability or consequences of accidents previously evaluated, or create the possibility of a new or.different kind of accident from any accident.previously evaluated, and does not. involve a significant reduction in a margin of safety, 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 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 s'afety of the public.
Principal Contributor: Donald M. Carlson, RSGB, NRR -
Theodore S. Michaels, PDSNP, NRR Dated: November 24, 1987 L