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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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Text
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20065-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 44 TO FACILITY OPERATING LICENSE NO. R-28 UNIVERSITY OF MICHIGAN DOCKET NO. 50-2
1.0 INTRODUCTION
By letter dated April 2,1998, the University of Michigan (licensee) submitted proposed changes to the Ford Nuclear Reactor Technical Specifications (TSs) to add a reactor pool coolant inlet temperature rundown for the control rods, if the inlet temperature equals 114*F in the forced convection mode. The licensee also modified the TSs to include in Table 3.1 a pool tempera-ture rundown at a pool temperature equaling 129'F, which already exists as a Limiting Safety System Setting (LSSS) in the Natural Convection Mode (see existing TSs 2.2.2.1).
2.0 EVALUATION The licensee has added, as a TS requirement, an automatic rundown of the control rods if the pool inlet temperature equals 114*F and the thermal power level is greater than 1.6 Mw. The actualinstallation of this rundown feature took place on September 30,1987, and was approved by the Safety Review Committee.
This rundown was added because it was discovered in October 1986 that the automatic
- rundown of the pool outlet temperature, with an LSSS set at 129'F, may not assure that the inlet temperature Safety Limit (SL) of 116*F would be met if the coolant rate through the reactor was increased. The possibility of this happening was observed when the nominal coolant flow was increased from 990 gallons per minute (gpm) to 1180 gpm. It was noted that the outlet temperature was 126.2*F and the inlet temperature was 114.8*F. Thus, the inlet temperature was 1.2*F from the SL while the outlet temperature was 2.8'F from the automatic rundown. The licensee took care of this situation on an interim basis by lowering the outlet temperature rundown to 126*F, but later decided to install an automatic rundown on the inlet temperature and set it at 114*F, which is 2*F below the SL of 116*F to allow for measurement errors.
The staff finds that the inlet temperature safety channel rundown provides automatic protective action to prevent exceeding the 2 Mw reactor coolant inlet temperature SL of 116*F under all anticipated operating conditions, and finds it acceptable.
The licensee also added, in Table 3.1 of the TS (page 13), a pool temperature rundown to be activated at a pool temperature of 129'F when the reactor is operated in the natural convection j flow mode. This rundown already exists since an LSSS in the natural convection mode of l I
9804210358 980416 } l PDR ADOCK 05000002 P PDR I' l
e 2-129'F is specified in, section 2.2.2.1 (page 9) of the TS. The rundown had never been put in the Limiting CondSo: s of Operation section of the TS, and this addition takes care of that omission. The staM iinds this acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
The amendment involves changes with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR Part 20. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of effluents that may be released offsite, and there is 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.
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, (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 of the public.
Principal Contributor: T. Michaels