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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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[pa aeg'og UNITED STATES
[ g NUCLEAR REGULATORY COMMISSION
$ j WASHINGTON, D. C. 20555
[
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0. 30 TO FACILITY LICENSE NO. R-28 UNIVERSITY OF MICHIGAN DOCKET N0.59-002 Introduction
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15N "The University of Michigan (UM) reactor operating license No. R-28 recently '
- 'was renewed for a period of twenty years. This amendment, requested by the licensee, adjusts the shutdown margin during reactor fuel loading changes (Section 3.1(5)) to be compatible with the staff's Safety Evaluation Report for the license renewal and with the values in Section 3.1(1), which is the cold clean shutdown margin with all shim safety rods fully inserted and the regulating rod fully withdrawn.
- j Evaluation ;
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' .. The minimum shutdown margin relative to a cold, clean, xenon-free condition for this core is 0.025 delta k/k as set forth in specification 3.1(1) rather e than 0.030 as set forth in specification 3.1(5). This discrepancy should
.f have been noted and corrected during the license renewal review. This change makes section 3.1(5) compatible with the remainder of Section 3.0.
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f Environmental Consideration This amendment involves changes in the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and changes in inspection or surveillance requirements. The staff has determined that the amendment involves no significant hazards consideration (as discussed below), there is no significant change in the types or signifi-cant increase in the amounts of any 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.
8511220493 851119 PDR ADOCK 05000002 P PDR
Conclusion The staff has 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 evaluated, does not 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 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 the activities authorized by the proposed amendment; 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 the health and safety of the public.
Principal Contributor: Harold Bernard Dated: November 5, 1985
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TECHNICAL SPECIFICATIONS Ford Nuclear Reactor
' Docket 50-2, License R-28 i November, 1984' 3.O LIMITING CONDITIONS FOR OPERATION 3.1 Reactivity Limits -
Applicability '.
This specification applies to the reactivity of the reactor core and to the reactivity worths of control rods and experiments.
When the reactor is operated with the heavy water reflector tank in place, the limits will not include the static reactivity worth of P.he tank. _
'- , Objective:
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[ To assure that the reactor can be controlled and shutdown
! ;7 ,_ at all times and that the safety. limits will not be exceeded. <
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, Specification, l
l (1) The shutdown margin relative to the cold, xenon free critical condition shall be at least .025 delta K/K with all three shim cafety rods fully inserted and the regulating rod fully withdrawn and 0.0045 delta K/K with the most reactive shim saf ety rod and the regulating rod i fully withdrawn.
. . (2) The overall core excess reactivity including i moveable experiments shall not exceed 0.038 delta K/K.
f (3) The total reactivity worth of all experiments shall not exceed 0.012 delta K/K. ,
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(4) The reactivity worth of each experiment shall be limited as follows:
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. Nanimum Ex neri ment Reactivity Worth Moveable 0.0012 delta K/K Secured 0.012 delta K/K (5) The reactor shall be suberf.tical by at least Q,Q21 delta K/K during fuel loading changes. ,
(6) Shim saf ety rods shall not be removed from the core f or inspection if the shutdown margin is less than 0.01 delta K/K with the most reactive evnaining shty saf ety rod fully withdrawn.
(7) The reactivity worth of the regulating rod shall not exceed 0.006 delta K/K.
Amendment No. 30 . page 9 m .