|
---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
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 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 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 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 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 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 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 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 1999-08-05
[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
[Table view] |
Text
_ _ _. . __
1
/ ,
, / / /
W(([,j .
MICHIGAN MEMORIAL-PHOENIX PROJECT PHOENIX MEMORIAL LABORATORY FORD NUCLEAR REACTOR ANN ARBOR. MICHIGAN 48109 2100 November 25,1998 Theodore S. Michaels, Senior Project Manager U.S. Nuclear Regulatory Commission Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Management Washington, D.C. 20555-0001 Docket 50-2, License R-28 Re: Notification of a Discovered System Deficiency - Failure of Reactor Building Ventilation Supply and Exhaust Dampers to Close
Dear Mr. Micheals:
This letter is a follow-up repon en the Ford Nuclear Reactor Ventilation Damper Cylinder problem that was initially reponed in a letter dated October 29,1998. The reactor was shutdown October 28 upon :
discovery that the reactor building ventilation dampers would not automatically close. The damper '
cylinder was repaired on November 2 and reactor operation was resumed November 3.
The reactor building confinement system exists to minimize the release of radioactivity to the unrestricted area in the event of a major experiment or fuel element failure. The reactor building ventilation supply and exhaust dampers are a part of the confinement system. The dampers are designed to close automatically when the building alarm is actuated by abnormally high radiation levels detected in the reactor building exhaust air (> 1 mrem /hr), if the fuel vault criticality monitor alarms or by operator action.
The proper operation of the damper cylinder had been verified when the reactor control systems were checked out on October 20,1998, as required by technical specification 4.3.1. On October 28,1998 at approximately 10:30 a.m., the day shift operator discovered that the damper cylinder was sticky while performing a routine daily surveillance check. The Assistant Manager for Reactor Operations was mformed and promptly evaluated the situation. The evaluation determined that the damper cylinder was not just sticky, but was inoperable. The day shift lead operator, upon being informed of the inoperable damper cylinder, then began a reactor shutdown at i1:14 a.m.
s University of Michigan Plant Department personnel were called to work on the dampers. They disconnected the air cylinder, then removed and disassembled it. Inspection of the disassembled ilD I
components revealed that water, oil, rust and dirt had collected inside the cylinder. Some of this /
material was lodged in the cup seals of the air cylinder's piston thereby causing the piston to bind. The air cylinder itself was not the source of any of this material, since its internal surfaces were free of rust and corrosion.
O '20 The air cylinder components were all cleaned and lubricated. The air cylinder was then reassembled and reinstalled. Plant Department installed a new three-way solenoid control valve and a new in-line oiler as replacement parts. The ventilation damper controls were exercised. The dampers worked smoothly and normally after the repairs were completed. Basqd on the successful refurbishment, the Assistant Manager for Reactor Operatjons authorized reactor restart and operation resumed November 3.
g} ab '4 9812010016 981125I PDR ADOCK 05000002 S PDR, Page 1 of 2 Phrine:17% r644220 Fax: 0146 4w1571 www.umtch edid-mmpp/
, s !
l -
l The components and piping of the reactor air system consist primarily of carbon steel and the i L compressed air is somewhat moisture-laden. This results in some corrosion and loose mst particles which are carried through the system and can collect at trapping points such as the ventilation damper ait cylinder. The moisture prob em is currently addressed by periodically blowing down several traps at
. low points in the air piping.
In order to prevent a future recurrence of this problem, clean air will be supplied to the damper air j cyliiider. Plant Department suggested and FNR management agreed that an in-line air filter be installed. ;
A modification request and supporting work order have been initiated to install an air filterjust before ;
the damper air cylinder solenoid valve. Also, copper air lines will be installed between the air filter and
' damper air cylinder. This work is scheduled for the week of November 30.
Sincerely, i
i John C. Lee, Interim Director .
Michigan Memorial- Phoenix Project l l
1
- )
i l
l xc: NRC Document Control Desk ;
Tom Burdick, NRC '
SRC Members l
l l
a
(
Page 2 of 2
\: -