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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20211B1671999-07-13013 July 1999 Special Rept on 990614 Re Test of Scram Set Point of Two of Five Low Primary Coolant Flow Safety Sys Channels.Caused by Trip Set Points Being Too Close to TS Limits.Compliance Procedure 23 Will Be Revised ML20236Y5941998-08-0606 August 1998 Special Rept:On 980706,operator Noted That One Sample Listed as Inches Long on Loading Sheet,Only 2 Inches Long.Errors Constitute Observed Inadequacy in Implementation of Administrative & Procedural Control.Procedures Revised ML20236S1711998-07-15015 July 1998 Ro:On 980615,large & Rapid down-shift on Three Different Meter Indications from One Ni Drawer Was Discovered.Caused by Failed Preamplifier in Wide Range Amplifier Subject Ni Drawer.Replaced Cabling,Detector & Preamplifier ML20198K9441998-01-0808 January 1998 Special Rept:On 971209,reactor Shutdown by High Power Scram Initiated by Wide Range Monitor of Nuclear Instrument Sys. Caused by Unanticipated Positive Reactivity Insertion. Reflector Sample Opened & Inspected ML20197D2751997-12-15015 December 1997 Ro:On 971026 & 1106,slight Elevation of Fission Products Were Detected in Primary Coolant Water Analyses.Caused by Slight Fabrication Flaw in Element MO-460.Surveillance of Bwx Technologies Fabrication Techniques Will Be Increased ML20196G8891997-07-15015 July 1997 Special Rept:On 970616,scram Setpoint for Low Flow Scram for Heat Exchanger 503A Leg Was 25 Gpm Below TS Limit.Caused by Drifting of Setpoint of Vutronik Monitor Switch DPS-928A. Adjusted Trip Setting & Retested Trip Setting ML20116E2621996-07-30030 July 1996 Ro:On 960701,emergency Generator Shutdown on High Coolant Temp.Caused by Sheared Water Pump Shaft.Replaced Defective Pump ML20100J3991996-02-22022 February 1996 Ro:On 960123,reactor Was Shut Down by Manual Scram When Console Operator Determined That Regulating Blade Was Inoperable.Caused by Seized Bearing on Gearbox Input Shaft. Bearing Replaced ML20097J4391996-01-26026 January 1996 Special Rept:On 951227,reactor Shutdown Occurred Due to Reactor in Operation W/Regulating Blade in Degraded Condition.Replaced Dowel Pin ML20082P4491995-04-19019 April 1995 Special Rept:On 950320,reactor Startup Occurred W/Source Range Monitor in Degraded Condition.Shutdown Taken by Console Operator ML20073K3221994-09-30030 September 1994 Special Rept:On 940902,reactor Scram Occurred Due to Failure of Inner Airlock Door Drive Sys.Airlock Door Drive Sys Repaired ML20069E0241994-05-25025 May 1994 Special Rept:On 940426,shift Supervisor Noted Decreasing Power Trend on Wide Range Monitor Chart.Problem Quickly Identified to Be One Loose & One Missing Set Screw in Motor to Gearbox Coupling.Missing Set Replaced W/New One ML20058M7421993-09-27027 September 1993 Ro:On 930907,determined That Scram Setpoint for Low Flow Scram for HX 503B Leg Below LSSS of 1625 Gpm Required by TS 2.2.Caused by Defective Alarm Trip Unit.Defective Alarm Trip Unit Replaced W/Spare Unit ML20056D8771993-08-12012 August 1993 Ro:On 930712-26,reactor Operated W/Operability of Automatically Closing Reactor Containment Isolation Door in Degraded Condition.Caused by Actuating Cam Maladjusted.Cam Readjusted & Tightened ML20125B6951992-12-0202 December 1992 Ro:On 921104,channel 4,5 or 6 95% Downscale Annunicator Received,Annunicator Locked in & Then Cleared Several Times. Caused by Setscrew,That Engages Motor Shaft to Gear Box, Coming Loose.Motor Shaft Modified to Add Flat Surface ML20099A7051992-07-20020 July 1992 Special Rept:From 920622-23,reactor Operated W/Unreliable Radiation Monitoring of Exhaust Stack Effluent.Caused by Pieces of Sheet Metal,Used as Bending Vanes,Breaking Loose & Disconnecting from Sampling Line.Probe Reconnected ML20099B6231992-07-20020 July 1992 Special Rept:On 920623,discovered Lower than Normal Chart Recorder Indication on Stack Radiation Monitor Gas Channel. Caused by Pieces of Sheet Metal Impacting Kinetic Probe. Tygon Tubing Connection Replaced W/Solid Tubing ML20086N1101991-12-10010 December 1991 Special Rept:On 911111,differential Pressure Indications Showed That One of Two Primary Coolant Isolation Valves Did Not Seat Properly.Caused by Valve Steam Falling Out of Valve Actuator.Actuator Key Replaced & Bottom Slot Recrimped ML20079L7191991-10-29029 October 1991 Ro:On 910930,primary Coolant Isolation Valve V507A Took Longer than Normal to Close & Differential Pressure Indications Indicated Valve Failed to Seat Properly.Caused by Valve Stem Binding.Valve Will Be Replaced ML20246A1031989-06-15015 June 1989 Ro:On 890603,discovered That Drive Chain Had Fallen Off Drive Gear for Regulating Blade Rotary Limit Switch.Reactor Shutdown Initiated.Chain for Rotary Limit Switch Assembly Returned to Drive Gear & Tension Adjusted ML20248G6241989-03-28028 March 1989 Ro:On 890302,reactor Operated for 2 H & 33 Minutes W/ Emergency Generator Local Switch in Stop Position.Caused by Personnel Error.Subj Local Switch Placed in Remote Position. Operator Involved Counseled.Checksheet Revised ML20206B9931988-10-31031 October 1988 Revised 881019 Special Rept on 880921 Event Re Reactor Operation W/Regulating Blade Being Inoperable.Second Sentence in Ltr Corrected ML20195D4911988-10-28028 October 1988 Ro:On 880929,difference of 10 F Between Temp Indications for Primary Loop a & Loop B Observed.Caused by Small Amounts of Resistance Introduced Into Compensation Loop Leads. Connection for Compensation Loop Will Be Double Checked ML20205N8811988-10-28028 October 1988 Ro:On 880929,Tech Spec Deviation Occurred Due to Intermediate Range Monitor Channel 3 Indicating Downscale & Associated Short Period Rod run-in & Scram Trip Inoperable. Caused by Breakdown of Cable Insulation.Cabling Replaced ML20205H8961988-10-19019 October 1988 Ro:On 880921,Channel 4 High Power Rod run-in Occurred & Regulating Blade Would Not Respond in Either Automatic or Manual Mode.Caused by Gear Box Assembly W/Internal Drive Gear Ridden Up Shaft Due to Loose Set Screw.Drive Repaired ML20154L3981988-09-15015 September 1988 Ro:On 880818,emergency Generator Cranking Limit Indication Found Tripped & Plant Failed to Start Lamp Energized. Caused by Linkage Lubrication Problem.Preventive Maint (PM) Procedure Added to PM Schedule ML20235G4991987-09-24024 September 1987 Ro:On 870825,closed Indicating Light for Automatically Closing Reactor Containment Isolation Door Did Not Turn On. Caused by Addl Drag Reducing Coast Distance of Door.Motor Drive Stop Microswitch Readjusted ML20206D0031987-03-31031 March 1987 Ro:On 870305,test Signal Simulating High Temp Fed to 980A Meter Relay Trip Unit,But Meter Relay Contacts Failed to Open.Caused by Decreased Capacitance Value in Meter Relay Control Circuit.Meter Relay Trip Unit Replaced ML20214N8381986-11-24024 November 1986 Ro:On 861030-31,reactor Operated W/Seal for Inner Airlock Door Deflated Due to Bleed Valve in Abnormal Position.Caused by Personnel Error.Procedures Will Be Revised & Addl Pressure Gauge Will Be Added to Air Supply Sys ML20214P2841986-09-10010 September 1986 Ro:On 860815,emergency Pool Fill Sys Discovered in Abnormal Lineup Due to Valve PIV-1 Being Closed.Caused by Improper Clearing of Red Tag Indicating Valve Opened on 860501. Reactor Startup Checksheet Revised to Ensure Valve Opened ML20211K3891986-08-20020 August 1986 Ro:On 860729,dosimeter Vendor,Rs Landauer & Co,Reported That TLD Finger Dosimeter Recorded 23,560 Mrem for June 1986.On 860609,employee Packed Tm-170 Wafers for Shipment.Committee to Investigate Exposure Activated ML20134E2881985-08-13013 August 1985 Ro:On 850718,during Front Panel Checks Prior to Reactor Startup,Rod run-in Trip Function for Power Range Monitor 5 Found Inoperable.Possibly Caused by Loose Pin Connection. Trip Unit Module Replaced & Operability Checked Weekly ML20126J4661985-05-31031 May 1985 Ro:On 850519,chain Link on Drive Chain for Regulating Blade Position Indicator Failed.Caused by Broken Drive Chain Link. Drive Chain Link Repaired & Regulating Blade Driven Full in for Position Indication Reset ML20112E1321985-03-18018 March 1985 Ro:On 850220,nuclear Instrumentation Channel 6 Power Range Monitor Indication Dropped from Indicated Power of 104% to 92%.Cause Not Determined.Down Scale Alarm of 75% Will Be Changed to 95% ML20112F0111985-01-11011 January 1985 Ro:On 841213,emergency Generator Stalled 45 After Assuming Emergency Electrical Loads During Emergency Generator Load Test CP-17.Cause Not Found.Stalling Did Not Recur During Subsequent Tests.Mods Will Reduce Starting Load ML20091Q9251984-06-0808 June 1984 Ro:On 840511,personnel Airlock Doors Operated Out of Sequence,Allowing Both Inner & Outer Doors to Open at Same Time.Caused by Outer Airlock Door Gasket Pulled Partly from Seat.Gasket Replaced ML20079K7491984-01-13013 January 1984 Ro:On 831215,emergency Generator Gasoline Engine Electrical Interlock Protective Circuit Tripped.Caused by Bent & Nearly Grounded Electrical Connecting Wire Spade Lug.Trip Sensor Leads Placed to Prevent Grounding ML20081J0821983-11-0101 November 1983 Ro:On 831003,during Full Power,Site Electrical Power Lost & Emergency Generator Operated in Degraded State.Cause Probably Due to Addition of STP Gas Treatment on 830923. Gas Pumped from Generator Tank.Sys Refilled ML20066H9661982-11-17017 November 1982 Ro:During 821021 Shutdown to Change Flux Trap Samples,Flux Trap Sample Hold Down Device Determined Improperly Installed During 821018 Shutdown.Caused by Hold Down Rod Assembly Pinned High.Device Properly Repinned ML20054F6981982-05-25025 May 1982 Ro:Advises of Mod to Corrective Action Noted in Informing NRC of Valve Left Open in Line That Penetrates Containment Wall.Red Danger Tags on Valves Outside Containment Removed,As Pipe Cap Insures Flow Path Isolated ML20062C0151978-10-31031 October 1978 Ro:On 781022,control Blade B Unexpectedly Dropped from Drive Magnet & Hung Up Approx 7 Inches Above Full Insertion. Probably Caused by Broken Outer Race of One of Eight Vertical Guide Bearings 1999-07-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212D4471999-09-20020 September 1999 Safety Evaluation Supporting Amend 31 to License R-103 ML20211B1671999-07-13013 July 1999 Special Rept on 990614 Re Test of Scram Set Point of Two of Five Low Primary Coolant Flow Safety Sys Channels.Caused by Trip Set Points Being Too Close to TS Limits.Compliance Procedure 23 Will Be Revised ML20206A9681999-04-21021 April 1999 Revised Page 4 to MURR QA Plan ML20202G9051998-12-31031 December 1998 Operations Monthly Summary for Univ of Mo Research Reactor for Dec 1998 ML20207A6981998-12-31031 December 1998 Reactor Operations Annual Rept for 980101-1231, for Univ of Missouri Research Reactor Facility.With ML20202G9171998-11-30030 November 1998 Operations Monthly Summary for Univ of Mo Research Reactor for Nov 1998 ML20202G9271998-10-31031 October 1998 Operations Monthly Summary for Univ of Mo Research Reactor for Oct 1998 ML20154M3301998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Univ of Missouri Research Reactor ML20154M3401998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Univ of Missouri Research Reactor ML20236Y5941998-08-0606 August 1998 Special Rept:On 980706,operator Noted That One Sample Listed as Inches Long on Loading Sheet,Only 2 Inches Long.Errors Constitute Observed Inadequacy in Implementation of Administrative & Procedural Control.Procedures Revised ML20154M3431998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Univ of Missouri Research Reactor ML20236S1711998-07-15015 July 1998 Ro:On 980615,large & Rapid down-shift on Three Different Meter Indications from One Ni Drawer Was Discovered.Caused by Failed Preamplifier in Wide Range Amplifier Subject Ni Drawer.Replaced Cabling,Detector & Preamplifier ML20154M3651998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Univ of Missouri Research Reactor ML20154M3731998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Univ of Missouri Research Reactor ML20154M3841998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Univ of Missouri Research Reactor ML20246P9931998-03-31031 March 1998 Monthly Operating Rept Summary for Mar 1998 for Univ of Missouri Research Reactor ML20246Q0231998-02-28028 February 1998 Monthly Operating Rept Summary for Feb 1998 for Univ of Missouri Research Reactor ML20203H4271998-02-26026 February 1998 Safety Evaluation Supporting Amend 30 to License R-103 ML20246Q0201998-01-31031 January 1998 Monthly Operating Rept Summary for Jan 1998 for Univ of Missouri Research Reactor ML20198K9441998-01-0808 January 1998 Special Rept:On 971209,reactor Shutdown by High Power Scram Initiated by Wide Range Monitor of Nuclear Instrument Sys. Caused by Unanticipated Positive Reactivity Insertion. Reflector Sample Opened & Inspected ML20203L0531997-12-31031 December 1997 Reactor Operations Annual Rept,970101-1231, for Univ of Missouri Research Reactor Facility ML20202H4091997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Univ of Mo Research Reactor ML20197D2751997-12-15015 December 1997 Ro:On 971026 & 1106,slight Elevation of Fission Products Were Detected in Primary Coolant Water Analyses.Caused by Slight Fabrication Flaw in Element MO-460.Surveillance of Bwx Technologies Fabrication Techniques Will Be Increased ML20202H3931997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Univ of Mo Research Reactor ML20202J1151997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Univ of Missouri Research Reactor ML20202J1201997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Univ of Missouri Research Reactor ML20211B2871997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Univ of Missouri Research Reactor ML20210R2701997-07-31031 July 1997 Univ of Missouri Research Reactor Operations Monthly Summary,July 1997 ML20196G8891997-07-15015 July 1997 Special Rept:On 970616,scram Setpoint for Low Flow Scram for Heat Exchanger 503A Leg Was 25 Gpm Below TS Limit.Caused by Drifting of Setpoint of Vutronik Monitor Switch DPS-928A. Adjusted Trip Setting & Retested Trip Setting ML20149L3761997-06-30030 June 1997 Monthly Operating Rept for June 1997 for Univ of Mo Research Reactor ML20141H6451997-05-31031 May 1997 Monthly Operating Rept for May 1997 for Univ of Mo Research Reactor ML20141H6581997-04-30030 April 1997 Monthly Operating Rept for April 1997 for Univ of Missouri ML20141H6691997-03-31031 March 1997 Monthly Operating Rept for Mar 1997 for Univ of Missouri ML20136D7211997-03-0606 March 1997 Safety Evaluation Supporting Amend 29 to License R-103 ML20141H7421997-02-28028 February 1997 Monthly Operating Rept for Feb 1997 for University of Missouri Research Reactor ML20141H6421997-01-31031 January 1997 Monthly Operating Rept for Jan 1997 for Univ of Mo Research Reactor ML20141H7001996-12-31031 December 1996 Monthly Operating Rept for Univ of Missouri Research Reactor for Dec 1996 ML20138Q6601996-12-31031 December 1996 Reactor Operations Annual Rept for 1996 ML20141H7221996-10-31031 October 1996 Monthly Operating Rept for Univ of Missouri Research Reactor for Oct 1996 ML20116E2621996-07-30030 July 1996 Ro:On 960701,emergency Generator Shutdown on High Coolant Temp.Caused by Sheared Water Pump Shaft.Replaced Defective Pump ML20141H6781996-06-30030 June 1996 Monthly Operating Rept for Univ of Missouri Research Reactor for June 1996 ML20149L3721996-05-31031 May 1996 Monthly Operating Rept for May 1996 for Univ of Mo Research Reactor ML20117L1091996-05-13013 May 1996 Univ of Missouri Research Reactor Operations Monthly Summary for Apr 1996 ML20117L1001996-03-31031 March 1996 Univ of Missouri Research Reactor Operations Monthly Summary for Mar 1996 ML20117L0951996-03-13013 March 1996 Univ of Missouri Research Reactor Operations Monthly Summary for Feb 1996 ML20117L0841996-03-0606 March 1996 Univ of Missouri Research Reactor Operations Monthly Summary for Jan 1996 ML20100J3991996-02-22022 February 1996 Ro:On 960123,reactor Was Shut Down by Manual Scram When Console Operator Determined That Regulating Blade Was Inoperable.Caused by Seized Bearing on Gearbox Input Shaft. Bearing Replaced ML20097J4391996-01-26026 January 1996 Special Rept:On 951227,reactor Shutdown Occurred Due to Reactor in Operation W/Regulating Blade in Degraded Condition.Replaced Dowel Pin ML20101F5381995-12-31031 December 1995 Revised Pages III-1 & VII-1 to 1995 Operations Annual Rept ML20100M7821995-12-31031 December 1995 Univ of Mo Research Reactor Reactor Operations Annual Rept Jan-Dec 1995 1999-09-20
[Table view] |
Text
r Research Reactor Center Research Park Columbia, Missouri 65211 ,
Telephone (314) 682-4211 l UNIVERSITY OF MISSOURI-COLUMBIA FAX [314) 882 = 3443 September 30,1991 Director of Nuclear Reactor llegulation ATTN: Document Control Desk Mail Station Pl-37 U.S. Nuclear Regulatory Commission Washington, DC 20555 REFERENCE- Docket No. 50-186 University of Missouri Research Reactor License H-103 SUHJECT: Report as required by Technical Specification 6.1.h(2) regarding Personnel Airlock Door Failure INTRODUCTION On September 2,1994, at 2332, with the reactor operating at 10 MW, a failure of the inner airlock door drive system allmved both inner and outer airlock doors to be open at the same time. The failure was promptly reported to the control room and the operator immediately scrammed the reactor. The reactor was secured by 2333.
Technical Specification 3.5.a requires that containment integrity be maintained at all times except when the reactor is secured, e d irradiated fuel with a decay time less than sixty days is not being handled. For reactor cc 4tainment integrity to exist one of the personnel airlock doors must be closed with the gasket inflated. The reactor was operated out of compliance with this Limiting Condition for Operation for approximately one minute.
DESCRIPTION The personnel airlock doors at the second level of the reactor building are part of the containment system described in the Original llazards Summary Report, Section 3.0. The airlock censists of two electric power driven steel doors and an intervening vestibule. Each door is suspended by trolleys from an overhead rail and is driven open or closed by means of a chain drive powered by an electric motor operating through a gear reducer. The control system for the two airlock doors is designed and interlocked to ensure that one door is always scaled. The interlock consists of a relay logic circuit which detects door " closed" position from a separate rotary limit switch assembly (see Fig.1) for each door, as well as seal inflation pressure for each door. When a door is driven closed a microswitch in the limit switch assembly actuates an air valve to inflate a gasket which seals against the door. This logic circuit enables one door to open only if the other door indicates closed and sealed.
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l At 2332, September 2,1994, an experimenter exited the containment building through the l personnel airlock doors. The inner airlock door began to shut when the drive chain became i detached from the door. The drive chain attaches to the door through a threaded coupling '
into a shock absorber, and the coupling became unthreaded. This allowed the chain to continue to drive the sprocket (" south sprocket") that also drives the rotary limit switch assembly. !
The rotary limit switch assembly continued to drive to the point where the door " closed" relay contacts made up and the inner door seal inflated. The inner door then electronically ;
appeared to be closed and sealed and the airlock door interlock satisfied. This enabled the outer airlock door to sequence open causing a momentary loss of containment.
When this occurred the control room operators recognized an abnormal sound from the door sequence and the Shift Supervisor investigated immediately. The experimenter called the ;
control room at the same time to report the failure and the reactor was shutdown and !
secured by 2333.
ANALYSIS ;
The basis for Technical Specification 3.5.a under Limiting Conditions for Operation is to ensure that the containment building can be isolated at all times except when the plant conditions are such that the probability of release of radioactivity is negligible. When the I airlock doors. malfunctioned, deviating from the Limiting Conditions for Operation, a reactor :
scram was immediately perfbrmed to make negligible the already low probability of release l of radioactivity while operating the reactor. This was the first failure of this type experienced l with the personnel airlock door drive system at MUrtit.
Iteview and evaluation of the semi-annual preventive maintenance inspection procedure for the airlock door drive system (BCl-S2) indicated that the procedure is adequately detailed to find and correct detectable problems with the drive system. This preventive maintenance :
procedure had been completed on August i,1994, and no apparent problems were found.
Analysis of the failure indicated that the degree of thread engagement into the coupling could not be detected by either the semiannual preventive maintenance inspection done by reactor operators, or by the daily mechanical routine inspection done by the machine shop staff.
Based on this evaluation, the engineering staff decided to modify the threaded coupling to include a 1/8" roll pin to prevent the coupling from unthreading (see Fig. 2).
While evaluating the safety significance of this event, we recognized that our Limitin s Conditions for Operation for containment integrity in MUllR Technical Specifications do not include Action requirements (similar to Specification 3.0.2 of power plant Standard Technical Specifications) that would allow implementation of an Action requirement (in this case, a prompt shutdown) within a specified time interval as constituting compliance with the specification. Technically, the second a failure occurs we are in non-compliance.
1
IAtter to Director of Nuclear Reactor Regulation September 30,1994 Page three Review of ANSI /ANS-15.1, American National Standard for Development of Technical Specifications for llescarch Reactors, recommends submission of a special report (Licensee Event Report) for " operation in violation of limiting conditions for operation established in the technical specifications unless prompt remedial action is taken"(Section G.6.2.c.(ii)).
MURIt stafT will perform a safety analysis to support a request for change to T.S. 3.5.a in order to establish a reasonable time to take remedial action and still meet compliance with Technical Specifications. This will alleviate the generation of a Licensee Event Report for conditions which do not represent a safety concern for the reactor or the public.
CORRECTIVE ACTION When the Limiting Condition for Operation of the personnel airlock doors with regard to containment integrity (T.S. 3.5.a) was not met, the reactor was immediately scrammed and ;
secured. This was the fastest way to put the reactor into Technical Specification compliance. 1 The airlock door drive system was repaired and placed back in service at 0222, September 3, l 1994. The reactor was refueled and returned to operation at 0544 September 3,1994.
During the next maintenance shutdown, September 6,1994, the modification described )
carlier was made to all fbur couplings associated with the airlock door system, l 1
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Walt A. Meyer Jr.
Reactor Manager ,
ENDORSEMENT: 1 l
lleviewegd Approved .
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Associate Director BOONE COUm NY COnnisskN Exp. Arn.14.1ogs Attachments: Figures 1 and 2 xc: Mr. Alexander Adams, Jr., USNRC Regional Administrator, NRC, Region 111 Dr. John P McCormick, Interim Vice Provost for Research s and Graduate School Dean, UMC Reactor Advisory Committee Reactor Safety Subcoinmittee 1
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SHOCK ABSORBER SHAFT COLLAR LOCK NUT
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\COLLAR FOR CONNECTION OF CHAIN TO SHDCK SHOCK ABSORBER AIR LOCK DOOR SHOCK ABSORBER - BEFORE MODIFICATION
-DRILL AND PRESS 1/8' ROLL PIN THRU COLLAR TO PREVENT SHAFT FROM BACKING OUT OF COLLAR 1
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AIR LOCK DOOR SHOCK ABSORBER - AFTER MODIFICATION
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