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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20205A6551999-03-19019 March 1999 Ro:On 990310,main Ventilation Damper Failed to Close on Receipt of High Radiation Test Signal.Cause Indeterminate. Relays Associated with Main Exhaust Damper/Fans & Main Intake Damper Were Replaced ML20206P5321999-01-0606 January 1999 Ro:On 981229,only One Nuclear Safety Period Scram Channel Was Operable,For Period of Five Minutes.Caused by Placement of Nuclear Safety Sys Channel 1 Input Signal Cable on Wrong Bnc Connector.Placed Channel on Correct Bns Connector ML20217E8071998-03-23023 March 1998 Ro:On 980127,containment Integrity No Longer Existed & Key Switch Was Still 'On' for One of Test & Calibr Procedures. Caused by Retrieving Tool Box from Truck Air Lock.Discussed Occurrence W/Personnel & Will Consider TS Rev Re Key Switch ML20092K8281995-09-22022 September 1995 Corrective Action for RO 50-20/1995-4,re Abnormal Situations Which Occurred on 950711 ML20091K3091995-08-18018 August 1995 Ro:On 950809,malfunction of Shim Blade Drive Mechanism Occurred.Determined That Mechanism Experienced Intermittent Slippage When Blade Being Withdrawn.Blade Drive Mechanism Assembly Procedure PM 7.1.1.1 Will Be Reviewed ML20086T7571995-07-28028 July 1995 RO 50-20/1995-4:on 950720,operated W/One Shim Blade Fully Inserted.Caused by Failure of Licensed Operators to Follow Written Procedure for Investigating Mismatch.Failed Proximity Switches Replaced ML20082B8551995-03-30030 March 1995 RO 50-20/1995-2:on 950320,operation of Reactor in natural- Circulation Mode W/O Required Two Operable Nuclear Safety Level Channels Set to Scram at or Less than 100 Kw,Mitr TS 3.7 ML20078S2241995-02-17017 February 1995 Reportable Occurrence 50-020/95-01:on 950206,voltage & Specific Gravity Measurements of Cell of Emergency Battery Bank Recorded at Less than Specified Weekly SR in TS 4.3.5. C/A Will Modify SR to Monthly ML20058Q2371993-12-17017 December 1993 RO 50-20/1993-1:on 931207,operation W/Fewer than Required Number of 100 Kw Nuclear Safety Sys Level Channels Identified.Caused by Faulty four-segment Relay in low-range Amplifier of Channel 5.Amplifier Replaced ML20094K0721992-03-12012 March 1992 RO 50-020/1992-2:on 911030,three Fission Chambers Missing During Annual Inventory of SNM Matl.Search for Missing Chambers Completed on 920311 W/O Locating Chambers.Snm Inventory for 1991 Has Been Amended ML20090D6661992-03-0202 March 1992 RO 50-20/92-1 on:920218,malfunction Occurred in Reactor Analog Controller Due to Improper Performance of Increase in Reactor Power.Caused by Operator Error.Analog Automatic Control Sys Investigated & Temporarily Repaired ML20082K5911991-08-22022 August 1991 RO 50-20/1991-1:on 910813,fission Product Gas Levels Rose from Normal Operating Levels to Max of 15% of Mpc.Caused by Small Blister on One of Element MIT-17 Fuel Plates. Corrective Action Consisted of Removing MIT-17 from Core ML20248C7111989-08-0404 August 1989 RO 50-20/1989-2:on 890726,console Operator Received Abnormal Bldg Alarm.Leak Test Revealed Crack on Sys Ref Line Which Senses Atmospheric Pressure Outside Containment.All Polyethylene Tubing in Sys Replaced ML20246P3071989-03-17017 March 1989 RO 50-20/1989-1:on 890308,operation W/Fewer than Required Number of Nuclear Safety Channel Level Scrams Due to Lack of High Voltage Power Supply (Hvps) to Channel 5.Reactor Shut Down & Hvps Energized to Supply Channel 5 ML20154M6501988-05-26026 May 1988 RO 50-20/1988-1:on 880511,incipient Fuel Clad Defect Detected.Caused by Small Blister on One Element MIT-12 Fuel Plate.Element MIT-12 Removed from Core ML20236S4931987-11-19019 November 1987 RO 50-20/1987-2:on 871110,improper Performance of Reactor Reshim Resulted in Excessive Power Rise.Caused by Operator Error.Operator Suspended from All Licensed Duties Pending Further Review of Circumstances & Disciplinary Measures ML20213G0601986-11-0606 November 1986 RO 50-20/1986-3:on 861027,shim Blade 6 Could Not Operate at full-out Position Due to Mechanical Interference.Caused by Misalignment of Blade Proximity Switch Tube.Switch Tube Reinstalled Properly ML20214V9001986-10-17017 October 1986 Revised RO 50-20/1986-2:on 861008,elevated Levels of Fission Gases Discovered in Primary Containment.Cause Undetermined. Refueling Initiated & Element MIT-19 Removed.All in-core Elements Sipped.No Abnormalities Found ML20214H9541986-10-17017 October 1986 RO 50-020/86-02:on 861008,elevated Levels of Fission Gases in Primary Containment Observed.Cause Unknown.Element MIT-19 Removed from Core & All in-core Elements Sipped ML20154S4591986-02-28028 February 1986 RO 50-20/1986-1:on 860219,fission Product Gas Levels Rose from Normal Operating Levels.Caused by Blister on Surface of Outer Fuel Plate of Element MIT-11.Element MIT-11 Removed from Core ML20137G3661985-07-23023 July 1985 RO 50-20/1985-2:on 850715,defect in Fuel Element Cladding Observed.Caused by High Rate of Outgassing from Fuel Element MIT-32.Defective Element Removed ML20137G3531985-04-18018 April 1985 RO 50-20/1985-1:on 850408,main Intake Valve Failed Light Test Maint Procedure.Caused by Excessive Wear of Valve Gasket.Gasket Replaced ML20081H8191983-09-15015 September 1983 RO 50-20/1983-2:on 830906,fission Product Gas Levels Rise from 2.8% Max Permissible Concentration in Jul 1983 to 4.57% in Aug Noted.Caused by Excessive Outgassing of Fuel Element MIT-08.Element Removed from Core ML20074A7521983-04-29029 April 1983 RO 50-20/1983-1:on 830419,main Intake Valve Closed & Could Not Be Reopened.Caused by Piston Rod Rupture Near Rod Eye, Leaving Valve in Closed Position.Defective Hydraulic Cylinder Shaft Replaced ML20063B9221982-08-17017 August 1982 Ro:On 820809,slight Increase Found in Levels of Fission Products in Reactor Primary Sys.Cause Under Investigation. Criterion for Operation W/Possible Faulty Core Element Per RO 50-20/79-4 Will Be Observed 1999-03-19
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20209C9331999-07-0808 July 1999 Vols 1 & 2 to SAR for Ma Institute of Technology Nuclear Reactor Lab ML20196K0331999-06-30030 June 1999 Quality Mgt Program for Generation of MITR-II Medical Therapy Facility Beams for Human Therapy, Reflecting Change to Provision 14 ML20205A6551999-03-19019 March 1999 Ro:On 990310,main Ventilation Damper Failed to Close on Receipt of High Radiation Test Signal.Cause Indeterminate. Relays Associated with Main Exhaust Damper/Fans & Main Intake Damper Were Replaced ML20206P5321999-01-0606 January 1999 Ro:On 981229,only One Nuclear Safety Period Scram Channel Was Operable,For Period of Five Minutes.Caused by Placement of Nuclear Safety Sys Channel 1 Input Signal Cable on Wrong Bnc Connector.Placed Channel on Correct Bns Connector ML20199H2371998-12-31031 December 1998 Revised SER for Fission Converter Facility ML20196B7541998-06-30030 June 1998 Mit Research Reactor Nuclear Reactor Lab Ma Inst of Technology,Annual Rept to Us NRC for Period 970701-980630. with ML20217E8071998-03-23023 March 1998 Ro:On 980127,containment Integrity No Longer Existed & Key Switch Was Still 'On' for One of Test & Calibr Procedures. Caused by Retrieving Tool Box from Truck Air Lock.Discussed Occurrence W/Personnel & Will Consider TS Rev Re Key Switch ML20217G2181997-10-0303 October 1997 SER for Fission Converter Facility ML20198P8071997-06-30030 June 1997 Annual Operating Rept for Jul 1996 - June 1997 ML20137L5901997-04-0303 April 1997 Safety Evaluation Supporting Amend 30 to License R-37 ML20129B3201996-06-30030 June 1996 Annual Rept to Us NRC for Period 950701-960630 ML20092K8281995-09-22022 September 1995 Corrective Action for RO 50-20/1995-4,re Abnormal Situations Which Occurred on 950711 ML20091K3091995-08-18018 August 1995 Ro:On 950809,malfunction of Shim Blade Drive Mechanism Occurred.Determined That Mechanism Experienced Intermittent Slippage When Blade Being Withdrawn.Blade Drive Mechanism Assembly Procedure PM 7.1.1.1 Will Be Reviewed ML20086T7571995-07-28028 July 1995 RO 50-20/1995-4:on 950720,operated W/One Shim Blade Fully Inserted.Caused by Failure of Licensed Operators to Follow Written Procedure for Investigating Mismatch.Failed Proximity Switches Replaced ML20092K2301995-06-30030 June 1995 Mit Research Reactor Annual Rept to NRC for Period Jul 1994 - June 1995 ML20082B8551995-03-30030 March 1995 RO 50-20/1995-2:on 950320,operation of Reactor in natural- Circulation Mode W/O Required Two Operable Nuclear Safety Level Channels Set to Scram at or Less than 100 Kw,Mitr TS 3.7 ML20078S2241995-02-17017 February 1995 Reportable Occurrence 50-020/95-01:on 950206,voltage & Specific Gravity Measurements of Cell of Emergency Battery Bank Recorded at Less than Specified Weekly SR in TS 4.3.5. C/A Will Modify SR to Monthly ML20072T3041994-06-30030 June 1994 Annual Rept for Mit Research Reactor for 930701-940630 ML20058Q2371993-12-17017 December 1993 RO 50-20/1993-1:on 931207,operation W/Fewer than Required Number of 100 Kw Nuclear Safety Sys Level Channels Identified.Caused by Faulty four-segment Relay in low-range Amplifier of Channel 5.Amplifier Replaced ML20056G8011993-06-30030 June 1993 Mit Research Reactor Nuclear Reactor Lab Mit,Annual Rept to NRC for Period 920701-930630 ML20128P4371993-02-16016 February 1993 Safety Evaluation Supporting Amend 27 to License R-37 ML20073H1451992-12-0909 December 1992 Study of MITR-II Core Tank Aging for Relicensing Consideration ML20114D9261992-06-30030 June 1992 Mit Research Reactor Nuclear Reactor Lab Mit,Annual Rept to NRC for 910701-920630 ML20094K0721992-03-12012 March 1992 RO 50-020/1992-2:on 911030,three Fission Chambers Missing During Annual Inventory of SNM Matl.Search for Missing Chambers Completed on 920311 W/O Locating Chambers.Snm Inventory for 1991 Has Been Amended ML20090D6661992-03-0202 March 1992 RO 50-20/92-1 on:920218,malfunction Occurred in Reactor Analog Controller Due to Improper Performance of Increase in Reactor Power.Caused by Operator Error.Analog Automatic Control Sys Investigated & Temporarily Repaired ML20082K5911991-08-22022 August 1991 RO 50-20/1991-1:on 910813,fission Product Gas Levels Rose from Normal Operating Levels to Max of 15% of Mpc.Caused by Small Blister on One of Element MIT-17 Fuel Plates. Corrective Action Consisted of Removing MIT-17 from Core ML20082L8451991-06-30030 June 1991 Mit Research Reactor Annual Rept to NRC for Jul 1990 to June 1991 ML20058N5741990-08-10010 August 1990 QA Program for MITR-II Spent Fuel Shipment ML20059G4331990-06-30030 June 1990 Mit Research Reactor Annual Rept to NRC for Jul 1989 - June 1990 ML20012D9651990-03-22022 March 1990 RO 50-20/1990-1:on 900312,incorrect Calculation of Estimated Critical Position (ECP) Attained During Reactor Startup. Caused by Failure to Check Second Portion of ECP Calculation Performed by Individual in Training ML20012C2771990-03-0909 March 1990 SER for BWR Coolant Chemistry Loop to Be Installed & Operated in Mitr ML20248C7111989-08-0404 August 1989 RO 50-20/1989-2:on 890726,console Operator Received Abnormal Bldg Alarm.Leak Test Revealed Crack on Sys Ref Line Which Senses Atmospheric Pressure Outside Containment.All Polyethylene Tubing in Sys Replaced ML20247H7041989-06-30030 June 1989 Mit Research Reactor Annual Rept for Jul 1988 - June 1989 ML20246P3071989-03-17017 March 1989 RO 50-20/1989-1:on 890308,operation W/Fewer than Required Number of Nuclear Safety Channel Level Scrams Due to Lack of High Voltage Power Supply (Hvps) to Channel 5.Reactor Shut Down & Hvps Energized to Supply Channel 5 ML20195K1161988-10-24024 October 1988 Suppl to PWR Loop Ser:Use of Large Circulating Pump ML20154J6221988-08-29029 August 1988 Revised Mit Research Reactor Annual Rept to NRC for Jul 1987 - June 1988 ML20153F5591988-06-30030 June 1988 Mit Research Reactor Annual Rept to NRC for Jul 1987 - June 1988 ML20154M6501988-05-26026 May 1988 RO 50-20/1988-1:on 880511,incipient Fuel Clad Defect Detected.Caused by Small Blister on One Element MIT-12 Fuel Plate.Element MIT-12 Removed from Core ML20151R7341988-04-19019 April 1988 Sser for PWR Coolant Chemistry Loop (Pccl) MITNRL-020 ML20236S4931987-11-19019 November 1987 RO 50-20/1987-2:on 871110,improper Performance of Reactor Reshim Resulted in Excessive Power Rise.Caused by Operator Error.Operator Suspended from All Licensed Duties Pending Further Review of Circumstances & Disciplinary Measures ML20237K6121987-06-30030 June 1987 Mit Research Reactor Annual Rept to NRC for Jul 1986 - June 1987 ML20151R7271987-02-13013 February 1987 SER for PWR Coolant Chemistry Loop (Pccl) MITNRL-020 ML20213G0601986-11-0606 November 1986 RO 50-20/1986-3:on 861027,shim Blade 6 Could Not Operate at full-out Position Due to Mechanical Interference.Caused by Misalignment of Blade Proximity Switch Tube.Switch Tube Reinstalled Properly ML20214V9001986-10-17017 October 1986 Revised RO 50-20/1986-2:on 861008,elevated Levels of Fission Gases Discovered in Primary Containment.Cause Undetermined. Refueling Initiated & Element MIT-19 Removed.All in-core Elements Sipped.No Abnormalities Found ML20214H9541986-10-17017 October 1986 RO 50-020/86-02:on 861008,elevated Levels of Fission Gases in Primary Containment Observed.Cause Unknown.Element MIT-19 Removed from Core & All in-core Elements Sipped ML20148B3011986-06-30030 June 1986 Mit Research Reactor Annual Rept to NRC for Period Jul 1985 - June 1986 ML20154S4591986-02-28028 February 1986 RO 50-20/1986-1:on 860219,fission Product Gas Levels Rose from Normal Operating Levels.Caused by Blister on Surface of Outer Fuel Plate of Element MIT-11.Element MIT-11 Removed from Core ML20214R3811986-01-31031 January 1986 Rept of Educational & Research Activities for Academic/ FY84-85 W/Selected Data from Previous Yrs ML20137G3661985-07-23023 July 1985 RO 50-20/1985-2:on 850715,defect in Fuel Element Cladding Observed.Caused by High Rate of Outgassing from Fuel Element MIT-32.Defective Element Removed ML20133H4081985-06-30030 June 1985 Mit Research Reactor Annual Rept to Us NRC for Jul 1984 - June 1985 1999-07-08
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Text
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NUCLEAR REACTOR LABORATORY -
AN INTERDEPARTMENTAL CENTER OF \ /
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MASSACHUSETTS INSTITUTE OF TECHNOLOGY ~
JOHN A. BERNARD 138 Albany Street. Cambndge, MA 02139-4296 Advahon Analysis Director Coolant Chemistry Director of Reactor Operations Telefax Nc47) 3-7}00 Tel. No. (ewy - u* Nuclear Medicine Pnncipal Research Engineer Reactor Engineering 1
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March 19,1999 U.S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, D.C. 205.55
Subject:
Reportable Occurrence 50-20/1999-1, Failure of Main Ventilation Damper to Close on Receipt of a High Radiation Test Signal.
Dear Sir or Madam:
The Massachusetts Institute of Technology hereby submits a report of an occurrence at the MIT Research Reactor (MITR) in accordance with paragraph 7.13.2(d) of the Technical Specifications. An initial report was made by telephone to NRC Region I on 12 March 1999.
The format and content of this report arc based on Regulatory Guide 1.16, Revision 1.
I
- 1. Renort No.: 50-20/1999-1 2a. Report Date; 19 March 1999 .
2b. Date of Occurrence: 10 March 1999 i
- 3. Facility: MIT Nuclear Reactor Laboratory 0 138 Albany Street i Cambridge, MA 02139 )
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- 4. Identification of Occurrence: Routine tests of the reactor building ventilation dampers were l performed on 10 March 1999, in accordance with written procedures. One of these tests involves l verification that the main ventilation dampers close on receipt of a high radiation signal. In addition, I the ventilation fans should stop. An initial test found that the main dampers failed to close and the l fans did not stop. The auxiliary ventilation dampers did close as they are designed to de in the event )
of a main damper failure. The test was then repeated several times and all dampers functioned properly. The individual who performed the test notified the Reactor Superintendent and entered ajob ,, , e in tne official work book (No. E2794, dated 3-10-99) with further investigation scheduled for the 4 b i next reactor shutdown which was slated for l' '4 arch 1999. )
The above test results were discussed at a regularly scheduled Operations / Radiation Protection I review meeting that was held on 11 March 1999 and it was decided to investigate the damper closure issue immediately. The concern was that there may have been a violation of Technical Specification No. 3.8.2(a) which stipulates that a ventilation damper shall close within a specified time of receipt of 100^19 9903310038 990319 PDR S ADOCK 05000020 Y.
PORjf
l U.S. Nuclear Regulatory Commission 1 4
March 19,1999 i Page 2 1 a hikh radiation signal. (Nois: The auxiliary dampers did close but they are not required to meet the
. time requirement.) Accordingly, the reactor was shut down on 11 March 1999. No cause for the initial test failure was found and the failure could not be repeated. The closure time of the auxiliary damper was modified to satisfy Technical Specification No. 3.8.2(a), and the reactor was restarted.
- 5. Conditions Prior to Occurrence: Tne reactor wa; eperating at 1 MW. >
- 6. Description of Occurrence: Figure One is a diagram of the circuitry associated with the plenum gas and particulate monitors and the ventilation dampers. The system is redundant in that there are two sets of plenum gas and particulate monitors, a main and auxiliary intake damper, and a main and auxiliary exhaust damper. The main and auxiliary dampers are in series. The system is interlocked so that receipt of a high radiation signal on any one of the four plenum monitors will stop the ventilation fans and cause the main ventilation dampers to close Also, if those dampers fail to close within ten seconds, the auxiliary dampers will close as the result of a second interlock. The main damper interlock is tested by lowering the trip on one of the plenum monitors to the background level.
- 7. Descriotion of Anoarent Cause of Occurrence: The reactor was shut down on 11 March 1999
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to check both electronic 'and mechanical systems. Also, a review of records was conducted. The following conclusions were reached:
a) A similar sequence of events (initial failure of main dampers to close; closure of auxiliary dampers) under different conditions occurred on two previous occasions,7 August 1998 and 4 December 1998. See Table One, Note ' '
b) The expected interlock sequence (fans stop, main dampers close; auxiliary dampers remain open) was observed to occur on all tests excep' those noted j above. Table One lists all tests since August 1998, when the system last i underwent major maintenance.
c) Physical inspection of the dampers showed no mechanical defects. (No.ts: If a mechanical defect were present, then one would expect the fans to stop and the main dampers to remain open. A mechanical failure does not explain the continued operation of the fans.)
d) Physical inspection and testing of the ratemeters (the plenum monitors) showed no defects. These are all newly installed equipment. As is evident from Figure One, a failure in the ratemeter would have resulted in the auxiliary dampers retraining open also, e) Physical inspection and testing of the relays that control the exhaust damper / fens, intake damper, and auxiliary dampers revealed no defects.
However, an intermittent failure of the 'irst two of these relays could not be eliminated as a possible failure mechanir n. j f) No errors were noted in the conduct of the test procedure.
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U.S. Nuclear Regulatory Commission March 19,1999 Page 3 ;
l 120 Vac V When the relays deenergize they Contacts open when Perform the following acts:
Plenum high radiation condition Part 1 - - -/ occurs deenergizing these relays coils C6A - Deenergizes the exhaust fan and core purge blower.
j Closes both main dampers.
C6B - Denergizes the intake fan.
Gas 1
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DI Closes auxiliary dampers if associated main damper is still open 10 s after receipt of a trip signal.
C6B D1 (C6A e
1 Plenum ---f Part 2 Plenum Gas 2
_ _ _/
I V 1 GND !
Figure One: Schematic of Effluent Monitor - Interlock Damper
a . -
U.S. Nuclear Regulatory Commission March 19,1999 Page 4 1 1
TABLE ONE Chronology of Tests of Ef0uent Monitor - Ventilation System Interlocks I
!) ale Test Result Time Since Last Test
. . _ l 08/07/98 Initial Test Unsatisfactory; (Major Maintenance) l Subsequent Tests Satisfactory i (3) J l
08/21/98 Satisfactory 2 Weeks 09/17/98 Satisfactory 4 Weeks 10/15/98 Satisfactory 4 Weeks 10/19/98 Satisfactory 4 Days 11/17/98 Satisfactory 4 Weeks 12/04/98 InitialTest Unsatisfactory; 2 Weeks Subsequent Tests Satisfactory (3) 12/28/98 Satisfactory 4 Weeks 02/01/99 Satisfactory 4 Weeks 02/(M/99 Satisfactory 3 Days 02/22/99 Satisfactory 3 Weeks I 02/23/99 Satisfactory 1 Day 03/10/99 Initial Test Unsatistactory; 2 Weeks Subsequent Tests Satisfactory i
i Notes: (1) Required test frequency is monthly.
(2) All tests prior to 08/07/98 were satisfactory.
(3) Reactor was shut down at time of test and fans were not operating.
Maintenance was in progress on the ventilation system and it was not clear if the failure was related to the on-going maintenance. Tests performed upon completion of the maintenance were satisfactory. j l
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U.S. Nuclear Regulatory Commission March 19,1999 Page 5
- 8. Ana5vsis of Occurrence: There was no safety significance to this occurrence because of the redundancy of the dampers in the ventilation system. The auxiliary dampers always closed within ten seconds of receipt of a high radiation signal and the amount of radiation available for release in ten seconds would be minor. This is because the MITR operates at low temperature and atmospheric pressure and because it uses cermet fuel. Hence, even if something as serious as the clad failure were to occur, a radiation release would be limited by the need for the fission products to diffuse through the fuel. Otha ' actors that lead to this conclusion are that:
a) The reactor console operator has the option to close the main intake and exhaust dampers maoually. This can be done from the reactor control room; and b) Writtea procedures instruct the operator to close the main ventilation dampers should they not close in an actual emergency.
- 9. Corrective Action: The immediate corrective action was to replace the relays associated with the main exhaust damper / fans and the main intake damper. Subsequent testing showed all interlocks to be functional. However, given the intermittent nature of this problem,it can not be assumed that the situation has been corrected.. Accordingly, the closing time for the auxiliary dampers has been reduced to meet the requirements of Technical Specification No. 3.8.2(a).
Long-term corrective action will consist of continued testing of the interlock. (Mqtc.: An increased test frequency (daily) has been instituted for one week. No repetition of the problem has been found thus far. A long-term increased test frequency is undesirable because it will cause damage to the damper gaskets.)
- 10. Failure Data: None.
Since y, -
- . s j fW& Gilt Thomas H. ewton, Jr., P.E. Edward S. La , NE Asst. Superintendent for Engineering Asst. Superintendent for Operations kG ohn A. Bernard, Ph.D., iP,P.E.
I)irector