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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of Shim Blade Drive Mechanism Occurred.Determined That Mechanism Experienced Intermittent Slippage When Blade Being Withdrawn.Blade Drive Mechanism Assembly Procedure PM 7.1.1.1 Will Be Reviewed ML20086T7571995-07-28028 July 1995 RO 50-20/1995-4:on 950720,operated W/One Shim Blade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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- 1"h 7 NUCLEAR REACTOR LABORATORY <[pt - Q AN INTERDEPARTMENTAL CENTER OF '%Q!%Y MASSACHUSETTS NSTITUTE OF TECHNOLOGY O.K. HARLING 138 Alt.sny Street Cambridge, Mass. 02139 L. CLARK. JR.
Director (617)253-4 2 11 Director of Reactor OperaSons February 28, 1986 Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatnry Commission Attn: Mr. R. Sommers, Reactor Inspector 631 Park Avenue King of Prussia, PA 19406
Subject:
Reportable Occurrence 50-20/1986-1, License R-37 Detection of a Blister on a Fuel Plate Centlemen:
Massachusetts Institute of Technology hereby submits the 10-day report of an occurrence at the MIT Research - Reactor, in accordance with paragraph 7.13.2(d) of the Technical Specifications. An initial report of this occurrence was made by telephone to Region.1 on February 20, 1986.
The format of this report is based on Regulatory Guide 1.16, Revision I.
- 1. Report No: 50-20/1986-1 2a. Report Date: 28 February 1986 2b. ~ Occurrence Date: 19 February 1986
- 3. Facility: MIT Nuclear Recctor Laboratory 138 Albany Street Cambridge, MA 02139
- 4. Identification of Occurrence:
Slightly elevated levels of fission product gases in the air purge that is maintained across the surface of the primary cool-ant had been observed for several weeks. These elevated levels, were intermittent, normally being present' for a few hours follow-ing reactor startup. A visual inspection of the core using alternately light and the Cerenkov radiation to illuminate the fuel plates revealed no abnormalities. Detection by a " sipping" process in which one liter samples of coolant are drawn through each fuel element, collected, and counted was not tried at this time because the results would have been inconclusive given the 8604010224 350 0 \\
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Dr. Thomas E. Murley Page 2 intermittent nature and low magnitude of the elevated gas levels.
Following startup at 1914 on 18 February 1986, elevated fission product gas levels were observed. (Note: The reactor was at power for seven minutes. The maximum fission gas level observed during this interval was approximately 11% of MPC.) . Power was then . reduced in accordance with existing procedures. It was decided to keep the reactor operating but at the reduced power level for several hours in order to generate enough activity so as to be detectable by the " sipping" process. The reactor was shutdown at 0030 on 19 Feb. 1986. All fuel elements were sipped on 19 Feb. 1986. Element MIT-11 was identified as having an ah-
.normally high rate of outgassing. A refueling was then initiated and element MIT-11 was removed from the core. Reactor operation was resumed later on 19 February and fission product gas release levels were observed to be normal.
- 5. Conditiori rior to Occurrence:
Element MIT-11 was first inserted in the re actor's B-Ring on 8 Sept. 1981. It remained in-core continuously until 29 March 1982 when it was removed. It was again inserted la the B-Ring on 16 August 1982 and removed on 27 June 1983. It was used in the C-Ring from 25 February 1985 to 1 April 1985 and again from 27 July 1985 to 19 February 1986, the day on which the blister was detected. The element wss inverted on 23 Sept. 1985. (Note:
Movement of elements between fuel rings, element rotation, and element inversion are standard techniques applied to all MITR fuel . elements as a means of minimizing the effect of flux grad-ients on fuel depletion.) With minor exceptions, the reactor was operated on its normal schedule of 90-100 hours / week of full-power operation during all periods in which element MIT-11 was in the core.
- 6. Description of the Occurrence:
The fission product gas levels obtained in accordance with standard sampling procedures rose from normal operating levels during the two-three wecks preceding the occurrence. This rise was intermittent. An increase to about 11% of MPC was observed for several minutes on 18 Feb.1986. All increases were well be-low the permitted concentrations.
- 7. Description of Apparent Cause of Occurrence:
The apparent cause of this occurrence is a blister on the surface of one of the outer fuel plates of element MIT-11. The presence of this blister was detected during a visual examination (under water) of the element once it had been removed from the core. (The blister is not visible with the element in the core.)
Dr. Thomas E. Murley i
Page 3 The blister is about 3/4 inches in width and 3/8 inches in height. It is at the extreme end of the fuel plate in the " dog-bone" regica. The area of the fuel plate that now contains the blister is such that it would have been at the lower end of the fuel element (i.e., high flux region) for all of its time in core until 23 Sept. 1985 when element MIT-11 was inverted. Upon in-i version, the area now covered by the blister became the upper end of the element (i.e., low flux region). A streak that runs ver-tically through the center of the blister is visible. The streak is initially quite dark and then somewhat lighter. The cause of this blister can not be determined without the use of hot cells and other special facilities not available at MIT. However, the existence of the dark streak suggests staining of the fuel plate, possibly as the result of an inclusion of foreign material at the blister site or from fission products leaked from the fuel matrix.
A simplified drawing showing the location of the blister on MIT-11 is attached to this report. One copy of a slide showing the blister has been sent to Region I. This slide was taken dur-ing the aforementioned visual inspection. The image was taken through. twelve feet of water.
It was not possible to determine if the blister also existed on the inside of the fuel plate in question because the element's end adapter blocks the view. All elements adjacent to MIT-11 were removed from the core and their exterior plates visually examined. No abnormalities were found.
- 8. Analysis of Occurrence:
Quality assurance records on the manufacture of element MIT-11 do not indicate any deviations from the MITR element spec-ifications for the plate on which the blister has f o rmed. Ele-ment MIT-11 had been in-core while 41,613.84 MWH of energy were produced. It has 399.87 grams of its original 506 gram loading of U-235 remaining. The point of peak burnup on MIT-11 was 49.09% of the allowed fission density (1.8.1021fissions /cc). The element as a whole had only attained 21.0% of the Ifmit. Primary coolant chemistry is carefully monitored. The three parameters measured (pH, chloride, conduutivity) have generally been as specified. The few deviations that have occurred were too brief and of too low a magnitude to have caused this occurrence.
Relative to effluent releases, the combination of standard sampling procedures and the existence of procedures for handling any abnormalities in the sampling results means that the problem was quickly diagnosed, identified, and corrected. No significant release occurred.
Dr. Thonca E. Murlsy Page 4
- 9. Corrective Action:
The-immediate corrective actic" consisted of removing element MIT-11 from the core. Fission product gas levels subse-quently decreased and are currently what was measured prior to the occurrence. All other in-core elements have been " sipped" and no abnormalitites were found.
- 10. Failure Data:
A cladding failure occurred to a "4M" series element in June 1979. Refer to ROR #50-20/79-4 dtd. 2 July 1979 and #50-20/79-4A dated 26 November 1980. Excess outgtssing occcurred in an "MIT" series element in Sept. 1983 and in another in July 1985. Refer to ROR #50-20/83-2 and #50-20/85-2. The current failure was less severe than the one in 1979. ("MIT" series fuel was made by Atomics International. The "4M" series by Gulf Atomic.) The ex-istence of a gradual and a slight increase in the fission product levels in the MITR's primary coolant was reported to Region I as a matter of information on 17 Aug. 1982. One element, MIT-21, was identified as being suspect at that time. MIT-li was in the core during part of 1982 but not during the months in which the elevated fission product gas levels were detected.
Operating experience with fuel from both manufacturers has been good, except as noted below. Of 43 elements made by Culf Atomic, (35 elements, 525 plates) have been permanently discharg-ed from the core after peak burnup approached the license limit.
Seven other elements (105 plates) are still in use. One failed in 1979 as reported' earlier, at an average burnup of 32.5%.
Average burnups on the Gulf Atomic fuel are in the range 42-44%.
(Note: It was incorrectly stated in ROR #50-20/85-2 that 41 of the Gulf Atomic elements had been permanently discharged.) Of the 36 elements made by AI and now in use, three elements (45 21 platee) have peak fission densities of 1.58 x 20 f/ce, average burnup 37.4%. 33 other elements now in use (495 plates) have peak fission densities in the range 0.14-0.97 x 1021gfce, on the basis of the above experience, the failures are very likely fabrication defects and not generic problems.
Sincerely, e k0 J A John A. Bernard , Ph.D Lincoln Clark, Jr.
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Superintendent Director of Operations JAP /gw cc: MITRSC USNRC-OMIPC USNRC-DMB
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Schematic of Fuel Element MIT-ll Showing Blister
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