|
---|
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
. - - . _ _ - _ _ - _ -
!=. - Nuclear Reactor Laboratory
( . .
The University of Michigan
- . . Ford Nuclear Reactor Phoenix Memorial Laboratory 2301 Bonisteel Boulevard 1 Ann Arbor, Michigan 48109-2100 (313) 764-6220 May 3, 1989 Docket 50-2
' License R-28 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. '20555 Reportable Occurrence No. 12 Release of Fission products from the Ford Nuclear Reactor Gentlemen:
ThisLletter.is a follow-up concerning our Reportable Occurrence No. 12-submitted on January 16,.1989.
Summary of Initial Fission Product Detection A fifteen minute analysis taken on December 27, 1988, after the reactor had been shutdown for five days, showed the following concentrations, in the reactor pool water, of the fission products,. iodine-131 and xenon-133:
I131 2.76x10-6 microcurie /ml Xe133 1. 3 9x10- 5 microcurie /ml The reactor was brought to full power on January 4, 1989.
A fifteen minute analysis of pool water sampled on that day showed no iodine-131. Xenon-133 concentration was about 25% of that measured December 27, 1988.' High background activity associated with reactor operation may have prevented detection of low concentrations of iodine-131. The pool water sample drawn on January 4, 1989 was analyzed again after five days of decay.
Iodine-131 was detected in the five-day analysis. It ic possible that iodine-131 was present in pool water before December 27, 1988. Background activity may have been too high to permit its detection in fifteen-minute analyses, and the iodine-131 could have decayed below detectable levels by the time our routine two-week analyses were performed.
We reanalyzed pool water data for the preceding year, this time looking for xenon-133 peaks. We had not previously looked for xenon-133 as a fission product indicator. We found low levels of xenon-133 in pool water back to October, 1988, but none earlier than that.
l 8905120220 890503 le/14 f PDR ADOCK 05000002 PDC bl ' O S
e w -
, i 4
'; . United States Nuclear. Regulatory. Commission l
, May 3, 1989 i
An analysis of water in the facility's radioactive ;
liquid retention tanks was performed. All liquids from the reactor facility are dumped into the retention tanks and analyzed .
prior to' discharge into the Ann Arbor sewer system. Between f December 27, 1988 and January 4, 1989, a pool water demineralized i was recharged. The recharge water was discharged into the .,
retention tanks.' The following concentrations of iodine-131 and cesium-137 were found:
l 1131 9.44x10-8 microcurie /ml Cs137 3.04x10-8 microcurie /ml l In an attempt to confirm the release of fission products, air samples were taken at several locations above the surface of the reactor pool on-January 5, 1988. Analysis of a high volume sample
.taken.directly over the reactor core showed very small, but detectable quantities of rubidium-88 (daughter of krypton-88) and cesium-138 (daughter of xenon-138). Representative concentrations were:
Rb88 2. 3 5x10- 10 microcurie /ml-of air Cs138 4.47x10-11 microcurie /ml of air Corrective Action Fuel elements were removed from the core one at a time and were replaced ^by other elements. When the reactor was returned to power, air samples and pool water samples were taken to determine if removal of a particular element reduced or eliminated fission t
product generation. Using this technique, one element was found to be releasing fission products, our element number 204. The element was first installed in the reactor core on April 27,-1987.
The element was manufactured by Babcock and Wilcox.
After removal of element 204, fission product activity in the reactor pool water dropped below detectable levels. We performed additional tests of every other element in the core to verify that a minute leak did not exist in another element. The reactor was operated in natural circulation at a power of 80 kilowatts to promote upward water flow through the elements. Maximum natural circulation power is 100 kilowatts. A liquid sipping tube was placed directly over each element in turn. Water from above each element was pumped through an ion exchange resin column to collect and concentrate any fission product ions. No fission products were detected using this technique. In addition, a 500 milliliter sample of water was drawn from above each element. pc'assium iodide carrier and silver nitrate were mixed into each ample to '
precipitate fission product iodine in the form of silver iodide.
None was detected.
i As the result of thewe tests, it was concluded that fuel element 204 was the single source of fission product releases. The page 2 1 1
i
L a .
(. United States Nuclear Regulatory Commission May 3, 1989 manufacturer has'been contacted to review its manufacturing process. While in the core, element 204 was always surrounded by J other elements. It was never in-a position, such as along the Jperimeter of the core, where it could have been damaged by experimental devices or routine operations evolutions.
Procedural' Changes Our regular pool-water analyses were conducted fifteen minutes and two weeks after sampling. The two-week analysis has been replaced by a one-week analysis. In'seven days, the source of high background, sodium-24, has decayed away, but relatively short-lived fission products such as iodine-131 are still detectable. Based on past analyses, fission products that were detectable after one week had decayed below detectable levels after~two weeks.
During the search for the leaking fuel element, we found that xenon-133 was a significantly more sensitive fission product indicator than iodine-131. Consequently, xenon-133 was added to our analysis library. Molybdenum-99 also was added to provide a strong indicator of particulate releases.
On.a monthly basis, air samples will be taken above the reactor pool. Particulate filters will be used to trap fission product daughters, rubidium-88 and cesium-138. A charcoal filter will be used to trap any fission product iodine.
Sincerely,
-/
Ronald F. Fleming Director xc: Dr. Linda S. Wilson, Vice President for Research John Jones, Director, Radiation Control Service Ken Schatzle, Director, OSEH Director, Region III, United States Nuclear Regulatory Commission Safety Review Committee Members i
L Page 3