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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
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- Nucicar !!cactor Laboratory The University of Michigan Ford Nuclear Reactor Phoenix Memorial Laboratory 2301 Bonisteel Boulevard November 25, 1992 Docket 50-2 License R-28 United Staten Nuclear Regulatory Commission A t t.n : Document Control Desk Wauhington, D.C. 20555 .
Reportable Occurrence No. 16 ~
Reactor Startup wi t.h Power Level Deviation Interlock Out. of .
Comminaion (Technical Specifications, Table 3.2)
Gent 1emon:
This letter is Reportable occurrence No. 16, startup of the Ford Nuclear Reactor with the power level deviation interlock as required b3 Technical specifications, Table 3.2, out of commission.
The event occurred on the afternoon of November 24, 1992, during a startup to cheth core reactivity that followed the performance of reactor pre-startup Checklist A. The fact that the interlock was out of commission was discovered during a subsequent performance of Checklist A on the midnight shift, November 25, 1992.
Sequence of Events on Tuesday, hvember 24, 1992, during a routine maintenance period, the shim nmge - control rod interlock system was removed from the reactor control system. The modification hc.d been reviewed and _
approved by t.h + facility Safety Review Committee on October 6, 1992.
Following the wi. ring modifications, a reactor pre-startup Checklist A was conducted to test the modification and to confirm the operation of the reactor control system. A wiring error had been raade during the modification that disabled the interlock that drops the reactor out of automatic control if the Linear Level neutron detection system indicated power is five percent below the automatic control setpoint, The fact that. this interlock was disabled was not discovered during the performance of Checklist A. A reconstruction of the performance of the check 1ist revealed the possible reason. A copy of step 33 of Checklist A is enclosed for reference.
- 1. Step 33 is the d rop-ou t -o f-au to test.
- 2. A senior reactor operator was at the console; a trainee was assisting with the checkout.
- 3. In step 33.a, the Linear Level selector switch is set to CALIBRATE which gives a power indication of 100%.
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-4 Reportable Occurrence No.'_16--
- i' United States NuclearfRegulatory. Commission-November 25, 1992 9
- 4. In step 33.b, the servo control _setpoint is set to 97%:
which permits the control rod to be put in automatic control. Indicated power must be at least 2% above the automatic control setpointito go--into automatic.
- 5. In Step 33.c. the control rod is manually withdrawn to 17-i_ inches. Zero to 24 inches is the full stroke of theirod.
l 6. In step 33.d, the reactor is placed in._ automatic control._ ~-c '
o Since the indication (100%)is above-the setpoint(97%),_the rod will begin to insert.
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- 7. In step 33.e, when the control rod is at 15 inches-and-going in, the operator increases the setpoint. _W hen the setpoint reaches 100%, control rod n.otion- stops.- As the setpoint is increased above 100%, the control' rod ;
withdraws. At a setpoint of 105%, the control rod drops out of automatic, satisfying the interlock. ,
- 8. In this case -the trainee must have increased the setpoint too-slowly. It-takes approximately'28 seconds for the~ -
control rod to travel from 15. inches to 0 inches. If she '
did not reach a 100% setpoint within that 28. seconds, the control rod would reach the lower.1'imit (0-inches)-and thef control-rod would drop out of automatic.= Reaching'the lower limit is accompanied =by a rundown 1(automatic insertion) of the' shim-safety rods.
- 9. In -f act the- drop-out-of-auto 1was ' observed by the E senior reactor operator, as wasca-cundown._ He misinterpreted-the rundown and-believed tho' drop-out-of-auto was due-to-ther Linear Level-indication being-five_ percent-below the ~
r setpoint, thus satisfying. step 32.- ,
Following the " successful" completion of Checklist A,_the_: reactor:
was started up to ~approximately~5_kw to perform.asshutdown margin and excess reactivity 1 check. The control rod'was withdrawn:toJ24
- inches-and the-shim. rods to crit'icality. The'reactorewastnever .
placed in automaticEcontrol. Following the reactivity measurement, the reactor was: shutdown and secured.
-r The midnight shift. November 25, 1992, performed a Checklist A--in
- preparation for. power-operation. LThe crew was'not'able1to .
successfully complete Step.33.s -The Assistant ManagerLand'the, F Electrical. Engineer were? notified 4 - Between 2 a.m.-and 8 a.m.., the procedure was retried, the wiring. mistake was discovered-and-corrected, and-Checklist A was satisfactorily completed..
- The personnel who_had conducted the' original Checklist A were '
-interviewed and the.seriesTof-errors.-and misinterpretations _were- ,
- resolved. At_9 a.m.', November-25, 1992, the: Reactor Manager gave-
- permission to
- startup the reactor for power operation.
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L Reportable Occurrence No. 16
. United States Nuclear Regulatory Commission November 25, 1992 l
Consequences of Operating Wi th t.he pc..ar Level Deviation Interlock Out. of Commission The worst possible consequence of operating with the power-level deviation interlock out of commission would be failure of the automatic control system followed by continuous withdrawal of the contro.1 rod. If the control rod were withdrawn from zero to 24 inches, 0.00475 delta K/K reactivity would be inserted. The-resultant nLable period would be t. seconds. At a period of 10 3 secotid s , an automatic rundown of t.he shim-safety rods occurs- The period scram setpoint is 5 seconds.
s Corrective Action The following changes to Checklist A will be made to ensure proper performance of Step 33.
33.c Withdraw the control rod to 23 inches.
33.e As the control rod begins to insert, increase the setpoint t. o 106%.
33.g Verify final control rod position above 5 inches.
Step 33.c will provide more time to adjust the setpoint. Step 33.g will ensure that a control rod lower limit d rop- o u t.-o f -au t o is not misinterpreted as a powe r level deviat ion drop-out-o f-nu to.
As a more general corrective action, when a modification is made, the functional changes related to the modification will be tested and verifled by the quality assurance. team members directly responsible for the modification. The Electrical Engineer was present during the initial performance of Checklist A, but neither he nor any other member of the quality assurance team was observing the pe r f o rmarm e of the checklist step-by-step.
Sincerely, Ronald F. Fleming Director xc: i> r . Wil'11am C. Kelly, Vice president. for Research Safety Review Committee Members Reactor Operations Staff United States Nuclear Regulatory Commission Attn: Charles Norelius 799 Roosevelt Road Glen Ellyn, .Ill i nc i s 60137 i.
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l r- FNR CONTROL SYSTEM STARTUP CHECELIST 'A' (continued)
Initial
- 30. Energize Linear Level automatic control unit.
- 31. Perform Log N channel tests:
- a. Turn LOG N test switch to positions 1, 2, and 3 to check calibration of Log N meter and recorder,
- b. Return Log N test switch to OPERATE.
- c. Turn Log N period test switch from OPERATE to CALIBRATE and check the calibration of the period meter and recorder,
- d. Press SCRAM RESET button. .
- e. Switch period recorder 0FF while withdrawing control rod and verify control rod withdrawal inhibit. _
- f. Return period recorder switch to the ON position. s 8 Turn Log N TRIP TEST ADJUST slowly to an indicated 30 second period and verif y control rod withdrawa! inhibit,
- h. Check auto rundown at 10 seconds.
- 1. Return Log N test circuitry to OPERATE.
- 32. Perform Linear Level rundown test,
- a. Simultaneously press TEST button and adjust potentiometer to read 115X.
- b. Note auto rundown,
- c. Adjust potentiometer to read 95X and release TEST button.
- d. Depress auto rundown RESET button.
- 33. Perform drop-out-of-auto test,
- a. Set Linear Level range selector switch to calibrate, j21 b, Set servo control setpoint at 97%.
- c. Withdraw control rod to 17.0 inches.
- d. Depress AUTO ON push button on console,
- e. When control rod inserts to 15.0 inches move setpoint to 106. _
- f. Note drop out of-auto control.
- 34. Perform control rod lower limit rundown test.
- 3. Set auto-control setpoint at 97%.
- b. Depress AUTO ON button, l16
- c. Note auto rundown when control rod reaches lower limit,
- d. Depress auto rundown RESET button.
- e. Set Linear Level range selector switch to lowest possible operating range.
- 35. Perform Linear Level abnormal test.
- a. Press and hold LINEAR LEVEL ABHORMAL TEST button.
- b. Note LIN LEV ABN alarm.
c Note 110% reading on console Linear Level meter.
- d. Release TEST button.
- 36. Return magnet contact simulator switches to 0FF.
- 37. Return shim range bypass switch to NONE BYPASSED.
- 38. Unbypass SHIM RANGE DEFEATED scram function.
- 39. Verify D20 LOW LEVEL alarm unbypassed.
- 40. Check po61 lev i functions.
- a. Test alarm at 5 inches.
- b. Test auto rundown at 12 inches.
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