IR 05000083/1985003

Insp Rept 50-083/85-03 on 851009-11.No Violation or Deviation Noted.Major Areas Inspected:Licensee Action on Previous Enforcement Matters & Sticking Safety Control Blade 3

ML20198D917
Person / Time
Site:	05000083
Issue date:	11/04/1985
From:	Debs B, Poertner W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20198D912	List: IR 05000083/1985003 ML20198D909
References
50-083-85-03, 50-83-85-3, NUDOCS 8511130077
Download: ML20198D917 (4)

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an niog UNITE 3 STATES

.w8 'o NUCLEAR REGULATORY COMMISSION

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Report No.: 50-83/85-03-

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Licensee: University of Florida 202 Nuclear Sciences Center

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Gainesville, FL 32601

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. Docket Nos'.: 50-83 License No.: .R-56 Facility Name: University of Florida Training Reactor (UFTR)

Inspection Conducted: October 9 - 11, 1985 e

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Inspector: _ k d 1Cm 11/4 /Bs'

W. K. Poertner / Ddte' Signed

' Approved by: [

jy B. T. Debs,' Acting Section Chief

///t//W Dhti! Signed J' Operational Programs Section

'. Division of Reactor Safety i

SUMMARY Scope: This special, announced inspection involved 15 inspector-hours on site-in the area of sticking safety control blade No. Results: No violations or deviations were identified.

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[ REPORT DETAILS Persons Contact 6d Licensee Employees

• Dr. W.'G. Vernetson, Acting. Director of Nuclear Facilities P. M. Whaley, Acting Reactor Manager

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H. Gogun, Senior Reactor Operator G. W. Fogle, Reactor Operator-

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• Attended exit interview Exit Interview The inspection scope and findings were summarized on October 11, 1985, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the license The--licensee did not. identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio . Licensee Action on Previous Enforcement Matters (0 pen) Deviation 85-01-01 - Failure to comply with FSAR Section 17, which commits the licensee to ANSI N402-1976, Section 2.4 " Design Control".

The inspector reviewed Standard Operating Procedure (SOP) 0.4,-10 CFR 50.59, Evaluation and Determination. The inspector also -reviewed Draft S0P 0.3, Control of Modifications, which is scheduled to be approved at the_ next-Reactor Safety Review Subcommittee (RSRS) meeting. The inspector reviewed the 50.59 evaluation for the installation of the vent / diluting fan interlock with the evacuation alarm. The 50.59 also included acceptance of .the wiring diagram for the modification. This item will remain open until the licensee has completed its procedures update which is scheduled for completion early in 198 . Unresolved Items Unresolved items were not identified during this inspectio . Sticking Safety Control Blade No. 3

, Background On January 26, 1985, safety control Blade-3 failed to drop from the 27-30 percent removed position. At the time of discovery, the unit was shutdown and safety blade-3 was withdrawn and the clutch current e

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interrupted to demonstrate the effect of rapid insertion of a large negative reactivity at a subcritical configuration following shutdown from full power. Licensee evaluation determined that the source of the binding was located outside the core region in the right angle shaft-gear box clutch area. To correct the problem, the gear box and motor clutch assembly were disassembled, cleaned, lubricated, and both bearings on .the right angle motor drive shaft were replaced. The blade was then tested to ensure proper operation prior to returning the unit to servic On September 3,1985, safety blade-3 failed to fully drop from a 64 percent removed position. The rod stuck at about 31 percent remove At the time of discovery, the reactor operator was commencing a power increase from the 1 watt critical positio The operator had accidentally raised safety blade-3 about 20 units instead of the Regulating Blad In returning the rod to its normal position, he felt the response was sluggish so he attempted to drop the rod. The rod dropped to about 31 percent removed and was subsequently driven in with the other three blades to shut the unit down. Licensee evaluation, to date, has determined that the problem is located within the core region; the most likely causes being a problem with the bearings supporting the blade shaft coupling or with the magnesium shroud i housing to blade clearance, either warpage misalignment or loose rivet During this inspection, the licensee commenced unloading the core to allow access to the control blades. The unloading had not been completed prior to the inspector leaving the sit Inspection Effort The inspector reviewed the following procedures:

! Standard Operating Procedure (SOP) - 0.1, Operating Document Controls SOP-0.2, Control of Maintenance SOP-0.4, 10 CFR 50.59, Evaluation and Determination 50P-A.1, Pre-operational Checks SOP-A.2, Reactor Startup SOP-A.3, Reactor Operations at Power SOP-A.4, Reactor Shutdown SOP-C.1, Irradiated Fuel Handling SOP-C.2, Fuel Loading SOP-D.1, Radiation Protection and Control SOP-D.2, Radiation Work Permit SOP-D.3, Primary Equipment Pit Entry The inspector reviewed the Off Normal Occurrence Reports for the January 26 and September 3,1985, sticking safety blade-3 events. The inspector reviewed the maintenance procedure to remove safety blade-3 and to perform inspections and maintenance to restore the blade to L

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L l operabilit The inspector also reviewed the 50.59 evaluations performed to allow removal of safety Blade-3 to perform inspections and maintenance and to allow modification of the control blade shroud to enable inspection of the control blad The ' inspector reviewed the operator logs for July through October 1985 and the maintenance log for January -through October 198 The maintenance work which was reviewed appeared to have been adequately reviewed and approved in accordance with the licensee's procedure The inspector also reviewed the 50.59 evaluations _ associated with some of the maintenance work. The console l' were adequately filled out and contained no unrecognized significan. problem The inspector reviewed the Monthly UFTR Utilization and General Activities Reports for February through August 1985 and the RSRS meeting minutes for February through June 198 The inspector reviewed the requalification records for the operators presently licensed at the UFTR . and reviewed the latest approved requalification program approved by NR P C.1 requires that training be conducted 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to fuel handling. The inspector attended the licensee's training session on

~ fuel handling. The inspector reviewed the radiation work ' permits for removing the fuel from the cor The inspector observed - the prepara-tions for and part of the core unloadin No violations or deviations were observed.

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