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| {{Adams | | {{Adams |
| | number = ML20138C511 | | | number = ML20155J161 |
| | issue date = 03/10/1986 | | | issue date = 05/06/1986 |
| | title = Insp Rept 50-083/86-01 on 860218-21.Violation Noted:Failure to Document Safety Review of Mod to Control Blade Shrouds | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-083/86-01 |
| | author name = Burnett P, Jape F | | | author name = Reyes L |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| | addressee name = | | | addressee name = Wethington J |
| | addressee affiliation = | | | addressee affiliation = FLORIDA, UNIV. OF, GAINESVILLE, FL |
| | docket = 05000083 | | | docket = 05000083 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-083-86-01, 50-83-86-1, NUDOCS 8604020516 | | | document report number = NUDOCS 8605220045 |
| | package number = ML20138C489 | | | title reference date = 04-17-1986 |
| | document type = INSPECTION REPORT, NRC-GENERATED, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = CORRESPONDENCE-LETTERS, NRC TO EDUCATIONAL INSTITUTION, OUTGOING CORRESPONDENCE |
| | page count = 6 | | | page count = 1 |
| }} | | }} |
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| i A rth UNITED STATES | | Yk(ud i |
| -[ q'o NUCLEAR REGULATORY COMMISSION
| | MAY 0 61986 UniversfyofFlorida i |
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| | ATTN: M)r. J. A. Wethington Acting Chairman, Nuclear Engineering Sciences Department 202 Nuclear Sciences Center Gainesville, FL 32611 Gentlemen: |
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| | SUBJECT: REPORT NO. 50-83/86-01 Thank you for your response of April 17, 1986, to our Notice of Violation issued on March 27, 1986, concerning activities conducted at your University of Florida Training Reactor facility under NRC License No. R-56. We have evaluated your response and found that it meets the requirements of 10 CFR 2.201. We will examine the implementation of your corrective actions during future inspections. |
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| n REGloN il y j 101 MARIETTA STREET, *I e ATL ANTA, GEORGI A 30323
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| Report No.: 50-83/86-01 Licensee: University of Florida 202 Nuclear Sciences Center Gainesville, FL 32601 Docket No.: 50-83 License No.:.R-56
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| . Facility Name: University of Florida Training Reactor Ir,spection Conducted: February 18 - 21, 1986 :
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| Inspector: dh '
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| ' g P. T. Burnett
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| 6/ / Date Signed Appro ed by: _/7A F. Jape, Sect' ion Chief (/ /
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| 8/4[[d Date Signed Engineering Branch Division of Reactor Safety SUMMARY Scope: This routine, unannounced inspection entailed 26 inspector-hours at the site during normal duty hours, in the areas of maintenance, modifications, and surveillanc Results: One violation was identified: Failure to docisment the safety review required by 10 CFR 50.59 paragraph PDR ADOCK 05000083 O PDR L
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| | We appreciate your cooperation in this matte |
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| REPORT DETAILS Persons Contacted Licensee Employees
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| * J. 0hanian, Chairman of RSRS and Associate Dean for Research, College of Engineering
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| * G. Vernetson, Acting Director of Nuclear Facilities
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| *P. M. Whaley, Acting Reactor Manager Other licensee employees contacted included operators and office personne * Attended exit interview Exit Interview The inspection scope and findings were summarized on February 21, 1986, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection findings. No dissen-ting comments were received from the license Ine licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection. One violation and licensee commitments are listed below: VIO 083/86-01-01: Failure to maintain records of facility changes as required by 10 CFR 50.59(b) paragraph IFI 083/86-01-02: Review SAR paragraph 7.2.3, and revise as necessary by August 31, 1986 - paragraph IFI 083/86-01-03: Review CORA calculations for proper identification of materials, and revise SAR as needed by August 31, 19S5 paragraph IFI 083/86-01-04: Evaluate storage and release of Wigner energy by May 31, 1987 - paragraph . Licensee Action or Previous Enforcement Matters (Closed) Deviation 083/85-01-01: Failure to comply with Section 17 of the Safety Analysis Report and ANSI N402-1976. The licensee has written and approved a series of procedures to implement the requirements on ANSI N402, Quality Assurance Program Requirements for Research Reactors. The organiza-tion 'of the procedures is different from that described in the licensee's letter of April 19, 1985, but it is consistent with later discussions between the licensee and Region II supervisio Each of the 17 program requirements of the standard is addressed in at least one of the new proce-dure .
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| - Unresolved Items No unresolved items were identified in this inspectio .
| | Sincerely, cn))k k OJ% 1h Luis A. Reyes, Acting Director Division of Reactor Projects cc: r. N. J. Diaz, Director of uclear Facilities bec icense Fee Management Branch cument Control Desk tate of Florida i |
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| 5. Reactor Maintenance and Modification (40750)
| | RII R RII RII RII P nett:lb Jay AHprdt VP ciera DV relli 0 / 3./86 Q(/ 2/86 0J/A/86 , /j,/86 -0//,/86 |
| On September 3,1985, the licensee reported that safety blade 3 failed to insert fully when dropped from a partially withdrawn position. A similar event had occurred on January 26, 1985. The licensee then shutdown the reactor for an exhaustive. investigation of the ca'uses of the blade failures and to implement the corrective action dictated by the results of the investigation. -This review and inspection of those activities were facili-tated by the licensee's practice of issuing internal progress reports to mark milestone events during the five-month outag Ultimately, the investigation led to the complete defueling of the reactor, partial removal of the graphite moderator, and complete disassembly of the control blade drives. The cause of the failure to insert was finally traced to a metallized graphite bushing that was frozen to shaft coupling assembly
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| =and had to be pried off for disassembly. The interior of the bushing was found to be rippled with rough wear. patterns. All other shaft bushings on drive 3 as well as the other drives slid off the shafts with eas A decision was made to replace all similar bushings on all drives with new ones of the same original design and material The shaft coupling to safety blade 3 was found to be rusted and scarred, and, in the opinion of the licensee, not serviceable. The decision was made to replace the AISI 1040 steel blade couplings on all four drive units with locally-fabricated couplings of 304 stainless stee To assure that all proposed modifications are evaluated for unreviewed safety question considerations, as required by 10 CFR 50.59, the licensee uses UFTR Form' SOP-0.4A, Unreviewed Safety Question and Determination, to guide the evaluation. Supporting documents are attached to the form as necessary. The inspector reviewed about a dozen of the forms completed during the outage, including that for the modification discussed above, and discussed selected cases with the licensee. In all but one case, the review and documentation were found to be acceptabl The exception was the modification of the control blade shrouds by cutting away part of the top of each shroud to facilitate viewing blade operation.
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| This modification was made early in the outage before the decision to remove the blades and drives totally 'was made. The Safety Analysis Report in paragraph 4.1.1 and Technical Specification 3.2.1(1) both state that the shrouds protect the control blades. However, none of the documentation of the safety review mention the protective function of the shrouds or how that function would be affected by the modification. Discussions with the reactor staff and members of the Reactor Safety Review Subcommittee (RSRS)
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| confirmed that the protective function was discussed during an RSRS meeting and that a conclusion that it was not an unreviewed safety question was reached. The. inspector.found the oral arguments convincing with respect to the safety issue. However, the lack of documentation has been identified as a potential violation: VIO 083/86-01-01: Failure to maintain records of facility changes as required by 10 CFR 50.59(b).
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| Following the completion of the maintenance and modification program, the control / safety blade drop times were measured repeatedly under a variety of conditions:
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| 'a . With no magnetic clutch following reconnecting of all drive components, With the magnetic clutch operating prior to fuel loading, Following fuel loading and the replacement of th'e first layer of shield blocks, and Following restacking of all concrete shield block The maximum average drop time for any rod for any condition was 0.475 seconds and the fastest average was 0.400 second These numbers are well within the one second limit of Technical Specifications, and in the licensee's judgement reflect a return to the as-new co'nditio . Review of the Safety Analysis Report (SAR)
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| The SAR was reviewed to gain familiarity with the facility. In that review, two items were identified ig which the SAR description of the facility did not appear to be accurate: Paragraph 7.2.3 describes operation of the control rod inhibit system and automatic control system, which is different from the performance described in Technical Specification 3. Surveillance procedures confirm performance in conformance to the requirements of Technical Specification Figure 4-16, which describes _ material areas used in the CORA computer program analysis of reactor neutronics, labels an area as water which properly should be graphit At the exit interview, the licensee made two commitments, which will be tracked as inspector followup items: IFI 083/86-01-02: Review SAR paragraph 7.2.3, and revise as necessary by August 31, 1986, IFI 083/86-01-03: Raview CORA calculations for proper identification of materials, and revise SAR as needed by August 31, 198 V
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| The SAR review also revealed .that the storage of Wigner energy in the graphite moderator and the potential for autorelease of that' energy had not been considered. At the exit interview, the licensee made a commitment to complete an analysis of the potential lifetime storage of Wigner energy and associated risks by May 31, 1987. This will be tracked as IFI 083/86-01-04:
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| Evaluate storage and release ~ of Wigner energ . Review of Surveillance Procedures The following surveillance procedures were reviewed: SOP-A.7 (Revision 1), Determination of Control Blade Integral or Differential Reactivity Wort The method of worth determination is that traditionally used on research reactors with semaphore control and safety blade Individual blades are dropped from the critical condi-tion at low po'wer, in this case 100 watts. The subcritical decay of flux is then analyzed to infer rod worth. The inspector witnessed portions of the worth determination for safety blade 2, including drops from 100, 90, 80, and 70% withdrawn. Later the results and analysis were discussed with members of the staff. The operators performing the surveillance appeared to be well versed in the procedure requirements and the methodology in us b .~ SOP-0.5 (Revision 1), UFTR Nuclsar Instrumentation Calibration Check and Heat Balance. The procedure reflects a technically adequate method of performing a heat balance and determining the thermal power of the reactor. However, vague definitions of the symbols used in the equa-tions' appear to make it difficult for less-experienced, newly-licensed, personnel to us P-E.7 (Revision 0), Measurement of Temperature Coefficient of Reac-tivity. This procedure is adequate to perform the annual -surveillance required by Technical Specification 4.2.1 to assure that the coolant temperature coefficient is negativ This surveillance has been overdue since November 1985; performance is not possible with the reactor shutdown. It is scheduled for performance after the rod worth determinatio The test completed on November 29, 1984, was acceptabl SOP-E.8 (Revision 0), Verification of the UFTR Negative Void Coeffi-cient of Reactivity. This procedure is responsive to the requirement of Technical Specification 4.2.1(3) to verify biennially that the coolant void coefficient is negativ The last performance of this procedure, on October 26, 1984, was revieved and found acceptabl Special Procedure for Sequencing Fuel Load Increments to Load UFTR Core was written spec fically to guide the- post-maintenance, post-modifica-tion refueling. Review of the completed procedure and discussions with facility personnel confirmed that the reloading had been accomplished in a safe and controlled manne t
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| 5 Requalification of Operators In the course of the extended outage none of the licensed operators were able to maintain their proficiency by operating the reactor. In a letter to NRC Region II, dated January 6,1986, the licensee proposed an operator requalification process. That process was found acceptable by the. region, and that finding was corresponded to the licensee in a letter . dated January 28, 198 Satisfactory completion of the requalification process for all current operators was confirmed by review of completed tests and records of performance. The final step in requalification of one operator,
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| a startup to one Watt, was witnesse No violations, other than the one identified in paragraph 5, or deviations were identifie a
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20211P4761999-09-0909 September 1999
Discusses Arrangements Made Between Recipient & Pj Isaac for Administration of Operator Licensing Exams at Univ of Florida Reactor Scheduled for Week of 991011
ML20211B3531999-08-16016 August 1999
Accepts Ltr as Formal Notification That JW Powers Will No Longer Be Performing Licensed Activities for Facility
ML20216D3041999-07-20020 July 1999
Submits Rept of Change in Facility Organization at Level 1 Which Is Level Responsible for Univ of Fl Training Reactor (Uftr) Facility Licenses,Charter & Site Administration
ML20209C4971999-06-29029 June 1999
Forwards 14 Day Rept on Potential TS Violation Re Failure to Measure Adequately Secondary Flow Limiting Safety Sys Setting,Which Was Reported by 990608 & 10 Telcon
ML20195J0931999-06-15015 June 1999
Informs That NRR Determined That Revs to Univ of Florida Operator Requalification Plan Submitted by Ltr Dtd 990514, Does Not Alter Intent of Presently Approved Orp.Submitted Orp Considered Acceptable
ML20195H5101999-06-0808 June 1999
Documents 990608 Telcon Between T Michaels & J Wolf Re Potential Inadequacies in Checking Secondary Cooling Low Flow Trip.Event May Be Potentially Reportable Occurrence Per TS Sections 4.1 & 6.6.2
ML20195B3981999-05-17017 May 1999
Provides Rept of Significant Change in Facility Organization at Level 3 Which Is Level Responsible for day-to-day Operations of Univ of Fl Training Reactor
ML20206U2431999-05-14014 May 1999
Forwards Rev 4 to Univ of Fl Training Reactor Operator Requalification & Recertification Training Program Plan for July 1999 - June 2001. Changes,Discussed
ML20205R0601999-04-16016 April 1999
Ack Receipt of Ltr Dtd 990218,which Encl Rev 11 to Univ of Florida Training Reactor Emergency Plan Submitted Under Provisions of 10CFR50.54(q).NRC Approval Not Required
ML20205E4641999-03-29029 March 1999
Forwards Updated Proposal Submitted to NRC to Meet 10CFR50.64 Requirements for Updating Scheduling of Uftr Conversion from HEU to LEU Fuel
ML20207A6051999-02-19019 February 1999
Forwards Rev 11 to Uftr SAR, Dtd Jan 1981 Which Was Initiated as Result of Changes in Personnel Monitoring Badges Supplied to Univ by NVLAP-accredited Supplier.Rev 11 to EP for Uftr, Encl
ML20155G8521998-11-0202 November 1998
Forwards Insp Rept 50-083/98-202 on 981006-09.No Violations Noted.No Significant Safety Issues Identified
ML20154E1621998-10-0101 October 1998
Forwards Insp Rept 50-083/98-201 on 980908-10.No Violations Noted.Univ of Fl Training Reactor Respiratory Protection Program Found to Conform to Requirements of 10CFR20.1703
ML20236X2691998-08-0303 August 1998
Forwards Rev 2 to Univ of Fl Training Reactor Respiratory Protection Program, Reflecting Changes Necessitated by Updated Univ of Fl Respiratory Protection Program Along W/ Recommendations from NRC Info Notices 97-066 * 98-020
ML20217M6461998-03-27027 March 1998
Forwards Updated Proposal Intended to Meet Requirements of 10CFR50.64(c)(2).Proposal Is Essentially Unchanged Except for Revised Schedule & Presence of Substantive Info on Progress to Date Including Final Fuel Bundle Design
ML20203C4261997-12-0303 December 1997
Forwards Amend 22 to License R-56 & Safety Evaluation.Amend Consists of Revs to TS 6.2.5(1) & on Figure 6.1 to Reflect Name Change from Dept of Nuclear Engineering Sciences to Dept of Nuclear & Radiological Engineering
ML20216B3501997-10-17017 October 1997
Forwards Pp Changes Which Constitute Rev 10 of Univ of Florida Training Reactor Emergency Plan.Rev 10 Consists of Set of Updates & Revs to 13 Listed Pages
ML20211N0381997-10-0707 October 1997
Forwards Explanatory Ltr & Change Pages That Constitute Rev 14 of Univ of Fl Training Reactor Physical Security Plan. Encls Withheld,Per 10CFR2.790(d)
ML20217H7881997-10-0606 October 1997
Forwards Corrected Page of Uftr Organizational Chart Submitted W/Amend 22 of Tss,Per 970903 Telcon.Encl Part of Chart Not Intended to Be Changed from Approved TSs
ML20217B2391997-09-0909 September 1997
Forwards Insp Rept 50-083/97-201 on 970630-0703.No Violations Noted
ML20217P3211997-08-22022 August 1997
Ack Receipt of Forwarding Rev 10 to Univ of Fl Training Reactor Emergency Plan.Rev Does Not Decrease Effectiveness of Emergency Plan.Nrc Approval Not Required
ML20198F7511997-08-0101 August 1997
Informs That on 970804,non-power Reactor Insp Program Will Be Transferred from Region II Ofc to NRR
ML20148G3321997-05-29029 May 1997
Forwards Univ of Fl Training Reactor Operator Requalification & Recertification Training Program Plan, Jul 1997-June 1999
ML20138D8841997-04-21021 April 1997
Informs That Dj Cronin Resigned as Acting Reactor Manager on 970328 & Wg Vernetson Assumed That Position on Same Date
ML20140C8631997-04-10010 April 1997
Forwards Rev 10 to Uftr Emergency Plan. Changes Contained in Plan,Discussed
ML20137R5231997-04-0808 April 1997
Forwards Most Recent Proprietary Quarterly Log of Security Events for Univ of Fl Training Reactor R-56 License at Univ of Fl.Encl Withheld
ML20137G6151997-03-27027 March 1997
Forwards Updated Proposal Submitted to NRC to Meet 10CFR50.64 Requirements for Updating Scheduling of Uftr Conversion from HEU to LEU Fuel
ML20137U6121997-03-25025 March 1997
Informs That NRC Region II Ofc Will Move to Atlanta Federal Ctr Complex on 970425.List of Telephone Numbers & Directions to New Ofc Encl
ML20137C1731997-03-20020 March 1997
Informs That Encl SRO Certificate Being Forwarded to JW Powers at Univ of Fl.W/O Encl
ML20140C7141997-03-17017 March 1997
Forwards Copy of 1995-96 Univ of Florida Training Reactor Annual Progress Rept in Compliance W/Requirements of Section 6.6.1 of Uftr TSs
ML20137C1151997-03-17017 March 1997
Forwards Ltr of 1995-96 Univ of Fl Training Reactor Annual Progress Rept
ML20137D6361997-03-17017 March 1997
Forwards Rev 10 to Univ of Fl Training Reactor SAR Dtd Jan 1981 Submitted as Part of Last Relicensing Effort.Rev Consists of Changes to Single Pp,Initiated as Result of Comments from Staff Member Checking Matls Re Training
ML20140C7221997-02-28028 February 1997
Forwards One Copy of 1995-96 Univ of Florida Training Reactor Annual Progress Rept Per TS Reporting Requirements
ML20137C1341997-02-28028 February 1997
Forwards 1995-96 Univ of Fl Training Reactor Annual Progress Rept
ML20136C3091997-02-27027 February 1997
Informs of Licensee Failure to Address Major Contributing Factor to Root Cause of Incident That Occurred at Facility on 970113 Re Improper Stack Calibr.Nrc Expects Licensees to Provide Appropriate Mgt Guidance of Licensed Activities
ML20135C1231997-02-25025 February 1997
Submits Copy of Results of Operator Initial Examination Conducted at University of Florida on 970210.W/o Encl
ML20135C3421997-02-25025 February 1997
Forwards Operator Licensing Exam Rept 50-083/OL-97-01 on 970210-11
ML20149M6731997-01-15015 January 1997
Discusses Potential TS Violation Re Improper Stack Monitor Calibr.Caused by Flawed Procedure That Failed to Correct for Delay of Cs-137 Calibr Source.Performed full-power Reactor Run on 970114 & Found Monitor to Be Properly Calibr
ML20132A9721996-12-12012 December 1996
Discusses Arrangements for Written & Operating Exams Scheduled for Wk of 970210.Listed Ref Matl for Exams Requested at Least 60 Days Prior to Exam Date
ML20128N4211996-10-10010 October 1996
Forwards Amend 21 to License R-56.Amend Consist of Revs to TS to Permit Submittal of Annual Rept for Activities 6 Months Following End of Uftr Prescribed End of Yr Which Occurs on 960831
ML20128N2971996-10-0303 October 1996
Repts Significant Change in Campus Radiation Control Function That Interacts W/Level 1 Personnel in Order to Facilitate Communications W/Commission
ML20117N3891996-09-0909 September 1996
Informs That D Simpkins Will No Longer Be Performing Licensed Activities for Facility
ML20117K7881996-09-0404 September 1996
Submits Significant Change in Facility Organization at Level 3,responsible for day-to-day Operation of Uftr
ML20116J5751996-08-0909 August 1996
Forwards Annual Progress Rept of Univ of Fl Training Reactor Sept 1994 - Aug 1995
ML20116A0671996-07-19019 July 1996
Submits Response to Violations Noted in Insp Rept 50-083/96-01.Corrective Actions:Facility Administrative Staff Logged Many H in Late June & Early Jul to Generate & Submit First of Two Repts
ML20113C9341996-06-21021 June 1996
Provides Explanatory Ltr & Change Pages That Constitute Rev 13 for Univ of Florida Training Reactor Physical Security Plan.W/O Encl
ML20101L3451996-03-27027 March 1996
Forwards Updated Proposal Submitted to NRC to Meet 10CFR50.64 Requirements for Updating Scheduling of Uftr Conversion from HEU to LEU Fuel. Proprietary Info Withheld
ML20094D0931995-10-27027 October 1995
Forwards Rev 12 to Physical Security Plan.Second Page Submitted to Assure Complete Current Copy of Univ of Fl Training Reactor.Rev Withheld
ML20092G0931995-09-14014 September 1995
Forwards Rev 9 to FSAR for Univ of Fl Training Reactor
ML20086M7661995-07-18018 July 1995
Forwards Rev 12 of Physical Security Plan for Univ of Florida Training Reactor Per 10CFR50.54.Encl Withheld
1999-09-09
[Table view]
Category:NRC TO EDUCATIONAL INSTITUTION
MONTHYEARML20058L7221990-07-20020 July 1990
Discusses NRC Familiarization Tour of Univ Reactor by Resident Inspectors Re Potential Consequences of Accident
ML20248C1501989-06-0202 June 1989
Advises That 890202 Proposed Changes to Emergency Plan May Be Incorporated Into Current Plan
IR 05000083/19890011989-05-12012 May 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-083/89-01
ML20244C4881989-04-0707 April 1989
Forwards Insp Rept 50-083/89-01 on 890227-0302 & Notice of Violation
ML20196D5061988-11-25025 November 1988
Forwards Exam Rept 50-083/OL-88-02 Administered on 881014
ML20151E6531988-07-11011 July 1988
Forwards Exam Rept 50-083/OL-88-01 on 880608-09
IR 05000083/19880011988-05-19019 May 1988
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-083/88-01
ML20151W8501988-04-27027 April 1988
Forwards Amend 17 to License R-56,revising Tech Specs to Allow Certain Activities When Reactor Shut Down,Reactor Vent Sys Secured & Stack Monitor Reading Greaater than 10 Counts Per
ML20151E6451988-04-0707 April 1988
Forwards Insp Rept 50-083/88-01 on 880314-17 & Notice of Violation
ML20148L0491988-03-17017 March 1988
Advises That Reactor Operator & Senior Operator Licensing Written Exams Scheduled for Wk of 880520 & Oral Exams Scheduled for 880601-02.List of Required Ref Matls & Rules & Guidelines Encl.Info Requested 60 Days Prior to Exams
ML20236Q2631987-11-13013 November 1987
Forwards Insp Rept 50-083/87-04 on 871019-22.No Violations or Deviations Noted
ML20215F4551987-06-11011 June 1987
Notifies of Reorganization of Nrr.Project Manager for Facility Is T Michaels
ML20215J8381987-06-0808 June 1987
Ack Receipt of 870526 Response to Violations Noted in Insp Rept 50-083/87-01 on 870326.Reviewed & Approved New Procedure Covering Conduct of Radwaste Shipment from Facility Acceptable
ML20214K0411987-05-11011 May 1987
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-083/87-01.Response Meets Requirements of 10CFR2.201
ML20214B1481987-05-0101 May 1987
Forwards IE Info Notice 86-028, Telephone Numbers to NRC Operations Ctr & Regional Ofcs, Indicating Proper Points of Contact for Notification & Current Telephone Numbers in Light of Questions Re Research Reactor Emergency Response
ML20214A5391987-04-28028 April 1987
Forwards Insp Rept 50-083/87-03 on 870406-08.No Violations or Deviations Noted
ML20212Q8891987-04-17017 April 1987
Advises That Span of Time from Receipt of Funding to Submittal of Application for Conversion from High Enriched U to Low Enriched U Too Long,In Response to .Updated Schedule Requested within 30 Days of Ltr Date
ML20206B0631987-04-0202 April 1987
Advises That 870303 Changes to Emergency Plan Consistent W/ Requirements of 10CFR50.54(q) & Acceptable.Immediate Implementation of Program Requested
ML20206D4491987-04-0101 April 1987
Ack Receipt of 870319 Response to 870220 Notice of Violation from Insp Rept 50-083/87-01
ML20205N8941987-03-26026 March 1987
Discusses Insp Rept 50-083/87-01 on 870209-11 & Forwards Notice of Violation.Civil Penalty Not Assessed Due to Prior Good Performance in Area of Violation & Prompt Action Taken Re Radwaste Transportation Program
IR 05000083/19870011987-03-0505 March 1987
Forwards Summary of 870226 Enforcement Conference Re Findings Discussed in Insp Rept 50-083/87-01.Attendance at Conference & Subjs Discussed Described in Encl Summary
ML20207T6421987-03-0505 March 1987
Forwards Summary of 870226 Enforcement Conference Re Findings Discussed in Insp Rept 50-083/87-01.Attendance at Conference & Subjs Discussed Described in Encl Summary
ML20207T4211987-02-20020 February 1987
Confirms 870218 Telcon Between Wg Vernetson & PE Fredrickson Re Enforcement Conference on 870226 at Univ to Discuss Potential Improper Transport of Licensed Matl Outside Confines of Facility
ML20207T3451987-02-20020 February 1987
Forwards Insp Rept 50-083/87-01 on 870209-11 & Notice of Violation.Violation Re Transportation of Radioactive Matl Under Consideration for Escalated Enforcement Action
ML20212N9591986-08-11011 August 1986
Forwards Sections I & II of Region II Incident Response Plan,Incorporating Lessons Learned from 1984 Full Field Exercise.Section III Withheld.W/O Encls
ML20211C0581986-06-0606 June 1986
Forwards Insp Repts 50-083/86-02 & 70-1068/86-02 on 860528-29.No Violations or Deviations Noted
IR 05000083/19860011986-05-0606 May 1986
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-083/86-01
ML20210H9171986-03-27027 March 1986
Lists Change in Telephone Number for H Bernard,Facility Project Manager,Due to NRR Reorganization.D Tondi New Nonpower Reactors & Safeguards Licensing Section Leader. Correspondence Should Be Sent to Listed Address
ML20138C4851986-03-27027 March 1986
Forwards Insp Rept 50-083/86-01 on 860218-21 & Notice of Violation
ML20154L4391986-03-0303 March 1986
Notifies of Limited Ban Placed on Exportation of Low Level Radwastes Generated by Licensees in Southeast Compact Commission Party States Effective 860301
ML20137Y0091985-11-25025 November 1985
Forwards Amend 16 to License R-56.Amend Corrects Typo on Page 12 of Tech Spec Issued as Amend 15 Re Limitations on Experiments
ML20198D9091985-11-0505 November 1985
Forwards Insp Rept 50-083/85-03 on 851009-11.No Violation Noted
ML20137Y5871985-10-0303 October 1985
Advises That 850606 Rev 6 to Physical Security Plan Consistent W/Provisions of 10CFR50.54 & Acceptable
ML20132G9391985-07-30030 July 1985
Advises That 850710 Rev 8 to Physical Security Plan Partially Consistent W/Provisions of 10CFR50.54(p).Portions Inconsistent Delineated on Encl.Encl Withheld (Ref 10CFR2.790)
ML20132E8431985-07-25025 July 1985
Forwards SER of Licensee 850226 Rev to Reactor Operator Requalification Program.Program Acceptable
ML20129D7681985-07-11011 July 1985
Forwards Safeguards Insp Repts 50-083/85-02 & 70-1068/85-02 on 850624-25.No Violations or Deviations Noted
IR 05000083/19850011985-05-0606 May 1985
Ack Receipt of Informing NRC of Steps Taken to Correct Deviation Noted in Insp Rept 50-083/85-01
ML20054L3881982-06-16016 June 1982
Ltr to All Research & Test Reactor Licensees Requesting That Reg Guide 2.6 (for Comment) & ANSI/ANS-15.16 (Draft II Dtd 811129) Be Used to Meet Requirement of Final Amend to 10CFR50.54(r) Re Emergency Planning.Fr Notice Encl
ML20148F3751978-10-12012 October 1978
Accepts Arognaut Res Reactor Security Plan & Rev.Requests That the Basic Plan & Revisions Be Consolidated Into One Document for Inclusion in the Renewal Lic
ML20147B8101978-09-0707 September 1978
Forwards IE Inspec Rept 50-083/78-05 & Notice of Violation
ML20137G4721971-06-23023 June 1971
Advises That Presence & Irradiation of Explosives in Reactor Must Be Evaluated Due to Potential for Damage to Reactor. Evaluation Requested Establishing Operating Restrictions,Max Quantity of Explosives Allowed in Facility & Form
1990-07-20
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20211P4761999-09-0909 September 1999
Discusses Arrangements Made Between Recipient & Pj Isaac for Administration of Operator Licensing Exams at Univ of Florida Reactor Scheduled for Week of 991011
ML20195J0931999-06-15015 June 1999
Informs That NRR Determined That Revs to Univ of Florida Operator Requalification Plan Submitted by Ltr Dtd 990514, Does Not Alter Intent of Presently Approved Orp.Submitted Orp Considered Acceptable
ML20205R0601999-04-16016 April 1999
Ack Receipt of Ltr Dtd 990218,which Encl Rev 11 to Univ of Florida Training Reactor Emergency Plan Submitted Under Provisions of 10CFR50.54(q).NRC Approval Not Required
ML20155G8521998-11-0202 November 1998
Forwards Insp Rept 50-083/98-202 on 981006-09.No Violations Noted.No Significant Safety Issues Identified
ML20154E1621998-10-0101 October 1998
Forwards Insp Rept 50-083/98-201 on 980908-10.No Violations Noted.Univ of Fl Training Reactor Respiratory Protection Program Found to Conform to Requirements of 10CFR20.1703
ML20203C4261997-12-0303 December 1997
Forwards Amend 22 to License R-56 & Safety Evaluation.Amend Consists of Revs to TS 6.2.5(1) & on Figure 6.1 to Reflect Name Change from Dept of Nuclear Engineering Sciences to Dept of Nuclear & Radiological Engineering
ML20217B2391997-09-0909 September 1997
Forwards Insp Rept 50-083/97-201 on 970630-0703.No Violations Noted
ML20217P3211997-08-22022 August 1997
Ack Receipt of Forwarding Rev 10 to Univ of Fl Training Reactor Emergency Plan.Rev Does Not Decrease Effectiveness of Emergency Plan.Nrc Approval Not Required
ML20198F7511997-08-0101 August 1997
Informs That on 970804,non-power Reactor Insp Program Will Be Transferred from Region II Ofc to NRR
ML20137U6121997-03-25025 March 1997
Informs That NRC Region II Ofc Will Move to Atlanta Federal Ctr Complex on 970425.List of Telephone Numbers & Directions to New Ofc Encl
ML20137C1731997-03-20020 March 1997
Informs That Encl SRO Certificate Being Forwarded to JW Powers at Univ of Fl.W/O Encl
ML20136C3091997-02-27027 February 1997
Informs of Licensee Failure to Address Major Contributing Factor to Root Cause of Incident That Occurred at Facility on 970113 Re Improper Stack Calibr.Nrc Expects Licensees to Provide Appropriate Mgt Guidance of Licensed Activities
ML20135C3421997-02-25025 February 1997
Forwards Operator Licensing Exam Rept 50-083/OL-97-01 on 970210-11
ML20135C1231997-02-25025 February 1997
Submits Copy of Results of Operator Initial Examination Conducted at University of Florida on 970210.W/o Encl
ML20132A9721996-12-12012 December 1996
Discusses Arrangements for Written & Operating Exams Scheduled for Wk of 970210.Listed Ref Matl for Exams Requested at Least 60 Days Prior to Exam Date
ML20128N4211996-10-10010 October 1996
Forwards Amend 21 to License R-56.Amend Consist of Revs to TS to Permit Submittal of Annual Rept for Activities 6 Months Following End of Uftr Prescribed End of Yr Which Occurs on 960831
ML20058B5991993-11-16016 November 1993
Ack Receipt of 930930 Rev 11 to Physical Security Plan. Changes Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion Into Plan
ML20059H0691993-11-0101 November 1993
Discusses Telcon Arrangements Made for Administration of Operator Licensing Exams.Written & Operating Exams Scheduled for Wk of 931213
ML20057F8531993-10-13013 October 1993
Advises That Operator Requalification Plan Acceptable
ML20057E4251993-10-0101 October 1993
Forwards Insp Rept 50-083/93-01 on 930914-15.No Violations Noted.Rept Details Withheld (Ref 10CFR2.790)
ML20058F4611990-10-26026 October 1990
Ack Receipt of ,Transmitting Rev 4 to Spert Assembly Physical Security Plan,
ML20058L7221990-07-20020 July 1990
Discusses NRC Familiarization Tour of Univ Reactor by Resident Inspectors Re Potential Consequences of Accident
ML20248C1501989-06-0202 June 1989
Advises That 890202 Proposed Changes to Emergency Plan May Be Incorporated Into Current Plan
IR 05000083/19890011989-05-12012 May 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-083/89-01
ML20244C4881989-04-0707 April 1989
Forwards Insp Rept 50-083/89-01 on 890227-0302 & Notice of Violation
ML20196D5061988-11-25025 November 1988
Forwards Exam Rept 50-083/OL-88-02 Administered on 881014
ML20151E6531988-07-11011 July 1988
Forwards Exam Rept 50-083/OL-88-01 on 880608-09
IR 05000083/19880011988-05-19019 May 1988
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-083/88-01
ML20151W8501988-04-27027 April 1988
Forwards Amend 17 to License R-56,revising Tech Specs to Allow Certain Activities When Reactor Shut Down,Reactor Vent Sys Secured & Stack Monitor Reading Greaater than 10 Counts Per
ML20151E6451988-04-0707 April 1988
Forwards Insp Rept 50-083/88-01 on 880314-17 & Notice of Violation
ML20150D8641988-03-18018 March 1988
Informs of Relocation of NRR to Rockville,Md.Official Mailing Address Still Remains Same & Project Managers Have New Locations & Phone Numbers.Ts Michaels Still Lead Project Manager for Facility & a Adams Will Serve as Backup
ML20148L0491988-03-17017 March 1988
Advises That Reactor Operator & Senior Operator Licensing Written Exams Scheduled for Wk of 880520 & Oral Exams Scheduled for 880601-02.List of Required Ref Matls & Rules & Guidelines Encl.Info Requested 60 Days Prior to Exams
ML20236Q2631987-11-13013 November 1987
Forwards Insp Rept 50-083/87-04 on 871019-22.No Violations or Deviations Noted
ML20215F4551987-06-11011 June 1987
Notifies of Reorganization of Nrr.Project Manager for Facility Is T Michaels
ML20215J8381987-06-0808 June 1987
Ack Receipt of 870526 Response to Violations Noted in Insp Rept 50-083/87-01 on 870326.Reviewed & Approved New Procedure Covering Conduct of Radwaste Shipment from Facility Acceptable
ML20214K0411987-05-11011 May 1987
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-083/87-01.Response Meets Requirements of 10CFR2.201
ML20214B1481987-05-0101 May 1987
Forwards IE Info Notice 86-028, Telephone Numbers to NRC Operations Ctr & Regional Ofcs, Indicating Proper Points of Contact for Notification & Current Telephone Numbers in Light of Questions Re Research Reactor Emergency Response
ML20214A5391987-04-28028 April 1987
Forwards Insp Rept 50-083/87-03 on 870406-08.No Violations or Deviations Noted
ML20212Q8891987-04-17017 April 1987
Advises That Span of Time from Receipt of Funding to Submittal of Application for Conversion from High Enriched U to Low Enriched U Too Long,In Response to .Updated Schedule Requested within 30 Days of Ltr Date
ML20206B0631987-04-0202 April 1987
Advises That 870303 Changes to Emergency Plan Consistent W/ Requirements of 10CFR50.54(q) & Acceptable.Immediate Implementation of Program Requested
ML20206D4491987-04-0101 April 1987
Ack Receipt of 870319 Response to 870220 Notice of Violation from Insp Rept 50-083/87-01
ML20205N8941987-03-26026 March 1987
Discusses Insp Rept 50-083/87-01 on 870209-11 & Forwards Notice of Violation.Civil Penalty Not Assessed Due to Prior Good Performance in Area of Violation & Prompt Action Taken Re Radwaste Transportation Program
IR 05000083/19870011987-03-0505 March 1987
Forwards Summary of 870226 Enforcement Conference Re Findings Discussed in Insp Rept 50-083/87-01.Attendance at Conference & Subjs Discussed Described in Encl Summary
ML20207T6421987-03-0505 March 1987
Forwards Summary of 870226 Enforcement Conference Re Findings Discussed in Insp Rept 50-083/87-01.Attendance at Conference & Subjs Discussed Described in Encl Summary
ML20207T4211987-02-20020 February 1987
Confirms 870218 Telcon Between Wg Vernetson & PE Fredrickson Re Enforcement Conference on 870226 at Univ to Discuss Potential Improper Transport of Licensed Matl Outside Confines of Facility
ML20207T3451987-02-20020 February 1987
Forwards Insp Rept 50-083/87-01 on 870209-11 & Notice of Violation.Violation Re Transportation of Radioactive Matl Under Consideration for Escalated Enforcement Action
ML20212N9591986-08-11011 August 1986
Forwards Sections I & II of Region II Incident Response Plan,Incorporating Lessons Learned from 1984 Full Field Exercise.Section III Withheld.W/O Encls
ML20211C0581986-06-0606 June 1986
Forwards Insp Repts 50-083/86-02 & 70-1068/86-02 on 860528-29.No Violations or Deviations Noted
IR 05000083/19860011986-05-0606 May 1986
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-083/86-01
ML20138C4851986-03-27027 March 1986
Forwards Insp Rept 50-083/86-01 on 860218-21 & Notice of Violation
1999-09-09
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Inspection Report - - 1986001 |
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Yk(ud i
MAY 0 61986 UniversfyofFlorida i
ATTN: M)r. J. A. Wethington Acting Chairman, Nuclear Engineering Sciences Department 202 Nuclear Sciences Center Gainesville, FL 32611 Gentlemen:
SUBJECT: REPORT NO. 50-83/86-01 Thank you for your response of April 17, 1986, to our Notice of Violation issued on March 27, 1986, concerning activities conducted at your University of Florida Training Reactor facility under NRC License No. R-56. We have evaluated your response and found that it meets the requirements of 10 CFR 2.201. We will examine the implementation of your corrective actions during future inspections.
We appreciate your cooperation in this matte
Sincerely, cn))k k OJ% 1h Luis A. Reyes, Acting Director Division of Reactor Projects cc: r. N. J. Diaz, Director of uclear Facilities bec icense Fee Management Branch cument Control Desk tate of Florida i
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