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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:EDUCATIONAL INSTITUTION TO NRC
MONTHYEARML20055H8411990-07-19019 July 1990 Submits Decommissioning Rept Info for Reactor,Per 10CFR50.33 & 50.75 Requirements.Funds for Decommissioning Will Be Requested from State of Fl Legislature When Decision to Decommission Facility Made ML20043E5811990-06-0404 June 1990 Advises of Appointment of P Achey as Chairman of Univ Radiation Control Committee,Effective 900412 ML20012C4951990-03-0707 March 1990 Advises That Jv Lombardi New Permanent President of Univ of Florida Effective 900305.President Responsible for Uftr Facility License,Charter & Site Administration ML20005G8231990-01-12012 January 1990 Forwards Rev 5 to Emergency Plan.Page 11-1 Re New Security Response Procedure Incorporated in List of Procedures Primarily for Completeness ML19354D8881990-01-12012 January 1990 Responds to NRC 891218 Ltr Re Violations Noted in Insp Rept 50-083/89-04.Corrective Actions:All NRC Required Surveillances Tracked as to Day of Month Performed to Assure Allowable Surveillance Intervals Not Exceeded ML20248B4791989-09-18018 September 1989 Forwards Rev 6 to FSAR for Univ of Florida Training Reactor, Consisting of Update of Chapter 11 of SAR Based on Internal Review ML20248F1111989-09-15015 September 1989 Advises That 890915 Safety Channel 1 High Voltage Trip Not Violation of Tech Specs But in View of Recent Equipment Problems,Recommends NRC Be Notified for Info Purposes.Trip Will Be Examined at 890919 Safety Review Meeting ML20244B7181989-05-30030 May 1989 Forwards Rev to Upgrade Operator Requalification & Recertification Program for Jul 1989 - June 1991 ML20247B4181989-05-0404 May 1989 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-083/89-01.Corrective Actions:Detailed Radiation Surveys of Vertical Port Area Taken & Documented ML20244D2181989-04-0303 April 1989 Informs of Significant Change in Facility Organization. Mm Criser Replaces RA Bryan as President of Univ & Holds Line Responsibility for Level 1 Administration of Reactor, Facility License,Charter & Site Administration ML20247K7991989-03-27027 March 1989 Forwards Updated Proposal Intended to Meet Requirements of 10CFR50.64(c)(2) for Scheduling of Fuel Conversion ML20246L3851989-02-24024 February 1989 Advises of Failure to Notify NRC of Significant Change in Facility Organization at Level I on 890221.Effective 880801, Wm Phillips Assumed Title of Dean of Univ,College of Engineering ML20235Q5211989-02-21021 February 1989 Informs of Replacement of W Chen W/Wm Phillips as Dean of Univ of Florida College of Engineering ML20196D6341988-11-30030 November 1988 Forwards 1987-1988 Univ of Florida Training Reactor Annual Progress Rept. W/O Encl ML20195F9551988-11-14014 November 1988 Advises That Reactor Safety Review Committee Reviewed & Concluded Potential Violation of Tech Specs,Section 6.3 Re Requirement That Facility Be Operated in Accordance W/Written Procedures,Per 881114 Telcon ML20206J1411988-11-0707 November 1988 Submits Followup on 881104 Event Re Failure of Temp Record to Track Properly & Requiring Unscheduled Shutdown.Probable Cause Isolated & Planned Recovery Will Be Reviewed by Reactor Safety Review Subcommittee within 24 H ML20205R4701988-10-17017 October 1988 Forwards Rev 3 to Emergency Plan,Consisting of Corrected Page 8-4 to Reflect That Other Hosps Now Designated to Handle Crystal River 3 Radiation Accident Victims ML20150B2301988-06-30030 June 1988 Forwards Rev 5 to Univ of Florida Training Reactor FSAR ML20150B6961988-06-13013 June 1988 Advises That Failure of Control Blade Safety 2 Clutch Indicating Lamp Constitutes Ro,Per 880613 Telcon ML20153H4501988-05-0606 May 1988 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-083/88-01.Corrective Actions:Scheduled Ar-41 Measurement Postponed Until Analysis to Assure Conservatism of Present Methodology Documented & Effluent Isotope Counting Planned ML20151V2071988-04-11011 April 1988 Notifies of Recurrence of Failure of Safety Channel 1 During Power Run Conducted for Senior Lab Training Operations Lab. Test Used to Verify Proper Operation of Safety Channel.Test Results Successful & Channel Returned to Normal Operation ML20150F3811988-03-22022 March 1988 Forwards Updated Proposal Re Requirements of 10CFR50.64(c)(2).Updated Proposal Includes Certification That Funding for Conversion Available Through DOE & Tentative Conversion Schedule Based on Fuel Availability ML20196J1521988-03-0707 March 1988 Forwards Revised Amend 17 Tech Spec Pages to 870602 Application for Amend,Per 880205 Request.Rev Addresses Areas of Concern Listed in ML20235H1271987-09-25025 September 1987 Forwards Rev 4 to FSAR as Part of Relicensing Effort.Rev Re Fire Protection & Communications Sys ML20214U9851987-05-29029 May 1987 Forwards Rev 3 to Fsar,Changing Part I Re Radiation Monitoring Concerning Environ Monitoring Sys & Part II Re App 15G as Part of Relicensing Effort.App 15G Will Be Added to SAR to Address Wigner Energy Storage & Graphite Fires ML20215A8971987-05-26026 May 1987 Forwards Std Operating Procedure Uftr SOP-D.5 Re Preparation & Transfer of Reactor Waste Shipments,Per 870423 Response to Violations Noted in Insp Rept 50-083/87-01.No Shipments Will Be Made Until Procedure Reviewed & Approved by NRC ML20214F4681987-05-14014 May 1987 Responds to NRC Re Highly Enriched U/Lowly Enriched U Conversion Schedule.Schedule Shortened by 8 Months as Shown on Encl Reworked Table II (Rev 1).All Analytical Work Will Be Performed in-house ML20210C1721987-04-23023 April 1987 Responds to NRC Re Violations Noted in Insp Repts 50-083/87-01 & 50-083/87-02.Corrective Actions:Produced New Policy Requiring Licensed Shipper & New Procedure to Control Shipment of Waste.No Shipments Until Procedure in Effect ML20205H5331987-03-26026 March 1987 Forwards Proposal Intended to Meet Requirements of 10CFR50.64(c)(2).Proposal Includes Certification That Funding for Conversion Available Through DOE & Tentative Schedule for Conversion ML20205N4101987-03-19019 March 1987 Responds to Violations Noted in Insp Rept 50-083/87-01. Corrective Actions:Notice Describing 10CFR19 & 20 Requirements & Stating Where Info Can Be Found Posted ML20207Q9281987-03-0303 March 1987 Forwards Revs to Emergency Plan,Including Page Corrections to Body of Plan (Pages 5-2,8-1,8-3 & 8-4) & Revs to Emergency Response Procedures SOP-B.1 & SOP-B.2 ML20215B1941986-12-19019 December 1986 Discusses 861211 Event Re Stack Dilute Fan & Core Vent Fan Secured by Actuation of Evacuation Alarm & Evacuation Alarm/ Core Vent Sys Interlocks White Stack Count Rate Approx 300 Cps ML20214V6071986-11-29029 November 1986 Forwards Annual Progress Rept of Univ of Florida Training Reactor,Sept 1985 - Aug 1986 ML20203E1391986-07-18018 July 1986 Forwards Rev 2 Pages for Facility Sar,Per NRC Insp 50-083/86-01 on 860218-21.Revs Concern Sections 7.3 & 7.6 & Figure 1-8 from Chapter 1 Re source-range Detector in Nuclear Instrumentation Channel 1 ML20205P0981986-05-13013 May 1986 Forwards Submitted to Region II Notifying That Js Tulenko,Chairman of Nuclear Engineering Sciences Dept, Holds Level 1 Administrative Responsibility for Facility,Per Tech Specs.Tulenko Should Be Put on Mailing List ML20205P1301986-05-0606 May 1986 Advises That Js Tulenko Made Permanent Chairman of Nuclear Engineering Sciences Dept on 860505 & Holds Level 1 Administrative Responsibility for Facility,Per Tech Spec Section 6.6.3,Paragraph 1 ML20197J7921986-04-17017 April 1986 Responds to Violations Noted in Insp Rept 50-083/86-01. Corrective Actions:Suppl to 50.59 Evaluation/Determination 85-17 Generated to Meet 10CFR50.59(b) Requirements.Full Compliance Will Be Achieved by 860615 ML20137V2881985-11-27027 November 1985 Forwards 1984-1985 Training Reactor Annual Progress Rept ML20132C6491985-09-0606 September 1985 Forwards Rev 9 to Physical Security Plan.Rev Removes Implication in Section 4.1 of SOP-F.1 Not Subj to 10CFR73.71.Change Labeled Technical Change Notice.Rev Withheld (Ref 10CFR2.790) ML20129J2061985-07-10010 July 1985 Forwards Rev 8 to Physical Security Plan,Reflecting Current Security Requirements & Implementation of Physical Security Plan.Rev Withheld (Ref 10CFR2.790) ML20098E5651984-09-25025 September 1984 Notifies of Complete Implementation on 840921 of Revised Emergency Plan Approved by NRC on 840604 ML20086M1521984-02-0101 February 1984 Forwards Proprietary Resubmission of Rev 7 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790) ML20082H5541983-11-22022 November 1983 Forwards Rev 7 to Physical Security Plan.Rev Withheld ML20076M2581983-09-15015 September 1983 Forwards Public Version of Licensee Request for Addl 30-day Extension Until 831015 to Submit Amends to Emergency Plan ML20076L1221983-07-29029 July 1983 Requests 30-day Extension Until 830915 to Submit Revised Emergency Plan ML20072S5561983-03-31031 March 1983 Forwards Rev 6 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790) ML20072L3241983-02-28028 February 1983 Forwards Operator Requalification & Recertification Program Plan for Jul 1983 - June 1985 ML20028B8171982-11-30030 November 1982 Forwards Annual Progress Rept of Univ of Fl Training Reactor, Sept 1981-Aug 1982 ML20066A4451982-10-27027 October 1982 Forwards Proposed Changes to 14 Pages of Tech Specs Transmitted by Granting 20-yr License Renewal. Changes Correct Typographical & Nomenclature Errors & Will Have No Significant Negative Effect on Safe Operation ML20027E2761982-10-26026 October 1982 Forwards Public Version of Proposed Emergency Plan 1990-07-19
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20211B3531999-08-16016 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 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 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 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 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 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 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 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 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 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 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 ML20086P9401995-07-11011 July 1995 Expresses Opinion That 10CFR20.1601(c) Can Readily Relieve Any Burden on License R-56 Operations,In Response to NRC 950605 Request for Input on Burden Associated W/Controlling Radiation Beams at Facility ML20086D3941995-06-12012 June 1995 Informs That E Mcalpine Relative to Failure of Primary Coolant Flow Line Return Sensor Discovered on 950609,per 950612 Telcon ML20084L8871995-05-31031 May 1995 Forwards Revised Plan Re Operator Requalification & Recertification Program for Jul 1995 Through June 1997 ML20083P3771995-05-11011 May 1995 Forwards Rev 8 Pages 5-9 & 9-7 for Univ of Fl Training Reactor (Uftr) SAR Dtd Jan 1991,consisting of Changes in Schematics Describing Uftr Secondary Water Cooling Sys to Reflect Mods That Have Been Implemented ML20081L9371995-03-27027 March 1995 Forwards Updated Proposal Intended to Meet Requirements of 10CFR50.64(c)(2),outlining How Licensee Intends to Include DOE Funding Certification for First Phase of Project ML20081J6851995-03-14014 March 1995 Advises That Univ Has Concluded That Leakage of Primary Coolant Heat Exchanger Potential Abnormal Occurrence & Potentially Reportable Per TS Section 6.6.2 ML20080F7391995-01-20020 January 1995 Forwards Rev 9 to Univ of Fl Training Reactor Emergency Plan. Changes Considered Relatively Minor in Nature,Result of Reviews of Plan & Response to Simulated Emergencies Following Emergency Drills ML20072R3891994-08-31031 August 1994 Responds to Violations Noted in Insp Rept 50-083/94-01. Licensees Currently Receiving Comments & Corrections on Draft Program ML20029D9321994-05-0606 May 1994 Responds to Violation Noted in Insp Rept 50-083/94-01. Corrective Action:Written Statement Issued to Potential Respiratory Users Re Leaving Area at Any Time for Relief While Engaged in Activities of Respiratory Program ML20065B8061994-03-28028 March 1994 Forwards Updated Proposal to Meet Requirements of 10CFR50.64(c)(2) for Updating Scheduling of Univ of Fl Training Reactor Conversion from HEU to LEU Fuel ML20057E8931993-09-30030 September 1993 Forwards Rev 11 of Psp,Section 11,Page 11-1.Rev Allows Authorized Individuals Granted Unescorted Access to Security Area to Leave Badges in Controlled Access Area W/O Wearing Badges During Normal Working Hours.Encl Withheld ML20056G5751993-08-0202 August 1993 Forwards Rev 8 to Univ of Fl Training Reactor Emergency Plan, Consisting of Updates & Minor Revs to Listed Pages. Floor Plan Updated to Reflect New Room Numbers & Ofc Setup ML20046B7521993-07-30030 July 1993 Informs of Change in Facility Organization at Level 3 ML20198H3881993-07-0707 July 1993 Forwards Proprietary Log of Security Events for Univ of Fl Training Reactor R-56 License at Univ of Fl.Encl Withheld ML20044G8331993-05-28028 May 1993 Forwards Revised, Operator Requalification & Recertification Training Program Plan of Univ of Florida Training Reactor Jul 1993 Through June 1995. ML20125E0171992-12-10010 December 1992 Forwards Rev 8 to Emergency Plan, Consisting of Set of Updates & Minor Revs to Pages to Include ii,v,1-5,Chapter 3, (Pages 3-1 Through 3-8),5-2,8-2,8-3 & 10-6 1999-08-16
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4 CEDLY TO
- y COLLEGE UNIVERSITY OF FLORIDA DEP ARTMENT OF NUCLE AR ENGINEERING SCIENCES 202 NUCLEAR SCIENCES CENTER c- ENGINEERING G AiN EsviLLE, rtoRiD A 32sii AREA CODE 904 PHON E 392-1401 4
DEPARTMENT OF NUCLE AR ENGINEERING SCIENCES July 18,1986 Office of Nuclear Reactor Regulations Division of PWR Licensing-B U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Herbert N. Berkow, Director Standardization and Special Projects Directorate Re: University of Florida Training Reactor Facility License R-56 Docket No. 50-83
Dear Sir:
The enclosed package contains Revision 2 pages for the UFTR Safety Analy-sis Report dated January,1981 submitted as part of our relicensing effort.
This Revision 2 is submitted as a result of an NRC inspection of our facility conducted on February 18-21, 1986, and as cited in Inspection Report No. 50-83/86-01 as Inspector Followup Item IFI 083/86-01-02. As requested in the Inspection Report and committed in our reply, our facility has committed to update Paragraph 7.2.3 of the UFTR Safety Analysis Report "which describes operation of the control rod inhibit system and automatic control system, which is different from the performance described in Technical Specification 3.2.1. Surveillance procedures confirm performance in conformance to the requirements of Technical Specifications." As a result of the review of Paragraph 7.2.3, this revision package also includes revisions to Sections 7.3 ard 7.6 as well as Figure 1-8 from Chapter 1.
All text changes are clearly indicated by vertical lines in the margine.
The two figure changes can be noted by comparison with origfnal figures. Many of the changes represent simple typographical errors or omissions, though severai involve facility description discrepancies discovered as a result of the NRC Inspection in February,1986. All changes have been reviewed by UFTR staff and by the Reactor Safety Review Subcommittee as required by Technical Specifications. A more detailed description of the revision is included as Attachment I. A summary table of the changed pages, along with the Revision 2 pages, is enclosed as Attachnent II.
8607240067 860718 g PDR ADOCK 05000033 O .O P POR FLORIDA'S CENTER FoR ENGINEERING EDUCATION AND RESEARCH ll EQU AL EMPLOYMENT OPPORTUNITY / A FFIRMATIVE A C TION EMPLOYER I
Letter to Office of Nuclear Reactor Regulations Page Two July 18, 1986 The enclosure consists of:
- 1. Three (3) signed originals and nileteen copies of this letter of transmittal.
- 2. Twenty-five (25) copies of the attachments containing a description of Revision 2 to the UFTR Safety Analysis Report as well as the 4 Revision 2 pages.
If further information is required, please let us know.
Sincerely, hfht ) it n e William G. Vernetson Associate Engineer and Director of Nuclear Facilities z1st) h?trelawu -
N6'tary Public' WGV:lmc Enclosures 3
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ATTACHMENT I DETAILED DESCRIPTION ,
UFTR SAR REVISION 2 As noted in NRC Inspection Report-No. 50-83/86-01, Paragraph 7.2.3 (Non-Nuclear Instrumentation Channels) describes operation of the control rod in-hibit system and automatic control system, which is somewhat different from the performance described in Technical Specifications Paragraph 3.2.1. It was also noted that surveillance procedures confirm performance in conformance with the requirements of the Technical Specifications. As a result of IFI 083/86-01-02, Paragraph 7.2.3 and Sections 7.3, 7.4, 7.5 and 7.6 as well as Figure 7-3 referenced in Section 7.2 and Figure 1-8 (duplicate of Figure 7-3) have been reviewed and revised as necessary.
First, Figure 7-3 in Section 7.2 and Figure 1-8 were noted to indicate a BF3 proportional chamber detector for the source range detector in Nuclear Instrumentation Channel 1. .This detector is described as a B-10 proportional detector in the text of Section 7.2, Paragraph 7.2.2.1.1; in addition, the B-10 detector, not a BF, detector was in place when the SAR was submitted. To correct the improper indication of the source range detector from a BF3 detec-tor to a B-10 detector, a corrected Figure 1-8 is attached. The same change is made on Figure 7-3.
Next, Paragraph 7.2.3 was reviewed and revised to include the following clarifications:
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- 1. Much of Section 7.2.3 was reworded to delineate more clearly the non-nuclear instrumentation system as existing and as described in the SAR; no substantive changes are included in this rewording.
- 2. Paragraph 7.2.3.2 describing the Control-Blade Withdrawal Inhibit System was rewritten to correspond exactly to the description on the UFTR Technical Specifications with some clarifications for ease of understand-ing. No substantive changes are included in this rewritten paragraph.
- 3. Paragraph 7.2.3.3 containing the description of the Automatic Control System was rewritten for clarification, again with no substantive changes.
- 4. A new Paragraph 7.2.3.4, " Process Monitoring and Control Systems" which expands upon the paragraphs following the description of the Automatic Control System was added. Again, the contents are not substantively changed; however, the section is now labelled and individual subsections are delineated in more detail as follows:
7.2.3.4.1, " Primary Coolant System" 7.2.3.4.2, " Secondary Coolant System" 7.2.3.4.3, " Shield Tank System" i Again this delineation of Paragraphs makes locating specific items easi-er; in addition, the information contained in these sections is better written and organized.
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Section 7.3 Reacter Trip System has also been reviewed and one change made to correct an SAR error in classifying trips. Section 7.3.1 " Nuclear In-duced Trips (Full Trips)" currently delineates four (4) trip conditions while Section 7.3.2 " Process Instrumentation Induced Trips (Rod-Drop Trips)" current-ly delineates thirteen (13) trip conditions. The last trip listed under Sec-tion 7.3.2 is "AC power failure (fail-safe criterion)." This trip condition has always caused a full trip (this is one of two methods used to dump the primary coolant to the storage tank) with two control blades partially removed so the rewritten Section 7.3 lists this trip under Section 7.3.1 so there are tive trip conditions listed under Section 7.3.2 and only twelve (12) trip con-ditions listed under 7.3.2. Section 7.3.2 is also relabelled as Process In-strumentation Induced Trips (Blade Drop Trips) to reflect UFTR use of control blades, not control rods. Again, the change simply reflects an accurate de-scription of a preexisting and licensed' system that. was incorrectly described.
in the Section 7.3 of the SAR submitted in 1981.
The review of Sections 7.4 and 7.5 does not show the need for any changes. The same is true for Sections 7.7 and 7.8. ' However, the review of Section 7.6;o, Safety-Related Display Instrumentation showed one incorrect
- reference at the end of the first paragraph. The reference to "Section 7.1.1.1"~ is changed to the proper reference which is "Section 7.1.2." In addition the remainder of Section 7.6 is rewritten to. provide a better, more accurate description of the Safety-Related Display Instrumentation. The only change in the description is in the final paragraph of 7.6 where the location of the portal monitoring systein is changed from "in the airlock" to "ou'tside the airlock" to reflect the current and pre-existing location of the portal monitor. This location is the preferred location to facilitate monitoring of
> personnel exiting not only from the Jairlock but also directly from the control. _
room if necessary. Again, the revision of this Section is not considered to involve any substantive changes from the system as relicensed but only to re-flect a more accurate and clearer description of the Safety-Related Display Instrumentation Systems.
In summary, this proposed revision simply corrects a number of typographi-cal or other inadvertent non-substantive errors and also provides a better, clearer and more accurate description of systems that are unchanged since sub-mittal of the UFTR Safety Analysis Report in 1981. The UFTR SAR Revision 2 along with a list of changed pages is included as Attachment II.
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ATTACHMENT II FINAL SAFETY ANALYSIS REPORT UNIVERSITY OF FLORIDA TRAINING REACTOR FACILITY LICENSE R-56; DOCKET NUMBER 50-83
-- Revision 2
'The attached Revision 2 pages revise the University of Floridd Training Reactor Final Safety Analysis Report as of July,1986. Revision 2 pages should be substituted to replace original pages as indicated in'the following table.
Original Pages Revision 2 Replacement Pages 1-21 1-21 7-7 7-7 7-9 7-9 7-11 1 7-11 7-13 7-13 7-15 7-15
- 7-16 7-16 and 7-17 Due to added material there is one mre page of text in Chapter 7 than ,
previously. Replacement of pages as noted here will put'all pages in the proper position.
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! NI CHANNEL I (LOG N , SAFETY I and . PERIOD)
LOG N I " LOG N" RECORDER PRE LOG B-10 - AMP AMP 4
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NI CHANNSL 1: UFTR Nuclear Instrumentation Channel 1 Diagram h&
Figure 1-8.
(Log N, Safety #1 and Period Channels).
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ID UFTR Nuclear Instrumentation Channel 1 Schematic (Log N, Safety #1 g Figure 7-3.
- and . Period Channels) . .
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servo amplifier, the signal is compared with the signal from the servo flux con-trol.
7.2.2.2+2 Safety Channel #2. As indicated in Figure 7-4, the safety channel receives a signal from an uncompensated ion chamber and consists of the ion chamber (with an independent high voltage supply), an operational amplifier, an adjustable bi-stable trip, and a meter ranging from 1% to 150% rated power. The Safety Chan-nel #2 system initiates a reactor trip at 125% power. Safety Channel #2 also ini-tiates a reactor trip whenever the high voltage applied to the chamber drops by 10%. The channel also generates test signals to cheek the functioning of the channel.
7.2.3 Non-Nuclear Instrumentation Channels The UFTR is supplied with several ps ocess instrumentation channels to monitor the normal operation of ~ the various systems, to aid in maintaining a steady-state power level and to trip the system whenever a potentially unsafe situation occurs or an instrument fails. Other channels supply information needed to safely operate the reactor but do not have protective functions. These Non-Nuclear . Instrumentation Channels are described in the next four subsections. '
7.2.3.1 Control-Blade Drive System. The control-blade drive circuit is shown in
' Figure 7-5; it consists of switches and indicating devices used in operating the four control blade drives. The twelve backlit push button switches are arranged in the center of the control panel in three rows of four vertical sets, one set for each control blade. Each set of switches contains a white DOWN switch, a red UP switch, and a yellow 0N (magnet on) switch.
- When the white DOWN light is illuminated, the control blade drive motor power circuit is prevented from drive action vf A the down backlit pushbutton switch. k' hen the red UP light is illuminated, control blades in manual control are similarly prevented from up' motion. The yellow ON light is series-coninected in the magnetic clutch power circuit so that if the yellow light is on, the magnetic clutch is energized; if the yellow ON light is off, the magnetic clutch is deenergized.
When any ON push button switch is depressed, magnet current is interrupted by actuatior, of the backlit switch, and the ON light remains extinguished for as long as the switch is depressed. If the control blade is above its down limit, the blade will gravity fall back into the core. Turning off the reactor key has tho same effect. In the event of a loss of power, these blades fail safe, falling into the
- core by gravity.
7.2.3.2 Control-Blade Withdrawal Inhibit System. The Control Blade Withdrawal Inhibit System is depicted in Figure 7-5; this Inhibit System is part of the reactor protection system and functions to prevent blade withdrawal for the following conditions:
- 1. Insufficient neutron source counts to assure the proper functioning of the source level instrumentation. A minimum source count rate of 2 cps (as measured by the wide range drawer operating on extended range) is required by the technical specifications, ,
- 2. A reactor period of 10 seconds or faster.
7-9 REV 2, 7/86
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- 3. Safety Channels 1 and 2 and wide range drawer Calibrate (or Safety 1 Trip Test) switches not in "0PERATE" or "0FF" condition. This inhibit condition assures the monitoring of neutron level increases and pre-vents disabling protective functions as control blades are raised.
- 4. Attempt to raise any two or more blades simultaneously when the reac-tor is in manual mode, or two or more safety blades simultaneously 1
when the reactor is in aiitomatic mode. This ' multiple blade withdrawal interlock is provided to prevent exceeding the maximum reactivity addition rate authorized by the UFTR Technical Specifications.
- 5. Power is raised in the automatic control mode at a period faster than 30 sec. The automatic. controller action is to inhibit further regula-ting blade withdrawal or drive the regulating blade down until the period is greater than. or equal to 30 seconds.
7.2.3.3 Automatic-Control System. The UFTR Automatic Control System'is used to~ hold reactor power at a steady power level during extended reactor operation at power and.may be used to make minor power changes within the maximum range of the switch setting. While the automatic mode of reactor control is selec-ted, the manual mode of operation is disabled; the control mode switch must be
' placed back in MANUAL before the regulating blade will respond to its UP or DOWN control switches. The neutron flux controller shown in Figure 7-6 com-
. pares the linear power signal from the pico-ammeter with the power demand sig-nal and moves the regulating blade in order to reduce any difference, thereby maintaining a steady power level.
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--7.2.3.4- Process Monitoring fnd Control Systems:
7.2.3.4.1 Primary Coolant System: A primary coolant flow monitor, with a ~
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sensor located in the primary fill line, indicates flow at the control console and prevents reactor operation, or trips the reactor, 'if flow is below the set point of 30 gpm (normal flow is about 40 gpm).
A coolant flow switch, located in the return line of the primary coolant system to the primary coolant storage tank, initiates a reactor trip in case of a loss of return flow. This flow switch serves as a backup for the-low flow reactor trip in the fill line ano activates only after the return line has been drained of water or the flow is reduced to less than about 10 gpm.
A sight glass, attached to the north wall of the reactor room, at the east side of the primary equipment pit, shows the water level in the core allowing a visual check of the primary coolant level. A float switch, located behind the sight glass, is wired to the reactor protection system. It prevents reactor operation, or activates the reacter trip system, when the water level in the core is below pre-set limits.
- Type "T" (copper-constantan) themocouples are located at each of the fuel box discharge lines to monitor water temperature from each fuel box to the,pri-mary coolant storage tank, and 2 thermocouples monitor the temperature of the bulk primary water going to and exiting from the core. The temperature infor-mation is sent to the 12 point recorder in the reactor control room. If any monitored temperature point exceeds preset levels, an audible alarm occurs at 150 F, and the reactor trips at 155 F.
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A resistivity meter mounted on the east wall of the control room enables monitoring resistivity of the primary coolant and functioning of the primary j coolant purification demineralizer system. The meter annunciates if system l resistivity drops below an adjustable, preset value. 1 To monitor water leakage from any source into the primary equipment pit, a level switch in a small sump at the lowest point of the pit floor will activate an alarm upon collecting.as little as two cups of water. The primary equipment pit sump alarm annunciates at a control unit mounted on the east wall of the control room.
7.2.3.4.2 Secondary Coolant System: The principal source of cooling water to remove reactor heat is the deep well, nominally rated at 200 gpm. A reduction of flow to 140 gpm will illuminate a yellow warning light on the right side of the control console. A reduction of flow to 60 gpm will illumi-nate a red scram warning light on the right side of the console, and will illuminate a red warning light on the secondary flow scram annunciator light.
Ten seconds later, the trip will occur. When using city water for reactor cooling, a low water flow of 8 gpm will trip the reactor. In either instance, the trip function is active only when reactor power is 1% or higher. A key operated switch on the console rear door switches secondary scram modes between well water or city water modes of operation.
7.2.3.4.3 Shield Tank System: A water level switch in the top of the reactor shield tank will trip the reactor when the water level drops below a preset value. This switch prevents reactor operation because of shield tank water loss due to evaporation or leakage. The purification loop on the west
- - side of- the shield tank has a flow indicator to monitor proper functioning of the loop.
7.3 Reactor Trip System The UFTR facility is provided with two types of reactor trips, both initiating the gravity insertion of all the control blades into the core.
These reactor trips can be classified into two categories:
- 1. Nuclear Instrumentation Induced Trips, which involve the insertion of the control blades into the core and the dumping of the primary water into the storage tank (this type of trip will dump primary water only l if 2 or mere control blades are not at bottom position);
- 2. Process Instrumentation Induced Trips, which involve only the inser- ,
tion of the control blades into the reactor core (without dumping of the primary water). Figure 7-7 shows a schematic diagram of the
! Protection System provided for the UFTR.
7.3.1 Nuclear Instrumentation Induced Trips (Full Trips)
One of five conditions must exist for the initiation of the Reactor Trip System with dump of primary water (Nuclear-Type Trip); these five conditions include:
7-13 REV 2, 7/86
- 1. Fast Period (3 seconds or less),
- 2. High Power, safety channel #1 (125%) or safety channel #2 (125%),
- 3. Reduction of high voltage to the neutron chambers of 10% or more,
- 4. Turning off the console magnet power switch.
- 5. A.C. power failure (fail-safe criterion).
7.3.2 Process Instrumentation Induced Trips (Blade-Drop Trips)
The conditions which must exist for the initiation of the Reactor Trip System without dump of primary water (process type trips) include:
- 1. Loss of power to the Reactor Vent Blower System.
- 2. Loss of power to Reactor Vent Diluting System.
- 3. Loss of power to the secondary system deep well pump when operating at or above 1 Kw and using this system for secondary cooling.
- 4. Dropping of secondary flow below 60 gpm (normal flow 200 gpm, alarm at 140 gpm) when operating at or above 1 Kw when using the well water ,
system for secondary cooling.
- 5. Dropping of secondary flow below 8 gpm when at or above 1 Kw when using city water for secondary cooling.
- 6. Drop in water level of the shield tank (about 4 in.)
- 7. Loss of power to primary coolant pump.
- 8. Reduction of primary coolant flow (normal 40 gpm, trip at 30 gpm);
flow sensor is located in the fill line.
- 9. Loss of primary coolant flow (return line).
- 10. Reduction of primary coolant level.
- 11. High temperature primary coolant return from the reactor (alarms at 150*F, trips at 155 F).
- 12. Manual reactor trip button depressed.
- A set of snnunciator lights located on the left side of the control con-sole indicates all scrams and 3 interlock conditions. In case of high reactor temperature, an audible alarm is set off at 150*F and the reactor trips at 155*F. The alarm continues to sound until the indicated temperature drops below 150*F.
A red rotating beacon located in the reactor cell together with three
" reactor on" lighted signs located on the outside of the east side of the Reactor building on the second floor level, on the entrance ~ hallway leading to the control room, and on the north outside reactor building wall, are all energized whenever the console key switch is turned to the "0N" position.
7.4 Engineering Safety Feature System As explained in Chapter 6, there are no separate Engineered Safety Features required in the UFTR aside from those built-in into the facility.
Therefore, no instrumentation or control system relative to this system is present.
7.5 Systems Required for Safe Shutdown .
The only system required for normal safe shutdown is the safety-control blades drive instrumentation channels allowing the operator to insert the blades into the core to shut the UFTR system down. Proper blade movement can 7-15 REV 2, 7/86
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be observed at the display panel where the four blade position indicators are located. In addition, the nuclear instrument channel read-outs provide another way for determining proper decrease in power for reactor shutdown. Neverthe-less, the only system really necessary for reactor shutdown is the control blade drive system. In case of failure of this system on a loss of power, the control blade system is' designed to fail safe; the blades drop by gravity into the system to shut the reactor down. A semi-annual measurement is made of
- blade drop times which'must be less than 1 second. Normal times are about 0.5 second. If the control blades do not function properly and the core overheats, the negative void and temperature coefficients will cause the core to go sub-critical and shut down even without insertion of the control blades. There-fore, instrumentation is not an absolute necessity for shutting the UFTR down because of its inherent safety features. In addition, the reactor can be made subcritical and power reduced by the operator-initiated action of dumping the primary coolant.
7.6 Safety-Related Display Instrumentation Readouts from all of the nuclear instrumentation and non-nuclear instru-mentation channels displayed at the reactor console are described in Section 7.2.1.
l The reactor vent system effluent monitor consists of a GM detector and preamplifier, which transmits a signal to the control room to monitor the gamma activity of the effluent in the downstream side of the absolute filter, before 1
dilution occurs. The stack monitoring system also consists of a log rate meter-circuit and indicator, a strip chart recorder, and an auxiliary log rate
_ m eter with.an adjustable alarm setting capability for monitoring the gross ac-tivity concentration of radioactive gases in the room effluent air entering the
- stack. If the activity reaches the preset (fixed) alarm level or if activity .
j reaches the auxiliary alarm setpoint (operator adjusted to the highest power level permitted or expected during the operation) the monitor will actuate an audible alarm in the control room.
A complete area radiation monitoring system consisting of three indepen-dent area monitors with remote detector assemblies and interconnecting cables, l
and strip chart recorders and count rate meters is available. The signals from i
j these detectors are sent directly to the log count rate meter and recorder, monitoring the gamma activity in the reactor room. Each detector has an energy compensated Geiger Counter with built-in Kr-85 check source which can be oper-ated from the control room. Two levels of alarm are provided. The high level latches in the alarm mode to preclude false hdicatica if a high level of radi-ation saturates the detector. Any two of the monitors seeing a high level of radiation will automatically actuate the building evacuation alarm. Actuation of the evacuation alarm automatically trips the reactor cell air conditioning j system and both the diluting fan and the vent fan.
i The stack monitor and 3 area monitor modules in the control room are equipped with test switches and green 'NO FAIL" lights that go out if the mo.dules do not receive signal pulses from the detectors. Floating battery packs supply power to the units in the event of electrical power loss.
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The reactor cell air monitoring system is equipped with a flow indicator l (LPM), a strip chart recorder and an audible and visible alarm setting. The monitor is a lead-shield, compact airborne particulate Geiger Counter detector. l The portal monitoring system outside the airlock leading from the reactor cell is a Beta-Gamma Portal Monitor (Model PCM-4A) console and portal frame.
It contains (eight) channels of Geiger tube detectors providing complete head to foot coverage of beta-gamma radiation plus individual alarm lights for each channel. An audible alarm will be activated any time the preset (count rate limit) is exceeded.
7.7 All Other Instrumentation Systems Required for Safety There are no other instrunentation systems required for the safe operation of the UFTR; all the necessary instrumentation has been covered in previous sections of this chapter.
7.8 Control Systems Not Required for Safety There are no control systems in the UFTR facility which do not have safety related functions as considered in this Safety Analysis Report. Consequently, all UFTR control systems have already been described in the preceding sections.
Even those controls which do not have a safety operational function do have a safety function in the sense of providing information on safe UFTR operation
'through read-outs supplied by the appropriate monitoring control.
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