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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20073B9901991-06-18018 June 1991 Forwards Rept Summarizing Findings of Orau Review of 59 Docket Files for Terminated Research & Test Reactors ML20245B4531989-06-0808 June 1989 Forwards Encl Listed Info on Decommissioned & Shutdown Reactors Requested During Discussions at Saxton on 890511 ML20155J4961988-10-19019 October 1988 Forwards Order Terminating License R-127,per 861110 Request. Amend 4 to Indenmity Agreement E-59,SER & Environ Assessment Also Encl IR 05000538/19880011988-08-0909 August 1988 Discusses Verification Survey Results as Suppl to Insp Rept 50-538/88-01 Re Termination of License R-127.Based on Radiological Surveys Facilities & Equipment Contamination Less than Limit & Exposure Measurements Less than Limit ML20151R9701988-07-29029 July 1988 Forwards Insp Rept 50-538/88-01 on 880623-24.No Violations or Deviations Noted ML20207B9161988-07-26026 July 1988 Forwards Corrected Page 4 of to G Kuzo,Correcting Error in Table of Smearable Surface Contamination ML20148G4481988-03-24024 March 1988 Submits Request for Verification of Final Survey & Issuance of Order to Terminate License R-127 Per 880126 Order. Certificate of Calibration Encl ML20150D9721988-03-18018 March 1988 Informs of NRC Relocation to Stated Address.Mailing Address Unchanged.A Adams Project Manager & TS Michaels back-up Project Manager ML20234F3531988-01-0606 January 1988 Lists Necessary Steps & Precautions Planned for Disassembly & Release of AGN-201 Reactor,Per 871221 Request ML20234F3881988-01-0505 January 1988 Informs of Awareness of NRC Requirements Re Possession & Assembly & Disposition of Component Parts of Reactor. Certification of Listed Items Under Oath Included ML20237D8271987-12-21021 December 1987 Forwards Request for Addl Info Re 861110 Application to Dismantle Facility & Dispose of Component Parts.Response Requested within 30 Days of Ltr Date ML20237K8561987-08-21021 August 1987 Forwards Tech Specs for Ludlum Model 3 Geiger Counters & Model 42-4,43-5 & 44-9 Detectors for Further Clarification of 870522 Response to NRC .B Leonard Will Be Representing Institute for Resource Mgt.Resume Encl ML20215A6761987-06-11011 June 1987 Informs of Name Change Due to NRR Reorganization & Appointment of a Adams as Facility Project Manager ML20214L1201987-05-22022 May 1987 Responds to 870422 Questions Re Licensee Decommissioning Plan.Diagram of Facility Organization for Decommissioning Provided.Rr Riley Resume & Radiation Control & Safety Manual Encl ML20213A6441987-04-22022 April 1987 Forwards Request for Addl Info Re Decommissioning Plan Supporting Application for Authorization to Decommission Facility.Response Requested within 30 Days ML20211C7001987-02-0606 February 1987 Forwards Fr Notice of Proposed Decommissioning of Memphis State Univ Reactor,Per 861112 Supplemented Application ML20207M9491987-01-0505 January 1987 Forwards Legible Pages of Request for Decommissioning Reactor ML20214C3701986-11-12012 November 1986 Forwards Request for Termination Survey,Application for Decommissioning & Decommissioning Plan.Qa Plan for Shipment of Reactor Fuel Will Be Sent to C Macdonald,Transportation Certification Branch,As Soon as Possible ML20214C4011986-11-10010 November 1986 Forwards Request for NRC Termination Survey of AGN-201, License R-127.Reactor Placed in Safstor Status & Awaits Final Removal by Inst for Resource Mgt After NRC & EPA Approval of Reactor Possession ML20214C4351986-11-10010 November 1986 Requests Decommissioning of AGN-201,License R-127.Fuel Removed & Placed in Safstor Status.Electrical Connections Between Reactor & Control Panel Disconnected & Drive Rod Assemblies & Core Tank Removed,Surveyed & Stored ML20154R3731986-03-26026 March 1986 Advises of NRR Reorganization.Telephone Number of J Dosa Changed.D Tondi New Section Leader for Nonpower Reactors & Safeguards Licensing Section.Correspondence Should Be Addressed to Nrc,Attention Document Control Desk ML20127J1861985-06-17017 June 1985 Forwards Amend 5 to License R-127 & Safety Evaluation. Amend Authorizes Possession,But Not Operation,Of Nuclear Reactor Located at Memphis State Univ in Memphis,Tn ML20099L1551985-03-15015 March 1985 Forwards Application for Amend to License R-127,authorizing possession-only in Safstor Status.Approval of Request Will Assure Protective Storage of Reactor & Reactor Fuel While Plans for Decommissioning Finalized ML20099H8411985-03-15015 March 1985 Forwards Upgraded Physical Security Plan Supporting Proposed Amend to License R-127,authorizing Safstor Status for Reactor & Reactor Fuel.Plan Withheld (Ref 10CFR73.21) ML20113F9691985-01-18018 January 1985 Requests Extension Until 850301 to Implement Revised Emergency Plan ML17298A6041983-08-0505 August 1983 FOIA Request for Agency Records Relevant to &/Or Generated in Connection W/Nrc Investigations,Insp or Repts on Allegations Made by R Gunderson & W Royce Re Facilities ML20080T5021983-07-14014 July 1983 Requests Review of NRC Serious Mishandling of Investigation of Worker Allegations Re Deficiencies in Electrical Work & Startup Testing Program at Facilities,On Behalf of R Gunderson & W Royce.Related Matl Encl ML20077H1131983-07-13013 July 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-538/83-01.Corrective Actions:Proper Planning & Priorities for Emergency Plan Audits Will Be Discussed W/Reactor Safety Committee at Future Meetings ML17298A4271983-06-23023 June 1983 Submits Required Data to Demonstrate That Line Voltage Regulators Perform as Acceptable Isolation Device by Limiting Primary Current Under Short Circuit Conditions to full-load Primary Current,Per SER (NUREG-0857) ML20069B0801983-03-0909 March 1983 Forwards Nuclear Reactor Operations Annual Rept for 1982 ML20028A1631982-10-26026 October 1982 Forwards Public Version of Revised Preliminary Draft Emergency Plan 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 ML19312A5641982-05-14014 May 1982 Provides Clarification to Amend 1 to License R-127 Re Resolution of Operating Conditions.Amend Authorizes Licensee to Operate Reactor at steady-state Power Levels ML20051L6581982-05-0505 May 1982 Forwards Annual Rept of Nuclear Reactor Operations. ML20010B6111981-05-27027 May 1981 Forwards Endorsement 6 to Nelia Policy NF-251 & Amend 2 to Indemnity Agreement E-59,per 800924 Request ML20003G0391981-04-20020 April 1981 Forwards Revised Page 25 to Physical Security Plan for SNM of Low Strategic Significance.Plan Withheld (Ref 10CFR2.790) ML19352A2801981-04-0303 April 1981 Forwards Revised Pages 13 & 14 for Physical Security Plan. Encls Withheld (Ref 10CFR2.790) ML19350C1461981-03-27027 March 1981 Forwards Ctr for Nuclear Studies,Memphis State Univ,1980 Annual Rept,Nuclear Reactor Operations. ML19321B1621980-07-23023 July 1980 Forwards Physical Security Plan for SNM of Low Strategic Significance.Plan Withheld (Ref 10CFR2.790) ML20149K1911980-05-0707 May 1980 Generic Ltr 80-38 to All Nonpower Reactor Licensees Re NPR Physical Protection Requirements.Summary of Certain NPR Physical Protection Requirements Encl & Should Aid in Determining Safeguards Requirements Applicable to Facility ML19296D1591980-02-0505 February 1980 Forwards 1979 Annual Rept of Nuclear Reactor Operations. ML19211A9101979-12-14014 December 1979 Forwards Executed Amend 3 to Indemnity Agreement E-59 Defining in Course of Transportation. ML19290B7371979-11-26026 November 1979 Forwards Followup Rept to RO-79-3 ML19249B4321979-08-28028 August 1979 Corrects Typographical Errors & Omissions in Application for Amend 1 to License R-127 Submitted in 790803 Ltr ML19248D3741979-08-0303 August 1979 Forwards Amend 1 to License R-127 ML19282C6191979-03-23023 March 1979 Requests Amend to License R-127 to Allow Power Operation at 20 Watt Levels Continuously & 1,000 Watt Levels Intermittantly ML19273B3461979-03-13013 March 1979 Forwards Followup Rept to Reportable Event on 790305 ML19276E8791979-01-29029 January 1979 Submits Followup Rept to Occurrence at AGN-201 Reactor Facility on 790125 Per Section 6.9.2 of App a to License R-127.Electrical Power Outage Occurred During Reactor Operation.Svc Restored in 3-h ML19259B2761978-12-22022 December 1978 DD Ebert Has Satisfactorily Completed 781218-21 Program in AGN-201 Reactor Operations Training.Recommends Individual for Operator License 1991-06-18
[Table view] Category:EDUCATIONAL INSTITUTION TO NRC
MONTHYEARML20207B9161988-07-26026 July 1988 Forwards Corrected Page 4 of to G Kuzo,Correcting Error in Table of Smearable Surface Contamination ML20148G4481988-03-24024 March 1988 Submits Request for Verification of Final Survey & Issuance of Order to Terminate License R-127 Per 880126 Order. Certificate of Calibration Encl ML20234F3531988-01-0606 January 1988 Lists Necessary Steps & Precautions Planned for Disassembly & Release of AGN-201 Reactor,Per 871221 Request ML20237K8561987-08-21021 August 1987 Forwards Tech Specs for Ludlum Model 3 Geiger Counters & Model 42-4,43-5 & 44-9 Detectors for Further Clarification of 870522 Response to NRC .B Leonard Will Be Representing Institute for Resource Mgt.Resume Encl ML20214L1201987-05-22022 May 1987 Responds to 870422 Questions Re Licensee Decommissioning Plan.Diagram of Facility Organization for Decommissioning Provided.Rr Riley Resume & Radiation Control & Safety Manual Encl ML20207M9491987-01-0505 January 1987 Forwards Legible Pages of Request for Decommissioning Reactor ML20214C3701986-11-12012 November 1986 Forwards Request for Termination Survey,Application for Decommissioning & Decommissioning Plan.Qa Plan for Shipment of Reactor Fuel Will Be Sent to C Macdonald,Transportation Certification Branch,As Soon as Possible ML20214C4011986-11-10010 November 1986 Forwards Request for NRC Termination Survey of AGN-201, License R-127.Reactor Placed in Safstor Status & Awaits Final Removal by Inst for Resource Mgt After NRC & EPA Approval of Reactor Possession ML20214C4351986-11-10010 November 1986 Requests Decommissioning of AGN-201,License R-127.Fuel Removed & Placed in Safstor Status.Electrical Connections Between Reactor & Control Panel Disconnected & Drive Rod Assemblies & Core Tank Removed,Surveyed & Stored ML20099L1551985-03-15015 March 1985 Forwards Application for Amend to License R-127,authorizing possession-only in Safstor Status.Approval of Request Will Assure Protective Storage of Reactor & Reactor Fuel While Plans for Decommissioning Finalized ML20099H8411985-03-15015 March 1985 Forwards Upgraded Physical Security Plan Supporting Proposed Amend to License R-127,authorizing Safstor Status for Reactor & Reactor Fuel.Plan Withheld (Ref 10CFR73.21) ML20113F9691985-01-18018 January 1985 Requests Extension Until 850301 to Implement Revised Emergency Plan ML20077H1131983-07-13013 July 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-538/83-01.Corrective Actions:Proper Planning & Priorities for Emergency Plan Audits Will Be Discussed W/Reactor Safety Committee at Future Meetings ML20069B0801983-03-0909 March 1983 Forwards Nuclear Reactor Operations Annual Rept for 1982 ML20028A1631982-10-26026 October 1982 Forwards Public Version of Revised Preliminary Draft Emergency Plan ML19312A5641982-05-14014 May 1982 Provides Clarification to Amend 1 to License R-127 Re Resolution of Operating Conditions.Amend Authorizes Licensee to Operate Reactor at steady-state Power Levels ML20051L6581982-05-0505 May 1982 Forwards Annual Rept of Nuclear Reactor Operations. ML20010B6111981-05-27027 May 1981 Forwards Endorsement 6 to Nelia Policy NF-251 & Amend 2 to Indemnity Agreement E-59,per 800924 Request ML20003G0391981-04-20020 April 1981 Forwards Revised Page 25 to Physical Security Plan for SNM of Low Strategic Significance.Plan Withheld (Ref 10CFR2.790) ML19352A2801981-04-0303 April 1981 Forwards Revised Pages 13 & 14 for Physical Security Plan. Encls Withheld (Ref 10CFR2.790) ML19350C1461981-03-27027 March 1981 Forwards Ctr for Nuclear Studies,Memphis State Univ,1980 Annual Rept,Nuclear Reactor Operations. ML19321B1621980-07-23023 July 1980 Forwards Physical Security Plan for SNM of Low Strategic Significance.Plan Withheld (Ref 10CFR2.790) ML19296D1591980-02-0505 February 1980 Forwards 1979 Annual Rept of Nuclear Reactor Operations. ML19211A9101979-12-14014 December 1979 Forwards Executed Amend 3 to Indemnity Agreement E-59 Defining in Course of Transportation. ML19290B7371979-11-26026 November 1979 Forwards Followup Rept to RO-79-3 ML19249B4321979-08-28028 August 1979 Corrects Typographical Errors & Omissions in Application for Amend 1 to License R-127 Submitted in 790803 Ltr ML19248D3741979-08-0303 August 1979 Forwards Amend 1 to License R-127 ML19282C6191979-03-23023 March 1979 Requests Amend to License R-127 to Allow Power Operation at 20 Watt Levels Continuously & 1,000 Watt Levels Intermittantly ML19273B3461979-03-13013 March 1979 Forwards Followup Rept to Reportable Event on 790305 ML19276E8791979-01-29029 January 1979 Submits Followup Rept to Occurrence at AGN-201 Reactor Facility on 790125 Per Section 6.9.2 of App a to License R-127.Electrical Power Outage Occurred During Reactor Operation.Svc Restored in 3-h ML19259B2761978-12-22022 December 1978 DD Ebert Has Satisfactorily Completed 781218-21 Program in AGN-201 Reactor Operations Training.Recommends Individual for Operator License 1988-07-26
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20073B9901991-06-18018 June 1991 Forwards Rept Summarizing Findings of Orau Review of 59 Docket Files for Terminated Research & Test Reactors ML20207B9161988-07-26026 July 1988 Forwards Corrected Page 4 of to G Kuzo,Correcting Error in Table of Smearable Surface Contamination ML20148G4481988-03-24024 March 1988 Submits Request for Verification of Final Survey & Issuance of Order to Terminate License R-127 Per 880126 Order. Certificate of Calibration Encl ML20234F3531988-01-0606 January 1988 Lists Necessary Steps & Precautions Planned for Disassembly & Release of AGN-201 Reactor,Per 871221 Request ML20237K8561987-08-21021 August 1987 Forwards Tech Specs for Ludlum Model 3 Geiger Counters & Model 42-4,43-5 & 44-9 Detectors for Further Clarification of 870522 Response to NRC .B Leonard Will Be Representing Institute for Resource Mgt.Resume Encl ML20214L1201987-05-22022 May 1987 Responds to 870422 Questions Re Licensee Decommissioning Plan.Diagram of Facility Organization for Decommissioning Provided.Rr Riley Resume & Radiation Control & Safety Manual Encl ML20207M9491987-01-0505 January 1987 Forwards Legible Pages of Request for Decommissioning Reactor ML20214C3701986-11-12012 November 1986 Forwards Request for Termination Survey,Application for Decommissioning & Decommissioning Plan.Qa Plan for Shipment of Reactor Fuel Will Be Sent to C Macdonald,Transportation Certification Branch,As Soon as Possible ML20214C4011986-11-10010 November 1986 Forwards Request for NRC Termination Survey of AGN-201, License R-127.Reactor Placed in Safstor Status & Awaits Final Removal by Inst for Resource Mgt After NRC & EPA Approval of Reactor Possession ML20214C4351986-11-10010 November 1986 Requests Decommissioning of AGN-201,License R-127.Fuel Removed & Placed in Safstor Status.Electrical Connections Between Reactor & Control Panel Disconnected & Drive Rod Assemblies & Core Tank Removed,Surveyed & Stored ML20099H8411985-03-15015 March 1985 Forwards Upgraded Physical Security Plan Supporting Proposed Amend to License R-127,authorizing Safstor Status for Reactor & Reactor Fuel.Plan Withheld (Ref 10CFR73.21) ML20099L1551985-03-15015 March 1985 Forwards Application for Amend to License R-127,authorizing possession-only in Safstor Status.Approval of Request Will Assure Protective Storage of Reactor & Reactor Fuel While Plans for Decommissioning Finalized ML20113F9691985-01-18018 January 1985 Requests Extension Until 850301 to Implement Revised Emergency Plan ML17298A6041983-08-0505 August 1983 FOIA Request for Agency Records Relevant to &/Or Generated in Connection W/Nrc Investigations,Insp or Repts on Allegations Made by R Gunderson & W Royce Re Facilities ML20080T5021983-07-14014 July 1983 Requests Review of NRC Serious Mishandling of Investigation of Worker Allegations Re Deficiencies in Electrical Work & Startup Testing Program at Facilities,On Behalf of R Gunderson & W Royce.Related Matl Encl ML20077H1131983-07-13013 July 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-538/83-01.Corrective Actions:Proper Planning & Priorities for Emergency Plan Audits Will Be Discussed W/Reactor Safety Committee at Future Meetings ML17298A4271983-06-23023 June 1983 Submits Required Data to Demonstrate That Line Voltage Regulators Perform as Acceptable Isolation Device by Limiting Primary Current Under Short Circuit Conditions to full-load Primary Current,Per SER (NUREG-0857) ML20069B0801983-03-0909 March 1983 Forwards Nuclear Reactor Operations Annual Rept for 1982 ML20028A1631982-10-26026 October 1982 Forwards Public Version of Revised Preliminary Draft Emergency Plan ML19312A5641982-05-14014 May 1982 Provides Clarification to Amend 1 to License R-127 Re Resolution of Operating Conditions.Amend Authorizes Licensee to Operate Reactor at steady-state Power Levels ML20051L6581982-05-0505 May 1982 Forwards Annual Rept of Nuclear Reactor Operations. ML20010B6111981-05-27027 May 1981 Forwards Endorsement 6 to Nelia Policy NF-251 & Amend 2 to Indemnity Agreement E-59,per 800924 Request ML20003G0391981-04-20020 April 1981 Forwards Revised Page 25 to Physical Security Plan for SNM of Low Strategic Significance.Plan Withheld (Ref 10CFR2.790) ML19352A2801981-04-0303 April 1981 Forwards Revised Pages 13 & 14 for Physical Security Plan. Encls Withheld (Ref 10CFR2.790) ML19350C1461981-03-27027 March 1981 Forwards Ctr for Nuclear Studies,Memphis State Univ,1980 Annual Rept,Nuclear Reactor Operations. ML19321B1621980-07-23023 July 1980 Forwards Physical Security Plan for SNM of Low Strategic Significance.Plan Withheld (Ref 10CFR2.790) ML19296D1591980-02-0505 February 1980 Forwards 1979 Annual Rept of Nuclear Reactor Operations. ML19211A9101979-12-14014 December 1979 Forwards Executed Amend 3 to Indemnity Agreement E-59 Defining in Course of Transportation. ML19290B7371979-11-26026 November 1979 Forwards Followup Rept to RO-79-3 ML19249B4321979-08-28028 August 1979 Corrects Typographical Errors & Omissions in Application for Amend 1 to License R-127 Submitted in 790803 Ltr ML19248D3741979-08-0303 August 1979 Forwards Amend 1 to License R-127 ML19282C6191979-03-23023 March 1979 Requests Amend to License R-127 to Allow Power Operation at 20 Watt Levels Continuously & 1,000 Watt Levels Intermittantly ML19273B3461979-03-13013 March 1979 Forwards Followup Rept to Reportable Event on 790305 ML19276E8791979-01-29029 January 1979 Submits Followup Rept to Occurrence at AGN-201 Reactor Facility on 790125 Per Section 6.9.2 of App a to License R-127.Electrical Power Outage Occurred During Reactor Operation.Svc Restored in 3-h ML19259B2761978-12-22022 December 1978 DD Ebert Has Satisfactorily Completed 781218-21 Program in AGN-201 Reactor Operations Training.Recommends Individual for Operator License 1991-06-18
[Table view] |
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Q; S\ MEMPHIS STATE UNIVERSITY s
- F p MEMPHIS. TENNESSEE 38152 Df4 (N 9 January 29, 1979
, . . l
~
'v h er for Nuclear Studies llsee of the 1)nrector (901) 454-268:
Director Region II, U. S. Nuclear Regulatory Cormiission Office of Inspection and Enforcement 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
Dear Sir:
Enclosed is the follow-up report to a reportable event that occurred at the Memphis State University AGN-201 Reactor facility on January 25, 1979. The report is submitted in accordance with section 6.9.2 of Appendix A to Facility Operating License R-127, Docket No. 50-538.
An electrical power outage occurred during reactor operation Restoration which resulted in an unscheduled reactor shutdown.
of electric power service was completed approximately three hours later, and normal reactor operation was resumed. Initial notifi-cation to your office was made by telephone and confimed by mail-gram on January 25, 1979.
Sincerely D. W Jones Director y RLD:dc
Enclosures:
(3) Follow-up Report to Reportable Occurrence cc: Dr. J. A. Rhodes, MSU Mr. J. Skolls, USNRC Mr. R. L. Dietz (5)
Mr. L. B. O' Kelly, MSU RCSC Dr. J. C. Williams, MSU RSC Mr. P. S. Hobbs, MSU Mr. J. W. Dutton, MSU
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Reactor Shutdown Checkoff Procedure (OP-5) was completed at 12:48 p.m., CST. Following a suitable wamup time, the Reactor Prestartup Checkoff Procedure (OP-2) was perfomed and no abnor-malities were noted. Reactor operation was resumed at 2:06 p.m.,
CST, January 25, 1979.
- 5. Safety Significance of the Occurrence.
None. A loss of electrical power de-energizes the Safety and Coarse Control Rod Holding Magnets causing a reactor scram and thus assures safe and inmediate shutdown in case of a power outa ge. Reactor systems perfomed as designed and as required by technical specification 3.3.
- 6. Cause of Failure.
The electric power outage was a result of outside contractor demolition and construction activities which interrupted the main service feeder to the entire MSU South Campus.
- 7. Corrective Action.
None. Corrective action to restore the South Campus electric service feeder was perfomed by MSU Physical Plant personnel and is under the cognizance and control of organizations outside the Center for Nuclear Studies and the AGN-201 Reactor Cacility.
- 8. Measures to Prevent Recurrence.
None. Measures to prevent recurrence of an electric power ;
outage of the nature described in this report are not within the capabilities of the Center for Nuclear Studies or AGN-201 Reactor Facility staff.
. 9. Similar Reportable Occurrences.
None.
Prepared by: (
Reactor ervisor
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- reactor room area gama monitor remained energized via an automatic-actuated, internal battery. Control Room and Reactor Roan lighting was provided by the automatic-actuated, battery powered, emergency lighting system.
Confirmation of the reactor's shutdown status was imediately made by conducting a gamma radiation survey in accordance with Facility Emergency Procedure EP-3. Radiation levels at the reactor shield tank were observed to be f .02 mR/hr wnich is less than one-tenth the dose rate expected at 4.8 millfWatts and is approxi-mately the nonnal background dose rate. The H 3 B03sample was removed from the experiment port, the Cadmium-loaded shutdown rod was installed and locked into the experiment port, and the Ra-Be neutron source was manually inserted to its nomal snutdown posi-tion. The reactor Shutdown Checkoff Procedure (0P-5) was completed to the maximum extent possible. Another more detailed gama radiation survey was conducted approximately one hour after the incident. Maximum dose-rate observed during this survey was recorded as 5 .01 mR/hr.
The Reactor Supervisor was in the Control Room at the time of the power failure. The Memphis State University Radiation Safety Officer was imediately notified. The event was reported to the USNRC Region II, Office of Inspection and Enforcernent, via telephone conversation between the CNS Operations Supervisor and Mr. J. Skolls (11:30 a.m., CST), and confiimed by mailgram to ,
the Director, USNRC Region II (3:07 p.m., EST) in compliance with section 6.9.2.a of the Facility Technical Specifications.
Electric power service was restored to the MSU South Campus at 12:41 p.m., CST. The reactor console was imediately energized to pemit the Safety and Coarse Control Rod f4agnet Assemblies and the Fine Control Rod to be returned to their fully withdrawn limits. Console instrumentation was energized and the nomal
- b. The reactor was supercritical with period 355 seconds at a power level of 4.8 milliWatts'. Safety Rods were fully in-serted (24 cm), Coarse Control Rod at 22.97 cm, Fine Control Rod at 16.40 cm, and reactor temperature was 19 C. A lucite sample (1 in. x .87 in. dia.) containing .12 grams H B0 was installed in the small diameter experiment port 3 3 at a position five inches from the core centerline.
- 4. Narrative.
At 9:51 a.m., CST, on January 25, 1979, contractor demoli- ~
tion and construction activities resulted in an electrical power outage to the entire South Campus of Memphis State University.
The AGN-201 Reactor, located on South Campus, was being operated by a student operator under the direct supervision of licensed Senior Operators for the purpose of measuring reactivity impor-tance functions. At the time of the unplanned event, the operator was increasing reactor power to achieve a convenient level at which to make a detemination of the reactivity effect from a lucite sample containing .12 grams H 3 00 3 . This exercise was being conducted as part of an approved operator training program.
The reactor stranTned, as designed and as required by the technical specifications, due to loss of reactor control power which interrupted electrical current to the Control Rod Holding Magnets. The sound of the Safety and Coarse Control Rods con- .
tacting their dashpots (fully withdrawn position) was heard by the operator and Senior Operato - in the Control Room, via a microphone located in the reactor skirt area, prior to the announcing / intercom system becoming inoperative. The Fine
. Control Rod, which has no scram function, ranained inserted to 16.40 cm. and the Safety and Coarse Rod Magnet Assemblies remained at the pre-scram positions. The Ra-Be neutron source renained at its withdrawn position. All console instrumenta-tion, alams, and safety circuits were deenergized. The
MEMPHIS STATE UNIVERSITY AGN-201 NUCLEAR REACTOR FACILITY LICENSE R-127, DOCKET N0. 50-538 FOLLOW-UP REPORT TO REPORTABLE OCCURRENCE Date of Report; January 29, 1979 Date of Occurrence: January 25, 1979 Date NRC Notification: ,lanuary 25, 1979
- 1. Reactor.
AGN-201, seri ' 108. Located at the Center for Nuclear Studies, Memphis State University, Memphis, Tennessee. Facility Operating License R-127, Docket No. 50-538.
- 2. Reportable Occurrence.
Electric power service to the Memphis State University South Campus was interrupted as a result of outside contractor demolition and construction activities. The unscheduled power outage occurred during AGN-201 reactor operation and, as a direct result of the event, caused reactor shutdown in the form of a silent reactor scram. Item 6.9.2.a.(7) of the Facility Technical Specifications applies.
- 3. Conditions at Time of Occurrence.
- a. An operator training program was in progress for the purpose of providing reactor startup experience for prospective licensees.
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