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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 ML20245D3221989-04-24024 April 1989 Advises That No Record Retention Required for Former License R-62 ML20154Q3031988-05-24024 May 1988 Forwards Insp Rept 50-124/88-01 on 880404.No Violations or Deviations Noted 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 ML20149H8101988-02-17017 February 1988 Informs That Reactor Bldg Can Be Released for Unrestricted Use Since Residual Contamination Levels for Reactor Bldg Comply W/Reg Guide 1.86,Table 1 in Response to 860717 License Termination Request ML20196E8031988-02-0505 February 1988 Provides Addl Clarification to Final Decommissioning Rept. Data from Resurvey of Suspect Blocks Confirm That Release Criteria Not Exceeded.Resurvey Encl ML20196D5151988-02-0303 February 1988 Forwards Orau 88/A-74, Confirmatory Radiological Survey of Argonaut Reactor Facility,Virginia Polytechnic Inst & State Univ,Blacksburg,Va, Final Rept.Facility Meets Guidelines for Terminating Operating Reactors ML20238C9981987-09-0303 September 1987 Forwards Amend to Final Rept Re Dismantlement & Disposition of Facility,Including Survey Maps Denoting Grids Surveyed & Survey Data on Ventilation Duct Work & Stack,In Response to Items Identified in Insp Rept 50-124/87-01 ML20237H6661987-08-0707 August 1987 Forwards Insp Rept 50-124/87-01 on 870727-29.No Violations or Deviations Noted ML20215D2151987-06-11011 June 1987 Informs That T Micheals Assigned as Project Manager for Facility Due to NRR Reorganization ML20206D5901987-04-0606 April 1987 Forwards Argonaut Reactor Facility Decommissioning Final Rept, Per 861029 Dismantlement & Disposition Order.Facility Now Meets Unrestricted Use Criteria.Termination of License Requested ML20211G1361986-10-29029 October 1986 Forwards Order Authorizing Dismantling of Facility & Disposition of Component Parts,Finding of No Significant Environ Impact,Safety Evaluation & Environ Assessment ML20214F6671986-09-10010 September 1986 Notifies of 861029-30 Physical Protection Seminar in Cherry Hill,Nj to Discuss Results of 12-yr Implementation of 10CFR73 for Protection Against Radiological Sabotage. Preliminary Agenda Encl IR 05000124/19860011986-08-22022 August 1986 Forwards Insp Rept 50-124/86-01 on 860808.No Violation or Deviation Noted.Rept Withheld (Ref 10CFR2.790 & 73.21) ML20212M2891986-08-19019 August 1986 Forwards Notice of Proposed Issuance of Orders Authorizing Dismantling of Facility & Disposition of Component Parts & Terminating Facility License, for Publication Per 860717 Application ML20214K6051986-08-13013 August 1986 Provides Clarification Re Calibr of Instrumentation Utilized for Radiation Detection,Per 860717 Request for Order Authorizing Facility Dismantlement & Disposition & Termination of License R-62 ML20212N9271986-08-11011 August 1986 Forwards Sections I & II to Region II Incident Response Plan,Incorporating Lessons Learned from 1984 Full Field Exercise.Section III Withheld.W/O Encl ML20203G0071986-07-17017 July 1986 Requests Order Authorizing Facility Dismantling & Disposition to Terminate License R-62 & Publication of Fr Notice.Forwards Decommissioning Plan,Including Security Plan,Tech Specs & Environ Rept ML20206M1691986-06-20020 June 1986 Grants 860516 Request to Take Samples from Biological Shielding of Reactor to Determine Amount of above-limit & Exempt Quantities of Reinforced Concrete That Must Be Removed ML20140G7181986-03-27027 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 ML20138G9801985-10-0808 October 1985 Responds to Ltr Re Removal of Unirradiated Highly Enriched U Fuel to Secure Facility.Fuel Will Be Shipped by Proto-Power Bisco to Doe.No Fuel Will Remain at Facility by 860101 ML20112E6161985-01-10010 January 1985 Forwards Revised Tech Specs,Reflecting 841022 Request for Possession Only License ML20140C0381984-05-0808 May 1984 Partial Response to FOIA Request for All Physical Security & Safeguards Insp Repts from 1979 to Present for Ucla,Univs of Washington & Florida,Virginia Polytechnic Inst & Iowa State Univ.Info Partially Withheld (Ref FOIA Exemption 4) IA-84-227, Partial Response to FOIA Request for All Physical Security & Safeguards Insp Repts from 1979 to Present for Ucla,Univs of Washington & Florida,Virginia Polytechnic Inst & Iowa State Univ.Info Partially Withheld (Ref FOIA Exemption 4)1984-05-0808 May 1984 Partial Response to FOIA Request for All Physical Security & Safeguards Insp Repts from 1979 to Present for Ucla,Univs of Washington & Florida,Virginia Polytechnic Inst & Iowa State Univ.Info Partially Withheld (Ref FOIA Exemption 4) ML20140C0351984-03-24024 March 1984 FOIA Request for All Physical & Safeguards Insp Repts from 1979 to Present at Ucla,Univ of Washington,Univ of Florida, Virginia Polytechnic Inst & Iowa State Univ ML20079G2681984-01-17017 January 1984 Responds to 831216 Generic Ltr 83-41 Re Fast Cold Starts of Diesel Generators.No Generators Used at Facility.No Response Required ML20083G0631983-12-14014 December 1983 Describes Actions to Rectify Violation of Operator Requalification program.Hot-functional Test Program Will Be Used to Familiarize Operators W/Console.All Procedures Will Be Reviewed.Actions Adequate Until Unit Restarted ML20085L1831983-09-27027 September 1983 Forwards Revs 1 & 2 to Physical Security Plan.Revs Withheld ML20069E7341983-03-17017 March 1983 Confirms That Proposal for Tech Spec Change Has Been Reviewed & Approved by Reactor Safety Committee ML20069E7171983-03-15015 March 1983 Forwards Remaining Tech Spec Changes for Amend to License R-62.Actual Connection & Testing Contingent on N-16 Calculations & Approved Test Procedures.Table Listing Summary of Specific Changes Encl ML20071C4081983-02-22022 February 1983 Forwards Annual Rept for VA Polytechnic Inst & State Univ Research Reactor,1982 ML20064M0161983-01-11011 January 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-124/82-01.Corrective Actions:Procedure Initiated for Reactor Audit & Review & SAR Will Be Submitted to Radiation Safety Committee Re Manual Control Rod Withdrawal ML20079J4131982-12-22022 December 1982 Forwards Confirmation by Reactor Safety Committee Chairman That Proposal for Tech Spec Change Reviewed & Approved ML20079J4171982-12-16016 December 1982 Forwards Application to Amend License R-62,revising Tech Specs to Delete Ultrasonic Flow Detector W/Paddle Wheel Detector w/1% Accuracy Min ML20066G4471982-11-0202 November 1982 Forwards Public Version of Revised Emergency Response 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 ML20038A6561981-11-0909 November 1981 Advises That Dr Pratner Will Replace AP Curtner as Reactor Supervisor on 811101 ML20010H2211981-08-25025 August 1981 Responds to NRC 810817 Ltr Re Violation Noted in IE Insp Rept 50-124/81-02.Corrective Actions:Interim Procedure Change Has Been Properly Documented & Approved According to Procedure VI.6 ML19341C5371981-02-25025 February 1981 Forwards Annual Operations Rept,Nuclear Research Reactor, VA Polytechnic Inst & State Univ,1980. ML20003C0371981-02-23023 February 1981 Forwards Final Reactor Operator Requalification Program, Revised to Include Deficient Items Identified in NRC 810212 Ltr,For Inclusion in Renewal Application for License R-62 ML19345B9971980-11-26026 November 1980 Forwards Security Plan & Application for Renewal of License R-62.W/o Encls ML19344E4431980-08-25025 August 1980 Forwards Complete Application for Class 104 License for Nuclear Research Reactor Facility.Prior Issuances Encl. Application Available in Central Files Only ML19330C3531980-08-0101 August 1980 Forwards Data Re Environ Radiation Dispersion,Per M Wohl Telcon Request ML19321A4781980-07-18018 July 1980 Forwards Proposed Tech Specs & Operator Requalification Program for Research Reactor Per License R-62 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 ML19345E2541980-03-19019 March 1980 Forwards Univ Draft Emergency Plan ML19309A5301980-03-19019 March 1980 Forwards PSAR ML19309B6191980-03-19019 March 1980 Forwards Sept 1979 Draft Emergency Plan ML19296B4121980-02-13013 February 1980 Forwards Annual Operating Rept 1979 1991-06-18
[Table view] Category:EDUCATIONAL INSTITUTION TO NRC
MONTHYEARML20196E8031988-02-0505 February 1988 Provides Addl Clarification to Final Decommissioning Rept. Data from Resurvey of Suspect Blocks Confirm That Release Criteria Not Exceeded.Resurvey Encl ML20238C9981987-09-0303 September 1987 Forwards Amend to Final Rept Re Dismantlement & Disposition of Facility,Including Survey Maps Denoting Grids Surveyed & Survey Data on Ventilation Duct Work & Stack,In Response to Items Identified in Insp Rept 50-124/87-01 ML20206D5901987-04-0606 April 1987 Forwards Argonaut Reactor Facility Decommissioning Final Rept, Per 861029 Dismantlement & Disposition Order.Facility Now Meets Unrestricted Use Criteria.Termination of License Requested ML20214K6051986-08-13013 August 1986 Provides Clarification Re Calibr of Instrumentation Utilized for Radiation Detection,Per 860717 Request for Order Authorizing Facility Dismantlement & Disposition & Termination of License R-62 ML20203G0071986-07-17017 July 1986 Requests Order Authorizing Facility Dismantling & Disposition to Terminate License R-62 & Publication of Fr Notice.Forwards Decommissioning Plan,Including Security Plan,Tech Specs & Environ Rept ML20138G9801985-10-0808 October 1985 Responds to Ltr Re Removal of Unirradiated Highly Enriched U Fuel to Secure Facility.Fuel Will Be Shipped by Proto-Power Bisco to Doe.No Fuel Will Remain at Facility by 860101 ML20112E6161985-01-10010 January 1985 Forwards Revised Tech Specs,Reflecting 841022 Request for Possession Only License ML20079G2681984-01-17017 January 1984 Responds to 831216 Generic Ltr 83-41 Re Fast Cold Starts of Diesel Generators.No Generators Used at Facility.No Response Required ML20083G0631983-12-14014 December 1983 Describes Actions to Rectify Violation of Operator Requalification program.Hot-functional Test Program Will Be Used to Familiarize Operators W/Console.All Procedures Will Be Reviewed.Actions Adequate Until Unit Restarted ML20085L1831983-09-27027 September 1983 Forwards Revs 1 & 2 to Physical Security Plan.Revs Withheld ML20069E7341983-03-17017 March 1983 Confirms That Proposal for Tech Spec Change Has Been Reviewed & Approved by Reactor Safety Committee ML20069E7171983-03-15015 March 1983 Forwards Remaining Tech Spec Changes for Amend to License R-62.Actual Connection & Testing Contingent on N-16 Calculations & Approved Test Procedures.Table Listing Summary of Specific Changes Encl ML20071C4081983-02-22022 February 1983 Forwards Annual Rept for VA Polytechnic Inst & State Univ Research Reactor,1982 ML20064M0161983-01-11011 January 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-124/82-01.Corrective Actions:Procedure Initiated for Reactor Audit & Review & SAR Will Be Submitted to Radiation Safety Committee Re Manual Control Rod Withdrawal ML20079J4131982-12-22022 December 1982 Forwards Confirmation by Reactor Safety Committee Chairman That Proposal for Tech Spec Change Reviewed & Approved ML20079J4171982-12-16016 December 1982 Forwards Application to Amend License R-62,revising Tech Specs to Delete Ultrasonic Flow Detector W/Paddle Wheel Detector w/1% Accuracy Min ML20066G4471982-11-0202 November 1982 Forwards Public Version of Revised Emergency Response Plan ML20038A6561981-11-0909 November 1981 Advises That Dr Pratner Will Replace AP Curtner as Reactor Supervisor on 811101 ML20010H2211981-08-25025 August 1981 Responds to NRC 810817 Ltr Re Violation Noted in IE Insp Rept 50-124/81-02.Corrective Actions:Interim Procedure Change Has Been Properly Documented & Approved According to Procedure VI.6 ML19341C5371981-02-25025 February 1981 Forwards Annual Operations Rept,Nuclear Research Reactor, VA Polytechnic Inst & State Univ,1980. ML20003C0371981-02-23023 February 1981 Forwards Final Reactor Operator Requalification Program, Revised to Include Deficient Items Identified in NRC 810212 Ltr,For Inclusion in Renewal Application for License R-62 ML19345B9971980-11-26026 November 1980 Forwards Security Plan & Application for Renewal of License R-62.W/o Encls ML19344E4431980-08-25025 August 1980 Forwards Complete Application for Class 104 License for Nuclear Research Reactor Facility.Prior Issuances Encl. Application Available in Central Files Only ML19330C3531980-08-0101 August 1980 Forwards Data Re Environ Radiation Dispersion,Per M Wohl Telcon Request ML19321A4781980-07-18018 July 1980 Forwards Proposed Tech Specs & Operator Requalification Program for Research Reactor Per License R-62 ML19345E2541980-03-19019 March 1980 Forwards Univ Draft Emergency Plan ML19309A5301980-03-19019 March 1980 Forwards PSAR ML19309B6191980-03-19019 March 1980 Forwards Sept 1979 Draft Emergency Plan ML19296B4121980-02-13013 February 1980 Forwards Annual Operating Rept 1979 ML19209D0961979-09-21021 September 1979 Responds to NRC 790730 Ltr Re Impact of Safeguards Upgrade Rule on Nuclear Reactor Facility.Provides Info on Size of Academic Staff,Student Enrollment & Economic Impact ML19208A3941979-09-0707 September 1979 Notifies That Rt Stone Will Take 2-yr Leave of Absence. Effective 790901,changes Will Be Made to Positions of Reactor Supervisor & Operators ML19269D3921979-04-18018 April 1979 Responds to NRC 790323 Ltr Re Violations Noted in IE Insp Rept 50-124/79-2.Correcctive Actions:All Procedures Being Rewritten & Monthly Reactor Operator Meetings Held 1988-02-05
[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 ML20196E8031988-02-0505 February 1988 Provides Addl Clarification to Final Decommissioning Rept. Data from Resurvey of Suspect Blocks Confirm That Release Criteria Not Exceeded.Resurvey Encl ML20196D5151988-02-0303 February 1988 Forwards Orau 88/A-74, Confirmatory Radiological Survey of Argonaut Reactor Facility,Virginia Polytechnic Inst & State Univ,Blacksburg,Va, Final Rept.Facility Meets Guidelines for Terminating Operating Reactors ML20238C9981987-09-0303 September 1987 Forwards Amend to Final Rept Re Dismantlement & Disposition of Facility,Including Survey Maps Denoting Grids Surveyed & Survey Data on Ventilation Duct Work & Stack,In Response to Items Identified in Insp Rept 50-124/87-01 ML20206D5901987-04-0606 April 1987 Forwards Argonaut Reactor Facility Decommissioning Final Rept, Per 861029 Dismantlement & Disposition Order.Facility Now Meets Unrestricted Use Criteria.Termination of License Requested ML20214K6051986-08-13013 August 1986 Provides Clarification Re Calibr of Instrumentation Utilized for Radiation Detection,Per 860717 Request for Order Authorizing Facility Dismantlement & Disposition & Termination of License R-62 ML20203G0071986-07-17017 July 1986 Requests Order Authorizing Facility Dismantling & Disposition to Terminate License R-62 & Publication of Fr Notice.Forwards Decommissioning Plan,Including Security Plan,Tech Specs & Environ Rept ML20138G9801985-10-0808 October 1985 Responds to Ltr Re Removal of Unirradiated Highly Enriched U Fuel to Secure Facility.Fuel Will Be Shipped by Proto-Power Bisco to Doe.No Fuel Will Remain at Facility by 860101 ML20112E6161985-01-10010 January 1985 Forwards Revised Tech Specs,Reflecting 841022 Request for Possession Only License ML20140C0351984-03-24024 March 1984 FOIA Request for All Physical & Safeguards Insp Repts from 1979 to Present at Ucla,Univ of Washington,Univ of Florida, Virginia Polytechnic Inst & Iowa State Univ ML20079G2681984-01-17017 January 1984 Responds to 831216 Generic Ltr 83-41 Re Fast Cold Starts of Diesel Generators.No Generators Used at Facility.No Response Required ML20083G0631983-12-14014 December 1983 Describes Actions to Rectify Violation of Operator Requalification program.Hot-functional Test Program Will Be Used to Familiarize Operators W/Console.All Procedures Will Be Reviewed.Actions Adequate Until Unit Restarted ML20085L1831983-09-27027 September 1983 Forwards Revs 1 & 2 to Physical Security Plan.Revs Withheld ML20069E7341983-03-17017 March 1983 Confirms That Proposal for Tech Spec Change Has Been Reviewed & Approved by Reactor Safety Committee ML20069E7171983-03-15015 March 1983 Forwards Remaining Tech Spec Changes for Amend to License R-62.Actual Connection & Testing Contingent on N-16 Calculations & Approved Test Procedures.Table Listing Summary of Specific Changes Encl ML20071C4081983-02-22022 February 1983 Forwards Annual Rept for VA Polytechnic Inst & State Univ Research Reactor,1982 ML20064M0161983-01-11011 January 1983 Responds to NRC Re Violations Noted in IE Insp Rept 50-124/82-01.Corrective Actions:Procedure Initiated for Reactor Audit & Review & SAR Will Be Submitted to Radiation Safety Committee Re Manual Control Rod Withdrawal ML20079J4131982-12-22022 December 1982 Forwards Confirmation by Reactor Safety Committee Chairman That Proposal for Tech Spec Change Reviewed & Approved ML20079J4171982-12-16016 December 1982 Forwards Application to Amend License R-62,revising Tech Specs to Delete Ultrasonic Flow Detector W/Paddle Wheel Detector w/1% Accuracy Min ML20066G4471982-11-0202 November 1982 Forwards Public Version of Revised Emergency Response Plan ML20038A6561981-11-0909 November 1981 Advises That Dr Pratner Will Replace AP Curtner as Reactor Supervisor on 811101 ML20010H2211981-08-25025 August 1981 Responds to NRC 810817 Ltr Re Violation Noted in IE Insp Rept 50-124/81-02.Corrective Actions:Interim Procedure Change Has Been Properly Documented & Approved According to Procedure VI.6 ML19341C5371981-02-25025 February 1981 Forwards Annual Operations Rept,Nuclear Research Reactor, VA Polytechnic Inst & State Univ,1980. ML20003C0371981-02-23023 February 1981 Forwards Final Reactor Operator Requalification Program, Revised to Include Deficient Items Identified in NRC 810212 Ltr,For Inclusion in Renewal Application for License R-62 ML19345B9971980-11-26026 November 1980 Forwards Security Plan & Application for Renewal of License R-62.W/o Encls ML19344E4431980-08-25025 August 1980 Forwards Complete Application for Class 104 License for Nuclear Research Reactor Facility.Prior Issuances Encl. Application Available in Central Files Only ML19330C3531980-08-0101 August 1980 Forwards Data Re Environ Radiation Dispersion,Per M Wohl Telcon Request ML19321A4781980-07-18018 July 1980 Forwards Proposed Tech Specs & Operator Requalification Program for Research Reactor Per License R-62 ML19345E2541980-03-19019 March 1980 Forwards Univ Draft Emergency Plan ML19309A5301980-03-19019 March 1980 Forwards PSAR ML19309B6191980-03-19019 March 1980 Forwards Sept 1979 Draft Emergency Plan ML19296B4121980-02-13013 February 1980 Forwards Annual Operating Rept 1979 ML19209D0961979-09-21021 September 1979 Responds to NRC 790730 Ltr Re Impact of Safeguards Upgrade Rule on Nuclear Reactor Facility.Provides Info on Size of Academic Staff,Student Enrollment & Economic Impact ML19208A3941979-09-0707 September 1979 Notifies That Rt Stone Will Take 2-yr Leave of Absence. Effective 790901,changes Will Be Made to Positions of Reactor Supervisor & Operators ML19269D3921979-04-18018 April 1979 Responds to NRC 790323 Ltr Re Violations Noted in IE Insp Rept 50-124/79-2.Correcctive Actions:All Procedures Being Rewritten & Monthly Reactor Operator Meetings Held 1991-06-18
[Table view] |
Text
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( ) VIRGINIA POLYTECHNIC INSTITUTE AND STATE UNIVERSITY
'Blacksburg, l'irginia 24061 NucuAR dCUVADON AN M.YMS LABORMORY March 19, 1980 Mr. Steve Ramos Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Ramos:
Enclosed are two copies of the Preliminary Safety Analysis Report for the VPI & SU reactor (License R-62). This document was prepared for opera-tion at a maximum power level of 500 kw. The PSAR has been reviewed and approved by both the Reactor Safety Committee and the Radiation Safety Com-mittee.
We would appreciate your reviewing the PSAR at your earliest convenience so that we can proceed with all the required construction work. Our tenta-
! tive schedule for construction is as follows:
April 1, 1980: Start installation of cooling tower May 1, 1980 : Start installation of new heat exchanger June 1, 1980 : Start modification of primary coolant system Enclosed also are two pre'iminary copies of our Emergency Plan which has also been reviewed by the Reactor Safety Committee and the Radiatior. Safety Committee.
Thanks for your cooperation.
Sincerely yours, T. F. Parkinson, Director Nuclear Reactor Laboratory TFP/fbl cc: A. P. Curtner, Reactor Supervisor g R. H. Miller, Chairman, Reactor Safety Committee #y R. A. Teekell, Chairman, Radiation Safety Committee Y
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VIRGIN 1A TECH REACTOR FACILITY EMERGENCY ?IAN SEPTEMBER 1979 DNAFT l
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l VIRGINIA TECH REACTOR FACILITY EMERGENCY PLAN SEPTEMBER 1979 TABLE OF CONTENTS Section Title Pg 1 PURPOSE OF EMERGENCY PLAN 1 2 DEFINITIONS 1 3 EMERGENCY ORGANIZATIONS 3 4 EMERGENCY RESPONSE ACTIONS 5 5 ADMINISTRATIVE CONTROLS 8
- Virginia Tech is the official name of Virginia Polytechnic Institute and State University (Legal Name) r-
I. PURPOSE OF EMERGENCY PLAN This document outlines the plan for responding to potential emergencies at Virginia Tech's Reactor Facility to minimize their effect on personnel, the Reactor Facility, and the environment.
To accomplish this goal, the emergency plan defines the emergency organi-zation and general actions to be taken in response to hypothesized emergencies of varying levels of severity. Specific actions to be taken to implement this plan in the case of actual emergencies are defined in the VA Tech Nuclear Research Reactors Procedures Manual.
II. DEFINITIONS A. Reactor Room. The room containing the 100 KW Argonaut reactor (Room 10, Robeson Hall).
B. Reactor Facility. The rooms 106, 108, 6, 8, and 10 of Robeson Hall contain work areas, laboratories, offices and the Reactor Control Room and Reactor Room.
C. Reactor Facility Restricted Area. The Reactor Facility and the roof area of Robeson Hall.
D. Affected Area. The area beyond the Reactor Facility restricted area in which the limits for radioactive materials or radiation exposure to individuals are likely to exceed those specified for unrestricted areas by 10 CFR Part 20.
E. Emergency Action Classes. The emergency action classes are methods used to define the relative severity of the emergency condition. The actions necessary to assess, correct and recover from emergencies are based on its severity as defined by these classes.
The Emergency Action Classes are:
Class 1 - Personnel Emergency. A personnel emergency is an acci-dent occurring within the Reactor Facility Restricted Area which requires the emergency treatment of one or more individuals.
These occurrences may be complicated by radioactive contamina-tion or radiation exposure.
This class of emergency does not necessarily have an effect on the reactor and immediate operator action to alter the reactor status is not required unless it is likely that the Class 1 emergency will escalate to a more severe (Class 3 or Class 4) 1 emergency.
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Class 2 - Energency Alert. An emergency alert results from situa-tions which can be recognized ds creating a hazard to the reactor or personnel that is not normally present. Examples of this class i
of occurrence are:
- a. Threats to or actual breaches of security, civil disturbances or bomb threats affecting the Reactor Facility.
- b. Instrumer.t readings or alarms indicating atypical reactor operating condition which does not require immediate shut down of the reactor as defined by the R-62 Technical Speci-
- ficatious,
- c. Severe natural phenomena, such as a tornado alert.
While time is available in these situations to prevent or minimize the effect of these occurrences, emergency alert conditions imply a rapid transition to the state of readiness by reactor personnel and the possible changes in normal reactor or facility operation.
Class 3 - Reactor Emergency. Situations which directly affect reactor safety and require immediate corrective action, but are predicted to have negligible radiological consequences outside of the Reactor Facility. Examples of these situations include:
- a. Fires or minor explosions in or near the reactor room.
- b. Malfunction of a reactor safety system component while the !
reactor is operating.
- c. Sudden or unexpected changes in reactivity, such as a large 4
increase in reactor power with no control rod movement.
Class 4 - Reactor Facility Emergency. Situations which directly l affect reactor safety and indicate that levels of radioactivity '
which exceed the limits specified in 10 CFR Part 20 for unrestricted areas may be released outside of the Reactor Facility restricted area. Framples of these situations are:
- a. Measurement of radioactivity dose rates greater than two milli- l rem per hour at the Reactor Facility Restricted Area boundary )
using a portable gamma radiation monitor. l
- b. Stack release containing radioisotopes which exceed the concen-i trations allowed for air in an unrestricted area by 10 CFR 20. l
3 III. EMERGENCY OT Q g ION AND EQUIPMENT A. On-Site Emergency Organization. The on-site emergency organization shall consist of the following persons, listed in order of their position in the chain of conmand in the event of an emergency.
- 1. Director of the Reactor Facility
- 2. Deputy Director of the Reactor Facility
- 3. Reactor Supervisor
- 4. Reactor Radiation Safety Officer
- 5. Senior Reactor Operators
- 6. Licensed Reactor Operators at the Facility The Director of the Reactor Facility shall take charge of all opera-tions and coordinate efforts to assess the severity of an emergency and determine corrective and protective actions to minimize the effects of the emergency.
The Reactor Radiation Safety Officer shall ensure that the emergency equipment is available for use during an emergency, determine whether any radioactivity has been released during the emergency, and recommend to the Director actions to minimize the effect of the emergency.
Other members of the on-site emergency organization shall assist in minimizing the effect cf the emergency as requested by the Director or defined in specific procedures. All reactor operators are qualified in the use of radiation detection equipment.
B. Off-site Emergency Organizations. The following organizations will respond to an emergency at the Reactor Facility if needed:
- 1. The Montgomery County Hospital has agreed to accept and treat per-sonnel injured at the Reactor Facility. Actions to be taken are identified in a Radiation Emergency Plan which was prepared by the Medical Center. The hospital can be contacted by telephone and two-way radio through the University's Security Division.
- 2. The Virginia Tech Security Division has agreed to respond to emer-gencies at the Reactor Facility. Actions to be taken are identi-fled in the department. The University's Security Division can be contacted by telephone.
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- 3. The Blacksburg Volunteer Rescue Squad has agreed to provide on-site medical aid and transport injured personnel to Montgomery County Hospital. The Rescue Squad can be contacted by telephone.
- 4. The Blacksburg Volunteer Fire Department will respond to emergen-cies at the Reactor Facility. The Fire Department can be contacted by telephone.
- 5. The Blacksburg Town Police Department will respond to emergencies at the Reactor Facility. The Police Department can'be contacted by telephone.
- 6. The Montgomery County Sherriff's Department and Virginia State Police can also be contacted if additional police assistance is needed. The organizations can be contacted by telephone.
- 7. The Virginia Office of Emergency Services and Oak Ridge Region Coordinating Office for Radiological Emergency Assistance can also assist in the event of a Reactor Facility Emergency. These offices j can be contacted by telephone. l 1
C. Emergency Equipment. Equipment which can be used in the event of an ,
emergency is available at the Reactor Facility and other sites as follows:
- 1. Reactor Facility
- a. Fixed radiation monitors as required by Virginia Tech's R-62 Technical Specifications.
- b. Portable radiation monitors for detecting neutron, gamma and charged particle radiation.
- c. Multichannel analyzers for determining specific radioactive isotopes present and absolute level of radioactivity.
- d. Assorted anti-contamination clothing.
- e. Emergency first aid equipment.
- f. Portable fire extinguishers.
- g. Telephones.
- 2. Rescue Squad Ambulance
- a. Emergency first aid equipment.
- b. Basic life support systems.
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, 3. Health Physics Laboratory, 100 W Randolph Hall (located about 500 feet northeast of the Reactor Facility).
- a. Portable radiation monitors.
- b. Multichannel analyzer.
- c. Fixed gm counters and NaI counters.
- 4. Montgomery County Hospital (located about 4 miles from the Reactor Facility).
- a. Complete medical' facilities.
- b. Portable radiation monitor.
- 5. Security Divisions Office, Building 201, (located about 1000 ft.
from the Reactor Facility).
- a. Portable radiation monitors and dosimeters.
- b. Anti-c clothing, signs, barrier material, etc.
IV. EMERGENCY RESPONSE ACTIONS A. Class 1 - Personnel Emergency. Immediate action will be taken to determine the number of people injured, the nature and severity of the injury, provide medical aid, and determine whether the accident has any potential for affecting operation or safety of the reactor.
The person first aware of a personnel injury should immediately con-
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tact the Reactor Supervisor or Facility Director using the Facility's internal communications system or ther method. The Reactor Supervi-sor or Facility Director will notify the Reactor Radiation Safety Officer and Rescue Squad. If necessary, emergency first aid will be administered pending arrival of the Rescue Squad. The level, if any, of radioactive contamination will be measured by the Reactor Radiation Safety Officer or other person qualified in radiation detection.
Actions to be taken in the event of a personnel emergency are defined in Virginia Tech's " Emergency / Abnormal Nuclear Reactor Procedures, Section V.".
B. Class 2 - Emergency Alert. Immediate action will be taken to deter-mine the nature and possible consequences of the potential emergency.
Based on this information, corrective action necessary to minimize the l
. adverse effects of the situation will be defined.
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To accomplish this objective, anyone aware of a situation which may I affect the reactor safety or safety of personnel at the Reactor Faci- i lity will notify the Facility Director and Reactor Supervisor. The l Director will determine response actions, such as securing the reactor and monitoring for radioactive effluents, based on the available in-formation and consultation with members of the emergency team as con-sidered necessary.
While the broad spectrum of emergency alerts precludes definition of specific actions in all cases, procedures for several possible situa-tions which may affect reactor or personal safety are contained in Virginia Tech's Nuclear Reactor ProceduresSection V. , " Emergency /
Abnormal Procedures." The Reactor Facility Security Plan and Contin-gancy Plan also includes procedures for possible alert conditions.
C. Class 3 - Reactor Emergency. Immediate action will be taken to shut down the reactor.
After the reactor is shut down the reactor operator will notify the Reactor Supervisor or Facility Director who will notify other members of the on-site emergency' organization if necessary.
In the event that an evacuation is necessary, the criteria for re- I entering the Reactor Facility are defined in Section E, below.
Specific procedures to follow in the event of a Reactor Emergency are included in Virginia Tech's Nuclear Reactor's Procedures,Section V., " Emergency / Abnormal Procedures."
D. Class 4 - Reactor Facility Emergency. Action will be taken to deter-aine the source, magnitude and affected area by the release of radio-active material. Personnel within the affected area will be informed that radioactive material has been released and protective ac'tions defined. Access to the affected area will be controlled by the Security Division. If the source of the radioactive release is the reactor, it will be shut down and the building evacuated.
The on-site emergency organization, the Radiation Safety Office, and the University's Security Division will be notified in the event of a Reactor Facility Emergency. Members of the Radiation Safety Office, or other qualified personnel will make radiation measurements to deter-mine the extent and level of airborne and other radioactive releases and to determine when the levels of radioactivity released have decrea-sed to acceptable levels.
The University's Security Division shall notify all personnel within the area where radioactivity levles in excess of two millirem per hour exist or areas where other limits for unrestricted areas are likely to l be exceeded. In the event of a major release which precludes timely I l
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- determination of the affected area, personnel within 500 feet of the
- l. Reactor Facility in the downwind sector (one sector covers 22.5 ]
degrees) and the two adjacent sectors will be notified. l l
The most likely protective action to be taken will be to inform personnel to remain inside with all windows and doors closed and ventilation systems turned off. The need to evacuate specific areas will be evaluated. Access to the affected area will be controlled by the University's Security Division.
Criteria for re-entering the Reactor Facility are defined in Section E below. Specific procedures to follow in the event cf a Reactor Faci-lity Emergency are provided in Virginia Tech's Nuclear Reactor's Pro-cedures,Section V., " Emergency / Abnormal Procedures."
E. Criteria for Re-entering the Reactor Facility. Following a reactor emergency or Reactor Facility emergency in which an evacuation is necessary, the Reactor Radiation Safety Officer and the Reactor Super-visor shall re-enter the building as described in Virginia Tech's Nuclear Reactor's procedures. Once a determination of the actual i radiation levles has been made, areas of the building having radiation levels below the limits established for unrestricted areas by 10 CFR 20 may be entered and used.
Entry into areas having high radiation levels for the purpose of radiation surveys, clean-up or other actions not judged to be neces-sary to the safety of the reactor or personnel should be planned and performed to limit the total dose to the whole body of any person to less than one rem. Both a TLD and a pocket dosimeter should be used to record the actual exposure.
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F. Methods Used to Account for Personnel. Following evacuation of the facility, it is important to account for all personnel. This will be accomplished by the following methods:
- 1. Discussions with personnel who have evacuated the Facility to con-firm that all personnel in the Facility prior to the evacuation are accounted for.
- 2. Check the TLD racks to determine that all TLD badges are either on the rack or on evacuated personnel. Personnel will be instructed to keep their TLDs during the evacuation instead of placing them on the, storage racks. Personnel in the Reactor Facility will either have TLD badges or be escorted (visitors only). Since the TLD badge storage rack is near the Reactor Facility exit, the radiation level should be low enough to allow determination of which TLD badges are stored on the rack following facility evacuation.
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- 3. During the initial re-entry to determine radiation levels, a visual check of all accessible areas .will be made to detect personnel within the facility.
G. Emergency Control Center. A central location for directing the emer- I gency actions will be established. The Facility Director win normally 4 be at the control center, unless it is necessary to be another location I to provide better control of the emergency actions. The emergency con- l trol center shan be established as follows:
- 1. Personnel emergency. As near to the accident location as possible while ensuring that acceptable radiation levels and adequate com- I munications are present. j l
- 2. Emergency alert and reactor emergencies in the Reactor Control Room. If evacuation is necessary, proceed to item G, 3. 1 i
- 3. Reactor Facility emergency. At a location having acceptable radia- l tion levels as determined by the Reactor Radiation Safety Officer, '
or other authorized person, and'having adequate communications. l l
V. ADMINISTRATIVE CONTROLS The foll.owing administrative controls will be used to ensure that the Emergency Plan and Procedures are useable in the event of an emergency.
A. A summary of emergency actions will be posted in the Reactor Facility and another copy in one of the emergency kits stored at Security. The purpose of this summary is to provide an up-to-date listing and phone i numbers of key personnel on the emergency organization and off-site l personnel and organizations who would participate in a reactor or I Reactor Facility emergency.
B. The Emergency Plan and Procedures for implementation of the plan will I be reviewed and, if necessary, updated by the Reactor Safety Sub-Commit-tee during even numbered years. Changes considered necessary based on the results of drills or other experience will be made as soon as practical.
C. Practica emergency drills will be undertaken at leace once each calendar year to test the response of the on-site emergency organization. The Facility Director will be responsible for defining the objective and details of each drill. Following the drill the on-site emergency
, organization will meet to critique the drill and determine whether changes to the procedures or additional personnel training are warranted.
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