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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 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) 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) 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
. .
~ e CDU.EGE OF ENGINEERING
'- i f . ., . _ .
- ' VIRGINIA POLYTECHNIC INSTITUTE, . -
AND STATE UNIVERSITY q
NUCLEAR REACTOR LABORATORY
- b 2*0' January 11, 1983 Mr. R. C. Lewis, Director Division of Project and Resident Programs U. S. Nuclear Regulatory Commission, Region II 101 Marietta Street, N.W.
Atlanta, GA 30303 Dear Sitt In response to your letter of December 15, 1982 (Report No.
50-124/82-01), we acknowledge the two violatiens cited in Appendix A.
With respect to Item A, while the required annual audits were partially carried out, we admit that our documentation of the audits was unsatisfactory. The reason for this violation was the lack of a formal procedure for carrying out the audits. In order to prevent a recurrence of the violation, we propose to initiate a procedure for reactor audit and review. The proposed procedure is included as Attachment I. We believe that this corrective action will prevent a recurrence of the violation. The proposed procedure will be presented to the Reactor Safety Committee on January 31, 1983, so we should be in full compliance af ter that date.
In regard to Item B, while the Radiation Safety Committee has reviewed the fact that we were manually withdrawing control rods for drop time measurement testing of control rods, we admit we do not have documentation for a safety analysis being performed on manual withdrawal of a control rod. The reason for the error was the fact that without the moderator in the core (procedure requirement), we have a negative reactivity of 30% AK/K inserted in the core. The max-imun reactivity any one control rod will insert when pulled is 0.77% AK/K. This fact was apparently taken to meet the safety anal-ysis requirements. We now realize we are in violation and propose to i correct this by submitting to the Radiation Safety Committee a Safety Analysis Report covering a manual rod withdrawal with moderator out of the core. The proposed Safety Analysis Report is included in Attach-ment II. We believe this corrective action will prevent any recurrence of the violation. The proposed Safety Analysis Report will go before the Reactor Safety Committee for approval at the 31 Jan ary 1983 meeting l
and we should be in full compliance after that time.
1 l
Sincerely yours, w, - ~
nomas F. Parkinson, Director O 4 0 PDR Nuclear Reactor Laboratory l
smw l
i attachments g cc: R. A. Teekell P. D. F
~
', ATTACHMENT I APPROVED / REVIEWED Datt Ch31rman, lacctor SIfsty Committ2s III.3 Reactor Audit and Review ($nnual)
In accordance with the Radiation Safety Manual, annual audits must be conducted in the following areas: Reactor Operations, Security, Special Nuclear Material Inventory and Safeguards. Accordingly, all procedures, Technical Specification operating logs and other documen- ,
tation pertaining to the safe operation and of the VPIGSU Nuclear l Reactor Laboratory shall be audited annually by three (3) members of the Reactor Safety Committee (R.S.C.) not directly associated with reactor operations. These members shall be designated at the general 2 R.S.C. meeting just prior to the quarter in which the audit is to be ,
performed. l All Special Nuclear Material (S.N.M.) shall be inventoried by:
- 1. The Reactor Supervisor
- 2. The University Reactor Radiation Safety Officer
- 3. One of the three members designated.iby; the R.S.C.
to take part in the annual audit.
As for the rest of the areas of the audit, the three members designated to perform the audit will perform the audit with only assistance from the reactor staff.
- 1. The Audit will consist of a review of the following:
A. Reactor Operations
- i. Reactor Operating logs i
- 11. Reactor Procedures
! iii. Reactor Operation /R.S.C. Meeting Minutes iv. Requalification procedures / documents
- v. Equipment calibration / maintenance data B. Security
- i. Security Procedures / documents C. Special Nuclear Material l
- i. All S.N.M. stored with the VPI&SU Nuclear Reactor Laboratory or assigned to the Nuclear Laboratory Personnel.
1 j D. Safeguards
- 1. Experiment Procedure / documentation l
ii. Annual Report l
iii. Technical Specifications iv. Safety Analysis Report
- 2. The Audit shall be documented by completing the attached report, with the exception of the S.N.M. inventory, which will documented on the S.N.M. report (NRC 742).
i N
_ _ _ _ _ _ _ _ _ _ - - - - _ _ _ a
. r----------------------- ___
ATTACHMENT I APPROVED / REVIEWED Data pig 2 2 .
Chairman, Re ctor SEfsty Conunittaa
~
III.3 (continued) j 3. The S.N.M. inventory shall consist of ctual " sighting" of all l
Special Nuclear Material listed in the previous S.N.M. report.
i (NRC 742) inventory, with adjustments made for any transfers since the previous inventory. Irradiated fuel sighting shall consist of inspection of fuel transfer logs, reactor core inventory, and confirmation of storage of the appropriate number of " hot" fuel plates as acorded in fuel storage logs.
Confirmation of fuel plate serial numbers shall be by inspection of individual serial numbers from not less than two (2) storage locations chosen at random by the consultant member of the S.N.M.
inventory team. (for non-irradiated fuel only.)
2 A. The formula used for burnup of U 235 shall be 4.356 x 10 grams /Mw-hr. The formula for burnup + transmutation of 2 grams /Mw-hr. x 98+580.
U 235 shall be 4.356 x 10 580 The figures reported on any completed NRC-732 forms shall be checked by the consulting member of the C.N.M. inventory team.
- 4. Any significant discrepancies (any excess or missing Items in the S.N.M. inventory) shall be reported immediat.ely to the chairman of the Radiation Safety Committec, Should the S.N.M. discrepancy not be readily resolved, the discrepancy shall be reported to the Nuclear Regulatory Commission within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 5. The report results (report sheet and NRC-732) shall be presented at the next genera 2 R.S.C. meeting along with recommendations for correction of any discrepancies found.
- 6. A copy of the results of the audit plus corrections performed for any discrepancies found shall be included in the annual report.
4 1
b i
6
\
- ATTACfDE:NT I LM.K'A%L@tL4294a'Le
- Pega 3 Data Chairman, Retctor Snfsty Committas
?
III.3 Reactor Audit and Review Report Sheet Areas listed below are to L3 audited annually and will include the subjects listed in Procedure III.3. Any comments will be placed in the space pro-vided and may be continued as necessary. All areas most be filled in.
Special Nuclear Material will use NRC-742.
A. Reactor Operations:
\
Continued / /
B. Security:
Continued / /
\
' ' - ~
.-- - - - - ,,,v,,7.-,-,ew, . , , - - - - - - - - , , - . .
_m---- - --- - - -+ - - . - - , -e +m -
. ATTACHMENT I APPROVED /REVIEifED Paga 4 Data !
. Chairman, R& actor Safety Committaa III.3 Reactor Audit and Review Rdport Sheet (continued)
C. Safeguards:
I Continued / /
D. Audit completed by:
1 I
l Reviewed:
Chainnan, Reactor Safety Committee i
i l
l
' " *N
6m
ATTACHMENT II I COIlJ!GE CF ENGINEERING I i VIRGINIA POLYTECHNIC INSTITUTE AND STATE UNIVERSITY
&cksberg, Virginia 24061 NUG. EAR REACTOR 1.ABORATORY i January 11, 1983 TECHNICAL SPECIFICATION CHANGE PROPOSAL RE: License No. R-62, Docket No. 50-124 Safety Analysis Report, Manut.1 Withdrawal of a Control Rod Drop Time Measurements and Analysis for Technical Specifications
SUBJECT:
Change in Technical Specifications 6.2.2 Maximum Reactivity Input Rate of Safety and Shim Rods TYPE: Nuclear PROPOSAL:
Original wording:
6.2.2 The two safety rods and the shim rod shall each have a reactivity worth of approximately 0.55% AK/K. The safety rods must be withdrawn sequentially prior to withdrawal of the shim or regulating rods. The maximum reactivity input rate of the safety and shim rods shall not exceed 0.02% AK/K/sec. The maximum time for insertion of the shim and safety rods following initiation of a SCRAM signal shall not exceed 0.8 seconds.
NeV wording:
6.2.2 The two safety rods and the shim rod shall each have a reactivity worth of approximately 0.55% AK/K. The safety rods must be withdrawn sequentially prior to withdrawal of the shim or regulating rods. The maximum time for insertion of the safety and shim rods following initiation of a SCRAM signal shall not exceed 0.8 seconds. The maximum reactivity input rate of the safety and shim rods shall not exceed l r 0.02% AK/K/sec. This reactivity input rate (0.02% AK/Ksec) l is not applicable when the core is devoid of water moderator.
I EFFECTS: See Attached Safety Analysis Report
SUMMARY
- See Attached Safety Analysis Report
9 I COLLEGE OF ENGINEERING
[ VIRGINIA POLYTECHNIC INSTITUTE AND STATE UNIVERSITY Bkcksberg, Virginia 24061 NUCEAR REACTOR LABORATORY January 11, 1983 SAFEY ANALYSIS REPORT RE: License No. R-62, Docket No. 50-124
SUBJECT:
Manual Withdrawal of a Control Rod for Control Rod Drop Time Measurements and Analysis for Technical Specifications TYPE: Mechanical / Nuclear PROPOSAL- We propose that the manual u thdrawal of a single control rod under the following conditions:
(1) Reactor Shutdown / Control Rods inserted (2) Core devoid of water coderator (3) Dump Valve Interlock enabled and activated; will not cause a Reactivity Addition Accident, will not impede or hinder the Reactor Safety Systems, will not exceed Safety System limiting settings, will not cause an uncontrolled radioactive release and that the reactivity input rate of 0.02t AK/K/sec.
is not applicable when the the core is devoid of water moderator, Therefore, this proposed manual withdrawal of a single control rod should be allowed in the Control Rod Droptime Measurement Procedure (IV.15) in order to expedite trouble shooting time prior to dismantling the core.
EFFECTS: The Argonaut Research Reactor at VPI & SU has.a shutdown condition defined as: all rods inserted, the water moderator
" dumped" to the dump tank and the console key removed. By
" dumping" the moderator, we void the core region of coolant /
moderator and achieve a negative 30.0% AK/K reactivity. The control rods then add an additional 2.161, AK/K of negative reactivity. When using Procedure IV.15, the reactor is not technically shutdown; however, as specified in pro-cedure IV.15, the Dump Valve Interlock must be activated and this condition prevents filling the core tanks.
A Reactivity Addition Accident cannot occur because with the moderator " dumped" the core reactivity is negative by 30.0% AK/K.
Thus with manual withdtawal of a single rod (maximum reactivity of any rod is 0.77% AK/K) a shutdown reactivity of -29.24% AK/K is maintained.
(-30.0% AK/K +. 0.77% AK/K = -29.24% AK/K) 1
SAFETY ANALYSIS REPORT Page 2 Date: January 11, 1983 .
EFFECTS: (continued)
Therefore, even with a single complete rod ejection the minimum shutdown targin of 0.5% AK/K will not be exceeded and a manual rod withdrawal will have no adverse effects oh the core.
A manual rod withdrawal with core devoid of water moderator will not impede or hinder any Reactor Safety System owing to the fact that the safety sys, tem will be energized, operable and in compliance with any specific provisions listed in Tech-
- nical Specifications for the VPI & SU Reactor, while the manual withdrawal is taking place.
As shown in the following analysis; no Safety System limiting settings will be exceeded:
(1) Neutron Countrate; not applicable, core devoid of water moderator (2) Coolant / moderator; A) Temperature not applicable, core devoid of water moderator B) Flow C) Operating level (3) Reactor Room Ventilation; No effect - fans remain on (4) Safety Rods 1 & 2 fully withdrawn; has bypass provision - only withdrawn singly (5) Reactor period / power set points; never reached due to -29.24% AK/K reactivity in core with core devoid of water moderator (6) Automatic controller servo set point; never effected, reactor not operating (7) Regulating Rod at upper or lower limit; rod not moved past upper or lower limits - also manual stops present (8) Activation of manual SCRAM switch (remote / manual);
not applicable - core not operating (-29.24% AK/K)
(9) Shield tank level; not applicable. core not operating (10) Earthquake SC, RAM; not applicable core not operating O _ _ . . _ . . _ . _ . . . . . _ _ _ . _ _ . . . ~ . - - . - . . .
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i SAFETY ANALYSIS RESORT . Page 3 Date: January 11, 1983 i
i EFFECTS: (continued)
(11) Radiation levels; operable - with core not operating levels will not change (12) Radiation level ffssion products monitors not applicable - core devoid of water moderator, I no flow to detector.
SUMMARY
- As mentioned in the previous statements, the reliability or safety of our facility will not be degraded nor will a a safety hazard be posed by manually withdrawing a single rod when the core is devoid of water moderator. By not exceeding the Safety System limiting settings we are protected against an uncontrolled radioactive release and therefore the re-quire:.ents set forth in the proposal are met. We propose that the manual ' cod withdrawal be included in the Control Mod Droptime Procedure hv.15) and that a reactivity input rate of 0.02% AK/K/sec. not be applicable when the core is devoid of water moderator.
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- APPROVED / REVIEWED D2to Chairman, Radiation Safety
- Committee IV.15 Measurement of Total Control Rod Drop Time A. Initial Conditions
- 1. Two individuals with the following minimum qualifications are available:
Rev. 7 (a) nuclear senior operator (b) reactor operator
- 2. The reactor control console switch key is installed, the console is on and manned by a reactor operator.
- 3. The dump valve disable interlock is activated and all control rods are fully inserted.
- 4. Log any jumpers installed or remo red from reactor instrumentation in the jumper log.
- 5. The graphite stack, core tanks and surrounding core region are at thermal equilibrium at 1.1300F. -
- 6. A Tektronix oscilloscope model 2213 or equivalent is available.
Rev. 7
- 7. If this is performed subsequent to a reactor run shutdown checks have been performed without removing the console key.
CAUTION: Do not leave the console unattended with the key inserted.
B. Precautions and Limitations
. 1. This procedure will be coordinated and performed by a senior reactor operator.
- 2. Observe all appropriate electrical safety precautions.
- 3. Use a 2 to 3 way AC adapter on the AC input power, to the l
oscilloscope to insure the oscilloscope power cord is not j grounded to earth ground.
- 4. The total control rod drop time is a Technical Specification limit (para. 6.2.2) and shall not exceed 0.8 seconds.
- 5. If control rod drop times exceed .65 seconds, inform the Reactor Supervisor. Check the alignnent between the drive mechanism and l the shaft. Operate the mechanism and listen for any abnormal j
i Rev. 7 ' sounds which may indicate bad bearings and/or re-alignment of the mechanism. If this still does not correct the problem and the mechanism appears to be functioning properly disconnect it from the control rod shaft. Rotate the mechanism by hand to ascertain if it requires maintenance. If this is required, perform
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procedures III.2 and IV.16.
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IV.15 (continued) APPROVED / REVIEWED P g3 2 Dato Chairman, Radisti:n SafGty j .
Committee IV.15 C. Procedure r
1._ Set the controls on the oscilloscope as follows:
i (a) Sync: ext.
(b) Sweep: 100M.S./cm..
(c) Stability: preset, adjust as necessary (d) Triggering level: + and near 0 (e) Main Sweep:. normal (f) Volts /Div.: 1 volt /cm sensitivity minimum NOTE: Connection from the trigger input to the reactor control console should be through a short length of shielded cable.
Connection from t* o vertical amplifier input to the console may be through a 10X probe or a short length of shielded cable.
The TB numbers refer to terminal connections on the rear of the console.
- 2. Make the following connections for each measurement:
(a) oscilloscope probe grounded to TB9-80 (b) trigger input TB9-3 (c) vertical amplifier input thru a.OlpF capacitor)
- 1. safety rod No. 1 TBil-14
- 2. safety rod No. 2 TBil-20
- 3. shim rod TBll-26 (d) Just prior to making the drop time test, the intensity control on the oscilloscope should be adjusted for a light trace. This will b'ea vertical line four or more centimeters high and should be located at the left cali-bration line on the CRT graticule. The triggering level control should be set on the positive side and as close to zero as is possible without accidental triggering due to noise. When the manual scram button is pushed the oscilloscope sweep circuit will be triggered and an intense trace will proceed from left to right across the screen of the CRT. The point at which the trace collapses to a central line is the end of the drop time.
(e) NOTE: With the respective jumpers installed allowing rod withdrawal you must manually reset the scram to ensure scram bus continuity (clutch voltage applied) .
- 3. Shim rod:
(a) Insure. safety rods and regulating rod are fully inserted.
(b) Install a jumper between TB9-75 and TB9-16. This disables the start-up interlock on the safety rods allowing the shim and regulating rod to be withdrawn.
(c) Insure the regulating rod is maintained fully inserted.
(d) Withdraw the shim rod fully until both analog and digital f
indicators verify the rod is fully withdrawn.
(e) Perform step 5, repeat as necessary.
(f) Remove the jumper between TB9-75 and TB9-16.
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IV.15 (continuid) LbbtIMta$the19sae P:.g2 3 Data Chairman, Raditticn S2fsty Committee l IV.15 C. (continued)
- 4. Safety rods:
(a) For safety rod 1 verify all other rods are fully inserted.
(b) Install a jumper between TB9-75 and TB9-ll. This disables the respective start-up interlocks allowing withdrawal of safety rod 1.
(c) Withdraw safety rod 1 fully until the top light energizes and both analog and digital indicators verify the rod is l fully withdrawn. l Perform step 5, repeat as necessary. l (d)
(e) Remove the jumper between TB9-75 and TB9-ll.
(f) For safety rod 2 verify all other rods are fully inserted.
(g) Install a jumper between TB9-75 and TB9-14. This disables the respr.ctive start-up interlocks allowing withdrawal of safety rod 2.
(h) Withdrawal safety rod 2 fully until the top light energizes and both analog and digital indicators verify the rod is fully withdrawn.
(i) Perform step 5, repoat as necessary.
(j) Remo 3 the jumper between TB9-75 and TB9-14.
. 5. On command by the senior reactor operator, the reactor operator will scram the reactor. The senior reactor operator will note the drop time by deserving the oscilloscope.
D. Final Conditions
- 1. Disconnect the oscilloscope from the back of the reacter control console.
- 2. Remove the reactor control console key. Verify all rods are inserted and complete shutdown checklist.
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