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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20216J9221999-09-28028 September 1999 Informs That DE Hughes,License SOP-10198-3,no Longer Working as Licensed Senior Reactor Operator with Penn State Univ, Effective 990731.Requests Appropriate Action to Remove Name from List of Active Licensees ML20248M0531998-06-0909 June 1998 Forwards Copy of Results of Operator Initial Exam Conducted at Pennsylvania State University on 980527-28.W/o Encl ML20203L3021998-02-27027 February 1998 Requests Addl Changes to Proposed Amend 32.Proposed Changes Are to Sections 3.4 & 3.5.Revised TS Amend Encl W/Changes & Repagination of Pages 12-22 & 42-44 ML20217R2911997-08-28028 August 1997 Informs That Pg Boyle License SOP-70072 No Longer Working as Licensed SRO W/Penn State Univ Breazeale Reactor Effective 970630 ML20198E9811997-08-0505 August 1997 Informs That Responsibility for Non-Power Reactor Insp Program Has Been Transferred from Regional Ofc to Nrr. Addresses Listed ML20137S4331997-04-0707 April 1997 Fulfills TS Requirement of Written Rept within 30 Days to NRC for Permanent Change in Facility Organization Involving Level 1 & 2 Personnel as Defined in Reactor Facility TSs ML20113E0761996-06-20020 June 1996 Forwards Results of Operator Initial Exam Conducted on 960610-11.W/o Encls ML20094P9041995-11-24024 November 1995 Advises That Aj Mclellan (SOP-70122) Has Resigned Position W/Penn State Univ Breazeale Reactor on 951110.Requests That NRC Take Appropriate Action to Remove Name from List of Active Licensees ML20090L2031992-03-10010 March 1992 Advises That Author Appointed to Position of Senior Vice President for Research & Dean of Graduate School,Effective 920301,replacing Cl Hosler ML20077J9091991-07-29029 July 1991 Notifies That on 910722 Facility Exhaust Sys Failed.Cause of Failure Was Breakdown of Insulation on Wiring That Supplies Power from Console Exhaust Sys Control Switches to Sys Relay Panel ML20076D8471991-07-25025 July 1991 Grants Permission to Issue Listed protected-proprietary Info in Support of 910708 Info Re Application for Amend to License R-2 ML20246P6181989-05-12012 May 1989 Forwards Safety Insp Rept 50-005/89-01 on 890501-02.No Violations Noted ML20154Q3321988-05-17017 May 1988 Forwards Description of Space Reassignment & Necessitated Changes to Physical Security Plan.Encl Withheld ML20154B3851988-05-0303 May 1988 Advises That Review & Evaluation of Pennsylvania State Univ Operator & Senior Operator Requalification Program Submitted on 871021 Completed & Acceptable.Request That Licensee Begin to Implement Approved Program Immediately ML20237H4851987-08-28028 August 1987 Forward Safety Insp Rept 50-005/87-03 on 870720-21.No Violations Noted ML20234A8141987-06-25025 June 1987 Forwards Exam Rept 50-005/87-02OL of Exam Administered on 870603-04 ML20198E5291985-10-18018 October 1985 Forwards Ltr of Transmittal for Rev to Security Plan Which Will Be Mailed on or About 851025.W/o Encl ML20098C8421984-09-21021 September 1984 Informs That Copies of NRC Approved Penn State Breazeale Nuclear Reactor Emergency Preparedness Plan Mailed to All Members of Emergency Organization & State of PA Emergency Mgt Agency.Plan Fully Implemented ML20040D6901982-01-21021 January 1982 Forwards Twenty-Sixth Annual Progress Rept of PA State Univ Breazeale Nuclear Reactor for Period Jul 1980-June 1981 & Repts Minor Changes Made During 1981 ML20039C4901981-12-18018 December 1981 Informs of Violation of Administrative Policy Which Requires Senior Reactor Operator at Control Console for All Power Level Changes.Reactor Shutdown on 811211 W/Only Licensed Operator Present.Procedures Will Be Discussed W/Operators ML19341B1931981-01-23023 January 1981 Submits Info Re Cost of Providing Addl Criticality Monitoring Sys at Facility.Requests 2-yr Exemption from Code Requirements ML19339C3761980-11-13013 November 1980 Forwards Revised Page 24 of Security Plan.Page Withheld (Ref 10CFR2.790) ML19210D0181979-11-13013 November 1979 Forwards Executed Amend 15 to Indemnity Agreement E-10 Defining Course of Transportation ML20125A6291979-06-22022 June 1979 Forwards IE Info Notice 79-16, Nuclear Incident at Tmi. No Action Required ML19289F6651979-06-11011 June 1979 Forwards Executed Amend 14 to Indemnity Agreement E-10 1999-09-28
[Table view] Category:EDUCATIONAL INSTITUTION TO NRC
MONTHYEARML20154Q3321988-05-17017 May 1988 Forwards Description of Space Reassignment & Necessitated Changes to Physical Security Plan.Encl Withheld ML20198E5291985-10-18018 October 1985 Forwards Ltr of Transmittal for Rev to Security Plan Which Will Be Mailed on or About 851025.W/o Encl ML20098C8421984-09-21021 September 1984 Informs That Copies of NRC Approved Penn State Breazeale Nuclear Reactor Emergency Preparedness Plan Mailed to All Members of Emergency Organization & State of PA Emergency Mgt Agency.Plan Fully Implemented ML20040D6901982-01-21021 January 1982 Forwards Twenty-Sixth Annual Progress Rept of PA State Univ Breazeale Nuclear Reactor for Period Jul 1980-June 1981 & Repts Minor Changes Made During 1981 ML20039C4901981-12-18018 December 1981 Informs of Violation of Administrative Policy Which Requires Senior Reactor Operator at Control Console for All Power Level Changes.Reactor Shutdown on 811211 W/Only Licensed Operator Present.Procedures Will Be Discussed W/Operators ML19341B1931981-01-23023 January 1981 Submits Info Re Cost of Providing Addl Criticality Monitoring Sys at Facility.Requests 2-yr Exemption from Code Requirements ML19339C3761980-11-13013 November 1980 Forwards Revised Page 24 of Security Plan.Page Withheld (Ref 10CFR2.790) ML19210D0181979-11-13013 November 1979 Forwards Executed Amend 15 to Indemnity Agreement E-10 Defining Course of Transportation ML19289F6651979-06-11011 June 1979 Forwards Executed Amend 14 to Indemnity Agreement E-10 1988-05-17
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20216J9221999-09-28028 September 1999 Informs That DE Hughes,License SOP-10198-3,no Longer Working as Licensed Senior Reactor Operator with Penn State Univ, Effective 990731.Requests Appropriate Action to Remove Name from List of Active Licensees ML20203L3021998-02-27027 February 1998 Requests Addl Changes to Proposed Amend 32.Proposed Changes Are to Sections 3.4 & 3.5.Revised TS Amend Encl W/Changes & Repagination of Pages 12-22 & 42-44 ML20217R2911997-08-28028 August 1997 Informs That Pg Boyle License SOP-70072 No Longer Working as Licensed SRO W/Penn State Univ Breazeale Reactor Effective 970630 ML20137S4331997-04-0707 April 1997 Fulfills TS Requirement of Written Rept within 30 Days to NRC for Permanent Change in Facility Organization Involving Level 1 & 2 Personnel as Defined in Reactor Facility TSs ML20113E0761996-06-20020 June 1996 Forwards Results of Operator Initial Exam Conducted on 960610-11.W/o Encls ML20094P9041995-11-24024 November 1995 Advises That Aj Mclellan (SOP-70122) Has Resigned Position W/Penn State Univ Breazeale Reactor on 951110.Requests That NRC Take Appropriate Action to Remove Name from List of Active Licensees ML20090L2031992-03-10010 March 1992 Advises That Author Appointed to Position of Senior Vice President for Research & Dean of Graduate School,Effective 920301,replacing Cl Hosler ML20077J9091991-07-29029 July 1991 Notifies That on 910722 Facility Exhaust Sys Failed.Cause of Failure Was Breakdown of Insulation on Wiring That Supplies Power from Console Exhaust Sys Control Switches to Sys Relay Panel ML20076D8471991-07-25025 July 1991 Grants Permission to Issue Listed protected-proprietary Info in Support of 910708 Info Re Application for Amend to License R-2 ML20154Q3321988-05-17017 May 1988 Forwards Description of Space Reassignment & Necessitated Changes to Physical Security Plan.Encl Withheld ML20198E5291985-10-18018 October 1985 Forwards Ltr of Transmittal for Rev to Security Plan Which Will Be Mailed on or About 851025.W/o Encl ML20098C8421984-09-21021 September 1984 Informs That Copies of NRC Approved Penn State Breazeale Nuclear Reactor Emergency Preparedness Plan Mailed to All Members of Emergency Organization & State of PA Emergency Mgt Agency.Plan Fully Implemented ML20040D6901982-01-21021 January 1982 Forwards Twenty-Sixth Annual Progress Rept of PA State Univ Breazeale Nuclear Reactor for Period Jul 1980-June 1981 & Repts Minor Changes Made During 1981 ML20039C4901981-12-18018 December 1981 Informs of Violation of Administrative Policy Which Requires Senior Reactor Operator at Control Console for All Power Level Changes.Reactor Shutdown on 811211 W/Only Licensed Operator Present.Procedures Will Be Discussed W/Operators ML19341B1931981-01-23023 January 1981 Submits Info Re Cost of Providing Addl Criticality Monitoring Sys at Facility.Requests 2-yr Exemption from Code Requirements ML19339C3761980-11-13013 November 1980 Forwards Revised Page 24 of Security Plan.Page Withheld (Ref 10CFR2.790) ML19210D0181979-11-13013 November 1979 Forwards Executed Amend 15 to Indemnity Agreement E-10 Defining Course of Transportation ML19289F6651979-06-11011 June 1979 Forwards Executed Amend 14 to Indemnity Agreement E-10 1999-09-28
[Table view] |
Text
T H E P ENNSYLVANI A S T ATE U NIVERSITY UNIVERSITY PARK, PENNSYLVANIA 16802 College of Engineering Area code 814 Brea/cale Nuclear Reactor 865-6351 30 Nov aber 1982 Robert E. Carter Project Manager Standardization and Special Projects Branch Division of Licensing Nuclear Regulatory Commission Washington, D.C. 20555 Subj ect: Leak Test Method for Non-TRIGA (PATR) Fuel Elements Docket No.: 50-5 NRC License: R-2
Dear Bob,
In regard to our conversation at the November Washington ANS meeting, it was decided that I should inform you in detail on the method to be used to leak test the non-TRICA (PATR) fuel elements. In Dr. R. G. Cunningham's letter of October 18, 1982 to your branch chief , Cecil Thomas, the NRC was provided with a description of the PATR fuel elements. Referring to this description, the UO2 fuel pellets are to be loaded into separate aluminum tubes and scaled by arc welding to form a fuel tube. These tubes will then be leak tested using a leak testing chamber which has been i designed and constructed to leak-test specimens up to 1-1/2 inches in diameter and up to 30 inches long. Several fuel tubes will be inserted in this device.
( The test procedure for this device consists of passing the test l specimens through a ball valve to the inside of the chamber. (See Figure 1).
l The chamber is then evacuated for about an hour to remove the air from the j chamber. The test chamber is then pressurized with helium at %175 psig, for a minimum of six hours. This, in turn, will pressurize the specimen under test, filling it with helium gas through any leaks that exist in it.
Once the test specimen is pressurized for at least six hours, it is removed from the test chamber and, without delay, immersed in a suitable liquid (isopropyl alcohol or ethylene glycol) and observed for bubbles.
Isopropyl alcohol or ethylene glycol should be used for immersion of the specimen to eliminate the possibility of being misled by bubbles formed in other liquids which originate from dissolved air in the liquid. O30 8212030010 821130 PDR ADOCK 05000005 p PDR
Pegn 2 Previous experience with this type of leak system .has -shown that the method will easily identify water leaks in the tubes. The method of assembling the fuel tubes to construct a PATR fuel element should not introduce new leaks. This is because the attachment area of the tubes to the aluminum fittings that hold them in place will be distant from the welds on the tubes. Nevertheless,'the first few PATR fuel elements constructed will be leak tested again to verify their integrity.
Records will be kept as a means of quality control to assure all PATR fuel elements are leak tight.
If you have further questions, please let me know.
4 Sincerely yours, M
, S. H. Levine, Director I
Breazeale Nuclear Reactor
~ Professor of Nuclear Engineering SHL/r cc: E. H. Klevans I. B. McMaster W. F. Witzig i.
R. G. Cunningham Reactor File
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