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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20210G6971999-07-30030 July 1999
Proposed Tech Specs Page 3-39,correcting Typo in Basis Re Storage & Handling of Fuel
ML20209C9231999-07-0808 July 1999
Rev 0,Vol 1 to Proposed TS for Ma Institute of Technology Nuclear Research Lab (MITR-III),in Support of Application for Renewal of License R-37
ML20207E4591999-05-27027 May 1999
Proposed Tech Spec Page 3-39,changing Basis of TS 3.10 to Add Item 3e to Second Line of Second Paragraph & Second Sentence of Fourth Paragraph Changed to Read as Listed
ML20199H2661998-12-31031 December 1998
Revised Proposed Tech Specs Pages Re 971003 Request for Amend to License R-37 & NRC RAI
ML20217G2251997-10-0303 October 1997
Proposed Tech Specs 6.6 Pertaining to Design & Operation of Fission Converter & TS & Minor Changes to Existing TS Necessitated by Adoption of TS 6.6
ML20126M5741992-12-30030 December 1992
Proposed Tech Spec 6.5, Generation of Medical Therapy Facility Beam for Human Therapy
ML20126D8371992-12-22022 December 1992
Proposed TS Section 6.5, Generation of Medical Therapy Facility Beam for Human Therapy & Quality Mgt Program for Generation of MITR-II Medical Therapy Facility Beam for Human Therapy
ML20106B2731992-09-23023 September 1992
Proposed TS 6.5, Generation of Medical Therapy Facility Beam for Human Therapy
ML20113H7261992-07-30030 July 1992
Proposed TS 6.5 Re Generation of Medical Therapy Facility Beam for Human Therapy
ML20235J0761989-02-13013 February 1989
Proposed Tech Spec Changes Revising Fission Density Limit & Amending Percentage of Voids Permitted in UA1(x) Type Fuel
ML20112J1961985-01-15015 January 1985
Proposed Tech Spec Changes Re Variable Reactivity & Shutdown Margin & Closed Loop Control Sys
ML20079J9371982-12-22022 December 1982
Proposed Tech Spec Changes Revising Frequencies for Surveillance Testing of ECCS & Charcoal Filters in Bldg Pressure Relief Sys.Sar Page 6.6 Re Tests & Surveillance Encl
ML20042B9301982-03-22022 March 1982
Draft Revised Tech Spec 5.2-1 Re Design of Reactor Core
ML19345H4201981-05-14014 May 1981
Proposed Changes to Tech Spec 3.10 Re Fuel Element & Core Component Handling & Storage
1999-07-08
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210G6971999-07-30030 July 1999
Proposed Tech Specs Page 3-39,correcting Typo in Basis Re Storage & Handling of Fuel
ML20209C9151999-07-0808 July 1999
Mitr Requalification Program, as Currently Approved & in Effect
ML20209C9231999-07-0808 July 1999
Rev 0,Vol 1 to Proposed TS for Ma Institute of Technology Nuclear Research Lab (MITR-III),in Support of Application for Renewal of License R-37
ML20207E4591999-05-27027 May 1999
Proposed Tech Spec Page 3-39,changing Basis of TS 3.10 to Add Item 3e to Second Line of Second Paragraph & Second Sentence of Fourth Paragraph Changed to Read as Listed
ML20199H2661998-12-31031 December 1998
Revised Proposed Tech Specs Pages Re 971003 Request for Amend to License R-37 & NRC RAI
ML20217G2251997-10-0303 October 1997
Proposed Tech Specs 6.6 Pertaining to Design & Operation of Fission Converter & TS & Minor Changes to Existing TS Necessitated by Adoption of TS 6.6
ML20044G5441993-05-28028 May 1993
Procedures for Conduct of Human Irradiations W/Mit Medical Therapy Facility.
ML20126M5791992-12-30030 December 1992
Revised Quality Mgt Program for Generation of MITR-II Medical Therapy Facility Beam for Human Therapy
ML20126M5741992-12-30030 December 1992
Proposed Tech Spec 6.5, Generation of Medical Therapy Facility Beam for Human Therapy
ML20126D8371992-12-22022 December 1992
Proposed TS Section 6.5, Generation of Medical Therapy Facility Beam for Human Therapy & Quality Mgt Program for Generation of MITR-II Medical Therapy Facility Beam for Human Therapy
ML20106B2731992-09-23023 September 1992
Proposed TS 6.5, Generation of Medical Therapy Facility Beam for Human Therapy
ML20113H7261992-07-30030 July 1992
Proposed TS 6.5 Re Generation of Medical Therapy Facility Beam for Human Therapy
ML20113H7271992-03-0606 March 1992
Quality Mgt Program for Generation of Medical Therapy Facility Beam for Human Therapy at Mit
ML20235J0761989-02-13013 February 1989
Proposed Tech Spec Changes Revising Fission Density Limit & Amending Percentage of Voids Permitted in UA1(x) Type Fuel
ML20112J1961985-01-15015 January 1985
Proposed Tech Spec Changes Re Variable Reactivity & Shutdown Margin & Closed Loop Control Sys
ML20079J9371982-12-22022 December 1982
Proposed Tech Spec Changes Revising Frequencies for Surveillance Testing of ECCS & Charcoal Filters in Bldg Pressure Relief Sys.Sar Page 6.6 Re Tests & Surveillance Encl
ML20042B9301982-03-22022 March 1982
Draft Revised Tech Spec 5.2-1 Re Design of Reactor Core
ML19345H4201981-05-14014 May 1981
Proposed Changes to Tech Spec 3.10 Re Fuel Element & Core Component Handling & Storage
ML20073H1411978-12-26026 December 1978
Procedure PM 7.4.4.2, ISI of Primary Core Tank & Fuel
1999-07-08
[Table view] |
Text
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I It has been calculated that fuel elements when stored in the locations
]
specified in 2b,2c,2d,3b,3c,3d, and 3e will have a calculated effective multiplication (kerr) factor of less than 0.9 under optimum conditions of j water moderation.
These specifications are also conservative for criticality safe handling
)
)
of MITR-1 fuel alone or in combination with MITR-II fuel.
The chief additional problems with spent fuel are those of shielding personnel from the emitted fission product gamma rays and preventing melting from afterheat. The shielding requirement is met by utilizing a shielded transfer flask (item 3e) for movements and temporary storage and more permanent ,
i shielding as indicated in 3a, b, c, and d. The requirement to prevent melting is
]
met by specifying that four days elapse between use of the fuel element in a core operating above 100 kW and removal of the element from the reactor pool.
1 This decay time was determined from experience wid1 the MITR-I combined with I 1
a conservative assumption of doubling the power density for the MITR-II.
The specification on removal of control element provides that the stuck rod criteria will always be met, even when one blade is removed for repair.
Thus, the reactor still would not go critical on the removal of a second con- ,
trol element.
9908030184 990730 3-39 PDR ADOCK 05000020 p PDR L