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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20236N4581998-07-0606 July 1998 Proposed Tech Specs Re Amend 45 to Ford Nuclear Reactor License Which Would Add Condition B(5) for re-irradiation, Organization Chart Update & Formatting Chages ML20217M2661998-04-0202 April 1998 Proposed Tech Specs Pages 7,8,13 & 17 Re Amend 44 to License R-28,incorporating Safety Channel on Reactor Coolant Inlet Temperature That Was Installed to Address Problem ML20059M3141993-08-0101 August 1993 Proposed Tech Specs Accommodating Implementation of New 10CFR20 ML20244D4981989-05-0808 May 1989 Rev 1 to Tech Specs for Ford Nuclear Reactor ML20137C4781985-11-30030 November 1985 Proposed Tech Specs,Changing Page 35,Figure 6.1, Organization Chart for Ford Nuclear Reactor, to Eliminate Supervisor of Reactor Operations Block ML20135H8051985-09-18018 September 1985 Proposed Changes to Tech Spec 3.1 Re Subcritical State of Reactor During Fuel Loading Changes ML20138L5921985-02-28028 February 1985 Proposed Tech Spec Changes,Including Section 3.1 Re Reactivity Limits & 3.9 Re Fission Density Limit ML20135A3391984-11-30030 November 1984 Proposed Revised Tech Spec Page 9 Re Subcriticality of Reactor During Fuel Load Changes 1998-07-06
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20236N4581998-07-0606 July 1998 Proposed Tech Specs Re Amend 45 to Ford Nuclear Reactor License Which Would Add Condition B(5) for re-irradiation, Organization Chart Update & Formatting Chages ML20248L6071998-06-0303 June 1998 Rev 1 to Operating Procedure OP-211, Operating Hot Demineralizer Sys (Hot Di) ML20217M2661998-04-0202 April 1998 Proposed Tech Specs Pages 7,8,13 & 17 Re Amend 44 to License R-28,incorporating Safety Channel on Reactor Coolant Inlet Temperature That Was Installed to Address Problem ML20059M3141993-08-0101 August 1993 Proposed Tech Specs Accommodating Implementation of New 10CFR20 ML20244D4981989-05-0808 May 1989 Rev 1 to Tech Specs for Ford Nuclear Reactor ML20137C4781985-11-30030 November 1985 Proposed Tech Specs,Changing Page 35,Figure 6.1, Organization Chart for Ford Nuclear Reactor, to Eliminate Supervisor of Reactor Operations Block ML20135H8051985-09-18018 September 1985 Proposed Changes to Tech Spec 3.1 Re Subcritical State of Reactor During Fuel Loading Changes ML20138L5921985-02-28028 February 1985 Proposed Tech Spec Changes,Including Section 3.1 Re Reactivity Limits & 3.9 Re Fission Density Limit ML20135A3391984-11-30030 November 1984 Proposed Revised Tech Spec Page 9 Re Subcriticality of Reactor During Fuel Load Changes 1998-07-06
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e TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 November, 1984
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3.O LIMITING CONDITIONS FOR OPERATION 3.1 - Reactivity Limits Applicability: ;
This specification applies to the reactivity of the reactor core and to the reactivity worths of control rods and experiments.
When the reactor is operated with the heavy water reflector tank in place, the limits will not include the static reactivity worth '
of the tank. ,
Objective-l To assure that the reactor can be controlled and shutdown ,
at all times and that the safety limits will not be exceeded. !
Specification: I I
(1) The shutdown margin relative to the cold, xenon free i critical condition shall be at least .025 delta K/K with l all three shim safety rods fully inserted and the regulating rod fully withdrawn and 0.0045 delta K/K with '
the most reactive shim safety rod and the regulating rod fully withdrawn.
(2) The overall core excess reactivity including moveable experiments shall not exceed O.038 delta K/K.
(3) The total reactivity worth of all experiments shall not exceed 0.012 delta K/K.
(4) The reactivity worth of each experiment shall be limited as follows:
Maximum Exoeriment Reactivity Worth Moveable 0.0012 delta K/K Secured 0.012 delta K/K (5) The reactor shall be subcritical by at least 0.025 delta K/K during fuel loading changes.
(6) Shim safety rods shall not be removed from the core for inspection if the shutdown margin is less than 0.01 delta K/K with the most reactive remaining shim safety rod fully withdrawn.
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l (7) The reactivity worth of the regulating rod shall not' l
I exceed.O.OO6 delta K/K.
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