(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
|
---|
Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20217M4551999-10-14014 October 1999 Application for Amend to License R-95,to Change TS Pages as Listed.Ts Pages Attached ML20217R3571997-08-20020 August 1997 Application for Amend to License R-95,requesting Listed Changes Be Made to Listed Pp & Sections ML20198F1791997-07-31031 July 1997 Application for Amend to Riaec License,Changing Page 7 Section 1.25.5 & 6 Ro,Page 14 Section 2.2.1 Limiting Safety Sys Settings in Forced Convection Mode & Page 16 Section 2.2.2.1 Limiting Safety Sys Setting in Natural Mode ML20148H8701997-06-0606 June 1997 Application for Amend to License R-95,requesting Submitted Changes Be Made to Listed Pp & Sections.Proposed TSs Encl. W/O Encl ML20148D9111997-05-20020 May 1997 Application for Amend to License R-95,requesting That Submitted Changes Be Made to Noted Pp & Sections ML20207D4911988-08-0505 August 1988 Application for Amend to License R-95,revising Tech Spec Page to Change Flow Rate in 115 Ft High Stack from 4,000 Cfm to Approx 14,000 Cfm ML20214S6421987-06-0202 June 1987 Application for Amend to License R-95,replacing Existing Tech Spec Pages 1 & 2 W/Enclosed Pages to Allow for Clarification,Designation Changes & Exclusion Area Const ML20116C5991985-04-24024 April 1985 Application for Amend to License R-95,modifying Tech Spec Page 26 to Change Ph Range from 5.5 to 7.5 & from 5.5 to 9 for Aluminum Piping for HX & Cooling Tower ML20113C2611985-01-15015 January 1985 Application for Amend to License R-95,revising Tech Specs to Change Design Spec Re Core & Control Sys Reactivity Worth to Performance Spec ML20024D0531983-07-28028 July 1983 Application to Amend License R-95,changing Tech Specs to Exempt Byproduct Matl Labs Outside Reactor Bldg from Requirement That Liquid Waste Flow to Retention Tanks in Reactor Bldg,Allowing Flexibility in Renewing License ML20027B5281982-09-15015 September 1982 Application to Amend License R-95,changing Tech Specs to Permit Installation & Use of Graphite Reflectors Slightly Different from Those Presently in Use.Justification Discussed 1999-10-14
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217M4551999-10-14014 October 1999 Application for Amend to License R-95,to Change TS Pages as Listed.Ts Pages Attached ML20199E8221997-11-12012 November 1997 Amend 25 to License R-95,correcting Omission from Previous TS Amend ML20217E2921997-09-23023 September 1997 Amend 24 to License R-95,clarifies TS Requirements & Corrects Typographical Errors ML20217R3571997-08-20020 August 1997 Application for Amend to License R-95,requesting Listed Changes Be Made to Listed Pp & Sections ML20198F1791997-07-31031 July 1997 Application for Amend to Riaec License,Changing Page 7 Section 1.25.5 & 6 Ro,Page 14 Section 2.2.1 Limiting Safety Sys Settings in Forced Convection Mode & Page 16 Section 2.2.2.1 Limiting Safety Sys Setting in Natural Mode ML20140H7331997-06-17017 June 1997 Amend 23 to Licensee R-95,removes Reactor Coolant Inlet Temp as TS Requirement in SL & Lsss,Section 2.1.1 & 2.2.1, Respectively ML20148H8701997-06-0606 June 1997 Application for Amend to License R-95,requesting Submitted Changes Be Made to Listed Pp & Sections.Proposed TSs Encl. W/O Encl ML20148D9111997-05-20020 May 1997 Application for Amend to License R-95,requesting That Submitted Changes Be Made to Noted Pp & Sections ML20132E2461996-12-18018 December 1996 Amend 22 to License R-95,providing for Extension of Annual TS Surveillances for Safety Blade Testing & Reactivity Calculations ML20205K6251988-10-20020 October 1988 Amend 16 to License R-95,changing Tech Specs to Clarify Exhaust Sources & Rates Entering Stack of Reactor Bldg ML20207D4911988-08-0505 August 1988 Application for Amend to License R-95,revising Tech Spec Page to Change Flow Rate in 115 Ft High Stack from 4,000 Cfm to Approx 14,000 Cfm ML20245C9721987-10-27027 October 1987 Amend 15 to License R-95,changing Tech Specs to Redefine Restricted Area to Include Reactor Bldg & Adjacent Ofc Lab Wing Only & to Exclude 3-acre Area Known as Nuclear Science Ctr ML20214S6421987-06-0202 June 1987 Application for Amend to License R-95,replacing Existing Tech Spec Pages 1 & 2 W/Enclosed Pages to Allow for Clarification,Designation Changes & Exclusion Area Const ML20128D3001985-05-20020 May 1985 Amend 14 to License R-95,changing Allowable Ph Range of Secondary Coolant Water from 5.5-7.5 to 5.5-9 ML20116C5991985-04-24024 April 1985 Application for Amend to License R-95,modifying Tech Spec Page 26 to Change Ph Range from 5.5 to 7.5 & from 5.5 to 9 for Aluminum Piping for HX & Cooling Tower ML20113C2611985-01-15015 January 1985 Application for Amend to License R-95,revising Tech Specs to Change Design Spec Re Core & Control Sys Reactivity Worth to Performance Spec ML20024D0531983-07-28028 July 1983 Application to Amend License R-95,changing Tech Specs to Exempt Byproduct Matl Labs Outside Reactor Bldg from Requirement That Liquid Waste Flow to Retention Tanks in Reactor Bldg,Allowing Flexibility in Renewing License ML20027B5281982-09-15015 September 1982 Application to Amend License R-95,changing Tech Specs to Permit Installation & Use of Graphite Reflectors Slightly Different from Those Presently in Use.Justification Discussed 1999-10-14
[Table view] |
Text
__ _ __
C w# . Gags STATE OF RHODE ISLAND AND PROVIDENCE PLANTATIONS KliODE ISLAND ATOMIC ENERGY COMMISSION Nuclear Science Center South Terry Road Narragansett, R. 1.02882 September 15, 1982 U. S. Nuclear Regulatory Commission Attn: Chief, Standardization and Special Products Branch Division of Licensing Washington, DC 20555 License R-95 Docket 50-193
Dear Sir:
It is hereby requested that the technical specifications for the Rhode Island Nuclear Science Center research reactor be amended to permit the installation and use of graphite reflectors which are slightly different from those presently used. These differences are necessitated by the changes in materials and their standard dimensions and designations which have occurred since the original reflectors were fabricated.
Amendments are requested in two sections of the technical specifications as follows:
Page 7, Section E.1. Principal Core Materials Change the entry for " Reflector" to read:
AGOT grade (or equivalent) graphite ond/or water. -
Justification: This change will make it explicitly clear that J any graphite the equivalent of AGOT is suitable. AGOT is a designation which was in comraon usage when the original reflectors l were fabricated. At present, graphites with characteristics l l comparable to AGOT are avai.lable with different designations. ,
i For example, a graphite called " nuclear grade 2" is available I j with characteristics comparable to AGOT.
Page 8, Sectioit E.3. Reflector Elements ! g Change the entire section to read:
, overall reflector element 3 in. x 3 in. x 40 in.
l dimensions, nominal Nominal clad thickness .1 in .
Nominal graphite 2.8 in. x 2.8 in. x 28.7 in, dimensions l
82092102_o8 l
- . . . . ._. _ _ _ _ _ . . _ . - . _ _ . - _ . _ _ - _ , m, - . . . - . , _ - ,
U. S. Nuclear Regulatory Commission September 15, 1982 .
Page 2 Justification: This change will make it possible to utilize standard size extrusions of aluminum for the fabrication of the "can" (clad) which surrounds the graphite. No change will be made in the outside dimensions and shape (envelope) of the reflector piece. The dimension change is an increase in the wall thickness of the aluminum can which surrounds the graphite and a corresponding decrease in the cross section dimensions of the graphite. This should create no significant differences in the performance of the reflector piece for the following reasons:
- 1. The center line temperature of a reflector with the thicker clad will be the same or smaller than the center line temperature of a reflector with the thinner clad. This is because the aluminum has a much bigger thermal conductivity than the graphite which it replaces and because the heat generatign source terms do not substantially change.
- 2. The increased amount of aluminum at the interface between the reactor core and the graphite reflector will have a negligible effect on the nulcear characteristics of the overall core. Because the aluminum has a higher neutron absorption cross section than the graphite it replaces, the overall effect will be one of a slight decrease in the reactivity worth of a reflector because of a small increase in absorption of thermal neutrons.
- 3. The strength of the aluminum container will be greatly improved.
It is requested that these amendments be approved as soon as possible so that the new reflectors may be utilized.
Thank you for your effort in this matter.
Very truly yours, ,
SwN 3 A&
A. Francis DiMeglio Director AFD:cd Signed and sworn to before me this /d day of September, 1982.
U ll ( v b-- , E My Commission expires on ( I u <i dc /90 .v i ;