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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20236S4451998-07-20020 July 1998 Forwards Copy of Recently Approved Regulation in Fr Which Permits Colleges & Univs to self-guarantee Decommissioning Costs If Certain Criteria Are Met.Requests Provision of Criterion to Be Used If School Decides to self-guarantee ML20217H6461998-04-28028 April 1998 Forwards Insp Rept 50-225/98-201 on 980407-10.No Violations Noted ML20217H4111997-08-0505 August 1997 Informs That Responsibility for Non-Power Reactor Insp Program Has Been Transferred from Regional Ofc to Nrr. Addresses Listed ML20148F0771997-05-29029 May 1997 Informs That Bs Craig Replaced Mn Galayda as Supervisor of RPI Reactor Critical Facility on 970516 ML20135C0821997-02-24024 February 1997 Forwards Certificate for Listed Newly Licensed Individual. W/O Encl ML20133A4721996-12-26026 December 1996 Forwards Results of Operator Initial Exam Conducted at Rensselaer Polytech Institute on 961119.W/o Encl ML20133D0691996-12-26026 December 1996 Forwards Initial Exam Rept 50-225/OL-96-01 on 961119, Administered to Employee Who Applied for License to Operate Licensee Reactor,& Exam & Answer Key.W/O Encl ML18065B2651995-07-21021 July 1995 Informs of 950711 Conversation W/S Holmes Re Change & Temporary Reduction in Radiation Safety Staffing within Past Yrs ML20058E4681993-11-26026 November 1993 Forwards Insp Repts 50-225/93-01 & 70-0920/93-01 on 931102-04.No Violations Noted ML20059J1231993-11-0303 November 1993 Discusses Telcon Arrangements Made for Administration of Operator Licensing Exam.Written & Operating Exams Scheduled for Wk of 940110 ML20092C8061991-08-16016 August 1991 Advises of Licensee Plans to Double Storage Capacity of Fuel Vault ML20077R6771991-08-0808 August 1991 Submits Results of Boric Acid Experiments on Known Core,Per Discussions W/Nrc & Univ Nuclear Safety Review Board.State Point Measurements Made Before & After Boric Acid Addition Agreed within Specified Reproducibility Errors ML20077D9561991-05-30030 May 1991 Forwards Corrected Affidavit for Withholding Supporting Matl to License Amend for RCF Critical CX-22 Facility (Ref 10CFR2.790) ML20073P8341991-05-15015 May 1991 Forwards Abb Cenp Critical Experiments in Reactor Critical Facility of Rpi ML20073G8631991-04-30030 April 1991 Forwards CE Proprietary Abb Cenp Critical Experiments in Reactor Critical Facility of Rensselaer Polytechnic Inst. Encl Withheld (Ref 10CFR2.790) ML20073G8561991-04-12012 April 1991 Forwards Addendum to Which Transmitted Presentation of Technical Info Re Calculation & Measurement of Tech Spec Parameters for Erbium Burnable Absorbers at Facility ML20070U7151991-04-0303 April 1991 Submits Decommissioning Rept,Per 10CFR50.33(k)(2),in Response to T Michaels .Assets W/Listed Market Value Deposited in Bank of New York in Mar 1991 ML20077A4371991-03-25025 March 1991 Forwards Info Re Calculation & Measurement of Tech Spec Parameters for Erbium Burnable Adsorbers at Univ Reactor Criticality Facility Developed by C-E.Info Withheld (Ref 10CFR2.790) ML20059K1611990-09-14014 September 1990 Forwards Completed Compliance Rept Re Decommissioning of Reactor,Per 900726 Request ML20059K1701990-09-13013 September 1990 Submits Decommissioning Funding Rept,Per 10CFR50.75(e)(2) ML20055H9501990-07-26026 July 1990 Advises That Submittal Re Decommissioning & Financial Assurance Will Be Sent in mid-Sept 1990 ML20247B2291989-07-19019 July 1989 Forwards Safety Insp Rept 50-225/89-01 on 890518-19.No Violations Noted ML20246A1571989-06-27027 June 1989 Advises That 881017 & 890309 & 0413 Changes to Physical Security Plan Consistent w/10CFR50.54(p) & Acceptable ML20247J1971989-05-22022 May 1989 Submits Annual Rept of Operations at RPI Reactor Critical Facility Required Under Tech Spec 6.5.1 ML20246P3331989-03-22022 March 1989 Forwards Agenda for 890418-19 Research & Test Reactor Seminars in King of Prussia,Pa Per .Updated Agenda Soon to Follow.Map of Local Area Also Encl ML20247E1771989-03-21021 March 1989 Forwards Request for Ref Matl Requirements for Reactor/ Senior Reactor Operator Licensing Exams,Scheduled for 890614-15 ML20235V7871989-02-17017 February 1989 Forwards Memo Describing Incident Which Occurred at Reactor Critical Facility.Understands That Incident Does Not Require Immediate Notification to NRC ML20206F8061988-11-0909 November 1988 Forwards Safety Insp Rept 50-225/88-04 on 880817-18 & Notice of Violation.Violations Indicate Need for Greater Mgt Oversight of & Attention to Licensed Activities ML20154R8881988-09-28028 September 1988 Forwards Safety Insp Rept 50-225/88-03 on 880812.No Violations Noted ML20246K9431988-09-16016 September 1988 Forwards BC Drobnicki Memo,Revising Memo Communicated to NRC on 880816.Encl Withheld (Ref 10CFR2.790(d)) ML20151G9851988-07-19019 July 1988 Forwards Safeguards Insp Repts 50-225/88-02 & 70-0920/88-01 on 880607-10 & Partially Withheld Notice of Violation ML20196L0361988-06-28028 June 1988 Forwards Exam Rept 50-225/88-01OL of Exam Administered During Wk of 880523.Licensee Should Describe,Within 30 Days, What Steps Will Be Taken to Assure Future License Applicants Will Possess Adequate Experience 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 ML20196K1521988-03-0808 March 1988 Final Response to FOIA Request.Forwards App E Document.App E Document Also Available in Pdr.App F Document Partially Withheld & App G Document Completely Withheld (Ref FOIA Exemptions 4 & 5),respectively IA-87-825, Final Response to FOIA Request.Forwards App E Document.App E Document Also Available in Pdr.App F Document Partially Withheld & App G Document Completely Withheld (Ref FOIA Exemptions 4 & 5),respectively1988-03-0808 March 1988 Final Response to FOIA Request.Forwards App E Document.App E Document Also Available in Pdr.App F Document Partially Withheld & App G Document Completely Withheld (Ref FOIA Exemptions 4 & 5),respectively ML20149M6751988-02-19019 February 1988 Forwards Exam Rept 50-225/87-02(OL) of Exams Administered on 871201-02 ML20235G7921987-09-22022 September 1987 Confirms 870917 Telcon Authorizing Licensee to Proceed W/ Conversion of High to Low Enriched U ML20235F7361987-09-22022 September 1987 Ack Reciept of 870811 Comments on Changes to Reactor Staffing at Rensselaer Polytechnic Inst Critical Experiment Reactor Facility.Conversion Granted ML20234C0041987-09-10010 September 1987 Summarizes 870909 Discussion Re F Wicks Intervention Document Which Alleges That Fj Rodriguez-Vera Inappropriate Reactor Supervisor Due to Status as Student.Student Visa Permits Employment on Campus ML20238A6071987-08-31031 August 1987 Forwards Amend 8 to License CX-22 & Safety Evaluation.Amend Changes License Conditions to Reflect Approval of Revised Security Plan Submitted on 870609.Rev to Plan Reflects New Measures Used to Protect SNM of Low Strategic Significance ML20235N7951987-07-0707 July 1987 Forwards Order Modifying License CX-22 to Convert from High to Low Enriched U,Safety Evaluation,Environ Assessment & Replacement Pages for Tech Specs,In Response to 861003 Request ML20215E0411987-06-12012 June 1987 Informs That Fence Mods Around Civil Protection & Security Zones of Facility Completed on 870611.Changes Return Facility to Spirit of Situation Prior to 861230 & of New Security Plan ML20215E1111987-06-0909 June 1987 Forwards Response to Comments Re Rensselear Polytechnic Inst Reactor Critical Facility Security Plan Dtd Jan 1987. W/O Encl ML20214U6461987-05-27027 May 1987 Informs of Recent Realignment within NRC Region I,Div of Reactor Projects That Affects Responsibility for Insp of Research & Test Reactor Facilities.Div Organization Chart & 10CFR50 Re Communications Procedures Amends Encl for Review ML20214K5511987-05-18018 May 1987 Forwards Insp Rept 50-225/87-01.Licenses of Two of Three Currently Licensed Operators Will Be Reactivated Upon Proper Application & Subsequently Renewed for Use W/New Core Configuration ML20213G5191987-05-13013 May 1987 Forwards Request for Addl Info Re Security Plan on Protection of SNM of Low Strategic Significance Submitted by .Encl Withheld (Ref 10CFR2.790(d)) ML20206Q5291987-04-15015 April 1987 Forwards Reactor Operator Requalification (Ror) Program for Rensselaer Polytechnic Inst Reactor Critical Facility (Rcf). Rept Includes Section Re Requalification of Currently Licensed Senior Reactor Operators ML20214Q5951987-04-10010 April 1987 Forwards EGG-NTA-7660, Evaluation of Spert Fuel at Rensselaer Polytechnic Inst, Technical Evaluation Rept Submitted as Part of Task 3 ML20205T5541987-03-31031 March 1987 Advises That 870205 Rev to Security Plan Will Be Reviewed w/861223 Security Plan.Headquarters Will Respond Re Rev ML20207S2931987-03-12012 March 1987 Forwards Missing Pages from App 3 to Ref 5 in Addendum to 870303 Answer to Question 16 Re Difxy Computer Code 1998-07-20
[Table view] Category:EXTERNAL CORRESPONDENCE
MONTHYEARML20092C8061991-08-16016 August 1991 Advises of Licensee Plans to Double Storage Capacity of Fuel Vault 1991-08-16
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Text
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- Pt I.*N I !M W 5 August 16,1991 Mr. Keith R. Brown Office of External Affairs U.S. Department of Energy Idaho Operations Office One Energy Drive -
Idah<> Falls, ID 84302
Dear Sir:
The RCF Fuel Vault (see Figures 1 and 2) currently is licensed under CX-22 to store about 600 SPERT(F1) fuel pins. To double this storage capacity certain modifications are required as noted below. Consideruon of these mod!fications involves fuel rack strength as well as criticality.
A current maximum of 15 SPERT(F1) fuel pins, each 42" long, are stored in each of 41 open aluminum storage tubes 5" in diameter and 42" in length. An additional aluminum storage tube 5" in diameter and 45" in length has a welded back cover and a bolted and wire-sealed front cover for storage of three demountable fuel pins. This wire-scaled aluminum storage tube is for security of the UC2 fuel pellets in the demountable fuel pins and was requested by the U.S. Nuclea-Regulatory Commission; it appears as the first item in Table 1.
Thirty-nine additional aluminum storage tubes appear as the second item in Table 2. The 80 = 41 + 39 storage tubes can hold 1200 = 80 x 15 SPERT(F1) fuel pins for a total of 1203 fuel pins, subject to strength and criticality considerations. The 81 fuel storage tubes are supported by a Unistrut structure which is bolted to the concrete back, floor, and sides of the 8' x 10' x 8' high Fuel Storage Vault. The bolt fastenings to the sides are a consequence of adding two Unistrut P1000 members (item 3 in Table 1) horizontally (see Figure 2) bolted into the side walls for additional stability. The main Unistrut structure is built up of 8 Unistrut P1000 vertical columns 80" high,18 Unistrut P3300 horizontal beams 120" long, and 36 Unistrut P3301 front-to-back members 25"long. The 81 aluminum storage tubes are fastened to the P3300 members with Unistrut P1122 clamps of which 162 are required, all of which are on hand. Forty of the aluminum storage tubes are wrapped with 15 mil thick cadmium sheets 28" in length and 18" in width, all of which are on hand. The total cost for the storage rack upgrade to double the stored fuel pins is $2430.
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Keith R. Brown August 14,1991
, Page 2 With 15 SPERT(F1) fuel pins stored in ech aluminum storage tube the capacity of the rack is 80 x 15 +3 or 1203 fuel pins, the calculated multip!! cation iactor flooded with water is far b210w 0.95 with or without the cadmium wraps. The static load is 1/20 of the allowable load on each Unistrut column and 1/8 of the allowable load on each Unisttut beam. No additional criticality calculations are required to demonstrate this, because the criticality calculations submitted earlier to the U.S.
NRC were for infinite arrays of storage tubes with and without cadmium wraps.
It is useful to compare the proposed fuel content of the fuel rack with that originally licensed in the 1950's. The origir.el. license assumed 81kg U 235,5.6kg U. -
238,6kg 0, and 760kg stainless steel in about 2900 fuel plates stored in the rack. Each SPERT(F1) fuel pin contains 35.2g U 235 so hi 1203 fuel pins there are 42.3kg U 235 and the pins have a mass of about 1200kg. Thus the proposed mass loading is somewhat larger and the U 235 loading is smaller.
Sincerely, ,
/ . ,,\ ,1 N Dr. Der.a!d " ihtris, Director RPI Reactor (*r. 3 cal 7acility (RCF)
DRitjjd cc R.C. Block J.Schoonbeck i R. Rohr E. Muzzey T. Michaels (USNRC) /
L
Table 1. Fuel Vault Components for Enhanced 5(gni,gg
- 1. One (1) closed storage tube of aluminum with wejded $ 280.00 back cover and bolted front cover with wire-seal fixture. ,
2.* Thirty nine (39) fuel storage tubes of aluminum 42" long by $1700.00 ,
5" outer diameter and about 1/8" wall thickness, cut and deburred.
- 3. Two (2) Unistrut P1000 members 10' long with bolt fixtures. $ 150.00
- 4. Installation 5 300.00 -
i Total
$2430.00
' Prices for aluminum are subject to change.
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..' l Figure 1. RPI Reactor Critical Facility (RCF) Showing Reactor Tank (RT), Subtank (ST), Core Water Storage Tank (WST), Reactor Fill Pump (FP), Sump Pump (SP),
Cable Swa chyard (SW) and Trench, Control Room, Control Console, Compuer (Comp), Power Panel (PP), Fuel Storage Vault (W), Fuel Stolage Rack (FSR), Utility i Panel (UP), Piping Pit (PI), Ion Er. change Columns (IE), Shielded Room (SR), Fuel l Rod Counting Apparatus (RCA), and Other Components.
i Figure 2. RCF Fuel Vault Showing Some of the 9 x 9 = 81 Fuel Storage Tubes and Clamps (dimensions in inches).
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