ML20078B624
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| ML20078B624 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 10/07/1994 |
| From: | Tehan T RHODE ISLAND, STATE OF |
| To: | Mendonca M Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20078B629 | List: |
| References | |
| NUDOCS 9410260164 | |
| Download: ML20078B624 (1) | |
Similar Documents at Rhode Island Atomic Energy Commission | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H8701999-10-15015 October 1999
[Table view]Responds to Recipient Informing NRC of from W Simoneau to Rhode Island Atomic Energy Commmission & Proposed Minutes from Rhode Island Commission Meeting of 990923 ML20205L0991999-04-0707 April 1999 Forwards Insp Rept 50-193/99-201 on 990322-26.No Violations Noted.Insp Included Review of Activities Authorized for Facility ML20155G4431998-10-14014 October 1998 Confirms 981014 Telcon That T Tehan Will Take Two Year re- Qualification Exam at Same Time SRO License Will Be Changed from Inactive to Active Status ML20154J3051998-10-13013 October 1998 Forwards Insp Rept 50-193/98-202 on 980921-25.No Violations Noted.Various Aspects of Safety Program Inspected Including Selective Exams of Procedures & Representative Records & Interviews with Personnel ML20203E0421998-02-13013 February 1998 Forwards Insp Rept 50-193/98-201 on 980113-15.No Noncompliance or Safety Concerns Were Identified ML20199E8141997-11-12012 November 1997 Forwards Amend 25 to License R-95 & Safety Evaluation.Amend Corrects Omission from Previous TS Amend ML20211J0081997-10-0202 October 1997 Forwards Corrected Copy of Page 29 of Amend 24 of TS Re Change Made by Amend 20 ML20217E2851997-09-23023 September 1997 Forwards Amend 24 to License R-95 & Se.Amend Clarifies TS Requirements & Corrects Typographical Errors ML20198F0111997-08-0505 August 1997 Informs That Responsibility for Non-Power Reactor Insp Program Has Been Transferred from Regional Ofc to Nrr. Addresses Listed ML20140H7241997-06-17017 June 1997 Forwards Amend 23 to License R-95 & Se.Amend Removes Reactor Coolant Inlet Temp as TS Requirement in SL & Lsss,Section 2.1.1 & 2.2.1,respectively ML20140F8331997-06-11011 June 1997 Forwards Results of 970528 Operator Initial Exam at Rhode Island Aec.W/O Encl ML20148J8071997-06-11011 June 1997 Forwards Operator Licensing Initial Exam Rept 50-193/OL-97-01 During Wk of 970526 ML20196G8941997-05-30030 May 1997 Informs of Error in ,Concerning Changes to Riaec License.Ts Page 63 Correct ML20140E7681997-04-23023 April 1997 Forwards Insp Rept 50-193/97-01 on 970311-14.No Violations Noted ML20135E1481997-03-0404 March 1997 Requests Matl Listed in Encl 1, Ref Matl for Reactor/Senior Reactor Operator Licensing Exams, at Least 60 Days Prior to 970526.Procedures for Administration & Review of Written Exams Requested ML20132E2351996-12-18018 December 1996 Forwards Amend 22 to License R-95 & Safety Evaluation.Amend Provides for Extension of Annual TS Surveillances for Safety Blade Testing & Reactivity Calculations ML20135E3531996-12-0505 December 1996 Requests One Time Extension to Allow Safety Blade Testing & Reactivity Calculations as Outlined Per Encl.One Month Extension Requested to Allow Testing to Be Done in Jan 1997 ML20134K4811996-11-13013 November 1996 Informs That B Smith,SOP-10724-1,has Retired & No Longer Needs to Maintain License ML20117A8001996-08-20020 August 1996 Forwards Info Which Constitutes Second Annual Rept Required by Rev One to TS ML20096D4081996-01-12012 January 1996 Provides Answers to Concerning Rev of Rhode Island Nuclear Science Ctr TS to Combine Radiation Safety Committee & Reactor Utilization Committee Into Single Committee Called Nuclear & Radiation Safety Committee ML20083M5121995-05-12012 May 1995 Forwards Second Rev to ECCS for Facility.Rev Incorporates Comments from Design Review Conducted by Anl ML20082S0001995-04-18018 April 1995 Advises That Shipment Id R95-030995B Made Successful Transit from Point of Origin to Destination on Schedule ML20082R9971995-04-0505 April 1995 Advises That 10CFR73 Shipment Id R95-030995A Successfully Transported from Point of Origin to Destination on Schedule ML20081J0781995-03-20020 March 1995 Forwards Rev of TS to Combine Radiation Safety Committee Reactor Utilization Committee Into Single Committee Called Nuclear & Radiation Safety Committee ML20078R3571994-12-16016 December 1994 Notifies of stand-down of Shipment W/Id Numbers R95-111894A, R95-111894B & Rescheduling of Shipment.Nrc to Be Notified of New Shipment Dates & New Id Numbers to Be Assigned ML20078R5861994-12-14014 December 1994 Proposes Rev of TS to Require Sampling of Secondary Coolant Sys for Radioactivity (TS 4.3.b) on Weekly Basis & Deletion of Requirement for Secondary Radiation Detector,Per Discussion W/Nrc.Revised TS Page 42 Encl ML20080B1411994-11-17017 November 1994 Advises That for Purposes of Completion of Notification Requirements Under 10CFR73.72,original Enrichment of Sf Assemblies Was 93%,appropriate Governors Notified According to NRC Requirements & Armed Escorts Will Be Provided ML20078B6241994-10-0707 October 1994 Forwards Ri Nuclear Science Ctr Proposed 3 MW or Higher ECCS Plan ML20072M6941994-08-24024 August 1994 Forwards Change to Physical Security Plan,Per 10CFR50.54(p)(2).Encl Withheld ML20072S2751994-08-24024 August 1994 Proposed That Section 3.7.1 of TS Be Changed as Listed, Concerning Rev of TS to More Clearly Define Allowed Reactor Operation W/O Particulate or Gaseous Stack Effluent Monitor in Svc ML19346J0111994-08-24024 August 1994 Informs That Annual Rept for 1993-1994 Would Be Administrative Burden than Technical Value.Full Rept Will Be Submitted for 1994-1995 ML20071G1801994-07-0505 July 1994 Notifies That Ef Spring Retired as Employee of Riaec & No Longer Has Need to Maintain Operators License at Facility Effective 940628.Spring RO License OP-2365-11 Should Be Expired,Per 10CFR50.74(b) ML20069H4681994-06-0101 June 1994 Forwards Rhode Island Nuclear Science Ctr Proposed 3 MW or Higher Emergency Core Cooling Sys Plan ML20069J6041994-05-17017 May 1994 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-193/94-01.Corrective Actions:Revision of Procedures & Radiation Safety Guide Has Started Which Would Be Completed by 940731 Rather than 940701 Due to Delays ML20070N7331994-04-13013 April 1994 Informs That 10CFR20 Training Requirements Fulfilled Re New Requirements Issued on 940223 Per Insp Rept 50-193/94-01 ML20063K7901994-02-18018 February 1994 Forwards Preliminary Rept on Ri Nuclear Science Ctr Conversion from HEU to LEU Fuel ML20063G0961994-01-31031 January 1994 Forwards Rev 1 to Tech Specs,Including Revs Resulting from Review Process to Date ML20058K3591993-12-0808 December 1993 Forwards Insp Rept 50-193/93-04 on 931116-18.No Violations Noted ML20058G8291993-12-0303 December 1993 Submits Change to Ri Atomic Energy Commission Physical Security Plan.Change Withheld ML20058A6551993-11-17017 November 1993 Forwards Revised Copy of Proposed TSs for License R-95, Incorporating Questions Received from NRC to Date ML20057C2411993-09-17017 September 1993 Forwards Insp Rept 50-193/93-03 on 930810-18.No Violations Noted ML20056H3101993-09-0202 September 1993 Forwards Revised Emergency Plan,Reflecting Comments from Recent NRC Region I Review of Plan.Copy of Old Plan Also Encl ML20056H2801993-08-24024 August 1993 Requests Addl Info to Continue Review of Application for Amend of OL R-95,per 921222 Submittal ML20056C1451993-03-18018 March 1993 Forwards Insp Rept 50-193/93-02 on 930223-25.No Violations Noted.Written Procedures for Some Health Physics Operations Not Formalized ML20128G6661993-02-0404 February 1993 Forwards Safeguards Insp Rept 50-193/93-01 on 930119-22.No Safety Concerns or Violations Noted ML20128E7271993-01-28028 January 1993 Advises That 921130 & 930107 Revs 4 & 5,respectively,to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20127H2611993-01-13013 January 1993 Forwards Revised Pages to Sar,Rev 1,addressing Issues Discussed in 930131 Telcon Re Amended Facility License,Leu Reactor Startup Plan,Reactor Core & Control Elements,Safety Sys Settings & Beryllium Lifetime ML20126F4461992-12-22022 December 1992 Forwards Rev 1 to SAR for Low Enriched Fuel Conversion of Ri Nuclear Science Ctr Research Reactor, Incorporating Questions Forwarded by NRC 920914 & 1102 Ltrs & Original & Revised Tech Specs,Per ANSI N378-1974 ML20116L3711992-11-0202 November 1992 Advises That Listed Multiple Choice Question B 016 from 921027 Initial/Requalification Exam Had Two Possible Answers.All Other Questions/Answers Resolved Satisfactorily at Exit Meeting ML20099A6181992-07-23023 July 1992 Forwards Rev 1 to SAR for Low Enriched Fuel of Rhode Island Nuclear Science Ctr Research Reactor, Per Telcon W/M Mendonca.Rev Updates Analysis of LOCA to Reflect Beamport Operational & Design Considerations 1999-04-07 Category:INCOMING CORRESPONDENCE MONTHYEARML20155G4431998-10-14014 October 1998
[Table view]Confirms 981014 Telcon That T Tehan Will Take Two Year re- Qualification Exam at Same Time SRO License Will Be Changed from Inactive to Active Status ML20211J0081997-10-0202 October 1997 Forwards Corrected Copy of Page 29 of Amend 24 of TS Re Change Made by Amend 20 ML20196G8941997-05-30030 May 1997 Informs of Error in ,Concerning Changes to Riaec License.Ts Page 63 Correct ML20135E3531996-12-0505 December 1996 Requests One Time Extension to Allow Safety Blade Testing & Reactivity Calculations as Outlined Per Encl.One Month Extension Requested to Allow Testing to Be Done in Jan 1997 ML20134K4811996-11-13013 November 1996 Informs That B Smith,SOP-10724-1,has Retired & No Longer Needs to Maintain License ML20117A8001996-08-20020 August 1996 Forwards Info Which Constitutes Second Annual Rept Required by Rev One to TS ML20096D4081996-01-12012 January 1996 Provides Answers to Concerning Rev of Rhode Island Nuclear Science Ctr TS to Combine Radiation Safety Committee & Reactor Utilization Committee Into Single Committee Called Nuclear & Radiation Safety Committee ML20083M5121995-05-12012 May 1995 Forwards Second Rev to ECCS for Facility.Rev Incorporates Comments from Design Review Conducted by Anl ML20082S0001995-04-18018 April 1995 Advises That Shipment Id R95-030995B Made Successful Transit from Point of Origin to Destination on Schedule ML20082R9971995-04-0505 April 1995 Advises That 10CFR73 Shipment Id R95-030995A Successfully Transported from Point of Origin to Destination on Schedule ML20081J0781995-03-20020 March 1995 Forwards Rev of TS to Combine Radiation Safety Committee Reactor Utilization Committee Into Single Committee Called Nuclear & Radiation Safety Committee ML20078R3571994-12-16016 December 1994 Notifies of stand-down of Shipment W/Id Numbers R95-111894A, R95-111894B & Rescheduling of Shipment.Nrc to Be Notified of New Shipment Dates & New Id Numbers to Be Assigned ML20078R5861994-12-14014 December 1994 Proposes Rev of TS to Require Sampling of Secondary Coolant Sys for Radioactivity (TS 4.3.b) on Weekly Basis & Deletion of Requirement for Secondary Radiation Detector,Per Discussion W/Nrc.Revised TS Page 42 Encl ML20080B1411994-11-17017 November 1994 Advises That for Purposes of Completion of Notification Requirements Under 10CFR73.72,original Enrichment of Sf Assemblies Was 93%,appropriate Governors Notified According to NRC Requirements & Armed Escorts Will Be Provided ML20078B6241994-10-0707 October 1994 Forwards Ri Nuclear Science Ctr Proposed 3 MW or Higher ECCS Plan ML20072M6941994-08-24024 August 1994 Forwards Change to Physical Security Plan,Per 10CFR50.54(p)(2).Encl Withheld ML20072S2751994-08-24024 August 1994 Proposed That Section 3.7.1 of TS Be Changed as Listed, Concerning Rev of TS to More Clearly Define Allowed Reactor Operation W/O Particulate or Gaseous Stack Effluent Monitor in Svc ML19346J0111994-08-24024 August 1994 Informs That Annual Rept for 1993-1994 Would Be Administrative Burden than Technical Value.Full Rept Will Be Submitted for 1994-1995 ML20071G1801994-07-0505 July 1994 Notifies That Ef Spring Retired as Employee of Riaec & No Longer Has Need to Maintain Operators License at Facility Effective 940628.Spring RO License OP-2365-11 Should Be Expired,Per 10CFR50.74(b) ML20069H4681994-06-0101 June 1994 Forwards Rhode Island Nuclear Science Ctr Proposed 3 MW or Higher Emergency Core Cooling Sys Plan ML20069J6041994-05-17017 May 1994 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-193/94-01.Corrective Actions:Revision of Procedures & Radiation Safety Guide Has Started Which Would Be Completed by 940731 Rather than 940701 Due to Delays ML20070N7331994-04-13013 April 1994 Informs That 10CFR20 Training Requirements Fulfilled Re New Requirements Issued on 940223 Per Insp Rept 50-193/94-01 ML20063K7901994-02-18018 February 1994 Forwards Preliminary Rept on Ri Nuclear Science Ctr Conversion from HEU to LEU Fuel ML20063G0961994-01-31031 January 1994 Forwards Rev 1 to Tech Specs,Including Revs Resulting from Review Process to Date ML20058G8291993-12-0303 December 1993 Submits Change to Ri Atomic Energy Commission Physical Security Plan.Change Withheld ML20058A6551993-11-17017 November 1993 Forwards Revised Copy of Proposed TSs for License R-95, Incorporating Questions Received from NRC to Date ML20056H3101993-09-0202 September 1993 Forwards Revised Emergency Plan,Reflecting Comments from Recent NRC Region I Review of Plan.Copy of Old Plan Also Encl ML20127H2611993-01-13013 January 1993 Forwards Revised Pages to Sar,Rev 1,addressing Issues Discussed in 930131 Telcon Re Amended Facility License,Leu Reactor Startup Plan,Reactor Core & Control Elements,Safety Sys Settings & Beryllium Lifetime ML20126F4461992-12-22022 December 1992 Forwards Rev 1 to SAR for Low Enriched Fuel Conversion of Ri Nuclear Science Ctr Research Reactor, Incorporating Questions Forwarded by NRC 920914 & 1102 Ltrs & Original & Revised Tech Specs,Per ANSI N378-1974 ML20116L3711992-11-0202 November 1992 Advises That Listed Multiple Choice Question B 016 from 921027 Initial/Requalification Exam Had Two Possible Answers.All Other Questions/Answers Resolved Satisfactorily at Exit Meeting ML20099A6181992-07-23023 July 1992 Forwards Rev 1 to SAR for Low Enriched Fuel of Rhode Island Nuclear Science Ctr Research Reactor, Per Telcon W/M Mendonca.Rev Updates Analysis of LOCA to Reflect Beamport Operational & Design Considerations ML20101U1911992-07-17017 July 1992 Forwards SAR for Low Enriched Fuel Conversion of Rhode Island Nuclear Science Ctr Research Reactor ML20091Q3981992-01-23023 January 1992 Forwards Executed Amendment to Indemnity Agreement E-25 & 14 ML19337F4991992-01-22022 January 1992 Forwards Rev to Physical Security Plan.Rev Withheld ML20091K9801992-01-22022 January 1992 Responds to NRC Re Violations Noted in Insp Rept of License R-95.Corrective Actions:Security Plan Rev Submitted for Review ML20086E4051991-11-18018 November 1991 Forwards Safety Analysis Rept for Low Enriched Fuel Conversion of Ri Nuclear Science Ctr Research Reactor ML20086D2051991-11-18018 November 1991 Forwards SAR for Low Enriched Fuel Conversion of Rhode Island Nuclear Science Ctr Research Reactor ML20067B2931991-01-23023 January 1991 Confirms 910116 Telcon Rept Re Complete Loss of Telephone Svcs,Including Both Voice & Burglar/Supervisory Alarm Sys. Caused by Telephone Lines Cut Through While Installing Phone Poles.Contact Verified Using two-way Radios ML20066C2801990-12-26026 December 1990 Advises That SAR Re Conversion of Reactor from High to Low Enriched U Fuel Will Be Submitted by 910401.Employee Retirement Incentive Programs Resulted in Retirement of Assistant Director for Reactor Operations ML20055H1281990-07-17017 July 1990 Submits Financial Info in Response to Decommissioning Rule (10CFR50.75) ML20012D5741990-03-22022 March 1990 Forwards Changes to Physical Security Plan.Encl Withheld ML20245J4271989-02-22022 February 1989 Requests Date for Submittal of SAR for Conversion of Reactor from Use of High Enriched U to Low Enriched U Fuel Extended from 890301 to 890901 ML20195H7901988-06-23023 June 1988 Requests That Date for Submission of Low Enriched U Conversion Application Be Extended to 890306.Extension Required to Do Remaining Work for Selection & Validation of Low Enriched Core for Facility ML20155B9011988-05-19019 May 1988 Responds to NRC Re Violations Noted in Insp Rept 50-193/88-01.Corrective Action:Full Compliance W/Tech Specs Achieved & Calculations Will Be Performed at Least Quarterly ML20151K5291988-04-12012 April 1988 Requests Concurrence in Subj Design Criteria So as Not to Interfere W/Operation of Reactor Facility Exhaust Stack ML20151U6351988-02-25025 February 1988 Provides Description of Servo Regulating Element Contained in Tech Specs,Per 880208 Telcon.During Review of Retyped Specs,Possible Discrepancy in Description Noted ML20237A3251987-12-0808 December 1987 Requests That Expected Date for Submitting Application to Convert from High to Low Enriched U Be Extended from 880104 to 880705,per 870323 Submittal of Proposed Schedule.Delay Due to Difficulties in Converting Re Use of Std Fuel Plate ML20236P9771987-11-0909 November 1987 Responds to NRC Re Amend 15 to License R-95.EPZ Will Not Be Modified During Const & After Completion of Ctr for Atmospheric Chemistry Studies Bldg.Provisions Made to Notify Workers During Const in Event of Emergency ML20236J3611987-08-0303 August 1987 Forwards Revised Emergency Plan for State of Ri Nuclear Science Ctr.Rev Corrects Spelling to Incorporate Name Change for Support Agency & Correct Refs ML20205C9111987-03-23023 March 1987 Submits Info to Meet Requirements of Highly Enriched U-low Enriched U (HEU-LEU) Conversion Rule.Schedule of Completion Dates Encl for After Conversion Approval 1998-10-14 |
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T STATE OF RHODE ISL.AND AND PROVIDENCE PLANTATIONS sfp?+ RHODE ISLAND ATOMIC ENERGY COMMISSION Nuclear Science Center South Ferry Road i Narragansett, R. I. 02882 October 7, 1994 9
Docket No. 50-193 [
Mr. Marvin Mendonca, Senior Project Manager 1
( Non-Power Reactors, Decommissioning and ;
Environmental Project Directorate Division of Reactor Projects - III/IV/V U. S. Nuclear Regulatory Commission ;
Washington, D.C. 20555 ;
Dear Mr. Mendonca-1 Enclosed you will find a copy of.the revised Emergency Core )
Cooling System (ECCS) 'for Facility License No. R-95. To )
reduce the leak rate during a design basis accident of a beam port leak, 1/2 inch orifices are currently being installed in all the beam port vent lines. The resulting leak rate is significantly less than the previous calculations and has resulted in a decision to reduce the l size of.the ECCS and simplify it's operation.-This revision l- incorporates all your comments from the previous design or i l makes the comment no longer applicable. If there are any
! questions, please call me at 401-789-9391.
Sincerely, i i
/ s, b Ds// -
Tdrry ehan :
Dir or J
l TT':cd Enclosure cc: Jim Matos, Argonne National Laboratory e-onpq .
nuuw%a 9410260164 941007 PDR ADOCK 05000193 i P PDR l
l 4'\ r l i _ _ ._ __. - . _ _ _ _ _ _ _ __-. . -
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