|
|
| Line 14: |
Line 14: |
| | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | page count = 3 | | | page count = 3 |
| | | project = TAC:M98904 |
| | | stage = Other |
| }} | | }} |
|
| |
|
| Line 55: |
Line 57: |
| The staff of the U.S. Nuclear Regulatory Commission (NRC) has completed its ! | | The staff of the U.S. Nuclear Regulatory Commission (NRC) has completed its ! |
| review and evaluation of a change to the Rhode Island Atomic Energy Commission ' | | review and evaluation of a change to the Rhode Island Atomic Energy Commission ' |
| Research Reactor Technical Specifications that you proposed in a letter dated June 6, 1997. The enclosed Amendment No. 23 change removes the reactor coolant inlet temperature as a Technical Specification requirement in the Safety Limits and the Limiting Safety System Settings, Section 2.1.1 and 2.2.1 respectively. Also, the amendment adds an existing pool temperature scram in Section 3.2 (Table 3.1), in order to be consistent with Safety Limit of Section 2.2.2. | | Research Reactor Technical Specifications that you proposed in a {{letter dated|date=June 6, 1997|text=letter dated June 6, 1997}}. The enclosed Amendment No. 23 change removes the reactor coolant inlet temperature as a Technical Specification requirement in the Safety Limits and the Limiting Safety System Settings, Section 2.1.1 and 2.2.1 respectively. Also, the amendment adds an existing pool temperature scram in Section 3.2 (Table 3.1), in order to be consistent with Safety Limit of Section 2.2.2. |
| A copy of the Safety Evaluation Report supporting Amendment No. 23 is also enclosed. l If you have any questions, please contact me at 301-415-1102. l l | | A copy of the Safety Evaluation Report supporting Amendment No. 23 is also enclosed. l If you have any questions, please contact me at 301-415-1102. l l |
| Sincerely, j hbN w' Theodore S. Michaels, Senior Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No. 50-193 | | Sincerely, j hbN w' Theodore S. Michaels, Senior Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No. 50-193 |
Letter Sequence Other |
|---|
|
|
MONTHYEARML20140H7241997-06-17017 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
Project stage: Other
ML20217E2851997-09-23023 September 1997
Forwards Amend 24 to License R-95 & Se.Amend Clarifies TS Requirements & Corrects Typographical Errors
Project stage: Approval
ML20199E8141997-11-12012 November 1997
Forwards Amend 25 to License R-95 & Safety Evaluation.Amend Corrects Omission from Previous TS Amend
Project stage: Approval
1997-06-17
[Table View] |
|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H8701999-10-15015 October 1999
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
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
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
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
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217H8701999-10-15015 October 1999
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
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
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
ML20148J8071997-06-11011 June 1997
Forwards Operator Licensing Initial Exam Rept 50-193/OL-97-01 During Wk of 970526
ML20140F8331997-06-11011 June 1997
Forwards Results of 970528 Operator Initial Exam at Rhode Island Aec.W/O Encl
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
ML20058K3591993-12-0808 December 1993
Forwards Insp Rept 50-193/93-04 on 931116-18.No Violations Noted
ML20057C2411993-09-17017 September 1993
Forwards Insp Rept 50-193/93-03 on 930810-18.No Violations Noted
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
ML20062E6991990-11-0909 November 1990
Forwards Insp Rept 50-193/90-01 on 901001.No Violations Noted
IR 05000193/19800011989-09-14014 September 1989
Discusses Insp of License 50-19380-01 on 890814 & 18 & Forwards Notice of Violation.Description of Actions to Improve Effectiveness of Overall Mgt Control Sys Requested
ML20246N9231989-03-22022 March 1989
Notifies of Research & Test Reactor 880418-19 Seminar in King of Prussia,Pa to Be Held by NRR & Region I.Proposed Agenda & Info for Making Accommodations for Seminar Encl
ML20246L9331989-03-16016 March 1989
Approves Univ 890222 Request to Extend Submission Date for High to Low Enriched U Conversion Application from 890301 to 890901
ML20205K5771988-10-20020 October 1988
Forwards Amend 16 to License R-95 & Safety Evaluation.Amend Clarifies Exhaust Sources & Rates Entering Stack of Reactor Bldg
ML20154S3571988-09-28028 September 1988
Forwards Safety Insp Rept 50-193/88-03 on 880826.No Violations Noted
ML20151L0041988-07-27027 July 1988
Forwards Health Physics Insp Rept 50-193/88-02 on 880622-23. No Violations Noted
ML20151B1851988-07-11011 July 1988
Advises That Re Extension to 880306 of Submission on High & low-enriched U Acceptable
ML20151E0801988-07-11011 July 1988
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-193/88-01
ML20154D0531988-05-11011 May 1988
Forwards Insp Rept 50-193/88-01 on 880328-31 & Notice of Violation.Util Encouraged to Carry Effort Through to Improve Tech Spec Clarity & Accuracy by Initiating Changes to Fully Reflect Current Conditions
ML20148S1531988-04-11011 April 1988
Advises That Inclusion of Ctr for Atmospheric Chemistry Studies in Emergency Plan for Reactor Unnecessary Due to Bldg Lying Outside of EPZ Boundary.Safety Evaluation Supporting Licensee 871109 Response Encl
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
ML20149E6601988-01-0404 January 1988
Responds to 871208 Request to Extend Submission Date to 880705 for High to Low Enriched U Conversion Application. Request Acceptable
ML20237C6361987-12-16016 December 1987
Forwards Exam Rept 50-193/87-01OL on 871020-21
ML20245C9611987-10-27027 October 1987
Forwards Amend 15 to License R-95 & Safety Evaluation. Amend Redefines Restricted Area to Include Reactor Bldg & Adjacent Ofc Lab Wing Only & to Exclude 3-acre Area Known as Nuclear Science Ctr
ML20215D0381987-06-11011 June 1987
Informs of Ofc Name Change to Standardization & Non-Power Reactor Project Directorate Due to Recent NRR Reorganization & Assignment of T Michaels as Project Officer
ML20214T8981987-06-0404 June 1987
Forwards Revised Form 398, Personal Qualifications Statement - Licensee. Revised Form Requires New Applicants to Complete Each Category Completely Including All Educ, Training & Experience Received Up to Date of Application
ML20214U7381987-05-27027 May 1987
Informs of Recent Realignment within Region I Div of Reactor Projects & Issuance of Final Rule, Communications Procedures Amends,10CFR50. Rule Changes Way Licensees Submit Written Communication.W/Rule & Region I Chart
ML20212Q9861987-04-20020 April 1987
Ack Receipt of Proposed Schedule for Conversion of Reactor from High Enriched to Low Enriched U,Submitted Per 10CFR50.64(c)(2)(i) Requirements.Notification of TS Michaels of Any Changes or Updates to Schedule Requested
ML20209B2091986-08-21021 August 1986
Forwards Health Physics Insp Rept 50-193/86-03 on 860724.No Violations Noted
ML20203M9171986-04-23023 April 1986
Forwards Insp Rept 50-193/86-02 on 860224-25.No Violation Noted
ML20210G9941986-03-27027 March 1986
Lists Change in Telephone Number for H Bernard,Facility Project Manager,Due to NRR Reorganization.D Tondi New Nonpower Reactors & Safeguards Licensing Section Leader. Correspondence Should Be Sent to Listed Address
ML20140J2621986-03-27027 March 1986
Informs That Effective 860331,TC Elsasser Will Replace EC Mccabe as Cognizant Section Chief for Facility Due to Realignment of Projects within Region I
ML20199F4341986-03-20020 March 1986
Discusses Recent Event at Research Reactor Re Licensee Unauthorized Transportation of Licensed Matl on 860127 W/O Proper License.Nrc Approved QA Program for Radiation Matl Packages Expired on 851231
ML20154A2011986-02-26026 February 1986
Forwards Insp Rept 50-193/86-01 on 860127.No Violation Noted
ML20138N0871985-12-17017 December 1985
Discusses NRC 850927 Order to Show Cause Why All Excess High Enriched U Fuel Should Not Be Removed to Secure Facility Away from Reactor Site.Consent to Order Understood, Since Hearing Not Requested,Nor Order Contested
IR 05000193/19850021985-11-29029 November 1985
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-193/85-02
ML20137M2161985-09-0606 September 1985
Forwards Insp Rept 50-193/85-03 on 850701 & 02.No Violations Observed
ML20134F3201985-08-12012 August 1985
Forwards Insp Rept 50-193/85-02 on 850611-12 & Notice of Violation
ML20126L8751985-06-0505 June 1985
Forwards Exam Rept 50-193/85-01 of Exam Administered During Wk of 850422
ML20126A6141985-06-0404 June 1985
Forwards Sanitized Spent Nuclear Fuel Route from Rhode Island Nuclear Science Ctr to Savannah River,Sc Per 850510 Request for Approval.Notification Requirements Still Apply Per 10CFR73.37 & 73.72
1999-04-07
[Table view] |
Text
- . . _ . - . - - . .
June 17, 1997 Mr. Terrance Yehan, Director Nuclear Science Center Rhode Island Atomic Energy Commission South Ferry Road Narrangansett, Rhode Island 02882
SUBJECT:
ISSUANCE OF AMENDMENT NO. 23 FOR FACILITY LICENSE N0. R-95 RHODE ISLAND ATOMIC ENERGY COMMISSION RESEARCH REACTOR (TAC NO. M98904)
Dear Mr. Tehan:
The staff of the U.S. Nuclear Regulatory Commission (NRC) has completed its review and evaluation of a change to the Rhode Island Atomic Energy Commission .
Research Reactor Technical Specifications that you proposed in a letter dated '
June 6, 1997. The enclosed Amendment No. 23 change removes the reactor i coolant inlet temperature as a Technical Specification requirement in the Safety Limits and the Limiting Safety System Settings, Section 2.1.1 and 2.2.1 respectively. Also, the amendment adds an existing pool temperature scram in :
Section 3.2 (Table 3.1), in order to be consistent with Safety Limit of -
Section 2.2.2.
A copy of the Safety Evaluation Report supporting Amendment No. 23 is also enclosed.
If you have any questions, please contact me at 301-415-1102.
Sincerely, Original signed by: l Theodore S. Michaels, Senior Project Manager i Non-Power Reactors and Decommissioning '
Project Directorate Division of Reactor Program Management Office of Oclear Reactor Regulation 7[/j i
Docket No. 50-193 j
Enclosures:
- 1. Amendment No. 23
- 2. Safety Evaluation '
cc w/ enclosures:
See next page DISTRIBUTION: . ..
Docket File 50-193' MSlosson OGC (015-B-18) GHill (2)(T-5C-3)
PUBLIC SWeiss TMichaels TDragoun PDND r/f EHylton Region I AAdams MMendonca WEresian PDoyle Plsaac PDND:PM h :!AJ OG PDND:(A)D TMichae s ton A/) - MMendonca 6//J/97 6/fj/97 v 6/jf/97 6/g/97 0FFICIAL RECORD COPY DOCUMENT NAME: A:\ AMEND 23 Dohk N000 93 gcIn CENTER COPY P PDR
5 I puo p & UNITED STATES j j NUCLEAR REGULATORY COMMISSION
\ . . . . . ,o/ June 17, 1997 Mr. Terrance Tehan, Director Nuclear Science Center ;
Rhode Island Atomic Energy Commission South Ferry Road Narrangansett, Rhode Island 02882
SUBJECT:
ISSUANCE OF AMENDMENT NO. 23 FOR FACILITY LICENSE NO. R-95 RH0DE ISLAND ATOMIC ENERGY COMMISSION RESEARCH REACTOR (TAC N0. M98904)
Dear Mr. Tehan:
The staff of the U.S. Nuclear Regulatory Commission (NRC) has completed its !
review and evaluation of a change to the Rhode Island Atomic Energy Commission '
Research Reactor Technical Specifications that you proposed in a letter dated June 6, 1997. The enclosed Amendment No. 23 change removes the reactor coolant inlet temperature as a Technical Specification requirement in the Safety Limits and the Limiting Safety System Settings, Section 2.1.1 and 2.2.1 respectively. Also, the amendment adds an existing pool temperature scram in Section 3.2 (Table 3.1), in order to be consistent with Safety Limit of Section 2.2.2.
A copy of the Safety Evaluation Report supporting Amendment No. 23 is also enclosed. l If you have any questions, please contact me at 301-415-1102. l l
Sincerely, j hbN w' Theodore S. Michaels, Senior Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No. 50-193
Enclosures:
- 1. Amendment No. 23 ;
- 2. Safety Evaluation '
cc w/ enclosures:
See next page
. . . ,,. . . . . _ . . . . . _ . _ . . . - - . _ - - - . - . - . . - . - . - . - = . . . . . . . _ - - - . - _ . . . .
t
. Rhrde Island Atomic Energy Commission Docket No. 50-193 i
cc: {
President, Town Council !
Town of Narragansett Town Hall i Narragansett, Rhode Island 02882 Governor of Rhode Island Providence, Rhode Island 02903 e
I-4 i
l l
l 1
i l
\
l 1
i l I
I l l l
? . - . . - _.