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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 ML20029D9091994-04-29029 April 1994 Ack Receipt of 940413 Response to Insp Rept 50-193/94-01 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 ML20045H4281993-06-30030 June 1993 Provides Info That Has Become Available Since Revised 10CFR20 Became Effective on 910620 & Forwards Two Press Releases Re Issuance & Implementation of Revised Part 20 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 ML20044F1841993-01-28028 January 1993 Forwards Reactor & Senior Reactor Operator License Certificates for Jj Cunningham & Tn Tehan,Respectively,Per Commission Request.W/O Encls 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 1999-04-07
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20155G4431998-10-14014 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 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 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 ML20072M6941994-08-24024 August 1994 Forwards Change to Physical Security Plan,Per 10CFR50.54(p)(2).Encl Withheld 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
[Table view] |
Text
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.9*
TATE OF RHODE ISLAND AND PROVIDENCE PLANTATIONS RHODE ISLAND ATOMIC ENERGY COMMISSION Nuclear Science Center South Ferry Road Narragansett, R.I. 02882-1197 January 12, 1996 i
l l
-Mr. Marvin Mendonca, Senior Project Manager i
Non-Power Reactors, Decommissioning and Environmental Project Directorate i
Division of Reactor Projects - III/IV/V U.
S. Nuclear Regulatory Commission Washington, DC 20555-0001 License R-95 Docket No. 50-193
Dear Mr. Mendonca:
This letter provides answers to your letter of August 3, 1995 concerning a revision of the Rhode Island Nuclear Science Center Technical Specifications to combine the Radiation Safety Committee and the Reactor Utilization Committee into a single committee called the Nuclear and Radiation Safety Committee (NRSC).
Technical specification 6.1 was changed to reflect the new name of the Nuclear Radiation Safety Committee and to indicate two qualified representatives from the faculty of the University of
{
Rhode Island. The purpose for adding these representatives is to provide more direct input from the main user groups of the facility. One member will be chosen from the main campus and one member from the Bay Campus. Vertical change bars have been l
l added in the right margin to reflect this change.
j Figure 6-1 has been revised to reflect the revisions to the l
name and composition of the committees shown on the l
organizational chart.
The Assistant Director for Reactor Operations has been added to the NRSC to provide additional technical expertise to the committee. Additionally, the Assistant Director has been added to the list of personnel not eligible for chairmanship of the committee. Vertical change bars have been added to the right margin to reflect this change.
190023
[id0 9601190119 960112 PDR ADOCK 05000193
\\
p PDR e.
i
i Mr. Marvin.Mendonca, Senior Project Manager 5,
January 12, 1996
+~,Page 2 l
Technical Specifications 6.4.4 and 6.5 have been corrected to remove reference to the previous Utilization Committee. A quorum has been specified to include a majority of the members plus representation from radiation safety, technical staff and i
the chairman. A requirement has been added to retain the minutes of the previous Reactor Utilization Committee for the life of the facility. Vertical change bars have'been added to reflect this change.
i If there are any questions regarding this change, please call me at 401-789-9391.
.)
Sincerel
)
er ehan Dir or TT:cd l
Enclosure (revised pages 53,54,56,58,59,60,61,62,66) cc:
Tom Dragoun, NRC, Region One i
l
TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193, License R-95 Revision 1 6.0 ADMINISTRATIVE CONTROLS 6.1 Organization and Management 1.
The Rhode Island Atomic Energy Commission (RI A EC) shall have the responsibility for the safe operation of the reactor.
The organization of RIAEC is shown in Figure 6-1.
The RIAEC shall appoint a i
Director and a
Nuclear and Radiation Safety Committee (NRSC) consisting of a minimum of seven members, as follows:
a.
The Director, RIAEC b.
The Assistant Director for Reactor Operations l
c.
The Radiation Safety Officer d.
A qualified representative from the faculty of Brown University e.
A qualified representative from the faculty of Providence College f.
Two qualified representatives from the fwlty of the University of Rhode Island A qualified alternate may serve in lieu of one of the above. The Director, Assistant Director and Radiation Safety Officer are not eligible for chairmanship of the Committee.
2.
An operator or senior operator licensed pursuant to 10CFR55 shall be present in the control room unless the reactor is secured as defined in these specifications.
The minimum operating crew shall be a
two individuals.
j l
3.
A licensed senior operator shall be on duty or readily l
I available on call whenever the reactor is in operation.
I i
Page 53 I
l
FIGURE 6.1 Rav: 01/02/96 RINSC Organizational Chart RHODE ISLAND TECHNICALSPECIFICATIONS ATOMIC ENERGY Rhode Island Nuclear Science Cente-mlSSm Docket 50-193, License R-95, i
Revision 1 I
ADMENDMENT21 NUCLEAR A' 40 RADIATION DIRECTOR SAFETY COMMITTEE (NRSC) l CONFIDENTIAL
- - - - - Lino Of Communicatio' STENO SECRETARY i
i e
i i
e b_________
ASST. DIRECTOR FOR REACTOR OPERATIONS i
i e
5 g
I I
y RADIATION OPEPATIONS ENGtEERNG PROTECTION RADIATION FEACTOR FACILITY PROTECTION N
N N
VACANT VACANT i
l PRINCIPAL I
REtCTOR
[
HEALTH OPERATOR 3
auSaST a
e i
l l
Reactm SENIOR CLERK N
ReAcrOR TYPIST OPERATOR /
OPERATOR /
CUSTODIAN STUDENT LAB OPERATOR /
N Electronics H.P. Tech Mec an i PARTTIME PARTTIME
~ -
TECIINICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193, License R-95 Revision 1 being performed in the facility including those of outside agencies.
b.
It shall be the responsibility of the Director to insure that all proposed experiments, design modifications, or changes in operating and emergency procedures are performed in accordance with the license.
Where uncertainty exists, the Director shall refer the decision to the NRSC.
2.
Senior Reactor Operators a.
A licensed senior reactor operator pursuant to 10CFR55 shall be assigned each shift and be responsible _ for all activities during his shift which may affect reactor operation or involve radiation hazards.
The reactor operators on duty shall be responsible directly to the se-nior operator, b.
The identity of and method for rapidly contacting the on-call senior reactor 1
operator shall be known to the reactor operator on duty.
The on-call senior reactor operator must be capable of being contacted by the duty reactor operator within ten minutes.
The senior reactor operator shall be present at the facility during initial startup and approach to power, recovery from an unplanned or unscheduled shutdown or significant reduction in power, and refueling.
The name of the person serving as senior reactor operator as well as the time he assumes the duty shall be entered in the reactor log.
When the senior operator is
- relieved, he shall turn the operation duties over to another licensed senior operator.
Page 56
TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193, License R-95 Revision 1 d.
The
- operator, under the senior reactor operator on duty, shall be responsible for the operation of the reactor according to the approved operating procedures, e.
The operator shall be authorized at any time to reduce the power of the reactor or to scram the reactor without reference to higher authority, when in his judgment such action appears advisable or necessary for the safety of the reactor, related equipment, or personnel.
Any person working on the reactor bridge shall be similarly authorized to scram the reactor' by pressing a scram button located on the bridge.
4.
Radiation ' Safety Officer The Radiation Safety Officer shall be responsible for assuring that adequate radiation monitoring and control are in effect to prevent undue exposure of individuals to radiation.
6.4 Review and Audit 1.
The NRSC shall review reactor operations to assure that the facility is operated in a manner consistent with public safety and within the terms of the facility license.
2.
The responsibilities of the NRSC include, but are not limited to, the following:
a.
Audit of operating, and emergency procedures and records, b.
Review and audit of proposed tests and experiments utilizing the reactor facilities.
Page 58
TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193, License R-95 Revision I c.
Review and audit of proposed changes to the facility systems or equipment, procedures, and operations.
d.
Determination of whether a
proposed change, test, or experiment would constitute an unreviewed safety question which may require a
change to the Technical Specifications or facility license, e.
Review of all violations of the Technical Specifications and Nuclear Regulatory Commission Regulations, and significant violations of internal rules or procedures, with recommendations for corrective action to prevent recurrence, f.
Review of the qualifications and competency of the operating organization to assure retention of staff quality.
g.
Review changes to the NRSC charter.
l
~
h.
Review, at least annually, the radiation safety aspects of the facility.
3.
The NRSC shall have a written charter defining such matters as the authority of the Committee, the subjects within its
- purview, and other such administrative provisions as are required for effective functioning of the Committee.
Minutes of all meetings of the Committee shall be kept.
All minutes of the previous Reactor Utilization Committee shall be retained for the life of the facility.
4.
A quorum of the NRSC shall consist of not less than four (4) members and shall include the Radiation Safety Officer or designee, the Director or the Assistant Director for Operations and the Chairman or designee.
Page 59
TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center o
Docket 50-193, License R-95 Revision 1 5.
The NRSC shall meet at least annually.
l 6.5 Operating Procedures Written procedures, reviewed and approved by the NRSC, j
shall be used for items 1-9 listed below.
The procedures shall be adequate to assure the safe operation of the reactor, but should not preclude the use of independent judgment and action should the situation require such.
1.
Startup, operation and shutdown of the reactor; 2.
Installation and removal of fuel elements, control blades and incore devices 'where necessary; 3
Maintenance procedures which could have an effect on reactor safety; 4.
Periodic surveillance of reactor instrumentation and safety systems, area monitors, and continuous air monitors; i
5.
Implementation of the physical Security Plan and Emergency Plan; 6.
Radiation control procedures; 7.
Receipt, inspection, and storage of new fuel elements; 8.
Storage and shipment of irradiated fuel elements.
9.
Experiment review on a case-by-case basis assuring that section 3.8.3(2) of ANSI /ANS 15.1 is satisfied.
Operational approval shall be by written approval by a licensed senior operator.
Written procedures should be established and supervision of the installation of such experiments shall be defined and exercised.
Page 60
TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193, License R-95 Revision - 1 Substantive changes to the above procedures shall be made only with the approval of the NRSC.
Temporary changes to the procedures that do not change their original intent may be ma_de by a Senior Operator.
Temporary changes to procedures shall be documented and subsequently reviewed by the NRSC Subcommittee.
6.6 Action to be Taken in the Event of a Reportable Occurrence In the event of a reportable occurrence:
1.
The Senior Reactor Operator shall be notified promptly and corrective action shall be taken immediately to place the facility in a safe condition until the cause of the reportable occurrence is determined and corrected.
2.
The Director shall report the occurrence to the NRSC.
The report shall include an analysis of the cause of the occurrence, corrective actions
- taken, and recommendations for appropriate action to prevent or reduce the probability of a
repetition of the occurrence.
3.
The NRSC shall review the report and the corrective actions taken.
4.
Notification shall be made to the NRC in accordance with Paragraph 6.8 of these specifications.
6.7 Action to be Taken in the Event a Safety Limit is Exceeded In the event a Safety Limit has been exceeded:
Page 61
TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193, License R-95 i
Revision 1 1.
The reactor will be shut down and reactor operations I
will not be resumed until authorization is obtained from the NRC.
2.
Immediate notification shall be made to the NRC in accordance with' paragraph 6.8 of these specifications and to the Director.
]
3.
A prompt report shall be prepared by the Senior Reactor Operator.
The report shall include a
complete analysis of the causes of the event and the extent of
.possible damage together with recommendations to prevent or reduce the probability of recurrence.
This report shall be submitted to the NRSC for review and appropriate
- action, and a
suitable similar report shall be submitted to the NRC in accordance with Paragraph 6.8 of these specifications and in support of a request for authorization for resumption of operations.
6.8 Reporting Requirements In addition to the requirements of applicable regulations, all written reports shall be sent to the U.
S. Nuclear Regulatory Commission, Attn:
Document Control Desk, Washington, DC 20555, with a copy to the Region I Administrator.
The written reports include the following:
1.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, a report by telephone through the NRC Operation Center, 301-951-0550 and the NRC Region 1:
a.
Any accidental release of radioactivity to unrestricted areas above permissible limits, whether or not the release resulted in property
- damage, personal inj ury or exposure.
b.
Any significant variation of measured values from a
corresponding predicted or Page 62
TECHNICAL SPECIFICATIONS Rhode Island Nuclear Science Center Docket 50-193, License R-95 o
Revision I g.
Fuel inventories and transfers; and h.
Changes to procedures systems, components, and equipment.
2.
Records to be retained for the life of the facility:
a.
Gaseous and liquid radioactive effluents released to the environs; b.
Off-site environmental monitoring surveys; c.
Personnel radiation exposures; d.
Updated, "as-built" drawings of the facility; and i
e.
Minutes of the NRSC (and previous Reactor Utilization Committee) meetings.
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