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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P7171999-10-26026 October 1999 Informs That Effective 991026,SW Holmes Will Be NRC Inspector for Facility at Dow Chemical Co,Due to Retirement of Previously Assigned Inspector ML20210P9881999-08-10010 August 1999 Forwards Insp Rept 50-264/99-201 on 990712-15.No Violations Noted.Insp Consisted of Selected Exams of Procedures & Representative Records,Interview with Personnel & Observations of Activities in Progress ML20210N3311999-08-0202 August 1999 Forwards Proprietary Details Re Loss of Communication Between Dow Emergency Services & Dow Triga Research Reactor. Details of Facility Security Plan Are Withheld Under Provisions of 10CFR2.790 ML20153B5451998-09-14014 September 1998 Forwards Proposed Modified Emergency Plan,Including Version in Form of Strikethrough Format (Deletions) or Bold Format (Additions) & Explanation for Change & Version Incorporated Into Text of Plan.With One Oversize Drawing ML20151Z4391998-07-27027 July 1998 Informs NRC That Wl Rigot Has Assumed Role of Facility Director of Dow Chemical Co Triga Nuclear Reactor,Replacing SB Butts.Sb Butts Will Replace J Roeck as Level 1 Mgt within Administration as Described in 6.1 of Facility TSs ML20203L1271998-02-26026 February 1998 Forwards Request for Addl Info Re Emergency Plan Submitted on 960708,as Supplemented on 980115.Responses Requested to Be Provided within 30 Days of Date of Ltr ML20203A0561998-02-11011 February 1998 Forwards Amend 8 to License R-108.Amend Increases Amount of Time from 30 to 60 Days That Temporary Radiation Monitor May Be Used in Place of Area Monitor ML20198P7821998-01-15015 January 1998 Forwards Proposed Modified Emergency Plan for Dow Triga Reactor & Responses to NRC ML20198B4181997-12-18018 December 1997 Forwards Insp Rept 50-264/97-201 on 971202-03.No Violations or Deviations Identified.Annual Emergency Plant Drill Acceptable Demonstration of Ability to Respond & to Mitigate Consequences of Reactor Event ML20217P3201997-08-22022 August 1997 Informs That Responsibility for Non-Power Reactor Insp Program Has Been Transferred from Nrr.All Related Repts, Correspondence & Inquires W/Docket Number Specified Should Be Directed to Listed Address ML20210R0971997-08-19019 August 1997 Forwards Amend 7 to License R-108 & Safety Evaluation.Amend Deletes Requirement for Scram Function on Min Reactor Period,Changes Periodic Insp of Reactor Fuel Schedule, & Modifies Facility Organizational Structure ML20141C2931997-06-16016 June 1997 Forwards Response to 970417 Request for Addl Info Re Amend Request for FOL R-108.Encl Includes Changes Proposed for Amend 7 & Explanation for Question Raised in NRC Ltr ML20140E5471997-04-23023 April 1997 Forwards Insp Rept 50-264/97-01 on 970407-11.No Violations Noted ML20135C7251997-02-24024 February 1997 Forwards Response to NRC Request for Addl Info Re Amend Request for Facility Operating License R-108,ltr Dtd 961217.Encl Includes Changes Proposed for Amend 7 & Explanation for Question Raised in Ltr ML20132D2781996-12-17017 December 1996 Forwards Request for Addl Info Re License Triga Research Reactor ML20132D5511996-12-16016 December 1996 Ack Receipt of Ltr Dtd 961030,transmitting Changes to Physical Security Plan for Dow Triga Research Reactor Submitted,Per 10CFR50.54(p) ML20133G3151996-12-0909 December 1996 Informs That Rept Describing Review of Decommissioning Costs Re Dow Triga Research Reactor Will Be Available for NRC Review When on-site Insp Occurs ML20129B5951996-10-0808 October 1996 Forwards Response to RAI Re 960912 Amend Request for License R-108 ML20129H1331996-10-0202 October 1996 Requests Addl Info Re Dow Triga Research Reactor Emergency Plan Submitted on 960708 Before Review Can Be Complete ML20115E6671996-07-0808 July 1996 Forwards Proposed Modified Emergency Plan,Including Strikethrough Format (Deletion) or Bold Format (Additions) Version & Version W/Changes Incorporated in Text ML20113C3661996-06-18018 June 1996 Responds to Request for Addl Info Re Amend Request for FOL R-108 ML20101H6281996-03-18018 March 1996 Forwards Annual Rept for Triga Facility for 1995 ML20087E4011995-08-0707 August 1995 Forwards TSs in Response to RAI Re 950607 Application for Amend to License R-108 ML20078M1371995-02-0808 February 1995 Forwards Response to RAI Re 941221 Application for Amend to License R-108 ML20069J1651994-06-0606 June 1994 Notifies That Cw Kocher Has Retired from Dow Chemical Co Effective 940531,therefore,no Longer Needs Senior Operator License SOP-3922 ML20065B2231994-03-28028 March 1994 Informs That Effective 940322,WL Rigot Has Replaced Cw Kocher as Supervisor for Dow Triga Nuclear Reactor (R-108) ML20057D4511993-09-30030 September 1993 Informs That RA Wolcott Replaced Jj Havel as Chairman of Reactor Operations Committee for Dow Triga Research Reactor ML20072Q9111991-03-14014 March 1991 Advises That Power Level Increase to 300 Kw,Authorized by Amend 5 to License R-108,issued on 890508,implemented. Neutron Detectors Near Reactor Core Moved to Reflect Higher Max Power Level ML20062F7411990-11-19019 November 1990 Forwards Microprocessor-Based I&C Sys for Dow Triga Research Reactor, Containing Mods to 901015 Amend Request for License R-108 ML20058N4841990-08-0101 August 1990 Forwards Insp Rept 50-264/90-01 on 900709-11.No Violations or Deviations Identified ML20055F6901990-07-0101 July 1990 Advises That Vendor Has Not Received Part 55 Svcs from NRC & Requests That 900627 Invoice I1111 Be Corrected ML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E5881990-02-20020 February 1990 Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790) ML20006E9071990-02-16016 February 1990 Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML18094B3291990-02-14014 February 1990 Forwards Printouts Containing RW-859 Nuclear Fuel Data for Period Ending 891231 & Diskettes ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML20011E5571990-02-0808 February 1990 Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821 ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20011E5981990-02-0505 February 1990 Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants ML20006D6611990-01-29029 January 1990 Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted ML20006C6711990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling 1999-08-02
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20210N3311999-08-0202 August 1999 Forwards Proprietary Details Re Loss of Communication Between Dow Emergency Services & Dow Triga Research Reactor. Details of Facility Security Plan Are Withheld Under Provisions of 10CFR2.790 ML20153B5451998-09-14014 September 1998 Forwards Proposed Modified Emergency Plan,Including Version in Form of Strikethrough Format (Deletions) or Bold Format (Additions) & Explanation for Change & Version Incorporated Into Text of Plan.With One Oversize Drawing ML20151Z4391998-07-27027 July 1998 Informs NRC That Wl Rigot Has Assumed Role of Facility Director of Dow Chemical Co Triga Nuclear Reactor,Replacing SB Butts.Sb Butts Will Replace J Roeck as Level 1 Mgt within Administration as Described in 6.1 of Facility TSs ML20198P7821998-01-15015 January 1998 Forwards Proposed Modified Emergency Plan for Dow Triga Reactor & Responses to NRC ML20141C2931997-06-16016 June 1997 Forwards Response to 970417 Request for Addl Info Re Amend Request for FOL R-108.Encl Includes Changes Proposed for Amend 7 & Explanation for Question Raised in NRC Ltr ML20135C7251997-02-24024 February 1997 Forwards Response to NRC Request for Addl Info Re Amend Request for Facility Operating License R-108,ltr Dtd 961217.Encl Includes Changes Proposed for Amend 7 & Explanation for Question Raised in Ltr ML20133G3151996-12-0909 December 1996 Informs That Rept Describing Review of Decommissioning Costs Re Dow Triga Research Reactor Will Be Available for NRC Review When on-site Insp Occurs ML20129B5951996-10-0808 October 1996 Forwards Response to RAI Re 960912 Amend Request for License R-108 ML20115E6671996-07-0808 July 1996 Forwards Proposed Modified Emergency Plan,Including Strikethrough Format (Deletion) or Bold Format (Additions) Version & Version W/Changes Incorporated in Text ML20113C3661996-06-18018 June 1996 Responds to Request for Addl Info Re Amend Request for FOL R-108 ML20101H6281996-03-18018 March 1996 Forwards Annual Rept for Triga Facility for 1995 ML20087E4011995-08-0707 August 1995 Forwards TSs in Response to RAI Re 950607 Application for Amend to License R-108 ML20078M1371995-02-0808 February 1995 Forwards Response to RAI Re 941221 Application for Amend to License R-108 ML20069J1651994-06-0606 June 1994 Notifies That Cw Kocher Has Retired from Dow Chemical Co Effective 940531,therefore,no Longer Needs Senior Operator License SOP-3922 ML20065B2231994-03-28028 March 1994 Informs That Effective 940322,WL Rigot Has Replaced Cw Kocher as Supervisor for Dow Triga Nuclear Reactor (R-108) ML20057D4511993-09-30030 September 1993 Informs That RA Wolcott Replaced Jj Havel as Chairman of Reactor Operations Committee for Dow Triga Research Reactor ML20072Q9111991-03-14014 March 1991 Advises That Power Level Increase to 300 Kw,Authorized by Amend 5 to License R-108,issued on 890508,implemented. Neutron Detectors Near Reactor Core Moved to Reflect Higher Max Power Level ML20062F7411990-11-19019 November 1990 Forwards Microprocessor-Based I&C Sys for Dow Triga Research Reactor, Containing Mods to 901015 Amend Request for License R-108 ML20055F6901990-07-0101 July 1990 Advises That Vendor Has Not Received Part 55 Svcs from NRC & Requests That 900627 Invoice I1111 Be Corrected ML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E5881990-02-20020 February 1990 Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790) ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E9071990-02-16016 February 1990 Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML20011E5571990-02-0808 February 1990 Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821 ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20011E5981990-02-0505 February 1990 Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants ML20011E2521990-01-29029 January 1990 Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790) ML20006D6611990-01-29029 January 1990 Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted ML20006C6711990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes ML18153C0951990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted ML20006D2431990-01-26026 January 1990 Provides Info Re Emergency Response Organization Exercises for Plants.Exercises & Callouts Would Necessitate Activation of Combined Emergency Operations Facility Approx Eight Times Per Yr,W/Some Being Performed off-hours & Unannounced ML18094B2861990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Aggressive Program of Monitoring,Insp & Matl Replacement Initiated in Advance of Generic Ltr 89-13 Issuance ML18153C0871990-01-26026 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures to Be Revised & Familiarization Sessions Will Be Conducted Prior to Each Refueling Outage ML19354E4191990-01-25025 January 1990 Comments Re Issuance of OL Amends & Proposed NSHC Determination Re Transfer of Operational Mgt Control of Plants & Views on anti-trust Issues Re Application for Amend for Plants ML17347B5451990-01-24024 January 1990 Informs of Plans to Apply ASME Code Case N-356 at Plants to Allow Certification Period to Be Extended to 5 Yrs.Rev to Inservice Insp Programs Will Include Use of Code Case ML19354E6711990-01-24024 January 1990 Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 ML19354E4461990-01-22022 January 1990 Forwards Proprietary Rev 1 to DPC-NE-2001, Fuel Mechanical Reload Analysis Methodology for MARK-BW Fuel, Adding Section Re ECCS Analysis Interface Criteria & Making Associated Administrative Changes.Rev Withheld ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20006A8001990-01-19019 January 1990 Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) ML16152A9091990-01-18018 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo 1999-08-02
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20055F6901990-07-0101 July 1990 Advises That Vendor Has Not Received Part 55 Svcs from NRC & Requests That 900627 Invoice I1111 Be Corrected ML19325E9001989-10-19019 October 1989 Forwards Text of Info Communicated to All Util W/ Westinghouse NSSS Design on Pressurizer Safety Valve Set Pressure Deviation Info Request Response ML19327A8441989-10-11011 October 1989 Forwards Pleadings,Motions & Orders Filed in Alchemie Reorganization Action.Alchemie Currently Preparing Reorganization Plan Which Will Serve as Framework for Future Company Business Activities ML19327B2491989-10-0606 October 1989 Forwards Justification for Extension of Applicability of 890807 SER Re Acceptance of BAW-10175, Rod Exchange Methodology Topical Rept. ML19327A8511989-10-0505 October 1989 Forwards Wh Arowood 890907 Ltr & Other Supplemental Info to Replace Info Previously Filed ML20247F4121989-08-31031 August 1989 Advises That Response to Order Modifying Licenses & Order to Show Cause Why Licenses Should Not Be Revoked Will Be Sent. Responses to NRC Three Basic Questions Re Status of Licensee Finances & Rationale for Having License Provided ML20246B1671989-08-0808 August 1989 Forwards Response to 890717 Request for Info Re Filings W/ Us Bankruptcy Court & Financial Capabilities.Ownership of Unclassified Equipment Remains Unchanged ML20247Q5521989-05-24024 May 1989 Notifies That J Smelser Contract Ended,Effective 890517. Mgt of Company by Listed Board of Director Members Will Continue Until New Chief Executive Officer Selected ML20247P8071989-04-0404 April 1989 Forwards Ltr in Which Concerns for Potential Significant Deficiency Under 10CFR21 Expressed ML20247G4991989-03-30030 March 1989 Forwards Proprietary BAW-10175P, Rod Exchange Methodology, Developed for Calculating Parameters While Performing Control Rod Measurements Using Rod Exchange Technique to Be Used at Plants.Rept Withheld (Ref 10CFR2.790) ML19324C3151989-02-20020 February 1989 Informs of Change in Vendor Plans for Inspecting Fuel Rods Containing Fuel Pellets Supplied by Ge.Ultrasonic Insp of Fuel Rods at Oconee 1 Found No Failed Rods in three-cycle, Discharged Fuel Assemblies ML20235M8971989-02-10010 February 1989 Requests Withholding of Proprietary WCAP 12125, Catawba Unit 1 Evaluation for Tube Vibration Induced Fatigue, Per 10CFR2.790 ML20206D6241988-11-11011 November 1988 Forwards Projected Decommission Costs of Centrifuge Machines to Be Transferred to New Facility at Oliver Spring,Tn. Licensee Will Be Able to Offset Total Decommissioning Costs by Setting Aside Annual Decommissioning Cost Plus Reserve ML20205Q6331988-11-0202 November 1988 Forwards Revised Proprietary Pages to BAW-10164P, RELAP5/Mod2-B&W,Advanced Computer Program for LWR LOCA & Non-LOCA Transient Analysis. Cso Film Boiling Correlation Replaced w/Condie-Bengston IV Correlation & Typos Corrected ML20205P9511988-11-0101 November 1988 Forwards Rev 6 to Security Plan for Alchemie Facility 1 - Cpdf,Oak Ridge,Tn & Rev 6 to Security Plan for Alchemie Facility 2 - Oliver Springs,Oliver Springs,Tn. Revs Withheld (Ref 10CFR2.790(d)) ML20195E4291988-10-31031 October 1988 Forwards Numbers 1-5 of Rev 5 to Alchemie Security Plans. Requests Replacement of Pages 23-25 & 35 & Encl Rev Page ML20205N3301988-10-27027 October 1988 Forwards Sketch of Feed Sys,Withdrawal Sys Refrigeration Cart & Typical Withdrawal,Large & Small,Pumping Stations ML20195B6091988-10-21021 October 1988 Forwards Summary of B&W Fuel Co Position Re Small Break LOCA Calculations Contained in Util FSARs for Upcoming Reload Cores Which Will Contain Fuel Mfg by B&W ML20154K3841988-09-12012 September 1988 Forwards Enhanced Facts Re Adequacy of Funding for Decontamination & Decommissioning (D&D) of Facilities. Intends to Establish Funded Reserve for D&D at Completion of Sale of Unclassified Equipment Not Needed for Production ML20154E6451988-08-31031 August 1988 Requests That 880722 & 0812 Ltrs Re Security Sys Components Be Withheld from Public Disclosure (Ref 10CFR2.790(d)) ML20207L7651988-08-30030 August 1988 Requests That Proprietary WCAP 11935, McGuire Unit 2 Evaluation for Tube Vibration Induced Fatigue, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20151H9381988-07-25025 July 1988 Forwards Proprietary BAW-10168P, B&W LOCA Evaluation Model for Recirculating Steam Generator Plants ML20151M9211988-07-20020 July 1988 Responds to 880621 Request for Addl Info Re Enrichment of Naturally Occurring radioisotopes.Te-123 Will Be Enriching Approx 60 G to About 50% ML20151L3321988-07-20020 July 1988 Forwards DOE Ltr Indicating Acceptance of Classified Matter. Licensee Agrees to Remove Any Toxic or Hazardous Matl from Classified Equipment Prior to Transfer to DOE for Disposal ML20151G9761988-07-14014 July 1988 Forwards Rev 2 to Security Plan for Shipment of Classified Matter.Rev Withheld (Ref 10CFR2.790) ML20150F1561988-07-0808 July 1988 Advises of Changes to Alchemie Board of Directors,Per 880618 Annual Stockholders Meeting ML20207C7931988-06-29029 June 1988 Advises That Jj Havel Replaced Mb Gibbs as Chair of Reactor Operations Committee,Effective 880623 ML20155F4441988-05-0404 May 1988 Responds to NRC & Request at 880504 Meeting Describing GE Program to Reconfirm Design Adequacy of Associated Circuits in GE Bwrs.Upon Completion of Phases 1 & 2 of Evaluation of Bwrs,Ge Will Submit Summary by 881104 ML20154C2651988-04-29029 April 1988 Forwards Mods to Suppl Application for Renewal of License R-108,per a Adams Request ML20151F7661988-03-29029 March 1988 Forwards Updated Pages to Proprietary BAW-10171P, REFLOD3B- Model for Multinode Core Reflooding Analysis, Per ECCS Methodology for Facilities Reloads.Mod Removes Henry Quench Temp Criteria & Potential Conflict in Logic.Pages Withheld ML20234C2231987-12-28028 December 1987 Forwards Proprietary BAW-10164P, RELAP5/MOD2-B&W,Advanced Program for LWR LOCA & Non-LOCA Transient Analysis. Rept Describes Computer Code Used to Analyze RCS Behavior During Blowdown Phase of LOCA Transient.Rept Withheld ML20234D1101987-12-14014 December 1987 Forwards Proprietary BAW-10171P, REFLOD3B,Model for Multinode Core Reflooding Analysis. Rept Describes Computer Code That B&W Will Be Using to Analyze RCS Behavior During Refill of LOCA Transient.Rept Withheld ML20237C3611987-11-24024 November 1987 Requests That Proprietary Rev 2 to WCAP-11386, Byron/ Braidwood T-Hot Reduction Final Licensing Rept, Be Withheld (Ref 10CFR2.790(b)(4)) ML20236C0261987-10-22022 October 1987 Forwards Proprietary BAW-10165P, FRAP-T6-B&W:Computer Code for Transient Analysis of LWR Fuel Rods. Rept Describes Computer Code That B&W Will Be Using for Future Transient Analyses of LWR Fuel Rods.Rept Withheld (Ref 10CFR2.790) ML20236B0621987-10-0505 October 1987 Informs That 870925 Audit of Triga Research Reactor Showed Two Tasks Involving Surveillance Required by Tech Specs Not Done Per Scheduled Weekly Checklist for Wk of 870713.Failure to Complete Tasks Did Not Violate Tech Specs LD-87-056, Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request1987-09-18018 September 1987 Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request ML20238A0461987-08-14014 August 1987 Forwards Supplementary Info Re Renewal of License R-108 for Dow Triga Research Reactor ML20237L4351987-08-14014 August 1987 Forwards Licensed Operator Requalification Program for Facility.Program Reflects Changes Made Following Guidance of Hn Berkow ,Ansi/Ans 15.1-1977 & Changes in 10CFR55 Effective 870526 ML20238A3091987-08-13013 August 1987 Forwards Answers to Questions Posed Following Submittal of May 1987 Formal Answers,Including More Detailed Info Re fire-fighting Equipment in Reactor Room & Nearby Areas & Detailed Analysis of Temp Rise Expected in Fuel Element ML20236H4971987-07-29029 July 1987 Forwards Draft Proprietary Topical Rept BAW-10166P, Beach Computer Code for Reflood Heat Transfer During Loca. Draft Submitted to Permit Interaction Between B&W,Nrc & Util. Affidavit for Withholding Encl.Fee Paid ML20236H1311987-07-28028 July 1987 Forwards Revised Security Plan,Per RA Erickson 870526 Request.Rev Withheld (Ref 10CFR2.790) ML20236B4141987-07-13013 July 1987 Forwards Proprietary Draft 1 of BAW-10168P, ...B&W LOCA Evaluation Model for Recirculating Steam Generator Plants, to Be Used for LOCA Analysis of Catawba & McGuire Reload Fuel Cycles.Rept Withheld (Ref 10CFR2.790).Fee Paid ML20196K1621987-07-0909 July 1987 Partially Deleted Ltr Submitting Addl Info in Response to NRC 861230 & 870211 Requests Re 860918 Application for Exemption from Requirement to Convert from High Enriched U to Low Enriched U for Reactor Fuel,Per Generic Ltr 86-12 ML20215L0591987-06-22022 June 1987 Responds to Request for Assurance That Facility Neutron Monitoring Sys Design Similar to Design of Other Plants.List of Plants W/Similar Design,Already Reviewed & Approved by Nrc,Encl ML20214T0611987-06-0202 June 1987 Forwards ALARA Policy Statement,Revised Requalification Program & Tech Specs & Addl Info in Support of Application for Renewal of License R-108,per a Adams Request ML20215D4081987-05-15015 May 1987 FOIA Request for Reactor Vessel Surveillance Capsule Repts for Turkey Point 4,Zion 2 & DC Cook 1 ML20213G8111987-05-13013 May 1987 Forwards Endorsement 60 to Nelia Policy NF-160 ML20237D2761987-04-27027 April 1987 Forwards List of 200 Parameters That Company Will Provide to Offsite Agencies,Per Request to D Schultz.List of Parameters That Will Be Available to NRC Via Zion Data Link During Coming Federal Field Exercise & Dryrun Also Encl ML20212R4711987-04-15015 April 1987 Forward Proprietary Draft 1 to BAW-10171P, REFLOD3B,Model for Multinode Core Reflooding Analysis, for Review of ECCS Methodology for Plants Fuel Reloads,Per . W/Affidavit.Draft Withheld (Ref 10CFR2.790).Fee Paid LD-87-017, Responds to 870327 Questions Re Steam Generator Tube Vibration Observed at Palo Verde Units 1 & 2.Definition & Scope of Program to Review Phenomenon Will Be Available for Review W/Nrc in Approx 90 Days1987-04-10010 April 1987 Responds to 870327 Questions Re Steam Generator Tube Vibration Observed at Palo Verde Units 1 & 2.Definition & Scope of Program to Review Phenomenon Will Be Available for Review W/Nrc in Approx 90 Days 1990-07-01
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Text
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DOW CHEMICAL U.S.A. ,
February 22, 1980 2DuND. WCHIGAN 6 US Nuclear Regulatory Comission Operating Reactors Branch #4 .
Division of Operating Reactors Washington, DC 20555
Dear Sirs:
DOCKET No 50-264, LICENSE R-108 This letter is to inform you of recent personnel changes regarding the operation of the Dow TRIGA research reactor, license R-108. Several members of the Reactor Operations Comittee (ROC) have moved to dif-ferent positions and were replaced. Harold Gill has been replaced by Jim Macki as Chairman of the Reactor Operations Comittee. Samuel Norwood has been replaced by Tracy Parsons as Health Physicist and Phil North has been replaced by Joan Simpson as a Senior Reactor Operator.
Sincerely, j'
'th" W Ralph R. Langner, Chairman
,bh Radiation Safety Comittee 1603 Building 517/636 4344 bjd ,
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MAY 7 980 Docket No. 50-264 Dow Chemical U.S.A. .
ATTN: Dr. R. R. Langner, Chairman Radiation Safety Committee Building 1603 Midland, Michigan 48640 Gentlemen:
Enclosed is IE Information Notice No. 80-19, "NIOSH Recall of Recirculat-ing-Mode Closed-Circuit) Self-Contained Breathing Apparatus (Rebreather),"
which addresses the NIOSH "stop-sales-and-recall" order to the manufac-turers of the BioPak 60P rebreather respirator. Should you have any questions related to the enclosed authorization or guidance, please con-tact this office.
Sincerely, James G. Keppler s Director
Enclosure:
IE Information Notice No. 80-19 cc w/ enc 1:
Central Files Director, NRR/DPM s Director, NRR/ DOR PDR NSIC TIf RII RIII haan/jp M
Keppler
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SSINS: 6870 Accession No.:
UNITED STATES 9000999999 %k ,
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 -
May 6, 1980 IE Information No. 80-19 NIOSH RECALL OF RECIRCULATING-MODE (CLOSED CIRCUIT) SELF-CONTAINED BREATHING APPARA1U5 (REBREATHER)
The NRC has been informed by the National Institute for Occupational Safety and Health (NIOSH), the agency that tests and certifies respirators, that some of the NIOSH-certified respiratory protective equipment that NRC licensees use might have been modified by the manufacturer without approval by NIOSH. NIOSH considers such modified equipment not to be certified, even though it might bear their test and certifification label.
The equipment in question is the BioPak 30P and 60P, NIOSH test-and-certifica-tion numbers TC-13f-84 and TC-13F-85, respectively. The BioPak 30P and 60P are respectively 30-minute and 60-minute, closed-circuit, recirculating-mode, self-contained breathing apparatuses (rebreathers), manufactured by BioMarine Industries, Inc. Our information leads us to believe that NRC licensees have purchased only the 60P equipment.
NIOSH has issued a "stop-sales-and-recall" order to the manufacturer for this equipment. Licensees who have such equipment should che.ck with the manufacturer to determine what action to take to assure that their equipment is in certified status.
The manufacturer's address and telephone number are:
BioMarine Industries Inc.
45 Great Valley Corporate Center Malvern, PA 19355 Tel: (215) 647-7200
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N IE Information Notice No. 80-19 Enclosure May 6, 1980 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued To Notice No. Issued 80-18 Possible Weapons Smuggling 5/5/80 All power reactor Pouch facilities with an OL, fuel fabrication and processing facilities and Materials Priority I licensees (processors and distributors) 80-17 Potential Hazards Associated 5/5/80 All radiography With Interchangable Parts Licenses On Radiographic Equipment 80-16 Shaft Seal Packing 4/29/80 All power reactor Causes Binding In Main facilities in your Steam Swing Check And Region with an OL or CP Isolation Valves 80-15 Axial (Longitudinal) 4/21/80 All Light Water Reactor Oriented Cracking In Facilities holding power Piping reactor OLs or cps 80-14 Safety Suggestions From 4/2/80 All power reactor Employees facilities with an OL or CP 80-13 General Electric Type SBM 4/2/80 All light water reactor Control Switches - Defective facilities holding power Cam Followers reactor OLs or cps 80-12 Instrument Failure Causes 3/31/80 All holders of power Opening of PORV and Block reactor OLs and cps Valve 80-11 General Problems with ASCO 3/14/80 All holders of Reactor Valves in Nuclear Application OL, CP, fuel fabrica-Including Fire Protection tion and processing Systems facilities 80-10 Partial Loss of Non-Nuclear 3/7/80 All power reactor Instrument System Power facilities holding Supply During Operation OLs and cps 80-09 Possible Occupational 3/7/80 All holders of Health Hazard Associated power reactor OLs with Closed Cooling Systems and near term cps
.8. Pe"w We FJUN 2 4 $80 Docket Nc.59-264 Dow Chemical U.S.A.
ATTN: Dr. R. R. Langner Radiation Safety Committee 1603 Building Midland, MI 48640 Gentlemen:
The enclosed IE Circular No. 80-14 is forwarded to you for information.
If there are any questions related to your understanding of the suggested actions, please contact this office.
Sincerely, James G. Keppler Director
Enclosure:
IE Circular No. 80-14 cc w/ encl:
Central Files Director, NRR/DPM Director, NRR/ DOR PDR NSIC.
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SGEESM&Me NUCLEAR REGULATORY COMMISSION @ns OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C. 20555 June 24, 1980 IE Circular No. 80-14 RADI0 ACTIVE CONTAMINATION OF PLANT DEMINERALIZED WATER SYSTEM AND RESULTANT INTERNAL CONTAMINATION OF PERSONNEL This circular describes an event which occurred at a nuclear power facility; however, the generic implications may be applicable to research reactors, and fuel cycle facilities.
On March 17, 1980, a licensee informed the NRC resident inspector that portions of the plant demineralized water (DW) system were found to be radioactively contaminated. A temporary hose used to add demineralized water to the spent fuel pool was the pathway for the cross-contamination. After this fuel pool makeup was completed on March 14, the temporary DW line (still connected to the DW header) was inadvertently left submerged in the fuel pool. Since the DW header pressure at the point of supply was relatively low (a DW booster pump had been secured), a siphoning action occurred, resulting in radioactive contamination of portions of the DW header.
On March 17, 1980, while performing routine secondary system chemical analyses, thelicenseediscoveredthatthedcaineralizedwatertapin_ghechemistrylab contained high levels of boron and had activity of 1.5 x 10 uCi/ml (mainly Cs-134, Cs-137, Co-58, Co-60 and Mn-54). It was subsequently discovered that demineralized water from the chemistry laboratory supply tap had been used to make five (5) pots of coffee. The remaining coffee was confiscated and the twenty-three (23) individuals who had consumed this coffee were whole-body counted. All involved individuals showed no intake greater than an equivalent 0.01 MPC-HRS. Analysis performed by the licensee's radiation consultant, based on the maximum concentration of radioactivity found in the coffee, indicated that the resultant 50 year dose commitment to an individual drinking eight ounces of this coffee would be less than 1 millirem.
Further licensee investigation revealed that the non-radiological chemistry DW l
f supply tap was the only DW supply point outside the Auxiliary Building l controlled area. This DW supply tap was tagged prohibiting human consumption j to prevent a similar event in the future.
It is recommended that you review your facilities use of demineralized water (DW) via temporary connections and give attention to the following:
- 1. Provisions should be made to assure that radioactive materials are not i inadvertently introduced into your facility's DW system via the improper use of temporary connections. A temporary cross connection between contaminated systems and the DW system without adequate physical controls to prevent cross-contamination should be prohibited.
l ObhN 3 .-
IE Circular No. 80-14 June 24, 1980 Page 2 of 2
- 2. In addition to some physical means of prever, ting backflow into the DW system, appropriate administrative controls should be established to ensure that the DW supply valve is secured and temporary hosing is disconnected from the DW supply header after use.
- 3. Use of plant-supplied DW for human consumption should be prohibited.
The potable water system should be the only authorized source of water for human consumption.
- 4. Examine potable and demineralized water systems to determine if pathways exist allowing or having the potential to allow contamination of these systems including temporary connections whereby siphons could cause situations described above.
No written response to this Circular is required. Your review of this matter to determine its applicability to your facility and any corrective and preven-tive actions taken or planned, as appropriate, will be reviewed during a subsequent NRC inspection. If you desire additional information regarding this matter, contact the Director of the appropriate NRC Regional Office.
IE Circular No. 80-14 Enclosure June 24, 1980 RECENTLY ISSUED IE CIRCULARS Circular Subject Date of Issued to No. Issue 80-13 Grid Strap Damage in 5/18/80 All holders of Reactor Westinghouse Fuel Assemblies OLs and cps 80-12 Valve-Shaft-To-Actuator Key 5/14/80 All holders of Reactor May Fall Out of Place When OLs and cps Mounted Below Horizontal Axis 80-11 Emergency Diesel Generator 5/13/80 All holders of a power Lube Oil Cooler Failures reactor OL or CP 80-10 Failure to Maintain 4/29/80 All holders of Reactor Environmental Qualification OLs and cps of Equipment 80-09 Problems With Plant Internal 4/28/80 All holders of a power Communications Systems reactor OL or CP 80-08 BWR Technical Specification 4/18/80 All General Electric Inconsistency - RPS Response BWR's holding a power Time reactor OL 80-07 Problems with HPCI Turbine 4/3/80 All holders of a power Oil System reactor OL or CP 80-06 Control and Accountability 4/14/80 Medical licensees in Systems for Implant Therapy Categories G and G1 Sources 80-05 Emergency Diesel-Generator 4/1/80 All holders of a power Lubricating Oil Addition and reactor OL or CP Onsite Supply 80-04 Securing of Threaded Locking 3/14/80 All holders of a power Devices on Safety-Related reactor OL or CP Equipment 80-03 Protection from Toxic Gas 3/6/80 All holders of a Hazards power reactor OL 80-02 Nuclear Power Plant Staff 2/1/80 All holders of Reactor Work Hours OLs, including research and test reactors, and cps
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o UNITED STATES NUCLEAR REGULATORY COMMISSION l
i y .E REGION lli 1 0 # 799 ROOSEVELT ROAD o GLEN ELLYN, ILLINOIS 60137 February 9, 1981 Gentlemen:
The enclosed IE Circular No. 81-02 is forwarded for your information.
A copy of this circular is also being mailed directly to each licensed reactor operator and senior reactor operator. No written response is required. If there are any questions related to your understanding of the recommended actions, please contact this office.
Sincerely,
- SY James G. Keppler Director
Enclosure:
IE Circular No. 81-02
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Docket No. 50-264 hI-C@
Dow Chemical U.S.A. , .
ATTN: Dr. L. W. Rampy, Chairman ,
Radiation Safety Committee 1803 Building Midland, MI 48640 cc w/ encl: -
Dr. 0. V. Anders Reactor Supervisor Mr. J. M. Macki, Chairman TRIGA Reactor Operations Committee Central Files AD/ Licensing AD/ Operating Reactors PDR ,
NSIC TIC 4
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SSINS No.: 6830 Accession No.:
IEC 81-02 8809ff9f9F" h{
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT i WASHINGTON, D.C. 20555 February 9, 1981 IE Circular No. 81-02: PERFORMANCE OF NRC-LICENSED INDIVIDUALS WHILE ON DUTY Description of Circumstances:
Recently, an NRC inspector observed two licensed reactor operators who I
appeared to be asleep while on duty in the control room. A subsequent NRC l investigation into the matter concluded that the operators were not fully
! attentive to their licensed duties of monitoring reactor conditions, which is a serious matter of safety significance. Furthermore, the investigation l concluded _that management controls were inadequate to assure the alertness of licensed operators while on duty. Enforcement action was taken after it was determined that attentive operators were not present at the controls as required by 10 CFR 50.54(k).
l Discussion:
NRC believes that a relationship exists between the professional attitude of a nuclear plant's operating and management personnel and the degree to which the health and safety of the public is protected. NRC believes that professional attitude is reflected in high standards of performance including pride in the facility as demonstrated by the nuclear power plant staff.
Factors making up this professional attitude include knowledge of all aspects of plant status by licensed control room operators, maintaining an orderly and clean working environment, aggressiveness of the operating staff to prevent operational problems, and correcting observed deficiencies. NRC believes that clarification of its position on this subject is necessary because several recent events involving licensed operators indicate a lack of a professional attitude at some nuclear power plants.
The following conditions and practices are among those the NRC believes to be necessary for the maintenance of a professional atmosphere in the control room and throughout the facility.
- 1. All on-duty NRC-licensed operators and operating supervisors must be aware of and responsible for the plant status at all times. This includes supervisors being responsible for the performance of all personnel assigned to their shift who could affect plant safety, regardless of specialty affiliation. Knowledge of the plant's status must be assured during shift changes by a formal watch turnover and relief.
Attachment:
< Racantiv issued IE circulars r'p"' b ,
IEC 81-02 February 9, 1981 Page 2 of 3
- 2. All on-duty NRC-licensed operators must be alert, remain within their immediate areas of responsibility until properly relieved, and be particularly attentive to the instrumentation and controls located within these areas at all times.
- 3. Potentially distracting activities in the control room and other watch stations must be prohibited (for example: radios, TV, alcohol use or drug abuse, games, horseplay, hobbies, and reading that is not directly job related).
- 4. Control room access must be limited to those persons on official business only and loitering in this area must be prohibited.
- 5. All necessary plant-related technical / administrative control room business must be conducted at a location and in such a manner that neither licensed control room operator attentiveness nor the professional atmosphere will be compromised. This includes activities associated with the use of special eating and training facilities for on-shift personnel.
Additional Information:
NRC inspectors will be particularly mindful of those conditions and practices described above during future inspections of licensed nuclear facilities.
l For more specific information, you are referred to the following NRC documents:
- 1. 10 CFR 50, " Domestic Licensing of Production and Utilization Facilities,"
Paragraph 50.54
- 2. 10 CFR 55, " Operators' Licenses," Paragraph 55.31 and 55.40
- 3. Regulatory Guide 1.114, " Guidance on Being Operator at the Controls of a Nuclear Power Plant"
- 4. IE Information Notice 79-20, Revision 1, "NRC Enforcement Policy -
NRC-Licensed Individuals"
- 5. Letter from D. G. Eisenhut, NRC, to All Licensees and Applicants, dated July 31, 1980,
Subject:
Interim Criteria for Shift Staffing The following excerpts are taken from some of these documents and are provided for your information:
- 1. Only licensed operators are permitted to manipulate the controls that directly affect the reactivity or power level of a reactor
[10 CFR 50.54(i)].
- 2. Licensed operators are required to be present at the controls at all times during the operation of the facility [10 CFR 50.54(k)].
- 3. Operation of mechanisms and apparatus other than controls that may indirectly affect the power level or reactivity of a reactor shall only be accomplished with the knowledge and consent of an operator licensed in accordance with Part 55 [10 CFR 50.54(j)].
l
IEC 81-02 February 9, 1981 Page 3 of 3
- 4. The NRC-licensed individual shall observe all applicable rules, regulations and orders of the Commission, whether or not stated in the license [10 CFR 55.31(d)].
- 5. The operating test, to the extent applicable to the facility, requires the applicant to demonstrate an understanding of:
The necessity for a careful approach to the responsibility associated with the safe operation of the facility
[10 CFR 55.23(1)].
- 6. In order for the operator at the controls of a nuclear power plant to be able to carry out these and other responsibilities in a timely fashion, he must give his attention to the condition of the plant at all times. He must be alert to ensure that the plant is operating safely and must be capable of taking action to prevent any progress toward a condition that might be unsafe (Regulatory Guide 1.114.B).
NRC policy regarding responsibility for safe operation of NRC-licensed facilities as stated in IE Information Notice 79-20, Revision 1, continues to be as follows:
- 1. "The facility licensee is responsible for assuring that the facility is operated safely and within the requirements of the license, technical specifications, rules, regulations, and Orders of the NRC, and for the actions of their on-duty employees while on site."
- 2. "NRC-licensed individuals are responsible for taking timely and proper actions that will not create or cause a hazard to ' safe operation of the facility' (i.e., actions or activities, including failure to take action, related to the facility that could have an adverse effect on the health and safety of the public, plant workers, or the individuals)."
Recommended Action for Licensee's Consideration:
Each power reactor licensee should review and revise, as necessary, their administrative controls regarding operator performance to ensure the guidance contained or referenced herein is incorporated. These administrative controls should prescribe performance requirements for licensed personnel and specify types of activities that are prohibited while licensed personnel are on duty.
These' administrative controls should be considered for applicability to other plant personnel whose actions, while on duty, may affect plant safety or the orderly conduct of facility operation. Licensees should assure dissemination of these administrative requirements to affected personnel.* It is also requested that licensees have their licensed personnel review this Circular and IE Information Notice 79-20, Revision 1, as well as Regulatory Guide 1.114.
No written response to this Circular is required. If you require additional information regarding this matter, contact the Director of the appropriate NRC Regional Office.
"A copy of this Circular was mailed directly to each licensed reactor operator and senior reactor operator.
Attachment IEC 81-02 I February 9, 1981 RECENTLY ISSUED IE CIRCULARS Circular Date of No. Subject Issue Issued to 81-01 Design Problems Involving 1/23/81 All power reactor Indicating Pushbutton facilities with Switches Manufactured by an OL or CP Honeywell Incorporated 80-25 Case Histories of 12/5/80 All radiography Radiography Events licensees 80-24 AECL Teletherapy Unit 12/2/80 All teletherapy Malfunction licensees 80-23 Potential Defects in Beloit 10/31/80 All power reactor Power Systems Emergency facilities with Generators OL or a CP 80-22 Confirmation of Employee 10/2/80 All holders of a Qualifications power reactor OL or CP architect-engineering companies and nuclear steam system suppliers
' 80-21 Regulation of Refueling 9/10/80 All holders of a ,
Crews power reactor OL or CP 80-20 Changes in Safe-Slab Tank 8/21/80 All Part 50 and Part Dimensions 70 fuel facility licensees 80-19 Noncompliance with 8/26/80 All medical licensees License Requirements for Medical Licensees 80-18 10 CFR 50.59 Safety 8/22/80 All power reactor Evaluations for Changes to facilities with an Radioactive Waste Treatment OL or CP Systems 80-17 Fuel Pin Damage Due to Water 7/23/80 All holders of PWR Jet from Baffle Plate Corner OLs and PWR cps OL = Operating Licenses CP = Construction Permit I
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