ML20085D095
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| ML20085D095 | |
| Person / Time | |
|---|---|
| Site: | Robinson, 05000000 |
| Issue date: | 08/07/1973 |
| From: | Utley E CAROLINA POWER & LIGHT CO. |
| To: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20085D093 | List: |
| References | |
| REF-SSINS-6820 IEB-73-02, IEB-73-2, NG-73-260, NUDOCS 8307200387 | |
| Download: ML20085D095 (3) | |
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20211G9851999-08-26026 August 1999
[Table view]Ltr Contract:Task Order 244 Entitled, Technical Assistance in Evaluating Proposed Increase in Allowed Ultimate Heat Sink Temperature of Hb Robinson,Unit 2, Under NRC-03-95-026 ML20206Q5281999-05-17017 May 1999 Responds to 990304 Request for Two Rail Routes to Be Used for Transport of Spent Fuel from Brunswick Steam Electric Plant,Southport,Nc & Hb Robinson Steam Electric Plant, Hartsville,Sc to Shearon Harris Npp,Near New Hill,Sc RA-99-0071, Forwards Rev 7 to Training & Qualification Plan & Rev 1 to Physical Security & Safeguards Contingency Plan for HBR2,per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld1999-04-0101 April 1999 Forwards Rev 7 to Training & Qualification Plan & Rev 1 to Physical Security & Safeguards Contingency Plan for HBR2,per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld ML20210J5761999-03-0404 March 1999 Requests Route re-approval for Rail Transportation Routes, Previously Approved by NRC by Ltr .Two Routes Requested to Be Reapproved,Rail Route 130 & 135.Util Requests That NRC Renew Route Approvals by 990416 RA-99-0011, Requests Change to HBR2 Physical Security & Safeguards Contingency Plan,Per 10CFR50.90.Change Involves Staffing & Location of Plant Security Force as Described in Encl.Encl Withheld1999-01-15015 January 1999 Requests Change to HBR2 Physical Security & Safeguards Contingency Plan,Per 10CFR50.90.Change Involves Staffing & Location of Plant Security Force as Described in Encl.Encl Withheld RA-98-0153, Transmits Description of Rev 0 to Physical Security & Safeguards Contingency Plan, Which Contains Plant Industrial Security Plan & Safeguards Contingency Plan,Per 10CFR72.44(e)1998-08-27027 August 1998 Transmits Description of Rev 0 to Physical Security & Safeguards Contingency Plan, Which Contains Plant Industrial Security Plan & Safeguards Contingency Plan,Per 10CFR72.44(e) RA-98-0136, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan, for Hb Robinson Steam Electric Plant,Iaw 10CFR50.54(p)(2) & 50.4(b)(4).Summary of Changes Contained in Attachment 1.Plan Withheld,Per 10CFR73.211998-07-17017 July 1998 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan, for Hb Robinson Steam Electric Plant,Iaw 10CFR50.54(p)(2) & 50.4(b)(4).Summary of Changes Contained in Attachment 1.Plan Withheld,Per 10CFR73.21 ML20236J9871998-06-24024 June 1998 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Entirety RA-98-0115, Forwards Rev 36 to Industrial Security Plan for Unit 2.Rev Withheld,Per 10CFR73.211998-06-18018 June 1998 Forwards Rev 36 to Industrial Security Plan for Unit 2.Rev Withheld,Per 10CFR73.21 ML20217P4601998-05-0101 May 1998 Forwards ERDS Implementation Documents Including Data Point Library Updates for Robinson (Number 248),Peach Bottom (Number 249),Surry (Number 250),Crystal River (Number 251), McGuire (Numbers 252 & 254) & Salem (Number 253).W/o Encl ML20212H2391998-03-24024 March 1998 Forwards Insp Rept 50-261/98-04 on 980223-25.No Violations Noted.Physical Security Program for Power Reactors Was Inspected RA-98-0020, Forwards Rev 35 to Industrial Security Plan for Rsep,Unit 2. Rev Incorporates Changes Associated W/Physical Mods Involved W/Implementation of Enhanced Defensive Strategy & Incorporates Addl Level of Descriptive Detail.Encl Withheld1998-02-26026 February 1998 Forwards Rev 35 to Industrial Security Plan for Rsep,Unit 2. Rev Incorporates Changes Associated W/Physical Mods Involved W/Implementation of Enhanced Defensive Strategy & Incorporates Addl Level of Descriptive Detail.Encl Withheld ML20198S2691998-01-22022 January 1998 Ack Receipt of & Fee in Amount of $55,000 in Payment of Civil Penalty Proposed by NRC in ML20198K6631998-01-0909 January 1998 Responds to NRC 971212 NOV & Proposed Imposition of Civil Penalty in Amount of $55,000.Corrective Actions:Switch Was Examined & Returned to Normal on 970820.Check for $55,000 for Payment of Civil Penalty Encl.W/O Encl IR 05000261/19970101997-12-12012 December 1997 Discusses Insp Rept 50-261/97-10 on 970831-1011 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000 RA-97-0248, Forwards Rev 34 to Industrial Security Plan for Unit 2.Rev Made Effective on 971204.Rev Withheld,Per 10CFR73.211997-12-0404 December 1997 Forwards Rev 34 to Industrial Security Plan for Unit 2.Rev Made Effective on 971204.Rev Withheld,Per 10CFR73.21 ML20199F2751997-11-19019 November 1997 Forwards Sent to Nuclear Energy Inst on Plant Recent Improved STS Conversion License Amend ML20199F6561997-11-18018 November 1997 Forwards Copy of to Nuclear Energy Inst on Hb Robinson Recent Improved STS Conversion License Amend,For Info & Consideration in Efforts to Convert to Improved STS ML20199F2891997-11-18018 November 1997 Forwards Copy of Sent to Nuclear Energy Inst on Hb Robinson Recent Improved STS Conversion License Amend,For Info & Consideration in Efforts to Convert to Improved STS ML20199F5251997-11-17017 November 1997 Forwards Copy of Sent by NRC to Nuclear Energy Institute on Hb Robinson Recent Improved STS Conversion License Amend,For Info & Consideration in Efforts to Convert to Improved STS ML20199C0501997-11-0707 November 1997 Requests Addl Info Re TSs Change Request to Convert to Improved STS for Plant.Licensee Should Prepare Similar Tables for Plant Conversion as NRC Writes Safety Evaluation RA-97-0188, Forwards Rev 6 to Security Personnel Training & Qualification Plan. Description of Each Change & Justification That Change Does Not Decrease Effectiveness of Training & Qualification Plan1997-09-18018 September 1997 Forwards Rev 6 to Security Personnel Training & Qualification Plan. Description of Each Change & Justification That Change Does Not Decrease Effectiveness of Training & Qualification Plan ML20217Q2601997-08-25025 August 1997 Forwards CP&L Semiannual FFD Program Performance Data for Period of 970101-0630,per 10CFR26.71(d) ML20137X8581997-04-16016 April 1997 Discusses 970324 Request for Two Rail Routes to Be Used for Transport of Sf from Southport,Nc & Hartsville,Sc to New Hill,Sc.Safeguards Info Encl ML20137N1591997-03-31031 March 1997 Informs That Licensee Facility Scheduled to Administer NRC GFE on 970409.Sonalsts,Inc Authorized Under Contract to Support NRC Administration of GFE Activities RA-97-0042, Requests Extension on Sf Rail Transportation Route Approval, Provided by CE Haughney1997-03-24024 March 1997 Requests Extension on Sf Rail Transportation Route Approval, Provided by CE Haughney ML20136A6101997-03-0101 March 1997 Final Response to FOIA Request for Documents.Forwards App C Documents Available in Pdr.App D Records Being Withheld in Part (Ref FOIA Exemption 4).App E Completely Withheld (Ref FOIA Exemption 7) ML20134Q0981997-02-21021 February 1997 Ninth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App P.App Q Documents Partially Withheld (Ref FOIA Exemption 6).Documents Also Available in PDR ML20147G2701997-02-19019 February 1997 Extends Invitation to Attend 970325 Meeting Between NRC & Carolina Power & Light Co to Discuss Robinson Nuclear Power Plants Performance Over Past 20 Years as Observer RA-97-0002, Forwards Rev 33 to Industrial Security Plan.Encl Withheld1997-02-12012 February 1997 Forwards Rev 33 to Industrial Security Plan.Encl Withheld RA-97-0028, Submits Advance Notification of Listed Upcoming Shipment of Irradiated Nuclear Reactor Fuel,Iaw 10CFR73.371997-02-0404 February 1997 Submits Advance Notification of Listed Upcoming Shipment of Irradiated Nuclear Reactor Fuel,Iaw 10CFR73.37 RA-97-0010, Provides Info Re Forthcoming Shipment of Irradiated Nuclear Reactor Fuel by Carolina Power & Light1997-01-21021 January 1997 Provides Info Re Forthcoming Shipment of Irradiated Nuclear Reactor Fuel by Carolina Power & Light ML20147B4181997-01-10010 January 1997 Provides Info Re Forthcoming Shipment of Irradiated Nuclear Reactor Fuel RA-96-0226, Notification of Forthcoming Shipment of Radioactive Matl in IF-300 Series Shipping Casks,To New Hill,Nc1996-12-20020 December 1996 Notification of Forthcoming Shipment of Radioactive Matl in IF-300 Series Shipping Casks,To New Hill,Nc ML20135B6351996-11-21021 November 1996 Notifies of Shipment of Irradiated Nuclear Reactor Fuel by Carolina Power & Light to Hb Robinson Steam Electric Plant, Unit 2 ML20134J8951996-11-0606 November 1996 Forwards Info IAW 10CFR73.37 Re Forthcoming Shipment of Irradiated Nuclear Fuel by CP&L ML20134K3151996-10-24024 October 1996 Forwards Info IAW 10CFR73.37 Re Forthcoming Shipment of Irradiated Nuclear Fuel by CP&L ML18065B0081996-10-14014 October 1996 Informs That Overheads Will Be Presented by Licensee at 961016 Meeting at NRC Headquarters in White Flint.Encl Withheld RA-96-0142, Forwards Correction to Ltr Re Spent Fuel Shipping1996-08-0808 August 1996 Forwards Correction to Ltr Re Spent Fuel Shipping ML20117C3961996-07-30030 July 1996 Provides Info IAW 10CFR73.37 Concerning Forthcoming Shipment of Irradiated Nuclear Reactor Fuel by CP&L RA-96-0133, Submits Summary Description of Proposed Vehicle Control Measures Required for Protection Against Malevolent Use of Vehicles at NPPs1996-07-17017 July 1996 Submits Summary Description of Proposed Vehicle Control Measures Required for Protection Against Malevolent Use of Vehicles at NPPs ML20147C2591996-06-17017 June 1996 Forwards Exam Outline for NRC Exam to Be Administered Wk of 960819 at Plant RA-96-0088, Forwards Three Copies of Rev 32 to Industrial Security Plan. Encl Withheld1996-04-29029 April 1996 Forwards Three Copies of Rev 32 to Industrial Security Plan. Encl Withheld ML20149K0451996-02-0101 February 1996 Final Response to FOIA Request for Records.Apps a & B Records Encl & Being Placed in Pdr.Foia Request 96-33 by CP&L Also Encl,As Requested.W/O FOIA Request 96-33 RA-96-0015, Transmits Three Copies of Rev 31 to Industrial Security Plan for Plant.Plan Withheld1996-01-29029 January 1996 Transmits Three Copies of Rev 31 to Industrial Security Plan for Plant.Plan Withheld RA-95-0194, Forwards Rev 29 to Industrial Security Plan.Rev Incorporates Changes Associated W/Elimination of Commitment to Incorporate TSC Into Protected Area When TSC Activated.Encl Withheld Per 10CFR73.211995-11-0808 November 1995 Forwards Rev 29 to Industrial Security Plan.Rev Incorporates Changes Associated W/Elimination of Commitment to Incorporate TSC Into Protected Area When TSC Activated.Encl Withheld Per 10CFR73.21 ML14183A6931995-09-18018 September 1995 Forwards Safety Evaluation Re Location of Technical Support Ctr.Licensee Request for Exception to TSC Location Requirement of Suppl 1 to NUREG-0737 Acceptable ML20149K1791995-08-22022 August 1995 Informs That NRC Continuing Review of Allegation RII-93-A-0125 Re Questionable Engineering Practices,In Ref to NRC ,Informing That NRC Initiated Actions to Develop & Examine Facts & Circumstances of Concern RA-95-0086, Forwards Rev 28 to Industrial Security Plan & Rev 5 to Safeguards Contingency Plan for Plant Unit 2.Encls Withheld Per 10CFR73.211995-05-0404 May 1995 Forwards Rev 28 to Industrial Security Plan & Rev 5 to Safeguards Contingency Plan for Plant Unit 2.Encls Withheld Per 10CFR73.21 ML20082H0051995-04-0404 April 1995 Requests re-approval of Transportation Route for Irradiated Reactor Fuel Shipment by 951201,per 10CFR73.37(b)(7) 1999-08-26 Category:INCOMING CORRESPONDENCE MONTHYEARRA-99-0071, Forwards Rev 7 to Training & Qualification Plan & Rev 1 to Physical Security & Safeguards Contingency Plan for HBR2,per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld1999-04-0101 April 1999
[Table view]Forwards Rev 7 to Training & Qualification Plan & Rev 1 to Physical Security & Safeguards Contingency Plan for HBR2,per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld ML20210J5761999-03-0404 March 1999 Requests Route re-approval for Rail Transportation Routes, Previously Approved by NRC by Ltr .Two Routes Requested to Be Reapproved,Rail Route 130 & 135.Util Requests That NRC Renew Route Approvals by 990416 RA-99-0011, Requests Change to HBR2 Physical Security & Safeguards Contingency Plan,Per 10CFR50.90.Change Involves Staffing & Location of Plant Security Force as Described in Encl.Encl Withheld1999-01-15015 January 1999 Requests Change to HBR2 Physical Security & Safeguards Contingency Plan,Per 10CFR50.90.Change Involves Staffing & Location of Plant Security Force as Described in Encl.Encl Withheld RA-98-0153, Transmits Description of Rev 0 to Physical Security & Safeguards Contingency Plan, Which Contains Plant Industrial Security Plan & Safeguards Contingency Plan,Per 10CFR72.44(e)1998-08-27027 August 1998 Transmits Description of Rev 0 to Physical Security & Safeguards Contingency Plan, Which Contains Plant Industrial Security Plan & Safeguards Contingency Plan,Per 10CFR72.44(e) RA-98-0136, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan, for Hb Robinson Steam Electric Plant,Iaw 10CFR50.54(p)(2) & 50.4(b)(4).Summary of Changes Contained in Attachment 1.Plan Withheld,Per 10CFR73.211998-07-17017 July 1998 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan, for Hb Robinson Steam Electric Plant,Iaw 10CFR50.54(p)(2) & 50.4(b)(4).Summary of Changes Contained in Attachment 1.Plan Withheld,Per 10CFR73.21 RA-98-0115, Forwards Rev 36 to Industrial Security Plan for Unit 2.Rev Withheld,Per 10CFR73.211998-06-18018 June 1998 Forwards Rev 36 to Industrial Security Plan for Unit 2.Rev Withheld,Per 10CFR73.21 RA-98-0020, Forwards Rev 35 to Industrial Security Plan for Rsep,Unit 2. Rev Incorporates Changes Associated W/Physical Mods Involved W/Implementation of Enhanced Defensive Strategy & Incorporates Addl Level of Descriptive Detail.Encl Withheld1998-02-26026 February 1998 Forwards Rev 35 to Industrial Security Plan for Rsep,Unit 2. Rev Incorporates Changes Associated W/Physical Mods Involved W/Implementation of Enhanced Defensive Strategy & Incorporates Addl Level of Descriptive Detail.Encl Withheld ML20198K6631998-01-0909 January 1998 Responds to NRC 971212 NOV & Proposed Imposition of Civil Penalty in Amount of $55,000.Corrective Actions:Switch Was Examined & Returned to Normal on 970820.Check for $55,000 for Payment of Civil Penalty Encl.W/O Encl RA-97-0248, Forwards Rev 34 to Industrial Security Plan for Unit 2.Rev Made Effective on 971204.Rev Withheld,Per 10CFR73.211997-12-0404 December 1997 Forwards Rev 34 to Industrial Security Plan for Unit 2.Rev Made Effective on 971204.Rev Withheld,Per 10CFR73.21 RA-97-0188, Forwards Rev 6 to Security Personnel Training & Qualification Plan. Description of Each Change & Justification That Change Does Not Decrease Effectiveness of Training & Qualification Plan1997-09-18018 September 1997 Forwards Rev 6 to Security Personnel Training & Qualification Plan. Description of Each Change & Justification That Change Does Not Decrease Effectiveness of Training & Qualification Plan ML20217Q2601997-08-25025 August 1997 Forwards CP&L Semiannual FFD Program Performance Data for Period of 970101-0630,per 10CFR26.71(d) RA-97-0042, Requests Extension on Sf Rail Transportation Route Approval, Provided by CE Haughney1997-03-24024 March 1997 Requests Extension on Sf Rail Transportation Route Approval, Provided by CE Haughney RA-97-0002, Forwards Rev 33 to Industrial Security Plan.Encl Withheld1997-02-12012 February 1997 Forwards Rev 33 to Industrial Security Plan.Encl Withheld ML18065B0081996-10-14014 October 1996 Informs That Overheads Will Be Presented by Licensee at 961016 Meeting at NRC Headquarters in White Flint.Encl Withheld RA-96-0142, Forwards Correction to Ltr Re Spent Fuel Shipping1996-08-0808 August 1996 Forwards Correction to Ltr Re Spent Fuel Shipping RA-96-0133, Submits Summary Description of Proposed Vehicle Control Measures Required for Protection Against Malevolent Use of Vehicles at NPPs1996-07-17017 July 1996 Submits Summary Description of Proposed Vehicle Control Measures Required for Protection Against Malevolent Use of Vehicles at NPPs ML20147C2591996-06-17017 June 1996 Forwards Exam Outline for NRC Exam to Be Administered Wk of 960819 at Plant RA-96-0088, Forwards Three Copies of Rev 32 to Industrial Security Plan. Encl Withheld1996-04-29029 April 1996 Forwards Three Copies of Rev 32 to Industrial Security Plan. Encl Withheld RA-96-0015, Transmits Three Copies of Rev 31 to Industrial Security Plan for Plant.Plan Withheld1996-01-29029 January 1996 Transmits Three Copies of Rev 31 to Industrial Security Plan for Plant.Plan Withheld RA-95-0194, Forwards Rev 29 to Industrial Security Plan.Rev Incorporates Changes Associated W/Elimination of Commitment to Incorporate TSC Into Protected Area When TSC Activated.Encl Withheld Per 10CFR73.211995-11-0808 November 1995 Forwards Rev 29 to Industrial Security Plan.Rev Incorporates Changes Associated W/Elimination of Commitment to Incorporate TSC Into Protected Area When TSC Activated.Encl Withheld Per 10CFR73.21 RA-95-0086, Forwards Rev 28 to Industrial Security Plan & Rev 5 to Safeguards Contingency Plan for Plant Unit 2.Encls Withheld Per 10CFR73.211995-05-0404 May 1995 Forwards Rev 28 to Industrial Security Plan & Rev 5 to Safeguards Contingency Plan for Plant Unit 2.Encls Withheld Per 10CFR73.21 ML20082H0051995-04-0404 April 1995 Requests re-approval of Transportation Route for Irradiated Reactor Fuel Shipment by 951201,per 10CFR73.37(b)(7) RA-95-0037, Forwards Summary of Description of Proposed Vehicle Control Measures & Vehicle Bomb Comparison.Encl Withheld1995-02-28028 February 1995 Forwards Summary of Description of Proposed Vehicle Control Measures & Vehicle Bomb Comparison.Encl Withheld ML20078B8801995-01-24024 January 1995 Transmits Safeguards Info Re 95-0055 Advance Fuel Shipment Notification.Encl Withheld RA-95-0012, Forwards Rev 27 to Industrial Security Plan.Changes Do Not Decrease Effectiveness of Plan & Level of Security Provided. Encl Withheld1995-01-19019 January 1995 Forwards Rev 27 to Industrial Security Plan.Changes Do Not Decrease Effectiveness of Plan & Level of Security Provided. Encl Withheld ML20079B3501994-12-27027 December 1994 Responds to NRC Re Violations Noted in Insp Rept 50-261/94-23.Corrective Actions:Procedure GP-007 Revised,Ts Section 3 Reviewed & Evaluation of RCS Temp Control Practices During Hot Shutdown Conditions Conducted.Fee Paid ML20077K3081994-12-20020 December 1994 Forwards Final Exercise Rept for 931130 Full Participation Plume Exposure & Partial Ingestion Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific to Plant ML20077F5731994-12-0909 December 1994 Discusses Commitments Made During Enforcement Conference Conducted 941017 Re Failure to Maintain Pressurizer Cool Down Rate within TS Limits & Failure to Establish Containment Integrity in Accordance W/Ts ML20077D0151994-12-0505 December 1994 Provides Addl Info to Supporting Request for Exemption from 10CFR73.55(d)(5) Re Issuance,Storage & Retrieval of Picture Badges for Contractors Who Have Been Granted Unescorted Access to Protected Areas of Bsep,Shnpp & Hbrsep.Withheld ML20073H4831994-09-29029 September 1994 Responds to NRC Re Violation Noted in Insp Rept 50-261/94-16.Corrective Action:Emergency Operating Procedures Were Revised to Place Operating Restrictions on HVS-1 ML20073H3181994-09-29029 September 1994 Responds to NRC Re Violations & Proposed Imposition of Civil Penalty Noted in Insp Rept 50-261/94-16. Corrective Actions:Plant Operating Procedures & EOPs Revised to Place Operating Restrictions on RAB Supply Fan HVS-1 ML20082T6121994-09-0606 September 1994 Forwards Rev 26 to Plant Industrial Security Plan for Unit 2.Encl Withheld Per 10CFR73.21 ML20071N0651994-07-29029 July 1994 Requests Exemption from 10CFR73.55(d)(5) Requirements Re Issuance,Storage & Retrieval of Picture Badges for Contractors That Is Granted Unescorted Access to Protected Areas ML20080Q4011994-06-20020 June 1994 FOIA Request for Documents of Any & All Documents,Records & Info Relating to Allegation or Allegations Designated by NRC W/Identifier RII-93-A-0182,relating to CP&L &/Or CP&L Plant, Unit 2 Including But Not Limited to Any NRC Insp ML20070A2481994-06-17017 June 1994 Forwards Rev 25 to Industrial Security Plan.Rev Withheld (Ref 10CFR73.21) ML20057E8861993-09-29029 September 1993 Forwards Rev 5 to Security Training & Qualification Plan for Hb Robinson Steam Electric Plant,Unit 2,per 10CFR50.54(p). Plan Withheld,Per 10CFR73.21 ML20057E8901993-09-29029 September 1993 Forwards Rev 4 to Safeguards Contingency Plan for Hb Robinson Steam Electric Plant,Unit 2,per 10CFR50.54(p). Plan Withheld,Per 10CFR73.21 ML20057C1671993-09-13013 September 1993 Forwards Rev 23 to Industrial Security Plan.Rev Incorporates Changes Associated W/Mgt Structure of Security Organization, New Equipment Location,Completion of O&M Bldg & Other Administrative Changes.Rev Withheld,Per 10CFR73.21 ML20149K1551993-08-23023 August 1993 Forwards Info Which May Help W/Investigation Re Being Terminated from CP&L in Nov 1992 ML20024H9071993-07-27027 July 1993 Provides Updated Status of Activities Being Performed at Auburn Steel Corporation Facility in Auburn,Ny ML20149K0811993-06-27027 June 1993 Forwards Ltr Sent to NRC on 930525,alleging That Employment W/Cp&L Terminated in Nov 1992 as Result of Compliants to NRC Re Erosion/Corrosion Program at Plant.Requests Info Re Action NRC Plans to Take ML20044G6101993-05-28028 May 1993 Forwards Rev 5 to Design Guide DG-II.20, Design Guide for Civil/Structural Operability Reviews & Rev 0 to 92C1737A, Recommended Operability Criteria for Piping Sys Subj to Level D Svc Ladings for Carolina Power & Light Nuclear.... ML20149K0571993-05-25025 May 1993 Alleges That Employment W/Cp&L Terminated in Nov 1992 as Direct Result of Complaints to NRC Re Erosion/Corrosion Program at Plant.Findings by NRC Outlined in 1992 SALP Rept ML20128M9051993-02-17017 February 1993 Forwards Addl Info for ERDS Data Point Library,Consisting of Revised & Replacement Pages ML20127M3911992-10-0202 October 1992 Forwards Util Response to Appeal to NRC Commissioners of NRC Staff Denial of Nirs Petitions for Immediate Enforcement Action of 920721 & 0812 ML20106C7931992-09-22022 September 1992 Provides Data Point Library Re Emergency Response Data Sys. Submittal Completes Emergency Response Data Sys Info Requirements Contained in NUREG-1394,Rev 1 ML20127E2951992-09-0303 September 1992 Forwards Appeal Under 10CFR2.206 of NRC 920819 Denial of 920721 Petition for Emergency Enforcement Action & 920812 Addenda ML20099F1221992-08-0505 August 1992 Forwards Rev 22 to Industrial Security Plan.Rev Withheld (Ref 10CFR73.21) ML20101M3501992-06-29029 June 1992 Forwards Rev 21A to Industrial Security Plan,Incorporating Changes Associated W/Access Authorization Program That Implements Requirements of 10CFR73.56.Rev Withheld (Ref 10CFR73.21) ML20095B1021992-04-0909 April 1992 Forwards Rev 21 to Industrial Security Plan for Plant.Rev Incorporates Changes Associated W/Access Authorization Program That Implements Requirements of 10CFR73.36.Rev Withheld (Ref 10CFR73.21) 1999-04-01 Category:UTILITY TO NRC MONTHYEARML17348B4941990-08-30030 August 1990
[Table view]Forwards Semiannual 10CFR26 fitness-for-duty Program Data for 900103-0630.Mgt Decision Made to Utilize Alcohol Breath Instruments as Screening Devices for Unscheduled Work Call Outs in Determining fitness-for-duty ML14188B6961990-04-23023 April 1990 Forwards Proprietary Thermal Hydraulic Compatibility Analysis of Advanced Nuclear Fuel High Thermal Performance for Hb Robinson,Unit 2. Rept Withheld (Ref 10CFR2.790(b)) ML18033B7561990-03-0202 March 1990 Responds to Crdr Portion of post-implementation Audit of TMI Action Plan Items I.D.1 & I.D.2 Conducted on 890613-16. Implementation of Reactor Coolant Pump Temp Indication Project Rescheduled for Refueling Outage 14 in 1992 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 ML20011F2531990-02-23023 February 1990 Forwards Rev 18 to Industrial Security Plan.Rev Withheld (Ref 10CFR73.21) 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 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 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) 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 ML14188B6731990-02-0606 February 1990 Forwards Proprietary Hb Robinson Unit 2,Cycle 14 SAR & Mechanical Licensing Rept for Hb Robinson High Thermal Performance Fuel Assemblies. Repts Withheld (Ref 10CFR2.790) 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) 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 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 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 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 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 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 ML18153C0771990-01-17017 January 1990 Forwards North Anna Power Station Emergency Plan Table 5.1, 'Min Staffing Requirements for Emergencies' & Surry... Table 5.1, 'Min Staffing Requirements...', for Approval,Per 10CFR50.54(q),NUREG-0654 & NUREG-0737,Suppl 1 ML20006A2011990-01-16016 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel in Anchor Darling Swing Check Valves.Eight Subj Valves Identified in Peach Bottom Units 1 & 2 & Will Be Returned to Mfg ML18153C0731990-01-15015 January 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or or Valves.... Util Replaced Studs in twenty-five Valves ML20006B8821990-01-10010 January 1990 Reissued Ltr Correcting Date of Util Ltr to NRC Which Forwarded Updated FSAR for Byron/Braidwood Plants from 881214 to 891214.W/o Updated FSARs ML20006A8201990-01-10010 January 1990 Forwards Errata to Rev 3 to BAW-1543,Tables 3-20 & E-1 of Master Integrated Reactor Vessel Surveillance Program Reflecting Changes in Insertion Schedule for A5 Capsule for Davis-Besse & Crystal River ML20005G6431990-01-10010 January 1990 Responds to Generic Ltr 89-21 Re Implementation of USI Requirements,Consisting of Revised Page to 891128 Response, Moving SER Ref from USI A-10 to A-12 for Braidwood ML20005G7601990-01-0404 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Plan. Privacy Info Should Be Deleted Prior to Placement in Pdr.W/ D Grimsley 900118 Release Memo ML20005F4641990-01-0303 January 1990 Advises That Licensee Implemented 10CFR26 Rule Re fitness-for-duty Program W/One Exception.Util Has Not Completed Background Check for Some of Program Administrators.Checks Expected to Be Completed by 900105 ML18153C0491990-01-0303 January 1990 Advises of Implementation of fitness-for-duty Program Which Complies w/10CFR26.Util Support Objective of Providing Assurances That Nuclear Power Plant Personnel Will Perform Tasks in Reliable & Trustworthy Manner ML18094B2331990-01-0303 January 1990 Certifies Util Implementation of fitness-for-duty Program, Per 10CFR26.Training Element Required by Rule Completed on 891215.Chemical Testing for Required Substances Performed at Min Prescribed cut-off Levels,Except for Marijuana ML20042D3731990-01-0202 January 1990 Forwards Revised Crisis Mgt Implementing Procedures, Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9, Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML17347B5051990-01-0202 January 1990 Certifies That Util Has fitness-for-duty Program Which Meets Requirements of 10CFR26.Util Adopted cut-off Levels Indicated in Encl ML20042D3381989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. Util Will Comply W/Ltr Recommendations W/Noted Exceptions.Response to Be Completed When Ltr Uncertainties Cleared ML17347B4961989-12-28028 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Considering Expansion of Plants to Include Addl safety-related & Position Changeable Valves W/ Emphasis on Maint & Testing ML18094B2291989-12-27027 December 1989 Requests to Apply ASME Section XI Code Case N-460 to Facilities Re Reduction in Exam Coverage on Class 1 & 2 Welds.Fee Paid ML18094B2201989-12-27027 December 1989 Advises of Intent to Provide follow-up Response to Generic Ltr 89-10 by 900831 to Describe Status of Program, Recommendation Exceptions & Any Schedule Adjustments ML20005E1911989-12-26026 December 1989 Forwards Revised Page 2 Correcting Plant Implementation Date for USI A-24 Requirements in Response to Generic Ltr 89-21 ML18153C0261989-12-26026 December 1989 Responds to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & surveillance.Motor-operated Valve Program Structured to Allow Similar Approach to motor-operated Dampers.Results Will Be Submitted in 30 Days 1990-08-30 |
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Carohna Power T. Light Company August 7, 1973
-File: 5211.2 Serial: NG-73-260
^
Mr. Norman C. Moscicy '
Directorate of Regulatory Operations U. S. Atomic Energy Commission ,
Region II - Suite 818 230 Peachtree Street, N.W.
Atlanta, Georgia 30303
Dear Mr. Moseley:
H. B. ROBINSON UNIT NO. 2 LICENSE NO. DPR-23 DRO BULIETIN No. 73-2 MALFUNCTION OF CONTAINMENT PURGE SUPPLY VALVE SWITCH In response to your letter of July 13, 1973, concerning DRO Bulletin No. 73-2, a review of the control circuit for the containment ventilation system isolation valves was made.
The review indicated the Robinson Unit 2 purge valve control system is unlike that of Point Beach 2 described in your bulletin. The purge valve control system and the two identical control systems for the two purge fan motors are interlocked. Turning a momentary contact switch on either of the fan control systems will automatically open the purge valves and start the fan motors. Thece switches on the fan control systems are the only means of manually opening the purge valves. Connected in series with the solenoid relays which actuate the valves are two sets of normally closed relay contacts. On receipt of a containment isolation signal or a signal from the radiation monitoring system these contacts will open, de-energir.ing the solenoid relays and closing the purge valves.
In the event that the control switch which manually operates the exhaust fan motors (and, consequently, the purge valves) failed such .
that these valves could not be closed from this switch, a containment isolation signal or a radiation monitoring system signal would independently close the valves. Therefore, under normal operating situations one of these two systems could be manually actuated from the control room to close f the isolation valves until repairs could be made on the failed switch.
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O O Mr. Norman C. Moscicy August 7, 1973 In an accident situation the valves would automatically close on receipt of a signal from these systems despite the failed switch.
We believe that our purge system meets the design requirements and needs no modification.
Yours very truly, hb E.
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't. Uticy ;[
Vice-President Bulk Power Supply KPY:NBB:mvp cc: Messrs. C. D. Barham N. B. Bessac B. J. Furr D. V. Menscer D. B. Waters
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,, .... O Letter from C trolina Power and Light Company, E. E. Utley. OCT 111973 dated August 7, 1973 - R0B 73 50-261 DISTRIBUTION:
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Directorate of Licensing (4)
DR Central Files PDR l Local PDR NSIC OIS, OR -
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