ML20210B504
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| ML20210B504 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 01/16/1987 |
| From: | Morgan R CAROLINA POWER & LIGHT CO. |
| To: | Verrelli D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| IEB-82-02, IEB-82-2, RNPD-86-6017, NUDOCS 8702090174 | |
| Download: ML20210B504 (2) | |
Similar Documents at Robinson | |
|---|---|
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 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 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 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) 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 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 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 ML20011F2531990-02-23023 February 1990 Forwards Rev 18 to Industrial Security Plan.Rev Withheld (Ref 10CFR73.21) 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) ML19332B9011989-11-10010 November 1989 Responds to Generic Ltr 89-07 Re Power Reactor Safeguards Contingency Planning for Surface Vehicle bombs.Short-term Actions Included in Safeguards Planning ML19327B4721989-10-24024 October 1989 Forwards Rev 3 to Safeguards Contingency Plan.Rev Withheld (Ref 10CFR73.21) ML19327B4751989-10-24024 October 1989 Forwards Rev 17 to Industrial Security Plan.Rev Withheld (Ref 10CFR73.21) ML18033B7471989-06-16016 June 1989 Responds to Violations Noted in Insp Rept 50-261/89-08. Corrective Actions:Surveillance Procedures Used for safety- Related Steam Driven Auxiliary Feedwater Pump Being Revised to Ensure Compatability When Performed Concurrently ML20245F3481989-04-24024 April 1989 Forwards Rev 16 to Industrial Security Plan.Rev Withheld (Ref 10CFR73.21) ML20245C1361989-04-17017 April 1989 Forwards Transcript of Dept of Labor 851216 Hearing in Columbia,Sc Re PA Blackburn Vs Metric Constructors,Inc. Believes That Hearing Record Strongly Supports Position That Enforcement Action Against CP&L Unwarranted ML20236B8371989-03-0202 March 1989 Provides Listing of Results of Util Analysis for Sr-89, Sr-90,Fe-55 & Tritium in NRC Spiked Samples Received on 890103 ML20151E6011988-07-15015 July 1988 Responds to Violations Noted in Insp of License DPR-23 & Enforcement Action 88-88 Re Proposed Imposition of Civil Penalties.Takes Exception to Violation as Stated.Analyses Indicate 10CFR50,App K Criteria Fully Met ML18033B7411988-05-27027 May 1988 Responds to Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants, Per 10CFR50.54(f) ML20196J4351988-03-0707 March 1988 Responds to Regulatory Effectiveness Review on 871207-11. Corrective Actions Withheld (Ref 10CFR2.790) ML20236W2421987-12-0202 December 1987 Requests That Listed Name & Address Be Published in Fr as Atty for Licensee in All Notices Re Brunswick Steam Electric Plant,Units 1 & 2,Shearon Harris Plant & H.B.Robinson Steam Electric Plant Unit 2 ML20236Q8321987-11-13013 November 1987 Responds to SALP Repts 50-261/87-22,50-324/87-19, 50-325/87-19 for Nov 1985 - June 1987 & 50-400/87-24 for Aug 1986 - June 1987.Issues Noted in Repts Re Util Overall Performance Discussed ML20236H1091987-10-27027 October 1987 Forwards Response to Insp Rept 50-261/87-26.Response Withheld (Ref 10CFR2.790(d) & 10CFR73.21) ML20236C5031987-10-21021 October 1987 Forwards Amended Rev 13 to Plant Security Plan,Per NRC 870925 Request for Addl Info.Rev Withheld (Ref 10CFR73.21) ML18004B9531987-09-30030 September 1987 Submits Results of Followup at Hb Robinson from Commitment for Further Action in Util Response to Insp Rept 50-400/87-22 Re Exposure to Noble Gas.Potential Unassigned Skin Dose to 11 Personnel Found Insignificant ML20235G7971987-09-23023 September 1987 Clarifies Response to 870824 RII-87-07-01-SL4 Notice of Violation.Corrective Actions:Procurement of 8-inch Schedule 160 Calibr Block Initiated ML20234F4021987-09-17017 September 1987 Forwards Addl Info Re Facility Responses to IE Bulletin 85-003,per NRC 870818 Request.Water Hammer Due to Valve Closure Not Considered in Determination of Differentials for Valves Listed in 860730 Response ML20238A2921987-08-21021 August 1987 Forwards Response to NRC Re Violations Noted in Insp Rept 50-400/87-22 & Assessment of Applicability of Finding at Facility.Util Denies Violation Re TLD Concentration of Noble Gas in Containment ML20235T7491987-08-14014 August 1987 Forwards Util Comments Re Exam Rept 50-261/OL-87-01 on 870811-14.Comments Made by Listed Instructors from Plant Training Unit ML20235X9721987-07-21021 July 1987 Forwards List of Changes to Facility Described in Fsar,Per 10CFR50.59 ML20215C8461987-06-11011 June 1987 Forwards Listing of Pressure Isolation Valves,Description of Periodic Testing,Leakage Acceptance Criteria,Operational Limits & Testing Frequency,In Response to Generic Ltr 87-06, Periodic Verification of Leak Tight Integrity.. ML20214R5051987-06-0202 June 1987 Forwards Rev 1 to Monthly Operating Rept for Apr 1987 Due to Mathematical Errors Re Operation Statistics & Shutdown Experience ML20210B3911987-04-29029 April 1987 Forwards Rev 1 to Monthly Operating Rept for Mar 1987.Rev Includes Addl Unit Shutdown Not Reported in Original Issue ML20206C2091987-03-20020 March 1987 Forwards Amend 1 to ISFSI SAR, for Incorporation Into Sar. Requests Completion of Encl Ack Form ML20205Q3681987-03-0606 March 1987 Documents Agreements Reached in 870105 Meeting W/Shearon Harris Energy & Environ Ctr & State of Sc Bureau of Radiological Health Re Environ Monitoring Program Coordination W/State of Sc.Sampling Calendar for 1987 Encl ML20212H4821987-02-27027 February 1987 Submits 1986 Annual Rept on Primary Safety & Relief Valve Challenges as Required by Tech Spec 6.9.1.b.3 ML20210T6411987-02-11011 February 1987 Advises That Redemonstration of Facility Exercise Scenario Forwarded to W Sartor for Exercise Scheduled on 870218. Controller/Evaluator Meeting Will Be Held on 870217 in Technical Support Ctr/Emergency Facility Training Bldg ML20210B3011987-02-0303 February 1987 Confirms 870109 & 13 Telcons W/Region II Re Violation Noted in Insp Rept 50-261/86-21.Corrective Actions:Training for Accident Assessment Team & Damage Control Team Completed on 861231 & 870109,respectively ML20212J9291987-01-16016 January 1987 Forwards Rev 4 to Security Personnel Training & Qualification Plan Re Use of Newly Installed Electronic Security Search Equipment.Rev Withheld (Ref 10CFR2.790 & 73.21) ML20210B5041987-01-16016 January 1987 Suppls Info Discussed in Insp Rept 50-261/86-12 Re IE Bulletin 82-02, Degradation of Threaded Fasteners in RCPB of PWR Plants. Reactor Vessel Head Closure Studs Addressed by Inservice Insp 05000261/LER-1986-012, Forwards LER 86-012-01,revising Level of Reactor Power from Which Unit Tripped from 42% to 13%.Operating Mode Marked N as Recommended by NUREG-10221987-01-15015 January 1987 Forwards LER 86-012-01,revising Level of Reactor Power from Which Unit Tripped from 42% to 13%.Operating Mode Marked N as Recommended by NUREG-1022 ML20207L6281987-01-0606 January 1987 Responds to Violations Noted in Insp Rept 50-261/86-28. Corrective Actions:Event Discussed W/Operators Involved & Disciplinary Action W/Operator & Two I&C Technicians Taken to Emphasize Importance of Following Procedures Correctly ML20207N7771987-01-0202 January 1987 Forwards Rev 0 to CPL-18-120, Supplemental Info in Support of Conservatisms in Criticality Analysis Performed for Hb Robinson ISFSI, Per NRC 861202 Request for Addl Info to Support Review of 861031 Application for Amend to License ML20207K1791987-01-0202 January 1987 Forwards Revs to Emergency Plan & Procedures & List of Revs. W/O Plan & Procedures ML20215F4081986-12-11011 December 1986 Forwards Rev 14 to Industrial Security Plan.Rev Involves Realignment of Portion of Protected Area Barrier & Associated Hardware.Rev Withheld (Ref 10CFR2.790(d)(1) & 73.21) ML20215A1231986-12-0505 December 1986 Forwards Meeting Notes Documenting 861020-24 Tech Spec Meeting in Bethesda,Md,Per Request ML20214K6551986-11-26026 November 1986 Forwards Rev 13 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20214L3921986-11-18018 November 1986 Responds to Violations Noted in Insp Rept 50-261/86-26. Corrective Actions:Changes to 1985 Facility Summary Rept Prepared & Submitted to NRC on 860926 & Personnel Responsible for Submittal of Rept Counseled ML20213G0801986-11-0404 November 1986 Forwards Revs to Emergency Plans & Procedures.W/O Encls ML20213G1161986-11-0303 November 1986 Forwards Response to IE Bulletin 86-003 Re Potential Failure of Multiple ECCS Pumps Due to Single Failure of air- Operated Valve in Min Flow Recirculation Line.Mechanical Block Installed on Each Valve Actuator & Procedures Revised ML20213D6531986-10-30030 October 1986 Forwards Rev 12 (Annex B) to Industrial Security Plan Re Security for Isfsi.Rev Withheld (Ref 10CFR73.21 & 2.790(d)(1)) ML20215J9621986-10-17017 October 1986 Responds to Violations Noted in Insp Rept 50-261/86-21. Corrective Actions:Accident Assessment & Damage Control Team Members Designated & Appropriate Training Initiated ML20215K0161986-10-16016 October 1986 Responds to Violations Noted in Insp Rept 50-261/86-20. Corrective Actions:Procedure Revised to Allow for SCBA Fit Testing & Personnel Trained in Procedural Guidance for Doing Surveys of Matls Prior to Release from Radiation Area ML20210C7911986-10-0202 October 1986 Forwards Comments Re 860930 Reactor & Senior Reactor Operator Written Exams Administered by CA Casto.Exams Reviewed by Listed Instructors from Training Unit ML18022A4451986-09-29029 September 1986 Requests Approval to Provide NRC W/Npdes Permit & Any Authorized Changes to Enable Adequate Notification of Significant Environ Events 1990-08-30 |
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ROBINSON NUCLEAR PROJECT DEPARTMENT POST OFFICE BOX 790 HARTSVILL SUH OLINA 29550 Robinson File No: 13510E Serial: RNPD/86-6017 Mr. David M. Verre11i, Chief U. S. Nuclear Regulatory Commission, Region II 101 Marietta Street NW Atlanta, Georgia 30323 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT 2 DOCKET No. 50-261 LICENSE NO. DPR-23 INSPECTION REPORT 86-12
Dear Mr. Verrelli:
USNRC Inspection Report 86-12 included information that closed IE Bulletin 82-02, " Degradation of Threaded Facteners in the Reactor Coolant Pressure Boundary of PWR Plants," for our facility. The inspector, W. P. Kleinsorge, reviewed our letters of July 30, 1982 and March 8, 1985, and determined that the requested actions of the bulletin have been acceptably addressed.
Mr. Kleinsorge also held discussions with responsible engineers, reviewed supporting documentation, and observed representative samples of work to verify that the actions identified in the letters of response have been completed.
IE Bulletin F2-02 allows licensees who are committed to the provisions of Regulatory Cuide 1.65, " Materials and Inspection for Reactor Vessel Closure Studs," to exclude reactor vessel head closure studs from the actions required by the bulletin. In our July 30, 1982 response letter, we stated that although H. B. Robinson Unit 2 is not committed to Regulatory Guide 1.65, the reactor vessel head studs are inspected in accordance with ASME Section XI.
We also stated that there have been no cases of reactor vessel head stud degradation. In our March 8, 1985 response letter, we identified procedures which include the requirements for threaded fasteners, one of which was FHP-015, " Reactor Vessel Stud Removal and Replacement," and we stated that there have been no identified corrosion problems associated with bolts or studs in reactor coolant pressure boundary closures within the scope of IE Bulletin 82-02 and no instances of stress corrosion cracking of threaded fasteners associated with lubricants or injection sealants.
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"Lett r to Mr. David M. Varrs11i S:ricia RNPD/86-6017 Page 2 The scope of Action,/ Items listed in IE Bulletin 82-02 is limited to steam generator and pressurizer manway closures and valve bonnets and pump flange connections installed on lines 6 inch diameter and greater. As stated above, the reactor vessel head closure studs are also included unless the licensee is committed to Regulatory Guide 1.65.
Regulatory Guide 1.65 of October, 1973, recommends that studs be examined in accordance with the requirements of Section XI as supplemented by surface examinations in accordance with Paragraph NB-2545 or NB-2546 of Section III of the ASME Code. Since the issue of Regulatory Guide 1.65,Section XI of the ASME Code has required volumetric and surface examination of reactor vessel studs. Currently, studs are examined volumetrically and with wet fluorescent magnetic particle methods. The magnetic particle examination is performed in accordance with Article 7,Section V as required by both Section XI and Paragraph NB-2545. All examinations are performed with the studs removed.
Selection is by numbers 1 through 17, 18 through 34, and 35 through 50 for periods 1, 2, and 3, respectively, of the current In-Service Inspection interval. This practice meets the intent of Regulatory Guide 1.65 even though we are not committed to it for compliance.
We have, therefore, deleted the reactor vessel head closure studs from the IE Bulletin 82-02 program since our In-Service Inspection Program addresses the concerns and actions of the bulletin and the Regulatory Guide.
l If you have any questions concerning this letter, please contact Mr. J. M. Curley at (803) 383-1367.
l Very truly yours, l
l R. E. Morgan General Manager H. B. Robinson S. E. Plant DAS:sdm l
l cc: C. P. Beatty, Jr.
W. P. Kleinsorge (NRC)
H. E. P. Krug (NRC)
C. Requa (NRC) i E. E. Utley
- A. R. Wallace I
1 l
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