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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20211G9851999-08-26026 August 1999 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
[Table view] Category:ENGINEERING/CONSTRUCTION/CONSULTING FIRM TO NRC
MONTHYEARML20236U5221987-10-19019 October 1987 FOIA Request for LERs for Listed Plants,Including All Attachments & Encls from Original Documents ML20087B9481971-06-25025 June 1971 Forwards Rept on Insp of Leak & Cracks in (a) Steam Generator at Hb Robinson II ML20086B5161970-07-10010 July 1970 Forwards Stress Analysis of Modified Main Steam Safety Valve Nozzle & Adjacent Steamline ML20086B5681970-05-26026 May 1970 Submits Addl Comments Re Valve Nozzle Failure & Recommendations for Followup Actions.Apparent Departure from Recommended Valve Installation Practices Warrant Thorough Review of Main Steam Safety Valve Nozzle Problem ML20086B5911970-05-24024 May 1970 Forwards Rept DC-67 Covering Trip to Ebasco & Stress Evaluation of Nozzle Failure.W/O Encl 1987-10-19
[Table view] 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 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
[Table view] |
Text
.. 1 iI.-
O ran cesaAL USE ONLY
( Pagn of 6 fardmeter, bn c.
Consulting Engineers
- Design - Analysis - Development 13545 WATERTOWN PLANK ROAD, ELM GROVE, W15 CON $1N 53122 784-7380 May 26, 1970 Mr. William C. Seidic, Senior Reactor Inspector United States Atomic Energy Commission Division of Compliance - Region II ,
230 Peachtree Street - NW Suite 818 Atlanta, Georgia 30303 Copics: Mr. L. Kornblith Mr. H. R. Denton CO-Hg.
Reference:
AEC Contract AT(11-1)-1658, Task A Consulting Services PAR : 69-70A Assignment DC-67
Dear Mr. Seidle:
Supplementing our report DC-67, this l etter contains some additional comments on the Robinson 2 valve nozzle failure and a number of recommendations for Compliance follow-up .
actions. -
- 1. In our report we pointed out that failure to consider the valve " popping".-thrust load was an apparent short-coming in meeting the general design requirements of the Power Piping code, B-31.1.0 as far as the sizing of the nozzle on the main steam lines was concerned.
Beyond this,the installation appears to violate the T.
recommended practice of the valve manufacturer in s _ ,_ ,,,.
number of ways:
a) Typically, the valve manufacturer (Crosby W1've and Gage Company) specifies the minimum cross
/ ti " f "*ld r*9"ir'd * " ""* hi" 7/9/'/d **tablishing the inside and outside diameters
"^1"* bY of ppW es the valve extension at the point of attachment.
j As these valves, in_a fossil plant, would normal-ly be mounted on a steam drum or heavy section
,/ nozzle extension, the weld joint would essentially N
0311180037 700922 PDR ADOCK 05000261
[QR -Q$G)/\[ % h fp endix B t,0 cA tic /
.o c
Pags 2 of 6 fa ra m eler, bn c.
- C O N S U LTIN G ENGINtits ELM OROVE, Wi$ con $lN Mr. William C. Seidle May 26, 1970 develop the full strength of the valve body if wolded up to full thickness.
Reference:
( WE are enclosing copies of pagos 6 &
7 of Crosby Catalog 402-SC which show typical mounting arrangements and dim-ensions for their HCA Series valves.
At the time of this writing, we have not yet received a bulletin on the HCU Series used at Robinson.)
From the figure and notes on Page 7 of the abouc reference, you will note that the "B" minus "A" diameters represent the minimum attachment cross section reconmonded by the manufacturer. If the HCU-65W valvo connection is similarly specified, we might conclude that the attachment weld ( to a stub nozzle or steam manifold) should occupy the full thicks.ess of the valve wall ( the 6.065" Dia.
to the 9" Dia. at the taper shown as approximately 0
45 on Attachment #2 to DC-65). Please note the following sentonces on page 7 of the reference:
" "B" dimensions are recommended minimum to withstand stresses induced by pressure and by bending moments due to reaction when valves arc discharging. Schedule pine must not be used for safety valve nozzles on boilers be-cause of insufficient wall thickness.8#
(underlining added)
We will check the recommended attachment area when further design information on the valves is re-ceived and follow up with a definite interpretation.
b) Note from the figures on pages 6&7 of the above reference, that recommended practice is to mount the discharge stack structurally isolated from the valve. As we understand the design j the stacks at Robinson are welded to the flange of the discharge elbow cantilever mounted to the valve body and no external support is provided. This feature, while not recommended, would in itself not be to serious if stress levels were kept low.
~ .
o o Page 3 cf 6 farbm eler, bn c.
CO N S U LTIN G ENGINEERS ELM OROVE, WISCONSIN l Mr. William C. Seidle l May 26, 1970 1
I
- c) The bulletin for the HCA S eries limits the moment l arm "L" from the valvo centerline to the discharge conterline to 24". The limitation for the HCU Ser -
ies will be checked and reported along with the recommended weld area discussed above. We under-stand from a telephone discussion with Mr. G. W.
Rainmuth, CO:Hg., that the offset dimension for the subject valve installation was quoted in the meeting at We stinghous , Pittsburgh, as 30".
It is normally good engineering practice, when specify-ing a manufacturer's product which is required to pro-vide warranted performance (such as the safety valve),
to obtain their approval of the application. In the i course of your further investigation, it might be im-portant to determine if Ebasco obtained Crosby's ap- h((3 proval of this and other applications of safety valves used in the Robinson-2 and other plants. WE feel that the conclusions of our report DC-67 and the apparent departure from recommended valve installation practices described above warrantsa thorough review of the eval- k untion and disposition of the main steam safety valve l nozzle problem and other similar valves in nuclear safety related systems by the AEC Compliance.
- 2. It is assumed that a formal report of the failure will be submitted by the licensee together with his pro-posed repair or modification program. It is recommend I ed that his evaluation of the cause of failure be re-viewed in terms of the stress related probability of failure described in our report DC-67, and in light of recommended design practice as well as for the metal-lurgical considerations.
From the presentation by Westinghouse personnel in the May 15 meeting, I got the impression that a thorough and comprehensive metallurgical report would be submit-ed. It also appeared that the conclusions of the metal-lurgical report would probably be essentially negative l as far as the cause of failure is concerned. '
,e ,, .i.
.- j
'l Pags 4 cf 6 fa ra m eler, bn c.
CON SULTINo ENGINEERS e un onovt, WISCONSIN Mr. William C. Seidle May 26, 1970 To the writer it was not obvious at the meeting, that Ebasco had plans to report formally on their stress analysis as part of the entire failure analysis program.
We feel that such an analysis would probably turn out to be the salient part of the failure investigation; and if the licensee does not intend to present a com-bined stress-metallurgical evaluation, he should be encouraged to do so. The analysis should not rule out the valve discharge or " popping" mode of loading.
Convincing evidence must be developed to show that the valve did not pop, if this conviction is maintained.
The analysis in our report was prepared using assumptions and speculations as to the thrtat loads and specific dimensions of the discharge pipe. In a review of the applicant's analysis we would expect to find specific loads, dimensions, pressures, and temperatures and the references therefor.
- 3. Two possible contributors to the stress field in the vicinity of the failure would be the residual stress in the wcid (not stress releived) and the restraint of the backing ring (fused to the root of the weld).
Their effect should be treated at least qualitatively in a comprehensive analysis of the failure. The type and size of the backing ring should be described and i
the welding procedure reviewed in this regard. The location of the split (if any) and tacks for the back-ing ring would also be of interest.
i f WE have concluded on the basis of our trial analysis, and
' the non-authenticated information obtained during the May 15th meeting describing the present installation and the l circumstances of the failure at Robinson-2, that there NO exists a high probability of further failures with this design. Of course the surface condition and geometry of A the nozzles ( in the transition area), (presence of under-cuts, stress risers, etc. ), the ccndition of individual welds (and backing rings), the materisis properties of the
g g Pags 5 of 6 fa rbnn eler, bn c.
CONSULTING ENGINEER $
sta GaovE, wasCONSIN Mr. William C. Seidle May 25, 1970 installed components, ambient conditions, handling loads experienced,and many other indeterminants are all factors which could determine whether a valve fails.. The number of times a valve pops will certasiy increase its likelihood of failure. For these cyclic loads at high stresses, low cycle fatigre might become an initiating cause of failure. In any case, the connection appears to be i stressed much too high under the discharge condition to '
have any confidence in its realiability.. It should be pointed out that our trial analysis showed the high-est stressed point to be adjacent to the valve trans-ition section section just above the weld. The section just below the weld where failure was experienced was stressed just slightly lower.
No doubt a "fix" will be proposed which will either rein-force the valve attachment and/or provide additional a external support to the discharge pipe. The new design should be supported by a thorough analytical treatment and be reviewed by AEC Compliance. If the valve is welded to the doubler plate on the steam line, care should be i taken in the detail design to assure that a full pene-tration connection of sufficient area is made to the l steam pipe itself. The reinforcement of the opening i should be checked and structural discontinuity stresses l between the valve and the steam line calculated. In
! other words, it is not obvious that merely eliminat-ing the nozzle and/or providing a heavier attachment weld will assure an adequate design. A fundamental des-ign analysis for pressure, thermal, seismic," popping",
wind and weight loads must be made as a minimum check-off to validate the new design.
We hope to follow up on this memo with some published-i dimensional information and thrust data on the valves l
shortly.
I
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Pag 2 6 of 6 a r a rn e le r, bn c.
CONSULTING ENGINttes ELM OROVE, WISCONSIN Mr. Willian C. Seidle May 26, 1970 If you have any questions or comments on our report or the contents of this letter, or require additional investigation in any specific area, please do not hesitate to contact the writer or Mr. Walter Foley at our office at any time.
Very truly yours, P 4ETER, Inc.
\, .
a.-
C -
Richard A. Lofy, P.E.
Consulting Engineer l
DC-67afile
7
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Foreword rating for Safety valves is only 90% of the actual Safety Valves are intended to open amt close with- flow.' The total pressure drop shouhl not exceed 2%
in a narrow prewure range; therefore imtallatiom re- of the valve act pressume to avoid rapid cycling of
- quire careful and anurate planning both as to inlet the valve or chatter. The wall thickness of the inlet and diuharge piping. The higher the operating pres- piping mmt be heavy enough to sesist bending mo-sure and the greater she vahe capacity, the more ments due to reaction when the valve discharges. See critical becomes the need for proper design of, the Reaction Charts, pages 13 - 16.
installation. .
Discharge Piping inlet Piping The discharge piping from Safety valves shot!!d Safety Valves should always be mounted in a be equal in size to, or larger than, the nominal valve vertical position diratly on noules having a well- outlet and shouhl be as simple and direct as possible.
rounded approach that provides smooth, unobstructed llroken connections with gencrous clearances (see il-flow from the vessel or line to the valve. A Safety lustration) are prefeired. Suitable Drip Pan Elbows ...
Valve should NEVER be installed on a fitting having are shown on page 28, Catalog 402. The discharge pipe an inside diameter smaller than the inlet connecion above the Drip Pan should be farmly anchored to the to_ the valve, or on excessively long fittings.
building structure and should be sired adequately to The pressure drop ouurring in the inlet piping avoid " blow back" of steam from around the Drip '-
between the valve and pressure soune should be com-puted at actual flow of the valve. It is well to re- Pan into the boiler room when valve is discharging.
Design comiderations are included in an article member that the ASME Iloiter Code (Section 1) "Sidng Ven't ~i liping for Safety Vahes" by Mr. Max
9' FIXED SUPPORT "'. P"
' '" """$' W "E A g ANCHORED TO DUILDING suomng m ober $1. Qre pap, sng extends
. STRUCTURE to a considerable length, it may be necewa_ry to in.
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crease the pipe size at the upper part of the stack.
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' If Maxim Silemers are used to reduce the noise of
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- the discharging Safety Valves (see page 29, Catalog
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} 402), there will be no irurcased back prenure imposed
' due to the Silencer.
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Where flexible hose connections are used in place
( DISCHARGE i
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of or in conjunction with Drip Pans, they must be
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, of sufficient length and flexii>ility so as to absorb ex-c' M]Q DR:P PAN $ kr . parbion and impose no sir.iim on the valve outlet hw n -
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.,. 1 pressure.
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,,O' CROS8Y Am-( ,
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{ Vl= Reaction Force grcm3 9- g in Pounds NOTE: AHow sufficient Drains are located in the valve bodies and should
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be piped to a drainage system to remove condensate
from the valve bodies. Separate drains are required pen on the dis-
- ** ' ' ^ Recommended to drain the Drip Pan and on certain types of installa-fr$"not to e"x. *i"i m"
- b[Su$ INdY. tions additional drainage from the discharge piping '
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cced 2% cf valve tE"*" '""
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tic,ns of expan-must be provided.
r Hydrostatic Testing of Boilers ,
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1%OUNDED SMOOTH [ pleted before flanged inlet Safety Valves are installed, the boiler openings being blanked off.
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, CROSIW Style IICA Valves for supercritical pres- '
> Sures with welded inlets are shipped with Ilydrostatic ;
Recommended installation Test Plug and O. Rings for facilitating hydrostatic w G testing of the boiler. This also applies to all welded
' inlet
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SCOPE OF DESIGN
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4'00 PSIG Amt 5000 l'SIG PHESSURE CL ASSES - WEl DED INLET ONLY 450DT6000 HCWiDF HCATISW G 03 03~ TWelded 4"-300 ;
4500& 5000 HCA 117W HCA 11CW H" 0.785 2" -Welded ' 6" 300 ,[ 4 f .[
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4500 & 5000 HCA 1'17W HCA 118W J 1.237 2" Welded G"-300 " ,.
4500 & 5000 HCA 117W HCA 118W - g K? 1.833 2%" Welded 6"-300
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4500 & 5000 HCA 117W
- HCA 118W K' 2 2.545 2%" Welded 6"-300 ic -
4500 & 5000 HCA 117W HCA 118W M- 3.00 3"-Welded 8"-200 Y4 4500 & 5000 HCA 117W HCA 118W ~ M2 3.07G 3" -Welded 8"-300 4 '
, NOTE: P,otective Ho kis are availabie for att vaives for oEtdoor l> oiler service. See Caialog 402, sage 27 '**
For Capaceiv Tables see pages 18 thru 22 For Dunensions and Materals see belovv and p ,ge 8.
GENERAL. DIMENSIONS Unches) AND WElGHTS (Lbs.)
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4500 PSIG Amt 5000 PblG PHESSUHE CLASSES: INLET - WELDEO ~ OUILET - 300 LB. USAS HF 6 */ ' 4500 & 50'00 2 4 4% 4% 8 6% 33% 40%
% 11 .190 ,
? 4500 & 5000 2 5 5% G, 11 8% 41 ' 48 % 313 c 3G04
]a .r E 4500 & 5000 2 , 5% 6 6 11 8% 44 51 % ,
,13 'i 410 .'
+ Mu 4500 & 5000 2% 5%- 7 7% 12 10 00 ' 70 % 14 N 660'
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, , . 4500 & 5000 2% 6 7 7% 12 * '10 60 70 '"% ' '14 #
"680I 4500 & 5000 3 7 8 8 %' 2 000 I 13 ,; 10% G2 72 ;10 4500 6 5000 3 7 8 8 13 - 10% 62 72 % 10 030 i FIXED SUPPORT
, - ANCHoHED To 8UIL ING Body and inlet material: Style HCA 117W, A217 WCG, sinucmRE r'....
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, Style HCA 118W, A217 WC9. Materials for temperatures over 10500 F on application.
3 "B" dimensions are recommended minimum to with-M gI(;;[ g . stand stresses induced by pressure and by bending Cs _
L~ wvax j ' moments due to reaction wh6n valves are discharging. '
, l Larger values of B may be used if desired. Schedule pipe CJ' : *pst not, be used for safety valve nonles on boilers DISCHARGE -
hQ, PAPE N l because of ir,suf ficient wall thickness.
- m; DRIP PAN - "A" dimensions may b.e supplied %" oversize where!nlet
' C, ,O piping as such that excessive pressure drop can occur in piping so that the ring 1.D. is not less than "A" H --.
DRAIN dimension.
( CROSBY --m Charts showing outlet reaction forces are available on
( l pages 13-10.
k The moment arm (distance between vertical Center line P-
'_-Ti of valve and of outlet pipe) should be as short as
, E possible, and not greater than 24".
Q v LJ A n -+- 77
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