|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J3141999-10-15015 October 1999 Requests Emergency Publication of Document Entitled South Carolina Electric & Gas Co;Vc Summer Nuclear Station,Environ Assessment Transmitted on 991015 to Ofc of Fr for Publication ML20217J3281999-10-15015 October 1999 Forwards Copy of Environ Assessment & Finding of No Significant Impact Re Application for Exemption from Requiremets of 10CFR50,Section 50.60(a) for VC Summer Nuclear Station ML20217F8851999-10-0808 October 1999 Forwards Insp Rept 50-395/99-06 on 990801-0911.One Violation Occurred Being Treated as NCV RC-99-0192, Forwards Updated 1999 ECCS Evaluation Model Revs Rept for VC Summer Nuclear Station.Rept Is Being Submitted Pursuant to 10CFR50.46,which Requires Licensees to Notify NRC of Corrections to or Changes in ECCS Evaluation Models1999-09-28028 September 1999 Forwards Updated 1999 ECCS Evaluation Model Revs Rept for VC Summer Nuclear Station.Rept Is Being Submitted Pursuant to 10CFR50.46,which Requires Licensees to Notify NRC of Corrections to or Changes in ECCS Evaluation Models RC-99-0181, Forwards Anticipated Schedule for Operator Licensing Examinations.Sce&G Requests That NRC Prepare Examinations Stated on Attachment1999-09-21021 September 1999 Forwards Anticipated Schedule for Operator Licensing Examinations.Sce&G Requests That NRC Prepare Examinations Stated on Attachment ML20212C5091999-09-15015 September 1999 Forwards Anticipated Schedule for Operator Licensing Exams for Sce&G.Util Requests That NRC Prepare Exams on Encl RC-99-0184, Submits Seven Requests for Using Alternatives to Requirements of ASME Code,Section XI Re Subsection IWE & Iwl Insps to Be Performed at Vsns.Proposed Alternatives Will Provide Acceptable Level of Quality & Safety1999-09-15015 September 1999 Submits Seven Requests for Using Alternatives to Requirements of ASME Code,Section XI Re Subsection IWE & Iwl Insps to Be Performed at Vsns.Proposed Alternatives Will Provide Acceptable Level of Quality & Safety ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211Q8911999-09-0101 September 1999 Sumbits Summary of Training Managers Conference on Recent Changes to Operator Licensing Program.Meeting Covered Changes to Regulations,Exam Stds,New Insp Program & Other Training Issues.List of Attendees Encl RC-99-0177, Forwards Rev 2 to VC Summer Nuclear Station,Colr for Cycle 12, IAW Section 6.9.1.111999-08-31031 August 1999 Forwards Rev 2 to VC Summer Nuclear Station,Colr for Cycle 12, IAW Section 6.9.1.11 RC-99-0173, Requests That Info Listed in Rvid,Version 2,be Amended to Reflect Date for VC Summer Nuclear Station,As Marked in Encl to Ltr1999-08-31031 August 1999 Requests That Info Listed in Rvid,Version 2,be Amended to Reflect Date for VC Summer Nuclear Station,As Marked in Encl to Ltr ML20211L5181999-08-30030 August 1999 Forwards Insp Rept 50-395/99-05 on 990620-0731.One Violation Identified & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML20211H2481999-08-25025 August 1999 Forwards Four Controlled Copies of Amend 43 to Physcial Security Plan. Summary of Plan Changes, Are Included as Part of Each Controlled Copy.Encls Withheld Per 10CFR73.21 05000395/LER-1999-004, Submits Suppl 1 to LER 99-004-00 Re Discovery of Several Fuel Assembly Top Nozzle Holdown Screws Which Had Failed. Root Cause Will Not Be Completed by 990829,as Committed.W Analysis Will Be Issued After Fall Outages Are Complet1999-08-24024 August 1999 Submits Suppl 1 to LER 99-004-00 Re Discovery of Several Fuel Assembly Top Nozzle Holdown Screws Which Had Failed. Root Cause Will Not Be Completed by 990829,as Committed.W Analysis Will Be Issued After Fall Outages Are Completed RC-99-0171, Notifies NRC of Intent Re Submittal of Application to Renew OL of Vcs.Preparatory Work Has Begun to Develop Application for License Renewal to Be Submitted After 020806 Contingent Upon Final Approval of Board of Directors1999-08-23023 August 1999 Notifies NRC of Intent Re Submittal of Application to Renew OL of Vcs.Preparatory Work Has Begun to Develop Application for License Renewal to Be Submitted After 020806 Contingent Upon Final Approval of Board of Directors RC-99-0152, Seeks Exemption Under 10CFR0.12a(2)ii from 10CFR50,App G Requirements to Establish pressure-temperature Limits Curves Using Methodology Presented in 1989 ASME Section Xi,App G1999-08-19019 August 1999 Seeks Exemption Under 10CFR0.12a(2)ii from 10CFR50,App G Requirements to Establish pressure-temperature Limits Curves Using Methodology Presented in 1989 ASME Section Xi,App G RC-99-0164, Forwards semi-annual Fitness for Duty Rept from 990101 to 990630 for VC Summer Nuclear Station,Iaw 10CFR26.71(d)1999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Rept from 990101 to 990630 for VC Summer Nuclear Station,Iaw 10CFR26.71(d) ML20210Q4851999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006 at VC Summer.Requests Info Re Individuals Who Will Take Exam,Personnel Who Will Have Access to Exam.Sample Registration Ltr Encl ML20210R5501999-08-0505 August 1999 Ack Receipt of 990707 Response to NCVs Identified on 990607 Re Activities Conducted at VC Summer.Informs That After Consideration of Basis for Denial of NCV 50-395/99-03, Concluded,For Reasons Stated,That NCV Occurred RC-99-0156, Forwards Rev 1 to VC Summer Nuclear Station COLR for Cycle 12, IAW TS Section 6.9.1.11.Sections 2.1 & 3.0 Were Added to Include Beacon Tsm1999-08-0404 August 1999 Forwards Rev 1 to VC Summer Nuclear Station COLR for Cycle 12, IAW TS Section 6.9.1.11.Sections 2.1 & 3.0 Were Added to Include Beacon Tsm RC-99-0147, Submits Attached Request for Relief from Performing SG PORV Strike Time Testing to Acceptance Criteria of Asme/Ansi OMa-19881999-07-26026 July 1999 Submits Attached Request for Relief from Performing SG PORV Strike Time Testing to Acceptance Criteria of Asme/Ansi OMa-1988 ML20210B7451999-07-22022 July 1999 Informs That as Result of Staff Review of Licensee Responses to GL 92-01,rev 1 & Rev 1,suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 ML20210E3771999-07-16016 July 1999 Forwards Insp Rept 50-395/99-04 on 990509-0619.One Violation Being Treated as Noncited Violation RC-99-0127, Estimates Submittal of Eleven Licensing Actions in Fy 2000. Based on Statistical Estimates of Past Licensing Actions, Number of Licensing Actions in Fy 2001 Should Be Approx Ten, in Response to AL 99-021999-07-0707 July 1999 Estimates Submittal of Eleven Licensing Actions in Fy 2000. Based on Statistical Estimates of Past Licensing Actions, Number of Licensing Actions in Fy 2001 Should Be Approx Ten, in Response to AL 99-02 RC-99-0129, Provides Response to non-cited Violations Noted in Insp Rept 50-395/99-03.C/As:concluded That Cask Loading Pit Inaccessible & Duration of Dose Rates on Operating Floor of Fhb So Short That High Radiation Area Did Not Exist1999-07-0707 July 1999 Provides Response to non-cited Violations Noted in Insp Rept 50-395/99-03.C/As:concluded That Cask Loading Pit Inaccessible & Duration of Dose Rates on Operating Floor of Fhb So Short That High Radiation Area Did Not Exist RC-99-0131, Forwards Rev 9 to VC Summer Nuclear Station Safeguards Contingency Plan,Per 10CFR50.54(p).Encl Withheld1999-07-0707 July 1999 Forwards Rev 9 to VC Summer Nuclear Station Safeguards Contingency Plan,Per 10CFR50.54(p).Encl Withheld ML20210B7111999-07-0606 July 1999 Provides Summary of 990701 Meeting with Sce&G in Atlanta, Georgia Re Recent Virgil C Summer Refueling Outage & Other Items of Interest.List of Meeting Attendees & Licensee Presentation Handouts Encl RC-99-0114, Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps, Under Oath or Affirmation1999-06-30030 June 1999 Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps, Under Oath or Affirmation ML20195H5861999-06-0707 June 1999 Confirms 990604 Telcon Between J Proper & R Haag Re Meeting Scheduled for 990701 in Atlanta,Ga,To Discuss Plant Refueling Outage & Items of Interest ML20207H5241999-06-0707 June 1999 Forwards Insp Rept 50-395/99-03 on 990328-0508.Six Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20207D1881999-05-28028 May 1999 Informs That Effective 990524,K Cotton Assigned as Project Manager,Project Directorate II-1,for Virgil C Summer Nuclear Station 05000395/LER-1999-006, Forwards LER 99-006-00,describing Identified Safety Hazard with GE 7.2kV Magne-Blast Circuit Breakers.Event Is Being Reported Per 10CFR21.21a(1)1999-05-17017 May 1999 Forwards LER 99-006-00,describing Identified Safety Hazard with GE 7.2kV Magne-Blast Circuit Breakers.Event Is Being Reported Per 10CFR21.21a(1) RC-99-0104, Forwards Amend 17 to Training & Qualification Plan, Under Provisions of 10CFR50.54(p).Summary of Plan Changes Is Included as Part of Controlled Copy1999-05-13013 May 1999 Forwards Amend 17 to Training & Qualification Plan, Under Provisions of 10CFR50.54(p).Summary of Plan Changes Is Included as Part of Controlled Copy RC-99-0105, Forwards Copy of Sce&G Co 1998 Annual Financial Rept & Sc Public Service Authority 1998 Annual Financial Rept, for VC Summer Nuclear Station1999-05-13013 May 1999 Forwards Copy of Sce&G Co 1998 Annual Financial Rept & Sc Public Service Authority 1998 Annual Financial Rept, for VC Summer Nuclear Station 05000395/LER-1999-005, Forwards LER 99-005-00 for VC Summer Nuclear Station.Rept Describes Potential Condition for Exceeding Vsns Plant Design Basis Due to Submergence Qualification Issues for Certain ESF Components1999-05-12012 May 1999 Forwards LER 99-005-00 for VC Summer Nuclear Station.Rept Describes Potential Condition for Exceeding Vsns Plant Design Basis Due to Submergence Qualification Issues for Certain ESF Components ML20206L5121999-05-11011 May 1999 Informs That NRC Reorganized,Effective 990328.Reorganization Chart Encl ML20206P5771999-05-0707 May 1999 Informs That During 980519 Telcon Between T Matlosz & G Hopper,Arrangements Were Made for Administration of Licensing Exam at Virgil C Summer Nuclear Station During Wk of 990927 RC-99-0080, Submits Supplemental Info Re 970128 Response to NRC GL 96-06 Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Addl Analysis & Manpower Expenditure Involved Not Cost Effective1999-05-0606 May 1999 Submits Supplemental Info Re 970128 Response to NRC GL 96-06 Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Addl Analysis & Manpower Expenditure Involved Not Cost Effective RC-99-0097, Forwards Sce&G Cycle 12 COLR, IAW TS Section 6.9.1.111999-05-0606 May 1999 Forwards Sce&G Cycle 12 COLR, IAW TS Section 6.9.1.11 RC-99-0092, Informs That Util Has Reviewed Proposed Notice of Rulemaking & Fully Endorse Comments Prepared & Submitted on Behalf of Commercial Nuclear Power Industry by NEI1999-05-0303 May 1999 Informs That Util Has Reviewed Proposed Notice of Rulemaking & Fully Endorse Comments Prepared & Submitted on Behalf of Commercial Nuclear Power Industry by NEI RC-99-0090, Submits Special Rept (Spr 1999-003) Re Completion of ISI of SG Tubes,Indicating Number of Tubes Plugged or Repaired in Each Generator,Per TS 4.4.5.5.a & Section 4.4.5.5.b1999-04-29029 April 1999 Submits Special Rept (Spr 1999-003) Re Completion of ISI of SG Tubes,Indicating Number of Tubes Plugged or Repaired in Each Generator,Per TS 4.4.5.5.a & Section 4.4.5.5.b ML20206E1681999-04-29029 April 1999 Informs That FERC & NRC Will Conduct Category I Svc Water Pond (Swp) Dam Insp at Facility on 990610 ML20206P5021999-04-26026 April 1999 Forwards Insp Rept 50-395/99-02 on 990214-0327.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR 05000395/LER-1999-002, Forwards LER 99-002-00 Re Condition for Exceeding Vsns Design Basis During Surveillance Testing Utilizing Certain ECCS Valves.Simplified Flow Diagram Included to Identify Configurations Discussed by Rept Encl1999-04-12012 April 1999 Forwards LER 99-002-00 Re Condition for Exceeding Vsns Design Basis During Surveillance Testing Utilizing Certain ECCS Valves.Simplified Flow Diagram Included to Identify Configurations Discussed by Rept Encl ML20205T2311999-04-0909 April 1999 Informs That on 990318,A Koon & Ho Christensen Confirmed Initial Operator Licensing Exam Scheduled for Y2K.Initial Exam Date Schedules for Wk of 000807 for Approx Eight Candidates ML20205G4181999-04-0101 April 1999 Advises That 970725 Application & Affidavit Which Submitted, WCAP-14932, Probabilistic & Economic Evaluation of Reactor Vessel Closure Head Penetration Integrity for Plant, Will Be Withheld from Public Disclosure,Per 10CFR2.790(a)(4) RC-99-0078, Submits Summary of Present Levels of Property Insurance & Cash Flow Statement for VC Summer Nuclear Station,Per 10CFR50.54(w)(3) & 10CFR140.21(e)1999-04-0101 April 1999 Submits Summary of Present Levels of Property Insurance & Cash Flow Statement for VC Summer Nuclear Station,Per 10CFR50.54(w)(3) & 10CFR140.21(e) 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARRC-99-0192, Forwards Updated 1999 ECCS Evaluation Model Revs Rept for VC Summer Nuclear Station.Rept Is Being Submitted Pursuant to 10CFR50.46,which Requires Licensees to Notify NRC of Corrections to or Changes in ECCS Evaluation Models1999-09-28028 September 1999 Forwards Updated 1999 ECCS Evaluation Model Revs Rept for VC Summer Nuclear Station.Rept Is Being Submitted Pursuant to 10CFR50.46,which Requires Licensees to Notify NRC of Corrections to or Changes in ECCS Evaluation Models RC-99-0181, Forwards Anticipated Schedule for Operator Licensing Examinations.Sce&G Requests That NRC Prepare Examinations Stated on Attachment1999-09-21021 September 1999 Forwards Anticipated Schedule for Operator Licensing Examinations.Sce&G Requests That NRC Prepare Examinations Stated on Attachment ML20212C5091999-09-15015 September 1999 Forwards Anticipated Schedule for Operator Licensing Exams for Sce&G.Util Requests That NRC Prepare Exams on Encl RC-99-0184, Submits Seven Requests for Using Alternatives to Requirements of ASME Code,Section XI Re Subsection IWE & Iwl Insps to Be Performed at Vsns.Proposed Alternatives Will Provide Acceptable Level of Quality & Safety1999-09-15015 September 1999 Submits Seven Requests for Using Alternatives to Requirements of ASME Code,Section XI Re Subsection IWE & Iwl Insps to Be Performed at Vsns.Proposed Alternatives Will Provide Acceptable Level of Quality & Safety RC-99-0177, Forwards Rev 2 to VC Summer Nuclear Station,Colr for Cycle 12, IAW Section 6.9.1.111999-08-31031 August 1999 Forwards Rev 2 to VC Summer Nuclear Station,Colr for Cycle 12, IAW Section 6.9.1.11 RC-99-0173, Requests That Info Listed in Rvid,Version 2,be Amended to Reflect Date for VC Summer Nuclear Station,As Marked in Encl to Ltr1999-08-31031 August 1999 Requests That Info Listed in Rvid,Version 2,be Amended to Reflect Date for VC Summer Nuclear Station,As Marked in Encl to Ltr ML20211H2481999-08-25025 August 1999 Forwards Four Controlled Copies of Amend 43 to Physcial Security Plan. Summary of Plan Changes, Are Included as Part of Each Controlled Copy.Encls Withheld Per 10CFR73.21 05000395/LER-1999-004, Submits Suppl 1 to LER 99-004-00 Re Discovery of Several Fuel Assembly Top Nozzle Holdown Screws Which Had Failed. Root Cause Will Not Be Completed by 990829,as Committed.W Analysis Will Be Issued After Fall Outages Are Complet1999-08-24024 August 1999 Submits Suppl 1 to LER 99-004-00 Re Discovery of Several Fuel Assembly Top Nozzle Holdown Screws Which Had Failed. Root Cause Will Not Be Completed by 990829,as Committed.W Analysis Will Be Issued After Fall Outages Are Completed RC-99-0171, Notifies NRC of Intent Re Submittal of Application to Renew OL of Vcs.Preparatory Work Has Begun to Develop Application for License Renewal to Be Submitted After 020806 Contingent Upon Final Approval of Board of Directors1999-08-23023 August 1999 Notifies NRC of Intent Re Submittal of Application to Renew OL of Vcs.Preparatory Work Has Begun to Develop Application for License Renewal to Be Submitted After 020806 Contingent Upon Final Approval of Board of Directors RC-99-0152, Seeks Exemption Under 10CFR0.12a(2)ii from 10CFR50,App G Requirements to Establish pressure-temperature Limits Curves Using Methodology Presented in 1989 ASME Section Xi,App G1999-08-19019 August 1999 Seeks Exemption Under 10CFR0.12a(2)ii from 10CFR50,App G Requirements to Establish pressure-temperature Limits Curves Using Methodology Presented in 1989 ASME Section Xi,App G RC-99-0164, Forwards semi-annual Fitness for Duty Rept from 990101 to 990630 for VC Summer Nuclear Station,Iaw 10CFR26.71(d)1999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Rept from 990101 to 990630 for VC Summer Nuclear Station,Iaw 10CFR26.71(d) RC-99-0156, Forwards Rev 1 to VC Summer Nuclear Station COLR for Cycle 12, IAW TS Section 6.9.1.11.Sections 2.1 & 3.0 Were Added to Include Beacon Tsm1999-08-0404 August 1999 Forwards Rev 1 to VC Summer Nuclear Station COLR for Cycle 12, IAW TS Section 6.9.1.11.Sections 2.1 & 3.0 Were Added to Include Beacon Tsm RC-99-0147, Submits Attached Request for Relief from Performing SG PORV Strike Time Testing to Acceptance Criteria of Asme/Ansi OMa-19881999-07-26026 July 1999 Submits Attached Request for Relief from Performing SG PORV Strike Time Testing to Acceptance Criteria of Asme/Ansi OMa-1988 RC-99-0129, Provides Response to non-cited Violations Noted in Insp Rept 50-395/99-03.C/As:concluded That Cask Loading Pit Inaccessible & Duration of Dose Rates on Operating Floor of Fhb So Short That High Radiation Area Did Not Exist1999-07-0707 July 1999 Provides Response to non-cited Violations Noted in Insp Rept 50-395/99-03.C/As:concluded That Cask Loading Pit Inaccessible & Duration of Dose Rates on Operating Floor of Fhb So Short That High Radiation Area Did Not Exist RC-99-0131, Forwards Rev 9 to VC Summer Nuclear Station Safeguards Contingency Plan,Per 10CFR50.54(p).Encl Withheld1999-07-0707 July 1999 Forwards Rev 9 to VC Summer Nuclear Station Safeguards Contingency Plan,Per 10CFR50.54(p).Encl Withheld RC-99-0127, Estimates Submittal of Eleven Licensing Actions in Fy 2000. Based on Statistical Estimates of Past Licensing Actions, Number of Licensing Actions in Fy 2001 Should Be Approx Ten, in Response to AL 99-021999-07-0707 July 1999 Estimates Submittal of Eleven Licensing Actions in Fy 2000. Based on Statistical Estimates of Past Licensing Actions, Number of Licensing Actions in Fy 2001 Should Be Approx Ten, in Response to AL 99-02 RC-99-0114, Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps, Under Oath or Affirmation1999-06-30030 June 1999 Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps, Under Oath or Affirmation 05000395/LER-1999-006, Forwards LER 99-006-00,describing Identified Safety Hazard with GE 7.2kV Magne-Blast Circuit Breakers.Event Is Being Reported Per 10CFR21.21a(1)1999-05-17017 May 1999 Forwards LER 99-006-00,describing Identified Safety Hazard with GE 7.2kV Magne-Blast Circuit Breakers.Event Is Being Reported Per 10CFR21.21a(1) RC-99-0104, Forwards Amend 17 to Training & Qualification Plan, Under Provisions of 10CFR50.54(p).Summary of Plan Changes Is Included as Part of Controlled Copy1999-05-13013 May 1999 Forwards Amend 17 to Training & Qualification Plan, Under Provisions of 10CFR50.54(p).Summary of Plan Changes Is Included as Part of Controlled Copy RC-99-0105, Forwards Copy of Sce&G Co 1998 Annual Financial Rept & Sc Public Service Authority 1998 Annual Financial Rept, for VC Summer Nuclear Station1999-05-13013 May 1999 Forwards Copy of Sce&G Co 1998 Annual Financial Rept & Sc Public Service Authority 1998 Annual Financial Rept, for VC Summer Nuclear Station 05000395/LER-1999-005, Forwards LER 99-005-00 for VC Summer Nuclear Station.Rept Describes Potential Condition for Exceeding Vsns Plant Design Basis Due to Submergence Qualification Issues for Certain ESF Components1999-05-12012 May 1999 Forwards LER 99-005-00 for VC Summer Nuclear Station.Rept Describes Potential Condition for Exceeding Vsns Plant Design Basis Due to Submergence Qualification Issues for Certain ESF Components RC-99-0097, Forwards Sce&G Cycle 12 COLR, IAW TS Section 6.9.1.111999-05-0606 May 1999 Forwards Sce&G Cycle 12 COLR, IAW TS Section 6.9.1.11 RC-99-0080, Submits Supplemental Info Re 970128 Response to NRC GL 96-06 Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Addl Analysis & Manpower Expenditure Involved Not Cost Effective1999-05-0606 May 1999 Submits Supplemental Info Re 970128 Response to NRC GL 96-06 Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions. Addl Analysis & Manpower Expenditure Involved Not Cost Effective RC-99-0092, Informs That Util Has Reviewed Proposed Notice of Rulemaking & Fully Endorse Comments Prepared & Submitted on Behalf of Commercial Nuclear Power Industry by NEI1999-05-0303 May 1999 Informs That Util Has Reviewed Proposed Notice of Rulemaking & Fully Endorse Comments Prepared & Submitted on Behalf of Commercial Nuclear Power Industry by NEI RC-99-0090, Submits Special Rept (Spr 1999-003) Re Completion of ISI of SG Tubes,Indicating Number of Tubes Plugged or Repaired in Each Generator,Per TS 4.4.5.5.a & Section 4.4.5.5.b1999-04-29029 April 1999 Submits Special Rept (Spr 1999-003) Re Completion of ISI of SG Tubes,Indicating Number of Tubes Plugged or Repaired in Each Generator,Per TS 4.4.5.5.a & Section 4.4.5.5.b 05000395/LER-1999-002, Forwards LER 99-002-00 Re Condition for Exceeding Vsns Design Basis During Surveillance Testing Utilizing Certain ECCS Valves.Simplified Flow Diagram Included to Identify Configurations Discussed by Rept Encl1999-04-12012 April 1999 Forwards LER 99-002-00 Re Condition for Exceeding Vsns Design Basis During Surveillance Testing Utilizing Certain ECCS Valves.Simplified Flow Diagram Included to Identify Configurations Discussed by Rept Encl RC-99-0078, Submits Summary of Present Levels of Property Insurance & Cash Flow Statement for VC Summer Nuclear Station,Per 10CFR50.54(w)(3) & 10CFR140.21(e)1999-04-0101 April 1999 Submits Summary of Present Levels of Property Insurance & Cash Flow Statement for VC Summer Nuclear Station,Per 10CFR50.54(w)(3) & 10CFR140.21(e) RC-99-0066, Submits Rept of Status of Decommissioning Funding (RR-1950), for Vsns Per 10CFR50.751999-03-31031 March 1999 Submits Rept of Status of Decommissioning Funding (RR-1950), for Vsns Per 10CFR50.75 ML20205B9981999-03-29029 March 1999 Informs That Authority & Sce&G Has Ownership Interests of one-third & two-thirds,respectively in VC Summer Nuclear Station.Operating License Scheduled to Expire in 2022.Rept Addresses Decommissioning Cost Estimates & Financing RC-99-0054, Forwards Rev 2 to VC Summer Nuclear Station Training Simulator Quadrennial Certification Rept,1996-99, Per 10CFR55.45(b)(5)(ii)1999-03-22022 March 1999 Forwards Rev 2 to VC Summer Nuclear Station Training Simulator Quadrennial Certification Rept,1996-99, Per 10CFR55.45(b)(5)(ii) RC-99-0053, Requests That Implementation Date of Proposed TS Change Request Re Best Estimate Analyzer for Core Operations - Nuclear (Beacon) Be Extended. Util Requests 120 Day Time Frame to Perform Initial Beacon Calibrs During Cycle 121999-03-22022 March 1999 Requests That Implementation Date of Proposed TS Change Request Re Best Estimate Analyzer for Core Operations - Nuclear (Beacon) Be Extended. Util Requests 120 Day Time Frame to Perform Initial Beacon Calibrs During Cycle 12 RC-99-0048, Informs That Util Has Implemented Policy That Requires All Personnel Granted Unescorted Access to Vsns Satisfactorily Complete Test on Site Specific Info1999-03-10010 March 1999 Informs That Util Has Implemented Policy That Requires All Personnel Granted Unescorted Access to Vsns Satisfactorily Complete Test on Site Specific Info ML20207J5661999-02-16016 February 1999 Requests That Proprietary Rev 1 to WCAP-14932 Re Rv Closure Head Penetrations Integrity for VC Summer Nuclear Plant,Be Withheld from Public Disclosure,Per 10CFR2.790(b)(4) RC-99-0026, Provides Response to NRC RAI Re TS Change Request Re Best Estimate Analyzer for Core Operations - Nuclear1999-02-0505 February 1999 Provides Response to NRC RAI Re TS Change Request Re Best Estimate Analyzer for Core Operations - Nuclear RC-99-0023, Informs That in Response to GL 97-06,SCE&G Informed NRC of Plan to Perform Secondary Side Examination Scheduled for Refueling Outage RF-11.SCE&G Has Decided to Defer Secondary Side Insp of Sg.Reasons for Change of Plan Listed1999-02-0101 February 1999 Informs That in Response to GL 97-06,SCE&G Informed NRC of Plan to Perform Secondary Side Examination Scheduled for Refueling Outage RF-11.SCE&G Has Decided to Defer Secondary Side Insp of Sg.Reasons for Change of Plan Listed 05000395/LER-1998-009, Forwards LER 98-009-01 for VC Summer Nuclear Station.Rept Describes Unanalyzed Condition for non-safety Related Component for Which All Failure Mechanisms Had Not Been Evaluated1999-01-28028 January 1999 Forwards LER 98-009-01 for VC Summer Nuclear Station.Rept Describes Unanalyzed Condition for non-safety Related Component for Which All Failure Mechanisms Had Not Been Evaluated RC-99-0015, Forwards Amend 16 to Training & Qualification Plan,Per 10CFR50.54(p).Summary of Changes,Encl1999-01-22022 January 1999 Forwards Amend 16 to Training & Qualification Plan,Per 10CFR50.54(p).Summary of Changes,Encl RC-99-0005, Responds to 980908 RAI Re GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations1999-01-15015 January 1999 Responds to 980908 RAI Re GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations RC-98-0225, Forwards Rev 41 to EP-100, Radiation Emergency Plan. List of Changes by Page Number Affected by Rev 41 Also Encl1998-12-14014 December 1998 Forwards Rev 41 to EP-100, Radiation Emergency Plan. List of Changes by Page Number Affected by Rev 41 Also Encl RC-98-0226, Forwards Amend 42 to Psp.Changes Do Not Degrade Safeguards Effectiveness in PSP or Safeguards Contingency Plan,As Described in 10CFR50.54(p).Without Encl1998-12-14014 December 1998 Forwards Amend 42 to Psp.Changes Do Not Degrade Safeguards Effectiveness in PSP or Safeguards Contingency Plan,As Described in 10CFR50.54(p).Without Encl RC-98-0216, Requests Extension of Response Period to 990115 to Respond to NRC 980908 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Util Intends to Utilize Industry Generic RAI Response1998-12-0404 December 1998 Requests Extension of Response Period to 990115 to Respond to NRC 980908 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Util Intends to Utilize Industry Generic RAI Response RC-98-0189, Provides Assessment Results of GL 98-02, Loss of Rc Inventory & Associated Potential for Loss of Emergency Mitigation Functions While in Shutdown Condition, Per 10CFR50.54f1998-11-24024 November 1998 Provides Assessment Results of GL 98-02, Loss of Rc Inventory & Associated Potential for Loss of Emergency Mitigation Functions While in Shutdown Condition, Per 10CFR50.54f RC-98-0207, Forwards 120-day Response to NRC GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment1998-11-11011 November 1998 Forwards 120-day Response to NRC GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment RC-98-0177, Informs That Sce&G Will Classify as Moderate Any Stratification Condition That Results in Total Cuf,Based on Design Basis Values Plus Any Contribution from Stratification,Of Between 0.1 & 0.71998-11-0909 November 1998 Informs That Sce&G Will Classify as Moderate Any Stratification Condition That Results in Total Cuf,Based on Design Basis Values Plus Any Contribution from Stratification,Of Between 0.1 & 0.7 RC-98-0194, Provides Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs1998-11-0202 November 1998 Provides Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Movs RC-98-0202, Forwards Response to RAI Re Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1998-10-30030 October 1998 Forwards Response to RAI Re Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions RC-98-0186, Expresses Appreciation for Opportunity to Present Topical Rept TR-104965, On-Line Monitoring of Instrument Channel Performance1998-10-26026 October 1998 Expresses Appreciation for Opportunity to Present Topical Rept TR-104965, On-Line Monitoring of Instrument Channel Performance RC-98-0185, Forwards non-proprietary Trs,Including Rev 0 to WCAP-15101, Analysis of Capsule W from Sce&G VC Summer Unit 1 Rv Radiation Surveillance Program & Rev 0 to WCAP-15103, Evaluation of PTS for VC Summer Unit 11998-10-0909 October 1998 Forwards non-proprietary Trs,Including Rev 0 to WCAP-15101, Analysis of Capsule W from Sce&G VC Summer Unit 1 Rv Radiation Surveillance Program & Rev 0 to WCAP-15103, Evaluation of PTS for VC Summer Unit 1 RC-98-0182, Responds to 980402 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs1998-10-0808 October 1998 Responds to 980402 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs RC-98-0178, Provides Comments on SALP Insp Rept 50-395/98-99.Util Ack That Station Can Enhance Future Performance Further with More Focus & Attention on Change Mgt Practices Re Plant & Procedure Changes1998-10-0505 October 1998 Provides Comments on SALP Insp Rept 50-395/98-99.Util Ack That Station Can Enhance Future Performance Further with More Focus & Attention on Change Mgt Practices Re Plant & Procedure Changes 1999-09-28
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20247M8281989-04-28028 April 1989 Requests That Proprietary WCAP-12189, Resistance Temp Detector Bypass Elimination Licensing Rept for VC Summer Nuclear Station Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20236A6471989-02-21021 February 1989 Forwards Affidavit Requesting That Encl Change C to Rev 7 to PCP-001, Process Control Program for Progressive Wet Waste Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20153D6591988-08-22022 August 1988 Forwards Affidavit Requesting Withholding of Proprietary Info from Semiannual Effluent & Waste Disposal Rept for 1988 ML20151M3331988-07-15015 July 1988 Submits Application for Withholding Proprietary WCAP-11857, Tubesheet Region Tube Alternate Plugging (L*) Criteria for Steam Generators in VC Summer Nuclear Station ML20148H0701988-03-21021 March 1988 Requests That Proprietary Rev 0 to WCAP-8687, Qualification of ATWS Mitigating Sys Actuation Circuitry in Std Seismic Cabinet Be Withheld from Public Disclosure (Ref 10CFR2.790) LD-88-001, Corrects Record Re Info Previously Provided in Re post-accident Uncertainties Associated W/Core Exit Thermocouple Sys Supplied by C-E.NRC Should Disregard Inclusion of Plant in Previous Info Package1988-01-0707 January 1988 Corrects Record Re Info Previously Provided in Re post-accident Uncertainties Associated W/Core Exit Thermocouple Sys Supplied by C-E.NRC Should Disregard Inclusion of Plant in Previous Info Package ML20154J5171987-12-0303 December 1987 Application for Withholding Proprietary WCAP-11656, Westinghouse Improved Thermal Design Procedure Instrument Uncertainty Methodology, from Public Disclosure,Per 10CFR2.790(b)(4) ML20238A0271987-08-20020 August 1987 Forwards Affidavit in Ref to Semiannual Effluent & Waste Disposal Rept for 1987. Affidavit Covers Proprietary Procedures Submitted as Part of Subj Rept & Portion of Rept Directly Ref Proprietary Matls ML20211A9731986-09-25025 September 1986 Advises That Safety Evaluation Supporting Implementation of Fission Product Barrier Approach to Emergency Event Classification... & NRC 860813 Encls Proprietary (Ref 10CFR2.790) NRC-86-3160, Submits Updated List of Plants Affected by Changes in ECCS Evaluation Model Described in Rev 1 to Addendum 3 to WCAP-9561-P1986-09-0808 September 1986 Submits Updated List of Plants Affected by Changes in ECCS Evaluation Model Described in Rev 1 to Addendum 3 to WCAP-9561-P ML20209G2221986-08-0101 August 1986 Requests That WCAP-11228-P, Tubesheet Region Plugging Criterion for Full Depth Hardroll Expanded Tubes, Be Withheld from Public Disclosure (Ref 10CFR2.790).Affidavit Encl ML20138D0481985-10-0909 October 1985 Requests Withholding Proprietary Rept Re Tubesheet Region Plugging Criterion for Full Depth Hardroll Expanded Tubes, from Public Disclosure (Ref 10CFR2.790) ML20137P5441985-09-0909 September 1985 Forwards Affidavit Re Confidential Info & Trade Secrets Contained in Dewatering & Waste Processing Control Procedures Submitted in South Carolina Electric & Gas 850830 Semiannual Effluent & Waste Disposal Rept ML20116D0761985-04-0202 April 1985 Requests Proprietary Rev 0 to Suppl 2-NP to WCAP-10170, Westinghouse Technical Support Complex Design & V & V Process for VC Summer Nuclear Station, Be Withheld (Ref 10CFR2.790) ML20099H6201985-01-16016 January 1985 Forwards Affidavit for Withholding Proprietary Version of VC Summer Pressure Pulsation Analysis Re Fatigue Usage of Steam Generator Preheater Mod, Per 10CFR2.790 ML20101F5471984-11-27027 November 1984 Requests Info Re Radial Peaking Factor Limit Transmitted in South Carolina Electric & Gas Co Be Withheld (Ref 10CFR2.790) ML20028G2931983-01-27027 January 1983 Application for Withholding Proprietary SGP-9.2-3009R, VC Summer Station Interim Power Operation Evaluation Rept. Affidavit Encl ML20065L6291982-09-30030 September 1982 Forwards Affidavit Requesting Interim Power Operation Evaluation Rept Be Withheld (Ref 10CFR2.790) ML20055A9801982-06-28028 June 1982 Forwards Westinghouse Evaluation of Reactor Vessel Level Indication Sys Performance at Semiscale Test Facility for Test S-1B-1 & Virgil C Summer Reactor Vessel Level Instrumentation Sys Functional Test ML20050B1751982-03-22022 March 1982 Forwards Revision 1 to Mobile Cement Solidification Sys Topical Rept CNSI-2. Proprietary Version Withheld (Ref 10CFR2.790).W/o Stated Affidavit ML20038A6531981-11-0909 November 1981 Forwards Proprietary & Nonproprietary Versions of Cement Solidification Topical Rept in Conjunction W/Facility 811030 OL Application ML20038A6551981-11-0909 November 1981 Requests That Proprietary Version of Cement Solidification Topical Rept Be Withheld (Ref 10CFR2.790). Affidavit Encl ML20038B6061981-11-0606 November 1981 Requests That Proprietary Version of WCAP-9912, Steam Generator Tube Plugging Margin Analysis for Virgil C Summer Nuclear Power Plant Unit 1 Be Withheld from Public Disclosure (Ref 10CFR2.790).Related Affidavit Encl ML19340D7831980-12-23023 December 1980 Requests Summary Rept,Westinghouse Reactor Vessel Level Instrumentation Sys for Monitoring Inadequate Core Cooling, (7300 Sys), Dtd Dec 1980 Be Withheld (Ref 10CFR2.790) Per Previously Submitted Application AW-77-18 Approved 771028 ML19318A0621980-05-0808 May 1980 Confirms 800508 Telcon W/E Blackwood Re Substantial Safety Hazard Notification Per 10CFR21.Discusses Westinghouse Charging Pump Operation & Interim Mods for 3-loop & 4-loop, Operating & Nonoperating Plants ML19256G2431979-11-15015 November 1979 Confirms Westinghouse 791115 Telephone Notification Re Rod Drop Analysis.Sar Analysis May Not Represent Most Limiting Assumption for Credible Single Failure.Forwards Info Identifying Affected Westinghouse Plants.W/O Encl ML19246B0221979-06-14014 June 1979 Discusses Noncompliance W/Qa Procedures Specified on Purchase Orders for Limit Switches Received from Butler & Land,Anchor Darling Valve Co & Bradner Industries.Will Replace Switches within 45 Days ML19241A8071979-04-24024 April 1979 Responds to IE Bulletins 78-12 & 12A.Forwards Rept on All Completed Reactor Vessels.W/O Encl ML19289E6271979-03-23023 March 1979 in Response to 780922 Part 21 Rept,Informs That Injection Pumps Were Removed & Inspected Using Newly Established Criteria of Suppl 2, & Were Reinstalled on Engines.No Further Action Contemplated ML19289E6241979-03-22022 March 1979 Notification of Test Results Indicated in 780922 Part 21 Rept.Cites Three Causes of Injection Pump Failure.Concludes Pumps Are Now Adequate.No Further Action Contemplated ML20147D7281978-12-0101 December 1978 Forwards Affidavit of R Wiesemann,Providing Info Necessary to Make Proprietary Determination Under 10CFR2.790(b) 1989-04-28
[Table view] |
Text
.
ATTACHMENT T rr October 9, 1985 c CAW-85-069 Mr. Harol 3 R. Denton, Director Office cf Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DIS 10SURE
Subject:
Tubesheet Region Plugging Criterion For Full Depth Hardroll Expanded Tubes
Reference:
South Carolina Electric & Gas Company Letter to NRC Dated October 1985
Dear Mr. Denton:
The proprietary material for which withholding is being requested in the referenced letter by South Carolina Electric & Gas Company is further identified in an affidavit signed by the owner of the proprietary information, Westinghouse Electric Corporstion. The affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Comission and addresses with specificity the considerations listed in paragraph (b)(4) of 10CFR Section 2.790 of the Commission's regulations.
The proprietary material for which withholding is being required is of the same technical type as' that proprietary material previously submitted with Application for Withholding CAW-81-79 Accordingly, this letter authorizes the utilization of the accompanying affidavit by South Carolina Electric & Gas Company. '
Correspondence with respect to the proprietary aspects of the application for 4
withholding or the Westinghouse affidavit should reference this letter,
, CAW-85-069, and should be addressed to the tridersigned.
Very truly yours, Ro t - Wiesemann, Manager l Regulatory & Legislative Affairs i
/1sv Enclosures l
cc: E. C. Shomaker, Esq.
l Office of the Executive Legal Director, NRC l
8510230155 851016 PDR ADOCK 05000395 P PDR L
, CAW-81-79 AFFIDAV!T !
COMMONWEALTH OF PENNSYLVANIA:
ss COUNTY OF ALLEGHENY:
Before me, the undersigned authority, personally appeared Robert A. Wiesemann, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Corporation (" Westinghouse") and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, infonnation, and belief:
eA nmA Robert A. Wiesemann, Manager Regulatory and Legislative Affairs Sworn to and subscribed l before me this 2 day of D u r./a 1981.
._/
! f. ' 'it?. .. u /s wsy
- . Notary Pub'lic f 1.*
- CAW-81-79 (1) I am Manager, Regulatory and Legislative Affairs, in the Nuclear Technology Division, of Westinghouse Electric Corporation and as such, I have been specifically delegated the function of reviewing 3 the proprietary information sought to be withheld from public dis- l closure in connection with nuclear power plant licensing or rule-making proceedings, and am authorized to apply for its withholding on behalf of the Westinghouse Water Reactor Divisions.
(2) I am making this , Affidavit in conformance with the provisions of 10CFR Section 2.790 of the Commission's regulations and in con-junction with the Westinghouse application for withholding ac-companying this Affidavit.
I (3) I have personal knowledge of the criteria and procedures utilized by Westinghouse Nuclear Energy Systems in designating information as a trade secret, privileged or as confidential commercial or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the in-formation sought to be withheld from public disclosure should be withheld.
(i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghous'e.
1 f
J t
CAW-81-79 (ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public.
Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilize,s a system to determine when and whether to hold certain types of information in confidence.
The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.
Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential com-petitive advantage, as follows:
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.)
where prevention of its use by any of Westinghouse's competitors without license from Westinghouse consti-tutes a competitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.
l l
l 1
CAW-81-79 (c) Its use by a competitor would reduce his expenditure of resources or improve his ccmpetitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
(d) It reveals cost or price information, production cap-acities, budget levels, or connercial strategies of Westinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or future West-inghouse or customer funded development plans and pro-grams of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent pro-tection may be desirable.
(g) It is not the property of Westinghouse, but must be treated as proprietary by Westinghouse according to agreements with the owner.
There are sound policy reasons behind the Westinghouse system which include the following:
(a) The use of such information by Westinghouse gives Westinghouse a corpetitive advantage over its com-petitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position!
l l
l l
I
CAW-81-79 l
I (b) It is information which is marketable in many ways. f The extent to which such infomation is available to '
competitors diminishes the Westinghouse ability to !
sell products and services involving the use of the infomation. ;
I i
(c) Use by our competitor would put Westinghouse at a
[
competitive disadvantage by reducing his expenditure
- of resources at our expense.
(d) Each component of proprietary infonnation pertinent to a particular competitive advantage is potentially !
as valuable as the total competitive advantage. If l competitors acquire components of proprietary infor- l mation, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive !
advantage. I (e) Unrestricted disclosure would jeopardize the position i of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition ,
in those countries. !
L (f) The Westinghouse capacity to invest corporate assets -
in research and development depends upon the success !
in obtaining and maintaining a competitive advantage. !
I
[
l [
i e
r CAW-81-79 !
i (iii) The information is being transmitted to the Comission in confidence and, under the provisions of 10CFR Section 2.790, it is to be received in confidence by the Comission. .
(iv) The information sought to be protected is not available in
- i public sources or available information has not been pre-
{
viously employed in tne same original manner or method to '
the best of our knowledge and belief. :
i (v) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in " Steam ;
Generator Tube Plugging Margin Analysis" for the Virgil C.
Sumer Nuclear Power Plant Unit No.1. WCAP-9912. Revi-sion 2 (Proprietary) being transmitted by South Carolina ;
Electric and Gas Company letter Application for Withholding Proprietary Information from Public Disclosure Nichols to !
Denton, November 1981. The proprietary infomation as sub- t mitted for South Carolina Electric and Gas Company, Virgil C.
Sumer Nuclear Station use is expected to be applicable in othar licensee and applicant submittals in response to cer- "
i tain NRC requirements for justification of the steam i generator tube plugging margin.
This infomation is part of that which will enable Westing-house to: ;
(a) Provide documentation of the analyses, method and test-ing for determining plugging margin. t P
k CAW-81-79 1
I (b) Establish the minimum wall thickness in compliance with !
Regulatory Guide 1.121. !
(c) Establish the stress limits versus thinning of the remaining tube wall.
(d) Establish the maximum allowable leakage in support of
. the leak-before-break criteria.
(e) Assist the customer to obtain NRC approval.
i Further this information has substantial commercial value as follows: i (a) Westinghouse plans to sell similar information to its customers for purposes of meeting NRC requirements for licensing documentation.
i i
(b) Westinghouse can sell support and defense of the tech-nology to its customers in the licensing process.
Public disclosure of this infonnation is likely to cause f
substantial harm to the competitive position of Westinghouse !
because it would enhance the ability of competitors to pro- -
vide similar analytical documentation and licensing defense services for commercial power reactors without commensur' ate expenses. Also, public disclosure of the information would enable others to use the information to meet NRC require-ments for licensing documentation without purchasing the -
right to use the information. '
I i
i
CAW-81-79 The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse effort and the expenditure of a considerable sum of money.
In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended for system d'esign software development.
~
Further the deponent sayeth not.
l l
I l
l
ATTACHMENT IV No Significant Hazards Determination
- 1. Does the proposed amendment invol"e a significant increase in the probability or consequences of an accident ,previously evaluated?
No.
The supporting P* evaluation demonstrates that the presence of the tubesheet will complement tube integrity in that region by precluding tube deformation beyond its initial outside diameter. The resistance to both tube rupture and tube collapse behavior is strengthened by the presence of the tubesheet in that region. Furthermore, the existing Technical Specification leakage rate requirements remain in place in the unlikely event leakage from this region does occur.
- 2. Does the proposed amendment create the possibility of a new cr different kind of accident from any accident previously evaluated?
No.
The enclosed supporting evaluation demonstrates that following the P*
criteria minimizes the potential for any possible tubesheet area tube indications that may exist from creating any type of accident condition.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
No.
As demonstrated in the attached evaluation, integrity of ~the tube bundle under both normal and postulated accident conditions will continue to be maintained. Current Technical Specification leakage rate limitations will continue to be met; therefore, any leakages will be limited to ensure safety margins are preserved.
In addition to the above supporting ~ conclusions, 'the proposed change to allow for repair of tubes according to an NRC approved sleeving method is considered to have a no significant hazards determination. The change will not involve a s ignificant increase in the probability or consequences of a new or previously evaluated accident because only an NRC approved sleeving method will be utilized for tube repair. This approved method will allow the plant to function in a manner which is consistent with normal and any postulated accident conditions.
The proposed change does not involve a significant reduction in a margin of safety because it only allows SCE&G-the option of utilizing another acceptable method of tube repair. Any repair method will have to be demonstrated to the Staff to be a satisfactory alternative to tube plugging.
l l
l