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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
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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:UTILITY TO NRC
MONTHYEARML20059K4071990-09-17017 September 1990
Advises That Author Succeeded Os Bradham as vice-president, Nuclear Operations,Effective 900915.All Correspondence to Util Should Be Sent to Listed Address
ML20059J9141990-09-14014 September 1990
Responds to Violations Noted in Insp Rept 50-395/90-21. Violation Occured,However Description of Violation in Error. Corrective Action:Valve XVT02803B Placed in Proper Position & Verification of Emergency Feedwater Sys Lineup Completed
ML20059E2821990-08-30030 August 1990
Advises That Programmed Enhancements Per Generic Ltr 88-17 Re Loss of DHR Implemented & Mods Operable
ML20059D6911990-08-29029 August 1990
Forwards Technical Rept 90-02, Seismic Activity Near VC Summer Nuclear Station for Apr-June 1990
ML20059B9541990-08-28028 August 1990
Forwards Semiannual Effluent & Waste Disposal Rept for Jan-June 1990, Per 10CFR50.36a & Sections 6.9.1.8 & 6.9.1.9 of Tech Spec
ML20056B4901990-08-22022 August 1990
Discusses NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Decision on Future Insp Frequency &/Or Sys Mods Should Be Deferred Until Internal Components Could Be Inspected
ML20059A2041990-08-16016 August 1990
Forwards First Semiannual fitness-for-duty Rept from 900103- 0630.Util Pleased W/Program,However,Concerned About Incorrect Test Results for Blind Performance Specimens Received from Roche Labs
ML20058P6581990-08-15015 August 1990
Forwards Monthly Operating Rept for Jul 1990 & Rev 13 to ODCM for Virgil C Summer Nuclear Station.Rev Implements Changes Necessary to Permit Removal of Radiological Effluent Specs from Tech Specs as Recommended by Generic Ltr 89-01
ML20058P7681990-08-13013 August 1990
Forwards Mods to 900516 Tech Spec Change Request Re Pressurizer Code Safety Valve Setpoint Tolerance & Mode 3 Exception,Per 900713 Telcon.Changes Do Not Affect Technical Intent of 900516 Submittal Nor Alter Safety Evaluation
ML20058N6961990-08-10010 August 1990
Responds to Violations Noted in Insp Rept 50-395/90-18. Corrective Action:Personnel Counseled on Procedural Compliance & Importance of Independent Verification in Maintaining Proper Sys Alignment
ML20056A3441990-08-0101 August 1990
Responds to NRC Request for Further Justification Re Relocating Emergency Operations Facility to Corporate Headquarters
ML20059A3691990-07-30030 July 1990
Ack Receipt of SALP Rept 50-395/90-11 & Forwards Comments on Rept
ML20056A0201990-07-27027 July 1990
Provides Notification That All Actions Re Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment, Completed
ML20055H9821990-07-20020 July 1990
Forwards Amend 28 to Physical Security Plan.Amend Withheld (Ref 10CFR73.21)
ML17305B7681990-07-19019 July 1990
Responds to NRC NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. No Transmitters Identified in Item 1 from Suspect Lots Identified by Rosemount
ML20044B0241990-07-11011 July 1990
Responds to Violations Noted in Insp Rept 50-395/90-15. Corrective Actions:Relay Rewired & Verified Against Design Drawings
ML20055F3631990-07-10010 July 1990
Forwards Rev 1 to Plant Core Operating Limits Rept Cycle 6, as Result of Typo
ML20055E0341990-07-0505 July 1990
Forwards Technical Rept 90-1, Seismic Activity Near VC Summer Nuclear Station for Period Jan-Mar 1990
ML20055D4661990-07-0303 July 1990
Forwards Amend 4 to Updated Virgil C Summer Nuclear Station Fire Protection Evaluation Rept, Effective 900301
ML20058K4421990-06-29029 June 1990
Forwards Response to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions
ML20043F6621990-06-0707 June 1990
Requests for Change in QA Program 10CFR50.54 & FSAR Biennial Reviews of Plant Procedures Based on Justification Contained in Proposed Change to FSAR.SAP-139 Will Be Revised Immediately Following Approval of Request
ML20043D5861990-06-0101 June 1990
Forwards LERs 90-004 & 90-006 Which Respond to Violation Noted in Insp Rept 50-395/90-12.Corrective Actions:Training Conducted & Tech Spec Instruments Evaluated for Adequate Testing
ML20043C5001990-05-29029 May 1990
Forwards marked-up Pages to Util 900410 Tech Spec Change Request Indicating Location of Incorrect Std Refs,Per 900419 Telcon W/Jj Hayes
ML20043B7351990-05-23023 May 1990
Forwards Rev 0 to Core Operating Limits Rept,Cycle 6.
ML20043A9181990-05-17017 May 1990
Forwards List Detailing Tubes in Which F* Criteria Applied During Steam Generator Tube Insp Subsequent to Fifth Inservice Eddy Current Exam.Location of Degradation Measured from Tube End on Hot/Cold Leg Up to Degradation
ML20043G4621990-05-0303 May 1990
Advises That Util Will Control Operations to Abide by More Restrictive Required Shutdown Margin Curve While Awaiting NRC Approval to Place Revised Curve in Tech Specs
ML20042G4741990-05-0101 May 1990
Special Rept Spr 90-003 Listing Number of Steam Generator Tubes Plugged or Repaired During Fifth Refueling Outage
ML20042E1931990-04-11011 April 1990
Forwards Seismic Activity Near VC Summer Nuclear Station, Oct-Dec 1989. Several Seismic Monitoring Stations Inoperable During Reporting Period & Also During First Quarter 1990
ML20012F3551990-04-0303 April 1990
Withdraws 900321 Request for Relief from Testing RHR Containment Isolation Valves Xvg 08701 A/B at Frequency Specified in ASME Section XI Code.Meeting Requested to Discuss Util Interpretation of Testing in 10CFR50,App J
ML20012E9061990-03-23023 March 1990
Submits Supplemental Response to Station Blackout Re Proper Documentation & Consistent Implementation of NUMARC 87-00 Guidance.Plant Currently Maintains Targeted Emergency Diesel Generator Reliability by Ensuring Compliance W/Tech Specs
ML20012E0431990-03-23023 March 1990
Forwards Corrected Pages to Rev 26 to Radiation Emergency Plan.
ML20012D9691990-03-23023 March 1990
Forwards, Sante Cooper 1989 Annual Financial Rept, South Carolina Gas & Electric 1989 Annual Financial Rept Summary of Present Levels of Property Insurance & Cash Flow Statement for VC Summer Nuclear Plant
ML20012E5881990-03-21021 March 1990
Forwards Corrected Slide to Clarify Util Current Plans Re Steam Generator Insp Plan,Per 900312 Meeting W/Nrc
ML20012D8271990-03-21021 March 1990
Requests Relief from Testing RHR Containment Isolation Valves Xvg 08701 A/B at Frequency Specified in ASME Section XI Code.Valves Will Be Tested at Frequency Specified for Type a Valves in 10CFR50,App J
ML20012D0371990-03-19019 March 1990
Responds to Generic Ltr 89-19 Re Design of Steam Generator Overfill Protection.Util Does Not Plan to Implement Physical Mods or Administrative Changes Since Overfill Protection Sys Meets or Exceeds Guidance in Generic Ltr
ML20012D4781990-03-16016 March 1990
Forwards First Annual ECCS Evaluation Model Revs Rept,Per 881017 Rev to 10CFR50.46.Rept Identifies Several Mods to Large & Small Break LOCA Evaluation Models Used at Facility & Provides Estimated Effects of Changes on ECCS Analyses
ML20012C0661990-03-0909 March 1990
Forwards Addl Info Re Natural Circulation Evaluation Program Rept,Per 900208 Telcon Request
ML20012A0921990-03-0101 March 1990
Forwards Response to Generic Ltr 90-01,consisting of Completed NRC Regulatory Impact Survey Questionnaire Sheets Containing Estimates of Time Spent by Managers on Insps & Audits
ML20006E3411990-02-0606 February 1990
Forwards Proprietary Addl Info,Per NRC 900104 Request,Re Util Tech Spec Change Request for Elimination of Resistant Temp Detector Bypass Manifold sys,marked-up Tech Spec Pages & Block Diagrams.Encls Withheld
ML20006D1241990-02-0101 February 1990
Requests Approval,Per 10CCFR50.55a,for Use of Alloy 690 Matl in Fabricating/Use of Steam Generator Plugs During Upcoming Refueling Outage.Alloy 690 Currently code-approved Matl for Steam Generator Tubing Based on Corrosion Resistance
ML20011E1211990-01-31031 January 1990
Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Util Currently Performs Visual Insps & Dredgings of Svc Water & Circulating Water Intake Structures Once Each Refueling Cycle
ML20006D2951990-01-26026 January 1990
Forwards WCAP-12464, VC Summer Nuclear Station Natural Circulation Evaluation Program Rept. Rept Provides Info to Resolve Branch Technical Position Rsb 5-1, Design Requirements for RHR Sys for Facility,Per 890719 Telcon
ML20006B1211990-01-24024 January 1990
Forwards Technical Rept 89-3, Seismic Activity Near VC Summer Nuclear Station for Period Jul-Sept 1989.
ML20006A7191990-01-19019 January 1990
Provides Update of long-term Corrective Action for 890711 Loss of Offsite Power.Installation of Voltage Regulator on 230/7.2 Kv Emergency Auxiliary Transformer Neither Required Nor Any Appreciable Benefit Derived from Installation
ML20006A5521990-01-16016 January 1990
Advises That Util Will Validate Adequacy of Any Sys Used for Periodic Inservice Insp & Will Upgrade,As Required,Eddy Current Test Methods Used as Better Methods Developed & Validated for Commercial Use,Per 900111 Discussion
ML20005H0791990-01-12012 January 1990
Advises That Response to NRC Request for Addl Info Re L* Implementation Will Be Submitted by 900801 Due to Refueling Outage Schedule
ML20005F1191990-01-0505 January 1990
Forwards Description of F* Application at Plant & Sample Eddy Current Lissajous Figures for 12 Steam Generator Tubes, Per 891218 Request for Extension of Application of F* Tube Plugging Criterion for Life of Steam Generators
ML20005G4921990-01-0505 January 1990
Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Bulletin & Core Shuffle Procedure Will Be Discussed Among Core Engineering Personnel in Documented Training Session
ML20005F4531990-01-0404 January 1990
Forwards Application for Approval to Incinerate Oil Contaminated W/Very Low Levels of Licensed Radioactive Matls within Site Boundary of Facility
ML20005F0601990-01-0303 January 1990
Forwards Justification for Continued Operation Re Pressurizer Surge Line Thermal Stratification,Per NRC Bulletin 88-011.Util Believes That Plant Can Continue Operation for at Least 20 Addl Heatup/Cooldown Cycles
1990-09-17
[Table view] |
Text
o L
SOUTH CA90UNA EttcTRic a GAS COMPANY post omer son re.
cot islA, SOUTH CAROUNA 29218 T. C. N:cHots,Jn.
vies e... .. ... o u.ea,. on.a.o.,
cuc-. May 7, 1981 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Welds with Partial Examinations
Dear Mr. Denton:
As requested by Mr. Martin Hum of the NRC, South Carolina Electric and Gas '
Company hereby provides a listing of the currently identified welds in which partial examinations were conducted to obtain a complete volumetric examination on each weld.
This list is for informational purposes only. Approximately ninety (90) percent of the examination reports were reviewed in the compilation of this list.
While this represents the majority of reports, there exists the possibility that the list could increase. As noted in the list no B-J, C-F or C-G welds requiring relief requests have been identified so far. However, some welds requiring relief requests could be discovered in the remaining unreviewed reports.
If you have any questions, please let us know.
Very truly yours, T. C. Nichols, Jr.
NEC:TCN:rh cc: V. C. Summer J. B. Knotts, Jr.
G. H. Fischer J. L. Skolds T. C. Nichols, Jr. O. S. Bradham D. A. Nauman H. E. Yocom W. A. Wiliams, Jr. H. N. Cyrus R. B. Clary ISEG A. R. Koon NPCF A. A. Smith File I J. Ruoff 8105150l%
h
- y. .. ;
The following is a listing of welds where examinations are limited by welded supports, branch connections, physical access, cenfiguration, etc. Where possibic, all welds were examined from both sides. In all cases, 100%.of the volume of the welds was examined from one or more directions in accordance.with ASME Code,Section XI. Welds are listed as to the isometric with limitations noted. Where a supplemental examination is used it is also noted.
ISOMETRIC WELD LIMITATIONS SUPPLEMENTAL CGE-1-1100 4 Bevel CGE-1-2100 1 Welded Pads 3 Welded Pads 4 Welded Pads 6 Welded Pads, Welded Support 9 thru 14 Norzles and Maaway CGE-1-3100 1 Welded Pads CGE-1-4100 1 thru 16 Grain Structure, Surface Bevels and Crowns 18BC Branch "onnection Surface 19BC Branch Connection Surface CGE-1-4101 1 Support, valve 2 Support 14 Valve 15 Valve 16 Welded ID Pin.te, Valve 17 Welded ID Plate 21 Nozzle CCE-1-4102 1 Nozzle Surface
. 7 Valve 8 Valve, Support 23 Valve CGE-1-4103 1 Valve 2 thru 9 Elbow Introdos 10 Valve 11 Valve 15 Nozzle, Nameplate 16 Nozzle, Nameplate a
0,
- ISOMETRIC WELD LIMITATIONS SUPPLEMENTAL ,
, CCE-1-4104 1 Valve 2 thru 5 Elbow Introdos 7 thru 16 Elbow Introdos 17 Valve 18 . Valve 19 Elbow Introdos -
20 Elbow Introdos 21 Nozzle CGE-1-4105' 2 Valve 3 ,
Valve .
4 thru 13 Elbow Introdos 14 _ Fittings 15 Fittings 16 Fittings CGE-1-4106 1 Valve 2 thru 5 Elbow Introdos 6 Valve 7 Valve 8 Elbow Introdos i 9 Elbow Introdos 10 Nozzle, Nameplate CGE-1-4107 1 Nozzle 2 thru 5 Elbow Introdos 6 Fittings 7 Fittings
. 8 Fittings ~
9 Elbow Introdos 10 Elbow Introdos 11 thru 15 Valve
! CCE-1-4108 18BW Fitting CGE-1-4110 IBW Elbow Introdos CGE-1-4114 1BW Fitting CGE-1-4200 1 thru 16 G ra in Structure, Surface Bevel and Crowns
.' CGE-1-4201 1 Valve 2 Valve l 4 Saddle Support l
7 Valve l
8 Valve 10 ID Plate 11 ID Plate 13 Valve e - _ -
r-
ISOMETRIC WELD LIMITATIONS SUPPLEMENTAL CCE-1-4202 1 Valve 2 thru 13 Introdos 14 Valve 15 Valve 16 thru 1.,9 Introdos 20 - Nozzle CGE-1-4203 l Valve 3 thru 16 Introdos 7 Valve 8 Valve t 9 Introdos 10 Introdoa 11 Nozzle
~
CGE-1-4'04 2 1 Reducer, ID Plate '
2 Valve, ID Plate 3 Valve,
~
ID Pinte 4 thru 7 Introdos '
10 Tee -
11 Tee .
12 Introdos 13 Introdos
- 20 . Valve, ID Plate 21 Valve, ,
ID Plate 22 Introdos 23 Introdos 24 Nozzle
. CGE-1-4205 1 Valve, ID Plate 2 thru 5 Introdos
. 6 thru 8 Valve, ID Plate 10 Introdos 11 Introdos 12 Nozzle CGE-1-4206 18BW Fitting
. e .
' ISOMETRIC WELD LIMITATIONS SUPPLEMT.NTAL CC E- 1 -4 211 9 Fitting, Crown 13 thru 15 Fitting, Crown
, CGE-1-4212 1 BW Fitting CGE-1-4300 1 thru 16 Grain Structure Surface
." Bevel, Crowns CCE-1-4301 W'S-1 Welded Lugs 1 Valve, Supports 2 Valve, Supports 4 Welded Supports 5 Welded Supports -
8 Valve, Supports 9 . Valve 11 '
I-Beam 13 Flange CGE-1-4302 1 Valve 6 Concavity 9 thru 11 Valve 13 Introdos 18 Introdos 20 Introdos CGE-1-4303 1 Valve -
2 Introdos 3 Welded Lug
. 4 thro 13 Introdos
. 14 Nozzle. ,-
,15 Valve
,17 ID Plate
- 18 ID Plate CGE-1-4304 '
/1 Nozzle 2 Introdos 3 ID Plate, Introdos 4 ID Plate,
. Introdos 5 Valve 6 Introdos
. 7 Introdos e
O
r
' ISOMETRIC WELD LIMITATIONS SUPPLEMENTAL CGE-1-43'05 1 ID Plate 2 ,ID Plate 3 Valve 4 Introdos 5
~
Introdos 7 -
Welded Lug 8,thru 11- Introdos 12 Tee 14 Fitting
, 15 Fitting 17 thru 19 Introdos 20 Valve 21 Valve 22 thru 24 Introdos ,
- 26 Nozzle CCE-1-4306 18 BW Fitting
'CGE-1-4 311 53 BW Fitting CCE-1-4312 1 BW Fitting CGE-1-4500 1 DM Nozzle
, Configurati.on
- 2 Nozzle ,
Configuration 13 Nozzle, Crown CG E- 1.-4
2 Flange 3 Nozzle 5 thru 10 Introdos 11 '
Flange, Crown 12 DM Nozzle L3 Flange 16 thru 21 Introdos 22 Flange, Crown 23 DM Nozzle
. 24 Flange, Nozzle 27 thru 32 Introdos CGE-1-4502 1 DM Nozzic 2 Nozzle -
5 thru 12 Introdos
' 13 thru 18 Fitting 19 Introdos 20 Introdos 21 Fitting -
O e
NM _ e e w we, ew
-w r , -
-ISCHETRIC WELD LIMITATIONS. SUPPLEMENTAL CCE-1-4503 1 . Nozzle ;
L 2 thru 5 Introdos
, 6 ID Plate, I Introdos 7 ,
.ID Plate, ,
Introdos
. 8'thru 18 Introdos 20 thru 29 Introdos 30 Valve 31 Valve 32 thru 36 Intro. dos *
.' 37 Fitting '
38 Fitting 39 thru 42 Introdos 43 Nozzle 44 DM Nozzle CCE i -4504 l 1 Nozzle 2 thru 20 Introdos 22 Introdos
~2 3 Introdos 24 Valve l 25 Valve 26 thru 29 Introdos
- 30 Fitting CGE-1-4505 1 Valve 2 Valve 3 Valve
- 4 , Reducer 5 . Fitting -
8 Fitting 9 Valve 10 Valve 11 Fitting 12 Valve 13 Valve, ID Plate 14 ID Plate, Valve
. 16 Valve CGE-2-1100 2 Nozzle, Handhold 5 Welded Pad 6 Welded Pad 8 Welded Pad 9 4 Nozzle, Handhold 10 Nozzle, Mendhold 11 Nozzle v s-o m, -
w-- ---. s r-. w- p
' ISOMETRIC- WELD LIMITATIONS SUPPLEMENTAL CCE-2-1200 1 Crown, Concavity, Skirt 2 Crown, Concavity, Skirt CCE-2-1330 1 .
Crown, Flange 2, Crown, Flange CCE-2-1360 1 Nozzle i 2 Support 3 Crown, Configuration 4 Nozzic ' ,
5 Support
, 6 Crown, Configuration
-7 ID Plate, Crown, Configuration 8 ID Plate, Crown, Configuration CGE-2-1380 1 Flange, Saddle
- . 2 Flange, Saddle CGE-2-0001 1 Valve 2 thru 12 Crown .
'13 Valve, Crown 16 In t r od o s , Cro,m Crown '
. 17 Crown _
. 17 A Crown .-
18 thru 20 Crown 21 Valve, Crown 22 Crown .
CGE-2-0002 24 Crown
/25 Crown 28 Crown 30 Crown 32 Crown 35 thru 38 Crown 40 Crown 42 Crown 45 Crown 46 Crown 48 Crown, Fftting 50 Crown, Fitting 51 Crown, Fitting.- = .. -
53 Crown 55 Crown -
58 thru 60 Crown 64 Crown
. 66 Crown 68 Crown O
7_ ..
,, .~
ISOMETRIC WELD LIMITATIONS SUPPLEMENTAL
~CGE-2-0003 24 Crown
.26 Crown 27 Crown 30 Crown 32 , Crown 33 Crown '
35 thru 38 Crown -
41 , Crown
'43 Crown 44 Crown 45 Crown
. 47 Crown '
48 Crown 50 Fitting, Crown . i
- 51 Fitting, Crown 54 Crown 56 Crown -
58 Crown
. CGE-2-0004 1 thru 12' Introdos, - - -
Crown, Reducer 14 Valve 15 thru 19 Fitting, Crown 20 Penetration 21- Penetratio'n
. :2 2 _Introdos, Crown, ID Plate 12 3 Introdos, Crown, ID Plate -
25 Introdos, Crown, ID, Plate 26 Valve CGE-2-0006 1 thru 8 Fitting, Crown, Introdos, Nozzle CGE-2-2100 1-1 Nozzle 1-7 Support Collar CGE-2-2101 1-11 Tee, Crown 1-25 Branch Pipe, Configuration 1-26 Branch Pipe, Configuration 4-1 Introdos 4-2 Introdos 4-3 Welded Support 4-3A Tee, Crown
! 4-3B Tee, Crown .
~
, 5-1 ID Plate
- - --w -' * * - ' ' " r T 'G r -*T'
+ ,.
1_I S OM ET R I C WELD LIMITATIONS' SUPPLEMENTAL CGE-2-2102 1-1 Crown, Nozzle 1-5 Welded Plate, Branch Pipe 1-7 Welded Support 1-9 , Welded Support r 1-12 -
Welded Plate, Branch Pipe ,
CGE-2-2103 121 Valve, c'rown '
123 . Valve, Crown CGE-2-2104 1-29 Tee, ID Plate
1-64 Elbow, Crown, Nozzle 1-67 Elbow, Crown, Nozzle CGE-2-2105 1-39 Crown, Reducer
-- CG E-2-210 6 1-52 Crown, Fitting, Nozzle ;
CGE-2-2107 1 Reducer .
FW 12 Welded Attschment, Nozzle
. FW 17 Welded Attachment, Nozzle CGE-2 2200 2-8 Penetration, Support 8 ID Plate CGE-2-2201 2-15 Crown, Saddle 1 2-17 Configuration FW 20 Branch, Crown 2-22 Valve, Crown 2-28 Valve, Crown 2-32 Welded Supports CGE-2-2202 2-1 Nozzle 2-3 10 Plate 2-5 Welded Attachment 2-9 Welded Attachment .
2-11 ID Plate CGE-2-2203 2-20 Crown ;
2-44 Valve, Crown !
2-60 Elbow, Nozzlc, Crown 2-61 Elbow, Nozzle, Crown h
b
'IS0 METRIC WELD h1MITATIONS SUPPL 5 MENTAL
'CGE-2-2204- 2-34 Elbow, Crown CGE-2-2205 FW-11 -
Nozzle FW-17 Welded Attachment CGE-2-2300 3-10. Elbow, Penetration-FW-13 ID Plate FW-14 ID Plate
'CG3-2-2301 3-13 Crown
.3-21 Welded ID Plate ,
3-23 Saddle Weld 3-31 Welded ID Plate
. 3-40 Nozzle, Crown 4-3 Welded Support, Introdos 4-3C Welde*d Support, Introdos ,
4-4 Welded Support,
~
Int'rodos 4-5 ^ Welded Support, -
Introdos 4-5A Welded Support, Introdos ,.
4-6 Introdos 4-6A Nozzle, Crown 4-7 Introdos -
. 4-8 Crown, Branch,
, .. Valve -
4-8A Welded ID Plate 4-9 . Nozzle, Crown 4-10 ID Nameplate, .
Crown 4-11 . ID Nameplate, Crown FW-6 Crown, Branch, Valve CGE-2-2302 9-1 Configuration 9-2A Configuratian 9-3 Welded Pads, Valve, Crown 9-4 Configuration 9-5 Welded Supports 4
I. e
.g: - .. -
ISOMETRIC WELD LIMITATIONS- S_UPPLEMENTAL
- CGE-2-2303 FW 11 Crown
FW 14 Crown, Welded Support FW 15 *
. Crown 3-1 Crown, Branch Pipe 3-2 5 Crown, Welded Support 3-2A Crown 3-3 Crown,
. Welded Support. -
3-5 Branch Pipe 3-7 Crown 8 thru 21 Crown 3-22 . Crown, Welded Plate -
3-23 thru 3-26 -
i CGE-2-2304 FW 3 Welded Plate, 4 Valve, Crown FW 4 Welded Plat.e, Valve, Crown FW 6 Welded Plate, Valve Crown CGE-2h2305 3-55 Elbow, Crown ,
3-57 Elbow, Crown CGE-2-2306 FW 9 Valve .
FW 10 Welded Attachment, Valve FW 11 Valve, Crown 3-40 Nozzle, Crown CGE-2-2330 5-1 Welded Plate, ,
. Saddle, Crown :
6-2 Welded Plate, Saddle, Crown !
. 6-3 Welded Plate, ;
Saddle, Crown 7-4 Introdos -
l
~
8-5 Introdas, Welhed i Support,' ID Plate FW-1 Crown, Welded .
Support, ID Plate -
B I
~~ _
,, , m .-e.. ,,_y ._
,9, p_ - . . - , _,
, ~
ISOMETRIC WELD LIMITATIONS SUPPLEMENTAL CGE-2-2351 4-1 Configuration 4-2 Configuration, Welded Support 4-3 Configuration 4-4 ,
~ Configuration 4-5 Welded Suppcrt 4-6 thru -
4-8 Configuration 4-10 thru 4-12 Crown 4-13 ' Valve ,
CGE-2-2352 FW 11 Welded Attachment
-CGE-2-2500 FW 9 Crown FW 22 Crown FW 23 Crown 22 Concavity 28 Tee
. 29A Branch Pipe
. 42 Nozzle, Tee 155 Nozzle, Tee 156A Crown 158 Crown ..
CGE-2-2501 FW 1 Penetracion, Crowp FW 38 Penet ation,
. Crova -
10 Penetration, Crown 183 Welded Support "
189 thru 192 Tee .
193A Crown, Branch Pipe 195A Crown, Branch Pipe 201A Crown, Branch Pipe .
305 Welded Support 306 Valve 307 Valve CGE-2-2700 32 Crown, Flange i 53 Crown, Flange .
72 Crown, Flange :
CGE-2-2701 204 Pump 211 Flange 212 Flange J
~Q
. ~ . , _ . .
j..
~ '
ISOMETRIC WELD LIMITATIONS' SUPPLEMENTAL CGE-2-2702 92' Flange 95 Welded ID Plate 148 Crown, Valve CGE-2-2703 100 ,
Crown 101 Crown 110 Crown
111 ~
Crown 129 . Valve
~
130 Valve 133 . Welded Support, ,s Crown 134 Welded Support, Crown
- 364 Valve
~ '
CGE-2-2'704 247 Valve 248 Valve 255 Valve 258 Fitting 265 Crown 297 Valve
- 298 Valve -
299 Fitting - ..
365 Valve 366 Introdos 368 Welded Support 372 -
Welded Support
.. 374 thru 377 Valve -
378 Fitting 379 Valve, Crown CGE-2-2705 277 Crown 284 Valve 285 Valve 286 Valve I CGE-2-2706 312 thru 315 Introdos, Concavity l CGE-2-2707 321 Concavity, ,
Introdos 322 Valve, Introdos -
329 thru i 331 , Concavity, ,
Introdos 339 thru -
341 Concavity, Introdos CGE-2-2708 353 Fitting 339 Concavity, i Introdos !
360 Concavity, Introdos
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' ISOMETRIC WELD LIMITATIONS SUPPLEMENTAL r
'CGE-2-2800 FW 10 thrh
4-24 Reducer, Crown .
380 Flange 421 , Valve 446 -
Flange 454 Welded Plate 462 Concavity 463 Concavity CGE-2-2801' 406 thru 408 Valve i 433 Concavity ~
439 Valve '
442 Valve 443 ' Valve CGE-2-2802
'~
145 Valve .
470 i Fitting ,
'473 Concavity '
CGE-2-2803 306 Valve, Crown '
486 Fitting ,
505 Crown 509 Valve,.. Crown ;
CGE-2-2804 1 . Valve, Crown !
2 Introdos, Crown _
. 4 Introdos, Crown
~
5 Introdos, Crown .."
8 Croan -
10- Crown, Valve
~
12 Introdos, Crown i 14 Introdos, Cr.own 15 Introdos, Crown '
17 Introdos, Crown
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ISOMETRIC WELD LIMITATIONS SUPPLEMENTAL ,
CCE-2-2805 1 Crown, Valve 3 -
Crown, Welded' Plate
. 4 Crown 6- Crown 9 , Crown .
~
. . 11 -
Crown l' 15 Crown 18 Crown 20 Crown -
21 Crown, Electric Conduit ,s i 23 Crown 25 Crown '!
27 Valve, Crown
- 30 Crown, Fitting [
31 Crown 32 Crown ,
33 Crown, Valve CCE-2-2806 2 Crown
-4 Crown, Welded- i Plate -
5 Crown -
7 Crown ,. .
9 Crown 12 Valve, Crown 14 Crown 15 Crown --
17 Crown '
19 Crown 23 . Crown 2 24 Valve, Crown These are the currently identified weld's which required partials i t 'o conduct a complete examination. Westinghouse has not yet identified any B-J, C-F or C-G welds requiring relief request.
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