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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
.
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o SOUTH CAROLINA ELECTRIC & GAS COMPANY POST OPPICE 764 COLuusiA. south CAROLINA 29218
. o. w. oixoN. ;n.
VICE P.E860ENr
- sucana o,Enariou, May 17, 1983 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 Operating License No. NPF-12 Environmental Qualification of Electric Equipment Important to Safety
Dear Mr. Denton:
As' required by 10CFR50.49 published in the Federal Register / Volume 48, No. 15/ Friday, January 21, 1983, South Carolina Electric and Gas Company (SCE&G) herein submits a list of electric equipment important to safety within the scope of the rule. In the attachment to our letter of February 19, 1982, SCE&G provided a summary of the qualification information for most of the equipment. In several letters -since that date SCE&G has provided additional information regarding certain pieces of equipment. This letter summarizes the information previously submitted and provides SCE&G's schedule for qualification of the remaining pieces of equipment.
IfLyou have any questions, please let us know.
Ve tr y you s, O. W. p xon, r.
CO:NEC:OWD/fjc
Attachment:
cc: V. C. Summer C. A. Price T. C. Nichols, Jr./O. W. Dixon, Jr. .A. R. Koon E.'H. Crews, Jr. C. L.-Ligon (NSRC)
E. C. Roberts G. J. Braddick H. N..Cyrus J. C. Miller J.-L. Skolds J. P. O'Reilly Group / General Managers J. B. Knotts, Jr.
O. S.-Bradham NPCF R. B.-Claryj File (Lic./Eng.) 4 8305250492 830517 PDR ADOCK 05000395 lt40 P pop __
Page 1 CLASS lE EQUIPMENT
. SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED AC 6" Motor Operated Gate Valve ROTORK 14NAl XVG7502 1 Operator XVG7503 1 AC 6" Motor Operated Gate Valve ROTORK 14NA2 XVG7501 1 Operator XVG7504 1 AH Limit' Switches for Reactor NAMCO EA-180 XDP0110A l' Building Cooling Unit HEPA XDP0110B 1 Filter Bypass Dampers XDP0lllA 1 XDP0lllB 1 AH Limit Switch for 36" Purge NAMCO EA-180 XVB0001B 1
-Line Isolation Valve XVB0002B 1 AH = Limit Switch for Air Damper NAMCO EA-180 XDP0012A 2 XDP0012B 2 XDP0013A 2 XDP0013B 2 AH . Damper Actuator Solenoid ASCO 206-381-7F XDP0110A 1 Valve for Reactor Building XDP0110B 1 Cooling. Unit HEPA Bypass XDP0lllA 1 Damper XDP0lllB 1
-AH Reactor Building Cooling Unit RELIANCE 5003UCZ MFN0097A 1 Fan Emergency Motor MFN0097B 1 MFN0097C 1 MFN0097D 1 J
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Page 2
' CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS
'SYS EQUIPMENT-DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED z- AH .' Solenoid Valve for-36" Purge ASCO NP-8316 XVB0001B 1
-Line-Isolation Valve XVB0002B 1
~AH Solenoid Valves for Air ASCO NP-8320 XDP0012A 2-Dampers XDP0012B 2 XDP0013A 2 XDP0013B 2 BD- 3" Air Operated Gate Valve ASCO NP-8316 XVG503A 1 Solenoid XVG503B 1 XVG503C 1
.BD 3" Air Operated Gate Valve .NAMCO EA-180 XVG503A 1.
Limit Switch XVG503B 1 XVG503C 1 SMB-000-5 XVG9605-- 1
~
CC '_ 8" Motor Operated Gate LIMITORQUE Valve Operator
'CC
- 4" Air. Operated Gate ASCO NP-8316 XVG9627A 1 Valve Solenoid XVG9627B 1 l
CC 8" Motor Operated Gate LIMITORQUE SMB-000-5 XVG9568 1 Valve Operator XVG9606 1
--CC' 3" Motor Operated Gate LIMITORQUE SMB-000-2 XVG9600 2 Valve Operator CC' 8" Motor' Operated Gate LIMITORQUE SMB-000-5 XVG9625 2 Valve Operator- XVG9626 2 a
Page 3 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER' QUALIFIED CC '16" Motor. Operated Butterfly LIMITORQUE SMB0005/H2BC XVB9526B 1 Valve. Operator XVB9687B- 1"
-XVB9526A 1
'XVB9687A 1'
~
CC. 20" Motor Operated Butterfly LIMITORQUE SMB0005/H2BC -XVB9503A _1 Valve Operator ,
XVB9503B 1 CC 16" Motor Operated Butterfly LIMITORQUE SMB0005/H2BC XVB9524A '2
. Valve Operator XVB9524B 2 XVB9525A 2
.XVB9525B 2 CC Component Cooling Water Pump WESTINGHOUSE LRA PAM/3840 Frame MPP0001A, 1
. Motor MPP0001B 1 MPP0001C 1 CC Component Cooling Water Flow ROSEMOUNT ll53DA4 IFT7263A 2 To Reactor Coolant Pump IFT7263B 2 Bearings CC' Component Cooling Water Surge ROSEMOUNT ll52DP4 ILT7092 1
-Tank Level Transmitters ILT7094 1 CC Component Cooling Water Flow ROSEMOUNT ll53DA4 IFT7273A 2 To Reactor Cooling Pump IFT7273B 2 Thermal Barriers '
-J
6 Page 4 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED
. CC- :4" Air Operated Gate Valve NAMCO EA-180 .XVG9627A '
1 Limit Switch XVG9627B 1 CI' RTD, Reactor Building PYCO 122-1010 ITE9201 1 Temperature ITE9203 1 CS 2". Globe Valve Motor LIMITORQUE SMB-00-10 .XVT8104 1
' Operator XVT8109A. 1 XVT8109B- 1 XVT8109C 1 XVT8100 1
' CS 4" Gate Valve Motor LIMITORQUE SB-00 LCV115C 1- .
, Operator LCVll5E 1 CS 8" Gate Valve Motor LIMITORQUE SB-00 LCVll5B 1 Operator LCVll5D , 1 CS 1-1/2" Globe Valve Motor LIMITORQUE SMB-00-10 XVT8102A 1
. Operator XVT8102B 1 XVT8102C 1
- CS 8" Gate Valve Motor LIMITORQUE SB-00 XVG8130A 1 Operator XVG8130B 1 XVG8131A 1 XVG8131B 1 4
e
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- Page . 5 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER -QUALIFIED SB-00
-CS 4" Gate Valve-Motor LIMITORQUE XVG8132A 1 Operator XVG8132B' l XVG8133A 1 XVGW133B 1 iCS- 3"'Ga'te Valve Motor LIMITORQUE SB-00 XVG8106 l'
-Operator XVG8107 1
'/ XVG8108 1 CS' 2". Globe. Valve Motor LIMITORQUE SMB-00-10 XVT8112 1 Operator CS ASCO NP-831654V XVT8152 1
. , <- ' 3" Globe. Valve Solenoid CS 2"~ Globe Valve Solenoid ASCO. NP-831654V XVT8149A 1 '
./ '? .
XVT8149B 1.
M s l XVT8149C 1 p
. CS" Stem-Mounted Limit. Switch NAMCO EA-180 XVT8152 1 f:
- 4,,7 CS. ' Charging' Pump Motor WESTINGHOUSE 6809 XPP0043A 1 XPP0043B 1 XPP0043C 1
. LCS Safety Injection Pump
~
TERAC GOULD HPL-C XET2002C 1
. Transfer Switch' i
i,
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> CLASS 1E EQUIPMENT 4'
w7 .
,.Stia.7ECT TO~ HARSH ENVIRONMENTAL CONDITIONS ,
6
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SYS EQUIPMENT DESCRIPTION + MANUFACTORER TYPE / MOD NUMBER TAG NUMBER QUALIFIED
- 4 CS- Boric Acid Tank Level' BARTON 752 ILT106 2
' Transmitter ILT108 2 ILT161 2 ILT163 2 EF 6" Motor Operated Gate LIMITORQUE SMB-00-5 XVG1001A 1 Valve Operator- XVG1001B 1 EF 8" Motor Operated Gate LIMITORQUE SMB-000-5 XVG1002 1 XVG1008 1 ;
'- Valve Operator XVG1037A 1 1 b,
XVG1037B 1 EF Emergency Feedwater Pump ASCO WP-HVA-206- IFV3531 1 Flow Control Valve Solenoid 381-3RVU IFV3536 1 IFV3541 1 IFV3546 1 IFV3551 1 IFV3556 1 EF 4" Swing Check Valve ASCO 206-381-3F XVC1009A 2 Solenoid XVC1009B 2 XVC1009C 2 EF Emergency Feedwater Pump GENERAL ELECTRIC K Horizontal MPP0021A 1 Motor Frame 8311Z MPP0021B 1 5K831155C7 SK831155C8 es
_ _ _ _ _ _ _ _a _
s Page 7 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED EF Motor Driven Emergency ROSEMOUNT ll53DA5 IFT3531 1 Feedwater Pump Discharge IFT3551 -1 Header Flow IFT3541 1 EF Emergency Feedwater to ROSEMOUNT ll53DA4 IFT3561 1 Steam Generator Flow IFT3571 1 4
IFT3581 1 EF Emergency Feedwater to ROSEMOUNT ll53DA5 IFT35SlA 1 Steam Generator.A Flow EF Emergency Feedwater to ROSEMOUNT ll53DA5 IFT3571A 1 Steam Generator B Flow EF Emergency Feedwater to ROSEMOUNT ll53DA5 IFT3581A 1 Steam Generator C Flow ES Motor Control Center SQUARE D Model 4 XMClDA2Y 2 ES Valve Canister Pentration D.G. O'BRIEN Valve Container, XRP0100A 1 l-lSC #4 XRP0100B 1 XRP0101A 1 XRP0101B 1 ES Outside Containment Plugs D.G. O'BRIEN T/Model XRP0100A 1 C-32 Plugs XRP0100B 1 Valve Canister XRP0101A 1 Penetrator XRP0lOlB 1 g
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Page ' 8 -
CLASS'lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL ~ CONDITIONS
. SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER . QUALIFIED ES Electrical Penetration D.G. O'BRIEN Low Voltage. XRP0007 1 Power / Control XRP0010 1 Components XRP00ll 1 With Exception XRP0014 1 of C-32 Plugs XRP0017 1 ;
XRP0028 1 XRP0030 1 ES Electrical Penetration D.G. O'BRIEN Instrumentation XRP0035 1 Components XRP0036 1 XRP0043 1 4
' With Exception of C-32 Plugs XRP0044 1 XRP0045 1 XRP0046 1 XRP0048 1 i XRP0051 1
' ES' Electrical Penetration D.G. O'BRIEN C-32 Plugs XRP0010 1 Plugs Outside Containment Low Voltage XRP00ll 1 Power Control- XRP0017 1 XRP0028 1 XRP0030 1 ES- Electrical' Penetration . D.G. O'BRIEN C-32 Plugs XRP0035 1 4
' Plugs Outside Containment Instrumentation XRP0036 1 ,
XRP0043 1 XRP0044 1 :
XRP0045 1 XRP0046 l' XRP0048- 1 XRP0051 1 .
i
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Page 9 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED
'ES Electrical Penetration Triax D.G. O'BRIEN Triax Connector XRP0043 2 Connectors Module M06 XRP0044 2 Plug R191010G04 XRP0045 2 XRP0046 2 D.G. O'BRIEN Triax Connector XRP0051A 4 (Victoreen High Range Monitor)
ES Power Transfer and Motor FIELD FABRICATED XPN0040 2 Control Panel for Charging Pump C Auxiliaries ET. Isolation Fuses In Heat GOULD/SHAWMUT N/A XPN2005 1 Tracing Panels FUSES XPN2006 1 XPN2007 1 XPN2008 1 XPN2009 1 XPN2010 1 ET l Isolation Fuse Blocks in BRYANT 1917 XPN2005 4 Heat Tracing' Panels ELECTRIC 3929 XPN2006 4 XPN2007 4 XPN2008 4 XPN2009 4 XPN2010 4
~
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\ T Page 10; P 4 oCLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS
-SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED:
.FS' 4" Motor Operated Gate LIMITORQUE SMB-000-5 XVG6797 2 Valve Operator, 2-
- FWL Feedwater-Flow DP. Transmitter BARTON 752 IFT0476 IFT0477 2 IFT0486- 2 IFT0487- 2 IFT0496 2 IFT0497 2 FW 3" Air. Operated Globe Valve ASCO NP-8316 XVT1678A 1 Solenoid ' XVT1678B 1 XVT1678C 1
' ~
-FW 1-1/2". Motor Operated Valve LIMITORQUE SMB-00 XVT1633A 1 Operator XVT1633B- 2 XVT1633C 2 FW '18"I Air-Hydraulic Globe SKINNER V5H61 XVG1611A 1
' Valve Solenoid XVG1611B 1 XVG1611C 1 FW. 3" Air Operated Globe Valve NAMCO EA-180 XVT1678A 1 Limit' Switch XVT1678B 1
, XVT1678C 1
-FW 18" Air-Hydraulic Globe NAMCO EA-180 XVG1611A 1 Valve Limit Switch XVG1611B 1 >
XVG1611C 1 i
. - - - . . - -- - .~. ._. ___ ___r -
, . , ~ -
Page 11 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS-
'SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED HR' Hydrogen Recombiner WESTINGHOUSE --
XHR0004A 1 XHR0004B 1 HR '. Hydrogen Recombiner Control WESTINGHOUSE --------
XPN0049A 2 Panels and'. Power Supply XPN0049B 2 XPN0050A 2 XPN0050B 2
'HR- 6" Air Operated Gate ASCO NP-8316 XVG6056 1-Valve' Solenoid' HR- 6"' Purge Isolation ASCO NP-8316 XVG6066 1 Valve Solenoid XVG6067 1 HR. ' Post Accident Hydrogen VALCOR V526-5292-20 XVX6050A 1
-Removal System Isolation XVX6050B 1 Solenoid valves XVX6051A 1 XVX6051B 1 XVX6051C- 1 t XVX6052A 1 t XVX6053A 1 XVX6054 1 HR Reactor: Building Wide Range ROSEMOUNT 1152AP7 IPT0954A 1 Pressure HR Narrow Range Containment BARTON 752 IPT950 2 -
Pressure Transmitter IPT953 2
t Page 12 CLASS 1E EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER. QUALIFIED HR 6" Air' Operated Gate NAMCO EA-180 XVG6056 1 Valve Limit Switch HR 6" Purge Isolation Valve NAMCO EA-180 XVG6066 1
. Limit Switch XVG6067 1 HR Reactor Building Hydrogen COMSIP, INC. KIII XPN7215A 2 Analyzer Panel and Remote XPN7258A 2 Control Panel XPN72588 2
- IA 6" Air Operated Globe Valve ASCO NP-8316 XPN2662B 1 Solenoid XPN2662A 1 IA 2" Air Operated Globe Valve ASCO NP-8323 XV'r2660 1 Solenoid IA
~
6" Air Operated Globe Valve NAMCO EA-180 XVT2662B 1 Limit Switch XVT2662A 1 IA 2" Air Operted Glove Valve NAMCO EA-180 XVT2660 1 Limit. Switch LD Electronic Transmitter, ROSEMOUNT 01153-0022-0001 ILT1969 1 Reactor Building RHR. ILT1970 1 Sump Level LD . Electronic Transmitter, ROSEMOUNT 01153-0022-0001 ILT1975 1 Reactor Building Level ILT1976 1 x - _ . _ - U
-. . .=. - - - - . . --
Page 13 CL7p'i lE EQUIPMENT SUBJECT TO HARS.1 ENVIRONMENTAL CONDITIONS
. S,YS - EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED MS Steam' Generator Level BARTON ILT0474 1 Narrow Range DP ILT0475 1 Trnasmitters ILT0476 1 ILT0484 1 ILT0485 1 ILT0486 1 ILT0494 1 ILT0495 1 ILT0496 1 MS First Stage Turbine BARTON 752 IPT446 2 Pressure Transmitter IPT447 2 MS Steam Flow DP Transmitter BARTON IFT0474 2 IPT0475 2 IFT0484 2 IFT0485 2 IFT0494 2 IFT0495 2
Page 14 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED MS Steam Pressure Transmitter BARTON IPT0474 1 IPT0475 1 IPT0476 1 IPT0484 1 IPT0485 1 IPT0486 1 IPT0494 1 IPT0495 1 IPT0496 1 MS Control Solenoid. ASCO WP-HVA-206-381- IFV2030 1 3RVU MS 32" Air Operated Isolation ALLIED 321X-21 XVM2801A 1 Valve Solenoid XVM2801B- 1 XVM2801C 1 MS 4" Air Operated Globe Valve ASCO NP-8316 XVT2869A 1 Solenoid XVT2869B 1 XVT2869C 1 MS <4" Motor Operated Gate Valve LIMITORQUE SMB-00 XVG2802A 1
. Operator XVG2802B 1
-MS 1-1/2" Air Operated Globe ASCO NP-8323 XVT2843A 1 Valve Solenoid XVT2843B 1 XVT2843C 1 XVT2877A 1 XVT2877B 1
4 r y p,o. -
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e 4 y,- i L
- - (
, Page 15 ,
CLASS lE EQUIPMENT 5
SUBJECT-TO HARSH ENVIRONMENTAL CONDITIONS.
-SYS EQUIPMENT DESCRIPTION- MANUFACTURER- TYPE / MOD NUMBER TAG NUMBER QUALIFIED.
1
. MS- Steam Generator' Power. ASCO 'WP-HVA-206-381- IPV2000 Relief Control Solenoid Valve 3RVU. IPV2010 1 h 6 IPV2020 1
. MS. 32". Air-. Operated.; Isolation NAMCO EA-740 XVM2801A 1-I -Valve Limit Switch -XVM2801B- 1 XVM2801C 1
' MS 4"1 Air-' Operated Glove Valve NAMCO. EA-180 .XVT2869A 1.
Limit Switch XVT2869B 1-
- XVT2869C 1-
. MS- ...1-1/2" Air Operated Globe.. NAMCO EA-180- XVT2843A ~1 Valve. Limit-Switch XVT2843B 1
- XVT2843C 1-XVT2877A 1 XVT2877B 1 1
l .ND 3" Air Operated Diaphragm ASCO 206-381-3RFV XVD6242A 1 Valve Solenoid NP-1 XVD6242B l
ND 3" Air ~ Operated. Diaphragm NAMCO EA-180 XVD6242A 1 XVD6242B
-Valve: Limit Switch 1 l
1:
4 NI Power R'ange Neutron Detector WESTINGHOUSE Dual Section NC-41 2
- . Ionization NC-42 2 Chamber NC-43 2 4- -
NC-44 2 1
- 4. ,
_ L - - _ ___ _ -._ _ _ _ _ _ . _ _ _ __. . .-, - -s
Page 16 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED RC . Narrow Range Resistance RdF ITE0412A 5._
Temperature Detector. ITE0412B 5 ITE0412C 5 ITE0412D 5 ITE0422A :5 ITE0422B- 5
. ITE0422C 5 ITE0422D 5
-ITE0432A 5 ITE0432B 5 ITE0432C 5-ITE0432D 5
. :RC Wide Range Resistance PYCO 122-3006 ITE0410/
Temperature Detector 0410A 1 ITE0413/
0413A 1 ITE0420/
0420A 1 ITE0423/
0423A 1 ITE0430/
0430A 1-ITE0433/
0433A 1
g, s>- ,
7 Page 17; CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER- TYPE / MOD NUMBER TAG NUMBER QUALIFIED
'RC ' Reactor Coolant Flow'DP BARTON 752 IFT0414- 2
.Transmiter IFT0415 2 IFT0416- 2 IFT0424, 2 IFT0425 2-IFT0426 2 IFT0434 2 IFT0435 2 IFT0436 2
'. RC - - Pressurizer Pressure BARTON IPT0455 1 Transmitter IPT0456 1 IPT0457. 1 RC Pressurizer Level DP BARTON IPT0459 1 Transmitter IPT0460 1 IPT0461 1 RC- .. Reactor l Coolant System BARTON IPT0402~ l
' Wide Range Pressure Transmitter
, .RC- Reactor Coolant. System VERITRAK IPT0403 3 4 Wide. Range' Pressure
-Transmitter
. RC. '1" Diaphragm Valve-Limit NAMCO EA-180 XVD8047: 1 Switch 5 _
j
Page 18 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED RC 1" Diaphagm. Valve Solen'.sid ASCO NP-831654V XVD8047 1 RC- Diaphragm Valve Solenoid ASCO. NP-831654V XVD8033 1 XVD8028 1 4
RC' 2" Motor Operated Globe LIMITORQUE SMB-00 XVT8095A 1 Valve Operator XVT8095B 1 XVT8096A 1 XVT8096B 1 RC Stem Mounted Limit Switch NAMCO EA-180 XVD8033 1 XVD8028 1 RC 3" Diaphragm Valve Limit. NAMCO EA-180 PCV444B 1 Switch PCV445A 1 PCV445B 1 RC 3"' Diaphragm Valve Solenoid ASCO NP-831654V PCV444B 1 PCV445A 1 PCV445B 1 RH 8" Gate' Valve Motor Operator LIMITORQUE SB-00 XVG8706A 1 XVG8706B 1 i
)
.s
+
Page 19 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALITIED
'RH
.2" Globe Valve Motor LIMITORQUE SMB-00-10 FCV602A. 1 Operator FCV602B l' RH- 12". Gate Valve Operator LIMITORQUE SB-2 XVG8701A '1 XVG8701B 1 XVGP702A 1 XVG8702B 1
'RH RHR Pump Motor WESTINGHOUSE 5008 XPP0031A 1 XPP0031B 1 RH- Stem Mounted Limit Switch NAMCO EA-180 XVG8706A 1 XVG8706B 1 RH 12" Gate Valve Limit Switch NAMCO EA-180 XVG8701B 1 XVG8702A 1 RM Containment High. Range Area. VICTOREEN 877-1 With RMG0018 1 Monitor Detector Connector and Cable SI 3" Gate Valve Motor LIMITORQUE SB-00. XVG8884 1
~ Operator XVG8885 1
' XVG8886 1 i
+
Paga 20 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED SI 14" Gate Valve Motor LIMITORQUE SB-2 XVG8811A 1 Operator XVG8811B 1 XVG8812A 1 XVG8812B l-XVG8809A 1 XVG8809B 1 SI 12" Gate Valve LIMITORQUE SBD-3 XVG8808A 2 Motor Operators XVG8808B 2 XVG8808C 2 SI 10" Gate Valve Motor LIMITORQUE SB-1 XVG8887A 1 Operator XVG8887B 1 SI 10" Gate Valve Motor LIMITORQUE SBD-3 XVG8888A 1 Operator XVG8888B 1 XVG8889 1 SI 3" Gate Valve Motor LIMITORQUE SB-00 XVG8801A 1 Operated XVG8801B 1 XVG8803A 1 XVG8803B 1 SI 3/d" Globe Valve Solenoid ASCO NP-831654V XVT8871 1 SI 1" Globe Valve Solenoid ASCO NP-331654v XVT8880 1 XVT8860 1
Page 21 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED SI 14" Gate Valve Limit Switch NAMCO EA-180 XVG8809A 1 XVG8809B 1 SI 3/4" Globe Valve ASCO NP-831654V XVT8961 1 SI Stem Mounted Limit Switch NAMCO EA-180 XVT8880 1 XVT8860 1 XVT8961 1 SI 3/4" Glove Valve Limit NAMCO EA-180 XVT8871 1 Switch SP 10" Motor Operated Gate LIMITORQUE SMB-00-15 XVG3003A 1 Valve Operator XVG3003B 1 SP 12" Motor Operated Gate LIMITORQUE SMB-005-10 XVG3001A 1 Valve Operator XVG3001B 1 SP 3" Motor Operated Gate LIMITORQUE SMB-000-2 XVG3002A 1 l Valve Operator XVG3002B 1 1 SP 12" Motor Operated Gate LIMITORQUE SMB-00-5 XVG3004A 1 Valve Operator XVG3004B 1 XVG3005A 1 XVG3005B 1 SP Reactor Building Spray GENERAL ELECTRIC K Horizontal MPP0038A 1 Pump Motor Frame 8210S MPP0038B 1 SK 821055C44
1 ,- - s
,c --i
~Page-22
~ "
CLASS lE EQUIPMENT.
SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS
- SYS ~ EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER -QUALIFIED
- SP;- -Reactor Building Spray' ROSEMOUNT ll53DA4 IFT7368- 1-
. Pump. Discharge Flow IFT7378 .1 NP832lA5E- 1.
~
SE. 1" Air' Operated Ball ASCO. XVA9311A-Valve Solenoid XVA9312A ~ 1-XVA9311B 1-XVA9312B 1
. SS- . Nuclear-Sampling System VALCOR - V526-5293-6 XVX9356A -1
-Isolation Solenoid valves XVX9356B l-XVX9339 1 XVX9364B 1 XVX9364C 1-XVX9357 1 XVX9365B 1 XVX9365C' l
XVX9387 1.
XVX9398A 1
~XVX9398B .1 ,
XVX9398C 1 i
SS 1" Air Operated Ball Valve NAMCO EA-180 XVA9311A 1.
. Limit-Switch XVA9312A 1 .)
XVA9311B 1 XVA9312B 1 9
Page 23 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS -EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED SW '16". Motor Operated Gate LIMITORQUE SMB-00-15 XVG3103A 1 Valve Operator XVG3107A 1 SW 12" Motor' Operated Gate LIMITORQUE SMB-00-10 XVG3111A 1 Valve Operator XVG3112A 1 SW 2" Air Operated Globe ASCO NP8323 XVT3164 1 Valve Solenoid XVT3165 1 XVT3169 1 SW 16" Motor Operated Butterfly LIMITORQUE SMB002/H2BC XVB3100A 1 Valve Operator SW 12" Motor Operated Butterfly LIMITORQUE SMB0002/H0BC XVB3110A 1 Valve Operator SW Service Water Booster Pump LOUIS ALLIS COG 5B/449TS MPP0045A 2 Motor Frame MPP0045B 2 SW .RTD, Service Water PYCO 122-4030- ITE4467 1 Temperature Out Of Reactor Building Cooling Units SW- Service Water Booster Pump ROSEMOUNT ll53DA4 IFT4466 1 Discharge Flow IFT4496 1 SW 2" Air Operated Globe Valve NAMCO EA-180 XVT3164 1 Limit Switch XVT3165 1 XVT3169 1 4
4 Page 24 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED VL Emergency Feedwater Pump RELIANCE TEAO XFN0083A 2 Area Coolig Unit Fan Motor XFN0083B 2 VL Service Water Booster Pump RELIANCE TEAO XFN0081A 2 Area Cooling Unit Fan XFN0081B 2 VL RHR/ Spray Pump From Cooling RELIANCE TEAO XFN0049A 1 Unit Fan Motor XFN0049B 1 VL Charging Pump Room Cooling RELIANCE TEAO XFN0046A 1 Unit Fan Motor XFN0046B 1 XFN0047 1 VL Auxiliary Building Motor RELIANCE TEAO XFN0132 2 Control Center and Switch-gear Air Handling Unit Fan Motor VU 2" Air Operated Globe ASCO NP8323 XVT6384A 1 Valve Solenoid XVT6384B 1 XVT6385A 1 XVT6385B 1 VU Air Operated Globe NAMCO EA-180 XVT6384A 1 Valve Limit Switches XVT6384B 1 XVT6385A 1 XVT6385B 1
O.
e Page 25 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER- TYPE / MOD NUMBER TAG NUMBER- QUALIFIED WL 3" Globe Valve Solenoid ASCO 206-381-6RVU LCV1003 1 NP-831654V XVD7136 1 WL 3/4" Globe Valve Solenoid ASCO NP-831654V XVD7126 1 XVD7150 1 WL '3/4" Globe Valve Limit NAMCO EA-180 XVD7126 1 Switch XVD7150 1 WL 3" Globe Valve Limit NAMCO EA-180 XVD7136 1 Switch 600 Volt Control Cable ROCKBESTOS Firewall III EK-B3(*) 1 600 volt Control Cable KERITE FR-FR EK-Bl(*) 1 600 Volt Power Cable KERITE HT-FR EK-A2(*) 1 EK-A3(*) 1
'Special Instrument Cable OKONITE Okozel EK-C6,A,B, C,(*) 1 Instrument Cable SAMUEL MOORE EPDM - HYPALON EK-Cl(*) 1 (3D and 3J) 6 8 KV Power Cable OKONITE EPR - HYPALON EK-Al(*) 1 Triaxial Cable BOSTON XLPE-TEFZEL EK-C2A(*) 2 INSULATED WIRE XLPE-HYPALON EK-C2B(*) 2
-Page.26 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRI FION- MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED Switchboard Wire ROCKBESTOS Firewall SIS EK-J9(*) 1 -
2/C #18 Twinax Cable BRAND REX TCD95285 EK-Cl2B(*) 1 ROCKBESTOS RSS-6-ll2 EK-J9C(*) 2 Switchboard Wire RAYCHEM Flamtrol EK-J2(*) 1 Heat Tracing RAYCHEM 10PTV1 EK-Hl(*) 1 Miscellaneous Connectors D.G. O'BRIEN C39P0001-G01 EL-44AA(*) 1 C42P5008G-G01 1 Low Voltage Power Terminations Sleeve RAYCHEM WCSF-N EK-I9A, 20A, 21A(*) 1 Motor Termination Kit RAYCHEM N-MCK EK-121B, 21C(*) 1 Kerite Splice KERITE S-2NS-NUC EK-I4B(*) 1 EK-I8A(*) 1 EK-ISA(*) 1 EK-I4C(*) 1 Terminal Blocks STATES ZWM EN-6 (*) 1 EN-74(*) 1
Page 27 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED 8 KV Cable Terminations Terminal Insulating Material
. Insulating Tape OKONITE T95 EKI3A9(*) 1 Jacketing Tape OKONITE T35 EKI3B(*) 1 Cement OKONITE 604-45-8104 EKI3C(*) 1 8'KV Cable Terminations For Component Cooling RAYCHEM Thermofit EKI2E(*) 1 Water Pump Motor HVT-CBN
or Charging Pump Motor RAYCHEM Thermofit EKI2E(*) 1 and Transfer Switch HVT-CBN For Emergency Feedwater Pump RAYCHEM Thermofit EKI2E(*) 1 HVT-CBN For Spray Pump Motor RAYCHEM Thermofit EKI2E(*) 1 HVT-CBN
Page 28 CLASS lE EQUIPMENT SUBJECT TO HARSH ENVIRONMENTAL CONDITIONS SYS EQUIPMENT DESCRIPTION MANUFACTURER TYPE / MOD NUMBER TAG NUMBER QUALIFIED Control Cable Terminations RAYCHEM WCSF-N EKI9A (*1 1 Splicing Sleeve EK120A(*) 1 Cable Breakout Type V RAYCHEM 302A812-52 EK19B (*) 1 Stube Connection Splice Kits RAYCHEM. NPKV EK-I20B, 1 20C(*) 1 AMP Connectors AMP 36906 EK-J1(*) 1 321280 Terminal Blocks ' STATES ZWM EN-6 (*) 1 EN-74(*) 1 Instrument Cable Terminations RAYCHEM WCSF-N EK-19A(*) 1 EK-I20A(*) 1 EK-I21A(*) 1
- 1. . Qualified. See Revision 4 of Virgil C. Summer Nuclear Station, Environmental Qualification of Safety Related Electrical Equipment per NUREG 0588 provided February 19, 1982.
- 2. Exempt from Qualification. See document described in (1) above.
- 3. Qualified. Information provided November 3, 1982.
- 4. Qualified. Information provided September 29, 1982.
- 5. Qualified. Information provided July 23, 1982.
o EQUIPMENT WHOSE QUALIFICATION IS INCOMPLETE
- 1. Reactor Vessel Level Indication System (RVLIS)
As discussed in our letter of March 8, 1983, the Westinghouse RVLIS system installed has been approved by the Staf f as documented in Generic Letter 82-28.
Westinghouse has recently provided South Carolina Electric and Gas Company (SCE&G) the_ test reports documenting the IEEE 323-1974 harsh environment qualification for the Barton Model 581 Hydraulic Isolators, the Barton Model 353 High Volume Sensors and the MINCO Model S8809 and S8810 RTDs which are installed. The review, acceptance and placement of the test reports in the equipment qualification file will be complete by the end of the second refueling outage after March 31, 1982 or by March 31, 1985 whichever is earlier.
- 2. Pressurizer Safety Valve Position Indication Switches As discussed in our letter of September 29, 1982, prototype switches have successfully completed all phases of environmental qualification testing up to the LOCA/MSLB. The vendor, Crosby Valve, is develop-ing a retest schedule. The retest and submittal of the test report by the vendor and the review, accep-tance and placement of the documentation in the equipment qualification file by SCE&G will be complete by the end of the second refueling outage after March 31, 1982 or by March 31, 1985 whichever is earlier.
-3. Core'Subcooling Monitor System As discussed in our letter of March 8, 1983, avail-ability of qualified incore thermocouple connectors, cable and other required hardware is being investi-gated. Hardware procurement and delivery limitations prohibit installation prior to our estimated first refueling outage. When the equipment is procured, the qualification documentation will be obtained, reviewed, approved and placed in the equipment qualification file. This will be complete by the end of the second refueling outage after March 31, 1982 or by March 31, 1985 whichever is earlier.
. _ _.
