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| | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | page count = 3 | | | page count = 3 |
| | project = | | | project = TAC:MA1592 |
| | stage = Approval | | | stage = Approval |
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| =Text= | | =Text= |
| {{#Wiki_filter:}} | | {{#Wiki_filter:. __ . .. _ __ _ _._ _ _.___.._._.____.___. _ _ _ _ _ _ . . _ _ _ |
| | November 4, 1998 |
| | ., , Mr. Giry J. Taylor Vice President, Nucber Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88 Jenkinsville, South Carolina 29065 |
| | |
| | ==SUBJECT:== |
| | APPROVAL TO USE ASME CODE CASE N-416-1 AT V. C. SUMMER NUCLEAR STATION (TAC NO. MA1592) - |
| | |
| | ==Dear Mr. Taylor:== |
| | a South Carolina Electric and Gas Company's (SCE&G's) {{letter dated|date=April 29, 1998|text=April 29,1998, letter}} submitted a relief request seeking NRC approval to use the alternative rules of the American Society of |
| | ; Mechanical Engineers (ASME) Code Case N-416-1 for Class 1,2, or 3 piping and components. |
| | J We determined that the proposed alternative to use Code Case N-416-1 with the additional |
| | ,. examinations proposed, in lieu of performing a system hydrostatic test on Class 1,2, and 3 piping and components after making welding repairs or installing replacement items by welding, |
| | , 'provides an acceptable level of quality and safety. Accordingly, your proposed alternative to use Code Case N-416-1 with additional surface examinations on the root-pass layer of butt and |
| | - socket welds on the pressure-retaining boundary of Class 3 components is authorized pursuant |
| | , to 10 CFR 50.55a(a)(3)(i) for Class 1,2, and 3 systems. We authorize the use of Code Case |
| | - N-416-1, with the additional surface examination as noted above, for the duration of the - |
| | currently approved inservice inspection program plan interval, or until the Code case is approved for general use by reference in Regulatory Guide 1.147.-- At that time, SCE&G must follow the conditions, if any, specified in the regulatory guide. The enclosed Safety Evaluation contains our evaluation of your relief request. |
| | , Sincerely, ORIGINAL SIGNED BY: |
| | Herbert N. Berkow, Director |
| | ;' Project Directorate ll-2 9811090054 981104 Division of Reactor Projects - l/il DR A M 05 5 p Office of Nuclear Reactor Regulation Docket No. 50-395 |
| | |
| | ==Enclosure:== |
| | Safety Evaluation NRC FILE CENTER CG.,P3l cc w/ encl: See next page i |
| | 'C M Q Distnbution-Docket File . PD ll-2 RF MTschiltz GHill(2) I PUBLIC JZwolinski LPlisco, Ril OGC TMcLellan ACRS FILENAME - G:\ SUMMER \MA1592.REL *See previous concurrence OFFICE PM.PDll-2 LA:PDil-2 EGCB* OGC* NLO DfQR-2 NAME MPadYan Dunnink GBagchi MYoung hBho[ |
| | DATE 11/ /98 11/J /98 10/20/98 10/28/98 11/ 3/98 COPY Yes/No Mo-Yes/No 1);,AqQ1 OFFICIAL RECORD COPY |
| | |
| | y.y m#*4 UNITED STATES g j t |
| | NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 20666-0001 |
| | $, / November 4,1998 Mr. Gary J. Taylor Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88 Jenkinsville, South Carolina 20065 |
| | |
| | ==SUBJECT:== |
| | APPROVAL TO USE ASME CODE CASE N-416-1 AT V. C. SUMMER NUCLEAR STATION (TAC NO. MA1592) |
| | Dear Mr. Taylor. |
| | South Carolina Electric and Gas Company's (SCE&G's) {{letter dated|date=April 29, 1998|text=April 29,1998, letter}} submitted a relief request seeking NRC approval to use the alternative rules of the American Society of Mechanical Engineers (ASME) Code Case N-416-1 for Class 1,2, or 3 piping and components. |
| | We determined that the proposed alternative to use Code Case N-416-1 with the additional examinations proposed, in lieu of performing a system hydrostatic test on Class 1,2, and 3 piping and components after making welding repairs or installing replacement items by welding, provides an acceptable level of quality and safety. Accordingly, your proposed alternative to use Code Case N-416-1 with additional surface examinations on the root-pass layer of butt and socket welds on the pressure-retaining boundary of Class 3 components is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for Class 1,2, and 3 systems. We authorize the use of Code Case N 416-1, with the additional surface examination as noted above, for the duration of the currently approved inservice inspection program plan interval, or until the Code case is approved for general use by reference in Regulatory Guide 1.147. At that time, SCE&G must follow the conditions, if any, specified in the regulatory guide. The enclosed Safety Evaluation contains our evaluation of your relief request. |
| | Sincerely, Op l' |
| | H rbert N. Berkow, Director roject Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-395 |
| | |
| | ==Enclosure:== |
| | Safety Evaluation cc w/ encl: See next page |
| | |
| | ' Mr. G:ry J. Teylor VIRGIL C. SUMMER NUCLEAR STATION South Carolina Electric & Gas Company cc: |
| | 4 Mr. R. J. White ' |
| | J. B. Knotts, Jr., Esquire |
| | ~ Nuclear Coordinator Winston & Strawn Law Firm 4 |
| | S.C. Public Service Authority 1400 L Street, N.W. |
| | c/o Virgil C, Summer Nuclear Station Washington, D.C. 20005-3502 Post Office Box 88, Mail Code 802 Jenkinsville, South Carolina 29065 i |
| | Resident inspector / Summer NPS c/o U.S. Nuclear Regulatory Commission Route 1, Box 64 Jenkinsville, South Carolina 29065 Regional Administrator, Region ll U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303 Chairman, Fairfield County Council Drawer 60 Winnsboro, South Carolina 29180 = |
| | j Mr. Virgil R. Autry, Director ! |
| | i Division of Radioactive Waste Management Bureau of Land & Waste Management |
| | ) |
| | Department of Health & Environmental Control i 2600 Bull Street Columbia,-South Carolina 29201 l ME. Robert M. Fowlkes, Manager I Ooerations - |
| | South Carolina Electric & Gas Company Virgil C. Summer Nuclear Statiorn Mail Code 303 ' |
| | Post Office Box 88 - |
| | . Jenkinsville, South Carolina 20065 e |
| | Ms. April R. Rice, Manager Nuclear Licensing & Operating Experience |
| | . South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station, Mail Code 830 |
| | . Post Office Box 88 j Jenkinsville, South Carolina 20065 a |
| | i 4 |
| | .-c., .. . .s-.. - - |
| | . ., .-n , ,}} |
Letter Sequence Approval |
|---|
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|
MONTHYEARML20155G4451998-11-0404 November 1998
Forwards Safety Evaluation Re Relief Request to ASME Code Case N-416-1,for Class 1,2 & 3 Piping & Components.Proposed Alternative with Addl Exams Proposed,In Lieu of Performing Sys Hydrostatic Test Provides Acceptable Level of Safety
Project stage: Approval
1998-11-04
[Table View] |
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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
[Table view]
Category:OUTGOING CORRESPONDENCE
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
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
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
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
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
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
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
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
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
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
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
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
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)
ML20196K9771999-03-25025 March 1999
Refers to Open Meeting Conducted at Licensee Request at NRC Region II Offices in Atlanta,Ga on 990315 Re Upcoming April 1999 Refueling Outage,Back Leakage Into Residual Heat Removal Sys & Licensee Position on Hazard Barriers
ML20205D7981999-03-23023 March 1999
Advises of NRC Planned Insp Effort Resulting from Summer Plant Performance Review for Period July 1998 Through Jan 1999.Historical Listing of Plant Issues & Details of NRC Insp Plan for Next Eight Months Encl
ML20204J7201999-03-15015 March 1999
Forwards Insp Rept 50-395/99-01 on 990103-0213.No Violations Noted.Sce&G Conduct of Activities During Insp Period Generally Characterized by Safety Conscious Operations & Conservative Decision Making
ML20207J0661999-03-0303 March 1999
Confirms 990226 Telephone Conversation Between a Rice & M Widman Re Meeting Scheduled for 990315.Purpose of Meeting Will Be to Discuss VC Summer Upcoming Refueling Outage & Items of Interest
ML20203F4351999-02-12012 February 1999
Forwards SER Finding Licensee Adequately Addressed GL 96-05 Requested Actions & Have Acceptable Program to Periodically Verify safety-related MOV design-basis Capability at Virgil C Summer Nuclear Station
ML20203G5751999-02-0505 February 1999
Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Ltr Indicating No Candidates or Ltr Listing Names of Candidates for Exam
ML20203G4091999-02-0101 February 1999
Forwards Insp Rept 50-395/98-10 on 981122-990102.No Violations Noted.Licensee Conduct of Activities at VC Summer Facility Was Generally Characterized by Safety Conscious Operations & Conservative Decision Making
ML20199J0571999-01-21021 January 1999
Forwards RAI Re 980918 Request for Amend to Plant Ts.Amend Would Incorporate New Best Estimate Analyze for Core Operations Core Power Distribution Monitoring & Support Sys Into Ts.Response Requested within 15 Days of Receipt of Ltr
ML20199K0281999-01-13013 January 1999
Discusses NRC Organization Charts to Be Implemented by Region 2 on 990117.Forwards Organization Charts for Info
ML20198Q7471999-01-0505 January 1999
Informs That 981204 Request to Extend RAI Response Period Re GL 97-01 to 990115 Has Been Accepted
ML20199E5971998-12-23023 December 1998
Provides Summary of Training Manager Conference Conducted on 981105.Forwards Agenda,List of Attendees,Handouts & Preliminary Schedule for FY99 & FY00.Goal of Providing Open Forum of Operator Licensing Issues Met
ML20198N8341998-12-21021 December 1998
Forwards Insp Rept 50-395/98-09 on 981011-1121 & NOV Re Failure to Follow Procedures During Snubber Testing
ML20198F4181998-12-18018 December 1998
Forwards SER Granting Licensee 980513 Request for Approval to Temporarily Repair ASME Code Class 3 Piping at VC Summer Nuclear Station Pursuant to 10CFR50.55a(g)(6)(i)
ML20198B7611998-12-0303 December 1998
Informs That on 981007,generic Fundamentals Exam Was Administered to 148 Candidates at 21 Facilities.Summary of Statistical Results of Exam Listed.Contents of Exam Along with Associated Input Data Needed for Updating Catalog Encl
ML20196G0981998-12-0303 December 1998
Requests Proposed Alternatives to Confirm That Listed Structures Free from Gross Erosion or Other Effects That Could Impair Structures Stability,Per NRC Category I SW Pond Dam Insp
ML20198A7711998-12-0202 December 1998
Advises of Planned Insp Effort Resulting from 981102 Insp Planning Meeting.Details of Insp Plan for Next 4 Months & Historical Listing of Plant Issues,Called Plant Issues Matrix Encl
ML20196D5831998-11-12012 November 1998
Informs That on 981007,NRC Administered Gfes of Written Operator Licensing Examination.Copies of Both Forms of Exam Including Answer Keys,Grading Results for Facility & Copies of Indivividual Answer Sheets Encl.Without Encl
ML20195E9761998-11-0909 November 1998
Forwards Insp Rept 50-395/98-08 on 980906-1010.No Violations Noted.Conduct of Activities at VC Summer Facility Was Generally Characterized by Safety Conscious Operations & Conservative Decision Making
ML20155G4451998-11-0404 November 1998
Forwards Safety Evaluation Re Relief Request to ASME Code Case N-416-1,for Class 1,2 & 3 Piping & Components.Proposed Alternative with Addl Exams Proposed,In Lieu of Performing Sys Hydrostatic Test Provides Acceptable Level of Safety
ML20154Q9451998-10-21021 October 1998
Forwards SE Re Approval to Use ASME Code Case N-498-1 for Periodic Hydrostatic Testing of ASME Class 3 Piping at Plant
ML20155B8071998-10-0909 October 1998
Extends Invitation to Attend Training Managers Conference on 981105 in Atlanta,Georgia.Conference Designed to Inform Regional Training & Operations Mgt of Issues & Policies That Affect Licensing of Reactor Plant Operators
ML20155B1561998-10-0505 October 1998
Forwards Insp Repts 50-395/98-07 on 980726-0905.No Violations Noted
ML20239A3671998-09-24024 September 1998
Forwards Insp Rept 50-395/98-06 on 980628-0725.No Violations Noted.During Insp Period,Nrc Received Response to NOV 50-395/98002-01.Response Meets Requirements of 10CFR2.201
ML20151V1911998-09-0808 September 1998
Forwards Request for Addl Info Re GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations. Response Requested within 90 Days of Date of Ltr
ML20153F0261998-09-0202 September 1998
Refers to Insp Rept 50-395/98-06 Issued on 980824.Ltr Transmitting Insp Rept Referred to Wrong Violation Number in Paragraph Three.Corrected Page with Violation Number 50-395/98004-01 Encl
ML20151T9241998-08-27027 August 1998
Informs of Change Being Implemented by Region II Re Administrative Processing of Licensee Responses to Novs. Licensee NOV Responses Which Accept Violations & Require No Addl Communication to Be Ack in Cover Ltr of Next Insp Rept
ML20239A4521998-08-26026 August 1998
Forwards SALP Insp Rept 50-395/98-99 for Period of 961027- 980725
1999-09-09
[Table view] |
Text
. __ . .. _ __ _ _._ _ _.___.._._.____.___. _ _ _ _ _ _ . . _ _ _
November 4, 1998
., , Mr. Giry J. Taylor Vice President, Nucber Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88 Jenkinsville, South Carolina 29065
SUBJECT:
APPROVAL TO USE ASME CODE CASE N-416-1 AT V. C. SUMMER NUCLEAR STATION (TAC NO. MA1592) -
Dear Mr. Taylor:
a South Carolina Electric and Gas Company's (SCE&G's) April 29,1998, letter submitted a relief request seeking NRC approval to use the alternative rules of the American Society of
- Mechanical Engineers (ASME) Code Case N-416-1 for Class 1,2, or 3 piping and components.
J We determined that the proposed alternative to use Code Case N-416-1 with the additional
,. examinations proposed, in lieu of performing a system hydrostatic test on Class 1,2, and 3 piping and components after making welding repairs or installing replacement items by welding,
, 'provides an acceptable level of quality and safety. Accordingly, your proposed alternative to use Code Case N-416-1 with additional surface examinations on the root-pass layer of butt and
- socket welds on the pressure-retaining boundary of Class 3 components is authorized pursuant
, to 10 CFR 50.55a(a)(3)(i) for Class 1,2, and 3 systems. We authorize the use of Code Case
- N-416-1, with the additional surface examination as noted above, for the duration of the -
currently approved inservice inspection program plan interval, or until the Code case is approved for general use by reference in Regulatory Guide 1.147.-- At that time, SCE&G must follow the conditions, if any, specified in the regulatory guide. The enclosed Safety Evaluation contains our evaluation of your relief request.
, Sincerely, ORIGINAL SIGNED BY:
Herbert N. Berkow, Director
- ' Project Directorate ll-2 9811090054 981104 Division of Reactor Projects - l/il DR A M 05 5 p Office of Nuclear Reactor Regulation Docket No. 50-395
Enclosure:
Safety Evaluation NRC FILE CENTER CG.,P3l cc w/ encl: See next page i
'C M Q Distnbution-Docket File . PD ll-2 RF MTschiltz GHill(2) I PUBLIC JZwolinski LPlisco, Ril OGC TMcLellan ACRS FILENAME - G:\ SUMMER \MA1592.REL *See previous concurrence OFFICE PM.PDll-2 LA:PDil-2 EGCB* OGC* NLO DfQR-2 NAME MPadYan Dunnink GBagchi MYoung hBho[
DATE 11/ /98 11/J /98 10/20/98 10/28/98 11/ 3/98 COPY Yes/No Mo-Yes/No 1);,AqQ1 OFFICIAL RECORD COPY
y.y m#*4 UNITED STATES g j t
NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 20666-0001
$, / November 4,1998 Mr. Gary J. Taylor Vice President, Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88 Jenkinsville, South Carolina 20065
SUBJECT:
APPROVAL TO USE ASME CODE CASE N-416-1 AT V. C. SUMMER NUCLEAR STATION (TAC NO. MA1592)
Dear Mr. Taylor.
South Carolina Electric and Gas Company's (SCE&G's) April 29,1998, letter submitted a relief request seeking NRC approval to use the alternative rules of the American Society of Mechanical Engineers (ASME) Code Case N-416-1 for Class 1,2, or 3 piping and components.
We determined that the proposed alternative to use Code Case N-416-1 with the additional examinations proposed, in lieu of performing a system hydrostatic test on Class 1,2, and 3 piping and components after making welding repairs or installing replacement items by welding, provides an acceptable level of quality and safety. Accordingly, your proposed alternative to use Code Case N-416-1 with additional surface examinations on the root-pass layer of butt and socket welds on the pressure-retaining boundary of Class 3 components is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for Class 1,2, and 3 systems. We authorize the use of Code Case N 416-1, with the additional surface examination as noted above, for the duration of the currently approved inservice inspection program plan interval, or until the Code case is approved for general use by reference in Regulatory Guide 1.147. At that time, SCE&G must follow the conditions, if any, specified in the regulatory guide. The enclosed Safety Evaluation contains our evaluation of your relief request.
Sincerely, Op l'
H rbert N. Berkow, Director roject Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-395
Enclosure:
Safety Evaluation cc w/ encl: See next page
' Mr. G:ry J. Teylor VIRGIL C. SUMMER NUCLEAR STATION South Carolina Electric & Gas Company cc:
4 Mr. R. J. White '
J. B. Knotts, Jr., Esquire
~ Nuclear Coordinator Winston & Strawn Law Firm 4
S.C. Public Service Authority 1400 L Street, N.W.
c/o Virgil C, Summer Nuclear Station Washington, D.C. 20005-3502 Post Office Box 88, Mail Code 802 Jenkinsville, South Carolina 29065 i
Resident inspector / Summer NPS c/o U.S. Nuclear Regulatory Commission Route 1, Box 64 Jenkinsville, South Carolina 29065 Regional Administrator, Region ll U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303 Chairman, Fairfield County Council Drawer 60 Winnsboro, South Carolina 29180 =
j Mr. Virgil R. Autry, Director !
i Division of Radioactive Waste Management Bureau of Land & Waste Management
)
Department of Health & Environmental Control i 2600 Bull Street Columbia,-South Carolina 29201 l ME. Robert M. Fowlkes, Manager I Ooerations -
South Carolina Electric & Gas Company Virgil C. Summer Nuclear Statiorn Mail Code 303 '
Post Office Box 88 -
. Jenkinsville, South Carolina 20065 e
Ms. April R. Rice, Manager Nuclear Licensing & Operating Experience
. South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station, Mail Code 830
. Post Office Box 88 j Jenkinsville, South Carolina 20065 a
i 4
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. ., .-n , ,
