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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:NRC TO UTILITY
MONTHYEARML20062G3481990-11-16016 November 1990 Forwards Insp Rept 50-395/90-27 on 901001-31.No Violations Noted ML20058F3981990-11-0101 November 1990 Ack Receipt of & Forwards Staff Understanding of 901025 Mtg Re Status of GSIs Unimplemented at Facility ML20058D2421990-10-29029 October 1990 Approves 900928 Request for Extension of Schedule for Implementation of Generic Ltr 89-10 Re motor-operated Valve Testing ML20058A5961990-10-19019 October 1990 Forwards Insp Rept 50-395/90-26 on 900918-19.Violations Noted But Not Cited ML20059N9491990-10-12012 October 1990 Ack Receipt of 900816 & 0920 Ltrs Which Forwarded Objectives & Scenario Package for 901107 Emergency Exercise ML20062B6781990-10-12012 October 1990 Requests Analyses of Liquid Samples Spiked W/Radionuclides Completed within 60 Days of Sample Receipt ML20058B5201990-10-12012 October 1990 Forwards Insp Rept 50-395/90-24 on 900901-30.No Violations or Deviations Noted ML20059J6091990-09-13013 September 1990 Advises That NRC Will Assess Conformance to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety- Related Equipment in post-implementation Audit Insps to Verify Adequacy of Util Efforts in Performing Verification ML20059E3341990-08-31031 August 1990 Advises That 881220 & 900822 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss Acceptable ML20059C4091990-08-30030 August 1990 Accepts Util 890301 & 900103 Responses to NRC Bulletin 88-011 Re Pressurizer Surge Line Thermal Stratification ML20059K1331990-08-28028 August 1990 Congratulates Rc Haag on Promotion to Position of Senior Resident Inspector at Plant ML20059C6231990-08-21021 August 1990 Requests Util Provide Ref Matls Listed in Encl for Written & Operating Exams Scheduled for Wk of 901126.Training Staff Should Retain Simulator Exam Scenerio Info Until Candidates Passed,Accepted Denial of Licenses or Completed Appeals ML20056B4551990-08-15015 August 1990 Forwards Insp Rept 50-395/90-21 on 900701-31 & Notice of Violation ML20059A3461990-08-13013 August 1990 Forwards Final SALP Rept 50-395/90-11 & Errata to Initial SALP Rept Covering Jan 1989 to Apr 1990 ML20058N9511990-08-13013 August 1990 Advises That 900720 Amend 28 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20056A7911990-08-0606 August 1990 Forwards Safety Evaluation Re Capability of Plant to Meet Requirements of Branch Technical Position Rsb 5-1, Design Requirements of RHR Sys IR 05000395/19900151990-07-19019 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-395/90-15. Implementation of Corrective Actions Will Be Examined During Future Insps ML20055H3751990-07-12012 July 1990 Forwards Insp Rept 50-395/90-18 on 900601-30 & Notice of Violation ML20055H6021990-07-0606 July 1990 Forwards Insp Rept 50-395/90-19 on 900611-15.Violations Noted ML20059M9581990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C7341990-06-0101 June 1990 Advises of EOP Insp to Be Performed at Plant on 900820-24. Insp Will Verify That Human Factors Considerations Adequately Addressed in EOPs & Review Adequacy of Technical Changes to EOPs in Response to Previous Insps ML20248E5131989-09-21021 September 1989 Forwards Amend 3 to Indemnity Agreement B-86,reflecting Changes to 10CFR140,effective 890701,increasing Primary Layer of Nuclear Energy Liability Insurance IR 05000395/19890131989-09-20020 September 1989 Ack Receipt of Util Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-395/89-13 ML20247Q0431989-09-18018 September 1989 Informs of Closeout of Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs ML20247H0981989-09-13013 September 1989 Advises That 890822 Amend 27 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion Into Plan ML20248C9361989-09-13013 September 1989 Forwards Insp Rept 50-395/89-17 on 890801-31.Findings Indicate That Certain Activities Appear to Violate NRC Requirements But Violations Not Being Cited ML20247F4711989-09-0707 September 1989 Discusses Requalification Program Evaluation Scheduled for Wk of 891204.Encl Ref Matls Requested by 891004 IR 05000395/19890141989-08-31031 August 1989 Discusses Insp Rept 50-395/89-14 on 890614-15 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000 ML20246P4371989-08-18018 August 1989 Forwards Insp Rept 50-395/89-15 on 890724-28 & Notice of Violation ML20245J0881989-08-16016 August 1989 Advises That Addl Info Needed to Support 890615 Submittal Re Proposal to Extend OL of Plant to 40 Yrs.Unclear W/Respect to Whether 30 or 40 Yr Operating Life Assumed ML20246D1291989-08-16016 August 1989 Advises That Reactor Operator & Senior Operator Written & Operating Exams Scheduled for Wk of 891204.All Completed Application Info Should Be Submitted 30 Days Prior to First Exam in Order to Review Training & Experience of Candidates ML20246E6681989-08-11011 August 1989 Confirms Util Participation in NRC Regulatory Impact Survey on 890913 at Plant Site,Per 890808 Telcon.Agenda Encl ML20246C6391989-08-10010 August 1989 Forwards Summary of 890728 Enforcement Conference on Insp Rept 50-395/89-14 Re Assumption of Licensed Operator Duties by Unqualified Operator ML20248D9541989-08-0707 August 1989 Forwards Insp Rept 50-395/89-16 on 890710-14.No Violations or Deviations Noted ML20246A5241989-08-0404 August 1989 Forwards Insp Rept 50-395/89-13 on 890701-31 & Notice of Violation ML20247R6031989-07-28028 July 1989 Forwards Insp Rept 50-395/89-12 on 890626-30.No Violations or Deviations Noted ML20247D5671989-07-12012 July 1989 Forwards Insp Rept 50/395/89-11 on 890601-30.Violations Not Being Cited Because Criteria for Categorization of licensee-identified Violations Met ML20246P8311989-07-11011 July 1989 Forwards Insp Rept 50-395/89-10 on 890605-08.No Violations or Deviations Noted ML20246K5631989-07-11011 July 1989 Confirms 890630 Telcon W/Dm Verrelli Re 890728 Enforcement Conference in Region II Ofc to Discuss Unqualified Operator Standing Watch at Facility.Proposed Agenda Encl ML20246P1671989-06-29029 June 1989 Advises That 890605 Amend 26 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable. Understands That More Detailed Description of Wall Ref in Item 12 on Page 5-7-B Will Be Included in Next Amend ML20245J8931989-06-26026 June 1989 Forwards Comments on Util Response to Generic Ltr 88-17 Re Expeditious Actions for Loss of DHR for Plant.Aspects of Response Not Fully Understood Listed for Consideration ML20245F4401989-06-22022 June 1989 Forwards Safety Evaluation Re Request for Relief from ASME Code Section XI Re Hydrostatic Test Requirement ML20245G2771989-06-13013 June 1989 Requests Util Complete Analyses of Liquid Samples Spiked W/Radionuclides within 60 Days of Receipt of Sample.Spiked Samples Will Be Sent Annually as Part of Routine Insp Program ML20244D7291989-06-12012 June 1989 Forwards Safety Evaluation Accepting Util 831104 Response to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Reliability On-Line Functional Testing ML20244C6601989-06-12012 June 1989 Advises That Based Upon Util Participation in Westinghouse Owners Group Program for Resolution of Item 1.b of NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification, 890301 Alternate Schedule Not Approved ML20245F7741989-06-0909 June 1989 Forwards Insp Rept 50-395/89-09 on 890501-31.No Violations or Deviations Noted ML20244D5931989-06-0101 June 1989 Forwards Requalification Exam Rept 50-395/OL-89-01 Administered During Wks of 890221 & 27 ML20244D0221989-05-30030 May 1989 Ack Receipt of Responding to NRC Re Weaknesses Noted in Program for Keeping Radiation Exposures ALARA IR 05000395/19890071989-05-23023 May 1989 Forwards Insp Rept 50-395/89-07 on 890401-30.Violations Noted ML20245B0361989-05-18018 May 1989 Forwards SALP Rept 50-395/88-32 for Aug 1987 - Dec 1988. Viewgraphs from 890328 Meeting Encl 1990-09-13
[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] |
See also: IR 05000395/1986022
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DEC 0 31987
Docket No.: 50-395
License No.: NPF-12
EA 87-07
South Carolina Electric and Gas Company
ATTN: Mr. D. A. Nauman, Vice President
Nuclear Operations
P. O. Box 764 (167)
Columbia, SC 29218
Gentlemen: 1
SUBJECT: NRC INSPECTION REPORT NO. 50-395/86-22
Our letter dated July 13, 1987, in response to your letter of April 9,1987,
stated that with regard to violation A, we concluded for the reasons presented
in the Enclosure to our letter, the violction occurred as stated in the Notice
of V M ation (NOV) transmitted with NRC Inspection Report No. 50-395/86-22.
With regard to your letter of August 7,1987, after careful review of the bases
for your denial, we continue to conclude, for the reasons presented in the
Enclosure to this letter, that the violation occurrer: as stated in the NOV. We
again have also considered your view that the proposed severity level for both
violations is not warranted and again concluded that the violations were
appropriately categorized as a Severity Level III problem.
Since you provided corrsctive actions for the violation durira the Enforcement
Conference held on December 16, 1986, as documented in NRC Inspection Report
No. 50-395/86-22 sent to you on March 12, 1987, no further response is
requi red. If your understanding of corrective actions has changed since this
meeting, you should provide the NRC an update of the corrective actions.
The NRC recognizes that the calculated dose of 420 rems is a quite conservative
value and that the safety implications of the dose may be significantly reduced
because of the extremely limited area of exposure. Because of the lessened
safety significance of this dose, as opposed to a similar dose to a large area
of skin, the NRC categorized the violation as a Severity Level III rather than
a Severity Level I, which is that listed in our Enforcement Policy in
10 CFR Part 2 for skin doses in excess of 375 rems. We recognize the unique j
circumstances of high doses to very small areas of the skin. We also agree ]
with your consultant's recommendation that the individual's cose record should i
contain a notation of the circumstances of this dose to put the dose in proper {
perspective. j
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South Carolina Electric -2- DEC 0 31987
and Gas Company
As we have indicated previously, the NRC recognizes the general need for a
reevaluation of the basis for dose assignment due to very small, highly
radioactive particles on the skin. The NRC formally requested the National
Council on Radiation Protection and Measurements to review and provide guidance
on the issue. We will keep you informed of any changes to our regulations and
criteria that may result from this review. In the interim, and unless there
are changes forthcoming, however, the agency will continue to' assess skin
exposures in accordance with the existing policy.
In accordance with Section .2.790 of the NRC's " Rules of Practice," Part 2,
Title 10, Code of Federal Regulations, a copy of this letter and its enclosure
will be placed in the NRC Public Document Room.
We appreciate your cooperation in this matter.
Sincerely,
OF3GRiAL W !E0 U"
lie 1SDilCR!,
J. Nelson Grace i
Regional Administrator
Enclosure:
Staff Assessment of Licensee i
Response to Notice of Violation with
Attachment
cc w/ encl:
0. S. Bradham, Director, Nuclear Plant
Operations
J. L. Skolds, Deputy Director
Operations and Maintenance
J. B. Knotts, Jr. 1
Debevoise and Liberman
W. A. Williams, Jr., Special
Assistant, Nuclear Operations -
Santee Cooper
A. M. Paglia, Jr., Manager
Nuclear Licensing
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South Carolina Electric -3- DEC O 31987
and Gas Company
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JLieberman, OE
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Enforcement Coordinators
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SConnelly, DIA
FIngram, PA
JHopkins, NRR
DE Files
DCS
State of South Carolina
NRC Resident Inspector
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ENCLOSURE
STAFF ASSESSMENT OF LICENSEE RESPONSE TO
NOTICE OF VIOLATION
Violation A (50-395/86-22-02) involved the failure to control licensed material
in such a manner as to limit the occupational dose to an individual's
extremities to less than 18.75 rems per calendar quarter as required by
10 CFR 20.101(a).
l
Licensee Comment: 1
10 CFR Part 20 does not prescribe a method of calculating non-uniform doses
resulting from a " hot particle" on the skin of an extremity, and NRC IEN 86-23
is not a regulatory requirement which can be made the basis for a Notice of
Violation.
NRC Response:
As stated previously in the Enclosure to our letter dated July 13, 1987, NRC
regulations are based on recommendations such as those in ICRP 26, Radiation
Protection Guidances to Federal Agencies (developed by EPA), NBS handbooks,
current research by recognized experts, and comments received during the public
comment period for proposed rule changes. The current 10 CFR Part 20 is based,
in substantial part, on the recommendations of NBS Handbook 59. Where there is
a need to clarify the intent of NRC regulations, the preferred approach is to 1
obtain clarification from the base document, in this case NBS 59. Thus in this
case, where specific implementation details on how to do assessments are not
included in 10 CFR Part 20, the source documents were used to define the methods
used.
With regard to IEN 86-23, it should be noted that the main purpose of this ~
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Notice was to inform licensees of occurrences of skin contamination by small
particles of radioactivity. Licensees were expected to review the information
in the Notice for applicability to their specific program. In addition, the
Notice reminded licensees of the long-standing NRC policy regarding assessments
of dose to the skin. The Notice did not create a regulatory requirement; it
did provide information on events and remind licensees of techniques for skin
dose calculation.
The NRC recognizes that significant advances have been achieveo in the field of
Health Physics as noted in your response. The proposed 10 CFR Part 20 has been
out for comment, and comments received are being reviewed. The general points
made by SCE&G and those provided by other sources regarding the advancements in
health physics will be considered during the review. Nonetheless, the current
regulations remain valid and in effect.
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Licensee Comment:
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Calculational methods consistent.with current good practice in the field of
' health physics, such as the method employed by SCE&G, should be accepted'in the
absence of a method prescribed, or incorporated by reference, in the
regulations.
The thirty year old method on which NRC guidance and regulatory interpretation
is based (NBS Handbook No. 59) results in significant over estimation of
biolcgical effects of such an exoosure which is inconsistent with the l
philosophy of current recommendations, such as International Commission on
Radiological Protection (ICRP) Publication 26 and the principles of ALARA.
Based on recommendations of the ICRP and previous guidance provided by the NRC,
SCE&G contends that guidance given in IEN 86-23 is inappropriate for
determining dose equivalent due to hot particle contamination. Furthermore,
ICRP-26 states in Paragraph 183, "... if the dose . distribution is extremely
non-uniform, as that from very small particles in contact with the skin, the
local absorbed dose (rads due to beta and gamma components) should be assessed
and used to predict possible local skin reactions." SCE&G implemented this
recommendation to determine the potential for non-stochastic effects (cosmetic
changes) and retained professional medical assistance to assure there were no
local skin reactions. The ICRP goes on to say that "It is inappropriate,
however, to relate such localized absorbed doses to the absorbed doses
corresponding to the dose-equivalent limit." Regulatory interpretation as
reflected in IEN 86-23 contradicts previous staff guidance, Regulatory
Guide 8.23, while ignoring both current state-of-the-art and ICRP recommenda-
tions.
NRC Response:
NRC recognizes the need for a reevaluation of the basis for dose assignment due
to very small, highly radioactive particles. Recently the NRC formally
requested the National Council on Radiation Protection and Measurements (NCRP)
to review and provide guidance on this issue. As appropriate, when this
guidance is received, the NRC will re-evaluate the current basis of
10 CFR 20.101(a). However, until, and unless, the basis of 10 CFR 20.101(a) is
changed, the guidance in NBS Handbook 59 and IE Notice 86-23 is to be used in
determining compliance with the current regulations. IEN 86-23, rather than l
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being contrary to the regulations, as you indicated, represents the NRC
position on how licensees should calculate the dose to the skin from
radioactive contamination. This guidance is considered most appropriate at
this time. It is not at all clear, as suggested by SCE&G, that the basis of
10 CFR 20.101(a) should be changed. Recent scientific publications (see
Attachment) have indicated that the ICRP-26 guidance is inadequate,
particularly for non-uniform exposures, and have suggested the continued use,
as an interim measure, of the current practice of determining skin dose at the
basal layer of the epidermis (7 mg/cm2) averaged over an area of one square
centimeter.
Licensee Comment:
Regulatory Guide 8.23 (in a footnote to Table 2) states that for the hands,
averaging over the whole area of the hands is acceptable, nominally 300 cm2,
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NRC Response:
i The NRC had noted the need for a change in this portion of Regulatory
Guide 8.23 since it implied a method of calculation different from that upon
which the regulations were based. Action has been initiated to revise this
Regulatory Guide to make it clearly consistent with NRC policy.
Licensee Comment:
! ICRP-26 does not, as pointed out by your response, support the omission of the
beta component; however, paragraph 17 states that the absorbed dose is
insufficient by itself to predict either the severity (non-stochastic) or the
probability (stochastic) of the deleterious effects on health resulting from
irradiation under unspecified conditions. The dose equivalent unit, rem, was
developed to correlate delayed stochastic effects with radiation exposure.
SCE&G has therefore assigned a dose equivalent which more appropriately
correlates the probability of future stochastic effects due to the skin
irradiation by this highly localized contamination. That dose equivalent which
reflects current understanding of the 1.tochastic risks associated with skin
dose, has been recorded as 0.43 rem and does not exceed the limits of
10 CFR 20.101(a).
NRC Response:
As stated in our letter of March 10, 1987, it is the NRC's position that the
methodology SCE&G used was inappropriate. The beta component cannot be
ignored, nor is it appropriate to average the dose over 100 cm2 Furthermore,
ICRP-26 does not suggest that the dose from the accidental contamination of
individuals from small particles should be averaged over any area larger than
one square centimeter. As stated above, the NRC does have under evaluation
consideration of changes in skin dose assessment methodology that might result
in a different factor for converison from a rad to a rem for doses to very small
areas of the skin. Until a decision is made on whether such a change is appro-
priate,10 CFR Part 20 specifies that for beta doses, one rad equals one rem.
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ATTACHMENT
NUREG/CR-4418, " Dose Calculation for Contamination of the Skin ,
Using the Computer Code VARSKIN," PNL 5610, August 1987.
Reece, W. D., et al., " Extremity Monitoring: Considerations for
Use, Dosimeter Placement and Evaluation," NUREG/CR-4297,
December 1985.
Charles, M. W. and J. Wells, "The Development of Criteria for
Limiting the Non-Stochastic Effects of Non-Uniform Skin Exposure,"
Proceedings of the 5th Congress of the International Radiation !
Protection Society, Jerusalem, March 1980.
' Rohlof, F. and M. Heinzelmann, " Calculation of Dose Rates for Skin
Contamination by Beta Radiation," Radiation Protection
~
Dosimetry 14 (4), 279-287 (1986).
Strather, J. W., " Radiation Damage to Skin," Report of a Workshop
on Radiation Damage to Skin, Fundamental and Practical Aspects,
Saclay, France, 9-11 October, 1985, NRPB Bulletin, No. 70,
(March 1986).
Francis, T. M. , " Dosimetry of Beta Particles and Low-Energy
X-Rays" Report of a Workshop held at the Nuclear Research Centre
(CEA),Sacla
(March 1986)y, France, 7-9 October, 1985, NRPB Bulletin, No. 70,
.
Charles, M. W. , " Skin, Eye, and Testis: Current Exposure Problems
and Recent Advances in Radiobiology," J. Soc. Radiol. Prot. 6, (2),
69-81 (1986).
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