|
|---|
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
ML20062B6781990-10-12012 October 1990
Requests Analyses of Liquid Samples Spiked W/Radionuclides Completed within 60 Days of Sample Receipt
ML20059N9491990-10-12012 October 1990
Ack Receipt of 900816 & 0920 Ltrs Which Forwarded Objectives & Scenario Package for 901107 Emergency Exercise
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
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
ML20246P8311989-07-11011 July 1989
Forwards Insp Rept 50-395/89-10 on 890605-08.No Violations or Deviations Noted
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
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
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
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 05000395/1988013
Text
_ _ . .
._
,
'
. . s I
^
,
sl
,
-
j
me
f
JUL 2 21988
Docket No. 50-395
License-No. NPF-12
EA 88-51
South Carolina Electric and Gas Company
ATTN: Mr. D. A. Nauman, Vice President
Nuclear Operations
P. O. Box 88
Jenkinsville, SC 29065
Gentlemen:
SUBJECT: ENFORCEMENT CONFERENCE SUMMARY
(NRC INSPECTION REPORT N0. 50-395/88-13)
This letter refers to the Enforcement Conference held at our request on
June 24, 1988. This conference concerned activities authorized for your
V. C. Summer facility. The issues discussed related to the inoperability of
the service water system and an inadequate post trip review. A list of
attendee:, a sunmary and a copy of your handout are enclosed. We are ;
continuing our rev;aw of these issues to determine the appropriate enforcement i
action.
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 enclosures )
will be placed in the NRC Public Document Room. i
Should you have any questions concerning this letter, please contact us. I
Sincerely,
J. Nelson Grace
Regional Administrator
Enclosures:
1. Enforcement Conference Summary
2. List of Attendees
3. Handout (s)
cc w/encis: (See page 2)
8808030174 880722 ' \
DR
ADOCK 05000395
PDC
.gj o t
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
a
. .
4
'
South Carolina Electric 'E 2 N
and Gas Company 2
s
cc w/encis:
0. S. Bradham, Director, Nuclear
Operations
J. L. Skolds, Deputy Director,
Operations and Maintenance
J. B.~Knotts, Jr.
Bishop, Cock, Purcell & Reynolds
W. A. Williams, Jr. , Technical
Assistant, Nuclear Operations -
Saritee Cooper
A. R. Koon, Jr., Manager
Nuclear Licensing
R. E. Rainear, Executive Vice President,
South Carolina Public Service Authority
bec w/encis:
J. Lieberman, DOE
G. R. Jenkins, EICS
DRS, Technical Assistant
J. J. Hayes, Project Manager, NRR
Document Control Desk
State of South Carolina
NRC Resident Inspector
- RII RII RI
'
RII,k
h
LNodenos:er HDa&nce DVerrelli ehl
07/If/88 07/g/88 07/gq/88
I
7//f/88
RI RII
GJen s rnst
07 88 07FS/88
l
.
. .
. JUL 2 21988
,
.
ENCLOSURE 1
MEETING SUMMARY
On June 24, 1988, rep,resentatives of South Carolina Electric and Gas Company
(SCE&G) attended an Enforcement Conference at the request of the NRC in the NRC
Region II Office in Atlanta, Georgia. The meeting was held to discuss NRC
concerns pertaining to a May 12, 1988 event where entry into Modes 2 and I were
made with both trains of the Reactor Building Cooling Units (RBCU) of the
Service Water (SW) System inoperable. The post trip review failed to detect
that RBCUs were inoperable due to low SW flow.
The NRC Region II Deputy Regional Administrator opened the meeting by reviewing
the NRC concerns pertaining to the switching of operational Modes while both
trains of RBCUs were inoperable and the failure of the post trip review to
identify the discrepancy.
The Vice President of SCE&G gave an opening statement. He then turned the
presentation over to his staff. SCE&G representatives provided a presentation
discussing those topics indicated in the attached handout which was distributed
to meeting attendees by SCE&G. Highlights of this presentation are provided
below:
The licensee provided the sequence of events, the reasons for the restart,
priority given to annunciators, post trip review, and post event actions. A
system description was provided for the service water system technical specifi-
cation affected, performance history and future plans. The licensee described
the reason why they failed to detect the low flow to the RBCUs in that they
reviewed the computer post trip review data, verified that SW pumps and SW
Booster pumps started and the pumps reached the required flow. However, the
review did not go far enough to show that the flow started decreasing below the
minimum level after 120 seconds from the time the pumps started. One of the
future plan actions to be incorporated is a graphical presentation of the post
trip data. This will provide a more visible means to identify any parameter
below the required values. The licensee stated that they took prompt correc-
tive action of declaring both trains inoperable after their independent review
determined SW flow to the RBCUs was below that required. They claimed that
they did not violate the action statemente of the Technical Specifications.
They stated that at the time of Mode changes they were not aware of the low
flows, that they did an adequate post trip review and all systems were func-
tioning properly. Nevertheless, corrective actions have been initiated to
prevent recurrence.
The NRC is presently considering enforcement action on this issue. This
meeting served to enhance tne NRC's understanding of the event and corrective
actions taken to assure proper flow through the RBCUs.
. .
JUL 2 2 Iggg
-
ENCLOSURE 2
LIST OF ATTENDEES
South Carolina Electric & Gas Company:
D. Nauman, Vice President, Nuclear Operations
0. Bradham, Director, fiuclear Plant Operations
J. Skolds, General Manager, Station Operations
G. Soult, Manager, Operations
G. Taylor, Associate Manager, Shift Engineering
J. Burke, Control Room Supervisor
R. Clary, Manager, Design Engineering
A. Koon, Manager, Nuclear Licensing
NRC Representatives:
M. Ernst, Deputy Regional Administrator
C. Hehl, Deputy Director, Division of Reactor Projects (DRP)
E. Merschoff, Deputy Director, Division of Reactor Safety
R. Goodard, Regional Counsel
G. Jenkins, Director, EICS
H. Dance, Chief, Projects Section 18, (DRP)
B. Uryc, Enforcement Specialist, Enforcement and Investigation
Coordination Staff (EICS)
L. Modenos, Project Engineer, Projects Section 18, DRP
R. Bernhard, Reactor Engineer, TPS, DRS
E. Reeves, Senior Project Manager, NRR
J. Hayes, Jr. , Project Manager, NRR
F. Jape, Chief, TPS, DRS
R. Prevatte, Senior Resident Inspector, Summer, DRP
l
1
i
1
- - _ _ -,
_
. ~
JUL
22
t
1999
t
--
EHCLOSURE 3
LICENSEE 14EETlHG 80TES
.
I
I
I
l
l
- - -- - - - - - - - - - - - - -
a
%
ENCLOSURE 3
_
l
NRC ENFORCEMENT CONFERENCE
!
JUNE 24,1988 '
l
. .
ATLANTA, GEORGIA
1
1
i
_-. - .-. .- -.
l
. . ;
l
1
-
S C E & G ATTENDEES
_
ENFORCEMENT CONFERENCE
June 24,1988
.
Dan Nauman - Vice President, Nuclear Operations I
t
Ollie Bradham - Director, Nuclear Plant Operations
Jack Skolds - General Manager, Station Operations
l
Gene Soult - Manager, Operations
1
i
Gary Taylor - Associate Manager, Shift Engineering
)
Johnny Burke - Control Room Supervi.sor .
Ron Clary - Manager, Design Engineering
Al Koon - Manager, Nuclear Licensing I
l
l
. .
'
1
' 1
ENFORCEMENT CONFERENCE AGENDA
_
June 24,1988
.
l. Introduction Dan Nauman
-
Vice President,
Nuclear Operations
11. Sequence of Events
e initiating Event to Restart Gene Soult i
Manager, Operations l
ee Annunciator Gene Soult
Manager, Operations
se Post Trip Review Gary Taylor .
Associate Manager, !
Shift Engineering
i
e Post Event Actions Gene Soult
Manager, Operations l
lil. Service Water System Jack Skolds 1
General Manager,
Station Operations
i
e Description
e Technical Specifications
e Performance History
e Future Plans
IV. Summary / Conclusions Ollie Bradham
I
Director, j
Nuclear Plant Operations
1
1
.-_ . . _ . _ .
_ . _ - - - - _ . -
_
. .
-
l
-
l
-
1
1
l
,
Gene Soult l
Sequence of Events
i nitiating Event to Restart
Annunciator
. .
P
l
l
l
-
.__ ._ _- .
. .
l
.
.
CLOSURE OF "A" MSIV EVENT
l. PART ONE
.
A. PLANT WAS OPERATING AT 100% POWER - ON LINE 191 OF
THE PREVIOUS 192 DAYS.
B. PERFORMING PARTIAL STROKE TESTING OF MAIN STEAM
ISOLATION VALVES WHEN " A" MSIV CLOSED.
C. IMPLEMENTED EMERGENCY OPERATING PROCEDURE FOR
SAFETY INJECTION / REACTOR TRIP. , ,
D. IMPLEMENTED EMERGENCY PLAN PROCEDURES. ,
I
l
1
1
- . . . _ , - .- .- , . . .
-
!
. . j
'
. ,
_
CLOSURE OF " A" MSIV EVENT (CON'T.)
ll. OPERATOR RESPONSE TO ANNUNCIATORS
A. PRIORITY SCHEME
B. TRAINING ON ANNUNCIATORS:
1. NORMAL PLANT CONDITIONS
2. UPSET CONDITIONS
C. EMERGENCY OPERAflNG METHODOLOGY, ,
Ill. POST TRIP REVIEW - GARY TAYLOR
,
t
.
l
l
- - - -
. .
l -
! .
_
Gary Taylor
1
Post Trip Review
. .
'
l
)
.
'
.
POST TRIP REVIEW
9 PRELIMINARY REVIEW BY THE SHIFT ENGINEER
'
.
- INDEPENDENT EVALUATION OF THE RX TRIP & Si
- DETERMINATION OF THE ULTIMATE CAUSE OF THE EVENT
- EVALUATION OF PLANT RESPONSE TO THE TRANSIENT
- VERIFICATION OF SAFETY EQUIPMENT
- COMPARISON TO THE TRANSIENT OF MARCH 17,198S
- DETERMINATION OF RELEASES TO THE ENVIRONMENT
o DOCUMENTS REVIEWED PRIOR TO START-UP
!
- OFF NORMAL OCCURRENCE REPORT * !
- EOP 1.1, POST TRIP REPORT *
- PLANT COMPUTER SEQUENCE OF EVENTS *
- PLANT COMPUTER ALARM MESSAGES *
- PLANT COMPUTER POST TRIP REVIEW *
- TECHNICAL SUPPORT COMPUTER DISCRETE CHANGES LOG *
- TECHNICAL SUPPORT COMPUTER POST TRIP REVIEW
l
[* DOCUMENTS REVIEWED PER SCE&G RESPONSE TO GENERIC LETTE
l. . - _ _. . -
. .
.
.
- 1
e RESOURCES EMPLOYED IN THE RESTART REVIEW
l
1
- ASSOCIATE l\/1ANAGER, SHIFT ENGINEERING l
- OPERATIONS ENGINEER
1
- ADMINISTRATIVE SHIFT ENGINEER
- ASSOCIATE MANGER, OPERATIONS l
1
- MANAGER, OPERATIONS
- DUTY SHIFT SUPERVISOR
'
- DUTY SHIFT ENGINEER l
l
o REVIEW OF SERVICE WATER TO THE RBCU'S
- VERIFICATION OF SW PUMP AND SW BOOSTER PUMP START
- VERIFICATION OF 4000 GPM TO THE RBCU'S
- PLANT COMPUTER ALARMS NOT PRESENT ON B TRAIN
- LACK OF HISTORICAL DATA FOR COMPARISON
1
i
1
'
1
_ _ _ . _ - . _ . _ . . . . - --
v - -- - ---- - -= ~ - - - - ~~~ - ~ ~
_ _ _ _ _ _ - - - - -- ___
7FCHNICAL SUPPORT ConPUTER PD$7 TP!P REV!fW
e MEev UTp 1SW 800 STEP PP re sw TO CPNT FAM COOLER FLOW /TERP1 SU 70 PG FLOU 0 SEPV DTR 70 CCu * SERV kTR PUMP 8
' s: gra . 'trMP 8 TM A TP M * TP A 7R A TR f) TR B4 TR A TR ae HT EXCH FLOW * HOOM Tr.m P *
,
39 e * * 1 * TR A TR P * *
- TE4440 TE4510' FT4466 FT4496* r74468 TE4467 F74498 TE44974 FT4462 FT44*2* FT4460 FT4490* TE9961 TE9962*
(DEGr) (DEGr) (GPM) (CPP) (CPM) (DFGF) (GPp) (DEGT) (GPM) (GPM) (GPM) (CP") ( U f. GF ) (DF6r)
- s sen start DATra 05/12/ B8 * to 5ECOND PRF-TRIP DATA *
18' %1:16 66.1 66.5 0.0 0.0 307.6 89.2 0.0 96.5 1008.6 967.1 8535.5 8976.6 80.8 81.0
' 84:%1:26 66.1 66.5 0.0 0.0 2P4.4 89.2 0.0 96.5 1002.9 964.4 8352.4 8882.2 80.8 81.0
84 :51:36 66.1 66.6 0.0 0.0 161.1 89.2 0.0 96.5 1005.7 962.4 8246.7 8874.1 80.8 80.9
i'*:%3:46 66.1 66.6 0.0 0.0 140.8 89.2 0.0 96.5 996.6 968.9 8457.1 8704.3 80.8 80.9
'48%3:56 66.1 66.6 0.0 0.0 J33.8 89.3 0.0 96.5 994.4 967.5 8315.1 8773.0 80.8 80.9
- '4
- 52:06 66.1 66.6 0.0 0.0 402.2 89.3 0.0 96.5 999.9 967.5 8465.2 9048.7 80.8 80.9
"*s%2:16 66,1 66.6 0.0 0.0 418.9 89.3 0.0 96.5 992.3 964.2 8565.6 ,8569.7 80.8 80.9
'*:52:26 66.1 66.6 0.0 0.0 140.8 89.3 0.0 96.5 908.5 976.2 8482.7 8606.2 80.4 80.9
- e*eeeeeeeeeeeeeeeese posee mEACTOR T IIP *** 05/12/88 04:52831 ***8 *************************
i
,.urM STAPT DATra 05/12/ bu * IO lECOND POST-TRIP DATA *
las%2:3n 66,1 66.6 0.0 0.0 372.6 89.3 0.0 96.5 !
999.6 971.3 8470.4 8790.1 80.8 80.9
- %2:46 66.1 66.6 1420.9 1079.7 1632.8 89.3 1574.7 96.5 965.5 941.1 9855.3 8361.4 80.8 80.9
!*:52:56 66.1 66.6 2094.2 1736.9 1959.4 89.2 1880.3 96.5 956.7 936.3 9650.7 7828.4 80.7 80.9
!* 93:08 66.1 66.6 5000.05 46n7.5 3310.1 89.2 1363.6 96.5 802.1 861.1 10147.25 6136.7 80.7 80.9
'*:93:16 66.1 66.6 4300.4 3989.7 3955.1 89.2 3677.7 96.5 908.8 901.2 7303.0 7449.1 80.7
!43%3:26 66.1 66.6 4422.3 4082.7 4107.8 89:2 4077,a 80.9
94:1_ , 908.8 879.9 7170.1 7559.7 80.7 80.9
66.1 66.6 4408.1 4119.0 4182.9 87,8 4002.3 92.5 906.7 887.4 7442.4 7866.8
les93:46 66.1 66.6 4420.1 4122.1 4120.4 87.2
80.7 00.9
4055.9 90.1 910.3 890.0 7432.2 7630.0 80.7 80.9
!4:53:56 66.1 66.6 4392.9 40*9.3 4099.5 86.7 4064.1 89.4 908.9 886.3
l4 94:06 66.1 66.6 4170.1 4057.0 3874.4 7393.2 7653.4 80.5 80.9
I 87.J 4069.2 89.4 921.6 892.0 7499.6 7807.5 80.5 80.9
4 94:16 66.1 66.6 4006.8 4127.5 3663.7 G6.7 4065.3 89.4 923,6 890.8 7462.2 7635.8
14:54 26 46.1 66.6 3929.0 3958.4 3666.0 80.5 80.9
83.3 3844.6 89.4 91986 083.3 7559.2 7666.6 80.5 80.9
!4 8%4:36 64.1 66.6 3925.9 3184.9 3672.6 80.0 3124.6 86.6 91 Sol 896.0 7584.6 7860.1 80.5 88.9
!*:54:46 66.0 66.6 3919.4 2575.8 3687.1 77.1 2514.4 R3.3
l0 :54:56 66.0 66.6 39J8.7 2288.5 3695.2 918e6 912.4 7573.0 7708.7 80.5 88.8
!0:55 06 74.8 2264.3 80.9 921e4 927.9 7523.4 7965.7 80.4 80.8
66.0 46.6 3902.9 2146.7 3675.7 73.3 2073.7 77.9 922 8
I:55:16
O 66.0 66.6 3939.2 2091.0 3654.9 932.6 7442.4 - 8204.0 80.4 88.8
0:55:26 72.0 2026.8 76.3 918.92 928.4 7551.8 8499.0 80.4
66.0 66.6 3950.1 2647.8 3676.1 71.4 1975.7 75.1 80.8
,0:55:36 66.0 66.6 3920.8 1971.1 3666.2 919.0 931.8 7568.0 8184.0 80.4 80.8
'0:55:46 70.8 1968.4 73.7 923.4 936.9 1482.4 8266.9 88.4
66.1 66.6 3937.7 1933.6 3701.0 70,2 2905.7 73.2 80.8
0:45 56 66.1 66.6 3923.1 1961.8 3640.9
916,9 934.8 7652.2 8124.7 80.4 80.8
0:56:06 69.8 1935.5 72.6 925.5 931.6 7515.1 8363.3
66.1 66.6 3902.9 1961.8 3705.1 69.8 1914.5 72.6 88.4 80.8
Pa%6: 16 66.1 86.6 3922.7 1977.6 3637.1 922.8 935.5 7455.4 4145.9 80.4 80.8
p 96:24 69.8 1958.1 72.0 924.4 933.9 7412.7 8344.5 80.4
66.1 66.6 3942.3 1916.1 3636.9 69.0 1937.1 ,73.0 80.8
P56:33 66.1 66.6 3912.6 1955.5 3725.6 918.4 932.5 7521.7 8491.6 80.4 80.8
69.8 1926.0 72.0 919.2 930.6 7513.8 8285.1
0:56:46 66.1 66.5 39:3.4 1942.2 3670.9 69.4 1969.9 51.5 80.4 80.8
355:53 66.1 66.5 3901.3 1986.4 3640.3 924.5 934.1 7561.3 8332.0 80.4 80.7
397:06 66.1 69.2 1908.5 71.5 928.4 937.5' 7510.0 8495.3
66.5 3897.8 1910.1 3618.2 69.2 1877.9 '71.5 80.3 80.7
357:16 66.1 66.5 3902.3 1908.1 3645.3 920.4 933,9 741n,7 80g7.2 80.3 80.7
D:57:26 66.1 66.5 3901.3 18*2.1 3644.5
69.2 1884.0 71.5 919.2 932.3 7570.9
69.2 1909.3 8271.1 80.3 80.7
71.5 922.9 935.6 7525.5 8218.9 80.3 80.7
' Ora stAPT DATra 05/12/88 * 1 M NUTE PnST= TRIP DATA *
_. .
. .
'
.
_
- INDEPENDENT EVALUATION OF THE RX TRIP & SI
.
- STRUCTURED POST TRIP REVIEW
a. GRAPHICAL PRESENTATION OF POST TRIP DATA
b. PLANT RESPONSE CHECKLIST
c. REVIEW GUIDE WHICH WILL INCLUDE NORMAL
OPERATING BANDS , INSTRUMENT SETPOINTS,
CONTROL AND PROTECTION FUNCTIONS AND
TECHNICAL SPECIFICATIONS
- PLANT & TSC COMPUTER REPLACEMENT IN PROGRESS
O
POST EVENT ACTIONS - GENE SOULT
l
,
.- , - - - - - - - - - - - - . . - . . - , - - --n, ,
,
.
.
EXAMPLE OF THE NEW GRAPHICAL FORMAT .~
s.000 u ,,,,,,,i,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,, ,,,,,,,,,
-
.. .
,
_
.
..
_ . .
~ .A '. ~
,
- It *.
3 .* _ . - . . . . . . . . ,
_- 3 g .,
-
3% -
'
% "e ' ' 4000 GPM LIMIT
~
4,000
-
'
-
_
3 3................. ......... ,,,,...... ,,,,,,,,,,,,,,,,,, ,
'
.
$ s
l
f
t
-
3
3 \
1
b'FT4466 - SERVICE WATER TO '
-
-
_
3 1 '
O 3
\
-
-
3 _
3,000 -
3 1 _
W -
i
-
J
~
\
-
3 y -
3 -
'
_~ 3 k ~
3 \
FT4496 - SERVICE WATER TO RBCU TI<AI.Si 8
G -
-
-
3
3 \s
%
[ _
as %
P 2,000 - l N
,g %__ , -
_- .g
.
- ~ - -
_.
M
_
-
- I ~
-
-
_g
. FLOW FROM SW PUMP 8 - 1740 GPM -
-
'f.;LJ -
5
- ji SW BOOSTER PUMPS ~
i ; START
- f
_
- i.000
7 .I
-
.I
'
- SW PUMPS
-
START -g
,
TSC POST TRIP REVIEW
)
, -
'
MAY 12,1988
-
3
~
_
l [
l
0 ' ' " " "
'#""'"'"""'"""'"'"'"""'"""""'""""""""""""""'"""""""""'"" '"'"'"'"'"""""
-40 -20 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 s
TIMF (SF('ONDS)
_ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ __ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ - - _ _ _ _ _ _ ___
. __ . _- .
-
-
!
1
l
Gene Soult i
i
=
l
l
1
Post Event Actions l
l
I
- .
l
,
-, . . , _ . _ . , , , .-.. - - . . , . . _ , , _ , , . . . . , , , _ _ ,
1
. .
.
\
'
l
POST EVENT ACTIONS
I
PART 11
!
l.
OPERATIONS MANAGEMENT NOTIFIED OF POSSIBLE LOW SW i
FLOW TO RBCU..
i
A. DECLARED BOTH TRAINS INOPERABLE BASED ON POST TRIP
DATA.
B. INITIATED TESTING OF SW TO RBCU'S.
C.
DECLARED " A" TRAIN SW TO RBC f5 OPERABLE. ,
l
D. CHECKED FUNCTIONAL SYSTEM COMPONENTS.
E.
INITIATED CHEMICAL FLUSH "6" TRAIN RBCU'S.
F.
DECLARED "B" TRAIN SW TO RBCU'S OPERABLE.
G. CHEMICAL FLUSH OF " A" TRAIN.
_ _ _ - - _ . . . _ -
-._ _ _ . _ _ - . _ . --
_ . _ -_ ._ _ ..__
I
. .
.
.
POST-EVENT ACTIONS (CON'T) !
l
11.
INCREASE FREQUENCY FROM 18 MONTH SURVEILLANCE OF FLOW
TO MONTHLY FLOW VERIFICATIONS.
'
i
A. TESTED " A" SWBP SAT ON 6/21/88.
Ill. OBSERVED REDUCED FLOW OF SW TO "B" TRAIN RBCU'S
A. INSPECTED SW PUMP BAYS FOR CLAM INFESTATION.
B.
PERFORMED a P CHECKS OF VARIOUS "B" TRAIN HEAT
EXCHANGERS. ,
,
,
IV.
SIMULATED BLACKOUT TESTING FOR WORST CASE TRANSIENT ON
SYSTEM
V. SERVICE WATER SYSTEM - JACK SKOLDS
- -._ __ -.
._ _ . -
._. - . _ . . - _ _ _ _ - - -
. . _
- -- - - - - - - - - -
l
. .
%
.
-
Jack Skolds
,
Service Water System
l
l
l
- .
l
l
,
- - - -- . ,-- - - - , , . - - , , , -
. _ _ _ ..
. .
.
-
l
SERVICE WATER / REACTOR BUILDING :
i COOLING UNITS
l
,
e ' System Description
e Technical Specifications
e Problems Encountered
e Future Plans
.
l
l
l
)
. _ . . - - - _ _ . . _ . . , _ . . - _ , . - -
. . . _ _ . . _ . _ _ . . _ . _ . _ _ . _ _ . . _ _ _ . _ . . _ . . _ _ - _ . _ _ . _ _ _ _ _ . . . . __
.
.
-
. - -
.
.N.
ji, . +
8 I'
',
i
'
-o,e %
-
.*w i 3 %i w
i i v.s s
% *
.
.
"
., : *
- I ' E.
., _{a. [h i
-
. i e :: .~
h {.
I.s
y 1. d,"1 I'
s.
.
i
!! !$
. .
\ '
v I v g'Il 5s
! l
,
.
I k *
. ..
. < "I
1 I.
~
4I -
"
l l lI .,- ,
'
h .[..,
J,s
i i !
_ A a.ght
.h
J,s *
.b '
/
c
3l
i
l=
i
.G4,'s:.,s L _.: _ . - . ,: '
. : . .
.
- - .. ..g. 3 .f . ,. t
i
k
wi .
l
e- ,
li al l t
4 '31 1
~@ I :
' fi a
. .
3: 4 1 i;$ .0 ;,,.' pl
'
~,l
I
4 1 * !
'
9 1,1 @-
'
.-"
s i
dg
-
~
g : ii. ,
'5
., i
f Og,si p
'J;
,
s. .V .@ -S! ! !!
3
I N,,r - .;.
.
2 .p
3
N #
' ;\>i4% - \>q Y '
l.
'
5: : .
- f
. .. , , . 1 -
j .J I, .,, g .
i 2 45 ggg-g g g a ;w @y (1
A , ,,
.
g, ,
n
.@O' @ g d
>rm .
r4. 4 x .@ =
.Il
!}
..!l g ! a
- 1 -- ap *R .., m. + C a
1
,4
. .
- ..
413' ii, . - ' i 1.*
"
2
l T ini
s
4
g
, . .. . .
11
gg
v
..
/ ' 's !a 1- .H ' .5 b
I Y8 -_8' . '. J"i ll j'i .v- j.
2
i
.
(_
'
l . , s i s s
8 .,- ,J.id II..
v-. -- j
.
1*;) } =.
. T. .. . , T. . w v. .,
.,e, ,
. ) * ! ,-
]!
-
} :
i! '
- : ax
II II
wy f . j 2f :!.! 5,
il
. .
3 -
'17 ,
f ..q T^ :I
j
.
" _ , -,; i I
- u
@-
~# r.i s
{$ lil
i +44
al M1
.
!! . . . . . . . !! i,
"
I I 'l .I I l ' I i jlg,g
.
" -
l = ;v x -v , .
.: * -
'.co-.g'l
ri>
- %
e+ik
.t i l 3, . L
.
@1. .
s:/. g . 9....,2
b -
i
-
I .;
s
,i
.
't <<
.
W r. i .
! I
>....s...._
gr : i ,@,).
I
.
g,,T. ...,... ... 3. I . . , ,i
I I. l!i' !l -:
b Mh
,
kI f ^-~ ~ h
- '
, hl!Ih
S. 8! !! $
.
I l!l e-- si
O- k *.
- .
}* -
8: . tri;i. :.
t 8 ..i
[
b s........
5..... .r 55w. Th ~ ......
-
. ..
-
. . . . . . .
.......,y
1;.1 3!
.
o i
_ _ _ _ _ _ - _ _ _ _ _ _ _ _ __ _ _ _ - _ _ - - _ _ _ . _ - _ - - - _ - - - -
._
. .
\
I
D
.
PLANT SYSTEMS _
)
3f,4_.7.4 SERV!CE WATER SYSTEM
L_IMITING CONDITION FOR OPERATION
__
3.7.4 At least.two independent service water loops shall be OPERABLE. I
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
!
With only one service water loop OPERABLE, restore at least two loops to
OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
I
SURVEILLANCE REQUIREMENTS
4.7.4 At least two service water loops shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (ma'nual,
power operated or automat 1c) servicing safety related equipment that
is not locked, sealed, or otherwise secured in position, is in its
correct position.
SUMMER - UHli 1 3/4 7-12 Amendment No. 21
- -
._.
.
1
. .
'
,
.
CONTAINMENT SYSTEMS
REACTOR BUILDING COOLING SYSTEM
LIMITING CONDITIONS FOR OPERATION
3.6.2.3 Two independent groups of reactor building cooling units shall be
OPERABLE with at least one of twc cooling units OPERABLE in slow speed in each
group. .
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
a. With one group of the above required reactor building cooling units
inoperable and both reactor building spray systems OPERABLE, restore l
the inoperable group of cooling units to OPERABLE status within l
7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in
COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l
b. With two groups of the above required reactor building cuoling units
inoperable, and both reactor building spray systems OPERABLE, restore
at least one group of cooling units to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> I
or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLO l
SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Restore both above required
groups of cooling units to OPERABLE status within 7 days of Initial
loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in
COLD SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c. With one group of the above required reactor building cooling units
inoperable and one reactor building spray system inoperable, restore
the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be
in at least HOT STANDBY within the next 6 hcurs and in COLD SHUT 00WN
within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Restore the inoperable group of
containment cooling units to OPERABLE status within 7 days of initial
loss or be in at least HOT STAN0BY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in
COLO SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVE*LLANCE REQUIREMENTS
4.6.2.3 Each group of reactor building cooling units shall be demonstrated
OPERABLE:
a. At least once per 31 days by:
1. Starting each cooling unit group from the control room, and
verifying that each cooling unit group operates for at least
15 minutes in the slow speed mode.
b. At least once per 18 months by:
1. Verifying that each f an group starts automatically on a safety
injection test signal.
2. Verifying a cooling water flow rate of greater than or equal to g
4,000 gpm to each cooling unit group. N
SUMMER - UNIT 1 3/4 6-14
-- -- - -
-. ._ .-
1
. .
l
'
. 1
-
SERVICE WATER SYSTEM HISTORY l
3/87 Identified High Ap on B Train RBCU.
-
1
Inspected RBCU 28 Cooler (Worst Ap) with
Fiberscope. Clean and very few clams. (2 of 22
tubes)
Inspected CCW HX. Very few clams.
1
4/87 Reviewed design data of coolers and pumps.
l
Reviewed Section XI test data. l
1
Ran Flow Balance Test. Met flow rate for 95 F.
Ap's were very close to design requirements.
l
S/87 Ran integrated safeguards test. Satisfactory.
Provided guidance to Operations.
, ,- - . , , - - - - __, - , - - , , _ , . - . , - . , ---., n , , - , e a , -r,- .
~
.
. .
'
,
.
~
FUTURE PLANS
- Modification to RBCU Valves, to increase flow
marg'in
- 2000 gpm requirement
- Technical Specification change approved
- Possible Strainer / Bypass Loop
- More Sophisticated Testing
.
-
"C" SW Pump
- More instrumentation
- Visualinspection Refuel 4
- Possible Flush / Filter (Later)
e Determine Cause of Flow Degradation
- Presently do not believe cause to be clams
t _ _ .
. . . _ _ - - - - - - - _ . - . - . . . - - - - . _ - . - . _ . . - . _ . .
- - - - -
.
. .
%
>
_
Ollie Bradham
.
Summary / Conclusions
1
i
. .
!
1
l
,
- - - - - - - - --,--_--,--,..------,--.,.,--n ,-- - ,- , - - ,,-, - , , - - - - - ~- - --,- - - - - - - - - - - - - , - - , - -- -- - -
0 *
)
_
NRC ENFORCEMENT CONFERENCE
'
JUNE 24,1988
<
SUMMARY
WE DID NOT VIOLATE SPECIFICATION
3.0.4. .
MANAGEMENT FOCUS ON SAFETY
VERSUS ECONOMICS
CHECKS AND BALANCES WORKED
DEDICATED TO RESOLVING PROBLEM
,
_
,___,_ _ ,
