Similar Documents at Surry |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18152B3571999-10-22022 October 1999 Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML20216F1381999-09-0808 September 1999 Forwards Retake Exam Repts 50-280/99-302 & 50-281/99-302 on 990824.One SRO Applicant Who Received re-take Operating Test Passed re-take Exam ML18152B4501999-09-0808 September 1999 Submits in Triplicate,Application for Renewal of License for Rd Scherer,Iaw 10CFR55.57.Requests That Certification of Medical Exam by Facility Licensee,Nrc Form 396,be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML18152B3711999-08-27027 August 1999 Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed ML18152B3851999-08-23023 August 1999 Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis ML18152B3661999-08-20020 August 1999 Provides Medical Status Rept for E Washington,As Required by License Conditions.Summary of E Washington Current Physical Exam & Pertinent Lab Data Attached.Encl Withheld,Per 10CFR2.790(a)(6) ML18152B3651999-08-20020 August 1999 Requests Removal of License Condition from Sh Wightman Operator License SOP-21538.Updated NRC Form 396 Is Encl.Form NRC 396 Withheld,Per 10CFR2.790(a)(6) ML18152B3681999-08-20020 August 1999 Submits 30-day Rept Re Two Instances in Which Conditions of Approval in Coc Were Not Observed in Making Shipment.Two Type B Shipments Using Model CNS 8-120B Package Were Made After Expiration of QA Program Approval Between 990531-0628 ML18152B3801999-08-18018 August 1999 Forwards Technical Rept NE-1206,Rev 0, Surry Unit 2,Cycle 16 Startup Physics Tests Rept, Summarizing Results of Physics Testing Program Performed After Initial Criticality on 990525 ML18152B3781999-08-13013 August 1999 Forwards ISI Summary Rept for Surry Power Station,Unit 2 for 1999 Refueling Outage.Rept Provides Summary of Examination Performed During Outage for Third ISI Interval.No New Commitments Were Made ML18152B3751999-08-13013 August 1999 Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML18152B4211999-05-25025 May 1999 Forwards Rev 1 to Relief Request P-11 to Clarify Original Intent of Request by Specifically Requesting Relief from Requirements of Section 6.1 of OM-6 ML18152A4741999-05-19019 May 1999 Forwards Completed Registration Form for Renewal of ASTs at Surry Nuclear Power Station,Iaw Section 9VAC 25-91-100.F ML18152B4171999-05-17017 May 1999 Provides Notification of Number of Steam Generator Tubes That Were Plugged During Spring 1999 Refueling Outage Planned ISI ML20217D6621999-05-14014 May 1999 Forwards NRC Operator Licensing Exams 50-280/99-301 & 50-281/99-301 (Including Completed & Graded Exams) for Tests Administered on 990329-0401 & 990412-15.Nine Candidates Passed (& One Failed) Exam ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML18152B4121999-05-0303 May 1999 Forwards Application for Renewal of License for SV Ross. Encl Withheld Per 10CFR2.790(a)(6) ML18152B4101999-04-29029 April 1999 Forwards Scope & Objectives for 990803 Surry Power Station Emergency Exercise.Without Encls ML18152B6561999-04-23023 April 1999 Forwards Annual Radioactive Effluent Release Rept for Surry Power Station,Jan-Dec 1998, Which Includes Summary of Quantities of Radioactive Liquid & Gaseous Effluents & Solid Waste Released During CY98 ML18152B6491999-04-13013 April 1999 Forwards MOR for Mar 1999 for Surry Power Station,Units 1 & 2.MOR for Feb 1999 Incorrectly Stated Gross Electrical Energy Generated (Mwh) for Unit 2.Rept Should Have Stated Monthly Figure as 568965.0 ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML18153A2721999-03-29029 March 1999 Forwards LER 99-002-00 Per 10CFR50.73.Listed Commitments Contained in Ltr 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18152B3571999-10-22022 October 1999 Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML18152B4501999-09-0808 September 1999 Submits in Triplicate,Application for Renewal of License for Rd Scherer,Iaw 10CFR55.57.Requests That Certification of Medical Exam by Facility Licensee,Nrc Form 396,be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML18152B3711999-08-27027 August 1999 Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed ML18152B3851999-08-23023 August 1999 Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis ML18152B3651999-08-20020 August 1999 Requests Removal of License Condition from Sh Wightman Operator License SOP-21538.Updated NRC Form 396 Is Encl.Form NRC 396 Withheld,Per 10CFR2.790(a)(6) ML18152B3681999-08-20020 August 1999 Submits 30-day Rept Re Two Instances in Which Conditions of Approval in Coc Were Not Observed in Making Shipment.Two Type B Shipments Using Model CNS 8-120B Package Were Made After Expiration of QA Program Approval Between 990531-0628 ML18152B3661999-08-20020 August 1999 Provides Medical Status Rept for E Washington,As Required by License Conditions.Summary of E Washington Current Physical Exam & Pertinent Lab Data Attached.Encl Withheld,Per 10CFR2.790(a)(6) ML18152B3801999-08-18018 August 1999 Forwards Technical Rept NE-1206,Rev 0, Surry Unit 2,Cycle 16 Startup Physics Tests Rept, Summarizing Results of Physics Testing Program Performed After Initial Criticality on 990525 ML18152B3781999-08-13013 August 1999 Forwards ISI Summary Rept for Surry Power Station,Unit 2 for 1999 Refueling Outage.Rept Provides Summary of Examination Performed During Outage for Third ISI Interval.No New Commitments Were Made ML18152B3751999-08-13013 August 1999 Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML18152B4211999-05-25025 May 1999 Forwards Rev 1 to Relief Request P-11 to Clarify Original Intent of Request by Specifically Requesting Relief from Requirements of Section 6.1 of OM-6 ML18152B4171999-05-17017 May 1999 Provides Notification of Number of Steam Generator Tubes That Were Plugged During Spring 1999 Refueling Outage Planned ISI ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML18152B4121999-05-0303 May 1999 Forwards Application for Renewal of License for SV Ross. Encl Withheld Per 10CFR2.790(a)(6) ML18152B4101999-04-29029 April 1999 Forwards Scope & Objectives for 990803 Surry Power Station Emergency Exercise.Without Encls ML18152B6561999-04-23023 April 1999 Forwards Annual Radioactive Effluent Release Rept for Surry Power Station,Jan-Dec 1998, Which Includes Summary of Quantities of Radioactive Liquid & Gaseous Effluents & Solid Waste Released During CY98 ML18152B6491999-04-13013 April 1999 Forwards MOR for Mar 1999 for Surry Power Station,Units 1 & 2.MOR for Feb 1999 Incorrectly Stated Gross Electrical Energy Generated (Mwh) for Unit 2.Rept Should Have Stated Monthly Figure as 568965.0 ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML18153A2721999-03-29029 March 1999 Forwards LER 99-002-00 Per 10CFR50.73.Listed Commitments Contained in Ltr ML18153A3421999-03-26026 March 1999 Provides Updated Medical Status Rept for Wb Gross in Accordance with License SOP-20476-02,Docket 55-5228,as Amended by 980320 License Amend.Informs That Gross Exhibits No Performance Problems & Will Continue on Current Medicine ML20204H0331999-03-17017 March 1999 Forwards Rev 5 to PSP for Surry & North Anna Power Stations & Associated Isfsis.Description & Justification for Changes Included with Plan Rev.Rev 5 to PSP Withheld Per 10CFR73.21 ML18153A3411999-03-15015 March 1999 Forwards Signed Applications & Medical Certificates for Initial License at Surry Power Station Units 1 & 2 for Listed Individuals.Without Encls 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML18153C3661990-09-20020 September 1990 Forwards Topical Rept VEP-NE-3-A, Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code. ML18153C3701990-09-18018 September 1990 Forwards Addl Info Re Facility Containment Isolation Valve Type C Test,Per 900914 10CFR50,App J Exemption Request ML18152A2341990-09-14014 September 1990 Requests Exemption from 10CFR50,App J Section III.D.3 Re Local Leak Rate Testing During Every Reactor Shutdown. Basis & Justification for Exemption Encl ML20059J3341990-09-13013 September 1990 Forwards Rev 15 to Nuclear Security Personnel Training & Qualification Plan.Rev Withheld ML18151A2901990-08-31031 August 1990 Forwards Rev 10 to Updated FSAR for Surry Power Station Units 1 & 2,representing Second Updated FSAR Submitted This Yr ML18153C3451990-08-29029 August 1990 Forwards Proprietary Semiannual Fitness for Duty Program Performance Data Rept for 900103-0630.Rept Includes Summaries of Mgt Sanctions Imposed,Actions Taken to Correct Program Weaknesses & Events Reported to Nrc.Encl Withheld ML18153C3381990-08-22022 August 1990 Responds to NRC 900723 Ltr Re Violations Noted in Insp Rept 50-280/90-21 & 50-281/90-21.Corrective actions:as-found-as- Left Conditions of Auxiliary Feedwater Evaluated & Found Operable ML18153C3391990-08-22022 August 1990 Requests Approval for Use of Plugs Fabricated of nickel- chromium-iron Uns N-06690 Matl (Alloy 690) to Plug Tubes in Steam Generators for Mechanical & Welded Applications ML18153C3161990-08-0101 August 1990 Provides Supplemental Response to NRC 900629 Ltr Re Electrical Crossties,Load Shedding on Nonblackout Unit & Emergency Diesel Generator Reliability.Emergency Diesel Generator Reliability Program in Place,Per Reg Guide 1.155 ML18153C3171990-08-0101 August 1990 Resubmits Synopsis of Changes to Updated Operational QA Program Topical Rept Vep 1-5A ML18153C3091990-07-30030 July 1990 Provides Outline of Plan to Meet 10CFR50 App G Requirements, for Low Upper Shelf Energy Matls,Per NRC 900521 Request ML18153C3061990-07-30030 July 1990 Forwards Revised Tech Spec Pages,Addressing Constitution of Quorum & Timeliness of Mgt Safety Review Committe Meeting Minutes,Per NRC Request ML18153C3051990-07-26026 July 1990 Advises That Util Submitted Decommissioning Funding Plan & Financial Assurance Info W/Isfsi License Application ML18153C3041990-07-26026 July 1990 Responds to NRC 900626 Ltr Re Violations Noted in Insp Rept 50-281/90-20.Corrective Actions:Leaking Drain Plug & Upper Drain Plug on Motor Replaced W/Oil Drain Assemblies Composed of Piping & Valves ML18153C3031990-07-26026 July 1990 Advises of Withdrawal of Request for NRC Review & Approval of Engineering Evaluation 8.Revised Evaluation Will Be Maintained Onsite for NRC Audit During Future Insps,Per Generic Ltr 86-10 ML18153C3101990-07-26026 July 1990 Forwards Decommissioning Financial Assurance Certification Rept..., Nuclear Decommissioning Trust Agreement & Nonqualified Nuclear Decommissioning Trust Amended & Restated Trust Agreement, Per 10CFR50.75 ML18153C2901990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Listed Transmitters Compiled.Transmitters Found Installed within Reactor Protection or ESFAS Have Been Replaced ML18153C2861990-07-12012 July 1990 Requests Cancellation of Operator Licenses for Listed Individuals.Licenses No Longer Required ML18153C2871990-07-11011 July 1990 Responds to Violations Noted in Insp Repts 50-280/90-18 & 50-281/90-18.Corrective Actions:Permanent Drain Line Installed & Matrix Which Describes Proper Ventilation Alignment for Plant Conditions Provided for Personnel Use ML18153C2851990-07-0606 July 1990 Forwards Response to Generic Ltr 90-04 Re Status of Generic Safety Issues ML18153C2831990-07-0303 July 1990 Advises That MW Hotchkiss No Longer Needs Operator License SOP-20548-1.Cancellation of License Requested ML18153C2821990-07-0303 July 1990 Requests Exemption from 10CFR50,App J,Paragraph III.A.6(b), Which Requires That When Two Consecutive Periodic Type a Tests Fail to Meet Applicable Acceptance Criteria Type a Test Shall Be Performed at Plant ML18153C3591990-06-28028 June 1990 Responds to SALP Repts 50-280/90-16 & 50-281/90-16 for Period 890701-900331.Corrective Actions Focus on Issues of Maint Backlog,Maint planning,post-maint Testing,Staffing & Procurement ML18153C2611990-06-21021 June 1990 Responds to NRC 900522 Ltr Re Violations Noted in Insp Repts 50-280/90-07 & 50-281/90-07.Corrective actions:as-built Configurations of 120-volt Ac & Dc Vital & Semivital Panel Breaker Installations Verified to Be Acceptable ML18153C2581990-06-18018 June 1990 Forwards Reissued Semiannual Radioactive Effluent Release Rept,Jul-Dec 1989. Rept Contains Info Re SR-89,Sr-90 & Fe-55 Analytical Results for Liquid Composite Samples ML18153C2591990-06-18018 June 1990 Forwards Response to NRC 900524 Request for Addl Info Re NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Engineering Will Initiate Study to Evaluate Enhancements of Cooldown & Possible Heatup Operation ML18153C2541990-06-15015 June 1990 Forwards Corrected Tech Specs Page 3.1-3,per Identification of Typo in 900522 Application for Amends to Licenses DPR-32 & DPR-37 ML18153C2521990-06-14014 June 1990 Responds to NRC 900515 Ltr Re Violations Noted in Insp Repts 50-280/90-09 & 50-281/90-09.Corrective Actions:Abnormal Procedures & Fire Contingency Action Procedures Being Upgraded Via Technical Procedure Upgrade Program ML18153C2501990-06-0808 June 1990 Confirms That Primary Policy Re Onsite Property Damage Insurance,Provided by Nuclear Mutual Limited ML18153C2361990-05-29029 May 1990 Responds to NRC 900427 Ltr Re Violations Noted in Insp Repts 50-280/90-14 & 50-281/90-14.Corrective Actions:Personnel Involved Counseled as to Importance of Properly Recording & Reporting Surveillance Data ML18153C1971990-04-24024 April 1990 Responds to Unresolved Items Noted in Insp Repts 50-338/89-12,50-339/89-12,50-280/88-19 & 50-281/88-19 Re Secondary Sys Containment Leakage & Concludes Leakage Need Not Be Quantified & Not Included in as-found Leakage ML18153C1961990-04-20020 April 1990 Forwards Facility Previous Tests & Projected Leakage Totals for Type C Testing for Valves & Penetrations,Per 900108 Ltr ML18153C1901990-04-18018 April 1990 Requests That Operator License OP-20447-1 for Ja Yourish Be Cancelled ML18153C1861990-04-0505 April 1990 Requests Exemption from 10CFR50,App J,Paragraph III.A.6(b). Util Implemented Corrective Action Program Which Meets Intent of Regulation in Establishing Containment Integrity ML18153C1671990-03-30030 March 1990 Submits Supplemental Response to 10CFR50.63, Loss of All AC Power. Understands That Load Mgt Schemes for Both Blackout & Nonblackout Units Allowed by Station Blackout Rule ML18151A2551990-03-30030 March 1990 Forwards Rev to, Corporate Emergency Response Plan & Rev to, Corporate Plan Implementing Procedures. ML18151A4941990-03-29029 March 1990 Forwards Listed Info Re Licensee Guarantees of Payment of Deferred Premiums,Per 10CFR140.21(e) ML18153C1631990-03-27027 March 1990 Responds to Violations Noted in Insp Repts 50-280/86-05 & 50-281/86-05.Corrective Action:Surveillance Tests Being Performed in Accordance W/Administrative Requirements of Station Procedures & Plans Implementing New Review Process ML18153C1551990-03-20020 March 1990 Clarifies 900108 Request for Exemption from 10CFR50,App J Re Type C Testing Requirements ML18153C1511990-03-19019 March 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47. Operability & Surveillance Requirements for Steam Generator Overfill Protection Sys Will Be Incorporated in Tech Spec Change ML18153C1661990-03-16016 March 1990 Discusses Waiver of Compliance Re Containment Vacuum Sys Operability,Per 900315 & 16 Telcons ML18153C1471990-03-14014 March 1990 Discusses Functional Test for High Setpoint for PORVs ML18153C1571990-03-12012 March 1990 Forwards List of Emergency Operating Procedures in Preparation for 900402-12 Insp.Vol I Is Emergency Operating Procedure Set & Consists of 47 Notebooks.Vol II Contains Fire Contingency Action (App R) Procedures ML18153C1371990-03-0808 March 1990 Forwards Suppl to 1986 Inservice Insp Summary Rept,Adding Two Missing NIS-2 Forms Containing Info Re Replacement of Bolting Matl on 1-RC-SV-1551C (Flange a) & 1-RC-HCV-1556A ML18153C1281990-03-0101 March 1990 Submits 1989 Annual Steam Generator Inservice Insp Rept Results.No Steam Generator Tubes Plugged in 1989 ML18153C1261990-03-0101 March 1990 Responds to Generic Ltr 90-01 Re NRC Regulatory Impact Survey.Survey Covers Type of Insp,Audit or Evaluation by NRC Resident,Nrc Regional Ofc,Nrc Teams & INPO ML18153C1231990-02-22022 February 1990 Responds to NRC 900123 Ltr Re Violations Noted in Insp Repts 50-280/89-32 & 50-281/89-32.Corrective Actions:Use of Lab Hood Attached to F-2 Fan Suction Prohibited & Contaminated & Radioactive Items Removed from Hood ML18152A4881990-02-0606 February 1990 Responds to NRC 891222 Ltr Re Violations Noted in Insp Repts 50-280/89-34 & 50-281/89-34 on 891029-1125.Corrective Actions:Steps in Operating Procedure 2-OP-1.3 Associated W/ Valve Test Being Evaluated for Inclusion in OP-7.1.1 ML18153C0991990-02-0101 February 1990 Withdraws 891018 Application for Amends to Licenses DPR-32 & DPR-37,increasing Pressurizer Safety Valve Setpoint Tolerance to +/- 3% of Nomical Lift Setpoint.Emergency Tech Spec Change Granted on 891116 Provided Modified Tolerances ML18153C0951990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted 1990-09-20
[Table view] |
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VIRGINIA ELECTRIC AND POWER RICHMOND, VIRGINIA 23261 September 1, 1981 I'!!('\
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J. L 0ATTS SENIOR VICE PRESIDENT Mr. James P. O'Reilly, Director Serial No. 466 Office of Inspection and Enforcement NO/RMT:acm U. S. Nuclear Regulatory Commission Docket Nos. 50-280 Region II 50-281 101 Marietta Street, Suite 3100 License Nos. DPR-32 Atlanta, Georgia 30303 DPR-37
Dear Mr. O'Reilly:
I very much appreciate the time extended to us last week to meet with you and other members of your staff in Atlanta to discuss results of recent NRC inspections and other matters pertaining to the quality of operations at Surry and North Anna~ Some of the matters we discussed, especially those related to commitments and our failure in some instances to meet specified dates in a timely manner concern me greatly.
As a follow up to our meeting, I have scheduled meetings at both stations with corporate and station personnel to convey my concern to them and to personally emphasize the importance and need for strict adherance to specified require-ments.
I indicated to you that we are taking other steps to improve our program including issuance of a revised escalation procedure on quality control inspection and audit findings that will provide written notification to my office in a timely manner if appropriate corrective action is not taken in the prescribed period. We are also transferring the quality assurance audit program responsibility to the corporate office to make it more uniform and effective. Additionally, we have begun a review of our written quality assurance program to assess specified requirements. I feel these efforts will result in an improved program and certainly a more effective one.
With regard to the specific concern relative to revising procedures at the time design changes are made operational the NPSQAM will be changed to streng-then the technical review process to require the identification of all pro-cedures including maintenance and surveillance requiring changes.
We at Virginia Electric & Power are, as we have always been, dedicated to pro-ducing electricity safely and let me again assure you that philosophy will be followed by all of our employees
- e VrnornIA ELECTRIC AND PowEH CoMPANY To James P. 0 1 Reilly
- The attached report provides you with a detailed response to I&E Inspection Reports Nos. 50-280/81-15 and 50-281/81-15. After reviewing these reports and the detailed responses, I feel that these actions, and others will deal with the issues that were identified and result in a greatly improved operations program.
We have determined that no proprietary information is contained in the reports. Accordingly, the Virginia Electric and Power Company has no objection to these inspection reports being made a matter of public disclosure. The information contained in the attached pages is true and accurate to the best of my knowledge and belief.
yours, Attachment City of Richmond Commonwealth of Virginia ,,d- 0 -A-
- Acknowledged before me this / day of ~ * , 19 8(
~ C , m_c.~
Notary Public My Commission expires: ;;).._...;;,-t, , 19 8 S
--'------ SEAL cc: Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing
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- VEPCO RESPONSE TO NRC NOTICE OF VIOLATION REPORT NO. 50-280/81-15, 50-281/81-15 VIOLATION A NRC COMMENT:
A. 10 CFR 50, Appendix B, Criterion XVI and the accepted QA Program, Section 17.2.16, require that measures shall be established to assure that conditions adverse to quality, such as failures and nonconformances are promptly identified and corrected, In the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective action taken to preclude repetition. The identification of the significant condition adverse to quality, the cause of the condition, and the corrective action taken shall be documented and reported to appropriate levels of management.
Contrary to the above, measures have not been established to assure that failures and nonconformances (including NRC concerns) are promptly corrected. Although measures have been established to assure that the
- cause of the condition is determined, corrective actions have not been effective to preclude repetition as evidenced by the number of problems identified during the previous inspection in the same functional area (Inspection Report No. 50-280/80-10 and 50-281/80-11). Specifically, Items C, D, G, and I in this Notice of Violation and Items A and Bin the Notice of Deviation, were not identified by the QA Program to assure that corrective actions designed to prevent recurrence were carried out as stated in correspondence to the NRC.
This is a Severity Level V Violation (Supplement I.E.).
RESPONSE
- 1. The violation is correct as stated.
- 2. Reason for the violation:
A loss of administrative control of commitment dates has occurred. A significant increase in items requiring response has been evident since the onset of TMI related lessons learned; moreover, this increase in required follow-up action does not yet appear to be abating. The procedure changes made to cope with the increasing volume of required action as well as increased management attention were not escalated sufficiently fast enough to adequately handle the increase in the amount of follow-up required *
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- 3. Corrective steps which have been taken and the results achieved:
A review of administrative practices has been made, and the need for an improved tracking system for commitments has been identified.
Additionally, the NPSQAM Section 18 has been revised to improve the escalation program. This revision provides a means for timely notification of progressively higher levels of management when corrective actions are not accomplished by a specified implementation date.
The specific corrective steps concerning violations C, D, G, and I are described under the respective headings.
- 4. Corrective steps which will be taken to avoid further violations:
A computerized tracking system for commitments has been developed to assist in the early identif_ication of specified action dates.
Approximately 75% of the station commitments have been entered in the new system, and reports are now being generated for proper follow-up of required actions. In addition, the improved escalation program provides a means to notify the next higher management levels of failure to respond at the specified time.
- 5. Date when full compliance will be achieved:
Full compliance will be achieved by October 1, 1981 *
- VIOLATION B NRC COMMENT :
B. Technical Specification 6.4.A.2 requires that written procedures shall be provided for the calibration and testing of instruments involving nuclear safety of the station. Technical Specification 4.18.A.l requires that fire detection instruments listed in Table 3.21-1 be demonstrated operable:
- 1. At least once per six months by channel function test, and
- 2. At least once per twelve months by performance of channel calibration Heat and smoke detectors are included in Table 3.21-1.
Contrary to the above, procedures issued to implement Technical Specification 4.18.A.l do not address channel function test or channel calibration of heat detectors installed in the cable tray room, the cable tunnel and the cable vault area. In addition, the procedures do not require channel calibration of smoke detectors installed in these areas.
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RESPONSE
- 1. The violation is correct as stated.
- 2. Reasons for the violations:
Existing procedures do not address channel calibration of the heat and smoke detectors since calibration of these detectors is impractical. Standard Technical Specifications do not require calibration of these instruments, and a change to the Surry Technical Specifications is necessary. Present procedures do require channel functional checks, but every channel is not tested at the required frequency.
- 3. Corrective action taken:
A Technical Specification change has been initiated to delete the calibration requirement, and changes to Station procedures have been initiated to insure that all channels are functionally tested at the required intervals. This type of corrective action was outlined in Audit S79-20 which identified the need for a complete review for the Periodic Test program to assure that all Technical Specifications requirements are satisfied.
- 4. Corrective action taken to avoid further violations:
A review of the Technical Specifications is presently underway to
insure that all surveillance requirements are adequately covered by approved procedures. A completion date of August 31, 1981 was established for this review and has been completed.
Date when full compliance will be achieved:
The channel test procedures will be modified by November 1, 1981, which is prior to the next scheduled performance test.
VIOLATION C.
NRC COMMENT:
C. 10 CFR 50, Appendix B, Criterion XVII and the accepted QA Program,Section 17.2.17 require that sufficient records be maintained to furnish evidence of activities affecting quality. Section 17.2.7 of the Program requires that specific records, such as copies of purchase requisitions, become a part of the station records.
Contrary to the above, copies of quality repeating purchasing requisition cards (on which each line is a separate purchase requisition) are not being maintained in station records
- I. . ... . ,. : . : .. ' .
e e This is a Severity Level V Violation (Supplement I.E.). A similar item was brought to your attention in our letter dated July 3, 1980 .
RESPONSE
- 1. The violation is correct as stated.
- 2. Reason for violation:
The procedure changes made to cope with the increasing volume of required action as well as increased management attention were not escalated sufficiently fast enough to adequately handle the increase in the amount of follow-up required.
- 3. Corrective steps which have been taken and the results achieved:
Copies of repeating purchasing requisition cards are presently being maintained in Station Records.
- 4. Corrective steps which will be taken to avoid further violations:
An administrative procedure describing a dual storage program for certain QA records will be established. The records program will be audited periodically.
5* Date when full compliance will be achieved:
- The storage of repeating purchasing requisition cards was completed on July 27, 1981. The dual records storage program will be established on or about November 1, 1981.
VIOLATION D:
NRC COMMENT:
D. 10 CFR 50, Append'ix B, Criterion V and the accepted QA Program, Section 17.2.5 require that activities affecting quality shall be prescribed by documented procedures and shall be accomplished in accordance with these procedures. ADM 51, Control of Procedures, dated January 1977, Section 51.3.2 and 51.3.3 requires that each supervisor who maintains an unused procedure depository shall establish procedures to ensure that;
- 1. Only current and approved procedures are in the unused depository.
- 2. Adequate supplies of unused procedures are on hand.
Contrary to the above, as of May 11, 1981, the procedures required by ADM 51 had not been established by each supervisor that maintains an unused procedure depository. Only the Operations Supervisor and Instrument and Control Supervisor had the required procedures.
This is a Severity Level V Violation (Supplement I.E.)
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e RESPONSE:
2.
The violation is correct as stated. A review of procedure depositories showed that only current and approved procedures in adequate supplies were being maintained in the unused procedure depositories.
Reason for violations:
As noted in Notice* of Violation A, this is an item involving a prior commitment. A loss of administrative control of commitment dates has occurred. A significant increase in items requiring response has been evident since the onset of TM! related lessons learned; moreover, this increase in required follow-up action does not yet appear to be abating.
The procedure changes made to cope with the increasing volume of required action as well as increased management attention were not escalated sufficiently fast enough to adequately handle the increase in the amount of follow-up required.
- 3. Corrective steps which have been taken and the results achieved:
Each supervisor who maintains an unused procedure depository has established the required written procedures.
- 4. Corrective steps which will be taken to avoid further violations:
Not applicable. Procedures are documented.
5* Date when full compliance will be achieved:
Full compliance has been achieved.
VIOLATION E NRC COMMENT :
E. 10 CFR 50, Appendix B, Criterion V and the accepted QA Program, Section 17.2.5 require that activities affecting quality shall be prescribed by documented procedures and shall be accomplished in accordance with these procedures.
- 1. The Nuclear Power Station Quality Assurance Manual, Section 12, Con-trol of Measuring and Test Equipment, Revision 8, dated September 1980, Paragraph 5.4(b) requires that if an instrument is not located for one year after having missed a required calibration date, it shall be removed from the Quality Control (QC) Program.
Contrary to the above, 19 pieces of equipment had missed their cali-bration due date by more than one year but had not been removed from the QC Program.
- 2. The VEPCO Development Policy Manual requires that the individual trained, the supervisor, the Nuclear Training Supervisor and the Station Manager sign the end-of-step examination and the comprehensive examination given to auxiliary operators
- Contrary to the above, the Station Manager did not sign the end-of-step examinations for three. individuals and the immediate supervisor
- did not sign the comprehensive examination for another individual.
e e
-This is a Severity Level V Violation (Supplement I.E.). A similar item was brought to your attention following a recent inspection at North
1.
2.
Anna (Report Nos. 50-338/81-07 and 50-339/81-07
- The violation is correct as stated.
Reason for violation:
Personnel tasked with calibration of equipment or removal of equipment from the Surry Quality Control Program failed to comply with the NPSQAM Section 12 instructions. The task of maintaining the records accurately has been made increasingly difficult over the past two years due to the large number of Health Physics survey instruments which have been lost or otherwise unaccounted for during the Steam Generator Replacement Project.
- 3. Corrective steps which have been taken and the results achieved:
All Quality Control records applicable to the calibration program have been reviewed by qualified personnel, and the supervisors of equipment which is overdue for calibration have been notified and the equipment which has been lost or otherwise is unuseable has been retired.
- 4. Corrective steps which will be taken to avoid further violation:
Personnel involved have been reinstructed in the correct procedures for
maintenance of calibration records
- Date when full compliance will be achieved:
Full compliance has been achieved.
RESPONSE: (E2)
- 1. The violation is denied.
- 2. The tests examined by the inspector were copies of the original examina-tion. The original exam cover sheet is routed to the main office in Richmond for filing in the individual's personnel record. All signature spaces are filled in on the originals, however, due to the routing procedure, the copies which are retained in the vault at Surry Training Center may be missing one or more signatures.
- 3. None required.
VIOLATION F NRC COMMENT:
F. 10 CFR 50, Appendix B, Criterion V and the accepted QA Program, Section 17.2.5 require that activities affecting quality shall be prescribed by procedures. The Nuclear Power Station Quality Assurance Manual (NPSQAM)
- Section 5, Instructions, Procedures and Drawings, Revision 19, dated September 1980, Paragraph 5.1, defines 18 different types of procedures that have been established to assure safe and orderly operation of the station. The accepted QA Program, Table 17.1.0, endorses ANSI Nl8.7-1972.
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e NRC COMMENT (CONTINUED)
- Section 5.4 of this Standard requires periodic review of procedures and states that the frequency of these reviews shall be specified.
Contrary to the above, 14 of 18 types of procedures identified in the NPSQAM are not periodically reviewed and the frequency of reviews is not specified. Examples of procedures not periodically reviewed are Quality Assurance and Periodic Test.
This is a Severity Level V Violation (Supplement I.E.).
RESPONSE
- 1. The violation as stated is correct.
- 2. Reason for violation:
While a Station ADM procedure required the periodic review of certain procedures, it was not fully understood until this IE inspection that all of the 18 procedures identified in the NPSQAM required a periodic review.
- 3. Corrective steps which have been taken and the results achieved:
A change to the NPSQAM is being processed which requires the periodic review of the 18 types of procedures. The check list for the Station Procedures audit has been revised to include an examination of the 18 types of procedures to verify the periodic review requirement.
- 4. Corrective steps which will be taken to avoid further violations:
The specific review requirement will be monitored by the Quality Control Department through the audit process to assure that all of the 18 types of procedures are reviewed periodically.
- 5. Date when full compliance will be achieved:
Full compliance will be achieved by December 31, 1982.
VIOLATION G NRC COMMENT:
G. 10 CFR 50, Appendix B, Criterion XII and the accepted QA Program, Sec-tion 17.2.13 require that measures be established to control the storage and preservation of material to prevent deterioration. Control of items with a limited shelf life constitute a deterioration control measure.
Contrary to the above, a program has not been developed to identify and control the receipt, storage and issuance of safety-related materials which have a limited shelf life.
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RESPONSE
- 1. The violation as stated is correct.
- 2. Reason for violation:
As noted in Notice of Violation A, this is an item involving a prior commitment. Establishment of the shelf life program was halted at the time of change in warehouse supervisors, and it was never reinstated.
The procedure changes made to cope with the increasing volume of required action as well as increased management attention were not escalated sufficiently fast enough to adequately handle the increase in the amount of follow-up required.
- 3. Corrective steps which have been taken and the results achieved:
Efforts to establish a shelf life program have been reinstituted.
- 4. Corrective steps which will be taken to avoid further violations:
The shelf life program will be formalized, and the program will be reviewed during the periodic audits of the warehousing area.
- 5. Date when full compliance will be achieved:
Full compliance will be achieved by June 30, 1982 *
NRC COMMENT:
H. 10 CFR 50, Appendix B, Criterion XVIII and the accepted QA Program, Section 17.2.18 require that follow-up action, including reaudit of deficient areas, shall be taken where indicated. Additionally, the accepted QA Program, Table 17.2.0 endorses ANSI N45.2.12 (Draft 3, Revision 4 - 1974). Section 4.5.2 of this standard requires that followup action by the auditing organization shall be performed by the audit team leader or management of the auditing organization to confirm that corrective action is acomplished as scheduled.
Contrary to the above, for Audit S-80-13, Finding 1 was closed with-out the auditing organization confirming that corrective action was accomplished as scheduled.
This is a Severity Level V Violation (Supplement I.E.)
RESPONSE
- 1. The violation as stated is correct *
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- 2. Reason for violation:
An audit finding was closed without confirming the corrective action because the auditor believed that the Station Manager's explicit directive to his supervisors was sufficient.
Corrective steps which have been taken and the results achieved:
The auditor has been reinstructed in the accepted methods to close open audit findings. This action is believed to be sufficiently effective that this practice will not be repeated.
- 4. Corrective steps which will be taken to avoid further violations:
No further corrective action is considered necessary.
- 5. Date when full compliance will be achieved:
Full compliance has been achieved.
VIOLATION I NRC COMMENT:
I. 10 CFR 50, Appendix B, Criterion XVIII and the accepted QA Program, Section 17.2.18 require a system of audits shall be carried out to verify compliance with all aspects of the quality assurance program.
- The accepted QA Program also states that provisions are established requiring that audits be performed in those areas where the require-ments of Appendix B to 10 CFR 50 are being implemented.
Contrary to the above, audits are not being conducted at the company offices in two areas, records and document control. Since a major portion of activities in each of these areas are being conducted and audited at the Surry site, a lower Severity Level has been assign~d.
This is a Severity Level VI Violation (Supplement I.F.)
RESPONSE
- 1. The violation as stated is correct.
- 2. Reason for violation:
As noted in Notice of Violation A, this is an item involving a prior commitment. The specific requirement to audit QA records in dual storage at the company offices had not been identified prior to the IE Inspection. Consequently, audits of this separate record storage program had not been performed *
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- VIOLATION I RESPONSE (CONTINUED)
- 3. Corrective steps which have been taken and the results achieved:
The requirement for a dual records storage program is acknowledged, and the procedure will be documented.
- 4. Corrective steps which will be taken to avoid further violations:
The dual storage of QA records will be audited on a periodic basis.
- 5. Date when full compliance will be achieved:
Full compliance will be achieved by November 1, 1981 *
.1 e
- VEPCO RESPONSE TO NOTICE OF DEVIATION INSPECTION REPORT 50-280/81-15, 50-281/81-15 DEVIATION A NRC COMMENT:
A. In response to Item I in the Notice of Violation transmitted by Region II letter dated July 3, 1980, VEPCO correspondence dated August 1, 1980, stated that VEPCO would prepare and issue for use, procedures which de-scribe the interface, responsibilities, lines of communications and flow of design information between VEPCO and their Architect Engineer by October 1, 1980.
Contrary to the above, procedures which describe the interface, respon-sibilities, lines of communications between VEPCO and their architect engineer were not prepared and issued for use until February 1, 1981.
RESPONSE
- 1. Description of corrective actions:
A review of administrative practices has been made, and the need for an improved tracking system for commitments has been identified. Addition-ally, the NPSQAM Section 18 has been revised to improve the escalation program. This revision provides a means for timely notification of progressively higher levels of management when corrective actions are not accomplished by a specified implementation date.
- 2. Corrective actions taken to avoid further deviation:
A computerized tracking system for commitments has been developed to assist in the early identification of specified action dates. Approxi-mately 75% of the station commitments have been entered in the new system and reports are now being generated for proper follow-up of required actions. In addition, the improved escalation program provides a means to notify the next higher management levels of failure to respond.
- 3. Date when corrective actions will be completed:
Full compliance will be achieved by October 1, 1981 *
.t e
B. In response to Item Bin the Notice of Violation transmitted by Region II letter dated July 3, 1980, VEPCO correspondence dated August 1, 1980, listed the following corrective step to avoid further violations: A change to the Nuclear Power Station Quality Assurance Manual (NPSQAM) has been intiated to require distribution of audit responses and other pertinent documentation to the recipients of the audit report; and that the date when full compliance will be achieved for this item is January 1, 1981.
Contrary to the above, the NPSQAM change was not approved until March 5, 1981.
RESPONSE
- 1. Description of corrective actions:
A review of administrative practices has been made, and the need for an improved tracking system for commitments has been identified.
Additionally, the NPSQAM Section 18 has been revised to improve the escalation program. This revision provides a means for timely notifi-cation of progressively higher levels of management when corrective actions are not accomplished by a specified implementation date *
- 2. Corrective actions taken to avoid further deviation:
A computerized tracking system for commitments has been developed to assist in the early identification of specified action dates. Approx-imately 75% of the station commitments have been entered in the new system and reports are now being generated for proper follow-up of required actions. In addition, the improved escalation program provides a means to notify the next higher*management levels of failure to respond.
- 3. Date when corrective actions will be completed:
Full compliance will be achieved by October 1, 1981 *
,w ,. r e e DEVIATION C NRC COMMENT:
C. In the licensee response dated December 10, 1980, to NUREG-0737, VEPCO committed the Shift Technical Advisors (STA's) to successfully complete college level training in a variety of areas.
Contrary to the above, one of the STA's assigned to the Surry Station did not attend any of the fundamentals courses. A letter dated August 13, 1980 from the professor who taught the courses for VEPCO stated that none of the STA's took the test on fluid mechanics and heat transfer.
The professor's letter also stated that attendance was down for many courses because plant need for the individuals in the program.
RESPONSE
- 1. Description of corrective actions:
During the summer of 1980 a professor from Old Dominion University con-ducted an engineering refresher course. The course was a mandatory re-quirement for two of the four designated Shift Technical Advisors (STA's). In addition, the course was made available for the entire engineering department, including summer student employees. Two of the four STA's were granted a waiver from attending the course due to their advanced SRO training in progress at that time. Unfortunately, this was not documented. The waivers will be documented an4 will be retained as permanent records.
- 2. Corrective actions taken to avoid further deviations:
Any exceptions taken to the STA Training Program, as stated in our response to NUREG-0737, will be fully documented. Training personnel will ensure that all appropriate records, including tests and attendance records, are retained as permanent records.
- 3. Date when corrective actions will be completed:
All corrective actions will be completed by 9/3/81 *