Similar Documents at Surry |
|---|
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] |
Text
, I VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND~ VIRGINIA 23261 R.li.LEASBUHO VICE PRESIDENT May 18, 1982 NucLEAll OPERATIONS Mr. Harold R. Denton Serial No. 282 Office of Nuclear Reactor Regulation PS E&C/JEW Attention: Mr. Stephen A. Varga, Chief Operating Reactors Branch No. 1 Docket Nos. 50-280 Division of Licensing 50-281 U. S. Nuclear Regulatory Commission License Nos. DPR-32 Washington, D. C. 20555 DPR-37
Dear Mr. Denton:
REQUEST FOR ADDITIONAL INFORMATION ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRIAL EQUIPMENT SURRY POWER STATION UNITS 1 AND 2 In a letter dated January 7, 1982, the NRC requested that Vepco supply copies of the documentation referenced in the I.E. Bulletin 79-0lB 90 Day Review to the Franklin Research Center. Part of the documentation requested includes Qualification Documentation Review (QDR) packages. These documents are intended to provide a complete record of the Vepco/NUS Corpo-ration review of the equipment listed on the equipment qualification 11 master list 11
- These packages will contain all the necessary documentation to support the qualification of the equipment for which a particular QDR was issued. It is our opinion that the review of qualification of items listed on the master list should be based on information contained in the QDRs rather than on isolated test reports or correspondence. Additionally, some references contained in the I.E. Bulletin 79-0lB 90 Day Review were not re-quired for qualification of equipment or for other reasons were not used to support the findings of the qualification review.
Attachment 1 provides a listing of the references requested and the status of these references with regard to this submittal. Also supplied is a computer listing of the equipment qualification master list (Attachment 2).
This list can be used as an index to the QDR files. The following information will be useful when using the master list:
- 1) REP: This symbol in the purchase order column indicates that the equipment has been identified as requiring re-placement as a result of our review.
, .. ;.: .820525,0174 820518
.: *. * : f:' Dll :.*ADQ<:K J).5000280 __
- :* ***. G ,....... *' -*':' :'.-.;,.'"--:-:'.." >:.'_.:/.*.poR*. ,:.* *_: *,.
l VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton 2
- 2) *DEL: This symbol in the file column indicates that the equipment has been deleted from the master list.
- 3) *T: This symbol in the file column indicates the item is aTMI item.
- 4) *NH: This symbol in the file column indicates the equip-ment is located in a mild (non-harsh) environment.
- 5) The numbers in the file column are the middle set of numbers in the QDR number (i.e., QDR number 5437-124-01 is the same as file number 124).
The material submitted in answer to your request of January 7, 1982, is being forwarded under separate cover to the Franklin Research Center from NUS Corporation in Gaithersburg, Maryland. NUS Corporation has been requested to copy you on their transmittal letter.
We are available at your earliest convenience should additional information be required.
Very truly yours,
~)~-~
Attachments JEW:mcc cc: Mr. R. C. DeYoung, Director NRC Office of lnspection and Enforcement Division of Reactor Operations Inspection Washington, D. C. 20555 (8 copies w/attachments)
Mr. Zoltan R. Rosztoczy, Branch Chief NRC Equipment Qualification Branch Division of Engineering Washington, D. C. 20555 (1 copy w/attachments)
l
-- ' e e VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton 3 cc: Mr. James P. 0 Reilly, Regional Administrator 1
Region I I 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 (1 copy w/attachments)
Mr. Cyril J. Crane Franklin Research Center The Parkway at Twentieth Street Philadelphia, PA 19103 (1 copy w/attachments)
l
- ATTACHMENT 1 SURRY POWER STATIONS UNITS 1 AND 2 I
A. General references Units 1 and 2 Reference Number Status/Comments a(2) This reference is not included in the submittal.
This le.*tter concerns North Anna Power Station Unit
- 2. At Surry Power Station; the RTD s will be 1
replaced.
b(3) This letter is not included in the submittal. This letter concerns North Anna Power Station At Surry Power Station the existing RTD s will be replaced.
1 c(5) This reference is included in QDR 5437-52-01 for Unit 1; and 5437-120-01 for Unit 2.
d(6) This reference is not included in the submittal.
This reference was not used by NUS in their review of the qualification for items on the master list.
A comprehensive report was obtained and used to complete the QDR's.
- This reference will be deleted.
e(7) This reference is not included in the submittal.
This report was prepared for North Anna Power Station.
At Surry, all Barton transmitters will be replaced.
therefore, this reference has not been used. TMI items have not all been evaluated yet, but will probably be replaced. This reference will be deleted.
f(9) This reference is not included in the submittal.
This reference was not used in any QDR because all Barton transmitters will be replaced. This reference will be deleted.
g(12) This reference is not included in the submittal.
This is not a complete report (includes only radia-tion versus bending elongation and tensile strength).
Other Cerro Wire Company reports were used which are complete and are liste*d in references 27, 27A, !
37, 92 and 94.
A.
- General references Units 1 and 2 (continued)
Reference e Page 2 Number Status/Corrunents h{13) This reference is not included in the submittal.
This report is not complete. Other Cerro Company reports which are complete were used to prepare the QDR. These reports are listed in references 27, 27A, 37, 92 and 94.
i ( 18) This reference is included in QDR's 5437-59-01 for Unit li ~nd 5437-127-01 for Unit 2.
k(23) This reference is included in QDR 5437-34-01 for Unit l; and 5437-96-01 for Unit 2.
1(24) This reference is included in QDR 5437-34-01 for Unit 1; and 5437-96-01 for Unit 2.
m(37) This reference is included in QDR 5437-51-01 for Unit 1; and 5437-119-01 for Unit 2.
n(38) This report is included in QDR 5437-60-01 for Unit 1; and 5437-130-01 for Unit 2.
0(40) This reference is included in QDR 5437-57-01 for Unit 1; and '5437-123-01 for Unit 2.
p( 42) This reference is included in QDR 5437-61-01 for Unit 1; and 5437-128-01 for Unit 2.
q(44) This reference is included in QDR 5437-34-01 for Unit 1; and 5437-96-01 for Unit 2.
r(45) This reference is not included in the submittal:
This is original correspondence concerning Limitorque Motor Operated Valves. NUS has removed all questions on Motor Operated Valves by implementing a field verification program and upgrading the actuactors with qualified replacement parts. This correspondence is no longer utilized.
s(47) This reference is not included in the submittal.
A certificate of conformance is not required for the QDR. The QDR package contains the required documentation.
A.
General references Units 1 and 2 (continued)
- Page 3 Reference Number Status/Comments t(51) This reference is not included in the submittal.
This is original correspondence concerning Limitorque Motor Operated Valves. NUS has re-solved all questions on Motor Operated Valves by implementing a field verification program to procure information defined in these letters from equipment nameplate.
u(52) This reference is not included in the submittal.
This is original correspondence concerning Limitorque Motor Qperated Valves. NUS has re-solved all questions on Motor Operated Valves by implementing a field verification program to procure information defined in these letters from equipment nameplate.
v(53) This reference is included in QDR 5437-54-01 for Unit l; and 5437-122-01 for Unit 2.
w(54) ' This reference is not included in the submittal.
This reference was not used by NUS in their review of the qualification for items on the master list.
Therefore, the reference wi 11 be de 1eted.
x(55) This reference is not included in the submittal.
This reference was not used by NUS in their review.
of the qualification for items on the master list.
Therefore, the reference will be deleted.
y(56) This reference is not included in the submittal.
This reference was not used by NUS in their review of the qualification for items on the master list.
Therefore, the reference will be deleted.
z(58) This reference is not included in the submittal.
This reference was not used by NUS in their review of the qualification for items on the master list.
Therefore, the reference will be deleted.
A.
General reference Units 1 and 2 (continued) e Page 4 Reference Number Status/Comments aa(60) This reference is not included in the submittal.
This reference was not used by NUS is .their review of the qualification for items on the master list.
Therefore, the reference will be deleted.
bb(61) This reference is included in QDR 5437-60-01 for Unit li ind 5437-130-01 for Unit 2.
cc(64) This reference is included in QDR s 5437-48-01 and 1
5437-58-01 for Unit 1; and 5437-133-01 and 5437-126-01 for Unit 2.
dd{68) This reference is included in QDR s 5437-48-01 and 1
5437-58-01 for Unit 1; and 5437-133-01 and 5437-126-01 for Unit 2.
ee(69) This reference is included in QDR s 5437-16-01 and 1
5437-41-01 for Unit 1; and 5437-77-01 and 5437-136-01 for Unit 2.
ffl 72) This reference is not included in the submittal.
This reference was not used by NUS in their review of the qualification for items on the master list.
Therefore, the reference will be deleted.
gg(73) This reference is not included in the submittal.
This reference was not used by NUS in their review of the qualification for items on the master list.
Therefore, the reference will be deleted.
ii (77) This reference is not included in the submittal.
This reference was not used by NUS in their reivew of the qualification for items on the master list.
Therefore, the reference will be deleted.
jj(79) This reference is not included in the submittal.
This reference was not used by NUS in their reivew of the qualification for items on the master lsit.
Therefore, the reference will be deleted.
A.
General reference Units 1 and 2 (continued) e Page 5 Reference Number Status/Comments kk{80) This reference is included in QDR 5437-61-01 for Unit 1; and 5437-128-01 for Unit 2.
11(82) This reference is included in QDR 5437-52-01 for Unit 1; and 5437-120-01 for Unit 2.
mm(83) This reference is not included in the submittal.
This is original correspondence concerning Limitorque Motor Operated Valves. NUS has re-solved all questions on Motor Operated Valves by implementing a field verification program to procure information defined in these letters from equipment nameplate.
nn{84) This reference is not included in the submittal.
This is original correspondence concerning Limitorque Motor Operated Valves. NUS has re-solved all questions on Motor Operated Valves by implementing a field verification program to procure information defined in these letters from equipment nameplate.
00(85) This reference is included in QDR 5437-59-01 for Unit 1; and 5437-127-01 for Unit 2.
pp(86) This reference is included in QDR 5437-59-01 for Unit 1, and 5437-127-01 for Unit 2.
qq {87) This reference is included in QDR 5437-59-01 for Unit 1; and 5437-127-01 for Unit 2.
rr(88) This reference is included in QDR 5437-59-01 for Unit 1; and 5437-127-01 for Unit 2.
ss(89) This reference is included in QDR 5437-59-01 for Unit 1; and 5437-127-01 for Unit 2.
tt{90) This reference is included in QDR 5437-42-01 for Unit l; and 5437-104-01 for Unit 2.
uu(91) This reference is included in QDR 5437-18-01 for Unit 1; and 5437-79-01 for Unit 2.
Page 6
-- ** A. General references uni 1 and 2 Reference Number Status/Comments vv(93) This reference is included in QDR's 5437-50-01 and 5437-55-01 for Unit 1; and 5437-118-01 and
. 5437-134-01 for Unit 2.
w(94) This reference is included in QDR s 5437-50-01 and 1
5437-55-01 for Unit 1; and 5437-118-0f and 5437-134-01 for Unit 2.
B. Specific References - Unit 1 xx(95) This reference is included in the submittal.
yy(97) This QDR package number has been changed from 5437-SOV-Ol to 5437-01-01. This reference is included in the submittal.
zz(99} This reference is included in the submittal.
aaa(lOl) This reference is included in the subm.ittal.
bbb(103) This reference is included in the submittal.
ccc( 105) This reference is included in the submittal.
ddd(l07) This reference is included in the submittal.
eee( 109) This reference is included in the submittal.
fff(lll) This reference is included in the submittal.
999(113) This reference is included in the submittal.
hhh(115) This reference is included in the submittal.
iii(l17) This reference is included in the submittal.
jjj(l19) This reference is included in the submittal.
kkk(121) This reference is included in the submittal.
111 (124) This QDR package number has been changed from 5437-MOV-1-01 to 5437-03-01. This reference *is included in the submittal.
nnn(l26) This QDR package number has been changed from 5437-MOV-1-02 to 5437-35-01. This reference is included in the submittal.
000(127) This QDR package number has been changed from 5437-62C-01 to 5437-48-01. This reference is included in the submittal.
.. - I B.
Specific References - Unit 1 (continued) e Page 7 Reference Number Status/Comments PPP(128) This reference is included in QDR 5437-19-01.
qqq{134) This reference is included in the submittal.
rrr(135) This reference is included in the submittal.
sss (136) This QbR package number should be 5437-15-01 in lieu of 5437-103-01. rhis reference is included in the submittal.
ttt(137) This QDR package number has been changed from 5437-62A-01 to 5437-63-01.
uuu{138) This reference is not included in the submittal.
This reference was not used by NUS in their review of qualification for items on the master list. Therefore, the reference will be deleted.
vvv(139) This reference is included in the submittal.
www(140) This reference is included in the submittal.
yyy(141) This reference is included in the submittal.
xxx(142) This. reference is included .in the submittal.
C. Specific References - Unit 2 xx(96) This reference is included in the submittal.
yy(98) This QDR package number has been changed from 5437-SOV-02 to'5437-64-01. This reference is included in the-submittal.
zz( 100) This reference is included in the submittal.
aaa( 102) This reference is included in the submittal.
bbb(104) This reference is included in the submittal.
ccc(106) This reference is included in the submittal ..
ddd{108) This reference is included in the submittal.
e Page 8 C. Specific References - Unit 2 (continued)
Reference
-Number Status/Comments eee(llO) This reference is included in the submittal.
fff(l12) This reference is included in the submittal.
ggg( 114) This QDR package number has been changed from 5437-123-02 to 5437-135-01. This reference is incl ud.ed* in the submittal.
hhh ( 116_) This QDR package number has been changed from 5437-125A-Ol to 5437-126-01. This reference is included in the submittal.
iii (118) This reference is included in the submittal.
jjj (120) This reference is included in the submittal.
kkk(122) ' This reference is included in the submittal.
111 (124) This QDR package number has been changed from 5437-MOV-2-01 to 5437-66-01. This reference is included in the submittal.
nnn(126) This QDR package number has been changed from 5437-MOV-2-02 to 5437-97-01. This reference is included in the submittal.
000(127) This reference is included in the submittal.
ppp(128) This reference is included in QDR 5437-80-01.
qqq(134) ihis reference is included in the submittal.
rrr(135) This reference is included in the submittal.
sss (136) This QDR package number should 5437-103-01 in lieu of 5437-103-15. This reference is included in the submittal.
ttt(137) This reference is included in the submitt~l.
uuu(138) This reference is not included in the submittal.
This reference was not used by NUS in their review of the qualification for items on the master list.
Therefore, the reference will be deleted.
e e Page 9 C. Specific References - Unit 2 (continued)
Reference
-Number Status/Comments vvv(139) This reference is included in the submittal.
wwwt140) This QDR package number has been chan~ed from 5437-103-02 to 5437-136-01. This reference is included in the submittal.
yyy(141) This ~eference is included in the submittal.
xxx(142) This reference is included in the submittal.
