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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 ML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr 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 ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML20212J9101999-10-0101 October 1999 Forwards SE Accepting Licensee 990916 & 27 Relief Requests IWE-3 for Plant.Se Addresses Only IWE-3 Due to Util Urgent Need for Relief.Requests IWE-7 & IWE-8 Will Be Addressed at Later Date 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 ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) 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 ML20216E6661999-09-10010 September 1999 Forwards Analysis of Capsule W Virginia Power North Anna Unit 1 Nuclear Power Plant Reactor Vessel Matl Surveillance Program, for Capsule Withdrawn on 980922 ML20211N2531999-09-0808 September 1999 Responds to Request to Exceed 60,000 Mwd/Mtu Lead Rod Burnup in Small Number of Fuel Rods in North Anna Unit 2.Informs That NRC Offers No Objection to Requested Use of Rods in Reconstituted Fuel Assembly.Se Supporting Request Encl 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 ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211J2211999-08-31031 August 1999 Approves Request to Remove Augmented ISI (Aii) Program for RCS Bypass Lines from North Anna Licensing Basis.Se Re Request to Apply LBB to Eliminate Augmented Insp Program on RCS Bypass Lines Encl ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint 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 ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal 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) 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) 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 ML20211B3871999-08-17017 August 1999 Requests Permission to Routinely Discharge from SW Reservior to Waste Heat Treatment Facility Under Existing Vpdes Permit Through Outfalls 108 & 103.Discharges Are Scheduled to Commence on 990907,due to High Priority Placed on Project ML20210T0671999-08-13013 August 1999 Informs of Completion of Review of Proposed Revs of Schedule for Withdrawal of Rv Surveillance Capsules Submitted by VEPCO on 981217.Approves Proposed Revs.Forwards Safety Evaluation 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 ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 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) ML20210N2921999-08-0505 August 1999 Discusses Which Submitted Proposed TSs Bases Change for Containment Leakage. Licensee Changes to Bases May Be Subj to Future Insps or Audits ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate 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 ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal 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) ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required 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) 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) ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines 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 ML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr 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 ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein 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 ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls 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 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. 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 ML20216E6661999-09-10010 September 1999 Forwards Analysis of Capsule W Virginia Power North Anna Unit 1 Nuclear Power Plant Reactor Vessel Matl Surveillance Program, for Capsule Withdrawn on 980922 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 ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint 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 ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal 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) 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) 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 ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 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) ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate 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 ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal 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 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) 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) 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) ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines 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 ML20212J2951999-06-22022 June 1999 Forwards Corrected Markup & Typed Version of Affected Pages. Requests That Attached Pages for Those Previously Provided in 990506 Submittal Be Replaced & Incorporated Into NRC Review of Proposed TS ML20196F1151999-06-22022 June 1999 Forwards Relief Requests NDE-047 & NDE-048 for North Anna Power Station,Unit 1 Re ASME Section XI ISI Program ML20195J7011999-06-15015 June 1999 Forwards Revised EPIP 2.01 Which Corrects Typo That Was Found in Step 10 of Procedure.Rev Does Not Implement Actions That Decrease Effectiveness of EP 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 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML20065D5671990-09-20020 September 1990 Forwards Rev 15 to Security Personnel Training & Qualification Plan.Rev Withheld ML18153C3661990-09-20020 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 ML20059H7391990-09-10010 September 1990 Forwards Rev 15 to ISFSI Nuclear Security Personnel Training & Qualification Plan.Rev Withheld ML20064A5201990-09-0707 September 1990 Responds to NRC Re Violations Noted in Insp Repts 50-338/90-15 & 50-339/90-15.Corrective Actions:Procedures Revised to Include Tolerance Bands for Temp Control Switch Setpoints & Involved Personnel Counseled ML20059H2931990-09-0707 September 1990 Advises of Review & Approval of ASME Section XI Inservice Insp Program Interval 1 Repair & Replacement Program Change to Applicable Code Edition & Addenda ML20059E5481990-08-31031 August 1990 Forwards Supplemental Info Re Deletion of Pressurizer Safety Valve Requirement During Mode 5.Current Tech Spec Requiring One Operable Safety Valve in Mode 5 Unnecessary & May Be Deleted 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 ML20063Q1241990-08-15015 August 1990 Provides Supplemental Info for 900115 Tech Spec Change Request Re Max Allowable Control Rod Drop Time.Retained DNBR Margin Tracked & Documented by Calculational Note ML20058N5941990-08-0808 August 1990 Responds to NRC Re Violations Noted in Insp Repts 50-338/90-11 & 50-339/90-11.Corrective Actions:Procedure Revised to Limit Applicablity to Small Refueling Cavity Leaks & Listed Evaluations & Revs Will Be Made to EOP ML18153C3171990-08-0101 August 1990 Resubmits Synopsis of Changes to Updated Operational QA Program Topical Rept Vep 1-5A 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 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 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 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 ML18153C3051990-07-26026 July 1990 Advises That Util Submitted Decommissioning Funding Plan & Financial Assurance Info W/Isfsi License Application 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 ML20055H5651990-07-20020 July 1990 Requests for Temporary Waiver of Compliance from Requirement of Tech Spec 3.3.1.1,Table 2.3-2 Re Response Time Testing. Request Does Not Pose Significant Hazards Consideration 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 ML20055F9361990-07-16016 July 1990 Advises That No 30-day Rept Will Be Made Re Degradation of Seismic Support Bolts of post-accident Hydrogen Recombiners 1-HC-HC-1 & 2-HC-HC-1 ML20044B3501990-07-13013 July 1990 Forwards Monthly Operating Repts for June 1990 & Corrected May 1990 Rept Pages for North Anna Power Station 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 ML20055E8121990-07-0909 July 1990 Requests Cancellation of Licenses Listed ML18153C2851990-07-0606 July 1990 Forwards Response to Generic Ltr 90-04 Re Status of Generic Safety Issues 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 ML18153C2831990-07-0303 July 1990 Advises That MW Hotchkiss No Longer Needs Operator License SOP-20548-1.Cancellation of License Requested ML20055D4831990-07-0303 July 1990 Requests That Operator License for Bl Shriver Be Cancelled. License No Longer Required ML20055D4841990-07-0303 July 1990 Requests That Operator Licenses for Listed Individuals Be Cancelled.Licenses No Longer Required ML20055D7701990-06-29029 June 1990 Submits Supplemental Response to Violations Noted in Insp Repts 50-338/90-04 & 50-339/90-04 Re Failure to Take Timely Corrective Action for Repair of B Low Head Safety Injection Pump (1-SI-P-1B).No Addl Purchasing Procedure Required 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 ML20043H9421990-06-21021 June 1990 Forwards Proprietary WCAP-12351, North Anna Unit 1 Evaluation for Tube Vibration Induced Fatigue, Per Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. Rept Withheld (Ref 10CFR2.790) 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 ML20043H1131990-06-15015 June 1990 Concludes That Removal of Temporary Loose Parts Monitoring Sys Does Not Increase Probability of Acccident,Create Possibility of New Kind of Accident & Does Not Reduce Margin of Safety ML20043G5711990-06-15015 June 1990 Forwards Response to Request for Addl Info Re Insp Rept 50-339/89-20 Concerning Plant Safety Sys Outage Mod Insp. Response Withheld (Ref 10CFR73.21) ML20055C8661990-06-15015 June 1990 Forwards Application for Reissuance of NPDES Permit 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 ML20043G8731990-06-14014 June 1990 Discusses Evaluation of ASME Section XI Testing for Outside Recirculation Spray Pumps ML20043H2091990-06-13013 June 1990 Forwards List of Corrective Actions & Current Status in Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. ML18153C2501990-06-0808 June 1990 Confirms That Primary Policy Re Onsite Property Damage Insurance,Provided by Nuclear Mutual Limited ML20043F4531990-06-0808 June 1990 Forwards, Core Surveillance Rept for North Anna 2,Cycle 7 W/Extended License Burnup Limit. Rept Contains Specific Power Distribution Limits Applicable for Cycle 7 Operation W/Burnup Limit Extension 1990-09-07
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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. S'l'EWABT VICE PRESIDENT NUCLEAR OPERATIONS May 6, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn: Mr. D. G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555 Gentlemen:
GENERIC LETTER 82-33 EMERGENCY OPERATIONS FACILITIES NORTH ANNA AND SURRY POWER STATIONS Seri a 1 No. 259 BSD:ses:0459C Docket Nos. 50-280 50-281 50-338 50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 Based on discussions with the NRC staff, Vepco, in our letter Serial No. 237 dated April 14, 1983, committed to provide a hardened Local EOF at each station, to provide a Central EOF in Richmond, and to revise by May 6, 1983 the Vepco EOF submittal previously provided by our letter Serial No. 102 dated April 8, 1982. Attached is our revised submittal describing our preliminary plan for this con~ept. Should you have questions or need additional information, please contact us. Attachment 8305130058 830506 PDR ADOCK 05000280 F PDR Very truly yours, 0L\~~ W. L. Stewart e -VIRGINIA ELECTRIC AND PoWER COMPANY TO Mr. Harold R. Denton . cc: Mr. Steven A. Varga, Chief . Operating Reactors Branch No. , .Mr. *Robert A.* Clark, Chief . Operating Reactors*
Branch. No .. 3
- Mr. J. P. O'Reilly Regional Administrator
-Region II Mr. D. J. Burke Resident Inspector
-Surry Mr. M. B. Shymlock Resident Inspector
-North Anna NRC positions were delineated in Generic Letter 82-33 Section 8.4. 1. NRC POSITION: (a) The EOF fs a licensee controlled and operated facility.
The EOF provides for management of overall licensee emergency response, coordination of* radiological and environmental assessment, development of recommendations for public protective actions, and coordination of emergency response activities with Federal, State and local agencies.
When the EOF is activated, it will be staffed by pre-designated emergency personnel identified in the emergency plan. A designated senior licensee official will manage licensee activities in the EOF. Facilities shall be provided in the EOF for the acquisition, display and evaluation of radiological and meteorological data and containment conditions necessary to determine protective measures.
These facilities will be used to evaluate the magnitude and effects of actual or potential radioactive releases from the plant and to determine dose projections.
VEPCO RESPONSE: (a) The Emergency Operations Facility <EOF) function is for management of Vepco 1 s overall li~ensee emergency response (including coordination with Federal, State and loc*a1 officials), coordination of radiological and environmental assessments, artd determination of recommended public protective actions. The facilities, the data systems and their attendant links are designed to provide the EOFs with a sophisticated mechanism for adequately respond~ng to and recovering from any plant emergency.
There will be a Local EOF <LEOF) at Surry Power Station, a LEOF at North Anna Power Station, and a Central EOF <CEOF) in Richmond.
The EOF is a common point for information exchange and response coordination of local, State, Federal and Vepco activities.
Representatives from State and Federal agencies are provided space and telephone communication equipment in both the LEOFs and the CEOF. The local counties operate and coordinate through the State EOF representative and have direct contact access with the Recovery Manager. The Recov~ry Manager, the designated senior licensee official, will have a separate functional area within the CEOF and the LEOF from which to coordinate the emergency response.
Travel time between the State Emergency Operations Center and the CEOF is about 15 minutes. ses/06638/1 NRC POSITION:
The EOF wi 11 be: (b) Located and provided with radiation protection features as described in Table 1 (previous guidance approved by the Commission>
and with appropriate radiological monitoring systems. ses/0663B/2 TABLE 1 EMERGENCY OPERATIONS FACILITY Option 1 Two Facilities Close-in Primary: Reduce Habitability o within 10 miles o protection factor= 5 o ventilation isolation with HEPA (no charcoal)
Backup EOF o between 10-20 miles o no separate, dedicated facility o arrangements for portable backup equipment o strongly recommended location be coordinated with off-site authorities o continuity of dose projection and decision making capability ses/06638/3 Option 2 One Facility o At or Beyond 10 miles. o No special protection factor. o If beyond 20 miles, specific approval required by the Commission, and some vision for NRC site team closer to site.
e For both Options: -located outside security boundary space for about 10 NRC employees
-none designated for severe phenomena, e.g., earthquakes Habitability requirements are only for the part of the EOF in which dose assessments communications and decision making take place. If a utility has begun construction of a new building for an EOF that is located within 5 miles, that new facility is acceptable (with less than protection factor of 5 and ventilation isolation and HEPA) provided that a backup EOF similar to 11 8 11 in Option l is provided.
VEPCO RESPONSE: (b) The integrated EOF will consist of a LEOF at Surry Power Station, a LEOF at North Anna Power Station, and a CEOF, at Vepco Headquarters in Richmond.
The CEOF will be the backup EOF. The CEOF will be manned and capable of assuming primary EOF function at all times after the LEOF is manned and may be manned prior to startup of the LEOF. This meets the intent ~xpressed by the NRC in Option l of Table l. *While.the permanent LEOFs ~re under construction, interim LEOFs will be established at both the North Anna and Surry sites. The Surry interim LEOF will be located at the Surry Training Facility.
The North Anna interim LEOF will be located at the North Anna Training Facility.
These buildings are constructed in accordance with good building practices and will therefore, offer some protection from radiation.
In the event the LEOF 1 s should be evacuated, personnel manning the interim LEOF will transfer to the CEOF. The CEOF meets all criteria for structure and habitability.
We anticipate the CEOF will be available for interim use on August 1, 1983. The CEOF will not have full data processing capabilities as described in section g or full communication capabilities as described in section f on August 1, 1983, but will be functional.
The probability of an LEOF evacuation will be reduced when the permanent hardened facilities are completed.
The permanent hardened LEOFs will be constructed adjacent or connected to the existing training facilities.
The present tonceptual design calls for the exposed exterior wal 1 s of the LEOF at North Ann*a to be constructed of 7 1/2 11 solid core masonry unit (CMU) with 3 1/2 11 brick facing. Walls, which are adjacent to the existing training center, will be built of 8 11
- solid CMU and will abut the 12 11 thick existing masonry wall. All exter*ior walls of the LEOF at Surry will be built of 12 11 CMU. The roof of each LEOF will be a 9 11 thick reinforced concrete slab. Based on the preliminary design, we project that the protection factor for the LEOFs to be greater than 8 for the attenuation of 0.7 MEV gamma radiation.
ses/0663B/4 The HVAC system of the hardened LEOF will provide ventilation isolation.
and HEPA filters will be used. The hardened LEOF will operate at positive pressure when airborne radioactive contaminants are detected.
Entry to the hardened LEOF addition will be through one of the three (3) two door vestibules.
At each LEOF, radiation detection equipment capable of continuously monitoring dose rates and airborne radioactivity concentrations will ba provided.
- Due to the position of the CEOF in relation to the plant sites, radiological monitoring will not be required.
NRC POSITION:
The EOF wi 11 be: <c> Sufficient to accommodate and support Federal, State, and local and licensee predesignated personnel, equipment and documentation in the EOF. VEPCO RESPONSE: (c) The interim LEOFs are sized to allow sufficient working space for assigned personnel.
The hardened LEOF design is currently a 2660 square foot structure whi~h has sufficient working space for assigned personnel, equipment, and documentation.
The space available in each facility and the floor plan for each facility will be reviewed by a human factors engineering consultant.
The CEOF has been sized to allow sufficient working space for those assigned positions currently planned with the potential for adding work stations in the future should it become desirable.
NRC POSITION:
The EOF wi 11 be: (d) Structurally built in accordance with the Uniform Building Code. VEPCO RESPONSE: (d) The LEOFs will be well engineered structures designed to the BOCA Code. Use of the BOCA Code is consistent with the design standard used for other structuies on iite. The BOCA Code is the uniform building code used in Virginia.
ses/0663B/5 The CEOF complex will be located on the fifth floor of the Vepco Corporate Headquarters.
This building was constructed in 1978 and meets City and State Building Code requirements.
It is above the "once in a hundred
year flood elevation of the James River. NRC POSITION:
The EOF will be: (e) Environmentally controlled to provide room air temperature, humidity and cleanliness appropriate for personnel and equipment.
VEPCO RESPONSE: (e) The HVAC system in the existing training center, interim LEOF, meets these provisions.
The HVAC system in the hardened LEOF will be designed to provide* ventilation isolation, room air temperature, humidity, and cleanliness appropriate for personnel and equipment.
The LEOF computer will be located in the existing training center simulator computer rooms. The HVAC system for the CEOF meets these provisions.
NRC POSITION: (f) The EOF will be~ Provided with reliable voice and data communications facilities to the TSC and control room, and reliable voice communication facilities to OSC and to NRC, State and local emergency operations centers. VEPCO RESPONSE: (f) The systems for the LEOFs and the CEOF will be designed to provide reliable voice and data communications facilities to the TSC and control room, and reliable voice communication facilities to the OSC and to the NRC, state, and local emergency operations centers. The communications at both the CEOF and LEOF's will generally be the same ~s those currently provided for in Vepco's interim EOFs. The communications links required for personnel manning the EOFs will be human factors engineered.
The conceptual plans for the communications systems are outlined below. These plans are subject to change as the design progresses and as requirements are identified.
ses/0663B/6 e e The CEOF work stations will be equipped with standard telephone
Necessary intercommunications will be provided between functional .areas of the CEOF complex and between functional areas of the CEOF center. Communication equipment to be provided in the CEOF include standard telephone extensions
<each with access to the Bell System Lines, WATS lines, and Vepco tie-lines), Instaphone(s), TSC ringdown, NRC HP network, two state Emergency Telephone Systems, CRT 1 s, and radio communications.
Work stations in each LEOF wil~ be equipped with standard telephone extensions.
Necessar-y intercommunications will_ be provided between functional areas.of the LEOF. Communications equipment to be provided in the EOF include standard telephone extensions
<each with access to the Bell System Lines, WATS lines, and Vepco tie-lines), Instaphone, TSC ringdown(s), NRC HP network, two State Emergency Telephone Systems, CRT 1 s, and radio communications.
At the Surry LEOF, communications will also include ringdown phones to James City County and Surry County offices. At the North Anna LEOF, communications will also include ringdown phones to Louisa and Spotsylvania County offices. NRC POSITION:
The EOF will be: (~) Capable of reliable collection, storage, analysis, display and communication of information on containment conditions, radiological releases and meteorology sufficient to determine site and regional status, determine changes in status, forecast status and take appropriate (g) actions. Variables from the following categories that are essential to EOF functions shall be available in the EOF: (i) variables from the appropriate Table l or 2 of Regulatory Guide l .97 (Rev. 2), and * (ii) the meteorological variables in Regulatory Guide 1.97 (Rev. 2) for site vicinity and regional data available via communication from the National Weather Service. VEPCO RESPONSE:
The data processing system which Vepco plans to install will provide reliable collection, storage, analysis, display, and communication of information needed to perform the EOF function.
The exact data, which will be available in the EOFs, has not been determined but adequate data will be provided since all information available in the Technical Support Center <TSC> can be made available in the EOF. ses/06638/7
-e Vepco has placed purchase orders for the seven (7) MODCOMP Classic II-75 computer systems which will form the Emergency Response Computer System. ) Two (2) computer systems will be Data Communications Processors (DCPs). One DCP will be located in each TSC. These computer systems will gather data from the emergency response remote multiplex system and supplemental data from other computers in the plant. The historical data storage function will be provided on the DCPs. At a minimum, a capability of recording 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of pre-event data and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of post-event data will be available.
Longer term data storage with reduced time resolution will be provided.
These historical data files will be available in the LEOF and CEOF via data links from the DCP. The five (5) remaining computer systems will be Emergency Response Facility Input/Output Processors CERFIO). One Cl) redundant ERFIO system will be located in each TSC, one Cl) ERFIO system in each LEOF, and one Cl) redundant ERFIO system in the CEOF. The accuracy of data in each EOF will be equal to the accuracy of data in the TSC. In each LEOF an ERFIO with a single CPU will receive data from the station DCP computer system in the TSC. The ERFIO processor located in the CEOF will consist of a functionally redundant computer system. Data will be received by the CEOF ERFIO Processor from both DCPs. This data will be transmitted from each DCP via a set of high speed redundarit serial data
- links. All required data will be passed to the EOF ERFIOs which will drive the required color graphic peripherals and printers.
EOF personnel will interact with the ERFIO processor via color graphic display consoles.
The number of consoles, the functions to be performed at each console, and the design of the consoles are being determined.
The design of consoles and displays will be human factor engineered and independently reviewed.
The ERFIO computers for the LEOFs will be installed in the existing simulator computer rooms of the training centers, the interim LEOFs. These computer tooms will not be hardened as this is neither practical nor* required.
The ERFIO computers will include complete color graphics and man machine interface software.
All EOF graphic display consoles can: l. Display a parameter's current or time dependent rate-of-change value. 2. Trend a parameter's current or time dependent rate-of-change value~ (Simulated strip chart recording, X-Y plotting, and bar charts (both horizontal and vertical).>
ses/0663B/8 I
- 3. Assign any parameter to a group of variables for subsequent display. 4. Display the current values of any previously defined group of parameters.
- 5. Display any pre-defined color graphic diagram and its associated parameter data. <Those displays related directly to the console purpose will be available for call-up with a minimum of keystrokes.)
- 6. Replay pre-event and post-event historical data. In addition to the graphic capability, gray scale or color video copiers will be provided to obtain a hard copy of any color* CRT screen desired. Also, 11 receive only 11 <RO) printers will be provided to allow printed logs, trends, etc. to be recorded.
NRC POSITION:
The EOF wi 11 be: * (h) Provided with up-to-date plant records (drawings, schematic diagrams, etc.), procedures, emergency plans and environmental information (such as geophysical data) needed to perform EOF functions
.. VEPCO RESPONSE:. (h) The CEOF and LEOFs will have ready access to up-to-date plant records, procedures, and emergency plans needed to exercise the overall management of the emergency response resources.
NRC POSITION:
The EOF wi 11 be: (i) Staffed using Table 2 (previous guidance approved by the Commission>
as a goal. Reasonable exceptions to goals for the number of additional staff personnel and tesponse times for their arrival. should be justified and will be considered by NRC staff. VEPCO RESPONSE: (i) The EOFs will be staffed to provide the overall management of resources and the continuous evaluation and coordination of activities during and after an accident.
Upon EOF activation, designated personnel will report directly to the LEOF to achieve full functional operation within one and one half (l 1/2) hours. ses/06638/9 e The LEOF will be manned with the designated personnel described in the Corporate Emergency Response Plan with Corporate support personnel continuously manning the CEOF during the emergency.
In the event that the LEOF is evacuated, the personnel in the CEOF would immediately assume the role of the personnel who had evacuated the LEOF. The LEOF and backup CEOF staff will participate in EOF activation drills, which will be conducted periodically in accordance with Vepco 1 s Corporate Emergency Response Plan. The drills wiil include operation of all facilities that will be used to perform EOF functions.
NRC POSITION:
The EOF will be: (j) Provided with industrial security when it is activated to exclude unauthorized personnel and when it is idle to maintain its readiness.
VEPCO RESPONSE: (j) The LEOFs will be located on site but outside the security boundary.
The LEOFs will be constructed adjacent or connected to the existing training centers, which are provided with adequate security protection.
The LEOFs can be provided timely security protection when activated.
The present LEOF conceptual design includes three (3) double door vestibules which can be used to control access. The details of security for these ,fa~ilities will be developed prior to the completion of their construction and will be similar to those for the CEOF. When the CEOF is manned, the corporate office Security staff will .ensure that appropriate access controls are augmented.
Additional off-duty Security personnel will be required to report for duty. All access points into the corporate headquarters will be either locked or under the administrative control of the corporate office Security Staff. Procedures wil*l be implemented to guarantee that increased access controls are maintained.
NRC POSITION:
The EOF will be: (k) Designed taking into account good human factors engineering principles.
ses/06636/10 VEPCO RESPONSE: (k) Vepco has contracted a human factors engineering consultant to review the design of all EOFs. Consultant personnel have interviewed Vepco personnel involved in the emergency response effort, and reviewed emergency plans and related NRC and industry documents to develop a basis for their design review. The consultant will also be involved in determining the number, size, and type of computer peripherals to be available for each work station, the voice communications links and equipment for each work station, and the format and types of color graphic displays which will be available on CRTs. ses/06638/11