Similar Documents at Surry |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18152B3571999-10-22022 October 1999 Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML20216F1381999-09-0808 September 1999 Forwards Retake Exam Repts 50-280/99-302 & 50-281/99-302 on 990824.One SRO Applicant Who Received re-take Operating Test Passed re-take Exam ML18152B4501999-09-0808 September 1999 Submits in Triplicate,Application for Renewal of License for Rd Scherer,Iaw 10CFR55.57.Requests That Certification of Medical Exam by Facility Licensee,Nrc Form 396,be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML18152B3711999-08-27027 August 1999 Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed ML18152B3851999-08-23023 August 1999 Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis ML18152B3661999-08-20020 August 1999 Provides Medical Status Rept for E Washington,As Required by License Conditions.Summary of E Washington Current Physical Exam & Pertinent Lab Data Attached.Encl Withheld,Per 10CFR2.790(a)(6) ML18152B3651999-08-20020 August 1999 Requests Removal of License Condition from Sh Wightman Operator License SOP-21538.Updated NRC Form 396 Is Encl.Form NRC 396 Withheld,Per 10CFR2.790(a)(6) ML18152B3681999-08-20020 August 1999 Submits 30-day Rept Re Two Instances in Which Conditions of Approval in Coc Were Not Observed in Making Shipment.Two Type B Shipments Using Model CNS 8-120B Package Were Made After Expiration of QA Program Approval Between 990531-0628 ML18152B3801999-08-18018 August 1999 Forwards Technical Rept NE-1206,Rev 0, Surry Unit 2,Cycle 16 Startup Physics Tests Rept, Summarizing Results of Physics Testing Program Performed After Initial Criticality on 990525 ML18152B3781999-08-13013 August 1999 Forwards ISI Summary Rept for Surry Power Station,Unit 2 for 1999 Refueling Outage.Rept Provides Summary of Examination Performed During Outage for Third ISI Interval.No New Commitments Were Made ML18152B3751999-08-13013 August 1999 Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML18152B4211999-05-25025 May 1999 Forwards Rev 1 to Relief Request P-11 to Clarify Original Intent of Request by Specifically Requesting Relief from Requirements of Section 6.1 of OM-6 ML18152A4741999-05-19019 May 1999 Forwards Completed Registration Form for Renewal of ASTs at Surry Nuclear Power Station,Iaw Section 9VAC 25-91-100.F ML18152B4171999-05-17017 May 1999 Provides Notification of Number of Steam Generator Tubes That Were Plugged During Spring 1999 Refueling Outage Planned ISI ML20217D6621999-05-14014 May 1999 Forwards NRC Operator Licensing Exams 50-280/99-301 & 50-281/99-301 (Including Completed & Graded Exams) for Tests Administered on 990329-0401 & 990412-15.Nine Candidates Passed (& One Failed) Exam ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML18152B4121999-05-0303 May 1999 Forwards Application for Renewal of License for SV Ross. Encl Withheld Per 10CFR2.790(a)(6) ML18152B4101999-04-29029 April 1999 Forwards Scope & Objectives for 990803 Surry Power Station Emergency Exercise.Without Encls ML18152B6561999-04-23023 April 1999 Forwards Annual Radioactive Effluent Release Rept for Surry Power Station,Jan-Dec 1998, Which Includes Summary of Quantities of Radioactive Liquid & Gaseous Effluents & Solid Waste Released During CY98 ML18152B6491999-04-13013 April 1999 Forwards MOR for Mar 1999 for Surry Power Station,Units 1 & 2.MOR for Feb 1999 Incorrectly Stated Gross Electrical Energy Generated (Mwh) for Unit 2.Rept Should Have Stated Monthly Figure as 568965.0 ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML18153A2721999-03-29029 March 1999 Forwards LER 99-002-00 Per 10CFR50.73.Listed Commitments Contained in Ltr 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18152B3571999-10-22022 October 1999 Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML18152B4501999-09-0808 September 1999 Submits in Triplicate,Application for Renewal of License for Rd Scherer,Iaw 10CFR55.57.Requests That Certification of Medical Exam by Facility Licensee,Nrc Form 396,be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML18152B3711999-08-27027 August 1999 Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed ML18152B3851999-08-23023 August 1999 Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis ML18152B3651999-08-20020 August 1999 Requests Removal of License Condition from Sh Wightman Operator License SOP-21538.Updated NRC Form 396 Is Encl.Form NRC 396 Withheld,Per 10CFR2.790(a)(6) ML18152B3681999-08-20020 August 1999 Submits 30-day Rept Re Two Instances in Which Conditions of Approval in Coc Were Not Observed in Making Shipment.Two Type B Shipments Using Model CNS 8-120B Package Were Made After Expiration of QA Program Approval Between 990531-0628 ML18152B3661999-08-20020 August 1999 Provides Medical Status Rept for E Washington,As Required by License Conditions.Summary of E Washington Current Physical Exam & Pertinent Lab Data Attached.Encl Withheld,Per 10CFR2.790(a)(6) ML18152B3801999-08-18018 August 1999 Forwards Technical Rept NE-1206,Rev 0, Surry Unit 2,Cycle 16 Startup Physics Tests Rept, Summarizing Results of Physics Testing Program Performed After Initial Criticality on 990525 ML18152B3781999-08-13013 August 1999 Forwards ISI Summary Rept for Surry Power Station,Unit 2 for 1999 Refueling Outage.Rept Provides Summary of Examination Performed During Outage for Third ISI Interval.No New Commitments Were Made ML18152B3751999-08-13013 August 1999 Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML18152B4211999-05-25025 May 1999 Forwards Rev 1 to Relief Request P-11 to Clarify Original Intent of Request by Specifically Requesting Relief from Requirements of Section 6.1 of OM-6 ML18152B4171999-05-17017 May 1999 Provides Notification of Number of Steam Generator Tubes That Were Plugged During Spring 1999 Refueling Outage Planned ISI ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML18152B4121999-05-0303 May 1999 Forwards Application for Renewal of License for SV Ross. Encl Withheld Per 10CFR2.790(a)(6) ML18152B4101999-04-29029 April 1999 Forwards Scope & Objectives for 990803 Surry Power Station Emergency Exercise.Without Encls ML18152B6561999-04-23023 April 1999 Forwards Annual Radioactive Effluent Release Rept for Surry Power Station,Jan-Dec 1998, Which Includes Summary of Quantities of Radioactive Liquid & Gaseous Effluents & Solid Waste Released During CY98 ML18152B6491999-04-13013 April 1999 Forwards MOR for Mar 1999 for Surry Power Station,Units 1 & 2.MOR for Feb 1999 Incorrectly Stated Gross Electrical Energy Generated (Mwh) for Unit 2.Rept Should Have Stated Monthly Figure as 568965.0 ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML18153A2721999-03-29029 March 1999 Forwards LER 99-002-00 Per 10CFR50.73.Listed Commitments Contained in Ltr ML18153A3421999-03-26026 March 1999 Provides Updated Medical Status Rept for Wb Gross in Accordance with License SOP-20476-02,Docket 55-5228,as Amended by 980320 License Amend.Informs That Gross Exhibits No Performance Problems & Will Continue on Current Medicine ML20204H0331999-03-17017 March 1999 Forwards Rev 5 to PSP for Surry & North Anna Power Stations & Associated Isfsis.Description & Justification for Changes Included with Plan Rev.Rev 5 to PSP Withheld Per 10CFR73.21 ML18153A3411999-03-15015 March 1999 Forwards Signed Applications & Medical Certificates for Initial License at Surry Power Station Units 1 & 2 for Listed Individuals.Without Encls 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML18153C3661990-09-20020 September 1990 Forwards Topical Rept VEP-NE-3-A, Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code. ML18153C3701990-09-18018 September 1990 Forwards Addl Info Re Facility Containment Isolation Valve Type C Test,Per 900914 10CFR50,App J Exemption Request ML18152A2341990-09-14014 September 1990 Requests Exemption from 10CFR50,App J Section III.D.3 Re Local Leak Rate Testing During Every Reactor Shutdown. Basis & Justification for Exemption Encl ML20059J3341990-09-13013 September 1990 Forwards Rev 15 to Nuclear Security Personnel Training & Qualification Plan.Rev Withheld ML18151A2901990-08-31031 August 1990 Forwards Rev 10 to Updated FSAR for Surry Power Station Units 1 & 2,representing Second Updated FSAR Submitted This Yr ML18153C3451990-08-29029 August 1990 Forwards Proprietary Semiannual Fitness for Duty Program Performance Data Rept for 900103-0630.Rept Includes Summaries of Mgt Sanctions Imposed,Actions Taken to Correct Program Weaknesses & Events Reported to Nrc.Encl Withheld ML18153C3381990-08-22022 August 1990 Responds to NRC 900723 Ltr Re Violations Noted in Insp Rept 50-280/90-21 & 50-281/90-21.Corrective actions:as-found-as- Left Conditions of Auxiliary Feedwater Evaluated & Found Operable ML18153C3391990-08-22022 August 1990 Requests Approval for Use of Plugs Fabricated of nickel- chromium-iron Uns N-06690 Matl (Alloy 690) to Plug Tubes in Steam Generators for Mechanical & Welded Applications ML18153C3161990-08-0101 August 1990 Provides Supplemental Response to NRC 900629 Ltr Re Electrical Crossties,Load Shedding on Nonblackout Unit & Emergency Diesel Generator Reliability.Emergency Diesel Generator Reliability Program in Place,Per Reg Guide 1.155 ML18153C3171990-08-0101 August 1990 Resubmits Synopsis of Changes to Updated Operational QA Program Topical Rept Vep 1-5A ML18153C3091990-07-30030 July 1990 Provides Outline of Plan to Meet 10CFR50 App G Requirements, for Low Upper Shelf Energy Matls,Per NRC 900521 Request ML18153C3061990-07-30030 July 1990 Forwards Revised Tech Spec Pages,Addressing Constitution of Quorum & Timeliness of Mgt Safety Review Committe Meeting Minutes,Per NRC Request ML18153C3051990-07-26026 July 1990 Advises That Util Submitted Decommissioning Funding Plan & Financial Assurance Info W/Isfsi License Application ML18153C3041990-07-26026 July 1990 Responds to NRC 900626 Ltr Re Violations Noted in Insp Rept 50-281/90-20.Corrective Actions:Leaking Drain Plug & Upper Drain Plug on Motor Replaced W/Oil Drain Assemblies Composed of Piping & Valves ML18153C3031990-07-26026 July 1990 Advises of Withdrawal of Request for NRC Review & Approval of Engineering Evaluation 8.Revised Evaluation Will Be Maintained Onsite for NRC Audit During Future Insps,Per Generic Ltr 86-10 ML18153C3101990-07-26026 July 1990 Forwards Decommissioning Financial Assurance Certification Rept..., Nuclear Decommissioning Trust Agreement & Nonqualified Nuclear Decommissioning Trust Amended & Restated Trust Agreement, Per 10CFR50.75 ML18153C2901990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Listed Transmitters Compiled.Transmitters Found Installed within Reactor Protection or ESFAS Have Been Replaced ML18153C2861990-07-12012 July 1990 Requests Cancellation of Operator Licenses for Listed Individuals.Licenses No Longer Required ML18153C2871990-07-11011 July 1990 Responds to Violations Noted in Insp Repts 50-280/90-18 & 50-281/90-18.Corrective Actions:Permanent Drain Line Installed & Matrix Which Describes Proper Ventilation Alignment for Plant Conditions Provided for Personnel Use ML18153C2851990-07-0606 July 1990 Forwards Response to Generic Ltr 90-04 Re Status of Generic Safety Issues ML18153C2831990-07-0303 July 1990 Advises That MW Hotchkiss No Longer Needs Operator License SOP-20548-1.Cancellation of License Requested ML18153C2821990-07-0303 July 1990 Requests Exemption from 10CFR50,App J,Paragraph III.A.6(b), Which Requires That When Two Consecutive Periodic Type a Tests Fail to Meet Applicable Acceptance Criteria Type a Test Shall Be Performed at Plant ML18153C3591990-06-28028 June 1990 Responds to SALP Repts 50-280/90-16 & 50-281/90-16 for Period 890701-900331.Corrective Actions Focus on Issues of Maint Backlog,Maint planning,post-maint Testing,Staffing & Procurement ML18153C2611990-06-21021 June 1990 Responds to NRC 900522 Ltr Re Violations Noted in Insp Repts 50-280/90-07 & 50-281/90-07.Corrective actions:as-built Configurations of 120-volt Ac & Dc Vital & Semivital Panel Breaker Installations Verified to Be Acceptable ML18153C2581990-06-18018 June 1990 Forwards Reissued Semiannual Radioactive Effluent Release Rept,Jul-Dec 1989. Rept Contains Info Re SR-89,Sr-90 & Fe-55 Analytical Results for Liquid Composite Samples ML18153C2591990-06-18018 June 1990 Forwards Response to NRC 900524 Request for Addl Info Re NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Engineering Will Initiate Study to Evaluate Enhancements of Cooldown & Possible Heatup Operation ML18153C2541990-06-15015 June 1990 Forwards Corrected Tech Specs Page 3.1-3,per Identification of Typo in 900522 Application for Amends to Licenses DPR-32 & DPR-37 ML18153C2521990-06-14014 June 1990 Responds to NRC 900515 Ltr Re Violations Noted in Insp Repts 50-280/90-09 & 50-281/90-09.Corrective Actions:Abnormal Procedures & Fire Contingency Action Procedures Being Upgraded Via Technical Procedure Upgrade Program ML18153C2501990-06-0808 June 1990 Confirms That Primary Policy Re Onsite Property Damage Insurance,Provided by Nuclear Mutual Limited ML18153C2361990-05-29029 May 1990 Responds to NRC 900427 Ltr Re Violations Noted in Insp Repts 50-280/90-14 & 50-281/90-14.Corrective Actions:Personnel Involved Counseled as to Importance of Properly Recording & Reporting Surveillance Data ML18153C1971990-04-24024 April 1990 Responds to Unresolved Items Noted in Insp Repts 50-338/89-12,50-339/89-12,50-280/88-19 & 50-281/88-19 Re Secondary Sys Containment Leakage & Concludes Leakage Need Not Be Quantified & Not Included in as-found Leakage ML18153C1961990-04-20020 April 1990 Forwards Facility Previous Tests & Projected Leakage Totals for Type C Testing for Valves & Penetrations,Per 900108 Ltr ML18153C1901990-04-18018 April 1990 Requests That Operator License OP-20447-1 for Ja Yourish Be Cancelled ML18153C1861990-04-0505 April 1990 Requests Exemption from 10CFR50,App J,Paragraph III.A.6(b). Util Implemented Corrective Action Program Which Meets Intent of Regulation in Establishing Containment Integrity ML18153C1671990-03-30030 March 1990 Submits Supplemental Response to 10CFR50.63, Loss of All AC Power. Understands That Load Mgt Schemes for Both Blackout & Nonblackout Units Allowed by Station Blackout Rule ML18151A2551990-03-30030 March 1990 Forwards Rev to, Corporate Emergency Response Plan & Rev to, Corporate Plan Implementing Procedures. ML18151A4941990-03-29029 March 1990 Forwards Listed Info Re Licensee Guarantees of Payment of Deferred Premiums,Per 10CFR140.21(e) ML18153C1631990-03-27027 March 1990 Responds to Violations Noted in Insp Repts 50-280/86-05 & 50-281/86-05.Corrective Action:Surveillance Tests Being Performed in Accordance W/Administrative Requirements of Station Procedures & Plans Implementing New Review Process ML18153C1551990-03-20020 March 1990 Clarifies 900108 Request for Exemption from 10CFR50,App J Re Type C Testing Requirements ML18153C1511990-03-19019 March 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47. Operability & Surveillance Requirements for Steam Generator Overfill Protection Sys Will Be Incorporated in Tech Spec Change ML18153C1661990-03-16016 March 1990 Discusses Waiver of Compliance Re Containment Vacuum Sys Operability,Per 900315 & 16 Telcons ML18153C1471990-03-14014 March 1990 Discusses Functional Test for High Setpoint for PORVs ML18153C1571990-03-12012 March 1990 Forwards List of Emergency Operating Procedures in Preparation for 900402-12 Insp.Vol I Is Emergency Operating Procedure Set & Consists of 47 Notebooks.Vol II Contains Fire Contingency Action (App R) Procedures ML18153C1371990-03-0808 March 1990 Forwards Suppl to 1986 Inservice Insp Summary Rept,Adding Two Missing NIS-2 Forms Containing Info Re Replacement of Bolting Matl on 1-RC-SV-1551C (Flange a) & 1-RC-HCV-1556A ML18153C1281990-03-0101 March 1990 Submits 1989 Annual Steam Generator Inservice Insp Rept Results.No Steam Generator Tubes Plugged in 1989 ML18153C1261990-03-0101 March 1990 Responds to Generic Ltr 90-01 Re NRC Regulatory Impact Survey.Survey Covers Type of Insp,Audit or Evaluation by NRC Resident,Nrc Regional Ofc,Nrc Teams & INPO ML18153C1231990-02-22022 February 1990 Responds to NRC 900123 Ltr Re Violations Noted in Insp Repts 50-280/89-32 & 50-281/89-32.Corrective Actions:Use of Lab Hood Attached to F-2 Fan Suction Prohibited & Contaminated & Radioactive Items Removed from Hood ML18152A4881990-02-0606 February 1990 Responds to NRC 891222 Ltr Re Violations Noted in Insp Repts 50-280/89-34 & 50-281/89-34 on 891029-1125.Corrective Actions:Steps in Operating Procedure 2-OP-1.3 Associated W/ Valve Test Being Evaluated for Inclusion in OP-7.1.1 ML18153C0991990-02-0101 February 1990 Withdraws 891018 Application for Amends to Licenses DPR-32 & DPR-37,increasing Pressurizer Safety Valve Setpoint Tolerance to +/- 3% of Nomical Lift Setpoint.Emergency Tech Spec Change Granted on 891116 Provided Modified Tolerances ML18153C0951990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted 1990-09-20
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. U. S. Nuclear Regulatory Commission Serial No. 88-7908 Attn: Document Control Desk NO/HWB:vlh R3 Washington , D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 GDC-2 REANALYSIS: SERVICE WATER SYSTEM During the Safety System Functional Inspection of the Surry Service Water System the NRC Staff identified a concern with regard to the ability of the Service Water System to perform its safety function during a hurricane as required by General Design Criterion 2 (GDC-2). For this reason, the NRC requested the results of the safety analysis which
- ** _.confirms that in the event of a hurricane concurrent with the loss of offsite power (LOOP) to both units, sufficient service water flow is provided to equipment necessary to ensure a safe hot shutdown.
We have completed our reanalysis that demonstrates the adequacy of the service water system with respect to compliance with GDC-2. Attachment 1 provides the results of this reanalysis. Also provided in this report is the necessary operator actions and the times to achieve and maintain cold shutdown in the event of a hurricane. We are revising the applicable station procedures to address the results of the analysis and will complete this effort by June 30, 1989.
Should you have any questions concerning this response please contact us.
W. L. Stewart Senior Vice President-Power Attachment 89051aA00017c! ~;ggg~ao PDR PNU p
cc: U. *s. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station
e ATTACHMENT 1
SUMMARY
REPORT HURRICANE SHUTDOWN ANALYSIS SURRY POWER STATION LTR 88-7909 - ATTACHMENT 1 - PAGE 1 OF 12
e*
BACKGROUND As a result of the recent Safety System Functional Inspection at the Surry Station, the NRC requested additional information on system performance in the event of a hurricane. The NRC request is as follows:
"During the Safety System Functional Inspection of the Surry Units 1 and 2 service water system conducted in September 1988, the staff identified a concern with regard to the ability of the service water system to perform its safety function during a hurricane as required by General Design Criterion 2.
Specifically, following a hurricane, Section 2.3 of the UFSAR indicates that the level in the service water discharge canal will be 24 ft-4 in. and the inlet canal level will be 26 feet. With the resulting differential head of approximately 1-1/2 feet, sufficient driving head to ensure adequate service water system flow to required components may not be available.
Therefore, please provide the results of your analysis which confirms that in the event of a hurricane and a loss of offsite power to both units, sufficient service water flow is provided to equipment necessary to ensure a safe hot shutdown. A concurrent design basis event (LOCA) need not be postulated.
Further, please identify the necessary actions and times to achieve and maintain cold shutdown under these conditions."
This report provides the results of analysis performed to demonstrate that in the event of a hurricane and associated loss of offsite power to both units, sufficient service water flow is provided to equipment necessary to ensure a safe hot shutdown. In addition to the analysis results, necessary actions and times to achieve and maintain cold shutdown in the event of a hurricane are provided.
LTR 88-7908 - ATTACHMENT 1 - PAGE 2 OF 12
e PROBABLE MAXIMUM HURRICANE In order to determine the maximum river surge during the probable maximum hurricane (PMH), the following analysis of water surface levels during the hu'rricane was performed:
- 1) Calculation of the open coast surge level and resultant surge level at the site as a function of time.
- 2) Calculation of the wave height and run-up at the site and at the low level intake structure.
- 3) Calculation of the wave run-up within the intake canal.
Open coast surge during the probable maximum hurricane was calculated at the entrance to the Chesapeake Bay using methods based on the Bathystropic Storm Tide theory. The highest open coast stillwater level consists of the following components:
- The highest astronomical tide.
- An initial rise to account for short period anomalies.
- The rise due to atmospheric pressure reduction.
- The surge generated by the wind component acting perpendicular to the ocean bottom contours.
- The surge generated by the wind component acting parallel to the ocean bottom contours.
Once the open coast stillwater level was determined, the storm surge was routed through the Chesapeake Bay and up the James River to the power station.
The mathematical model used for storm surge routing consisted of the one-dimensional continuity and momentum equations applicable to variable area estuaries, embayments, or sea-level canals. The equations are solved simultaneously by means of an explicit finite-difference scheme to yield values of tidal elevation and flow along the longitudinal axis of the waterway. The model LTR 88-7908 - ATTACHMENT 1 - PAGE 3 OF 12
e takes i-nto account the effects of wind stress, river inflow, ocean tidal hydrograph and nonconveyance river water storage.
The entire James River from the river mouth at Chesapeake Bay to Richmond, Virginia, the head of tide, was considered in the mathematical model. The first 75 miles of the river reach from the river mouth was divided into 25 three-mile segments. An adequate storage area was provided in the model to account for the total tidal area of the remaining upstream river reach.
The model was used for storm surge routing by applying the open coast PMH storm surge hydrograph at the river mouth. In addition, an average wind of 91 mph along the PMH maximum wind axis covering the entire river reach was used to account for wind setup along the river. A constant coefficient of 2.8 x 10-6 was used to compute the surface wind stress. The mean monthly fresh water flow of 10,000 cfs was used as the river inflow during the PMH storm surge routing.
The storm surge hydrograph based on the mean sea level datum (MSL) at the Surry station and calculated in the manner described above, is shown in Figure 1. The maximum stillwater level at the Surry station river intake is 22.6 MSL.
HURRICANE SHUTDOWN ANALYSIS In order to demonstrate the safe shutdown of the units in the event of the hurricane surge calculated above, the analyses described in the following paragraphs were performed.
The overall approach of the analysis is to bring the operating unit(s) to a hot shutdown based on sufficient hurricane warning. Hot shutdown units are maintained at hot shutdown (RCS temperature above 350°F) until the storm surge recedes below the level required to obtain sufficient service water flow to allow further cooldown. Unit(s) at cold shutdown or in refueling mode would be maintained at cold shutdown (RCS temperature below 200°F). Refueling activities would be suspended prior to the arrival of the hurricane.
The total amount of condensate that can be stored in missile-protected tankage and be made available to the auxiliary feedwater (AFW) system to provide for hot shutdown unit cooling is described in the UFSAR Section 10.3.5.2. The volume LTR 88-7908 - ATTACHMENT 1 - PAGE 4 OF 12
e e i~cludes the minimum required by Technical Specification limits for the emergency condensate storage tanks plus the contents of the underground emergency condensate makeup tanks. Based on the relationship between AFW volume and energy removal calculation, the heat energy removal capability of the available AFW was determined. Total integrated decay heat and cooldown limitations were examined to determine the length of stay allowed at hot shutdown before cooldown must start. The calculations take no credit for the use of the firewater system which can be used to extend this staytime.
Several intake canal profiles were developed to examine the effect of service water flow as the discharge intake elevation rose with the storm surge and then receded.
The time sequence and levels of the storm surge came from the storm surge analysis described earlier. These values reflect the most severe storm expected to occur (design basis hurricane-PMH). Profiles were developed for 1, 2, and 3 component cooling water (CCW) heat exchangers with an initial canal height of 23 and 26 feet.
During the development of the profiles, variables such as emergency service water makeup and canal outleakage were examined.
Reduced service water flows to the component cooling water heat exchangers were calculated based on the intake canal profiles. The effect of the reduced flow on plant thermal relationships was evaluated using the Heat Exchanger Effectiveness Method using conservative values for fouling factors and tube plugging for the CCW heat exchanger. Heat transfer capabilities were calculated providing the resultant service water, component cooling water, letdown, and residual heat removal system temperatures.
Additionally, a calculation of the resultant drop of the water level in the intake canal was performed based on a starting elevation of 23 feet. The analysis determined that sufficient service water inventory was available during a storm which causes low river levels such that the emergency service water pumps are not available.
SUMMARY
OF CALCULATION RESULTS
- 1. River surge elevations with respect to time are presented in Figure 1.
LTR 88-7908 - ATTACHMENT 1 - PAGE 5 OF 12
e
- 2. The available intake canal inventory at elevation 23 ft reduces to 18 ft with no makeup to the canal and required service water flows are provided to the station to maintain units at hot or cold shutdown.
- 3. 196,000 gallons of condensate are available per unit to maintain hot shutdown.
An additional 60,000 gallons are also available to the hot shutdown unit when the other unit is in cold shutdown or refueling via a unit cross-connect.
- 4. The available condensate of 196,000 gallons will maintain hot shutdown for 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> including RCS cooldown to 350°F. With one unit at cold shutdown, the available condensate of 256,000 gallons will maintain the hot shutdown unit for 38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br /> including RCS cooldown to 350°F.
- 5. With two (2) units at hot shutdown and an intake canal elevaHon initially at 23 feet (proposed Technical Specification minimum), the units can be maintained at hot shutdown conditions throughout the hurricane event.
- 6. With one (1) unit at hot shutdown and one (1) unit at cold shutdown and an initial intake canal elevation of 26 feet, the units can be maintained at hot shutdown and cold shutdown, respectively throughout the design basis hurricane event.
- 7. With two (2) units at cold shutdown and an initial intake canal elevation of 26 feet, the units can be maintained at cold shutdown throughout the design basis hurricane event.
- 8. With one or two units at cold shutdown, two (2) emergency service water pumps, three (3) component cooling water (CCW) heat exchangers and two (2)
CCW pumps are required during the design basis hurricane event.
- 9. For hot shutdown units during the design basis hurricane event, one (1) CCW heat exchanger, one (1) CCW pump, and one (1) auxiliary feedwater train is required per unit.
- 10. Table 1 provides the resulting system temperatures for the hot shutdown and cold shutdown units.
LTR 88-7909 - ATTACHMENT 1 - PAGE 6 OF 12
- 11. The hot shutdown units can proceed to cold shutdown approximately 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> after the hurricane hits the site using existing equipment and procedures for loss of offsite power. The 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> corresponds to the time when the river surge recedes to below an elevation of 8 ft which is the minimum discharge tunnel elevation with loss of tunnel vacuum priming. Cooldown may actually begin earlier, however, the rate of cooldown will be limited by the available service water flow and/ or increase in RCS and CCW temperatures.
DESCRIPTION OF HURRICANE SHUTDOWN ACTIONS Hurricane watches and warnings are provided by the National Weather Service (NWS). Hurricane watches are issued for an area 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> prior to the expectation of hurricane conditions. Hurricane warnings are issued for an area 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the expectation. of wind speeds in excess of 73 mph. With the institution of a hurricane warning, station personnel will have sufficient time to take action prior to* arrival of the hurricane.
During the 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> period prior to the hurricane, the site will start hurricane preparations such as closing missile doors, putting flood protection barriers in place, and preparing equipment required for shutdown. This will require installation of the emergency service water (ESW) pump house door watertight seal plates and ventilation louver opening covers. Also, preparation will be required to ensure three (3) CCW heat exchangers are operable when one or two units are at cold shutdown.
With the NWS 24-hour hurricane warning, procedures for extreme weather conditions will be invoked. These procedures will require placing the operating units in hot shutdown and maintaining the cold units at cold shutdown as follows:
For two units operating prior to the hurricane warning, the units will be shut down 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> before the hurricane is anticipated to reach the site (i.e., this is defined as when sustained wind speeds exceeds 70 mph onsite). Decay heat removal will be performed using the circulating water system until a loss of power occurs at which time the auxiliary feedwater system will be used. For analysis basis, this is assumed that the loss of power occurs coincident with the LTR 88-7908 - ATTACHMENT 1 - PAGE 7 OF 12
arrival of hurricane winds on site. This criteria is consistent with guidelines provided in NUMARC 87-00 (Section 2.11 "Hurricane Preparations") used for Station Blackout analysis.
With one or both units in cold shutdown or refueling mode at the time of the warning, the water elevation in the Intake Canal must be raised to above 26 feet to ensure that sufficient driving head is available to provide heat removal capability for the Component Cooling System during the expected storm surge.
Reanalysis of the wave run-up within the intake canal identifies a required freeboard of only 4 feet from the top of the canal (elevation 36 feet).
Accordingly, the canal water level will be procedurally required to be 28 feet prior to the arrival of the hurricane to ensure adequate head during the storm surge.
Due to the potential for the intake canal siphoning back through the circulating water pump discharge lines, the circulating water pumps will be shut down prior to the hurricane reaching the site. The plant has been modified to passively break the siphon at elevation 23 ft, however, the hurricane analysis requires an elevation of 26 ft to ensure adequate service water flows with peak river surge. Therefore, the circulating water pumps will be shut down and siphon broken after raising the canal elevation to 28 feet.
To ensure adequate decay heat removal of the shutdown unit(s) at the peak river surge (el 22.6 ft), the CCW heat exchangers and pumps will be cross-connected to allow the flow of the CCW pumps to be equally distributed to the three operable CCW heat exchangers. Also, to minimize the CCW heat loads, nonessential heat loads will be isolated. The analysis is based on using CCW to the Residual Heat Removal (RHR) heat exchangers for decay heat removal for cold shutdown units, and CCW for heat removal for letdown and auxiliary feedwater for decay heat removal for the hot shutdown units.
For the case where one unit was initially operating and one unit was at cold shutdown, an additional 60,000 gallons of condensate is available for the operating unit by cross-connecting to the cold shutdown unit. This additional 60,000 gallons will allow AFW operation for a total of 38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br /> after shutdown of the circulating water system. The decay heat load analysis is based on the operating unit(s) being LTR 88-7908 - ATTACHMENT 1 - PAGE 8 OF 12
shut down two (2) hours prior to the hurricane reaching the site and a loss of power o*ccuring. However, in order to ensure that a canal level of 28 ft is established and isolation of the circulating water system occurs without siphoning the canal, the operating unit will be shut down while sustained wind speeds are lower than 35 mph. This will enable operators to visually observe the operation of the circulating water pump discharge piping active vacuum breakers as each pump is shut down, thus ensuring that a reverse siphon is not established.
Upon the hurricane warning, operators will be required to:
- 1) Start two emergency service water (ESW) pumps after the circulating water pumps are isolated or loss of power occurs.
- 2) Close or verify closed service water and circulating water isolation valves except in the flowpaths for the following equipment:
- Control room and Emergency Switchgear Room Chiller service water pumps.
- 3) Align and cross-connect the CCW system such that all of the operating CCW pumps feed all of the three operating CCW heat exchangers.
- 4) Isolate CCW loads except for:
RHR heat exchangers (cold shutdown unit(s))
- Letdown (nonregenerative) heat exchangers (hot shutdown unit(s))
- Penetration cooling coils
- Neutron shield tank cooler
- Loads assumed in analysis; but not essential to maintain hot or cold shutdown.
- 5) Monitor CCW outlet temperatures and adjust the service water outlet valves as necessary to maintain normal system temperatures as the surge reduces the driving head for the heat exchangers. As the driving head diminishes, and with the outlet valves wide open, CCW temperatures LTR 88-7908 - ATTACHMENT 1 - PAGE 9 OF 12
will rise to the values identified in Table 1. As the river recedes and the driving head increases, the outlet valves will again be throttled to maintain normal CCW temperatures.
. 6) Align the hot shutdown unit(s) for RHR decay heat removal after the river recedes* to below an elevation of 8 feet and cool down units to cold shutdown.
CONCLUSIONS
- 1) In the event of a design base hurricane which causes a blowout of the river, resulting in the loss-of-suction of the ESW pumps, there is sufficient intake canal inventory at the proposed Technical Specification minimum level of 23 feet to maintain the units at hot or cold shutdown for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period without makeup to the canal.
- 2) With both units at hot shutdown and decay heat being removed by the AFW system, the Technical Specification intake canal level of 23 feet provides sufficient inventory to maintain the units at hot shutdown throughout the design base hurricane.
- 3) With one or two units at cold shutdown, a minimum canal elevation of 26 feet is needed in order to ensure that sufficient heat removal capability is maintained.
- 4) With both units at hot shutdown, the units can be maintained at hot shutdown utilizing the AFW system for decay heat removal for 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br />. With one unit at hot shutdown and one unit at cold shutdown, the hot shutdown unit can be maintained at hot shutdown for 38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br /> on the AFW system. The above times are based on using Technical Specification condensate volumes of the emergency condensate storage tanks plus 100,000 gallons from the emergency condensate makeup tanks. Other sources of condensate are available (the condensate tanks (300,000 gallons) and the fire protection system) but were not considered for the analysis.
LTR 88-7908 - ATIACHMENT 1 - PAGE 10 OF 12
- 5) The cold shutdown units can be maintained at cold shutdown (RCS < 200°F) throughout the storm surge.
- 6) . The hot shutdown units can proceed to cold shutdown, if needed, when the river recedes below an elevation of 8 ft. This is approximately 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> after the design base hurricane reaches the site. The cooldown will be performed using normal loss of power procedures and system capacities.
LTR 88-7908 - ATIACHMENT 1 - PAGE 11 OF 12
e TABLE1 RESULTANT SYSTEM TEMPERATURE HURRICANE SHUTDOWN ANALYSIS I. Two (2) plants at cold shutdown.
RHR hot 190°F CCW cold 119°F CCW hot 130°F
. SW hot 109°F
- 2. For one (1) unit at hot shutdown and one (1) unit at cold shutdown.
Cold Plant RHR hot 190°F CCW cold 115°F CCW hot 127°F SW hot 106°F Hot Plant CCW (non-reg. hx) out 113°F ccw cold 102°F CCW hot 111°F SW hot 105°F
- 3. For two (2) units at hot shutdown.
Same as for hot plant above.
LTR 88-7908 - ATIACHMENT 1 - PAGE 12 OF 12
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