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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 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 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 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) 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) 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 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 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 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 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
MONTHYEARML18153C3661990-09-20020 September 1990 Forwards Topical Rept VEP-NE-3-A, Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code. ML20065D5671990-09-20020 September 1990 Forwards Rev 15 to Security Personnel Training & Qualification Plan.Rev Withheld 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 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 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 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 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 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 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 ML20055D4841990-07-0303 July 1990 Requests That Operator Licenses for Listed Individuals Be Cancelled.Licenses No Longer Required ML20055D4831990-07-0303 July 1990 Requests That Operator License for Bl Shriver Be Cancelled. License No Longer Required 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 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 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) 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 ML20055C8661990-06-15015 June 1990 Forwards Application for Reissuance of NPDES Permit 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) 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 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 ML20043G8731990-06-14014 June 1990 Discusses Evaluation of ASME Section XI Testing for Outside Recirculation Spray Pumps 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 ML20043H2091990-06-13013 June 1990 Forwards List of Corrective Actions & Current Status in Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss 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 ML18153C2501990-06-0808 June 1990 Confirms That Primary Policy Re Onsite Property Damage Insurance,Provided by Nuclear Mutual Limited 1990-09-07
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e Attachment Page 1 NOBTH ANNA POWER STATION UNIT NOS. 1 AND 2 RESPONSE TO IE BULLETIN NO. 80-16 "Potential Misapplication of Rosemount, Inc. Model 1151 and 1152 Pressure Transmitters with either "A" or "D" output codes".
(1) The Rosemount Inc. Transmitter Model Number 1152 is presently installed at the North Anna Power Station Units 1 and 2 in various applications.
No model number 1151 transmitters are utilized.
There are (2) model number 1152 transmitters with the following (5) process applications:
Narrow Range Steam Generator Level (9) Transmitters Main Steam Line Steam Flow (6) Transmitters Reactor Coolant Wide Range Pressure (1) Transmitter Casing Cooling Tank Level - Unit 1 Only (2) Transmitters Emergency Condensate Storage Tank (2) Transmitters Level - Unit 2 Only An attached table identifies pertinent information on these transmitter applications.
(2) Each transmitter application was reviewed* for input process conditions that could result in anomalous output signals. The determination is as follows:
Narrow Range Steam Generator Level The maximum input differential pressure condition possible for this transmitter is 144 inches of H o, which could occur if the water level in 2
the steam generator falls below the lower level tap. The minimum input differential pressure condition possible is O inches of water which could occur if the water level in the steam generator rises above the upper level tap. The input process conditions cannot exceed these extremes because the level sensing taps are fixed to the steam generator and thereby limit the measurement range of differential pressure by the transmitter.
Steam generator level transmitters are reverse acting with a maximum differential pressure producing a minimum transmitter level output. From Enclosure 1 of the Bulletin, the input differential pressure to produce an anomalous output from an overpressure condition is (150" H 0 x 1. 4 =
2 210" H 0). Reverse pressure conditions are not considered possible for 2
this application since the transmitter reference water column is fixed to the upper level tap.
Since the transmitter input is limited by the tap connections to 144 inches of water, it cannot exceed the 210 inches of water limit and no anomalous output should result.
Attachment Page 2 Main Steam Line Steam Flow For normal operating conditions, steam flow remains within the range of the transmitter; however, it is conceivable that the steam flow would be very high during the initial phase of a steam break accident as analyzed in Section 15. 4. 2 of the FSAR. A review of this section reveals from Figure 15.4.2-2 that a maximum steam flow from the affected steam generator of 3095 lbs/sec could exist for: a very brief period of. time following a complete main steam line rupture (3095 lbs/sec .x 3600 sec/hour= 11,142,000 lbs/hr.).
Using the methodology of the Bulletin, the limiting overpressure condition for the transmitter is (2770" H O x 1.4 = 3878" H 0), which could result in an erroneous indication at full scale. Normal full scale output of the steam flow transmitter is 1687 .4" H 0, which equals a 6
5 x 10 lbs/hour. Since steam pressure conditions at2 the flow measuring nozzle are not precisely known during the hypothesized steam line break, it is assumed, for purposes of analysis, that the differential pressure generated across the nozzle will exceed the overpressure limit of 3878 inches of water.
Although the steam flow transmitter may exhibit anomalous output during the initial phase of a major steam line break, no design basis assump-tions are violated. During the accident transient, the reactor is protected and safety injection is actuated by steam flow differential l:- ..
pressure which accurately sensed at a differential pressure equivalent to less than ll0% power (1256.7 11 H 0). Consequently, the protective fea-tures of the steam flow transmitter 2 function. properly before the process exceeds the transmitter overpressure limit of 3878 inches of water.
A transmitter reverse pressure condition is not considered possible for normal steam flow, since the transmitter taps are fix=d in relation to the flow measuring nozzle. However, a steam line break upstream of the flow measuring nozzle may cause the process flow to reverse. In this case the transmitters on the broken line are inoperable and the remaining transmitters on the unbroken line provide high steam flow protection.
The transmitters are not subject to anomalous output described in the Bulletin during normal and transient operations. During a brief period following a major steam break, the transmitter may exhibit anomalous output; however, the protective features function properly prior to reaching the transmitters full scale. Additionally no incorrect operator action occurs since the steam flow reduces rapidly on scale following a major steam break.
Wide Range Reactor Coolant Pressure Since the reactor coolant pressure is limited by code safety valves to less than 2485 psig, the reactor coolant pressure transmitters do not exceed the pressure conditions necessary to produce anomalous output.
- *~ '.. 'IJ' Attachment Page 3 Using the methodology of the Bulletin, the limiting overpressure condition of the transmitter is (3000 psig x 1.4 = 4200 psig). In addi-tion, reverse pressure conditions are not applicable.
Casing Cooling Tank Level Since the casing cooling tank is vented to atmosphere and limited by its height to 35 feet, 6 inches, the pressure exerted on the level trans-mitter can not exceed 426 inches of water (35 feet x 12 in/ft = 420 in.,
420 in.+ 6 in.= 426 inches of water).
Using the methodology of the Bulletin, the limiting overpressure condition of the transmitter is (750 in. of water x 1.4 = 1051 inches of water). This amount is greater than the maximum achievable pressure of the process; therefore no anomalous output will be produced. Additional-ly, reverse pressure conditions are not applicable to the transmitter since it is vented to atmosphere.
Emergency Condensate Storage Tank (110,000 Gallons)
Since the emergency condensate storage tank is vented to atmosphere and limited by its height of 32 feet 9 inches, the pressure exerted on the level transmitter cannot exceed 363 inches of water (32 ft. x 12 in/ft =
354 in., 354 in.+ 9 in.= 363 inches of water). - *
- Using the methodology of the Bulletin, the limiting overpressure condition of the transmitter is (750 inches of water x 1. 4 = 1051 inches of water), which is greater than the maximum achievable pressure of the process; therefore no anomalous output will be produced. ,Additionally, reverse pressure conditions are not applicable to the trasmitter since it*
is vented to atmosphere.
(3) Corrective Action For the five applications of Model 1152 Transmitters utilized at North Anna, no design basis assumptions are violated. Based on the*
analysis and evaluation performed, no corrective actions are required.
Attachment Page 4 VALUES OF PROCESS RANGE OF PROCESS VARIABLE WHICH VARIABLE MEASURED FOR COULD.PRODUCE COMPLETED MODEL TRANS RANGE TRANS RANGE NORMAL ACCIDENT ANOMALOUS SERVICE/
APPLICATION NUMBER LIMITS SETTINGS CONDITIONS CONDITIONS INDICATIONS FUNCTION N.R.
Stm. Gen.
Level 1152DP4A 0 to 150" H o 2
0% to 100%
Level 140.1 to 36.3 H 0 2
33 to 44%
Level 0 to 100%*
Level
. 210" H20 Level fil>/Stm. Gen.
6 Stm. 1152DP6A 0 to 2770 11 0 to 1687.4" 0 to 4xl0 6 0 to llxlO Flow H0 H 0 Lb/Hr Lb/Hr . 3878" H 0 &/Steam 2 2 2 Flow RC Wide Range 1152GP9A 0 to 3000 0 to 2335 0 to 2335 0-2485 4200 Pressure/
Press. Psig Psig Psig Psig Psig RC Press.
Casing Cooling 1152LL5A240 0 to 750" 0 to 365.25 11 0 to 365.25 11 0 to 365.25" >1051" H O Pressure/
H 6 2
Tank H 0 2
H 0 2 H 0 2 2 Liq. Le. .
Level'i'~
Emergency Condensate 1152DPSAPB 0 to 750" 0 to 289.50" 0 to 289.50" 0 to 289.5" >1051" H 0 Pressure/
Storage H0 H o H 0 H0 2 Liq. Level Tank-1,,\- 2 2 2 2
~\-*Unit 2 Only
Attachment 2 Page 1 SURRY POWER STATION RESPONSE TO IE BULLETIN 80-16 POTENTIAL MISAPPLICATION OF ROSEMOUNT, INC.
MODELS 1151 AND 1152 PRESSURE TRANSMITTERS WITH EITHER "A" OR "D" OUTPUT CODES
- 1. _Determine i~ your facility has installed or plans to install Rosemount, Inc. Model 1151 or 1152 pressure transmitters with output codes "A" or "D" in any safety-related application.
RESPONSE
It has been determined that there are Model 1152 pressure transmi.tters installed at Surry Power Station.
- 2. If it is determined that your facility has the transmitters described in 1 above in any safety-related application, determine whether they can be exposed to input pressures that could result in anomalous output signals during normal operation, anticipated transients or design bases acci-dents. If the affected transmitters can be exposed to input pressures that could result in anomalous output signals, perform a worst case analysis to determine whether the anomalous signals could result in vio-lating any design bases assumption. The safety-related application shall include control, protective or indication functions. If any safety-rela-ted application does not conform to the above requirements address the basis for continued plant operation until the problem is resolved and provide an analysis of all potential adverse system effects which could occur as a result of a postulated pressure transmitter* ma:Loperation decribed in Enclosure 1 of this bulletin. In each instance, the analysis should include the effects of postulated transmitter maloperation as it relates to indication, control and protective functions. The analysis shall address both incorrect automatic system operation and incorrect operator actions caused by erroneous indications. Address the confor-mance to : IEEE 279, Section 4. 20 in your analysis. Include in your analysis the following table:
- a. Complete model number.
- b. Transmitter range limits.
- c. Transmitter range setting.
- d. Range of process variable measured for (1) normal and (2) accident conditions.
- e. Values of process variable which could produce anomalous indication based upon your evaluation.
- f. Service/function.
RESPONSE
The attached data sheets provide the information requested in Item 2 above.
Attachment 2 Page 2
- 3. Submit a complete description of all corrective actions required as a result of your analysis and evaluations, together with the schedule for accomplishing the corrective actions.
RESPONSE
No corrective actions are planned at this time. An ongoing analysis is being conducted concerning the range of process variable measured for accident conditions. Should the results of this analysis yield any information contrary to our findings it will be forwarded as a supple-ment to this submittal.
Surr~wer Station Response to IE Bulletin 80-16 A. Model No: 1152 DP5A92PB . Serial No.236678 B. Range Limits: 0-750" H20
- c. Range Settings: 0-400" H 0 2
D. Range of Process Variable Measured for Normal Conditions: 0-400" H 0 = 4-20 ma OUT Accident Conditions: 400" 2 E. Values of Process Variable which could Produce Anomalous Indication: 1050" H o 2
F; Service/Function: Aux. Feed Pump Discharge flow to 2C S/G.
A. Model No. 1152 DP4A92PB Serial No . . 52215 B. Range Limits: 0-150" HO 2
C. Range Settings: 0-25" HO 2
D. Range of Process Variable Measured for Normal Conditions: 0-25" H 0 = 4-20 ma OUT.
Accident Conditions: 14" 2 E. Values of Process Variable which could Produce Anomalous Indication: 210" H 0 2
F. Service/Function: TK A accumulator level.
A. Model No: 1152 DP4A92PB Serial No. 52543 B. Range Limits: 0-150" HO 2
- c. Range Settings: 0-25" H 0 2
D. Range of Process Variable Measured for Normal Conditions: 0-25" H 0 = 4-20 ma OUT.
Accident Conditions: 14" 2
- E. Values of Process Variable which could Produce Anomalous Indication: 210" H20 F. Service/Function: TK A accumulator level
~-y Power Station Rli!ponse to IE Bulletin 80-16 A. Model No: 1152 DP4A92PB Serial No. 69970 B. Range Limits: 0-150 11 H20 C. Range Settings: 0-25 11 H 0 2
D. Range of Process Variable Measured for Normal Conditions: 0-25" H 0 = 4-20 ma OUT.
2 Accident Conditions: 14" E. Values of Process Variable which could Produce Anomalous Indication: 210" H 0 2
F. Service/Function: TK B accumulator level A. ~1odel No. 1152 DP4A92PB Serial No. 52214 B. Range Limits: 0-150" HO 2
C. Range Settings: 0-25" H 0 2
D. Range of Process Variable Measured for Normal Conditions: 0-25 11 H o = 4-20 ma OUT.
Accident Conditions: 14" 2 E. Valu~s of Process Variable which could Produce Anomalous Indication: 210 11 H 0 2
F .. Service/Function: Accumulator TK B level A. Model No: 1152 DP4A92PB Serial No. 51984 B. Range Limits: 0-150" H 0 2
C. Range Settings: 0-25" H 0 2
D. Range of Process Variable Measured for Normal Conditions: 0-25" H o = 4-20 ma OUT.
Accident Conditions: 14" 2 E. Values of Process Variable which could Produce Anomalous Indication: 210 11 H 0 2
F. Service/Function: Accumulator TK C level
~--- - . _., __ -~----
Surr~ower Station Response to IE Bulletin 80-16 A. Model No: 1152 DP4A92PB Serial No. 115723 B. Range.Limits: 150" HO 2
C. Range Settings:
D. Range of Process Variable Measured for Normal Conditions: 12-37" Hi = 4-20 ma *our.*
Accident Conditions: 14 11 E. Values of Process Variable which could Produce Anomalous Indication: 210" H o 2
F. Service/Function: Accumulator TK A Level A. Model No. 1152 DP4A92PB Serial No. 52216 B. Range Limits: 0-150" H 0 2
C. Range Settings: 12-37" HO 2
D. Range of Process Variable Measured for Normal Conditions: 12-37" H o = 4-20 ma OUT.
f* Accident Conditions: 14" 2 E. Values of Process Variable which could Produce Anomalous Indication: 210' H o 2
F. Service/Function:. Accumulator TK A Level A. Model No: 1152 DP4A92PB Serial No. 51982 B. Range Limits: 0-150" H 0 2
C. Range Settings: 12-37" H 0 2
D. Range of Process Variable Measured for Normal Conditions: 12-37" H o = 4-20 ma OUT.
Accident Conditions: 14" 2 E. Values of Process Variable which could Produce Anomalous Indication: 210" H o 2
F. Service/Function: Accumulator TK B Level
S ~ Power Station R~onse to IE Bulletin 80-16 A. Model No: 1152 DP4A92PB Serial No. 52218 B. Range Limits: 0-150" HO 2
C. Range Settings: 12-37'" H b 2
D. Range of Process Variable Measured for Normal Conditions: 1.2-37" H 0 = .4-20 ma OUT.
2 Accident Cond.itions: 14" E. Values of Process Variable which could Produce Anomalous Indication: 210" H 0 2
F. Service/Function: Accumulator TK B Level A. Model No. 1152 DP4A92PB Serial No. 52541 B. Range Limits: 0-150" H 0 2
C. Range Settings: 12-37" HO 2
D. Range of Process Variable Measured for Normal Conditions: 12-37" H o = 4-20 ma OUT.
2 Accident Conditions: 14" E. Values of Process Variable which could Produce Anomalous Indication: 210 H o 2
F. Service/Function: Accumulator TK C Level A. Model No: 1152 DP4A92PB Serial No. 52542 B. Range Limits: 0-150" HO 2
C. Range Settings: 12-37" HO 2
D. Range of Process Variable Measured for Normal Conditions: 12-37" H 0 4-20 ma OUT.
2 Accident Conditions: 14" E. Values of Process Variable which could Produce Anomalous Indication: 210 11 H20 F. Service/Function: Accumulator TK C Level
Surr~wer Station Response to IE Bulletin 80-16 A. Model No: 1152 DP4A92PB Serial No. 89296 B. Range Limits: 0-150" H 0 2
C. Range Settings: 0-48" HO 2
D. Range of Process Variable Measured for Normal Conditions: 0-48" = 4-20 ma OUT.
Accident Conditions: 48" E. Values of Process Variable which could Produce Anomalous Indication: 210" H 0 2
F. Service/Function: Primary Drain Transfer TK Level A. Model No. 1152 DP4A92PB Serial No. 115725 B. Range Limits: 0-150" H 0 2
C. Range Settings: 0-100" HO 2
D. Range of Process Variable Measured for Normal Conditions: 0-100" H o = 4-20 ma OUT.
' Accident Conditions: 100" 2 E. Values of Process Variable which could Produce Anomalous Indication: 210" H o 2
F. Service/Function: . Reactor Coolant Pump Thermal Barrier HX OUT Flow A. Model No: 1152 DP4A92PB Serial No.52217 B. Range Limits: 0-150"
. H20 C. Range Settings: 0-25" H 0 2
D. Range of Process Variable Measured for Normal Conditions: 0-25" H o = 4-20 ma OUT.
2 Accident Conditions: 14" E. Values of Process Variable which could Produce Anomalous Indication: 210" H 0 2
F. Service/Function: Accumulator TK C Level
e S~y Power Station Re~ponse to IE Bulletin 80-16 A. Model No: 1152 DP4A22DP Serial No. 48968 B. Range Limits: 0-150 11 HO 2
C. Range Settings: 0-48 11 HO 2
D. Range of Process Variable Measured for Normal Conditions: 0-48" H 0 = 4-20 ma OUT.
Accident Conditions: 48 11 2 E. Values of Process Variable which could Produce Anomalous Indication: 210" H o 2
F. Service/Function: Primary Drains Transfer TK Level