Forwards Functional Description of Upgraded Meteorological Facilities Required by NUREG-0654,App a & NUREG-0737,Item III.A.2.Sys Will Be Fully Operational,Pending Completion of NUREG-0696 RequirementsML18139B431 |
Person / Time |
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Site: |
Surry, North Anna |
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Issue date: |
07/02/1981 |
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From: |
Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
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To: |
Harold Denton, Eisenhut D Office of Nuclear Reactor Regulation |
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References |
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RTR-NUREG-0654, RTR-NUREG-0696, RTR-NUREG-0737, RTR-NUREG-654, RTR-NUREG-696, RTR-NUREG-737, TASK-3.A.2.1, TASK-3.A.2.2, TASK-TM 405, NUDOCS 8107070159 |
Download: ML18139B431 (15) |
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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 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 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 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 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 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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{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,, VIRGINIA 23261 July 2, 1981 R. IJ. LEA.SBUBO V:rc:,s PllBSJDENT NUCLJ:lAJ< 0P1:lRATIONS Mr. Harold R. Denton, Director Serial No. 405 Office of Nuclear Reactor Regulation NO/LEN:ms Attn: Mr. Darrell G. Eisenhut, Director Docket Nos. 50-280, 50-281 Division of Licensing 50-338, 50-339 U. S. Nuclear Regulatory Commission License Nos. DPR-32, DPR-37 Washington, D. C. 20555 NPF-4, NPF-7 Gentlemen:
FUNCTIONAL DESCRIPTION OF THE UPGRADED METEOROLOGICAL FACILITIES NORTH ANNA AND SURRY POWER STATIONS Attached is Vepco's Functional Description of the Upgraded Meterological Facilities for North Anna and Surry Power Stations. This submittal is required by NUREG 0654 Appendix 2 and NUREG 0737 Item III.A.2.
Because data obtained from the Meterological Facilities must input to the Emergency Response Facilities (NUREG 0696), Vepco's Meterological System will not be fully operable until the requirements of NUREG 0696 are complete. We are presently attempting to complete the required construction activities to have data available in the Control Room by August 1, 1981. However, our recent site activities have been dedicated to returning two units to service and this may delay the completion until August 21, 1981.
If you have any questions or concerns, please contact us.
Very tf~~/prs ,/1 .*
/l!J fea,,-{ur R.H. Leasburg Vice President Nuclear Operations Attachment s1070701s9 aro7*02 -
PDR ADOCK 05000280 F PDR
e e VEPCO FUNCTIONAL DESCRIPTION OF THE UPGRADED METEOROLOGICAL FACILITIES PROVIDED TO MEET NUREG 0654 APPENDIX 2, "METEOROLOGICAL CRITERIA FOR EMERGENCY PREPAREDNESS AT OPERATING NUCLEAR POWER PLANTS" Introduction 10CFR Part 50.47 requires that each station's Emergency Plan shall provide
"(A)dequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition *** "
In order to meet this requirement and in the interest of following the criteria set forth in tt.Jreg 0654 Appendix 2, the Vepco program for installing upgraded meteorological facilities at its nuclear stations was developed. The upgraded meteorological program utilizes a great deal of the equipment and software to be installed as part of the Vepco nuclear station's emergency response facilities. This equipment and software was described in greater detail in Vepco's recent submittal to the NRC, "Vepco Emergency Response Facilities, tt.Jreg-0696 Implementation Plan, Revision One: .l.Jne 1, 1981, Surry Power Station, North Anna Power Station."
The basic functions provided by the Vepco upgraded meteorological program are:
- 1. A capability for making meteorological measurements.
- 2. A capability for making real-time predictions of the atmospheric effluent transport and diffusion.
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e e
- 3. A capability for remote interrogation of the atmospheric measurements and predictions by appropiate organizations.
Meteorological Measurements 10CFR Part 50 Appendix E requires that emergency facilities and equipment shall include "(E)quipment for determining the magnitude of and for continuously assessing the impact of the release of radioactive materials to the environment." In order to address this requirement, the Vepco nuclear stations will receive meteorological measurements from primary and backup systems.
A primary meteorological measurements system is supplied for both operating nuclear sites. Proposed Revision 1 to Regulatory Guide 1.23 was used for guidance in designing the primary meteorological measurements system for the sites.
North Anna Primary System The primary meteorological monitoring site at North Anna consists of a Rohn Model 80, guyed, 160-foot tower located approximately 1900 feet East of the Unit 1 reactor containment. Sensors are located at the lo-meter, 48-meter, and ground levels. Wind speed, wind direction, sigma (theta),
ambient temperature, one-half of differential temperature, and dew point temperature are measured at the lo-meter elevation. Wind speed, wind direction, sigma (theta), and one-half of differential temperature are measured at the 48-meter elevation. Precipitation is monitored at the ground level. Signal cables are routed through conduit from each location W/4669/2
e into the instrument shelter at the base of the tower. Inside the shelter, the signals are. routed to the appropriate signal-conditioning equipment whose outputs go to: 1) strip chart recorders; 2) digital data recorders; and 3) an interface with the intelligent remote multiplex system.
Table 1 shows a detailed list of the sensors installed on the North Anna primary meteorological tower.
Surry Primary System The primary meteorological monitoring at Surry site consists of a Rohn Model 90, guyed, 150-foot tower located approximately 4500 feet southeast of the Unit 1 reactor containment. Sensors are located at the 10-meter, 45-meter, and ground levels. Wind speed, wind direction, sigma (theta),
ambient temperature (which is also one-half of differential temperature),
and dew point temperature are measured at the lo-meter elevation. Wind speed, wind direction, sigma (theta), and one-half of differential temperature are measured at the 45-meter elevation. Precipitation is monitored at the ground level. Signal cables are routed through conduit from each location into the instrument shelter at the base of the tower.
Inside the shelter, the signals are routed to the appropriate signal-conditioning equipment whose outputs go to: 1) strip chart recorders; 2) digital data recorders and 3) an interface with the intelligent remote multiplexer system.
Table 2 shows a detailed list of the sensors installed on the Surry primary meteorological tower.
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e e A backup meteorological measurements system is supplied also for both operating nuclear sites. Again, proposed Revision 1 to Regulatory Guide 1.23 was used for guidance in designing the backup meteorological measurements system for both sites.
North Anna Backup System The North Anna backup meteorological monitoring site consists of a Rohn Model 25, free-standing, lo-meter tower. This tower is located approximately 1300 feet Northeast of the Unit 1 reactor containment and serves as the back-up meteorological monitoring site. A sensor at the top of the mast monitors wind speed, wind direction, and sigma (theta). The signal path, instrument shelter and data recording are identical to those described at the primary tower. All three parameters are interfaced to the intelligent remote multiplexing system equipment.
Table 1 shows a detailed list of the sensors installed on the North Anna backup meteorological tower.
SUrry Backup System The Surry backup meteorological monitoring site consists of a Rohn Model 25, free-standing, IO-meter tower. This tower is located approximately 3000 feet east-southeast of the Unit 1 reactor containment and serves as the back-up meteorological monitoring site. A sensor at the top of the mast monitors wind speed, wind direction, and sigma (theta). The signal cables are run through conduit into an equipment shelter at the site. The signals are routed to signal-conditioning equipment, and the resulting signals are fed to: 1) strip chart recorders; 2) digital data recording equipment; and 3) an interface with the intelligent remote multiplexing system.
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e e Table 2 shows a detailed list of the sensors installed on the' Surry backup meteorological tower.
All data from both site's primary and backup meteorological towers is sent to the station's control rooms as 4-20ma current signals over individual shielded pair cables. Once there, all parameters are collected by the Nureg 0696 Emergency Response Facility (ERF) data system via the intelligent remote multiplex system. Each station's ERF data system is functionally redundant and meets the overall 99% availability requirement in f\lJreg 0696. *(Seethe June 1, 1981 Vepco submittal on Nureg 0696 Emergency Response Facilities for further information). Once collected by the multiplex system, these parameters are placed in the ERF data base thus making all the site meteorological field data available for display in the station's Technical Support Center (TSC) or the Vepco central office Emergency Operations Facility (EDF). Certain input sensor information in the control rooms are also hardwired for display on the main control room meteorological panels. Tables 3 and 4 list each meteorological input parameter and its transmitted location.
Atmospheric Transport and Diffusion Assessment A near real-time, site specific atmospheric transport and diffusion model for assessing accidental airborne radioactive releases will be available for use upon installation and operation of t'l.lreg 0696 Emergency Response Facility data communications processor hardware and software on the schedule as presented in "Vepco Emergency Response Facilities, NUREG-0696 Implementation Plan, Revision one: June 1, 1981, Surry Power Station, North Anna Power Station, Virginia Electric and Power Company."
~ --~ ~
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e e Development of the Class A model will consider Nuclear Regulatory Commission guidance information, expected to be available by October, 1981, for reactor licensees concerning the meteorological elements to be considered in the development of an emergency plan and in the application of the Class A model for varying terrain environments. Development of the Class B model will depend upon the Nuclear Regulatory Commission's reappraisal of Class B capability.
The Class A model will use actual 15 minute average meteorological field data obtained from the station's meteorological system as discussed in the previous section. The Class A model will provide relative concentrations (X/Q) and transit times within the plume exposure EPZ. Atmospheric diffusion rates will be based on atmospheric stability as a function of site-specific conditions.
Source characteristics (release mode, and building complex influence) will be factored into the model. The output from the Class A model will include plume dimensions and position, and the location, magnitude, and arrival time of (1) the peak relative concentration and (2) the relative concentrations at approximate locations.
The calculated output of the Class A model will be placed in each operating site's ERF data base for display in the station's TSC and in the central office EDF. The exact parameters to be calculated and provided to each station's ERF data base will be determined following receipt of additional guidance on the Class A model from the NRC.
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e Remote Interrogation In order to meet the requirement in 10CFR Part 50 that "(P)rovisions for communications by the licensee with the NRC Headquarters and the appropriate
- NRC Regional Office Operations Center from the nuclear power reactor control room, the onsite technical support center, and the near-site emergency operations facility" and " *** among the nuclear facility, the principle state and local emergency operations centers *** ", each operating nuclear site's ERF data system will have the capability of being remotely interrogated.
As previously mentioned, the field input meteorological data as well as the Class A model output data will be available in each station's ERF data base.
Therefore, any or all of this data can be made available for remote interrogation. Any knowledgable party with an acceptable terminal* and modem will be capable of dialing into the applicable computer port in each station's ERF system and upon passing a security check will receive printouts of the required data. Two dedicated ports (one primary, one backup) will be provided for the NRC's use with additional ports provided for state and local emergency operations centers as necessary. The formats of the reports will be determined in the future using Regulatory Guide 1.23 (final version) as guidance. Documentation for procedures to access and use the remote interrogation subsystem will be provided to the emergency response organizations that require them and the NRC and will be available in each station's control room and TSC as well as the Vepco central office EDF.
*An acceptable terminal is an 1200 baud 80 column ASCII terminal with a RS-232-C interface.
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TABLE*l NORTH ANNA METEOROLOGICAL SYSTEM SENSORS MANUFACTURER MODEL NUMBER PARAMETER MEASUREMENT METHOD ACCURACY Meteorology! 1074-22 1) Wind speed 1) Light Chopper (variable .:t.0-25 mph Research, Inc. frequency)
Frequency to voltage .:!:_0.25 mph circuit card
- 2) Wind Direction 2)a) 0-540 Potentiometer +2.5° (strip chart recording and telemetry)
Resistance to voltage circuit card b) sine/cosine potentiometer (digital recording)
Dual buffer amplifier +1.6° card
- 3) Sigma (theta) 3) Sigma azimuth amplifier Linearity= .:!:_0.5%
circuit card (input F .S.,
from 540 output) Stability= .:t.2% F.S.
Root Sum of Squares (RSS) = +0.35 mph, +2.9% (540), +3.90 (sine/cosine), +0.90 sigma Rosemount, Inc. 104-ABG-l Sensor, upper 1/2 Platinum +O.l30F Delta T RTD 104-ABG-2 Sensor, lower 1/2 Platinum +0.130F Delta T, RTD e Sensor, Ambient T Platinum RTD +0.130F 442 ARDA Delta T Resistance to maDC +0.1% = 0.0250F Transmitter circuit 442 ARPA Ambient T R~sistance to maDC +0.1% = +o.1a°F transmitter circuit RSS = +0.1B6°F Delta T (+o.103oc), +o.220F Ambient (+o.12oc) lMRl 1074-22 sensors are used at all three locations (48-meter and IO-meter primary tower elevations and IO-meter backup tower elevation)
TABLE 1 (can't)
MANUFACTURER MODEL NUMBER PARAMETER MEASUREMENT METI-OD ACCURACY EG&G 110 Dew Point Chilled mirror maintained +Q.SOF Temperature at dew point temperature Meteorology 302 Raingauge with Tipping bucket +1% at 3"/hr Research, Inc. heater +5% at 10"/hr
TABLE 2 SURRY METEOROLOGICAL SYSTEM SENSORS MANUFACT~ER MODEL NUMBER PARAMETER MEASUREMENT METI-OD ACCURACY Belfort Instrument 5-405 Rainfall Tipping bucket +1% at l"/hr.
Company +4% at 3"/hr
+6% at 6"/hr EG & G 110 Dew point Chilled mirror maintained +0.50F temperature at dew point temperature Meteorology 1074-22 1) Wind Speed 1) Light chopper (variable +0.25 mph Research, Inc. frequency)
Frequency to voltage +0.25 mph circuit card Root sum of squares (RSS) = .:t_0.35 mph
- 2) Wind Direction 2)a) 0-540 potentiometer +2.50 (strip chart recording and telemetry)
Resistance to voltage +1.40 circuit card RSS =
b) Sine/cosine potentiometer (digital recording)
Dual buffer amplifier +1.60 circuit card
- 3) Sigma (theta)l RSS =
- 3) Sigma azimuth amplifier Linearity= +0.5%
e--
circuit card (input from F.S = +0.2250 540 output) Stability=
+2% F.S. = +Q.90 RSS = +0.90 lTo be added to primary tower.
TABLE 2 (can't)
MANUFACTURER MODEL NUMBER PARAMETER MEASUREMENT METI-OD ACCURACY Rosemount, Inc. 104mb 12 ADCA Temperature Platinum RTD Sensors 2 Endevco 4473.2 RTD Signal Resistance to millivolt +0.120F {T)
Conditioner conversion +o.0120F (Delta T)
RSS (Ambient T) = +0.180F RSS (Delta T) = +0.180F 210-meter sensor is for Ambient T and one-half Delta T W/4669/11
e TABLE 3 PRIMARY TOWER PARAMETERS Transmitted Locations ERF control Remote Database Room Interrogation
- 1. Wind Direction (Upper) X X X
- 2. Wind Speed (Upper) X X X
- 3. Sigma Theta (Upper) X X
- 4. Wind Direction (Lower) X X X
- s. Wind Speed (Lower) X X X
- 6. Sigma Theta (Lower) X X
- 7. Ambient Temperature (Lower) X X X
- 9. Dewpoint Temperature (Lower) X X
- 9. Delta Ambient Temperature X X X (Upper-Lower)
- 10. Precipitation X X
- 11. Solar Radiation (l'brth Anna only) X X Notes:
- 1) Table applies to both North Anna and Surry
- 2) All parameters going to the ERF database will be available for printout in the TSC and EOF. The control room parameters are hardwired.
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** TABLE 3 PRIMARY TOWER PARAMETERS Transmitted Locations ERF Control Remote Database Room Interrogation
- 1. Wind Direction (Upper) X X X
- 2. Wind Speed (Upper) X X X
- 3. Sigma Theta (Upper) X X
- 4. Ambient Temperature (Upper, Calculated) X X
- 5. Wind Direction (Lower) X X X
- 6. Wind Speed (Lower) X X X
- 7. Sigma Theta (Lower) X X
- 8. Ambient Temperature (Lower) X X X
- 9. Dewpoint Temperature (Lower) X X
- 10. Delta Ambient Temperature X X X (Upper-Lower)
- 11. Precipitation X X Notes:
- 1) Table applies to both North Anna and Surry
- 2) All parameters going to the ERF database will be available for printout in the TSC and EDF. The control room parameters are hardwired.
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i
BACKUP TOWER PARAMETERS Transmitted Locations ERF Control Remote Database Room Interrogation
- 1. Wind Direction X X X
- 2. Wind Speed X X X
- 3. Sigma Theta X X X Notes:
- 1) Table applies to both North Anna and Surry
- 2) All parameters going to the ERF database will be available for printout in the TSC and EDF. The control room parameters are hardwired.
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