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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K1051999-10-19019 October 1999 Ack Receipt of Ltr Dtd 990707,which Transmitted Rev 29 to Callaway Plant Physical Security Plan,Under Provisions of 10CFR50.54(p).Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required 05000482/LER-1999-002, Forwards LER 99-002-00,re Identification of Surveillance Performed in Modes Other than Those Required by TS SR 4.6.3.2.a.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-002-00,re Identification of Surveillance Performed in Modes Other than Those Required by TS SR 4.6.3.2.a.Commitments Made by Util Are Encl 05000482/LER-1994-014, Forwards LER 94-014-00 Re Util Identification of Missed Surveillance Required by TS Prior to Changing Modes.List of Commitments Made by Licensee,Encl1999-10-15015 October 1999 Forwards LER 94-014-00 Re Util Identification of Missed Surveillance Required by TS Prior to Changing Modes.List of Commitments Made by Licensee,Encl ML20217F7481999-10-14014 October 1999 Informs That Based on Approval of Core Assessment Damage Guidance in WCAP-14696,rev 1 for Westinghouse Nuclear Power Plants,Licensee May Use WCAP-14696,rev 1 at Wolf Creek Generating Station ML20217G2071999-10-14014 October 1999 Forwards Insp Rept 50-483/99-10 on 990913-16.No Violations Noted.Insp Was to Review Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise ML20217F8701999-10-13013 October 1999 Provides Summary of Meeting on 991007 with Representatives of Wolf Creek Nuclear Station in Burlington,Kansas Re Status of Licensee Radiation Protection Program.List of Meeting Attendees & Licensee Presentation Encl ML20217C1721999-10-0707 October 1999 Forwards Insp Rept 50-482/99-09 on 990830-0903.No Violations Noted.Purpose of Insp to Perform Routine Operational Status Insp of Emergency Preparedness Program & to Resolve Questions Re Revised Emergency Plan ML20217B5901999-10-0505 October 1999 Informs That Staff Concludes That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Callaway Plant,Unit 1 ML20217B5711999-10-0505 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & Uec Responses for Callaway NPP Unit 1 ,990224 & 990628.Informs That Staff Reviewed Responses & Concluded That All Requested Info for GL 98-01 Provided ML20217A4881999-09-29029 September 1999 Forwards Changes to Plant Data Point Library,Iaw 10CFR50,App E,Section VI.3.a.ERDS Point Affected Is RDS0001 ML20216H9291999-09-29029 September 1999 Informs That Licensee Responses to GL 97-06, Degradation of Steam Generator Internals Acceptable & Did Not Identify Any New Concerns with Condition of SG Intervals at Plant ML20212G1681999-09-24024 September 1999 Notifies NRC of Change in Status of Licensed Individual at Plant,Per 10CFR50.74.RL Acree Holds License OP-42654 at Plant,But Has Been Permanently Reassigned from Position for Which Plant Has Certified Need for RO License ML20216F9591999-09-22022 September 1999 Forwards Withdrawal of Amend Request Re Ultimate Heat Sink Temp for Wolf Creek Generating Station ML20212G0221999-09-22022 September 1999 Forwards Insp Rept 50-483/99-11 on 990812-20.No Violations Noted.Team Found,Weakness in flow-accelerated Corrosion Monitoring Program Resulted in No Previous Insp of Pipe Segment Which Failed ML20212G5641999-09-20020 September 1999 Forwards Insp Rept 50-482/99-13 on 990725-0904.Three Violations Being Treated as Noncited Violations 05000482/LER-1999-011, Forwards LER 99-011-00 Re Identification of Missed Surveillance Due to Exceeding Flow Rate Specified in TS for Ccps.List of Util Commitments Contained in Attachment I1999-09-17017 September 1999 Forwards LER 99-011-00 Re Identification of Missed Surveillance Due to Exceeding Flow Rate Specified in TS for Ccps.List of Util Commitments Contained in Attachment I ML20212D9381999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of WCGS on 990818.Areas of EP & Engineering Warranted Increase in NRC Action.Nrc Plan to Conduct Add Insp Beyond Core Insp Program Over Next 7 Months to Address Listed Questions 05000482/LER-1999-010, Forwards LER 99-010-00,re Failure to Correctly Perform TS Surveillance 4.3.3.6.Encl Identifies Actions Committed to by Util1999-09-16016 September 1999 Forwards LER 99-010-00,re Failure to Correctly Perform TS Surveillance 4.3.3.6.Encl Identifies Actions Committed to by Util ML20212D9341999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Callaway Plant.In Area of Ep,C/As Taken in Response to Problems Identified During Previous Exercises Warrant More in-dept Review.Details of Insp Plan Through March 2000 Encl ML20217D5791999-09-15015 September 1999 Provides Formal Documentation of Reviews & Discussions Re Technical Ltr Rept for Proprietary Info.Review of Ltr Was Discussed in Telcon & Via e-mail Messages. Summary of Telcons as Documented on 990708,included ML20212C9211999-09-15015 September 1999 Forwards NRC Form 536, Operating Licensing Examination Data, in Response to NRC Administrative Ltr 99-03 05000482/LER-1999-006, Forwards LER 99-006-01,re Identification of Failure to Enter LCO for TS 3.6.1.1 While Taking Containment Atmosphere Samples During Power Operation.Commitments Made by Util Are Encl1999-09-15015 September 1999 Forwards LER 99-006-01,re Identification of Failure to Enter LCO for TS 3.6.1.1 While Taking Containment Atmosphere Samples During Power Operation.Commitments Made by Util Are Encl ML20216F1641999-09-14014 September 1999 Forwards Insp Rept 50-482/99-12 on 990816-20.No Violation Noted.Determined That Solid Radwaste Mgt & Radioactive Matls Transportation Programs Were Properly Implemented ML20212A4921999-09-13013 September 1999 Forwards Insp Rept 50-483/99-08 on 990725-0904.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20212B1521999-09-10010 September 1999 Forwards Insp Rept 50-483/99-07 on 990809-13.No Violations Noted.Inspectors Used Annual Licensed Operator Requalification Exams to Assess Licensed Operator Performance ML20212A4701999-09-10010 September 1999 Rssponds to NRC 990709 RAI Re Util Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection Iwe. Acceptance Criteria for Liner Plate Pressure Boundary Thickness Will Be Limited to 10% Nominal Thinning 05000482/LER-1999-009, Forwards LER 99-009-00 Re Util Identification of Fire Suppression Issue Affecting Safe Shutdown Components. Attachment I Identifies Actions Committed to by Licensee in Encl LER1999-09-10010 September 1999 Forwards LER 99-009-00 Re Util Identification of Fire Suppression Issue Affecting Safe Shutdown Components. Attachment I Identifies Actions Committed to by Licensee in Encl LER ML20212A5651999-09-10010 September 1999 Informs of Completion of Review of & Encl Objectives for Wolf Creek Generating Station 1999 Emergency Preparedness Exercise Scheduled for 991117.Determined Exercise Objectives Appropriate to Meet EP Requirements ML20211M7151999-09-0303 September 1999 Forwards Changes to Wolf Creek Generating Station Data Point Library.Emergency Response Data Sys Points Affected Are EJL0007 & EJL0008 05000482/LER-1999-008, Forwards LER 99-008-00,re Efsa at Plant.Attachment I Identifies Actions Committed to by Licensee in LER1999-09-0303 September 1999 Forwards LER 99-008-00,re Efsa at Plant.Attachment I Identifies Actions Committed to by Licensee in LER ML20211K8301999-09-0202 September 1999 Forwards marked-up TS Page Deleting Inequality Signs from Trip Setpoints in SR 3.3.5.3 & Reflecting Info on Calibr Tolerance Band,Per 990708 Application to Amend License NPF-42 ML20211N0081999-09-0202 September 1999 Informs That NRC Staff Has Reviewed Submittals & Concluded Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves ML20211N0321999-09-0202 September 1999 Forwards SE Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20211K1941999-08-31031 August 1999 Forwards Rev 31 to WCGS Physical Security Plan,Safeguards Contingency Plan & Training & Qualification Plan,Iaw 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20211H1491999-08-26026 August 1999 Forwards Insp Rept 50-482/99-16 on 990809-13.No Violations Noted.Insp Focused on Low as Is Reasonably Achievable Program,Training Program for Contract Radiation Protection Personnel & Radiation Protection QA Program ML20211A8581999-08-18018 August 1999 Forwards Insp Rept 50-482/99-08 on 990316-0724.One Violation Being Treated as Noncited Violation ML20211B0241999-08-18018 August 1999 Ack Receipt of Ltr Dtd 990714,transmitting Scenario for Licensee Upcoming Biennial Exercise.Based on Review,Nrc Determined That Exercise Scenario Sufficient to Meet Emergency Plan Requirements & Exercise Objectives ML20211G2201999-08-17017 August 1999 Forwards Exam Rept 50-482/99-301 on 990726-29.Exam Evaluated Six Applicants for SO Licenses & Three Applicants for RO Licenses ML20210U0991999-08-13013 August 1999 Forwards Insp Rept 50-482/99-11 on 990712-16.No Violations Noted.Insp Was to Review Radiological Environ Monitoring Program ML20210U9751999-08-13013 August 1999 Informs That Licensee Identified That Answer Key for One Question on 990720 Written Exam & Event Classification for on Job Performance Measure Required Mod.Description & Justification for Proposed Mod,Including Technical Ref,Encl ML20210T9121999-08-13013 August 1999 Forwards Insp Rept 50-483/99-06 on 990613-0724.One Severity Level 4 Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20210R7241999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for 990101-990630,IAW 10CFR26.71(d) ML20210R5621999-08-12012 August 1999 Forwards Monthly Operating Rept for July 1999 for Wolf Creek Generating Station,Per TS 6.9.1.8 & GL 97-02.Revised Repts for Apr,May & June 1999,correcting Number of Hours Reactor Critical,Encl ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ULNRC-04085, Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power1999-08-11011 August 1999 Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power ML20210P0371999-08-10010 August 1999 Forwards SE Granting Licensee 980710 Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code for Second 10-year Interval ISI at Plant,Unit 1 ML20210P7491999-08-0909 August 1999 Ack Receipt of ,Which Transmitted Wolf Creek Radiological Emergency Response Plan 06-002,Rev 0,under Provisions of 10CFR50,App E,Section V ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210N0061999-08-0303 August 1999 Forwards Response to NRC 990401 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Motor-Operated Gate Valves ULNRC-04079, Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal 1999-09-03
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEAR05000482/LER-1994-014, Forwards LER 94-014-00 Re Util Identification of Missed Surveillance Required by TS Prior to Changing Modes.List of Commitments Made by Licensee,Encl1999-10-15015 October 1999 Forwards LER 94-014-00 Re Util Identification of Missed Surveillance Required by TS Prior to Changing Modes.List of Commitments Made by Licensee,Encl 05000482/LER-1999-002, Forwards LER 99-002-00,re Identification of Surveillance Performed in Modes Other than Those Required by TS SR 4.6.3.2.a.Commitments Made by Util Are Encl1999-10-15015 October 1999 Forwards LER 99-002-00,re Identification of Surveillance Performed in Modes Other than Those Required by TS SR 4.6.3.2.a.Commitments Made by Util Are Encl ML20217A4881999-09-29029 September 1999 Forwards Changes to Plant Data Point Library,Iaw 10CFR50,App E,Section VI.3.a.ERDS Point Affected Is RDS0001 ML20212G1681999-09-24024 September 1999 Notifies NRC of Change in Status of Licensed Individual at Plant,Per 10CFR50.74.RL Acree Holds License OP-42654 at Plant,But Has Been Permanently Reassigned from Position for Which Plant Has Certified Need for RO License 05000482/LER-1999-011, Forwards LER 99-011-00 Re Identification of Missed Surveillance Due to Exceeding Flow Rate Specified in TS for Ccps.List of Util Commitments Contained in Attachment I1999-09-17017 September 1999 Forwards LER 99-011-00 Re Identification of Missed Surveillance Due to Exceeding Flow Rate Specified in TS for Ccps.List of Util Commitments Contained in Attachment I 05000482/LER-1999-010, Forwards LER 99-010-00,re Failure to Correctly Perform TS Surveillance 4.3.3.6.Encl Identifies Actions Committed to by Util1999-09-16016 September 1999 Forwards LER 99-010-00,re Failure to Correctly Perform TS Surveillance 4.3.3.6.Encl Identifies Actions Committed to by Util ML20212C9211999-09-15015 September 1999 Forwards NRC Form 536, Operating Licensing Examination Data, in Response to NRC Administrative Ltr 99-03 05000482/LER-1999-006, Forwards LER 99-006-01,re Identification of Failure to Enter LCO for TS 3.6.1.1 While Taking Containment Atmosphere Samples During Power Operation.Commitments Made by Util Are Encl1999-09-15015 September 1999 Forwards LER 99-006-01,re Identification of Failure to Enter LCO for TS 3.6.1.1 While Taking Containment Atmosphere Samples During Power Operation.Commitments Made by Util Are Encl ML20217D5791999-09-15015 September 1999 Provides Formal Documentation of Reviews & Discussions Re Technical Ltr Rept for Proprietary Info.Review of Ltr Was Discussed in Telcon & Via e-mail Messages. Summary of Telcons as Documented on 990708,included ML20212A4701999-09-10010 September 1999 Rssponds to NRC 990709 RAI Re Util Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection Iwe. Acceptance Criteria for Liner Plate Pressure Boundary Thickness Will Be Limited to 10% Nominal Thinning 05000482/LER-1999-009, Forwards LER 99-009-00 Re Util Identification of Fire Suppression Issue Affecting Safe Shutdown Components. Attachment I Identifies Actions Committed to by Licensee in Encl LER1999-09-10010 September 1999 Forwards LER 99-009-00 Re Util Identification of Fire Suppression Issue Affecting Safe Shutdown Components. Attachment I Identifies Actions Committed to by Licensee in Encl LER ML20211M7151999-09-0303 September 1999 Forwards Changes to Wolf Creek Generating Station Data Point Library.Emergency Response Data Sys Points Affected Are EJL0007 & EJL0008 05000482/LER-1999-008, Forwards LER 99-008-00,re Efsa at Plant.Attachment I Identifies Actions Committed to by Licensee in LER1999-09-0303 September 1999 Forwards LER 99-008-00,re Efsa at Plant.Attachment I Identifies Actions Committed to by Licensee in LER ML20211K8301999-09-0202 September 1999 Forwards marked-up TS Page Deleting Inequality Signs from Trip Setpoints in SR 3.3.5.3 & Reflecting Info on Calibr Tolerance Band,Per 990708 Application to Amend License NPF-42 ML20211K1941999-08-31031 August 1999 Forwards Rev 31 to WCGS Physical Security Plan,Safeguards Contingency Plan & Training & Qualification Plan,Iaw 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20210U9751999-08-13013 August 1999 Informs That Licensee Identified That Answer Key for One Question on 990720 Written Exam & Event Classification for on Job Performance Measure Required Mod.Description & Justification for Proposed Mod,Including Technical Ref,Encl ML20210R5621999-08-12012 August 1999 Forwards Monthly Operating Rept for July 1999 for Wolf Creek Generating Station,Per TS 6.9.1.8 & GL 97-02.Revised Repts for Apr,May & June 1999,correcting Number of Hours Reactor Critical,Encl ML20210R7241999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for 990101-990630,IAW 10CFR26.71(d) ULNRC-04085, Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power1999-08-11011 August 1999 Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power ML20210N0061999-08-0303 August 1999 Forwards Response to NRC 990401 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Motor-Operated Gate Valves ULNRC-04079, Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20210J1371999-07-29029 July 1999 Requests NRC Approval of Methodology for Determining RCS Pressure & Temp & Overpressure Mitigation Sys PORV Limits. Attachment I Provides Proposed Changes to Improved TS ML20210H2551999-07-29029 July 1999 Provides 180-day Response to NRC Request for Info Re GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ULNRC-04076, Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs1999-07-28028 July 1999 Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs ULNRC-04075, Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves1999-07-28028 July 1999 Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves A93443, Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves1999-07-28028 July 1999 Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves ULNRC-04070, Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power1999-07-27027 July 1999 Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power ULNRC-04071, Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-021999-07-27027 July 1999 Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-02 05000483/LER-1998-008, Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved1999-07-27027 July 1999 Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved ML20210F5931999-07-27027 July 1999 Forwards semi-annual Fitness for Duty Performance Data Rept for Wcnoc,Per 10CFR26.71(d).Rept Covers Period of 990101- 0630 ML20210F5881999-07-23023 July 1999 Submits Response to Administrative Ltr 99-02, Operator Reactor Licensing Action Estimates, ML20212A3291999-07-15015 July 1999 Forwards Scenario Manual Containing Description of Callaway Plant 1999 Biennial Emergency Response Plan Exercise to Be Conducted 990914.Correspondence to Satisfy 60-day Submittal Requirement ML20209H0751999-07-14014 July 1999 Forwards Monthly Operating Rept for June 1999 for Wolf Creek Generating Station,Per TS 6.9.1.8 & GL 97-02.Max Dependable Capacity Has Been Updated from 1163 to 1170,as Determined by Calculations Based on Capacity Test Results of July 1998 ML20209H0441999-07-14014 July 1999 Forwards Response to NRC 990326 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. Summary of Util Commitments Provided in Attachment 2 ML20209G9871999-07-14014 July 1999 Informs of Changes Affecting Wolf Creek Security Plan,Per 10CFR50.54(p)(2).Encl Provides Description of Changes & Justification for Changes ML20209F3471999-07-0909 July 1999 Forwards Response to NRC 990624 RAI to Complete NRC Review of Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection IWE ML20209E0611999-07-0808 July 1999 Forwards Addl Pages to Rev 12 of USAR & Commitment Changes, Inadvertently Omitted from 990311 Submittal ML20209H2471999-07-0707 July 1999 Forwards Rev 29 to Physical Security Plan,Per 10CFR50.54(p). Rev Withheld,Per 10CFR73.21 ML20209C6031999-07-0606 July 1999 Provides Applicants View as Result of 990618 Memo & Order Directing Parties to Address Proper Disposition of Existing Antitrust License Condition Attached to OL for Facility Due to Planned Changes in Ownership of Facility.With Svc List ML20196K8231999-07-0606 July 1999 Submits Kansas Electric Power Cooperative,Inc Ltr Pursuant to Commission Direction in Memo & Order CLI-99-19.Addresses Disposition of Existing Antitrust Conditions Attached to License for Wolf Creek Unit 1 Re Proposed License Transfer ML20209B7131999-07-0101 July 1999 Submits Response to NRC Request for Info Re GL 98-01, Suppl 1, Y2K Readiness of Computer Sys at Npps. Response on Status of Facility Y2K Readiness Was Requested by 990701.Disclosure Encl ML20209B5151999-06-29029 June 1999 Informs That Util Completed Analyses & Modifications to Address Items Discussed in GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20209C0171999-06-28028 June 1999 Forwards Special Rept 99-01 Re Fifteenth Year Inservice Containment Bldg Tendon Surveillance Failure.Observed Voids in Sheathing Filler Grease Do Not Indicate Degradation of post-tensioning Sys,Based on Encl Evaluation ML20209B6851999-06-28028 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Nuclear Power Plants. Disclosure Rept Encl ML20196G9681999-06-22022 June 1999 Informs NRC That BC Ryan Will Be Leaving Ks State Univ for Position with Wolf Creek Nuclear Operating Corp,Effective 990701 ML20196G5621999-06-21021 June 1999 Informs NRC of Implementation of Amend 132 to Callaway License NPF-30 to Allows Installation of Electrosleeves for Steam Generator Tube Repair for Two Cycles Following Installation of First Electrosleeve ML20212J2441999-06-18018 June 1999 Submits Request for Alternate Exam Requirements for Plant Re ISI Program Plan.Plant Does Not Torque Bolted Connections to Stress Values Greater than 100 Ksi 05000482/LER-1999-007, Forwards LER 99-007-00,re Condition in Which Wolf Creek Generating Station TS 3.3.2 Was Not Met.Commitments Made by Util Also Encl1999-06-18018 June 1999 Forwards LER 99-007-00,re Condition in Which Wolf Creek Generating Station TS 3.3.2 Was Not Met.Commitments Made by Util Also Encl ML20196A0251999-06-17017 June 1999 Requests That Written Exams for Reactor Operator & SRO for Plant Be Administered Beginning Wk of 990719 & Followed by Operating Exam During Wk of 990726 to Personnel Listed in Attachment.Proprietary Info Encl.Proprietary Info Withheld ML20195K0641999-06-15015 June 1999 Forwards MOR for May 1999 for Wolf Creek Generating Station & Corrected Page 2 of 2 of Apr 1999 Mor,Adding That Unit Entered Intomode 5 for Restart During Month of Apr & Correcting Shutdown Duration Hours from 672 to 671 1999-09-03
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML19325E9001989-10-19019 October 1989 Forwards Text of Info Communicated to All Util W/ Westinghouse NSSS Design on Pressurizer Safety Valve Set Pressure Deviation Info Request Response ML19327A8441989-10-11011 October 1989 Forwards Pleadings,Motions & Orders Filed in Alchemie Reorganization Action.Alchemie Currently Preparing Reorganization Plan Which Will Serve as Framework for Future Company Business Activities ML19327B2491989-10-0606 October 1989 Forwards Justification for Extension of Applicability of 890807 SER Re Acceptance of BAW-10175, Rod Exchange Methodology Topical Rept. ML19327A8511989-10-0505 October 1989 Forwards Wh Arowood 890907 Ltr & Other Supplemental Info to Replace Info Previously Filed ML20247F4121989-08-31031 August 1989 Advises That Response to Order Modifying Licenses & Order to Show Cause Why Licenses Should Not Be Revoked Will Be Sent. Responses to NRC Three Basic Questions Re Status of Licensee Finances & Rationale for Having License Provided ML20246B1671989-08-0808 August 1989 Forwards Response to 890717 Request for Info Re Filings W/ Us Bankruptcy Court & Financial Capabilities.Ownership of Unclassified Equipment Remains Unchanged ML20247Q5521989-05-24024 May 1989 Notifies That J Smelser Contract Ended,Effective 890517. Mgt of Company by Listed Board of Director Members Will Continue Until New Chief Executive Officer Selected ML20247P8071989-04-0404 April 1989 Forwards Ltr in Which Concerns for Potential Significant Deficiency Under 10CFR21 Expressed ML20247G4991989-03-30030 March 1989 Forwards Proprietary BAW-10175P, Rod Exchange Methodology, Developed for Calculating Parameters While Performing Control Rod Measurements Using Rod Exchange Technique to Be Used at Plants.Rept Withheld (Ref 10CFR2.790) ML19324C3151989-02-20020 February 1989 Informs of Change in Vendor Plans for Inspecting Fuel Rods Containing Fuel Pellets Supplied by Ge.Ultrasonic Insp of Fuel Rods at Oconee 1 Found No Failed Rods in three-cycle, Discharged Fuel Assemblies ML20235M8971989-02-10010 February 1989 Requests Withholding of Proprietary WCAP 12125, Catawba Unit 1 Evaluation for Tube Vibration Induced Fatigue, Per 10CFR2.790 ML20206M4871988-11-11011 November 1988 Requests That Proprietary Info Marked in WCAP-11883, Implementation of Steam Generator Low Low Level Reactor Trip Time Delay & Environ Allowance Modifier in Callaway Plant Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20206D6241988-11-11011 November 1988 Forwards Projected Decommission Costs of Centrifuge Machines to Be Transferred to New Facility at Oliver Spring,Tn. Licensee Will Be Able to Offset Total Decommissioning Costs by Setting Aside Annual Decommissioning Cost Plus Reserve ML20205Q6331988-11-0202 November 1988 Forwards Revised Proprietary Pages to BAW-10164P, RELAP5/Mod2-B&W,Advanced Computer Program for LWR LOCA & Non-LOCA Transient Analysis. Cso Film Boiling Correlation Replaced w/Condie-Bengston IV Correlation & Typos Corrected ML20205P9511988-11-0101 November 1988 Forwards Rev 6 to Security Plan for Alchemie Facility 1 - Cpdf,Oak Ridge,Tn & Rev 6 to Security Plan for Alchemie Facility 2 - Oliver Springs,Oliver Springs,Tn. Revs Withheld (Ref 10CFR2.790(d)) ML20195E4291988-10-31031 October 1988 Forwards Numbers 1-5 of Rev 5 to Alchemie Security Plans. Requests Replacement of Pages 23-25 & 35 & Encl Rev Page ML20205N3301988-10-27027 October 1988 Forwards Sketch of Feed Sys,Withdrawal Sys Refrigeration Cart & Typical Withdrawal,Large & Small,Pumping Stations ML20195B6091988-10-21021 October 1988 Forwards Summary of B&W Fuel Co Position Re Small Break LOCA Calculations Contained in Util FSARs for Upcoming Reload Cores Which Will Contain Fuel Mfg by B&W ML20154K3841988-09-12012 September 1988 Forwards Enhanced Facts Re Adequacy of Funding for Decontamination & Decommissioning (D&D) of Facilities. Intends to Establish Funded Reserve for D&D at Completion of Sale of Unclassified Equipment Not Needed for Production ML20154E6451988-08-31031 August 1988 Requests That 880722 & 0812 Ltrs Re Security Sys Components Be Withheld from Public Disclosure (Ref 10CFR2.790(d)) ML20207L7651988-08-30030 August 1988 Requests That Proprietary WCAP 11935, McGuire Unit 2 Evaluation for Tube Vibration Induced Fatigue, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20154A1291988-08-26026 August 1988 Submits Application for Withholding Proprietary WCAP-11883, Implementation of Steam Generator Low Low Level Reactor Trip Time Delay & Environ Allowance Modifier in Callaway Plant from Public Disclosure (Ref 10CFR2.790) ML20151H9381988-07-25025 July 1988 Forwards Proprietary BAW-10168P, B&W LOCA Evaluation Model for Recirculating Steam Generator Plants ML20151M9211988-07-20020 July 1988 Responds to 880621 Request for Addl Info Re Enrichment of Naturally Occurring radioisotopes.Te-123 Will Be Enriching Approx 60 G to About 50% ML20151L3321988-07-20020 July 1988 Forwards DOE Ltr Indicating Acceptance of Classified Matter. Licensee Agrees to Remove Any Toxic or Hazardous Matl from Classified Equipment Prior to Transfer to DOE for Disposal ML20151G9761988-07-14014 July 1988 Forwards Rev 2 to Security Plan for Shipment of Classified Matter.Rev Withheld (Ref 10CFR2.790) ML20150F1561988-07-0808 July 1988 Advises of Changes to Alchemie Board of Directors,Per 880618 Annual Stockholders Meeting ML20155F4441988-05-0404 May 1988 Responds to NRC & Request at 880504 Meeting Describing GE Program to Reconfirm Design Adequacy of Associated Circuits in GE Bwrs.Upon Completion of Phases 1 & 2 of Evaluation of Bwrs,Ge Will Submit Summary by 881104 ML20151F7661988-03-29029 March 1988 Forwards Updated Pages to Proprietary BAW-10171P, REFLOD3B- Model for Multinode Core Reflooding Analysis, Per ECCS Methodology for Facilities Reloads.Mod Removes Henry Quench Temp Criteria & Potential Conflict in Logic.Pages Withheld ML20234C2231987-12-28028 December 1987 Forwards Proprietary BAW-10164P, RELAP5/MOD2-B&W,Advanced Program for LWR LOCA & Non-LOCA Transient Analysis. Rept Describes Computer Code Used to Analyze RCS Behavior During Blowdown Phase of LOCA Transient.Rept Withheld ML20234D1101987-12-14014 December 1987 Forwards Proprietary BAW-10171P, REFLOD3B,Model for Multinode Core Reflooding Analysis. Rept Describes Computer Code That B&W Will Be Using to Analyze RCS Behavior During Refill of LOCA Transient.Rept Withheld ML20237C3611987-11-24024 November 1987 Requests That Proprietary Rev 2 to WCAP-11386, Byron/ Braidwood T-Hot Reduction Final Licensing Rept, Be Withheld (Ref 10CFR2.790(b)(4)) ML20236C0261987-10-22022 October 1987 Forwards Proprietary BAW-10165P, FRAP-T6-B&W:Computer Code for Transient Analysis of LWR Fuel Rods. Rept Describes Computer Code That B&W Will Be Using for Future Transient Analyses of LWR Fuel Rods.Rept Withheld (Ref 10CFR2.790) LD-87-056, Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request1987-09-18018 September 1987 Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request ML20236H4971987-07-29029 July 1987 Forwards Draft Proprietary Topical Rept BAW-10166P, Beach Computer Code for Reflood Heat Transfer During Loca. Draft Submitted to Permit Interaction Between B&W,Nrc & Util. Affidavit for Withholding Encl.Fee Paid ML20236B4141987-07-13013 July 1987 Forwards Proprietary Draft 1 of BAW-10168P, ...B&W LOCA Evaluation Model for Recirculating Steam Generator Plants, to Be Used for LOCA Analysis of Catawba & McGuire Reload Fuel Cycles.Rept Withheld (Ref 10CFR2.790).Fee Paid ML20196K1621987-07-0909 July 1987 Partially Deleted Ltr Submitting Addl Info in Response to NRC 861230 & 870211 Requests Re 860918 Application for Exemption from Requirement to Convert from High Enriched U to Low Enriched U for Reactor Fuel,Per Generic Ltr 86-12 ML20215L0591987-06-22022 June 1987 Responds to Request for Assurance That Facility Neutron Monitoring Sys Design Similar to Design of Other Plants.List of Plants W/Similar Design,Already Reviewed & Approved by Nrc,Encl ML20214R4761987-05-18018 May 1987 Documents Deviations Noted at Facility Re Existence of RTV Foam Seals Not Conforming to Requirements,Per 870515 Telcon W/Region Iv.Preliminary Evaluations on Acceptable Methods of Repair Will Be Completed by 870522 ML20215D4081987-05-15015 May 1987 FOIA Request for Reactor Vessel Surveillance Capsule Repts for Turkey Point 4,Zion 2 & DC Cook 1 ML20237D2761987-04-27027 April 1987 Forwards List of 200 Parameters That Company Will Provide to Offsite Agencies,Per Request to D Schultz.List of Parameters That Will Be Available to NRC Via Zion Data Link During Coming Federal Field Exercise & Dryrun Also Encl ML20212R4711987-04-15015 April 1987 Forward Proprietary Draft 1 to BAW-10171P, REFLOD3B,Model for Multinode Core Reflooding Analysis, for Review of ECCS Methodology for Plants Fuel Reloads,Per . W/Affidavit.Draft Withheld (Ref 10CFR2.790).Fee Paid LD-87-017, Responds to 870327 Questions Re Steam Generator Tube Vibration Observed at Palo Verde Units 1 & 2.Definition & Scope of Program to Review Phenomenon Will Be Available for Review W/Nrc in Approx 90 Days1987-04-10010 April 1987 Responds to 870327 Questions Re Steam Generator Tube Vibration Observed at Palo Verde Units 1 & 2.Definition & Scope of Program to Review Phenomenon Will Be Available for Review W/Nrc in Approx 90 Days ML20206E7851987-04-0202 April 1987 Confirms Intention to Use FOAM2 Computer Program as Part of ECCS Evaluation Model for Westinghouse Designed Plants. Review of Applicability of Code to Westinghouse Designed Plants Requested Prior to 880701 ML20237D6431987-03-25025 March 1987 Forwards Technical & Cost Proposal for Task Order 009, Continuing Exercise Support to NRC Operations Ctr, Electronic Transmission of Plant Parameters During Exercises, Under Contract NRC-05-86-170 ML20237D6681987-03-0404 March 1987 Forwards Revised Draft Statement of Work Proposed for Task Order 009, Continuing Exercise Support to NRC Operations Ctr,Electronic Transmission of Plant Parameters During Exercises, for Contract NRC-05-86-170 ML20237D6881987-02-14014 February 1987 Forwards Parameters & Computer Points That Author Will Be Attempting to Get Util to Make Available for Transmission to NRC During Federal Field Exercise - 2 ML20205G1591987-01-20020 January 1987 Requests Proprietary Responses to NRC Review Questions Re Resistance Temp Detector Bypass Elimination Be Withheld (Ref 10CFR2.790) NRC-87-3194, Documents 861231 Telcon Re Anomalous Plant Data at Callaway & Wolf Creek.Investigation Initiated.Data Specs for McGuire, Catawba & Millstone Will Be Transmitted1987-01-0707 January 1987 Documents 861231 Telcon Re Anomalous Plant Data at Callaway & Wolf Creek.Investigation Initiated.Data Specs for McGuire, Catawba & Millstone Will Be Transmitted ML20214P1911986-11-19019 November 1986 Forwards Proprietary NEDC-31336, GE Instrument Setpoint Methodology, Per Lrg Instrument Setpoint Methodology Group .Rept Applicable to Listed Plants & Withheld (Ref 10CFR2.790) 1989-08-08
[Table view] |
Text
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~ Attachme.4t 3 d .
1 sox 355 Westinghouse Water Reactor PittsburghPemsyfvana15230 ;
Electric Corporation Divisions ,
March 22,1984 CAW-84-22 Mr. Harold R. Denton Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Comission Phillips Building 7920 Norfolk Avenue Bethesda, Maryland 20014 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE y e
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SUBJECT:
Response to NRC Questions on Setpoint Methodology for SNUPPS >-
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REF: Att Letter from SNUPPS to NRC (Petrick to Denton), March,1984 U
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Dear Mr. Denton:
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The proprietary material transmitted by the reference letter for which g withholding is being requested by the Standardized Nuclear Unit Power Plant System (SNUPPS) is of the same technical type as that proprietary material previously submitted by Westinghouse concerning Reactor Protection
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System / Engineered Safety Features Actuation System Setpoint Methodology. The W G
previous application for withholding, AW-76-60, was accompanied by an affidavit signed by the owner of the proprietary information, Westinghouse Electric Ccrporation. Further, the affidavit submitted to justify the previous material was approved by the Comission on April 17, 1978, and is equally applicable to the subject material. The subject proprietary material is being submitted by y the Standardized Nuclear Unit Power Plant System (SNUPPS) for theCKansas City Power and Light Company's Wolf Creek (STN 50 482) and the Union Electric -
Company's Callaway (STN 50 483).
8404040088 840323 PDR ADOCK 05000482 A PDR 7
- Pir. Harold R. D;nton March 22, 1984 j Accordingly, this letter authorizes the utilization by SNUPPS of the previously furnished affidavit. A copy of the affidavit, AW-76-60, dated December 1, 1976, is attached.
Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference CAW-84-22 and should-be addressed to the undersigned.
Very truly yours, Robert A. Wiesemann, Manager Regulatory & Legislative Affairs
/dr Attachment cc: E. C. Shomaker, Esq.
Office of the Executive Legal Director, NRC 4
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4 All-76-60 AFFIDAVIT-COW 0NWEALTH OF pef;NSYLVANIA:
ss COUNTY OF ALLEGHENY:
Before me, the undersigned authority, personally appeared Robert A. Wiesemann, who, being by me duly sworn according to law, de-poses and says that he is authorized'to execute this Affidavit on behalf
- of W'estinghouse Electric Corporation (" Westinghouse") and that the aver-ments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief
<4 E! Uf.42.dU
- Robert A. Wiesemann, Manager Licensing Programs Sworn to and subscribed before,methis8 day of II/ord d 1976.
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/ Notary Public .,
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AW-76-60 (1) I am Manager, Licensing Programs, in the Pressurized Water Reactor Systems Division, of Westinghouse Electric Corporation and as such,
.I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public dis-closure in connection with nuclear power plant licensing or rule-making proceedings, and am authorized to apply for its withholding "on behalf of the Westinghouse Water Reactor Divisions.
(2) I am making this Affidavit in conformance with the provisions of 10 CFR Section 2.790 of the Commission's regulations and in con-junction with the Westinghouse application for withholding ac-companying this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse Nuclear Energy Systems in designating information '
as a trade secret, privileged or as confidential commercial or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the in-formatio 6 sought to be withheld from public disclosure should be withheld.
(i) The information sought to be. withheld'from public disclosure -
is owned and has been field in confidence by Westinghouse.
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AW-7G-60 e
(ii) The information is of a type customarily held in confidence by Westinghouse and no't customarily disclosed to the public.
Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The ap-plication of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required. .
Under that system, information is held in confidence if it falls in one or more of several types', the release of which might result in the loss of an existing or potential com-petitive advantage, as follows:
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.)
where prevention of its use by any of Westinghouse's
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competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or
- - improved marketability.
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AW-76-60 (c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
(d) It reveals cost or price information, production cap-acities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or future West-inghouse or customer funded development plans and pro-grams of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent pro-tection may be desirable.
(g) It is not the property of Westinghouse, but must be treated as proprietary by Westinghouse according to agreements with the owner.
- There are sound policy reasons behind the Westinghouse system which include the following:
(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its com-l petitors. It is,' therefore, withheld from disclosure to protect the Westinghouse competitive position.
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AW-76-60 (b) It is information which is marketable in many ways. e The extent to 'which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.
(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
(d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary infor-mation, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.
(e) Unrestricted disclosure would jeopardize the pos.ition
' of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition in those countries.
(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success
. . in obtaining and maintaining a competitive advantage.
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AW-76-60 e .
. i (iii) The information ,is being transmitted to the Commission in l
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confidence and, under the provisions of 10 CFR Section 2.790, it is to be received in confidence by the Commission.
(iv) The information is not available in public sources to the best of our knowledge and belief.
(v) The proprietary information sought to be withheld in this sub-mittal is that which is appropriately marked in the attach-mers to Westinghouse letter number NS-CE-1298, Eicheldinger to Stolz, dated December 1,1976, concerning information relating to NRC review of WCAP-0567-P and WCAP-8568 entitled, " Improved Thermal Design Procedure," defining the sensitivity of DNB ratio to various core parameters. The letter and attachment are being submitted in response to the NRC request at the October.29, 1976 NRC/ Westinghouse meeting.
This information enables Westinghouse to:
(a) Justify the Westinghouse design.
(b) Assist its customers to obtain licenses.
(c) Meet warranties. .
(d) Provide greater operational flexibility to customers assuring them of safe and reliable operation.
(e) Justify increased power capability or operating margin for plants while assuring safe and reliable operation.
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- AW-76-60 (f) Optimize reactor design and performance while maintaining a high level of fuel integrity.
Further, the information gained from the improved thermal design procedure is of significant commercial value as follows:
I (a) Westinghouse uses the information to perform and justify analyses which are sold to customers.
(b) Westinghouse sells analysis services based upon the ,
experience gained and the methods developed.
Public disclosure of this information concerning design pro-cedures is likely to cause substantial harm to the competitive position of Westinghouse because competitors could utilize this information to assess and justify their own designs without commensurate expense.
The parametric analyses performed and their evaluation represent a considerable amount of highly qualified development effort.
This work was contingent upon a design method development pro- ,
gram which has been underway during the past two years.
Altogether, a substantial amount of money and effort has been expended by Westinghouse which could only be duplicated by a competitor if he were to invest similar sums of money and pro-vided he had the appropriate talent available.
Further the deponent sayeth not.
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( i Attachment 2
. WESTINGHOUSE RESPONSE TO NRC OUESTIONS ON SETPOINT ME'IHODr1 nnY FOR SNUPPS
- 1. The methodology utilized in deter 1nining the adequacy of the difference between the nominal trip setpoint in the Technical Specifications and the setpoint assumed in the SNUPPS accident analyses is the same as that utilized for Virgil C. Stamer. '!his methodology was approved by the staff in NUREG-0717, supplement No. 4, dated 8/82.
- 2. Four protection factions have nominal trip setpoints such that the 955 probability value for the instrument mcertainties could place the trip function within 5% of the top or bottom of the instrumentation calibration range. The functions and closeness to the top or bottom of the range are:
A. Power range Neutron Flux - High Setpoint - [] +a,c from top of instrument range, B. PressurizerWaterLevel-High-[]*** from top of instrument range, C. Steam Generators Water Level - Low-Low - []+a,c from bottom of instrument range, and D. Pressurizer Pressure - Low - SI - []+8'" from bottom of instrument range.
In a continuing effort to monitor protection system operability, Westinghouse has reviewed reported LERs for RPS and ESF trip ftmetions, and when available, plant data on fm etional test results. During this monitoring process, there t
has been no indication that the above trip functions experience any more additional drift than trip ftmetions with setpoints greater than 55 from the top or bottom of the instrtunent span. As part of the calibration procedures, several points across the calibrated instrument range including the 0% and 100%
span values are checked. Inspection of as left/as found data from these checks do not indicate any significant variances from the instrument range intermediate points. In addition, transmitters are purchased such that the upper and lower range limits for the transmitters are greater than the upper and lower range values, (See SAMA Standard PMC 20.1-1973), i.e., the calibrated instrument range is not the design limit for the device. Based on the above, Westinghouse does not believe that ftmetions which have 955 probability setpoints (when including uncertainties using the approved Westinghouse setpoint methodology) within 5% of j the top or bottom of the instrument range will respond any differently than any l
other protection function.
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- 10. NOT WESTIN
- 1. ALL VALUES IN PERCENT SP AN.
y 2. AS NOTED IN T ABLE 15.0-4 0F FSAR.
II. [
[t.q7 ,[ 1 3. AS NOTED IN T ABLES 2.2-1 AND 3.3-4 0F 12. [
PL ANT TECHNIC AL SPEC IFIC AT10NS.
- 4. INCLUDED IN [ ]+ e.c 13. [
- 14. [
S. NOT USED ]N THE SAFETY AN ALYSIS.
- 6. AS N O T E D IN F IGURE 15.0 - 1 0 F F S AR . 15. INCLUDE D
- 7. AS NOTED IN TABLE 2.2-1 NOTE I 0F 16. INC ORE X PL ANT TECHNIC AL SPE C IFIC ATIONS. T ABLE 4.3
- 8. AS NOTED IN T ABLE 2.2-1 NOTE 3 0F t7. [
PL ANT TECHNIC AL SPEC 1FIC AT 10NS. '
- 9. NOT NOTED IN T ABLE 15.0-4 0F FSAR BUT USED IN SAFETY AN ALYSIS.
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PROCESS PRI.
PROTECTION CHANNEL [CURC CC til I POWER R ANGE, NEUTRON FLUX - HIGH SETPOINT 2 POWER R ANGE, NEUTRON FLUX - LOW SETP0lNT 3 POWER R ANGE, NEUTRON FLUX -
HIGH POSIT IVE R ATE 4 POWER R ANGE, NEUTRON FLUX - HIGH NE GAT IVE R AT E 5 INTERMEDI ATE R ANGE, NEUTRON FLUX
.-__ L s 3 u A c L NNJiGra- [LLU2 -____-.___ __ ___ _--------_---- --- -------- --- --- -._____ _
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[6MrL=R/ro e Cou OAy N OTE S F OR T ABL E 3 - 16,RE V.O iTINGHOUSE SCOPE.
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- 19. [
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- D IN [ ]+e.c EXC ORE f(A!) C OMPARISON AS NOTED IN (4.3 -! 0F PL ANT TECHN IC AL SPEC IF IC AT IONS
]+ e.c T ABLE 3 - 16 RE AC T OR PROTEC TION SYSTE M/EN GINEERE D SAFE TY FE ATURES ACTU ATION SYSTEM CHANNEL ERROR ALLOWANCES C ALLAWAY. _ STATION
- ' = INSTRUMENT R
= SENSOR 6 7_ 8 9 2 3 4 5 TEMPERATURE DRIFT E NVIR ONVE NT AL C AllBR ATION COMPARATOR TEMP
' PR IM ARY C AL IBR AT l0N PRESSURE SE T TIN G EF til ALLOWANCE ACCURACY AC CUR AC Y EFFECTS EFFECTS
$LEVENT til til (1) ACCURACY
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10 11 12 13 14 15 16 17 IE MPER ATURE DRIFT SAFETY STS STS TOTAL CHANNEL MARGly EFFECTS (1) ANALYSIS ALLOWABLE TRIP ALL OWANCE ST AT IST IC AL (1) 111 L IM IT VAL UE SETPOINT (1) AL L OWANC E
...o (21 (3) (3) II) + a.c l.O 118% R TP 112.3% RTP 109% RTP i 1.0 35% RTP 28.3% RTP 25% RTP 2 0.5 151 6.3% RTP 4.0% RTP 3 6.9% P 4 0.5 6.3% R TP 4.0% R TP 4.2 (5) 35.3% R TP 25% RTP 5 5 5 3.0 (5) 1.6 10 1.0gg,g lg
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- OVERTE MPE,R ATURE AT AT C H AN NE L 8 T AVG CHANNEL 9 _
10 PRESSURIZER PRESSURE CHANNEL 11 ffAI) CHANNEL 12 OVERPOWER AT AT C H A N N E t_
13 14 T AVG CHANNEL IS PRESSUR IZER PRE SSURE - LOW, RE AC TOR T R IP 16 PRESSURlZER PRESSURE - HIGH _.
17 PRESSURIZER WATER LEVEL - HIGH 18 L OSS OF FLOW 19 STEAM GE NER ATOR WATER LEVEL - L OW-L OW _ _.
20 U N DE R V OL T AGE - R C P _
21 U N DE R F RE QUE NC Y - RCP 22 C ONTAINMENT PRESSURE - H I GH - l _ _ _ _ _ - . _ _ _ _ _ _
23 PRESSURIZER PRESSURE - L OW.S l ____ _ ___
24 STE AMLINE PRESSURE - LOW 25 CONT AINMENT PRESSURE - HIGH-2 26 C ONTAINMENT PRESSURE - H IGH -3 - - -
27 NEGAT IVE STE AM PRESSURE R ATE - HIGH _ _ _
28 STEAM 3ENER ATOR WATER LEVEL - H IGH - H [GH
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29 RWST LEVEL - L OW, AUTOM ATIC SWITCHOVER _
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