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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 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 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 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 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 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 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 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-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 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-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 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 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 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 ML20209B6851999-06-28028 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Nuclear Power Plants. Disclosure Rept Encl 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 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:UTILITY TO NRC
MONTHYEARML20064A6951990-09-18018 September 1990 Requests one-time Waiver to Alter Licensed Operator Requalification Training Program Cycle to Be Better Aligned W/Natl Exam Schedule ML20059G2971990-09-0404 September 1990 Notifies of Implementation of Procedure on 900831 to Correct wide-range Gas Monitor Display for Noble Gas Spectrum ML20059G4991990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jan-Jun 1990 & Rev 0 to APA-ZZ-01003, Odcm ML20059E6151990-08-29029 August 1990 Forwards Semiannual fitness-for-duty Program Performance Data Rept for Jan-June 1990,per 10CFR26.71(d) ML20059E9611990-08-28028 August 1990 Reaffirms Commitment to Safe & Responsible Operation of Facility in Face of Tender Offer for Util Stock.Accepts W/O Qualification,Responsibility for Continued Safe & Reliable Operation of Plant ML20059D5281990-08-27027 August 1990 Provides Correct Ltr Number for Jul 1990 Monthly Operating Rept.Correct Ltr Number Should Be No 90-0226 ML20059C3371990-08-23023 August 1990 Advises That Util Plans to Remove Some Thimble Plugging Devices from Plant During Upcoming Refueling Outage.No License Amend Required.Revs to Tech Spec Bases 3/4.2.2 & 3/4.2.3 That Reflect All Removal of Thimble Plugs Encl ML20059B3691990-08-21021 August 1990 Forwards Proprietary TR-90-0024 W01, Wolf Creek Nuclear Operating Corp Rod Exchange Methodology for Startup Physics Testing, Per Discussion at 890518 Meeting.Rept Withheld (Ref 10CFR2.790) ML20059C1781990-08-21021 August 1990 Forwards Proprietary TR-90-0025 W01, Core Thermal-Hydraulic Analysis Methodology for Wolf Creek Generating Station, for Review & Approval by 920101.Rept Withheld (Ref 10CFR2.790) ML20058P1001990-08-10010 August 1990 Forwards Wolf Creek Generating Station Inservice Insp Rept, for Fourth Refueling Outage,Period 2,Interval 1. Nonconforming Conditions Requiring Repair/Replacement of Supports Identified During Routine Maint Activities ML20058N1421990-08-0909 August 1990 Responds to Insp Rept 50-482/90-08 Re Effectiveness of Techniques Used to Detect Erosion/Corrosion Degradation. Existing erosion-corrosion Program Effective in Identifying Wall as Nonrelevant Volumetric Anomalies ML20058N2051990-08-0707 August 1990 Advises of Implementation of Amend 55,rev to Tech Spec 3/4.7.1.2 Re Auxiliary Feedwater Sys,Effective 900807 ML20058L2011990-08-0101 August 1990 Forwards Inadvertently Omitted Index of Proposed Tech Spec from Re RCS ML20081E1971990-07-27027 July 1990 Forwards Rev 6 to Indexing Instruction T210.0002/Q101, Qualification/Certification Documentation & Rev 6 to T210.002/R353, Required Reading/Personnel Form 2 ML20055J0641990-07-26026 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-482/90-24.Corrective Action:All Dose Personnel Receiving Retraining within Normal 7-wk Training Cycle Which Began on 900723 & Emergency Procedure EPP 01-7.3 Will Be Revised ML20055H2091990-07-23023 July 1990 Informs That Util Has Commenced Cash Tender Offer to Purchase Outstanding Shares of Each Class of Common & Preferred Stock of Kansas Gas & Electric Co.Util Convinced That Proposed Merger Will Have No Effect on Plant Operation ML20055G8331990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20055F6671990-07-13013 July 1990 Forwards Monthly Operating Rept for June 1990 for Wolf Creek Generating Station & Corrected Pages 1,4 & 5 to May 1990 Rept ML20044B1821990-07-0909 July 1990 Forwards Westinghouse Revised Proprietary RCS Flow Measurement Uncertainty Calculation Supplementing Setpoint Studies Submitted in Attachment to Util 900412 Ltr.Encl Withheld ML20055E7861990-07-0505 July 1990 Forwards Callaway Plant 1990 Annual Exercise Scenario on 900530 ML20055E5261990-07-0505 July 1990 Forwards Revised marked-up Tech Spec Pages for 900306 Application for Amend to License to Place cycle-specific Core Operating Parameters in Core Operating Limits Rept ML20055D9941990-07-0505 July 1990 Forwards Addl Info Re Seismic Design Considerations for Certain safety-related Vertical Steel Tanks,Per 890525 Request ML20055D5011990-07-0202 July 1990 Forwards Change in Status of Licensed Operators Since Transmitted,Per 10CFR50.74 ML20055D2111990-06-29029 June 1990 Responds to Request for Addl Info Re Violations Noted in Insp Rept 50-482/90-05.Corrective Actions:Change Made to Adm 02-005, Reactor Operators Qualifications & Responsibilities ML20055D0481990-06-29029 June 1990 Responds to NRC Re Violations Noted in Insp Rept 50-482/90-17.Corrective Actions:Procedure Adm 03-600 Revised on 900430,to Ensure That Respirator User Issued Model & Size for Which Fit Tested & Trained ML20058K4011990-06-28028 June 1990 Forwards Emergency Preparedness 1990 Field Exercise Scenario for Exercise Scheduled for 900829 ML20044A6601990-06-25025 June 1990 Forwards Requested Info Re Seismic Design of safety-related above-ground Vertical Liquid Storage Tanks,Per 900404 Ltr. All Stresses on Tank Roof Angle,Connecting Cylinder to Roof,Remain within Code Allowables Under Postulated Loads ML20043H8371990-06-21021 June 1990 Forwards Response to Generic Ltr 90-04 Re Status of Implementation of Generic Safety Issues at Facility ML20043H2851990-06-18018 June 1990 Forwards Revised LERs 85-058-01 & 90-002-00,adding Rept Dates Inadvertently Omitted from Original Submittals ML20043G7691990-06-13013 June 1990 Responds to NRC 900514 Ltr Re Violations Noted in Insp Rept 50-482/90-16.Corrective Actions:Movement of Spent Pool Bridge Toward Location FF06 Halted & Bridge Crane Returned to Location DD02 ML20043H2721990-06-12012 June 1990 Forwards 10CFR50.59 Annual Rept Summaries of Written Safety Evaluations of Changes Approved & Implemented for Plant from 890330 to Present ML20043F4051990-06-11011 June 1990 Forwards Monthly Operating Rept for May 1990 & Corrected Page 2 for Apr 1990 ML20043E7491990-06-0808 June 1990 Forwards Rev to Figure 3.4-2 to 880620 Application for Amend Revising Tech Specs 3/4.4.9.1 & 3/4.4.9.3.Rev Corrects Editorial Error ML20043E8211990-06-0808 June 1990 Informs of Plant Radiological Emergency Preparedness Exercise for 1990 Scheduled for 900829.Schedule Discussed W/Personnel from Region IV Emergency Preparedness,Fema,State of Ks & Coffey County ML20043E2161990-06-0505 June 1990 Forwards Endorsements 42-48 for Nelia Policy NF-264 & Endorsements 28-34 for Maelu Policy MF-111 ML20043E8721990-06-0505 June 1990 Notifies NRC of Changes in Status of Operator Licenses ML20043G9331990-06-0404 June 1990 Forwards Rev 13 to Operating QA Manual. ML20043D7101990-05-31031 May 1990 Forwards NPDES Renewal Application Submitted to State of Mo Dept of Natural Resources on 900518 ML20043D3271990-05-31031 May 1990 Forwards Rev 17 to Physical Security Plan,Safeguards Contingency Plan & Security Training & Qualification Plan. Rev Withheld (Ref 10CFR73.21) ML20058K1911990-05-30030 May 1990 Forwards Radiological Emergency Preparedness Exercise Objectives for 1990 ML20043B4791990-05-24024 May 1990 Documents Administrative Error in Rev to Radiological Emergency Response Plan Submitted on 900116 ML20043B5841990-05-22022 May 1990 Responds to NRC 900423 Ltr Re Violations Noted in Insp Rept 50-483/90-04.Corrective Actions:Security Post Instructions Modified to Require Check of Security Container in QA Area ML20043B4361990-05-22022 May 1990 Responds to Request for Addl Info Re Proposed Revs to Tech Specs 3/4.4.9.1 & 3/4.4.9.3 Re Pressure/Temp Limits for RCS & Overpressure Protection Sys ML20042F2831990-04-30030 April 1990 Forwards Rev 11 to Inservice Testing Program. ML20042F1161990-04-30030 April 1990 Provides Clarification to SALP 9 Rept 50-483/90-01 for Sept 1988 - Jan 1990.Licensee Voluntarily Retested Few Remaining Const Workers Originally Approved for Unescorted Access Using mini-IPAT ML20042E8691990-04-30030 April 1990 Forwards Documentation of Util Ability to Make Payment of Deferred Premiums ML20042F2901990-04-27027 April 1990 Forwards Util 900402 Ltr Documenting Agreement Between State of Mo Historic Preservation Officer & Util Re Cultural Resources ML20042E3021990-04-13013 April 1990 Forwards Supplemental Response to NRC 900316 Ltr Re Violations Noted in Insp Rept 50-482/90-05.Corrective Actions:Air Check Valves to Main Steam & Feedwater Isolation Valves Added to Preventive Maint Program ML20042D8491990-04-0202 April 1990 Forwards Listing of Present Level of Nuclear Property Insurance Coverage & Sources of Insurance,Per 10CFR50.54(w) ML20012F1601990-03-29029 March 1990 Submits Supplemental Info Re Util Response to Station Blackout.Callaway Will Comply W/Numarc Station Blackout Initiative 5A Re Emergency Diesel Generator 1990-09-04
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SNUPPS Standardized Nuclear Unit Power Plant System 5 Choke Cherry Road Nicholas A. Petrick Rockville, Moryland 20850 Executive Director (MH 869 8010 September 22, 1981 SLNRC 81-109 FILE: 0541 SUBJ: PSB Review
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dir. Harold R. Denton, Director ,9 e$ S Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
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Docket Nos. STN 50-482, STN 50-483,
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and STN 50-486 ,
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Dear Mr. Denton:
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In discussions with Dr. Gordon Edison, NRC project manager for the SNUPPS applications, it was learned that additional information was required in order for the Power Systems Branch to complete their review. The purpose of this letter is to provide that information.
Analysis of Offsite Power System The enclosure to this letter includes changes to the SNUPPS FSAR that will be incorporated in the next revision. These char.ges include the additional descriptions and results of analyses for the offsite power system.
Degraded Grid Voltage The enclosed FSAR changes address this topic.
I Separation Inside NSSS Cabinets The enclosed FSAR changes confirm that field run cabling meets the requirements of WCAP-8892A.
Submerged Electrical Equipment The. following Class IE equipment is located telow the post-accident
- flood level:
EPHV88088, EPHV8808C - FSAR Fig. 6.3-1 Sheet 4 BBHV80378, BBHV8037A - FSAR Fig. 5.1-1 Sheet 2 og)
D EMHV8823, EMHV8824, EMH'."1881 - FSAR Fig. 6.3-1 Sheet 2 #
Containment Sump Level Instrumentation - FSAR Section 18.2.12.2 7
8109240353 810922 PDR ADOCK 05000482 A PDR
, SLNRC 81-109 Page Two The locating of these valves and instruments below the flood line does not jeopardize the integrity of the Class IE power system. Also, there is no non-Class IE equipment, powered from Class IE sources, located below the flood level. Valves EPHV8808C and EPHV88088 are accumulator isolation M0 valves which are open during power operation. This position is also their safety function position. When these valves are open, both their power and control circuits are de-energized by physically securing their associated circuit breaker in the tripped position. Therefore any spurious shorts of the valve due to flooding cannot cause the valves to close or otherwise prevent them from per-forming their safety function.
Valves BBHV8037A and BBHV8037B are Pressurizer Relief Tank drain M0 Valves. These valves are designated Class lE to enable the plant to achieve cold shutdown using only safety-grade components. They have no accident mitigation requirements. Spuricus travel of these valves will not have any effect on the ability to mitigate any accident. The power circuits to these valves are normally deenergized. The control circuits are doubly fused to ensure adequate penetration protection in the event of control circuit shorts resulting from the flooding.
Valves EMHV8823, EMHV8824 and EMHV8881 are all 3/4" containment isola-tion valves for ECCS test lines. These valves are normally closed with their solenoids deenergized and a CIS signal is provided to also deenergize their solenoids and close the valves. The valves are not required to operate after an accident. Flooding of these valves after deenergization cannot, due te the control circuit. design, cause the valve to spuriously open.
The containment sump level instrumentation is also located below flood level. This equipment is fully qualified for a submerged environment.
Regulatory Guide 1.63, Position 1 The SNUPPS design is committed to satisfying regulatory position Cl of RG 1.63, Revision 1. This position requires that the electrical penetration assemblies withstand, without seal f ailure, the total range of available time-current characteristics assuming a single f ailure of any overcurrent protective device.
SNUPPS is currently reviewing all electrical penetration assembly protective device settings and capabilities to verify that the above position is satisfied. The results of the review will demonstrate that, for all penetrations, both the pri:Ory and backup protection will act to protect the penetration from f ailure for the full range of
~
available f ault current. Available means of obtaining assurance that this protection is achieved include adjustment of settings, using additional fuses, and use of parallel conductors within the electrical penetration asseinbly,
, SLNRC 81-109 Page Three Insulating-Regulating Transformers SNUPPS will provide an analysis, based on transformer tests, demon-strating that the isolating - regulating transformers are qualified isolation devices. If this analysis should be unsuccessful and the isolating - regulating transformers are not acceptable as qualified isolation devices, an alternate method of isolation will be used in this application.
Analysis of Load Sequences The SNUPPS Load Shedder and Emergency Load Sequencer (LSELS) is pro-vided to automatically sequence the required safety loads onto the Class IE busses as determined by the sensed conditions. A separate LSELS is provided for each load group.
A Failure Modes and Effects Analysis (FMEA) and a reliability study have been performed. These studies have conclusively shown that no failxe within a single LSELS can result in the failure of both sources of offsite power. The chief reason for this is that the only time harmful interaction between the onsite and offsite power systems is possible is when the two systems are operating in parallel. This mode of operation only occurs under operator action and supervision.
Otherwise, interlocks prevent the interaction of the two systems at all times. The LSELS cannot cause either the diesel generator breaker or the incoming offsite breaker to close. It can only initiate load shedding, bus tripping, and sequential loading of the Class IE busses.
The alignme,J of the onsite and offsite power systems is determined by design features and operator actions outside the purview of the LSELS.
Thus any failure of an LSELS can affect, at most, one onsite power source and one offsite power source.
To further ensure the reliability and availability of the LSELS, it is provided with an automatic test indication (ATI) feature. This ATI continuously performs self-diagrasis functions on the LSELS circuitry and alarms when a fault is discovered.
Very ul ours,
\ Chec(
Nicholas A. Petrick RLS/bds/11a23 Enclosure cc: J. K. Bryan UE G. L. Koester KGE
- 0. T. McPhee KCPL T. Vandel NRC/WC W. Hansen NRC/ Cal
Enclosure to SLNRC 81-
SNUPPS .
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) 8.2 OFFSITE POWER SYSTEM 9 The offsite ac power supply for the startup, nornal operation, and safe shutdown of each of the SNUPPS units is supplied from the transmission network of each system. The principal design bases as applied to the offsite power system are described in Section 8.1.4. The offsite power systems are described in Section 8.2 of each Site Addendum.
The instrumentation associated with the offsite ac power system provides sufficient information to determine the system availability at any time.
Table 1.7-1 of the FSAR contains drawings 10466-E-01NB01 and 10466-E-01NB02, Single Line Meter and Relay Diagrams These for the drawings Safety-Related 4.16-kV busses NB01 and NB02.
show the surveillance details of Table the ESF transformers 8.3-4 andFailure of the FSAR, their associated 4.16-kV bus.
Modes and Effects Analysis, shows the system failure modes and >
the method of such failure detection.
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II'. d s E R*C l The offsite power systems from the transmission line network to the startup transformer That and ESF transformer XNB01 are discessed in Section 8.2 of each Site addendum.
portior of the offsite power system is not in the SNUPPS " Standardized" design.
Thz portion of the of fsite power system f rom the startup transformer and ESF transformer XNB01 to the 4.16 KV Class TE busses is within the scope of the SNUPPS " Standardized" design and is discussed b. A A *sbae44 4
- n aw A A. 4es.'g Twophysicallyindependentsourcesofoffsitepower{arebroughttotheonsitepower cystem. One circuit is fed from ESF Transformer XNB01 and supplies power normally to its associated 4.16 KV Class IE bus. The other circuit is fed from one secondary winding of the startup transformer, through ESF transformer XNB02, and supplies power normally to its associated 4.16 KV Class *IE bus. In addition, each offsite power circuit can be marually aligned to supply power to[8pposite or both 4.16 KV Class IE busses if required. Each of these offsite power circuits is designed to be available in sufficient time to ensure that specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceejed fol~ awing a loss of all onsite power sources and the remaining offsite power circait.
The two ESF transformers XNB01 and XNB02 are separated by a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire wall. The cables associated with each of these offsite power circuits are routed in separate and distinct rsesways. The duct banks and other routing features of the two circuits are shown on drawings E-OR0224 E-0R3321 E-0R3221 and E-CR3211 for the cables from the ESF transformers to the 4.16 KV Class IE busses, on drawings E-0R0223, E-OR4331, E-OR4321 and E-0R0224 for esbles from the startup transformer to the 13.8 KV switchgear and from the 13.8 KV switchgear to ESF transformer XNB02.
The offsite power circuits, including the tr sformers and cables, pave been sized to carry their anticipated loads continuously. ESF transformers e44 sized to carry both safety related luad groups continuously. The secondary feeder cables to the 4.16 KV Class IE busses are sized in excess of that required to carry their maximum load continuously.
The startup transformer is sized to carry its anticipated load continuously, but may be l
l slightly overloaded under certain abnormal conditions. For additional details of the eizing of these components, refer to Section 8.3.1.
No component of these two of fsite pswer circuits is shared between units at the Callaway Site.
These two circuits are fully testable. Since they are continuously energized and largely possive, they are continusouly tested by their use. When one circuit is shutdown, relays, meters and other instruments can be tested and calibrated as required.
l Control and instrumentation power for these offsite power circuits is provided by the Non-Class IE DC system. A DC power source from separate station batteries is provided to
! each offsite power circuit for control and relaying purposes.
l From the above considerations it is concluded that the installation, sizing and control of l
both of the offsite power circuit are designed so as to minimize the liklihood of their simultaneous failure under operating and accident conditions.
For additiodddetails concerning the compliance of the offsite power system with General D: sign Criteria, refer to Section 3.1 i
) -
SNUPPS LOAD-SHEDDING CIRCUITS - Upon recognition of a loss of or degraded voltage on a 4.16-kV Class IE bus, a logic signal is initiated to effect the foJ1owing on each load group:
- a. Shed selected loads
- b. Send signal to start diesel
/4 c. Trip 4.16-kV preferred power supply breakers _
l o voltage sensing schemes on each Class IE 4.16-kV bus loyed to initiate the logic signal. One scheme wil:
re nize a loss of voltage, and the other will reco ..ze
(/ l([ degra voltage d voltage conditions. Each scheme is prov' ignals through four potential transfo d
rs located on each .
To sense a 1 of voltage, four instan eous-type under-voltage relays e provided. Logic i rovided to allow load shedding an rip of the inco g breaker on 2-out-of-4 undervoltage signal These rel are cet below the minimum expected voltage duri diese equencing.
i Four additional undervolt logic circuits are provided for i
each bus to recognize d a voltage conditions. These
! circuits are set abov the min ' um motor starting voltage during normal oper _on with a t' e delay set to prevent unwanted trippin Logic is provi d to allow load shedding and trip of th neoming breaker on ut-of-4 undervoltage.
Each incom' g breaker is provided with on time delay under-voltage ay to monitor the voltage on the urce side of the br er. This relay contact closes on und oltage and is i' series with the undervoltage logic describe above to i tr' .
This relay is set above the undervoltage pro -tion scribed above with a time delay sufficient to preve. trip uring motor starting. Closing of the incoming breake r prevented until preferred power is available. /)
As each generator reaches rated voltage and frequency, the generator breaker connecting it to the corresponding 4.16-kV bus closes. With the SIS, connection of the diesel generator to the 4.16-kV bus is not made unless the preferred source of power is lost. The diesel generator is able to accept l loads within 10 seconds after receipt of a starting signal,
.and all automatically sequenced loads are connected to
'the Class IE bus within 35 seconds thereafter. Refer to Figure 8.3-2. Relays at the diesel generator detect generator rated voltage and frequency conditions and provide a permis-I sive interlock for the closing of the respective generator circuit breaker. Upon loss of the preferred source of power lO, without a LOCA, the load segaencer system initiates the starting of the diesel generators and sheds all loads, except the load centers and the centrifugal charging pumps.
l l 8.3-11
h5Elt.T 2.
f Two voltage sensing schemes are employed on each 4.16 KV Class IE bus to initiate the required logic signal. One scheme will recognize a loss of voltage and the other will recagnize a degraded voltage. Four potential transformers on each bus provide the necessary input voltages to the protective devices necessary to achieve the above protection.
In order to recognize a loss of voltage, four instantaneous undervoltage relays are used. The output contacts of these relays are directed to logic circuits that process the four undervoltage input circuits into the 2-out-of-4 logic circuit described above. This scheme is used on each bus.
The loss of voltage logic strnal is set below the minimum bus voltage encountered during diesel generator a gential loading. A brief time delay is employed to prevent false trips arising from transient undervoltage (spike) conditions.
In order to recognize a degraded voltage, a diverse protection scheme is used.
The above four potential transformers each provide an anal'og output signal of 0-120 volts. This signal is directed to logic circuits and processors that convert the analog signals into a 2-out-of-4 logic signal whenever the signal drops below a preset value. This scheme serves only to trip the incoming offsita power circuits breakers when that power source has been determined to be degraded. This design cannot adversely affect the sequential loading of the diesel generators.
The degraded voltage logic signal is set at the minimum permissable continuous bus voltage. A time delay is provided that prevents damage to or spurious tripping of the permanently connected Class IE loads by limiting the amount of time they are exposed to a degraded voltage. The final voltage and time setpoints will be deter-mined based on an analysis of the auxiliary power distribution system, including the Class IE busses at all voltage levels. The use of an SIS contact in series with the degraded voltage logic circuit output contact ensures that the Class IE busses will be immediately separated from the offsite power system whenever an accident occurs and the offsite power system is not able to accept the loads continuously. An alarm is also provided to alert the operator to a degraded voltage condition. It is delayed until any motor starting-induced voltage transient bus had sufficient time to clear.
?
B s---- -. , . - - . . - - - - _ . , _ _
SNUPPS
( e. Load group 1 and protection channels 1 and 3 and load group 2 and protection channels 2 and 4 cables are routed through separate cable chases and cable spreading rooms. The former circuits enter the lower cable spreading room, while the latter cir-cuits enter t. upper cable snreading room.
- f. The independence of redundant NSSS safety-related systems is discussed below:
Safety-related reactor trip, engineered safety features actuation, and instrumentation and control power supply systems are designed to meet the independence and separation requirements of Cri-terion 22 of the 1971 General Design CI 'eria and Paragraph 4.6 of IEEE 279, 1971.
Channel independence is carried throughout the system, extending from the sensor through to the devices actuating the protective function. Physi-cal separation of wiring for each redundant channel set is used. Redundant analog equipment is separated by locating modules in different protection rack sets.
Each redundant channel set is energized from a sepa-rate ac power feed.
There are four separate process protection analog rach sets. Separation of redundant analog channels begins at the process sensors and is maintained in the analog protection racks to the redundant trains in the logic racks. Redundant analog channels are separated by locati.lg modules in different rack sets.
Within these racks, field run nonsafety-related shielded cables having a signal level of 100 V or less are routed in common wireways with safety-related shielded cables with no physical separation. Internal cabinet safety and nonsafety-related cables are simi-larly routed. Justificatior for this method of routing cisetosa containea in Reference swue4 caue.5 *e +we581.* Tho omeA5 4Ndd can non-arf. c*dt*d " " *"f"* +'*+(,'4 e st u-a.s r.e. s.
L Two reactor trip breakers are actua ed by two sepa-rate logic matrices which interrupt power to the 1P control rod dr2ve mechanisms. The breaker main
.: contact: are connected in series with the power supply so that opening cither breaker interrupts power to all control rod drive mechanisms, permit-ting the rods to free fall 2nto the core.
Protection system channel inputs are separated from the solid state protection system train out-puts as follows:
8.3-27
. _ _ - -- . . _ . .- . _ . _ - - .