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Category:CORRESPONDENCE-LETTERS
MONTHYEAR05000482/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 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 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 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 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 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-1999-006, 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 ML20212C9211999-09-15015 September 1999 Forwards NRC Form 536, Operating Licensing Examination Data, in Response to NRC Administrative Ltr 99-03 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 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 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 ML20211M7151999-09-0303 September 1999 Forwards Changes to Wolf Creek Generating Station Data Point Library.Emergency Response Data Sys Points Affected Are EJL0007 & EJL0008 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 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 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 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 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 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 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 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 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 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 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 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, ML20210B8191999-07-20020 July 1999 Ack Receipt of ,Which Transmitted Wolf Creek EP Implementing Procedure 06-005,Rev 1.Implementation of Changes Will Be Subj to Insp to Confirm That Changes Does Not Decrease Effectiveness of EP ML20209H5411999-07-15015 July 1999 Forwards Insp Rept 50-482/99-07 on 990614-18.No Violations Noted.Insp Focused on Radiation Program During Normal Operating Conditions 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 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 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 ML20209E3581999-07-12012 July 1999 Discusses Util 980925 Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Wolf Creek Generating Station ML20209E0611999-07-0808 July 1999 Forwards Addl Pages to Rev 12 of USAR & Commitment Changes, Inadvertently Omitted from 990311 Submittal 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 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 ML20196K0501999-07-0202 July 1999 Forwards Insp Rept 50-482/99-06 on 990502-0612.Three Violations Occurred & Being Treated as Noncited Violations, Consistent with App C of Enforcement Policy 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 ML20209A7461999-06-29029 June 1999 Informs of Changes in Project Mgt Staff Assigned to Wcgs. Effective 990628,J Donohew Will Assume PM Responsibilities 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 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 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 ML20212C9211999-09-15015 September 1999 Forwards NRC Form 536, Operating Licensing Examination Data, in Response to NRC Administrative Ltr 99-03 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 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 ML20211M7151999-09-0303 September 1999 Forwards Changes to Wolf Creek Generating Station Data Point Library.Emergency Response Data Sys Points Affected Are EJL0007 & EJL0008 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 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 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 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, 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 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 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 ML20209E0611999-07-0808 July 1999 Forwards Addl Pages to Rev 12 of USAR & Commitment Changes, Inadvertently Omitted from 990311 Submittal 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 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 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 ML20195G4391999-06-11011 June 1999 Provides Details for Missed Rept Re 10CFR50.46 Thirty Day Rept of ECCS Model Revs.Attachment I Provides Summary of Commitments Made in Submittal 05000482/LER-1999-005, Forwards LER 99-005-00,re Esfa.Commitments Made by Util Are Encl1999-06-11011 June 1999 Forwards LER 99-005-00,re Esfa.Commitments Made by Util Are Encl 05000482/LER-1997-027, Forwards LER 97-027-00 Re Identification of Missed Surveillance Required by TS 4.3.3.5.2.Encl 1 Identifies Actions Committed to by Util1999-06-0404 June 1999 Forwards LER 97-027-00 Re Identification of Missed Surveillance Required by TS 4.3.3.5.2.Encl 1 Identifies Actions Committed to by Util ML20195B9811999-05-26026 May 1999 Forwards 1998 Annual Repts for Ks Electric Power Cooperative Inc,Ks City Power & Light Co & Western Resources,Inc, Including Wholly Owned Subsidiary Kg&E Co ML20196L3361999-05-18018 May 1999 Forwards Rev 1 to Cycle 11 COLR for WCGS, IAW TS Section 6.9.1.9 05000482/LER-1999-004, Forwards LER 99-004-00 Re Failure to Maintain Containment Closure During Fuel Movement as Required by TS 3.9.4.c. Attachment I to Ltr Identifies Actions Committed to by Plant in Encl LER1999-05-12012 May 1999 Forwards LER 99-004-00 Re Failure to Maintain Containment Closure During Fuel Movement as Required by TS 3.9.4.c. Attachment I to Ltr Identifies Actions Committed to by Plant in Encl LER ML20206Q8141999-05-11011 May 1999 Requests NRC Work with Industry to Resolve Generic Changes to Allow Permanent Change to TSs Prior to June 2000.Encl Provides TS Limited Duration Action Statement Until 990930 05000482/LER-1999-003, Forwards LER 99-003-00,re Failure to Perform TS SR 4.9.2.c Prior to Entering Mode 6.Commitments Made by Util Are Encl1999-05-10010 May 1999 Forwards LER 99-003-00,re Failure to Perform TS SR 4.9.2.c Prior to Entering Mode 6.Commitments Made by Util Are Encl ML20206K5141999-05-0707 May 1999 Provides Info Re Number of Tubes Plugged in Each Sg,As Required by TS 4.4.5.5.ISI of SGs B & C Completed on 990424,resulting in Mechanical Plugging of One Tube in SG B & Five Tubes in SG C ML20206J0711999-05-0505 May 1999 Forwards Guarantees of Payment of Deferred Premiums for Owners of Wolf Creek Generating Station,As Required by 10CFR140.21 ML20206D9551999-04-29029 April 1999 Forwards 1999 Annual Radioactive Effluent Release Rept 22, for Reporting Period Jan-Dec 1998,per Section 6.9.1.7 of WCGS Ts.Attachment to Ltr Identifies Commitments Resulting from Correspondence ML20206C7321999-04-22022 April 1999 Provides Notification of Changes at WCGS Affecting Plant Physical Security Plan,Per 10CFR50.54(p).Changes Identified in Attachment I Will Be Incorporated Into Plan by 990831. Commitments Made by Util Are Included in Attachment II ML20206B2051999-04-20020 April 1999 Forwards Revs to RERP Implementing Procedures,Including Rev 1 to EPP 06-001, CR Operations, Rev 1 to EPP 06-002, TSC Operations, Rev 3 to EPP 06-004, Public Info Organization & Rev 1 to EPP 06-005, Emergency.. ML20205L7431999-04-0606 April 1999 Confirms 990401 Telcon with NRC Re Late Payment Notice That Util Received for Invoice RL0295-99.Licensee Understands Invoice to Be Cancelled ML20205F1601999-03-30030 March 1999 Forwards Rept Re Status of Decommissioning Funding for WCGS, Per 10CFR50.75.Kansas Gas & Electric Co Decommissioning Trust Agreement,Encl ML20205K9481999-03-26026 March 1999 Responds to NRC Ltr Re Violations Noted in Insp Rept 50-482/98-05.Corrective Actions:Training Was Provided to Mrep Members Through Use of Contract Individual Experienced in Maint Rule Programs.Change to Commitment Date,Encl ML20196K7261999-03-26026 March 1999 Forwards Certified Copy of ITS & ITS Bases,As Committed in Licensee to Nrc.Summary of Editorial Corrections, Also Encl ML20205A1961999-03-25025 March 1999 Provides Suppl 2 to 970515 Application for Amend to License NPF-42,providing Changes to TS Based on 990310 & 19 Discussions with NRC Re Conversion to Improved TS 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 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 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) 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) 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 ML20058L2011990-08-0101 August 1990 Forwards Inadvertently Omitted Index of Proposed Tech Spec from Re RCS 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 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 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 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 ML20058K4011990-06-28028 June 1990 Forwards Emergency Preparedness 1990 Field Exercise Scenario for Exercise Scheduled for 900829 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 ML20043F4051990-06-11011 June 1990 Forwards Monthly Operating Rept for May 1990 & Corrected Page 2 for Apr 1990 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 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 ML20043E8721990-06-0505 June 1990 Notifies NRC of Changes in Status of Operator Licenses 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 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 ML20042E8691990-04-30030 April 1990 Forwards Documentation of Util Ability to Make Payment of Deferred Premiums 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 ML20012D9911990-03-22022 March 1990 Responds to NRC 900220 Ltr Re Violations Noted in Insp Rept 50-482/90-02.Corrective Actions:Procedure CNT-660, Rigging Revised to Incorporate safety-related Manway Covers Which May Be Removed W/O Addl Safety Evaluation ML20012C9841990-03-19019 March 1990 Provides Util Response to Generic Ltr 89-19 Re Request for Action on Resolution of USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants. Mods Made to ESFAS Logic Design ML20012C6841990-03-15015 March 1990 Responds to NRC 900213 Ltr Re Violations Noted in Insp Rept 50-482/89-26.Corrective actions:10CFR73.71,App G Reviewed to Determine If Any Reporting Requirements Not Properly Reflected in Security & Operations Procedures ML20012A1601990-02-23023 February 1990 Forwards Semiannual Radioactive Effluent Release Rept 10 for Jul-Dec 1989 & Rev 5 to ODCM for Wolf Creek Generating Station. ML20012A5631990-02-23023 February 1990 Forwards Total Pump Study & Revises Info Previously Provided on Safety Injection Pumps & Centrifugal Charging Pumps in Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. ML20006F7151990-02-21021 February 1990 Provides Present Levels of Onsite Property Damage Insurance Being Maintained,Per 10CFR50.54(w)(2) ML20012B0781990-02-14014 February 1990 Forwards Cycle 5 Radial Peaking Factor Limit Rept,Per Tech Spec Section 6.9.1.9 ML20006D6541990-02-0808 February 1990 Forwards Amend to Physical Security Plan.Proposed Change Will Require Submittal of Fingerprint Cards to NRC in Lieu of Currently Required Criminal Records Check.Proposed Changes & Safety Evaluation Withheld ML20006E3551990-02-0707 February 1990 Responds to NRC 900103 Ltr Re Violations Noted in Insp Rept 50-482/89-30.Corrective Actions:Communications Flow Process Between Facilities & Locations of Operations Status Boards Will Be Reviewed to Identify Needed Improvements ML20006E1871990-02-0707 February 1990 Advises That Bt Kckinney,Senior Reactor Operator,No Longer Employed at Util ML20011E1041990-01-30030 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Util Developed Plan & Schedule to Accomplish Reviews,Evaluations & Insps Recommended in Part IV ML19354E8831990-01-23023 January 1990 Forwards Response to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. ML20005G7791990-01-16016 January 1990 Forwards Monthly Operating Rept for Dec 1989 for Wolf Creek & Revised Operating Data Repts for Feb-Nov 1989,reflecting Thermal Generation Using New Calorimetric Procedure That Uses Main Steam Flow Instead of Feedwater Flow ML20006A0051990-01-16016 January 1990 Forwards Rev 25 to Facility Radiological Emergency Response Plan & Revs to Radiological Emergency Response Plan Implementing Procedures.Procedures Effective 891220 ML20005H1801990-01-15015 January 1990 Forwards Amend 4 to Indemnity Agreement B-99 ML20005E8591990-01-0404 January 1990 Certifies That Util Implemented fitness-for-duty Program That Meets Requirements of 10CFR26 ML20005E1921989-12-26026 December 1989 Affirms That Util Will Meet Schedule Requirements of Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. ML20011D4801989-12-20020 December 1989 Responds to NRC 891120 Ltr Re Violations Noted in Insp Rept 50-482/89-27.Corrective Actions:Personnel Completed Detailed Review of Tech Spec Surveillance Requirements to Ensure That Each Item Properly Addressed in Surveillance Procedures ML19332F8731989-12-14014 December 1989 Requests Authorization to Use ASME Section XI Code Case N-401-1, Eddy Current Exam,Section Xi,Div 1, Per 10CFR50.55a(a)(3),since Case Not Currently Listed in Reg Guide 1.147,Rev 7 as Endorsed by NRC ML19332F9131989-12-14014 December 1989 Notifies That DM Brown No Longer Employed at Facility as Senior Reactor Operator,Per 10CFR50.74 1990-09-18
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THE ELECTFMC COMPANY xansas cas ano siecraic couraar GLENN L MOESTER wett Pars'OENT NUCLE AR May 30, 1985 Mr. R.P. Denise, Director Wolf Creek Task Force U.S. melear Regulatory Comission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Mr. Barold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Conmission mshington, D.C. 20555 KMLNRC 85-140 Re: Docket No. SIN 50-482 Ref: 1) KMLNRC 85-031 dated 1/14/85 from GIKoester, KG&E, to RPDenise, NRC
- 2) KMLNRC 85-030 dated 1/14/85 from GIKoester, KG&E, to HRDenton, NRC Subj: Clarification Regarding Raceway and Cable Separation
Dear Gentlemen:
References 1 and 2 provided a response to Inspection Report 50-482/84-51 on cable separation and the marked up Wolf Creek Final Safety Analysis Report (FSAR) changed pages required by the response. In the process of incorporating the FSAR revisions included in Reference 2, KG&E has identified a need for further clarification.
The references did not point out that a limited amount of non-safety-related lighting, connunication, fire protection and speciality cable are not qualified to IEEE 383, but mcet its intent in one or more of the following ways: 1) exposed cables covered with flame retardant coatings; 2) installation in a i totally enclosed metal conduit system; 3) installation consisting of short lengths of exposed cable between the ends of a totally enclosed metal conduit system routed to a conponent and the connection to the cocponent (e.g. at light fixtures, piblic address devices and conpiter peripherals); 4) installation in non-safety-related areas separated from safety-related areas by fire boundaries; or 5) evaluation on a case-by-case basis for 00, adverse inpact on the fire protection program. ,
l 8506040169 850530 k PDR ADOCK 05000402 O PDR 201 N. Market - WicNta, Kansas - Mail Address: Ro. Box 208 i Wichta, Kansas 67201 - Telephone: Area Code (316) 2616451
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10DBC 85-140 May 30, 1985
! It has been verified that the power block and site-specific cable routing have no safety inpact resulting from the non-IEEE-383 qualified cables; therefore, there is no reduction in the level of protection provided' by the fire protection program as described in the FSAR.
Attactunent 1 provides a reivsed response to Inspection Report 482/84-51. Attachment 2 provides a revised PSAR markup which will be formally incorporated into the first update of the Nblf :
Creek FSAR. The information in Attachments 1 and 2 supercede the information provided by References 1 and 2.
If you have any questions, please contact Mr. Otto Maynard of my staff.
Yours very truly, Glenn L. Koester Vice President - NLx: lear GU:: dab xc: P0'Connor (2)
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STATE OF KANSAS )
) SS CITY OF WICHITA )
Glenn L. Koester, of lawful age, being first duly sworn upon oath says that he is Vice President - Nuclear and an Officer of Kansas Gas and Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said Company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
By _ M #
Glenn L. Koester Vice President - Nuclear SUBSCRIBED and sworn to before me this day of M , 198 k
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Attachment 1 VIOLATION 482/84-51: VIOLATION OF 10CFR50, APP. B, CRITERION III Finding:
10 CFR Part 50, Appendix B, Criterion III, requires that applicable regulatory requirements aM the design basis, as defined in 10 CFR 50.2 and as specified in the license application, are correctly translated into specifications, drawings, procedures, and instructions.
10 CFR 50.2 defines " design bases" as that information which identifies the specific functions to be performed by a structure, system, or component of a facility, aM the specific values or ranges of values chosen for controlling parameters as reference bounds for design.
Section ,8.3.1.4.1.1 of the license application specifies that cables from different separation groups will, in accordance with IEEE Standard 384-177 (SIC) practice, be in steel conduit or enclosed raceway or separated by a fire barrier when the normal 5-foot and 3-foot horizontal separation cannot be maintained.
Section 8.1.4.3 of the license application specifies that deviations from the IEEE Standard 384-1977 practice which reduce the minimum spatial separation between circuits be supported by analysis and, in accordance with the specified Regulatory Guide 1.75-1974, be considered part of the licensee's application.
Contrary to the above, a number of nonsafety conduits to safety cable trays and cables exiting the trays did not meet the spatial requirments for ,
cables frm different separation groups in accordance with your conmitment ,
to Regulatory Guide 1.75 and IEEE-384 nor was such deviation supported by an J analysis, as specified in the license application.
Revised Response:
a) Corrective steps which have been taken and results achieved:
Item 1. An analysis has been performed and the results are as follows:
'Ihe safety design basis is to protect the safety-related cables from failure of the non-safety-related circuits, and not vice-versa. In consideration of this limit, enclosing the non-safety circuits in conduit and maintaining at least 1 inch separation provides an acceptable level of protection. The conduit can contain only a limited quantity of combustible material (cable insulation & jacket) . Furthermore, there is insufficient oxygen inside the l conduit to support combustion of more than a fraction of the available material.
Cables are qualified to IEEE-383, except as noted below, and meet the flame retardant requirements specified within and, therefore, the cables will not support combustion. Certain non-safety-related communication, lighting, 1
n fire protection and other specialty cables (e.g. cords, couputer:-ribbon cable) are not qualified to IEEE-383, but are considered by MG&E to meet its intent-in one of.the following ways:
- 1) exposed cables covered with flame retardant coatings; 2)~ installation in a totally enclosed metal' conduit system; ..
3). installation consisting of short lengths of exposed cable between_the ends of a totally enclosed metal conduit systen routed to a component and-the connection to the couponent; 4)' installation in non-safety-related areas separated from safety-related areas by fire boundaries;
- 5) evaluation on a case-by-case basis for adverse impact on the fire protection program.
I Based on these considerations,-it is established that 1-inch separation .
l' 'between 'a conduit containing non-safety-related circuits and an open tray,
! containing safety-related circuits is sufficient to assure that any- failure within the ncn-safety-related circuits .will not propogate into and compromise the integrity of the safety-related circuits.
Itan 2. In accordance with Regulatory Gaide 1.75 this analysis will be-incorporated.into the Final Safety Analysis Report Section 8.1.4.3 L as described in Attachnent 2.
I It should also be noted that in Section 8.1.4.3 in the Final Safety Analysis Report that IEEE 384-1974 is consmitted to and not, according to Inspection Report 50-482/84-51, IEFE 384-1977.
i
} b) Corrective steps which will be taken to avoid further violation:
'Because of the corrective steps that have been taken in part a), KGEE
, will-- be in full conpliacce with licensing conunitments; therefore, no
! further corrective steps are necessary.
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! c) Date when full conpliance will be achieved:
'Ihe FSAR change to Section 8.1.4.3 is shown'in Attachment 2 and will be incorporated into the first update of the FSAR.
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! 2 S
Attut ,n r .1
. SNUPPS
- b. For cable trays of different separation groups, there is a minimum vertical separation of 5 feet:
between open-top trays stacked vertically. In the limited number of areas where trays of different separation groups are stacked with less than 5 feet of vertical separation, a fire barrier is placed between the two neparation groups. The barrier extends 1 foot to each side of the tray system (or to the wall).
- c. In the case where a tray of one separation group crosses over a tray of a different separation _ group and the vertical separation is less than 5 feet, a fire barrier is installed extending 1 foot from each side of each tray and 5 feet along each tray from the crossover.
- d. Where it is necessary that cables of different separation groups approach the same or adjacent control panels with less than 3-foot horizontal or 5-foot vertical spacing, isolation is maintained by installing both separation groups in steel conduit or enclosed wireway or by installing fire barriers betseen the separation groups. In the case of horizontal separation, the barrier extends 1 foot below the bottom of the tray (or to the floor) to I foot above the top of the tray (or to the ceiling).
In the case of vertical spacing, the barrier extends 1 foot on each side of the tray system (or to.the wall ) .'
- e. Isolation between separation groups is. considered to be adequate where physical separation is less than that indicated in Items a, b, and c above, provided the circuits of different separation groups are run in enclosed raceways that qualify as i
barriers or other barriers are installed.between
- the different separation groups. The minimum i
distance between these enclosed raceways and be -
, tween barriers and raceways is 1 inch. The bar-riers are instal ed as ase ' bed in a through d above.
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+ - -
CABLE SPREADING AREAS - The cabic spreading a.rea does not contain high energy equipment such as switchgear, trans-
- formers, rotating equipment, or potential sources of missiles or pipe whip and is not used for storing flammable materials.
I (circuits in the cable spreading area are limited to control t
and instrument functions and also those power supply circuits l
p r. . S 8.3-25 -4M
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e Attachment 2 INSERT A In cases of open trays containing-related cables and totally enclosed cor.duits containing non-safety related cables, the safety design basis is to protect the safety related cables from failure of the non-safety related circuits, and not vice-versa.
In consideration of this limit, enclosing the non-safety circuits in raceway and maintaining at least one inch separation provides an acceptable level of protection. The conduit can contain only a limited quantity of combustible material (cable insulation and jacket) . Furthermore, there is insuffient l
oxygen inside the conduit to support conbustion of more than a fraction of the available material.
Based on these considerations, it is established that one-inch separation between a conduit containing non-safety related circuits and an open tray containing safety related circuits is sufficient to assure that any failure within the non-safety related circuits will not propagate into and compromise the integrity of the safety related circuits.
SNUPPS APCSB 9.5-1 Appendix A SNUPPS
- When safety-related cables do not satisfy the safety-related cables satisfy the provisions of Regu-provisions of Regulatory Guide 1.75, all exposed latory Guide 1.75.
cables should be covered with an approved fire retardant coating and a fixed automatic water fire
- suppression system should be provided.
(d) Cable and cable tray penetration of fire barriers (d) Cable and cable tray penetration of fire barriers (vertical and horizontal) should be sealed to (vertical and horizontal) are sealed to give protection give protecticn at least equivalent to that fire at least equivalent to the barrier which they pene-barriers for horizontal and vertical cable trays trate. Typical horizontal and vertical cable tray should, as a minimum, meet the requirements of penetrations are tested to prevent the spread of fire and retain structural soundness when exposed to a ASTM E 119, " Fire Test of Building construction 3-hour fire as discussed in 9.5.1.2.2.
and Materials," including the hose stream test.
Where installed penetration seals are deficient with respect to fire resistance, these seals may be protected by covering both sides with an approved fire retardant material. The adequacy of using such material should be demonstrated by suitable testing.
(e) Fire breaks should be provided as deemed (e) Fire breaks are provided as decaed necessary by the necessary by the fire nazards analysis. Flame fire hazards analysis. The cable rating is compatible or fire retardant coatings may be used as a with the construction of the fire break. Refer to fire break for grouped electrical cables to Appendix 9.58 and Section 9.5.1.2.2.
limit spread of fire in cable ventings.
(Possible cable derating owing to use of such coating materials must be considered during design.)
(f) Elt ;trical cable constructions should as a (f) Electrical cable passes the IEEE 383-1974 flame test d"'
ei .2us pass the current IEEE No. 383 flame h /cef~ oC th-t. (This does not imply that cables passing cr m e e,-f y f4e_ v*c.q u e
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15
- test will not require additional fire protection.)
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For cable installation in operating plants and plants under construction that do not meet the IEEE No. 383 flame test requirements, all cables must be covered with an approved flame retardant coating and properly derated.
(g) To the extent practical cable construction that (g) See response to D.2(c) above, does not give off corrosive gases while burning should be used. (Applicable to new cable instal-lations.)
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SNUPPS APPENDIX 9.5B FIRE HAZARDS ANALYSIS SECTION TITLE / DESCRIPTION PAGE(S) 9.5B.1 Introduction 9.5B-1 through 9.5B-2 9.5B.2 Assumptions on Plant 9.5B-2 through'9.5B-3 Conditions 9.5B.3 Fire Effects on Electrical 9.5B-3 Equipment and Safe Shutdown Information 9.5B.4 General Information on 9.5B-3 through 9.5B-4 Design Features 9.5B.5 Combustible Loadings dra! 9.5B-4 through 9.5B-5 fir m s. :foreed 9.5B.6 Fire Hazards Review 9.5B-5 through 9.5B-7 Methodology Fire Area A-1 Auxiliary Building - El. 9.5B-8 through 9.5B-13 1974 to 1988, General
. Area, Rooms 1101-1106, 1115, 1120-1125, 1128-1130, 1201-1207, 1329 '
2 Auxiliary Building Safety- 9.5B-15 through 9.5B-18 Related Pump Area Rooms 1111-1114 3 Boric Acid Tank Rooms, 9.5B-19 through 9.5B-22 Rooms 1116, 1117, 1407 4 Auxiliary Building Safety- 9.5B-23 through 9.5B-26 Related Pump Area, Rooms 1107-1110 5 Auxiliary Building Stair- 9.5B-27 through 9.5B-28 way an.d Elevator (South),
Room 1119 6 Auxiliary Building Stair- 9.5B-29 through 9.5B-30 way (North), Room 1127 7 Boron Injection Tank and 9.3B-32 through 9.5B-33 Pump Room, Room 1126 Rena==44 9.5B-1 W
. AWehra x SNUPPS In most fire areas, the boundaries are defined by walls, floors, and ceilings. In the reactor building, however, such natural bound, aries do not completely enclose localized. fire hazards. For the fire areas inside of the containment, the provisions of Appendix R, Paragraphs III.G.2.d, e, and f were addressed. '
Where a fire barrier is indicated, penetration seals in the barrier are fire rated for the same or greater time period, unless otherwise indicated.
All areas of the plant protected with water suppression systems have sufficient drainage capacity to prevent the run-off of water into other fire areas. All drains through-out the plant drain to their respective building sumps. From there, sump pumps transfer the water to the radwaste system.
Smoke and heat are assumed to be removed from areas affected by a postulated fire by the plant HVAC systems until such time that the fire dampers are actuated. Flexible duct and portable fans would be used to remove the remaining smoke to allow access to the area, as required, for manual fire fighting. The smoke would be removed via the flexible duct to an operable plant exhaust.
Equipment need times used in the fire hazards analysis are not absolute requirements and are listed to demonstrate that adequate time is available for operator action.
Emergency lighting is provided for areas which must be manned for safe shutdown and for access and egress to fire areas.
It consists of scaled beam units with individual 8-hour minimum battery power supplies.
9.5B.5 COMBUSTIBLE LOADINCS AND FL AME Sf#r4 9 Combustible loadings were determined for each room in the fire area through a review of design drawings. For each fire area, only those rooms which contain fixed or transient combustible materials and/or safe shutdown equipment are listed in the analysis. Other rooms are located and identi-fied on the figures. The term " negligible" is used where no measurable quantity of fixed combustible material has been identified.
Although fire hazard effects on exposed conduits have been evaluated for safe shutdown, electric cable inside metal conduit has not been considered as contributing to the fire loading in the hazard areas.
-nc.. 14 9.58-4 9/e+
Mha .,,t1 e; . SNUPPS' Noncombustible materials are defined to meet one of the following criteria:
. a. Material. of which no part will burn.
.' b' . -
Surface materials not over 1/16-inch thick.with a flame spread rating of 50 or .less aus measured by -
ASTM E 84-1976.
- c. Interior finishes which meet a. or are listed by an.
approved organization for surface flame spread of 25 or less per ASTM E 84-1976 and potential heat release of 3,500 Btu /lb or less per ASTM D 3286-1973.
The fixed combustible loading is based on the total floor area of. each room. Unless indicated otherwise, the. specific location of combustible material within a room is not a significant factor in the analysis.
A _significant amount of the fixed combustibles in the plant is electric cable insulation. The specific calorific value-for each type and size of cable was used in calculating the maximum heat loading for each fire area. The following are
/
//4 / *a+ cable insulation types used in the plant and their heat of combustion: l Insulation Range of Heat Type of Combustion Supplier FR(HC711) 8,700 - 13,100 Btu /ft Kerite NS(H170) 8,450 - 23,600 Btu /ft Kerite XLPE 90 Btu /ft Rockbestos .
Neoprene 630 - 4,390 Btu /ft Rockbestos' Hypalon. 645 - 8,070 Btu /ft Anaconda Hypalon 490 - 5,080 Btu /ft BIW -
Hypalon 950 Btu /ft Brand Rex Hypalon 370 - 2,385 Btu /ft Samuel Moore & Co.
- All' safety-related cable in the general plant area is qualified to'IEEE 383-1974. All single conductors inside control a
els meet the flame resistance requirements of I,CEA S-19-81 A bN P Transient combustibles are estimated based on maintenance ande,. g. 4 -yo A
- o operations requirements. Their heat loading contribution to an area is not quantified, but they are considered as a means by which an exposure fire could occur.
9.5B.6 FIRE HAZARDS REVIEW MET!!ODOLOGY The SNUPPS fire hazards analysis, originally conducted in 1977, has been updated periodically as the design of the plant has been finalized. The most recent update reflects
- ... L
9.5B-5 Sy4 4-
~
.- Attachment 2 INSERT B Lighting, fire. protection, communication and specialty cables which are flame retardant but not qualified to IEEE-383-1974; and other communication and specialty cable (e.g cords and computer ribbon cable), are limited in use in the following manner: -
A. Covered with a flame retardant coating per the requirements of (BTP) APCSB 9.5-1, Appendix A;
.B. installed in a totally enclosed metal conduit system; C. consist of short lengths of exposed cable between the end of a totally enclosed metal conduit system routed to a component and the connection to the component (e.g.
at light fixtures 3end public address devices);^
sna es.,pr e p seipho sis D. located in non-safety related areas which are separated from safety related areas by fire rated boundaries; or E. evaluated on a case-by-case basis for adverse impact on the fire' protection program.