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| | number = ML20137C208 | | | number = ML20137C208 |
| | issue date = 03/20/1997 | | | issue date = 03/20/1997 |
| | title = Ack Completion of Licensing Action of GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217 & Requests to Retain All Documentation Related for Future NRC Audits & Insp | | | title = Ack Completion of Licensing Action of GL 92-08, Thermo-Lag 330-1 Fire Barriers, & Requests to Retain All Documentation Related for Future NRC Audits & Insp |
| | author name = Stone J | | | author name = Stone J |
| | author affiliation = NRC (Affiliation Not Assigned) | | | author affiliation = NRC (Affiliation Not Assigned) |
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| | contact person = | | | contact person = |
| | document report number = GL-92-08, GL-92-8, TAC-M85625, NUDOCS 9703240178 | | | document report number = GL-92-08, GL-92-8, TAC-M85625, NUDOCS 9703240178 |
| | | title reference date = 12-17-1992 |
| | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | page count = 4 | | | page count = 4 |
| | | project = TAC:M85625 |
| | | stage = Other |
| }} | | }} |
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| : 3. Modifications to reroute wrapped conduits and raceways, or | | : 3. Modifications to reroute wrapped conduits and raceways, or |
| : 4. Replace existing Thermo-Lag 330-1 with Darmatt KM-1. This includes the radiant energy heat shield used inside containment. | | : 4. Replace existing Thermo-Lag 330-1 with Darmatt KM-1. This includes the radiant energy heat shield used inside containment. |
| By letter dated February 3, 1997, you stated that the corrective actions had been completed at the Wolf Creek Generating Station and that Thermo-Lag is no longer relied on to satisfy WCNOC's commitment to 10 CFR 50, Appendix R. On the basis of its review, the staff has determined that you have provided the information requested in GL 92-08 and the actions tracked by TAC No. M85625 are complete. | | By {{letter dated|date=February 3, 1997|text=letter dated February 3, 1997}}, you stated that the corrective actions had been completed at the Wolf Creek Generating Station and that Thermo-Lag is no longer relied on to satisfy WCNOC's commitment to 10 CFR 50, Appendix R. On the basis of its review, the staff has determined that you have provided the information requested in GL 92-08 and the actions tracked by TAC No. M85625 are complete. |
| For other issues related to Thermo-Lag, WCNOC committed to take the following | | For other issues related to Thermo-Lag, WCNOC committed to take the following |
| ; actions: 3 | | ; actions: 3 |
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| : 2. With respect to ampacity issues, vendor-supplied ampacity derating factors would be utilized for any Darmatt KM-1 material installed to replace Thermo-Lag. | | : 2. With respect to ampacity issues, vendor-supplied ampacity derating factors would be utilized for any Darmatt KM-1 material installed to replace Thermo-Lag. |
| : 3. For Thermo-Lag that is left installed in the plant, the material would be evaluated and added to the combustible loading for the applicable i fire areas, using industry-developed heat release values for the I material. Also, the plant Fire Hazards Analysis would be updated with the new combustible loading values. | | : 3. For Thermo-Lag that is left installed in the plant, the material would be evaluated and added to the combustible loading for the applicable i fire areas, using industry-developed heat release values for the I material. Also, the plant Fire Hazards Analysis would be updated with the new combustible loading values. |
| By letter dated February 3, 1997, you stated that the above corrective actions for the resolution of the Thermo-Lag issues not related to 10 CFR 50 Appendix R, had been implemented at the Wolf Creek Generating Station. | | By {{letter dated|date=February 3, 1997|text=letter dated February 3, 1997}}, you stated that the above corrective actions for the resolution of the Thermo-Lag issues not related to 10 CFR 50 Appendix R, had been implemented at the Wolf Creek Generating Station. |
| The March 10, 1995, June 20, 1996 and August 23, 1996, responses forwarded information on ampacity derating of Thermo-Lag 330-1 which emerged as a result of the GL 92-08 review. The staff is continuing to review the issue of , | | The March 10, 1995, June 20, 1996 and August 23, 1996, responses forwarded information on ampacity derating of Thermo-Lag 330-1 which emerged as a result of the GL 92-08 review. The staff is continuing to review the issue of , |
| ampacity derating. The resolution of these ampacity derating issues are being treated generically and tracked by TAC No. M82809. You will be informed when the staff has completed its review. | | ampacity derating. The resolution of these ampacity derating issues are being treated generically and tracked by TAC No. M82809. You will be informed when the staff has completed its review. |
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| : 3. For Thermo-Lag that is left installed in the plant, the material would l be evaluated and added to the combustible loading for the applicable l fire areas, using industry-developed heat release values for the , | | : 3. For Thermo-Lag that is left installed in the plant, the material would l be evaluated and added to the combustible loading for the applicable l fire areas, using industry-developed heat release values for the , |
| material. Also, the plant Fire Hazards Analysis would be updated with l the new combustible loading values. | | material. Also, the plant Fire Hazards Analysis would be updated with l the new combustible loading values. |
| 4 By letter dated February 3, 1997, you stated that the above corrective actions for the resolution of the Thermo-Lag issues not related to 10 CFR 50 Appendix R, had been completed at the Wolf Creek Generating Station. | | 4 By {{letter dated|date=February 3, 1997|text=letter dated February 3, 1997}}, you stated that the above corrective actions for the resolution of the Thermo-Lag issues not related to 10 CFR 50 Appendix R, had been completed at the Wolf Creek Generating Station. |
| The March 10, 1995, June 20, 1996 and August 23, 1996, responses forwarded information on ampacity derating of Thermo-Lag 330-1 which emerged as a result of the GL 92-08 review. The staff is continuing to review the issue of ampacity derating. The resolution of these ampacity derating issues are being 2 | | The March 10, 1995, June 20, 1996 and August 23, 1996, responses forwarded information on ampacity derating of Thermo-Lag 330-1 which emerged as a result of the GL 92-08 review. The staff is continuing to review the issue of ampacity derating. The resolution of these ampacity derating issues are being 2 |
| treated generically and tracked by TAC No. M82809. You will be informed when the staff has completed its review. | | treated generically and tracked by TAC No. M82809. You will be informed when the staff has completed its review. |
Letter Sequence Other |
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MONTHYEARML20059B0841993-12-22022 December 1993 Forwards RAI Re GL-92-08, Thermo-Lag 330-1 Fire Barriers, Per 10CFR50.54(f) for Plant.Requests Addl Info on Configurations & Amounts of Thermo-Lag Fire Barriers Installed in Plant & Cable Loadings Project stage: RAI ML20073R9971994-02-0909 February 1994 Forwards Response to NRC 931222 RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers Project stage: Other ML20070G7081994-07-15015 July 1994 Responds to Request for Addl Info Re GL 92-08,Thermo-Lag 330-1 Fire Barriers,Issued on 941222 Project stage: Request ML20078S7891994-12-22022 December 1994 Responds to 940923 Request for Addl Info Re GL 92-08 Concerning Thermo-Lag Fire Barrier Protection Sys Project stage: Request ML20086A6481995-06-27027 June 1995 Forwards Suppl Response to NRC 941229 follow-up to RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers & Rept from Nucon Intl,Inc, Pyrolysis Gas Chromatography Analysis of 5 Thermo-Lag Fire Barrier Samples Project stage: Other ML20137C2081997-03-20020 March 1997 Ack Completion of Licensing Action of GL 92-08, Thermo-Lag 330-1 Fire Barriers, & Requests to Retain All Documentation Related for Future NRC Audits & Insp Project stage: Other 1994-02-09
[Table View] |
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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:OUTGOING CORRESPONDENCE
MONTHYEARML20217F7481999-10-14014 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20209A7461999-06-29029 June 1999 Informs of Changes in Project Mgt Staff Assigned to Wcgs. Effective 990628,J Donohew Will Assume PM Responsibilities ML20195G3451999-06-0909 June 1999 Ack Receipt of Ltr Dtd 990105,which Transmitted Wolf Creek Emergency Plan Form Apf 06-002-01 Emergency Action Levels, Rev 0,dtd 990105,under Provisions of 10CFR50,App E,Section V.No Violations of 10CFR50.54(q) Identified During Review ML20195D5111999-06-0202 June 1999 Forwards Safety Evaluation Authorizing Inservice Inspection Program Alternative for Limited Reactor Vessel Shell Weld Exam & Relief Request from Requirements of ASME Code,Section XI for Wolf Creek Generating Station ML20207E2791999-05-25025 May 1999 Announces Corrective Action Program Insp at Wolf Creek Reactor Facility,Scheduled for 990816-20.Insp Will Evaluate Effectiveness of Activities for Identifying,Resolving & Preventing Issues That Degrade Quality of Plant Operations ML20207A8681999-05-25025 May 1999 Informs That NRC Ofc of NRR Reorganized Effective 990328. as Part of Reorganization,Division of Licensing Project Mgt Created ML20207A3491999-05-21021 May 1999 Forwards Insp Rept 50-482/99-03 on 990321-0501.Four NCVs Noted ML20206H3901999-05-0707 May 1999 Informs That on 990407,NRC Administered Generic Fundamentals Exam Section of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However Copy of Master Exam with Answer Key Encl for Info.Without Encl ML20206H5941999-05-0505 May 1999 Forwards Insp Rept 50-482/99-04 on 990405-09.No Violations Noted.Scope of Inspection Included Review of Implementation of Licensee Inservice Insp Program for Wolf Creek Facility Refueling Outage 10 ML20206H2891999-04-30030 April 1999 Forwards Exemption from Requirements of 10CFR50.60, Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation, for Wcgs.Exemption Related to Application ML20205L8541999-04-0909 April 1999 Forwards Insp Rept 50-482/99-02 on 990207-0320.Five Violations Identified & Being Treated as Noncited Violations ML20205J3371999-04-0606 April 1999 Forwards Request for Addl Info Re Wolf Creek Generating Station IPEEE & 971208 Response to RAI from NRC Re Ipeee. RAI & Schedule for Response Were Discussed with T Harris on 990405 ML20205K4451999-04-0303 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/98-05 & of Need for Larger Scope of Review for Planned C/As for Violation 50-482/98-05,which Requires Extending Completion Time ML20205H7091999-04-0202 April 1999 Discusses 990325 Meeting at Plant in Burlington,Ks to Discuss Results of PPR Completed on 990211 ML20205G5851999-04-0101 April 1999 Forwards RAI Re Licensee 960214 Submittal of 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant. Response Requested within 120 Days of Receipt of Ltr ML20205C2101999-03-26026 March 1999 Informs That NRC Staff Reviewed WCNOC 960918,970317 & 980429 Responses to GL 96-05, Periodic Verification of Design- Basis Capability of Safety-Related Movs. Forwards RAI Re MOV Program Implemented at Wolf Creek Generating Station ML20204H7571999-03-23023 March 1999 Discusses WCNOC 990202 Proposed Rev to Response to GL 81-07, Control of Heavy Loads, for Wcgs.Rev Would Make Reactor Building Analyses Consistent with TS & Change Commitment Not to Allow Polar Crane Hook Over Open Rv.Revs Approved ML20205A4221999-03-19019 March 1999 Advises of Planned Insp Effort Resulting from Wolf Creek Plant Performance Review for Period 980419-990125. Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 8 Months Encl ML20207L5941999-03-0404 March 1999 Informs That Staff Accepts Util 981210 Requested Approval for Use of ASME Code,Section III Code Case N-611, Use of Stress Limits as Alternative to Pressure Limits,Section III, Div 1,Subsection NC/ND-3500, for Certain Valve Components ML20207F3121999-03-0303 March 1999 Informs That Info Provided in Entitled, Addl Info Requested for Topics Discussed During Oct 14-15 Meeting, from Wcnoc,Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) ML20207F4491999-03-0303 March 1999 Forwards Signed Copy of Updated Computer Access & Operating Agreement Between NRC & Wcnoc,Per ML20207F0411999-02-26026 February 1999 Informs That KM Thomas Will Resume Project Mgt Responsibilities for Wcngs,Effective 990301 ML20206U6131999-02-0202 February 1999 Forwards Draft SER on Proposed Conversion of Current TSs for Wolf Creek Generating Station to Improved Tss.Encl Draft SER Being Provided for Review to Verify Accuracy & to Prepare Certified Improved TSs ML20202B7391999-01-26026 January 1999 Forwards Insp Rept 50-482/99-01 on 990111-14.No Violations Noted.Nrc Understands That During 990114 Exit Meeting,Vice President,Operations/Chief Operating Officer Stated That Util Would Revise Security Plan ML20199H4671999-01-15015 January 1999 Forwards Insp Rept 50-482/98-20 on 981115-1226.No Violations Noted.Conduct at Wolf Creek Generally Characterized by safety-conscious Operations & Sound Maintenance Activities ML20199B0591999-01-11011 January 1999 Forwards Y2K Readiness Audit Rept for Wolf Creek Nuclear Generating Station.Purpose of Audit Was to Assess Effectiveness of Wolf Creek Nuclear Operating Corp Programs for Achieving Y2K Readiness ML20199A0991998-12-29029 December 1998 Informs That on 981202,NRC Staff Completed Insp Planning Review (Ipr) of WCGS & Advises of Planned Insp Effort Resulting from Ipr.Forwards Historical Listing of Plant Issues,Referred to Plant Issues Matrix IR 05000482/19980121998-12-18018 December 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/98-12.NRC Have Withdrawn Violation 50-482/98-12-02 for First Example Re Procedure AP 05-0001 ML20198B2701998-12-16016 December 1998 Informs That Staff Has Incorporated Rev of Bases for TS 3/4.7.1.2, Afs Into WCGS Tss,Per 981108 Request.Rev Specifies Essential SWS Requirements for turbine-driven Afs. Overleaf Pages Provided to Maintain Document Completeness ML20196K0321998-12-0808 December 1998 Informs That Staff Has Incorporated Rev of Bases for TS 3/4.4.4, Relief Valves, Requested by .Rev Clarifies Bases to Be Consistent with Amend 63 to Wolf Creek TSs .Rev Acceptable.Bases Page Encl 1999-09-29
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+ *'%
et
) y NUCLEAR REGULATORY COMMISSION
- I o & WASHINGTON, D.C. 20006-0001
'% March 20,1997 Mr. Otto L. Maynard President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, Kansas 66839
SUBJECT:
COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 92-08,
" THERM 0-LAG 330-1 FIRE BARRIERS," DATED DECEMBER 17, 1992, i
WOLF CREEK GENERATING STATION (TAC NO. M85625)
Dear Mr. Maynard:
By letters dated April 16, 1993, February 9, 1994, July 15, 1994, December 22, 1994, February 15, 1995, March 10, 1995, March 29, 1995, June 27, 1995, June 20, 1996, August 2, 1996, August 23, 1996, and February 3,1997, Wolf Creek Nuclear Operating Corporation (WCN0C) responded to Generic Letter (GL) 92-08, "Thermo-Lag 330-1 Fire Barriers," dated December 17, 1992, and follow-up requests for additional information dated May 24, 1993, June 15, 1993, December 22, 1993, September 23, 1994, December 29, 1994, May 21, 1996, and July 2,1996, in regard to Thermo-Lag 330-1 fire barriers installed at the Wolf Creek Generating Station.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed your letters.
- Your responses stated that one of the following actions would be completed for l Thermo-Lag conduit and raceway applications installed to satisfy commitments '
to 10 CFR 50, Appendix R:
- 1. An analysiT te document that the fire barrier wrap on the raceway is not required to u hieve safe shutdown,
- 2. Modifications to the plant such that the fire wrap on the raceways would no longer be required for 2,afe shutdown,
- 3. Modifications to reroute wrapped conduits and raceways, or
- 4. Replace existing Thermo-Lag 330-1 with Darmatt KM-1. This includes the radiant energy heat shield used inside containment.
By letter dated February 3, 1997, you stated that the corrective actions had been completed at the Wolf Creek Generating Station and that Thermo-Lag is no longer relied on to satisfy WCNOC's commitment to 10 CFR 50, Appendix R. On the basis of its review, the staff has determined that you have provided the information requested in GL 92-08 and the actions tracked by TAC No. M85625 are complete.
For other issues related to Thermo-Lag, WCNOC committed to take the following
- actions
- 3
\) O\l 9703240178 970320 2
. PDR ADOCK 0500
Mr. Otto L. Maynard March 20, 1997 1
i
- 1. With respect to Thermo-Lag installed to achieve physical independence between electrical systems associated with the Class 1E power system, WCNOC would document that the existing .Thermo-Lag installations satisfy the requirements of~IEEE 384-74.
- 2. With respect to ampacity issues, vendor-supplied ampacity derating factors would be utilized for any Darmatt KM-1 material installed to replace Thermo-Lag.
- 3. For Thermo-Lag that is left installed in the plant, the material would be evaluated and added to the combustible loading for the applicable i fire areas, using industry-developed heat release values for the I material. Also, the plant Fire Hazards Analysis would be updated with the new combustible loading values.
By letter dated February 3, 1997, you stated that the above corrective actions for the resolution of the Thermo-Lag issues not related to 10 CFR 50 Appendix R, had been implemented at the Wolf Creek Generating Station.
The March 10, 1995, June 20, 1996 and August 23, 1996, responses forwarded information on ampacity derating of Thermo-Lag 330-1 which emerged as a result of the GL 92-08 review. The staff is continuing to review the issue of ,
ampacity derating. The resolution of these ampacity derating issues are being treated generically and tracked by TAC No. M82809. You will be informed when the staff has completed its review.
You should retain all documentation related to the resolution of the concerns with Thermo-Lag 330-1 fire barrier systems for future NRC audits or inspections, j
~
If you have any questions regarding this matter, please contact me at (301) ,
415-3063. !
Sincerely, Original Signed By James C. Stone, Senior Project Manager 1 Project Directorate IV-2 ;
Division of Reactor Projects III/IV l Office of Nuclear Reactor Regulation Docket No. 50-482 DISTRIBUTION:
Docket File EPeyton cc: See next page PUBLIC WBateman PDIV-2 Reading JStone !
JRoe ACRS ,
EAdensam TMarsh OGC JCalvo D0udinot LTran AHowell, RIV WJohnson, RIV DOCUMENT NAME: 85625CLO.WC *See Previous Concurrence OFC PDIV-2/PMh PDIV-2/LA' NRR:SPLB* NRR:EELB* .
NAME JStone:ye E TMarsh -JCalvo DATE 3/%/97 340/97 3/19/97 3/12/97 0FFICIAL RECORD COPY
l 5 Mr. Otto L. Maynard March 20, 1997
- 1. With respect to Thermo-Lag installed to achieve physical independence between electrical systems associated with the Class IE power system, ;
j WCNOC would document that the existing Thermo-Lag installations satisfy the requirements of IEEE 384-74.
- 2. With respect to ampacity issues, vendor-supplied ampacity derating factors would be utilized for any Darmatt KM-1 material installed to replace Thermo-Lag.
- 3. For Thermo-Lag that is left installed in the plant, the material would l be evaluated and added to the combustible loading for the applicable l fire areas, using industry-developed heat release values for the ,
material. Also, the plant Fire Hazards Analysis would be updated with l the new combustible loading values.
4 By letter dated February 3, 1997, you stated that the above corrective actions for the resolution of the Thermo-Lag issues not related to 10 CFR 50 Appendix R, had been completed at the Wolf Creek Generating Station.
The March 10, 1995, June 20, 1996 and August 23, 1996, responses forwarded information on ampacity derating of Thermo-Lag 330-1 which emerged as a result of the GL 92-08 review. The staff is continuing to review the issue of ampacity derating. The resolution of these ampacity derating issues are being 2
treated generically and tracked by TAC No. M82809. You will be informed when the staff has completed its review.
You should retain all documentation related to the resolution of the concerns with Thermo-Lag 330-1 fire barrier systems for future NRC audits or inspections.
3 If you have any questions regarding this matter, please contact me at (301) 415-3063.
Sincerely, l
[
James C. Stone, Senior Project Manager l Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nucles Peactor Regulation Docket No. 50-482 cc: See next page l
l l 1
s
. l 4
o Mr. Otto L. Maynard March 20, 1997 4 cc:
Jay Silberg, Esq. Chief Operating Officer Shaw, Pittman, Potts & Trowbridge Wolf Creek Nuclear Operating Corporation 2300 N Street, NW P. O. Box 411 Washington, D.C. 20037 Burlington, Kansas 66839 Regional Administrator, Region IV Supervisor Licensing U.S. Nuclear Regulatory Commission Wolf Creek Nuclear Operating Corporation 611 Ryan Plaza Drive, Suite 1000 P.O. Box 411 Arlington, Texas 76011 Burlington, Kansas 66839 Senior Resident Inspector U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident Inspectors Office !
P. O. Box 311 8201 NRC Road Burlington, Kansas 66839 Steedman, Missouri 65077-1032 Chief Engineer Utilities Division i Kansas Corporation Commission 1500 SW Arrowhead Road Topeka, Kansas 66604-4027
. Office of the Governor State of Kansas Topeka, Kansas 66612 Attorney General Judicial Center 301 S.W. 10th 2nd Floor Topeka, Kansas 66612 County Clerk l
Coffey County Courthouse l Burlington, Kansas 66839 Public Health Physicist Bureau of Air & Radiation i Division of Environment Kansas Department of Health and Environment Forbes Field Building 283 i Topeka, Kansas 66620 4 4
i I
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