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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:NRC TO UTILITY
MONTHYEARIR 05000482/19900261990-11-14014 November 1990 Ack Receipt of Responding to NRC Requesting Addl Info Concerning 900731 Notice of Violation from Insp Rept 50-482/90-26 IR 05000482/19900341990-11-0909 November 1990 Forwards Notice of Violation Re Insp Rept 50-482/90-34 & Summary of Enforcement Conference on 901106 ML20058D7601990-11-0101 November 1990 Forwards Summary of Staff Understanding of Current Status Re GSIs Remaining Unimplemented at Facility,Per GL-90-04 ML20058E1391990-10-26026 October 1990 Forwards Final SALP Rept 50-482/90-14 on 900401-0630 ML20058B2831990-10-23023 October 1990 Forwards Insp Rept 50-482/90-34 on 900926-1005.Violations Noted ML20062C9971990-10-19019 October 1990 Forwards Insp Rept 50-482/90-31 on 900801-0914 & Notice of Violation ML20058A3621990-10-18018 October 1990 Advises That Util 900925 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2, Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable ML20059P0671990-10-15015 October 1990 Ack Receipt of Requesting Withdrawal of Request for Relief Re Procurement of ASME Section III Matls ML20062B3081990-10-0505 October 1990 Forwards Insp Rept 50-482/90-30 on 900730-0810.Violations Noted But Not Cited.Four Open Items Identified ML20059N3091990-10-0101 October 1990 Forwards Insp Rept 50-482/90-28 on 900701-31 & Notice of Violation ML20059M6851990-09-28028 September 1990 Ack Receipt of 900830 Response to Violations Noted in Insp Rept 50-482/90-26.Addl Info Re Troubleshooting Required ML20059M0451990-09-27027 September 1990 Requests Addl Info Re Seismic Design Consideration for safety-related Vertical Steel Tanks.Info Needed within 90 Days Following Receipt of Ltr ML20059J3541990-09-11011 September 1990 Forwards Initial SALP Rept 50-482/90-14 for Apr 1989 - June 1990.Areas of Operations,Radiological Controls,Maint/ Surveillance & Engineering/Technical Support Rated Category 2,while Area of Security & Emergency Remained Category 1 ML20059C4171990-08-23023 August 1990 Accepts Util 890531 Response to NRC Bulletin 88-011 Re Surge Line Stratifiction.Nrc Topical Rept Evaluation Encl ML20059A7431990-08-14014 August 1990 Ack 900808 Visit to Region IV & Info Re Status of Actions on Recent Kansas City Power & Light Co Offer to Purchase Kansas Gas & Electric Co.Util Assurance That Offer to Purchase Will Have No Effect on Safety Operations of Importance to NRC ML20058P2581990-08-14014 August 1990 Ack Receipt of Transmitting Scenario for Upcoming Annual Exercise.Nrc Understands That Util Taking Actions to Resolve Concerns Expressed in FEMA 900727 Memo ML20058P2421990-08-13013 August 1990 Forwards Insp Rept 50-482/90-23 on 900507-11 & 0629-0703 & Notice of Violation.No Response to Violation Required Due to Corrective Action Implemented Prior to Inspectors Departure IR 05000482/19900241990-08-0606 August 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/90-24.Responses to Training Violation & Unresolved Item Re Min Protective Action Recommendations Responsive to Insp Rept Concerns ML20055J4891990-07-31031 July 1990 Advises That NRC Form 474, Simulation Facility Certification, Submitted on 900110,complete & Requires No Further Info.Simulation Facility Acceptable for Purposes of 10CFR55.31(a)(4) Based on Certification of Facility ML20055J4881990-07-31031 July 1990 Discusses Util 891226 Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance ML20056A2851990-07-31031 July 1990 Forwards Insp Rept 50-482/90-26 on 900601-30 & Notice of Violation.Violation Re Failure to Update Info Into Updated FSAR Noted But Not Cited ML20056A1731990-07-30030 July 1990 Advises That Requalification Program Evaluation Scheduled at Plant Site During Wks of 901022 & 29.Util Requested to Furnish Approved Items Listed in Encl 1.Failure to Supply Ref Matl May Result in Postponement of Exam ML20058L3311990-07-27027 July 1990 Summarizes 900724 Meeting W/Util in Region IV Ofc Re Changes to Operator Licensing Program.Meeting Agenda,Attendance List & Viewgraphs Encl ML20055J3971990-07-24024 July 1990 Requests Addl Info Re Steam Generator Tube Rupture Operator Action Times for Plant.Response Requested within 30 Days of Receipt of Ltr IR 05000482/19900171990-07-19019 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/90-17 ML20059N8021990-07-10010 July 1990 Ack Receipt of Transmitting Objective & Guidelines for Upcoming Emergency Preparedness Exercise. Util Exercise Scenario,Submitted on 900628,currently Under Review ML20055F6251990-07-0909 July 1990 Forwards Summary of 900626 Meeting W/Util in Region IV Ofc Re Licensee Performance During Latest Refueling Outage. Attendance List Encl ML20055D9881990-07-0505 July 1990 Forwards Insp Rept 50-482/90-25 on 900611-15.No Violations or Deviations Noted.One Unresolved Item Noted ML20055D9531990-07-0505 July 1990 Forwards Insp Rept 50-482/90-22 on 900501-31.Noncited Violation Noted.One Unresolved Item Identified IR 05000482/19900051990-07-0505 July 1990 Ack Receipt of 900629 & 0413 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/90-05 ML20058K3611990-06-26026 June 1990 Forwards Insp Rept 50-482/90-24 on 900514-18 & Notice of Violation.Unresolved Items Noted Re Discrepancy Between Emergency Plan & Emergency Plan Implementing Procedures Re Min Protective Action Recommendations During Emergency IR 05000482/19900161990-06-26026 June 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/90-16 ML20055C7671990-06-18018 June 1990 Forwards Insp Rept 50-482/90-27 on 900604-08.No Violations or Deviations Noted ML20059M9091990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248C6401989-09-27027 September 1989 Forwards Insp Rept 50-482/89-25 on 890911-25.No Violations Noted or Deviations Identified ML20248E7801989-09-21021 September 1989 Forwards Amend 4 to Indemnity Agreement B-99.Amend Increases Primary Nuclear Energy Liability Insurance.Util Requested to Submit Signed Amend to Signify Acceptance ML20247N1671989-09-20020 September 1989 Forwards Safety Evaluation Re Plant First 10-yr Inservice Testing Program & Requests for Relief Re Reclassification of 16 Valves from Passive to Active & Clarification of Cold Shutdown Justification ML20247M9531989-09-19019 September 1989 Forwards Insp Rept 50-482/89-22 on 890828-0901.No Violations Noted ML20247K0501989-09-14014 September 1989 Forwards Insp Rept 50-482/89-23 on 890801-31.No Citation for Violation Described in Paragraph 3 Issued,Per Section V.G.1 of NRC Enforcement Policy IR 05000482/19890051989-09-0606 September 1989 Ack Receipt of 890531 & 0831 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-482/89-05 ML20247B1931989-08-30030 August 1989 Forwards Summary of Region Iv/Senior Util Executives Meeting on 890818 in Arlington,Tx.Topics Discussed Included, Improving Communications,Salp Process in Region IV & Enforcement.List of Attendees & Agenda Encl ML20246F9131989-08-21021 August 1989 Forwards Request for Addl Info Re 880620 Proposed Revs to Tech Specs 3/4.4.9.1 & 3/4.4 9.3, RCS Pressure/Temp Limits & Overpressure Protection Sys, Respectively ML20246D6441989-08-17017 August 1989 Informs That Request to Withdraw Application for Amend to License NPF-42 Granted ML20245J6031989-08-14014 August 1989 Advises That Licensing Exams Scheduled for Wk of 891120.Ref Matl Listed on Encl Should Be Provided by 890920. Procedures for Administration of Written Exams Also Encl ML20245H2921989-08-0808 August 1989 Forwards Insp Rept 50-482/89-21 on 890701-31.No Violations or Deviations Noted ML20248A2171989-07-31031 July 1989 Forwards Summary of 890623 Meeting at Facility to Discuss SALP for Apr 1988 - Mar 1989 & Util 890721 Response to SALP Rept.Viewgraphs Also Encl ML20247N7251989-07-31031 July 1989 Concurs That Requirements of License Condition 2.C.(7), Attachment 3,Item (2) Re Emergency Response Capabilities Have Been Met,Based on Review of Util & on Past Emergency Preparedness Insps 1990-09-28
[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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MAR - 91989
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In Reply Refer To:
Docket: STN 50-482/88-32 Wolf Creek Nuclear Operating Corporation ATTN: Bart D. Withers President and Chief Executive Officer P.O. Box 411 .
Burlington, Kansas 66839 Gentlemen:
Thank you for your. letters of February 13 and 28,1989, in response to our letter and Notice of Violation dated January 12, 1989. We have reviewed your .
replies and find them responsive to the concerns raised in our Notice of Violation. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and ,
will be maintaine
Sincerely, Original Signed lly A. D. Beach L. J. Callan, Director Division of Reactor Projects cc:
Wolf Creek Nuclear Operating Corporation ATTN: Otto Maynard, Manager of Licensing P.O. Box 411 Burlington, Kansas 66839 (cc's continued)
1 RI RPS:RPB FRPS:RPB C:SEPS:R C:RPB C:RPS/D :D Pg DChaney/ sir LRicketson' 'RBaer BMur Holler $Nn 0;/]/89 3/fr/89 J/gp/89 4]/, ray
/89 3/7/89 } /i /89 s903160448 800309 ADOCK 0500 2 gDR
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l Wolf Creek Nuclear Operation Corporation -2-l Wolf Creek Nuclear Operatir.g Corporation ATTN: Gary Boyer, Plant Manager P.O. Box 411 i Burlington, Kansas 66839 l Kansas Corporation Commission ATTN: Robert D. Elliott, Chief Engineer Fourth Floor, Docking State Office Building Topeka, Kansas 66612-1571 Kansas Radiation Control Program Director i
l bec to DMB (IE06)
bec distrib, by RIV w/ copy of licensee's letter: 1 R. D. Martin, RA J Myron Karman, ELD,. MNBB (1)
Resident Inspector Section Chief, DRP/A)
DRP j RPB-DRSS -
RIV File DRS MIS System RSTS Operator Lisa Shea, RM/ALF Inspector Section Chief B. Murray ;
R. L. Bangart i R. E. Hall Project Engineer, DRP/A B.DeFayette, RIII Callaway, RIII ,
D. Pickett, NRR Project Manager l l
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W4)NUCLEAROPERATING LF CREEK g-1 - '
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Bart D. Vesthers President sad
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February 13, 1989 WM 89-0047 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station Pl-137 Washington, D. C. 20555 Reference: Letter dated January 12, 1989 from L. J. Callan, NRC, B. D. Withers, WCNOC Subject: i Docket No. 50-482: Response to Violation 482/8832-01, 02, 03 and 04
Gentlemen:
ttached is Wolf Greek Nuclear Operating Corporation's (WCNOC) response to Violations 482/8832-01, 02, 03 and 04 which were documented in the Referenc Violation 482/8832-01 involved the failure to post notices of violation Violation 482/8832-02 involved the failure to post high radiation areas. Violation 482/8832-03 involved the failure to follow procedures for collection and transfer of radioactive wast Violation 482/8832-04 involved the failure to meet transportation regulation Additionally, the reference requested a response on the steps that WCNOC has taken and plans to take to improve the performance in the areas of inattentiveness of health physics technicians and apparent deterioration in l
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the effectiveness of the health physics supervisory staff. Per discussions on February 7, 1989 between Mr. E. J. Holler, NRC Region IV, and Mr. K. Petersen, WCNOC, a response will be provided to the concerns by March 1, 198 If you have any questions concerning this matter, please contact me or Mr. O. L. Maynard of my staf Very truly yours, L
Bart D. Withers President and *
BDW/jad Chief Executive Officer Attachment cc: B. L. Bartlett (NRC), w/a E. J. Holler (NRC), w/a i
R. D. Martin (NRC), w/a D. V. Picke t t eDRE$ Alv/Burlington, KS 66839 / Phone:(316) 364 8831
. An Equal opportundy Envoyer WFACVET
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Attachrant to WM 89-0047 Page 1 of 7 I Violation (482/8832-01): Failure to Post Notices of Violations Finding:
10 CFR Part 19.11(a) requires that each licensee shall post current copies of certain documents including any Notice of Violation involving ,
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radiological working conditions and any response from the license Contrary to the above, the NRC inspectors determined on November 15, 1988, that the licensee had not posted che' Notice of Violation issued with NRC Inspection Report- 50-482/88-25, dated October 21, 1988, which contained two
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violations involving radiological working conditions and the response to the
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Notice of Violatio Reason for Violation:
Upon receipt of NRC Inspection Report 482/88-25, Licensing and Plant Support personne1' reviewed the Notice of Violation and determined that the two violations did not specifically involve radiological working conditions and
'therefore did not require posting- in accordance with 10 CFR Part 19.1 Discussions with the NRC inspectors revealed that their interpretation of 10 CFR 19.11(a)(4) is that this posting requirement applies to any 10 CFR Part 19.12 or Part 20 violation, or any violation of radiation protection program implementing procedure WCNOC disagrees with this very conservative interpretation of the requirements and believes that this interpretation may result in the posting of violations that do not involve radiological working condition However, using the NRC inspectors'
interpretation, WCNOC agrees that the violations issued with NRC Inspection Report 482/88-25 should have been poste Corrective Steps That Have Been Taken and Results Achieved:
After discussions with the NRC inspectors regarding their interpretation of the posting required by 10 CFR 19.11(a)(4), WCNOC posted copies of the Notice of Violation in the designated location Procedure ADM 01-085, "10 CFR Posting Requirement" and KP-L2201, "NRC Correspondence Processing" were reviewed against the 10 CFR 19 posting requirements and have been revised to reflect the above' NRC inspectors'
interpretation Corrective Steps Which Will Be Taken to Avoid Further Violations:
The above corrective steps should prevent further violation j Date When Full Compliance Will Be Achieved _:
Full compliance has been achieve )
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Attachment to WM 89-0047
Page 2 of 7 Violation (482/8832-02): Failure to Post High Radiation Areas Findinz:
Technical Specification (TS) 6.12.1 requires, in part, that high radiation areas, gasam exposure rates greater than or equal to 100 milliram per hour (mrem /hr) but less than 1000 mrem /hr at 18 inches, be conspicuously posted in accordance with 10 CFR Part 20.20 Contrary to the above, NRC inspectors determined on November 15, 1988, that two accessible areas within containment exhibited radiation levels of 100 l mrem /hr and 160 mrem /hr at 18 inches were not properly poste Reason for Violation:
The root cause for the failure to properly post a High Radiation Area has been attributed to non-licensed utility personnel erro Extensive review of all surveys performed in the Reactor Coolant Drain Tank (RCDT) area on the 2000' elevation indicated that hot spots were detected at various times prior to November 15, 198 Based on the surveys, the radiation levels would change from a High Radiation level to less than 100 mrem /hr depending on the evolutions associated with the RCD On at least three of the surveys, prior to November 15, 1988, one of the hot spots was recorded as 1 100 mrem /hr at 18 inches. These surveys did not indicate that the area was posted as a High Radiation Area. However, two HP Supervisors, when questioned, remembered the area being posted as " Caution High Radiation Are RWP Required for Entry" during their Containment entries prior to November 15, 198 Sometime during this time period (October 7 to November 15, 1988), l scaffolding was installed in the area near the RCDT. Evidently, the posting !
was removed during the scaffolding installation and/or as a result of ,
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radiation levels decreasing below 100 mrem /hr and the area was not repeste Personnel error was involved in that the area was not reposted for radiation levels above 100 mrem /hr at 18 inches, as a High Radiation Area.
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I Corrective Steps That Have Been Taken and Results Achieved Technicians surveyed the areas and erected a barrier and posted the two areas immediately after being informed of the NRC Inspector's findings on November 15, 198 Technicians were made aware of the finding and were reminded to ensure that all areas were posted properl Subsequent surveys show that the area was posted properly as a High Radiation Area.
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Page 3 of 7 Corrective Steos Which Will Be Taken to Avoid Further Violations:
A memo was sent to all HP personnel describing thememo, In the violation and the HP personnel apparent circumstances that caused the violatio are directed to 03-013 ensure that all areas are posted in accordance the with location of procedure HPH and to note on survey documentation, such postin They are also cautioned to be especially sensitive to areas as the RCDT, which may experience radiation level changes on a daily basi to place in the contractor A copy of the memo has been sent to Training Training Files and in the Impact Files for HP Technician Trainin Date When Full Compliance Will Be Achieved:
Full compliance has been achieve Violation (482/8832-03): Failure to Follow Procedures FindinR:
" Procedures for personnel Technical Specification 6.11 requires that, requirements of radiation protection shall be prepared consistent with theand adhered to for all 10 CFR Part 20 and shall be approved, maintained,
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operations involving personnel radiation exposures.'
Health Physics Procedure HPH 09-503 " Collection and Transfer of Radioactive Waste,' Item 5.1.3.4.1, requires that each container or bag of radioactive waste must be narked, when not in the presence of Health Physics personnel, whichever with the highest contact radiation level or the background level, is appropriat . 16, 1988, that Contrary to the above, NRC Inspectors determined on Novemberthe prestenciled approximately ' six bags of radioactive material (with Radioactive Material,") and three capped and unmarked yellow containing other bags of radioactive material, located in an outside inscription, drums area adjacent to the radwaste and containment buildings, were not adequately controlled and had not been properly marked to indicate the radiation
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level Reason for Violation:
The root cause for improper bagging of waste materials has been attributed to non-licensed personnel erro .
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Attachment to WM 89-0047
- Page 4 of 7 had been used in the I The filters had no l tio externall l The material in question consisted levels measurable of filters thatseconda trash, a sample had detectable However, to contamination or radiation allow free-release of the materials as cleandioactive was present material which to be collected and analyzed to ensure no rathe materials Sincewere the placed in yellow bags internally. Consequently, L'
d in Step 2.3 of HPH are prestenciled with ' CAUTION was the material RADIOACTIVE was adequately MATER the contract technicians felt that d 09-503),
controlled and did not present a radiological hazar . i s of procedure error was involved in that the specific instruct ont ining the filters Personnel HPH 09-503 were not followed, which required the bags con abackground to be marked indicating radiation levels asas non-detectable Achieved:
Corrective Steos That Have Been Taken accordance andwithResults procedure all bags of j
that The bags were resurveyed and properly marked reminded in ith procedure HPH 09-503, HPH 09-50 Technicians and deconners were l radioactive material must be marked in accordance wpersonne l when not in the presence of Health Physica h Violations:
g Corrective Steos Which Will Be Taken to Avoid Furt er been revised to add a NOTE which emphasizes the Procedure HPH 09-503 has bag must be marked i peresent the fact that any yellow " Radioactive Material" irrespective of the lev procedure, on the material in the ba Date When Full Compliance Vill Be Achieved _:
Full compliance has been achieve Failure to Meet Transportation Regulations _
Violation (482/8832-04):
Finding: shall transport any licensed 10 CFR 71.5(a) requires that no licensee l ce of use. or deliver material outside the confinescarrier of his plant or for transport, other pappropriate a unless the licensee to the l
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any licensed material to a i
complies with applicable requirements18 of the regulat ons '
I mode of transport of DOT in 49 CFR Parts 170-l i
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- Page 5 of 7 1 49 CFR 173.425(c)(3) requires that for shipments of low specific activity material in exclusive use vehicles the external radiation levels comply with 49 CFR 173.44 CFR 173.441(b)(2) requires that radiation levels not exceed 200 including mrem the top /hr and on any point on the outer surfaces of the vehicle, underside of^the vehicl CFR Parts 173.425(b)(6) and 49 CFR 173.448(a) require that a shipment be braced so as to prevent shifting of lading, radioactive material containers, !
under conditions norma 11y' incident to transportatio I j
contrary to the above, radiation surveys of by state of Nevada inspectors at licensee Waste Shipment 88B08 I
1988, Beatty, Nevada, on June 3, determined that the radiation level at one point under the transport trailer was 260 to 275 mrem /hr, and that the lading (55 gallon drums / barrels) had shifted during transpor I Reason for Violation:
The root cause for exceeding radiation limits for transportation and for inadequate bracing has been attributed to inadequate, procedure l The instrument normally used at Wolf Creek Generating StationThe (WCGS) for radiation j monitoring radiation levels is the R0-2 or R0-2A lon chambe level measured by the Nevada inspector was in an isolated area near the The !
trailer axle that was difficultinstrument to access with an R0-2 instrumen with a small Geiger Hueller Nevada inspector used an E-520 and which detector, wh'ich made access to the point in question much easier, than the ,
also indicated a significantly (about 30%) higher radiation level i ion chamber used at WCG Personnel from WCGS traveled to the Nevada site !
to check the shipment' prior to it being unloaded. The spot measured by the Nevada inspector as 260 to 275 mrem /hr with the G-M probe, was measured with'
by a WCGS. R0-2 and some difficulty, at approximately the same locationSince the highest reading indicated a maximum reading of 200 mrem /h !
listed on the manifest was about 170 mrem /hr, either the 200 mrem /hr spot or was not detected by the technician using the R0-2 when surveyed at WCGS, of the the slight shifting of the load during transit changed the location radiation readin l l
The shifting of lading is thought to be due to allowing too much space Shipment 88B08 shifted forward between the drums when they were loade shif It indicating that horizontal space was available for the load to '
appears that the ' riding up onto the locking rings of adjacent * containers,"
was also a result of the excess space available for the drums to move horizontally and ride up onto other drum _ _ _ _ - - _ _ _ _ _ _ _ _
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Procedure HPH 09-513, ' Outgoing Vehicle Surveys' was inadequate in that it had no instructions for the technician to use different or additional survey instruments when radiation levels were near the limits and/or when areas were difficult to access with the R0-2 ion chambe Procedure HPH 09-514, " Transport Vehicle Loading and Inspection' was inadequate in that it did not require the loader and the QC Inspector to ensure that the drums were packed tightly together prior to installing the rear bracing. According to the Barnwell, S.C. Burial Site, they have had no problems with shipments of drums shifting, when the drums are packed closely together and properly braced and shored at the rea Corrective Stens That Have Been Taken and Results Achieved:
Procedure HPH 09-513 was revised to include a note that instructs the technicians to use both an R0-2 ion chambay and an E-520 GM type instrument to measure radiation levels external to the vehicle (trailer) for Nevada shipments when packages (drums) of greater than 500 mrem /hr are included in the shipmen Some shipments of drums were made in which the drums were banded together to help prevent shiftin The type of trailer required for banded drums is no longer availabl WCGS personnel have researched information en adequate bracing by contacting other utilitics and other burial site One shipment of drums was made to the Barnwell, site in Decembe The drums were packed closely together and braced and shored at the rear. They were braced at the top in the rear with a friction ba They were shored at the bottom in the rear with toe-nailed two-by-four There were no problems with lading shift or radiation levels at the burial
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sit Corrective Stens Which Will Be Teken to Avoid Further Violations:
Procedure HPH 09-513 has been further revised to require radiation surveys external to the vehicle (trailer) on all shipments, irrespective of burial site destination, to be surveyed by both an E-520 GM type instrument and an R0-2 ion chamber when packages or drums of greater than 500 mrem /hr are included in the shipmen .
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. Page 7 of 7 An engineering evaluation has been conducted to determine if additional bracing requirements are necessary for radwaste shipment The disposition has been reviewed and has been factored into procedure HPH 09-514, as appropriat Procedure HPH 09-514 was revised to require all shipments of drums to be tightly packed from front to rear before bracing and shoring are properly placed at the rear. Additional guidance was incorporated into the procedure to prevent movement of the drums in the vertical directio Date When Full Compliance Will Be Achieved:
Full compliance has been achieve .
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