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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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In Reply Rdfer To:
' Docket: STN 5,0-482-n .
Wolf Creek Nuclear.0perating Corporation :
ATTN: Bart D.' Withers L ' President and Chief Executive Officer P.O. Box 411 1
'Burlington, Kansas 66839
' Gentlemen:.
I
SUBJECT:
. LICENSING EXAMINATIONS AT WOLF CREEK GENERATING STATION (WCGS).
-In a' telephone conversation between Mr. Janes Gilmore of your staff and a Mr. K. M. Kennedy, Chief Examiner, arrangements were made for the administration !
of licensing examinations at the Wolf Creek facility during the week of l November 20,o1989.
l To neet the above schedule, it will be necessary for you to furnish the reference.
mt.terial listed in Enclosure 1, " Reference Material Requirements.for. Reactor / ,
Senior Reactor Operator Licensing Examinations " by September 20, 1989. Any delays .!
in. receiving approved, properly bound, and indexed reference material could result in a delay in administering the examinations. Mr. Gilmore has been advised of our reference material requirements and where to send the material.
-You'are responsible for providing adequate space and accommodations for admin-istration of the written examinations. Enclosure 2, " Requirements for Admin- j
~ istration of Written Examinations," describes our requirements for conducting !
these examinations. Mr. Gilmore has also been infonned of these requirements. {
Enclosure 3, "Proteoures for the Administration of Written Examinations " contains l the rules and guidelines that will be in effect during the administration of the i written examinations. The facility management is responsible for ensuring that all. applicants are eware of these rules.
-The facility staff review of the written examinations will be conducted in ar. cord-ance with requirements specified in Enclosure 4, " Requirements for Facility Review of Written Examinations." Mr. Gilmore has been informed of these requirements. 1
'o .In order to document simulator examinations effectively, the Chief Examiner >
will have the simulator operator record predetermined plant conditions (e.g., #
plant pressure, temperature, pressurizer level, etc.), for each simulator scenario. .The applicants will be responsible for providing this information with any appeal of a simulator operating examination. Therefore, your training y staff should retain the original simulator examination scenario information
' untilf all applicants who took examinations have either passed the operating ,
examination, accepted the denial of their license, or filed an appeal.
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All completed reactor operator and senior reactor operator license applications
-3' should be submitted at.least 30 days before the first examination date so that we shall.be able to review the training and experience of the candidates,
' process the nedical certifications, and prepare final examiner assignments after applicant eligibility has been determined. If the applications '
art not received at least 30 days before the examination date, it is likely that a postponement will be necessary.
i This request is covered by Office of Management and Budget Clearance Number 3150-0101, which expires May 31, 1992. The estimated average burden is 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per response, including gathering, copying, and mailing the required material."-Send comments regarding this burden estimate or ary other aspect of this collection of information, including suggestions for reducing this burden, to,the' Records and Reports Managenent Branch, Division of Information Support Services, Office of Information Resources Management, U.S. Nuclear Regulatory Consission, Washington, D.C. 20555; and to the Paperwork Reduction Project (3150-0101), Office of Management and Budget, Washington, D.C. 20503.
Thank you for your consideration in this. matter. If you have any questions regarding the examination procedures and requirements, please contact Mr. J. L. Pellet, Chief, Operator Licensing Section, at (817) 860-8159.
Sincerely, Odo nna! Signed By:
Thomas P.Gwynn James L. Milhoan, Directer Division of Reactor Projects
Enclosures:
- 1. Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations
- 2. Requirements for Administration of Written Examinations
- 3. Procedures for Administration of Written Examinations
- 4. Requirements for Facility Review of Written Examinations cc w/ enclosures:
Wolf Creek Nuclear Operating Corporation ATTN: Otto Maynard, Manager Fegulatory Services P.O. Box 411 Curlington, Kansas 66839
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, Wolf Creek Nuslear Oherating Corporation-ATTN: Gary Boyer.J Plant Manager -
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? Kansas Corporation Couunission y : ATTN: - Robert" D.5E1110tt,' Chief Engineer -
-Fourth Floor,: Docking. State Office Building Topeka.~ Kansas ' L66617-1571 cc , Kansas Radiation Control Program Director J .. .bec w/ enclosures:- '
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.i J i bcc d'istrib. by RIV:. .
e w 'RRI 4 R. D. Martin, RA Sectionj Chief.- (DRP/D) ~ K. M. Kennedy
. R. DeFayette, RIII. J. L.. Pellet.
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- MIS System E. Haycraft
' Project <EngineerL(DRP/D): LFMB-Facilities Sectica.
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, .D.V. Pickett,;NRRProjectManager(MS: 13-D-18)-
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ENCLOSURE 1 REFERENCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS
- 1. Existing. learning objectives, job performance measures, and lesson plans (including training manuals, plant orientation manual, system descriptions, reactor theory, thermodynamics, etc.).
Training materials should include all substantive written materf al used for preparing applicants for initial R0 and SR0 licensing. The written material should include learning objectives and the details presented during lectures, rather than outlines. Training materials should be identified by plant and unit, bound, and indexed. Failure to provide complete, properly bound, and indexed plant reference material may result in the cancellation of the examinations and the return of the material to the person who is the corporate officer responsible for plant operation (e.g., Vice President of Nsclear Operations). If there are deficiencies in the licensee material, this should be explained in a cover letter accompanying the material. Training materials, which include the following, should be provided:
System descriptions including descriptions of all operationally relevant flow paths, components, controls, and instrumentation.
System training material should draw parallels to the actual procedures used for operating the appliceble system.
Complete and operationally useful descriptions of all safety-system interactions and, where available, B0P system interactions under emergency and abne nal conditions, including consequences of anticipated operator error, maintenance error, and equipment failure.
Training material used to clarify and strengthen understanding of emergency operating precedures.
Comprehensive theory material that includes fundamentals in the area of theory of reactor operation, thermodynamics, heat transfer, and fluid flow, as well as specific application to actual in-plant components. For example, mechanical theory material on pumps should include pump theory as well as descriptions of how these principles actually apply to major plant pumps and the systems in which they are installed (i.e., reactor coolant pumps, all ECCS pumps, recirculation pumps, feedwater pumps, and emergency feedwater pumps). Reactor theory material should include descriptions that draw explicit ties between the fundamentals and the actual operating limits followed in the plant (i.e., reactor theory material should contain explanations as to how principles relate to the actual curves used by operators to verify shutdown ECP margin or calculate an ECP).
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, 2. . Complete Procedure Index (including surveillance procedures, etc.)
- 3. All administrative. procedures (as applicable to reactor operation or safety)
'4. All integrated plant procedures (normal or general operating procedures)
- 5. Emergency procedures (emergency instructions, abnormal or special procedures)
- 6. Standing orders (important orders that are safety-related and may supersede the regular procedures)
- 7. Surveillance procedures (procedures that are run frequently, i.e., weekly or that can be run on the simulator)
- 8. Fuel-handling and core-loadin procedure, when appropriate) g procedures, (initial core-loading
- 9. Annunciator / alarm procedures
- 10. Radiation protection manual (radiation control mar. val or procedures)
- 11. Emergency plan implementing procedures
- 12. Technical Specifications (and interpretations, if available)
- 13. System operating procedures
- 14. Piping and instrumentation diagrams, electrical single-line diagrams, or flow diagrams
- 15. Technical Data Book, and/or plant curve information as used by operators and facility precautions, limitations, and setpoints (PLS) for the facility
- 16. Questions and answers specific to the facility training program which may be used in the written or cperating examinations (voluntary by facility licensee)
- 17. The following material for the plant reference stnulation facility:
- a. List of all preprogrammed initial conditions
- b. List of all present malfunctions with a clear identification number.
The list should include cause and effect information. Specifically, for each malfunction a concise description cf the expected result, or range of results, that will occur upon implementation should be previded. Additionally, an indication of which annunciators are to be initially expected should be given.
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- c. A description of simulator failure capabilities- for valves,. breakers.
indicators and alams
- d. Where the capability exists, an explanation of the ability tb vary f, .the severity of a'particular malfunction should be provided, i.e.,
", z ability to vary the size of a given LOCA or steam leak, or the
. ability to'cause a slow. failure of a component such as a feed pump, turbine generator, or.' major. valve (e.g., drifting shut of'a main
, feedwater control valve)
- e. An identification-of modeling conditions / problems'that may impact the >
examination:
- f. . Identification'of any known performance test discrepancies'not yet corrected g.. Identification of differences between the simulator and the reference.
plant's control room '
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- h. ~ Copies'of facility generated scenarios that expose the applicants to
- situations of, decreased pressure control (PWR) degraded heat removal ,
capability (PWP. and BWR) and containment challenges (PWR and BWR) may be provided (voluntary by licensee)
M i. Simulat'or instructor's manual (voluntary by licensee)
- j. Description of the scenarios used for the training' class (voluntary by.. licensee)
. - 18. Additional-material required by the examiners to develop examinations that meet the requirements of these Standards and the regulations.
6 . The above reference material should be the approved, current issue, and it should be so marked. If a plant has not finalized some~of the material, the Chief Examiner shall' verify with the facility that the most complete..up-to-date
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material.is available and that agreement.has been reached with the licensee for limiting changes before the administration of the examination. All procedures
- ' and reference; material should be bound in the form used by the control' room
/ operators, with appropriate indexes or tables of contents so that they can be used' efficiently.
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ENCLOSURE 2 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN-EXAMINATIONS
- 1. A single room shall be provided for administration of the written examination..
p The~ location of this room and supporting restroom facilities shall be such as toiprevent contact with all other facility and/or contractor personnel during' the written examination.. If necessary, the' facility should make arrangements for=the use of a suitable room at a loca'1' school, motel, or other building.. Obtaining this room is the responsibility of the licensee.
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L 2. Minimum spacing is required to ensure examination integrity as determined by the Chief, Examiner. Minimum spacing should be one. applicant per table, with a 3-foot space between tables.
3.- Suitable arrangements shall be made by the facility if the applicants are to have~ lunch, coffee, or other refreshments. These arrangements shall comply with Item 1 above and shall be reviewed by the examiner and/or proctor.
- 4. The facility licensee shall. provide pads of'8 1/2- by 11-inch lined paper-in unopened packages for each applicant's use in completing the examination.
The examiner shall distribute these pads to the applicants.-
. 5. Applicants may bring pens, pencils, calculators, or slide rules into the examination room. Only black ink or dark pencils should be used for writing answers to. questions.
- 6. The licensee shall provide ore set of steem tables for each applicant. When requested by the Chief Examiner, the licensee shall prepare copies of large documents (e.g., Technical Specifications, Emergency Plan Implementing Procedures, or Emergency Operating Procedures) for use by the applicants.
Such request will normally be made to the licensee at least one working day prior to ths written examination. The examiner shall distribute the steam tables to the applicants. No wall charts, models, and/or other training materials shall be visible in the examination room. No other equipment or reference material shall be allowed unless provided by the examiner.
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k ENCLOSURE 3 PROCEDURES FOR THE ADMINISTRATION OF WRITTEN EXAMINATIONS The Chief Examiner or proctor shall:
- 1. Check identification badges.
- 2. Pass out examinations and all handouts. Remind applicants not to review examination until instructed to do so.
READ THE FOLLOWING INSTRUCTIONS VERBATIM:
"During the administration of this examination the following rules apply:
"1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
"2. After the examination has'been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have not received or given assistance in ccmpleting the examination. This must be done after you complete the examination."
READ THE FOLLOWING INSTRUCTIONS:
- 1. Restroom trips are to he limited and only one applicant at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 2. Use black ink or dark pencil only to facilitate legible reproductions.
- 3. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
- 4. Fili in the date on the ;aaer sheet of the examination (if r.ecessary).
- 5. Use only the paper provided for your answers.
- 6. Print your name in the upper right-hand corner of the first page of each section of the answer sheet and initial each succeeding page.
- 7. Consecutively number each answer sheet.
- 8. Write "End of Category __" at the etid of your answers to a category.
- 9. Start each category on a new page.
- 10. Write on only one side of the paper.
- 11. Write "Last Page" on the last answer sheet.
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- 12. Number each answe'r to correspond with the question, for example: 1.4. 6.3.
' 13. Skip at least three lines between each answer.
- 14. Separate completed answer sheets from the pad and place them face down on your desk or table.
- 15. Use abbreviations only if they are commonly used in facility literature.
Avoid using symbols such as less than or greater than signs to avoid a simple transposition error resulting in an incorrect answer. Write it out.
- 16. The point value for each question is indicated in parentheses after the question. The amount of blank space on an examination question page is NOT an indication of the depth of answer required.
- 17. Show all calculations, methods, or assumptions used to obtain an answe.r and justify your answer for any short answer or essay ouestions, whether indicated in the question or not.
- 18. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK.
- 19. Proportional grading will be applied to short enswer or essay questions requesting a list. Any additior,a1 wrong information that is provided may count against you. For example, if a question is worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth 0.20 points. If one of your five responses is incorrect. 0.20 will be deducted and your total credit for that question will be 0.80 instead of 1.00 even though you got the four correct answers.
- 20. If the intent of a question is unclear, ask questions of the examiner only.
- 21. When you complete your examination, you shall:
- a. Assemble your examination as follows:
(1) Examination questions on top.
(2) Examination aids - figures, tables, etc.
(3) Answer pages including figures which are part of the answer.
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- b. Turn in your examination and all pages used to answer the examination l questions. j
- c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.
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. 4 , while the examination .is:still in progress, your license- may be
. denied'or revoked..
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ENCLOSURE 4
-REQUIREMENTS FOR FACILITY REVIEW 0F WRITTEN EXAMINATIONS At the option of the Chief Examiner, the facility may review the written 7
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examination up to two weeks prior to its administration. This review may take. place at the facility or in the Regional: office. The_ Chief Examiner-will coordinate the details of the. review with the facility.
I Whenever this option of examination review is utilized, the facility. _
reviewers shall sign the following statement prior to being-allowed. access to the examination:
- a. Preexamination Security Agreement I, , agree that I will not knowin any information concerning the. replacement (or initial) gly divulge examination scheduled for to any unauthorized persons. :I understand that I am not to participate in any instrue. tion involving those reactor operhter or senior reactor operator applicants scheduled to be' administered the above replacement (or initial) examination from now until after the examination has been administered.:
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In addition, the facility staff reviewers will sign the following statement after the written examination has been administered:
- b. Postexamination Security Agreement I, , did not, to the best of my knowledge, divulge.any information concerning the written _ examination to any unauthorized persons.
administered on I did not participate in providing any instruction to those reactor operator and senior reactor operator applicants who were administered the examination from the time that I was allowed access to the examination.
Signature /Date 1
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4 2.- Regardless of whether the above examination review option is exercised, imediately. folhwing the administration of the written examination, the facility will be provided a copy of the examination with all changes that were made during the examination administration for their review.
If the facility did not review the examination prior to its administration, they will have five (5) working days from the day of the written examination to submit formal coments. If the facility reviewed the examination prior to its administration, any additional comments must be given to an examiner prior to his/her leaving the site at the end of the week of the written examination administration. In either case, the comments will be addressed to the responsible Regional office by the highest level of corporate management for plant operations, e.g., Vice President for Nuclear Operations.
A copy of the submittal will be forwarded to the Chief Examiner, as appropriate Comments not submitted within the required time frame will be considered for inclusion in the gracing process on a case-by-case basis by the Regional Office Section Chief. Should the comment submittal deadline not be met, a long. delay lin grading the examinations may occur.
- 3. The following. format should be adhered to.for submittal of specific comments:
- a. Listing of hRC question, answer and reference
- b. Facility comment / recommendation
- c. Reference (to support facility comment)
! NOTES: 1. No change to the examination will be made without submittal of a reference to support the facility comment. Any supporting documentation that was not previously supplied, should be provided.
- 2. Comments made without a concise facility recommendation will not be addressed.
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