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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H5811999-10-15015 October 1999 Forwards 1999 Update to FSAR, for McGuire Nuclear Station.With Instructions,List of Effective Pages for Tables & List of Effective Pages for Figures ML20217G7861999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20217F3591999-10-13013 October 1999 Forwards Info Copy of Cycle 14 COLR for McGuire Nuclear Station,Unit 1 ML20217F3261999-10-13013 October 1999 Submits Quantity of Tubes Insp from Either Side of SGs A-D & Lists Tubes with Imperfections,Locations & Size.No Tubes Removed from Svc by Plugging.Total of Eleven Tubing Wear Indications Identified at Secondary Side Supports in SGs ML20217F8011999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of McGuire Nuclear Station.Areas That Warranted More than Core Insp Program Over Next Five Months,Not Identified.Historical Listing of Plant Issues Encl ML20217J5091999-10-0606 October 1999 Forwards Revs to Section 16.15-4.8.1.1.2.g of McGuire Selected Licensee Commitments Manual.Section Has Been Revised to Allow Testing of Portions of DG Fuel Oil Sys Every 10 Yrs ML20217C8351999-10-0505 October 1999 Communicates Correction to Info Provided During 990917 Meeting with Duke Energy & NRC Region Ii.Occupational Radiation Safety Performance Indicator Values Should Have Been Presented as 1 Instead of 0 ML20217C4471999-10-0404 October 1999 Forwards Insp Repts 50-369/99-06 & 50-370/99-06 on 990801- 0911.Determined That One Violation Occurred & Being Treated as Non-Cited Violation ML20212J2191999-10-0404 October 1999 Informs That Util 980326 Response to GL 97-06, Degradation of SG Internals Provides Reasonable Assurance That Condition of Steam Generator Internals Are in Compliance with Current Licensing Bases for Facility ML20212J7801999-10-0404 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for McGuire NPP & 990615.Informs That NRC Reviewed Responses & Concluded That All Requested Info Re Y2K Readiness Provided.Subj GL Considers to Be Closed ML20212M1651999-09-23023 September 1999 Refers to 990917 Meeting at Region II Office Re Licensee Presentation of self-assessment of McGuire Nuclear Station Performance.List of Attendees & Licensee Presentation Handouts,Encl ML20212D1671999-09-20020 September 1999 Forwards Exemption & SER from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Re Isolation of Main Steam Branch Lines Penetrating Containment.Exemption Related to Licensee Application ML20212B6491999-09-15015 September 1999 Informs That Encl Announcement Re 990913 Application for Amend to Licenses NPF-9 & NPF-7 Forwarded to C Observer in North Carolina,For Publication ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station ML20212A0501999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementing Code Case for Duration of Insp Interval ML20212A2631999-09-0909 September 1999 Forwards Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valve Inservice Testing Program, IAW 10CFR50.55a. Section 8.0 Contains Summary of Changes & Detailed Description of Changes Associated with Rev 25 ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 ML20211J3671999-08-31031 August 1999 Forwards Public Notice of Application for Amend to License NPF-9 Seeking one-time Extension of Surveillance Frequency for TS SR 3.1.4.2 Beyond 25% Extension Allowed by TS SR 3.0.2 ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211K8831999-08-26026 August 1999 Forwards Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs ML20211G5181999-08-24024 August 1999 Forwards SE Re second-10-yr Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210V0171999-08-13013 August 1999 Confirms Conversation Between M Cash & M Franovich on 990806 Re Mgt Meeting,Scheduled for 990917 to Present self- Assessment of Plant Performance.Meeting Will Be Held in Atlanta,Ga ML20210S2231999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210T4511999-08-10010 August 1999 Forwards Response to NRC RAI Re 981014 Standby Nuclear Svc Water Pond Dam Audit Conducted by FERC ML20210R4311999-08-10010 August 1999 Forwards Summary Rept of Mods,Minor Mods,Procedure Changes & Other Misc Changes Per 10CFR0.59 ML20210R0031999-08-10010 August 1999 Forwards Revised TS Bases Pages to NRC for Info & Use. Editorial Changes Were Made to Correct Incorrect UFSAR Ref Number Associated with Certain Reactor Coolant Sys Pressure Isolation Valves ML20210Q3701999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date in Order to Register Individuals to Take Exam ML20210H7691999-07-21021 July 1999 Submits Summary of 990715 Meeting at Facility Re Presentation of Results of Most Recent Periodic Ppr.List of Meeting Attendees Encl ML20209H1551999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for May 1999 Also Encl ML20210E1931999-07-13013 July 1999 Forwards Insp Repts 50-369/99-04 & 50-370/99-04 on 990509-0619.Four Violations of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20209G5151999-07-0808 July 1999 Forwards Amended Pages to Annual Radioactive Effluent Release Repts, for 1997 & 1998 for McGuire Nuclear Station. Portion of Rept Was Inadvertently Omitted Due to Administrative Error,Which Has Been Corrected ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20196J4381999-06-29029 June 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1,NRC Revised Info in Rvid & Releasing Rvid Version 2 ML20196G3721999-06-24024 June 1999 Documents Verbal Info Provided to NRR During Conference Call Re Relief Requests 98-002 & 98-003 ML20196G7461999-06-22022 June 1999 Requests Exemption from Requirements of 10CFR54.17(c) That Application for Renewed Operating License Not Be Submitted to NRC Earlier than 20 Yrs Before Expiration of Operating License Currently in Effect ML20195K3601999-06-14014 June 1999 Forwards MORs for May 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised MORs for Apr 1999.Line 6 Max Dependable Capacity (Gross Mwe) on Operating Data Rept Should Be Revised to 1114 from Jan 1998 to Apr 1999 ML20195D5691999-06-0303 June 1999 Submits Ltr to Facilitate Closing of Inspector Follow Up Item 50-369,370/97-15-05,re Revising Site Drawings in UFSAR Into Summary one-line Flow Diagrams,Per NRC 990327 Telcon ML20195F1851999-06-0202 June 1999 Forwards Insp Repts 50-369/99-03 & 50-370/99-03 on 990328- 0508.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20195E8771999-06-0202 June 1999 Confirms Telcon with M Cash on 990524 Re Public Meeting for 990715.Purpose of Meeting to Discuss Results of NRC Most Recent PPR ML20207D0521999-05-21021 May 1999 Informs That in Telcon on 990519 Between a Orton & Rf Aiello Arrangements Made for Administration of Initial Written Exam for McGuire Nuclear Station on 990603.Exam Will Be Administered at Catawba Simultaneously with Written Exam ML20196L1791999-05-20020 May 1999 Communicates Util Licensing Position Re Inoperable Snubbers. Licensee Has Determined That Structure of ITS Has Resulted in Certain Confusion Re Treatment of Inoperable Snubbers ML20196L1851999-05-20020 May 1999 Forwards Proprietary & non-proprietary Version of Rev 1 to TR DPC-NE-3004, Mass & Energy Release & Containment Response Methodology, Consisting of Finer Nodalization of Ice Condenser Region.Proprietary Info Withheld ML20206T4481999-05-13013 May 1999 Forwards Rev 3 to Topical Rept DPC-NE-3002-A, UFSAR Chapter 15 Sys Transient Analysis Methodology, IAW Guidance Contained in NUREG-0390 ML20206R0791999-05-13013 May 1999 Forwards Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised Monthly Operating Repts for Mar 1999 1999-09-09
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217F8011999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of McGuire Nuclear Station.Areas That Warranted More than Core Insp Program Over Next Five Months,Not Identified.Historical Listing of Plant Issues Encl ML20217C4471999-10-0404 October 1999 Forwards Insp Repts 50-369/99-06 & 50-370/99-06 on 990801- 0911.Determined That One Violation Occurred & Being Treated as Non-Cited Violation ML20212J2191999-10-0404 October 1999 Informs That Util 980326 Response to GL 97-06, Degradation of SG Internals Provides Reasonable Assurance That Condition of Steam Generator Internals Are in Compliance with Current Licensing Bases for Facility ML20212J7801999-10-0404 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for McGuire NPP & 990615.Informs That NRC Reviewed Responses & Concluded That All Requested Info Re Y2K Readiness Provided.Subj GL Considers to Be Closed ML20212M1651999-09-23023 September 1999 Refers to 990917 Meeting at Region II Office Re Licensee Presentation of self-assessment of McGuire Nuclear Station Performance.List of Attendees & Licensee Presentation Handouts,Encl ML20212D1671999-09-20020 September 1999 Forwards Exemption & SER from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Re Isolation of Main Steam Branch Lines Penetrating Containment.Exemption Related to Licensee Application ML20212B6491999-09-15015 September 1999 Informs That Encl Announcement Re 990913 Application for Amend to Licenses NPF-9 & NPF-7 Forwarded to C Observer in North Carolina,For Publication ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20212A0501999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementing Code Case for Duration of Insp Interval ML20211J3671999-08-31031 August 1999 Forwards Public Notice of Application for Amend to License NPF-9 Seeking one-time Extension of Surveillance Frequency for TS SR 3.1.4.2 Beyond 25% Extension Allowed by TS SR 3.0.2 ML20211K8831999-08-26026 August 1999 Forwards Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs ML20211G5181999-08-24024 August 1999 Forwards SE Re second-10-yr Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20210V0171999-08-13013 August 1999 Confirms Conversation Between M Cash & M Franovich on 990806 Re Mgt Meeting,Scheduled for 990917 to Present self- Assessment of Plant Performance.Meeting Will Be Held in Atlanta,Ga ML20210Q3701999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date in Order to Register Individuals to Take Exam ML20210H7691999-07-21021 July 1999 Submits Summary of 990715 Meeting at Facility Re Presentation of Results of Most Recent Periodic Ppr.List of Meeting Attendees Encl ML20210E1931999-07-13013 July 1999 Forwards Insp Repts 50-369/99-04 & 50-370/99-04 on 990509-0619.Four Violations of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20196J4381999-06-29029 June 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1,NRC Revised Info in Rvid & Releasing Rvid Version 2 ML20195E8771999-06-0202 June 1999 Confirms Telcon with M Cash on 990524 Re Public Meeting for 990715.Purpose of Meeting to Discuss Results of NRC Most Recent PPR ML20195F1851999-06-0202 June 1999 Forwards Insp Repts 50-369/99-03 & 50-370/99-03 on 990328- 0508.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20207D0521999-05-21021 May 1999 Informs That in Telcon on 990519 Between a Orton & Rf Aiello Arrangements Made for Administration of Initial Written Exam for McGuire Nuclear Station on 990603.Exam Will Be Administered at Catawba Simultaneously with Written Exam ML20206L5631999-05-11011 May 1999 Forwards Two Documents Requesting That NRC Place on Docket 50-369 & 50-370,technical Interface Agreement 97-02 & Related Staff Evaluation ML20206N3451999-05-11011 May 1999 Forwards SE of Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206M2121999-05-11011 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created ML20206C0451999-04-23023 April 1999 Forwards Insp Repts 50-369/99-02 & 50-370/99-02 on 990214-0327.No Violations Noted ML20205Q6641999-04-15015 April 1999 Forwards Amend 10 to Indemnity Agreement B-83 for Signature & Return to Document Control Desk ML20205M6741999-04-13013 April 1999 Discusses 980318 Telcon of Licensing Bases Record Change Re Duke Energy Corp License Amend Request, & Staff Approval in Form of TS Amends 184 & 166,dtd 980930.Forwards Revised Pp to SE of 980930 ML20205T1711999-04-0909 April 1999 Informs That on 990317 Ho Christensen & a Orton Confirmed Initial Operator Licensing Exam Schedule for Y2K.Initial Exam Dates for Wks of 000508 & 22 for Approx 13 Candidates ML20205M2601999-03-25025 March 1999 Informs That NRC Completed PPR of Plant on 990201.Plant Issues Matrix & Insp Plan for Next 8 Months Encl ML20205A9371999-03-24024 March 1999 Forwards Evaluated & Final Rept from Ferc,Related to 981014 Dam Safety Audit Conducted at McGuire Nuclear Station for Category I Standby Service Water Pond Dam.List of Actions That Should Be Taken by Util to Ensure Safety of Dam,Encl ML20205H9201999-03-18018 March 1999 Forwards Exam Repts 50-369/99-301 & 50-370/99-301 on 990125- 0205.Of Eleven SRO & RO Candidates Taking Written Exam & Operating Tests,Nine Passed & Two Failed,Representing 82% Pass Rate ML20204E3221999-03-10010 March 1999 Forwards Insp Repts 50-369/99-01 & 50-370/99-01 on 990103- 0213.Non-cited Violation Noted ML20207M9091999-03-0505 March 1999 Informs That Info Submitted by Application, Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20203J0431999-02-16016 February 1999 Discusses Review of Plant,Units 1 & 2 IPEEE Submittal.Staff Concludes That Util IPEEE Process,Capable of Identifying Most Likely Severe Accidents & Severe Accidents Vulnerabilities.Intent of Suppl 4 to GL 88-20 Met ML20203C2411999-02-0505 February 1999 Discusses Draft Operation Insp Rept for McGuire Nuclear Station Standby Nuclear Service Water Pond Dam Conducted on 981028.Draft Rept States That Dam Appeared to Be in Good Condition & Adequately Maintained ML20203G3361999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Names of Candidates for Exam ML20202E3861999-01-28028 January 1999 Refers to GL 96-05 Issued on 960918 & DPC 980331 Updated Response to GL 96-05 Indicating Intent to Implement Provisions of JOG Program on MOV Periodic Verfication at Mcguire.Rai Re JOG Program McGuire Encl ML20199L4421999-01-25025 January 1999 Informs That by Encl Ltrs & 981223,NRC Has Responded to WOG Positions Re C/As to Address Generic Aspects of part-length CRD Mechanism Housing Issue That Originated as Result of 980123 Leak at Pings ML20203A4171999-01-22022 January 1999 Refers to 990119 Meeting Conducted in Region II Ofc for Presentation of self-assessment of McGuire Nuclear Station Performance & Future Plant Initiatives.List of Attendees & Presentation Handouts Encl ML20198Q7711999-01-0505 January 1999 Informs That Staff Review of GL 97-05, SG Tube Insp Technique, Did Not Identify Any Concerns with SG Tube Insp Techniques Employed at McGuire That Would Indicate That Util Not in Compliance with Current Licensing Bases for Plant ML20198Q7551999-01-0505 January 1999 Forwards RAI Re 980722 Request for Amend to Plant,Units 1 & 2 TSs to Permit Use of Westinghouse Fuel.Response Requested on or Before 990131 ML20199F6031998-12-23023 December 1998 Submits Summary of 981105 Training Managers Conference.List of Attendees & Matl Used in Presentation Enclosed ML20198N8771998-12-18018 December 1998 Forwards Insp Repts 50-369/98-10 & 50-370/98-10 on 981004- 1121.No Violations Noted ML20198N7001998-12-14014 December 1998 Confirms 981210 Conversation Between M Cash & E Lea Concerning Meeting Scheduled for 990119.Purpose of Meeting to Present self-assessment of Plant Performance ML20198A4221998-12-11011 December 1998 Forwards SE Accepting Licensee 980115 Request for Relief from Requirements of ASME BPV Code,Section Xi,Table IWB-2500-1,for Plant ML20196F2901998-11-23023 November 1998 Advises of Planned Insp Effort Resulting from Insp Planning Meeting Held on 981102.Details of Insp Plan for Next Four Months & Historical Listing of Plant Issues Called PIM Encl ML20196B0011998-11-23023 November 1998 Forwards Emergency Response Data Sys Implementation Documents,Which Include Data Point Library Updates for Listed Plants.Changes Should Be Made to Data Base as Soon as Possible.Without Encl ML20195J5401998-11-19019 November 1998 Forwards RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. Staff Requests Response to RAI by 990205 ML20196C7681998-11-13013 November 1998 Forwards Copy of Answer Key & Master Bwr/Pwr GFE Section of Written Operator Licensing Exam,Administered on 981007 by Nrc.Without Encl 1999-09-23
[Table view] |
Text
I JAN I 21993 Duke Power Company ATIN: Mr. T. C. McMeekin Vice President McGuire Site 12700 Hagers ferry Road Huntersville, NC 28078-8985 Gentlemen:
SUBJECT:
REQUAllflCATION PROGRAM EVALUATION - MCGUIRE NUCLEAR STATION EXAMINATION REPORT NO. 50-369/93-300 Arrangements have been made between Mr. Dave McGinnis, Director of Operations Training, and Mr. Garry Harris, License Examiner, for an evaluation of the requalification program and licensed personnel at your McGuire Nuclear Station. The evaluation visit is scheduled for the week of May 31, 1993. The requalification examinations and the subsequent evaluation of the facility requalification program will be performed in accordance with Sections 601 through 604 of NUREG 1021, Operator Licensing Examiner Standards, Revision 6.
You are encouraged to ensure that your training staff and proposed examinees are familiar with these standards.
Please note that Revision 7 of the Examiner Standards may be available for use by the time of the examinations. We will coordinate with your staff to determine whether you would prefer to be evaluated under the new or old standards.
For the examiners to adequately prepare for this visit, it will be necessary for the facility to furnish the approved iteins listed in Enclosure 1, >
" Reference Material Requirements." Failure to supply the reference material as required by Enclosure 1 may result in postponement of the examination. The Chief Examiner may request that the facility submit a proposed examination for use during the examination week in addition to the material requirements of-Enclosure 1. Submission of a proposed examination, even if requested, is optional. However, if a proposed examination is submitted,-those personnel participating in its development may become subject to the security restrictions described below. Mr. McGinnis has been advised of our reference material requirements, whether a proposed examination is requested, and where these items are to be sent.
Your attention is directed to the guidance promulgated in Revision 6 to NUREG-1021 pertaining to the content and scope of simulator examination scenarios. The scenario examination bank should cover the entire spectrum of Emergency Operating Procedures (EOPs), including alternate decision paths within E0Ps, and incorporate a range of failures with varying degrees of severity for the same type event. Each scenario'should contain simultaneous l events that require prioritization of actions and allocation of-resources, and should exercise E0Ps in-depth, i.e., scenarios require transitions and/or decisions to be made on actions to take within the E0Ps. ; <
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Duke Power Company 3 JAN I 21993 This request is covered by Office of Management and Budget (OMB) Clearance Number 3150-0101, which expires October 31, 1995. This estimated average i 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, xeroxing, and mailing the required material. Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reducing this burden, to the Information and Records Management Branch, MNBB-7714, Division of information Support Services, Office of Information Resources Management, U. S. 11uclear Regulatory Commission, Washington, D. C.
20555, and to the Paperwork Reduction Project (3150-0101), Office of Information and Regulatory Affaire,, NL08-3019, Office of Management and Budget Washington, D. C. 20503.
Thank you for your consideration in this matter. If you have any questions on the evaluation process, please contact Mr. Michael L. Ernstes, Chief, Operator Licensing Section 2, at (404) 331-5594, or myself at (404) 331-5541.
Sincerely, SRIGillAL SIGNED BY T. A. PEEBLES Thomas A. Peebles, Chief Operations Branch .
Division of Reactor Safety
Enclosures:
- 1. Reference Material Requirements 2, Administration of Requalification Examinations
- 3. fiRC Rules and Guidance for Examinees cc w/encls:
F E. M. Geddie, Station Manager Duke Power Company McGuire Nuclear Station 12700 Hagers ferry Road Huntersville -NC 28078-8985 Dave M. McGinnis, Director McGuire Operations Training Duke Power Company Training and Technology Center 13339 Hagers Ferry Road Huntersville, NC 28078-8985 R. O. Sharpe Compliance Duke Power Company 12700 Hagers Ferry Road Huntersville, NC_ 28078-8985 (cc w/encls cont'd - see page 4) wua-te--g-ws+-am>= rte--+f "mi as- +* w' w a r w- ur-wV--- w- ("w we--,pw--d iee er w were a+ +--w-'- > -ri-- "P--+--as m -er- ri- + - - ' - -
- j Duke Power Company 4 JAN I 21993 cc w/encls cont'd:
R. L. Gill Nuclear Generation Department Mail Stop EC050 Duke Power Company P. O. Box 1006 Charlotte, NC 28201-1006 A. V. Carr, Esq.
Duke Power Company 422 South Chiirch Street _
Charlotte, NC 28242-0001 J. Michael McGarry, Ill, Esq.
Winston and Strawn 1400 L Street, NW Washington, D. C. 20005 Dayne N. Brown, Director Division of Radiation Protection N. C. Department of Environment, Health & Natural Resources P. O. Box 27687 Raleigh, NC 27611-7687 County Manager of Mecklenburg County 720 East Fourth Street Charlotte, NC 28202 T. Richard Purycar Nuclear Technical Services Manager Carolinas District Westinghouse Electric Corporation P. O. Box 32817 Charlotte, NC 28232 Dr. John M. Barry, Director Mecklenburg County Department of Environmental Protection 700 North Tryon Street Charlotte, NC 28203 Karen E. Long Assistant Attorney General N. C. Department of Justice #
P. O. Box 629 Raleigh, NC 27602 (bcc w/o encls - see page 5)
Duke Power Company- 5 bec w/o encls:
i S. Ebneter, RA A. Gibson, DRS
- 1. Reed, NRR !
A. Herdt, DRP G. Belisle, DRP W. Miller, DRP M. Ernstes, DRS .I G. Harris, DRS --
i K. VanDoorn, McGuire 1
Senior Resident inspector l U. S. Nuclear Regulatory Commission ,
12700 Hagers ferry Road Huntersvilla, NC 28078-8985 bcc w/encls:
Document Control Desk 1
f FOR LIST OF CONCURRENCES, SEE ATTACHED FAGE Ril:DRS' - RII:DRS RII:DRS GHarris:GAH/far MErnstes TPeebles 1/- /93 1/ ./93 1/ /93 Document name: g\ia\mcguire\r30090da.geh-
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T. Reed, NRR-A. Gibson, DRS A. lierdt, DRP G. Belisle, DRP W. Miller, DRP M. Ernstes, DRS '
G. liarris, DRS
- K VanDoorn, McGuire Senior Resident Inspector U. S. Nuclear Regulatory Commission 12700 llagers ferry Road lluniersville, NC -28078-8985 bcc w/entls:
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! [NCl05URL1 Rf f ERf NC f IMTf R1 Al RIQUIRf!!$1S lest items to support all aspects of the requalification examination must be provided to the NRC 60 days prior to the examination date.
All test items should be developed in accordance with the guidelines provided in Sections 602 through 604 of NUREG 1021, Operator Licensing Examiner Standards, and their respective attachments.
lor the first requalification evaluation at the f acility, the submittal must contain at least-700 test items for use in the written examination. They should be equally divided between the two sections of the examination, and there must be at least 350 test items for use in each section.
75 Job Perf ormance Measures (JHis) f or use on the walk-through portion of the operating examination. To the extent possible, approximately 40 percent of the JPMs should evaluate "in plant" tasks (system / component operation outside the control room).
15 simulator scenarios of approximately 50 minutes each in length for use on the simulator port ion of the operating examination for examinations administered in one week, for subsequent requalificalion examinations facilitles are expected to make submittals reflecting progress toward the following targets over the next five years after the initial evaluation visit:
A minimum of 700 test items for use in the written examination equally divided between the two sections of the written examination and which cover all safety-related elements of the f acility Job Task Analysis (J1A). The bank shall be dynamic in nature, in that at least 150 questions a year shall be reviewed, revised, or generated. New questions that are developed should cover equipment and system modifications, recent industry, and licensee events and procedural changes.
JPMs to evaluate each operator aed senior operator safety-related task identified in the facility JTA, which meet the criteria in ES-603, The JPM bank should expand at a rate of at least ten JPMs per year until this goal is reached. It is estimated at 125 - 150 JPMs will be the final result. Development of the questions associated with the JPMs shall also continue, such that there is a representative sample of qu^stions given the knowledges associated with the task listed in the J1A.
1 Enclosure 1 2 1
A bank of at least 30 simulator scenarios which reflect all plausible or expected abnormal and emergency situations to which control room i
operators are expected to respond or control. At least five scenarios
, per year should be generated until all aspects of the emergency operating procedures are covered with sufficient variation in the type and scope of initiating events and level of degradation, for all requalification examination and evaluation visits, the facility shall:
Submit an Examination Test Outline / Sample Plan which meets the i
requirements of ES-601, Attachment 1.
Provide the associated examination banks (written, simulator, and JPM) and associated reference material to the region and contractor. . At a l- minimum, this shall include Technical Specifications, -applicable plant operating, surveillance and administrative procedures, abnormal and emergency operating procedures, emergency plan procedures, and training material utilized in the requalification training (including student handouts and lesson plans). Additional reference material may be requested by the Chief Examiner.
-If a proposed examination is submitted to the region, also submit a copy j of the simulator scenario portion to the Chief, Regional Support and l Oversight Section, Operator Licensing Branch, Division of Licensee l Performance and Quality, Washington, DC 20555, 45 days in advance of the first day of the examinations. The reason for the increased per/od of days is-to allow a reasonable amount of time for feedback, discussion and l
\ time to make any necessary changes.
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ff4Cl0SURE 2 ADMl!11STRAT10tl Of REQUAllflCAT10ft EXAMit4AT lolls
- 1. An evaluation of at least 12 facility licensed operators is required for a program evaluation. llormally the crew scheduled for requalification training during the period selected for the program evaluation should be selected. The sample will include other licensed operators who are not routinely performing shift duties or ara not maintaining an active license per 10 CFR 55 53(3). The restrictions on crew composition in the simulator are described in ES-601 C.I.b. and ES-604.
- 2. The simulator and simulator operator (s) shall be provided for examination development. The date(s) and duration of time needed to develop the _
examinations will be aoreed upon by the Chief Examiner and the facility.
- 3. 1he ref erence material used in the simulator will be reviewed by the Chief Examiner. fio material will be used that is solely used for training.
- 4. A single room shall be provided for completing Section B of the written examination. The location of this room and supporting rest room facilities shall be such as to prevent contact with all other facility and/or contractor personnel for the duration of the examination.
- 5. Minimum spacing is required to ensure examination integrity and will be evaluated by the Chief Examiner. Minimum spacing consists of one examinee per table and a 3-foot space between tables, llo wall charts, models, and/or other training materials shall be present in the examination room.
- 6. Copies of reference material for Section B of the written examination shall be provided for each examinee. The reference material will be reviewed by the Chief Examiner and will consist of Technical Specifications, operating / abnormal procedures, administrative procedures, and Emergency Plans as available to the plant operatorc.
- 7. Video taping capabilities may be utilized. The facility should contact the Chief Examiner for restrictions related to its usage.
- 8. An attempt will be made to distinguish between R0 and SRO knowledge and abilities to the extent that such a distinction is supported by the f acility training materials.
- 9. prudent scheduling of exam week activities is important to help alleviate undue stress on the operators. Your training staff and the Chief Examiner should work very closely in formulating a schedule which does not result in excessive delays in crews or individuals being administered their examination. The following are some suggestions for structuring the exam activities to achieve this purpose:
__ 2 Don't bring in crews or individuals well bef ore their scheduled exam iimes.
When examining operators in groups, it is better to hold the group just completing their exam vice the groups that are taking their exam later.
Following simulator scenarios, the facility evaluators and NRC examiners should quickly determine whether follow-up questioning is required, so that the crew may be released to talk among themselves about the scenario. _
Ensure that time validation of JPMs, particularly those performed in the simulator, is conducted accurately. A reasonable schedule should be established to prevent operators from waiting for simulator availability to complete their JPMs.
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{NCLOSURE 3 l
NRC RULES AND GUIDANCE FOR EXAMINEES
- 1. Use black ink or dark pencil DNLY to facilitate legible reproduction. ;
- 2. Print your name in the blank provided on the cover sheet of the i examination.
- 3. fill in the date on the cover sheet of the examination, if necessary.
- 4. Answer each question on the examination, if add!tional paper is required, use only the lined paper provided by the examiner.
- 5. Use abbreviations only if they are commonly used in facility literature. -
- 6. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
- 7. Show-all calculations, methods, or assumptions used to obtain an answer to a short answer test item, whether asked for in the question or not.
- 8. Unless solicited, the location of references need not be stated.
- 9. Proportional grading will be applied. Any additional 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 response 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, even '
though you may have listed the four correct responses in the answer key.
' 10. Partial credit may be given, except on multiple choice questions.
Therefore, ANSWER ALL PARTS Of THE QUESTION, AND DO NOT LEAVE ANY ANSWERS BLANK. i
- 11. If parts-of the examination are not clear with respect to their intent, t ask questions of the examiner only.
- 12. You must sign the statement on the cover sheet that indicates the work on the examination is your own and that you have not received or been given any assistance in completing the examination. This must be signed AFTER the examination has been completed.
- 13. Rest room trips are to be limited, and only one examinee'at a time may leave. You must avoid all contact with anyone outside the examination room to avoid even the appearance or possibility of examination compromise, J
s.-ww,.h.
Enclosure 3 2
- 14. Cheating on the examination would result in a revocation of your license and could result in more severe penalties.
- 15. Each section of the examination is designed to take approximately 90 minutes to complete. You will be given two hours to complete each section to allow for thirty minutes of review.
- 16. The examination has been time validated by knowledgeable persons. -You should be aware that-not every answer needs to be verified by consulting l a reference, and excessive. usage of reference material may cause you to ,
not complete the exam in the allotted time. I
- 17. Due to the existence of questions that will require all examinees to refer to the same indications or controls, particular care must be taken i to maintain individual examination security and avoid any possibility of l
, compromise or appearance of cheating. l l
- 18. When you are finished and have turned in.your completed _ examination, _
l leave the examination area. -!
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i Duke Power Company 2 JAN I 21993 You are requested to desir,nate at least one employee to be a member of a joint NRC-facility examination team. The employee shall be an active SR0 (per the requirements of 10 CFR 5! .53(e) or (f) from the McGuire Nuclear Station Operations Department. You are encouraged to designate a second employee from the training staff to be a member of the examination team. This employee should be an active SRO (per the requirements of 10 CFR 55.53(e) or (f)), but may be a facility or INPO certified instructor. If desired and agreed to by ;
the Chief Examiner, you may designate one additional employee from the i training staff with appropriate qualifications to be a member of the examination team, in addition to these individuals, a simulator operator must ,
be made available for scenario preview and validation during the on-site examination preparation week. In some cases, it may be necessary te designate a simulator operator during the test item review period. This individual will also be subject to the examination security agreement.
Any facility representatives under the security agreement shall be restricted from knowingly communicati'a by any means the content or scope of the examination to unauthorizeo persons and from participating in any facility programs such as instruction, examination, or tutoring N which an identified l requalification examinee (s) will be present. These rest. ctions shall apply from the day that the facility representative signs the examination security 4 agreement indicating that the representative understands that he or she has specialized knowledge of the examination. The Chief Examiner will determine when facility representatives have received specialized knowledge concerning the examination and require execution of an examination security agreement.
l In most cases, the examination team members will not be required to enter into an examination security agreement more than 60 days prior to the examination week. The simulator operator will normally become subject to the requirements during the examination preparation and validation week, but in some cases, this may occur as much as 30 days prior to the examination week to support operating test item review and revision.
l Sixty days prior to the examination administration date, the facility training staff shall identify and provide directly to the NRC's Chief Examiner a list of the proposed operators, including crew composition, for the ext.mination.
Also, to ensure privacy, the only copy of the current mailing address and Part 55 docket number of each proposed operator should be mailed in an l envelope labeled "To Be Opened By Addressee Only" to the attention of Mr.
l Thomas A. Peebles, Chief, Operations Branch, Division of Reactor Safety, Region 11.
The facility management is responsible for providing adequate space and accommodations to properly develop and conduct the examinations. Enclosure 2,
" Administration of Requalification Examinations," describes our requirements for developing and conducting the examinations. Mr. McGinnis has-also been informed of these requirements. Also, a facility operations management representative (as a minimum, first level above shift supervisor) should observe the simulation facility examination process at the site.
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