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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:NRC TO UTILITY
MONTHYEARML20058H4551990-11-0707 November 1990 Forwards Insp Repts 50-369/90-20 & 50-370/90-20 on 901001-05 & 1101.No Violations or Deviations Noted IR 05000369/19900141990-10-17017 October 1990 Ack Receipt of 900928 Response Re Violations Noted in Insp Repts 50-369/90-14 & 50-370/90-14 ML20058B9631990-10-12012 October 1990 Advises That Liquid Samples,Spiked W/Radionuclides,Will Be Sent to Facilities for Radiochemical Analyses for Tritium, Fe-55,Sr-89 & Sr-90.Analyses Should Be Completed within 60 Days ML20058A2931990-10-10010 October 1990 Forwards Insp Repts 50-369/90-19 & 50-370/90-19 on 900924-28.No Violations or Deviations Noted ML20059M8081990-09-25025 September 1990 Approves 900820 Revised Relief Request 89-02 to Replace 20- Inch Carbon Steel Elbow W/Stainless Steel Pipe ML20059K4451990-09-17017 September 1990 Advises That Ta Reed Assigned as Project Manager for Plant ML20059L5611990-09-13013 September 1990 Forwards Insp Repts 50-369/90-17 & 50-370/90-17 on 900726-0828.Violations Noted But Not Cited ML20059K6671990-09-10010 September 1990 Forwards Insp Repts 50-369/90-15 & 50-370/90-15 on 900813- 17.Violation Noted But Not Cited ML20059K0051990-09-0505 September 1990 Forwards Exam Rept 50-369/OL-90-02 Administered on 900730- 0802 IR 05000369/19900111990-09-0505 September 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-369/90-11 & 50-370/90-11 ML20058N7901990-08-0909 August 1990 Forwards Safety Evaluation Supporting Util 890213 Relief Request 89-01 Re ASME Code Section XI Hydrostatic Testing Requirements ML20058P8381990-08-0303 August 1990 Discusses 900731 Enforcement Conference Re 900626 Event at Facility Involving Inoperability of Both Emergency Generators.List of Attendees & Supporting Info Encl ML20056A5571990-08-0202 August 1990 Requests Addl Info Re DPC-NE-2004, Core Thermal-Hydraulic Methodology Using VIPRE-01 for McGuire & Catawba. Requests Response Expeditiously IR 05000369/19900091990-07-30030 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-369/90-09 & 50-370/90-09 ML20056A5811990-07-24024 July 1990 Forwards Insp Repts 50-369/90-11 & 50-370/90-11 on 900522-0625 & Notice of Violation.Util Requested to Include in Response,Any Mgt Actions to Be Taken to Prevent Subj Event from Recurring ML20056A5171990-07-24024 July 1990 Confirms Arrangements for 900731 Enforcement Conference in Region II Ofc to Discuss Util Recent Problems Re Inoperability of Both Unit 1 Emergency Diesel Generators for Approx 26 H ML20055H4811990-07-13013 July 1990 Forwards Insp Repts 50-369/90-14 & 50-370/90-14 on 900626-0705.Violations Noted.Enforcement Conference Scheduled for 900731 to Discuss Violations ML20055H4721990-07-0303 July 1990 Ack Receipt of 900522 & 0621 Ltrs Forwarding Objectives & Scenario Package for Emergency Preparedness Exercise Scheduled for Wk of 900813 ML20059M9241990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl IR 05000369/19890141989-09-22022 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-369/89-14 ML20248B6601989-09-22022 September 1989 Forwards Insp Repts 50-369/89-15 & 50-370/89-15 on 890605-09 & 19-23.No Violations or Deviations Noted. Attention Invited to Weaknesses Identified in Rept Re Program for Molded Case Circuit Breakers ML20248C6181989-09-20020 September 1989 Ack Receipt of 890628 Response Transmitting Description of Additions to & Deviations from Generic Emergency Response Guidelines for Plant as Requested in ML20247P4051989-09-20020 September 1989 Forwards Insp Repts 50-369/89-30 & 50-370/89-30 on 890821-24.Noncited Violation Noted ML20248D5891989-09-20020 September 1989 Ack Receipt of 890818 Response to Violations Noted in Insp Repts 50-369/89-05 & 50-370/89-05 IR 05000369/19890271989-09-19019 September 1989 Forwards Insp Repts 50-369/89-27 & 50-370/89-27 on 890814-18.Violations Noted But Not Cited ML20247G6451989-09-13013 September 1989 Ack Receipt of 890828 Request for Relief from Limiting Condition for Operation Action Statement 3.6.1.8, Annulus Ventilation Sys. Understands That One Train of Sys Returned to Svc & Both Trains Declared Operable on 890825 ML20247K1281989-09-11011 September 1989 Forwards Insp Repts 50-369/89-29 & 50-370/89-29 on 890821-25.No Violations or Deviations Noted ML20247B5711989-08-31031 August 1989 Forwards Insp Repts 50-369/89-26 & 50-370/89-26 on 890807-11.No Violations or Deviations Noted ML20246E8541989-08-23023 August 1989 Forwards Exam Repts 50-369/OL-89-01 for Units 1 & 2 Administered on 890626-30 ML20246P2411989-08-22022 August 1989 Forwards Insp Repts 50-369/89-22 & 50-370/89-22 on 890724-28.No Violations or Deviations Noted ML20246N6381989-08-21021 August 1989 Forwards Insp Repts 50-369/89-21 & 50-370/89-21 on 890707-18 & Notice of Violation ML20246D0391989-08-18018 August 1989 Forwards Insp Repts 50-369/89-20 & 50-370/89-20 on 890717-21.No Violations or Deviations Noted ML20246C9591989-08-17017 August 1989 Requests Deletion of NRC to Licensee on NRC Followup of Plant Alert Critique Action Items from Licensee Records & to Refer to 890714 Version of Ltr in Any Future Correspondence on Same Subj ML20246D0651989-08-0909 August 1989 Forwards Insp Repts 50-369/89-18 & 50-370/89-18 on 890629-0728.No Violations or Deviations Noted ML20245L3961989-08-0808 August 1989 Forwards Insp Repts 50-369/89-16 & 50-370/89-16 on 890602-28 & Notices of Violation & Deviation ML20245F4241989-08-0808 August 1989 Forwards Insp Repts 50-369/89-23 & 50-370/89-23 on 890727. Violations Noted ML20248C0561989-08-0303 August 1989 Forwards Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants.Nrc Requested to Be Notified Upon Completion of Human Factors Review ML20248D3251989-08-0101 August 1989 Forwards Summary of Comments on Action Items Arising from Critique of Plant Alert on 890307-08,per ML20247K5901989-07-24024 July 1989 Forwards Insp Repts 50-369/89-19 & 50-370/89-19 on 890710-14.No Violations or Deviations Noted ML20247H7461989-07-18018 July 1989 Forwards Amends 100 & 82 to Licenses NPF-9 & NPF-17, Respectively & Safety Evaluation.Amends Update Pressure & Temp Limits in Tech Spec 3/4.4.9 for Heatup & Cooldown of RCS IR 05000369/19890111989-07-17017 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-369/89-11 & 50-370/89-11 ML20236E6381989-07-17017 July 1989 Forwards Insp Repts 50-369/89-14 & 50-370/89-14 on 890422- 0601 & Notice of Violation.Corrective Actions to Address Concern Re Mgt Controls Requested ML20247D3961989-07-14014 July 1989 Forwards Summary of NRC Comments Re Action Items Arising from McGuire Alert Critique on 890307-08.Alert Critique Beneficial & Should Result in Improved Coordination of Joint Response to Future Emergency Situations ML20246Q0631989-07-13013 July 1989 Forwards Insp Repts 50-369/89-17 & 50-370/89-17 on 890605- 09.No Violations or Deviations Noted.Unresolved Item Identified ML20246K3791989-07-0707 July 1989 Ack Receipt of 890623 Response to Violations Noted in Insp Repts 50-369/89-12 & 50-370/89-12 ML20245K5941989-06-29029 June 1989 Forwards SER Accepting Licensee 831104 & 850524 Responses to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Reliability - On-Line Functional Testing of Reactor Trip Sys. Technical Evaluation Rept EGG-NTA-8341 Also Encl ML20246A2951989-06-29029 June 1989 Forwards Request for Addl Info Re NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs ML20246C4481989-06-29029 June 1989 Forwards Safety Evaluation Granting Relief from Hydrostatic Pressure Testing Requirement of Section XI of ASME Boiler & Pressure Vessel Code,Per 880627 & 890216 Requests.Util Alternative NDE & Inservice Leak Testing Acceptable ML20246A6071989-06-26026 June 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-369/89-02 & 50-370/89-02 ML20246B2271989-06-23023 June 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-369/89-05 & 50-370/89-05.NRC Understands That Revised Response Addressing Weakness in Mgt Oversight Will Be Submitted 1990-09-05
[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
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April 5, 1989 I
1 Duke Power Company ATTN: Mr. H. B. Tucker Vice President Nuclear Production Department 422 South Church Street Charlotte, NC 28242 Gentlemen:
SUBJECT:
REACTOR OPERATOR AND SENIOR OPERATOR LICENSING EXAMINATIONS In a telephone conversation between Mr. Dave McGinnis, Operations Training Director, and Mr. Curt Rapp, NRC Region II Operator Licensing Section 2, arrangements were made for administration of the replacement examinations at the McGuire Nuclear Station. The written and operating examinations are scheduled for the week of June 26, 1989.
In order for us to meet the above schedule, it will be necessary for the facility to furnish the approved reference material listed in Enclosure 1,
" Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examination," by April 10, 1989. Any delay in receiving approved, properly bound and indexed reference material, or the submittal of inadequate or incomplete reference materiel will result in the examinations being rescheduled.
Mr. McGinnis has been advised of our reference material requirements and the examiners' names and addresses where each set is to be mailed.
The facility management is responsible for providing adequate space and accommodations in order to properly conduct the written examinations.
Enclosure 2, " Requirements for Administration of Written Examinations,"
describes our requirements for conducting these examinations. Mr. McGinnis ;
has also been informed of these requirements.
In addition, to better document simulator examinations, the Chief Examiner will have the facility simulator operator record prespecified plant conditions j (i.e., plant pressure, temperature, pressurizer level, etc.), for each l simulator scenario. The candidate will be responsible for providing this I information, along with any appeal of his simulator operating examination. .
Therefore, the facility training staff should retain the simulator examination '
scenario information until all candidates taking the examination have passed ]
the operating examination, accepted the denial of their license, or had their appeals completed.
8904180105 890405 PDR ADOCK 05000369 y PDC i (
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.- s, Duke Power Company 2 April 5,1989-Enclosure 3 contains the Rules and Guidelines that will be in effect during the administration of the written examination. The facility management 'is responsible for ensuring that all candidates are aware ~ of these Rules.
All completed reactor operator and senior reactor operator license application information'should be submitted at least 30 days before the'first' examination.
dates so that we will be able to review the training and experience of'the
. candidates, ; process :the medical certifications, and prepare final examiner assignments after candidate eligibility has been determined.
This request is covered by Office of Management and Budget Clearance Number
.3150-0101 which expires May 31, 1989. 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, xeroxing, and mailing the required-material. Comments on the accuracy of this estimate and suggestions to reduce the burden may be directed to the Office of Management and Budget, Paperwork
' Reduction Project (3150-0101), - Room 3208, New Executive Office Building, Washington D. C. 20503, and the U. S. Nuclear Regulatory Commission, Records and Reports Management Branch, Office of Information Resources Management, Washington D. C. 20555.
The facility staff review of the written examination will be conducted in accordance with requirements specified in Enclosure 4, " Requirements for Facility' Review of Written Examination." Mr. McGinnis has been informed of these requirements.
Thank you for your consideration la this matter. If you have any questions regarding the examination procedbres and requirements, please contact Mr. Ken Brockman, Chief, Operator L; censing Section 2, at 404/331-5594. .
I Sincerely, (original signed by K. Brockman)
Thomas A. Peebles, Chief Operations Branch Division of Reactor Safety
Enclosures:
- 1. Reference Material Requirements for Reactor / Senior Reactor i Operator Licensing Examinations
- 2. Requirements for Administration of Written Examinations 1
- 3. NRC Rules and Guidelines for Written Examinations i
- 4. Requirements for Facility Review of Written Examinations ;
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D. McGinnis, Training Supervisor l T. L. McConnell, Plant Manager i l
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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,reactortheory, thermodynamics,etc.).
A copy of the facility Job and Task Analysis (JTA), specifying the knowledges and abilities required of an operator at the facility. Each .
particular knowledge and/or ability will include an importance rating l correlating it to ensuring the health and the safety of the public. If a JTA is not furnished, the Knowledges and Abilities Catalog for Nuclear Power Plant Operators, NUREG 1122 (1123) will be used to establish content validity for the examination.
All Job Performance Measures (JPMs) used to ascertain the competence of the operators in performing tasks within the control room complex and, as !
identified in the facility JTAs, outside of the control room, i.e., local operations.
Training materials shall include all substantive written material used I for preparing applicants for initial R0 and SR0 licensing. The written material shall include learning objectives and the details presented I during lectures, rather than outlines. Training materials shall be ;
identified by plant and unit, bound, and indexed. FAILURE TO PROVIDE :
COMPLETE, PROPERLY B0UND AND INDEXED PLANT REFERENCE MATERIAL MAY RESULT IN THE RETURN OF THE MATERIAL TO THE PERSON WHO IS THE HIGHEST LEVEL OF CORPORATE MANAGEMENT WHO 15 RESPONSIBLE FOR PLANT OPERATIONS (E.G., VICE PRESIDENT OF NUCLEAR OPERATIONS). ACCOMPANYING THE MATERIAL WILL BE A i C0VER LET1ER EXPLAINING THE DEFICIENCIES IN THE REFERENCE MATERIAL AND THE FACT THAT THIS WAS THE REASON THE EXAMINATIONS WERE CANCELLED OR POSTPONED. Training materials which include the following shall be provided:
4
- 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 applicable system.
- Complete and operationally useful descriptions of all safety-system interactions and, where available, BOP system interactions under emergency and abnormal conditions, including consequences of anticipated operator error, maintenance error, and equipment failure.
Training material used to clarify and strengthen understanding of emergency operating procedures.
1
4
. ' Enclosure 1 2 4
i' 4
- Comprehensive theory material that includes fundamendli"in the area j of theory of reactor operation, thermodynamics, heat transfer and i' fluid flow, as well as specific application .to actual in-plant .
components. For example, mechanical theory material on pumps shall 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., Reacter Coolant Pumps, all ECCS pumps, Recirculation pumps,- Feedwater pumps and Emergency Feedwater pumps). . Reactor Theory. material shall include descriptions: that draw explicit ties between the fundamentals and the actual operating limits followed in the plant (i.e., reactor theory material shall contain explanations how principles relate to the actual curves used by operators to verify shutdown margin or calculate an ECP).
- 2. Complete Procedure Index (alphabetical by subject).
- 3. All administrative procedures (as applicable to reactor operation or safety).
- 4. All integrated plant procedures (normal or general operating procedures)..
5.
Emergency procedures . ) procedures (emergency instructions, abnormal or special
- 6. Standing orders (important orders that are safety-related and may supersede the regular procedures).
4
- 7. Fuel-handling-and core-1oading procedures. I
- 8. Annunciator procedures (alarm procedures, including set points).
- 9. Radiation protection manual (radiation control manual or procedures).
- 10. Emergency plan implementing procedures.
- 11. Technical Specifications.
- 12. System operating procedures.
- 13. Piping and instrumentation diagrams, electrical single-line diagrams, or flow diagrams.
- 14. Technical Data Book, and/or plant curve information as used by operators and facility precautions, limitations, and set points (PLS) for the ,
facility. !
- 15. Questions and answers that the facility licensee has prepared and which may be used in the written or operating examinations.
- 16. The following on the plant reference simulation facility:
- a. List of all readily available initialization points.
4
Enclosure 1- '3
- b. List of all preset malfunctions with a clear identification number.
The list should include cause and effect information. Specifically,
< 'for each malfunction, a' concise description of the expected result, or range of results, that will occur upon implementation should be provided. Additionally, .an indication of.which annunciators are to be initially expected should be given.
- c. A description of simulator capabilities for valves, breakers, .
indicators, and alarms,
- d. Where the capability exists, an explanation of the ability to vary .
the severity of a particular malfunction should be provied, i.e., I ability to vary the' size of a given LOCA or steam lea' e the ability to cause a slow failure of a component such as a iced pump, turbine generator or major ' valve (e.g., drifting shut of a main feedwater control valve),
- e. An identification of modeling conditions / problems that ma) impact the examination.
- f. Identification' of any known Performance Test Failures not yet completed.
9 Identification of significant differences between the simulator and !
the reference plant's control room. !
- h. Copies of facility generated scenarios that expose the candidates to ,
situations of degraded oressure control (PWR), degraded heat removal !
capability (PWR and BWR), and containment challenges (BWR) shall be l provided,
- i. Simulator instructors manual.
.j, Description of the scenarios used for the training class (voluntary by' licensee).
- 17. Surveillance procedures (procedures that are frequently run,, i.e., weekly ordaily).
- 18. Additional material required by the examiners to develop examinations that meet the requirements of these standards and the regulations.
The above reference material should be approved, final issues and 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 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 with appropriate indexes or tables of contents so that they can be used efficiently. Failure to provide complete, properly bound and indexed plant reference material will result in the material being returned and could result in cancellation or rescheduling of the examinations.
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i ENCLOSURE 2 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS
- 1. A single room shall be provided for completing the written examination.
The location of this room and supporting restroom facilities shall be such as to prevent contact with all other f acility and/or contractor personnel during the duration of the written examination. If necessary, the facility should make arrangements for the use of a suitable room at a local school, motel, or other building. Obtaining this room is the responsibility of the licensee.
- 2. Minimum spacing is required to ensure examination integrity as determined by the Chief Examiner. Minimum spacing should be one candidate per table, with a 3-foot space between tables. No wall charts, models, and/or other training materials shall be present in the examination I toom.
- 3. Suitable arrangements shall be made by the facility if the candidates are '
to have lunch, coffee, or other refreshments. These arrangements shall comply with Item 1 above. These arrangements shall be reviewed by the examiner and/or proctor.
- 4. The facility staff shall be provided a copy of the written examination and answer key after the last candidate has completed and handed in his written examination. The facility staff shall then have five working days to provide formal written comments with supporting documentation on the examination and answer key to the Chief Examiner or to the Regional Office Section Chief.
- 5. The facility licensee shall provide pads of 8-1/2 by 11 inch lined paper in unopened packages for each candidate's use in completing the examination. The examiner shall distribute these pads to the candidates. All reference material needed to complete the examination }
stall be furnished by the examiner. Candidates can bring pens, pencils, l calwlators, or slide rules into the examination room, and no other equipnant or reference material shall be allowed. ] '
- 6. Only blank ink or dark pencils should be used for writing answers to questions. ,
- 7. The licensee shall provide one set of steam tables for each applicant.
The examiner shall distribute the steam tables to the applicants. No wall charts, models, and/or other training materials shall be present in j the examination room. No other equipment or reference material shall be l allowed unless provided by the examiner.
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ENCLOSURE 3 PROCEDURES FOR THE ADMINISTRATION OF WRITTEN EXAMINATIONS
- 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: 1 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 completing the examination. This must be done after you complete the examination.
l I
READ THE F0LLOWING INSTRUCTIONS
- 1. - Restroom trips are to be 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. l
- 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 Fill in the date on the cover sheet of the examination (if necessary). {
- 5. You may write your answers on the examination question page or on a separate sheet of paper. US'E ONLY THE PAPER PROVIDED AND DO NOT WRITE ON i THE BACK SIDE OF THE PAGE. I
- 6. If you write your answers on the examination question page and you need more space to answer a specific question, use a separate sheet of the paper provided and insert it directly after the specific question. DO NOT WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
- 7. Print your name in the upper right hand corner of the first page of each l section of your answer sheets whether you use the examination question pages or separate sheets of paper. Initial each page.
L :
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9 Enclosure 3 2 i
- 8. Before you turn in your examination, consequently number each answer ;
sheet, including any additional pages inserted when writing your answers i on the examination question page.
- 9. If you are using separate sheets, number each answer as to category and '
number (i.e., 1.04,6.10) and skip at least 3 lines between answers to allow space for grading.
- 10. Write "End of Category " at the end of your answers to a category.
- 11. Start each category on a new page. ,
- 12. Write "Last Page" on the last answer sheet.
- 13. Use abbreviations only if they are commonly used in facility literature. l Avoid using symbols such as > or < signs to avoid a simple transposition error resulting in an incorrect answer. Write it out.
- 14. 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 indicat bn of the depth of answer required.
- 15. Show all calculations, methods, or assumptions used to obtain an answer.
- 16. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 17. 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 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.
- 18. If the intent of a question is unclear, ask questions of the examiner only.
- 19. When turning in your examination, assemble the completed examination with examination questions, examination aids, and answer sheets. In addition, turn in all scrap paper.
- 20. To pass the examination, you must achieve an overall grade of 80 percent or greater and at least 70 percent in each category.
- 21. There is a time limit of (6) hours for completion of the examination (or some other time if less than the full examination is taken).
- 22. When you are done and have turned in your examination, leave the examination area (DEFINE THE AREA). If you are found in this area while the examination is still in progress, your license may be denied or revoked.
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- .'. t ENCLOSURE 4 l
}
l REQUIREMENTS FOR FACILITY REVIEW 0F WRITTEN EXAMINATIONS
- 1. At the option of the Chief Examiner, the facility may review the written 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. An NRC examiner will always be present during the review.
Whenever this option of examination review is utilized, the ' facility reviewers will sign the following statement prior to being allowed access '
to the examination. The examination or written notes will not by retained by the facility. l
- a. Pre-Examination Security Agreement I agree that I will not knowingly divulge any !
'information concerning the replacement (or initial) examination scheduled for to any unauthorized persons. I understand that-I am not to participate in any instruction involving those reactor operator or senior reactor operator applicants scheduled to be administered the above replacement (or initial) examination from now until after the examination has been administered. I understand that violation of this security agreement could result in the examination being voided.
i Signature /Date In addition, the facility staff reviewers will sign the following statement after the written examination has been administered,
- b. Post-Examination Security Agreement I did not, to the best of my knowledge, divulge any information concerning the written examination administered on to any unauthorized persons. I did not participate in providing any instruction to those reactor j
- operator and senior reactor operator applicants who were
[
j administered the examination from the time that I was allowed access to the examination.
l Signature /Date
- Fri.
1
-Enclosure 4 2
- 2. Regardless of whether the above examination review option is exercised,
-immediately following the administration of the written examination, the facility staff shall be provided a marked up copy of the examination and the answer key. The copy of the written examination shall include pen and ink changes made to questions during the examination administration.
If the facility did not review the examination prior to its administra-tion, they will have five (5) working days from the day of the written-examination to submit formal comments. 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 grading process on a case-by-case basis by the Regional Office Section Chief. Should the comment submittal deadline not be met, a-long delay in ,
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. ;
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- 2. Comments made without a concise facility recommendation will not be addressed.
- 4. A two-hour post examination review may be held at the discretion of the Chief Examiner. If this review is held, the facility staff should be j informed that only written comments that are properly supported will be l considered in the grading of the examination.
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