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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J3341999-10-19019 October 1999 Forwards Request for Addl Info Re Sale of Portion of Land Part of Oyster Creek Nuclear Generating Station Site Including Portion of Exclusion Area ML20217E0181999-10-0606 October 1999 Provides Nj Dept of Environ Protection Comments on Oyster Creek Nuclear Generating Station TS Change Request 267 Re Clarifications to Several TS Sections ML20216J7591999-09-30030 September 1999 Informs NRC That Remediation Efforts for Software Sys Etude & Rem/Aacs/Cico Have Been Completed According to Schedule & Now Y2K Ready 05000219/LER-1998-011, Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts1999-09-30030 September 1999 Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts ML20212J6721999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Oyster Creek Nuclear Generating Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216K1421999-09-29029 September 1999 Provides NRC with Name of Single Point of Contact for Purpose of Accessing Y2K Early Warning Sys,As Requested by NRC Info Notice 99-025 ML20217D1661999-09-27027 September 1999 Forwards Proprietary Completed NRC Forms 396 & 398,in Support of License Renewal Applications for Listed Individuals,Per 10CFR55.57.Encl Withheld ML20217B2531999-09-24024 September 1999 Informs That on 980903,Region I Field Ofc of NRC Ofc of Investigations Initiated Investigation to Determine Whether Crane Operator Qualification/Training Records Had Been Falsified at Oyster Creek Nuclear Generating Station ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212A7921999-09-13013 September 1999 Forwards Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817 to Plant ML20212B5571999-09-10010 September 1999 Forwards Rev 11 to Oyster Creek Emergency Dose Calculation Manual, IAW 10CFR50,App E,Section V ML20211N2941999-09-0303 September 1999 Responds to NRC 990802 Telcon Request for Environ Impact Assessment of TS Change Request 251 Concerning Movement of Loads Up to 45 Tons with RB Crane During Power Operations ML20211J9831999-09-0202 September 1999 Discusses 990804 Telcon Re Sale of Portion of Oyster Creek Nuclear Generating Station Land.Requests Info Re Location of All Areas within Property to Be Released Where Licensed Radioactive Matl Present & Disposition of Radioactive Matl ML20211J6771999-08-30030 August 1999 Submits Response to NRC 990802 Telcon Request for Gpu to Provide Environ Impact Assessment for Tscr 251 ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj ML20211C0161999-08-19019 August 1999 Advises That Info Submitted by Ltr,Dtd 990618, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool, Holtec Rept HI-981983,rev 4,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211B9011999-08-18018 August 1999 Forwards Rev 0 to EPIP 1820-IMP-1720.01, Emergency Public Info Implementing Procedure ML20210U4341999-08-17017 August 1999 Responds to to Chairman Dicus of NRC on Behalf of Fm Massari Concern About Oyster Creek Nuclear Generating Station Not Yet Being Fully Y2K Compliant ML20210Q7331999-08-12012 August 1999 Responds to Re TS Change Request (TSCR)264 from Oyster Creek Nuclear Generating Station.Questions Re Proposed Sale of Property within Site Boundary & Exclusion Area ML20210L6311999-08-0606 August 1999 Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2 ML20210D2801999-07-22022 July 1999 Submits Response to Administrative Ltr 99-02 Operating Reactor Licensing Action Estimates. Estimate of Licensing Actions Projected for Fy 2000 Encl.No Projection Provided for Fy 2001 ML20209H5001999-07-14014 July 1999 Forwards Revised TS Pages 3.1-15 & 3.1-17 Which Include Ref to Note (Aa) & Approved Wording of Note H of Table 3.1.1, Respectively ML20210U4411999-07-12012 July 1999 Forwards Article from Asbury Park Press of 990708 Faxed to Legislative Officer by Mutual Constitute Fm Massari Indicating That Oyster Creek Nuclear Generating State Not Fully Y2K Compliant ML20209G1451999-07-0909 July 1999 Forwards Rev 1 to 2000-PLN-1300.01, Oyster Creek Generating Station Emergency Plan. Attachment 1 Contains Brief Summary of Changes,Which Became Effective on 990702 ML20209E0821999-07-0707 July 1999 Forwards TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20209B7501999-07-0101 July 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Generic Ltr 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Licensee Y2K Readiness Disclosure for Ocngs,Encl ML20196G1361999-06-23023 June 1999 Provides Status of Corrective Actions Proposed in in Response to Insp Rept 50-219/98-80 & Revised Schedule for Completion of Actions Which Are Not Yet Complete ML20196E6421999-06-22022 June 1999 Forwards Revised Pages of TS Change Request 261,dtd 990618. Replacement Requested Due to Several Dates Being Omitted on Certain Pages ML20195G6541999-06-0707 June 1999 Discusses 981204 Initiation to Investigate Whether Contract Valve Technician,Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20195G6631999-06-0707 June 1999 Discusses 981204 Intiation to Investigate Whether Contract Valve Technician Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20209B0561999-06-0404 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart ML20195D0551999-06-0303 June 1999 Forwards TS Change Request 226 to License DPR-16,permitting Operation with Three Recirculation Loops.Certificate of Svc & Tss,Encl ML20195C5511999-05-25025 May 1999 Forwards Book of Controlled Drawings Currently Ref But Not Contained in Plant Ufsar.Drawings Were Current at Time of Submittal ML20206N7711999-05-11011 May 1999 Forwards Rev 0 to Oyster Creek Emergency Plan, IAW 10CFR50.47(b) & 10CFR50.54(q).Changes Became Effective on 990413 ML20206H9441999-04-28028 April 1999 Forwards Application for Amend to License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons Using Reactor Bldg Crane During Power Operations,Per NRC Bulletin 96-002 ML20206B6991999-04-26026 April 1999 Forwards Copy of Rev 11 to UFSAR & Rev 10 to Oyster Creek Fire Hazards Analysis Rept. Without Fire Hazard Analysis ML20206D3801999-04-26026 April 1999 Forwards Rev 11 to UFSAR, & Rev 10 to Fire Hazards Analysis Rept, for Oyster Creek Nuclear Generating Station, Per 10CFR50.712(e) ML20206A9931999-04-22022 April 1999 Forwards Number of Personnel & Person Rems by Work & Job Function Rept for Period Jan-Dec 1998. Included in Rept Is Listing of Number of Station,Util & Contractor Personnel as Well as Diskette Reporting 1998 Occupational Radiation ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 ML20205P8411999-04-15015 April 1999 Forwards TS Change Request 267 to License DPR-16,modifying Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4. Certificate of Svc Encl ML20205P5381999-04-14014 April 1999 Ack Receipt of Re Request for Exception to App J. Intended Correction Would Need to Be Submitted as Change to TS as Exceptions to RG 1.163 Must Be Listed in Ts,Per 10CFR50,App J ML20205P9401999-04-12012 April 1999 Informs NRC That Gpu Nuclear Is Modifying Oyster Creek FSAR to Reflect Temp Gradient of 60 F & to Correct Historical Record ML20205P0651999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Results of PPR Used by NRC Mgt to Facilitate Planning & Allocation of Insp Resources 05000219/LER-1998-015, Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page1999-04-0505 April 1999 Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page ML20205J3281999-04-0101 April 1999 Discusses Arrangements Made on 990323 for NRC to Inspect Licensed Operator Requalification Program at Oyster Creek Nuclear Generating Station During Week of 990524 ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20205F0611999-03-25025 March 1999 Submits Info on Sources & Levels of Property Insurance Coverage Maintained & Currently in Effect for Oyster Creek Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20205E1171999-03-24024 March 1999 Forwards Rev 39 to Oyster Creek Security Plan & Summary of Changes,Iaw 10CFR50.54(p).Rev Withheld ML20207F0331999-03-0404 March 1999 Forwards Insp Rept 50-219/98-12 During Periods 981214-18, 990106-07 & 20-22.Areas Examined During Insp Included Implementation of GL 89-10 & GL 96-05.No Violations Noted ML20207K2471999-02-25025 February 1999 Forwards Fitness for Duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Ny 1999-09-30
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058H9421990-11-16016 November 1990 Forwards List of Unimplemented Generic Safety Issues at Facility,Per Generic Ltr 90-04 ML20058J0451990-11-0909 November 1990 Forwards Insp Rept 50-219/90-20 on 901022-26.No Violations Noted.Review of Preparations for Drywell Occupancy During Fuel Movement Identified Areas of Concern ML20058C7291990-10-24024 October 1990 Discusses Insp Rept 50-219/90-80 on 900625 & 29 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Violation Considered Severity Level III & Involved Unqualified Operators at Reactor Controls IR 05000219/19890811990-10-18018 October 1990 Ack Receipt of Informing NRC of Actions Taken to Correct Violations Noted in AIT Insp Rept 50-219/89-81 Re RPS Low Vacuum Setting ML20058A8241990-10-18018 October 1990 Forwards Safety Insp Rept 50-219/90-16 on 900823-0922 & Notice of Violation ML20058A6381990-10-18018 October 1990 Forwards SE Conditionally Accepting Util Insp & Repairs for Igscc,Per Generic Ltr 88-01 ML20058A6601990-10-16016 October 1990 Forwards Request for Addl Info Re Drywell Corrosion Program, Including Sampling of Shell Surfaces for UT Measurements ML20062B8641990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20062A6871990-10-11011 October 1990 Documents Review of Util 900921 Integrated Schedule ABC List Update.Listed Projects Acceptable Except for Items B/A-328 ADA & B/A-402946 ML20058F3211990-10-0303 October 1990 Forwards Safety Insp Rept 50-219/90-17 on 900918-21.No Violations Noted.Schedule for Identification & Disposal of Contents of Tanks in Old Radwaste Bldg Requested within 45 Days of Ltr Date IR 05000219/19900091990-10-0101 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/90-09 ML20059M5201990-09-21021 September 1990 Forwards Safeguards Insp Rept 50-219/90-15 on 900820-24.No Violations Noted ML20059J8021990-09-11011 September 1990 Advises That Util 900621 Response to Open Item Re USI A-46 & Schedule,Acceptable.Requests That Util Confirm Seismic Adequacy of CRD Hydraulic Control Units within 30 Days of Completion of Walkdown ML20059H3291990-09-0606 September 1990 Advises That 900831 Commitment to Install Hardened Wetwell Vent at Plant Acceptable ML20059G3911990-09-0505 September 1990 Recognizes Efforts of G Bond & W Douglas Re Implementation of Emergency Response Data Sys (ERDS) Link at Facility. ERDS Link at Facility Operational & Should Be Implemented in Emergency Response Planning ML20058Q4361990-08-15015 August 1990 Forwards Safety Insp Rept 50-219/90-11 on 900610-0711. Unresolved Item Noted ML20058P0801990-08-0909 August 1990 Forwards Requalification Program Evaluation Rept 50-219/90-05OL on 900409-0608.Util Should Respond within 30 Days of Receipt of Ltr Confirming Corrective Actions Committed to During 900424 Interim Exit Meeting ML20058M3581990-08-0808 August 1990 Requests Addl Info Listed in Encl Re Util 900521 & 0720 Responses to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow. Info Requested within 10 Days of Receipt of Ltr ML20058N0771990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Licensees Establishment of Engineering Managers Forum to Share Experiences ML20056A6071990-07-20020 July 1990 Forwards Insp Rept 50-219/90-09 on 900422-0609 & Notice of Violation.Util Should Identify & Correct Any Programmatic Weaknesses Re Failure to Perform Adequate Radiation Surveys ML20055G4141990-07-11011 July 1990 Requests Util Provide Ref Matls Listed in Encl for Senior Reactor Operator Licensing & Requalification Exams Scheduled for 901015 ML20058K5061990-06-28028 June 1990 Forwards Supplemental Safety Evaluation for Plant Dcrdr. NRC Concludes That Licensee Submittal Meets NUREG-0737, Suppl 1 Dcrdr Requirements & Therefore,Issue Considered Resolved ML20055E3021990-06-15015 June 1990 Forwards Backfit Analyses for Plant Re Installation of Hardened Wetwell Vent,Per Generic Ltr 89-16 ML20059M8321990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C3171990-02-16016 February 1990 Forwards Safety Insp Rept 50-219/89-29 on 891203-900106 & Ack Receipt of 900115 & 19 Responses to Insp Repts 50-219/89-21 & 50-219/89-27 ML20248B5511989-09-27027 September 1989 Informs of Correction to NRC Re Util Response to Generic Ltr 88-11 IR 05000219/19890031989-09-22022 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/89-03 NUREG-1382, Forwards Draft NUREG-1382, SER Re Full-Term Operating License for Oyster Creek Nuclear Generating Station, for Review1989-09-20020 September 1989 Forwards Draft NUREG-1382, SER Re Full-Term Operating License for Oyster Creek Nuclear Generating Station, for Review IR 05000219/19890051989-09-14014 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/89-05 ML20247K4491989-09-14014 September 1989 Forwards Insp Rept 50-219/89-18 on 890724-28.No Violations Noted ML20247K9771989-09-12012 September 1989 Forwards Safety Insp Rept 50-219/89-20 on 890829-30.No Violations Noted ML20247H7201989-09-0808 September 1989 Forwards Corrected SALP Rept 50-219/87-99 for Oct 1987 - Jan 1989 ML20246M7261989-08-30030 August 1989 Forwards Safety Evaluation Accepting Licensee 890624 Response to Integrated Plant Safety Assessment Section 4.11, Seismic Design Consideration, Items 4.11(1), Piping Sys & 4.11(3), Electrical Equipment ML20246J5961989-08-24024 August 1989 Forwards Safety Insp Rept 50-219/89-16 on 890702-29 & Notice of Violation.Attention Required to Ensure Engineering Evaluations of Potential Safety Problems Performed ML20246G1641989-08-21021 August 1989 Forwards SALP Final Rept 50-219/87-99 on Oct 1987 - Jan 1989 ML20246H5751989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purposes of Setting Occupational Exposure Limits & Requests to Ensure That Licensee Procedures Incorporate Applicable Dose Limits of 10CFR20 ML20247K0981989-08-15015 August 1989 Requests That Licensee Take Listed Actions Re Upgrade of Pipe Supports & Anchorages to Meet IE Bulletin 79-02 & 79-14 Requirements Using New Response Floor Spectra for Plant. Response Re Compliance Requested within 30 Days ML20246C3671989-08-15015 August 1989 Forwards Safety Insp Rept 50-219/89-19 on 890802-04.No Violations or Deviations Noted ML20246B0561989-08-14014 August 1989 Forwards Safety Insp Rept 50-219/89-15 on 890627-30.No Violations Noted.Items of Concern Noted in Area of Appointments to Technical & Supervisory Positions & Training Programs to Maintain & Upgrade Personnel Qualifications ML20245G1091989-08-10010 August 1989 Advises That Licensee 890726 Response to Generic Ltr 88-11, NRC Position on Embrittlement of Reactor Vessel Matls & Impact on Plant Operations, Acceptable ML20245G4931989-08-10010 August 1989 Advises That Util 890719 Response to Generic Ltr 89-08 Re Implementation of long-term Erosion/Corrosion Monitoring Program Meets Intent of NUMARC Program.Records & Results from Implementation Should Be Maintained ML20245L1971989-08-0808 August 1989 Forwards Safety Insp Rept 50-219/89-14 on 890604-0701.No Violations Noted.Insp Focused on Open Items Over 3 Yrs Old, Including Response to SALP Rept 50-219/85-99 ML20247P9641989-07-31031 July 1989 Advises That Category ABC List of Projects in Semiannual Update for 6 Months Since 881202 Considered in Compliance W/ Approved long-range Planning Program & Acceptable ML20245F6211989-07-26026 July 1989 Requests Util Provide Ref Matls Listed in Encl for Reactor Operator & Senior Operator Exams Scheduled for Wks of 891009 & 16,by 890905.Delay in Receiving Ref Matl May Result in Exam Being Rescheduled ML20247M4251989-07-26026 July 1989 Confirms Telcon on 890718 W/M Laggart & Eh Gray Re SSFI to Be Conducted at Facility During Wk of 890814-28.Insp to Focus on Design,Operation & Maint of Emergency Svc Water Sys.Background Info Requested by 890807 ML20247N1091989-07-25025 July 1989 Forwards Safety Insp Rept 50-219/89-11 on 890606-08.Due to Similarities Between 890524 Dress Rehearsal & 0607 Exercise, Exercise Does Not Qualify as Required Annual Test of Emergency Plan Since Same Staff Used & Scenario Known ML20247L7321989-07-25025 July 1989 Forwards Safety Insp Rept 50-219/89-12 on 890430-0603 & Notice of Violation IR 05000219/19880381989-07-24024 July 1989 Discusses Safety Insp Rept 50-219/88-38 on 881204-890114 & Forwards Notice of Violation.Violation Classified as Severity Level IV Since Unauthorized Entry Occurred as Result of Isolated Lapse in Vigilance by Security Officer ML20247A6731989-07-17017 July 1989 Forwards Safety Evaluation Accepting Licensee Response to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys Reliability on-line Testing ML20246L6291989-07-11011 July 1989 Ack Receipt of Forwarding Payment of Civil Penalty in Amount of $50,000 Proposed in NRC 1990-09-06
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217J3341999-10-19019 October 1999 Forwards Request for Addl Info Re Sale of Portion of Land Part of Oyster Creek Nuclear Generating Station Site Including Portion of Exclusion Area ML20212J6721999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Oyster Creek Nuclear Generating Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20217B2531999-09-24024 September 1999 Informs That on 980903,Region I Field Ofc of NRC Ofc of Investigations Initiated Investigation to Determine Whether Crane Operator Qualification/Training Records Had Been Falsified at Oyster Creek Nuclear Generating Station ML20212A7921999-09-13013 September 1999 Forwards Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817 to Plant ML20211J9831999-09-0202 September 1999 Discusses 990804 Telcon Re Sale of Portion of Oyster Creek Nuclear Generating Station Land.Requests Info Re Location of All Areas within Property to Be Released Where Licensed Radioactive Matl Present & Disposition of Radioactive Matl ML20211C0161999-08-19019 August 1999 Advises That Info Submitted by Ltr,Dtd 990618, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool, Holtec Rept HI-981983,rev 4,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20210U4341999-08-17017 August 1999 Responds to to Chairman Dicus of NRC on Behalf of Fm Massari Concern About Oyster Creek Nuclear Generating Station Not Yet Being Fully Y2K Compliant ML20210Q7331999-08-12012 August 1999 Responds to Re TS Change Request (TSCR)264 from Oyster Creek Nuclear Generating Station.Questions Re Proposed Sale of Property within Site Boundary & Exclusion Area ML20210L6311999-08-0606 August 1999 Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2 ML20195G6541999-06-0707 June 1999 Discusses 981204 Initiation to Investigate Whether Contract Valve Technician,Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20195G6631999-06-0707 June 1999 Discusses 981204 Intiation to Investigate Whether Contract Valve Technician Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20209B0561999-06-0404 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart ML20205P5381999-04-14014 April 1999 Ack Receipt of Re Request for Exception to App J. Intended Correction Would Need to Be Submitted as Change to TS as Exceptions to RG 1.163 Must Be Listed in Ts,Per 10CFR50,App J ML20205P0651999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Results of PPR Used by NRC Mgt to Facilitate Planning & Allocation of Insp Resources ML20205J3281999-04-0101 April 1999 Discusses Arrangements Made on 990323 for NRC to Inspect Licensed Operator Requalification Program at Oyster Creek Nuclear Generating Station During Week of 990524 ML20207F0331999-03-0404 March 1999 Forwards Insp Rept 50-219/98-12 During Periods 981214-18, 990106-07 & 20-22.Areas Examined During Insp Included Implementation of GL 89-10 & GL 96-05.No Violations Noted ML20206U3551999-02-0505 February 1999 Refers to Concerns Recipient Expressed to V Dricks on 990126 Related to Oyster Creek About Event Which Occurred on 970801 & About Administrative Control of EDG Vendor Manuals ML20199L2471999-01-22022 January 1999 Discusses GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 & Gpu Nuclear 960418 & 981202 Responses for Ocngs.Informs That Based on Confirming GL 96-01 Commitments Review Effort Closed ML20199G8241999-01-12012 January 1999 Responds to Ltr to Senator Lt Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20199G8631999-01-0707 January 1999 Responds to Ltr to Senator Lt Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20198B2121998-12-0909 December 1998 Advises of Planned Insp Efforts Resulting from Licensee Irpm Review.Historical Listing of Plant Issues & Details of Insp Plan for Next 6 Months Encl ML20196C6001998-11-25025 November 1998 Forwards Insp Rept 50-219/98-09 on 980914-1025 & Notice of Violation.Inspector Identified That Security Force Member Left Running Unlocked Vehicle Unattended in Protected Area ML20195G8901998-11-17017 November 1998 Responds to to Lt Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20195G9101998-11-17017 November 1998 Responds to to Lt Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20195G8801998-11-17017 November 1998 Responds to to Senator Lt Conners Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20195G9181998-11-17017 November 1998 Responds to to Lt Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community IR 05000219/19980031998-11-13013 November 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/98-03 Issued on 980717.Corrective Actions Will Be Examined During Future Insp of Licensed Program ML20196D1431998-11-10010 November 1998 Forwards Exam Forms with Answers,Results Summary for Plant & Individual Answer Sheets of GFE Section of Written Operator Licensing Exam,Administered on 981007.Without Encl ML20195C4111998-11-0606 November 1998 Discusses 980825 Gpu Submittal of Proposed Mod for Ocnpp Core Support Plate Which Involved Installation of Wedges During 17R Outage.Licensee Intends to Use Recommendations of BWRVIP-25 & BWRVIP-50.SE Accepting Proposed Mod Encl ML20195B7981998-11-0505 November 1998 Discusses Alternative Evaluation of Flaws in Ferritic Piping.Core Spray Sys Test Line Was Concluded to Have Acceptable Level of Quality & Safety ML20155C6881998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7201998-10-29029 October 1998 Responds to Ltr to Assemblyman Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7051998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7481998-10-29029 October 1998 Responds to Ltr to Assemblyman Morgan, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6241998-10-29029 October 1998 Responds to Ltr to Senator Connors,Dtd 980926,re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7021998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6661998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6841998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6721998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7251998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7371998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6981998-10-29029 October 1998 Responds to Recent Ltr to Senator Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6481998-10-29029 October 1998 Responds to Ltr to Sentor Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7091998-10-29029 October 1998 Responds to Ltr to Assemblyman Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C8781998-10-29029 October 1998 Informs That Oyster Creek Generating Station Operating License,Paragraph 2.C.5 Re Evaluation of Core Spray Internals Insp Requires Authorization from NRC Before Plant Is Restarted from Refueling Outage.Plant Restart Authorized ML20155C7301998-10-29029 October 1998 Responds to Ltr to 9th District Legislative Offices, Re Possible Closure of Oyster Creek Nuclear Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155D2041998-10-26026 October 1998 Forwards Synopsis of 980604 Investigation Rept 1-98-027 Re Possible Discrimination Against Employee for Contacting NRC in Nov 1997 with Security & Safety Concerns ML20154Q9021998-10-20020 October 1998 Forwards Insp Rept 50-219/98-08 on 980727-0913.No Violations Noted.Licensee Have Established & Implemented Effective Programs for Initial & Continuing Training of Workers, Especially Those Having Access to Controlled Areas ML20154L3001998-10-14014 October 1998 Forwards Safety Evaluation Re Reduced Scope of IGSCC Insp, During Refueling Outage 17 ML20154J8251998-10-0707 October 1998 Discusses Concerns Raised to NRC on 980913 Re Oyster Creek. Thoroughness of NRC Insps as Documented in NRC Integrated Insp Rept 50-219/98-03 Was of Concern 1999-09-30
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I JUL 111990
- Docket No. 50-219
, GPU Nuclear Corporation
' ATTN: Mr. Eugene E. Fitzpatrick Vice President and Director F
syster Creek Nuclear Generating Station P.-0. Box 388-P Forked River, New Jersey. 08731-E -- Gentl emen :
Subject:
SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS AND REQUALIFICATION
. EXAMINATIONS
< In a' telephone conversation between Mr. H. Tritt, Operations Training Supervisor,
-and Ms. Tracy Walker, Senior Operations Engineer, arrangements were made for-the administration of licensing examinations and requalification examinations at the Oyster Creek Nuclear Generating StTtion.
The examinations are scheduled for the week of October 15, 1990.
. To meet the above schedule, it will be necessary for you to -furnish the reference material listed in Enclosure 1, " Reference Material Requirements" by August i 13, 1720, Any delay-in receiving approved, properly bound and indexed reference matrnal, or the submittal of inadequate or incomplete reference material may result in; the' examination being rescheduled. Mr. H. Tritt has been advised of Lour' reference material requirements, and the address where each set is=to be-mailed.
You are responsible for providing adequate space and accommodations-for administration'of the written examinations. Enclosure 2, " Requirements for Administration of Written-Examination," describes our requirements for conducting these examinations.
Enclosure 3 contains the Rules and Guidelines that will be in effect during the administration of the written examinations. The' facility management is responsible for ensuring that all applicants are aware of these rules.
=The facility staff review of the initial licensing written examination will be conducted in accordance with requirements specified in Enclosure 4, " Requirements for Facility Review of Written Examinations.;"
The' Chief Examiner may request that the facility submit a proposed examination for use during the examination week in addition to the reference material requirements of Enclosure 1. Submission of a proposed examination, even if requested, is 4 optional. However, if a proposed examination is submitted, those personnel
' participating in its development will become subject to the security restrictions described below.
l OFFICIAL RECORD COPY WALKER /REQUAL/50-219 - 0001.0.0 07/03/90 h 9007230154 900711 I PDR ADOCK 03000219 ' ll3 V FDC
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GPU Nuclear Corporation 2 Any facility. representatives under the security agreement shall be restricted from knowingly communicating by any means the content or scope of the requalifi-cation examination to unauthorized persons and from participating _in any facility programs such as instraction, examination, or tutor.ing in which an identifled requalification examinee (s) will be present. These restrictions shall apply from the day that the facility representative signs the examination security 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.
Preliminary senior reactor operator license applications should be submitted at least 30 days before the examination dates so that we will be able to review the training and experience of the candidates, process the medical certifi-cations, and prepare final examiner assignments after applicant eligibility has been determined. If the applications are not received at least 30 days before the examination dates, it is likely that a pastponement will be necessary.
Applications certifying completion of all tra:ning requirements should be received by the Region fourteen (14) days prior to the examination date, Mr. Tritt has been informed of the above requiremen's.-
This request is covered by Office of Management and Budget Clearance Number 3150-0101 which expires May 31, 1992. The estimated average burden is 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per response, including gathering, 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 Records and Reports Management uranch, Division of Information Support Services, Office of Information Resources Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555; and to the Paperwork Reduction Project (3150-0101), Office of Management and Budget, Washington, D.C. 20503.
Thank you for your consideration in this matter. If you have any questions regarding the examination procedures and requirements, please contact me at (215) 337-5210.
Sincerely, Original Sigueo byA,
&do:afd:n RICHARD J* CONF" Chief Richard J. Conte, BWR Section Operations Branch Division of Reactor Safety 0FFICIAL RECORD COPY WALKER /REQUAL/50-219 - 0001.1.0 1 07/03/90
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'GPU Nuclear Corporation 3
Enclosures:
- 1. Reference Material. Requirements
- 2. Requirements for Administration of Written Examinations
- 3. NRC Rules and Guidelines for Written Examinations-
,4. Requirements for Facility Review of Written Examinations se cc w/encls:
s.
J. Kowalski, Training Manager M, Laggart, BWR Licensing Manager Licensing Manager, Oyster Creek Public Document Room (PDR) local Public Document Room (LPDR)
- Nuclear Safety-Information Center (NSIC)
NRC Resident Inspector State of New Jersey-bec w/encis:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o encl)
.Section Chief, DRP.
J. Caldwell, ED0 A. ' Dromerick, Project Manager,- NRR T, Walker, DRS-R. Conte, DRS OL Facility File DRS Files (3)
DRS:RI DRS:RI
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/ 07/jj/90 07//v/90 OFFICIAL RECORD COPY WALKER /REQUAL/50-219 - 0001.1.1 07/03/90
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ENCLOSURE 1 REFERENCE MATERIAL REQUIREMENTS
- 1. Existing learning objectives, Job Performance Measures and lesson plans (including training manuals, plant orientation manual, system descriptions, etc.).
A copy of the facility Job and Task Analysis (JTA), specifying the knowledge and abilities required of an operator at the facility. Each particular knowledge and/or ability will include an importance rating correlating it to ensuring the health and safety of the public.
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 for preparing applicants for initial SRO licensing. The written material shall include learning objectives and the details presented during lectures, rather than outlines. Training materials shall be identified by plant and unit, bound, tabbed, and indexed. Training materials, which include the following, shall be provided:
. System descriptions including descriptions of all operationally
. relevant flow paths, components, controls and instrumentation.
System training material should draw parallels to the actual procedures used for operating the applicable system.
Complete and operationally useful descriptions of a" safety-systi.1
. interactions and, where available, B0P 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.
- 2. ' Complete Procedure Index (inciuding surveillance procedures, etc.)
-3. All administrative procedures (as applicable to reactor operation or safety) 4, All integrated plant procedures (normal or general operating procedures)
- 5. All emergency procedures (emergency instructions, abnormal or special procedures)
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- 6. Standing orders (important orders that are safety related and may super- !
sede the regular procedures)
- 7. Surveillance procedures (procedures that are run frequently, i.e., weekly) 8.: Fuel-handling and core-loading procedures g 9. All annunciator / alarm response procedurt
- 10. Radiation protection manual (radiation- control manual or procedures) I L :ll. . Emergency plan implementing procedures q
- 12. Technical Specifications (and interpretations, if available) i
- 13. System operating procedures
- 14. Piping and Instrumentation-diagrams, electrical single-line diagrams, or i flow diagrams '
- 15. Technical Data Book, and/or Plant curve information as.used by operators f and facility precautions, limitations and set points (PLS) for the facility i
-16. Licensee Event Reports for the previous two years (as applicable to
. licensed operators)
- 17. Questions and answers specific to the facility training program which may ;
-be used -in the written or operating examinations in addition to the items specified in item 18 (voluntary by licensee) t
.18 .- Test, items to support the' written and plant walk-through portions of the i requalification examinations.
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[ a. A minimum of 700 test items for use in the written examination .
equally divided between the two ;ections of the written examinatior.
and-which~ cover all safety related elements of the facility job task analysis'(JTA)
- b. A minimum of 75 Job performance measures (JPMs) for use on the walk-through portion of the operating examination. To the extent possible, approximately 40% of the JPMs should evaluate "in plant" t
- u. tasks (system / component operation outside the control room)
- c. An Examination Test Outline or Sample Plan (to be submitted by September 17,1990)
- 19. Any additional training material utilized 1, ' " nsed operator requalification training not included in ite..
1 through 17.
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'The above reference material shall be approved, final issues and:shall 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 adminstration of the examination. All procedures and reference material shall be bound with appropriate indices or tables of ,}
contents so'that they can be used efficiently. Failure to provide complete, -)
properly bound'and indexed plant' reference material could result in cancell--
. j ation or rescheduling of the examinations, i 1
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t ENCLOSURE 2 h 2 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS
- 1. A single room shall be provided for administration of the initial written i examination and Section B of the requalification examination. The location of this room and supporting restroom facilities shall be such as to prevent i L contact with all other facility and/or contractor. personnel during the '
written examination. If necessary, the facility should make arrangement ,
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 cs determined ;
by.the Chief Examiner. Minimum spacing should be one applicant per table ,
with a three foot space between tables. ,
- 3. Suitable arrangements shall be made by the facility if the applicants are !
to have lunch, coffee, or.other refreshments. These arrangements shall comply with item 1 above and shall be reviewed by the examiner and/or !
1 -proctor. -
t e 4. The facility licensee shall provide pads of 8-1/2 by 11 inch lined paper in unopened packages for each applicant's use in competing the examina-tion. The examiner shall distribute these pads to the applicants.
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'5. Applicants may bring pens, pencils, calculators or slide rules into the ,
examination room. Only black ink or dark. pencils should be used for !
writing answers to questions.
- 6. 'The reference material used in the control room mockup for Section A of the requalification examination will be reviewed by the chief examiner. '
No material will be used that is solely used for training.
7 .- Copies of reference material for Section B of.the requalification written examination shall be provided. The reference material will be reviewed by the chief examiner and will consist of Technical Specifications, operating / abnormal procedures, administnitive procedures, and Emergency ,
Plans os available to the plant operators. . Examinees for the initial' ,
licensing examination will not have access to these materials. No wall '
charts, models, other training materials shall be present-in the #
examination room.
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ENCLOSURE 3 NRC RULES AND GUIDELINES FOR WRITTEN EXAMINATIONS
< 1. Use black ink or dark pencil ONLY to facilitate legible reproduction. -!
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- 2. Print your.name in th> blank provided on the cover sheet of the examina- i h
tion.
r 7, 3. Fill in the date on ti.. cover sheet of the examination, if necessary.
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- 4. . Answer each question on the examination or aaswer sheet provided. If additional paper is required, use only the lined paper provided by the p examiner. Do not write on the back side of the page. 3 Use abbreviations only if they are commonly used in facility literature.
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.6. The point -value for each question is indicated in parentheses after the i p -question and can be used as a guide for the depth of answer required. ;
- 7. Show all calculations, methods or assumpt ons used to obtain an answer to . #
a short answer test item.
- 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 t points, and you give five responses. each response will be worth 0.20 ;
potnts. If one of your five responsst is incorrect 0.20 will be deducted and your total credit for tha questfen will be 0.80, even though you may have listed the four co rect responses in the answer key. ;
- 10. Partial credit s:9y be given, except or multiple choice questions.
Therefore, ANSMR ALL PARTS OF THE QUMTION AND 00.NOT LEAVE ANY ANSWERS ;
BLANK. ,
- 11. If parts of the examination are not cia r with respect to their intent, I ask questions of the examiner nnly, h 12. . You must sign tne statemer:t on the cover sheet that indicates the work on the examination is your own and that you have not received of buen given ,
assistance in completing the examiantion,- This must be sign +c AFTER the examination has been completed. -
- 13. Rest room trips are to be limited and only one ex.aminee at h time may leave. You must avoid all contact with anyone outside the examination '
, room to avoid even the appearaneta or possibility of examinction I
eomptomise. '
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- 14. Cheating on the examination would result in automatic denial of your- !
application or revocation of your license and could result in more severe !
! , penalti?s.
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- 15. When you are finished and have turned.in your completed examination, L s leave the examination area. If you are found in this crea while the ;
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' examination is in progress your license may be denied or revoked. '
fore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK. ;
- 16. To pass the examination, you must achieve a grade of 80% or greaser.
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! For Requalification Examinations j
~ 17. Each section of the' examination is designed to take approximately 90 I 1
minutes to complete. You will be given two hours to complete each L
, section to allow for thirty minutes of review. t 18.. The_ examination has been time validated by knowledgeable persons. You I should be aware'that not'every answer needs to be verified by consulting .
- a. reference and excessive usage of reference material may cause you to .
not complete the exam in the allotted time.
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- 19. . Due to existence of questions that will require all- examinee's to refer t'o -
the same. indications or controls, particular care must be taken to ,
maintain individual examination security and avoid any possibility of l
. compromise or appearance of cheating. ;
For. initial. examinations:
- 20. There is a time limit of four (4) hours for completion of the i' examination.
. 21.- .When turning in your examination, assemble the completed examination with examination-questions, examination aids and answer sheets. In addition a turn-in all scrap paper. '
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ENCLOSURE _4 REQUIREMENTS FOR FACILITY REVIEW OF WRITTEN EXAMINATIONS j i I. At the option of the Chief Examiner, the facility may review the written examination up to two weeks prior to its administration. Tais review may '
take place at the facility.or in the Regional office. The review will be r conducted using the same material sent to the NRC for exam generation ;
purposes. The Chief Examiner will coordinate the details of the review ;
with.the facility. An NRC examiner will always be present during the +
g review.
i When thi, option of examination review is utilized, the facility reviewers
't will: sign the- following statement prior to being allowed access to the :
examination. The examination or written notes will not be retained by the i
facility.
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- a. Pre-Examination Security Agreement I, acknowledge that I have acquired specialized know-ledge concerning the examination scheduled for t at _ as of the date of my signature below. I agree i
that I will not knowingly divulge any information concerning this
- examination to any unauthorized persons. I understand that I am not i to participate in any instruction involving those applicants '
scheduled to be administered the above examination from this date >
until<after the examination has been administered. I further under-4 stand that violation of the conditions of this agreement may result in the examination being cancelled and/or enforcement ac'. ion against ,
myself'or the facility licensee by whom I am employed or represent. '
Signature /Date
' In addition, the facility staff reviewers will sign the following a 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 examinations administered during the week of at to any unauthorized- i persons. I did not participate in providing any instruction to4those
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applicants who were administered the examination from the date. I entered into this security agreement until the completion of
-examination administration.
L L Signature /Date
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- 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-L 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 0 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 on site 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-I grading the examination may occur.
- 3. The following format should be adhered to for submittal of specific 1 comments;
- a. Listing of.NR0 Question, answer and reference
- 5. Facility comment / recommendation
- c. Reference (to support facility comment)
NOTES: 1. No change to the examination will be made without submittal of references to support the facility comment. -Any supporting documentation that was not previously supplied, should be provided.
- 2. Comments made without a concise facility recommendation will-not be addressed.
'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
-informed that only written comments that are properly supported will be considered in the grading of the examination.
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