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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M7571999-10-22022 October 1999 Advises That Attachment 1 to ,Marked as Proprietary,Re Safety Limit MCPR & Fuel Vendor Change Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) ML20217M2101999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20217H8471999-10-18018 October 1999 Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs ML20217K8441999-10-15015 October 1999 Submits Revised Commitment to NRC Bulletin 90-01,Suppl 1 for Hope Creek Generating Station ML20217H9771999-10-13013 October 1999 Forwards SRO & RO Initial Exam Rept 50-354/98-302,suppl Rept on 990125-29,mtg Meeting on 990322,990429-30 & 0617-18 in-office Review & 990720 Telcon on Appeal Results.Overall, 11 of 16 Applicants Received NRC Licenses ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML20217C4391999-10-0606 October 1999 Informs That Util Authorized to Administer Initial NRC Retake Written Exam to Applicant Listed,During Week of 991011 ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys ML20217A9601999-10-0404 October 1999 Forwards Errata Redressing Deficiencies & Correcting Two Typos to Ufsar,Rev 10.Incorporate Attached Pages/Figures Into Controlled Copies of UFSAR ML20217A6861999-10-0101 October 1999 Forwards Insp Rept 50-354/99-05 on 990711-0829.Four Violations Occurred Re Areas of Fire Protection,Operation at Reduced Feedwater Inlet Temp & safety-related Battery Charging Operation & Being Treated as NCVs LR-N990430, Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review1999-09-28028 September 1999 Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML20217K7781999-09-16016 September 1999 Forwards Discharge Monitoring Rept for Hope Creek Generating Station for Month of Aug 1999. Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML20212B4021999-09-13013 September 1999 Submits Supplemental Info Related to Hope Creek License Change Request (LCR) H98-08,submitted to NRC on 981230, Re Flood Protection TS Changes ML18107A5221999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations ML20211N5421999-09-0808 September 1999 Forwards Amend 121 to License NPF-57 & Safety Evaluation. Amend Revises TSs by Relocating Procedural Details of RETS to Offsite Dose Calculation Manual LR-N990395, Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also1999-09-0101 September 1999 Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also ML20211B5341999-08-20020 August 1999 Forwards RAI Re 2nd 10-yr ISI Interval Relief Requests Re Plant.Info Requested to Be Provided within 60 Days of Receipt of Ltr ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML20210R4911999-08-11011 August 1999 Forwards Insp Rept 50-354/99-04 on 990530-0711.No Violations Noted.Inspectors Reviewed Performance Indicators Submitted as Part of Pilot Program for New Regulatory Oversight Process & Verified Data ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 ML20210H9241999-07-26026 July 1999 Informs That State of Nj Dept of Environ Protection Has No Comments on Licensee 990517 Request for Amend to TS by Adding TS 3.3.10, Instrumentation of OPRM Sys ML20210F3271999-07-22022 July 1999 Forwards SE Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3 Re First 10-year Interval for ISI Program at Hope Creek ML20210D3971999-07-16016 July 1999 Forwards Discharge Monitoring Rept for Hope Creek Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection 05000354/LER-1999-007, Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl1999-07-14014 July 1999 Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl ML20209G2831999-07-14014 July 1999 Disclosure Closure of TAC MA1194 Re Licensee Response to RAI to GL 92-01,Rev 1,Suppl 1, Rc Structural Integrity, for Plant LR-N990250, Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds1999-07-0909 July 1999 Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds ML20196J4421999-07-0101 July 1999 Forwards Request for Addl Info Re Increase of Allowable Main Steam Isolation Valve (MSIV) Leak Rate & Deletion of MSIV Sealing Sys for Plant LR-N990316, Responds to NRC Request for Info Re Y2K Readiness at Npps, Per GL 98-01,suppl 1.Disclosure Encl1999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Npps, Per GL 98-01,suppl 1.Disclosure Encl ML18107A4131999-06-25025 June 1999 Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC ML20196F9441999-06-21021 June 1999 Forwards Insp Rept 50-354/99-03 on 990419-0529.Violations Noted.Two Violations of NRC Requirements Occurred Re Reactor Bldg Ventilation Setpoints & Control Rod Drop Analyses ML20196E6471999-06-21021 June 1999 Forwards Revised marked-up TS Page for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively. Revised Pages Do Not Alter Conclusions Reached in 10CFR50.92 No Significant Hazards Analysis Previously Submitted ML20209B6441999-06-21021 June 1999 Offers No Comments on Licensee 990529 Request for Revs to Plant Radiological Effluent Ts,Per GL 89-01 ML20209C0621999-06-21021 June 1999 Forwards NPDES Discharge Monitoring Rept,May 1999, for Hcgs.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection ML20196E9631999-06-17017 June 1999 Informs That Util Has Made Change to Commitment Stated in NRC Ser,Suppl 5.Commitment That Has Been Changed Is Item Number 1 of First Paragraph on Page 9-3 of Ser,Suppl 5 ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First LR-N990295, Submits Change 1 to Relief Request RR-A4,which Clarifies Requirements Re Snubber Visual Insps.Request Was Submitted as Part of Plant Second Interval ISI Program on 9905111999-06-16016 June 1999 Submits Change 1 to Relief Request RR-A4,which Clarifies Requirements Re Snubber Visual Insps.Request Was Submitted as Part of Plant Second Interval ISI Program on 990511 05000354/LER-1999-006, Forwards LER 99-006-00 Re Esfa B Channel Primary Containment Isolation Signal Actuation.Attachment a Lists Commitments Util Making to NRC Re LER1999-06-15015 June 1999 Forwards LER 99-006-00 Re Esfa B Channel Primary Containment Isolation Signal Actuation.Attachment a Lists Commitments Util Making to NRC Re LER ML20195J1101999-06-0707 June 1999 Informs of Completion of Review of Providing Updated Status on Implementation of Commitments Made in Response to GL 89-13.Confirms Revs Made to Previous Commitments to Resolve Monitoring Pressure Drop Problem ML20195J1051999-06-0707 June 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Jw Clifford Will Be Section Chief for Hope Creek Generating Station ML20207F2681999-06-0303 June 1999 Responds to by Forwarding Gfes & NRC Written Exam Grades for List of Hope Creek Operators Submitted by DE Jackson.Absence of Gfes Grade Indicates That Operator Previously Issued RO or SRO License.Without Encl ML20207D0201999-05-27027 May 1999 Discusses 990512 Meeting to Identify Insp Activities at Hope Creek Facility Over Next Six Months & Informs of Planned Insps in Order for Licensee to Have Opportunity to Prepare & Provide Region I with Feedback on Schedule Conflicts ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML20207A3451999-05-20020 May 1999 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs ML20195B9931999-05-20020 May 1999 Forwards NPDES Discharge Monitoring Rept,Apr 1999, for Hgcs.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection ML20206Q4461999-05-14014 May 1999 Forwards SE Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant ML20206U8451999-05-14014 May 1999 Forwards Insp Rept 50-354/99-02 on 990308-0418.Violations Re Fuel Handling Errors & Missed Temp Monitoring During Reactor Vessel Head Tensioning Occurred & Being Treated as non-cited Violation 1999-09-08
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062E7751990-11-15015 November 1990 Discusses Util 900910 Submittal of Addl Info Re Reliability of Bailey Solid State Logic Modules ML20197H7051990-11-0808 November 1990 Forwards Exam Rept 50-354/90-17OL Administered During Wks of 900827,0924 & 1001 ML20058H0531990-11-0606 November 1990 Informs That Dembek Replaced C Shiraki as Staff Project Manager for Plant ML20058H0461990-11-0606 November 1990 Forwards List of Unimplemented Gsis,Per Generic Ltr 90-04 ML20062B6611990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20059P0031990-10-0505 October 1990 Grants 900928 Request for Regional Waiver of Compliance Re Safety Auxiliaries Cooling Sys ML20058N8261990-08-13013 August 1990 Advises That Request for Relief from ASME Code Requirements for Svc Water Piping,Granted Until Next Scheduled Outage Per 10CFR50.55a(g)(6)(i) & Guidance of Generic Ltr 90-05 ML20058M4371990-08-0101 August 1990 Forwards Safety Insp Rept 50-354/90-13 on 900618-22.No Violations Noted ML20058L7541990-07-23023 July 1990 Forwards Radiological Controls Insp Rept 50-354/90-15 on 900625-29.No Violations Noted ML20059M9281990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20043G3471990-06-11011 June 1990 Advises That Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wks of 900924 & 1001.Ref Matl Listed in Encl 1 Requested by 900724 ML20055C6241990-05-22022 May 1990 Forwards Exam Rept 50-354/90-06OL Administered During Wk of 900319 ML20034C4021990-04-24024 April 1990 Clarifies NRC Position on Reporting Requirements in Generic Ltr 88-01 on NRC Review & Approval of Flaw Evaluations Prior to Resumption of Operation ML20012E7671990-03-22022 March 1990 Forwards Safety Insp Rept 50-354/90-02 on 900226-0302.No Violations Noted.Several Radiation Monitor Calibr Results Reviewed in Region I Ofc During Wk of 900312.Results within Acceptance Criteria ML20012D0221990-03-20020 March 1990 Advises That Individual Plant Exam Approach,Methodology & Schedule,Provided in in Response to Generic Ltr 88-20,acceptable.Schedule Changes Should Be Reported to NRC ML20012D6081990-03-15015 March 1990 Forwards Safety Insp Repts 50-354/90-04,50-272/90-06 & 50-311/90-06 on 900226-0302.No Violations Noted ML20033E8621990-03-0505 March 1990 Forwards Results of Generic Fundamentals Exam Section of Written Operator Licensing Exam Administered on 900207 ML20033F0361990-03-0202 March 1990 Requests Addl Info Re Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment ML20006E1651990-02-0707 February 1990 Forwards Maint Team Insp Rept 50-354/89-80 on 891002-13 & Notice of Violation.Team Concluded That Util Implementing Generally Effective Maint Program.Improvements Needed to Reduce Backlog of Overdue Maint Procedure Reviews ML20006B4931990-01-29029 January 1990 Advises That Installation of Hardened Wetwell Vent at Facility,Described in ,Acceptable Per Generic Ltr 89-16.Use of Individual Plant Exams to Develop Supplemented Criteria for Vent Mod Design Acceptable ML19354E3351990-01-22022 January 1990 Forwards Safety Insp Rept 50-354/89-20 on 891107-900105.No Violations Noted ML20005F6621990-01-0505 January 1990 Advises That Licensee 881207 Submittal Re Simulator Certification Per 10CFR55.45(b)(2) Complete.Util Responsible for Regulatory Compliance w/plant-ref Simulator ML20006D7051990-01-0505 January 1990 Forwards Revised NRC Forms 396 & 398,personal Qualifications Statement & Certification of Medical Exam by Licensee, Respectively IR 05000354/19890121990-01-0505 January 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Licensed Operator Requalification Insp Rept 50-354/89-12(OL).Effectiveness of Util Written Commitments Considered Unresolved ML20042D3331989-12-22022 December 1989 Advises That Senior Reactor Operator Licensing Exams Scheduled for 900320-22.Ref Matl Listed in Encl 1 Should Be Furnished by 900119 ML20005E0681989-12-22022 December 1989 Forwards Requalification Remediation Exam Rept 50-354/89-21OL Administered During Wk of 891204 ML19354D5531989-12-21021 December 1989 Forwards Safety Insp Rept 50-354/89-17 on 890926-1106.No Violations Noted ML20248G5531989-09-26026 September 1989 Forwards Exam Rept 50-354/89-08OL Administered During Wk of 890717 IR 05000354/19890141989-09-19019 September 1989 Forwards Safety Insp Rept 50-354/89-14 on 890620-0814.No Violations Noted.Inspectors Noted Addl Attention to Detail Errors by Facility Personnel Similar to Ones Described in Most Recent SALP Rept 50-354/88-99 ML20246E7631989-08-22022 August 1989 Informs of Maint Program Team Insp Scheduled for 891002-13 to Focus on Maint Performance & Whether Components,Sys & Structures Adequately Maintained & Repaired to Perform Intended Safety Function.Encl Ref Matl Requested ML20246J4371989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purpose of Setting Occupational Exposure Limits.Procedures Should Incorporate Applicable Dose Limits of 10CFR20 ML20246C3941989-08-15015 August 1989 Forwards Safeguards Insp Repts 50-272/89-19,50-311/89-17 & 50-354/89-15 on 890710-14.No Violations Noted ML20247N4481989-07-24024 July 1989 Forwards Insp Rept 50-354/89-13 on 890626-30.No Violations Noted ML20247J2841989-07-24024 July 1989 Forwards SER & EGG-NTA-8341 Re Generic Ltr 83-28,Item 4.5.3, Reactor Trip Reliability-On-Line Functional Testing of Reactor Trip Sys ML20246J8671989-07-12012 July 1989 Forwards Safety Insp Rept 50-354/89-11 on 890501-0619.No Violations Noted ML20246F7291989-07-0606 July 1989 Forwards to Ecology Ctr of Southern California Re Petition to Fix or Close Reactors Designed by Ge.Ltr States That Petition Being Treated Under 10CFR2.206 ML20245J8061989-06-27027 June 1989 Grants Util 871211 Relief Requests 3.1.1.1,3.1.1.2 & 3.1.1.3 Re Inservice Insp Plan Category B-A Reactor Vessel Welds,Per 871211 SER ML20247M8211989-05-25025 May 1989 Forwards Directors Decision,Ltr of Transmittal & Fr Notice Re Denial of Ocre 10CFR2.206 Petition on BWR Stability. Request to Reopen Rulemaking on Anticipated Transients W/O Scram Being Considered as Petition Under 10CFR2.802 ML20246N3441989-05-11011 May 1989 Forwards Safety Insp Rept 50-354/89-09 on 890314-0430.No Violations Noted ML20247A0611989-05-0404 May 1989 Forwards SER Accepting Util Response to Generic Ltr 83-28, Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing. Technical Evaluation Rept Also Encl ML20247A7781989-05-0303 May 1989 Extends Invitation to Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Meeting Agenda Encl ML20245B6681989-04-10010 April 1989 Forwards Safety Insp Rept 50-354/89-06 on 890227-0303.No Violations Noted ML20244B5961989-04-0707 April 1989 Forwards Exam Rept 50-354/89-04OL Administered During Wk of 890214 ML20248J3851989-04-0404 April 1989 Advises That Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wk of 890717.Encl Ref Matl Requested by 890515 to Meet Schedule ML20248J1761989-03-31031 March 1989 Forwards Safety Insp Rept 50-354/89-02 on 890124-0313 & Notice of Violation.Concludes That Uncontrolled Installation of Electrical Jumpers in Controls of Drywell Equipment Drain Pumps Represented Violation of NRC Requirements ML20247M9521989-03-27027 March 1989 Forwards Insp Rept 50-354/89-05 on 890227-0303.No Violations Noted.Apparent Violation of Radiation Protection Procedures Identified by NRC Reviewed for Nonissuance of Notice of Violation ML20247E2771989-03-24024 March 1989 Requests Addl Info Re IGSCC Problems in BWR Austenitic Stainless Steel Piping,Per Generic Ltr 88-01.Response Should Be Provided within 60 Days ML20247D3561989-03-23023 March 1989 Confirms Requalification Program Evaluation Scheduled for Wk of 890619,per Telcon.Util Should Furnish Approved Items Listed in Encl 1 ML20247C2371989-03-20020 March 1989 Forwards Eg&G Idaho Evaluation Accepting Rev 10 to ODCM for Plant.Number of Points Remain Open Re Eg&G Suggestions That Could Make ODCM More Useful & Complete ML20236B6061989-03-0606 March 1989 Forwards Safety Insp Rept 50-354/89-03 on 890206-10.No Violations Noted 1990-08-13
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M7571999-10-22022 October 1999 Advises That Attachment 1 to ,Marked as Proprietary,Re Safety Limit MCPR & Fuel Vendor Change Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) ML20217M2101999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20217H8471999-10-18018 October 1999 Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs ML20217H9771999-10-13013 October 1999 Forwards SRO & RO Initial Exam Rept 50-354/98-302,suppl Rept on 990125-29,mtg Meeting on 990322,990429-30 & 0617-18 in-office Review & 990720 Telcon on Appeal Results.Overall, 11 of 16 Applicants Received NRC Licenses ML20217C4391999-10-0606 October 1999 Informs That Util Authorized to Administer Initial NRC Retake Written Exam to Applicant Listed,During Week of 991011 ML20217A6861999-10-0101 October 1999 Forwards Insp Rept 50-354/99-05 on 990711-0829.Four Violations Occurred Re Areas of Fire Protection,Operation at Reduced Feedwater Inlet Temp & safety-related Battery Charging Operation & Being Treated as NCVs ML20211N5421999-09-0808 September 1999 Forwards Amend 121 to License NPF-57 & Safety Evaluation. Amend Revises TSs by Relocating Procedural Details of RETS to Offsite Dose Calculation Manual ML20211B5341999-08-20020 August 1999 Forwards RAI Re 2nd 10-yr ISI Interval Relief Requests Re Plant.Info Requested to Be Provided within 60 Days of Receipt of Ltr ML20210R4911999-08-11011 August 1999 Forwards Insp Rept 50-354/99-04 on 990530-0711.No Violations Noted.Inspectors Reviewed Performance Indicators Submitted as Part of Pilot Program for New Regulatory Oversight Process & Verified Data ML20210F3271999-07-22022 July 1999 Forwards SE Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3 Re First 10-year Interval for ISI Program at Hope Creek ML20209G2831999-07-14014 July 1999 Disclosure Closure of TAC MA1194 Re Licensee Response to RAI to GL 92-01,Rev 1,Suppl 1, Rc Structural Integrity, for Plant ML20196J4421999-07-0101 July 1999 Forwards Request for Addl Info Re Increase of Allowable Main Steam Isolation Valve (MSIV) Leak Rate & Deletion of MSIV Sealing Sys for Plant ML20196F9441999-06-21021 June 1999 Forwards Insp Rept 50-354/99-03 on 990419-0529.Violations Noted.Two Violations of NRC Requirements Occurred Re Reactor Bldg Ventilation Setpoints & Control Rod Drop Analyses ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195J1051999-06-0707 June 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Jw Clifford Will Be Section Chief for Hope Creek Generating Station ML20195J1101999-06-0707 June 1999 Informs of Completion of Review of Providing Updated Status on Implementation of Commitments Made in Response to GL 89-13.Confirms Revs Made to Previous Commitments to Resolve Monitoring Pressure Drop Problem ML20207F2681999-06-0303 June 1999 Responds to by Forwarding Gfes & NRC Written Exam Grades for List of Hope Creek Operators Submitted by DE Jackson.Absence of Gfes Grade Indicates That Operator Previously Issued RO or SRO License.Without Encl ML20207D0201999-05-27027 May 1999 Discusses 990512 Meeting to Identify Insp Activities at Hope Creek Facility Over Next Six Months & Informs of Planned Insps in Order for Licensee to Have Opportunity to Prepare & Provide Region I with Feedback on Schedule Conflicts ML20207A3451999-05-20020 May 1999 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs ML20206U8451999-05-14014 May 1999 Forwards Insp Rept 50-354/99-02 on 990308-0418.Violations Re Fuel Handling Errors & Missed Temp Monitoring During Reactor Vessel Head Tensioning Occurred & Being Treated as non-cited Violation ML20206Q4461999-05-14014 May 1999 Forwards SE Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant ML20206Q6211999-05-14014 May 1999 Informs That on 990119 Licensee Provided NRC with Several Revised TS Bases Pages for Plant.Ts Bases Pages B 3/4 6-1 & B 3/4 6-2 Were Revised ML20206R2691999-05-12012 May 1999 Informs That During 990504 Telcon Between J Caruso & H Hanson,Arrangements Were Made for Administration of Licensing Written Retake Exam at Hope Creek Nuclear Generating Station During Week of 990927 ML20206C8431999-04-22022 April 1999 Forwards SER Authorizing Util 980728 Submitted Relief Requests Associated with Changes Made to Repair Plan for Core Spray Nozzle Weld N5B ML20205S7911999-04-19019 April 1999 Forwards Insp Rept 50-354/99-01 on 990124-0307.Violations Noted.Some Human Performance Errors Occurred During Numerous Outage Activities,Util Appropriately Reacted to Each of Errors & Initiated Corrective Actions ML20205R0861999-04-14014 April 1999 Informs That Final Review of Hard Copy of PPR Re Hope Creek, Issued 990409 Had Error.Electronic Version e-mailed Was Not Effected.Forwards Pp with Correction in Margin.Without Encl ML20205R0461999-04-14014 April 1999 Forwards Associated Page with Correction Marked in Margin of PPR of Salem Issued 990409.During Final Review of Hard Copy, Error Was Noted.Without Encl IR 05000354/19983021999-04-0909 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-354/98-302 Issued on 990226.Response Indicates That Licensee Corrected Violation & Initiated Measures to Prevent Recurrence ML20205N2481999-04-0909 April 1999 Discusses Hope Creek Generating Station Plant Performance Review Conducted for Period April 1998 Through Jan 1999 & Informs of NRC Planned Insp Effort Resulting from Ppr. Historial Listing & Insp Plans for Next Few Months Encl ML20205G5961999-03-19019 March 1999 Forwards Safety Evaluation of Relief Request Re ASME Code Case N-567, Alternate Requirements for Class 1,2 & 3 Replacement Components Section Xi,Div 1. Request Acceptable ML20205F8771999-03-18018 March 1999 Forwards SE Authorizing Licensee 971222 Relief Requests Re Second 10-year Interval for Pumps & Valves IST Program for Hope Creek Generating Station ML20207D5741999-03-0101 March 1999 Discusses Pse&G 980604 Updated Response to GL 96-05 Indicating Intent to Implement Provisions of JOG Program on MOV Periodic Verification at Hope Creek Generating Station. Forwards RAI Re GL 96-05 Program at Hope Creek ML20198H6211998-12-24024 December 1998 Forwards Notice of Withdrawal of 970826,as Suppl 980424 & 0924 Amend Request for FOL NPF-57.Proposed Change Would Have Modified Facility TSs Pertaining to Filtration,Recirculation & Ventilation Sys Surveillance Testing Requirements ML20198L3571998-12-22022 December 1998 Forwards Insp Rept 50-354/98-11 on 981101-1212.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Effective Engineering & Maint Practices & Careful Radiological Work Controls ML20198H6661998-12-17017 December 1998 Informs That Attachment 1 to Ltr LR-N98404,dtd 980825 Marked as Proprietary,Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20196K1371998-12-0909 December 1998 Advises of Planned Insp Effort Resulting from Hope Creek Insp Review Planning Meeting Conducted on 981110.Details of Insp Plan for Next 6 Months Encl ML20197H3841998-12-0707 December 1998 Informs That Licensee Authorized to Administer Initial Written Exams to Listed Applicants on 981222.NRC Region I Operator Licensing Staff Will Administer Operating Tests ML20196H0301998-12-0101 December 1998 Informs That NEDC-32511P,rev 1,dtd Oct 1998 Marked as Proprietary,Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20196F7991998-11-30030 November 1998 Forwards Rept Representing Results of 981026-29 Audit of Year 2000 Pragram at Hope Creek Generating Station.Audit Conducted as Followup to NRC GL 98-01, Year 2000 Readiness of Computer Sys at Npps, Issued 980511 ML20196D0711998-11-23023 November 1998 Forwards Insp Rept 50-354/98-10 on 980920-1031 & Notice of Violation Re Preforming Single Cell Charge on safety-related Battery Cell in Configuration Prohibited by Station Procedures ML20154Q7071998-10-16016 October 1998 Forwards Exam Rept 50-354/98-03OL Conducted by NRC During Periods of 980304-12,0519-21,22-28 & 0629.All Five Reactor Operator Applicants & Four of Five Senior Reactor Applicants Passed Exams ML20154P4011998-10-0909 October 1998 First Final Response to FOIA Request for Records.Records in App a Available in Pdr.Records in App B Partially Withheld (Ref FOIA Exemption 3) IA-98-323, First Final Response to FOIA Request for Records.Records in App a Available in Pdr.Records in App B Partially Withheld (Ref FOIA Exemption 3)1998-10-0909 October 1998 First Final Response to FOIA Request for Records.Records in App a Available in Pdr.Records in App B Partially Withheld (Ref FOIA Exemption 3) ML20154J8501998-10-0909 October 1998 Forwards Insp Rept 50-354/98-08 on 980809-0919 & Notice of Violation Re Inadequate Corrective Actions to Resolve Steam Leaks from Piping Located in Torus Room ML20154F1121998-10-0202 October 1998 Forwards Insp Rept 50-354/98-09 on 980817-26 & 0908.No Violations Identified.Major Areas Inspected:Maint, Engineering & Mgt Meeting ML20154B3341998-09-29029 September 1998 Requests That Encl Info on GE Rept NEDC-32511P Be Reviewed & Revised Proprietary Version of Subj Rept Be Submitted.Some Info in Rept Should Not Be Exempt from Public Disclosure & Should Be Released & Placed in PDR ML20154B3781998-09-25025 September 1998 Informs That Facility Scheduled to Administer NRC Generic Fundamentals Exam on 981007.Sonalysts,Inc Authorized Under Contract to Support NRC in Administration of Activities. Ltr & Encls Provide Instructions & Guidelines IR 05000354/19980061998-09-11011 September 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-354/98-06 Issued on 980721 IR 05000354/19980021998-09-11011 September 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-354/98-02 on 980423.Response Indicated Violations Corrected & Measures Initiated to Prevent Recurrence ML20151W9711998-09-10010 September 1998 Informs That as Part of NRC PRA Implementation Plan, Commission Has Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Have Been Assigned as SRAs in Region I 1999-09-08
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' Docket NoL 50-354 DEC 221989 d
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' Public Service Electric-& Gas Company o ATTN: Mr.; Steven E. Miltenberger
-Vice President and-fy.
. Chief Nuclear,0fficer LPost Office Box 236:
.Hancocks' Bridge,,New Jersey.08038 Gentlemen:
'J
SUBJECT:
SENIOR' REACTOR OPERATOR LICENSING EXAMINATIONS
+
[P lInLa telephone conversation between Mr. W. Gott, Principal Training Supervisor
'and Msr T nWalker, Senior Operations Engineer, arrangements were made for the
- administration of;1icensing examinations at the Hope Creek Generatin Station.
l The written examinations'are scheduled for March 20, 1990. The c w ating-'
Lexaminations are scheduled.for Maren 21-22, 1990.
To meet the:above-schedule, it will be necessary for you to.fuitish the refer-ence material listed in Enclosure 1, " Reference Material Requirements for Senior Rea'ctor1 Operator.~ Licensing l Examinations," by January 19,11990. 1Any delayiin receiving approved,. properly bound andLindexed reference material, -or ethelsubmittalr ofoinadequate or incomplete reference materi~al may. result in the examination;being rescheduled.
Mr. Gott has been^ advised of our-reference imateria1Ltequirements,Jand the address where each-set is to be mailed.
y.
You:are> responsible forlproviding adequate spaceLand accommodations for admini-
-stration of"the written' examinations., " Requirements for Admini -
.stration of Written Examination," describes our requirements for conducting these examinations.
' contains the Rules and Guidelines that will be in effect during the
-administration'of the written examination. The facility management is respons-ible 'for ensuring that all applicants are aware of chese rules.
The facility staff review of the written examination will be cond'ucteM in accordance with requ!rements specified in Enclosure 4, " Requirements 4 r Fr.ci-litytReview of Written Examinations."
To better document simulator examinations, the Chief Examiner will have the csimulator operator. record predetermined plant conditions (i.e., plant pressure, V
. temperature, etc.), for each simulator scenario. The applicants will be
. responsible for providing..this information, with any appeal of a simulator 3 pera;.ing examination.
Therefore, your training staff should retain the 0
' original-simulator examination scenario information until all applicants who took examinations-have either passed the operating examination, accepted the
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- denial of their license, or filed an ypeal.
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!All-completed license applications 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 applicant eligibility has been determined.
If the applications are not received atileast 30' days before the examination a
dates, it is likely that;a postponement will be necessary.
Mr. Gott has been informed'of the above requirements.
I' This request is covered by 0ffice 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 Branch, 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 the 1
undersigned at (215) 337-5210.
Sincerely, GrannatSig$edBy:
Richard J. Conte, Chief Boiling Water Reactor Section Operations Branch Civision of Reactor Safety
Enclosures:
- 1.:
Reference Material Requirements for Senior. Reactor Operator Licensing Examinations 2.-
Requirements for Administration of Written Examinations 3.
NRC. Rules and Guidelines for Written Examinations 4.
Requirements _for Facility Review of Written Examinations cc w/encis:
S. 'LaBruna, Vice President-Nuclear Scott B. Ungerer, Manager, Joint Generation Projects Department, Atlantic Electric Company J..J. Hagen, General Manager - Hope Creek Operations B.. A'. Preston, General Manager - Licensing and Regulation EH..D. Hanson, Manager, Nuclear Training R. Fryling, Jr., Esquire Licensing Project Manager, NRR OFFICIAL RECORD COPY WALKEs/H0PECREEK90-DAY /12/12-
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local: Public Document Room (LPDR) y,
,.NuclearJSafety/ Info'rmationCenter.(NSIC)-
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RegionLI! Docket Room (with concurrences).
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-:R. Conte, DRS'
-T.. Walker, Examiner, DRS m'
H. Williams, Examiner..DRS -
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ENCLOSURE 1 a-B
' REFERENCE MATERIAL REQUIREMENTS FOR SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS w;c i
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, Existing learning objectives, Job Performance Measures and lesson plans (including' training manuals, plant orientation manual, system descript-ions,etc.)
A copy of the_ facility Job ~and Task Analysis (JTA), specifying the know--
ledges-and abilities required of an operator at the facility.
Each parti-cular knowledge and/or ability will-include an importance rating correlat-ing it to ensuring the= health and the safety of the public.
If a JTA is i
l not furnished,=the Knowledges and Abilities Catalog for Nuclear Power Plant Operators, NUREG 1122(112.1) will be used to establish content valid-ity for the examination.
r 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.u j
Training materials shall include all substantive written material used for preparing applicants for initial SR0 licensing.
The written mater-ial shall. include learning objectives and the details presented during-1ectures,- 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:
H LSystem descriptions including descriptions of all operationally T
relevant flow paths, components, controls and instrumentation.
System training material should draw parallels to the actual proce-
'dures used for operating the applicable system.
i Complete and operationally useful descriptions of all safety-system
- interactions and, where available, B0P system interactions under emergency and abnormal conditions, including consequences of anti-cipated operator error, maintenance error, and equipment failure.
Training material used to clarify and strengthen understanding of emergency operating procedures.
12.
Complete Procedure Index (including surveillance procedures, etc.)
'3.
All administrative procedures (ae, applicable to reactor operation or safety) i
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All integrated plant procedures (normal' or general operating procedures) 5.
All emergency procedures (emergency instructions, abnormal or special pro-cedures) e s
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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 e
or that.can be run on the simulator) 8.
. Fuel-handling and core-loading procedures
'9.
All annunciator / alarm response procedures 10.
Radiation protection manual (radiation control manual or procedures)
- 11. ' Emergency plan implementing procedures
- 12. Technical Specifications (and interpretations, if available).
13.
System operating. procedures
- 14. - Piping and Instrumentation diagrams, electrical single-line diagrams, or flow diagrams.
- 15. Technical Data Book, and/or plant curve information as used by operators and facility precautions, limitations, and. set points (PLS) for the facility
.16.
Licensee Event-Reports for the previous two years (as applicable to licensed operators)
- 17.
Examination Question Bank specific to the facility training program which
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may be used in the written or operating examinations, in part'cular,-
r multiple choice questions for the written examination (Voluntery by licensee)
- 18. 'The following on.the plant reference simulation facility a.
List of all preprogrammed initial conditions b.
List of all preset malfunctions with a clear identification number.
The list shall 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 shall be provided. Additionally, an indication of which annunciators are to be initially expected should be given.
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A description of' simulator failure capabilities for valves, breakers, c.
indicators and alarms d.
Where the capability exists, an explanation of the ability to vary
-the severity of a particular_ malfunction shall be provided, i.e.,
-ability to vary the size of a given LOCA or steam leak, or the abil-
- ity;to cause a slow failure of a component such as a feed pump, tur-bine generator or major valve.
(e.g., drifting shut of a main feed-water control valve) e.
An identification of modeling conditions / problems that may impact the examination
. f.-
Identification of any known performance test discrepancies not yet
-corrected g..
- Identification of-differences between the simulator and the reference plant's control room h.
Copies of-facility generated scenarics that expose the applicants to situations of degraded heat removal capability and containment challenges (Voluntary by licensee).
1.
Simulator instructors manual (Voluntary by licensee)
Ej.-
Description oi. the scenarios used for the training class (Voluntary by licensee) 19; Additional material required by the examiners to develop examinations that meet the requirements of.these standards and the regulations 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' administration 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 cancella-
- tion'or rescheduling of the examinations.
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,x ENCLOSURE 2 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS 1..
A single room shall be provided for administration of the written examina-tion.
The location.of this room and supporting restroom facilities shall be such as to prevent contact with all other facility and/or contractor personnel during the written examin. tion.
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 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 1unch, coffee,-or other refreshments. These arrangements shall comply with= Item 1 above and shall be reviewed by the examiner and/or proctor.
4.: gThe facility licensee shall provide pads of 8-1/2 by 11 inch lined-paper in unopened packages for each applicant's use in completing the examina-tion..The examiner shall distribute these pads to the applicants.
5.
Applicants may bring pens, pencils, calculators or slide rules into the examination room. Only black ink or dark per.cils should be used for writing answers to questions.
6.
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 the examination room.
No other equipment or reference material shall be allowed unless provided by the examiner.
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3 ENCLOSURE 3
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NRC RULES'AND GUIDELINES FOR WRITTEN EXAMINATIONS 1.-
' Check identification badges.
2.
Pass out examinations and all handouts.
Remind applicants not to review examination until instructed to do so.
i READ THE FOLLOWING INSTRUCTIONS VERBATIM:
- During the administration of this examination the following rules apply:
1.
Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
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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.
READ THE FOLLOWING INSTRUCTIONS 3.
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 l
, room to avoid even the appearance or possibility of cheating.
4.
Use black' ink or dark pencil only to facilitate legible reproductions.
l 5.
Print your name in the blank provided in the upper right-hand corner of the examination cover sheet, i
6 '.
Fill in the date'on the cover sheet of the examination (if necessary).
7.
You should write your answers on the examination question page. DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
8.
If 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.
00 NOT WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
9..
Initial each page of your answer sheets.
10.
Before you turn in your examination, consecutively number each answer sheet, includir.g any additional pages inserted when writing your answers on the examination question page.
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. 11. Write "Last Page" on the last answer sheet, P:
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Use abbreviations only if they are commonly used in facility literature.
Avoid using symbols such as < or > signs to avoid a simple transposition error resulting in an incorrect answer. Write it out.
~13. - The point value for each question is indicated in parentheses af ter the question. The amount of blank space on an examination question page is NOT an indication of the depth of answer required.
14.
Show all calculations, methods, or assumptions used to obtain an answer.
15.
Partial credit may be given for other than multiple choice questions.
Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
16.
Partial credit will NOT be awarded for questions using multiple choice.
selection. formatting. The correct answer must stand on its own merit, 17.
Proportional grading will be applied. Any additional wrong information L
'that is provided may count against you.
For example, if a question is l--
worth one point and asks for four responses, each of which is worth 0.25 l;
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.
l-18.
If the' intent of~a question is unclear, ask questions of the examiner only.
19.
Ensure that all information you wish to have evaluated as part of your answer is on your answer sheet.
Scrap paper will be disposed of immedi-J ately following the examination without reviews.
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- 20.
When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets.
In addition, L
turn in all scrap paper.
- 21. To pass the examination, you must achieve an overall grade of 80%.
'22.
There is a time limit of 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> for completion of the examination.
- 23. When you are done and have turned in your examination, leave the examina-tion 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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s-t ENCLOSURE 4 d
- REQUIREMENTS FOR FACILITY REVIEW 0F WRITTEN EXAMINATIONS At the opti'n of-the Chief Examiner, the' facility may review the written 1.
o 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 exam-iner will always be present during the review.
When this option of examination review is utilized, the facility reviewers will sign the following statement prior to being allowed access to the
. examination.- The euamination or written notes will not be retained by the facility.
a.
-Pre-Examination Security Agreement I
agree that I will not knowingly divulge any informa-tion concerning the replacement (or initial) examination scheduled for to any unauthorized persons.
I ' understand tliat I am not to participate in any instruction involving those reactor operator or senior reactor operator applicants scheduled to be admini-stered the above replacement (or initial) examination from now until cafter the examination has been administered.
I understand that viola-tion of this security agreement could result in the examination being voided-,
Signature /Date In addition, the facility staff reviewers will sign the following state-ment after the written examination has been administered, b.
Post-Examination Security Agreement I
did not, to the best of knowledge, divulge any informa-tion concerning the written examination administered on to any unauthorized persons.
I did not participate in providing.any instruction to those reactor operator and senior reactor operator appli-cants who were administered the examination from the time that I was allowed access to the examination.
Signature /Date
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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 l
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 on site-level of corporate management for plant operations, e.g.,
Vice President for Nuclear.0perations. 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 examination may occur.
3.
The following format should be adhered to-for submittal of specific comments:
a.
Listing of NRC 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 of:a reference to support the facility comment. Any supporting documentation that was not previously supplied, should be provided.
2.
Comments made without a concise facility recommendation will not be addressed.
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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