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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20138H3831999-10-25025 October 1999 Forwards Draft Model of Renewed License for Calvert Cliffs, Unit 2 to Illustrate How List of Minimum Requirements Could Be Incorporated Into License Condition ML20217M9991999-10-22022 October 1999 Forwards Response to NRC 990930 RAI Re Void Swelling Degradation Mechanism,Per License Renewal Application for Ccnpp,Units 1 & 2 ML20217M1721999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept Form Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20212M2631999-10-0404 October 1999 Informs That Staff Concluded That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Calvert Cliffs Nuclear Power Plant ML20216J8671999-10-0101 October 1999 Forwards Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant. Rev Accurately Presents Changes Made Since Previous Submittal,Necessary to Reflect Info & Analyses Submitted to NRC or Prepared,Per to NRC Requirements ML20212J7811999-09-30030 September 1999 Requests That Licensee Address Potential Aging Mgt Issue Re Effects of Void Swelling of Rv Internals by Making Plant Specific Commitment to Implement Focused age-related Degradation Insp for Evidence of Void Swelling in Future ML20212J5611999-09-29029 September 1999 Informs That on 990916,NRC Completed mid-cycle Plant Performance Review of Calvert Cliffs.No Areas in Which Util Performance Warranted Addl Insp Beyond Core Insp Program Identified.Historical Listing of Plant Issues,Encl ML20216H7831999-09-28028 September 1999 Forwards Addl Info Re NRC SER for Ccnpp,Units 1 & 2,per License Renewal Application ML20212D5361999-09-20020 September 1999 Forwards Rev 1 to Calculation CA04048, Fuel Handling Accident During Reconstitution, as Agreed During 990909 Telcon ML20212C1861999-09-15015 September 1999 Requests That NRC Complete Review of TR CED-387-P,Rev 00-P, Abb Critical Heat Flux Correlations for PWR Fuel, by 000201.Util Expects to Use ABB-NV Correlation for Current non-mixing Vane Fuel in Reload Analyses in 2000 for Ccnpp ML20212A2001999-09-0808 September 1999 Forwards Insp Repts 50-317/99-06 & 50-318/99-06.Two Violations Being Treated as Noncited Violations ML20211N8971999-09-0707 September 1999 Responds to Ltr to D Rathbun of NRC Dtd 990720,in Which Recipient Refers to Ltr from Wc Batton Expressing Support on Renewal Application of Baltimore Gas & Electric Co for Calvert Cliffs Plants ML20211H9841999-08-31031 August 1999 Provides Comments Re Data Entered in Rvid for Ccnpp,Units 1 2,per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211K3091999-08-27027 August 1999 Informs That During 990826 Telcon,L Briggs & B Bernie Made Arrangements for NRC to Inspect Licensed Operator Requalification Program at Calvert Cliffs Npp.Insp Planned for Wk of 991025 ML20211J1611999-08-17017 August 1999 Documents Bg&E Consultations with MD Dept of Natural Resources Re Potential Impacts to Chesapeake Bay Critical Area & Forest Interior Dwelling Bird Habitat,Per Ccnpp License Renewal.Telcons Ref Satisfy Consulting Requirement ML20210V1181999-08-17017 August 1999 Forwards Toxic Gases Calculations for Control Room Habitability,As Discussed During 990713 Telcon.Util Will Make Final Submittal for Toxic Gases After NRC Has Completed Review of ARCON96 ML20210T5061999-08-16016 August 1999 Forwards Rev 0 to Ccnpp COLR for Unit 2,Cycle 13, Per Plant TS 5.6.5 ML20210U2761999-08-13013 August 1999 Forwards Listed Info Re Guarantee of Payment of Deferred Premiums for Ccnpp,Units 1 & 2,IAW 10CFR140.21 Requirements ML20210S8131999-08-12012 August 1999 Forwards Summary of Various Open Licensing Actions for Bg&E That Were Completed During Unit 2 Refueling Outage Ending 990506 ML20210S8101999-08-12012 August 1999 Forwards Application Requesting Renewal of License for Mv Seckens,License SOP-10369-2.Without Encl ML20210S7901999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data for Period of 990101-990630,IAW 10CFR36.71(d) ML20210Q1941999-08-11011 August 1999 Informs That Info Submitted in 981130 Application Re CEN-633-P,Rev 03-P,dtd Oct 1998,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20210N5881999-08-0606 August 1999 Forwards ISI Rept for Ccnpp,Unit 2,fulfilling Intentions & Requirements Stated in Program Plan & Commitment to Comply with ASME Code Section XI ISI Requirements ML20210N1291999-08-0505 August 1999 Forwards NRC Response to W Batton Ltr Expressing Support of Renewal Application for Calvert Cliffs Plants as Requested in Ltr ML20210N5491999-08-0505 August 1999 Requests That License SOP-10371-2,for RW Scott,Be Renewed IAW 10CFR55.57.Individual Has Satisfactorily Discharged License Responsibilities Competently & Safely.Without Application ML20210N5471999-08-0505 August 1999 Requests That License SOP-10031-3,for DF Theders,Be Removed from Active Files for Ccnpp,Due to Individual Being Reassigned to Position No Longer Requiring License ML20210N9291999-08-0404 August 1999 Forwards Clarification to Initial Response to Biennial Rept on Status of Decommissioning Funding,As Required by 10CFR50.75(f)(1) ML20210J0741999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by Nrc.Web Site Should Reflect Info within 2 Wks ML20211B5381999-07-30030 July 1999 Expresses Appreciation for Support in Y2K Training & Tabletop Exercise Held on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by NRC ML20211C0951999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 ML20211C3251999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 ML20210E4941999-07-23023 July 1999 Informs That 1999 Emergency Response Plan Exercise Objectives Is Scheduled for Wk of 991025.Exercise Scenario Will Test Integrated Capability & Major Portion of Elements Existing within Emergency Response Plan ML20210D0911999-07-22022 July 1999 Responds to to Chairman Jackson Referring to Ltr from New 7th Democratic Civic Club,Inc.Forwards Staff Response to W Batton,President of New 7th Democratic Civic Club,Inc ML20210C5011999-07-21021 July 1999 Informs That SL Walters,License OP-10096-3 & CC Zapp,License Number SOP-2188-9,have Been Reassigned within Organization & No Longer Require NRC License,Per 10CFR50.74(a).Removal of Subject Licenses from Active Files for Ccnpp,Requested ML20210C2681999-07-20020 July 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e) ML20210A5021999-07-20020 July 1999 Responds to ,Expressing Support for Renewal of Operating Licenses for Calvert Cliffs Plant & to Concerns Re Lack of Specificity for License Renewal Regulations & Length of Time Set Aside for Public Comment ML20211N9101999-07-20020 July 1999 Forwards Correspondence Author Received from New 7th Democratic Club Civic,Inc Raising Some Serious Concerns About Renewal of Nuclear Reactor Licenses for Calvert Cliffs Power Plant ML20210C8461999-07-19019 July 1999 Informs That CF Farrow,License OP-10648-1,will No Longer Be Employed with Bg&E,As of 990709,per 10CFR50.74(a).Removal of Subject License from Active Files for Ccnpp,Requested ML20209J5171999-07-16016 July 1999 Forwards Comments from Accuracy Review of License Renewal Application SER ML20210B7651999-07-15015 July 1999 Forwards SER Denying Licensee Proposed TS Amend Dtd 981120, to Delete TS Requirements for Tendon Surveillance & Reporting Because TS Requirements Duplication of Requirements in 10CFR50.55a.Notice of Denial Encl ML20209G2081999-07-13013 July 1999 Forwards Insp Repts 50-317/99-05 & 50-318/99-05 on 990509- 0626.No Violations Noted ML20210A6311999-07-0606 July 1999 Discusses Closure of TACs MA0532 & MA0533 Re Response to Requests for Addl Info to GL 92-01,rev1,suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2 ML20209C1391999-07-0202 July 1999 Forwards Responses to Open & Confirmatory Items Based on Review of SER for Bg&E Application for Renewal of Operating Licenses for Calvert Cliffs.Bg&E Intends to Forward Comments Based on Accuracy Verification in Near Future ML20210D1531999-06-30030 June 1999 Informs of Receipt of from New 7th Democratic Civic Club,Inc Expressing Support for License Renewal. Requests Consideration in Addressing Concerns & Recommendations ML20209B5781999-06-29029 June 1999 Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML20210D1741999-06-24024 June 1999 Expresses Opinions on Renewal of Nuclear Reactor Licenses Re Plant & Support Renewal Application of Bg&E.Requests That NRC Revise Procedures to Allow Sufficient Time for Public to Review,Evaluate & Respond to Info ML20211H8431999-06-23023 June 1999 Ack Participation of Calvert Cliffs Nuclear Engineering Dept in NRC Cooperative Research Project with Univ of Virginia. Copy of Relevant Portion of NRC Cooperative Agreement with Univ of Virginia Encl ML20196C6831999-06-21021 June 1999 Discusses Proposed Alternative Submitted by Bg&E for Calvert Cliffs NPP to Requirements of 10CFR50.55a(g)(4) in Regard to Compliance with Latest Approved Edition of ASME Code,Section XI for Third Ten Year Insp Interval Beginning on 990701 ML20196C4291999-06-21021 June 1999 Forwards Rev to ERDS Data Point Library for Ccnpp,Unit 2,per 10CFR50,App E,Section VI.3.a.Table Provides Brief Summary of Changes ML20195J8271999-06-16016 June 1999 Ack Receipt of to Jackson,Chairman of NRC Re Environ Impacts of Increased Patuxtent River Complex Flight Operations on Ccnpp.Clarification & Correction of Listed Statement Found on Page Two,Provided 1999-09-08
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062G6791990-11-21021 November 1990 Forwards SE Determining That Load Profile Used During Surveillance Test Procedures Meets Requirement of Tech Spec 4.8.2.3.2.e,per Unresolved Item Noted in Insp Repts 50-317/90-80 & 50-318/90-80 IR 05000317/19900281990-11-14014 November 1990 Discusses 901102 Enforcement Conference Re Insp Repts 50-317/90-28 & 50-318/90-28 Covering Security Event ML20216K1541990-11-13013 November 1990 Forwards Safety Insp Repts 50-317/90-31 & 50-318/90-31 on 901029-1102.No Violations Noted ML20217A0131990-11-0909 November 1990 Forwards Insp Repts 50-317/90-25 & 50-318/90-25 on 900916-1020.One Noncited Violation Noted ML20058E9821990-11-0101 November 1990 Forwards List of Unimplemented Generic Safety Issues at Plant,Per Util 900627 Response to Generic Ltr 90-04 ML20058A7001990-10-19019 October 1990 Forwards Safeguards Insp Repts 50-317/90-28 & 50-318/90-28 on 901010 & 11.Violation Noted ML20058A6841990-10-17017 October 1990 Forwards Insp Repts 50-317/90-23 & 50-318/90-23 on 900812- 0915.No Violations Noted ML20059N9421990-10-12012 October 1990 Advises of Resolution of Auxiliary Feedwater Issue,Per .Issue Concerns Ability of AFW Sys to Provide Flow to Steam Generators Following Pipe Break ML20062B2041990-10-12012 October 1990 Advises of Acceptance of 900924 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28, Item 2.2,Part 2 Vendor Interface for Safety-Related Components IR 05000317/19900081990-10-11011 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-317/90-08 & 50-318/90-08 ML20059N5781990-10-0909 October 1990 Advises That Util 900510 Submittal of Revised Section of Inservice Insp Program Plan Addressed Provisions of Safety Evaluation ML20062B8361990-10-0909 October 1990 Forwards Special Team Insp Rept 50-317/90-24 on 900904-07 Re 900830 Reactor Vessel Water Level Anomaly ML20059N2231990-10-0101 October 1990 Forwards Safety Evaluation Accepting Proposed Actions Re Potential Design Deficiency,Per LER 89-023 ML20059N1181990-09-28028 September 1990 Forwards Safety Insp Repts 50-317/90-22 & 50-318/90-21 on 900827-31.No Violations Noted.Post Maint Testing Program Assessed to Be Comprehensive,Well Implemented & Met Objectives of Performance Improvement Program ML20059M7751990-09-27027 September 1990 Advises That NRC Approved Request for Relief from ASME Code Section XI Re Reactor Coolant Charging Pumps in ML20059K7041990-09-0707 September 1990 Ack Receipt of Util 900515 Response to Violations Noted in Insp Repts 50-317/90-01 & 50-318/90-01.Agrees That Thrust of Notice of Violation Not Accurate But That Actual Violation Was Failure to Comply w/10CFR50,App B,Criterion Xvi ML20059E3371990-08-27027 August 1990 Forwards Insp Repts 50-317/90-17 & 50-318/90-15 on 900710-13.No Violations Noted.Util Requested to Provide Complete Corrective Actions Being Considered to Prevent Recurrence of Welding Deficiencies within 30 Days ML20059E1921990-08-24024 August 1990 Forwards Insp Repts 50-317/90-18 & 50-318/90-17 on 900716-20.No Violations Noted ML20059E2981990-08-23023 August 1990 Advises That 890313,1103 & 900228 Revs 9,10 & 11 to Plant Contingency Plan,Consistent w/10CFR50.54 & Acceptable.Revs Withheld (Ref 10CFR73.21) ML20058N3641990-08-0909 August 1990 Forwards Notice of Withdrawal of 900801 Applications for Amend to License DPR-69 Re Shift of Min Pressurization Temp Between 530 & 20 Psia on Heatup & Cooldown Curves ML20058P1331990-08-0808 August 1990 Forwards Radiation Safety Insp Repts 50-317/90-14 & 50-318/90-12 on 900625-29.No Violations Noted ML20058N0481990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Other Power Reactor Licenses in Region 1 Should Provide for Sharing of Info & Experiences Involving Engineering Initiatives & Solutions of Problems Common to All ML20056A4081990-07-24024 July 1990 Forwards Insp Repts 50-317/90-12 & 50-318/90-11 on 900604-08.No Violations Noted ML20055G5931990-07-18018 July 1990 Forwards Corrected Cover Ltr for Insp Repts 50-317/90-10 & 50-318/90-10,revising Insp Rept Numbers ML20055H1211990-07-18018 July 1990 Advises That Encl Review of Cen 387-P, C-E Owners Group Pressurizer Surge Line Flow Stratification Evaluation, Inadequate.Insufficient Bases Provided to Conclude That Power Surge Line Meets Code Limits for 40-yr Plant Life ML20055G5951990-07-18018 July 1990 Corrected Cover Ltr Forwarding Insp Repts 50-317/90-10 & 50-318/90-10 ML20055F9241990-07-17017 July 1990 Informs That All Activities Re Reactor Vessel Level Monitoring Sys & Core Exit Thermocouples Completed Except for Tech Specs Based on Review of 870501 & 880427 Submittals ML20055F9561990-07-17017 July 1990 Advises That Actions Re NRC Bulletin 87-002, Fastener Testing to Determine Conformance W/Applicable Matl Specs, Adequate,Per Insp Repts 50-317/90-08 & 50-318/90-08 ML20055G1331990-07-12012 July 1990 Forwards Insp Repts 50-317/90-13 & 50-318/90-13 on 900603-30.No Violations Observed ML20055F5421990-07-10010 July 1990 Advises That Requalification Program Evaluation Scheduled for Wk of 901022.Facility Requested to Furnish Approved Items Listed in Encl 1, Ref Matl Requirements in Order for Examiners to Adequately Prepare for Visit ML20055E5311990-07-0606 July 1990 Forwards Request for Addl Info Re Facility Control Assembly Action Program,Per 900607 Control Element Assembly Failure at Maine Yankee.Confirmation of NRC Understanding That Util Intends to Implement C-E Plan Also Requested ML20055E9081990-07-0202 July 1990 Forwards Exam Repts 50-317/90-07OL & 50-318/90-07OL on 900507-10 ML20055J3181990-06-29029 June 1990 Forwards Insp Repts 50-317/90-10 & 50-318/90-10 on 900604-08.No Violations Noted ML20055D0731990-06-27027 June 1990 Advises That Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wk of 901029.Ref Matls,Listed on Encl,Should Be Provided by 900829 IR 05000317/19900041990-06-14014 June 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-317/90-04 & 50-318/90-04.Also Ack Schedular Slippage from 900601 to 0701 for Resolution of Unresolved Items ML20059M8351990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248E9161989-10-12012 October 1989 Advises That Licensing Activities Associated W/Nrc Bulletin 88-004,considered Complete ML20248D3591989-09-25025 September 1989 Forwards Amend 10 to Indemnity Agreement B-70,reflecting Changes to 10CFR140,effective 890701 IR 05000317/19890191989-09-22022 September 1989 Forwards Safety Insp Repts 50-317/89-19 & 50-318/89-20 on 890807-11.No Violations Noted ML20247Q2781989-09-21021 September 1989 Forwards Safety Insp Repts 50-317/89-21 & 50-318/89-21 on 890818 & Notices of Violation & Deviation ML20247P6701989-09-20020 September 1989 Forwards Request for Addl Info Re Util 890525 Response to Generic Ltr 88-14, Instrument Air Supply Problems Affecting Safety-Related Equipment. Info Requested within 35 Days of Ltr Date ML20247P6611989-09-18018 September 1989 Requests Addl Info Re Generic Ltr 88-05, Boric Acid Corrossion of Carbon Steel Reactor Pressure Boundary.... NRC Should Be Notified of Full Implementation of Program within 30 Days Following Implementation ML20247Q2371989-09-15015 September 1989 Requests Addl Info Re Util 890502 Response to Generic Ltr 89-08 Re Implementation of long-term Erosion/Corrosion Monitoring Program to Ensure Structural Integrity of All & Two Phase high-energy Carbon Steel Sys at Plant ML20247G2841989-09-13013 September 1989 Approves 890207 Request to Withhold CEN-382(B)-P, Verification of Acceptability of 1-PIN Burnup Limit of 60 Mwd/Kg for Calvert Cliffs,Units 1 & 2 from Public Disclosure (Ref 10CFR2.790) ML20247E8311989-09-0909 September 1989 Requests Util Furnish Ref Matl in Encl List, Ref Matl Requirements for Reactor/Senior Reactor Operator Licensing Exam, by 891004.Written Exam Scheduled for 891204 & Operating Exams Scheduled for 891205-08 ML20246Q1781989-09-0505 September 1989 Discusses Conclusions of Investigation 1-89-003 Re QC Inspector Harassment & Intimidation by Craft Personnel. Insufficient Evidence Found to Conclude Incidents Constitute Violation of 10CFR50.7.Response Requested within 30 Days ML20246K1251989-08-31031 August 1989 Ack Receipt of & Payment of Civil Penalty in Amount of $75,000,proposed by NRC in ML20246L3301989-08-28028 August 1989 Forwards Insp Repts 50-317/89-14 & 50-318/89-14 on 890516-0703 & Notice of Violation.Mgt of Surveillance Programs Has Been Source of Continuing Concern to NRC IR 05000317/19890121989-08-24024 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-317/89-12 & 50-318/89-12 ML20246G1221989-08-22022 August 1989 Forwards Safety Insp Repts 50-317/89-17 & 50-318/89-18 on 890717-21 & Notice of Deviation 1990-09-07
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20138H3831999-10-25025 October 1999 Forwards Draft Model of Renewed License for Calvert Cliffs, Unit 2 to Illustrate How List of Minimum Requirements Could Be Incorporated Into License Condition ML20217M1721999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept Form Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20212M2631999-10-0404 October 1999 Informs That Staff Concluded That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Calvert Cliffs Nuclear Power Plant ML20212J7811999-09-30030 September 1999 Requests That Licensee Address Potential Aging Mgt Issue Re Effects of Void Swelling of Rv Internals by Making Plant Specific Commitment to Implement Focused age-related Degradation Insp for Evidence of Void Swelling in Future ML20212J5611999-09-29029 September 1999 Informs That on 990916,NRC Completed mid-cycle Plant Performance Review of Calvert Cliffs.No Areas in Which Util Performance Warranted Addl Insp Beyond Core Insp Program Identified.Historical Listing of Plant Issues,Encl ML20212A2001999-09-0808 September 1999 Forwards Insp Repts 50-317/99-06 & 50-318/99-06.Two Violations Being Treated as Noncited Violations ML20211N8971999-09-0707 September 1999 Responds to Ltr to D Rathbun of NRC Dtd 990720,in Which Recipient Refers to Ltr from Wc Batton Expressing Support on Renewal Application of Baltimore Gas & Electric Co for Calvert Cliffs Plants ML20211K3091999-08-27027 August 1999 Informs That During 990826 Telcon,L Briggs & B Bernie Made Arrangements for NRC to Inspect Licensed Operator Requalification Program at Calvert Cliffs Npp.Insp Planned for Wk of 991025 ML20210Q1941999-08-11011 August 1999 Informs That Info Submitted in 981130 Application Re CEN-633-P,Rev 03-P,dtd Oct 1998,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20210N1291999-08-0505 August 1999 Forwards NRC Response to W Batton Ltr Expressing Support of Renewal Application for Calvert Cliffs Plants as Requested in Ltr ML20211C0951999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 ML20210J0741999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by Nrc.Web Site Should Reflect Info within 2 Wks ML20211C3251999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 ML20211B5381999-07-30030 July 1999 Expresses Appreciation for Support in Y2K Training & Tabletop Exercise Held on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by NRC ML20210D0911999-07-22022 July 1999 Responds to to Chairman Jackson Referring to Ltr from New 7th Democratic Civic Club,Inc.Forwards Staff Response to W Batton,President of New 7th Democratic Civic Club,Inc ML20210A5021999-07-20020 July 1999 Responds to ,Expressing Support for Renewal of Operating Licenses for Calvert Cliffs Plant & to Concerns Re Lack of Specificity for License Renewal Regulations & Length of Time Set Aside for Public Comment ML20210B7651999-07-15015 July 1999 Forwards SER Denying Licensee Proposed TS Amend Dtd 981120, to Delete TS Requirements for Tendon Surveillance & Reporting Because TS Requirements Duplication of Requirements in 10CFR50.55a.Notice of Denial Encl ML20209G2081999-07-13013 July 1999 Forwards Insp Repts 50-317/99-05 & 50-318/99-05 on 990509- 0626.No Violations Noted ML20210A6311999-07-0606 July 1999 Discusses Closure of TACs MA0532 & MA0533 Re Response to Requests for Addl Info to GL 92-01,rev1,suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2 ML20211H8431999-06-23023 June 1999 Ack Participation of Calvert Cliffs Nuclear Engineering Dept in NRC Cooperative Research Project with Univ of Virginia. Copy of Relevant Portion of NRC Cooperative Agreement with Univ of Virginia Encl ML20196C6831999-06-21021 June 1999 Discusses Proposed Alternative Submitted by Bg&E for Calvert Cliffs NPP to Requirements of 10CFR50.55a(g)(4) in Regard to Compliance with Latest Approved Edition of ASME Code,Section XI for Third Ten Year Insp Interval Beginning on 990701 ML20196E0371999-06-16016 June 1999 Forwards Insp Repts 50-317/99-03 & 50-318/99-03 on 990321-0508.Apparent Violation Being Considered for Escalated Enforcement Action ML20207G4331999-06-0707 June 1999 Informs That in Response Request by Nrc,Fema Evaluated Adequacy of Evacuation Plans & Training of Local First Responders for Area Around Ccnpp.Copy of FEMA & Encl to Ltr,Which Provides FEMA Recommendations Encl ML20207G4701999-06-0707 June 1999 Informs of Reorganization in NRR Ofc,Effective 990328. Organization Chart Encl ML20207B2491999-05-21021 May 1999 Forwards Insp Repts 50-317/99-04 & 50-318/99-04 on 990405-16.No Violations Noted.Insp Revealed Few Potential & Plausible Aging Effects NRC Team Determined Should Be Included in License Renewal Application ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20206A6171999-04-22022 April 1999 Responds to Request for Statistics on Allegation Re Plant by J Osborne.Encl Tables Provides Breakdown of Allegations by Source Category for Allegations Receive in CY95-98 & First Six Month of 1999 ML20205R0961999-04-15015 April 1999 Forwards Insp Repts 50-317/99-01 & 50-318/99-01 on 990131- 0320.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20205P1381999-04-0909 April 1999 Discusses 990223 Ppr.Forwards Plant Issues Matrix & Insp Plan.Since Spring 1998 Unit 1 Operated at Essentially Full Power.Unit 2 Had Similar Power History Except for Jul 1998 Manual Reactor Trip Due to Small Bore Pipe Steam Leak ML20205P1281999-04-0808 April 1999 Forwards Monthly Status Rept on Licensing Activities & Regulatory Duties of NRC for Mar 1999.Targets for Licensing Action Age & Completion Rates & License Renewal Process for Calvert Cliffs Remains on Schedule ML20205E5511999-03-26026 March 1999 Forwards Insp Repts 50-317/99-02 & 50-318/99-02 on 990208-12.No Violations Noted.Insp Was First of Three Planned Visits to Verify Ccnpp License Renewal in Compliance with Requirements of Rule for License Renewal ML20205G8841999-03-24024 March 1999 Discusses Bg&E Application Filed on 980408 for Renewal of Operating Licenses DPR-53 & DPR-68 for Calvert Cliffs Units, 1 & 2.For Listed Reasons,Partial Exemption from 10CFR170 Fees Granted IAW 10CFR170.11(b)(1) ML20205B0291999-03-24024 March 1999 Informs That Author Determined That Partial Exemption from 10CFR170 Fee Requirements Appropriate for Footnote 4 of License Renewal Application for Plants,Units 1 & 2,dtd 980408,that Staff Determines Has Generic Value to Industry ML20204H6281999-03-21021 March 1999 Forwards SER Reflecting Status of Staff Review of Util License Renewal for Calvert Cliffs Nuclear Power Plants, Units 1 & 2 ML20207E9641999-03-0404 March 1999 Forwards Insp Repts 50-317/98-12 & 50-318/98-12 on 981213- 990130 & Notice of Violation Re Failure of Maint Workers to Tighten Bolting for Svc Water Heat Exchanger ML20207G8631999-02-25025 February 1999 Forwards Operator Initial Exam Repts 50-317/99-301OL & 50-318/99-301OL on 990122 & 25-29 (Administration) & 990201- 05 (Grading).All Applicants Passed All Portions of Exams ML20203D3981999-02-0505 February 1999 Forwards Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons ML20203A6141999-02-0303 February 1999 Submits Details on Listed Areas Re Inspection Plan of Insp Scheduled for 990203 ML20202J1901999-01-28028 January 1999 Discusses License Renewal for Operating Power Reactors.Two Applications Received for Renewing Operating Licenses. Commission Established Adjudicatory Schedule Aimed at Completing License Renewal Process in 30-36 Months ML20202H7621999-01-28028 January 1999 Discusses Guidance Re License Renewal for Operating Power Reactors Developed in Response to FY99 Energy & Water Development Appropriations Act Rept 105-581 ML20199G4121999-01-20020 January 1999 Forwards SE Accepting Util USI A-46 Implementation Program for Plant ML20199K8481999-01-19019 January 1999 Forwards Insp Repts 50-317/98-11 & 50-318/98-11 on 981025-1212.No Violations Noted ML20199L6621999-01-19019 January 1999 Informs That Licensee Authorized to Administer Initial Written Exam to Listed Applicants on 990122.NRC Region I Operator Licensing Staff Will Administer Operating Test to Applicants ML20199F4101999-01-0808 January 1999 Forwards SE Accepting Util 960213,0725 & 981202 Responses to GL 95-07, Pressure Locking & Thermal Binding of Safety- Related Power-Operated Gate Valves ML20198S4291999-01-0707 January 1999 Requests Addl Info Re License Renewal Application as Application Relates to Staff Position on Environ Qualification ML20198S7491999-01-0707 January 1999 Forwards SER Accepting Licensee ,Suppl by 980424 & 1124 Ltrs Proposing Changes to Rev 49 of Calvert Cliffs Nuclear Power Plant Quality Assurance Program Description in Accordance with 10CFR50.54(a)(3) ML20196K2991999-01-0404 January 1999 Forwards Notice of Consideration of Approval of Transfer of Facility Operating License & Matl License & Opportunity for Hearing in Response to Application ML20202D0271998-12-15015 December 1998 Forwards Notice of Withdrawal of Application for Amend to License DPR-69.Proposed Change Would Have Modified Svc Water Head Tanks.Without Encl ML20198L3431998-12-12012 December 1998 Forwards Insp Repts 50-317/98-10 & 50-318/98-10 on 980706-10 & 1118.Insp Rept Documents App R Issues Which Constituted Violations of NRC Requirements.Nov Not Issued Because, Violations Identified by Licensee Staff as Part of C/A ML20198B1791998-12-10010 December 1998 Advises of Planned Insp Effort Resulting from Calvert Cliffs NPP Review Conducted on 981110.Details of Insp Rept for Next 6 Months & Historical Listing of Plant Issues Considered During Process Encl 1999-09-08
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- Docket Nos. 50-317
.50-318
- Baltimore Gas and Electric Company ATTN: ;Mr. George C; Creel jy_ 'Vice President
' Nuclear. Energy-
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Calvert Cliffs Nuclear Power Plant MD Rts 2 & 4, P.O. Box 1535
'Lusby, Maryland :20657 Gentlemen:
SUBJECT:
REACTOR OPERATOR AND SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS In'a telephone conversation between Mr. J. Hill, Supervisor, Operations Training, and Mr. J.: Prell,' Examiner, arrangements were made for'the administration of
-licensing-examinations at_the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2.
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The written examinations are scheduled for December 4., 1989. The operating y examinations are scheduled for December 5-8, 1989.
To ' meet the above schedule, it will be necessary for you to furnish the refer-u ence material listed in Enclosure 1, " Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations," by October 4,1989.
' Any delay in receiving approved, properly bound and indexed reference mater.ial, or the submittal of inadequate or incomplete reference material may result in.
the examination being rescheduled. Mr. Hill has-been advised of our reference
- material requirements, and the address where each set is to be mailed.
You are responsible for providing adequate space and accommodations for 9dmini-stration of the written examinations. Enclosure 2, " Requirements for Admini-stration 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 examination. The facility management is respons-
-ible.for ensuring that all applicants are aware of these rules.
The. facility staff-review of the written examination will be conducted in accordance with requirements specified in Enclosure 4, " Requirements for Facility . Review of Written Examinations."
To better document simulator examinations, the Chief Examiner will have the simulator operator record predetermined plant conditions (i.e., plant i
' pressure, temperature, pressurizer level, etc.), for each simulator scenario. '
The applicants will be responsible for providing this information, with any l 8909180013 890909 PDR N
V ADOCK 05000317 PDC f g f
., : ~ J Ba1.timore Gas & Electric Company. 2 :
1; appeal of a simulator operating examination. Therefore, your training staff should retain the original simulator examination scenario information until all applicants who took examinations have either passed the opuating examination, accepted the dental of their license, or filed an appeal.
All completed seni'or reactor operator -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 cantidates, process the medical certifications, and prepare final examiner assignments after applicant eligi-bility has been determined. If the applications are not received at least 30 days before the examination dates, it is likely that a postponement will be necessary.
Mr. Hill has been informed of the above requirements.
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 reg 0rding this burden estimate or any other aspect of this collection of-information, including suggestions for reducing this burden, to the Records and Reports Management P. ranch,-Division of Information Support Services, Office of Information Resources Mr.nagement, 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 undersigned at (215) 337-5211.
Sincerely, Original igned Byt' ete elgroth, ef PWR Section Operations Branch Division of Reactor Safety
Enclosures:
- 1. Reference Material Requirements for Reactor / 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/ enclosures:
W. J. Lippold, General Supervisor, Technical Services Engineering
.T. Magette, Administrator, Nuclear Evaluations J. Hill, Supervisor - Operations Training I 0FFICIAL RECORD COPY PRELL/C.C. 90-DAY /8/31/89 - 0001.0.1 06/16/87
.. : g Baltimore Gas & Electric Company 3 p Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of Maryland (2) bec w/encls:
, Region I Docket' Room (with concurrences)
J. Wiggins, DRP L. Tripp, DRP D. Limroth, DRP S. McNeil, NRR J. Dyer, EDO Chief Examiner
-Assigned Examiners OL- Facility File Project Manager, NRR DRS Files (2) bec w/o encls:
Management Assistant, DRMA DRS:RI i[
DRS:RI DR :
Eselgroth G o Prell/sifqdg{g 9/5/89 9/ /89 7
/ 89 0FFICIAL RECORD COPY PRELL/C.C. 90-DAY /8/31/89 - 0002.0.0 06/I6/87
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ENCLOSURE.1 REFERENCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS I '. Existing learning. objectives, Job Performance Measures and lesson plans-(including training manuals, plant orientation manual, system descript-ions,- reactor. theory, thermodynamics, etc.)
A copy of the facility Job and Task Analysis (JTA), specifying the know-ledges and abilities required'of an operatcr at the facility. Each parti-
.cular knowledge and/or abilit'y will include an importance rating correlat--
.ing it to ensuring the health and the safety.of the public. If a JTA is
- not-furnished, the Knowledges and Abilities' Catalog for Nuclear Power Plant Operators,.NUREG 1122 (1123) will be used to establish content valid-ity for the examination.
l 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 R0 and SR0 licensing. The written mater-
.ial 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. FAILURE TO PROVIDE COMPLETE, PROPERLY BOUND AND INDEXED PLANT REFERENCE MATERIAL MAY RESULT IN THE RETURN OF THE MATERIAL T0 THE PERSON WHO IS THE HIGHEST LEVEL OF CORPORATE.
l MANAGEMENT WHO IS RESPONSIBLE FOR PLANT OPERATIONS (E.G., VICE PRESIDENT OF NUCLEAR OPERATIONS). ACCOMPANYING THE MATERIAL WILL BE A COVER LETTER EXPLAINING THE DEFICIENCIES IN THE REFERENCE MATERIAL AND THE FACT THAT THIS WAS THE REASON THE EXAMINATIONS WERE CANCELLED OR POSTPONED. Train-ing materials which include the following shall be provided:
System descriptions including descriptions of all operationally relevant flow patht...' components, controls and instrumentation. .
. System training material should draw parallels to the actual proce-dures used for operating the applicable system.
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.
Comprehensive theory' material that includes fundamentals in the area of theory of reactor operation, thermodynamics, heat transfer and I
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2 fluid flow, as well as specific' application to actual in plant com-ponents. For example, mechanical theory material on pumps shall include pump theory as well as descriptions of how these principles ,
actually apply to major plant pumps and the systems in which they are {
installed (i.e. , Reactor Coolant Pumps, all ECCS pumps, Recirculation '
pumps, Feedwater pumps and Emergency Feedwater pumps). Reactor Theory material shall include descriptions that draw explicit ties 'l between the fundamentals and the actual operating limits followed in l the plant (i.e., reactor theory material should contain explanations how principles relate to the actual curves used by operators to verify shutdown margin or calculate an ECP).
- 2. Complete Procedure Index (including surveillance procedures, etc.)
- 3. All Administrative Procedures (as applicable to reactor operation or safety)
- 4. All integrated plant procedures (normal or general operating procedures)
- 5. All emergency procedures (emergency instructions, abnormal or special pro- ,
cedures)
- 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 or that can be run on the simalator)
- 8. Fuel-handling and core-loading procedures, (initial core-loading proce-dure, when appropriate) j
- 9. All annunciator / alarm procedures
- 10. Radiation protection manual (radiation control manual or procedures) i
- 11. Emergency plan implementing procedures j 1
- 12. Technical Specifications (and interpretations, if available) for all units i for which licenses are sought.
- 13. System Operating Procedures
- 14. Piping and Instrumentation diagrams, electrical single-line diagrams, or I flow diagrams j
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- 15. Technical Data Book, and/or Plant curve information as used by operators j and facility precautions, limitations, and set points (PLS) for the j facility I l
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-16. Licensee' Event Reports for the previous two years. l
- 17. Examination Question Bank specific to the facility training program which may be used in the written or operating examinations. In particular, multiple choice questions'for the written examination. (Voluntary by ,
licensee). l
- 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.
- c. A description of simula+or failure capabilities for valves, b eakers, 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-later 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 scenarios that expose the applicants to situations of degraded pressure control (PWR), degraded heat removal capability (PWR and BWR) and containment challenges (PWR and BWR).
(Voluntary by licensee).
- 1. Simulator instructors manual (voluntary by licensee). '
- j. Description of the scenarios used for the training class.
- 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
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I 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-7'
-tion or rescheduling of the examinations.
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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. examination. If necessary, the facility should make arrangements for the use of a suitable room at a local school, motel, or other building. Obtaining this room.is the responsibility of the licensee.
- 2. Minimum spacing is required to ensure examination integrity as determined by the Chief Examiner. Minimum spacing should be one 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 refreshimnts. These arrangements shall comply with Item 1 above and shall be reviewed by the examiner and/or proctor.
- 4. The facility licensee shall provide pads of 8-1/2 by 11 inch lined paper in unopened packages for each applicant's use in completin'g 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 pencils 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.
ENCLOSURE 3 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.
. READ THE FOLLOWING INSTRUCTIONS VERBATIM:
During the administration of this. examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. After the examination has been completed, you must sign the statement on the cover sheet, indicating that the work is your own and you have not received or given assistance in 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 '
room to avoid'even.the appearance or possibility of cheating.
- 4. Use black . ink or dark pencil only to facilitate legible reproductions.
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- 5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
- 6. Fill in the date on the cover sheet of the examination (if necessary).
- 7. You may write your answers on the examination question page or on a separate sheet of paper. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
- 8. If you write your answers on the examination question page and you need more space to answer a specific question, use a separate sheet of the paper provided and insert it directly after the specific question. DO NOT WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
- 9. Print your name in the upper right hand corner of the first page of each section of your answer sheets whether you use the examination question pages or separate sheets of paper. Initial each page.
- 10. Before you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination question page.
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- 11. If you are using separate sheets, number each answer as to category and n' umber (i .e. 1.04,6.10) and skip at least 3 lines between answers to allow space for grading.
- 12. Write "End of Category " at the end of your answers to a category.
- 13. Start each category on a new page-.
- 14. Write "Last Page" on the last answer sheet.
- 15. 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.
- 16. The point value for each question is indicated in parentheses after the question. The amount of blank space on an examination question page is
-NOT an indication of the depth of answer required.
.17. Show all calculations, methods, or assumptions used to obtain an answer.
.38. Partial credit may be given for other than multiple choice questions.
Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK.
~19. Partial credit will NOT be awarded for questions using multiple choice selection formatting. The correct answer must stand on its own merit.
- 20. Proportional grading will be applied. Any additional wrong information that is provided may count against you. For example, if a question is worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth 0.20 points. If one of your five responses is incorrect, 0.20 will be deducted and your total credit for that question will be 0.80 instead of 1.00 even though you got the four correct answers.
I 21. If the intent of a question is unclear, ask questions of the examiner l only.
- 22. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition, turn in all scrap paper.
- 23. To pass the examination, you must achieve an overall grade of 80% or greater and at least 70% in each category.
- 24. 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 without review immediately following the examination.
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- 25. There is a time limit of (6) hours for completion of the examination (or some other time if less than the full examination is taken).
- 26. 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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i ENCLOSURE 4 REQUIREMENTS FOR FACILITY REVIEW OF WRITTEN EXAMINATIONS ]
-I. At the option of the Chief Examiner, the facility may review the written
-examination up to two weeks prior to its administration. This review may take place at the facility or inLthe Regional office. .The Chief Examiner will coordinate the details of the review with the. facility. An NRC exam-iner will alweys 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 examination 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 that 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 after the examination has been administered. I understand that viola -
tion of this security agreement could result in the examination being voided.
P Signature /Date In addition, the facility staff reviewers will sign the following statement after the written examination has been administered,
- b. Post-Examination Security Agreement I did not, to the best of knowledge, divulge any information concerning the written examination administered on to any unauthorized persons. I did not participate in providing any instruction to those reactor opera-tor and senior reactor operator applicants who were administered the examination from the time that I was allowed access to the examination.
Signature /Date
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'2 L2. . Regardless of whether the above examination review option is exercised, immediately following the administration of the written examination, the facility staff shall be provided a marked up' copy of the examination and-
.the' answer key. . The copy of the written examination shall' include pen and
. ink changes made to questions during the examination administration.
If the facility did not review the examination prior to its administra-
. tion, they will: have five (5) working days from the day of the written examination to submit formal comments. If the. facility reviewed the.
examination. prior to its administration, any additional comments must be given to an examiner prior to his/her leaving the site at the end of the week of the written examination administration. In either case, the comments will be addressed to the responsible Regional Office by the highest 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 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 document:ation 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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