|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217D5211999-09-30030 September 1999 Informs That Remediating 3D Monicore Sys at Pbaps,Units 2 & 3 & 3D Monicore/Plant Monitoring Sys at Lgs,Unit 2 Has Been Completed Ahead of Schedule ML20216J3981999-09-29029 September 1999 Submits Comments for Lgs,Unit 1 & Pbaps,Units 2 & 3 Rvid,Rev 2,based on Review as Requested in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20212J6561999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Limerick Generating Station on 990913.Identified No Areas in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20212H6401999-09-24024 September 1999 Forwards Revised Epips,Including Rev 11 to ERP-101 & Rev 18 to ERP-800.Copy of Computer Generated Rept Index Identifying Latest Revs of LGS Erps,Encl ML20212E7941999-09-22022 September 1999 Requests Authorization for Listed Licensed Operators to Temporarily Suspend Participation in Licensed Operator Requalification Program at LGS ML20212E8081999-09-22022 September 1999 Provides Notification That Listed Operators Have Been Permanently Reassigned to Duties That Do Not Require Maintaining Licensed Operator Status,Per 10CFR50.74 ML20212F5481999-09-20020 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing, for Pbaps,Units 2 & 3 & Lgs,Units 1 & 2 ML20212F8991999-09-17017 September 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at Lgs,Units 1 & 2 Have Been Completed 05000353/LER-1999-010, Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl1999-09-16016 September 1999 Forwards LER 99-010-00,re Manual Actuation of Esf.Main CR Ventilation Sys Was Placed in Chlorine Isolation Mode Due to Rept of Faint Odor of Chlorine in Unit 2 Reactor Encl ML20216F7821999-09-16016 September 1999 Forwards Insp Repts 50-352/99-05 & 50-353/99-05 on 990713-0816.One Violation Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Inoperability of Automatic Depression Sys During Maint ML20212A8751999-09-13013 September 1999 Forwards Safety Evaluation of First & Second 10-year Interval Inservice Insp Plan Request for Relief ML20211N5061999-09-0909 September 1999 Forwards TSs Bases Pages B 3/4 10-2 & B 3/4 2-4 for LGS, Units 1 & 2,being Issued to Assure Distribution of Revised Bases Pages to All Holders of TSs ML20212A0091999-09-0909 September 1999 Provides Notification That Licenses SOP-11172 & SOP-11321, for SO Muntzenberger & Rh Wright,Respectively,Are No Longer Necessary as Result of Permanent Reassignment ML20211P8571999-09-0808 September 1999 Forwards Reactor Operator Retake Exams 50-352/99-303OL & 50-353/99-303OL Conducted on 990812 ML20211P3891999-09-0303 September 1999 Informs That During 990902 Telcon Between J Williams & B Tracy,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wk of 991018 05000352/LER-1999-009, Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed1999-09-0101 September 1999 Forwards LER 99-009-00,providing 30-day Written follow-up Rept Re Performance of Maint That Affected Safeguard Sys for Which Compensatory Measures Had Not Been Employed ML20211H2571999-08-26026 August 1999 Informs of Individual Exam Result on Initial Retake Exam on 990812.One Individual Was Administered Exam & Passed ML20211E9191999-08-24024 August 1999 Forwards fitness-for-duty Program Performance Data for Jan-June 1999 for PBAPS & LGS IAW 10CFR26.71(d).Data Includes Listed Info ML20211E9731999-08-23023 August 1999 Forwards LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5, Per TS SRs 4.0.5 & 10CFR50.55a(g) ML20211D6761999-08-20020 August 1999 Forwards non-proprietary Revised Emergency Response Procedures (Erps),Including Rev 29 to ERP-110, Emergency Notification & Rev 17 to ERP-800, Maint Team & Proprietary App ERP-110-1.App Withheld Per 10CFR2.790(a)(6) ML20210T4271999-08-13013 August 1999 Informs That NRC Revised Info in Rvid & Releasing Rvid Version 2 as Result of Review of 980830 Responses to GL 92-01 Rev 1,GL 92-01 Rev 1 Suppl 1 & Suppl Rai.Tacs MA1197 & MA1198 Closed ML20210U2211999-08-10010 August 1999 Forwards Insp Repts 50-352/99-04 & 50-353/99-04 on 990525-0712.One Violation Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Late Performance of off-gas Grab Sample Surveillance 05000353/LER-1999-005, Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint1999-08-10010 August 1999 Forwards LER 99-005-00,re Actuation of Primary Containment & Reactor Vessel Isolation Control Sys,Esf.Fuse Failed Due to Mechanical Failure of Cold Solder Joint ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML20210P4191999-08-0404 August 1999 Forwards Initial Exam Repts 50-352/99-302 & 50-353/99-302 on 990702-04 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam NUREG-1092, Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls1999-08-0303 August 1999 Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls ML20210L2011999-07-28028 July 1999 Forwards Final Personal Qualification Statement (NRC Form 398) for Reactor Operator License Candidate LB Mchugh ML20211F2641999-07-27027 July 1999 Forwards Three Copies of Rev 12 to LGS Physical Security Plan, Rev 4 to LGS Training & Qualification Plan & Rev 2 to LGS Safeguards Contingency Plan. Without Encls 05000352/LER-1999-008, Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator1999-07-23023 July 1999 Forwards LER 99-008-00 Re 990623 Failure of Plant HPCI Sys to Start Due to Failure of HPCI Turbine,Hydraulic Actuator 05000353/LER-1999-004, Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs1999-07-23023 July 1999 Forwards LER 99-004-00 Re 990701 Discovery of Pressure Setpoint Drift of Thirteen Mss SRV Due to Corrosion Induced Bonding within SRVs ML20210E6211999-07-22022 July 1999 Submits Rev to non-limiting Licensing Basis LOCA Peak Clad Temps (Pcts) for Limerick Generating Station (Lgs),Units 1 & 2 & Pbaps,Units 2 & 3 ML20216D3081999-07-19019 July 1999 Requests Renewal of OLs for Listed Individuals,Iaw 10CFR55.57.NRC Forms 398 & 396,encl for Applicants.Without Encl ML20216D8041999-07-19019 July 1999 Submits Summary of Final PECO Nuclear Actions Taken to Resolve Scram Solenoid Pilot Valve Issues Identified in Info Notice 96-007 05000352/LER-1999-006, Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error1999-07-12012 July 1999 Forwards LER 99-006-00 Re 990614 Discovery That Grab Sample of Plant Offgas Sys Was Not Obtained within Time Limit Required by TS 3.3.7.12,Action 110 Due to Personnel Error ML20209F6341999-07-0909 July 1999 Submits Supplemental Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 2.Rev 0 to 1H61R & GE-NE-B13-02010-33NP Repts & Revised Pages to Summary Rept Previously Submitted,Encl ML20209G9121999-07-0909 July 1999 Informs That Ja Hutton Has Been Appointed Director,Licensing for PECO Nuclear,Effective 990715.Previous Correspondence Addressed to Gd Edwards Should Now Be Sent to Ja Hutton ML20209C9041999-07-0808 July 1999 Forwards Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 & Revised Monthly Repts for May 1999 ML20210B4441999-07-0808 July 1999 Forwards Preliminary NRC Form 398 & NRC Form 396 for Reactor Operator for License Candidate LB Mchugh.Candidate Failed Category B Portion of Operating Exam Given at LGS During Week of 990315.Tentative re-exam Has Been Scheduled 990812 05000353/LER-1999-003, Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure1999-07-0707 July 1999 Forwards LER 99-003-00,re Bypass of RW Cleanup Leak Detection Sys Isolation Function on Three Separate Occasions.Bypass of Safety Function Was Caused by Inadequate Review & Approval of Change to Procedure ML20209D8821999-07-0707 July 1999 Submits Estimate of Number of Licensing Actions Expected to Be Submitted in Years 2000 & 2001,as Requested by Administrative Ltr 99-02.Renewal Applications for PBAPS, Units 2 & 3,will Be Submitted in Second Half of 2001 ML20209D2671999-07-0202 July 1999 Responds to NRC 990322 & 0420 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 05000352/LER-1999-004, Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys1999-07-0101 July 1999 Forwards LER 99-004-00,re Inoperability of Automatic Depressurization Sys Portion of Eccs.Condition Resulted from Incomplete Impact Review of Isolating Portion of ADS Nitrogen Backup Supply on Operability of ECCS Sys ML20209B7001999-06-30030 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20212J5401999-06-28028 June 1999 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs. Bulletin Closed for Unit 2 by NRC ML20207H8271999-06-24024 June 1999 Informs NRC That Util Has Completed Core Shroud Insps for LGS Unit 2.Proprietary Rept GE-NE-B13-02010-33P & non-proprietary Rev 0 to 1H61R,encl.Proprietary Rept Withheld,Per 10CFR2.790(a)(4) ML20196G7041999-06-24024 June 1999 Forwards Insp Repts 50-352/99-03 & 50-353/99-03 on 990413- 0524.No Violations Noted.Nrc Concluded That Licensee Staff Continued to Operate Both Units Safely ML20196A5641999-06-15015 June 1999 Provides Info Re Util Use of Four Previously Irradiated LGS, Unit 1,GE11 Assemblies in Unit 2 Cycle 6.Encl 990518 GE Ltr Provides Objective of Lead Use Assemblies Program & Outlines Kinds of Measurements That Will Be Made on Assemblies ML20195J6831999-06-11011 June 1999 Provides Proprietary Objectives for Lgs,Units 1 & 2,1999 Emergency Preparedness Exercise Scheduled to Be Conducted on 990914.Licensee Identifies Which Individuals Should Receive Copies of Info.Proprietary Info Withheld 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062G4531990-11-20020 November 1990 Forwards SE Supporting Util Actions to Address Indication in Reactor Vessel Recirculation Riser nozzle-to-safe End Weld ML20062G4021990-11-19019 November 1990 Forwards Safety Insp Repts 50-352/90-21 & 50-353/90-20 on 900827-31.No Violations Noted ML20062F1771990-11-13013 November 1990 Confirms Dates of 901126-30 for NRC Equipment Qualification Insp of Facility ML20058F1981990-11-0505 November 1990 Advises That 901002 Response to Generic Ltr (GL) 90-03, Relaxation of Staff Position in GL 83-28,Item 2.2 Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable ML20058E6121990-10-29029 October 1990 Forwards Radiological Safety Insp Repts 50-352/90-24 & 50-353/90-23 on 901001-05.No Violations Noted ML20058D2371990-10-26026 October 1990 Informs of Impending fitness-for-duty Program Insp & Requests 10CFR26.20 Required Policies & Procedures ML20058C1331990-10-23023 October 1990 Advises That Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wk of 910121 & Requalification Program Evaluation Scheduled for Wks of 910114 & 21.Ref Matl Listed on Encl Should Be Provided by 901029 ML20058A6241990-10-18018 October 1990 Forwards Insp Repts 50-352/90-22 &50-353/90-21 on 900912-19. No Violations Noted ML20062B7891990-10-12012 October 1990 Forwards Safety Insp Repts 50-352/90-20 & 50-353/90-19 on 900813-0916.No Violations Noted ML20059N5841990-10-0303 October 1990 Informs That Issuance of Senior Reactor Operator Licenses, for Fuel Handling Only,For More than One Facility Conditionally Acceptable IR 05000352/19900801990-09-28028 September 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/90-80 & 50-353/90-80.Requests Status of Planned Revs to Procedures & Expected Completion Dates in 910130 Response ML20059F6561990-08-29029 August 1990 Forwards Notice of Withdrawal of 900516 Application for Amend to License NPF-39,revising Tech Specs to Allow one- Time Extension of Visual Insp Period for Three Small Inaccessible Snubbers in Drywell ML20058N0531990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Licensees Establishment of Engineering Managers Forum ML20058M5981990-08-0303 August 1990 Forwards Safety Insp Repts 50-352/90-17 & 50-353/90-16 on 900522-0701 & Notice of Violation.Inspectors Continued to Note Problems W/Procedure Compliance & in Technical Adequacy & Implementation of Procedures ML20058M3311990-08-0303 August 1990 Forwards Radiological Safety Insp Repts 50-352/90-19 & 50-353/90-18 on 900709-13.No Violations Noted.Weakness Observed in Maint of Station Health Physics Procedures ML20055E8641990-07-10010 July 1990 Comments on Util 891228 Response to Generic Ltr (GL) 89-10, Safety-Related Motor-Operated Valve (MOV) Testing & Surveillance. Requests Proposed Schedule for Completion of GL Program Along W/Justification for Alternative Schedule ML20055F5591990-07-0303 July 1990 Forwards Safety Insp Repts 50-352/90-80 & 50-353/90-80 on 900521-25.Plant Transient Response Implementing Plan (Trip) Technically Acceptable.Unresolved Items Noted.Impact of Insp Findings on Peach Bottom Trip Procedures Should Be Reviewed ML20059M8671990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20058K1961990-05-31031 May 1990 Forwards Results & Conclusions of Regulatory Effectiveness Review on 900507-11.Encl Withheld (Ref 10CFR73.21) ML20055C3091990-02-14014 February 1990 Forwards Safety Insp Repts 50-352/90-03 & 50-353/90-03 on 900116-19.No Violations Noted ML20248E7421989-09-27027 September 1989 Forwards Exam Repts 50-352/89-13OL & 50-353/89-22OL Administered on 890612-16 & 19.NRC Concerned About Effectiveness of Util Candidate Screening & Evaluation Process That Permitted Marginal Individual for NRC Exam ML20248G6601989-09-27027 September 1989 Forwards Operational Readiness Insp Rept 50-353/89-81 on 890730-0804 & Notice of Violation ML20248E5181989-09-22022 September 1989 Forwards Safety Insp Repts 50-352/89-15 & 50-353/89-24 on 890626-0730.No Violations Noted.Repts Delineate NRC Concerns Identified During mid-cycle SALP Review & Licensee self-assessment of Conduct of Operations ML20248G9611989-09-21021 September 1989 Forwards Amend 7 to Indemnity Agreement B-101,reflecting Increase in Primary Layer of Liability Insurance.Amends Conform to Changes Made to Price-Anderson Act Enacted on 880820 NUREG-1376, Forwards Tech Specs,NUREG-1376 & Sser 9 Re Application for OL for Facility.W/O Encls1989-09-11011 September 1989 Forwards Tech Specs,NUREG-1376 & Sser 9 Re Application for OL for Facility.W/O Encls ML20247N2331989-09-0808 September 1989 Forwards Insp Repts 50-352/89-17 & 50-353/89-25 on 890724-27.No Violations Noted.Corrective Actions Re Failure of Operators to Properly Classify Events Effective ML20247E7991989-09-0606 September 1989 Forwards Safety Insp Rept 50-352/89-16 on 890807-11.No Violations Noted ML20246D5641989-08-23023 August 1989 Forwards Corrective Action Insp Rept 50-353/89-201 During Wk of 890424 Re Independent Design Assessment.Assessment Provided Needed Addl Assurance That Plant Design Met Licensing Commitments ML20246N4111989-08-15015 August 1989 Forwards FEMA Rept on 890614 Plant Remedial Exercise.Rept Indicates That Deficiency Identified in Lower Pottsgrove Township During 880405 full-participation Exercise.Offsite Preparedness Adequate ML20245K0161989-08-11011 August 1989 Advises That 890403 Response to Generic Ltr 83-28,Item 2.1 Parts 1 & 2 Acceptable ML20245G1511989-08-10010 August 1989 Discusses Emergency Preparedness Insp Repts 50-352/89-11 & 50-353/89-17 on 890522-26 & 0607 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of 75,000 ML20245H7151989-08-0909 August 1989 Discusses Insp Rept 50-352/89-14 on 890629 & Forwards Notice of Violation.Insp Reviewed Circumstances Involving Transport of Contaminated Waste from Unit to Quadrex Recycle Ctr in Oak Ridge,Tn on 890620 ML20245J8171989-08-0909 August 1989 Advises That Listed Schedule Should Be Used for All Emergency Exercises,Including Submittal & Review of Objectives & Scenario Packages Prior to Exercise ML20245G6721989-08-0808 August 1989 Forwards Environ Assessment & Finding of No Significant Impact Re Request for Exemption from 10CFR50.44(c)(3)(i) to Extend Permitted Time of Operation W/Noninerted Containment Until Completion of 100 H Warranty Run ML20248C3571989-07-31031 July 1989 Forwards Request for Addl Info Re Consideration of Severe Accident Mitigation Design Alternatives.Response Requested within 30 Days of Ltr Receipt ML20248D8901989-07-28028 July 1989 Forwards Safety Insp Repts 50-352/89-12 & 50-353/89-19 on 890529-0625 & Notice of Violation.Fire Protection Issues, Discussed in Section 3.1,may Represent Potential Enforcement Issues NUREG-1371, Forwards Tech Specs,NUREG-1371,issued by NRR Re Application for Ol.W/O Stated Encl1989-07-25025 July 1989 Forwards Tech Specs,NUREG-1371,issued by NRR Re Application for Ol.W/O Stated Encl ML20247N4761989-07-25025 July 1989 Forwards Enforcement Conference Rept 50-352/89-14 on 890717. Apparent Violation Noted in Insp Rept 50-352/89-14 Re Area of Transportation of Radioactive Matl Discussed ML20246N1801989-07-13013 July 1989 Forwards Preoperational Insp Rept 50-353/89-20 on 890530- 0621.Programs Adequate to Support Testing & Startup ML20246N4171989-07-12012 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/89-80 & 50-353/89-80 ML20246K5461989-07-11011 July 1989 Forwards Reactive Safety Insp Rept 50-352/89-14 on 890629. Violations Noted.Concern Expressed Re Lack of Control in Area of Properly Packaging Matl to Ensure External Radiation Levels Mantained.Enforcement Conference Scheduled ML20246G2921989-07-0707 July 1989 Forwards Safety Insp Rept 50-353/89-21 on 890530-0602.No Violations Noted ML20246F5911989-07-0606 July 1989 Forwards to Ecology Ctr of Southern California Re Petition to Fix or Close All Nuclear Power Reactors Designed by Ge.Ltr Ack Receipt of Petition Filed by Ecology Ctr & States Petition Filed Under 10CFR2.206 NUREG-1360, Forwards Tech Specs,NUREG-1360 & Sser 8 Re Application for OL for Unit 2.W/o Encl1989-07-0303 July 1989 Forwards Tech Specs,NUREG-1360 & Sser 8 Re Application for OL for Unit 2.W/o Encl ML20246B6061989-06-27027 June 1989 Ack Receipt of Re Alleged Discrimination Against Employee for Engaging in Protected Activities.Nrc Considers Matter Closed by Review of Info ML20245F0401989-06-22022 June 1989 Forwards License NPF-83 Authorizing Fuel Loading & Precriticality Testing of Util & Fr Notice.Amend 4 to Indemnity Agreement B-101 Also Encl ML20245H6901989-06-21021 June 1989 Forwards Safety Insp Repts 50-352/89-11 & 50-353/89-17 on 890522-26 & 0607.Violations Noted.Enforcement Conference Will Be Held on 890705 to Discuss Operators Inability to Properly Classify Certain Events During walk-through Exams ML20245E6141989-06-20020 June 1989 Forwards SER Accepting Util 890331 & 0602 Responses to NRC Bulletin 88-005, Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co at Williamstown,Nj ML20245F2941989-06-20020 June 1989 Approves Util 880621 Power Ascension Test Program for Facility,Per Reg Guide 1.68,for Execution ML20245F2991989-06-16016 June 1989 Forwards Safety Insp Rept 50-353/89-23 on 890605-07.No Violations or Deviations Noted 1990-09-28
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20212J6561999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Limerick Generating Station on 990913.Identified No Areas in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216F7821999-09-16016 September 1999 Forwards Insp Repts 50-352/99-05 & 50-353/99-05 on 990713-0816.One Violation Noted & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Inoperability of Automatic Depression Sys During Maint ML20212A8751999-09-13013 September 1999 Forwards Safety Evaluation of First & Second 10-year Interval Inservice Insp Plan Request for Relief ML20211N5061999-09-0909 September 1999 Forwards TSs Bases Pages B 3/4 10-2 & B 3/4 2-4 for LGS, Units 1 & 2,being Issued to Assure Distribution of Revised Bases Pages to All Holders of TSs ML20211P8571999-09-0808 September 1999 Forwards Reactor Operator Retake Exams 50-352/99-303OL & 50-353/99-303OL Conducted on 990812 ML20211P3891999-09-0303 September 1999 Informs That During 990902 Telcon Between J Williams & B Tracy,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wk of 991018 ML20211H2571999-08-26026 August 1999 Informs of Individual Exam Result on Initial Retake Exam on 990812.One Individual Was Administered Exam & Passed ML20210T4271999-08-13013 August 1999 Informs That NRC Revised Info in Rvid & Releasing Rvid Version 2 as Result of Review of 980830 Responses to GL 92-01 Rev 1,GL 92-01 Rev 1 Suppl 1 & Suppl Rai.Tacs MA1197 & MA1198 Closed ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210U2211999-08-10010 August 1999 Forwards Insp Repts 50-352/99-04 & 50-353/99-04 on 990525-0712.One Violation Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy.Violation Re Late Performance of off-gas Grab Sample Surveillance ML20210P4191999-08-0404 August 1999 Forwards Initial Exam Repts 50-352/99-302 & 50-353/99-302 on 990702-04 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam NUREG-1092, Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls1999-08-0303 August 1999 Informs J Armstrong of Individual Exam Results for Applicants on Initial Exam Conducted on 990702 & 990712-14 at Facility.All Six Individuals Who Were Administered Exam, Passed Exam.Without Encls ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 ML20212J5401999-06-28028 June 1999 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs. Bulletin Closed for Unit 2 by NRC ML20196G7041999-06-24024 June 1999 Forwards Insp Repts 50-352/99-03 & 50-353/99-03 on 990413- 0524.No Violations Noted.Nrc Concluded That Licensee Staff Continued to Operate Both Units Safely ML20206Q5871999-05-14014 May 1999 Advises That Info Contained in ,Which Submitted Revised Procedures for Plant EP Response Procedures Will Be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R3031999-05-11011 May 1999 Informs That on 990407,NRC Administered GFE Section of Written Operator Licensing Exam to Employees of Facility. Forwards Copies of Both Forms of Exam,Including Answer Keys & Grading Results of Facility ML20206N1111999-05-0707 May 1999 Forwards Insp Repts 50-352/99-02 & 50-353/99-02 on 990302-0412.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20206H2651999-05-0606 May 1999 Informs That on 990112 Licensee Submitted to NRC Core Shroud Insp Plan for Plant,Unit 2,in Response to GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors ML20206G5131999-05-0303 May 1999 Approves Change of Completion Date for Implementation of Thermo-Lag Fire Barrier Corrective Actions at Plant from End of April 1999 Limerick Unit 2 RFO to 990930 ML20206H8301999-04-30030 April 1999 Forwards Exam Repts 50-352/99-301 & 50-353/99-301 on 990312-19 (Administration) & 22-26 (Grading).Four of Five RO Applicants & Three of Four SRO Applicants Passed All Portions of Exams ML20206E6951999-04-30030 April 1999 Advises That Plant,Unit 2 Cycle 6 Safety Limit Mcpr, ,contained in PECO Energy Co 990311 Application & 990204 Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20206F4221999-04-27027 April 1999 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990312 & 990315-19 at Facility.Completed ES-501-2,power Plant Licensing Exam Results Summary & Summary of Overall Exam Results Encl.Without Encl ML20205N2291999-04-0909 April 1999 Discusses Limerick Generating Station Plant Performance Review Conducted for Period April 1998 Through 990115 & Informs of NRC Planned Insp Effort Resulting from Review. Historial Listing of Plant Issues,Encl IR 05000352/19980091999-03-30030 March 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/98-09 & 50-353/98-09 Issued on 990106.Actions Will Be Examined During Future Insp of Licensed Program ML20205C2711999-03-26026 March 1999 Forwards Insp Repts 50-352/99-01 & 50-353/99-01 on 990112-0301.One Violation Noted & Being Treated as Non-Cited Violation.Staff Conduct of Activities During Insp Generally Characterized by Safe & Conservative Decision Making ML20205G7651999-03-22022 March 1999 Forwards RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, for Plant, Units 1 & 2.Response Requested within 90 Days of Receipt of Ltr ML20204G9721999-03-11011 March 1999 Informs of Completion of Review of Changes Proposed by PECO Energy Co to Lgs,Units 1 & 2,EALs.Proposed EALs Incorporate Guidance in NUMARC/NESP-007,Rev 2.Forwards Safety Evaluation Supporting Proposed Changes ML20204H8171999-03-10010 March 1999 Discusses Request That NEDC-32645P, Limerick Generating Station,Units 1 & 2,SRV Setpoint Tolerance Relaxation Licensing Rept, Rev 2,dtd Dec 1998,be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20207J0611999-03-0808 March 1999 Provides Authorization to Administer Initial Written Exams to Listed Applicants on 990312.NRC Region I Operator Licensing Staff Will Administer Operating Tests on 990315-19 at Limerick Generating Station ML20203G6721999-02-17017 February 1999 Second Partial Response to FOIA Request for Documents. Records in App D Encl & Being Made Available in Pdr.App E Records Being Withheld in Part (Ref FOIA Exemption 5) & App F Records Completely Withheld (Ref FOIA Exemptions 6 & 7) ML20203B9001999-02-0808 February 1999 First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6) ML20202J0261999-02-0303 February 1999 Informs of Completion of Licensing Action for NRC Bulletin 96-03, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors ML20203A6111999-01-22022 January 1999 Confirms 990115 Conversation Between Mj Williams & P Orphanos Re Arrangements Made for Administration of Licensing Exam at Limerrick Generating Station & Peach Bottom Atomic Power Station During Week of 990705 ML20199F9251999-01-11011 January 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/98-05 & 50-353/98-05 ML20199C6501999-01-0606 January 1999 Forwards Insp Repts 50-352/98-09 & 50-353/98-09 on 981018- 1130 & Notice of Violation.Violation of Concern Because Technicians Exercised Poor Judgement & Deviated from Procedure in Attempt to Resolve Problem Without Mgt ML20198H4951998-12-18018 December 1998 Forwards Results of Audit of Licensee Year 2000 Program for Limerick Generating Station,Units 1 & 2 ML20198A3721998-12-10010 December 1998 Forwards Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20198B1751998-12-0808 December 1998 Advises of Planned Insp Effort Resulting from Limerick mid-year Insp Resource Planning Meeting Held on 981110. Historical Listing of Plant Issues & Details of Insp Plan for Next Six Months Encl IR 05000352/19980081998-11-23023 November 1998 Discusses licensee-identified Issue Involving Potential for Bypass of Suppression Pool as Documented in Insp Repts 50-352/98-08 & 50-353/98-08.NOV Will Not Be Issued & Civil Penalty Will Not Be Proposed ML20196C3311998-11-23023 November 1998 Forwards Insp Repts 50-352/98-08 & 50-353/98-08 on 980901-1017.No Violation Identified.Security Program Insp Identified That Security Program Effectively Protects Public Health & Safety ML20195D1491998-11-13013 November 1998 Forwards RAI Re on-going Review of IPEEE Submittal Dtd 951014.Understands That Licensee Will Inform NRC in Writing, by 981130,on How Question Re Effects of New Probable Max Precipitation at Plant,Units 2 & 3 Will Be Addressed IR 05000352/19980061998-10-15015 October 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/98-06 & 50-353/98-06 on 980826.Finds C/As for Violation Involving Failure to Select Performance Measures to Be Acceptable ML20154F8191998-10-0101 October 1998 Forwards Notice of Withdrawal of 960503 & Suppl Application for Amend to Fols.Amend Would Have Modified Facility TSs Pertaining to Rev to Frequency of Testing Stand Gas Treatment Sys & Reactor Encl Recirculation Sys ML20154A3461998-09-25025 September 1998 Forwards Insp Repts 50-352/98-07 & 50-353/98-07 on 980707-0831.No Violations Noted.Weaknesses Noted with Reactor Engineering Support to Rod Pattern Adjustment ML20153G4291998-09-24024 September 1998 Forwards Request for Addl Info Re Licensee Revised Emergency Action Level Guidelines for Limerick Generating Station, Units 1 & 2 & Peach Bottom Atomic Power Station,Units 2 & 3. Response Requested within 30 Days of Receipt of Ltr ML20153D0151998-09-21021 September 1998 Informs of Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, for Plant, Units 1 & 2 ML20151X2421998-09-11011 September 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-352/98-04 & 50-353/98-04 on 980805 ML20151W9601998-09-10010 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 Were Selected as SRAs for Region I ML20237D5421998-08-26026 August 1998 Ack Receipt of & Fee for $55,000 in Payment for Civil Penalty Proposed by NRC in .C/As Will Be Examined During Future Insps 1999-09-09
[Table view] |
Text
, .- , _ _ _ _
March'14, 1989' 1
Docket-Nos. 50-352/353 Philadelphia Electric Company ATTN: Mr. C.LA. McNeill Executive Vice President Nuclear Correspondence. Control Desk P. O. Box 7520 Philadelphia, PA 19101- .. l 1
.A Gentlemen: L i-
SUBJECT:
REACTOR OPERATOR AND SENIOR REACTOR OPERATOR LICENSING ,
'i EXAMINATIONS In a telephone conversation between Mr. E. Firth, Superintendent,. Training,.
l and Mr. T. Easlick, Examiner, arrangeraents were made for the ' administration of licensing examinations at the Limerick Generating Station.'
The written examinations are scheduled for the wee'k of June 12, 1989..The operating examinations are scheduled for June 13-16,~ 1989.-
4 r
To meet the above schedule, it will be necessary for you to furnish the.
reierence material listed in Enclosure 1, " Reference. Material Requirements
- for Reactor / Senior Reactor Operator Licensing Examinations," by April.10, l 1989. Any delay in receiving approved, properly bound andl indexed reference material, or the submittal of inadequate or incomplete reference material
~
may result in the examination being rescheduled. Mr. Firth has been advised of our reference material requirements, and the address where each set is be be mailed.
You are responsible for providing adequate space and accommodations for . ,
administration of the written examinations. Enclosure 2 " Requirements for Administration of Written Examination," describes our' requirements for I
conducting these examinations. I Enclosure 3 contains the Rules a~nd Guidelines that will be in effect during the administration of.the written examination. The facility management is j responsible for. ensuring that all applicants are aware of these rules.
The facility' staff review of the writtnn examination will be conducted in accordance with requirements specifiedLin Enclosure 4, " Requirements for Facility Review of Written Examinations,."
l To better document simulator examinations, the Chief Examiner will have the .
simulator operator record predetermined plant conditions (i.e., plant-pressure, temperature, etc), for each simulator scenario. The applicants will be responsible for providing this information, with any appeal of a simulator operating examination. Therefore, your training staff'should retain the original simulator examination scenario information until all' ~\ / 1 V
applicants who took the examinations have either passed the operating. ;
examination, accepted the denial of their license, o'r filed an appeal.
0FFICIAL RECORD COPY- ' \\
MbO 03'52 PDC LIW/) DAY.Dv6/ 'l V
< r e l Philadelphia Electric Company j All completed reactor operator and senior 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 candidates, process the medical certifications, and l prepare final examiner assignments after applicant eligibility has been i determined, if the applications are not received at.least 30 days before the examination dates, it is likely that a postponement will be necessary. I Mr. E. Firth has been informed of the above requirements. l This request is covered by Office of Management and Budget Clearance ,
Number 3150-0101 which expires May 31, 1989. The estimated average burden )
is 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per response, including gathering, xeroxing and mailing the i required material. Comments on the accuracy of this estimate and suggestions l to reduce the burden may be directed to the Office of Management and Budget, 1 l Paperwork Reduction Project 3150-0101, Room 3208, New Executive Office 1 Building, Washington D.C. 20503, and the U.S. Nuclear Regulatory Commission, ,
j Records and Reports Management Branch, Office of Information Resources l Management, Washington, D.C. 20555 ]
Thank you for your consideration in this matter. If you have any questions I regarding the examination procedures and requirements, please contact me at (215) 337-5124.
Sincerely, N girma Signed Ur (
l Richard J. Conte, Chief l
BWR Section Operations Branch ;
Division of Reactor Safety
Enclosures:
- 1. Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations
- 2. Require.nents for Administration of Written Examinations -
l 3. NRC Rules and Guidelines for Written Examinations
- 4. Requirements for Facility Review of Written Examinations l
l l
1
! 0FFICIAl. RECORD COPY l
L
v- -
- e Philadelphia Electric Company CC John S. Kemper, Sr., Senior Vice President - Nuclear E. C. Kistner, Chairman, Nuclear Review Board Graham M. Leitch, Vice President, Limerick Generating Station J. W. Gallagher, Vice President - Nuclear Troy B. Conner, Jr., Esquire Eugene J. Bradley, Esquire, Assistant General Counsel V, M. Alden, Director, Licensing Section S. Joseph Kowalski, Vice President, Nuclear Engineering W- T. Ullrich, Superinter. dent, Limerick 2 Project J. M. Corcoran, Quality Assurance Manager Dave Honan E. Firth, Superintendent, Training Public Document Room (PDR)
Local Public Document Room (LPDR) l Nuclear Safety Information Center (NSIC) l NRC Resident Inspector l
Commonwea?th of Pennsylvania l
l l
i l
l
.~
n -
1
.' s -
Philadelphia Electric Company 4 !
I bec w/ enclosures: .
T. Easlick ]
Chief, OLB,.NRR 1 OL Facility File !
Project Manager, NRR j RegionI'DocketRoom(withconcurrences)- {
Section Chief, DRP .t Robert J. Bores, DRSS l
.]
l j
l 1
?
)
i i
i 0FFICIAL RECORD COPY RI:DRS RI:DRS RI:DRS 1 Curigy Eas ck Cok 03/L3 /89 03//w/89 /
03/h/89 i
i i
l 1
UM 90DA Y.be6
ENCLOSURE 1 REFERENCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACIOR OPERATOR LICENSING EXAMINATIONS
- 1. Existing learning objectives, Job Performance Measures and lesson plans (including training manuals, plant oriatation manual, system descrip-tions, reactor theory, thermodynamics, etc.)
A copy of the facility Job and Task Analysis (JTA), specifying the knowledges and abilities required of an operator at the ' facility. .Each particular knowledge and/or ability will include an importance rating correlating it to ensuring the health and the safety of the public. If a JTA is not furnished, the Knowledges and Abilities Catalog for Nuclear Power Plant Operators, NUREG 1122 (1123) will be used to establish cortent validity for the examination.
l All Job Performance Measures (JPMs) used to acertain 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 material shall include learning objectives and the details presented during lectures, rather than outlines. Training materials shall be identified by plant and unit, bound, tabbed, and indexed. FAILURE TO PROVIDE. COMPLETE,. PROPERLY BOUND AND INDEXED PLANT REFERENCE MATERIAL MAY RESULT IN THE RETURN OF THE MATERIAL TO THE PERSON WHO IS THE HIGHES LEVEL 0F CORPORATE MANAGEMENT WHO IS RESPONSIBLE FOR PLANT OPERATI (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 WE CANCELLED OR POSTPONED. Training materials which include the following shall.be provided:
System descriptions including descriptions of all operationally relevant flow paths, components, controls and System training material should draw parallels instrumentation.
to the actual procedures 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, o
1 l
l
Jhv.
Comprehensive -theory material that includes ' fundamentals in the area-of theory of reactor .' operation , thermodynamics, heat transfer and
' compone'ts.
fluid flow, n
as well as. specific application to actual Lin plant 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 between the' fundamentals and the actual operating' limits followed in 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.) 1 '
- 3. i l
All Administrative Procedures (as applicable to reactor , operation or safety) l j 4. All integrated plant procedures .(normal or-general operating procedures) i
- 5. All emergency procedures '(emergency instruction $, abnormal procedures) or special i
- 6. !
Standing orders (important orders that are safety related and may super-sede_the regular procedures)
I 7. ' Surveillance procedures (procedures that are run frequently, i.e. Weekly or that can be run on the simulator)
- 8. Fuel-handling and core-loading procedure,whenappropriate)'
procedures, (initial core-loading
- 9. All annunciator / alarm procedures
- 10. Radiation protection manual (radiation control manual or procedures) '
- 11. Emergency plan implementing procedures 1
- 12. Technical Specifications interpretations, if available) for all unitsforwhichlicensesare(and sought.
l
- 13. System Operating Procedures l
- 14.
' Piping flow diagramsand Instrumentation diagrams, electrical single-line diagrams, or 15.
Technical Data Book, and/or Plant curve information as used by operators and facility j facility precautions, limitations, and set points (Pl.S) for the 1
l I
l ;
l 1
l
- 16. l Questions and answers specific to the facility training program which may j be used in the written or operatir.g examinations (voluntary by facility licensee)
- 17. 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.
Tne list shall include cause 'and effect information. Specifically, for each malfunction a concise description of the expected result, or !
rance of results, that will occur upon implementation shall be ;
provided. Additionally, an indication.of which annunciators are to be initially expected should be given.
q
- c. A description of simulator failure capabilities for valves, breakers, indicators and alarms.
i ;
l d. Where the capability exists, an explanation of the ability to vary
! j the severity of a particular malfunct' ion shall be provided, i.e., j i
ability to vary the size of a given LOCA orateam leak, or the abil- ~ j ity to cause a slow failure of a component such as a feed pump, tur-b1ne generator or major valve. (e.g., drif ting shut of a main j feedwater control valve) , i
- e. i An identification of modeling conditions / problems that may impact the examination.
f.
Identification of any known performance test discrepancies not yet corrected.
g.
Identification plant's controlofroomdifferences between the simulator and the reference 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) may be provided (voluntary by lice.nsee) 1.
Simulator instructors manual (veluntary by licensee).
J. Description by licensee). of the scenarios used for the training class (voluntary 18.
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 l marked.
If a plant has not finalized some of t!e material, the Chief Examiner shall verify with the facility that the most complete, up-to-date material is available and that changes before the agreement administration has been reached with the licensee for limiting 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 Di ant reference material could result in cancellation or rescheduling.of the examinations l
i i
.s .
f t
4, ENCLOSURE 2
. REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS :
- 1. A' single room shall be .provided. for administration .of the' written
~
examination. 'The 1ocation of'this roo_m and supporting restroom facilities.
i
' shall be such / as ? to preventL contact L with Ja11' other facility and/ori contractor personnel .during the written examination. .If necessary, the facility should make arrangements' for. the use 'of a suitable - room. at. a .
4, local school, motel, or other ' building. - Obtaining this . roorr 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- 5 to have lunch, coffee, or other. refreshments. 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 compl eting ; . the examination. 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 fort writing answers to questions. . '
i
- 6. !
The licensee. shall provide one set of st'eam 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.
l J
1 L
L
ENCLOSURE 3 PROCEDURES FOR THE ADMINISTRATION OF WRITTEN EXAMINATIONS
- 1. Check identification badges.
- 2. Pass out examinations and all handouts. Remind applicants not to review examination until instructed to do so.
READ THE FOLLOWING INSTRUCTIONS VERBATIM:
During the administration of this examination the following rules apoly:
- 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
~
dune after you complete the examination. -
READ THE FOLLOWING INSTRUCTIONS
- 1. Restroom trips are to be limited and only one applicant at a time may <
leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 2. Use black ink or dark pencil only to facilitate legible reproductions. ;
- 3. Print your name in the blank provided in the upper right-hand corner of l
the examination cover sheet.
4.
Fill in the date on the cover sheet of the examination (if necessary).
5.
You may write your answers on the examination question page or on a separate sheet of paper. USE ONLY THE PAPER PROVIDED AND 00 NOT WRITE ON THE BACK SIDE OF THE PAGE.
- 6. If you write your answers on the examination question page. and you need more space to answer a specific question, use a separate sheet of the paper provided and insert it directly after the specific question. 00 NOT WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
- 7. Print your name in the upper right hand corner of the first page of each section of your answer sheets whether you use the examination question pages or separate sheets of paper. Initial each page.
- 8. 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. .
~
- 9. If you are using separate sheets, number each answer as to category and number (i.e. 1.04, 6.10) and skip at least 3 lines between answers to allow space for gracing.
i
- 10. Write "End of Category " at the end of your answers to a category.
- 11. Start each category on a new page.
- 12. Write "Last Page" on the last answer sheet
- 13. Use abbreviations only if they are commonly used in facility literature.
Avoid using symbols such as < or > signs to avoid a simple transposition error resulting in an incorrect answer. Write it out.
- 14. The point value for each question is indicated in parentheses after the question. The amount of blank space on an examination question page is l
NOT an indication of the depth of answer required.
- 15. Show all calculations, methods, or assumptions used to obtain an answer. i
- 16. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK.
1 -
- 17. Proportional grading will be applied. Any additional wrong information that is provided may count against you. For example, if a question is worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth 0.20 points. If one of your five rnponses 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, y.
18.
1 If the intent of a question is unclear, ask questiors of the examiner only.
19.
When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition, turn in,all scrap paper.
- 20. To pass the examination, you must achieve an overall grade of 80% or greater and at least 70% in each category.
- 21. There is a time limit of (6) hours for completion of the examination.
(or some ~other time if less than the full examination is taken.)
1
- 22. When you are done and have turned in your examination, leave the examination area (DEFINE THE AREA). If you are found in this area while the examination i s still in progress, your license may be denied or revoked.
9
m I
1
'1 Enclosure 4- '
A REQUIREMENTS FOR FACILITY REVIEW OF WRITTEN EXAMINATIONS
- 1. At the. option of the > Chief. Examiner, the facility may. review the written examination up to two weeks prior to its administration. This review'may take place at the facility or in the Regional office. The aChief Examiner vill coordinate the details of ' the review with the . facility. .An NRC axaminer will always be present during the review.
When this option of -examination - review is utilized, the facility. !
reviewers will sigt. 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 information concerning the replacement (or initial) examination 4 scheduled for -
to any unauthorized persons. .I understand that I am not to participate in any instruction involving those reactor operator or senior reactor operator applicants scheduled to be administered the above replacement (or initial) examination from now until after the examination has been administered. I understand that violation of this security agreement could result in the examination being voided. 1-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 operator and senior reactor operator applicants who were administered the examination from the time that I was allowed access to the examination.
l Signature /Date 1
i
..E..
. .- +
)
- 2. Regardless of whether the ' above examination review option is exercised, .
immediately. following' the: administration .of thef written ' examination, the 7 facility staff shall be.provided a marked.up copy of .the examination and; I i the answer key. The copy of the' written ; examination shall include pen
.1 and ink changes made to questions during the: examination Administration'. {
If the facility did not review the examination' prior to :its
. adiim n strati on, t hey' wil l have five (5) working ' days from the ' day.of ' the
~
L I- written. examination' to submit formal comments. If the . facility reviewed the examination prior to its administration, -any additional . comments must 3 be given to an examiner prior to his/her leaving the site' at the end of ,
- the week of the written examination: administration. InJeither case, the.
comments ' will . be ' addressed , to the responsible Regional. Office by' .the-
- highest on site level of ccrporate management = for' plantioperations, e.g. , -
Vice President for Nuclear Operations. A. copy of the: submittal will be i forwarded to the Chief Examiner, .as: appropriate. Comments - not submitted !
within the required time frame _ will _' be . considered Lfor inclusion in :the j grading process on a- case-by-case . basis by the Regional Office ~ Section Chief. Should the comment submittal ' deadl-ine not be' met, a -long delay. l in grading the examination may occur. - -
I 1
- 3. The follbwing format should- be adhered ' to for ~submittal
- a. Listing of NRC Question, answer and reference !
Y
- b. Facility comment / recommendation-s
- c. Reference (to support facility comment)' l i
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 Exarniner.. 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.
k.
- _ _ _ _ _ _ . _ _ . _ _ . . _ _ _ . -