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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M6631999-10-19019 October 1999 Forwards Insp Rept 50-277/99-07 & 50-278/99-07 on 990920.No Violations Noted ML20217K9241999-10-14014 October 1999 Forwards Amend 234 to License DPR-56 & Se.Amend Consists of Changes to TS in Response to Application & Suppls ,1001 & 06,which Will Support PBAPS Mod P00507,which Will Install Digital Pr Neutron Mining Sys ML20217F7391999-10-14014 October 1999 Requests Addl Info Re Peach Bottom Atomic Power Station Units 2 & 3 Appendix R Exemption Requests ML20217F6841999-10-13013 October 1999 Forwards Senior Reactor Operator Initial Exam Repts 50-277/99-302(OL) & 50-278/99-302(OL) Conducted on 990913- 16.All Applicants Passed All Portions of Exam ML20217F3021999-10-12012 October 1999 Provides Written Confirmation That Thermo-Lag 330-1 Fire Barrier Corrective Actions at PBAPS Have Been Completed.Ltr Also Confirms Completion of Actions Required by Confirmatory Order Modifying Licenses, ML20217E7451999-10-0808 October 1999 Forwards Response to NRC 990820 RAI Concerning Proposed Alternatives Associated with Third ten-yr Interval ISI Program for Pbaps,Units 2 & 3 ML20217B7701999-10-0606 October 1999 Submits Corrected Info to NRC 980528 RAI Re Util Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20217B9151999-10-0606 October 1999 Provides Clarifying Info to Enable NRC to Complete Review of License Change Request ECR 98-01802,re Changes Necessary to Support Installation of Digital Pr Neutron Monitoring & Incorporate long-term T/H Stability Solution Hardware ML20217C4141999-10-0606 October 1999 Forwards Response to NRC 981109 RAI Re Resolution of USI A-46 for Pbaps.Proprietary Excerpts from GIP-2,Ref 25 Results of BWR Trial Plant Review Section 8 Also Encl. Proprietary Excerpts Withheld ML20217B3181999-10-0505 October 1999 Advises That Info Submitted in 990712 Application,Which Contained Attachment Entitled, Addl Info Re Cycle Spec SLMCPR for Peach Bottom 3 Cycle 13,dtd 990609, with Affidavit,Will Be Withheld from Public Disclosure ML20217B4051999-10-0505 October 1999 Forwards Amend 233 to License DPR-56 & Safety Evaluation. Amend Changes Minimum Critical Power Ratio Safety Limit & Approved Methodologies Referenced in Core Operating Limits Report 05000278/LER-1999-004, Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv)1999-10-0101 October 1999 Forwards LER 99-004-00 Re Multiple Unplanned ESF Actuations During Planned Mod Activities in Main Cr,Per Requirements 10CFR50.73(a)(2)(iv) ML20217B8891999-10-0101 October 1999 Forwards Response to RAI Re Request to Install Digital Power Range Neutron Monitoring Sys & Incorporate long-term,thermal-hydraulic Stability Solution Hardware. Revised TS Table 3.3.2.1-1 Encl ML20217D5211999-09-30030 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 ML20212J6851999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Peach Bottom Atomic Power Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl New Insps Beyond Core Insp Program.Historical Listing of Plant Issues Encl 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 ML20212J5751999-09-28028 September 1999 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990913-16 at Licensee Facility.Without Encls ML20216J0191999-09-27027 September 1999 Forwards Request for Addl Info Re Util 990301 Request to Support Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware,For Plant ML20212H6171999-09-24024 September 1999 Forwards Rev 2 to COLR for Pbaps,Unit 2,Reload 12,Cycle 13, IAW TS Section 5.6.5.d.Rept Incorporates Revised Single Loop Operation MAPLHGR Flow Multiplier ML20216H6451999-09-24024 September 1999 Forwards Notice of Withdrawal of Util 990806 Application for Amends to Fols DPR-44 & DPR-56.Proposed Change Would Have Involved Temporary Change to Increase Limit for Average Water Temp of Normal Heat Sink ML20212H5431999-09-24024 September 1999 Informs of Decision to Inspect H-3 & H-4 Shroud Welds During Upcoming 3R12 Outage Scheduled to Begin Late Sept 1999 ML20216H6751999-09-24024 September 1999 Forwards Amends 229 & 232 to Licenses DPR-44 & DPR-56, Respectively & Ser.Amends Will Delete SR Associated Only with Refueling Platform Fuel Grapple Fully Retracted Position Interlock Input,Currently Required by SR 3.9.1.1 ML20216F8811999-09-23023 September 1999 Withdraws 990806 Exigent License Change Application.Tech Spec Change to Allow Continued Power Operation with Elevated Cooling Water Temps During Potentially Extreme Weather Conditions No Longer Needed Due to Favorable Weather ML20212E8661999-09-22022 September 1999 Discusses GL 98-01 Y2K Readiness of Computer Sys at NPPs & Supplement 1 & PECO Response for PBAPS Dtd 990630. Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient During Y2K Transition 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 ML20212D1191999-09-17017 September 1999 Forwards SE Re Proposed Alternatives to ASME Section XI Requirements for Containment Inservice Insp Program at Plant,Units 2 & 3 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 ML20211P2961999-09-0707 September 1999 Provides Authorization to Administer NRC Approved Initial Written Exams to Listed Applicants on 990913 at Peach Bottom Npp,Delta,Pennsylvania ML20211K7031999-08-30030 August 1999 Forwards Response to NRC 990826 RAI Re License Change Application ECR 99-01255,revising TSs 2.1.1.2 & 5.6.5 ML20211E6941999-08-26026 August 1999 Forwards Request for Addl Info Re Min Critical Power Ratio. Response Should Be Submitted within 30 Days of Ltr Receipt ML20211Q4491999-08-25025 August 1999 Responds to Re Changes to PBAPS Physical Security Plan,Safeguards Contingency Plan & Guard Training & Qualification Plan Identified as Revs 13,11 & 9, Respectively.No NRC Approval Is Required,Per 10CFR50.54(p) 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 ML20211D5421999-08-23023 August 1999 Forwards Amends 228 & 231 to Licenses DPR-44 & DPR-56, Respectively & Se.Amends Revise TSs to Correct Typographical & Editorial Errors Introduced in TSs by Previous Amends ML20211A9721999-08-20020 August 1999 Forwards Request for Addl Info Re Third 10-year Interval Inservice (ISI) Insp Program Plan for Plant,Units 2 & 3 ML20210T5451999-08-12012 August 1999 Forwards Copy of Environ Assessment & Findings of No Significant Impact Re Licensee Request for Amends to Plant. Amends Consist of Changes to TS to Correct Typos & Editorial Errors Introduced in TS by Previous Amends ML20210P8321999-08-11011 August 1999 Responds to NRC 990715 Telcon Re Util 990217 Submittal of Proposed Alternatives to Requirements of 10CFR50.55a(g)(6)(ii)(B)(1) Re Containment Inservice Insp Program ML20210P8151999-08-11011 August 1999 Forwards Final Pages for Pbaps,Unit 2 & 3 OLs Re License Change Application ECR 99-01497,which Reflects Change in Corporate Structure at Pse&G ML20211B6521999-08-10010 August 1999 Informs That Dp Lewis,License SOP-11247,has Been Permanently Reassigned & No Longer Requires License,Per 10CFR50.74.Util Requests That Subject Individual Be Removed from List of License Holders ML20210P1561999-08-10010 August 1999 Submits Response to Requests for Addl Info Re GL 92-01,rev 1,Suppl 1, Rv Structural Integrity, for Pbap,Units 1 & 2. NRC Will Assume That Data Entered Into Rvid Are Acceptable for Plants,If Staff Does Not Receive Comments by 990901 ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210N7831999-08-0909 August 1999 Forwards Copy of Notice of Consideration of Issuance of Amends to Fols,Proposed NSHC Determination & Opportunity for Hearing, Re 990806 Request for License Amends.Amends Incorporate Note Into PBAPS TS to Permit One Time Exemption ML20210P0801999-08-0404 August 1999 Forwards Initial Exam Repts 50-277/99-301 & 50-278/99-301 on 990702-14 (Administration) & 990715-22 (Grading).Six of Limited SRO Applicants Passed All Portion of Exam 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 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 ML20210J0161999-07-30030 July 1999 Forwards Copy of Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amends Re 990723 Application ML20210H5341999-07-27027 July 1999 Forwards Insp Repts 50-277/99-05 & 50-278/99-05 on 990518- 0628.NRC Determined That Two Severity Level IV Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20210F3731999-07-23023 July 1999 Submits Confirmation That,Iaw 10CFR50.80,PSE&G Is Requesting NRC Approval of Transfer of Ownership Interests in PBAPS, Units to New Affiliated Nuclear Generating Company,Pseg Nuclear LLC 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 ML20210E5811999-07-21021 July 1999 Forwards Final Tech Specs Pages for License Change Application.Proposed Change Will Revise Tech Specs to Delete Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS 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 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062F2241990-11-0909 November 1990 Forwards SSFI Repts 50-277/90-80 & 50-278/90-80 on 900917- 1003 Conducted by Corrective Action Review Team.Corrective Actions Generally Acceptable W/Some Weaknesses Noted IR 05000277/19900191990-11-0707 November 1990 Forwards Exam Repts 50-277/90-19OL & 50-278/90-19OL Administered During Wk of 900924 ML20062D5381990-11-0606 November 1990 Forwards List of Unimplemented Generic Safety Issues at Facilities,Per Generic Ltr 90-04 ML20058G1541990-10-31031 October 1990 Requests That Util Furnish Ref Matl Listed in Encl 1, Ref Matl Requirements, for Administration of Licensing Exams & Evaluation of Requalification Program Scheduled for Wk of 910304 ML20062C7451990-10-26026 October 1990 Forwards Safety Evaluation Accepting Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow ML20058D2371990-10-26026 October 1990 Informs of Impending fitness-for-duty Program Insp & Requests 10CFR26.20 Required Policies & Procedures ML20062B8211990-10-11011 October 1990 Forwards Final SALP Repts 50-277/89-99 & 50-278/89-99 for Jul 1989 to May 1990.Improvements Noted ML20062A0651990-10-0505 October 1990 Forwards Safety Insp Repts 50-277/90-17 & 50-278/90-17 on 900814-0924.One Violation 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 ML20059M6561990-09-22022 September 1990 Ack Receipt of Util Re Corrective Actions Taken in Response to Insp Repts 50-277/90-13 & 50-278/90-13 ML20059J1971990-09-13013 September 1990 Ack Receipt of & Payment for Civil Penalty Proposed by NRC in in Amount of $75,000 ML20059H0701990-09-11011 September 1990 Requests Addl Info Re Audit Rept Distribution,Per 890711 & 900420 Application Request for Removal of Organization Charts from Tech Spec Per Guidance Provided in Generic Ltr 88-06 & Miscellaneous Administrative Changes ML20059K7211990-09-0606 September 1990 Forwards Safety Insp Repts 50-277/90-15 & 50-278/90-15 on 900723-27 & Notice of Violation ML20056B2691990-08-23023 August 1990 Forwards Request for Addl Info Re 880126 Application for Amends to Licenses,Revising Tech Specs to Provide More Restrictive Limits on Emergency Svc Water Sys.Response Should Be Provided within 60 Days of Ltr Receipt ML20059A6581990-08-16016 August 1990 Requests Discussion of Measures Considered &/Or Taken to Reduce Amount of Time Needed to Obtain Effluent Sample Analyses Results,Per 870121 Application for License Amends to Licenses DPR-44 & DPR-56 ML20058N0531990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Licensees Establishment of Engineering Managers Forum ML20056A5011990-07-30030 July 1990 Forwards Safety Insp Repts 50-277/90-13 & 50-278/90-13 on 900516-0702 & Notice of Violation ML20055E1711990-07-0606 July 1990 Requests That Licensee Provide Data on Channel Box Bow Vs Exposure Associated W/Methods Used to Account for Effects of Channel Box Bow During Second Bundle Lifetime Channel Boxes, Per 900425 Response to Bulletin 90-002,within 30 Days ML20055E9611990-07-0505 July 1990 Requests Addl Info Re Util 891228 Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance ML20055D0721990-06-27027 June 1990 Advises That Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wks of 900924 & 1001.Ref Matls,Listed on Encl,Should Be Provided by 900724 ML20055C8761990-06-15015 June 1990 Forwards Safety Insp Repts 50-277/90-10 & 50-278/90-10 on 900403-0515.No Violations Noted.Increased Mgt Attention Warranted to Ensure That Instances of Failure to Complete Surveillance Testing Identified & Corrected ML20059M8671990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248H8041989-10-0505 October 1989 Grants Termination of Requirements Set Forth in Section VA of Order to Permit Operation of Both Units at Full Power ML20248H1361989-10-0303 October 1989 Forwards Unexecuted Amend 22 to Indemnity Agreement B-28, Reflecting Changes to 10CFR140 Re Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20248G2291989-09-29029 September 1989 Forwards Safety Insp Repts 50-277/89-21 & 50-278/89-21 on 890901.No Violations Noted.Insp Concluded That Improvements in Radiological Controls Program Have Been Slow.Addl Mgt Attention to Program Warranted ML20248E2351989-09-27027 September 1989 Forwards Summary of Issues Re Verification of Quality of Certain Types of Activities Performed for Mods at Facility. Mods Cover Automatic Depressurization Sys/Msiv Instrument Nitrogen Accumulator & Svc Water Pipe Replacement ML20248A4111989-09-25025 September 1989 Forwards Restart Team Safety Insp Repts 50-277/89-20 & 50-278/89-20 on 890730-0902.No Violations Noted ML20248E5581989-09-21021 September 1989 Forwards SER Supporting Use of Frosstey Fuel Performance Code Described in Topical Rept PECo-FMS-003, Steady-State Fuel Performance Methods Rept. Addl Applications of Subj Code Require NRC Review & Approval ML20247L9331989-09-13013 September 1989 Advises That Written Reactor Operator Licensing Exams Scheduled on 891211 & Operating Exams on 891212-15.Ref Matl Listed on Encl Should Be Provided by 891001.Simulator Exam Scenario Should Be Retained Until Exam Process Completed ML20247E8491989-09-0707 September 1989 Forwards SALP Board Repts 50-277/88-99 & 50-278/88-99 for Aug 1988 - June 1989 ML20247B8711989-09-0101 September 1989 Forwards Restart Safety Insp Repts 50-277/89-19 & 50-278/89-19 on 890618-0729.No Violations Noted ML20246E0241989-08-21021 August 1989 Forwards Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Item 2.1 (Parts 1 & 2) Re Components Required to Trip Reactor & Interface W/Nmss Vendors or Vendors of Each Component,Respectively ML20246J4571989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purpose of Setting Occupational Exposure Limits,Per Info Notice 81-26.Util Should Ensure That Procedures Incorporate Applicable Dose Limits in 10CFR20 ML20248D0261989-08-0101 August 1989 Confirms 890714 Telcon & Requests Assistance & Cooperation in Review of Allegation Involving Plant.Util Should Fully Review Allegation & Take Action in Accordance W/Encl Instructions.Encl Withheld (Ref 10CFR2.790) ML20248C0421989-07-28028 July 1989 Responds to Util in Response to NRC Re Potential Violation of 10CFR50.7.Review of Record Indicates That Violation May Have Occurred.No Further Action Warranted as Case Settled Prior to Investigation ML20247E3191989-07-21021 July 1989 Relaxes Requirements of Section V.A of 870331 Order to Permit Operation of Unit 2 to Full Power ML20246F6121989-07-0606 July 1989 Forwards NRR to Ecology Ctr of Southern California Re Petition to Fix or Close All Nuclear Power Reactors Designed by Ge.Petition Being Treated Under 10CFR2.206 ML20246C3681989-06-30030 June 1989 Forwards Safety Evaluation Supporting 871019 Response to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability, On-Line Testing of Reactor Trip Sys. Existing Test Intervals Consistent W/High Reactor Trip Sys Availability ML20246B9561989-06-28028 June 1989 Forwards Annual Emergency Preparedness Exercise Safety Insp Repts 50-277/89-17 & 50-278/89-17 on 890614.No Violations Noted ML20246B9161989-06-28028 June 1989 Advises That Requirements of 870331 Order Relaxed to Permit Unit 2 Operation Not to Exceed 70% Full Power,In Accordance W/Section Ve of Order ML20246A0001989-06-26026 June 1989 Forwards Restart Safety Insp Repts 50-277/89-16 & 50-278/89-16 on 890507-0617 & Notice of Violation ML20245C9671989-06-16016 June 1989 Requests Addl Info on Response to Generic Ltr 88-01 on IGSCC in Matls.Response Should Be Provided within 60 Days of Receipt of Ltr ML20247M7731989-05-26026 May 1989 Forwards Director'S Decision Re Ohio Citizens for Responsible Energy 10CFR2.206 Petition Re 880309 Power Oscillation Event at Lasalle,Unit 2 ML20247N8481989-05-25025 May 1989 Forwards Safety Insp Repts 50-277/89-12 & 50-278/89-12 on 890410-13.No Violations Noted ML20247L6481989-05-24024 May 1989 Forwards Restart Safety Insp Repts 50-277/89-15 & 50-278/89-15 on 890402-0506.No Violations Noted.Two Issues Remain Unresolved,Including HPCI Sys Wiring Error That Occurred During Plant Mod Installed in Mar & Apr 1989 ML20247K9191989-05-18018 May 1989 Forwards Electrical Insp Repts 50-277/89-13 & 50-278/89-13 on 890405-07 & 13.Issues to Be Resolved Before Unit 3 Restart Listed.No Violations Noted ML20246N3401989-05-10010 May 1989 Advises That Written Senior Reactor Operator Licensing Exams Scheduled for 890814 & Operating Exams Scheduled for Wk of 890918.Ref Matls Listed on Encl Should Be Provided by 890601 ML20246Q3711989-05-0303 May 1989 Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Agenda & Info Re Lodging Arrangements Encl ML20245J0821989-04-26026 April 1989 Modifies Requirements Set Forth in 870331 Order,Section V.A to Permit Operation of Unit 2 Not to Exceed 35% Full Power ML20245F3181989-04-26026 April 1989 Requests Encl Addl Info Re Util 890310 Application for Amends to Licenses DPR-44 & DPR-56 Re Intermediate Detector Not in Startup Position for Calibr 1990-09-06
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M6631999-10-19019 October 1999 Forwards Insp Rept 50-277/99-07 & 50-278/99-07 on 990920.No Violations Noted ML20217K9241999-10-14014 October 1999 Forwards Amend 234 to License DPR-56 & Se.Amend Consists of Changes to TS in Response to Application & Suppls ,1001 & 06,which Will Support PBAPS Mod P00507,which Will Install Digital Pr Neutron Mining Sys ML20217F7391999-10-14014 October 1999 Requests Addl Info Re Peach Bottom Atomic Power Station Units 2 & 3 Appendix R Exemption Requests ML20217F6841999-10-13013 October 1999 Forwards Senior Reactor Operator Initial Exam Repts 50-277/99-302(OL) & 50-278/99-302(OL) Conducted on 990913- 16.All Applicants Passed All Portions of Exam ML20217B4051999-10-0505 October 1999 Forwards Amend 233 to License DPR-56 & Safety Evaluation. Amend Changes Minimum Critical Power Ratio Safety Limit & Approved Methodologies Referenced in Core Operating Limits Report ML20217B3181999-10-0505 October 1999 Advises That Info Submitted in 990712 Application,Which Contained Attachment Entitled, Addl Info Re Cycle Spec SLMCPR for Peach Bottom 3 Cycle 13,dtd 990609, with Affidavit,Will Be Withheld from Public Disclosure ML20212J6851999-09-29029 September 1999 Informs of Completion of mid-cycle PPR of Peach Bottom Atomic Power Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl New Insps Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20212J5751999-09-28028 September 1999 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 990913-16 at Licensee Facility.Without Encls ML20216J0191999-09-27027 September 1999 Forwards Request for Addl Info Re Util 990301 Request to Support Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware,For Plant ML20216H6751999-09-24024 September 1999 Forwards Amends 229 & 232 to Licenses DPR-44 & DPR-56, Respectively & Ser.Amends Will Delete SR Associated Only with Refueling Platform Fuel Grapple Fully Retracted Position Interlock Input,Currently Required by SR 3.9.1.1 ML20216H6451999-09-24024 September 1999 Forwards Notice of Withdrawal of Util 990806 Application for Amends to Fols DPR-44 & DPR-56.Proposed Change Would Have Involved Temporary Change to Increase Limit for Average Water Temp of Normal Heat Sink ML20212E8661999-09-22022 September 1999 Discusses GL 98-01 Y2K Readiness of Computer Sys at NPPs & Supplement 1 & PECO Response for PBAPS Dtd 990630. Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient During Y2K Transition ML20212D1191999-09-17017 September 1999 Forwards SE Re Proposed Alternatives to ASME Section XI Requirements for Containment Inservice Insp Program at Plant,Units 2 & 3 ML20211P2961999-09-0707 September 1999 Provides Authorization to Administer NRC Approved Initial Written Exams to Listed Applicants on 990913 at Peach Bottom Npp,Delta,Pennsylvania ML20211E6941999-08-26026 August 1999 Forwards Request for Addl Info Re Min Critical Power Ratio. Response Should Be Submitted within 30 Days of Ltr Receipt ML20211Q4491999-08-25025 August 1999 Responds to Re Changes to PBAPS Physical Security Plan,Safeguards Contingency Plan & Guard Training & Qualification Plan Identified as Revs 13,11 & 9, Respectively.No NRC Approval Is Required,Per 10CFR50.54(p) ML20211D5421999-08-23023 August 1999 Forwards Amends 228 & 231 to Licenses DPR-44 & DPR-56, Respectively & Se.Amends Revise TSs to Correct Typographical & Editorial Errors Introduced in TSs by Previous Amends ML20211A9721999-08-20020 August 1999 Forwards Request for Addl Info Re Third 10-year Interval Inservice (ISI) Insp Program Plan for Plant,Units 2 & 3 ML20210T5451999-08-12012 August 1999 Forwards Copy of Environ Assessment & Findings of No Significant Impact Re Licensee Request for Amends to Plant. Amends Consist of Changes to TS to Correct Typos & Editorial Errors Introduced in TS by Previous Amends ML20210P1561999-08-10010 August 1999 Submits Response to Requests for Addl Info Re GL 92-01,rev 1,Suppl 1, Rv Structural Integrity, for Pbap,Units 1 & 2. NRC Will Assume That Data Entered Into Rvid Are Acceptable for Plants,If Staff Does Not Receive Comments by 990901 ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210N7831999-08-0909 August 1999 Forwards Copy of Notice of Consideration of Issuance of Amends to Fols,Proposed NSHC Determination & Opportunity for Hearing, Re 990806 Request for License Amends.Amends Incorporate Note Into PBAPS TS to Permit One Time Exemption ML20210P0801999-08-0404 August 1999 Forwards Initial Exam Repts 50-277/99-301 & 50-278/99-301 on 990702-14 (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 ML20210J0161999-07-30030 July 1999 Forwards Copy of Notice of Consideration of Approval of Transfer of FOL & Issuance of Conforming Amends Re 990723 Application ML20210H5341999-07-27027 July 1999 Forwards Insp Repts 50-277/99-05 & 50-278/99-05 on 990518- 0628.NRC Determined That Two Severity Level IV Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209F2461999-07-15015 July 1999 Request Addl Info Re Relief Request CRR-01 Through CRR-11 for Plant,Units 2 & 3.RAI Undtd 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 ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195K2251999-06-11011 June 1999 Forwards Insp Repts 50-277/99-04 & 50-278/99-04 on 990405- 0517.One Severity Level IV Violation of NRC Requirements Identified & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20207G2051999-06-0707 June 1999 Informs of Reorganization in NRR Ofc,Effective 990328. Reorganization Chart Encl ML20207B8381999-05-24024 May 1999 Forwards FEMA Final Exercise Rept for Peach Bottom Atomic Power Station Plume Exposure Pathway Exercise Conducted on 981117.One Deficiency & 27 Areas Requiring Corrective Actions Identified ML20207A0541999-05-17017 May 1999 Acks 990512 & 14 Telcons with Licensee Re Util Request That Rev 8 of NUREG-1021, OL Exam Stds for Power Reactors Be Followed Rather than Interim Rev 8 for Exams in Sept 1999. Request Acceptable ML20206K2231999-05-0606 May 1999 Informs That Author Authorized to Exercise Discretion & Not Issue NOV or Civil Penalty Re Violation Util Identified Involving Unit 2 Rod Block Monitoring Sys Being Inoperable for 29 of 185 Control Rods ML20206K1921999-05-0606 May 1999 Discusses 990503 Telcon Between J Williams & B Bierly Re Arrangements Made for Administration of Licensing Exam at Peach Bottom Facility During Week of 990913 ML20206A1511999-04-20020 April 1999 Forwards Request for Addl Info Re Util 980514 Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-operated Valves. Response Requested within 90 Days of Ltr Receipt ML20206A2801999-04-20020 April 1999 Discusses Proposed Changes Submitted by PECO on 980416, 981116,990122 & 990211 to Plant Emergency Action Levels (Eals).Eals Incorporate Guidance in NUMARC/NESP-007,Rev 2. SE Supporting Proposed EALs Encl ML20205N1961999-04-0909 April 1999 Informs of NRC Planned Insp Effort Resulting from Peach Bottom Atomic Power Station Plant Performance Review Conducted for Period April 1998 to 990115.Historical Listing of Plant Issues & Insp Plans Through Jan 2000 Encl ML20205K7321999-04-0707 April 1999 Forwards Amends 227 & 230 to FOLs DPR-44 & DPR-56, Respectively.Amends Consist of Changes to TS SRs Re Secondary Containment Doors,In Response to 980204 Application,As Revised by ML20205J0531999-04-0101 April 1999 Ack Receipt of 990326 Notice of Enforcement Discretion Request & Documents Resolution.Notes That E3 EDG Returned to Operable Status on 990327,within 14 Day Completion Time Required by Ts.No Enforcement Discretion Necessary ML20205B9891999-03-25025 March 1999 Forwards Insp Repts 50-277/99-01 & 50-278/99-01 on 990105-0215.Violation Noted & Being Treated as non-cited Violation.Nrc Concluded That Staff Maintained Effective Influents Controls & Effective Security Program ML20203H8101999-02-12012 February 1999 Discusses Completion of Licensing Action for Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in BWR, ML20203H7751999-02-12012 February 1999 Discusses Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, for Peach Bottom Atomic Power Station ML20202J5251999-02-0101 February 1999 Forwards Insp Repts 50-277/98-11 & 50-278/98-11 on 981110- 990104 & Notice of Violation Re Failure to Complete Facility Licensed Operator Requalification Program ML20202J8081999-02-0101 February 1999 Forwards Insp Repts 50-277/98-09 & 50-278/98-09 & Notice of Violation.Insp Focused on Reactor Core Isolation Cooling & 4kV Electrical Distribution Sys Operation Under Normal & Emergency Operation Conditions 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 ML20198P1761998-12-30030 December 1998 Forwards from R Calvan Transmitting FEMA Rept for Spring 1998 Peach Bottom Atomic Power Station Ingestion Exposure Pathway Exercise.No Deficiencies Identified During Exercise Conducted on 980407-09,980506 & 980519-21 ML20198K5911998-12-24024 December 1998 Forwards Emergency Response Data Sys Implementation Documents Which Include Data Point Library Updates for Fermi (Number 268),Peach Bottom (Number 269) & Beaver Valley (Number 270).Without Encls IR 05000277/19980081998-12-21021 December 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-277/98-08 & 50-278/98-08 Issued on 981028 ML20198D4071998-12-16016 December 1998 Forwards Emergency Preparedness Insp Repts 50-277/98-12 & 50-278/98-12 on 981116-19.No Exercise Weaknesses,Safety Concerns or Violations of NRC Requirements Identified 1999-09-07
[Table view] |
Text
f'~~ 7 ,~
L JUN 2 7133 !
Docket Nos.: 50-277
+
50-278 L
Philadelphia Electric Company ATTN: Mr. D. M. Smith
. Senior Vice President-Nuclear Nuclear Group Headquarters .
6- Correspondence Control Desk -!
P. O. Box 195
[~ Wayne, Pennsylvania 19087-0195 .;
I Gentlemen:
Subject:
REACTOR OPERATOR AND SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS In a telephone conversation between Mr. R. Andrews and Mr. T. Easlick, ,
Chief Examiner,; arrangements were made for the administration of licensing-examinations at the Peach Bottom Atomic Power Station. ;
The examinations are scheduled for the weeks of September 24, 1990, and October ;
1, 1990. ,
To meet the abeve schedule, it will be necessary for you to furnish the refer-ence material listed in Enclosure 1, " Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examination," by July 24, 1990. Any
- delay in receiving approved, properly bound and indexed reference material, or the submittal of inadequate or incomplete reference material may result in the -
examination being rescheduled. Mr. Andrews 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 admini-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 responsible 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 ;,perator record predetermined plant conditions (i.e., plant pressure, temperature, ets;.).. for ach simulator scenario. The applicants will be responsible for providing this information, with any appeal of a simulator operating examination. Therefore, your training staff should re.ain the origi-nal simulator examination scenario information until all applicants who took 9007030179 900627 Ik FDR ADOCK 05000277 .
V PDC --
/ .
Philadelphia Electric Company 2 examinations have either passed the operating examination, eccepted the denial of their license, or filed an appeal.
F All completed license applications should be submitted at least 30 days before the first examination dates so that we will be able to review the training and experience of the candidates, process the medical certifications, and prepare .
final examiner assignments af ter applicant eligibility 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. Andrews 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, 1990. The estimated average burden is 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per response, including gathering, xeroxing and mailing the required -
material. Send comments regarding this burden estimate or any other aspect of
- this collection of-information, including suggestions for reducing this burden, to the Records and Reports Management Branch, Division of Information Support Services, Office of Information Resources Management, V,$. Nuclear Regulatory Commission, Washington, D.C. 20555; and to the Paperwork Reduction Project (3150-0101), Office of Management and Budget, Washington, D.C. 20503.
Thank you for your consideration in this matter. If you have any questions-regarding the examination procedures and requirements, please contact me at (215) 337-5210.
Sincerely, Origina1 Signed 871 RICHARD J. CONTE Richard J. Conte, Chief BWR 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/encis:
D. R. Helwig, Vice President of Nuclear Engineering and Services R. J. Lees, Chairman, Nuclear Review Board D. B. Miller, Vice President for Peach Bottom 0FFICIAL RECORD COPY EASLICK/PB 10/1/6/20/90 - 0001.0.1 ,
05/23/90
..:, p 9
~
Philadelphia Electric Company 3 cc w/encis._(cont'd.):
J. Urban, General Manager, Fuels Department, Delmarva Power & Light Co.
J. F. Franz, Plant Manager, Peach Bottom Atomic Power Station T. E. Cribbe, Regulatory Engineer, Peach Bottom Atomic Power Station J. P. Wilson, Acting Project Manager, Peach Bottom Atomic Power Station T. B. Conner, Jr. , Esquire W. H. Hirst, Director, Joint Generation Projects De'partment, _
Atlantic Electric B. W. Gorman, Manager, External Affairs E. J. Cullen, Esquire, Assistant General Counsel (Without Report)
R. L Hovis, Esquire R. McLean, Power Plant Siting, Nuclear Evaluations G. Hunger, Director, Licensing Section D. Poulsen, Secretary of Harford County Council J. H. Walter, Chief Engineer, Public Service Commission of Maryland R. Andrews,. Training Manager Public Document Room (PDR)
Local Public Documerit Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector Commonwealth of Pennsylvania bec w/encis:-
Region-I Docket Room (with concurrences)
. Management Assistant, DRMA (w/o'encir)
R.:Bellamy, DRSS DRP Section Chief R. Blough, DRP P..-Kaufman, DRP L. Doerflein, DRP M. Miller, SLO J. Caldwell, EDO G. Suh, NRR R.. Conte, DRS ^
,T. Easlick, DRS '
OL Facility File DRS_ Files (5)
DRS: /
[DRS:RI.
Easlick/dmg 06/pf90 Con /
u c) h s OFFICIAL RECORD COPY EASLICK/PB 10/1/6/20/90 - 0001.1.0 05/23/90 4
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i ES-201 Rev 5 01/01/89 Enclosure 1 REFERENCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS
- 1. Existing learning objectives, Job Performance Measures and lesson plans (including training manuals, plant orientation manual, system descriptions, 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 content validity for the examination.
All Job Performance Measures (JPMs) used to ascertain the competence of the operators in performing tasks within the control room complex and, as ident.ified 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, 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 HIGHEST LEVEL OF CORPORATE MANAGEMENT WHO IS RESPONSIBLE FOR PLANT OPERATIONS (E.G., VICE PRESIDENT OF NUCLEAR OPERATIONS). ACCOMPANYING THE MATERIAL WILL BE A l COVER LETTER EXPLAINING THE DEFICIENCIES IN THE REFERENCE MATERIAL AND THE l FACT THAT THIS WAS THE REASON THE EXAMINATIONS WERE 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 instrumentation.
System training material should draw parallels to the actual procedures used for operating the applicable system.
l Complete and operationally useful descriptions of all safety-system interactions and, where available, BOP system interactions under emergency and abnormal conditions, including consequences of antic-ipated 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 aree.
of theory of reactor operation, thermodynamics, heat transfer and l
i ES-201 !
Rev 5 01/01/89 Enclosure 1 (Continued) fluid flow, as well as specific application to actual in plant com- i 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 instal'ed (i.e., Reactor Coolant Pumps, all ECCS pumps, Recirculation pumps, 'eedwater pumps and Emergency Feedwater pumps). Reactor i Theory material shall include descriptions that draw explicit ties !
between the fundamentals and the actual operating limits followed in !
the plant (i.e., reactor theory material shall contain explanations I i
how principles relate to the actual curves used by operators to !
verify shutdown margin or calculate an ECP). l
- 2. Complete Procedure Index (including surveillancs procedures, etc.)
- 3. All administrative procedures (as applicable to reactor operation or I I safety) I
- 4. All integrated plant procedures (normal or general operating nrocedures)'
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- 5. All emergency procedures (emergency instructions, abnormal or special '
procedures) 6.
l l ) Standing orders (important orders that are safety related and may super- l sede the regular procedures)
- 7. Surveillance procedures (procedures that are run frequently, i.e. Weekly l or that can be run on the simulator) 1 8. Fuel-handling and core-loading procedures, (initial core-loading procedure, when appropriate) 1
'l
- 9. All annunciator / alarm procedures 1 j 10. Radiation protection manual (radiation control manual or procedures) '
- 11. Emergency plan implementing procedures
- 12. Technical Specifications (and interpretations, if available) for all units for which licenses are sought.
- 13. System operating procedures
- 14. Piping and instrumentation diagrams, electrical single-line diagrams, or flow diagrams
- 15. Technical Data Book, and/or plant curve information as used by operators !
and facility precautions, limitations, and set points (PLS) for the facility j l
- ES-201
. Rev 5 01/01/89 Enclosure 1 (Continued)
- 16. Questions and answers specific to the facility training program which may be used in the written or operating examinations (voluntary by facility licensee)
- 17. The following on the plant reference simulation facility "
- a. List of all preprogrammed initial conditir,ns
- b. List of all preset malfunctions with r. clen 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 shall be given.
- c. A description of simulator failure capabilities for valves, breakers, 1
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 i
ability to cause a slow failure of a component such as a feed pump, turbine generator or major valve (e.g., drifting shut of a main feedwater 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 9
Identification plant's control of differences between the simulator and the reference room
- h. Copies of facility generated scenarios that expose the applicants to situations of degraded prc sure control (PWR), degraded heat removal capability (PWR and BWR) and containment challenges (PWR and BWR) may be provided (voluntary by licensee)
- 1. Simulator instructors manual (voluntary by licensee) j.
Description of the scenarios used for the training class (voluntary by licensae)
- 18. Additional material required by the examiners to develop examinations that meet the requirements of these Standaros and the regulations.
[
E5-201 !
+ Rev 5 01/01/89 3
Enclosure 1 (Continued)
The above reference material shall be approved, final issues and shall be so marked. If a plant has not finalized some of the material, the Chief Examiner shall verify with the facility that the most complete, up-to-date material is +
available and that agreement has been reached with the licensee for limiting ,
changes before the administration of the examination. All procedures and reference material shall be bound with appropriate indices or tables of contents so that they can be used efficiently. Failure to provide complete, properly bound and indexed plant reference material could result in cancellation or rescheduling of the examinations.
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ES-208 Rev 5 01/01/89 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 3 foot space between tables.
- 3. Suitable arrangements shall be made by ths facility if the applicants are to have lunch, coffee or other refreshments. These arrangements shall comply with Item 1 above and shall be reviewed by the examiner and/or 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 completing 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 for writing answers to questions. l
- 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.
g- ,
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ES-301 4 Rev 5 01/01/89 R
Enclosure 3 PROCEDURES FOR THE ADMINISTRATION OF VRITTEN 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:
Ouring 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. ;
1
- 2. After the examir.ation 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.
i 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 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 1
separate sheet of paper. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON 3
THE BACK SIDE OF THE PAGE.
- 6. If you write your answers on the examination question page and you need 1 more space to answer a specific question, use a separate sheet of the i paper provided and insert it directly after the specific question. DO NOT l WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE. l
- 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 l on the examination question page.
e
' E X S1 '
Rev 5 01/01/89 i
/
Enclosure 3 (Continued)
I 9.
If you are using separate sheets, number each answer as to category and !
number (i.e. 1.04,6.10) and skip at least 3 lines between answers to allow space for grading. !
- 10. Write "End of Category " at the end of your answers to a category, i
- 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.
ihe amount of b'ank space on an examination question page is NOT an indication of the depth of answer required.
- 15. Show all calculations, methods, or assumptions used to obtain an answer.
- 16. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION
' AND 00 NOT LEAVE ANY ANSWER BLANK. Partial credit will NOT be given on
, multiple choice cuestions.
- 17. proportional grading will be applied. Any additional wrong information that is provided may count against you. For example, if a question is worth one point and asks for four responses, each of which is worth 0.25
- points, and you give five responses, each of your responses will be worth 0.20 points. If one of your five responses is incorrect, 0.20 will be deducted and your total credit for that question will be 0.80 instead of 1.00 even though you got the four correct answers.
18.
If the intent of a question is unclear, ask questions of the examiner only.
- 19. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition, turn in all scrap paper.
- 20. To pass the examination, you must achieve an overall grade of 80*4 or greater and at least 70?4 in each category.
- 21. There is a time limit of (6) hours for completion of the examination.
(or some other time if less than the full examination is taken.)
- 22. When you are done and have turned in your examination. leave the examination seea (CEFINE THE AREA). If you are found in this area wnile the examination is mil in progress, your license may ce cenied or revokea.
23.
Ensure is on yourthat all information answer you wish to have evaluated as part of your answer sheet. Scrap paper will be disposed of without review immediately following the examination.
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l ES-231 l .
.. Rev 5 01/01/89 Enclosure 4 i
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 Chief Examiner will coordinate the details of the review with the facility. An NRC ;
examiner will always be present during the review.
Whenever this option of examination review is utilized, the facility reviewers will sign the following statement prior to being allowed access to the examination. The examination or written notes will nol by retained by the facility,
- a. Pre-Examination Security Agreement I agree that I will not knowingly divulge any inf ormation 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 i 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.
Signature /Cate In addition, the facility staff reviewers will sign the following statement after the wri.tten 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.
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Signature /Date
'e - ES-201
. Rev 5 01/01/89 Enclosure 4 (Continued)'
- 2. Regardless of whether the above examination review option is exercised, immediately following the administration of the written examination, the facility staff shall be provided a marked up copy of the examination and the answer key. The copy of the written examination shall include pen end ink changes made to questions during the examination administration.
If the facility did not review the examination prior to its administration, 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, ahy additional com'nents 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 gradir.g the examinations 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 thri examination will be made without submittal of a reference to support the facility comment. Any supporting documentation that was not previously supplied, should be provided.
- 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. ;
,