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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20209H6921999-07-15015 July 1999 Forwards Comments on Preliminary Accident Sequence Precursor Analysis Provided in NRC Re Operational Condition Reported in LER 269/1998-04 ML20195H1681999-06-10010 June 1999 Forwards Copy of Preliminary ASP Analysis of Operational Condition Discovered at Ons,Units 1,2 & 3 on 980212 & Reported in LER 269/98-004,for Review & Comment ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20206E4101999-04-26026 April 1999 Forwards Four Copies of Rev 9 Todpc Nuclear Security & Contingency Plan,Per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 ML20205T1301999-04-0909 April 1999 Informs That on 990317,C Efin & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Y2K.Initial Exam Dates Scheduled for Wks of 000710 & 17 for Approx 13 Candidates ML20205B0571999-03-24024 March 1999 Informs That Author Determined That Partial Exemption from 10CFR170 Fee Requirements Appropriate for Footnote 4 of Review of License Renewal Application for Ons,Units 1,2 & 3, That Staff Determines Has Generic Value to Industry ML20207C0501999-02-25025 February 1999 Submits Annual Rept Specifying Quantity of Each of Principal Radionuclides Released to Environment in Liquid & Gaseous Effluents,Per 10CFR72.44(d)(3).Effluent Release from ISFSI for CY98 Was Zero ML20202J1901999-01-28028 January 1999 Discusses License Renewal for Operating Power Reactors.Two Applications Received for Renewing Operating Licenses. Commission Established Adjudicatory Schedule Aimed at Completing License Renewal Process in 30-36 Months ML20202H7621999-01-28028 January 1999 Discusses Guidance Re License Renewal for Operating Power Reactors Developed in Response to FY99 Energy & Water Development Appropriations Act Rept 105-581 ML20198S8721999-01-0707 January 1999 Responds to Message to Marks Re Info Request on Appeal Deadline & Desire to Serve Appeal Either by e-mail or by Alternative Regular Mail ML20198Q8871999-01-0707 January 1999 Responds to to Chairman SA Jackson Re Issues for Consideration for Commission During Oconee License Renewal Process.Commissioners Must Remain Impartial During Pendency of Case.Copy of Order LBP-98-33 Encl.Served on 990107 ML20198Q8971998-12-17017 December 1998 Expresses Concerns Re License Renewal of Duke Energy,Oconee Nuclear Station,Units 1,2 & 3.Commends NRC on Steps Agency Has Undertaken to Conclude Renewal Process.With Certificate of Svc.Served on 990107 05000269/LER-1998-012, Forwards LER 98-012-01,re RB Spray Pumps Being Declared Inoperable Due to Npsh.Rept Has Been Revised to Indicate Results of Testing & Corrective Actions Taken to Date1998-12-0303 December 1998 Forwards LER 98-012-01,re RB Spray Pumps Being Declared Inoperable Due to Npsh.Rept Has Been Revised to Indicate Results of Testing & Corrective Actions Taken to Date 05000269/LER-1998-013, Forwards LER 98-013-00 Re Condition Prohibited by Ts,Per 10CFR50.73(a)(1)(d).Circumstances & Causes for Event Have Not Been Fully Determined & Will Be Provided in Supplemental LER on or Before 9812021998-11-0202 November 1998 Forwards LER 98-013-00 Re Condition Prohibited by Ts,Per 10CFR50.73(a)(1)(d).Circumstances & Causes for Event Have Not Been Fully Determined & Will Be Provided in Supplemental LER on or Before 981202 ML20155D2651998-10-23023 October 1998 Expresses Appreciation for Supporting Commission Initiative in Issuing Recent Statement of Policy on Conduct of Adjudicatory Proceedings.Case-specific Orders Were Issued in Calvert Cliffs & Oconee License Renewal Proceedings ML20155B1481998-10-21021 October 1998 Informs That as Result of Discussion of Issues Re Recent Events in Ice Condenser Industry,Ice Condenser Mini-Group (Icmg),Decided to Focus Efforts on Review & Potential Rev of Ice condenser-related TS in Order to Clarify Issues ML20154B9421998-09-30030 September 1998 Amends Chattooga River Watershed Coalition Petition to Intervene in Proceedings Re Application of Duke Energy Corp to Renew OLs for Oconee Nuclear Station,Units 1,2 & 3 ML20154A8971998-09-30030 September 1998 Requests That Submitted Info Be Attached to Amends to Petition to Intervene in Proceedings Re Application of Duke Energy Corp to Renew Operating Licenses for Units 1,2 & 3 ML20153H6881998-09-27027 September 1998 Requests Consideration of Motion to Enlarge Time Required to Submit Amended Petition to Intervene in Proceeding Re Application of Duke Energy Corp to Renew OLs for Facilities ML20153E4721998-09-24024 September 1998 Forwards Notices of Appearances for Attorneys Representing Duke Energy Corp,Applicant in Proceeding for License Renewal of Oconee Units 1,2 & 3.With Certificate of Svc ML20153D1831998-09-17017 September 1998 Ack Receipt of of Duke Energy Co Inviting Reconsideration of Denial by NRC CFO of Duke Exemption Request from Annual Fee Requirements for General License Under 10CFR171.11(d) ML20151S7501998-08-31031 August 1998 Provides Update on Commitment Made by Licensee in Response to NOV & Imposition of Civil Penalty Re Valves in Ldst Instrument Lines That Were Incorrectly Translated Into Station Procedures ML20237B0871998-08-11011 August 1998 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 981007.Sample Registration Ltr Encl ML20236V9581998-07-27027 July 1998 Forwards Corrected Pages 3.5-30b of 961211 & 3.16-2 of 970205 TS Bases.Old Amend Numbers Were Left on Pages.Rev Changes Footer on Both Pages to Reflect Bases Changes ML20236P9451998-07-15015 July 1998 Forwards Emergency Response Data Sys Implementation Documents Including Data Point Library Updates for Oconee (Number 255),Dresden (Number 257) & Susquehanna (Number 258) ML20153D1961998-07-0909 July 1998 Requests NRC Reconsider & Grant Util Request for Exemption from Duplicative License Fee Under 10CFR171.11(d) for Storage of Spent Nuclear Fuel at Oconee Nuclear Station ML20236J9871998-06-24024 June 1998 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Entirety ML20247G0881998-05-14014 May 1998 Provides Rev 2 to Section 3.3, Instrumentation, in Support of TS-362 Amend Request.Position on Testing of Analog Trip Type Instruments W/Regard to Transition from CTS to ITS, Restated.Summary Description of Its/Bases Changes,Encl 05000269/LER-1998-002, Forwards LER 98-002-01 Re non-isolable Weld Leak on Pressurizer Surge Line Drain Pipe Which Resulted in Unit Shutdown1998-04-30030 April 1998 Forwards LER 98-002-01 Re non-isolable Weld Leak on Pressurizer Surge Line Drain Pipe Which Resulted in Unit Shutdown ML20217G0351998-03-26026 March 1998 Submits Ltr to Update Commitment Made by Oconee in Response to Subject Violation.Update Assures That Details of Particular CA Are Appropriately Contained in Docketed Correspondence ML20203J9301998-02-26026 February 1998 Submits Response to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. Suppl 1 to Bulletin Attached & Contains Listed Commitments ML20199J7441998-02-0202 February 1998 Responds to NRC Bulletin 96-004 for NUHOMS-24P Sf Storage Sys Used at Plant Site.Nrc Reviewed Response & Found Response to Be Acceptable ML20198K9321998-01-13013 January 1998 Ack Receipt of Requesting Exemption from 10CFR171 for ISFSI License SNM-2503 & General License Provisions of 72.214 ML20198M9361998-01-12012 January 1998 Responds to Request That rept,BAW-2303P,rev 3 Be Considered Exempt from Mandatory Public Disclosure.Determined That Info Sought to Be Withheld Contains Proprietary Commercial Info & Will Be Withheld from Public Disclosure ML20203C8481997-12-10010 December 1997 Forwards Emergency Response Data Sys Implementation Documents for Plants.W/O Encl 05000269/LER-1997-003, Forwards LER 97-003-01 Re post-LOCA Boron Dilution Design Basis Not Being Met.Rept Includes Updated Info & Revised Corrective Action1997-11-12012 November 1997 Forwards LER 97-003-01 Re post-LOCA Boron Dilution Design Basis Not Being Met.Rept Includes Updated Info & Revised Corrective Action ML20198Q5741997-11-0303 November 1997 Provides Suppl to Initial 971020 Application for Amend to TS Re SG Tubing Surveillance Requirements,In Response to NRC 971030 Request for Addl Info.Proprietary Rev 3 to BAW-2303P, OTSG Repair Roll Qualification Rept Encl.Rept Withheld ML20211P1591997-10-17017 October 1997 Ack Receipt of & Check for $330,000 in Payment for Civil Penalty.Corrective Actions Will Be Examined During Future Insp ML20217D7261997-10-0101 October 1997 Informs That Staff Intends to Use Working Draft SRP-LR as Aid in Reviewing License Renewal Submittals Received from Dpc,Other Licensees & Owners Groups.Policy Issues Will Be Referred to Commission for Resolution ML20211F7981997-09-25025 September 1997 Submits Response to Violations Noted in Insp Repts 50-269/97-10,50-270/97-10 & 50-287/97-10 & Proposed Imposition of Civil Penalty in Amount of $330,000.Corrective Actions:Ldst Instrument Mods on All Three Units Completed ML20217D9341997-09-22022 September 1997 Informs That NRC Staff Has Accepted Deferral of Completion of Certain Actions Requested by Bulletin 96-03, Potential of Plugging of ECCS Strainers by Debris in Boiling Water Reactor ML20211C8021997-09-18018 September 1997 Forwards Revised TS Amend Re Reactor Bldg Structural Integrity.Previously Submitted TSs Contained Editorial Error ML20210T7121997-09-0404 September 1997 Informs That Representatives from Oconee Who Compose LERs Would Like to Meet W/Staff & AEOD at Convenient Place & Time to Facilitate Process.Concerns Addressed in Encl ML20216G5821997-09-0404 September 1997 Informs That 970730 Submittal Re Oconee Nuclear Station, Units 1,2 & 3 Will Be Marked Proprietary & Being Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEC Act of 1954 IR 05000269/19970071997-08-27027 August 1997 Discusses Insp Repts 50-269/97-07,50-270/97-07,50-287/97-07, 50-269/97-08,50-270/97-08 & 50-287/97-08 on 970606 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $330,000 ML20210N1531997-08-13013 August 1997 Confirms 970807 Telcon Between J Burchfield & R Carroll Re Management Meeting to Be Conducted at Oconee Nuclear Station on 970922.Purpose of Meeting to Discuss Oconee Emergency Power Project Initiatives ML20210M8381997-08-13013 August 1997 Confirms Conversation Between J Burchfield & R Carroll on 970807 Re Mgt Meeting to Be Conducted in Region II Ofc on 971113.Meeting to Discuss Status of Plant Performance Improvement Initiatives ML20210N1121997-08-12012 August 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 971008. Facililty Must Submit Either Ltr Indicating No Candidates Scheduled to Participate or Listing Names of Candidates ML20149J4841997-07-21021 July 1997 Forwards Addl Pages to Rev 5 to Duke Power Co Nuclear Security & Contingency Plan. Encl Withheld 1999-08-10
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058H0631990-11-0606 November 1990 Forwards Partially Withheld Insp Repts 50-269/90-32, 50-270/90-32 & 50-287/90-32 on 901015-19 ML20058B2271990-10-12012 October 1990 Confirms 901010 Telcon W/T Curtiss Re Request for Regional Waiver of Compliance.Waiver Granted on One Time Basis & for Max of 4 H to Allow Testing of Reactor Coolant Makeup Pump Prior to 901102 ML20058A6491990-10-0202 October 1990 Forwards SALP Repts 50-269/90-24,50-270/90-24,50-287/90-24 & 72-0004/90-24 for Feb 1989 - Jul 1990 ML20055J1301990-07-24024 July 1990 Forwards Partially Withheld Safeguards Insp Repts 50-269/90-22,50-270/90-22 & 50-287/90-22 on 900625-29.No Violations or Deviations Noted ML20055C9631990-06-25025 June 1990 Forwards Insp Repts 50-269/90-18,50-270/90-18 & 50-287/90-18 on 900604-08.No Violations or Deviations Noted ML20059M9241990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20246N2501989-08-29029 August 1989 Advises That Portions of 890725 Rev 29 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p).Util Should Revert to Commitments Previously Approved or Modify Plan to Accommodate Encl Comments & Resubmit Corrected Plan Pages ML20246F0891989-08-24024 August 1989 Approves Route Request for Shipments of Spent Fuel from Plant to Lynchburg,Va,Per 890720 Request.Proposed Route Encl ML20247K6921989-07-26026 July 1989 Forwards Safeguards Insp Repts 50-269/89-20,50-270/89-20 & 50-287/89-20 on 890626-30.Violations Noted.Enforcement Conference Will Be Scheduled to Discuss Violations ML20244B2981989-05-23023 May 1989 Forwards Insp Repts 50-269/89-10,50-270/89-10 & 50-287/89-10 on 890410-14 & Notice of Violation.Rept Details & Notice of Violation Withheld (Ref 10CFR2.790 & 73.21) IR 05000269/19890051989-05-0505 May 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-269/89-05, 50-270/89-05 & 50-287/89-05 ML20248K5451989-04-0505 April 1989 Responds to 890224 & 0322 Ltrs Re NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification. NRC Agrees W/Suggestion for 890407 Meeting to Discuss Util Schedular Proposal ML20235R0811989-02-25025 February 1989 Advises That Incorporation of ASME Code Case N-401-1 Into Inservice Insp Programs at Plants Acceptable,Per 880815 Request.Code Case N-401, Eddy Current Exam & Rev to Code, Code Case N-401-1 Found to Be Technically Equivalent ML20196C7381988-12-0202 December 1988 Requests That Util Address Generic Ltr 88-17 Re Loss of DHR During Nonpower Operation.Issue of High Priority & Should Be Addressed Accordingly ML20195K1691988-11-30030 November 1988 Discusses 881017 Request for Approval of Route for Transport of Spent Reactor Fuel from Oconee Nuclear Station,Seneca,Sc to B&W Lynchburg Research Ctr,Lynchburg,Va ML20195B5081988-10-20020 October 1988 Advises That 880929 Rev 27 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20207M8651988-10-14014 October 1988 Forwards Amends 171,171 & 168 to Licenses DPR-38,DRP-47 & DPR-55,respectively & Safety Evaluation.Amends Revise Tech Specs to Test Only Initiation Control Circuitry of Reactor Bldg Spray Sys W/O Energizing Pump ML20154M5461988-09-21021 September 1988 Advises That 880808 Rev 26 to Physical Security Plan Consistent W/Requirements of 10CFR50.54(p) & Acceptable IR 05000269/19880291988-09-21021 September 1988 Forwards Insp Repts 50-269/88-29,50-270/88-29 & 50-287/88-29 on 880822-26.No Violations or Deviations Noted ML20154J4731988-09-20020 September 1988 Forwards Request for Addl Info to Complete Review of LER 269/87-05 Re Potential Tripping of HPI Pump Motors on Overcurrent for Pump Starting During Loca.Info Requested within 45 Days of Date of Ltr ML20151M5781988-07-27027 July 1988 Forwards Comments in Resposne to 880331 Submittal of SAR for ISFSI ML20150E8661988-07-12012 July 1988 Ack Receipt of Appealing NRC 871029 Denial of Util 870901 Backfit Claim Re Containment Integrated Leak Rate Testing Requirements Per App J of 10CFR50.Matter Currently Under Review ML20151G0371988-07-0707 July 1988 Advises That 880525 Rev 25 to Physical Security Plan Consistent w/10CFR50.54(p) & Acceptable.Other Portions Require Clarifications or Review by Inspector on Site IR 05000269/19880131988-06-27027 June 1988 Forwards Summary of 880607 Meeting Re Concerns Noted in Insp Repts 50-269/88-13,50-270/88-13 & 50-287/88-13. List of Attendees Also Encl ML20155J2221988-05-31031 May 1988 Confirms 880614 & 15 Meetings at Site in Preparation for Maint Team Insp of Plant During 880711-15 & 25-29,per 880525 Telcon.Matls That Team Would Like to Have Available for Preparation Review Identified in Encl ML20197D6001988-05-27027 May 1988 Requests That Tech Specs Change Requests for McGuire Be Based Upon Pen & Ink Identified Changes,As Presently Practiced on Catawba.Retyped Pages Should Continue to Be Used for Oconee Requests ML20148E4451988-03-21021 March 1988 Forwards Insp Repts 50-269/88-05,50-270/88-05 & 50-287/88-05 on 880217-0316.No Violations Noted ML20150A6341988-03-0303 March 1988 Advises That Scope & Objectives for Plant Radiological Emergency Preparedness Excercise Scheduled for 880414 Meet Requirements for Annual Emergency Exercise ML20196G9641988-02-29029 February 1988 Advises That 870216 Rev 23 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable IR 05000287/19870291988-02-19019 February 1988 Ack Receipt of 880107 Submittal of Analytical Results of Spiked Liquid Samples,Per Insp Repts 50-413/87-29 & 50-287/87-29.Comparison of Results to Known Values & Acceptance Criteria for Comparison Encl ML20148T1431988-01-20020 January 1988 Discusses SALP Repts 50-269/87-33,50-270/87-33,50-287/87-33, 50-369/87-29.50-370/87-29.50-413/87-26 & 50-414/87-26 & 871027 & 29 Meetings,In Response to .No Changes to SALP Rept Warranted.Briefing Slides Encl NUREG-1231, Forwards NUREG-1231, SER Re B&W Owners Group Plant Reassessment Program. NRC Unable to Reach Final Conclusion on Acceptability of Human Factors Portion of Program. Consideration of NRC Recommendations Requested1987-11-0606 November 1987 Forwards NUREG-1231, SER Re B&W Owners Group Plant Reassessment Program. NRC Unable to Reach Final Conclusion on Acceptability of Human Factors Portion of Program. Consideration of NRC Recommendations Requested ML20235W7341987-10-0606 October 1987 Discusses Arrangements for Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wk of 871214.Encl List of Ref Matl Requested by 871014 in Order to Meet Schedule.Requirements for Exams & Guidelines Also Encl ML20235L3261987-09-29029 September 1987 Responds to to Zech Informing That Ltrs Recently Received from Two Members of Smud Board of Directors Requesting Adjudicatory Hearing Does Not Reflect Views of Majority of Board.Nrc Responded to Kehoe & Smeloff Re Issue ML20235B6261987-09-16016 September 1987 Responds to 870812 Request for Hearing to Address Design Flaws in Each of Five Specific Sys Identified in Ucs Petition & Ability of NRC to Evaluate & Assess Level of Danger Inherent in Continued Operation of B&W Plants ML20235B6581987-09-16016 September 1987 Responds to 870912 Request for Hearing Re Design Flaws in Five Specific Sys Identified in Ucs Petition & NRC Ability to Evaluate & Assess Level of Danger Inherent in Continued Operation of B&W Plants ML20238F6911987-09-10010 September 1987 Forwards Exam Rept 50-269/OL-87-01 for Units 1,2 & 3 of Exams Administered on 870713-17.Reactor Operator & Senior Reactor Operator Questions & Answer Key,Facility Written Exam Comments & Simulation Facility Fidelity Rept Also Encl ML20238A4831987-08-31031 August 1987 Forwards AEOD Assessment of LERs for Plant During SALP Period Mar 1986 - Jul 1987,for Info.Overall Quality of LERs Improved Slightly from Previous Evaluation.Quality of Discussions of Personnel/Procedural Errors Decreased ML20238D8751987-08-27027 August 1987 Ack Receipt of Transmitting Proposed Amend to Physical Security Plan.Response to Encl Comments Requested within 30 Days of Ltr Receipt ML20237K0441987-08-25025 August 1987 Requests Review of Encl Safety Issues Mgt Sys Plant Data & Info Re Implementation Status of Facility Generic Issues. Response Requested by 870930 IR 05000269/19870281987-08-0707 August 1987 Forwards Insp Repts 50-269/87-28,50-270/87-28 & 50-287/87-28 on 870713-16.No Violations or Deviations Noted ML20206E0341987-04-13013 April 1987 Advises That Written,Oral & Simulator Exams Scheduled for Wk of 870713,per Telcon.Ref Matl from Encl Approved List Should Be Submitted by 870513.Requirements for Conducting Exams Also Encl ML20206F5311987-03-30030 March 1987 Discusses Telcon Arrangements Made for Evaluation of Requalification Program.Evaluation Visit Scheduled for Wk of 870720 W/Written Exam Administered in Preceeding Wk.Requests Ref Matl Listed in Encl 1 for Examiner to Prepare for Visit ML20205Q2731987-03-25025 March 1987 Advises That Util Will Submit Supplemental Response to Notices of Violation Noted in Insp Repts 50-269/86-32, 50-270/86-32,50-287/86-32,50-369/86-32,50-370/86-32, 50-413/86-44 & 50-414/86-47 by 870403 ML20205C5811987-03-19019 March 1987 Forwards Safety Evaluation Documenting Concurrence W/Encl Contractor rept,EG&G-NTA-7462,re Util Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing. Response Acceptable ML20205N6231987-03-18018 March 1987 Forwards Insp Repts 50-269/87-10,50-270/87-10 & 50-287/87-10 on 870210-0309.No Violations or Deviations Noted ML20205N6931987-03-17017 March 1987 Forwards Insp Repts 50-269/87-09,50-270/87-09 & 50-287/87-09 on 870209-13.No Violations or Deviations Noted ML20207T4361987-03-12012 March 1987 Forwards Insp Repts 50-269/87-06,50-270/87-06 & 50-287/87-06 on 870126 & 30.No Violations or Deviations Noted ML20207T4541987-03-12012 March 1987 Forwards Slide Presentation & Attendee List for 870304 Meeting W/Util,Bnwl & Inel Re PRA Application Program. Comments on Program Requested ML20207T5381987-03-12012 March 1987 Discusses Functional Insp Repts 50-269/86-16,50-270/86-16 & 50-287/86-16 on 860505-0611 & Proposed Imposition of Civil Penalties in Amount of $25,000 1990-07-24
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20195H1681999-06-10010 June 1999 Forwards Copy of Preliminary ASP Analysis of Operational Condition Discovered at Ons,Units 1,2 & 3 on 980212 & Reported in LER 269/98-004,for Review & Comment ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20205T1301999-04-0909 April 1999 Informs That on 990317,C Efin & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Y2K.Initial Exam Dates Scheduled for Wks of 000710 & 17 for Approx 13 Candidates ML20205B0571999-03-24024 March 1999 Informs That Author Determined That Partial Exemption from 10CFR170 Fee Requirements Appropriate for Footnote 4 of Review of License Renewal Application for Ons,Units 1,2 & 3, That Staff Determines Has Generic Value to Industry ML20202H7621999-01-28028 January 1999 Discusses Guidance Re License Renewal for Operating Power Reactors Developed in Response to FY99 Energy & Water Development Appropriations Act Rept 105-581 ML20202J1901999-01-28028 January 1999 Discusses License Renewal for Operating Power Reactors.Two Applications Received for Renewing Operating Licenses. Commission Established Adjudicatory Schedule Aimed at Completing License Renewal Process in 30-36 Months ML20198Q8871999-01-0707 January 1999 Responds to to Chairman SA Jackson Re Issues for Consideration for Commission During Oconee License Renewal Process.Commissioners Must Remain Impartial During Pendency of Case.Copy of Order LBP-98-33 Encl.Served on 990107 ML20198S8721999-01-0707 January 1999 Responds to Message to Marks Re Info Request on Appeal Deadline & Desire to Serve Appeal Either by e-mail or by Alternative Regular Mail ML20155D2651998-10-23023 October 1998 Expresses Appreciation for Supporting Commission Initiative in Issuing Recent Statement of Policy on Conduct of Adjudicatory Proceedings.Case-specific Orders Were Issued in Calvert Cliffs & Oconee License Renewal Proceedings ML20153D1831998-09-17017 September 1998 Ack Receipt of of Duke Energy Co Inviting Reconsideration of Denial by NRC CFO of Duke Exemption Request from Annual Fee Requirements for General License Under 10CFR171.11(d) ML20237B0871998-08-11011 August 1998 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 981007.Sample Registration Ltr Encl ML20236P9451998-07-15015 July 1998 Forwards Emergency Response Data Sys Implementation Documents Including Data Point Library Updates for Oconee (Number 255),Dresden (Number 257) & Susquehanna (Number 258) ML20236J9871998-06-24024 June 1998 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Entirety ML20199J7441998-02-0202 February 1998 Responds to NRC Bulletin 96-004 for NUHOMS-24P Sf Storage Sys Used at Plant Site.Nrc Reviewed Response & Found Response to Be Acceptable ML20198K9321998-01-13013 January 1998 Ack Receipt of Requesting Exemption from 10CFR171 for ISFSI License SNM-2503 & General License Provisions of 72.214 ML20198M9361998-01-12012 January 1998 Responds to Request That rept,BAW-2303P,rev 3 Be Considered Exempt from Mandatory Public Disclosure.Determined That Info Sought to Be Withheld Contains Proprietary Commercial Info & Will Be Withheld from Public Disclosure ML20203C8481997-12-10010 December 1997 Forwards Emergency Response Data Sys Implementation Documents for Plants.W/O Encl ML20211P1591997-10-17017 October 1997 Ack Receipt of & Check for $330,000 in Payment for Civil Penalty.Corrective Actions Will Be Examined During Future Insp ML20217D7261997-10-0101 October 1997 Informs That Staff Intends to Use Working Draft SRP-LR as Aid in Reviewing License Renewal Submittals Received from Dpc,Other Licensees & Owners Groups.Policy Issues Will Be Referred to Commission for Resolution ML20217D9341997-09-22022 September 1997 Informs That NRC Staff Has Accepted Deferral of Completion of Certain Actions Requested by Bulletin 96-03, Potential of Plugging of ECCS Strainers by Debris in Boiling Water Reactor ML20216G5821997-09-0404 September 1997 Informs That 970730 Submittal Re Oconee Nuclear Station, Units 1,2 & 3 Will Be Marked Proprietary & Being Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEC Act of 1954 IR 05000269/19970071997-08-27027 August 1997 Discusses Insp Repts 50-269/97-07,50-270/97-07,50-287/97-07, 50-269/97-08,50-270/97-08 & 50-287/97-08 on 970606 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $330,000 ML20210M8381997-08-13013 August 1997 Confirms Conversation Between J Burchfield & R Carroll on 970807 Re Mgt Meeting to Be Conducted in Region II Ofc on 971113.Meeting to Discuss Status of Plant Performance Improvement Initiatives ML20210N1531997-08-13013 August 1997 Confirms 970807 Telcon Between J Burchfield & R Carroll Re Management Meeting to Be Conducted at Oconee Nuclear Station on 970922.Purpose of Meeting to Discuss Oconee Emergency Power Project Initiatives ML20210N1121997-08-12012 August 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 971008. Facililty Must Submit Either Ltr Indicating No Candidates Scheduled to Participate or Listing Names of Candidates ML20148P5161997-06-30030 June 1997 Second Partial Response to FOIA Request for Documents.App B Records Being Made Available in PDR ML20141C6191997-06-23023 June 1997 Forwards RAI Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Related Gate Valves ML20148E0001997-05-29029 May 1997 Forwards SER Re 960724 Request Relief from Volumetric Exam Coverage Requirements of ASME Code,Section XI,1989 Edition, for Certain Welds in SG & in Letdown Cooler Heat Exchangers for Oconee Units 1,2 & 3.Request Granted ML20140A7241997-05-27027 May 1997 Requests That Interim Response Be Provided to Encl Amended Questions Re High Pressure Injection/Makeup Line Crack Found at Plant,Unit 2.Response Requested by 970529 ML20137Z5171997-04-22022 April 1997 Forwards RAI Re Plants Response to NRR Draft Rept on Plant Emergency Power Sys ML20137R1641997-04-0808 April 1997 Forwards RAI Re 960819 Response to NRC Bulletin 96-004, Chemical,Galvanic,Or Other Reactions in Spent Fuel Storage & Transportation Casks ML20147G4521997-03-0404 March 1997 Forwards Responses to Four Questions Raised During Region II 1996 USNRC Training Managers Conference ML20135D3171996-12-0606 December 1996 Forwards RAI Re Licensee Responses to Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel,Over Fuel in Reactor Core,Or Over Safety-Related Equipment ML20134Q0761996-11-20020 November 1996 Conveys Results & Conclusions of Encl Operational Safeguards Response Evaluation,Conducted at Plant,Units 1,2 & 3 from 960520-23.W/o Encl ML20059F7201994-01-0606 January 1994 Forwards Insp Repts 50-269/93-32,50-270/93-32,50-287/93-32, 50-369/93-31,50-370/93-31,50-413/93-35 & 50-414,respectively on 931213-17.Violations Noted.Failure to Protect Safeguards Info IR 05000269/19930281993-12-23023 December 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-269/93-28, 50-270/93-28 & 50-287/93-28 IR 05000269/19930291993-11-30030 November 1993 Discusses 931108 Enforcement Conference in Region II Ofc, Re Apparent Violation Noted in Insp Repts 50-269/93-29, 50-270/93-29 & 50-287/93-29 on 931019-27.List of Attendees, Meeting Summary & Licensee Presentation Encl IR 05000269/19930271993-11-18018 November 1993 Forwards Insp Repts 50-269/93-27,50-270/93-27 & 50-287/93-27.No Violations Identified ML20058B3811993-11-16016 November 1993 Forwards Safeguards Info Referenced in Preliminary Draft Guide to Facilitate Comments on Proposed Rule for Protection Against Malevolent Use of Vechicles at Nuclear Power Plants. W/O Encl IR 05000269/19930221993-11-0505 November 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-269/93-22, 50-270/93-22 & 50-287/93-22.Understands That Revised Response Will Be Provided by 931203 ML20062J5471993-10-29029 October 1993 Forwards SE of Util 930128 & 0714 Supplemental Responses to IE Bulletin 79-27.Concerns Specified in Bulletin Have Been Adequately Addressed IR 05000269/19930241993-10-19019 October 1993 Forwards Insp Repts 50-269/93-24,50-270/93-24 & 50-287/93-24 on 930829-0925 & Notice of Violation ML20057G2661993-10-15015 October 1993 Responds to Licensee 870407 Request for Relief from Certain Section XI ASME Code Requirements Re Pressure Testing of Purification Demineralizers.Informs That SE Will Not Be Supplemented Due to Relief Being Granted IR 05000269/19930231993-09-24024 September 1993 Forwards Insp Repts 50-269/93-23,50-270/93-23,50-287/93-23 & 72-0004/93-23 on 930823-28 & Notice of Violation ML20057C3451993-09-17017 September 1993 Forwards Insp Repts 50-269/93-22,50-270/93-22 & 50-287/93-22 on 930725-0828 & Notice of Deviation ML20059B5861993-09-10010 September 1993 Ltr Contract,Providing Incremental Funds to Task Order 73, Mod 1, Electrical Distribution Sys Functional Insp - Oconee, Under Contract NRC-03-90-031 IR 05000269/19930201993-09-0303 September 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-269/93-20, 50-270/93-20 & 50-287/93-20 IR 05000269/19930211993-08-18018 August 1993 Forwards Insp Repts 50-269/93-21,50-270/93-21 & 50-287/93-21 on 930627-0724 & Notice of Violation IR 05000269/19930171993-08-0909 August 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-269/93-17, 50-270/93-17 & 50-287/93-17.Response Meets Requirements of 10CFR2.201 1999-08-10
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October 6, 1987 k
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l Duke Power Company '
ATTN: Mr. H. B. Tucker, Vice President Nuclear Production Department !
t 422 South Church Street
} Charlotte, NC 28242 Gentlemen:
SUBJECT:
REACTOR OPERATOR AND SEN10R OPERATOR LICENSING EXAMINATIONS -
i OCONEE NUCLEAR STATION I
l In a telephone conversation between Mr. Dale Tidwell, Instructor, and Mr. Charles Casto, NRC Region II Operator Licensing Section, arrangements l were made for administration of the retake examinations at NRC Region II, j
j Atlanta, Georgia.
The written examinations are scheduled for the week of December 14, 1987. In order for us to meet the above schedule, it will be necessary for the facility to furnish updates to the approved reference material listed in Enclosure 1,
" Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations," by October 14, 1987. Any delay in receiving properly bound and I indexed reference material will result in a delay in administering the l examinations. Our examinations are scheduled far in advance with considerable l planning to utilize our present limited examiner manpower and to meet the examination dates requested by the various facilities. Therefore, missing the October 14, 1987 deadline, even by a few days, will likely result in a long delay, because it may not be possible to reschedule examinations at other facilities. Mr. Tidwell has been advised of our reference material sets that are required, and the examiners' names and addresses where each set is to be mailed.
Enclosure 2, " Requirements for Administration of Written Examinations," describes our requirements for conducting these examinations. Mr. Tidwell has also been informed of these requirements.
Enclosure 2 also cantains 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 candidates are aware of these Rules.
All reacto, aperator and senior reactor operator license applications should normally be submitted at least 60 days before the first examination dates so that we will be able to review the training and experience of the candidates, process the medical certifications, and prepare final examiner assignments after candidate 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.
8710190005 071006 PDR ADOCK 05000269 V PDR
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Duke Power Company 2 October 6, 1987 This request for information was approved by the Office of Management and Budget under Clearance Number 3150-0101 which expires on May 31, 1989. Comments on burden and duplication may be directed to the Office of Management and Budget, 4 Reports Management, Room 3208, New Executive Office Building, Washington, DC 20503.
The facility staff review of the written examination will be conducted in accordance with requirements specified in Enclosure 3, " Requirements for i Facility Review of Written Examination." Mr. Tidwell has been informed of these requirements, f Thank you for your consideration in this matter. If you have any questicns ,
regarding the examination procedures and requirements, please contact !
Mr. John F. Munro at 404/331-5544 or Mr. William M. Dean at 404/331-5601.
Sincerely, (ORIGINAL SIGNED BY C. A. JULIAN)
Caudie A. Julian, Chief Operations Branch Division cf Reactor Safety
Enclosures:
- 1. Reference Material Requirements
- 2. Requirements for Administration of Written Exams
- 3. Facility Review Requirements cc w/encls: ]
T. Barr, Training Supervisor 1 M. S. Tuckman, Plant Manager J bec w/encis:
H. Pastis, Projects Manager, NRR !
T. Peebles, Section Chief, DRP l William Dean, OL Examiner 1 Senior Resident Inspector Document Control Desk .
State of South Carolina l
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CAJu~ian 10/45/87 10/g/87 10/4 /87 10/f/87
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l'15 ENCLOSURE 1 REFERENCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS i
- 1. Existing learning objectives and lesson plans (including training manuals, ;
plant orientation manual, system descriptions, reactor theory, thermo- i dynamics,etc.)
Training materials should include all substantive written material used for preparing candidates for initial R0 and SR0 licensing. The written material should be inclusive of learning objectives and the details presented during i lecture, rather than outlines. Training materials should be identified Lj )
plant and unit, bound, and indexed. Failure to provide complete, properly i bound and indexed plant reference material will result in canceling or i rescheduling of the examinations. Training materials which include the following should be provided:
- a. System descriptions including descriptions of all operationally i relevant flow oaths, components, controls and instrumentation.
System training material should draw parallels to the actual procedures used for operating the applicable system,
- b. Complete and operationally useful descriptions of all safety-system interactions and, where available, B0P system interactions under emergency and abnormal conditions, including consequences of ,
anticipated operator error, maintenance error, and equipment failure. !
- c. Training material used to clarify and strengthen understanding of emergency operating procedures, q
- d. Comprehensive theory material that includes fundamentals in the area >
of theory of reactor operation, thermodynamics, heat transfer and fluid flow, as well as specific application to actual in-plant components. For example, mechanical theory material on pumps should 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 should 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 of how principles relate to the actual curves used by operators to verify shutdown margin or calculate an ECP).
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,. r Enclosure 1 2
- 2. Procedure Index (alphabetical by subject) '
- 3. A11'administrativeprocedures(asapplicabletoreactoroperationorsafety)
- 4. All integrated plant procedures (normal or general operating procedures)
- 5. Emergency procedures (emergency instructions, abnormal or special procedures)
- 6. Standing orders (important orders that are safety-related and may supersede the regular procedures)
- 7. Fuel-handling and core-loading procedures, (initial core-loading procedure, when appropriate)
- 8. Annunciator procedures (alarm procedures, including set points)
- 9. Radiation protection manual (radiatbn control manual or procedures)
- 10. Emergency plan implementing proceduces
- 11. Technical Specifications
- 12. System operating procedures
- 13. Piping and instrumentation diagrams, electrical single-line diagrams, or flow diagrams
- 14. Technical Data Book, and/or plant curve information as used by operators and facility precautions, limitations, and set points (PLS) for the facility ;
'15. Questions and answers that the facility licensee has prepared (voluntary by facility licensee)
- 16. The following on the plant reference simulation facility
- a. List of all readily available initialization points
- b. List of all preset malfunctions with a clear identification number. ,
I The list should include cause and effect information. Specifically, i for each malfunction, a concise description of the expected result, or range of results, that will occur upon implementation should be provided. Additionally, an indication of which annunciators are to be initially expected should be given,
- c. A description of simulator failure capabilities for valves, breakers, indicators and alarms.
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i Enclosure 1 3
- d. Where the capability exists, an explanation of the ability to vary the severity of a particular malfunction should be provided, i.e., ability to vary the size of a given LOCA or steam leak, or the 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 Failures not yet completed .
l g. Identification of significant differences between the simulator and l the reference plant's control room I h. Copies of facility generated scenarios that expose the candidates to situations of degraded pressure control (PWR), degraded heat removal '
capability (PWR and BWR), and containment challenges (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 licensee)
- 17. All material different from that listed in items 1-16 that is specific to the Operator Requalification Training Program
- 18. Additional material required by the examiners to develop examinations that meet the requirements of these standards and the regulations.
The above reference material should be approved, final issues and should 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 should be bound with appropriate indexes or tables of contents so that they can be used efficiently. /
ENCLOSURE 2 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS
- 1. A single room shall be provided for completing the written examination.
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 duration of 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 candidate per table, with a 3-ft. space between tables. No wall charts, models, and/or other training materials shall be present in the examination room. 1
- 3. Suitable arrangements shall be made by the facility if the candidates are to have lunch, coffee, or other refreshments. These arrangements shall comply with Item 1 above. These arrangements shall be reviewed by the examiner and/or proctor.
- 4. The facility staff shall be provided a copy of the written examination and answer key after the last candidate has completed and handed in his written examination. The facility staff shall then have five working days to provide formal written comments with supporting documentation on the examination and answer key to the chief examiner or to the regional office section chief.
- 5. The facility licensee shall provide pads of 8-1/2 by 11 inch lined paper in unopened packages for each candidate's use in completing the examination. i The examiner shall distribute these pads to the candidates. All reference l material needed to complete the examination shall be furnished by the examiner. Candidates can bring pens, pencils, calculators, or slide rules into the examination room, and no other equipment or reference material shall be allowed.
- 6. Only bleck ink or dark pencils should be used for writing answers to questions, i
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L Enclosure.2: 2 NRC RULES AND GUIDELINES'FOR LICENSE EXAMINATIONS
?', During the administration'of this examination the following rules apply:
.1. . Cheating on the examination means an automatic denial of your application
- and could result in more severe penalties.
.2. Restroom trips'are to be limited and only one candidate 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.
3.- Use black ink or. dark pencil.only to facilitate' legible reproductions.
- 4. Print yourname in the blank provided on the cover sheet of the examination.
5.- -Fill in the'date on the cover sheet of the examination (if necessary).
.d. Use only the paper provided for answers.
- 7. Print your name'in the upper right-hand corner of the first page of each section of the answer sheet.
- 8. Consecutively number each answer sheet, write "End of Category " as appropriate, start each category on a new page, write on only one side of the paper, and write "Last Page" on the last answer sheet.
- 9. . Number each answer as to category and number, for example,1.4, 6.3.
- 10. Skip at least three lines between each answer.
- 11. ' Separate answer sheets from pad and place finished answer sheets face down on-your desk or' table.
- 12. Use. abbreviations only if they are commonly used in facility literature.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems, whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
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Enclosure 2 3-
- 16. If parts of the examination are not clear as to intent, ask questions of the examiner only.
- 17. .You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.
- 18. When you complete your examination, you shall:
- a. Assemble your examination as follows:
(1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are a part of the answer.
- b. Turn in your copy of the examination and all pages used to answer the examination questions.
- c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions,
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
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' ENCLOSURE'3 REQUIREMENTS FOR FACILITY-REVIEW 0F WRITTEN EXAMINATION.
-1. . There sh'all be no review of the. written examination,by the' facility staff before or during the administration of. the examination. Following .the administration of the written examination, the facility staff shall be
, provided a marked-up copy of the examination and the answer key.
- 2. The facility will have five (5) working. daysi from the day the written examination is given.to provide formal comment submittal. The submittal will be made to the responsible regional office by the highest level ~of coporate management for plant operations, e.g., Vice President for Nuclear Operations. A copy of the submittal will be forwarded ' to L the chief examiner, as appropriate. Comments not submitted within'five.(5) working days'will'be considered for inclusion ~1n 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 for' finalization. of the examination results may occur.
- 3. The following format should be adhered to for submittal of specific comments:
- a. Listing of NRC question, answer and reference o
- b. Facility comment
- c. Supporting documentation NOTES: 1. No change to-the examination will be made without submittal of complete, current, and approved reference material.
- 2. Conrnents made without a concise facility recommendation will not be addressed.
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