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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 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 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:INCOMING CORRESPONDENCE
MONTHYEARML20209H6921999-07-15015 July 1999 Forwards Comments on Preliminary Accident Sequence Precursor Analysis Provided in NRC Re Operational Condition Reported in LER 269/1998-04 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 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 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 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 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 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 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 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 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 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 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 ML20149J4841997-07-21021 July 1997 Forwards Addl Pages to Rev 5 to Duke Power Co Nuclear Security & Contingency Plan. Encl Withheld ML20141F1381997-06-25025 June 1997 Forwards Rev 4 to Nuclear Security Training & Qualification Plan, Per 10CFR50.4 ML20140C9531997-06-0303 June 1997 Requests NRC Approval of Amend to Oconee ISFSI to Obtain Commission Approval of Proposed Rev 6 to Encl Physical Security Plan.W/O Encls ML20148C8621997-05-22022 May 1997 Informs That TR BAW-2241P Will Be Ref in Future Submittals of P/T Limit Curve Revs for B&W Plants as Result of 970519 Telcon Between L Lois & J Taylor ML20141K1981997-05-19019 May 1997 Forwards Rev 6 to Duke Power Co Nuclear Security & Contingency Plan.Encl Withheld,Per 10CFR73.21 ML20138G8981997-04-30030 April 1997 Forwards Rev 5 to DPC Security & Contingency Plan.Encl Withheld ML20138B3421997-04-22022 April 1997 Submits Response to Request for Addl Info Re Proposed Amend to Reactor Bldg Structural Integrity Tech Specs.Info Provided in Attachments 2 & 3 Supersedes Revised Pages & Markup Pages in Attachment 1 & 2,respectively ML20137N0231997-03-26026 March 1997 Forwards Revised TS 3.1.6 Bases Pages Deleting Detection Time of Reactor Bldg Air Particulate Monitor for RCS Leak of 1 Gpm ML20137B4731997-03-12012 March 1997 Forwards Rev 3 to Security Training & Qualification Plan.Rev Withheld,Per 10CFR73.21 ML20134P3831997-02-18018 February 1997 Submits Clarification of Design Basis Requirements at ONS for Permanently Installed Insulation in Response to NRC Bulletin 93-002, Debris Plugging of Emergency Core Cooling Suction Strainers ML20138L2101997-02-14014 February 1997 Forwards Monthly Operating Repts for Jan 1997 for Oconee Nuclear Station,Units 1,2 & 3 & Revised Monthly Operating Status Repts for Dec 1996 ML20134G5511997-02-0404 February 1997 Requests Exemption to Requirements of 10CFR70.24 Re Criticality Accident Monitoring,Per 10CFR70.14(a) & 70.24(d) ML20133M5971997-01-13013 January 1997 Forwards Revs to Oconee Selected Licensee Commitments Manual ML20138G8411996-12-26026 December 1996 Submits Supplementatl Info Re Emergency Power Engineered Safeguards Functional Test Amend Request ML20132F0911996-12-17017 December 1996 Forwards Response to 961212 & 13 Telcons Re Amend to Licenses for Proposed Changes to Updated Final Safety Analysis Rept Re one-time Emergency Power Engineered Safeguards Functional Test 05000269/LER-1996-008, Forwards Suppl to LER 96-008 Concerning Missed Valve Surveillance Which Resulted in Borated Water Storage Tank Technical Inoperability1996-10-31031 October 1996 Forwards Suppl to LER 96-008 Concerning Missed Valve Surveillance Which Resulted in Borated Water Storage Tank Technical Inoperability ML20134H2231996-10-30030 October 1996 Forwards Revised TS 3.7 Bases,Indicating Info Deleted ML20129B2571996-10-16016 October 1996 Submits Addl Info Re 960220 Application for Amends to Licenses DPR-38,DPR-47 & DPR-55 Concerning Proposed Rev to Chemistry TS Sections 3.1.5,3.1.10 & 4.1,in Response to NRC Telcon Request.Revised TS Pages Encl ML20128H2731996-09-19019 September 1996 Forwards Public Version of Rev 96-06 to Plant Emergency plan.W/961003 Release Memo ML20117D5691996-08-23023 August 1996 Requests Exemption for Ons,Units 1 & 2 & Cns,Units 1 & 2 Iaw/Provisions of 10CFR73.5, Requirements for Physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage ML20116F0051996-08-0101 August 1996 Forwards Corrected Page for Proposed Amend to TS Re Removal of Es Signal from Valves LPSW-4 & LPSW-5 ML20117E6031996-06-26026 June 1996 Forwards Public Version of Change 2 to RP/0/B/1000/01, Emergency Classification & Change 4 to RP/0/B/1000/22, Procedures for Site Fire Damage Assessment & Repair ML20112A0581996-05-14014 May 1996 Responds to NRC Bulletin 96-002, Movement of Heavy Loads Over Spent Fuel,Over Fuel in Reactor Core or Over Safety-Related Equipment ML20115C4371996-05-13013 May 1996 Responds to NRC Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel,Over Fuel in Reactor Core,Or Over Safety-Related Equipment, ML20117D4931996-04-24024 April 1996 Submits Clarification of Reporting Requirements Under 10CFR50.72(b)(2)(vi) ML20107K4991996-04-19019 April 1996 Forwards Rev 2 to Security Training & Qualification Plan. Changes Identified in Rev 2 Do Not Decrease Effectiveness of Plan & Thereby Submitted,Per 10CFR50.54(p),(2).Rev Withheld, Per 10CFR73.21 ML20107K5361996-04-18018 April 1996 Forwards Rev 4 to Util Security & Contingency Plan 1999-07-15
[Table view] Category:UTILITY TO NRC
MONTHYEARML16259A2391990-08-22022 August 1990 Forwards Public Version of Rev 27 to Company Crisis Mgt Implementing Procedure CMIP-2, News Group Plan. W/ Dh Grimsley 900906 Release Memo ML20059C1201990-08-20020 August 1990 Forwards Rept Summarizing Util Findings Re Three False Negative Blind Performance Urine Drug Screens Which Occurred During Jan & Feb 1990.Recommends That NRC Consider Generic Communication to Clearly State Reporting Requirement ML20063Q2671990-08-14014 August 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 36 to CMIP-1,Rev 32 to CMIP-4,Rev 36 to CMIP-5,Rev 41 to CMIP-6,Rev 40 to CMIP-7,Rev 27 to CMIP-8 & Rev 35 to CMIP-9.W/DH Grimsley 900821 Release Memo ML20055C9851990-06-25025 June 1990 Forwards Rev 9 to Training & Qualification Plan.Rev Withheld ML16152A9841990-06-19019 June 1990 Forwards Revised Public Version of Rev 90-03 to Vol B of Epips,Including CP/2/A/2002/04C, Operating Procedure for Post-Accident Liquid Sampling, & Maint Directive 8.1 ML20044A4491990-06-14014 June 1990 Forwards Public Version of Rev 90-05 to Vol C to EPIP Manual. W/Dh Grimsley 900627 Release Memo ML16152A9821990-06-14014 June 1990 Forwards Public Version of Rev 90-02 to Vol B to Oconee Nuclear Station Epips. W/Dh Grimsley 900627 Release Memo ML20043E2571990-05-31031 May 1990 Forwards Request for Relief 90-01 from Requirements of Section XI of ASME Boiler & Pressure Vessel Code Re Inservice Insp During Second 10-yr Interval ML20043F4761990-05-30030 May 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Consisting of Rev 20 to CMIP-13 & Deletion of CMIP-15 & CMIP-17.W/900612 Release Memo ML20043A5441990-05-16016 May 1990 Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project ML16152A9621990-05-0909 May 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 35 to CMIP-1,Rev 26 to CMIP-2,Rev 31 to CMIP-4,Rev 35 to CMIP-5,Rev 40 to CMIP-6,Rev 39 to CMIP-7 & Rev 26 to CMIP-8.W/DH Grimsley 900517 Release Memo ML16152A9531990-05-0202 May 1990 Forwards Proprietary DPC-NE-2000P-A & Nonproprietary DPC-NE-2000-A, DCHF-1 Correlation for Predicting Heat Flux in Mixing Vane Grid Fuel Assemblies. Proprietary Rept Withheld ML20042H0321990-04-30030 April 1990 Forwards Public Version of Rev 90-04 to Vol C to EPIP Manual ML15217A1051990-03-26026 March 1990 Forwards Revised 1989 Annual Radiological Environ Operating Rept,Consisting of Revised Pages Summarizing Annual Liquid Dose Calculations ML20012D6941990-03-21021 March 1990 Advises of No Human Engineering Discrepancy Mods of Safety Significance for Overall Operation of Plant,Per 880420 Commitment ML16152A9411990-03-14014 March 1990 Forwards Public Version of Rev 90-01 (Vol a) to Emergency Plan Manual & Revs 90-01 (Vol B) & 90-03 (Vol C) to EPIP Manual.W/Dh Grimsley 900329 Release Memo ML20012B3741990-03-0101 March 1990 Requests Extension to Respond to Generic Ltr 90-01 Re Participation in Regulatory Impact Survey Until 900402.Util in Process of Completing Questionnaires for All Units ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML20012B4541990-02-21021 February 1990 Forwards Public Version of Vol C to Rev 90-02 to EPIP Manuals ML20012B3661990-02-21021 February 1990 Forwards Rev 1 to Cycle 12 Reload Rept,Changing Assumed RCS Flow & Correcting Typo ML20012B1691990-02-19019 February 1990 Forwards Public Version of Crisis Mgt Implementing Procedures,Including Rev 34 to CMIP-1,Rev 25 to CMIP-2, Rev 30 to CMIP-4,Rev 34 to CMIP-5,Rev 39 to CMIP-5 & Rev 38 to CMIP-7 ML19354E6711990-01-24024 January 1990 Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 ML20006C7181990-01-22022 January 1990 Forwards Rev 30 to Security Plan.W/O Encl ML16152A9061990-01-19019 January 1990 Forwards Public Version of Rev 90-01 to Vol C to Oconee Nuclear Station Implementing Procedures Emergency Plan & Rev 89-03 to Vol a to Oconee Nuclear Station Emergency Plan. W/900131 Release Memo ML16152A9091990-01-18018 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo ML20005G7601990-01-0404 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Plan. Privacy Info Should Be Deleted Prior to Placement in Pdr.W/ D Grimsley 900118 Release Memo ML20005G1181990-01-0404 January 1990 Forwards Response to NRC Recommendations in 890828 Audit Evaluation Rept Re Safety & Performance Improvement Program. Util Fully Committed to Enacting Recommendations from Program Via B&W Owners Group Improvement Program ML20042D3731990-01-0202 January 1990 Forwards Revised Crisis Mgt Implementing Procedures, Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9, Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML19351A5721989-12-0707 December 1989 Withdraws Commitment to Install Cavitating Venturies or Any Other Mod to Relieve Operator Burden in Ensuring That Emergency Feedwater Pumps Protected from Runout in Postulated Accidents W/Low Steam Generator Pressurization ML20011D2411989-11-30030 November 1989 Forwards Revised Crises Mgt Implementing Procedures, Including Rev 23 to CMIP-2 & Rev 3 to CMIP-15 ML16152A8751989-11-21021 November 1989 Forwards Proprietary DPC-NE-2003P-A & Nonproprietary DPC-NE-2003-A, Core Thermal-Hydraulic Methodology Using VIPRE-01. Proprietary Rept Withheld ML19332C6571989-11-20020 November 1989 Advises That Listed Addl Protective Measures Will Be Provided for Auxiliary Svc Water Piping,Per 890530 Ltr ML16152A8731989-11-0101 November 1989 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 31 to CMIP-1,Rev 28 to CMIP-4,Rev 32 to CMIP-5,Rev 37 to CMIP-6,Rev 36 to CMIP-7,Rev 25 to CMIP-8 & Rev 31 to CMIP-9.W/891020 Release Memo ML16152A8701989-10-30030 October 1989 Forwards Public Version of Rev 32 to Crisis Mgt Plan for Nuclear Stations. W/891113 Release Memo ML16152A8641989-10-18018 October 1989 Forwards Public Version of Revs 89-05 & 89-07 to Vol B & C, Respectively,Of Implementing Procedures Emergency Plan. W/891030 Release Memo ML19351A2771989-10-13013 October 1989 Advises That Tech Spec Amend Request,Including Revised 15 EFPY Pressure/Temp Limits & Revised Low Temp Overpressure Protection Sys Operability Requirements Will Be Submitted by 891115,per Commitment in 890131 Ltr Re Generic Ltr 88-11 ML19325C9181989-10-0909 October 1989 Forwards Rev 8 to Training & Qualification Plan.Rev Withheld ML20248F1971989-09-29029 September 1989 Clarifies Tech Spec Rev,Consisting of Changes to App J Test Requirements for Valves CA-27,HP-155 & CF-47.All Lines Leading from Auxiliary Bldg to Valves HP-155 & CA-27 Maintained Normally Isolated Through Closed Manual Valves ML20246G9561989-08-23023 August 1989 Submits Details of Method for Reporting Findings Resulting from Design Basis Documentation Program,Per 890728 Meeting. Util Agrees to Submit LER for Each Finding Identified in Design Basis Documentation Program ML20245H4841989-08-0909 August 1989 Forwards Addl Info on DPC-NE-3000, Thermal-Hydraulic Transient Analysis Methodology, Per 890718 & 19 Telcons Re Steam Generator Heat Transfer Modeling W/Retran Code ML20245L6441989-08-0404 August 1989 Documents 890726 Conference Call Re Implementation Schedule for ATWS Mods.Proposed Schedule for Mods to Install ATWS Mitigation Sys Actuation Circuitry Based on Decision to Utilize Programmable Logic Controller ML20248C0091989-07-31031 July 1989 Advises That Response to Generic Ltr 89-06, SPDS, Will Be Delayed Due to Late Date of Receipt of Ltr.Submittal Anticipted by 890808 ML20247H4211989-07-25025 July 1989 Forwards Rev 29 to Security Plan.Rev Withheld ML20247K0211989-07-21021 July 1989 Responds to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment, Clarifying Info in .Use of Unqualified Components in Vent Paths for Valves Acceptable Based on Secondary Side Cooling ML20246G1711989-07-20020 July 1989 Submits Route Info for Shipment of Eight Irradiated Fuel Rods from Oconee to B&W Lynchburg Research Ctr in Sept 1989, Consisting of Single Shipment w/NLI-1/2 Spent Fuel Shipping Cask.Approval Requested by 890901 ML20247A8991989-07-13013 July 1989 Forwards Rev 4 to Process Control Program ML20246P5721989-07-13013 July 1989 Forwards Request for Relief 89-06 from Requirement of Section of XI of ASME Boiler & Pressure Code Re Second 10-yr Interval Inservice Insp.W/Three Oversize Drawings ML20246K2101989-06-28028 June 1989 Forwards Public Version of Revised Crisis Mgt Implementing procedures.W/890711 Release Memo ML20247N9591989-05-30030 May 1989 Forwards Request for Relief 89-04 from Inservice Insp Requirements of Section XI of ASME Boiler & Pressure Vessel Code,Based on Impracticality of Performing Full Volumetric Exam of Turbine Stop Valve Upper Head to Valve Body Studs ML20247E5401989-05-15015 May 1989 Confirms 890504 Discussion Re Acceptance of Util Proposed Schedule for Implementation of ATWS Mods.Util Cannot Commit to Submitting Final Design Description Earlier than 890901 1990-08-22
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i December 19, 1974 i
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Mr. Norman C. Moseley, Director Directorate of Regulatory Operations
! U. S. Atomic Energy Co= mission Region II - Suite 818 230 Peachtree Street, Northwest I Atlanta, Georgia 30303 Re: R0 Inspection Report 50-269/74-10 50-270/74-8 50-287/74-11
Dear Mr. Moseley:
We have rcviewed R0 Inspection Report Nos. 50-269/74-10, 50-270/74-8 and 50-287/74-11. Duke Power Company does not consider the infor-mation contained in this report to be proprietary.
With regard to the specific concerns identified in your letter, please find attached our responses. In addition to the information provided in the attached, we have taken actions to improve the effectiveness of our management control systems. Most significant of these actions is the recent reorganization within the Steam Production Department. This reorganization has served to clarify areas of j responsibility, and the authority commensurate thereto, both within the Steam Production Department General Office and within the station organization. Also, the position of Manager, Nuclear Production has been established. The nuclear station Managers report to the Manager, Nuclear Production who, in turn, reports to the Vice President, Steam Production. This change has served to strengthen line management i
control and involvement with regard to nuclear station operations.
To assist management in effectively discharging its responsibilities, a program has been developed to maintain and periodically distribute a written compilation of all outstanding cccmitments relating to Oconee Nuclear Station. In this manner, it can be assured that proper and timely actions are taken with regard to items identified.
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Mr. Wor ~an C. Moseley Page 2 December 19, 1974 It is felt that actions taken to date, and which are continuing, have served to significantly improve the effectiveness of the management control system with regard to the operation of Oconee Nuclear Station.
Very truly yours,
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RESPO:'SES TO R0 INSPECTION REPORT 50-269/74-10, 50-270/74-8, 50-287/74-11 December 19, 1974 i
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ITEM I.A.l.b: .
i Technical Specification 6.4.1 requires that procedures be developed and adhered to for activities affecting quality. Section 3.2.2.5 of the DPC Steam Pro-duction Department (SPD) Administrative Policy Manual (APM) for Nuclear Stations requires each station to establish a periodic testing schedule to assure that all safety-related testing is performed and properly evaluated
- in a timely manner.
Contrary to the above, a periodic testing schedule has not been developed and (Details II, implemented as specified by paragraph 3.2.2.5 of the APM.
paragraph 4.a) ,
RESPONSE
A computer program has been pr(pared for the purpose of scheduling periodic tests. This program is presently available for statien use and the information for a number of periodic tests has been input to the program data base. Those tests are currently being scheduled thereby. Information for other periodic tests with a frequency of greater than weekly is currently being input to the program data base. This task should be completed by January 15, 1975, and, subsequent to that date, the program will be used for scheduling such periodic tests.
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ITEM 1.A.l.a: -
Technical Specification 6.1.?.l.d.5 requires the Station Review Committee (SRC) to review proposcd safety-related changes or modifications to the station design.
Contrary to the above, the SRC did not review station modification re, quest 0-300-S, which changed the steam generator water level control from 95%
to 50% for natural circulation cooling. (Details I, paragraph 3.a)
RESPCNSE:
As noted in the inspection report, DetaiIs I, paragraph 3.a. the modification to change the steam generator level control setpoint for natural circulation cooling frca 95% to 50% was recommended by the Babcock and Wilcox Ccapany (B&W) in a letter dated July 24, 1974. The Station Review Committee31, (SRC) 1974.
reviewed the safety implications of the recommended change on July It is considered that this review of the safety i=plications of, and concurrence with, the proposed modification was adequate.
With regard to'SRC review of future station modifications, new policies for the control of modifications are to be incorporated into the Steam Production Department's " Administrative Policy Manual for Nuclear TheseStations" policiesonrequire December 20, 1974, for implementation on January 1, 1975.
that the SRC review each proposed modification to safety-related structures, systems and components subsequent to design of the modification and prior to implementation of the modification. These policies also require that the fact that such a review has been performed be verified prior to implementation of the subject ecdification.
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Technical Specification 6.4.1 requires that the station be operated and main-
! tained in accordance with approved procedures, and Technical Specification 6.1.2.1.d requires the SRC to review safety considerations, unusual events, violations of Technical Specifications and new procedures that affect nuclear safety. .
Contrary to the above:
(1) No documentary evidence could be located to verify that the following
-procedures had been reviewed by the.SRC. .
(a) PT/1/A/201/3, Core Flood System.
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(b) PT/0/A/204/9, Reactor Building Spray System Engineered Safeguards Tests (c) PT/0/A/202/ll, High Pre? ure Injection System Performance Test (Details II, paragraph 2.d(2))
(2) An i= proper valve lineup resulting in an unplanned drop in the level of the Borated Water Storage Tank for Unit 1, on August 26, 1974, was not reviewed for safety considerations by the SRC. (Details III, paragraph 2.e)
RESPONSE
(1) Subsequent to the exit interview of November 13, 1974, a review of those procedures noted as not having been reviewed by the Station Review Co=mittee (SRC) was conducted. This review determined that documentary evidence is available with regard to SRC review of two of the noted procedures. PT/1/A/0201/03, Core Flood System, was reviewed by the SRC on October 17, 1972, as indicated by a copy of the procedure in the I
Master File. PT/0/A/0202/ll, High Pressure Injection System Perfor=ance Test, was reviewed by the SRC on November 18, 1972, as shown by SRC minutes.
No written evidence can be found showing that PT/0/A/0204/09, Reactor Building Spray System Engineered Safeguards Test, was reviewed prior to its approval on March 10, 1973, as required by Technical Specification 6.1.2.1.d. however, a complete revisio, to this procedure was reviewed by the SRC on July 25, 1974, prior to the initial utilization of this procedure. It is felt that since the date of this incident, i.e., March,
- 1973, that'the control of the preparation, review and approval of pro-1 cedures has continually improved. This is evidenced by the fact that, I although PT/0/A/0204/09 was not originally reviewed by the SRC, the July, l 1974 revision to the procedure did receive SRC review.
(2) The incident cited occurred on August 26,'1974. O'n August 27, 1974,'an investigation was conducted to determine if Technical Specifications had been violated and it was concluded that a Technical Specifications violation had not occurred. Based on this conclusion, this incident was l
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not classified as an Abnormal Occurrence or an Unusual Event and, therefore, was not reviewed by the SRC. Since the date of ehis incident, however, management has placed increased emphasis on the importance of reviewing incidents promptly for their safety significance and reportability to the AEC as an Abnormal Occurrence or Unusual Event - see response to Violation I.A.l.d. Incidents similar to the one noted are currently being re-viewed by the SRC as required. It is believed that, as a result of these corrective actions, present methods are adequate to assure future com-pliance with the Technical Specifications.
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, ' ); ITEM I'.A.1.d:
Technical Specification 6.1.2.1.d.3 requires the SRC to review all unusual events. Technical Specification 6.6.2.1.b requires that unusual events be reported to the Directorate of Regulatory Operations within 30 working days.
Contrary to the above: ,
i (1) The SRC did not review a condition that permitted both doors of the Unit 2 reactor building personnel hatch to be opened at the same time, which (Details III,
! could have resulted in a loss of containment integrity.
paragraph la) ,
l (?) A report of the unusual event was not submitted to the Directorate of j Regulatory Operations. (Details III, paragraph 1.a) -
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- RESPONSE
i The deficiency noted in Details III, paragraph 1, of the inspection report resulted from the failure to note the interlock failure in the shif t j supervisor's log. The incident was noted in the Unit 2 reactor operations f
log, but no entry was made in the shift supervisor's log due to the fact i that (1) existing unit conditions (cold shutdown) did not require containment l integrity, (2) timely maintenance action, and (3) the administrative controls i imposed (a man was stationed inside the hatch to control traffic and prevent i both doors from being opened simultaneously) during the time the interlock was inoperable. If the incident had been noted in the shif t supervisor's log, it would have been brought to the attention of the Technical Servicas l
Engineer, who is more knowledgeable of the Oconee FSAR, and a better determi-i nation of the reportability of the incident would have been made.
As noted in Details III, paragraphs 1 and 2, the Technical Services Engineer reviews the shif t supervisor's log to identify any incidents or conditions
, which warrant further investigation. The results of this investigation, including recommended corrective action, are summarized in an Incident Investi;,ation Report. These reports are reviewed by the Station Review
]) Co=nittee (SRC), station management, and the Licensing Unit in the General 4
Office. If it is determined that the incident is reportable to the AEC i under the definitions of Abnormal Occurrence or Unusual Event centained in L the Technical Specifications, the Incident Investigation Report, with SRC
! and station Manager comments, is forwarded to the Licensing Unit for i preparation of a report'to the AEC.
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. ITEM 1.A.1.c: .
Technical Specification 6.4.l requires that operation of the station be conducted in accordance with procedures appropriate to the circumstances.
Contrary to the above:
of a (1) The emergency procedure stating action to be taken in the event loss of coolant flow was not changed, following a change of the steam generator level setpoints. (Details 1, paragraph 3.a)
(2) The ccatrolling procedure for unit startup, OP/2/A/1102/1, was not revised to reflect Change No. 6 (issued May 29, 1974) to the technical specifications. (Details III, paragraph 2.a)
(3) Procedure PT/0/B/200/5, Running Reactor Coolant Pump Motors, was in-adequate, in that the procedure permitted irstallation of jumpers on safety-related equipment and did not specify removal of the jumpars following completion of testing. (Details III, paragraph 2.c)
RESPONSE
With regard to the three items listed, the following corrective action has been taken:
1974 to change the (1) Change 1 to EP/0/A/1800/06 was made on December 4, OTSG level setpoint from 95% to 50%.
(2) Change No. 20 to OP/2/A/1102/1 revised OP/2/A/1102/01, the controlling procedure for unit startup, to reflect Change No. 6 to the Technical Specifications. Change No. 20 was approved on October 18, 1974.
(3) Change No. 2 to PT/0/B/0200/05, dated October 18, 1974, corrects the deficiency noted in this procedure.
To prevent recurrence of incidents similar to those noted above, a more complete review of station modifications and Technical Specificatica changes will be performed, and procedure changes will be made in a timely manner. Specifically with regard to station modifications, new policies for the control of modifications are to be incorporated into the Steam Pro-duction Department's " Administrative Policy Manual for Nuclear Stations" on These policies December 20, 1974, for implementation on January 1,1975.
will require that verification of the completion of a modification include verification that any required procedure changes have been made.
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y ITEM 1.A.l.f: .
Technical Specification 6.1.1.5 requires that a training program be established the provision of for all personnel, including security procedures, which meet ANSI M18.1.
Contrary to the above, training and retraining of personnel(Details in secur,ity I, pro-cedures has not been effected for all station employees.
paragraph 4.d)
RESPONSE
Employees have previously received train'ing in station In ordersecurity althbugh a to improve formal training program had not been established.
employee training in station security requirements, a formal training program has been developed, and will be presented to all station during January, 1975. of the orientation training in the area of security procedures as partRetraining of all Oconee employee program for new employees.
procedures will be conducted annually.
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ITEM X.A.l.g:
Technical Specification 6.1.2.2.b states that the activities of the Nuclear Safety Review Committee (NSRC) shall be guided by a written charter, and lists the activities that must be contained within the charter.
Contrary to the above, the following activities, required to be contained in the SSRC charter, are not discussed in the by-laws which serve as a charter.
(1) Subjects w.i. thin the purview of the committee.
(2) Identification of managecent position to which the group reports,.
(3) Provisions for assuring that the committee is kept inforced of matters within its purview.
RESPONSE
The By-Laws (Charter) of the Nuclear Safety Review Committee are presently being revised to fully reflect the requirements of the current Technical Specifications'. The By-Laws will be revised within ene month following each future revision of the Technical Specifications af fecting the Nuclear Safety Review Committee. It is expected that the current revision of the By-Laws will be completed by February 1, 1975.
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li ' ITEM I. A.1.h: ,
Technical Specification 6.1.2.2.1 requires the NSRC to review abnormal occurrences and unusual events.
Contrary to the above, the NSRC did not review the abnormal occurrence (incorrectly reported as an unusual event), relating to the failure of,the Unit 2 Low Pressure Injection Valve. (Details II, paragrapn 5.g(1))
RESPONSE
The Nuclear Safety Review Committee (NSRC) reviewed the unusual event relating to the failure of a Unit 2 low pressure injection valve as Oconee In'cident Report B-174 during their review of the July 15, 1974 minutes of the Station Review Committee (SRC). This review is documented as Item 7 of the September 27, 1974 Minutes of the NSRC. Prior to the September 27, 1974 meeting of the SSRC, the Chairman distributed Unusual Event Report No. UE-27 0/74-3, which describes this valve failure to all members for review. Members then had the opportunity to ask questicas or make comments, as appropriate, during the September 27, 1974 meeting.
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ITEM 1.A.l.i: , .
! Criterion XVI of Appendix B to 10 CFR 50 requires that prompt corrective action to preclude recurrence of nonconforming items be taken.
Contrary to the above, prompt corrective action was not taken of deficiencies identified in an internal QA audit performed on June 10, and in a reau,dit of August 16, 1974, concerning document control and tagging of equipment. The QA records do not reflect that corrective action to prevent recurrence had been taken as of October 23, 1974. (Details I, paragraph 6.a)
RESPONSE: ,
Quality Assurance Department personnel conducted Level II audit 0-74-1 during the week of June 10, 1974, and issued a report thereof on June 21, 1974. On July 26, 1974, Mr. J. E. Smith, bbnager, Oconee Nuclear Station, responded to the concerns noted in the audit report. Quality Assurance Department personnel conducted a reaudit on August 16, 1974, the report of which was issued on August 20, 1974. The report of the reaudit did not specifically request a response and, therefote, none was prepared at that time. A response to the reaudit has since been transmitted by Mr. Smith to the Steam Production Depart-ment General Office. This response is currently being processed and will be forwarded to the Quality Assurance Department by January 1, 1975.
On November 5,1974, Mr. William O. Parker, Jr. , Vice President, Steam Production, established a policy for future handling of Level II audit reports. Also, on December 20, 1974, a revision to the Steam Production Departnent's " Administrative Policy Manual for Nuclear Statiens" is to be issued which will include requirements for the proper and timely correction of identified deficiencies. As a result of these actions, incidents of the type noted should not recur.
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1TCt I.A.l.j:
Criterion lG'III of Appendix g to 1C CT: 50 requires that audits be perfor=ed by appropriately trained personnel in the areas being audited.
Contrary to the above, none of the Level I QA auditors performing audits of the operating facilities have received appropriate training or are experienced in reactor opeJations. (Details I, paragraph 6.c) -
RESPO:;SE:
During 1975, selected Quality Assurance Department personnel involved in performing Level I audits will receive formal training in reactor op'brations.
This training will consist of classroom instruction and discussion, supplemented with appropriate video tapes, on nuclear station systems and procedures.
It is anticipated that each participant in the training will receive approxi-mately 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> of training.
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3 ITEM 1.A.l.k:
l r Technical Specification 6.1.2.1.a requires the superintendent to appoint an on-site review committee (SRC) consisting of at least five members of the station supervisory staf f. Technical Specification 6.1.2.1.c specifies that a quorum shall consist of the chairman plus two = cabers.
Contrary to the above, SRC meetings were conducted without the required quorum of supervisory members present. (Details II, paragraph 2.a)
RESPCNSE:
The Tcchniccl Specifications 6.1.2.la requires that the Manager appo' int a Statior. Review Committee of at least five members of the Station Supervisory Staff, it requires representation from Operations and Technical Services and that personnel with expertise appropriate to items being considered participate on the Committee.
The initial comnittee was made up of the Station Assistant Superintendent as Chairman, the Operating Engineer, the Technical Support Engineer, the Main-tenance Supervisor, and the Health Physics Supervisor. With the initiation of station operation and development of the expertise of other station personnel, the number of individuals in the station supervisory organization qualified to serve on this committee has increased. The Manager has performed a continuing review of personnel in the station supervisory organization as regards their qualifications and listed those who are qualified to serve on a basic five man committee. The Intrastation I<*.ter is a list of supervisory personnel qualified to participate on this cons;; tee and is not intended to infer that this is a thirty-three man committee.
Normally, meetings of this committee are scheduled with five members present with representation from the Operacions and Technical Services Groups participating, Where items of a particular discipline are being considered, a member of the supervisory organization in the area being considered is included in the committee meeting. Special called meetings require at least a quorum present.with participation of a member of the supervisory organi-zation who has expertise in the area being considered.
As regards Section 12A.5 of the FSAR, this is only a partial listir.g of the station supervisory organization, ar.d it is not required or intended that all station supervisory personnel be identified. Sectica 12A.5 is intended to establish that there are in the station org--1:ation adequate supervisory personnel with technical capabilities to s . _ly operate and maintain the station in keeping with the safety review atd in keeping with ANSI 18.1.
The Intrastation Letter is being revised to clarify any misunderstanding that any have resulted.
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/ XTEM I.A.2.a:
- Technical Specifications 6.5.2.d and 6.5.2.h require station maintenance histories for safety related structures, systems and components, including periodic testing records, be prepared and maintained thefor a minimum station of six shall be years. Technical Specification 6.4.1 states that operated in accordance with approved procedures.
Contrary to the above:
(1) No documentation could be provided to show that the replacement of pressurized safety valves was done in accordance with an approved records'of the procedure and the maintenance history and periodic test II, paragraph (Details installed safety valves could not be located.
4.b(1))
be (2) Records of the periodic tests of the Core Flood System could not located. (Details II, paragraph 4.b(2))
RESPONSE
Details II, paragraph 4.b(1),
(1) As indicated in the inspection report, documentation is availabic which verifies that the Oconee 1 pressurizer safety valves were properly adjusted by Dresser Industries, the valve manufacturer. Discussion with the supervisor involved in the replacement of the valves determined that a copy of PT/0/A/0200/29 was used and completed at that time. During the subsequent review and audit process, however, the completed procedure was misplaced. Consequently, the periodic test records and maintenance histories were not updated.
Reorganization of the station Maintenance Group in July of this year introduced a Planning Section, which has the responsibility for maintaining maintenance histories. Document transmittal controls are now in effect which require a document receipt signature when documents are received for permanent storage.
This method of handling should preclude similar occurrences in the future.
(2) OP/ /A/1102/01, Controlling Procodure for Unit Startup, has been revised to require that PT/ /A/0201/03, Core Flood System, be completed during each unit startup. This change will assure that the necessary testing is adequately documented.
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Ltr to Duke Pcwer Ccepany from !i. C. Moseley dated ggy g 7 jg74 RO Inspection Report ::cs. 50-269/74-10, 50-270/74-8 and 50-287/74-11 DISTRIBUTIC3:
H. D. Thornburg, RC RO:HQ (5)
Directorate of Licensing (13)
E C .% DR Central Files Regulatory Standards
- To be dispatched at a later date I
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