ML20150B182
Letter Sequence Other | |
---|---|
Initiation
Questions
Results
Other: 0CAN048804, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant, 3F0288-18, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-420, A07039, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage, BECO-88-050, Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-001, ML20147F998, ML20147G854, ML20148A890, ML20148B666, ML20148K225, ML20148Q724, ML20149M198, ML20150A899, ML20150B182, ML20150B526, ML20150C407, ML20150D397, ML20151A945, ML20151B202, ML20151E018, ML20151E419, ML20151E868, ML20151G115, ML20151G791, ML20151H779, ML20151H965, ML20151Q920, ML20154D233, ML20154E154, ML20155A456, ML20155E392, ML20196H353, ML20205P688, ML20235J165, ML20235J168, ML20236A614, ML20236A849, ML20236D105, ML20236F547, ML20236S018, ML20247K075, NRC-88-0072, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers, RBG-27645, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant, W3P88-0051, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin | |
MONTHYEARML20235S2971987-10-0202 October 1987
[Table View]Summary of 870923 Meeting W/Westinghouse Re Technical Basis for Westinghouse Recommended Actions,Criteria & Conclusions in to Utils That Use Models DS-416,DSL-416, DS-420,DS-206 & DSL-206 Switchgear in Class 1E Svc Project stage: Meeting ML20236A6141987-10-16016 October 1987 Advises That Util Insp of Reactor Trip Breakers Revealed Catawba Pole Shaft Which Had Welds W/Indications of Cracking.Forwards Informal Technical Communication from Franklin Research Ctr Re Initial Observation Project stage: Other ML20236A8491987-10-16016 October 1987 Forwards I.6177-5-1, Interim Rept on McGuire Reactor Trip Breaker 2B Failure Evaluation & Rcommended Corrective Actions from Westingtonhouse. Rept Explains Mechanical Binding Which Kept Breaker from Opening on 870702 Project stage: Other ML20236D1051987-10-21021 October 1987 Provides Record of 871020 Telcon Between D Hood,D Sellers & V Hodge of NRC & J Mcvicker & Cowne of Bg&E Re Unit 1 480 Volt Circuit Breaker W/Broken Weldment Connecting Ctr Pole Lever to Pole Shaft.Util Exam Results in 860918 Memo Project stage: Other ML20236F5471987-10-23023 October 1987 Documents 871020 Telcon W/Util Re Unit 2 Circuit Breaker Pole Shaft Weld Failure Project stage: Other ML20236F9651987-10-27027 October 1987 Notification of 871103 Meeting W/Util & Westinghouse in Philadelphia,Pa to Discuss Results of Franklin Research Ctr Exam of Cracks in Pole Shaft Welds of Reactor Trip Breaker Project stage: Meeting ML20236S0181987-11-18018 November 1987 Summarizes 871020 Telcon Between NRC & Util Re Two Broken Fillet Welds on Pole Shaft Assembly of Circuit Breaker That Energizes Emergency Fire Protection Pumps for Facility. Photographs Attached to 870710 Memo to NRC Encl Project stage: Other ML20149M1981988-02-16016 February 1988 Advises That Since Util No Longer Operating Reactor Licensee Due to 870430 Shutdown & 870804 Amend,Modifying License DPR-45 to Possess But Not Operate Status,Generic Ltr 88-01 Determined Inapplicable to Facility Project stage: Other 3F0288-18, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-4201988-02-23023 February 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-420 Project stage: Other ML20196H3531988-02-25025 February 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Westinghouse Ds Series Circuit Breakers Installed at Facility Project stage: Other ML20147G8541988-03-0101 March 1988 Responds to NRC Bulletin 88-001 Re Westinghouse Ds Series Circuit Breakers Used in safety-related Applications.Plant Does Not Have Any Westinghouse Ds Series Circuit Breakers Project stage: Other ML20147F9981988-03-0404 March 1988 Submits Response to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Author Does Not Utilize Any Westinghouse Circuit Breakers,As Identified in Subj Bulletin,In Class 1E Applications at Facility Project stage: Other ML20150B1821988-03-0707 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breakers in Class 1E Applications So Bulletin 88-001 Does Not Apply to Plant Project stage: Other ML20148A8901988-03-0707 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Unit 1 Has No Westinghouse Ds Circuit Breakers Used in Class 1E Application.Unit 2 Reactor Trip & Bypass Breakers Insp Initiated Per Info Notice 87-035 Project stage: Other ML20150A8991988-03-0909 March 1988 Provides Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Determined That Westinghouse Series Ds Circuit Breakers Not Employed at Plant.Insp Required by Bulletin Not Applicable to Plant Project stage: Other ML20150C4071988-03-11011 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Determined That Westinghouse Type Ds Circuit Breakers Not Used at Plant Project stage: Other BECO-88-050, Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-0011988-03-15015 March 1988 Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-001 Project stage: Other ML20148B6661988-03-16016 March 1988 Responds to 880205 NRC Compliance Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Westinghouse Ds Series Circuit Breakers Not Used in Class IE Svc at Plant Project stage: Other NRC-88-0072, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers1988-03-24024 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers Project stage: Other ML20148K2251988-03-25025 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Two Reactor Trip Breakers & Two Reactor Trip Bypass Breakers Subj to Bulletin Used at Millstone Unit 3.Main Pole Shaft Weld Insps Completed by 880225 Project stage: Other ML20151G7911988-03-28028 March 1988 Confirms That Westinghouse Ds Breakers Not Used at Facility, Per IE Bulletin 88-001, Defects in Westinghouse Circuit Breakers Project stage: Other W3P88-0051, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin1988-03-29029 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin Project stage: Other ML20151A9451988-03-30030 March 1988 Responds to IE Bulletin 88-001 Re Westinghouse Ds/Dsl Circuit Breakers.Ref Components Not Utilized at Facility Project stage: Other 0CAN048804, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant1988-04-0101 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant Project stage: Other ML20151B2021988-04-0404 April 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Insp of All Westinghouse DS-415 Reactor Trip & Bypass Breakers Completed on 880308 & Results Encl Project stage: Other RBG-27645, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant1988-04-0404 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant Project stage: Other ML20148Q7241988-04-0707 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Westinghouse Models DS-206,DSL-206, DS-416,DSL-416 or DS-420 Breakers in Class 1E Circuits at Hatch Project stage: Other ML20151H7791988-04-0707 April 1988 Informs That Westinghouse Ds Circuit Breakers Not Utilized in Any 1E Application at Plant But Used in non-1E Applications & Will Be Included in Util Preventive Maint Program Project stage: Other ML20151E4191988-04-0808 April 1988 Responds to 880205 NRC Bulletin 88-01 Re Defects in Westinghouse Circuit Breakers for Facilities.Westinghouse Ds Series Circuit Breakers Not Used at Plants.Other Provisions of Bulletin Do Not Apply to Plants Project stage: Other ML20151E8681988-04-11011 April 1988 Forwards Response to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers in Class 1E Svc.All Required long-term & short-term Insps Completed Project stage: Other ML20151H9651988-04-13013 April 1988 Responds to NRC Bulletin 88-001, Deficiencies in Westinghouse Circuit Breakers. Bulletin Addresses Deficiencies Exclusive to Westinghouse Ds/Dsl Type Circuit Breakers & Outlines Specific Insps to Be Performed Project stage: Other ML20151G1151988-04-13013 April 1988 Ack Receipt of in Response to NRC Bulletin 88-001 Re Westinghouse Circuit Breakers.Plant Does Not Use or Plan Use of Circuit Breakers,Therefore Matter Closed Project stage: Other ML20205P6881988-04-20020 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Circuit Breakers Subj to Bulletin Installed in Plant Project stage: Other ML20155E3921988-06-0909 June 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit breakers.Sixty-six of sixty-seven Breakers Required New Pole Shafts Due to Failure of Welds to Meet Bulletin Requirements Resulting from Insp Project stage: Other ML20150B5261988-06-30030 June 1988 Informs That All Class 1E DS-416 Breakers Now in Use Comply W/Nrc Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers Project stage: Other ML20150D3971988-07-0505 July 1988 Advises That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20151E0181988-07-14014 July 1988 Advises That Util 880407 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20151Q9201988-08-0202 August 1988 Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20154D2331988-09-0909 September 1988 Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory & No Further Reply Necessary Project stage: Other ML20154E1541988-09-0909 September 1988 Advises That 880408 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20155A4561988-09-29029 September 1988 Requests Addl Info Re Util 880908 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Response Requested within 70 Days of Ltr Date Project stage: Other ML20235J1681989-02-17017 February 1989 Advises That 880314 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers Satisfactory. Westinghouse Ds Series Circuit Breakers Not Used in safety-related Applications at Plant Project stage: Other ML20235J1651989-02-17017 February 1989 Provides Final Response to NRC Bulletin 88-001, Defects in Westinhouse Circuit Breakers. Alignment Check Specified in 871201 Submittal Satisfactorily Performed During Installation of Replacement Pole Shaft in Breakers Project stage: Other ML20247C7191989-05-15015 May 1989 Forwards Supplemental Response to NRC Bulletin 88-001 Re Westinghouse Series Ds Circuit Breakers.Insp Info Corrected Project stage: Supplement ML20247K0751989-05-24024 May 1989 Responds to NRC Bulletin 88-001 Re Defects of Westinghouse Circuit Breakers.All forty-seven Westinghouse Type Ds Breakers Inspected Were Found to Have Acceptable Breaker Mechanism Alignment Project stage: Other A07039, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage1989-07-24024 July 1989 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage Project stage: Other 1988-03-07 |
ML20150B182 | |
Person / Time | |
---|---|
Site: | Oconee |
Issue date: | 03/07/1988 |
From: | Tucker H DUKE POWER CO. |
To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
References | |
IEB-88-001, IEB-88-1, TAC-65955, TAC-65956, NUDOCS 8803160218 | |
Download: ML20150B182 (1) | |
Similar Documents at Oconee | |
---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20211B7881999-08-10010 August 1999
[Table view]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 Category:INCOMING CORRESPONDENCE MONTHYEARML20209H6921999-07-15015 July 1999
[Table view]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 Category:UTILITY TO NRC MONTHYEARML16259A2391990-08-22022 August 1990
[Table view]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 |
Text
c.
e, e DuxE POWER GOMPANY c P.O. BOX 03189 CHARLOTTT1. N.O. 98949 l HALB.TUCKEN Tatsenows -
exa resoconut (704) 073 4838 staraan enoe.wrion
-l March 7, 1988
, U.S.' Nuclear Regulatory Conunission Document Control Desk Washington, D.C. 20555
Subject:
Oconee Nuclear Station Docket Nos. 50-269, -270, -287 NRC Bulletin No. 88-01 TACS 65955/65956 i
Gentlemen: ;
l The following information is in response to NRC Bulletin No. 88-01 dated Febru- l ary 5, 1988 concerning defects in Westinghouse circuit breakers. Oconee Nuclear i Station does not use Westinghouse DS circuit breakers in Class IE applicstions. [
l As such, Bulletin 88-01 does not apply to Oconee Nuclear Station.
I declare under penalty of perjury that the statements set forth herein are true ano correct to the best of my knowledge.
Very truly yours, I
a d. - - - I .
L i Hal B. Tucker i i PJN/300/j ge .
I Attachment l
1 xc: Dr. J. Nelson Grace, Regional Administrator i U.S. Nuclear Regulatory Commission - Region II l
- 101 Marietta St. NW l' Suite 2900 - Atlanta, GA 30323
. l j Ms. Helen Pastis Office of Nuclear Reactor Regulation f j U.S. Nuclear Regulatory Commission i
- j. . Washington, D.C. 20555 ,
4 l Mr. P.H. Skinner 1 NRC Resident Inspector t
Oconee Nuclear Station i s
8G03160218 880307 8 0 PDR ADOCK 05000269 l t
i O DCD .
~ l
, _ _ _ _ . - _ .- - - - - --