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| | number = ML20217C472 | | | number = ML20217C472 |
| | issue date = 07/11/1991 | | | issue date = 07/11/1991 |
| | title = Responds to NRC 910613 Ltr Re Violations Noted in Insp Repts 50-269/91-09,50-270/91-09 & 50-287/91-09.Corrective Actions: Inoperable Flow Transmitter Repaired & Crossover Flow Instrumentation on Two Units Checked | | | title = Responds to NRC Re Violations Noted in Insp Repts 50-269/91-09,50-270/91-09 & 50-287/91-09.Corrective Actions: Inoperable Flow Transmitter Repaired & Crossover Flow Instrumentation on Two Units Checked |
| | author name = Tuckman M | | | author name = Tuckman M |
| | author affiliation = DUKE POWER CO. | | | author affiliation = DUKE POWER CO. |
Line 11: |
Line 11: |
| | contact person = | | | contact person = |
| | document report number = NUDOCS 9107150332 | | | document report number = NUDOCS 9107150332 |
| | | title reference date = 06-13-1991 |
| | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE |
| | page count = 6 | | | page count = 6 |
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| ( ') or **%{' *s : } }J | | ( ') or **%{' *s : } }J |
| * rh-lo s l%ij outit Powen July 11, 1991 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Subject Oconee Nuclear Station Docket Nos. 50-269, -270, -287 Inspection Report 50-269, -270, -287/91-09 Reply to Notice of Violation Gentlemen , | | * rh-lo s l%ij outit Powen July 11, 1991 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Subject Oconee Nuclear Station Docket Nos. 50-269, -270, -287 Inspection Report 50-269, -270, -287/91-09 Reply to Notice of Violation Gentlemen , |
| By letter dated June 13, 1991, the NRC Jesued Inspection Report Nos. 50-269/91-09, 50-270/91-09 and 50-287/91-09 with a Notice of Violation. Pursuant to the provisions of 10 CFR 2.201, I am submitting a written response to the violation identified in the above Inspection Report. | | By {{letter dated|date=June 13, 1991|text=letter dated June 13, 1991}}, the NRC Jesued Inspection Report Nos. 50-269/91-09, 50-270/91-09 and 50-287/91-09 with a Notice of Violation. Pursuant to the provisions of 10 CFR 2.201, I am submitting a written response to the violation identified in the above Inspection Report. |
| I declare under penalty of perjury that the statements set forth herein are true and correct to the best of my knowledge. | | I declare under penalty of perjury that the statements set forth herein are true and correct to the best of my knowledge. |
| Very truly yours, | | Very truly yours, |
|
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20209H6921999-07-15015 July 1999 Forwards Comments on Preliminary Accident Sequence Precursor Analysis Provided in NRC Re Operational Condition Reported in LER 269/1998-04 ML20195H1681999-06-10010 June 1999 Forwards Copy of Preliminary ASP Analysis of Operational Condition Discovered at Ons,Units 1,2 & 3 on 980212 & Reported in LER 269/98-004,for Review & Comment ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20206E4101999-04-26026 April 1999 Forwards Four Copies of Rev 9 Todpc Nuclear Security & Contingency Plan,Per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 ML20205T1301999-04-0909 April 1999 Informs That on 990317,C Efin & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Y2K.Initial Exam Dates Scheduled for Wks of 000710 & 17 for Approx 13 Candidates ML20205B0571999-03-24024 March 1999 Informs That Author Determined That Partial Exemption from 10CFR170 Fee Requirements Appropriate for Footnote 4 of Review of License Renewal Application for Ons,Units 1,2 & 3, That Staff Determines Has Generic Value to Industry ML20207C0501999-02-25025 February 1999 Submits Annual Rept Specifying Quantity of Each of Principal Radionuclides Released to Environment in Liquid & Gaseous Effluents,Per 10CFR72.44(d)(3).Effluent Release from ISFSI for CY98 Was Zero ML20202J1901999-01-28028 January 1999 Discusses License Renewal for Operating Power Reactors.Two Applications Received for Renewing Operating Licenses. Commission Established Adjudicatory Schedule Aimed at Completing License Renewal Process in 30-36 Months ML20202H7621999-01-28028 January 1999 Discusses Guidance Re License Renewal for Operating Power Reactors Developed in Response to FY99 Energy & Water Development Appropriations Act Rept 105-581 ML20198S8721999-01-0707 January 1999 Responds to Message to Marks Re Info Request on Appeal Deadline & Desire to Serve Appeal Either by e-mail or by Alternative Regular Mail ML20198Q8871999-01-0707 January 1999 Responds to to Chairman SA Jackson Re Issues for Consideration for Commission During Oconee License Renewal Process.Commissioners Must Remain Impartial During Pendency of Case.Copy of Order LBP-98-33 Encl.Served on 990107 ML20198Q8971998-12-17017 December 1998 Expresses Concerns Re License Renewal of Duke Energy,Oconee Nuclear Station,Units 1,2 & 3.Commends NRC on Steps Agency Has Undertaken to Conclude Renewal Process.With Certificate of Svc.Served on 990107 05000269/LER-1998-012, Forwards LER 98-012-01,re RB Spray Pumps Being Declared Inoperable Due to Npsh.Rept Has Been Revised to Indicate Results of Testing & Corrective Actions Taken to Date1998-12-0303 December 1998 Forwards LER 98-012-01,re RB Spray Pumps Being Declared Inoperable Due to Npsh.Rept Has Been Revised to Indicate Results of Testing & Corrective Actions Taken to Date 05000269/LER-1998-013, Forwards LER 98-013-00 Re Condition Prohibited by Ts,Per 10CFR50.73(a)(1)(d).Circumstances & Causes for Event Have Not Been Fully Determined & Will Be Provided in Supplemental LER on or Before 9812021998-11-0202 November 1998 Forwards LER 98-013-00 Re Condition Prohibited by Ts,Per 10CFR50.73(a)(1)(d).Circumstances & Causes for Event Have Not Been Fully Determined & Will Be Provided in Supplemental LER on or Before 981202 ML20155D2651998-10-23023 October 1998 Expresses Appreciation for Supporting Commission Initiative in Issuing Recent Statement of Policy on Conduct of Adjudicatory Proceedings.Case-specific Orders Were Issued in Calvert Cliffs & Oconee License Renewal Proceedings ML20155B1481998-10-21021 October 1998 Informs That as Result of Discussion of Issues Re Recent Events in Ice Condenser Industry,Ice Condenser Mini-Group (Icmg),Decided to Focus Efforts on Review & Potential Rev of Ice condenser-related TS in Order to Clarify Issues ML20154B9421998-09-30030 September 1998 Amends Chattooga River Watershed Coalition Petition to Intervene in Proceedings Re Application of Duke Energy Corp to Renew OLs for Oconee Nuclear Station,Units 1,2 & 3 ML20154A8971998-09-30030 September 1998 Requests That Submitted Info Be Attached to Amends to Petition to Intervene in Proceedings Re Application of Duke Energy Corp to Renew Operating Licenses for Units 1,2 & 3 ML20153H6881998-09-27027 September 1998 Requests Consideration of Motion to Enlarge Time Required to Submit Amended Petition to Intervene in Proceeding Re Application of Duke Energy Corp to Renew OLs for Facilities ML20153E4721998-09-24024 September 1998 Forwards Notices of Appearances for Attorneys Representing Duke Energy Corp,Applicant in Proceeding for License Renewal of Oconee Units 1,2 & 3.With Certificate of Svc ML20153D1831998-09-17017 September 1998 Ack Receipt of of Duke Energy Co Inviting Reconsideration of Denial by NRC CFO of Duke Exemption Request from Annual Fee Requirements for General License Under 10CFR171.11(d) ML20151S7501998-08-31031 August 1998 Provides Update on Commitment Made by Licensee in Response to NOV & Imposition of Civil Penalty Re Valves in Ldst Instrument Lines That Were Incorrectly Translated Into Station Procedures ML20237B0871998-08-11011 August 1998 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 981007.Sample Registration Ltr Encl ML20236V9581998-07-27027 July 1998 Forwards Corrected Pages 3.5-30b of 961211 & 3.16-2 of 970205 TS Bases.Old Amend Numbers Were Left on Pages.Rev Changes Footer on Both Pages to Reflect Bases Changes ML20236P9451998-07-15015 July 1998 Forwards Emergency Response Data Sys Implementation Documents Including Data Point Library Updates for Oconee (Number 255),Dresden (Number 257) & Susquehanna (Number 258) ML20153D1961998-07-0909 July 1998 Requests NRC Reconsider & Grant Util Request for Exemption from Duplicative License Fee Under 10CFR171.11(d) for Storage of Spent Nuclear Fuel at Oconee Nuclear Station ML20236J9871998-06-24024 June 1998 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Entirety ML20247G0881998-05-14014 May 1998 Provides Rev 2 to Section 3.3, Instrumentation, in Support of TS-362 Amend Request.Position on Testing of Analog Trip Type Instruments W/Regard to Transition from CTS to ITS, Restated.Summary Description of Its/Bases Changes,Encl 05000269/LER-1998-002, Forwards LER 98-002-01 Re non-isolable Weld Leak on Pressurizer Surge Line Drain Pipe Which Resulted in Unit Shutdown1998-04-30030 April 1998 Forwards LER 98-002-01 Re non-isolable Weld Leak on Pressurizer Surge Line Drain Pipe Which Resulted in Unit Shutdown ML20217G0351998-03-26026 March 1998 Submits Ltr to Update Commitment Made by Oconee in Response to Subject Violation.Update Assures That Details of Particular CA Are Appropriately Contained in Docketed Correspondence ML20203J9301998-02-26026 February 1998 Submits Response to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. Suppl 1 to Bulletin Attached & Contains Listed Commitments ML20199J7441998-02-0202 February 1998 Responds to NRC Bulletin 96-004 for NUHOMS-24P Sf Storage Sys Used at Plant Site.Nrc Reviewed Response & Found Response to Be Acceptable ML20198K9321998-01-13013 January 1998 Ack Receipt of Requesting Exemption from 10CFR171 for ISFSI License SNM-2503 & General License Provisions of 72.214 ML20198M9361998-01-12012 January 1998 Responds to Request That rept,BAW-2303P,rev 3 Be Considered Exempt from Mandatory Public Disclosure.Determined That Info Sought to Be Withheld Contains Proprietary Commercial Info & Will Be Withheld from Public Disclosure ML20203C8481997-12-10010 December 1997 Forwards Emergency Response Data Sys Implementation Documents for Plants.W/O Encl 05000269/LER-1997-003, Forwards LER 97-003-01 Re post-LOCA Boron Dilution Design Basis Not Being Met.Rept Includes Updated Info & Revised Corrective Action1997-11-12012 November 1997 Forwards LER 97-003-01 Re post-LOCA Boron Dilution Design Basis Not Being Met.Rept Includes Updated Info & Revised Corrective Action ML20198Q5741997-11-0303 November 1997 Provides Suppl to Initial 971020 Application for Amend to TS Re SG Tubing Surveillance Requirements,In Response to NRC 971030 Request for Addl Info.Proprietary Rev 3 to BAW-2303P, OTSG Repair Roll Qualification Rept Encl.Rept Withheld ML20211P1591997-10-17017 October 1997 Ack Receipt of & Check for $330,000 in Payment for Civil Penalty.Corrective Actions Will Be Examined During Future Insp ML20217D7261997-10-0101 October 1997 Informs That Staff Intends to Use Working Draft SRP-LR as Aid in Reviewing License Renewal Submittals Received from Dpc,Other Licensees & Owners Groups.Policy Issues Will Be Referred to Commission for Resolution ML20211F7981997-09-25025 September 1997 Submits Response to Violations Noted in Insp Repts 50-269/97-10,50-270/97-10 & 50-287/97-10 & Proposed Imposition of Civil Penalty in Amount of $330,000.Corrective Actions:Ldst Instrument Mods on All Three Units Completed ML20217D9341997-09-22022 September 1997 Informs That NRC Staff Has Accepted Deferral of Completion of Certain Actions Requested by Bulletin 96-03, Potential of Plugging of ECCS Strainers by Debris in Boiling Water Reactor ML20211C8021997-09-18018 September 1997 Forwards Revised TS Amend Re Reactor Bldg Structural Integrity.Previously Submitted TSs Contained Editorial Error ML20210T7121997-09-0404 September 1997 Informs That Representatives from Oconee Who Compose LERs Would Like to Meet W/Staff & AEOD at Convenient Place & Time to Facilitate Process.Concerns Addressed in Encl ML20216G5821997-09-0404 September 1997 Informs That 970730 Submittal Re Oconee Nuclear Station, Units 1,2 & 3 Will Be Marked Proprietary & Being Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEC Act of 1954 IR 05000269/19970071997-08-27027 August 1997 Discusses Insp Repts 50-269/97-07,50-270/97-07,50-287/97-07, 50-269/97-08,50-270/97-08 & 50-287/97-08 on 970606 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $330,000 ML20210N1531997-08-13013 August 1997 Confirms 970807 Telcon Between J Burchfield & R Carroll Re Management Meeting to Be Conducted at Oconee Nuclear Station on 970922.Purpose of Meeting to Discuss Oconee Emergency Power Project Initiatives ML20210M8381997-08-13013 August 1997 Confirms Conversation Between J Burchfield & R Carroll on 970807 Re Mgt Meeting to Be Conducted in Region II Ofc on 971113.Meeting to Discuss Status of Plant Performance Improvement Initiatives ML20210N1121997-08-12012 August 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 971008. Facililty Must Submit Either Ltr Indicating No Candidates Scheduled to Participate or Listing Names of Candidates ML20149J4841997-07-21021 July 1997 Forwards Addl Pages to Rev 5 to Duke Power Co Nuclear Security & Contingency Plan. Encl Withheld 1999-08-10
[Table view] Category: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 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 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 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 ML20108C7031996-04-18018 April 1996 Forwards Public Version of Rev 96-03 to Vol B of Epips, Including Cover Sheet,Table of Contents Page 1,change 7 to CP/1&2/A/2002/05 & Change 6 to CP/3/A/2002/05 1999-07-15
[Table view] |
Text
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- rh-lo s l%ij outit Powen July 11, 1991 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Subject Oconee Nuclear Station Docket Nos. 50-269, -270, -287 Inspection Report 50-269, -270, -287/91-09 Reply to Notice of Violation Gentlemen ,
By letter dated June 13, 1991, the NRC Jesued Inspection Report Nos. 50-269/91-09, 50-270/91-09 and 50-287/91-09 with a Notice of Violation. Pursuant to the provisions of 10 CFR 2.201, I am submitting a written response to the violation identified in the above Inspection Report.
I declare under penalty of perjury that the statements set forth herein are true and correct to the best of my knowledge.
Very truly yours,
- k. h.
M. S. Tuckman, Vice President Nuclear Operations rnov710.lbj xc: S. D. Ebneter Regional Administrator, Region II L. A. Wiens, ONRR NRC Resident Inspector Oconee Nuclear Station i
9107150332 910711 PDR ADOCK 05000269
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/ I I J Q PDR
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VIOLATION J t27 0 2 87 / 91- 09-01) , SEVERITY LEVEL _{1111 Technical Specification 3.3.1.c(1) requires valves llP-409 and
!!P-410 to be operable whenever reactor power is greater than 60 percent of f ull power. Technical Speci fication 3.3.1.c(2 ) requires that if the above valves are inoperable and are not restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, reactor power shall be reduced to below 60 percent of full power within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Technical Specifications define operable as all essential instrumentation required in order to assure performance of the saftty functions being capable of performing its related support functions.
Contrary to the above, valves 311P-409 and 211P-410 were inoperable for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> as described below, and during numerous periods of reactor operations reactor power was not reduced below 60 percent of full power within an additional 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:
- 1. Valve 311P-409 was inoperable from May 1984 until March 1991, due to the fact that the liigh Pressure Injection crossover flow instrument to the "B" liigh Pressure Injection lloader was inoperable as a result of modifications to the flow instrumentation that resulted in the impulse lines being reversed.
- 2. Volvo 211P-410 was inoperable f rom initial installation in 1980 until March 1991 due to the fact that the :ligh Pressure Injection crossovor flow instrument to the "A" High Pressure Injection header was inoperable as a result of the orifice plate in the flow elemunt being installed in the reverso direction.
RESPONSE TO 311P-409 PROBLEM:
- 1. Reason for the violation:
Valve 311P-409 was considered to have been inoperable because indications would have shown no flow through 311P-409, potentially preventing safety functions from being adequately performed if this backup line had to be used.
The violation occurred due to insufficient post modification testing. In May 1984, a flow test was not specified to be performed as part of Nuclear Station Modification (NSM) ON-1782 Part u, which replaced the llPI crossover flow instrumentation and impulse lines.
~',' .
NRC Violation Rosponso P'ge Two In November 1988, Oconee's current Post Modification Testing program was implemented. The program requires testing to be performed that verifles proper installation / operation and verifies that the installed NSM performs as intended according to its desigli.
In March, 1991 it was discovered that the lupulse lines cad boon reversed during 1984. This discovery was the result of NSM ON-32589 being performed, which specified that as part of the post modification testing following the installation, flow would be established through.each crossover loop.
- 2. The corrective stops which have been taken and the results achieved:
The inoperable flow transmitter was repaired by reversing the :
lines betwoon the manifold and the transmitter. ,
The transmitter was verified operable by the performance of a positive flow test.
The crossover flow instrumentation on the other two units was checked and the impulse lines were found to be tubed correctly, in addition, an evaluation was made concerning what other saf ety-significant instrumentation could be susceptible to
-this kind of-error. Because actual use of instrumentation immediately reveals- " rolled" tubing connectiona, safety-significant instrumentation which is not used during routino operation or testing was identified. The Standby Shutdown Facility-(SSF) Auxiliary Servict Water (ASW) flow instruments -
for the two steam generators en each unit woro identified as tha - only safety-significant _ instrume.itation which is not actually used during operation- or testing. All tubing connections on the SSF ASW flow instrumentation were physically verified on all three units. No tubing errors or other problems woro found.
3._ Corrective steps that will be taken to avoid further violations:
Unita 1 and 2 crossover flow instrumentation will be positive flow tested as_part of the Post-Modification Testing program Jn the next outage in which the instrumentation on these units will also be upgraded to Laprove accuracy. The current Post Maintenan00 end Modification Testing programs, as upgraded in 1988, require testing or other verifications which would identify this type of problem before returning equipment to serv 1Co.
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NRC Violation Responso Pago Threo
- 4. Dato when full compitance wil] be achieved:
Full ,; mplianco has been achiaved through the actions listed in (1) and (2). As an additional verification, flow testing of the Unit 1 and 2 IIPI crossover instrumontation will bo performed as follows:
-Unit 1 crossover flow instrumentation will be tostod during the End of Cycle 13 Refuelirag Outage (scheduled to begin August 1, 1991) ,
l Unit 2 crossover flow institumentatioti will be tested during l the End of Cyclo 12 Refueling Outage (scheduled to begin January 2, 1992) e RESPONSE TO 211P-410: ,
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- 1. Reason for the violation:
Valvo 211P-410 was consirfored to have boon inoperable because the indicated flow would have been loss than actual, so that runout protection for the High Pressure Injection pump might not have boon adequcto, if this backup lino had to be used.
The violation is the result of personnel error. In 1980, under. Nuclear Station Modification (NSM) ON-1080 Part A, the orifice plato was installed in the reverso direction. The procedure used for tho installation contained a sign-of f stop that stated, " Instal). orifico platos in proper direction of flow and in accorda"tco with MP/0/A/1800/3, Replacement of Caskets in Flanges". However, tho method for determining the
--proper direct 'on of flow was not included in the procedure.
The step was t.gned of f by the craf t supervisor. The step was followed by a Quality Control verification that the flango was installed correctly.
- 2. The corrective steps which have.been taken and the results achieved:
Design Engineering. performed an operability evaluation based L on calculation 05C-4323. This evaluation showed that by limiting indicated flow to 300 gpm all requirements would be mot even with tho flow orifice reversed.
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i NRC Violation Response Page Four The Emergency Operating Procedure was revised to limit the maximum indicated flow through the 'A' crossover loop to 300 gallons per minute. Operators wore given training on this change.
An identical oritice was fabricated and testod to obtain flow data in order to confirm the operability evaluation.
All other accesssible safety-signJficant flow orifices were inspecteo for. proper orientation. Three additional errors were discovered: Unit 1 'B' Reactor Building Spray (RBS) flow orifice, Unit 2 'B' RBS flow orifice, Unit 2 'B' Emergency Feedwater (EFW) flow orifice. The 1 'B' and 2 'B' RBS flow I orifices ware corrected. An operability evaluation was performed for the 2 'D' EFW flow orifice. It was found to be operable, as the of fect upon indicated flow would not be large enough to af fect the flow -instruments safoty functions. Three remaining safety-related orifices (for the SSF Reactor Coolant i flow on each unit)
Makeup (RCMU) located in the Reactor Building will be inspected during the next outage of suf ficient length. If an SSF RCMU flow orifice were reversed, it would not prevent the system from performing _its safety-function.
- 3. Corrective steps that will be taken to avoid further violations:
- a. The reversed HPI flow ort.fice will be reinstalled in the correct position during the next outage - of sufficient duration.
- b. The reversed EFW flow crifice will be reinstalled in the correct position during the f. ext outage of sufficient duration. In addition, the orifice will be inspected for degradation before reinstalling.
- c. The three remaining safety-related flow orifices (one per unit) will be inspected to ensure correct installation.
- d. Maintenance personnel having responsibility- for installation of orifices will be trained on the importance of proper incta11ation and given training concerning the installation of basic types of orifices i emphasizing the guidelines set forth in NRC Information l
Notice 90-65.
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- e. The Nuclear Station Modification Program will be revised to ensure that . procedures to install orifice plates include instructions that define the direction of flow within the piping.
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NRC Violation.Rosponso Page Fivo
- 4. Dato when full compliance will be ach.ioved
- a. Thee Unit 2 llPI flow orifico will be reinstalled in the correct position before complot. ion of the End of Cyc)o 12 Itofueling Outage (scheduled to begin January 2, 1992).
- b. The Unit 2 EFW flow orifice will be checked for degradation and reinstalled in the correct position bef oro completion of the End of Cyclo 12 Ref ueling Outago (scheduled to uogin January 2, 1992),
- c. The S3F RCMU flow orificos (eno por bnit) will be inspected before completion of the next refueling outage Unit 1 EOC 13 Refueling Outage - scheduled to begin August. 1, 1991 Unit 2 EOC 12 Refueling Out. age - scheduled to begin January 2, 1992 Unit 3 EOC 13 Refueling Outage - scheduled to begin June 4, 1992
- d. Maintenanco personnel responsiblo for orifico installation will be trained by December 31, 1991,
- o. The NSM program will be revised by December 1, 1991 to provido ins t ruc t. ions concerning orifico plate installation and flow direction within the piping.
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