|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217E9711999-10-13013 October 1999 Submits Notification of Major Changes to Trojan Liquid Radioactive Waste Treatment Sys,Iaw PGE-1201.Detailed Description of Change Provided ML20217C8171999-10-0606 October 1999 Forwards Notice of Receipt of Availability for Comment & Meeting to Discuss License Termination Plan,Per 990805 Application ML20216F7621999-09-23023 September 1999 Forwards Corrected Response to Request 2 Contained in NRC 990920 RAI Re Application of Pacificorp for Transfer of License NPF-1.Response 2 Should Have Stated That Na General Partnership Is Partnership Formed in Nv ML20216F2871999-09-20020 September 1999 Informs NRC of Developments That Have Occurred Since 990524 Application Was Filed Re Pacificorp Transfer of License of FOL NPF-1.NRC Is Urged to Act & Approve Transaction Expeditiously by 990930.Supporting Documentation Encl ML20211Q3281999-09-0909 September 1999 Forwards Insp Rept 50-344/99-06 on 990630-0701,21 & 0408-08. No Violations Noted.Insp Conducted to Review Decommissioning Activities Underway at Trojan Site & to Accompany Shipment of Reactor Vessel to Hanford,Washington for Burial ML20211J2101999-08-30030 August 1999 Forwards Request for Addl Info Re Application for Approval of Proposed Corporate Merger of Pacificorp & Scottishpower ML20211B6611999-08-16016 August 1999 Forwards fitness-for-duty Program Performance Data Rept for Period of 990101-0630,IAW 10CFR26.71(d) ML20211B4091999-08-16016 August 1999 Forwards Environ Assessment & Finding No Significant Impact to Application for an Exemption & License Amend Dated 980129.Proposed Exemption & License Amend Would Delete Security Plan Requirements of 10CFR50.54(p) & 10CFR73.55 ML20211A7131999-08-16016 August 1999 Forwards Environ Assessment & Finding of No Significant Impact to Application for Exemption & License Amend Dtd 980827.Proposed Exemption & License Amend Would Delete EP Requirements of 10CFR50.54(q),10CFR50.47(b) & 10CFR50,app E ML20210R7691999-08-11011 August 1999 Forwards Proposed Rev 23 to PGE-8010, Trojan Nuclear QAP, in Response to NRC 990708 RAI Re Relocation of TS ACs to Qap.Revised QAP Will Be Made Effective Concurrently with Implementation of License Change Application Lca 245 ML20210H5971999-07-27027 July 1999 Forwards Notice of Consideration of Approval of Application Re Merger & Opportunity for Hearing.Notice Being Forwarded to Ofc of Fr for Publication ML20216D6611999-07-23023 July 1999 Submits Summary of Proprietary Submittals for Transtor Part 71 & Part 72 & Trojan ISFSI Applications ML20210F8601999-07-22022 July 1999 Forwards Rev 1 to PGE-1076, Trojan Reactor Vessel Package Sar. Changes to Rept Contained in Rev 1 Received NRC Approval by Ltr ML20210A6401999-07-19019 July 1999 Corrects Ref in Item 4 of Which Constitutes Rev 2 of Authorization from Wf Kane, for Trojan Reactor Vessel Package as Approved Package for Shipment Under General License,Subj to Listed Conditions ML20210B4481999-07-12012 July 1999 Forwards Rept Describing Effects of Earthquake That Occurred on 990702 Near Satsop,Wa,Iaw Trojan Nuclear Plant Defueled Sar,Section 4.1.3.1 ML20209D6231999-07-0808 July 1999 Forwards RAI Re Licensee 980827 Request for Amend That Would Delete Number of License Conditions & TS Requirements That Would Be Implemented After All Sf Has Been Removed from 10CFR50 Licensed Area.Response Requested within 30 Days ML20209C6481999-07-0606 July 1999 Forwards Rev 8 to Defueled Sar,Including Changes Since Last Submittal.Attachment Includes Brief Description of Each Change Included in Rev ML20209B7821999-07-0101 July 1999 Responds to NRC 990609 RAI Re License Change Application 244 & Accompanying Request for Exemption.Detailed Info Supports Estimation of Remaining Radioactive Matl Previously Provided by Licensee ML20212J3281999-06-15015 June 1999 Forwards Amend 22 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, IAW 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities & Does Not Reduce Effectiveness of Fire Protection ML20195J0111999-06-0909 June 1999 Responds to Requesting License & Exemption Re Emergency Preparedness ML20207D3861999-06-0101 June 1999 Forwards Rev 1 to PGE-1077, Trojan Nuclear Plant Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20196L1251999-05-24024 May 1999 Forwards Application for Amend to License NPF-1 for Indirect Transfer of License,To Extent That Such Approval Required Solely to Reflect Change in Upstream Economic Ownership of Pacificorp ML20207A2751999-05-14014 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created.Organization Chart Encl ML20206N9411999-05-11011 May 1999 Forwards Revised Epips,Including Rev 7 to EPIP 3, Response Organization Checklists & Rev 9 to EPIP 5, Emergency Preparedness Test Propgram. Changes to EPIPs 3 & 5 Ref New Owners of on-site Railroad Line,Portland & Western Railroad ML20206J8681999-05-0707 May 1999 Forwards Insp Repts 50-344/99-05 & 72-0017/99-04 on 990419-22.No Violations Noted.Insp Observed Work Activities Associated with Lifting of Reactor Vessel in Preparation for Removal & Shipment to Hanford Reservation for Burial ML20206J7931999-05-0707 May 1999 Forwards Insp Repts 50-344/99-04 & 72-0017/99-02 on 990322- 25 & 29-0408.One Violations Identified & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20206H4331999-05-0505 May 1999 Forwards Amend 201 to License NPF-1 & Se.Amend Revises PDTSs by Deleting ISFSI Area,Revises Subsection 4.1.1,replaces Figure 4.1-1 with New Figure 4.1-1 & Adds New Page to Figure 4.1-1 to Reflect Access Control (ISFSI) Area ML20206N1571999-05-0404 May 1999 Forwards Util Quarterly Decommissioning Status Rept for First Quarter of 1999,IAW State of or Energy Facility Siting Council Order Approving Trojan Decommissioning Plan, ML20206E1731999-04-29029 April 1999 Informs That NRC Staff Has Performed an Acceptance Review of Trojan Nuclear Plant License Termination Plan,Submitted by ,To Determine Whether LTP Provides Adequate Info to Allow Staff to Conduct Detailed Review ML20206E0211999-04-28028 April 1999 Forwards Copy of Environ Assessment & Finding of No Significant Impact Re 970212 Application for Amend.Proposed Amend Would Revise Trojan Permanently Defueled TS to Delete ISFSI Area ML20206C9591999-04-23023 April 1999 Forwards Amend 200 to License NPF-1 & Safety Evaluation. Amend Changes License NPF-1 by Revising License Condition 2.C.(10), Loading of Fuel Into Casks in Fuel Building ML20206C9221999-04-23023 April 1999 Forwards Amend 199 to License NPF-1 & Safety Evaluation. Amend Changes License NPF-1 by Adding New License Condition Entitled, Loading of Fuel Into Casks in Fuel Building ML20205S9761999-04-21021 April 1999 Forwards Trojan Nuclear Plant,Radiological Environ Monitoring Rept for CY98. Rept Submitted in Accordance with Trojan Permanently Defueled TS 5.8.1.2 & Sections IV.B.2, IV.B.3 & Iv.C of App I to Title 10CFR50 ML20205T5471999-04-20020 April 1999 Forwards Insp Repts 50-344/99-03 & 72-0017/99-03 on 990301-04,15-18 & 22-25.No Violations Noted ML20205N9061999-04-13013 April 1999 Forwards Insp Rept 50-344/99-02 on 990329-0401.No Violations Noted.Inspectors Examined Portions of Physical Security, Access Authorization & FFD Programs ML20205P7301999-04-0808 April 1999 Forwards PGE-1009-98, Operational Ecological Monitoring Program for TNP,Jan-Dec 1998, Including All Existing non-radiological Effluents ML20205B3661999-03-25025 March 1999 Transmits Completed Application for Renewal of NPDES Permit for Trojan Nuclear Plant,Iaw License NPF-1,App B,Epp,Section 3.2 ML20204G1781999-03-18018 March 1999 Forwards Rev 4 to PGE-1063, Suppl to Applicants Environ Rept - Post Operating License Stage ML20204B7551999-03-18018 March 1999 Forwards Updated TS 5.6 Re High Radiation Area,Per Telcons with Nrc.Justification for TS Was Provided Previously with Util Ltr Dtd 990317,but Has Been Updated & Is Included as Encl 2 ML20204C5151999-03-17017 March 1999 Forwards Licensee Comments on NRC Preliminary SER & License Re Trojan Isfsi.Encl Includes Justification for Inclusion in ISFSI TS of Alternative Method to 10CFR20.1601(c) for Controlling Access to High Radiation Areas ML20207J3721999-03-10010 March 1999 Forwards License Amend Application 247 Requesting Amend to License NPF-1 to Add License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan, Also Encl.With Certificate of Svc ML20207L0011999-03-0808 March 1999 Transmits Tnp co-owners Annual Rept of Status of Decommissioning Funding for Tnp.Rept Is Based on Most Recent Analysis of Tnp Decommissioning Estimate & Funding Plan,Per Rev 6 to Pge, Tnp Decommissioning Plan ML20207G9691999-03-0303 March 1999 Forwards Rev 6 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Summary of Changes,Attached.Revised Portions Denoted by Side Bars ML20207D7751999-03-0202 March 1999 Forwards Amend 21 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, Per 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities ML20207B0441999-02-24024 February 1999 Forwards Endorsements 139 to Nelia Policy NF-0225 & 2 to Nelia Policy NW-0602 ML20207J0701999-02-11011 February 1999 Forwards Proposed Ts,Update to ISFSI SAR & Revised Calculation,Per Application for Trojan ISFSI License ML20202G4291999-02-0202 February 1999 Forwards Rev 0 to PGE-1076, Trojan Reactor Vessel Package Sar. Approval,With Certain Conditions,For one-time Shipment of Trojan Reactor Vessel Package Granted by Commission Via Ltr ML20202G0931999-01-26026 January 1999 Submits Following Info That Will Be Needed for NRC Staff to Complete Review & Issue Trojan ISFSI License,As Result of 990121 Meeting with NRC Following Insp & Observation of ISFSI Preoperational Testing During Wk of 990118 ML20202F2551999-01-25025 January 1999 Forwards Fitness for Duty Program Performance Data Rept for July-Dec 1998 ML20202C1621999-01-21021 January 1999 Forwards Insp Repts 50-344/98-04 & 72-0017/98-01 & NOV Re Inadequate Actions Taken by Radiation Protection Technician to Ensure That Radiological Conditions Safe Prior to Removing Warning Signs for Airborne Radioactivity Area 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217E9711999-10-13013 October 1999 Submits Notification of Major Changes to Trojan Liquid Radioactive Waste Treatment Sys,Iaw PGE-1201.Detailed Description of Change Provided ML20216F7621999-09-23023 September 1999 Forwards Corrected Response to Request 2 Contained in NRC 990920 RAI Re Application of Pacificorp for Transfer of License NPF-1.Response 2 Should Have Stated That Na General Partnership Is Partnership Formed in Nv ML20216F2871999-09-20020 September 1999 Informs NRC of Developments That Have Occurred Since 990524 Application Was Filed Re Pacificorp Transfer of License of FOL NPF-1.NRC Is Urged to Act & Approve Transaction Expeditiously by 990930.Supporting Documentation Encl ML20211B6611999-08-16016 August 1999 Forwards fitness-for-duty Program Performance Data Rept for Period of 990101-0630,IAW 10CFR26.71(d) ML20210R7691999-08-11011 August 1999 Forwards Proposed Rev 23 to PGE-8010, Trojan Nuclear QAP, in Response to NRC 990708 RAI Re Relocation of TS ACs to Qap.Revised QAP Will Be Made Effective Concurrently with Implementation of License Change Application Lca 245 ML20216D6611999-07-23023 July 1999 Submits Summary of Proprietary Submittals for Transtor Part 71 & Part 72 & Trojan ISFSI Applications ML20210F8601999-07-22022 July 1999 Forwards Rev 1 to PGE-1076, Trojan Reactor Vessel Package Sar. Changes to Rept Contained in Rev 1 Received NRC Approval by Ltr ML20210B4481999-07-12012 July 1999 Forwards Rept Describing Effects of Earthquake That Occurred on 990702 Near Satsop,Wa,Iaw Trojan Nuclear Plant Defueled Sar,Section 4.1.3.1 ML20209C6481999-07-0606 July 1999 Forwards Rev 8 to Defueled Sar,Including Changes Since Last Submittal.Attachment Includes Brief Description of Each Change Included in Rev ML20209B7821999-07-0101 July 1999 Responds to NRC 990609 RAI Re License Change Application 244 & Accompanying Request for Exemption.Detailed Info Supports Estimation of Remaining Radioactive Matl Previously Provided by Licensee ML20212J3281999-06-15015 June 1999 Forwards Amend 22 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, IAW 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities & Does Not Reduce Effectiveness of Fire Protection ML20207D3861999-06-0101 June 1999 Forwards Rev 1 to PGE-1077, Trojan Nuclear Plant Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20196L1251999-05-24024 May 1999 Forwards Application for Amend to License NPF-1 for Indirect Transfer of License,To Extent That Such Approval Required Solely to Reflect Change in Upstream Economic Ownership of Pacificorp ML20206N9411999-05-11011 May 1999 Forwards Revised Epips,Including Rev 7 to EPIP 3, Response Organization Checklists & Rev 9 to EPIP 5, Emergency Preparedness Test Propgram. Changes to EPIPs 3 & 5 Ref New Owners of on-site Railroad Line,Portland & Western Railroad ML20205S9761999-04-21021 April 1999 Forwards Trojan Nuclear Plant,Radiological Environ Monitoring Rept for CY98. Rept Submitted in Accordance with Trojan Permanently Defueled TS 5.8.1.2 & Sections IV.B.2, IV.B.3 & Iv.C of App I to Title 10CFR50 ML20205P7301999-04-0808 April 1999 Forwards PGE-1009-98, Operational Ecological Monitoring Program for TNP,Jan-Dec 1998, Including All Existing non-radiological Effluents ML20205B3661999-03-25025 March 1999 Transmits Completed Application for Renewal of NPDES Permit for Trojan Nuclear Plant,Iaw License NPF-1,App B,Epp,Section 3.2 ML20204G1781999-03-18018 March 1999 Forwards Rev 4 to PGE-1063, Suppl to Applicants Environ Rept - Post Operating License Stage ML20204B7551999-03-18018 March 1999 Forwards Updated TS 5.6 Re High Radiation Area,Per Telcons with Nrc.Justification for TS Was Provided Previously with Util Ltr Dtd 990317,but Has Been Updated & Is Included as Encl 2 ML20204C5151999-03-17017 March 1999 Forwards Licensee Comments on NRC Preliminary SER & License Re Trojan Isfsi.Encl Includes Justification for Inclusion in ISFSI TS of Alternative Method to 10CFR20.1601(c) for Controlling Access to High Radiation Areas ML20207J3721999-03-10010 March 1999 Forwards License Amend Application 247 Requesting Amend to License NPF-1 to Add License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan, Also Encl.With Certificate of Svc ML20207L0011999-03-0808 March 1999 Transmits Tnp co-owners Annual Rept of Status of Decommissioning Funding for Tnp.Rept Is Based on Most Recent Analysis of Tnp Decommissioning Estimate & Funding Plan,Per Rev 6 to Pge, Tnp Decommissioning Plan ML20207G9691999-03-0303 March 1999 Forwards Rev 6 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Summary of Changes,Attached.Revised Portions Denoted by Side Bars ML20207D7751999-03-0202 March 1999 Forwards Amend 21 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, Per 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities ML20207B0441999-02-24024 February 1999 Forwards Endorsements 139 to Nelia Policy NF-0225 & 2 to Nelia Policy NW-0602 ML20207J0701999-02-11011 February 1999 Forwards Proposed Ts,Update to ISFSI SAR & Revised Calculation,Per Application for Trojan ISFSI License ML20202G4291999-02-0202 February 1999 Forwards Rev 0 to PGE-1076, Trojan Reactor Vessel Package Sar. Approval,With Certain Conditions,For one-time Shipment of Trojan Reactor Vessel Package Granted by Commission Via Ltr ML20202G0931999-01-26026 January 1999 Submits Following Info That Will Be Needed for NRC Staff to Complete Review & Issue Trojan ISFSI License,As Result of 990121 Meeting with NRC Following Insp & Observation of ISFSI Preoperational Testing During Wk of 990118 ML20202F2551999-01-25025 January 1999 Forwards Fitness for Duty Program Performance Data Rept for July-Dec 1998 ML20199J1661999-01-14014 January 1999 Submits Summary of ISFSI Lid Welding Demonstration to Be Held 990118-25.Dates & Days Are Tentative & Can Be Adjusted as Necesssary or as Required ML20199J0801999-01-12012 January 1999 Forwards Schedule for Trojan Nuclear Plant ISFSI pre-op Test,Per Request ML20206Q0121999-01-0808 January 1999 Forwards Rev 1 to PGE-1073 Tnp ISFSI Security Plan,As Result of 981208 Telcon with Nrc.Encl Withheld,Per 10CFR73.21 ML20206P5991999-01-0404 January 1999 Requests That Svc List for Delivery of Documents from NRC Be Updated,Per 981230 Telcon.Substitute for Listings of HR Pate & J Westvold,Submitted ML20198T1651999-01-0404 January 1999 Forwards Rev 5 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Table 2.2-5 Is Revised to Depict Major Components Removed from Plant During 1998.Revs Are Denoted by Side Bars ML20198E3981998-12-17017 December 1998 Forwards Updated ISFSI Emergency Plan,Per 981123 & Discussion in Meeting with NRC on 981119.Description of Changes Encl ML20196E2851998-11-25025 November 1998 Forwards Final Rept of Matl Properties of Neutron Shielding Matl to Be Used in Trojan ISFSI & Test Repts That Verified Matl Properties ML20196D9831998-11-24024 November 1998 Forwards Listed ISFSI Calculation Refs,Per 981110 Telcon ML20196B2321998-11-23023 November 1998 Informs That,Per Commitments Made in 981119 Meeting with Nrc,Rev to PGE-1075 Will Be Submitted No Later than 981218 ML20195J2321998-11-17017 November 1998 Forwards Rev 7 to Trojan Nuclear Plant Defueled Sar. Attachment to Ltr Includes Brief Description of Each Change Included in Rev ML20195E4811998-11-10010 November 1998 Forwards Rev 51 to Trojan Nuclear Plant Security Plan.Rev Withheld,Per 10CFR73.21 ML20155E0331998-10-27027 October 1998 Forwards Amend 7 to PGE-1052, Quality-Related List Classification for Tnp. Amend Removes Ref to Several Clean Up Sys,Deletes Exemptions Allowed by Reg Guide 1.143 & Deletes Figures No Longer Required to Support Discussion ML20154M4151998-10-14014 October 1998 Requests That Further Review of License Change Application LCA-238 Be Suspended as Result of Progress Made in Decommissioning,Installation of Natural Gas Pipe Line ML20154A4751998-09-28028 September 1998 Forwards Amend 20 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, Reflecting Revisions to Fire Protection Program Made During Decommissioning Activities ML20153D3021998-09-21021 September 1998 Forwards Rev 0 to PGE-1077, Tnp Reactor Vessel & Internals Removal Project Transportation Safety Plan, Per Request That Util Submit Description of Measures to Be Taken to Ensure Safe Transport of Tnp Rv & Internals Package ML20151X7171998-09-10010 September 1998 Forwards Rev 3 to PGE-1063, Trojan Nuclear Power Station, Suppl to Applicant Environ Rept. Section 4.5 Revised to Delete Ref to Selected Room Coolers ML20151X8571998-09-10010 September 1998 Provides Rev 2 to Poge, Trojan NPP Permanently Defueled TS Bases. Changes Identified in Revised Text by Side Bars ML20153B0001998-09-0909 September 1998 Forwards Figures & Tables Identifying Nodes Assigned for Trojan ISFSI Transfer Station Analysis,TI-056,Rev 1 ML20237E9421998-08-27027 August 1998 Requests Exemption of Emergency Plan Requirements of 10CFR50.54(q),10CFR50.47(b) & 10CFR50,App E Following Transfer of Spent Nuclear Fuel to ISFSI ML20237E1811998-08-25025 August 1998 Forwards Description of Review Methodology & Summary of Results,Including List of Identified Variations from Guidance Contained in Std Review Plan,Per NUREG-1536 ML20151W5381998-08-25025 August 1998 Forwards Rev 22 to PGE-8010, Poge Nuclear QA Program for Trojan Nuclear Plant. Rev Reflects Administrative Changes That Continue to Meet Requirements of 10CFR50,App B 1999-09-23
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L6651990-09-21021 September 1990 Forwards Application for Amend to License NPF-1,consisting of License Change Application 203,Rev 1.Rev Reduces Scope of Previous Changes Re Tech Spec Table 3.6-1, Containment Isolation Valves ML20059J9841990-09-14014 September 1990 Responds to Re Violations Noted in Insp Rept 50-344/90-21.Corrective Action:Individual Employee Terminated on Day of Event ML20059J9691990-09-14014 September 1990 Forwards Estimates of Facility Operator Licensing, Requalification & Generic Fundamentals Exam Requirements for FY91-94,per Generic Ltr 90-07 ML20059J0321990-09-0707 September 1990 Requests That Six Listed Candidates Take PWR & Generic Fundamentals Exam to Be Administered on 901010 ML20059D8031990-08-31031 August 1990 Forwards Update on Actions for NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs ML20059D2401990-08-30030 August 1990 Extends Commitment Date from 900831 to 901031 to Amend FSAR Per Util 900404 Response to Notice of Violation ML20059D0831990-08-30030 August 1990 Revises Response to Violations Noted in Insp Rept 50-344/90-02.License Document Change Request Correcting FSAR Discrepancy Noted in App A,Violation C Re Request for Design Change Initiated & Will Be Incorporated Into Amend 14 ML20059C1741990-08-28028 August 1990 Forwards Rev 31 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20059D5601990-08-28028 August 1990 Forwards Fitness for Duty Performance Rept for 900103-0630. Overall Positive Rate for All Testing Conducted at Plant from 900103-0630 Is 0.71% ML20059D3201990-08-28028 August 1990 Responds to Deficiencies Identified by FEMA During 891115 Emergency Preparedness Exercise at Plant.Corrective Actions: Procedures Revised to Prioritize Roadblocks & Clearly Define Roadblocks for 5-mile & 10-mile Locations ML20058M7861990-08-0303 August 1990 Forwards Monthly Operating Rept for Jul 1990.W/o Encl ML20056A1551990-07-31031 July 1990 Forwards Updated Response to Address Maint/Surveillance Area of SALP for Period from Jan 1989 - Mar 1990.Overall Plant Performance During Period Acceptable & Found to Be Directed Toward Safe Operation ML20055J3421990-07-26026 July 1990 Forwards Decommissioning Financial Assurance Certification Rept for Plant,Per 10CFR50.75.Certifies That Finanical Assurance Utilizing Methodology as Listed Will Be Available to Decommission Plant ML20055G7131990-07-20020 July 1990 Comments on Operator Licensing Exams Administered on 900717 ML20055G7141990-07-19019 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Plant Has Four Rosemount Model 1153DD6 Differential Pressure Transmitters Installed to Associated Logics for Safety Injection ML20055F8791990-07-16016 July 1990 Forwards 1989 Annual Repts for Portland General Corp,Eugene Water & Electric Board & Pacific Power & Light Co ML20055F8161990-07-13013 July 1990 Advises of New Addressee for Nrc/Util Correspondence ML20055F6911990-07-13013 July 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions ML20055F2441990-07-12012 July 1990 Forwards Response to SALP Evaluation for Jan 1989 - Mar 1990 Re Maint/Surveillance.Util Plans to Improve Performance in Areas of Operation Through Commitment of Support from Nuclear Div Mgt & Personal Involvement of Corporate Mgt ML20055F2961990-07-0606 July 1990 Forwards Addl Info Re ATWS Mitigating Sys Actuation Circuitry ML20055E0241990-07-0606 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-344/90-11.Corrective Actions:Generic Issues That Contributed to Violation Will Be Discussed During Mgt Meetings & Quality Insp Supervisor Counseled ML20055E0281990-07-0606 July 1990 Informs That Actions Committed to in Util Re Replacement of Breaker During 1990 Refueling Outage & Provision of Rept Documenting Replacement of Breaker, Complete,Per NRC Bulletin 88-010 ML20055E3401990-07-0606 July 1990 Forwards Application for Renewal of Plant NPDES Permit ML20055E1751990-07-0606 July 1990 Provides Update to 891130 Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Rev to Maint Procedure 12-4, Valve Air Actuators, to Include Maint Insp Completed in Apr 1990 ML20058K4891990-06-30030 June 1990 Discusses Reduced Min Measured RCS Flow for Plant.Encl Figure 3.2-3 & Evaluation Support Operation W/No Tech Spec Setpoint Changes ML20055D0441990-06-29029 June 1990 Advises That Response to Generic Ltr 90-04 Re Status of Generic Safety Issues at Facility Delayed from 900629 to 900713 ML20055D0411990-06-29029 June 1990 Discusses Design Verification Program Re Main Steam Support Structure.Extension of Completion Date for Project Justified Since Documentation,Not Mod of Main Steam Support Structure Is Reason for Delay ML20055D7091990-06-26026 June 1990 Forwards Steam Generator Tube Plugging Rept,Per Inservice Insp ML20055C2691990-02-20020 February 1990 Responds to NRC Re Violations Noted in Insp Rept 50-344/89-30.Corrective Actions:Administrative Order 5-8 Temporary Mods to Be Evaluated for Need to Improve Control Over Temporary Mods Issued for Both Trains of Sys ML17311A1041989-10-30030 October 1989 Advises That Commitment Date for Performance of Surveillance Moved to 891130 to Allow for Incorporation in Biennial Audit Per Rev 1 to LER 89-08.NRC Resident Inspector Informed of Change on 891013 ML20248G7631989-10-0606 October 1989 Forwards Description of Alternate Compensatory Measures Implemented During Upgrade Activities.W/O Encl ML20248G3131989-10-0303 October 1989 Forwards Response to Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Programs. Revised Topical Rept PGE-1048 Will Be Submitted by 891117 ML20248E2391989-09-29029 September 1989 Forwards Summary of Action Plan to Resolve Fuel Bldg Overstress Conditions ML20248D3711989-09-29029 September 1989 Forwards Rept of Util Plan for Improving Performance of Nuclear Div Staff.New Mgt Described in Plan Will Serve as Catalyst for Decisive Performance Changes ML20248G9001989-09-29029 September 1989 Forwards Rev 1 to PGE-1049, Inservice Insp Program for Second 10-Yr Interval from 860520-960519 ML20248D6161989-09-28028 September 1989 Requests 14-day Extension Until 890928 to Respond to Violations Noted in Insp Rept 50-344/89-09.Individuals Involved in Providing Input to Response Currently Assigned to Solving Problems During Current Forced Outage ML20248G1071989-09-28028 September 1989 Advises That Util Will Submit Final Closeout of NRC Bulletin 88-004, Potential Safety-Related Pump Losss, by 900115 05000344/LER-1989-007, Informs That Rev 1 to LER 89-07 Will Be Submitted by 891013, Due to Forced Outage & Difficulties1989-09-28028 September 1989 Informs That Rev 1 to LER 89-07 Will Be Submitted by 891013, Due to Forced Outage & Difficulties ML20248D4211989-09-27027 September 1989 Suppls 881004 Response to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. NDE Confirmed That No Existing Flaws Exist in Critical Piping Locations Re Thermal Stratification ML20247G9011989-09-15015 September 1989 Responds to Generic Ltr 89-06 Re SPDS Requirements,Per NUREG-0737,Suppl 1 as Clarified by NUREG-1342.Concludes That Isolators Used Were Acceptable for Interfacing SPDS W/Safety Sys,Therefore Util Does Not Intend to Make Mods to SPDS ML20247C2801989-09-0808 September 1989 Responds to NRC Re Violations Noted in Insp Rept 50-344/89-18.Corrective Action:Reevaluation of OAR 87-29, Involving Mods to Hydrogen Gas Supply Sys Implemented as Part of 1989 Refueling Outage 05000344/LER-1989-012, Advises That Rev 1 to LER 89-012 Will Be Submitted by 890920 Due to Extension of 1989 Refueling Outage & Plant Trip of 8908091989-09-0808 September 1989 Advises That Rev 1 to LER 89-012 Will Be Submitted by 890920 Due to Extension of 1989 Refueling Outage & Plant Trip of 890809 ML20247B9281989-09-0808 September 1989 Responds to NRC Re Violations Noted in Insp Rept 50-344/89-12 & Forwards Review of Closeout of First 10-yr Inservice Insp Interval.Concurs That Primary Reason for Individual Problems Was Lack of Insp Contractor Activities ML20247E9371989-09-0707 September 1989 Discusses Nuclear Div Improvement Plan,Per Recent Event Re Containment Recirculation Sump.Util Corrective Actions, Including Organizational Changes,Encl.Plant Improvement Plan Will Be Submitted by 891001 ML20247A6171989-09-0505 September 1989 Informs That Intake Structure Mod Completed as Scheduled & Security Plan Rev Will Be Submitted by 891015 ML20246M5181989-08-31031 August 1989 Forwards Update on Action Plan Developed in Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment ML20246M5771989-08-31031 August 1989 Forwards Status of Progress in Achieving Improvement Goals Identified in 890515 SALP Response Re Safety Assessment/ Quality Verification.Addl Resources Applied to Qualify commercial-grade Suppliers ML20246M5651989-08-31031 August 1989 Discusses long-term Pipe Support Design Verification Program for Plant.Evaluation of Fuel Bldg Confirmed & Quantified Code Overstresses Existing Under Seismic & Tornado Loading Conditions.Details of Action Plan Will Be Sent by 890929 1990-09-07
[Table view] |
Text
.
- amme PbrtlanciGeneral Nde W Set D wms vee f%w:
October 14, 1985 Trojan Nuclear Plant Docket 50-344 License NPF-1 Mr. John B. Martin Re51onal Administrator, Region V U.S. Nuclear Regulatory Commission Creekside Oaks Office Park 1450 Maria Lane, Suite 210 Walnut Creek CA 94596
Dear Mr. Martin:
Inspection Report 50-344/85-025 Vendor Pror. ram Branch Inspection The results of the Vendor Program Branch Inspection of the Trojan Nuclear Plant conducted on August 9-16 were transmitted by NRC Office of Inspection and Enforcement letter dated September 26, 1985. In reviewing this letter and inspection report, we feel a need to provide supplementary information that clarifies our vendor interf ace practices and interpretation of the associated regulatory requirements, and also to provide some additional details on certain specific inspection findings. This information is provided in the attachment.
We are well along with a major updating of our vendor interface programs, as a result of the previous findings in this area by our quality assurance organization and our Nuclear Operations Board, and as a result of the impetus added by the Vendor Program Branch findings. However, we beliove our past practices have been in compliance with a literal interpretation of the regulations of 10 CFR Part 21 and Appendix B to 10 CFR Part 50. Fol-lowing discussions with the Vendor Program Branch, we do understand their current interpretation of the intent of these regulations and how they are being interpreted and enforced elsewhere, even though our procurement and quality programs have been previously approved by the NRC.
A principal reason for differing interpretations of both 10 CFR Part 21, Appendix B to 10 CFR Part 50, and associated ANSI standards (ANSI N18.7 and N45.2.13) involves the appilcation of quality assurance controls to commer-cial grade, or comercially available, off-the-shelf items. This was the major cause for both of the potential violations identified by the Vendor Program Branch at Trojan. We believe that the nuclear industry and the NRC M R 8510310220 051014 2 U
- DR ADOCK 05000344 t 2 m PDR ly ~ b],[g 5
~
.? g gj
'} l: , ,
l
. . :, . . , v .on n ,o
^ -
6 L il t ,
i N Genier-d MCo T4xv1y Mr. John B. Martin October 14, 1985 Page 2 need to resolve this generic issue in concert, so that it becomes better understood what conunercial grade items are, and what level of quality assurance and associated documentation is required or necessary.
In sununary, while we are connaitted to make immediate improvements in our l vendor interface programs, we do not believe there have been any violations of regulatory requirements. Most importantly, based on our follow-up evaluations and improvements to date, we do not believe that our past pro-curement practices have jeopardized the quality or safety of the operation of Trojan, i Sincerely s
! Bart D. Withers I
Vice President Nuclear I Attachment 1
} c: Mr. Lynn Frank, Director j State of Oregon 1 Department of Energy I
l 4
4
(
f 1
)
j i
Trojan Nuclear Plant Mr. John B. Martin Docket 50-344 Attachment License NPF-1 October 14, 1985 Page 1 of 7 PGE RESPONSE AND COMMENTS ON INSPECTION REPORT 50-344/85-025 NRC Item 3b - Procurement PGE's safety-related procurement activities are inadequate in that they fail to meet their commitments to ANSI 45.2.13 and Regulatory Guide 1.123 with respect to verifying the validity of their suppliers' certificates and the effectiveness of their supplier's certification program.
PGE Response The thrust of this finding is that certain cafety-related equipment pur-chased as PGE QA Code D did not have verified suppliers' certificates.
Our procedures, namely NPEP 300-1, allowed the use of QA Code D for pro-curement of off-the-shelf or standard design quality-related equipment when some form of documentation was required, but for which the supplier was not required to have a quality assurance (QA) program. PGE engineer-ins evaluations v. .e performed to e7tablish the requisite requirements and cont ols to be applied to such purenases. This is in compliance with t'o requirements of ANSI N18.7-1976, Section 5.2.13, for commercially off-the-shelf procurements. It is important to note that many of PGE's Code D purchases were for quality-related equipment that was not safety-related.
ANSI 45.2.13-1976 does require tha "means should bn provided to verify the validity of supplier certificates and t'io effectiveness of the certi-fication system, such as during the rerformance of audite of the supplier or independent inspection or test of the items. Such verifications should be conducted by the purchaser at intervals commensurate with the supplier's past quality performance." This requirement is subject to varied inter-pretation. Evaluation and approval of Code D purchases by both Engineering and QA personnel provided reasonable assurance of past qua1Lty performance by the selected supplier. Certification of testing by independent labora-tories, together with PGE's receipt inspection and any preinstallation checks and tests, further served to verify certification.
Five Nuclear Division Procedures (NDPs) have been drafted to strengthen the Nuclear Division procurement program. We are qualifying current Code D vendors via available industry registers, engineering evaluation records, available Plant testing and/or performance records or audits of the supplier to verify certifications. Purchase orders for the last year by the Nuclear Plant Engineering Department (NPED) and for the last six months by the Plant have been reviewed. To date, only 11 vendors who supplied equipment or services under code D purchase orders h.ve been identified that are not qualified by being listed in the CASE register, Bechtel's qualified supplier list, or the ASME vendor " white book". These 11 were either services or products supplied through a distributor. Two
Trojan Nuclear Plant Mr. John B. Martin Docket 50-344 Attachment License NPF-1 October 14, 1985 Page 2 of 7 of the 11 have been qualified based on the engineering evaluation per-formed; two were for engineering services that have been evaluated as not safety-related, and one was for a Plant service performed to our proce-dures (and therefore only our QA program applied). The remaining six suppliers will be qualified by one of the above methods. We are confident that they can be qualified based on our efforts to date.
NRC Item 3e - Procurement The thrust of this potential violation of 10 CFR Appendix B is that PGE improperly procured Pafety-related components from two vendors by not
- verifying that the t;ndors had effective QA programs and by not imposing any specific quality requirements on the vendors in the purchase orders.
PCE Response Neither of the two examples cited for this item are safety-related, por 10 CFR 50, Appendix B, since neither component prevents or mitigates the consequences of postulated accidents that could cause undue risk to the health and safety of the public. (See Introduction to Appendix B.) The auxiliary feedwater square root extractor feeds a control room flow indi-cator; the RCS pressure recorder is also for control room indication, l
! Neither of these components is utilized as an active part of the Roactor protection or Engineered Safety Features Actuation Systems. Accordingly, neither of these two examples support a finding related to noncompilance with 10 CFR 50, Appendix B, since this regulation does not apply.
While safety-related components have been purchased under similar pCE QA l Code D purchase orders, it is our position that a graded level of QA, per General Design Criterion 1 of Appendix A to 10 CFR 50, has been applied to i such components through the requirements of pGE's own QA program and implementing procedures for design, procurement, documentation, receipt, i testing, and installation, even though specific QA requirements and/or 10 CFR 50, Appendix B, itself may not have been imposed on the vendor.
1 The Nuclear Division procurement program requires safety-related items i purchased to a specific Trojan specification or unique to Trojan, be l bought from a vendor with a QA program. Items that were commercini, such as relays, breakers, solenoid valves, recorders, switches, etc that had been qualified by the manufacturer for the nucioar industry were bought Code D. We did not believe that Appendix B was required to be applied by pCE on the vendors of these commercial items. The qualification by the manufacturer to a nuclear standard of one of his catalog items, in of
- itself, did not make it unique to the nuclear industry; further, refer-encing of certain nucioar standards (eg, IERE 323) in purchase documents was considered in some cases to implicitly require application of a QA program by the vendor. Therefore, Appendix B requirements were not applicabic to those commercial purchases.
ls Trojan Nuclear Plant Mr. John B. Martin ,
! Docket 50-344 Attachment i
License NPF-1 October 14, 1985 ,
Page 3 of 7 3
- Although there was no objective evidence in the Nuclear Quality Assurance i Department's (NQAD) files that vendors supplying Code D safety-related I materials were qualified vendors, there was evidence in the NPED files
{*
that an appropriate quality evaluation was performed prior to purchasing these items. NQAD does review and sign-off on all quality-related pur-chase orders including those items in Table 1.
l NRC Item 4 - 10 CFR Part 21 l The thrust of this NRC-identified potential violation of the requirements f
of 10 CFR Part 21 is that PCE did not impose any specific QA or Part 21 i requirements on a vendor that supplied breaker trip units, and that PCE's
} procedures are deficient since they did not require a Part 21 evaluation i for a malfunction that occurred when the trip uni's were tested.
PCE Response I
i 1
The subject breaker trip units were purchased as a standard design off-the-shelf item in accordance with Procedure NPEP 300-1, using a PCE
- QA Code D purchase requisition. The trip units were being provided as an
- Appendix R fire protection backfit to provide added breaker coordination j protection of a safety-related bus from a nonsafety-related associated
- lighting circuit in which the breakers were provided. ,
A l While the trip units were identified on the PCE purchase order to be .
! Class 1E and to meet seismic requiroments, they are considered to be I j commercial grade components. The trip units were only labeled as
] Class 1E for vendor identification purposes - they were not to be utilized i
- for a Class 1E application at Trojan. The devices were ordered from a 4
catalog and are in general industrial use. The devices supplied to Trojan are no different than those supplied to other industrial users. Per Sec- i tion 21.3 (al) of 10 CFR 21, since neither the manufacturer's design nor specification of these trip units is unique to NRC-licensed facilities, i they are clearly a commercial grade item, and are not subject to 10 CFR i
Part 21 evaluation and reporting requirements until af ter dedication.
Further, a determination was performed and documented per Section 21.31 of j Part 21, that 10 CFR 21 did not apply. ,
1 :
The engineer for this modification specified in the Detailed Construction Package that the trip units be tested prior to installation. D" ring this test, the units failed and were returned to the vendor, who PCE informed i by telephone. Since the trip units had not yet been designated for use,
! they were therefore not yet dedicated, per Section 21.3 (a4) and (c1) of j Part 21. Accordingly, by both Part 21 and PCE's Part 21 procedure i (NDP 100-4), no Part 21 evaluation nor report was mandated.
i
{ Even if the breaker trip units were considered to be basic components, the j deviation which caused them to fall would not have resulted in a defect !
1 !
l i ,
i b
! I
Trojan Nuclear Plant Mr. John B. Martin Docket 50-344 Attachment License NPF-1 October 14, 1985 Page 4 of 7 per Section 21.3 (d2), since they had not yet been installed or placed into use or operation. However, to comply with what the Vendor Program Branch considers to be the intent of Part 21, we have immediately processed a change to our Part 21 procedure to clarify when evaluation and reporting is required for basic components.
NRC Item 5 - Control of Nonconformina Material The thrust of the unresolved item in this area is that several mechanical snubbers which had failed testing were found without QC hold tags. There was also a question about the appropriate use of Maintenance Requests (MRs) and Nonconformance Reports (NCRs).
PGE Response The failed snubbers should have either been tagged with QC hold tags or should have been immediately returned to the vendor (which they now have been). Procedure NDP 600-1 is being revised to clarify the appropriate use and evaluations for NCRs and MRs.
NRC Item 6 - Emergency Diesel Generator (EDG) Maintenance
- a. Valve Line-Up Verification A discrepancy was noted that none of the EDC cooling system valves were marked or tagged with the appropriate designator, making identification of the valves difficult.
PCE Response The subject valves do not require special marking or tagging. However, we will review the human factors aspect of this further to improve opera-tional identification if needed.
I
- b. Maintenance l
The thrust of this finding is that PGE has failed to maintain an effective interface with the EDG supplier and that the EDG preventive maintenance program at Trojan is out of date.
l l
4 9
Trojan Nuclear Plant Mr. John B. Martin Docket 50-344 Attachment License NPF-1 October 14, 1935 Page 5 of 7 PGE Response PGE has maintained close contact with Power Systems Division (PSD) of Morrison Knutson concerning preventive maintenance and modifications of the EDGs. This has included regular reviews by PSD of our maintenance program, including onsite reviews by their technical representatives.
Vendor recommendations, including several Power Pointers, that have been received by Trojan have been evaluated and incorporated as appropriate.
Because of our particular EDG service conditions, not all vendor recommen-dations are applicable. Numerous EDG modifications recommended by EMD-GM and provided through PSD have been made, such as turbocharger replacement, soak back lube oil addition, viscous vibration damper installation, etc.
j We will formally request a complete set of past and future vendor recom-i mendations for use in updating our vendor manual for the EDGs.
J j NRC Item 7 - Terry Turbines The thrust of this unresolved item is that PGE accepted and installed equipment which did not conform to the design analyzed in the seismic analysis.
PGE Response The alignment pins have been installed to restore the terry turbine to its original, analyzed seismic level.
j NRC Item 9b - Centrifugal Charging Pump Speed Increasers l
The thrust of this NRC-identified weakness is that PGE failed to perform a timely 10 CFR Part 21 evaluation of a potentially serious common mode failure involving the keyed coupling of the CCP dpeed increaser and pump.
PGE Response j PGE identified the problem using a Part 21 evaluation form (SPI 200-25) on April 1, 1985. In addition, a Maintenance Engineer discussed the keyway condition with the speed increaser vendor during the first week of April.
i A major revision to our Part 21 procedure was issued (Revision 0 to I
NDP 100-4) on April 4, 1985. As a result, the Maintenance Department was
- requested to resubmit 10 CFR Part 21 evaluations that were in progress l' using the new forms in NDP 700-4. During discussions regarding this request for resubmittal, it was determined that the problem was not a Part 21 type defect. The problem appeared to be confined to an undersized l key on one CCP only, rather than being generic to the other CCP on the
! diesel-driven AFW pump speed changers. Because of the isolated nature of l the problem, it did not appear to warrant further evaluation under l
l l
l l._-_._---_.,_.-_ _ _ _ , - _ , _ _ _ ---.._._ _ .-,,._._-----.-_____-~.m_._ - - - - - - ~ .
Trojan Nuclear Plant Mr. John B. Martin Docket 50-344 Attachment License NPF-1 October 14, 1985 Page 6 of 7 Part 21. This problem was further discussed between PGE's OERP Coordina-tor and the Maintenance Supervisor in June with the conclusion remaining that Part 21 reporting was not warranted. Because of NRC concern in this inspection, we have initiated a formal Part 21 evaluation.
NRC Item 10 - Post-Modification Testing The thrust of NRC comments in this area is that test documentation was incomplete, missing, or unavailable for several modifications.
PGE Response As part of an evaluation in August of AFW System problems and a special surveillance during the first week of October, the PGE Nuclear Quality Assurance Department addressed four specific concerns expressed in the subject inspection report,
- a. RHR System Modification - In every modification reviewed (including RHR System modification), we have determined that documentation existed which demonstrated that appropriate installation checks and tests were performed, even though it may not have been included in the As-Built Packages. However, if testing was performed via an existing POT, PICT, or MP, these testing data were located in the files associated with the POT, PICT, or MP.
- b. MSIV Isolation Modification - Both DCP 1 (Electrical) and DCP 2 (Mechanical) were reviewed. It was determined that combinations of portions of three POTS, one PICT, FCN #8 to DCP 1, and a system pressure test were completed that verified proper operation.
- c. AFW Flow Control Modification - TPT-137 was reviewed. This Plant test extensively tested the control aspects of the AFW flow control valves including the high flow condition valve closure function. Addition-ally, it was determined that as part of the I&C flow instrumentation calibration procedure, the high flow valve closure function is veri-fled. (It should be noted that POT and PICT data sheets are located separately in their chronological files. However, the above data for the MSIVs and AFW modifications were available at the time of the inspection.)
- d. Control of Testing - Inconsistencies associated with the identifica-tion of testing requirements for modifications were identified in PGE's August 1985 QA evaluation of AFW System problems. The process has been reviewed. Action is being taken to clearly identify responsibility and provide additional guidance in preparing and reviewing modification packages.
I 1
Trojan Nuclear Plant Mr. John B. Martin Docket 50-344 Attachment License NPF-1 October 14, 1985 Page 7 of 7
- e. Verification of C of C Data No specific examples are provided to support a conclusion that func-tional tests do not verify the validity of the vendor's certification systems. Such tests most frequently do serve to verify that newly installed components perform their intended function as described or inferred by the procurement documents and any vendor certifica+ , to this effect.
J JWL/kal 0513W.1085 i
6 i
1 I
l