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MONTHYEARML20213A5121987-01-27027 January 1987 Forwards Evaluation of Cycle 9 Startup Physics Testing & Westinghouse Evaluation of Plant Control Rod Worth Measurements.Based on Evaluations,Addl Measurements Not Required Project stage: Other ML20206B3211987-04-0606 April 1987 Safety Evaluation Supporting Cycle 9 Core Physics Data. Performance of middle-of-life Core Physics Measurements Verifying Shutdown Margin for End of Cycle Not Necessary Project stage: Approval ML20206B2771987-04-0606 April 1987 Forwards Safety Evaluation Supporting Cycle 9 Core Physics Data.Addl Measurements of middle-of-life Core Physics Verifying Shutdown Margin for End of Cycle Not Necessary Project stage: Approval 1987-01-27
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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
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O POHTLAND GENEMAL ELECTRIC COMI*ANY 821 S. W. S ALM ON STRFET WILLIAM J. LINDBLAo PO RT LA N o. O REGON 97204 1503}226-8875 January 27, 1987 Trojan Nuclear Plant Docket 50-344 License NPF-1 U.S. Nuclear Regulatory Conunission ATTN: Document Control Desk Washington DC 20555
Dear Sir:
Trojan Cycle S Core Physics Data Pursuant to discussions between T. L. Chan of the NRC and G. A. Zimmerman of PCE, attached is our documented evaluation of the Cycle 9 Core Physics Data.
Initially, because of differences between design predictions and test data for shutdown margin, consideration had been given to performing taiddle-of-life (MOL) core physics measurements to verify the accuracy of the antici-pated end-of-life design conditions. We have recently concluded that additional measurements are not required. That conclusion is supported in Attachments 1 and 2, which are evaluations of the Cycle 9 data by PGE and Westinghouse, respectively. At PGE, formal evaluations were performed by the Fuel Operations Department as well as the Plant Staff, and discrep-ancies in the data were reviewed by the Plant Review Board and the Trojan Wuclear Operations Board. Each of these separate evaluations and reviews i concluded that additional core physics measurements are unnecessary; with continuing reviews specified by the TNOB.
We would be pleased to discuss these results with you.
l Sincerely, i "S _
i Attachments c: Mr. David Kish, Acting Director State of Oregon Department of Energy I
l Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. Gary Kellund Resident Inspector Trojan Nuclear Plant 8702030318 870127 O PDR ADOCK 05000344 P-PDR lh
. ~ . _, - . - . . . ..-- - . _
Trojan Nuclear Plant Document Control Desk Docket 50-344 January 27, 1987
-License NPF-1 Attachment 1 Page 1 of 5 EVALUATION OF CYCLE 9 STARTUP PHYSICS TESTING
Background
j During the performance of the Core Physics Testing following startup for Cycle 9 reactor operations on June 18, 1986, several measurements I
were outside the acceptance criteria. The anomalous results are categorized as follows:
i
- 1. Control rod worths were generally lower than predicted. l
- 2. The worth of all the control rods as indicated by the boron end l points for the all-rods-in-minus one (ARI-1) condition was
- inconsistent with the reactivity computer measurement.
l
\
7
- 3. Neutron flux in the central portion of the core was higher than predicted and neutron flux on the periphery of the core was lower
, than predicted at BOL, HZP conditions.
i An evaluation was initiated to determine the root cause and effect of l
( the unexpected data, and to ensure that EOL conditions will meet the
} Technical Specification requirements for shutdown margin.
Discussion The measured control rod worths for Control Banks B and A, and the combined worth for control Banks D, C, and B were outside the
- PCE-established acceptance criteria of the Reload Cycle 9 Startup Low Power Physics Test. Additional measurements were taken, usirs both the reactivity computer and boron samples. The ARI-l configuration, not l originally scheduled to be measured, was determined. Note that the
! predicted values for Control Banks ~B and A have differed from measured values more than the values predicted for other banks for the last several years. The bank worth for Control Bank B, located near the i
perimeter of the core, has normally been predicted higher than measured, ,
j and the worth for Bank A, located near the center of the core, has j normally been predicted lower than measured.
Investigation concerning the core physics data concentrated primarily in two areas:
l l 1. Validity of the reactivity computer.
+
Inaccuracles in the reactivity computer data are due to uncertainties in the delayed neutron parameters, inability to model the changes
! occurring in the delayed neutron parametero ao power distribution
- changes due to rod insertion, inaccuracy of the analog reactivity i
9 I-
. _ _ - - ~ .. _ . ,
t Trojan Nuclear Plant Document Control Desk lI Docket 50-344 January 27, 1987 License NPF-1 Attachment 1 Page 2 of 5 4
i computer components, inaccuracles in interpreting the reactivity computer traces, errors due to the use of a point kinetics technique i
for a three-dimensional reactor, errors due to a background gamma signal to the flux detector (which is more significant when reactor power is extremely low), and errors due to thermal feedback if reactor power nears the point of adding heat during data measure-1 ments. The combined use of a low-leakage core loading pattern and the short duration refueling shutdown caused the background gamma j signal to be higher this cycle than in most previous cycles. Efforts 3 to attain a low-leakage core loading pattern had been initiated in Cycle 5. However, a complete low-leakage core loading pattern was not attained until this cycle. Core physics measurements during the previous two cycles had indicated that the neutron-to-ganna signal ratio was lower that in prior cycles. The fact that the refueling outage was shorter than other refueling outages did not permit the gamma flux to decay as much as in the past. These effects caused the reactivity computer to indicate reactivity values which, for the ARI-1 measurement, were lower (after attempts to compensate) than actual by approximately 2 percent. Also, the reactivity computer j checkout, which was performed by comparing the reactivity indicated by the reactivity computer when the reactor is on a stable reactor
- period to the value calculated from the measured reactor period,
! indicated that the reactivity computer was reading low by approxi-
- mately 3 percent. These inaccuracies contribute to an inherent error
- in the reactivity computer data of at least 17 percent. Over the i course of an extended measurement program such as an ARI-1 determina-l tion, a reactivity computer bias error may tend to accumulate. We believe that the combination of uncertainties in the reactivity computer measurements caused the ARI-1 rod worth measurement to be
, low.
The calibration of the reactivity computer was verified to have been performed by experienced personnel in accordance with equipment i operating instructions. The observed indications of errors were
! within the 17 percent inherent error band and within the acceptance l criteria.
As a further check of the measured data, the reactivity computer data was sent to Westinghouse for analysis. Westinghouse obtained essentially the same rod worths from the trace data as PGE had. r f 2. Accuracy of the boron samples.
l l
To verify the results obtained by means of the boron samples, additional boron analyses were performed. Backup analyses were
! independently performed by Westinghouse with essentially the same i measurement results. It was determined that the uncertainties in the baron moaouromonto woro approximatoly 13 porcont, banad upon tho methodology used to determine the boron concentration. The errors i
h
Trojan Nuclear Plant Document Control Desk Docket 50-344 January 27, 1987 4
License NPF-1 Attachment 1 Page 3 of 5 4
associated with an ARI-l worth measurement based on two boron samples i
(before and after conditions) will tend to be limited since the boron sample values are subtracted. Thus, the errors tend to cancel.
It was concluded that the unusual difference between the rod worth l
measurements obtained by the reactivity computer and the worth indicated by the boron end point measurements was due to the particular accumula-tion of errors in the reactivity computer data. Furthermore, a review of i the reactivity computer traces indicated some boren dilution had con-tinued during the initial phases of the ARI-l reactivity measurements.
When the reactivity computer measured data are compensated for this
- dilution, the results are within the acceptance criteria (shutdown margin j of greater than 1.6 percent at both BOL and EOL) in the Trojan Technical a
Specifications and are reflected in the data shown on Table 1 of Attachment 2.
- Since the measured data obtained via boron analyses is believed to be accurate, an examination was made to determine if predicted data was representative of conditions in the reactor. Several areas affecting the predictive model were examined, two of which were the assumed burnup of i previous cycles and the core baffle assembly modeling treatment.
The core follow data compiled at Trojcn over the last several cycles indicates that true core power has been less than indicated power level l- and the difference is attributed to feedwater flow venturi fouling. This i
discrepancy results in a difference between actual cycle burnup and the i burnup that is calculated assuming that indicated power is accurate.
Although adjustments were made at the end of each cycle based on boron letdown data in an attempt to account for the burnup difference, the adjustments were found to be too small for Cycles 7 and 8.
i
- A second item investigated was the baffle modeling. A revised core baffle assembly treatment, taking into account observed trends in power
' distribution behavior at Trojan, was developed and incorporated in the predictive models. The new model resulted in a small reduction in pre-dicted boron concentration throughout Cycle 9, as well as a beginning of cycle inboard power shift of approximately 3 percent which decreases to less than 0.5 percent at end-of-cycle.
In addition, a small error in predicted boron concentration and power distribution at BOL, HZP conditions was found to exist due to the reduced power operation at the end of Cycle 8 which affected the amount of samarium in the fuel at the beginning of Cycle 9. These changes to the models improved control rod worth predictions and power distribution
- predictions at BOL while not significantly changing predictions at EOL.
Trojan Nuclear Plant Document Control Desk Docket 50-344 January 27, 1987 License NPF-1 Attachment 1 Page 4 of 5 Conclusions Based on the above evaluations and considerations, it was concluded that errors existed in the reactivity computer data, and that the chemistry data is more accurate. Secondly, it can be concluded that adequate shutdown margin exists in the Trojan reactor at beginning-of-life and end-of-life and additional core physics measurements are not needed.
The attached table summarizes the calculated / measured rod worth and shutdown margin for the Trojan Nuclear Plant for Cycle 9.
An investigation is continuing to determine the potential impact of B-10 depletion on core physics measurements. A sample has been sent to Westinghouse to determine the quantity of B-10 in the boric acid used at Trojan. Results are expected by January 31, 1987 and will be accounted for, as required, in calculations of critical and shutdown boron concentrations. The TNOB will further review this issue upon completion of the B-10 measurements.
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- Worth H^*
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Reactive Design Shutdown. Shutdown S--
(ARI-1) Requirements Margin Margin Conunents 3
W Calculated Worth 5094 Beginning of Life (BOL) Less 10%* -2480 2105 1600 505 pcm > Tech spec limit
{
= 4585 i
j Measured Worth BOL 4803 -2480 2407 1600 807 pcm > Tech Spec limit Using Boron Samples i
l W Calculated Worth 5586
- End of Life (EOL) Less 10%* -3300 1727 1600 127 pcm > Tech Spec limit
= 5027
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5245 -3300 1945 1600 345 pcm > Tech Spec limit U ng r S s i
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- Additional uncertainty applied to rod worth calculations.
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- Trojcn Nuclear Plant Document Centrol Desk Docket 50-344 January 27, 1987 License NPF-1 Attachment 2 l Page 1 of 2 WESTINGHOUSE EVALUATION OF TROJAN N-1 CONTROL ROD WORTH MEASUREMENTS An extensive review of the neutronics models and measured data for Trojan Cycle 9 as well as previous cycles has been performed. The review led to improved prediction versus measurement results for the Cycle 9 core by accountiny, for less than full power operation in previous cycles. Due to feedwater flow ventuel fouling Trojan has consistently operated slightly below 100 percent power, hence actual burnup is less than calculated fuel burnup and actual reactivity is slightly higher. For Cycle 9 and future cycles, Plant calorimetric evaluation is expected to eliminate this dis-cropancy. Westinghouse has since evaluated this phenomenon and adjusted their predictions for this effect. These changes resulted in improved agreement between measured and predicted N-1 control rod worth at beginning-of-life (BOL), while not significantly changing predicted N-1 worth at end-of-life (EOL). At BOL, uncertainties in assembly burnups and fission product concentrations in reinserted fuel often lead to small IN-OUT tilts for Trojan. These discrepancies burn out with time because assemblies operating at higher power levels will deplete faster and, consequently, lose reactivity faster than those assemblies operating at lower power which tends to reduce assembly reactivity differences between predicted values and measured values with cycle operation. As a result of this effect, EOL power distributions essentially do not exhibit IN-0UT power tilts, and more than sufficient shutdown margin to meet the techni-cal specification requirements at EOL is predicted. The improved pre-dicted values with their associated revised errors are shown on Table 1, with the original predicted and measured values.
The ARI-l worth based on boron end points at BOL has been measured to be within the 10 percent allowance when compared to the predicted value.
The boron end point measurements were verified by Westinghouse chemists to give the same N-1 worth reported by PGE chemists. Westinghouse believes that these boron end points are the most reliable source of data for BOL N-1 worth. Westinghouse recommends the use of boron end points as the most accurate means for determining that the shutdown margin is met.
Based on previous cycle operation and core behavior with burnup described
- above, the EOL ARI-1 worth is expected to fall within the 10 percent allowance of the predictions. Based on the current rod insertion limits, an additional margin exists in the Rod Insertion Allowance (RIA) at EOL j which reduces the RIA requirement. This reduces the EOL reactivity design requirement and increases the calculated shutdown margin to j 1.73 percent. Consequently, there is no shutdown margin concern when boron end points are used as the basis for control rod worth determination.
In summary, analysis of the Cycle 9 startup results show that sufficient shutdown margin is available throughout cycle operation and no additional data is necessary. Westinghouse will continue to oxamina and improve our models based on operational experience.
o C5Y
- ;L6L 85a TABLE 1 'S w2 TROJAN CYCLE 9 STARTUP
SUMMARY
E?5 7y7 ec~g Original Revised' g, Parameter W Pred. W Pred. Measured Original Error Revised Error 7 (M - P) (M - P R) 5.
P PR HZP ARO Boron (ppm) 1558 1579 1587 29 ppm 8 ppm HZP Din Boron (ppm) 1435 1454 1468 33 ppm 14 ppm Bank D worth (ppm) 123 125 119 -3.3% -4.8%
Bank D worth (pem) 1053 1056 1012 -3.9% -4.2%
Bank C worth (pcm) 909 959 850 -6.5% -11.4%
Bank B worth (pcm) 1242 1125 891 -28.% -20.8%
Bank A worth (pem) 493 575 576 17.% 0.2%
DCBA Boron End Point (ppm) 1130 1143 1150 20 ppm 7 ppm DCBA worth (ppm) 428 436 437 2.1% 0.2%
DCBA worth (pcm) 3694 3715 3329 -9.9% -10.4%
N-1 Boron End Point 942 978 1022 80 ppm 44 ppm N-1 worth (ppm) 616 601 565 -8.3% -6.0%
N-1 worth (pcm) 5324 5094 4343 to 4526* -18.4% to -15.0% -14.7% to -11.1%
N-1 worth (pem-BW)** 5236 5109 4803 -8.3% -6.0%
Boron Worth (pem/ ppm) -8.5 -8.5 -8,5 0 0
- The measured value of 4343 pcm does not account for observed boron dilution and tempera-ture change effects that occurred during the K-6 (the most reactive rod) rod swap with Shutdown Banks A and B, and is not affected by core flux distribution skewing. The measured value of 4526 pcm was derived using reactivity computer worth during the rod swap gsgg.gr of K-6 with Shutdown Banks A and B and assumes that the core flux distribution skewing gggg would not adversely affect the reactivity computer results. ,, o g g
- BW - value obtained by conversion of ppm to pcm using the measured borun worth, o *N mgUn 82 S 0;"
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