Letter Sequence Request |
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MONTHYEARML20207Q5371987-01-20020 January 1987
Proposed Tech Specs,Revising Surveillance Requirements for Safety Injection Sys Accumulator Isolation Valves
Project stage: Other
ML20207Q5341987-01-20020 January 1987
Application to Amend License NPF-1,incorporating License Change Application 150 to Revise Surveillance Requirements for Safety Injection Sys Accumulator Isolation Valves. Description of Change Encl
Project stage: Request
ML20207Q5291987-01-20020 January 1987
Forwards Application to Amend License NPF-1,incorporating License Change Application 150 to Revise Surveillance Requirements for Safety Injection Accumulator Isolation Valves.W/Certificate of Svc Encl.Fee Paid
Project stage: Request
ML20234C8101987-07-0202 July 1987
Forwards Replacement Pages to License Change Application (Lca) 150 Requesting Amend to License NPF-1,per Telcon.Lca Revises Surveillance Requirements for Safety Injection Accumulator Isolation Valves
Project stage: Other
ML20236H4611987-07-28028 July 1987
Forwards Request for Addl Info Re 870120 Tech Spec Change Request Re Disconnection of Power from Accumulator Isolation Valve Operator.Response Requested within 60 Days of Ltr Receipt
Project stage: RAI
ML20235T0111987-10-0202 October 1987
Forwards Response to NRC Request for Addl Info Re License Change Application 150.Schematic Diagram Safety Injection Sys Valves Figures 1 & 2 Encl
Project stage: Request
ML20147C6561988-01-12012 January 1988
Forwards Request for Addl Info Discussed During 871110 Telcon Re Util 870120 Proposed Tech Spec Change Re Surveillance Requirements for Power Lockout of Accumulator Isolation Valves.Response Requested within 30 Days
Project stage: RAI
ML20149L3871988-02-19019 February 1988
Responds to NRC 880112 Request for Addl Info Re License Change Application 150,revising Tech Specs Surveillance Requirements for Safety Injection Accumulator Isolation Valves
Project stage: Request
ML20151H2971988-07-14014 July 1988
Forwards Amend 148 to License NPF-1 & Safety Evaluation. Amend Revises Surveillance Requirements for Safety Injection Accumulator Isolation Valves in Tech Spec Section 3/4.5, Eccs
Project stage: Approval
1987-07-28
[Table View] |
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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
ML20151X8571998-09-10010 September 1998
Provides Rev 2 to Poge, Trojan NPP Permanently Defueled TS Bases. Changes Identified in Revised Text by Side Bars
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
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
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
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
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
ML20059J9691990-09-14014 September 1990
Forwards Estimates of Facility Operator Licensing, Requalification & Generic Fundamentals Exam Requirements for FY91-94,per Generic Ltr 90-07
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
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)
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
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%
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
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
ML20055F8161990-07-13013 July 1990
Advises of New Addressee for Nrc/Util Correspondence
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
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
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
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
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
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
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
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
ML20248G1071989-09-28028 September 1989
Advises That Util Will Submit Final Closeout of NRC Bulletin 88-004, Potential Safety-Related Pump Losss, by 900115
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
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
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
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
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
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
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
ML20246J8641989-08-28028 August 1989
Responds to NRC Re Violations Noted in Insp Rept 50-344/89-02.Corrective Actions:Util Assembled Interdepartmental Task Force in Nov 1988 to Review Incidents & Determine Root Causes
ML20246H5351989-08-25025 August 1989
Informs That Rev to Topical Rept PGE-1049, Trojan Nuclear Plant Inservice Insp Program for Second 10-Yr Interval Will Be Submitted for Approval by 890929
1990-09-07
[Table view] |
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Portland General BechicCoirvoy I E:
David W. Cockfield Vice President. Nuclear October 2, 1987 Trojan Nuclear Plant Docket 50-344 Licenso NPF-1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk ;
Washington DC 20555 '
Dear Sir:
Response to Roquest for Additional Information License Change Application 150 By your letter dated July 28, 1987, Portland General Electric Company received a request for additional information on License Chango Appli-cation 150. This proposed license change would reviso Trojan Technical Specification surveillance requirements for safety injection accumula-tor isolation valves. Attached is our response to your request.
Sincerely, y, AW /
Attachment c: Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. R. C Barr Resident Inspector Trojan Nuclear Plant Mr. David Kish, Director State of Oregon Department of Energy Mr. Michael J. Sykes Chairman of County Commissioners 8710090227 871002 PDR ADOCK 05000344 i P PDR 121 S W Edmon SDwt. Po1 and Oregan 97200
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Trojan Nuclear Plant. Document Control Desk Docket.50-344 October 2, 1987 License NPF Attachment Page 1 of 4 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION LICENSE CHANGE APPLICATION 150 Information Request #1 Provide an electrical schematic and description of the: lockout feature on the accumulator isolation valve control room switches referred to in your January 20, 1987 letter.
Response
Figures 1 and 2 of the electrical control. schematic diagram for the
" Accumulator Tank 1 Outlet Isolation Valve MO 8808A" (Scheme #AB2510) are provided on Pages 3 and 4 of this attachment. These figures illustrate the operation of the combination valve control switch / lockout switch as it will function upon installation.
Referring to Figure 2, the switch has a normal, open, and close position with a spring return to normal. The switch handle is rotated clockwise to 1 open the valve and counterclockwise to close the valve. When the valve is fully open, a red indicating light is lit. When the valve is fully >
i closed, a green indicating light is lit. The valve switch is placed in lockout by pulling out on the handle when in the normal position. Once in lockout, the handle cannot be rotated in either direction.
Referring to Figure 1, pulling out the control switch (42-2510) to the !
lockout position opens contact between F1 and F12 and between F7 and F6. 6 This deenergizes the open and close control circuitry and electrically prevents valve movement (in addition to the mechankcal restriction of the handle when in lockout).
Information Request #2 Provide a description of the proceduro you intend to use to accomplish the' proposed surveillance requirement (4.5.1.C) to verify that power to the isolation valves operator is disconnected. This is the procedure that would involve the use of the lockout feature on the accumulator isolation valve control room switches.
Response
Trojan Nuclear Plant Periodic Operating Test POT-2-3, Emergency Core Cooling System (ECCS) Valve In-Service Test, is the procedure which will be used to accomplish the proposed surveillance requirement (Trojan Technical Specification 4.5.1.C). This POT provides instructions for j performing monthly valve positions and breaker and power lockout switch positions during Modes 1-4 for those ECCS valvec listed on data shoots attached to the procedure. The accumulator isolation valves, MO 8808A-D,
t c'
Trojan Nuclear Plant Document Control Desk Docket 50-344 October 2, 1987 License NPF-1 Attachment Page 2 of 4 are included on the list of these valves requiring monthly checks. The data sheet will require two checks for each isolation valve. The first will verify that the valve is in the open position when Reactor Coolant !
System pressure is greater than 1000 psig by checking control room !
indication. The second will verify that the control switch is in the lockout position with the blocking collar installed.
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- - No. HP No. g l 52 i 11.5 ACCUM. TANK 1 OUTLET ISOL. VALVE M08800A AB25tB B25 59 34 36 :n 8 3 18 52 ' 11.5 ACCUM. TANK 2 OUTLET ISOL. VALVE N088888 882610 826 @
j 52 19.5 ACCUM. TANK 3 OUTLET ISOL. VALVE M08800C AB25tl B25 52<
' 52 19.5 ACCUM. TANK 4 OUTLET ISOL. VALVE M088000 902611 B26 52<
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Document Control Desk October 2, 1987 M Attachment
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APERTURE CARD Also AvaHable On Aperture Card l
! I INDICATION CLOSE OPEN CLOSE ALARMS l.
_ _ REMOTE a.. LOCAL _ IREMiLOC5 !REMa_ LOC- STATUS .t ANNUNCIATOR a r LIGHTS I T l- l l
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- t. CONTACT CLOSES ON SAFETY INJECT! Ort Elld{
1, 2. VALVE SHOWN IN FULLY OPEN POSITION. j g,,. '
IR. IRA Q.) J '
- 3. FOR SCHEMES A82510 & AB251 PULL IF. 2FA tkl t:. VIRES TO ,G1IA & WIRE INTERNALLY TO $13A.
- K603 IF. 2F (F) th FOR SCHEMES BB2618 & 8B2611 PULL WIRES TO -
, g (NOTE di (13g.
M _, 4. CONTACT OPENS ON SAFETY INJECTION, I O 5. CONTACT CLOSES AT AND ABOVE P1), LOW-(l.ZQ .4y PRESSURIZER PRESSURE.
- IF R, B25 I 9 R,. 3R' 6. FOR SWITCH DEVELOPMENT SEE FIGURE 2.
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Document Control October 2, 1987 j Attachment {
Page 4 of 4 )
4 l
1 I
'OSITION
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42-2610 YERTGd CS 42-3611 CkNO n CS .
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$efn Also Available Gu "I Aperture Card fNORMAL lAL ONLY TROJM NUCLEAR PLei l Mk "O" *M N - D b _
" ET E rs;,e 2 M TL* c w oon an. 8-2889 "" 3 "2 eve onc twin M e &
ISSUED FOR LC A- lGo ( A/oTT4_Mf 5"'2"Oj e
SCHEMATIC DIAGRAM $.
SAFETY INJECTION SYSTEM VALVES i
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