Letter Sequence Approval |
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MONTHYEARML20132D3111985-07-16016 July 1985 Safety Evaluation Concluding That Breakout of Spirit Lake Would Not Affect Safe Operation of Plant.Outlet Tunnel Reduces Threat of Breakout.Two Map Diagrams Encl Project stage: Approval ML20132D3041985-07-16016 July 1985 Forwards Safety Evaluation Concluding That Breakout of Spirit Lake Would Not Affect Safe Operation of Plant.Outlet Tunnel Constructed to Reduce Threat of Potential Debris Dam Failure & Breakout of Lake Project stage: Approval ML20141E8951986-04-10010 April 1986 Forwards NRC Review of Us Army Corps of Engineers Study Re Possible Flood Levels at Facility.Study Showed Higher Flood Levels than Design Basis Flood Level.Permanent Flood Protection Unnecessary.Alternative Measures Suggested Project stage: Approval 1985-07-16
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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:NRC TO UTILITY
MONTHYEARML20062F9241990-11-0808 November 1990 Forwards Insp Rept 50-344/90-29 on 900902-1006 & Notice of Violation ML20058F3761990-11-0101 November 1990 Ack Receipt of Re Corrective Actions Taken in Response to Violations Noted in Insp Rept 50-344/90-23 ML20058A3231990-10-12012 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-344/90-20 ML20058B6381990-10-12012 October 1990 Forwards Revised Section 1, Persons Contacted of Insp Rept 50-344/90-20,correcting Errors in Personnel & Positions ML20059M6981990-09-25025 September 1990 Ack Receipt of in Response to NRC Re Violations Noted in Insp Rept 50-344/90-21 ML20059M1941990-09-18018 September 1990 Forwards Insp Rept 50-344/90-25 on 900820-24.No Violations Noted ML20059L1711990-09-18018 September 1990 Provides Info Re Gfes of Operator Licensing Written Exam to Be Administered on 901010.W/o Encls ML20059F5331990-09-0707 September 1990 Ack Receipt of 900828 Response to NRC 900801 Request for Info Re FEMA Observations of 891115 Emergency Preparedness Exercise.Corrective Actions Described in Util Response Will Be Verified & Followed Through Routine Insp Program ML20059E8501990-09-0606 September 1990 Forwards Enforcement Conference Rept 50-344/90-26 on 900830. NRC Concludes That Corrective Actions Discussed Should Improve Plant Performance ML20059D5231990-08-30030 August 1990 Informs That Util Responses to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment Confirms That All Requirements Completed & Implemented ML20059D0951990-08-30030 August 1990 Advises That Util 900126 Response to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations, Acceptable & Review Concluded ML20059D0971990-08-30030 August 1990 Forwards SER Accepting Util 880311,0401 & 1223 & 900319 & 0622 Responses to NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes ML20059D3071990-08-29029 August 1990 Forwards Exam Rept 50-344/OL-90-03 Administered on 900717-19 & 23.All But One Initial Reactor Operator Passed Exam.Operating Portion of Initial Licensing Exam Revealed Some Generic Training Weaknesses ML20059C7801990-08-27027 August 1990 Forwards Amend 162 to License NPF-1 & Safety Evaluation. Amend Revises Tech Spec 3/4.6.1, Containment Integrity ML20056B2511990-08-21021 August 1990 Forwards Safeguards Insp Rept 50-344/90-23 on 900719-0817. Violation Noted But Not Cited.Characterization of Apparent Violation in Insp Rept May Change as Result of Further NRC Review.Enforcement Conference Scheduled for 900830 ML20059A6991990-08-17017 August 1990 Advises That Util 900119 Program Description Including Positions on Static Testing to Ensure Proper Switch Settings & motor-operated Valve Problem Trending Schedules May Be Reviewed During Possible Further NRC Insp ML20059C1951990-08-16016 August 1990 Forwards Insp Rept 50-344/90-21 on 900609-0721.Violations Noted.W/O Notice of Violation ML20056B2421990-08-15015 August 1990 Advises That 900712 & 31 Responses to SALP Rept 50-344/90-09 Appropriate.Page 18 of Initial Rept Changed to Relect Effort by Util Engineering Groups in Design of ATWS Mitigation Sys Actuation Circuitry,Per 900615 Board Meeting ML20056A5141990-08-0303 August 1990 Advises That Response to NRC Bulletin 88-010, Molded Case Circuit Breakers, Complete,Per 890331,0414,0725 & s.If Subsequent Insp Identifies Deficiencies in Actions & Responses,Issue Will Be Reopened ML20058L4401990-08-0202 August 1990 Forwards Corrected Amend 161 to License NPF-1,revising Items 6.4.1 & 6.4.2 Re Administrative Controls ML20058L5501990-08-0202 August 1990 Forwards Safety Evaluation Concluding That Instrumented Ammonia Detection Unnecessary for Protection of Control Room Personnel Based on Review of Submittals ML20056A6231990-08-0101 August 1990 Forwards FEMA Rept Re Observation of Offsite Activities During Plant Emergency Preparedness Exercise on 891115.NRC Understands That FEMA Rept for 900724,remedial Drill Will Close Five Deficiencies.W/O Encls ML20059A4011990-08-0101 August 1990 Forwards Insp Rept 50-344/90-17 on 900604-07.No Violations or Deviations Noted IR 05000344/19900111990-07-27027 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-344/90-11 ML20056A0471990-07-20020 July 1990 Forwards SALP Mgt Meeting Insp Rept 50-344/90-22 on 900615 ML20055H3211990-07-13013 July 1990 Advises That 900330 & 0504 Amend 22 to Radiological Emergency Plan Meets 10CFR50.54(q) Requirements & Acceptable ML20055H5671990-07-11011 July 1990 Forwards Insp Rept 50-344/90-19 on 900611-15 & Notice of Violation IR 05000344/19900181990-07-10010 July 1990 Forwards Safeguards Insp Rept 50-344/90-18 on 900625-29.No Violations Noted.Rept Withheld (Ref 10CFR2.790(d)) ML20055E7851990-07-0909 July 1990 Forwards Safety Evaluation Re Procedures Generation Program for Plant,Per Util 831110 & s.Ltrs Should Be Reviewed to Address Programmatic Improvements Outlined in Section 2 of Rept ML20055G6311990-07-0606 July 1990 Forwards Insp Rept 50-344/90-16 on 900506-0609.No Violations or Deviations Noted ML20055E4061990-07-0303 July 1990 Discusses 900630 Submittal Re Reduced Measured Min RCS Flow for Plant.New Measured Min Flow Limit for RCS Flow Will Be Reflected in Proposed Change to Tech Specs to Be Submitted by 900713 ML20055C7481990-06-18018 June 1990 Forwards Amend 161 to License NPF-1 & Safety Evaluation. Amend Changes Qualification Requirements,As Specified in Tech Spec 6.3.1,that Must Be Met by Radiation Protection Manager ML20059M8941990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C3881990-02-12012 February 1990 Forwards Mgt Meeting Rept 50-344/90-01 on 900112.Licensee Must Thoroughly Follow Through on Implementation of Improvement Plans & Place High Priority on Assuring That Personnel Understands Goals & Objectives ML20248A8601989-09-27027 September 1989 Ack Receipt of 890828 & 0923 Responses to NRC 890727 Notice of Violation.Nrc Notes That Licensee Did Not Ack Violation B Re Proficiency of Security Officers in Use of Assigned Weapons IR 05000344/19890121989-09-27027 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-344/89-12.Contested Violation Re Interpretation of SNT-TC-1A Requirements Will Be Further Examined IR 05000344/19890181989-09-25025 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-344/89-18 ML20248D3331989-09-25025 September 1989 Forwards Amend 6 to Indemnity Agreement B-78,reflecting Changes to 10CFR140,effective 890701 ML20248B7751989-09-19019 September 1989 Submits Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exam to Be Administered 891004 & Forwards Map Describing Location of Exam & Other Info.W/O Encls IR 05000344/19890171989-09-12012 September 1989 Forwards Insp Rept 50-344/89-17 on 890618-0729 & Notice of Violation.Insp Identified That ESF Components Had Been Operated Outside Normal Design Limits ML20247H7401989-09-0101 September 1989 Forwards Enforcement Conference Rept 50-344/89-22 on 890824 Re Containment Recirculation Sump Debris & Design Problems ML20246N7881989-08-31031 August 1989 Informs That 880420 Rev 20 to Physical Security Plan Partially Consistent W/Provisions of 10CFR50.54(p).Trash Rack Functioning as Protected Area & Vital Area Barrier Unacceptable ML20247C1431989-08-29029 August 1989 Forwards Insp Rept 50-344/89-09 on 890522-0609 & 0719-21 & Notice of Violation.Licensee Generally Implemented Committed Programs to Enhance Understanding & Implementation of Plant Design Basis ML20246D8121989-08-21021 August 1989 Confirms 890821 Telcon Between Ae Chaffee & Td Walt Re Mgt Meeting/Enforcement Conference on 890824 at Plant to Discuss Insp Findings as Documented in Insp Rept 50-344/89-19 ML20246H9561989-08-15015 August 1989 Forwards Insp Rept 50-344/89-19 on 890712-0808.Violations Noted.Insp Findings Indicate That Util Mgt Oversight of Plant Activities Associated W/Sump Have Been Ineffective ML20245H3601989-08-10010 August 1989 Forwards Corrected Page to Amend 152 Issued to License NPF-1 on 890515 IR 05000344/19890141989-08-0707 August 1989 Ack Receipt of 890707 & 28 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-344/89-14. Handwritten Notes Encl ML20245L1301989-08-0404 August 1989 Forwards Insp Rept 50-344/89-12 on 890522-0601 & Notice of Violation.Insp Determined That Inservice Contractor & Licensee Oversight of Contractor Activities Need Significant Improvement ML20245K2541989-08-0303 August 1989 Forwards Insp Rept 50-344/89-18 on 890712-14 & Notice of Violation.Nrc Views Util Handling of Hydrogen Issues as Missed Opportunities to Focus on & Resolve long-standing & Potentially Significant Safety Issue IR 05000344/19890081989-07-27027 July 1989 Discusses Safeguards Insp Rept 50-344/89-08 & Security Insp Rept 50-344/89-02 & Forwards Notice of Violation Re Safeguards Info Protection & Firearms Training Adequacy.Encl Withheld (Ref 10CFR2.790) 1990-09-07
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217C8171999-10-0606 October 1999 Forwards Notice of Receipt of Availability for Comment & Meeting to Discuss License Termination Plan,Per 990805 Application 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 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 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 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 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 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 ML20195J0111999-06-0909 June 1999 Responds to Requesting License & Exemption Re Emergency Preparedness 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 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 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 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 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 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 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 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 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 ML20198E9871998-12-21021 December 1998 Informs That NRC Staff Acks Delay & Understands Bnfl Fuel Solutions Will Submit Revised Schedule for Responding to Second Transtor Shipping Cask RAI No Later than 981231. Current Schedule Last Updated on 981030 ML20198S1661998-12-17017 December 1998 Final Response to FOIA Request for Documents.Records Encl & Identified in App C & D.App E Records Withheld in Part & App F Records Withheld in Entirety (Ref FOIA Exemption 5) & App G Records Withheld in Entirety (Ref FOIA Exemptions 4 & 5) ML20195D9471998-11-0404 November 1998 Informs of NRC Final Decision on Portland General Electric Co Request for Approval of one-time Shipment of Decommissioned Rv Package from Trojan Nuclear Power Plant Near Richland,Wa.Commission Approved Request on 981022 ML20155F6471998-11-0202 November 1998 Informs of NRC Final Decision on Portland General Electric Co Request for Approval of one-time Shipment of Decommissioned Rv Package from Tnp Near Ranier,Or to Disposal Site at Hanford Nuclear Reservation ML20155G7371998-10-30030 October 1998 Forwards Insp Rept 50-344/98-202 on 980831-0903. No Violations Noted.Insp Program Covered Maint Program, Safety Review Program & Follow Up on Previous Inspector Follow Items Re Modular Sf Cooling Sys ML20155E0491998-10-29029 October 1998 Forwards SER Granting Two Specific Exemptions Under 10CFR71.8 for Approval of Trojan Reactor Vessel Package for one-time Shipment to Us Ecology Disposal Facility Near Richland,Wa ML20155H0171998-10-29029 October 1998 Informs of Us NRC Final Decision on Poge Request for Approval of one-time Shipment of Decommissioned Reactor Vessel Package from Trojan Nuclear Power Plant,To Disposal Site at Hanford Nuclear Reservation,Near Richland.Wa ML20155F6001998-10-29029 October 1998 Informs of NRC Final Decision on Portland General Electric Co Request for Approval of one-time Shipment of Decommissioned Rv Package from Plant Near Ranier,Or Disposal Site at Hanford Nuclear Reservation ML20151Z6461998-09-17017 September 1998 Refers to Insp Rept 50-344/98-02 Issued on 980701 Re Modular Spent Fuel Pool Cooling Sys.Info Provided in Re New Spent Fuel Pool Sys Reviewed.Insp 50-344/98-03 & 50-344/98-202 Also Included Reviews of Sys Design & Testing ML20151Y8761998-09-11011 September 1998 Responds to Re NRC Efforts on Review Activities for Proposed one-time Shipment of Trojan Reactor Vessel,For Disposal.Nrc decision-making Process Acting in Parrallel & in Concert with Other Necessary Approvals ML20237F1281998-08-27027 August 1998 First Partial Response to FOIA Request for Documents. Forwards App a Records Already Available in Pdr.App B Records Being Made Available in PDR ML20237E5781998-08-25025 August 1998 Forwards Insp Rept 50-344/98-03 on 980727-30.No Violations Noted ML20237B4271998-08-14014 August 1998 Expresses Appreciation for Contribution to NRC Public Meeting Held in Kelso,Wa on 980730 Re Proposed One Time Shipment of Trojan Decommissioned Rv for Disposal ML20237A4101998-08-11011 August 1998 Forwards RAI Re Plant Request for Amend to Support Repowering Site W/Natural Gas Fired,Combined Cycle Turbines. Response Requested to Be Provided within 60 Days of Date of Ltr ML20236T5651998-07-21021 July 1998 Responds to to Chairman Jackson Expressing Concern W/Nrc Schedules for Reviewing Portland General Electric Co Applications for on-site Sf Storage & for one-time Shipment of Reactor Vessel ML20236G9671998-07-0101 July 1998 Forwards Insp Rept 50-344/98-02 on 980601-04.No Violations Noted.Plans to Replace Existing Spent Fuel cooling,make-up Water & clean-up Sys W/New Self Contained Sys Were Discussed W/Staff ML20249B8581998-06-18018 June 1998 Informs That Tj Kobetz Has Assumed Project Management Responsbilities for Proposed Trojan Isfsi.Communications W/ NRC Should Be Directed to Tj Kobetz.Written Correspondence Should Continue to Go DCD ML20247N6681998-05-22022 May 1998 Forwards Insp Rept 50-344/98-01 on 980504-07.No Violations Noted.Insp Focused on Physical Security Program ML20217L0571998-04-29029 April 1998 Forwards Insp Rept 50-344/98-201 on 980223-26.No Violations Noted.Specific Areas Examined Included Training & Certification of Qualified Evaluators,Independent Reviewers & Independent Safety Reviewers;Procedural Controls IR 05000344/19970051998-03-25025 March 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-344/97-05.Actions Will Be Reviewed During Future Insp to Determine That Full Compliance Has Been Achieved & Will Be Maintained ML20217A5491998-03-18018 March 1998 Submits Update on Actions Taken by NRC Since 970613 Response Re Portland General Electric Co Request for Approval of 1-time Shipment of Decommissioned Reactor Vessel.Two Issues Identified for Review in Utility Request,Submitted ML20217A4221998-03-11011 March 1998 Submits Update on Actions Taken by NRC Since 970613 Response Re Portland General Electric Co Request for Approval of one-time Shipment of Decommissioned Reactor Vessel.Two Issues for Review in Utility Request Submitted ML20202J0741998-02-18018 February 1998 Grants Request for Extension of Response to NOV in Insp Rept 50-344/97-05.New Response Deadline 980317 ML20203A9061998-02-18018 February 1998 Informs of 980209 Meeting W/Poge in Region IV to Discuss Proposed Changes to Security Provisions for Protected Area at Plant.List of Attendees & Handouts Provided by Util Encl ML20202C1791998-02-0909 February 1998 Returns Responses to 970731 RAI-2 Re 960326 Application for Trojan Isfsi,Due to Overall Poor Quality.Proprietary Documents Are Being Returned Under Separate Cover as Required Affidavits Were Not Provided ML20203F4661998-01-30030 January 1998 Requests That Staff Ask Us Ecology,In Coordination W/Portland General Electric Co,To Perform Comprehensive & Defensible Pathways Analysis to Demonstrate Suitability of Proposed Wastes for Disposal at Hanford Disposal Site ML20199D7481998-01-23023 January 1998 Forwards Omitted Cover Page for Insp Rept 50-344/97-05 on 971201-03 ML20199F0021998-01-23023 January 1998 Forwards Omitted Page of Insp Rept 50-344/97-05 ML20199F0241998-01-15015 January 1998 Forwards Insp Rept 50-344/97-05 on 971201-03 & Notice of Violation.Areas Reviewed as Part of Insp Included;Sfp TS Compliance,Cold Weather Preparations,Results of 1997 Emergency Exercise & Followup on Notification to NRC ML20198F7411998-01-0707 January 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-344/97-03. Implementation of Corrective Actions Will Be Reviewed During Future Insp to Determine That Compliance Achieved 1999-09-09
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April 10, 1986 j Docket No. 50-344 ' DISTRIBUTION Vocket File NRC PDR L PDR Gray File PAD-3 Rdg OELD Mr. Bart D. Withers H. Thompson T. Chan Vice President Nuclear K. Johnston C. Vogan Portland General Electric Company E. Jordan B. Grimes 121 S.W. Salmon Street J. Partlow ACRS 10 Portland, Oregon 97204
Dear Mr. Withers:
Enclosed for your information is the staff's review of the U.S. Army Corps of Engineers' (COE) study regarding possible flood levels at the Trojan Nuclear Plant. Results of the COE study showed higher flood levels, in some instances, than the Trojan design basis floud level of 45 feet, mean sea level.
We have determined that the condition for which the COE assumed would result in flood levels greater than the plant grade of 45 feet exceeded the staff's assumptions regarding the design basis flood. However, for the condition which.
is consistent with our design basis flood, water levels would reach plant grade. This level is 4 feet higher than the maximum water level assumed in the Final Safety Analysis Report (FSAR). This difference is attributed to the actual determination of the Columbia River's discharge profile and is considered more accurate than the projected discharge information used in the FSAR.
We' conclude that permanent flood protection in this case is not necessary;.
alternative measures have been suggested in the enclosure.
/s/TChan Terence L. Chan, Project Manager PWR Project Directorate No. 3 Division of PWR Licensing-A
Enclosure:
As stated l
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L See next page
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l OFFICIAL RECORD COPY 8604220416 860410
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.i Mr. Bart D. Withers Portland General Eletric Company Trojan Nuclear Plant cc:
Senior Resident Inspector U.S. Nuclear Regulatory Commission --
Trojan Nuclear Plant _
Post Office Box 0 Rainier, Oregon 97048 Robert M. Hunt, Chairman Board of County Commissioners
, Columbia County St. Helens, Oregon 97501 William T. Dixon Oregon Department of Energy i Labor and Industries Building t
Room 111 Salem, Oregon 97310 Regional Administrator, Region V U.S. Nuclear Regulatory Commission c
Office of Executive Director for Operations i
1450 Maria Lane Suite 210 l Walnut Creek, California 94596 i
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REVIEW 0F CORPS OF ENGINEERS REPORT CONCERNING FLOODING AT THE TROJAN NUCLEAR PLANT i
Background
The design basis flood considered by the staff in licensing the Trojan Nuclear Plant is the flood that would result from a catastr phic failure of Grand Coulee Dam, which is located on the Columbia River about 524 miles l upstream of Trojan. This flood would result in a maximum stillwater level
. of 41 feet at the Trojan Plant. To allow for higher water levels which could
[ result from wind generated water waves, the Trojan plant grade elevation was F
f set at 45 feet.
In 1982, the U.S. Army Corps of Engineers (COE) conducted inundation mapping studies for the lower Columbia River. The portion of the river li l studied included the reach of the river on which the Trojan Plant is s
located. The COE studies showed higher flood levels, in some instances, than the Trojan Plant design basis flood level of 45 feet msl.
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This report discusses the result of the staff's review of the COE report i
and the staff's conclusions regarding the safety of the Trojan Plant
- with res.pect to flooding.
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Purpose and Results of the COE Studies . . .
[ The COE studies were performed under the COE's Dam Safety Program to determine the extent of fleoding associated with hypothetical dam failures on the Columbia River. The studies reflect events of an extremely remote nature and as such are not intended in any way to I reflect upon the integrity of the dams included in the study.
. The purpose of the studies was to prepare inundation maps showing the i
extent of flooding associated with various postulated conditions at each i
of the lower Columbia River dam projects. In downstream order these projects are McNary, John Day, the Dalles, and Bonneville Dams. The Trojan Plant is located about 73 miles downstream of Bonneville Dam.
l For each of the dams considered by the COE, three postulated conditions j were analyzed as follows:
i CONDITION 1 Probable Maximum Flood (PMF) Without Dam Failure i For. this condition it was assumed that a PMF would occur on the lower Columbia River. With the exception of Bonneville Dam, all r
other dams were found capable of discharging the PMF without overtopping. The COE study concluded that because of its outdated N
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s hydrologic design, Bonneville Dam would be overtopped under PMF Conditions. Under conditions of overtopping, Bonneville dam was assumed to fail, f CONDITION 2 Probable Maximum Flood (PMF) With Dam Failure Although none of the dams except Bonneville would be overtopped by
( the PMF, the COE in this scenario assumed that all dams would fail
. during the PMF. The dam failures were modeled using the National Weather Service (NWS) DAMBRK computer model. The outflow
! hydrographs were routed downstream through the Bonneville i
! tailwater. The Bonneville hydrograph was then routed down the Columbia River past the Trojan Plant to the Pacific Ocean using the NWS DWOPER unsteady flow model.
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I CONDITION 3 Dam Failure at Normal High Pool Level b
3 This condition assumed that a dam failure would occur during the i
spring normal high pool. The flood hydrograph from each failed dam i
was routed downstream to the Pacific Ocean using the same NWS
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1 For the three conditions described above, the COE computed water surface elevations using cross-sections along the lower Columbia River.,_These elevations were then used to develop floodplain maps for the reach of the Columbia River extending from McNary dam to the Pacific Ocean.
1 k Staff Review of COE Studies i
s General Design Criteria (GDC-2), " Design Basis for Protection Against 4
Natural Phenomena," requires that structures, systems and components important to safety be designed to withstand the effects of natural phenomena such as floods. Regulatory Guide (RG) 1.59, " Design Basis i Floods for Nuclear Power Plants," describes combinations of flood-causing events which provide adequate design flood bases to meet the requirements
!- of GDC-2. With the exception of Bonneville Dam, all of the dams studied t
by the COE can safely pass their respective PMF's without be(ng over-0 topped. Therefore, hydrologic events would not cause any of the dams, j except Bonneville, to fail. Dam failures then, would have to be caused i .
! by seismic or other non-hydrologic events.
I I i RG 1.59 suggests that a 25 year flood be considered coincident with a non-hydrologic dam failure. Therefore, considering a PMF coincident with a dam failure, as was done by the COE in condition 2, is a sequence of events more severe than required to be considered for a design basis flood because a PMF'is a much more severe event than a 25 year flood.
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i The COE study determined flood levels at cross-sections located both ,
upstream and downstream of the Trojan Plant. The cross-sectioni closest to the Trojan Plant are at river miles 66.1 and 75. Water surface elevations at the Trojan Plant, which is located at river mile 72.4 were
determined by interpolation by the NRC staff. The tabulation below shows interpolated flood elevations at the Trojan site for the three conditions considered by the COE.
Columbia River Water Surface Elevations in ft msl
- at the Trojan Plant Condition 2 Condition 3
. Condition 1 .PMF with PMF Dam Failure PMF without multiple at normal high Dam dam failure dam failure pool level P McNary 45 48 16 s John Day 45 47 19
- The Dalles 45 45 12
' - Bonneville 45 45 12 j This tabulation shows that for Condition 2, flood levels would equal or exceed the Trojan Plant grade elevation of 45 feet. However, as discussed above, Condition 2 floods are of greater magnitude than floods which have to be considered for design of nuclear power plants.
i Condition 1 floods, which are consistent with design bases floods, would result in water levels of 45 feet for all scenarios considereLby the COE.
Although this elevation is the same as the plant grade elevation, wind generated waves coul'd cause water levels to exceed plant grade elevation and potentially affect the safe operation of the plant. ;
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The Columbia River drainage basin is very large, comprised of an area of
' approximately 260,000 square miles. The upper reaches of the drainage area are bounded by the Rocky Mountains on the east and the Cascade Range I on the west. It is in these mountainous areas that snow can accumulate in the winter months and contribute to high river flows when the snow
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melts in the spring. A PMF on the Columbia River would result from rapid melting of an extraordinarily large and extensive snow pack. Such a snow
- pack would be evident several months before actual melting occurred.
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Flood forecasts for the Columbia River are made through the cooperative effort of the Columbia River Water Management Group (CRWMG). This group consists of representatives of eleven federal agencies and from the states that border the Columbia River. As part of the flood forecasting I
- program, the Soil Conservation Service (SCS) regularly conducts airplane flights over the Columbia River basin during the winter months to determine depth and extent of snow pack. Using tFe information obtained during these snow flights, the COE is able to forecast potential river I .
floods, weeks or even months before they actually occur.
i Staff Conclusions Since the Trojan Plant grade elevation of 45 feet is the same as the COE's predicted PMF level, only the effects of water waves running up on safety-related structures are of concern. However, since potential floods can be forecast well in advance of their occurrence, there would l
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be sufficient time for the licensee to implement some temporary actions to protect any safety-related structures or equipment which coul.d be adversely affected by flooding. Thus the staff concludes that permanent flood protection measures are not necessary. However, it would be prudent for the licensee to determine if wind wave runup could adversely affect the safe operation and shutdown of the plant. If the conclusion is that there would be no adverse effects, the basis for the conclusion should be provided. Otherwise, an operating procedure to define the f
- j. actions to be taken in the event of an impending PMF on the Columbia River should be developed. These procedures should as a minimum identify the actions to be.taken and the event that will initiate implementation of those actions. An example of such an event could be a flood level in
! Bonneville or other upstream impoundments or a discharge from the dams or l any other measurable activity that could be identified with sufficient warning time to permit implementation of protective plans at the Trojan Plant before the actual flood occurred. In addition, the procedures l should describe the level to which ficod protection would be provided at the plant and identify the safety-related structures, systems or components that would have to be protected.
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