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MONTHYEARML20205M3491986-04-11011 April 1986
Proposed Tech Specs Deleting Fuel Rod Weight Limit in Section 5.3.1
Project stage: Other
ML20205M3401986-04-11011 April 1986
License Change Application 139 for Amend to License NPF-1, Deleting Fuel Rod Weight Limit in Tech Spec Section 5.3.1
Project stage: Other
ML20205M3351986-04-11011 April 1986
Forwards License Change Application 139 for Amend to License NPF-1,deleting Fuel Rod Weight Limit in Tech Spec Section 5.3.1.Fee Paid
Project stage: Other
ML20206F1101986-06-0909 June 1986
Forwards Amend 116 to License NPF-1 & Safety Evaluation. Amend Removes Max Total Fuel Rod Weight Limit of 1,760 G U from Section 5.3.1 of Tech Specs
Project stage: Approval
1986-04-11
[Table View] |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20204B7691999-03-18018 March 1999
Proposed Tech Specs 5.6 Re High Radiation Area.Certificate of Svc,Encl
ML20207J0831999-02-11011 February 1999
Proposed Tech Specs for Trojan Isfsi,Stating Length of Time Air Pads Can Be Installed & Inflated
ML20151X8671998-09-10010 September 1998
Rev 2 to Proposed TS Bases,Changing Name of Cooling Sys to Modular Spent Fuel Pool Cooling & Cleanup Sys & Updates Spent Fuel Pool Heat Up Info to 3 1/2 Years After Plant Shutdown
ML20238E8291998-08-27027 August 1998
Proposed Tech Specs,Deleting Number of License Conditions & TS Requirements as Prerequisite to Implementing Requested Amend to Transfer Nuclear Sf from Existing 10CFR50 Licensed Area to Proposed 10CFR72,ISFSI Area
ML20199J5801998-01-29029 January 1998
Proposed Tech Specs Pages,Deleting Security Plan Requirements of 10CFR50.54(p) & Part 73 for Trojan Plant After Spent Nuclear Fuel Is Moved to Proposed ISFSI Area
ML20134C9901997-01-28028 January 1997
Proposed Tech Specs 5.0 Re Administrative Controls
ML20134A9571997-01-16016 January 1997
Proposed Tech Specs LCO 3.1.4 Re Spent Fuel Pool Load Restrictions
ML20134B5881997-01-16016 January 1997
Proposed Tech Specs Deleting Paragraph 2.(C)(7) to Allow Loading & Handling of Spent Fuel Casks & Insertion of New License Condition Authorizing Loading of Spent Fuel & Other Matls in Fuel Building
ML20134B8631997-01-16016 January 1997
Proposed Tech Specs Re Delete Paragraph 2.(C)(7) to Allow pre-operational Testing & Load Handling of Spent Fuel Transfer & Storage Casks in Trojan Fuel Building
ML20135B5071996-11-27027 November 1996
Proposed Tech Specs Reflecting New Fuel Debris Storage Container Design & Storage of non-fuel Bearing Components & Fuel Rod Storage Container in Trojan ISFSI
ML20129E7341996-10-23023 October 1996
Proposed Tech Specs Re Spent Fuel Pool Debris Processing
ML20059A5601993-10-21021 October 1993
Proposed Tech Specs Modifying Security License Conditions for Clarity
ML20127P2121993-01-27027 January 1993
Proposed TS 6.2.2.f Re Composition of Fire Brigade & TS Table 6.2-1 Re Min Shift Crew Composition for Shift Manager & Noncertified Operator
ML20127M6391992-11-16016 November 1992
Proposed Tech Specs for Deferral of Unscheduled Steam Generator ISI
ML20141M1901992-03-27027 March 1992
Proposed Tech Specs Re Surveillance Requirements for Lco. Response to Request for Addl Info on Subj Encl
ML20059L6701990-09-21021 September 1990
Proposed Tech Spec Table 3.6-1, Containment Isolation Valves
ML20247C8941989-07-19019 July 1989
Proposed Tech Spec Table 3.6-1, Containment Isolation Valves
ML20245C8091989-06-12012 June 1989
Proposed Tech Specs,Changing Orifice Size of Steam Line Safety Valves Shown in Tech Spec Table 4.7-1, Steam Line Safety Valves Per Loop
ML20235L9441989-02-10010 February 1989
Proposed Tech Specs,Allowing Mods to Control Auxiliary Fuel Bldg Complex Resulting in Increase in Lateral Shear Forces on Any Story
ML20235Q9191989-02-10010 February 1989
Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements for Containment Integrity for Equipment Hatches
ML20154D1781988-09-0909 September 1988
Proposed Tech Specs Revising Pressurizer LPSI Setpoint
ML20151T5951988-08-12012 August 1988
Proposed Tech Specs,Revising Surveillance Requirements for ECCS Check Valves
ML20151A0381988-07-0808 July 1988
Proposed Tech Specs Re Radioactive Gaseous Effluents & Radioactive Liquid Waste Sampling & Analysis Program
ML20151U7171988-04-14014 April 1988
Revised Proposed Tech Specs Re Plant Sys,As Part of Rev 1 to License Change Application 142
ML20148K5971988-03-23023 March 1988
Proposed Revised Tech Specs Re RCS
ML20148C2101988-03-18018 March 1988
Proposed Tech Specs,Reflecting Revised Offsite & Facility Organization Charts
ML20196J9031988-03-0101 March 1988
Proposed Tech Specs Modifying OL NPF-1,removing 3.5% U-235 Limit on Reactor Fuel Assemblies & Increase Enrichment Limit for New Fuel Storage Racks to 4.5%.Certificate of Svc Encl
ML20147E7371988-03-0101 March 1988
Proposed Tech Specs Re Containment Isolation Valves
ML20149K1901988-02-17017 February 1988
Proposed Tech Specs,Adding New Instruments for Monitoring Steam Generator Blowdown Sys Liquid Effluent Radioactivity
ML20149L6981988-02-15015 February 1988
Proposed Tech Specs Re Offsite & Facility Organization Charts.Util Certificate of Svc Encl
ML20149H1121988-02-0404 February 1988
Proposed Tech Specs Revising Operability & Surveillance Requirements for Component Cooling Water Sys
ML20147D4561988-01-15015 January 1988
Proposed Tech Specs,Revising Offsite & Facility Organization Charts
ML20195H8971987-12-24024 December 1987
Proposed Tech Specs Deleting Sections Re Fire Protection
ML20237D6971987-12-18018 December 1987
Proposed Tech Specs,Requiring Measurement of Initial Discriminator Bias Curve for Each Detector & Subsequent Discrimination Bias Curves Obtained,Evaluated & Compared to Initial Curves
ML20237D6551987-12-16016 December 1987
Proposed Tech Specs Deleting Provision for Continued Plant Operation in Section 3/4.4.6.2 & Requiring Prompt Unit Placement in Cold Shutdown After Pressure Boundary Leakage Occurrence
ML20236W7611987-11-20020 November 1987
Proposed Tech Specs Including Effects of Nuclear Fuel Design Changes
ML20236Q2271987-11-16016 November 1987
Proposed Tech Specs,Resolving Control Room Habitability Issues
ML20236P4391987-11-13013 November 1987
Proposed Tech Specs,Extending Surveillance Time Period for Verifying Control Rod Insertability During Control Rod Worth & Shutdown Margin Tests to 7 Days.Certificate of Svc Encl
ML20236N3861987-11-0909 November 1987
Proposed Tech Spec,Revising Tech Spec 3.9.9 to Resolve Inconsistencies within Tech Specs.W/Certificate of Svc
ML20236N5881987-08-0606 August 1987
Proposed Tech Spec Section, Bases Correcting Section for Agreement W/Definition of Pressure Boundary Leakage
ML20235W5571987-07-14014 July 1987
Proposed Tech Specs Re Solid Radwaste Sys
ML20215K8381987-06-22022 June 1987
Proposed Tech Spec Table 3.3-1,revising Operability Requirements for Reactor Trip Breakers & 4.3-1,revising Surveillance Requirements for Manual Reactor Trip,Reactor Trip Breakers & Bypass Breakers
ML20210B6241987-04-29029 April 1987
Proposed Tech Specs Revising Typos & Clarifying Appropriate Process to Be Used for Review & Approval of Temporary Changes to Procedures.Certificate of Svc Encl
ML20209D0251987-04-20020 April 1987
Proposed Tech Specs Re RCS Surveillance Requirements
ML20206D9261987-04-0303 April 1987
Revised Tech Spec Pages 3/4 8-6 & 3/4 8-7 Re Onsite Power Distribution Sys,Per License Change Application 128
ML20206A6221987-04-0303 April 1987
Revised Tech Spec Page 7,clarifying License Change Application 124 Re power-operated Valves
ML20245A2631987-02-26026 February 1987
Proposed Tech Specs,Consisting of Revised Pages for License Change Application 124 & License Change Application 135, Adding Steamline Isolation Valves & Valve CV-8825 Back Onto Table 3.6-1 & Excluding Containment Airlocks from Criteria
ML20211P0031987-02-20020 February 1987
Proposed Tech Specs Re Steam Generator Tube Plugging Criteria in Tube Sheet Region
ML20211H4021987-02-11011 February 1987
Proposed Tech Specs Increasing Setpoint Tolerance for Pressurizer & Main Steam Safety Valves from 1% to 2%
ML20207Q5371987-01-20020 January 1987
Proposed Tech Specs,Revising Surveillance Requirements for Safety Injection Sys Accumulator Isolation Valves
1999-03-18
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210M7291999-08-0505 August 1999
Replacement Pages to PGE-1078, Trojan Nuclear Plant License Termination Plan. with D&D Modeling Runs for Determination of Screening Dcgls & Survey Area Maps Indicating Preliminary Survey Units
ML20207D3951999-06-0101 June 1999
Rev 1 to Trojan Nuclear Plant Reactor Vessel & Internals Removal Project Transportation Safety Plan
ML20204B7691999-03-18018 March 1999
Proposed Tech Specs 5.6 Re High Radiation Area.Certificate of Svc,Encl
ML20207J3911999-03-10010 March 1999
Trojan Nuclear Plant License Termination Plan
ML20207J0831999-02-11011 February 1999
Proposed Tech Specs for Trojan Isfsi,Stating Length of Time Air Pads Can Be Installed & Inflated
ML20153D3081998-09-21021 September 1998
Rev 0 to PGE-1077, Tnp Reactor Vessel & Internals Removal Project Transportation Safety Plan
ML20151X8671998-09-10010 September 1998
Rev 2 to Proposed TS Bases,Changing Name of Cooling Sys to Modular Spent Fuel Pool Cooling & Cleanup Sys & Updates Spent Fuel Pool Heat Up Info to 3 1/2 Years After Plant Shutdown
ML20238E8291998-08-27027 August 1998
Proposed Tech Specs,Deleting Number of License Conditions & TS Requirements as Prerequisite to Implementing Requested Amend to Transfer Nuclear Sf from Existing 10CFR50 Licensed Area to Proposed 10CFR72,ISFSI Area
ML20199J5801998-01-29029 January 1998
Proposed Tech Specs Pages,Deleting Security Plan Requirements of 10CFR50.54(p) & Part 73 for Trojan Plant After Spent Nuclear Fuel Is Moved to Proposed ISFSI Area
ML20196J5131997-07-29029 July 1997
Rev 0 to Trojan Second Integrated Test Rept,Filter Media Processing Sys Trojan Nuclear Plant Spent Fuel Pool Debris Project
ML20196J5241997-07-29029 July 1997
Rev 2 to In-Canal Equipment,Filter Media Processing Sys, Trojan Nuclear Plant Spent Fuel Pool Debris Project
ML20137T9361997-04-0808 April 1997
Rev 1 to Trojan Proof of Principle Test Summary
ML20137G1731997-03-20020 March 1997
Rev 6 to Trojan Plant Procedure,Tpp 20-2, Radiation Protection Program
ML20137K5151997-03-0404 March 1997
Rev 0 to Trojan Proof of Principle Test Summary
ML20138L1901997-01-30030 January 1997
Reactor Vessel & Internals Removal Plan
ML20134C9901997-01-28028 January 1997
Proposed Tech Specs 5.0 Re Administrative Controls
ML20134B8631997-01-16016 January 1997
Proposed Tech Specs Re Delete Paragraph 2.(C)(7) to Allow pre-operational Testing & Load Handling of Spent Fuel Transfer & Storage Casks in Trojan Fuel Building
ML20134B5881997-01-16016 January 1997
Proposed Tech Specs Deleting Paragraph 2.(C)(7) to Allow Loading & Handling of Spent Fuel Casks & Insertion of New License Condition Authorizing Loading of Spent Fuel & Other Matls in Fuel Building
ML20134A9571997-01-16016 January 1997
Proposed Tech Specs LCO 3.1.4 Re Spent Fuel Pool Load Restrictions
ML20135B5071996-11-27027 November 1996
Proposed Tech Specs Reflecting New Fuel Debris Storage Container Design & Storage of non-fuel Bearing Components & Fuel Rod Storage Container in Trojan ISFSI
ML20129E7341996-10-23023 October 1996
Proposed Tech Specs Re Spent Fuel Pool Debris Processing
ML20059L1721993-11-30030 November 1993
Final Update to PGE-1043,Amend 3, Accident Monitoring Instrumentation Review, Identifying Rept as Historical by Placing Explanation in Preface to Be Inserted at Front of Document
ML20059A5601993-10-21021 October 1993
Proposed Tech Specs Modifying Security License Conditions for Clarity
ML20057F1631993-09-30030 September 1993
Updated Trojan Nuclear Div Manual
ML20057D9131993-09-30030 September 1993
Amend 14 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan. W/Four Oversize Drawings
ML20056F9971993-08-26026 August 1993
Rev 9 to Odcm
ML20127P2121993-01-27027 January 1993
Proposed TS 6.2.2.f Re Composition of Fire Brigade & TS Table 6.2-1 Re Min Shift Crew Composition for Shift Manager & Noncertified Operator
ML20126B7231992-12-0303 December 1992
Rev 13 to Chemistry Manual Procedure CMP 1, Primary-to-Secondary Leak Rate
ML20127M6391992-11-16016 November 1992
Proposed Tech Specs for Deferral of Unscheduled Steam Generator ISI
ML20126B7491992-09-25025 September 1992
Rev 7 to Event-Specific Emergency Instruction ES-3.3, Post- SG Tube Rupture Cooldown Using Steam Dump
ML20126B7061992-09-25025 September 1992
Rev 7 to Emergency Contingency Action Procedure ECA-3.2, SG Tube Rupture W/Loss of Reactor Coolant - Saturated Recovery Desired
ML20126B7331992-09-25025 September 1992
Rev 7 to Emergency Contingency Action Procedure ECA-3.3, SG Tube Rupture W/O Pressurizer Pressure Control
ML20126B7411992-09-25025 September 1992
Rev 8 to Event-Specific Emergency Instruction ES-3.2, Post- Steam Generator Tube Rupture Cooldown Using SG Blowdown
ML20126B7451992-09-25025 September 1992
Rev 7 to Event-Specific Emergency Instruction ES-3.1, Post- SG Tube Rupture Cooldown Using Backfill
ML20126B7601992-09-25025 September 1992
Rev 18 to Emergency Instruction EI-3, SG Tube Rupture
ML20126B7181992-09-23023 September 1992
Rev 7 to Emergency Contingency Action Procedure ECA-3.1, SG Tube Rupture W/Loss of Reactor Coolant - Subcooled Recovery Desired
ML20126B7141992-08-20020 August 1992
Rev 19 to Off-Normal Instruction ONI-12, High Activity Radiation Monitoring
ML20210D5281992-06-0808 June 1992
Errata to Amend 6 to PGE-1025, Environ Qualification Program Manual
ML20141M1901992-03-27027 March 1992
Proposed Tech Specs Re Surveillance Requirements for Lco. Response to Request for Addl Info on Subj Encl
ML20126B7201992-01-24024 January 1992
Rev 2 to Off-Normal Instruction ONI-3-12, SG Tube Leak
ML20062F7391990-11-15015 November 1990
Amend 4 to PGE-1049, Trojan Nuclear Plant Inservice Insp Program for Second 10-Yr Interval,Jan 1987 - Dec 1996
ML20059L6701990-09-21021 September 1990
Proposed Tech Spec Table 3.6-1, Containment Isolation Valves
ML20247C8941989-07-19019 July 1989
Proposed Tech Spec Table 3.6-1, Containment Isolation Valves
ML20245C8091989-06-12012 June 1989
Proposed Tech Specs,Changing Orifice Size of Steam Line Safety Valves Shown in Tech Spec Table 4.7-1, Steam Line Safety Valves Per Loop
ML20247E5331989-03-29029 March 1989
Rev 0 to Procedure QTS-VT-100, Visual Exam Procedure
ML20248D3271989-03-27027 March 1989
Rev 0 to QAP-VT-108, Visual Exam
ML20247E5491989-03-0202 March 1989
Rev 0 to Procedure TNP-QAP-VT108, Visual Exam
ML20235L9441989-02-10010 February 1989
Proposed Tech Specs,Allowing Mods to Control Auxiliary Fuel Bldg Complex Resulting in Increase in Lateral Shear Forces on Any Story
ML20235Q9191989-02-10010 February 1989
Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements for Containment Integrity for Equipment Hatches
ML20154D1781988-09-0909 September 1988
Proposed Tech Specs Revising Pressurizer LPSI Setpoint
1999-08-05
[Table view] |
Text
F-LCA 139 Page 5 of 5 DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 60 psig and a temperature of 288'F.
PENETRATIONS 5.2.3 Penetrations through the reactor containment building are designed and shall be maintained in accordance with the original design provisions contained in Section 6.2.4 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.3 REACTOR CORE FUEL ASSEM8 LIES 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with 11rcaloy-4. Each fuel rod shall have a nominal active fuel length of 144 inches. The initial core loading l shall have a maximum enrichment of 3.15 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 3.5 weight percent U-235.
CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 53 full length control rod assemblies.
The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing. Eight part length control rod assemblies originally installed in the core contained a nominal 36 inches of absorber material at their lower ends. The part length control rod assemblies have been removed and are stored in the spent fuel pool.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant :ystem is designed and shall be maintained:
TROJAN-UNIT 1 5-4 Amendment No. 70 8604150196 860411 PDR
~
P ADOCK 05000344 PDR
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )
)
l PORTLAND GENERAL ELECTRIC COMPANY, ) Docket 50-344 i THE CITY OF EUGENE, OREGON, AND ) Operating License NPF-1 PACIFIC POWER & LIGHT COMPANY )
)
l (TROJAN NUCLEAR PLANT) )
CERTIFICATE OF SERVICE I hereby certify that copies of License Change Application 139 to the Operating License for Trojan Nuclear Plant, dated April 11, 1986, have been served on the following by hand delivery or by deposit in the United States mail, first class, this lith day of April 1986:
Mr. Lynn Frank, Director State of Oregon Department of Energy 625 Marion Street NE Salem OR 97310 Mr. Michael J. Sykes Chairman of County Commissioners Columbia County Courthouse St. Helens OR 97051
. w-
~G. . Zimmerman, Manager Nu ea r Regulation Branch Nuc en Safety & Regulation Subscribed and sworn to before me this lith day of April 1986.
Notary Public of Orej[on 9MyCommission e rea[ -
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