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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20210M5901999-08-0505 August 1999 Rev 1 to License Change Application 247,dtd 990310,for Amend to License NPF-1,adding License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan. with Certificate of Svc ML20196L1311999-05-24024 May 1999 Application for Amend to License NPF-1 for Indirect Transfer of License,To Extent That Such Approval Required Solely to Reflect Change in Upstream Operating Ownership of Pacificorp ML20207J3801999-03-10010 March 1999 Application for Amend to License NPF-1,adding License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan ML20198T1851999-01-0707 January 1999 Rev 3 to License Change Application 237 Re Spent Fuel Cask Loading in Fuel Bldg ML20198T1451999-01-0707 January 1999 Rev 3 to License Change Application 237 to License NPF-1, Inserting New License Condition to Authorize Loading of Spent Fuel & Other Matls Into Transtor Transfer & Storage Casks in Fuel Bldg ML20238E8261998-08-27027 August 1998 Application for Amend to License NPF-1,deleting Number of License Conditions & TS Requirements as Prerequisite to Implementing Requested Amend to Transfer of Nuclear Sf from Existing 10CFR50 Licensed Area to Proposed 10CFR72 ISFSI ML20199J5641998-01-29029 January 1998 Application for Amends to License NPF-1,deleting Security Plan Requirements of 10CFR50.54(p) & Part 73 for Trojan Plant After Spent Nuclear Fuel Is Moved to Proposed ISFSI Area ML20134C9781997-01-28028 January 1997 Application for Amend to License NPF-1,requesting to Clarify Controls That Will Be Used for Rev & Maint of Certified Fuel Handler Training Program ML20134A9531997-01-16016 January 1997 Application for Amend to License NPF-1,requesting Deletion of Paragaph 2.(C)(7) to Allow pre-operational Testing & Load Handling of Spent Fuel Transfer & Storage Casks in Trojan Fuel Bldg ML20134B7841997-01-16016 January 1997 License Change Application (Lca) 240 to License NPF-1.LCA Proposes to Delete Paragraph 2.(C)(7) to Allow Loading & Handling of Spent Fuel Casks in Trojan Fuel Bldg as Described in 10CFR72 License Application Submitted Mar 1996 ML20129E4751996-10-23023 October 1996 Application for Amend to License NPF-1,requesting Addition to Paragraph 2.(C)(8) to Allow Processing & Handling of Spent Fuel Pool Debris ML20059A5431993-10-21021 October 1993 Application for Amend to License NPF-1 to Modify Security License Condition for Clarity & Minimize Burden Associated W/Processing Application to Reflect Current Security Plan Rev ML20127P1691993-01-27027 January 1993 License Change Application 229 to License NPF-1,modifying OL to possession-only License to Allow Util to Possess SNM But Not Operate Nuclear reactor.Marked-up License NPF-1 Encl ML20127P2031993-01-27027 January 1993 License Change Application 230 to License NPF-1,revising Facility Staffing & Training Requirements in Light of Transition of Facility to Permanently Defueled Status ML20127M6361992-11-26026 November 1992 License Change Application 227 to License NPF-1,revising TS to Defer Unscheduled SG ISI Required by TS 4.4.5.3.c.1 Following primary-to-secondary Tube Leakage in Excess of TS Limits ML20141M1881992-03-27027 March 1992 Rev 1 to License Change Application 186 to License NPF-1, Changing TS 4.0.3 to Negatively State Failure to Perform Required Surveillances on Schedule Constitutes Noncompliance W/Operability Requirements of Lco,Per Generic Ltr 87-09 ML20059L6681990-09-21021 September 1990 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 ML20247C8771989-07-19019 July 1989 Application for Amend to License NPF-1 Consisting of License Change Application 179.Amend Changes Description of Turbine Steam Supply Valves in Tech Spec Table 3.6-1 from motor-operated to air-operated ML20246A7491989-06-30030 June 1989 Application for Amend to License NPF-1,consisting of License Change Application 182,reflecting Reorganization of Util Nuclear Div.Certificate of Svc & Description of Change Encl ML20244E6111989-06-12012 June 1989 Application for Amend to License NPF-1,changing Orifice Size of Steam Line Safety Valves Shown in Tech Spec Table 4.7-1, Steam Line Safety Valves Per Loop ML20235L9421989-02-10010 February 1989 Application for Amend to License NPF-1,consisting of License Change Application 174.Amend Revises Tech Specs to Allow Mods to Control Auxiliary Fuel Bldg Complex Resulting in Increase in Lateral Shear Forces of Any Story ML20235Q9101989-02-10010 February 1989 Application for Amend to License NPF-1,consisting of License Change Application 173,clarifying Surveillance Requirements for Containment Equipment Hatch ML20154D1681988-09-0909 September 1988 Application for Amend to License NPF-1,revising Tech Specs Re Setpoint for Pressurizer LPSI Ressure Safety Injection Necessary to Accommodate New Instrumentation ML20151T4991988-08-12012 August 1988 Application to Amend License NPF-1,consisting of License Change Application 169,revising Tech Specs Surveillance Requirements for ECCS Check Valves ML20151A0351988-07-0808 July 1988 Application for Amend to License NPF-1,incorporating Miscellaneous Editorial Corrections & Clarifications ML20148C2061988-03-18018 March 1988 Application for Amend to License NPF-1,consisting of License Change Application 162,Rev 2,revising Tech Specs Re Offsite & Facility Organization Charts ML20147E7291988-03-0101 March 1988 Application for Amend to License NPF-1,consisting of Rev 1 to License Change Application 124,revising Tech Specs Re Containment Isolation Valves ML20196J8861988-03-0101 March 1988 License Change Application 165 Requesting Amend to License NPF-1,modifying Tech Specs by Removing 3.5% U-235 Limit on Reactor Fuel Assemblies & Increase Enrichment Limit for New Fuel Storage Racks to 4.5% ML20149K1401988-02-17017 February 1988 Application for Amend to License NPF-1,consisting of License Change Application 163,revising Tech Specs to Add New Instruments for Monitoring Steam Generator Blowdown Sys Liquid Effluent Radioactivity & Flow Rate ML20149L6891988-02-15015 February 1988 Application for Amend to License NPF-1,consisting of Rev 1 to License Application 162,revising Offsite & Facility Organization Charts.Description of Requested Changes Encl ML20149H0921988-02-0404 February 1988 Application for Amend to License NPF-1,consisting of License Change Application 164.Amend Revises Operability & Surveillance Requirements & Bases for Component Cooling Water Sys ML20147D4431988-01-15015 January 1988 Application for Amend to License NPF-l Consisting of License Change Application 162,revising Offsite & Facility Organization Charts ML20195H8801987-12-24024 December 1987 Application for Amend to License NPF-1,consisting of License Change Application 151,removing Portions of Tech Specs Re Fire Protection & Relocating Them to Vol 1 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan.. ML20237D6801987-12-18018 December 1987 Application for Amend to License NPF-1 Consisting of License Change Application 160,changing Tech Specs to Delete Requirement for Obtaining source-range Nuclear Instrument Detector Plateau Curves ML20237D6471987-12-16016 December 1987 Application for Amend to License NPF-1 Consisting of Rev 1 to License Change Application 154,to Correct Tech Specs Section 3/4.4.6.2 for Agreement W/Definition of Pressure Boundary Leakage ML20236W7391987-11-20020 November 1987 License Change Application 161 for Amend to License NPF-1, Revising Tech Specs to Include Effects of Nuclear Fuel Design Changes ML20236Q2191987-11-16016 November 1987 Application for Amend to License NPF-1,consisting of Rev 1 to License Change Application 142,resolving Control Room Habitability Issues by Changing Tech Spec Sections Re Chlorine Detection Sys & Control Emergency Ventilation Sys ML20236P4371987-11-13013 November 1987 Application for Amend to License NPF-1,consisting of License Change Application 153,revising Tech Specs to Extend Surveillance Time Period for Verifying Control Rod Insertability from 24 H to 7 Days ML20236N3821987-11-0909 November 1987 Application for Amend to License NPF-1,consisting of License Change Application 159,revising Tech Spec 3.9.9 to Resolve Inconsistencies within Tech Specs ML20236N5761987-08-0606 August 1987 Application for Amend to License NPF-1,consisting of License Change Application 154,correcting Tech Spec Section, Bases for Agreement W/Definition of Pressure Boundary Leakage ML20235W5301987-07-14014 July 1987 Application for Amend to License NPF-1,consisting of License Change Application 155 Re Solid Radwaste Sys ML20215K8131987-06-22022 June 1987 Application for Amend to License NPF-1,consisting of License Change Application 132,revising Operability Requirements for Reactor Trip Breakers & Surveillance Requirements for Manual Reactor Trip & Breakers ML20210B5801987-04-29029 April 1987 Application for Amend to License NPF-1,consisting of License Change Application 156,revising Tech Specs to Correct Typos & to Clarify Appropriate Process Used for Review & Approval of Temporary Changes to Procedures ML20209D0031987-04-20020 April 1987 Supplemental Application for Amend to License NPF-1, Incorporating License Change Application 152 Re Unneccessary Plugging of Steam Generator Tubes Which Increases Personnel Exposure & Reduces RCS Flow ML20212E2321987-02-26026 February 1987 Application for Amend to License NPF-1,consisting of Revised Pages for License Change Application 124 & License Change Application 135,adding Steamline Isolation Valves & Valve CV-8825 Back Onto Tech Spec Table 3.6-1 ML20211N9551987-02-20020 February 1987 Application to Amend License NPF-1,revising Steam Generator Tube Plugging Criteria in Tube Sheet Region.Fee Paid ML20211H3791987-02-11011 February 1987 License Change Application for Amend to License NPF-1, Increasing Setpoint Tolerance for Pressurizer & Main Steam Safety Valves from 1% to 2% 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 ML20207M5741987-01-0909 January 1987 Application for Amend to License NPF-1,consisting of Rev 1 to License Change Application 134,revising Min Contained Vol of Water Required in Condensate Storage Tank ML20215D2431986-12-12012 December 1986 Application for Amend to License NPF-1,consisting of License Change Application 127,separating Surveillance Requirement 4.7.3.1.c Into 4.7.3.1.c & 4.7.3.1.d & Listing Four Component Cooling Water Valves W/Modified Closure Signals 1999-08-05
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20210M5901999-08-0505 August 1999 Rev 1 to License Change Application 247,dtd 990310,for Amend to License NPF-1,adding License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan. with Certificate of Svc ML20196L1311999-05-24024 May 1999 Application for Amend to License NPF-1 for Indirect Transfer of License,To Extent That Such Approval Required Solely to Reflect Change in Upstream Operating Ownership of Pacificorp ML20206H4411999-05-0505 May 1999 Amend 201 to License NPF-1,revising PDTSs by Deleting ISFSI Area,Changes Also Revise TSs by Revising Subsection 4.1.1 & Replacing Existing Figure 4.1-1 with New Figure 4.1-1 & Adding New Page to Figure 4.1-1 as Listed ML20206C9301999-04-23023 April 1999 Amend 199 to License NPF-1,changes License NPF-1 by Adding New License Condition Entitled, Loading of Fuel Into Casks in Fuel Building ML20206C9701999-04-23023 April 1999 Amend 200 to License NPF-1,changes License by Revising License Condition 2.C.(10), Loading of Fuel Into Casks in Fuel Building ML20207J3801999-03-10010 March 1999 Application for Amend to License NPF-1,adding License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan ML20198T1451999-01-0707 January 1999 Rev 3 to License Change Application 237 to License NPF-1, Inserting New License Condition to Authorize Loading of Spent Fuel & Other Matls Into Transtor Transfer & Storage Casks in Fuel Bldg ML20198T1851999-01-0707 January 1999 Rev 3 to License Change Application 237 Re Spent Fuel Cask Loading in Fuel Bldg ML20238E8261998-08-27027 August 1998 Application for Amend to License NPF-1,deleting Number of License Conditions & TS Requirements as Prerequisite to Implementing Requested Amend to Transfer of Nuclear Sf from Existing 10CFR50 Licensed Area to Proposed 10CFR72 ISFSI ML20199J5641998-01-29029 January 1998 Application for Amends to License NPF-1,deleting Security Plan Requirements of 10CFR50.54(p) & Part 73 for Trojan Plant After Spent Nuclear Fuel Is Moved to Proposed ISFSI Area ML20148K3491997-06-0909 June 1997 Amend 198 to License NPF-1,revising possession-only License to Add Sf Debris in Plant Fuel Bldg ML20148D2551997-05-23023 May 1997 Amend 197 to License NPF-1,revising Permanently Defueled TS to Delete Requirement for NRC Prior Approval of Changes to Certified Fuel Handler Training Program ML20141H3031997-05-19019 May 1997 Amend 196 to License NPF-1,revising License to Delete Prohibition on Moving Spent Fuel Assembly Shipping Cask Into Fuel Building ML20137K5521997-03-31031 March 1997 Application for Coc 9271,requesting Approval to Allow one- Time Shipment of Trojan Rv Package as Type B Exclusively for Radioactive Matl Transportation Package ML20134C9781997-01-28028 January 1997 Application for Amend to License NPF-1,requesting to Clarify Controls That Will Be Used for Rev & Maint of Certified Fuel Handler Training Program ML20134B7841997-01-16016 January 1997 License Change Application (Lca) 240 to License NPF-1.LCA Proposes to Delete Paragraph 2.(C)(7) to Allow Loading & Handling of Spent Fuel Casks in Trojan Fuel Bldg as Described in 10CFR72 License Application Submitted Mar 1996 ML20134B5761997-01-16016 January 1997 Application for Amend to License NPF-1,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 ML20134A9531997-01-16016 January 1997 Application for Amend to License NPF-1,requesting Deletion of Paragaph 2.(C)(7) to Allow pre-operational Testing & Load Handling of Spent Fuel Transfer & Storage Casks in Trojan Fuel Bldg ML20134F1061996-10-31031 October 1996 Amend 195 to License NPF-1,revising Section 5.0,ACs,of Plant Permanently Defueled Tss,App A,To Reflect Organization Changes of Licensee,As They Apply to Oversight & Mgt of Plant ML20129E4751996-10-23023 October 1996 Application for Amend to License NPF-1,requesting Addition to Paragraph 2.(C)(8) to Allow Processing & Handling of Spent Fuel Pool Debris ML20058K1281993-12-0606 December 1993 Amend 193 to License NPF-1,relocating RETS to ODCM & PCP in Accordance W/Gl 89-01 & Changing Required Frequency for Submittal of Radioactive Effluent Release Rept from Semiannual to Annual ML20059A5431993-10-21021 October 1993 Application for Amend to License NPF-1 to Modify Security License Condition for Clarity & Minimize Burden Associated W/Processing Application to Reflect Current Security Plan Rev ML20057D0771993-09-22022 September 1993 Amend 192 to License NPF-1,relocating Portions of Plant TS Re Plant Fire Protection Program from TS to Topical Rept PGE-1012 ML20128K1001993-02-11011 February 1993 Corrected TS Page 3/4 3-49a to Amend 189 to License NPF-1, Reflecting Correct Spelling of Kziu in Items 4.c & 6.c ML20127P1691993-01-27027 January 1993 License Change Application 229 to License NPF-1,modifying OL to possession-only License to Allow Util to Possess SNM But Not Operate Nuclear reactor.Marked-up License NPF-1 Encl ML20127P2031993-01-27027 January 1993 License Change Application 230 to License NPF-1,revising Facility Staffing & Training Requirements in Light of Transition of Facility to Permanently Defueled Status ML20127P5741993-01-26026 January 1993 Amend 189 to License NPF-1,revising Plant TS 3/4.3.3.7, Fire Protection Instrumentation ML20125B8031992-12-0404 December 1992 Amend 188 to License NPF-1,deleting License Condition 2.C.(11) Re Fuel Assemblies ML20127M6361992-11-26026 November 1992 License Change Application 227 to License NPF-1,revising TS to Defer Unscheduled SG ISI Required by TS 4.4.5.3.c.1 Following primary-to-secondary Tube Leakage in Excess of TS Limits ML20141M1881992-03-27027 March 1992 Rev 1 to License Change Application 186 to License NPF-1, Changing TS 4.0.3 to Negatively State Failure to Perform Required Surveillances on Schedule Constitutes Noncompliance W/Operability Requirements of Lco,Per Generic Ltr 87-09 ML20059L6681990-09-21021 September 1990 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 ML20059C7901990-08-27027 August 1990 Amend 162 to License NPF-1,revising Tech Spec 3/4.6.1, Containment Integrity ML20058L4511990-08-0202 August 1990 Corrected Amend 161 to License NPF-1,revising Items 6.4.1 & 6.4.2 Re Administrative Controls ML20055C7511990-06-18018 June 1990 Amend 161 to License NPF-1,changing Qualification Requirements,As Specified in Tech Spec 6.3.1,that Must Be Met by Radiation Protection Manager ML20245H3661989-08-10010 August 1989 Corrected Page 3/4 7-18 to Amend 152 to License NPF-1 ML20247C8771989-07-19019 July 1989 Application for Amend to License NPF-1 Consisting of License Change Application 179.Amend Changes Description of Turbine Steam Supply Valves in Tech Spec Table 3.6-1 from motor-operated to air-operated ML20246A7491989-06-30030 June 1989 Application for Amend to License NPF-1,consisting of License Change Application 182,reflecting Reorganization of Util Nuclear Div.Certificate of Svc & Description of Change Encl ML20245E6491989-06-20020 June 1989 Amend 154 to License NPF-1,revising Tech Spec 5.7.2.2 to Allow Mods to control-auxiliary-fuel Bldg Complex ML20244E6111989-06-12012 June 1989 Application for Amend to License NPF-1,changing Orifice Size of Steam Line Safety Valves Shown in Tech Spec Table 4.7-1, Steam Line Safety Valves Per Loop ML20247M9211989-05-24024 May 1989 Amend 153 to License NPF-1,permitting Use of Upgraded Fuel Assemblies Which Incorporate Features of Westinghouse VANTAGE5 Fuel Assemblies & Allowing Extended Fuel Burnup to 60 Gwd/Mt & Higher Nuclear Peaking Factors ML20247H9521989-05-15015 May 1989 Amend 152 to License NPF-1,revising Tech Specs Re Chlorine Detection Sys & Control Room Emergency Ventilation Sys ML20246P5991989-05-12012 May 1989 Corrected Amend 58 to License NPF-1,consisting of Tech Spec Page 3/4 1-15 Re Borated Water Sources During Shutdown ML20247F1871989-03-17017 March 1989 Amend 151 to License NPF-1,revising Tech Specs by Deleting U-235 Fuel Enrichment Limit on Fuel Assemblies & Authorizing Storage & Use of New Fuel Assemblies W/Enrichment Up to 4.5 Weight Percent ML20236C4651989-03-15015 March 1989 Corrected Tech Spec Page 3/4 3-47 to Amend 93 to License NPF-1 ML20235T5291989-02-28028 February 1989 Amend 150 to License NPF-1,reflecting Merger of Pacific Power & Light & Utah Power & Light Companies to Form Pacificorp ML20235L9421989-02-10010 February 1989 Application for Amend to License NPF-1,consisting of License Change Application 174.Amend Revises Tech Specs to Allow Mods to Control Auxiliary Fuel Bldg Complex Resulting in Increase in Lateral Shear Forces of Any Story ML20235Q9101989-02-10010 February 1989 Application for Amend to License NPF-1,consisting of License Change Application 173,clarifying Surveillance Requirements for Containment Equipment Hatch ML20154D1681988-09-0909 September 1988 Application for Amend to License NPF-1,revising Tech Specs Re Setpoint for Pressurizer LPSI Ressure Safety Injection Necessary to Accommodate New Instrumentation ML20151X1121988-08-17017 August 1988 Corrected Page to Amend 142 of License NPF-1 Re Administrative Controls ML20151T4991988-08-12012 August 1988 Application to Amend License NPF-1,consisting of License Change Application 169,revising Tech Specs Surveillance Requirements for ECCS Check Valves 1999-08-05
[Table view] |
Text
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.3 ATTACHMENTI to VPN-007-99 LICENSE CHANGE APPLICATION (LCA) 247-LICENSE AMENDMFNT FOR APPROVAL OF PGE-1078,
" TROJAN NUCLEAR PLANT LICENSE TERMINATION PLAN" I
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LICENSE CHANGE APPLICATION (LCA) 247 i LICENSE AMENDMENT FOR APPROVAL' OF PGE-1078, l
" TROJAN NUCLEAR PLANT LICENSE TERMINATION PLAN" i L
1 TABLE OF CONTENTS Background and Reason for the Change ...................................................................... .................... 2 ;
Descripti on o f C hange . .... . ..... . .. . . ... ..... ... .... . . . .. .. . . ...... .. . .. . .. . .. .... . . . .. ....... . . . . ... ... . .. ... .. . . . .. . . .. . ... . . . . . .. ... . . .. . 2 i
i No Signincant Hazards Consideration Determination..................................................... ................ 3 i o
- Environmental Impact Consideration Determination ............................................................ .......... 4 5 S ched ule Consideration . . . . . .. . . . .. . . . .. .. . ... . . . .. . .. . . . . . . .. . . .. .. . .. .. .. ... . .. ... .. .. . .... . .. . . . . .. .. ........ .. . . ....... . . .. ..... . .. .. . .. 5 d
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, . March 10,1999 Faae 2 of 5 j u :
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- 1. Background and Reason for the Change Portland General Electric Company (PGE) announced permanent cessation of power operations of the Trojan Nuclear Plant (TNP) on January 4,1993. PGE submitted a proposed TNP Decommissioning Plan and Environmental Report Supplement on January 26,1995, which were approved by the Nuclear Regulatory Commission (NRC) on April 15,1996. The facility currently
' is undergoing active decontamination and dismantlement in accordance with the approved TNP ,
Decommissioning Plan. ,
, l The TNP Decommissioning Plan was submitted and approved in accordance with the NRC's rule governing decommissioning and termination oflicense,10 CFR 50.82, " Application for !
Termination of License." This rule has since been revised. The revised rule, specifically 10 CFR 50.82(aX9), requires all power reactor licensees to submit a license termination plan, i either prior to or with the licensee's application for license termination, for NRC approval at least -
- two years before termination of the license date. Attachment III to PGE letter VPN-007-99 submits for NRC approval PGE-1078, " Trojan Nuclear Plant License Termination Plan."
Therefore, VPN-007-99, Attachment III, as submitted to the NRC on March 10,1999, satisfies the requirement of10 CFR 50.82(aX9).
10 CFR 50.82(aX10) also stipulates that the License Termination Plan shall be approved by license amendment, subject to such conditions and limi*.ations as the NRC deems appropriate and necessary. !Ihis proposed license change, provided as Attachments I and II to VPN-007-99, is submitted to satisfy the requirerr' nt of 10 CFR 50.82(aX10) for approval of the License .;
Termination Plan by license amendment. . !
- 2. Description of Change !
PGE proposes to amend the license to incorporate a new License Condition 2.C(11).
Attachment II contains the annotated License Conditions page.
The current license, which includes license amendments through Amendment 198, contains 1:ine
' License Conditions in Section 2.C. LCA 237, submitted by VPN-005-99," License Change :
Application (LCA) 237, Revision 3, Spent Fuel Cask Loading in the Fuel Building," dated January 7,1999, proposes to add a License Condition 2.C(10). LCA 237 is anticipated to be implemented prior to this LCA 247. Therefore, this proposed license change will be assigned the next sequential number, anticipated to be License Condition 2.C(11), as follows:
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- iAttachment I VPN-007-99 March'10,1999 -
Page 3 of 5-
"(II) ' License Termination
- The licensee shall implement and maintaF 4 effect all provisions of the approved License Termination Plan as described in PGE-10 N, " Trojan Nuclear Plant License Termination Plan," and as approved in the SER dated - .' The licensee may make changes to POE-1078 without prior rpproval provided the proposed changes do not:
(a) Involve an unreviewed safety question or changes to the technical specifications as specified in 10 CFR 50.59; or (b) 1 Violate the requirements of 10 CFR 50.82(a)(6)."
3.- No Significant Hazards Consideration Determination In accordance with the requirements of 10 CFR 50.92, " Issuance of Amendment," this license amendment request conforms to the standards for a determination of no significant hazards consideration based upon the following:
- 1. Tiw proposedlicense amendment does not involve a signipcant increase in the probability or consequences ofan accident previously evaluated \
\
The requested license amendment does not authorize additional plant activities beyond those that already may be conducted under the approved TNP Decommissioning Plan and ' j
' the Defueled Safety Analysis Report (DSAR). Accident analyses are included in the !
appmved TNP Decommissioning Plan and incorporated into the TNP DSAR. No systems, structures, or components that could initiate or be required to mitigate the consequences of
. an accident are affected by the proposed change in any way not previously evaluated in the ,1 approved TNP Decommissioning Plan and DSAR. Therefore, the proposed change is administrative in nature and as such does not involve a significant increase in the ' )
probability or consequences of an accident previously evaluated.
- 2. The proposed license amendment does not create thepossibility ofa new or diferent kind ofaccidentfrom any accidentpreviously evaluated }
. The requested license amendment does not authorize additional plant activities beyond s those_that already may be conducted under the approved TNP Decommissioning Plan and ' ;
j ,
the DSAR. -Accident analyses are included in the approved TNP Decommissioning Plan
~
, - and incorporated into the DSAR. The proposed change does not affect plant systems, structures, or components in any way _not previously evaluated in the approved TNP
. Decommissioning Plan and DSAR, and no new or different failure modes will be created.
' Therefore, the proposed change is administrative in nature and as such does not create the possibilitp of a new or different kind of acddent from any accident previously evaluated. i r _
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Attachment I , :
VPN-007-99 ;
' March 10,1999 Page 4 of 5 ' '
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- 3. The proposed license amendment does not involve a significant reduction in a margin of l safety. :
Approval of the TNP License Termination Plan by license arnendment is administrative in nature since the decommissioning and fuel storage activities described in the TNP License l
Termination Plan are consistent with those in the approved *iNP Decommissioning Plan and DSAR. Therefore, the proposed change does not involve a significant reduction in a r margin of safety. ;
Based on the precedLig analysis, it is concluded that the requested amendment to Trojan Facility i Operating (Possession Only) License NPF-1 is acceptable, and involves no significant hazards !
consideration as defined in 10 CFR 50.92. I
- 4. EnvironmentalImpact Considerations Determination This amendment request satisfies the criteria specified in 10 CFR 51.22(c)(9) for a categorical exclusion from the requirements to perform an environmental assessment or to prepare an environmental impact statement. The specific criteria of 10 CFR 51.22(c)(9) are addressed as follows:
(i) The amendment imrolves no sigm*ficant hazards consideration.
As demonstrated above, the proposed amendment does not involve a significant hazards consideration.
'(ii) There is no sigm'ficant change in the types or significant increase in the amounts ofany efluents that may be released ofsite.
The requested license amendment does not authorize additional plant activities beyond those that may already be conducted under the approved TNP Decommissioning Plan and the DSAR. The TNP Supplement to Applicant's Environmental Report- Post Operating License Stage, prepared and submitted in conjunction with the TNP Deconunissioning Plan and approved by the NRC, concluded that decommissioning activities would be 4 accomplished with no significant adverse environmental impacts. ' Die TNP License Termination Plan evaluates this conclusion and determines that there is no new information or significant environmental change associated with ' activities described in the TNP License Termination Plan. Thus, the proposed change will result in no significant change in the types or significant increase in the amounts of any effluents that may be released offsite.
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VPN-007-99 $
March 10,1999 i Page 5 of 5 l l
(iii) There is no sigm'ficant increase in individual or cumulative occupational radiation j exposure. - -
The requested license amendment does not authorize additional plant activities beyond those that may already be conducted under the approved TNP Decommissioning Plan and the DSAR. The TNP Supplement to Applicant's Environmental Report - Post Operating
~ License Stage, prepared and submitted in conjunction with the TNP Decommissioning Plan
' and approved by the NRC, concluded that decommissioning activities would be -
accomplished with no significant adverse environmental impacts. The TNP License.
Termination Plan evaluates this conclusion and determines that there is no new information or significant environmental chang; associated with activities described in the TNP License
. Termination Plan. Thus, the proposed change will result in no significant increase in individual or cumulative occupational radiation exposure.
. Based on the prWing analysis, it is concluded that the proposed change to the 'INP license !
satisfies the criteria delineated in 10 CFR 51.22(c)(9) for categorical exclusion from the !
requirements of an environmental impact statement or environmental assessment.
, 5. Schedule Consideration Following approval, it is requested that 30 days be provided for implementation of this amendment.
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ATTACHMENTII .
to VPN-007-99 ;
l i i ANNOTATED LICENSE PAGE ' i 1
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(5) The licensee may proceed with and is required to complete the modifications i identified in Paragraphs 3.1.1 through 3.1.18 of the NRC Fire Protection Safety Evaluation Report on the Trojan Nuclear Plant dated March 22,1978. These modifications shall be completed by the end of the second refueling outage of ,
the Trojan facility and prior to return to operation for Cycle 3. In addition, the I licensee shall submit the additional information identified in Table 3.2 of this !
Safety Evaluation Report in accordance with the schedule contained therein. In the event these dates for submittal cannot be met, the licensee shall submit a ;
report explaining the circumstances, together with a revised schedule. j (6) Primary Shieldino Modification The licensee is authorized to modify the primary shielding design as described ,
in PGE letter dated April 22,1977, as supplemented and amended by letters dated September 22 and 23,1977, December 22,1977, January 4 and 24,1978, March 20, and April 4,1978.
(7) Soent Fuel Assembiv Shiocino Cask Deleted (Amendment 196) l 196 (8) Fire Protection l l
The licensee shallimplement and maintain in effect all provisions of the l .
approved fire protection program as described in PGE-1012, " Trojan Nuclear l Plant Fire Protection Plan" and as approved in the SER dated September 22,1993 subject to the following provision: l I92 l
I The licensee may make changes to the approved fire l l protection program without prior approval of the Commission
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l only if those changes would not adversely impact the safe l storage of irradiated fuel or increase the likelihood of an l offsite release of radioactive material due to a fire. l (9) Soent Fuel Pool Debris Processino l l
gg The licensee is authorized to process spent fuel pool debris in accordance with l199 A E letter dated October 23,1996.
D. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and l safeguards contingency plans including amendments made pursuant to provision of the Miscellaneous Amendments and Search Requirements to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards information protected under 10 CFR 73.21, are entitled: " Trojan Nuclear Plant Security Plan", with i
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(11) License Termination !
4 The licensee shall implement and maintain in effect all provisions of the appmved License Termination Plan as described in PGE-1078, " Trojan Nuclear Plant License ]'
Termination Plan," and as approved in the SER d aed - , Thelicensee may make changes to PGE-1078 without pric appmval provided the proposed changes do not:
(a). Involve an unreviewed safety question. or changes to the technical specifications as specified in 10 CFR 50.59; or .
l (b) - Violate the requirements of 10 CFR 50.82(a)(6).
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i ATTACHMENTIII to VPN-007-99 i
i PGE-1078, " TROJAN NUCLEAR PLANT LICENSE TERMINATION PLAN" l
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i TO: Distribution LGD-041-99 .
FROM: L. G. Dusek dr ?
' DATE: March 10,1999 1 i
SUBJECT:
Transmittal of Prooosed PGE-1078 "Troian Nuclear Plant l License Termination Plan." Dated March 1999 j Enclosed is your copy of the above mentioned document. j i
Please acknowledge receipt of this document by completing the lower portion of this transmittal )
and returning it to the location given below.. !
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LGD/ pas l l
Enclosure I l
3/10/99 i l
l ' ACKNOWLEDGMENT PGE-1078 "Troian Nuclear Plant License Termination Plan" ;
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I hereby acknowledge receipt of Controlled Copy Number (s) [O of the above subject document. j i
Signature Date ;
1 Return to: Pat Schaffran <
Trojan Nuclear Plant L ~ 71760 Columbia River Hwy.
Rainier, OR 97048 4'
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- no102 l a n c .
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,.s P G E-10 7 8
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LTrojan Nuclear Plant License Termination Plan l 1
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