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MONTHYEARML20148C2101988-03-18018 March 1988 Proposed Tech Specs,Reflecting Revised Offsite & Facility Organization Charts Project stage: Other 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 Project stage: Request ML20148C1981988-03-18018 March 1988 Forwards Application for Amend to License NPF-1,consisting of Rev 2 to License Change Application 162,revising Tech Specs to Reflect Changes to Offsite & Facility Organization Charts Project stage: Request ML20151N3671988-07-26026 July 1988 Forwards Page 6-5 of Tech Specs as Revised by Amend 146 to License NPF-1.Page Inadvertently Omitted from Amend Project stage: Other 1988-03-18
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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] |
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PORTLAND CENERAL ELECTRIC COMPANY EUGENE WATER & ELECTRIC BOARD AND PACIFIC POWER & LIGHT COMPANY Operating License NPF-1 Docket 50-344 License Change Application 162, Revision 2 This License Change Application requests modifications to Operating License NPF-1 for the Trojan Nuclear Plant to revise the Offsite and Facility Organization charts in the Technical Specifications.
PORTLAND GENERAL ELECTRIC COMPANY B M D. W. Coc)cfield Vice President i Nuclear Subscribed and sworn to before me this 18th day of March 1988.
i Notary Public of Oceg6h My Commission Expires: &d f / / '
I d I
( '~"
! -8803220304 880318 i PDF( ADOCK 05000344 P DCD
LCA 162, Revision 2 Page 1 of 6 DESCRIPTION OF CHANGES
- 1. The following addition is made to Trojan Technical Specification Figure 6.2-1, Offsite Organization:
Manager, Nuclear Security reporting to the General Manager, Corporate Security.
- 2. The following deletions or corrections are made to Figure 6.2-1:
- a. Board of Directors and Chairman of the Board are deleted,
- b. Manager, System Control is deleted,
- c. General Manager, Trojan Nuclear Plant is deleted,
- d. Plant Review Board is deleted.
- e. Senior Vice President, General Counsel and Secretary is deleted.
- f. Senior Vice President, Electric Operations is changed to read Vice President, Power Services.
- g. Vice President, Operating Services is deleted,
- h. Vice President, Power Systems in changed to read Vice President, Power Management.
- i. Manager, Power Supply is changed to read General Manager, Power Marketing.
- j. Manager, Fuel Operations is changed to read Manager, Power and Fuel Contracts and changed to report to General Manager, Power Marketing.
- k. General Manager, Purchasing and Materials Management is changed to read Purchasing Agent.
- 1. General Manager, Corporate Security, is changed to report to Vice President, Nuclear.
- 3. The following additions are made to Trojan Technical Specification Figure 6.2-2, Facility Organization:
- a. Vice President, Nuclear.
- b. General Manager, Technical Functions.
- c. System Engineering Branch Manager reporting to the Manager, Technical Services.
LCA 162. Revision 2 Page 2 of 6
- d. Surveillance & Test Engineering Branch Manager reporting to the Manager, Technical Services.
- e. Plant Review Board reporting to the General Manager,
- f. Performance. Monitoring / Event Analysis reporting to the Vice President, Nuclear.
- g. Manager, Personnel Protection reporting to the General Manager.
- h. Plant Safety Coordinator reporting to the Manager, Personnel Protection.
- i. Quality Assurance Operations Branch Manager and Quality Control Supervisor reporting to the Manager, Nuclear Quality Assurance (QA).
- j. Procurement Supervisor reporting to Manager, Plant Services.
- 4. The following deletions or corrections are made to Figure 6.2-2:
- a. Manager of Safety and Labor is changed to read Manager, Staffir6/Mealth and Safety.
- b. Safety Coordinator is changed to read Health and Safety Specialist.
- c. Manager, Plant Modifications is changed to report tc the General Manager, Technical Functions,
- d. Maintenance, Operations. Training, Chemistry, and Radiation Protection Supervisors are cl.anged to Branch Managers.
- e. All staff positionc below the Supervisor level are deleted with the exception of Operations.
.f. Engineering Supervisor is deleted.
- g. Planner Scheduler is changed to read Manager, outage Planning and Scheduling.
- h. Shift Technical Advisors (STAS) are changed to report directly to the Manager, Technical Services.
- i. Chemistry and Radiation Protection Brinch Managers and Plant Safety Coordinator are changed to report to the Manager, Personnel Protection.
- j. Director, Corporate Security is changed to read Manager, Nuclear Security.
. r LCA 162, Revision 2 Page 3 of 6
- k. Security Supervisor is changed to read Branch Manager, Nuclear Security.
- 5. In Trojan Technical Specification 6.3.1, the title of Radiation Protection Supervisor is changed to read Radiation Protection Branch Manager. In the list of Plant Review Board members of Trojan Techni-cal Specification 6.5.1.2, the positions of Engineering, Maintenance, Operations, QA, and Radiation Protection Supervisor are changed to read System Engineering, Maintenance, Operations, Quality Assurance Operations, and Radiation Protection Branch Manager, respectively.
REASON FOR CHANGES
- 1. The changes described in 1, 2b, e, f, g, h, i, j, k, and 1 above are made to reflect the current Corporate organization. The deletions of the General Manager, Trojan Nuclear Plant, and the Plant Review Board (2c and d atavo) are made since these are onsite positions which are more appropriately shown on the Facility Organization chart of Figure 6.2-2. The deletions of the Board of Directors and Chairman of the Board (2a above) are made to simplify the organization chart.
The change in Corporate Security reporting to the Vice President, Nuclear is made due to the large security involvement at the Trojan Nuclear Plant. This will allow more unified implementation and control of security measures requiring coordination of engineering design and maintenance support as well as regulatory interface.
- 2. The addition of the Plant Review Board in Figure 6.2-2 appropriately reflects its advisory position to the General Manager as described in Technical Specification 6.5.1. The System Engineering and Surveil-lance and Test Engineering Branch Managers are new positions, assuming the duties previously held by the Engineering Supervisor.
This division of responsibilities provides greater management oveJ-sight of Plant engineering activities. The Systen Engineering Branch Manager is responsible for providing technical support for Plant operations through evaluation and resolution of equipment and system problems for primary, balance-of-plant, and electrical systems. He is also responsible for performing the operational experience reviews as they relate to Plant system performance, and provides engineering for Plant modifications, safety and operability analysis and proco-dure development.
The Surveillance and Test Engineering Branch Manager is responsible for monitoring Plant performance through the use of test and surveil-lance procedures in order to ensure that the Plant performance con-forms to license requirements, applicable codes and standards, and goals for efficient operation. He is also responsible for the American Society of Mechanical Engineers (ASME)Section XI Inservice Inspection Program, Inservice Testing Program for Pumps and Valves, and Repair and Replacement Program.
1
a LCA 162, Revision 2 Page 4 of 6 Performance Monitoring / Event Analysis (PM/EA) is a new group responsible for supporting line management in trending, event analysis, review, and performance monitoring of activities that effect the safe and reliable operation of the Trojan Nuclear Plant.
PM/EA activities will be directed by the Vice President, Nuclear to ensure the most effective utilization of resources to monitor Nuclear Division activities.
The Manager, Personnel Protection, is a new position assuming responsibility for chemistry, radiatica protection, and safety.
This change provides greater management oversight on these three areas which support the safe operation of Trojan. The Plant Safety Coordinator, now reporting to the Manager, Personnel Protec-tion, coordinates the onsite industrial safety program. This is not a new position at Trojan, but is now being reflected in the organiza-tion chart in the Tecnnical Specifications.
The new positions of Quality Assurance (QA) Operations Branch Manager and Quality Control (QC) Supervisor reflect a division of QA and QC responsibilities within the onsite QA organization. The previous position of QA Supervisor had respcnsibility for both QA and QC functions. The position of QA Operations Branch manager now has responsibility for the following: coordinating and scheduling the performance of audits, surveillances, and review of Trojan Nuclear Plant OTerations and onsite support organizations; reviewing and con-curring with onsite-prepared quality ~related purchase requisitions; functioning as the QA representative on the Plant Review Board; issuing and tracking all onsite Nonconforming Activity Reports (NCARs); and reviewing and concurring with all onsite quality-related procedures. QC functions, performed by the QC Supervisor, include the following: provide QA/ Nondestructive Examination (NDE) coverage of construction, maintenance, and modification activities; tracking 111 Nonconformance Reports (NCRs) issued at Trojan; conducting material raceipt inspections; and developing, maintaining and approving QC/NDE procedures and guidelines for observation of in-process work.
The Procurement Supervisor is a new position assuming responsibility for ordering Plant equipment and materials. This includes material for warehouse inventory, Plant modifications and maintenance. The addition of this position relieves the Materials Supervisor of pro-curement responsibilities. This allows greater attention to be placed on his other responsibilities which include the receiving, handling, storage, shipping, and issuing of Plant equipment and materials.
- 3. The changes to titles in Figure 6.2-2 are made to reflect current position names. The shift in reporting for the Manager, Plant Modifications, centralizes responsibility and control of the design and installation of Plant design changes with the General Manager, Technical Functions.
LCA 162, Revision 2 Page 5 of 6 The detailed organizational structures below the supervisor level are not necessary for this organization chart and are deleted, with the exception of the Operations Branch.
The change in reporting for the STAS clarifies overall program responsibility under the Manager, Technical Services. This change does not reflect any shift in responsibility. Previously, the organization chart placed the STAS under the Reactor Engineer. The Reactor Engineer, serving as an STA himself, continues to have sup-port responsibilities such as scheduling watch rotations. However, since the Reactor Engineer is a staff position below the Supervisor level, it has been removed from the organization chart. The change from Director, Corporate Security to Manager, Nuclear Security more accurately shows the security organizational line of reporting.
4 The title changes in Trojan Technical Specifications 6.3.1 and 6.5.1.2 reflect the new position names already described. No changes to the Plant Review Board membership have been made.
SIGNIFICANT HAZARDS CONSIDERATIONS In accordance with the requirements of 10 CFR 50.92, this License Change Application is judged to involve no significant hazards based upon the following considerations:
- 1. Does the proposed license amendment involve a significant increase in the probability or consequences of an accident?
This change is administrative only correcting position titles, adding new positions, simplifying unnecessary detail, and reflecting the assignment of responsibility for administering the onsite QA, and STA programs. No change is being made to any of the approved programs, nor the physical configuration of the Plant. All limiting conditions for operation and safety system settings will continue to be imposed.
With respect to the STA program, all required training, experience, and duty requirements of Trojan Technical Specification Sections 6.2, 6.3, and 6.4 will continue.
With respect to the QA Program, the functions, duties, and responsi-bilities assigned in PGE-8010, Nuclear QA Program, will continue to be performed.
Therefore, there is no increase in the probability or the consequences of an accident previously evaluated.
LCA 162 Revision 2 Page 6 of 6
- 2. Does the proposed licetae amendment create the possibility of a new or different kind of accident from any previously evaluated?
As noted above, there are no substantive changes to onsite programs.
This change is administrative only and does not create the possibility of a new or different kind of accident.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
As noted above, this change does not involve a substantive change to any of the involved programs. This change is administrative only and has no effect on the margin of safety.
In the April 6, 1983 Federal Register, the NRC published a list of examples of amendments that are not likely to involve significant hazards concerns. Example No. 1 of that '.ist states the following to show why this amendmerit is not considered likely to involve a significant hazards consideration:
"Purely administrative change to Technical Specifications: For example, a change to achieve consistency throughout the Technical Specifications, correction of an error, or a change in nomenclature."
SAFETY / ENVIRONMENTAL EVALUATION Safety and environmental evaluations were performed as required by 10 CFR 50 and the Trojan Technical Specif) cations. This review deter-mined that an unreviewed safety question does not exist since Plant operations remain consistent with the Final Safety Analysis Report, adequate surveillance is maintained, and there is no conceivable impact upon the environment.
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