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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20206H4411999-05-0505 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 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 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 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 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 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 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 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 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 ML20151X1121988-08-17017 August 1988 Corrected Page to Amend 142 of License NPF-1 Re Administrative Controls ML20151X8271988-08-0303 August 1988 Amend 149 to License NPF-1,deleting Offsite & Facility Organization Charts from Tech Specs ML20151N6661988-07-26026 July 1988 Page 6-5,inadvertently Omitted from Amend 146 to License NPF-1 ML20151H3011988-07-14014 July 1988 Amend 148 to License NPF-1,revising Surveillance Requirements for Safety Injection Accumulator Isolation Valves in Tech Spec Section 3/4.5, Eccs ML20151L4271988-07-11011 July 1988 Amend 147 to License NPF-01,revising Surveillance Requirements for Tech Spec 3/4.6.1.1 ML20151E4531988-07-11011 July 1988 Amend 147 to License NPF-1,revising Surveillance Requirements in Tech Spec Section 3/4.6.1.1, Containment Integrity ML20196G0261988-06-23023 June 1988 Amend 145 to License NPF-1,revising Means by Which Source Range Neutron Flux Instrumentation Calibr Will Be Performed ML20196C1311988-06-22022 June 1988 Amend 144 to License NPF-1,revising Tech Specs Re Ref of Remote Shutdown Station ML20196F9291988-06-16016 June 1988 Amend 143 to License NPF-1,changing Tech Spec Section 3/4.3.3.10 by Adding Two Instruments for Monitoring Steam Generator Blowdown Liquid Effluent Discharge ML20154D4841988-05-11011 May 1988 Amend 142 to License NPF-1,permitting Relief from Limiting Condition for Operation 3.0.4 for Tech Spec Sections 3.2.4, 3.9.2,3.9.7,3.9.9 & 3.9.11 Re Power Distribution ML20154A1111988-05-0303 May 1988 Amend 141 to License NPF-1,revising Tech Spec Section 3/4.7.3, Component Cooling Water Sys to Be Consistent W/ split-train Operation ML20148S6421988-04-11011 April 1988 Amend 140 to License NPF-1,revising Offsite & Facility Organization Charts for Tech Specs ML20151B3751988-03-31031 March 1988 Amend 139 to License NPF-1,revising Tech Spec Section 3/4.10, Special Test Exceptions by Extending Surveillance Time Period for Verifying Control Rod Insertability During Rod Worth & Shutdown Margin Tests from 24 H to 7 Days ML20237A7261987-12-0707 December 1987 Amend 138 to License NPF-1,incorporating Changes to Physical Security Plan by Deleting Condensate Storage Tank from Classification as Vital Equipment ML20236X5171987-12-0101 December 1987 Amend 137 to License NPF-1,revising Tech Spec Table 3.3-1, Reactor Trip Sys Instrumentation & Table 4.3-1, Reactor Trip Sys Instrumentation Surveillance Requirements, Per Generic Ltr 85-09 ML20236M9851987-11-0909 November 1987 Amend 136 to License NPF-1,revising Tech Spec Section 3/4.11.3, Solid Radwaste, to Delete Nonexistent Ref ML20235V6071987-10-0202 October 1987 Amend 135 to License NPF-1,revising Tech Spec Section 6 Re Review & Approval of Temporary Changes to Procedures & Correcting Typos ML20235R9121987-09-14014 September 1987 Errata to Amends 121 & 130 to License NPF-1,correcting Erroneously Replaced Pages & Adding Intentionaly Blank Page ML20238B0081987-09-0101 September 1987 Amend 134 to License NPF-1,revising Tech Specs by Increasing Setpoint Tolerance for Pressurizer & Main Steam Safety Valves ML20236P6621987-08-0707 August 1987 Amend 133 to License NPF-1,revising Steam Generator Tube Plugging Criteria Based on Use of F* Distance Criteria ML20236H5531987-07-30030 July 1987 Amend 132 to License NPF-1,revising Tech Spec Section 3/4.8.2, Onsite Power Distribution Sys ML20209D9401987-04-22022 April 1987 Amend 131 to License NPF-1,changing Tech Specs Re Reactor Trip Sys & ESFAS Instrumentation Requirements ML20209D3981987-04-22022 April 1987 Amend 129 to License NPF-1,changing Tech Spec Section 4.6.3.1.2 to Allow Containment Isolation Valve Stroke Testing W/O Mode Limitation ML20209B8221987-04-22022 April 1987 Amend 130 to License NPF-1,revising Tech Spec Section 3.7.1.4 to Reflect Increase in Min Water Level Required to Be Maintained in Condensate Storage Tank ML20206H6581987-04-0909 April 1987 Amend 127 to License NPF-1,changing Tech Specs to Revise Reactor Vessel Matl Irradiation Surveillance Schedule & pressure-temp Limits ML20212R3071987-04-0909 April 1987 Amend 128 to License NPF-1,changing Tech Specs by Redefining & Clarifying Review Responsibilities of Plant Review Board & Plant General Manager ML20206B5711987-04-0202 April 1987 Amend 126 to License NPF-1,providing Editorial Corrections to Tech Spec Sections 4.4.6.1.b & 3.4.9.3 & Revising Table 3.6-1 to Permit Administrative Control of Valve MD-059 Operation 1999-05-05
[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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s dpn uouq'o ~g UNITED STATES
. 8 o NUCLEAR REGULATORY COMMISSION h e $ W ASHINGTON. D. C. 20555 tg . . . . . ,o PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.149 License No. NPF-1
- 1. The Nuclear Regulatory Commission (the Comission) has found that:
A. The application for amendment by Portland General Electric Company, et al., (the licensee) dated March 31, 1988 as revised June 27, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set fcrth in 10 CFR Chapter I; B. The facility will o)arate in conformity with the application, the provisions of tie Act, and the regulations of the Comission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
8808260117 880803 DR ADOCK05000,g4 1
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-1 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised th 'ough Amendment No.149 . are hereby incorporated in the license. The licensee shall operate the facility in acco dance with the Technical Specifica-tions, except where otherwise stated in specific license conditions.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION George X ighto. Director Project Directorate Y Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications ,
Date of Issuance: August 3, 1988 l
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ATTACHMENT TO LICENSE AMENDMENT N0J49 TO FACILITY OPERATING LICENSE NO. NPF-1 DOCKET N0. 50-344 Revise Appendix A as follows:
Remove Pages Insert Pages XVI XVI 6-1 6-1 6-la 6-2 6-2 6-3 6-3 6-4a 6-4a 6-5 6-5
INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY............................................ 6-1 6.2 ORGANIZATIONAL RE0VIREMENTS 6.2.1 6ENERAL................................................. 6 -1 6.2.2 FACILITY STAFF.......................................... 6-la 6.3 FACILITY STAFF OVALIr.ICAT10NS............................. 6-5 6.4 TRAINING.................................................. 6-5 l 6.5 REVIEW AND AUDIT l
6.5.1 PLANT REVIEW BOARD Function............................................... 6-5 Composition............................................ 6-6 Alternates............................................. 6-6 Meeting Frequency...................................... 6-6 Quorum................................................. 6-6 l
Responsibilities....................................... 6-6 Authority.............................................. 6-7 l
R e c o rd s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-8 6.5.2 TROJAN NUCLEAR OPERA 110NS BOARD Function............................................... 6-8 Composition............................................ 6-9 Alternates............................................. 6-9 1
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{ TROJAN-UNIT 1 XVI Amendment No. 97. 149 l - August 3, 1988 l
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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The General Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence. .
6.2 ORGANIZATIONAL REQUIREMENTS 6.2.1 GENERAL A facility and a corporate organization shall be established for unit operation and corporate management. The facility and corporate organizations shall include the positions for activities af fecting the safety of the nuclear power plant. -
- a. Lines of authority, responsibility and communication shall be estab-lished and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organizational charts, functional descriptions of departmental responsibilities and relationships, and l job descriptions for key personnel positions, c,r in equivalent forms of documentation. These requirements shall be documented in the FSAR.
- b. The Vice President Nuclear shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staf f in operating, maintaining, and providing technical support to the plant to ensure nuclear safety,
- c. The Plant General Manager shall be responsible for overall unit safe operation and shall have control over those f acility activities necessary for safe operation and maintenance of the plant.
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- d. The individuals who train the operating staff and those who carry out
, the quality assurance functions may report to the appropriate facility
! staf f managers; however, they shall have suf ficient or to ensure their independence from operating pressures,ganizational freedom
- e. Although radiation protection individuals may report to a facility staff manager for matters relating to radiological health and safety of employees and the public, the radiation protection mani.ger shall have l direct access to the onsite individual having responsibility for overall unit management. Radiation protection personnel shall have the authority to cease any work activity when worker safety is jeopardized or in the event of unnecessary personnel radiation exposures.
Amendment No. 78, 42, 50 149 TROJAN-UNIT 1 6-1 August 3, 1988
ADMINISTRATIVE CONTROLS 6.2.2 FACILITY STAFF The Facility organization shall be subject to the following:
- a. Each on duty shift shall be composed of at least the minimum shif t crew composition shown in Table 6.2-1. The minimum shift crew necessary for safe shutdown is five.
- b. At least one licensed Operator shall be in the control room when fuel is in the reactor.
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- c. At least two licensed Operators shall be present in the i control room during reactor start-up, scheduled reactor l shutdown and during recovery from reactor trips.
- d. An individual qualified in radiation protection procedures
- shall be on site when fuel is in the reactor.
l e. All CORE ALTERATIONS after the initial fuel loading shall l be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation, i
l f. A Fire Brigade of at least 5 members shall be maintained I onsite at all times. The Fire Brigade shall not include members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency. Fire Brigade ccmposition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accom-modate unexpected absences of onduty members provided imediate action is taken to restore the Fire Brigade compcsition to within the minimum requirement of S.
Amendment No. 149 TRO.lAN-UNIT 1 6-la August 3, 1988
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( Figure 6.2-1 Intentionally Deleted ) ,
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I TROJAN UNIT 1 6-2 AmendmentNo.52,if,8{I 9 l 198, H9, '
August 3, 1988
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( Figure 6.2-2 Intentionally Deleted )
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TROJAN-WIT 1 6-3 Amendment No. (2,55,88.88 713,714,146 149
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August 3, 1988
ADMINISTRATIVE CONTROLS
- g. Administrative procedures shall be developed and implemented to limit the working hours of shift personnel who perform safety .
related functions (i.e., senior reactor operators, reactor operators, health physicists, auxiliary operators), and key maintenance personnel of the unit staff.
Key maintenance personnel of the unit staff are those personnel who are responsible for the correct performance of maintenance, repair, modification or calibration of safety related structures, systems or components, and who are personnel performing or immediately supervising the performance of such activities.
This applies to key naintenance personnel whether on shift or not.
Adequate shif t coverage shall be maintained without routine heavy l
use of overtime. The baseline for determining overtime use will l
be a 40-hour work week when the plant is operating. However, in I
the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:
- a. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shif t turnover time.
- b. An individual should not be permitted to work more than l 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> I in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period, all excluding shift turnover time.
- c. A break of at least eight hours should be allowed between work periods, including shift turnover time.
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- d. Except during extended shutdown periods, the use of over-l time should be considered on an individual basis and not for the entire staff on a shift.
Any deviation from the above guidelines must be authorized by the Plant General Manager or, in his absence, Duty Plant Manager, or I higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Routine deviation from the above guidelines is not authorized.
- h. The Shif t Supervisor and Assistant Shif t Supervisor shall each hold a Senior Reactor Operator License. The Control Operator and Assistant Control Operator shall each hold a Reactor Operator License.
TROJAN-UNil 1 6-4a AmendmentNo.fd/ 149 August 3, 1988 f
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'- ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Radiation Protection Branch Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shift Technical Advisor who shall have a bachel..s degree or equivalent in a scientific or engineering discipline with specific training in Plant design, and response and analysis of the Plant for transients and accidents.
6.3.2 The Operations Branch Manager shall hold a Senior Reactor Operator License.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staf f shall be maintained under the direction of the General Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix 'A" of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the General Manager and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975, except for Fire Brigade training sessions which shall be held at least quarterly.
6.5 REVIEW AND AUDIT .
6.5.1 PLANT REVIEW BOARD (PRB)
FUNCTION 6.5.1.1 The Plant Review Board shall function to advise the General Manager on all natters related to nuclear safety.
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l 6-5 Amendment No'. 42, 56, IJ6 149 TROJAN-UN11 1 August 3, 1988 l
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