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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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J 4 69"'#N +
E UNITED STATES v
Q .
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NUCLEAR REGULATORY COMMISSION
$i -
.y. 8 ,j ' WASHINGTON, D. C. 20555 l
.....l i
PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDl1ENT TO FACILITY OPERATING LICENSE Amendment No.152 License No. NPF-1
- 1. The Nuclear Regulatory Comission (the Comission) has found that: '
-A. The application for amendment by Portland General Electric Company, etal.,(thelicensee)datedSeptember 30, 1986, as revised and siIpSemented November 16, 1987 and April 14, 1968, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B. The facility will o>erate in conformity with the application, the provisions of t1e Act, and the regulations of the Comission;-
C. Thereisreasonableassurance(i)thattheactivitiesauthorized I 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 Comission's regulations; D. The issuance of this anendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuence of this anendment is in accordance with 10 CFR Part 51 of the Comission's regulations ano all applicable requirements have been satisfied.
P L _:__= _--_ _
4 1
- 2. Accordingly, the license is amended by changes to the Technical l Specifications as indicated in the attachment to this license I amendment, and paragraph 2.C.(2) of Facility Operating License i No. NPF-1 is hereby amended to read as follows: l (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.152 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifica-tions, except where otherwise stated in specific license conditions.
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- 3. This license' amendment is effective as o'f the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION George W Knighton, 1 rector Project Directorate V Division of Reactor Projects III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: May 15, 1989 l
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n- 'e ATTACHMENT TO LICENSE AMENDMENT- fl0.152 TO FACILITY OPERATING LICENSE N0. NPF-1 DOCKET NO. 50-344 Revise Appendix A as follows:
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Remove Pages Insert Pages 3/4 3-47 3/4 3-47 3/4 7-18 3/4 7-18 3/4 7-19 3/4 7-19 3/4 7-20 3/4 7-20 B3/4 7-5 B3/4 7-5 B3/4 7 Sa i
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________...____m. _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ __.__ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _
4 INSTRUMENTATION CHLORINE DETECTION SYSTEMS -
LIMITING CONDITION FOR OPERATION 3.3.3.6 Two independent chlorine detection systems, with their alarm / trip-setpoints adjusted to actuate at a chlorine concentration of $ 5 ppm, shall be OPERABLE.
APPLICABILITY: ALL MODES.
ACTION: ,
- a. With one chlorine detection system inoperable, restore the inoperable detection system to OPERABLE status within 7 days or within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> initiate and maintain operation of the control room emergency ventilation system in the recircula-tion mode of operation.
- b. With both chlorine detection systems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control room emergency
- ventilation system in the recirculation mode of operation,
- c. The provis. ions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.3.3.6 Each chlorine detection system sha'il be verified energized at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.
i TROJAN-UNIT 1 3/4 3-47 Amendment No. 93152 0
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PLANT SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM L LIMITING CONDITION FOR OPERATION 3.7.6.1 Two independent control room emergency ventilation systems shall be OPERABLE.
APPLICABILITY: ALL MODES.
ACTION:
I MODES 1, 2, 3, and 4:
With one control room emergency ventilation system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
With both control room emergency ventilation systems inoperable
[where inoperability of one or both systems is due solely to i
failure of the system (s) to maintain the control room at a posi- l tive pressure of 11/8 ihch WG relative to outside atmosphere or to adjacent spaces, but able to maintain the control room at a positive pressure of 21/16 inch WG), restore at least one system to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
MODES 5 and 6:
- a. With one control room emergency ventilation syst(m inoperable, restore the inoperable system to OPERABLE status within 7 days or initiate and maintain operation of the remaining OPERABLE
, control room emergency ventilation system in the recirculation mode of operation.
- b. With both control room emergency ventilation s'ystems inoperable, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE REQUIREMENTS
- 4. 7. 6.1 Each control room emergency ventilation system shall be demon-strated OPERABLE:
- a. At least once per 31 days on a STAGGERED TEST BASIS by initiating flow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least 10 bcurs with the TROJAN-UNIT 1 3/4 7-1B Amendment No. 77, 3B ,152 l
4, l 1
a LCA 142, Revision'1 ')
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Attachment i Page 3 of 6 !
PLANT' SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) preheaters on and maintains the control room air temperature
{c
$ 110*F.
- b. At least once per 31 days by verifying that the system maintains l the control room at a positive pressure of 11/8 in. WG relative i to the outside atmosphere and to other adjacent spaces during system operation.
- c. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:
- 1. -Verifying that' the charcoal adsorbers remove 1 99.95% of l l a halogenated hydrocarbon ref rigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 3000 cfm i 10%. l
- 2. Verifying that the HEPA filter banks remove 1 99.95% of the j DOP when they are tested in place in accordance with ANSI 9 N510-1975 while operating the ventilation system at a flow rate of 3000 cfm i 10%. l
- 3. - Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, demonstrates a pene-tration of 51.0 percent when tested in accordance with ASTM D3803-79 Methyl lodide Penetration Test Methods at 30*C and 70 percent relative humidity.
- 4. Verifying a system flow rate of 3000 cfm i 10% (of which makeup flow is 5 525 cfm) during system operation in the pressurization mode.of operation when tested in accordance with ANSI N510-1915.
- d. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by veri-fying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with i
TROJAN-UNIT 1 3/4 7-19 Amendment No. yg 152 1
.a
,; -.,g PLANT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) '
Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, demonstrates a penetration of 51.0 percent when tested in accordance with ASTM D3803-79 Methyl Iodide Penetra-
. tion Test Methods at 30*C and-70 percent relative humidity.
- e. At least once per 18 months by:
- 1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is < 6 inches Water Gauge while operating the ventilation system at a flow rate of 3000 cfm i 10%.
- 2. Verifying that on a Safety Injection signal,.the control room nonnal air conditioning system (CB-2) stops and isolation dampers close to automatically isolate the control room w. thin 3 seconds; the CB-3 (water sampling laboratory exhaust), CB-4 (toilet and lunch room exhaust), CB-5 (Control Building supply),
CB-6 (mechanical room exhaust), and CB-10 (Control Building air ,
. conditioning supply) systems stop; and that CB-1 (control room emergency ventilation system) automatically starts.
- 3. Verifying that on a High Radiation signal, the control room normal air conditioning system (CB-2) stops and isolation dampers close to automatically isolate the control room within 3 seconds; and the CB-3 (water san.pling laboratory
[ exhaust), CB-4 (toilet and lunch rorsm exhaust), CB-5 (Control Building supply), CB-6 (mechanical room exhaust), and CB-10 (Control Building air conditioning supply) systems stop.
- 4. Verifying that on a High Chlorine signal and High 502 signal the control room normal air conditioning system (CB-2) stops
' and isolation dampers close to automatically isolate the con-trol room within 3 seconds; and the CB-3 (water sampling
, laboratory exhaust), CB-4 (toilet and lunch room exhaust),
CB-5 (Control Building supply), CB-6 (mechanical room exhaust), and CB-10 (Control Building air conditioning supply) systems stop.
l f. After each complete or partial replacement of HEPA filter banks )
by verifying that the HEPA filter banks remove t 99.95% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 3000 10%.
- g. After each complete .or partial rep 1& cement of a charcoal adsorber I bank by verifying that the charcoal adsorbers remove 199.95% of a )
halogenated hydrocarbon refrigerant tett gas when they are tested i in-place in accordance with ANSI N510-1975 while operating the filter train at a flow rate of 3000 cfm ! 10%.
TROJAN-UNIT 1 3/4 7-20 Amendment No. 79, ygg,152
j PLANT SYSTEMS BASES -
3/4.7.6 CONTROL ROOM VENTILATION SYSTEM The OPERABILITY of the control room ventilation system ensures that
- 1) the ambit'.! ei- temperature does.not exceed the allowable temperature for continuaaz * :s rating for the equipment and instrumentation cooled by this system sad 2) the control room will remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design pro-visions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A",10 CFR 50. System operability can be affectec by ECCS recirculation leakage and Containment leakage should the conditions assumed in FSAR Section 15.6.5.6 be exceeded.
The OPERABILITY of this system in conjunction with contral room design provisions is also based on limiting the toxic gas exposure to control room personnel consistent with the FSAR design basis and Regulatory Guide 1.95.
Recirculation mode cf operation is defined as operation of the control roem emergency ventilation system with the outside air dampers closed. In the event of a radiation release while operating the system in the recirculation mode of operation, the system is operated in the pressurization mode of operation by opening the outside air dampers. '
Operation of the system in this nenner nwets the intent of this specification and satisfies the FSAR cosign basis and requ?rements of GDC 19.
3/4.7.7 SEALED SOURCE CONTAMINATION The limitations on sealed source removable contamination ensure that the total b*dy or individual organ irradiation does not exceed allowable limits in the esent of ingestion or inhalation of the source material.
The limitations on removable contamination for sources . requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. Leakege of sources excluded from the requirements of this specification represent less than one maximum permissible body burden
, ; for total body irradiation if the source material is inhaled or ingested.
3/4.7.8 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. The fire suppression system consists of the water system, sprinklers and fire hose stations. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.
TROJAN-UNIT 1 B 3/4 7-5 Amendment No. 78, 28 ,152
PLANT SYSTEMS BASES (Continued)
In the' event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the af fected areas until the inoperable equipment is restored to service.
i TROJAN-UNIT 1 B 3/4 7-Sa Amendment No. 78, 26, 152
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