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MONTHYEARML20138N4761985-11-0101 November 1985 Proposed Changes to Tech Spec 3/4.1.3, Movable Control Assemblies, Re Electrical Inoperability of Control Rods Project stage: Request ML20138N4671985-11-0101 November 1985 Application for Amend to License NPF-1,consisting of License Change Application 133,revising Tech Spec 3/4.1.3, Movable Control Assemblies, Re Electrical Inoperability of Control Rods Project stage: Request ML20138N4551985-11-0101 November 1985 Forwards Application for Amend to License NPF-1,consisting of License Change Application 133,revising Tech Spec 3/4.1.3, Movable Control Assemblies, Re Electrical Inoperability of Control Rods.Fee Paid Project stage: Request ML20140E7121986-01-28028 January 1986 Proposed Tech Spec 3/4.1.3, Moveable Control Assemblies, Re Control Rod Operability Project stage: Other ML20140E7041986-01-28028 January 1986 Revised Application 133 to Amend License NPF-1,authorizing Changes to Tech Spec 3/4.1.3, Moveable Control Assemblies. Rev Forwarded Per Discussion Re 851101 License Change Application 133 Project stage: Other ML20211D3451986-05-29029 May 1986 Forwards Amend 115 to License NPF-1 & Safety Evaluation. Amend Changes Tech Spec 3/4.1.3 to Allow Operation to Continue for 72 H for Diagnosis & Repair When One or More Control Rod Assemblies Electrically Inoperable Project stage: Approval ML20206M0981986-06-24024 June 1986 Forwards Corrected Tech Spec Pages 3/4 1-19 & B 3/4 1-3, Issued as Page 3/4 1-18a & W/O Incorporating Amend 114, Respectively,Per Amend 115 to License NPF-1 Issued on 860529.W/o Encls Project stage: Other 1986-01-28
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20204B7691999-03-18018 March 1999 Proposed Tech Specs 5.6 Re High Radiation Area.Certificate of Svc,Encl ML20207J0831999-02-11011 February 1999 Proposed Tech Specs for Trojan Isfsi,Stating Length of Time Air Pads Can Be Installed & Inflated ML20151X8671998-09-10010 September 1998 Rev 2 to Proposed TS Bases,Changing Name of Cooling Sys to Modular Spent Fuel Pool Cooling & Cleanup Sys & Updates Spent Fuel Pool Heat Up Info to 3 1/2 Years After Plant Shutdown ML20238E8291998-08-27027 August 1998 Proposed Tech Specs,Deleting Number of License Conditions & TS Requirements as Prerequisite to Implementing Requested Amend to Transfer Nuclear Sf from Existing 10CFR50 Licensed Area to Proposed 10CFR72,ISFSI Area ML20199J5801998-01-29029 January 1998 Proposed Tech Specs Pages,Deleting Security Plan Requirements of 10CFR50.54(p) & Part 73 for Trojan Plant After Spent Nuclear Fuel Is Moved to Proposed ISFSI Area ML20134C9901997-01-28028 January 1997 Proposed Tech Specs 5.0 Re Administrative Controls ML20134A9571997-01-16016 January 1997 Proposed Tech Specs LCO 3.1.4 Re Spent Fuel Pool Load Restrictions ML20134B5881997-01-16016 January 1997 Proposed Tech Specs Deleting Paragraph 2.(C)(7) to Allow Loading & Handling of Spent Fuel Casks & Insertion of New License Condition Authorizing Loading of Spent Fuel & Other Matls in Fuel Building ML20134B8631997-01-16016 January 1997 Proposed Tech Specs Re Delete Paragraph 2.(C)(7) to Allow pre-operational Testing & Load Handling of Spent Fuel Transfer & Storage Casks in Trojan Fuel Building ML20135B5071996-11-27027 November 1996 Proposed Tech Specs Reflecting New Fuel Debris Storage Container Design & Storage of non-fuel Bearing Components & Fuel Rod Storage Container in Trojan ISFSI ML20129E7341996-10-23023 October 1996 Proposed Tech Specs Re Spent Fuel Pool Debris Processing ML20059A5601993-10-21021 October 1993 Proposed Tech Specs Modifying Security License Conditions for Clarity ML20127P2121993-01-27027 January 1993 Proposed TS 6.2.2.f Re Composition of Fire Brigade & TS Table 6.2-1 Re Min Shift Crew Composition for Shift Manager & Noncertified Operator ML20127M6391992-11-16016 November 1992 Proposed Tech Specs for Deferral of Unscheduled Steam Generator ISI ML20141M1901992-03-27027 March 1992 Proposed Tech Specs Re Surveillance Requirements for Lco. Response to Request for Addl Info on Subj Encl ML20059L6701990-09-21021 September 1990 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20247C8941989-07-19019 July 1989 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20245C8091989-06-12012 June 1989 Proposed Tech Specs,Changing Orifice Size of Steam Line Safety Valves Shown in Tech Spec Table 4.7-1, Steam Line Safety Valves Per Loop ML20235L9441989-02-10010 February 1989 Proposed Tech Specs,Allowing Mods to Control Auxiliary Fuel Bldg Complex Resulting in Increase in Lateral Shear Forces on Any Story ML20235Q9191989-02-10010 February 1989 Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements for Containment Integrity for Equipment Hatches ML20154D1781988-09-0909 September 1988 Proposed Tech Specs Revising Pressurizer LPSI Setpoint ML20151T5951988-08-12012 August 1988 Proposed Tech Specs,Revising Surveillance Requirements for ECCS Check Valves ML20151A0381988-07-0808 July 1988 Proposed Tech Specs Re Radioactive Gaseous Effluents & Radioactive Liquid Waste Sampling & Analysis Program ML20151U7171988-04-14014 April 1988 Revised Proposed Tech Specs Re Plant Sys,As Part of Rev 1 to License Change Application 142 ML20148K5971988-03-23023 March 1988 Proposed Revised Tech Specs Re RCS ML20148C2101988-03-18018 March 1988 Proposed Tech Specs,Reflecting Revised Offsite & Facility Organization Charts ML20196J9031988-03-0101 March 1988 Proposed Tech Specs Modifying OL NPF-1,removing 3.5% U-235 Limit on Reactor Fuel Assemblies & Increase Enrichment Limit for New Fuel Storage Racks to 4.5%.Certificate of Svc Encl ML20147E7371988-03-0101 March 1988 Proposed Tech Specs Re Containment Isolation Valves ML20149K1901988-02-17017 February 1988 Proposed Tech Specs,Adding New Instruments for Monitoring Steam Generator Blowdown Sys Liquid Effluent Radioactivity ML20149L6981988-02-15015 February 1988 Proposed Tech Specs Re Offsite & Facility Organization Charts.Util Certificate of Svc Encl ML20149H1121988-02-0404 February 1988 Proposed Tech Specs Revising Operability & Surveillance Requirements for Component Cooling Water Sys ML20147D4561988-01-15015 January 1988 Proposed Tech Specs,Revising Offsite & Facility Organization Charts ML20195H8971987-12-24024 December 1987 Proposed Tech Specs Deleting Sections Re Fire Protection ML20237D6971987-12-18018 December 1987 Proposed Tech Specs,Requiring Measurement of Initial Discriminator Bias Curve for Each Detector & Subsequent Discrimination Bias Curves Obtained,Evaluated & Compared to Initial Curves ML20237D6551987-12-16016 December 1987 Proposed Tech Specs Deleting Provision for Continued Plant Operation in Section 3/4.4.6.2 & Requiring Prompt Unit Placement in Cold Shutdown After Pressure Boundary Leakage Occurrence ML20236W7611987-11-20020 November 1987 Proposed Tech Specs Including Effects of Nuclear Fuel Design Changes ML20236Q2271987-11-16016 November 1987 Proposed Tech Specs,Resolving Control Room Habitability Issues ML20236P4391987-11-13013 November 1987 Proposed Tech Specs,Extending Surveillance Time Period for Verifying Control Rod Insertability During Control Rod Worth & Shutdown Margin Tests to 7 Days.Certificate of Svc Encl ML20236N3861987-11-0909 November 1987 Proposed Tech Spec,Revising Tech Spec 3.9.9 to Resolve Inconsistencies within Tech Specs.W/Certificate of Svc ML20236N5881987-08-0606 August 1987 Proposed Tech Spec Section, Bases Correcting Section for Agreement W/Definition of Pressure Boundary Leakage ML20235W5571987-07-14014 July 1987 Proposed Tech Specs Re Solid Radwaste Sys ML20215K8381987-06-22022 June 1987 Proposed Tech Spec Table 3.3-1,revising Operability Requirements for Reactor Trip Breakers & 4.3-1,revising Surveillance Requirements for Manual Reactor Trip,Reactor Trip Breakers & Bypass Breakers ML20210B6241987-04-29029 April 1987 Proposed Tech Specs Revising Typos & Clarifying Appropriate Process to Be Used for Review & Approval of Temporary Changes to Procedures.Certificate of Svc Encl ML20209D0251987-04-20020 April 1987 Proposed Tech Specs Re RCS Surveillance Requirements ML20206D9261987-04-0303 April 1987 Revised Tech Spec Pages 3/4 8-6 & 3/4 8-7 Re Onsite Power Distribution Sys,Per License Change Application 128 ML20206A6221987-04-0303 April 1987 Revised Tech Spec Page 7,clarifying License Change Application 124 Re power-operated Valves ML20245A2631987-02-26026 February 1987 Proposed Tech Specs,Consisting of Revised Pages for License Change Application 124 & License Change Application 135, Adding Steamline Isolation Valves & Valve CV-8825 Back Onto Table 3.6-1 & Excluding Containment Airlocks from Criteria ML20211P0031987-02-20020 February 1987 Proposed Tech Specs Re Steam Generator Tube Plugging Criteria in Tube Sheet Region ML20211H4021987-02-11011 February 1987 Proposed Tech Specs Increasing Setpoint Tolerance for Pressurizer & Main Steam Safety Valves from 1% to 2% ML20207Q5371987-01-20020 January 1987 Proposed Tech Specs,Revising Surveillance Requirements for Safety Injection Sys Accumulator Isolation Valves 1999-03-18
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210M7291999-08-0505 August 1999 Replacement Pages to PGE-1078, Trojan Nuclear Plant License Termination Plan. with D&D Modeling Runs for Determination of Screening Dcgls & Survey Area Maps Indicating Preliminary Survey Units ML20207D3951999-06-0101 June 1999 Rev 1 to Trojan Nuclear Plant Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20204B7691999-03-18018 March 1999 Proposed Tech Specs 5.6 Re High Radiation Area.Certificate of Svc,Encl ML20207J3911999-03-10010 March 1999 Trojan Nuclear Plant License Termination Plan ML20207J0831999-02-11011 February 1999 Proposed Tech Specs for Trojan Isfsi,Stating Length of Time Air Pads Can Be Installed & Inflated ML20153D3081998-09-21021 September 1998 Rev 0 to PGE-1077, Tnp Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20151X8671998-09-10010 September 1998 Rev 2 to Proposed TS Bases,Changing Name of Cooling Sys to Modular Spent Fuel Pool Cooling & Cleanup Sys & Updates Spent Fuel Pool Heat Up Info to 3 1/2 Years After Plant Shutdown ML20238E8291998-08-27027 August 1998 Proposed Tech Specs,Deleting Number of License Conditions & TS Requirements as Prerequisite to Implementing Requested Amend to Transfer Nuclear Sf from Existing 10CFR50 Licensed Area to Proposed 10CFR72,ISFSI Area ML20199J5801998-01-29029 January 1998 Proposed Tech Specs Pages,Deleting Security Plan Requirements of 10CFR50.54(p) & Part 73 for Trojan Plant After Spent Nuclear Fuel Is Moved to Proposed ISFSI Area ML20196J5131997-07-29029 July 1997 Rev 0 to Trojan Second Integrated Test Rept,Filter Media Processing Sys Trojan Nuclear Plant Spent Fuel Pool Debris Project ML20196J5241997-07-29029 July 1997 Rev 2 to In-Canal Equipment,Filter Media Processing Sys, Trojan Nuclear Plant Spent Fuel Pool Debris Project ML20137T9361997-04-0808 April 1997 Rev 1 to Trojan Proof of Principle Test Summary ML20137G1731997-03-20020 March 1997 Rev 6 to Trojan Plant Procedure,Tpp 20-2, Radiation Protection Program ML20137K5151997-03-0404 March 1997 Rev 0 to Trojan Proof of Principle Test Summary ML20138L1901997-01-30030 January 1997 Reactor Vessel & Internals Removal Plan ML20134C9901997-01-28028 January 1997 Proposed Tech Specs 5.0 Re Administrative Controls ML20134B8631997-01-16016 January 1997 Proposed Tech Specs Re Delete Paragraph 2.(C)(7) to Allow pre-operational Testing & Load Handling of Spent Fuel Transfer & Storage Casks in Trojan Fuel Building ML20134B5881997-01-16016 January 1997 Proposed Tech Specs Deleting Paragraph 2.(C)(7) to Allow Loading & Handling of Spent Fuel Casks & Insertion of New License Condition Authorizing Loading of Spent Fuel & Other Matls in Fuel Building ML20134A9571997-01-16016 January 1997 Proposed Tech Specs LCO 3.1.4 Re Spent Fuel Pool Load Restrictions ML20135B5071996-11-27027 November 1996 Proposed Tech Specs Reflecting New Fuel Debris Storage Container Design & Storage of non-fuel Bearing Components & Fuel Rod Storage Container in Trojan ISFSI ML20129E7341996-10-23023 October 1996 Proposed Tech Specs Re Spent Fuel Pool Debris Processing ML20059L1721993-11-30030 November 1993 Final Update to PGE-1043,Amend 3, Accident Monitoring Instrumentation Review, Identifying Rept as Historical by Placing Explanation in Preface to Be Inserted at Front of Document ML20059A5601993-10-21021 October 1993 Proposed Tech Specs Modifying Security License Conditions for Clarity ML20057F1631993-09-30030 September 1993 Updated Trojan Nuclear Div Manual ML20057D9131993-09-30030 September 1993 Amend 14 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan. W/Four Oversize Drawings ML20056F9971993-08-26026 August 1993 Rev 9 to Odcm ML20127P2121993-01-27027 January 1993 Proposed TS 6.2.2.f Re Composition of Fire Brigade & TS Table 6.2-1 Re Min Shift Crew Composition for Shift Manager & Noncertified Operator ML20126B7231992-12-0303 December 1992 Rev 13 to Chemistry Manual Procedure CMP 1, Primary-to-Secondary Leak Rate ML20127M6391992-11-16016 November 1992 Proposed Tech Specs for Deferral of Unscheduled Steam Generator ISI ML20126B7491992-09-25025 September 1992 Rev 7 to Event-Specific Emergency Instruction ES-3.3, Post- SG Tube Rupture Cooldown Using Steam Dump ML20126B7061992-09-25025 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.2, SG Tube Rupture W/Loss of Reactor Coolant - Saturated Recovery Desired ML20126B7331992-09-25025 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.3, SG Tube Rupture W/O Pressurizer Pressure Control ML20126B7411992-09-25025 September 1992 Rev 8 to Event-Specific Emergency Instruction ES-3.2, Post- Steam Generator Tube Rupture Cooldown Using SG Blowdown ML20126B7451992-09-25025 September 1992 Rev 7 to Event-Specific Emergency Instruction ES-3.1, Post- SG Tube Rupture Cooldown Using Backfill ML20126B7601992-09-25025 September 1992 Rev 18 to Emergency Instruction EI-3, SG Tube Rupture ML20126B7181992-09-23023 September 1992 Rev 7 to Emergency Contingency Action Procedure ECA-3.1, SG Tube Rupture W/Loss of Reactor Coolant - Subcooled Recovery Desired ML20126B7141992-08-20020 August 1992 Rev 19 to Off-Normal Instruction ONI-12, High Activity Radiation Monitoring ML20210D5281992-06-0808 June 1992 Errata to Amend 6 to PGE-1025, Environ Qualification Program Manual ML20141M1901992-03-27027 March 1992 Proposed Tech Specs Re Surveillance Requirements for Lco. Response to Request for Addl Info on Subj Encl ML20126B7201992-01-24024 January 1992 Rev 2 to Off-Normal Instruction ONI-3-12, SG Tube Leak ML20062F7391990-11-15015 November 1990 Amend 4 to PGE-1049, Trojan Nuclear Plant Inservice Insp Program for Second 10-Yr Interval,Jan 1987 - Dec 1996 ML20059L6701990-09-21021 September 1990 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20247C8941989-07-19019 July 1989 Proposed Tech Spec Table 3.6-1, Containment Isolation Valves ML20245C8091989-06-12012 June 1989 Proposed Tech Specs,Changing Orifice Size of Steam Line Safety Valves Shown in Tech Spec Table 4.7-1, Steam Line Safety Valves Per Loop ML20247E5331989-03-29029 March 1989 Rev 0 to Procedure QTS-VT-100, Visual Exam Procedure ML20248D3271989-03-27027 March 1989 Rev 0 to QAP-VT-108, Visual Exam ML20247E5491989-03-0202 March 1989 Rev 0 to Procedure TNP-QAP-VT108, Visual Exam ML20235L9441989-02-10010 February 1989 Proposed Tech Specs,Allowing Mods to Control Auxiliary Fuel Bldg Complex Resulting in Increase in Lateral Shear Forces on Any Story ML20235Q9191989-02-10010 February 1989 Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements for Containment Integrity for Equipment Hatches ML20154D1781988-09-0909 September 1988 Proposed Tech Specs Revising Pressurizer LPSI Setpoint 1999-08-05
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LCA 133
. Attachment 1 Page 1 of 4 REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All rods (shutdown and control) shall be OPERABLE and l positioned within i 12 steps (indicated position) of their group step counter demand position.
APPLICABILITY: MODES 1* and 2*
ACTION:
The ACTION to be taken is based on the cause of inoperability of the control rods as follows:
ACTION More Than CAUSE OF INOPERABILITY One Rod One Rod a) Immovable as a result of excessive (1) (1) f riction or mechanical interference or known to be untrippable.
b) Misaligned from its group step (4) (2) counter demand height or from any other rod in its group by more than i 12 steps (indicated position).
c) Inoperable due to a rod control urgent (3) (3) failure alarm or other electrical i
problem in the rod contrcl system, but presumed trippable.
ACTION 1 - Determine that the SHUTDOWN MARGIN requirement of Specifica-tion 3.1.1.1 is satisfied within 1 hoor and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 2 - Be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 3 - Restore the inoperable rods 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 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 />.
- See Special Exceptions 3.10.2 and 3.10.4.
TROJAN-UNIT 1 3/4 1-18 Amendment No. 79 8511050201 851101 PDR ADOCK 05000344 P PDR
LCA 133 Attachment 1 Page 2 of 4 REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION ACTION 4 - POWER OPERATION may continue provided that within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either: l
- 1. The rod is restored to OPERABLE status within the above alignment requirements, or
- 2. The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that:
a) An analysis of the potential ejected rod worth is performed within 3 days and the rod worth is deter-mined to be 5 0.98% ak at zero power and 5 0.21%
ak at RATED THERMAL POWER for the remainder of the fuel cycle, and b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined 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 c) The THERMAL POWER level is reduced to 5 75% of RATED THERMAL POWER WITHIN one hour and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to 5 85% of RATED THERMAL POWER, or d) The remainder of the rods in the group with the inoperable rod are aligned to within i 12 steps of the inoperable rod within one hour while maintaining the rod sequence and insertion limits of Figures 3.1-1 and 3.1-2; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.5 during subsequent operation.
SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each rod shall be determined to be within the l
group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
4 .1. 3 .1. 2 Each rod not fully inserted shall be determined to be OPERABLE by l movement of at least 10 steps in any one direction at least once per 31 days.
- l i
l l
TROJAN-UNIT l 3/4 1-18a Amendment No. 70 I i
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1
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LCA 133 Attachment 1 Page 3 of 4 REACTIVITY CONTROL SYSTEMS BASES 1 3/4.1.2 BORATION SYSTEMS (Continued)
With the RCS temperature below 200*F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable.
The boron inventory in the RWST or BAT is sufficient (a) to compensate for an inadvertent positive reactivity addition to the Reactor Coolant System of approximately 1 percent ak/k while in MODE 5 at 200*F; and (b) to l maintain a constant RCS reactivity while the temperature is decreased from 200*F to 80*F. In MODE 6, the BAT inventory is sufficient to increase the boron concentration to compensate for an inadvertent positive reactivity addition of approximately 1 percent ak/k while in the refueling mode.
These conditions require 8494 usable gallons of 7000-ppm borated water from the boric acid storage tanks or 23,432 usable gallons of 2000-ppm borated water from the refuelir.g water storage tank.
The required boric acid storage tank volume of 8494 gallons has been increased to a value greater than the minimum level indicating range (741 gallons), to 9235 gallons. The required RWST volume of 23,432 gallons must be increased to account for nonusable volume due to tank geometry, letdown and vortexing considerations (78,000 gallons), to 101,432 gallons (rounded to 102,000 gallons).
3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is main-tained, and (3) the potential effects of a rod ejection accident are limited.
OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits.
For purposes of determining compliance with Specification 3.1.3.1, any immovability of a control rod invokes ACTION Statement 3.1.3.1.a. Before utilizing ACTION Statement 3.1.3.1.c, the rod control urgent failure alarm must be illuminated or an electrical problem must be detected in the rod control system. The rod may then be presumed trippable if the rod was demonstrated OPERABLE during the last performance of Surveillance Require-ment 4.1.3.1.2 and met the rod drop time criteria of Specification 3.1.3.3 during the last performance of Surveillance Requirement 4.1.3.3.
TROJAN-UNIT 1 B 3/4 1-3 Amendment No. 58, 95,
LCA 133 Attachment 1 Page 4 of 4 REACTIVITY CONTROL SYSTEMS BASES 3 /4 .1. 3 MOVABLE CONTROL ASSEMBLIES (Continued)
The ACTIb:8 statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original criteiia are met. Misc.lignment of a rod requires measurement of peaking factors or a restriction of THERMAL POWER; either of these restrictions provides assurance of fuel rod integrity during continued operation. The reactivity worth of a misaligned rod is limited fcc tue remainder of the fuel cycle to prevent exceeding the assumptions used in the accident analysis for a rod ejection accident.
The maximum rod drop time restriction is consistent with the assumed rod drop time used in the accident analyses. Measurement with Tavg >550*F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.
Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more f requent verifications required if an automatic monitoring channel is inoperable. These verification f requencies are adequate for assuring
. that the applicable ICO's are satisfied.
TROJAN-UNIT 1 B 3/4 1-4 Amendment No. 58, 70
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION i l
l In the Matter of ) '
)
PORTLAND GENERAL ELECTRIC COMPANY, ) Docket 50-344 THE CITY OF EUGENE, OREGON, AND ) Operating License NPF-1 PACIFIC POWER & LICHT COMPANY )
)
(TROJAN NUCLEAR PIANT) )
CERTIFICATE OF SERVICE I hereby certify that copies of License Change Application 133 to the Operating License for Trojan Nuclear Plant, dated November 1, 1985, have been served on the following by hand delivery or by deposit in the United States mail, first class, this 1st day of November 1985:
Mr. Lyna Frank, Director State of Oregon Department of Energy Labor & Industries Blds, Rm 102 Salem OR 97310 Mr. Robert L. King Chairman of County Commissioners l
Columbia County Courthouse St. Helens OR 97051 1
4 7we-Qo t- G. A. Zimmerman, Manager Nuclear Regulation Branch Nuclear Safety & Regulation Subscribed and sworn to before me thir 1st day of November 1985.
b.
Notary Public of Orefdn My Commission Expires: h M s -
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