Letter Sequence Other |
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MONTHYEARML20126H8391985-06-14014 June 1985 Proposed Tech Specs Adding fail-to-start to Group of Emergency Diesel Generator Trips Not Automatically Bypassed Upon Loss of Voltage on Emergency Bus &/Or Safety Injection Signal.Certificate of Svc Encl Project stage: Other ML20126H8191985-06-14014 June 1985 Application for Amend to License NPF-1,consisting of License Change Application 123,adding fail-to-start to Group of Emergency Diesel Generator Trips Not Automatically Bypassed Upon Loss of Voltage Project stage: Request ML20126H7621985-06-14014 June 1985 Forwards Application for Amend to License NPF-1,consisting of License Change Application 123,adding fail-to-start to Group of Emergency Diesel Generator Trips Not Automatically Bypassed Due to Loss of Voltage.Fee Paid Project stage: Request ML20133P7541985-10-29029 October 1985 Proposed Tech Specs,Increasing Min Water Level to Be Maintained in Condensate Storage Tank to 70%.Certificate of Svc Encl Project stage: Other ML20133P7391985-10-29029 October 1985 Application for Amend to License NPF-1,consisting of License Change Application 134,revising Tech Specs to Increase Min Water Level to Be Maintained in Condensate Storage Tank to 70% Project stage: Request ML20133P7281985-10-29029 October 1985 Forwards Application for Amend to License NPF-1,consisting of License Change Application 134,revising Tech Specs to Increase Min Water Level to Be Maintained in Condensate Storage Tank to 70%.Fee Paid Project stage: Request ML20215N7011986-10-29029 October 1986 Forwards Amend 121 to License NPF-1 & Safety Evaluation. Amend Changes Tech Specs to Add fail-to-start to Automatic Diesel Generator Trips That Would Not Be Bypassed Upon Voltage Loss on Emergency Bus &/Or Safety Injection Signal Project stage: Approval ML20207M5791987-01-0909 January 1987 Proposed Tech Specs Re Min Water Level Required to Be Maintained in Condensate Storage Tank Project stage: Other 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 Project stage: Request ML20207M5541987-01-0909 January 1987 Forwards Application for Amend to License NPF-1,consisting of Rev 1 to License Change Application 134,revising Min Water Level Required to Be Maintained in Condensate Storage Tank.Certificate of Svc Encl Project stage: Request ML20209B7751987-04-22022 April 1987 Forwards Amend 130 to License NPF-1 & Safety Evaluation. Amend Revises Tech Spec Section 3.7.1.4 to Reflect Increase in Min Water Storage Level Required to Be Maintained in Condensate Storage Tank,Per Util 851029 & 870109 Requests Project stage: Approval ML20235P6541987-09-14014 September 1987 Forwards Corrected Pages to Amends 121 & 130 to License NPF-1.Page 3/4 8-3 Erroneously Replaced.Page B3/4 7-2a Should Have Been Intentionally Blank Since Revised Bases Incorporated Into Page B3/4 7-2 Project stage: Other 1986-10-29
[Table View] |
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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 134 .
o Attachment 1 Page 1 of 2 PLANT SYSTEMS CONDENSATE STORAGE TANK
' LIMITING CONDITION FOR OPERATION 3.7.1.4_ The condensate storage tank shall be OPERABLE with a minimum contained volume of 222,000 gallons of water.* l APPLICABILITY: MODES 1, 2, and 3.
ACTION:
With the condensate storage tank inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
- a. Restore the condensate storage t'ank to OPERABLE status or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or i
- b. Demonstrate the OPERABILITY of the Service Water System as a backup supply to the auxiliary feedwater pumps and restore the condensate storage tank to OPERABLE status within 7 days or be in NOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. .
SURVEILLANCE REQUIREMENTS N
4.7.1.4.1 The condensate storage tank shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the water level is within its limit when the tank is the supply source for auxiliary feedwater pumps.
4 4.7.1.4.2 The Service Water System shall be demonstrated OPERABLE at i least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that at least one Service Water System train is operating and that the Service Water System-feedwater isolation valves are either open or OPERABLE whenever the Service Water System is the supply source for the auxiliary feedwater pumps.
- Until modifications to the Auxiliary Feedwater System, including alterations to prevent spurious low suction pressure trips for the safety-related auxiliary feedwater pumps, are completed a minimum condensate storage tank level of 70 percent (325,000 gallons) shall be maintained.
J 8511010171 e!!1029 PDR ADOCK 05000344 P PDR j 1 TROJAN-UNIT 1 3/4 7-8 p-- wwm,aw-w-- y--,w,v-er,--m wg ,
LCA 134
- Attachment 1 Page 2 of 2 PLANT SYSTEMS BASES 3/4.7.1.4 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with steam discharge.
at atmosphere. concurrent with total loss of offsite power. Tha minimum contained volume accounts for: (1) water volume required to be delivered
- to the steam generators (196,000 gallons), (2) unusable volume in the bottom of the condensate storage tank (16,000 gallons), and (3) instrument error (9,500 gallons), rounded off to 222,000 gallons.
Temporarily, a minimum volume of 325,000 gallons (70-percent indicated level) is being maintained in the condensate storage tank to reduce the likelihood of low suction pressure trips when both safety-related auxiliary feedwater pumps are started simultaneously. Following Auxiliary Feedwater System modifications that provide alternate means of preventing common mode failure of the safety-related auxiliary feedwater pumps due to loss of suction, and alterations to prevent spurious low suction pressure trips, a minimum CST level of 70 percent will no longer be required.
W i
TROJAN-UNIT 1 B 3/4 7-2a 1
4
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)i i
UNITED STATES OF AMERICA I NUCLEAR REGULATORY COMMISSION l I
In the Matter of ) !
)
PORTLAND CENERAL ELECTRIC COMPANY, ) Docket 50-344 THE CITY OF EUGENE, OREGON, AND ) Operating License NPF-1 PACIFIC POWER & LIGHT COMPANY )
)
(TROJAN NUCLEAR PLANT) )
CERTIFICATE OF SERVICE I hereby certify that copies of License Change Application 134 to the Operating License for Trojan Nuclear Plant, dated October 29, 1985, have been served on the following by hand delivery or by deposit in the United States mail, first class, this 29th day of October 1985:
Mr. Lynn Frank, Director State of Oregon Department of Energy Labor & Industries Bldg. Rm 102 Salem OR 97310 Mr. Robert L. King Chairman of County Commissioners Columpla County Courthouse St. Helens OR 97051 yee G. A7 Zimmerman, Manager Nuclear Regulation Branch Nuclear Safety & Regulation Subscribed and sworn to before me this 29th day of October 1985.
Notary Public of Ore gn OMyCommission #
[
LCA 134 Page 1 of 2 REASON FOR CHANGE 1
Recent difficulties with the Auxiliary Feedwater (AFW) System have indi-cated that the safety-related AFW pumps are prone to low suction pressure trips on startup if the condensato storage tank (CST) level is less than 60 percent, particularly if both ? umps are started simultaneously. A.
Temporary Plant Test verified thr.t both pumps could be started simul-taneously from an automatic ini+,iation signal, and would continue to run and perform their design functions, if minimum CST level (when the pumps are started) was limited to 60 percent indicated. The minimum allowable level (for Modes 1, 2, and 3) was increased to 70 percent to account for instrument error and for the static head provided by the water in the suction pressure transmitter reference leg. From the Control Room Curves and Tables Manual, 70-percent level corresponds to a minimum contained volume of 325,000 gallons.
As stated in our letter of August 12, 1985, we do not consider this Technical Specification change to be necessary. A minimum CST level of 70 percent is being incorporated into Plant operating procedures as a limit below which one AFW pump will be declared inoperable, and the Action Statement of Technical Specification 3.7.1.2, Auxiliary Feedwater System will be implemented. Action Statement a of Technical Specifica-tion 3.7.1.2 requires that, with onc of the two safety-related AFW pumps inoperable, the inoperable pump must be restored 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 the Plant placed in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Submittal of this Technical Specification change (to a minimum CST level of 60 percent) was requested by the USNRC in your letter of September 13, 1985 (E. J. Butcher to B. D. Withers).
DESCRIPTION OF CHANGE Page 3/4 7-8. TTS 3.7.1.4. Condensate Storage Tank The minimum contained volume in the CST during operation in Modes 1, 2, and 3 is changed from 196,000 to 222,000 gallons. As described in the revised Bases for Technical Specification 3.7.1.4, the specification mandating 196,000 gallons does not account for instrument error and the .
unusable volume in the CST. A footnote is added to Technical Specifica-tion 3.7.1.4 explaining that an interim minimum CST level of 70 percent (325,000 gallons) will be maintained in the CST until modifications to the AFW System, including alterations to prevent spurious low suction pressure AFW pump trips, are completed.
Page B 3/4 7-2a. Bases 3/4.7.1.4 The Bases section for Technical Specification 3.7.1.4 has been expanded to identify the components of the 222,000 gallons minimum CST level. The interim minimum CST level of 70 percent (325,000 gallons) is also explained in the' revised Bases.
-. . . -. _ -- - _ _- ~_. -
LCA 134
' Page 2 of 2 SIGNIFIC_ ANT MAZARDS CONSIDERATION Ir. a letter to the NRC of August 12, 1985 (B. D. hithers to
- E. J. Butcher), PGE has already conunitted to maintaining 160-percent.
level in the CST by administrative controls. As noted in that letter.
- increasing the minimum operating level in the CST to 60 percent does not constitute an unreviewed safety question because the piobability of occurrence or the consequences of an accident or malfunction of equipment 1 important to safety previously evaluated in the safety analysis report is not increased. Raising the CST minimum water level to 60 percent decreases the probability and the consequences of an accident or malfunc-tion of equipment important to safety. A level of 60 pe. cent provides greater assurance that both AFW pumps will automatical'.y start and operate, and provides a greater volume of water in t*se CST for heat removal. These discussions also apply to increasing the minimum operating level in the CST to 70 percent.
f The possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report is not created by
+ increasing the minimum CST level to 70 percent. A minimum level of 70 percent provides additional conservatism and does not create the possibility for an accident or a malfunction of a different type than evaluated previously.
Also, the margin of safety defined in the basis for any Technical Speci-fication has not been reduced by this increase in minimum CST level. The margin of safety is increased by this change.
Based on the above, this Technical Specifiestion change does not involve a significant hazards consideration.
SAFETY / ENVIRONMENTAL EVALUATION Safety and environmental evaluations were performed as required by 10 CFR 50 and the Trojan Technical Specifications. This review deter-mined that an unreviewed safety question does not exist since Plant operations remain consistent with the Updated FSAR, adequate surveillance is maintained, and there is no conceivable impact upon the environment.
SCHEDULE CONSTDERATIONS Mone.
,- r-.-- - - - , , . - - , _ _ , .-w.,- ---, - --,- , - - - - - - - - - n,- ,, - - , -
I
'- LCA 134 ,
Attachment 1 Page 1 of 2 PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPERATION 3.7.1.4 The condensate storage tank shall be OPERABLE with a minimum contained volume of 222,000 gallons of water.* l APPLICABILITY: MODES 1, 2, and 3.
ACTION:
With the condensate storage tank inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
- a. Restore the condensate storage tank to OPERABLE status or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or
- b. Demonstrate the OPERABILITY of the Service Water System as a backup supply to the auxiliary feedwater pumps and restore the condensate storage tank to OPERABLE status within 7 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.1.4.1 The condensate storage tank shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the water level is within its limit when the tank is the supply source for auxiliary feedwater pumps.
4.7.1.4.2 The Service Water System shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that at least one Service Water System train is operating and that the Service Water System-feedwater isolation valves are either open or OPERABLE whenever the Service Water System is the supply source for the auxiliary feedwater pumps.
- Until modifications to the Auxiliary Feedwater System, including alterations to prevent spurious low suction pressure trips for the safety-related auxiliary feedwater pumps, are completed a minimum condensate storage tank level of 70 percent (325,000 gallons) shall be maintained.
f l l TROJAN-UNIT 1 3/4 7-8
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LCA 134
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PLANT SYSTEMS BASES 3/4.7.1.4 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with steam discharge at atmosphere concurrent with total loss of offsite power. The minimum contained volume accounts for: (1) water volume required to be delivered to the steam generators (196,000 gallons), (2) unusable volume in the bottom of the condensate storage tank (16,000 gallons), and (3) instrument error (9,500 gallons), rounded off to 222,000 gallons.
Temporarily, a minimum volume of 325,000 gallons (70-percent indicated level) is being maintained in the condensate storage tank to reduce the likelihood of low suction pressure trips when both safety-related auxiliary feedwater pumps are started simultaneously. Following Auxiliary Feedwater System modifications that provide alternate means of preventing common mode failure of the safety-related auxiliary feedwater pumps due to loss of suction, and alterations to prevent spurious low suction pressure trips, a minimum CST level of 70 percent will no longer be required.
TROJAN-UNIT 1 B 3/4 7-2a
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