Letter Sequence Other |
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MONTHYEARML20211B8701986-06-0909 June 1986 Proposed Tech Spec 4.6.2.2.d,changing Containment Spray Sys Spray Additive Tank Flow Rate Surveillance Test Requirements Project stage: Other ML20211B8641986-06-0909 June 1986 License Change Application 143 to License NPF-1,changing Containment Spray Sys Spray Additive Tank Flow Rate Surveillance Test Requirements in Tech Spec 4.6.2.2.d Project stage: Other ML20211B8461986-06-0909 June 1986 Forwards License Change Application 143 to License NPF-1 Changing Tech Specs to Restore Original Surveillance Test Methodology Used During 1975 & 1981 Surveillances.Tech Spec 4.6.2.2.d Inadequate.W/Certificate of Svc.Fee Paid Project stage: Other ML20211K3051986-06-20020 June 1986 Forwards Amend 117 to License NPF-1 & Safety Evaluation. Amend Changes Tech Spec 4.6.2.2.d to Revise Containment Spray Sys Spray Additive Tank Flow Rate Surveillance to Reinstate Original Test Method Project stage: Approval 1986-06-20
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20210M5901999-08-0505 August 1999 Rev 1 to License Change Application 247,dtd 990310,for Amend to License NPF-1,adding License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan. with Certificate of Svc ML20196L1311999-05-24024 May 1999 Application for Amend to License NPF-1 for Indirect Transfer of License,To Extent That Such Approval Required Solely to Reflect Change in Upstream Operating Ownership of Pacificorp ML20207J3801999-03-10010 March 1999 Application for Amend to License NPF-1,adding License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan ML20198T1851999-01-0707 January 1999 Rev 3 to License Change Application 237 Re Spent Fuel Cask Loading in Fuel Bldg ML20198T1451999-01-0707 January 1999 Rev 3 to License Change Application 237 to License NPF-1, Inserting New License Condition to Authorize Loading of Spent Fuel & Other Matls Into Transtor Transfer & Storage Casks in Fuel Bldg ML20238E8261998-08-27027 August 1998 Application for Amend to License NPF-1,deleting Number of License Conditions & TS Requirements as Prerequisite to Implementing Requested Amend to Transfer of Nuclear Sf from Existing 10CFR50 Licensed Area to Proposed 10CFR72 ISFSI ML20199J5641998-01-29029 January 1998 Application for Amends to License NPF-1,deleting Security Plan Requirements of 10CFR50.54(p) & Part 73 for Trojan Plant After Spent Nuclear Fuel Is Moved to Proposed ISFSI Area ML20134C9781997-01-28028 January 1997 Application for Amend to License NPF-1,requesting to Clarify Controls That Will Be Used for Rev & Maint of Certified Fuel Handler Training Program ML20134A9531997-01-16016 January 1997 Application for Amend to License NPF-1,requesting Deletion of Paragaph 2.(C)(7) to Allow pre-operational Testing & Load Handling of Spent Fuel Transfer & Storage Casks in Trojan Fuel Bldg ML20134B7841997-01-16016 January 1997 License Change Application (Lca) 240 to License NPF-1.LCA Proposes to Delete Paragraph 2.(C)(7) to Allow Loading & Handling of Spent Fuel Casks in Trojan Fuel Bldg as Described in 10CFR72 License Application Submitted Mar 1996 ML20129E4751996-10-23023 October 1996 Application for Amend to License NPF-1,requesting Addition to Paragraph 2.(C)(8) to Allow Processing & Handling of Spent Fuel Pool Debris ML20059A5431993-10-21021 October 1993 Application for Amend to License NPF-1 to Modify Security License Condition for Clarity & Minimize Burden Associated W/Processing Application to Reflect Current Security Plan Rev ML20127P1691993-01-27027 January 1993 License Change Application 229 to License NPF-1,modifying OL to possession-only License to Allow Util to Possess SNM But Not Operate Nuclear reactor.Marked-up License NPF-1 Encl ML20127P2031993-01-27027 January 1993 License Change Application 230 to License NPF-1,revising Facility Staffing & Training Requirements in Light of Transition of Facility to Permanently Defueled Status ML20127M6361992-11-26026 November 1992 License Change Application 227 to License NPF-1,revising TS to Defer Unscheduled SG ISI Required by TS 4.4.5.3.c.1 Following primary-to-secondary Tube Leakage in Excess of TS Limits ML20141M1881992-03-27027 March 1992 Rev 1 to License Change Application 186 to License NPF-1, Changing TS 4.0.3 to Negatively State Failure to Perform Required Surveillances on Schedule Constitutes Noncompliance W/Operability Requirements of Lco,Per Generic Ltr 87-09 ML20059L6681990-09-21021 September 1990 Application for Amend to License NPF-1,consisting of License Change Application 203,Rev 1.Rev Reduces Scope of Previous Changes Re Tech Spec Table 3.6-1, Containment Isolation Valves ML20247C8771989-07-19019 July 1989 Application for Amend to License NPF-1 Consisting of License Change Application 179.Amend Changes Description of Turbine Steam Supply Valves in Tech Spec Table 3.6-1 from motor-operated to air-operated ML20246A7491989-06-30030 June 1989 Application for Amend to License NPF-1,consisting of License Change Application 182,reflecting Reorganization of Util Nuclear Div.Certificate of Svc & Description of Change Encl ML20244E6111989-06-12012 June 1989 Application for Amend to License NPF-1,changing Orifice Size of Steam Line Safety Valves Shown in Tech Spec Table 4.7-1, Steam Line Safety Valves Per Loop ML20235L9421989-02-10010 February 1989 Application for Amend to License NPF-1,consisting of License Change Application 174.Amend Revises Tech Specs to Allow Mods to Control Auxiliary Fuel Bldg Complex Resulting in Increase in Lateral Shear Forces of Any Story ML20235Q9101989-02-10010 February 1989 Application for Amend to License NPF-1,consisting of License Change Application 173,clarifying Surveillance Requirements for Containment Equipment Hatch ML20154D1681988-09-0909 September 1988 Application for Amend to License NPF-1,revising Tech Specs Re Setpoint for Pressurizer LPSI Ressure Safety Injection Necessary to Accommodate New Instrumentation ML20151T4991988-08-12012 August 1988 Application to Amend License NPF-1,consisting of License Change Application 169,revising Tech Specs Surveillance Requirements for ECCS Check Valves ML20151A0351988-07-0808 July 1988 Application for Amend to License NPF-1,incorporating Miscellaneous Editorial Corrections & Clarifications ML20148C2061988-03-18018 March 1988 Application for Amend to License NPF-1,consisting of License Change Application 162,Rev 2,revising Tech Specs Re Offsite & Facility Organization Charts ML20147E7291988-03-0101 March 1988 Application for Amend to License NPF-1,consisting of Rev 1 to License Change Application 124,revising Tech Specs Re Containment Isolation Valves ML20196J8861988-03-0101 March 1988 License Change Application 165 Requesting Amend to License NPF-1,modifying Tech Specs by Removing 3.5% U-235 Limit on Reactor Fuel Assemblies & Increase Enrichment Limit for New Fuel Storage Racks to 4.5% ML20149K1401988-02-17017 February 1988 Application for Amend to License NPF-1,consisting of License Change Application 163,revising Tech Specs to Add New Instruments for Monitoring Steam Generator Blowdown Sys Liquid Effluent Radioactivity & Flow Rate ML20149L6891988-02-15015 February 1988 Application for Amend to License NPF-1,consisting of Rev 1 to License Application 162,revising Offsite & Facility Organization Charts.Description of Requested Changes Encl ML20149H0921988-02-0404 February 1988 Application for Amend to License NPF-1,consisting of License Change Application 164.Amend Revises Operability & Surveillance Requirements & Bases for Component Cooling Water Sys ML20147D4431988-01-15015 January 1988 Application for Amend to License NPF-l Consisting of License Change Application 162,revising Offsite & Facility Organization Charts ML20195H8801987-12-24024 December 1987 Application for Amend to License NPF-1,consisting of License Change Application 151,removing Portions of Tech Specs Re Fire Protection & Relocating Them to Vol 1 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan.. ML20237D6801987-12-18018 December 1987 Application for Amend to License NPF-1 Consisting of License Change Application 160,changing Tech Specs to Delete Requirement for Obtaining source-range Nuclear Instrument Detector Plateau Curves ML20237D6471987-12-16016 December 1987 Application for Amend to License NPF-1 Consisting of Rev 1 to License Change Application 154,to Correct Tech Specs Section 3/4.4.6.2 for Agreement W/Definition of Pressure Boundary Leakage ML20236W7391987-11-20020 November 1987 License Change Application 161 for Amend to License NPF-1, Revising Tech Specs to Include Effects of Nuclear Fuel Design Changes ML20236Q2191987-11-16016 November 1987 Application for Amend to License NPF-1,consisting of Rev 1 to License Change Application 142,resolving Control Room Habitability Issues by Changing Tech Spec Sections Re Chlorine Detection Sys & Control Emergency Ventilation Sys ML20236P4371987-11-13013 November 1987 Application for Amend to License NPF-1,consisting of License Change Application 153,revising Tech Specs to Extend Surveillance Time Period for Verifying Control Rod Insertability from 24 H to 7 Days ML20236N3821987-11-0909 November 1987 Application for Amend to License NPF-1,consisting of License Change Application 159,revising Tech Spec 3.9.9 to Resolve Inconsistencies within Tech Specs ML20236N5761987-08-0606 August 1987 Application for Amend to License NPF-1,consisting of License Change Application 154,correcting Tech Spec Section, Bases for Agreement W/Definition of Pressure Boundary Leakage ML20235W5301987-07-14014 July 1987 Application for Amend to License NPF-1,consisting of License Change Application 155 Re Solid Radwaste Sys ML20215K8131987-06-22022 June 1987 Application for Amend to License NPF-1,consisting of License Change Application 132,revising Operability Requirements for Reactor Trip Breakers & Surveillance Requirements for Manual Reactor Trip & Breakers ML20210B5801987-04-29029 April 1987 Application for Amend to License NPF-1,consisting of License Change Application 156,revising Tech Specs to Correct Typos & to Clarify Appropriate Process Used for Review & Approval of Temporary Changes to Procedures ML20209D0031987-04-20020 April 1987 Supplemental Application for Amend to License NPF-1, Incorporating License Change Application 152 Re Unneccessary Plugging of Steam Generator Tubes Which Increases Personnel Exposure & Reduces RCS Flow ML20212E2321987-02-26026 February 1987 Application for Amend to License NPF-1,consisting of Revised Pages for License Change Application 124 & License Change Application 135,adding Steamline Isolation Valves & Valve CV-8825 Back Onto Tech Spec Table 3.6-1 ML20211N9551987-02-20020 February 1987 Application to Amend License NPF-1,revising Steam Generator Tube Plugging Criteria in Tube Sheet Region.Fee Paid ML20211H3791987-02-11011 February 1987 License Change Application for Amend to License NPF-1, Increasing Setpoint Tolerance for Pressurizer & Main Steam Safety Valves from 1% to 2% ML20207Q5341987-01-20020 January 1987 Application to Amend License NPF-1,incorporating License Change Application 150 to Revise Surveillance Requirements for Safety Injection Sys Accumulator Isolation Valves. Description of Change Encl ML20207M5741987-01-0909 January 1987 Application for Amend to License NPF-1,consisting of Rev 1 to License Change Application 134,revising Min Contained Vol of Water Required in Condensate Storage Tank ML20215D2431986-12-12012 December 1986 Application for Amend to License NPF-1,consisting of License Change Application 127,separating Surveillance Requirement 4.7.3.1.c Into 4.7.3.1.c & 4.7.3.1.d & Listing Four Component Cooling Water Valves W/Modified Closure Signals 1999-08-05
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20210M5901999-08-0505 August 1999 Rev 1 to License Change Application 247,dtd 990310,for Amend to License NPF-1,adding License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan. with Certificate of Svc ML20196L1311999-05-24024 May 1999 Application for Amend to License NPF-1 for Indirect Transfer of License,To Extent That Such Approval Required Solely to Reflect Change in Upstream Operating Ownership of Pacificorp ML20206H4411999-05-0505 May 1999 Amend 201 to License NPF-1,revising PDTSs by Deleting ISFSI Area,Changes Also Revise TSs by Revising Subsection 4.1.1 & Replacing Existing Figure 4.1-1 with New Figure 4.1-1 & Adding New Page to Figure 4.1-1 as Listed ML20206C9301999-04-23023 April 1999 Amend 199 to License NPF-1,changes License NPF-1 by Adding New License Condition Entitled, Loading of Fuel Into Casks in Fuel Building ML20206C9701999-04-23023 April 1999 Amend 200 to License NPF-1,changes License by Revising License Condition 2.C.(10), Loading of Fuel Into Casks in Fuel Building ML20207J3801999-03-10010 March 1999 Application for Amend to License NPF-1,adding License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan ML20198T1451999-01-0707 January 1999 Rev 3 to License Change Application 237 to License NPF-1, Inserting New License Condition to Authorize Loading of Spent Fuel & Other Matls Into Transtor Transfer & Storage Casks in Fuel Bldg ML20198T1851999-01-0707 January 1999 Rev 3 to License Change Application 237 Re Spent Fuel Cask Loading in Fuel Bldg ML20238E8261998-08-27027 August 1998 Application for Amend to License NPF-1,deleting Number of License Conditions & TS Requirements as Prerequisite to Implementing Requested Amend to Transfer of Nuclear Sf from Existing 10CFR50 Licensed Area to Proposed 10CFR72 ISFSI ML20199J5641998-01-29029 January 1998 Application for Amends to License NPF-1,deleting Security Plan Requirements of 10CFR50.54(p) & Part 73 for Trojan Plant After Spent Nuclear Fuel Is Moved to Proposed ISFSI Area ML20148K3491997-06-0909 June 1997 Amend 198 to License NPF-1,revising possession-only License to Add Sf Debris in Plant Fuel Bldg ML20148D2551997-05-23023 May 1997 Amend 197 to License NPF-1,revising Permanently Defueled TS to Delete Requirement for NRC Prior Approval of Changes to Certified Fuel Handler Training Program ML20141H3031997-05-19019 May 1997 Amend 196 to License NPF-1,revising License to Delete Prohibition on Moving Spent Fuel Assembly Shipping Cask Into Fuel Building ML20137K5521997-03-31031 March 1997 Application for Coc 9271,requesting Approval to Allow one- Time Shipment of Trojan Rv Package as Type B Exclusively for Radioactive Matl Transportation Package ML20134C9781997-01-28028 January 1997 Application for Amend to License NPF-1,requesting to Clarify Controls That Will Be Used for Rev & Maint of Certified Fuel Handler Training Program ML20134B7841997-01-16016 January 1997 License Change Application (Lca) 240 to License NPF-1.LCA Proposes to Delete Paragraph 2.(C)(7) to Allow Loading & Handling of Spent Fuel Casks in Trojan Fuel Bldg as Described in 10CFR72 License Application Submitted Mar 1996 ML20134B5761997-01-16016 January 1997 Application for Amend to License NPF-1,deleting Paragraph 2.(C)(7) to Allow Loading & Handling of Spent Fuel Casks & Insertion of New License Condition Authorizing Loading of Spent Fuel & Other Matls in Fuel Building ML20134A9531997-01-16016 January 1997 Application for Amend to License NPF-1,requesting Deletion of Paragaph 2.(C)(7) to Allow pre-operational Testing & Load Handling of Spent Fuel Transfer & Storage Casks in Trojan Fuel Bldg ML20134F1061996-10-31031 October 1996 Amend 195 to License NPF-1,revising Section 5.0,ACs,of Plant Permanently Defueled Tss,App A,To Reflect Organization Changes of Licensee,As They Apply to Oversight & Mgt of Plant ML20129E4751996-10-23023 October 1996 Application for Amend to License NPF-1,requesting Addition to Paragraph 2.(C)(8) to Allow Processing & Handling of Spent Fuel Pool Debris ML20058K1281993-12-0606 December 1993 Amend 193 to License NPF-1,relocating RETS to ODCM & PCP in Accordance W/Gl 89-01 & Changing Required Frequency for Submittal of Radioactive Effluent Release Rept from Semiannual to Annual ML20059A5431993-10-21021 October 1993 Application for Amend to License NPF-1 to Modify Security License Condition for Clarity & Minimize Burden Associated W/Processing Application to Reflect Current Security Plan Rev ML20057D0771993-09-22022 September 1993 Amend 192 to License NPF-1,relocating Portions of Plant TS Re Plant Fire Protection Program from TS to Topical Rept PGE-1012 ML20128K1001993-02-11011 February 1993 Corrected TS Page 3/4 3-49a to Amend 189 to License NPF-1, Reflecting Correct Spelling of Kziu in Items 4.c & 6.c ML20127P1691993-01-27027 January 1993 License Change Application 229 to License NPF-1,modifying OL to possession-only License to Allow Util to Possess SNM But Not Operate Nuclear reactor.Marked-up License NPF-1 Encl ML20127P2031993-01-27027 January 1993 License Change Application 230 to License NPF-1,revising Facility Staffing & Training Requirements in Light of Transition of Facility to Permanently Defueled Status ML20127P5741993-01-26026 January 1993 Amend 189 to License NPF-1,revising Plant TS 3/4.3.3.7, Fire Protection Instrumentation ML20125B8031992-12-0404 December 1992 Amend 188 to License NPF-1,deleting License Condition 2.C.(11) Re Fuel Assemblies ML20127M6361992-11-26026 November 1992 License Change Application 227 to License NPF-1,revising TS to Defer Unscheduled SG ISI Required by TS 4.4.5.3.c.1 Following primary-to-secondary Tube Leakage in Excess of TS Limits ML20141M1881992-03-27027 March 1992 Rev 1 to License Change Application 186 to License NPF-1, Changing TS 4.0.3 to Negatively State Failure to Perform Required Surveillances on Schedule Constitutes Noncompliance W/Operability Requirements of Lco,Per Generic Ltr 87-09 ML20059L6681990-09-21021 September 1990 Application for Amend to License NPF-1,consisting of License Change Application 203,Rev 1.Rev Reduces Scope of Previous Changes Re Tech Spec Table 3.6-1, Containment Isolation Valves ML20059C7901990-08-27027 August 1990 Amend 162 to License NPF-1,revising Tech Spec 3/4.6.1, Containment Integrity ML20058L4511990-08-0202 August 1990 Corrected Amend 161 to License NPF-1,revising Items 6.4.1 & 6.4.2 Re Administrative Controls ML20055C7511990-06-18018 June 1990 Amend 161 to License NPF-1,changing Qualification Requirements,As Specified in Tech Spec 6.3.1,that Must Be Met by Radiation Protection Manager ML20245H3661989-08-10010 August 1989 Corrected Page 3/4 7-18 to Amend 152 to License NPF-1 ML20247C8771989-07-19019 July 1989 Application for Amend to License NPF-1 Consisting of License Change Application 179.Amend Changes Description of Turbine Steam Supply Valves in Tech Spec Table 3.6-1 from motor-operated to air-operated ML20246A7491989-06-30030 June 1989 Application for Amend to License NPF-1,consisting of License Change Application 182,reflecting Reorganization of Util Nuclear Div.Certificate of Svc & Description of Change Encl ML20245E6491989-06-20020 June 1989 Amend 154 to License NPF-1,revising Tech Spec 5.7.2.2 to Allow Mods to control-auxiliary-fuel Bldg Complex ML20244E6111989-06-12012 June 1989 Application for Amend to License NPF-1,changing Orifice Size of Steam Line Safety Valves Shown in Tech Spec Table 4.7-1, Steam Line Safety Valves Per Loop ML20247M9211989-05-24024 May 1989 Amend 153 to License NPF-1,permitting Use of Upgraded Fuel Assemblies Which Incorporate Features of Westinghouse VANTAGE5 Fuel Assemblies & Allowing Extended Fuel Burnup to 60 Gwd/Mt & Higher Nuclear Peaking Factors ML20247H9521989-05-15015 May 1989 Amend 152 to License NPF-1,revising Tech Specs Re Chlorine Detection Sys & Control Room Emergency Ventilation Sys ML20246P5991989-05-12012 May 1989 Corrected Amend 58 to License NPF-1,consisting of Tech Spec Page 3/4 1-15 Re Borated Water Sources During Shutdown ML20247F1871989-03-17017 March 1989 Amend 151 to License NPF-1,revising Tech Specs by Deleting U-235 Fuel Enrichment Limit on Fuel Assemblies & Authorizing Storage & Use of New Fuel Assemblies W/Enrichment Up to 4.5 Weight Percent ML20236C4651989-03-15015 March 1989 Corrected Tech Spec Page 3/4 3-47 to Amend 93 to License NPF-1 ML20235T5291989-02-28028 February 1989 Amend 150 to License NPF-1,reflecting Merger of Pacific Power & Light & Utah Power & Light Companies to Form Pacificorp ML20235L9421989-02-10010 February 1989 Application for Amend to License NPF-1,consisting of License Change Application 174.Amend Revises Tech Specs to Allow Mods to Control Auxiliary Fuel Bldg Complex Resulting in Increase in Lateral Shear Forces of Any Story ML20235Q9101989-02-10010 February 1989 Application for Amend to License NPF-1,consisting of License Change Application 173,clarifying Surveillance Requirements for Containment Equipment Hatch ML20154D1681988-09-0909 September 1988 Application for Amend to License NPF-1,revising Tech Specs Re Setpoint for Pressurizer LPSI Ressure Safety Injection Necessary to Accommodate New Instrumentation ML20151X1121988-08-17017 August 1988 Corrected Page to Amend 142 of License NPF-1 Re Administrative Controls ML20151T4991988-08-12012 August 1988 Application to Amend License NPF-1,consisting of License Change Application 169,revising Tech Specs Surveillance Requirements for ECCS Check Valves 1999-08-05
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l PORTLAND GENERAL ELECTRIC COMPANY EUGENE WATER & ELECTRIC BOARD AND PACIFIC POWER & LIGHT COMPANY Operating License NPF-1 Docket 50-344 License Change Application 143 This License Change Application requests modifications to Operating License NPF-1 for the Trojan Nuclear Plant to change the Containment Spray System spray additive tank flow rate surveillance test requirements in Technical Specification 4.6.2.2.d.
PORTLAND GENERAL ELECTRIC COMPANY By ^rM Bart D. Withers Vice President Nuclear Subscribed and sworn to before me this 9th day of June 1986.
A /
' ' Notary Public of C.'egon My Commission Expires: Dd Ib h 8606120101 860609 PDR ADOCK 05000344 P PDR m
O LCA 143 Page 1 of 3 DESCRIPTION OF CHAN E This change returns the Containment spray additive tank flow rate surveillance requirement in Technical Specification 4.6.2.2.d to its original format prior to the issuance of Amendment 87. The current Technical Specification is in the format described in Revision 4 to NUREG-0452, Standard Technical Specifications for Westinghouse Pressurized Water Reactors, to allow measurement of flow through drain valves CS-026 cod CS-027. This testing method will not work at Trojan, however, due to a system configuration limitation which was not recognized during testing done to support the Technical Specification change to the new format.
The proposed Technical Specification will require the NaOH tank to be drained and refilled with water. The flow rate of the water from the spray additive tank to the eductor will then be measured with the Con- '
tainment spray pump on recirculation to the Refueling Water Storage Tank (RWST). The proposed change is shown in Attachment 1.
REASON FOR CHANGE In 1981, the spray additive tank flow rate was measured by draining the NaOH from the tank, refilling the tank with water and then educting the water into the Containment Spray System with the pump on recirculation to the RWST. This testing verified the flow rate from the spray additive tank to be 37 3 spm. Subsequently, a data acquisition test was run to support a Technical Specification change to allow verification of spray additive flow rate by gravity drainage from system drain valves with NaOH in the tank in accordance with Revision 4 of NUREG-0452, Standard Technical Specifications for Westinghouse Pressurized Water Reactors. !
The data acquisition test measured a flow rate of approximately 28 spm ,
of NaOH for each train of Containment spray. These values were used to i change the Technical Specifications.
This year, while performing the test for the first time under the new Technical Specification, a flow of only approximately 16 spm of NaOH was achieved through each drain valve. While performing the test by gravity drainage of water from the RWST, a flow of approximately 28 gpm was measured. After several attempts to achieve the required flow rates with NaOH, a line-loss calculation was performed to determine the expected flow rate from the drain valves. The calculation showed the flow rate should be 14.35 spm with the limiting line-loss component being the i 3/4-in. drain valves. This result corresponded well with the measured NaOH flow rate. In order to verify a flow rate of 34-40 spm from the spray additive tank, the throttle valves (CS-003 and CS-004) must be the limiting line-loss components. Therefore, it was determined this test methodology could not be utilized at Trojan as it would not demonstrate the system could achieve the design flow rate. It is suspected that a valve lineup error was made when the data acquisition test was run in 1981 and that gravity flow from the RWST was what was measured at that time.
l LCA 143 Page 2 of 3 Since the inadequacy of the test could not have been identified until the test was run, the need for the emergency Technical Specification change could not have been averted. It should be noted, however, inat the test has a 5-year periodicity and the test will not be overdue until after September 1, 1987. Therefore, the Technical Specification chenge is actually required in time to allow the test to be completed by then.
The inability to perform the test in accordance with the Technical Speci-fications does not render the system inoperable, but demonstrates the Technical Specification is not adequate for determining operability. The system is still considered to be in an operable condition since this was demonstrated in 1981 by successful performance of the surveillance test previously described in the Technical Specifications. Since the previous test was adequate for demonstrating system operability, it is proposed that the Technical Specification surveillance requirement be changed back to the original surveillance requirement. As long as this change is made in time for the test to be performed within the surveillance test inter-val, the Technical Specifications will be satisfied. In the interim, gravity flow tests have been performed to demonstrate the spray additive tank outlet line is not blocked. Two tests were performed, one with MO-2056A and both drain valves (CS-026 and CS-027) open and one with MO-2056B and both drain valvos open. Flow rates through the spray additive tank outlet line of approximately 30 gpm were achieved. Cal-culations to support this flow test predicted flow rates of approximately 26.5 spm. Therefore, it has been concluded the spray additive tank out-let line is not blocked and the system would achieve 34-40 spm of spray additive flow.
SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION This change does not involve a significant increase in the probability or consequences of an accident since this change only proposes an alternate method for verifying operability of the spray additive system. There-fore, the proposed change does not alter the likelihood of supplying NaOH to the Containment spray water nor the amount of NaOH supplied.
This change does not create the possibility of a new or different kind of accident. Neither the design of the Containment Spray System nor the manner in which it would be operated in an accident are being altered.
The design basis of 34-40 gpm of spray additive flow is not being changed, only the method for verifying that flow is being changed. The proposed change to Surveillance Requirement 4.6.2.2.d is not related to accident creation.
This change does not involve a significant reduction in a margin of safety. Since no change is proposed to the Limiting Condition for Operation, the spray additive system will continue to ensure that:
(1) the iodine removal efficiency of the spray water is meintained, and (2) corrosion effects on components within containment are minimized, to the same extent as assumed in the accident analysis.
LCA 143 Page 3 of 3 In the April 6, 1983 Federal Register, the NRC published a list of examples of amendments that are not likely to involve a Significant Hazards Consideratior.. Example No. 2 of that list applies to this change and states:
"A change that constitutes an additional limitation, restriction, or control not presently included in the Technical Specifications, eg, a more stringent surveillance requirement."
This example is judged to apply because the proposed change requires an operational test using the Containment spray pumps as opposed to the less restrictive gravity flow test through drain valves.
Based on the above evaluation, the proposed change does not pose a significant hazard.
S_AFETY/ ENVIRONMENTAL EVALUATION Safety and environmental evaluations were performed as required by 10 CFR 50 and the Technical Specifications and are summarized below.
Since the change only proposes a different method for verifying operabil-ity of the spray additive system, the probability or consequences of an accident are not increased, nor is there a possibility of creating a different kind of accident. For the same reason, the probability or consequences of a malfunction of equipment important to safety are not increased, nor is there a possibility of creating a different kind of malfunction.
This change does not affect the Bases of the Technical Specifications or any FSAR analyses because no change is proposed which affects the assumptions or results of the accident analyses.
This change does not have any environmental effect because this change does not involve an unreviewed environmental question and no affect to the public health and safety will occur.
SAB/kal 5770k.686 l
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