ML17284A626
ML17284A626 | |
Person / Time | |
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Site: | Columbia ![]() |
Issue date: | 05/21/1998 |
From: | Poslusny C NRC (Affiliation Not Assigned) |
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Shared Package | |
ML17284A627 | List: |
References | |
NUDOCS 9806030102 | |
Download: ML17284A626 (6) | |
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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML17284A8891999-10-0606 October 1999
[Table view]Amend 159 to License NPF-21, Revising TS 3.4.11, RCS Pressure & Temp (PT) Limits ML17284A8851999-09-27027 September 1999 Amend 158 to License NPF-21,revising Minimum Critical Power Ratio Safety Limits ML17284A8361999-08-0202 August 1999 Amend 157 to License NPF-21,reflecting Name Change of Licensee from Washington Public Power Supply System to Energy Northwest & Name Change of Facility from Wpps Nuclear Project 2 to WNP-2 ML17292B5381999-01-27027 January 1999 Amend 156 to License NPF-21,revising TS SR 3.8.1.8 to Remove Restriction on Testing of Manual Transfer Between Startup & Backup Offsite Power Sources While in Modes 1 or 2 ML17292B5091998-12-29029 December 1998 Amend 155 to License NPF-21,authorizing Storage of Byproduct,Source & Special Nuclear Matls at WNP-2 Site ML17284A6301998-05-29029 May 1998 Amend 154 to License NPF-21,permitting Continued Use of Existing Siemens Power Corp MCPR Safety Limits for WNP-2 Fuel Cycle 14 & Changes Asea Brown Boveri MCPR Safety Limit for Single Loop Operation as Listed ML17284A6261998-05-21021 May 1998 Amend 153 to License NPF-21,authorizing Incorporation of Changes to Description of Facility in Fsar,As Described in Util 980416 Application ML17292B0581997-09-18018 September 1997 Amend 152 to License NPF-21,revising IST Requirements Specified in TS 5.5.6 for Inboard PCIV on TIP Sys Nitrogen Purge Line ML17292A9281997-07-0303 July 1997 Amend 151 to License NPF-21,revising TS 2.1.1.2 for MCPR Safety Limits of 1.13 for Two Loop Operation & 1.14 for Single Loop Operation of Siemens Power Corp Atrium 9X9 Fuel ML17292A9101997-06-11011 June 1997 Amend 150 to License NPF-21,revising TS SR 3.3.1.1.15,RPS Response Time Functions 3 & 4 & SR 3.3.6.1.7,PCIS Response Time,Functions 1.a,1.b & 1.c,adding Note to Indicate That Sensor Excluded ML17292A5251996-10-0101 October 1996 Amend 148 to License NPF-21,revising TS 6.3 to Change Operations Manager Qualification Requirements Associated W/Operations Knowledge ML17292A5151996-09-19019 September 1996 Amend 147 to License NPF-21,adding Reactor Water Cleanup Sys High Blowdown Containment Isolation Trip Function & Associated Limiting Condition for Operation & SR to TS ML17292A3031996-06-0404 June 1996 Amend 146 to License NPF-21,modifying TS to Support Cycle 12 Operation & Reflecting Use of New Fuel Obtained from ABB/C-E ML17292A2991996-06-0303 June 1996 Amend 145 to License NPF-21,modifying TS to Reflect Replacement of Existing Reactor Recirculation on Flow Control Sys W/Adjustable Speed Drive Sys ML17292A2241996-05-0808 May 1996 Amend 144 to License NPF-21,modifying TS for Leak Tests of Containment Isolation Valves ML17291B1841995-12-26026 December 1995 Corrected Page Xvii W/Overleaf Page for Document Correctness to Amend 143 to License NPF-21.Error, Administrative & Involves Changes Made by Amend 139 Not Included on Page Xvii ML17291B1331995-11-24024 November 1995 Amend 143 to License NPF-21,modifying Index of WNP-2 TS by Deleting Ref to Bases Pp ML17291B0991995-11-0909 November 1995 Correction to Amend 137 to License NPF-21.Amend Increased Authorized Max Power Level of Reactor from 3,323 Mwt to 3,486 Mwt & Modified TS to Incorporate Increased Power Limit in Plant Operating Limits ML17291B0701995-10-0505 October 1995 Amend 142 to License NPF-2,changing Surveillance Requirement Contained in TS 4.6.6.1.b.3 to Provide More Appropriate Acceptance Criteria for Demonstrating Operability of Pchrs ML17291B0261995-09-18018 September 1995 Amend 141 to License NPF-21,revising TS Surveillance Requirements Re Demonstration of Jet Pump Operability & Correcting Several Administrative Discrepancies ML17291B0011995-08-23023 August 1995 Amend 140 to License NPF-21,revising signal-to-noise Ratio for Source Range Monitors,As Recommended by GE ML17291A8931995-06-26026 June 1995 Amend 139 to License NPF-21,consisting of Changes to TS in Response to 940712 Application ML17291A8151995-05-17017 May 1995 Amend 138 to License NPF-21,revising TS to Change Figure 3.1.5-2 Sodium Pentaborate Tank,Vol Vs Concentration Requirements to Reflect Low Vol Alarm & Low Limit Values ML17291A7761995-05-0202 May 1995 Amend 137 to License NPF-21,increasing Authorized Max Power Level of Reactor from Current Limit of 3,323 Mwt to 3,486 Mwt ML17291A7131995-03-27027 March 1995 Amend 135 to License NPF-21.Amend Relocates Requirements Re Safety/Relief Valve Position Inidication Instrumentation from TS 3/4.3.7.5 & TS 3/4.4.2 to Other licensee-controlled Documents ML17291A5851995-01-0505 January 1995 Amend 133 to License NPF-21,revising TS to Delete Ref to Written Relief from ASME Code Requirements Being Granted by NRC ML17291A4281994-09-29029 September 1994 Amend 132 to License NPF-21,modifying TS to Add Note to TS Table 3.6.3-1, Pcivs, Allowing Operation of Facility Until Next Plant Shutdown,But Not Later than 950515,w/o Meeting single-failure Criterion for Logic Circuit for CIVs ML17291A3881994-09-14014 September 1994 Corrected Pages 3/4 6-23 & 3/4 6-24 to Amend 127 to License NPF-21 ML17291A3731994-08-22022 August 1994 Amend 131 to License NPF-21,relocating Requirements Re Seismic Monitoring Instrumentation from TS to FSAR ML17291A3041994-07-28028 July 1994 Amend 130 to License NPF-21,modifies TS to Add Inservice Insp Requirements for Reactor Coolant Sys Piping in Accordance W/Gl 88-01, NRC Position on Intergranular Stress Corrosion Cracking in BWR Austentic Stainless Steel Piping ML17291A2731994-07-21021 July 1994 Errata to Amend 128 to License NPF-21.Page 3/4 3-74,Item 9, Entitled Drywell Hydrogen Concentration, Issued W/ R in Channel Calibr Column Instead of Original Q ML17291A2261994-07-14014 July 1994 Errata to Amend 122 to License NPF-21,correcting Administrative Errors ML17291A2291994-07-0808 July 1994 Amend 128 to License NPF-21,re Changes to TS to Add Footnote to TS Table 4.3.7.5-1, Accident Monitoring Instrumentation SR Exempting SRV Position Indicator Channel Calibration from TS 4.0.4 Requirements ML17291A1841994-06-28028 June 1994 Amend 126 to License NPF-21,modifying Administrative Section of TS to Reflect Mgt & Organizational Changes at Util for Operation of Plant ML17291A1801994-06-28028 June 1994 Amend 127 to License NPF-21,changing Equipment Numbering on Three Primary Containment Isolation Valves ML17291A1671994-06-17017 June 1994 Amend 125 to License NPF-21,changing TS Table 3.6.3-1 by Increasing Stroke Time for RCIC V-8 Valve to 28 & Deleting Note (J) Ref from RCIC-V-8 & RCIC-V-63 ML17291A1481994-06-15015 June 1994 Amend 124 to License NPF-21,changing Containment Purge & Vent Valve TS by Removing Requirement Limiting Valve Open Position to Less than or Equal to 70 Degrees & Removing Surveillance Requirement Verifying Valves Blocked ML17291A1041994-05-27027 May 1994 Amend 122 to License NPF-21,adding Special Test Exception for Inservice Leak Testing & Hydrostatic Testing & Deleting Table B 3/4.4.6-1 Reactor Vessel Toughness from TS Bases ML17290B1341994-04-29029 April 1994 Amend 121 to License NPF-21,modifying TS to Reflect New Refueling Mast ML17290A9471994-01-31031 January 1994 Amend 120 to License NPF-21,modifies TS to Defer Response Time Testing for Low Pressure ECCS Until Startup Following Next Cold Shutdown,But Not Later than Startup Following Completion of Spring 1994 Refueling Outage ML17290A6931993-10-15015 October 1993 Amend 119 to License NPF-21,adding one-time Extension to Requirement for Testing Response Times of Actuation Channels for Containment Isolation ML17290A5971993-09-0808 September 1993 Amend 118 to License NPF-21,modifying Administrative Section of TS to Make Cnsrb Responsible to Amdo,Util Designated Manager ML17290A4261993-06-10010 June 1993 Amend 117 to License NPF-21,modifying TS to Implement Replacement of Current Noble Gas Monitor & Grab Sample Sys w/in-line,continuously Operating post-accident Sampler ML17290A4221993-06-10010 June 1993 Amend 116 to License NPF-21,modifying TS to Change Surveillance Test Intervals & Allowable Outage Times for Reactor Core Isolation Sys Actuation Instrumentation ML17290A3181993-05-12012 May 1993 Amend 115 to License NPF-21,modifying Design Features Section of TS to Incorporate Replacement Control Rod Blades Made of Boron Carbide & Hafnium ML17290A1941993-04-0909 April 1993 Amend 114 to License NPF-21,adding Footnote to TS 3.7.3, Reactor Core Isolation Cooling Sys, That Allows Plant Operation to Continue W/Rcic Automatic Transfer of Suction Path to Suppresion Pool Disabled Until 930517 ML17289B1981993-03-0808 March 1993 Amend 113 to License NPF-21,changing Section 6 of TS to Modify Title of Nuclear Safety Assurance Group to Nuclear Safety Assurance Div & Director of Licensing ML17289B1411993-01-26026 January 1993 Amend 112 to License NPF-21,eliminating MSL Radiation Monitor Scram Isolation Valve Closure Functions from TS ML17289B1191993-01-19019 January 1993 Corrected TS Pages to Amend 98 to License NPF-21,correcting Administrative Error in TS Table 3.3.7.12-1,explosive Gas Monitoring Instrumentation ML17289B0441992-12-0909 December 1992 Amend 111 to License NPF-21,modifying Bases & Action Statement for TSs 3.4.3.1 & 3.4.3.2 to Assure That Sections of TS Related to Leak Detection in Accordance W/Generic Ltr 88-01 1999-09-27 Category:TEXT-LICENSE APPLICATIONS & PERMITS MONTHYEARGO2-99-181, Application for Amend to License NPF-21,revising TS 3.3.6.1, Table 3.3.6.1-1, Primary Containment Isolation Instrumentation. Footnote (D) Is Removed Since Both Inboard & Outboard Trip Sys Are Now Functional in All Modes1999-10-13013 October 1999
[Table view]Application for Amend to License NPF-21,revising TS 3.3.6.1, Table 3.3.6.1-1, Primary Containment Isolation Instrumentation. Footnote (D) Is Removed Since Both Inboard & Outboard Trip Sys Are Now Functional in All Modes ML17284A8891999-10-0606 October 1999 Amend 159 to License NPF-21, Revising TS 3.4.11, RCS Pressure & Temp (PT) Limits ML17284A8851999-09-27027 September 1999 Amend 158 to License NPF-21,revising Minimum Critical Power Ratio Safety Limits ML17284A8361999-08-0202 August 1999 Amend 157 to License NPF-21,reflecting Name Change of Licensee from Washington Public Power Supply System to Energy Northwest & Name Change of Facility from Wpps Nuclear Project 2 to WNP-2 GO2-99-145, Application for Amend to License NPF-21,revising TS 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown1999-07-29029 July 1999 Application for Amend to License NPF-21,revising TS 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown GO2-99-142, Application for Amend to License NPF-21,removing License Condition 2.C.(16),Attachment 2,Item 3(b) Re post-accident Neutron Flux Monitoring1999-07-29029 July 1999 Application for Amend to License NPF-21,removing License Condition 2.C.(16),Attachment 2,Item 3(b) Re post-accident Neutron Flux Monitoring GO2-99-146, Application for Amend to License NPF-21,amending Tech Specs SR 3.8.4.6 of TS 3.8.5, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown1999-07-29029 July 1999 Application for Amend to License NPF-21,amending Tech Specs SR 3.8.4.6 of TS 3.8.5, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown GO2-99-144, Application for Amend to License NPF-21,revising Tech Specs SR 3.5.2.2, Condensate Storage Tank Water Level1999-07-29029 July 1999 Application for Amend to License NPF-21,revising Tech Specs SR 3.5.2.2, Condensate Storage Tank Water Level GO2-99-143, Application for Amend to License NPF-21,revising TS Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & 5.a1999-07-29029 July 1999 Application for Amend to License NPF-21,revising TS Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & 5.a ML17292B6891999-06-0303 June 1999 Application for Amend to License NPF-21,reflecting Change in Name of Washington Public Power Supply Sys to Energy Northwest.Marked-up Copy of Affected Pages of OL for Plant, Encl GO2-99-076, Application for Amend to License NPF-21,revising TS 3.4.11 to Replace Existing Reactor Pressure Temp Limit Curves by 0006301999-04-20020 April 1999 Application for Amend to License NPF-21,revising TS 3.4.11 to Replace Existing Reactor Pressure Temp Limit Curves by 000630 GO2-99-064, Application for Amend to License NPF-21,requesting Mod to MCPR Safety Limits by 990930 to Allow Continued Power Operation at Plant Following Restart from R-14 RFO1999-04-0707 April 1999 Application for Amend to License NPF-21,requesting Mod to MCPR Safety Limits by 990930 to Allow Continued Power Operation at Plant Following Restart from R-14 RFO ML17292B5381999-01-27027 January 1999 Amend 156 to License NPF-21,revising TS SR 3.8.1.8 to Remove Restriction on Testing of Manual Transfer Between Startup & Backup Offsite Power Sources While in Modes 1 or 2 ML17292B5091998-12-29029 December 1998 Amend 155 to License NPF-21,authorizing Storage of Byproduct,Source & Special Nuclear Matls at WNP-2 Site GO2-98-215, Application for Amend to License NPF-21,revising TS SR 3.8.1.8 to Allow for Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 9901251998-12-17017 December 1998 Application for Amend to License NPF-21,revising TS SR 3.8.1.8 to Allow for Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 GO2-98-187, Supplemental Application for Amend to License NPF-21, Requesting Minor Wording Changes to Clarify Intent of Proposed New License Section 2.B.(6).Addl Info That Describes Physical Storage of Matls,Encl1998-11-0909 November 1998 Supplemental Application for Amend to License NPF-21, Requesting Minor Wording Changes to Clarify Intent of Proposed New License Section 2.B.(6).Addl Info That Describes Physical Storage of Matls,Encl GO2-98-142, Application for Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-11998-08-0505 August 1998 Application for Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 GO2-98-128, Application for Exigent Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc, Battery E-B1-21998-07-17017 July 1998 Application for Exigent Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc, Battery E-B1-2 ML17284A6301998-05-29029 May 1998 Amend 154 to License NPF-21,permitting Continued Use of Existing Siemens Power Corp MCPR Safety Limits for WNP-2 Fuel Cycle 14 & Changes Asea Brown Boveri MCPR Safety Limit for Single Loop Operation as Listed ML17284A6261998-05-21021 May 1998 Amend 153 to License NPF-21,authorizing Incorporation of Changes to Description of Facility in Fsar,As Described in Util 980416 Application GO2-98-071, Application for Amend to License NPF-21,modifying Requirement That cold-worked Austenitic Stainless Steel Used in Newly Designed ECCS Pump Suction Strainers Must Have Yield Strength Not Greater than 90,000 Psi1998-04-16016 April 1998 Application for Amend to License NPF-21,modifying Requirement That cold-worked Austenitic Stainless Steel Used in Newly Designed ECCS Pump Suction Strainers Must Have Yield Strength Not Greater than 90,000 Psi GO2-97-219, Application for Amend to License NPF-21,modifying Min Critical Power Ratio Safety Limits by 980515 to Allow Continued Power Operation at WNP-2 Following Restart from R-13 Refueling Outage1997-12-0404 December 1997 Application for Amend to License NPF-21,modifying Min Critical Power Ratio Safety Limits by 980515 to Allow Continued Power Operation at WNP-2 Following Restart from R-13 Refueling Outage ML17292B0581997-09-18018 September 1997 Amend 152 to License NPF-21,revising IST Requirements Specified in TS 5.5.6 for Inboard PCIV on TIP Sys Nitrogen Purge Line GO2-97-156, Application for Amend to License NPF-21,modifying Inservice Testing Requirements Specified in TS 5.5.6 for Inboard Primary Containment Isolation Valve on Transvering in-core Probe (TIP) Sys Nitrogen Purge Line1997-08-14014 August 1997 Application for Amend to License NPF-21,modifying Inservice Testing Requirements Specified in TS 5.5.6 for Inboard Primary Containment Isolation Valve on Transvering in-core Probe (TIP) Sys Nitrogen Purge Line GO2-97-144, Application for Amend to License NPF-21,adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 Efpys.Changes Support Vessel Leak Testing1997-07-16016 July 1997 Application for Amend to License NPF-21,adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 Efpys.Changes Support Vessel Leak Testing ML17292A9281997-07-0303 July 1997 Amend 151 to License NPF-21,revising TS 2.1.1.2 for MCPR Safety Limits of 1.13 for Two Loop Operation & 1.14 for Single Loop Operation of Siemens Power Corp Atrium 9X9 Fuel ML17292A9101997-06-11011 June 1997 Amend 150 to License NPF-21,revising TS SR 3.3.1.1.15,RPS Response Time Functions 3 & 4 & SR 3.3.6.1.7,PCIS Response Time,Functions 1.a,1.b & 1.c,adding Note to Indicate That Sensor Excluded GO2-97-102, Application for Amend to License NPF-21,requesting Mod of Minimum Critical Power Ratio Safety Limits by 9706151997-05-20020 May 1997 Application for Amend to License NPF-21,requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 GO2-97-057, Application for Amend to License NPF-21,modifying Response Time Testing Surveillance Requirements for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation1997-03-22022 March 1997 Application for Amend to License NPF-21,modifying Response Time Testing Surveillance Requirements for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation GO2-96-199, Application for Amend to License NPF-21 to Modify TS for Secondary Containment & Standby Gas Treatment Sys to Reflect Revised Secondary Containment Drawdown & post-accident Analyses Results.Affidavit,Encl1996-10-15015 October 1996 Application for Amend to License NPF-21 to Modify TS for Secondary Containment & Standby Gas Treatment Sys to Reflect Revised Secondary Containment Drawdown & post-accident Analyses Results.Affidavit,Encl GO2-96-194, Application for Amend to License NPF-21,requesting Addition of Section 2B(6) Re Allowance of Storage of Byproduct, Source & Special Nuclear Materials1996-10-10010 October 1996 Application for Amend to License NPF-21,requesting Addition of Section 2B(6) Re Allowance of Storage of Byproduct, Source & Special Nuclear Materials ML17292A5251996-10-0101 October 1996 Amend 148 to License NPF-21,revising TS 6.3 to Change Operations Manager Qualification Requirements Associated W/Operations Knowledge ML17292A5151996-09-19019 September 1996 Amend 147 to License NPF-21,adding Reactor Water Cleanup Sys High Blowdown Containment Isolation Trip Function & Associated Limiting Condition for Operation & SR to TS GO2-96-159, Requests Amend to License NPF-21,revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-19711996-08-0909 August 1996 Requests Amend to License NPF-21,revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 ML17292A3031996-06-0404 June 1996 Amend 146 to License NPF-21,modifying TS to Support Cycle 12 Operation & Reflecting Use of New Fuel Obtained from ABB/C-E ML17292A2991996-06-0303 June 1996 Amend 145 to License NPF-21,modifying TS to Reflect Replacement of Existing Reactor Recirculation on Flow Control Sys W/Adjustable Speed Drive Sys ML17292A2241996-05-0808 May 1996 Amend 144 to License NPF-21,modifying TS for Leak Tests of Containment Isolation Valves GO2-96-089, Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage1996-04-24024 April 1996 Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage GO2-96-060, Application for Amend to License NPF-21,revising Containment Leakage Testing1996-03-19019 March 1996 Application for Amend to License NPF-21,revising Containment Leakage Testing GO2-96-014, Application for Amend to License NPF-21 Re Primary Containment Leakage Testing1996-01-19019 January 1996 Application for Amend to License NPF-21 Re Primary Containment Leakage Testing ML17291B1841995-12-26026 December 1995 Corrected Page Xvii W/Overleaf Page for Document Correctness to Amend 143 to License NPF-21.Error, Administrative & Involves Changes Made by Amend 139 Not Included on Page Xvii GO2-95-265, Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC1995-12-0808 December 1995 Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC ML17291B1331995-11-24024 November 1995 Amend 143 to License NPF-21,modifying Index of WNP-2 TS by Deleting Ref to Bases Pp ML17291B0991995-11-0909 November 1995 Correction to Amend 137 to License NPF-21.Amend Increased Authorized Max Power Level of Reactor from 3,323 Mwt to 3,486 Mwt & Modified TS to Incorporate Increased Power Limit in Plant Operating Limits GO2-95-228, Application for Amend to License NPF-21,revising TS to Reflect Replacement of Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys1995-10-26026 October 1995 Application for Amend to License NPF-21,revising TS to Reflect Replacement of Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys ML17291B0701995-10-0505 October 1995 Amend 142 to License NPF-2,changing Surveillance Requirement Contained in TS 4.6.6.1.b.3 to Provide More Appropriate Acceptance Criteria for Demonstrating Operability of Pchrs ML17291B0261995-09-18018 September 1995 Amend 141 to License NPF-21,revising TS Surveillance Requirements Re Demonstration of Jet Pump Operability & Correcting Several Administrative Discrepancies ML17291B0011995-08-23023 August 1995 Amend 140 to License NPF-21,revising signal-to-noise Ratio for Source Range Monitors,As Recommended by GE ML17291A8931995-06-26026 June 1995 Amend 139 to License NPF-21,consisting of Changes to TS in Response to 940712 Application GO2-95-105, Application for Amend to License NPF-21,modifying Index of TS by Deleting Ref to Bases Pages.Future Changes to Bases Info Will Be Evaluated Per 10CFR50.591995-06-0606 June 1995 Application for Amend to License NPF-21,modifying Index of TS by Deleting Ref to Bases Pages.Future Changes to Bases Info Will Be Evaluated Per 10CFR50.59 1999-09-27 |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 W
Amendment No. 153 License No. NPF-21 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Washington Public Power Supply System (licensee) dated April 16, 1998, as supplemented by letters dated April28, 1998, and May 8, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (I) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment willnot be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Accordingly, the license is amended to authorize changes to the Final Safety Analysis Report and paragraph 2.C.(30) of Facility Operating License No. NPF-21 is hereby amended to read as follows:
9806030L02 98052i PDR ADQCK 05000397 P
Ij (30) i' The Additional Conditions contained in Appendix C, as revised through Amendment No. 153, are hereby incorporated into this license.
Washington Public Power Supply System shall operate the facility in accordance with the Additional Conditions.
This amendment is effective as of its date of issuance and shall be implemented within 90 days from the date of issuance.
Implementation of the amendment is the incorporation in the Final Safety Analysis Report of the changes to the description of the facilityas described in the licensee's application dated April 16, 1998, as supplemented by letters dated April28, 1998, and May 8, 1998, and evaluated in the staff's Safety Evaluation attached to this amendment.
FOR THE NUCLEAR REGULATORYCOMMISSION Chester Poslusny, enior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Page 2 of Appendix C Date of Issuance:
May 21, 1998
l II Amendment Implementation D t 153 This amendment authorizes the licensee to incorporate in the Final Safety Analysis Report (FSAR) certain changes to the description of the facility. Implementation of this amendment is the incorporation of these changes as described in the licensee's application dated April 16, 1998, as supplemented by letters dated April28, 1998, and May 8, 1998, and evaluated in the staffs Safety Evaluation dated May 21, 1998.
90 days from the date of issuance.
153 This amendment is conditioned on the licensee Refueling Outage completing the commitments regarding inspection R-14.
of ECCS suppression pool screen material coupons as described in the licensee's supplemental letter dated April28, 1998, and evaluated in the staffs Safety Evaluation dated May 21, 1998.
Amendment No. 153