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MONTHYEARML20134D5231985-08-0101 August 1985 Proposed Tech Spec Changes Re Operability of Fire Detection Instrumentation Project stage: Other ML20134D5191985-08-0101 August 1985 Application to Amend License DPR-54,upgrading Existing Tech Specs for Compliance W/App R Requirements & Providing Addl Tech Specs Re Fire Protection Features.Safety Analysis & NSHC Determination Encl Project stage: Request ML20137L2221985-11-25025 November 1985 Rev 1 to Proposed Amend 137,changing Tech Specs to Add Water Deluge Sys in Area of Auxiliary Feedwater Pumps Project stage: Other ML20137L1991985-11-25025 November 1985 Application for Amend to License DPR-54,consisting of Rev 1 to Proposed Amend 137,adding Water Deluge Sys in Area of Auxiliary Feedwater Pumps,Per Discussion at 850206 Meeting on Fire Protection Project stage: Meeting ML20153E5241986-02-20020 February 1986 Proposed Tech Spec Table 3.14-2,adding Water Suppression Zone 110 to Auxiliary Feedwater Pump Project stage: Other ML20153E5171986-02-20020 February 1986 Application for Amend to License DPR-54,consisting of Suppl 1 to 850801 & 1125 Proposed Amend 137,Rev 1.Suppl Revises Tech Specs to Include Addl Water Suppression Zone 110 to Table 3.14-2 Per 10CFR50,App R.Safety Analysis Encl Project stage: Request ML20207Q6381986-12-24024 December 1986 Proposed Tech Specs Adding Water Suppression Zone 104 to Table 3.14-2 Per 10CFR50,App R Project stage: Other ML20207Q6281986-12-24024 December 1986 Rev 1,Supplement 2 to Application for Amend 137 to License DPR-54,revising Tech Specs to Include Water Suppression Zone 104 on Table 3.14-2 Per 10CFR50,App R.Safety Analysis & No Significant Hazards Evaluation Encl Project stage: Supplement ML20238B0441987-08-27027 August 1987 Forwards Amend 85 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs to Include Fire Protection Components in Auxiliary,Turbine & Svc Nuclear Electrical Bldgs & Clarifies Requirements on Fire Barriers Project stage: Approval 1986-12-24
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20129E3801996-10-14014 October 1996 Application for Amend to License DPR-54,representing Updated Licensing Basis for Operation of Shutdown Rancho Seco Nuclear Facility During Permanently Defueled Mode ML20058L4281993-12-0909 December 1993 Application for Proposed License Amend 187 to DPR-54 Re Changes Needed to Make PDTS Consistent W/New 10CFR20 Regulations.New 10CFR20 Effective 940101 ML20127N3291993-01-19019 January 1993 Application for Amend to License DPR-54,consisting of Proposed Amend 186,changing Organization & Requests Changes to Permanently Defueled Tech Specs Section D6.0 Administrative Controls Pages ML20246F0991989-07-0505 July 1989 Application for Amend to License DPR-54,resubmitting Rev 1 to Proposed Amend 102,deleting Remaining Nonradiological Items Contained in App B of Tech Specs.Shutdown of Facility on 890607 Makes Submittal of Improved Specs Impractical ML20235Y6011989-03-0606 March 1989 Application for Amend to License DPR-54,consisting of Suppl 1 to Proposed Amend 175,Rev 0,for one-time Extension for Certain Surveillances Required by Tech Specs to Be Performed Beginning 890329 ML20245H8851989-02-28028 February 1989 Rev 1 to Proposed Amend 130 to License DPR-54,adding Operating Requirements to Tech Specs Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation ML20195F7641988-11-18018 November 1988 Rev 1 to 881007 Proposed Amend 170,defining Applicability Requirements of Tech Spec 3.4 W/Respect to Auxiliary Feedwater Sys Flow Paths.Rev Deletes Words to the Condenser from Spec 4.8.1 ML20206F2811988-11-15015 November 1988 Suppl 1 to 880930 Application for Amend 166,Rev 1 to License DPR-54 Revising Tech Spec 4.6.4.f to Ensure Equipment Required to Verify Vital 120 Volt Ac Bus Operability ML20205R8631988-11-0404 November 1988 Application for Amend to License DPR-54,consisting of Rev 1 to Proposed Amend 172,withdrawing Request to Delete Reactor Bldg Spray Line Requirements & Justifying Removal of DHR Inlet Lines ML20205M8881988-10-28028 October 1988 Application for Amend 169 to License DPR-54,modifying Nuclear Svc Battery Surveillance Requirements.Fee Paid ML20205L2611988-10-25025 October 1988 Application for Amend to License DPR-54,consisting of Proposed Amend 173,modifying Tech Spec 3.14 to Remove Requirements for Fire Suppression Sys in Fire Zones 75-80. Fee Paid ML20155G2161988-10-0707 October 1988 Application for Amend to License DPR-54,clarifying Operational Mode Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Sys Train.Fee Paid ML20155B8111988-09-30030 September 1988 Application for Rev 1 to Amend 166 to License DPR-54, Revising Tech Specs Re Reactor Protection Sys Trip Setting Limits by Making Editorial Corrections & Technical Changes ML20155B4251988-09-30030 September 1988 Application for Amend to License DPR-54,making Editorial Corrections & Administrative Changes.Fee Paid ML20154J5521988-09-19019 September 1988 Application for Amend to License DPR-54,consisting of Proposed Amend 172,changing Local Leak Rate Test Requirements for Containment Penetrations.Fee Paid ML20154D7531988-09-0808 September 1988 Application for Amend to License DPR-54,consisting of Rev 1 to Amend 168,replacing Organization Charts W/More General Administrative Controls CEO-88-024, Supplemental Application for Amend to License DPR-54, Consisting of Rev 1 to Proposed Amend 102,deleting App B of Tech Specs1988-07-27027 July 1988 Supplemental Application for Amend to License DPR-54, Consisting of Rev 1 to Proposed Amend 102,deleting App B of Tech Specs CEO-88-002, Application for Proposed Amend 130 to License DPR-54,adding Operating Requirements Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation.Fee Paid1988-06-21021 June 1988 Application for Proposed Amend 130 to License DPR-54,adding Operating Requirements Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation.Fee Paid ML20155K0611988-06-14014 June 1988 Rev 0,Suppl 2 to Proposed Amend 159 to License DPR-54,making Minor Corrections to Tech Spec Table 3.5.5-1, Accident Monitoring Instrumentation,Items 5 & 14, & Table 4.1-1, Items 65 & 92 & Adding Second Note to Table 4.1-1,Item 80 ML20195J4561988-06-10010 June 1988 Application for Amend to License DPR-54,consisting of Proposed Amend 67,reducing Count Time Required for prebatch- Release Sample Analysis.Ser & NSHC Analysis Encl.Fee Paid ML20150D1791988-03-17017 March 1988 Application for Amend to License DPR-54,consisting of Proposed Amend 166,modifying Tech Specs to Correct Typos & Make Further Editorial Changes to Those Submitted in Proposed Amend 139.Fee Paid ML20196G5001988-03-0101 March 1988 Application for Amend to License DPR-54,consisting of Suppl 6 to Rev 0 to Amend 164,revising Tech Spec 4.1-1,Item 44.c & Tech Spec 4.10.1.E.2 to State Total Quantity of Gaseous Chlorine in Restricted Area ML20149K8521988-02-12012 February 1988 Suppl 4 to Rev 2 of Proposed Amend 138 to License DPR-54, Revising Tech Spec 6.5.1.6.d to Identify What Items Do Not Require Plant Review Committee Review ML20196D9001988-02-11011 February 1988 Suppl 1 to Rev 2 to Application for Amend 155 to License DPR-54,adding Term Dewatering to Process Control Program. Description of Changes Encl ML20149G1611988-02-0808 February 1988 Application for Amend to License DPR-54,consisting of Rev 0, Suppl 4 to Proposed Amend 164,adding Note to Tech Spec 3.3 to Eliminate Conflict W/Tech Spec 3.2.2.2 ML20196B7981988-02-0101 February 1988 Application for Proposed Amend 138 to License DPR-54.Amend Revises Nuclear Organization Chart,Figure 6.2-2 as Listed ML20148J3461988-01-13013 January 1988 Application to Amend License DPR-54,consisting of Proposed Amend 165,changing Tech Specs to Add Ventilation Radiation Monitor to Interim Onsite Storage Bldg.Fee Paid ML20149E5881988-01-0606 January 1988 Supplemental Application for Amend to License DPR-54, Consolidating Applicability Requirement for Containment Integrity in Tech Spec 3.6 Applicability Statement ML20149E1521987-12-23023 December 1987 Application for Amend to License DPR-54,consisting of Proposed Amend 159 Incorporating Accident Monitoring Instrumentation Recently Installed or Upgraded,Per Rev 3 to Reg Guide 1.97.Supersedes Amends 131 & 132.Fee Paid ML20149E8521987-12-23023 December 1987 Supplemental Application for Amend to License DPR-54, Consisting of Rev 2 to Proposed Amend 155,establishing New Set of Lower Limits of Detection for Prebatch Release & Composite post-release Analyses ML20236W8581987-12-0303 December 1987 Application for Amend to License DPR-54,consisting of Rev 0, Suppl 2 to Proposed Amend 164,combining Tech Specs 3.3.1.E & 3.3.1.F for Nuclear Svc Cooling & Raw Water.Revised Tech Spec Page 3-21 Encl ML20236U3241987-11-25025 November 1987 Suppl 1 to 860922 Application for Amend to License DPR-54, Consisting of Proposed Amend 145,adding Wording to Tech Spec Page 1-2b Re Surveillance of Internal Vent Valves to Cycle 8 Refueling Outage ML20236U0681987-11-25025 November 1987 Suppl 1 to Rev 0 to 871001 Application for Amend to License DPR-54,consisting of Proposed Amend 164.Attachment 1 Consists of Response to NRC Questions & Comments on Subj Proposed Amend & Util 871028 Responses to 34 Concerns ML20236V5821987-11-25025 November 1987 Application for Amend to License DPR-54,consisting of Suppl 2 to Rev 2 to Proposed Amend 138,changing Tech Spec Figures 6.2-1 & 6.2-2 to Assign Nuclear Security Manager & Staff Directly to Nuclear Power Production ML20236S0821987-11-17017 November 1987 Supplemental Application for Amend to License DPR-54, Consisting of Suppl 2 to Rev 2 to Proposed Amend 147, Concerning Diesel Generators ML20236P3411987-11-0606 November 1987 Supplemental Application for Rev 2 to Proposed Amend 152 to License DPR-54,revising Tech Specs Re Limiting Conditions for Operation of Instrumentation Sys ML20236K3761987-11-0202 November 1987 Application for Amend to License DPR-54,consisting of Proposed Amend 138,Rev 2,Suppl 1,adding non-licensed Personnel to Tech Spec Table 6.2-1,limited Representation to Tech Spec 6.5.2.5 & LERs to Tech Spec 6.5.2.6 ML20236D6451987-10-23023 October 1987 Application for Amend to License DPR-54,modifying Tech Specs to Provide Exception to Requirement That key-operated Shutdown Bypass Switch Not Be Used During Reactor Power Operation.Fee Paid ML20235R4051987-10-0303 October 1987 Rev 1 to Proposed Amend 155,revising Radiological Effluent Tech Specs to Incorporate Clarifications & Correct Editorial Errors ML20235Q4781987-10-0101 October 1987 Application for Proposed Amend 164 to License DPR-54, Consisting of Enhancements to Tech Specs to Resolve Certain Comments Resulting from NRC Region V Feb & Mar 1987 Contracted Comparison of Plant Tech Specs to Sts.Fee Paid ML20235F4521987-09-21021 September 1987 Application for Proposed Amend 162 to License DPR-54, Changing Tech Specs Re Concentration of Oxygen in Waste Gas Holdup Sys to Provide for When Sys Free of Potentially Explosive Gases,As for Example,During Maint.Fee Paid ML20195G4201987-09-16016 September 1987 Rev 2 to Proposed Amend 138,revising Tech Specs to Reflect Addl Organizational Changes Due to Need for Addl Mgt Staffing for Present Outage & from Expansion of long-term Mgt Function ML20236M3391987-07-31031 July 1987 Application for Amend to License DPR-54,consisting of Rev 2 to Proposed Amend 152,clarifying Proposed Limiting Conditions of Operation & Addl Surveillance Requirements for Emergency Feedwater Initiation & Control Sys ML20235F7541987-06-30030 June 1987 Application for Amend to License DPR-54,consisting of Amend 155,revising Tech Specs Re Radiological Effluents to Ensure Compliance W/Regulatory Requirements Concerning Effluent Monitoring & Nearby Land Use Identification.Fee Paid ML20235B8011987-06-29029 June 1987 Application for Amend to License DPR-54,revising Tech Specs to Modify Air Flow Rate Through Control Room Technical Support Ctr Essential Filtering Sys Per 10CFR50.91(b)(1).Fee Paid ML20235B6001987-06-29029 June 1987 Application for Amend 160 to License DPR-54,adding Tech Specs for Min Meteorological Instrumentation Required for Emergency Response Purposes Per Suppl 1 NUREG-0737 & Reg Guide 1.97.Fee Paid ML20214E2161987-05-14014 May 1987 Rev 1 to 860228 Application for Proposed Amend 111 to License DPR-54,reevaluating Effect of Containment Purging Coincident W/Loca Using TID Source Terms,Per NRC Request. Safety Analysis Also Encl ML20214D6371987-05-14014 May 1987 Application for Amend to License DPR-54,consisting of Proposed Amend 158,revising Tech Specs to Permit Operation of Combustible Gas Control Sys Using Two Proposed Thermal Hydrogen Recombiners.Fee Paid ML20209A7041987-04-23023 April 1987 Application for Amend to License DPR-54,revising Amend 82 Re Deficiency in Providing for Venting & Surveillance Testing of Low Temp Overpressure Protection Sys & Establishing Flow Rate for Nuclear Svc Electrical Bldg HVAC Unit.Fee Paid ML20206H1281987-04-0101 April 1987 Application for Amend to License DPR-54,revising &/Or Adding Addl Sections to Tech Specs & Addressing Safety Impact of Bringing Tdi Diesel Generators Into Svc. Description of Proposed Changes Encl 1996-10-14
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20211H7881999-08-13013 August 1999 Amend 126 to License DPR-54,changing Permanently Defueled TS (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP (Sfp)Level Alarm Switches with Generic Ref to SFP Level Instrumentation ML20198G8211997-08-22022 August 1997 Amend 125 to License DPR-54,revising TS to Incorporate Revised 10CFR20, Stds for Protection Against Radiation & Amending Refs from NRC Region V to Region IV ML20129E3801996-10-14014 October 1996 Application for Amend to License DPR-54,representing Updated Licensing Basis for Operation of Shutdown Rancho Seco Nuclear Facility During Permanently Defueled Mode ML20058L4281993-12-0909 December 1993 Application for Proposed License Amend 187 to DPR-54 Re Changes Needed to Make PDTS Consistent W/New 10CFR20 Regulations.New 10CFR20 Effective 940101 ML20127N3291993-01-19019 January 1993 Application for Amend to License DPR-54,consisting of Proposed Amend 186,changing Organization & Requests Changes to Permanently Defueled Tech Specs Section D6.0 Administrative Controls Pages ML20059G9521990-09-10010 September 1990 Amend 115 to License DPR-54,revising License Condition Re Fire Protection Plan,Adding Administrative Controls to Tech Specs in Support of Fire Protection Plan & Relocating Fire Protection Requirements to Fire Protection Plan ML20247B6821989-07-19019 July 1989 Errata to Amends 109,110 & 111 to License DPR-54,correcting Omission of Language ML20247B3461989-07-17017 July 1989 Amend 112 to License DPR-54,revising Tech Specs to Increase Max Closure Time for Selected Containment Isolation Valves & Add 12 Valves to Table 3.6-1 ML20246F0991989-07-0505 July 1989 Application for Amend to License DPR-54,resubmitting Rev 1 to Proposed Amend 102,deleting Remaining Nonradiological Items Contained in App B of Tech Specs.Shutdown of Facility on 890607 Makes Submittal of Improved Specs Impractical ML20245E1101989-06-20020 June 1989 Amend 111 to License DPR-54,revising Section 2.C.(4) to Remove Requirements for Certain Fire Doors & Dampers ML20245A1901989-06-0909 June 1989 Amend 110 to License DPR-54,revising Tech Specs by Removing Tabular Listing of Snubbers as Suggested by Generic Ltr 84-13 ML20248B6171989-06-0505 June 1989 Amend 108 to License DPR-54,modifying Paragraph 2.C.(3) of License to Require Compliance W/Amended Physical Security Plan ML20248B9311989-06-0505 June 1989 Amend 107 to License DPR-54,removing Requirements for Fire Suppression Sys in Fire Zones 75-80 from Tech Spec 3.14 ML20248B9531989-06-0505 June 1989 Amend 109 to License DPR-54,revising Tech Spec 4.17 Steam Generators & Associated Bases & Tables 4.17-2A & 4.17-2B to Permit Repairs of Steam Generator Tubes by Means of Tube Sleeves ML20247K7121989-05-23023 May 1989 Amend 105 to License DPR-54,clarifying Operational Mode of Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Train & Revising Surveillance Requirements & Frequency of Verifying Auxiliary Feedwater Sys Flow Path ML20247M9071989-05-23023 May 1989 Amend 106 to License DPR-54,revising Tech Spec 4.17, Steam Generators, to Provide for More Extensive Insp of Steam Generator Tubes by Defining Special Tube Areas to Complete 100% Insp Where Degradation Expected ML20247K6811989-05-16016 May 1989 Amend 104 to License DPR-54,deleting Tech Specs Re Reactor Vessel Matl Surveillance ML20245F8931989-04-18018 April 1989 Amend 103 to License DPR-54,revising Tech Specs by Changing Air Flow Rate Through Reactor Bldg Purge Valves,Adding Requirement to Test Reactor Bldg Purge Exhaust HEPA Filters ML20248E9221989-03-29029 March 1989 Amend 102 to License DPR-54,changing Tech Specs to Permit one-time Extension for Certain Local Leak Rate Tests to Cycle 8 Refueling Outage & Revising Surveillance Period for Local Leak Rate Tests on DHR Suction Piping ML20235Y6011989-03-0606 March 1989 Application for Amend to License DPR-54,consisting of Suppl 1 to Proposed Amend 175,Rev 0,for one-time Extension for Certain Surveillances Required by Tech Specs to Be Performed Beginning 890329 ML20245H8851989-02-28028 February 1989 Rev 1 to Proposed Amend 130 to License DPR-54,adding Operating Requirements to Tech Specs Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation ML20195F7641988-11-18018 November 1988 Rev 1 to 881007 Proposed Amend 170,defining Applicability Requirements of Tech Spec 3.4 W/Respect to Auxiliary Feedwater Sys Flow Paths.Rev Deletes Words to the Condenser from Spec 4.8.1 ML20206F2811988-11-15015 November 1988 Suppl 1 to 880930 Application for Amend 166,Rev 1 to License DPR-54 Revising Tech Spec 4.6.4.f to Ensure Equipment Required to Verify Vital 120 Volt Ac Bus Operability ML20205R8631988-11-0404 November 1988 Application for Amend to License DPR-54,consisting of Rev 1 to Proposed Amend 172,withdrawing Request to Delete Reactor Bldg Spray Line Requirements & Justifying Removal of DHR Inlet Lines ML20205M8881988-10-28028 October 1988 Application for Amend 169 to License DPR-54,modifying Nuclear Svc Battery Surveillance Requirements.Fee Paid ML20205L2611988-10-25025 October 1988 Application for Amend to License DPR-54,consisting of Proposed Amend 173,modifying Tech Spec 3.14 to Remove Requirements for Fire Suppression Sys in Fire Zones 75-80. Fee Paid ML20155G2161988-10-0707 October 1988 Application for Amend to License DPR-54,clarifying Operational Mode Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Sys Train.Fee Paid ML20155B8111988-09-30030 September 1988 Application for Rev 1 to Amend 166 to License DPR-54, Revising Tech Specs Re Reactor Protection Sys Trip Setting Limits by Making Editorial Corrections & Technical Changes ML20155B4251988-09-30030 September 1988 Application for Amend to License DPR-54,making Editorial Corrections & Administrative Changes.Fee Paid ML20155D3051988-09-28028 September 1988 Amend 100 to License DPR-54,deleting Organizational Charts from Tech Spec Administrative Section ML20154J5521988-09-19019 September 1988 Application for Amend to License DPR-54,consisting of Proposed Amend 172,changing Local Leak Rate Test Requirements for Containment Penetrations.Fee Paid ML20154D7531988-09-0808 September 1988 Application for Amend to License DPR-54,consisting of Rev 1 to Amend 168,replacing Organization Charts W/More General Administrative Controls CEO-88-024, Supplemental Application for Amend to License DPR-54, Consisting of Rev 1 to Proposed Amend 102,deleting App B of Tech Specs1988-07-27027 July 1988 Supplemental Application for Amend to License DPR-54, Consisting of Rev 1 to Proposed Amend 102,deleting App B of Tech Specs ML20151L5331988-07-14014 July 1988 Redistributed Amend 99 to License DPR-54,adding Limiting Conditions of Operation & Surveillance Requirements Re Shunt Trip Attachment Installed at Facility in Response to Generic Ltr 83-28 CEO-88-002, Application for Proposed Amend 130 to License DPR-54,adding Operating Requirements Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation.Fee Paid1988-06-21021 June 1988 Application for Proposed Amend 130 to License DPR-54,adding Operating Requirements Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation.Fee Paid ML20155K0611988-06-14014 June 1988 Rev 0,Suppl 2 to Proposed Amend 159 to License DPR-54,making Minor Corrections to Tech Spec Table 3.5.5-1, Accident Monitoring Instrumentation,Items 5 & 14, & Table 4.1-1, Items 65 & 92 & Adding Second Note to Table 4.1-1,Item 80 ML20195J4561988-06-10010 June 1988 Application for Amend to License DPR-54,consisting of Proposed Amend 67,reducing Count Time Required for prebatch- Release Sample Analysis.Ser & NSHC Analysis Encl.Fee Paid ML20151B3231988-03-30030 March 1988 Errata to Amends 97 & 98 to License DPR-54,correcting Inadvertent Errors in Tech Specs ML20148J8461988-03-17017 March 1988 Amend 98 to License DPR-54,revising Tech Specs by Reducing Limits of Detection for Liquid Radioactive Effluents & Changing Requirements to Address Hardware Changes in Effluent Sys ML20150D1791988-03-17017 March 1988 Application for Amend to License DPR-54,consisting of Proposed Amend 166,modifying Tech Specs to Correct Typos & Make Further Editorial Changes to Those Submitted in Proposed Amend 139.Fee Paid ML20153B2851988-03-15015 March 1988 Amend 97 to License DPR-54,modifying Various Sections of Tech Specs to More Closely Resemble B&W STS ML20196G5001988-03-0101 March 1988 Application for Amend to License DPR-54,consisting of Suppl 6 to Rev 0 to Amend 164,revising Tech Spec 4.1-1,Item 44.c & Tech Spec 4.10.1.E.2 to State Total Quantity of Gaseous Chlorine in Restricted Area ML20149M8541988-02-19019 February 1988 Amend 96 to License DPR-54,revising Administrative Controls Section of Tech Specs to Reflect Changes in Plant Mgt & Organization ML20149L6911988-02-12012 February 1988 Amend 95 to License DPR-54,revising Tech Specs to Reflect Hardware Mods Associated W/Reactor Bldg Combustible Gas Control.Hydrogen Purge Sys Replaced W/Incontainment Hydrogen Recombiner Sys ML20149K8521988-02-12012 February 1988 Suppl 4 to Rev 2 of Proposed Amend 138 to License DPR-54, Revising Tech Spec 6.5.1.6.d to Identify What Items Do Not Require Plant Review Committee Review ML20196D9001988-02-11011 February 1988 Suppl 1 to Rev 2 to Application for Amend 155 to License DPR-54,adding Term Dewatering to Process Control Program. Description of Changes Encl ML20149L2601988-02-0909 February 1988 Amend 94 to License DPR-54,adding Criteria to Tech Specs to Reflect Addition of Two Diesel Generators & Associated Mods to Facility Emergency Electrical Distribution Sys ML20149G1611988-02-0808 February 1988 Application for Amend to License DPR-54,consisting of Rev 0, Suppl 4 to Proposed Amend 164,adding Note to Tech Spec 3.3 to Eliminate Conflict W/Tech Spec 3.2.2.2 ML20196B7981988-02-0101 February 1988 Application for Proposed Amend 138 to License DPR-54.Amend Revises Nuclear Organization Chart,Figure 6.2-2 as Listed ML20148J3461988-01-13013 January 1988 Application to Amend License DPR-54,consisting of Proposed Amend 165,changing Tech Specs to Add Ventilation Radiation Monitor to Interim Onsite Storage Bldg.Fee Paid 1999-08-13
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$SMU- SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street, P.o. Box 15830. Sacramento CA 95852-183o.(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA RJR 85-375 August 1, 1985 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION HUGH L THOMPSON JR DIRECTOR DIVISION OF LICENSING V S NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 DOCKET NO. 50-312 i
LICENSE N0. DPR-54 PROPOSED AMENDMENT NO. 137 i In accordance with 10 CFR 50.59, the Sacramento Municipal Utility District hereby proposes to amend its Operating License DPR-54 for Rancho Seco Nuclear Generating Station Unit No. 1. Per the requirements of 10 CFR 50.92, this
, Proposed Amendment 137 has been evaluated by a No Significant Hazards Con-sideration in Attachment 1.
The attached Technical Specifications are provided to upgrade the existing Technical Specifications to be in compliance with the applicable Appendix R requirements based on the 1985 Rancho Seco FHAR update. In addition, as stated in the District's letter to NRC dated May 16, 1985, the District committed to provide by August 1, 1985, Technical Specifications to address NRC concerns as to fire protection features of the NSEB Attachment II to this submittal is a description of the proposed changes for Proposed Amendment 137.
Enclos'ed is a check for $150.00 as required by 10 CFR 170.21, " Statement of Fees."
Should you have any questions concerning this proposal, please contact Mr.Ron so 0 % at Rancho Seco Nuclear Generating Station.
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R. ODRIGU(
9 kJO N
od ASSISTANT GENERA MANAGER, NUCLEAR ,
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g Subscribed and sworn to before me ,,,_,,,,,,9 this /# day of 66u-4 6 , 1985. l ,,,,, PATRICIA K. GEISLER O
li[NEp-:' we NOTABY y rret.Ic-cAttrORNIA
, rRINCIPAL OFFICE IN j p, l M SACRAMENTO COUNTY 8 'f .MU m/ \e _A [ My Commission Egires February 16,1988 ;j g
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Notary Pub 1ic / *"*""""""""""""""""""""*""*""""""""*2 RANCHO SECO NUC, LEAR GENERATING STATION O 1444o Twin Cities Road, Herald, CA 95638-9799;(209) 333-2935
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8NT3 MUNICIPAL UTILITY DISTRICT
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S Street, P.O. Box 15830, Secrements. CA 95813 (916) 452 3211 1. Prsi nt 4 - credit Memo 1 3- - - 2.so.e. T.E s . neteausa 8880267-201 088450 i
. 3 Decit Mems 6 -Otner INwesCE ADJUSTaeEwys DISCOUNT NET INwOICE NO. DATE G5 DOSS AmeOU NT e NO. 137 07/25/35 150.00 0.00 0.00 150.00
- ** ** ** 15 0. 0 0 s=weeste e#es DETACM eEPORE DEPOSITING CHECM _
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. '( SMUD MANM OF AME RIC A 088450 SACRAMENTO MUNICIPAL UTILITY DISTRICT """'"'"*"' C^
6201 S Street.P.O. Box 15830, Sacramento CA 95813
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F REFERENCE 800 , -
.-DATE 8880267-201' g,07/25/85 .^
PAY EXACTLY k *******150.00) $
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PAY TO THE
"'" IssuRslNG ACCOUNT U.S. NUCLEAR REGULATORY COMM.
ATTN: WILLIAM 0. MILLER, CHIEF .
LICENSE FEE MANAGEMENT 8R ANCH ' ;, , : .:. .- ,
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WASHINGTON DC 20555 ;
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APPENDIX R TECHNICAL SPECIFICATIONS The District has embarked on an Appendix R reevaluation program. This program, to date, has resulted in the identification of.1) revisions to previously submitted exemptions; 2) additional exemption requests; 3) plant modifications; and .4) revision to the response to Generic Letter 81-12 (i.e.,
alternate shutdown capability). In addition, the District has developed the 1985 Rancho Seco Fire Hazard Analysis Report (FHAR) update based on providing alternative shutdown capability. Fire areas requiring plant modifications to comply with Appendix R requirements are provided with necessary compensatory measures until such time as those modifications are completed. The District has ensured Rancho Seco's compliance with Appendix R, III.G, either by analysis, modification, exemption request, or by putting suitable compensatory measures into place until resolution of the concern is reached.
The attached Technical Specifications are provided to upgrade the existing Technical Specifications to be in compliance with the applicable Appendix R requirements based on the 1985 Rancho Seco FHAR update. In addition, as stated in the District's letter to NRC dated May 16, 1985, the District committed to provide by August 1, 1985, Technical Specifications to address NRC concerns as to fire protection features of the NSEB. This submittal provides these additional Technical Specifications for the NSEB fire protection features. In support of this effort, the District has revised or drafted a total of 50 Appendix R procedures.
O
~
y y SAFETY ANALYSIS
$. RANCHO SECO NUCLEAR GENERATING STATION l.og Ns.
NCR NG , WORK REQUEST No.
ECN.No. ,
N/A- N/A N/A
Description:
(A detailed description of the desiredggs d w tgtgigt groggejffcatiggig inegdggeg iS*c'l* uke P d d 'i M I* N e'd3 protection components in the auxiliary building, turbine building, and NSEB, and clarify requirements on fire barriers. The minimum operable require-mints for heat, flame, and smoke detectors have been increased from approximately 50 percent of those available to requiring 100 percent of the available detectors being .
. operable.
' Reason for Change:
(A statement as to why the change is being requested.)
These revisions will upgrade the existing technical specifications to be in compliance with the applicable Appendix R requirements based on the 1985 Rancho Seco Fire Hazard Analysis Report (FHAR) update.
Evaluation and Basis for Safety Findings: ,
(The evaluation will address itself to specific sections of the SAR or Technical Specifications as applicable. If a safety question is involved, this will be so stated.) The fire protection components are based on the 1985 Rancho Seco FHAR update which defines areas containing redundant systems important to safe shutdown. The circuits for detection systems, CO2 systems, ana water suppression systems are non-class 1 and hav.e'no impact on safety related circuits or equipment. Failure considerations for water systems are discussed in USAR section 9.9.2.2 for auxiliary building and there is no adverse safety impact.
(See Attached)
Safety Findings:
Yes No O ~ G The proposed change is a change to the facility as described in the SAR.
- The fire protection components, if actuated,
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- O The proposed change affects Nuclear Safety, may impact nuclear safety.
O G The proposed' change does involve an Unreviewed Safety Question (If an Unreviewed Safety Question is involved, check the appropriate reason).
O Probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased.
O Possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created.
O The margin of safety as defined in the basis for any Technical Specification is reduced.
3 O The proposed change does involve a change in the Technical Specifications.
E - O The proposed change does involve an addition to the Technical Specifications.
i DATE REVIEW ENGINE DATE UCENSING ENGtNEER 7
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SAFETY ANALYSIS RANCHO SECO NUCLEAR GENERATING STATION ATTACHMENT The minimum operable requirements for detectors have been increased because
.the present operability requirement does not adequately address the cross zoning features of some of the detection systems. Also there are certain conditions when the loss of the second detector in a system will not be detectable in the control room and only. a walkdown of the system can determine detector operability.
Other changes are administrative in nature and have no safety impact.
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I Attachmsnt I .
No Significant Hazards Determination f-The proposed technical specifications have been evaluated and the District has determined that there is "No Significant Hazard consideration". The basis of this determination is:
- 1. Additional detectors, water suppression systems, carbon dioxide systems, and hose stations have been added to the j Tables to reflect the 1985 Rancho Seco FHAR update which !'
defines the safety related fire areas or areas containing redundant systems important to safe shutdown. Attachment II ,
-contains a detailed analysis of each proposed change. (See ;
items 2 through 14, 16 through 21, 23 through 26, 28, and 29.)
This change is a "No Significant Hazard Consideration" i based in example (ii) on page 14870 of Federal Register i notice dated April 6, 1983 which states " A change that i constitutes an additional limitation, restriction or control. not presently included in the Technical '
Specifications; for example, a more stringent surveillance requirement."
- 2. Specifications 3.14.3.1, 3.14.4.1 and 3.14.5.1 have been reformatted to a table format. The system location titles and zone designations have been revised to be consistent ,
with the titles and zone designations used on the control room displays. The fire protection technical specification bases and definition of the areas protected by fire barriers have been revised to be consistent with the 1985 Rancho Seco FHAR update. The reporting requirements of specification 6.9.5.E has 1,een modified to be consistent with specification 3.14. Attachment II contains a detailed analysis of each proposed change. See items 1, 15, 22, 27, 30, 31, and 32.
These changes are a "No Significant Hazard Consideration" based on example (i) on page 14870 of Federal Register notice dated April 6, 1983 which states "A purely administrative change to Technical Specifications,cfor example, a change to achieve consistency throughout the Technical Specifications, correction of an error, or a
- change in nomenclature" (
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- Description of Proposed Changes !
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- 1. Table 3.14-1, pages 3-55 through 3-55c--Instrument location title and zone designations have been revised to be consistent with titles and zone designations used on the control room displays. (NSHC No. 2)*
- 2. Table 3.14-1, pages 3-55 through 3-55c--The minimum operable require-ments for heat, flame, and smoke detectors have been increased 4
from approximately 50 percent of those available to requiring 100 percent of the available detectors being operable. A reanalysis I of the system design and control room display features has shown that the present operability requirement does not adequately ad-dress the cross zoning features of some of the detection systems.
Also, there are certain conditions where the loss of the second detector in a system will not.be detectable in the control room and only a walkdown of the system can determine detector opera- ,
bility. Therefore, the operability requirements have been in-creased in a conservative manner such that the loss of a single :
i detector will result in the establishment of hourly fire watch until the problem can be repaired. (NSHC No. 1)
- 3. Table 3.14-1, page 3-55--Existing detector zones 5 (South East l' Uncontaminated Area--Turbine Deck, Auxiliary Building) and 7 (Con-taminated Area--Turbine Deck, Auxiliary Building) have been added h to provide fire detection for portions of redundant systems impor-i tant to safe shutdown as described in the 1985 Rancho Seco Fire Hazard Analysis Report (FHAR) update. See fire area RT1. (NSHC No. 1)
- 4. Table'3.14-1, pages 3-55 through 3-55b--Existing detections zones 31 (Auxiliary Lube Oil Area--Grade Level, Turbine Building), 32 l
(Main Lube Oil Area--Grade Level, Turbine Building), 33 (Hydrogen i
Sealed Oil Unit--Grade Level, Turbine Building), 35 (Main Feed l
Pump Area), and 53-54 (Turbine Area) have been added to provide fire detection for portions of redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire area 71. (NSHC No. 1)
- 5. Table 3.14-1, pages 3-55--Existing detection zone 20 (Electrical Penetration Room--Mezzanine Level, Auxiliary Building) has been added to provide fire detection for portions of redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire areas 27 and 28. (NSHC No. 1)
- 6. -Table 3.14-1, page 3-55--Existing detection zone 21 (Reactor
. Building, 20 feet to 40 feet Level) has been added to provide detection for portions of redundant system's important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire area 69. (NSHC No. 1)
O(NSHC--Refers tn "No Significant Haza'rds Consideration" in Attachment I) 1
' 7. Table 3.14-1, paga 3-55a--Existing detection zone 42 (Electrical Penetration Room--Grade Level, Auxiliary Building) has been added to provide fire detection for portions of redundant systems impor-tant to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire areas 36, 62, and RBl. (NSHC No. 1)
- 8. Table 3.14-1, page 3-55a--Existing detection zone 43 (Chemical Mix Area--Grade Level, Auxiliary Building) has been added to provide fire detection for portions of redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire areas 36 and RG1. (NSHC No. 1)
- 9. - Table 3.14-1, page 3-55b--Existing detection zone 46 (Hut Area--
Basement Level, Auxiliary Building) has been added to provide fire detection for portions of redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire areas 47 and RB2. (NSHC No. 1)
- 10. Table 3.14-1, page 3-55b--Existing detection zone 83 (NSEB Corridor, 1 foot Level) has been added to provide fire detection for portions of redundant systems important to safe shutdown as described in the 1985 Rancho seco FHAR update. See fire area 83. (NSHC No. 1)
- 11. Table 3.14-1, page 3-55b--Existing detection zone 85 (NSEB Corridor, 40 feet Level) has been added to provide fire detection for portions of redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR Update. See fire are 85. (NSHC No. 1) . T
- 12. Table 3.14-1, page 3-55c--Existing detection zone 87 (NSEB Com-puter Room B) has been added to provide fire detection for por-tions of redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire area 87. (NSHC No.
1)
- 13. Table 3.14-1, page 3-55c--Existing detection zone 89 (NSEB Computer Room A) has been added to provide fire detection for portions of redundant systems important to safe shutdown as des-cribed in the 1985 Rancho Seco FHAR update. See fire area 89.
(NSHC No. 1)
- 14. Table 3.14-1, page 3-55c--New detection zone 104 (Technical Sup-port Center) has been added to provide fire detection for portions of redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire area 2. (NSHC No. 1)
- 15. Table 3.14-1, page 3-55c--New detection zone 109 (Chemical Lab Area--Auxiliary Building) has been added to provide fire detection for portions of redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire area RT1.
(NSHC No. 1) -
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'16.' Tabl$ 3.14-1, pagn 3-55c--New detection zono 110 (Auxiliary Feed-water Pump Area) has been added to provide fire detection for por-tion of redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire area 69. (NSHC No.
- 1) ,
- 17. Specification 3.14.3.1, pages 3-56, 3-56b, and 3-56c--Specifica-tion 3.14.3.1 has been reformatted to refer to Table 3.14-3 which provide a list of water suppression zones required to be operable.
The area location titles and zone designations have been revised to be consistent with the titles and zone designations used on the control room displays. (NSHC No. 2)
- 18. Table 3.14-2, page 3-56b--Existing water suppression zones 5 (South East Uncontaminated Area--Turbine Deck, Auxiliary Build-ing), 6 (North West Uncontaminated Area--Turbine Deck, Auxiliary Building), and 7 (Contaminated Area--Turbine Deck, Auxiliary Building) have been added to provide fire suppression for portions of redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire area RT1. (NSHC No.
1)
- 19. Table 3.14-2, page 3-56b--Existing water suppression zones (Mez-zanine Level--Turbine Building), 31 (Auxiliary Lube Oil Area--
Grade Level, Turbine Building), 33 (Hydrogen Sealed Oil Unit), and 35 (Main Feed pump Area) have been added to provide fire suppres-sion for portions of redundant systems important to safe shutdown' as described in the 1985 Rancho Seco FHAR update. See fire area
- 71. (NSHC No. 1)
- 20. Table 3.14-2, page 3-56b--Existing water suppression zone 18 (Air Condition Equipment Room-Mezzanine Level, Auxiliary Building) has been added to provide fire suppression for portions of redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire area RGl. (NSHC No. 1)
- 21. Table 3.14-2, p3ge 3-56b--Existing water suppression zone 19 (Com-munications Rochi--Mezzanine Level, Auxiliary Building) has been added to provide fire suppression for portions of redundant sys-tems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire areas 27 and 28. (NSHC No. 1)
- 22. Table 3.14-2, page 3-56c--Existing water suppression zone 47 (Pipe Penetration Area--Basement Level, Auxiliary Building) has been added to provide fire suppression for portions of redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire area RBl. (NSHC No. 1)
- 23. Table 3.14-2, page 3-56c--Existing water suppression zone 83 (NSEB-Corridor, 1 foot Level) has been added to provide fire suppression for portions of redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire area 83.
(NSHC No. 1) 3
- 24. Table 3.14-2, page 3-56c--Existing water suppression zona 85 (NSEB Corridor, 40 feet Level) has been added to provide fire suppression for portions of redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. Se's fire area 85.
(NSHC No. 1)
- 25. Table 3.14-2, page 3-56c--Existing water suppression zone 87 (NSEB Computer Room B) has been added to provide fire suppression for portions of redundant systems important to safe shutdown as des-cribed in the 1985 Rancho Seco FHAR update. See fire area 87.
(NSHC No. 1)
- 26. Table 3.14-3, page 3-56c--Existing watera suppression zone 89 (NSEB Computer Room A) has been added to provide fire suppression for portions of redundant systems important to_ safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire area 89.
(NSHC No. 1)
- 27. Specification 3.14.4.2, pages 3-56, 3-56d, and 3-56e--Specifica-tion 3.14.4.2 has been reformatted to refer to Table 3.14-4 which provides a list of carbon dioxide suppression zones required to be operable. The area location titles and zone designations have been revised to be consistent with the titles and zone designa-tions used on the control room display. (NSHC No. 2)
- 28. Table 3.14-3, page 3.56d--Existing carbon dioxide suppression zone 11 (West Battery Room--Mezzanine Level, Auxiliary Building) has '
been added to provide fire suppression for portions of redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire area 15. (NSHC No. 1)
- 29. Table 3.4-3, page 3-55e--Existing carbon dioxide suppression zones 53-54 (Turbine Area) have been added to provide fire suppression for portions of redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire area 71.
(NSHC No. 1)
- 30. Table 3.14-3, page 3-55e--Existing carbon dioxide suppression zone 1 79 (NSEB Battery GB) has been added to provide fire suppression for portions cWE redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire area 79.
l' (NSHC No. 1)
- 31. Table 3.14-3, page 3-55e--Existing carbon dioxide suppression zone i
80 (NSEB Battery GA) has been added to provide fire suppression for portions of redundant systems important to safe shutdown as i
described in the 1985 Rancho Seco FHAR update. See f re area 80.
l (NSHC No. 1) .
- 32. Specification 3.14.5.1, pages 3-56a 3-57a, 3-57a and 3-57b--
Specification 3.14.5.1 has been reformatted to place the list of required hydrants in Table 3.14-4. (NSHC No. 2) The hose stations l
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- 33. Table 3.14-4, page 3-57a--Existing NSEB Hose Stations FpHS-N-005 and FPHS-N-006 (Third Floor Corridor) have been added to provide fire i suppression for portions of redundant systems important to safe shutdown as described in the 1985 Rancho Seco FHAR update. See fire area 85. (NSHC No. 1)
- 34. Table 3.14-4, pages 3-57a and 3-57b--Existing Turbine Building Hose Stations (6 hose stations per level with a total of 18 hose stations) have been added to provide fire suppression for portions of redundant systems important to safe shutdown as described in
, the 1985 Rancho Seco FHAR update. See fire area 71. (NSHC No. 1)
- 35. Specification 3.14.6.1, page 3-58--Specification 3.14.6.1 has been revised to require all fire rated assemblies separating safety-related areas or separating portions of redundant systems important to safe shutdown within a fire area to be operable. The 1985 Rancho Seco FHAR update is based on separating portions of redundant systems important to safe shutdown within a fire area and this specification has been revised to be consistent with the FHAR.
(NSHC No. 2)
- 36. Bases, pages 3-58 and 3-59--The bases have been revised to be consistent with the revised specifications and the method used in the 1985 Rancho Seco FHAR update. (NSHC No. 2)
- 37. Specification 6.9.5.E, pages 6-12f and 6-12q--The special re- .
porting requirement of item E has been revised to be consistent with the reporting requirements of technical specification 3.14.
(NSHC No. 2) t 5
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