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MONTHYEARML20133M5531985-10-18018 October 1985 Proposed Tech Specs,Changing Offsite & Onsite Organization Charts Project stage: Other ML20133M5451985-10-18018 October 1985 Application for Amend to License DPR-54,consisting of Proposed Amend 138,changing Offsite & Onsite Organization Charts.Fee Paid Project stage: Request ML20205E9921986-08-12012 August 1986 Proposed Tech Specs,Changing Corporate Organizations That Provide Support to Nuclear Safety & Revising Shift Crew Personnel Complement for Compliance w/10CFR50.54(m)(2)(i) Project stage: Other ML20205E9791986-08-12012 August 1986 Application for Rev 1 to Proposed Amend 138 to License DPR-54,changing Corporate Organizations That Provide Support to Nuclear Safety & Revising Complement of Shift Crew Personnel for Compliance w/10CFR50.54(m)(2)(i) Project stage: Request ML20211E9231986-10-17017 October 1986 Forwards Updated Interim Organizational Charts for Nuclear Restart Implementation & Nuclear Plant Dept & Tabular Listing of Interim Corporate & Onsite Positions as Compared to Tech Spec Figures 6.2-1 & 6.2-2 Project stage: Other ML20211B2701987-02-11011 February 1987 Forwards Target Nuclear Organization for Restart (Transition Plan) for Review.Plan Provided to Facilitate Transition from Interim (Prestart) to Ultimate Nuclear Organization. Organizational Chart,Resumes & Position Descriptions Encl Project stage: Other 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 Project stage: Other ML20234D6591987-09-16016 September 1987 Proposed Tech Specs,Reflecting Addl Organizational Changes Due to Need for Addl Mgt Staffing for Present Outage & from Expansion of long-term Mgt Function Project stage: Other ML20236K3921987-11-0202 November 1987 Proposed Tech Spec Table 6.2-1, Shift Crew Personnel & License Requirements & Pages 6-7 & 6-8,adding non-licensed Personnel,Statement Re Limiting Representation to Minority of Quorom & Lers,Respectively Project stage: Other 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 Project stage: Request ML20236V7961987-11-25025 November 1987 Proposed Tech Spec Figures 6.2-1 & 6.2-2,reflecting Util Corporate Support of Nuclear Safety & Nuclear Organization Chart,Respectively Project stage: Other 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 Project stage: Request ML20149E5971988-01-0606 January 1988 Proposed Tech Spec 3.6,consolidating Applicability Requirement for Containment Integrity in Applicability Statement Project stage: Other 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 Project stage: Supplement ML20196B8071988-02-0101 February 1988 Proposed Tech Spec Figure 6.2-2, Nuclear Organization Chart Project stage: Other 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 Project stage: Request 1987-11-25
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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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SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, PO. Box 15830, Sacramento CA 95852-1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA JEW 86-322 August 12, 1986 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION FRANK J MIRAGLIA DIRECTOR PWR-B DIVISION U S NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 DOCKET N0. 50-312 LICENSE N0. DPR-54 PROPOSED AMENDMENT NO. 138, REVISION 1 In accordance with 10 CFR 50.90, the Sacramento Municipal Utility District proposes to amend its Operating License DPR-54 for Rancho Seco Nuclear Generating Station Unit No. 1.
Proposed Amendment No. 138, Revision 1 supersedes the originally Proposed Amendment No. 138 submitted to the NRC on October 16, 1985. Subsequent to the original submittal, there have been organization changes made by the District, both on site and at the corporate offices. This proposed amendment presents the Rancho Seco organization changes to date, and also identifies current corporate organizations that provide support to nuclear safety for Rancho Seco. Additionally, the complement of shift crew personnel is revised for compliance with 10 CFR 50.54(m)(2)(i). Details of this proposed amendment are provided in Attachments I, II and III, which are the Description of and Reason for Proposed Changes, the Safety Analysis, and No Significant Hazards Consideration, respectively.
The proposed changes are exclusive to Appendix A of the Technical Specifications.
Although the same organization changes are applicable to Appendix B, no amendment is proposed pending completion of NRC's review of Proposed Amendment No. 102 (December 12,1984), which requests deletion of Appendix B in its entirety from the Technical Specifications.
Pursuant to 10 CFR 50.91(b)(1), the Radiological Health Branch of the California State Department of Health Services has been informed of this proposed amendment by mailed copy of this submittal.
The District has determined that no license fees are required with this revision since a check for $150.00 was sent to the Commission with the initial submittal of Proposed Amendment No. 138.
The District would appreciate prompt review of this proposed amendment by the NRC, and upon issuance allow 90 days for implementation.
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Should you require any further information with respect to this revised proposed amendment, please contact Mr. Ron W. Colombo at Rancho Seco Nucl Generatin ta ion Unit 1.
7
. Wird DEPUTY GENERAL MANAGER, NUCLEAR Attachments Subscribed and sworn to before me this 12 % day of Auo ost,' 1986.
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ATTACHMENT I DESCRIPTION OF AND REASONS FOR PROPOSED CHANGES Proposed Amendment No.138, Revision 1, supersedes the original submittal of Proposed Amendment No. 138 on October 16, 1985,'and consists of organization changes with respect to Rancho Seco made by the District subsequent to the original submittal. Specifically, the following changes to the Technical Specifications are proposed:
- 1. The title for Figure 6.2-1 is changed on the Table of Contents, List of figures, page xii. See item 5 for details.
- 2. Throughout the Technical Specifications, position and group titles are changed or added as shown in Figures 6.2-1 and 6.2-2. The title changes are considered more descriptive of the management function, and the new positions reflective of the broader management oversight with respect to Rancho Seco.
- 3. The staff individual's qualifications identified in Specification 6.2.2d.
(page 6-1) is expanded to include radiation protection practices as well as procedures, and in Specification 6.2.2g. (page 6-1a), the term " health physicists" is changed to " radiation protection personnel". The first change adds to the individual's qualification requirement; the second is the result of a title change.
- 4. Table 6.2-1, Shift Crew Personnel and License Requirements, (page 6-2) is revised to be in accord with 10 CFR 50.54(m)(2)(i).
- 5. Figure 6.2-1, SMUD Nuclear Safety Organization Chart, (page 6-2a) is retitled to SMUD Corporate Support of Nuclear Safety to Rancho Seco. Accordingly, many of the corporate organizations which do not provide routine nuclear safety support of the plant are deleted. This simplification of Figure 6.2-1 is in agreement with the Standard Technical Specifications. The revised title of Figure 6.2-1 is also shown on the Table of Contents, List of Figures (page xii).
- 6. Figure 6.2-2, Plant Organization Chart (page 6-2b) is amended to show the revised and new positions and organization titles. Also, shift crew personnel and their license requirements are deleted, being redundant with Table 6.2-1. The footnote " Routine Reporting Requirements on Personnel Changes" and the designations on the organization chart to which the footnote applies is replaced with a general footnote stating:
" Organization changes may be made per 10 CFR 50.59 without prior NRC approval."
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- 7. Specification 6.5.1, Plant Review Committee (PRC), (pages 6-3 through 6-5) is revised to reflect the currently proposed charter. Composition of the PRC is revised, and responsibilities are amended to specify review of procedures' safety evaluations rather than the total procedures (Specification 6.5.1.6a).
A similar change is made with respect to proposed changes and modifications (Specification 6.5.1.6d). In addition, since the PRC reviews facility operations for potential safety hazards through routine review of design changes, procedure changes or violations, operating deficiencies, etc.,
Specification 6.5.1.6e and 6.5.1.6f are considered redundant and are deleted.
- 8. Specification 6.5.2, Management Safety Review Comittee, (pages 6-6 through 6-10a) is revised extensively to reflect the currently proposed charter.
Included in this is deletion of items a. through h., in Specification 6.5.2.1, Function, (page 6-6) and reference to listing of item a. through g. in Specification 6.5.2.7, Review, (pages 6-7 and 6-8). In Specification 6.5.2.3, it is made clear that the limitation on alternates is for the purposes of establishing a quorum. In addition, Specification 6.5.2.9, Records, is moved for editorial reasons to 6.5.2.8, and the forwarding of audit reports to the Deputy General Manager-Nuclear and to the General Manager is deleted. This is administratively made the responsibility of Nuclear Quality which also has the audit responsibilities. As revised, the MSRC reviews the QA program and does an oversight review of the QA Audit Program (see 6.5.2.7m and n).
- 9. Specification 6.5.2.8, Audits (page 6-9) is changed to Specification 6.5.4, which, in view of changes described in item 8 above, is a more appropriate location.
- 10. Specification 6.5.3, Technical Review and Controls, (pages 6-10 and 6-10a) is added in its entirety. This addition describes a new review and approval process for procedures, test and experiments, and plant modifications and describes overall responsibilities for these reviews which affect the safety of the plant. This change will broaden the safety review process and permit greater attention to detail in the performance of safety reviews. The PRC will maintain an oversight responsibility but will no longer be the sole safety review organization. The safety review process proposed in Specifica-tion 6.5.3 is consistent with the safety review process currently in use at several other licensed facilities.
- 11. Specification 6.8.2, (page 6-11), regarding temporary changes to procedures listed in Specification 6.8.1 is deleted in its entirety, being now addressed in the newly added Specification 6.5.3.
- 12. Cognizance of facility activities audits (Specification 6.5.4, formerly Specification 6.5.2.8) is made the responsibility of the Manager, Nuclear Quality rather than the MSRC as previously specified. The District considers this proposed change, placing cognizant responsibilities with the department performing the audits (Nuclear Quality) and oversight responsibilities with the MSRC (6.5.2.7m), a more efficient balance of management responsibilities with respect to audit coverage and performance.
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- 13. Specification 6.5.4.7 replaces existing Specification 6.5.2.9, and adds MSRC reporting requirements of Specification 6.5.2.7 reviews to responsible management. Sections 6.5.2.7e, f, g and h are excluded from such reporting by the MSRC since the immediacy of such events as significant Technical Specification violations, operating abnormalities, LERs and design or operating deficiencies would administratively result in earlier notification to the Deputy General Manager-Nuclear and the General Manager and staff by the affected department (s).
- 14. Specification 6.6.1 on LERs is edited slightly, and 6.6.1b is revised, deleting position titles and adding instead the MSRC which is made up of or reports to these previously listed positions.
- 15. Specification 6.8.2 is modified to eliminate redundancy with the newly introduced Specification 6.3.1, and for the same reason, Specification 6.8.3 is deleted.
- 16. Specification 6.9.3 is. changed to show the current NRC addresses to which monthly reports are submitted.
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ATTACl#ENT II SAFETY ANALYSIS Proposed Amendment No. 138, Revision 1, supersedes the original Proposed Amendment No. 138 submitted to the NRC on October 16, 1986. Both proposed amendments address the same topic, that of organization changes.
Subsequent to the original submittal, there have been organization changes made by the District, both on site and at the corporate offices, resulting
.in revised and new position titles and organization groups.
The proposed amendment will require changes to Chapter 12 of the USAR. These are administrative changes and do not change the intent of Chapter 12.
The proposed amendment updates and functionally enhances the following:
- 1. Table 6.2-1, Shift Crew Personnel and License Requirements expanded for compliance with 10 CFR 50.54(m)(2)(i).
- 2. The overall organization, position titles, responsibilities and PRC and MSRC composition based on the reorganization.
- 3. Actions and processes required for activities whichfd affect nuclear safety.
Specifically, Proposed Amendment 138, Revision 1, revises much of Section 6, Administrative Controls which describe or delineate the following:
- 1. the assignment of plant operating responsibilities;
- 2. the reporting chain up through the General Manager;
- 3. the organization of the plant staff;
- 4. the function and responsibilities of each major safety review committee;
- 5. the minimum shift crew complement, and
- 6. the qualification requirements for key members of the plant staff.
This safety analysis has reviewed the above items against:
10 CFR 50.36(c) iib (5), Administrative Controls; 10 CFR 50.4(b), Common Standards; 10 CFR 50.54(j) through (m), and
! NUREG 0737/1.A.1.1 and I.A.1.3.
On the basis of District reviews of the proposed changes against the above listed regulations, it is concluded that the proposed amendment is acceptable.
Acceptability of the proposed amendment delineating the revised operating organization is a significant input to the requirement that the District is technically qualified as required by 10 CFR 50.40(b); that adequate licensed l operators are available to meet the requirements of Section 50.54(j) through i (m); the adequacy of the on shift personnel to provide initial facility response l in the event of an emergency; organizational requirements for the Nuclear Plant Manager and Radiation Protection Superintendent; qualification requirements of the plant personnel in the USAR and safety review functions of the on and off site review conmittees. In addition, Rancho Seco complies with the requirements of TMI Action Plan items 1.A.1.1 and 1.A.1.3.
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ATTACHMENT III NO SIGNIFICANT HAZARDS CONSIDERATION Proposed Amendment No. 138, Revision 1, supersedes the originally submitted
, Proposed Amendment No. 138 sent to the NRC on October 16, 1986. Both proposed amendments address the same subject, that of organization changes. Revision 1 of the Proposed Amendment is submitted as a result of further changes to the organization made by the District subsequent to the original submittal.
Specifically, the proposed changes to the Rancho Seco Technical Specifications are as follows:
- 1. The title for Figure 6.2-1 is changed on the Table of Contents, List of Figures, page xii. See item 5 for details.
- 2. Throughout the Technical Specifications, position and group titles are changed or added as shown in Figures 6.2-1 and 6.2-2. The title changes are considered more descriptive of the management function, and the new positions reflective of the broader management oversight with respect to Rancho Seco.
- 3. The staff individual's qualifications identified in Specification 6.2.2d.
(page 6-1) is expanded to include radiation protection practices as well as procedures, and in Specification 6.2.2 9. (page 6-1a), the term " health-physicists" is changed to " radiation protection personnel". The first change adds to the individual's qualification requirement; the second is the result of a title change.
- 4. Table 6.2-1, Shift Crew Personnel and License Requirements, (page 6-2) is revised to be in accord with 10 CFR 50.54(m)(2)(i).
- 5. Figure 6.2-1, SMUD Nuclear Safety Organization Chart, (page 6-2a) is retitled to SMUD Corporate Support of Nuclear Safety to Rancho Seco. Accordingly, many of the corporate organizations which do not provide routine nuclear
! safety support of the plant are deleted. This simplification of Figure
! 6.2-1 is in agreement with the Standard Technical Specifications. The
- revised title of Figure 6.2-1 is also shown on the Table of Contents, List of Figures (page xii).
l 6. Figure 6.2-2, Plant Organization Chart (page 6-2b) is amended to show the revised and new positions and organization titles. Also, shift crew personnel and their license requirements are deleted, being redundant with Table 6.2-1. The footnote " Routine Reporting Requirements on i Personnel Changes" and the designations on the organization chart to l which the footnote applies is replaced with a general footnote stating:
l " Organization changes may be made per 10 CFR 50.59 without prior NRC l
approval."
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. 7. Specification 6.5.1, Plant Review Committee (PRC), (pages 6-3 through 6-5) is revised to reflect the currently proposed charter. Composition of the PRC is revised, and responsibilities are amended to specify review of procedures' safety evaluations rather than the total procedures (Specification 6.5.1.6a).
A similar change is made with respect to proposed changes and modifications (Specification 6.5.1.6d). In addition, since the PRC reviews facility operations for potential safety hazards through routine review of design changes, procedure changes or violations, operating deficiencies, etc.,
Specification 6.5.1.6e and 6.5.1.6f are considered redundant and are deleted.
- 8. Specification 6.5.2, Management Safety Review Committee, (pages 6-6 through 6-10a) is revised extensively to reflect the currently proposed charter.
Included in this is deletion of items a. through h., in Specification 6.5.2.1, Function, (page 6-6) and reference to listing of item a. through g. in Specification 6.5.2.7, Review, (pages 6-7 and 6-8). In Specification 6.5.2.3, it is made clear.that the limitation on alternates is for the purposes of establishing a quorutn. In addition, Specification 6.5.2.9, Records, is moved for editorial reasons. to 6.5.2.8, and the forwarding of audit reports to the Deputy General Manager-Noclear and to the General Manager is deleted. This is administratively made the responsibility of Nuclear Quality which also has the audit responsibilities. As revised, the MSRC reviews the QA program and does an over sist review of the QA Audit Program (see 6.5.2.7m and n).
- 9. Specification 6.5.2.8, Audits (page 6-9) is changed to Specification 6.5.4, which, in view of changes described in item 8 above, is a more appropriate location.
- 10. Specification 6.5.3, Technical Review and Controls, (pages 6-10 and 6-10a) is added in its entirety. This addition describes a new review and approval process for procedures, test and experiments, and plant modifications and describes overall responsibilities for these reviews which affect the safety of the plant. This change will broaden the safety review process and permit greater attention to detail in the performance of safety reviews. The PRC will maintain an oversight responsibility but will no longer be the sole
! safety review organization. The safety review process proposed in Specifica-
- l. tion 6.5.3 is consistent with the safety review process currently in use at several other licensed facilities.
f 11. Specification 6.8.2, (page 6-11), regarding temporary changes to procedures listed in Specification 6.8.1 is deleted in its entirety, being now addressed in the newly added Specification 6.5.3.
- 12. Cognizance of facility activities audits (Specification 6.5.4, formerly Specification 6.5.2.8) is made the responsibility of the Manager, Nuclear Quality rather than the MSRC as previously specified. The District considers this proposed change, placing cognizant responsibilities with
-the department performing the audits (Nuclear Quality) and oversight responsibilities with the MSRC (6.5.2.7m), a more efficient balance of management responsibilities with respect to audit coverage and performance.
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13._ Specification 6.5.4.7 reolaces existing Specification 6.5.2.9, and adds MSRC reporting requirements of Specification 6.5.2.7 reviews to responsible-management. Sections 6.5.2.7e, f, g and h are excluded from such reporting by the MSRC'since the immediacy of such events as Technical Specification violations, significant operating abnormalities, LERs and design or operating deficiencies would administratively result in earlier notification to the Deputy General Manager-Nuclear and the General Manager and staff by the affected department (s).
- 14. Specification 6.6.1 on LERs is edited slightly, and 6.6.1b-is revised, deleting position titles and adding instead the MSRC which is made up of or reports to these previously listed positions.
- 15. Specification 6.8.2 is modified to eliminate redundancy with the newly introduced Specification 6.3.1, and for the same reason, Specification 6.8.3 is deleted.
- 16. Specification 6.9.3 is changed to show the current NRC addresses to which monthly reports are submitted.
The District has reviewed the above changes and the reasons for them (Items 1 through 16) and concluded that all are purely administrative. With the exception of one change (Item 4, above), the proposed changes have no effect on plant design or operation. The exception, Item 4, which updates the shift crew personnel and license requirements on Table 6.2-1 affect plant operations, but in an enhancing manner.
The District has reviewed the proposed rr. organization changes against each of the criterion of 10 CFR 50.92 and concle.ded that plant operation with the proposed reorganization would not:
- a. involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed reorganization is purely administrative which, with the exception of the increased shift crew personnel and license requirements, an enhancement, is judged to have no effect on plant design or operation. Accordingly, it is concluded that the proposed changes do not have any involvement with previously evaluated accidents.
- b. create the possibility of a new or different kind of accident from any previously analyzed. For the reasons given in a.) above, it is concluded that the proposed changes do not introduce a new or different accident from any previously analyzed.
c ., involve a significant reduction in a margin of safety. As discussed above, the proposed changes have no effect on plant design and, with one exception, none also on plant operation. The one exception, which involves an increase in the quantity of shift crew oersonnel and their license requirements, is an enhancement to plant operations. None of the changes are seen as constituting a redaction in safety margins.
On the basis of the above, the District concludes that the proposed changes, purely administrative, do not constitute any significant hazards and in no way endanger the health and safety of the public.
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