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MONTHYEARML20210P5131986-09-22022 September 1986 Proposed Tech Specs,Replacing Phase Imbalance/Underpower Relay for Each Reactor Coolant Pump W/Undercurrent Relays Project stage: Other ML20210P4471986-09-22022 September 1986 Application for Proposed Amend 150 to License DPR-54, Changing Tech Specs to Replace Phase Imbalance/Underpower Relay for Each Reactor Coolant Pump W/Undercurrent Relays. B&W Engineering Info Record 51-1164378-01 Encl.Fee Paid Project stage: Request ML20149E5401988-01-0808 January 1988 Forwards Response to NRC Questions Re Reactor Coolant Pump Undercurrent Relay Project stage: Other 1986-09-22
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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 O 6201 s Street, P.O. Box 15830. Sacramento CA 95852-1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CAllFORNIA JEW 86-358 September. 27 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 N0. 150 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. 150 consists of replacing the phase imbalance /underpower relay for each Reactor Coolant Pump with undercurrent relays. Details of this proposed change are presented in Attachments I, II and III which are the Description of and Reasons for Proposed Changes, Safety Analysis and Bases for No Significant Hazards Determination, respectively.
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.
Enclosed is a check in the amount of $150.00 as required by 10 CFR 170.21,
" Schedule of Fees."
The District requests prompt review of this proposed amendment since it is planned, if approved, to implement this change before restart of the plant.
Should you require any further information with respect to this Proposed Amendment, please contact Mr. Ron W. Colombo at Rancho Seco Nuclear Generating Station Unit No. 1.
.E. WARD Subscribed and sworn to before me DEPUTY GENERAL MANAGER this & day of Stc6edf1986.
NUCLEAR Attachments O DI cc Re9i on V (2)
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OFFICIAL SEAL" DMW DARMG B6100607[f$ggr7p2 \ ' NOTARY PUBUC-CAUFORMIA PDR ADO 6000312 ny SACRAWJRo co. ex CoONTY P pon , _ -_ - m m p;r ;on.i2.i990
ATTACHMENT I DESCRIPTION OF AND REASONS FOR PROPOSED CHANGE Proposed Amendment No. 150 consists of replacing the phase balance and power sensing relays used in the Reactor Coolant Pump motor monitors with undercurrent relays. The existing relays, manufactured by Wilmar Electronics, have been in service since 1971. These relays have been the source of continuous problems since their initial installation, resulting in frequent reportable occurrences and requiring many repairs, both by the manufacturer and by District personnel.
Because of these recurring problems, the District contracted Babcock & Wilcox to perform an engineering study to consider replacing the troublesome Wilmar phase balance /underpower relays with undercurrent relays manufactured by Brown Boveri (Model ITE-37).
The study noted that the Wilmar relays are unique to Rancho Seco, and that all other B&W PWRs utilize current sensing methods, two of which are similar'to that proposed for Rancho Seco. A copy of the B&W study (Document 51-1164378-00) is enclosed with Attachment II, Safety Analysis.
The proposed changes with respect to the Rancho Seco Technical Specifications affect Tables 3.5.1-1 and 4.1-1 as described below:
- 1. Table 3.5.1-1, Instruments Operating Conditions, Page 3-30a: Under Auxiliary Feedwater, changed Item 2 from: " Phase Imbalance /Underpower RCP:" to: " Undercurrent RCP:."
- 2. Table 4.1-1, Instrument Surveillance Requirements, Page 4-7b: Changed Item 48a from: " Phase Imbalance /Underpower RCP" to: " Undercurrent RCP."
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ATTACHMENT II SAFETY ANALYSIS i
Proposed Amendment No. 150 consists of replacing the existing phase imbalance /
underpower relays used in the Reactor Coolant Pump motor monitors with under-current relays. The existing relays, in use since their initial installation in 1971, have experienced numerous component failures and calibration problems resulting in many reportable occurrences.
At the request of the District, Babcock & Wilcox performed an engineering study of the proposed replacement (see enclosed B&W document 51-1164378-00),and concluded that the use of undercurrent relays instead of phase imbalance /
underpower relays will adequately perform the required function of monitoring i loss of electrical power to the Reactor Coolant Pump motors. The' District 4
has reviewed the B&W study and reaches the same conclusion.
On this basis, the District considers that the proposed changes will have no adverse effect on plant safety or-to that of the public.
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BWNP-20440 3 (8/85)
, , b [* ENGINEERING INFORMATION RECORD Safety Related:
Document identifier 51-1164378-01 Yes O No 3 i Title Study of Proposed Reolacement of Wilmar Relavs in the Reactor Coolant Puns
.ionitors at Rancho Seco Prepared by b 6 a I, I b'
- k ' ) Date 7-/7-Eb Reviewed by Aadv b- [5 * ~ Date 7-2/-%
) '
Remarks:
This report reviews the acceptability of a proposed design change to the Reactor Coolant Pump Monitors (RCPM) at Rancho Seco wherein Wilmar phase balance relays will be removed and the Wilmar underpower relays are replaced by undercurrent relays. An examination is made of RCPM designs at the other operating B&W plants, RCPM functional requirements, functional comparisons between the existing versus the proposed design, affected licensing documentation, and recommended design criteria. The s-report concludes that the proposed design change will allow the j RCPM to adequately perform its required function.
Revision 01 provides current relay setpoint recommendations and Technical Specification revision recommendations.
Page 1 of 7
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51-1164378-01 Page 2 of 7 i STUDY OF PROPOSED REPIACEMENT OF WILMAR REIAYS ,
IN THE REACTOR COOLANT PUMP MONITORS !
B&W TASK 752 l l
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1.0 INTRODUCTION
l The Reactor Coolant Pump Monitors (RCPM) at Rancho Seco presently utilize Wilmar phase balance and power sensing relays to provide RCP status signals to the RPS and ICS.
Since installation, the Wilmar relays have experienced numerous component failures and calibration problems. To alleviate these problems, SMUD is considering eliminating l the phase balance relays and replacing the power sensing relays with undercurrent relays. Because B&W provided the functional requirements for the RCPMs, SMUD has requested that B&W review the acceptability of this proposed change. l l
2.0 DISCUSSION In preparing this report, the following items were examined:
(1) What' types of Reactor Coolant Pump Monitors are in use at the.other cperating B&W plants.
(2) What are the functional requirements for the RCPMs.
(3) How do the proposed undercurrent relays compara " -
functionally with the existing phase balance and power sensing relays for the purposes of meeting the functional requirements determined in (2) above.
(4) What effect, if any, does the proposed change have upon previous licensing documentation.
(5) Recommended design criteria applicable to the proposed design change.
The following is detailed discussion of each of these items.
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51-1164378-01 Page 3 of 7 2.1 Survey of Reactor Coolant Pump Monitors at Other Operatina B&W Plants Schematic diagrams of RCPM circuits for Oconee, TMI-1, Arkansas Nuclear One, Crystal River, and Davis Besse were examined to determine the methods used to monitor the RCP status. Two plants utilized current transducers in one phase of each RCP to provide a signal to a comparator which provided both undercurrent and, in one case, overcurrent trips to the RPS. The remaining plants utilized watt transducers to sense' motor power to determine RCP status.
Nonc of the plants su:icycd utilized phase balance relays in the RCPM signal to the RPS.
From the above survey, it can be concluded that the scheme proposed by SMUD to utilize undercurrent relays to provide RCP status information to the RPS would not be unique with respect to B&W plants, but rather that two plants already utilize schemes to provide RCP status based only upon motor current. ..
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2.2 Reactor Coolant Pumo Monitor Functional Recuirements The functional requirements for the SMUD RCP monitors are given in the SMUD Technical Specifications Section 2.3.1.B:
"The pump monitors prevent the minimum core DNBR from decreasing below the CHR correlation limit by tripping the reactor due to (a) the loss of two reactor pumps in one reactor coolant loop and (b) loss of one or two reactor coolant pumps during two pump operation. The pump moni* ors also restrict power level to 55 percent for one reactor coolant pump operation in each loop". Per SMUD USAR Section 14.1.2.6.1, a pump failure can occur from loss of electrical power, or a mechanical failure which is considered to be a <
locked rotor and is used as a bounding accident which covers also a separation of the pump impeller from the motor shz.ft.
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l 51-1164378-01 Page 4 of 7 The locked rotor analysis referred to in USAR Section 14.1.2.6.3 assumes that the RPS trips on overpower based on ;
flow and imbalance. Therefore, because the trip due to loss of an RCP due to mechanical failures does not require pump status input, the RCPM is only required to monitor a loss of electrical power to the RCPs.
2.3 Functional Comparison Between Phase Balance and Undernower Relav Combination Versus Undercurrent Relav In order to determine the capability of undercurrent relays to perform tha role of the phase balance and underpower .
relays which they would replace in the RCPM, a comparison is made below of the function of each device.
A ' current sensing relay differs in function from a power sensing relay in that while both devices utiliza current magnitude as inputs, the power sensing relay also utilizes the additional inputs of voltage magnitude and phase angle between the current and the voltage, which is a measure of power factor.
Q From the three values of voltage, current and
[f power factor the power sensing relay derives a value for active power (watts). The undercurrent relay senses only the current magnitude, which for the full range of motor operation from stalled to no load speed, is not proportional to the motor power. However, for the normal RCP operating range from cold to hot reactor coolant conditions the power factor remains practically constant. Therefore, for this range, the current and power are relatively prrportional, provided that the voltage remains reasonably stable. Due to the proportionality between the current and power throughout the range of normal RCP motor operation, the undercurrent relay and the underpower relay behave in a similar manner in this range and either device can be set to trip outside of this range. Therefore, the undercurrent relay is an
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51-1164378-01 Page 5 of 7 adequate replacement for the underpower relay for the function which the underpower relay performs in the RCPM, which is to sense loss of power to the RCP motor.
The proposed design change would eliminate the phase balance relays from the RCPM. This change is acceptable on the
- basis that the maximum possible phase imbalance, which occurs when one phase is open circuited, will result in a reduction in motor speed of only 8 RPM for cold loop conditions and 5 RPM for hot loop conditions (See Attachment I). This represents a maximum change in speed of 0.68% ,
which will have negligible affect on the DNBR referred to in Section 2.2.
1 2.4 Licensine Documentation Affected by the ProDosed Desian Chance Both the SMUD USAR. and Technical Specifications were reviewed for impact by the proposed design change. USAR Section 7.1 addresses the RCPMs as being " power monitors". '
- L If the design change is incorporated, the RCPMs will no ,_j longer directly monitor pump power, therefore, the - USAR should be revised accordingly. Also, Table 7.1-2 in the USAR should be revised to delete the phase unbalance sensors. Similar changes are also required to the Technical Specifications Table 3.5.1-1, Auxiliary Feedwater Item 2, and Table 4.1-1, Item 48A. j 2.5 Recommended Desian Criteria 2.5.1 The design change should retain the single failure criterion of IEEE 279 to the extent that no single l
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51-1164378-01 Page 6 of 7 failure of an RCPM component will prevent the Reactor Protection System from fulfilling its protective functions when action is required. It is recommended that four relays be provided in the RCPM for each motor, one relay for each RPS channel.
2.5.2 Means should be provided for physical and electrical channel separation and isolation of the RPS circuit from non-IE circuits.
2.5.3 All equipment in the Class 1 portion of the RCPM and the RCPM cabinet should be seismically qualified.
2.5.4 Undercurrent relay trip setpoints should be established which will allow reliable sensing of loss of RCP motor electrical power without causing spurious actuations during normal RCP operation. The previous setpoint of 300 amperes recommended by B&W in a 8/20/71 letter from R.J. Cuffin to R.A. Horry is suitable for this purpose. .
_.1 2.5.5 The response time of the undercurrent relays should be
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examined to ensure that the maximum response time requirements imposed on the original equipment is not exceeded, and that the response time is not so short as to cause spurious actuations.
3.0 CONCLUSION
The design change proposed by SMUD to replace the Wilmar l phase balance and underpower relays in the RCPM with undercurrent relays will allow the RCPM to adequately perform its required function of monitoring loss of electrical power to the RCP motors.
[ ATTACHMENT 1 Sabccc'< & Vi!!co;; '
Mr. Roy A. Norry ECP Motor Single Fnasing Protection *
~ June 25, 1971 vill result in line currents on the re=aining two phases of 'approximately
-274-and.454 of rated current for the cold and hot loop conditions after slowdown. Since these currents are in the ran;;e of protection of the over- '
current relay, one could expect it to trip should the phase balance relay -
fail entirely. However, with the phase balance relay ' set for.25g ~ imbalance.,
4 e.wculd. .
e:epect.a.. trip-te'ocee:vithin the..5;second
- - . . - - . . . . a setting.
Since the unit is at speed prior to single phasing and the single phase -
line voltr.ge vill not dip below 92p d of rated voltage, then the unit vill not stall. The rate of change of speed from three phase to sin 6 1e operation is governed by the total rotating inertia of the system (phase including loop water), and the difference between the pu=p load curve and motor torque curves. -
The change in speed for 10700 HP steady state conditions from thr'ee p' nase to single phase operation 1s from 1176 to 1168 RE4.
For a hot loop HP of 8050, this change is from 1182 RPM to 1177 RR4.
Eas.ed--~bfebnelaying %cribe.J.,a* Mind- m nbject.ios to single. phase . opera ,
stion,Sor. a period. ef..five sec =ds before_.the. motor -is--removed from.the line.
Should an tte=pt be 'made to restart the.. unit with single phase power,-
adequate protection should' aga.in'be' afforded by the phase balance relay
_vs protection curve .0501-0199F.
Attached for your infor=ation is the 3W 1etter to A-C dated May 19, 1971.
Please advise if you have any further questions on this subject. .
. Very truly.yours, .
R. T. Schemer Project Manager ,
. J. Cuffia Project Engineer -
cc:
J. J.' Mattimoe - *
. 1 D. W. Harris , l 1
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ATTACHMENT III BASES FOR N0 SIGNIFICANT HAZARDS DETERMINATION Proposed Amendment No. 150 consists of replacing the phase balance and power sensir,9 relays used in the Reactor Coolant Pump motor monitors with undercurrent relays. The existing relays, manufactured by Wilmar Electronics, have been in service since 1971. These relays have been the source of continuous problems since tLn r initial installation, resulting in frequent reportable occurrences, and requiring many repairs both by the manufacturer and by District personnel.
Because of these recurring problems, the District contacted Babcock & Wilcox to perform an engineering study to consider replacing the troublesome Wilmar phase balance /underpower relays with undercurrent relays manufactured by Brown Boveri (Model ITE-37).
The study noted that the Wilmar relays are unique to Rancho Seco, and that all other B&W PWRs utilize current sensing methods, two of which are similar to that proposed for Rancho Seco.
The B&W concluded that the use of undercurrent relays instead of phase imbalance /
underpower relays will adequately perform the required function of monitoring loss of electrical power to the Reactor Coolant Pump (RCP) motors. The District has reviewed the B&W study and reaches the same conclusion.
The District has also reviewed the proposed change against each of the criterion of 10 CFR 50.92 and concluded that plant operation would not:
- 1. involve a significant increase in the probability or consequences of an accident previously evaluated. As indicated above, the engineering studies have concluded that the use of undercurrent relays will adequately acrform the same function of monitoring loss of power to the RCP motors as phasa imbalance /
underpower relays. Accordingly, the probability or consequences of an accident previously evaluated is not seen as being increased by the proposed change.
- 2. create the possibility of a new or different kind of accident from any previously analyzed. The use of undercurrent relays has been determined to provide an equivalent function to those of phase imbalance /underpower relays.
Therefore, any malfunction of the former, although expected to be significantly less frequent than the latter, is considered to have the same effect on plant operation. Thus, no new or different kind of accident from any previously analyzed is foreseen.
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- 3. involve a significant reduction in a margin of safety. Since engineering studies have determined that the proposed undercurrent relays will provide an equivalent function to the existing phase imbalance /underpower relays, it is concluded !
that no margins of safety will be reduced.
Based on the above determinations, the District has concluded that there is reasonable assurance that the health and safety of the public will not be endangered by plant operation in the proposed manner. I l