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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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$SMUD 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 CALIFORNIA JEW 86-249 September 24,1986 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 NO. DPR-54 PROPOSED AMENDMENT NO. 134 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. 134 revises various parts of Specification 4.17 (Steam Generators) to add sleeving as a method of mitigating 0TSG tube leaks.
Basically, the wording " plug defective tubes" is changed throughout Specification 4.17 and its bases to " plug or repair defective tubes." In addition, Specification 4.17.2.b.1 revises the first sample inspection to exclude tubes with previous detectable wall penetrations if they have been plugged or sleeve repaired in the affected area.
These changes are proposed to permit the use of steam generator tube sleeving as an alternate to tube plugging. The process, developed and qualified by Babcock & Wilcox, can be performed remotely, thus minimizing exposure to maintenance personnel. Additionally, steam generation through sleeve repaired tubes continue with only a slight thermodynamic reduction whereas in plugged tubes, steam generation is completely terminated.
In the future, should the District choose to repair the OTSG tubes in a manner different from that presented in this proposed amendment, the alternate method, including a different sleeving method, will not proceed without prior NRC approval of the method.
The proposed changes are discussed in detail in Attachments I, II and III, which are the Safety Analysis, "No Significant Hazards" Evaluation, and Description of Proposed Changes, 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 $150.00 as required by 10 CFR 170.21,
" Schedule of Fees."
861003o130 DR 860w4 60 ADOCK 05000312 t
m- ;
y po$ J
l' Should you require any further information with respect to this Proposed Amendment, please contact Mr. Ron W. Colombo at Rancho Seco Nuclear Gen-eratin Station Unit . 1.
-. E. WARD DEPUTY GENERAL MANAGER, NUCLEAR Attachments cc: RegionV(2)
INP0 MIPC (2)
Subscribed and sworn to before me this 7 4+h day of_ h 1986
!an Q Notary Public r-~ g v
'^^[^ OFFICI AL,'Ss^t, DAWN DARLlilG t:OTADYI4J3UC CAUFORNIA
[/ CACM'E.NTO COUNTY My Ce<rm En:res kn. 12,1990
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ATTACHMENT I SAFETY ANALYSIS Proposed Amendment No. 134 revises various parts of Specification 4.17 (Steam Generators) to add tube sleeving as a method of mitigating OTSG tube leaks.
The method, developed by Babcock & Wilcox, is presented in detail in a proprietary B&W report, BAW-1823P, Once-Through Steam Generator Mechanical Sleeve Qualification, which is being mailed under separate cover to Mr.
Sidney Miner, NRC Project Manager. A non-proprietary version, BAW-1823, t is enclosed with this proposed amendment.
The report addresses pertinent aspects of the sleeving process which affect nuclear safety; such as strength and leakage of the mechanical sleeves, corrosion resistance, effect on plant performance, vibration, method of installation, examination for defects ar.d verifications of p~oper installation, radiological exposure and analysis for transient and accident conditions.
The report concludes that the mechanical tube sleeves are qualified for use in degraded 0TSG tubes and are strong enough and sufficiently leak-free to be used as a permanent remedy to keep degraded tubes in service. It also recommends that up to 10,000 of these mechanical sleeves (5,000 per steam generator) can be installed to correct or prevent tube degradation.
A comparison of the report BAW-1823P with the System Design evaluation for the steam generators in Section 4.3.4 of the USAR indicates the design basis for the sleeves is enveloped by the USAR. The report includes an evaluation of the reduction in flow and superheat that would be expected for the worst case in each 0TSG and concludes that the effect on plant operations is considered minimal. The B&W report provides sufficient details to conclude that the sleeve repair of up to 10,000 0TSG tubes does not alter the design basis and therefore does not involve an Unreviewed Safety Question.
Prior to beginning work, all personnel involved in steam generator tube sleeving operations will have received GET plant-specific training on site in radiological protection, and special training in a full-scale mockup of the upper head of the steam generator. This on site training will incorporate all applicable provisions of Reg. Guides 8.13, 8.19 and 8.27.
Actual dose rates observed at Ranchn Seco in February and March, 1986, were compared to those assumed in BAW-1823P. It was found that the actual rates are generally lower than those assumed in the B&W report by factors of 2 to
- 6. The observed dose rates at Rancho Seco are as follows:
Location Dose Rate 1" from tubesheet 5 R/h 18" from tubesheet 3 R/hr centerline of manway 0.8 R/hr 3 ft. outside manway 200 mr/hr low background area 40 mr/hr cutside staging area 10 mr/hr
Applying the above dose rates to elapsed time measured by B&W in their proving run results in the estimated exposures shown on the attachment to this safety analysis. The " Conservative" column shown includes allowances for expected contingencies in the sleeving operation.
Note that setup and removal of the remote manipulator would add an additional estimated 1.0 manrem to the total exposure for sleeving in each 0TSG. An allowance of about 30 percent should also be included for various support activities such as health physics, QC, tool engineers, video engineers and profilometry.
Arkansas Power & Light Company (AP&L) sleeved 5 defective ( > 40% through wall degradation) and 5 good steam generator tubes at their AN0 1 unit as a demonstration case for B&W's tube sleeving program. The NRC approved AN0's Technical Specification amendment which allowed the sleeving of the 10 steam generator tubes. The 10 sleeved tubes at ANO have performed in an operating reactor for one full cycle without any signs of problems.
On the basis of the above analysis and on review of the above referenced B&W proprietary report on qualification of the proposed tube sleeving method, the District has concluded that tube sleeving as an alternate to plugging of defective tubing in the OTSGs would not affect the safety of the plant or the health and safety of the public.
/
o - 1 A'17ACHMENT ,
~
r No Contingency Conservative Rancho Seco Elapsed Estimated Elapsed Estimated Time, Dose, Time, Dose, Activity Area Dose Rem /hr Hr. Manrem Hr. Manrem (Batch of 20 Sleeves
.80 .008 .006 .013 .010 Flare tubes .058 .500 .100
.20 .292
.04 450 .018 .500 .020
.750 .082 1.013 .130
.80 .186 .149- .250 *200 Insert Sleeves .833 .167
.20 .734 .147
.04 2.850 .144 3.000 .120 3.770 .410 4.083 .487
.80 .017 .014 .025 .020 Upper Roll .250 .050
.20 .194 .039 ,
.04 1.222 .049 1.500 .060 1.433 .102 1.775 .130
.80 .025 .020 .033 .026 Lower Roll 1.250 .250
.20 1.092 .218
.04 5.783 .231 7.000 .280 6.900 - .469 8.283 .556
.80 .017 .014 .025 .020 EC Examination .333 .067
.20 .233 .047 (sleeve baseline) .022 1.000 .040
.04 .550
.800 .083 1.358 .127,
.01 24.000 .480 36.000 .720 Containment Support (2 Men)
Total 20 sleeves 1.626 2.150 f
per sleeve avg. 0.081 .108 4
e 8 i .
._ , _ - . _ _ -. _ , - , ,- , - - - . y , _ . - _ --
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ATACl#ENT II "N0 SIGNIFICANT HAZARDS" EVALUATION Proposed Amendment No. 134 revises various parts of Specification 4.17 (Steam Generators) to add internal sleeving as a method of mitigating future tube leaks in the once-through steam generators (OTSGs) at Rancho Seco. The method has been developed and qualified by Babcock & Wilcox (B&W) through extensive analyses, laboratory tests and in a prototype test at an operational nuclear power operating facility (M.01).
Sleeving has-been shown to be a safe and effective method of repair for defec-tive steam generator tubes. Several thousand tubes have been successfully sleeved in steam generators throughout the world. A B&W report, BAW-1823, Revision 1, "Once-Through Steam Generator Mechancial Sleeve Qualification",
provides a description of the analysis and testing performed to demonstrate the acceptability of the mechanical sleeve design. A copy of this report is enclosed with this proposed amendment. Mechanical strength, vibration, leak resistance, corrosion resistance, installation process control, inservice inspection techniques, and plant performances are described and shown to meet all expected NRC acceptance criteria.
The District has reviewed the proposed method of sleeving defective OTSG tubing and concluded that the use of this alternate to tube plugging would not:
- 1. involve a significant increase in the probability or consequences of an accident previous evaluated.
The USAR conservatively evaluated a double-ended rupture of a steam generator tube. A severed tube with a mechanical sleeve installed in it has been shown by tests to have mechanical strength at least
- as great as that of a new tube. Thus, a sleeved tube is no more likely to rupture than any other tube in the generator.
A sleeved tube is functionally equivalent to an unsleeved tube except for less effective heat transfer due to the air gap and slight pressure drop due to the primary flow constriction. Analysis has shown that if 5000 sleeves were installed in each generator the steam scperheat temp-erature would be reduced by 7.7 F at full power and primary flow would be reduced by less than-1%. These differences have been compared to the existing plant safety analysis calculations and it was found that up to 5000 tubes per steam generator may be sleeved without invalidating the existing analysis basis of the units.
- 2. create the possibility of a new or different kind of accident from any accident previously evaluated.
3 The only equipment affected by sleeving is the steam generator. The most severe malfunction of a steam generator is a tube rupture, and the consequences of a ruptured sleeve are no worse than the consequences of a ruptured tube. Sleeving does not increase the probability of steam generator failure because the sleeved tube has been shown to be mech-anically stronger than an unsleeved tube. Thus a steam generator ,
with sleeved tubes would perform in the same manner as one without sleeved tubes, and there is no risk of a new or different accident.
ATTAC K NT II "N0 SIGNIFICANT HAZARDS" EVALUATION con't...
- 3. involve a significant. margin of safety.
The integrity of steam generator tubes is enhanced by the installa-tion of sleeves due to the increased vibration stability margin and the ability to bridge over imperfections and degradations. Thus the margin of safety is not reduced.
On the basis of the above, the District concludes that the proposed use of internal sleeving for mitigating future OTSG tube leaks does not constitute a significant hazard, and in no way endangers the health and safety of the public.
ATTAC MENT III DESCRIPTION OF PROPOSED CHANGES
- 1. Specification 4.17.2b.1., page 4-52: Added: "or sleeve repaired" after the word " plugged."
- 2. Specification 4.17.4a.3., page 4-54: Added: "in the pressure coundary" after the word " tube."
- 3. Specification 4.17.4a.4., page 4-54: Deleted: "a tube containing" after the word "means" in the first sentence, and replaced the second sentence in its entirety with the sentence: "A tube or sleeve contain-ing a defect in its pressure boundary is defective, and shall be either plugged or repaired by sleeving."
- 4. Specification 4.17.5a., page 4-54: Changed " tubes plugged" to " tubes plugged or repaired."
- 5. Specification 4.17.7b., page 4-55: Changed "will be plugged" to "will be plugged or repaired."
- 6. Specification 4.17 Bases, page 4-55a: Changed " Plugging will be re-quired" in the third sentence of the top paragraph to " Repair or plug-ging will be required."
- 7. Specification 4.17 Bases, page 4-55a: Inserted the following as the second paragraph:
" Degraded steam generator tubes can be repaired by the installation of sleeves which span the area of degradation and serve as a replace-ment pressure boundary for the degraded portion of the tube, thus per-mitting the tube to remain in service."
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