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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
[Table view] |
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(gSMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT D P. O, Box 16830 Sacramento CA 95852-1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA y-NOV 17 1987 -
AGM/NPP 87-379 O. S. Nuclear Regulatory Commission
'. Attn: Frank J. Miraglia, Jr.
- Associate Director for Projects Philips Bldg.
7920 Norfolk Avenue Bethesda, MD 20014 DOCKET 50-312 RANCHO SECO NUCLEAR GENERATING STATION LICENSE NO. DPR-54 PROPOSED AMENDMENT 147, REVISION 2, SUPPLEMENT 2
Dear Mr. Miraglia:
Based ond' iscussions between the District and NRC, the District supplements
' the April 1,1987 submittal of Proposed Amendment 147 Revision 2 and the September 22, 1987 submittal of Proposed Amendment 147, Revision 2, Supplement 1.
Attachment 1 is the District's response to NRC questions and comments on Proposed Amendment 147. Attachment 2 is the revised Proposed Amendment 147 pages which incorporate the changes agreed to in the discussions between the District and NRC.
The Safety Analysis and no significant hazards consideration in the District's April 1,1987 submittal of Proposed Amendment 147 Revision 2 are not changed or affected by this supplement.
P f 0
i RANCHO SECO NUCLEAR GENERATING STATION O 14440 Twin Cities Road, Herald, CA 95638-9799;(209) 333-2935
.. AGM/NPP 87-379 Frank J. Miraglia, Jr. NOV 171987 Please cor, tact me if you have any questions. Members of your staff with questions: requiring additional information or clarification may contact Mr. Robert Roehler at (209) 333-2935,' extension 4918.
Sincerely, y ose F. Fir 11t Assistant General Manager, '
Nuclear Power Production.
Sworn' to and subscribed before me this ' / day of November 1987.
/4/1 ld W U N4)lary Putnic' omunL BEAL l
- M ". f IUDY E. LUNA r
-Attachments .
m;^g;gtg;gt;ga g cc: G. Kalman, NRC, Bethesda
^ ~ ~ ~ ~ ~ ~ 'j u, c- ny ., u, u mi A..D'Angelo, NRC, Rancho Seco 1
j Y L
K g'.(.E
[ ..,.,
p, ,
ATTACHMENT 1 L : DISTRICT RESPONSE TO NRC QUESTIONS AND COMMENTS ON PROPOSED AMENDMENT 147 L1 l1. "NRCls'taff withdrew question 1.
District Response: .N/A
- 2. ,3.7.2. A'1, 3.7.2.B.1_and 3.7.2.E.1 require demonstration of diesel t generator operability within 24. hours. Need to make it clear that this is onlyj required if. a diesel . generator has not been tested within 24 i hours to eliminate excessive. diesel generator starts. '
District: Response: . Statement added to only require testing if a diesel
-generator.has not been tested within the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 3. '3.7i2.B.2,' 3.7.2.E.1; and 3.7.2.E.2 have no LC0 if diesel generators go
,, .'into preplanned preventive maintenance or testing.
, i District Response:' Statement for preplanned preventive maintenance and testing moved to Action b. in 3.7.2.B.2 and 3.7.2.E.1 and deleted statement from 3.7.2.E.2. Non-0PERABLE
' diesel generator LC0 is now applicable during preplanned preventive maintenance and testing.
- 4. -Provide justification for running diesel generators with no load and how long.no load run is acceptable.
District Resp'onse: Although operation of the diesel at low loads is not recommended for long durations, the District maintains that occasional, short term operation of the Rancho Seco EMD diesel engines (GEA and GEB) is not detrimental to the availability of emergency power. SRP Section 8.3.1.f indicates that EMD diesel engines should be provided with a heavy duty turbocharger mechanical gear drive assembly to assure optimum-availability after running the engines at no-load or light load for extended periods. The District has installed this assembly on its EMD diesels. These improvements, per discussion with the manufacturer, are the only effective modifications known to improve no-load operation. Past experience has shown that the EMD diesel engines have run for at ;
least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with no-load or light load and then 1 accepted a load of 1500 kw and run for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at that load. Furthermore, the number of times that these diesels shall have to be started to satisfy Technical Specification Section 3.7.2 should be 1 minimal .
l 1
y ,
i s [. , ! 4. LDistrict. Response: (Cont.)-
,y The design of the District's TDI (GEA2 and GEB2)
, diesels is fundamentally different from the EMD
- o. diesels in several ways. Because of these
, differences, the TDI engines'are suitable for prolonged operation in no-load or light-load
' conditions. In fact, this' engine design' has
, undergone a special no-load endurance test for 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> followed by the successful. application of a 57%
step' load.' Based on the above considerations, the L.l '
proposed Technical. Specifications should not 4: - >
adversely affect the operation and availability of
- the. District's EMD and TDI emergency diesel g
generators.
L5. _ : Justify two offsite sources or redefine offsite power sources in 3.7.2.A.1.
District Response: This specification has been revised to conform with Standard Technical Specifications and Generic Letter 84-15, 3.7.1. A has been revised and 3.7.1.C, 3.7.2.F m"
and 3.7.2.G have been deleted based on this change.
The District has combined the specification for the offsite lines and startup transformers because the
, , existing Technical Specifications are not consistent for this equipment and do not reflect the existing e plant design. The existing specifications allow all offsite. lines to be inoperable with no time limit, but allowed' unlimited operation with only one startup transformer inoperable while requiring the plant to shutdown if two startup transformers were inoperable. Based on the inconsistency for offsite power in the existing-Technical Specification, the
=-
District has revised the specifications per the guidance in Standard Technical Specifications, Generic Letter 84-15, and Regulatory Guide 1.93. The District considers this change to be appropriate ;
because the redundant AC power system remains available. The offsite sources are historically very reliable and any degradation is generally easier to detect'and restore than the onsite AC power sources.
, 6. 3.7.2.B.2.b is not consistent with 3.7.2.E LCO for two diesel generator inoperability.
District Response: 3.7.2.B.2.b revised to refer to applicable two diesel
^ generator inoperable specification.
f
- = = _ -
- 7. 3.7.2.B.2.a,' 3.7.2 E.1.a and 3.7.2.E.2.a are not consistent with 3.7.2.C
- LCO for one offsite circuit inoperability.
' District Response: 3.7.2.B.2.a, 3.7.2.E.1.a and 3.7.2.E.2 have been revised to refer to applicable offsite circuit inoperable specification.
- 8. 3.7.2.B.3.C could have a diesel generator inoperable for 12 days.-
District Response: 3.7.2.B.3 deleted.
- 9. Justify 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> LC0 in 3.7.2.B.3.b.
District Response: 3.7.2.B.3 deleted. This diesel generator combination has been moved to 3.7.2.E.2.
- 10. 3.7.2.B.2.b does not require diesel generators to be tested if not tested before LCO is terminated.
District Response: Added note to require testing to be completed. ;
- 11. 3.7.2.B.2.b and 3.7.2.E.1.b requires testing once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. No additional tests required for 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO. Testing once each additional 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for 7 day LCO.
. District Response: 3.7.2.B.2.b and 3.7.2.E.1.b revised.
- 12. In 3.7.2.E.1 use of "/" is confusing. Also should use "or" instead of Conina.
District Response: "or" added and "/" replaced with "and".
- 13. -3.7.2.C last paragraph is not clear as to when 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LC0 applies.
District Response: Statement added to clarify LC0 starts with initial condition.
- 14. 3.7.2.E.2, needs justification for 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> LCO.
District Response: The time was determined based on the guidance of Reg l Guide l.93. Two hours is judged to be the time required to complete the initial problem confirmation and coordinate the onsite shutdown activities for an orderly plant shutdown. This allows the offsite power dispatchers to take expedited actions to lessen the severity of the loss of this source to the grid.
This time and the associated actions avoids the potential risks of an immediate shutdown yet severely limits the plant's exposure time to this degraded condition. This also provides sufficient time to identify problems, ensure they will not effect shutdown and to deal with them if they are a minor problem, thus avoiding unnecessary plant shutdown.
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l 15.- 3.7.2.E.2 does not require surveillance for offsite circuits or remaining diesel generators.
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. District Response: Requirement added to survey the offsite lines.
This action does not require the remaining diesels to be tested since.two trains are considered to be out of service and the exposure of the remaining diesels to the increased starts and some possible common mode failure will not confirm that one good onsite source is available. The LC0 is only 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, which is not sufficient time to test the remaining diesels. If {
one diesel is returned to OPERABLE then the ACTION of 3.7.2.B.2 would be required. ,
- 16. 3.7.2.E.2.b is:168 hour LC0 correct.
District Response: "168" deleted.
- 17. 3.7.2.E.2.b GEA/GEB is listed in this action item. Where are the other diesel ger.erator pairs listed?
District Response: GEA/GEB2, GEB/GEA2, and GEA2/GEB2 added to 3.7.2.E.2.b. ,
18.- 3.7.2.E.1 Action, does comma between GEA/GEA2, GEB/GEB2 mean "or"?
District Response: "or" added in place of comma.
19, 3.7.2.F, justify 205 hours0.00237 days <br />0.0569 hours <br />3.38955e-4 weeks <br />7.80025e-5 months <br />.
District Response: 3.7.2.F deleted, 205 hours0.00237 days <br />0.0569 hours <br />3.38955e-4 weeks <br />7.80025e-5 months <br /> deleted.
- 20. 3.7.2.F.a, no Action statement.
District Response: 3.7.2.F deleted.
- 21. 3.7.2.F this Tech Spec should be the same as loss of 2 lines.
District Response: . 3.7.2.F deleted. This specification has been revised to conform with Standard Technical Specifications and Generic Letter 84-15. 3.7.1. A has been revised and 3.7.1.C, 3.7.2.F and 3.7.2.G have been deleted based on this change.
- 22. 3.7.2.G, justify 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> LCO. l I
District Response: 3.7.2.G deleted. See Item 5. I l
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i 4l 23.- 3.7.2.G, why is this' different than loss of all lines?
District . Response: 3.7.2.G deleted. This specification has been revised
- " to conform with Standard Technical Specifications and
- Generic Letter 84-15. 3.7.1.A has been revised and 3.7.1.C, 3.7.2.F and 3.7.2.G have been deleted based on this change.
24, 3.7.2.H, existing Tech Specs say to verify other bus and equipment is operable,. justify. removing from Tech Specs.
District Response: Added statement from existing Technical l Specifications.
25.' .3.7.2.H.b, justify 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> LCO.
District Response: 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> LCO deleted.
- 26. 3.7.2.I, justify 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> LCO.
District Response: ~2 hour LC0 ' deleted.
- 27. 3.7.2.J.C, ~ justify 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> LCO.
District Response: 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> LCO deleted.
- 28. 3.7.2.K.1, justify 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO.
District Response: The LC0 is consistent with the LC0 for Batteries and Battery Chargers.
- 29. 3.7.2.K.2, justify 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> LCO.
District Response: This specification has been deleted.
- 30. Tables 3.7-2 and 4.1-1, terminology is not consistent with table 3.7-1.
District Response: Table 4.1-1 revised to correctly identify specific relays.
31, 4.6.3. A, Note 1 allows fast starts to exceed 10 seconds except for every 184 days.
District Response: Note amended to require 10 second time whenever a fast start is performed.
- 32. Why aren't air start receivers in Tech Specs?
District Response: Pressure is constantly monitored with a low pressure alarm in the Control Room. Therefore a Technical Specification surveillance is not required to ensure t1e air start receiver is operable. NRC withdrew this comment.
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- 33. 4.6.3.A.S. Why isn't loading time included in this specification?
District Response: A.90 second loading time has been added. The District understands that Generic Letter 84-15 only requires this timed loading to be performed every 184 days. All other monthly testing will allow slow loading as recommended by the manufacturer to minimize mechanical stress and wear.
34 Item C.3 page 4-35c, Note 1 does not apply, Note 3 does.
District Response: Note 1 changed to Note 3.
- 35. Item 2 page.4-35c, why is Note 4 referenced?
District Response: Note 4 deleted.
- 36. . Note 6 page 4-35c, Note 6 is not necessary.
District Response: Note 6 deleted.
- 37. Why isn't 4.8.1.1.2.d.2 of Generic Letter 84-15 included?
District Response: This specification has been added.
- 38. Why isn't 4.8.1.1.2.d.3 of Generic Letter 84-15 included?
District Response: -This specification has been added.
- 39. Why isn't 4.8.1.1.2.d.8 of Generic Letter 84-15 included?
District' Response: This specification has been added.
- 40. NRC withdrew this comment.
- 41. .Why isn't the last sentence 4.8.1.1.2.d 7 of Generic Letter 84-15 included? I l
District Response: This specification has been added.
- 42. Why isn't 4.8.1.1.2.d.6.C of Generic Letter 84-15 included? ,
District Response: This specification has been added.
- 43. 4.6.3.E.2, this should be done every refueling. Remaining Section 4.6.3.E should be deleted.
District Response: 4.6.3.E.2 moved to Section 4.6.3.C. Remainder of
, 4.6.3 E deleted.
- 44. Page 4-35d, 4.8.1.1.2, item D is missing a sentence.
District Response: Item D corrected.
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'45. AddL"are in service".to 3.7.1.A.
' District Response:".Added "are:in service" to 3.7.1.A.
46.' _Where is the requirement to drain and clean the diesel generator' fuel tanks?
District Response: -The District commits to' drain and clean each fuel oil storage--tank for the _ diesel generators at least once
. per.10 years effective the date of this letter.
i OTHER CHANGES TO PROPOSED AMENDMENT 147:
.l The bases for Specification 3.7_ states that "The 35,000 gallons of fuel stored in _each storage tank permit operation of the diesel generators A and B for seven days.". Based on recent testing, the 7 day fuel consump' ion for diesel regenerators A and B cou l d exceed 35,000 gallons. Therefore, the District has
,: increased the' fuel storage requirement to 37,000 gallons. This changes 3.7.1.E.2,and the bases for 3.7. The fuel storage tanks for diesel generators
. A and'B each have a capacity of 50,000 gallons.
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