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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20211J9861999-09-0101 September 1999 Application for Amends to Licenses DPR-53 & DPR-69,changing Definition of Azimuthal Power Tilt in TS 1.1,correcting Peak Linear Heat Rate Safety Limit in TS 2.1.1.2 & Correcting Dc Voltage Range Listed in Surveillance Requirement 3.3.6.2 ML20211G7591999-08-27027 August 1999 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 3.7.13 to Allow Placement of One or More Fuel Assemblies on SFP Rack Spacers to Support Fuel Reconstruction Activities During Continuing Fuel Assembly Movement ML20196E2101998-11-30030 November 1998 Application for Amends to Licenses DPR-53 & DPR-69,allowing Repair of Defective SG Tubes with leak-limiting Alloy 800 sleeves.Non-proprietary Rev 03-P to CEN-633-NP & Proprietary Rev 03-P to CEN-633-P,encl.Proprietary Info Withheld ML20195K3711998-11-20020 November 1998 Application for Amends to Licenses DPR-53 & DPR-69,removing TS Originally Developed from Reg Guide 1.35 & Implementing Requirements of 1992 Edition Through 1992 Addenda of ASME B&PV Code Section Xi,Subsections IWE & Iwl,Per 10CFR50.55a ML20196A6001998-11-20020 November 1998 Application for Amends to Licenses DPR-53 & DPR-69, Requesting Indirect Transfer of Control,Pursuant to 10CFR72.50,of Matls License SNM-2505 for Plant ISFSI ML20195J7131998-11-19019 November 1998 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 3.7.6, SWS, by Adding One SWS Heat Exchanger Inoperable as New Condition for LCO 3.7.6 ML20154N1861998-10-16016 October 1998 Application for Amends to Licenses DPR-53 & DPR-69 to Incorporate Revised TS 3.3.1 & 3.3.2 to Clarify Inconsistency Between TS Wording & Design Bases as Described in TS Bases & UFSAR ML20236S1341998-07-20020 July 1998 Application for Amend to License DPR-59,implementing Mod That Involves Replacing SW Heat Exchangers W/New Plate & Frame Heat Exchangers Having Increased Thermal Performance Capability ML20236S5591998-07-20020 July 1998 Application for Amend to Licenses DPR-53 & DPR-69,providing Alternate Cooling Water Supply to Maintain EDGs Operability During 1999 Refueling Outage ML20198K9591998-01-12012 January 1998 Rev 11 to 961204 Application for Amends to Licenses DPR-53 & DPR-69,converting to Improved Sts,Per NUREG-1432 ML20217K6591997-10-22022 October 1997 Application for Amends to Licenses DPR-53 & DPR-69, Incorporating Both Steady State & Transient Degraded Voltage Setpoints Into Tss,As Opposed to Current Single Degraded Voltage Setpoint ML20211J2691997-10-0202 October 1997 Application for Amend to License DPR-53,revising TS to Reflect New Electrical Capacity for 1B Edg.Significant Hazards Considerations Associated W/Change Have Been Evaluated ML20141F9181997-05-16016 May 1997 Application for Amend to License DPR-53,implementing Mod Involves Replacing Service Water Heat Exchangers W/New Plate & Frame Heat Exchangers Having Increased Thermal Performance Capability ML20136A9751997-03-0606 March 1997 Application for Amend to License DPR-69,allowing Mod to Unit 2 SW Sys Which Constitutes Unreviewed Safety Question in 10CFR50.59 ML20134D2871997-01-31031 January 1997 Application for Amends to Licenses DPR-53 & DPR-69,changing to Support Larger Number of Plugged SG Tubes for Future Operating Cycles ML20149M0801996-12-0404 December 1996 Application for Amends to Licenses DPR-53 & DPR-69,revising TSs to Be Generally Consistent w/NUREG-1432,Rev 1,thus Replacing 2 Current Sets of TSs W/Single Set Applicable to Both Units ML20135A5171996-11-26026 November 1996 Application for Amends to Licenses DPR-53 & DPR-69,adopting Option B of 10CFR50,App J,To Require Types B & C Containment Leakage Rate Testing to Be Performed on performance-based Testing Schedule ML20128H5971996-10-0303 October 1996 Application for Amend to License DPR-53,changing Provisions for Receiving,Possessing & Using Byproduct,Source & Special Nuclear Matl at Plant ML20117L7801996-09-10010 September 1996 Application for Amends to Licenses DPR-53 & DPR-69 Requesting Extension of ESFAS Automatic Actuation Logic Surveillance from Monthly to Quarterly ML20116F8231996-08-0101 August 1996 Application for Amends to Licenses DPR-53 & DPR-69,allowing Use of Blind Flanges During Modes 1-4 in Plant Containment Purge Sys ML20116E3571996-07-26026 July 1996 Application for Amends to Licenses DPR-53 & DPR-69,to Repair Defective SG Tubes by Electrosleeving ML20117J1911996-05-28028 May 1996 Application for Amend to License DPR-53 & DPR-69,requesting Exigent Amends to Allow Installation of Proposed Modification of Unit 1 & 2 Service Water (SRW) Systems ML20101K5911996-03-28028 March 1996 Application for Amends to Licenses DPR-53 & DPR-69, Requesting to Reduce Moderator Temp Coefficient Limit Shown on TS Figure 3.1.1-1 ML20101D8211996-03-15015 March 1996 Suppl to LAR Re Sleeving Option for SG Tube Repair.Proposes Rev to TS Wording in Attachments (A-3) & (A-4) by Removing Generic Ref to Technical Repts & Replace W/Ref to Specfic Approved Repts ML20096D4291996-01-16016 January 1996 Application for Amends to Licenses DPR-53 & DPR-69,adopting Option B of 10CFR50,App J to Require Type a Containment Lrt to Be Performed on performance-based Testing Schedule ML20095K2701995-12-21021 December 1995 Application for Amends to Licenses DPR-53 & DPR-59, Requesting Temporary Exemption & TS Change to Allow Placement of Four Lead Test Fuel Assemblies in Unit 1 Reactor Core During Cycles 13,14 & 15 ML20095C7421995-12-0707 December 1995 Application for Amends to Licenses DPR-53 & DPR-69 to Add Analysis Technique to List of Approved Core Operating Limits Analytical Methods in TS for Plant ML20094S1481995-11-30030 November 1995 Application for Amends to Licenses DPR-53 & DPR-59,allowing Installation of Tube Sleeves as Alternative to Plugging to Repair Defective SG Tubes ML20094D6131995-11-0101 November 1995 Application for Amends to Licenses DPR-53 & DPR-69,upgrading ESF Electrical Sys at Plant to Provide Addl Protection from Loss of Electrical Power ML20093M4141995-10-20020 October 1995 Application for Amend to License DPR-53,extending 18-month Surveillances to 960331 ML20098C0661995-10-0202 October 1995 Application for Amend to License DPR-69,requesting Extension of Unit 2 TS Action Statements 3.7.6.1.a & B from 7 Days to 30 Days for Loss of Emergency Power to Support 1996 Refueling Outage ML20086N2341995-07-13013 July 1995 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 5.2.1 to Allow Use of Lead Fuel Assemblies & Requests Temporary Exemption from Requirements of 10CFR50.46, 10CFR50.44 & 10CFR50,App K for Ccnpp Unit 1 ML20085D4901995-06-0909 June 1995 Application for Amends to Licenses DPR-53 & DPR-69, Implementing Changes to Radiological Effluent TS Per GL 89-01 ML20084R0111995-06-0606 June 1995 Application for Amends to Licenses DPR-53 & DPR-69.Amends Would Revise TSs to Extend Certain 18-month Frequency Surveillances to Refueling Interval ML20084P9681995-06-0202 June 1995 Application for Amends to Licenses DPR-53 & DPR-69,proposing TS Re Pressurizer Safety Valves Lift Tolerance ML20087H9141995-04-28028 April 1995 Application for Emergency Amend to License DPR-53.Amend Would Revise CREVS TSs to Provide an Extension of Allowed Outage Time ML20081D0411995-03-15015 March 1995 Application for Amends to Licenses DPR-53 & DPR-69 to Reformat Current Administrative Controls Section & Relocate Several Requirements to Other Documents & Programs ML20079A5771995-02-24024 February 1995 Application for Amend to License DPR-69,allowing Extension of Interval Between First & Second Type a Test During Second Service Period & Extension of Second Service Period to 12 Years to Coincide w/1999 Plant Inservice Insp ML20078G8161995-01-31031 January 1995 Application for Amends to Licenses DPR-53 & DPR-69,revising TS to Increase Min Amount of Trisodium Phosphate Dodecahydrate Verified in TS Surveillance ML20073G2401994-09-23023 September 1994 Application for Amends to Licenses DPR-53 & DPR-69,allowing one-time Extension from 7 to 14 Days of AOT for Dedicated Class 1E Emergency Power Source During 1995 Refueling Outage ML20071P4421994-08-0404 August 1994 Application for Amend to License DPR-53 & DPR-69,eliminating TS 3/4.3.3.3 for Seismic Monitoring Instrumentation, Relocating Requirements for Operation & Testing of Seismic Monitoring Instrumentation to Plant Updated FSAR ML20149E8321994-08-0202 August 1994 Application for Amends to Licenses DPR-53 & DPR-69,revising Surveillances Associated W/Edgs to Add High Crankcase Pressure to EDG Trips Which Are Verified to Be Automatically Bypassed on Safety Injection Actuation Signal ML20071N2961994-08-0202 August 1994 Application for Amends to Licenses DPR-53 & DPR-69, Incorporating TS 3.9.1, Refueling Operations,Boron Concentration ML20069H6471994-06-0808 June 1994 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 4.6.2.2.d,extending Surveillance Interval from 18 to 24 Months ML20069H6191994-06-0808 June 1994 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 4.8.1.1.1.b,extending Alternate Offsite Power Circuit Surveillance Frequency from 18 to 24 Months ML20069H6311994-06-0808 June 1994 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 4.7.1.2.c,extending Interval for Three Auxiliary Feedwater Surveillance Requirements from 18 to 24 Months ML20069C3921994-05-27027 May 1994 Application for Amend to License DPR-69,revising Heatup & Cooldown Curves & LTOP Controls for Unit 2 to Support Mods to LTOP Sys Scheduled for Spring 1995 Refueling Outage ML20069C2801994-05-27027 May 1994 Application for Amends to Licenses DPR-53 & DPR-69, Revising TS Surveillance Test Interval from Monthly to Quarterly for Several Channel Functional Tests for RPS & ESFAS ML20058K2831993-12-0808 December 1993 Application for Amends to Licenses DPR-53 & DPR-69,revising TS Associated W/Content of Design Features ML20059L4051993-11-11011 November 1993 Application for Amends to Licenses DPR-53 & DPR-69,revising TSs by Relocating Tables of Response Time Limits for Reactor Protection Sys & ESFAS Instruments from TSs to Updated FSAR 1999-09-01
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20211J3431999-09-0101 September 1999 Amends 231 & 207 to Licenses DPR-53 & DPR-69,respectively, Revising Appropriate TSs to Permit Use of leak-limiting Alloy 800 Repair Sleeves Developed by ABB-CE ML20211J9861999-09-0101 September 1999 Application for Amends to Licenses DPR-53 & DPR-69,changing Definition of Azimuthal Power Tilt in TS 1.1,correcting Peak Linear Heat Rate Safety Limit in TS 2.1.1.2 & Correcting Dc Voltage Range Listed in Surveillance Requirement 3.3.6.2 ML20211G7591999-08-27027 August 1999 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 3.7.13 to Allow Placement of One or More Fuel Assemblies on SFP Rack Spacers to Support Fuel Reconstruction Activities During Continuing Fuel Assembly Movement ML20205P7761999-04-14014 April 1999 Amends 230 & 206 to Licenses DPR-53 & DPR-69,respectively, Revising TS 3.7.6 to Allow Operation of Units 1 & 2 with One SRW Plate & Frame Heat Exchanger in Subsystem Secured ML20207L2911999-03-0808 March 1999 Amend 205 to License DPR-69,permitting One Time Change to TS 3.8.2 to Provide Alternate Cooling to EDGs During Replacement of Service Water Heat Exchangers in 1999 Refueling Outage ML20196J6721998-12-0808 December 1998 Amends 229 & 204 to Licenses DPR-53 & DPR-69,respectively, Revising TS 3.3.1 & TS 3.3.2 to Clarify Inconsistency Between TS Wording & Design Bases as Described in TS Bases & UFSAR ML20196E2101998-11-30030 November 1998 Application for Amends to Licenses DPR-53 & DPR-69,allowing Repair of Defective SG Tubes with leak-limiting Alloy 800 sleeves.Non-proprietary Rev 03-P to CEN-633-NP & Proprietary Rev 03-P to CEN-633-P,encl.Proprietary Info Withheld ML20196A6001998-11-20020 November 1998 Application for Amends to Licenses DPR-53 & DPR-69, Requesting Indirect Transfer of Control,Pursuant to 10CFR72.50,of Matls License SNM-2505 for Plant ISFSI ML20195K3711998-11-20020 November 1998 Application for Amends to Licenses DPR-53 & DPR-69,removing TS Originally Developed from Reg Guide 1.35 & Implementing Requirements of 1992 Edition Through 1992 Addenda of ASME B&PV Code Section Xi,Subsections IWE & Iwl,Per 10CFR50.55a ML20195J7131998-11-19019 November 1998 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 3.7.6, SWS, by Adding One SWS Heat Exchanger Inoperable as New Condition for LCO 3.7.6 ML20154N1861998-10-16016 October 1998 Application for Amends to Licenses DPR-53 & DPR-69 to Incorporate Revised TS 3.3.1 & 3.3.2 to Clarify Inconsistency Between TS Wording & Design Bases as Described in TS Bases & UFSAR ML20236S5591998-07-20020 July 1998 Application for Amend to Licenses DPR-53 & DPR-69,providing Alternate Cooling Water Supply to Maintain EDGs Operability During 1999 Refueling Outage ML20236S1341998-07-20020 July 1998 Application for Amend to License DPR-59,implementing Mod That Involves Replacing SW Heat Exchangers W/New Plate & Frame Heat Exchangers Having Increased Thermal Performance Capability ML20249C0021998-06-23023 June 1998 Corrected Amends 227 & 201 to Licenses DPR-53 & DPR-69. Revision Due to Failure to Include Pages 10-13,Section 3.4, Reactor Coolant Sys, or Se,Table L,Matrix of Less Restrictive Changes & in Bases,Page B 3.7.6-5 ML20248B0131998-05-23023 May 1998 Amends 228 & 202 to Licenses DPR-53 & DPR-69,respectively, Revising TS for Reduction of Total Reactor Coolant Sys Flow Limit from 370,000 Gpm to 340,000 Gpm in Support of Increased SG Tube Plugging ML20216H1661998-03-17017 March 1998 Amends 226 & 200 to Licenses DPR-53 & DPR-69,respectively, Change TSs to Incorporate Both Steady State & Transient Degraded Voltage Setpoints as Opposed to Current Single Degraded Voltage Setpoints ML20203A6461998-02-10010 February 1998 Amend 225 to License DPR-53,authorizing Rev of UFSAR in Response to as Supplemented 971114,to Reflect Installation of Svc Water HX W/New Plate & Frame HX ML20198K9591998-01-12012 January 1998 Rev 11 to 961204 Application for Amends to Licenses DPR-53 & DPR-69,converting to Improved Sts,Per NUREG-1432 ML20198K5481998-01-0505 January 1998 Amend 224 to License DPR-53,consisting of Changes to TSs 4.8.1.1.2.a.5,4.8.1.1.2.d.4 & 4.8.1.1.2.d.5,in Response to Application Transmitted by ML20202C3561997-11-18018 November 1997 Amends 223 & 199 to Licenses DPR-53 & DPR-69,respectively, Incorporating Refs to New C-E TR Describing SG Tube Sleeves, Deleting Refs to Previous C-E TR & Incorporating Sleeve/Tube Insp Scope & Expansion Criterion ML20217K6591997-10-22022 October 1997 Application for Amends to Licenses DPR-53 & DPR-69, Incorporating Both Steady State & Transient Degraded Voltage Setpoints Into Tss,As Opposed to Current Single Degraded Voltage Setpoint ML20211J2691997-10-0202 October 1997 Application for Amend to License DPR-53,revising TS to Reflect New Electrical Capacity for 1B Edg.Significant Hazards Considerations Associated W/Change Have Been Evaluated ML20211J4791997-10-0202 October 1997 Amends 222 & 198 to Licenses DPR-53 & DPR-69,respectively, Reduce Mtc Limit on TS Figure 3.1.1-1 ML20141F9181997-05-16016 May 1997 Application for Amend to License DPR-53,implementing Mod Involves Replacing Service Water Heat Exchangers W/New Plate & Frame Heat Exchangers Having Increased Thermal Performance Capability ML20135F7971997-03-0707 March 1997 Amends 221 & 197 to Licenses DPR-53 & DPR-69.Amends Modify TSs Requirements to Allow Use of Blind Flanges During Modes 1-4 in Plants Unit 1 & 2 Containment Purge Sys Instead of Two Outboard 48 Inch Isolation Valves ML20136A9751997-03-0606 March 1997 Application for Amend to License DPR-69,allowing Mod to Unit 2 SW Sys Which Constitutes Unreviewed Safety Question in 10CFR50.59 ML20134N6951997-02-19019 February 1997 Amend 220 to License DPR-53 Concerning Provisions at Plant for Receiving,Possessing & Using Byproduct,Source & Special Nuclear Matl ML20134K7261997-02-11011 February 1997 Amends 219 & 196 to Licenses DPR-53 & DPR-69,changing TSs in Response to & Adopting Option B,10CFR50,app J to Require Type B & C Containment Leakage Testing to Be Performed on Performance Based Testing Schedule ML20134D2871997-01-31031 January 1997 Application for Amends to Licenses DPR-53 & DPR-69,changing to Support Larger Number of Plugged SG Tubes for Future Operating Cycles ML20134A9491997-01-23023 January 1997 Amends 218 & 195 to Licenses DPR-53 & DPR-69,respectively, Revising TS to Extend Automatic Actuation Logic Channel Fuctional Test Interval of Engineering Safety Features Actuation System & Surveillance Test Interval of Valves ML20149M0801996-12-0404 December 1996 Application for Amends to Licenses DPR-53 & DPR-69,revising TSs to Be Generally Consistent w/NUREG-1432,Rev 1,thus Replacing 2 Current Sets of TSs W/Single Set Applicable to Both Units ML20135A5171996-11-26026 November 1996 Application for Amends to Licenses DPR-53 & DPR-69,adopting Option B of 10CFR50,App J,To Require Types B & C Containment Leakage Rate Testing to Be Performed on performance-based Testing Schedule ML20129D6911996-10-18018 October 1996 Amends 217 & 194 to Licenses DPR-53 & DPR-69,respectively, Implementing Changes to RETS IAW GL 89-01, Implementation of Programmatic for Radiological Effluent TS in Admin Controls Section of TSs & Relocation of Procedural.. ML20128H5971996-10-0303 October 1996 Application for Amend to License DPR-53,changing Provisions for Receiving,Possessing & Using Byproduct,Source & Special Nuclear Matl at Plant ML20117L7801996-09-10010 September 1996 Application for Amends to Licenses DPR-53 & DPR-69 Requesting Extension of ESFAS Automatic Actuation Logic Surveillance from Monthly to Quarterly ML20117H6211996-08-26026 August 1996 Amends 216 & 193 to Licenses DPR-53 & DPR-69,respectively, Revising TS Section 6.0 Administrative Controls to Be Consistent W/Sts & Allow STA to Perform Dual Roles ML20116F8231996-08-0101 August 1996 Application for Amends to Licenses DPR-53 & DPR-69,allowing Use of Blind Flanges During Modes 1-4 in Plant Containment Purge Sys ML20116E3571996-07-26026 July 1996 Application for Amends to Licenses DPR-53 & DPR-69,to Repair Defective SG Tubes by Electrosleeving ML20112J3271996-06-17017 June 1996 Amends 215 & 192 to Licenses DPR-53 & DPR-69,revising Applicable UFSAR Sections to Reflect Installation of Variable Flow Controller for Service Water Inlet Control Valves for Containment Air Coolers ML20117J1911996-05-28028 May 1996 Application for Amend to License DPR-53 & DPR-69,requesting Exigent Amends to Allow Installation of Proposed Modification of Unit 1 & 2 Service Water (SRW) Systems ML20101N3101996-04-0202 April 1996 Amends 214 & 191 to Licenses DPR-53 & DPR-69,respectively, Reflecting New Plant Electrical Distribution Configuration, Surveillance & Limiting Condition for Operation of New SR EDG ML20101K5911996-03-28028 March 1996 Application for Amends to Licenses DPR-53 & DPR-69, Requesting to Reduce Moderator Temp Coefficient Limit Shown on TS Figure 3.1.1-1 ML20101G9181996-03-22022 March 1996 Amends 213 & 190 to Licenses DPR-53 & DPR-69,respectively, Allowing Installation of Tube Sleeves as Alternative to Plugging for Repairing SG Tubes Using Repair Techniques Developed by Westinghouse Electric Corp ML20101D8211996-03-15015 March 1996 Suppl to LAR Re Sleeving Option for SG Tube Repair.Proposes Rev to TS Wording in Attachments (A-3) & (A-4) by Removing Generic Ref to Technical Repts & Replace W/Ref to Specfic Approved Repts ML20101G2791996-03-13013 March 1996 Amends 212 & 189 to Licenses DPR-53 & DPR-69,respectively, Revising TSs to Reflect Approval for Use of 10CFR50,App J, Option B,For Plant Containment Leakage Rate Test Program for Type a Tests ML20100H1321996-02-21021 February 1996 Amend 211 to License DPR-53,allowing Use of Cladding Matl Other than Zircaloy or ZIRLO ML20097E3461996-02-0505 February 1996 Amends 210 & 188 to Licenses DPR-53 & DPR-69,respectively, Adding Convolution Analytical Technique for Analysis of Pretrip MSLB Event ML20096D4291996-01-16016 January 1996 Application for Amends to Licenses DPR-53 & DPR-69,adopting Option B of 10CFR50,App J to Require Type a Containment Lrt to Be Performed on performance-based Testing Schedule ML20095L7481995-12-28028 December 1995 Amend 209 to License DPR-53,revising CC-1 TSs by Extending Certain 18-month Instrument Surveillance Intervals by Max of 39 Days to 960331 ML20095K2701995-12-21021 December 1995 Application for Amends to Licenses DPR-53 & DPR-59, Requesting Temporary Exemption & TS Change to Allow Placement of Four Lead Test Fuel Assemblies in Unit 1 Reactor Core During Cycles 13,14 & 15 1999-09-01
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1 Rosss:nt EL Duxs os Baltimore Gas and Electric Company Calven Chfs Nuclear Power Plant Vice President 1650 Calven Cli[fs Parkway Nucler rgy Lusby Maryland 20657 410 586-2200 Ext. 4455 local 410 260-4455 Baltimore l
June 8,1994 1
U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 License Amendment Request; Extension of Auxiliary Feedwater Testing Surveillancys from 18 to 24 Months
REFERENCE:
(a)
NRC Generic Letter 91-04, Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle, dated April 2,1991 Pursuant to 10 CFR 50.90, the Baltimore Gas and Electric Company hereby requests an Amendment to Operating Licenses Nos. DPR-53 and DPR-69 by the incorporation of the changes described below to the Technical Specifications for Calvert Cliffs Unit Nos.1 and 2.
DESCRIPTION The proposed amendment would revise the Calvert Cliffs Nuclear Power Plant (CCNPP) Units 1 and 2 Technical S,ecification 4.7.1.2.c to extend the interval for three Auxiliary Feedwater (AFW) surveillance requirements from 18 to 24 months.
Cahcrt Cliffs has been operating on a 24-month fuel cycle since July 1987 (Unit 2), and July 1988 (Unit 1), performing some Technical Specification surwillances, such as those described here, during mid-cycle outages. This request is i
one of a wries of proposed license amendments that would climir. ate the need for mid-cycle surveillance outages by extending 18-month frequency surveillances to refueling interval (nominally l
24 moaths).
1 The Technical Specification surveillances of concern verify fnat upon receipt of an Auxiliary Feedwater Actuation System (AFAS) test signal, AFW automatic valves actuate, the AFW pumps start, and the AFW System provides the flow rate assumed by the CCNPP safety analyses.
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Document Control Desk June 8,1994 Page 2 '
HACKGROUND The AFW System is a safety-related system designed to provide an alternate supply of feedwater to the steam generators for the removal of decay heat and cooldown of the Reactor Coolant System if the Main Feedwater System, a non-safety-related system, is unavailable. The AFW System can also be used for normal cooldown of the Reactor Coolant System and to fill the steam generators prior to normal operation.
He AFW System has two turbine-driven pumps and one motor-driven pump, drawing water from a condensate storage tank. The AFAS starts the motor-driven pump and opens the steam supply valves to the turbine-driven pumps when the level in either steam generator drops to a low level setpoint. Normal alignment of the turbine driven pumps has one pump start automatically and one remain in standby. Flow control valves regulate flow to the steam generators for removing decay heat. In the event of a high differential pressure between steam generators event, such as a steam generator tube rupture or main steam line break, AFW flow to the affected steam generator is isolated when an AFAS Block signal shuts the blocking valves in each AFW line to the affected steam generator.
He AFW surveillances with 18-month frequencies verify:
cach automatic valve in the flowpath actuates to its correct positien upon receipt of each AFAS test signal (4.7.1.2.c.1);
cach AFW pump automatically starts upon receipt of each AFAS test signal (4.7.1.2.c.1); and the AFW System is capable of providing a minimum of 300 gallons per minute (gpm) nominal flow to each flow leg (4.7.1.2.c.2).
These surveillances ensure the AFW pumps, flow control valves, blocking valves and the electrical signal paths function properly. Monthly and 18-month surveillance tests both verify proper operation of the valves and that the appropriate AFW pumps start. The 18-month surveillance is i
different from the monthly surveillance in that the 18-month surveillance is performed with the pump discharge valve open ta allow AFW flow into tb" steam generators and verifies the minimum AFW flow rate of 300 gpm in each leg using AFW flor t ' atin~g controllers.
Calvert Cliffs has been operating on a 24-month f uel cycle since July 1987 (Unit 2), and July 1988 (Unit 1), performing Technical Specification surveillances with 18-month frequencies during mid-cycle outages, as needed. This request is one of a series of proposed license amendments that would eliminate the need for mid-cycle outages by extending 18-month frequency surveillances to a refueling frequency.
}tEOUESTED CilANGE Revise Technical Specification 4.7.1.2.c as shown on the marked-up pages attached to this transmittal, increasing the surveillance interval from 18 months to the refueling interval (nominally 24 months).
Document Control Desk June 8,1994 Page 3 SAFE"lY ANAL,YSIS The AFW System maintains water level ia the steam generators and removes decay heat if the Main Feedwater System is unavailable. Reference (a) states that for cases where 18 month surveillances do not involve calibration of instruments that perform safety functions, licensees should evaluate the effect on safety of the change in surveillance intervals which supports a conclusion that the effect on safety is small. Licensees should confirm that historical maintenance and surveillance data do not invalidate this conclusion. The monthly AFW surveillances test the same functions as the 18-month tests, except for flow rate. An evaluation of the monthly and 18-month surveillances from January 1,1989 to December 31,1993 on the AFW components effected by this change found no test failures during performance of Surveillance 4.7.1.2.c. Examining overall reliability, there has been only one turnine-driven AFW pump trip in over seventy starts during this period, three of which were demand starts. There have been no recorded failures of the motor-driven pump to start during this period. No instruments are calibrated by these 18-month surveillances.
Prior to 1989, the AFW System met Technical Specification requirements, but we believed that plant safety could be enhanced by improving AFW System performance. As a result of modifications and administrative improvements begun in 1989, the CCNPP AFW System had an INPO criteria-based unavailability index in 1993 ofless than 0.01.
Based on the AFW System reliability and the surveillance history provided, we conclude that the requested surveillance extension will not adversely affect our ability to detect degradation in the AFW System, and does not invalidate any assumption in the plant licensing basis.
j DETERMINATION OF SIGNIFICANT IIA 7ARDS The proposed change has been evaluated against the standards in 10 CFR 50.92 and has been determined to not involve a significant hazards consideration, in that operation of the facility in accordance with the proposed amendments:
1.
Would not involve a significant increase in the probability or consequences of an accident previously evaluated.
The Auxiliary Feedwater (AFW) System provides a safety-related source of feedwater to the steam generators to mitigate design basis accidents involving loss of Main Feedwater. Failure of the AFW System is not an initiator for any previously analyzed accident. Therefore, the proposed change does not involve an increase in the probability of an accident previously evaluated.
A historical review of surveillance test results and system performance indicates that the AFW System is very reliable. In addition, monthly surveillances of the AFW System will continue to verify proper pump and valve operation. The AFW System reliability and monthly surveillances provide assurance that undetected system degradation will not occur between 24-month surveillances. Therefore, the AFW System will continue to perform its safety function and there will be no significant increase in the consequences of accidents.
Therefore, the proposed Technical Specification changes do not increase the probability or consequences of an accident previously evaluated.
1 Document Control Desk June 8,1994
,Page 4 2.
Would not create the possibility of a new or different type of accident from any accident previously evaluated?
This requested revision to increase the interval for some AFW surveillances from 18 to 24 months does not involve a significant change in the design or operation of the plant.
I No hardware is being added to the plant as part of the proposed change. The proposed change will not introduce any new accident initiators. Therefore, this change would not create the possibility of a new or different type of accident from any accident previously evaluated.
3.
Does operation of thefacility in accordance with thepoposed amendment involve a significant reduction in a margin ofsafety?
The AFW System provides a margin of safety by providing a safety-related alternate supply of feedwater to the steam generator for removal of decay heat and cooldown of the Reactor Coolant System. The proposed ch:nges do not affect the operation or design of the AFW System. Monthly surveillances and historical data provide assurance that the reduction in surveillance frequency will not adversely affect our ability to detect degradation in the system.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
SCIIEDULE This change is requested to be approved and issued by December 1,1994. However, issuance of this amendment is not currently identified as having an impact on outage completion or continued plant operation.
fNVIHONMENTAL ASSESSMENT The proposed amendment would change requirements with respect to the installation or use of a facility component located within the restricted area, as defined in 10 CFR Part 20, or changes to an inspection er surveillance requirement. We have determined that the proposed amendment involves no significant hazards consideration, and that operation with the proposed amendment would result in no significant change in the types or significant increases in the amounts of any effluents that may be released offsite, and in no significant increase in individual or cumulative occupational radiation exposure, nerefore, the proposed amendment is eligible for categorical exclusion as set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment is needed in connection with the approval of the proposed amendment.
SAFIm' COMMITTEE HlWIEW nese proposed changes to the Technical Specifications and our determination of significant 1 azards have been reviewed by our Plant Operations and Safety Resiew Committee and Offsite Safety Review Committee. ney have concluded that implementation of these changes will not result in an undue risk to the health and safety of the public.
q.
!.i Document Control Desk 4
June 8,1994 i
Pagc 5 Should you have any questions regarding this matter, we will be pleased to discuss them with you.
l i
y yours,
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t STATE OF MARYLAND :
- TO WIT :
i COUNTY OF CALVERT
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b I hereby certify that on the hb day of d_uAo
,19 94, before m the subscriber, r
a Notary Public of the State of Maryland in and for g,t 1f, e 4 f-
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personally appeared Robert E. Denton, being duly sworn, and stues that he is Vice Presidenvof the Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he provides the -
foregoing response for the purposes therein set forth; that the statements made are true and correct i
to the best of his knowledge, information, and belief; and that he was authorized to provide the -
response on behalf of said Corporation.
I/+-
WITNESS my Hand and Notarial Scal:
c.
Notary Public j
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t My Commission Expires:
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U (pate
.]
RED /JV/ dim Attachments: (I)
Unit 1 Marked.up Technical Specification Page (2)
Unit 2 Marked-up Technical Specification Page ec:
D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC D. G. Mcdonald, Jr., NRC 1
T. T. Martin, NRC P. R. Wilson, NRC R. I. McLean, DNR J. H. Walter, PSC 1
)
i
ATTACHMENT (1)
UNIT 1 TECHNICAL SPECIFICATION MARKED-UP PAGE 3/47-7
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