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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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CH ARLES II. CRUSE Baltimore Gas and Electric Company Vice President Calvert Cliffs Nuclear Power Plant Nuclear Energy 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 410 495-4455 March 28,1996 U. S. Nuclear Regulatory Comndssion 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: Change to the Moderator Temperature Coefficient
REFERENCES:
(a)
Letter from Mr. S. A. McNeil (NR.C) to Mr. J. A. Tiernan (BGE), dated May 4,1987, Issuance of Amendment 108 for Calvert Cliffs Unit 2 (b)
Letter from Mr. S. A. McNeil (NRC) to Mr. J. A. Tiernan (BGE), dated May 16,1988, Unit 1 Cycle 10 Technical Specification Amendment (TAC No. 67143)
(c)
Letter from Mr. S. A. McNeil (NRC) to Mr. J. A. Tieman (BGE), dated March II,1988, Request for Additional Information - Unit 1 Cycle 10 Reload (TAC 67143)
(d)
Letter from Mr. S. A. McNeil (NRC) to Mr. J. A. Tiernan (BGE), dated November 2,1988, Safety Evaluation Conceming Conformance to the A'lWS Rule (TAC Nos. 59079 and 59080)
Pursuant to 10 CFR 50.90, the Baltimore Gas and Electric Company (BGE) hereby requests an amendment to Operating License Nos. DPR-53 and DPR-69 to reduce the moderator temperature coefficient (MTC) limit shown on Technical Specification Figure 3.1.1-1.
This proposed change is necessary to support changes in the safety analyses made to accommodate a larger number of plugged steam generator (SG) tubes for future operating cycles. In addition, we are providing information to clarify the relationship of MTC to an Anticipated Transient Without Scram event in our licensing basis.
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Documerst Control Desk March 28,1996 Page 2 l
BACKGROUND As the SGs at Calvert Cliffs age, it may be necessary to plug additional SG tubes. One of the inputs into
. several of the safety analyses is the amount of heat transfer area available in the secondary system.
Herefore, the numbn of SG tubes plugged impacts these safety analyses. To ensure that the safety analyses remain boundmg, we assume that the number of tubes plugged are greater than the number we expect to have plugged during the operating cycle. It is, therefore, necessary to increase the number of SG tubes that are assumed plugged in appropriate safety analyses to support,the potential need to plug additional SG tubes. For several of the safety analyses supporting Unit 1 Cycle 13 and Unit 2 Cycle 11 operaton, BGE has assumed an increased number of plugged SG tubes. Unit 1 Cycle 13 operation is planned to begin in spring 1996, and Unit 2 Cycle 11 is currently in progress.
REOUESTED CHANGE The safety analyses for the current fuel cycles assume 500 tubes per SG are plugged and the maximum beginning-of-cycle MTC is assumed to follow the curve in Technical Specification Figure 3.1.1-1. If we need to plug additional tubes during the outage, that could take us beyond the current limit (500 tubes).
Increasing the number of SG tubes assunux! to be plugged in the analyses to above 500 reduces the calculated heat transfer area from the Reactor Coolant System (RCS) to the secondary side of the SG.
This causes a larger increase in RCS temperature and pressure during certain plant heatup events. In order to mitigate the RCS pressure and temperature increase for these events with an increased number of plugged SG tubes, it is necessary to credit a more restrictive (less positive) limit on the maximum positive MTC in these analyses. A less positive MTC results in reduced core reactivity during plant heatup events.
His reduced core reactivity mitigates the increase in RCS temperature and pressure during these events, ne limitatens on MTC are provided to ensure that the assumptions used in the accident analyses remain valid for each fuel cycle. Four analyses are affected by the change in the assumption regarding the number of plugged SG tubes and require a compensating decrease in MTC. Rey are the loss of Load, Loss of Feedwater Flow, Feed Line Break, and Contiol Element Assembly Withdrawal events (Updated Final Safety Analysis Report Sections 14.5,14.6,14.26, and 14.2). These analyses were reanalyzed using approved methodologies to determine the effect of the change in plugged SG tubes. He results of the analyses remain within the previously approved limits. He change to the MTC limit more than offsets the effects of the increased number of plugged SG tubes. We are proposing a change to the allowable positive MTC limits shown on Technical Specification Figure 3.1.1-1. The proposed limit will be more restrictive than the existing limit (see marked-up pages in Attachments 2 and 3) to match the assumptions used in the events listed above.
CLARIFICATION OF THE LICENSING BASIS Technical Specification 3.1.1.4 allows full power operation with a positive MTC; however, an outstanding comnutment existed related to anticipated transient without scram (ATWS) compliance to design reactor cores with a negative full power MTC at equilibrium xenon conditions. References (a) and (b) indicate our commitment to the Nucicar Regulatory Commission (NRC) to design cores with a negative full power MTC to ensure that if there were an ATWS event, the acceptable margin of safety would not be i
u-
Document Control Desk March 28,1996 Page 3 compromised. As discussed in Reference (c), this commitment was made in lieu of an evaluation of a positive MTC on the safety margin provided for an ATWS event. An attemative to evaluating the effect of an ATWS event on the reactor core is to install the mitigating features required by the ATWS rule (10 CFR 50.62). At the time that References (a) and (b) were issued, we had not completed installation of our ATWS mitigation hardware. Herefore, since that time, BGE has implemented the commitment to design cores with a negative full power MTC. The predicted and measured full power MTC at equilibrium xenon conditions has been negative on both Units since 1987.
Since then, BGE has implemented the long-term ATWS resolution by installing the Diverse Scram System on both Unit I and Unit 2. This system has been reviewed and accepted by NRC (Reference d) as meeting the requirements of 10 CFR 50.62. Based on installing the Diverse Scram System as the long-term resolution to ATWS, it is no longer necessary for BGE to design cores such that the full power MTC is negative. Therefore, BGE considers this proposed Technical Specification limit on the maximum positive MTC to be the sole MTC limitation for core design and operation. This consideration has little real effect on how BGE will design cores in the future since some margin to the proposed MTC limit of + 0.15 X 104
@/.y will be preserved in the design process. However, considering this proposed Technical Specification limit on the maximum positive MTC as the sole requirement for core design and operation, with respect to a limit on positive MTC, clarifies our current licensing basis.
SCHEDULE Baltimore Gas and Electric Company does not consider NRC approval of this change to the Technical Specifications necessary prior to startup for Unit 1 Cycle 13 operation (spring 1996). Administrative procedures at the plant will be changed to ensure the proposed MTC limit is met during Unit 1 Cycle 13 operation. The current predicted maximum full power MTC for Unit 1 Cycle 13 at equilibrium xenon conditions is negative. Technical Specifications will not be violated during operation of Unit i Cycle 13 without this change. However, in order for the Technical Specifications to remain consistent with safety analysis assumptions, we request that this change be approved by September 1,1996. Baltimore Gas and Electric Company requests that this change be made to both the Unit I and Unit 2 Technical Specifications at this time since the safety analyses supporting an increase in the number of plugged SG tubes are applicable to both Units 1 and 2. He current full power MTC for Unit 2 is negative and will become more negative as the cycle progresses.
We have evaluated the significant hazards considerations associated with this change as required by 10 CFR 50.92, and determined that there are none (see Attachment I for a complete discussion). We have also determined that operation with the proposed amendment would not result in any significant change in the types or significant increases in the amounts of any efiluents that may be released offsite. It also would
)
not result in a significant increase in individual or cumulative occupational radiation exposure. Herefore, the proposed amendment is eligible for categorical exclusion as set forth in 10 CFR 51.22(c)(9). The Plant Operations and Offsite Safety Review Committees have reviewed the proposed change and concurred that the change will not result in an undue risk to the health and safety of the public.
A
Document Control Desk March 28,1996 Page 4 Should you have questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, j
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/ M 14 STATE OF MARYLAND i
- TO WIT :
COUNTY OF CALVERT I hereby certify that on the 2 fl1) day of M
Cd fL/A.l) h before me, the subscriber, a
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. personally Notary Public of the State of Maryland in and for appeared Charles H. Cruse, being duly sworn, and states that he is Vice President of tp Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he provides the foregomg response for the purposes therein set forth; that the statements made are true and correct to the best of his knowledge, information, and belief; and that he was authorized to provide the response on behalf of said Corporation.
WITNESS my Hand and Notarial Seal:
(A4Adf)
Notary Public My Commission Expires:
b h
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Ijate CHC/ PSF / dim i
Attachments:
(1)
Determination of Significant Hazards (2)
Unit 1 Marked-Up Technical Specification Page (3)
Unit 2 Marked-Up Technical Specification Page cc:
D. A. Brune, Esquire J. E. Silberg, Esquire L. B. Marsh, NRC D. G. Mcdonald, Jr., NRC T. T. Martin, NRC Resident Inspector, NRC R. I. McLean, DNR J. H. Walter, PSC
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l ATTACIIMENT (1) i i
l 1
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4 i
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j DETERMINATION OF SIGNIFICANT HAZARDS i
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t 1
i 1
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Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant March 28,1996
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