Letter Sequence Request |
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MONTHYEARML20127D0161992-09-0101 September 1992 Application for Amends to Licenses DPR-53 & DPR-69,revising TS 5.6.1 to Decrease Enrichment Limit of Spent Fuel Storage Racks from 5.0 Weight Percent (W/O) U-235 to 4.52 W/O U-235 to Correct Errors in ABB/C-E Calculations Project stage: Request 1992-09-01
[Table View] |
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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
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] |
Text
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1
. i f BALTIMORE GAS AND ELECTRIC 1650 CALVERT CtJFFS PARKWAY . LUSBY, MARYLAND 20057-4702 l 0""'M,",',"
y p September 1,1W2 AecLt a si E nt sour
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t U. ii. Nuclear Regulatoiy Commission Washington, DC 20555 ATI'ENTION: Document Control Desk ,
SUBJEC'n Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50 317 & 50 318 License Amendment Request: Spent Fuel Pool EnrictLrnGl.t.liFil i .
REFERENCES:
(a) Ixtier from htr. S. A. hicNeil (NRC) to htr. G. C. Creel (BG&E),
dated January 10, 1990, Issuance of License Amendment (Unit 1 TAC 68416; Unit 2 TAC 68417)
(b) letter from S. A. Toelle (CE) to htr. R. C. Jones (NRC), dr4ted -
February 28, 1992, Accuracy of Fuel Storage Rack Criticality Calculations (c) Letter from S. A. Toclle (CE) to h1r. L 1. Kopp (NRC), dated h1 arch 27, 1992, Accuracy of Fuel Storage Rael: Criticality Calculations (d) letter from hir G. C. Creel (BG&E) to NRC Document Control ,
Desk, dated June 4,1992, Discovery of Non Conservative Technical SpeciGeations (c) letter from hir. G. C. Creel (BG&E) to NRC Document Control Desk, dated July 28,1992, Update of License Amendment Schedule (f) EPRI NP-6159, December 1988, "An Assessment of Bora0cx Performance in Spent Fuel Storage Racks" Gentlemen:
The Baltimore Gas and Electric Company hereby requests an Amendment to its Operating License Nos. DPR 53 and DPR-69 for Calvert Cliffs Unit Nos.1 and 2, respectively, with the submittal of the proposed changes to the Technical Specifications.
090015 j) h56#
t 9209110104 920901 l DR ADOCK0500g7 - () '
I j
-- __._. - - - - .. - - _ ..-_~
. Document Control Desk
, September 1.1992 Page 2 DESCHIPTION The proposed amendment would revise the Unit Nos.1 and 2 Spent Fuel Pool enrichment limit. The ;
Spent Fuel Pool enrichment limit is being decreased from th< .urrent value of 5.0 weight percent !
(w/o) U.235 to 4.52 w/o U 235 because of errors in the calculations performed by ABB/ Combustion !
Ungineering which supported 5.0 w/o U 235.
IIACKGROUND The Calvert Cliffs Spent Fuel Pool holds fuel from both units. It is actually two pmts separated by a dividing wall but connected by a weir gate. The north half of the pool connects to the Unit 1 containment and the south half connects to the Unit 2 containment. Fuel from the two units is not sepegated as the two halves of the Spent Fuel Pool are treated as one pool. Figure (1) is a schematic of the Spent Fuel Pool. *
%c Spent Fuel Pool has been reracked several times over the life of the plant. With the existing configuration of high density poisoned racks, the Unit 1 racks are nearly identical to the Unit 2 racks (see Figure 2). De distinction between the two halves is the type of poison material used. %c '
Unit I racks use a boron carbide composite material which is not susceptible to gap formation. The poison material used in Unit 2 racks is Boraflex. Boraficx is susceptible to gap formation for reasons related to irradiation behavior and manufacturing techniques. Therefore a reactivity penalty is typically applied to Boraflex when performing criticality analyses.
In Reference (a) the Nuclear Regulatory Commission (NRC) approved an increase in the maximum allowed enrichment of fuel in the Spent Fuel Pool to 5.0 w/o U 235. This submittal treated the two .
halves of the pool as identical by applying the boraficx penalty to both sets of racks. %is was a conservative step which simplified the analytical treatment of the pools.
E In early 1992, ABB/ Combustion Engineering informed the NRC of errors in the Spent Fuel Pool l criticahty calculations performed for several iower plants l References (b) and (c)]. Baltimore Gas and Electric Company (BG&E) had used t1ese incorrect calculations to support the request to increase the maximum allowed enrichment of fuelin the Spent Fuel Pool to 5.0 w/o U 235.
- Upon notification of the errors, BO&E immediately assessed the situation to confirm that fuel assemblics stored to date in the 1001 had not presented a safety concern and that placement of new fuelinto the pool in support of the reload of Unit 1 Cycle 11 was acceptable. Preliminary analysis showed that the errors reduced the allowable enrichment for the Unit 1 pool to 4.55 w/o U-235 and for the Unit 2 pool to 4.15 w/o U-235. In order to ensure that the preliminary enrichment limits were adhered to, we separated the two pools using administrative controls pending the final analysis.
References (d) and (c) documented BG&E's notification of the problem and the schedule to correct the Technical Specifications. Final analysis resulted in a maximum allowable enrichment of 4.52 w/o U-235 for both pools.
ItEOUESTEI CilANGES l Change Technical Specification 5.6.1 for Unit Nos.1 and 2 to decrease the enrichment limit of the l spent fuel storage racks to 4.52 w/o U 235 as shown in Attachments (1) and (2), respectively.
l I
L
. Document Control Desk
.Septensber 1,1992 Page 3 SMislYJNA13 SIN /.1URI11 ICATION The proposed change to the Technical Specifications will allow s*croge of fuel enriched to 4.52 w/o U.235 in the = pent fuel racks of both Units. The Unit I spent fuel storage racks use a poison material made of a toron carbide composite not susceptible to gap formation. The as fabricated areal density of the boron carbide composite is 0.024 grams of U-10 per square centimeter. It has a design end-of life areal density of 0.02 grams of B-10 per square centimeter which was assumed in the analysis. The poison material is 0.09 inches thick and is sandwiched between two stainless steel sheets, each 0.06 inches thick. The poison sheets are 6.5 inches wide.
The Unit 2 storage racks are identical to those of Unit 1 except that a different poison mato ial is used. The Unit 2 racks use Borauex with an areal density of 0.02 grams of B-10 per .quare centimeter. "Ihe poison sheets are nominally 0.08 inches thick (0.07 inches was used in the analysis) and 6.5 inches wide. The effects of Bora0cx gapping were considered. The causes of Horanex gap formation are related to the irradiation behavior of the material and to manufacturing practices.
When the material becomes brittle and shrinks under irradiation, gaps have been shown to form where the material was constrained.
The manufacturer for the Calvert Cliffs racks has indicated that there were no manufacturing directives which would have led to constraint of the Botaflex sheets during rack manufacture.
Therefore, the sheets would be less likely to form gaps. As no measurements have been made to determine the existence of gaps at Calvert Cliffs, a conservative gap penalty was applied to arount for the possibility that they may exist. Four-inch gaps were assumed to exist in eve y shut of Boranex and the gaps in the four walls of any given rack cell were assumed to be axially aligned.
Based on research done by EPRI on Boranex sheets constrained during manufacturing l Reference (f)] relatively few cumulative gaps have been observed to exceed two inches. Therefore, the four. inch gap assumed in the Baranex sheets is conservative.
The four-inch gaps in adjacent tack cells were assumed to be staggered slightly, with a two-inch vertical scparation which leads to a checkerboard pattern when h30 king at the entire pool. This is significantly more conservative than assuming a random gap distribution which industry experience indicates is the more likely case. The gaps were assumed to be distributed preferentially around the axial centerline of the fuel assembly. The worth of the gaps will be the greatest in the highest Dux region of the fuel assembly. The Oux is highest at the fuel centerline, and decreases as the ends of the fuel assembly are approached. Therefore, for conservatism the gap penalty was calculated at the axial location of highest worth, the centerline of the fuel.
The only calculational difference between the two rack designs is the penalty associated with the Boranex gapping for the Unit 2 racks. For operational convenience, the lower calculated enrichment limit for the Unit 2 racks is proposed for the entire pool. The maximum allowable enrichment limit for a k-effective value of 0.95 is 4.52 w/o U-235. Attachment (3)is a description of the analysis used to calculate the new enrichment limit.
-- - - - , _ - - ~ ~ _ - - , , _ - , - - - - - _ _ -
Document Control Desk September 1,1992 Page 4)glitMINglON OF SIGNIFICANT ll A7A1(I)S
%e proposed changes have been evaluated against the standards in 10 CFR 50.92 and have been determined to not involve a significant harards consideration, in that operation of the facility in accordance with the proposed amendment:
L Would not incohe a sigsificant increase in the pn>bability or consequences of an accident previously evaluated.
De only accident previously evahm i in the Updated Final Safety Analysis Report which involves the Spent Fuel Poolis the fte handling accident. Fuel assembly emichment is not a -
precursor to this accident. He isotopic inventory co smed in the fuel handling accident is not adversely effected by the decicase in enrichment of U435. Derefore, the proposed change to the Spent Fuel Pool enrichment limit does not imalve a significant increase m the probability or consequences of an accident previously evaluated.
- 2. Would not increase the possibihty of a new or different type of accident from any accident prcriously evaluated.
The proposed change to the allowed enrichment of fuel in the Spent Fuct Pool does not result in any change to the configuration or operation of the plant. Specifically, no new hardware is being added to the plant as a part of the proposed change nor are there significantly different types of operations being introduced, he only potential for a new type of accident lies in the area of accidental criticality. The Spent Fuel Pool maintains fuel in a suberitical condition with k effective less than 0.95 (no credit is taken for soluble boron being present in the pool). The required degree of suberiticality continues to be met at the new enrichment limit of 4.52 w/o U-235 which ensures an accidental criticality will not occur. Therefore, the proposed change to the Spent -
Fuel Pool enrichment limit does not create the possibility of a new or different type of accided from those previously evaluated.
- 3. Would not invah e a sipsificant reduction in the margin of safety.
The margin of safety maintained in the Spent Fuel Pool is the degree to which the fuel is maintained subcritical. The proposed change to the allowed enrichment of fuelin the Spent Fuel Pool will ensure that the margin of safety is maintained. The maximum multiplication factor for storing fuel assemblies with a 4.52 w/o U-235 is 0.95. The previously approved maximum multiplication factor for 5.0 w/o was 0.946. He new maximum multiplication factor does not represent a significant reduction in the margin of safety. Therefore, the proposed change to the Spent Fuel Pool enrichment limit does not involve a significant reduction in the margin of safety.
Based on the above, we have concluded that these changes do not constitute a significant hazard.
1
,, Document Control Desk Sepicmber 1, 692 Page 5 SCilEI)UI.E These changes are requested to be approved and issued by February 28,1993.
S4F1lIlCOMMl'ITEIMINIEW These changes to the Technical Specifications and our determination of significant hazards have been reviewed by our Plant Operations and Safety Review Committee and Off-Site Safety Review Committee. They have concluded that implementation of these changes will not result in an undue risk to the health and safety of the public.
Should you have any questions regarding this matter, we will be pleased to discuss them with you.
f rVery truly yourt;/
A STATE OF MARYLAND 2 TO WIT COUNTY OF CALVERT I hereby certify that on the f day of Seokmber .1992, before me, the subscriber, a Notary Public of the State of Maryland in' and for ('a loe4 Ocu d d ,
personally appeared George C. Creel, being duly sworn, and states that he is Vice P/esident of the Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he provides the foregoing response for the purposea 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 lland and NotarialScal: MNotary / he/
Public My Commission Expires: !u m 8, / N '
Date GCC/LMD/Imd/bjd/dtm Attachments: (1) Unit 1 Technical Specification Page (2) Unit 2 TechnicalSpecification Page (3)' Description of Analysis 1
_ _ _ _ _ . _ . _ _ _ . . . . . _ _ _ _ . _ _ _ _ _ _ . _ _ . . . _ -_.m______._.... . ...._ _ _ . _ _ . . .. ._
4
.. Document Control Desk
. September 1,1992 Page 6 cc: D. A. Brune, Esquire J. E. Silberg, Esqui:e it A. Capra, NRC D. O. McDonaki, Jr., N RC T. T. Martin, NRC P. R. Wilson, NRC F. L McLean, DNR j.11. Walter, PSC i
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4 4
SPENT FUEL POOL FLOOR l
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. FIGUltE (1)
CONCEl'TUAI. IlltAWING OF CitOSS SECilON OF SI'ENT FUEL IRACK POISON SHEET OUTER WALL
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p y INNER WALL ,
4 I 1
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