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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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n
. BALTIMORE GAS AND ELECTRIC CHARLES CENTER P. O. BOX 1475 BALTIMORE, MARYLAND 21203 I I
JOSEPH A.TIERNAN vice Passiotwv NucLEAn Ewenov l 1
September 25, 1987 l 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 Reauest for Amendment
REFERENCES:
(A) Setpoint Methodology Topical Report, CENPD-199-P, Rev.1-P- A.
(B) 48FRl4870, April 6,1983.
Gentlemen:
The Baltimore Gas and Electric Company hereby requ'sts an Amendment to its Operating License Nos. DPR-53 and DPR-69 for Calvert Cliffs Unit Nos.1 & 2, respectively, with the submittal of the proposed changes to the Technical Specifications.
CIIANGE (BG& E FCR 87-3003)
Change Figure 2.2- 1, 3.2-2, and 3.2-4 of the Unit I and Unit 2 Technical Specifications as shown on the marked-up copies attached to this transmittal. i l
LISCUSSION l This proposed change will revise the following Unit I and Unit 2 Technical Specification figures:
- 1. Figure 2.2-1 (Axial Power Distribution Trip Limiting Safety System Settings (APD LSSS)). This figure is associated with Technical Specification 2.2- 1 (Table 2.2- 1, item 8) and is widened in both the positive and negative directions below 70% power.
- 2. Figure 3.2-2 (Linear 11 eat Rate Axial Flux Offset Control Limits). This figure is associated with Technical Specification 3.2.1 (Linear lleat Rate Limiting Condition for Operation (L11R LCO) and is widened in the negative h direction below 50% power. /;A B710060094 B70925 00 PDR p
ADOCK 05000317 PDR
, g f d ,,
2
r Document Centrol Desk September 25, 1987 Page 2 L
- 3. Figure 3.2-4 (DNB Axial- Flux Offset Control Limits). Th*s ; figure is associated 'with Technical Specification 3.2.5 (DNB Limiting Condition for Operation (DNB LCO) and is widened in the negative direction below 50%
f power.
During plant startup, when power is below the APD trip bypass of 15% power, the measured Axial Shape Index (ASI) can be more negative than the current APD trip limit.
This is caused by xenon and reactivity feedback induced perturbations in the axial power shape associated with rapidly changing power and temperatures. Technical Specification 2.2-1 requires that the plant remain below 15% power until the ASI falls within the APD LSSS operating band, or the reactor will trip. An APD trip at this power level is not a safety concern, since the induced perturbations in the axial shape will usually dampen out before a significant power level is reached (i.e., in the 20-40% power range). In addition, at low power levels sufficient conservatism exists in the current APD LSSS, DNB LCO, and LHR LCO to permit relaxation of the ASI operatir.g bands without compromising any safety margin.
DETERMIN ATION OF SIGN!FICANT HAZARDS This proposed change has been evaluated against the standards in 10 CFR 50.92 and has been determined to involve no significant hazards considerations, in that operation of the facility in accordance with the proposed amendment would not:
(i) involve a significant increase in the probability or consequences of an accident previously evaluated; or The APD trip is not credited directly in any transient analysis for Calvert Cliffs Unit I and Unit 2 (i.e., its performance is not modeled). Instead the APD trip is cred:ted indirectly.
By virtue of the Setpoint methodology, the APD LSSS ensures that the Specified Acceptable Fuel Design Limit (SAFDL) on fuel centerline melt is not violated during certain Design Basis Events (DBE). A transient simulation is therefore not required except for those events which result in system changes not considered in the APD LSSS analysis (e.g., CEA drop which resr.its in a violation of the Power Dependent Insertion Limits, Technical Specification Figure 3.1 -2). The transient simulations determine the margin degradation for those events not covered and the corresponding Required Overpower Margin (ROPM) data to be factored into the Limiting Conditions for Operation. This methodology is described in Chapter 1 of Combustion Engineering's (C-E) approved setpoint methodology topical report, [Ref.
( A)]. Therefore, the proposed change to the APD LSSS will not impact the transient analyses of Chapter 14. ,
I At low power levels, the operating band set by the DNB LCO and LHR LCO is I credited, at zero power conditions, in the following accident analyses:
- 1. Control Element Assembly (CEA) Withdrawal,
- 2. Excess Load, and
- 3. CEA Ejection.
The CEA Ejection analysis considers axial shapes of positive ASI values.
Since no changes are proposed in the positive ASI region of the LCOs, the
l Document Control Desk l ' September 25, 1987 Page 3 l
CEA E.iection event will not be affected. Thus, the proposed changes will l only affect the CEA Withdrawal and Excess Load events.
L An evaluation of the CEA Withdrawal and Excess Lsad analyses showed that the proposed changes will make the transient minimum DNBR more limiting.
However, the impact is very small and the current minimum DNBR values are high enough for these events that the DNBR design limits will not be violated. Therefore, the proposed changes to the DNB LCO and LHR LCO do not significantly impact the Unit 1 Cycle 9 and Unit 2 Cycle 8 transient analyses.
(ii) create the possibility of a new or different type of accident from any accident previously evaluated; or The proposed changes to the APD LSSS, DNB LCO, and LHR LCO do not result in any change in the configuration of the plant, equipment design or equipment used nor does it require any changes in the accident analysis methodology.
Therefore, the proposed changes will not create the possibility of a new or different kind of accident from any accident previously evaluated.
(iii) involve a significant reduction in a margin of safety.
1 The proposed changes were evaluated for potential impact on the following items:
- a. The margin to fuel centerline melt limits
- b. The margin to DNB limits
- c. The margin to the LOCA peak linear heat rate limits j
- d. The core power versus planar radial peaking factor LCO 1 (Technical Specification Figure 3.2-3a) I
- e. The Thermal Margin / Low Pressure LSSS (Technical Specification Figures 2.2-2 and 2.2-3) 1
- f. The core power versus integrated radial peaking factor LCO !
(Technical Specification Figure 3.2-3c) j l
The evaluation of each of these items is discussed below.
- a. Marcin to Fuel Centerline Melt Limits An evaluation of the Calvert Cliffs Unit i Cycle 9 and Unit 2 Cyde 8 APD LSSS analysis was performed. This evaluation showed that at pov er levels less than 70 % of rated power there exists sufficient conservatism in the current APD LSSS to accomodate the proposed change.
The proposed change still contains sufficient margin to the current i fuel centerline melt safety limits. Therefore, the proposed change I does not significantly impact the margin to the fuel centerline melt limits. l
- b. Marcin to DNB L.imits An evaluation of the Calvert Cliffs Unit 1 Cycle 9 and Unit 2 Cycle 8 i DNB LCO enalysis was performed. This evaluation showed that at power i l
)
J
(
Document Control Desk September 25, 1987 Page 4 levels less than 50 % of rated power there exists sufficient conservatism in the current DNB LCO to accomodate the proposed change.
The proposed change still contains sufficient margin to the current DNB safety limits. Therefore, the proposed change does not significantly impact the margin to the DNB limits.
- c. Marcin to the LOCA Peak Linear Heat Rate Limits An evaluation of the Calvert Cliffs Unit ! Cycle 9 and Unit 2 Cycle 8 LliR LCO analysis was performed. This evaluation showed that at power levels less than 50 % of rated power there exists sufficient conservatism in the current LIIR LCO to accomodate the proposed change.
The proposed change still contains sufficient margin to the current LOCA peak linear heat rate limits. Therefore, the proposed change does not significantly impact the margin to the LOCA peak linear heat rate limits,
- d. Core Power Versus Planar Radial Peakinn Factor LCO The core power versus planar radial peaking factor tradeoff curve ensures that the APD LSSS remains conservative if the measured unrodded planar radial peaking factor is greater than the Technical Specification limit of 1.70. This limit curve was reanalyzed using the proposed APD LSSS changes. The results showed that there is no impact on the Unit 1 Cycle 9 and Unit 2 Cycle 8 tradeoff curves,
- c. Thermal Marcin/ Low Pressure LSSS The Calvert Cliffs Unit I Cycle 9 and Unit 2 Cycle 8 Thermal Margin / Low Pressure LSSS was reanalyzed because the APD LSSS is credited in that analysis. This analysis was performed using the proposed APD LSSS changes. The results showed that there is no impact on the Thermal Margin / Low Pressure LSSS.
- f. Core Power Versus Intenrated Radial Peakinn Factor LCO The Calvert Cliffs Unit 1 Cycle 9 and Unit 2 Cycle 8 core power versus integrated radial peaking factor tradeoff curve was reanalyzed because the APD LSSS and DNB LCO are credited in that analysis. This analysis was performed using the proposed APD LSSS and DNB LCO changes. The results showed that there is no impact on the tradeoff curves.
The methodology used in the safety evaluation is found in C-E's approved setpoint methodology topical report [ Reference ( A)].
The Commission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists by providing certain examples of amendments that are considered least likely to involve significant hazards considerations (Reference (B)]. The proposed changes are most like example (vi) because the proposed changes will allow an expanded operating envelope for ASI at low power levels; however, the results of the changes are clearly within all acceptable criteria.
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. Document Control Desk September 25, 1987 Page 5 Therefore, based on the above considerations, BG&E has -determined that this change does not involve a significant hazards consideration.
E6FETYCOMMITTEE REVIEW These proposed' changes to the Technical Specifications and our determination of significant hazards have been reviewed by our Plant Operations and Off-Site Safety Review Committees, and they have concluded that implementation of these changes will not result in an undue risk to the health and safety of the public.
FEE DETERMINATION Pursuant to 10 CFR 170.21, we are including BG&E Check No. ( 1912793 )
in the amount of $150.00 to the NRC to cover the application fee for this request.
Very truly yours, STATE OF MARYLAND :
- TO WIT:
COUNTYOFCALVERT :
Joseph A. Tiernan, being duly sworn states that he is Vice President of 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 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 Notarial Seal: >W C 0 Notary Public My Commission Expires: ph h /j/998 V ( B 7[W 3t4) M / 7 8 7 Date JAT/JES/Imt Attachments cc: D. A. Brune, Esquire J. E. Silberg, Esquire R. A.Capra,NRC S. A.McNeil, NRC W. T. Russell, NRC T. Foley/D. C. Trimble, NRC T. Magette, DNR