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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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83 ALTIMORC ,
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GAS AND '
ELECTRIC I i 1650 cal. VERT CUFFS PARKWAY
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March 15,1992 U. S. Nuclear Regulatory Commission Washington, DC 2P55 ATTENTION: Document Control Desk SUWECT: Calver? Cliffs Nuclear Power Plant Unit No. 2: Docket No. 50-318 Btquest for EmcIgency License AmendmengEylveillance lleauhrJDals Gentlemen:
llattimore Gas and Electric Company (llG&E) hereby requests an 1;mergency Amendment to its Operating License No. DPR-69 for Calvert Cliffs Unit No. 2, to allow operation of Unit 2 after completion of modifications to the Containment Spray System. the lodine Removal System, and the Containment Cooling System. Dese modifications will change the type of Engineered Safety Features Actuation System (ESFAS) signal that starts these systems. Accordmgly, we request a change to the surveillance requirements which addresses the ESFAS signals to these systems, pursuant to 10 CFR 50.90.
I)ESCHIPTION During the ongoing Electrical Distribution System Functional Inspection (EDSFI), an unusual , and highly improbabic, accident scenario was identified which has the potentiel to adversely impact the operation of our onsite electrical distribution rystem during a loss of offsite power. Specihcally, it could have resulted in greater than expected voltage drops at the Emergency Diesel Generators (EDG), which could have imparted the proper operation of some engineered safety features in the interest of safety, all of the EDGs were declared inoperable and both Units were subsequently shet down. Unit I has cetered a scheduled refueling outage. Modifications are being performed to clitninnte the possibility of an execssive voltage drop at the EDGs. These modifications will result in changes to the ESFAS signals sup, lied to some equipment and will require changes to the .
surveillance requirements for this equ pment.
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i Document Control Deck March 25,1W2
.. Page 2 llACKGHOUNJ)
During accident conditions accompanied by a toss of offsite power, the EDO sequencers will automatically load the EDOs in a controlled manner. The sequencer initielly bk) cts the Safety injection Actuation Signal (SIAS) and Containment Spray Actuation Signal (CSAS) to the equipment to be sequenced and then unbh>cks thesc signals m controlled steps. Engineered Safety features equipment requires two different signals to start; an accident response signal (SIAS, CSAS.
etc.) and a permissive signal fmm the EDO sequencer. His unblocking is the permissive signal from the sequencer, which by itself will not stait the equipment. %c equipment must hase on additional signal (SIAS, CSAS, etc.) to start. Because the loss of coolant incid ent (LOCl) sequencer is ini,iated upon receipt of a SIAS, equipment w hich is also started on a Sl AS signal will receive both signals and i start as soon as the sequencer unblocks it. Ilowever, some equipment does not start upon receipt of l a SIAS and must have an a.iditional signal present to start. Bota the Containment Spray System and I the Containment Cooling System must also receive a CSAS in order to start after the sequencer unblocks it. He lodine Removal System requires a Containment isolation Signal (CIS) to start after l the sequencer unblocks it. These additions'algnals may not be present at the time the SIAS actuates l became of their differem initiation setpoints. %c additional signals add an clement of uncertainty to the acwal start time of this equipment. nis uncertainty couhl lead to a situation whcce equipment which is assumed to start at sequencer step 3 is not started until sequencer step 7, which could lead to the simultaneous starting of the equipment from two different steps. This could cause low voltage conditions in the electn .al distribution system and prevent safety equipment from operating properly.
To climinate the unecriainty associated with the equipment start t ime, a modification is being performed which will change the start signals of the containment spray pumps, the containment cooler fans and the iodine removal units. After the modiGeations are performed, these cornponents will receive their start signals from a SI AS only.
}{JMESTED CllANGE nc Technical Specifications for this equipment specifies which ESFAS signal must be used to test the equipment during refueling intervals. The proposed changes to the Technical Speci0 cations will change the specific signal name to a requirement that the equipment be tested utilizing "the appropriate ESFAS test signal". The affected Technical Specifications are: 4.6.2.1.b.1,4.6.2.1.b.2, 4.6.2.2.b, and 4.6.3.1.d.2.
The Technical Speci0 cation changes being requested are similar for the four affected Technical Specifications. Technical Speci0 cation 4.6.2.1.b.1 and 2 address some of the surveillance requirements for the Containment Spray System. %c Technical Specification requires that, *. . .
cach automatic valve in the now path actuates to its correct position on Safety injection Actuation test signal." We propose to change the Technical Specification to, ". . . each automatic valve la the Dow W ; duates <a fis correct position on the appropriate ESFAS test signal." The containment spc y hwp turycinance currently requires that the spray pump start automatically on a containment
& 'rk. on test signal. Similar wording has been proposed to require that the spray pump start
-auc #n oy on receipt of the appropriate ESFAS test $;gnal. Simi!arly, Technical SpechWon 4.6.2.2.b addresses the start signals required by the contamment cooling units. %c propowd change would replace the specific signal name with the generie wording described above.
Technical Specification 4.6.3.1.d.2 addresses the surveillance testing for the iodine removal units. It L
requires that the Glter trains start upon receipt of a containment isolation test signal. We are ll proposing to change the wording of the surveillance to climinate the reference to a particular ESFAS test signal and s**ute the generic wording proposed above.
Document Control Desk March 25, IW2
, Page 3 FAI tilY AN4lNSISl.lWIIIKMIDE 1he function of the Containment Spray System is to limit the rise in containment atmosphere pressure and temperature after an accident, and thus reduce the possibility of leakage of air mrne radioacthity to the outside environment. As currently designed, the containment spray pumps are started by a CSAS. in prevent an inadvertent actuation of containment spray in the case of an undesired CSAS, the containment spray valves are opened only by a SlAS. 'the modiGeation that will be performed will reverse this arrangement of signals and equipment; the containment spray pumps will start on a SIAS and the containment spray valves will open on a CSAS. The containment pressure setpoint for a CSAS is 4.25 psig, while the pressure setpoint for a SIAS is 2.8 psig. By changing the signals on the containment spray pumps, the containment spray pumps would be started
~
at the lower set 1 mint pressure. 1he containment pressure / temperature resp (mse to a Loss of-Coolant Accident (LOCA), as calculated for Updated Final Safety Analysis Report (UFSAR)
Section 14.20 is unchanged by this modification because containment spray is assumed to commence 60 seconds after pressure in the contallment reaches 4.75 psig. 'the opening of the containrnent spray valves on a CSAS enn.res that initiation of containment spray is still tmunded by the UFSAR analyses. The function of the containment spray system is unchanged. Because the start signals for the containment spray pumps and valves have been changed, a change to the surveillance requirements which desenbe the test signals for these components is necessary.
1he function of the containment Air Cooling System is to limit the containment atmosphere pressure and temperature after an accident, and thus reduce the possibility ofleakage of airtorne radioactivity to the outside environment. As currently designed, the air cooler fans receive their low speed start signal from CSAS. Additionally, the semce water outlet valves for the air coolers open upon receipt of a CSAS. A modincation is being performed which will replace the CSAS start signals with a SlAS start signal. Because SIAS is actuated before CSAS on high containment pressure (2.8 psig versus 4.25 psig), the air coolers wuuld start sooner in a pressuritation transient than previously assumed.
1here is no detrimental ciTect to starting the air coolers earlier in a transient and it would have no impact on long term containment response. Because the start signal for the containment air coolers t has been modiGed, a change to the surveillance requirements which address the test signals for the air coolers is necessary.
1hc iodine removal units are designed to collect the iodine which could be released into the containment atmosphere following a postulated accident. 1he fans would start on a CIS in the current design. As in the systems described above, the fan start signalis being changed from a CIS to a SIAS. Although toth CIS and SIAS are actuated at a containment pressure of 2.8 psig, SIAS can also be actuated by a low pressurizer pressure condhion. Ily switching the signal from CIS to SlAS, the iodine removal units might be actuated during an event which did not result in containment pressurization. 1here is no detrimental effect to operating the lodine removal units during a transient in which they might not be needed. The effectiveness of the charcoal is tested after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of operation to ensure that they still retain the capacity for iodine removal assumed in the accident analyses. Because the start signal for the iodine removal units has been changed, a change to the surveillance requirement which addresses the test signal for the iodine removal units is necessary.
Other systems are being similarly modified, however, tt.cre is no impact on the Technical Specifications from these additional modiGeations.
Document Control Desk March 25,1992 ;
, Page 4 ;
l DLTERMINK110N OF NQ SIGNIFICANT 1147d}1113 l
This propsed change has been evaluated agalmt the standards in 10 CFR 50.92 and has been '
determined to involve no sigt.ificant haards considerations, in that operation of the facility in accordance with the proposed amendrnent wuu!d not:
- 1. involve a significant increase in the probability or consequences of an accident previously evaluated;or The changes to the surveillance acquirements associated with the Containment Spray System, the Containment Cooling System and the lodine Reinoval System rencet the changes made to the Engineered Safety Features Actuation System (ESFAS) signals that this equipment receives. The proposed changes will ensure that the equipment continues to be tested in a manner consistent with its safety function by verifying that the equipment resgxmds as required to the a?propriate ESFAS signal. Therefore, there has been no increase in the probabiity or consequences of a previously evaluated accident.
- 2. crrate the possibility of a new or different type of accidentfrom any accidentpreviously evaluated; or The change in test signal requirements reDects the change made to the ESFAS signals received by the equipment. No new test requirernents have been added, nor have any been deleted.1he equipment will not be tested in a manner different than the existing test requirementt 1herefore, the possibility of a new os different type of accident from any previously evaluated has not been created.
- 3. involve a significant reduction in a margin ofsafety.
The proposed Technical Specification changes ensure that the affected equipment i will continue to be tested in a manner consistent with its safety function. No additional requirements are being proposed and no existing testing requirements are being rc:noved, Therefore, there is no seduction in the margin of safety assoela9 d with these testing requirements.
STATEMENT OF_131ERGEN_GY CIRC 11MSTANCljj The Technical Specifications, unless amended, would prevent Unit 2 from start!ng up on schedule, ncicfore, we request that this amendment be treated as an emergency change. This situation occurred as the result of our evaluation of the icsponse of the onsite electrical distribution mtem to a specific accident scenario. During that evaluation, we determined that the electricsl distribution system may not have functioned properly, ihus preventing safety equipment from functioning -
properly. In response, we are undertaking improvements to the onsite c!cctrical distribution system so that it would function properly during this specific accident scenario, These modifications will change the actuation signal for several engineered safety features resuhing in a coricsponding change in the Technical Specification surveillance requirements. This situation could not have been avoided because it is based on an unusual and highly improbabic scenario. Application for an amendment was made as soon as possible after the need was identified.
4 Document Control Desk March 25,1992
, . 'Page5 l
Unit 2 is currently in a forced outage to perform improvements to the electrical distribution system.
Following the modifications, the Containment Spray System, the Containment Cooling System and the lodine Removal System will be considered inoperable because of their inability to satisfy Surveillance Requirernents 4.6.2.1.b.1,4.6.2.1.b.2,4.6.2.2.b, and 4.6.3.1.d.2, respectively, railute te satisfy these requirements would prohibit a Mode change.
i l
sal IslY CON 1M11 TEE REVil3V These proposed 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, and :y have concluded that implementation of these changes will not result in '
an undue risk to the heak nd safety of the public.
Should you have any questions regarding tHs matter, we will be pleased to discuss them with you.
Very truly nuts, O
(/ ,
STATE OF MARYLAND t TO WIT COUNTY OF CALVERT t 92, before me, the .ubscriber, a Notary Public of the I hereby State of Maiylandecrtify that on for in and the(42 25th 1ay hurf, L of March,1]4zMG t - appeared George C.
, personally Creel, being duly sworn, and states that he is Vice PresR!cnt of the Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he provides the foregoing response for the 3urposes therein set forth; that the statements made are true and correct to the best of his
. cnowledge,information, and belief; and that he was authoriicd to provide the response on behalf of said Corporation.
W11NE90 my lland and Notarial Seah /. AMM c Notary Public d My Commission Expires: h 1 N Date '? b b
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GCC/ PSF / psf / dim Attachments
4 Document Control Desk March 25, lW2
. Pagc 6 cc: D. A. Isrune, Paquire J. E. Silberg, F2 quire R. A. Capta, NRC D. G. Mcdonald, Jr., NRC T.T. Martin, NRC L 11 Nicholson, NRC R.1. M"'.can. DNR J.11. Walter. PSC M'
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