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MONTHYEARML20095L0071992-05-0101 May 1992 Application for Amend to License DPR-53,allowing Plant Operation After Completion of Mods Currently Being Developed to Containment Spray Sys,Iodine Removal Sys & Containment Cooling Sys Project stage: Request 1992-05-01
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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
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BAtTlMORE GAS AND ELECTRIC 1650 CALVERT CUFFS PARKWAY
- LUSBY, MARYLAND 20657-4702 GEORot C CREEL Van PRESIDCNT Nuc.t A R DdROY (4to) aeo444ss May 1,1992 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit No.1; Docket No. 50-317 Reonest for License Amendment: Surveillance Requirements
REFERENCES:
(a) Letter from Mr. G. C. Creel (BG&E) to Document Control Desk (NRC), dated March 25,1992, " Request for Emergency License Amendment: Surveillance Requiremer.ts' (b) Letter from Mr. D. G. Mcdonald (NRC) to Mr. G. C. Creel (BG&E), dated March 27, 1992, Issuance of Unit 2 Emergency Amendment No.148 (TAC No. M83005)
Gentlemen:
Baltimore Gas and Electric Company (BG&E) hereby requests an Amendment to its Operating I.icense No. DPR-53 for Calvert Cliffs Unit No.1, to allow operation of Unit I after completion of modifications currently being developed to the Containment Spray System, the Iodine Removal System, and the Containment Cooling System. These planned modifications will change the type of Engineered Salety Features Actuation System (ESFAS) signal that starts these systems. Accordingly, we request a change to the surveillance requirements which addresses the ESFAS signals to these systems, pursuar.t to 10 CFR 50.90. This request is identical to the request made for Unit 2 in Reference (a) and which was approved in Reference (b).
DESCRIPTION During the recent Electrical Distribution SysNm Functional Inspection (EDSFI), an unusual , and highly improbable, accident scenario was identified which has the potential to adversely impact the operation of our onsite electrical distribution system during a loss of offsite power. Specifically, it could have resulted in greater than expected voltage drops at the Emergency Diesel Generators (EDG), which could base impacteel the proper operation of some engineered safety features. In the imerest of safety, all of the EDGs were declared inoperable ar. I both Units were subsequently shut down. Unit 1 entered a scheduled refueling outage. Modifications are being planned to climinate
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Document Control Desk May 1,1992 Page 2 the possibility of an excessive voltage drop at the EDGs. When complete, these modifications will result in changes to the ESFAS signals supplied to some equipment and will require changes to the surveillance requirements for this equipment.
IIACKG[4UND During accident conditions accompt.nied by a loss of offsite power, the EDG sequencers will automatically load the EDGs in a controlled manner. The sequencer initially blocks she Safety Injection Actuation Signal (SIAS) and Containment Spray Actuation Signal (CSAS) to the equipment to be sequenced and then unblocks these signals in controlled steps. Engineered Safety features equipment requires two different signals to start; an accident response signal (SIAS, CSAS, etc.) and a permissive signal from the EDG sequencer. This unblocking is the permissive signal from the sequencer, which by itself will not start the equipment. The equipment must have an additional signal (SIAS, CSAS, etc.) to start. Because the Loss-of-Coolant incident (LOCl) sequencer is initiated upon receipt of a SIAS, equipment which is also started on a SIAS signal will receive both signals and start as soon as the sequencer .mblocks it. However, some equipment does not start upon receipt of a SIAS and must have an additional signal present to start. Both the Containment Spray System and the Containment Cooling System must also receive a CSAS in order to start after the sequencer unblocks it. The lodine Removal System requires a Containment Isolation Signal (CIS) to start after the sequencer unblocks it. These additional signals may not be I. resent at the time the SIAS actuates because of their differen, initiation setpoints. The additional signals add an element of uncertainty to the actual start time of this equipment. This uncertainty could lead to a situation where equipment which is assumed, for example, to start at sequencer Step 3 is not started until sequencer Step 6, which could lead to the simultaneous starting of the equipment from two different steps. This could cause low voltage conditions in the electrical distribution system and prevent safety equipment from operating properly.
To eliminate the uncertainty associated with the equipment start time, a modification is being planned which will change the start signals of the containment spray pumps, the containment cooler fans and the iodine removal units. After the modifications are performed, this equipment will receive their start signals from a SIAS.
IEG ' STED CllANGE The 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 Specifications 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.l.b.1, 4.6.2.1.b.2, 4.6.2.2.b, and 4.6.3.1.d.2.
The Technical Specification changes being requested are similar for the four affected Technical Specifications. Te:hnical Specification 4.6.2.1.b.1 and 2 address some of the surveillance requirements for the Containment Spray System. The Technical Specification requires that, ". . .
cach automatic valve in the flow path actuates to its correct position on Safety Injection Actuation test signal." We propose to change the Technical Specification to, ". . . each automatic valve in the flow path actuates to its carrect position on the appropriate ESFAS test signal? The containment spray pmp smeillance currently requires that the spray pump start automatically on a containmet..
spray actuation test signal. Similar wording has been proposed to require that the spray pump start autornatically on receipt of the appropriate ESFAS test signal. SNilarly, Technical I
l
L .
Document Control Desk May 1,1992 -
Page 3 Specification 4.6.2.2.b addresses the start signals required by the containment cool:ng units. The proposed change would replace the specific signal name with the generic wording described above.
Technical Specification 4.63.1.d.2 addresses the surveillance testing for the iodine removal units. It requires that the filter trains start upon receipt of a centainment isolation test signal. We are proposing to change the wording of the surveillance to eliminate the reference to a particular ESFAS test signal and substitute the generic wording proposed above.
SAFITIY ANALYSIS /JUSTIl3 CATION The 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 airborne radioactivity to the outside environment. As currently designed, the containment spray pumps are started by a CSAS. To prevent an inadvertent actuation of containment spray in the case of an undesired CSAS, the containment spray valves are opened only by a SIAS. The modification that is being planned d reverse this arrangement of signals and equipment; the containment spray pumps wlll start on a SIAS and the containment spray valves will open on a CSAS. %e containment prusure setpoint for a CSAS is 4 25 psig, while the pressure setpoint fcr 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 setpoint pressure. The containment pressure / temperature response 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 cantainment reaches 4.75 psig. The onening of the containment spray valves on a CSAS ensures that initiation of containment spray is still bounded by the UFSAR analyses. Because the start signals for the containment spray pumps and valves have been changed, a change to the surveillance requirements whicl, describe the test signals for these components is necessary.
The function of the Containment Air Cooling System is to limit the containment atmosphere pressure and temperature after an accident, and thus reduce the possibility of leakage of airborne radioactivity to the outside environment. As currently designed, the air cooler fans receive their low speed start signal from CSAS. Addition _Ily, the ser ice water outlet valves for the air coolers open upon receipt of a CSAS. A modification is being planned which will replace the CSAS start signals with a SIAS start signal. Because SIAS is actuated before CSAS on high containment pressure (2.8 psig versus 4.25 psig), the air coolers would start sooner in a pressurization transient than previously assumed. There is no dctrimental effect 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 will be modified, a change to the suivcillance requirements which address the test signals for the air coolers is necessary.
The iodine removal units are designed to colleet the iodine which could be released into the containment atmosphere following a postulated accident. The fans would start on a CIS in the current design. As in the systems described above, the planned modification will change the fan start signal from a CIS to a SIAS. Although both CIS and SIAS are actuated at a containment pressure of 2.8 psig. SIAS can also be actuated by a low pressurizer pressure condition. By switching the signal from CIS to SIAS, the iodine removal units might be actuated during an event which did not result in containment pressurization. There is no detrimental effect to operating the iodine 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 removai units will be
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Document Control Desk May 1,1992 Page 4 changed, a change to the surveillance requirement which addresses the test signal for the iodine removal units is necessary.
Other systems may be similarly modified, however, there is no impact on the Technical Specifications from these planned modifications.
DETERMINATION OF NO SIGNIFICANT llAZARDS 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:
(1). involve a significant increase in the probability or consequences of an accident previously evaluated; or The planned modifications to the start signals received by some engineered safety features equipment will maintain the loading of that equipment within the timing steps assumed by the EDG sequencer design . The EDG sequencers will continue to +
perform their function as described in the Updated Final Safety Analysis Report (UFSAR). The modified systems will continue to function so that they meet the assumptions of the accident analyses in Section 14 of the UFSAR. Therefore, there has been no significant increase in the probability or consequences of a previously evaluated accident.
(2) create the possibility of a new or different type of accident from any accident previously evaluated; or The planned modifications to the start signal to seiected Engineered Safety Features Actuation System (ESFAS) components does not create the possibility of a new or different type of accident from any presiously evaluated. Changing the Containment Spray Actuation Signal (CSAS) start to a Safety Injection Actuation Signal (SIAS) start will allow the containment spray pumps to start, the containment cooler fans to start in low speed, and the sersice water outlet valves to open during an event that does not cause a high pressure condition in containment. Operating the pumps, fans.
and valves during an event that does not cause a high pressure condition in containment will add a load to the EDGs that was not considered for these events.
However, this additional load is within the capacity of the EDGs because the EDG capacity is based on events where this equipment is assumed to operate.
When the planned modifications are complete, the containment spray valves will open on a CSAS instead of SIAS. Therefore, the valves will open after the pumps have started and only when containment pressure is high enough to warrant the use of containment sprays. Operating the containment spray pumps with these valves closed is accommodated by the existing recirculation lines for the pumps. The containment spray piping will be evaluated to determine if it can withstand the loads associated with opening the valve after the pump had been started and any necessary modifications performed. By reversing the signals to the containment spray pumps and valves, the system will continue to function as designrd and an inadvertent spray down of containment will be avoided.
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. Document Control Desk May 1,1992 Page5 Under the planned modification, the start signal for the iodine removal units will be changed from Containment Isolation Signal (CIS) to SI AS. This will allow the iodine removal units to start during events which may not cause a high pressure condition in containment. Operating the iodine removal units in an event that does not cause a high pressure condition will add a load to the EDGs that was not considered for those events. This additional load is within the capacity of the EDGs because EDO capacity is determined by events where this equipment is assumed to operate.
Under the planned modifications, these systems will continue to operate in ways that have been previously analyzed. The containment cooling units and the iodine removal units could begin functioning sooner in the accident scenario than assumed by the accident analyses or could function during accid"nts where its function was not -
assumed to occur. Operation of this equipment in this manner will not have a detrimental effect on the containment structure. Both the containment cooling units and the iodine removal units are used in routine operation to maintain ccmtainment temperature within its limits during normal operation and to speed the cleanup of the g containment atmosphere during a shutdown. Q Therefore, the proposed changes to the Technical Specifications do not create the ,
possibility of a new or different type of accident previously evaluated.
(3) involve a significant reduction in a margin ofsafety.
The margin of safety is not reduced by the planned modifications to the start signals of the engineered safety features described above. The functions of each system continue to meet the accident assumptions stated in UFSAR Section 14. The planned modifications will ensure that the EDGs continue to perform their function as described in the UFSAR. Thus , all the accident analyses will remain valid and the proposed changes to the Technical Specifications do not involve a sign;ficant reduction in the margin of safety.
SCllEDULE
. Unit 1 i3 currently in a scheduled refueling outage. Following the planned 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 Requirements 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. Failure to satisfy these requirements will prohibit entering into Mode 4. Mode 4 entry is currently scheduled for June 24,1992. Therefore, we request approval of these proposed Technical Specification changes by June 22,1992.
. Document Control Desk May 1,1992 i Page 6 sal'lflT COMMITI'EE REV1EW These proposed changes to the Technical Specif: cations and our determination of significant hazards have been reviewed by our Plant Operations and Safety Review Committee and Off-Site Safety Review Committee, and they have concluded that implementation of these changes will not result in an unde: 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.
Very truly yours,
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STATE OF MARYLAND :
- TO WIT :
COUNTY OF CALVERT :
,3 .
I hereby certify that on the bl day of i i /W '/,191 Abefp're me, the subscriber, a Notary Public of the State of Maryland in and for / (G ' T h 64 personally appeared George C. Crect, being duly sworn, and states that he is Vice President of the Baltimore Gas and Electric Company, a corporation of the State of Maryland; thaf 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.
./ i : .
!In i ln j ~/ l ( h.#k WITNESS my Hand and Notarial Scal:
[] Notary Public mcmmewNmW erM.W My Commission Expires:
Date GCC/ PSF / psf / dim cc: D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC D. G. Mcdonald, Jr., NRC T. T. Marti 3, NRC L E. Nicholson, NRC R. I. mci.can, DNR J. H. Walter, PSC
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