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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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- i BALTIMORE GAS AND i ELECTRIC CHARLES CENTER
- P.O. BOX 1475 BALTIMORE, MARYLAND 21203 CHRis H. POINDEXTER VICE PRESIDENT ENGINEERING AND CO**STRUCTION June 28,1985 U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 ATTENTION: Mr. Edward 3. Butcher, Jr., Chief Operating Reactors Branch #3 Division of Licensing
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Request for Amendment
REFERENCES:
(a) BG&E letter from Mr. A. E. Lundvall, Jr., to Mr. R. A. Clark, dated December 7,1981 (b) BG&E letter from Mr. A. E. Lundvall, Jr., to Mr. R. A. Clark, dated September 22,1982 (c) I&E Inspection Report 50-317/85-09; 50-318/85-09 (d) Letter from Mr. R. A. Clck, NRC, to Mr. A. E. Lundvall, Jr, BG&E, dated October 24, 1930, Order for Modification of License, Environmental Qualification Gentlemen:
The Baltimore Gas and Electric Company hereby requests an Amendment to its Operating License Nos. DPR-53 and DPR-69 for Calvert Cliffs Unit Nos.1 & 2, respectively, with the submittal of the proposed changes to the Technical Specifications.
CHANGE NO.1 (BG&E FCR 85-32)
Change pages 3/4 3-13 and 3/4 6-25 of the Unit Nos. I and 2 Technical Specifications as shown on the marked-up copies attached to this transmittal.
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June 28,1985 Page 2 DISCUSSION This proposed change deletes reference to the Containment Purge Isolation Valves' MODE 5 applicability in OPERABILITY Table 3.3-3 of the Engineering Safety Feature Actuation System Instrumentation Technical Specification. Also, in order to provide consistency, we propose to similarly delete reference to the MODE 5 applicability of the Containment Purge Isolation Valve isolation times of OPERABILITY Table 3.6-1, Containment Isolation Valves.
By an earlier application for license amendment, reference (a), we requested and received approval to maintain the purge air inlet and exhaust isolation valves in the closed position during plant operation. Technical Specification 3.6.1.7 now requires that the purge supply and exhaust valves be maintained closed, with the air to the air operator isolated and the solenoid air supply valve deenergized in MODES 1-4. Coincident with this change, the " applicable modes" of the manual containment purge valves isolation (TS Table 3.3-3) were changed to provide operational requirement consistency. MODE 5 applicability was unnecessarily added to the table. This error was complicated by a later application for license amendment, reference (b), that instituted a containment purge isolation valve seal replacement program. This program necessitates " tagging-out" the purge valve control switches during MODE 5 seal replacement. Therefore, this proposed change corrects the current discrepancy by removing the inconsistent containment purge valve MODE 5 OPERABILITY requirement.
DETERMINATION OF SIGNIFICANT HAZARDS CONSIDERATIONS 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 any increase in the probability or consequence of any accident previously evaluated in the Updated Final Safety Analysis Report.
Containment Integrity is only required in MODES 1-4. Additionally, during core alterations or movement of irradiated fuel within the containment, the status of the containment penetrations is closely maintained. A review of the accidents analyzed in the Updated Final Safety Analysis Report revealed no accidents which would require isolation of the containment purge valves in MODE 5.
(ii) Create the possibility of a new or different type of accident from any accident previously evaluated.
No new equipment, system alignments beyond those previously bounded by current Technical Specifications, or accident analyses are involved in the proposed change.
(iii) involve a significant reduction in the margin of safety.
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Mr. E. 3. Butcher, Jr.
June 28,1985 Page 3 The bases for the appropriate Technical Specifications are not being altered. This proposed change only corrects a current Technical Specification discrepancy.
CHANGE NO. 2 (BG&E FCR's 85-1008 & 85-1013)
Change page 3/4 8-10 of the Unit 1 and 2 Technical Specifications as shown on the marked-up copies attached to this transmittal.
DISCUSSION This proposal (FCR 85-1008) would change the Battery Service Test, surveillance 4.8.2.3.2.d.2, for 125-volt DC Batteries 12 and 22 to reflect their updated design load cycle. A review of the emergency loads supplied by 125-volt DC Batteries 12 and 22 for the design load cycle (two hour discharge caused by a LOCI on Unit I and simultaneous undervoltage on Units 1 and 2) has been conducted. The updated design load cycle is determined to be greater than the simulated or " dummy" loads currently used for 125-volt Batteries 12 and 22 during the Battery Service Test performed every 18 months. A safety analysis has been completed which verifies that 125-volt DC Batteries 12 and 22 have ample capacity to supply power for the updated design load cycle. A review of the design load cycle for 125-volt Batteries 11 and 21 is currently in progress, however,it is not anticipated that the result of this review will be larger than the dummy loads currently used during their Battery Service Tests.
This proposal (FCR 85-1013) would also increase the battery terminal voltage required to be maintained during the Battery Service Test for all of the 125-volt DC Batteries from 100 volts to 105 volts. 105 volts is required for OPERABILITY of the emergency loads supplied by the batteries. Battery terminal voltage has not decreased below 105 volts during any previous performance of this surveillance. A safety analysis has been conducted which verifies that all 125-volt DC Batteries have adequate capacity to supply the emergency loads for the design load cycle while maintaining battery terminal voltage at least 105 volts.
DETERMINATION OF SIGNIFICANT HAZARDS CONSIDERATIONS This proposal has been reviewed against the standards set forth 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 (11) create the possibility of a new or different kind of accident from any accident previously evaluated; or (iii) involve a significant reduction in a margin of safety.
_ _ __ A
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. ~:4 Mr. E. J. Butcher, Jr.
June 28,1985 Page 4 The proposed change would increase the amperes drawn by 125-volt DC Batteries 12 and 22 and increase the minimum terminal voltage to be maintained by all 125-volt DC Batteries during the performance of the Battery Service Test every 18 months. Thio change would make the surveillance more stringent and, therefore, the probability or consequences of an accident previously evaluated would not be increased and no margin of safety would be reduced.
This proposal would not modify equipment or change system alignments. The procedural change involved would not create the possibility of a new or different accident.
CHANGE NO. 3 (BG&E FCR 85-31)
Change page 3/4 9-4 of the Unit I and 2 Technical Specifications as shown on the marked-up copies attached to this transmittal.
DISCUSSION This proposed change to the Technical Specifications is being processed in response to Reference (c), Unresolved Item 317/85-09-03, concerning use of the temporary closure device as an acceptable replacement for the emergency escape hatch airlock door.
Facility Change Request (FCR)83-103 designed and analyzed a temporary closure device with penetrations to be installed on the emergency personnel escape hatch to facilitate work inside containment during core alterations or movement of irrradiated fuel within the containment. The supporting Safety Analyses determined that the temporary closure device penetrations will prevent direct access from the containment atmosphere to the outside atmosphere. The Technical Specification bases 3/4.9.4 states that there is a lack of containment pressurization potential while in the refueling mode. Thus, the most limiting case of release of radioactivity that could occur during refueling is through a fuel handling incident. This incident, analyzed in the Updated FSAR section 14.18, will not result in containment pressurization, and therefore would not challenge the integrity of the temporary closure device. Additionally, the closure and its penetrations meet the applicable design requirements of the permanent door and penetrations for MODES 5 and
- 6. Based on these safety analyses, FCR 83-103 was determined not to constitute an unreviewed safety question.
This change provides for a clarification of Technical Specification 3.9.4.b concerning the requirement to have one escape hatch door closed during core alterations or movement of irradiated fuel. This proposed change explicitly addresses the emergency escape hatch temporary closure device in the Technical Specifications.
DETERMINATION OF SIGNIFICANT HAZARDS CONSIDERATIONS 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:
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4 Mr. E. 3. Butcher, Jr.
June 28,1985 Page 5 (i) Involve any increase in the probability or consequence of any accident previously evaluated in the Updated Final Safety Analysis Report.
The temporary closure device is an acceptable replacement for the personnel emergency escape hatch door. This change only provides a clarification of the Technical Specifications by recognizing the temporary closure device.
(ii) Create the possibility of a new or different type of accident from any accident previously evaluated.
No modifications to the intent of the Technical Specifications are being made, therefore, no new accident previously unanalyzed will be created by this proposed change.
(iii) Involve a significant reduction in the margin of safety.
There will be no change in the operability and closure restrictions necessary to restrict radioactive material release from the containment. The proposed change only clarifles the current Technical Specification wording by recognizing the use of the temporary closure device in place of an emergency escape hatch airlock door.
CHANGE NO. 4 (BG&E FCR 85-30)
Change pages XVI,6-21 and 6-22 of the Unit I and 2 Technical Specifications as shown on the marked-up copies attached to this transmittal.
DISCUSSION This change is being proposed to delete the superseded Environmental Qualification (EQ) deadlines from the Technical Specifications. By reference (d) the NRC transmitted an Order for Modification of License which added the original EQ deadlines to the Technical Specifications. The two deadlines specify the date by which Class IE electrical equipment must be environmentally qualified and the date by which records describing EQ methods must be available. These deadlines have been superseded by the issuance of a final rule in 10 CFR 50.49. BG&E is committed to the revised EQ deadlines contained in the Code of Federal Regulations, as modllled by approved exemption requests.
Therefore, it is proposed to delete the EQ deadlines from the Technical Specifications,
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June 28,1985 Page 6 DETERintNATION OF SIGNIFICANT HAZARDS This proposed change to the Technical Specifications has been evaluated against the standards in 10 CFR 50.92. It has been determined that this change involves no significant hazards considerations, in that operation of the facility in accordance with the proposed change would nots (i) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (ii) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (lii) Involve a significant reduction in a margin of safety.
The change is administrative in nature and would not alter the schedule for or type of modifications or documentation presently committed to by BG&E to meet 10 CFR 50.49. Therefore, this proposed change would not increase the probability or consequence of a previously analyzed accident, create the possibility of a new accident or decrease any margin of safety.
CHANGE NO. 5 (BG&E FCR 82-138)
Change pages 3/41-21,3/41-25,3/43-16,3/44-8,3/47-72,3/49-11,3/410-5, B 3/41-3, B 3/4 9-3 and 6-14 of the Unit No.1 Technical Specifications; pages 3/41-21, 3/41-25,3/4 3-16, 3/4 3-41, 3/4 4-8,3/4 7-1,3/4 7-64,3/4 9-11,3/410-5, B 3/4 9-3,6-6 and 6-14 of the Unit No. 2 Technical Specifications; and, pages 5.1-1, 5.3-1, 5.5-1 and Figure 5.2-1 of Appendix B to the Unit Nos.1 & 2 Technical Specifications as shown on the marked up copies attached to this transmittal.
DISCUSSION The proposed change would correct numerous syntax, spelling and typographical errors and update several organizational titles. All proposed corrections are administrative in nature and do not affect plant operation or safety.
The proposed changes are described below:
P_ age, Unit (s) Change VI 2 "exhause" to " exhaust" 3/4 1-21 1&2 "within" to "with" 3/41-25 1&2 "the above figure" to " Figure 3.1-2" 3/41-25 1 "3.12" to "3.1-2"
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June 28,1985 Page 7
.P. gge,_ UnitW Chante i 3/4 3-16 1&2 " provide" to "provided" 3/4 3-41 2 "INSTURMENT" to " INSTRUMENT" 3/44-8 1&2 " tubes" to " tube"
- 3/47-1 2 " lime" to "line" 3/4 7-5a 2 "sybsystem" to " subsystem" 3/47-64 2 "460" to "4160" 3/4 7-72 1 "460" to "4160"
! 3/4 9-11 1&2 " fuel spent fuel pool" to " spent fuel pool" l
3/4 10-5 1&2 "shotdown" to " shutdown" l "de= energized" to "de-energized" "xeon" to " xenon" B3/41-3 1 "sxfficienta to " sufficient" l B 3/4 9-3 1&2 "is a critical array" to "in a critical array" 6-6 2 " General Foreman" to " General Supervisor" 6-14 1&2 "originial" to " original" App. B 1&2 " Chief Environmental Engineer" to 5.1-1 " Director, Environmental Programs" App. B 1&2 " DIRECTOR ENVIRONMENTAL STUDIES Fig. 5.2-1 AND MONITORING" to DIRECTOR ENVIRONMENTAL PROGRAMS" App. B 1&2 " Environmental Engineering Group" to 5.3-1 " Environmental Programs Unit" m .__. . . _ _ - _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ ..-
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Mr. E. 3. Butcher, Jr.
June 28,1985 Page8 P_ge, Unit (s) Change App. B 1&2 " Environmental Engineering Group" to 5.5-1 " Environmental Programs Unit" (two places)
" Chief Environmental Engineer" to
" Director, Environmental Programs" (two places)
DETERMINATION OF SIGNIFICANT HAZARDS CONSIDERATIONS This proposed change has been reviewed against the standards set forth 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 an increase in the probability of occurrence or consequences of an accident previously evaluated; or (11) create the possibility of a new or different kind of accident from any accident previously analyzed; or (iii) involve a significant reduction in the margin of safety.
The proposed change is administrative in nature and does not involve a change to equipment, procedures, or limits.
SAFETY COMMITTEE 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.
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June 28,1985 Page 9 FEE DETERMINATION Pursuant to 10 CFR 170.21, we are including BG&E Check No. (A334904) 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:
CITY OF BALTIMORE :
Chris H. Polndexter, 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 Ccrporation.
WITNESS my Hand and Notarial Scal: A <- ~ c M 2 4.~. -
Notary Public My Commission Expires: 73//I6 Date CHP/BEH/MTF/dtm cc: D. A. Brune, Esquire G. F. Trowbridge, Esquire D. H. Jaffe, NRC T. Foley, NRC T. Magette, DNR