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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
BALTI M ORE GAS AND ELECTRIC CHARLES CENTER P.O. BOX 1475 BALTIMORE, MARYLAND 21203 ARTHUR E. LUNDVALL, JR.
vict PRESIDENT SUPPLY September 20,1983 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTENTION: Mr. 3. R. Miller, C aef Operating Reacto, s Branch #3 Division of Licens: ag
SUBJECT:
Calvert Clifis Nuclear Power Plant Unit No.1, Docket No. 50-317 Request for Amendment Gentlemen:
The Baltimore Gas and Electric Company hereby requests an Amendment to its Operating License No. DPR-53 for Calvert Cliffs Unit No.1, to reflect a planned i
modification to the hydrogen purge system outlet isolation valves MOV-6900 and MOV-6901. This modification consists of the addition of a Safety Injection Actuation Signal (SIAS) to the valve operators.
i Pursuant to the procedural requirements of 10 CFR 50 paragraphs 50.59, 50.91 and 50.92, this letter forwards our notification of the proposed license amendment and provides a determination with regard to significant hazards considerations. In addition, with regard to operation of the modified portion of the system in MODES 1 through 4, a preliminary determination on significant hazards is submitted.
l More detailed information based on the safety analyses being performed by our architechtural engineer will be forwarded in a supplement to this request at a later date, l
and will allow a final determination of significant hazards for operation in MODES 1 l through 4.
Our present intention is to perform the physical modifications during the upcoming Unit I refueling outage beginning October 1,1983. We plan to modify the valves and perform functional testing that will permit opening and shutting the valves while in MODES 5 and
- 6. The valves will be locked closed and administratively maintained in the closed position prior to entry into MODE 4, following completion of the outage. This condition will be maintained by proposed Technical Specification 3/4.6.1.8 during MODES 1 through 4 until receipt of the approved Technical Specifications.
8309260154 830920 PDR ADOCK 05000317 P PDR (,C,{
E't90* * 'li
r Mr. 3. R. Miller September 20,1983 Page 2 PROPOSED CHANGES (BG&E FCR 83-104)
- 1. Remove old page 3/4 6-23 and replace with marked-up page 3/4 6-23 incorporating the changes, which consist of the addition of "SIAS" under the column entitled
" isolation channels", a change in the name of the function to " containment vent isolation" and the insertion of " < 20" for isolation time for both MOV-6900 and MOV-6901.
- 2. Add a new Technical Specification 3/4.9.14 consisting of a limiting condition for operation, surveillance requirements, and Technical Specification bases as shown on the attached proposed Technical Specification pages. This additional Technical Specification assures that the containment vent isolation valves are maintained shut during core alterations or movement of irradiated fuel within the containment.
- 3. Add new Technical Specification 3/4.6.1.8 as shown on the attached proposed Technical Specification page. This Technical Specification assures that the isolation valves will be maintained shut in MODES 1-4 until receipt of the final NRC Safety Evaluation regarding operational use of the containment vent system.
DISCUSSION AND DETERMINATION OF SIGNIFICANT HAZARDS During normal operation the containment must occasionally be vented to maintain containment internal pressure below the Technical Specification upper limit of 1.8 psig.
Presently, and in the past, this has been performed by venting the containment atmosphere through the containment normal sump isolation valves which exhaust to the Emergency Core Cooling System (ECCS) pump room sump, and subsequently to the environment via the ECCS pump room ventilation system exhaust filter train. While this method of venting the containment has been acceptable in the past and is carefully controlled and monitored, an operationally easier and more useful method is possible through the use of a portion of the existing Hydrogen Purge system. The portion of this system to be used as a vent path consists of a four inch diameter hydrogen purge outlet line, which terminates in the penetration room in the main plant vent piping upstream of the penetration room exhaust filter train.
The function of Post Loss of Coolant Accident (LOCA) hydrogen control is more than adequately performed by the installed, redundant, safety grade hydrogen recombiners.
We, therefore, intend to delete reference to the hydrogen purge system in the Updated Final Safety Analysis Report (FSAR), and install a blind flange on the air replenishment
( portion of the system (penetration 48b). The new function of the H2Purge outlet as a
- containment vent system will be addressed in the next revision to the FSAR.
l Presently, the hydrogen purge outlet containment isolation valves (MOV-6900 and i MOV-6901) are maintained closed in accordance with Technical Specifications to prevent unnecessary exposure of the public if an accident resulting in airborne radioactivity release were to occtm. b order to allow venting of the containment through these valves during MODES 1 through 4, yet still provide the necessary protection to the public in the event of an accident, the physical modification will provide for closure of these valves on a Safety injection Actuation Signal (SIAS).
k
Mr. 3. R. Miller September 20,1983 Page 3 Normally, during power operations, these valves will remain shut and only be opened for brief periods of time to allow venting. Initiation of SlAS from either of two diverse parameters (containment pressure high or pressurizer pressure low) would close the isolation valves within 20 seconds, ensuring that the site boundary doses are maintained within a small fraction of the limits of 10 CFR 100.
The proposed Technical Specification changes would then, update Table 3.6-1 to reflect the addition of an SIAS closure signal to the hydrogen purge outlet isolation valves (to be renamed containment vent isolation valves) and provide limitations to prevent their use during MODES 1-4, or during core alterations or movement of irradiated fuel within the -
containment. These restrictions on operation of the containment vent valves preclude any need for installation of a Containment Radiation Signal (CRS) closure feature or for any safety analysis regarding postulated accidents during core alterations or fuel handling operations. To meet licensing requirements the above restrictions also ensure the isolation valves will be maintained shut in MODES 1-4, until receipt of the final NRC Safety Evaluation regarding operational use of the Containment Vent System.
Based on current review of the presently analyzed accidents in the Updated Final Safety Analysis Report, we find this proposed change does not involve a significant increase in the probability or consequences of these accidents, nor does it create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed change does not involve a significant reduction in the margin of safety as defined in the Technical Specification bases. With additional restrictions imposed by proposed Technical Specification 3/4.6.1.8, the proposed change falls under the examples of amendments not likely to involve a Significant Hazards Consideration, as listed in Federal Register Volume 48, No. 67 dated Wednesday, April 6,1983. We conclude that the proposed change does not involve a Significant Hazards Consideration.
A preliminary evaluation based on the above review of Chapter 14 of the updated Final Safety Analysis Report has yielded a determination that operation of the Containment Vent System in MODES 1-4 does not involve a Significant Hazards Consideration. This evaluation will be supplemented following our review of the safety analysis currently performed by our Architectural Engineer. We will forward the results of our review in a final determination which supplements our submittal.
SAFETY COMMITTEE REVIEW These proposed changes to the Technical Specifications and our determination of significant hazards have been reviewed by our Plant Operations and Safety 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. The forthcoming supplemental detailed safety analysis will be submitted following additional safety committee reviews.
f i
( 1 1
l Mr. J. R. Miller September 20,1983 Page 4 FEE DETERMINATION We request that you consider this change request as a supplement to the Unit I re-load application dated August 22,1983.
We have determined, pursuant to 10 CFR Part 170, paragraph 170.22, that this Amendment request consists of a Class III amendment for Calvert Cliffs Unit No.1.
Accordingly, we are including Baltimore Gas and Electric Company Check No. B297515 in the amount of $4,000.00 to cover the fee for this request.
Very truly yours, x w AEL/ JET /sjb 3
STATE OF MARYLAND :
- TO WIT:
CITY OF BALTIMORE :
Arthur E. Lundvall, Jr., being duly sworn states that he is Vice President of the Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he provides the foregoing response for the purposes therein set forth; that the statements made are true and correct to the best of his knowledge,information, and belief; and that he was authorized to provide the response on behalf of said Corporation.
WITNESS my Hand and Notarial Seal:
Y/[e Notary n// bPublic? a dw' My Commission Expires ht)/[</f[b if f '
cc: J. A. Biddison, Jr., Esquire G. F. Trowbridge, Esquire D. H. Jaff e, NRC R. E. Architzel, NRC R. E. Corcoran, Chief (DHMH)
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ALTIMORE GAS AND ELECTRIC COMPANY .e.:o coy 93645-01
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B297515 ~
300 , ,,o m.e'er ,a r.mcr ast m:E" . 6ce cits' 0:ssdusi - ~ nor Avount 3U9082 09 12 83 $4,000.00 C1 css 3 Technical Specification Change Unit 1 Table 3.6-1 adds SIAS signal to hydrogen purge valves' i
I i .
09 13 83 TOTALS >', $4,000.00 DETACH THIS PORTION BEFORE DEPOSiflNG CHECK
_7 }?
$20 Es: BALTIMORE GAS AND ELECTRIC COMPANY BALTIMORE, MARYLAND 21203
-SEP 13,83 A P/OUN T CHECA P.'p/8 E R
. PAY EXACTLY **4.000.00** $4.000.00** B297515.
US NUCLEAR REGULATORY **
TO THE COMMISSION **
Washington. DC. 20555 CRDER OF EXtsMit ED MARYLAND NAT6ONAL BANK j j BALTIMCHE. MD. ggg eO 29 7 5 L Se a:G 5 2000 LEiBi: L t. La 28 7 3is 26 DR m__,_._ _.. _ . _ . _ _ _ . _ _ _ . . ~_. _ . _ _ _ _ _ _ _ _
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O TABLE 1.6-1 (Continued)
Q -
]
CONTAINilENT ISOLATION VALVES .
ISOLMION VALVE. ! W ATION PCHEIRAil0N ISOLATION IDENTIFICATION NO. FUltCTION_ TiHF fSEC0 fibs) %
7 NO. CliANNEL _
/
3
(
230-1 Fire Protection NA
. 44 NA flA NA 238-1 ,
y HA /
- r. NA H0V-6200 *
~'.
I Ilydrogen Sample Outlet fiA ,-
ttA SV-6540A 47A
SV-6507A NA /
NA '
/
Ilydrogen Sample Outlet HA 4 470 NA SV-6540E / 9 NA O HA SV-6507E s g a . a
- m. 4 SV-6540F Hydrogen Sample Outlet tiA (I ~
U 47C NA HA '.
tiA SV-6507f '
liydrogen Sample Return fiA 470 flA SV-6540G NA SV-6507G HA /
/
s
,-Hydrosci. Pur5: C u 'd ; t - + 620 /
M anA --M--5IAS B liOV-6900 -wr- g a o
-Nh--SZn5 h H01-6901 awr,wnxr vtxt tsoutf/M (I f-f Ce
' l '. $'
.I ._
+
o
A6fH[l/NC, OPER/?TIONS
- CONTAINelfN T VEar IsotArroN V/1LVf3 L /PflTIN& C M blT10N ntA LPfA/1710H ._
O 4* l4 T/' C Centa inmen t vcp t t.rp/a labp valvts sf all be c/esec' Nt'L / C A 8sti YY l buring Cott E A L 76RATtON$ er r,evertw : c l' l
kradefed heI witAin the c oNlasvi,1 est.
ItC TION : With one or inste e.w/aasnrest vent .isclofica val.es open, 41ned6kly suspend s// dpetaMas s !vokayi cwi
/1LTERAT/ oms ee snovem ea t of irradiiz1cd be/ vidah /Ae.
cow briartext.
snMEllLANCf AfaulM/1ENTS
- 4. 9, /Y 7he cashinctes t vent isolo Ma veNes sAall be de kenixed fa be closed us1hok '72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.s p nbr h Me duer coa E chref of sad a.t er le<rf cacee$per m,, gest 7 days hrsodtl ko!l u e l jw$ n'a 4lt e.
AL YdRAT/DNS coa ki:vsten t.
c
- c. _.
MCMbfN f NO -
[/1LVfAT Cl.lffS -t/NJT I JlsfQ-
- f. -
r REPJELING OPERATIONS I 3AsEs 3/4.9.10 and 3/4.9.11 '.'ATER LEVEL-REACTOR VESSEL AND SPENT PJEL 2 COL 2ATER LE'/EL The restrictions en minimum water level ensure that sufficient water depth is available to rencve 99". of the assumed 100 icdine sac activity released frca the rupture of an irradiated fuct assembly.
The minimum water depth is consistent with the assumptions of the accident analysis.
3/a.9.12 SPENT FUEL PCOL VENTILATION SYSTEM The limitations on the spent fuel pool ventilation system ensure /
thatbeall will radioactive filtered inrougn the material released HEPA filters frcm an and charcoal irradiated adsorber i
cr ce ~ fuel asse The OPERASILITY of this system and tne discharge to the atmcsphere. c' resulting iodine removal capacity are consistent with the assumpticr.:
the accident analyses.
3/4.9.13 SFEMT FUEL CASK HANDLING CRANE The restriction on movement of the spent fuel shipping cask within one cask length of any fuel assembly ensures that in the event this icac is dropped (1) the stored spent fuel assccblics will not be damaged ,
and (2) any possible distortion of fuel in the storage racks will c.ot result is a critical array.
3/4.9.iy exrmMmpr vtar 15<)terisa vmves "The OPEM6Ill7Y and closare res4ra %s og lhe cea ta wmca c vcat isolaNon values are sdfs'cient t.o res%'ct radbac Hue. imt A. fuel element raphsrc based upaa Me. lack o f csw er an.u-a -
release fron th e. R E f u Et.iN G tt o b t. ,
(
pressuriza6ca ptenWal WAlle sa l c 1-V
' cal VecT C! IF;2 s"t *T 1 3 2/a 9-3
LONTPiNM[N r s* YS Tfris-f i
. DnTAMMrs/f* V6y7 s/S76A.
t I
L '/ML7/d6..CbMot[tdM AW DPCAATRW ._-
- ~
l J.6,l.S' 7he esalaskera+ veu + isola /ha vs/ues rie v s '!ct Mff-Q lh e
\ MCV ?'idt shn// be resia Isined cased by b/'Cd b^4fs lbt? $ t' Y el!
< f >* &Wf $4/f f f Cffd ef d $ P1/1/ Yd/Y/ I head .cui/cAe r /ecked is /de c/0 sed porHrba.
I APM/cn8/a rf : rionts I,.2,3, up y ACTits : ui /A one sr beIh esaistSwen t vea t irelt hi a t . i efea , clore the. spes vs/se(s) iss?Aik sse Acue :.,dc io ai /ess/ //s7 staxoBY ur%k the sex + 6 Aou<s saj w C0L.O SHurpoWAl ao%'a 4he follomky 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
/ttau1/itrt CRT5 Su R tiEIL LAN e C - ___.
con teknest vent i.colalion volves sh1l:
'l. 6 . I. T 7*Ae he delern&cd closed a. + les s + once. per 3o ds y s ,
%<. no+or s,wesfors by ve<ifyag na+ pauser +v is
? renoved and Me vs/ve s ta& ale sAu t ,
t CPLuf t1 T* CetffS - um 7 I Jh b -4 e 71mndwn <;
l