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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17335A5551999-10-12012 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5591999-10-11011 October 1999 Supplement to Application for Amends to Licenses DPR-58 & DPR-74,replacing Correct TS Pages Inadvertently Included in 990923 Submittal.Attached Pages Also Include Appropriate Administrative Changes ML17335A5411999-10-0101 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Containment Recirculation Sump Water Inventory.Calculation & non-proprietary WCAP-15302 Rept Also Encl ML17326A1571999-09-23023 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,involving Movement of Loads in Excess of Design Basis Seismic Capability of Auxiliary Bldg Load Handling Equipment & Structures ML17326A1421999-09-17017 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,to Allow Credit of Rod Cluster Control Assemblies for Cold Leg Large Break LOCA Subcriticality.Ts Pages & non-proprietary Versions of WCAP-15246 Encl.Proprietary Version Withheld ML17326A1161999-09-10010 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling ML17326A0921999-08-17017 August 1999 Application for Amend to License DPR-58,to Change TS 3/4.4.5 & Bases for TS 3/4.4.5,3/4.4.6.2 & 3/4.4.8 to Remove voltage-based Repair Criteria,F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarify Bases Sections ML17325B6041999-05-21021 May 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Limitations of Positive Reactivity Additions in Several TS Action Statements ML17325B5511999-04-19019 April 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3/4.8.1.2, Electrical Power Systems & Associated Bases to Provide one-time Extension of 18-month Surveillance Interval for Specific SRs ML17335A3661998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,adding TS for Distributed Ignition Sys ML17335A3631998-12-0303 December 1998 Application for Amend to License DPR-58,revising TS 3/4.7.7, Sealed Source Contamination & Associated Bases to Address Testing Requirements for Fission Detectors ML17335A3591998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,making Administrative Changes to Remove Obsolete Info,To Provide Consistency Between Units 1 & 2,to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17335A3561998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A2631998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp ML17335A2761998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2671998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled ML17335A2311998-09-14014 September 1998 Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm ML17335A1901998-08-28028 August 1998 Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs ML17334A7471998-06-10010 June 1998 Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change ML17334B7011998-03-0303 March 1998 Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases ML17334B6561997-10-0808 October 1997 Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl ML17333B0431997-09-19019 September 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9831997-08-11011 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2101997-08-0101 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS ML17333A8281997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8311997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted ML17333A7121996-12-20020 December 1996 Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency ML17334B5941996-07-11011 July 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl ML17334B5901996-06-19019 June 1996 Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking. ML17334B5891996-06-11011 June 1996 Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05 ML17333A4201996-04-0808 April 1996 Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3551996-03-12012 March 1996 Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5 ML17334B5751996-02-29029 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl ML17334B5741996-02-26026 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks ML17333A3201996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3151996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test ML17333A2641996-01-12012 January 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2391995-12-19019 December 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B ML17332B0111995-11-10010 November 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9971995-10-20020 October 1995 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV ML17332A9111995-08-0606 August 1995 Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified ML17334B5561995-08-0404 August 1995 Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld ML17332A8271995-06-30030 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1 ML17334B5501995-06-20020 June 1995 License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07 ML17332A7991995-06-15015 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H ML17334B5481995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria ML17334B5461995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08 ML17332A7661995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty ML17332A7741995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1 ML17332A7771995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly 1999-09-23
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17335A5551999-10-12012 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5591999-10-11011 October 1999 Supplement to Application for Amends to Licenses DPR-58 & DPR-74,replacing Correct TS Pages Inadvertently Included in 990923 Submittal.Attached Pages Also Include Appropriate Administrative Changes ML17335A5411999-10-0101 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Containment Recirculation Sump Water Inventory.Calculation & non-proprietary WCAP-15302 Rept Also Encl ML17326A1571999-09-23023 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,involving Movement of Loads in Excess of Design Basis Seismic Capability of Auxiliary Bldg Load Handling Equipment & Structures ML17326A1421999-09-17017 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,to Allow Credit of Rod Cluster Control Assemblies for Cold Leg Large Break LOCA Subcriticality.Ts Pages & non-proprietary Versions of WCAP-15246 Encl.Proprietary Version Withheld ML17326A1161999-09-10010 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling ML17326A0921999-08-17017 August 1999 Application for Amend to License DPR-58,to Change TS 3/4.4.5 & Bases for TS 3/4.4.5,3/4.4.6.2 & 3/4.4.8 to Remove voltage-based Repair Criteria,F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarify Bases Sections ML17325B6041999-05-21021 May 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Limitations of Positive Reactivity Additions in Several TS Action Statements ML17325B5511999-04-19019 April 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3/4.8.1.2, Electrical Power Systems & Associated Bases to Provide one-time Extension of 18-month Surveillance Interval for Specific SRs ML17335A3661998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,adding TS for Distributed Ignition Sys ML17335A3631998-12-0303 December 1998 Application for Amend to License DPR-58,revising TS 3/4.7.7, Sealed Source Contamination & Associated Bases to Address Testing Requirements for Fission Detectors ML17335A3591998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,making Administrative Changes to Remove Obsolete Info,To Provide Consistency Between Units 1 & 2,to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17335A3561998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A2631998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp ML17335A2761998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2671998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled ML17335A2311998-09-14014 September 1998 Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm ML17335A1901998-08-28028 August 1998 Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs ML17334A7471998-06-10010 June 1998 Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change ML17334B7011998-03-0303 March 1998 Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases ML17334B6561997-10-0808 October 1997 Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl ML17333B0431997-09-19019 September 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9831997-08-11011 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2101997-08-0101 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS ML17333A8281997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8311997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted ML17333A7121996-12-20020 December 1996 Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency ML17334B5941996-07-11011 July 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl ML17334B5901996-06-19019 June 1996 Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking. ML17334B5891996-06-11011 June 1996 Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05 ML17333A4201996-04-0808 April 1996 Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3551996-03-12012 March 1996 Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5 ML17334B5751996-02-29029 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl ML17334B5741996-02-26026 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks ML17333A3201996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3151996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test ML17333A2641996-01-12012 January 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2391995-12-19019 December 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B ML17332B0111995-11-10010 November 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9971995-10-20020 October 1995 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV ML17332A9111995-08-0606 August 1995 Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified ML17334B5561995-08-0404 August 1995 Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld ML17332A8271995-06-30030 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1 ML17334B5501995-06-20020 June 1995 License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07 ML17332A7991995-06-15015 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H ML17334B5481995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria ML17334B5461995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08 ML17332A7661995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty ML17332A7741995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1 ML17332A7771995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly 1999-09-23
[Table view] |
Text
CATEGORY 1 REGULA0t<>> INFORMATION DISTRIBUTIONOISTEM (RIDE)
ACCESSION NBR:9603110148 DOC!DATE: 96/02/29 NOTARIZED: YES DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) 58~
SUBJECT:
Application for amends to licenses DPR-58 a DPR-74,revising C TS to reduce boric acid concentration in boric acid from approx 12 percent to approx 4 percent by weight. g~ y~~P Technical r'ept presenting justificaion for changes encl.
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N H/HICB 1 1 NRR/DSSA/SPLB NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT OGC/HDS2 1 0 EXTERNAL: NOAC 1 1 NRC PDR NOTE TO ALL MRZDSN RECTPXENTS>
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Indiana htichigan Power Company P.O. Box 16631 Columbus, OH 43216 February 29, 1996 AEP:NRC:1232 Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
Donald C. Cook Nuclear Plant Units 1 and 2 TECHNICAL SPECIFICATION CHANGE REQUEST'ORIC ACID STORAGE SYSTEM BORON CONCENTRATION REDUCTION This letter and its attachments constitute an application for amendment to Donald C. Cook Nuclear Plant Units 1 & 2 technical specifications (T/Ss). The proposed change will reduce the boric acid concentration in the boric acid storage syst'm from approximately 12 percent to approximately 4 percent by weight. The high boric acid concentration presently creates several operational problems. The high boric acid concentration causes accelerated Boric Acid Transfer pump seal wear which requires additional maintenance. The heat tracing associated with the high boric acid concentration also contributes to higher maintenance requirements through temperature degradation of the diaphragm valves. In addition, the heat tracing system itself requires significant maintenance to keep it fully operational and much of this activity results in radiation exposure to the maintenance personnel.
I Specifically, we propose to modify T/Ss 3.1.2.7 and 3.1.2.8 such that the minimum required usable borated water volume in the boric acid storage system is increased and'he maximum boron concentration is decreased. A related proposal is also made to increase the minimum required flow rate in action statements for T/Ss 3.1.1.1, 3.1.1.2, 3.9.1, and 3.10.1 and add an additional surveillance requirement for this Elow rate in T/S 4.1.2.2.d.
Finally, it is proposed that the minimum temperature requirement in T/Ss 4.1.2.1.a, 4.1.2.2.a, 3.1.2.7.a.3, and 3.1.2.8.a.3 be decreased to 63'F. The bases section 3/4.1.2 is also updated to reflect these changes.
A description of the proposed changes and analysis concerning significant hazards consideration pursuant to 10 CFR 50.92 are contained in Attachment l. Attachment 2 contains the existing T/S pages marked to reElect proposed changes. Attachment 3 contains 9603ii0148 960229 PDR ADQCK 05000315 II p PDR
U. S. Nuclear Regulatory Commission AEP:NRC:1232 Page 2 the proposed, revised T/S pages. The justifications for the proposed changes are presented in Attachment 4.
Implementation of the reduced boron concentration for both units will not be accomplished until plant modifications are complete.
Therefore, a period of one year from the approval date is requested to implement the T/S changes. Units 1 and 2 will reduce boron concentration while in an operational mode. Please note that the proposed T/S changes are similar to those approved for Sequoyah Nuclear Plant and Salem Nuclear Generating Station.
Our letter AEP:NRC:1207, which has previously been submitted for approval, proposes to change the shutdown margin requirement for modes 1 through 4 and also proposes to change the minimum temperature of the borated water in the refueling water storage tank (RWST). This submittal reflects the current shutdown margin and minimum RWST borated water temperature requirements'e believe that the proposed T/S changes will not result in (1) a significant change in the amount of effluent that may be released off site, or (2) a significant increase in individual or cumulative occupational radiation exposure.
These proposed T/S changes have been reviewed and approved by the Plant Nuclear Safety Review Committee and by the Nuclear Safety and Design Review Committee.
In compliance with the requirements of 10 CFR 50.91(b)(l), copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and the Michigan Department of Public Health.
Sincerely, E. E. Fitzpatrick Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS ~5~ DAY OF 1996 Notary Public eh
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U. S. Nuclear Regulatory Commission AEP:NRC:1232 Page 3 Attachments cc: A. A. Blind G. Charnoff H. J. Miller NFEM Section Chief NRC Resident Inspector - Bridgman J ~ R. Padgett
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ATTACHMENT 1 TO AEP:NRC:1232 DESCRIPTION OF PROPOSED TECHNICAL SPECIFICATION CHANGES AND 10 CFR 50.92 SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS
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ATTACHMENT 1 to AEP:NRC:1232 Page 1 DESCRIPTION OF CHANGES IN TECHNICAL SPECIFICATIONS (both units)
Action statement for T/S 3.1.1.1 (page 3/4 l-l) is changed to increase the required rate of boration to 34 gpm and decrease the required boron concentration of the solution to 6,550 ppm.
- 2. Action statement for T/S 3.1.1. 2 (page 3/4 1-3) is changed to increase the required rate of boration to 34 gpm and decrease the required boron concentration of the solution to 6,550 ppm.
- 3. Surveillance requirement T/S 4.1.2.l.a (page 3/4 1-7 for Unit 1 and page 3/4 1-8 for Unit 2) is changed to decrease the required temperature to 63'F. It is also proposed that the temperature measurements be made of the physical plant areas containing the components of the flow path from the boric acid tank to the blending tee rather than the temperature of the flow path itself. The reference to the heat tracing system is removed. These changes are proposed because the heat tracing system is not needed to operate with lower boric acid storage tank boron concentrations.
Surveillance requirement T/S 4.1.2.2.a (page 3/4 1-9) is changed to decrease the required temperature to 63'F, It is also proposed that the temperature measurements be made of the physical plant areas containing the components of the flow path from the boric acid tank to the blending tee rather than the temperature of the flow path itself. The reference to the heat tracing system is removed. These changes are proposed because the heat tracing system is not needed to operate with lower boric acid storage tank boron concentrations.
- 5. Surveillance requirement T/S 4.1.2.2.d (page 3/4 1-10) is added which requires verification of the flow rate of the flow path from the boric acid storage tank (BAST), which is required by T/S 3.1.2 '.a. The flow verification is to be performed once per 18 months during shutdown.
- 6. T/S 3.1.2.7.a (page 3/4 1-15) is changed to eliminate the reference to the heat tracing system.
- 7. T/S 3.1.2.7.a.l (page 3/4 1-15) is changed to increase the minimum usable borated water volume to 5,000 gallons.
- s. T/S 3.1.2.7.a.2 (page 3/4 1-15) is changed to establish required boron concentration in the boric acid storage system between 6,550 ppm and 6,990 ppm.
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ATTACHMENT 1 to AEP:NRC:1232 Page 2 T/S 3.1.2.7.a.3 (page 3/4 1-15) is changed to establish minimum solution temperature of 63 F which is consistent with the new boron concentration specified in item 8 above.
- 10. T/S 3.1.2.8.a (page 3/4 1-16) is changed to eliminate the reference to the heat tracing system.
ll. T/S 3.1.2.8.a.l (page 3/4 1-16) is changed to increase the minimum usable borated water volume to 8,500 gallons. A note "Not required when borated water is injected into the RCS to meet SHUTDOWN MARGIN requirements of MODES 3 and 4," was added to allow using this borated water for core boration after shutdown. Once the borated
'ater is used for the intended purpose of increasing the RCS boron concentration, then no additional volume is required.
- 12. T/S 3.1.2.8.a.2 (page 3/4 1-16) is changed to establish required boron concentration in the boric acid storage system between 6,550 ppm and 6,990 ppm.=
13.~ T/S 3.1. 2. 8.a.
~ ~ ~ ~ 3 (page 3/4 1-16) is changed to establish minimum solution temperature of 63'F which is consistent with the new boron concentration specified in item 12 above.
- 14. Action Statement for T/S 3.9.1 (page 3/4 9-1) is changed to increase the minimum required rate of boration to 34 gpm and decrease the required boron concentration of the solution to 6,550 ppm.
- 15. Action statement a. and action statement b, for T/S 3.10.1 (page 3/4 10-1) are changed to increase the minimum required rate of boration to 34 gpm and decrease the required boron concentration of the solution to 6,550 ppm.
ATTACHMENT 1 to AEP:NRC:1232 Page 3 DESCRIPTION OF CHANGES IN THE BASES (Unit 1)
- 16. The following changes are proposed for the BASES for T/S 3/4.1.2 BORATION SYSTEMS (pages 3/4 1-2 and 3/4 1-3):
16.1" The words "5) associated heat tracing systems" were removed from the list of components required to perform boron injection. The numbering in the list of components was adjusted. This change is required because there will be no need for the heat tracing system with the reduced boron concentration in the boric acid storage system.
16.2 The statement "The maximum expected boration capability, usable volume requirement, is 5641 gallons of 20,000 ppm borated water from the boric acid storage tanks or 99,598 gallons of 2400 ppm borated water from the refueling water storage tank," in the last paragraph on page B 3/4 1-2 was changed to "The maximum expected boration capability, usable volume requirement, is 8500 gallons of 6550 ppm borated water from the boric acid storage tanks for providing required SHUTDOWN MARGIN after xenon decay and cooldown to 547 F and additional borated water from a second boric acid storage tank, or batching tank, or refueling water storage tank for further cooldown to 200'F. With the refueling water storage tank as the only source, based on conservative calculations, a maximum of 99598 gallons of 2400 ppm borated water is required."
16.3 The statement "This condition requires either 2890 gallons of 20,000 ppm borated water from the boric acid storage tanks or 76,937 gallons of 2400 ppm borated water from the refueling water storage tank." in the second paragraph ongallons'page B 3/4 1-3 was changed to "This condition requires either 900 gallons of 6,550 ppm borated water from the boric acid storage tanks or 3265 gallons of 2400 ppm borated water from the refueling water storage tank. The boric acid storage tank boration source volume of T/S 3.1.2.7 has been conservatively increased to 5,000 "
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ATTACHMENT 1 to AEP:NRC:1232 Page 4 DESCRIPTION OP CHANGES IN THE BASES (Unit 2)
The following changes are proposed for the BASES for T/S 3/4.1.2 BORATION SYSTEMS (pages B 3/4 1-2 and B 3/4 1-3):
17.1, The words "5) associated heat tracing systems" were removed from the list of components required to perform boron injection. The numbering in the list of components was adjusted. This change is required because there will be no need for the heat tracing system with the reduced boron concentration in the boric acid storage system.
17.2 The statement "The maximum expected boration capability, usable volume requirement is 4905 gallons of 20,000 ppm borated water from the boric acid storage tanks or 69,215 gallons of borated water from the refueling water storage tank." in the third paragraph on page B 3/4 1-3 was changed to "The maximum expected boration capability usable volume requirement is 8500 gallons of 6550 ppm borated water from the boric acid storage tanks for providing required SHUTDOWN MARGIN after xenon decay and cooldown to 547'F and additional borated water from a second boric acid storage tank, or batching tank, or refueling water storage tank for further cooldown to 200'F.
With the refueling water storage tank as the only source, based on conservative calculations, a maximum of 69215 gallons of 2400 ppm borated water is required."
17.3 The statement "The boration source volume from the boric acid storage tanks has conservatively been increased to 5650 gallons, This value was chosen to be consistent with Unit 1." at the end of the third paragraph on page B 3/4 1-3 were deleted. New analyses described in Attachment 4 were performed for both units. Therefore, the boration source volume for both units is the same.
17.4 The statements "This condition requires usable volumes of either 298 gallons of 20,000 ppm borated water from the boric acid storage tanks or 2408 gallons of borated water from the refueling water storage tank. The boration source volumes of T/S 3.1.2.7 have been conservatively increased to 4300 gallons from the boric acid storage tanks and 90,000 gallons from the refueling water storage tank.
These volumes are based on conservative calculations performed for Cycle 6 of Unit 2. The calculations assumed a final MODE 6 RCS boron concentration of 2000 ppm." in the fifth paragraph on page B 3/4 1-3 were changed to: "This condition requires usable volumes of either 900 gallons of 6,550 ppm borated water from the boric acid storage tanks or 3265 gallons of borated water from the refueling
ATTACHMENT 1 to AEP:NRC:1232 Page 5 water storage tank. The boration source volumes of Technical Specification 3.1.2.7 have been conservatively increased to 5,000 gallons from the boric acid storage tank and 90,000 gallons from the refueling water storage tank."
DESCRIPTION OF EDITING CHANGES IN TECHNICAL SPECIFICATIONS (both units)
Surveillance requirements T/Ss 4.1.2.2.b and 4.1.2.2.c were moved from page '3/4 1-10 to page 3/4 1-9 REASON FOR CHANGE Because of the requirement to maintain highly concentrated boric acid in the boric acid storage system, the solution has to be kept at a high temperature of at least 145 F. This is accomplished by heat tracing all associated tanks and pipes. The high boric acid concentration presently creates several operational problems. The heat tracing requirements for the CVCS are extensive and require significant maintenance to keep the system operable. If a heat trace failure is undetected, the possibility of pipe blockage because of boric acid precipitation may render one of the flow paths inoperable, impacting the safety system availability. In addition, the heat tracing results in the degradation of the diaphragm valves associated with the boric acid system piping. The high boric acid concentration causes accelerated Boric Acid Transfer pump seal wear and can result in pump inoperability.
JUSTIFICATION FOR THE CHANGE The boron concentration in the boric acid storage tank is not taken into consideration in any Chapter 14 FSAR accident analyses. The steam line break analysis assumed zero boron concentration in the boron injection tank. The boric acid storage tank boron concentration is also not considered in the LOCA analysis. Attachment 4 provides analysis supporting the boron reduction project.
The investigation shows that safe shutdown will be achieved from all expected operational conditions.
10 CFR 50.92 SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS Per 10 CFR 50.92, a proposed change does not involve a significant hazards consideration if the change does not:
involve a significant increase in the probability or consequences of an accident previously evaluated,
- 2. create the possibility of a new or different kind of
ATTACHMENT 1 to AEP:NRC:1232 Page 6 accident from any accident previously evaluated, and
- 3. involve a significant reduction in a margin of safety.
Criterion 1 Does the change involve a significant increase in the probability or consequences of an accident previously evaluatedf NO, The BAST water volume and boron concentration were not credited in any Chapter 14 safety analysis. Therefore, no change in the probabilities of the accident analysis will result from the BAST water volume and boron concentration change. In addition, since the BAST water volume and boron concentration are not taken into consideration in any safety analysis, the consequences of an accident previously evaluated in the FSAR are not increased. The heat tracing system is currently only necessary to prevent precipitation of existing high boric acid concentration in the plant systems. The reduction in boron concentration in this proposal eliminates the need for the heat tracing system. The existence of the heat, tracing system was not part of any safety analysis and disabling of the heat tracing system will not result in a significant increase in the probability or consequences of an accident previously evaluated.
Criterion 2 Does the change create the possibility of a new or different kind of accident from any accident previously evaluatedf NO. Since the minimum required water flow from the boric acid storage system to the reactor coolant system was increased to counteract any possible operational transients, as shown in Attachment 4, the change in BAST water volume and boron concentration and disabling of the heat tracing system do not create the possibility of an accident which is different from any already evaluated in the FSAR. No new or different failure modes have been defined for any system or component nor has any new limiting single failure been identified.
Criterion 3 Does the change involve a significant reduction in a margin of safety' NO. The margin of safety requirements are not affected by the removal of the heat tracing system arid the reduction of the boric acid concentration in the boric acid storage system. The required flow
ATTACHMENT 1 to AEP:NRC:1232 Page 7 paths and borated water sources are unaffected by this proposal.
The required quantity of borated water is still available based upon the performed evaluation, and appropriate surveillance requirements ensure the ability to deliver this borated water. The reduction of the boric acid concentration in the BASTs will ensure that the boric acid remains in solution at the normal room temperature in the auxiliary building. With the above changes, there will be a net improvement in system reliability and accordingly the proposed changes do not affect the margin of safety.
Conclusion It is concluded that operation of Cook Nuclear Plant Units 1 and 2 with a changed BAST water volume and boron concentration and disabled heat tracing system as described herein does not involve any significant hazards consideration as defined in 10 CFR 50.92.
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