Similar Documents at Cook |
---|
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
ACCELERATED DI TRJBUTION DEMONS ATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8910310003 DOC.DATE: 89/10/17 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana & 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME AUTHOR AFFILIATION ALEXICH,M.P. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) R SUBZECT: Application for amends to Licenses DPR-58 & DPR 74,revising Tech Specs re controlled leakage.
D DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 5 5 D GIITTER,Z'NTERNAL:
NRR/DEST/ADS 7E 1 1 NRR/DEST/ESB 8D 1 1 D NRR/DEST/ICSB 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/RSB 8E 1 1 NRR/DOEA/TS B 1 1 1 1 S NUDOCS-ABSTRACT 1 1 OC/~ 1 '
OGC/HDS1 1 0 G FIL Ol 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 D
D NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 19 p8,
Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 R
SNSIAMA MCNSIMN PQHfM AEP'NRC:1070 10 CFR 50.90 Donald C. Cook Nuclear Plant Units 1 and 2 License Nos. DPR-58 and DPR-74 Docket Nos. 50-315 and 50-316 CONTROLLED LEAKAGE TECHNICAL SPECIFICATION CHANGE U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Attn: T. E. Murley October 17, 1989
Dear Dr. Murley:
This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss) for the Donald C.
Cook Nuclear Plant Units 1 and 2, Specifically, we are proposing to modify T/S 3/4.4.6.2 (Operational Leakage) and its associated Bases such that the requirements for controlled leakage are made more restrictive. The reason for the change and our 10 CFR 50.92 significant hazards analysis are found in Attachment l. Attachment 2 contains the proposed revised T/S pages, We believe the proposed changes will not result in (1) a significant change in the types of effluents or a significant increase in the amounts of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.
This T/S change is intended to correct a deficiency in our present T/Ss so that the assumptions of the applicable accident analysis are adequatel'y protected. As described in Attachment 1 to this letter, we have administratively implemented restrictions above the present T/S requirements that are protecting the accident analysis assumptions.
These proposed changes have been reviewed 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)(1), copies of this letter and its attachments have been transmitted to Mr. R. C. Callen of the Michigan Public Service Commission and the Michigan Department of Public Health.
85'i03i000S '8'yl-017 --- -~
PDR ADGCK 05000315 P PQC IJ
Dr. T. E. Murley AEP:NRC:1070 Attachment 1 to this letter includes AEP drawings OP-2-5129 and OP-2-5128A. In accordance with the restrictions as to use set forth on the AEP drawings, AEP hereby releases these documents to the NRC for its information and use in connection with this submittal. AEP also permits the NRC to reproduce the drawings as necessary to facilitate review and distribution of the drawings to meet NRC requirements.
This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, M. . Ale ch Vice President ldp Attachments cc: D. H. Vi.lliams, Jr.
A. A. Blind - Bridgman R. C. Callen G. Charnoff A. B. Davis NRC Resident Inspector - Bridgman NFEM Section Chief
ATTACHMENT 1 TO AEP;NRC:1070 REASONS AND 10 CFR 50.92 ANALYSIS FOR CHANGES TO THE DONALD C. COOK NUCLEAR PLANT TECHNICAL SPECIFICATIONS to AEP:NRC:1070 Page 1 Introduction The Technical Specification (T/S) change proposed in this letter is intended to ensure the T/Ss accurately reflect the requirements of the safety analysis with regards to controlled leakage. To facilitate the review, we have included the following flow diagrams:
- 1) OP-2-5129 CVCS Reactor Letdown and Charging
- 2) OP-2-5128A Reactor Coolant Descri tion of Chan e As currently written, T/S 3,4.6.2.e (Operational Leakage) limits controlled leakage to 52 gpm. Surveillance requirement 4.4.6.2.1. requires measurement of controlled leakage at least once per 31 days. Controlled leakage is defined in Section 1 of the T/Ss as "that seal water flow supplied to the reactor coolant pump seals." Ve are proposing to amend the subject T/S such that the controlled leakage limit is expressed as a line resistance, rather than a specific flow rate. The seal line resistance w be measured at least once per 31 days when the pressurizer ill p ressure is within 20 psi of its nominal full pressure ~alue.
The seal line resistance measured during2the surveillance must be greater than or equal to 2.27 E-1 ft/gpm . The seal line R SL'sistance is determined from the following expression:
R ~ 2.31 (P - P )
SL 2
Q where: P charging pump header pressure, psig CHP P
SX 2112 psig (Unit 1 low pressure operation) 2262 psig (Unit 1 high pressure operation) 2262 psig (Unit 2 operation) 2.31 conversion factor (12 in/ft)2 /(62.3 lb/ft3 )
total seal injection flow, gpm Additionally, we have added an exemption from the requirements of T/S 4.0.4 for entry into Modes 3 and 4, deleted a footnote from T/S 3.4.6.2 Action (c) involving reporting requirements for reactor coolant pressure boundary leakage, and modified the Bases section to reflect'the controlled leakage requirement change,
Attachment 1 to AEP:NRC:1070 Page 2 Reason for Chan e The change to the controlled leakage requirements results from our conclusion that the present limit of 52 gpm cannot by itself ensure compliance with the assumptions of the safety analysis.
For the LOCA analyses with minimum safeguards assumptions, the fuel vendors assume that all of the flow that is diverted from the boron injection tank (BIT) line by the seal injection line is unavailable for core cooling. (Although a portion of the seal water is injected into the reactor coolant system, there is no T/S limit on this flow and therefore all of the seal flow is assumed unavailable for core cooling,) The fuel vendor analyses assume a seal line hydraulic resistance of 0.227 ft/gpm .
Surveillance requirement 4.4.6.2.l,c is intended to verify that the actual seal line resistance is greater than or equal to this value. It is complemented by T/S 4.5.2.h (ECCS Subsystems),
which, as discussed in T/S Bases 3/4.5,2 and 3/4.5.3, assures that the BIT throttle valves are adjusted such that: a) total pump flow does not exceed runout conditions when the system is in its minimum resistance configuration, b) the proper flow split exists between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and c) the total ECCS flow to all injection points is equal to or above that assumed in the ECCS-LOCA analyses.
The nominal developed head of the charging pump at runout (550 gpm) is approximately 1431 feet. Therefore, the flow diverted through the seal line under Emergency Core Cooling System (ECCS) operation at 0 psig is:
ft/gpm ) 1/2 2
(1431 ft/0 '27 79 gpm As a result, T/S 4.5.2.h specifies a nominal pump runout flow rate of 550 gpm with a simulated seal flow of 80 gpm and a maximum of 470 gpm through the BIT. During normal operation, the Unit 2 pressurizer pressure is maintained at a nominal pressure of 2235 psig. The resulting pressure at the seal injection point in the reactor coolant pump is approximately 2260 psig. Assuming normal letdown (75 gpm), the charging pump discharge pressure should be at least 2413 psig. The corresponding seal injection flow rate is:
2
((2413 - 2260) psi/(0.227 ft/gpm )
+ (12 in/ft) /(62 lb/ft ))
40 gpm
Attachment 1 to AEP:NRC:1070 Page 3 The current T/S only specifies a maximum flow rate. The T/S does not provide any limits on RCS or pump discharge pressure that correspond to the flow limit. As seen in the example above, the 52 gpm limit would be nonconservative with the charging pump head assumed in the example.
The Westinghouse Standard T/Ss specify a controlled leakage limit in gpm. The Standard T/S surveillance requirement specifies that the modulating valve (corresponding to Cook Nuclear Plant valve QRV-251, shown at location J-5 on drawing OP-2-5129) must be fully open. Although this is an enhancement over the present Cook Nuclear Plant T/S, it presents operational difficulties since it requires valve QRV-251 to be fully opened in order to perform the test. Since QRV-251 is the main valve used to throttle charging flow during normal operations, it is not generally fully open. The operator must carefully adjust QRV-200 (shown at location H-3 on drawing OP-2-5129) to maintain the necessary charging flow and pressurizer level during the test.
Since we have recognized that the present T/S is inadequate, we have implemented administrative controls to ensure that the controlled leakage surveillance accurately reflects the safety analysis assumptions. Controlled leakage, as measured during the surveillance, is administratively limited to 40 gpm, We are presently performing the surveillance outlined by the Standard T/S, except that we measure the charging pump header pressure to ensure it is consistent with the 40 gpm controlled leakage limit and the resistance assumed in the Westinghouse analysis.
Our proposed T/S change ensures that the accident analysis assumptions are protected while eliminating the difficulty associated with the Standard T/S surveillance. The actual line resistance is determined rather than a simple flow rate. In performing the surveillance, we are currently planning to measure pump discharge pressure using pressure instrument QPI-250, since it reads out in the 'control room. The instrument is in the pump discharge header downstream of QRV-251. This is conservative since it predicts a lower system resistance and therefore will make it more difficult to pass the test. Also, since pump discharge pressure is measured downstream of QRV-251, there is no need to fully open the valve, as the standard T/S requires, (The instrument is shown at location K-4 on drawing OP-2-5129).
Seal line flow will be determined by summing the flow indicated in the control room by instruments QFI 210, 220, 230, and 240, that indicate the seal flow to reactor coolant pumps 1 through 4, respectively. (The instruments are shown at location B-4 on drawing OP-2-5128A.) The conversion from pressurizer pressure to seal injection point pressure (P ) was calculated using a methodology provided to us by Weshinghouse. This methodology accounts for pressure effects such as the difference in elevation between pressurizer programmed level and the seal- injection
Attachment 1 to AEP:NRC:1070 Page 4 points. The Westinghouse equations were applied to programmed RCS conditions (temperature and pressurizer level) for both units at various power levels. The values for P I specified in the proposed T/Ss correspond to 100% power operation since this conservatively results in the largest value of P . Two values for P SI> are specified for Unit 1, corresponding to the two discrete pressurizer pressure values (2235 psig and 2085 psig) which are supported by the Unit 1 reduced temperature and pressure program (Reference Unit 1 T/S Amendment 126).
The seal line resistance, as determined by the proposed surveillance requirement, is applicable at full This is because the pressure at the seal in]ection pressure'onditions.
point, which cannot be directly measured, has been calculated assuming full pressure operation, This is recognized by the Standard T/S, which specifies the LCO and the surveillance requirement at a pressurizer pressure of 2235 + 20 psig, (In practice, full pressure operation is the most limiting because it requires the lowest line resistance to provide adequate flow to the reactor coolant pump seals.) We have added a footnote to the LCO and worded the proposed surveillance requirement such that it is clear that the T/S is applicable with average pressurizer pressure at its full pressure value. (We have maintained the 20 psi tolerance from the Standard T/S, since pressurizer pressure may fluctuate slightly around its nominal value.) We have also added a T/S 4.0.4 exemption for T/S 4.4.6.2.1 for entry into Modes 3 and 4. The 4.0.4 exemption will allow entry into Modes 3 and 4 before the controlled leakage surveillance is completed, This change is consistent with the Standard T/S. As discussed above, the surveillance is to be performed with the RCS fully pressurized. This condition is typically established in Mode 3.
While the RCS pressure is changing, it may be necessary to ad]ust seal flow to the reactor coolant pumps using needle valves CS-438
-1, -2, -3, and -4, (These valves are shown on drawing 2-5128A at B-4.) A change in needle valve position alters the system resistance, rendering obsolete any resistance measurements taken beforehand.
We are also proposing to delete a footnote associated with T/S 3,4.6.2 Action (c) that involves reporting of reactor coolant pressure boundary leakage pursuant to T/S 6.9.1 ~ The reportability requirements of T/S 6,9,1 have been modified because of changes to the LER rule (10 CFR 50.73), and T/S 6.9.1 no longer contains requirements related to reporting of pressure boundary leakage. This change is therefore purely administrative in nature, intended only to remove a superseded reference from the T/Ss.
Attachment 1 to AEP:NRC:1070 Page 5 10 CFR 50.92 Criteria Per 10 CFR 50.92, a proposed amendment will not involve a significant hazards consideration if the proposed amendment does not:
- 1) Involve a significant increase in the probability or consequences of an accident previously analyzed,
- 2) " Create the possibility of a new or different kind of accident from any accident previously analyzed or evaluate'd, or
- 3) Involve a significant reduction in a margin of safety.
Criterion 1 We are proposing to modify the T/S surveillance requirement for controlled leakage such that it accurately reflects the assumptions of the LOCA analysis. The present T/S wording is vague, and does not by itself ensure consistency with the analysis, The revised surveillance requirement places additional restrictions on the plant, and would be expected to increase, rather than decrease, safety. The proposed addition of a T/S 4.0.4 exemption for Modes 3 and 4 and the clarifications that the specification is applicable with the RCS fully pressurized are a reduction to the current requirements, but are consistent with performing the surveillance with the RCS fully pressurized, and are similar to the Standard T/S requirements. Since there are no substantive differences between the Cook Nuclear Plant controlled leakage configuration and that reflected by the Standard T/S, the change would not be expected to decrease safety, For these reasons, we believe the change does not involve a significant increase in the probability or consequences of a previously analyzed accident, nor should it involve a significant reduction in a margin of safety.
Criterion 2 The only change to plant operations is the method of measuring controlled leakage. The proposed method requires no changes in plant equipment lineups. Data is recorded from existing instrumentation, and then is mathematically manipulated to ensure the resistance is in compliance with the accident analysis assumptions. Since the change involves no new modes of plant operation, nor any physical changes to the plant, the change should not create the possibility of a new or different kind of accident from any accident previously analyzed or evaluated,
Attachment 1 to AEP:NRC:1070 Page 6 Criterion 3 See Criterion 1 above.
Lastly, we note that the Commission has piovided guidance concerning the determination of significant hazards by providing examples (48 FR 14870) of amendments considered not likely to involve significant hazards consideration. The first example refers to changes that are purely administrative in nature. This example is applicable to the deletion of the footnote referring to the reporting requirements of T/S 6.9,1, The second example refer's to changes that, constitute an additional limi.tation, restriction, or control not presently included in the T/Ss: for example, more stringent surveillance requirements. The proposed surveillance requirement, as described above, is more restrictive than the present surveillance requirement. The additional restrictions are intended to ensure compliance with the accident analysis assumptions. The sixth Federal Register example refers to changes that may result in some increase to the probability or consequences of a previously analyzed accident, but the results of which are within clearly established acceptance limits. The T/S 4.0,4 exemption and limiting of applicability to a fully pressurized RCS we have p'roposed are similar to the Standard T/Ss, and therefore fit the stated example.