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 RIDSPROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9410170196 DOC.DATE:
94/10/07NOTARIZED:
NODOCKETIFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION PFITZPATRICK,E.
IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)R
SUBJECT:
Application foramendstolicensesDPR-586DPR-74,request changerereactorcoolantsystempressureisolation valves.DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR IENCLgSIZE:ITITLE:ORSubmittal:
GeneralDistribution NOTESRECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J INTERN:%LE,CENTZRNRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT EXTERNAL:
NOACCOPIESLTTRENCL111111111111RECIPIENT IDCODE/NAME PD3-1PDNRR/DE/EELB NRR/DRPWNRR/DSSA/SRXB OGC/HDS2NRCPDRCOPIESLTTRENCL111111111011DUNNOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEiVASTE!CONTACTTHE DOCUifENT CONTROLDESK,ROO!vIPl-37(EXT.504-2083)TOELINIINATEYOURMAML'ROD!DISTRIBUTION LISTSI'ORDOCUMENTS YOUDON"I'L'ED!TOTALNUMBEROFCOPIESREQUIRED:
LTTR13ENCL12 JE)III indianaMichiganPowerCompanyP.O.8ox16631Cofumbus, OH43216AEP:NRC:1180A DonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74ADDITIONAL INFORMATION FORTECHNICAL SPECIFICATION CHANGEREQUESTREACTORCOOLANTSYSTEMPRESSUREISOLATION VALVESU.S.NuclearRegulatory Commission DocumentControlDeskWashington, DC20555Attn:W.T.RussellOctober7,1994
DearMr.Russell:
Reference:
AEP:NRC:1180, Technical Specification ChangeRequest,November15,1993Inaccordwithrequestsfromyourstaff,thisletteranditsattachments supplyadditional information tosupportandamendourpreviousapplication, contained inthereferenced letter,foratechnical specification l,'T/S)changeforDonaldC.CookNuclearPlantUnits1and2.Specifically, inthereferenced letterweproposedandsupported thedeletionoftheoverlyrestrictive leakagelimitation requirements forReactor'oolantSystemPressureIsolation ValveslistedinT/STable3.4-0,whilemaintaining themore,reasonable testingrequirements forthesubjectvalvesinaccordance withASMESectionXI.Inconversations heldonSeptember 26,1994,yourstaffindicated thattherewerenotechnical concernswiththesubjectrequest;however,theysuggested aslightlydifferent approachtoachieving thesamechange.Insteadofdeletingthesubjecttestingrequirements fromtheT/Ss,thestaffsuggested andweagreedtoreplacethecurrentT/Stestingrequirements withthoserequiredbyASMESectionXI.9'410170196 941007PDRRDQDK050003i5I.....=..PDR,o(
Mr.W.T.Russell-2-AEP:NRC:1180A Attachment 1tothislettercontainstheadditional information requested byyourstafftosupportthesemodifications toourT/Ss.Foryourconvenience, allofthepreviously suppliedinformation inthereferenced letterhasbeenincludedinthisattachment, withchangesindicated intherighthandmargintoaddresstheNRC'srequested approachasoutlinedabove.TheaffectedT/Spages,markedtoshowproposedrevisions, areincludedinAttachment 2.Attachment 3containstheaffectedT/Spages,withproposedchangestypedinplace.Webelievethattheproposedchangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
TheT/Schangesoriginally proposedinthereferenced letterwerereviewedbythePlantNuclearSafetyReviewCommittee andtheNuclearSafetyandDesignReviewCommittee.
Thechangestothatsubmittal includedhereinhavebeenreviewedbythePlantNuclearSafetyReviewCommittee andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee atitsnextscheduled meeting.Incompliance withtherequirements of10CFR50.91(b)(1),
copiesofthisletteranditsattachments havebeentransmitted tothe~MichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.Thisletterissubmitted pursuantto10CFR50.30(b)and,assuchanoathstatement isattached.
Sincerely, VicePresident cadAttachments Mr.W.T.RussellAEP:NRC'1180A cc:A.A.BlindG.CharnoffJ.B.Martin-RegionIIINFEMSectionChiefNRCResidentInspector
-BridgmanJ.R.Padgett COUNTYOFFRANKLINE.E.Fitzpatrick, beingdulysworn,deposesandsaysthatheistheVicePresident oflicenseeIndianaMichiganPowerCompany,thathehasreadtheforgoingTechnical Specification ChangeRequestReactorCoolantSystemPressureIsolation Valvesandknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledge andbelief.Subscribed andsworntobeforemethis~4dayof19~%NTARYPUBLCR)TAD.HILLNOTARYPUBLIC.STATEOFOHIO 4il ATTACHMENT 1TOAEP'NRC:1180A DESCRIPTION OFPROPOSEDCHANGESAND10CFR50.92 SIGNIFICANT HAZARDSCONSIDERATION ANALYSIS~~
ATTACHMENT 1TOAEP:NRC:1180A Page1BACKGROUND TheReactorSafetyStudyWASH-1400/NUREG 75/014(Reference,l) analyzeda.so-called EventVSequenceresulting inanintersystem loss-of-coolant accident(ISLOCA).
Itwasconcluded thattheISLOCAwasasignificant contributor tocoredamagefrequency sincethecontainment isbypassedandreactorcoolantisreleaseddirectlytotheauxiliary building.
Asaresultoftheabovefinding,theUSNRCissuedaletter,"LWRPrimaryCoolantSystemPressureIsolation Valves,"datedFebruary25,1980,(Reference 2),requesting LWRlicensees toprovidethefollowing information:
'Describe thevalveconfiguration atyourplantandindicateifanEventVisolation valveconfiguration existswithintheClassIboundaryofthehighpressurepipingconnection PCSpipingtolowpressuresystempiping;e.g.,(1)twocheckvalvesinseries,or(2)twocheckvalvesinserieswithaMOVI2...,Ifeithero'ftheaboveEventVconfigurations existsmt.'yourfaci3.ity,'indicate whether.;:.continuous
'surveillance
'r'eqiodictests.are'e'ingaccomplished onsuchvalvestoensureintegrity.
Alsoindicatewhethervalveshavebeenknown,orfound,tolackintegrity; and3.IfeitheroftheaboveEventVconfigurations existatyourfacility, indicatewhetherplantprocedures shouldberevisedorifplantmodifications shouldbemadetoincreas'e reliability.
AEPSCresponded totheaboveUSNRCletterwithletterAEP:NRC:0371, "ReactorCoolantSystemPressureIsolation Valves,"datedMarch24,1980,(Reference 3).Inthisletter,theUSNRCwasinformedthatthefollowing valveconfigurations areusedatCookNuclearPlant:1)Aminimumofthreecheckvalvesinseries,2)Twocheckvalveswithaminimumofaclosedmotoroperatedvalveinseries, ATTACHMENT 1TOAEP:NRC:1180A Page23)Twocheckvalveswithaclosedhandoperatedvalveinseries,and/or4)Acheckvalvewithtwoclosedairoperatedvalves.inseries.AEP:NRC:0371 concluded that:"Therefore noEventVconfiguration existsattheCookNuclearPlant.Consequently, therequestsinItems2and3ofMr.Eisenhut's letterarenotapplicable totheCookNuclearPlant."OnApril20,1981,theUSNRCissuedan"OrderforModification ofLicensesConcerning PrimaryCoolantSystemPressureIsolation Valves"forCookNuclearPlant(Reference 4).Thisorderstatedthat"Wehaveconcluded thataWASH-1400 EventVvalveconfiguration existsatyourfacilityandthatthecorrective actionasdefinedintheattachedorderisnecessary."
AttachedtotheorderweretheTechnical Evaluation Report(TER)supporting theorderandthenewtechnical specifications (T/Ss)which,according totheorder,"...willensurepublichealthandsafetyovertheoperating lifeofyourfacility."
ThesenewT/Sswereincorporated atthattimeintotheoperating licensesforCookNuclear.Plant.,'h1987,'the'USNRC'.issued generic.,let<br.(GL)'.87-06;
"."Periodic Verific'ation ofLeak'TightIntegrity ofPressureIsolation
'Valves"'(Reference 5).InourresponsetothatGL,AEP:NRC:1041 (Reference 6),westatedthat12-SI-170L2, 12-SI-170L3, 12-RH-133, and12-RH-134 areleaktestedasperthesurveillance requirements intheT/Ss.Theproposedchangesinthissubmittal, therefore, modifyourresponsetoGL87-06.Finally,in1992,theUSNRCissuedinformation notice92-36,"Intersystem LOCAOutsideContainment" (Reference 7).Thisinformation noticelistedeleven"Observed PlantVulnerabilities toISLOCAPrecursors."
Areviewofthisinformation noticeconcluded thattheconcernsraisedareadequately addressed bycontrolscurrently inplaceorplannedattheCookNuclearPlant..TheproposedchangestotheT/Sswillnotalterthisconclusion becauseourresponsetotheinformation noticewasnotbasedonexistingT/Ss.
ATTACHMENT 1TOAEP'NRC'1180A Page3COOKNUCLEARPLANTIPEOnMay1,1992,AEPSCresponded togenericletter88-20(Reference 8),inAEP:NRC:1082E, Individual PlantExamination (IPE)submittal (Reference 9),andprovidedfurtherinformation ontheanalysisoftheISLOCAinReference 10.(SeetheEnclosure, tothis
Attachment:
DonaldC.CookNuclearPlant,PathsConsidered asPossibleEventV-Sequence LOCA,takenfromReference 10).Inthedetermination oftheISLOCAinitiating eventfrequency, leaktestingof12-SI-170L2, 12-SI-170L3, 12-RH-133, and12-RH-134, asrequiredbythesurveillance requirements intheT/Ss,wasaddressed.
TheIPEforCookNuclearPlantconcluded thattheISLOCAwastheaccidentthatcontributed theleasttotheoverallcoredamagefrequency.
Thecalculated ISLOCAinitiating eventfrequency wasapproximately 6.70E-07, andthecalculated probability ofISLOCAcoredamagewasapproximately 5.4E-08.Thecontribution tooverallcoredamagefrequency fromanISLOCAislessthan0.1%ofthe6.26E-05IPEcalculated coredamagefrequency perreactoryear.Itisseen,therefore, thatthecontribution fromanISLOCAeventatCookNuclearPlantisnegligible.
ACOMPARISON.
OFWASH1400VSCOOKCLEARPLANTWITH.RESPECT
'~TOXSOOATheISLOCA.accident isde'scribed inSection5.3.2.5ofWASH.-1400, andthequantification ofitscoredamagefrequency, isSoundinAppendixV,Section4.4ofWASH-1400.
Thecoredamagefrequency calculated inWASH-1400 is4.00E-06/reactor year.WASH-1400 evaluated threepathwaysoftwocheckvalvesinseries,andassumedthatthe600psiLowPressureInjection System(LPIS),onceexposedtoRCSpressure, wouldfailandcreateapproximately a6"effective diameterLOCA.Nootheraccidentinitiation featuresormitigating actionsweremodeled.IntheCookNuclearPlantIPE,ninedifferent pathwaysforanISLOCAeventwereanalyzed.
Thesepathways(seeEnclosure tothisAttachment),
consisted ofeitherthreecheckvalvesinseries,twocheckvalvesandaclosedmotoroperatedvalve(MOV)inseries,ortwonormallyclosedMOVsinseries.AlthoughWASH-1400 lookedatcheckvalveleaktestingasasensitivity
- analysis, theCookNuclearPlantIPEaccounted forthein-placeleaktestingwhen'alculating theprobability ofanISLOCAoccurring.
Inaddition, theCookNuclearPlantIPEmodeledmitigating actionsfortheISLOCAeventintheeventtree.The ATTACHMENT 1TOAEP:NRC:1180A Page4.lowpressureinjection systempipingwasreviewed, andfoundtobecapableofwithstanding thefullpressureofthereactorcoolantsystem.Onlyhoopstresseswerefoundtobesignificant, sinceafterinitiation ofanISLOCAtheheatuprateofthepipingwouldberelatively slow,minimizing thermalstresses.
Thus,isolation oftheLOCApathwayandpotentially successful mitigating activities arepossible.
TheIPEISLOCAinitiating eventfrequency wasapproximately anorderofmagnitude lowerthantheWASH-1400 coredamagefrequency (4.00E-06),
andtheIPEISLOCAcoredamagefrequency valuewasapproximately twoordersofmagnitude lowerthantheWASH-1400 values.Finally,toaddresstheimpactofremovingtheT/Srequirements andonlytesting12-SI-170L2, 12-SI-170L3, 12-RH-133, and12-RH-134 atarefueling outagefrequency, asensitivity runwasmadeinsupportofthissubmittal.
Sincetheinservice inspection programwilldiscoverarupturedvalve,theadditional T/Srequirement wasonlycreditedwiththeabilitytoidentifyastuckopenvalve.Thiscreditwasremovedforthissensitivity run.ItwasfoundthattheISLOCAinitiating eventfrequency, andISLOCAprobability ofcoredamagewouldalsoincreaseby5.4%tothemid5.00E-08range,andtheoverallcoredamagefrequency wouldremainunchanged.
Thus,theproposedT/Swillessentially
'rovideprotection equivalent totheexistingT/SfromanISLOCA.ISTPROGRAMThesubjectcheckvalvesofthissubmittal arecurrently beingtestedinMode5,ColdShutdown, asrequiredbytheT/Sssurveillance requirements priortogoingtoMode4,HotShutdown.
Theallowable leakratecannotexceed1gpm.IftheT/Ssaremodifiedasrequested, thesevalveswouldcontinuetobetestedundertheISTProgram(ASMEBoilerandPressureVesselCode,SectionXI),onarefueling outagefrequency, liketheirsistervalvesint'eotherloops'intheResidualHeatRemovalSystem.Theacceptance criteriafortheleaktestingofthesevalvesundertheISTProgramhasbeendefinedhereas0.5gpmpernominalinchofvalvesize,consistent withNUREG-1431 (Reference 12).
ATTACHMENT 1TOAEP:NRC:1180A Page5DESCRIPTION OFPROPOSEDTECHNICAL SPECIFICATION CHANGESTheproposedchangesarelistedbelow.Theyareidentical forbothunits.1~PT/S3.4.6.2f.Replaceinitsentirety.
2.T/S3.4.6.2APPLICABILITY:
Delete"**"andreplacewitha"*"3.T/S3.4.6.2ACTIONc.Delete"exceptwhen...by50$ormore."T/S3.4.6.2ACTIONc,footnote*.Deletethefootnote.
5.T/S3.4'.2APPLICABILITY, footnote**.ChangetheIt'lltoII*II6.T/S4.4.6.2.2.
Replaceitwiththefollowing text:"Eachreactor'oolantsystempressure.isolation valvespecified inTable3..4-.0'shallbe.,'demonstrate@'
OPERABLE'pursuant
.to..'Sp'ecification 4:05."7.T/S3/4.6.2,Table3.4-0.ReplacetheTableinitsentirety.
10CFR502SIGNIFICANT HAZARDSCONSIDERATION ANALYSISPer10CFR50.92,aproposedamendment toanoperating licensewillnotinvolveasignificant hazardsconsideration iftheproposedamendment satisfies thefollowing threecriteria:
1)Doesnotinvolveasignificant increaseintheprobability orconsequences ofan.accidentpreviously
- analyzed, 2)doesnotcreatethepossibility ofanewordifferent kindofaccidentfromanaccidentpreviously analyzedorevaluated, or3)doesnotinvolveasignificant reduction inamarginofsafety.
ATTACHMENT 1TOAEP:NRC:1180A Page6Criterion 1TheISLOCAisnotoneoftheaccidents previously analyzedinChapter14,SafetyAnalysis, oftheCookNuclearPlantUpdatedFinalSafetyAnalysisReport.Chapter14analyzesthelargebreakLOCAinSection14.3.1,and"lossofreactorcoolantfromsmallrupturedpipesorfromcracksinlargepipeswhichactuatestheECCS,"orsmallbreakLOCAinSection14.3.2.Therefore, theproposedT/Ssmodifications totheReactorCoolantSystempressureisolation valvesinTable3.4-0,willnotincreasetheprobability ortheconsequences ofthelargebreakorthesmallbreakLOCAspreviously analyzedfortheCookNuclearPlant.Criterion 2TheReactorCoolantSystempressureisolation valvesinTable3.4-0oftheT/SswereaddedbecauseWASH-1400 identified theISLOCAasasignificant contributor tocoredamagefrequency.
Theproposedmodifications ofthesubjectvalvesTechnical Specification surveillance requirements torelyonthetestingrequirements mandatedbytheIn-Service TestingProgramofASMEXIdoesnotcreatethepossibility ofanewordifferent kindofaccidentfromthelargebreakorthesmallbreakLOCAspreviouely
.analyzed'or.
theCookNuclearPlant.,I~riterfon 3Theproposedmodifications totheReactorCoolantSystempressureisolation valvestestingrequirements inTable3.4-0oftheT/Ss,willresultinthesevalvesonlybeingtestedonarefueling outagefrequency aspartoftheASMEB6PVCodeSectionXIISTProgram.Thissomewhatreducedtestingfrequency willresultinaslightincreaseintheISLOCAinitiating eventfrequency, andISLOCAcontribution tocoredamagefrequency by5.4%,fromlower5.00E-08/reactor yeartomid5.00E-08/reactor year.Thisinsignificant increasewillnotaffecttheoverallcoredamagefrequency of6.26E-05/reactor year.Therefore, itisconcluded thattheproposedchangestotheT/Srequirements fortheReactorCoolantSystempressureisolation valvesinTable3.4-0,willnotresultinasignificant reduction inthemarginofsafetythatexistsatCookNuclearPlanttopreventanISLOCAortomitigatetheconsequences ofanISLOCA.
ATTACHMENT 1TOAEP:NRC:1180A Page7REFERENCES WASH-1400/NUREG 75/014,ReactorSafetyStudy:AnAssessment ofAccidentRisksinU.S.Commercial NuclearPlants,USNRC,October1975.2.USNRCLettertoallLWRLicensees:
LWRPrimaryCoolantSystemPressureIsolation Valves,February25,1980.3.AEP:NRC:0371, ReactorCoolantSystemPressureIsolation Valves,March24,1980.4.Letter,S.A.Varga,USNRCtoJ.Dolan,IndianaandMichiganElectricCompany,OrderforModification ofLicensesConcerning PrimaryCoolantSystemPressureIsolation Valves,April20,1981.5.USNRCGenericLetter(GL)87-06,"PeriodicVerification ofLeakTightIntegrity ofPressureIsolation Valves,"March13,1987.6.7..AEP:NRC:1041, GenericLetter87-06,PeriodicVerification
'of'LeakTight'Integrity of"Pressure Isolation Valves>..November 12,3.987,'X~USNRCInformation Notice92-36,."Intersystem LOCAOutsideContainment,"
May,7,1992.8.Initiation oftheIndividual PlantExamination forSevereAccidentVulnerabilities
-10CFR50.54(f),
GenericLetterNo.'8-20, November23,1988.9.AEP:NRC:1082E, Individual PlantExamination Submittal, ResponsetoGenericLetter88-20,May1,1992.10.AEP:NRC:1082F, Individual PlantExamination ResponsetoNRCQuestions,
.February 24,1993.AEP:NRC:1180, Technical Specification ChangeRequest,ReactorCoolantSystemPressureIsolation Valves,November15,1993.12.NUREG-1431, StandardTechnical Specifications forWestinghouse Plants,September 1992.
ATTACHMENT 2TOAEP:NRC:1180A MARKED-UP TECHNICAL SPECIFICATION PAGES