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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
.ACCELERATED DIQGBUTION DEMONSTP TION SYSTEM REGULATORY INFORMATION DISTRIBUTION STEN (BIDS)
P ACCESSXQN NBR: 9206180194 DGC. DATE: 92/08/12 NOTARIZED: YES DOCKET (I:
! FACXL: 50-31,5 Donald C.
50-316 Donald C.
Cook Cook Nuclear Poeer P lant'nit ii Indiana 8 05000315 Nuclear Power Planti Unit 2. Xndiana N 05000316 AUTH. NANE AUTHOR AFFILIATXGN FITZPATRICK'. Indiana Nichigan Poeer Co. (formerly Indiana 5 Nichigan Ele RECIP. NAXE RECXr XENT AFFILIATION NURLEYi T. E. Document Control Branch (Document Control Desk3
SUBJECT:
Application for amends to Licenses DPR-58 DPR-74> modifying Zc Unit 1 TS 3. 3. 3. 8. Table 3. 3-11 5 Unit 2 TS 3. 3. 3. 6> Table
- 3. 3-10 to change min channels required to be operable for safettI valve position indicator acoustic monitor.
D DISTRIBUTION CODE: A001D COPIES RECEIVED: LTR iENCL j SIZE:
TITLE: OR Submittal: General Distribution NOTES:
REC I P IENT COPIES RECIPIENT COPIES ID CODE/NAI"!E LTTR ENCL ID CODE/N*NE LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 D
STANGi J 2 2 D I NTER MAL: NRR/DET/ESGB 1 NRR/DOEA/QTSB11 1 NRR/DST/SELB 7E 1 NRR/DST/6 I C BSH7 1 NRR/DST/SRXB BE 1 1 NUDGCS-ABSTRACT 1 GC/ 1 0, OGC/HDS2 1 0 FXLE 01 RES/DSXR/EXB 1 1 EXTERNAL: NRC PDR D
D NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMEPWS YOU DON'T NEED!
TOTAL NUMBER OF COPXES REQUIRED: LTTR ib ENCL 14
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l
Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 AEP:NRC:1170D Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 UNITS 1 AND 2 PRESSURIZER SAFETY VALVE POSITION INDICATOR ACOUSTIC MONITOR TECHNICAL SPECIFICATION AMENDMENT REQUEST U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Attn: T. E. Murley August 12, 1992 Dear Dr. Murley; This letter and its attachments constitute an application for Technical Specifications (T/Ss) changes for Donald C. Cook Nuclear Plant Units 1 and 2. Specifically, we are proposing to modify Unit 1 T/S 3.3.3.8 Table 3.3-11 and Unit 2 T/S 3.3.3.6 Table 3.3-10 to change the minimum channels operable for the pressurizer safety valve position indicator acoustic monitor (Instrument 14) to two out of three total from one per valve. We are also proposing to remove the *****footnotes and references to the *****footnotes that were added during the previous operating cycle for each unit and are no longer in effect.
Attachment 1 provides a detailed description of the proposed changes, the justification for the changes, and our proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50.92(c). Attachment 2 contains the existing T/Ss pages marked to reflect the proposed changes. Attachment 3 contains the proposed T/Ss pages.
The 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. J. R. Padgett of the Michigan Public Service Commission and to the Michigan Department of Public Health.
'i>
,
- 9208i80194 9208i2 P" ADOCK "I~DR, 050003i 5 PDR
ll Dr. T. E. Hurley AEP:NRC:1170D This letter is submitted pursuant to 10 CFR 50.54(f) and, as such, an oath of affirmation is enclosed.
Sincerely, E. E. Fitzpat ick Vice President dag Enclosure Attachments cc: D. H. Williams, Jr.
A. A. Blind - Bridgman J. R. Padgett G. Charnoff NFEH Section Chief A. B. Davis - Region III NRC Resident Inspector - Bridgman
COUNTY OF FRANKLIN E. E. Fitzpatrick, being duly sworn, deposes and says that he is the Vice President of licensee, Indiana Michigan Power Company, that he has read the forgoing Units 1 and 2 Pressurizer Safety Valve Position Indicator Acoustic Monitor Technical Specification Amendment Request, and knows the contents thereof; and that said contents are true to the best of his knowledge and belief.
Subscribed snd sworn to before me this lasr day of 19~(
NOTARY UBLIC
Attachment 1 to AEP:NRC:1170D 10CFR50.92 Determination for Proposed Changes to the Donald C. Cook Nuclear Plant Units 1 and 2 Technical Specifications
Attachment 1 to AEP:NRC:1170D Page 1 1.0 SECTIONS TO BE CHANGED Unit 1: Table 3.3-11 of Technical Specification (T/S) 3.3.3.8.
Unit 2: Table 3.3-10 'of Technical Specification (T/S) 3.3.3.6.
2.0 EXTENT OF CHANGES We are proposing to change the minimum number of channels operable for the pressurizer safety valve position indicator acoustic monitors (Instrument 14 in Unit 1 T/S Table 3.3-11 and Unit 2 T/S Table 3.3-
- 10) from one per valve to two out of three total.
We are also proposing to delete the *****footnotes and references to the ***** footnotes in the same tables because the referenced operating cycle has been completed and they are no longer applicable.
3.0 CHANGES RE UESTED Identical changes are being sought for both the Unit 1 and Unit 2 Technical Specifications.
3.1 UNIT 1 We are proposing to make the following changes to the Unit 1 -"""
Technical Specifications.
Revise Table 3 3-11 "Post-Accident Monitorin Instrumentation" Currently, Instrument 14 of Table 3.3-11 has an exception denoted by a *****footnote. We are proposing to delete this footnote.
Also, Instrument 14 of Table 3.3-11 requires that as a minimum, one channel per valve be operable. We are proposing to change this to require that, as a minimum, two out of three channels total be operable.
3.2 UNIT 2 We are proposing to make the following changes to the Unit 2 Technical Specifications.
Revise Table 3 3-10 "Post-Accident Monitorin Instrumentation" Currently, Instrument 14 of Table 3.3-10 has an exception denoted by a *****footnote. We are proposing to delete this footnote.
Attachment 1 to AEP:NRC:1170D Page 2 Also, Instrument 14 of Table 3.3-10 requires that, as a minimum, one channel per valve be operable. We are proposing to change this to require that, as a minimum, two out of three channels total be operable.
4.0 DISCUSSION S stem Descri tion The reactor coolant system is protected against overpressurization by control and protective circuits, such as the pressurizer pressure high reactor trip, and by the three power-operated relief and three safety valves connected to the top of the pressurizer. Upon opening, these valves discharge steam into the pressurizer relief tank, which condenses and collects the valve effluent. This submittal addresses the monitoring instrumentation associated with the pressurizer safety valves and the pressurizer relief tank.
The purpose of the acoustic monitors is to provide the operator with information regarding safety valve position during post-accident conditions. Two independent monitoring systems exist that alert the operator to the passage of steam through the safety valves due to valve lift. In one of the independent monitoring systems, an acoustic monitor (QR-107A, B, and C) on the discharge of each safety valve detects acoustic vibrations generated from the steam flowing through the pressurizer safety valve, and actuates an alarm and provides a visual display of percentage of full flow in the control room. Due to the magnitude of the acoustic vibrations and the sensitivity of the instrumentation, all three monitors will detect the opening of any one of the three pressurizer safety valves. The acoustic monitors were added to meet the requirements of NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short Term Recommendations," and NUREG-0737, "Clarification of TMI Action Plan Requirements," and are environmentally qualified.
During normal operation the acoustic monitors are not used to detect pressurizer safety valve leakage. In the other independent monitoring system, a temperature sensor (NTA-151, -152, -153) downstream of the acoustic sensor generates a signal that actuates a control room alarm when a temperature increase is experienced in the line, as would be the case if the pressurizer safety valve released steam. The attached simplified diagram illustrates this portion of the system. Indications of the temperature, pressure and water level of the pressurizer safety relief tank are also provided in the control room and provide additional indication of pressurizer safety valve leakage during normal operation. The temperature of the water
Attachment 1 to AEP:NRC:1170D Page 3 in the pressurizer relief tank is measured and indicated by instrument number NTA-351. An alarm resulting from this signal is actuated by high ~ater temperature, and informs the operator that cooling of the "pressurizer relief tank contents is required. The pressurizer relief tank pressure transmitter (NPA-351) operates a high and low pressure alarm. The pressurizer relief tank level transmitter (NLA-351) provides a signal for a level indication and a high and low tank level alarms. Consequently, a discharge from one of the pressurizer safety valves will cause these instruments to provide an alarm indication in the control room. All downstream temperature, pressure, and tank level indications are not environmentally qualified.
In an emergency situation, the operator does not use a signal from the pressurizer safety valve position indicator acoustic monitors as, an action initiator. The operator responds to other indications of loss of reactor coolant inventory. As the operator does not have direct control of the pressurizer safety valve, "where" the loss of inventory is occurring is of less importance than compensating for the loss of inventory. In addition, the Cook Nuclear Plant emergency operating procedures do not reference the pressurizer safety valve position indicator acoustic monitors for the reason stated above.
Reason for Pro osed Technical S ecification Chan e Re uest The request to remove the footnotes and references to the footnotes is made in order to clarify the Technical Specifications and to remove unnecessary information.
With regard to changing the minimum number of operable channels from one per valve to two out of three total, in letters AEP:NRC:1170 dated December 16, 1991 and AEP:NRC:1170B dated January 22, 1992, amendments were requested to the Unit 2 and Unit 1 Technical Specifications, respectively, to introduce the *****footnotes which are proposed to be deleted by this letter. These requests were made on an expedited basis to preclude an unwarranted shutdown of each reactor unit. We believe the relief that was granted on a temporary basis can be safely implemented on a permanent basis. Since most of the pressurizer safety valve position indicator acoustic monitor system is inaccessible during power operation, this has the advantage of potentially eliminating the need for plant shutdown or for expedited or emergency T/S relief should an acoustic monitor become inoperable in the future.
We believe that having an acoustic monitor inoperable does not warrant reactor and plant shutdown. As the T/Ss are currently stated, should one pressurizer safety valve position indicator
4 Attachment 1 to AEP:NRC:1170D Page 4 acoustic monitor become inoperable, it must be restored to operable status within thirty days or the unit must be in hot shutdown within the subsequent twelve hours. Thermal cycling from unwarranted plant shutdowns increases the likelihood of reactor vessel fatigue stress cycles and unnecessarily challenges the safety systems. Because a signal from the pressurizer safety valve position indicator acoustic monitors is not necessary nor used to ensure the safe shutdown of the unit even if a pressurizer safety valve is opened or stuck open during an emergency situation, we believe that a plant shutdown due to an inoperable acoustic monitor would be unwarranted.
Justification for Pro osed Technical S ecification Chan es For the removal of the footnotes and references to the footnotes, the operating cycles for which the footnotes were valid have been concluded. Therefore, the footnotes are no longer applicable and should be removed.
For the reduction in the minimum number of channels oper'able from one per valve to two out of three total, first, the temperature sensor installed downstream of each pressurizer safety valve provides indication and alarm on both the control room panel and the plant computer. Past experience has shown these temperature sensors to be effective leak detection devices.
In addition, the pressurizer safety valve position indicator acoustic monitoring system has shown in the past that when one of the pressurizer safety valves opens, all -three safety valve position indicator acoustic monitor channels are actuated. This is caused by the sensitivity of the accelerometers and the fact that the three safety valves and their associated acoustic monitor sensors are in close proximity to each other and tied together through common piping. Thus, if the pressurizer safety valve associated with the inoperable position indicator acoustic monitor channel discharges, the remaining two position indicator acoustic monitor channels would alert the operator, An additional benefit to this effect is that it also enables the operator to discriminate a valid alarm indication from an invalid alarm indication.
Other instrumentation exists that provides the operator with indication of pressurizer safety valve actuation. The pressurizer safety valves discharge into the pressurizer relief tank. The temperature, pressure, and liquid level of the tank are indicated and alarmed in the control room. A change in these parameters would alarm and alert the operator of a safety valve discharge .condition.
Attachment 1 to AEP:NRC:1170D Page 5 Finally, in an emergency situation, the operator does not use a signal from the pressurizer safety valve position indicator acoustic monitors as an action initiator. The operator responds to other indications of loss of reactor coolant inventory. As 'the operator does not have direct control of the pressurizer safety valve, "where" the loss of inventory is occurring is of less importance than compensating for the loss of inventory. In addition, the Cook Nuclear Plant emergency operating procedures do not reference the pressurizer safety valve position indicator acoustic monitors.
5.0 NO SIGNIFICANT HAZARDS DETERMINATION We have evaluated the proposed T/Ss exemption and have determined that it should not require a significant hazards consideration based Operation of the Cook on the criteria established in 10CFR50.92(c).
Nuclear Plant in accordance with the proposed amendment will not:
(1) Involve a si nificant increase in the robabilit or conse uences of an accident reviousl evaluated.
Although the proposed exemption results in the operator having one less source of information on plant status, it does not create a significant increase in the probability or consequences of an accident previously evaluated. The acoustic monitors do not perform a function vital to safe shutdown or to the isolation of the reactor, or the reactor coolant system pressure boundary, nor is there a mechanism involving an operable or inoperable pressurizer safety valve acoustic monitor which would initiate an accident. These monitors were added to meet the requirements of NUREG-0578 and NUREG-0737. During normal operations, other instrumentation exists that provides the operator with indication of safety valve actuation. The acoustic monitors are not necessary to and are not used in the emergency operating procedures. In addition, the acoustic monitors being inoperable will not result in an uncontrolled release of radiation to the environment and will not initiate an accident.
Finally, although the operator may have one less channel operable, the operator receives no less information than if all three channels are operable because"one valve opening causes all operable channels to actuate Therefore, we conclude that the proposed T/Ss changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
(2) Create the ossibilit of a new or different kind of accident from an reviousl anal zed
.As previously stated, the purpose of the acoustic monitor is 'to provide the operator with information regarding safety valve position
E tC I I'
Attachment 1 to AEP:NRC:1170D Page 6 that may assist in the mitigation of the consequences of an accident.
Specifically, it provides information that a safety valve has lifted.
However, the operator has other mechanisms for obtaining equivalent information. In addition, the signals generated by an acoustic monitor do not initiate any other equipment actuation, nor will the inoperability of an acoustic monitor initiate any accident.
Consequently, the proposed T/Ss changes do not create the possibility of a new or different kind of accident from any previously analyzed.
(3) Involve a si nificant reduction in a mar in of safet The proposed T/Ss changes result in the operator potentially having one less source of information on plant status. However, we believe the margin of safety is not reduced for several reasons. First, the operator is provided with other viable flow detection devices to determine pressurizer safety valve position, i.e., the temperature sensor on the discharge line associated with the inoperable acoustic monitor, and pressurizer relief tank level (NLA-351), temperature (NTA-351) and pressure (NPA-351) indications. Also, the acoustic monitors are not used by the operators in an emergency situation, as.
the operator relies on other indications of loss of reactor coolant inventory per the emergency operating procedures. In addition, previous experience with th'e pressurizer safety valve position indicator acoustic monitoring system has shown that, when any one of the pressurizer safety valves opens, all three safety valve position indicator acoustic monitors are actuated. Because of this, the operator receives no less information regardless if only two or three channels are operable.
Based on the above, we believe that having an acoustic monitor inoperable does not warrant reactor and plant shutdown. As the T/Ss are currently stated, should one pressurizer safety valve position indicator acoustic monitor become inoperable, it must be restored to operable status within thirty days or the unit must be in hot shutdown within the subsequent twelve hours. Thermal cycling from unwarranted plant shutdowns increases the likelihood of reactor vessel embrittlement and unnecessarily challenges the safety systems.
Because a signal from the pressurizer safety valve position indicator acoustic monitors is not necessary nor used to ensure the safe shutdown of the unit even if a pressurizer safety valve is opened or stuck open during an emergency situation, we believe that a plant shutdown due to an inoperable acoustic monitor would be unwarranted.
We believe that the unit can be operated safely and that we would still meet the intent of NUREG-0538 and NUREG-0737 with only two out of three pressurizer safety valve position indicator acoustic monitors operable.
Attachment 1 to AEP:NRC:1170D Page 7 6.0 PENDING T Ss PROPOSALS IMPACTING THIS SUBMITTAL There is currently one other T/Ss proposal under review that impacts this submittal. In our submittal AEP:NRC:1137, dated February 15, 1991, changes are proposed to Unit 1 T/S page 3/4 3-55 and Unit 2 T/S page 3/4 3-46. The changes proposed in this submittal (AEP:NRC:1170D) are to be made in addition to those in AEP:NRC:1137.
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/UPTURN DLSCS PRESSURlZgg RELIEF TANK