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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
ACCELERATEDRIDSPROCESSING)REGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9410170196DOC.DATE:94/10/07NOTARIZED:NODOCKETIFACIL:50-315DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATIONPFITZPATRICK,E.IndianaMichiganPowerCo.(formerlyIndiana&MichiganEleRECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)R
SUBJECT:
ApplicationforamendstolicensesDPR-586DPR-74,requestchangerereactorcoolantsystempressureisolationvalves.DISTRIBUTIONCODE:AOOIDCOPIESRECEIVED:LTRIENCLgSIZE:ITITLE:ORSubmittal:GeneralDistributionNOTESRECIPIENTIDCODE/NAMEPD3-1LAHICKMAN,JINTERN:%LE,CENTZRNRR/DRCH/HICBNRR/DSSA/SPLBNUDOCS-ABSTRACTEXTERNAL:NOACCOPIESLTTRENCL111111111111RECIPIENTIDCODE/NAMEPD3-1PDNRR/DE/EELBNRR/DRPWNRR/DSSA/SRXBOGC/HDS2NRCPDRCOPIESLTTRENCL111111111011DUNNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEiVASTE!CONTACTTHEDOCUifENTCONTROLDESK,ROO!vIPl-37(EXT.504-2083)TOELINIINATEYOURMAML'ROD!DISTRIBUTIONLISTSI'ORDOCUMENTSYOUDON"I'L'ED!TOTALNUMBEROFCOPIESREQUIRED:LTTR13ENCL12 JE)III indianaMichiganPowerCompanyP.O.8ox16631Cofumbus,OH43216AEP:NRC:1180ADonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74ADDITIONALINFORMATIONFORTECHNICALSPECIFICATIONCHANGEREQUESTREACTORCOOLANTSYSTEMPRESSUREISOLATIONVALVESU.S.NuclearRegulatoryCommissionDocumentControlDeskWashington,DC20555Attn:W.T.RussellOctober7,1994
DearMr.Russell:
Reference:
AEP:NRC:1180,TechnicalSpecificationChangeRequest,November15,1993Inaccordwithrequestsfromyourstaff,thisletteranditsattachmentssupplyadditionalinformationtosupportandamendourpreviousapplication,containedinthereferencedletter,foratechnicalspecificationl,'T/S)changeforDonaldC.CookNuclearPlantUnits1and2.Specifically,inthereferencedletterweproposedandsupportedthedeletionoftheoverlyrestrictiveleakagelimitationrequirementsforReactor'oolantSystemPressureIsolationValveslistedinT/STable3.4-0,whilemaintainingthemore,reasonabletestingrequirementsforthesubjectvalvesinaccordancewithASMESectionXI.InconversationsheldonSeptember26,1994,yourstaffindicatedthattherewerenotechnicalconcernswiththesubjectrequest;however,theysuggestedaslightlydifferentapproachtoachievingthesamechange.InsteadofdeletingthesubjecttestingrequirementsfromtheT/Ss,thestaffsuggestedandweagreedtoreplacethecurrentT/StestingrequirementswiththoserequiredbyASMESectionXI.9'410170196941007PDRRDQDK050003i5I.....=..PDR,o(
Mr.W.T.Russell-2-AEP:NRC:1180AAttachment1tothislettercontainstheadditionalinformationrequestedbyyourstafftosupportthesemodificationstoourT/Ss.Foryourconvenience,allofthepreviouslysuppliedinformationinthereferencedletterhasbeenincludedinthisattachment,withchangesindicatedintherighthandmargintoaddresstheNRC'srequestedapproachasoutlinedabove.TheaffectedT/Spages,markedtoshowproposedrevisions,areincludedinAttachment2.Attachment3containstheaffectedT/Spages,withproposedchangestypedinplace.Webelievethattheproposedchangeswillnotresultin(1)asignificantchangeinthetypesofeffluentsorasignificantincreaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificantincreaseinindividualorcumulativeoccupationalradiationexposure.TheT/SchangesoriginallyproposedinthereferencedletterwerereviewedbythePlantNuclearSafetyReviewCommitteeandtheNuclearSafetyandDesignReviewCommittee.ThechangestothatsubmittalincludedhereinhavebeenreviewedbythePlantNuclearSafetyReviewCommitteeandwillbereviewedbytheNuclearSafetyandDesignReviewCommitteeatitsnextscheduledmeeting.Incompliancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtothe~MichiganPublicServiceCommissionandtotheMichiganDepartmentofPublicHealth.Thisletterissubmittedpursuantto10CFR50.30(b)and,assuchanoathstatementisattached.Sincerely,VicePresidentcadAttachments Mr.W.T.RussellAEP:NRC'1180Acc:A.A.BlindG.CharnoffJ.B.Martin-RegionIIINFEMSectionChiefNRCResidentInspector-BridgmanJ.R.Padgett COUNTYOFFRANKLINE.E.Fitzpatrick,beingdulysworn,deposesandsaysthatheistheVicePresidentoflicenseeIndianaMichiganPowerCompany,thathehasreadtheforgoingTechnicalSpecificationChangeRequestReactorCoolantSystemPressureIsolationValvesandknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledgeandbelief.Subscribedandsworntobeforemethis~4dayof19~%NTARYPUBLCR)TAD.HILLNOTARYPUBLIC.STATEOFOHIO 4il ATTACHMENT1TOAEP'NRC:1180ADESCRIPTIONOFPROPOSEDCHANGESAND10CFR50.92SIGNIFICANTHAZARDSCONSIDERATIONANALYSIS~~
ATTACHMENT1TOAEP:NRC:1180APage1BACKGROUNDTheReactorSafetyStudyWASH-1400/NUREG75/014(Reference,l)analyzeda.so-calledEventVSequenceresultinginanintersystemloss-of-coolantaccident(ISLOCA).ItwasconcludedthattheISLOCAwasasignificantcontributortocoredamagefrequencysincethecontainmentisbypassedandreactorcoolantisreleaseddirectlytotheauxiliarybuilding.Asaresultoftheabovefinding,theUSNRCissuedaletter,"LWRPrimaryCoolantSystemPressureIsolationValves,"datedFebruary25,1980,(Reference2),requestingLWRlicenseestoprovidethefollowinginformation:'DescribethevalveconfigurationatyourplantandindicateifanEventVisolationvalveconfigurationexistswithintheClassIboundaryofthehighpressurepipingconnectionPCSpipingtolowpressuresystempiping;e.g.,(1)twocheckvalvesinseries,or(2)twocheckvalvesinserieswithaMOVI2...,Ifeithero'ftheaboveEventVconfigurationsexistsmt.'yourfaci3.ity,'indicatewhether.;:.continuous'surveillance'r'eqiodictests.are'e'ingaccomplishedonsuchvalvestoensureintegrity.Alsoindicatewhethervalveshavebeenknown,orfound,tolackintegrity;and3.IfeitheroftheaboveEventVconfigurationsexistatyourfacility,indicatewhetherplantproceduresshouldberevisedorifplantmodificationsshouldbemadetoincreas'ereliability.AEPSCrespondedtotheaboveUSNRCletterwithletterAEP:NRC:0371,"ReactorCoolantSystemPressureIsolationValves,"datedMarch24,1980,(Reference3).Inthisletter,theUSNRCwasinformedthatthefollowingvalveconfigurationsareusedatCookNuclearPlant:1)Aminimumofthreecheckvalvesinseries,2)Twocheckvalveswithaminimumofaclosedmotoroperatedvalveinseries, ATTACHMENT1TOAEP:NRC:1180APage23)Twocheckvalveswithaclosedhandoperatedvalveinseries,and/or4)Acheckvalvewithtwoclosedairoperatedvalves.inseries.AEP:NRC:0371concludedthat:"ThereforenoEventVconfigurationexistsattheCookNuclearPlant.Consequently,therequestsinItems2and3ofMr.Eisenhut'sletterarenotapplicabletotheCookNuclearPlant."OnApril20,1981,theUSNRCissuedan"OrderforModificationofLicensesConcerningPrimaryCoolantSystemPressureIsolationValves"forCookNuclearPlant(Reference4).Thisorderstatedthat"WehaveconcludedthataWASH-1400EventVvalveconfigurationexistsatyourfacilityandthatthecorrectiveactionasdefinedintheattachedorderisnecessary."AttachedtotheorderweretheTechnicalEvaluationReport(TER)supportingtheorderandthenewtechnicalspecifications(T/Ss)which,accordingtotheorder,"...willensurepublichealthandsafetyovertheoperatinglifeofyourfacility."ThesenewT/SswereincorporatedatthattimeintotheoperatinglicensesforCookNuclear.Plant.,'h1987,'the'USNRC'.issuedgeneric.,let<br.(GL)'.87-06;"."PeriodicVerific'ationofLeak'TightIntegrityofPressureIsolation'Valves"'(Reference5).InourresponsetothatGL,AEP:NRC:1041(Reference6),westatedthat12-SI-170L2,12-SI-170L3,12-RH-133,and12-RH-134areleaktestedasperthesurveillancerequirementsintheT/Ss.Theproposedchangesinthissubmittal,therefore,modifyourresponsetoGL87-06.Finally,in1992,theUSNRCissuedinformationnotice92-36,"IntersystemLOCAOutsideContainment"(Reference7).Thisinformationnoticelistedeleven"ObservedPlantVulnerabilitiestoISLOCAPrecursors."AreviewofthisinformationnoticeconcludedthattheconcernsraisedareadequatelyaddressedbycontrolscurrentlyinplaceorplannedattheCookNuclearPlant..TheproposedchangestotheT/SswillnotalterthisconclusionbecauseourresponsetotheinformationnoticewasnotbasedonexistingT/Ss.
ATTACHMENT1TOAEP'NRC'1180APage3COOKNUCLEARPLANTIPEOnMay1,1992,AEPSCrespondedtogenericletter88-20(Reference8),inAEP:NRC:1082E,IndividualPlantExamination(IPE)submittal(Reference9),andprovidedfurtherinformationontheanalysisoftheISLOCAinReference10.(SeetheEnclosure,tothis
Attachment:
DonaldC.CookNuclearPlant,PathsConsideredasPossibleEventV-SequenceLOCA,takenfromReference10).InthedeterminationoftheISLOCAinitiatingeventfrequency,leaktestingof12-SI-170L2,12-SI-170L3,12-RH-133,and12-RH-134,asrequiredbythesurveillancerequirementsintheT/Ss,wasaddressed.TheIPEforCookNuclearPlantconcludedthattheISLOCAwastheaccidentthatcontributedtheleasttotheoverallcoredamagefrequency.ThecalculatedISLOCAinitiatingeventfrequencywasapproximately6.70E-07,andthecalculatedprobabilityofISLOCAcoredamagewasapproximately5.4E-08.ThecontributiontooverallcoredamagefrequencyfromanISLOCAislessthan0.1%ofthe6.26E-05IPEcalculatedcoredamagefrequencyperreactoryear.Itisseen,therefore,thatthecontributionfromanISLOCAeventatCookNuclearPlantisnegligible.ACOMPARISON.OFWASH1400VSCOOKCLEARPLANTWITH.RESPECT'~TOXSOOATheISLOCA.accidentisde'scribedinSection5.3.2.5ofWASH.-1400,andthequantificationofitscoredamagefrequency,isSoundinAppendixV,Section4.4ofWASH-1400.ThecoredamagefrequencycalculatedinWASH-1400is4.00E-06/reactoryear.WASH-1400evaluatedthreepathwaysoftwocheckvalvesinseries,andassumedthatthe600psiLowPressureInjectionSystem(LPIS),onceexposedtoRCSpressure,wouldfailandcreateapproximatelya6"effectivediameterLOCA.Nootheraccidentinitiationfeaturesormitigatingactionsweremodeled.IntheCookNuclearPlantIPE,ninedifferentpathwaysforanISLOCAeventwereanalyzed.Thesepathways(seeEnclosuretothisAttachment),consistedofeitherthreecheckvalvesinseries,twocheckvalvesandaclosedmotoroperatedvalve(MOV)inseries,ortwonormallyclosedMOVsinseries.AlthoughWASH-1400lookedatcheckvalveleaktestingasasensitivityanalysis,theCookNuclearPlantIPEaccountedforthein-placeleaktestingwhen'alculatingtheprobabilityofanISLOCAoccurring.Inaddition,theCookNuclearPlantIPEmodeledmitigatingactionsfortheISLOCAeventintheeventtree.The ATTACHMENT1TOAEP:NRC:1180APage4.lowpressureinjectionsystempipingwasreviewed,andfoundtobecapableofwithstandingthefullpressureofthereactorcoolantsystem.Onlyhoopstresseswerefoundtobesignificant,sinceafterinitiationofanISLOCAtheheatuprateofthepipingwouldberelativelyslow,minimizingthermalstresses.Thus,isolationoftheLOCApathwayandpotentiallysuccessfulmitigatingactivitiesarepossible.TheIPEISLOCAinitiatingeventfrequencywasapproximatelyanorderofmagnitudelowerthantheWASH-1400coredamagefrequency(4.00E-06),andtheIPEISLOCAcoredamagefrequencyvaluewasapproximatelytwoordersofmagnitudelowerthantheWASH-1400values.Finally,toaddresstheimpactofremovingtheT/Srequirementsandonlytesting12-SI-170L2,12-SI-170L3,12-RH-133,and12-RH-134atarefuelingoutagefrequency,asensitivityrunwasmadeinsupportofthissubmittal.Sincetheinserviceinspectionprogramwilldiscoverarupturedvalve,theadditionalT/Srequirementwasonlycreditedwiththeabilitytoidentifyastuckopenvalve.Thiscreditwasremovedforthissensitivityrun.ItwasfoundthattheISLOCAinitiatingeventfrequency,andISLOCAprobabilityofcoredamagewouldalsoincreaseby5.4%tothemid5.00E-08range,andtheoverallcoredamagefrequencywouldremainunchanged.Thus,theproposedT/Swillessentially'rovideprotectionequivalenttotheexistingT/SfromanISLOCA.ISTPROGRAMThesubjectcheckvalvesofthissubmittalarecurrentlybeingtestedinMode5,ColdShutdown,asrequiredbytheT/SssurveillancerequirementspriortogoingtoMode4,HotShutdown.Theallowableleakratecannotexceed1gpm.IftheT/Ssaremodifiedasrequested,thesevalveswouldcontinuetobetestedundertheISTProgram(ASMEBoilerandPressureVesselCode,SectionXI),onarefuelingoutagefrequency,liketheirsistervalvesint'eotherloops'intheResidualHeatRemovalSystem.TheacceptancecriteriafortheleaktestingofthesevalvesundertheISTProgramhasbeendefinedhereas0.5gpmpernominalinchofvalvesize,consistentwithNUREG-1431(Reference12).
ATTACHMENT1TOAEP:NRC:1180APage5DESCRIPTIONOFPROPOSEDTECHNICALSPECIFICATIONCHANGESTheproposedchangesarelistedbelow.Theyareidenticalforbothunits.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.Replaceitwiththefollowingtext:"Eachreactor'oolantsystempressure.isolationvalvespecifiedinTable3..4-.0'shallbe.,'demonstrate@'OPERABLE'pursuant.to..'Sp'ecification4:05."7.T/S3/4.6.2,Table3.4-0.ReplacetheTableinitsentirety.10CFR502SIGNIFICANTHAZARDSCONSIDERATIONANALYSISPer10CFR50.92,aproposedamendmenttoanoperatinglicensewillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentsatisfiesthefollowingthreecriteria:1)Doesnotinvolveasignificantincreaseintheprobabilityorconsequencesofan.accidentpreviouslyanalyzed,2)doesnotcreatethepossibilityofanewordifferentkindofaccidentfromanaccidentpreviouslyanalyzedorevaluated,or3)doesnotinvolveasignificantreductioninamarginofsafety.
ATTACHMENT1TOAEP:NRC:1180APage6Criterion1TheISLOCAisnotoneoftheaccidentspreviouslyanalyzedinChapter14,SafetyAnalysis,oftheCookNuclearPlantUpdatedFinalSafetyAnalysisReport.Chapter14analyzesthelargebreakLOCAinSection14.3.1,and"lossofreactorcoolantfromsmallrupturedpipesorfromcracksinlargepipeswhichactuatestheECCS,"orsmallbreakLOCAinSection14.3.2.Therefore,theproposedT/SsmodificationstotheReactorCoolantSystempressureisolationvalvesinTable3.4-0,willnotincreasetheprobabilityortheconsequencesofthelargebreakorthesmallbreakLOCAspreviouslyanalyzedfortheCookNuclearPlant.Criterion2TheReactorCoolantSystempressureisolationvalvesinTable3.4-0oftheT/SswereaddedbecauseWASH-1400identifiedtheISLOCAasasignificantcontributortocoredamagefrequency.TheproposedmodificationsofthesubjectvalvesTechnicalSpecificationsurveillancerequirementstorelyonthetestingrequirementsmandatedbytheIn-ServiceTestingProgramofASMEXIdoesnotcreatethepossibilityofanewordifferentkindofaccidentfromthelargebreakorthesmallbreakLOCAspreviouely.analyzed'or.theCookNuclearPlant.,I~riterfon3TheproposedmodificationstotheReactorCoolantSystempressureisolationvalvestestingrequirementsinTable3.4-0oftheT/Ss,willresultinthesevalvesonlybeingtestedonarefuelingoutagefrequencyaspartoftheASMEB6PVCodeSectionXIISTProgram.ThissomewhatreducedtestingfrequencywillresultinaslightincreaseintheISLOCAinitiatingeventfrequency,andISLOCAcontributiontocoredamagefrequencyby5.4%,fromlower5.00E-08/reactoryeartomid5.00E-08/reactoryear.Thisinsignificantincreasewillnotaffecttheoverallcoredamagefrequencyof6.26E-05/reactoryear.Therefore,itisconcludedthattheproposedchangestotheT/SrequirementsfortheReactorCoolantSystempressureisolationvalvesinTable3.4-0,willnotresultinasignificantreductioninthemarginofsafetythatexistsatCookNuclearPlanttopreventanISLOCAortomitigatetheconsequencesofanISLOCA.
ATTACHMENT1TOAEP:NRC:1180APage7REFERENCESWASH-1400/NUREG75/014,ReactorSafetyStudy:AnAssessmentofAccidentRisksinU.S.CommercialNuclearPlants,USNRC,October1975.2.USNRCLettertoallLWRLicensees:LWRPrimaryCoolantSystemPressureIsolationValves,February25,1980.3.AEP:NRC:0371,ReactorCoolantSystemPressureIsolationValves,March24,1980.4.Letter,S.A.Varga,USNRCtoJ.Dolan,IndianaandMichiganElectricCompany,OrderforModificationofLicensesConcerningPrimaryCoolantSystemPressureIsolationValves,April20,1981.5.USNRCGenericLetter(GL)87-06,"PeriodicVerificationofLeakTightIntegrityofPressureIsolationValves,"March13,1987.6.7..AEP:NRC:1041,GenericLetter87-06,PeriodicVerification'of'LeakTight'Integrityof"PressureIsolationValves>..November12,3.987,'X~USNRCInformationNotice92-36,."IntersystemLOCAOutsideContainment,"May,7,1992.8.InitiationoftheIndividualPlantExaminationforSevereAccidentVulnerabilities-10CFR50.54(f),GenericLetterNo.'8-20,November23,1988.9.AEP:NRC:1082E,IndividualPlantExaminationSubmittal,ResponsetoGenericLetter88-20,May1,1992.10.AEP:NRC:1082F,IndividualPlantExaminationResponsetoNRCQuestions,.February24,1993.AEP:NRC:1180,TechnicalSpecificationChangeRequest,ReactorCoolantSystemPressureIsolationValves,November15,1993.12.NUREG-1431,StandardTechnicalSpecificationsforWestinghousePlants,September1992.
ATTACHMENT2TOAEP:NRC:1180AMARKED-UPTECHNICALSPECIFICATIONPAGES
