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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
A.CCEI.EEBBOCUMENTBISUTIONSYSTEMREGULORYINFORMATIONDISTRIBUTSYSTEM(RIDS)ACCESSIONNBR:9311190228DOC.DATE:93/11/15NOTARIZED:YESDOCKETFACIL:50-315DonaldC.CookNuclearPowerPlant,Unit1,XndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATIONFITZPATRICK,E.IndianaMichiganPowerCo.(formerlyIndiana6MichiganEleRECIP.NAMERECIPIENTAFFILIATIONMURLEY,T.E.DocumentControlBranch(DocumentControlDesk)
SUBJECT:
ApplicationforamendstolicensesDPR-586DPR-74,revisingTS3/4.6.2,"RCSOperationalLeakage"bydeletingTable3.4-0,"RCSPressureIsolationValves,"LCO3.4.6.2f6Actionc&SRs4.4.6.2.2forbothunits.DISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:GeneralDistributionDNOTES:RECIPIENTIDCODE/NAMEPD3-1LANETZEL,BINTERNAL:NRR/DE/EELBNRR/DRCH/HICBNRR/DSSA/SRXBOC/LFDCBRE5OlEXTERNAL:NRCPDRCOPIESLTTRENCL1122111111101111RECIPIENTIDCODE/NAMEPD3-1PDNRR/DORS/OTSBNRR/DSSA/SPLBNUDOCS-ABSTRACTOGC/HDS2NSICCOPIESLTTRENCL111111111011DDSDSDNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.504-2065)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!DTOTALNUMBEROFCOPIESREQUIRED:LTTR15ENCL13 indianaMichip~PowerCompaP.O.Box1663Coturnbus,OH43216AEP:NRC:1180DonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74TECHNICALSPECIFICATIONCHANGEREQUESTREACTORCOOLANTSYSTEMPRESSUREISOLATIONVALVESU.S.NuclearRegulatoryCommissionDocumentControlDeskWashington,DC20555Attn:T.E,MurleyNovember15,1993
DearDr.Murley:
Reference:
1)2)3)4)USNRCLettertoallLWRLicensees:LWRPrimaryCoolantSystemPressureIsolationValves,February25,1980AEP:NRC:0371,ReactorCoolantSystemPressureIsolationValves,March24,1980Letter,S.A.Varga,USNRCtoJ.Dolan,IndianaandMichiganElectricCompany,OrderforModificationofLicensesConcerningPrimaryCoolantSystemPressureIsolationValves,April20,1981WASH1400/NUREG75/014,ReactorSafetyStudy:AnAssessmentofAccidentRisksinU.S.CommercialNuclearPower-Plants,.USNRC,October19755)6)AEP:NRC1082E,IndividualPlantExaminationSubmittal/ResponsetoGenericLetter88-20,May1,1992AEP:NRC1082F,IndividualPlantExaminationResponsetoNRCQuestions,February24,199349311190228931115FDRADDCXOS000315PPDR Dr.T.E.Murley-2-AEP:NRC:1180Thisletteranditsattachmentsconstituteanapplicationforatechnicalspecification(T/S)changeforDonaldC.CookNuclearPlantUnits1and2.Specifically,weproposetochangeT/S3/4.6.2,"ReactorCoolantSystemOperationalLeakage,"bydeletingTable3.4-0,"ReactorCoolantSystemPressureIsolationValves,"LimitingConditionforOperation3.4.6.2fandActionc.,andSurveillanceRequirements4.4.6.2.2,forbothunits.Wearealsoproposingthreeeditorialchangesineachunit'sT/S,andthedeletionofthelastparagraphintheBasesforT/S3/4.6.2.TheReactorCoolantSystempressureisolationvalvesinTable3.4-0oftheTechnicalSpecificationswereaddedtotheLimitingConditionforOperationonReactorCoolantSystemOperationalLeakagepursuanttoaUSNRClettertoallLWRlicensees,"LWRPrimaryCoolantSystemPressureIsolationValves",datedFebruary25,1980(Reference1)andfollowingadditionalplantspecifictransmittalsonthissubject(References2and3).Reference1wasissuedasaresultofthefindinginReference4thatanintersystemloss-of-coolantaccident(ISLOCA)wasasignificantcontributortocoredamagefrequency(EventV).Recently,theIndividualPlantExamination(IPE)(Reference5)forCookNuclearPlantfoundthatthecontributiontooverallcoredamagefrequencyfromanISLOCAwastheleast(0.08$)ofallinitiatingeventcontributors.ThiswasinlargemeasureduetothedesignofpotentialEventV-sequenceflowpathsatCookNuclearPlantcomparedtothatusedinWASH-1400.ThepotentialpathsatCookNuclearPlantcontaineitherthreecheckvalves,acombinationoftwocheckvalvesandaclosedmotoroperatedvalve,ortwoclosedmotoroperatedvalves,whereasthetypicalWASH-1400flowpathcontainedonlytwocheckvalvesinserieswithalockedopenvalveasshowninFigureV-3ofReference4.TheresultantIPEEventV-sequenceinitiatingeventfrequency(describedinReferences5and6)wasapproximatelyanorderofmagnitudelowerthantheWASH-1400valueof4.00E-6andwasalsoaboutthreeordersofmagnitudelowerthantheaverageaccidentinitiatingeventfrequencyemployedintherestoftheIPE.Additionally,theWASH-1400analysesusedtheveryconservativeassumptionthat,whenthein-seriescheckvalvesfail,thepressurizedlowpressurepipingalsofailed.Amorerealisticplant-specificscenariowasmodeledintheCookNuclearPlantIPEISLOCAanalyses,whereinexistingplantdesigncapabilitieswereusedwhichreducedtheeffectsofthisaccident(seeresponsetoquestion3inReference6).Thus,theEventVsequencewasfoundtobeaninsignificantcontributor,bothtotheCookNuclearPlantcoredamagefrequencyandoff-sitedoses.
Dr.T.E.Murley-3-AEP:NRC:1180Inadditiontotheabove,thisrequestisalsobeingmadebecausestartupoftheCookNuclearPlantUnits1and2followingrefuelingoutageshasbeendelayedonanumberofoccasionsasadirectresultoftheunnecessarilyrestrictivetestingrequirementsandacceptancecriteriamandatedbytheTechnicalSpecificationsforthevalvesinTable3.4-0.AllofthesubjectvalveswillstillbetestedonarefuelingoutagefrequencytotheleakagelimitsofASMEXIundertheISTprogram..ThiswillcontinuetoprovideprotectionfromthepotentialoccurrenceofanEventVaccidenttypetoensurethehealthandsafetyofthepublic.TheproposedchangesandoursignificanthazardsconsiderationanalysisareprovidedinAttachment1.Theproposedmarked-uprevisedT/SpagesareincludedinAttachment2.Attachment3containsthetypedproposedrevisedT/Spages.Webelievethattheproposedchangeswillnotresultin(1)asignificantchangeinthetypesofeffluentsorasignificantincreaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificantincreaseinindividualorcumulativeoccupationalradiationexposure.TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommitteeandtheNuclearSafetyandDesignReviewCommittee.Incompliancewiththerequirementsof10CFR50.91(b)(l),copiesofthisletteranditsattachmentshavebeentransmittedtotheMichiganPublicServiceCommissionandtotheMichiganDepartmentofPublicHealth.Thisletterissubmittedprusuantto10CFR50.30(b)and,assuchanoathstatementisattahced.Sincerely,E.E.FitzarickVicePresidentehAttachments 4-I COUNTYOFFRANKLINE.E.Fitzpatrick,beingdulysworn,deposesandsaysthatheistheVicePresidentoflicenseeIndianaMichiganPowerCompany,thathehasreadtheforgoingTechnicalSpecificationChangeRequestReactorCoolantSystemPressureIsolationValvesandknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledgeandbelief.Subscribedandsworntobeforemethisl~dayof.NOTARYPUBLICD)ANAl:.EADSNotaryPublic,StateofOhioMycommissionexpires2.2495 Dr.T.E.Murley-4-AEP:NRC:1180cc:A.A.BlindG.CharnoffJ.B.Martin-RegionIIINFEMSectionChiefNRCResidentInspector-BridgmanJ~R.Padgett Dr.T.E.Murley-5-AEP:NRC:1180bc:S.J.BrewerJ.B.Kingseed/J.M.Nieto/R.B.BennettD.H.MalinJ.D.Benes/E.V.Gilabert/J.J.RipakJ.D.Grier/D.F.Powell/J.G.NogradyM.L.Horvath-BridgmanJ.B.ShinnockW.G.Smith,Jr./S.H.SteinhartB.A.Wetzel,NRC-Washington,DCAEP:NRC:1180DC-N-6015.1
COUNTY0FRANKLNE.E.Fitzpatrick,beingdulysworn,deposesandsaysthatheistheVicePresidentoflicenseeIndianaMichiganPowerCompany,thathehasreadtheforgoingTechnicalSpecificationChangeRequestReactorCoolantSystemPressureIsolationValvesandknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledgeandbelief.SubscribedandsworntobeforemethisdayofOL/~adwc,i9y>Zc-~.NOTARYPUBLICDIA<sAL~QDSNotaryPublic,StateofOhioMycommissionexpires22495 ATTACHMENT1TOAEP:NRC:1180DESCRIPTIONOFPROPOSEDCHANGESAND10CFR50.92SIGNIFICANTHAZARDSCONSIDERATIONANALYSIS ATTACHMENT1TOAEP'NRC'1180Page1BCKGROUNDTheReactorSafetyStudy(WASH-1400/NUREG75/014)(Reference1)analyzedaso-calledEventVSequenceresultinginanintersystemloss-of-coolantaccident(ISLOCA).ItwasconcludedthattheISLOCAwasasignificantcontributortocoredamagefrequencysincethecontainmentisbypassedandreactorcoolantisreleaseddirectlytotheAuxiliaryBuilding.Asaresultoftheabovefinding,theUSNRCissuedaletter,"LWRPrimaryCoolantSystemPressureIsolationValves,"datedFebruary25,1980,(Reference2)requestingLWRlicenseestoprovidethefollowinginformation:1.DescribethevalveconfigurationatyourplantandindicateifanEventVisolationvalveconfigurationexistswithintheClassIboundaryofthehighpressurepipingconnectionPCSpipingto.lowpressuresystempiping;e.g.,(1)twocheckvalvesinseries,or(2)twocheckvalvesinserieswithaMOV;2.IfeitheroftheaboveEventVconfigurationsexistsatyourfacility,indicatewhethercontinuoussurveillanceorperiodictestsarebeingaccomplishedonsuchvalvestoensureintegrity.Alsoindicatewhethervalveshavebeenknown,orfound,tolackintegrity;and3.IfeitheroftheaboveEventVconfigurationsexistatyourfacility,indicatewhetherplantproceduresshouldberevisedorifplantmodificationsshouldbemadetoincreasereliability.AEPSCrespondedtotheaboveUSNRCletterwithletterAEP:NRC:0371,"ReactorCoolantSystemPressureIsolationValves,"datedMarch24,1980(Reference3).Inthisletter,theUSNRCwasinformedthatthefollowingvalveconfigurationsareusedatDonaldC.CookNuclearPlant:1)Aminimumofthreecheckvalvesinseries2)Twocheckvalveswithaminimumofaclosedmotoroperatedvalveinseries ATTACHMENT1TOAEP:NRC:1180Page23)Twocheckvalveswithaclosedhandoperatedvalveinseries4)AcheckvalvewithtwoclosedairoperatedvalvesinseriesAEP:NRC:0371concludedthat:"ThereforenoEventVconfigurationexistsattheCookPlant.Consequently,therequestsinItems2and3ofMr.Eisenhut'sletterarenotapplicabletotheCookNuclearPlant."OnApril20,1981,theUSNRCissuedan"OrderforModificationofLicensesConcerningPrimaryCoolantSystemPressureIsolationValves"fortheDonaldC.CookNuclearPlant(Reference4).Thisorderstatedthat"WehaveconcludedthataWASH-1400EventVvalveconfigurationexistsatyourfacilityandthatthecorrectiveactionasdefinedintheattachedOrderisnecessary."AttachedtotheOrderweretheTechnicalEvaluationReport(TER)supportingtheOrderandthenewTechnicalSpecificationswhich,accordingtotheOrder,"...willensurepublichealthandsafetyovertheoperatinglifeofyourfacility."ThesenewTechnicalSpecificationswereincorporatedatthattimeintotheOperatingLicensesforCookNuclearplant.ThesearethesameTechnicalSpecificationsthatwearenowproposingtodelete.In1987,theUSNRCissuedGenericLetter(GL)87-06,"PeriodicVerificationofLeakTightIntegrityofPressureIsolationValves"(Reference5).InourresponsetothatGL,AEP:NRC:1041(Reference6),westatedthat12-SI-170L2,12-SI-170L3,12-RH-133,and12-RH-134areleaktestedasperthesurveillancerequirementsintheTechnicalSpecifications.Theproposedchangesinthissubmittal,therefore,modifyourresponsetoGL.87-06.Finally,in1992,theUSNRCissuedInformationNotice92-36,"IntersystemLOCAOutsideContainment"(Reference7).Thisinformationnoticelistedeleven"ObservedPlantVulnerabilitiestoISLOCAPrecursors."AreviewofthisinformationnoticeconcludedthattheconcernsraisedareadequatelyaddressedbycontrolscurrentlyinplaceorplannedattheCookNuclearPlant.TheproposedchangestotheTechnicalSpecificationswillnotalterthisconclusionbecauseourresponsetotheinformationnoticewasnotbasedonexistingtechnicalspecifications.
ATTACHMENT1TOAEP:NRC:1180Page3COOKNUCLEARPLANTIPEOnMay1,1992,AEPSCrespondedtoGenericLetter88-20(Reference8),inAEP:NRC:1082E,IndividualPlantExamination(IPE)submittal(Reference9)andprovidedfurtherinformationontheanalysisoftheISLOCAinReference10.(SeetheEnclosuretothis
Attachment:
DonaldC.CookNuclearPlant,PathsConsideredasPossibleEventV-SequenceLOCA,takenfromReference10).InthedeterminationoftheISLOCAinitiatingeventfrequency,leaktestingof12-SI-170L2,12-SI-170L3,12-RH-133,and12-RH-134,asrequiredbythesurveillancerequirementsintheTechnicalSpecifications,wasaddressed.TheIPEforCookNuclearPlantconcludedthattheISLOCAwastheaccidentthatcontributedtheleasttotheoverallcoredamagefrequency.ThecalculatedISLOCAinitiatingeventfrequencywasapproximately6.70E-07,andthecalculatedprobabilityofISLOCAcoredamagewasapproximately5.4E-08.ThecontributiontooverallcoredamagefrequencyfromanISLOCAislessthan0.18ofthe6.26E-05IPEcalculatedcoredamagefrequencyperreactoryear.Itisseen,therefore,thatthecontributionfromanISLOCAeventatCookNuclearPlantisnegligible.COMPARISONOFWASH-1400VSCOONUCLEARPLANTWITHRESPEC~TOSLOGTheISLOCAaccidentisdescribedinSection5.3.2.5ofWASH-1400,andthequantificationofitscoredamagefrequencyisfoundinAppendixV,Section4.4ofWASH-1400.ThecoredamagefrequencycalculatedinWASH-1400is4.00-06/reactoryear.WASH-1400evaluated3pathwaysof2checkvalvesinseriesandassumedthatthe600psiLowPressureInjectionSystem(LPIS),onceexposedtoRCSpressure,wouldfailandcreateapproximatelya6"effectivediameterLOCA.Nootheraccidentinitiationfeaturesormitigatingactionsweremodeled.IntheCookNuclearPlantIPE,ninedifferentpathwaysforanISLOCAeventwereanalyzed.Thesepathways(seeEnclosuretothisAttachment),consistedofeitherthreecheckvalvesinseries,twocheckvalvesandaclosedmotoroperatedvalve(MOV)inseries,ortwonormallyclosedMOVsinseries.AlthoughWASH-1400lookedatcheckvalveleaktestingasasensitivityanalysis,theCookNuclearPlantIPEaccountedforthein-place'eaktestingwhencalculatingtheprobabilityofanISLOCAoccurring.Inaddition,theCookNuclearPlantIPEmodeledmitigatingactionsfortheISLOCAeventintheeventtree.The ATTACHMENT1TOAEP'NRC'1180Page4IPEISLOCAinitiatingeventfrequencywasapproximatelyanorderofmagnitudelowerthantheWASH-1400coredamagefrequency(4.00E-06)andtheIPEISLOCAcoredamagefrequencyvaluewasapproximatelytwoordersofmagnitudelowerthantheWASH-1400values.Finally,toaddresstheimpactofremovingtheT/Srequirementsandonlytesting12-SI-170L2,12-SI-170L3,12-RH-133,and12-RH-134atarefuelingoutagefrequency,asensitivityrunwasmadeinsupportofthissubmittal.ItwasfoundthattheISLOCAinitiatingeventfrequency,andISLOCAprobabilityofcoredamagewouldalsoincreaseby5.4%tothemid5.00E-08range,andtheoverallcoredamagefrequencywouldremainunchanged.STPOGThesubjectcheckvalvesofthissubmittalarecurrentlybeingtestedinMode5,ColdShutdown,asrequiredbytheTechnicalSpecificationssurveillancerequirementspriortogoingtoMode4,HotShutdown.Theallowableleakratecannotexceed1gpm.IfthesecheckvalvesareremovedfromtheTechnicalSpecifications,theywouldcontinuetobetestedundertheISTProgram(ASMEBoilerandPressureVesselCode,SectionXI),onarefuelingoutagefrequency,liketheirsistervalvesintheotherloopsintheResidualHeatRemovalSystem.TheacceptancecriteriafortheleaktestingofthesevalvesundertheISTProgramis5gpm.DESCRIPTIONOFPROPOSEDTECHNICALSPECIFICATONCHANGSTheproposedchangesarelistedbel'ow.Theyareidenticalforbothunits.T/S3'.6.2d.Add"and"attheendoftheline.2.T/S3.4.6.2e.Delete"and,"andaddaperiodafterIIgpm2II3.T/S3.4.6.2f.Deleteinitsentirety.4,T/S3.4.6.2APPLICABILITY:Delete"~"andreplacewitha"*".5.T/S3.4.6.2ACTIONc.Deleteinitsentirety.T/S3.4.6.2ACTIONc,footnote*.Deletethefootnote.
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ATTACHMENT1TOAEPNRC:1180Page57.T/S3.4.6.2APPLICABILITY,footnote~.Changethen~nton*n~8.T/S4.4.6.2.2.Deleteinitsentirety.9.T/S3/4.6.2,Table3.4-0.DeletetheTableandthefootnote(a)initsentirety.10.T/S3/4.6.2,Bases.Deletethelastparagraphinitsentirety.10CFR509SIGNIFICANTHAZARDSCONSDERATONANALYSISPer10CFR50.92,aproposedamendmenttoanoperatinglicensewillnotinvolveasignificanthazardsconsiderationiftheproposedamendmentsatisfiesthefollowingthreecriteria:1)Doesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed,2)Doesnotcreatethepossibilityofanewordifferentkindofaccidentfromanaccidentpreviouslyanalyzedorevaluated,or3)Doesnotinvolveasignificantreductioninamarginofsafety.4CrterionTheISLOCAisnotoneoftheaccidentspreviouslyanalyzedinChapter14,SafetyAnalysis,oftheCookNuclearPlantUpdatedFinalSafetyAnalysisReport.Chapter14analyzesthelargebreakLOCAinSection14.3.1,and"lossofreactorcoolantfromsmallrupturedpipesorfromcracksinlargepipeswhichactuatestheECCS",orsmallbreakLOCAinSection14.3.2.Therefore,deletingfromtheTechnicalSpecificationstheReactorCoolantSystempressureisolationvalvesinTable3.4-0,willnotincreasetheprobabilityortheconsequencesofthelargebreakorthesmallbreakLOCAspreviouslyanalyzedfortheCookNuclearPlant.
I ATTACHMENT1TOAEP:NRC:1180Page6CriterionTheReactorCoolantSystempressureisolationvalvesinTable3.4-0oftheTechnicalSpecificationswereaddedbecauseWASH-1400identifiedtheISLOCAasasignificantcontributortocoredamagefrequency.DeletionofthesubjectvalvesfromtheTechnicalSpecificationsandrelianceonthetestingrequirementsmandatedbytheIn>>ServiceTestingProgramofASMEXIdoesnotcreatethepossibilityofanewordifferentkindofaccidentfromthelargebreakorthesmallbreakLOCAspreviouslyanalyzedfortheCookNuclearPlant.Criteion3DeletingtheReactorCoolantSystempressureisolationvalvesfromthetestingrequirementsinTable3.4-0oftheTechnicalSpecificationswillresultinthesevalvesonlybeingtestedonarefuelingoutagefrequencyaspartoftheASMEB&PVCodeSectionXIISTProgram.ThissomewhatreducedtestingfrequencywillresultinaslightincreaseintheISLOCAinitiatingeventfrequency,andISLOCAcontributiontocoredamagefrequencyof5.4S,fromlower5.00E-08/reactoryeartomid5.00E-08/reactoryear.Thisinsignificantincxeasewillnotaffecttheoverallcoredamagefrequencyof6.26E-05/reactoryear.Therefore,itisconcludedthattheproposeddeletionoftheReactorCoolantSystempressux'eisolationvalvesinTable3.4-0oftheTechnicalSpecifications,aswellastheproposeddeletionoftheportionsoftheTechnicalSpecificationsthatareaffectedbyTable3.4-0,willnotresultinasignificantreductioninthemarginofsafetythatexistsatCookNuclearPlanttopreventanISLOCAortomiti'gatetheconsequencesofanISLOCA.REFERENCESWASH-1400/NUREG75/014,ReactorSafetyStudy:AnAssessmentofAccidentRisksinU.S.CommercialNuclearPlants,USNRC,October1975.2.USNRCLettertoallLWRLicensees:LWRPrimaryCoolantSystemPressureIsolationValves,February25,1980.3.AEP:NRC:0371,ReactorCoolantSystemPressureIsolationValves,March24,1980.
ATTACHMENT1TOAEP'NRC'1180Page74.Letter,S.A.Varga,USNRCtoJ.Dolan,IndianaandMichiganElectricCompany,OrderforModificationofLicensesConcerningPrimaryCoolantSystemPressureIsolationValves,April20,1981.5.USNRCGenericLetter(GL)87-06,"PeriodicVerificationofLeakTightIntegrityofPressureIsolationValves,"March13,1987.6.AEP:NRC:1041,GenericLetter87-06,PeriodicVerificationofLeakTightIntegrityofPressureIsolationValves,November12,1987.7.USNRCInformationNotice92-36,"IntersystemLOCAOutsideContainment",May,7,1992.8.InitiationoftheIndividualPlantExaminationforSevereAccidentVulnerabilities-10CFR50.54(f),GenericLetterNo.88-20,November23,1988.9.AEP:NRC1082E,IndividualPlantExaminationSubmittal,ResponsetoGenericLetter88-20,May1,1992.10.AEP:NRC1082F,IndividualPlantExaminationResponsetoNRCQuestions,February24,1993.
Attachment1toAEP:NRC:1180ENCLOSUREPage8DONALDC.COOKNUCLEARPLANTPATHSCONSIDEREDASPOSSIBLEV-SEQUENCELOCASSlL70LLTOLOOPICOL.DLEGroumAI'%%i.~Do4CCUHIIUITIRSSI-166LI$1L6LLLTOLOOP4COLDLEGSl-170L4SI-166L4ICN-311!SI-LSLETOLOOPIHOTLEGTOLOOP4HOTLEGSl-L58LIIHO-315Sl-158L4LCINO-316SI-152NICN-265rROHNORTH$1PLPLP$1-170L2TOLOOP2COLDL.EGSl-161L2FRIHACCUHULATORSSI-L66L2ICN-111'5%L5""TOLOOP3COLDLEGSl-1701.3RH-134Sl161L3Sl-166LIHO-326!ICN321$1-LSLVPRDHvEST!RHRPUHPSlL58L2TOLOOP2HOTLEGSl-158L3TOLOOP3HOTLEGrROHLmIHO-L28IHO-325LCICH-L29ICH-265SI"152$SV-L03SETAT450PSITORHRSUCTIONHEADERFIGURE11REFERENCEDRAVINGTOP-1-5143"20108
