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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20217F1951999-10-0707 October 1999 Application for Amend to License NPF-29,to Revise Licensing Basis to Credit One of Insights/Conclusions of NUREG-1465, Revised Source Term Insights ML20211E7061999-08-20020 August 1999 Application for Amend to License NPF-29,incorporating Many of Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0791999-06-29029 June 1999 Suppl to 980720 Application for Amend to License NPF-29, Implementing BWROG Enhanced Option I-A,reactor Stability long-term Solution.Rev to TS 3.4.1 Inadvertently Omitted from Original Application ML20196G6901999-06-23023 June 1999 Application for Amend to License NPF-29,revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5241999-05-0606 May 1999 Application for Amend to License NPF-29,changing TSs Required to Support Ggns,Cycle 11 Operation,Including Slmcpr.Portions of Encl Re Addl Info on Calculated Cycle Specific SL MCPR for Plant Cycle 11 Withheld ML20206R9271999-01-12012 January 1999 Application for Amends to Licenses NPF-29 & NPF-47,proposing Required Actions Consistent with NRC Accepted Change to BWR Improved TS NUREG-1433 & NUREG-1434 ML20236T1551998-07-20020 July 1998 Application for Amend to License NPF-29,revising TSs Re BWROG Enhanced Option I-A Reactor Stability Long Term Solution ML20198J3451998-01-0909 January 1998 Revised Application for Amend to License NPF-29,providing Clarifications to Amend & Adding Restriction to Allowed Interval Extensions Re Option B of 10CFR50,app J ML20198N3851997-10-28028 October 1997 Application for Amend to License NPF-29,revising TS to Implement Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20210V5461997-09-18018 September 1997 Application for Amend to License NPF-29,reflecting Decrease of Two Recirculation Loop SLMCPR to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12.Proprietary Info Re SLMCPR for Cycle 10,encl.Proprietary Info Withheld ML20134E1191996-10-22022 October 1996 Application for Amend to License NPF-29,revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Pressure, Curves Using Methodology of Reg Guide 1.99,Rev 2, Radiation Embrittlement.. ML20117P4421996-09-19019 September 1996 Application for Amend to License NPF-29,changing Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117G6661996-08-27027 August 1996 Application for Amend to License NPF-29,modifying Tech Specs Surveillance Requirements for Safety/Relief Valves ML20116F0141996-07-31031 July 1996 Rev 1 to Application for Amend to License NPF-29,revising TSs Required to Support Cycle 9,reload 8.Rev 1 to J11-02863SLMCPR, GGNS Cycle 9 Safety Limit MCPR Analysis Encl.Rept Withheld ML20113B7341996-06-20020 June 1996 Application for Amend to License NPF-29,redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20112E1741996-05-31031 May 1996 Application for Amends to Licenses NPF-29 & NPF-47 Adding Addl Acceptable Required Actions to Tech Spec Limiting Condition for Operation (LCO) 3.9.1, Refueling Equipment Interlocks ML20117F4541996-05-0909 May 1996 Application for Amend to License NPF-29,modifying SRV Surveillance Test for Relief Mode of Operation ML20117D6901996-05-0909 May 1996 Application for Amend to License NPF-29,revising TSs to Support Unit 1,cycle 9 Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits ML20111B2631996-05-0808 May 1996 Application for Amend to License NPF-29,placing Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3551996-05-0606 May 1996 Application for Amend to License NPF-29,changing Name from Mississippi Power & Light to Entergy Mississippi,Inc ML20107E2521996-04-18018 April 1996 Application for Amend to License NPF-29,prohibiting Performance of 24-h EDG Maint Run While Unit in Either Mode 1/2 RBG-42766, Application for Amends to Licenses NPF-29 & NPF-47,adding Addl Acceptable Method of Fuel Movement,Control Rods Removed or Withdrawn from Defueled Core Cells1996-04-18018 April 1996 Application for Amends to Licenses NPF-29 & NPF-47,adding Addl Acceptable Method of Fuel Movement,Control Rods Removed or Withdrawn from Defueled Core Cells ML20100J8311996-02-22022 February 1996 Application for Amend to License NPF-29,modifying Safety Setpoint to Tolerance Requirements for Safety/Relief Valves ML20097C3491996-02-0101 February 1996 Application for Amend to License NPF-29,revising TS Bases to Include Changes Since 950221 Approval of TS Bases RBG-42193, Rev to Application for Amend to License NPF-29 & Proposed Amend to License NPF-47,revising TS 3/4.6.2.2, Drywell Bypass Leakage1995-11-20020 November 1995 Rev to Application for Amend to License NPF-29 & Proposed Amend to License NPF-47,revising TS 3/4.6.2.2, Drywell Bypass Leakage ML20087B5031995-08-0101 August 1995 Application for Amend to License NPF-29,by Revising TS Assoc W/Various ESF Sys Following Design Fuel Handling Accident ML20086N2071995-07-21021 July 1995 Application for Amend to License NPF-29,proposing to Recapture Approx 2 1/2 Yrs of Low/No Power Operation by Extending 40-yr Operating License Term from 220616 to 241101 ML20078S4891995-02-14014 February 1995 Application for Amend to License NPF-29 Consisting of Changes to TS Requirements 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6481995-02-10010 February 1995 Application for Amend to License NPF-29,consisting of Mod to Proposed Amend to OL (PCOL-93/13),requesting to Perform Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4431994-11-0909 November 1994 Application for Amend to License NPF-29,revising TS Associated W/Various ESF Sys Following Design Basis Fuel Handling accident.Mark-up of Current Ts,Proposed TS & mark- Up Improved TS Encl ML20076F9781994-10-12012 October 1994 Application for Amend to License NPF-29,consisting of PCOL-94/01,closing & Deleting License Condition 2.C.(26) for Turbine Disc integrity.Mark-up of Affected OL Page & Proprietary Supporting Info Encl.Proprietary Info Withheld ML20069P4401994-06-17017 June 1994 Proposed Amend to OL (PCOL-94/02),removing License Conditions for EDGs Associated w/NUREG-1216 ML20059H6011994-01-13013 January 1994 Application for Amend to License NPF-29,consisting of Proposed Amend to OL PCOL-93/15,removing 2,324 Spent Fuel Pool Storage Limit & Allowing Full Use of Spent Fuel Storage Spaces ML20059A4801993-10-22022 October 1993 Application for Amend to License NPF-29,modifying Testing Frequencies for Drywell Bypass Test & Airlock Tests ML20059B0131993-10-15015 October 1993 Application for Amend to License NPF-29,converting Current GGNS TS to TS Based Largely on NUREG-1434,Rev 0 ML20056E2861993-08-17017 August 1993 Application for Amend to License NPF-29,proposing Changes to Amend TS Section 3/4.3.7.10, Loose Part Detection Sys by Relocating Loose Part Detection Instrumentation to Administrative Controls ML20056D5321993-08-11011 August 1993 Proposed Change to OL (PCOL-93/09) to License NPF-29, Amending TS Section 3/4.3.7.5 by Relocating Certain Accident Monitoring Instrumentation from TS to Administrative Control,Per NUREG-1434,Rev 0,w/respect to RG 1.97 ML20046D2041993-08-11011 August 1993 Proposed Change to OL (PCOL-93/07) to License NPF-29, Amending TS Section 3/4.3.7.10, Loose Part Detection Sys by Relocating Locating Loose Part Detection Instrumentation from TS to Administrative Controls,Per NUREG-1434,Rev 0 ML20046D1911993-08-11011 August 1993 Proposed Change to OL (PCOL-93/06) to License NPF-29, Revising TS to Support Compliance W/New Requirements of 10CFR20 & 10CFR50.36a ML20056C7131993-07-15015 July 1993 Application for Amend to License NPF-29,proposing Changes to Remove Operability Requirements for auto-test Feature of Load Shedding & Sequencing Sys & Increase AOT for Inoperable Load Shedding & Sequencing Sys from Eight to Twelve Hours ML20045H7111993-07-14014 July 1993 Application for Amend to License NPF-29,changing TS to Eliminate Previous Retrictions on Ensuring Operability of Igniters in Encl Areas & Igniters in Open Areas Adjacent to Inoperable Igniters & Redefining Hydrogen Ignition Sys ML20044F1571993-05-20020 May 1993 Proposed Amend PCOL-93/04 to License NPF-29,revising TS 4.8.3.1.2 & 4.8.3.2.2 to Remove Operability Requirements for auto-test Feature of Load Shedding & Sequencing (LSS) Sys & Increase AOT for Inoperable LSS Sys from Eight to 24 H ML20044F1621993-05-20020 May 1993 Proposed Amend PCOL-92/09 to License NPF-29,removing Unnecessary Operability Requirements for IRMs & APRMs During Plant Shutdown Conditions.Ts Changes Follow NUREG-1434, Rev 0 Requirements ML20116D1391992-10-29029 October 1992 Application for Amend to License NPF-29,consisting of Proposed Change,Revising TS Per Generic Ltr 88-16, Removal of Cycle Specific Parameter Limits from TS, That Will Change Each Fuel Cycle ML20118A5681992-09-14014 September 1992 Application for Amend to License NPF-29,deleting TS Tables 3.6.4-1 Re Containment & Drywell Isolation Valves, 3.6.6.2-1 Re Secondary Containment Ventilation Sys & 3.8.4.2-1 Re MOV Thermal Overload Protection,Per GL 91-08 ML20113H6001992-07-29029 July 1992 Application for Amend to License NPF-29,consisting of PCOL-92/03,changing Selected TS Instrumentation Surveillance Test Intervals & Allowed Outage Times,Based on Cited GE Repts ML20101B6681992-05-29029 May 1992 Application for Amend to License NPF-29,changing TS Bases 3/4.9.7, Crane Travel - Spent Fuel & Upper Containment Fuel Storage Pools ML20096B8861992-05-0606 May 1992 Application for Amend to License NPF-29,changing TS Re Primary Containment Penetration Conductor Overcurrent Protective Devices,Under Exigent Circumstances,Per Generic Ltr 89-10 ML20095K0351992-04-30030 April 1992 Application for Amend to License NPF-29,changing TS 3/4.3.1 Re Reactor Protection Sys instrumentation,3/4.3.6 Re Control Rod Block Instrumentation & 3/4.3.7.6 Re Source Range Monitors,Per Violations in Insp Rept 50-416/92-04 ML20095E7341992-04-22022 April 1992 Suppl to 910626 Application for Amend to License NPF-29, Modifying Wording of Requested Change to LCO 3.3.2,Action B Re Extension of Instrumentation Surveillance Intervals & Allowed Outage Times 1999-08-20
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217F1951999-10-0707 October 1999 Application for Amend to License NPF-29,to Revise Licensing Basis to Credit One of Insights/Conclusions of NUREG-1465, Revised Source Term Insights ML20211E7061999-08-20020 August 1999 Application for Amend to License NPF-29,incorporating Many of Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0791999-06-29029 June 1999 Suppl to 980720 Application for Amend to License NPF-29, Implementing BWROG Enhanced Option I-A,reactor Stability long-term Solution.Rev to TS 3.4.1 Inadvertently Omitted from Original Application ML20196G6901999-06-23023 June 1999 Application for Amend to License NPF-29,revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5241999-05-0606 May 1999 Application for Amend to License NPF-29,changing TSs Required to Support Ggns,Cycle 11 Operation,Including Slmcpr.Portions of Encl Re Addl Info on Calculated Cycle Specific SL MCPR for Plant Cycle 11 Withheld ML20206R9271999-01-12012 January 1999 Application for Amends to Licenses NPF-29 & NPF-47,proposing Required Actions Consistent with NRC Accepted Change to BWR Improved TS NUREG-1433 & NUREG-1434 ML20236T1551998-07-20020 July 1998 Application for Amend to License NPF-29,revising TSs Re BWROG Enhanced Option I-A Reactor Stability Long Term Solution ML20217P0241998-04-0606 April 1998 Amend 135 to License NPF-29,revising TSs for GGNS to Permit Implementation of Containment Leak Rate Testing Provisions of 10CFR50,App J,Option B ML20198J3451998-01-0909 January 1998 Revised Application for Amend to License NPF-29,providing Clarifications to Amend & Adding Restriction to Allowed Interval Extensions Re Option B of 10CFR50,app J ML20198N3851997-10-28028 October 1997 Application for Amend to License NPF-29,revising TS to Implement Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20210V5461997-09-18018 September 1997 Application for Amend to License NPF-29,reflecting Decrease of Two Recirculation Loop SLMCPR to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12.Proprietary Info Re SLMCPR for Cycle 10,encl.Proprietary Info Withheld ML20134E1191996-10-22022 October 1996 Application for Amend to License NPF-29,revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Pressure, Curves Using Methodology of Reg Guide 1.99,Rev 2, Radiation Embrittlement.. ML20117P4421996-09-19019 September 1996 Application for Amend to License NPF-29,changing Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117G6661996-08-27027 August 1996 Application for Amend to License NPF-29,modifying Tech Specs Surveillance Requirements for Safety/Relief Valves ML20116F0141996-07-31031 July 1996 Rev 1 to Application for Amend to License NPF-29,revising TSs Required to Support Cycle 9,reload 8.Rev 1 to J11-02863SLMCPR, GGNS Cycle 9 Safety Limit MCPR Analysis Encl.Rept Withheld ML20113B7341996-06-20020 June 1996 Application for Amend to License NPF-29,redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20112E1741996-05-31031 May 1996 Application for Amends to Licenses NPF-29 & NPF-47 Adding Addl Acceptable Required Actions to Tech Spec Limiting Condition for Operation (LCO) 3.9.1, Refueling Equipment Interlocks ML20117D6901996-05-0909 May 1996 Application for Amend to License NPF-29,revising TSs to Support Unit 1,cycle 9 Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits ML20117F4541996-05-0909 May 1996 Application for Amend to License NPF-29,modifying SRV Surveillance Test for Relief Mode of Operation ML20111B2631996-05-0808 May 1996 Application for Amend to License NPF-29,placing Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3551996-05-0606 May 1996 Application for Amend to License NPF-29,changing Name from Mississippi Power & Light to Entergy Mississippi,Inc ML20107E2521996-04-18018 April 1996 Application for Amend to License NPF-29,prohibiting Performance of 24-h EDG Maint Run While Unit in Either Mode 1/2 RBG-42766, Application for Amends to Licenses NPF-29 & NPF-47,adding Addl Acceptable Method of Fuel Movement,Control Rods Removed or Withdrawn from Defueled Core Cells1996-04-18018 April 1996 Application for Amends to Licenses NPF-29 & NPF-47,adding Addl Acceptable Method of Fuel Movement,Control Rods Removed or Withdrawn from Defueled Core Cells ML20100J8311996-02-22022 February 1996 Application for Amend to License NPF-29,modifying Safety Setpoint to Tolerance Requirements for Safety/Relief Valves ML20097C3491996-02-0101 February 1996 Application for Amend to License NPF-29,revising TS Bases to Include Changes Since 950221 Approval of TS Bases RBG-42193, Rev to Application for Amend to License NPF-29 & Proposed Amend to License NPF-47,revising TS 3/4.6.2.2, Drywell Bypass Leakage1995-11-20020 November 1995 Rev to Application for Amend to License NPF-29 & Proposed Amend to License NPF-47,revising TS 3/4.6.2.2, Drywell Bypass Leakage ML20087B5031995-08-0101 August 1995 Application for Amend to License NPF-29,by Revising TS Assoc W/Various ESF Sys Following Design Fuel Handling Accident ML20086N2071995-07-21021 July 1995 Application for Amend to License NPF-29,proposing to Recapture Approx 2 1/2 Yrs of Low/No Power Operation by Extending 40-yr Operating License Term from 220616 to 241101 ML20078S4891995-02-14014 February 1995 Application for Amend to License NPF-29 Consisting of Changes to TS Requirements 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6481995-02-10010 February 1995 Application for Amend to License NPF-29,consisting of Mod to Proposed Amend to OL (PCOL-93/13),requesting to Perform Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4431994-11-0909 November 1994 Application for Amend to License NPF-29,revising TS Associated W/Various ESF Sys Following Design Basis Fuel Handling accident.Mark-up of Current Ts,Proposed TS & mark- Up Improved TS Encl ML20076F9781994-10-12012 October 1994 Application for Amend to License NPF-29,consisting of PCOL-94/01,closing & Deleting License Condition 2.C.(26) for Turbine Disc integrity.Mark-up of Affected OL Page & Proprietary Supporting Info Encl.Proprietary Info Withheld ML20069P4401994-06-17017 June 1994 Proposed Amend to OL (PCOL-94/02),removing License Conditions for EDGs Associated w/NUREG-1216 ML20059H6011994-01-13013 January 1994 Application for Amend to License NPF-29,consisting of Proposed Amend to OL PCOL-93/15,removing 2,324 Spent Fuel Pool Storage Limit & Allowing Full Use of Spent Fuel Storage Spaces ML20059A4801993-10-22022 October 1993 Application for Amend to License NPF-29,modifying Testing Frequencies for Drywell Bypass Test & Airlock Tests ML20059B0131993-10-15015 October 1993 Application for Amend to License NPF-29,converting Current GGNS TS to TS Based Largely on NUREG-1434,Rev 0 ML20056E2861993-08-17017 August 1993 Application for Amend to License NPF-29,proposing Changes to Amend TS Section 3/4.3.7.10, Loose Part Detection Sys by Relocating Loose Part Detection Instrumentation to Administrative Controls ML20046D2041993-08-11011 August 1993 Proposed Change to OL (PCOL-93/07) to License NPF-29, Amending TS Section 3/4.3.7.10, Loose Part Detection Sys by Relocating Locating Loose Part Detection Instrumentation from TS to Administrative Controls,Per NUREG-1434,Rev 0 ML20046D1911993-08-11011 August 1993 Proposed Change to OL (PCOL-93/06) to License NPF-29, Revising TS to Support Compliance W/New Requirements of 10CFR20 & 10CFR50.36a ML20056D5321993-08-11011 August 1993 Proposed Change to OL (PCOL-93/09) to License NPF-29, Amending TS Section 3/4.3.7.5 by Relocating Certain Accident Monitoring Instrumentation from TS to Administrative Control,Per NUREG-1434,Rev 0,w/respect to RG 1.97 ML20056C7131993-07-15015 July 1993 Application for Amend to License NPF-29,proposing Changes to Remove Operability Requirements for auto-test Feature of Load Shedding & Sequencing Sys & Increase AOT for Inoperable Load Shedding & Sequencing Sys from Eight to Twelve Hours ML20045H7111993-07-14014 July 1993 Application for Amend to License NPF-29,changing TS to Eliminate Previous Retrictions on Ensuring Operability of Igniters in Encl Areas & Igniters in Open Areas Adjacent to Inoperable Igniters & Redefining Hydrogen Ignition Sys ML20044F1571993-05-20020 May 1993 Proposed Amend PCOL-93/04 to License NPF-29,revising TS 4.8.3.1.2 & 4.8.3.2.2 to Remove Operability Requirements for auto-test Feature of Load Shedding & Sequencing (LSS) Sys & Increase AOT for Inoperable LSS Sys from Eight to 24 H ML20044F1621993-05-20020 May 1993 Proposed Amend PCOL-92/09 to License NPF-29,removing Unnecessary Operability Requirements for IRMs & APRMs During Plant Shutdown Conditions.Ts Changes Follow NUREG-1434, Rev 0 Requirements ML20116D1391992-10-29029 October 1992 Application for Amend to License NPF-29,consisting of Proposed Change,Revising TS Per Generic Ltr 88-16, Removal of Cycle Specific Parameter Limits from TS, That Will Change Each Fuel Cycle ML20118A5681992-09-14014 September 1992 Application for Amend to License NPF-29,deleting TS Tables 3.6.4-1 Re Containment & Drywell Isolation Valves, 3.6.6.2-1 Re Secondary Containment Ventilation Sys & 3.8.4.2-1 Re MOV Thermal Overload Protection,Per GL 91-08 ML20113H6001992-07-29029 July 1992 Application for Amend to License NPF-29,consisting of PCOL-92/03,changing Selected TS Instrumentation Surveillance Test Intervals & Allowed Outage Times,Based on Cited GE Repts ML20101B6681992-05-29029 May 1992 Application for Amend to License NPF-29,changing TS Bases 3/4.9.7, Crane Travel - Spent Fuel & Upper Containment Fuel Storage Pools ML20096B8861992-05-0606 May 1992 Application for Amend to License NPF-29,changing TS Re Primary Containment Penetration Conductor Overcurrent Protective Devices,Under Exigent Circumstances,Per Generic Ltr 89-10 ML20095K0351992-04-30030 April 1992 Application for Amend to License NPF-29,changing TS 3/4.3.1 Re Reactor Protection Sys instrumentation,3/4.3.6 Re Control Rod Block Instrumentation & 3/4.3.7.6 Re Source Range Monitors,Per Violations in Insp Rept 50-416/92-04 1999-08-20
[Table view] |
Text
- _.
REEOtAWEE,IIW.
December 6, 1988 U. S. Nuclear Regulatory Cormiission Mail Station P1-137 Washingtor;, D. C. 20555 Attention: Document Control Desk Gentlemen:
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No 50-416 License No. NPF-29 Cycle 4 Reload Proposed Amendment to the Operating License (PCOL-88/21)
AECM-88/0241 Syster. Energy Resuurces, Inc. (SERI) is submitting by this letter a proposed amendn'ent to the Grand Gulf Nuclear Station (GGNS), Unit 1 Operating License. This amendment pertains to those technical specification changes required to support the Cycle 4 Reload for GGNS.
In accordance with the provisions of 10 CFR 50.4 and 50.30, the signed [
original of the requested amendment is enclosed and the appropriate copies will be distributed. The attachment provides the technical justification and discussion to support the requested amendment. This amendment has been reviewed and accepted by the Plant Safety Review Committee and the Safety Review Corrinittee.
The amendment package under cover of this letter (provided as Attachment
- 3) :onsists of the follo,.ing components:
- 1. Description of Technical Specification (TS) changes
- 2. Justification of requested TS changes
- 3. No Significant Hazard Consideration Determination
$9 4. Marked-up TS pages gm 5. Grand Gulf Nuclear Station Unit 1 Cycle 4 Reload Summary Report Proposed Startup Physics Tests 6.
cah '
& 7. Advanced Nuclear Fuels Corporation (ANF) Technical Reports:
Mo a. ANF-88-149, "Grand Gulf Unit 1 Cycle 4 Reload Analysis" av November 1988 08 b. ANF-88-150, "Grand Gulf Unit 1 Cycle 4 Plant Transient CA Analysis" November 1988 U" c. ANF-88-183(P), "Grand Gulf Unit 1 Reload XN-1.3, Cycle 4 Og Mechanical Design Report" November 1988 Mo 8. NES00-88-003, "Grand Gulf Nuclear Station Unit 1 Revised Flow
- Dependent Thermal Limits" November 1988 g g o ,p;3- l.oav. , <v ls un : t/k4 s A//
s y S p. .v ..m L e s,n f 8 Of J14AECM88120201 - 1 dit/sekl/SO.*C bcl, fnr 4 gg.gyg I j
i AECM-88/0241 Page 2 As discussed with the NRC Staff on July 28, 1988 the Technical Specification changes reflect insertion of a new ANF fuel batch; introduction of four 9x9-5 Lead Test Assemblies; and revision of thermal limits for a full ANF core, based on ANF methodology. ,
To facilitate reload related procedure development, training, and testing activities in support of plant startup for Cycle 4 SERI requests your approval t of this proposed license amendment by March 24, 1989. (
Based on the guidelines presented in 10 CFR 50.92, SERI has concluded l that this proposed amendment involves no significant hazards considerations. ;
In accordance with the requirements of 10 CFR 170.21, an application fee of $150 is attached to this letter Yours truly, ;
t AY - CL-_- - l
- k. T. Cottle Vice President, Nuclear Operations l l i WTC:jjb Attachments: 1. Remittance of $150 Application Fee
- 2. Affirmation per 10 CFR 50.30
- 3. GGNS PCOL-88/21 ;
cc: Mr. T. H. Cloninger (w/a)
Mr. R. B. McGehee (w/a) i Mr. N. S. Reynolds (w/a)
) 3
!'r. H.
Mr. H.O.L.Christenson Thbmas (w/o)(w/a) t l Mr. Malcolm L. Ernst, Acting Regional Administrator (v/a)
. V. S. Nuclear Regulatory Commission
! Region II i 101 Marietta St., N. W., Suite 2900 i Atlanta, Georgia 30323 l Mr. L. L. Kintner, Project Manager (w/a) l Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Cormission Mail Stop 14820 l Washington, D.C. 20555 Dr. Alton B. Cobb (w/a) l State Health Officer l
State Board of Health l Box 1700 l Jackson, Mississippi 39205 l
J14AECM88120201 - 2
( =
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE NO. NPF-29 f'
DOCKET N0. 50-416 IN THE MATTER OF MISSISSIPPI POWER & LIGHT COMPANY ar1d SYSTEM ENERGY RESOURCES, INC.
and SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION AFFIRMATION I I, W. T. Cottle, being duly sworn, state that I am Vice President, 3
' Nuclear Operations of System Energy Resources, Inc.; that on behalf of System Energy Resources, Inc., and South Mississippi Electric Power Association I am authorized by Syste'n Energy Resources, Inc. to sign and file with the Nuclear Regulatory Comission, this application for amendment of the Operating License of the Grard Gulf Nuclear Station; that I signed this application as Vice President, Nuclear Operations of System Energy Resources, Inc.; and that the str.tements made and the matters set forth therein are true and correct te the best of my knowledge, information and belief.
WVM _
l W. T. Cottle 1
S.' ATE OF MISSISSIPPI C0bl'T OF HINDS SUCSCRIBE0 AND SWORN T0 be re me, a Notary Publip, in and for the County and State above named, this day of /UfA%46 ) , 1988.
(SEAL)
/J u , t u] YW I My commission expires:
r, c ,t- . s t.:t ::st 4
J14AECM88120201 - 4
SUBJECT:
NL-88/16, Technical Specification changes to address reload Cycle 4.
Technical Specifications 3/4.2.1, 3/4.2.4 and 5.3.1.
Figures 3.2.1-1, 3.2.1-Id, 3.2.1-le, 3.2.1-2, 3.2.3-1, 3.2.3-2 and 3.2.4-1.
Bases 2.1.1, 2.1.2, 3/4.2.1 and 3/4.2.3.
Affected Pages: 82-la, B2-2, 3/4 2-1, 3/4 2-2, 3/4 2-2d, 3/4 2-2e, 3/4 2-3a, 3/4 2-5, 3/4 2-6, 3/4 2-7, 3/4 2-7a, 83/4 2-1, 83/4 2-4, 83/4 2-6 and 5-5.
DESCRIPTION OF CHANGES:
- 1. Bases 2.1.1: (Administrative) Change "Exxon Nuclear Company" to "Advanced Nuclear Fuels Corporation". Change "ENO" to "ANF" at two locations.
- 2. Bases 2.1.2: (Administrative) Change "Once" to "One" and "ENC" to "ANF".
TECH - 1
- 3. Specification 3/4.2.1: Revise text to delete reference to fuel type 8CR210, to reference MAPLHGR curves for one new 8x8 fuel type and new 9x9-5 Lead Test Assemblies (LTAs), and to defineSinn'eLoopOperation(SLO)limitforthe9x9-5 LTAs.
4 Figure 3.2.1-1: Revise the figure to provide a bounding MAPLHGR curve for Cycle 4 for all 8x8 fuel during single loop operation. Change title of figure.
- 5. Figure 3.2.1-1d: Add one MAPLHGR curve for new ANF 8x8 fuel type.
v or new 9x9-5 LTA.
- 6. Figure 3.2.1-le: Add one MAPLHGR curvs-
- 7. Figure 3.2.1-2: Add MAPFAC curves for Non loop Manual and loop f
Manual modes based on full ANF core. Delete the 102.5%
and 107% maximum core flow MAPFAC f curves for ANF fuel and the 102.5% maximum core flow curve for GE fuel.
Revise the 107% maximum core flow MAPFAC f for GE fuel to delete that portion of the curve with MAPFACf greater than 0.06 and change the curve description.
- 8. Figure 3.2.3-1: Add MCPR curves for Non Loop Manual and Loop Manual f
modes based on full ANF core. Delete the 102.5% and 107% maximum core flow MCPR f curves.
TECH - 2 t
- 9. Figure 3.2.3-2: Revise the figure to show MCPR p limit based on full ANF Core.
- 10. Specification 3/4.2.4: Delete references to GE fuel LHGR.
(Administrative) Delete references to ENC.
- 11. Figure 3.2.4-1: Revise the figure to add one LHGR curve for new 9x9-5 LTA. (Administrative) Change title of figure.
(Administrative) Correct plotting error in the LHGR curve for 8x8 fuel type.
- 12. Bases 3/4.2.1: Add references to MAPLHGR curves for new ANF fuel types. Revise text to discuss revised MAPLHGR curve for single loop operation. Revise text to discuss ,
MAPF'C curves based on Loop Manual and Non loop Manual f
medes of operation. Delete description of flow runout to 102.5% and 107% of rated flow. Revise text describing the MAPFAC p curves.
- 13. Bases 3/4.2.3: Delete description of evaluation of transients for GE core. Revise text to discuss MCpR curves based on f
Loop Manual and Non Loop Manual modes of operation.
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I Delete description of flow runout to 102.5% and 107% of
! rated flow. Delete cycle-specific discussion for MCPRg .
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(Administrative) Add reference for Figure B3/4 2.3 1 l
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'14 Specification 5.3.1: Rcvise text to generalize description for all Cycle 4 fuel types.
DISCUSSION:
Reasons for Changes The proposed Technical Specification changes reflect:
o Insertion of new ANF reload fuel batch loaded for operation during Cycle 4.
o introduction of four ANF 9x9-5 Lead Test Assemblies to deronstrate operational performance prior to full 9x9-5 reload in Cycle 5.
o Revision of thermal limits for full ANF core based on ANF calculational methodology.
Discussion of Changes Specification 3/4.2.1 is revised to add one MAPLHGR curve each for the new ANF 8x8 fuel type and 9x9-5 LTAs to be loaded in Cycle 4 The SLO MAPLHGR l
limit for the 8x8 ANF fuel is defined as the 8x8 SLO MAPLHGR value (Figure i
3.2.1-1) multiplied by the minimum of the SLO MAPFACf, MAPFAC p or 0.86.
The SLO MAPLHGR limit for the 9x9-5 LTA is defined as the 9x9-5 MAPLHGR multiplied by the minimum of the corresponding MAPFAC f, MAPFAC p or 0.86.
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Figure 3.2.1-1 is revised to pro, de a bounding MAPLHGR curve for Cycle 4 for all 8x8 fuel types durina single loop operation.
Figures 3.2.1 2 and 3.2.3-1 are revised to define flow dependent thermal limits, MAPFAC and MCPR , respectively, based on a conservative bound of 7 f the maximum credible recirculation flow. An increase to the maximum core flow is assumed to occur by the slow opening to the maximum open position of one or both of the recirculation flow control valves. Separate consideration is given to the "Locp Manual" and "Non Loop Manual" modes of For the Non Loop Manual modes, both valves are assumed to open 4 operation.
simultaneously since a single centroller determines the position of both i 1
recirculation flow control vr.lves. For the Loop Manual mode, the valve positions are controlled irdependently and only one valve can credibly be assumed to open. The MAPFAC f ard MCPR f curves for 10?.5% flow and 107%
flow are deleted and replaced by curves for the Non Loop Manual and Loop Manual operational modes. The 107% flow MAPFAC f curve for GE fuel is retained for use in determining the off-rated MAPLHGR during single loop operation. The p3rtion of this curve for MAPFAC f values above 0.86 is l
deleted.
I Figure 3.2.3-2 is revised to define MCPR p limits for Cycle 4 as a function j of power level. The limit is based on ANF methodology applied to a full ANF core.
Specification 3/4.2.4 is revised to delete referent.es to the LHGR for GE fuel.
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Figure 3.2.4-1 is revised to add one LilGR curve for the new ANF 9x9-5 LTA to be loaded in Cycle 4 The LHGR curve for the 8x8 fuel in Figure 3.2.4-1 is re-drawn to correct a plotting error in order to.be consistent with the values shown.
Specification 5.3.1 is revised to generalize the description for all Cycle 4 fuel types.
The affected bases were revised to reflect the Techn! cal Specifications changes and to provide corresponding justification.
JUST!,F_ICATION:
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MAPLHGR Limits i The MAPLHGR limits for previously loaded ANF fuel were established on a cycle-independent basis and remain applicable for Cycle 4. Single Loop Operation is discussed in the following section. A MAPLHGR limit for the l
new 8x8 fuel type is added to the Technical Specifications for Cycle 4.
The MAPLHGR limit for the new fuel type is determined u ng methods l
consistent with those used for fuel types introduced is*c the core for previous reloads. The MAPLHGR limit was established from the LHGR limits by dividing the ANF 8x8 LHGR limit by the exposure dependent maximum local l
l peaking factor. The MAPLHGR limit is consistent with the LHGR limit so l
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that at reduced power and/or reduced flow, the allowable LHGR will be limited by the product of the MAPFACp or MAPFAC f multipliers and the MAPLHGR limits.
Single Loop Operation MAPLHGR The MAPLHGR limit for Single Loop Operation (SLO) for the 8x8 fuel has been conservatively revised to bound Cycle 4 operation. The MAPLHGR for ANF fuel inserted during the first reload is bounded by the SLO MAPLHGR limits for exposures up to 28.5 GWd/MTV. This exposure is expected to be exceeded by the first ANF reload batch during Cycle 4. Accordingly, the Cycle 4 SLO MAPLPGR limit has been conservatively defined. This limit is the minimum of the MAPLHGR limits applicable during Cycle 4 for all Ox8 fuel types and the Cycle 3 SLO MAPLPGR limit. As in Cycle 3, the Cycle 4 off-rated SLO MAPLHGR operating limit for all 0x8 fuel types is determined l
f by multiplying the SLO MAPLHGR limit by the minimun of the SLO MAPFACf .
MAPFAC or 0.86. The SLO MAPFAC is based on the limiting MAPFAC f curve p f for GE fuel . The portion of this curve for MAPFACf values above 0.86 is deleted since 0.86 is the raximum allowable value during SLO.
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Flow Dependent Thermal Limits The flow dependent thermal limits, MCPR fand MAPFACf . were constructed based on ANF analyses for GGNS-1 while assuring adequate margin to limits following a flow runout event. An added conservatism to bound possible f
l variations in subsequent cycles was introduced (see attached report NES00-88-003). These linits are applicable for a full ANF core and were t
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confirmed by ANF for Cycle 4 (see attached report ANF-88-149). Each of the limits is determined for both the Loop Manual and the Non loop Manual modes of operation.
The Loop Manual mode of operation is the only mode in which the two recirculation loops are controlled independently. The most severe flow runout event in this mode involves the flow increase of one loop while the other loop is unaffected (i.e., recirculation flow control v31ve (FCV) position is unchanged). The initial and final core flow values for the one loop runout esent are provided in report NES00-88-003. The flow increases were determined conservatively to bound the expected increases in flow rates. Tlie flow increase as a result of the one loop runout event is smaller than 1he increase during the two loop runout event.
In the Non Loop Manual modes of operation, a single controller controls
! the position of both recirculation FCVs. The most severe flow runout event for the Non Loop Manual trodes of operation, is, therefore the two loop runout event. A conservative maximum core flow (110% of rated core flow) is used to bound the marimum achievable core flow for the limiting runout event.
I Power-Dependent MCpR Limit The power-dependent MCPR, MCPR p
, wl.s constructed using ANF methodology for a full ANT core. The MCPR above 40% of rated power is based on the p
generic ANF CRWE results for BWR-6. The Cycle 3 limit has been confirmed l
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at and below 40% of rated power and at 100% power. Analyses of the most limiting core-wide transients and local events confimed the MCPR p limit for use in Cycle 4 (see atached report ANF-88-149).
Lead Test Assemblies _
The insertion of four ANF 9x9-5 LTAs in non-limiting core locations is inconsequential to the behavior of the core, which includes a total of 800 fuel assemblies. Analyses were perfomed to assure that operating limits determined to apply to an all 8x8 core would be applicable to the LTAs.
The LTA design is mechanically and thermal-hydraulically compatible with the 8x8 fuel core. The thermal and mechanical performance of the LTA for the limiting events analyzed by ANF for Cycle 4 are bounded by the 8x8 ,
fuel performance. The MAPLHGR and LHGR limits (including limits for SLO) provide adequate margin to the requirements of 10CFR50.46 and the fuel mechanical design criteria, respectively. Additional margin is provided i by placing the LTAs in non-limiting locations. Results of specific l analyses are provided in ANF report ANF-88-149.
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