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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
^
1 l
ES Ent:rgy f"'= y="a"* '"'
Operations -
' 0 w . 6.. s l
J W. T. Cottle August 15, 1991 O.S. Nuclear Regulatory Commission Hall Station PI-137 Washington, D.C. 20555 Attent(on: Document Control Desk
Subject:
Grand Gulf Nuclear Statlon Unit 1 Docket No. 50-416 License No. NPF-29 P.emoval of 4.16 kV Bus Un6 rvoltage (BOP Lond Shed)
Actuat ion Instrumentation Technical Specification Requirements Proposed Amendment to the Operating License (PC0h-91/20)
GNRO-91/00146 l'
Gentlemen:
Entergy Operations, Inc. is submit. ting by this lett-r a proposed amendment to the Grand Gulf Nuclear Station Opernin.- License. The proposed aroendment requests changes to fechnical Specification Table 3.3.3-1, " Emergency Core Cooling Syttom Actuation Instrumentation,"
Table 3.3.3-2, " Emergency Core Cooling System Act.uation Instrumentation E 'ints," and Table 4.3.3.1-1, " Emergency Core Cooling System Actuation Ins umentation Surveillance Reluirements."
The proposed change would remove requirement > for-tne Balance of ilant
-(DOP) Land Shedding feature of the Land Shed and Sequencing System. This feature uns a causal factor in two automatic reactor trip t.ransients init iated by non-valid DOP load shed r,!gnals. Due to the severity of the transients (i.e., multiple snfety system acturitions), the prohnbility of recurrence, nnd absence of a safety basis for thn BOP Load Shedding feature, we request that. this proposed amendment receive expedited review and response. Upon approval, Entergy Operations intends to nroceed with disabli .g the BOP Load Shedding feature in order to prevent similat
-transients in the future.
In accordance with the provinionn of 10CFR50.4, .the signed original of the requested amnndment is enclosed. Attachment 2 provides the discussion and justification to support the requested amendment. This amendment request has been reviewed and accepted by the Plant Safety Paview Committee and the Safety Review Committee.
G9108081/SNLICFLR - 1.
DOQ~l^^9108220246.910915
' OO!
PDR ADOCK 05000416 :
P- PDR
/(/
August 15, 1991 GNRO-91/00146 Page 2 of 3 Based on the guidelines given in 10CFR50.92, Entergy Operations has 4
concludnd that. thir. proposed amondment involves no significant hazards considerations.
Yours truly,
} w ro*ent"~
WTC/BSF/ams attachments: 1. Affirmation per 10CFR50.30
, 2. GGNS PCOL-91/20 Mr. D. C. liintz (w/a) cc:
4 Mr. J. I.. Mathis (w/a)
Mr. R. B. McGehen (w/a)
, Mr. N. S. Reynolds (w/a)
Mr.11. I.. Thomas (w/o)
Mr. F. W. Titus (w/a)
Mr. Stewart D. Ebneter (w/a)
Regional Administrator
, U.S. Nuclear Regulatory. Commission Region II 101 Mariotta St...N.W., Suito 2900 Atlanta, Georgia 30323 Mr. L.1.. Kintner, Project Manager (w/a)
Office of Nuc1 car Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 11D21 Washington, D.C. 20555 Dr. Alton B. Cobb (w/a)
Stato lloalth Of ficer State Board of floalt h P.O. Ilox 1700 4
Jackson, Mississippi 39205 G9108081/SNLICFLR - 2
,,- - - , . . - - . --. , .- ,- e
I l
l-11EPORE Tile UNITED STATES NUCI. EAR REGill.ATORY COMMISSION I.ICENSE NO. N PF- 29 DOCKET NO. 50-416 IN Tile MATTER OF MISSISSIPDI POWER & I,1CIIT COMPANY and SYSTEM ENERGY RESOURCES, INC.
and SOUTil MISSISSIPPJ El.ECTRIC l'0WER ASSOCI ATION and ENTERGY OPERATIONS, INC.
AFFIkMATIDS 1, W. T. Cottle, botng duly sworn, stato that I am Vice Prnsident, Operations GGNS of Entorgy Operations, Inc.; that on behalf of Entergy ,
Operations. Inc., System Energy Rnsourcos, Inc., and South Mississippi Electric Pownr Assocle. tion I am authorized by Entorgy Operations, Inc. to sign and filn with thn Nuclear Regulatory Cammission, this application for amnndment of thn Operating 1,lennso of the Grand Gulf Nuclear Station; that I-signnd this application ari Vice Prnsident, Operations GGNS of Ent ergy Operations, Inc.; and that thn statements mado and the matters set forth thornin are trun and correct to thn bnst of my knowindgn, informat ion and bolinf.
My - /' b r==
W. T. Cottle STATE OF MISSISSIPPI COUNTY OF CI.AIBORNE SUBSCRIBED AND SWORN f0 bnfore me, a Notary Public, in and for the County and State abovn named, this \h day of by d , 1991,
( SEAI.)
d h edYb1; ara \D O M Notnry ibi My commission expires:
yy ccmmhdan Drhes l# L M G9108081/SNLICFI.R - 4
Attachment 2 to GNRO-91/00146 PROPOSED CHANGE TO THE 0PERATING LICENSE-REMOVAL OF 4,16 KV BUS UNDERVOLTAGE (BOP LOAD SHED) ACTUATION INSTRUMENTATION TECHNICAL SPECIFICATION REQUIREMENTS
-(GGNS PCOL-91/20) 4 4
5 G9108081/SNLICFLR - 6 3 ,
gn--w r rw- a
. - . - - ~ . _ . - . . . - . - - . - - -.. - . . _ . - .. . - .. . .- -
Attachmnnt 2 to GNRO-91/00146 Page 1 of 5 l
A. SUBJECT
- 1. Removal of 4.16 kV Bon Undervoltage Balance of plant (DOp) Load Shedding Actuation Instruunntation Technical Specification Requirements.
- 2. The affected Technical Specifications are:
- a. Table 3.3.3-1 page 3/4 3-29,
- b. Tahlo 3.3.3-2 page 3/4 3-32, and
- c. Table 4.3.3.1 pago 3/4 3-35a.
B. DISCUSSION
- 1. Thn proposed amendment request.s changns to Technical Specification Table 3.3.3-1, " Emergency Core Cooling System Actuation Instrumentation," Table 3.3.3-2, " Emergency Core Cooling System Actuat. ion Instrumentation Sotpoints," and Tabic 4.3.3.1-1, " Emergency Core Cooling dyntem actuatloc Instrumentation Surveillanco Requirements." The proposed change is described below.
- 2. The requested revision removes the requirementr, contained _in Iter. D.1.b of each of the a f fected tahins. This revision removes the operability, setpoints, and survn111ance requirements for the 4.16 kV Bus Undervaltago DOP Load Shedding circuits.
- 3. The affected Technical Specification pages are attached and marked up to reflect the proposed changes.
C. JUSTIFICATION / BACKGROUND' The 4.16 kV Bus Undervoltage BOP Load Shedding circuits are part of l
t he Load Shndit 3 and Sequencing . System (LS : rystem). Thi basic function of the 1.SS System is to disconnect (shed) and connect, automatically in sequence, loads on the Class IE buses. The hSS=
accomplishes this without degrading the -integrity, voltage, or frequency of thn Class IE pownr supply.
LSS System Safety Related Functions As discussed;in References 1 and'2, the LSS System depends on two means of detncting unacceptabic voltage levels in the Class 1E electrical system. These two methods are detecting the completo loss of voltage (primary method) or a sustained,- degraded voltage condition (secondary method) on a Class 1E 4.16 kV hus.
G9108081/SNb1CFLR - 7
Attachment 2 t o CNRO-91/00146
' age 2 of 5 One set of bistables monitor voltage at the 4.16 kV Class IE bus of its safety division. These bistablos are the primary method for detecting unacceptable voltage levels. A measured nominal voltage of less than 70 percent for 0.5 seconds indicates unacceptable degradation (completo loss of voltago) of the preferred (offsite) source powering the bus. The LSS then dt. connects the Class 1E niectrical system from the offsite source and sequences the loads onto the orsite Class lE source.
A second set of bistables act upon observing a nor.inal bus voltage between 70 porcent and 90 percent for 9 seconds when the bus is powered by the of fsite sourco. 7 %se histables provido the secondary method of detecting unacceptable voltage levels in the Class lE olectrical system. This condition is indicative of a severe degradation of the entirn grid since automatic relaying on the network would normally restore nominal voltage in much less than 9 seconds if tho transmission system were manageable. The LSS then disconnects the Class 1E niectrical system from the offsite souren and sequences the loads onto the onsite Class IE source.
These two methods provide the basis for the bounding accident analyses.
LSS System BOP Load Shedding Feature As discussed in Reference 1, a third set of hist 6bles measu o voltage on the Class IE buses. These bistables are actuated by an observed bus voltage of 80 percent, or less, of nominal. Upon receipt of both a Loss of Coolant Accident-(LOCA) signal and the 80 percent bus voltage signal, the LSS then disconnects (sheds) the BOP 6.9 kV and 4.16 kV buses from the offsite power source. Tho' BOP Load Shedding feature is inhibited if the second level of undervoltage protection provided by the LSS System has already act'iated. The operation of the BOP Load Shedding feature does not af fect the, operation of the Class 1E onsite clectrical power system. The successful operation of the BOP Load Shedding capability is not a prerequisite for any safety function.
This BOP Load Shedding capability was designed to offer a possible improvement in the voltago profile at the Class -1?E electrical buses
-under extreme system operating conditions. These operating conditions includa minimum grid voltage during -full power operation of both Units 1 and 2 with one service transformer out of service followed by a LOCA on one unit. This voltage improvement was desired to optimize Class 1E bus voltage when offsite power is available cluring the Design Basis Accident (DIIA).
The potential for. the extreme system operating condition. of minimum grid voltage during full-power operation of both' units no longer.
exists due to the cancellation of Unit 2. . As a reeult, tha potential for voi tage improvement is outweighed by the potential for trarcilents resulting from the non-valid operation of this feature. The successful operation of this feature is not credited in.the system voltage calculations for Unit 1.
G9108081/SNLICFLR - 8
Attachment 2 to GNRO-91/00146 Pago 3 of 5 Summary Deletion of the .hnical Specification requirements on the operability, setpoints, and testing of the BOP 1.oad Shedding capability is rnquested. This will allow for the fut uro removal of this feature of the LSS Syntem. Either this capability is not ,
required or its removal would rnsult in a nnt benefit to safety for the following reasons:
- 1. The potential for the extremo system operating r.ondition of minimum grid voltage during full-power operation of both units no lons,nr oxista due to the canenllat ion of Unit. 2.
- 2. Tho successful operation of this featuro is not credited in the system voltagn calculatious for Unit 1.
- 3. The successful operat.fon of this featurn is not a prorcquisite for any safety function including the proper operation of the Class lE elect.rical system. Thereforn, t.ho equipment associ9tod with the performance of this is non-safety related.
.4. The B0p Load Shedding circulty resulted'in non-valid sh6dding of the BOP loads on 09/16/90 and-07/28/91.- The shedding of-the B0p loads resulted in reactor trips (via turbine trips) and subsequert challenges to safety systems. Conroctivn actions taken prevent recurrence of these specific events. Ilownver, removal of-~this feature would provent recurrence of this trancient resulting from any event causing this featurn's--
non-valid operat.fon.
In order to segregate. the non-safety related equipment f rom thn-safety related LSS Systnm equipment, the LSS do ign 'Is modular. This allows for casy retroval of the BOP Load Shodding feature whilo assuring thorn is no adverso affect on the LSS Systora safety related functions.
l D. NO SIGNIFICANT IIAZARDS_ CONSIDERATIONS-
- 1. Entergy Operattons, Inc.1s- proposing the delotion of the requirement.n for t.be 4.16 kV Bun Undervol Lago 110P Load Shedding feature from the Technical Specificat.fons and subsequent removal of this featurn f rom the LSS System.
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- 2. Thn Commiss!on has provided standaros for.dotermining whethor a-no significatt nazards consideration exists as stated in 10CFR50.92(c).- A proposed amendment to an operating licenso involves no algnificant hazards' consideration if operation of
=the facility-in accordance with-the proposed amondment~ would not: -(1) InvcIve a significant increase in the probability or.
consequencen of an accident previously evaluatod; or (2):creato the possibility of a new or dif ferent kind of accident. from any accident previously evaluated; or (3) 17volve a significant~ !
reduction in a margin of safety.
--G9108081/SNLICFLR - 9
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Attachment 2 to GNRO-91/00146 page 4 of 5
- 3. Entergy Operations has ovaluated t he no significant hazards considerations in its request for a license amendment, in accordnnce with 10CPR50.91(a), Entergy Operatious is providing tho analysis of the proposed amendment against. the three-standards .In 10CFREO.92:
- a. No significant increase in the probability or consequences of an accident previously evaluated results from this chango.
(1) lon successful operat Jon of this feature is not assumed to prevent any accident. The potentini for the extremo system operating condition, for which this 4 feat.ure provided the greatest benefit, no longer exists due to tae cancellation of Unit 2.
Consnquently, the probability of occurrence of a_DBA LOCA with degraded grid conditions resulting in a concurrent Loss of Of fsito Power (LOP) could not. be significant ly af fected by the disabling of t.his <
i featuro. As a-result, the removal of the requirements (and thn removal of the font. urn) will not i significantly increase the probability of an accident.
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- (2) The success ful operation of th.is function is not -a-
- proroquisito for any safety function including tho-proper operation of the Class 1E: electrical system.-- l 1
As-a result, the removal of thn' requirements (and tho
- - removal of the feature) will.not increase tho -
consequences of: an accident.
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, (3) Thornfore,-tho-probability or. consequences of previously analyzed accidents are not; increased.
- b. The chango would not creato- the possibility of a new or '
i dif forent kind of accident - from any previously ' analyzed.-
4 (1) Tho - requested change wilI not cdd any plant- equipment,
' introduce any now modos ~ of pla,t operation,lorj add any -
new testing configurations.-
(2) Curront accident analysis . boun'd' degraded ' voltage .
conditions:affected by the removal of L this fnature.
(3) Thorofore, ' operating thn plant with_ the.proposet change will notferente the possibility of,s new or-
- dif forent: kind of accident; from 'any accident previously evaluated.
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,G9108081/SNLICFLR ;10_
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Attachment 2 to GNRO-91/00146-page 5 of 5
- c. This change would not involve a significant reduction in the margin of safety.
(1) The proposed change does not affect the methodology used in the offsite dose analysis nor the acceptance criteria associated with any accident analysis.
(2) The successful operation of this feature is not a prerequisite for any safety function and is not taken-credit for in the system voltage calculations for Unit 1.
(3) The non-inlid operation of this feature has resulted in challenges to safety systems at, the result of two turbino trips and associrted ' reactor trips. Removal of this feature will remove the possibility of this cause of unnecessary challenges to safety systems.
(4) Removal of the Bop Load Shedding capability-will result in a-not benefit to safety.
- 4. Based on the above evaluation, operation in accordance with the proposed amendment involves no significant hazards considerations.
E. REFERENCES
- 1. Grand Gulf Nuclear Station _ Final Safety Analysis yepoyte Updated-through Amendment 5, section 8.3.1.1.~3.
- 2. NUREG-0831, Safety Evaluation Report Related to-th9 Operation of Grand Gulf Nuclear Station, U.ij ts 11 and- 2, and Supplemen't v.
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