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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
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E(E MISSISSIPPI POWER & L Helping Build Mississippi P. O. BOX 1640. J ACKSON, MISSISSIPPI 39205 July 20, 1984 I.Offf[IO.,o.,,,.oem.
U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 Attention: Mr. Harold R. Denton, Director
Dear Mr. Denton:
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-13 File 0260/0840/L-860.0 Proposed Amendment to the Operating License (PCOL-84/17)
AECM-84/0374 In accordance with the provisions of 10 CFR 50.59 and 10 CFR 50.90, Mississippi Power & Light (MP&L) requests an amendment to License NPF-13, for Grand Gulf Nuclear Station (GGNS) Unit 1. This proposed amendment is being submitted to comply with the request contained in the July 17, 1984 letter from E. G. Adensam (NRC) to L. F. Dale (MP&L) regarding the TDI Engine Inspection.
In accordance with provisions of 10 CFR 50.30, three (3) signed originals and forty (40) copies of the requested amendment are enclosed. The attachment provides the complete technical justification and di .cussion to support the requested amendment. This amendment has been reviewad and accepted by the Plant Safety Review Committee (PSRC) and the Safety Review Committee (SRC).
Based on the guidelines presented in 10 CFR 50.92, it is the opinion of MP&L that this proposed omendment involves no significant hazards considerations.
Based upon an evaluation of the proposed changes, MP&L has concluded that there should be no additional fee for the proposed technical specification changes.
Yours truly
'A JBR:rg Attachments: GCNS PCOL-84/17 (l
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PDR ADOCK 05000416 PDR P
Member Middle South Utilities System
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3 AECM-84/0374 Peg 2 2 MISSISSIPPI POWER O LIZHT C2MPANY cc: Mr. G. B. Taylor (w/o)
Mr. R. B. McGehee (w/a)
Mr. N. S. Reynolds (w/o)
Mr. J. P. O'Reilly (w/a)
Regional Administrator Region 11 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30303 Mr. R. C. DeYoung, Director (w/a)
Office of Inspection & Enforcement U.-S. Nuclear Regulatory Commission Washington, D.C. 20555 Dr. Alton B. Cobb (w/a)
State Health Officer State Board of Health Box 1700 Jackson, Mississippi 39205 e
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-BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE NO. NPF-13 DOCKET No. 50-416 IN THE MATTER OF MISSISSIPPI POWER & LIGHT COMPANY and MIDDLE SOUTH ENERGY, INC.
and SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION AFFIRMATION I, J. B. Richard, being duly sworn, stated that I am Senior Vice President - Nuclear of Mississippi Power & Light Company; that on behalf of Mississippi Power & Light Company, Middle South Energy. Inc., and South Mississippi Electric Power Association I am authorized by Mississippi Power &
Light Company to sign and file with the Nuclear Regulatory Commission, this application for amendment of the Operating License of the Grand Gulf Nuclear
, Station; that I signed this application as Senior Vice President - Nuclear of Mississippi Power _ & Light Company; and that the statements made and the matters set forth therein are true and correct to the best of my knowledge, information and belief.
( k J . B/. Rf' chard
- STATE OF MISSISSIPPI g COUNTY OF HINDS Public, in and for the County andSUBSCRIBED AND SWORN State above named, TOday this fsPf4 before of me,CZ->
a Notary / vt 1984, a
(SEAL) l Notiry Puhl c My commission expir.s
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r = p, -N SUgJECT: -Technical Specification 4.8.1.1.2.a.5, 4.8.1.1.2.d.3, 4.8.1.1.2.d.9, 4.8.1.1.2.d.10, and Bases 3/4.8.1. The affected pages'are 3/4 8-3, 3/4 8-4, 3/4 8-6, and B 3/4 8-1.
DESCRIPTION OF CHANGES:
This proposed change reduces the required loading, during testing, for diesel generators 11 and 12. It is proposed that the present 7000 KW and 7700 KW loading requirements in the Technical Specifications be reduced to 5450 KW. This change also applies a maximum load of 5740 KW to the diesel generators during the required surveillance testing. This change also would limit the auto-connected loads on the Division I and II diesel generators.
JUSTIFICATION: The NRC has expressed a concern regarding the reliability of the TDI diesels at GGNS and requested in a letter from E. G.
Adensam to L. F. Dale, dated July 17, 1984 (MAEC-84/0267),
that MP&L propose changes to the Technical Specifications. It was requested that the changes specify that the monthly and the 18 month surveillance testing be conducted at an engine load corresponding to 185 psig Brake Mean Effective Pressure (BMEP). MP&L has determined that a generator load of approximately 5740 KW corresponds to 185 psig BMEP.
In complying with the NRC request, MP&L has determined that the test values for the diesel generator loading should be specified as at least 5450 KW, but not to exceed 5740 KW.
The lower value of 5450 KW is approximately 78% of the continuous rating of the diesels and is greater than the auto-connected loads required for the loss of offsite power and post-LOCA conditions. Loss of offsite power loads and LOCA loads required to shutdown the plant and maintain it in a safe condition represent less than 70% of the continuous rating. There exists sufficient capacity and capability in the onsite power supplies to assure that (1) the fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded and (2) the core is cooled and containment integrity and other vital functions are maintained in the event of postulated accidents as requried by GDC-17.
The upper limit of 5740 KW will ensure that the NRC requested value is not exceeded during testing. These limits (5450 KW and 5740 KW) establish a reasonable, achievable test band that will permit verification of operability while ensuring that the requested load limit is not exceeded.
Requiring verification that the auto-connected loads do not exceed the reduced value will ensure that the sequential 4
loading of the diesels during emergency operations will not exceed 5740 KW. .
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. s Testing' at this reduced load would still demonstrate that the diesel generators are capable of providing the required electrical power necessary to supply the loads required for a loss of offsite power or LOCA event. Limiting the engine load during testing to this reduced load would enhance the potential for. engine availability during accident conditions by reducing the stresses and wear placed on the engine components due to the frequent surveillance testing.
SIGNIFICANT HAZARDS CONSIDERATIONS:
The proposed change limits the load at which the Division I and Division II diesel gener. tors are tested at during the surveillance testing. This limit has been established per NRC request in order to better assure the reliability of the diesel generators. The new test limit is greater than the maximum loadir.g required to safely shutdown the plant following a design basis accident.
This change in the diesel generator loading during testing does not increase the probability of different accidents or equipment malfunctions from those currently evaluated in the FSAR. This change does not reduce the margin of safety as the design continuous load rating of the diesel generators has not been affected. Thus no significant hazards considerations are associated with this change.
It is the MP&L position that such limits are not required; however, these limits will decrease the working stresses and wear in the diesel engine components. This reduction would of course, contribute to the enhanced reliability and life of the engine. _
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. ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class 1E distribution system,shall be:
- a. Determined OPERABLE at least once per 7 days by verify.ing correct breaker alignments and indicated power availability, and
- b. Demonstrated OP'ERABLE at least once per 18 months during shutdown by manually transferring unit power supply from the normal circuit to the alternate circuit.
4.8.1.1.2 Each of the above required diesel generators shall be demonstrated CPERABLE:
- a. In accordance with the frequency specified in Table 4.8.1.1.2-1 on a STAGGERED TEST BASIS by:
- 1. Verifying the fuel level in the day tank.
- 2. Verifying the fuel level in the fuel storage tank.
- 3. Verifying the fuel transfer pump starts and transfers fuel from the storage system to the day tank. -
- 4. Verifying the diesel starts from ambient condition and accelerates to at least 441 rpm for diesel generators 11 and 12 and 882 rpm for diesel generator 13 in less than or equal to 10 seconds. T,he generator voltage and frequency shall be 4160 **426 volts and 60
- 1.2 Hz within 10 seconds after the start signal. The diesel generator shall be started for this test by using one of the following signals:
a) Manual.
b) Simulated loss of offsite power by itself.
l c) Simulated loss of offsite power in conjunction with an ESF actuation test signal.
d) An ESF actuation test signal by itself.
[ 5. Verifying the diesel generator is synchronized, leaded to greater i than or equal toJ000 h" for diesel generators 11 and 12 and I 5450 W W } 3300 kW for diesel generator 13 in less than or equal to 60 seconds, nok b *Fe**d and operates with these loads for at least 60 minutes.
O 6. Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.
- 7. Verifying the lifessure in all diesel generator air start receivers to be greater than or equal to:
a) 160 psig for diesel generator 11 and 12, and b) 175 psig for diesel generator 13.
l b. At least once per 31 days and after each operation of the diesel whpre the period of operation was greater than or equal to I hour by checking for and removing accumulated water from the day fuel tanks.
GRAND GULF-UNIT 1 3/4 8-3 Amendment No. 7, 8,3 9 -
7_ __ .__.y,--,--.,-----m * ' " " - ' - ' " " " ' ' -
' ELECTRICAL POWER SYSTEMS
-SURVEILLANCE REQUIREMENTS (Continued)
- c. . At least once per 92 days and from new 611 prior to addition to the storage tanks by verifying that a sample obtained in accordance with ASTM-D270-1975 has a water and sediment content of les's than or equal to. 05 volume percent and a kinematic viscosity 9 40*C;of greater than or equal to 1.9 but less than or equal to 4.1 when tested in accordance*
with ASTM-D975-77, and an impurity level of less than 2 mg. of insolubles
' per 100 al. when tested in accordance with ASTM-D2274-70, except that the test of new' fuel for impurity level shall be performed within 7 days after addition of the new fuel to the storage tank. '
- d. At least once per 18 months, during shutdown, by:
- 1. Subjecting the diesel to an inspection in accordance with pro-
- cedures prepared in conjunction with its manufacturer's recom-mandations for this class of standby service.
- 2. Verifying the diesel generator capability to reject a load of greater than or equal to 1200 kW (LPCS Pump) for diesel generator
_. 11, greater than or equal to 550 kW (RHR B/C Pump) for diesel generator 12, and greater than or equal to 2180 kW (HPCS Pump) for diesel generator 13 while maintaining less than or equal to 75% of the difference between nominal speed and the overspeed trip setpoint, or 15% above nominal, whichever is less.
- 3. Verifying the diesel generator capability to reject a load of al leas 4 s4so kW 7999-hW.for diesel generators 11 and 12 and 3300 'kW for diesel g4 4 4. we=d / generator 13 without tripping. The generator vo hage shall not ,
me gw exceed.5000 volts during and following the load rejection.
l
- 4. Simula' ting a loss of offsite power by itself, and:
a) For Divisions 1 and 2:
- 1) Verifying deenergization of the emergency busses and load shedding from the emergency busses.
l 2) Verifying the diesel generator starts on the auto-start f signal, energizes the emergency busses with permanently
! connected loads within 10 seconds, energizes the auto-
[ connected. shutdown loads through the load sequencer and j .
operates for greater than or equal to 5 minutes while its l- generator is loaded with the shutdown loads. After ener-
! gization, the steady state voltage and frequency of the j
emergency busses shall be maintained at 4160 1 416 volts and 60 1 1.2 Hz during this test.
b) For Division 3:
- 1) Verifying de-energization of the emergency bus.
- 2) Verifying the diesel generator starts on the auto-start signal, energizes the emergency bus with the loads within
, 10 seconds and operates for greater than or equal to L 5 minutes while its generator is loaded with the sh0tdown
! . loads. After energization, the steady state voltage and frequency of the emergency bus shall be maintained at 4160
- 416 volts and 60 i 1.2 Hz during this test.
l t
GRAND GULF-UNIT 1 3/4 8-4 Amendment No. 7,3 9 -
' ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) g 8. Verifying that all automatic diesel generator trips are 4j automatically bypassed upon an ECCS actuation sigsal except:
4}gg g a) For Divisions 1 and 2, engine overspeed, gen'erator -
3 differential current, low lube oil pressure,'and generator g ,1 g u j} ,
ground overcurrent.
9 w 2 b) For Division 3, engine overspeed and generator differer.tial J #
~MM&
3 r% N current.
g s * -$ o -8.g) laring the. first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of this test, the diesel L
l ::: # $ ,) .6 f be loaded toTreater4an or equal to 7700 esel gen-i U erators 11 and 12 and 36h-fo generator 13 and during Je +# 6 m 3 jj,f Lhe remaining 22 hour2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> s test, E,e'dieset generator shall
~
u~ ; 4#g '- be loaded '
.or diesel generators 11 and If'ahd-3300.JM i
' .J -+w sel oenerator 13./ The generator voltage and frequency I 4 shall be 4160 2 416 volts and 60 2 1.2 Hz within 10 seco.1ds after
-' ) h $, p the start signal; the steady state generator voltage and frequency
.- shall be maintained within these limits during this test. Within 0 7 h4 -5 $ 5 minutes after completing this 24-hour test, perform Surveillance
- 3 I. r -
Requirement 4.8.1.1.2.d.7.a).2) and b).2)*.
- 0. Verifying that the auto-connected loads ac (tesel generatorr
)b[Ef*
5- i do not exceed t'e e^^tt"ucu: -'tf ;; ef 000 kW for di'5'l r e DN generato.rs 11 and 12 and 3300 kW for diesel generator 13.
lj lli
. Verifying the diesel generator's capability to:
}In$
A N- a) Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simulated restoration of offsite power,
! b) Transfer its loads to the offsite power source, and l c) Be restored to its standby status.
- 12. Verifying that with the diesel generator operating in a test mode and connected**to its bus that a simulated ECCS actuation signal:
a) For Divisions 1 and 2, overrides the test mode by return-l ing the diesel generator to standby operation.
I b) For Division.3, overrides the test mode by bypassing the i diesel generator automatic trips per Surveillance Require-ment 4.8.1.1.2.d.8.b). *
- 13. Verifying that with all diesel generator air start receivers
- pressurized to less than or equal to 256 psig and the compres-l sors secured, the diesel generator starts at least 5 times from ambient conditions and accelerates to at least 441 rpm for diesel generators 11 and 12 and 882 rpm for diesel generator 13 in ,less than or equal to 10 seconds.
, "If Surveillance Requirement 4.8.1.1.2.d.4.a)2) or b)2) are not satisfactorily completed, it is not necessary to repeat the preceding 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test. Instead, the diesel generator may be operated at rated load for one hour or until operating temperatures have stabilized.
GRAND GULF-UNIT 1 3/4 8-6 Amendment No. 7, 9, -
a..t 3/4.8 ELECTRICAL POWER SYSTEMS BASES 3/4.8.1, 3/4.8.2 and 3/4.8.3 A.C. SOURCES. D.C. SOURCES and ONSITE POWER DISTRIBUTION SYSTEMS
' The OPERA 8ILITY of the A.C. and D.C. power sources and associated distribution systems during operation ensures that sufficient power will be i available to supply the safety related equipment required for (1) the safe shutdown of the facility and (2) the mitigation and control of accident ;
conditions within the facility. The minimum specified independent and ~
redundant A.C. and 0.C. power sources and distribution systems satisfy the '
requirements of General Design Criteria 17 of Appendix "A" to 10 CFR 50.
The ACTION requirements specified for the levels of degradation of the ,
power sources provide restriction upon continued facility operation commen-surate with the level of degradation. The OPERABILITY of the power sources
'are consistent with the initial condition assumptions of the accident analyses -
and.we based upon maintaining at least Division 1 or 2 of the onsite A.C. and
'O.C. power s6urces and associated distribution systems OPERABLE during accident conditions coincident with an assumed loss of offsite power and single failure of the other onsite A.C. Division 3 supplies the high pressure core spray (HPC5). system only., source.
.. The A.C. and D.C. source allowable out-of-service times are based on Regulatory Guide 1.93, " Availability of Electrical Power Sources", December i' 1974. When diesel generator 11 or 12 is inoperable, there is an additional trains, ACTION componentsrequirement todepend and devices, that verify on that theall required remaining systems, OPERABLE subsystems,l diese gen- ,
erster 11 er 12 as a source of emergency power, are also OPERA 8LE. This '
requirement is intended to provide assurance that a loss of offsite power event will not result in a complete loss of safety function of critical .
systems during the period diesel generator 11 or 12 is inoperable. The tern-verify as used in this context means to administrative 1y check by examining !
Iogs or other information to determine if certain con.ponents are out-of-service for maintenance or other reasons. It does not mean to perform the surveillance requirements needed to demonstrate the OPERA 81LITY of the .
component. -
The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that i (1) the facility can be maintained in the shutdown or refueling condition for extended time periods and (2) sufficient instrumentation and control capability 1,s available for monitoring and maintaining the unit status. ;
The surveillance requirements for demonstrating the OPERABILITY of the diesel generators are in accordance with the recommendations of Regulatory Guide 1.9, " selection of Diesel Generator set Capacity for Standby Power Supplies". March 10, 1971, Regulatory Guide 1.108, " Periodic Testing of Diesel :
Generator Units Used as Onsite Electric Power Systems at Nuclear Power s Plants". Revision 1 August 1977 and Regulatory Guide 1.137" Fuel-011 Systems .
for Standby Diesel denerators", Revision 1, October 1979, sAeff Me bividen 1 *d ;
A. dingsf /*a.e/ f**NM r*turemek /fs+ ween rw.sMei rd a.s Mofed [
in s let%. &*m 1.G. Ade.nsan h L.F. Dak,daled 19 -Tults 19N .
GRAW GULF-UNIT 1 8 3/4 8-1 l -
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