|
---|
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
-
>:n ..
b NYSTEM ENERGY RESOLIRCES, INC.
C m D U m n J:
May 2, 1988 hY.M U/ m U. S. Nuclear Regulatory Comission Washington, D. C. 20555 Attention: Document Control Desk Gentlemen:
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Implementation of GL 88-06: Revision to Technical Specifications Section 6.0 Proposed Amendment to the Operating License (PCOL-88/06)
AECM-88/0085 System Energy Resources, Inc. (SERI) is submitting by this letter a proposed amendment to the Grand Gulf Operating License to implement the Technical Specification changes encouraged by Generic Letter 88-06. The proposed amendment replaces the organiza+. ion charts in Technical Specifications Section 6.0 with more general organizational requirements. The proposed amendment confonns to the guidance provided in Generic Letter 88-06.
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 Comittee and the Safety Review Committee.
Based on the guidelines presented in 10 CFR 50.92, SERI has concluded that this proposed amendment involves no significant hazards considerations.
I In accordance with the requirements of 10 CFR 170.21, an application fee of $150 is attached to this letter.
You uly, l 1
ODK:bms .
l t, Attachments: 1. Remittance of $150 Applicati6n Fee
- 2. Affirmation per 10 CFR 50.30 / M y hp 0 0N ;
3.
cc: (See Next Page)
GGNS PCOL-88/06 -
if $g l i
8805100194 880502 I PDR ADOCK 05000416 1 P DCD N' l W. ' *A Y l wx J16AECM88041401 - 1 """'" "
AECM-88/0085 Page 2 cc: Mr. T. H. Cloninger (w/a)
Mr. R. B. McGehee (w/a)
Mr. N. S. Reynolds (w/a)
Mr.
Mr. R.H.C.L. Thomas Butcher (w/a (w/o))
Dr. J. Nelson Grace, Regional Administrator (w/a)
U. S. Nuclear Regulatory Commission Region II 101 Marietta St., N. W., Suite 2900 Atlanta, Georgia 30323 Mr. L. L. Kintner, Project Manager (w/a)
Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 14320 Washington 0.C. 20555 Dr. Alton B. Cobb (w/a)
State Health Officer State Board of Health Box 1700 ,
Jackson, Mississippi 39205 l
1 i
J16AECM88041401 - 2
l >
.a.
l f i l
i BEFORE THE l L UNITED STATES NUCLEAR REGULATORY COMMISSION
! l i i LICENSE N0. NPF-29 -
DOCKET NO. S0-416
- I IN THE MATTER OF s
l MISSISSIPPI POWER & LIGHT COMPANY !
I
, and SYSTEM ENERGY RESOURCES, INC. l and SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION l
- l AFFIRMATION l
l i I, 0. D. Kingsley, Jr., being duly sworn, state that I am Vice !
President, 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 System Energy Resources, Inc. to sign and file ;
- with the Nuclear Regulatory Commission, this application for amendment of the i i Operating License of the Grand Gulf Nuclear Station; that I signed this application as Vice President, Nuclear Operations of System Energy Resources,
- Inc.; and that the statements made and the matters set fortMtherein are true ,
and correct to the best of my knowledge, information and ef. ;
T). D.NKingfl , rp STATE OF HISSISSIPPI COUNTY OF HINDS
/
SUBSCRIBED AND SWORN T0 beforp me, a Notary Public, in and for the CountyandStateabovenamed,this1# day of c/)h , 1988.
g (SEAL) i
/ A -, r . C Notary Public M
i My commission expires: ,
rj t- ,r- 1, : .1. n:t J16AECM88041401 - 4
4 Attachment 3 to AECM-88/0085 A. SUBJECT
- 1. NLS 86/15 Implementation of Generic Letter 88-06: Revision to !
Technical Specifications Section 6.0. i
- 2. Affected Technical Specifications:
- a. Index - Page xix.
- b. Offsite, Administrative Controls Subsection 6.2.1 - Page 6-1 ;
4
- c. Unit Staff Administrative Controls Subsection 6.2.2 - Pages '
6-1 and 6-2
$- d. Offsite Organization, Figure 6.2.1 Page 6-3
- e. Unit Organization, Figure 6.2.2 Page 6-4.
i B. DISCUSSION
- 1. The proposed change replaces the organization charts currently in the !
Technical Specifications with more general organizational requirements. '
l Most aspects of the organization charts are already required by regulation, other Technical Specifications or the Updated Final Safety Analysis Report (UFSAR). The general requirements provided to replace !
the organization charts capture the essence of those organizational features depicted on the charts that are not covered by other specifications and are important to the NRC for ensuring the plant i
! will be operated safely. l
- 2. In Generic Letter (GL) 88-06, the staff determined that with appropriate changes to the administrative requirements, the onsite and offsite organization charts may be removed from the Technical I
Specifications. The staff also found that the above change will not J
reduce plant safety and it is generically applicable to all power 1' reactors. The staff concluded that removal of the organization charts from Technical Specifications will provide greater flexibility 1 for licensees to implement changes in both the onsite and offsite organizational structure, consistent with the Comission policy on Technical Specification improvement. The staff encouraged licensees to propose Technical Specification changes that are consistent with 4 the guidance provided in GL 88-06. I l
. 3. Consistent with the NRC guidance provided in GL 88-06 the following ;
j changes are proposed: I
- a. The index is modified to indicate the revised Technical
. Specification subsection title headings, i
- b. Subsection 6.2.1 is revised to be applicable for both offsite !
. and onsite organizations. The reference to Figure 6.2.1-1 is i
deleted and replaced with more general organizational requirements which capture the essential aspects of the I organizational structure that are defined by the existing onsite and offsite organization charts. ,
i J16AECM88041401 - 5
Attachment 3 to AECM-88/0085
- c. The reference to Figure 6.2.2-1 is deleted in Subsection 6.2.2.
In addition, a statement is added designating those positions
~
in the onsite organization that require a Senior Reactor Operator (SR0) license. -
- d. Figure 6.2.1-1 is deleted.
l
- e. Figure 6.2.2-1 is deleted.
- 4. Attached to this proposed Technical Specification change are the affected Technical Specification pages.
C. JUSTIFICATION ,
- 1. The content required in the Administrative Controls Section of the Technical Specifications is specified in 10CFR50.36.c(5). The ,
regulation requires that the Technical Specifications contain the ,
controls and provisions that are necessary to assure operation of ;
the facility in a safe manner and does not specifically require inclusion of organizational charts in the Technical Specifications.
Currently, organization changes result in System Energy Resources, 2.
Incorporated's (SERI) processing and the NRC's review of unnecessary .
license amendments. The benefit of this proposed change is that it ;
would permit SERI to implement changes to the structure of the :
offsite or onsite organizations without first having to obtain NRC approval through the issuance of a license amendment to update :
organization charts in the Technical Specifications. Replacement of the organization charts with more general organizational requirements i will eliminate this needless expenditure of resources for both ,
organizations.
- 3. As stated in GL 88-06, it has been the NRC's experience that ,
organization charts by themselves have been of little help in !
ensuring that the objectives of administrative control requirements !
are met. Specific operational requirements are required elsewhere in the Technical Specifications that bear more directly nn operational ;
safety than organization charts. The staff summarized that many of i the details shown on the onsite and offsite organization charts are ;
not essential to the safe operation of the facility. l
- 4. The staff's guidance issued in GL 88-06 stated that the only aspects of organization charts which are important to safety, not covered by :
other specifications, and must remain in Technical Specifications ;
are those listed below: t (a) A requirement that lines of authority, responsibility, and 1 communication shall be established and defined from the highest )
management levels through intermediate levels to and including i all operating organization positions. Those relationships l shall be documented and updated, as appropriate, in the fonn of ;
organization charts, functional descriptions of departmental '
responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. -
1 J16AECM88041401 - 6
Attachment 3 to AECM-88/0085 (b) Designation of an executive position that has corporate responsibility for overall plant nuclear safety and authority to take such measures as may be needed to ensure acceptable performance of staff in operating,rlaintaining, and providing technical support to the plant to ensure nuclear safety.
(c) Designation of a management position in the onsite organization that is responsible for overall unit operation and has control over those onsite activities necessary for safe operation and maintenance of the plant.
(d) Designation of those positions in the onsite organization that require a senior reactor operator (SRO) or reactor operator (RO) license.
(e) Provisions of sufficient organizational freedom to be independent of operational pressures to those individuals who perform the functions of health physics, quality assurance, and training of the operating staff.
SERI is adding the above information to Technical Specification Subsections 6.2.1 and 6.2.2 to replace those aspects important to safety contained in the organization charts (Figure 6.2.1-1 and 6.2.2-1) which are being deleted. The staff concluded in GL 88-06 that since the above cenditions will be maintained in the Technical Specifications, removal of the organization charts represents no reduction in current safety requirements.
1
- 5. SERI has ensured that the organizational information described in (a) above is incorporated in the UFSAR and is referenced in the proposed Technical Specification change. The current Grand Gulf Nuclear Station UFSAR contains the organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions as specified by 10CFR50.34(b)(6)(i). As required by 10CFR50.71(e), SERI submits annual updates to the UFSAR. Therefore, the NRC will continue to be inforned of organizational changes without having the organization charts in the Technical Specifications.
- 6. Figure 6.2.2-1 currently specifies that certain positions require an SR0 license. These qualification requirements are not designated elsewhere in the Technical Specifications outside of the organization chart in Figure 6.2.2-1. For this reason, a statement is being added to Technical Specification 6.2.2 specifying the positions which require an SRO license that were designated in Figure 6.2.2-1.
Table 6.2.2-1 will remain to indicate the minimum shift crew composition and the number of personnel required to have an R0 license on shift. Positions which require havir been an SR0 or having been certified on a plant of this type are currently j indicated in UFSAR Figure 13.1-2 and will remain as such. Therefore, i no position qualifications will be lost when Figure 6.2.2-1 is deleted.
t J16AECM88041401 - 7
Attachment 3 to AECH-88/0085
- 7. The Technical Specifications have been examined for additional references to the organization charts and none were found other than those in the attached affected Technical Specification pages.
- 8. The guidance provided in GL 88-06 has been used to prepare this proposed Technical Specification amendment request. The proposed changes do not differ from the GL 88-06 guidance other than in the titles and names of various positions.
D. SIGNIFICANT HAZARDS CONSIDERATION
- 1. The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated because replacement of the organization charts with more general organizational requirements in the Technical Specifications is administrative in nature. No physical alterations of plant configuration or changes to setpoints or operating parameters are proposed. These changes do not alter SERI's comitment to maintain a management structure that contributes to the safe operation and maintenance of the plant. As in the past, the NRC will continue to be informed of organizational changes through other required controls.
10CFR50.34(b)(6)(i) requires that the applicants' organizational structure be included in the UFSAR, Chapter 13 of the UFSAR provides a description of the organization anJ detailed organization charts.
As required by 10CFR50.71(e), SERI submits annual updates to the UFSAR.
j 2. The proposed amendment does not create the possibility of a new or different kind of accident than previously evaluated because the proposed change is administrative in nature, and no physical alterations of plant configuration or changes to setpoints or operating parameters are proposed.
- 3. The proposed amendment does not involve a significant reduction in a I margin of safety. Since the proposed amendment retains those aspects of the organizational charts which are important to safety, removal of the organization charts represents no reduction in the current margin of safety.
Based on the above reasoning, SERI has detennined that the proposed amendment does not involve a significant hazards consideration.
j l.
J16AECH88041401 - 8 l
-. -__ . . - _ _ . - . . - _ . . _ .