|
---|
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
.a. Oo . ,
. e EYETEM ENERGY REEDLINCES, INC.
OLM9 ) KJGREY Jo vce nesow
- July 15, 1988 U. S. Nuclear Regulatory Comission Mail Station P1-137 Washington, D. C. 20555 Attention: Document Control Desk Gentlemen:
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Proposed Plant Staff Engineering Organization and PSRC Membership Change Proposed Amendment to the Operating License (PC0L-88/11)
AECM-88/0128 System Energy Resources, Inc. (SERI) is submitting by this letter a proposed amendment to the Grand Gulf Nuclear Station (GGNS) Operating License.
The proposed amendment is the result of a planned change in the plant staff organization to consolidate certain engineering personnel and functions in the Nuclear Operations site organization.
The engineering staffs in the Technical Support Group, the Plant I Modification & Construction Group Retest section and the Maintenance Group will be consolidated into a new Performance and System Engineering Department.
This new organization will provide a source of engineering expertise on plant systems, components and programs thereby eliminating duplication of engineering tasks in the site Nuclear Operations organization.
SERI by letter dated June 3, 1988 (AECM-88/0106) has requested removal of the onsite and offsite organization charts from the GGNS Unit 1 Technical Specifications pursuant to NRC Generic Letter 88-06. Those proposed changes i are pending NRC Staff approval; therefore, no changes to those Technical Specification organization charts are proposed. The planned organization change does modify the composition of the Plant Safety Review Comittee (PSRC) membership listed in Technical Specification 6.5.1.2. That change is proposed and discussed in Attachment 3 to this letter.
[
I 'l hh !
,fI P O 60X 2r73 l #OSCH MSSSm 3m&ID l M mm)
^"*"*5 " * '
J16AECM88062102 - 1 j
l .
AECM-88/0128 Page 2 The planned organization change is consistent with the findings and recommendations of the 1987 Institute of Nuclear Power Operations evaluation of GGNS. The planned change is unrelated and independent of the proposed Middle South Utilities, Inc. and SERI Nuclear consolidation described by SERI letter to the NRC dated July 1, 1988 (AECM-88/0130).
The proposed change involves only the Nuclear Operations organization and does not affect the existing dedicated SERI organization supporting GGNS, including the Nuclear Plant Engineering organization.
The planned organization changes ware discussed with members of NRC Region II and NRR staffs on July 13, M, and 15,1988. As discussed with NRC Staff, '.,ERI plans to request enforceinent discretion tc allow implementation of the proposed organization on July 18, 1988. The planned organization changes represent a clear improvement in the use of site 2ngineering resources and SERI feels it is advantageous to implement these improvements as soon as possible.
Enforcement discretion will enable SERI to realize the immediate benefits of the organizational changes until the proposed amendments are approved. That request will be submitted under separate cover.
In accordance with the provisions of 10 CFR 50.4, the original of the.
requested amendment is enclosed and the appropriate copies will be distributed.
Attachment 3 provides the technical justification and discussion to support the requested amendment. This amendment has been reviewed and accepted by the Plant Safety Review Committee and the Safety Review Committee.
Based on the guidelines presented in 10 CFR 50.92, SERI has concluded that this proposed amendment involves no significant hazards considerations.
In accordance with the requirements of 10 CFR 170.21, an application fee of $150 is attached to this letter.
Your uly,
/
ODK:bms Attachments: 1. Remittance of $150 Application Fee
- 2. Affirmation per 10 CFR 50.30
- 3. GGNS PCOL-88/11 cc: (See Next Page)
J16AECM88062102 - 2
' AECM-88/0128' Page 3
.cc: Mr. T. H. Cloninge 1(w/a)
Mr. R. B. McGehee (w/a)
Mr. N. S. Reynolds (w/a)
Mr. H. L. Thomas (w/o)
Mr. R. C. Butcher (w/a)
Dr. J. Nelson Grace', Regional Administrator (w/a)
U. S.LNuclear 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 14820 Washington, D.C. 20555 Dr. Alton B. Cobb (w/a)
State Health Officer State Board of Health Box 1700 Jackson, P4ssissippi 39205 J16AECM88062102 - 3
1 l
BEFORE THE q UNITED STATES NUCLEAR REGULATORY COMMISSION !
LICENSE NO. NPF-29 DOCKET N0. 50-416 IN THE MATTER OF MISSISSIPPI POWER & LIGHT COMPANY and SYSTEM ENERGY RESOURCES, INC.
and SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION AFFIRMATION 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
')perating 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 fort therein are true and correct to the best of my knowledge, information and ef.
.\ .
STATE OF MISSISSIPPI COUNTY OF HINDS SUBSCRIBED AND SWORN T0 beforA me, a ta y Pyblic, in and for the County and State above named, this @-ay of . ;<.IM . , 1988.
(SEAL) dd/Ahn a Notary Public My comission expires: l uj com*@n E@n St4 26 M l l
l J16AECM88062102 - 5 1 i
- - Attachment 3 to AECM-88/0128 A. SUBJECT
- 1. NL 88/08 Proposed Plant Staff Engineering Organization and PSRC Membership Change
- 2. Revised Technical Spec' fications:
- a. Plant Safety Review Coninittee Composition, 6.5.1.2 - Page 6-7.
B. DISCUSSION
- 1. Presently, the engineering expertise of the plant staff organization resides in four distinct sections: Technical Engineering, Reactor Engineering, Plant Modification and Construction (PM&C), and Maintenance Engineering (I&C, Mechanical and Electrical, Planning &
Scheduling) as shown in Figure 1. With this. separation of the plant engineering expertise a clear division of responsibility does not exist. This contributes to some degree of confusion and misunderstanding, which in turn detracts from SERI's full capability to effectively and_ efficiently resolve plant problems.
- 2. is being consolidated into the Performance Plant staff engineering and System Engineering (P&SE) Department under a new position, the Manager P&SE. P&SE will be formed by consolidating various engineering staffs - those in Technical Engineering, Reactor Engineering, PM&C, and Maintenance Engineering. P&SE will serve as a single source of engineering expertise on plant systems. This strengthened organization will enhance the operation of Grand Gulf Nuclear Station (GGNS) by providing a focused management approach to plant engineering functions.
By consolidating the plant engineering expertise, duplication of engineering tasks within the various organizations will be essentially eliminated. Consolidating resources will mean a more effective use of engineering capabilities on site.
- 3. The formation of the plant staff engineering organization is independent of the proposed overall SERI consolidation described in the SERI letter (AECM-88/0130) dated July 1, 1988 and is not being done to accommodate the integration of the other nuclear facilities.
Likewise, the realignment will not affect the SERI offsite support functions including the design engineering organization, Nuclear Plant Engineering (NPE). In fact, the realignment is designed to improve the interface between NPE and plant staff in the areas of maintenance, engineering, and operations.
- 4. The Manager, P&SE will be responsible for activities necessary to support the operations of GGNS, Unit 1. This includes System Engineering management, Inservice Inspection Program management, Reactor Engineering management and the engineering support of maintenance and operations. The Manager, P&SE will report to the GGNS General Manager and will be assisted by the System Engineering Superintendent, the Reactor Engineering Superintendent and the Engineering Support Superintendent.
J16AECM88062102 - 6
Attachment 3 to AECM-88/0128
- 5. The System Engineering Superintendent will be responsible for plant staff system engineering functions. The system engineering function will-provide system engineers who have.overall system and component expertise on their assigned systems. He will be responsitle for technical activities associated with design changes, the collection, collating and evaluation of data, reliability analysis and root cause analysis. The System Engineering Superintendent will have three System Engineering Supervisors under his direction and will report to the Manager, P&SE.
- 6. The Engineering Support Superintendent will provide administrative support to the Manager, P&SE. He will also be responsible for those portions of programs such as Inservice Inspection, Thermal Performance Monitoring and Equipment Qualification. assigned to the plant staff. The Engineering Support Superintendent will have two supervisors, the Inservice Inspection Supervisor and Engineering Support Supervisor, under his direction and will report to the Manager, P&SE.
- 7. The Reactor Engineering Superintendent will be responsible for onsite core management and periodic reactor testing, in-plant nuclear materials control and accountability, and providing assistance to reactor operators during control rod pattern adjustments. The Reactor Engineering Superintendent will report to the Manager, P&SE.
- 8. As a part of the organizational realignment, the Technical Support Superintendent position is being deleted. The Technical Support Superintendent is currently a member of the Plant Safety Review Committee (PSRC) as indicated in Technical Specification (TS) 6.5.1.2.
Therefore, with this position being deleted the following i administrative change is proposed to TS 6.5.1.2: replace the Technical Support Superintendent with the Manager, P&SE.
i
- 9. TS Figure 6.2.1-1 and 6.2.2-1 provide the organizational charts associated with GGNS and would require changes with this reorganization; however, a proposed TS change was submitted by SERI letter (AECM-88/0106) dated June 3,1988 that will remove these figures .from l the TS. This proposed organizational realignment has been evaluated i against the criteria of 10CFR50.59 and determined not to constitute !
an unreviewed safety question. Also, the appropriate Updated Final l Safety Analysis Report (UFSAR) change request has been initiated to I have the UFSAR reflect the organizational changes.
C. JUSTIFICATION
- 1. With the new organization all the duties, responsibilities and functions being performed will now be performed in a more productive and effective manner. The new organization will allow SERI to develop a better predictive and preventive maintenance program. The P&SE staff will be composed of the engineers presently in the various plant staff engineering sections; thus all required minimum qualifications of Technical Specification 6.3.1 will continue ^.o be met. There will be a clear division of responsibility whic' 11 eliminate confusion and misunderstanding.
J16AECM88062102 - 7
Attachment'3 to AECM-88/0128
- 2. As a result of the elimination of the Technical' Support Superintendent position the Manager,-P&SE will be added as a member of the PSRC.
Neither the number of PSRC members nor the level of expertise will
. change. In addition, the majority of work activities previously supervised by the Technical Support Superintendent will .now be the responsibility of the Manager, P&SE. Therefore, the.same perspective brought to the PSRC by the Technical Support Superintendent will still exist when the Manager, P&SE is added to the PSRC.
D. N0 SIGNIFICANT HAZARDS CONSIDERATIONS As discussed in 10CFR50.92, the following discussions are provided to the NRC Staff in support of "no significant hazards considerations."
- 1. No significant increase in the probability or consequences of an accident previously evaluated results from this change.
- a. This realignment of the plant staff engineering groups will have no negative effect on plant design or operation because P&SE will actively look for ways to improve the performance of specific systems and components, as well as overall plant performance. With responsibility and accountability being assigned for designated plant systems, components, and programs the knowledge of specific systems will be enhanced. The same i level of expertise applied to the PSRC review function will exist with the approval of the proposed change. Since essentially the same representation will exist there will be no loss in PSRC effectiveness,
- b. Therefore, there is no increase in the probability or consequences of previously analyzed accidents due to the proposed change.
- 2. This change would not create the possibility of a new or different I kind of accident from any previously evaluated.
- a. Since there is no loss in PSRC effectiveness, the proposed change is administrative in nature. No physical alterations of plant configuration or changes to setpoints or operating parameters are proposed. The same level and quality of PSRC review is maintained and unaltered by this proposed change. l
- b. Therefore, the possibility of a new or different kind of accident from any previously evaluated is not created.
- 3. This change would not involve a significant reduction in the margin of safety. H
- a. There will be no physical changes to the plant equipment, setpoints or operating modes as a result of the proposed change. This administrative change maintains the level and .
quality of PSRC review by maintaining essentially the same level of expertise applied to the PSRC review function.
- b. Therefore, this proposed change will not involve a significant reduction in'the margin of safety.
i i
J16AECM88062102 - 8
i l .
l .
SITE DIRECTOR i
I l MANAGER GGNS PM&C GENERAL MANAGER I -
________i ITEST & SYSTEM, i ENGR MANAGER MANAGER MANAGER i
L__S_UPT __i PLANT PLANT PLANT MAINTENANCE OPERATIONS SUPPORT I I I ELECTRICAL MECHANICAL PLANNING &l l&C PLANT l SUPT SUPT hhf" SUPT LICENS NG
~- ~~
l ~~UTRiddi ELE I I~~~~~~l I~ I TECH I MECHMIChi I l&C ENGRI I I
ENGR I ENGR ENGINEERS I I SUPV I I SUPPORTi l I I I L_SUEV__I __SUPV__ l I L_S_UET__I I COMPUTER 1 l
l TECH I R%
i SUPPORT i I ENGR i FM L_SUPV__l [_SUPV__1 $[
ea gu
.______I REACTORI ,
I ENGR '
-- INDICATES DELETED FIGURE 1 b SRV_ _i L_i OR CHANGED POSITION
SITE DIRECTOR GGNS MANAGER GENERAL PM&C MANAGER I
1 I ,_ _ _ _ _ _I_ _ _ _ _ _ l I
MANAGER MANAGER I MANAGER MANAGER I
PLANT PLANT I PERFORMANCE PLANT t _ _E_kG_ E_ _ _G_ _ _l MAINTENANCE OPERATIONS I SUPPORT l ,___l___, ,___L___, ,___1___, ,___t___,
i SYSTEM i i REACTOR I i ENGINEERING 1 I COMPUTER I ELECTRICAL I ENGINEERING I I ENGINEERING I I SUPPORT I. I SERVICES I SUPT I
SUPT ' ' I 3 I ' I
'-- r-- J ' - - SUPT --- ' ' - SUPT - - - - ' '- SUPT
3
_ ,____.1____,
I SYSTEM i MECHANICAL i ENGINEERING 1 PLANT
- 1 ENGINEERING I i SUPT i i SUPPORT I LICENSING -
'___SUPV ____> i-
' - SUPV i
SUPT gg i SYSTEM i -eg I&C "-------' #
_- I ENGINEERING l- ' me SUPT I L------
SUPV i
l ISI $j-i SUPV i. Pmm.
PLANNING & - I SYSTEM i g.
SCHEDULING _ i ENGINEERING t_-
SUPT I SUPV I u_______3 FIGURE 2 i_ _ i mens mucum m m:w posmos
- _- _-