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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20217F1951999-10-0707 October 1999 Application for Amend to License NPF-29,to Revise Licensing Basis to Credit One of Insights/Conclusions of NUREG-1465, Revised Source Term Insights ML20211E7061999-08-20020 August 1999 Application for Amend to License NPF-29,incorporating Many of Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0791999-06-29029 June 1999 Suppl to 980720 Application for Amend to License NPF-29, Implementing BWROG Enhanced Option I-A,reactor Stability long-term Solution.Rev to TS 3.4.1 Inadvertently Omitted from Original Application ML20196G6901999-06-23023 June 1999 Application for Amend to License NPF-29,revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5241999-05-0606 May 1999 Application for Amend to License NPF-29,changing TSs Required to Support Ggns,Cycle 11 Operation,Including Slmcpr.Portions of Encl Re Addl Info on Calculated Cycle Specific SL MCPR for Plant Cycle 11 Withheld ML20206R9271999-01-12012 January 1999 Application for Amends to Licenses NPF-29 & NPF-47,proposing Required Actions Consistent with NRC Accepted Change to BWR Improved TS NUREG-1433 & NUREG-1434 ML20236T1551998-07-20020 July 1998 Application for Amend to License NPF-29,revising TSs Re BWROG Enhanced Option I-A Reactor Stability Long Term Solution ML20198J3451998-01-0909 January 1998 Revised Application for Amend to License NPF-29,providing Clarifications to Amend & Adding Restriction to Allowed Interval Extensions Re Option B of 10CFR50,app J ML20198N3851997-10-28028 October 1997 Application for Amend to License NPF-29,revising TS to Implement Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20210V5461997-09-18018 September 1997 Application for Amend to License NPF-29,reflecting Decrease of Two Recirculation Loop SLMCPR to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12.Proprietary Info Re SLMCPR for Cycle 10,encl.Proprietary Info Withheld ML20134E1191996-10-22022 October 1996 Application for Amend to License NPF-29,revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Pressure, Curves Using Methodology of Reg Guide 1.99,Rev 2, Radiation Embrittlement.. ML20117P4421996-09-19019 September 1996 Application for Amend to License NPF-29,changing Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117G6661996-08-27027 August 1996 Application for Amend to License NPF-29,modifying Tech Specs Surveillance Requirements for Safety/Relief Valves ML20116F0141996-07-31031 July 1996 Rev 1 to Application for Amend to License NPF-29,revising TSs Required to Support Cycle 9,reload 8.Rev 1 to J11-02863SLMCPR, GGNS Cycle 9 Safety Limit MCPR Analysis Encl.Rept Withheld ML20113B7341996-06-20020 June 1996 Application for Amend to License NPF-29,redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20112E1741996-05-31031 May 1996 Application for Amends to Licenses NPF-29 & NPF-47 Adding Addl Acceptable Required Actions to Tech Spec Limiting Condition for Operation (LCO) 3.9.1, Refueling Equipment Interlocks ML20117F4541996-05-0909 May 1996 Application for Amend to License NPF-29,modifying SRV Surveillance Test for Relief Mode of Operation ML20117D6901996-05-0909 May 1996 Application for Amend to License NPF-29,revising TSs to Support Unit 1,cycle 9 Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits ML20111B2631996-05-0808 May 1996 Application for Amend to License NPF-29,placing Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3551996-05-0606 May 1996 Application for Amend to License NPF-29,changing Name from Mississippi Power & Light to Entergy Mississippi,Inc ML20107E2521996-04-18018 April 1996 Application for Amend to License NPF-29,prohibiting Performance of 24-h EDG Maint Run While Unit in Either Mode 1/2 RBG-42766, Application for Amends to Licenses NPF-29 & NPF-47,adding Addl Acceptable Method of Fuel Movement,Control Rods Removed or Withdrawn from Defueled Core Cells1996-04-18018 April 1996 Application for Amends to Licenses NPF-29 & NPF-47,adding Addl Acceptable Method of Fuel Movement,Control Rods Removed or Withdrawn from Defueled Core Cells ML20100J8311996-02-22022 February 1996 Application for Amend to License NPF-29,modifying Safety Setpoint to Tolerance Requirements for Safety/Relief Valves ML20097C3491996-02-0101 February 1996 Application for Amend to License NPF-29,revising TS Bases to Include Changes Since 950221 Approval of TS Bases RBG-42193, Rev to Application for Amend to License NPF-29 & Proposed Amend to License NPF-47,revising TS 3/4.6.2.2, Drywell Bypass Leakage1995-11-20020 November 1995 Rev to Application for Amend to License NPF-29 & Proposed Amend to License NPF-47,revising TS 3/4.6.2.2, Drywell Bypass Leakage ML20087B5031995-08-0101 August 1995 Application for Amend to License NPF-29,by Revising TS Assoc W/Various ESF Sys Following Design Fuel Handling Accident ML20086N2071995-07-21021 July 1995 Application for Amend to License NPF-29,proposing to Recapture Approx 2 1/2 Yrs of Low/No Power Operation by Extending 40-yr Operating License Term from 220616 to 241101 ML20078S4891995-02-14014 February 1995 Application for Amend to License NPF-29 Consisting of Changes to TS Requirements 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6481995-02-10010 February 1995 Application for Amend to License NPF-29,consisting of Mod to Proposed Amend to OL (PCOL-93/13),requesting to Perform Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4431994-11-0909 November 1994 Application for Amend to License NPF-29,revising TS Associated W/Various ESF Sys Following Design Basis Fuel Handling accident.Mark-up of Current Ts,Proposed TS & mark- Up Improved TS Encl ML20076F9781994-10-12012 October 1994 Application for Amend to License NPF-29,consisting of PCOL-94/01,closing & Deleting License Condition 2.C.(26) for Turbine Disc integrity.Mark-up of Affected OL Page & Proprietary Supporting Info Encl.Proprietary Info Withheld ML20069P4401994-06-17017 June 1994 Proposed Amend to OL (PCOL-94/02),removing License Conditions for EDGs Associated w/NUREG-1216 ML20059H6011994-01-13013 January 1994 Application for Amend to License NPF-29,consisting of Proposed Amend to OL PCOL-93/15,removing 2,324 Spent Fuel Pool Storage Limit & Allowing Full Use of Spent Fuel Storage Spaces ML20059A4801993-10-22022 October 1993 Application for Amend to License NPF-29,modifying Testing Frequencies for Drywell Bypass Test & Airlock Tests ML20059B0131993-10-15015 October 1993 Application for Amend to License NPF-29,converting Current GGNS TS to TS Based Largely on NUREG-1434,Rev 0 ML20056E2861993-08-17017 August 1993 Application for Amend to License NPF-29,proposing Changes to Amend TS Section 3/4.3.7.10, Loose Part Detection Sys by Relocating Loose Part Detection Instrumentation to Administrative Controls ML20056D5321993-08-11011 August 1993 Proposed Change to OL (PCOL-93/09) to License NPF-29, Amending TS Section 3/4.3.7.5 by Relocating Certain Accident Monitoring Instrumentation from TS to Administrative Control,Per NUREG-1434,Rev 0,w/respect to RG 1.97 ML20046D2041993-08-11011 August 1993 Proposed Change to OL (PCOL-93/07) to License NPF-29, Amending TS Section 3/4.3.7.10, Loose Part Detection Sys by Relocating Locating Loose Part Detection Instrumentation from TS to Administrative Controls,Per NUREG-1434,Rev 0 ML20046D1911993-08-11011 August 1993 Proposed Change to OL (PCOL-93/06) to License NPF-29, Revising TS to Support Compliance W/New Requirements of 10CFR20 & 10CFR50.36a ML20056C7131993-07-15015 July 1993 Application for Amend to License NPF-29,proposing Changes to Remove Operability Requirements for auto-test Feature of Load Shedding & Sequencing Sys & Increase AOT for Inoperable Load Shedding & Sequencing Sys from Eight to Twelve Hours ML20045H7111993-07-14014 July 1993 Application for Amend to License NPF-29,changing TS to Eliminate Previous Retrictions on Ensuring Operability of Igniters in Encl Areas & Igniters in Open Areas Adjacent to Inoperable Igniters & Redefining Hydrogen Ignition Sys ML20044F1571993-05-20020 May 1993 Proposed Amend PCOL-93/04 to License NPF-29,revising TS 4.8.3.1.2 & 4.8.3.2.2 to Remove Operability Requirements for auto-test Feature of Load Shedding & Sequencing (LSS) Sys & Increase AOT for Inoperable LSS Sys from Eight to 24 H ML20044F1621993-05-20020 May 1993 Proposed Amend PCOL-92/09 to License NPF-29,removing Unnecessary Operability Requirements for IRMs & APRMs During Plant Shutdown Conditions.Ts Changes Follow NUREG-1434, Rev 0 Requirements ML20116D1391992-10-29029 October 1992 Application for Amend to License NPF-29,consisting of Proposed Change,Revising TS Per Generic Ltr 88-16, Removal of Cycle Specific Parameter Limits from TS, That Will Change Each Fuel Cycle ML20118A5681992-09-14014 September 1992 Application for Amend to License NPF-29,deleting TS Tables 3.6.4-1 Re Containment & Drywell Isolation Valves, 3.6.6.2-1 Re Secondary Containment Ventilation Sys & 3.8.4.2-1 Re MOV Thermal Overload Protection,Per GL 91-08 ML20113H6001992-07-29029 July 1992 Application for Amend to License NPF-29,consisting of PCOL-92/03,changing Selected TS Instrumentation Surveillance Test Intervals & Allowed Outage Times,Based on Cited GE Repts ML20101B6681992-05-29029 May 1992 Application for Amend to License NPF-29,changing TS Bases 3/4.9.7, Crane Travel - Spent Fuel & Upper Containment Fuel Storage Pools ML20096B8861992-05-0606 May 1992 Application for Amend to License NPF-29,changing TS Re Primary Containment Penetration Conductor Overcurrent Protective Devices,Under Exigent Circumstances,Per Generic Ltr 89-10 ML20095K0351992-04-30030 April 1992 Application for Amend to License NPF-29,changing TS 3/4.3.1 Re Reactor Protection Sys instrumentation,3/4.3.6 Re Control Rod Block Instrumentation & 3/4.3.7.6 Re Source Range Monitors,Per Violations in Insp Rept 50-416/92-04 ML20095E7341992-04-22022 April 1992 Suppl to 910626 Application for Amend to License NPF-29, Modifying Wording of Requested Change to LCO 3.3.2,Action B Re Extension of Instrumentation Surveillance Intervals & Allowed Outage Times 1999-08-20
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217F1951999-10-0707 October 1999 Application for Amend to License NPF-29,to Revise Licensing Basis to Credit One of Insights/Conclusions of NUREG-1465, Revised Source Term Insights ML20211E7061999-08-20020 August 1999 Application for Amend to License NPF-29,incorporating Many of Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0791999-06-29029 June 1999 Suppl to 980720 Application for Amend to License NPF-29, Implementing BWROG Enhanced Option I-A,reactor Stability long-term Solution.Rev to TS 3.4.1 Inadvertently Omitted from Original Application ML20196G6901999-06-23023 June 1999 Application for Amend to License NPF-29,revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5241999-05-0606 May 1999 Application for Amend to License NPF-29,changing TSs Required to Support Ggns,Cycle 11 Operation,Including Slmcpr.Portions of Encl Re Addl Info on Calculated Cycle Specific SL MCPR for Plant Cycle 11 Withheld ML20206R9271999-01-12012 January 1999 Application for Amends to Licenses NPF-29 & NPF-47,proposing Required Actions Consistent with NRC Accepted Change to BWR Improved TS NUREG-1433 & NUREG-1434 ML20236T1551998-07-20020 July 1998 Application for Amend to License NPF-29,revising TSs Re BWROG Enhanced Option I-A Reactor Stability Long Term Solution ML20217P0241998-04-0606 April 1998 Amend 135 to License NPF-29,revising TSs for GGNS to Permit Implementation of Containment Leak Rate Testing Provisions of 10CFR50,App J,Option B ML20198J3451998-01-0909 January 1998 Revised Application for Amend to License NPF-29,providing Clarifications to Amend & Adding Restriction to Allowed Interval Extensions Re Option B of 10CFR50,app J ML20198N3851997-10-28028 October 1997 Application for Amend to License NPF-29,revising TS to Implement Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20210V5461997-09-18018 September 1997 Application for Amend to License NPF-29,reflecting Decrease of Two Recirculation Loop SLMCPR to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12.Proprietary Info Re SLMCPR for Cycle 10,encl.Proprietary Info Withheld ML20134E1191996-10-22022 October 1996 Application for Amend to License NPF-29,revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Pressure, Curves Using Methodology of Reg Guide 1.99,Rev 2, Radiation Embrittlement.. ML20117P4421996-09-19019 September 1996 Application for Amend to License NPF-29,changing Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117G6661996-08-27027 August 1996 Application for Amend to License NPF-29,modifying Tech Specs Surveillance Requirements for Safety/Relief Valves ML20116F0141996-07-31031 July 1996 Rev 1 to Application for Amend to License NPF-29,revising TSs Required to Support Cycle 9,reload 8.Rev 1 to J11-02863SLMCPR, GGNS Cycle 9 Safety Limit MCPR Analysis Encl.Rept Withheld ML20113B7341996-06-20020 June 1996 Application for Amend to License NPF-29,redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20112E1741996-05-31031 May 1996 Application for Amends to Licenses NPF-29 & NPF-47 Adding Addl Acceptable Required Actions to Tech Spec Limiting Condition for Operation (LCO) 3.9.1, Refueling Equipment Interlocks ML20117D6901996-05-0909 May 1996 Application for Amend to License NPF-29,revising TSs to Support Unit 1,cycle 9 Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits ML20117F4541996-05-0909 May 1996 Application for Amend to License NPF-29,modifying SRV Surveillance Test for Relief Mode of Operation ML20111B2631996-05-0808 May 1996 Application for Amend to License NPF-29,placing Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3551996-05-0606 May 1996 Application for Amend to License NPF-29,changing Name from Mississippi Power & Light to Entergy Mississippi,Inc ML20107E2521996-04-18018 April 1996 Application for Amend to License NPF-29,prohibiting Performance of 24-h EDG Maint Run While Unit in Either Mode 1/2 RBG-42766, Application for Amends to Licenses NPF-29 & NPF-47,adding Addl Acceptable Method of Fuel Movement,Control Rods Removed or Withdrawn from Defueled Core Cells1996-04-18018 April 1996 Application for Amends to Licenses NPF-29 & NPF-47,adding Addl Acceptable Method of Fuel Movement,Control Rods Removed or Withdrawn from Defueled Core Cells ML20100J8311996-02-22022 February 1996 Application for Amend to License NPF-29,modifying Safety Setpoint to Tolerance Requirements for Safety/Relief Valves ML20097C3491996-02-0101 February 1996 Application for Amend to License NPF-29,revising TS Bases to Include Changes Since 950221 Approval of TS Bases RBG-42193, Rev to Application for Amend to License NPF-29 & Proposed Amend to License NPF-47,revising TS 3/4.6.2.2, Drywell Bypass Leakage1995-11-20020 November 1995 Rev to Application for Amend to License NPF-29 & Proposed Amend to License NPF-47,revising TS 3/4.6.2.2, Drywell Bypass Leakage ML20087B5031995-08-0101 August 1995 Application for Amend to License NPF-29,by Revising TS Assoc W/Various ESF Sys Following Design Fuel Handling Accident ML20086N2071995-07-21021 July 1995 Application for Amend to License NPF-29,proposing to Recapture Approx 2 1/2 Yrs of Low/No Power Operation by Extending 40-yr Operating License Term from 220616 to 241101 ML20078S4891995-02-14014 February 1995 Application for Amend to License NPF-29 Consisting of Changes to TS Requirements 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6481995-02-10010 February 1995 Application for Amend to License NPF-29,consisting of Mod to Proposed Amend to OL (PCOL-93/13),requesting to Perform Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4431994-11-0909 November 1994 Application for Amend to License NPF-29,revising TS Associated W/Various ESF Sys Following Design Basis Fuel Handling accident.Mark-up of Current Ts,Proposed TS & mark- Up Improved TS Encl ML20076F9781994-10-12012 October 1994 Application for Amend to License NPF-29,consisting of PCOL-94/01,closing & Deleting License Condition 2.C.(26) for Turbine Disc integrity.Mark-up of Affected OL Page & Proprietary Supporting Info Encl.Proprietary Info Withheld ML20069P4401994-06-17017 June 1994 Proposed Amend to OL (PCOL-94/02),removing License Conditions for EDGs Associated w/NUREG-1216 ML20059H6011994-01-13013 January 1994 Application for Amend to License NPF-29,consisting of Proposed Amend to OL PCOL-93/15,removing 2,324 Spent Fuel Pool Storage Limit & Allowing Full Use of Spent Fuel Storage Spaces ML20059A4801993-10-22022 October 1993 Application for Amend to License NPF-29,modifying Testing Frequencies for Drywell Bypass Test & Airlock Tests ML20059B0131993-10-15015 October 1993 Application for Amend to License NPF-29,converting Current GGNS TS to TS Based Largely on NUREG-1434,Rev 0 ML20056E2861993-08-17017 August 1993 Application for Amend to License NPF-29,proposing Changes to Amend TS Section 3/4.3.7.10, Loose Part Detection Sys by Relocating Loose Part Detection Instrumentation to Administrative Controls ML20046D2041993-08-11011 August 1993 Proposed Change to OL (PCOL-93/07) to License NPF-29, Amending TS Section 3/4.3.7.10, Loose Part Detection Sys by Relocating Locating Loose Part Detection Instrumentation from TS to Administrative Controls,Per NUREG-1434,Rev 0 ML20046D1911993-08-11011 August 1993 Proposed Change to OL (PCOL-93/06) to License NPF-29, Revising TS to Support Compliance W/New Requirements of 10CFR20 & 10CFR50.36a ML20056D5321993-08-11011 August 1993 Proposed Change to OL (PCOL-93/09) to License NPF-29, Amending TS Section 3/4.3.7.5 by Relocating Certain Accident Monitoring Instrumentation from TS to Administrative Control,Per NUREG-1434,Rev 0,w/respect to RG 1.97 ML20056C7131993-07-15015 July 1993 Application for Amend to License NPF-29,proposing Changes to Remove Operability Requirements for auto-test Feature of Load Shedding & Sequencing Sys & Increase AOT for Inoperable Load Shedding & Sequencing Sys from Eight to Twelve Hours ML20045H7111993-07-14014 July 1993 Application for Amend to License NPF-29,changing TS to Eliminate Previous Retrictions on Ensuring Operability of Igniters in Encl Areas & Igniters in Open Areas Adjacent to Inoperable Igniters & Redefining Hydrogen Ignition Sys ML20044F1571993-05-20020 May 1993 Proposed Amend PCOL-93/04 to License NPF-29,revising TS 4.8.3.1.2 & 4.8.3.2.2 to Remove Operability Requirements for auto-test Feature of Load Shedding & Sequencing (LSS) Sys & Increase AOT for Inoperable LSS Sys from Eight to 24 H ML20044F1621993-05-20020 May 1993 Proposed Amend PCOL-92/09 to License NPF-29,removing Unnecessary Operability Requirements for IRMs & APRMs During Plant Shutdown Conditions.Ts Changes Follow NUREG-1434, Rev 0 Requirements ML20116D1391992-10-29029 October 1992 Application for Amend to License NPF-29,consisting of Proposed Change,Revising TS Per Generic Ltr 88-16, Removal of Cycle Specific Parameter Limits from TS, That Will Change Each Fuel Cycle ML20118A5681992-09-14014 September 1992 Application for Amend to License NPF-29,deleting TS Tables 3.6.4-1 Re Containment & Drywell Isolation Valves, 3.6.6.2-1 Re Secondary Containment Ventilation Sys & 3.8.4.2-1 Re MOV Thermal Overload Protection,Per GL 91-08 ML20113H6001992-07-29029 July 1992 Application for Amend to License NPF-29,consisting of PCOL-92/03,changing Selected TS Instrumentation Surveillance Test Intervals & Allowed Outage Times,Based on Cited GE Repts ML20101B6681992-05-29029 May 1992 Application for Amend to License NPF-29,changing TS Bases 3/4.9.7, Crane Travel - Spent Fuel & Upper Containment Fuel Storage Pools ML20096B8861992-05-0606 May 1992 Application for Amend to License NPF-29,changing TS Re Primary Containment Penetration Conductor Overcurrent Protective Devices,Under Exigent Circumstances,Per Generic Ltr 89-10 ML20095K0351992-04-30030 April 1992 Application for Amend to License NPF-29,changing TS 3/4.3.1 Re Reactor Protection Sys instrumentation,3/4.3.6 Re Control Rod Block Instrumentation & 3/4.3.7.6 Re Source Range Monitors,Per Violations in Insp Rept 50-416/92-04 1999-08-20
[Table view] |
Text
- f. o . e,.
MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi P. O. B O X 164 0, J AC K S O N, MIS SIS SIP PI 3 9 2 0 5 April 25, 1983 JAMES P. McGAUGHY, JR vecs possiosa, 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-83/06)
AECM-83/0254 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.
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 discussion to support the requested amendment. This amendment has been reviewed and accepted by the Plant Safety Review Committee (PSRC) and the Safety Review Committee (SRC).
In accordance with the requirements of 10 CFR 170.22, we have determined that the proposed amendment includes three safety issues, Items 4, 5, and 8.
The remaining portion is considered to be administrative in nature. Based on the guidance provided by the Project Manager (NRC), we have determined that the total fee is $5,200. A remittance of $5,200 is attached to this letter.
Yours truly,
,1 1
? /
JPM: sap .,
Attachments: CGNS PCOL-83/06 p [1 cc: (See Next Page) /
00 I s
I h 8304280037 830425 PDR ADOCK 05000416 P PDR Member Middle South Utilities System
- ' - =* - - AECM-83/0254
- E' MISSISSIPPI POWER Q L12HT COMPANY cc: Mr. J. B. Richard (w/o)
Mr. G. B. Taylor (w/o)
Mr. R. B. McGehee (w/o) -
Mr. T. B. Conner (w/o)
Mr. J. P. O'Reilly (w/a)
Regional Administrator Office of Inspection & Enforcement, Region II 101 Marietta Street, N.W., Suite 3100 Atlanta, Georgia 30303 Mr. R. C. DeYoung, Director (w/a)
Office of Inspection &. Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 4
-..+-, ,- _,-,..-%,,-- . ,-.m ,
... .., +
JBEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION V
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. P. McGaughy, Jr. , being duly sworn, stated that I am 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.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.
.'P. McGaugn3f/ 3r.
STATE OF MISSISSIPPI ~
COUNTY OF ti?NDS SUBSCRIBED AND SWORN TO before.me, a Notary Public, in and for the County and State- above named, this 256 day of /9//D L , 1983.
(SEAL)
}kh% \ i Totary Public My commission expires:
13 E4J!doAN 196 5 F12sp
PROPOSED CHANGE TO THE OPERATING LICENSE NPF-13 PCOL-83/06 Mississippi Power & Light (MP&L) requests that the operating license for Grand Gulf Nuclear Station (GGNS) (NPF-13) be amended as detailed below.
These proposed changes, as discussed below, are provided for Nuclear Regulatory Commission (NRC) review and approval per 10 CFR 50.90.
- 1.
SUBJECT:
Technical Specification 3.7.5, Sealed Source contamination, page 3/4 7-26.
DISCUSSION: Technical Specification 3.7.5 states: "Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcuries of removable contamination."
10CFR31.5(c) (2) (ii) states: " Devices containing only tritium or not more than 100 microcuries of other beta and/or gamma emitting material or 10 microcuries of alpha emitting material
.....need not be tested for any purpose."
Technical Specification 3.7.5 should be revised to read ".. 10 microcuries of alpha emitting material..."
JUSTIFICATION: Technical Specification 3.7.5 should be revised to conform to the Code of Federal Regulations, 10 CFR 31.5 (c)(2)(ii) .
- 2.
SUBJECT:
Technical Specification 4.7.5.3, Reports, page 3/4 7-27.
DISCUSSION: Technical Specification 4.7.5.3 states: "A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage test reveal the presence of greater than or equal to 0.005 microcuries of removable contamination."
10CFR31.5(c) (5) states: ".... upon the detection of 0.005 microcuries or more of removable radioactive contamination t shall ....., within 30 days, furnish to the .....
! Commission...., a report....."
Technical Specification 4.7.5.3 should be revised to read "...
( submitted to the Commission within 30..."
JUSTIFICATION: Technical Specification 4.7.5.3 should be revised to conform to the Code of Federal Regulations, 10CFR31.5(c).
I l
F4
~
3.'(GGNS - 682)
SUBJECT:
Technical Specification 4.7.6.1.1.e.1, page 3/4 7-29.
DISCUSSION: Surveillance Requirement 4'.7.6.1.1.e.1 requires verification at least once per 18 months that each automatic valve in the flow path of the fire suppression water system actuates'to its correct position. This item should be deleted.
JUSTIFICATION: FSAR Section 9.5 and Appendix 9A present the layout of the fire suppression water system. The only automatic valves within the fire suppression water: system are containment isolation valves which are normally open. The position of these isolation valves is verified at least once per thirty-one (31) days in accordance with Surveillance Requirement 4.7.6.1.1.c. Upon actuation of the fire suppression water system, the isolation
, valves are not actuated and remain in their normal open positions. Since this requirement is not applicable to the GGNS design, Surveillance Requirement 4.7.6.1.1.e.1 should be deleted.
- 4. (GGNS - 209)
SUBJECT:
Technical Specification 4.7.6.1.3.a, page 3/4 7-30.
DISCUSSION: Technical Specification Surveillance Requirement 4.7.6.1.3.a should.be revised such.that electrolyte level and specific gravity should be verified for only the pilot cells of the diesel driven fire pump starting batteries.
JUSTIFICATION: The proposed change provides greater consistency between the Grand Gulf Nuclear Station Technical Specifications and the Standard Technical Specifications for General Electric Boiling Water Reactors NUREG-0123. The Standard Technical l Specifications require only verification of the electrolyte level and the specific gravity of the pilot cells for the diesel driven fire pump starting batteries. Verification of the specific gravity for each cell is accomplished each 92 days I.
per Surveillance Requirement 4.7.6.1.3.b.
- 5. (GGNS - 152, 211, 211a, 223, 241)
SUBJECT:
Technical Specification 4.7.6.3.1, 4.7.6.3.2.b.1, 3.7.6.4, and 4.7.6.4; pages 3/4 7-33 and 3/4 7-34.
DISCUSSION: Technical Specification 4.7.6.3.1 requires position verification of valves in the flow path of each C09 system.
The design of the differential pressure valves in these systems precludes position verification.
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Technical Specifications 4.7.6.3.2.b.1 and 4.7.6.4.c.1 (new 4.7.6.4.b.1) require destructive testing of the electro-thermal links and should be revised to allow verification that an actuation signal is received by the electro-thermal links rather than requiring actual operation.
Technical Specifications 3.7.6.4.b and 3.7.6.4.c should be' revised to specify the actual area protected by the halon systems is the under floor area.
Technical Specification 4.7.6.4.a is not applicable to the Grand Gulf design and should be deleted.
JUSTIFICATION: All of the C09systems are supplied from a centralized CO 2 storage facility. System actuation causes repositioning of differential pressure valves at the storage tank and the affected area. These valves operate on differential pressure across a piston and are not designed for direct manual control.
Since the valves are not designed for direct manual control, they are not provided with position indicators. Furthermore, re-positioning of these valves would result in system alarms to alert operating personnel of a problem in the system. Since these valves are not subject to direct manual manipulation, position indicators are not provided, and repositioning would produce system alarms, position verification of these valves is unwarranted.
The electro-thermal links utilized for ventilation damper control are single operation devices. Once operated, they must be replaced. All of the electro-thermal links utilized in C07 and halon system areas have been approved by Underwriters Laboratory. This approval is obtained through extensive testing to assure reliability of operation; therefore, verifying that an actuation signal is received when a detector trip occurs is sufficient to verify operability of the electro-thermal links. In addition, a test of the damper associated with the electro-thermal link would require operation, hence destruction, of the electro-thermal links.
Since damper failures result from mechanical degradation such as corrosion, obstruction, or deformation of moving parts, j periodic visual inspection of dampers as required by l- Surveillance Requirement 4.7.7.1 is sufficient to ascertain if
[ any mechanical degradation has occurred. If mechanical
- degradation has not occurred, then the damper should be l
operable.
The halon systems specified in specifications 3.7.6.4.b and t 3.7.6.4.c protect the under floor area of the PGCC. These areas are described in the FSAR, Appendix 9A, Table 9A-2, area designations OC502, OC503, and OC703 The proposed change does not affect the technical requirements.
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Technical Specification 4.7.6.4 is not applicable since the Grand Gulf halon systems do not contain verifiable valves in the flow path. All valves are totally enclosed, nitrogen pressure or explosive pin actuated, and can not be manually manipulated or externally verified.
- 6. (GGNS - 681)
SUBJECT:
Technical Specification Table 3.7.6.5-1, page 3/4 7-36 and 3/4 7-37.
DISCU3SION: The locations for fire hose stations listed in Technical Specification Table 3.7.6.5-1 should be revised to reflect the as-built location of the fire hose stations.
JUSTIFICATION: Plant as-built drawings and inspection.of hose station locations confirm that the proposed changes to Technical Specification Table 3.7.6.5-1 will correctly reflect the location of these hose stations. The arrangement drawings in Appendix 9A of the Grand Gulf Nuclear Station. Final Safety Analysis Report will be revised to agree with the as-built-drawings and the locations shown in revised Technical Specification Table 3.7.6.5-1.
- 7. (GGNS - 153, 232, 239)
SUBJECT:
Technical Specification Table 3.7.6.6-1, page 3/4 7-39.
DISCUSSION: Technical Specification Table 3.7.6.6-1 lists the yard fire hydrants and associated hydrant hose houses which are required to be operable by Technical Specification 3.7.6.6. The only yard fire hydrants which should be required to be operable are the yard hydrants which are capable'of supplying hose streams to the diesel generator buf1 ding. Therefore, the other yard fire hydrants and associated hydrants hose houses should be deleted from Table 3.7.6.6-1. In addition, the elevation for these fire hydrants should be revised to the correct value.
The heading title " Hydrant Number / Fire Water Loop Schedule l, Number" should be changed to " Hydrant Number / Hydrant Hose
- House Number". The hydrant hose house numbers should be added l to the column beside the hydrant numbers.
JUS 71FICATION: Technical Specification Bases Section 3/4 7.6 states that fire l
protection systems must be operable to ensure that adequate fire suppression capability exists to confine and extinguish fires which occur in any portion of the facility where safety related equipment is located. The only areas of the plant containing essential equipment which refer to the yard fire hydrants and associated hydrant-hose houses as an alternative l
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source of fire suppression agents are the areas in the diesel generator buf1 ding which .are discussed in Subsection 7.2.4 of Appendix 9A of the GGNS FSAR. The only yard hydrants and associated hydrant hose houses which should be required to.be operable in Technical Specification Table 3.7.6.6-1 are the hydrants and hydrant hose houses which might supply hose streams to the diesel generator building.
The numbering system used in the GGNS fire protection system provides a " Hydrant Hose House Number" as a more useful identifier than a " Fire Water Loop Schedule Number"; therefore, the heading should be changed from " Hydrant Number / Fire-Water Loop Schedule Number" to " Hydrant Number / Hydrant Hose House Number". The numbers in'this column should also be revised accordingly. Finally, the elevation for the fire hydrants corresponds to the grade elevation of 133'0". The elevation of 126'0" presently contained in Table 3.7.6.6-1 refers to the elevation of the water supply piping which is below grade elevation.
- 8.
SUBJECT:
Technical Specification Table 3.3.7.9-1, pages 3/4 3-77 and 3/4 3-79.
t DISCUSSION: Technical Specification 3.3.7.9 requires that fire detection instrumentation for each fire detection zone listed in Table 3.3.7.9-1 be operable. Table 3.3.7.9-1 includes ionization smoke detectors in the auxiliary building main steam tunnel.
The smoke detectors should be removed from service and deleted from the table.
JUSTIFICATION:-Fire detection in the main steam tunnel (Area 1A305) is provided by two ionization smoke detectors, per Technical Specification 3.3.7.9. The maximum ambient temperature in this area is 125'F; however, the maximum operating temperature of
- the installed. smoke detectors is approximately 122*F. Since the maximum operating temperature of the smoke detectors may be exceeded, spurious alarms may occur; these' detectors may have to be routinely declared inoperable during normal plant operation. Establishment of the hourly fire watch required by Technical Specification 3.3.7.9.a would not be consistent with the intent of ALARA guidance since the dose rate in this area during normal operation will be approximately 5 rem /hr.
Removal of these smoke detectors is justifiable based on the 5 insignificant fire heat load in this area (reference FSAR Table 9A-2) and the low probability of transient combustibles in this area since access is under strict administrative control.
If a fire does occur in this area, it will be sensed by four dual-element thermocouples which monitor ambient air temperature and initiate alarms in the control room on high 4
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temperature. These thermocouples are part of the leak detection system. For thase reasons, the smoke detectors in the main steam tunnel should be removed from service and, therefore, the Technical Specifications should be revised to reflect this.
- 9. (GCNS - 450)
SUBJECT:
Bases Section 2.2.1, page B 2-6; Bases Sections 3/4.3.2 and 3/4.3.3, page B 3/4 3-2; Bases Sections 3/4.3.4, 3/4.3.5, and 3/4.3.6, page B 3/4 3-3.
DISCUSSION: Bases Sections 2.2.1, 3/4.3.2, 3/4.3.3, 3/4.3.4, 3/4.3.5, 3/4.3.6 states that " operation with a trip setpoint less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal or less than the drift allowance assumed for each trip in the safety analysis." The difference between the Trip Setpoint and Allowable Value, however, should be greater than the instrument drift. The affected Bases Sections should be changed to reflect this position.
JUSTIFICATION: The Allowable Value is a quantity bounded by the Safety Analysis. It is a limitation which should not be exceeded by instrument drift. Therefore, the Trip Setpoint is determined such that normal instrument drift will not allow the trip set to exceed the Allowable Value. Hence, the maximum drift allowance should be less than the difference between Trip Setpoint and Allowable Value. This will assure that instrument drift will not exceed the Allowable Value thereby preventing a trip at a less conservative value than assumed in the Safety Analysis.
Changing the wording as indicated on the marked-up pages will l more accurately describe the bases for the referenced system instrumentation Allowable Values.
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