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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARJAFP-99-0278, Application for Amend to License DPR-59,providing Rev C to Proposed TS Change Converting Current TSs to Improved Standard Tss.Withdrawal of JPTS-95-004,proposed TS Changes Re Inservice Leak & Hydrostatic Testing Operation,Reflected1999-10-14014 October 1999 Application for Amend to License DPR-59,providing Rev C to Proposed TS Change Converting Current TSs to Improved Standard Tss.Withdrawal of JPTS-95-004,proposed TS Changes Re Inservice Leak & Hydrostatic Testing Operation,Reflected JAFP-99-0279, Correction to 980226 Application for Amend to License DPR-59,revising Ref 19 to Assume 90% SBGT Sys Charcoal Efficiency,Instead of 99%.Ref 19 on TS Page 285 Needs to Be Changed from Rev 0 to Rev 1,based on Revised Calculation1999-10-14014 October 1999 Correction to 980226 Application for Amend to License DPR-59,revising Ref 19 to Assume 90% SBGT Sys Charcoal Efficiency,Instead of 99%.Ref 19 on TS Page 285 Needs to Be Changed from Rev 0 to Rev 1,based on Revised Calculation ML20216J8321999-09-29029 September 1999 Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases.Change Extends LCO for RHRSW Sys from 7 Days to 11 Days with Special Conditions to Allow for Installation of Mod to Division a RHRSW Strainer ML20196F5931999-06-22022 June 1999 Application for Amend to License DPR-59,changing to Pressure Temp limits.Pressure-temp Curves & Associated LCO & Bases Changes Included in Proposed Amend ML20195B8741999-06-0101 June 1999 Revised Application for Amend to License DPR-59,converting Plant CTS to Be Consistent with Improved Std TS in NUREG-1433,Rev 1,dtd Apr 1995 ML20206U1351999-05-19019 May 1999 Application for Amend to License DPR-59,requesting 14 Day AOT for EDG Sys ML20205K1041999-04-0505 April 1999 Application for Amend to License DPR-59,removing Position Title of General Manager from Sections & Will State That If Site Executive Officer Is Unavailable,Responsibilities Will Be Delegated to Another Staff Member,In Writing ML20205D8271999-03-26026 March 1999 Application for Amend to License DPR-59,converting CTS to Be Consistent with Improved Std TS in NUREG-1433,Rev 1 ML20199H3511999-01-15015 January 1999 Application for Amend to License DPR-59,removing Local Power Range Monitor (LPRM) Signal Calibr Method from TS Table 4.1-2 JAFP-98-0385, Revised Application for Amend to License DPR-59,revising Design Features.Rev 7 to non-proprietary & Proprietary Versions of HI-971661, Licensing Rept for Reracking of Ja FitzPatrick SFP, Encl.Proprietary Info Withheld1998-12-0303 December 1998 Revised Application for Amend to License DPR-59,revising Design Features.Rev 7 to non-proprietary & Proprietary Versions of HI-971661, Licensing Rept for Reracking of Ja FitzPatrick SFP, Encl.Proprietary Info Withheld ML20236X7811998-08-0303 August 1998 Application for Amend to License DPR-59,proposing Rev to Note Which Will Allow TS Section 1.1.A Re SLMCPR to Be Applicable During Cycle 14 ML20236M6151998-07-10010 July 1998 Application for Amend to License DPR-59 to Relocate Portions of TS 3/4.6.C, RCS - Coolant Chemistry, from TS to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process ML20236L2741998-07-0606 July 1998 Application for Amend to License DPR-59,amending Tech Specs Section 3.5.b.1 Re Main Condenser Steam Jet Air Ejector & Table 3.10-1 Re Radiation Monitoring Sys That Initiates &/Or Isolates Sys ML20249B1551998-06-16016 June 1998 Application for Amend to License DPR-59,relocating Safety Review Committee Review,Audit & Related Record Keeping Requirements from Tech Specs to Chapter 17 of Fsar,Per Administrative Ltr 95-06 ML20217K0361998-03-30030 March 1998 Application for Amend to License DPR-59,changing Interval of Selected LSFT from Semiannually to Once Per 24 Months & Revising Definition of LSFT to Be Consistent w/NUREG-1433 ML20247F7791998-02-26026 February 1998 Application for Amend to License DPR-59,changing Allowable Containment Leakage Rate to 1.5 Percent Per Day & Assumed Value of Filter Efficiency for SBGT Used in Calculations to Determine Dose Effects to Onsite ML20202G8551998-02-0606 February 1998 Revised Application for Amend to License DPR-59,to Revise TS Tables 3.2-2 & 4.4-2,revising Allowed Outage Times for 4kV Emergency Bus Undervoltage Trip Functions & Replace Generic Actions for Inoperable Instrument Channels ML20202D5391998-02-0606 February 1998 Application for Amend to License DPR-59,allowing RCS Pressure Tests to Be Performed in Cold Shutdown Mode ML20202D3881998-02-0606 February 1998 Application for Amend to License DPR-59,revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads ML20203J6671997-12-12012 December 1997 Application for Amend to License DPR-59,revising TS Section 6.2.2.6 Re Administrative Controls for Normal Working Hours of Plant Staff Who Perform Safety Related Functions ML20217H9801997-10-14014 October 1997 Application for Amend to License DPR-59,proposing Revision to TS Re Design Features Section,Including Revised Limits for Fuel Storage.Changes Correct Maximum Exposure Dependent, Infinite Lattice Multiplication Factor for Fuel Bundles ML20217G2991997-10-0808 October 1997 Application for Amend to License DPR-59,reflecting Change in LCO ML20140D8011997-04-14014 April 1997 Application for Amend to License DPR-59,deleting Plant Staff Performance Audit Requirement from Section 6.5.2.9.b & Incorporating Plant Staff Performance Review Requirement in Section 6.5.2.8 ML20135B1871996-11-26026 November 1996 Application for Amend to License DPR-59,requesting That Snubber Operability,Surveillance & Records Requirements in TS Be Relocated to Plant Controlled Documents ML20115G0581996-07-12012 July 1996 Application for Amend to License DPR-59,revising Min Critical Power Ratio Safety Limit ML20113B6261996-06-20020 June 1996 Application for Amend to License DPR-59,supporting Adoption of Primary Containment Leakage Rate Testing Requirements of Option B 10CFR50,App J at Plant ML20112D5661996-05-30030 May 1996 Application for Amend to License DPR-59,eliminating Selected Response Time Testing Requirements ML20112D1501996-05-30030 May 1996 Application for Amend to License DPR-59,revising Minimum Critical Power Ratio Safety Limit & Associated Basis ML20112D2671996-05-30030 May 1996 Application for Amend to License DPR-59,revising ATWS Recirculation Pump Trip Reactor Pressure ML20112B6411996-05-16016 May 1996 Application for Amend to License DPR-59,deleting Requirement for PORC to Review Fire Protection Program & Implementing Procedures.Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B ML20108D1151996-04-24024 April 1996 Application for Amend to License DPR-59,supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J & Clarifying Numerical Value of Allowable Containment Leakage Rate as 1.5% Per Day ML20107M4461996-04-24024 April 1996 Application for Amend to License DPR-59,relocating TS 3.11.B/4.11.B Crescent Area Ventilation & Associated Bases from TS to Controlled Procedure ML20101H6671996-03-27027 March 1996 Application for Amend to License DPR-59,adopting Primary Containment Lrt Requirements of Option B to 10CFR50,App J at Plant & Clarifies Numerical Value of Allowable Containment Lrt as 1.5% Per Day ML20101F8311996-03-22022 March 1996 Application for Amend to License DPR-59,revising TS to Implement BWROG Option I-D long-term Solution for Thermal Hydraulic Stability ML20101H3671996-03-22022 March 1996 Application for Amend to License DPR-59,changing TS Table 3.2-2, Core & Containment Cooling Sys Initiation & Control Instrumentation Operability Requirements ML20097A1921996-02-0101 February 1996 Application for Amend to License DPR-59,allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20100C2911996-01-25025 January 1996 Application for Amend to License DPR-59,revising Allowed out-of-service Times for Single Inoperable EDGs to Accommodate on-line Maint of EDGs ML20097J6661996-01-25025 January 1996 Application for Amend to License DPR-59,revising TS to Extend Instrumentation & Miscellaneous Surveillance Test Intervals to Support 24-month Operating Cycle ML20095F7051995-12-14014 December 1995 Application for Amend to License DPR-59,revising TSs to Incorporate IST Requirements of Section XI of ASME Boiler & Pressure Vessel Code JPN-95-051, Application for Amend to License DPR-59,proposing to Extend Surveillance Test Intervals for SLC Sys to Support 24 Month Operating Cycles1995-11-30030 November 1995 Application for Amend to License DPR-59,proposing to Extend Surveillance Test Intervals for SLC Sys to Support 24 Month Operating Cycles ML20094B6471995-10-25025 October 1995 Application for Amend to License DPR-59,revising TS Re Extensionof Containment Sys Surveillance Test Intervals to Accommodate 24 Month Operating Cycles ML20092H5341995-09-15015 September 1995 Application for Amend to License DPR-59,proposing TS by Extending Surveillance Test Intervals for Auxiliary Electrical Sys to Support 24 Month Operating Cycles ML20086P6421995-07-21021 July 1995 Application for Amend to License DPR-59.Amend Would Replace title-specific List of Members on PORC W/More General Statement of Membership Requirements ML20085G3561995-06-15015 June 1995 Application for Amend to License DPR-59,proposing Changes to Ts,By Extending Surveillance Test Intervals for Control Rod Sys to Support 24 Month Operating Cycles ML20083M8081995-05-12012 May 1995 Application for Amend to License DPR-59,extending Surveillance Test Intervals for Esws to Support 24 Month Operating Cycles,Per GL 91-04 JPN-95-022, Application for Amend to License DPR-59.Amend Would Extend Surveillance Test Intervals for Nuclear Steam Supply Sys to Support 24 Month Operating Cycles1995-04-12012 April 1995 Application for Amend to License DPR-59.Amend Would Extend Surveillance Test Intervals for Nuclear Steam Supply Sys to Support 24 Month Operating Cycles JPN-95-011, Application for Amend to License DPR-59,to Extend Surveillance Test Intervals for Snubber Systems to Support 24 Month Operating Cycles1995-03-0202 March 1995 Application for Amend to License DPR-59,to Extend Surveillance Test Intervals for Snubber Systems to Support 24 Month Operating Cycles JPN-95-007, Application for Amend to License DPR-59,to Impose Operability & Surveillance Requirements for Rv Overfill Protection Instrumentation1995-02-22022 February 1995 Application for Amend to License DPR-59,to Impose Operability & Surveillance Requirements for Rv Overfill Protection Instrumentation JPN-94-065, Application for Amend to License DPR-59,revising TSs Re PORC Membership & Review Responsibilities1994-12-0202 December 1994 Application for Amend to License DPR-59,revising TSs Re PORC Membership & Review Responsibilities ML20076F4631994-10-0707 October 1994 Application for Amend to License DPR-59,changing TS Re Safety/Relief Valve Testing Requirements 1999-09-29
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARJAFP-99-0279, Correction to 980226 Application for Amend to License DPR-59,revising Ref 19 to Assume 90% SBGT Sys Charcoal Efficiency,Instead of 99%.Ref 19 on TS Page 285 Needs to Be Changed from Rev 0 to Rev 1,based on Revised Calculation1999-10-14014 October 1999 Correction to 980226 Application for Amend to License DPR-59,revising Ref 19 to Assume 90% SBGT Sys Charcoal Efficiency,Instead of 99%.Ref 19 on TS Page 285 Needs to Be Changed from Rev 0 to Rev 1,based on Revised Calculation JAFP-99-0278, Application for Amend to License DPR-59,providing Rev C to Proposed TS Change Converting Current TSs to Improved Standard Tss.Withdrawal of JPTS-95-004,proposed TS Changes Re Inservice Leak & Hydrostatic Testing Operation,Reflected1999-10-14014 October 1999 Application for Amend to License DPR-59,providing Rev C to Proposed TS Change Converting Current TSs to Improved Standard Tss.Withdrawal of JPTS-95-004,proposed TS Changes Re Inservice Leak & Hydrostatic Testing Operation,Reflected ML20216J8321999-09-29029 September 1999 Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases.Change Extends LCO for RHRSW Sys from 7 Days to 11 Days with Special Conditions to Allow for Installation of Mod to Division a RHRSW Strainer ML20196F5931999-06-22022 June 1999 Application for Amend to License DPR-59,changing to Pressure Temp limits.Pressure-temp Curves & Associated LCO & Bases Changes Included in Proposed Amend ML20195B8741999-06-0101 June 1999 Revised Application for Amend to License DPR-59,converting Plant CTS to Be Consistent with Improved Std TS in NUREG-1433,Rev 1,dtd Apr 1995 ML20206U1351999-05-19019 May 1999 Application for Amend to License DPR-59,requesting 14 Day AOT for EDG Sys ML20205K1041999-04-0505 April 1999 Application for Amend to License DPR-59,removing Position Title of General Manager from Sections & Will State That If Site Executive Officer Is Unavailable,Responsibilities Will Be Delegated to Another Staff Member,In Writing ML20205D8271999-03-26026 March 1999 Application for Amend to License DPR-59,converting CTS to Be Consistent with Improved Std TS in NUREG-1433,Rev 1 ML20199H3511999-01-15015 January 1999 Application for Amend to License DPR-59,removing Local Power Range Monitor (LPRM) Signal Calibr Method from TS Table 4.1-2 JAFP-98-0385, Revised Application for Amend to License DPR-59,revising Design Features.Rev 7 to non-proprietary & Proprietary Versions of HI-971661, Licensing Rept for Reracking of Ja FitzPatrick SFP, Encl.Proprietary Info Withheld1998-12-0303 December 1998 Revised Application for Amend to License DPR-59,revising Design Features.Rev 7 to non-proprietary & Proprietary Versions of HI-971661, Licensing Rept for Reracking of Ja FitzPatrick SFP, Encl.Proprietary Info Withheld ML20236X7811998-08-0303 August 1998 Application for Amend to License DPR-59,proposing Rev to Note Which Will Allow TS Section 1.1.A Re SLMCPR to Be Applicable During Cycle 14 ML20236X5831998-07-29029 July 1998 Amend 245 to License DPR-59,consisting of Changes to TS in Response to Application Transmitted by ,Requesting Rev of Reactor Protection Sys Normally Supply Electrical Protection Assembly Undervoltage Trip Setpoint ML20236M6151998-07-10010 July 1998 Application for Amend to License DPR-59 to Relocate Portions of TS 3/4.6.C, RCS - Coolant Chemistry, from TS to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process ML20236L2741998-07-0606 July 1998 Application for Amend to License DPR-59,amending Tech Specs Section 3.5.b.1 Re Main Condenser Steam Jet Air Ejector & Table 3.10-1 Re Radiation Monitoring Sys That Initiates &/Or Isolates Sys ML20249B1551998-06-16016 June 1998 Application for Amend to License DPR-59,relocating Safety Review Committee Review,Audit & Related Record Keeping Requirements from Tech Specs to Chapter 17 of Fsar,Per Administrative Ltr 95-06 ML20217K0361998-03-30030 March 1998 Application for Amend to License DPR-59,changing Interval of Selected LSFT from Semiannually to Once Per 24 Months & Revising Definition of LSFT to Be Consistent w/NUREG-1433 ML20247F7791998-02-26026 February 1998 Application for Amend to License DPR-59,changing Allowable Containment Leakage Rate to 1.5 Percent Per Day & Assumed Value of Filter Efficiency for SBGT Used in Calculations to Determine Dose Effects to Onsite ML20202G8551998-02-0606 February 1998 Revised Application for Amend to License DPR-59,to Revise TS Tables 3.2-2 & 4.4-2,revising Allowed Outage Times for 4kV Emergency Bus Undervoltage Trip Functions & Replace Generic Actions for Inoperable Instrument Channels ML20202D3881998-02-0606 February 1998 Application for Amend to License DPR-59,revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads ML20202D5391998-02-0606 February 1998 Application for Amend to License DPR-59,allowing RCS Pressure Tests to Be Performed in Cold Shutdown Mode ML20203J6671997-12-12012 December 1997 Application for Amend to License DPR-59,revising TS Section 6.2.2.6 Re Administrative Controls for Normal Working Hours of Plant Staff Who Perform Safety Related Functions ML20217H9801997-10-14014 October 1997 Application for Amend to License DPR-59,proposing Revision to TS Re Design Features Section,Including Revised Limits for Fuel Storage.Changes Correct Maximum Exposure Dependent, Infinite Lattice Multiplication Factor for Fuel Bundles ML20217G2991997-10-0808 October 1997 Application for Amend to License DPR-59,reflecting Change in LCO ML20140D8011997-04-14014 April 1997 Application for Amend to License DPR-59,deleting Plant Staff Performance Audit Requirement from Section 6.5.2.9.b & Incorporating Plant Staff Performance Review Requirement in Section 6.5.2.8 ML20135B1871996-11-26026 November 1996 Application for Amend to License DPR-59,requesting That Snubber Operability,Surveillance & Records Requirements in TS Be Relocated to Plant Controlled Documents ML20115G0581996-07-12012 July 1996 Application for Amend to License DPR-59,revising Min Critical Power Ratio Safety Limit ML20113B6261996-06-20020 June 1996 Application for Amend to License DPR-59,supporting Adoption of Primary Containment Leakage Rate Testing Requirements of Option B 10CFR50,App J at Plant ML20112D2671996-05-30030 May 1996 Application for Amend to License DPR-59,revising ATWS Recirculation Pump Trip Reactor Pressure ML20112D1501996-05-30030 May 1996 Application for Amend to License DPR-59,revising Minimum Critical Power Ratio Safety Limit & Associated Basis ML20112D5661996-05-30030 May 1996 Application for Amend to License DPR-59,eliminating Selected Response Time Testing Requirements ML20112B6411996-05-16016 May 1996 Application for Amend to License DPR-59,deleting Requirement for PORC to Review Fire Protection Program & Implementing Procedures.Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B ML20107M4461996-04-24024 April 1996 Application for Amend to License DPR-59,relocating TS 3.11.B/4.11.B Crescent Area Ventilation & Associated Bases from TS to Controlled Procedure ML20108D1151996-04-24024 April 1996 Application for Amend to License DPR-59,supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J & Clarifying Numerical Value of Allowable Containment Leakage Rate as 1.5% Per Day ML20101H6671996-03-27027 March 1996 Application for Amend to License DPR-59,adopting Primary Containment Lrt Requirements of Option B to 10CFR50,App J at Plant & Clarifies Numerical Value of Allowable Containment Lrt as 1.5% Per Day ML20101F8311996-03-22022 March 1996 Application for Amend to License DPR-59,revising TS to Implement BWROG Option I-D long-term Solution for Thermal Hydraulic Stability ML20101H3671996-03-22022 March 1996 Application for Amend to License DPR-59,changing TS Table 3.2-2, Core & Containment Cooling Sys Initiation & Control Instrumentation Operability Requirements ML20097A1921996-02-0101 February 1996 Application for Amend to License DPR-59,allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20100C2911996-01-25025 January 1996 Application for Amend to License DPR-59,revising Allowed out-of-service Times for Single Inoperable EDGs to Accommodate on-line Maint of EDGs ML20097J6661996-01-25025 January 1996 Application for Amend to License DPR-59,revising TS to Extend Instrumentation & Miscellaneous Surveillance Test Intervals to Support 24-month Operating Cycle ML20095F7051995-12-14014 December 1995 Application for Amend to License DPR-59,revising TSs to Incorporate IST Requirements of Section XI of ASME Boiler & Pressure Vessel Code JPN-95-051, Application for Amend to License DPR-59,proposing to Extend Surveillance Test Intervals for SLC Sys to Support 24 Month Operating Cycles1995-11-30030 November 1995 Application for Amend to License DPR-59,proposing to Extend Surveillance Test Intervals for SLC Sys to Support 24 Month Operating Cycles ML20094B6471995-10-25025 October 1995 Application for Amend to License DPR-59,revising TS Re Extensionof Containment Sys Surveillance Test Intervals to Accommodate 24 Month Operating Cycles ML20092H5341995-09-15015 September 1995 Application for Amend to License DPR-59,proposing TS by Extending Surveillance Test Intervals for Auxiliary Electrical Sys to Support 24 Month Operating Cycles ML20086P6421995-07-21021 July 1995 Application for Amend to License DPR-59.Amend Would Replace title-specific List of Members on PORC W/More General Statement of Membership Requirements ML20085G3561995-06-15015 June 1995 Application for Amend to License DPR-59,proposing Changes to Ts,By Extending Surveillance Test Intervals for Control Rod Sys to Support 24 Month Operating Cycles ML20083M8081995-05-12012 May 1995 Application for Amend to License DPR-59,extending Surveillance Test Intervals for Esws to Support 24 Month Operating Cycles,Per GL 91-04 JPN-95-022, Application for Amend to License DPR-59.Amend Would Extend Surveillance Test Intervals for Nuclear Steam Supply Sys to Support 24 Month Operating Cycles1995-04-12012 April 1995 Application for Amend to License DPR-59.Amend Would Extend Surveillance Test Intervals for Nuclear Steam Supply Sys to Support 24 Month Operating Cycles JPN-95-011, Application for Amend to License DPR-59,to Extend Surveillance Test Intervals for Snubber Systems to Support 24 Month Operating Cycles1995-03-0202 March 1995 Application for Amend to License DPR-59,to Extend Surveillance Test Intervals for Snubber Systems to Support 24 Month Operating Cycles JPN-95-007, Application for Amend to License DPR-59,to Impose Operability & Surveillance Requirements for Rv Overfill Protection Instrumentation1995-02-22022 February 1995 Application for Amend to License DPR-59,to Impose Operability & Surveillance Requirements for Rv Overfill Protection Instrumentation JPN-94-065, Application for Amend to License DPR-59,revising TSs Re PORC Membership & Review Responsibilities1994-12-0202 December 1994 Application for Amend to License DPR-59,revising TSs Re PORC Membership & Review Responsibilities 1999-09-29
[Table view] |
Text
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- BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of )
POWER AUTHORITY OF THE STATE OF NEW YORK ) Docket No. 50-333 l
James A. FitzPatrick Nuclear Power Plant )
i APPLICATION FOR AMENDMENT TO OPERATING LICENSE l Pursuant to Section 50.90 of the regulations of the Nuclear Regulatory Commission (NRC), the Power Authority of the State of New York, as holder of Facility Operating License No. DPR-59, hereby applies for an Amendment to the Technical Specifications contained in Appendix A and Appendix B of the license.
This application for amendment seeks to revise Appendix A (Section 6.1) and Appendix B (Section 7.1) of the James A. FitzPatrick Technical Specifications. These changes will remove the position title of General Manager from these sections and will state that if the Site Executive Officer is unavailable, he will delegate his responsibilities to another staff member, in writing. In addition, the position title of Resident Manager, used in Appendix B, Section 7.1, will be replaced by Site Executive Officer.
The proposed changes to the Technical Specifications are included as Attachment I to this l application. The Safety Evaluation is included as Attachment 11.
l POWER AUTHORITY OF THE STATE OF NE YORK
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J nubel 99 41gg g g g g33 Senior Vice President and P PDR Chief Nuc!:.ar Officer STATE OF NEW YORK COUNTY OF WESTCHESTER Subsc t 's5ged and daySworn to before 1999.
ofGPAi.L. me A4 'h ' * >
/
Notary Public SERALDME STRMWD hussry Pubhc. State of fees 44 leo 4991272 en Westchester een Emnes Jen 31, ed
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e 0 0 4
ATTACHMENT I TO JPN-99-011 PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING ADMINISTRATIVE CONTROLS (JPTS-99-002) i i
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT l l
DOCKET NO. 50-333 DPR-59 i
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- l l
JAFNPP 6.0 ADMINISTRATIVE CONTROLS Administrative Controls are the means by which plant operations are subject to management control. Mearures specified in this section provide for the assignment of responsibilities, plant organization, staffing qualifications and related requirements, review and audit mechanisms, procedural controls and reporting requirements. Each of these measures are necessary to ensure safe and efficient facility operation.
6.1 RESPONSIBILITY l The Site Executive Officer is responsible for safe operation of the plant and shall delegate in writing the succession to this responsibility during his absence.
6.2 ORGANIZATION 6.2.1 Facility Manaaement and Technical Suonort 1
Onsite and offsite organizations shall be established for plant operation and corporate management, respectively. The onsite and offsite organizations shall include the j positions for activities that affect the safety of the nuclear power plant.
l 1. Lines of authority, responsibility, and communication shall be established and defined l for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be oocumented and updated, as appropriate, in the form of organization charts, functional descriptions of department responsibilities and relationships, and job descriptions for key personnel l positions, or in equivalent forms of documentation. These requirements shall be
- documented in the Updated FSAR.
l
! 2. The Site Executive Officer shall be responsible for overall plant operation, and shall l have control over those onsite activities that are necessary for safe operation and l main'.anance of the plant.
l 1
- 3. The Chief Nuclear Officer shall take any measures needed to ensure acceptable '
performance of the staff in operating, maintaining, and providing technical support to ;
l the plant to ensure nuclear safety. I
- 4. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
l 6.2.2 Plant Staff 1
The plant staff organization shall be as follows:
- 1. Each shift crew shall be composed of at least the minimum shift crew composition shown in Table 6.2-1; Amendment No. - 50, 60, 78, l ' 1,130,137, ' 78, 203, 220, 2287 247 i
i i
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, JAFNPP 7.0 ADMINISTRATIVE CONTROLS j 7.' 1' RE$PONSIBILITY I
- a. The Site Executive Officer shall have direct responsibility for assuring the operation of l the James A. FitzPatrick Plant is conducted in such a manner as to provide continuing protection to the environment and shall delegate in writing the succession to this responsibility during his absence.
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- b. Implementation of the Radiological Effluent Technical Specifications is the responsibility of the General Manager - Operations, with the assistance of the plant staff organization.
7.2 PROCEDURES Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Section 5
" Facility Administrative Policies and Procedures" of ANSI 18.7-1972 and Regulatory Guide 1.33, November 1972, Appendix A. In addition, procedures shall be established, implemented and maintained for the PCP, ODCM, and Quality Control Program for effluent and environmental monitoring using the guidance in Regulatory Gu ds 4.1, Revision 1.
7.3 REPORTING REQUIREMENTS
- a. Planned Liauid and Gaseous Releases The limits for radioactive materials contained in liquid and gaseous effluents are l contained in Specifications 2.3,3.3 and 3.4. I
- b. Environmental Samoles Exceedina Limits of Table 6.1-2 When the limits of Table 6.1-2 are exceeded, refer to Specification 6.1.b for reporting I requirements.
- c. Semiannual Radioactive Effluent Release Report Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality.
- 1. The Radioactive Effluent Release Report shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit l
using as guidance Regulatory Guide 1.21, Revision 1, June 1974, " Measuring, Ewaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", with data summarized on a quarterly basis following the format of Appendix B thereof.
Amendment No. 03, 203, 65 i
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- 9 ATTACHMENT 11 TO JPN-99-011 SAFETY EVALUATION OF PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING ADMINISTRATIVE CONTROLS (JPTS-99-002)
NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 DPR-59
I .
i Attachment ll j JPN-99-011 Page 1 of 5 1
SAFETY EVALUATION RELATED TO PROPOSED TECHNICAL SPECIFICATION CHANGES REGARDING ADMINISTRATIVE CONTROLS (JPTS-99-002)
Section 1 - Description of Channes This application for amendment setAs to revise Appendix A (Section 6.1) and Appendix B (Section 7.1) of the James A. FitzPatrick Technical Specifications (TS). These changes will remove the stipulation that if the Site Executive Officer (SEO) is unavailable, one of the dyee General Managers will assume his responsibilities. Instead, the TS section will say that the SEO will delegate, in writing, the succession of his responsibilities during his absence. In addition, the position title of Resident Manager, used in Appendix B, Section 7.1, will be replaced by Site Executive Officer. The specific TS changes are as follows.
Appendix A. Section 6.1 Replace:
"The Site Executive Officer is responsible for safe operation of the plant. During periods when the Site Executive Officer is unavailable, one of the three General Manager will assume this responsibility. In the event all four are unavailable, the Site Executive i Officer may delegate this responsibility to other qualified supervisory personnel."
With:
"The Site Executive Officer is responsible for safe operation of the plant and shall i delegate in writing the succession to this responsibility during his absence."
Appendix B. Section 7.1 Replace:
"The Resident Manager shall have direct responsibility for assuring the operation of the James A. FitzPatrick Plant is conducted in such a manner as to provide continuing i protection to the environment. During periods when 'e Resident Manager is unavailable, onc of the three Generall&nagers w. .:ume his responsibility. In the event all four are unavailable, the Resident Manager may delegate this responsibility to other qualified supervisory personnel."
With:
l "The Site Executive Officer shall have direct responsibility for assuring the operation of the James A. FitzPatrick Plant is conducted in suc5 a manner as to provide continuing
( protection to the environment and shall delegate in writing the succession to this I responsibility during his absence."
i Attachment 11 JPN-99-011 Page 2 of 5 Section ll- Purpose of Proposed Channes The proposed changes model the General Electric Standard Technical Specifications (NUREG-1433) and will allow the SEO to delegate his responsibilities to qualified personnel without specifying their position titles in Section 6.1 of TS Appendix A or Section 7.1 of TS Appendix B.
Section ill - Safety implications of the Proposed Chanaes This proposed amendmer't request revises Appendix A (Section 6.1) and Appendix B .
(Section 7.1) which discuss the delegation of the SEO's responsibilities in his absence.
Currently, these specifications state that the SEO will delegate his responsibilities to one of the l
I General Managers if he is unavailable. If the SEO and General Managers are unavailable, then the SEO may delegate his responsibilities to other qualified supervisory personnel.
The current wording ithe TC does not allow the SEO to delegate his responsibilities to t!
Plant Manager (a newly created management position) unless all three General Managers se also unavailable. Since the Plant Manager is the second highest level of management at the plant and the General Managers report to him, the Plant Manager should be permitted to undertake the SEO's responsibilities,in his absence, regardless of the availability of the General Managers. Therefore, this amendment request eliminates the specific reference to the General Manager positions in Appendix A (Section 6.1) and Appendix B (Section 7.1) and allows the SEO to delegate, in writing, his responsibilities to a qualified personnel member, such as the Plant Manager.
This TS change does not change the intent of the current specifications, in that the Plant Manager or other qualified personnel, such as one of the General Managers, will assume the responsibilities of the SEO in his absence. However, it eliminates the need for future TS amendments to these sections based solely on organizational changes such as the creation of '
new or revised management positions (such as the Plant Manager), title changes to the position of General Manager, or a change to the number of General Managers. These types of organizational changes can then be evaluated through the use of 6he 10 CFR 50.59 process, rather than the TS amendment process. This will reduce the unnecessary burden on NRC and licensee resources associated with processing license amendment requests related to these areas. This TS change models the comparable administrative controls section of the General Electric Standard Technical Specifications (b"' REG-1433).
The changes to Appendix B (Section 7.1) also include the replacement of the position title of Resident Manager with Site Executive Officer. This position title change was approved by the NRC in Amendment 228 (Reference). However, the reference to Resident Manager in this section was inadvertently missed and is being corrected as part of this amendment application. !
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l 1-Attachment ll JPN-99-011 Page 3 of 5 Section IV - Evaluation of No Sionificant Hazards Consideration Consistent with the criteria of 10 CFR 50.92, the enclosed application is judged to involve no signincant hazards based on the following information:
(1) Does the proposed license amendment involve a significant increase in the probability or consequences of an accident previously ar.alyzed?
Response
The proposed changes to Appendix A (Section 6.1) and Appendix B (Section 7.1) are administrative in nature in that they do not change the intent of the Technical Specifications. If the SEO is unavailable, he will still delegate his responsibilities to a qualified personnel member, such as the Plant Manager or one of the General Managers. These changes can not cause an accident or contribute to the probability or consequences of one.
The replacement of the position title of Resident Manager with Site Executive Officer in Appendix B, Section 7.1, was already approved by the NRC in Amendment 228.
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously analyzed.
(2) Does the proposed license amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: ;
The proposed changes to Appendix A (Section 6.1) and Appendix B (Section 7.1) are administrative in nature as they do not affect the function of plant equipment or the way the equipment operates. The changes do not change the intent of the current TS, in that if the SEO is unavailable, he will delegate his responsibilities to another personnel member such as the Plant Manager or one of the General Managers. Appendix A (Section 0.1) and Appendix B (Section 7.1) are being revised to eliminate the need for future TS changes to these sections resulting solely from the creation of new or revised management positions (such as the Plant Manager), title changes to the position of General Manager, or a change to the number of General Managers. These types of crganizational changes will be evaluated using the criteria of 10 CFR 50.59.
The replacement of the position title of Resident Manager with Site Executive Officer in l
l Appendix B, Section 7.1, was already approved by the NRC in Amendment 228.
Therefore, the proposed license amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated. j
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i Attachment 11 JPN-99-011 Page 4 of 5 l
(3) Does the proposed amendment involve a significant reduction in a margin of safety?
Response
The proposed changes to Appendix A (Section 6.1) and Appendix B (Section 7.1) are
! administrative changes associated with the delegation of the SEO's responsibilities
- when he is unavailable. These changes do not change the intent of the current TS, in that in the SEO's absence, he will still delegate his responsibilities to other personnel members such as the Plant Manager or General Mnnagers.
The replacement of the position title of Resident Manager with Site Executive Officer in Appendix B, Section 7.1, was already approved by the NRC in Amendment 228.
Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
Section V -Implementation of the Proposed Chanees This amendment request meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) as follows:
(i) the amendment involves no significant hazards consideration.
As dertirestrated in Section IV of this evaluation, the proposed change involves no significant hazards consideration.
(ii) there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite.
The proposed changes do not involve a physical alteration to the plant or revisions to any plant operating procedures. The changes are administrative in nature and do not affect the amounts of any effluents that may be released offsite.
l (iii) there is no significant increase in individual or cumulative occupational radiation exposure.
The propo md changes do not alter plant operating or surveillance procedures, and therefore will not change individual or cumulative occupational radiation exposure.
Based on the above, it is concluded that there will be no impact on the environment resulting from the proposed changes and the proposed changes meet the criteria specified in 10 CFR i
51.22 for a categorical exclusion from the requirements of 10 CFR 51.21 relative to requiring a L
specific environmental assessment by the Commission. Additionally, implementation of the proposed changes will not adversely alter or affect the ALARA program or the Fire Protection Program.
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l Attachment II JPN-99-011 Page 5 of 5 Section VI - Conclusion Based upon the discussion in previous sections, the changes to Appendix A, Section 6.1 and Appendix B, Section 7.1 are administrative in nature as they do not change the intent of the current Technical Specifications.
The Plant Operating Review Committee (PORC) and Safety Review Committee (SRC) have reviewed these proposed changes and have concluded that the changes do not involve an unreviewed safety question or a significant hazards consideration as defined in 10 CFR 50.92, and do not endanger the health and safety of the public.
Section Vil- Reference NRC letter (Amendment 228), C. Carpenter to W. Cahill, Jr., " Issuance of Amendment for James A. FitzPatrick Nuclear Power Plant," dated October 13,1995.
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l ATTACHMENT lil TO JPN-99-011 MARK-UP OF TECHNICAL SPECIFICATION PAGES REGARDING ADMINISTRATIVE CONTROLS (JPTS-99-002)
NOTE 1: Deletions are shown in Str?.cret, and additions are shown in bold.
l NOTE 2: Previous amendment revision bars are not shown.
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I NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 j DPR-59 l 1
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