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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
l 1
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION l I
In the Matter of )
NEW YORK POWER AUTHORITY ) Docket No. 50-333 James A. FitzPatrick Nuclear Power Plant )
APPLICATION FOR AMENDMENT TO OPERATING LICENSE The New York Power Authority requests an amendment to the Technical Specifications contained in Appendix A to Facility Operating License DPR-59 for the James A. FitzPatrick Nuclear Power Plant. This application is filed in accordance with Section 10 CFR 50.90 of the Nuclear Regulatory Commission's regulations.
This application for an amendment to the James A. FitzPatrbk Technical Specifications (TS) proposes to delete the requirement for the Plant Operating Review Committee (PORC) 4 to review the fire protection program and implementing procedures. This proposal will I reduce the administrative burden on the committee while making PORC's responsibilities more consistent with the other responsibilities described in Section 6.1.5.6 of the TS.
PORC will continued to oversee changes to the FitzPatrick fire protection program through its review of nuclear safety evaluations.
An additional change is proposed to delete redundant fire protection program inspection and audit requirements from Specification 6.14.A and 6.14.B. Similar inspections and audits are performed under the cognizance of the Safety Review Committee (SRC), as required by Specification 6.5.2.9.
Attachment I contains the proposed new TS pages and Attachment 11 is the Safety Evaluation for the proposed changes. A markup of the affected TS pages is included as Attachment 111.
New York Power Authority ;
/ s W. J. Cahill, Jr.
Chief Nuclear Officer I
STATE OF NEW YORK COUNTY OF WESTCHESTER Subscribed and sworn to before me day of 1996. EE.EEN E. O'CONNOR this bT4 f
/ pisesry Putdoo, State of NewWok No.4991062 j Ouellflod in westchester cou ,
Mo,,~ _ yhV Casuniesson Empires.lenuant 21, g/ , 9 p-- i 9
Motary Public /
9605230050 960516 PDR ADOCK 05000333 p PDR
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1 Attachment I to JPN-96-023 l 1
REVISED TECHNICAL SPECIFICATION PAGE0 PORC REVIEW OF FIRE PROTECTION PROGRAM l l
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} (JPTS-95-005) l i 1 e
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4 4
New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 j
~ . . . - . . _ -. - . ...... __ ,.
LIST OF PAGE CHANGES PORC REVIEW OF FIRE PROTECTION PROGRAM (JPTS-95-005) l l
Revise Appendix A as follows:
Remove Paae Insert Pace 249 249 258 258 l l
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t l-I i
-. .j JAFNPP i ;
I 6.5.1.3 Altemates Altemative members shall be appointed in writing by the PORC Chairman to serve on a i temporary basis.
- l. 6.5.1.4 Meeting Frequency i
l Meetings will be called by the Chairman as the occasions for review or investigation arise.
l Meetings will be no less frequent than once a month.
6.5.1.5 Quorum i t
l A quorum of the PORC shall consist of the Chairman or a Vice-Chairman and five members including designated altemates. Vice-Chairmen may act as members when not acting as Chairman. A quorum shall contain no more than two attemates.
6.5.1.6 Responsibilities L The PORC shall be responsible for the: ;
1
- a. Review of 10 CFR 50.59 safety and environmental impact evaluations associated with j procedures and programs required by Specification 6.8, and changes thereto. ,
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- b. Review of proposed tests and experiments that affect nuclear safety.
- c. Review of proposed changes to the Operating License and Technical Specifications.
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- d. Review of proposed changes or modifications to plant systems or equipment that affect j nuclear safety. j
- e. Investigation of violations of the Technical Specifications. The PORC shall prepare and present a report covering the evaluations and recommendations to prevent recurrence to the Site Executive Officer, who will then forwand the report to the Chief Nuclear Officer, the Vice President Regulatory Affairs and Special Projects, and to the Chairman of the Safety Review Committee.
- f. Review of plant operations to detect potential safety hazards.
- g. Performance of special reviews and/or investigations at the request of the Site Executive Officer.
- h. Review of all reportable events.
i 1. Review of the Process Control Program and the Offsite Dose Calculation Manual (ODCM) l i
! and changes thereto, 4 !
Amendment No. " '"' ^' " ^ ' " "
249 j L .
l JAFNPP 6.12 INDUSTRIAL SECURITY PROGRAM An industrial security program shall be maintained throughout the life of the plant in accordance with the provisions of the Plant Security Plan.
6.13 EMERGENCY PLAN ,
THIS SECTION PURPOSELY BLANK i
6.14 FIRE PROTECTION PROGRAM THIS SECTION PURPOSELY BLANK l 1
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Amendment No. 37, S1, 228, 258
I Attachment il to JPN-96-023 SAFETY EVALUATION l
PORC REVIEW OF FIRE PROTECTION PROGRAM (JPTS-95-005)
New York Power Authority 1
JAMES A. FITZPATRICK NUCLEAR POWER PLANT I
! Docket No. 50-333 )
! DPR-59 l l
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Attachment 11 to JPN-96-023 SAFETY EVALUATION Page 1 of 5
- 1. DESCRIPTION l The proposed change to the James A. FitzPatrick Technical Specifications (TS) deletes the requirement for the Plant Operating Review Committee (PORC) to review the fire protection program and implementing procedures. This proposal will reduce the administrative burden on the committee while making PORC's responsibilities more consistent with the other responsibilities described in Section 6.5.1.6 of the TS.
PORC will continue to oversee changes to the FitzPatrick fire protection program through its review of nuclear safety evaluations.
An additional change is proposed to delete redundant fire protection program inspection and audit requirements from Specification 6.14.A and 6.14.B. Similar inspections and audits are performed under the cognizance of the Safety Review Committee (SRC), as required by Specification 6.5.2.9.
- 1. PORC Responsibilities Paae 249 Delete Specification 6.5.1.6.j, which states:
"j. Review the FitzPatrick Fire Protection Program and implementing procedures and changes thereto."
- 2. Fire Protection Program Inspection and Audit Requirements I Eaqe 250 l
Delete Specification 6.14.A and 6.14.B, which state:
1 "A. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified licensee personnel or an outside fire protection firm.
B. An inspection and audit by an outside qualified fire consultant shall be i
performed at intervals no greater than 3 years." I Replace with the phrase "THIS SECTION PURPOSELY BLANK." Revised Specification 6.14 to read:
l "6.14 FIRE PROTECTION PROGRAM THIS SECTION PURPOSELY BLANK" A
d i
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' Attachment ll to JPN-96-023 SAFETY EVALUATION Page 2 of 5
- 11. PURPOSE OF THE PROPOSED CHANGE
- 1. PORC Responsibilities The changes will reduce the administrative burden on the PORC by eliminating review requirements which provide a limited safety benefit. Deleting PORC's responsibility for review of the fire protection program and implementing procedures does not increase the probability or consequences of a fire at FitzPatrick nor will it decrease the effectiveness of the program. Other review and oversight responsibilities will provide a high degree of confidence in the overall quality of the fire protection program and implementing procedures.
Removal of Fire Protection Requirements from the Technical Specifications This PORC responsibility was added by Amendment 218 (References 1,2 and 3).
The amendment revised the TS to relocate fire protection requirements to the fire protection program in accordance with the guidance provided in NRC Generic Letter (GL) 88-12, " Removal of Fire Protection Requirements from the Technical Specifications," (Reference 4). GL 88-12 recommended that licensees propose two changes to the administrative controls section of the TS. These changes were (1) the PORC shall be given responsibility for the review of the fire protection program and implementing procedures, and (2) fire protocuon program implementation shall be added to the list of elements for which written procedures are required. GL 88-12 states that the emergency plan and security plan were used as models to determine the appropriate administrative controls for fire protection.
New Review and Approval Process for Procedures Subsequent to the relocation of fire protection requirements, the NRC issued Amendment 222 (References 5,6 and 7) to the FitzPatrick TS. This amendment established a new review and approval process for procedures required by TS Section 6.8. This process relies upon qualified individuals to perform technical and safety reviews of procedures and eliminates the requirement for PORC review of procedures. Amendment 222 also removed the review and audit requirements for emergency and security plans based on recommendations of Generic Letter 93-07, " Modification of the Technical Specification Administrative Control Requirements for Emergency and Security Plans," (Reference 8). With the issuance of Amendment 222, the basis for PORC review of the fire protection program and implementing procedures was superseded.
PORC review of the fire protection program and implementing procedures does not provide a significant safety benefit because adequacy of the program and procedures is assured by the procedure review and approval process implemented by Amendment 222. The procedure review and approval process requires that l safety and technical reviews of procedures be performed by qualified individuals,
! that required safety and/or environmentalimpact evaluations be reviewed by PORC, and that procedures be approved by appropriate members of plant 4
management. The procedure review and approval process is applicable to procedures that implement and define the fire protection program.
Attachment 11 to JPN-96-023 SAFETY EVALUATION Page 3 of 5 Operating License Condition Amendment 218 also revised the FitzPatrick Facility Operating License to include the NRC's standard fire protection license condition. This condition requires that any changes to the fire protection program be approved by the NRC, unless the changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
10 CFR 50.59 and UFSAR The NRC-approved fire protection program is included in FSAR Section 9.8.5,
" Fire Protection Program," and thus, any changes to the program as described in the FSAR are controlled under the provisions of 10 CFR 50.59.
Safety Review Committee Inspection and Audit inspection and audit of the fire protection program is performed under the cognizance of the SRC as required by Specification 6.5.2.9.
l 2. Fire Protection Program Inspection and Audit Requirements Deleting Specification 6.14.A and 6.14.B will remove inspection and audit requirements that are redundant to those performed under the cognizance of the SRC. Specification 6.5.2.9 establishes these audits, and includes the following:
(1) an independent fire protection inspection and audit shall be performed annually l utilizing either qualified offsite licensee personnel or an outside fire protection l firm, and (2) an inspection and audit of the fire protection program shall be l performed by an outside qualified fire consultant at intervals no greater than 3 years. Therefore, the inspection and audit requirements of Specification 6.14.A and 6.14.B are redundant to the requirements of Specification 6.5.2.9. In addition, the audits required by Specification 6.14.A and 6.14.B are performed concurrent with the redundant audits listed in Specification 6.5.2.9.
Consequently, deleting Specification 6.14.A and 6.14.B will not reduce periodic audits and inspections of the fire protection program.
Ill. SAFETY IMPLICATIONS OF THE PROPOSED CHANGE l
' PORC review of the fire protection program and implementing procedures does not enhance safety because adequacy of the program is assured by the fire protection license condition, the procedure review and approval process implemented by Amendment 222, the provisions of 10 CFR 50.59, and inspections and audits performed under the cognizance of the SRC. The inspection and audit requirements contained in Specification 6.14.A and 6.14.B are redundant to the SRC audit requirements contained in Specification 6.5.2.9.
Consequently, deleting PORC's responsibility for review of the fire protection program and implementing procedures, and deleting the inspection and audit requirements contained in Specification 6.14.A and 6.14.8 will not degrade the fire potection
- program. Therefore, there is no safety implication with the proposed change.
Attachment ll to JPN-96-023 SAFETY EVALUATION Page 4 of 5 IV. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION Operation of the FitzPatrick plant in accordance with the proposed amendment would not involve a significant hazards consideration as defined in 10 CFR 50.92, since it would not:
- 1. involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed changes delete the Plant Operating Review Committee (PORC) review of the fire protection program and implementing procedures, and deleted fire protection inspection and audit requirements that are redundant to those performed under the cognizance of the Safety Review Committee (SRC).
The changes do not introduce any new modes of plant operation, make any physical changes, or alter any operational setpoints. Therefore, the changes do not degrade the performance of any safety system assumed to function in the accident analysis. Consequently, there is no effect on the probability or consequences of an accident.
- 2. create the possibility of a new or different kind of accident from those,previously evaluated.
No physical changes to the plant or changes to equipment operating procedures are proposed. The changes are administrative and will not have any direct affect on equipment important to safety. Therefore the changes cannot create the possibility of a new or different kind of accident.
- 3. involve a significant reduction in the margin of safety.
Adequacy of the fire protection program and implementing procedures is assured by the fire protection license condition, the procedure review and approval process implemented by Amendment 222, the provisions of 10 CFR 50.59, and inspections and audits performed under the cognizance of the SRC.
Consequently, deleting PORC's responsibility for review of the fire protection program and implementing procedures, and deleting the inspection and audit requirements contained in Specification 6.14.A and 6.14.B will not degrade the fire protection program. Therefore, the proposed changes do not involve a significant reduction in the margin of safety.
V. IMPLEMENTATION OF THE PROPOSED CHANGE Implementation of the proposed change will not adversely affect the ALARA or fire protection programs at the FitzPatrick plant, nor will the change impact the l environment. I l
l
1 Attachment 11 to JPN-96-023 SAFETY EVALUATION Page 5 of 5 l VI. CONCLUSION i
)
Based on the discussion at ove, the requirement for the PORC to review the fire i protection program and irrplementing procedures, and the inspection and audit requirements of Specification 6.14.A and 6.14.B, can be removed from the Technical l
- Specifications without adversely affecting the fire protection program. !
- The Plant Operating Review Committee (PORC) and Safety Review Committee (SRC) have reviewed this proposed change to the Technical Specifications and have concluded that it does not involve an unreviewed safety question or a significant hazards consideration and will not endanger the health and safety of the public.
Vll. REFERENCES
- 1. NRC letter, J. E. Menning (USNRC) to W. J. Cahill, Jr. (NYPA) dated November 3, 1994, regarding issuance of amendrnent for James A. FitzPatrick Nuclear Power Plant (TAC NO. M89987). Fransmits amendment 218 and associated safety evaluation.
- 2. NYPA letter, W. A. Josiger to USNRC (JPN-94-033) dated July 21,1994, regarding proposed changes tc the Technical Specifications and to the Operating License to relocate Technical Specification requirements for fire protection to an administrative procedure.
- 3. NYPA letter, W. J. Cahill, Jr. to USNRC (JPN-94-049) dated September 26, 1994, regarding revision to proposed changes to the Technical Specifications and to the Operating License to relocate Technical Specification requirements for fire protection to an administrative procedure.
- 4. NRC Generic Letter 88-12, " Removal of Fire Protection Requirements from Technical Specifications," dated August 2,1988.
- 5. NRC letter, N. F, Conicella (USNRC) to W. J. Cahill, Jr. (NYPA) dated January 18, 1995, regarding issuance of amendment for James A. FitzPatrick Nuclear Power Plant (TAC NO. M89706). Transmits amendment 222 and associated safety evaluation.
- 6. NYPA letter, W. A. Josiger to USNRC (JPN-94-029) dated June 17,1994, regarding proposed changes to Technical Specifications regarding Plant Operating Review Committee (PORC) membership and review responsibilities.
- 7. NYPA letter, W. J. Cahill, Jr. to USNRC (JPN-94-065) dated December 2,1994, regarding supplement to proposed changes to Technical Specifications regarding Plant Operating Review Committee (PORC) membership and review responsibilities.
- 8. NRC Generic Letter 93-07, " Modification of the Technical Specification Administrative Control Requirements for Emergency and Security Plans," dated I
December 28,1993.
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