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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20210K3631999-07-30030 July 1999 Marked-up & Revised TS Bases Page B 3/4 5-2 Re ECCS ML20196G3671999-06-23023 June 1999 Proposed Tech Specs Increasing AOT for Crac from 30 Days to 60 Days on One Time Basis for Each Train to Facilitate on- Line Implementation of Design Enhancements During Current Operating Cycle ML20198E7411998-12-16016 December 1998 Proposed Tech Specs Pages Re LAR-98-15,involving Relocation of TS 3/4.7.10 & Associated TS Table 3.7-3 to Technical Requirements Manual ML20198E7831998-12-16016 December 1998 Proposed Tech Specs Pages to LAR 98-09,re Editorial & Administrative Changes to TS ML20155J1821998-11-0404 November 1998 Proposed Tech Specs 4.5.2b.1,removing Prescriptive Requirements of Using Venting Process as Sole Means to Verify That ECCS Piping Is Full of Water ML20249B4181998-06-17017 June 1998 Proposed Tech Specs 3.7.6 Re Control Room Emergency Makeup Air & Filtration Subsystem ML20247R7021998-05-20020 May 1998 Proposed Tech Specs Re Rev of Refueling Water Storage Tank low-low Level Setpoint ML20217E8871998-04-22022 April 1998 Proposed Tech Specs Re Surveillance Intervals to Accommodate 24-month Fuel Cycle,Per GL 91-04 ML20217F9651998-04-21021 April 1998 Proposed Tech Specs Page 3/4 5-5 Re Venting of Operating Chemical Vol & Control Sys Centrifugal Charging Pump ML20216C5921998-04-0808 April 1998 Proposed Tech Specs Changing Surveillance Intervals to Accommodate 24-month Fuel Cycle Per GL 91-04 ML20217Q2981998-04-0303 April 1998 Proposed Tech Specs Pages Re LAR 98-02,proposing Changes to TS to Accommodate Fuel Cycles of Up to 24 Months ML20217M3771998-03-27027 March 1998 Proposed Tech Specs 3.7.6 Re Control Room Emergency Makeup Air & Filtration Subsystem ML20217F0961998-03-23023 March 1998 Proposed Tech Specs Pages,Incorporating New Spec 3.0.5 Administrative Controls,Currently Approved for Use in NUREG-1431 ML20217Q1031998-03-0505 March 1998 Proposed Tech Specs Incorporating Programmatic Controls for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20217N7321998-03-0202 March 1998 Proposed Tech Specs Pages,Revising Frequency for Performance of Specific Surveillances & Deleting Requirements for Accelerated Testing When Number of Valid Test Failures Associated W/Edgs Is Met or Exceeded ML20217N8211998-03-0202 March 1998 Proposed Tech Specs 4.5.2B.1,excluding Prescriptive Requirement to Vent Operating CVCS CCP Casing ML20211E9981997-09-26026 September 1997 Proposed Tech Specs 3.7.6,separating Requirements for CR HVAC Sys Re Operation of CR Emergency Makeup Air & Filtration Sys Subsystem & CR Air Conditioning Subsystem ML20148G0011997-05-29029 May 1997 Proposed Tech Specs Replacing Term Zircaloy W/Terminology That Identifies NRC Approved Westinghouse Fuel Assembly Design Consisting of Assemblies W/Either ZIRLO or Zircaloy- 4 Fuel Cladding Matl ML20135C3541997-02-26026 February 1997 Proposed Tech Specs,Providing Retyped Page of Proposed Changes Re Design Features Fuel Assembly Reconstitution ML20134Q3451997-02-18018 February 1997 Proposed Tech Specs 5.3.1 Re Fuel Assemblies ML20134L8681997-02-12012 February 1997 Proposed Tech Specs 6.0 Re Administrative Controls ML20129B8361996-10-17017 October 1996 Proposed Tech Specs,Consisting of Change Request 96-02, Proposing Changes That Involve Relocation of Four TS Re Instrumentation Requirements Contained in TS Section 3/4.3 & Relocation of Selected Requirements ML20129B7761996-10-16016 October 1996 Proposed Tech Specs,Consisting of Change Request 96-06, Proposing Four Changes Re EDG Requirements Contained in TS 3/4.8.1, AC Sources ML20113B2031996-06-20020 June 1996 Proposed Tech Specs Re Svc Water Cooling Tower Loop Electrical Supply ML20117K3111996-06-0404 June 1996 Proposed Tech Specs Re Containment Leakage Testing Modifying Implementing Performance Based Program at Seabrook Station IAW 10CFR50,App J,Option B & Reg Guide 1.163 Requirements ML20094D5341995-10-30030 October 1995 Proposed Tech Spec 3.4.6.2, RCS Operational Leakage Pressure Isolation Valve Table ML20092M1071995-09-22022 September 1995 Proposed TS 3.3.2,Table 3.3-3, ESFAS Instrumentation, Correcting Action Ref for Functional Unit 8.b Re Automatic Switchover to Containment Sump/Rwst Level low-low ML20098A4721995-09-20020 September 1995 Proposed Tech Specs,Relocating Functional Unit 6.b, FW Isolation-Low RCS Tavg Coincident W/Rt from TS Requirements Manual Licensee Controlled Document ML20092K2201995-09-20020 September 1995 Proposed Tech Specs,Changing Plant TS Bases Section 3/4.9.1 for Refueling B Concentration ML20092F9171995-09-12012 September 1995 Proposed Tech Specs Bases Section Clarifying What Specifically Constitutes Operable Pressurizer Safety Valve in Mode 5 ML20092A6331995-09-0505 September 1995 Proposed Tech Specs,Revising Main Steam Safety Valve Setpoints & Max Allowable Power Range Neutron Flux High Setpoints W/Inoperable Main Steam Safety Valves ML20091S1601995-08-28028 August 1995 Proposed Tech Specs Re Positive Moderator Temp Coefficient ML20086R2111995-07-24024 July 1995 Proposed Tech Specs,Relocating Table 3.4-1, RCS PIVs from TS 3.4.6.2, RCS Operational Leakage to Techical Requirements Manual ML20085L1161995-06-16016 June 1995 Proposed Tech Specs Re Increased Requirements for Core Reactivity Control Available from Borated Water Sources ML20084U5521995-06-0707 June 1995 Proposed Tech Specs,Consisting of Amend Request 95-02, Revising Footnote to SR 4.4.7 & Table 3.4-2 to Increase Temp Limit at Which Rc O Levels Determined by Sampling from 180 Degrees F to 250 Degrees F ML20084N9561995-05-31031 May 1995 Proposed Tech Specs Re Operation of Core W/Positive Moderator Temp Coefficient ML20082L5211995-04-16016 April 1995 Proposed Tech Specs,Revising TS 3.9.4 That Addresses Containment Bldg Penetrations to Allow Use of Alternate Containment Bldg Penetration Closure Methodologies for Postulated Accident Scenarios During Core Alterations ML20078E0491995-01-25025 January 1995 Proposed Tech Specs Re Changing of Surveillance Requirement 4.6.1.2.a from Specific Schedule for Performance of Containment ILRTs ML20078L5561994-11-23023 November 1994 Proposed Tech Specs Re Independent Technical Reviews ML20076G4701994-10-0707 October 1994 Proposed Tech Specs Re Administrative Control Requirements for Emergency & Security Plans,Per GL 93-07 ML20072G0371994-08-15015 August 1994 Proposed Bases of TS 3/4.1.1.3, Moderator Temp Coefficient & 3/4.3.3.2, Incore Detector Sys ML20059H6381994-01-14014 January 1994 Proposed Tech Specs,Changing Administrative Controls in Section 6.0 to Redefine Composition of Sorc,Create Station Qualified Reviewer Program,Delete Requirement to Perform Periodic Procedure Reviews & Revise TS 6.4.2.9 ML20058C3161993-11-23023 November 1993 Proposed Tech Specs,Allowing Operation of Core within Axial Flux Difference Band Expanded from Current Band in TSs & Improved Fuel Cycle Mgt Through Implementation of Core Design Enhancements ML20059C5441993-10-28028 October 1993 Proposed Tech Specs Implementing Thirteen Line Item Improvements Recommended by GL 93-05, Line-Item TS Improvements to Reduce SRs for Testing During Power Operation ML20056F7671993-08-26026 August 1993 Proposed Tech Specs Requesting Exercise of Enforcement Discretion from Requirement to Perform Channel Check on Narrow Range RWST low-low Level Transmitters ML20045C5571993-06-18018 June 1993 Proposed Tech Spec 6.2.3 Reflecting Title Change to Independent Technical Reviews & Deletion of Requirement to Maintain Five Person Organization,Iseg ML20045D5841993-06-18018 June 1993 Proposed Tech Specs Reducing Frequency of Surveillances, Required to Verify Integrity of CST Enclosure ML20127F8101993-01-13013 January 1993 Proposed TS 6.8.1.4 Re Submittal Frequency of Semiannual Radioactive Effluent Release Rept ML20117A8041992-11-25025 November 1992 Proposed Tech Specs for Incore Detector Sys ML20106E4181992-11-0303 November 1992 Proposed TS Section 6.2.2.f Deleting Requirement That Operations Manager Hold or Have Held Senior Reactor Operator License Prior to Assuming Operations Manager Position 1999-07-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210R8051999-08-10010 August 1999 Startup Test Rept for Cycle 7 ML20210K3631999-07-30030 July 1999 Marked-up & Revised TS Bases Page B 3/4 5-2 Re ECCS ML20196G3671999-06-23023 June 1999 Proposed Tech Specs Increasing AOT for Crac from 30 Days to 60 Days on One Time Basis for Each Train to Facilitate on- Line Implementation of Design Enhancements During Current Operating Cycle ML20198E7411998-12-16016 December 1998 Proposed Tech Specs Pages Re LAR-98-15,involving Relocation of TS 3/4.7.10 & Associated TS Table 3.7-3 to Technical Requirements Manual ML20198E7831998-12-16016 December 1998 Proposed Tech Specs Pages to LAR 98-09,re Editorial & Administrative Changes to TS ML20155J1821998-11-0404 November 1998 Proposed Tech Specs 4.5.2b.1,removing Prescriptive Requirements of Using Venting Process as Sole Means to Verify That ECCS Piping Is Full of Water ML20249B4181998-06-17017 June 1998 Proposed Tech Specs 3.7.6 Re Control Room Emergency Makeup Air & Filtration Subsystem ML20247R7021998-05-20020 May 1998 Proposed Tech Specs Re Rev of Refueling Water Storage Tank low-low Level Setpoint ML20217E8871998-04-22022 April 1998 Proposed Tech Specs Re Surveillance Intervals to Accommodate 24-month Fuel Cycle,Per GL 91-04 ML20217F9651998-04-21021 April 1998 Proposed Tech Specs Page 3/4 5-5 Re Venting of Operating Chemical Vol & Control Sys Centrifugal Charging Pump ML20216C5921998-04-0808 April 1998 Proposed Tech Specs Changing Surveillance Intervals to Accommodate 24-month Fuel Cycle Per GL 91-04 ML20217Q2981998-04-0303 April 1998 Proposed Tech Specs Pages Re LAR 98-02,proposing Changes to TS to Accommodate Fuel Cycles of Up to 24 Months ML20217M3771998-03-27027 March 1998 Proposed Tech Specs 3.7.6 Re Control Room Emergency Makeup Air & Filtration Subsystem ML20217F0961998-03-23023 March 1998 Proposed Tech Specs Pages,Incorporating New Spec 3.0.5 Administrative Controls,Currently Approved for Use in NUREG-1431 ML20217Q1031998-03-0505 March 1998 Proposed Tech Specs Incorporating Programmatic Controls for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20217N8211998-03-0202 March 1998 Proposed Tech Specs 4.5.2B.1,excluding Prescriptive Requirement to Vent Operating CVCS CCP Casing ML20217N7321998-03-0202 March 1998 Proposed Tech Specs Pages,Revising Frequency for Performance of Specific Surveillances & Deleting Requirements for Accelerated Testing When Number of Valid Test Failures Associated W/Edgs Is Met or Exceeded ML20217Q1111998-02-25025 February 1998 Rev 18 to Odcm ML20211F4401997-09-26026 September 1997 Cycle 6 Startup Test Rept for Seabrook Station,Unit 1 ML20211E9981997-09-26026 September 1997 Proposed Tech Specs 3.7.6,separating Requirements for CR HVAC Sys Re Operation of CR Emergency Makeup Air & Filtration Sys Subsystem & CR Air Conditioning Subsystem ML20195J1451997-07-23023 July 1997 Rev 15 to Seabrook Station Operating Experience Manual (Ssoe) ML20148G0011997-05-29029 May 1997 Proposed Tech Specs Replacing Term Zircaloy W/Terminology That Identifies NRC Approved Westinghouse Fuel Assembly Design Consisting of Assemblies W/Either ZIRLO or Zircaloy- 4 Fuel Cladding Matl ML20148K1251997-05-0707 May 1997 Rev 6 to Part I, Seabrook Station Pump & Valve IST Program Plan ML20135C3541997-02-26026 February 1997 Proposed Tech Specs,Providing Retyped Page of Proposed Changes Re Design Features Fuel Assembly Reconstitution ML20134Q3451997-02-18018 February 1997 Proposed Tech Specs 5.3.1 Re Fuel Assemblies ML20134L8681997-02-12012 February 1997 Proposed Tech Specs 6.0 Re Administrative Controls ML20138J3351996-12-19019 December 1996 Rev 16 to Offsite Dose Calculation Manual ML20129B8361996-10-17017 October 1996 Proposed Tech Specs,Consisting of Change Request 96-02, Proposing Changes That Involve Relocation of Four TS Re Instrumentation Requirements Contained in TS Section 3/4.3 & Relocation of Selected Requirements ML20129B7761996-10-16016 October 1996 Proposed Tech Specs,Consisting of Change Request 96-06, Proposing Four Changes Re EDG Requirements Contained in TS 3/4.8.1, AC Sources ML20113B2031996-06-20020 June 1996 Proposed Tech Specs Re Svc Water Cooling Tower Loop Electrical Supply ML20117K3111996-06-0404 June 1996 Proposed Tech Specs Re Containment Leakage Testing Modifying Implementing Performance Based Program at Seabrook Station IAW 10CFR50,App J,Option B & Reg Guide 1.163 Requirements ML20115J7481996-03-26026 March 1996 Procedure for Ultrasonic Examination of Centrifugally Cast Stainless Steel Piping Using Low Frequency SAFT-UT System ML20138J3621996-03-21021 March 1996 Process Control Program ML20100G8351996-02-16016 February 1996 Startup Test Rept,Cycle 5. W/ ML20094D5341995-10-30030 October 1995 Proposed Tech Spec 3.4.6.2, RCS Operational Leakage Pressure Isolation Valve Table ML20092M1071995-09-22022 September 1995 Proposed TS 3.3.2,Table 3.3-3, ESFAS Instrumentation, Correcting Action Ref for Functional Unit 8.b Re Automatic Switchover to Containment Sump/Rwst Level low-low ML20092K2201995-09-20020 September 1995 Proposed Tech Specs,Changing Plant TS Bases Section 3/4.9.1 for Refueling B Concentration ML20098A4721995-09-20020 September 1995 Proposed Tech Specs,Relocating Functional Unit 6.b, FW Isolation-Low RCS Tavg Coincident W/Rt from TS Requirements Manual Licensee Controlled Document ML20092F9171995-09-12012 September 1995 Proposed Tech Specs Bases Section Clarifying What Specifically Constitutes Operable Pressurizer Safety Valve in Mode 5 ML20092A6331995-09-0505 September 1995 Proposed Tech Specs,Revising Main Steam Safety Valve Setpoints & Max Allowable Power Range Neutron Flux High Setpoints W/Inoperable Main Steam Safety Valves ML20091S1601995-08-28028 August 1995 Proposed Tech Specs Re Positive Moderator Temp Coefficient ML20086R2111995-07-24024 July 1995 Proposed Tech Specs,Relocating Table 3.4-1, RCS PIVs from TS 3.4.6.2, RCS Operational Leakage to Techical Requirements Manual ML20085L1161995-06-16016 June 1995 Proposed Tech Specs Re Increased Requirements for Core Reactivity Control Available from Borated Water Sources ML20084U5521995-06-0707 June 1995 Proposed Tech Specs,Consisting of Amend Request 95-02, Revising Footnote to SR 4.4.7 & Table 3.4-2 to Increase Temp Limit at Which Rc O Levels Determined by Sampling from 180 Degrees F to 250 Degrees F ML20084N9561995-05-31031 May 1995 Proposed Tech Specs Re Operation of Core W/Positive Moderator Temp Coefficient ML20083K7351995-04-19019 April 1995 Rev 74 to Emergency Response Manual (Sser) ML20082L5211995-04-16016 April 1995 Proposed Tech Specs,Revising TS 3.9.4 That Addresses Containment Bldg Penetrations to Allow Use of Alternate Containment Bldg Penetration Closure Methodologies for Postulated Accident Scenarios During Core Alterations ML20081J6021995-03-22022 March 1995 Revised Table A.3-1, Radioactive Liquid Waste Sampling & Analysis Program, to ODCM ML20078E0491995-01-25025 January 1995 Proposed Tech Specs Re Changing of Surveillance Requirement 4.6.1.2.a from Specific Schedule for Performance of Containment ILRTs ML20079B2491994-12-27027 December 1994 Proposed Changes to Part a of ODCM 1999-08-10
[Table view] |
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DESIGN FEATURES l l
DESIGN PRESSURE AND TEMPERATURE l
5.2.2 The containment building is designed and shall be maintained for a !
maximum internal pressure of 52.0 psig and a temperature of 296 F 0
53 REACTOR CORE f FUEL ASSEMBLIES \ E. LD o f
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5.3.1 The reactor shall contain 193 fue assemblies. Each assembly shall i consist of a matrix of cylindricalCnrg lad fuel rods with an initial l composition of natural or slightly enri uranium dioxide (UO2 ) as fuel l material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod '
configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions. Reload fuel i shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 5.0 weight percent U-235.
CONTROL R00 ASSEMBLIES 5.3.2 The core shall contain 57 full-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber i material. The nominal values of absorber material shall be 80% silver, 15% '
indium, and 5% cadmium. All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
- a. In accordance with the Code requirements specified in Section 5.2 of the FSAR. with allowance for normal degradation pursuant to the .
applicable Surveillance Requirements.
- b. For a pressure of 2485 psig, and
- c. For a temperature of 650 F. except for the pressurizer which is 680 F.
VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12.255 cubic feet at a nominal Tg of 588.5 F.
5.5 (THIS SPECIFICATION NUMBER IS NOT USED) 9706050124 970529 PDR ADOCK 05000443 P PDR SEABROOK - UNIT 1 5-9 Amendment No. frl.
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III. RETYPE OF PROPOSED CHANGES 1
h Refer to the attached retype of the proposed changes to the Technical Specifications. The l attached retype reflects the currently issued version of the Technical Specifications. Pending Technical Specification. changes or Technical Specification changes issued subsequent to this j submittal are not reflected in the enclosed retype. The enclosed retype should be checked for >
continuity with Technical Specifications prior to issuance.
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DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The containment building is designed and shall be maintained for a maximum internal pressure of 52.0 psig and a temperature of 296 F.
5.3 REsCTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of cylindrical ZIRLO or Zircaloy-4 clad fuel rods with an l initial composition of natural or slightly enriched uranium dioxide (UO ) as fuel material. Limited substitutions of zirconium alloy or stainless sleel filler rods for fuel rods in accordance with NRC-a) proved applications of fuel rod configurations, may be used. Fuel assemblies s1all be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes )
and methods and shown by tests or analyses to comply with all fuel safety j design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions. Reload fuel shall be similar in physical design to the initial core loading and shall have <
a maximum enrichment of 5.0 weight percent U-235.
l CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 57 full-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber mater ial . The nominal values of absorber material shall be 80% silver. 15%
! indium, and 5% cadmium. All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM j i
l
! DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
- a. In accordance with the Code requirements specified in Section 5.2 l of the FSAR. with allowance for normal degradation pursuant to the t
applicable Surveillance Requirements,
- b. For a pressure of 2485 psig, and
- c. For a temperature of 650 F except for the pressurizer which is 680 F.
VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12.255 cubic feet at a nominal Tm of 588.5 F.
5.5 (THIS SPECIFICATION NUMBER IS NOT USED) l SEABROOK - UNIT 1 5-9 Amendment No. f4.
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- l IV. DETERMINATION OF SIGNIFICANT IIAZARDS FOR PROPOSED CII ANGES License Amendment Request (LAR) 97-02 proposes a change to reactor core fuel assembly j design feature requirements contained in Technical Specification 5.3.1, " Fuel Assemblies." The '
proposed change will allow the use of fuel assemblies containing ZIRLO or Zircaloy-4 as a fuel l
cladding material for fuel rods at Seabrook Station.
In accordance with 10 CFR 50.92, North Atlantic has reviewed the attached proposed change and l has concluded that it does not involve a significant hazards consideration (SHC). The basis for the conclusion that the proposed change does not involve a SHC is as follows:
- 1. The proposed change does not involve a significant increase in the probability or consequences ofan accidentpreviously evaluated.
The methodologies used in the accident analyses remain unchanged. The proposed change does not change or alter the design assumptions for the systems or components used to mitigate the consequences of an accident. Use of ZIRLO fuel cladding does not adversely affect fuel performance or impact nuclear design methodology. Therefore, accident analysis results are not significantly impacted.
The operating limits will not be changed and the analysis methods to demonstrate I operation within the limits will remain in accordance with NRC-approved ,
I methodologies. Other than the fuel design enhancements to the fuel assemblies cladding and grids, there are no physical changes to the plant associated with this Technical Specification change. A safety analysis will continue to be performed for each specific reload cycle to demonstrate compliance with all fuel safety design bases.
The 10 CFR 50.46 criteria are applied to the ZlRLO clad fuel rods. The use of these fuel assemblies will not result in a change to the reload design and safety analysis limits.
Since the original design criteria are met, the ZlRLO clad fuel rods will not be an initiator for any new accident. The clad material is similar in chemical composition and has similar, physical and mechanical properties as Zircaloy-4. Thus, the cladding integrity is maintained and the structural integrity of the fuel assembly is not affected.
ZlRLO cladding improves corrosion performance and dimensional stability. Since the dose predictions in the safety analyses are not sensitive to the fuel rod cladding material used, the radiological consequences of accidents previously evaluated in the safety analysis remain valid.
- 2. The proposed change does not create the possibility of a new or di((erent kind of accidentfrom anypreviously analy:ed.
The possibility for a new or different kind of accident from any accident previously evaluated is not created since the fuel assemblies containing ZlRLO clad fuel rods will satisfy the same design bases as that currently used for Zircaloy-4 clad fuel assemblies.
All design and performance criteria will continue to be met and no new single failure mechanisms have been defined. In addition, the use of ZlRLO fuel assemblies does not Page 6
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- j involve any alterations to plant equipment or procedures which would introduce any new i or unique operational mode or accident precursor. Therefore, the possibility for a new or i different kind of accident from any accident previously evaluated is not created.
- 3. The proposed change does not involve a sigmficant reduction in the margin ofsafety.
The margin of safety is not signiGcantly reduced since the ZlRLO clad fuel assemblies will not change the reload design and safety analysis limits. Their use will take into consideration the normal core operating conditions allowed for in the Technical SpeciGcations. Each specific cycle's reload core will continue to be speciGeally evaluated using NRC approved reload design methods and approved fuel rod design models. This will include consideration of the core physics analysis peaking factor and l core average linear heat rate effects. I Based on the above evaluation, North Atlantic concludes that the use of fuel assemblies
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containing ZlRLO clad fuel rods will not signiGeantly affect the performance or safety analyses ;
of the plant, and that the proposed change to the Technical SpeciGcations does not constitute a ;
signiGeant hazard.
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. 1 V. PROPOSED SCHEDULE FOR LICENSE AMENDMENT ISSUANCE AND EFFECTIVENESS North Atlantic requests that LAR 97-02 be reviewed on an exigent basis pursuant to the requirements of 10 CFR 50.91(a)(6) and that a license amendment be issued to support startup from the current refueling outage (i.e. MODE 2). North Atlantic is currently conducting Refueling Outage 5 with the current best estimate for achieving criticality (MODE 2) on June 16, 1997. It should be noted, however, that North Atlantic believes that there are multiple opportunities available to improve on this schedule which may result in MODE 2 being achieved earlier than June 16,1997. North Atlantic will keep the NRC apprised of schedule changes that may result in MODE 2 being achieved earlier than June 16,1997.
North Atlantic requests a license amendment having immediate effectiveness and implementation required within 60 days.
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VI. ENVIRONMENTAL IMPACT ASSESSMENT North Atlantic has reviewed the proposed license amendment against the criteria of 10CFR51.22 for environmental considerations. The proposed changes do not involve a significant hazards consideration, nor increase the types and amounts of effluent that may be released offsite, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, North Atlantic concludes that the proposed change meets the criteria delineated in 10CFR51.22(c)(9) for a categorical exclusion from the requirements for an Environmental Impact Statement.
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