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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
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MARKUP OF PROPOSED CHANGES Refer to the attached markup of the proposed changes to the Technical Specifications. The r attached markup reflects the currently issued revision of the Technical Specifications listed L
below. Pending Technical Specifications or Technical Specification changes issued subsequent -
l' to this submittal are not reflected in the enclosed markup.
The following Technical Specification is included in the attached markup:
! Technical Specification Iille Page(s) g
. TS 3.7.6 Control Room Emergency 3/4716-
- Makeup Air and Filtration Subsystem l
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Page 4 9804080008 980327 PDR ADOCK 05000443 P PDR
PLA... SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY MAKEUP AIR AND FILTRATION SUBSYSTEM LIMITI'GN CONDITION FOR OPERATION 3.7.6 Two independent Control Room Emergency Makeup Air and Filtration Subsystems shall be OPERABLE.
APPLICABILITY: All MODES ACTION:
MODES 1, 2, 3 and 4:
With one Control Room Emergency Makeup Air and Filtration Subsystem inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
MODES 5 and 6:
- a. With one Control Room Emergency Makeup Air and Filtration Subsystem inoperable, restore the inoperable system to OPERABLE status within 7 days or initiate and maintain operation of the remaining OPERABLE
_ontrol Room Emergency Makeup Air and Filtration Subsyster.; in the filtration / recirculation mode.
- b. With both Control Room Emergency Makeup Air and Filtration Subsystems inoperable, or with the OPERABLE Control Room Emergency Makeup Air and Filtration Subsystem, required to be in the filtration / recirculation mode by ACTION a., not capable of being powered by an OPERABLE emergency power _sourcet suspend all operations involving CORE ALTERATIONSJr posiitiv reactivi Ll - - - -
SURVEILLANCE REOUIREMENTS 4.7.6 Each Control Room Emergency Makeup Air and Filtratio1 Subsystem shall be demonstrated OPERABLE:
- a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room is maintained below the limiting equipment qualification temperature in the control room area,
- b. At least once per 31 days on a STAGGERED TEST BASIS by initiating,
, from the control room, flow through the HEPA filters and charcoal l
adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters operating; SEABROOK - UNIT 1 3/4 7-16
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. .bl. . REIYPE OF PROPOSED CHANGES .
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- Refer to the attached retype of the proposed ' changes to the Technical Specifications. The-attached retype reflects the currently issued version of the Technical Specifications. Pending l
Technical Specification changes or Technical Specification changes issued subsequent to this !
submittal are not reflected in the enclosed retype. The enclosed retype should be checked for j continuity with Technical Specifications prior to issucnce. i e
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PLANT SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY MA.KEUP AIR AND FILTRATION SUBSYSTit 1 -
LIMITING CONDITION FOR OPERATION l 3,7.6 Two independent Control Room Emergency Makeup Air and Filtration l Subsystems shall be OPERABLE.
APPLICABILITY: All MDDES ACTION:
MODES 1, 2, 3 and 4:
l With one Control Room Emergency Makeup Air and Filtration Subsystem inoperable, restore the ino)erable system to OPERABLE status within 7 days or be in at least HOT STAND 3Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
MODES 5 and 6:
- a. With one Lontrol Room Emergency Makeup Air and Filtration Subsystem inoperable, restore the inoperable system to OPERABLE status within 7 days or initiate and maintain operation of the remaining OPERABLE l Control Room Emergency Makeup Air and Filtration Subsystem in the filtration / recirculation mode.
- b. With both Control Room Emergency Makeu] Air and Filtration Subsystems inoperable, or with the OPERABLE Control Room Emergency Makeup Air and Filtration Subsystem. required to be in the l filtration / recirculation mode by ACTION a. not capable of being powered by an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS.
SURVEILLANCE REOUIREMENTS 4.7.6 Each Control Room Emergency Makeup Air and Filtration Subsystem shall be demonstrated OPERABLE:
- a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room is l maintained below the limiting equipment qualification temperature in the control room area.
t
- b. At least once per 31 days on a STAGGERED TEST BASIS by initiating, !
from the control room, flow through the HEPA filters and charcoal !
adsorbers and verifying that the system operates for at least 10 {
continuous hours with the heaters operating: '
l l l l SEABROOK - UNIT 1 3/4 7-16 Amendment ,
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i IV. DETERMINATION OF SIGNIFICANT IIAZARDS FOR PROPOSED CIIANGES 1 4
License Amendment Request (LAR) 08-07 proposes to modify the action requirements as presently contained in Technical Specification 3.7.6, " Control Room Emergency Makeup Air l and Filtration". Currently, the action for both trains of CREMAFS inoperable in Modes 5 and 6 i requires the suspension of all operations involving core alterations or positive reactivity changes.
The proposed change will modify the existing requirement by eliminating the restriction of suspending positive reactivity changes.
l In accordance with 10 CFR 50.92, North Atlantic has reviewed the attached proposed change and has concluded that it does not involve a significant hazards consideration (SHC). The basis for j the conclusion that the proposed change does not involve a SHC is as follows:
- 1. The prcposed change does not involve a signficant increase in the probability or consequences cfan accidentpreviously evaluated.
The proposed changes have no impact on the probability or consequences of an accident previously evaluated in the UFSAR. The control room ventilation systems are support ,
systems which have a role in the detection and mitigation of accidents but do not l contribute to the initiation of any accident previously eva!=ted. The removal of the i positive reactivity addition restriction in Mode 5 and 6 has no impact on the course of any accidents previously evaluated. There are no presently evaluated positive reactivity or boron dilution accidents that credit the CREMAFS to mitigate its consequences or provide radiological protection. The positive reactivity restriction is overly restrictive in that it does not allow cooldown below 200 F when Mode 5 is entered as a result of both I trains of CREMAFS being inoperable nor does it allow Reactor Coolant System I temperature to vary.
The restriction is also redundant to Technical Specification 3.1.1.2 " Reactivity Control Systems Shutdown Margin- Tm less than or equal to 200 F"in Mode 5 and Technical Specification 3.9.1 " Refueling Operations Boron Concentration" in Mode 6. Technical l Specification 3.1.1.2 action, with shutdown margin less than the limit specified in the l Core Operating Limits Report or with the Reactor Coolant System boron concentration less than 2000 ppm boron, requires immediate and continued boration until the restoration of the required shutdown margin or boron concentration. Similarly, Technical Specification 3.9.1 actions require suspension of core alterations or positive reactivity changes in addition to immediate and continued boration until the restoration of the required shutdown margin (K,n) or boron concentration while in Mode 6.
Sufficient shutdown margin ensures that (1) the reactor can be made suberitical from all operating conditions,(2) the reactivity transients associated with the postulated accident conditions are controllable within acceptable limits and (3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition. The above referenced reactivity control system specifications provide the necessary protection for postulated reactivity addition accident conditions. Therefore, modifying the Technical Specification action that requires the suspension of positive reactivity changes and core alterations with both trains of the CREMAFS inoperable Page 6
i does not involve a significant increase in the consequences of an accident previously evaluated.
- 2. The proposed change does not create the possibility of a new or different kind of accidentfrom anypreviously anal):ed.
The proposed change that removes the positive reactivity addition restriction in Mode 5 and 6 does not create the possibility of a new accident nor does it create the possibility of a difTerent kind of accident previously evaluated. There are no presently evaluated positive reactivity or boron dilution accidents that credit the CREMAFS to mitigate its consequences or provide radiological protection. The addition of positive reactivity during the above described situation is overly restrictive and furthermore redundant to Technical Specification 3.1.1.2 " Reactivity Control Systems Shutdown Margin- T.,, less than or equal to 200 F" in Mode 5 and Technical Specification 3.9.1 " Refueling Operations Boron Concentration" in Mode 6. The above referenced reactivity control system specifications provide the necessary protection for postulated reactivity addition accident conditions. Therefore, modifying the Technical Specification action that requires the suspension of positive reactivity changes and core alterations with both trains of the CREMAFS inoperable does not create the possibility of a new or different accident from any previously evalaated.
- 3. The proposed change does not involve a significant reduction in the margin ofsafety.
The changes being proposed do not revise equipment design or operation nor do they make changes to Technical Specification required safety limits or safety system settings, in addition, they do not alter the environmental conditions which are to be maintained in the control room during normal operation and following an accident and they do not revise the accident analyses. Therefore, the proposed changes do not involve a significant reduction in the margin of safety.
Based on the above evaluation, North Atlantic concludes that the activities associated with the proposed changes satisfy the no significant hazards consideration of 10CFR50.92(c) and, accordingly, a no significant hazards consideration finding isjustified.
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V. . PROPOSED SCHEDULE FOR LICENSE AMENDMENTISSUANCE AND '
EFFECTIVENESS North Atlantic requests NRC review of LAR 98-07 and issuance of a license amendment by September 30,'1998, having immediate effectiveness and implementation required within 60 days; i
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- VI. , hNVIRONMENTAL IMPACT ASSESSMENT
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- North Atlantic has reviewed the proposed license amendment against the criteria 'of 10CFR51.22 i
for environmental considerations.' . He proposed changes do not involve a significant hazards 1 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 - .l j
10CFR51.22(c)(9) for a categorical exclusion from the requirements for. an Environmental l
. Impact Statement.
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