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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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-- I h,' - Markun of Pronosed Chance See attached l markup of propo ed changes to Technical' Specifications.
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3 9210280181 921022-PDR ADOCK 05000443
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EMERGENCY CORE COOLING SYSTEMS
~
ECCS SUBSYSTEMS - T, GREATER THAN OR EQUAL TO 350*F SURVEltLANCE REQUIREMENTS l
4.5.2 (Cortinued)
- g. By verifying the correct position of each electrical and/or mechanical- '
position stop for the following ECCS throttle valves:
- 1) Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE, and
- 2) At least once per 18 months.
High Head SI System Intermediate Head SI System Valve Number Valve Number SI-V-143 SI-V-80 SI-V-147 SI-V-85 SI-V-151 SI-V-104 L
SI-V-155 SI-V-109 SI-V-117 SI-V-121 SI-V-125 SI-V-129'
- h. By performing a flow balance test, curing shutdown, following com-pletion of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying that:
- 1) For centrifugal charging pump lines, with a single pump running:
a)_ The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 337 gpm, and b) The total pump flow rate is less than or equal to 550 gpm.
- 2) For Safety Injection pump lines, with a single pump running:
a) The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 445 gpm, and b) The total pump flow rate is less than or equal to 660 gpm.
- 3) For RHR pump lines, with a single pump running, the sum of the injection line flow rates is greater than or equal to M g %
3967 /
SEABROOK - UNIT 1 3/4 5-7 .
III,. Retvoc of Proposed Chance See attached retype of proposed changes to-Technical Specifications,- _ The attached A:
retype reflects the -currently issued version of Technical Specifications. Pending -
Technical Specific'ation changes or.'Iechnical Specification changesisisued subsequent to-this submittal'are not reflected in _the enclosed retype. The enclosed retype should' be checked for continuityLwith Technical Specifications prior to issuance, Revision bars are provided in the right hand margin to designate a change in the text.:
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r ECCS SUBSYSTEMS - T., GREATER THAN OR E0 VAL TO 350*F SURVElllANCE REOUIREMENTS 4.5.2 (Continued)
- g. By verifying the correct position of each electrical and/or mechanical position stop for the following ECCS throttle valves:
- 1) Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE, and
- 2) At least once per 18 months.
Hiah Head 51 System Intermediate Head S1 System Valve Number Valve Number SI-V-143 SI-V-80 SI-V-147 SI-V-85 Si-V-151 SI-V-104 3 SI-V-155 SI-V-103 SI-V-117
.) SI-V-121 SI-V-125 SI-V-129
- h. By performing a flow balance test, during shutdown, following completion of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying that:
- 1) For centrifugal charging pump lines, with a single pump running: _
a) The sum of the injection line flow rates, excluoing the highest #10w rate, is greater than or equal to 337 gpm, and b) The total pump flow rate is less than or equal to 550 gpm.
- 2) For Safety Injection pump lines, with a single pump running:
a) The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 445 gpm, and b) The total pump flow rate is less than or equal to 660 gpm.
- 3) For RHR pump lines, with a single pump running, the sum of the injection line flow rates is greater than or equal to 3869 l gpm.
SEABROOK - UNIT 1 3/4 5-7 Arnendment No.
- . - - - . - . - - . ~. - - - .- .- - . - - - - - ~ - .- . - - ~
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4 ivc Safety Evaluation of I.icense Amendment Reouest 9212 Proonsed Chance
- During a routine review of the Station procedure for cold shutdown testing of the Residual llent Removal (RilR) System North Atlantie dircovered that the acceptance value specified in the procedure for the' sum of_ the injection line flow rates with~ a single pump- running differed from the value specified in T-chnical Specification Surveillt. ace Requirement 4.5.2h.3- At North _ Atlantic's request Westinghouse reviewed the. value in Surveillance Requirement 4.5.2h.3 and determined that the current value:
of 2828 gpm is the appropriate value for flow through three of the four RHR injection lines, and that the correct value for flow through all four of the injection lines-is 3868.4 gpm.
The proposed . Technical Specification change _ is consistent with the design basis Emergency Core Cooling System (ECCS) analysis performed by Westinghouse. The Seabrook ECCS analysis is based on the calculated flow rate down three of the four Ri!R injection lines. The fourth line is assumed to spill to containment. Thus, the flow rate in three lines must be sufficient to deliver the required value of RilR flow-to the core. The calculated value of flow to the core used in this analysis is 2828.4 gpm. The calculated value used in the analysis for the total flow delivered to the core down four injection lines is 3868.4 - gpm. The ECCS analysis performed by Westinghouse for North Atlantic is available for review at WestinF ouse.h The purpose of Technical Specification 3/4.5.2 Surveillance Requirements is to casure that each of the ECCS components meets the assumptions used in the safety analysis.
In the case of Technical Specification Surveillance Requirernent 4.5.2h.3 the purpose of verifying that the sum of the injection line flow rates meets or exceeds a minimum value _is to ensure that an ECCS flow to all injection points at least equals the value .
assumed'in the ECCS analyses.
The existing acceptance value in Technical Specifications for the sum of the injection line flow rates for the-Residual Heat Removal (RHR) pump lines _with a single pump running. is 2828 gpm. Since the intent of Technical Specification _ Surveillance Requirement 4.5.2h.3 is to verify the total flow through all four RilR pump _ injection-lines, an acceptance value of at least 3686.4 gpm is required to ensure that the minimum RHR flow will be provided to the core during- a design basis accident.
Failure to provide this minimum flow could result in an insufficient removal of decay heat and possible core damage.
A review of UFSAR sections 5.4.1 and 6.3 verifies that the proposed change does not alter the design, function, or operation of the-RHR system. This proposed change does not effect any existing accident analyses, and it does not introduce the possibility of any accidents or malfunctiot.s not already analyzed. Since the: proposed change is increasing the current acceptance value for injection : line flow to the more
- conservative value. used in the accident analysis,- it does not decrease the- margin of safety . as defined in ~ the Technical Specification . bases - but preserves the margin originally assumed.
While a lower acceptance value for the sum of the RHR injection line flow rates is currently in Technical Specification Surveillance Requirement 4.5.2h.3, the system flow rate was _ verified to be greater - than _3868.4 gpm during titial testing _
(Westinghouse Low Head Safety' Injection Test Procedure TAC 02). North Atlantic has verified that the RilR- system was always capable of performing-its ECCS design function as reported in LER 92-002-00.
5 i
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O 4 9
V. Determination of Sinnificant lla7ards for I.icense Amendment Reouest 92-12 Proposed Chance =
(1) The proposed ~ change does not involve a significant increase in the probability or consequences of an accident previously evaluated, The proposed change to Technical Specification Surveillance Requirement,4.5.2b.3 -
revises the acceptance value of the sum of the injection line flow rates with a ringle pump running to conform with the value used in the Seabrook Station Emergency Core Cooling System (ECCS) analysis performed by Westinghouse. This revised acceptance
- value is more conservative than the current Technical Specification value.
The Residual Heat Removal (R11R) System provides the low head ECCS flow necessary in the event of a Loss of Coolant Accident (LOCA). ECCS flow must be sufficient to. remove the stored heat and fission product decay heat from the reactor core to prevent fuel damage that might impair effective cooling of the eore.
The Seabrook Station ECCS analysis is based on the calculated flow rate down three of the four RilR injection lines since the fourth line is assumed to : Spill to containment. The calculated flowrate down three of the four injection lines'in this analysis is 2828.4 gpm. The calculated total pump flow rate down all four injection
, lines _is 3868.4 gpm. Since the actual values used in the analysis for the total _ flow rate down three and four injection lines are 2712 gpm and 3828 gpm, respectively, the proposed value of 3869 gpm, which includes an allowance of 5% for pump-degradation, is conservative.
Technical Specification Surveillance Requirement 4.5.2h.3 is performed as part of.a ~
flow balance test during shutdown when modifications to the ECCS subsystems have been made that alter the subsystem flow characteristics. This surveillance requirement verifies that after the modification the total ECCS flow to the reactor core is equal to or greater than the flow assumed in the ECCS analysis.
The proposed change to Technical Specification Surveillance Requirement 4.5.2h.3 does not alter the design of the RilR system or any other plant system. The RilR system design parameters and operation are not changed, The proposed change is necessary to correct an error in the Technical Specifications whereby the acceptance value for the flow rate through three injection lines was inadvertently used instead of the correct flow rate value through four injection lines. In addition, the revised acceptance value in the proposed change is more conservative than the existing valuci -i Therefore, this proposed change does not increase the probabili_ty of an accident previously evaluated nor will it increase the consequences of any accident.
(2) The proposed change does not create the possibility of a new or different kind of .
accident from aay accident previously evaluated.
The proposed change to Technical Specification Surveillance Requirement 4.5.2h.3 does not affect the design, function or operation of the RilR system. As a subsystem.of the Seabrook Station ECCS, the RilR System will continue to be capable of injecting low pressure cooling water in the event of a LOCA to remove stored and fission product decay heat,and maintain effectir core cooling. The acceptance value for the sum of the RilR injection line flow . tes with a single pump running is more ,
I 6
4 conservative than the value being replaced and meets the value used in the design
-basis Seabrook Station ECCS analysis.
There are no new failure modes introduced by'this. proposed change. its intent is to correct an error in the existing Technical Specifications whereby the acceptance value for the sum of the flow rates in three-lujection lines was used .instead of the value.
for the sum of four injection lines. Therefore, the possibility of a new or d_ifferent kind of accident than those already evaluated is not created by this proposed change.
(3) The proposed change does not result in a significant reduction in -the margin of ,
safety.
The Technical Specification Ilases state that the purpose of the surveillance requirement for flow b*ilance testing following modifications to ECCS subsystems that might alter the subsystem flow characteristics is to verify that proper ECOS flow will be maintained in the event of a LOCA. Proper ECCS flow is defined by the design basis ECCS analysis. The Scabrook Station ECCS analysis used a calculated flow rate value for the sum of the four injection line flow rates of 3868.4 gpm. The acceptance value for the sum of the four injection line flow rates which is currently in Technical Specification Surveillance Requirement 4.5.2h.3 is less than 3868.4 gpm. The proposed change revises the acceptance value in the surveillance requirement to 3869 gpm.
Since the proposed change is resising the acceptance value to a more conservative value which is bounded by the design basis ECCS analysis, the change will not reduce the margin of safety.
7
VI. IInvironmental Impact Assessment North Atlantic has reviewed the proposed license amendment = against the criteriu of.-
10CFR$1.22 for environmental considerations,. The proposed changes do not involve a .,ignificant hazards consideration, nor increase the types a nd amounts _of effluents' (hat ' may - be released offsite, not significantly increase -ladividual . or -- cumulative
. occupational radiation c?posures. 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, i
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