|
---|
Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20196G3531999-06-23023 June 1999 LAR 99-19 for License NPF-86,increasing AOT for Cracs 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 ML20207J6201999-03-15015 March 1999 Application for Amends to Licenses NPF-49 & NPF-86, Transferring Control of Licenses to Reflect Change in Upstream Economic Ownership of Parent Company of Nep,Vols I & Ii.Pages 48,49 & Annual Rept 1996 Pages 2 & 3 Omitted ML20207G9261999-03-0505 March 1999 Suppl Application for Transfer of License NPF-86,requesting Consent for Transfer of Montaup Electric Co Interest in OL for Seabrook Station to Little Bay Power Corp ML20198E7291998-12-16016 December 1998 Application for Amend to License NPF-86.Amend Involves Relocation of TS 3/4.7.10 & Associated TS Table 3.7-3 to Technical Requirements Manual ML20198E7781998-12-16016 December 1998 License Amend Request 98-09 to License NPF-86,either Revising Refs & Statements That Are Inaccurate or Providing Relief from Administrative Controls Which Provide Insignificant Safety Benefit ML20155J1671998-11-0404 November 1998 LAR 98-17 to License NPF-86,revising TS SR 4.5.2b.1 to Remove Prescriptive Requirements of Using Venting Process as Sole Means to Verify That ECCS Piping Is Full of Water ML20154F9971998-09-29029 September 1998 Application 98-16 for Amend to License NPF-86,reflecting Removal of Montaup Electric Co & Addition of Little Bay Power Corp ML20249B4161998-06-17017 June 1998 Revised LAR 98-07,reflecting Proposed Changes in LAR 98-07 W/Recently Issued License Amend 56 Which Split TS 3/4.7.6 Into Separate TSs,3/4.7.6.1 & 3/4.7.6.2 ML20247R6821998-05-20020 May 1998 LAR 97-07 to License NPF-86,revising Refueling Water Storage Tank low-low Level Setpoint ML20217E8611998-04-22022 April 1998 LAR 98-04 to License NPF-86,changing TS Surveillance Intervals to Accommodate 24 Month Fuel Cycle,Per GL 91-04 ML20216C5751998-04-0808 April 1998 Application 98-03 for Amend to License NPF-86,changing TS Surveillance Intervals to Accommodate 24-month Fuel Cycle, Per GL 91-04 ML20217Q2761998-04-0303 April 1998 Application for Amend to License NPF-86,LAR 98-02,proposing Changes to TS to Accomodate Fuel Cycles of Up to 24 Months, Per GL 91-04, Changes in TS Surveillance Intervals to Accommodate 24-Month Fuel Cycle ML20217M3671998-03-27027 March 1998 LAR 98-07 to License NPF-86,modifying Tech Specs 3.7.6, Control Room Emergency Makeup Air & Filtration Subsystem ML20217F0931998-03-23023 March 1998 Application for Amend to License NPF-86,proposing Administrative Change to TS to Incorporate Administrative Controls of New Specification 3.0.5,currently Approved for Use in NUREG-1431 ML20217Q0971998-03-0505 March 1998 Application for Amend to License NPF-86,incorporating Programmatic Controls in TS for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20217N7231998-03-0202 March 1998 Application for Amend to License NPF-86,changing TS to Revise Frequency for Performance of Specific Surveillances & Delete Requirements for Accelerated Testing When Number of Valid Test Failures Associated W/Edgs Is Met or Exceeded ML20217N8151998-03-0202 March 1998 Application for Amend to License NPF-86,changing TS to Exclude Prescriptive Requirement to Vent Operating CVCS CCP Casing ML20211E9761997-09-26026 September 1997 Application for Amend (LAR 97-05),changing TS 3.7.6 by Separating Requirements for Control Room HVAC Sys Re Operation of Control Room Emergency Makeup Air & Filtration Sys Subsystem & Control Room Air Conditioning Subsys ML20141B3521997-06-19019 June 1997 License Amend Request 97-03 to License,Revising TS Administrative Control 6.8.1.6.b to Include Ref to NRC Approved W Topical Rept WCAP-12610-P-A, Vantage + Fuel Assembly Ref Core Rept ML20148F9971997-05-29029 May 1997 License Amend Request 97-02,to License NPF-86,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 ML20134Q3291997-02-18018 February 1997 Application for Amend to License NPF-86,changing Reactor Core Fuel Assembly Design Features Requirements Contained in Tech Specs 5.3.1, Fuel Assemblies ML20134L8591997-02-12012 February 1997 Application for Amend to License NPF-86,requesting Rev to TS Section 6.0 Re Administrative Controls ML20129B8211996-10-17017 October 1996 Application for Amend to License NPF-86,consisting of Change Request 96-02,proposing Changes That Involve Relocation of Four TS Re Instrumentation Requirements Contained in TS Section 3/4.3 ML20129B7631996-10-16016 October 1996 Application for Amend to License NPF-86,consisting of Change Request 96-06,proposing Four Changes Re EDG Requirements Contained in TS 3/4.8.1, AC Sources ML20113B1911996-06-20020 June 1996 License Amend Request 96-17 to License NPF-86,increasing Allowed Outage Time for Inoperable Svc Water Cooling Tower Loop Electrical Supply to Be Equivalent to Allowed Outage Time for Inoperable Svc Water Cooling Tower Loop ML20117K3051996-06-0404 June 1996 Application for Amend to License NPF-86,implementing Performance Based Containment Leak Rate Testing Program at Seabrook Station by Changing Tss.Request Submitted IAW 10CFR50,App J,Option B & Reg Guide 1.163 Requirements ML20092M1011995-09-22022 September 1995 Application for Amend to License NPF-86,consisting of LAR 95-07 Re Automatic Switchover to Containment Sump/Rwst Level low-low ML20098A4711995-09-20020 September 1995 Application for Amend to License NPF-86,relocating Functional Unit 6.b, FW Isolation- Low RCS T Avg Coincident W/Rt from TS 3.3.2 to Plant TS Requirements Manual Licensee Controlled Document ML20092K2091995-09-20020 September 1995 Application for Amend to License NPF-86,changing TS 3/4.9.1 Re Refueling Boron Concentration (Ref NUREG-1431) ML20092F9141995-09-12012 September 1995 Application for Amend to License NPF-86,TS Bases for RCS Safety Valves Bases Section 3/4.4.2 Were Made to Clarify What Specifically Constitutes Operable Pressurizer Safety Valve in Mode 5 ML20092A6251995-09-0505 September 1995 Application for Amend to License NPF-86,revising Main Steam Safety Valve Setpoints & Max Allowable Power Range Neutron Flux High Setpoints W/Inoperable Main Steam Safety Valves ML20086R2091995-07-24024 July 1995 LAR 95-03 to License NPF-86,relocating Table 3.4-1, RCS PIVs from TS 3.4.6.2, RCS Operational Leakage to Technical Requirements Manual ML20085L1101995-06-16016 June 1995 Application for Amend to License NPF-86.Amend Would Increase Requirements for Core Reactivity Control Available from Borated Water Sources ML20084U5391995-06-0707 June 1995 Application for Amend to License NPF-86,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 ML20084N9501995-05-30030 May 1995 Application for Amend to License NPF-86.Amend Will Allow Operation of Core W/Positive Moderator Temp Coefficient ML20082L5001995-04-17017 April 1995 Application for Amend to License NPF-86,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 ML20078E0351995-01-25025 January 1995 Application for Amend to License NPF-86,to Revise Surveillance Requirement 4.6.1.2.a from Specific Schedule for Performance of Containment ILRTs ML20076G2691994-10-0707 October 1994 License Amend Request 94-03 to License NPF-86,modifying TS Administrative Control Requirements for Emergency & Security Plans,Per GL 93-07 ML20059H6321994-01-14014 January 1994 LAR 93-20 to License NPF-86,changing Administrative Controls in TS 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 ML20058C2991993-11-23023 November 1993 LAR 93-18 to License NPF-86,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 ML20059C5191993-10-28028 October 1993 LAR 93-14 to License NPF-86,changing TS to Implement 13 Line Item Improvements Recommended by GL 93-05, Line-Item TS Improvements to Reduce SRs for Testing During Power Operation ML20057F2981993-10-0404 October 1993 Application for Amend to License NPF-86,proposing Changes to TS Correcting Inconsistency within TS by Deleting Requirement to Verify EDG Speed ML20056F7641993-08-26026 August 1993 LAR Requesting Exercise of Enforcement Discretion from Requirement to Perform Channel Check on Narrow Range RWST low-low Level Transmitters ML20045C5541993-06-18018 June 1993 LAR 93-08 to License NPF-86,changing Title of TS 6.2.3 to Independent Technical Reviews & Deleting Requirement to Maintain Five Person Organization,Iseg ML20045D5831993-06-18018 June 1993 LAR Proposing Changes to Seabrook Station Tech Specs to Reduce Frequency of Surveillances Which Are Required to Verify Integrity of CST Enclosure ML20036A4491993-05-0707 May 1993 License Amend Request 93-05 to License NPF-86,changing TS to Permit Mod of Containment Structure Air Purge & Heating Subsystem to Provide More Reliable Means of Containment Isolation for Two Containment Penetrations ML20035H2191993-04-23023 April 1993 License Amend Request 93-04 to License NPF-86,changing TS to Increase Surveillance Test Interval,Allowed Outage Time & Channel Bypass Time for Reactor Trip Sys & ESFAS ML20035E2541993-04-0808 April 1993 License Amend Request 93-03 to License NPF-86,correcting Safety Limit Curves of TS Figure 2.1-1, Reactor Core Safety Limit - Four Loops in Operation ML20035E2621993-04-0707 April 1993 License Amend Request 93-02 to License NPF-86,changing TS to Redefine Requirements for Operable Svc Water Sys & to Consolidate Svc Water Requirements for UHS ML20034F5261993-02-26026 February 1993 License Amend Request 93-01 to License NPF-86,changing TS 3/4.7.3 to Redefine Requirements for Operable Primary Component Cooling Water Sys to Enhance Plant Operations & Outage Flexibility 1999-06-23
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217C8411999-10-0505 October 1999 Amend 64 to License NPF-86,revising TSs 3.7.6.1 & 3.7.6.2 to Delete Restriction to Suspend All Operations Involving Positive Reactivity Changes During Plant Conditions Specified ML20212L1071999-10-0101 October 1999 Amend 63 to License NPF-86,relocating TS 3/4.7.10, Area Temperature Monitoring, & Associsted TS Table 3.7-3.to Technical Requirements Manual ML20212D0761999-09-17017 September 1999 Amend 62 to License NPF-86,revising TS 3.7.6.2 to Increase AOT for Control Room Air Conditioning Subsystem from 30 to 60 Days to Allow Adequate Time to Replace Portions of Existing System During Current Operating Cycle ML20210Q1631999-08-12012 August 1999 Amend 61 to License NPF-86,revising TS SR 4.5.2b.1 to Delete Prescribed Method of Venting ECCS Which Would Allow Alternate Method to Verify That ECCS Piping Will Be Full of Water ML20196G3531999-06-23023 June 1999 LAR 99-19 for License NPF-86,increasing AOT for Cracs 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 ML20207J6201999-03-15015 March 1999 Application for Amends to Licenses NPF-49 & NPF-86, Transferring Control of Licenses to Reflect Change in Upstream Economic Ownership of Parent Company of Nep,Vols I & Ii.Pages 48,49 & Annual Rept 1996 Pages 2 & 3 Omitted ML20204E3391999-03-12012 March 1999 Amend 60 to License NPF-86,revising TS Table 3.3-4 to Depict Change to Refueling Water Storage Tank low-low Level Setpoint ML20207G9261999-03-0505 March 1999 Suppl Application for Transfer of License NPF-86,requesting Consent for Transfer of Montaup Electric Co Interest in OL for Seabrook Station to Little Bay Power Corp ML20198E7781998-12-16016 December 1998 License Amend Request 98-09 to License NPF-86,either Revising Refs & Statements That Are Inaccurate or Providing Relief from Administrative Controls Which Provide Insignificant Safety Benefit ML20198E7291998-12-16016 December 1998 Application for Amend to License NPF-86.Amend Involves Relocation of TS 3/4.7.10 & Associated TS Table 3.7-3 to Technical Requirements Manual ML20155J1671998-11-0404 November 1998 LAR 98-17 to License NPF-86,revising TS SR 4.5.2b.1 to Remove Prescriptive Requirements of Using Venting Process as Sole Means to Verify That ECCS Piping Is Full of Water ML20154F9971998-09-29029 September 1998 Application 98-16 for Amend to License NPF-86,reflecting Removal of Montaup Electric Co & Addition of Little Bay Power Corp ML20249C6401998-06-24024 June 1998 Amend 58 to License NPF-86,revises TS 4.5.2.b.1 for ECCS Subsystems to Delete Requirements to Vent Operating Chemical Volume & Control Sys Centrifugal Charging Pump Casing ML20249B4161998-06-17017 June 1998 Revised LAR 98-07,reflecting Proposed Changes in LAR 98-07 W/Recently Issued License Amend 56 Which Split TS 3/4.7.6 Into Separate TSs,3/4.7.6.1 & 3/4.7.6.2 ML20247R6821998-05-20020 May 1998 LAR 97-07 to License NPF-86,revising Refueling Water Storage Tank low-low Level Setpoint ML20217E8611998-04-22022 April 1998 LAR 98-04 to License NPF-86,changing TS Surveillance Intervals to Accommodate 24 Month Fuel Cycle,Per GL 91-04 ML20216C7861998-04-0909 April 1998 Amend 56 to License NPF-86,revising App a TSs Re Requirements for Control Room Subsystems ML20216C5751998-04-0808 April 1998 Application 98-03 for Amend to License NPF-86,changing TS Surveillance Intervals to Accommodate 24-month Fuel Cycle, Per GL 91-04 ML20217Q2761998-04-0303 April 1998 Application for Amend to License NPF-86,LAR 98-02,proposing Changes to TS to Accomodate Fuel Cycles of Up to 24 Months, Per GL 91-04, Changes in TS Surveillance Intervals to Accommodate 24-Month Fuel Cycle ML20217M3671998-03-27027 March 1998 LAR 98-07 to License NPF-86,modifying Tech Specs 3.7.6, Control Room Emergency Makeup Air & Filtration Subsystem ML20236R9301998-03-26026 March 1998 Amend 55 to License NPF-86,modifing TS Sections 6.0, Administrative Control, to Reflect Recent Organizational Changes & Changes to Approval Title for Section Qualified Reviewer Program & Correcting Incorrect Ref in TS 6.4.3.9.b ML20217F0931998-03-23023 March 1998 Application for Amend to License NPF-86,proposing Administrative Change to TS to Incorporate Administrative Controls of New Specification 3.0.5,currently Approved for Use in NUREG-1431 ML20216H8341998-03-17017 March 1998 Amend 54 to License NPF-86,revising App a TSs Relating to Requirements for AC Power Sources,Changing Certain Requirements Related to EDG Stated in TS 3/4.8.1, AC Sources ML20217Q0971998-03-0505 March 1998 Application for Amend to License NPF-86,incorporating Programmatic Controls in TS for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20217N7231998-03-0202 March 1998 Application for Amend to License NPF-86,changing TS to Revise Frequency for Performance of Specific Surveillances & Delete Requirements for Accelerated Testing When Number of Valid Test Failures Associated W/Edgs Is Met or Exceeded ML20217N8151998-03-0202 March 1998 Application for Amend to License NPF-86,changing TS to Exclude Prescriptive Requirement to Vent Operating CVCS CCP Casing ML20211E9761997-09-26026 September 1997 Application for Amend (LAR 97-05),changing TS 3.7.6 by Separating Requirements for Control Room HVAC Sys Re Operation of Control Room Emergency Makeup Air & Filtration Sys Subsystem & Control Room Air Conditioning Subsys ML20141D5901997-06-24024 June 1997 Amend 53 to License NPF-86,modifying TS to Identify Fuel Assemblies Design Features ML20141D1391997-06-24024 June 1997 Amend 52 to License NPF-86,modifying TS 6.8.1.6.b to Include Reference to NRC W Topical Rept WCAP-12610-P-A, Vantage+Fuel Assembly Reference Core Rept, Dtd April 1995 ML20141B3521997-06-19019 June 1997 License Amend Request 97-03 to License,Revising TS Administrative Control 6.8.1.6.b to Include Ref to NRC Approved W Topical Rept WCAP-12610-P-A, Vantage + Fuel Assembly Ref Core Rept ML20148F9971997-05-29029 May 1997 License Amend Request 97-02,to License NPF-86,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 ML20141B9781997-05-13013 May 1997 Amend 51 to License NPF-86,revising TSs Re Reactor Core Fuel Assembly Design Features Requirements Contained in TS 5.3.1, Fuel Assemblies ML20135F9261997-03-12012 March 1997 Amend 50 to License NPF-86 Revising App a TSs Related to in-core Detector Sys,Seismic Instrumentation,Meteorological Instrumentation & Turbine Overspeed Protection ML20135C1561997-02-24024 February 1997 Amend 49 to License NPF-86,revising Plant App a TSs 1.7, Containment Integrity, 3/4.6.1, Primary Containment, & 3/4.6.5, Containment Enclosure Bldg, to Incorporate Provisions of Option B to 10CFR50,App J ML20134Q3291997-02-18018 February 1997 Application for Amend to License NPF-86,changing Reactor Core Fuel Assembly Design Features Requirements Contained in Tech Specs 5.3.1, Fuel Assemblies ML20134L8591997-02-12012 February 1997 Application for Amend to License NPF-86,requesting Rev to TS Section 6.0 Re Administrative Controls ML20129B8211996-10-17017 October 1996 Application for Amend to License NPF-86,consisting of Change Request 96-02,proposing Changes That Involve Relocation of Four TS Re Instrumentation Requirements Contained in TS Section 3/4.3 ML20129B7631996-10-16016 October 1996 Application for Amend to License NPF-86,consisting of Change Request 96-06,proposing Four Changes Re EDG Requirements Contained in TS 3/4.8.1, AC Sources ML20117F8621996-08-30030 August 1996 Amend 48 to License NPF-86,revising TS 3.8.3.1,action A,To Increase from 8 H to 7 Days,Allowable Time That 480 Volt Bus E64 May Be Less than Fully Energized ML20113B1911996-06-20020 June 1996 License Amend Request 96-17 to License NPF-86,increasing Allowed Outage Time for Inoperable Svc Water Cooling Tower Loop Electrical Supply to Be Equivalent to Allowed Outage Time for Inoperable Svc Water Cooling Tower Loop ML20117K3051996-06-0404 June 1996 Application for Amend to License NPF-86,implementing Performance Based Containment Leak Rate Testing Program at Seabrook Station by Changing Tss.Request Submitted IAW 10CFR50,App J,Option B & Reg Guide 1.163 Requirements ML20108D9981996-05-0707 May 1996 Amend 47 to License NPF-86,revising App a TS 3.3.2, Engineered Safety Features Actuation Sys Instrumentation ML20095L0681995-12-21021 December 1995 Corrected Page 3/4 4-25 & 26 W/Overleaf for Completeness of Amend 46 to License NPF-86.Error Involved TS Page W/O Page & Amend Number ML20095L0641995-12-21021 December 1995 Corrected Pages 3/4 3-33,3/4 3-26 & 3/4 3-19 & 20 W/Overleafs for Completeness of Amends 45 & 46 to License NPF-86 ML20094R1741995-11-29029 November 1995 Amend 45 to License NPF-86.Amend Revises App a TS Re Relocation of Functional Unit 6.b, Feedwater Isolation - Low RCS Tavg Coincident with a Reactor Trip from TS 3.3.2 to Technical Requirements Manual ML20094P9741995-11-28028 November 1995 Amend 44 to License 44,revise App a TS Re RCS Leakage & Deletes Table 3.4-1 from TS Section 3.4.6.2 & Ref Table 3.4-1 from Limiting Condition for Operation 3.4.6.2 F ML20094F4371995-11-0202 November 1995 Amend 43 to License NPF-86,modifying App a TSs for Turbine Cycle Safety Valves ML20092M1011995-09-22022 September 1995 Application for Amend to License NPF-86,consisting of LAR 95-07 Re Automatic Switchover to Containment Sump/Rwst Level low-low ML20098A4711995-09-20020 September 1995 Application for Amend to License NPF-86,relocating Functional Unit 6.b, FW Isolation- Low RCS T Avg Coincident W/Rt from TS 3.3.2 to Plant TS Requirements Manual Licensee Controlled Document ML20092K2091995-09-20020 September 1995 Application for Amend to License NPF-86,changing TS 3/4.9.1 Re Refueling Boron Concentration (Ref NUREG-1431) 1999-09-17
[Table view] |
Text
--
"A " " ""' "
M North
==inni= Aflanfic Energy Service Corporation Facility. Operating License NPF-86 Docket No. 50-443 License Amendment Request No. 93-02 Service Water System / Ultimate Heat Sink.
OPERABILITY _ Requirements This License Amendment Request is submitted by North Atlantic Energy Service i
Corporation pursuant to 10CFR50.90. The following information is enclosed in support of this License Amendment Request:
1 Section I Introduction and Description of Proposed Changes i
.Section II Markup of Proposed Changes
. Section 111 Retype of Proposed ChangesSection IV Safety Evaluation of Proposed Changes l
.Section V Determination of Significant Hazards for Proposed Changes i
j
.Section VI Proposed Schedule for License Amendment issuance and Effectiveness Section Vil EnvironmentalImpact Assessment d
Section Vill Other Supporting information j
Sworn and Subscribed to before megs.
1 7/l day of MM<
,1993 i
[g p 4/& 8-I 1dO Ted C.,efgenbaum F
l 4lotary Public Senior Vice Presider
- ard Chief Nuclear Officer 9304150096 930407 r
~
yDR ADOCK 05000443 1,, _, a 2 c..
a _
c..rs PDR
E I.
Introduction and Descrintion of Pronosed Chances, A.
Introduction The purpose of the proposed Technical Specification change is to combine Technical j
Specification 3/4.7.5, Ultimate Heat Sink, with Technical Specification 3/4.7.4, Service i
Water System, and redefine the requirements for an OPERABLE Service Water i
System. The design of the Seabrook Station Service Water System employs two j
redundant loops. Each loop is equipped with two full capacity service water pumps, which use the Atlantic Ocean as the ultimate heat sink, and a cooling tower service i
water pump which uses the atmosphere as the ultimate heat sink. Seabrook Station's Technical Specifications currently require two OPERABLE Service Water loops with each loop having three OPERABLE pumps (two service water pumps and one cooling
+
tower service water pump) when in Modes 1, 2, 3, and 4 This - requirement unnecessarily exceeds single failure criteria since the second service we.ter pump is not required for normal or design basis accident conditions and the associated i
cooling tower service water pump provides the required redundancy for the postulated design basis event. The proposed change redefines an OPERABLE service water loop as having one OPERABLE service water pump and one OPERABLE I
cooling tower service water pump. Additional changes are proposed to the duration f
that a cooling tower service water pump may be inoperable and to the surveillance requirements for service water pumps.
The requirements for transferring primary and secondary system heat loads are currently contained in two Technical Specifications. Technical Specification 3/4.7.4 specifies the requirements for the service water and cooling tower service water I
pumps and valves. Technical Specification 3/4.7.5 specifies the requirements for the service water pumphouse and the mechanical draft cooling tower. Both Technical Specifications must be met to have an operable system to transfer the required heat loads.
This praposed change would consolidate these requirements into one Technical Speci'ication.
1
(
The Service _ Water System is designed such that in the event of a Loss of Coolant i
Accident (LOCA) concurrent with a loss of offsite power, a single service water pump supplying a single flow train powered from its associated emergency diesel generator will provide sufficient capability to dissipate the heat loads. Service Water System cooling water for each loop is normally supplied by one of the two service water pumps which are located in the service water pumphouse. Cooling water is supplied to the service water pumphouse from the Atlantic Ocean via underground tunnels.
in addition, to the service water pumphouse, a Seismic Category 1 mechanical draft cooling tower, with one cooling tower service water pump per loop, provides the required cooling water flow should the service water pumphouse fail to provide a sufficient supply of water due to seismic failure of the tunnels (see Figure 1).
i A cooling tower actuation signal is generated if low service water pressure is sensed by two out of three loop pressure instruments and at least one service water pump breaker closed. These pressure instruments are safety related Class 1E devices. A tower actuation signal must be manually initiated if both service water pump breakers are open due to maintenance and/or electrical fault to transfer the coolkg water supply from the service water pumphouse to the cooling tower.
I Each service water pump is capable of supplying 100 percent of the flow required by l
a single loop to dissipate plant heat loads during normal full power operation and during postulated accident conditions. The cooling tower service water pump in each loop is also capable of providing 100 percent of the required cooling water flow in 1
3 I
i that loop to dissipate heat loads during the design basis event upon failure of the service water pumphouse tunnels. Thus. Technical Specifications currently require j
that the Service Water System hase two OPERABLE loops with three OPERABLE pumps in each loop, each capable of dissipating post-LOCA heat loads.
North Atlantic performed a Probabilistic Risk Assessment of the proposed change in service water system requirements to one operable pump, the revised AOTs for two I
service water pumps within the same loop, and the revised AOT for one cooling tower j
service water pump, to determine their impact on core damage frequency. This PRA l
evaluation modified the Service Water System fault tree model to reflect the longer l
allowed outage times (AOT's) for planned or corrective maintenance on the Service Water System during power operation. The results of the evaluation indicate the proposed changes will have a minor effect on system unavailability and a smallimpact l
(2.5E-6 per year) on the core damage frequency (CDF). This change in CDF is insignificant within the uncertainty bounds of the CDF distribution. The Service j
Water System Probabilistic Risk Assessment is enclosed herein in Section VIII.
B.
Description of Proposed Changes 4
The current Technical Specification requirement to have three OPERABLE pumps per service water loop is overly restrictive. As stated in the UFSAR, the Service Water System is designed to dissipate the heat loads of the design basis event using one of the six pumps (two service water pumps and one cooling tower service water 4
pump per loop). In addition, the proposed changes to Technical Specification 3/4.7.4 will enhance plant operation by providing greater flexibility in planning and j
performing maintenance on the Service Water System. Most maintenance on the i
pumps is currently performed during refueling outages due to the restrictive nature i
l of the current Technical Specifications. Performing planned maintenance at times
)
other than during u tages would provide greater flexibility in outage planning and would likely improve plant and component reliability. The proposed changes will also r
permit the performance of unplanned maintenance during plant operation while l
minimizing plant heatup and cooldown cycles.
l l
The proposed changes to Technical Specification 3/4.7.4 are described below:
i 1.
The Limiting Conditic i for Operation will be changed as follows:
a.
Service Watt r System _ OPERABILITY will be defined in terms of f
service water loops and the service water pumphouse, cooling tower i
service water loops and the mechanical draft cooling tower, and the cooling tower makeup system, b.
An OPERABLE service water loop will be defined as consisting'of one OPERABLE service water pump and an OPERABLE cooling tower service water pump. The standby pump is removed from Technical Specifications stillleaving redundant loops each with redundant pumps capable of providing adequate service water flow to dissipate heat loads during the design basis event..A Probabilistic Risk Assessment Evaluation performed by the North Atlantic Reliability and Safety Engineering Group demonstrates that the change in core damage frequency associated with this change is insignificant within the bounds of uncertainty.
2.
Action Statement (a), which permits operation with one inoperable service l
water pump for seven days, will be deleted.
l 2
s 3.
Action Statement (b), which permits operation with two service water pumps inoperable (one inoperable pump in each loop) for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, is deleted.
4 Action Statement (c), which permits operation with two service water pumps in one loop inoperable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, is deleted.
5.
Action Statement (d), which permits operation with a cooling tower service water pump inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, is deleted.
6.
Proposed Action Statement (a) permits an inoperable service water loop for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Allowed Outage Time (AOT) is consistent with i
the Standard Technical Specifications for Westinghouse Pressurized Water Reactors (NUREG-1431). This AOT will apply to the entire service water loop flowpath with the exception of the associated cooling tower service water pump, as discussed above.
7.
Proposed Action Statement (b)' increases the AOT for the cooling tower service water pumps from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to seven days. This change is based on the l
lower contribution to risk of the cooling tower service water pumps as compared to the normally operating service water pumps. The acceptability of this change is supported by the Service Water System Probabilistic Risk l
Assessment Evaluation (Section Vill).
l 8.
Proposed Action Statement (c) specifies a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AOT for two cooling tower l
loops or the mechanical draft cooling tower. This is consistent with the existing AOT for the cooling tower in Technical Specification 3/4.7.5.
9.
Proposed Action Statement (d) specifies a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AOT for two loops other than the two cooling tower loops and for the service water pumphouse.
10.
Proposed Action Statement (e) specifies a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AOT for the portable tower makeup pump system. Currently, Technical Specification 3.7.5 ACTION d.,
does not specify an AOT for the portable tower makeup pump. If this pump is inoperable for reasons other than improper storage, a one hour report is l
required.
This is consistent with the curre -t requirement in Technical l
Specification 3/4.7.5.
l l
11.
Propose /..arveillance Requirement 4.7.4.1 incerporates existing Surveillance
(
Requir _ents 4.7.4.a and 4.7.4.b.1 as they apply to the service water loops.
l The rcquirement specified in Surveillance Requirement 4.7.4.b.2 to verify that each of the four service water pumps starts automatically upon loss of or failure to start of the redundant pump within the loop is deleted. With the standby service water pump not required for loop OPERABILITY, the basis for testing the automatic start capability of these pumps as a Technical i
Specification Surveillance no longer exists. The deletion of this portion of Surveillance Requirement 4.7.4.b.2 does not affect the regular inservice testing which is performed on the service water pumps and cooling tower service water pumps as required by Technical Specification Surveillance Requirement 4.0.5.
The OPERABILITY of the service water pumps and cooling tower service water pumps is demonstrated during quarterly inservice testing of these pumps as required by North Atlantic Procedure MA 6.4
- Inservice Testing of Pumps."
12.
Proposed Surveillance Requirement 4.7,4.2 incorporates existing Surveillance Requirements 4.7.4.4 and 4.7.4.b.1 as they apply to the cooling tower loops.
3 i
i i
j g
i i
l In addition, it incorporates existing Surveillance Requirement 4.7.5.d.1 and adds a Surveillance Requirement to verify that the service water cooling tower pumps start on a Tower Actuation signal.
j 13.
Proposed Surveillance Requirement 4 ' c.3 incorporates existing Surveillance l
Requirement 4.7.5.a.1.
i 14.
Proposed Surveillance Requirement 4.7.4.4 incorporates existing Surveillance l
Requirements 4.7.5.a.2, 4.7.5.b, 4.7.5.c, and 4.7.5.d.2.
15.
Technical Specification 3/4.7.5 will be deleted.
16.
Bases 3/4.7.4, Service Water System, is revised to add additional details concerning Service Water System operation and to incorporate the bases for 1
Technical Specification 3/4.7.5.
i j
17.
Bases 3/4.7.5, Ultimate Heat Sink, will be deleted.
i In summary, all of the requirements of Technical Specification 3/4.7.5 have been j
incorporated in the proposed Technical Specification 3/4.7.4.
j 1
Seabrook Station Technical Specification 3/4.7.5 specifies the requirements for the ultimate heat sink. This specification has been consolidated into the proposed
^
Technical Specification 3/4.7.4 This consolidation is proposed to reduce the potential for confusion between the Specifications and to control station operation in a manner consistent with the station design basis. The ultimate heat sink is the Atlantic Ocean when the service water pumps are utilized and the atmosphere when 4
the cooling tower service water pumps are utilized.
]
1 3
i 4
a
- i E
6 FW
$W
$o$
EO W:
NI
{
>D oc t-W M
eL 2
Q E
C k
b b
Zw
=
9E E
I
(
O,
- e. u 5
?!
O GOI CI CN is t-i*
i*
i T
L._T i
+
fs A
/N dN A
1
\\
g 1r
' f Y
o
..a 2
J'
- % gh 4 <
c o o l
os.
O O
E. c.
- w
.wa
( C
.a CH,r E _!,!. O_
i O
u 5
0 I
i
- -a a
W r
E
=
g e
U S
E
~
E O
3 m
i 3
dk
'N
_b w
[(
g M
e g
o g
{t O
g a
mn a
o4 E
E a,t C%.
w w
=
v a
2f l
.h fI
- z. *
).
E Z
Co
'8
~I 3
EI g
? [ "' C$
E 0'
'\\
$"x m
n!
v:
n XI
./-
\\
.
I X
C1 C"1 _7
-l 1
O?, C3 C" C-1 I
2--
E!
3-
!=
3.
c:
r1 e-t-
uw c.
u.
c=
$m A m.
<r ik ik (s
Ak hfTW1 Y kivut 5 m
I i
-