|
|---|
Category:OPERATING LICENSES & AMENDMENTS
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
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
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
ML20216C7861998-04-0909 April 1998
Amend 56 to License NPF-86,revising App a TSs Re Requirements for Control Room Subsystems
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
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
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
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
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
ML20108D9981996-05-0707 May 1996
Amend 47 to License NPF-86,revising App a TS 3.3.2, Engineered Safety Features Actuation Sys Instrumentation
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
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
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
ML20091Q7321995-08-31031 August 1995
Amend 40 to License NPF-86,revising App a Re Containment Bldg Penetrations
ML20083Q5591995-05-19019 May 1995
Amend 39 to License NPF-86,deleting from Ts,Certain Audit Responsibilities of Nuclear Safety Audit Review Committee & Review Responsibilities of Station Operation Review Committee Re Emergency Plan,Security Plan & Procedures
ML20083D0741995-05-17017 May 1995
Amend 37 to License NPF-86,revising App a TSs Re Schedule for Performing Type a Containment ILRTs
ML20082H9491995-04-10010 April 1995
Amend 36 to License NPF-86,revising TS to Allow Longer Surveillance Test Intervals & AOTs for RPS & ESFAS & Removing Requirement to Perform RTS Analog Channel Operational Test on Staggered Basis
ML20078R0091995-02-14014 February 1995
Amend 35 to License NPF-86,modifying TS to Rename TS 6.2.3 from Independent Safety Engineering Group to Independent Technical Reviews & Replacing Requirements for Five Person Independent Safety Engineering Group
ML20078H4701995-01-26026 January 1995
Amend 34 to License NPF-86,revising App a to Specify Composition of Sorc,Implement Station Qualified Reviewer Program & to Revise Time Which Nuclear Safety Audit Review Committee Must Issue Repts & Minutes
ML20080C3111994-12-0606 December 1994
Corrected Tech Spec Page 2-1 for Amend 33 to License NPF-86,including Rev to Revised Figure 2.1-1
ML20024J2031994-10-0505 October 1994
Amend 32 to License NPF-86,revising App a Re Operability Requirements for Primary Component Cooling Water Sys & Ultimate Heat Sink
ML20065J5491994-04-0707 April 1994
Amend 30 to License NPF-86 Supporting TS Changes in Allowable Time Intervals for Performing SR on Plant Components During Power Operation
ML20063M2411994-03-0707 March 1994
Amend 29 to License NPF-86,modifies LCO of TS 3.6.1.7 by Deleting Requirements Applicable to 36-inch Containment Shutdown Purge Supply & Exhaust Isolation Valves in Containment Air Purge Sys
ML20059F0611994-01-0707 January 1994
Amend 28 to License NPF-86,revising Station,Unit 1 Operating License to Reflect Transfer of VT Electric Generation & Transmission Cooperative,Inc Undivided Ownership Interest to Util
ML20059L9521993-11-10010 November 1993
Amend 26 to License NPF-86,revising Tech Specs to Reduce Frequency of Surveillances Required to Verify Integrity of Condensate Storage Tank at Least Every 18 Months
ML20057D7481993-09-28028 September 1993
Amend 25 to License NPF-86,modifying TS Surveillance Requirement Re RWST Narrow Range Level Transmitters
ML20056H2401993-08-24024 August 1993
Amend 24 to License NPF-86,revising TS Figure of Reactor Core Safety Limit Curves
ML20056G1361993-08-16016 August 1993
Amend 22 to License NPF-86,revising App a TS Re Reporting Radioactive Effluent Releases from Facility
ML20056G2671993-08-16016 August 1993
Amend 23 to License NPF-86,revising Plant Operating License to Reflect Name Change of Joint Owner Following Indirect Transfer of Control of Eua Power Corp Interest in Operating License
ML20106D1421992-09-30030 September 1992
Amend 17 to License NPF-86,allowing Verification of Operability of Reactor Trip Breaker Shunt Trip Circuitry Prior to First Planned or Unplanned Shutdown
ML20099F5271992-08-10010 August 1992
Amend 13 to License NPF-86,revising TS to Decouple Loss of Offsite Power/Safety Injection Test from 24 H Diesel Generator Surveillance Run
ML20099G2981992-08-10010 August 1992
Amend 12 to License NPF-86,providing Replacement of RTD Bypass Sys for Measurement of Primary Loop Temp w/fast-response thermowell-mounted RTDs
ML20101B4381992-05-29029 May 1992
Amend 10 to License NPF-86,revising License to Reflect Transfer of Operations & Maintenance of Seabrook Station, Unit 1 to North Atlantic Energy Svc Co
ML20086D6791991-11-18018 November 1991
Amend 8 to License NPF-86,changing Tech Spec for Facility to Redefine Fully Withdrawn Position of All Rcca Banks to Minimize Localized Rcca Wear
ML20083D1491991-09-12012 September 1991
Corrected Amend 6 to License NPF-86,providing Overlap Pages, Instruction Sheet & TS Change Pages
ML20082M8941991-08-27027 August 1991
Amend 6 to License NPF-86,revising TS to Increase Allowable Max Enrichment of Reload Fuel Assemblies to 5.0 Weight Percent U-235 from Current 3.5 Weight Percent U-235
ML20085A7531991-07-12012 July 1991
Amend 3 to License NPF-86,revising Tech Specs Re Removal of RHR Isolation Valve Autoclosure Interlock
ML20065M4771990-12-0606 December 1990
Amend 2 to License NPF-86,revising Tech Specs Re Dc Battery Surveillance Testing
ML20055H8101990-07-26026 July 1990
Amend 2 to License NPF-86,allowing United Illuminating Co to Enter Into Arrangement for Sale & Leaseback of Portion of Financial Interest in Facility to Certain Equity Investors
ML20012E2361990-03-15015 March 1990
License NPF-86 for Seabrook Station,Unit 1
ML20244D0991989-05-26026 May 1989
License NPF-67,authorizing Operation of Facility to Power Levels Not Exceeding 5% of Rated Power & Limiting Operation to No More than 0.75 Effective Full Power Hours
ML20154Q8871988-09-27027 September 1988
Amend 1 to License NPF-56,changing Tech Spec Setpoints for Pressurizer Pressure,Pressurizer Water Level & Steam Generator Water Level Channels as Result of Replacing Veritak/Tobar Transmitters W/Rosemount Transmitters
ML20215N2921986-10-17017 October 1986
License NPF-56 for Facility
1999-09-17
[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
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)
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
1999-09-17
[Table view] |
Text
..
ATTACUMEt1T TO LICEt!SE AMEtIDt1EttT f40. 6 FACIL11Y OPERATit;G LICEtiSE !!0. flPF-86 DOCLET 110. 50-443 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overlap pages have been provided for your convenience.
Remove Insert ix ix xii xii 1/4 9-16*
3/4 9-17*
3/4 9-18*
B 3/4 9-3 B 3/4 9-3 5-9 5-9 5-10 5-10
- Denotes new page 91093000659[h43 PDR ADOCK O PDR P
INDEX 1
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS........................
3/4 9-4 3/4.9.5 COMMUNICATIONS.,.........................................
3/4 9-5 3/4.9.6 REFUELING MACHINE............................
3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE AREAS..................
3/4 9-7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level.......
3/4 9-8 Low Water Level................
3/4 9-9 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM..........
3/4 9-10 3/4.9.10 WATER LEVEL - RE ACTOR VESSEL.............................
3/4 9-11 3/4.9.11 WATER LEVEL - STORAGE P0OL.............................
3/4 9-12 3/4.9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM.....
3/4 9-13 3/4.9.13 SPENT FUEL ASSEMBLY STORAGE.,..........................
3/4 9-16 FIGURE 3.9-1 FUEL ASSEMBLY BURNUP VS, INITIAL ENRICHMENT.
FOR SPENT FUEL ASSEMBLY ST0 RAGE.....................
3/4 9-17 3/4.9.14 NEW FUEL ASSEMBLY STORAGE...
3/4 9-18 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN..........................................
3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS..
3/4 10-2 3/4.10.3 PHYSICS TESTS............................................
3/4 10-3 3/4.10.4 REACTOR COOLANT L00PS...............................
3/4 10-4 3/4.10.5 POSITICN INDICATION SYSTEM - SHUTD0WN....................
3/4 10-5 3/4.10.6 REACTOR COOLANT L00PS....................................
3/4 10-6 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration........................................
3/4 11-1 Dose.........................
3/4 11-2 Liquid Radwaste Treatment System.........................
3/4 11-3 Liquid Holdup Tanks....................................
3/4 11-4 3/4.11.2 GASEOUS EFFLUENTS Dose Rate.............................
3/4 11-5 Dose - Noble Gases.......
3/4 11-6 Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form.....
3/4 11-7 Gaseous Radwaste Treatment System.....
3/4 11-8 Explosive Gas Mixture - System.........................
3/4 11-9 3/4.11.3 SOLID RADI0 ACTIVE WASTES..
3/4 11-10 3/4.11.4 TOTAL D0SE................
3/4 11-12 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM.........
3/4 12-1 SEABROOK - UNIT 1 ix Amenament No. 6
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.12.2 LAND USE CENSUS..........................................
3/4 12-3 3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM.......................
3/4 12-5 3.0/4.0 BASES 3/4.0 APPLICABILITY...............................................
B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4 L1 B0 RATION CONTR0L..........................................
B 3/4 1-1 3/4.1.2 B0 RATION SYSlEMS..........................................
B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES................................
B 3/4 1-3 l
3/4.2 POWER DISTRIBUTION LIMITS.......
B 3/4 2-1 3/4.2.1 AXIAL FLUX DIFFERENCE.....................................
B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACT 0R........................
B 3/4 2-2 3/4.2.4 QUADRANT POWER TILT RATI0.................................
B 3/4 2-3 3/4.2.5 DNB PARAMETERS............................................
B 3/4 2-4 4
3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION...............
B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION................................
B 3/4 3-3 3/4.3.4 TURBINE OVERSPEED PROTECTION..............................
B 3/4 3-6 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION.............
B 3/4 4-1 3/4.4.2 SAFETY VALVES.............................................
B 3/4 4-1 3/4.4.3 PRESSURIZER...............................................
B 3/4 4-2 3/4.4.4 RELIEF VALVES.............................................
B 3/4 4-2 3/4.4.5 STEAM GENERATORS..........................................
B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE............................
B 3/4 4-3 3/4.4.7 CHEMISTRY.................................................
B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY..............................
B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS...............................
B 3/4 4-7 FIGURE B 3/4.4-1 FAST NEUTRON FLUENCE (E>1MeV) AS A FUNCTION OF FULL POWER SERVICE LIFE..................................
B 3/4 4-9 FIGURE B 3/4.4-2 EFFECT OF FLUENCE AND COPPER CONTENT ON SHIFT OF RT FOR REACTOR VESSELS EXPOSED TO 550 F......
B 3/4 4-10 NOT SEABROOK - UNIT 1 x
l INDEX BASES SECTION PAGE TABLE B 3/4.4-1 REACTOR VESSEL TOUGHNESS...
B 3/4 4-11 3/4.4.10 STRUCTURAL INTEGRITY.....
B 3/4 4-16 3/4.4.11 REACTOR COOLANT SYSTEM VENTS.....................
B 3/4 4-16
^
3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS...............
B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS...
B 3/4 5-1 3/4.5.5 REFUELING WATER STORAGE TANK.
B 3/4 5-2 3/4. 6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT...............
B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.
B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES.....
B 3/4 6-3 3/4.6.4 COMBUSTIBLE GAS CONTROL........
B 3/4 6-3 3/4.6.5 CONTAINMENT ENCLOSURE BUILDING.......
B 3/4 6-4 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE..........
B 3/4 7-1 3/4.7.2 STEAM GENEPATOR PRESSURE / TEMPERATURE LIMITATION..
B 3/4 7-3 3/4.7.3 PRIMARY COMPONENT COOLING WATER SYSTEM.............
B 3/4 7-3 3/4.7.4 SERVICE WATER SYSTEM.............
B 3/4 7-3 3/4.7.5 ULTIMATE HEAT SINK......................................
B 3/4 7-3 3/4.7.6 CONTROL ROOM EMERGENCY MAKEUP AIR AND FILTRATION SUBSYSTEM..............
B 3/4 7-3 3/4.7.7 SNUBBERS......
B 3/4 7-4 3/4.7.8 SEALED SOURCE CCNTAMINATION..
B 3/4 7-5 3/4.7.9 (This specification number is not used)..
B 3/4 7-5 3/4.7.10 AREA TEMPERATURE MONITORING.........................
B 3/4 7-5 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, and ONSITE POWER DISTRIBUTION.
B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES............
B 3/4 8-3 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION,....
B 3/4 9-1 3/4.9.2 INSTRUMENTATION.......
B 3/4 9-1 3/4.9.3 DECAY TIME..................
B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS..............
B 3/4 9-1 3/4.9.5 COMMUNICATIONS......
B 3/4 9-1 3/' 9.6 REFUELING MACHINE...........
B 3/4 9-1 5/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING.,
B 3/4 9-2 SEABROOK - UNIT 1 xi
1 INDEX l
BASES SECTION PAGE 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION............
B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM..........
B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE P00L.........................................
B 3/4 9-2 3/4.9.1? FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM......
B 3/4 9-2 3/4.9.1 SPENT FUEL ASSEMBLY ST0 RAGE........................
B 3/4 9-3 3/4.9.14 NEW FUEL ASSEMBLY ST0 RAGE..............................
B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...............
B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS....
B 3/4 10-1 3/4.10.3 PHYSICS TESTS...
B 3/4 10-1 3/4.10.4 REACTOR COOLANT LOOPS..................................
B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN....................
B 3/4 10-1 3/4.10.6 REACTOR COOLANT LOOPS....
B 3/4 10-1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS...........
B 3/4 11-1 E
3/4.11.2 GASEOUS EFFLUENTS.......
B 3/4 11-2 3/4.11.3 SOLID RADI0 ACTIVE WASTES.........
B 3/4 11-5 3/4.11.4 TOTAL 005E......................................
B 3/4 11-5 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM........
B 3/4 12-1 3/4.12.2 LAND USE CENSUS.,..............................
B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM......
B 3/4 12-2 5.0 DESIGN FEATURES 5.1 SITE 5.1.1 EXCLUSION AREA.................
5-1 5-1 5.1.2 LOW POPULATION ZONE.......
5.1.3 MAPS DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADI0 ACTIVE GASEOUS AND LIQUID EFFLUENTS......
5-1 FIGURE 5.1-1 SITE AND EXCLUSION AREA BOUNDARY...............
5-3 FIGURE 5.1-2 LOW POPULATION ZONE....
5-5 FIGURE 5.1-3 LIQUID EFFLUENT DISCHARGE LOCATION................
5-7 5.2 CONTAINMENT 5.2.1 CONFIGURATION.
5-1 5-9 5.2.2 DESIGN PRES $URE AND TEMPERATURE.
SEABROOK - UNIT 1 xii Arendment No. 6
REFUELING OPERATIONS FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM SURVEILLANCE REQUIREMENTS 4.9.12d (Continued) 3)
Verifying that the filter cross connect valve can be manually j-opened, and 4)
Verifying that the heaters dissipate 951 11 kW when tested in accordance with ANSI N510-1980.
e.
After each complete or partiel replacement of a HEPA filter bank, by verifying that the cleanup system satisfies the in place penetration leakage testing acceptance-criteria of less than 0.05% in accordance I
with ANSI N510-1980 for a 00P test aerosol while operating the system at a flow rate of 16,450 cfm i 10%.
f.
After each complete or partial replacement of a charcoal adsorber bank, by verifying that the cleanup system satisfies the in place penetration leakage testing acceptance criteria of less than 0.05%
in accordance with ANSI f:510-1980 for a halogenated hydrocarbon re-frigerant test gas while operating the system at a flow rate of 16,450 cfm i 10%.
4 SEABROOK - UNIT 1 3/4 9-15
REFUEllNG OPERATIONS 3/4.9.13 SPENT FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION 3.9.13 fuel assemblies stored in the Spent Fuel Pool shall be placed in the spent fuel storage racks according to the criteria shown in Figure 3.9-1.
APl i.'.CABI L ITY:
Whenever fuel is in the Spent Fuel Pool.
ACTION:
With the-requirements of the above specification not satisfied, a.
suspend all other fuel movement within the Spent Fuel Pool and move the non-complying fuel assemblies to allowable locations in the Spent Fuel Pool in accordance with Figure 3.9-1.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.13.1 The burnup of each fuel assembly to be stored in the Spent Fuel Pool shall be determined from it's measured burnup nistory prior to storage in the Spent Fuel Pool.
A complete record of each assembly shall be maintained as long as that fuel assembly is retained on-site.
4.9.13.2 After fuel assembly (ies) movement into or within the Spent Fuel Pool, the position of the fuel assembly (ies) that was (were) moved shall be checked and independently verified to be in accordance with the criteria in Figure 3.9-1 i
SEABROOK - UNIT 1 3/4 9-16 Amendment No. 6
I I
l l
~
1 can be sters: anywhere 2 must not be road next to 3 3 must te stored nort tc 1 or empty beatent ]
20 -
I/
Type 1 15 G
3 i-g h
e 10 l
1 Type 2
=
5
)!
/
Type 3 0-1 2.5 2.75 3.0 3.25 3.5 3.75 4.0 4.25 4!5 4.75 5.0 InrJat Enrienment (w/o U235)
Figure 3. 9-7.
Fuel Asse=bly Burnup vs. Initial Enrich =ent For Spent Tuol Assembly Storage r.
set. BROOK - U'iIT 1 3/c 9 17 Amendner,t flo. 6 6
1 REFUELING OPERATIONS i
3/4.9.14 NEW FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION 3.9.14 The New Fuel Storage Vault may be maintained with a full loading of 90 as.temblies with fuel enrichment up to 3.675 w/o 2 3 sU.
Theloadin0mustbe reduced to 81 assemblies for enrichments from 3.675 to 5.0 w/o 23 0 by limiting the fuel assembly placement in the central column of the New Fuel Storage Vault to every other location.
APPLICABILITY:
Whenever fuel is in the New Fuel Storage Vault.
ACTION:
a.
With the requirements of the above specifications not satisfied, suspend all other fuel movement within the New Fuel Storage Vault and move the non-complying fuel assemblies to allowable locations in the New Fuel Storage Vault in accordance with the requirements of the above specification.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.14.1 After fuel assembly (ies) movement into or within the New Fuel Storage Vault, the position of the new fuel assembly (ies) that was (were) moved shall be checked and independently verified to be in accordance with the requirements of the above specification.
SEABROOK - UNIT 1 3/4 9-18 Amendment No. 6
REFUELING OPERATIONS BASES 3/4.9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTE_H (Continued) t for at least 10 continuous hours in a 31-day period is sufficient to reduce the builoup of nioisture on the adsorbers and HEPA filters.
The OPERABILITY or this system and the resulting iodine removal capacity are consistent with the assumptions of the safety analyses.
ANSI N510-1980 will be used as a proce-dural guide for surveillance testing.
3/4.9.13 SPENT FUEL ASSEMBLY STORAGE l
Restrictions on placement of fuel assemblies of certain em ichments within the Spent Fuel Pool is dictated by Figure 3.9-1.
These restrictions ensure that the K,ff of the Spent Fuel Pool will always remain less than 0.95 assuming the pool to be flooded with unborated water.
The restrictions delineated in Figure 3.9-1 and the action statement are consistent with the criticality safety analysis performed for the Spent Fuel Pool as documented in the FSAR.
3/4.9.14 NEW FUEL ASSEMBLY STORAGE Restrictions on placement of fuel assemblies of certain enrichments within the New Fuel Storage Vault is dictated by Specification 3/4.9.14. These restric-tions ensure that the K of the New Fuel Storage Vault will always remain less eff than 0.95 assuming the area to be flooded with unborated water.
In addition, these restrictions ensure that the K of the New Fuel Storage Vault will eff always remain less than 0.98 when aqueous foam moderation is assumed.
The restrictions delineated in Specification 3/4.9.14 and the action statement are coi.sistent with the criticality safety analysis performed for the New Fuel Storage Vault as documented in the FSAR.
r SEABROOK - UNIT 1 B 3/4 9-3 Amendment No. 6
/
l 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 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly con-taining 264 fuel rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel length of 144 inches.
The initial core loading shall have a maximum enrichment of 3.15 weight percent U-235.
Reload fuel shall be similar in phy-sical design to the initial core loading and shall have a maximum enrichment of 5.0 weight percent U-235.
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 material.
The nominal values of absorber material shall be 80% silver, 15% in-dium, 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 pressurn 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 12,265 cubic feet at a nominal T f 588.5 F.
avg 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
SEABROOK - UNIT 1 5-9 Amendment No. 6
DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY
- 5. 6.1.1 The spent fuel storage racks are designed and shall be maintained with:
A k,ff equivalent to less than or equal to 0.95 when flooded with a.
unborated water, which includes margin for uncertainty in calcula-tion methods and mechanical tolerances with a 95% probability at a 95% confidence level.
b.
A nominal 10.35 inch center-to-center distance between fuel assemblies placed in the storage racks.
5.6.1.2 The new fuel storage racks are designed and shall be maintained with:
a.
Ak equivalent to less than or equal to 0.95 when flooded with eff unborated water, which includes margin for uncertainty in calcula-tional rethods and mechanical tolerances with a 95% probability at a 95% confidence level.
b.
A k,ff equivalent to less than or equal to 0.98 when aqueous foam moderation is assumed, which includes margin for uncertair.ty in calculational methods and mechanical tolerances with a 95% probability at c 95% confidence level, c.
A nominal 21 inch center-to-center distance between fuel assemblies placed in the storage racks.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 14 feet 6 inches.
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1236 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMI_T 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
SEABROOK - UNIT 1 5-10 Amendment No. 6
DISTRIBUTION:
l Doc ket Tite' h0-443 4 i;RC PDR/LPDR P01-3 Reading File M. Rushbrook G. Edison DGC - 15018 D. Pagan - tillBB 3206 B. Grines - 9A3 E. Jordan - MNBB 3701 G. Hill (4) - PI-37 Vanda Jories - MNBB 7103 C. Grimes - 11F23 L. Kopp - 8E23 J. Linville, Fegion 1 s
b
\\
1
.
