View source for L-HU-06-029, Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity

{{Adams
| number = ML061980223
| issue date = 07/13/2006
| title = Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
| author name = Weinkam E
| author affiliation = Nuclear Management Co, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000266, 05000301
| license number = DPR-024, DPR-027
| contact person = 
| case reference number = L-HU-06-029
| document type = Letter type:L, Technical Specifications
| page count = 6
}}

=Text=
{{#Wiki_filter:Committed to Nuclear Excellence Nuclear Management Company, LLC L-HU-06-029 10 CFR 50.90 July 13, 2006 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Supplement to Application For Technical Specification lmprovement Regardinq Steam Generator Tube Inteqrity Reference 1) License Amendment Request (LAR) titled, "Application For Technical Specification lmprovement Regarding Steam Generator Tube Integrity",
dated February 16,2006 By letter dated February 16,2006, Nuclear Management Company (NMC) submitted the referenced LAR to adopt Technical Specification (TS) improvements regarding steam generator tube integrity provided in Technical Specification Task Force (TSTF)
Standard Technical Specification Change Traveler TSTF-449, "Steam Generator Tube Integrity", Revision 4. This letter supplements the referenced LAR with the revised TS Table of Contents page showing the addition of new Specification 3.4.17 which Reference 1 proposed to include in the TS. NMC is submitting this supplement in accordance with the provisions of 10 CFR 50.90. provides revised Table of Contents page ii.
The additional information provided in this supplement does not impact the conclusions of the Determination of No Significant Hazards Consideration and Environmental Assessment presented in the Reference February 16, 2006 submittal as supplemented May 11,2006.
In accordance with 10 CFR 50.91, NMC is providing a copy of this letter and enclosure to the designated State Official.
Summarv of Commitments This letter contains no new commitments and no revisions to existing commitments.
700 First Street Hudson, Wisconsin 54016 Telephone: 715-377-3300

Document Control Desk Page 2 I declare under penalty of perjury that the foregoing is true and correct.
Executed on 13 July 2006.
Director, Nuclear Licensing and Regulatory Services Nuclear Management Company, LLC Enclosures (I )
cc:    Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Senior Resident Inspector, Point Beach Nuclear Plant, USNRC State Official, Ms. Ave M. Bie - Public Service Commission of WI

ENCLOSURE I Proposed Technical Specification Table of Contents (final)
Point Beach Nuclear Plant Units 1 and 2 Technical Specification Table of Contents Page ii 3 page follows

TECHNICAL SPECIFICATIONS TABLE OF CONTENTS 1.0       USE AND APPLICATION ............................................................................. 1.1.1 1.1            Definitions............................................................................................1.1.1 1.2            Logical Connectors .............................................................................. 1.2.1 1.3            Completion Times ................................................................................ 1.3.1 1.4            Frequency........................................................................................... 1.4.1 2.0       SAFETY LIMITS (SLS) .................................................................................2.0.1 2.1            SLs ......................................................................................................
2.0.1 2.2            SL Violations ........................................................................................ 2.0.1 3.0       LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ............. 3.0.1 3.0       SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ............................ 3.0.4 REACTIVITY CONTROL SYSTEMS ............................................................ 3.1 .1.1 SHUTDOWN MARGIN (SDM) ............................................................. 3.1.1.1 Core Reactivity .............................................................................. 3.1.2.1 Moderator Temperature Coefficient (MTC) .......................................... 3.1.3.1 Rod Group Alignment Limits ................................................................ 3.1.4.1 Shutdown Bank Insertion Limits...........................................................3.1.5.1 Control Bank Insertion Limits ............................................................... 3.1.6.1 Rod Position Indication ........................................................................ 3.1.7.1 PHYSICS TESTS Exceptions-MODE 2 ........................................ 3.1.8.1 3.2       POWER DISTRIBUTION LIMITS ................................................................. 3.2.1.1 3.2.1          Heat Flux Hot Channel Factor (FQ(Z))
(FQMethodology) ........................................................................ 3.2.1-1 3.2.2          Nuclear Enthalpy Rise Hot Channel Factor (F! H) ............................ 3.2.2-1 3.2.3          AXIAL FLUX DIFFERENCE (AFD) ......................................................3.2.3-1 3.2.4          QUADRANT POWER TILT RATIO (QPTR) ......................................... 3.2.4-1 3.3       INSTRUMENTATION................................................................................. 3.3.1.1 3.3.1          Reactor Protection System (RPS) Instrumentation .............................. 3.3.1-1 3.3.2          Engineered Safety Feature Actuation System (ESFAS)
Instrumentation........................................................................... 3.3.2-1 3.3.3          Post Accident Monitoring (PAM) Instrumentation................................. 3.3.3-1 3.3.4          Loss of Power (LOP) Diesel Generator (DG)
Start and Load Sequence Instrumentation.................................. 3.3.4-1 3.3.5          Control Room Emergency Filtration System (CREFS)
Actuation Instrumentation............................................................ 3.3.5-1 3.3.6          Boron Dilution Alarm ............................................................................ 3.3.6-1 3.4       REACTOR COOLANT SYSTEM (RCS) ................................................... 3.4.1.1 3.4.1          RCS Pressure, Temperature. and Flow Departure from Nucleate Boiling (DNB) Limits ..................................................... 3.4.1-1 3.4.2          RCS Minimum Temperature for Criticality ............................................ 3.4.2-1 3.4.3          RCS Pressure and Temperature (PR) Limits ....................................... 3.4.3-1 3.4.4          RCS Loops - MODES 1 and 2 ............................................................ 3.4.4-1               1 Point Beach                                                                            Unit 1 -Amendment No. 201 Unit 2 .      Amendment No. 206

TECHNICAL SPECIFICATIONS TABLE OF CONTENTS 3.4       REACTOR COOLANT SYSTEM (continued)
RCS Loops .MODE 3......................................................................... 3.4.5.1 RCS Loops .MODE 4 ......................................................................... 3.4.6.1 RCS Loops .MODE 5, Loops Filled.....................................................3.4.7.1 RCS Loops .MODE 5, Loops Not Filled ........................................ 3.4.8.1 Pressurizer .......................................................................................... 3.4.9.1 Pressurizer Safety Valves .................................................................... 3.4.10-1 Pressurizer Power Operated Relief Valves (PORVs) ........................... 3.4.1 1-1 Low Temperature Overpressure Protection (LTOP) ............................. 3.4.12.1 RCS Operational LEAKAGE ................................................................               3.4.13.1 RCS Pressure Isolation Valve (PIV) Leakage ...................................... 3.4.14.1 RCS Leakage Detection Instrumentation............................................. 3.4.15.1 RCS Specific Activity ...........................................................................3.4.1 6-1 Steam Generator (SG) Tube Integrity .................................................. 3.4.17.1                 1 3.5       EMERGENCY CORE COOLING SYSTEMS (ECCS) .................................. 3.5.1.1 3.5.1         Accumulators ....................................................................................... 3.5.1-1 3.5.2         ECCS-Operating.................................................................................. 3.5.2-1 3.5.3         ECCS-Shutdown..................................................................................        3.5.3-1 3.5.4         Refueling Water Storage Tank (RWST) ........................................ 3.5.4-1 CONTAINMENT SYSTEMS .........................................................................3.6.1-1 Containment ........................................................................................ 3.6.1-1 Containment Air Locks.........................................................................3.6.2.1 Containment Isolation Valves ............................................................... 3.6.3.1 Containment Pressure ..................................................................... 3.6.4.1 Containment Air Temperature...........................................................3.6.5.1 Containment Spray and Cooling Systems............................................3.6.6.1 Spray Additive System......................................................................... 3.6.7.1 PLANT SYSTEMS ........................................................................................ 3.7.1 -1 Main Steam Safety Valves (MSSVs).................................................... 3.7.1-1 Main Steam lsolation Valves (MSIVs) and Non-Return Check Valves .................................................... 3.7.2-1 Main Feedwater Isolation..................................................................... 3.7.3.1 Atmospheric Dump Valve (ADV) Flowpaths ......................................... 3.7.4.1 Auxiliary Feedwater (AFW) System ..................................................... 3.7.5.1 Condensate Storage Tank (CST) ........................................................ 3.7.6.1 Component Cooling Water (CC) System............................................ 3.7.7.1 Service Water (SW) System ............................................................... 3.7.8.1 Control Room Emergency Filtration System (CREFS) ......................... 3.7.9.1 Fuel Storage Pool Water Level ............................................................ 3.7.10-1 Fuel Storage Pool Boron Concentration............................................... 3.7.11-1 Spent Fuel Pool Storage ...................................................................... 3.7.12.1 Secondary Specific Activity .................................................................. 3.7.1 3-1 Point Beach                                              ii                            Unit 1 -Amendment No.
Unit 2 . Amendment No.

TECHNICAL SPECIFICATIONS TABLE OF CONTENTS ELECTRICAL POWER SYSTEMS ...............................................................3.8.1.1 AC Sources-Operating .........................................................................3.8.1.1 AC Sources-Shutdown.........................................................................3.8.2-1 Diesel Fuel Oil and Starting Air ............................................................ 3.8.3-1 DC Sources-Operating......................................................................... 3.8.4-1 DC Sources-Shutdown ........................................................................ 3.8.5-1 Battery Cell Parameters .......................................................................       3.8.6-1 Inverters-Operating    .............................................................................. 3.8.7-1 Inverters-Shutdown.............................................................................. 3.8.8-1 Distribution Systems-Operating ...........................................................3.8.9-1 Distribution Systems-Shutdown ........................................................... 3.8.1 0-1 3.9       REFUELING OPERATIONS......................................................................... 3.9.1-1 3.9.1         Boron Concentration ............................................................................      3.9.1-1 3.9.2         Nuclear Instrumentation....................................................................... 3.9.2-1 3.9.3         Containment Penetrations .................................................................. 3.9.3-1 3.9.4         Residual Heat Removal (RHR) and Coolant Circulation-High Water Level .......................................................3.9.4-1 3.9.5         Residual Heat Removal (RHR) and Coolant Circulation-Low Water Level........................................................3.9.5-1 3.9.6         Refueling Cavity Water Level ............................................................... 3.9.6-1 4.0       DESIGN FEATURES.................................................................................... 4.0.1 4.1           Site Location........................................................................................4.0.1 4.2           Reactor Core .......................................................................................4.0.1 4.3           Fuel Storage ........................................................................................ 4.0.2 ADMINISTRATIVE CONTROLS ................................................................... 5.0-1 Responsibility ...................................................................................... 5.1.1 Organization ........................................................................................ 5.2.1 Unit Staff Qualifications........................................................................5.3.1 Procedures .......................................................................................... 5.4.1 Programs and Manuals ........................................................................ 5.5.1 Reporting Requirements...................................................................... 5.6.1 High Radiation Area ............................................................................. 5.7.1 Point Beach                                              iii                            Unit 1 -Amendment No. 201 Unit 2 .      Amendment No. 206}}