ML071380443
| ML071380443 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 05/17/2007 |
| From: | NRC/NRR/ADRO/DORL/LPLI-2 |
| To: | |
| Miller G, NRR/DORL, 415-2481 | |
| Shared Package | |
| ML071420135 | List: |
| References | |
| TAC MD0696 | |
| Download: ML071380443 (6) | |
Text
ATTACHMENT TO LICENSE AMENDMENT NO. 115 FACILITY OPERATING LICENSE NO. NPF-86 DOCKET NO. 50-443 Replace the following page of Facility Operating License No. NPF-86 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Remove Insert 3 3 Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages as indicated. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
Remove Insert v v vi vi x x xiv xiv xv xv 1-4 1-4 1-5 1-5 3/4 4-13 3/4 4-13 3/4 4-14 3/4 4-14 3/4 4-15 3/4 4-15 3/4 4-16 3/4 4-16 3/4 4-16a 3/4 4-17 3/4 4-17 3/4 4-18 3/4 4-18 3/4 4-19 3/4 4-19 3/4 4-20 3/4 4-20 3/4 4-21 3/4 4-21 3/4 4-22 3/4 4-22 3/4 4-23 3/4 4-23 3/4 4-24 3/4 4-24 3/4 4-25 3/4 4-25 3/4 4-26 3/4 4-26 3/4 4-27 3/4 4-27 3/4 4-28 3/4 4-28 3/4 4-29 3/4 4-29 3/4 4-30 3/4 4-30 3/4 4-31 3/4 4-31 3/4 4-32 3/4 4-32 3/4 4-33 Corrected by letter dated May 17, 2007
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE TABLE 4.3-5 (THIS TABLE NUMBER IS NOT USED) ................................................... 3/4 3-58 Explosive Gas Monitoring Instrumentation 3/4 3-60 TABLE 3.3-13 EXPLOSIVE GAS MONITORING INSTRUMENTATION ........................ 3/4 3-61 TABLE 4.3-6 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-64 3/4.3.4 (THIS SPECIFICATION NUMBER IS NOT USED) .............................................. 3/4 3-67 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation ................................................................................... 3/44-1 Hot Standby ................................................................................................................ 3/4 4-2 Hot Shutdown.......... ..................................... ...................... 3/44-4 Cold Shutdown - Loops Filled .................................................................................. 3/4 4-6 Cold Shutdown - Loops Not Filled........................................................................... 3/4 4-7 3/4.4.2 SAFETY VALVES S hutdow n ..................................................................................................................... 3/4 4-8 O perating ..................................................................................................................... 3/4 4-9 3/4.4.3 P R ESS UR IZER .......................................................................................................... 3/4 4-10 3/4.4.4 R ELIEF VA LV ES ........................................................................ 3/44-11 3/4.4.5 STEAM GENERATOR (SG) TUBE INTEGRITY............................. 3/4 4-13 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems .......................................... 3/4 4-14 Operational Leakage ................................................................................................. 3/4 4-15 3/4.4.7 (THIS SPECIFICATION NUMBER IS NOT USED) .............................................. 3/4 4-18 1 3/4.4.8 SPECIFIC ACTIVITY .......................................... 3/4 4-19 SEABROOK - UNIT 1 V Amendment No. 50,66,93, 115 Corrected by Letter Dated May 17, 2007
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE FIGURE 3.4-1 DOSE EQUIVALENT 1-131 REACTOR COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE REACTOR COOLANT SPECIFIC ACTIVITY > lpCi/gram DOSE EQUIVALENT 1-131.................................... 3/44-20 TABLE 4.4-3 REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM....................................... 3/44-21 3/4.4.9 PRESSURE/TEMPERATURE LIMITS General 3/4 4-22 FIGURE 3.4-2 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS -
APPLICABLE UP TO 11.1 EFPY 3/4 4-23 I FIGURE 3.4-3 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS -
APPLICABLE UP TO 11.1 EFPY................................ 3/4 4-24 Pressurizer........................................... 3/4 4-25 Overpressure Protection Systems .............................................................. 3/4 4-26 FIGURE 3.4-4 RCS COLD OVERPRESSURE PROTECTION SETPOINTS ........ 3/4 4-29 3/4.4.10 STRUCTURAL INTEGRITY......................................................................................3/4 4-30 3/4.4.11 REACTOR COOLANT SYSTEM VENTS ........................... 3/4 4-31 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS Hot Standby, Startup, and Power Operation .................................................... I..... 3/4 5-1 Shutdown ................................................... 3/4 5-3 3/4.5.2 ECCS SUBSYSTEMS - Tavg GREATER THAN OR EQUAL TO 350°F ............ 3/4 5-4 3/4.5.3 ECCS SUBSYSTEMS - Tavg LESS THAN 350°F .................................................. 3/4 5-8 ECCS SYBSYSTEMS - Tavg Equal To or Less Than 2001F ................................ 3/4 5-10 3/4.5.4 REFUELING WATER STORAGE TANK ............................ 3/45-11 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containm ent Integrity .............................................................................................. 3/4 6-1 Containm ent Leakage ................................................................................................ 3/4 6-2 SEABROOK - UNIT 1 vi Amendment No. 7O,89, 115 Corrected By Letter Dated May 17, 2007
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.12.2 (THIS SPECIFICATION NUMBER IS NOT USED) .............................................. 3/4 12-3 3/4.12.3 (THIS SPECIFICATION NUMBER IS NOT USED) .............................................. 3/4 12-5 3.0/4.0 BASES 3/4.0 APPLICABILITY B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL....................................... B 3/4 1-1 3/4.1.2 BORATION SYSTEMS B 3/4 1-3 3/4.1.3 MOVABLE CONTROL ASSEMBLIES.................................... B 3/4 1-4 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 FACTOR .............. B 3/4 2-2 3/4.2.4 QUADRANT POW ER TILT RATIO......................................................................... B 3/4 2-3 3/4.2.5 DNB PARAM ETERS................................................................................................. B 3/4 2-4 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 (THIS SPECIFICATION NUMBER IS NOT USED) .............................................. 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 3/44-1 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 GENERATOR (SG) TUBE INTEGRITY.................................................. B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE B 3/4 4-3 3/4.4.7 (THIS SPECIFICATION NUMBER IS NOT USED) .............................................. 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 (THIS FIGURE NUMBER NOT USED) .............................................. B 3/4 4-9 FIGURE B 3/4.4-2 (THIS FIGURE NUMBER NOT USED) .............................................. B 3/4 4-10 SEABROOK - UNIT 1 x Amendment No. 50,66,74, 89, 93,115 Corrected By Letter DatedMay 17, 2007
INDEX 6.0 ADMINISTRATIVE CONTROLS SECTION PAGE 6.4 (THIS SPECIFICATION NUMBER IS NOT USED) .............................................. 6-4 6.5 (THIS SPECIFICATION NUMBER IS NOT USED) .............................................. 6-4 6.6 SAFETY LIMIT VIOLATION 6-4 6.7 PROCEDURES AND PROGRAMS 6-5 6.8 REPORTING REQUIREMENTS 6.8.1 ROUTINE REPORTS......................................... 6-14 Startup R eport............................................................................................................ 6-14 A nnual R eports .......................................................................................................... 6-15 Annual Radiological Environmental Operating Report ......................................... 6-15 Annual Radioactive Effluent Release Report ........................................................ 6-15 CORE OPERATING LIMITS REPORT............................ 6-16 Steam Generator Tube Inspection Report ........................................................... 6-21 6.8.2 SPECIAL REPORTS.. ................................................................................................ 6-21 SEABROOK - UNIT 1 xiv Amendment No. 34, 67, 73, 88, 104,!09,0 113,115 Corrected By Letter Dated May 17, 2007 !
INDEX 6.0 ADMINISTRATIVE CONTROLS SECTION PAGE 6.9 (THIS SPECIFICATION NUMBER IS NOT USED) .................... 6-21 6.10 RADIATION PROTECTION PROGRAM 6-22 6.11 HIGH RADIATION AREA 6-22 6.12 PROCESS CONTROL PROGRAM (PCP) ....................... ..................................... 6-23 6.13 OFFSITE DOSE CALCULATION MANUAL (ODCM) ................... 6-23 6.14 MAJOR CHANGES TO LIQUID, GASEOUS, AND SOLID RADWASTE TREATMENT SYSTEMS 6-24 6.15 CONTAINMENT LEAKAGE RATE TESTING PROGRAM ............... 6-25 SEABROOK - UNIT 1 xv Amendment No. 34, 70, 88, 115 Corrected By Letter Dated May 17, 2007