ML022530199
| ML022530199 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 09/05/2002 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| Download: ML022530199 (9) | |
Text
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION .................. 3/4 7-11 3/4.7.3 PRIMARY COMPONENT COOLING WATER SYSTEM ..................................... 3/4 7-12 3/4.7.4 SERVICE WATER SYSTEM / ULTIMATE HEAT SINK ....................................... 3/4 7-13 3/4.7.5 (THIS SPECIFICATION NUMBER IS NOT USED) ............................................. 3/4 7-14 3/4.7.6 CONTROL ROOM SUBSYSTEM ........................................................................ 3/4 7-16 Emergency Makeup Air and Filtration ............................................................... 3/4 7-16 Air Conditioning .................................................................................................. 3/4 7-18a 3/4.7.7 SNUBBERS .......................................................................................................... 3/4 7-19 3/4.7.8 SEALED SOURCE CONTAMINATION ............................................................... 3/4 7-20 3/4.7.9 (THIS SPECIFICATION NUMBER IS NOT USED) ............................................. 3/4 7-22 3/4.7.10 (THIS SPECIFICATION NUMBER IS NOT USED) ............................................. 3/4 7-23 TABLE 3.7-3 (THIS TABLE NUMBER IS NOT USED) ....................................................... 3/4 7-24 3/4.8 ELECTRICAL POWER SYSTEMS 314.8.1 A.C. SOURCES Operating .............................................................................................................. 3/4 8-1 TABLE 4.8-1 (THIS TABLE NUM BER IS NOT USED) ......................................................... 3/4 8-10 Shutdown .............................................................................................................. 3/4 8-11 3/4.8.2 D.C. SOURCES Operating .............................................................................................................. 3/4 8-12 TABLE 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS ........................................... 3/4 8-14 Shutdown .............................................................................................................. 314 8-15 3/4.8.3 ONSITE POWER DISTRIBUTION Operating .............................................................................................................. 3/4 8-16 Shutdown .............................................................................................................. 3/4 8-18 Trip Circuit for Inverter I-2A .................................................................................. 314 8-19 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES A.C. Circuits Inside Prim ary Containm ent ........................................................ 3/4 8-20 Containment Penetration Conductor Overcurrent Protective Devices and Protective Devices for Class 1E Power Sources Connected to Non-Class 1E Circuits ................................................................................................. 3/4 8-21 Motor-Operated Valves Thermal Overload Protection ..................................... 3/4 8-24 3/4.9 REFUELING OPERATIONS BORON CONCENTRA TION ................................................................................ 3/4 9-1 3/4.9.1 3/4.9.2 INSTRUM ENTATION ........................................................................................... 3/4 9-2 3/4.9.3 DECAY TIM E ........................................................................................................ 3/4 9-3 SEABROOK - UNIT 1 viii Amendment No. 56,59,63,85
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4 9-4 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS ..................................... 3/4 9-5 3/4.9.5 (THIS SPECIFICATION NUMBER IS NOT USED) ............................... 3/4 9-6 3/4.9.6 (THIS SPECIFICATION NUMBER IS NOT USED) ............................... 3/4 9-7 3/4.9.7 (THIS SPECIFICATION NUMBER IS NOT USED) ...............................
3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION 3/4 9-8 High W ater Level .................................................................................. 3/4 9-9 Low W ater Level ................................................................................... 3/4 9-10 3/4 9.9 (THIS SPECIFICATION NUMBER IS NOT USED) .............................. 3/4 9-11 I 3/4 9.10 WATER LEVEL - REACTOR VESSEL ................................................ 3/4 9-12 3/4 9.11 WATER LEVEL - STORAGE POOL .................................................... 3/4 9-13 3/4 9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM 3/4 9-16 3/4 9.13 SPENT FUEL ASSEMBLY STORAGE ................................................
FIGURE 3.9-1 FUEL ASSEMBLY BURNUP VS. INITIAL ENRICHMENT 3/4 9-17 FOR SPENT FUEL ASSEMBLY STORAGE ........................................ 3/4 9-18 3/4.9.14 NEW FUEL ASSEMBLY STORAGE .....................................................
3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10-1 3/4.10.1 SHUTDOW N MARGIN ......................................................................... 3/4 10-2 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS 3/4 10-3 3/4.10.3 PHYSICS TESTS ................................................................................. 3/4 10-4 3/4.10.4 REACTOR COOLANT LOOPS ............................................................ 3/4 10-5 3/4.10.5 POSITION INDICATION SYSTEM- SHUTDOWN ...............................
3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4 11-1 (THIS SPECIFICATION NUMBER IS NOT USED) .............................. 3/4 11-2 (THIS SPECIFICATION NUMBER IS NOT USED) ............................... 3/4 11-3 (THIS SPECIFICATION NUMBER IS NOT USED) ............................... 3/4 11-4 Liquid Holdup Tanks .............................................................................
3/4.11.2 GASEOUS EFFLUENTS 314 11-5 (THIS SPECIFICATION NUMBER IS NOT USED) .............................. 3/4 11-6 (THIS SPECIFICATION NUMBER IS NOT USED) ............................... 3/4 11-7 (THIS SPECIFICATION NUMBER IS NOT USED) ............................... 3/4 11-8 (THIS SPECIFICATION NUMBER IS NOT USED) ............................... 3/4 11-9 Explosive Gas Mixture - System ............................................................ 3/4 11-10 3/4.11.3 (THIS SPECIFICATION NUMBER IS NOT USED) ............................... 3/4 11-12 3/4.11.4 (THIS SPECIFICATION NUMBER IS NOT USED) ...............................
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4 12-1 3/4.12.1 (THIS SPECIFICATION NUMBER IS NOT USED) ...............................
ix Amendment No. 6,34-66, -2, 8 5 SEABROOK - UNIT I
INDEX BASES PAGE SECTION B 3/4 4-11 TABLE B 3/4.4-1 REACTOR VESSEL TOUGHNESS .........................................................
B 3/44-16 3/4.4.10 STRUCTURAL INTEGRITY .................................................................................
B 3/4 4-16 3/4.4.11 REACTOR COOLANT SYSTEM VENTS ............................................................
3/4.5 EMERGENCY CORE COOLING SYSTEMS B 3/4 5-1 3/4.5.1 ACCUMULATORS ............................................................................................... B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS .......................................................................... B 3/4 5-2 3/4.5.4 REFUELING W ATER STORAGE TANK .............................................................
3/4.6 CONTAINMENT SYSTEMS B 3/4 6-1 3/4.6.1 PRIMARY CONTAINMENT .................................................................................. B 3/4 6-3 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 6-4 3/4.6.5 CONTAINMENT ENCLOSURE BUILDING .........................................................
3/4.7 PLANT SYSTEMS B 3/4 7-1 3/4.7.1 TURBINE CYCLE ................................................................................................. B 314 7-3 3/4.7.2 STEAM GENERATOR 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 / ULTIMATE HEAT SINK ....................................... B 3/4 7-3A 3/4.7.5 (THIS SPECIFICATION NUMBER IS NOT USED) ............................................. B 3/4 7-4 3/4.7.6 CONTROL ROOM SUBSYSTEMS ...................................................................... B 3/4 7-4 3/4.7.7 SN U BBE RS .......................................................................................................... B 3/4 7-5 3/4.7.8 SEALED SOURCE CONTAMINATION ............................................................... B 3/4 7-5 3/4.7.9 (THIS SPECIFICATION NUMBER IS NOT USED) ............................................. B 3/4 7-5 3/4.7.10 (THIS SPECIFICATION NUMBER IS NOT USED) .............................................
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 B 3/4 8-1 ONSITE POWER DISTRIBUTION ....................................................................... B 3/4 8-3 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES .......................................
3/4.9 REFUELING OPERATIONS B 3/4 9-1 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 TIM E ........................................................................................................ B 3/4 9-1 3/4.9.4 (THIS SPECIFICATION NUMBER IS NOT USED) ............................................. B 3/4 9-1 3/4.9.5 (THIS SPECIFICATION NUMBER IS NOT USED) ............................................. B 3/4 9-1 3/4.9.6 (THIS SPECIFICATION NUMBER IS NOT USED) ............................................. B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING ...................................
xA Amendment No. 66--63,8 5 SEABROOK - UNIT 1
INDEX BASES SECTION PAGE B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION ............. B 3/4 9-2 3/4.9.9 (THIS SPECIFICATION NUMBER IS NOT USED) .................................
3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and B 3/4 9-2 STORAGE POOL .............................................................................. B 3/4 9-2 3/4.9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM B 3/4 9-3 3/4.9.13 SPENT FUEL ASSEMBLY STORAGE ....................................................
ASSEMBLY STORAGE ........................................................ B 3/4 9-3 3/4.9.14 NEW FUEL 3/4.10 SPECIAL TEST EXCEPTIONS B 3/4 10-1 3/4.10.1 SHUTDOW N 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 ................................................................
3/4.11 RADIOACTIVE EFFLUENTS B 3/4 11-1 3/4.11.1 (THIS SPECIFICATION NUMBER IS NOT USED) ................................. B 3/4 11-2 3/4.11.2 GASEOUS EFFLUENTS .......................................................................... B 3/4 11-5 3/4.11.3 (THIS SPECIFICATION NUMBER IS NOT USED) ................................. B 3/4 11-5 3/4.11.4 (THIS SPECIFICATION NUMBER IS NOT USED) .................................
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING B 3/4 12-1 3/4.12.1 (THIS SPECIFICATION NUMBER IS NOT USED) ................................. B 3/4 12-1 3/4.12.2 (THIS SPECIFICATION NUMBER IS NOT USED) ................................. B 314 12-2 3/4.12.3 (THIS SPECIFICATION NUMBER IS NOT USED) .................................
flF!l(N FFATURES 1; n ;=.ql~m FE5-1E 5.1 SITE 5.1.1 EXCLUSION AREA ................................................................................. 5-1 5.1.2 LOW POPULATION ZONE ...................................................................... 5-1 5.1.3 MAPS DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY 5-1 FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS .................
5-3 FIGURE 5.1-1 SITE AND EXCLUSION AREA BOUNDARY ................................ 5-5 FIGURE 5.1-2 LOW POPULATION ZONE ........................................................... 5-7 FIGURE 5.1-3 LIQUID EFFLUENT DISCHARGE LOCATION .............................
5.2 CONTAINMENT 5-1 5.2.1 CO NFIGURATION .................................................................................... 5-9 5.2.2 DESIGN PRESSURE AND TEMPERATURE ..........................................
SEABROOK - UNIT 1 Ali Amendment No. 61 6g, 85
REFUELING OPERATIONS 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPRATION 3.9.4 The containment building penetrations shall be in the following status:
- a. The equipment door closed and held in place by a minimum of four bolts, doors of one
- b. A minimum of one door in each airlock is closed, however both personnel airlock may be open if:
- 1) One personnel airlock door is capable of being closed, and to
- 2) A designated individual is available outside the personnel airlock close the door.
atmosphere to
- c. Each penetration providing direct access from the containment the outside atmosphere shall be either:
or
- 1) Closed by a manual or automatic isolation valve, blind flange, equivalent; or
- 2) Be capable of being closed by an OPERABLE automatic Containment Purge and Exhaust Isolation System; or at the
- 3) Be capable of being closed by a designated individual available penetration.*
APPL ICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.
ACTION:
suspend all With the requirements of the above specification not satisfied, immediately fuel in the operations involving CORE ALTERATIONS or movement of irradiated containment building.
A designated individual shall not be used for manual isolation of valves CAP-V1, CAP-V2, CAP-V3, and/or CAP-V4.
SEABROOK - UNIT 1 3/4 9-4 Amendment No. 40, 8 5
REFUELING OPERATIONS 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS SURVEILLANCE REQUIREMENTS penetrations:
4.9.4 For the above required containment building containment building
- a. Determine that each of the above required 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the penetrations shall be in its required condition within ALTERATIONS or start of, and at least once per 7 days during CORE and building, movement of irradiated fuel in the containment Isolation System
- b. Demonstrate that the Containment Purge and Exhaust 10 days prior to within is OPERABLE at least once every 18 months and of irradiated fuel in the the start of CORE ALTERATIONS or movement purge and exhaust containment building by verifying that containment Radiation test signal isolation occurs on manual initiation and on a High area monitoring from each of the manipulator crane radiation instrumentation channels.**
3.9.4.c.1 or
- Not required for those valves complying with Specification Specification 3.9.4.c.3.
AmendIment No. 40 85 SEABROOK- UNIT I 3/4 9-4A
REFUELING OPERATIONS 3/4.9.9 (This specification number is not used.)
3/4 9-10 Amendment No. 85 SEABROOK - UNIT I
3/4.9 REFUELING OPERATIONS BASES 3/4.9.2 INSTRUMENTATION ensures that The OPERABILITY of the Source Range Neutron Flux Monitors the reactivity condition of the detect changes in redundant monitoring capability is available to core.
3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel has elapsed to allow the assemblies in the reactor vessel ensures that sufficient time time is consistent with the radioactive decay of the short-lived fission products. This decay assumptions used in the safety analyses.
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS of a fuel handling The Limiting Condition for Operation (LCO) limits the consequences fission product radioactivity for accident in containment by limiting the potential escape paths providing direct access from released within containment. The LCO requires any penetration closed except for the the containment atmosphere to the outside atmosphere to be alternate closure OPERABLE containment purge and exhaust penetrations, the approved methods and the containment personnel airlock.
that a designated For the approved alternate closure methods, the LCO requires individual must be available to close or direct the remote closure of the penetration in the at the penetration or event of a fuel handling accident. "Available" means stationedassociated with the penetration.
performing activities controlled by a procedure on equipment assurance that manual The inside containment fuel handling accident analysis provides size, within the assumed time, can be isolation of penetration valves up to a 12-inch diameterrespect to the 36-inch diameter CAP attained with the use of a designated individual. With would most likely exceed valves, a designated individual is not allowed since manual closure the assumed closure time.
For the personnel airlocks (containment or equipment hatch), the LCO ensures that the airlock can be closed after containment evacuation in the event of a fuel handling capable of being closed requires that the accident. The requirement that the airlock door is be easily and quickly removed.
door can be closed and is not blocked by objects that cannot for the door seals and sealing As an example, the use of removable protective covers individual located outside of the surfaces is permitted. The requirement for a designated containment will minimize airlock area available to close the door following evacuation of the the release of radioactive material.
both of the personnel The fuel handling accident analysis inside containment assumes (or equivalent area) is open.
airlock doors are open and an additional 12" diameter penetration the available activity is released The analysis is bounded by these assumptions since all of within a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period.
System ensures The OPERABILITY of the Containment Purge and Exhaust Isolation isolated upon detection that the containment vent and purge penetrations will be automatically of this system is required to of high radiation levels within the containment. The OPERABILITY atmosphere to the restrict the release of radioactive material from the containment environment.
B 3/4 9-2a Amendment No. 85 SEABROOK- UNIT I
3/4.9 REFUELING OPERATIONS (Continued)
BASES 3/4.9.9 (THIS SPECIFICATION NUMBER IS NOT USED.)
3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the safety analysis.
3/4.9.12 FUEL STORAGE BUILDING EMERGENCY AIR CLEANING SYSTEM The limitations on the Fuel Storage Building Emergency Air Cleaning System ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere.
Operation of the system with the heaters operating for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. The OPERABILITY of 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 procedural guide for surveillance testing.
3/4.9.13 SPENT FUEL ASSEMBLY STORAGE Restrictions on placement of fuel assemblies of certain enrichments within the Spent Fuel Pool is dictated by Figure 3.9-1. These restrictions ensure that the Keff 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 restrictions ensure that the Keff of the New Fuel Storage Vault will always remain less than 0.95 assuming the area to be flooded with unborated water. In addition, these restrictions ensure that the Keff of the New Fuel Storage Vault will 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 consistent with the criticality safety analysis performed for the New Fuel Storage Vault as documented in the FSAR.
SEABROOK - UNIT I B 3/4 9-4 Amendment No. 6, 8 5