ML021090603
| ML021090603 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/18/2002 |
| From: | NRC/NRR/DLPM |
| To: | |
| References | |
| TAC MB4231, TAC MB4232 | |
| Download: ML021090603 (11) | |
Text
INDEX DEFINITIONS SECTION PAGE 3/4.9 REFUELING OPERATIONS (Continued) 3/4.9.6 D E L E T E D........................................
3/4 9-6 3/4.9.7 D E L E T E D.............................................................................................................................
3/4 9-8 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION 3/4 9-9 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM 3/4 9-10 3/4.9.10 WATER LEVEL - REACTOR VESSEL 3/49-11 3/4.9.11 STORAGE POOL WATER LEVEL 3/4 9-12 3/4.9.12 STORAGE POOL VENTILATION SYSTEM 3/4 9-13 3/4.9.13 SPENT FUEL CASK MOVEMENT 3/4 9-17 3/4.9.14 SPENT FUEL CASK DROP PROTECTION SYSTEM 3/49-18 3/4.9.15 STORAGE POOL BORON CONCENTRATION 3/4 9-19 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 PRESSURE/TEMPERATURE LIMITATION-REACTOR CRITICALITY.......................
3/4 10-3 3/4.10.4 PH Y SIC S T E ST S..................................................................................................................
3/4 10-5 3/4.10.5 NATURAL CIRCULATION TESTS 3/4 10-6 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQ U ID H O LD U P TA N KS..................................................................................................
3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS E xplosive G as M ixture.........................................................................................................
3/4 11-2 G as Storage T anks.................................................................................................................
3/4 11-3 COOK NUCLEAR PLANT-UNIT 1 X
AMENDMENT 41=0, 9,267
INDEX DEFINITIONS SECTION PAGE 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.8 H Y D RA U LIC SN U BBERS..........................................................................................................
B 3/4 7-5a 3/4.8 ELECTRICAL POWER SYSTEMS B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 BO RON CO N CENTRA TION......................................................................................................
B 3/4 9-1 3/4.9.2 IN STR U M EN TA TIO N................................................................................................................
B 3/4 9-1 3/4.9.3 D E C A Y T IM E B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS......................................................................
B 3/4 9-1 3/4.9.5 C O M M U N ICA TIO N S..................................................................................................................
B 3/4 9-1 3/4.9.6 D E L E T E D B 3/4 9-2 3/4.9.7 D E L E T E D B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION..........................................
B 3/49-2 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 ST O RA G E PO O L.............................................................................................
B 3/4 9-3 3/4.9.12 STORAGE POOL VENTILATION SYSTEM............................................................................
B 3/4 9-3 3/4.9.13 SPENT FUEL CASK M OVEM ENT............................................................................................
B 3/4 9-4 3/4.9.14 SPENT FUEL CASK DROP PROTECTION SYSTEM..............................................................
B 3/4 9-4 3/4.9.15 STORAGE POOL BORON CONCENTRATION.......................................................................
B 3/4 9-4 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SH U TD OW N M A RG IN...............................................................................................................
B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS........................................................
B 3/4 10-1 AMENDMENT 2., 42, 473, 489, -28, 267 COOK NUCLEAR PLANT-UNIT I XIII
3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.9 REFUELING OPERATIONS 3.9.6 DELETED COOK NUCLEAR PLANT-UNIT 1 Page 3/4 9-6 AMENDMENT 267
3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.9 REFUELING OPERATIONS THIS PAGE INTENTIONALLY BLANK AMENDMENT 267 1
COOK NUCLEAR PLANT-UNIT 1 Page 3/4 9-7 I
3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.9 REFUELING OPERATIONS 3.9.7 DELETED AMENDMENT 1-04,4-3,486, 2-3, 267 COOK NUCLEAR PLANT-UNIT 1 Page 3/4 9-8
3/4 BASES 314.9 REFUELING OPERATIONS 3/4.9.6 DELETED 3/4.9.7 DELETED 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140OF as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effect of a boron dilution incident and prevent boron stratification.
The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability. With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.
3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment vent and purge penetrations will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.
COOK NUCLEAR PLANT-UNIT 1 Page B 3/4 9-2 AMENDMENT 78-,267 I; A*-i1 7?' 99,
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 23/4.9 REFUELING OPERATIONS (Continued) 3/4.9.6 D E L E T E D...............................................................................................................................
3/4 9-6 3/4.9.7 D E L E T E D...............................................................................................................................
3/4 9-7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION....................................
3/4 9-8 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM..................................
3/4 9-9 3/4.9.10 WATER LEVEL-REACTOR VESSEL..................................................................................
3/4 9-10 3/4.9.11 STORAGE POOL WATER LEVEL.......................................................................................
3/4 9-11 3/4.9.12 STORAGE POOL VENTILATION SYSTEM.......................................................................
3/4 9-12 3/4.9.13 SPENT FUEL CASK MOVEMENT.......................................................................................
3/4 9-16 3/4.9.14 SPENT FUEL CASK DROP PROTECTION SYSTEM.........................................................
3/4 9-17 3/4.9.15 STORAGE POOL BORON CONCENTRATION..................................................................
3/4 9-18 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SH U TD O W N M A RG IN..........................................................................................................
3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION L IM IT S....................................................................................................................................
3/4 10 -2 3/4.10.3 PH Y SIC S T E ST S....................................................................................................................
3/4 10-3 3/4.10.4 REACTOR COOLANT LOOPS..............................................................................................
3/4 10-4 3/4.10.5 POSITION INDICATOR CHANNELS - SHUTDOWN........................................................
3/4 10-5 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQ U ID H O LD U P TA N K S....................................................................................................
3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS E xplosive G as M ixture............................................................................................................
3/4 11-2 G as S torage T anks...................................................................................................................
3/4 11-3 COOK NUCLEAR PLANT-UNIT 2 X
AMENDMENT 0-4,-4--5,248
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.8 SEALED SOURCE CONTAMINATION..............................................................................
B 3/4 7-6 3/4.8 ELECTRICAL POWER SYSTEMS...........................................................................................
B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.................................................................................................
B 3/4 9-1 3/4.9.2 IN STR U M EN TA TIO N...........................................................................................................
B 3/4 9-1 3/4.9.3 D E C A Y T IM E.........................................................................................................................
B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS..................................................................
B 3/4 9-1 3/4.9.5 C O M M U N IC A TIO N S.............................................................................................................
B 3/4 9-1 3/4.9.6 D E L E T E D B 3/4 9-2 3/4.9.7 D E L E T E D B 3/4 9-2 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 9-3 3/4.9.10 and 3/4 9.11 WATER LEVEL - REACTOR VESSEL AND STORAGE POOL....................... B 3/4 9-3 3/4.9.12 STORAGE POOL VENTILATION SYSTEM.......................................................................
B 3/4 9-3 3/4.9.13 SPENT FUEL CASK MOVEMENT.......................................................................................
B 3/4 9-4 3/4.9.14 SPENT FUEL CASK DROP PROTECTION SYSTEM.........................................................
B 3/4 9-4 3/4.9.15 STORAGE POOL BORON CONCENTRATION..................................................................
B 3/4 9-4 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SH U TD O W N M A RG IN..........................................................................................................
B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS..........................
B 3/4 10-1 AMENDMENT -047, 46, 445,49-248 XIII COOK NUCLEAR PLANT-UNIT 2
3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.9 REFUELING OPERATIONS 3.9.6 DELETED AMENDMENT 248 COOK NUCLEAR PLANT-UNIT 2 Page 3/4 9-6
3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.9 REFUELING OPERATIONS 3.9.7 DELETED AMENDMENT 8, 96, 47,
-6, 248 COOK NUCLEAR PLANT-UNIT 2 Page 3/4 9-7
3/4 BASES 3/4.9 REFUELING OPERATIONS 3/4.9.6 DELETED 3/4.9.7 DELETED 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140OF as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effect of a boron dilution incident and prevent boron stratification.
The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability. With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.
COOK NUCLEAR PLANT-UNIT 2 AMENDMENT 248 Page B 3/4 9-2