ML041960439
| ML041960439 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 07/09/2004 |
| From: | NRC/NRR/DLPM/LPD2 |
| To: | |
| Moroney B, NRR/DLPM, 415-3974 | |
| Shared Package | |
| ML041920006 | List: |
| References | |
| TAC MB6627, TAC MB6628 | |
| Download: ML041960439 (4) | |
Text
INDEX LIST OF FIGURES (continued)
FIGURE PAGE 3.4-3 REACTOR CORE SYSTEM PRESSURE - TEMPERATURE LIMITATIONS FOR 21.7 EFPY, COOLDOWN AND INSERVICE TEST ...... 3/4 4-31b 3.4-4 REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITATIONS FOR 21.7 EFPY, MAXIMUM ALLOWABLE COOLDOWN RATES .3/4 4-32 4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST .3/4 7-25 5.1-1 SITE AREA MAP .5-2 5.6-1 a REQUIRED FUEL ASSEMBLY BURNUP vs INITIAL ENRICHMENT and DECAY TIME, REGION II, 1.3 w/o ........................ 5-4B 5.6-1b REQUIRED FUEL ASSEMBLY BURNUP vs INITIAL ENRICHMENT and DECAY TIME, REGION II, 1.5 w/o ........................... 5-4C 5.6-1 c REQUIRED FUEL ASSEMBLY BURNUP vs INITIAL ENRICHMENT and DECAY TIME, REGION I, 1.4 w/o .............................. 54DD 5.6-1d REQUIRED FUEL ASSEMBLY BURNUP vs INITIAL ENRICHMENT and DECAY TIME, REGION I, 1.82 w/o ............................ 5-4E 5.6-le REQUIRED FUEL ASSEMBLY BURNUP vs INITIAL ENRICHMENT, REGION I, 2.82 w/o............................................................................................ 5-4F 5.6-1f REQUIRED FUEL ASSEMBLY BURNUP vs INITIAL ENRICHMENT, REGION II CASK PIT STORAGE RACK .5-4G 6.2-1 DELETED .6-3 6.2-2 DELETED. 6-4 ST. LUCIE - UNIT 2 XXII Amendment No. 9,2 43,40, 4-2.
44i-:7 135
DESIGN FEATURES =
VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 10,931 + 275 cubic feet at a nominal Tavg of 572 0F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY 5.6.1 a. The spent fuel storage racks are designed and shall be maintained with:
- 1. A keff equivalent to less than 1.0 when flooded with unborated water, including a conservative allowance for biases and uncertainties as described in Section 9.1 of the Updated Final Safety Analysis Report.
- 2. A keff equivalent to less than or equal to 0.95 when flooded with water containing 520 ppm boron, including a conservative allowance for biases and uncertainties as described in Section 9.1 of the Updated Final Safety Analysis Report.
- 3. A nominal 8.96 inch center-to-center distance between fuel assemblies placed in the spent fuel pool storage racks and a nominal 8.80 inch center-to-center distance between fuel assemblies placed in the cask pit storage rack.
- 4. The cask pit storage rack shall contain neutron absorbing material (Boral) between stored fuel assemblies when installed in the spent fuel pool.
- b. Fuel placed in Region I of the spent fuel storage racks shall be stored in a configuration that will assure compliance with 5.6.1 a.1 and 5.6.1 a.2, above, with the following considerations:
- 1. Fresh fuel shall have a nominal average U-235 enrichment of less than or equal to 4.5 weight percent.
- 2. The reactivity effect of CEAs placed in fuel assemblies may be considered.
- 3. The reactivity equivalencing effects of burnable absorbers may be considered.
- 4. The reactivity effects of fuel assembly burnup and decay time may be considered as specified in Figures 5.6-1 c through 5.6-1 e.
- c. Fuel placed in Region II of the spent fuel storage racks shall be placed in a configuration that will assure compliance with 5.6.1 a.1 and 5.6.1 a.2, above, with the following considerations:
- 1. Fuel placed in the Region II spent fuel pool storage racks shall meet the burnup and decay time requirements specified in Figure 5.6-1 a or 5.6-1 b.
Fuel placed in the Region II cask pit storage rack shall meet the burnup requirements specified in Figure 5.6-1f.
- 2. The reactivity effect of CEAs placed in fuel assemblies may be considered.
- 3. The reactivity equivalencing effects of burnable absorbers may be considered.
ST. LUCIE - UNIT 2 54 Amendment No. ;, 5,44-1,135
DESIGN FEATURES (continued)
CRITICALITY (continued) 5.6.1 d. The new fuel storage racks are designed for dry storage of unirradiated fuel assemblies having a U-235 enrichment less than or equal to 4.5 weight percent, while maintaining a keff of less than or equal to 0.98 under the most reactive condition.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 56 feet.
CAPACITY 5.6.3 The spent fuel pool storage racks are designed and shall be maintained with a storage capacity limited to no more than 1360 fuel assemblies, and the cask pit storage rack is designed and shall be maintained with a storage capacity limited to no more than 225 fuel assemblies. The total Unit 2 spent fuel pool and cask pit storage capacity is limited to no more than 1585 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 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.
ST. LUCIE - UNIT 2 594A Amendment No.7, 4,135
40 0)M y
I-2 LL a) cm a)
Initial Fuel Enrichment, wt% U-235 FIGURE 5.6-1f REQUIRED FUEL ASSEMBLY BURNUP vs INITIAL ENRICHMENT REGION II CASK PIT STORAGE RACK ST. LUCIE - UNIT 2 5-4G Amendment No.135