ML17229B071

Proposed Tech Specs Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity, Per Soluble Boron Credit

ML17229B071
Person / Time
Site:	Saint Lucie
Issue date:	03/19/1999
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17229B070	List: ML17229B069 ML17229B071
References
NUDOCS 9903250099
Download: ML17229B071 (12)

Text

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LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/4.8.2 D.C. SOURCES OPERATING .3/4 8-10 SHUTDOWN .. .~...3/4 8-13

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3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS OPERATING ..... .3/4 8-14

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SHUTDOWN...................~............................ ~ .. . ..

~ ~ ~ ~ ~ ... ~ ~ ~ ~ . ~ . ~ ~... ~ . ~ ..3/4 8-16 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICES .............................. . ~ ~ ... ~ ~ ... . .... .~...3/4 8-1 7

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3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION ..3/4 9-1 3/4.9.2 INSTRUMENTATION.. .3/4 9-2 3/4 9.3 DECAY TIME........... ~ ........~......... ..~...~........~ ~ ~ .~ ., ..

~ ~ .~~ ., ~ ~ ..~....3/4 9-3 3/4.9.4 CONTAINMENTBUILDING PENETRATIONS .3/4 9-4 3/4.9.5 COMMUNICATIONS ....3/4 9-5 3/4.9.6 MANIPULATORCRANE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~~~~~ ~~~ ~~ ~~~~~~ 3/4 9 6 3/4.9.7 CRANE TRAVELSPENT FUEL STORAGE POOL BUILDING..~..... ~ ~ ~ .. . . ..

~ ~ ~ ~ ~ ..3/4 9-7 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL ...........;......~.........~... ~ .. ~ .~..........., ~ ..~... ~ ~ . ~ ..3/4 9-8 LOW WATER LEVEL .. . ~~ ~ .3/4 9-9 3/4.9.9 CONTAINMENTISOLATION SYSTEM. .....3/4 9-10 3/4.9.10 WATER LEVEL REACTOR VESSEL .~.~ ..3/4 9-11 3/4.9.11 SPENT FUEL STORAGE POOL ...3/4 9-12 3/4.9.12 SPENT FUEL CASK CRANE .3/4 9-13 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN . ...3/4 10-1 3/4.10.2 MODERATOR TEMPERATURE COEFFICIENT, GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS .....~..... ~ .~.~ .3/4 10-2 3/4.10.3 REACTOR COOLANT LOOPS 3/4 10-3

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3/4.10.4 CENTER CEA MISALIGNMENT........................... ..~......... ~ ......3/4 10-4 3/4.10.5 CEA INSERTION DURING ITC, MTC, AND POWER COEFFICIENT MEASUREMENTS ...~.... .. .~......3/4 10-5

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ST. LUCIE- UNIT2

~ IX Amendment No.

9903250099 9903i9 PDR ADOCK 050003S9 P POR j

INDEX LIST OF FIGURES Continued FIGURE PAGE 3.4-3 REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITATIONS FOR 15 EFPY, COOLDOWN AND INSERVICE TEST .. 3/4 4-31b 3.4-4 REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITATIONS FOR 15 EFPY, MAXIMUMALLOWABLECOOLDOWN RATES .........~............ 3/4 4-32 4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONALTEST .. 3/4 7-25 B 3/4.4-1 NIL-DUCTILITYTRANSITION TEMPERATURE INCREASE AS A FUNCTION OF FAST (E >1 MeV) NEUTRON FLUENCE (550'F IRRADIATION)FOR REACTOR VESSEL BELTLINE MATERIALS ....... B 3/4 4-10 5.1-1 SITE AREA MAP 5-2 5.6-1a REQUIRED FUEL ASSEMBLY BURNUP vs INITIALENRICHMENT and DECAY TIME, REGION II, 1.3 w/o 5-4B 5.6-1b REQUIRED FUEL ASSEMBLY BURNUP vs INITIALENRICHMENT and DECAY TIME, REGION II, 1.5 w/o ... ~... ~.............................~.......

~ ~ ~ ....... 5-4C 5.6-1c REQUIRED FUEL ASSEMBLY BURNUP vs INITIALENRICHMENT and DECAY TIME, REGION I, 1.4 w/o ~ 5-4D 5.6-1d REQUIRED FUEL ASSEMBLY BURNUP vs INITIALENRICHMENT and DECAY TIME, REGION I, 1.82 w/o .. 5-4E 5.6-1 e REQUIRED FUEL ASSEMBLY BURNUP vs INITIALENRICHMENT, R EGION ly 2e82 w/0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o 5 4F 6.2-1 DELETED. ~ ~ ~ ~ ~ ~ ~ I ~ ~~~~ ~~~~~~~~~ ~ I~ \~~~

6.2-2 DELETED. .. 6-4 ST. LUCIE- UNIT2 XXII Amendment No. 8,29,59

'EFUELING OPERATIONS 3/4.9.11 SPENT FUEL STORAGE POOL 3.9.11 The Spent Fuel Storage Pool shall be maintained with:

a. The fuel storage pool water level greater than or equal to 23 ft over the top of irradiated fuel assemblies seated in the storage racks, and

b. The fuel storage pool boron concentration greater than or equal to 1720 ppm.

APPLICABILITY: Whenever irradiated fuel assemblies are in the spent fuel storage pool.

ACTION:

a. With the water level requirement not satisfied, immediately suspend all movement of fuel assemblies and crane operations with loads in the fuel storage areas and restore the water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

b. With the boron concentration requirement not satisfied, immediately suspend ail movement of fuel assemblies in the fuel storage pool and initiate action to restore fuel storage pool boron concentration to within the required limit.

c. The provisions of Specification 3.0.3 are not applicable.

4.9.11 The water" level in the spent fuel storage pool shall be determined to be at least its minimum required depth at least once per 7 days when irradiated fuel assemblies are in the fuel storage pool ~

4.9.11.1 Verify the fuel storage pool boron concentration is within limit at least once per 7 days.

ST. LUCIE- UNIT2 3/4 9-12 Amendment No.

'1 REFUELING OPERATIONS SFS 3/4.9.10 and 3/4.9.11 WATER LEVEL-REACTOR VESSEL and SPENT FUEL 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.

The limit on soluble boron concentration in LCO 3/4.9.11 is consistent with the minimum boron concentration specified for the RWT, and assures an additional subcritical margin to the value of kefI which is calculated in the spent fuel storage pool criticality safety analysis to satisfy the acceptance criteria of Specification 5.6.1. Inadvertent dilution of the spent fuel storage pool by the quantity of unborated water necessary to reduce the pool boron concentration to a value that would invalidate the criticality safety analysis is not considered to be a credible event. The surveillance frequency specified for verifying the boron concentration is consistent with NUREG-1432 and satisfies, in part, acceptance criteria established by the NRC staff for approval of criticality safety analysis methods that take credit for soluble boron in the pool water. The ACTIONS required for this LCO are designed to preclude an accident from happening or to mitigate the consequences of an accident in progress, and shall not preclude moving a fuel assembly to a safe position.

3/4.9.12 SPENT FUEL CASK CRANE The maximum toad which may be handled by the spent fuel cask crane is limited to a loaded multi-element cask which is equivalent to approximately 100 tons. This restriction is provided to ensure the structural integrity of the spent fuel pool in the event of a dropped cask accident. Structural damage caused by dropping a load in excess of a loaded multi-element cask could cause leakage from the spent fuel pool in excess of the maximum makeup capability.

ST. LUCIE - UNIT 2 8 3/4 9-3 Amendment No.

I3ESIGN FEATURES VOLUME 5.4.2 . The total water and steam volume of the reactor coolant system is 10,931 k 275 cubic feetatanominalT, of572'F.

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 pool and spent fuel storage racks shall be maintained with:

1. A k,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 k,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 storage racks.

5.6.1 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 5.6-1c through 5.6-1e.

5.6.1 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:

Fuel placed in Region II shall meet the burnup and decay time requirements specified in Figure 5.6-1 a or 5.6-1b.

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 5-4 Amendment No. %,95

DESIGN FEATURES 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 k,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 storage pool is designed and shall be maintained with a storage capacity limited to no more than 1360 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 5-4A Amendment No: 2

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o Ill Figure 5.6-1 a K

=I Required Fuel Assembly Burnup vs Initial Enrichment and Decay Time lO Region II, 1.3 w/o 50000 n 0 years C

CD 5 years 40000 Acceptable Burnup 15 years 2

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