ML072040316

Tech Spec Pages for Amendments 234 and 229 Regarding Spent Fuel Pool Boraflex Remedy

ML072040316
Person / Time
Site:	Turkey Point
Issue date:	07/17/2007
From:	NRC/NRR/ADRO/DORL/LPLII-2
To:
Mozafari B, NRR/ADRO/DORL, 415-2020
Shared Package
ML071800411	List: ML071800198 ML072040316
References
TAC MC9740, TAC MC9741
Download: ML072040316 (19)

Text

3 E. Pursuant to the Act and 10 CFR Parts 40 and 70 to receive, possess, and use at any time 100 milligrams each of any source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactively contaminated apparatus; F. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by-the operation of Turkey Point Units Nos. 3 and 4.

3. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect, and is subject to the additional conditions specified below:

A. Maximum Power Level The applicant is authorized to operate the facility at reactor core power levels not in excess of 2300 megawatts (thermal).

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.234 are hereby incorporated into this renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

c. Final Safety Analysis Report The licensee's Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on November 1, 2001, describes certain future inspection activities to be completed before the period of extended operation.

The licensee shall complete these activities no later than July 19, 2012.

The Final Safety Analysis Report supplement as revised on November 1, 2001, described above, shall be included in the next scheduled update to the Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following the issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

Unit 3 Renewed License No. DPR-31 Amendment No. 234

3 E. Pursuant to the Act and 10 CFR Parts 40 and 70 to receive, possess, and use at any time 100 milligrams each of any source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactively contaminated apparatus; F. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of Turkey Point Units Nos. 3 and 4.

3. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect, and is subject to the additional conditions specified below:

A. Maximum Power Level The applicant is authorized to operate the facility at reactor core power levels not in excess of 2300 megawatts (thermal).

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 229 are hereby incorporated into this renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

C. Final Safety Analysis Report The licensee's Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on November 1,2001, describes certain future inspection activities to be completed before the period of extended operation.

The licensee shall complete these activities no later than April 10, 2013.

The Final Safety Analysis Report supplement as revised on November 1, 2001, described above, shall be included in the next scheduled update to the Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following the issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

Unit 4 Renewed License No. DPR-41 Amendment No. 229

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM ................................ 3/4 9-10 3/4.9.10 W ATER LEVEL - REACTOR VESSEL ......................................................... 3/49-11 3/4.9.11 WATER LEVEL - STORAGE POOL ............................. 3/4 9-12 3/4.9.12 HANDLING OF SPENT FUEL CASK ............................................................ 3/4 9-13 3/4.9.13 RADIATIO N MO NITO RING .......................................................................... 3/4 9-14 3/4.9.14 SPENT FUEL STO RAG E ............................................................................. 3/4 9-15 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOW N MARGIN ................................................................................. 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS ....... 3/4 10-2 3/4.10.3 P HY S IC S T E S T S ......................................................................................... 3/4 10-3 3/4.10.4 (This specification number is not used) ......................................................... 3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN ........................................ 3/4 10-5 TURKEY POINT -7 UNITS 3 & 4 xiii AMENDMENT NOS. 234 AND 229

flNDEX DESIGN FEATURES SECTION PAGE 5.1 SITE 5 .1.1 S IT E LO C AT IO N ......................................................................................................... 5-1 5.2 CONTAINMENT 5.2 .1 C O NF IG URA T IO N ...................................................................................................... 5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE .............................................................. 5-1 5.3 REACTOR CORE 5 .3.1 F UE L A S S E MB LIE S ................................................................................................... 5-4 5.3.2 CO NTRO L RO D ASSEM BLIES .................................................................................. 5-4 5.4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE .............................................................. 5-4 5.4.2 VOLUME. ............................ ........................... 5-4 5.5 FUEL STORAGE 5 .5 .1 C R IT ICA LIT Y .............................................................................................................. 5-5 5 .5 .2 D R A INA G E ................................................................................................................. 5-6 5 .5 .3 CA P A C ITY .................................................................................................................. 5-6 TABLE 5.5-1 BLANKETED FUEL - MINIMUM REQUIRED FUEL ASSEMBLY BURNUP (Bu) AS A FUNCTION OF ENRICHMENT (En) AND COOLING TIME (Ct).. 5-7 TABLE 5.5-2 NON-BLANKETED FUEL - MINIMUM REQUIRED FUEL ASSEMBLY BURNUP (Bu) AS A FUNCTION OF ENRICHMENT (En) AND COOLING TIME (Ct) ................................................ 5-10 TABLE 5.5-3 FUEL CATEGORIES RANKED BY REACTIVITY ......................................... 5-13 FIGURE 5.5-1 ALLOWABLE REGION I STORAGE ARRAYS ............................................. 5-14 FIGURE 5.5-2 ALLOWABLE REGION II STORAGE ARRAYS ............................................ 5-15 FIGURE 5.5-3 ALLOWABLE INTERFACES BETWEEN REGION II- REGION I ARRAYS. 5-16 FIGURE 5.5-4 ALLOWABLE REGION II STORAGE ADJACENT TO SPENT FUEL PIT W A LLS ......................................................................................................... 5 -17 5.6 COMPONENT CYCLIC OR TRANSIENT LIMIT .......................................................... 5-18 TABLE 5.6-1 COMPONENT CYCLIC OR TRANSIENT LIMITS ......................................... 5-19 TURKEY POINT - UNITS 3 & 4 xiV AMENDMENT NOS. 234 AND 229

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met; either:

a. A Keff of 0.95 or less, or

b. A boron concentration of.greater than or equal to 1950 ppm.

APPLICABILITY: MODE 6.*

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 16 gpm of a solution containing greater than or equal to 3.0 wt% (5245 ppm) boron or its equivalent until Keff is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 1950 ppm, whichever is the more restrictive.

SURVEILLANCE REQUIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:

a. Removing or unbolting the reactor vessel head, and

b. Withdrawal of any full-length control rod in excess of 3 feet from its fully inserted position within the reactor vessel.

4.9.1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

4.9.1.3 Valves isolating unborated water sources** shall be verified closed and secured in position by mechanical stops or by removal of air or electrical power at least once per 31 days.

• The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

• • The primary water supply to the boric acid blender may be opened under administrative controls for makeup.

TURKEY POINT - UNITS 3 & 4 3/4 9-1 AMENDMENT NOS. 234 AND 229

REFUELING OPERATIONS 3/4.9.14 SPENT FUEL STORAGE LIMITING CONDITION FOR OPERATION 3.9.14 The following conditions shall apply to spent fuel storage:

a. The minimum boron concentration in the Spent Fuel Pit shall be 1950 ppm.

b. The combination of initial enrichment, burnup, and cooling time of each fuel assembly stored in the Spent Fuel Pit shall be in accordance with Specification 5.5.1.

APPLICABILITY: At all times when fuel is stored in the Spent Fuel Pit.

ACTION:

a. With boron concentration in the Spent Fuel Pit less than 1950 ppm, suspend movement of spent fuel in the Spent Fuel Pit and initiate action to restore boron concentration to 1950 ppm or greater.

b. With condition b not satisfied, suspend movement of additional fuel assemblies into the Spent Fuel Pit and restore the spent fuel storage configuration to within the specified conditions.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEI LLANCE REQUIREMENTS 4.9.14.1 The boron concentration of the Spent Fuel Pit shall be verified to be 1950 ppm or greater at least once per month.

4.9.14.2 A representative sample of inservice Metamic inserts shall be visually inspected in accordance with the Metamic Surveillance Program described in UFSAR Section 16.2. The surveillance program ensures that the performance requirements of Metamic are met over the surveillance interval.

TURKEY POINT - UNITS 3 & 4 3/4 9-15 AMENDMENT NOS. 234 AND 229

DESIGN FEATURES 5.5 FUEL STORAGE 5.5.1 CRITICALITY 5.5.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. A keff less than 1.0 when flooded with unborated water, which includes an allowance for biases and uncertainties as described in UFSAR Chapter 9.

b. A keff less than or equal to 0.95 when flooded with water borated to 650 ppm, which includes an allowance for biases and uncertainties as described in UFSAR Chapter 9.

c. A nominal 10.6 inch center-to-center distance for Region I and 9.0 inch center-to-center distance for Region II for the two region spent fuel pool storage racks. A nominal 10.1 inch center-to-center distance in the east-west direction and a nominal 10.7 inch center-to-center distance in the north-south direction for the Region I cask area storage rack.

d. A maximum enrichment loading for fuel assemblies of 4.5 weight percent of U-235.

e. No restriction on storage of fresh or irradiated fuel assemblies in the cask area storage rack.

N

f. Fresh or irradiated fuel assemblies not stored in the cask area storage rack shall be stored in accordance with Specification 5.5.1.3 or configurations that have been shown to comply with Specification 5.5.1 .la and 5.5.1.1 b using the NRC approved methodology in UFSAR Chapter 9.

5.5.1.2 The racks for new fuel storage are designed to store fuel in a safe subcritical array and shall be maintained with:

a. A nominal 21 inch center-to-center spacing.to assure keff equal to or less than 0.98 for optimum moderation conditions and equal to or less than 0.95 for fully flooded conditions.

b. Fuel assemblies placed in the New Fuel Storage Area shall contain no more than 4.5 weight percent of U-235.

TURKEY POINT - UNITS 3 & 4 5-5 AMENDMENT NOS. 234 AND 229

DESIGN FEATURES 5.5.1.3 Credit for burnup and cooling time is taken in determining acceptable placement locations for spent fuel in the two-region spent fuel racks. Fresh or irradiated fuel assemblies shall be stored in compliance with the following:

a. Any 2x2 array of Region I storage cells containing fuel shall comply with the storage patterns in Figure 5.5-1 and the requirements of Table 5.5-1 and 5.5-2, as applicable. The reactivity rank of fuel assemblies in the 2x2 array (rank determined using Table 5.5-3) shall be equal to or less than that shown for the 2x2 array.

b. Any 2x2 array of Region II storage cells containing fuel shall:

i. Comply with the storage patterns in Figure 5.5-2 and the requirements of Table 5.5-1 and 5.5-2, as applicable. The reactivity rank of fuel assemblies in the 2x2 array (rank determined using Table 5.5-3) shall be equal to or less than that shown for the 2x2 array, ii. Have the same directional orientation for Metamic inserts in a contiguous group of 2x2 arrays where Metamic inserts are required, iii. Comply with the requirements of 5.5.1.3.c for cells adjacent to Region I racks, and iv. Comply with the requirements of 5.5.1.3.d for cells adjacent to the spent fuel pit walls.

c. Any 2x2 array of Region II storage cells that interface with Region I shall comply with the rules of Figure 5.5-3. Arrays II-E and Il-F may interface with Region I without special restriction.

d. Any 2x2 array of Region II storage cells may adjoin a row of assemblies with a reactivity rank of 11-2 (or lower) that is located in the outer row adjacent to the spent fuel pit wall. The outer row of reactivity rank 11-2 (or lower) fuel assemblies need not contain any Metamic inserts or full length RCCAs, as long as the following additional requirements are met:

i. Fuel is loaded to comply with the allowable storage patterns defined in Figure 5.5-4, and ii. Arrays II-E and II-F are loaded without any additional restriction on that 2x2 array. Arrays II-E and II-F do not have empty cells, Metamic inserts, or RCCAs that restrict the interface with the adjoining reactivity rank 11-2 (or lower) fuel assemblies.

DRAINAGE 5.5.2 The spent fuel storage pit is designed and shall be maintained to prevent inadvertent draining of the pool below a level of 6 feet above the fuel assemblies in the storage racks.

CAPACITY 5.5.3 The spent fuel pool storage racks are designed and shall be maintained with a storage capacity limited to no more than 1404 fuel assemblies in two region storage racks, and the cask area storage rack is designed and shall be maintained with a storage capacity limited to no more than 131 fuel assemblies. The total spent fuel pool storage capacity is limited to no more than 1535 fuel assemblies.

TURKEY POINT - UNITS 3 & 4 5-6 AMENDMENT NOS. 234 AND 229

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Table 5.5-1 Blanketed Fuel - Minimum Required Fuel Assembly Burnup (Bu) as a Function of Enrichment (En) and Cooling Time (Ct) 0 See note 1 for use of Table 5.5-1 z

--i Fuel Blanketed Fuel Blanketed Fuel Category Storage Curve Coefficients1 Minimum Burnup' (GWd/MTU) for Initial Enrichmene A B C D __ E_ ___ F G

__ _ Time g Cooin _2.5_ w%

_ 3.0 w% 3.3 w% 4.0 w% 4.5 w%

1-14 NIA N/A N/A N/A N/A N/A N/A NIA N/A N/A N/A N/A N/A 1-2 18.8602 -1.090486 0.266387 -0.00474496 -0.158563 0.00314739 -30.1637 0 10.17 16.60 20.20 27.83 32.62 2.5 9.87 16.11 19.59 26.96 31.57 5 9.60 15.67 19.06 26.19 30.62 10 9.18 14.98 18.20 24.94 29.10 15 8.92 14.52 17.62 24.08 28.04 20 8.82 14.30 17.32 23.61 27.45 I1-1 16.2639 -0.712257 0.175883 -0.00399237 -0.166686 0.00370969 -19.5118 0 16.70 22.87 26.40 34.15 39.25 2.5 16.13 22.10 25.52 32.99 37.90 5 15.62 21.43 24.74 31.96 36.70 10 14.82 20.34 23.49 30.32 34.78 15 14.27 19.61 22.65 29.23 33.50 20 13.99 19.24 22.22 28.67 32.85-11-2 14.4600 -0.372732 0.132275 -0.00617104 -0.187813 0.00526411 -12.8293 0 20.99 27.20 30.83 39.05 44.69 2.5 20.19 26.18 29.68 37.59 43.02 5 19.48 25.28 28.67 36.32 41.57 10 18.32 23.85 27.07 34.35 39.32 15 17.50 22.89 26.04 33.11 37.94 20 17.04 22.42 25.56 32.62 37.44 11-3 15.4624 -0.501267 -0.06553 0.00160009 -0.161078 0.00340497 -11.2483 0 24.27 30.63 34.32 42.58 48.18 2.5 23.17 29.33 32.91 40.90 46.31 5 22.19 28.18 31.65 39.41 44.65 10 20.60 26.32 29.63 37.00 41.97 15 19.53 25.05 28.25 35.36 40.13 20 18.96 24.38 27.51 34.47 39.14

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0; Table 5.5-1 (continued) m Blanketed Fuel - Minimum Required Fuel Assembly Burnup (Bu) as a Function of Enrichment (En) and Cooling Time (Ct) 0 See note 1 for use of Table 5.5-1 z

Fuel Blanketed Fuel Blanketed Fuel C Category Storage Curve Coefficients' Minimum Burnup' (GWd/MTU) for Initial Enrichment2 z A B D EF G Cooling A B C D E F G 3imeg 2.5 w% 3.0 w% 3.3 w% 4.0 w% 4.5 w%

CA) 11-4 15.3172 -0.444842 -0.114363 0.00273060 -0.162664 0.00344467 -9.1868 0 26.33 32.76 36.52 44.96 50.73 2.5 25.09 31.34 34.98 43.16 48.73 5 24.00 30.08 33.61 41.55 46.96 10 22.25 28.04 31.41 38.97 44.09 15 21.06 26.67 29.92 37.20 42.14 20 20.44 25.94 29.13 36.27 41.10 90 11-5 15.1701 -0.387768 -0.163521 0.00394514 -0.164014 0.00345174 -7.1273 0 28.37 34.89 38.71 47.35 53.29 2.5 27.02 33.34 37.05 45.41 51.15 5 25.82 31.97 35.57 43.69 49.26 10 23.90 29.77 33.20 40.93 46.22 15 22.60 28.28 31.59 39.05 44.14 20 21.93 27.50 30.75 38.06 43.05 00 11-6 13.4516 -0.078364 -0.266734 0.00288411 -0.147006 0.00446530 -3.3460 0 29.79 36.30 40.19 49.21 55.60

- 2.5 28.30 34.64 38.42 47.20 53.42 5 26.97 33.17 36.87 45.45 51.53 10 24.86 30.85 34.43 42.73 48.61 15 23.44 29.35 32.88 41.05 46.85 m 20 22.73 28.66 32.20 40.41 46.23 z

11-7 13.7900 -0.086680 -0.355570 0.00574698 -0.145745 0.00426994 -2.0705 0 31.86 38.52 42.49 51.70 58.23 m 2.5 30.17 36.65 40.53 49.50 55.86 z 5 28.67 35.02 38.81 47.58 53.80 z 10 26.31 32.45 36.11 44.60 50.61 0 15 24.76 30.80 34.41 42.76 48.67 20 24.03 30.09 33.70 42.06 47.99 CA) z 0

(0

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m Table 5.5-1 (continued)

Blanketed Fuel - Minimum Required Fuel Assembly Burnup (Bu) as a Function of Enrichment (En) and Cooling Time (Ct) 0 See note 1 for use of Table 5.5-1 zZ.--

Fuel Blanketed Fuel Blanketed Fuel C Category Storage Curve Coefficients 1 Minimum Burnup1 (GWd/MTU) for Initial Enrichment 2 z A B C D E F G Cooling 2.5 w% 3.0 w% 3.3 w% 4.0 w% 4.5 w%

.-I

0) Time 11-8 14.1212 -0.094016 -0.448138 0.00877894 -0.143511 0.00402944 -0.7808 0 33.93 40.74 44.80 54.20 60.86 2.5 32.04 38.67 42.63 51.80 58.29

{6_ 5 30.37 36.86 40.74 49.71 56.06

, ,_ _10 27.75 34.04 37.79 46.47 52.61 15 26.07 32.25 35.94 44.47 50.51 20 25.34 31.51 35.19 43.71 49.75 Notes

.0 1. All relevant uncertainties are explicitly included in the criticality analysis. For instance, no additional allowance for burnup uncertainty is required. For a fuel assembly to meet the requirements of a Fuel Category, the assembly burnup must exceed the "minimum burnup" given in the table for the assembly "cooling time" and "initial enrichment." Alternatively, the specific minimum burnup required for each fuel assembly may be calculated from the following equation: Bu = A x En + B x En2 + C x Ct + D x Ct + E x Ct x En + F x Ct2 x En + G. Only cooling times of 0, 2.5, 5, 10, 15 and 20 years may be used in this equation. Actual cooling time (Ct) is rounded down to the nearest value.

2. Nominal central zone U-235 enrichment: Axial blanket material is not considered when determining enrichment.

m 3. Cooling time in years.

Z

4. Fresh unburned fuel up to 4.5 w% U-235 enrichment: No burnup is required.

0 0

W)

CD

C m

Table 5.5-2 Non-Blanketed Fuel - Minimum Required Fuel Assembly Burnup (Bu) as a Function of Enrichment (En) and Cooling Time (Ct)

See note 1 for use of Table 5.5-2 Fuel Non-Blanketed Fuel Non-Blanketed Fuel Category Storage Curve Coefficients' Minimum Burnup' (GWd/MTU) for Initial Enrichment2 A B C D E F G Cooling 1.8 2.5 3.0 3.5 4.0 Time w% w% w% w% w%

I-14 N/A N/A N/A N/A N/A NIA N/A N/A N/A NIA N/A N/A N/A 1-2 18.1371 -0.944126 0.253120 -0.00553408 -0.151450 0.00334051 -29.3574 0 0.23 10.08 16.56 22.56 28.08 2.5 0.18 9.79 16.08 21.90 27.25 5 0.14 9.53 15.66 21.33 26.52 10 0.08 9.11 14.99 20.40 25.34 15 0.05 8.84 14.55 19.79 24.56 20 0.03 8.70 14.33 19.48 24.16 Il-1 11.9800 0.158287 0.237665 -0.00688305 -0.192273 0.00492032 -14.2029 0 7.87 16.74 23.16 29.67 36.25 2.5 7.62 16.16 22.36 28.64 35.00 5 7.38 15.66 21.66 27.75 33.91 10 6.99 14.85 20.56 26.35 32.22 15 6.69 14.31 19.85 25.46 31.16

• 20 6.49 14.04 19.53 25.10 30.74 11-2 11.8419 0.287918 0.113820 -0.00527641 -0.175033 0.00507248 -9.9305 0 12.32 21.47 28.19 35.04 42.04 2.5 11.84 20.71 27.22 33.87 40.67 5 11.41 20.04 26.38 32.86 39.49 10 10.69 18.98 25.07 31.30 37.68 15 10.17 18.28 24.25 30.37 36.63 20 9.83 17.96 23.94 30.06 36.32 11-3 12.6055 0.361578 -0.075193 0.00118870 -0.152297 0.00386780 -8.6212 0 15.24 25.15 32.45 39.93 47.59 2.5 14.42 24.08 31.20 38.50 45.98 5 13.70 23.14 30.11 37.25 44.58 10 12.56 21.68 28.41 35.32 42.41 15 11.83 20.76 27.35 34.12 41.07 20 11.51 20.38 26.92 33.65 40.56

Table 5.5-2 (continued)

_ Non-Blanketed Fuel - Minimum Required Fuel Assembly Bumup (Bu) as a Function of Enrichment (En) and Cooling Time (Ct) z See note 1 for use of Table 5.5-2 C Fuel Non-Blanketed Fuel Non-Blanketed Fuel z Category Storage Curve Coefficients' Minimum BumupI (GWd/MTU) for Initial Enrichmente A B C D E F G Cooling3 1.8 2.5 3.0 3.5 4.0 Time w% w% w% w% w%

.0 11-4 12.6130 0.436168 -0.128105 0.00275389 -0.151579 0.00377707 -7.0392 0 17.08 27.22 34.73 42.45 50.39 2.5 16.13 26.03 33.36 40.90 48.67 5 15.31 24.99 32.16 39.56 47.17 10 14.02 23.37 30.31 37.46 44.83 15 13.21 22.36 29.15 36.16 43.39 20 12.88 21.96 28.70 35.67 42.85 11-5 12.6086 0.517311 -0.185177 0.00442008 -0.150482 0.00367344 -5.3438 0 19.03 29.41 37.14 45.12 53.37 2.5 17.96 28.09 35.64 43.45 51.52 5 17.02 26.94 34.34 42.00 49.91 10 15.57 25.16 32.32 39.73 47.41 15 14.67 24.05 31.06 38.33 45.86 20 14.32 23.62 30.58 37.80 45.27 11-6 17.1055 -0.116940 0.024104 -0.00410005 -0.262366 0.00761230 -10.7361 0 19.67 31.30 39.53 47.70 55.81 2.5 18.61 29.81 37.74 45.61 53.42 65 17.67 28.51 36.18 43.79 51.35

> 10 16.15 26.47 33.77 41.01 48.20 K_ 15 15.11 25.18 32.30 39.36 46.36 z 20 14.55 24.63 31.76 38.83 45.85 117 17.5099 -0.130912 .0.143634 0.00199657 -0.235656 0.00625103 -9.1041 0 21.99 33.85 42.25 50.58 58.84 z 2.5 20.65 32.13 40.25 48.31 56.29

- 5 19.48 30.63 38.51 46.33 54.08 0 10 17.64 28.29 35.82 43.28 50.68 15 16.45 26.83 34.16 41.42 48.62 20 15.93 26.25 33.64 40.76 47.92

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m Table 5.5-2 (continued)

Non-Blanketed Fuel - Minimum Required Fuel Assembly Burnup (Bu) as a Function of Enrichment (En) and Cooling Time (Ct)

See note 1 for use of Table 5.5-2 Fuel Non-Blanketed Fuel Non-Blanketed Fuel Category Storage Curve Coefficients 1 Minimum Burnupl (GWd/MTU) for Initial Enrichmente A B C D E F G Cooling 1.8 2.5 3.0 3.5 4.0 Time 3 w% w% w% w% w%

11-8 17.9109 -0.143928 -0.308137 0.00796481 -0.209912 0.00492410 -7.4704 0 24.30 36.41 44.97 53.45 61.87 2.5 22.69 34.45 42.76 51.01 59.17 5 21.29 32.75 40.85 48.87 56.82 10 19.13 30.11 37.86 45.55 53.16 15 17.80 28.48 36.01 43.48 50.88 20 17.31 27.86 35.30 42.68 49.98 Notes

1. All relevant uncertainties are explicitly included in the criticality analysis. For instance, no additional allowance for burnup uncertainty is required. For a fuel assembly to meet the requirements of a Fuel Category, the assembly burnup must exceed the "minimum burnup" given in the table for the assembly "cooling time" and "initial enrichment." Alternatively, the specific minimum burnup required for each fuel assembly may be calculated from the following equation: Bu = A x En + B x En 2 + C x Ct + D x Ct 2+E x Ct x En + F x Ct2 x En + G. Only cooling times of 0, 2.5, 5, 10, 15 and 20 years may be used in this equation. Actual cooling time (Ct) is rounded down to the nearest value.

2. Nominal U-235 enrichment.

m z 3. Cooling time in years.

m 4. Fresh unirradiated fuel up to 4.5 w% U-235 enrichment: No burnup is required.

z z

0 z

(0

Table 5.5-3 Fuel Cateqories Ranked by Reactivity1 Fuel Category Region I Region II I-1 I1-1 1-2 11-2 11-3 11-4 11-5 11-6 11-7 11-8 Notes

1. Reactivity Rank: Fuel Category is ranked in decreasing order of reactivity, e.g. 11-2 is less reactive than I1-1, etc.

TURKEY POINT - UNITS 3 & 4 5-13 AMENDMENT NOS. 234 AND 229

FIGURE 5.5-1 ALLOWABLE REGION I STORAGE ARRAYS 14 1 2 34 DEFINITION ' ILLUSTRATION ' ,'

Array I-A Checkerboard pattern of Category I-1 assemblies and empty (water filled) cells.

El Array I-B Category 1-2 assembly in every cell. II2I~II Array I-C Category I-1 assemblies and Category 1-2 assemblies:

Each Category I-1 assembly shall have a full length RCCA in the assembly. The number of Category I-1 assemblies ~jj~jh~jj~j ~jH~jj~j with RCCAs in the assemblies is unrestricted.

Notes:

1. Fuel Categories are determined from Tables 5.5-1 and 5.5-2.

2. Shaded cells indicate the fuel assembly contains a full length RCCA.

3. E indicates an empty (water filled) cell.

4. Attributes for each 2x2 array are as stated in the definition. Diagram is for illustrative purposes only.

TURKEY POINT - UNITS 3 & 4 5-14 AMENDMENT NOS. 234 AND 229

FIGURE 5.5-2 ALLOWABLE REGION II STORAGE ARRAYS 14 12 34 DEFINITION ' ILLUSTRATION , , ,

Array Il-A 1 Category I1-1 assembly in three of every four cells: Il-I I1-1 One of every four cells is empty (water-filled). 11-1 E Array II-B Category 11-2 assembly in every cell: Two of every four cells contain a [1-2 1 1,2 [E1-2 1-2 Metamic insert (or full length RCCA in the assembly). 11-2 1 1 11-2 ] Ml-1 Array II-C 11-3 11-5 11-5 11-3 Checkerboard pattern of Category 11-3 and 11-5 assemblies:

One of every four cells contains a Metamic insert (or full length 11-5[11.3 1311-6' RCCA in the assembly). Metamic inserts (or RCCAs) may be in either 11-3 or 11-5 cells.

Array II-D Category 11-4 assembly in every cell: One of every four 11-4 11-4 cells contains a Metamic insert (or full length RCCA in the 11-4 11-4 assembly).

Array II-E 11-8 11-6 Checkerboard pattern of Category 11-6 and 11-8 assemblies. 11-6 11-8 Array Il-F Category 11-7 assembly in every cell. 11-7117

[1-7j11-7 Notes:

1. Fuel Categories are determined from Tables 5.5-1 and 5.5-2.

2. Shaded cells indicate either a Metamic insert in the cell or the fuel assembly contains a full length RCCA.

3. E indicates an empty (water filled) cell.

4. Attributes for each 2x2 array are as stated in the definition. Diagram is for illustrative purposes only.

TURKEY POINT - UNITS 3 & 4 5-15 AMENDMENT NOS. 234 AND 229

FIGURE 5.5-3 ALLOWABLE INTERFACES BETWEEN REGION II - REGION I ARRAYS 1 2 345 DEFINITION1'4 ILLUSTRATION ' , , ,

Region I Rack

[-2 1-2 1-2 1-2 For Array Il-A, the empty cell shall be in 1-2 1-2 1-2 1-2 the row adjacent to the Region I Rack.

11-1 E 11-1 E I1-1_ Il-1 I1- I1-1__

Array II-A Region I Rack Region I Rack Region I Rack 1-2 1-2 1-2 1-2 1-2 1-2 1-2 1-2 1-2 1-2 1-2 1-2 For Array Il-B, the reactivity rank of 1-2 11-2 -21 1-2 1-2 1-2 1-2 1-2 1-2 1-2 1-2 1-2 assemblies adjacent to the Region I rack shall be reduced from a rank of 11-2 to a 11-4 4 11-4 11-4 11-4 11-4 11-4 11-4 11-4 11-4 11-4 11-4 reactivity rank of 11-4 or lower. The Array Il-B pattern shall have the required 11-2 J11-2 111-2 111-2 11-2 11-2 11-2 11-2 11-2 11-2 11-2 11-2 Metamic insert (or full length RCCA in the Array Il-B Array Il-B Array Il-B assembly) placed in the row adjacent to the Region I rack.

Region I Rack Region I Rack Region I Rack 1-2 1-2 1-2 1-2 - 1-

-2 1-2 1-2 1-2 1-2 1-2 1-2 1-2 1-2-2 1 1-2 1-2 2I: 1-2 1-2 1-2 For Arrays Il-C and II-D, the Metamic insert (or full length RCCA in the 11-3 '11-5 11-3 11-5 11-5 111-3 11-5 111-3 1 11-4 11-4 11-4 11-4 assembly) shall be placed in the row 11-5 11-3 11-5 11-3 1 11-5 11-4 11-4 1 1-4 1-4 adjacent to the Region I rack.

Array Il-C Array Il-C Array 11-D Notes:

1. Fuel Categories are determined from Tables 5.5-1 and 5.5-2.

2. Shaded cells indicate either a Metamic insert in the cell or the fuel assembly contains a full length RCCA.

3. E indicates an empty (water filled) cell.

4. Attributes for each 2x2 array are as stated in the definition. Diagram is for illustrative purposes only.

5. Region I Array 1-2 is depicted as the example; however, any Region I array is equally representative.

TURKEY POINT - UNITS 3 & 4 5-16 AMENDMENT NOS. 234 AND 229

FIGURE 5.5-4 ALLOWABLE REGION II STORAGE ADJACENT TO SPENT FUEL PIT WALLS 4 1 23 DEFINITION"1 ILLUSTRATION ' ' ,4 Spent Fuel Pit Wall An assembly of rank 11-2 placed in the II-2 1-2 I1-2 II1-3 1-2 1-2 1-2 1-2 1-2 1-2 1-2 1-2 peripheral row of a Region II storage 11-3 11-5 113 -5 1-2 1-2 1-2 1-2 1-2 1-2 1-2 1-2 rack shall not be adjacent to a Region I storage rack. 15 11-5 11-3 1-2 I-2 1-2 I-2 1-2 1-2 1-2 1-2 Region 2 (Array II-C) Region I (Array I-B)

Spent Fuel Pit Wall For Array II-A, the empty cell in the 11-2 11-2 11-2 11-2 11-1 11-1 11-1 21-1 2x2 Il-A array shall be adjacent to the 11-1 E I11 E 11-1 E 11-1 E peripheral row that contains the category 11-2 assembly(s). For Array II-A 11 -1 1 1-1 11-1 11-1 1-2 I1-2 only, the peripheral row may contain Array Il-A Array Ia-A category I1-1 assemblies as the outer two rows will comply with Array II-A requirements.

Spent Fuel Pit Wall For Array Il-B, the Metamic insert 11-2 11-2 11-2 11-2 11-2 11-2 11-2 11-2 11-2 11-2 11-2 11-2 (or full length RCCA in the assembly) 11-2 11-2 11-2 11-2 11-2 W1-2 11-2 11-2 11-2 11-2 11-2 11-2 shall be adjacent to the peripheral row that contains the category 11-2 11-2 11-2 11-2 11-2 11-2 *11-2 111-2 11-2 11-2 11-2 11-2 11-2 assembly(s). Array 11-B Array 11-B Array 11-B

• Spent Fuel Pit Wall For Arrays Il-C and II-D, the 11-2 11-2 11-2 11-2 11-2 11-2 11-2 11-2 11-2 11-2 11-2 11-2 Metamic insert (or full length RCCA in the assembly) shall be adjacent to the 11-5 11-3 11-5 11-3 11-5 11-3 11-5. II_ 11-4 11-4 11-4 11-4 peripheral row that contains the 11-3 11-5 11-3 13 11-5 1[11-3 11-5 114 11-4 1[1-4 11-4 category 11-2 assembly(s). Array Il-C Array Il-C Array 1I-D Notes:

1. Fuel Categories are determined from Tables 5.5-1 and 5.5-2.

2. Shaded cells indicate either a Metamic insert in the cell or the fuel assembly contains a full length RCCA.

3. E indicates an empty (water filled) cell.

4. Attributes for each 2x2 array are as stated in the definition. Diagram is for illustrative purposes only.

TURKEY POINT - UNITS 3 & 4 5-17 AMENDMENT NOS. 234 AND 229

DESIGN FEATURES 5.6 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.6.1 The components identified in Table 5.6-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.6-1.

TURKEY POINT - UNITS 3 & 4 5-18 AMENDMENT NOS. 234 AND 229

TABLE 5.6-1 COMPONENT CYCLIC OR TRANSIENT LIMITS 0 COMPONENT CYCLIC OR TRANSIENT LIMIT DESIGN CYCLE OR TRANSIENT C

Reactor Coolant System 200 heatup cycles at < 100°F/h Heatup cycle - Tavg from < 200'F z and 200 cooldown cycles at to >_550 0 F.

C,, < 100°F/h. Cooldown cycle - Tavg from _ 550'F (n to < 200 0 F.

200 pressurizer cooldown cycles Pressurizer cooldown cycle at < 200°F/h. temperatures from > 650°F to < 200 0 F.

80 loss of load cycles, without > 15% of RATED THERMAL POWER to immediate Turbine or Reactor trip. 0% of RATED THERMAL POWER.

T1 40 cycles of loss-of-offsite Loss-of-offsite A.C. electrical A.C. electrical power. ESF Electrical System.

80 cycles of loss of flow in one Loss of only one reactor reactor coolant loop. coolant pump.

400 Reactor trip cycles. 100% to 0% of RATED THERMAL POWER.

m z

150 leak tests. Pressurized to _ 2435 psig.

m z

z 5 hydrostatic pressure tests. Pressurized to > 3100 psig.

0

-I, Secondary Coolant System 6 loss of secondary pressure Loss of Secondary pressure z

50 leak tests Pressurized to > 1085 psig 0

(D 35 hydrostatic pressure tests. Pressurized to > 1356 psig.