ML17346A631

Proposed Tech Specs Re Expansion of Spent Fuel Storage Facilities

ML17346A631
Person / Time
Site:	Turkey Point
Issue date:	11/16/1984
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17346A630	List: ML17346A629 ML17346A631
References
NUDOCS 8411190453
Download: ML17346A631 (22)

Text

TABLE OF CONTENTS (Continued)

Section Title ~Pa e 3.0 Engineering Safety Features 3.0-1 Safety Injection and RHR Systems 3.0-1 Emergency Containment Cooling Systems 3.0-3 Emer gency Containment Filtering System 3.0-0 Component Cooling System 3.0-0a Intake Cooling Water System 3.0-5 Post Accident Containment Vent System 3.0-6 Control Room Ventilation 3.0-6 3.5 Instrumentation 3.5-1 3.6 Chemical and Volume Control System 3.6-1 3.7 Electrical Systems 3.7-1 3.8 Steam Power Conversion Systems 3.8-1 3.9 Radioactive Materials Release 3.9-1 Liquid Wastes 3.9-1 Gaseous Wastes 3.9-3 Containerized Wastes 3.9-5 3.10 Refueling 3.10-1 3.11 Miscellaneous Radioactive Materials Sources 3.11-1 3.12 Cask Handling 3.12-1 3.13 Snubbers 3.13-1 3.10 Fire Protection Systems 3.10-1 3.15 Overpressure Mitigating System 3.15-1 3.16 Reactor Coolant System Pressure Isolation Valves 3.16-1 3.17 Spent Fuel Storage 3.17-1 0.0 SURVEILLANCE REQUIREMENTS 0.1-1 0.1 Operational Safety Review 0.1-1 0.2 Reactor Coolant System In Service Inspection 0.2-1 0.3 Reactor Coolant System Integrity 0.3-1 Containment Tests 0.0-1 Integrated Leakage Rate Test - Post Operational 0.0-1 Local Penetration Tests 0.0-2 Report of Test Results 0.0-2 Isolation Valves 0.0-3 Residual Heat Removal System 0.0-3 Tendon Surveillance 0.0 0 End Anchorage Concrete Surveillance 0.0-6 Liner Surveillance 0.0-7 0.5 Safety Injection 0.5-1 0.6 Emergency Containment Cooling Systems 0.6-1 0.7 Emergency Containment Filtering and Post Accident Containment Vent Systems 0.7-1 0.8 Emergency Power System Periodic Tests 0.8-1 0.9 Main Steam Isolation Valves 0.9-1

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TABLE OF CONTENTS (Continued)

Section Title ~Pa e 83.5 Bases for Limiting Conditions for Operation, Instrumentation 83.5-1 83.6 Bases for Limiting Conditions for Operation, Chemical and Volume Control System 83.6-1 83.7 Bases for Limiting Conditions for Operation, Electrical Systems 83.7-1 Bases for Limiting Conditions for Operation, Steam and Power Conversion Systems 83.8-1 83.9 Bases for Limiting Conditions for Operation, Radioactive Materials Release 83.9-1 83.10 Bases for Limiting Conditions for Operation, Refueling 83.10-1 83.11 Bases for Limiting Conditions for Operation, Miscellaneous Radioactive Material Sources 83.11-1 83.12 Bases for Limiting Conditions for Operation, Cask Handling 83.12-1 83.13 Bases for Limiting Conditions for Operation, Snubbers 83.13-1 83.10 Bases for Fire Protection System 83.10-1 83.15 Bases for Limiting-Conditions of Operation, Overpressure Mitigating System 83.15-1 83.17 Bases for Limiting Conditions for Operation, 83.17-1 Spent Fuel Storage 80.1 Bases for Operational Safety Review 80.1-1 80.2 Bases for Reactor Coolant System In-Service Inspection 80.2-1 84.3 Bases for Reactor Coolant System Integrity 80.3-1 80.0 Bases for Containment Tests 80.0-1 80.5 Bases for Safety Injection Tests 80.5-1 80.6 Bases for Emergency Containment Cooling System Tests 80.6-1 80.7 Bases for Emergency Containment Filtering and Post Accident Containment Venting Systems Tests 80.7-1 80.8 Bases for Emergency Power System Periodic Tests 80.8-1 80.9 Bases for Main Steam Isolation Valve Tests 80.9-1 80.10 Bases for Auxiliary Feedwater System Tests 80.10-1 80.11 Bases for Reactivity Anomalies 80.11-1 80.12 Bases for Environmental Radiation Survey 80.12-1 80.13 Bases for Fire Protection Systems 80.13-1 80.10 Bases for Snubbers 80.10-1 80.15 Bases for Surveillance Requirements, Overpressure Mitigating System 80.15-1 Iv Amendment Nos. and

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LIST OF TABLES Table Title 3.5-1 Instrument Operating Conditions for Reactor Trip 3.5-2 Engineering Safety Features Actuation 3.5-3 Instrument Operating Conditions for Isolation Functions 3.5-0 Engineered Safety Feature Set Points 3.13-1 Safety Related Snubbers 3.10-1 Fire Detection System 3.17-1 Spent Fuel Burnup Requirements for Storage in Region II of the Spent Fuel Pit 0.1-1 Minimum Frequencies for Checks, Calibrations and Test of Instrument Channels 0.1-2 Minimum Frequencies for Equipment and Sampling Tests 0.2-1 Reactor Coolant System In-Service Inspection Schedule 0.12-1 Operational Environmental Radiological Surveillance Program 0.12-2 Operational Environmental Radiological Surveillance Program Types of Analysis 6.2-1 Operating Personnel Amendment Nos. and

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3.12 CASK HANDLING Applies to limitations during cask handling.

O~b'ective= To minimize the possibility of an accident during cask handling operations that would affect the health and safety of the public.

"iE " iE (1) The spent fuel cask shall not be moved into the spent fuel pit until all the spent fuel in the pit has decayed for a minimum of 1525 hours0.0177 days <br />0.424 hours <br />0.00252 weeks <br />5.802625e-4 months <br />.++

(2) Only a single element cask may be moved into the spent fuel pit.

(3) A fuel assembly shall not be removed from the spent fuel pit in a shipping cask until it has decayed for a minimum of 120 days.~

(0) HEAVY LOADS shall be prohibited from travel over irradiated fuel assemblies in the spent fuel pool (refer to T.S. 3.10.10).

" The Region 10 fuel which was in the Unit 3 reactor during the period of April 19, 1981, through April 20, 1981, may be removed from the Unit 3 spent fuel pit in a shipping cask after a minimum decay period of ninety-five (95) days.

++ The spent fuel cask can be moved into the Unit 0 Spent Fuel Pit after a minimum decay of 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> until the new two-region high density spent fuel racks are installed.

3.12-1 Amendment Nos. and

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3.17 SPENT FUEL STORAGE Applies to limitations on the storage of spent fuel assemblies.

O~bective= To minimize the possibility of exceeding the reactivity design limits for storage of spent fuel.

(1) Fuel assemblies containing more than 0.1 weight percent of U-235 shall not be placed in the single region spent fuel storage racks.

After installation of the two-region high density spent fuel racks, the maximum enrichment loading for fuel assemblies in the spent fuel racks is 0.5 weight percent of U-235.

(2) The minimum boron concentration while fuel is stored in the Spent Fuel Pit shall be 1950 ppm.

(3)>> Storage in Region II of the Spent Fuel Pit shall be further restricted by burnup and enrichment limits specified in Table 3.17-1.

(0)>> During the re-racking operation only, fuel that does not meet the burnup requirements for normal storage in Region II may be stored in Region II in a checkerboard arrangement (i.e., no fuel stored in adjacent spaces).

>> This Technical Specification is applicable only after installation of the new two-region high density spent fuel racks.

3.17-1 Amendment Nos. and

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TABLE 3.17-1 SPENT FUEL BVRNUP RE UIREMENTS FOR STORAGE IN REGION H OF THE SPENT FUEL PIT Initial Discharge Burnup w/o GVD/iVTT 1.5

1. 75 5.0 2.0 9.0 2.2 2.0 10. 8 2.6 17.

2.8 6'2.6 3.0 3.2 25.0 3.0 27.0 3.6 29.6 3.8 31. 8

$ .0 30.0 0.2 0.5 39.0 Lineat interpolation between two consecutive points will yield conservative results.

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TABLE 0.1-2 (Sheet 2 of 3)

MINIMUMFRE UENCIES FOR E UIP MENT AND SAMPLING TESTS Max. Time F~re uency Between Tests Days

5. Control Rods (cont'd) Partial movement of Biweekly while 20 full length rods critical

6. Pressurizer Safety Valves Set Point Each refueling NA shutdown

7. Main Steam Safety Valves Set Point Each refueling NA shutdown

8. Containment Isolation Trip Functioning Each refueling NA shutdown

9. Refueling System Interlocks Functioning Prior to each NA refueling

10. Accumulator Boron Concentration At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of >1%

of tank volume.t

11. Reactor Coolant System Evaluate Daily NA Leakage

12. Diesel Fuel Supply Fuel inventory Weekly 10

13. Spent Fuel Pit Boron Concentration Monthly

10. Fire Protection Pump and Operable Monthly Power Supply

15. Turbine Stop and Control Closure Monthly+

Valves, Reheater Stop and Intercept Valves

16. LP Turbine Rotor Inspector V, MT, PT Every 5 years 6 years (w/o rotor disassembly)

17. Spent Fuel Cask Crane Functioning Within 7 days 7 days when

- Interlocks crane is being used to maneuver spent fuel cask.

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TABLE 0.1-2 (Sheet 3 of 3)

MINIMUMFRE UENCIES FOR E UIPMENT AND SAMPLING TESTS Max. Time Check ~pre cene Between Tests Days

18. Coolant Loops During power operation, Once every 12 hrs. 12 hrs.

verify three (3) reactor coolant loops in operation and circulating reactor coolant.

At shutdown with average coolant temperature > 350 F, verify

a. One (1) reactor coolant Once every 12 hrs. 12 hrs.

loop in operation and circulating reactor coolant.

b. A second coolant loop Once every 7 days 7 days operable.

At shutdown (not refueling) with average coolant temperature < 350 F, verify

a. One (1) coolant loop is in Once every 12 hrs. 12 hrs.

operation and circulating reactor coolant.

b. A second coolant loop Once every 7 days '

days operable.

At refueling shutdown, Once every 0 hrs. 0 hrs.

verify that one (1) residual heat removal coolant loop is in operation and circulating sufficient reactor coolant to maintain core outlet temperature below 160 F.

N.A. during cold or refueling shutdowns. The specified tests, however, shall be performed prior to heatup above 200 F.

N.A. during cold or refueling shutdowns, or at hot shutdown when all main steam isolation valves are shut. The specified tests, however, shall be performed within one surveillance period prior to starting the turbine.

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5A FUEL STORAGE

1. The New and Spent Fuel Pit structures are designed to withstand the anticipated earthquake loadings as Class 1 structures. Each Spent Fuel Pit has a stainless steel liner to ensure against leakage.

2. The spent fuel storage racks provide safe subcritical storage of fuel assemblies by providing sufficient center-to-center spacing or a combination of spacing and poison to assure Keffy is equal to or less than 0.95 for normal operations and postulated accidents. Fuel assemblies containing more than 0.1 weight percent of U-235 shall not be placed in the single region spent fuel storage racks. After installation of the two-region high density spent fuel racks, the maximum enrichment loading for fuel assemblies in the spent fuel racks is 0.5 weight percent of U-235.

The racks for new fuel storage are designed to store fuel in a safe subcritical array. The fuel is stored vertically in an array with sufficient 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. Fuel containing more than 0.5 weight percent of U-235 shall not be placed in the New Fuel Storage Area.

3. Credit for burnup is taken in determining placement locations for spent fuel in the two-region spent fuel racks.+ Strict administrative controls are employed to evaluate the burnup of each spent fuel assembly stored in areas where credit for burnup is taken. The burnup of spent fuel is ascertained by careful analysis. of burnup history, prior to placement into the storage locations. Procedures shall require an independent check of the analysis of suitability for storage. A complete record of such analysis is kept for the time period that the spent fuel assembly remains in storage onsite.

+ During rack installation, it will be necessary to temporarily store Region I fuel in the Region H spent fuel racks. Strict administrative controls will be utilized to maintain a checkerboard storage configuration, i.e., alternate cell occupation, in the Region II racks.

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83.12 BASES FOR LIMITINGCONDITIONS FOR OPERATION, CASK HANDLING Requiring spent fuel decay time to be a minimum of 1525 hours0.0177 days <br />0.424 hours <br />0.00252 weeks <br />5.802625e-4 months <br /> prior to moving a spent fuel cask into the spent fuel pit will keep potential offsite doses well within 10 CFR Part 100 limits should a dropped cask strike the stored fuel assemblies.

The restriction to allow only a single element cask to be moved into the spent fuel pit will ensure the maintenance of water inventory in the unlikely event of an uncontrolled cask descent. Use of a single element cask which nominally weighs about twenty-five tons will also increase crane safety margins by about a factor of four.

Requiring the spent fuel decay time be at least 120 days prior to moving a fuel assembly outside the fuel storage pit in a shipping cask will ensure that potential offsite doses are a fraction of 10 CFR 100 limits should a dropped cask and ruptured fuel assembly release activity directly to the atmosphere.

The restriction on movement of HEAVY LOADS over irradiated fuel assemblies in the spent fuel pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the FSAR. For the purpose of this specification, HEAVY LOADS are defined as loads greater than 2000 pounds.(1) (Refer to T.S. 1.36 and T.S. B3.10)

References:

~lFSAR Table 3.2.3-1 B3.12-1 Amendment iVos. and

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B3.17 BASES FOR LIMITINGCONDITIONS FOR OPERATION, SPENT FUEL STORAGE

1. The spent fuel storage racks provide safe subcritical storage of fuel assemblies by providing sufficient center-to-center spacing or a combination of spacing and poison to assure keff is equal to or less than 0.95 for normal operations and postulated accidents.

2.+ The spent fuel racks are divided into two regions. Region I racks have a 10.6 inch center-to-center spacing and the Region II racks have a 9.0 inch center-to-center spacing. Because of the larger center-to-center spacing and poison (B10) concentration of Region I cells, the only restriction for placement of fuel is that the initial fuel assembly enrichment is equal to or less than 0.5 weight percent of U-235. The limiting value of U-235 enrichment is based upon the assumptions in the spent fuel safety analyses and assures that the limiting criteria for criticality is not exceeded. Prior to placement in Region II cell locations, strict controls are employed to evaluate burnup of the spent fuel assembly. Upon determination that the fuel assembly meets the burnup requirements of Table 3.17-1, placement in a Region II cell is authorized. These positive controls assure the fuel enrichment limits assumed in the safety analyses will not be exceeded.

+ This Technical Specification is applicable upon installation of the new two-region high density spent fuel racks.

B3.17-1 Amendment Nos. and

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