ML17346A631
| ML17346A631 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 11/16/1984 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17346A630 | List: |
| References | |
| NUDOCS 8411190453 | |
| Download: ML17346A631 (22) | |
Text
TABLEOF CONTENTS (Continued)
Section 3.0 3.5 3.6 3.7 3.8 3.9 3.10 3.11 3.12 3.13 3.10 3.15 3.16 3.17 Title Engineering Safety Features Safety Injection and RHR Systems Emergency Containment Cooling Systems Emer gency Containment Filtering System Component Cooling System Intake Cooling Water System Post Accident Containment Vent System Control Room Ventilation Instrumentation Chemical and Volume Control System Electrical Systems Steam Power Conversion Systems Radioactive Materials Release Liquid Wastes Gaseous Wastes Containerized Wastes Refueling Miscellaneous Radioactive Materials Sources Cask Handling Snubbers Fire Protection Systems Overpressure Mitigating System Reactor Coolant System Pressure Isolation Valves Spent Fuel Storage
~Pa e 3.0-1 3.0-1 3.0-3 3.0-0 3.0-0a 3.0-5 3.0-6 3.0-6 3.5-1 3.6-1 3.7-1 3.8-1 3.9-1 3.9-1 3.9-3 3.9-5 3.10-1 3.11-1 3.12-1 3.13-1 3.10-1 3.15-1 3.16-1 3.17-1 0.0 0.1 0.2 0.3 0.5 0.6 0.7 0.8 0.9 SURVEILLANCEREQUIREMENTS Operational Safety Review Reactor Coolant System In Service Inspection Reactor Coolant System Integrity Containment Tests Integrated Leakage Rate Test - Post Operational Local Penetration Tests Report of Test Results Isolation Valves Residual Heat Removal System Tendon Surveillance End Anchorage Concrete Surveillance Liner Surveillance Safety Injection Emergency Containment Cooling Systems Emergency Containment Filtering and Post Accident Containment Vent Systems Emergency Power System Periodic Tests Main Steam Isolation Valves 0.1-1 0.1-1 0.2-1 0.3-1 0.0-1 0.0-1 0.0-2 0.0-2 0.0-3 0.0-3 0.0 0 0.0-6 0.0-7 0.5-1 0.6-1 0.7-1 0.8-1 0.9-1
,,-- 84111~o+SSO500025
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- Section TABLEOF CONTENTS (Continued)
Title
~Pa e 83.5 83.6 83.7 83.9 83.10 83.11 83.12 83.13 83.10 83.15 83.17 80.1 80.2 84.3 80.0 80.5 80.6 80.7 80.8 80.9 80.10 80.11 80.12 80.13 80.10 80.15 Bases for Limiting Conditions for Operation, Instrumentation Bases for Limiting Conditions for Operation, Chemical and Volume Control System Bases for Limiting Conditions for Operation, Electrical Systems Bases for Limiting Conditions for Operation, Steam and Power Conversion Systems Bases for Limiting Conditions for Operation, Radioactive Materials Release Bases for Limiting Conditions for Operation, Refueling Bases for Limiting Conditions for Operation, Miscellaneous Radioactive Material Sources Bases for Limiting Conditions for Operation, Cask Handling Bases for Limiting Conditions for Operation, Snubbers Bases for Fire Protection System Bases for Limiting-Conditions of Operation, Overpressure Mitigating System Bases for Limiting Conditions for Operation, Spent Fuel Storage Bases for Operational Safety Review Bases for Reactor Coolant System In-Service Inspection Bases for Reactor Coolant System Integrity Bases for Containment Tests Bases for Safety Injection Tests Bases for Emergency Containment Cooling System Tests Bases for Emergency Containment Filtering and Post Accident Containment Venting Systems Tests Bases for Emergency Power System Periodic Tests Bases for Main Steam Isolation Valve Tests Bases for Auxiliary Feedwater System Tests Bases for Reactivity Anomalies Bases for Environmental Radiation Survey Bases for Fire Protection Systems Bases for Snubbers Bases for Surveillance Requirements, Overpressure Mitigating System 83.5-1 83.6-1 83.7-1 83.8-1 83.9-1 83.10-1 83.11-1 83.12-1 83.13-1 83.10-1 83.15-1 83.17-1 80.1-1 80.2-1 80.3-1 80.0-1 80.5-1 80.6-1 80.7-1 80.8-1 80.9-1 80.10-1 80.11-1 80.12-1 80.13-1 80.10-1 80.15-1 Iv Amendment Nos.
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Table LIST OF TABLES Title 3.5-1 3.5-2 3.5-3 3.5-0 3.13-1 3.10-1 3.17-1 0.1-1 0.1-2 0.2-1 0.12-1 0.12-2 6.2-1 Instrument Operating Conditions for Reactor Trip Engineering Safety Features Actuation Instrument Operating Conditions for Isolation Functions Engineered Safety Feature Set Points Safety Related Snubbers Fire Detection System Spent Fuel Burnup Requirements for Storage in Region II of the Spent Fuel Pit Minimum Frequencies for Checks, Calibrations and Test of Instrument Channels Minimum Frequencies for Equipment and Sampling Tests Reactor Coolant System In-Service Inspection Schedule Operational Environmental Radiological Surveillance Program Operational Environmental Radiological Surveillance Program Types of Analysis Operating Personnel Amendment Nos.
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3.12 CASK HANDLING O~b'ective=
Applies to limitations during cask handling.
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.
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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.
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TABLE3.17-1 SPENT FUEL BVRNUP RE UIREMENTS FOR STORAGE IN REGION H OF THE SPENT FUEL PIT Initial w/o 1.5
- 1. 75 2.0 2.2 2.0 2.6 2.8 3.0 3.2 3.0 3.6 3.8
$.0 0.2 0.5 Discharge Burnup GVD/iVTT 5.0 9.0
- 10. 8 17.
6'2.6 25.0 27.0 29.6
- 31. 8 30.0 39.0 Lineat interpolation between two consecutive points willyield conservative results.
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TABLE0.1-2 (Sheet 2 of 3)
MINIMUMFRE UENCIES FOR E UIPMENTAND SAMPLINGTESTS 5.
Control Rods (cont'd) 6.
Pressurizer Safety Valves Partial movement of full length rods Set Point F~re uency Biweekly while critical Each refueling shutdown Max. Time Between Tests Days 20 NA 7.
Main Steam Safety Valves Set Point Each refueling shutdown NA 8.
Containment Isolation Trip Functioning Each refueling shutdown NA 9.
Refueling System Interlocks Functioning Prior to each refueling NA
- 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 Leakage Evaluate Daily NA
- 12. Diesel Fuel Supply
- 13. Spent Fuel Pit
- 10. Fire Protection Pump and Power Supply Fuel inventory Boron Concentration Operable Weekly Monthly Monthly 10
- 15. Turbine Stop and Control Valves, Reheater Stop and Intercept Valves Closure Monthly+
Every 5 years 6 years
- 17. Spent Fuel Cask Crane
- Interlocks Functioning Within 7 days 7 days when crane is being used to maneuver spent fuel cask.
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TABLE0.1-2 (Sheet 3 of 3)
MINIMUMFRE UENCIES FOR E UIPMENTANDSAMPLINGTESTS Check
~pre cene Max. Time Between Tests Days
- 18. Coolant Loops During power operation, verify three (3) reactor coolant loops in operation and circulating reactor coolant.
Once every 12 hrs.
12 hrs.
At shutdown with average coolant temperature
> 350 F, verify a.
One (1) reactor coolant loop in operation and circulating reactor coolant.
Once every 12 hrs.
12 hrs.
b.
A second coolant loop operable.
At shutdown (not refueling) with average coolant temperature
< 350 F, verify Once every 7 days 7 days a.
One (1) coolant loop is in Once every 12 hrs.
12 hrs.
operation and circulating reactor coolant.
b.
A second coolant loop operable.
Once every 7 days days At refueling shutdown, 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.
Once every 0 hrs.
0 hrs.
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 willbe 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 HEAVYLOADS 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, HEAVYLOADS 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.
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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.
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