ML050310149

Technical Specification Pages Re Spent Fuel Pool Max Enrichment Limit

ML050310149
Person / Time
Site:	Calvert Cliffs
Issue date:	01/27/2005
From:	Office of Nuclear Reactor Regulation
To:
References
TAC MC0935
Download: ML050310149 (9)

Text

TABLE OF CONTENTS 3.5.5 Trisodium Phosphate (TSP).......................... 3.5.5-1 3.6 CONTAINMENT SYSTEMS.................................... 3.6.1-1 3.6.1 Containment........................................ 3.6.1-1 3.6.2 Containment Air Locks.............................. 3.6.2-1 3.6.3 Containment Isolation Valves....................... 3.6.3-1 3.6.4 Containment Pressure............................... 3.6.4-1 3.6.5 Containment Air Temperature........................ 3.6.5-1 3.6.6 Containment Spray and Cooling Systems.............. 3.6.6-1 3.6.7 Deleted 3.6.8 Iodine Removal System (IRS)........................ 3.6.8-1 3.7 PLANT SYSTEMS.......................................... 3.7.1-1 3.7.1 Main Steam Safety Valves (MSSVs)................... 3.7.1-1 3.7.2 Main Steam Isolation Valves (MSIVs)............... 3.7.2-1 3.7.3 Auxiliary Feedwater (AFW) System................... 3.7.3-1 3.7.4 Condensate Storage Tank (CST)...................... 3.7.4-1 3.7.5 Component Cooling (CC) System...................... 3.7.5-1 3.7.6 Service Water (SRW) System........................ 3.7.6-1 3.7.7 Saltwater (SW) System............................... 3.7.7-1 3.7.8 Control Room Emergency Ventilation System (CREVS).. 3.7.8-1 3.7.9 Control Room Emergency Temperature System (CRETS).. 3.7.9-1 3.7.10 Emergency Core Cooling System (ECCS) Pump Room Exhaust Filtration System (PREFS) ............. 3.7.10-1 3.7.11 Spent Fuel Pool Exhaust Ventilation System (SFPEVS) ...................................... 3.7.11-1 3.7.12 Penetration Room Exhaust Ventilation System (PREVS) ........................................ 3.7.12-1 3.7.13 Spent Fuel Pool (SFP) Water Level .................. 3.7.13-1 3.7.14 Secondary Specific Activity........................ 3.7.14-1 3.7.15 Main Feedwater Isolation Valves (MFIVs)............ 3.7.15-1 3.7.16 Spent Fuel Pool (SFP) Boron Concentration.......... 3.7.16-1 3.7.17 Spent Fuel Pool (SFP) Storage...................... 3.7.17-1 3.8 ELECTRICAL POWER SYSTEMS............................... 3.8.1-1 3.8.1 AC Sources-Operating .............................. 3.8.1-1 3.8.2 AC Sources-Shutdown .............................. 3.8.2-1 3.8.3 Diesel Fuel Oil.................................... 3.8.3-1 3.8.4 DC Sources-Operating .............................. 3.8.4-1 3.8.5 DC Sources-Shutdown .............................. 3.8.5-1 3.8.6 Battery Cell Parameters........................... 3.8.6-1 3.8.7 Inverters-Operating ................................ 3.8.7-1 CALVERT CLIFFS - UNIT 1 iii Amendment No. 246 CALVERT CLIFFS - UNIT 2 Amendment No.246

TABLE OF CONTENTS 3.8.8 Inverters-Shutdown ........... ..................... 3.8.8-1 3.8.9 Distribution Systems-Operating .................... 3.8.9-1 3.8.10 Distribution Systems-Shutdown ............. ........ 3.8.10-1 3.9 REFUELING OPERATIONS . . . ........ 3.9.1-1 3.9.1 Boron Concentration . . . .......... 3.9.1-1 3.9.2 Nuclear Instrumentation . . . .......3.9.2-1 3.9.3 Containment Penetrations . . . ........ 3.9.3-1 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation-High Water Level . ... 3.9.4-1 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation-Low Water Level ................................ 3.9.5-1 3.9.6 Refueling Pool Water Level . . . ........ 3.9.6-1 4.0 DESIGN FEATURES .. . . ........................................ 4.0-1 4.1 Site Location . . ........................................ 4.0-1 4.2 Reactor Core . . ......................................... 4.0-1 4.3 Fuel Storage . . . ........................................ 4.0-2 5.0 ADMINISTRATIVE CONTROLS.................................... 5.1-1 5.1 Responsibility ......................................... 5.1-1 5.2 Organization ........................................... 5.2-1 5.2.1 Onsite and Offsite Organizations . . ........ 5.2-1 5.2.2 Unit Staff ......................................... 5.2-2 5.3 Unit Staff Qualifications . . ............ 5.3-1 5.4 Procedures ............................................. 5.4-1 5.5 Programs and Manuals ................................... 5.5-1 5.5.1 Offsite Dose Calculation Manual ......... ........... 5.5-1 5.5.2 Primary Coolant Sources Outside Containment ........ 5.5-2 5.5.3 Not Used ........................................... 5.5-2 5.5.4 Radioactive Effluent Controls Program .............. 5.5-2 5.5.5 Component Cyclic or Transient Limit ................ 5.5-5 5.5.6 Concrete Containment Tendon Surveillance program... 5.5-6 5.5.7 Reactor Coolant Pump Flywheel Inspection Program... 5.5-6 5.5.8 Inservice Testing Program . . ........... 5.5-6 5.5.9 Steam Generator Tube Surveillance Program .......... 5.5-7 5.5.10 Secondary Water Chemistry Program ................. . 5.5-17 5.5.11 Ventilation Filter Testing Program ................ . 5.5-17 5.5.12 Explosive Gas and Storage Tank Radioactivity Monitoring Program ... .......................... 5.5-20 5.5.13 Diesel Fuel Oil Testing Program .................... 5.5-21 5.5.14 Technical Specifications Bases Control Program ..... 5.5-21 CALVERT CLIFFS - UNIT 1 iv Amendment No.246 CALVERT CLIFFS - UNIT 2 Amendment No.246

TABLE OF CONTENTS 5.5.15 Safety Function Determination Program (SFDP)....... 5.5-22 5.5.16 Containment Leakage Rate Testing Program........... 5.5-23 5.6 Reporting Requirements................................. 5.6-1 5.6.1 Occupational Radiation Exposure Report............. 5.6-1 5.6.2 Annual Radiological Environmental Operating report. 5.6-1 5.6.3 Radioactive Effluent Release Report................ 5.6-2 5.6.4 Monthly Operating Reports.......................... 5.6-3 5.6.5 CORE OPERATING LIMITS REPORT (COLR) ................ 5.6-3 5.6.6 Not Used........................................... 5.6-9 5.6.7 Post-Accident Monitoring Report................... 5.6-9 5.6.8 Tendon Surveillance Report......................... 5.6-9 5.6.9 Steam Generator Tube Inspection Report............. 5.6-9 CALVERT CLIFFS - UNIT 1 v Amendment No.246 CALVERT CLIFFS - UNIT 2 Amendment No.246

SFP Boron Concentration 3.7.16 3.7 PLANT SYSTEMS 3.7.16 Spent Fuel Pool (SFP) Boron Concentration LCO 3.7.16 Boron concentration of the SFP shall be 2 2000 ppm.

APPLICABILITY: When fuel assemblies are stored in the SFPs. I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent Fuel Pool boron ----------- NOTE------------

concentration not LCO 3.0.3 is not applicable.

within limit.

A.1 Suspend movement of Immediately fuel assemblies in the SFPs. I AND A.2 Initiate action to Immediately restore boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify boron concentration is greater than 7 days 2000 ppm.

CALVERT CLIFFS - UNIT 1 3.7.16-1 Amendment No. 246 CALVERT CLIFFS - UNIT 2 Amendment No. 246

SFP Storage 3.7.17 3.7 PLANT SYSTEMS 3.7.17 Spent Fuel Pool (SFP) Storage LCO 3.7.17 The combination of initial nominal enrichment and burnup of each fuel assembly stored in the Unit 2 Spent Fuel Pool shall be in accordance with the following:

(a) Irradiated fuel assemblies may be stored in any rack location in the Unit 2 Spent Fuel Pool provided the combination of burnup and initial nominal enrichment is in the acceptable range of Figure 3.7.17-1, and (b) Irradiated or unirradiated fuel assemblies with a combination of burnup and initial nominal enrichment that are not in the acceptable range of Figure 3.7.17-1 may be stored in the Unit 2 Spent Fuel Pool if surrounded on all four adjacent faces by empty rack cells or other non-reactive materials.

APPLICABILITY: Whenever any fuel assembly is stored in the Unit 2 Spent Fuel Pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the ----------- NOTE----------

LCO not met. LCO 3.0.3 is not applicable.

A.1 Initiate action to Immediately move the non-complying fuel assembly to an acceptable storage location.

CALVERT CLIFFS - UNIT 1 3.7.17-1 Amendment No.246 CALVERT CLIFFS - UNIT 2 Amendment No.246

SFP Storage 3.7.17 SURVEILLANCE REQUIREMENTS U SURVEILLANCE FREQUENCY SR 3.7.17.1 Verify by administrative means that the Prior to initial enrichment, burnup and storage storing the location of the fuel assembly is in fuel assembly accordance with Figure 3.7.17-1. in the Unit 2 Spent Fuel Pool CALVERT CLIFFS - UNIT 1 3.7.17-2 Amendment No.246 CALVERT CLIFFS - UNIT 2 Amendment No.246

SFP Storage 3.7.17 50.00 45.00 40.00 ED 35.00 30.00 3

-c 25.00 2

.0 20.00 co:

C:

15.00 a)

C' 10.00 5.00 0.00 2.0 2.5 3.0 3.5 4.0 4.5 5.0 U-235 Enrichment (wlo)

Figure 3.7.17-1 Discharge Burnup vs. Initial Enrichment for Unit 2 SFP CALVERT CLIFFS - UNIT 1 3.7.17-3 Amendment No.246 CALVERT CLIFFS - UNIT 2 Amendment No.246

Design Features 4.0 4.0 DESIGN FEATURES 4.2.2 Control Element Assemblies The reactor core shall contain 77 control element assemblies.

4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 5.00 weight percent;

b. keff < 1.00 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.7.2 of the Updated Final Safety Analysis Report (UFSAR) and keff < 0.95 if fully flooded with water borated to 350 ppm, which includes an allowance for uncertainties as described in Section 9.7.2 of the UFSAR;

c. A nominal 10-3/32-inch center-to-center distance between fuel assemblies placed in the high density fuel storage racks; 4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent;

b. keff < 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.7.1 of the UFSAR; CALVERT CLIFFS - UNIT 1 4.0-2 Amendment No. 246 CALVERT CLIFFS - UNIT 2 Amendment No. 246

Design Features 4.0 4.0 DESIGN FEATURES

c. ketf < 0.95 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.7.1. of the UFSAR; and

d. A nominal 18-inch center-to-center distance between fuel assemblies placed in the storage racks.

4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 63 ft.

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity, for both Units 1 and 2, limited to no more than 1830 fuel assemblies.

CALVERT CLIFFS - UNIT 1 4.0-3 Amendment No.246 CALVERT CLIFFS - UNIT 2 Amendment No.246