ML022690740

TS Pages for Amds 154 & 154 Credit Soluble Boron in the Spent Fuel Pool Criticality Analysis Tacs. MB2983 & MB2984

ML022690740
Person / Time
Site:	Diablo Canyon
Issue date:	09/25/2002
From:	Brian Benney Office of Nuclear Reactor Regulation
To:
Benney B, NRR/DLPM, 415-3764
Shared Package
ml022690752	List: ML022610080 ML022690740
References
TAC MB2983, TAC MB2984
Download: ML022690740 (9)

Text

TABLE OF CONTENTS (continued) 3.7 PLANT SYSTEMS...............................................................................................................

3.7-1 3.7.1 Main Steam Safety Valves (MSSVs)...........................................................................

3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs)..........................................................................

3.7-4 3.7.3 Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulating'Valves (MFRVs), MFRV Bypass Valves, and Main Feedwater Pump (MFWP) Turbine Stop Valves.................................................................................................................

3.7-6 3.7.4 10% Atmospheric Dump Valves (ADVs)......................................................................

3.7-8 3.7.5 Auxiliary Feedwater (AFW ) System.............................................................................

3.7-10 3.7.6 Condensate Storage Tank (CST) and Fire Water Storage Tank (FWST).................... 3.7-13 3.7.7 Vital Component Cooling W ater (CCW ) System..........................................................

3.7-14 3.7.8 Auxiliary Saltwater System (ASW )...............................................................................

3.7-16 3.7.9 Ultimate Heat Sink (UHS)............................................................................................

3.7-17 3.7.10 Control Room Ventilation (CRVS)................................................................................

3.7-18 3.7.11 Control Room Emergency Air Temperature Control System (CREATCS) - Not Used.3.7-20 3.7.12 Auxiliary Building Ventilation System (ABVS)..............................................................

3.7-21 3.7.13 Fuel Handling Building Ventilation System (FHBVS)...................................................

3.7-23 3.7.14 Penetration Room Exhaust Air Cleanup System (PREACS) - Not used...................... 3.7-25 3.7.15 Spent Fuel Pool W ater Level.......................................................................................

3.7-26 3.7.16 Spent Fuel Pool Boron Concentration.........................................................................

3.7-27 3.7.17 Spent Fuel Assembly Storage.....................................................................................

3.7-28 3.7.18 Secondary Specific Activity..........................................................................................

3.7.33 3.8 ELECTRICAL POW ER SYSTEMS.......................................................................................

3.8-1 3.8.1 AC Sources - Operating..............................................................................................

3.8-1 3.8.2 AC Sources - Shutdown..............................................................................................

3.8-11 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air Turbocharger Air Assist.............................

3.8-14 3.8.4 DC Sources - Operating..............................................................................................

3.8-18 3.8.5 DC Sources - Shutdown..............................................................................................

3.8-21 3.8.6 Battery Cell Parameters..............................................................................................

3.8-23 3.8.7 Inverters - Operating...................................................................................................

3.8-26 3.8.8 Inverters - Shutdown...................................................................................................

3.8-27 3.8.9 Distribution Systems - Operating.................................................................................

3.8-29 3.8.10 Distribution Systems - Shutdown.................................................................................

3.8-31 3.9 REFUELING OPERATIONS................................................................................................

3.9-1 3.9.1 Boron Concentration....................................................................................................

3.9-1 3.9.3 Nuclear Instrumentation..............................................................................................

3.9-2 3.9.4 Containment Penetrations...........................................................................................

3.9-3 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level................ 3.9-4 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level................. 3.9-6 3.9.7 Refueling Cavity W ater Level......................................................................................

3.9-8 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................................................................................................................

4.0-1 (continued)

DIABLO CANYON POWER PLANT Page 3 of 4 Amendment No.

154

Spent Fuel Pool Boron Concentration 3.7.16 3.7 PLANT SYSTEMS 3.7.16 Spent Fuel Pool Boron Concentration LCO 3.7.16 The spent fuel pool boron concentration shall be Ž 2000 ppm.

APPLICABILITY:

When fuel assemblies are stored in the spent fuel pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel pool boron

--......... ----- NOTE----

concentration not within LCO 3.0.3 is not applicable.

limit.

A 1 Suspend movement of Immediately fuel assemblies in the spent fuel pool.

AND A.2 Initiate action to restore Immediately spent fuel pool boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify the spent fuel pool boron concentration is 7 days within limit.

DIABLO CANYON - UNITS 1 & 2 3.7-27 Unit 1 -Amendment No. 4-35 j154 Unit 2 - Amendment No. 435,154 I

Spent Fuel Assembly Storage 3.7.17 3.7 PLANT SYSTEMS 3.7.17 Spent Fuel Assembly Storage LCO 3.7.17 APPLICABILITY:

Fuel assembly storage in the spent fuel pool shall be maintained such that any four cells shall be in a configuration as shown in Figure 3.7.17-1.

Whenever any fuel assembly is stored in the spent fuel pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Requirements of the LCO A.1 NOTE not met.

LCO 3.0.3 is not applicable.

Initiate action to move the Immediately noncomplying fuel assembly into an acceptable storage location.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.17.1 Verify by administrative means that the fuel Prior to each fuel assembly characteristics and its expected storage assembly move, when location is in accordance with LCO 3.7.17.

the assembly will be stored in the spent fuel pool.

DIABLO CANYON - UNITS 1 & 2 3.7-28 Unit 1 - Amendment No. 435,154 Unit 2 - Amendment No. 4-35, 154

Spent Fuel Assembly Storage 3.7.17 G

W W

G All Cell Configuration 2x2 Array Configuration Checkerboard Configuration All Cell:

A Fuel assembly with a discharge burnup in the "acceptable" region of Figure 3.7.17-2.

2x2 Array:

F (a) Fuel assembly with an initial enrichment _ 4.9 wt% U-235; or (b) Fuel assembly with an initial enrichment < 5.0 wt% U-235 and an IFBA loading equivalent to 16 rods each with 1.5 mg 10B/in over 120 inches.

B Fuel assembly with a discharge burnup in the "acceptable" region of Figure 3.7.17-3.

Checkerboard:

G Fuel assembly with an initial enrichment < 5.0 wt% U-235.

W Water cell - locations where fuel assemblies are not present, non-fissile components are permitted.

FIGURE 3.7.17-1 ALLOWABLE STORAGE CONFIGURATIONS (ALL CELL, 2X2 ARRAY, CHECKERBOARD)

FOR THE SPENT FUEL POOL DIABLO CANYON - UNITS 1 & 2 3.7-29 Unit I - Amendment No. 154 Unit 2 - Amendment No. 154 A

A A

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2.0 2.5 3.0 3.5 4.0 4.5 5.0 Initial Enrichment, Wt% U-235 FIGURE 3.7.17-2 MINIMUM REQUIRED ASSEMBLY DISCHARGE BURNUP AS A FUNCTION OF INITIAL ENRICHMENT AND FUEL PELLET DIAMETER FOR AN ALL CELL STORAGE CONFIGURATION' DIABLO CANYON - UNITS 1 & 2 3.7-30 Unit 1 - Amendment No. 435,154 Unit 2 - Amendment No. 4-35,154 I

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1.0 15 2.0 25 30 35 40 4.5 5.0 Initial Enrichment, Wt% U-235 FIGURE 3.7.17-3 MINIMUM REQUIRED ASSEMBLY DISCHARGE BURNUP AS A FUNCTION OF INITIAL ENRICHMENT FOR A 2X2 ARRAY STORAGE CONFIGURATION DIABLO CANYON - UNITS 1 & 2 3.7-31 Unit 1 - Amendment No. 154 Unit 2 - Amendment No. 154

Spent Fuel Assembly Storage 3.7.17 THIS PAGE NOT USED DIABLO CANYON - UNITS 1 & 2 3.7-32 Unit 1 - Amendment No. -45, 154 Unit 2 - Amendment No. 4-35,154

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The DCPP site consists of approximately 750 acres which are adjacent to the Pacific Ocean in San Luis Obispo County, California, and is approximately twelve (12) miles west-southwest of the city of San Luis Obispo.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of Zircalloy or ZIRLO clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (U0 2) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core locations.

4.2.2 Control Rod Assemblies The reactor core shall contain 53 control rod assemblies. The control rod material shall be silver, indium, and cadmium, as approved by the NRC.

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 5.0 weight percent;

b.

keff < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1.2.3 of the FSAR;

c.

keff < 0.95 if fully flooded with water borated to 806 ppm, which includes an allowance for uncertainties as described in Section 9.1.2.3 of the FSAR;

d.

A nominal 11 inch center to center distance between fuel assemblies placed in the fuel storage racks; (continued)

DIABLO CANYON - UNITS 1 & 2 4.0-1 Unit 1 - Amendment No. 4-35,154 Unit 2 - Amendment No 4-35,154

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued)

e.

Fuel assemblies with a discharge burnup in the "acceptable" region of Figure 3.7.17-2 for the all cell configuration as shown in Figure 3.7.17-1;

f.

Fuel assemblies with a discharge burnup in the "acceptable" region of Figure 3.7.17-3 for the 2x2 array configuration as shown in Figure 3.7.17-1.

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.

k*, _< 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1.1.1 of the FSAR;

c.

keff 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.1.1.1 of the FSAR; and

d.

A nominal 22 inch center to center distance between fuel assemblies placed in the storage racks.

4.3.2 Drainage The spent fuel storage pools are designed and shall be maintained to prevent inadvertent draining of the pool below elevation 133 ft.

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1324 fuel assemblies.

DIABLO CANYON - UNITS 1 & 2 4.0-2 Unit 1 - Amendment No. 435,154 Unit 2 - Amendment No. 1-45, 154