ML13330A925

Enclosure 2 - Volume 15 - Improved Technical Specifications Conversion, ITS Chapter 4.0, Design Features, Revision 0

ML13330A925
Person / Time
Site:	Sequoyah
Issue date:	11/22/2013
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
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References
NUREG-1431, Rev 4
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Enclosure 2, Volume 15, Rev. 0, Page 1 of 35 ENCLOSURE 2 VOLUME 15 SEQUOYAH NUCLEAR PLANT UNIT 1 AND UNIT 2 IMPROVED TECHNICAL SPECIFICATIONS CONVERSION ITS CHAPTER 4.0 DESIGN FEATURES Revision 0 Enclosure 2, Volume 15, Rev. 0, Page 1 of 35

Enclosure 2, Volume 15, Rev. 0, Page 2 of 35 LIST OF ATTACHMENTS

1. ITS Chapter 4.0 - DESIGN FEATURES Enclosure 2, Volume 15, Rev. 0, Page 2 of 35

, Volume 15, Rev. 0, Page 3 of 35 ATTACHMENT 1 ITS 4.0, DESIGN FEATURES , Volume 15, Rev. 0, Page 3 of 35

Enclosure 2, Volume 15, Rev. 0, Page 4 of 35 Current Technical Specification (CTS) Markup and Discussion of Changes (DOCs)

Enclosure 2, Volume 15, Rev. 0, Page 4 of 35

Enclosure 2, Volume 15, Rev. 0, Page 5 of 35 A01 ITS ITS Chapter 4.0 5.0 DESIGN FEATURES 5.1 SITE LOCATION The Sequoyah Nuclear Plant is located on a site near the geographical center of Hamilton County, 4.1 Tennessee, on a peninsula on the western shore of Chickamauga Lake at Tennessee River mile (TRM) 484.5. The Sequoyah site is approximately 7.5 miles northeast of the nearest city limit of Chattanooga, Tennessee, 14 miles west-northwest of Cleveland, Tennessee, and approximately 31 miles south-southwest of TVA's Watts Bar Nuclear Plant.

EXCLUSION AREA 5.2.1 DELETED LOW POPULATION ZONE 5.1.2 DELETED SITE BOUNDARY FOR GASEOUS EFFLUENTS 5.1.3 DELETED SITE BOUNDARY FOR LIQUID EFFLUENTS 5.1.4 DELETED 5.2 CONTAINMENT CONFIGURATION 5.2.1 DELETED DESIGN PRESSURE AND TEMPERATURE 5.2.2 DELETED August 2, 2006 SEQUOYAH - UNIT 1 5-1 Amendment No. 309 Page 1 of 16 Enclosure 2, Volume 15, Rev. 0, Page 5 of 35

Enclosure 2, Volume 15, Rev. 0, Page 6 of 35 A01 ITS ITS Chapter 4.0 THIS PAGE INTENTIONALLY DELETED August 2, 2006 SEQUOYAH - UNIT 1 5-2 Amendment No. 42, 114, 309 Page 2 of 16 Enclosure 2, Volume 15, Rev. 0, Page 6 of 35

Enclosure 2, Volume 15, Rev. 0, Page 7 of 35 A01 ITS ITS Chapter 4.0 THIS PAGE INTENTIONALLY DELETED August 2, 2006 SEQUOYAH - UNIT 1 5-3 Amendment No. 309 Page 3 of 16 Enclosure 2, Volume 15, Rev. 0, Page 7 of 35

Enclosure 2, Volume 15, Rev. 0, Page 8 of 35 A01 ITS ITS Chapter 4.0 4.2 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of zircaloy or M5 clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide as fuel material.

Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with NRC-4.2.1 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 regions. Sequoyah is authorized to place a limited number of lead test assemblies into the reactor as described in the Framatome-Cogema Fuels report BAW-2328, beginning with the Unit 1 Operating Cycle 12.

CONTROL ROD ASSEMBLIES 4.2.2 5.3.2 The reactor core shall contain 53 full length and no part length control rod assemblies. The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 DELETED VOLUME 5.4.2 DELETED 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 DELETED August 2, 2006 SEQUOYAH - UNIT 1 5-4 Amendment No. 45, 144, 180, 258, 268, 309 Page 4 of 16 Enclosure 2, Volume 15, Rev. 0, Page 8 of 35

Enclosure 2, Volume 15, Rev. 0, Page 9 of 35 A01 ITS ITS Chapter 4.0 DESIGN FEATURES 4.3 5.6 FUEL STORAGE 4.3.1 CRITICALITY - SPENT FUEL 4.3.1.1 5.6.1.1 The spent fuel storage racks are designed for fuel enriched to 5 weight percent U-235 and shall be maintained with:

4.3.1.1.a 4.3.1.1.b

a. A keff less than critical when flooded with unborated water and a keff less than or equal to 0.95 when flooded with water containing 300 ppm soluble boron.*

4.3.1.1.c

b. A nominal 8.972 inch center-to-center distance between fuel assemblies placed in the storage racks.

c. Arrangements of one or more of three different arrays (Regions) or sub-arrays as illustrated in Figures 5.6-1 and 5.6-1a. These arrangements in the spent fuel storage pool have the following definitions:

1. Region 1 is designed to accommodate new fuel with a maximum enrichment of 4.95

+/- 0.05 wt% U-235, (or spent fuel regardless of the fuel burnup), in a 1-in-4 checkerboard arrangement of 1 fresh assembly with 3 spent fuel assemblies with enrichment-burnup and cooling times illustrated in Figure 5.6-2 and defined by the equations in Table 5.6-1. Cooling time is defined as the period since reactor shutdown at the end of the last operating cycle for the discharged spent fuel assembly. The presence of a removable, non-fissile insert such as a burnable poison rod assembly (BPRA) or either gadolinia or integral fuel burnable absorber (IFBA) in a fresh fuel assembly does not affect the applicability of Figure 5.6-2 or Table 5.6-1.

Two alternative storage arrays (or sub-arrays) are acceptable in Region 1 if the fresh fuel assemblies contain rods with either gadolinia or integral fuel burnable absorber (IFBA). For these types of assemblies, the minimum burnup of the spent fuel in the 1- See ITS of-4 sub-array are defined by the equations in Table 5.6-2. 3.7.15 Restrictions in Region 1 Any of the three sub-arrays illustrated in Figure 5.6-1a may be used in any combination provided that:

1) Each sub-array of 4 fuel assemblies includes, in addition to the fresh fuel assembly, 3 assemblies with enrichment and minimum burnup requirements defined by the equations in Tables 5.6-1 and 5.6-2, as appropriate.

2) The arrangement of Region 1 sub-arrays must not allow a configuration with fresh assemblies adjacent to each other.

3) If Region 1 arrays are used in conjunction with Region 2 or Region 3 arrangements (see below), the arrangements shall not allow fresh fuel assemblies to be adjacent to each other (see also Figure 5.6-1).

• For some accident conditions, the presence of dissolved boron in the pool water may be taken into 4.3.1.1.b account by applying the double contingency principle which requires two unlikely, independent, concurrent events to produce a criticality accident.

December 19, 2000 SEQUOYAH - UNIT 1 5-5 Amendment No. 13, 60, 114, 144, 167, 265 Page 5 of 16 Enclosure 2, Volume 15, Rev. 0, Page 9 of 35

Enclosure 2, Volume 15, Rev. 0, Page 10 of 35 A01 ITS ITS Chapter 4.0 DESIGN FEATURES 4.3 5.6 FUEL STORAGE 4.3.1 CRITICALITY - NEW FUEL 4.3.1.2.a 5.6.1.2 The new fuel pit storage racks are designed for fuel enriched to 5.0 weight percent U-235 and shall be maintained with the arrangement of 146 storage locations shown in Figure 5.6-4. The cells shown 4.3.1.2.d as empty cells in Figure 5.6-4 shall have physical barriers installed to ensure that inadvertent loading of fuel assemblies into these locations does not occur. This configuration ensures keff will remain less than or 4.3.1.2.b equal to 0.95 when flooded with unborated water and less than or equal to 0.98 under optimum moderation 4.3.1.2.c conditions.

DRAINAGE 4.3.2 5.6.2 The spent fuel pit is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 722 ft.

CAPACITY 4.3.3 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 2091 fuel assemblies. In addition, no more than 225 fuel assemblies will be stored in a rack module in the cask loading area of the cask pit.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 DELETED August 2, 2006 SEQUOYAH - UNIT 1 5-5b Amendment No. 167, 225, 309 Page 6 of 16 Enclosure 2, Volume 15, Rev. 0, Page 10 of 35

Enclosure 2, Volume 15, Rev. 0, Page 11 of 35

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ITS Chapter 4.0 Figure 4 3.1 2-1 il Besic Cell ?l inch X 2l inch T Erp"f 9.4X5CdlR"ilEks Cell 146 / 180 t o'qling Penem Figure 5.6-4 New Fuel Pit Storage Rack Loading Pattern December 19, 2000 SEQUOYAH - UNIT 1 5-59 Amendment No. 225 Page 7 of 16 Enclosure 2, Volume 15, Rev. 0, Page 11 of 35

Enclosure 2, Volume 15, Rev. 0, Page 12 of 35 A01 ITS ITS Chapter 4.0 THIS PAGE INTENTIONALLY DELETED August 2, 2006 SEQUOYAH - UNIT 1 5-6 Amendment No. 36, 114, 157, 309 Page 8 of 16 32 Enclosure 2, Volume 15, Rev. 0, Page 12 of 35

Enclosure 2, Volume 15, Rev. 0, Page 13 of 35 A01 ITS ITS Chapter 4.0 5.0 DESIGN FEATURES 5.1 SITE LOCATION The Sequoyah Nuclear Plant is located on a site near the geographical center of Hamilton County, 4.1 Tennessee, on a peninsula on the western shore of Chickamauga Lake at Tennessee River mile (TRM) 484.5. The Sequoyah site is approximately 7.5 miles northeast of the nearest city limit of Chattanooga, Tennessee, 14 miles west-northwest of Cleveland, Tennessee, and approximately 31 miles south-southwest of TVA's Watts Bar Nuclear Plant.

EXCLUSION AREA 5.1.1 DELETED LOW POPULATION ZONE 5.1.2 DELETED SITE BOUNDARY FOR GASEOUS EFFLUENTS 5.1.3 DELETED SITE BOUNDARY FOR LIQUID EFFLUENTS 5.1.4 DELETED 5.2 CONTAINMENT 5.2.1 DELETED DESIGN PRESSURE AND TEMPERATURE 5.2.2 DELETED August 2, 2006 SEQUOYAH - UNIT 2 5-1 Amendment No. 298 Page 9 of 16 Enclosure 2, Volume 15, Rev. 0, Page 13 of 35

Enclosure 2, Volume 15, Rev. 0, Page 14 of 35 A01 ITS ITS Chapter 4.0 THIS PAGE INTENTIONALLY DELETED August 2, 2006 SEQUOYAH - UNIT 2 5-2 Amendment No. 34, 104, 298 Page 10 of 16 Enclosure 2, Volume 15, Rev. 0, Page 14 of 35

Enclosure 2, Volume 15, Rev. 0, Page 15 of 35 A01 ITS ITS Chapter 4.0 THIS PAGE INTENTIONALLY DELETED August 2, 2006 SEQYOYAH - UNIT 2 5-3 Amendment No. 298 Page 11 of 16 Enclosure 2, Volume 15, Rev. 0, Page 15 of 35

Enclosure 2, Volume 15, Rev. 0, Page 16 of 35 A01 ITS ITS Chapter 4.0 DESIGN FEATURES 4.2 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of zircaloy or M5 clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance 4.2.1 with NRC-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 regions.

Sequoyah is authorized to place a limited number of lead test assemblies into the reactor, as described in the Framatome Cogema Fuels Report BAW-2328, beginning with the Unit 2 Operating Cycle 10 core.

CONTROL ROD ASSEMBLIES 4.2.2 5.3.2 The reactor core shall contain 53 full length and no part length control rod assemblies. The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 DELETED VOLUME 5.4.2 DELETED 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 DELETED August 2, 2006 SEQUOYAH - UNIT 2 5-4 Amendment No 37, 125, 172, 234, 249, 298 Page 12 of 16 Enclosure 2, Volume 15, Rev. 0, Page 16 of 35

Enclosure 2, Volume 15, Rev. 0, Page 17 of 35 A01 ITS ITS Chapter 4.0 DESIGN FEATURES 4.3 5.6 FUEL STORAGE 4.3.1 CRITICALITY - SPENT FUEL 4.3.1.1 5.6.1.1 The spent fuel storage racks are designed for fuel enriched to 5 weight percent U-235 and shall be maintained with:

4.3.1.1.a 4.3.1.1.b

a. A keff less than critical when flooded with unborated water and a keff less than or equal to 0.95 when flooded with water containing 300 ppm soluble boron.*

4.3.1.1.c

b. A nominal 8.972 inch center-to-center distance between fuel assemblies placed in the storage racks.

c. Arrangements of one or more of three different arrays (Regions) or sub-arrays as illustrated in Figures 5.6-1 and 5.6-1a. These arrangements in the spent fuel storage pool have the following definitions:

1. Region 1 is designed to accommodate new fuel with a maximum enrichment of 4.95

+/- 0.05 wt% U-235, (or spent fuel regardless of the fuel burnup), in a 1-in-4 checkerboard arrangement of 1 fresh assembly with 3 spent fuel assemblies with enrichment-burnup and cooling times illustrated in Figure 5.6-2 and defined by the equations in Table 5.6-1. Cooling time is defined as the period since reactor shutdown at the end of the last operating cycle for the discharged spent fuel assembly. The presence of a removable, non-fissile insert such as a burnable poison rod assembly (BPRA) or either gadolinia or integral fuel burnable absorber (IFBA) in a fresh fuel assembly does not affect the applicability of Figure 5.6-2 or Table 5.6-1.

Two alternative storage arrays (or sub-arrays) are acceptable in Region 1 if the fresh fuel assemblies contain rods with either gadolinia or integral fuel burnable absorber (IFBA). For these types of assemblies, the minimum burnup of the spent fuel in the See ITS 1-of-4 sub-array are defined by the equations in Table 5.6-2. 3.7.15 Restrictions in Region 1 Any of the three sub-arrays illustrated in Figure 5.6-1a may be used in any combination provided that:

1) Each sub-array of 4 fuel assemblies includes, in addition to the fresh fuel assembly, 3 assemblies with enrichment and minimum burnup requirements defined by the equations in Tables 5.6-1 and 5.6-2, as appropriate.

2) The arrangement of Region 1 sub-arrays must not allow a configuration with fresh assemblies adjacent to each other.

3) If Region 1 arrays are used in conjunction with Region 2 or Region 3 arrangements (see below), the arrangements shall not allow fresh fuel assemblies to be adjacent to each other (see also Figure 5.6-1).

• For some accident conditions, the presence of dissolved boron in the pool water may be taken 4.3.1.1.b into account by applying the double contingency principle which requires two unlikely, independent, concurrent events to produce a criticality accident.

December 19, 2000 SEQUOYAH - UNIT 2 5-5 Amendment No. 4, 52, 125, 157, 256 Page 13 of 16 Enclosure 2, Volume 15, Rev. 0, Page 17 of 35

Enclosure 2, Volume 15, Rev. 0, Page 18 of 35 A01 ITS ITS Chapter 4.0 DESIGN FEATURES 4.3 5.6 FUEL STORAGE 4.3.1 CRITICALITY - NEW FUEL 4.3.1.2.a 5.6.1.2 The new fuel pit storage racks are designed for fuel enriched to 5.0 weight percent U-235 and shall be maintained with the arrangement of 146 storage locations shown in Figure 5.6-4. The cells 4.3.1.2.d shown as empty cells in Figure 5.6-4 shall have physical barriers installed to ensure that inadvertent loading of fuel assemblies into these locations does not occur. This configuration ensures keff will remain 4.3.1.2.b less than or equal to 0.95 when flooded with unborated water and less than or equal to 0.98 under 4.3.1.2.c optimum moderation conditions.

DRAINAGE 4.3.2 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 722 ft.

CAPACITY 4.3.3 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 2091 fuel assemblies. In addition, no more than 225 fuel assemblies will be stored in a rack module in the cask loading area of the cask pit.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 DELETED August 2, 2006 SEQUOYAH - UNIT 2 5-5b Amendment No. 157, 216, 298 Page 14 of 16 Enclosure 2, Volume 15, Rev. 0, Page 18 of 35

Enclosure 2, Volume 15, Rev. 0, Page 19 of 35 ITS G) ITS Chapter 4 A Figure4312-1 n Besic Cell 3l inch .X 3l incb T E*pry Cdl 9.4X5CdlRscks 146 / t80 t"o'.tjng Pancm Figure 5.6-4 New Fuel Pit Storage Rack Loading Pattern December 19, 2000 SEQUOYAH - UNIT 2 5-59 Amendment No. 216 Page 15 of 16 Enclosure 2, Volume 15, Rev. 0, Page 19 of 35

Enclosure 2, Volume 15, Rev. 0, Page 20 of 35 A01 ITS ITS Chapter 4.0 THIS PAGE INTENTIONALLY DELETED August 2, 2006 SEQUOYAH - UNIT 2 5-6 Amendment No. 28, 104, 147, 298 Page 16 of 16 Enclosure 2, Volume 15, Rev. 0, Page 20 of 35

Enclosure 2, Volume 15, Rev. 0, Page 21 of 35 DISCUSSION OF CHANGES ITS Chapter 4.0, DESIGN FEATURES ADMINISTRATIVE CHANGES A01 In the conversion of the Sequoyah Nuclear Plant (SQN) Current Technical Specifications (CTS) to the plant specific Improved Technical Specifications (ITS), certain changes (wording preferences, editorial changes, reformatting, revised numbering, etc.) are made to obtain consistency with NUREG - 1431, Rev. 4.0, "Standard Technical Specifications - Westinghouse Plants" (ISTS) and additional Technical Specification Task Force (TSTF) travelers included in this submittal.

These changes are designated as administrative changes and are acceptable because they do not result in technical changes to the CTS.

MORE RESTRICTIVE CHANGES None RELOCATED SPECIFICATIONS None REMOVED DETAIL CHANGES None LESS RESTRICTIVE CHANGES None Sequoyah Unit 1 and Unit 2 Page 1 of 1 Enclosure 2, Volume 15, Rev. 0, Page 21 of 35

Enclosure 2, Volume 15, Rev. 0, Page 22 of 35 Improved Standard Technical Specifications (ISTS) Markup and Justification for Deviations (JFDs)

Enclosure 2, Volume 15, Rev. 0, Page 22 of 35

Enclosure 2, Volume 15, Rev. 0, Page 23 of 35 CTS Design Features 4.0 4.0 DESIGN FEATURES 5.1 4.1 Site Location INSERT 1

[ Text description of site location. ] 1 5.3 4.2 Reactor Core 5.3.1 4.2.1 Fuel Assemblies 193 M5 clad The reactor shall contain [157] fuel assemblies. Each assembly shall consist of a 1 matrix of [Zircalloy or ZIRLO] fuel rods with an initial composition of natural or 5 Zircaloy slightly enriched uranium dioxide (UO2) 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 regions. 2 INSERT 2 5.3.2 4.2.2 [Control Rod] Assemblies 1 53 full length and no part length The reactor core shall contain [48] [control rod] assemblies. The control material 1 shall be [silver indium cadmium, boron carbide, or hafnium metal] as approved by 2 the NRC. INSERT 3 5.6 4.3 Fuel Storage 5.6 4.3.1 Criticality 5.6.1.1 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

5.6.1.1 a. Fuel assemblies having a maximum U-235 enrichment of

[4.5] weight percent, 1 3 5.0  ;

5.6.1.1.a, b. keff 0.95 if fully flooded with unborated water, which includes an Footnote

• allowance for uncertainties as described in [Section 9.1 of the 2 FSAR], INSERT 4 8.972 5.6.1.1.b [ c. A nominal [9.15] inch center to center distance between fuel 1 assemblies placed in [the high density fuel storage racks], ]

[ d. A nominal [10.95] inch center to center distance between fuel 1 assemblies placed in [low density fuel storage racks], ]

SEQUOYAH UNIT 1 Amendment XXX Westinghouse STS 4.0-1 Rev. 4.0 4 Enclosure 2, Volume 15, Rev. 0, Page 23 of 35

Enclosure 2, Volume 15, Rev. 0, Page 24 of 35 CTS 4.0 1

INSERT 1 5.1 The Sequoyah Nuclear Plant is located on a site near the geographical center of Hamilton County, Tennessee, on a peninsula on the western shore of Chickamauga Lake at Tennessee River mile (TRM) 484.5. The Sequoyah site is approximately 7.5 miles northeast of the nearest city limit of Chattanooga, Tennessee, 14 miles west-northwest of Cleveland, Tennessee, and approximately 31 miles south-southwest of TVA's Watts Bar Nuclear Plant.

2 INSERT 2 5.3.1 Sequoyah is authorized to place a limited number of lead test assemblies into the reactor as described in the Framatome-Cogema Fuels report BAW-2328, beginning with the Unit 1 Operating Cycle 12.

2 INSERT 3 5.3.2 The full length control rod assemblies shall contain a nominal 142 inches of absorber material.

The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing.

2 INSERT 4 5.6.1.1.a, A keff less than critical when flooded with unborated water and a keff less than or equal to 0.95 Footnote

• when flooded with water containing 300 ppm soluble boron. For some accident conditions, the presence of dissolved boron in the pool water may be taken into account by applying the double contingency principle which requires two unlikely, independent, concurrent events to produce a criticality accident; and Insert Page 4.0-1 Enclosure 2, Volume 15, Rev. 0, Page 24 of 35

Enclosure 2, Volume 15, Rev. 0, Page 25 of 35 CTS Design Features 4.0 4.0 DESIGN FEATURES 5.6 4.3 Fuel Storage (continued)

[ e. New or partially spent fuel assemblies with a discharge burnup in the "acceptable range" of Figure [3.7.17-1] may be allowed 1 unrestricted storage in [either] fuel storage rack(s), and ]

[ f. New or partially spent fuel assemblies with a discharge burnup in the "unacceptable range" of Figure [3.7.17-1] will be stored in compliance with the NRC approved [specific document containing 1 the analytical methods, title, date, or specific configuration or figure]. ]

5.6.1.2 4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

5.6.1.2 a. Fuel assemblies having a maximum U-235 enrichment of

[4.5] weight percent, 1 3 5.0  ;  ;

5.6.1.2 b. keff 0.95 if fully flooded with unborated water, which includes an 2 3

allowance for uncertainties as described in [Section 9.1 of the 1 FSAR],

under optimum moderation conditions; 5.6.1.2 c. keff 0.98 if moderated by aqueous foam, which includes an 2 allowance for uncertainties as described in [Section 9.1 of the 1 FSAR], and 3 INSERT 5 5.6.1.2 d. A nominal [10.95] inch center to center distance between fuel 1 2

assemblies placed in the storage racks.

5.6. 2 4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation [23 ft]. 1 722 5.6.3 4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage 2091 capacity limited to no more than [1737] fuel assemblies. INSERT 6 1 2 2

INSERT 7 SEQUOYAH UNIT 1 Amendment XXX Westinghouse STS 4.0-2 Rev. 4.0 4 Enclosure 2, Volume 15, Rev. 0, Page 25 of 35

Enclosure 2, Volume 15, Rev. 0, Page 26 of 35 CTS 4.0 2

INSERT 5 5.6.1.2 The arrangement of 146 storage locations shown in Figure 4.3.1.2-1. The cells shown as empty cells in Figure 4.3.1.2-1 shall have physical barriers installed to ensure that inadvertent loading of fuel assemblies into these locations does not occur.

2 INSERT 6 5.6.3 In addition, no more than 225 fuel assemblies will be stored in a rack module in the cask loading area of the cask pit.

Insert Page 4.0-2a Enclosure 2, Volume 15, Rev. 0, Page 26 of 35

Enclosure 2, Volume 15, Rev. 0, Page 27 of 35 CTS 4.0 2

INSERT 7 Basic Cell 21 inch X 21 inch Empty Cell 9 - 4 X 5 Cell Racks 146 / 180 Loading Pattern Figure 5.6-4 Figure 4.3.1.2-1 New Fuel Storage Rack Loading Pattern Insert Page 4.0-2b Enclosure 2, Volume 15, Rev. 0, Page 27 of 35

Enclosure 2, Volume 15, Rev. 0, Page 28 of 35 CTS Design Features 4.0 4.0 DESIGN FEATURES 5.1 4.1 Site Location INSERT 1

[ Text description of site location. ] 1 5.3 4.2 Reactor Core 5.3.1 4.2.1 Fuel Assemblies 193 M5 clad The reactor shall contain [157] fuel assemblies. Each assembly shall consist of a 1 matrix of [Zircalloy or ZIRLO] fuel rods with an initial composition of natural or 5 Zircaloy slightly enriched uranium dioxide (UO2) 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 regions. 2 INSERT 2 5.3.2 4.2.2 [Control Rod] Assemblies 1 53 full length and no part length The reactor core shall contain [48] [control rod] assemblies. The control material 1 shall be [silver indium cadmium, boron carbide, or hafnium metal] as approved by 2 the NRC. INSERT 3 5.6 4.3 Fuel Storage 5.6 4.3.1 Criticality 5.6.1.1 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

5.6.1.1 a. Fuel assemblies having a maximum U-235 enrichment of

[4.5] weight percent, 1 3 5.0  ;

5.6.1.1.a, b. keff 0.95 if fully flooded with unborated water, which includes an Footnote

• allowance for uncertainties as described in [Section 9.1 of the 2 FSAR], INSERT 4 8.972 5.6.1.1.b [ c. A nominal [9.15] inch center to center distance between fuel 1 assemblies placed in [the high density fuel storage racks], ]

[ d. A nominal [10.95] inch center to center distance between fuel 1 assemblies placed in [low density fuel storage racks], ]

SEQUOYAH UNIT 2 Amendment XXX Westinghouse STS 4.0-1 Rev. 4.0 4 Enclosure 2, Volume 15, Rev. 0, Page 28 of 35

Enclosure 2, Volume 15, Rev. 0, Page 29 of 35 CTS 4.0 1

INSERT 1 5.1 The Sequoyah Nuclear Plant is located on a site near the geographical center of Hamilton County, Tennessee, on a peninsula on the western shore of Chickamauga Lake at Tennessee River mile (TRM) 484.5. The Sequoyah site is approximately 7.5 miles northeast of the nearest city limit of Chattanooga, Tennessee, 14 miles west-northwest of Cleveland, Tennessee, and approximately 31 miles south-southwest of TVA's Watts Bar Nuclear Plant.

2 INSERT 2 5.3.1 Sequoyah is authorized to place a limited number of lead test assemblies into the reactor as described in the Framatome-Cogema Fuels report BAW-2328, beginning with the Unit 1 Operating Cycle 12.

2 INSERT 3 5.3.2 The full length control rod assemblies shall contain a nominal 142 inches of absorber material.

The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing.

2 INSERT 4 5.6.1.1.a, A keff less than critical when flooded with unborated water and a keff less than or equal to 0.95 Footnote

• when flooded with water containing 300 ppm soluble boron. For some accident conditions, the presence of dissolved boron in the pool water may be taken into account by applying the double contingency principle which requires two unlikely, independent, concurrent events to produce a criticality accident; and Insert Page 4.0-1 Enclosure 2, Volume 15, Rev. 0, Page 29 of 35

Enclosure 2, Volume 15, Rev. 0, Page 30 of 35 CTS Design Features 4.0 4.0 DESIGN FEATURES 5.6 4.3 Fuel Storage (continued)

[ e. New or partially spent fuel assemblies with a discharge burnup in the "acceptable range" of Figure [3.7.17-1] may be allowed 1 unrestricted storage in [either] fuel storage rack(s), and ]

[ f. New or partially spent fuel assemblies with a discharge burnup in the "unacceptable range" of Figure [3.7.17-1] will be stored in compliance with the NRC approved [specific document containing 1 the analytical methods, title, date, or specific configuration or figure]. ]

5.6.1.2 4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

5.6.1.2 a. Fuel assemblies having a maximum U-235 enrichment of

[4.5] weight percent, 1 3 5.0  ;  ;

5.6.1.2 b. keff 0.95 if fully flooded with unborated water, which includes an 2 3

allowance for uncertainties as described in [Section 9.1 of the 1 FSAR],

under optimum moderation conditions; 5.6.1.2 c. keff 0.98 if moderated by aqueous foam, which includes an 2 allowance for uncertainties as described in [Section 9.1 of the 1 FSAR], and 3 INSERT 5 5.6.1.2 d. A nominal [10.95] inch center to center distance between fuel 1 2

assemblies placed in the storage racks.

5.6. 2 4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation [23 ft]. 1 722 5.6.3 4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage 2091 capacity limited to no more than [1737] fuel assemblies. INSERT 6 1 2 2

INSERT 7 SEQUOYAH UNIT 2 Amendment XXX Westinghouse STS 4.0-2 Rev. 4.0 4 Enclosure 2, Volume 15, Rev. 0, Page 30 of 35

Enclosure 2, Volume 15, Rev. 0, Page 31 of 35 CTS 4.0 2

INSERT 5 5.6.1.2 The arrangement of 146 storage locations shown in Figure 4.3.1.2-1. The cells shown as empty cells in Figure 4.3.1.2-1 shall have physical barriers installed to ensure that inadvertent loading of fuel assemblies into these locations does not occur.

2 INSERT 6 5.6.3 In addition, no more than 225 fuel assemblies will be stored in a rack module in the cask loading area of the cask pit.

Insert Page 4.0-2a Enclosure 2, Volume 15, Rev. 0, Page 31 of 35

Enclosure 2, Volume 15, Rev. 0, Page 32 of 35 CTS 4.0 2

INSERT 7 Basic Cell 21 inch X 21 inch Empty Cell 9 - 4 X 5 Cell Racks 146 / 180 Loading Pattern Figure 5.6-4 Figure 4.3.1.2-1 New Fuel Storage Rack Loading Pattern Insert Page 4.0-2b Enclosure 2, Volume 15, Rev. 0, Page 32 of 35

Enclosure 2, Volume 15, Rev. 0, Page 33 of 35 JUSTIFICATION FOR DEVIATIONS ITS Chapter 4.0, DESIGN FEATURES

1. The ISTS contains bracketed information and/or values that are generic to Westinghouse vintage plants. The brackets are removed and the proper plant specific information/value is inserted to reflect the current licensing basis.

2. ISTS 4.0 has been changed to address Sequoyah Nuclear Plant (SQN) site specific requirements for fuel assemblies, control rod assemblies, and fuel storage. This change is acceptable because it reflects the current licensing basis.

3. These punctuation corrections have been made consistent with the Writer's Guide for the Improved Technical Specifications, TSTF-GG-05-01, Section 5.1.3.

4. Changes are made (additions, deletions, and/or changes) to the ISTS that reflect the plant specific nomenclature, number, reference, system description, analysis, or licensing basis description.

5. Typographical/grammatical error corrected.

Sequoyah Unit 1 and Unit 2 Page 1 of 1 Enclosure 2, Volume 15, Rev. 0, Page 33 of 35

Enclosure 2, Volume 15, Rev. 0, Page 34 of 35 Specific No Significant Hazards Considerations (NSHCs)

Enclosure 2, Volume 15, Rev. 0, Page 34 of 35

Enclosure 2, Volume 15, Rev. 0, Page 35 of 35 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATIONS ITS Chapter 4.0, DESIGN FEATURES There are no specific No Significant Hazards Considerations for this Specification.

Sequoyah Unit 1 and 2 Page 1 of 1 Enclosure 2, Volume 15, Rev. 0, Page 35 of 35