ML062230111

Tech Spec Pages for Amendment 298 Regarding Changes to Cyclic and Transient Limits with Design Features Revision (TS 05-02)

ML062230111
Person / Time
Site:	Sequoyah
Issue date:	08/02/2006
From:	NRC/NRR/ADRO/DORL/LPLII-2
To:
Pickett D, NRR/DORL, 415-1364
Shared Package
ML061390246	List: ML062230095 ML062230111
References
TAC MC8532, TAC MC8533
Download: ML062230111 (11)

Text

(4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the Sequoyah and Watts Bar Unit 1 Nuclear Plants.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The Tennessee Valley Authority is authorized to operate the facility at reactor core power levels not in excess of 3455 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.2 9 8 , are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Initial Test Program The Tennessee Valley Authority shall conduct the post-fuel-loading initial test program (set forth in Section 14 of Tennessee Valley Authority's Final Safety Analysis Report, as amended), without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:

a. Elimination of any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential;

b. Modification of test objectives, methods or acceptance criteria for any test identified in Section 14 of TVA's Final Safety Analysis Report as amended as being essential;

c. Performance of any test at power level different from there described; and Amendment No. 298

INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE LOCATIO N ................................................................................................................................... 5-1 EXCLUSION AREA (DELETED) ................................................................................................... 5-1 LOW POPULATION ZONE (DELETED) ....................................................................................... 5-1 SITE BOUNDARY FOR GASEOUS EFFLUENTS (DELETED) .................................................... 5-1 SITE BOUNDARY FOR LIQ UID EFFLUENTS (DELETED) .......................................................... 5-1 5.2 CONTAINM ENT (DELETED) ................................................................................................................ 5-1 CONFIG URATION (DELETED) ..................................................................................................... 5-1 DESIGN PRESSURE AND TEM PERATURE (DELETED) ........................................................... 5-1 5.3 REACTOR CORE FUEL ASSEM BLIES ....................................................................................................................... 5-4 CO NTROL ROD ASSEM BLIES ...................................................................................................... 5-4 5.4 REACTO R COOLANT SYSTEM (DELETED) ..................................................................................... 5-4 DESIGN PRESSURE AND TEMPERATURE (DELETED) ........................................................... 5-4 VOLUM E (DELETED) .................................................................................................................... 5-4 5.5 METEORO LOG ICAL TOW ER LOCATION (DELETED) ..................................................................... 5-4 5.6 FUEL STORAGE CRITICALITY - SPENT FUEL ......................................................................................................... 5-5 CRITICALITY - NEW FUEL ......................................................................................................... 5-5a DRA INAGE ................................................................................................................................... 5-5a CAPACITY ............................................................................ ........................................................ 5-5b 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT (DELETED) ........................................................... 5-5b SEQUOYAH - UNIT 2 XVI Amendment No 298

DEFINITIONS RATED THERMAL POWER (RTP) 1.27 RATED THERMAL POWER (RTP) shall be a total reactor core heat transfer rate to the reactor coolant of 3455 MWt.

REACTOR TRIP SYSTEM (RTS) RESPONSE TIME 1.28 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its (RTS) trip setpoint at the channel sensor until loss of stationary gripper coil voltage. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and the methodology for verification have been previously reviewed and approved by NRC.

REPORTABLE EVENT 1.29 DELETED SHIELD BUILDING INTEGRITY 1.30 SHIELD BUILDING INTEGRITY shall exist when:

a. The door in each access opening is closed except when the access opening is being used for normal transit entry and exit.

b. The emergency gas treatment system is OPERABLE.

c. The sealing mechanism associated with each penetration (e.g., welds, bellows or O-rings) is OPERABLE.

SHUTDOWN MARGIN 1.31 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

SITE BOUNDARY 1.32 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee.

SEQUOYAH - UNIT 2 1-6 Amendment No. 63, 132, 146, 242, 264, 267, 284, 298

5.0 DESIGN FEATURES 5.1 SITE LOCATION 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.

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 I SEQUOYAH - UNIT 2 5-1 Amendment No. 298

THIS PAGE INTENTIONALLY DELETED 5-2 Amendment No. 34,104, 298 SEQUOYAH - UNIT 2

THIS PAGE INTENTIONALLY DELETED SEQYOYAH - UNIT 2 5-3 Amendment No- 298

DESIGN FEATURES 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-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 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 SEQUOYAH - UNIT 2 5-4 Amendment No. 37, 125, 172, 234, 249, 298

DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY - NEW FUEL 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 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 equal to 0.95 when flooded with unborated water and less than or equal to 0.98 under optimum moderation conditions.

DRAINAGE 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 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 SEQUOYAH - UNIT 2 5-5b Amendment No. 157, 216, 298

THIS PAGE INTENTIONALLY DELETED SEQUOYAH - UNIT 2 5-6 Amendment No. 28, 104, 147, 298

ADMINISTRATIVE CONTROLS

b. Air lock testing acceptance criteria are:

1) Overall air lock leakage rate is _ 0.05 La when tested at _ŽPa.

2) For each door, leakage rate is _ 0.01 La when pressurized to Ž>6 psig for at least two minutes.

The provisions of SR 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

The provisions of SR 4.0.3 are applicable to the Containment Leakage Rate Testing Program.

i. Configuration Risk Management Program (DELETED)

j. Technical Specification (TS) Bases Control Program This program provides a means for processing changes to the Bases of these TSs.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1. A change in the TS incorporated in the license or

2. A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.

d. Proposed changes that meet the criteria of Specification 6.8.4.j.b above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

k. Reserved I. Component Cyclic and Transient Limit This program provides controls to track the FSAR, Section 5.2.1, cyclic and transient occurrences to ensure that components are maintained within the design limits.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted in accordance with 10 CFR 50.4.

SEQUOYAH - UNIT 2 6-10 Amendment No. 28, 50, 64, 66, 134, 207, 223, 231, 271,272, 298

ADMINISTRATIVE CONTROLS STARTUP REPORT 6.9.1.1 DELETED 6.9.1.2 DELETED 6.9.1.3 DELETED ANNUAL REPORTS-6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 DELETED 1-A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

SEQUOYAH - UNIT 2 6-11 Amendment No. 28, 34, 50, 64, 66, 107, 134, 165, 207. 223, 231, 271, 272, 289,298