ML073320367

Technical Specifications, Issuance of Amendment Storage of Areva Np Fuel

ML073320367
Person / Time
Site:	Brunswick
Issue date:	11/27/2007
From:	NRC/NRR/ADRO/DORL/LPLII-2
To:
Bailey S , NRR/DORL,415-1321
Shared Package
ML073310582	List: ML073310552 ML073320367
References
TAC MD4061, TAC MD4062
Download: ML073320367 (6)

Text

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 243, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.

For Surveillance Requirements (SRs) that are new in Amendment 203 to Renewed Facility Operating License DPR-71, the first performance is due at the end of the first surveillance interval that begins at implementation

,of Amendment 203. For SRs that existed prior to Amendment 203, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 203.

(a)

Effective June 30, 1982, the surveillance requirements listed below need not be completed until July 15, 1982. Upon accomplishment of the surveillances, the provisions of Technical Specification 4.0.2 shall apply.

Specification 4.3.3.1, Table 4.3.3,-1 Items 5.a and 5.b (b)

Effective July 11 1982, through July 8, 1982, Action statement "a" of Technical Specification 3.8.1.1 shall read as follows:

ACTION:

a. With either one offsite circuit or one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.A. sources by performing Surveillance Requirements 4.8.1.1.1.a and 4.8.1.1.2.a.4 within two hours and at least once per. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter;. restore at least two offsite circuits and four diesel generators to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within. the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(3)

Deleted by Amendment No. 206.

D.

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of.

.10 CFR 50.90 and 1.0 CFR :50.54(p). The plans, which contain Safeguards Information protected under-10 CFR 73.21, are entitled: -'Physical Security Plan; Revision 2," and "Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006, and "Guard Training and Qualification Plan, Revision 0,"

submitted by letter dated September 30, 2004.

Renewed License No. DPR-71' Amendment No. 243

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location 4.1.1 Site and Exclusion Areas The site area and exclusion area are the same area. This area is and shall be maintained as the area located within the site area boundary as shown in Figure 4.1-1.

4.1.2 Low Population Zone The low population zone is and shall be maintained as the area located within a circle with its center at the plant and a radius of two miles.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 560 fuel assemblies. Each assembly shall consist of a matrix of Zircaloy clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (U0 2) as fuel material, gadolinia rods, water rods or channels, and a surrounding channel. 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 NRC staff approved codes and methods and have been shown by tests or analyses to comply with all safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

4.2.2 Control Rod Assemblies The reactor core shall contain 137 cruciform shaped control rod assemblies.

The control material shall be boron carbide or hafnium absorber material as approved by the NRC.

(continued)

Brunswick Unit 1 4.0-1 Amendment No. 243 I

Design Features 4.0 4.0 DESIGN FEATURES (continued) 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.

PressurizedWater Reactor (PWR) fuel assemblies having a maximum k-infinity of 1.41 in the normal reactor core configuration at Cold conditions;

b.

(Not used.)

c.

keff 5 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; and

d.

Sufficient center to center distance between fuel assemblies placed in the storage racks to ensure the ke, limit is not exceeded.

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

a.

(Not used.)

b.

keff < 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;

c.

ke,<ft 0.90 when in a dry condition, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; and

d.

Sufficient center to center distance between fuel assemblies placed in storage racks to ensure the keff limits are not exceeded.

(continued)

Brunswick Unit 1

• 4.0-2 Amendment No. 243 1

as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (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, and special nuclear materials without restriction to chemical of physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5)

Pursuant to the Act and 10 CFR Parts 30 and 70 to posses, but not separate, such byproduct and special nuclear materials as may be produced by the operation of Brunswick Steam Electric Plant, Unit Nos. 1 and 2, and H. B. Robinson Steam Electric Plant, Unit No. 2 (6)

Carolina Power & Light Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Report dated November 22, 1977, as supplemented April 1979, June 11, 1980, December 30, 1986, December.6, 1989, July 28, 1993, and February 10, 1994 respectively, subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

C.

This renewed license shall be deemed to contain and is subject.to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2923 megawatts (thermal).

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as.

revised.through Amendment No. 271*,are hereby incorporatedin the license. Carolina Power &* Light Company shall operate the facility in aCcordance with the Technical Specifications.

Renewed License No. DPR-62 Amendment No. 271

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location 4.1.1 Site and Exclusion Areas The site area and exclusion area are the same area. This area is and shall be maintained as the area located within the site area boundary as shown in Figure 4.1-1.

4.1.2 Low Population Zone The low population zone is and shall be maintained as the area located within a circle with its center at the plant and a radius of two miles.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 560 fuel assemblies. Each assembly shall consist of a matrix of Zircaloy clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (U0 2 ) as fuel material, gadolinia rods, water rods or channels, and a surrounding channel. 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 NRC staff approved codes and methods and have been shown by tests or analyses to comply with all safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

4.2.2 Control Rod Assemblies The reactor core shall contain 137 cruciform shaped control rod assemblies.

The control material shall be boron carbide or hafnium absorber material as approved by the NRC.

(continued)

Brunswick Unit 2 4.0-1 Amendment No. 271 I

Design Features 4.0 4.0 DESIGN FEATURES (continued) 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.

Pressurized Water Reactor (PWR) fuel assemblies having a maximum k-infinity of 1,41 in the normal reactor core configuration at cold conditions;

b.

(Not used.)

c.

keff 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; and

d.

Sufficient center to center distance between fuel assemblies placed in the storage racks to ensure the keff limit.is not exceeded.

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

a.

(Not used.)

b.

kef < 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR;

c.

keff<5 0.90 when in adry condition, which includes an allowance for uncertainties as described in Section 9.1 of the-UFSAR; and

d.

Sufficient center to center distance between fuel assemblies placed in storage racks to ensure the keff limits are not exceeded.

(continued)

Brunswick Unit 2 4.0-2 Amendment No. 271 I