ML080310826

Technical Specifications Amendment 151/License NPF-85, Allowed a One Time Type a Test Extension

ML080310826
Person / Time
Site:	Limerick
Issue date:	02/20/2008
From:	Peter Bamford NRC/NRR/ADRO/DORL/LPLI-2
To:	Pardee C Exelon Generation Co
Bamford, Peter J., NRR/DORL 415-2833
Shared Package
ml080310759	List: ML080310769 ML080310786 ML080310826
References
TAC MD5199
Download: ML080310826 (2)

Text

(4) Pursuant to the Act and 10 CFR Parts 30, 40, 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 facility, and to receive and possess, but not separate, such source, byproduct, and special nuclear materials.as contained in the fuel assemblies and fuel channels from the Shoreham Nuclear Power Station.

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 (except as exempted from compliance in Section 2.D. below) 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 Exelon Generation Company is authorized to operate the facility at reactor core power levels of 3458 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 151 , are hereby incorporated into this license. Exelon Generation Company shall operate the facility in accordance with the.Technical Specifications and the Environmental Protection Plan.

(3) Fire Protection (Section 9.5, SSER-2, A4)*

Exelon Generation Company shall implement and. maintain in effect all provisions of the approved Fire Protection Program as described in the Updated Final Safety Analysis Report for the facility, and as approved in the NRC Safety Evaluation Report dated August 1983 through Supplement 9, dated August 1989, and Safety Evaluation dated November 20, 1995, subject to the following provision:

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

• The parenthetical notation following the title of license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

Amendment No. 1-, 2-7, 51-, 68, 2, 4-98, 151

ADMINISTRATIVE CONTROLS .... _ _

PROCEDURES AND PROGRAMS (Continued)

g. Primary Containment Leakage Rate.Testing Programr A program shalll be established to implement the leakage rate testing of the containment as required by 10*CFR 50.54 .(o) and 10-CFR 50, Appendix J,

• Option B, as modi fled "by approved exemptions. Th.is program shall be in accordancewith the guidelines contained.in Regulatory Guide 1.163 "Performance-Based Containment Leakage Test program," dated September 1995, as modified by the following exception.to NEI 94-01, Rev. 0.,

"Industry JY'Guideline"for Implementing Performance-Based Option of 10 CFR 50, Appendix

a. Section 9.2.3: The first Type A test performed after May211 1999 shall be performed no later than May 21, 2014.

The peak calculated containment internal pressure.for the design *basis loss of coolant accident, Pa, is 44.0 psig.

The maximum' allowable primary containment leakage rate, La, at P,., shall be 0.5% of primary containment air weight per day.

Leakage rate acceptance criteria are:

a. Primary Containment leakage rate acceptance criterion is less than or equal to 1.0 L During the first unit startup following testing in, accordance with this program, the leakage rate acceptance criteria are less than or equal to 0.60 La for the Type B and Type C tests and less than or equal to 0.75 L. for Type A tests;

b. Air.lock testing acceptance criteria, are:

1) Overall airlock leakage *rate is less than or equal to 0.05 L, when tested at greater than or equal to P,.

2) Seal leakage rate is less than or equal to 5 scf er hour when the gap between the door seals is pressurized to 10 psig.

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

The provisions of Specification 4.0.3 are applicable to the tests described in the Primary Containment Leakage Rate Testing Program.

h: Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

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:

A change in the TS incorporated in the license; or A change to the UFSAR 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 UFSAR.

d. Proposed changes that meet the criteria of 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).

LIMERICK - UNIT 2 6-14c Amendment No. 9-ý, 24, 151