ML080430565

Tech Spec Pages for Amendment 244 Regarding Extension of Appendix J, Type a Integrated Leakage Rate Test Interval

ML080430565
Person / Time
Site:	McGuire
Issue date:	02/13/2008
From:	NRC/NRR/ADRO/DORL/LPLII-1
To:
Stang J, NRR/DORL, 415-13456
Shared Package
ML073400621	List: ML073400670 ML080430565
References
TAC MD4654
Download: ML080430565 (2)

Text

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(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; (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproducts and spedal nuclear materials as may be produced by the operation of McGuire Nuclear Station, Units 1 and 2, and; (6) Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.

C. This renewed operating license shell 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 Inaffect; and Is subject to the additional conditions specified or Incorporated below:.

(1) Maximum P0wer Level The licensee Is authorized to operate the facility at a reactor core full steady state power level of 3411 megawatts thermal (100%).

(2) Technical Specificatlons The Technical S pecifications contained In Appendix A, as revised through Amendment No.-244 kare hereby incorporated into this renewed operating license. The licen~ee shall operate the facility in accordance with the Technical Specifications.

(3) Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation.

Duke shall complete these activities no later than June 12, 2021, and shall notify the NRC In writing when implementation of these activities Is complete and can be verified by NRC Inspection.

The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be Included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (eX4), following Issuance of this renewed operating license.

Until that update is complete, Duke may make changes to the programs described in.such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth In 10 CFR 50.59 and otherwise complies with the requirements In that section.

Renewed License No. NPF-9 Amendment No, 244-

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs'and Manuals The following programs shall be established, implemented, and maintained.

5.5.1 Offsite Dose Calculation Manual (ODCM)

The ODCM shall contain the methodology and. parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program.

Licensee initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained.

This documentation shall contain:

1. sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and

2. a determination that the change(s) do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

b. Shall become effective after the approval of the Station Manager; and

c. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that

-was-changed, and-shall-indicate-the-date-(ie--e-.7moth-aýnd-aY)- th-echan-ge" was implemented.

5.5.2 Containment Leakage Rate Testing Program A program shall 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 modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based.

Conma,,,f,,e,,-kt est Program," dated September 1995, as modified by the following exceptions:

NEI 94-01-1995, Section 9.2.3: The first.Type A test performed after the May 27, 1993 (Unit 1) and August 20, 1993 (Unit 2) Type A test shall be performed no later than plant restart after the End Of Cycle 19 Refueling Outage (Unit 1) and August 19, 2008 (Unit 2), and McGuire Units 1 and 2 5.5-1 ) Amendment Nos. 244/193