ML063260025

Tech Spec Pages for Amendment 191 Technical Specification 5.6.5, Core Operating Limits Report (COLR)

ML063260025
Person / Time
Site:	Diablo Canyon
Issue date:	11/21/2006
From:	NRC/NRR/ADRO/DORL/LPLIV
To:
Wang A, NRR/DORL/LP4, 415-1445
Shared Package
ML063040036	List: ML063260025
References
TAC MC9299
Download: ML063260025 (2)

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 (5.1 Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such b1yproduct and special nuclear materials as may be produced by the operation of theifacility.

C. This License shall be deemed to contain and Is subject to the conditions spacfied In the Commission's ragul;-tions set forth In 10 CFR Chapter I and Is subject to all appli6able provAsions of the Act and to the rules, regulations, and orders of the Commission now or hereafter Ineffect; and Is subject to the additional conditions specified or incorporated belowM (1) Maximum Power Level The Pacific Gas and Elecirio Company is authorized to operate the facility at reactor core power leVeIs not Inexc.ass of 341.1 megawatts thermal (100% rated power) In accordance withthe conditions specified herein.

(2) Technical Speclfications The Technical Specifications contained InAppendix A and the Environmental

- .Protection. Plan .contained InAppendix B, .as revised through Amendm ent No.

191 9 , re hereby Incorporated inthe license. Pacific Gas &Electric Company shall bperaWeihe facility In accordanca with the Technictl Spicificattons and the Environmental Protection Plan, except where otherwise stated Inspecific license conditions.

(3) Initial Test Program-The Pacific Gas and Electric Company shall conduct the post-fuel-loading Initial test pribg!'rn (set forth In Section 14 of Pacific Gas and Electric Companhys Final Safety Ahalysis Report, BS arnehd*d), without- naking any major inodifications of this program unless Modifications have been Identified and have received prior NRC approval. Major mrodlfieations are defined as:

a. -liminallon of any test Identified in Section 14 of PG&E's Final Safety.

Analysis Report as amended as being essential; Amendment No.- _1 91

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. WCAP-10216-P-A, Revision 1A, Relaxation of Constant Axial Offset Control FQ Surveillance Technical Specification, February 1994 (Westinghouse Proprietary),

2. WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July 1985 (Westinghouse Proprietary),

3. WCAP-8385, Power Distribution Control and Load Following Procedures, September 1974 (Westinghouse Proprietary),

4. WCAP-10054-P-A, Westinghouse Small Break LOCA ECCS Evaluation Model Using the NOTRUMP Code, August 1985. (Westinghouse Proprietary), and

5. WCAP-10054-P-A, Addendum 2, Revision 1, "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection Into the Broken Loop and COSI Condensation Model," July 1997 (Westinghouse Proprietary), and

6. WCAP-12945-P-A, Westinghouse Code Qualification Document for Best-Estimate Loss of Coolant Analysis, June 1996. (Westinghouse Proprietary), and

7. WCAP-12945-P-A, Addendum 1-A, Revision 0, "Method for Satisfying 10 CFR 50.46 Reanalysis Requirements for Best Estimate LOCA Evaluation Models," December 2004. (Westinghouse Proprietary) (Unit 1 Only).

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

(continued) 5.0-27 Unit 1 - Amendment No. -154,1-3,, 1 91 Unit 2 - Amendment No. 435 136