ML063550031

Tech Spec Pages for Amendment 192 Regarding TS 5.6.5, Core Operating Limits Report.

ML063550031
Person / Time
Site:	Diablo Canyon
Issue date:	12/20/2006
From:	NRC/NRR/ADRO/DORL/LPLIV
To:
Wang A, NRR/DORL/LPL4, 301-415-1445
Shared Package
ML063380018	List: ML063380020 ML063550031
References
TAC MC9567
Download: ML063550031 (2)

Text

(4) Pursuant to the Aft and 10 CFR Parti 30, 402 and 70, to recei';e, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, fon 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 5 but not separate, such byproduct and special. nuclear materials as may be produced by the operation of the facillty.

C. This Licehse shall be deemed to c6ntain, and is subject to the conditions specified in the Commission's regulations.set forth in 10 CFR Chapter I.

• and is subject to all applicabte provisions of the Act and to the rules- regulations', and orders of the Connission now or hereafter in effect; and is subject to the additional conditions specified or incor-porated below: .

(1) Maximum Power Level The Pacific Gas and Electric Company Is authorized to operate the facility at reactor core power levels not in excess of 3411 mgwts..t h.erpal .(1*rted. power)..in.accordance-with.

t-codfflt).ons specified herein.

(2) Technical Specifications (SSEA 32, Section 8)* and. Environmental Protection.Plan The Technical 5pec fications-%ontatn"d In Appendix A and the Env.ir1 ntel.PPotect*l*.Plan contained in Appendix B, as revised throughM S Aendment .'* ere hereby incorporated in the license.

jb Pacific Gas 9 Elictric .cph y ;shal I operate the facility in' f

accordance with the Technical spetifications and the Environmental ProteCtion Plan, e~cept vihere other-wse stated in specific license

• conditfIon. .

(3) "nitIýal1_-Test Program -(ssFP. 32. section 4. .4.2 "Any changes t "-he "nitlal Test Program described ip Sect-ion 14 of the FSAR tiade in accbrdance with the prois ions ofJ1 C.FR 90.0 sh511 b6 reported, In accordance with 50.59(b) within one

. . m of change.

• The paenthet1taI notatio, following dente.the se n of the Safety Evaluatiotitle *he of manyd 3i~ense t

Report and/or its uconditions supplemen ts.

• wherein the license condition Is discussed..

Amen.dment No. 192

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-1 2945-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 I Only), and

8. WCAP-16009-P-A, Revision 0, Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM), January 2005. (Westinghouse Proprietary)

(Unit 2 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)

DIABLO CANYON - UNITS 1 & 2 5.0-27 Unit 1 - Amendment No. 435 436,191 Unit 2*- Amendment No. 435 436,192