ML20044D014

Proposed TS 6.12.3.2 Ref BAW-10179P-A, Safety Criteria & Methodology for Acceptable Cycle Reload Analyses

ML20044D014
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/07/1993
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20044D013	List: 1CAN059301, Application for Amend to License DPR-51,revising TS to Replace Current Refs to B&W Topical Repts W/Ref to BAW-10179P-A, Safety Criteria & Methodology for Acceptable Cycle Reload Analyses ML20044D014
References
NUDOCS 9305170023
Download: ML20044D014 (2)

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PROPOSED TECliNICAL SPECIFICATION CIIANGES s

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9305170023 930507 PDR P-ADOCK 05000313 PDR l

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6.12.3 CORE OPERATING LIMITS REPORT 6.12.3.1 The core operating 1imits shall be established and documented in

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the CORE OPERATING. LIMITS REPORT prior to each reload = cycle or prior to any remaining part of a-reload cycle.

6.12.3.2 The analytical methods used to determine the core _ operating limits addressed by the individual Technical Specification shall be those previously reviewed and approved by-the NRC'in Babcock

& Wilcox Topical Report BAW-10179P-A, " Safety Criteria and-Methodology for Acceptable Cycle Reload Analyses" (the approved' revision at the time the reload analyscs are performed). The approved revision number shall be identified in the CORE OPERATING LIMITS REPORT.

6.12.3.3 The core operating limits shall be determined so that all-applicable limits (e.g. fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

6.12.3.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance for each reload cycle to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

Amendment No. /A, 17, ES, JJE, J57 142 (next page is 146)