ML20046B580

Proposed Revised TS Page 6.7-5 Incorporating Ref to Revised Methodologies Described in WCAP-13677 & NSPNAD-93003

ML20046B580
Person / Time
Site:	Prairie Island
Issue date:	07/29/1993
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20046B562	List: ML20046B561 ML20046B566 ML20046B580
References
NUDOCS 9308050183
Download: ML20046B580 (2)

Text

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Exhibit C Prairie Island Nuclear Generating Plant License Amendment Request Dated July 29, 1993 Revised Technical Specification Page Exhibit C consists of a revised page for the Prairie Island Nuclear Generating Plant Technical Specifications with the proposed changes incorporated. The revised page is listed below:

Pa r.e -

TS-6.7-5 n

9308050183 930729 t;"l PDR ADOCK 05000282 ha p PDR LM

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TS.6.7-5 I 1

XN-NF-77-57 (A), XN-NF-77-57, Supplement-1 (A), " Exxon Nuclear ,

Power Distribution Control for Pressurized Water Reactors Phase l II", May, 1981 l WCAP-13677-A, "10 CFR 50.46 Evaluation Model Report: W-COBRA / TRAC 2-Loop Upper Plenum Injection Model Update to Support ZIRLOn4 j Cladding Options", April 1993  ;

1 NSPNAD-93003-A, " Transient Power Distribution Methodology", l (latest approved version) I

c. The core operating limits shall be determined such that all j applicable limits (e.g., fuel thermal-mechanical limits, core  !

thermal-hydraulic limits, ECCS limits, nuclear limits such as I shutdown margin, and transient and accident' analysis limits) of j the safety analysis are met. i

d. The CORE OPERATING LIMITS REPORT, including any mid-cycle  !

revisions or supplements thereto, shall be supplied upon issuance,  ;

for each reload cycle, to the NRC Document Control Desk with ,

copies to the Regional Administrator and Resident Inspector. t T

B. REPORTABLE EVENTS The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified by a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and ,

b. Each REPORTABLE EVENT shall be reviewed by the Operations .

Committee and the results of this review shall be submitted to the Safety Audit Committee and the Vice President Nuclear Generation.  ;

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