ML20078N438

Proposed Tech Specs,Re cycle-specific Variables

ML20078N438
Person / Time
Site:	Waterford
Issue date:	12/02/1994
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20078N436	List: ML20078N434 ML20078N438
References
NUDOCS 9412060283
Download: ML20078N438 (2)

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ADMINISTRATIVE CONTROLS INDUSTRIAL SURVEY OF T0XIC OR HAZARD 0US CHEMICALS REPORT 6.9.1.9 Surveys and analyses of major industries in the vicinity of Waterford 3 which could have significant inventories of toxic chemicals onsite to determine impact on safety shall be performed and submitted to the Commission at least once every 4 years. l l

6.9._.10 A survey of major pipelines (6 4 inches) within a 2-mile radius of Waterford 3. l which contain explosive or flammable materials and may represent a hazard to Waterford 3.

including scaled engineering drawings or maps which indicate the pipeline locations, shall be performed and submitted to the Commission at least once every 4 years.

CORE OPERATING LlHITS REPORT (COLR) i 6.91.11 Core operating limits shall be established and documented in the COREOPERATING LIMITS  !

REPORT prior to each reload cycle or any remaining part of a reload cycle. '

6.9.1.11.1 The analytical methods used to determine the core operating limic , shall be those previously reviewed and approved by the NRC as follows:

1)"The ROCS and DIT Computer Codes for Nuclear Design," CENPD-266-P-A. April 1983: and "C-E Methodology for Core Designs Containing Gadolinia-Urania Burnable Absorber," CENPD-275-P-A May 1988. (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins. 3.1.1.3 for MTC. 3.1.3.6 for Regulating CEA Insertion Limits. 3.1.2.9 Baron Dilution (Calculation of CBC & IBW) and 3.9.1 Boron Concentration).

2) "C-E Method for Control Element Assembly Ejection Analysis." CENPD-0190 A, January 1976. (Methodology for Specification 3.1.3.6 for Regulating CEA Insertion Limits and 3.2.3 for Azimuthal Power Tilt).

3) " Modified Statistical Combination of Uncertainties" CEN-356(V)-P-A. May 1988, (Methodology for Specification 3.2.4 for DNBR Margin and 3.2.7 for ASI). ,

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4) " Calculative Methods for the C-E Large Break LOCA Calculation Model For The Analysis of C-E and W Designed HSSS." CEMPD-132, Supplement 3-P- A. June 1985. (Methodology for ,

Specification 3.1.1.3 for MTC. 3.2.1 for Linear Heat Rate. 3.2.3 for Azimuthal Power l

Tilt and 3.2.7 for ASI). i

5) " Calculative Methods for the C-E Small Break LOCA Evaluation Model .' CENPD-137-P.

August 1974: Supplement 1. January 19/7. (Methodology for Specification 3.1.1.3 for MTC. 3.2.1 for Linear Heat Rate. 3.2.3 for Azimuthal Power Tilt and 3.2.7 for ASI). I 1

6)"CESEC - Digital Simulation of a Combustion Engineering Nuclear Steam Supply S

1 stem",CENPD-107. December 1981. (Methodology for Specification 3.1.1.1 and 3.1.1.2 for Shutdown Margins. 3.1.1.3 for MTC. 3.1.3.1 for Movable Control Assemblies - CEA Posi tion. 3.1.3.6 for Regulating CEA Insertion Limits, 3.1 3.7 for Part Length CEA Insertion Limits and 3 2.3 for Azimuthal Power Tilt.

WATERFORD - UNIT 3 6 20 AMENDMENT NO,68 9412060283 941202 PDR P ADOCK 05000382 PDR

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. 4 ADMINISTRATIVE CCffROLS 6.9.1.'11.3 The core operating limits shall be determined such that all applicable limits

{e_.3. , fuel thermal limits, core thermal-hydraulic limits. ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are

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6.9.1.11.4 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.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Of fice of the NRC within the time period specified for each report.

6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

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l l WATERFORD - UNIT 3 6-20a AMENDHENT NO.

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