ML20081B462

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Proposed Tech Specs,Revising Ref in TS 6.9.1.6.b for Analytical Method Used to Determine Core Operating Limits for Heat Flux Hot Channel Factor for TS 3.2.2
ML20081B462
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 03/09/1995
From:
HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20081B453 List:
References
NUDOCS 9503160193
Download: ML20081B462 (2)


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PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS l

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, ST-HL-AE-5036 Attachment 3 Page1 of1 CORE OPERATING LIMITS REPORT (Continued)

(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient).

0 2. WCAP 8385, " POWER DISTRIBUTION AND LOAD FOLLOWINO PROCEDURES TOPICAL REPORT", September,1974 (W Proprietary).

(Methodology for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset l Control).)  !

3. Westinghouse letter NS-TMA-2198, T.M. Anderson (Westinghouse) to K. Kniel (Chief 1 of Core Perfonnance Branch, NRC) January 31,1980 -'

Attachment:

Operation and i Safety Analysis Aspects of an Improved Load Follow Package. j (Methodology for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset

. A Control)Nos.pproved Docket 50-369 andby50-370.

NRC Su plement No. 4 to NUREG-0422 January.~ 1981

4. NUREG-0800, Standard Review Plan, U. S. Nuclear Regulatory Commission, Section  !

4.3, Nuclear Design, July,1981. Branch Technical Position CPB. 4.3-1, Westinghouse Constant Axial Offset Control (CAOC), Rev. 2, July 1981.

(Methodology for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset Control).)

5. WCAP 9220 P A, R:".1, " WEST!NCHOUSE ECCS EVALUAT!ON MODEL 1981 VERSION", Febru= !"S2 'W Premicia '. WCAP-10266;PJA' WCAP-1.lS24-NP-Al"Refr2Me'1981N"efsion of the WestirioW,t ECCSReO2)

Evaluation;Model Using the BASH Code"t KabadifJXNt; et."al" March:1987 'insl6 din Addendum 11-AM" Power Shape Sensitivity. Studies." December 1987;and Addendum ~g 2-A,;" BASH Methodology]mprovements and Reliability; Enhancements" Mayil988j (Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)

6. CAP 9561-P A, ADD. 3, REV.1, "" ART A 1: A COMPUTER CODE FOR THE D E C T C C T1h A A T I' A KI A T VC f C AI' D CCf AAn TD A k?CY CKYTC CDCPIAT DCDADT.

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Preprietary).

(Mc:hode!cgy for Specifica:ica 3.2.2 Heat Flux Het C=nne! Factor.)

6.9.1.6.c 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.

6.9.1.6.d 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.

SOUTH TEXAS - UNITS I & 2 6-22 Unit 1 - Amendment No. 47l Unit 2 - Amendment No. 36 T$CASWMih0 002

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