ML20211D866
| ML20211D866 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 09/16/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211D867 | List: |
| References | |
| NUDOCS 9709290267 | |
| Download: ML20211D866 (2) | |
Text
.__________ _ _ _ _ _ _ _ - _
'o.
ADMINISTRATIVE CONTR0Lt
@ LY OPERATING REPORTI 6.9.1.5. Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves shall be submitted on a monthly basis to the Director, Office of Resource Mana,ge-ment, U.S. Nuclear Regulatory Commission Washington, D.C.
20555, with a copy to the Regional Admin'strator of the Replonal Office of the NRC ne later than the 15th of each month following the ca endar month covered by lhe report.
CORE OPERATING LIMITI REPORT 5.9.1.6.a Core o erating limits shall be established and documented in the CORE 0?ERATING LINITS REPORT before each reload cycle, or any part of a reload cycle for the following:
1.
Moderator Temperature Coefficient 80L and E0L limits, and 300 ppa surveillance limit for Specification 3/4.1.1.3, 2.
Shutdown Bank Insertion Limit for Specification 3/4.1.3.5, 3.
Control Bank Insertion Limits for Specification 3/4.1.3.6, 4.
Antal Flux Of fference-limits and target band for Specification 3/4.2.1, 5.
Heat Fg)Not Channel Factor, K(Z), Power Factor Multiplier, and (F,,
for Specification 3/4.2.2, and 6.
Nuclear Enthalpy Rise Not Channel Factor, and Power Factor Multipiter for specification 3/4.2.3.
The CORE OPERATING LIMITS REPORT shall be maintained available in the Control Room.
6.9.1.6.b The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:
1.
WCAP 9272-P-A, ' WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY *, July,1985 (W Proprietary).
(Methodology for specification 3.1.1.3 - Moderator Temperature Coefftetent, 3.3.3.5 - Shutdown Rod Insertion Limit 3.1.3.6 -
Control Bank Insertion Limits 3.2.1-AxialFluxDIfference, 3.2.2 - Heat Flux Hot Channel, Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)
1.A.
WCAP 12942-P-A, '5AFETY EVALUATION SUPPORTING A MORE NEGATIVE E0L MODERATOR TEMPERATURE COEFFICIENT TECHNICAL SPECIFICATION FOR THE SOUTH TEXA5 PROJECT ELECTRIC GENERATING STATION UNITS 1 AND 2.'
SOUTH TEXA5 - UNITS 1 & 2 6-21 Unit 1 - Amendment No. 9, N, 45, 47 Unit 2 - Amendment No. 4, W, 44, 36 N b ooN NONI9e P
PDR m
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORI IWDilDkte (Methodology for Specificatlon 3.1.1.3 - Moderator Temperature Coefficient) 2.
WCAP 8385 " POWER DISTRIBU110N AND LOAD FOLLOWING PROCEDURES TOPICAL REPORT", September, 1974 (W Proprietary).
(Methodology for Specification 3.2.1 - Axial Flux Difference (ConstantAxialOffsetControl).)
3.
Westinghouse letter NS-TMA-2198, 1.M. Anderson (Westinghouse) to K. Kniel (Chief of Core Performance Branch, NRC)
January 31, 1980 -
Attachment:
Operation and Safety Analysis Aspects os an improved Load Follow Package.
(Methodology for Specification 3.2.1 - Axial Flux Difference (Censtant Axial Offset D.,ntrol). Approved by NRC Supplement No. 4 to NUREG-0422, January, 1981 Docket Nos. 50-369 and 50-370.)
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).)
Sa. WCAP-10266-P-A, Rev. 2, WCAP-ll524-NP-A, Rev. 2. "The 1981 l
Version of the Westinghouse ECCS Evaluation Model Using the BASH Code", Kabadi, J.N., et al., March 1987; including Addendum 1-A, ' Power Shape Sensitivity Studies," December 1987 and Addendum 2-A, "8 ASH Methodology improvements and Reliability Enhancements" May 1988.
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
Sb.
WCAP-12610-P-A, " VANTAGE + Fuel Assembly Reference Core Report,"
April, 1995 (W Proprietary) for loss of Coolant Accident (LOCA)
Evaluation models with ZlRLO clad fuel for rod heatup calculation.
(Methodology for Specification 3,2.2 - Heat Flux Hot Channel 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.
SOUTH TEXAS - UNITS 1 & 2 6-22 Unit 1 - Amendment No. 27,35,47,M,89 Unit 2 - Amendment No. 47,25,35,61,76