ML042050060
| ML042050060 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/21/2004 |
| From: | NRC/NRR/DLPM |
| To: | |
| Cotton K, NRR/DLPM, 301-415-1438 | |
| References | |
| TAC MC0239 | |
| Download: ML042050060 (2) | |
Text
REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4.1.1.3 The MTC shall be determined to be within its limits during each fuel cycle as follows:
- a.
The MTC shall be measured and compared to the BOL limit specified in the COLR prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading.
- b.
The MTC shall be measured at any THERMAL POWER and compared to the 300 ppm surveillance limit specified in the COLR (all rods withdrawn, RATED THERMAL POWER condition) within 7 EFPD after reaching an equilibrium boron concentration of 300 ppm*. In the event this comparison indicates the MTC is more negative than the 300 ppm surveillance limit specified in the COLR, the MTC shall be remeasured, and compared to the EOL MTC limit specified the COLR, at least once per 14 EFPD during the remainder of the fuel cycle.
Measurement of the MTC in accordance with SR 4.1.1.3.b may be suspended, provided that the benchmark criteria in WCAP-1 3749-P-A and the Revised Prediction specified in the COLR are satisfied.
I SUMMER - UNIT 1 3/4 1-5 Amendment No.75, 88, 169
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)
(Methodology for Specifications 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Rod Insertion Limits, 3.1.3.6 - Control Rod Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 -
RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor.)
- b.
WCAP-1 0216-P-A, Rev. 1A, "RELAXATION OF CONSTANT AXIAL OFFSET CONTROL Fa SURVEILLANCE TECHNICAL SPECIFICATION," February 1994 (W Proprietary).
(Methodology for Specifications 3.2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (Fa Methodology for W(z) surveillance requirements).)
- c.
WCAP-10266-P-A, Rev. 2, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE," March 1987; Including Addendum 2-A, "BASH METHODOLOGY IMPROVEMENTS AND RELIABILITY ENHANCEMENTS," May 1988, (W Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
- d.
WCAP-12472-P-A, 'BEACON CORE MONITORING AND OPERATIONS SUPPORT SYSTEM," August 1994, (W Proprietary).
(Methodology for Specifications 3.2.2 - Heat Flux Hot Channel Factor, 3.2.3 -
RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor, and 3.2.4 -
Quadrant Power Tilt Ratio.)
- e.
WCAP-13749-P-A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement,'
March 1997, (Westinghouse Proprietary).
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient.)
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements there to shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
SUMMER - UNIT 1 6-16a Amendment No. 88,121, 133,112,169