Letter Sequence Other |
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TAC:MB9502, Revise Topical Report References in ITS 5.6.5, Colr (Open) TAC:MB9503, Revise Topical Report References in ITS 5.6.5, Colr (Open) |
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MONTHYEARML0321003742003-07-25025 July 2003
Facsimile Transmissions Supporting Upcoming Conference Call
Project stage: Other
ML0324505002003-08-27027 August 2003
Technical Specifications, Administrative Changes to Section 6 to Adopt Format for Topical Report References
Project stage: Other
ML0324003162003-08-27027 August 2003
Amendments 235 & 234 to Licenses DPR-32 and DPR-37 Respectively. Amendments Make Administrative Changes to Section 6 of Technical Specifications to Adopt Format for Topical Report References
Project stage: Other
ML0330104502003-10-20020 October 2003
Cycle 19, Revision 1 to Core Operating Limits Report
Project stage: Other
2003-07-25
[Table View] |
Technical Specifications, Administrative Changes to Section 6 to Adopt Format for Topical Report References| ML032450500 |
| Person / Time |
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| Site: |
Surry  |
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| Issue date: |
08/27/2003 |
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| From: |
NRC/NRR/DLPM |
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| To: |
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| References |
|---|
| TAC MB9502, TAC MB9503 |
| Download: ML032450500 (1) |
|
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[Table view] |
Text
TS 6.2-2 The analytical methods used to determine the core operating limits identified above shall be those previously reviewed and approved by the NRC, and identified below.
The COLR will contain the complete identification for each of the TS referenced topical reports used to prepare the COLR (i.e., report number, title, revision, date, and any supplements). The core operating limits shall be determined so that 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. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided for information for each reload cycle to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
REFERENCES
- 1. VEP-FRD-42-A, "Reload Nuclear Design Methodology" 2a. WCAP-9220-P-A, "Westinghouse ECCS Evaluation Model - 1981 Version," (W Proprietary) 2b. WCAP-9561-P-A, "BART A-1: A Computer Code for the Best Estimate Analysis of Reflood Transients-Special Report: Thimble Modeling in W ECCS Evaluation Model," (W Proprietary) 2c. WCAP-10266-P-A, "The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code," (W Proprietary) 2d. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," (W Proprietary) 2e. WCAP-10079-P-A, NOTRUMP, A Nodal Transient Small Break and General Network Code," (W Proprietary) 2f. WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Report," (Westinghouse Proprietary) 3a. VEP-NE-2-A, "Statistical DNBR Evaluation Methodology" 3b. VEP-NE-3-A, "Qualification of the WRB-1 CHF Correlation in the Virginia Power COBRA Code" AmendmentNos. 235 and 234