ML022590359
| ML022590359 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/13/2002 |
| From: | NRC/NRR/DLPM |
| To: | |
| References | |
| TAC MB3905 | |
| Download: ML022590359 (2) | |
Text
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 COLR (continued)
- 6.
EMF-2310 (P)(A), Revision 0, Framatome ANP, inc., May 2001, "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors."
(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)
- 7.
XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company. (LCOs 3.1.6, 3.2.1, & 3.2.2)
- 8.
ANF-89-151(P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)
- 9.
EMF-92-153(P)(A) and Supplement 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation. (LCOs 3.2.1, 3.2.2, & 3.2.4)
- 10.
XN-NF-621(P)(A), "Exxon Nuclear DNB Correlation for PWR Fuel Designs," Exxon Nuclear Company. (LCOs 3.2.1, 3.2.2, & 3.2.4)
- 11.
XN-NF-82-06(P)(A) and Supplements 2, 4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Exxon Nuclear Company. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)
- 12.
ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWDIMTU,"
Advanced Nuclear Fuels Corporation. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)
- 13.
XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)
Palisades Nuclear Plant 5.0-26 Amendment No. 49, Lu'
5.0-26 Amendment No. -t-9, 209 Palisades Nuclear Plant
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 COLR (continued)
- 14.
EMF-92-116(P)(A), "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation. (LCOs 3.1.6, 3.2.1, 3.2.2,
& 3.2.4)
- 15.
EMF-2087(P)(A), "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation. (LCOs 3.1.6, 3.2.1,
& 3.2.2)
- 16.
ANF-87-150 Volume 2, "Palisades Modified Reactor Protection System Report: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation. [Approved for use in the Palisades design during the NRC review of license Amendment 118, November 15, 1988] (LCOs 3.1.6, 3.2.1, & 3.2.2)
- 17.
EMF-1961(P)(A), Revision 0, Siemens Power Corporation, July 2000, "Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors." (LCOs 3.1.6, 3.2.1, 3.2.2, 3.2.4)
- 18.
EMF-2328 (P)(A), Revision 0, Framatome ANP, Inc., March 2001, "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based." (LCOs 3.1.6, 3.2.1, & 3.2.2)
- c.
The core operating limits shall be determined such that all applicable limits (e.g.,
fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems limits, nuclear limits such as shutdown margin, transient analysis limits, and accident analysis limits) of the safety analysis are met.
- d.
The COLR, including any mid cycle revisions or supplements, shall be provided, upon issuance for each reload cycle, to the NRC.
Amendment NO. i-,
zui Palisades Nuclear Plant 5.0-27 Palisades Nuclear Plant Amendment NO. i-bt, zi-ý,,<uý
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5.0-27