ML17290A894

Proposed TS Paragraph 6.9.3.2,consisting of Listing of Analytical References Used to Determine Core Operating Limits for Each Cycle Reload

ML17290A894
Person / Time
Site:	Columbia
Issue date:	01/06/1994
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
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ML17290A893	List: ML17290A892 ML17290A894
References
NUDOCS 9401240258
Download: ML17290A894 (4)

Text

CONTROLLED COPY AQHINISlRATIYE CONTROLS CORE OPERATING LIMITS REPORT (Continued) 6.9.3.2 The analytical methods used to determine the core operating limits shall be those topical reports and those revisions and/or supplements of the topjcal report previously reviewed and approved by the NRC, which describe the methodology applicable to the current cycle. For WNP-2 the topical reports are:

I. ANF-1125(P)(A), and Supplements 1 and 2, "ANFB Critical Power Correlation," April 1990

2. Letter, R. C. Jones (NRC) to R. A. Copeland (AMF), "NRC Approval of ANFB Additive Constants for ANF 9x9-9X BWR Fuel," dated November 14, 1990

3. ANF-NF-524(P)(A), Revision 2 and Supplements 1 and 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Bailing Water Reactors," November 1990

4. ANF-913(P)(A), Volume 1, Revision 1 and Volume 1, Supplements 2, 3 and 4, "COTRANSA 2: A Computer Program for Boiling Water Reactor Transient Analysis," August 1990

5. ANF-CC-33(P)(A), Supplement 2, "HUXY: A Generalized Multirod Heatup Code with 10 CFR 50, Appendix K Heatup Option," January 1991

6. XN-NF-80-19(P)(A), VoIuttLe 1, Supplements 3 and 4, "Advanced Nuclear Fuel Methodology for Boiling Water Reactors,"

November 1990

7. XN-NF-80-19(P)(A), Volume 4, Revision 1, "Exxon Nuclear Method-ology Boiling Water Reactors: Application of the ENC Methodology t to BWR Reloads," June 1986

8. XN-NF-80-19(P)(A), Volume 3, Revision 2, "Exxon Nuclear Method-ology for Boiling Water Reactors THERMEX: Thermal Limits Method-ology Summary Oescription," January 1987

9. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Oesign for Exxon Nuclear Jet Pump BWR Reload Fuel," September 1986

10. ANF-89-014(P)(A), Revision 1 and Supplements 1 and 2, "Advanced Nuclear Fuels Corporation Generic Mechanical Oesign for Advanced Nuclear Fuels'Corporation 9x9-D and 9x9"9X HWR Reload Fuel,"

October 1991'1.

XN-NF-81-22(P)(A), "Generic Statistical Uncertainty Analysis Methodology," November 1983

12. NEDE"24011-P-A-6, "General Electric Standard Application for Reactor Fuel," April 1983 WASHINGTON NUCLEAR - UNIT 2 6-21 Amendment Mo. 94, t09 940i240258 940106 PDR ADOCK 05000397 P PDR

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13. NEDE-23785-1-PA, Revision 1 "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident, Volume III, SAFER/GESTR Application Methodology," October 1984

14. NEDO-20566A, "General Electric Company Analytical Model for Loss-of-Coolant Analysis in Accordance with 10CFR50 Appendix K," September 1986