ML17291A837

Proposed Tech Specs Section 6.9.3.2,adding Ref to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications

ML17291A837
Person / Time
Site:	Columbia
Issue date:	06/06/1995
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17291A833	List: ML17291A832 ML17291A837
References
NUDOCS 9506140338
Download: ML17291A837 (5)

Text

ATTACHMENT1 Proposed Change to Section 6.9.3.2 of the %NP-2 Technical Specification 950b140338 950bOb PDR ADOCK 05000397 P PDR

J (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 topical report previously reviewed and approved by the NRC, which describe the methodology applicable to the current cycle. For MNP-2 the topical reports are:

1. ANF-1125(P)(A), and Supplements 1 and 2, 'ANFB Critical Power Correlation,'pril 1990

2. Letter, R. C. Jones (NRC) to R, A. Copeland (ANF), 'NRC Approval of ANFB Additive Constants for ANF 9x9-9X BMR Fuel,'ated Hovember 14, 1990

3. ANF-HF-524(P)(A), Revision 2 and Supplements I and 2, "Advanced Huclear Fuels Corporation Critical Power Hethodology for Boiling Mater Reactors,'ovember 1990

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

5. AHF-CC-33(P)(A), Supplement 2, 'HUXY: A Generalized Hultirod Heatup Code with 10 CFR 50, Appendix K Heatup Option,'anuary 1991

6. XN-HF-80-19(P)(A), Volume I, Supplements 3 and 4, 'Advanced Nuclear Fuel Nethodology for Boiling Mater Reactors,'ovember 1990

7. XN-NF-80-19(P)(A), Volume 4, Revision I, "Exxon Nuclear Hethodology Boiling Mater Reactors: Application of the EHC Hethodology to BMR Reloads,'une 1986

8. XH-HF-80-19(P)(A), Volume 3, Revision 2, 'Exxon Nuclear Hethodology for Boiling 'Mater Reactors THERHEX: Thermal Limits Kethodology SusIaary Description," January 1987

9. XN-HF-85-67(P)(A), Revision I, "Generic Hechanical Design for Exxon Nuclear Jet Pump BMR Reload Fuel," September 1986

10. ANF-89-014(P)(A), Revision 1 and Supplements 1 and 2, 'Advanced Nuclear Fuels Corporation Generic Hechanical Design for Advanced Nuclear Fuels Corporation 9x9-IX and 9x9-9X BMR Reload Fuel," October 1991

11. XH-NF-81-22(P)(A), "Generic Statistical Uncertainty Analysis Hethodology,'ovember 1983

12. HEDE-24011-P-A-10-US, 'General Electric Standard Application for Reactor Fuel,'.S. Supplement, Harch 1991 13! HEDE-23785-1-PA, Revision 1, 'The GESTR-LOCA and SAFER Hodels for the Evaluation of the Loss-of-Coolant Accident, Volume III, SAFER/GESTR Application Hethodology," October 1984

14. HED0-20566A, 'General Electric Company Analytical Hodel for Loss-of-Coolant Analysis in Accordance with 10 CFR 50 Appendix K," September 1986 15 'HF-CC-074(P)(A), 'Volume 1 STAIF - A Computer Program for BMR Stability in the Frequency Domain, Volume 2 STAIF A Computer Program for BMR Stability in the Frequency Domain, Code qualification Report,"

July 1994.

16. WPPSS-FTS-127(A), Qualification of Core Physics Methods for BWR Design and Analysis", November 1994

17. WPPSS-FTS-129(A), Revision 1, "BWR Transient Analysis Model", November 1994

18. WPPSS-FTS-131(A), Revision 1, "Applications Topical Report for BWR Design and Analysis", November 1994

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ATTACHMENT2 No Significant Hazards Consideration Determination In accordance with the criteria for a significant hazards consideration established in 10 CFR 50.92, the Supply System has evaluated the proposed amendment to the WNP-2 Technical Specifications and determined that it does not represent a significant hazards consideration. The following discussion is provided in support of this conclusion.

Does the amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

The proposed amendment does not remove or modify existing Technical Specification requirements or safety limits. The Technical Specifications will continue to require operation within an'alyzed core operating limits and appropriate actions be taken when, or if, limits are exceeded. There will be no changes to the physical design of the plant as a result of adding the proposed references to Section 6.9.3.2. The results of analytical determination of core operating limitations is not assumed as the initiator of any analyzed event, and the approved safety analysis is still applicable. Therefore, the proposed amendment to Technical Specification 6.9.3.2 does not involve a significant increase in the probability or consequences of an accident previously evaluated.

Does the amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

The proposed amendment does not remove or modify existing Technical Specification requirements or safety limits. The Technical Specifications will continue to require operation within analyzed core operating limits and appropriate actions be taken when, or if, such limits are exceeded. The technical methodology outlined in the three new reports is in accordance with accepted principals, and the specific reports proposed for inclusion in the Technical Specifications by this request have been previously approved by NRC for use at WNP-2 as a basis for core reload analyses. Therefore, the proposed amendment to Technical Specification 6.9.3.2 does not create the possibility of a new or different type of accident from any accident previously evaluated.

3. Does the amendment involve a significant reduction in a margin of safety?

Plant safety limits are established through LCOs, limiting safety system settings, and safety limits specified in the Technical Specifications. There willbe no changes to either the physical design of the plant or to any of these settings and limits as a result of adding the proposed references to Section 6.9.3.2. The ability to mitigate the consequences of all accidents previously evaluated will be maintained and nuclear safety is not adversely affected because the technical methodology outlined in the three new reports is in accordance with accepted principals, and the specific reports proposed for inclusion in the Technical Specifications by this request have been previously approved by NRC for use at WNP-2 as a basis for core reload analyses. Therefore, the proposed amendment to Technical Specification 6.9.3.2 does not significantly reduce any margin of safety.

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