ML18046A409
| ML18046A409 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 02/16/1981 |
| From: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.30, TASK-TM NUDOCS 8102190600 | |
| Download: ML18046A409 (2) | |
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consumers Power company
- General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 * (517) 788*0650 February 16, 1981
- Director, Nuclear Reactor Regulation Att Mr Dennis M Crutchfield, Chief Operating Reactors Branch No 5 U S Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
CORRECTION TO LETTER OF DECEMBER 19, 1980 -
CLARIFICATION OF TMI ACTION PLAN REQUIREMENTS Enclosed is a copy of page 225 of the Palisades Plant NUREG-0737 Item II.K.3.30 response dated December 19, 1980 which was inadvertently left out of a few copies of our submittal.
This page is being given full distribution to be sure that all concerned will have received it.
David P Hoffman Nuclear Licensing Administrator CC JGKeppler, USNRC NRC Resident Inspector-Palisades Plant
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II.K. 3. 30 REVISED SMALL BREAK LOSS OF COOLANT ACCIDENT METHODS TO SHOW COMPLIANCE WITH 10 CFR PART 50, APPENDIX K NRC POSITION The analysis methods used by Nuclear Steam Supply System (NSSS) vendors and/or fuel suppliers for small break Loss of Coolant Accident (LOCA) analysis for compliance with Appendix K to 10 CFR Part 50 should be revised, documented and submitted for NRC approval.
The revisions should account for comparisons with experimental data, including data from the LOFT Test and Semiscale Test*
facilities.
LICENSEE ACTION Consumers Power Company is participating in the C-E Owners Group to sponsor preparation of prediction of. LOFT Test L3-6.
Documentation of the C-E Owners Group's plans for the test prediction and response to related NRC requirements is provided in Reference 9 (C).
DEVIATIONS FROM AND BASIS FOR Recommendations Because of the iinportance of these tests in evaluation of the adequacy of present small break LOCA models, Consumers Power Company feels that it is inappropriate to consider further model documentation or changes until ccmpletic;m of the NRC review of these test predictions. Therefore, Consumers Power Company will continue to participate as a member of the C-E Owners Group to support preparation of the predictions cf the LOFT Test: L3-6 (I).
Schedule Outline of program will not be provided until completion of NRC review of the test predictions for the reasons stated above (D).
REFERENCES
- 1.
NUREG-0565, Recommendation 2.2.2.a
- 2.
NUREG.-0611, Recommendation 3. 2.1. a
- 3.
- 4.
NUREG-0626, Recommendation A.12
- 5.
NUREG-0635, Recommendations 3.2.1.a and 3.2.5.a
- 6.
Letter From D G Eisenhut, NRC, to All Operating Reactor Licensees, Dated May 7, 1980
- 7.
Letter From D G Eisenhut, NRC, to All Licensees of Operating Plants and Applicants for Operating Licenses and Holders of Construction Permits, Dated September 5, 1980 nul280-0031a-43 225