ML20211C890

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Discusses Use of Bechtel BN-TOP-1, Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Plants, for Plant Preoperational Containment Leakage Testing
ML20211C890
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 01/17/1984
From: Dupont S
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Lynch M
Office of Nuclear Reactor Regulation
Shared Package
ML20211C861 List:
References
FOIA-86-370, FOIA-86-A-147 NUDOCS 8610220048
Download: ML20211C890 (1)


Text

.iI January 17, 1984 MEMORANDUM TO: ~ M. D. Lynch, Project Manager, Division of Licensing, NRR THRU: J. Streeter, Chief, Engineering Branch No.1, RIII 4 4. Ages.,cideb Tat PS% heh m ,ft.in FROM: S. G. DuPont, Reactor Inspector, Test Program section, RIII

SUBJECT:

USE OF BN-TOP-1 FOR THE FERMI-2 PREOPERATIONAL CONTAINMENT LEAKAGE TESTING PER APPENDIX J.

As discussed with you on January 16, 1984, the Region III staff is taking exception with the Fermi-2 facility's adoption of a minimum test duration of eight hours for a Type A containment integrated leak rate test to be performed as a preoperational test in accordance with the Bechtel Topical Report, BN-TOP-1, " Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Plants", Revision 1.

The Region's staff position of requiring a complete collection of test data from a minimum test duration of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for preoperational testing has been established with the Type A tests performed at LaSalle-1 and 2, and Callaway facilities, and is in agreement with the Region II staf f position.

j Our position differs from your office's position, as described in the December 12, 1983, letter to Mr. Harry Tauber from Mr. B. J. Youngblood, l

only in requiring an initial or preoperational test. duration of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to establish a wide collection base to be used by future Type A tests k

using the BN-TOP-1 report.

1 by5 46 We would appreciate any further comments from your staff on this matter. t 8610220048 861009 PDR FOIA PUNTE86-A-147 PDR M g. $ ; 6 5 t),c . Stevie G. DuPont Reactor Inspect

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Test Program Section Region III {,)

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