ML20117D506
| ML20117D506 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 05/07/1985 |
| From: | Jens W DETROIT EDISON CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20117D509 | List: |
| References | |
| NE-85-0707, NE-85-707, NUDOCS 8505100124 | |
| Download: ML20117D506 (2) | |
Text
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Detroit l[h r
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l Director of Nuclear Reactor Regulation l
Attention:
Mr. B. J. Youngblood, Chief yh i
Licensing Branch No. 1 7
Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Dear Mr. Youngblood References (1)
Fermi 2 l
NRC License No. NPF-33 (2)
Detroit Edison to NRC Letter, "Formi 2 Vacuum Breakers", EF2-61967, dated March 16, 1983 (3)
Detroit Edison to NRC Letter, " Submittal of t
Reports for the Fermi 2 Vacuum Breakers",
EF2-06296, dated November 9, 1982 (4)
Detroit Edison to NRC Letter, " Evaluation of the Enrico Fermi 2 Drywell-to-Wetwell Vacuum Breakers", EF2-59061, dated August 18, 1982
Subject:
Renubmittal of Permi 2 Vacuum Breaker Report References (2), (3), and (4) supplied information for the Fermi 2 wetwell-to-drywell vacuum breakers and their ability to withstand chugging and condensation osci21ation loads.
Reference (4) also documented modifications to be made to the vacuum breakers to assure that they can withstand postulated impact loads fram these events.
Supplement 5 to the Fermi 2 Safety Evaluation Report stated the generic models proposed by GE had been reviewed by the staff and were acceptable for use for analyses and/or qualification of the vacuum breakers provided the more conservative drywell model was used, plant unique results were submitted, and any plant unique deviations from the methodology were identified.
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Mr. B. J. Youngblood May 7, 1985 NE-85-9707 Page 2 Accordingly, please find attached a copy of the report, " Mark I-Wetwell to Drywell Differential Pressure Load and Vacuum Breaker Response for the Fermi Atomic Power Plant Unit 2" by Continuum Dynamics, Inc..
The report provides plant unique-results based on applicable data from Fermi 2.
In some cases, generic data was used where the range of plant unique data was shown by CDI not'to impact the results.
The most conservative drywell model was used and there are no plant unique deviations from the methodology accepted by the NRC.
Modifications to the vacuum breakers noted in Reference (4),have been completed and the. modified vacuum breakers meet the impact loads in the attached report.
This should provide the requested resolution of this item for full power licensing as stated in Section 3.8.1.1 of Supplement 5 to the Fermi 2 Safety Evaluation Report.
Should you have any questions, please contact Mr. O. K. Earle at (313) 586-4211. ' ~
Sincerely,
(
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,/
f' cca Mr. P. M. Byron j(p, 4MO Mr. M. David Lynch Mr. J. C. Lane USNRC' Document Control Desk Washington, D.C. 20555 4
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