L-84-343, Advises That Intake Structure Pump Encl Fan Housing & Condensate Storage Tank Vent Hood Housing Modified,Per Sser 2 (NUREG-0843).Reactor Auxiliary Bldg Sliding Door Satisfies NRC Allowable Ductility Factor
| ML17215A684 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 11/29/1984 |
| From: | Williams J FLORIDA POWER & LIGHT CO. |
| To: | John Miller Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0843, RTR-NUREG-843 L-84-343, NUDOCS 8412070181 | |
| Download: ML17215A684 (3) | |
Text
REGULATO INFORMATION DISTRIBUTION TEM (RIDS)
ACCESSION NBR: 8412070 i81 DOC ~ DATE: 84/11/29 NOTARIZED: NO, FACIL!50 389 St., Lucie Plant~
Unit 2i Flor ida Power 8 Light Co.
AUTH",NAME AUTHOR AFFILIATION WILLIAMS'
~ W.
F l or i de Power 8 Light Co.
RECIP ~ NAME RECIPIENT AFFILIATION MILLER'
~ R ~
Operating Reactors Branch 3
SUBJECT!'dvises that intake structur e pump enc]
fan housing condensate storage tank vent". hood housing modi fied'er-SSER 2
~ Re'actor auxiliary bldg sliding door satisfies NRC allowable ductility factor DI'STRIBUTION CODE!
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~alii~,~~4 FLORIDAPOWER 5 LIGHT COMPANY Office of Nuclear Reactor Regulation Attention:
Mr. James R. Miller, Chief Operating Reactors Branch, IE3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 November 29, 1984 L-84-343
Dear Mr. Miller:
Re:
St. Lucie Unit No. 2 Docket No. 50-389 Tornado Missile Protection The St. Lucie Unit 2 Safety Evaluation Report (NUREG-0843) Supplement No. 2, Section 3.5.3 identified three structures requiring strengthening because the design ductility ratio was greater than that allowed by the NRC staff.
Two of these structures, the Intake Structure Pump enclosure fan housing and the Condensate Storage Tank vent hood housing, were modified as required.
The third structure, the Reactor Auxiliary Building sliding door, was not modified because the certified material test report for the structural member in question specified an actual yield stress of 59 ksi, rather than the 50 ksi assumed in the original design.
Therefore, the unmodified structure satisfies the NRC staff's allowable ductility factor, and no modification was necessary.
Very truly yours,
~
J. W. Wi s, Jr.
Group VI e President Nuclear Energy JWW/RJS/kgn I
84 12070 18 1 0500038 1 841129 PDR ADOCK E
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