ML20128C417
| ML20128C417 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 04/08/1969 |
| From: | Dromerick A US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 9212040399 | |
| Download: ML20128C417 (3) | |
Text
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W8 1969 9
R. S. 2nd, Assistant Director for Raeeter Projoets, ML /-
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S. Imrias, Assistemt Dimeter far Snector
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The enclosed list of gaestions rejresents the infomation we unast have to couplete our safety review of the subject plant. A draft copy of these gaestions vose given to D. B. Vassallo on April 1,1969
/y A. W. Dromerick, Chief Containment & Component Technology RT-309A Branch DRL:SSTB:JFK Division of Reactor Licensing
Enclosure:
List of 41estions ccw/ encl:
D. R. Maller D. B. Yassallo DISTRIBUTI9N:
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DRL Reading SSTB Reading a
AD/RT Reading 4
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e MONTICELLO US ? I Docket no. 50-263 1.
In paragraph 6 3, pase 3-6.4, you state that tne reactor vessel internals are designed to maintain a reflooding capability following a loss-of-coolant accident and that the internals are also designed to preclude a failure mode which would result in any part being dischased through the main steam line in the event of a steam line breek.
Please describe the extent and the findings of the analyses by which these conclusions are reached.
Include the following specific information in your deceription for the directly added simultaneous peak loads resulting frc= normal operation plus the verst loss of coolant accident plus the design basic earthquake and for the combination of the normal operating loads plus the peak loads from the worst loss of coolant accident.
(a) The methods of analysis (elastic,-clastic-plastic, limit, etc).
(b) The limits to wh,1ch the critical co=ponents were evaluated (streas, strain, deflection, buckling, etc) with numerical values for several critical items.
(c) Fcr each method of analysis relate the possible errors in the analytical method and the possible errors in loads used for the stress calculations to the targin of safety which is being provided.
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With regsrd to the reactor internal structures please provide the following information:
(a) Has a conplete vibration analysis been made which takes into account both the normal and emergency modes of operation?
(b) Please provide a listing of the reactor internal vibration tests which are considered necessary for the Monticello plant.
In this i
listing include the number, type and location of instruments for each test.
(c) State the conditions under which the vibration tests vill be conducted, i.e.,
cold, hot functional.
(d) For test conditions other than hot functional, state the basis and methods for correlating the test data with t'he hot functional i
condition, e.g., relate the significance of changes in fluid i
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l density, changed clearances due to thermal expansion.
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