ML19319D508
| ML19319D508 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/13/1973 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19319D504 | List: |
| References | |
| NUDOCS 8003170634 | |
| Download: ML19319D508 (1) | |
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Attachment A g
3EB RECULATORY POSITIdN PREOPERATIONAL PIPING DYNAMIC EFFECTS TEST PROGRAM Preoperational piping vibrational and dynamic effects testing should be conducted during startup functional testing on piping systems and restraints classified 'as ASME Class 1 and Class 2 components.
The pursoce of these tests is to confirm that these components have been desig _d to withstand the dynamic loadings from o,erational transient conditions that will be encountered during service as required by ASME Code Section III, par.
NB-3622.3 and NC-3622.* An acceptable test program to confirm the ade-quacy of the designs should consist of the following:
a.
A listing of the different flow modes of operation and transients such as pump trips, valve clo's'ures, etc. to which the components will be subjected during the test.**
For example, the transients associated with the Reactor Coolant System heatup tests should 8
include, but not necessarily be limited to:
(1) Reactor coolant pump start (2) Reactor coolant pump trip (3) Operation of pressure-relieving valves b.
A list of selected locations in the piping system that vill be subjected to visual inspection and measurements (if needed) as performed by the piping designer during these tests. For each of these selected locations, the allowable deflection (peak-to-peak) criteria that will be applied to establish that, the stress li=its are within the design levels should be provided.
c.
If vibration is noted beyond the acceptance levels set by the criteria of b. abovt corrective restraints should be designed, incorporated in the piping system analysis and installed.
If during the test, the piping systems restraints are deter =ined to be.inadec,uate or damaged, corrective restraints should be installed and another test should be performed to determine that the vibrations have been reduced to an ac:tI*: Lie level.
T
- Reference ASME Code Section III, " Nuclear Power Plant Components"
- Additional guidance for the selection of such transients is provided in the AEC Guide for Planning of Initial Startup Programs" December 7, 1970.
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