ML19210A107
| ML19210A107 | |
| Person / Time | |
|---|---|
| Site: | Crane, Crystal River  |
| Issue date: | 06/13/1978 |
| From: | Grimes B Office of Nuclear Reactor Regulation |
| To: | Taylor J BABCOCK & WILCOX CO. |
| Shared Package | |
| ML19210A104 | List: |
| References | |
| NUDOCS 7910240826 | |
| Download: ML19210A107 (5) | |
Text
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REQUEST FOR ADDITIONAL INFORMATION INTEGRITY OF CONTROL ROD GUIDE TUBE (CRGT)
BABC0CK & WILCOX FACILITIES Answers to the following questions should be supported with data and drawings to the extent possible.
1.
Describe the details of any routine surveillance of fuel assemblies performed at your facilities using your NSSS design.
2.
Have examinations of the fuel assembly guide tubes to detect wear been completed at any facility using your NSSS design? If so, provide the following information:
The method of examination (i.e. destructive testing, eddy-cur-a.
rent testing, periscope, borescope, mechanical gage, TV, etc. )
b.
The reas of CRGT examined.
Qualification of the examination procedure.
c.
d.
The number of CRGT sampfed it each facility and the applicable operational parameters including: the core location; EFpH; time in service; related control rod parameters; fluence; etc.
Results of observations or measurements.
e.
3.
Were any CRGT destructively tested (e.g., by mechanical or metallographic means) and what observations or measurements were made?
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What correlations were suggested between operating parameters and CRGT condition?
} k b.)h 79102 0
2-5.
If specific examinations for CRGT wear have not been completed at any facility, either provide other evidence for the absence of wear or answer the following:
a.
Are examinations planned? If so, provide details as requested in 2 a-d.
b.
Have out-of-pile wear tests been completed? If so, provide details including qualification of the test procedure and answers to 2 a-d.
Address vibration, fatique, flow visualization, etc.
6.
Document any other observations of wear or degradation found in the examination of your fuel assemblies (i.e., grid wear, post wear,etc.). Provide the results of your assessment of the consequence of these observations.
Describe any design changes effected to either mitigate the consequences of this wear or eliminate the wear.
7.
If CRGT wear has been found at facilities using your NSSS design:
What have been the attributive causes?
a.
5.
Have correlations been made to characterize the phenomena with respect to operating procedures and plant specific core parameters?
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- Are specific locations within the core or particular c.
CRGT within an assembly rrcre susceptible?
8.
If CRGT wear has been observed at any facility using your NSSS design:
Desc:-ibe your efforts to reassess the mechanical integrity a.
of the core with worn CR3T to demonstrate tnat cool-ability and scramability exist for the normal, seismic
- nd anticipated operational occurrence loading conditions.
Describe the worst condition analyzed.
b.
Discuss your structural design bases.
Indicate if provisions have been made to accommodate wear in the design.
What amount of wear or related degradation would be cause for rejection for reload?
Provide the allowable stresses used in the structural analysis. Discuss the effects of tem:erature strain rate, notch severity, irradiation and hydrogen content on mechanical properties used to establish the allowable stresses.
Provide the results of your structural analysis surrrarizing the c.
CRGT loads and the primary and secondary stress intensities for normal, fuel handling, and accident loading conditions.
d.
Discuss the effects of CRGT wear on the thermal-hydraulic performance of the reactor under nor nal and accident conditions.
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. 9.
Discuss any control rod scram testing that has been completed to demonstrate scramability in worn CRGT. Address the effects of worn CRGT on scramability for the worst expected guide tube geometry.
Include the strain-deflection limits for control rod functionability.
10.
If examinations for CRGT wear have not been or will not be made at representative facilities using your NSSS design, provide justif'eation for continued operation of these facilities.
11.
B&W has redesigned the guide tube lock nuts of later design fuel assemblies by mking a change from zircaloy to stainless steel to mitigate the effects of observed wear in the upper region of the guide tube.
Indicate which design is employed at each B&W designed facility and indicate any observations that have been made to detect wear in this area and/or verify the adequacy of the redesign.
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