ML19294A912
| ML19294A912 | |
| Person / Time | |
|---|---|
| Issue date: | 04/18/1978 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Grossman M, Knight J Office of Nuclear Reactor Regulation, NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| Shared Package | |
| ML19294A895 | List: |
| References | |
| TASK-AS, TASK-BN-101 BN--101, BN-101, SECY-79-88, NUDOCS 7905080217 | |
| Download: ML19294A912 (2) | |
Text
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ENCLOSURE D to Containment Buckling j f
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NUCLEAR REGULATORY COMMisslON 2
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MEMORANDUM FOR: Milton J. Grossman, Hearing Division Director and Chief Counsel, OELD James P. Knight, Assistant Director for Engineering
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Division of Systems Safety, NRR
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D. B. Vassallo, Assistant Director for Light Water j 'l Reactors, Division of Project Management, NRR f
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SUBJECT:
BOARD NOTIFICATION - BUCKLING OF STEEL CONTAINMENT
- f SHELLS (BN-101)
We are now in receipt of the enclosed April 10, 1978 M, Grossman memorandum on the above subject.
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In our opinion the information is still very preliminary with no clear staff position as yet, which appeared to be the basis for not notifying Boards of the high energy line break situation. However, we would agree f
to forwarding to appropriate Boards for information, the enclosed question sent to Allens Creek as being typical of information being supplied to 5 ;-
applicants on this matter. Please note that the information of signifi-cance is contained in the last two paragraphs of Question 130.21 and requests no information from the applicant.
It states that we are not in
,c a position to change previously accepted criteria at this time.
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p The original I. Sibweil memorandum suggested that BWR Mark III and PWR ice condenser containments could be impacted.
It appears to us that all
[J free standing steel containments would have buckling as a design considera-
' :s tion.
J. Knight should clarify this and provide a list of plants affected.
I will then prepare another recommendation regarding Board notification on 7
this matter.
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. B. Yassallo, Assistant Director
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for Light Water Reactors
-4' Division of Project Management N
Enclosure:
Tt-As stated cc w/ enclosure:
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E. Case R. DeYoung J. Stolz E. Volgenau V. 5+ello K. Kniel R. Boyd D. Eisenhut
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--)R. Ma ttson T. Engelhardt S. Varga H. Denton B. Grimes I&E (7) 1.:
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130-3 1 i 13r0.18 The anti-corrosion measure as described in Section 3.8.3.1.3 which is the same as in GESSAR-238 may not be adequate, and it is our
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understanding that the GESSAR-238 application is being revised to includ(Tew anti-corrosion measures, provide information to show
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that'your proposed measures are adequate.
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'The following questions are related to the Containment Structures Design Report, dated July 1977 and prepared by ESASCO services,)nc.:
130.19 Describe how the effect of multiple ubsequent actuati'on of re[ lief valves f'{.
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has'been considered in the design,p the containmen't structure InSection4.4.itisstatedtha'tinthecombin/
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ation of to,tal loads, other 130.20 (RSp) loads and seismic loads inAhree directi, cps'will be ac 'nplished by *he Ii SRSS method.
It is thedtaff's oosition that the SP. % method ma r-be used only for the,<6mbination of shsmic loads'in three dipections'/
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but not for the tot 11 combination'of all loads. For the latt,er the combination should be done by the.absolete sum method unless information
] s provide Q o, justify your method.
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t 130.21 In section 5.0 and 6.0 it is stated that the design of the steel containment
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will be in conformance with the requirements of ASME Code Section III r..
Suosection NE and Regulatory Guide 1.57 and that a factor of safety of 2 against buckling is used. Since the actual factors of safety against ll buckling ill be different for different load combinations, indicate the actual f actor of safety for each load combination as shown in Table 6.1-1.
Also describe the method of analysis used to compute these factors of safety.
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In a report entitled " Stability Criteria for Primary Metal Containment 7,
Vessel thder Static and Dynamic loads" written for GE by R. L. Citterley of Anamet: Laboratory, Inc., a factor of safety against buckling ranging from L l1 2.0 to 2.75 is recommended. Also recently the 1977 summer addenda of
.R the ASME Code recuires a factor of safety of between 2.0 and 3.0 against l ?
buckling depending upon the applicable service limits.
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Due to the lack of experimental data and uncertainties in establishing the h
theoretical buckling load, we have an ongoing techhical assistance program
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to study this issue.
It is expected that any final design recommendations H;
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or guidelines resulting from this program will be evaluated for possible t.
use in our licensing review work. We are not at.this time in a position to y i'7 make any changes to previously accepted criteria. However we urge you to MO study your buckling criteria further and form a strong technical basis J3 for your approach. As indicated above, through the help of our outside J
consultant, we shall develop our technical position and shall decide the extent to which the position thus developed will be applied to previously accepted applications.
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