ML20234F214
| ML20234F214 | |
| Person / Time | |
|---|---|
| Site: | 05000000, 05000531 |
| Issue date: | 09/16/1974 |
| From: | Maccary R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Moore V US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20234C970 | List:
|
| References | |
| FOIA-87-40 NUDOCS 8707080142 | |
| Download: ML20234F214 (4) | |
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SEP 161974 j
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ld Yoss A. Moore, Assistaat Director f-for Light Water Rasctors, Group 2 g
Directorate of fAa===ias sy U,3 c m Ar ELECTRIC CORPORATION, GESSAR-251, PROJECT Mo. 538 k[j Project Names General Electric Standard Safety Analysis Report (GESSAR-251) 37 Suppliar: General Electric p
Project Numbers 538
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Responsible Branch.and Project Manager: LWR 2-1; D. M. Crutchfield Raquested completion Date: September 25, 1974 c
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Description of Responses Acceptance Review p4.
Baview Status: Complete N
In accordance with the schedule for Acceptance Review, September 3, 1974 Q
Crutchfield~to TR A/D's, the Materials Engineering Branch,' Directorate of' G-
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Licensing, has conducted an Acceptance Review of the subject application, j
i The following is a stansary of our review of the SAR.
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Areas of Reviews s
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Oct. 1972 SAR H'
SAR Standard MITB Areas of Review Sections.
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Formst Yeviewed l
4 M-6.2.2 Reactor vassal internals (materials) 4.2.2 li 4.2.3 Reactivity control systems (materials) 4.2.3 j~
5.2.3.1 Material specifications 5.2.3.1
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5.2.3.2 Compatibility with reactor coolant 5.2.3.2 i
5.2.3.3 Compatibility with external insulation and 5.2.3.3 c.J l
environmental atmosphere 7) l 5.2.3.4 Chemistry of reactor coolant 5.2.3.4 d
l 5.2.4.1 Compliance with code requirements 5.2.4.1 il 5.2.4.2 Acceptable fracture energy levels 5.2.4.2 4
5.2.4.3 operating limitations during heatup, cooldown, 5.2.4.3
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and hydrotest 5.2.4.4 Material e3nrve111ance program 5.2.4.4 5.2.4.5 C$pability to anneal 5.2.4.5 5.2.5 Austenitic stainless steel 5.2.5 IT.l '
5.2.7 RCPB 1mm h ge detection systems 5.2.7 i'{
5.2.8 Inservice inspection progran 5.2.8 6.0 Engineered safety features (materials) 6.0 4.-
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SEP 161974 Yoss A. Moore g,:j
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Additional Informatlhn' Required
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@d Additional information vill be needed in the area of materials for reactor vessel internals, reactivity control systems, and engineerad L;,j safety features. A pre 14=4 nary request for additional information is enclosed.
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Assessment of Acceptabi.11ty:
zub-ft The SAR containa approximately 90% of the Materials Engineering y
Branch's required information.
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Conclusion:==
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We find the information submitted in the SAR sufficiently complete that an evaluation can be perform $d with one round of questions, w
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.i<)j R. R. Maccary, Assistant Director
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H; for Engineering S;j Directorate of Licensing k,_
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6 Preliminary Request for sl Additional Information i$
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S. H. Hanauer, DRTA 7.!
F. Schroeder, L M
S. Varga, L y
J. Stolz, L g,3 D. M. Crutchfield, L R. Martin, L S. S. Pawlicki, L Vi W. S. Baralton, L
'3 R. M. Gustafson, L d
K. G. Boge, L 4
k cc v/o enc 1:
ili A. Giambusso. L W. G. Mcdonald, L a
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MATERIALS ENGINEERING -
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f l'20.1 In Section 4.2.2.1.2.5 of the SAR you state that the material p
(4.2.2) used for fabricating most of the reactor vessel core support hj and reactor' internal structures is solution heat-treated.
lg unstabilized type 304 austenitic stainless steel. List other
@f materials used for these components and list their specifications.
et a.iN 120.2 In Section 4.2.3.1.1.2 of the SAR you state that type 304 fj (4. 2.3) austenitic stainless steel comprises the major portion of the Q-assembly. Lis't other materials used for the reactivit'y Id!
control system and list their specifications.
j.iy lfd 120.3 Provide the following information concerning metallic materials fi (6.0) used for components of engineered safety features.
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(1) List the specifications for the principal pressure-p retaining ferritic materials, austenitic stainless steels, p.;
and non-ferrous metals, including bolting and weld 46 materials, in each component (e.g., vessels, piping, f, _,
pumps, and valves) that is part of the ESF.
k (2) List the ESF materials of construction that will be g
exposed to the cere cooling water and containment sprays y
in the event of a loss-of-coolant accident, and describe y
the compatibility of the construction materials with the f.]
cooling solutions.
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(3) Provide the following information for avoidance of stress-N corrosion cracking of austenitic stainless steels for
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components of the ESF during all stages of component y
manufacture and reactor construction:
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(a) Sufficient details for avoidance of significant sensitization during fabrication and assembly of
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austenitic stainless steel components of the ESF to 43 indicate that the degree of freedom from sensitization
@d will be comparable to the recommendations of Regulatory Guide 1.44, " Control of the Use of
- tij Sensitized Stainless Steel." Provide a description P.i!
of materials (including provision for 5% minimum M-delta ferrite when required), welding and heat treat-ing processes, inspections, and tests.
%Q (b) Sufficient details about the process controls to y
minimize exposure to, contaminants capable of causing
'j stress-corrosion cracking of austenitic stainless 0
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steelatomponents.of the ESF to show-that'the process f:
controls will provide'a degree of surface cleanliness, l
during all stages of component manufacture and reactor construction, comparable to the recommenda-f
'tions of Regulatory ~ Guide l.44, " Control. of. the Use of. Sensitized Stainless Steel," and Regulatory, Guide 1.37, " Quality Assurance. Requirements for Cleaning of Fluid Systems and Associated' Components t'
of Water Cooled Nuclear Power Plants."
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I (c) Details on cold worked austenitic stainless steels.
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for components of.the ESF.. Ifisuch steels have
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l yield strengths greater than 90.000 psi, provide 7
assurance that they will be compatible with the core' cooling water and the containment sprays in the event.
of a loss-of-coolant accident.
(d). Sufficient information about the selection, procure-F ment, testing, storage, and installation of any l..
nonmetallic thermal insulation for austenitic j
that concentration of chloride, fluoride, sodium, stainless steel components of the ESF to indicate
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an0 silicate in the insulation will be comparable to' the recommendations of Regulatory Guide 1.56,
" Nonmetallic Thermal Insulation for Austenitic Stainless Steel."
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