ML20234F274
| ML20234F274 | |
| Person / Time | |
|---|---|
| Site: | 05000000, 05000531 |
| Issue date: | 09/23/1974 |
| 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 8707080162 | |
| Download: ML20234F274 (5) | |
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L-Rdg Project File 538
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};3 Voss A. Moore. Assistant Director for Light Water Reactors. Group 2 4
Directorate of Licensing.
@M GENERAL ELECTRIC COWANY - 251 GENERAL ELECTRIC STANDARD SAFETY j
ANALYSIS PIPORT. NUCLEAR STEAM SUPPLY SYSTEM (251 GESSAR NSSS) g-PRELIMINARY REVIEW OF THE SSAR V..
Plant Name: N/A
{[j Licensing Stage: Preliminary Review of 251 GESSAR NSSS u
Project Musber: _538 3
Responsible Branch and Project Manager: LWR-2-1, D. M Crutchfield Requested Completion Date: Septem6er 25.1974 Applicant's Response Date Necessary for Completion of Next Action -
D Planned on Pmject: Unknown ici' Description of Response: Preliminar/' Review Q
Review Status: -Complete Ei, The 251 GESSAR NSSS submitted by tho' applicant has been reviewed
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by the' Structural Engineering Branch to evaluate its acceptability S
as to completeness. The degne of completeness of the app 11 cation I
has been judged on the basis of the " Standard Forest and Content of b:$ -
Safety Analysis Reports for Nuclear Power Plants.". The enclosure, p
SSAR Preliminary Review Notes, presents the details on the review
$I-of the applicant's SSAR.
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The overall assessment of the application indicates that, in the reviewed sections. primarily assigned to SES, approximately 8% of the information required is considered missing. Nevertheless, it u
f is recouniended that the applicat m be accepted for docketing and, s
in the meantime, the information ifated, be requested from the Q-applicant.
01181 al sign a by:
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R. R. Maccary, Assistant Director d
for Engineering W
Directorate of Licensing d:
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Enclosure:
SSAR Preliminary Review Notes
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251 GESSAR NSSS-AEC PROJECT N0. 50-538 e
%'3 SSAR PRELIMINARY kEVIEW NOTES STRUCTLEAEffiGINEERING BRANCH
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Areas of Review-.
d g+s The following sections, for which the Structural Engineering Branch has the primary review responsibility, were reviewed
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for completeness on the basis of the October 1972' issue,
.,1a Revision 1, of the " Standard Format and Content of Safety A
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Analysis Reports for Nuclear Power Plants."
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}l3 October 1972 SAR q'g; -
Format Section Section K
3.3 3
3.3 r.w 3.4 3.4 (t}
3.5.1 3.5.1 A.,
3.5.4 3.5.4
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41-9 3.5.5 3.5.5 i
- 3. 7.1 3.7.1 q
3.7.2 3.7.2
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3.7.3 3.7.3 q
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3.7.4 3.7.4 N,
3.8 3.8 d
'1 B.
Identification of Major Deficiency Areas 14 13.1 The applicant should identify those systems and components G
(3.3) d within the 251 GESSAR NSSS scope of supply that should not M
be exposed to the effects of wind and tornado in Section 3.3 M
for balance of plant (B0P) designers to determine appropriate it) plant layout and select protective structures as needed for the identified items. Alternatively, the applicant may
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Q define in Section 3.3 prescribed levels of wind and tornado l
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loadings to which systems and components of the NSSS are J{
designed so that a 80P designer can determine whether the j
systems and components require protection from applicable
?j wind and tornado effects given a set of pertinent site parameters.
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13.2 NSSS-BOP interface design infonnation applicable to water f
(3.4) 1,!
level and flood consideration for 251 GESSAR components and systems similar to those specified in Question 13.1 should sjj be included in Section 3.4.
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Q 80.M Tid h diEDIE5iUEK M N M L S ud A S S = 5 $ M 5.YS U I N A N D:
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Ny 13.3 NSSS-B0P interface design information regarding missile 5
(3. 5.1 )
protection consideration-for-251 GESSAR components and 7
systems sim_ilar.to those specified in Question 13.1 shouli Q
be provided ih' Section 3.5.1.
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- 3 13.4 In Section 3.7 clear stipulation of allowable NSSS-B0P (3.7) interface seismic loads, forces, displacements and strains,
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etc., for systems and components within the scope of supply 22 of 251 GESSAR should be included.
M 3
13.5 In Sections 3.8.1 and 3.8.2 the interface design information M
(3.8.1 and and parameters that will be provided by General Electric y
3.8.2 Ccmpany to applicants referring to 251 GESSAR or vice versa, h
for use in the design of either the NSS system or the d
containment should be described and discussed with augmen-tation by sketches as required. This would include contain-ment pressure, mass and energy releases following LOCA accidents, y
the loads from various postulated pipe breaks and' pipe reaction forces, equipment reactioneloads, floor respons' ' spectra and e
y deflections which could be tolerated by systems and components
/i within the scope of 251 GESSAR NSSS.
3d 13.6 In Section 3.8.3, General Electric Company should outline
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(3.8.3) the method to be utilized which will address the design interfaces between the NSS systems and equipment supplied W-by General Electric Company and the internal structures of
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Q the containment which constitute a part of the balance of d
plant.
It should be made clear as to whether GE will have q
1 a range of values for interface design parameters or specific values of the same parameters for which the balance of plant 3
must be designed. These specific interface design parameters t
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. for the NSSS should be adequately defined and provided in the section.
Examples of some of the parameters which must be Fj considered are mentioned in the question 13.5.
With the 1
P!
interface design parameters defined, B0P designers may adopt appropriate design measures to ensure that the required NSSS g
interface parameters and requirements are fully met. Al ter-i$
natively, a specific BOP design associated with a specific site can be evaluated ;tgainst 251 GESSAR NSSS interface design V{
parameters to establish compatibility between the two plant systems.
h, The applicant should indicate its basic position regarding a
Z these design interface integration problems and provide J
sufficient information for review, accordingly.
4 C.
Preliminary Areas of Concern E
g 13.7 Because of an increase in diameter of the reactor vessel and (3.7) d its associated changes, the seismic responses of the PPV a
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@i and' internals system may be:significantly. changed from -
F those of a model usinLajmaller diameter vessel. ' The 7
L applicant shoul,d difcuss any changes in dynamic model,
!.h key analytical parameters and responses in the SAR.-
2 6
13.8.-
. In LSection 3.7.3.15, a reference is made to Section k
- (3. 7. 3 )*
3.7.3.2.3 for a description of the reactor seismic 4
analysis; The referenced.section cannot be. found in the'-
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'SAR.
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13.9-The basis-for adepting damping values of. 5% for'0BE and
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'l(3.7.1)'
6% for SSE in. determination of seismic responses for fuel
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elements as propcsed in Table 3.7.1 should be provided.
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