ML19308D783
| ML19308D783 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/03/1969 |
| From: | Bromerick A US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8003180716 | |
| Download: ML19308D783 (5) | |
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. Roger S. Boyd, AU/RP, unL
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Saul Levine, AD/RT, DP1 PLORIDA POWER CORPOPATION -- CRYSTAL RIVER NUCLEAR GENERATING PLANT, UNIT 3, ' DOCKET NO.,50-302 -- STRUCTUML REVIEW OF AMENDMENT 7, DATED JULY 15, 1969 We have reviewed the structural information presented in Amendment 7 for the Crystal River Nucicar Generating Plant and found it acceptablo in three of the four specific areas reviewed.
The throo acceptablo items are detailed below.
1.
Cadwald Testing -- Appendix 53, pp. 5D-5 to SD-7 Tho Cabeld splice testing program as submitted in Ancade nt 7 is acceptable with regard to ST guidolinas, if the progran procedures apply separately to each crew ia addition to each har si:e and each V sition as stated in the nnondaent.
2.
Dynas c.uclynis - - p. 2, supplement i It is requested that the topical repere to be tube.itted uhich is bein; prepared by Gilbert As:cciates be submitted as soon as pessible.
3, Foundations -- Foundation inrestigation (Supplement 2b, Itea 1)
The revisions in the foundation concepts appear to adequately provide for suitable foundaticas based on the subsurface information-available at this time.. The~ applicant shculd -
continue to keep the regulatory staff advised on new and pertinent subsurface information and any related changes
.in foundation design concepts.
Tho area in which additional information will be required in order that we nay evaluate the adequacy of the propos'ed design e
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to protect the public health and-safety is ths concerned with the Contain:.ent nodesign.- The additional information needad-to permit us to proceed with our roview of Amendment 7 is given in the enclosure.
g A.-W.
Dromerick, Chief Containment G Component RT-734A Technology Branch DRL: CGCT3: aES Division of 'tcactor Licensin;:
Enclosure:
Addl Info Requirod -
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CRYSTAL RIVER NUCLEAR GENERATING PLANT --UNIT 3 Docket No. 50-302 Containment Redesign -- Additional information in this area is required for the review.
Required 'information will be available'chen the following questions have been answered.
- 1.
Figure 5B-12 indicates that the relaxation as a percentage of the guaranteed ultimate tensile strength is projected at 40 years to be less than 2t for the low relaxation wire
-proposed for use.
What value of relaxation will be used e
when calculating the number of tendons required?
2.
What level of prestressing is being prov'ded in the vertical,
. hoop and dcme portic.,
nC the contairnent?
Present these lezele.a-; i.;w/ft arJ as a 2.act:_n of ".
-3.
Are the vartical tendans placed on t:o different radii as in F1,,ure 3C-L cc on one raaius as la Figure 5-1?
4.
T:le computatica on page 33-5 for allowable bearing stresses using-th> recomnended formula (26-1) of ACI 318-63 presents a conflict in view of the statement on page 5B-10 that f'.
C1 will be taken as 4000 psi.
The stress determined under the bearing plate was non-conservatively determined.
It is felt that'the jacking force of 0.8 fjA should be the minimum s
force used to si:e the bearing plate.
Please correct these non-conservative assumptions.
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. 5.
Section 6. 2.4. 2 describes a " Tendon Fati;;ue Test" whose purpose is stated "to demonstrate that the tendon will perform satisfactorily under fatigue loading.
This test should be specified as a " Dynamic Test," with the purpose being to demonstrate the acceptability of an ungrouted ten-don anchorage.
The cyclic loading of 50 cycles does not incorporate any requirenent for the rate of-loading.
e Sinca this test := a cyna:nic tes t, it should be related in frequency te the containment building's dynanic response.
Please consider these itens for Section o.2.4.2.
6 P rov i,i e a str m anal): is for the anchera:e hardware tes te,i as prescribed in ^ ct!o -
9..'.4.8, 6. 2. !. '1, and 0.2.4.10 so that conparisen-ta th-10.s t re
'1 S can 5e made.
Provide the r e s u l t., 4C uoth the test ruralts and the theoretical analysis ns soon a., they are :iv s. l ab l e.
7.
.l hat will be the cyclic rate of loading used in the environ-nental tests of Sections v...'.3 and 6.2.1.7?
3.
How many sample tendons will ce tested under each of the test conditions presented in Section 6.2.4?
9.
To what extent does the reinforcing within each of the test blocks to be used in the Test Program, represent the arrange-ment of reinforcin; to be used in the containment anchorage
- one?
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- 10. 'Specify.and present sample calculations of the analysis to be used;for each of the typical anchorage zones and
' describe how triaxial states of stress will be treated and whether any cracking will be present.
Define the boundary conditions that will be used if loca] analyses are used by the-finite element method.
Present sketches to show the anchorage-:one reinforcing and provide details as to how the-steel was proportioned.
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