ML19220C312
| ML19220C312 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/30/1974 |
| From: | Washburn B US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904300166 | |
| Download: ML19220C312 (5) | |
Text
s UNITED STATES e
j q
ATOMIC ENERGY COMMISSION l'N J G e
- [
W ASHWGTCN. O.C.
M545 s.
%,,,, /
October 30, 1974 Decket No. 50-320 APPLICANTS:
Metropolitan Edison Company Jersey Central Power and Light Ccmpany Pennsylvania Electric Company FACILITY:
Three Mile Island Nuclear Station, Unit 2
SUMMARY
OF OCTOBER 21, 1974 MEETING IU BETHESDA TO DISCUSS STRUCTURAL DESIGN CHANGES On October 21, 1974, the applicants ' representatives met with members of the Regulatory Licensing and Operations staffs to discuss structural design changes.
A list of attendees is attached.
Significant discussion pointe are summarized belcw.
1.
Partial embedment of temocrary colar crane structural steel su;corts in tne structural concrete of the re-fuelinc canal insice containment.
Fcr those areas involving the subject embedment, we need formal, explicit assurance a.) that the as-built wall can carry all design leads, including earthquake leads, and b.) that the concrete could be and was acceptably poured around the structural elements.
The staff discussed the analyses and information which would be meaningful in providing the required assurance.
Approximate stress analyses of the as-built structures, where the embedments are involved, would provide bases for evaluation.
These should consider differential pressures, temperature loads and earthquake loads as used in the original design.
Stress analyses of the area around the embedments of the tcwer support hori ental and vertical plates are of particular importance since this region carries the maximum loading and the plates cannot transmit shear and tensile loading.
Analyses should show that sufficient steel was installed to acccmmodate the calculated stresses in the areas of embedment.
As-built drawings er sketches should be submitted in o 1 i b, c9 m
7904300 W
/
y
. Summary of October 21, 1974 meeting---
support of the analyses and in support of the descrip-tion of the structural details.
Meaningful information on the concrete pour would include details of how the concrete was placed, min-imum slump figures, statement on vibration of the pour, and mix and design strength of the concrete.
The applicants' representatives indicated that they would submit a report st=narizing their study which would include stress analyses and information per-taining to the adequacy of the reinforcing and cual-ity of the concrete pours.
The applicants will in-form us by letter of their proposed schedule to submit this report.
2.
Tendon system changes.
The applicants reported that the previously evaluated and selected tendon strand supplier has stopped making these strands.
A new supplier has been found; however the new supplier will make strands which are of lesser diameter than those originally evaluated.
The tendon wedges have been redesigned using the same principle with revised gecmetry as compared to the previously reviewed design.
Tests comparable to those made during the original evaluation have been ccmpleted and a report is in preparacion.
The appli-cants and A-E will arrive at a decision on the use of this new design following full scale tests using 54 s trands.
Three test wedges and one test strand were presented by the applicants' representatives for visual exami-nation.
The staff indicated that we need a very detailed re-port similar to that originally submitted for our evaluation.
This report should indicate that the materials satisfy applicable ASTM specifications and that the materials and designs satisfy the joint ACI-ASME draft code (Concrete Reactor Vessels and Con-tainments,Section III, Division 2 of ASME Boiler and Pressure Vessel Code) on pre-stressing contain-ments.
RO-I needs to be notified, by the applicants, of all testing, including grouting tests, so that they may observe.
n Gl w.u
Summary of October 21, 1974 meeting---
The applicants' representatives indicated that they plan a December 1974 submittal of the report on these tendon system changes and that they need resolution by mid-January 1975 in order to maintain their present construction schedule.
The staff stated that we will need a very detailed, completely adequate report and will require about six weeks for review.
fl
' l /f Yf/ N '
W.
Washburn, Project Manager Light Water Reactors Branch 2-2 Directorate et Licensing
Attachment:
As stated nQ 717 U<
L1J
Attachnent Jocket No. 50-320
- -,As.-
3.,,
.d.i.. 2
.a_ iu.4uC :AR, Am. Co,,
s m, a.r e L. 7.,.
t q _. q 3 c~t;m A m. y r ', C v" *. C o. r o. 21. ~_ ^74-----
- m. T..< g
.e, - m.u.. A p.i.ng.-.
a i
~C
.. s 2
J
- 0.. rc.,d. L JOQ1VAI C..d tua0
.Lv na L.S,.
L,,e Aet
.f,usca-J. H. Wrigat GPUSC J. '!.
Vann GPUSC L. ~aribian OPUSC J. I. hunkel GPU J. F. 'Jcore c,PU R. H..Cason UE1C Inc.
J. C. Archer Burns and Roe
', l.
R. Cobean, Jr.
Burns and Roe
!... G. Suare:
Stressteel Corp.
S. A. Folsom AEC: RO I J. 3. Hendersen AEC: R0 HQ A. L. Glucknann AEC: L-SE3
- 3. W. Washburn AEC: L-RP
!b2 L i ' '
i i
o DISTRI3L*TICN:
Docket File R0 (3)
AEC PDR M. Service L PDR Participant
. Reading ACRS (16)
LWR 2-2 Reading R. Denise K. Coller R. Purple V.
A. Moore G. Lear R. C. DeYoung D. J. Skovholt D.
R.
M.ulle r W.
R. Butler J. F. Stol:
R.
A.
Clark R. E.
Ireland D. 3. Vassallo K.
Kniel 0.
Parr A.
Schwencer R. J. Sche =el D. L. Zie= ann P. L. Collins G. W. Knighton G.
Dicker
- 3. J. Youngb1 cod W. H. Regan, Jr.
S. Varga D. Eisenhut F. Schroeder R. R. Maccary V.
Stello R. L. Tedesco H.
R. Denton J. P. Knight S. S. Pawlicki L. C. Shao T. h. Novak D. F. Ross R. W.
Hous ton T. A.
Ippolito C. Long G. Lainas V.
Senaraya R. H. Vollme r 3.
K. G ri=es W.
?. Ga==ill J. Kastner M-Spangler R.
L.
Ballard
.' l'roject Mana ge r Project Manager CGC n
n1E 0g' t
i J s