ML19220B171
| ML19220B171 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/04/1975 |
| From: | Maccary R Office of Nuclear Reactor Regulation |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 7904250492 | |
| Download: ML19220B171 (2) | |
See also: IR 05000320/1975008
Text
N...
-
O
,
'-
. * = = ,
,
N
Occket No.:
50_ 29
i
R. H. Grier, Director
Division of Reactor Inspectipn Programs
Office of Inspection and Enforcement
METROPOLITAN EDISCH COMPANY - THREE MILE ISLAtID PLANT, UNIT 12
DEVIATICNS NOTED IN I.SPECTION REPORT 50-320/75-8
(a) APPLICANT'S Lu dR DATCD AUGUST 21, 1975
(b)
K. V. SEYFRIT'S NOTE TO R. T. CARLSON DATED CCTOBER 6,1975
STRUCTURAL EVALUATICN (TAR #1940)
Plant Name:
Three Mile Island Unit #2
Deckat No.: 50-320
Licensing Stage:
FSAR-OL Review
Branch and Project Leader Requesting Assistance: CRIP; R. Shewmaker
Requested Ccr:oletion Date:
November 10, 1975
Technical Review Branches Involved: S+"uctural Engineeri..;
Description of Request: Memo dated October 23, 1976
Review Status: Co@lete
In accordance with your request the Structural Engineering Branch,
Division of Technical Review, has reviewed and evaluated structural
sections of the documents listed above.
The inspection Report 50-320/75-8 lists three deviations as follows:
Deviation A
Comressive strength tests on cubes of the grout at seven days were
not perfomed by the applicant. They are required by the FSAP, and
ACI Standard 301. However the applicant has made compression tests
at 28 days. It shculd be noted that the design of the containment
structune does not rely on the strength of the grout, but only on
its capacity to prevent corrosion of the tendons. The applia nt's
conclusion is that this deviation does not impair the functional
capacity of the structure and we concur with this conclusion.
Deviation B
The applicant did not perform chemical tests on grout.
It should
be noted that in the PSAR in answer to SE3 question 2.10 in su;'ple-
ment f 2 Fage 2.10-5, revised March 10, 1969 the applicant stated:
Conclusion
"
,
't h trirpr.t 5 tM :bcft df:c':: 6
$t m tegt'c' agi st
erittlement, requires ' as' psien, stresd
-
of corrosiod, pitting cor
the three dangerous f m
, , , , , , ,
an~ absolute
corrosion, and hydrogonw
minimum the exclusion of agressive-agents which,_in
this apolica-
_ - _ . . . . . -
'v~*-*
oa75 S*
. . . . .
_
_ .
. .
_
.-
Ferns MC 318 (Re. 9-5 5) moi 0240
T.T u. e. eave ==esswt == inn =e arric er n on- sas.e se
73 239
79042504%
4
.
@
'
.
R. H. Grier
-2-
575
'
'
tion, are chlorides, nitrates and sulchf-.
The ACI " criteria for Reinforced Ccncrete Nuclear Power Containment
Stmetures" published in January 1972, in 3.2.3 reccrrends for freshly
mixed grout limits on chlorida and sulfate content. The "ASME
Boiler and Pressure Vecsel Code",Section III, Civision 2 establishes
in CC-2243.3 limits for chlorides and nitrates for freshly mixed
gr ou t.
This code is referenced by the acplicant in the FSAR,
Section 3.8.1.2 Page 3.8-2.
Becsuse of its possible bearing on corrosien of tendons we feel
dat this deviation is of the greatest icportance. We therefore
reccrmnend that the applicant performs:
(a) For tendons already
gmuted:
tests for nitrates and chlorides performed on samnles
of grout fabricated using the same Imterials and crecedures as uwd
in the original gmut.
(b) For tendons not yet grouted we recommend
the perfomance of tests as required by the ASME Code.
Deviaticn C
The applicant has not detemined the alkalinity of the wet grout.
It is krxnin historically that grout mixes in general provide the
required pH.
The pertinent codes do not require this detemination.
We themfore concur. with the applicant's suggestion that this deter-
mination can be avoided without impairing the capability of the
structum to function as required.
Conclusions
We recanmend that the applicant be required to perfom the tests
indicated for Deviation B.
We also expect that the applicant will provide us with the final
draft of Appendix 3E on grouting which has bes
9thdrawn by the
applicant in Araendment 31. This Appendix 3E is
ntial to pemit
us to finalizt our evaluation of the FSAR.
R. R. Maccary, Assistant Director
for Engineering
Division of Technical Review
Office of Nuclear Reactor Regulation
cc:
R. Boyd, RL
V. Moore, RL
H. D. Th!&nburg, IE
W. Mcdonald, MIPC
K. Kniel, RL
T. Abell, MIPC
FC i r=, 7
B ,u , E
'
p.w a r , E^
<
o.
s.
n.
_.
S. Varga, R L
K. Y. Sey'ri.t, IE'
Jt, Kehnemuyi, TR
.._
a.ne.
D. ' F. Knuth , Ic
J. H. Sniezek, IE
L. Shao, TR
..A.. G. -Davi s , IE---- G.4.-- Reinmuth RIB- -
A.Glt9kmann,TR
.u--.*
om *
. _ . . . . . . . _ . .
_
C._lanmTR
l __
R. She wakcr .IE
.
.,.
a ..:......
,..n.
, 4 g ae [A r.9;Av4.-
c-
r- m m < a,. 9.s 3 > incu o24o
.
O.
.
.
. 25
- ,
-
'i:1 2 4 1
,
_
TR:5EB
TR:SEB
TR:S B
TR:SEB 'I
"R:AD:E /
' f'
"l'
~ ~ ~
y
o,,,c e
x7807 #4,
~~^ M / f
-1
e
AGl uckmanniIa CTan
KKapur -
--
1. c hd.
-l Rhac' car [~'
- - - -
-
-
.u--*
M/3/75
18/ 3 /75
10/ 3 /75
. - . -
. .. /3 /. 7 5
-
10/.J /..75
-
1
.,,,, ,
gy.
.. . - - . .
-
-
Foran AEC.318 i Rev. 9 * )) ARCM 0240
- w. e, eovsammmv enecmese oreicas s era.ese see