ML19308C806
| ML19308C806 | |
| Person / Time | |
|---|---|
| Site: | Palisades, Crane  |
| Issue date: | 01/27/1970 |
| From: | Hendrie J Advisory Committee on Reactor Safeguards |
| To: | Seaborg G US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19308C802 | List: |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8002070540 | |
| Download: ML19308C806 (4) | |
Text
-
~'
l
....i...
=
(,.J ADVI3ORY COMMITTEE ON REACTOR S.. EGUARDS a
UNITED STATES ATOMIC ENERGY COMMISSION WASH INGTON. D.C.
20545
' January 27,,1970 i?.
.s&
Honorable Glenn T. Seaborg Chairman U. S. Ato.nic Energy Coanission a
Washington, D. C.
20545
's L'G
Subject:
REPORT ON PALISADES PLANT
,Sj 7.
Dear Dr. Seaborg At a Special Maeting, January 23-24, 1970, the Advisory Coanittee on 6"
Reactor Safeguards completed its review of the application by Consumers
. [.,
Powar Company for authorization to operate the Palisades Plant at
- .g power levels up to 2200 MWt..TMs project was also considered at the 113th ACRS meeting, Septsmber 4-6, 1969, the 115th ACRS meeting,
~
November 6-8, 1969, and the 116th ACRS masting, December 11-13', 1969.
s4 Subcomittee meetings wore held on July 31, 1969, at'the site, and on October 29, 1969, December 3, 1969, and January 22, 1970, in Washington, gf.
D. C.
During its review, the Co::xnittee had the benefit of discussions with representativas of Consmers Power Company, Ccchustion Engineering, Inc., Bechtel Corporation, the AEC Regulatory Staff, and their consultants.
The Cocnittee also had the benefit of the documents listed. The Committee
["
reported to you on the construction of this plant in its letter dated January 18, 1967.
J
~,.
The site for the Palisades Plant consists of 487 acres on the eastern 1-shore of Lake Michigan in Covert Township, approximately four and one-half miles south of South Haven, Michigan. The minimum exclusion radius
.'.R for the site is 2300 feet and the nearest population center of more than 91 25,000 residents consists of the cities of Benton Harbor and St. Joseph,
8 Michigan, which are approximately 16 miles south of the site.
N W.'i The nuclear steam supply system for the Palisades Plant is the first
~X of the Combustion Engineering line currently licensed for construction.
. Jf A feature of the Palisades reactor is the omission of the thermal shield.
l g Studies wore made by the applicant to show that omission of the shield pp would not adversely affcet the flow characteristics within the reactor Lc vossel or siter the thermal stresses in the walls of the vessel in a
.,,:.e.
manner detrimontal to safe operation of the plant. Surveillance specimens N'
in the vessel will be uced to monitor the radiation damage during the h
life of-the plant. If these specimens reveal changes that af feet the li.-
safety of the plant, the reactor vessel will be annealed to reduce i.I3 l.:
h',.Q ~
m i
eoo2o7o ff0
^
p4
's m n. :m
- n
.o -
-.. :z.n.v y:.~n um. *.~.-~ '_ l ' ' '
.l &.,*f. s.*,,.. ' * ~
- mSxn ??:: : '. : n., N 't. '.**
('.
- f}' g
- l*s,A l
)
,hl.e
~.
m....
.., n, f _,
- 'q
.,,e
.s r
m,
.n
~
.a
{;$
3 Honorable Glenn T. Seaborg January 27, 1970
\\,
radiation danage effects. The results of annaaling vill be confirmnd i,.
by tests on additional surveillance specimons provided. for this purpose.
Prior,to accumulation of a peak fluenca of 1019 nyt (/1 Mev) on r.he roactor vessel wall, the Regulatory Staff should reovaluate the centinued suitability of the currently proposed startup, cooldown, and opernting conditions.
- ...j The secondary containment is a reinforced concrete structure consisting N'f of a cylindrical portion prestreased in both the vertical and circumferential
{.y; directions, a dome roof prestressed in three directions, and a flat non-J; prostressed base. Before operation, it will be pressurized and extensive measurements will be made of gross deformations and of strains in the liner, reinforcement, and concrete, and the patta.rn and size of cracks
'i in the concrete will be observed and measured. The applicant has proposed
'y?
suitable acceptance criteria for the pressure test, and the ACRS recocuends M.
that the Regulatory Staf f review and assess the results of this test
,?
prior to operation at significant power.
5' The prestressing tendons in the containment consist of ninety, one-quarter-
~
inch diameter wires. They are not grouted or bonded, and are protected
(-
from corrosion by grease pumped into the tendon sheaths. The applicant
(;;..
has proposed that selected tendons be inspected periodically for broken wires, loss of prestress, and corrosion. If degradation is detected, the inspection can be extended to the remaining tendons, all of which 4
are accessible. The applicant is performing studies to determine the appropriate number and interval for tendon inspection. This matter should be resolved in a manner satisfactory to the Regulatory Staff.
The core is calculated to have a slightly negativa moderator coefficient at full powor operation at beginning-of-life, but uncertainties in the I '
calculations are such that the existence of a positive moderator coeffi-eient cannot be precluded. The applicant has stated that the moderator g;
coef ficient will not exceed +0.5 x 10-4 A k/k/or at d. sinning-of-lire, Q
computed from start-up test data on a conservative basis. The applicant f.-p
]j also plans to perform tests to verify that divergent azimuthal xenon oscillations cannot occur in this reactor. The Committee reco::xnends that b9 the Regulatory Staff follow the measurements and analyses required to T
establish the value of the moderator coefficient.
.k f.G The meteorological observation program conducted at the site subsequent y
.M to the Cocrnittee's report to you on January 18, 1967, indicated the
?$
need for the addition of iodine removal equipment to the containment I$
for use in the unlikely event of a loss-of-coolant accident. The applicant M
proposed to install means for adding sodium hydroxide to the water in the containment spray system. However; because of uncertainties regarding
)b the generation of hydrogen and the effects of other materials resulting
'y b5 Q.]
i 'O f
t #
- $k T;M W.n y".y ;2.q?m?.%. q @ % w <',. w
.n n :m -
... v.a.,:,..
. G, a..
nonorable Glenn T. Reshorg January 27, 1970 i
from'the reaction of this alkaline nolution with the relatively large amounts of aluminum in the containment, this spray additive will not k;; _ '
will carry out studies of iodine removal by borated water sprays be used unless it can be shown by further studies that the use of sodium hydroxide is clearly acceptable. In addition, the applicant i[
without sodium hydroxide. If the results of these studies are not acceptable, a dif ferent iodine removal system satisfactory to the A
?
Regulatory Staff will be installed at the first refueling outage.
., }f report on the applicant's plans will be submitted to the AEC within slf i six months following issuance of a provisional operation license. The Consittee believes that this procedure is satisfactory for operation
[I y j,.I at power levels not exceeding 2200 MWt.
c.,.
,. ?
The applicant has stated that if fewer than four primary coolant pumps are operating, the reactor overpower trip settings will be reduced
^
p,j such that the safoty of the reactor is assured in the absence of automatic 3-changes in the thermal margin trip settings.
.i The Committee believes that, for transients having a high probability
~
, J of occurrence, and for which action of a protective system or other engineered safety feature is vital to the public health and safety, 1
{f' b:,
an exceedingly high probability of successful action is needed. Conamm i^
failure modos must be considered in ascertaining an acceptable level of
> i.
protection. Studies are to be made on further means of preventing f
commen failure modes from negating scram action, and of design features tp '
to make tolerable the consequences of failure to scram during anticipated transients. The applicant should consider the results of such studies and incorporate appropriate provisions in the Palisades Plant.
d#
The Committee recommends that attention be given to the long _ term ability of vital compononts, such as electrical equipment and cables, n,..g to withstand the environmont of the containment in the unlikely event 17.
l' ?Q of a loos-of-coolant accident. This matter is applicable to all large,
" j[
water-cooled power reactors.
V. :$
- 3*
Continuing research and engineering studies are expected to lead to
. I) enhancement of the safety of water-cooled reactors in other areas than those mentioned: for example, by determination of the extent of the
?_ 4:I.
generation of hydrogen by radiolysis and from other sources, and
.}
development of meant to control the concentration of hydrogen in the containment, in the unlikely event of a loss-of-coolant accident; by l.. :q iA development of instrumentation for inservice monitoring of the pressure
- j C) vessel and other parts of the primary system for vibration and detection q?!
of loose parts in the system; and by evaluation of the consequences of 3j; water contamination by structural materials and coatings in a loss-of-
};
coolant accident. As solutions to these problers develop and are evaluated
.:n
[t
.*?
a I
- .o L
.9 l.
y
.. e.,
.4,3, ~.-..., m...,w..,.._.c.3.... y..m 3;..,,,, x.... 7
.;..g;,.
3,,;,
r4 Eonorable Glo~nn T. Seabcrg 4
January 2.,
1970
.1 by the RoCulatcry Staff, appropriate action should be taken by the app on a reasonable time scale.
- n.
- 5,
'the 1dvisory Cocnittee on Reactor Safeguards beltsves that, if due regard is given to the items s.antioned above, and subject to satisfactory completion of construction and pre-operational testing, there is reasonable 2200 Wt without undue risk to the haalth and safety of 37,
- p.-
,.g.. ;'.c Sincerely yours, Original Sisnod by
,V J. oseph__L.. Hendrio i,.
' ~ ~.
Josoph M. Hendrie Chairman
,;.~
.e.'
R-.o.. ferencea :
...t 1.
Final Safoty Analysis Report for the Palisades Plant
{' l2 2.
- - (~-
ideents No. 9-19 to license application yY
.t-es s.- -,
3
..lt 94 j.'.j. r 1.? j !'
.*..t
".
- i.L
%;. ;n<
V x..
p';. s.-
. 34 f:
s s
.), 00
-,t.;.,,,
t-
- $..i
- 'ii
- n, '.
,.~,
Si
{g 'i. '.
~4 '
- M..".
g%+
Revised Page
. c i
, ~ *,.. ~ *
- y -+ s, p.>,v o f-r e, r*., t.g s, = e,,= v..s t y,. ?*>,
- *y
.r*
- ~
o.'
~ *
- .y u m,,7
', g if,-.
[p;5;,-
- ff. ',
W".,,. = ;
- a e.r: ex -l c
~
s
. '