ML20037B583
| ML20037B583 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Nine Mile Point, Indian Point, Oyster Creek, Haddam Neck, San Onofre, Yankee Rowe, Humboldt Bay, La Crosse, Big Rock Point  |
| Issue date: | 05/02/1974 |
| From: | Muntzing L US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Nader R AFFILIATION NOT ASSIGNED |
| Shared Package | |
| ML20037B577 | List: |
| References | |
| TASK-05-06, TASK-5-6, TASK-RR NUDOCS 8010210871 | |
| Download: ML20037B583 (6) | |
Text
W " i..'i W{.f M 7pgN.
ATOMIC ENERGY COMMISSION wa.,cion. o.c. :os4s g"ry. ( % ;"
..e
=EL 3.yp v.T::
m:x:.
o v
_ ~_.
- MAY ~
2 1s74 '
=
rs g;
- =
==
Nr.' nclph tiader
- ;:m 171919th Street, N. W.
_.m
=
Washington, D. C. 20009
~.~..~.r
-m
==--s
Dear F.r. Nader:
~ ~ ~
=
As requested in your April 5,1974 letter,. a list of those reactor f.
pressure vessels for light. water power reactors licensed under the Atenic Energy Act which were not designed and constructed to Section 9
III, I;uclear Power Plant Components, of the ASME Boiler and Pressure.
Vessel Code is enclosed.
P,egarding the safety of these older vessels which were not designed and EC=e:=
constructed to Section III, Nuclear Power Plant Components, of the ASME "5
Boiler and Pressure Vessel Code, we have the following. comments.
y
=
Section III was published in the July lgd5 edition of the ASME Boiler s= ~
and Pressure Vessel Code.
The design and fabrication initiation dates for these vessels are prior to the effective date of Section III. and Ine casign and fabrication proceeded on the basis of the existing code requirements at that tice, i.e., Sections I and/or VIII, as appropriate.
E At the time of the construction permit. review of these plants, our-review, as well as that of the ACRS, consisted of a careful consider-atica of the design, design analyses methods, design cargins, materials, fabrication, and quality assurance programs for these pressure vessels
=
described in the applications, and an evaluation to determine that
~
cc:,pliance with these commitments and with the' codes existing at that time gtve reasonable assurance that these vessels would acequately.
%j E
uithstand the design loadings which the vessels may experience over
=R
, I their service lifetime without ioss of structural integrity.
In I addition, during the operating license review of these plants, as is
{ taken p. ace during plant construction, a review of the pertinent-the case for a chan;es in the ASME code requirements was made to deternine that no significant additional requirements had.been developed that would be
( beyond the basic capabilities of these 'ves'sels.
These relatively few water-cooled reactor vessels desicned and fabricated in accordance with Section I anc/or VIII of the ASME Code have perfccc:ed n =i well,'but compared to later reactor vessel designs, they are small and
"="
rela.tively simple, with fewer penetrations and regions of discentinuity, and desigacd for lower power sys:sms.
The nuclear industry, as any viable segment of the economy, un:iergoes change.
As the number, size, 8010210 Q j' o
- i*
', ' ~..
'y E55 4S@
- 5. k. f
.. ~. -
=w
~ I~ '
g=.7=;
9:%
o
- ==55 complexity, and power level of nuclear vessels have increased, sc has
=
-the-techno. logy progressed, advanced methods of design and fabrication EE E have come into acceptance and incorporated into codes and standards, E.Egi and 'the product more knowledgeably tailored to an intended service.
e==~ i
=
These changes in the Code requirements which further reduced _ the already
-g= =
small probability of pressure vessel failure, give added assurance,
-6.3 especially when viewed in the context of increases in number, size, and
=iTE l
power level of nuclear vessels, of mairitaining this small probability.
8 as the population of nuclear power plants increase.
.lDk.
Another aspect of pressure vessel integrity important not only to these
===-7.
early vessels but to all power rea'ctor vessels, concerns the control of the fracture toughness of the vessel-material and the radiation effects -
q;g thereon.
These older vessels (as are all vessels) are under continued r.=. =
3 surveillance by the Regulatory staff.
Strict operational requirements
=?
have been established to limit vessel pressurization to temperatures
==E=E l
well above the_ nil ductility threshold.
The P,egulatory staff and the
=".5"2 reactor operators monitor the actual exposures of these vessels and on
- 7.77l.:
l the basis of this -surveillance we have required, where appropriate,
=;. :...
. ~
changes in operating procedures to maintain adequate margins in fracture toughness.
Our knowledge of radiation effects on vessel materials is continually being refined as the surveillance specimens in operating reactors are examined and tested, and this information is utilized in establishing appropriate requirements to provide added assurance in the J;r;
_.. =
safe operation of these and all nuclear. reactor vessels.
The Regulatory staff believes, with the Co:rmittee, that the probabilit'y '
of a sudden najor pressure vessel failure of these yessels is very icw,
=";;;;
but believes, with the Committee, that continuing attention must be
- lA l
devoted to 'the matter of pressure vessel integrity of all plants both
==,:
operating and proposed.
.i,ncerely,
]
s Q \\.,,r :
Q_L-,
'="
~
f.., .
N E'
}:\\
i L. Manning M htzing ( N
\\
siiC=,
s Director of Regulation s
s*
- =:
Enclosure:
n=
~
As stated 9"4 g
~.I'.7.'
' 7. [.1 1
INN...
W e
...,--....w.i-.
,.w
-,w
! in UL l'i!'
Hi...
Uli m
.m M
^'
- ._ JUl!!!
m x;n 1...
.t -
c.
REACTOR VESSELS DESIGNED TO SECTIONS I AND/0R VIII 0F Tile ASME BOILER AND PRESSURE VESSEL CODE POWER SHELL ESTIMATED TOTAL CAPACITY MW VESSEL THICKNESS - -
g P_L,j].
(THERMAL)
MAlERIAL INCllES IRRADIATION 2
TO DATE (NEUT./CM )
DRESDEN I 700
'A 302 grade B 5 5/8 1.5 x.10
~
l9 Grundy County, Illinois Commonwealth Edison Co.
Docket No. 50-10
~
CP: May 4',
1956
.' 01. : September 28, 1959 YAi!KEE R0WE 540 A 102 grade B 7 7/8 9.6 x 10 I0 Rowe, Massachusetts Yankee Atomic Ele'ctric Co.
Docket No. 50-29 CP:
November 4, 1957 OL:
July 9, 1960 INd$!NPOINT 585 A 212 grade B 6.95 3.3 x 10 18 Westchester, New York Consolidated Edison Docket No.50-003 CP: May 4,.1956 i
OL:
March 26, 1962
}lUMROLDT BAY 240 A 202 grade B.
4 3/4 1.7-x 10I9 Eureka, California
-Pacific Gets and Electric Co.
Occket No. 50-133
-CP:
November 9, 1960 01.:
August '20,1952 e
w
- a
E
.. Hi.
- iu i i!!
!!! i II 1m 1
!.l!!
b c!!!b ii!!hi !!!!!d!!.
IM IION '
t 1
l l
2-9 POWER SHELL ESTIftATED TOTAL-CAPACITY MW VESSEL THICKNESS IRRADIATION PLANT-(TilERMAL)
MATERIAL INCliES TO DATEJil1UT./CH )
2 n
BIG ROCK PQINT bi' Charlevoix CEnty, Michigan 240 A-302 grade B 5.5 1.69 x 10 I9 Consumers Power
. Docket No. 50-155 CP:
May 31, 1960' OL:
August 30, 1962 SAfl Of!0FRE 1 11 210 A 302 grade B 9.75 9 x 10IO j
San Diego County, California Southern California Edison &
San Diego Gas & Electric Co.
Docket No. 50-206
~ CP:
March 2,1964 OL:
March 27,1967 2
18 CONNECTICUT YANKEE 1 473 A 302 grade B 10 5/8 4.5 x 10
- pd!'
liartford, Connecticu.t Connecticut Yankee Atomic Power Co'.
Docket No. 50-213
.CP:
May 26, 1964 OL:
June 30, 1967
~, LACROSSE BWR.
165 A 302~ grade B 4
3 x J0 18-Monroe County, Wisconsin Oairyland Power Corporation Dacket No. 50-409 CP:
March 29, 1963 t
OL:
July 3,1967
,e
i! !
Er n:
y-
!i!!
m ir
,1 mu jo q
i e%;!"
1 h?
'li:t-
"'t.
I!:li!
% n: u
.i t. i;;'::
_ u_,., e, l
~
- f
,c POWER SHELL ESTIMATED TOTAL CAPACITY MW VESSEL THICKNESS IRRADIATION i
2 PLANT (THERMAL)
MATERIAL INCHES TO DATE (NEUT./CM )
i 37 OYSTER CREEK-1600 A 302 grade B '
7 1/8 4 x 10 Barnagat Bay, New Jersey s.
Jersey Central Power & Light
' - - ~ '
Co.
Docket No: 50-219 CP:
December 15, 1964 OL: -April 9, 1969 i
16
~
'NINC' MILE POINT - 1 1538 A 302 grade B 7 1/8 4 x 10 Oswego County, New York Niagra Mohawk Power Corporation Docket No: 5 0-220 CP:
April 12, 1965 OL:
August'22, 1969 e
.s!
e
. k.
J O
4
'g 3
1 g,
=
'bec: ' Attached L'isV
\\=
=f,_.
Consumers Power Company 5" 5T
$..T Consolidated. Edison Company p _3 of New York, Inc.
ATTN: Mr. Ralph B. Sewell ATTN:
Mr. William J. Cahill, Jr.
Nuclear Licensing Administrator
.==
Vice President
'212 West Michigan Avenue s.-es 4 Irving Place Jackson, Michigan 49201
=m:;.
Niagara Mohawk Power Corporation Dairyland Power Cooperative s b ro9
==
ATTN: Mr. Philip D. Raymond ATTN; Mr. John P. Madgett
-~P Vice President - Engineering General Manager
= = _..
300 Erie Boulevard West 2615 East Avenue, South p
Syracuse, New York 13202 La Crosse, Wisconsin 54601
]
3,22, i
Jersey Central Power & Light Company
=:;;;-
ATTN: Mr. E. R. Finfrock, Jr.
Vice President - Generation
- 9) " ' 1 t;zy i
Madison Avenue at Punch Bowl Road
=
Morristown, New Jersey 07960 i
Connecticut Yankee Atomic Power Comapany h-2/3
'.=f.~
l AITN; Mr. D. C. Switzer i
President
= =5f
=
P. O. Box 270
=
Hartford, Connecticut 06101 l
l Yankee Atcaic Electric Company ATTN:
G. Carl Andognini, Assistant to the i
Vice President
=:
20 Turnpike Road Westboro, Massachusetts 01581
=
l Sdthern California Edison Co.
i ATTN:
Mr. Jack B. Moore
=+
C j
Vice PresMent 2244 Walnut Grove Avenue
=
i-P. O. Box 800 l
Rosemead, California 91770
)
Comonwealth Edison Company s-, -/o ATTN:
Mr. J. S. Abel i
Nuclear Licensing Administrator Boiling Water Reactors P. O. Box 767 Chicago, Illinois 60690
.-me.1 Pacific Gas & Electric Company go- / 3 3 73 ATTN: Mr. Fredrick T. Searls Vice President and
~~
General Counsel g.:.=I l
77 Beale Street
-. =:
San francisco, California 94106 l
~
m