[Federal Register Volume 64, Number 145 (Thursday, July 29, 1999)]
[Proposed Rules]
[Pages 41050-41054]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 99-19130]
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NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
RIN 3150-AG19
List of Approved Spent Fuel Storage Casks; Revision, NUHOMS 24-P
and NUHOMS 52-B
AGENCY: Nuclear Regulatory Commission.
ACTION: Proposed rule.
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SUMMARY: The Nuclear Regulatory Commission (NRC) is proposing to amend
its regulations containing the list
[[Page 41051]]
of approved spent fuel storage cask designs to add an amended version
of Certificate of Compliance Number (CoC No.) 1004 to this list. The
amended version reflects a change of ownership of this certificate from
VECTRA Technologies, Inc. to Transnuclear West, Inc., (TN West) as well
as an amendment to the certificate. This rulemaking also implements a
Director's Decision, in response to a petition filed by the Toledo
Coalition for Safe Energy, et al., regarding the cask design, approved
by CoC No. 1004, in which the Director determined that a rulemaking
should be conducted to require a fabrication inspection of dry shielded
canister (DSC) shell welds.
DATES: The comment period expires October 12, 1999. Comments received
after this date will be considered if it is practical to do so, but the
NRC is able to assure consideration only for comments received on or
before this date.
ADDRESSES: Comments may be sent to: Secretary, U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001, Attn: Rulemakings and
Adjudications Staff. Hand deliver comments to 11555 Rockville Pike,
Rockville, MD 20852-2738, between 7:30 a.m. and 4:15 p.m. on Federal
workdays.
You may also provide comments via the NRC's interactive rulemaking
web site through the NRC's home page (http://www.nrc.gov). This site
provides the availability to upload comments as files (any format) if
your web browser supports that function. For information about the
interactive rulemaking site, contact Ms. Carol Gallagher, (301) 415-
5905; e-mail [email protected].
Certain documents related to this rulemaking, including comments
received by the NRC, may be examined at the NRC Public Document Room,
2120 L Street NW. (Lower Level), Washington, DC 20003-1527. These same
documents also may be viewed and downloaded electronically via the
interactive rulemaking website established by NRC for this rulemaking.
FOR FURTHER INFORMATION CONTACT: Stan Turel, telephone (301) 415-6234,
e-mail, [email protected] of the Office of Nuclear Material Safety and
Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001.
SUPPLEMENTARY INFORMATION:
Background
Section 218(a) of the Nuclear Waste Policy Act of 1982, as amended
(NWPA), requires, ``. . . for the dry storage of spent nuclear fuel at
civilian nuclear power reactor sites, with the objective of
establishing one or more technologies that the [Nuclear Regulatory]
Commission may, by rule, approve for use at the sites of civilian
nuclear power reactors without, to the maximum extent practicable, the
need for additional site-specific approvals by the Commission.''
Section 133 of the NWPA states, in part, that ``[t]he Commission shall,
by rule, establish procedures for the licensing of any technology
approved by the Commission under Section 218(a) for use at the site of
any civilian nuclear power reactor.''
To implement this mandate, the NRC approved dry storage of spent
nuclear fuel in NRC-approved casks under a general license by
publishing a final rule in 10 CFR Part 72 entitled, ``General License
for Storage of Spent Fuel at Power Reactor Sites'' (55 FR 29181; July
18, 1990). This rule also established a new Subpart L within Part 72,
entitled ``Approval of Spent Fuel Storage Casks,'' that contains
procedures and criteria for obtaining NRC approval of dry storage cask
designs.
The NRC subsequently issued a final rule to amend Part 72 by adding
to the list of approved spent fuel storage cask designs CoC No. 1004 to
VECTRA Technologies, Inc., of San Jose, California, for the
standardized NUHOMS-24P and NUHOMS-52B spent fuel storage cask designs
(59 FR 65898; December 22, 1994). The NUHOMS design consists of a
sealed, dry shielded canister (DSC), which contains the spent fuel
assemblies. A loaded DSC is stored inside a ventilated, horizontal,
concrete vault (i.e., storage module).
The Petition
The Toledo Coalition for Safe Energy, et al., filed a petition with
the NRC on December 5, 1995, pursuant to 10 CFR 2.206. The petitioners
raised concerns on the safety of the NUHOMS-24P spent fuel storage cask
design regarding a reduction in the thickness of the welds in the walls
of three DSCs fabricated for use at the Davis-Besse nuclear power
plant. In addition, the petitioners questioned the NRC's administrative
process by which VECTRA was permitted to deliver the DSCs containing
wall thinning to the Davis-Besse facility and by which the licensee for
Davis Besse was permitted to use these casks. The petitioners claimed
that an NRC rulemaking or some other public proceeding was necessary to
grant permission for the transfer and use of these spent fuel storage
casks.
The Petition was referred to the Director of the NRC's Office of
Nuclear Material Safety and Safeguards (NMSS) for action under the
NRC's regulations in 10 CFR 2.206. On February 5, 1997, the Director of
NMSS issued Director's Decision 97-03 (DD-97-03) that granted the
Petition, in part. The decision found that the minimum wall thickness
measured by VECTRA in the three DSCs was 0.581 inch, less than the
original design wall thickness of 0.625 inch specified in the Safety
Analysis Report (SAR). VECTRA performed calculations demonstrating that
a DSC with a 0.500 inch uniform minimum wall thickness still met the
American Society of Mechanical Engineers, Boiler and Pressure Vessel
Code (ASME Code), allowable stress values and satisfied the NRC's
design criteria. VECTRA submitted these calculations in a letter dated
September 5, 1995. In a Safety Evaluation (SE), dated October 5, 1995,
the NRC accepted VECTRA's wall thickness calculation as meeting the
ASME Code allowable stress values. However, the NRC indicated that
because of the limited experience in performing weld thickness
measurements, it was reasonable for VECTRA to establish a fabrication
margin of 0.063 inch above the 0.500 inch minimum design wall
thickness. The decision stated, in part, ``while VECTRA failed to
comply with its SAR commitment of 0.625 inch, its failure resulted in
no compromise of safety. Nonetheless, the failure raised an issue of
poor control during the fabrication process.'' The decision also found
that existing NUHOMS-24P casks remained acceptable for continued use.
The decision further found that VECTRA had no procedure to measure the
final wall thickness in the area of the welds, after grinding or in any
subsequent steps in the fabrication process, which would provide an
adequate level of control in maintaining minimum acceptable wall
thickness. VECTRA failed to comply with the NRC's requirement under
Sec. 72.150 to have procedures that include appropriate qualitative and
quantitative acceptance criteria for determining that important
activities have been satisfactorily accomplished. The decision
indicated that CoC No. 1004 should be modified to require a fabrication
inspection procedure to assure that DSC weld-grinding operations do not
result in wall thinning below acceptable levels. Accordingly, the
petitioners' request was granted, in part. The decision is available
for review in the NRC Public Document Room as ``Director's Decision
Under 10 CFR 2.206, DD # 97-03.''
Discussion
The NRC is proposing to revise information contained in Sec. 72.214
under
[[Page 41052]]
CoC No. 1004 to reflect Amendment No. 1 to CoC No. 1004 and to address
four administrative issues in the current language in Sec. 72.214.
These four administrative issues include (1) correcting the expiration
date of CoC No. 1004 from the present ``(20 years after the final rule
effective date)'' to ``January 23, 2015;'' (2) correcting the title and
revision number of the standardized NUHOMS SAR to be consistent with
the approach the NRC proposed for CoC SARs in a new Sec. 72.248 (see
proposed rule in 63 FR 56098; October 21, 1998); (3) revising the CoC
to reflect the transfer of the CoC from VECTRA Technologies, Inc. to
Transnuclear West, Inc., (TN West); and (4) specifying the
applicability of Amendment No. 0 and Amendment No. 1 to this CoC.
Change 1 keeps the certificate expiration date consistent with the
NRC's policy for Part 72 CoCs, which is to use 20 years from the date
the final rule is effective. The final rule adding CoC No. 1004 to
Sec. 72.214 was effective on January 23, 1995; consequently, the
expiration date for this CoC is January 23, 2015.
Change 2 keeps CoC No. 1004 consistent with other proposed changes
to Part 72. The SAR Title will be changed from ``Safety Analysis Report
for the Standardized NUHOMS Horizontal Modular Storage System for
Irradiated Nuclear Fuel, Revision 2'' to ``Final Safety Analysis Report
for the Standardized NUHOMS Horizontal Modular Storage System for
Irradiated Nuclear Fuel.'' In the new Sec. 72.248, a final SAR is to be
submitted to the Commission within 90 days after approval of the cask
design and then will be updated periodically. Replacement pages will be
provided to the Commission, but FSAR revision numbers will not be used.
Change 3 recognizes the transfer of the CoC from VECTRA to TN West,
NRC received letters dated December 18, 1997, from both VECTRA and TN
West describing the purchase of VECTRA's intellectual properties and
assets associated with NUHOMS technology by TN West. In its December
18, 1997, letter, TN West described that it planned to conduct
fabrication activities in accordance with the quality assurance program
described in Section 11 of the NUHOMS SAR. TN West further described
that it had acquired the composite records of casks manufactured under
CoC No. 1004 and that it had records associated with changes to the
NUHOMS design implemented after issuance of the CoC.
Change 4 describes how general licensees would continue to use
spent fuel storage casks manufactured under CoC No. 1004, Amendment No.
0 (i.e., the initial CoC), if the cask being used was fabricated before
[insert effective date of the final rule]. After [insert effective date
of the final rule], casks must be manufactured in accordance with CoC
No. 1004, Amendment No. 1.
This proposed rule would issue Amendment No. 1 to CoC No. 1004.
Amendment No. 1 would revise and reformat the CoC to be consistent with
the NRC's current format and layout for Part 72 certificates.
Conditions No. 1 through 8 would be renumbered and Condition No. 9
would remain the same. Additionally, Condition No. 4 (previously
Condition No. 6) would be revised to implement DD-97-03. Because the
Director granted the Petition, in part, and to ensure future compliance
with Sec. 72.150 with respect to DSC shell-weld thickness, the revised
Condition No. 4 to CoC No.1004 would require inspection of DSC shell
welds and specify a minimum shell-weld thickness. Condition No. 4 would
be revised to read as follows:
Fabrication activities shall be conducted in accordance with a
quality assurance program as described in Section 11.0 of the SAR.
All fabrication acceptance tests and procedures shall be performed
in accordance with detailed written procedures. TN West shall ensure
that 100 percent of the full penetration longitudinal and
circumferential butt welds used for the DSC shell are inspected
using radiographic examination. Inspections shall be performed on
each shell weld after the weld is ground flush with surrounding
surfaces, and the weld and the base metal wall thickness shall be
greater than or equal to 0.500 inch.
VECTRA's analysis indicated that a wall design of 0.500 inch would
satisfy NRC design criteria. In a letter dated August 7, 1995, VECTRA
described plans to perform measurements of shell-weld thickness during
the DSC fabrication process. By letter dated September 5, 1995 (NRC
document Accession Number 9509110095), VECTRA submitted an analysis,
NUH004.0213, ``Standardized NUHOMS-24P DSC Shell Minimum Acceptable
Uniform Thickness,'' Revision 1, which evaluated the structural
acceptability of a standardized NUHOMS-24P DSC with a minimum shell
thickness of 0.500 inch. 1 In a Safety Evaluation (SE) dated
October 5, 1995, (Accession Number 9512200130) the NRC staff concluded
that the structural capability of the DSC would not be compromised with
a shell-weld thickness of 0.500 inch. In a letter dated December 11,
1998 (Accession Number 9812300347), VECTRA [TN West] submitted an
analysis, NUH004.0218, ``Standardized NUHOMS-52B DSC Shell Minimum
Acceptable Uniform Thickness,'' Revision 1, that evaluated the
structural acceptability of a standardized NUHOMS-52B DSC with a
minimum shell thickness of 0.500 inch. In a safety evaluation dated
January 22, 1999 (Accession Number 9902110261), the NRC staff concluded
that with a wall thickness of 0.500 inch, the NUHOMS-52B DSC can
acceptably meet structural design codes.
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\1\ The Standardized NUHOMS system includes two versions: the
NUHOMS-24P which stores up to 24 pressurized-water reactor
assemblies and the NUHOMS-52B which stores up to 52 boiling-water
reactor assemblies. The staff examined minimum weld thickness issues
for the NUHOMS-24P in a safety evaluation dated October 5, 1995. For
completeness, the staff examined minimum weld thickness issues for
the NUHOMS-52B in a safety evaluation dated January 22, 1999.
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The Director, in his Decision, specifically proposed amending CoC
No. 1004 to require that, in the fabrication of the DSC, the shell and
basket assembly must be inspected to ensure that structural design
margins, associated with the ASME Code Section III allowable stress
values, are not compromised. VECTRA established fabrication inspection
procedures, including fabrication margins to ensure that the DSC shell
welds are not reduced to a thickness less than 0.500 inch. VECTRA
established an ``administrative'' minimum fabrication limit of 0.563
inch. This limit would allow for uncertainties in weld thickness
measurements, weld shrinkage, and weld grinding operations and would
ensure that the weld and base metal are not reduced less than the
analyzed wall thickness of 0.500 Inch. Because the safety evaluation
supporting the Director's Decision relied on a 0.500 inch weld
thickness, proposed Amendment No 1 to CoC No. 1004 requiring a 0.500
inch weld thickness is consistent with DD-97-03.
Based on the October 1995 and January 1999 safety evaluations, the
newly established fabrication inspection procedures, and the proposed
Amendment No. 1 to CoC No. 1004, the NRC staff has concluded that the
NUHOMS-24P and -52B cask design when used in accordance with the
conditions specified in the CoC as amended, and NRC regulations, will
meet the requirements of Part 72 and thus ensure adequate protection of
the public health and safety. Furthermore, as indicated in DD-97-03,
NUHOMS-24P casks previously manufactured before DD-97-03 was issued
will continue to adequately protect public health and safety.
The proposed Amendment No. 1 to CoC No. 1004, the VECTRA safety
[[Page 41053]]
analyses, and the NRC staff safety evaluations are available for
inspection and comment at the NRC Public Document Room, 2120 L Street,
NW. (Lower Level), Washington, DC 20003-1527. Single copies of the
proposed Amendment No. 1 to CoC No. 1004 may be obtained from Stan
Turel, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, telephone (301) 415-
6234, email [email protected].
Discussion of Proposed Amendments by Section
Section 72.214 List of Approved Spent Fuel Storage Casks
The text in Sec. 72.214 for Certificate No. 1004 would be revised
as follows:
(1) The name of person that submitted the SAR (i.e., name of the
certificate holder) would be changed to ``Transnuclear West, Inc.'';
(2) The title of the SAR would be changed to ``Final Safety
Analysis Report for the Standardized NUHOMS Horizontal Modular Storage
System for Irradiated Nuclear Fuel'';
(3) The expiration date for the certificate would be changed to
``January 23, 2015''; and
(4) A new line on the applicability of Amendment No. 0 and
Amendment No. 1 would be added.
In addition to the changes to the rule language in Sec. 72.214, the
text for Condition No. 4 of CoC No. 1004 would be revised as described
above.
Applicability
Amendment No. 1 to CoC No. 1004 would apply to TN West's
manufacture of NUHOMS-24P or -52B DSCs, or to a general licensee using
the NUHOMS-24P or -52B cask system, where the manufacture of the DSC
was completed after [insert effective date of the final rule]. General
licensees who possess a NUHOMS-24P or -52B DSC, whose fabrication was
completed before [insert effective date of the final rule], would
continue to use the original version [Amendment No. 0] of CoC No. 1004
in implementing the requirements of Sec. 72.212 for the operation of an
independent spent fuel storage installation.
Finding of No Significant Environmental Impact: Availability
Under the National Environmental Policy Act of 1969, as amended,
and the NRC regulations in Subpart A of 10 CFR Part 51, the NRC has
determined that this rule, if adopted, would not be a major Federal
action significantly affecting the quality of the human environment
and, therefore, an environmental impact statement is not required. It
would not change safety requirements and would not have significant
environmental impacts. The proposed rule would revise the listing of
approved spent fuel storage casks contained in Sec. 72.214 by
correcting certain information listed under this certificate and by
issuing Amendment No. 1 which revises Condition No. 4 to CoC No. 1004
for the Standardized NUHOMS-24P and -52B cask system. The NRC has
concluded that Standardized NUHOMS-24P and -52B cask system designs, as
modified by Amendment No. 1 to the CoC, can continue to be used to
safely store spent fuel. The environmental assessment and finding of no
significant impact on which this determination is based are available
for inspection at the NRC Public Document Room, 2120 L Street NW.
(Lower Level), Washington, DC. Single copies of the environmental
assessment and finding of no significant impact are available from Stan
Turel, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, telephone (301) 415-
6234, email [email protected].
Paperwork Reduction Act Statement
This proposed rule does not contain a new or amended information
collection requirement subject to the Paperwork Reduction Act of 1995
(44 U.S.C. 3501 et seq.). Existing requirements were approved by the
Office of Management and Budget, approval number 3150-0132.
Public Protection Notification
If a means used to impose an information collection does not
display a currently valid OMB control number, the NRC may not conduct
or sponsor, and a person is not required to respond to, the information
collection.
Voluntary Consensus Standards
The National Technology Transfer Act of 1995, (Pub. L. 104-113),
requires that Federal agencies use technical standards that are
developed or adopted by voluntary consensus standards bodies unless the
use of such a standard is inconsistent with applicable law or otherwise
impractical. In this proposed rule, the NRC would issue Amendment No. 1
to CoC No. 1004 for the NUHOMS-24P and -52B cask system, which is
currently listed in Sec. 72.214. This action does not constitute the
establishment of a standard that establishes generally-applicable
requirements.
Plain Language
The Presidential Memorandum dated June 1, 1998, entitled, ``Plain
Language in Government Writing,'' directed that the Government's
writing be in plain language. The NRC requests comments on this
proposed rule specifically with respect to the clarity and
effectiveness of the language used. Comments should be sent to the
address listed under the heading ADDRESSES above.
Regulatory Analysis
On July 18, 1990 (55 FR 29181), the Commission amended 10 CFR Part
72 to provide regulations for the storage of spent nuclear fuel under a
general license in cask designs approved by the NRC. Any civilian
nuclear power reactor licensed under 10 CFR Part 50 was issued a
general license under Part 72 to use NRC-approved cask designs to store
spent nuclear fuel if: (1) They notify the NRC in advance, (2) the
spent fuel is stored under the conditions specified in the CoC, and (3)
the conditions of the general license are met. In that rulemaking, four
spent fuel storage cask designs were approved for use at reactor sites,
and were listed in Sec. 72.214. That rulemaking envisioned that storage
cask designs approved in the future would be added to the listing in
Sec. 72.214 through the rulemaking process. Procedures and criteria for
obtaining NRC approval of new spent fuel storage cask designs were
provided in Part 72, Subpart L. The NRC subsequently amended Part 72
and authorized issuance of CoC No. 1004 to VECTRA Technologies, Inc.,
of San Jose, California, for the standardized NUHOMS-24P and -52B spent
fuel storage cask designs (59 FR 65898; December 22, 1994).
This proposed rule would issue Amendment No. 1 to CoC No. 1004.
Amendment No. 1 would revise and reformat the CoC to be consistent with
the NRC's current format and layout for Part 72 certificates.
Conditions No. 1 through 8 would be renumbered and Condition No. 9
would remain the same. Additionally, Condition No. 4 (previously
Condition No. 6) would be revised to implement the direction of DD-97-
03. The NRC has deemed necessary the changes to CoC No. 1004 to ensure
compliance with Part 72 quality assurance requirements. On August 29,
1995, the NRC issued an enforcement action in the form of a Notice of
Nonconformance to VECTRA regarding VECTRA's failure to comply with the
quality assurance regulations in Sec. 72.150. Specifically, VECTRA
failed to ensure that adequate wall thickness was maintained in DSCs
manufactured
[[Page 41054]]
under CoC No. 1004. Subsequently, the Director, NMSS, in response to a
petition from the Toledo Coalition for Safe Energy, et al. found, in
Director's Decision 97-03, that an inspection procedure requiring the
performance of minimum wall thickness measurements would be reasonable
and directed that CoC No. 1004 be amended to include such a
requirement. Consequently, the NRC considers this rule, in part, to be
an administrative action taken to implement DD-97-03.
General licensees would continue to use spent fuel storage casks
manufactured under CoC No. 1004, Amendment No. 0, if the cask was
fabricated before [insert effective date of the final rule]. After
[insert effective date of the final rule], casks must be manufactured
in accordance with CoC No. 1004, Amendment No. 1.
The alternative to this proposed action would be to allow outdated
information to remain in CoC No. 1004 and to withhold Amendment No. 1
to CoC No. 1004 and forgo inclusion of an explicit requirement for
measuring DSC shell-weld thickness. However, based on the concerns
identified with VECTRA's control of the fabrication process described
in the Notice of Nonconformance, the NRC deemed that addition of an
explicit requirement for measuring wall thickness in CoC No. 1004 is
necessary.
Approval of the proposed rule would provide both the NRC staff and
the public additional assurance that DSCs manufactured under CoC No.
1004 are fabricated in accordance with the approved design and Part 72
quality assurance requirements, and would have no adverse effect on
public health and safety.
This proposed rule has no significant identifiable impact or
benefit on other Government agencies. Based on the above discussion of
the benefits and impacts of the alternatives, the NRC concludes that
the requirements of the proposed rule are commensurate with the NRC's
responsibilities for public health and safety and the common defense
and security. No other available alternative is believed to be
satisfactory, and thus, this action is recommended.
Regulatory Flexibility Certification
In accordance with the Regulatory Flexibility Act of 1980, (5
U.S.C. 605(b)), the NRC certifies that this rule will not, if
promulgated, have a significant economic impact on a substantial number
of small entities. This proposed rule affects only the operation of
nuclear power plants, independent spent fuel storage facilities, and
Transnuclear West, Inc. The companies that own these plants do not fall
within the scope of the definition of ``small entities'' set forth in
the Regulatory Flexibility Act or the Small Business Size Standards set
out in regulations issued by the Small Business Administration at 13
CFR Part 121.
Backfit Analysis
The backfit rule (Secs. 50.109 or 72.62) does not apply to
certificate holders. Moreover, this proposed rule does not involve any
provisions that would impose backfits as defined in those regulations
because the amended version of CoC No. 1004 is applicable only to casks
to be fabricated after the effective date of the final rule. General
licensees who currently possess these casks may operate under the
original CoC No. 1004 (Amendment No. 0) which remains on the list of
approved cask designs at Sec. 72.214. Therefore, a backfit analysis is
not required.
List of Subjects In 10 CFR Part 72
Criminal penalties, Manpower training programs, Nuclear materials,
Occupational safety and health, Reporting and recordkeeping
requirements, Security measures, Spent fuel.
For the reasons set out in the preamble and under the authority of
the Atomic Energy Act of 1954, as amended; the Energy Reorganization
Act of 1974, as amended; and 5 U.S.C. 553; the NRC is proposing to
adopt the following amendments to 10 CFR Part 72.
PART 72--LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF
SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE
1. The authority citation for Part 72 continues to read as follows:
Authority: Secs. 51, 53, 57, 62, 63, 65, 69, 81, 161, 182, 183,
184, 186, 187, 189, 68 Stat. 929, 930, 932, 933, 934, 935, 948, 953,
954, 955, as amended, sec. 234, 83 Stat. 444, as amended (42 U.S.C.
2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2232, 2233,
2234, 2236, 2237, 2238, 2282); sec. 274, Pub. L. 86-373, 73 Stat.
688, as amended (42 U.S.C. 2021); sec. 201, as amended, 202, 206, 88
Stat. 1242, as amended, 1244, 1246 (42 U.S.C. 5841, 5842, 5846);
Pub. L. 95-601, sec. 10, 92 Stat. 2951 as amended by Pub. L. 10d-
48b, sec. 7902, 10b Stat. 31b3 (42 U.S.C. 5851); sec. 102, Pub. L.
91-190, 83 Stat. 853 (42 U.S.C. 4332); secs. 131, 132, 133, 135,
137, 141, Pub. L. 97-425, 96 Stat. 2229, 2230, 2232, 2241, sec. 148,
Pub. L. 100-203, 101 Stat. 1330-235 (42 U.S.C. 10151, 10152, 10153,
10155, 10157, 10161, 10168).
Section 72.44(g) also issued under secs. 142(b) and 148(c), (d),
Pub. L. 100-203, 101 Stat. 1330-232, 1330-236 (42 U.S.C. 10162(b),
10168(c),(d)). Section 72.46 also issued under sec. 189, 68 Stat.
955 (42 U.S.C. 2239); sec. 134, Pub. L. 97-425, 96 Stat. 2230 (42
U.S.C. 10154). Section 72.96(d) also issued under sec. 145(g), Pub.
L. 100-203, 101 Stat. 1330-235 (42 U.S.C. 10165(g)). Subpart J also
issued under secs. 2(2), 2(15), 2(19), 117(a), 141(h), Pub. L. 97-
425, 96 Stat. 2202, 2203, 2204, 2222, 2244, (42 U.S.C. 10101,
10137(a), 10161(h)). Subparts K and L are also issued under sec.
133, 98 Stat. 2230 (42 U.S.C. 10153) and sec. 218(a), 96 Stat. 2252
(42 U.S.C. 10198).
2. Section 72.214, Certificate of Compliance Number 1004, is
revised to read as follows:
Sec. 72.214 List of approved spent fuel storage casks.
* * * * *
Certificate Number: 1004
Amendment Number: 0 and 1
Amendment Applicability:
Amendment No. 0 is applicable for casks manufactured before
[insert effective date of final rule].
Amendment No. 1 is applicable for casks manufactured after
[insert effective date of final rule].
SAR Submitted by: Transnuclear West, Inc.
SAR Title: Final Safety Analysis Report for the Standardized NUHOMS
Horizontal Modular Storage System for Irradiated Nuclear Fuel
Docket Number: 72-1004
Certificate Expiration Date: January 23, 2015
Model Numbers: Standardized NUHOMS-24P and NUHOMS-52B
* * * * *
Dated at Rockville, Maryland, this 7th day of July, 1999.
For the Nuclear Regulatory Commission.
William D. Travers,
Executive Director for Operations.
[FR Doc. 99-19130 Filed 7-28-99; 8:45 am]
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