Clarification of the Recent Revisions to the Regulatory Requirements for Packaging of Uranium Hexafluoride (UF6) for TransportationML031210564 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, 05000370 |
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Issue date: |
04/30/1990 |
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From: |
Teneyck E Office of Nuclear Material Safety and Safeguards |
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To: |
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References |
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IN-90-027, NUDOCS 9004240313 |
Download: ML031210564 (13) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, 05000370 |
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Category:NRC Information Notice
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:05000370]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:05000370]] </code>. |
--'-UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR MATERIALS
SAFETY AND SAFEGUARDS
WASHINGTON, D.C. 20555 April 30, 1990 NRC INFORMATION
NOTICE NO. 90-27: CLARIFICATION
OF THE RECENT REVISIONS
TO THE REGULATORY
REQUIREMENTS
FOR PACKAGING
OF URANIUM HEXAFLUORIDE (UF 6) FOR TRANSPORTATION
Addressees
All Uranium Fuel Fabrication
and Conversion
Facilities.
Purpose
- This notice Is being issued to review and clarify the significant
features of two recent rulemaking
actions which were completed
by the U.S. Department
of Transportation (DOT), relating to the regulatory
requirements
for the packaging of UF for transportation.
It is suggested
that recipients
review the infor-matiog here, and consider actions, if appropriate, to preclude possible problems in the transport
of UF .However, this information
does not constitute
new U.S.Nuclear Regulatory
C;Amission (NRC) requirements, therefore
no specific action or written response Is required.Background:
The routine transportation
of UF,, both as a non-fissile
radioactive
material (depleted
and natural uranium, a "low specific activity" [LSA) material)
and as a fissile radioactive
material (when containing
'greater than" 1.0 weight percent U-235), constitutes
a very significant
volume of radioactive
materials transportation
in the nuclear fuel cycle, both within the USA and worldwide.
UF is packaged for transport
in cylinders
which must meet certain inspection, testing and in-service
requirements
which are found in the 49 CFR DOT regu-lations and certain physical standards
which are adopted by reference
in those regulations.
The primary type of packaging
used are cylinders
of steel, nickel, or monel in various diameters
ranging from 1 inch to 48 inches.For shipments
of the unenriched
UF6 as an LSA, non-fissile
radioactive
material, the cylinders
are normally shipped bare, without protective
overpacks.
Over-packs are used, however, for the shipment of enriched UF , as a fissile material, when the U-235 content exceeds 1.0 weight percent. The overpacks
used are either of the DOT Specifications
2OPF or 21PF Series as prescribed
in 49 CFR 178.120 and 178.121 of DOT regulations, or as authorized
in several NRC Certificates
of Compliance. (See Attachment
1.) Most shipments
of UF are made in exclusive- use highway or rail vehicles, and in equivalent
defined stowage areas or inter-modal freight containers
aboard seagoing vessels.9004240313
.
IN 90-27 April 30, 1990 Before November 1986, the DOT regulations
were not specific on the standards for the cylinders, but rather, referenced
the need to use a "strong tight package" for exclusive-use
shipments.
For non-exclusive-use
shipments, the cylinders
were required to meet the requirements
for DOT Specification
7A, Type A packaging.
[The cylinders
actually used, however, were in accordance
with industry standards
that exist in ANSI N14.1 and/or a Department
of Energy (DOE) document, ORO-651].
On November 17, 1986, DOT issued a new regulation
49 CFR 173.420) specifying
cylinder standards
and other requirements
for all shipments
of UF Several supplemental
notices and amendments
were subsequently
issued in the Docket HM-166V, with the last revision of the final rule having been issued on August 29, 1989.As for the protective
overpacks
for the cylinders, DOT originally
issued its regulatory
specifications
for the DOT Specifications
2OPF and 21PF series in 1974. Over the years, during the use of these overpacks, increasing
diffi-culties have been experienced
in their use, maintenance
and quality control.The primary difficulty
has been with the tendency of the packagings
to collect and retain water within the phenolic foam insulating
medium within the walls of the overpack.
Although the presence of this water is not an immediate safety problem, the water does increase the gross weight of the packages significantly, and also accelerates
corrosion
of the metal and rotting of the wood components
of the overpacks.
It often tends to 'slosh' out from the drain holes, and sometimes
creates considerable
alarm to the public and to carriers, when water (albeit non-radioactive
water) is observed to be leaking from a package marked "RADIOACTIVE" in commerce.
Accordingly, DOE petitioned
DOT for rulemaking
to amend the DOT 21PF series protective
overpack specification, so as to authorize
the use of an improved design that would correct the deficiencies.
A notice of proposed rulemaking
was issued in August 1984, with the final rule issued on September
20, 1988 (Docket HM-190).During the interim period, between the notice and final rule, several NRC-licensee shippers of UF in protective
overpacks
applied for and received NRC certificates
of compliance
authorizing
use of non-DOT specification, improved overpacks.
Discussion:
Attachments
2 and 3 are chronological
summaries
of the two recently completed DOT rulemaking
dockets relating to UF packaging
and transportation.
Attach-ment 2 summarizes
the Docket HM-166V 9n cylinder requirements, and Attachment
3 summarizes
the Docket HM-190 rule changes on the DOT Specification
21PF series of protective
overpacks.
Attachment
1 is a summary of the present status of several NRC certificates
of compliance
for overpacks
that are similar to the DOT Specification
21PF overpacks.
Discussion
of each of these areas follows: CYLINDERS The net effect of the cylinder rulemaking
imposed by the new 49 CFR 173.420 in Docket HM-166V has been to formalize, as regulatory
requirements, the use of cylinders
which have already been in use for many years, pursuant to certain industry standards, as well as other requirements (e.g., requirements
for UF 6 IN 90-27 April 30, 1990 to be In solid fiorm and specified
vl inetric fill liipits). .In carrying out te ru ema ng, owever, severa dY culties were Observed te.g., he method of cleaning for other than new cylinders, provisions
for use of existing cylinders, etc.), as evidenced
by the series of eight notices and amendments
between April 1986 and April 1989. It is noted that the final rule also formalizes
the use of the DOT Class 106A multiunit
tank car tank (which is actually referred to in the industry as the Model 30A cylinder).
However, both of the published
industry standards
-- ANSI N14.1-1987 and ORO-651, Rev. 5 -- have taken the position that the Model 30A cylinder is obsolete, and will be replaced by the Model 30B. In effect, therefore, DOE has stated that it will no longer fill Model 30A cylinders
at its gaseous diffusion facilities
after December 31, 1992.For any existing cylinder constructed
before the new rules, continued
use is authorized, provided that it was designed, inspected, tested, and marked in accordance
with the 1987, 1982 or 1971 version of ANSI N14.1, in effect at the time of construction;
or for cylinders
manufactured
before June 30, 1987,Section III, Div. I of the ASME Code.PROTECTIVE
OVERPACKS The net result of the rulemaking
in Docket HM-190 has been to upgrade the regulatory
requirements
for the fabrication, maintenance, and use of the DOT Specification
21PF-1 protective
overpacks.
The key dates for compliance
with these new rules are: April 1, 1989--Construction
of all new overpacks
must be in accordance
with DOT Specification
21PF-1B afte'rthis
date, and these overpacks
marked as such; and April 1, 1991--Refurbishment
and conversion
of all existing overpacks
to the requirements
of DOT Specification
21PF-1A must be accomplished
and these overpacks
marked as such.During the period between April 1, 1989 and April 1, 1991, therefore, the use of unmodified
DOT Specification
21PF-1 overpacks
continues
to be authorized.
However, both the owners of unmodified
overpacks
and the U.S. enrichment
plants which fill the cylinders
for subsequent
loading into the overpacks
are taking steps to perform quality control inspections
of the overpacks
to correct defi-ciencies, such as containing
excessive
water. (See Attachment
4). If such inspections
reveal excessive
water, measures are being taken to remove the overpack from service for drying, resealing, gasket replacement, or other necessary
refurbishment, or if necessary, for disposal.
The U.S. enrichment
plants are also requesting
the owners of unmodified
overpacks
to supply them with acceptance
certifications
stating that the quality control inspections
and other maintenance
procedures
have been accomplished.
IN 90-27 April 30, 1990 r NRC CERTIFICATES
OF COMPLIANCE
During the period of the Docket HM-190 rulemaking, several U.S. owners of pro-tective overpacks
for 30" cylinders
obtained certificates
of compliance
from the NRC to authorize
the use of overpacks
of improved design. These are sum-marized in Attachment
1. A comparison
of the specifics
of the DOT Specification
21PF-1A and 18 requirements
with these certificates
indicates
that there will islTTTremain
a need for the certificates, in that there are substantial
dif-Terences between, for example, the Model UX-30 (USA/9234/AF)
and the NCI-21-PF-1 JUSA/9196/AF)
and the DOT specifications.
Eli a eth Q. Eyck, Actng Director Di f-ion of Safeguards
and Transportation
Office of Nuclear Material Safety and Safeguards
Technical
Contact: A. W. Grella, NMSS (301) 492-3381 Attachments:
1. NRC Certificates
of Compliance
for UF 6 Overpacks 2. Chronology
of UF 6 Cylinder Rulemaking (HM-166V)3. Chronology
of UF Overpack Rulemaking (HM-190)4. "Interim Inspection
and Sealing Procedures
for DOT-21PF-1 Overpacks" 5. List of Recently Issued NMSS Information
Notices 6. List of Recently Issued NRC Information
Notices
Attachment
1 IN 90-27 April 30, 1990 U.S. NUCLEAR REGULATORY
COMMISSION (NRC)____. _@ _.__ .._ ..rFRTJFIEATIS
7FWCOMPLIANCE
ISUED FOR UF CTIVE OVERPACKS wSWl rw -vfw w , _w." _,.,.,_CERT #REV #8 MODEL #REGISTERED
USERS COMMENTS USA/4909/AF
GEr2l-PF-I
W-21.PF-1 General Electric Westinghouse
May be equivalent
t-S6pec 21-PF-1A or 1B.Authorized
gross weight: 8000 lbs.USA/9196/AF
2 UX-30 Nuclear Packaging U.S. Department
of Energy (DOE)Not equivalent
to Specs. 21-PF-1A or 1B: uses different
insu-lating media and has other physical features which differ. Author-ized gross weight: 8000 lbs.USA/9234/AF
0 NCI-21rPF-I
Nuclear Inc.Containers
Similar, but not equivalent
to Spec. 21-PF-1B;
auth.gross weight: 8700 lbs.AdvanceO Nuclear Fuels USA/6553/AF
3 Paducah Tiger DOE Overpack for model 48A and 48X 10-ton cylinders.
Authorized
gross weight: 37,500 lbs.
Attachment
2 IN 90-27 April 30 1990 CHRONOLOGY
OF UF 6 RULE-MAKING (DOCKET HM-166V)Date NUMBER MAJOR ACTIONS INVOLVED April 11, 1986 Nov. 18, 1986 Dec. 24, 1986 March 12, 1986 July 6, 1987 July 6, 1987 Notice 86-2 Amdts. 172-107 and 173-198 Andt. 173-198 Amdt. 173-199 Amdt. 173-198 Notice 87-7 Proposes adding specific requirements, as a new paragraph
173.420, for all UF cylinders, referencing
ANSI N14.1-1982 standards;
also would require UF to be in solid form; and would impose a volumetric.
fill limit of 61-percent
at 70 0 F; and would require Internal pressure to be less than 14.7 psia at 701F.Adopts the changes as proposed in Notice 86-2, and adds requirement
for cleaning of cylinders per App. A of ANSI N14.1-1982.
Eff. Date: January 1, 1987.Delays effective
required date for applicability
of ANSI standards
to new cylinders
to June 30, 1987 and references
additional
applicability
of above changes to previous editions of ANSI N14.1.Also provides notice of public meeting to be held on March 2, 1987 to discuss UF 6 rule-making.
Eff. Date: January 1, 1987.An emergency
final rule which amends Nov. 18, 1986 final rule by removing the requirement
for other than new cy fnders or those undergoing
periodic retesting
to be cleaned in accordance
with App. A of ANSI N14.1-1982.
Eff. Date: March 12, 1987.Revises final rule of Nov. 18 and Dec. 24, 1986, so as to reference
an alternative
to use cylinders
manufactured
to U.S. Department
of Transporation (DOT) Class 106A multiunit
tank car tanks. (Model 30A cylinders), in addition to those conforming
to ANSI N14.1-1982 (for cylinders manufactured
after May 30, 1987).Eff. Date: June 30, 1987.Proposes to authorize
the indefinite
continued use of cylinders
which were not made in accordance
with ANSI N14.1-1987 or DOT Class 106A tanks.
Attachment
2 IN 90-27 April 30, 1990 April 6, 1988 April 29, 1989 Notice 88-2 Amdts 171-103 and 173-214 Proposes to amend the earlier rule-making
to permit use of cylinders
manufactured
in accordance
with ANSI N14-1-1987;
and to permit loading of depleted UF6 to a fill limit of 62.percent
by volume rather than 61 percent at 70'F.Amends previous final rules by authorizing
continued
use of cylinders
manufactured
before June 30, 1987, in accordance
with Section VIII, Div. I of the ASME Code in effect at time of manufacture;
and also authorizes
a fill limit of 62 percent by volume for depleted UF at 201C.Eff. date: September
29, 1989.
Attachment
3 IN 90-27 April 30, 1990 CHRONOLOGY
OF UFg PROTECTIVE
OVERPACK RULEMAKING (HM-190)Date Aug. 16. 1984 Sept. 20, 1908 NUMBER Notice # 84-7 Amdts. 171-96, 173-206, and 178-90 ACTION INVOLVED Proposal to modify design of Spec. 21-PF-1 overpacks
to alleviate
problems resulting from water in-leakage, retention
and sub-sequent leaking out. Based on U.S. Depart-ment of Energy (DOE) petition.
Contained proposals
for required physical modifications
to existing overpacks
and requirements
for newly constructed
overpacks.
Major changes would be the use of stainless
rather than carbon steel and reversal of steps joints on shell closure interfaces.
Final rule based on earlier notice. Revisions essentially
as proposed.
Modified overpacks to be designated
as Spec. 21-PF-1A and newly constructed
overpacks
as Spec. 21-PF-1B.Eff. date: April 1, 1991 for required modITYTaTions
as Spec. 21-PF-1A;
and April 1, 1989, for new construction
as Spec. 21-PF-1B.
Attachment
4 IN 90-27 April 30, 1990 [This procedure
was sent by the U.S. Department
of Energy (DOE), Oak Ridge Operations
Office on January 18, 1990, to the owners of U.S. Department
of Transportation (DOT) Spec. 21PF-1 Overpacks.
It has currently
been implemented
by DOE enrichment
plants.This procedure
is quoted below.]"INTERIM INSPECTION
AND SEALING PROCEDURES
FOR DOT-21PF-1 OVERPACKS" 21PF- Overpack Conference
The U.S. Department
of Energy and Martin Marietta Energy Systems, Inc., hosted the first conference
on the DOT-21PF-1 Overpack at the DOE Gaseous Diffusion Plant in Piketon, Ohio on November 14-15, 1989. The conference
was attended by representatives
from the DOT, NRC, DOE, U.S. and non-U.S. industrial
firms. One of the primary concerns of conference
attendees
was the establishment
of criteria for acceptance
of overpacks
in the interium between now and the deadline (April 1991) for the full implementation
of the provisions
of 49CFR278.121.
Accordingly, a working group was formed to recommend
procedures
that could be adopted by industry prior to April 1991.The procedures
described
in this report were recommended
to the conference
at the end of the morning session.Introduction
It has been known for a long time that the foam insulation
in the 21PF-1 Overpack will pick up water due to its open cell structure, and that the water may subsequently
leak out of the foam through the vent holes in the outer shell. Although numerous studies have shown that the water does not adversely affect the thermal and impact protection
capabilities
of the foam, the public perceives
a leaking overpack as hazardous.
This public perception
is reason enough to take whatever steps are necessary
to preclude leaking overpacks.
49CFR178.121 requires that all existing overpacks
be dried and modified to meet the 21PF-1A standards
by April 1991.
Attachment
4 IN 90-27 April 30, 1990 The 21PF-1A standards
required that neither the top half nor the bottom half of the overpack contain more than 25 pounds of water. This amount of water will be absorbed by the foam and will not leak out even when the foam is subjected
to the compressive
loading imposed by a full UF cylinder.
The problem with this requirement
is that accurate initial taWe weights were not obtained when the existing overpacks
were manufactured, such that water pickup cannot be determined
by simply weighing the overpacks.
This will not be a problem in the future because the packages will be accurately
weighed when they are dried and modified, and the new dry tare weight will be engraved on the modified overpack's
stainless
steel nameplates.
Between now and April 1991, there is a need for some method for satisfactorily
determining
that no leaking overpack will be used in public transportation
without prematurely
implementing
49CFR178.121.
The following
procedures
were developed
by the working group and recommended
to the conference
as one workable answer to this problem.Procedure Prior to shipping an overpack to a USDOE enrichment
facility, the overpack will be prepared and inspected
as follows to ensure that water leakage will not be a problem when the overpack is loaded with a full UF 6 cylinder: 1. Drill out the four bottommost
vent holes in the overpack using a i" drill.2. Load the overpack with a full weight cylinder;
use either a loaded UF 6 cylinder or a dummy cylinder which is the same diameter and weight as a loaded UF 6 cylinder.3. Maintain the load test for a minimum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> at temperatures
above freezing.4. Inspect for leakage while under load.5. If any leakage is found; remove the overpack from service to be dried and refurbished, or to be discarded.
6. If no leakage is found: (a) Use Silicone RTV Caulking to seal the metal/wood
interface
at the closure plane step joint.(b) Use Silicone RTV Caulking to seal the spaces between skip welds on all external reinforcements.(c) Reseal the bottom vent holes using i" plastic capplugs set in Silicone RTV Caulking.
Attachment
4 AN j90-2 g o pr 3 ,1990 (d) Inspect to ensure that the overpack is in sound condition
and the gaskets are acceptable
and in place.(e) Use matching paint to touch up old indications
of water leakage so that enrichment
facility inspectors
will not treat them as indica-tions of fresh new leaks.(f) Accompany
each overpack shipment with a certification
that the overpack has been inspected, sealed, and painted as described above and that the overpack is in sound condition
and free of water leaks when loaded.Enrichment
Facility Acceptance
The purpose of providing
overpacks
with the above described
certification
to the enrichment
facilities
is to provide the means for the overpack to be loaded and shipped from the enrichment
facility with no more than the routine inspection
for soundness
and for absence of water leakage. With such user provided certification
and with physical evidence that the overpacks
have been sealed as described
above and are not leaking, a DOE enrichment
facility would permit shipment of UF in such an overpack without accurate water weight data on the overpack.
Thi4 provision
will not apply to overpacks
which have been modified and certified
as meeting DOT-21PF-1A
specifications
and will not apply to any overpacks
after April 1991.
Attachment
5 IN 90-27 April 30, 1990 LIST OF RECENTLY ISSUED NMSS INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to: 90-24 90-20 90-16 90-15 Transportation
of Model SPEC 2-T Radiographic
Exposure Device Personnel
Injuries Resulting
from Improper Operation
of Radwaste Incinerators
Compliance
with New Decommissioning
Rule Reciprocity:
Notification
of Agreement
State Radiation Control Directors
before Beginning
Work in Agreement States Accidental
Disposal of Radioactive
Materials Extended Interim Storage of Low-Level
Radioactive
Waste by Fuel Cycle and Materials Licensees Importance
of Proper Response to Self-Identified
Violations
by Licensees 04/10/90 03/22/90 03/07/90 03/07/90 03/06/90 02/05/90 01/12/90 All NRC licensees authorized
to use, transport, or operate radiographic
exposure devices and source changers.All U.S. NRC licensees who process or incinerate
radioactive
waste.All materials
licensees.
All holders of NRC materials
licenses that authorize
use of radio-active material at temporary
job sites.All NRC byproduct materials
licensees.
All holders of NRC materials
licenses.All holders of NRC materials
licenses.90-14 90-09 90-01**Correct Number for 90-01 should be 90010145.
Attachment
6 IN 90-27 April 30, 1990 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 89-70, Supp. 1 90-26 90-25 90-24 Possible Indications
of Misrepresented
Vendor Products Inadequate
Flow of Essential
Service Water to Room Coolers and Heat Exchangers
for Engineered
Safety-Feature
Systems Loss of Vital AC Power with Subsequent
Reactor Coolant System Heat-Up Transportation
of Model Spec 2-T Radiographic
Exposure Device Improper Installation
of Patel Conduit Seals Unanticipated
Equipment Actuations
Following Restoration
of Power to Rosemount
Transmitter
Trip Units Potential
Failure of Motor-Operated Butterfly
Valves to Operate Because Valve Seat Friction was Under-estimated Personnel
Injuries Resulting from Improper Operation
of Radwaste Incinerators
4/26/90 4/24/90 4/16/90 4/10/90 4/4/90 3/23/90 3/22/90 3/22/90 All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All NRC licensees authorized
to use, transport, or operate radiographic
exposure devices and source changers.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All NRC licensees who process or incinerate
radio-active waste.90-23 90-22 90-21 90-20 OL = Operating
License CP = Construction
Permit
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list | - Information Notice 1990-01, Importance of Proper Response to Self-Identified Violations by Licensees (12 January 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-02, Potential Degradation of Secondary Containment (22 January 1990)
- Information Notice 1990-03, Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by Failure of the Swing Arm (23 January 1990, Topic: Liquid penetrant)
- Information Notice 1990-04, Cracking of the Upper Shell-to-Transition Cone Girth Welds in Steam Generators, (26 January 1990, Topic: Nondestructive Examination, Thermal fatigue)
- Information Notice 1990-05, Inter-System Discharge of Reactor Coolant (29 January 1990)
- Information Notice 1990-06, Potential for Loss of Shutdown Cooling While at Low Reactor Coolant Levels (29 January 1990)
- Information Notice 1990-07, New Information Regarding Insulation Material Performance and Debris Blockage of PWR Containment Sumps (30 January 1990)
- Information Notice 1990-08, KR-85 Hazards from Decayed Fuel (1 February 1990)
- Information Notice 1990-08, KR-85 Hazards From Decayed Fuel (1 February 1990)
- Information Notice 1990-09, Extended Interim Storage of Low-Level Radioactive Waste by Fuel Cycle and Materials Licensees (5 February 1990, Topic: Decommissioning Funding Plan, Uranium Hexafluoride)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Liquid penetrant)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Nondestructive Examination, Stress corrosion cracking, Liquid penetrant)
- Information Notice 1990-11, Maintenance Deficiency Associated with Solenoid-Operated Valves (28 February 1990)
- Information Notice 1990-12, Monitoring or Interruption of Plant Communications (28 February 1990)
- Information Notice 1990-13, Importance of Review and Analysis of Safeguards Event Logs (5 March 1990)
- Information Notice 1990-14, Accidental Disposal of Radioactive Materials (6 March 1990, Topic: Brachytherapy)
- Information Notice 1990-15, Reciprocity Notification of Agreement State Radiation Control Directors Before Beginning Work in Agreement States (17 March 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-16, Compliance with New Decommissioning Rule (7 March 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-17, Weight and Center of Gravity Discrepancies for Copes-Vulcan Valves (8 March 1990, Topic: Earthquake)
- Information Notice 1990-18, Potential Problems with Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-18, Potential Problems With Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-19, Potential Loss of Effective Volume for Containment Recirculation Spray at PWR Facilities (14 March 1990)
- Information Notice 1990-20, Personnel Injuries Resulting from Improper Operation of Radwaste Incinerators (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction was Underestimated (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction Was Underestimated (22 March 1990)
- Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units (23 March 1990, Topic: Reactor Vessel Water Level)
- Information Notice 1990-23, Improper Installation of Patel Conduit Seals (4 April 1990)
- Information Notice 1990-24, Transportation of Model Spec 2-T Radiographic Exposure Device (10 April 1990, Topic: Exclusive Use)
- Information Notice 1990-24, Transportation of Model SPEC 2-T Radiographic Exposure Device (10 April 1990, Topic: Exclusive Use)
- Information Notice 1990-25, Loss of Vital AC Power With Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-25, Loss of Vital AC Power with Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-26, Inadequate Flow of Essential Service Water to Room Coolers and Heat Exchangers for Engineered Safety-Feature Systems (24 April 1990)
- Information Notice 1990-27, Clarification of the Recent Revisions to the Regulatory Requirements for Packaging of Uranium Hexafluoride (UF6) for Transportation (30 April 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-28, Potential Error In High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-28, Potential Error in High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-29, Cracking of Cladding and Its Heat-Affected Zone in the Base Metal of a Reactor Vessel Head (30 April 1990, Topic: Nondestructive Examination, Liquid penetrant)
- Information Notice 1990-30, Ultrasonic Inspection Techniques for Dissimilar Metal Welds (1 May 1999, Topic: Intergranular Stress Corrosion Cracking, Dissimilar Metal Weld, Exclusive Use)
- Information Notice 1990-31, Update on Waste Form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-31, Update on Waste form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-32, Surface Crack and Subsurface Indications in the Weld of a Reactor Vessel Head (3 May 1990)
- Information Notice 1990-33, Sources of Unexpected Occupational Radiation Exposures at Spent Fuel Storage Pools (9 May 1990, Topic: Overexposure)
- Information Notice 1990-34, Response to False Siren Activations (10 May 1990, Topic: Siren)
- Information Notice 1990-35, Transportation of Type a Quantities of Non-Fissile Radioactive Materials (24 May 1990, Topic: Siren)
- Information Notice 1990-37, Sheared Pinion Gear-To-Shaft Keys in Limitorque Motor Actuators (24 May 1990)
- Information Notice 1990-38, License and Fee Requirements for Processing Financial Assurance Submittals for Decommissioning (6 November 1990, Topic: Authorized possession limits)
- Information Notice 1990-39, Recent Problems with Service Water Systems (1 June 1990)
- Information Notice 1990-40, Results of NRC-Sponsored Testing of Motor-Operated Valves (5 June 1990, Topic: Weak link, Siren)
- Information Notice 1990-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and Ak Circuit Breakers (12 June 1990, Topic: Siren)
- Information Notice 1990-42, Failure of Electrical Power Equipment Due to Solar Magnetic Disturbances (19 June 1990, Topic: Siren)
- Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers (29 June 1990)
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