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, Mcguire, 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 ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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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, Mcguire, 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 |
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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 [[:Mcguire]] 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]] </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 [[:Mcguire]] 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]] </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 (UF6 ) 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 UF6
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. Itis 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. Ineffect, therefore, DOE has stated
that itwill 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 itwas designed, inspected, tested, and marked in
accordance with the 1987, 1982 or 1971 version of ANSI N14.1, ineffect 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
tective overpacks for 30" cylinders obtained certificates of compliance of pro- the NRC to authorize the use of overpacks of improved design. These from
marized in Attachment 1. A comparison of the specifics of the DOT are sum- Specification
21PF-1A and 18 requirements with these certificates indicates that there
islTTTremain a need for the certificates, in that there are substantial will
Terences between, for example, the Model UX-30 (USA/9234/AF) and the dif- JUSA/9196/AF) and the DOT specifications. NCI-21-PF-1 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 UF6 Overpacks
2. Chronology of UF6 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
wSWl rw -vfw w
7FWCOMPLIANCE ISUED FOR UF
, _w." _,.,.,_
CTIVE OVERPACKS
CERT # REV # MODEL # REGISTERED USERS COMMENTS
USA/4909/AF 8 GEr2l-PF-I General Electric May be equivalent
W-21.PF-1 Westinghouse t-S6pec 21-PF-1A or 1B.
Authorized gross
weight: 8000 lbs.
USA/9196/AF 2 UX-30 Nuclear Packaging Not equivalent to
U.S. Department of Specs. 21-PF-1A or
Energy (DOE) 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 Containers Similar, but not
Inc. equivalent to
Spec. 21-PF-1B; auth.
AdvanceO Nuclear gross weight: 8700 lbs.
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 UF6 RULE-MAKING (DOCKET HM-166V)
Date NUMBER MAJOR ACTIONS INVOLVED
April 11, 1986 Notice 86-2 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 700F; and would require Internal
pressure to be less than 14.7 psia at 701F.
Nov. 18, 1986 Amdts. 172-107 Adopts the changes as proposed in Notice 86-2, and 173-198 and adds requirement for cleaning of cylinders
per App. A of ANSI N14.1-1982.
Eff. Date: January 1, 1987.
Dec. 24, 1986 Andt. 173-198 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 UF6 rule-making.
Eff. Date: January 1, 1987.
March 12, 1986 Amdt. 173-199 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.
July 6, 1987 Amdt. 173-198 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.
July 6, 1987 Notice 87-7 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 Notice 88-2 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.
April 29, 1989 Amdts 171-103 Amends previous final rules by authorizing
and 173-214 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 NUMBER ACTION INVOLVED
Aug. 16. 1984 Notice # 84-7 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.
Sept. 20, 1908 Amdts. 171-96, Final rule based on earlier notice. Revisions
173-206, and essentially as proposed. Modified overpacks
178-90 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 UF6 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 UF6 cylinder or a dummy cylinder which is the same diameter and weight as a
loaded UF6 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 Transportation of Model 04/10/90 All NRC licensees
SPEC 2-T Radiographic authorized to use, Exposure Device transport, or operate
radiographic exposure
devices and source
changers.
90-20 Personnel Injuries 03/22/90 All U.S. NRC licensees
Resulting from Improper who process or incinerate
Operation of Radwaste radioactive waste.
Incinerators
90-16 Compliance with New 03/07/90 All materials licensees.
Decommissioning Rule
90-15 Reciprocity: Notification 03/07/90 All holders of NRC
of Agreement State Radiation materials licenses that
Control Directors before authorize use of radio- Beginning Work in Agreement active material at
States temporary job sites.
90-14 Accidental Disposal of 03/06/90 All NRC byproduct
Radioactive Materials materials licensees.
90-09 Extended Interim Storage of 02/05/90 All holders of NRC
Low-Level Radioactive Waste materials licenses.
by Fuel Cycle and Materials
Licensees
90-01* Importance of Proper 01/12/90 All holders of NRC
Response to Self-Identified materials licenses.
Violations by Licensees
- 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, Possible Indications of 4/26/90 All holders of OLs
Supp. 1 Misrepresented Vendor or CPs for nuclear
Products power reactors.
90-26 Inadequate Flow of 4/24/90 All holders of OLs
Essential Service Water or CPs for nuclear
to Room Coolers and Heat power reactors.
Exchangers for Engineered
Safety-Feature Systems
90-25 Loss of Vital AC Power 4/16/90 All holders of OLs
with Subsequent Reactor or CPs for nuclear
Coolant System Heat-Up power reactors.
90-24 Transportation of Model 4/10/90 All NRC licensees
Spec 2-T Radiographic authorized to use, Exposure Device transport, or operate
radiographic exposure
devices and source
changers.
90-23 Improper Installation of 4/4/90 All holders of OLs
Patel Conduit Seals or CPs for nuclear
power reactors.
90-22 Unanticipated Equipment 3/23/90 All holders of OLs
Actuations Following or CPs for nuclear
Restoration of Power power reactors.
to Rosemount Transmitter
Trip Units
90-21 Potential Failure of Motor- 3/22/90 All holders of OLs
Operated Butterfly Valves or CPs for nuclear
to Operate Because Valve power reactors.
Seat Friction was Under- estimated
90-20 Personnel Injuries Resulting 3/22/90 All NRC licensees
from Improper Operation of who process or
Radwaste Incinerators incinerate radio- active waste.
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)
- 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)
- 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, 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)
- 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)
- Information Notice 1990-24, Transportation of Model SPEC 2-T Radiographic Exposure Device (10 April 1990)
- 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)
- 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: Dissimilar Metal Weld)
- 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)
- Information Notice 1990-34, Response to False Siren Activations (10 May 1990)
- Information Notice 1990-35, Transportation of Type a Quantities of Non-Fissile Radioactive Materials (24 May 1990)
- 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)
- Information Notice 1990-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and Ak Circuit Breakers (12 June 1990)
- Information Notice 1990-42, Failure of Electrical Power Equipment Due to Solar Magnetic Disturbances (19 June 1990)
- Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers (29 June 1990)
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