Clarification of Transportation Requirements Applicable to Return of Spent Radiopharmacy Dosages from Users to SuppliersML031190094 |
Person / Time |
---|
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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
---|
Issue date: |
11/07/1989 |
---|
From: |
Burnett R NRC/NMSS/IMNS |
---|
To: |
|
---|
References |
---|
IN-89-074, NUDOCS 8911010053 |
Download: ML031190094 (9) |
|
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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
---|
Category:NRC Information Notice
MONTHYEARInformation Notice 2020-02, Flex Diesel Generator Operational Challenges2020-09-15015 September 2020 Flex Diesel Generator Operational Challenges ML20225A0322020-09-0303 September 2020 NRC Choice Letter to NAC International with Attached Safety Inspection Report, IR 0721015/2020201, February 24-27, 2020 and July 22, 2020, Inspection of NAC International in Norcross, Georgia Information Notice 2012-09, PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs.2019-11-30030 November 2019 PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs. Information Notice 2011-20, NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011)2019-07-24024 July 2019 NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011) ML19196A2452019-07-15015 July 2019 Public Notice - Sequoyah Nuclear Plant, Unit 2 - Exigent Amendment to Facility Operating License Information Notice 2019-01, Inadequate Evaluation of Temporary Alterations2019-03-12012 March 2019 Inadequate Evaluation of Temporary Alterations ML16028A3082016-04-27027 April 2016 NRC Information Notice; IN 2016-05: Operating Experience Regarding Complications From a Loss of Instrumentation Air Information Notice 2015-05, Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps Information Notice 2015-05, Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps Information Notice 2013-20, OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-20, Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-11, OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2013-11, Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Contain2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Con2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notic2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool Information Notice 2012-13, Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool Information Notice 2012-11, Age Related Capacitor Degradation2012-07-23023 July 2012 Age Related Capacitor Degradation ML12031A0132012-02-0606 February 2012 U.S. Nuclear Regulatory Commission Investigation Report No. 2-2010-058, Cpn International, Inc Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components2011-09-26026 September 2011 Licensee Event Reports Containing Information Pertaining to Defects to Basic Components Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues2011-08-0101 August 2011 Steel Containment Degradation and Associated License Renewal Aging Management Issues Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping2011-07-26026 July 2011 Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. 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 [[:05000000]] OR [[:Zimmer]] 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 [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
I/
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, D.C. 20555 November 7, 1989 NRC INFORMATION NOTICE NO. 89-74: CLARIFICATION OF TRANSPORTATION REQUIREMENTS
APPLICABLE TO RETURN OF SPENT RADIOPHARMACY
DOSAGES FROM USERS TO SUPPLIERS
Addressees
All manufacturers and distributors of radlopharmaceuticals for medical use, nuclear pharmacies, and medical licensees.
Purpose
This notice is provided to answer questions that frequently have arisen about
the regulatory requirements applicable to transportation of packages, containing
radioactive materials in the form of uspent' radiopharmacy dosages, from the user
back to the original supplier. Most of these questions have involved the
performance of shipper' responsibilities in such shipments.
It is expected that addressees will review the information here for applicabi- lity to their licensed activities, and consider actions, as appropriate, to
avoid problems in transport of such materials. However, suggestions contained
in this notice do not constitute any new U.S. Nuclear Regulatory Commission
(NRC) requirements, and no written response is required.
Background:
In the practice of nuclear medicine in the United States, many thousands of
routine shipments of diagnostic radiopharmaceuticals are made each day. Most
of these shipments are from the supplier" radiopharmacy, using private vehicles, to the licensee 'user," e.g., a hospital or physician. One major supplier, in
fact, transports between 1000 to 3000 shipments daily. As a part of the process, the user-licensee then returns such packages to the supplier, now containing
residual "spentm dosages, contaminated syringes, syringe shields, and multi- dose vials. The user places these materials in the original as-received
packagings, which are then picked up routinely by the supplier at the time
'fresh" packages are delivered to the users.
Discussion:
Pursuant to 10 CFR Section 71.5, NRC licensees who either transport licensed
radioactive material outside of their place of use, or deliver such material
to a carrier for transport, must comply with the applicable requirements of
the U.S. Department of Transportation (DOT) regulations 49 CFR Parts 170 to 179.
8911010053 Z
~fS,'2 C
j
IN 89-74 November 7, 1989 Radiopharmacy material shipments almost always involve situations
supplier is a "shipper" acting as a private carrier. The where the
"user" most often is transferring the residual spent-dosage hospital or physician
supplier, who then also assumes responsibility for performing packages to the
functions, as well as the carrier functions. the "shipper"
The questions/answers that follow are intended to clarify
the most frequently
asked questions which have arisen:
Q1. Who must act as the "shipper?"
A. Either party, e.g., the radiopharmacy (supplier) or its
may act as the shipper. DOT regulations provide no specificcustomer (user)
of a "shipper." The regulations do prescribe many requirements definition
to shippers, consignors, or the "...person who offers for applicable
DOT has taken the position that shipper functions actually transport."
by more than one party. This is, of course, the situation may be performed
radwaste "brokers." In that case, the waste generator may in the case of
of the shipper functions, such as filling, closing, and marking perform certain
and preparing a shipping paper. The generator then transfers the packages
to the broker, who receives and takes title to the packages, the shipment
manifest, and loads the package onto his vehicle for transport prepares a new
point or to a burial site. The broker, in effect, becomes to a collection
acting as a private carrier. Likewise, in radiopharmacy the shipper
shipment operations, the supplier functions as a shipper acting as a private
delivery of fresh packages to the user, as well as in thecarrier, in both the
spent-dosage packages from ITe user. In any case, all parties pickup of the
shippers assume liabilTEtyfor any violations that may occur. acting as
Q2. In the case of radiopharmacy spent-dosage shipments
from the user back to
the supplier, who is it preferable to have act as the shipper?
A. As stated previously, either party may act as the shipper, preferable that the supplier assume the responsibility. but it is usually
That is because
the supplier is generally more knowledgeable than the user about
requirements regulatory
for shippers and, likewise, is more apt
adequately equipped to meet those requirements. NRC than the user to be
strongly recommends
that the supplier and the user sign an agreement clearly
respective roles and responsibilities of each party, as delineating the
they relate to
shipper functions, thus eliminating any potential misunderstandings.
such a written agreement, the supplier may rely on the user With
agent in carrying out certain shipper functions. In such to act as his
will hold that supplier totally responsible for ensuring a case NRC
requirements are met. The agreement should be maintained that all shipper
furnished to an inspector upon request. In the absence onfile- and
of such a written
agreement, NRC will generally consider the end-user licensee
responsible for compliance with regulatory shipper requirements to be solelyi
returning radiopharmacX packages to the supplier. This when
is because the
end-user in this case is the point of origin of the shipment.
IN 89-74 November 7, 1989 Q3. What quality control measures would be appropriate on the part of the
supplier?
A. The return of spent radiopharmacy dosages as limited-quantity packages is
not technically subject to the formal shipper requirements for a quality
control program, as outlined in 49 CFR Section 173.475, as would be for
instance, the shipping of labeled Type A packages. However, if the sup- plier relies on the user to perform certain shipper functions on his
behalf, it is appropriate that the supplier establish procedures to ensure
compliance with shipping requirements for limited-quantity packages. Such
a program should Include: establishment and dissemination of packaging
procedures for the users to follow; provision for training of the Involved
user personnel; periodic audits by the supplier of the user's performance, to identify discrepancies; and provisions to effect corrective actions by
the user when discrepancies are observed. The specifics of this quality
control program should be covered in the written agreement between supplier
and end user. (See Question 2.)
Q4. Limited-quantity packages of return shipments of spent dosages sometimes
are placed within opaque plastic bags which may be either five-sided slip- covers or six-sided covers, providing almost total enclosure of the shipment.
This procedure often is used in lieu of performing contamination surveys to
assure compliance with 49 CFR Subsections 173.421(c) and 173.443(a). Please
comment on this?
A. Yes. In the first place, the two types of bags in question do not afford
the same quality of protection. The slipcover bags, since they do not
totally enclose the packaging, are not as effective as the six-sided
covers in preventing contamination. Although either of the bags nay
be a means of avoiding surface contamination, this is not the intended
use. The primary purpose of both types of bags is to display the limited- quantity statement required by 49 CFR Subsection 173.421-1 and to cover
the labels and marking that were opropriate when the package first came
into the user's facility. In order to ensure compliance with the limits
for surface contamination, as stated in Subsection 173.421(c), and certi- fied to by the statement on the bag, NRC strongly recommends that a
contamination survey be performed, although this is not mandatory for
limited-quantity packages. If contamination levels are found to exceed
the regulatory limits of Subsection 173.443(a), the user or the supplier
(if that supplier has assumed responsibility for the shipper functions)
will be found to be in violation of the section, regardless of whether
a contamination survey was made.
Q5. Some radiopharmaceuticals are returned to a supplier unused by the
the end user and not spent." These packages will usually be Type A,
since they exceed-the activity limits for a "limited quantity," as
specified'in 49 CFR Sections 173.421 to 173.423. Does this present
any complications?
'-
IN 89-74 November.7, 1989 A. Definitely. Different regulatory requirements are specified for packaging, labeling, marking, and shipping papers for Type A packages. If the end user
fails to inform the supplier that such packages are not limited-quantity, the packagings, labels, markings, and shipping papers may not be appropriate
to the material being returned. Whatever arrangements have been established
in the written agreement between the two parties, as to who performs the
specified shipper functions, should also hold for these situations. The
more formal requirements for a quality control program, as outlined in
49 CFR Section 173.475, would now apply for a package that contains more
than a limited quantity, e.g., a Type A package.
Q6. Packages containing residual materials and spent dosages usually contain
much less radioactivity than the original, Incoming Type A, labeled
packages. What are the principal requirements applicable to such
limited quantitites in order that they might qualify as "Radioactive
Material, limited quantity" packages?
A. The requirements of 49 CFR Section 173.421, Subsection 173.421-1, and Section 173.423 apply.
Briefly, these requirements state that:
1. The package must be strong, tight...";
2. The radiation level at any point on the external surface of the
package may not exceed 0.5 mrem/hr;
3. The radioactive content may not exceed the limits specified in
49 CFR Section 173.423;
4. Removable radioactive surface contamination on the exterior of
the packagl may not exceed the prescribed limits, e.g., 2,200
d/m/100 cm [49 CFR Subsection 173.443(a)];
5. The outside of the inner packaging, or if there is no inner packaging, the outside of the package itself must be marked "RADIOACTIVE;" and,
6. A notice, with prescribed wording per 49 CFR Subsection 173.421-1, must be included in,.on or identifiably with the package, certifying
that the package meets the requirements 7orlimited-quantity
radioactive materials.
Q7. I understand that distribution of nuclear medicine materials in the
United States is largely accomplished by a network of non-licensed
contract motor and air carriers who operate under exemptions issued
by DOT (DOT E-8308 for highway shipments and DOT E-7060 for air shipments).
Does this information notice relate to those shipments?
I
IN 89-74 November 7, 1989 A. No. The contract carriers involved as parties to those two exemptions
are license-exempt and therefore subject solely'to DOT Jurisdiction.
In effect, they are responsible for the carrier requirements of DOT
regulations, not the shipper requirements. They are also responsible
for maintenance of the raFa-tion-protection programs. §jspecied in
each exemption. In cases where 'spent' packages of MO - TC generators
are being returned by an end-user to a supplier using the contract carrier, the end-user is the originator of the return shipment and clearly is
responsible for the shipper functions.
Robert F. Burnett, Director
Division of Safeguards and
Transportation
Office of Nuclear Material Safety
and Safeguards
Technical Contact:
A. W. Grella, NMSS
(301) 492-3381 Attachment: List of Recently Issued NRC Information Notices
Attachment
IN 89-74 November 7, 1989 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
89-73 Potential Overpressurization 11/1/89 All holders of OLs
of Low Pressure Systems or CPs for nuclear
power reactors.
89-72 Failure of Licensed Senior 10/24/89 All holders of OLs
Operators to Classify or CPs for nuclear
Emergency Events Properly power reactors.
89-71 Diversion of the Residual 10/19/89 All holders of OLs
Heat Removal Pump Seal or CPs for nuclear
Cooling Water Flow During power reactors.
Recirculation Operation
Following a Loss-of- Coolant Accident
89-70 Possible Indications of 10/11/89 All holders of OLs
Misrepresented Vendor or CPs for nuclear
Products power reactors.
89-69 Loss of Thermal Margin 9/29/89 All holders of OLs
Caused by Channel Box or CPs for BWRS.
Bow
89-68 Evaluation of Instrument 9/25/89 All holders of OLs
Setpoints During or CPs for nuclear
Modifications power reactors.
89-67 Loss of Residual Heat 9/13/89 All holders of OLs
Removal Caused by or CPs for PWRs.
Accumulator Nitrogen
Injection
89-66 Qualification Life of 9/11/89 All holders of OLs
Solenoid Valves or CPs for nuclear
power reactors.
88-46, Licensee Report of 9/11/89 All holders of OLs
Supp. 4 Defective Refurbished or CPs for nuclear
Circuit Breakers power reactors.
OL = Operating License
CP e Construction Permit
IN 89-74 November 7, 1989 A. No. The contract carriers involved as parties to those two exemptions
are license-exempt and therefore subject solely to DOT jurisdiction.
In effect, they are responsible for the carrier requirements of DOT
regulations, not the shipper requirements. They are also responsible
for maintenance of the ra dation-protection programs, § speckied in
each exemption. Incases where 'spent packages of MO - TC generators
are being returned by an end-user to a supplier using the contract carrier, the end-user is the originator of the return shipment and clearly is
responsible for the shipper functions.
Robert F. Burnett, Director
Division of Safeguards and
Transportation
Office of Nuclear Material Safety
and Safeguards
Technical Contact:
A. W. Grella, NMSS
(301) 492-3381 Attachment: List of Recently Issued NRC Information Notices
Also reviewed by: Concurrence with minor Editorial changes:
EKraus, NMSS USDOT EEJakel, OGC STreby, OGC 10/24/89
Technical Editor MWangler, DOT
(2 times) 9/89 SGDB * SGDB * SGDB * IMNS * SGTR * SGTR
AGrella:ne PTing DKasun JGlenn GMcCorkle RBurnett
10/23/89 10/23/89 10/23/89 10/10/89 10/23/89 10/ /89
A. No. The contract carriers involved as parties to those two exemptions
are license-exempt and therefore subject solely to DOT jurisdiction.
In effect, they are responsible for the carrier requirements of DOT
regulations, not the shiPper requirements. They are also responsible
for maintenance of the raiat0ion-protection progrags, as9 pecified in each
exemption. In cases where 'spent" packages of MO - TC generators are
being returned by an end-user to a supplier using the contract carrier, the end-user is the originator of the return shipment and clearly is
responseiblefor the shipper functions.
Robert F. Burnett, Director
Division of Safeguards and
Transportation
Office of Nuclear Material Safety
and Safeguards
Technical Contact:
A. W. Grella. NMSS
(301) 492-3381 V
Attachment:
List of Recently Issued
NRC Information Notices
DISTRIBUTION:
SGDB r/f
AGrella
PTing
DKasun
Also reviewed by: Concurrence with minor Editorial changes:
EKraus, NMSS USDOT EEJakel, OGC STreby, OGC 10/24/89
Technical Editor MWangler, DOT
(2 times) 9/89 SGDB * SGDB * SGDB * IMNS * SGTR * SG
AGrella:ne PTing DKasun JGlenn GMcCorkle RB tt
10/23/89 10/23/89 10/23/89 10/10/89 10/23/89 10/5l/89
6
A. No. The contract carriers involved as parties to those two exemptions
are license-exempt and therefore subject solely to DOT jurisdiction.
In effect, they are responsible for the carrier requirements of DOT
regulations, not the shipper requirements.Theiy are also responsible
for maintenance of the rada tion-erotection progrgs, asg§pecified in each
exemption. In cases where 'spent packages of MO - TC generators are
being returned by an end-user to a supplier, using the contract carrier, the end-user is the originator of the return shipment, and clearly is
responsiTElefor the shipper functions.
Robert F. Burnett, Director
Division of Safeguards and
Transportation
Office of Nuclear Material Safety
and Safeguards
Technical Contact:
A. W. Grella, NMSS
(301) 492-3381 Attachment:
List of Recently Issued
NRC Information Notices
DISTRIBUTION:
SGDB r/f
AGrella
PTing
DKasun
SGDB D SGD X l MNS SGTX SGTR 4 eso ecea¢fi
P or
AGrel Tane /PT DXGlenn
sg GMcckrkle RBurnett .r ,s triwr
10 1h9 3/8 1 899 10/JO/89 1/0 /89 10/ /89 Aus NJs
7otSe
reetfocP. ,,hdh*ooy
Ire
hd~k,Id.coes
c.0 6/t,r
CC Tore,, Pett
U 1 e6fvit*
|
---|
|
list | - Information Notice 1989-01, Valve Body Erosion (4 January 1989)
- Information Notice 1989-02, Criminal Prosecution of Licensee'S Former President for Intentional Safety Violations (9 January 1989)
- Information Notice 1989-03, Potential Electrical Equipment Problems (11 January 1989)
- Information Notice 1989-04, Potential Problems from the Use of Space Heaters (17 January 1989)
- Information Notice 1989-05, Use of Deadly Force by Guards Protecting Nuclear Power Reactors Against Radiological Sabotage (19 January 1989)
- Information Notice 1989-06, Bent Anchor Bolts in Boiling Water Reactor Torus Supports (24 January 1989)
- Information Notice 1989-07, Failures of Small-Diameter Tubing in Control Air, Fuel Oil & Lube Oil Systems Render Emergency Diesel Generators Inoperable (25 January 1989)
- Information Notice 1989-08, Pump Damage Caused by Low-Flow Operation (26 January 1989)
- Information Notice 1989-09, Credit for Control Rods Without Scram Capability in the Calculation of Shutdown Margin (26 January 1989, Topic: Shutdown Margin)
- Information Notice 1989-10, Undetected Installation Errors in Main Steam Line Pipe Tunnel Differential Temperature-Sensing Elements at Boiling Water Reactors (27 January 1989)
- Information Notice 1989-11, Failure of DC Motor-Operated Valves to Develop Rated Torque Because of Improper Cable Sizing (2 February 1989, Topic: Shutdown Margin)
- Information Notice 1989-12, Dose Calibrator Quality Control (9 February 1989)
- Information Notice 1989-13, Alternative Waste Management Procedures in Case of Denial of Access to Low-Level Waste Disposal Sites (8 February 1989, Topic: Shutdown Margin, Authorized possession limits)
- Information Notice 1989-15, Second Reactor Coolant Pump Shaft Failure at Crystal River (16 February 1989, Topic: Shutdown Margin)
- Information Notice 1989-16, Excessive Voltage Drop in DC Systems (16 February 1989, Topic: Shutdown Margin, Battery sizing)
- Information Notice 1989-17, Contamination and Degradation of Safety-Related Battery Cells (22 February 1989)
- Information Notice 1989-18, Criminal Prosecution of Wrongdoing Committed by Suppliers of Nuclear Products or Services (24 August 1990)
- Information Notice 1989-20, Weld Failures in a Pump of Byron-Jackson Design (24 February 1989, Topic: Health Physics Network)
- Information Notice 1989-21, Changes in Performance Characteristics of Molded-Case Circuit Breakers (27 February 1989, Topic: Health Physics Network)
- Information Notice 1989-23, Environmental Qualification of Litton-Veam Cir Series Electrical Connectors (3 March 1989, Topic: Health Physics Network)
- Information Notice 1989-24, Nuclear Criticality Safety (6 March 1989, Topic: Health Physics Network)
- Information Notice 1989-25, Unauthorized Transfer of Ownership or Control of Licensed Activities (7 March 1989, Topic: Health Physics Network)
- Information Notice 1989-26, Instrument Air Supply to Safety-Related Equipment (7 March 1989, Topic: Health Physics Network)
- Information Notice 1989-27, Limitations on the Use of Waste Forms and High Integrity Containers for the Disposal of Low-Level Radioactive Waste (8 March 1989, Topic: Process Control Program)
- Information Notice 1989-28, Weight and Center of Gravity Discrepancies for Copes-Vulcan Air-Operated Valves (14 March 1989)
- Information Notice 1989-29, Potential Failure of Asea Brown Boveri Circuit Breakers During Seismic Event (15 March 1989)
- Information Notice 1989-30, High Temperature Environments at Nuclear Power Plants (1 November 1990)
- Information Notice 1989-31, Swelling and Cracking of Hafnium Control Rods (22 March 1989)
- Information Notice 1989-32, Surveillance Testing of Low-Temperature Overpressure-Protection Systems (23 March 1989, Topic: Stroke time)
- Information Notice 1989-33, Potential Failure of Westinghouse Steam Generator Tube Mechanical Plugs (23 March 1989)
- Information Notice 1989-34, Disposal of Americium Well-Logging Sources (30 March 1989)
- Information Notice 1989-35, Loss & Theft of Unsecured Licensed Material, Attachment 1 to NRC Information Notice 1990-014: Accidental Disposal of Radioactive Materials. (Also includes Attachments 2 & 3) (30 March 1989)
- Information Notice 1989-35, Loss & Theft of Unsecured Licensed Material, Attachment 1 to NRC Information Notice 1990-014: Accidental Disposal of Radioactive Materials. (Also Includes Attachments 2 & 3) (30 March 1989, Topic: Moisture-Density Gauge)
- Information Notice 1989-36, Excessive Temperatures in Emergency Core Cooling System Piping Located Outside Containment (4 April 1989)
- Information Notice 1989-37, Proposed Amendments to 40 CFR Part 61, Air Emission Standards for Radionuclides (4 April 1989)
- Information Notice 1989-38, Atmospheric Dump Valve Failures at Palo Verde Units 1, 2, and 3 (5 April 1989, Topic: Emergency Lighting)
- Information Notice 1989-39, List of Parties Excluded from Federal Procurement or Non-Procurement Programs (5 April 1989)
- Information Notice 1989-40, Unsatisfactory Operator Test Results and Their Effect on the Requalification Program (14 April 1989)
- Information Notice 1989-41, Operator Response to Pressurization of Low-Pressure Interfacing Systems (20 April 1989)
- Information Notice 1989-42, Failure of Rosemount Models 1153 and 1154 Transmitters (21 April 1989)
- Information Notice 1989-43, Permanent Deformation of Torque Switch Helical Springs in Limitorque SMA-Type Motor Operators (1 May 1989)
- Information Notice 1989-44, Hydrogen Storage on the Roof of the Control Room (27 April 1989, Topic: Coatings)
- Information Notice 1989-45, Metalclad, Low-Voltage Power Circuit Breakers Refurbished with Substandard Parts (8 May 1989, Topic: Commercial Grade Dedication, Coatings)
- Information Notice 1989-46, Confidentiality of Exercise Scenarios (11 May 1989, Topic: Coatings)
- Information Notice 1989-47, Potential Problems with Worn or Distorted Hose Clamps on Self-Contained Breathing Apparatus (18 May 1989, Topic: Coatings)
- Information Notice 1989-48, Design Deficiency in the Turbine-Driven Auxiliary Feedwater Pump Cooling Water Systems (22 May 1989, Topic: Coatings, Temporary Modification)
- Information Notice 1989-49, Failure to Close Service Water Cross-Connect Isolation Valves (22 May 1989, Topic: Coatings)
- Information Notice 1989-50, Inadequate Emergency Diesel Generator Fuel Supply (30 May 1989)
- Information Notice 1989-51, Potential Loss of Required Shutdown Margin During Refueling Operations (31 May 1989, Topic: Shutdown Margin, Coatings)
- Information Notice 1989-52, Potential Fire Damper Operational Problems (8 June 1989, Topic: Safe Shutdown, Shutdown Margin, Fire Barrier, Fire Protection Program)
... further results |
---|