Potential Safety Issue Regarding the Shipment of Fissile MaterialML031050508 |
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 |
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Issue date: |
12/06/1996 |
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From: |
Haughney C NRC/NMSS/SFPO |
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To: |
|
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References |
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IN-96-063, NUDOCS 9612040215 |
Download: ML031050508 (9) |
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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>. |
K) JIM MCKNIGHT UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, DC 20555 December 5, 1996 NRC INFORMATION
NOTICE 96-63: POTENTIAL
SAFETY ISSUE REGARDING
THE SHIPMENT OF FISSILE MATERIAL
Addressees
All U.S. Nuclear Regulatory
Commission
licensees
authorized
to possess special nuclear material in unsealed quantities
greater than a critical mass.
Purpose
The U.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice to alert addressees
to an issue with potential
safety significance
regarding
shipments
using the fissile material exemption
provisions
and general licenses.
It is expected that recipients
will review this information
for applicability
to their facilities
and consider actions, as appropriate, to avoid similar problems.
However, suggestions
contained
in this information
notice are not NRC requirements;
therefore, no specific action nor written response is required.Description
of Circumstances
An NRC licensee recently informed NRC of a potential
situation
where one of the fissile material exemptions
in 10 CFR 71.53 would not have provided adequate criticality
safety if large amounts of an exempt concentration
of fissile material were to be transported
in the presence of a special moderating
material (i.e., beryllium).
A recent contract was awarded to the licensee to process weapons-usable
enriched uranium materials.
The waste product, a uranium-beryllium
filtercake, met the fissile exemption
provisions
in 10 CFR 71.53 and 49 CFR 173.453. The presence of beryllium
in significant
quantities
in NRC-regulated
fissile exempt shipments
is extraordinary, and was not considered
in the development
of the fissile exemptions
in the regulations.
NRC has reviewed and verified the licensee's
calculations, and has concluded
that the current regulations
need to be revised to preclude criticality
in fissile exempt shipments
made under 10 CFR 71.53, and fissile shipments
made underthe general licenses in 10 CFR 71.18 and 10 CFR 71.22. This information
notice is being issued to provide additional, timely notice, to licensees, of this potential
safety issue, while the regulatory
revisions
are made.Discussion
The licensee proposed to employ the provision
in 10 CFR 71.53(d), or the parallel provision
in the U.S. Department
of Transportation (DOT) regulations, 49 CFR 173.453(d).
J//1 961204021 on jl4Pqt PDR ETE OO~tc 99 IN 96-63 December 5, 1996 Section 71.53(d) exempts fissile material from the requirements
in 10 CFR 71.55 and 71.59 (i.e., the additional
requirements
placed on fissile packages and shipments
to preclude criticality), provided the package does not contain more than 5 grams (0.18 ounces) of fissile material in any 10-liter (610-cubic-inch)
volume. The fissile exemptions
appearing
in 10 CFR 71.53 are assumed to provide inherent criticality
control for all practical
cases in which fissile materials exist at or below the applicable
regulatory
limits (i.e., independent
calculations
would generally not be expected nor required).
Consequently, the fissile exemptions
generally
do not place limits on the types of moderating
or reflecting
material present in fissile exempt packages, nor the number of fissile exempt packages that can be shipped in a single consignment, and do not require that a transport
index (see 10 CFR 71.4) be assigned to packages for criticality
control.Further, the fissile material exemptions
and general license provisions
allow any licensee to make shipments
without first seeking NRC approval.A fairly realistic
computer model of the enriched uranium-beryllium
oxide waste packages, as loaded for shipment into a sea-land container, and at 0.5 grams per liter, could not be demonstrated
to provide adequate nuclear criticality
safety. Because the current regulations
would allow the possibility
of criticality
in fissile exempt shipments, and since there is no assurance
that such shipments
will not occur, NRC intends to revise 10 CFR Part 71 to address exclusion
of beryllium
and other special moderating
material (e.g., deuterium
and graphite)
in the shipment of fissile materials, and to limit the amount of fissile exempt material that can be transported
in a single consignment.
NRC has contacted
the U.S. Department
of Energy (DOE) and the DOT on this issue. DOE is a shipper of fissile material, which could include the special moderating
materials
in question.NRC and DOT are coordinating
the revisions
to their respective
regulations.
NRC notes that very few licensees
are involved in the shipment of fissile materials
with beryllium, graphite, or deuterium.
However, for those licensees
that are involved in such shipments, it is important
that programs be assessed to ensure that adequate criticality
safety is provided where fissile materials
are transported
with materials
known or expected to have moderating
properties
greater than water. As demonstrated
by the licensee in this case, the existing fissile material exemptions
cannot be presumed, without independent
analysis, to preclude nuclear criticality
in all cases.
I):K,)IN 96-63 December 5, 1996 This information
notice requires no specific action nor written response.
If you have any questions
about the information
in this notice, please contact the individual
listed below, or the appropriate
NRC regional office.Charles J. Haighney, Actirt Dire Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards
Technical
contact: Earl P. Easton, NMSS (301) 415-8520 e-mail: exe@nrc.gov
Attachments:
1. List of Recently Issued NMSS Information
Notices 2. List of Recently Issued NRR Information
Notices o k')~ Gu A 7- Attachment
I IN 96-63 December 5, 1996 Page 1 of I LIST OF RECENTLY ISSUED NMSS INFORMATION
NOTICES Info rmation Notice No.Date of Issuance Subject Issued to 96-57 96-54 96-53 Incident-Reporting
Require-ments Involving
Intakes, During a 24-Hour Period that May Cause a Total Effective
Dose Equivalent
in Excess of 0.05 Sv (5 rem)Vulnerability
of Stainless Steel to Corrosion
When Sensitized
Retrofit to Amersham 660 Posilock Radiography
Camera to Correct Incon-sistency in 10 CFR Part 34 Compatibility
Cracked Insertion
Rods on Troxler Model 3400 Series Portable Moisture Density Gauges Residual Contamination
Remaining
in Krypton-85 Handling System After Venting Recordkeeping, Decommis-sioning Notifications
for Disposals
of Radioactive
Waste by Land Burial Authorized
Under Former 10 CFR 20.304, 20.302, and Current 20.2002 10/30/96 10117/96 10/15/96 09/26/96 09/11/96 08/19196 All U.S. Nuclear Regulatory
Commission
licensees All material licensees All industrial
radiography
licensees All U.S. Nuclear Regulatory
Commission
portable gauge licensees
and vendors All material licensees All U.S. Nuclear Regulatory
Commission
licensees 96-52 96-51 96-47 v>Attachment
2 IN 96-63 December 5, 1996 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 96-62 96-61 96-60 96-59 96-58 Potential
Failure of the Instantaneous
Trip Function of General Electric RMS-9 Programmers
Failure of a Main Steam Safety Valve to Reseat Caused by an Improperly
Installed
Release Nut Potential
Common-Mode
Post-Accident Failure of Residual Heat Removal Heat Exchangers
Potential
Degradation
of Post Loss-of-Coolant
Recirculation
Capability
as a Result of Debris RCP Seal Replacement
with Pump on Backseat Incident-Reporting
Require-ments Involving
Intakes, During a 24-Hour Period That May Cause a Total Effective
Dose Equivalent
in Excess of 0.05 Sv (5 rems)11/20/96 11/20/96 11/14/96 10/30/96 10/30/96 10/29/96 All holders of OLs and CPs for nuclear power plants 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 holders of OLs or CPs for pressurized-water
reactors All U.S. Nuclear Regulatory
Commission
licensees 96-57 OL = Operating
License CP = Construction
Permit
K>IN 96-63 v2 December 5, 1996 This information
notice requires no specific action nor written response.
If you have any questions
about the information
in this notice, please contact the individual
listed below, or the appropriate
NRC regional office.ChaSes J. Haugfey Charles J. Haughney, Acting Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards
Technical
contact: Earl P. Easton, NMSS (301) 415-8520 e-mail: exeenrc.gov
Attachments:
1. List of Recently Issued NMSS Information
Notices 2. List of Recently Issued NRR Information
Notices 96-63.IN*See Previous Concurrence.
OFC SFPO* I c SFPO* l c SFPO* I c NRR/OECB*
I c OGC* lc TEditor I NAME RLewis:LMG
EEaston SShankman
AEChaffee
ENJenson EKraus*DATE 10/10/96 10/10/96 10/10/96 10/10/96 11/25/96 11/25/96 OFC lIMOB l I SFP t I I l- I NAME KRamsey CJH_ ney DATE 1/27/96 W215196 Ia; v4 i _ _C_ CO E E CO E N L S R O C C =COVER E = COVER & ENCLOSURE N = NE) CQPT
IN 96-##KJ i2 October ##, 1996 present in fissile exempt packages, nor the number of fissile exempt packages that can be shipped in a single consignment, and do not require that a transport
index (see 10 CFR 71.4) be assigned to packages for criticality
control. Further, the fissile material exemptions
and general license provisions
allow any licensee to make shipments
without first seeking NRC approval.A fairly realistic
computer model of the enriched uranium-beryllium
oxide waste packages, as loaded for shipment into a sea-land container, and at 0.5 grams per liter, could not be demonstrated
to provide adequate nuclear criticality
safety. Because the current regulations
would allow the possibility
of criticality
in fissile exempt shipments, and since there is no assurance
that such shipments
will not occur, NRC intends to revise 10 CFR Part 71 to address exclusion
of beryllium
and other special moderating
material (e.g., deuterium
and graphite)
in the shipment of fissile materials, and to limit the amount of fissile exempt material that can be transported
in a single consignment.
NRC has contacted
the U.S. Department
of Energy (DOE) and the DOT on this issue. DOE is a shipper of fissile material, which could include the special moderating
materials
in question.
NRC and DOT are coordinating
the revisions
to their respective
regulations.
NRC notes that very few licensees
are involved in the shipment of fissile materials-with
beryllium, graphite, or deuterium.
However, for those licensees
that are involved in such shipments, it is important
that programs be assessed to ensure that adequate criticality
safety is provided where fissile materials
are transported
with materials
known or expected to have moderating
properties
greater than water. As demonstrated
by the licensee in this case, the existing fissile material exemptions
cannot be presumed, without independent
analysis, to preclude nuclear criticality
in all cases.This information
notice requires no specific action nor written response.
If you have any questions
about the information
in this notice, please contact the individual
listed below, or the appropriate
NRC regional office.Charles J. Haughney, Acting Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards
Attachments:
1. List of Recently Issued NMSS Information
Notices 2. List of Recently Issued NRR Information
Notices Contact: Earl P. Easton, NMSS (301) 415-8520 e-mail: exe@nrc.gov
S:WPROJRXL1FIZ.IN
See Previous Concurrence.
OFC SFPON* c SFPO l c SFPO
I c OGCN lc TEditor I NAME RLewis:LMG
EEaston SShankman
AEChaffee
ENJenson EKraus *DATE I 10/10/96 I 10/10/96 I 10/10/96 I 10/10/96 1 11/25/96 1 11/25/96 I--OFC IMOB I SFP lL,/ I l _NAME KRamseyeK
CJHa_ _ _DATE 1I9 196 12- ?79 _6 _,,___. __ _ ________C -COVER E = COVER & LNULUbUKIt
N = Nu iurO
>-considerations
and shipping experience
indicate that the criticality
of fissile exempt packages is not an immediate
threat to worker and public health and safety, the possibility
of criticality
in fissile exempt shipments
has prompted NRC to revise 10 CFR Part 71, to address the possible inclusion
of beryllium
and other special moderating
material (e.g., deuterium
and graphite)
in the shipment of fissile materials, and to limit the amount of fissile exempt material which can be transported
in a single consignment.
NRC staff has also contacted
the Department
of Transportation (DOT) on this issue, as DOT regulations
contain a parallel provision
to 10 CFR 71.53 (i.e., 49 CFR 173.453).NRC and DOT are coordinating
the revisions
to their respective
regulations.
In practice, operating
and administrative
limits and procedures
should prevent the collection
of fissile materials
in amounts or geometries
which could achieve criticality
as a result of any single change in the conditions
necessary
for criticality
safety. Nevertheless, NRC notes that until the expedited
regulatory
revisions
are made, good practice would be for licensees
to exercise caution in deciding whether to ship: (1) fissile materials
with materials
known or expected to have moderating
properties
greater than water; or (2)single consignments
of fissile exempt packages in excess of 290 grams of uranium-235 or 180 grams of other fissile radionuclides.
As demonstrated
by the licensee in this case, the existing fissile material exemptions
cannot be presumed, without independent
analysis, to preclude nuclear criticality
in all cases.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below, or the appropriate
NRC Regional Office.William D. Travers, Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards
Attachments:
1. List of Recently Issued NMSS Information
Notices 2. List of Recently Issued NRR Information
Notices Contact: Earl P. Easton, NMSS (301) 415-8527 S:IPROJIRXLFIZ.IN
See Previous Concurrence.
OFC lSFPO l -SFPO l f-0 e-O NRR/OECB l OGC l TEDITOR I NAME RLeg -sAG EEas aman b affee WReamer EKraus lATVS I J.JIIAIg -I -&.10 & I 0 I la;: I a lIda I I , -I I /on LO#% IV. I(V U l TO'I 1J1_IU 1 v IU Iva % I I I Ef %I OFC DWM I IMOB l SFPO I SFP NAME RJohnson KRamsey CJHaughney
WDTravers DATE I/ /96 / /96 / /96 I /96 l C = COVER E = COVER & ENCLOSURE
N = NO COPY 2 IN 96-##/ H October ##, 1996 shipped in a single consignment, and do not require that a transport
index (see §71.4) be assigned to packages for criticality
control. Further, the fissile material exemptions
and general license provisions
allow any licensee to make shipments
without first seeking NRC approval.A fairly realistic
computer model of the enriched uranium-beryllium
oxide waste packages, as loaded for shipment into a sea-land container, and at 0.5 grams per liter, could not be demonstrated
to provide adequate nuclear criticality
safety. Because the current regulations
would allow the possibility
of criticality
in fissile exempt shipments, and since there is no assurance
that such shipments
will not occur, NRC intends to revise 10 CFR Part 71, to address exclusion
of beryllium
and other special moderating
material (e.g., deuterium
and graphite)
in the shipment of fissile materials, and to limit the amount of fissile exempt material which can be transported
in a single consignment.
NRC staff has contacted
the U.S. Department
of Energy (DOE) and the DOT on this issue.DOE is a shipper of fissile material, which could include the special moderating
materials
in question.
NRC and DOT are coordinating
the revisions
to their respective
regulations.
NRC notes very few licensees
are involved in the shipment of fissile materials
with beryllium, graphite, or deuterium.
However, for those licensees
that are involved in such shipments, it is important
that programs be assessed to ensure that adequate criticality
safety is provided where fissile materials
are transported
with materials
known or expected to have moderating
properties
greater than water. As demonstrated
by the licensee in this case, the existing fissile material exemptions
cannot be presumed, without independent
analysis, to preclude nuclear criticality
in all cases.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the individual
listed below, or the appropriate
NRC Regional Office.Charles J. Haughney, Acting Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards
Attachments:
1. List of Recently Issued NMSS Information
Notices 2. List of Recently Issued NRR Information
Notices Contact: Earl P. Easton, NMSS (301) 415-8520 e-mail: exe@nrc.gov
S:IPROJIRXLIFIZ.IN
- See Previous Concurrence.
OPP3 OFC SFPO* I c SFPO* lc SFPO* I c NRR/OECB*
I c OG TE TOR I NAME RLewis:LMG
EEaston SShankman
AEChaffee
_____enson
EKraus DATE I /196 / /96 1 1/96 I /196 1 196 I /196 OFC DWM I IMOB l FlO I Sl FPO I jI NAME RJohnson KRamsey CJHaughney
WDTravers DATE I/ /96 I /96 1 /196 / /96 J .I.. ==_C = COVER E = COVER & ENCLOSURE N = NU COPlY
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list | - Information Notice 1996-01, Potential For High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-01, Potential for High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-02, Inoperability of Power-Operated Relief Valves Masked by Downstream Indications During Testing (5 January 1996, Topic: Stroke time)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation as a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation As a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-04, Incident Reporting Requirements for Radiography Licensees (10 January 1996, Topic: Brachytherapy)
- Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel (18 January 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-06, Design & Testing Deficiencies of Tornado Dampers at Nuclear Power Plants (25 January 1996)
- Information Notice 1996-07, Slow Five Percent Scram Insertion Times Caused by Viton Diaphragms in Scram Solenoid Pilot Valves (26 January 1996)
- Information Notice 1996-08, Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate Valve (5 February 1996, Topic: Anchor Darling, Cold shutdown justification)
- Information Notice 1996-09, Damage in Foreign Steam Generator Internals (12 February 1996, Topic: Earthquake)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which Is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential For Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-12, Control Rod Insertion Problems (15 February 1996)
- Information Notice 1996-13, Potential Containment Leak Paths Through Hydrogen Analysis (26 February 1996)
- Information Notice 1996-14, Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1 (1 March 1996)
- Information Notice 1996-15, Unexpected Plant Performance During Performance of New Surveillance (8 March 1996)
- Information Notice 1996-16, BWR Operation with Indicated Flow Less than Natural Circulation (14 March 1996)
- Information Notice 1996-17, Reactor Operation Inconsistent with the Updated Final Safety Analysis Report (18 March 1996)
- Information Notice 1996-18, Compliance with 10 CFR Part 20 for Airborne Thorium (25 March 1996, Topic: Brachytherapy)
- Information Notice 1996-19, Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal (2 April 1996)
- Information Notice 1996-20, Demonstration of Associated Equipment Compliance with 10 CFR 34.20 (4 April 1996, Topic: Brachytherapy)
- Information Notice 1996-21, Safety Concerns Related to the Design of the Door Interlock Circuit on Nucletron High-Dose Rate and Pulsed Dose Rate Remote Afterloading Brachytherapy Devices (10 April 1996, Topic: Brachytherapy)
- Information Notice 1996-22, Improper Equipment Settings Due to Use of Nontemperature-Compensated Test Equipment (11 April 1996, Topic: Brachytherapy)
- Information Notice 1996-23, Fires in Emergency Diesel Generator Exciters During Operation Following Undetected Fuse Blowing (22 April 1996, Topic: Brachytherapy)
- Information Notice 1996-24, Preconditioning of Molded-Case Circuit Breakers Before Surveillance Testing (25 April 1996, Topic: Brachytherapy)
- Information Notice 1996-25, Traversing In-Core Probe Overwithdrawn at Lasalle County Station, Unit 1 (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems with Overhead Cranes (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems With Overhead Cranes (30 April 1996)
- Information Notice 1996-27, Potential Clogging of High Pressure Safety Injection Throttle Valves During Recirculation (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-28, Suggested Guidance Relating to Development and Implementation of Corrective Action (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-29, Requirements in 10 CFR Part 21 for Reporting and Evaluating Software Errors (20 May 1996, Topic: Brachytherapy)
- Information Notice 1996-30, Inaccuracy of Diagnostic Equipment for Motor-Operated Butterfly Valves (21 May 1996)
- Information Notice 1996-31, Cross-Tied Safety Injection Accumulators (22 May 1996)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (II) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (ii) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Nondestructive Examination)
- Information Notice 1996-33, Erroneous Data From Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-33, Erroneous Data from Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-34, Hydrogen Gas Ignition During Closure Welding of a VSC-24 Multi-Assembly Sealed Basket (31 May 1996)
- Information Notice 1996-35, Failure of Safety Systems on Self-Shielded Irradiators Because of Inadequate Maintenance and Training (11 June 1996)
- Information Notice 1996-36, Degradation of Cooling Water Systems Due to Icing (12 June 1996, Topic: High winds, Ultimate heat sink, Frazil ice)
- Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown (18 June 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-38, Results of Steam Generator Tube Examinations (21 June 1996)
- Information Notice 1996-39, Estimates of Decay Heat Using ANS 5.1 Decay Heat Standard May Vary Significantly (5 July 1996)
- Information Notice 1996-40, Defciencies in Material Dedication and Procurement Practices and in Audits of Vendors (7 October 1996, Topic: Coatings, Troxler Moisture Density Gauge)
- Information Notice 1996-41, Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation (26 July 1996)
- Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves (5 August 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-43, Failures of General Electric Magne-Blast Circuit Breakers (2 August 1996)
... further results |
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