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 Date of
Notice No. Subject Issuance Issued to
96-57 Incident-Reporting Require- 10/30/96 All U.S. Nuclear Regulatory
ments Involving Intakes, Commission licensees
During a 24-Hour Period
that May Cause a Total
Effective Dose Equivalent
in Excess of 0.05 Sv (5 rem)
96-54 Vulnerability of Stainless 10117/96 All material licensees
Steel to Corrosion When
Sensitized
96-53 Retrofit to Amersham 660 10/15/96 All industrial radiography
Posilock Radiography licensees
Camera to Correct Incon- sistency in 10 CFR Part 34 Compatibility
96-52 Cracked Insertion Rods 09/26/96 All U.S. Nuclear Regulatory
on Troxler Model 3400 Commission portable gauge
Series Portable Moisture licensees and vendors
Density Gauges
96-51 Residual Contamination 09/11/96 All material licensees
Remaining in Krypton-85 Handling System After
Venting
96-47 Recordkeeping, Decommis- 08/19196 All U.S. Nuclear Regulatory
sioning Notifications for Commission licensees
Disposals of Radioactive
Waste by Land Burial
Authorized Under Former
10 CFR 20.304, 20.302, and Current 20.2002
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 Potential Failure of the 11/20/96 All holders of OLs
Instantaneous Trip Function and CPs for nuclear
of General Electric RMS-9 power plants
Programmers
96-61 Failure of a Main Steam Safety 11/20/96 All holders of OLs or
Valve to Reseat Caused by an CPs for nuclear power
Improperly Installed Release reactors
Nut
96-60 Potential Common-Mode Post- 11/14/96 All holders of OLs or
Accident Failure of Residual CPs for nuclear power
Heat Removal Heat Exchangers reactors
96-59 Potential Degradation of 10/30/96 All holders of OLs or
Post Loss-of-Coolant CPs for nuclear power
Recirculation Capability reactors
as a Result of Debris
96-58 RCP Seal Replacement with 10/30/96 All holders of OLs or
Pump on Backseat CPs for pressurized-water
reactors
96-57 Incident-Reporting Require- 10/29/96 All U.S. Nuclear
ments Involving Intakes, Regulatory Commission
During a 24-Hour Period licensees
That May Cause a Total
Effective Dose Equivalent
in Excess of 0.05 Sv
(5 rems)
OL = Operating License
CP = Construction Permit
IN 96-63 K> 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* Ic 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 lI SFP t I l- I I
NAME KRamsey CJH_ ney
DATE 1/27/96 W215196 Ia;v4 i _ _
N L S R
CO E & ENCLOSURE OC
C_ CO
C =COVER E EE= COVER 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 * c NRR/OECBh* I c OGCN lc TEditor I
NAME RLewis:LMG EEaston SShankman AEChaffee ENJenson EKraus *
DATE I 10/10/96 I 10/10/96 I--
I 10/10/96 I 10/10/96 1 11/25/96 1 11/25/96 OFC IMOB I SFP I l _ lL,/
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
LO#% IV.
I J.JIIAIgU
I(V
- ITO'I- l &.10
& I I 0 la;: I
1J1_IUa 1lIdav IIU I ,
Iva %
- II I
I I/on
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* Ic 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 I
FlO 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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