Potential Blockage by Debris of Safety System Piping Which Is Not Used During Normal Operation or Tested During SurveillancesML031060270 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 03500354, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
02/13/1996 |
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From: |
Crutchfield D Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-96-010, NUDOCS 9602070259 |
Download: ML031060270 (11) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 03500354, 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 [[: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 [[:03500354]] 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 [[: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 [[:03500354]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
14 UNITED STATES
NUCLEAR REGULATORY COMMISSION
- ' OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 February 13, 1996 NRC INFORMATION NOTICE 96-10: POTENTIAL BLOCKAGE BY DEBRIS OF SAFETY SYSTEM
PIPING WHICH IS NOT USED DURING NORMAL
OPERATION OR TESTED DURING SURVEILLANCES
Addressees
nuclear power
All holders of operating licenses or construction permits for
reactors.
Purpose
information
The U.S. Nuclear Regulatory Commission (NRC) is issuing this by debris, of
notice to alert addressees to the potential for the blockage, safety system piping in boiling-water reactors (BWRs) or pressurized-water
the information
reactors (PWRs). It is expected that recipients will review as appropriate, to
for applicability to their facilities and consider actions, this information
avoid similar problems. However, suggestions contained in or written
notice are not NRC requirements; therefore, no specific action
response is required.
notice was the
The source of the information--contained in this information Economic Cooperation
incident reporting system (IRS) of the Organization for
Agency. The Spanish regulatory staff
and Development Nuclear Energy
authorized public dissemination of this information.
Description of Circumstances
are usually
During refueling outages at PWRs in Spain, containment sumps inlet pipes
inspected visually to ensure that the sump, screens, and suction
and that the
in the emergency core cooling system (ECCS) are free of debris, sumps screens are not corroding.
its containment
In November 1993, the licensee of a PWR in Spain inspected it unusual
sumps during outage surveillance. The licensee did not consider to the sump
for the sumps to contain water because there is some leakage the ECCS borated
during functional testing of a three-way valve which connects the individual
tanks with the containment sumps. However, in this case, dirty, so he had it
inspecting the sump believed that the water was unusually that three of the
siphoned off. Once the water had been removed, he could seefor the ECCS. A
four sumps had debris in the bottom below the suction pipe two of the four
closer examination of the ECCS suction lines revealed that
960pt70259
\Jk Jtr, 31 jib
iLR I
fi
IN 96-10
February 13, 1996 ECCS lines taking suction from the sumps were partially blocked by debris.
One of the two partially blocked lines had almost half the flow area of the
pipe blocked off; the other was blocked less. It is believed that the debris
had been there since the plant was commissioned, and that this event demon- a
strated a significant failure of the surveillance program. Figure 1 shows
cross-sectional view of the sump and indicates where the debris was found.
Upon further review, the Spanish regulators noted that there are no technical
specification requirements to inspect the piping from the containment sumps to
the ECCS to ensure that it is clear of any obstruction by debris. It was also
noted that many sections of piping on safety systems in both PWRs and BWRs are
only called upon to function during accident conditions, and are not used
during normal operation or tested during functional surveillance tests.
Confidence in the operability of these pipes was based on the fact that they
had not been used since they were tested before plant startup.
In response to the event, Spanish regulators issued a generic letter which
asked their licensees to take four actions. First, they were requested to
establish administrative controls, including a locking device, on the sump
hatch and on any other removable sump parts (PWRs only). Second, they were
requested to inspect the containment sump and the piping between the sump and
the first ECCS valve which separates the part of the system that is
functionally tested from the part that is not (PWRs only). Third, they were
requested to inspect the sump every refueling outage. If more than 1 kilogram
of debris was found in the sump, licensees were then requested to reinspect
the piping between the sump and the functionally tested portion of the ECCS
(PWRs only). And fourth, licensees were requested to identify piping segments
of safety systems through which flow does not occur, either during normal
operation or during surveillance testing, and to analyze whether there are
reasonable guarantees that no obstruction exists (BWRs and PWRs). Examples of
the piping segments that would require this analysis are crossover piping from
the essential service cooling system to the auxiliary feedwater system (PWRs),
relief valve discharge piping (PWRs), low-pressure coolant injection suction
piping from the condensate storage tank (BWRs), and crossover connections
between low-pressure coolant injection trains (BWRs).
Discussion
The licensee in this case concluded that the safety significance of this event
was small because the partial blockage of the lines would not prevent the ECCS
from providing sufficient core cooling. However, it was also noted that some
of the debris could have been entrained in the water flow and could have
detrimental effects on other parts of the system (e.g., pump and valve
components and heat exchangers). The licensee initial corrective actions
(prior to issuance of the generic letter) included cleaning up the sumps and
. -. . 4 v>
IN 96-10
February 13, 1996 suction lines, locking sump hatches, and establishing administrative controls.
These corrective actions address the root cause of the presence of debris in
the sump and suction line.
It has been noted in previous NRC generic communications that debris could
prevent such safety systems as the ECCS from functioning reliably throughout a
design-basis accident. These previous NRC communications have dealt with the
potential for debris to clog the ECCS strainers (operational debris, loss-of- coolant-accident-generated debris, or a combination of both). The debris
described in this information notice is another example of the potential
fordebris to impair the operation of safety systems. Although the licensee in
this case has determined that the debris found in its sump was insufficient to
prevent the ECCS from performing its safety function, such debris could damage
individual components of the safety system (e.g., pumps), degrade system
performance, or (in combination with the debris generated during a loss-of- coolant accident) could accelerate a loss of net positive suction head for the
ECCS pumps.
Related Generic Communications
Cooling Suction Strainers," dated May, 11, 1993, and February 18, 1994.
Cooling Systems Caused by Foreign Material Blockage," dated
December 23, 1992.
Strainers at a Foreign BWR," dated September 30, 1992.
and Incorrect Screen Configurations," dated November 21, 1989.
Piping Systems," dated November 16, 1988.
Recirculation Capability Due to Insulation Debris Blockage," dated
May 19, 1988.
K>
IN 96-10
February 13, 1996 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below.
e s .Crut r
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Eric J. Benner, NRR
(301) 415-1171 Internet:ejbl@nrc.gov
Robert B. Elliott, NRR
(301) 415-1397 Internet:rbe@nrc.gov
Attachments:
1. Figure 1: Scheme of Containment Sump
2. List of Recently Issued NRC Information Notices
4~N 5ZJ*4 rj
.I
FIGURE 1. Scheme of containment sump
Strainer Inspection hatch Concrete
.
- A A -- A
A _
A A A
a CO D (Dl
03 CD C+(
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-a),
(D I a)
to :r '
a 01-= o
'-< 0 CD
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Attachment 2 IN 96-10
February 13, 1996 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
96-09 Damage in Foreign Steam 02/12/96 All holders of OLs or CPs
Generator Internals for pressurized water
reactors
96-08 Thermally Induced Pres- 02/05/96 All holders of OLs or CPs
sure Locking of a High for nuclear power reactors
Pressure Coolant Injec- tion Gate Valve
96-07 Slow Five Percent Scram 01/26/96 All holders of OLs or CPs
Insertion Times Caused for boiling water reactors
By Viton Diaphragms in
Scram Solenoid Pilot
Valves
96-06 Design and Testing 01/25/96 All holders of OLs or CPs
Deficiencies of Tornado for nuclear power reactors
Dampers at Nuclear Power
Plants
96-05 Partial Bypass of Shutdown 01/18/96 All holders of OLs or CPs
Cooling Flow from the for boiling water reactors
Reactor Vessel
96-04 Incident Reporting Require- 01/10/96 All radiography licensees
ments for Radiography and manufacturers of radio- Licensees graphy equipment
96-03 Main Steam Safety Valve 01/05/96 All holders of OLs or CPs
Setpoint Variation as a for nuclear power reactors
Result of Thermal Effects
OL = Operating License
CP = Construction Permit
<I
IN 96-10
February 13, 1996 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Eric J. Benner, NRR
(301) 415-1171 Internet:ejbl@nrc.gov
Robert B. Elliott, NRR
(301) 415-1397 Internet:rbe@nrc.gov
Attachments:
1. Figure 1: Scheme of Containment Sump
2. List of Recently Issued NRC Information Notices
Reviewed and concurred on by tech editor 12/18/95 IN faxed to Jose Villadoniga of Consejo De Seguiridad on 2/6/96.
IN concurred on by Bill Upshaw of International Programs on 1/4/95 Reviewed by Mike Cullingford on 2/6/96.
DOCUMENT NAME: 96-1O.IN
To receive a copy of this document, Indicate In the box: AC" - Copy without enclosures 'E' - Copy with enclosures "N' - No copy
OFFICE TECH CONTS I SCSB:DSSA I PECB:DRPM I D:4PM IP
NAME EBenner* CBerlinger* AChaffee* D4 d
DATE 01/03/96 01/16/96 01/18/96 02/ /96 OFFICIAL RECORD COPY
IN 96-xx
February xx, 1996 potential for foreign material to impact operation of safety systems.
Although the licensee in this case has determined that the debris found in
their sump was insufficient to prevent the ECCS from performing its safety
function, such this debris could damage individual components of the safety
system (e.g., pumps), degrade system performance or, in combination with the
debris generated during a loss-of-coolant accident, could accelerate a loss of
net positive suction head for the ECCS pumps.
Related Generic Communications
NRC Bulletin 93-02 and Supplement 1: 'Debris Plugging of Emergency Core
Cooling Suction Strainers," dated May, 11, 1993, and February 18, 1994.
Cooling Systems Caused by Foreign Material Blockage," dated
December 23, 1992.
Strainers at a Foreign BWR," dated September 30, 1992.
and Incorrect Screen Configurations," dated November 21, 1989.
Piping Systems," dated November 16, 1988.
Recirculation Capability Due to Insulation Debris Blockage," dated
May 19, 1988.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Eric J. Benner, NRR
(301) 415-1171 Internet: EJBINRC.GOV
Robert B. Elliot, NRR
(301) 415-1397 Internet: RBE@NRC.GOV
Attachments:
1. Figure 1: Scheme of Containment Sump
2. List of Recently Issued NRC Information Notices
Reviewed and concurred on by tech editor 12/18/95 IN concurred on by Bill Upshaw of International Programs on 1/4/95
DOCUMENT NAME: G:\EJB1\FOREIGN.IN
To receive a copy of this document, Indicate hi the box: 'C' . Copy without enclosures 'E' = Copy with enclosures 'N' - No copy
OFFICE PECB:DRPM I C SC/PECB:DRPM I N C SCSB:DSSA I E C/PECB:DRPM C DRPM I
NEBenner* EGoodwin* CBerlinger* IAChaffee* DCrutchfield
DATE 1/3/96 1/4/96 01/16/96 01/18/96 01/ /96 OFFICIAL RECORD COPY hID PA..
ANr96-xx
January xx, 1996 example of the potential for foreign material to impact operation the of safety
systems. Although the licensee in this case has determined that debris
found in their sump was insufficient to prevent the ECCS from performing its
safety function, it is important to realize that this debris could damage
individual components of the safety system (e.g., pumps), degradea system loss-of- performance or, in combination with the debris generated during
coolant accident, could accelerate a loss of net positive suction head for the
ECCS pumps.
Related Generic Communications
Cooling Systems Caused by Foreign Material Blockage"
Cooling Suction Strainers"
Strainers at a Foreign BWRN
and Incorrect Screen Configurations"
Piping Systems"
Recirculation Capability Due to Insulation Debris Blockage"
This information notice requires no specific action or writtenplease response. If
you have any questions about the information in this notice, contact
one of the technical contacts listed below.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Eric J. Benner, NRR
(301) 415-1171 Internet: EJBINRC.GOV
Robert B. Elliot, NRR
(301) 415-1397 Internet: RBE@NRC.GOV
Reviewed and concurred on by tech editor 12/18/95 IN concurred on by Bill Upshaw of International Programs on 1/4/95
DOCUMENT NAME: G:\EJB1\FOREIGN.IN No copy
To receive acopy of this document. Indicate In the box: wC" - Copy without enclosures 'E' - Copy with enclosures N -
IPECB:DRPM I C SC/PECB:DRPM I N C/SCSB:DSSA I E C/PECE PM C DRPM I
OFFICE
NAME IEBenner* IEGoodwin* CBerlinger* ACha %DCrutchfield
DATE 1/3/96 1/4/96 01/16/96 01/f /96 J-% 01/ /96 OFFICiAL RECORD COPY
December xx, 1995 example of the potential for foreign material to impact operation of safety
systems. Although the licensee in this case has determined that the debris
found in their sump was insufficient to prevent the ECCS from performing its
safety function, it is important to realize that this debris could damage
individual components of the safety system (e.g., pumps), degrade system
performance or, in combination with the debris generated during a loss-of- coolant accident, could accelerate a loss of net positive suction head for the
ECCS pumps.
Related Generic Communications
Cooling Systems Caused by Foreign Material Blockage"
Cooling Suction Strainers'
Strainers at a Foreign BWRE
and Incorrect Screen Configurations"
Piping Systems"
Recirculation Capability Due to Insulation Debris Blockage"
This ; information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Tech nical contact: Eric J. Benner, NRR
(301) 415-1171 2/s77 /B~77A.
E-mail: EJB1@NRC.GOV
Robert B. Elliot, NRR
(301) 415-1397 E-mail: RBE@NRC.GOV
Reviewed and concurred on by tech editor 12/18/95 IN concurred on by Bill Upshaw of International Programs on 1/4/95
DOCUMENT NAME: G:\EJB1\FOREIGN.IN
Tn rvaei a*nnv documnnt. Indlenta In the box: 'C'
nf Mthis = Coov without enclosures 'E' - Coov with enclosures 'N' - No copy
I
OFFICE
'NAME
Contacts
EEGoodwin*
.C SC/PECB:DRPM I N
}CB[I 1 CC/SCSB:gA
I EC/PECB:DRPM
AChaffee
I lC/RPM
DCrutchfield
DATE 1/3/96 1/ /96 1/4/96 96 l 017e/ /96 01/ /96 OFFICIAL RECORD COPY
\t95-xx
December xx, 1995 example of the potential for foreign material to impact operation of safety
systems. Although the licensee in this case has determined that the debris
found in their sump was insufficient to prevent the ECCS from performing its
safety function, it is important to realize that this debris could damage
individual components of the safety system (e.g., pumps), degrade system
performance or, in combination with the debris generated during a loss-of- coolant accident, could accelerate a loss of net positive suction head for the
ECCS pumps.
Related Generic Communications
Cooling Systems Caused by Foreign Material Blockage"
Cooling Suction Strainers"
Strainers at a Foreign BWR"
and Incorrect Screen Configurations"
Piping Systems"
Recirculation Capability Due to Insulation Debris Blockage"
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Eric J. Benner, NRR
(301) 415-1171 E-mail: EJBINRC.GOV
Robert B. Elliot, NRR
(301) 415-1397 E-mail: RBE@NRC.GOV
Reviewed and concurred on by tech editor 12j18/95 Use of Spanish documentation for IN approved by Bill Upshaw of International
Programs on 1/3/95 DOCUMENT NAME: G:\EJB1\FOREIGN.IN
To receive a copy of this document, indicate Inthe box: "C" *= Copy without enclosures 'E" =Copy with enclosures 'N" - No copy
OFFICE PECB:DRPM SC/PECB:DRPM I C/SCSB:DSSA I -C/PECB:DRPM l C/DRPM Il
INAME EBenner ith5 IEGoodwink,. ICBerlinger AChaffee DCrutchfield
DATE 01/1 /96 U 01/ /96 101/ /96 01/ /96 01/ /96 OFFICIAL RECORD COPY
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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)
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