Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement InstrumentsML031060366 |
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: |
01/30/1995 |
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From: |
Grimes B Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-95-008, NUDOCS 9501240226 |
Download: ML031060366 (12) |
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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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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>. |
X '..UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 January 30, 1995 NRC INFORMATION
NOTICE 95-08: INACCURATE
DATA OBTAINED WITH CLAMP-ON ULTRASONIC
FLOW MEASUREMENT
INSTRUMENTS
Addressees
All holders of operating
licenses or construction
permits for nuclear power reactors.PurDose The U.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice to alert addressees
to difficulties
in accurately
measuring
flow rates with clamp-on ultrasonic
flow measurement
instruments.
It is expected that recipients
will review the 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 or written response is required.DescriDtion
of Circumstances
O October 14, 1993, while performing
a high head safety injection (HHSI) flow balance test, the licensee for North Anna Unit 2 determined
that the as-found safety injection
cold leg branch line flow rates did not meet the technical specification
requirements.
The as-found cold leg branch line flow rates had also failed to meet the technical
specification
requirements
during the previous test in April 1992.The North Anna Technical
Specifications
give limits related to both minimum and maximum safety injection
line flow rates. For North Anna, these two technical
specification
limits resulted in an very narrow allowed operating band, which required the use of highly accurate flow measurement
instruments
for flow tests.The licensee performed
the flow balance using System 990 Uniflow Universal Transit-Time
Flowmeters
manufactured
by Controlotron
of Hauppauge, New York.The Uniflow flowmeter
is a clamp-on non-intrusive
portable flowmeter
that uses multi-pulse, transit-time
ultrasonic
technology
to measure precisely
the flow rate. The flowmeter
induces alternate
upstream and downstream
ultrasonic
signals and measures the difference
in transit times. This information
is then used to determine
the axial fluid velocity and the flow rate through the pipe. Inaccuracies
associated
with the use of these instruments
at North Anna combined with the narrow band of allowable
flows caused problems which contributed
to the failure to meet technical
specification
requirements.
P4 R I r p.# sCC 's 9501240226 UtjxW ¢ vv -31-15 lk 0 (t
v-' IN 95-08 January 30, 1995 Discussion
The licensee examined the 1993 North Anna Unit 2 flow balance test data and observed that some of the data indicated
that the instrument
errors significantly
exceeded accuracies
assumed for the tests. Numerous factors may affect the accuracy of this flowmeter
including
pipe dimensions, fluid flow effects, transducer
mounting, and instrument
setup and operation.
After the test, the licensee investigated
and concluded
that the instrument
inaccuracy
most likely was caused by flow effects associated
with the piping configuration.
The piping arrangement, which contained
several out-of-plane
bends that forced the flow to change direction
numerous times before entering the straight section of pipe containing
the ultrasonic
transducers, may have caused a stable swirl-type
flow profile corkscrewing
down the pipe. The licensee postulated
that the swirl flow added a radial flow error to the test instruments.
The flowmeter
was calibrated
assuming a primarily
axial flow profile. In subsequent
testing at a national laboratory, Controlotron
ultrasonic
flowmeter
data varied up to 5% at different
orientations
around the pipe at a position approximately
15 pipe diameters
downstream
of a single bend. The test configuration
did not include any out-of-plane
bends, indicating
that it is also possible for a non-uniform
flow profile to exist in the absence of out-of-plane
bends, causing flow measurements
with larger than expected errors.The licensee noted that the instrument
output during the test did not give any indication
of measurement
problems.
The instruments
displayed
little noise and only the expected small-magnitude
random flow fluctuations.
The lack of erratic instrument
readings could easily be interpreted
as meaning the readings were valid (i.e., within the stated accuracy).
However, the licensee tested the instrument
and determined
that it could register a stable reading while a significant
error was occurring.
Therefore, the licensee concluded that repeatability
of the data does not prove that the flow has been measured accurately.
After the test failure, the licensee found several inconsistencies
in the test data which indicated
problems in data accuracy.
As an example, when the A HHSI pump replaced the C HHSI pump as the operating
pump, without any other changes in system resistance, the B cold leg flow rate increased
by 8.4 percent while the A cold leg flow rate increased
by 1.5 percent and the C cold leg flow rate did not change. The licensee concluded
that these values corresponded
to an implausible
change in the highest cold leg flow path from loop A to loop B when the sole change was which injection
pump was operating.
In addition, the head curve for the A HHSI pump was lower than that for the
I I n-' IN 95-08 January 30, 1995 C HHSI pump; thus, the A HHSI pump would be expected to supply flow rates less than the C HHSI pump for the same system resistance.
However, the ultrasonic
instruments
indicated
that the A HHSI pump delivered
3.3 percent more flow than the C HHSI pump. This was contrary to the previously
measured pump head curve data. At the same time, installed
plant process instruments
indicated that the A HHSI pump delivered
3.4 percent less flow than the C HHSI pump, a measurement
consistent
with the pump curves.The licensee could not determine
with certainty
the factors that resulted in the unanticipated
measurement
errors in this event. Conditions
specific to an application
can cause deviations
from the vendor-supplied
instrument
accuracies.
However, during the investigation
the licensee developed
methods that could be used to determine
when the ultrasonic
flowmeter
may not yield the assumed accuracy.
These methods include comparing
ultrasonic
flowmeter data from several locations
or different
orientations
at the same location or by comparing
the data from these instruments
with data from permanently
installed
instruments.
Test results can also be compared with expected system behavior.The NRC staff has approved a request from the licensee of the North Anna plant to modify the technical
specification
that specifies
the acceptance
criteria for the HHSI pump flow rates. The change removes the specific fixed values for the flow from the technical
specifications
and permits the licensee to establish
allowable
values by analysis, providing
greater operational
flexibility.
The licensee is also planning to (1) install permanent
flow instrumentation
that will supply highly accurate data for future flow balance testing and (2) supply training concerning
the accuracy of clamp-on ultrasonic
flowmeters
to the personnel
who use them.Licensees
frequently
use flow measurements
to demonstrate
that safety-related
component
performance
is adequate to meet the demands indicated
by the accident or transient
analyses.
Therefore, obtaining
accurate flow measurements
is important
to safety. When balancing
the flow of HHSI injection
paths, flow rates need to be accurately
measured to demonstrate
that the unit complies with the assumptions
in safety analyses and is operated in an analyzed condition.
At North Anna the licensee initially
failed to detect inaccurate
flow data because of a failure to verify the consistency, repeatability
and reasonableness
of the data from the ultrasonic
flow measurement
instruments.
Although technical
specification
requirements
were not met at North Anna, the licensee later analyzed the issue and concluded that the HHSI system would have performed
its design safety function.
s '-' IN 95-08 January 30, 1995 This information
notice requires no specific action or written response.
If you have any question about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.ran K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
Technical
contacts:
Donald R. Taylor, RII Larry W. Garner, RII (703) 894-5421 (404) 331-4663 Hukam C. Garg, NRR (301) 504-2929 Attachment:
List of Recently Issued Information
Notices
.Re-ttachment
IN 95-08 January 30, Page I of 1 1995 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 95-07 Radiopharmaceutical
Vial Breakage during Preparation
01/27/95 All USNRC medical licensees authorized
to use byproduct material for diagnostic
procedures.
95-06 Potential
Blockage of Safety-Related
Strainers by Material Brought Inside Containment
01/25/95 All holders of OLs or CPs for nuclear power reactors.95-05 Undervoltage
Protection
Relay Settings Out of Tolerance
Due to Test Equipment
Harmonics 01/20/95 All holders Permits for reactors.of Construction
nuclear power 95-04 95-03 Excessive
Cooldown and Depressurization
of the Reactor Coolant System Following
a Loss of Offsite Power Loss of Reactor Coolant Inventory
and Potential Loss of Emergency
Mitiga-tion Functions
While in a Shutdown Condition Problems with General Electric CR2940 Contact Blocks in Medium-Voltage
Circuit Breakers DOT Safety Advisory: High Pressure Aluminum Seamless and Aluminum Composite
Hoop-Wrapped
Cylinders 01/19/95 01/18/95 01/17/95 01/04/95 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 U.S. Nuclear Regulatory
Commission
licensees.
95-02 95-01 OL -Operating
License CP = Construction
Permit
> S 95-08 January 30, 1995 This information
notice requires no specific action or written response.
If you have any question about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Original signed by Brian K. Grime!Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
Technical
contacts: Donald R. Taylor, RII (703) 894-5421 Larry W. Garner, RII (404) 331-4663 Hukam C. Garg, NRR (301) 504-2929 Attachment:
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Notices DOCUMENT NAME: 95-08.IN NOTE: VENDOR COMMENTS RECEIVED, NO SIGNIFICANT
CHANGES WERE MADE OFFICE *RPB:ADM by Email *OGCB:DORS
Phoncon ,AME TechEd AJKugler DRTaylor LWGarner DATE 09/07/94 09/13/94 09/22/94 09/22/94 OFFICE *DRP:RI Iby Phoncon *HICB:DRCH
HCGarg JSWermiel
BABoger DATE 09/27/94 09/, W94 / 09/22/94 09/22/94 OFFICE C/OECB:DOPS
OP /NAME AEChaffee*
Arxi es DATE 11 /22/94 01&1y 95 T OFFICIAL RECORD COPY
-IN 95-XX January XX, 1995 This information
notice requires no specific action or written response.
If you have any question about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
Technical
contacts:
Donald R. Taylor, RII (703) 894-5421 Larry W. Garner, RI!(404) 331-4663 Hukam C. Garg, NRR (301) 504-2929 Attachment:
List of Recently Issued Information
Notices DOCUMENT NAME: S:\DOPS_SEC\CLAMP-ON.INR
mnTE- VENDOR COMMENTS RFCFTVFD NO SIGNIFICANT
CHANGES WERE MADE OFFICE *RPB:ADM by Emai t *OGCB:DORS
Phoncon NAME TechEd AJKugler DRTaylor LWGarner DATE 09/07/94 09/13/94 09/22/94 09/22/94 OFFICE *DRP: RIIby Phoncon *HICB:DRCH
HCGarg JSWermiel
BABoger DATE 09/27/94 09/19/94 09/22/94 09/22/94 OFFICE C/OECB:DOPS
D/DOPS NAME AEChaffee*
BKGrimes DATE 11/22/94 11/ /94 _ _ _ _=OFFICIAL RECORD COPY
<-/IN 94-XX November XX, 1994 This information
notice requires no specific action or written response.
If you have any question about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
Technical
contacts:
'onald R. Taylor, RII (70 ) 894-5421 Lar y W. Garner, RII (40 ) 331-4663 Huk C. Garg, NRR (30 ) 504-2929 Attachment:
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Notices DOCUMENT NAME: S:\DOPSSEC\CLAMP-ON.INR
MnTr- vrTnnn rnMMFNTq RFCFIVFED
NO SIGNIFICANT
CHANGES WERE MADE OFFICE *RPB:ADM by EmaiL *OGCB:DORS
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HCGarg JSWermiel
BABoger DATE 09/27/94 09/19/94 09/22/94 09/22/94 OFFICE C/OECB:DOPS
D/DOPS NAME AEChaffee*
BKGrimes _ _, 11/22/94 11/ /94 OFFICIAL RECORD COPY
IN 94-XX November XX, 1994 This information
notice requires no specific action or written response.
If you have any question about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
Technical
contacts: Donald R. Taylor, RII (703) 894-5421 Larry W. Garner, RII (404) 331-4663 Hukam C. Garg, NRR (301) 504-2929 Attachment:
List of Recently Issued Information
Notices NOTF VFNDOR COMMENTS RECEIVED.
NO SIGNIFICANT
CHANGES WERE MADE OFFICE *RPB:ADM by Email *OGCB:DORS
Phoncon NAME TechEd AJKugler DRTaylor LWGarner DATE 09/07/94 09/13/94 09/22/94 09/22/94 OFFICE *DRP:RIIby
Phoncon *HICB:DRCH
HCGarg JSWermiel
BABoger DATE 09/27/94 09/19/94 09/22/94 09/22/94 OFFICE C/OECB:DOPS
D/DOPS NAME AEf ffeBKGrimes
DATE 11/2494 Af 11/ /94 __I DOCUMENT NAME: G:\IN\CLAMP-0N.INK
IN 94-XX November XX, 1994 This information
notice requires no specific action or written response.
If you have any question about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
Technical
contacts: Donald R. Taylor, RII (703) 894-5421 Larry W. Garner, RII (404) 331-4663 Hukam C. Garg, NRR (301) 504-2929 Attachment:
List of Recently Issued NRC Information
Notices NOTE: VENDOR COMMENTS RECEIVED, NO SIGNIFICANT
CHANGES WERE MADE OFFICE *RPB:ADM by Email *OGCB:DORS
Phoncon NAME TechEd AJKugler DRTaylor LWGarner DATE 09/07/94 09/13/94 09/22/94 09/22/94 OFFICE *DRP:RII by Phocon *HICB:DRCH
HCGarg JSWermiel
BABoger DATE09/27/94
09/19/94 09/22/94 09/22/94 OFFICE C/OECB:DOPS
D/DOPS NAME AEChaffee
BKGrimes DATE .11/ /94 DOCUMENT NAME: t:\IN\CLAMP-ON.IN
IN 94-XX September
XX, 1994 This information
notice requires no specific action or written response.
If you have any question about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: Donald R. Taylor, RII (703) 894-5421 Larry (404)W. Garner, RII 331-4663 Hukam (301)C. Garg, NRR 504-2929 Attachment:
List of Recently Issued Information
Notices OFFICE *RPB:ADM by Emal OGCB:DORS
RII DRP:RII NAME TechEd jAJKugler
j DRTaylor LWGarner DATE 09/07/94 09/13/94 09/ /94 09/ /94 OFFICE DRP:RII HICB: C/HICB:DRCH
D/DRH_NAME DMVerrelli
HCGar ^ JSWermieltior
DATE 09/ /94 09///94 _J09/22/94 O9/il/94 OFFICE C/OGCB:DORS
D/DORS NAME ELDoolittle
BKGrimes DATE 09/ /94 09/ /94 tt1 /2.
IN 94-XX September
XX, 1994 This information
notice requires no specific action or written response.
If you have any question about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: Uonald R. Taylor, RII (703) 894-5421 Larry W. Garner, RII (404) 331-46E3 Hukam C. Garg, NRR (301) 504-2929 Attachment:
List of Recently Issued Information
Notices OFFICE *RPB:ADM EMA)L OGCB:DORS
RII DRP:RII NAME TechEd AJKu ler DRTaylor LWGarner DATE 09/07/94 09/13/94 09/ /94 09/ /94 OFFICE DRP:RII HICB:DRCH
C/HICB:DRCH
D/DRCH NAME DMVerrelli
HCGarg JSWermiel
BABoger DATE 09/ /94 09/ /94 09/ /94 09/ /94 OFFICE C/OGCB:DORS
D/DORS NAME ELDoolittle
BKGrimes II DATE 09/ /94 09/ /394
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list | - Information Notice 1995-01, DOT Safety Advisory: High Pressure Aluminum Seamless and Aluminum Composite Hoop-Wrapped Cylinders (4 January 1995, Topic: Brachytherapy)
- Information Notice 1995-02, Problems With General Electric CR2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems With General Electric Cr2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems with General Electric CR2940 Contact Blocks in Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-03, Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition (18 January 1995, Topic: Packing leak)
- Information Notice 1995-04, Excessive Cooldown and Depressurization of the Reactor Coolant System Following Loss of Offsite Power (11 October 1996, Topic: Safe Shutdown, Shutdown Margin, Probabilistic Risk Assessment, Troxler Moisture Density Gauge)
- Information Notice 1995-05, Undervoltage Protection Relay Settings Out of Tolerance Due to Test Equipment Harmonics (20 January 1985)
- Information Notice 1995-06, Potential Blockage of Safety-Related Strainers by Material Brought Inside Containment (25 January 1995, Topic: Foreign Material Exclusion)
- Information Notice 1995-07, Radiopharmaceutical Vial Breakage During Preparation (27 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained With Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-09, Use of Inappropriate Guidelines and Criteria for Nuclear Piping and Pipe Support Evaluation and Design (31 January 1995)
- Information Notice 1995-10, Potential for Loss of Automatic Engineered Safety Features Actuation (3 February 1995)
- Information Notice 1995-11, Failure of Condensate Piping Because of Erosion/Corrosion at Flow-Straightening Device (24 February 1995)
- Information Notice 1995-12, Potentially Nonconforming Fasteners Supplied by A&G Engineering II, Inc (21 February 1995)
- Information Notice 1995-13, Potential for Data Collection Equipment to Affect Protection System Performance (24 February 1995)
- Information Notice 1995-14, Susceptibility of Containment Sump Recirculation Gate Valves to Pressure Locking (28 February 1995)
- Information Notice 1995-15, Inadequate Logic Testing of Safety-Related Circuits (7 March 1995)
- Information Notice 1995-16, Vibration Caused by Increased Recirculation Flow in a Boiling Water Reactor (9 March 1995)
- Information Notice 1995-17, Reactor Vessel Top Guide and Core Plate Cracking (10 March 1995, Topic: Safe Shutdown)
- Information Notice 1995-18, Potential Pressure-Locking of Safety-Related Power-Operated Gate Valves (15 March 1995)
- Information Notice 1995-19, Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch Mechanism (22 March 1995)
- Information Notice 1995-20, Failures in Rosemount Pressure Transmitters Due to Hydrogen Permeation Into Sensor Cell (22 March 1995)
- Information Notice 1995-21, Unexpected Degradation of Lead Storage Batteries (20 April 1995)
- Information Notice 1995-22, Hardened or Contaminated Lubricant Cause Metal-Clad Circuit Breaker Failures (21 April 1995)
- Information Notice 1995-23, Control Room Staffing Below Minimum Regulatory Requirements (24 April 1995)
- Information Notice 1995-24, Summary of Licensed Operator Requalification Inspection Program Findings (25 April 1995, Topic: Job Performance Measure, License Renewal)
- Information Notice 1995-25, Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit (11 May 1995)
- Information Notice 1995-26, Defect in Safety-Related Pump Parts Due to Inadequate Treatment (31 May 1995)
- Information Notice 1995-27, NRC Review of Nuclear Energy Institute, Thermo-Lag 330-1 Combustibility Evaluation Methodology Plant Screening Guide. (31 May 1995, Topic: Safe Shutdown, Fire Barrier, Exemption Request, Fire Protection Program)
- Information Notice 1995-28, Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites (5 June 1995, Topic: Safe Shutdown, Tornado Missile, Safe Shutdown Earthquake, Earthquake)
- Information Notice 1995-29, Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems (7 June 1995, Topic: Nondestructive Examination)
- Information Notice 1995-30, Susceptibility of Low-Pressure Coolant Injection Valves to Pressure Locking (3 August 1995, Topic: Hydrostatic, Power-Operated Valves)
- Information Notice 1995-31, Motor-Operated Valve Failure Caused by Stem Protector Pipe Interference (9 August 1995)
- Information Notice 1995-32, Thermo-Lag 330-1 Flame Spread Test Results (10 August 1995, Topic: Fire Barrier)
- Information Notice 1995-33, Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3 (23 August 1995)
- Information Notice 1995-34, Air Actuator and Supply Air Regulator Problems in Copes-Vulcan Pressurizer Power-Operated Relief Valves (25 August 1995)
- Information Notice 1995-35, Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation (28 August 1995)
- Information Notice 1995-36, Potential Problems with Post-Fire Emergency Lighting (29 August 1995, Topic: Safe Shutdown, Emergency Lighting, Exemption Request)
- Information Notice 1995-37, Inadequate Offsite Power System Voltages During Design-Basis Events (7 September 1995)
- Information Notice 1995-38, Degradation of Boraflex Neutron Absorber in Spent Fuel Storage Racks (8 September 1995)
- Information Notice 1995-39, Brachytherapy Incidents Involving Treatment Planning Errors (19 September 1995, Topic: Brachytherapy)
- Information Notice 1995-40, Supplemental Information to Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes. (20 September 1995, Topic: Hydrostatic, Nondestructive Examination, Brachytherapy)
- Information Notice 1995-41, Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam Generators (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-42, Commission Decision on Resolution of Generic Issue 23, Reactor Coolant Pump Seal Failure. (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-43, Failure of Bolt-Locking Device on Reactor Coolant Pump Turning Vane (28 September 1995, Topic: Brachytherapy)
- Information Notice 1995-44, Ensuring Compatible Use of Drive Cables Incorporating Industrial Nuclear Company Ball-Type Male Connectors (26 September 1995, Topic: Brachytherapy)
- Information Notice 1995-45, American Power Service Falsification of American Society for Nondestructive Testing Certificates (4 October 1995, Topic: Brachytherapy)
- Information Notice 1995-46, Unplanned, Undetected Release of Radioactivity from the Exhaust Ventilation System of a Boiling Water Reactor (6 October 1995, Topic: Brachytherapy)
- Information Notice 1995-47, Unexpected Opening of a Safety/Relief Valve & Complications Involving Suppression Pool Cooling Strainer Blockage (30 November 1995)
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