Information Notice 1995-08, Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments: Difference between revisions

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{{#Wiki_filter:X '..UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555January 30, 1995NRC INFORMATION NOTICE 95-08: INACCURATE DATA OBTAINED WITH CLAMP-ONULTRASONIC FLOW MEASUREMENT INSTRUMENTS
{{#Wiki_filter: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==
==Addressees==
All holders of operating licenses or construction permits for nuclear powerreactors.PurDoseThe U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice to alert addressees to difficulties in accurately measuring flow rateswith clamp-on ultrasonic flow measurement instruments. It is expected thatrecipients will review the information for applicability to their facilitiesand 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 CircumstancesO October 14, 1993, while performing a high head safety injection (HHSI) flowbalance test, the licensee for North Anna Unit 2 determined that the as-foundsafety injection cold leg branch line flow rates did not meet the technicalspecification requirements. The as-found cold leg branch line flow rates hadalso failed to meet the technical specification requirements during theprevious test in April 1992.The North Anna Technical Specifications give limits related to both minimumand maximum safety injection line flow rates. For North Anna, these twotechnical specification limits resulted in an very narrow allowed operatingband, which required the use of highly accurate flow measurement instrumentsfor flow tests.The licensee performed the flow balance using System 990 Uniflow UniversalTransit-Time Flowmeters manufactured by Controlotron of Hauppauge, New York.The Uniflow flowmeter is a clamp-on non-intrusive portable flowmeter that usesmulti-pulse, transit-time ultrasonic technology to measure precisely the flowrate. The flowmeter induces alternate upstream and downstream ultrasonicsignals and measures the difference in transit times. This information isthen used to determine the axial fluid velocity and the flow rate through thepipe. Inaccuracies associated with the use of these instruments at North Annacombined with the narrow band of allowable flows caused problems whichcontributed to the failure to meet technical specification requirements.P4 R I r p.# sCC 's9501240226UtjxW ¢ vv -31-15 lk 0 (t
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:
List of Recently Issued Information
 
Notices DOCUMENT NAME: 95-08.IN NOTE: VENDOR COMMENTS RECEIVED, NO SIGNIFICANT
 
CHANGES WERE MADE OFFICE *RPB:ADM by Email *OGCB:DORS
 
*RIIby Phoncon *DRP:RIIby
 
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
 
*C/HICB:DRCH
 
*D/DRCH NAME DMVerrelli
 
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
 
*RIIby Phoncon *DRP:RIIby
 
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
 
*C/HICB:DRCH
 
*D/DRCH KANE DMVerrelli
 
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:
List of Recently Issued Information
 
Notices DOCUMENT NAME: S:\DOPSSEC\CLAMP-ON.INR
 
MnTr- vrTnnn rnMMFNTq RFCFIVFED
 
NO SIGNIFICANT
 
CHANGES WERE MADE OFFICE *RPB:ADM by EmaiL *OGCB:DORS
 
*RI Iby Phoncon *DRP:RI Iby Phoncon NAME TechEd AJKugler DRTaylor LWGarner DATE 09/07/94 09/13/94 09/22/94 09/22/94 OFFICE *DRP:RI Iby Phomon *HICB:DRCH
 
*C/HICB:DRCH
 
*D/DRCH OMWE DMVerrelli
 
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
 
*RIIby Phoncon *DRP:RIIby
 
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
 
*C/HICB:DRCH
 
*D/DRCH NAME DMVerrelli
 
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
 
*RIIby Phoncon *DRP:RIIby
 
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
 
*C/HICB:DRCH
 
*D/DRCH NAME DMVerrelli
 
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


v-' IN 95-08January 30, 1995 DiscussionThe licensee examined the 1993 North Anna Unit 2 flow balance test data andobserved that some of the data indicated that the instrument errorssignificantly exceeded accuracies assumed for the tests. Numerous factors mayaffect the accuracy of this flowmeter including pipe dimensions, fluid floweffects, transducer mounting, and instrument setup and operation. After thetest, the licensee investigated and concluded that the instrument inaccuracymost likely was caused by flow effects associated with the pipingconfiguration. The piping arrangement, which contained several out-of-planebends that forced the flow to change direction numerous times before enteringthe straight section of pipe containing the ultrasonic transducers, may havecaused a stable swirl-type flow profile corkscrewing down the pipe. Thelicensee postulated that the swirl flow added a radial flow error to the testinstruments. The flowmeter was calibrated assuming a primarily axial flowprofile. In subsequent testing at a national laboratory, Controlotronultrasonic flowmeter data varied up to 5% at different orientations around thepipe at a position approximately 15 pipe diameters downstream of a singlebend. 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 inthe absence of out-of-plane bends, causing flow measurements with larger thanexpected errors.The licensee noted that the instrument output during the test did not give anyindication of measurement problems. The instruments displayed little noiseand only the expected small-magnitude random flow fluctuations. The lack oferratic instrument readings could easily be interpreted as meaning thereadings were valid (i.e., within the stated accuracy). However, the licenseetested the instrument and determined that it could register a stable readingwhile a significant error was occurring. Therefore, the licensee concludedthat repeatability of the data does not prove that the flow has been measuredaccurately.After the test failure, the licensee found several inconsistencies in the testdata which indicated problems in data accuracy. As an example, when theA HHSI pump replaced the C HHSI pump as the operating pump, without any otherchanges in system resistance, the B cold leg flow rate increased by8.4 percent while the A cold leg flow rate increased by 1.5 percent and theC cold leg flow rate did not change. The licensee concluded that these valuescorresponded to an implausible change in the highest cold leg flow path fromloop 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
Notices OFFICE *RPB:ADM EMA)L OGCB:DORS


I In-' IN 95-08January 30, 1995 C HHSI pump; thus, the A HHSI pump would be expected to supply flow rates lessthan the C HHSI pump for the same system resistance. However, the ultrasonicinstruments indicated that the A HHSI pump delivered 3.3 percent more flowthan the C HHSI pump. This was contrary to the previously measured pump headcurve data. At the same time, installed plant process instruments indicatedthat the A HHSI pump delivered 3.4 percent less flow than the C HHSI pump, ameasurement consistent with the pump curves.The licensee could not determine with certainty the factors that resulted inthe unanticipated measurement errors in this event. Conditions specific to anapplication can cause deviations from the vendor-supplied instrumentaccuracies. However, during the investigation the licensee developed methodsthat could be used to determine when the ultrasonic flowmeter may not yieldthe assumed accuracy. These methods include comparing ultrasonic flowmeterdata from several locations or different orientations at the same location orby comparing the data from these instruments with data from permanentlyinstalled instruments. Test results can also be compared with expected systembehavior.The NRC staff has approved a request from the licensee of the North Anna plantto modify the technical specification that specifies the acceptance criteriafor the HHSI pump flow rates. The change removes the specific fixed valuesfor the flow from the technical specifications and permits the licensee toestablish allowable values by analysis, providing greater operationalflexibility. The licensee is also planning to (1) install permanent flowinstrumentation that will supply highly accurate data for future flow balancetesting and (2) supply training concerning the accuracy of clamp-on ultrasonicflowmeters to the personnel who use them.Licensees frequently use flow measurements to demonstrate that safety-relatedcomponent performance is adequate to meet the demands indicated by theaccident or transient analyses. Therefore, obtaining accurate flowmeasurements is important to safety. When balancing the flow of HHSIinjection paths, flow rates need to be accurately measured to demonstrate thatthe unit complies with the assumptions in safety analyses and is operated inan analyzed condition. At North Anna the licensee initially failed to detectinaccurate flow data because of a failure to verify the consistency,repeatability and reasonableness of the data from the ultrasonic flowmeasurement instruments. Although technical specification requirements werenot met at North Anna, the licensee later analyzed the issue and concludedthat the HHSI system would have performed its design safety function.
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


s '-' IN 95-08January 30, 1995 This information notice requires no specific action or written response. Ifyou have any question about the information in this notice, please contact oneof the technical contacts listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.ran K. Grimes, DirectorDivision of Project SupportOffice of Nuclear Reactor RegulationTechnical contacts: Donald R. Taylor, RII Larry W. Garner, RII(703) 894-5421 (404) 331-4663Hukam C. Garg, NRR(301) 504-2929Attachment: List of Recently Issued Information Notices
C/HICB:DRCH


.Re-ttachmentIN 95-08January 30,Page I of 11995LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to95-07Radiopharmaceutical VialBreakage during Preparation01/27/95All USNRC medical licenseesauthorized to use byproductmaterial for diagnosticprocedures.95-06Potential Blockage ofSafety-Related Strainersby Material Brought InsideContainment01/25/95All holders of OLs or CPsfor nuclear power reactors.95-05Undervoltage ProtectionRelay Settings Out ofTolerance Due to TestEquipment Harmonics01/20/95All holdersPermits forreactors.of Constructionnuclear power95-0495-03Excessive Cooldown andDepressurization of theReactor Coolant SystemFollowing a Loss ofOffsite PowerLoss of Reactor CoolantInventory and PotentialLoss of Emergency Mitiga-tion Functions While ina Shutdown ConditionProblems with GeneralElectric CR2940 ContactBlocks in Medium-VoltageCircuit BreakersDOT Safety Advisory:High Pressure AluminumSeamless and AluminumComposite Hoop-WrappedCylinders01/19/9501/18/9501/17/9501/04/95All holders of OLs or CPsfor nuclear power reactors.All holders of Ols or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All U.S. Nuclear RegulatoryCommission licensees.95-0295-01OL -Operating LicenseCP = Construction Permit
D/DRCH NAME DMVerrelli


> S 95-08January 30, 1995 
HCGarg JSWermiel
-IN 95-XXJanuary XX, 1995 
<-/IN 94-XXNovember XX, 1994 IN 94-XXNovember XX, 1994 This information notice requires no specific action or written response. Ifyou have any question about the information in this notice, please contact oneof the technical contacts listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Project SupportOffice of Nuclear Reactor RegulationTechnical contacts:Donald R. Taylor, RII(703) 894-5421Larry W. Garner, RII(404) 331-4663Hukam C. Garg, NRR(301) 504-2929Attachment: List of Recently Issued Information NoticesNOTF VFNDOR COMMENTS RECEIVED. NO SIGNIFICANT CHANGES WERE MADEOFFICE *RPB:ADM by Email *OGCB:DORS *RIIby Phoncon *DRP:RIIby PhonconNAME TechEd AJKugler DRTaylor LWGarnerDATE 09/07/94 09/13/94 09/22/94 09/22/94OFFICE *DRP:RIIby Phoncon *HICB:DRCH *C/HICB:DRCH *D/DRCHNAME DMVerrelli HCGarg JSWermiel BABogerDATE 09/27/94 09/19/94 09/22/94 09/22/94OFFICE C/OECB:DOPS D/DOPSNAME AEf ffeBKGrimesDATE 11/2494 Af 11/ /94 __IDOCUMENT NAME:G:\IN\CLAMP-0N.INK


IN 94-XXNovember XX, 1994 This information notice requires no specific action or written response. Ifyou have any question about the information in this notice, please contact oneof the technical contacts listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Project SupportOffice of Nuclear Reactor RegulationTechnical contacts:Donald R. Taylor, RII(703) 894-5421Larry W. Garner, RII(404) 331-4663Hukam C. Garg, NRR(301) 504-2929Attachment: List of Recently Issued NRC Information NoticesNOTE: VENDOR COMMENTS RECEIVED, NO SIGNIFICANT CHANGES WERE MADEOFFICE *RPB:ADM by Email *OGCB:DORS *RIIby Phoncon *DRP:RIIby PhonconNAME TechEd AJKugler DRTaylor LWGarnerDATE 09/07/94 09/13/94 09/22/94 09/22/94OFFICE *DRP:RII by Phocon *HICB:DRCH *C/HICB:DRCH *D/DRCHNAME DMVerrelli HCGarg JSWermiel BABogerDATE09/27/94 09/19/94 09/22/94 09/22/94OFFICE C/OECB:DOPS D/DOPSNAME AEChaffee BKGrimesDATE .11/ /94DOCUMENT NAME: t:\IN\CLAMP-ON.IN
BABoger DATE 09/ /94 09/ /94 09/ /94 09/ /94 OFFICE C/OGCB:DORS


IN 94-XXSeptember XX, 994This information notice requires no specific action or written response. Ifyou have any question about the information in this notice, please contact oneof the technical contacts listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Donald R. Taylor, RII(703) 894-5421Larry(404)W. Garner, RII331-4663Hukam(301)C. Garg, NRR504-2929Attachment:List of Recently Issued Information NoticesOFFICE *RPB:ADM by Emal OGCB:DORS RII DRP:RIINAME TechEd jAJKugler j DRTaylor LWGarnerDATE 09/07/94 09/13/94 09/ /94 09/ /94OFFICE DRP:RII HICB: C/HICB:DRCH D/DRH_NAME DMVerrelli HCGar ^ JSWermieltiorDATE 09/ /94 09///94 _J09/22/94 O9/il/94OFFICE C/OGCB:DORS D/DORSNAME ELDoolittle BKGrimesDATE 09/ /94 09/ /94tt1 /2.
D/DORS NAME ELDoolittle


IN 94-XXSeptember XX, 994This information notice requires no specific action or written response. Ifyou have any question about the information in this notice, please contact oneof the technical contacts listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Uonald R. Taylor, RII(703) 894-5421Larry W. Garner, RII(404) 331-46E3Hukam C. Garg, NRR(301) 504-2929Attachment:List of Recently Issued Information NoticesOFFICE *RPB:ADM EMA)L OGCB:DORS RII DRP:RIINAME TechEd AJKu ler DRTaylor LWGarnerDATE 09/07/94 09/13/94 09/ /94 09/ /94OFFICE DRP:RII HICB:DRCH C/HICB:DRCH D/DRCHNAME DMVerrelli HCGarg JSWermiel BABogerDATE 09/ /94 09/ /94 09/ /94 09/ /94OFFICE C/OGCB:DORS D/DORSNAME ELDoolittle BKGrimes IIDATE 09/ /94 09/ /394  
BKGrimes II DATE 09/ /94 09/ /394}}
}}


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Revision as of 14:01, 31 August 2018

Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments
ML031060366
Person / Time
Site: Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant  Entergy icon.png
Issue date: 01/30/1995
From: Grimes B K
Office of Nuclear Reactor Regulation
To:
References
IN-95-008, NUDOCS 9501240226
Download: ML031060366 (12)
v • d • e


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:

List of Recently Issued Information

Notices DOCUMENT NAME: 95-08.IN NOTE: VENDOR COMMENTS RECEIVED, NO SIGNIFICANT

CHANGES WERE MADE OFFICE *RPB:ADM by Email *OGCB:DORS

  • RIIby Phoncon *DRP:RIIby

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

  • C/HICB:DRCH
  • D/DRCH NAME DMVerrelli

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

  • RIIby Phoncon *DRP:RIIby

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

  • C/HICB:DRCH
  • D/DRCH KANE DMVerrelli

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:

List of Recently Issued Information

Notices DOCUMENT NAME: S:\DOPSSEC\CLAMP-ON.INR

MnTr- vrTnnn rnMMFNTq RFCFIVFED

NO SIGNIFICANT

CHANGES WERE MADE OFFICE *RPB:ADM by EmaiL *OGCB:DORS

  • RI Iby Phoncon *DRP:RI Iby Phoncon NAME TechEd AJKugler DRTaylor LWGarner DATE 09/07/94 09/13/94 09/22/94 09/22/94 OFFICE *DRP:RI Iby Phomon *HICB:DRCH
  • C/HICB:DRCH
  • D/DRCH OMWE DMVerrelli

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

  • RIIby Phoncon *DRP:RIIby

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

  • C/HICB:DRCH
  • D/DRCH NAME DMVerrelli

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

  • RIIby Phoncon *DRP:RIIby

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

  • C/HICB:DRCH
  • D/DRCH NAME DMVerrelli

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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