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

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| issue date = 01/30/1995
| issue date = 01/30/1995
| title = Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments
| title = Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments
| author name = Grimes B K
| author name = Grimes B
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name =  
| addressee name =  
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| page count = 12
| page count = 12
}}
}}
{{#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 isthe
 
then used to determine the axial fluid velocity and the flow rate through
 
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       Ir      p.#sCC       's
 
9501240226 UtjxW ¢ vv     -31-15                                     lk (t
 
0
 
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


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
curve data. At the same time, installed plant process instruments indicated


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.
that the A HHSI pump delivered 3.4 percent less flow than the C HHSI pump, a


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
measurement consistent with the pump curves.


.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
The licensee could not determine with certainty the factors that resulted in


> S 95-08January 30, 1995 
the unanticipated measurement errors in this event. Conditions specific to an
-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
application can cause deviations from the vendor-supplied instrument


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.
accuracies. However, during the investigation the licensee developed methods


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  
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, 1995 Page I of 1 LIST OF RECENTLY ISSUED
 
NRC INFORMATION NOTICES
 
Information                                    Date of
 
Notice No.              Subject                Issuance    Issued to
 
95-07          Radiopharmaceutical Vial      01/27/95    All USNRC medical licensees
 
Breakage during Preparation                authorized to use byproduct
 
material for diagnostic
 
procedures.
 
95-06          Potential Blockage of          01/25/95    All holders of OLs or CPs
 
Safety-Related Strainers                    for nuclear power reactors.
 
by Material Brought Inside
 
Containment
 
95-05          Undervoltage Protection        01/20/95    All holders of Construction
 
Relay Settings Out of                      Permits for nuclear power
 
Tolerance Due to Test                      reactors.
 
Equipment Harmonics
 
95-04          Excessive Cooldown and        01/19/95    All holders of OLs or CPs
 
Depressurization of the                    for nuclear power reactors.
 
Reactor Coolant System
 
Following a Loss of
 
Offsite Power
 
95-03          Loss of Reactor Coolant        01/18/95    All holders of Ols or CPs
 
Inventory and Potential                    for nuclear power reactors.
 
Loss of Emergency Mitiga- tion Functions While in
 
a Shutdown Condition
 
95-02          Problems with General          01/17/95    All holders of OLs or CPs
 
Electric CR2940 Contact                    for nuclear power reactors.
 
Blocks in Medium-Voltage
 
Circuit Breakers
 
95-01          DOT Safety Advisory:          01/04/95    All U.S. Nuclear Regulatory
 
High Pressure Aluminum                      Commission licensees.
 
Seamless and Aluminum
 
Composite Hoop-Wrapped
 
Cylinders
 
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              Larry W. Garner, RII
 
(703) 894-5421                      (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            Larry W. Garner, RI!
                        (703) 894-5421                  (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:RIIby  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 W. Garner, RII
 
(404) 331-4663 Hukam C. Garg, NRR
 
(301) 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_      tt1 /2.
 
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
 
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}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Latest revision as of 04:30, 24 November 2019

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
Office of Nuclear Reactor Regulation
To:
References
IN-95-008, NUDOCS 9501240226
Download: ML031060366 (12)


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 isthe

then used to determine the axial fluid velocity and the flow rate through

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 Ir p.#sCC 's

9501240226 UtjxW ¢ vv -31-15 lk (t

0

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, 1995 Page I of 1 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

95-07 Radiopharmaceutical Vial 01/27/95 All USNRC medical licensees

Breakage during Preparation authorized to use byproduct

material for diagnostic

procedures.

95-06 Potential Blockage of 01/25/95 All holders of OLs or CPs

Safety-Related Strainers for nuclear power reactors.

by Material Brought Inside

Containment

95-05 Undervoltage Protection 01/20/95 All holders of Construction

Relay Settings Out of Permits for nuclear power

Tolerance Due to Test reactors.

Equipment Harmonics

95-04 Excessive Cooldown and 01/19/95 All holders of OLs or CPs

Depressurization of the for nuclear power reactors.

Reactor Coolant System

Following a Loss of

Offsite Power

95-03 Loss of Reactor Coolant 01/18/95 All holders of Ols or CPs

Inventory and Potential for nuclear power reactors.

Loss of Emergency Mitiga- tion Functions While in

a Shutdown Condition

95-02 Problems with General 01/17/95 All holders of OLs or CPs

Electric CR2940 Contact for nuclear power reactors.

Blocks in Medium-Voltage

Circuit Breakers

95-01 DOT Safety Advisory: 01/04/95 All U.S. Nuclear Regulatory

High Pressure Aluminum Commission licensees.

Seamless and Aluminum

Composite Hoop-Wrapped

Cylinders

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 Larry W. Garner, RII

(703) 894-5421 (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 Larry W. Garner, RI!

(703) 894-5421 (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:RIIby 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 W. Garner, RII

(404) 331-4663 Hukam C. Garg, NRR

(301) 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_ tt1 /2.

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

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