Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement InstrumentsML031060366 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
01/30/1995 |
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From: |
Grimes B Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-95-008, NUDOCS 9501240226 |
Download: ML031060366 (12) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
X '..
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 January 30, 1995 NRC INFORMATION NOTICE 95-08: INACCURATE DATA OBTAINED WITH CLAMP-ON
ULTRASONIC FLOW MEASUREMENT INSTRUMENTS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
PurDose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to difficulties in accurately measuring flow rates
with clamp-on ultrasonic flow measurement instruments. It is expected that
recipients will review the information for applicability to their facilities
and consider actions, as appropriate, to avoid similar problems. However, suggestions contained in this information notice are not NRC requirements;
therefore, no specific action or written response is required.
DescriDtion of Circumstances
O October 14, 1993, while performing a high head safety injection (HHSI) flow
balance test, the licensee for North Anna Unit 2 determined that the as-found
safety injection cold leg branch line flow rates did not meet the technical
specification requirements. The as-found cold leg branch line flow rates had
also failed to meet the technical specification requirements during the
previous test in April 1992.
The North Anna Technical Specifications give limits related to both minimum
and maximum safety injection line flow rates. For North Anna, these two
technical specification limits resulted in an very narrow allowed operating
band, which required the use of highly accurate flow measurement instruments
for flow tests.
The licensee performed the flow balance using System 990 Uniflow Universal
Transit-Time Flowmeters manufactured by Controlotron of Hauppauge, New York.
The Uniflow flowmeter is a clamp-on non-intrusive portable flowmeter that uses
multi-pulse, transit-time ultrasonic technology to measure precisely the flow
rate. The flowmeter induces alternate upstream and downstream ultrasonic
signals and measures the difference in transit times. This information 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
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list | - Information Notice 1995-01, DOT Safety Advisory: High Pressure Aluminum Seamless and Aluminum Composite Hoop-Wrapped Cylinders (4 January 1995, Topic: Brachytherapy)
- Information Notice 1995-02, Problems With General Electric CR2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems With General Electric Cr2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems with General Electric CR2940 Contact Blocks in Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-03, Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition (18 January 1995, Topic: Packing leak)
- Information Notice 1995-04, Excessive Cooldown and Depressurization of the Reactor Coolant System Following Loss of Offsite Power (11 October 1996, Topic: Safe Shutdown, Shutdown Margin, Probabilistic Risk Assessment, Troxler Moisture Density Gauge)
- Information Notice 1995-05, Undervoltage Protection Relay Settings Out of Tolerance Due to Test Equipment Harmonics (20 January 1985)
- Information Notice 1995-06, Potential Blockage of Safety-Related Strainers by Material Brought Inside Containment (25 January 1995, Topic: Foreign Material Exclusion)
- Information Notice 1995-07, Radiopharmaceutical Vial Breakage During Preparation (27 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained With Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-09, Use of Inappropriate Guidelines and Criteria for Nuclear Piping and Pipe Support Evaluation and Design (31 January 1995)
- Information Notice 1995-10, Potential for Loss of Automatic Engineered Safety Features Actuation (3 February 1995)
- Information Notice 1995-11, Failure of Condensate Piping Because of Erosion/Corrosion at Flow-Straightening Device (24 February 1995)
- Information Notice 1995-12, Potentially Nonconforming Fasteners Supplied by A&G Engineering II, Inc (21 February 1995)
- Information Notice 1995-13, Potential for Data Collection Equipment to Affect Protection System Performance (24 February 1995)
- Information Notice 1995-14, Susceptibility of Containment Sump Recirculation Gate Valves to Pressure Locking (28 February 1995)
- Information Notice 1995-15, Inadequate Logic Testing of Safety-Related Circuits (7 March 1995)
- Information Notice 1995-16, Vibration Caused by Increased Recirculation Flow in a Boiling Water Reactor (9 March 1995)
- Information Notice 1995-17, Reactor Vessel Top Guide and Core Plate Cracking (10 March 1995, Topic: Safe Shutdown)
- Information Notice 1995-18, Potential Pressure-Locking of Safety-Related Power-Operated Gate Valves (15 March 1995)
- Information Notice 1995-19, Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch Mechanism (22 March 1995)
- Information Notice 1995-20, Failures in Rosemount Pressure Transmitters Due to Hydrogen Permeation Into Sensor Cell (22 March 1995)
- Information Notice 1995-21, Unexpected Degradation of Lead Storage Batteries (20 April 1995)
- Information Notice 1995-22, Hardened or Contaminated Lubricant Cause Metal-Clad Circuit Breaker Failures (21 April 1995)
- Information Notice 1995-23, Control Room Staffing Below Minimum Regulatory Requirements (24 April 1995)
- Information Notice 1995-24, Summary of Licensed Operator Requalification Inspection Program Findings (25 April 1995, Topic: Job Performance Measure, License Renewal)
- Information Notice 1995-25, Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit (11 May 1995)
- Information Notice 1995-26, Defect in Safety-Related Pump Parts Due to Inadequate Treatment (31 May 1995)
- Information Notice 1995-27, NRC Review of Nuclear Energy Institute, Thermo-Lag 330-1 Combustibility Evaluation Methodology Plant Screening Guide. (31 May 1995, Topic: Safe Shutdown, Fire Barrier, Exemption Request, Fire Protection Program)
- Information Notice 1995-28, Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites (5 June 1995, Topic: Safe Shutdown, Tornado Missile, Safe Shutdown Earthquake, Earthquake)
- Information Notice 1995-29, Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems (7 June 1995, Topic: Nondestructive Examination)
- Information Notice 1995-30, Susceptibility of Low-Pressure Coolant Injection Valves to Pressure Locking (3 August 1995, Topic: Hydrostatic, Power-Operated Valves)
- Information Notice 1995-31, Motor-Operated Valve Failure Caused by Stem Protector Pipe Interference (9 August 1995)
- Information Notice 1995-32, Thermo-Lag 330-1 Flame Spread Test Results (10 August 1995, Topic: Fire Barrier)
- Information Notice 1995-33, Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3 (23 August 1995)
- Information Notice 1995-34, Air Actuator and Supply Air Regulator Problems in Copes-Vulcan Pressurizer Power-Operated Relief Valves (25 August 1995)
- Information Notice 1995-35, Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation (28 August 1995)
- Information Notice 1995-36, Potential Problems with Post-Fire Emergency Lighting (29 August 1995, Topic: Safe Shutdown, Emergency Lighting, Exemption Request)
- Information Notice 1995-37, Inadequate Offsite Power System Voltages During Design-Basis Events (7 September 1995)
- Information Notice 1995-38, Degradation of Boraflex Neutron Absorber in Spent Fuel Storage Racks (8 September 1995)
- Information Notice 1995-39, Brachytherapy Incidents Involving Treatment Planning Errors (19 September 1995, Topic: Brachytherapy)
- Information Notice 1995-40, Supplemental Information to Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes. (20 September 1995, Topic: Hydrostatic, Nondestructive Examination, Brachytherapy)
- Information Notice 1995-41, Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam Generators (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-42, Commission Decision on Resolution of Generic Issue 23, Reactor Coolant Pump Seal Failure. (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-43, Failure of Bolt-Locking Device on Reactor Coolant Pump Turning Vane (28 September 1995, Topic: Brachytherapy)
- Information Notice 1995-44, Ensuring Compatible Use of Drive Cables Incorporating Industrial Nuclear Company Ball-Type Male Connectors (26 September 1995, Topic: Brachytherapy)
- Information Notice 1995-45, American Power Service Falsification of American Society for Nondestructive Testing Certificates (4 October 1995, Topic: Brachytherapy)
- Information Notice 1995-46, Unplanned, Undetected Release of Radioactivity from the Exhaust Ventilation System of a Boiling Water Reactor (6 October 1995, Topic: Brachytherapy)
- Information Notice 1995-47, Unexpected Opening of a Safety/Relief Valve & Complications Involving Suppression Pool Cooling Strainer Blockage (30 November 1995)
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