Accuracy of Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to Generic Letter 89-10)ML031060610 |
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: |
03/16/1994 |
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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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GL-89-010 IN-94-018, NUDOCS 9403100159 |
Download: ML031060610 (9) |
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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>. |
' ., ^- /
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 March 16, 1994 NRC INFORMATION NOTICE 94-18: ACCURACY OF MOTOR-OPERATED VALVE DIAGNOSTIC
EQUIPMENT (RESPONSES TO SUPPLEMENT 5 TO
GENERIC LETTER 89-10)
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
This information notice is intended to alert addressees to information
submitted by various nuclear power plant licensees related to the accuracy of
motor-operated valve (MOV) diagnostic equipment. The information was
submitted in response to Supplement 5, "Inaccuracy of Motor-Operated Valve
Diagnostic Equipment," to Generic Letter (GL) 89-10, "Safety-Related Motor- Operated Valve Testing and Surveillance." It is expected that recipients will
review the information for applicability to their facilities and consider
actions, as appropriate, related to operability of MOYs. However, suggestions
contained in this information notice do not constitute NRC requirements;
therefore, no specific action or written response is required.
Background
In GL 89-10 (June 28, 1989), the NRC staff asked holders of operating licenses
and construction permits for nuclear power plants to provide additional
assurance of the capability of safety-related MOVs and certain other MOVs in
safety-related systems to perform their intended functions by reviewing MOV
design bases, verifying MOV switch settings initially and periodically, testing MOVs under design-basis conditions where practicable, improving
evaluations of MOV failures and necessary corrective action and trending MOV
problems. The NRC staff issued several supplements to GL 89-10 to clarify or
modify its recommendations.
As an integral part of most GL 89-10 programs, licensees are relying on MOV
diagnostic equipment to provide information on the thrust required to open or
close the valve, as well as the thrust delivered by the motor actuator. The
various types of MOV diagnostic equipment estimate stem thrust using different
methods, such as spring pack displacement or strain in the stem, the mounting
bolts, or the yoke. Because some licensees make decisions regarding the
operability of safety-related MOVs on the bases of diagnostic equipment
9403100159 ftR q -0i ~
7'4031I
-I 311q
-IN 94-18 March 16, 1994 thrust readings, the accuracy of MOV diagnostic equipment can have a
significant effect on the safe operation of a nuclear power plant.
During the implementation of GL 89-10, the NRC staff became aware of new
information on the accuracy of MOV diagnostic equipment. This new information
raised a generic concern regarding the reliability of the data produced by MOV
diagnostic equipment. For example, on February 3, 1992, the MOV Users Group
(MUG) of nuclear power plant licensees released "Final Report - MUG Validation
Testing as Performed at Idaho National Engineering Laboratories" (Volume 1).
The report stated that the MOV diagnostic equipment that relied on spring pack
displacement to estimate stem thrust was not as accurate as its vendors
claimed. In addition, the NRC staff learned that specific MOV diagnostic
equipment that relies on valve yoke strain to estimate stem thrust was less
accurate than had been previously reported.
On March 2, 1992, the NRC staff held a public meeting with representatives of
ITI-MOVATS to discuss the accuracy of the ITI-MOVATS thrust measuring device
(TMD) to estimate stem thrust on the basis of spring pack displacement. At
this meeting, the representatives of ITI-MOVATS described the results of their
field validation program which showed that, in some instances, the TMD may be
less accurate than licensees had assumed. The ITI-MOVATS representatives also
discussed the results of their activities to resolve concerns about the fact
that the TMD is calibrated in the valve opening direction, although it also is
used to predict the thrust delivered by the actuator in the valve closing
direction. ITI-MOVATS prepared Engineering Report 5.2 (March 13, 1992) to
provide guidance to its licensee customers for evaluating the capability of an
MOV to perform its safety function under design-basis conditions in light of
the decreased accuracy of the TMD. The Nuclear Management and Resources
Council (NUMARC) developed guidelines for licensees to use in evaluating MOVs
that had been set up using the TMD.
ASEA-Brown Boveri (ABB) Impell manufactures MOV diagnostic equipment (known as
OATIS) that relies on spring pack displacement to estimate stem thrust.
Following the release of the MUG report, Impell representatives stated that
they would be working with their licensee customers to develop new accuracy
values.
Liberty Technologies has manufactured MOV diagnostic equipment, referred to as
valve operation test and evaluation system (VOTES), that estimates the thrust
required to open or close a valve based on the strain of the valve yoke.
The VOTES system does this by measuring the diametral strain (the change in
diameter) of the valve stem for a given yoke strain. The stem thrust is then
calculated using the diametral strain and the nominal engineering properties
of the stem. This stem thrust is compared to the yoke strain to provide a
correlation between the yoke strain and the stem thrust. Once this
correlation has been established, the stem thrust can be more easily
determined by measuring the yoke strain. On October 2, 1992, Liberty
Technologies notified the NRC, in accordance with 10 CFR Part 21, that it had
found two new factors that can affect the thrust values obtained with its
VOTES equipment. Those factors are (1) the possible use of improper stem
\-'IN 94-18 March 16, 1994 material constants and (2) the failure to account for a torque effect when the
equipment is calibrated by measuring the strain of the threaded portion of a
valve stem.
In its October 2 submittal, Liberty Technologies provided guidance to
licensees for correcting the thrust data by performing hand calculations, and
stated that the new Version 2.3 of its VOTES software would be of help in
performing the corrections.
On June 28, 1993, the NRC staff issued Supplement 5 to GL 89-10 requesting
licensees and construction permit holders (1) to re-examine their MOV programs
and to identify measures taken to account for uncertainties in properly
setting valve operating thrust to ensure operability and (2) to evaluate the
schedule necessary to first consider the new information on MOV diagnostic
equipment inaccuracy and then to take appropriate action'in response to that
information. Within 90 days of receipt of Supplement 5 to 4L 89-10, licensees
were required (1) to notify the NRC staff of the diagnostic equipment used to
confirm the proper size, or to establish settings, for safety-related MOVs, and (2) to report whether they had taken actions or planned to take actions
(including schedule) to address the new information on the accuracy of MOV
diagnostic equipment.
Description of Circumstances
The NRC staff has reviewed the responses to Supplement 5 to GL 89-10 submitted
by licensees and construction permit holders. The staff has found that, for
the most part, licensees and permit holders have been actively addressing the
uncertainties regarding the accuracy of MOV diagnostic equipment. The newly
recognized reduced accuracy of MOV diagnostic equipment can raise questions
regarding (1) the adequacy of torque switch settings to provide sufficient
thrust while not exceeding thrust or torque structural limits and (2) the
capability of actuator motors with the present settings. In their responses, licensees and permit holders indicated that many MOVs had the potential for
underthrusting or overthrusting as a result of the less-than-expected accuracy
of MOV diagnostic equipment. Consequently, some licensees reported that MOVs
have been retested, adjusted, or modified to resolve the concerns regarding
the accuracy of MOV diagnostic equipment. The staff will discuss specific
aspects of the response to Supplement 5 to GL 89-10 with individual licensees
during future inspections.
The following is a summary of the issues relating to the accuracy of MOV
diagnostic equipment as reported by licensees in their responses to
Supplement 5 to GL 89-10.
1. ITI-MOVATS Engineering Report 5.2 discussed the calibration of the ITI-
MOVATS TMD in the open direction with reliance on the calibration to
measure thrust in the close direction. This ITI-MOVATS report focuses on
accuracy corrections for the TMD under static test conditions. The NRC
staff knows of no ITI-MOVATS guidance related to accuracy corrections for
the use of the TMD under dynamic test conditions.
IN 94-18 March 16, 1994 2. The temporary installation of the ITI-MOVATS torque thrust cell (TTC) for
diagnostic testing can affect the actuator output thrust. ITI-MOVATS
Special Test Report 6.0 addresses the actuator repositioning effect. The
licensee of the Oyster Creek Nuclear Power Plant stated in its response to
Supplement 5 to GL 89-10 that this special test report indicates that ITI-
MOVATS recommends that actuator repeatability values and thrust/torque
measurement error values be revised when using a temporarily installed
TTC.
3. The torque effects and the material characteristics that are relevant to
the use of the Liberty Technologies' VOTES diagnostic equipment is
discussed in this company's Part 21 notification of October 2, 1992.
4. In addition to the issues involving torque effects and material
characteristics, Liberty stated in its Part 21 notification of October 2,
1992, that (a) incorrect thrust readings can arise with the use of long
cable lengths between the signal conditioning box and the breakout box
when calibrating a VOTES sensor with a U-clamp or D-clamp; (b) under
certain conditions, one or more of the four operational amplifiers in the
breakout box oscillates and causes a thrust indication which can be lower
or higher than actual by a factor of about two or four; and (c) CB 23-100
cables were mistakenly shipped without the offset resistor (which results
in a lower-than-actual torque indication from the VTC load cell).
5. The licensee of the Cooper Nuclear Power Plant reported in its response to
Supplement 5 to GL 89-10 that Liberty Technologies is evaluating the issue
of calibration of its equipment in one direction and reliance on thrust
measurements in the other direction.
6. The Cooper licensee reported that Liberty Customer Service Bulletin
CSB-030 (May 6, 1993), 'Proximity Probe Type Calibrators With a Possible
3% Shift in Sensitivity," alerts VOTES users to possible changes in the
sensitivity of the proximity probe-type calibrator that can overpredict
thrust readings.
7. The licensee of the Susquehanna Nuclear Power Station reported in its
response to Supplement 5 to GL 89-10 that factors that can affect VOTES
accuracy are (a) the change in stem transition areas resulting from
Liberty Technologies' refinement of its finite element model, (b) changes
in effective stem diameters, (c) the need to differentiate between General
Purpose
ACME and Stub ACME threads when determining torque correction
factors and effective stem diameters, and (d) new accuracy values based on
torque correction values and percent extrapolation beyond calibration
ranges.
8. The licensee of the Maine Yankee Nuclear Power Plant noted in its response
to Supplement 5 to GL 89-10 that it had submitted a notice in accordance
with 10 CFR Part 21 on July 21, 1993, regarding its determination that the
accuracy cited by Liberty Technologies for its VOTES equipment is only
IN 94-18 March 16, 1994 appropriate for torque switch trip when the Best-Fit-Straight-Line (BFSL)
calibration method is used. As a result of this question regarding the
accuracy of the VOTES calibration method, the Susquehanna licensee
reported that its diagnostic tests will need to be repeated using the BFSL
calibration method. Liberty Technologies is in the process of issuing a
customer service bulletin that will give guidance on the inaccuracies of
the results obtained by using the BFSL method. The service bulletin will
also include a summary of a statistical analysis that was done to verify
the accuracy of the BFSL method.
Related Generic Communications
The NRC has issued other generic communications on the accuracy of MOY
diagnostic equipment. For example, the NRC issued Inforpation Notice (IN)
92-23, "Results of Validation Testing of Motor-Operated Valye Diagnostic
Equipment," to alert licensees to the potential decreased accuracy of MOV
diagnostic equipment manufactured by ITI-MOVATS and ABB Impell; and IN 93-01,
"Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty
Technologies.'
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Thomas G. Scarbrough, NRR
(301) 504-2794 Allen G. Hansen, NRR
(301) 504-1390
Attachment:
List of Recently Issued NRC Information Notices
Attachment
IN 94-18 March 16, 1994 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
94-17 Strontium-9O Eye Appli- 03/11/94 All U.S. Nuclear Regulatory
cators: Submission of Commission Medical Use
Quality Management Plan Licensees.
(QMP), Calibration, and
Use
94-16 Recent Incidents Resulting 03/03/94 All U.S. Nuclear Regulatory
in Offsite Contamination Commission material and fuel
cycle licensees.
94-15 Radiation Exposures during 03/02/94 All U.S. Nuclear Regulatory
an Event Involving a Fixed Commission licensees author- Nuclear Gauge ized to possess, use, manu- facture, or distribute
industrial nuclear gauges.
94-14 Failure to Implement 02/24/94 All holders of OLs or CPs
Requirements for Biennial for nuclear power and non- Medical Examinations and power reactors and all
Notification to the NRC licensed reactor operators
of Changes in Licensed and senior reactor
Operator Medical Conditions operators.
92-36, Intersystem LOCA 02/22/94 All holders of OLs or CPs
Supp. 1 Outside Containment for nuclear power reactors.
94-13 Unanticipated and Un- 02/22/94 All holders of OLs or CPs
intended Movement of for nuclear power reactors.
Fuel Assemblies and
Other Components due to
Improper Operation of
Refueling Equipment
94-12 Insights Gained from 02/09/94 All holders of OLs or CPs
Resolving Generic for nuclear power reactors.
Issue 57: Effects of
Fire Protection System
Actuation on Safety- Related Equipment
OL - Operating License
CP = Construction Permit
' IN 94-18 March 16, 1994 appropriate for torque switch trip when the Best-Fit-Straight-Line (BFSL)
calibration method is used. As a result of this question regarding the
accuracy of the VOTES calibration method, the Susquehanna licensee
reported that its diagnostic tests will need to be repeated using the BFSL
calibration method. Liberty Technologies is in the process of issuing a
customer service bulletin that will give guidance on the inaccuracies of
the results obtained by using the BFSL method. The service bulletin will
also include a summary of a statistical analysis that was done to verify
the accuracy of the BFSL method.
Related Generic Communications
The NRC has issued other generic communications on the accuracy of MOV
diagnostic equipment. For example, the NRC issued Information Notice (IN)
92-23, "Results of Validation Testing of Motor-Operated Valve Diagnostic
Equipment," to alert licensees to the potential decreased accuracy of MOV
diagnostic equipment manufactured by ITI-MOVATS and ABB Impell; and IN 93-01,
"Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty
Technologies."
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below.
Odgfnal igned by
Brian K. Grimes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Thomas G. Scarbrough, NRR
(301) 504-2794 Allen G. Hansen, NRR
(301) 504-1390
Attachment:
List of Recently Issued NRC Information Notices
OFFICE DE/EMEB* OGCB/DORS* *TECH ED DE/EMEB* C:DE:EMEB
NAME AGHansen DCKirkpatrick RSanders TScarbrough JNorberg
DATE J_01/31/94 I01/27/94 _ 01/494 i1.A-
01/31/94 101/31/94 D:DE/NRR* I AC:OGCB/DORS*
WHodges AJKugler JA IIII
02/01/94 03/03/94 103/I /94 UUMUMtNI NAMt: %-1W.IrN
IN 94-XX
March xx, 1994 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical Contacts: Thomas G. Scarbrough, NRR
(301) 504-2794 Allen G. Hansen, NRR
(301) 504-1390
OFFICE DE/EMEB* OGCB/DORS* *TECH ED DE/EMEB* C:DE:EMEB
NAME AGHansen DCKirkpatrick RSanders TScarbrough JNorberg
DATE J01/31/94 101/27/94 j01/14/94 01/31/94 I01/31/94 D:DE/NRR* AC:OGCB/DORS D:DORS/NRR
WHodges AJKuglerq'- BKGrimes II
02/01/94 03/03/94 03/ /94 UULUMtN I N.AM : iLUIUbb. IN
IN 94-XX
February xx, 1994 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical Contacts: Thomas G. Scarbrough, NRR
(301) 504-2794 Allen G. Hansen, NRR
(301) 504-1390
OFFICE -D9'M/iDB OGCB DORS *TECH ED DE/EMEB tA 4 rC C
NAME AGHans e DCKirkpatrick RSanders TScarbrough JN Xerg
DATE 7Z
/94 D<_ /94 01/14/94 0t/.z/94 I0t/.Ti/94 D:DE/NRR C:OGCB/DORS D:DORS/NRR
WHodgesg -6HMar4cus BKGrimes
w]L '1
02// /94 02/ /94 02/ /94 AME AL9
..MA,ITNAME:
VO ..._U_ 5 ...
DOCUM IL891055.1N
Otf
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list | - Information Notice 1994-01, Turbine Blade Failures Caused by Torsional Excitation from Electrical System Disturbance (7 January 1994)
- Information Notice 1994-02, Inoperability of General Electric Magne-Blast Breaker Because of Misalignment of Close-Latch Spring (7 January 1994)
- Information Notice 1994-03, Deficiencies Identified During Service Water System Operational Performance Inspections (11 January 1994, Topic: Biofouling)
- Information Notice 1994-04, Digital Integrated Circuit Sockets with Intermittent Contact (14 January 1994)
- Information Notice 1994-05, Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves (19 January 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-06, Potential Failure of Long-Term Emergency Nitrogen Supply for the Automatic Depressurization System Valves (28 January 1994)
- Information Notice 1994-07, Solubility Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20 (28 January 1994)
- Information Notice 1994-08, Potential for Surveillance Testing to Fail to Detect an Inoperable Main Steam Isolation Valve (1 February 1994)
- Information Notice 1994-09, Release of Patients with Residual Radioactivity from Medical Treatment & Control of Areas Due to Presence of Patients Containing Radioactivity Following Implementation of Revised 10 CFR Part 20 (3 February 1994, Topic: Brachytherapy)
- Information Notice 1994-10, Failure of Motor-Operated Valve Electric Power Train Due to Sheared or Dislodged Motor Pinion Gear Key (4 February 1994)
- Information Notice 1994-11, Turbine Overspeed and Reactor Cooldown During Shutdown Evolution (8 February 1994)
- Information Notice 1994-12, Insights Gained from Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment (9 February 1994, Topic: Overspeed trip)
- Information Notice 1994-13, Unanticipated and Unintended Movement of Fuel Assemblies and Other Components Due to Improper Operation of Refueling Equipment (28 June 1994)
- Information Notice 1994-14, Failure to Implement Requirements for Biennial Medical Examinations and Notification to the NRC of Changes in Licensed Operator Medical Conditions (24 February 1994)
- Information Notice 1994-15, Radiation Exposures During an Event Involving a Fixed Nuclear Gauge (2 March 1994)
- Information Notice 1994-16, Recent Incidents Resulting in Offsite Contamination (3 March 1994)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (Qmp), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-18, Accuracy of Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to Generic Letter 89-10) (16 March 1994)
- Information Notice 1994-19, Emergency Diesel Gemerator Vulnerability to Failure from Cold Fuel Oil (16 March 1994)
- Information Notice 1994-20, Common-Cause Failures Due to Inadequate Design Control and Dedication (17 March 1994)
- Information Notice 1994-21, Regulatory Requirements When No Operations Are Being Performed (18 March 1994)
- Information Notice 1994-22, Fire Endurance & Ampacity Derating Test Results for 3-Hour Fire-Rated Thermo-Lag 330-1 Fire Barriers (16 March 1994, Topic: Fire Barrier)
- Information Notice 1994-23, Guidance to Hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program (25 March 1994, Topic: Fire Barrier)
- Information Notice 1994-24, Inadequate Maintenance of Uninterruptible Power Supplies & Inverters (24 March 1994, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1994-25, Failure of Containment Spray Header Valve to Open Due to Excessive Pressure from Inertial Effects of Water (15 March 1994, Topic: Fire Barrier)
- Information Notice 1994-26, Personnel Hazards and Other Problems from Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water Reactor (28 March 1994, Topic: Fire Barrier)
- Information Notice 1994-27, Facility Operating Concerns Resulting from Local Area Flooding (31 March 1994, Topic: Fire Barrier)
- Information Notice 1994-28, Potential Problems with Fire-Barrier Penetration Seals (5 April 1994, Topic: Fire Barrier)
- Information Notice 1994-29, Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction Pressure (11 April 1994, Topic: Boric Acid)
- Information Notice 1994-30, Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station (19 August 1994, Topic: Fire Barrier)
- Information Notice 1994-31, Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles (14 April 1994, Topic: Hydrostatic)
- Information Notice 1994-32, Revised Seismic Estimates (29 April 1994, Topic: Earthquake)
- Information Notice 1994-33, Capacitor Failures in Westinghouse Eagle 21 Plant Protection Systems (9 May 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-34, Thermo-LAG 330-660 Flexi-Blanket Ampacity Derating Concerns (13 May 1994, Topic: Fire Barrier)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(Mmr) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(MMR) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System (24 May 1994, Topic: Reactor Vessel Water Level, Stress corrosion cracking, Integrated leak rate test)
- Information Notice 1994-37, Misadministration Caused by a Bent Interstitial Needle During Brachytherapy Procedure (27 May 1994, Topic: Brachytherapy)
- Information Notice 1994-38, Results of Special NRC Inspection at Dresden Nuclear Power Station, Unit 1 Following Rupture of Service Water Inside Containment (27 May 1994)
- Information Notice 1994-39, Identified Problems in Gamma Stereotactic Radiosurgery (31 May 1994)
- Information Notice 1994-40, Failure of a Rod Control Cluster Assembly to Fully Insert Following a Reactor Trip at Braidwood, Unit 2 (26 May 1994)
- Information Notice 1994-41, Problems with General Electric Type Cr124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-41, Problems with General Electric Type CR124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-42, Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors (7 June 1994)
- Information Notice 1994-43, Determination of Primary-to-Secondary Steam Generator Leak Rate (10 June 1994, Topic: Grab sample)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand Because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-45, Potential Common-Mode Failure Mechanism for Large Vertical Pumps (17 June 1994, Topic: Biofouling)
- Information Notice 1994-46, Nonconservative Reactor Coolant System Leakage Calculation (20 June 1994)
... further results |
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