Inadequate DC Ground Detection in Direct Current Distribution SystemsML031060424 |
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: |
11/25/1994 |
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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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IN-94-080, NUDOCS 9411170279 |
Download: ML031060424 (14) |
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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>. |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 November 25, 1994 NRC INFORMATION NOTICE 94-80: INADEQUATE DC GROUND DETECTION IN DIRECT
CURRENT DISTRIBUTION SYSTEMS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to the potential for operating with undetectable
grounds in vital direct current (dc) distribution systems due to inadequate
ground-detection equipment or inadequate ground-alarm setpoints or both. 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 do not
constitute NRC requirements; therefore, no specific action or written response
is required.
Background
NRC Information Notice 88-86 and its supplement, "Operating with Multiple
Grounds in Direct Current Distribution Systems," alerted all addressees to
potential problems and failure modes caused by grounds on vital dc
distribution systems, which are normally ungrounded systems. Specifically, several plants had operated for extended periods with grounds on their dc
systems. The information notice also listed licensee event reports (LERs)
related to dc system grounds. Supplement 1 described a specific failure mode
whereby grounds on a dc system could cause equipment to remain energized
during harsh environments instead of assuming the de-energized state needed to
comply with protection system requirements.
Description of Circumstances
Discussions between the staff and several licensees indicated that ground
detectors may not be capable of detecting certain grounds and that ground
detector alarm resistance-to-ground values may be inadequate. In addition, the discussions indicated that some licensee reviews and actions associated
with Information Notice 88-86 and Supplement 1 were limited to specific
examples cited, such as qualification of ASCO solenoids. Other specific
examples follow.
9411170279 PDnn 1o k o:¢E
c i4 cgo r LI aI,)
okItr0+ir-e-- '34-11
, A_, IN-94-80
November 25, 1994 Point Beach
During a monthly surveillance test on June 4, 1990, the licensee noted a solid
ground on the dc distribution system. Although the ground detector was
equipped with an alarm, the control room annunciator had not alarmed. The
licensee determined that as a result of its design, the ground detector could
become magnetized when a ground of one polarity occurred. Consequently, if a
solid ground occurred of the opposite polarity, the hysteresis or
magnetization of the ground relay coil would prevent actuation of the ground
detector. The licensee concluded that the ground detector was insensitive and
incapable of detecting even solid grounds. As corrective action, a new, more- sensitive ground detector was installed with an alarm value set at
20,000 ohms.
Palisades
On August 8, 1991, the licensee discovered a solid ground in a dc system. The
associated control room annunciator had not alarmed. The ground-detector- alarm setpoint was based on a 5-milliampere (ma) current; however, the maximum
current that could flow in the circuit was determined to be only 4.2 ma.
Also, if a ground occurred gradually, it would not be detected because of the
mechanical properties of the detector-alarm mechanism. For corrective action, the licensee is monitoring the battery voltage on the positive and negative
buses once each shift.
Fermi
In September 1991, an NRC inspection determined that the licensee 260-volt
battery ground detector could not consistently detect grounds since the
relative brightness of lights was being used subjectively to indicate the
presence of a ground. To improve sensitivity, the licensee replaced the
existing 25-watt light bulbs with 10-watt bulbs. This change raised the
threshold for detecting grounds from about 92 ohms to about 1000 ohms.
Davis-Besse
During a November 15-19, 1993 inspection, the NRC determined that the ground
detector on the new alternate station blackout diesel generator battery was
only capable of detecting solid grounds and that the detector manufacturer
could not quantify the setpoint. In response, the licensee proposed to review
the adequacy of the present ground detector and investigate alternative
methods to detect the presence of grounds in the dc system.
Grand Gulf
On November 1, 1994, a reactor scram occurred due to a ground in the "A"
backup scram valve control circuitry while a half scram was already present
due to surveillance testing of the reactor protection system. The hard
ground, in conjunction with the use of a newly upgraded 125-volt dc ground
A
u_ IN-94-80
November 25, 1994 detector, enabled enough current to flow to energize the backup scram valve's
solenoid and open the backup scram valve. The modified detector circuitry
provided a 1000-ohm path through an annunciating relay (control room alarm) to
ground. This upgraded detector circuitry replaced a circuit which originally
had a 100,000-ohm path to ground. For corrective action the licensee has
removed the hard ground, will disable the 1000-ohm path and has de-energized
the detector circuit used for local ground indication except when periodic
ground checks are performed.
Discussion
In Information Notice 88-86, Supplement 1, the staff described the potential
for ASCO solenoid valves to inadvertently actuate or fail to drop out due to
grounds of approximately 4000 ohms or less at the Summer station. The Summer
licensee has also removed the on-line ground detector because its inherent
1500-ohm resistance-to-ground value was below the plant threshold value.
After Information Notice 88-86 Supplement 1 was issued, the staff met with
Commonwealth Edison on March 1, 1989, to discuss corrective action for the
ground problem at Quad Cities (discussed in Information Notice 88-86). The
Commonwealth Edison review revealed the potential for inadvertent relay
operation at a much higher ground-resistance value for General Electric HFA,
HMA, and HGA 125-volt dc relays. All Commonwealth Edison nuclear plants now
have ground-clearing action with priorities based on two ground-threshold
values, 125,000 and 20,000 ohms. The 125,000-ohm value is based on the
minimum ground current required to keep an HGA relay from dropping out when
its normal power is removed and an additional ground exists between the relay
and its actuating switch contact (see Figure 1). The 20,000-ohm threshold is
based on the minimum current needed to pick up the most sensitive relay
(General Electric HMA) under the same conditions. (For further information on
determining a ground threshold for a dc system, see Annex C of IEEE Std 946-
1992, "IEEE Recommended Practice for the Design of DC Auxiliary Power Systems
for Generating Stations.")
Nuclear power plant dc distribution systems are typically two-wire ungrounded
battery/charger systems equipped with ground-detection/alarm circuitry
including features such as annunciation in the control room, local indication, and recording. Ground detectors are incorporated in the dc systems so that if
a single ground does occur, personnel are aware of the ground and can take
immediate steps to clear the ground fault from the system.
Failure to promptly eliminate a single ground could mask subsequent additional
grounds. Multiple grounds could lead to unpredictable spurious operation of
equipment, inoperable equipment, unanalyzed loads on batteries, or unanalyzed
equipment failure modes that could be expected to occur during harsh
environments attendant to accidents. In addition, installed ground detectors
and portable ground-locating equipment themselves may create a ground on the
dc system and may not maintain a minimum threshold resistance-to-ground value
above which predictable system/component operation can be assured.
'> <IN-94-80
November 25, 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 or the appropriate NRR project
manager.
NBf an K. G imes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: Roger Mendez, RIII
(708) 829-9745 Fred Burrows, NRR
(301) 504-2901 Attachments:
1. Figure 1: Ground-Threshold Valves
2. List of Recently Issued NRC Information Notices
fit Id (4JA 4 f
Attachment 1 IN 94-80
November 25, 1994 1oJ!M W"" A&=
I 4MP I LJ stch contact
for relay.
I I r solenod. tc.
I A..I I Meond
I ---*So
. -OW fauf
Inev +/-1 I_ I 300 Knfe
MMA
%IW
dc
_ I I
_ I I
I reay.
solnod. etc.
I I
PB
I
L n m~ u. m. m~ -
PP* lp- eft
` Threshold R stanceTo-Groun
Note: A complete circut through the rely (or olnold), ground buf And
edn . Is shown by a heay m.
Figure 1
" Iachment 2 IN 94-80
November 25, 1994 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
94-79 Microbiologically 11/23/94 All holders of OLs or CPs
Influenced Corrosion for nuclear power reactors.
of Emergency Diesel
Generator Service
Water Piping
94-78 Electrical Component 11/21/94 All holders of OLs or CPs
Failure due to Degrada- for nuclear power reactors.
tion of Polyvinyl Chloride
Wire Insulation
94-77 Malfunction in Main Gen- 11/17/94 All holders of OLs or CPs
erator Voltage Regulator for nuclear power reactors.
Causing Overvoltage at
Safety-Related Electrical
Equipment
94-76 Recent Failures of Charging/ 10/26/94 All holders of OLs or CPs
Safety Injection Pump Shafts for pressurized water
reactors.
93-60, Reporting Fuel Cycle 10/20/94 All 10 CFR Part 70
Supp. 1 and Materials Events to fuel cycle licensees.
the NRC Operations Center
94-75 Minimum Temperature 10/14/94 All holders of OLs or CPs
for Criticality pressurized-water reactors
(PWRs).
94-74 Facility Management 10/13/94 All U.S. Nuclear Regulatory
Responsibilities for Commission Medical
Purchased or Contracted Licensees.
Services for Radiation
Therapy Programs
94-73 Clarification of Critical- 10/12/94 All fuel fabrication
ity Reporting Criteria facilities.
94-72 Increased Control Rod 10/05/94 All holders of OLs or CPs
Drop Time from Crud for pressurized water
Buildup reactors.
OL = Operating License
CP = Construction Permit
\K>, VIN-94-80
November 25, 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 or the appropriate NRR project
manager.
Original signed by B.D. Liaw for
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: Roger Mendez, RIII
(708) 829-9745 Fred Burrows, NRR
(301) 504-2901 Attachments:
1. Figure 1: Ground-Threshold Valves
2. List of Recently Issued NRC Information Notices
DOCUMENT NAME: 94-80.IN
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DATE 08/22/94 08/23/94 08/22/94 09/02/94 a 08/ /94 llOFFICE lOGCB/DOPS l lOGCB/DOPS l lOECB/DOPS l /A A I
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DATE 09/23/94 09/27/94 10/31/94 1_1__h /94 OFFICIAL RECORD COPY
IN-94-XX
October 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 or the appropriate NRR project
manager.
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: Roger Mendez, RIII
(708) 829-9745 Fred Burrows, NRR
(301) 504-2901 Attachments:
1. Figure 1: Ground-Threshold Valves
2. List of Recently Issued NRC Information Notices
DOCUMENT NAME: S:\DORSSEC\INGR2 *See Previous Concurrence
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IN-94-XX
October 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 or the appropriate NRR project
manager.
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: Roger Mendez, RIII
(708) 829-9745 Fred Burrows, NRR
(301) 504-2901 Attachments:
1. Figure 1: Ground-Threshold Valves
2. List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\NANCY\INGR2 *See Previous Concurrence
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OFFICIAL RECORD COPY K.
IN-94-XX
October 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 or the appropriate NRR project
manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical Contact:
Roger Mendez, RIII
(708) 829-9745 Fred Burrows, NRR
(301) 504-2901 Attachments:
1. Figure 1: Ground-Threshold Valves
2. List of Recently Issued NRC Information Notices
0-
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/f.00t<
IN-94-XX
September 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 or the appropriate NRR project
manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical Contact:
Roger Mendez, RIII
(708) 829-9745 Fred Burrows, NRR
(301) 504-2901 Attachments:
1. Figure 1: Ground-Threhold Valves
2. List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\SHARED/INGR2 *See Previous Concurrence
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DATE 09/23/94 09/27/94 09/ /94 _
.L OFFICIAL RECORD COPY
IN-94-XX
September 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 or the appropriate NRR project
manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical Contact:
Roger Mendez, RIII
(708) 829-9745 Fred Burrows, NRR
(301) 504-2901 Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\SHARED/INGR2 *See Previous Concurrence
- Concurrence August 24, 1994, via telephone
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DATE 09/ /94 09/ /94 09/ /94 09/02/94 08/ /94 To receive a eopy of this document, indicate In the box C-Copy w/ -attachment/enclosure
I Copy with atta htent/enclosure U* So eopy
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DATE 09/o?3/94 09/31/94 0re9 OFFICIAL RECORD COPY ,. JP I
IN-94-XX
August 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 or the appropriate NRR project
manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical Contact:
Roger Mendez, RIII
(708) 829-9745 Fred Burrows, NRR
(301) 504-2901 Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\SHARED/INGR2 *See Previous Concurrence
- Concurrence August 24, 1994, via telephone
To receive a copy of this document, indicate in the box C=Copy wvo attachment/enclosure E=Copy with attachment/encLosure K a No
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OFFICE OGCB/NRR E Sl NRj _
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DATE 08/ /94 08/ /94 08/ /94 OFFICIAL RECORD COPY
IN-94-XX
August 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 or the appropriate NRR project
manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical Contact:
Roger Mendez, RIII
(708) 829-9745 Fred Burrows, NRR
(301) 504-2901 Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\SHARED/INGR2 To receive a copy of this document, indicate in the box C=Copy wlo attachment/enclosure E=Copy with attachment/encLosure N KNo copy
[ OFFICE
NAME
DATE
EELBNRR
F
08/cg;,/94
/tr
I EELBiNRR
EWe0
4 Il ADM/PUB
RSanders
O8/6Z1 9 4
4 Il EELB/NRRI
CBerlinger
08/ /94 DORS/NRR
BKGrimes
08/ /94 I
OFFICIAL RECORD COPY
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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)
- 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)
- 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)
- 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)
- 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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