Inadequate Control Over Vehicular Traffic at Nuclear Power Plant SitesML031200669 |
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 ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
02/18/1992 |
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From: |
Rossi C Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-92-013, NUDOCS 9202110001 |
Download: ML031200669 (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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Category:NRC Information Notice
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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 February 18, 1992 NRC INFORMATION
NOTICE 92-13: INADEQUATE
CONTROL OVER VEHICULAR
TRAFFIC AT NUCLEAR POWER PLANT SITES
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 continuing
problems resulting
from the failure of some licensees
to maintain adequate control over vehicular
traffic at their plants.These licensees
failed to follow established
administrative
procedures
related to the use of self-propelled
cranes. Their failures resulted in unnecessary
challenges
to safety systems and threatened
the health and safety of plant personnel.
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.Description
of Circumstances
Diablo Canyon Unit 1: On March 7, 1991, during a refueling
outage, the Diablo Canyon Nuclear Power Plant, Unit 1, experienced
a total loss of offsite power (LOOP). The event was caused when an electrical
flashover
occurred between a 500 kV transmission
line and the boom of a mobile crane. The boom was positioned
approximately
three feet from the transmission
line. At the time of the event, power to plant loads was being supplied from offsite by back-feeding
through the main output transformer
from the 500 kV switchyard.
Two standby startup transformers, the normal sources of offsite power to the plant, had been removed from service for scheduled
maintenance.
The flashover
caused protective
relaying to actuate to isolate the faulted line and, as a result, offsite power to plant loads was interrupted.
All three emergency
diesel generators
started and loaded successfully.
Operation of the residual heat removal system was restored within about 1 minute. The temperature
of the core did not increase.
No radiological
release resulted.The fault did not affect Diablo Canyon, Unit 2, which was operating
at full power.Palo Verde Unit 3: On November 15, 1991, while the Palo Verde Nuclear Generating
a ion , was shutdown in hot standby, the boom of a 35-ton truck-mounted
AAClec on 2/1 9 lJ-I CL-
..... I N 9 2 -1 3 February 18, 1992 crane made contact with one of two 13.8 kV offsite power feeder lines located in the plant's protected
area. The crane was being used to replace the "A" phase bushing on the main output transformer.
The original bushing had been damaged by lightning
a day earlier. Prior to final installation
and after high voltage testing had been completed, the bushing was returned to its shipping cask. The crane operator shut down the crane motor and engaged one of several braking devices on the crane boom. The crane operator then exited the crane cab to discuss replacement
procedures
with other maintenance
personnel.
A wind gust caused the boom of the crane to rotate and contact one of the phases of the 13.8 kY feeder. The feeder was transmitting
power from the startup trans-former to various vital and non-vital
loads in the "A" train. The electrical
fault current which was generated
was not of sufficient
magnitude
to cause protective
devices to actuate because the crane had not been grounded as required by plant procedure.
Therefore, the feeder remained energized
and the fault current initiated
small asphalt fires in the areas where the crane's front outrigger
pads made ground contact. The rear outrigger
pads were not extended.The maintenance
foreman (the foreman) contacted
the shift supervisor
and incorrectly
identified
the "B" train feeder as being faulted. The shift supervisor
opened the supply circuit breaker for the "B" train feeder before the foreman could correct his misstatement.
Electrical
power was interrupted
to non-vital
loads, including
two of four reactor coolant pumps (RCPs). Power to vital train "B" loads was momentarily
interrupted
but was reestablished
following-the
successful
start and Toa-din-g
of the train "B" emergency
diesel generator (EDG).The correct "A" feeder was subsequently
deenergized, resulting
in the start and loading of the "A" EDG and causing the loss of power to the remaining
two operating
RCPs. The reactor was cooled by natural circulation
for about 28 minutes until a reactor coolant pump was started. A notification
of an unusual event was made by the licensee based on a fire located in the protected
area lasting longer than 10 minutes. The event resulted in no personnel
injuries and no release of radioactive
material.Fermi Unit 2: On December 12, 1991, an event involving
a self-propelled
crane occurred at the Enrico Fermi Atomic Power Plant, Unit 2. The Fermi Unit was in cold shutdown in preparation
for replacing
a main output transformer.
The crane, with its boom extended, attempted
to turn onto a roadway that is outside the protected
area but inside the owner controlled
area at the plant. While the crane spotter was directing
traffic, the crane operator proceeded
to turn onto the roadway. A lifting strap, which was dangling from the end of the crane boom made momentary
contact with one phase of a 120 kV transmission
line which was providing
offsite power to the plant. The circuit breaker for the line immediately
opened and reclosed, interrupting
and reestablishing
the power supply in a matter of cycles. No LOOP resulted.When the operator stopped the crane, the crane came to rest with the end of the boom extended above the transmission
line and with the transmission
line passing between the boom and lifting strap. The operator then backed up the crane. A second contact occurred between the transmission
line and the lifting
IN 92-13 February 18, 1992 strap. The circuit breaker again opened and reclosed rapidly so that no actual LOOP occurred.
The crane operator then informed his supervisor
of the event.No personnel
injuries or equipment
damage resulted.
No challenge
to plant safety systems occurred.Discussion
Information
Notice 90-25, Supplement
1, "Loss of Vital AC Power with Subsequent
Reactor Coolant System Heat-up," informed licensees
of problems that can occur when vehicular
traffic is not properly controlled
near safety systems or systems important
to safety. A significant
operating
event occurred at the Alvin W. Vogtle Generating
Plant (Vogtle) on March 20, 1990. An NRC incident investigation
team described
the circumstances
of the event in detail in NUREG-1410
titled, "Loss of Offsite AC Power and the Residual Heat Removal System During Mid-Loop Operations
at Vogtle Unit 1 on March 20, 1990." The Vogtle Unit 1 event was initiated
when a fuel and lubricants
truck, conducting
routine operations
in the switchyard, backed into a support column for a 230 kV feeder which was supplying
offsite power to the Unit. Ensuing events led to the total loss of vital ac power at the plant and operation
in natural circu-lation while the reactor coolant system was drained down to mid-loop.One of the lessons learned from the Vogtle incident was the need for licensees to develop appropriate
programs for controlling
vehicular
traffic at their sites. Although the events at the Diablo Canyon, Palo Verde, and Fermi plants were of less safety significance
than the Vogtle event, they demonstrate
that problems associated
with inadequate
control of vehicles continue to occur.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Charles E. Rossi, Direc Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
contact: N. Fields, NRR (301) 504-1173 Attachment:
List of Recently Issued NRC Information
Notices
r Q la 1-<C I , toW m c e I 2 C I-m:n~C)Z 0z Zoj 00 6 (n 2 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Date of Attachment
IN 92-13 February 18. 1992 Page I of I IInformation
tNotice No.92-12 92-11 92-10 92-09 92-08 92-07 92-06 92-05 Subject Effects of Cable Leakage Currents on Instrument
Settings and Indications
Soil and Water Contamina- tion at Fuel Cycle Facil-ities Brachytherapy
Incidents Involvihg
Iridium-192
Wire Used In Endobronchial
Treatments
Overloading
and Subsequent
Lock Out of Electrical
Buses During Accident Conditions
Revised Protective
Action Guidance for Nuclear Inci-dents Rapid Flow-Induced
Erosion/Corrosion
of Feedwater
Piping Reliability
of ATHS Mitiga-tion System and Other NRC Required Equipment
Not Controlled
by Plant Tech-nical Specifications
Potential
Coil Insulation
Breakdown
in ABB RXHH2 Relays Issuance Issued to 02/10/92 All holders of OLs or CPs for nuclear power reactors.02/05/92 All uranium fuel fabrica-tion and conversion
facil-ities.'01/31/92 All Nuclear Regulatory
Com-mission (NRC) licensees authorized
to use iridiwu-192 for brachy-therapy; manufacturers
and distributors
of iridium-192 wire for use In brachy-therapy.01/30/92 All holders of OLs or CPs for nuclear power reactors.01/23/92 All fuel cycle and materi-als licensees
authorized
to possess large quanti-ties of radioactive
materi-1al.01/09/92 All holders of OLs or CPs for pressurized
water reactors.01/15/92 All holders of OLs or CPs for nuclear power reactors.01/08/92 All holders of OLs or CPs for nuclear power reactors.0 a t ; 6 a OL -Operating
License CP I Construction
Permit
IN 92-13 February 18, 1992 strap. The circuit breaker again opened and reclosed rapidly so that no actual LOOP occurred.
The crane operator then informed his supervisor
of the event.No personnel
injuries or equipment
damage resulted.
No challenge
to plant safety systems occurred.Discussion
Information
Notice 90-25, Supplement
1, *Loss of Vital AC Power with Subsequent
Reactor Coolant System Heat-up," informed licensees
of problems that can occur when vehicular
traffic is not properly controlled
near safety systems or systems important
to safety. A significant
operating
event occurred at the Alvin W. Vogtle Generating
Plant (Vogtle) on March 20, 1990. An NRC incident investigation
team described
the circumstances
of the event in detail in NUREG-1410
titled, "Loss of Offsite AC Power and the Residual Heat Removal System During Mid-Loop Operations
at Vogtle Unit 1 on March 20, 1990." The Vogtle Unit 1 event was initiated
when a fuel and lubricants
truck, conducting
routine operations
in the switchyard, backed into a support column for a 230 kV feeder which was supplying
offsite power to the Unit. Ensuing events led to the total loss of vital ac power at the plant and operation
in natural circu-lation while the reactor coolant system was drained down to mid-loop.One of the lessons learned from the Vogtle incident was the need for licensees to develop appropriate
programs for controlling
vehicular
traffic at their sites. Although the events at the Diablo Canyon, Palo Verde, and Fermi plants were of less safety significance
than the Vogtle event, they demonstrate
that problems associated
with inadequate
control of vehicles continue to occur.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager., A harles E. Rossi, Directo Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
contact: N. Fields, NRR (301) 504-1173 Attachment:
List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
OFC : DOEA:OEAB
- ADM:RPB : DRPW:PD5 : DRPW:PD5 :DRPW:PD3-1
- SC:DOEA:OEAB:
-_- ___ ___ ___--_ __ ____ ------------
___ __ _____ ---------NAME : NFields* : JMain* : HRood* : CTrammell*
- TColburn*
- DFischer*
- -_- _ ___ ________ ___ ________ ---------DATE : 01/22/92 : 01/14/92 : 01/23/92 : 01/22/92 :01/28/92
- 01/30/92
- OFC :C:DOEA:OEAB
- C:DOEA:OGCB
- D:DOE :-NAME :AChaffee*
- CBerlinger*
- CRossi : DATE :01/31/92
- 02/10/92
- 02////9 DOCUMENT NAME: IN 92-13 IN 92-XX January xx, 1992 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
contact: N. Fields, NRR (301) 504-1173 Attachment:
List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
OFC : DOEA:OEAB
- ADM:RPB : DRPW:PD5 : DRPW:PD5 :DRPW:PD3-1
- SC:DOEA:OEAB:
NAME : NFields* : JMain* : HRood* : CTrammell*
- TColburn*
- DFischer*
- DATE : 01/22/92 : 01/14/92 : 01/23/92 : 01/22/92 :01/28/92
- 01/30/92
- OFC :C:DOEA:OEAB
- C: 0 B :D:DOEA__--- _ _----- :--. ,-- ------------
- .------------:------------:------------:---------
NAME :AChaffee*
- CBe in er :CRossi : DATE :01/31/92
- V/0/92 : / /92 : : : OFFICIAL RECORD COPY Document Name: IN/HF
IN 92-XX January xx, 1992 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
contact: N. Fields, NRR (301) 504-1173 Attachment:
List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
OFC : DOEA:OEAB
- ADM:RPB : DRPW:PD5 : DRPW:PD5 :DRPW:PD3-1
- SC:DOE :OEAB: NAME : NFields* : JMain* : HRood* : CTrammell*
- TColburn*
- DF cher : NAM N.els J*ain ..DATE : 01/22/92 : 01/14/92 : 01/23/92 : 01/22/92 :01/28/92
- 1/3q/92 : OFC :C:DOEA:OEAB
- C:DOEA:OGCB
- D:DOEA : :----- :-6Z&'--------:------------:------------
--------NAME :ACha fee :CBerlinger
- CRossi : : : DATE : L/31/92 : / /92 : / /92 : : : OFFICIAL RECORD COPY Document Name: IN/NF
This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office Of Nuclear Reactor Regulation (NRR) project manager.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
contact: N. Fields, NRR (301) 504-1173 Attachment:
List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
OFC : DOEA:OEAB
- ADM:RPB : DRPW:PD5 : DRPW:PD5 :DRPW:PD3-1
- SC:DOEA:OEAB:
_ _ ------ _ ____ _ ------------
_-__-___-____
NAME : NFields* : JMain* : HRood iTz : CTrammell*
- TColburn
- DFischer___ _ _ _ _ _____ _ -------------
DATE : 01/22/92 : 01/14/92 : \ /25/92 : 01/22/92 :' /ze/92 : / /92 OFC :C:DOEA:OEAB
- C:DOEA:OGCB
- D:DOEA : :____- _ ____ _____ ___ __ ------------
NAME :AChaffee
- CBerlinger
- CRossi : : DATE : / /92 :/ /92 :/ /92 : OFFICIAL RECORD COPY Document Name: IN/NF
IN 92-XX January xx, 1992 One of the lessons learned from the Vogtle incident was the need for licensees to develop appropriate
procedures
governing
vehicular
traffic in protected areas. Although the events at the Diablo Canyon and Palo Verde plants were of less safety significance
than the Vogtle event, they nevertheless
call into question the adequacy of the affected licensees'
programs for controlling
vehicular
traffic at their sites. The Diablo Canyon and Palo Verde events may prompt licensees
to reevaluate
the adequacy of their followup actions regarding the lessons learned from the Vogtle event.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office Of Nuclear Reactor Regulation (NRR) project manager.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
contact: N. Fields, NRR (301) 504-1173 Attachment:
List of Recently Issued NRC Information
Notices OFC : DOEA:PEAB
- JAM:RPB : DRPW:PD5 : DRPS JD5 :SC:DOEA:OEAB:C:DOEA:OEAB
NAME : NFields HM1' HRood C ammell DFischer :AChaffee
- -- ------- ------------
A , f O ------------
- ------------
___ ___ _ _ _ __ _DATE: / /2.2/92 : /1,9/92 : / /92 : /y4P92 : / /92 : / /92 OFC :C:DOEA:OGCB
- D:DOEA : : : : NAME :CBerlinger
- CRossi : : DATE: / /92 : / /92 : : : : OFFICIAL RECORD COPY Document Name: IN/NF
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list | - Information Notice 1992-01, Cable Damage Caused by Inadequate Cable Installation Procedures and Controls (3 January 1992)
- Information Notice 1992-02, Relap5/MOD3 Computer Code Error Associated with the Conservation of Energy Equation (3 January 1992)
- Information Notice 1992-02, Relap5/Mod3 Computer Code Error Associated with the Conservation of Energy Equation (3 January 1992)
- Information Notice 1992-03, Remote Trip Function Failures in General Electric F-Frame Molded-Case Circuit Breakers (6 January 1992)
- Information Notice 1992-04, Potter and Brumfield Model Mdr Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment)
- Information Notice 1992-04, Potter and Brumfield Model MDR Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs RXMH2 Relays (8 January 1992)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs Rxmh2 Relays (8 January 1992)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in ABS RXMH2 Relays (8 January 1992)
- Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment Not Controlled by Plant Technical Specifications (15 January 1992)
- Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment not Controlled by Plant Technical Specifications (15 January 1992)
- Information Notice 1992-07, Rapid Flow-induced Erosion/Corrosion of Feedwater Piping (9 January 1992)
- Information Notice 1992-08, Revised Protective Action Guidance for Nuclear Incidents (23 January 1992)
- Information Notice 1992-09, Overloading and Subsequent Lock Out of Electrical Buses During Accident Conditions (30 January 1992)
- Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire Used in Endobronchial Treatments (31 January 1992, Topic: Brachytherapy)
- Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire used in Endobronchial Treatments (31 January 1992, Topic: Brachytherapy)
- Information Notice 1992-11, Soil and Water Contamination at Fuel Cycle Facilities (5 February 1992, Topic: Brachytherapy)
- Information Notice 1992-12, Effects of Cable Leakage Currents on Instrument Settings and Indications (10 February 1992, Topic: Brachytherapy)
- Information Notice 1992-13, Inadequate Control Over Vehicular Traffic at Nuclear Power Plant Sites (18 February 1992, Topic: Brachytherapy)
- Information Notice 1992-14, Uranium Oxide Fires at Fuel Cycle Facilities (21 February 1992, Topic: Brachytherapy)
- Information Notice 1992-15, Failure of Primary Systems Compression Fitting (24 February 1992)
- Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown (25 February 1992, Topic: Reactor Vessel Water Level, Temporary Modification, Brachytherapy)
- Information Notice 1992-17, NRC Inspections of Programs Being Developed at Nuclear Power Plants in Response to Generic Letter 89-10 (26 February 1992, Topic: Stroke time)
- Information Notice 1992-18, Potential for Loss of Remote Shutdown Capability During a Control Room Fire (28 February 1992, Topic: Hot Short, Safe Shutdown)
- Information Notice 1992-19, Misapplication of Potter and Brumfield Mdr Rotary Relays (2 March 1992)
- Information Notice 1992-19, Misapplication of Potter and Brumfield MDR Rotary Relays (2 March 1992)
- Information Notice 1992-20, Inadequate Local Leak Rate Testing (3 March 1992)
- Information Notice 1992-21, Spent Fuel Pool Reactivity Calculations (24 March 1992)
- Information Notice 1992-23, Results of Validation Testing of Motor-Operated Valve Diagnostic Equipment (27 March 1992)
- Information Notice 1992-24, Distributor Modification to Certain Commercial-Grade Agastat Electrical Relays (30 March 1992)
- Information Notice 1992-25, Pressure Locking of Motor-Operated Flexible Wedge Gate Valves (2 April 1992, Topic: Stroke time, Hydrostatic)
- Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of ITE/Gould A.C. Relays used in Safety-Related Applications (3 April 1992)
- Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of Ite/Gould A.C. Relays Used in Safety-Related Applications (3 April 1992)
- Information Notice 1992-28, Inadequate Fire Suppression System Testing (8 April 1992, Topic: Safe Shutdown)
- Information Notice 1992-29, Potential Breaker Miscoordination Caused by Instantaneous Trip Circuitry (17 April 1992)
- Information Notice 1992-30, Falsification of Plant Records (23 April 1992)
- Information Notice 1992-31, Electrical Connection Problem in Johnson Yokogawa Corporation YS-80 Programmable Indicating Controllers (27 April 1992)
- Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (Within 10 Miles) Emergency Operations Facilities and Technical Support Centers (29 April 1992)
- Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (within 10 Miles) Emergency Operations Facilities and Technical Support Centers (29 April 1992)
- Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices Are Installed (30 April 1992)
- Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices are Installed (30 April 1992)
- Information Notice 1992-34, New Exposure Limits for Airborne Uranium and Thorium (6 May 1992)
- Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping Inside Containment at a Boiling Water Reactor (6 May 1992)
- Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping inside Containment at a Boiling Water Reactor (6 May 1992)
- Information Notice 1992-36, Intersystem LOCA Outside Containment (7 May 1992)
- Information Notice 1992-37, Implementation of the Deliberate Misconduct Rule (8 May 1992)
- Information Notice 1992-38, Implementation Date for the Revision to the EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (26 May 1992, Topic: Brachytherapy)
- Information Notice 1992-39, Unplanned Return to Criticality During Reactor Shutdown (13 May 1992, Topic: Fuel cladding)
- Information Notice 1992-40, Inadequate Testing of Emergency Bus Undervoltage Logic Circuitry (27 May 1992)
- Information Notice 1992-41, Consideration of Stem Rejection Load In Calculation of Required Valve Thrust (29 May 1992, Topic: Anchor Darling)
... further results |
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