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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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
CL-
AAClec on 2/1 9 lJ-I
..... IN 92-13 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
2 C
I-
m
Attachment
IN 92-13 February 18. 1992
- n~ Page I of I
r Q C)Z LIST OF RECENTLY ISSUED
0z NRC INFORMATION NOTICES
I
la 1-
<C Zoj IInformation Date of
tNotice No. Subject Issuance Issued to
I ,
toW
m 00 92-12 Effects of Cable Leakage 02/10/92 All holders of OLs or CPs
c e 6 Currents on Instrument for nuclear power reactors.
Settings and Indications
92-11 Soil and Water Contamina- 02/05/92 All uranium fuel fabrica- (n tion at Fuel Cycle Facil- tion and conversion facil- ities ities.'
2
92-10 Brachytherapy Incidents 01/31/92 All Nuclear Regulatory Com- Involvihg Iridium-192 Wire mission (NRC) licensees
Used In Endobronchial authorized to use
Treatments iridiwu-192 for brachy- therapy; manufacturers and
distributors of iridium-192 wire for use In brachy- therapy.
92-09 Overloading and Subsequent 01/30/92 All holders of OLs or CPs
Lock Out of Electrical for nuclear power reactors.
Buses During Accident
Conditions
92-08 Revised Protective Action 01/23/92 All fuel cycle and materi- Guidance for Nuclear Inci- als licensees authorized
dents to possess large quanti- ties of radioactive materi-
1al.
92-07 Rapid Flow-Induced Erosion/ 01/09/92 All holders of OLs or CPs
Corrosion of Feedwater Piping for pressurized water
reactors.
92-06 Reliability of ATHS Mitiga- 01/15/92 All holders of OLs or CPs
tion System and Other NRC for nuclear power reactors.
Required Equipment Not
Controlled by Plant Tech- nical Specifications
92-05 Potential Coil Insulation 01/08/92 All holders of OLs or CPs
Breakdown in ABB RXHH2 Relays for nuclear power reactors.
OL - Operating License
0
CP I Construction Permit
a
t 6a;
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
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
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
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
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 : DRPSJD5 :SC:DOEA:OEAB:C:DOEA:OEAB
NAME : NFields HRood
HM1' 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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