Control Rod Insertion ProblemsML031060255 |
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: |
02/15/1996 |
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From: |
Crutchfield D Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-96-012, NUDOCS 9602090161 |
Download: ML031060255 (10) |
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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. 20555-0001 February 15, 1996 NRC INFORMATION NOTICE 96-12: CONTROL ROD INSERTION PROBLEMS
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 recent events during which rod control cluster
assemblies failed to insert fully. 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
South Texas Project
On December 18, 1995, with South Texas Unit 1 at 100 percent power, a pilot
wire monitoring relay actuation caused a main transformer lock out which
resulted in a turbine trip and reactor trip. While verifying that control
rods had inserted fully after the trip, operators noted that the rod bottom
lights of three control rod assemblies were not lit; the digital rod position
indication for each rod indicated six steps withdrawn. Boration of the
reactor coolant system was occurring with the charging pump suction having
been transferred to the refueling water storage tank. One rod did drift into
the fully inserted rod bottom position within one hour, and the other two rods
were manually inserted later. During subsequent testing of all control rods
in the affected banks, the rod position indication for the same three
locations as well as a new location indicated six steps withdrawn. As
compared to prior rod drop testing, no significant differences in rod drop
times were noted before reaching the upper dashpot area for any of the control
rods. Within an hour after the rod drop tests, two of the rods drifted to rod
bottom position and the other two were manually inserted. All four control
rods were located in fuel assemblies that were in their third cycle with
burnup greater then 42,880 megawatt days(MWD)/metric ton uranium(MTU).
CPf\ j45T OcA7(ce-~ cW~4oI2- o
9602090161 ;
ts>\3Sq
IN 96-12 February 15, 1996 Wolf Creek
from 80-percent power, five control
On January 30, 1996, after a manual scram insert fully. Two rods remained'at six
rod assemblies at Wolf Creek failed to one at 18 steps. Three of the affected
steps withdrawn, two at 12 steps, and
20 minutes, one within 60 minutes, and
rods drifted to fully inserted within the scram, the licensee initiated
the last one within 78 minutes. After all rods did not insert fully. The
emergency boration, as required, becausefuel with burnup greater than
five rods were all in 17x17 VANTAGE 5H
47,000 MWD/MTU.
Discussion
fuel length core design is used.
At both South Texas units, a 14-foot active 12-foot active fuel design and the
Several differences between the standard fuel design is approximately 76.2 cm
14-foot one are as follows: the 14-foot assembly design, it has 10 mid grids
[30 inches] longer than the standard fuel25.4 cm [10 inches] longer and
compared to 8 and the dashpot region is rod radial clearances above and in
comprises a double dashpot. The controlassembly are similar to those of the
the dashpot region of the 14-foot fuel contains three different 17x17 fuel
standard design. The South Texas core VANTAGE 5H--all of which are designed
types--Standard XL, Standard XLR, and was the first operating cycle with
and fabricated by Westinghouse. This 57 silver-indium-cadmium rods. The
VANTAGE 5H fuel. The core also contains Standard XLR fuel assemblies.
four affected rods were found in twice-burned
traces revealed no significant change
During subsequent testing, the rod drop rods did not show recoil on the
in dashpot entry time; however, the affected
affect that is normally seen in the
rod drop trace. Recoil is a dampening hub spring contact against the fuel
traces due to control rod assembly spiderwere tested, the results revealed no
assembly. When similar rods in Unit 2 the "no recoil" effect but inserted
adverse indications. One rod did show
fully into the core.
testing of all of the control rod
At Wolf Creek, subsequent cold, full flowrods, including the five control rods
assemblies indicated that eight control January 30, 1996, reactor trip, did
that did not fully insert following the rod, H2, paused at 96 steps, not fully insert when tripped. One control to 30 steps over the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
stopped at 90 steps, and slowly inserted The 7 other affected rods stopped
The control rod was then manually inserted.5 of which fully inserted within
at various heights in the dashpot region, to the bottom within one and a half
22 minutes. One of the other two driftedbe manually inserted. The remaining
hours while the remaining rod needed to a number of the rods did not
45 rods fully inserted when dropped, although
Of the total 53 control rod
exhibit the expected number of recoils. the dashpot region) is a hafnium
assemblies, H2 (thie only rod slowing outside control rod
control rod, while the remaining are silver-indium-cadmium
rods that stuck, as well as those rods
assemblies. The licensee retested all and the results were similar to the
that failed to recoil more than twice, previous testing.
I
IN 96-12 February 15, 1996 Westinghouse, Westinghouse Owners Group, and the respective licensees are
pursuing the root cause identification of these events. Possible root causes
are as follows: debris (foreign matter), control rod or drive line
degradation, corrosion products, thimble tube bow, fuel assembly bow and/or
twist, reduction in thimble tube diameter, adverse alignment of guide tube
cards, and/or design tolerances.
Some foreign reactors have also experienced slow and/or stuck control rod
assemblies.
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 Office of
Nuclear Reactor Regulation project manager.
a or
Division of Reactor P gram Management
Office of Nuclear Reactor Regulation
Technical contacts: Margaret Chatterton, NRR
(301) 415-2889 Internet: msc1@nrc.gov
Stephen Koenick, NRR
(301) 415-2841 Internet: ssk2@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
K>
Attachment
IN 96-12 February 15, 1996 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
96-11 Ingress of Demineralizer 02/14/96 All holders of OLs or CPs
Resins Increases Potential for pressurized water
Stress Corrosion Cracking nuclear power reactors
of Control Rod Drive
Mechanism Penetrations
96-10 Potential Blockage by 02/13/96 All holders of OLs or CPs
Debris of Safety System for nuclear power reactors
Piping Which is Not Used
During Normal Operation
or Tested During Surveil- lances
96-09 Damage in Foreign Steam 02/12/96 All holders of OLs or CPs
Generator Internals for pressurized water
reactors
96-08 Thermally Induced Pres- 02/05/96 All holders of OLs or CPs
sure Locking of a High for nuclear power reactors
Pressure Coolant Injec- tion Gate Valve
96-07 Slow Five Percent Scram 01/26/96 All holders of OLs or CPs
Insertion Times Caused for boiling water reactors
By Viton Diaphragms in
Scram Solenoid Pilot
Valves
96-06 Design and Testing 01/25/96 All holders of OLs or CPs
Deficiencies of Tornado for nuclear power reactors
Dampers at Nuclear Power
Plants
96-05 Partial Bypass of Shutdown 01/18/96 All holders of OLs or CPs
Cooling Flow from the for boiling water reactors
Reactor Vessel
96-04 Incident Reporting Require- 01/10/96 All radiography licensees
ments for Radiography and manufacturers of radio- Licensees graphy equipment
OL = Operating License
CP = Construction Permit
IN 96-12 February 15, 1996 Westinghouse, Westinghouse Owners Group, and the respective licensees are
pursuing the root cause identification of these events. Possible root causes
are as follows: debris (foreign matter), control rod or drive line
degradation, corrosion products, thimble tube bow, fuel assembly bow and/or
twist, reduction in thimble tube diameter, adverse alignment of guide tube
cards, and/or design tolerances.
Some foreign reactors have also experienced slow and/or stuck control rod
assemblies.
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 Office of
Nuclear Reactor Regulation project manager.
original signed by
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Margaret Chatterton, NRR
(301) 415-2889 Internet: mscl@nrc.gov
Stephen Koenick, NRR
(301) 415-2841 Internet: ssk2@nrc.gov
Reviewed and concurred on by tech editor 02/01/96 *SEE PREVIOUS
CONCURRENCES
DOCUMENT NAME: 96-12.IN
To receive a copy of this document, Indicate in the box: 'C' = Copy without enclosures 'E'
IOFFICE ITECH CONTS I IC:SPLB I
l c:
NAME MChatterton* RJones* AChaffee
SKoenick* L
DATE 02/07/96 02/08/96 02/08/96
02/06/96 ,~- I-T,'T~AI nrd~r l dflflv
I
UrrtIMaL KLtUKU 6ur l
IN 96-xx
February xx, 1996 hafnium control rod, while the remaining are silver-indium-cadmium RCCAs. toThe
licensee retested all rods that stuck, as well as those rods that failed
recoil more than twice, and the results were similar to the previous testing.
Some foreign reactors have also experienced slow and/or stuck RCCAs.
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 Office of
Nuclear Reactor Regulation project manager.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Margaret Chatterton, NRR
(301) 415-2889 Internet: mscl~nrc.gov
Stephen Koenick, NRR
(301) 415-2841 Internet: ssk2@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
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IN 96-xx
February xx, 1996 hafnium control rod, while the remaining are silver-indium-cadmium RCCAs. The
licensee retested all rods that stuck, as well as those rods that failed to
recoil more than twice, and the results were similar to the previous testing.
Some foreign reactors have also experienced slow and/or stuck RCCAs.
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 Office of
Nuclear Reactor Regulation project manager.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Margaret Chatterton, NRR
(301) 415-2889 Internet: mscl@nrc.gov
Stephen Koenick, NRR
(301) 415-2841 Internet: ssk2@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\IN\IN ST CR.SSK
OFFICE PECB/DRPM I SPLB /DSSA ADM:PUB I SC:SPLBDSSA 1 RIVDRS
NAME SKoenick* MChatterton* TECH ED* EWeiss*
DATE 2/06/96 2/07/96 2/01/96 2/07/96 l 2/08/96 OFFICE IBC:SPLB/DSSA I ISC:PECB/DOPS-1C/PECB:DOPS I DRPM I -
NAME RJones* EGoodw/ n ( AChaffee DCrutchfeld
DATE 2/08/96 E /96
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IN 96-xx
February xx, 1996 rods did not exhibit the expected number of recoils. The licensee retested
all rods that stuck, as well as those rods that failed to recoil more than
twice, and the results were similar to the previous testing.
Some foreign reactors have also experienced of slow and/or stuck RCCAs.
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 Office of
Nuclear Reactor Regulation project manager.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Margaret Chatterton, NRR
(301) 415-2889 Internet: mscltnrc.gov
Stephen Koenick, NRR
(301) 415-2841 Internet: ssk2@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
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February xx, 1996 Some foreign reactors have also experienced of slow and/or stuck RCCAs.
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 Office of
Nuclear Reactor Regulation project manager.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Margaret Chatterton, NRR
(301) 415-2889 Internet: msclnrc.gov
Stephen Koenick, NRR
(301) 415-2841 Internet: ssk2@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\IN\IN ST CR.SSK
OFFICE PECB/DRPM I SPLB/DSSA I ADM:PUB I SC:SPLB/DSSA I lRIV/DRS I j
NAME SKoenick* MChatterton* TECH ED* EWeiss*
DATE 2/06/96 2/07/1/92/ 96 2/07/96 2/ /96
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DATE 2/ T/96 I 2/ /96 12/ /96 See previous concurrence
OFFICIAL RECORD COPY
Dennis M. Crutchfi'YXd, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts:
Stephen Koenick, NRR
(301) 415-2841
/_ Internet: ssk2@nrc.gov
Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\IN\IN-DAMP
OFFICE SPLB/DSSA I SCSPLB/DSSA I ADM:PUB I BC:SPLB/DSSA I RIV/DRS I
NAME MChatterton EWeiss TECH ED kp6 RJones
DATE 2/ /96 2/ /96 2///96 2/ /96 2/ /96 I
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list | - Information Notice 1996-01, Potential For High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-01, Potential for High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-02, Inoperability of Power-Operated Relief Valves Masked by Downstream Indications During Testing (5 January 1996, Topic: Stroke time)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation as a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation As a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-04, Incident Reporting Requirements for Radiography Licensees (10 January 1996, Topic: Brachytherapy, Overexposure, Depleted uranium)
- Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel (18 January 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-06, Design & Testing Deficiencies of Tornado Dampers at Nuclear Power Plants (25 January 1996)
- Information Notice 1996-07, Slow Five Percent Scram Insertion Times Caused by Viton Diaphragms in Scram Solenoid Pilot Valves (26 January 1996)
- Information Notice 1996-08, Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate Valve (5 February 1996, Topic: Anchor Darling, Cold shutdown justification)
- Information Notice 1996-09, Damage in Foreign Steam Generator Internals (12 February 1996, Topic: Eddy Current Testing, Earthquake)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which Is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential For Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996, Topic: Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996, Topic: Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- Information Notice 1996-12, Control Rod Insertion Problems (15 February 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-13, Potential Containment Leak Paths Through Hydrogen Analysis (26 February 1996, Topic: Stress corrosion cracking, Integrated leak rate test)
- Information Notice 1996-14, Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1 (1 March 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-15, Unexpected Plant Performance During Performance of New Surveillance (8 March 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-16, BWR Operation with Indicated Flow Less than Natural Circulation (14 March 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-17, Reactor Operation Inconsistent with the Updated Final Safety Analysis Report (18 March 1996)
- Information Notice 1996-18, Compliance with 10 CFR Part 20 for Airborne Thorium (25 March 1996, Topic: Stress corrosion cracking, Brachytherapy)
- Information Notice 1996-19, Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal (2 April 1996, Topic: Tone Alert Radio, Siren)
- Information Notice 1996-20, Demonstration of Associated Equipment Compliance with 10 CFR 34.20 (4 April 1996, Topic: Brachytherapy)
- Information Notice 1996-21, Safety Concerns Related to the Design of the Door Interlock Circuit on Nucletron High-Dose Rate and Pulsed Dose Rate Remote Afterloading Brachytherapy Devices (10 April 1996, Topic: Brachytherapy)
- Information Notice 1996-22, Improper Equipment Settings Due to Use of Nontemperature-Compensated Test Equipment (11 April 1996, Topic: Brachytherapy)
- Information Notice 1996-23, Fires in Emergency Diesel Generator Exciters During Operation Following Undetected Fuse Blowing (22 April 1996, Topic: Brachytherapy, Overspeed trip, Overspeed)
- Information Notice 1996-24, Preconditioning of Molded-Case Circuit Breakers Before Surveillance Testing (25 April 1996, Topic: Brachytherapy)
- Information Notice 1996-25, Traversing In-Core Probe Overwithdrawn at Lasalle County Station, Unit 1 (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems with Overhead Cranes (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems With Overhead Cranes (30 April 1996)
- Information Notice 1996-27, Potential Clogging of High Pressure Safety Injection Throttle Valves During Recirculation (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-28, Suggested Guidance Relating to Development and Implementation of Corrective Action (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-29, Requirements in 10 CFR Part 21 for Reporting and Evaluating Software Errors (20 May 1996, Topic: Brachytherapy)
- Information Notice 1996-30, Inaccuracy of Diagnostic Equipment for Motor-Operated Butterfly Valves (21 May 1996)
- Information Notice 1996-31, Cross-Tied Safety Injection Accumulators (22 May 1996)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (II) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (ii) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-33, Erroneous Data From Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-33, Erroneous Data from Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-34, Hydrogen Gas Ignition During Closure Welding of a VSC-24 Multi-Assembly Sealed Basket (31 May 1996)
- Information Notice 1996-35, Failure of Safety Systems on Self-Shielded Irradiators Because of Inadequate Maintenance and Training (11 June 1996)
- Information Notice 1996-36, Degradation of Cooling Water Systems Due to Icing (12 June 1996, Topic: High winds, Ultimate heat sink, Frazil ice)
- Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown (18 June 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-38, Results of Steam Generator Tube Examinations (21 June 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-39, Estimates of Decay Heat Using ANS 5.1 Decay Heat Standard May Vary Significantly (5 July 1996)
- Information Notice 1996-40, Defciencies in Material Dedication and Procurement Practices and in Audits of Vendors (7 October 1996, Topic: Coatings, Commercial Grade, Troxler)
- Information Notice 1996-41, Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation (26 July 1996, Topic: Feedwater Heater)
- Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves (5 August 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-43, Failures of General Electric Magne-Blast Circuit Breakers (2 August 1996, Topic: Hardened grease)
... further results |
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