Failure of a Main Steam Safety Valve to Reseat Caused by an Improperly Installed Release NutML031050516 |
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: |
11/20/1996 |
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From: |
Martin T Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-96-061, NUDOCS 9611140131 |
Download: ML031050516 (10) |
|
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, DC 20555-0001 November 20, 1996 NRC INFORMATION NOTICE 96-61: FAILURE OF A MAIN STEAM SAFETY VALVE TO
RESEAT CAUSED BY AN IMPROPERLY INSTALLED
RELEASE NUT
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 failure of a main steam safety valve (MSSV) to reseat during a plant
transient as a result of an improperly installed release nut. 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
At Arkansas Nuclear One, Unit 1 (ANO-1), there are eight MSSVs on each of the A and B
steam generators. On May 19, 1996, the plant experienced a feedwater transient and a
reactor trip. Six of the MSSVs on the B steam header opened as designed, but one of these
failed to close following the secondary overpressure condition. As a result of the stuck-open
MSSV (PSV-2685), the secondary side of the B steam generator was isolated in accordance
with plant emergency procedures and allowed to toil dry. None of the A MSSVs opened
during this event, and the A steam generator remained operable.
The licensee determined that PSV-2685 failed to reseat because a release nut on the valve
spindle had been improperly installed. The release nut is installed to provide a surface
against which a lifting lever can bear to permit opening of the valve manually. The nut is
castellated to provide a slot through which a cotter pin may be aligned with a hole in the
spindle so that, with the cotter pin engaged in the slot and extending through the hole in the
stem, the nut would be prevented from tuming. With the nut held in its fixed position, there
was to be a specified clearance between the bottom of the nut and the top of the lifting lever
beneath to allow for expansion and contraction of the spindle during thermal cycles.
Following the ANO-1 event, the licensee found that the release nut had been threaded onto
the valve spindle at a position too low to be property staked by the cotter pin. Because the
cotter pin could not prevent the rotation of the nut, vibration occurring during the valve
discharge caused the nut to turn and travel down the stem until it rested upon the lifting lever
mechanism. Without any clearance between the bottom of the nut and the top of the lever, the valve was held open. x
9611140131 P AR t p tI t .O1D\
,>gw 6ntll;l8 rt e-
K>11 IN 96-61 November 20, 1996 As a result of Ks review of the event, the licensee concluded that a contributing cause of the
problem was an inadequate instruction related to establishing the proper position of the
release nut with respect to the cotter pin hole in the stem. The instruction, derived from
vendor guidance, specified the clearance between the release nut and the lifting lever as
1/16 inch to 1/8 inch. The minimum value of 1/16 inch was necessary to allow enough space
to accommodate thermal effects on clearances, but the maximum value of 1/8 inch was an
unneeded limitation that distracted attention from the need to ensure that the nut was staked
sufficiently with the cotter pin to preclude nut rotation. The licensee changed the
maintenance procedure to eliminate the confusion about the nut-to-lever clearance and
modified the design of the release nut to increase the depth of the slot, thereby providing
greater assurance of proper engagement between the cotter pin and the nut. In subsequent
action, the licensee determined that the manual lifting devices were unnecessary from an
operational standpoint and removed the lever and nut assemblies from all the steam safety
valves.
The licensee also found other MSSVs that had less-than-desirable engagement between the
release nut and the cotter pin. These valves were on the main steam headers from both the
A and the B steam generators. If a transient caused valves on both headers to open and
they failed to reseat, reactor decay heat removal could have been accomplished using main
or emergency feedwater in a "trickle-feed" process specified in the existing emergency
operating procedures.
Discussion
Other operating reactor events have occurred that involved the failure of MSSVs to reseat as
a result of the rotation of release nuts. In February 1984, at St. Lucie Unit 2, an MSSV stuck
partially open following the actuation of the valve. An MSSV at the Davis-Besse Nuclear
Power Station stuck open in March 1984, permitting the steam generator to boil dry. In both
of these events, the release nuts on the MSSVs rotated because the cotter pins had corroded
and failed. The corrective actions consisted of either replacing the cotter pins with stainless
steel pins or removing those parts of the lifting mechanism that the release nut would contact
if the nut were to rotate downward. These events are addressed in NRC Information
Notice 84-33, "Main Steam Safety Valve Failures Caused by Failed Cotter Pins." More
recently, in 1993, an MSSV failed to reseat at Crystal River Unit 3 because the release nut
was not engaged with the cotter pin, just as in the current ANO-1 event. The Crystal River
event is described in Licensee Event Report 93-09, submitted to the NRC by the licensee, Florida Power Corporation, by letter dated October 13, 1993, Docket No. 50-302.
Licensees have also reported situations in which the cotter pins were missing from the
release nuts. A main steam safety valve failed to reseat at ANO-1 in May 1989 because the
cotter pin was missing, as reported in Licensee Event Report 89-018. The Oconee licensee
reported, under the requirements of 10 CFR Part 50.72, that, during inspections of Units 2 and 3 on October 14, and October 24, 1996, respectively, cotter pins were missing
from 4 of 16 main steam safety valves on Unit 2 and from 2 of 16 valves on Unit 3. On
IN 96-61 November 20, 1996 October 31, 1996, the Millstone licensee reported, also under the requirements of 10 CFR
Part 50.72, that inspection of the main steam safety valves on Unit 3 showed that the cotter
pins were missing from 2 of the 20 valves.
The valves at ANO-1, Davis-Besse, Crystal River, and Millstone were manufactured by
Dresser Industries, Inc. The valves at St. Lucie and Oconee were manufactured by Crosby
Valve and Gage company.
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 (NRR) project manager.
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Charles G. Hammer, NRR
(301) 415-2791 Email: cgh@nrc.gov
Terrence Reis, Region IV
(817) 860-8185 Email: txr@nrc.gov
Robert A. Benedict, NRR
(301) 415-1157 Email: rabl@nrc.gov
Attachments:
1. Steam Safety Valve
2. List of Recently Issued NRC Information Notices
60 Jk/ka
IN 96-61 November 20, 1996 STEAM SAFETY VALVE
COTTER F'IN SPINDLE
lU T ....- ::-
TOP LEV 'ER
FRONT TOP
......................
W-oJ
Attachment 2 IN 96-61 November 20, 1996 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
96-60 Potential Common-Mode Post- 11/14/96 All holders of OLs or
Accident Failure of Residual CPs for nuclear power
Heat Removal Heat Exchangers reactors
96-59 Potential Degradation of 10/30/96 All holders of OLs or
Post Loss-of-Coolant CPs for nuclear power
Recirculation Capability reactors
as a Result of Debris
96-58 RCP Seal Replacement with 10/30/96 All holders of OLs or
Pump on Backseat CPs for pressurized-water
reactors
96-57 Incident-Reporting Require- 10/29/96 All U.S. Nuclear
ments Involving Intakes, Regulatory Commission
During a 24-Hour Period licensees
That May Cause a Total
Effective Dose Equivalent
in Excess of 0.05 Sv
(5 rems)
OL = Operating License
CP = Construction Permit
IN 96-61 November 20, 1996 October 31, 1996, the Millstone licensee reported, also under the requirements of 10 CFR
Part 50.72, that inspection of the main steam safety valves on Unit 3 showed that the cotter
pins were missing from 2 of the 20 valves.
The valves at ANO-1, Davis-Besse, Crystal River, and Millstone were manufactured by
Dresser Industries, Inc. The valves at St. Lucie and Oconee were manufactured by Crosby
Valve and Gage company.
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 (NRR) project manager.
original signed by
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Charles G. Hammer, NRR
(301) 415-2791 Email: cgh@nrc.gov
Terrence Reis, Region IV
(817) 860-8185 Email: btr@nrc.gov
Robert A. Benedict, NRR
(301) 415-1157 Email: rabl@nrc.gov
Attachments:
1. Steam Safety Valve
2. List of Recently Issued NRC Information Notices
Tech Editor reviewed and concurred on 08/24/96
- SEE PREVIOUS CONCURRENCES
DOCUMENT NAME: 96-63.IN
To receive a copy of this document. Ihdlcate hI the box: 'C - Copy w/o
attachment/enclosure E' - Copy w/attachmentfenclosure 'N' - No copy
OFFICE TECH CONTS I C/EMEB:DE I C/PECB:DRPM RPM [ i
NAME CHammer* RWessman* AChaffee* TMa7ti, -
TReis EFG for AEC
RBenedict*_
DATE 08/27/96 08/27/96 11/12/96 j, /y1/96
11/07/96 l
OFFICIAL RECORD COPY
IN 96-xx
November xx, 1996 four of 16 main steam safety valves on Unit 2 and from two of 16 valves on Unit 3. On
October 31, 1996, the Millstone licensee reported, also under the requirements of 10 CFR
Part 50.72, that inspection of the main steam safety valves on Unit 3 showed that the cotter
pins were missing from two of the twenty valves.
The valves at ANO-1, Davis-Besse, Crystal River, and Millstone were manufactured by
Dresser Industries, Inc. The valves at St. Lucie and Oconee were manufactured by Crosby
Valve and Gage company.
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 (NRR) project manager.
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: Charles G. Hammer, NRR
(301) 415-2791 Email: cgh@nrc.gov
Terrence Reis, Region IV
(817) 860-8185 Email: txrenrc.gov
Robert A. Benedict, NRR
(301) 415-1157 Email: rabl@nrc.gov
Attachments:
1. Steam Safety Valve
2. List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
DOCUMENT NAME: G:\RAB1\ANONUTIN.REV
To receive a copy of this document, Indicate hi the box: 'C' - Copy w/o
attachment/enclosure E - Copy w/attachmentlenclosure 'N' - No copy
OFFICE TECH CONTS I C/EMEB:DE C/PECB:DRPM I
NAME CHamler* RWessman* AChaffee* TMartin
TReis EFG for AEC
RBenedict*
DATE 08/27/96 08/27/96 11/12/96 / /96
.11/07/96 O F_ RECORD
OFFICIAL RECORD CUPY
IN 96-xx
November xx, 1996 cotter pin was missing, as reported in Licensee Event Report 89-018. The Oconee licensee
reported, under the requirements of 10 CFR Part 50.72, that, during inspections of Units 2 and 3 on October 14, 1996, and October 24, 1996, respectively, cotter pins were missing
from four of 16 main steam safety valves on Unit 2 and from two of 16 valves on Unit On
October 31, 1996, the Millstone licensee reported, also under the requirements of Il, KFR
Part 50.72, that inspection of the main steam safety valves on Unit 3 showed th - he cotter
pins were missing from two of the twenty valves.
The valves at ANO-1, Davis-Besse, Crystal River, and Millstone were m ufactured by
Dresser Industries, Inc. The valves at St. Lucie and Oconee were m ufactured by Crosby
Valve and Gage company.
This information notice requires no specific action or written re onse. Ifyou have any
questions about the information in this notice, please conta one of the technical contacts
listed below or the appropriate Office of Nuclear Reactor gulation (NRR) project manager.
Thomas T artin, Director
Division Reactor Program Management
Office f Nuclear Reactor Regulation
Technical Contacts: Charles G. Hammer, R
(301) 415-2791 Email: cgh@nrc.g
Terrence Reis egion IV
(817) 860-81 Email: txr nrc.gov
Robert . Benedict, NRR
(301 415-1157 E I: rabi@nrc.gov
Attachments:
1. Steam Safety V e
2. List of Recentl ssued NRC Information Notices
DOCUMENT NAME: G:\ B1\ANONUTIN.REV
To mceive a copy of ths docu tr.kiicate In the box: 'C - Copy w/o
attachmentlenclosurs E - y w/attachment/ nclosure 'N' - No copy
OFFICE TECH PONTS C/EMEB:DE C/PECB:DRPM D/DRPM I
NAME CR r*RWessman* AChaffee TMartin
TR nedict* Eqq7 DATE 8/27/96 08/27/96 96 / /96
/CA 7 /96 R/
/ . OFFICIAL RECORD COP
IN 96- October , 1996 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 (NRR) project man er.
Thomas T. Martin, Director
Division of Reactor Program nagement
Office of Nuclear Reactor R ulation
Technical Contacts: Charles G. Hammer, NRR
(301) 415-2791 Email: cghenrc.gov
Terrence Reis, Region IV
(817) 860-8185 Email: txr@nrc.gov
Robert A. Benedict, NRR
(301) 415-1157 Email: rabl@nrc.gov
Attachments:
1. Steam Safety Valve
2. List of Recently Issued NRC Informati Notices
- SEE PREVIOUS CONCURRENCES
DOCUMENT NAME: G:\RAB1\ANONUTIN. V
To receive a copy of this document. indicate in the box: - - Copy w/o
attachmentlenclosure 'E' - Copy w/attachment/enclosre N' - No copy --- - - - I
OFFICE TECH CONTS I VEMEB:DE C/PECB:DRPM
NAME CHalammer* ,RWessman* AChaffee TMartin
TReis rvtb-ti'ol
RBenedict*_ _ _ _ __ _ _ _
DATE 08/27/96 / 08/27/96 / /96 / /96
_/ /96 r -TAI - rM U__Il I
_
UI-1-LIML KtUKU CUPT
(--)
K>
IN 96- August , 1996 Page 3 of
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 (NRR) project manager.
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: Charles G. Hammer, NRR
(301) 415-2791 Email: cgh@nrc.gov
Terrence Reis, Region IV
(817) 860-8185 Email: txr@nrc.gov
Robert A. Benedict, NRR
(301) 415-1157 Email: rabl@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\RAB1\ANONUTIN.REV
To receive a copy of this document, hdlcate hI the box: 'C - Copy w/o
attachment/enclosure 'E'- Copy w/attachmentlenclosure 'N - No cop
OFFICE TECH CONTS C/EMEB:DE /PECB:DRPM D/DRPM
NAME CHammer C00b RWessm AChaffee TMartin
RBenedict
/'-/6' X
DATE t/1/2-796 U;10 A l96 /'/96 /9 /96
//96 j= A"A*
^ty
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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)
- 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: 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)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-12, Control Rod Insertion Problems (15 February 1996)
- Information Notice 1996-13, Potential Containment Leak Paths Through Hydrogen Analysis (26 February 1996)
- Information Notice 1996-14, Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1 (1 March 1996)
- Information Notice 1996-15, Unexpected Plant Performance During Performance of New Surveillance (8 March 1996)
- Information Notice 1996-16, BWR Operation with Indicated Flow Less than Natural Circulation (14 March 1996)
- 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: Brachytherapy)
- Information Notice 1996-19, Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal (2 April 1996)
- 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)
- 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: Nondestructive 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)
- 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, Troxler Moisture Density Gauge)
- Information Notice 1996-41, Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation (26 July 1996)
- 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)
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