Loss of Residual Heat Removal Caused by Accumulator Nitrogen InjectionML031180745 |
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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
09/13/1989 |
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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-89-067, NUDOCS 8909070043 |
Download: ML031180745 (7) |
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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, 05000000, Zimmer, 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 [[:05000000]] OR [[:Zimmer]] 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 [[:05000000]] OR [[:Zimmer]] 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 September 13, 1989 NRC INFORMATION NOTICE NO. 89-67: LOSS OF RESIDUAL HEAT REMOVAL CAUSED
.:BY ACCUMULATOR NITROGEN INJECTION
Addressees
- '.: -
All holders of operating licenses or construction permits forLpre~surized water
reactors (PWRs).
Purpose
- . '. . . ;
This information notice is intended to alert addressees to potential problems
resulting from the loss of residual heat removal (RHR) cauied'by the injection
of nitrogen from an accumulator.into the reactor coolantisystemi (RCS). It is
expected that recipients will review the information f6r applicability to'their
facilities and consider actions, as appropriate,'to'avoid'tsimilai problems.
However, suggestions contained in thislinformation notice do' not constitute
NRC requirements; therefore:,-no specific'action or written response is required.
Description of Circumstances
Salem Unit 1 lost both RHR pumps for about 50 minutes'6n:May 20, 1989, as a
result of an injection of nitrogen from an accumulator into the RCS'and, sub- sequently, into the:RHR system. This injection'occurred while the licensee
was conducting full-flow testing of the accumulator check yalves' The reactor
was in Mode 5 (cold shutdown) after-a recent refueling with the reactor.head
installed. .The RCS was filled to a cold calibrated pressurizer level of
10 percent withiair contained;in.the reactor vessel 'head and in'the steam
generator U-tubes. All accumulators were filled to normal operating level
and were pressurized to approximately 600 psig.
At.9:25 a.m., while performing a post-maintenance full-flow test of the check
valves for accumulator 13, the accumulator isolttion valve remained open'for
about 70 seconds as a result of an operator error. During this time, approxi- mately 1800 cubic feet of nitrogen at about 62 psig entered the RCS. As the
nitrogen expanded into the RCS, the pressurizer level went off-scale high, and
the reactor pressure rose from 14 psig to about 51 psig. The operator, not
realizing that nitrogen had been injected-into the RCS, initiated pressurizer
level ,restoration by draining the RCS to the refueling water storage tank
(RWST). At 9:35 a.m., the operator observed zero RHR flow and a reduction
of the pump motor current from 44 amps to about 21 amps.
K 890907004) A
r
IN 89-67 September 13, 1989 The operator, assuming that the pump was'mechanfically damaged, secured the pump
and started the second RHR pump, When this pump exhibited the same character- istics as the other pump, the operator real'zed that the pumps were gas bound
and started venting the RHR system. Venting was slow because of the size of
the vent lines and .an RHR. system qonfiguration that allowed air entrapment.
Operators also had dIfficulty-in locating one vent and drain valve; when it
was located,-an-installed cap had to be removed. Slow venting continued until
10:18 a.m. when the operators initiated filling of the RHR system, using gravity
feed from the RWST. At this time, the core exit temperature had increased to.
1221F from a pre-event value of 920F. At 10:23 a.m., the RHR system was filled, and RHR pump 11 was successfully started. At 10:37 a.m.,.RHR pump 12 was placed
in'service, and RHR pump 11 was secured to'return the system to normal operation.
Because of an inadequate abnormal operating procedure and emergency classifi- cation guide, a 10 CFR 50.72 report for this loss of RHR pumps was not made.
until May 22, 1989.
Discussion: < i
An assessment of this loss-of-RHR-pump event at S'alem'Unit I identified the
folloWing'concernis' ' .' Uni 1 i the
1. 'IThe operators appeaied to believe that nitrogen i~njection lntQ the RCS
'-
was not possible'dui-ng the full-flow test of'the accumulator check valves.
This mindset caused the operators to drain the RCS when the pressurizer
level kept increasing due to the expansion of tnj'ected.nitrogen.'
2. The abnormal operat'in" procedures and the memrge'ncy classification guide
did not adequately address the potentiay' for loss of RHR cooling. The
symptom-oriented procedures did not address the reactor parameters during
a loss of shutdown cooling while in Modes 5 and 6..'Consequently, the
event was nbot r'eporteddfmmediitely under 10 CFR 50.72.
3. The operators were not adequqte ly trained, to differenitiate gas binding of
- theRHR pumps from methanical damage'. Thi s caused the operators to.start
RHR pump 11 when they erroneously' concluded that RHR pump 1Z was mechani- cally damaged. .
4. Elevation differences-f'the RHR suction pipe, the difficulty in locating
one vent and drain' vialve;aid the $ize'of the vent lines caused'the venting
I:opdration to be extrenely-slow. Iaddition, complete system yenting was
not possible because "as was trapped in the high pointsfof the RHR system.
5. .:The appropriateness oif performing-a full-flow test of the accumulator
check valves with fuel in the reactor vessel had not been fully assessed.
An event similar to the one described in this information notice would.
not occur to this extent if this test'had been conducted while the core
was off-loaded. Furthermore, if this test had been performed with either
reduced accumulator nitrogen pressure or with the reactor vessel head
removed, the effects of nitrogen injection into the RCS would have been
minimized.
IN 89-67 September 13, 1989 Ituis important to note that if the accumulator check valve full-flow tests had
been conductedlwhen'they.are more commonly performed, during the shutdown prior
to refueling, and an event similar to the one described in this information
notice had occurred, the consequences could have been much'more significant.
It is also important to'note that operator training provided in response to
NRC Generic Letter 88-17, "Loss of Decay Heat Removal," did assist the operators
in restoring the RHR system once gas binding of the system was recognized.
This information.notice requires no specific action or written response.'. If
you'have any questions about the information in this notice, please contact one
of.the technical contacts listed below or the appropriate NRR project manager.
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Daniel Prochnow, NRR
(301.) 492-1166 Warren Lyon, NRR' - -
.. (301) 492-0891 .
Attachment: List of Recently Issued NRC Information'Notices
..
- .'_... .. _. .
ih aunt
Septesber 13, 1989 Page 1 of I
LIST Of RECENTLY ISSUED
XRC INFORMATION NOTICES
Itotice No SubJect u.Lw or"
issuance Issued to
89-66 Qualification Life of 9/11/89 All holders of OLs
Solenoid Valves or CPs for nuclear
power reactors.
88-41* Licensee Report of 9/11/83 All holders of OLs
Supp. 4 Defective Refurbished or CPs for nuclear
Circuit Breakers power reactors.
89-65 Potential for Stress 9/8/89 All holders of OLE
Corrosion Cracking in or CPs for PURs.
Steen Generator Tube
Plugs Supplied by
Babcock and Wilcox
89-64 Electrical Bus Bar Failures 9/7/89 All holders of OLs
or CPs for nuclear
power reactors.
89-63 Possible Subaurgence of 9/1/89 All holders of OLs
Electrical Circuits Located or CPs for nuclear
Above the Flood Level Because power reactors.
of Water Intrusion and Lack
of Drainage
89-62 Malfunction of Borg-Warner 8/31/89 All holders of OLE
Pressure Seal Bonnet Check or CPs for nuclear
Valves Caused By Vertical. pcwer reactors.
Misalignment of Disk
89-61 Failure of Borg-Warner Gate 8/30/89 All holders of OLs
valves to Close Against or CPs for nuclear
Differential Pressure power reactors.
s8-48, Licensee Report of Defective 8/22/89 All holders of OLE
Supp. 2 Refurbished Valves or CPs for nuclear
power reactor.
89-60 Maintenance of Teletherapy 8/18/89 All NRC Medical
__ _ - Unit _t
T ii1verag-ticense eas
OL
CP
UNITED STATES FRT CLASS MAI
NUCLEAR REGULATORY COMMISSION POSTAGE
WASHINGTON, D.C. 20555 USNRAC
PERMIT No. 0-w
OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE. $300
IN 89-67 September 13, 1989 It is important to note that if the accumulator check valve full-flow tests had
been conducted when they are more commonly performed, during the shutdown prior
to refueling, and an event similar to the one described in this information
notice had occurred, the consequences could have been much more significant.
It is also important to note that operator training provided in response to
NRC Generic Letter 88-17, "Loss of Decay Heat Removal," did assist the operators
in restoring the RHR system once gas binding of the system was recognized.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact one
of the technical contacts listed below or the appropriate NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Daniel Prochnow, NRR
(301) 492-1166 Warren Lyon, NRR
(301) 492-0891 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
- C/OGCB:DOEA:NRII *RPB:ARM
CHBerlinger TechEd
9/f/89 9/6/89 9/01/89
- OGCB:DOEA:NRR*SRXB:DEST:NRR *C/SRXB:DEST:NRR *SAD/DEST:NRR *D/DEST:NRR
DProchnow WLyon MHodges AThadani JRichardson
8/16/89 8/16/89 8/18/89 8/20/89 8/20/89
.: I. 'a
IN 89-xx
September xx, 1989 It is important to note that if the accumulator check valve full-flow tests had
been conducted when they are more commonly performed, during the shutdown prior
to fuel refueling, and an event similar to the one described in this informa- tion notice had occurred, the consequences could have been much more signifi- cant. It is also important to note that operator training provided in response
to NRC Generic Letter 88-17, "Loss of Decay Heat Removal," did assist the
operators in restoring the RHR system once gas binding of the system was
recognized.
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 contacts listed below or the appropriate NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Daniel Prochnow, NRR
(301) 492-1166 Warren Lyon, NRR
(301) 492-0891 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
D/DOEA:NRR C/OGC *RPB:ARM
CERosSi CHBerlin etI TechEd
9/ /89 9/ /89 9/01/89
- OGCB:DOEA:NRR*SRXB:DEST:NRR *C/SRXB:DEST:NRR *SAt/DEST:NRR *D/DEST:NRR
DProchnow WLyon MHodges AThadani JRichardson
8/16/89 8/16/89 8/18/89 8/20/89 8/20/89
IN 89-xx
August xx, 1989 It is also important to note that this event indicated that operator training
provided in response to NRC Generic Letter 88-17 (Loss of Decay Heat Removal)
did assist the operators in restoring the RHR system once gas binding of the
system was recognized.
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 NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Daniel Prochnow, NRR
(301) 492-1166 Warren Lyon, NRR
(301) 492-0891 Attachment: List of Recently Issued NRC Information Notices
OGCB:DOEA:NRR RXB:DEST:NRR C:S DEST: NRR SAD:DEST:NRR f DEST:NRR
DProchnow W8/o/8 MHod es AThadani 'Richardson
8/i1 /89 8/Y6/89 8/l1F/89 - 8/ V4/89 8/2A /89 VSRPM:ARM C:OGCB:DOEA:NRR D:DOEA:NRR
Tech Ed CHBerlinger CERossi
X1 1/89 8/ /89 8/ /89
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list | - Information Notice 1989-01, Valve Body Erosion (4 January 1989)
- Information Notice 1989-02, Criminal Prosecution of Licensee'S Former President for Intentional Safety Violations (9 January 1989)
- Information Notice 1989-03, Potential Electrical Equipment Problems (11 January 1989, Topic: Overexposure)
- Information Notice 1989-04, Potential Problems from the Use of Space Heaters (17 January 1989)
- Information Notice 1989-05, Use of Deadly Force by Guards Protecting Nuclear Power Reactors Against Radiological Sabotage (19 January 1989)
- Information Notice 1989-06, Bent Anchor Bolts in Boiling Water Reactor Torus Supports (24 January 1989)
- Information Notice 1989-07, Failures of Small-Diameter Tubing in Control Air, Fuel Oil & Lube Oil Systems Render Emergency Diesel Generators Inoperable (25 January 1989, Topic: Overspeed)
- Information Notice 1989-08, Pump Damage Caused by Low-Flow Operation (26 January 1989, Topic: Integrated leak rate test)
- Information Notice 1989-09, Credit for Control Rods Without Scram Capability in the Calculation of Shutdown Margin (26 January 1989, Topic: Shutdown Margin)
- Information Notice 1989-10, Undetected Installation Errors in Main Steam Line Pipe Tunnel Differential Temperature-Sensing Elements at Boiling Water Reactors (27 January 1989)
- Information Notice 1989-11, Failure of DC Motor-Operated Valves to Develop Rated Torque Because of Improper Cable Sizing (2 February 1989, Topic: Shutdown Margin)
- Information Notice 1989-12, Dose Calibrator Quality Control (9 February 1989)
- Information Notice 1989-13, Alternative Waste Management Procedures in Case of Denial of Access to Low-Level Waste Disposal Sites (8 February 1989, Topic: Shutdown Margin, Authorized possession limits)
- Information Notice 1989-15, Second Reactor Coolant Pump Shaft Failure at Crystal River (16 February 1989, Topic: Shutdown Margin)
- Information Notice 1989-16, Excessive Voltage Drop in DC Systems (16 February 1989, Topic: Shutdown Margin, Battery sizing)
- Information Notice 1989-17, Contamination and Degradation of Safety-Related Battery Cells (22 February 1989)
- Information Notice 1989-18, Criminal Prosecution of Wrongdoing Committed by Suppliers of Nuclear Products or Services (24 August 1990, Topic: Stress corrosion cracking)
- Information Notice 1989-20, Weld Failures in a Pump of Byron-Jackson Design (24 February 1989, Topic: Health Physics Network)
- Information Notice 1989-21, Changes in Performance Characteristics of Molded-Case Circuit Breakers (27 February 1989, Topic: Health Physics Network)
- Information Notice 1989-23, Environmental Qualification of Litton-Veam Cir Series Electrical Connectors (3 March 1989, Topic: Health Physics Network)
- Information Notice 1989-24, Nuclear Criticality Safety (6 March 1989, Topic: Health Physics Network)
- Information Notice 1989-25, Unauthorized Transfer of Ownership or Control of Licensed Activities (7 March 1989, Topic: Health Physics Network)
- Information Notice 1989-26, Instrument Air Supply to Safety-Related Equipment (7 March 1989, Topic: Health Physics Network)
- Information Notice 1989-27, Limitations on the Use of Waste Forms and High Integrity Containers for the Disposal of Low-Level Radioactive Waste (8 March 1989, Topic: Process Control Program)
- Information Notice 1989-28, Weight and Center of Gravity Discrepancies for Copes-Vulcan Air-Operated Valves (14 March 1989)
- Information Notice 1989-29, Potential Failure of Asea Brown Boveri Circuit Breakers During Seismic Event (15 March 1989, Topic: Commercial Grade)
- Information Notice 1989-30, High Temperature Environments at Nuclear Power Plants (1 November 1990, Topic: Stress corrosion cracking)
- Information Notice 1989-31, Swelling and Cracking of Hafnium Control Rods (22 March 1989)
- Information Notice 1989-32, Surveillance Testing of Low-Temperature Overpressure-Protection Systems (23 March 1989, Topic: Stroke time)
- Information Notice 1989-33, Potential Failure of Westinghouse Steam Generator Tube Mechanical Plugs (23 March 1989)
- Information Notice 1989-34, Disposal of Americium Well-Logging Sources (30 March 1989)
- Information Notice 1989-35, Loss & Theft of Unsecured Licensed Material, Attachment 1 to NRC Information Notice 1990-014: Accidental Disposal of Radioactive Materials. (Also includes Attachments 2 & 3) (30 March 1989)
- Information Notice 1989-35, Loss & Theft of Unsecured Licensed Material, Attachment 1 to NRC Information Notice 1990-014: Accidental Disposal of Radioactive Materials. (Also Includes Attachments 2 & 3) (30 March 1989, Topic: Moisture-Density Gauge, Uranium Hexafluoride)
- Information Notice 1989-36, Excessive Temperatures in Emergency Core Cooling System Piping Located Outside Containment (4 April 1989)
- Information Notice 1989-37, Proposed Amendments to 40 CFR Part 61, Air Emission Standards for Radionuclides (4 April 1989)
- Information Notice 1989-38, Atmospheric Dump Valve Failures at Palo Verde Units 1, 2, and 3 (5 April 1989, Topic: Emergency Lighting)
- Information Notice 1989-39, List of Parties Excluded from Federal Procurement or Non-Procurement Programs (5 April 1989)
- Information Notice 1989-40, Unsatisfactory Operator Test Results and Their Effect on the Requalification Program (14 April 1989)
- Information Notice 1989-41, Operator Response to Pressurization of Low-Pressure Interfacing Systems (20 April 1989)
- Information Notice 1989-42, Failure of Rosemount Models 1153 and 1154 Transmitters (21 April 1989)
- Information Notice 1989-43, Permanent Deformation of Torque Switch Helical Springs in Limitorque SMA-Type Motor Operators (1 May 1989)
- Information Notice 1989-44, Hydrogen Storage on the Roof of the Control Room (27 April 1989, Topic: Coatings)
- Information Notice 1989-45, Metalclad, Low-Voltage Power Circuit Breakers Refurbished with Substandard Parts (8 May 1989, Topic: Commercial Grade Dedication, Coatings, Commercial Grade)
- Information Notice 1989-46, Confidentiality of Exercise Scenarios (11 May 1989, Topic: Coatings)
- Information Notice 1989-47, Potential Problems with Worn or Distorted Hose Clamps on Self-Contained Breathing Apparatus (18 May 1989, Topic: Coatings, Fatality)
- Information Notice 1989-48, Design Deficiency in the Turbine-Driven Auxiliary Feedwater Pump Cooling Water Systems (22 May 1989, Topic: Coatings, Temporary Modification)
- Information Notice 1989-49, Failure to Close Service Water Cross-Connect Isolation Valves (22 May 1989, Topic: Coatings)
- Information Notice 1989-50, Inadequate Emergency Diesel Generator Fuel Supply (30 May 1989)
- Information Notice 1989-51, Potential Loss of Required Shutdown Margin During Refueling Operations (31 May 1989, Topic: Shutdown Margin, Coatings)
- Information Notice 1989-52, Potential Fire Damper Operational Problems (8 June 1989, Topic: Safe Shutdown, Shutdown Margin, Fire Barrier, Fire Protection Program)
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