Foreign Experience Regarding Boron DilutionML031190351 |
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, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
09/06/1991 |
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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-91-054, NUDOCS 9108300203 |
Download: ML031190351 (5) |
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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, 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 [[: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 [[:Atlantic Nuclear Power Plant]] </code>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 September 6, 1991 NRC INFORMATION NOTICE 91-54: FOREIGN EXPERIENCE REGARDING BORON DILUTION
Addressees
All holders of operating licenses or construction permits for pressurized
water reactors (PWRs).
Purpose
The U.S. Nuclear Regulatory-Commission (NRC) is issuing this information
notice'to alert addressees.to a potential sequence of events that may result
in a rapid injection of unborated reactor coolant water into the reactorcore.
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 require- ments; therefore, no specific action or written response is required.
Description of Circumstances
The NRC has learned of analyses, performed by a foreign program, of certain
events and event sequences which indicate that there is a potential for a
rapid injection into a PWR reactor core of unborated reactor coolant whose
effects would be more severe than similar events considered in the safety
analyses of most U.S. plants.
The adverse events involve the accumulation of a significant volume of
unborated water in a part of the primary coolant system during plant shutdown.
Various actions performed during plant shutdown could result in such an
accumulation. Once the unborated water is accumulated, the startup of an idle
reactor coolant pump could send the unborated water into the reactor core causing
a significant and unplanned reactivity insertion.
The following sequence of events is evaluated in the foreign study.
The sequence is initiated by the loss of one of two offsite electrical power
sources. This loss of power, occurs while the reactor coolant water is being
diluted for reactor startup. At this time, decay heat is insufficient to
cause natural circulation of the reactor coolant. It is assumed that the
operating reactor coolant pump(s) are powered from the failed offsite power
source and cease running. However, the charging pumps, powered from the
alternate power source, continue to operate and a significant volume of
unborated water is accumulated in the reactor coolant system. If,at this
9108300203 E4q LD (Oia'2
002098 mI: i s stI
IN 91-54 September 6, 1991 point, an idle reactor coolant pump is started, the accumulated volume of
weakly borated or unborated water would be injected into the reactor core.
Discussion of Safety Significance
The safety analyses for most U.S. nuclear plants do not address this explicit
sequence of events. However, the staff is aware of one representative analysis
of a similar sequence for a U.S. PWR. In that analysis, the results indicate
that such an accident could cause some core damage but that breach of the
reactor coolant system would be unlikely. The NRC is continuing to study other
possible sequences that could cause a similar unplanned injection of unborated
water. The above postulated sequence of events would occur as a result of
actions performed during plant restart from a shutdown condition and as such is
being considered as part of the NRC's review of shutdown risk.
This accident sequence 'involves several assumptions regarding plant conditions
and equipment configuration and, therefore, may not apply to a particular U.S.
plant. Training and procedures that emphasize the need to ensure uniform
boron concentration in the reactor coolant system at all times and the imple- mentation of-appropriate caution in starting an idle reactor coolant loop can
reduce the probability of occurrence of such an event.
This information notice requires no specific action or written response. If
youhave any quesions abottt the Information-4n this notiepklease_.contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation project manager.
CRoOe &W
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contacts: N. Prasad Kadambi, NRR
(301) 492-0841 M. Caruso, NRR
(301) 492-3235 Attachment: List of Recently Issued NRC Information Notices
r , .
Attachment
IN 91-54 September 6, 1991 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
89-90, Pressurizer Safety Valve 09/05/91 All holders of OLs or CPs
Supp. 2 Lift Setpoint Shift for nuclear power reactors.
91-53 Failure of Remote Shutdown 09/04/91 - All holders of OLs or CPs
System Instrumentation for nuclear power reactors.
Because of Incorrectly
Installed Components
91-52 Nonconservative Errors 08/29/91 All holders of OLs or CPs
In Overtemperature Delta- for Westinghouse (W)-designed
Temperature (OTAT) Set- nuclear power reactors.
point Caused by Improper
Gain Settings
86-14, Overspeed Trips of AFW, 08/26/91 All holders of OLs or CPs
-Supp-. 2 HPC0-6nd;RCIC Turbiiies for nuclear power reactors.
91-51 Inadequate Fuse Control 08/20/91 All holders of OLs or CPs
Programs for nuclear power reactors.
91-50 A Review of Water Hammer 08/20/91 All holders of OLs or CPs
Events After 1985 for nuclear power reactors.
91-49 Enforcement of Safety 08/15/91 All Nuclear Regulatory Com- Requirements for Radiog- mission (NRC) licensees
raphers authorized to use sealed
sources for industrial
radiography.
91-48 False Certificates of Con- 08/09/91 All holders of OLs or CPs
formance Provided by West- for nuclear power reactors.
inghouse Electric Supply
Company for Refurbished Com- mercial-Grade Circuit
Breakers
91-47 Failure of Thermo-Lag 08/06/91 All holders of OLs or CPs
Fire Barrier Material to for nuclear power reactors.
Pass Fire Endurance Test
OL = Operating License
CP = Construction Permit
- t.IN - 91-54 September 6, 1991 point, an idle reactor coolant pump is started, the accumulated volume of
weakly borated or unborated water would be injected into the reactor core, Discussion of Safety Significance
The safety analyses for most U.S. nuclear plants do not address this explicit
sequence of events. However, the staff is aware of one representative analysis
of a similar sequence for a U.S. PWR. In that analysis, the results indicate
that such an accident could cause some core damage but that breach of the
reactor coolant system would be unlikely. The NRC is continuing to study other
possible sequences that could cause a similar unplanned injection of unborated
water. The above postulated sequence of events would occur as a result of
actions performed during plant restart from a shutdown condition and as such is
being considered as part of the NRC's review of shutdown risk.
This accident sequence involves several assumptions regarding plant conditions
and equipment configuration and, therefore, may not apply to a particular U.S.
plant. Training and procedures that emphasize the need to ensure uniform
boron concentration in the reactor coolant system at all times and the imple- mentation of appropriate caution in starting an idle reactor coolant loop can
reduce the probability of occurrence of such an event.
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 Signiu tj
CrIes E.k
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contacts: N. Prasad Kadambi, NRR
(301) 492-0841 M. Caruso, NRR
(301) 492-3235 Attachment: List of Recently Issued NRC Information Notices
- See previous concurrence.
SRXB:DST:NRR C:SRXB:DST:NRR D:DST,
- MCaruso *RJones *AThadani
08/21/91 08/21/91 08/24/91 DFC :OGCB:DOEA:NRR:C:OGCB:DOEA:NRR:IP :TechEd :D:DOEA:NRR :
- - -- .
- - -- - - - -- - -- - -4-- .-- - - - ------- -----
NAME :*Pkadambi :*CHBerlinger :HJFaulkner:*JMain :C .
DATE :08/08/91 :08/28/91 :08/21/91* :08/09/91 :Oq/J3/91 :
Document Name: IN 9154
S
~
K) IN 91-XX
\,/August XX, 1991 point, an idle reactor coolant pump is started, the accumulated
weakly borated or unborated water would be injected into the volume of
reactor vessel.
Discussion of Safety Significance:
The safety analyses for most U.S. nuclear plants do not address
sequence of events. However, the staff is aware of one representative this explicit
analysis of a similar sequence for a U.S. PWR. In that analysis, indicate that such an accident could cause-some core damage but the results
the reactor coolant system integrity would be unlikely. The that breach of
NRC is continuing
to study other possible sequences that could cause a similar
injection of unborated water. The above postulated sequence unplanned
result of actions performed during plant restart from a shutdown of events was the
as such is being considered as part of the NRC's review of shutdown condition and
risk.
This accident sequence involves several assumptions regarding
and equipment configuration, and therefore may not apply to plant conditions
a particular U.S.
plant. Training and procedures that emphasize the need to ensure
boron concentration in the reactor coolant system at all times uniform
implementation of appropriate caution in starting an idle reactor the and
can reduce the probability of occurrence of such an event. coolant loop
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please call one
of the technical contacts 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. Prasad Kadambi, NRR
(301) 492-0841 M. Caruso, NRR
(301) 492-3235 Attachment: List of Recently Issued NRC Information Notices
- See previous concurrence.
SRXB:DST:NRR C:SRXB:DST:NRR D:DST
- MCaruso *RJones *AThadani
08/21/91 08/21/91 08/24/91 OFC :OGCB:D A:NRR:C:OGCB
--- A-RR:IP :TechEd :D:DOEA:NRR
_---- _ ----
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NAME :*Pkada I CHBerlnger :HJFaulkner:*JMain :CERossi
DATE :08108/1 :08 91 :08/21/91* :08/09/91 :08/ /91 Document Name: BORON DILUTION/8/27/91
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list | - Information Notice 1991-01, Supplier of Misrepresented Resistors (4 January 1991, Topic: Fitness for Duty)
- Information Notice 1991-02, Brachytherapy Source Management (7 January 1991, Topic: Fitness for Duty, Brachytherapy)
- Information Notice 1991-03, Management of Wastes Contaminated with Radioactive Materials (Red Bag Waste & Ordinary Trash) (7 January 1991, Topic: Fitness for Duty, Brachytherapy)
- Information Notice 1991-04, Reactor Scram Following Control Rod Withdrawal Associated with Low Power Turbine Testing (28 January 1991, Topic: Fitness for Duty)
- Information Notice 1991-05, Intergranular Stress Corrosion Cracking in Pressurized Water Reactor Safety Injection Accumulator Nozzles (30 January 1991, Topic: Fitness for Duty, Hydrostatic, Liquid penetrant)
- Information Notice 1991-06, Lock-up of Emergency Diesel Generator and Load Sequencer Control Circuits Preventing Restart of Tripped Emergency Diesel Generator (31 January 1991, Topic: Fitness for Duty, Brachytherapy)
- Information Notice 1991-07, Maintenance Deficiency Associated with General Electric Horizontal Custom 8000 Induction Motors (4 February 1991, Topic: Fitness for Duty, Brachytherapy)
- Information Notice 1991-08, Medical Examinations for Licensed Operators (5 February 1991, Topic: Brachytherapy)
- Information Notice 1991-09, Counterfeiting of Crane Valves (25 September 2007)
- Information Notice 1991-10, Summary of Semiannual Program Performance Reports on Fithess-For-Duty (FFD) in the Nuclear Industry (12 February 1991)
- Information Notice 1991-12, Potential Loss of Net Positive Suction Head (NPSH) of Standby Liquid Control System Pumps (15 February 1991)
- Information Notice 1991-13, Inadequate Testing of Emergency Diesel Generators (Edgs) (4 March 1991)
- Information Notice 1991-13, Inadequate Testing of Emergency Diesel Generators (EDGs) (4 March 1991)
- Information Notice 1991-14, Recent Safety-Related Incidents at Large Irradiators (5 March 1991, Topic: Fitness for Duty, Coatings, Incorporated by reference, Brachytherapy, Uranium Hexafluoride)
- Information Notice 1991-15, Incorrect Configuration of Breaker Operating Springs in General Electric AK-Series Metal-Clad Circuit Breakers (6 March 1991)
- Information Notice 1991-16, Unmonitored Release Pathways from Slightly Contaminated Recycle and Recirculation Water Systems at a Fuel Facility (6 March 1991, Topic: Fitness for Duty, Brachytherapy)
- Information Notice 1991-17, Fire Safety of Temporary Installation or Services (11 March 1991)
- Information Notice 1991-18, High-Energy Piping Failures Caused by Wall Thinning (18 December 1991)
- Information Notice 1991-19, Steam Generator Feedwater Distribution Piping Damage (12 March 1991)
- Information Notice 1991-20, Electrical Wire Insulation Degradation Caused Failure in a Safety-Related Motor Control Center (19 March 1991)
- Information Notice 1991-21, Inadequate Quality Assurance Program of Vendor Supplying Safety-Related Equipment (19 March 1991)
- Information Notice 1991-22, Four Plant Outage Events Involving Loss of AC Power or Coolant Spills (19 March 1991)
- Information Notice 1991-23, Accidental Radiation Overexposures to Personnel Due to Industrial Radiography Accessory Equipment Malfunctions (26 March 1991, Topic: Fitness for Duty, Brachytherapy)
- Information Notice 1991-24, Recent Operating Experience Involving Reactor Operation Without a Licensed Reactor Operator or Senior Reactor Operator Present in the Control Room (26 March 1991)
- Information Notice 1991-25, Commercial-Grade Structural Framing Components Supplied As Nuclear Safety-Related Equipment (1 April 1991)
- Information Notice 1991-25, Commercial-Grade Structural Framing Components Supplied as Nuclear Safety-Related Equipment (1 April 1991)
- Information Notice 1991-26, Potential Nonconservative Errors in the Working Format Hansen-Roach Cross-Section Set Provided with Keno and Scale Codes (2 April 1991, Topic: Fitness for Duty, Brachytherapy)
- Information Notice 1991-27, Incorrect Rotation of Positive Displacement Pump (10 April 1991)
- Information Notice 1991-28, Cracking in Feedwater System Piping (15 April 1991)
- Information Notice 1991-29, Deficiencies Identifie During Electrical Distribution System Functional Inspections (15 April 1991)
- Information Notice 1991-30, Inadequate Calibration of Thermoluminescent Dosimeters Utilized to Monitor Extremity Dose at Uranium Processing and Fabrication Facilities (23 April 1991, Topic: Brachytherapy, Uranium Hexafluoride)
- Information Notice 1991-31, Nonconforming Magnaflux Magnetic Particle (14AM) Prepared Bath (9 May 1991)
- Information Notice 1991-32, Possible Flaws in Certain Piping Systems Fabricated by Associated Piping and Engineering (15 May 1991, Topic: Hot Short, Liquid penetrant)
- Information Notice 1991-33, Reactor Safety Information for States During Exercises and Emergencies (31 May 1991)
- Information Notice 1991-34, Potential Problems in Identifying Causes of Emergency Diesel Generator Malfunctions (3 June 1991)
- Information Notice 1991-35, Labeling Requirements for Transporting Multi-Hazard Radioactive Materials (7 June 1991)
- Information Notice 1991-36, Nuclear Plant Staff Working Hours (10 June 1991)
- Information Notice 1991-37, Compressed Gas Cylinder Missile Hazards (10 June 1991)
- Information Notice 1991-38, Thermal Stratification in Feedwater System Piping (13 June 1991, Topic: Unanalyzed Condition)
- Information Notice 1991-39, Compliance with 10 CFR Part 21, Reporting of Defects and Noncompliance. (17 June 1991)
- Information Notice 1991-40, Contamination of Nonradioactive System and Resulting Possibility for Unmonitored, Uncontrolled Release to the Environment (19 June 1991)
- Information Notice 1991-41, Potential Problems with the Use of Freeze Seals (27 June 1991)
- Information Notice 1991-42, Plant Outage Events Involving Poor Coordination Between Operations and Maintenance Personnel During Valve Testing and Manipulations (27 June 1991)
- Information Notice 1991-43, Recent Incidents Involving Rapid Increases in Primary-To-Secondary Leak Rate (5 July 1991, Topic: Grab sample)
- Information Notice 1991-45, Possible Malfunction of Westinghouse Ard, Bfd, & Nbfd Relays, & A200 DC & DPC 250 Magnetic Contactors (5 July 1991)
- Information Notice 1991-46, Degradation of Emergency Diesel Generator Fuel Oil Delivery Systems (18 July 1991)
- Information Notice 1991-47, Failure of Thermo-Lag Fire Barrier Material to Pass Fire Endurance Test (6 August 1991, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1991-48, False Certificates of Conformance Provided by Westinghouse Electric Supply Company for Refurbished Commercial-Grade Circuit Breakers (9 August 1991, Topic: Fire Barrier)
- Information Notice 1991-49, Enforcement of Safety Requirements for Radiographers (15 August 1991, Topic: High Radiation Area, Fire Barrier)
- Information Notice 1991-50, a Review of Water Hammer Events After 1985 (20 August 1991, Topic: Fire Barrier)
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