Degradation of Emergency Diesel Generator Fuel Oil Delivery SystemsML031190492 |
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: |
07/18/1991 |
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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-91-046, NUDOCS 9107110017 |
Download: ML031190492 (6) |
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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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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 [[: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 .
July 18, 1991 NRC INFORMATION NOTICE NO. 91-46: DEGRADATION OF EMERGENCY DIESEL
GENERATOR FUEL OIL DELIVERY SYSTEMS
Addressees
- .
All holders of operating licenses or.construction permits for nclear -power
reactors..
Purpose
This information notice is intended to alert addressees to otential i
inoperability of multiple emergency diesel generators (EDGs resulting from
common cause degradations: (1) degraded fuel oil delivery systems and,
(2) failure to meet Technical Specification (TS) testing requirements intended
to detect potentially degraded quality of the fuel oil stored on site. 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 do not constitute NRC
requirements; therefore, no specific action or written response is required.
Description of Circumstances
Over the past four years, several licensees have-submitted licensee event
reports (LERs) describing degradations in EDG operability or-other
safety-related equipment attributable to problems with the fuel oil system.
Descriptions of selected LERs are presented below to illustrate three classes
of problems.
I. Inappropriate painting of fuel injection assemblies
McGuire Unit 1: On June 25,.1990, while the unit was operating at full
power, the licensee, Duke Power,.declared'two EDGs inoperable on discovery
that paint had been inappropriately sprayed on the exciter commutator
rings and on.the back side of the fuel rack pivot.points...This condition
- .prevented the EDG output from attaining the TS-required 4160 volts in the
allotted time (11 seconds).. (LER,50-369/90-17-01)
Palo Verde Unit 3: On March 28, 1990, while the unit was operating at
full power, the licensee, Arizona Pubiic Service, discovered paint in the
ports for the EDG fuel pump fuel oil metering rods, making the. EDG inoper- able, because the paint would most likely have prevented operation.of the
fuel oil injection system. (LER 50-530/90-03)
9107110017 V tl 4
- lia tit't, 9 It-o0 9 to 910$ 1
IN 91-46 July 18, 1991 Byron Unit 1: On March 28, 1989, while the unit was
80 PeFiFof full power, the licensee, Commonwealth operating at
Edison, discovered
that an EDG failed to start during the monthly surveillance test because
inappropriately applied paint was binding the fuel oil metering rods
thus preventing the EDG from getting enough fuel and
oil to start.
(LER 50-327/89-25)
II. Fouling of fuel oil filters or strainers
Dresden Unit 2: On December 24, 1988, while the unit was shut down, all the reactor fuel removed from the reactor vessel, and with both with
reactor protection system (RPS) buses being powered from one EDG,
frequency decreased below the setpoint of the underfrequency relaysthe EDG
associated with the motor-generator sets. When the relays actuated, RPS buses were deenergized, resulting in a scram signal on both RPS the
channels. The standby gas treatment system was automatically initiated -
and the reactor building ventila-tion system was automatically isolated.
The licensee, Commonwealth Edison, determined the root cause to be-a'"
fouled fuel oil filter. (LER 50-237/88-20)
Turkey Point Unit 3: On September 20, 1988, while the unit w'as operating
at full power, the licensee, Florida Power and Light, declared its
inoperable due to high fuel oil pressure. At the time of the event,B.EDG
Unit 4 was shut down and the A EDG was out of service for maintenance.
The licensee'determined the root cause to be an'excessive interval'between
fuel oil filter replacements that allowed gradual accumulation of
late matter inthe filter. (LER 50-250/88-22) particu- Ginna: On February 20, 1987, while the unit was shut'down- and with
sfalton electrical power being supplied by the EDGs, the licensee, all
Rochester Gas and Electric, discovered low fuel oil levels-in both
day.
tanks because the fuel oil transfer pump suction strainers were partially
plugged. The particulate contamination was analyzed as weld flux
from
plant construction activities and fibrous material from either cleaning
rags or filter media. The licensee had to drain and flush the fuel
transfer pump suction piping several times to prevent plugging of
strainers when the fuel-oil from the storage tanks was recirculated. the
(LER 50-244/87-01)
III. Potential degradation-of fuel oil quality, as measured by licensees'
TS
Susquehanna Unit 1: OnJuly 26, 1990, with both units operating at
power, te Tcensee, Pennsylvania Power and Light, declared an EDG. full
able because a sample of fuel' oil from a storage tank exceeded its inoper- limit for the concentration of insoluble matter (2mg/100 ml, using TS
ASTM-D2274-70 oxygen accelerated stability test), indicating a loss the
stability of the stored'fuel oil. (LER 50-387/90-15) of
Perry Unit 1: On April 5, 1990 (LER 50-440/90-05-01), and on
January , 1989 (LER 50-440/89-01-01), the licensee, Cleveland Electric
Illumination, declared safety-related equipment inoperable
sample of fuel oil from a storage tank exceeded its TS limitbecause
for the
a
IN 91-46 July 18, 1991 concentration of insoluble matter (2 mg/100 ml, using the ASTM-D2274-70
test). In April 1990, the licensee declared its high-pressure core spray
system inoperable'while the unit was operating at full power and in :
January 1989, the licensee declared an EDG inoperable while the unit was.
operating at 70 percent of full power. In the April 1990 event, the
licensee attributed the degradation to a contaminant found in the biocide
additive and to-degradation of'the material coating the storage tank. In
January 1989, the licensee believed the fuel oil aging was accelerated by.
the addition of new fuel oil a few days before the.event. .
WNP Unit 2: On January 3, 1990, while the unit was operating at full '
power, the licensee, Washington Public Power Supply, declared all three of
its EDGs inoperable, because an EDG fuel oil test of samples drawn on
December 27, 1989, indicated that the fuel oil in all three storage tanks
did not meet the oxygen accelerated stability criterion, and entered the
limiting condition of operation (LCO) for TS 3.0.3. At the time'of this
report, the licensee's TS required that EDG fuel oil be tested.in aIccor- dance with the standard ASTM-D2274-70, with particulate contamination not
exceeding 2 mg/100 ml. The licensee reviewed past surveillance results, which were typically half the TS limit, found no discernible trends, and
consulted two fuel oil experts, who indicated that no reason existed forka
step increase in the stability measure.
The licensee believes the root cause of this event to be the fuel oil
analysis method. The licensee submitted an emergency amendment,.which
included the substitution of a filter cleanliness test based on the
standard ASTM-D2276-78, Method A, with particulate contamination not
exceeding 10 mg/l, for the oxygen accelerated stability test based on
ASTM-D2274-70. On March 30, 1990, the NRC temporarily approved-the.
amendment. On June 4, 1990, the NRC permanently approved a yrevision of
the amendment that-included changes in addition to this test substitution,,
The' filter cleanliness test is designed to measure particulate contamina-,'.:
tion existing in the fuel oil whereas the oxygen accelerated stability ..
test is designed to measure the potential of-the fuel oil for forming
gums, varnishes, and tars in the future. The filter cleanliness test
results for the samples of fuel oil drawn on December 27, 1989, were
acceptable. Results of both the-oxygen accelerated stability test and the
filter cleanliness test for samples drawn from both tank bottoms and
transfer pump discharges on-January 2, 1'990, and on January 3, 1990, were
acceptable. (LER 50-397/90-01)
Diablo Canyon Unit 1: On May 5, 1988, while the unit was shut down, the
licensee, Pacific Gas and Electric, observed the power output. of an EDG to
decrease below the licensee's acceptance criterion for a 24-hour load
test. The licensee determined that the primary fuel oil filter had.become.
clogged with a fungus growing in the day tank supplying that EDG. The
licensee also found fungus and spores in the other day tanks and in the
fuel oil storage tanks. The licensee added a.biocide and filtered the, fuel oil in the'day tanks until its acceptance criteria were met for.flash'
point, gravity, viscosity, and particulate contamination (10 mg/l, using
the ASTM-D2276-78 Method A, particulate contamination test).
(LER 50-275/88-145
IN 91-46 July 18, 1991 Discussion:
The lessons to be learned from the LERs that deal with inappropriate painting
incidents are'self-evident. Similarly, the LERs that deal with partially
plugged fuel'oil filters or strainers show that regular and careful maintenance
of these components is important to reliable EDG operation. In particular, these LERs show that the.-period of time between replacement of filters and
strainers should not be excessive and that cleanliness.of maintenance opera- tions performed on the fuel.deli'very system is important. The subject of
filter maintenance was previously discussed in NRC Information Notice
No. 87-04, "Diesel Generator Fails Test Because of Degraded Fuel." Some of the
LERs on TS testing problems are concerned with actual degradations of fuel
oil
quality but primarily address' the particular test used in the TS.
The main concern with- degraded EDG fuel oil (particulateicontamination) lies
its potential for clogging filters, strainers, and fuel injection equipment in
through which the fuel oil. must flow and thus..causing 'engine fai'lure. All-fuel
oil tends to degrade in.two general ways during extended storage. The first, way is oxidation and polymerization of the fuel oil to yieldsoluble and.'
insoluble gums. The second way is clustered microbiological growth of.bacte- ria, fungi, or yeasts.ot the interface of the fuel oi.l and water present
bottom of the storage tank. Through chemical processes, the bacteria'produce at the
solids and additional water. The bacterial solids may accumulate in the
of the fuel storage tank and not pose a problem for EDG operability until bottom
fuel transfer pump draws them into its suction pipe. All these solid mate-the
rials, the gums, the microbiological growth, and the bacterial sludge, as
as foreign debris, are collectively called particulate contamination. well
Focusing on the question of degraded fuel oil quality, note that several.
standards are used in individual plant.TS requiriements for testing EDG fuel
oil. Most plants use the American Society for Testing and Materials (ASTM)
"Standard Specification for Diesel Fuel Oils," ASTM-D975-XX, where XX-rrepre- sentsthe year of the modification used, for testing the quality qf fuel oil, both freshly delivered and stored. It includes tests for a number of fuel
properties, including flash point, cloud'point, distillation temperature, water
and sediment content, carbon, residue, ash content, sulfur content, viscos.ity, corrosive potential, and Cetane number (ignition quality). Some plants' TS,
only require the water, sediment, and viscosity tests.. Some plants' TS contain
a requirement for:-the oxygen accelerated'stability test described in "Standard
Test Method for Oxidation Stability of Distillate Fuel Oil (Accelerated Method),"
ASTM-D2274-XX, and some plants' TS contain a requirement for the particulate
contamination test described in "Standard Test Methods for Particulate Contam- inant ian Aviation Turbine Fuels," ASTM-D2276-XX. The American Nuclear Society
(ANS) in its standard approved bythe American National Standards Institute
(ANSIS, "Fuel Oil Systems for Emergency Diesel Generators," ANS.I/ANS-59.51-1989, recommends in AppendixtC the ASTM-D2276-XX particulate contamination test.
The ASTM-D975 standard is intended as a statement of permissible, limits of
significant fuel properties used for specifying the' wide variety of commercially
available diesel fuel' oils. As such, it most readily applies to determination
of the quality of new fuel oil, but does not readily apply to the question
of
IN 91-46 July 18, 1991 particulate contamination in stored fuel oil. The oxygen accelerated stability
test of the ASTM-D2274 standard .predicts the potential for future degradation
of fuel oil but does not show the existing st-Ne of degradation. On the other
hand, the particulate contamination test of the ASTM-D2276 standard readily
applies to the question of particulate contamination in stored fuel oil.
Revision 4A of the Westinghouse Standard TS (STS) contains comprehensive oil, in
requirements on testing and monitoring the condition of stored EDG fuel
which the salient features are (1)use of the ASTM-D2276 particulate power contami- nation test and (2) testing for and removal of water. Some nuclear
plants, such as McGuire Units 1 and.2, Wolf Creek, Limerick Units 1 and individ- 2, and
WNP Unit 2, have voluntarily adopted this revision of the STS in their
ual plant TS. In the LER for WNP 2 (above), the licensee determined that
incorporation of this total program in its plant TS was an effective corrective oil. The
action for its problems in determining the quality of its stored fuel guidance on
Electric Power Research Institute (EPRI) has provided additional
this point in "Storage and Handling of Fuel Oil for Standby Diesel Generator
Systems," EPRI NP-63140, August 1988.
This information notice requires no specific action or writtenplease response. If
you have any questions about the information in this notice, call one of
the technical contacts listed below or the appropriate NRR project manager.
harles~E.Ross Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Vern Hodge, NRR Frank Witt, NRR
(301) 492-1861 (301) 492-0767 Ed Tomlinson, NRR Pete Prescott, NRR
(301) 492-3150 (301) 492-1011 Attachment: List of Recently Issued NRC Information Notices
Attachment 1 IN 91-46 -
July 18, 1991 Page 1-of 1 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
91-45 Possible Malfunction of 07/05/91 All holders of OLs or CPs
Westinghouse ARD, BFD, and for nuclear power reactors.
NBFD Relays, and A200 DC
and DPC 250 Magnetic Con- tactors
91-44 Improper Control of 07/08/91 All nuclear fuel facilities.
Chemicals in Nuclear Fuel
Fabrication
91-43 Recent Incidents Involving 07/05/91 All holders of OLs or CPs
Rapid Increases in Primary- for pressurized-water
to-Secondary Leak Rate reactors (PWRs).
91-42 Plant Outage Events 06/27/91 All holders of OLs or CPs
Involving Poor Coordina- for nuclear power reactors.
tion Between Operations
and Maintenance Personnel
During Valve Testing and
Manipulations
91-41 Potential Problems with 06/27/91 All holders of OLs or CPs
The Use of Freeze Seals for nuclear power reactors.
88-63, High Radiation Hazards 06/25/91 All holders of OLs or CPs
Supp. 2 from Irradiated Incore for nuclear power reactors, Detectors and Cables research reactors, and
test reactors.
91-40 Contamination of Non- 06/19/91 All holders of OLs or CPs
radioactive System and for nuclear power reactors.
Resulting Possibility for
Unmonitored, Uncontrolled
Release to the Environment
91-39 Compliance with 10 CFR 06/17/91 All Nuclear Regulatory
Part 21, "Reporting of Commission (NRC) material
Defects and Noncompliance" licensees.
91-38 Thermal Stratification in 06/13/91 All holders of OLs or CPs
Feedwater System Piping for nuclear power reactors.
OL = Operating License
CP = Construction Permit
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list | - Information Notice 1991-01, Supplier of Misrepresented Resistors (4 January 1991, Topic: Fitness for Duty, Overspeed)
- Information Notice 1991-02, Brachytherapy Source Management (7 January 1991, Topic: Fitness for Duty, Brachytherapy, Overspeed)
- 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, Intergranular Stress Corrosion Cracking, 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, Overspeed)
- 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, Overexposure)
- 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, Topic: Feedwater Heater)
- 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, Overexposure)
- 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, Depleted uranium)
- 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, Intergranular Stress Corrosion Cracking, 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, Topic: Commercial Grade)
- 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, Overexposure)
- Information Notice 1991-50, a Review of Water Hammer Events After 1985 (20 August 1991, Topic: Fire Barrier, Water hammer)
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