Degradation of Boraflex Neutron Absorber CouponsML031070107 |
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: |
09/10/1993 |
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From: |
Grimes B K Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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-nr IN-93-070, NUDOCS 9309070206 |
Download: ML031070107 (9) |
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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>. |
I UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON
D.C. 20555 September
10, 1993 NRC INFORMATION
NOTICE 93-70: DEGRADATION
OF BORAFLEX NEUTRON ABSORBER COUPONS
Addressees
All holders of operating
licenses or construction
permits for nuclear power reactors.PurDose The U.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice to alert recipients
to a potentially
significant
problem pertaining
to degradation
of Boraflex neutron absorber coupons. 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.Background
Palisades
has high-density
fuel storage racks installed
in the spent fuelpool that use Boraflex, a proprietary
neutron absorbing
material that was manufactured
by Brand Industrial
Services, Incorporated (BISCO). The storage racks are supplied by Westinghouse.
The Boraflex is attached to the walls of each canister and is held in place by a stainless
steel wrapper, which is spot welded to the walls.The licensee has a surveillance
program using Boraflex coupons to indicate the status of the Boraflex contained
in the high density storage racks in the spent fuel pool. Recently observed degradation
of several of these coupons, which may be due to exposure to high level gamma radiation
in conjunction
with interaction
with pool water, raised questions
about the integrity
of the Boraflex contained
in the storage racks. Significant
loss of Boraflex in the high-density
fuel racks could result in loss of the subcriticality
margin in the spent fuel pool. 'Through a commitment
to the NRC, Palisades
was required to test and inspect the Boraflex coupons after 5 years of use. The tests include opening the coupons for visual observation, neutron attenuation
determination, and a Boraflex hardness test.DescriDtion
of Circumstances
During a period from August 17 through 19, 1993, 5 of the existing 10 Boraflex coupons were removed from the spent fuel pool, 4 being full-length
coupons 9309070206 Phi tE funt 3- O7G O1~
IN 93-70 September
10, 1993 and 1 a short-set
coupon (see Figure 1). During removal of the full-length
coupons a powdery substance
and a grey debris cloud were observed emanating from the coupons. Further investigation
of the full-length
coupons revealed that one coupon had lost an estimated
90 percent of its Boraflex, two others 50 percent, and one 38 percent. Investigation
of the short-set
coupon showed that it had retained 100 percent of its Boraflex.
The licensee has determined
that the Boraflex in the 4 full-length
coupons and the short-set
coupon came from different
lots of material.A principal
difference
between the short-set
and the full-length
coupons is their geometrical
design. The short-set
coupon consists of eight compartments
encapsulating
the Boraflex with pool water accessing
only the edges of the coupons. However, in the full-length
coupon Boraflex is sandwiched
axially over the entire length of coupon and bolted between two 0.51-mm [0.020-inch]
stainless
steel metal strips. The licensee postulated
that a much larger area of the full-length
coupon was exposed to the pool water environment
and flow.In addition, the full-length
coupon has a 12.7-mm [0.5-inch]
hole through the metal strip on the top portion of the coupon, which contributes
to the pool water flow around the Boraflex.
The licensee has no immediate
plans for removal or testing of the remaining
five coupons in the spent fuel pool, but does intend to conduct neutron "blackness" testing in the spring of 1994.The licensee also had initiated
measurements
of the silica content of the spent fuel pool water. No increase in silica above normal 1-4 ppm levels have been observed except in instances
when the pool boron concentration
was increased.
Because silica filler material is a constituent
of Boraflex, the presence of silica in the water may be an indication
of degradation
of the Boraflex in the fuel pool.Discussion
Potential
degradation
mechanisms
for Boraflex include (1) gamma flux, which changes the material characteristics
of the base polymer, and (2) chemical environment, namely the accessibility
of water to the Boraflex.
The licensee has not drawn firm conclusions
as to (1) the root cause of the observed degradation
of Boraflex in the coupons, or (2) the correlation
of the behavior of Boraflex in the coupons to that in the storage racks.Degradation
of the Boraflex in fuel storage racks could reduce the subcriticality
margin in the spent fuel pool. The design basis assumes a 5 percent subcriticality
margin on the basis of lowest pool temperature, no boron concentration
in the pool water, and minimum spacing between fuel assemblies.
In its preliminary
analysis, the licensee assumed no boron in the pool water and a complete loss of Boraflex from the fuel storage racks. This reduced the subcriticality
margin from greater than 5 percent to about 2 percent. However, the licensee used the burnup for the currently
stored fuel in the criticality
calculation.
This is higher than the design burnup value, implying less reactive fuel in the fuel pool than assumed in the design calcul ation.The licensee took several compensatory
measures, including
(1) making the operating
staff aware not to dilute the spent fuel pool, (2) increasing
the
IN 93-70 September
10, 1993 spent fuel pool chemistry
sampling frequency
to daily, and (3) keeping the boron concentration
in the spent fuel pool above 1800 ppm, which exceeds the technical
specification
requirement
for boron concentration.
With these precautions
a subcriticality
margin greater than 5 percent would be maintained.
Degradation
of Boraflex has been previously
addressed
by NRC in Information
Notice 87-43, "Gaps in Neutron-Absorbing
Material in High-Density
Spent Fuel Storage Racks," September
8, 1987. The Electric Power Research Institute, which has been studying this phenomenon
for several years, has recently published
an interim report, "Boraflex
Test Results and Evaluation," TR-101986, February 1993.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.(~/'Bran Grimes, Director Division of Operating
Reactor Support Office of Nuclear Regulatory
Regulation
Technical
contacts:
Kombiz Salehi, RIII (708) 790-5782 K. I Parczewski, NRR (301) 504-2705 Larry Kopp, NRR (301) 504-2879 Vern Hodge, NRR (301) 504-1861 Attachments:
1. Figure 1, Palisades
Boraflex Coupon Types 2. List of Recently Issued NRC Information
Notices
IN 93-70.- tSeptember
10, 1993 spent fuel pool chemistry
sampling frequency
to daily, and (3) keeping the boron concentration
in the spent fuel pool above 1800 ppm, which exceeds the technical
specification
requirement
for boron concentration.
With these precautions
a subcriticality
margin greater than 5 percent would be maintained.
Degradation
of Boraflex has been previously
addressed
by NRC in Information
Notice 87-43, "Gaps in Neutron-Absorbing
Material in High-Density
Spent Fuel Storage Racks," September
8, 1987. The Electric Power Research Institute, which has been studying this phenomenon
for several years, has recently published
an interim report, "Boraflex
Test Results and Evaluation," TR-101986, February 1993.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 Uy Maian K. Grime$Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Regulatory
Regulation
Technical
contacts:
Kombiz Salehi, RIII (708) 790-5782 K. I Parczewski, NRR (301) 504-2705 Larry Kopp, NRR (301) 504-2879 Vern Hodge, NRR (301) 504-1861 Attachments:
1. Figure 1, Palisades
Boraflex Coupon Types 2. List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
OFFICE OGCB:DORS:NRR
DRS:RIII DD:DRS:RIII
SRXB:DSSA:NRR
C:SRXB:DSSA:NRR
NAME *CVHodge *KSalehi *WLForney
- LIKopp *RCJones DATE 09/02/93 09/02/93 09/02/93 09/03/93 09/03/93 Tech Ed D:DSSA EMCB:DE:NRR
EMCB:DE:NRR
C:EMCB:DE:NRR
C:OEAB:DORS
09/01/93 09/04/93 01J0 M22 09/03/93 09/03/93 09/03/93 11 _ _ _ _ ,_C:OGCB:DORS:NRR
j I 09/03/93 09/7 /93 DOCUMENI NAME: 93-/U.IN
K>IN 93-xx I September
xx, 1993 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. I Brian K. Grimes, Director Division of Operating
Reactor Supi Office of Nuclear Regulatory
Regul 0ort at on Technical
Contact: Kombiz Salehi, (708) 790-5782 RIII K. I Parczewski, NRR (301) 504-2705 Larry Kopp, NRR (301) 504-2879 Vern Hodge, NRR (301) 504-1861 Attachments:
1. Figure 1, Palisades
Boraflex Coupon Types 2. List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
... ..... -..' at .-law. 1 OFFICE OGCB:DORS:NRR
DRS: RI I¢ .RP DD DR4:RIIIr SRXB:DSSA:NRR
- L/C:SRXB:DSSA:NRRL
NAME CVHodge KSalehi WLForney LIKop RC ones, DATE O /l2/93 CO/72/93 £ /O2I93 7/3 /93 /3 /93*Tech Ed D:DSS r EMCB:DE:NRR
_MCB:DE:NRS
C: 7 U D NRR IOEAB:DORS
ACThada i Strosnider
XParczewski
RAHermann
j 0aef ffee/9 / /9 /3 /93 '1 /,3/93 § /3 /93 ___________
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GHMarcus OI M BKGrimes q/13 /93 / /93 DOCUMENT NAME: PALN0902.CVH
4Adr of ads? >.4 A 42XsK 4-ct-M etO 4 vJ IN 93-xx September
xx, 1993 The licensee took several compensatory
measures, including
(1) making the operating
staff aware to not dilute the spent fuel pool, (2) increasing
the spent fuel pool chemistry
sampling frequency
to daily, and (3) keeping the boron concentration
in the spent fuel pool above 1800 ppm, which exceeds the technical
specification
requirement
for boron concentration.
Degradation
of Boraflex has been previously
addressed
by NRC in Information
Notice 87-43, "Gaps in Neutron-Absorbing
Material in High-Density
Spent Fuel Storage Racks," September
8, 1987. The Electric Power Research Institute, who has been studying this phenomenon
for several years, has recently published
an interim report, "Boraflex
Test Results and Evaluation," TR-101986, February 1993.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
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Regulatory
Regulation
Technical
Contact: Kombiz Salehi, RIII (708)790-5782 K. I Parczewski, NRR Larry Kopp, NRR Vern Hodge, NRR (301) 504-2705 (301) 504-2879 (301) 504-1861 Attachments:
1. Figure 1, Palisades
Boraflex Coupon Types 2. List of Recently Issued NRC Information
Notices rnmriIDDrrr
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OFFICE lOGCB:DORS:NRR
DRS:RIII D:DRS:RIII
SRXB:DSSA:NRR
C:SRXB:DSSA:NRR
NAME CVHodge Ug KSalehi TOMartin LIKopp RCJones DATE Oq/ol0/93
/ /93 / /93 /93 /93 Tech Ed D:DSSA EMCB:DE:NRR
EMCB:DE:ND
C:EMCB:DE:NRR
C:OEAB:DORS
q j ACTHADANI
JStrosnider
KIParczews'ki
RAHermann
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D:DORS:NRR
GHMarcus [BKGrimes/ /93 J / /93 DOCUMENT NAME: PALNOFIG.CVH
K-I Attachment
1 IN 93-70 September
10, 1993 Figure 1_Palisades
Boraflex a Coupon Types a Bodfes mate w boned bloom two I 3 Shoet M Paf kn*Q Ii..I I 3i i 3_..I: I --I 39r Ia le i ! 2 I I I4 i..4 I.I I E Li
Axtachment
2 IN 93-70 September
10, 1993 Page 1 of I LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 93-69 93-68 92-16, Supp. 2 93-67 93-66 93-65 93-64 93-63 Radiography
Events at Operating
Power Reactors Failure of Pump Shaft Coupling Caused by Temper Embrittlement
during Manufacture
Loss of Flow from the Residual Heat Removal Pump during Refueling Cavity Draindown Bursting of High Pressure Coolant Injection
Steam Line Rupture Discs Injures Plant Personnel Switchover
to Hot-Leg Injection
Following A Loss-of-Coolant
Accident in Pres-surized Water Reactors Reactor Trips Caused by Breaker Testing with Fault Protection
Bypassed Periodic Testing and Preventive
Maintenance
of Molded Case Circuit Breakers Improper Use of Soluble Weld Purge Dam Material 09/02/93 09/01/93 08/23/93 08/16/93 08/16/93 08/13/93 All holders of OLs or CPs for nuclear power reactors and all radiography
licensees.
All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for pressurized
water reactors.Al 1 for holders of OLs or CPs nuclear power reactors.08/12/93 08/11/93 All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.* OL = Operating
License CP = Construction
Permit
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list | - Information Notice 1993-01, Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty Technologies (4 January 1993)
- Information Notice 1993-02, Malfunction of a Pressurizer Code Safety Valve (4 January 1993, Topic: Loop seal)
- Information Notice 1993-04, Investigation and Reporting of Misadministrations by the Radiation Safety Officer (7 January 1993)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-06, Potential Bypass Leakage Paths Around Filters Installed in Ventilation Systems (22 January 1993)
- Information Notice 1993-07, Classification of Transportation Emergencies (1 February 1993)
- Information Notice 1993-08, Failure of Residual Heat Removal Pump Bearings Due to High Thrust Loading (1 February 1993, Topic: Probabilistic Risk Assessment)
- Information Notice 1993-09, Failure of Undervoltage Trip Attachment on Westinghouse Model DB-50 Reactor Trip Breaker (2 February 1993)
- Information Notice 1993-10, Dose Calibrator Quality Control (2 February 1993)
- Information Notice 1993-11, Single Failure Vulnerability of Engineered Safety Features Actuation Systems (4 February 1993)
- Information Notice 1993-12, Off-Gassing in Auxiliary Feedwater System Raw Water Sources (11 February 1993)
- Information Notice 1993-13, Undetected Modification of Flow Characteristics in High Pressure Safety Injection System (16 February 1993)
- Information Notice 1993-14, Clarification of 10 CFR 40.22, Small Quantities of Source Material (18 February 1993)
- Information Notice 1993-15, Failure to Verify the Continuity of Shunt Trip Attachment Contacts in Manual Safety Injection and Reactor Trip Switches (18 February 1993)
- Information Notice 1993-16, Failures of Not-Locking Devices in Check Valves (19 February 1993, Topic: Anchor Darling, Flow Induced Vibration)
- Information Notice 1993-17, Safety Systems Response to Loss of Coolant and Loss of Offsite Power (25 March 1994, Topic: Fire Barrier, Backfit)
- Information Notice 1993-18, Portable Moisture-Density Gauge User Responsibilities During Field Operations (10 March 1993, Topic: Moisture Density Gauge, Moisture-Density Gauge, Stolen)
- Information Notice 1993-19, Slab Hopper Bulging (17 March 1993, Topic: Hydrostatic)
- Information Notice 1993-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators (24 March 1993)
- Information Notice 1993-21, Summary of NRC Staff Observations Compiled During Engineering Audits or Inspections of Licensee Erosion/Corrosion Programs (25 March 1993, Topic: Weld Overlay)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993)
- Information Notice 1993-26, Grease Soldification Causes Molded-Case Circuit Breaker Failure to Close (31 January 1994)
- Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization (8 April 1993, Topic: Reactor Vessel Water Level)
- Information Notice 1993-28, Failure to Consider Loss of DC Bus in the Emergency Core Cooling System Evaluation May Lead to Nonconservative Analysis (9 April 1993, Topic: Fuel cladding)
- Information Notice 1993-29, Problems with the Use of Unshielded Test Leads in Reactor Protection System Circuitry (12 April 1993)
- Information Notice 1993-30, NRC Requirements for Evaluation of Wipe Test Results; Calibration of Count Rate Survey Instruments (12 April 1993)
- Information Notice 1993-31, Training of Nurses Responsible for the Care of Patients with Brachytherapy Implants (13 April 1993, Topic: Brachytherapy)
- Information Notice 1993-32, Nonconservative Inputs for Boron Dilution Events Analysis (21 April 1993, Topic: Shutdown Margin)
- Information Notice 1993-33, Potential Deficiency of Certain Class Ie Instrumental and Control Cables (28 April 1993)
- Information Notice 1993-33, Potential Deficiency of Certain Class IE Instrumental and Control Cables (28 April 1993, Topic: Brachytherapy)
- Information Notice 1993-34, Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment (6 May 1993, Topic: Brachytherapy)
- Information Notice 1993-35, Insights from Common-Cause Failure Events (12 May 1993, Topic: Brachytherapy)
- Information Notice 1993-36, Notifications, Reports, and Records of Misadministrations (7 May 1993, Topic: Brachytherapy)
- Information Notice 1993-37, Eyebolts with Indeterminate Properties Installed in Limitorque Valve Operator Housing Covers (19 May 1993, Topic: Brachytherapy)
- Information Notice 1993-38, Inadequate Testing of Engineered Safety Features Actuation Systems (24 May 1993)
- Information Notice 1993-39, Radiation Beams From Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-39, Radiation Beams from Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-40, Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material (26 May 1993, Topic: Safe Shutdown, Fire Barrier, Fire Protection Program)
- Information Notice 1993-41, One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems (28 May 1993, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1993-42, Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by Yelan (9 June 1993)
- Information Notice 1993-43, Use of Inappropriate Lubrication Oils in Satety-Related Applications (10 June 1993)
- Information Notice 1993-44, Operational Challenges During a Dual-Unit Transient (15 June 1993)
- Information Notice 1993-45, Degradation of Shutdown Cooling System Performance (16 June 1993)
- Information Notice 1993-46, Potential Problem with Westinghouse Rod Control System and Inadvertent Withdrawal of Single Rod Control Cluster Assembly (10 June 1993)
- Information Notice 1993-47, Unrecognized Loss of Control Room Annunciators (18 June 1993)
- Information Notice 1993-48, Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated Oil (6 July 1993)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
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