Thermo-LAG 330-660 Flexi-Blanket Ampacity Derating ConcernsML031060554 |
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: |
05/13/1994 |
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From: |
Grimes B Office of Nuclear Reactor Regulation |
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To: |
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References |
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-nr IN-94-034, NUDOCS 9405090108 |
Download: ML031060554 (12) |
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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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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>. |
-1 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 May 13, 1994 NRC INFORMATION NOTICE 94-34: THERMO-LAG 330-660 FLEXI-BLANKET AMPACITY
DERATING CONCERNS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to a potential problem involving the use of
nonconservative ampacity derating data by licensees based on previous
representations by the vendor, Thermal Science, Inc. (TSI). It is expected
that recipients will review the information for applicability to their
facilities and consider actions, as appropriate, to avoid similar problems.
However, suggestions contained in this information notice are not NRC
requirements; therefore, no specific action or written response is required.
Description of Circumstances
The vendor, TSI, stated in a purchase document, OTSI's Bid Document 618,"
dated June 25, 1986, for Northeast Utilities Service Company (Millstone
Units 1 and 2) that the Thermo-Lag 330-660 Flex-Blanket material will produce
test results similar to those of the Thermo-Lag 330-1 material. For example, the vendor cited a 7.47 percent ampacity derating factor for the Thermo- Lag 330-1 material based on reported test results for a 1-hour-rated fire
barrier conduit system.
On November 8, 1993, the NRC staff wrote to TSI requesting information
regarding the ampacity derating data provided licensees for the application of
the Thermo-Lag 330-660 Flexi-Blanket fire barrier system.
On December 22, 1993, TSI responded stating that Texas Utilities Electric
Company had recently conducted an ampacity derating test at the Omega Point
Test Laboratories. The test, using a 1-hour design (three 0.64 cm
[0.250 inch] layers) of the Thermo-Lag 330-660 Flexi-Blanket material, had
resulted in a 21.2 percent ampacity derating factor for a 3C/#6 AWG Air Drop
configuration. In addition, the vendor stated that, to the best of its
knowledge, no ampacity derating test has been performed on the 3-hour design
(five 0.64 cm [0.250 inch] layers) of the Thermo-Lag 330-660 Flexi-Blanket
fire barrier system.
9405090108 ?D)V 't tE £eLtc-e- lqfia03q ¶Lst Ia3 At/7/f X0 1
Vt V IN94-34 May 13, 1994 Attachment 1 contains a list of the organizations that TSI identified as
having purchased the Thermo-Lag 330-660 Flexi-Blanket material for use in
nuclear power generating plants.
Discussion
Title 10 of the Code of Federal Regulations, Part 50, Appendix A, General
Design Criterion (GDC) 17, "Electric power systems," if applicable, requires
that onsite and offsite electric power systems be provided to permit the
functioning of structures, systems, and components important to safety. The
safety function of either electrical power system (assuming the other system
is not functioning) is to provide sufficient capacity and capability to ensure
that vital functions are maintained. Cables routed in electrical raceways are
derated to ensure that systems have sufficient capacity and capability to
perform their intended safety functions. Other factors that affect ampacity
derating include cable fill, cable loading, cable type, raceway construction, and ambient temperature.
Cable derating calculations that are based on inaccurate or nonconservative
derating factors could result in the installation of undersized cables or
overfilling of raceways. Either of these conditions could cause operating
temperatures to exceed design limits within the raceways, thereby reducing the
expected design life of the cables. TSI stated in the 1986 procurement
document referenced above that the Thermo-Lag 330-660 material will produce
similar ampacity results as those of the Thermo-Lag 330-1 material. Because
of the wide range of ampacity derating factors documented for various Thermo- Lag materials, some licensees may not have adequately accounted for the
insulating effects of the Thermo-Lag 330-660 material in their derating
analyses.
The National Electrical Code, Insulated Cable Engineers Association
publications, and other industry standards provide general ampacity derating
factors for open-air installations, but do not include derating factors for
fire barrier systems. The Insulated Conductors Committee of the Institute of
Electrical and Electronics Engineers (IEEE) Power Engineering Society, Task
Force 12-45, has been developing IEEE Standard Procedure P848, "Procedure for
the Determination of the Ampacity Derating of Fire Protected Cables," for use
as an industry standard. The industry consensus standard development process
may result in the formulation of a uniform technical approach to the deter- mination of ampacity derating factors for cables enclosed by fire barrier
systems.
Related Generic Communications
In NRC Information Notice (IN)92-46, "Thermo-Lag Fire Barrier Material
Special Review Team Final Report Findings, Current Fire Endurance Tests, and
Ampacity Calculation Errors," the staff informed licensees that a licensee had
discovered a mathematical error in the calculation of the ampacity derating
IN94-34 v May 13, 1994 factor as published in an Industrial Testing Laboratories, Incorporated, test
report. A preliminary assessment of the use of lower-than-actual ampacity
derating factors indicates that the Thermo-Lag barrier installations may allow
cables to reach temperatures that exceed their ratings, which could accelerate
cable aging.
In IN 94-22, 'Fire Endurance and Ampacity Derating Test Results for 3-Hour
Fire-Rated Thermo-Lag 330-1 Fire Barriers," the staff informed licensees of
the preliminary results of fire endurance and ampacity derating tests
conducted by NRC at the Underwriters Laboratories, Incorporated, during
December 1993. The principal objective of the tests was to evaluate the
performance of the barriers against the results of tests previously reported
by TSI.
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 Nuc ar
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Ronaldo V. Jenkins, NRR
(301) 504-2985 Attachments:
1. Licensees Who Purchased Thermo-Lag 330-660
Flexi-Blanket Thermal Barrier Material
2. List of Recently Issued NRC Information Notices
,j Attachment No. 1 IN 94-34 May 13, 1994 LICENSEES WHO PURCHASED
THERMO-LAG 330-660 FLEXI-BLANKET THERMAL BARRIER MATERIAL'
Utility I Facility
Carolina Power & Light Co. Brunswick
Cleveland Electric Illuminating Co. Perry Nuclear Plant
Commonwealth Edison Braidwood Station
Entergy Operations, Inc. Waterford 3
Consumers Power Palisades
Florida Power Corporation Crystal River Unit 3
Fluor Engineers Co. San Onofre
Georgia Power E. I. Hatch
Plant Vogtle
Gulf States Utilities2 River Bend
GPU Nuclear Oyster Creek
-Three Mile Island
Long Island Lighting Shoreham
Iowa Electric Duane Arnold Plant
Northern States Power Prairie Island
South Carolina Electric & Gas Co. Virgil C. Summer
Tennessee Valley Authority Browns Ferry
Watts Bar
Toledo Edison Co. Davis Besse Power Station
Texas Utilities Electric Comanche Peak Units 1 and 2 Washington Public Power Supply System WNP-2
1 From TSI letter to NRC dated December 22, 1993.
2Licensee is now Entergy Operations, Inc.
AtV_ chment No. 2 IN 94-34 May 13, 1994 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
94-33 Capacitor Failures in 05/09/94 All holders of OLs or CPs
Westinghouse Eagle 21 for nuclear power reactors.
Plant Protection Systems
93-53, Effect of Hurricane 04/29/94 All holders of OLs or CPs
Supp. 1 Andrew on Turkey Point for nuclear power reactors.
Nuclear Generating
Station and Lessons Learned
94-32 Revised Seismic Hazard 04/29/94 All holders of OLs or CPs
Estimates for nuclear power reactors.
94-31 Potential Failure of 04/14/94 All holders of OLs or CPs
Wilco, Lexan-Type HN-4-L for nuclear power reactors.
Fire Hose Nozzles
90-68, Stress Corrosion Cracking 04/14/94 All holders of 01 or CPs
Supp. 1 of Reactor Coolant Pump for pressurized water
Bolts reactors.
Leaking Shutdown Cooling 04/12/94 All holders of OLs or CPs
Isolation Valves at for nuclear power reactors.
Cooper Nuclear Station
94-29 Charging Pump Trip during 04/11/94 All holders of OLs or CPs
a Loss-of-Coolant Event for pressurized water
Caused by Low Suction reactors.
Pressure
92-51, Misapplication and 04/12/94 All holders of OLs or CPs
Supp. 1 Inadequate Testing of for nuclear power reactors.
Molded-Case Circuit
Breakers
Potential Problems with 04/05/94 All holders of OLs or CPs
Fire-Barrier Penetration for nuclear power reactors.
Seals
OL - Operating License
CP - Construction Permit
IN 94-34 May 13, 1994 factor as published in an Industrial Testing Laboratories, Incorporated, test
report. A preliminary assessment of the use of lower-than-actual ampacity
derating factors indicates that the Thermo-Lag barrier installations may allow
cables to reach temperatures that exceed their ratings, which could accelerate
cable aging.
In IN 94-22, "Fire Endurance and Ampacity Derating Test Results for 3-Hour
Fire-Rated Thermo-Lag 330-1 Fire Barriers," the staff informed licensees of
the preliminary results of fire endurance and ampacity derating tests
conducted by NRC at the Underwriters Laboratories, Incorporated, during
December 1993. The principal objective of the tests was to evaluate the
performance of the barriers against the results of tests previously reported
by TSI.
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.
Oiighial Ugnid f
Brian K.Grimei
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Ronaldo V. Jenkins, NRR
(301) 504-2985 Attachments:
1. Licensees Who Purchased Thermo-Lag 330-660
Flexi-Blanket Thermal Barrier Material
2. List of Recently Issued NRC Information Notices
OFFICE *OGCB\DORS *Tech Editor *EELB\DE *C:\EELB\DE
NAME RJKiessel MMejac RVJenkins CHBerlinger
DATE 4/12/94 T,
1 4/14/94
-
4/18/94 4 4/21/94 OFFICE *D: DE\NRR *C:OGCB\DORS D: w
NAME BWSheron AJKugler fB e`(e
DATE 4/22/94 5/05/94 1 5/ /94 Document Name: 94-34.IN
IN 94- xx
May xx, 1994 factor as published in an Industrial Testing Laboratories, Incorporated, test
report. A preliminary assessment of the use of lower-than-actual ampacity
derating factors indicates that the Thermo-Lag barrier Installations may allow
cables to reach temperatures that exceed their ratings, which could accelerate
cable aging.
In IN 94-22, "Fire Endurance and Ampacity Derating Test Results for 3-Hour
Fire-Rated Thermo-Lag 330-1 Fire Barriers," the staff informed licensees of
the preliminary results of fire endurance and ampacity derating tests
conducted by NRC at the Underwriters Laboratories, Incorporated, during
December 1993. The principal objective of the tests was to evaluate the
performance of the barriers against the results of tests previously reported
by TSI.
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 Reactor Regulation
Technical contact: Ronaldo V. Jenkins, NRR
(301) 504-2985 Attachments:
1. Licensees Who Purchased Thermo-Lag 330-660 Flexi-Blanket Thermal Barrier
Material
2. List of Recently Issued NRC Information Notices
OFFICE *OGCB\DORS *Tech Editor *EELB\DE *C:\EELB\DE ]
NAME RJKiessel MMejac RVJenkins CHBerlinger l
DATE 4/12/94 4/14/94 4/18/94 4/21/94
OFFICE *D:DE\NRR C:OGCB\DORS D:DORS\NRR
NAME BWSheron AJKugler e BKGrimes S
DATE 4/22/94 1 5/S-/94 5/ /94 Document Name: G:\RJK\NRCINS\NRCIN.421
IN 94- xx
April xx, 1994 factor as published in an Industrial Testing Laboratories, Incorporated, test
report. A preliminary assessment of the use of lower-than-actual ampacity
derating factors indicates that the Thermo-Lag barrier installations may allow
cables to reach temperatures that exceed their ratings, which could accelerate
cable aging.
In IN 94-22, "Fire Endurance and Ampacity Derating Test Results for 3-Hour
Fire-Rated Thermo-Lag 330-1 Fire Barriers," the staff informed licensees of
the preliminary results of fire endurance and ampacity derating tests
conducted by NRC at the Underwriters Laboratories, Incorporated, during
December 1993. The principal objective of the tests was to evaluate the
performance of the barriers against the results of tests previously reported
by TSI.
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 Reactor Regulation
Technical contact: Ronaldo V. Jenkins, NRR
(301) 504-2985 Attachments:
1. Licensees Who Purchased Thermo-Lag 330-660 Flexi-Blanket Thermal Barrier
Material
2. List of Recently Issued NRC Information Notices
I-. - concurrence
- --
OFFICE *OGCB\DORS *Tech Editor *EELB\DE *C:\EELB\DE
NAME . RJKiessel MMejac RVJenkins CHBerlinger
DATE 4/12/94 4/14/94 4/18/94 4/21/94
- I I
OFFICE *D:DE\NRR C:OGCB\DORS D:DORS\NRR
NAME BWSheron AJKugler BKGrimes
l
DATE 1 4/22/94 5/ /94 5/ /94 Document Name: G:\RJK\NRCINS\NRCIN.421
IN 94- xx
April xx, 1994 conducted by NRC at the Underwriters Laboratories, Incorporated, during
December 1993. The principal objective of the tests was to evaluate the
performance of the barriers against the results of tests previously reported
by TSI.
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 Reactor Regulation
Technical contact: Ronaldo V. Jenkins, NRR
(301) 504-2985 Attachments:
1. Licensees Who Purchased Thermo-Lag 330-660 Flexi-Blanket Thermal Barrier
Material
2. List of Recently Issued NRC Information Notices
/,t d21
OFFICE *OGCB\DORS *Tech Editor EELB\DE C `\t
J at
NAME RJKiessel MMejac RVJenkins 4 CHBerlinger
DATE 1 4jI94 4/14/94 4/L/942 bL 4 X /94 j
V 71 OFFICE 6: OKNRR C:OGCB\DORS D:DORS\NRR
NAME BWkdon AJKugler BKGrimes
DATE 4/iZ,/94 4/ /94 4/ /94 Document Name: :\ G\JK\NRGIN5\NRULN.4Z1 a0Alp
Attachments:
1. Licensees Who Purchased Thermo-Lag 330-660 Flexi-Blanket Thermal Barrier
Material
2. List of Recently Issued NRC Information Notices
- Cev nrwinmic rnlrinrrenre
OFFICE OGCB\DORS 1 ITech Editor EELB\DE C:\EELB\DE
NAME Riessel X . M*J4vC-
$t.fl RVJenkins CHBerlinger
DATE 4/)r./94 4/1fi/94 j 4/ /94 4/ /94 OFFICE D:DE\NRR C:OGCB\DORS D:DORS\NRR
NAME BWSheron AJKugler BKGrimes
DATE 4/ /94 4/ /94 4/ /94 Ii
Document Name: b:NKJKNNK~lNb\NK~lN.4Z1
I
K)
IN 94-XX
March xx, 1994 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 Reactor Regulation
Technical contact: Ronaldo V. Jenkins, NRR
(301) 504-2985 Attachment:
List of Recently Issued NRC Information Notices
Document Name: G:\SHARED\INTHERM.660
D/DORS:NRR C/OGCB:DORS:NRR
BKGrimes GHMarcus
3/ /94 3/ /94 EELB:DE:NRR SC/EELB:DE:NRR OGCB:DORS:NRR RPB:ADM
- RVJenkins PGill U TechEd*-)l
2/16/94 2/.26/94 3/ /94 2/22/94
IN 94-XX
January xx, 1994 This inform tion 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 Regula ion (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Ron ido V. Jenkins, NRR
(301 504-2985 Attachment:
List of Recently Issued NRC I formation Notices
Document Name: G:\SHARED\ RM.660
D/DORS:NRR C/OGCB:DORS:NRR
BKGrimes GHMarcus
2/ /94 2/ /94 EELB:DE:NRR SC/EELB:DE:NRR C/EELB:DE. RR OGCB:DORS:NRR RPB:ADM
RVJenkinsooev~ie PGill CHBerlinge TechEd*
2//e/94 ' 2/ /94 2/ /94 2/ /94 2/ /94
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list | - Information Notice 1994-01, Turbine Blade Failures Caused by Torsional Excitation from Electrical System Disturbance (7 January 1994)
- Information Notice 1994-02, Inoperability of General Electric Magne-Blast Breaker Because of Misalignment of Close-Latch Spring (7 January 1994)
- Information Notice 1994-03, Deficiencies Identified During Service Water System Operational Performance Inspections (11 January 1994, Topic: Biofouling)
- Information Notice 1994-04, Digital Integrated Circuit Sockets with Intermittent Contact (14 January 1994)
- Information Notice 1994-05, Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves (19 January 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-06, Potential Failure of Long-Term Emergency Nitrogen Supply for the Automatic Depressurization System Valves (28 January 1994)
- Information Notice 1994-07, Solubility Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20 (28 January 1994)
- Information Notice 1994-08, Potential for Surveillance Testing to Fail to Detect an Inoperable Main Steam Isolation Valve (1 February 1994)
- Information Notice 1994-09, Release of Patients with Residual Radioactivity from Medical Treatment & Control of Areas Due to Presence of Patients Containing Radioactivity Following Implementation of Revised 10 CFR Part 20 (3 February 1994, Topic: Brachytherapy)
- Information Notice 1994-10, Failure of Motor-Operated Valve Electric Power Train Due to Sheared or Dislodged Motor Pinion Gear Key (4 February 1994)
- Information Notice 1994-11, Turbine Overspeed and Reactor Cooldown During Shutdown Evolution (8 February 1994, Topic: Overspeed trip, Overspeed)
- Information Notice 1994-12, Insights Gained from Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment (9 February 1994, Topic: Overspeed)
- Information Notice 1994-13, Unanticipated and Unintended Movement of Fuel Assemblies and Other Components Due to Improper Operation of Refueling Equipment (28 June 1994)
- Information Notice 1994-14, Failure to Implement Requirements for Biennial Medical Examinations and Notification to the NRC of Changes in Licensed Operator Medical Conditions (24 February 1994, Topic: Overspeed)
- Information Notice 1994-15, Radiation Exposures During an Event Involving a Fixed Nuclear Gauge (2 March 1994, Topic: Overspeed)
- Information Notice 1994-16, Recent Incidents Resulting in Offsite Contamination (3 March 1994, Topic: Overspeed)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use (11 March 1994, Topic: Brachytherapy, Overspeed)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (Qmp), Calibration, and Use (11 March 1994, Topic: Brachytherapy, Overspeed)
- Information Notice 1994-18, Accuracy of Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to Generic Letter 89-10) (16 March 1994)
- Information Notice 1994-19, Emergency Diesel Gemerator Vulnerability to Failure from Cold Fuel Oil (16 March 1994)
- Information Notice 1994-20, Common-Cause Failures Due to Inadequate Design Control and Dedication (17 March 1994)
- Information Notice 1994-21, Regulatory Requirements When No Operations Are Being Performed (18 March 1994)
- Information Notice 1994-22, Fire Endurance & Ampacity Derating Test Results for 3-Hour Fire-Rated Thermo-Lag 330-1 Fire Barriers (16 March 1994, Topic: Fire Barrier)
- Information Notice 1994-23, Guidance to Hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program (25 March 1994, Topic: Fire Barrier)
- Information Notice 1994-24, Inadequate Maintenance of Uninterruptible Power Supplies & Inverters (24 March 1994, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1994-25, Failure of Containment Spray Header Valve to Open Due to Excessive Pressure from Inertial Effects of Water (15 March 1994, Topic: Fire Barrier, Water hammer)
- Information Notice 1994-26, Personnel Hazards and Other Problems from Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water Reactor (28 March 1994, Topic: Fire Barrier)
- Information Notice 1994-27, Facility Operating Concerns Resulting from Local Area Flooding (31 March 1994, Topic: Fire Barrier)
- Information Notice 1994-28, Potential Problems with Fire-Barrier Penetration Seals (5 April 1994, Topic: Fire Barrier, Operability Determination)
- Information Notice 1994-29, Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction Pressure (11 April 1994, Topic: Boric Acid)
- Information Notice 1994-30, Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station (19 August 1994, Topic: Fire Barrier, Local Leak Rate Testing)
- Information Notice 1994-31, Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles (14 April 1994, Topic: Hydrostatic, Stress corrosion cracking)
- Information Notice 1994-32, Revised Seismic Estimates (29 April 1994, Topic: Stress corrosion cracking, Earthquake)
- Information Notice 1994-33, Capacitor Failures in Westinghouse Eagle 21 Plant Protection Systems (9 May 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-34, Thermo-LAG 330-660 Flexi-Blanket Ampacity Derating Concerns (13 May 1994, Topic: Fire Barrier, Stress corrosion cracking)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(Mmr) from the Facepiece on the Mine Safety Appliances (16 May 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(MMR) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System (24 May 1994, Topic: Reactor Vessel Water Level, Stress corrosion cracking, Integrated leak rate test)
- Information Notice 1994-37, Misadministration Caused by a Bent Interstitial Needle During Brachytherapy Procedure (27 May 1994, Topic: Stress corrosion cracking, Brachytherapy)
- Information Notice 1994-38, Results of Special NRC Inspection at Dresden Nuclear Power Station, Unit 1 Following Rupture of Service Water Inside Containment (27 May 1994)
- Information Notice 1994-39, Identified Problems in Gamma Stereotactic Radiosurgery (31 May 1994)
- Information Notice 1994-40, Failure of a Rod Control Cluster Assembly to Fully Insert Following a Reactor Trip at Braidwood, Unit 2 (26 May 1994)
- Information Notice 1994-41, Problems with General Electric Type Cr124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-41, Problems with General Electric Type CR124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-42, Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors (7 June 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-43, Determination of Primary-to-Secondary Steam Generator Leak Rate (10 June 1994, Topic: Grab sample)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand Because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-45, Potential Common-Mode Failure Mechanism for Large Vertical Pumps (17 June 1994, Topic: Biofouling)
- Information Notice 1994-46, Nonconservative Reactor Coolant System Leakage Calculation (20 June 1994, Topic: Unidentified leakage)
... further results |
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