Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier MaterialML031080040 |
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 ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
05/26/1993 |
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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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IN-93-040, NUDOCS 9305260385 |
Download: ML031080040 (14) |
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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>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 May 26, 1993 NRC INFORMATION NOTICE 93-40: FIRE ENDURANCE TEST RESULTS FOR THERMAL
CERAMICS FP-60 FIRE BARRIER MATERIAL
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 results of fire endurance and ampacity derating
test reports submitted by Thermal Ceramics on the FireMaster FP-60 fire
barrier system and the results of NRC staff reviews. 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.
Descriotion of Circumstances
In Generic Letter (GL) 92-08, wThermo-Lag 330-1 Fire Barriers," the staff
stated it would evaluate other known fire barrier materials and systems that
are used by licensees to fulfill NRC fire protection requirements. The staff
is now evaluating fire barriers manufactured by other vendors to verify the
ability of the barriers to adequately perform their 1-hour or 3-hour fire
resistive functions and to meet stated ampacity derating values. Thermal
Ceramics, Inc., formerly the Insulating Products Division of Babcock and
Wilcox, Inc., of Augusta, Georgia, manufactures the FP-60 fire barrier system
and submitted reports on two fire endurance tests and one ampacity derating
test to the NRC in a letter of February 23, 1993.
Discussion
In its review of the Thermal Ceramics reports, the staff identified the
following information.
In its product literature, Thermal Ceramics states that the FP-60 product is
manufactured for use on cable trays, conduits, junction boxes, and other cable
raceways. The primary component, the FireMaster FP-60 blanket, is a ceramic
fiber blanket with thicknesses varying from 2.5 cm [1 inch] to 7.6 cm
[3 inches]. Optional aluminum or stainless steel foil, Kao-Tex (woven cloth),
or other cloth facings are provided for physical protection of the blanket.
The vendor claims that the material, when installed according to the
instructions, is qualified for up to a 13/4-hour fire rating using the American
9305260385 ' P I)oktce. 93-o
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IN 93-40
May 26, 1993 Society for Testing and Materials (ASTM) Standard E-119, "Standard Test
Methods for Fire Tests of Building Construction and Materials."
FIRE ENDURANCE TESTS
According to one report submitted by Thermal Ceramics, a.1-hour fire endurance
test of the FP-60 fire barrier in various configurations was performed at
Underwriters Laboratories, Inc. (UL File R11044-1, Project 84NK8356, March 22, 1985). The test followed UL Subject 1724, "Outline of
Investigation, Fire Tests for Electrical Circuit Protective Systems,"
May 1984. According to the report, the furnace temperatures followed the
ASTM E-119 standard time-temperature curve for fire exposure, and the barriers
were subjected to a solid hose stream test. The report also states that
circuit integrity was monitored.
Documented test configurations included 91.4 cm [36 inch] wide open-ladder and
solid-back steel cable trays, an air drop assembly, 12.7 cm [5 inch] diameter
steel conduits, and a 30.5x15.2 cm (12x6 inch] steel Junction box. All
configurations contained cables. Two hundred fifty thermocouples were
reportedly used to measure temperatures of cables, cable trays, Junction
- boxes, conduits and electrical circuit protective systdms on the unexposed
1 side of the assembly.
x According to the report, within 30 seconds of the start of the test, the
j filament tape around the blanket wrap ignited. At 5 minutes, flames
- reportedly issued from seams and butt joints. The report also states that at
20 minutes, some of the wrap slipped out of position resulting in an opening
^ in the barrier, and at 60 minutes, there was a 8.9 cm [3X inch] opening
in the
barrier. Some thermocouple measurements reportedly ranged from 204 'C
[400 OF] to 260 eC [500 OF] at the end of the fire test.
After the test, some cables were documented to be fused together, and cable
jackets were melted and blistered. The hose stream eroded the bottom surface
of the cable tray barrier so that the tray was exposed.
The UL report concluded that the tested fire barrier had a 1-hour fire rating
because circuit integrity was maintained during the fire exposure and hose
stream test. However, it appears that the UL approval is limited to minimum
91.4 cm [36 inch] wide cable trays and 12.7 cm [5 inch] or larger-diameter
conduits with minimum No. 16 AWG jacketed multi-conductor cables or minimum
No. 300 MCM jacketed copper single conductor power cables with polyvinyl
chloride jackets.
The second fire endurance test report submitted by Thermal Ceramics documented
a Southwest Research Institute small-scale test, "One Hour Fire Qualification
Test of a Protective Envelope for Class 1E Electrical Conduit Circuits," (SwRI
Project 01-8305-053, February 1986). According to this report, the test
employed the ASTM E-119 standard time-temperature curve for fire exposure and
a subsequent solid hose stream test. The report also states that circuit
integrity was monitored. SwRI documented the use of a small-scale furnace
(maximum test specimen of 425.8 square cm (66 square inches]) to test a
2.5 cm [1 inch] diameter conduit with a pull box, a 5.1 cm [2 inch] diameter
conduit with a junction box, and an air drop. According to the report,. these
IN 93-40
May 26, 1993 test assemblies each contained a single-conductor power cable and two control
cables, all with PVC jackets.
Recorded cable temperatures (measured at the cable jackets) at the end of the
fire exposure ranged from 146.5 'C (296 *F] to 164 C (327 OF]. According hoseto
the report, circuit integrity was maintained during the fire exposure and
stream tests.
The barrier and cable conditions after the fire exposure were not reported.
The test report suggests that the hose stream test caused some barrier damage, although the test report did not clearly report the extent of damage. SwRI
did not report a conclusion as to the acceptability of the fire barrier
system.
In a letter of April 27, 1993 to Thermal Ceramics, Inc., the staff expressed
concerns regarding the ability of the FP-60 system to meet existing NRC fire
barrier acceptance criteria.
AMPACITY DERATING TEST
The ampacity derating test report submitted by Thermal Ceramics was SwRI
Project 01-8818-210, "Ampacity Derating of Fire-Protected Cables in Conduit
and Cable Trays Using Babcock & Wilcox, Incorporated's Passive Fire Protection
System," issued by SwRI on July 8, 1986. According to the report, a 1-hour
fire barrier was used in the test. Three-conductor XLPE-insulated 6 AWG
cables with Hypalon protective wraps were reportedly installed in a
61 cm (24 inch] wide by 10.2 cm [4 inch] deep cable tray, and 3-conductor
XLPE-insulated 3 AWG cables with Hypalon protective wraps were installed in a
10.2 cm [4 inch] diameter conduit. Both assemblies were reported to be
3.7 m [12 feet] long and completely filled. The report stated that
thermocouples were installed in slits' in the cable insulation.
According to the report, a steady-state temperature of 90 eC (194 *F) at the
hottest single thermocouple was monitored. Equilibrium temperature was
reportedly established when a steady-state condition (+/-1 eC per hour (+/-1.8 OF
per hour]) was achieved for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> without any perturbation to the system.
The ampacity derating for the cable tray and conduit was estimated to be 62.4 and 41.4 percent, respectively, based on the test results.
Some licensees use the FP-60 fire barrier system to achieve physical
independence of electrical systems in accordance with Regulatory Guide 1.75, Physical Independence of Electrical Systems." Ampacity derating in fire
barrier systems installed to achieve physical independence of electric systems
is a consideration in the design of such systems as well as in those installed
to protect safe shutdown capability from a fire.
Cables enclosed in electrical raceways protected with fire barrier materials
are derated to ensure that systems have sufficient capacity and capability to
perform their intended safety functions. These cables are derated because of
the insulating effect of the fire barrier material. Other factors that affect
ampacity derating include cable fill, cable loading, cable type, raceway
construction, and ambient temperature.
IN 93-40
May 26, 1993 Cable derating calculations that are based on inaccurate or nonconservative
derating factors could result in installation of undersized cables or raceway
overfilling. This could cause operating temperatures to exceed design limits
within the raceways thereby reducing the expected design life of the cables.
In the letter to Thermal Ceramics, Inc., of April 27, 1993, the staff
requested additional information on ampacity derating.
The National Electrical Code, Insulated Cable Engineers Association (ICEA)
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 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 formulate an appropriate technical
approach to the determination of ampacity derating factors for cables enclosed
by fire barrier systems.
The staff is continuing to review this product for its ability to perform its
fire resistive function and will evaluate whether further generic
communications are needed to address the issues discussed above.
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: Isabel M. Miller, NRR
(301) 504-2852 Attachment:
List of Recently Issued Information Notices
May 26, 1993 Cable derating calculations that are based on inaccurate or nonconservative
derating factors could result in installation of undersized cables or raceway
overfilling. This could cause operating temperatures to exceed design limits
within the raceways thereby reducing the expected design life of the cables.
In the letter to Thermal Ceramics, Inc., of April 27, 1993, the staff
requested additional information on ampacity derating.
The National Electrical Code, Insulated Cable Engineers Association (ICEA)
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 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 formulate an appropriate technical
approach to the determination of ampacity derating factors for cables enclosed
by fire barrier systems.
The staff is continuing to review this product for its ability to perform its
fire resistive function and will evaluate whether further generic
communications are needed to address the issues discussed above.
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. Orginal ignd y
Brian K.Grimes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Isabel M. Miller, NRR
(301) 504-2852 Attachment:
List of Recently Issued Information Notices
- SPLB:DSSA *SPLB:DSSA *TechEd
IMiller SWest DGable
05/06/93 , 05/06/93 05/10/93
CMcCracken JGoldberg CBerlinger
5/20/93 5/20/93 05/25/93
- DD:DSSA *D:DSSA *OGCB:DORS
MVirgilio AThadani GMarcus Grimes
05/25/93 05/25/93 05/25/93 S g&493 DOCUMENT NAME: 93-40.IN
IN 93-XX
May xx, 1993 Cable derating calculations that are based on inaccurate or nonconservative
derating factors could result in installation of undersized cables or raceway
overfilling. This could cause operating temperatures to exceed design limits
within the raceways thereby reducing the expected design life of the cables.
In the letter to thermal ceramics of April 27, 1993, the staff requested
additional information on ampacity derating.
The National Electrical Code, Insulated Cable Engineers Association (ICEA)
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 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 formulate an appropriate technical
approach to the determination of ampacity derating factors for cables enclosed
by fire barrier systems.
The staff is continuing to review this product for its ability to perform its
fire resistive function and will evaluate whether further generic
communications are needed to address the issues discussed above.
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: Isabel M. Miller, NRR
(301) 504-2852 Attachment:
List of Recently Issued Information Notices
SPLB:DSSA SPLB:DSSA TechEd
05/06/93 05/06/93 05/10/93 SPLB:DSSA OGC *DE:EELB
CMcCracken* JGoldberg* CBerlinger
5/20/93 5/20/93 05/25/93
- DD:DSSA *D:DSSA *OGCB:DORS D:DORS
MVirgilio AThadani GMarcus BGrimes
05/25/93 05/25/93 05/25/93 / /93 DOCUMENT NAME: INPSB.1
4 factors for open-air installations but do not include derating factors for
fire barrier systems. The Insulated Conductors Committee of the 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 staff encourages
licensees to participate in the industry consensus standard development
process to formulate an appropriate technical approach to the determination of
ampacity derating factors for cables enclosed by fire barrier systems.
The staff is continuing to review this product for its ability to perform its
fire resistive function and will take further action if appropriate.
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: Isabel M. Miller, NRR
(301) 504-2852 Attachment:
List of Recently Issued Information Notices
SPLB:DSSA SPLB:DSSA TechEd
05/06/93 05/06/93 05/10/93 SPLB:DSSA OGC DE:EELB
CMcCracken* JGoldberg* CBerlinger*
5/20/93 5/20/93/ / /93 DD:DSSA D:DSSA M OGCBD;ORS D: DORS
MVirgilio* AThadani &M GMar~ BGrimes
/ /93 5 f1;93 1-/ (/93 AlS / /93
[G:\THERMOLA\OTHERVEN\IN FP60.R3]
Originator: Isabel Miller
_L
factors for open-air installations but do not include derating factors for
fire barrier systems. The Insulated Conductors Committee of the 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 staff encourages
licensees to participate in the industry consensus standard development
process to formulate an appropriate technical approach to the determination of
ampacity derating factors for cables enclosed by fire barrier systems.
This information notice requires no specific action or written response.
The staff is continuing to review this product for its ability to perform its
fire resistive function and will take further action if appropriate. 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: Isabel M. Miller, NRR
(301) 504-2852 Attachment:
List of Recently Issued Information Notices
SPLB:DSSA SPLB:DSSA TechEd
05/06/93 05/06/93 05/10/93 SPLB:DSSA OGC DE:EE
CMcCracken* JGoldberg* CBerltTrg r
5/20/93 5/20/93 -jstk093 DD:DSSA,~ D:DSSA OGCB:DORS D:DORS
M9irgil9 AThadani GMarcus BGrimes
/ /93 / /93 / /93
[G:\THERMOLA\OTHERVEN\IN FP60.R3]
Originator: Isabel Miller
1__ . '\1 factors for open-air installations but do not include derating factors for
fire barrier systems. The Insulated Conductors Committee of the 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 staff encourages
licensees to participate in the industry consensus standard development
process to formulate an appropriate technical approach to the determination of
ampacity derating factors for cables enclosed by fire barrier systems.
This information notice requires no specific action or written response. The
staff is continuing to review this product for its ability to perform its fire
resistive function and will take further action if appropriate. Licensees are
advised to consider this information when contemplating any changes to their
current fire protection program. 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: Isabel M. Miller, NRR
(301) 504-2852 Attachment:
List of Recently Issued Information Notices
SPLB:DSSA SPLB:DSSA TechEd
05/06/93 05/06/v 05/10/93 SPLB:DSSP( ' L DE:EELB
CMcCrackelr CBerlinger
_.5/P/93 / /93 DD:DSSA D:DSSA OGCB:DORS D: DORS
MVirgilio AThadani GMarcus BGrimes
/ /93 / /93 / /93 / /93
[G:\THERMOLA\OTHERVEN\IN FP60.R2]
Originator: Isabel Miller
This information notice required 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.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: K. Steven West, NRR
(301) 504-1220
Attachment:
List of Recently Issued Information Notices
SPLB:DSSA SPLB:DSSA
IMiller SWest
/ /93 / /93 6:7/0/93 OGC SPLB:DSSA DE:EELB
JGoldberg CMcCracken CBerlinger
/ /93 / /93 / /93 DD:DSSA D:DSSA OGCB:DORS D: DORS
GHolahan AThadani GMarcus BGrimes
04/ /93 04/ /93 04/ /93 / /93
. ,- -. 1
- l *
consider actions as appropriate.
This information notice required 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.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contai K. Steven West, NRR
(301) 504-1220
Attachment:
List of Recentl2 ssued Information Notices
SPLB:DSSA,. TechEd
IMilletgfYL SIest RiStnde-e
5f/6 /93 t576 /93 / /93 OGC SPLB:DSSA DE: EELB
JGoldberg CMcCracken CBerlinger
/ /93 / /93 / /93 DD: DSSA D: DSSA OGCB:DORS D: DORS
GHolahan AThadani GMarcus BGrimes
04/ /93 04/ /93 04/ /93 / /93
[G:\THERMOLA\FP-60 IN.R1]
Originator: IsabeT Miller
I -1 Attachment
IN 93-40
May 26, 1993 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-39 Radiation Beams from 05/25/93 All holders of OLs or CPs
Power Reactor Biolog- for nuclear power reactors.
ical Shields
93-38 Inadequate Testing of 05/24/93 All holders of OLs or CPs
Engineered Safety for nuclear power reactors.
Features Actuation
System
93-37 Eyebolts with Indeter- 05/19/93 All holders of OLs or CPs
minate Properties In- for nuclear power reactors.
stalled in Limitorque
Valve Operator Housing
Covers
93-36 Notifications, Reports, 05/07/93 All U.S. Nuclear Regulatory
and Records of Misadmin- Commission medical
istrations licensees.
93-35 Insights from Common- 05/12/93 All holders of OLs or CPs
Cause Failure Events for nuclear power plants
(NPPs).
93-34, Potential for Loss of 05/06/93 All holders of OLs or CPs
Supp. 1 Emergency Cooling for nuclear power reactors.
Function Due to A
Combination of
Operational and Post- Loca Debris in Contain- ment
93-34 Potential for Loss of 04/26/93 All holders of OLs or CPs
Emergency Cooling for nuclear power reactors.
Function Due to A
Combination of
Operational and Post- Loca Debris in Contain- ment
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)
... further results |
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