Fire Endurance Test Results for Electrical Raceway Fire Barrier Systems Constructed from 3M Company Interam Fire Barrier MaterialsML031060151 |
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: |
11/14/1995 |
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From: |
Crutchfield D Office of Nuclear Reactor Regulation |
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To: |
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References |
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GL-86-010 IN-95-052, NUDOCS 9511080324 |
Download: ML031060151 (11) |
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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. 20555-0001 November 14, 1995 NRC INFORMATION
NOTICE 95-52: FIRE ENDURANCE
TEST RESULTS FOR ELECTRICAL
RACEWAY FIRE BARRIER SYSTEMS CONSTRUCTED
FROM 3M COMPANY INTERAM FIRE BARRIER MATERIALS
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 inform addressees
of the results of recent fire endurance
tests for electrical
raceway fire barrier systems constructed
from 3M Company Interam fire barrier materials.
It is expected that recipients
will review the information
for applicability
to their facilities
and consider this information, as appropriate, in their review of Interam fire barriers.Backaround
On April 20, May 17, and July 7, 1995, the NRC staff visited Omega Point Laboratories (OPL), San Antonio, Texas, to witness full-scale
fire endurance tests for electrical
raceway fire barrier systems constructed
from 3M Company Interam fire barrier materials.
These tests were sponsored
by Peak Seals Corporation (Peak Seals). Peak Seals informed the NRC staff that the test specimens
included in this test program were intended to represent
generic Interam fire barrier systems and that these test programs were conducted
in accordance
with Generic Letter (GL) 86-10, Supplement
1, 'Fire Endurance
Test Acceptance
Criteria for Fire Barrier Systems Used To Separate Redundant
Safe Shutdown Trains Within the Same Fire Area." The following
information
is based on observations
made by the NRC staff who witnessed
these fire tests.The NRC staff has not reviewed the test reports.Description
of Circumstances
1-Hour Fire Endurance
Tests The first test assembly included nominal 24-inch and 6-inch-wide
steel cable trays; 1-inch, 2-inch, 3-inch, and 5-inch-diameter
steel conduits;
a 2-inch diameter air drop; each was arranged in a U-shaped configuration;
and a 12-inch by 12-inch by 8-inch steel junction box. With regard to the 2-inch-diameter steel conduit, the Junction box was installed
in one of its vertical runs and the 2-inch diameter air drop was installed
in the other. These test specimens
did not include cable fill and were supported
by a common trapeze 9511080324- K4 //6t~zEzt-0
t f51(14 IN 95-52 November 14, 1995 support. They were protected
with three layers of Interam E53A fire barrier mat material.
Each layer was 7.6 mm [0.3 inch] thick.On April 20, 1995, OPL subjected
the test assembly to the test fire specified in American Society for Testing and Materials (ASTM) Standard E-119, "Fire Test of Building Construction
and Materials," for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. After the fire exposure, the test specimens
were subjected
to a fog-nozzle
hose stream test.The 24-inch-wide
cable tray; the 3-inch-, 2-inch-, and 1-inch-diameter
conduits;
and the air drop exceeded the temperature
rise acceptance
criteria of GL 86-10, Supplement
1, near the end of the 1-hour fire exposure.
None of the barriers burned through during the fire exposure nor were they breached by the hose stream. Table 1 (see Attachment
1) summarizes
the test specimen and fire barrier configurations
and the results of the April 20, 1995, test.The second test assembly included a 24-inch-wide
steel cable tray, 1-inch- and 5-inch-diameter
steel conduits, and a 2-inch-diameter
air drop. These test specimens
did not contain cables and were protected
with three layers of Interam E54A fire barrier mat material.
Each layer was 10 mm [0.4 inch]thick.On May 17, 1995, OPL subjected
the test assembly to the test fire specified
in ASTM Standard E-119 for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. After the fire exposure, it subjected
the test specimens
to a fog-nozzle
hose stream test. These 1-hour test specimens met the acceptance
criteria of Supplement
1 to GL 86-10. Table 2 (see Attachment
1) summarizes
the test specimen and fire barrier configurations
and the results of the May 17, 1995, test.3-Hour Fire Endurance
Test The third test assembly included nominal 24-inch- and 6-inch-wide
steel cable trays; nominal 1-inch-, 3-inch-, and 5-inch-diameter
steel conduits;
a 2-inch-diameter air drop; each was arranged in a U-shaped configuration;
and a nominal 12-inch by 12-inch by 8-inch steel junction box. The cable trays were filled with a single layer of mix cables. The cable trays, the 1-inch- and 3-inch-diameter
steel conduits, and the air drop were protected
with five layers of Interam E54A fire barrier mat material.
The 5-inch-diameter
conduit and the Junction box were protected
with six layers of Interam E54A fire barrier mat material.
Each layer was 10 mm [0.4 inch] thick.On July 7, 1995, OPL subjected
the test assembly to the test fire specified
in ASTM Standard E-119 for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. After the fire exposure, it subjected
the test specimens
to a fog-nozzle
hose stream test. The barriers did not burn through during the fire exposure, nor were they breached by the hose stream.There was no visible damage to the test specimen cables. However, all of the test specimens
exceeded the temperature
rise acceptance
criteria of GL 86-10, Supplement
1. Table 3 (see Attachment
1) summarizes
the test specimen and fire barrier configurations
and the results of the July 7, 1995 test.Discussion
Section 50.48 of Title 10 of the Code of Federal Regulations
requires that each operating
nuclear power plant must have a fire protection
plan that
IN 95-52 November 14, 1995 satisfies
General Design Criterion (GDC) 3 of Appendix A to 10 CFR Part 50.Fire protection
features required to satisfy GDC 3 include features to ensure that one train of systems necessary
to achieve and maintain shutdown conditions
is free of fire damage. One means of satisfying
this requirement
is to separate one safe shutdown train from its redundant
train with a fire-rated barrier. The level of fire resistance
required of the barrier, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, depends on the other fire protection
features in the fire area.The NRC issued guidance on acceptable
methods of satisfying
the regulatory
requirements
of GDC 3 in Branch Technical
Position (BTP) Auxiliary
and Power Conversion
Systems Branch (APCSB) 9.5-1, 'Guidelines
for Fire Protection
for Nuclear Power Plants"; Appendix A to BTP APCSB 9.5-1; BTP Chemical Engineering
Branch (CMEB) 9.5-1, "Fire Protection
for Nuclear Power Plants"; and GL 86-10,"Implementation
of Fire Protection
Requirements." These guidance documents state that the fire resistance
ratings of fire barriers should be established
in accordance
with National Fire Protection
Association (NFPA) Standard 251,"Standard
Methods of Fire Tests of Building Construction
and Materials" (1975), by subjecting
a representative
test specimen to a standard fire exposure.On March 25, 1994, the NRC issued Supplement
1 to GL 86-10 to (1) clarify the applicability
of the test acceptance
criteria in GL 86-10 to raceway fire barrier systems, (2) specify a set of fire endurance
test acceptance
criteria that are acceptable
for demonstrating
that fire barrier systems can perform the required fire-resistive
function and maintain the protected
safe shutdown train free of fire damage, (3) specify acceptable
options for hose stream testing, and (4) specify criteria for cable functionality
testing when a deviation
is necessary, such as when the fire barrier temperature
rise criteria are exceeded or the test specimen cables sustain visible damage.These positions
are incorporated
by the NRC staff in its review and evaluation
of the adequacy of fire endurance
tests and fire barrier systems proposed by licensees
or applicants
to satisfy existing NRC fire protection
rules and regulations.
Some temperatures
observed during the tests exceeded the maximum allowable temperature
acceptance
criteria of Supplement
1 to GL 86-10. In accordance
with this supplement, an engineering
evaluation
could be performed
to determine
the acceptability
of an in-plant Interam fire barrier that was bounded by a deviating
test specimen configuration.
Information
about such evaluations
can be found in Enclosure
2 of Supplement
1 to GL 86-10. By letter dated August 7, 1995 [accession
number 9509050173
], Peak Seals submitted
to the NRC staff additional
documentation
relating to the thermal performance
of the 3-hour fire barrier test specimens
for information.
1 NFPA adopted ASTM Standard E-119 as NFPA Standard 251.
IN 95-52 November 14, 1995 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 Regulation (NRR) project manager.fiel rector Division of Reactor Pr ram Management
Office of Nuclear Reactor Regulation
Technical
contacts:
Patrick M. Madden, NRR (301) 415-2854 Amarjit Singh, NRR (301) 415-1237 Attachments:
1. Tables 1, 2, and 3, Summaries
of Endurance
Tests 2. List of Recently Issued NRC Information
Notices
K>_Att__Lament
1 IN 9-5-52 November 14, 1995 Tnhla 1 mnrmarv nf Anril 20. 1995 Fire Endurance
Test Peak Seals -3M Company 1-Hour Interam Fire Barriers Allowable
single point unexposed-side
temperature
criterion
-399 F'Allowable
average unexposed-side
temperature
criterion
-324 OF (Shading shows temperatures
that exceeded, acceptance
criteria of GL 86-10 Supplement
1)TEST SPECIMEN THERMOCOUPLE
AVERAGE MAXIMUM REMARKS ILOCATIONS (OF)(F)}6" Cable tray Front side rail 262 338 Protected
with three layers of Interam E53A.Rear side rail J 262 337 Copper conductor Ila Met acceptance
criteria.24" Cable tray Front side rail Rear side rail Copper conductor Protected
with four layers of Interam E53A.Exceeded the maximum single point temperature
criterion
at 50X minutes and the average temperature
rise criterion
at 54X minutes.______________
.4 5" Conduit Conduit surface Copper conductor 1 277 1 370 I 217 275 3" Conduit Conduit surface Copper conductor 2" Conduit Conduit surface Copper conductor 1- Conduit Conduit surface Copper conductor 2" air drop Copper conductor Protected
with three layers of Interam E53A.Met acceptance
criteria.Protected
with three layers of Interarn E53A.Exceeded the maximum single point temperature
criterion
at 59 X minutes and the average temperature
rise criterion
at 53 X minutes.Protected
with three layers of Interam E54A.Exceeded the maximum single point temperature
criterion
at 55X minutes and the average temperature
rise criterion
at 55 minutes.Protected
with two layers of Interam E53A and an outer layer of Interam E54A.Exceeded maximum single point temperature
criterion
at 49X minutes and the average temperature
rise criterion
at 52 minutes._________________________________
I Protected
with three layers of Interam E54A.Exceeded average temperature
rise criterion
at 59 minutes._______ .-Junction box 2S7 311 Protected
with three layers of Interam E54A.Met acceptance
criteria.'Temperatures
measured during testing and the acceptance
temperatures
are presented
in aF in all Tables of this attachment
to minimize error and confusion.
Att.,,_ment
1 IN 95;-52 November 14, 1995 Table 2. Summary of May 17, 1995 Fire Endurance
Test Peak Seals -3M Company 1-Hour Interam Fire Barrier Allowable
single point unexposed-side
temperature
criterion
.405 OF Allowable
average unexposed-side
temperature
criterion
-330 OF TEST SPECIMEN THERMOCOUPLE
AVERAGE MAXIMUM REMARKS LOCATIONS (OF) (OF'24" Cable tray Front side rail 290 389 Protected
with three layers of 3M Interam E54A Rear side rail 301 354 Met acceptance
criteria.Copper conductor
22265 l_______________
5' Conduit Conduit surface 224 251 Protected
with three layers of E54A.Copper conductor
217 244 Met acceptance
criteria.1" Conduit Conduit surface 308 374 Protected
with three layers of E54A.Copper conductor
286 346 Met acceptance
criteria.2" Air drop Copper conductor
242 279 Protected
with three layers of Interam E54A.Met acceptance
criteria.
At lament 1 IN 95-52 November 14, 1995 Table 3. Summary of July 7. 1995 Fire Endurance
Test Peak Sea Allowable
single ;Allowable
averal (Shading shows temperature
TEST SPECIMEN THERMOCOUPLE
LOCATIONS 6" Cable tray Front side rail Rear side rail Copper conductor 24" Cable tray Front side rail Rear side rail Copper conductor 5" Conduit Conduit surface Copper conductor 3' Conduit Conduit surface Copper conductor 1" Conduit Conduit surface Copper conductor 2" Air drop Copper conductor Junction box Metal surface Is- 3M Company 3-Hour Interam Fire Barrier piInt unexposed-side
temperature
criterion
-407 OF ge unexposed-side
temperature
criterloon
-332 OF a that exceeded acceptance
criteria of GL 86-10. Supplement
1).AVERAGE ([F)I MAXIMUM (1F)I REMARKS Protected
with five layers of Interam E54A. Exceeded the maximum single point temperature
criterion
at 158 minutes and the average temperature
rise criterion
at 166 minutes.301 343 406 243 334 Protected
with five layers of Interam E54A. Exceeded the maximum single point temperature
criterion
at 176 minutes and the average temperature
rise criterion
at 167 minutes.Protected
with five layers of Interam E54A. Exceeded the maximum single point temperature
criterion
at 161 minutes and the average temperature
rise criterion
at 178 minutes..Protected
with five layers of Interam E54A. Exceeded the maximum single point temperature
criterion
at 148 minutes and the average temperature
rise criterion
at 152 minutes.Protected
with six layers of Interam E54A. Exceeded the maximum single point temperature
criterion
at 126 minutes and the sversge temperature
rise criterion
at 167 minutes..Protected
with five layers of Interam E54A. Exceeded the maximum single point temperature
criterion
and the average temperature
rise criterion
at 152 minutes..Protected
with six layers of Interam E54A. Exceeded the average temperature
rise criterion
at 165 minutes.
< ~tachment
2 IN 95-52 November 14, 1995 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 95-51 95-50 95-49 95-48 95-47 95-46 95-12, Supp. 1 95-45 95-44 Recent Incidents
Involving Potential
Loss of Control of Licensed Material Safety Defect in Gammamed 12i Bronchial
Catheter Clamping Adapters Seismic Adequacy of Thermo-Lag
Panels Results of Shift Staffing Study Unexpected
Opening of a Safety/Relief
Valve and Complications
Involving Suppression
Pool Cooling Strainer Blockage Unplanned, Undetected
Release of Radioactivity
from the Exhaust Ventilation
System of a Boiling Water Reactor Potentially
Nonconforming
Fasteners
Supplied by A&G Engineering
II, Inc.American Power Service Falsification
of American Society for Nondestructive
Testing (ASNT) Certificates
Ensuring Compatible
Use of Drive Cables Incorporating
Industrial
Nuclear Company Ball-Type
Male Connectors
10/27/95 10/30/95 10/27/95 10/10/95 10/04/95 10/06/95 10/05/95 10/04/95 09/26/95 All material and fuel cycle licensees.
All High Dose Rate Afterloader (HDR) Adapters.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 nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All Radiography
Licensees.
OL = Operating
License CP = Construction
Permit
IN 95-52 November 14, 1995 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 Regulation (NRR) project manager.orig /s/'d by DNCrutchfield
Dennis M. Crutchfield, Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
contacts: Patrick M. Madden, NRR (301) 415-2854 Amarjit Singh, NRR (301) 415-1237 Attachments:
1. Tables 1, 2, anm 2. List of Recentl, AWAS4 3, Summaries
of Endurance
Tests Issued NRC Information
Notices&&I--6'zp "'Ilke4-TechEd reviewed this document on 9/11/95 DOCUMENT NAME: 95-52.IN To ,eceive a copy of this document, Indicate In the box: *C' a Copy Without attachientenctoSurM
IE -Copy with attachmentlwclosure
IN' -No copy iOFFICE PECB:DRPM*
l C:PECB/DRPM*
I D/DRPV1J-n,1 A i NAME IJCarter IAEChaffee
DMCruVif!el
d DATE 09/28/95 11/02/95 111/ /95 OFFICIAL RECORD COPY
IN 95-xx November xx, 1995 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 Regulation (NRR) project manager.Dennis M. Crutchfield, Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
contacts:
Patrick M. Madden, NRR (301) 415-2854 Amarjit Singh, NRR (301) 415-1237 Attachments:
1. Tables 1, 2, and 3, Summaries
of Endurance
Tests 2. List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:\IN\3MIN
To mcev. a copy of Weh docunnt. inducate I the box: IC' -Copy without attachment/encloss
'Ew
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OFFICE SPLB:DSSA*
I ADM:PUB* PECB:DRPM*
I C:PER RRPM NAME ASingh Tech Editor JCarter/RLD
A~hOW DATE 09/28/95 109/11/95 l09/28/95 ti/2/g§PL3 OFFICE ID:DRPM/NRR
I II.N. .No copy!NAME 1DPMCrutchfield
JDATE I1 4 ! !J5I~~OFFICIAL RECORD COPY
IN 95-xx September
xx, 1995 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 Regulation (NRR) project manager.Dennis M. Crutchfield, Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
contacts: Patrick M. Madden, NRR (301) 415-2854 Amarjit Singh, NRR (301) 415-1237 Attachments:
1. Tables 1, 2, and 2. List of Recently 3, Summaries
of Endurance
Tests Issued NRC Information
Notices.or DOCUMENT NAME: G:\IN\3M I.I ( 'ff-To rete a copy o o docunwra j2 box: 'C' -Copy wfthout anachmnten
cosL 'E' -Copy with atchmentlenciosure
-No copy OFFICE SPLB:DSS\A
1, ] 'I ADM:PUB* I IP fTRPM I PECB/DRPM
Z I I C:PECB/DRPM
I NAME ASingh ) A Tech Editor IJZarter RJKi I.fT AChaffee DATE m 95 109/11/95
/95 O&5 OFFICE D:DRPM/NRR
I I NAME DMCrutchfleld
DATE 09/ /__ 95_I OFFICIAL RECORD COPY
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list | - Information Notice 1995-01, DOT Safety Advisory: High Pressure Aluminum Seamless and Aluminum Composite Hoop-Wrapped Cylinders (4 January 1995, Topic: Brachytherapy)
- Information Notice 1995-02, Problems With General Electric CR2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems With General Electric Cr2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems with General Electric CR2940 Contact Blocks in Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-03, Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition (18 January 1995, Topic: Packing leak)
- Information Notice 1995-04, Excessive Cooldown and Depressurization of the Reactor Coolant System Following Loss of Offsite Power (11 October 1996, Topic: Safe Shutdown, Shutdown Margin, Probabilistic Risk Assessment, Troxler Moisture Density Gauge)
- Information Notice 1995-05, Undervoltage Protection Relay Settings Out of Tolerance Due to Test Equipment Harmonics (20 January 1985)
- Information Notice 1995-06, Potential Blockage of Safety-Related Strainers by Material Brought Inside Containment (25 January 1995, Topic: Foreign Material Exclusion)
- Information Notice 1995-07, Radiopharmaceutical Vial Breakage During Preparation (27 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained With Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-09, Use of Inappropriate Guidelines and Criteria for Nuclear Piping and Pipe Support Evaluation and Design (31 January 1995)
- Information Notice 1995-10, Potential for Loss of Automatic Engineered Safety Features Actuation (3 February 1995)
- Information Notice 1995-11, Failure of Condensate Piping Because of Erosion/Corrosion at Flow-Straightening Device (24 February 1995)
- Information Notice 1995-12, Potentially Nonconforming Fasteners Supplied by A&G Engineering II, Inc (21 February 1995)
- Information Notice 1995-13, Potential for Data Collection Equipment to Affect Protection System Performance (24 February 1995)
- Information Notice 1995-14, Susceptibility of Containment Sump Recirculation Gate Valves to Pressure Locking (28 February 1995)
- Information Notice 1995-15, Inadequate Logic Testing of Safety-Related Circuits (7 March 1995)
- Information Notice 1995-16, Vibration Caused by Increased Recirculation Flow in a Boiling Water Reactor (9 March 1995)
- Information Notice 1995-17, Reactor Vessel Top Guide and Core Plate Cracking (10 March 1995, Topic: Safe Shutdown)
- Information Notice 1995-18, Potential Pressure-Locking of Safety-Related Power-Operated Gate Valves (15 March 1995)
- Information Notice 1995-19, Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch Mechanism (22 March 1995)
- Information Notice 1995-20, Failures in Rosemount Pressure Transmitters Due to Hydrogen Permeation Into Sensor Cell (22 March 1995)
- Information Notice 1995-21, Unexpected Degradation of Lead Storage Batteries (20 April 1995)
- Information Notice 1995-22, Hardened or Contaminated Lubricant Cause Metal-Clad Circuit Breaker Failures (21 April 1995)
- Information Notice 1995-23, Control Room Staffing Below Minimum Regulatory Requirements (24 April 1995)
- Information Notice 1995-24, Summary of Licensed Operator Requalification Inspection Program Findings (25 April 1995, Topic: Job Performance Measure, License Renewal)
- Information Notice 1995-25, Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit (11 May 1995)
- Information Notice 1995-26, Defect in Safety-Related Pump Parts Due to Inadequate Treatment (31 May 1995)
- Information Notice 1995-27, NRC Review of Nuclear Energy Institute, Thermo-Lag 330-1 Combustibility Evaluation Methodology Plant Screening Guide. (31 May 1995, Topic: Safe Shutdown, Fire Barrier, Exemption Request, Fire Protection Program)
- Information Notice 1995-28, Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites (5 June 1995, Topic: Safe Shutdown, Tornado Missile, Safe Shutdown Earthquake, Earthquake)
- Information Notice 1995-29, Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems (7 June 1995, Topic: Nondestructive Examination)
- Information Notice 1995-30, Susceptibility of Low-Pressure Coolant Injection Valves to Pressure Locking (3 August 1995, Topic: Hydrostatic, Power-Operated Valves)
- Information Notice 1995-31, Motor-Operated Valve Failure Caused by Stem Protector Pipe Interference (9 August 1995)
- Information Notice 1995-32, Thermo-Lag 330-1 Flame Spread Test Results (10 August 1995, Topic: Fire Barrier)
- Information Notice 1995-33, Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3 (23 August 1995)
- Information Notice 1995-34, Air Actuator and Supply Air Regulator Problems in Copes-Vulcan Pressurizer Power-Operated Relief Valves (25 August 1995)
- Information Notice 1995-35, Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation (28 August 1995)
- Information Notice 1995-36, Potential Problems with Post-Fire Emergency Lighting (29 August 1995, Topic: Safe Shutdown, Emergency Lighting, Exemption Request)
- Information Notice 1995-37, Inadequate Offsite Power System Voltages During Design-Basis Events (7 September 1995)
- Information Notice 1995-38, Degradation of Boraflex Neutron Absorber in Spent Fuel Storage Racks (8 September 1995)
- Information Notice 1995-39, Brachytherapy Incidents Involving Treatment Planning Errors (19 September 1995, Topic: Brachytherapy)
- Information Notice 1995-40, Supplemental Information to Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes. (20 September 1995, Topic: Hydrostatic, Nondestructive Examination, Brachytherapy)
- Information Notice 1995-41, Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam Generators (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-42, Commission Decision on Resolution of Generic Issue 23, Reactor Coolant Pump Seal Failure. (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-43, Failure of Bolt-Locking Device on Reactor Coolant Pump Turning Vane (28 September 1995, Topic: Brachytherapy)
- Information Notice 1995-44, Ensuring Compatible Use of Drive Cables Incorporating Industrial Nuclear Company Ball-Type Male Connectors (26 September 1995, Topic: Brachytherapy)
- Information Notice 1995-45, American Power Service Falsification of American Society for Nondestructive Testing Certificates (4 October 1995, Topic: Brachytherapy)
- Information Notice 1995-46, Unplanned, Undetected Release of Radioactivity from the Exhaust Ventilation System of a Boiling Water Reactor (6 October 1995, Topic: Brachytherapy)
- Information Notice 1995-47, Unexpected Opening of a Safety/Relief Valve & Complications Involving Suppression Pool Cooling Strainer Blockage (30 November 1995)
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