Engineering Basis for Structural Integrity of Raceway Supports Associated W/1 H Rated Cable Protective Envelope Sys Upon Exposure to FireML20078F811 |
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Comanche Peak ![Luminant icon.png](/w/images/d/d7/Luminant_icon.png) |
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09/27/1983 |
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TEXAS UTILITIES SERVICES, INC. |
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ML20078F801 |
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References |
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NUDOCS 8310110177 |
Download: ML20078F811 (8) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20211M2981999-08-0606 August 1999 Rev 1 to CPSES Fuel Storage Licensing Rept, CPSES Credit for Soluble Boron & Expansion of Spent Fuel Storage Capacity, Consisting of Revised Title Page and 4-1 ML20210J9391999-06-30030 June 1999 CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20205R5701999-04-14014 April 1999 Rev 6 to ER-ME-067, TU Electric Engineering Rept,Evaluation of Thermo-Lag Fire Barrier Sys ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML20199J5391998-02-0202 February 1998 CPSES Commitment Matl Change Evaluation Rept 0002 for 960202-970801 ML20198Q7181997-10-24024 October 1997 Rev 5 to ER-ME-067, Evaluation of Thermo-Lag Fire Barrier Systems ML20137D3601997-03-20020 March 1997 Engineering Self-Assessment Rept ML20129F6991996-10-25025 October 1996 Justification for SPC 1986 LBLOCA Evaluation Model W/Interim Adjustment for Non-Physical Behavior ML20100F2761996-02-13013 February 1996 Rev 0 of Engineering Rept, Resolution of NRC GL 95-07 'Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves.' ML20116M4021996-02-0101 February 1996 Commitment Matl Change Evaluation Rept 0001 for 941101- 960201 ML20095K5411995-12-18018 December 1995 Nonproprietary Small Break LOCA Analysis Methodology ML20094P7971995-11-22022 November 1995 Rev 0 to CPSES Risk-Based IST Program Risk Ranking Determination Study ML20094P7821995-11-22022 November 1995 CPSES Risk-Based IST Program Risk Ranking Determination Study Summary Rept ML20094P4231995-09-29029 September 1995 Pyrolysis Gas Chromatography Analysis of 10 Thermo-Lag Fire Barrier Samples ML20085N2911995-06-21021 June 1995 Individual Plant Exam of External Events for Severe Accident Vulnerabilities TXX-9432, Rev 0 to CPSES Fuel Storage Licensing Rept,Cpses Expansion of Spent Fuel Storage Capacity1994-12-0909 December 1994 Rev 0 to CPSES Fuel Storage Licensing Rept,Cpses Expansion of Spent Fuel Storage Capacity ML20097A3821994-08-19019 August 1994 Individual Plant Exam of External Events,Seismic,Cpses ML20069M8761994-06-10010 June 1994 Engineering Rept Evaluation of Unit 1 & Unit 2 Thermo-Lag Configurations ML20064M6081994-03-21021 March 1994 Engineering Rept Evaluation of Thermo-Lag Fire Barrier Sys ML20059F5431993-10-0505 October 1993 Engineering Rept, Evaluation of Fir Endurance Test Results Related to Cable Functionality in 1-1/2 & 2 Inch Conduits ML18010B0841993-05-0505 May 1993 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20127K8121993-01-19019 January 1993 Rev 0,to Evaluation of Unit 2 Thermo-Lag Configurations ML20126G2121992-12-23023 December 1992 Rev 2 to ER-ME-067, Evaluation of Thermo-Lag Fire Barrier Systems ML20126C0421992-12-18018 December 1992 Suppl 6 to Human Factors Control Room Design Review of Comanche Peak Steam Electric Station ML20126A3621992-12-15015 December 1992 Rev 3 to Receipt,Dispensing,Quality & Insp Requirements for Thermo-Lag Fire Barrier Matls ML18010A9521992-11-30030 November 1992 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20116C9511992-10-27027 October 1992 Individual Plant Exam Submittal:Comanche Peak Steam Electric Station Vol II:Back-End Analysis ML20115D2241992-09-29029 September 1992 Rev 1 to HI-92880, Criticality SE of Comanche Peak Fuel Storage Facilities W/Fuel of 5% Enrichment ML20127C8291992-09-0808 September 1992 Rev 1 to Interim Engineering Rept, Evaluation of Thermo-Lag Fire Barrier Sys ML20114B8051992-09-0101 September 1992 Suppl 5 to Human Factors Control Room Design Review of Comanche Peak Steam Electric Station ML20114C6101992-08-31031 August 1992 Individual Plant Exam Comanche Peak Steam Electric Station Vol 1:Front-End Analysis ML20105A7821992-08-14014 August 1992 Engineering Rept on Thermo-Lag 330-1 Fireproofing Coating Thicknesses Required for 1 & 2 Hour Fire Ratings for Various Structural Steel Members Used by Texas Utils Svcs,Inc ML20105A8471992-08-0606 August 1992 Rev 0 to Comanche Peak Steam Electric Station Unit 2 Engineering Bwip Check Valve 2AF-0083 Failure Investigation ML20116C9621992-07-16016 July 1992 Review of IPE Level 2 Draft Repts for Cpses ML20078H1581992-06-19019 June 1992 CPSES Thermo-Lag Barrier Applications Thermo-Lag Fire Test Conduit & J-Box Test Assemblies. Preliminary Test Results ML20095H2411992-04-13013 April 1992 Validation Efforts for Comanche Peak Steam Electric Station Unit 2 ML20094P3371992-03-26026 March 1992 Control Room Simulator 10CFR55 Certification Initial Rept TXX-9200, RHR Line Summary Rept1992-03-23023 March 1992 RHR Line Summary Rept ML20086E3861991-10-31031 October 1991 Pressurizer Surge Line Transient Justification ML20079D0481991-06-21021 June 1991 Engineering Rept, Testing & Analysis of Commercial-Grade Swing Arms in Borg-Warner Check Valves, June 1991 ML20077E0271991-05-31031 May 1991 Methodology for Reactor Core Response to Steamline Break Events ML20217C4601991-05-31031 May 1991 Reactivity Anomaly Events Methodology ML20073Q8291991-05-17017 May 1991 Small Break LOCA Analysis Methodology ML20084V1401991-03-31031 March 1991 Safety Evaluation for Operation of Comanche Peak Unit 1 W/ Positive Moderator Temp Coefficient ML20079D0571991-03-31031 March 1991 Final Rept on Analysis of Check Valve Swing Arms, Mar 1991 ML20066F4331991-01-31031 January 1991 Draft Analysis of Flow Stratification in Surge Line of Comanche Peak Reactor ML20066L0691990-12-31031 December 1990 Large Break LOCA Analysis Methodology ML20066B2391990-12-31031 December 1990 Control Rod Worth Analysis ML20067B1291990-12-24024 December 1990 Suppl 1 to TUE-1 DNB Correlation ML20062D9041990-11-12012 November 1990 Unit One Loose Parts Monitoring Sys Special Rept 1999-08-06
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E8021999-10-0707 October 1999 CPSES Unit 1 Cycle 8 Colr ML20217G4151999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Cpses,Units 1 & 2 ML20212F7671999-09-24024 September 1999 SER Granting Relief Request C-4 Pursuant to 10CFR50.55a(g)(6)(i) for Unit 2,during First 10-year ISI Interval & Relief Requests B-15,B-16 & B-17 Pursuant to 10CFR50.55a(g)(6)(i) ML20216J5701999-09-16016 September 1999 Rev 2 to CPSES Unit 2 Cycle 5 Colr TXX-9920, Monthly Operating Repts for Aug 1999 for Cpses.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Cpses.With ML20211M2981999-08-0606 August 1999 Rev 1 to CPSES Fuel Storage Licensing Rept, CPSES Credit for Soluble Boron & Expansion of Spent Fuel Storage Capacity, Consisting of Revised Title Page and 4-1 ML20210U4081999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Cpses,Units 1 & 2 ML20210D8321999-07-23023 July 1999 Safety Evaluation Accepting Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20209H7661999-07-15015 July 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Comanche Peak Steam Electric Station,Units 1 & 2 ML20209H2721999-07-0909 July 1999 2RF04 Containment ISI Summary Rept First Interval,First Period,First Outage ML20209H2631999-07-0909 July 1999 2RF04 ISI Summary Rept First Interval,Second Period,Second Outage ML20209G7501999-07-0808 July 1999 SER Finding That Licensee Individual Plant Exam of External Events Complete with Regard to Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given Design, Operation & History of Comanche Peak Steam Electric Station ML20196L0191999-07-0808 July 1999 Safety Evaluation Granting Request Relief B-6 (Rev 2),B-7 (Rev2),B-12,B-13,B-14 & C-9,pursuant to 10CFR50.55a(g)(6)(i).Technical Ltr Rept Also Encl ML20210J9391999-06-30030 June 1999 CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20209G0801999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Cpses,Units 1 & 2 ML20196J0621999-06-29029 June 1999 Safety Evaluation Supporting Proposed Changes to Emergency Plan Re Licenses NPF-87 & NPF-89 Respectively ML20195G5141999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Comanche Peak Steam Electric Station,Units 1 & 2.With ML20216E0711999-05-21021 May 1999 1999 Graded Exercise - Comanche Peak Steam Electric Station ML20206Q0091999-05-14014 May 1999 Safety Evaluation Accepting GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Comanche Peak Electric Station,Unit 1 ML20206H2061999-05-0606 May 1999 SER Accepting Exemption to App K Re Leading Edge Flowmeter for Plant,Units 1 & 2 ML20196L2241999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Cpses,Units 1 & 2 ML20205R5701999-04-14014 April 1999 Rev 6 to ER-ME-067, TU Electric Engineering Rept,Evaluation of Thermo-Lag Fire Barrier Sys ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205J7831999-04-0101 April 1999 Rev 0 to ERX-99-001, CPSES Unit 2 Cycle 5 Colr ML20205N3101999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Cpses,Units 1 & 2 ML20204H6371999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Comanche Peak Units 1 & 2 ML20205N1481999-02-28028 February 1999 Corrected Monthly Operating Rept for Feb 1999 for CPSES, Units 1 & 2 ML20203A4881999-02-0303 February 1999 Safety Evaluation Granting Requests for Relief B-3 - B-6,C-2 & C-3 for Plant,Unit 2 ML20210J9201999-02-0101 February 1999 CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802- 990201 ML20202D0101999-01-27027 January 1999 Safety Evaluation Supporting First 10-yr Interval ISI Program Plan Requests for Relief B-9,B-10 & B-11 for CPSES, Unit 1 ML20199E9961998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Cpses,Units 1 & 2 ML20207D6091998-12-31031 December 1998 1998 Annual Operating Rept for Cpses,Units 1 & 2. with ML20197K2371998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Cpses,Units 1 & 2 ML20195F3161998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Cpses,Units 1 & 2 ML20154M8841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Cpses,Units 1 & 2 ML20154B5741998-09-30030 September 1998 Safety Evaluation Re Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Motor-Operated Valves. Licensee Has Established Acceptable Program ML20151W0361998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Cpses,Units 1 & 2. with ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML20237C4061998-08-14014 August 1998 Safety Evaluation Supporting Request to Implement Risk Informed IST Program ML20237C6721998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Cpses,Units 1 & 2 ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20236R0711998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Cpses,Units 1 & 2 ML20249B2581998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Cpses,Units 1 & 2 ML20248A1671998-05-22022 May 1998 Interim Part 21 Re Enterprise DSR-4 & DSRV-4 Emergency diesel.Post-installation Testing Revealed,High Em/Rfi Levels Affected New Controllers,Whereas Original Controllers Were unaffected.Follow-up Will Be Provided No Later than 980731 ML20247G3241998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Cpses,Units 1 & 2 ML20216B8661998-04-0101 April 1998 Rev 0 to ERX-98-001, CPSES Unit 1 Cycle 7 Colr ML20216J3061998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Cpses,Units 1 & 2 ML20216J1861998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Comanche Peak Steam Electric Station ML20197A6951998-02-24024 February 1998 Inservice Insp Summary Rept,First Interval,Second Period, First Outage ML20199J5391998-02-0202 February 1998 CPSES Commitment Matl Change Evaluation Rept 0002 for 960202-970801 1999-09-30
[Table view] |
Text
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Engineering Basis for Structural Integrity of Raceway Supports Associated With One Hour Rated Cable Protective Envelope Systems upon Exposure to Fire i
Texas Utilities Services Inc.
l Comanche Peak (SES)
September 27, 1983 l
l l
0310110177 031004 I
hDRADOCK 05000445 1 PDR
4 t It is the position of CPSES that cable tray structural supports used on cable trays with one hour fire rated protective envelopes, (1) will not be exposed to fires of sufficient duration and temperatures to cause failure of the support, and (2) because of the seismic spacing and load carrying ability of the supports, even a failure of a support can be tolerated without loss of the essential cables.
The basis for the one hour rating of the protective cable envelope systems is to meet the NRC requirements as clarified by comments to 10CFR50, Appendix R, "...the activation of an automatic... suppression q system does not occur until sufficient... heat has been developed by the i fire. Therefore, the commission is requiring a one (1) hour barrier to ensure that the fire damage will be limited to one train until the fire is extinguished."1 This one hour barrier is designed to provide
! interim protection of cables until suppression systems can bring the fire under control.
CPSES accepts this NRC position for cables since the failure mode of cable (insulation degradation with resultant grounds) can occur very rapidly, especially in the presence of even relatively small quantities of transient combustibles. It is concievable that such failures could occur prior to initiation of automatic suppression and thus it is prudent to protect cables until suppression systems are actuated.
Cable tray structural supports, however, do not have the same failure mode and, for a given fire, require a much longer duration and higher temperatures to fail than do the unprotected cables. Thus what may be reasonable and prudent for protection of cables is not necessarily reasonable and prudent for the cable tray structural supports.
Three aspects of the Comanche Peak (SES) plant design ensure that structural integrity will be maintained during and after a fire; (1) the fire detection and automatic water suppression system, (2) the seismic support design criteria, and (3) the plant configuration.
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- 1) Automatic water suppression and fire detection. ,
The water suppression system for CPSES is designed hydraulically by Grinnell Fire Protection Special Hazards to meet the requirements of NFPA 13 and NFPA 15. The area sprinkler coverage is typically installed at three separate elevations in the areas of the plant where protection is provided. Area sprinklers are installed at the ceiling level to sense heated gases of combustion, limit the spread of these gases, and control the spread of the fire in combustible materials. Area sprinklers are also installed beneath congestion (i.e., ducts, pipe) but above insitu combustibles (cable jacket, insulation) and area sprinklers are installed below all congestion to provide protection against transient combustibles. In addition to area coverage, special hazard sprinklers are installed where horizontal cable tray configurations are stacked more than three high; these sprinklers are positioned to direct water individually on each tray in these concentrated configurations. The heads are designed to actuate at temperatures of 175 to 2120F based on ambient plant operating conditions. The effectiveness of this design is illustrated by preliminary test results presented in NUREG/CR-2607, pg. 46-51.2 The times required to sense and even extinguish IEEE/383 qualified cable fires in the Sandia tests were 3
significantly less than one hour.
Rapid Fire detection also provides an effective manual backup to the automatic suppression systems.
It is apparent that actuation of automatic suppression will not only prevent structural support damage, but in all probability extinguish the firc.
- 2) Seismic design of supports.
The factors important to maintaining structural integrity in a fire
, include the structural support stress level and the steel temperature. The cable raceway support systems at CPSES are i
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i designed to carry load combinations that include deadweight and seismic loads based on 60% of minimum yield stress of A-36 steel.
The tray supports are typically four to six inch channel installed with approximately eight feet spacing. The seismic design requires a load carrying capability four to eight times the deadweight load
- of a fully loaded raceway. Thus the stress level in these supports is very low.
The temperature of the support member will be lower than the
- surrounding gas temperature and is a function of the ability of the steel to conduct and radiate heat away. Heat removal is in turn a function of the surface to volume ratio4and the cross-sectional area of the member. Because of the seismic design, CPSES supports
! have better heat removal capabilities than typical non-seismic i
supports and thus will be at a lower temperature. Al so, critical temperature (maximum temperature without failure) increases with decreasing stress. Again, because of the seismic design of the supports with its resultant low stresses, a higher critical temperature is expected. Accepted critical temperatures for ASTM i A36 steel in the usage anticipated at CPSES ranges from 1000 F5 to 11000 F.6
- 3) Plant Configuration The characteristics of a fire are influenced by four factors related to plant configuration: a) combustible loading (fuel / area),
b) ventilation (natural or forced draft), c) compartment geometry
' and thermal properties of construction, and d) the combustion '
characteristics of the fuel (rate of heat release).
To establish a point of reference, these factors will be compared to those seen in an ASTM E-119 fire. The ASTM E-119 fire was chosen because it is extremely conservative and a fire of this severity is not expected in those areas where one hour fire barriers are used.
a) The combined insitu and transient combustible loading at C?SES ranges from 250 to 90,000 Btu /ft2 (as defined in the Fire Hazard Analysis) and typically is significantly less than that used in the E-119 fire. In the most severe case (full burnout), fire duration is less than 60 minutes and is less severe than the E-119 time-temperature curve. Full burnout is not anticipated, however, due to the presence of sprinkler protection and the effect of the other three factors that inhibit fire development compared to the E-119 fire as discussed below.
b) The ventilation system at CPSES is designed to isolate fires by use of fire dampers in the ducts at fire barriers. This design generates a ventilation controlled fire and tends to slow the heat release compared to an optimum ventilated fire.
c) Compartment geometry and the thermal properties of construction.
The typical E-119 furnance is designed to efficiently utilize the burned fuel, reflecting heat back into the enclosed compartment furnance space (approximately 8'x10'x9') and effectively insulate the furnance. Heat sinks consists only of the test assembly. By contrast CPSES compartments are large and have 20 ft. ceilings.
The concrete surface of the ceilings and floors absorb over 80% of the incident radiant heat.9 The installed cable trays are generally more then 6 feet from ceiling / wall corners so radiant energy reflection does not play a significant role in fire devel opment. The TSI one hour barriers used on the protected cable raceways utilizes a sublimation heat removal process and thus provides an additional heat sink. The coated raceways also act as a heat shield for portions of the structural support. The overall effect of plant geometry is the reduction of temperature l by dissipation and heat removal. i l
d) Combustion characteristics of the fuel - The insitu combustibles are the dominant loading in areas where one hour rated protective envelopes are utilized. The CPSES plant design incorporates l l
1
r-features to limit the potential for and the severity of fires.
Interior finish items have generally been limited to ASTM E84 valves of 25. The primary insitu combustible material is IEEE 383 qualified CPE and CSPE jacketed cables which by nature of its construction is a slow heat release material and resists progagation of flames due to the high radiant flux levels required to achieve ignition. Critical heat flux for cross linked PE is 200% higher than non IEEE-383 qualified cable.II This tends to localize the effects of the fire to a limited number of structural supports and reduces even these effects in severity to a level well below those experienced in an ASTM E-119 fire. Al so, since the structural supports of concern are associated with cable raceways already protected with one hour rated barriers, the local insitu combustible loading is generally significantly lower than the average loading of the compartment. Combustibles enclosed in one hour barriers are not considered part of the combustible loading.
In summary, it is the CPSES position that the structural integrity of the cable raceway supports is assured in a fire environment without the need for supplemental fire resistant coatings. Integrity is assured because of the limited nature and duration of the potential fires and because of the cooling and suppression effects of automatic sprinkler systems. Thi s position is consistant with: the Nuclear Fire Protection Group's t
I interpretation of the 10CFR50 Appendix R requirements; the utility l
industry practice of not coating other similar steel supports (pipe, l platforms, HVAC, etc.); and, the results of the B&B fire test of the HEMYC system where non-seismic supports (2-1/2" x 2-1/2" x 1/4") without fire resistant coating did not structurally fail in an ASTM E-119 fire.12 l
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REFERENCES
- 1. " Fire Protection Program for Operating Nuclear Power Plants",
10CFR50, Appendix R, 76602 Federal Register, Vol. 45, No. 225, November 1980.
- 2. D. A. Dube, " Fire Protection Research Program for the U.S.
> Nuclear Regulatory Commission 1975-1981" SAND 82-0431, NUREG/CR-260/, Sandia National Laboratories, Albuquerque, N.M.,
- April 1983.
- 3. D. F. Boring, J. C. Spence, W. G. Wells, Fire Protection Through Modern Building Codes, fifth edition, American Iron and Steel Institute, Washington, D.C., 1981.
- 4. Manual of Steel Construction, seventh edition, American Institute of Steel Construction, Inc. New York, 1970 and 1973.
i
- 5. Boring, pg. 37.
- 6. Fire Protection Handbook, fourteenth edition, Gordon P. McKinnon
< Editor, National Fire Protection Association, Boston, Mass.1976, j pg. 6-56
- 7. Boring, pg. 38.
- 8. D. A. Dube, pg. 88.
- 9. Mark's Standard Handbook for Mechanical Engineers, seventh edition. T. Baumeister, Editor, McGraw-Hill Book Co., New York, l pg. 4-110, fig.1,1967.
- 10. Ibid, pg. 71.
) 11. D. A. Dube, pgs. 68-71.
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- 12. " Fire Test for Electrical Cable Tray Protection with the HEMYC System" Fire Test Report, B8B Insulation, Inc. , Houston, TX. ,
October 21, 1981.
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