ML20133A024: Difference between revisions

From kanterella
Jump to navigation Jump to search
StriderTol Bot insert
 
StriderTol Bot change
 
(One intermediate revision by the same user not shown)
Line 19: Line 19:


=Text=
=Text=
{{#Wiki_filter:,
{{#Wiki_filter:bb July 22,1985 Docket No. 50-289 DI_STRTRUTION WRussell a
July 22,1985                                                     bb Docket No. 50-289                                                                           DI_STRTRUTION                   WRussell a   w L PDR                           ACRS-10 Mr. Henry D. Hukill, Vice President                                                         ORB #4 Rdg                     RIngram and Director - TMI-1                                                                     HThompson                       0 Thompson GPU Nuclear Corporation                                                                     OELD                           JThoma P. O. Box 480                                                                               EJordan                         Gray File Middletown, Pennsylvania 17057                                                               E81ackwood                     H0rnstein RFerguson                       TWambach
w L PDR ACRS-10 Mr. Henry D. Hukill, Vice President ORB #4 Rdg RIngram and Director - TMI-1 HThompson 0 Thompson GPU Nuclear Corporation OELD JThoma P. O. Box 480 EJordan Gray File Middletown, Pennsylvania 17057 E81ackwood H0rnstein RFerguson TWambach


==Dear Mr. Hukill:==
==Dear Mr. Hukill:==
DKubicki                       Glainas In our Safety Evaluation Report dated June 4, 1983, we granted exemptions to the technical requirements of Appendix R to 10 CFR 50. The exemptions were based, in part, on your comitment to install 1-hour fire-rated barriers around certain shutdown-related cables. By letter dated February 14, 1984, you proposed using fire-rated cable in lieu of fire barriers for certain applications in the plant. At our request, your letter dated February 11, IS85 provided a " worst-case" sample exemption request for one location in the plant to enable us to evaluate the viability of the proposal. The example also requested exemption for the protection of some barrier supports, but we have evaluated only the exemption for " fire-rated" cable. Enclosed is our sample evaluation of this information.
DKubicki Glainas In our Safety Evaluation Report dated June 4, 1983, we granted exemptions to the technical requirements of Appendix R to 10 CFR 50. The exemptions were based, in part, on your comitment to install 1-hour fire-rated barriers around certain shutdown-related cables. By {{letter dated|date=February 14, 1984|text=letter dated February 14, 1984}}, you proposed using fire-rated cable in lieu of fire barriers for certain applications in the plant. At our request, your letter dated February 11, IS85 provided a " worst-case" sample exemption request for one location in the plant to enable us to evaluate the viability of the proposal. The example also requested exemption for the protection of some barrier supports, but we have evaluated only the exemption for " fire-rated" cable. Enclosed is our sample evaluation of this information.
Based on our sample evaluation, we conclude that the use of Rockbestos
Based on our sample evaluation, we conclude that the use of Rockbestos
;        " fire-rated" cable in the Fuel Handling Building Fire Zone FH-FZ-1, can be shown to provide an equivalent level of safety to that obtained by installing 1-hour fire-rated barriers around vulnerable shutdown-related cables in this area. However, additional information should be provided in support of the actual exemption requests as indicated in our evaluation. Exemption requests, with supporting information, should be prepared for each fire area
" fire-rated" cable in the Fuel Handling Building Fire Zone FH-FZ-1, can be shown to provide an equivalent level of safety to that obtained by installing 1-hour fire-rated barriers around vulnerable shutdown-related cables in this area. However, additional information should be provided in support of the actual exemption requests as indicated in our evaluation.
<      in which fire-rated cable is being considered including the Fuel Handling C
Exemption requests, with supporting information, should be prepared for each fire area in which fire-rated cable is being considered including the Fuel Handling Building. We also request that you provide a schedule for submitting these C
Building. We also request that you provide a schedule for submitting these exemption requests.
exemption requests.
Sincerely.
Sincerely.
                                                                                    %m % x ca n
%m % x ca n
                                                                                      ) a&\                       R.a '
) a&\\
Joh. c. f.<0t, Chief Operating Reactors Branch #4 Division of Licensing cc: See next page 32rr hdor   '
R.a '
g                                                                  /
Joh. c. f.<0t, Chief Operating Reactors Branch #4 Division of Licensing cc: See next page 32rr hdor g
ORB                   ORB #4:DL                   ORB # 'DL                               CH   DE                 CHEM:DE mpson;cf         JIFora                       JSt                                     RFe guson                 VBenaroya 1/fr/85 7                  7//9/85                     7/                     _
/
7/g85                     7/W5 8508050306 850722
ORB ORB #4:DL ORB # 'DL CH DE CHEM:DE mpson;cf JIFora JSt RFe guson VBenaroya 1/fr/85 7//9/85 7/
  !          PDR       ADOCK 05000289 1
7/g85 7/W5 7
F                         PDR
8508050306 850722 PDR ADOCK 05000289 1
    , <,        ,-ee- 4,-.,e-       ,,,---,er ,e, - , , - - - - - , . - - - -      ---r - - - _ , ,    , , - - - - . .en.~ ..  . - - - - - -    ---,r
F PDR
,-ee-4,-.,e-
,,,---,er
,e,
---r
.en.~
---,r


Mr. Henry D. Hukill                       Three Mile Island Nuclear Station GPU Nuclear Corporation                   Unit No I cc:
Mr. Henry D. Hukill Three Mile Island Nuclear Station GPU Nuclear Corporation Unit No I cc:
Mr. R. J. Toole                     Mr. Richard Conte 0&M Director, TMI-1                 Senior Resident Inspector (TMI-1)
Mr. R. J. Toole Mr. Richard Conte 0&M Director, TMI-1 Senior Resident Inspector (TMI-1)
GPU Nuclear Corporation             U.S.N.R.C.
GPU Nuclear Corporation U.S.N.R.C.
Middletown, Pennsylvania 17057     P.O. Box 311 Middletown, Pennsylvania 17057 Richard J. McGoey Manager, PWR Licensing GPU Nuclear Corporation             Regional Administrator, Region I 100 Interpace Parkway               U.S. Nuclear Regulatory Commission Parsippany, New Jersey 70754       631 Park Avenue King of Prussia, Pennsylvania   19406 Mr. C. W. Smyth TMI-I Licensing Manager             Mr. Robert B. Borsum GPU Nuclear Corporation             Babcock & Wilcox P. O. Rox 480                       Nuclear Power Generation Division Middletown, Pennsylvania 17057     Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 G. F. Trowbridge, Esq.
Middletown, Pennsylvania 17057 P.O. Box 311 Middletown, Pennsylvania 17057 Richard J. McGoey Manager, PWR Licensing GPU Nuclear Corporation Regional Administrator, Region I 100 Interpace Parkway U.S. Nuclear Regulatory Commission Parsippany, New Jersey 70754 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. C. W. Smyth TMI-I Licensing Manager Mr. Robert B. Borsum GPU Nuclear Corporation Babcock & Wilcox P. O. Rox 480 Nuclear Power Generation Division Middletown, Pennsylvania 17057 Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 G. F. Trowbridge, Esq.
Shaw, Pittman, Potts & Trowbridge   Governor's Office of State Planning 1800 M Street, N.W.                   and Development Washington, D.C. 20036             ATTN:   Coordinator, Pennsylvania State Clearinghouse Ivan W. Smith, Esq., Chairman       P. O. Box 1323 Atomic Safety and Licensing Board   Harrisburg, Pennsylvania 17120 U.S. Nuclear Regulatory Commission Washington, D.C. 20555           Mr. Earl B. Hoffman Dauphin County Commissioner Sheldon J. Wolfe, Esq., Chairman   Dauphin County Courthouse Atomic Safety and Licensing Board   Front and Market Streets U.S. Nuclear Regulatory Commission Harrisburg, Pennsylvania 17101 Washington, D.C. 20555 Dauphin County Office of Emergency Mr. Gustave A. Linenberger, Jr.       Preparedness Atomic Safety and Licensing Board   Court House, Room 7 U.S. Nuclear Regulatory Comissjon   Front and Market Streets Washington, D.C. 20555           Harrisburg, Pennsylvania 17101 Dr. James Lamb, III                 Mr. David D. Maxwell, Chairman Administrative Judge               Board o'f . Supervisors 313 Woodhaven Road                 Londonderry Township Chapel Hill, North Carolina   17514 FRD#1 - Geyers Church Road Middletown, Pennsylvania 17057 Mr. David Hetrick Administrative Judge               Mr. Thomas M. Gerusky, Director Professor of Nuclear Energy         Bureau of Radiation Protection University of Arizona               Pennsylvania Department of Tucson, Arizona 85721                 Environmental Resources P. O. Box 2063 Harrisburg, Pennsylvania 17120
Shaw, Pittman, Potts & Trowbridge Governor's Office of State Planning 1800 M Street, N.W.
and Development Washington, D.C.
20036 ATTN:
Coordinator, Pennsylvania State Clearinghouse Ivan W. Smith, Esq., Chairman P. O. Box 1323 Atomic Safety and Licensing Board Harrisburg, Pennsylvania 17120 U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Mr. Earl B. Hoffman Dauphin County Commissioner Sheldon J. Wolfe, Esq., Chairman Dauphin County Courthouse Atomic Safety and Licensing Board Front and Market Streets U.S. Nuclear Regulatory Commission Harrisburg, Pennsylvania 17101 Washington, D.C.
20555 Dauphin County Office of Emergency Mr. Gustave A. Linenberger, Jr.
Preparedness Atomic Safety and Licensing Board Court House, Room 7 U.S. Nuclear Regulatory Comissjon Front and Market Streets Washington, D.C.
20555 Harrisburg, Pennsylvania 17101 Dr. James Lamb, III Mr. David D. Maxwell, Chairman Administrative Judge Board o'f. Supervisors 313 Woodhaven Road Londonderry Township Chapel Hill, North Carolina 17514 FRD#1 - Geyers Church Road Middletown, Pennsylvania 17057 Mr. David Hetrick Administrative Judge Mr. Thomas M. Gerusky, Director Professor of Nuclear Energy Bureau of Radiation Protection University of Arizona Pennsylvania Department of Tucson, Arizona 85721 Environmental Resources P. O. Box 2063 Harrisburg, Pennsylvania 17120


GPU Nuclear Corporation             Three Mile Island, Unit 1 cc:
GPU Nuclear Corporation Three Mile Island, Unit 1 cc:
Thomas Y. Au, Esq.                       Sen. Allen R. Carter, Chairman Office of Chief Counsel                 Joint Legislative Committee on Energy Department of Environmental Resources   P. 0. Box 142 505 Executive House                     Suite 513 P. O. Box 2357                           Senate Gressette Building Harrisburg, Pennsylvania 17120           Columbia, South Carolina 29202 Mr. Bob Stein, Director of Research     Ms. Frieda Berryhill, Chairman Committee on Energy                     Coalition for Nuclear Power Plant P. O. Box 11867                           Postponement 104 Blatt Building                       2610 Grendon Drive Columbia, South Carolina 29211           Wilmington, Delaware 19808 Ms. Jane Lee                             William S. Jordan, III, Esq.
Thomas Y. Au, Esq.
183 Valley Road                         Harmon, Weiss & Jordan Etters, Pennsylvania   17319             20001 S Street, N.W.
Sen. Allen R. Carter, Chairman Office of Chief Counsel Joint Legislative Committee on Energy Department of Environmental Resources P. 0. Box 142 505 Executive House Suite 513 P. O. Box 2357 Senate Gressette Building Harrisburg, Pennsylvania 17120 Columbia, South Carolina 29202 Mr. Bob Stein, Director of Research Ms. Frieda Berryhill, Chairman Committee on Energy Coalition for Nuclear Power Plant P. O. Box 11867 Postponement 104 Blatt Building 2610 Grendon Drive Columbia, South Carolina 29211 Wilmington, Delaware 19808 Ms. Jane Lee William S. Jordan, III, Esq.
Suite 430 Ms. Marjorie M. Aamodt                   Washington, D.C. 20009 Mr. Norman Aamodt 200 North Church Street                 Lynne Bernabei, Esq.
183 Valley Road Harmon, Weiss & Jordan Etters, Pennsylvania 17319 20001 S Street, N.W.
Parkesburg, Pennsylvania 19355           Government Accountability Project 1555 Connecticut Ave., N.W.
Suite 430 Ms. Marjorie M. Aamodt Washington, D.C.
Ps. Louise Bradford                     Washington, D.C. 20009 TMIA 1011 Green Street                       Michael W. Maupin, Esq.
20009 Mr. Norman Aamodt 200 North Church Street Lynne Bernabei, Esq.
Harrisburg Pennsylvania 17102           Hunton & Williams 707 East Main Street Mr. Marvin I. Lewis                     P. O. Box 1535 6504 Rradford Terrace                   Richmond Virginia 23212 Philadelphia, Pennsylvanic 19149 Jordan D. Cunningham, Esq.
Parkesburg, Pennsylvania 19355 Government Accountability Project 1555 Connecticut Ave., N.W.
Mr. Chauncey Kepford                     Fox, Farr and Cunningham Ms. Judith H. Johnsrud                   2320 North 2nd Street Environmental Coalition on Nuclear Power Harrisburg, Pennsylvania 17110 433 Orlando Avenue State College, Pennsylvania 16801       Ms. Ellyn R. Weiss Harmon, Weiss & Jordan Mr. Bruce Molholt                       2001 S Street, N.W.
Ps. Louise Bradford Washington, D.C.
Haverford College                       Suite 430 Haverford, Pennsylvania 19041           Wa'sh.ington, D.C. 20009 Mr. Donald E. Hossler                   Michael McBride, Esq.
20009 TMIA 1011 Green Street Michael W. Maupin, Esq.
501 Vine Street                         LeBoeuf, Lamb, Leiby & McRae Middletown, Pennsylvania 17057           Suite 1100 1333 New Hampshire Avenue, N.W.
Harrisburg Pennsylvania 17102 Hunton & Williams 707 East Main Street Mr. Marvin I. Lewis P. O. Box 1535 6504 Rradford Terrace Richmond Virginia 23212 Philadelphia, Pennsylvanic 19149 Jordan D. Cunningham, Esq.
Mr. Ad Crable                           Washington, D.C. 20036 Lancaster New Era 8 West King Street Lancaster, Pennsylvania 17602
Mr. Chauncey Kepford Fox, Farr and Cunningham Ms. Judith H. Johnsrud 2320 North 2nd Street Environmental Coalition on Nuclear Power Harrisburg, Pennsylvania 17110 433 Orlando Avenue State College, Pennsylvania 16801 Ms. Ellyn R. Weiss Harmon, Weiss & Jordan Mr. Bruce Molholt 2001 S Street, N.W.
Haverford College Suite 430 Haverford, Pennsylvania 19041 Wa'sh.ington, D.C.
20009 Mr. Donald E. Hossler Michael McBride, Esq.
501 Vine Street LeBoeuf, Lamb, Leiby & McRae Middletown, Pennsylvania 17057 Suite 1100 1333 New Hampshire Avenue, N.W.
Mr. Ad Crable Washington, D.C.
20036 Lancaster New Era 8 West King Street Lancaster, Pennsylvania 17602


GPU Nuclear Corporation           Three Mile Island, Unit I cc:
GPU Nuclear Corporation Three Mile Island, Unit I cc:
Atomic Safety & Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Atomic Safety & Licensing Appeal Board Panel (8)
Atomic Safety & Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C.
U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Docketing and Service Section Office of the Secretary U.S. Nuclear Regulatory Commission Washington, D.C. 20555 i
20555 Atomic Safety & Licensing Appeal Board Panel (8)
U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Docketing and Service Section Office of the Secretary U.S. Nuclear Regulatory Commission Washington, D.C.
20555 i
0 4
0 4
i i
i i
i
i


l Enclosure SAMPLE EXEMPTION REQUEST THREE MILE ISLAND NUCLEAR STATION, UNIT 1 DOCKET N0. 50-289 4
l Enclosure SAMPLE EXEMPTION REQUEST THREE MILE ISLAND NUCLEAR STATION, UNIT 1 DOCKET N0. 50-289 1.0 Introduction 4
1.0 Introduction By letter dated February 14, 1984, the licensee proposed to use Rockbestos
By {{letter dated|date=February 14, 1984|text=letter dated February 14, 1984}}, the licensee proposed to use Rockbestos
                      " fire-rated" cable in lieu of installing 1-hour fire-rated barriers to protect certain shutdown-related circuits. At our request, the licensee identified some locations in the plant where the use of the " fire-rated" cable would represent a " worst-case" condition. A " sample" exemption request with supporting information was submitted by letter dated February 11, 1985.
" fire-rated" cable in lieu of installing 1-hour fire-rated barriers to protect certain shutdown-related circuits. At our request, the licensee identified some locations in the plant where the use of the " fire-rated" cable would represent a " worst-case" condition. A " sample" exemption request with supporting information was submitted by {{letter dated|date=February 11, 1985|text=letter dated February 11, 1985}}.
This exemption is intended to be a test case to determine the viability of using " fire-rated" cable in other locations.
This exemption is intended to be a test case to determine the viability of using " fire-rated" cable in other locations.
A specific exemption request is needed for each fire area where " fire-rated" cable is proposed in lieu of fire barriers, including a specific request for the Fuel Handling Building. The itens discussed in the following evaluation should be discussed for each specific request.
A specific exemption request is needed for each fire area where " fire-rated" cable is proposed in lieu of fire barriers, including a specific request for the Fuel Handling Building. The itens discussed in the following evaluation should be discussed for each specific request.
j 2.0 Evaluation of Fuel Handling Building - Fire Zone FH FZ I II l                     2.1 Exemption Peouested The licensee requested an exemption from Section III.G of Appendix R to 10 CFR 50 to the extent that it requires that redundant shutdown-related systems be separated by a 1-hour fire-rated barrier and be free of fire damage.
II 2.0 Evaluation of Fuel Handling Building - Fire Zone FH FZ I j
l 2.1 Exemption Peouested The licensee requested an exemption from Section III.G of Appendix R to 10 CFR 50 to the extent that it requires that redundant shutdown-related systems be separated by a 1-hour fire-rated barrier and be free of fire damage.
2.? Discussion 3
2.? Discussion 3
This fire area is bounded by walls, floor, and ceiling of reinforced concrete. These structural features separate this fire area from other plant locations which the licensee has identified as separate fire areas. Our i                     evaluation of fire area boundary features will be covered in a separate SER.
This fire area is bounded by walls, floor, and ceiling of reinforced concrete. These structural features separate this fire area from other plant locations which the licensee has identified as separate fire areas. Our i
1/   We have evaluated this exemption on the basis that fire rated cable will be installed within or throughout a fire area; however, the licensee designates this fire area as a fire zone.
evaluation of fire area boundary features will be covered in a separate SER.
1/
We have evaluated this exemption on the basis that fire rated cable will be installed within or throughout a fire area; however, the licensee designates this fire area as a fire zone.
l
l


This fire area contains the following shutdown-related systems:
. This fire area contains the following shutdown-related systems:
: 1. Make-up and Purification Pumps MU-P-1A,18 and IC power circuits;
1.
: 2. Auxiliary 0i1 Pumps MU-P3A, 38 and 3C power circuits;
Make-up and Purification Pumps MU-P-1A,18 and IC power circuits; 2.
: 3. Reactor Building Emergency Cooling Units AH-E-1A, 18 and IC power circuits; 4     Decay Heat Pumps DH-P-1A and IB, power circuits;
Auxiliary 0i1 Pumps MU-P3A, 38 and 3C power circuits; 3.
: 5. Borated Water Storage Tank Monitoring instrument circuits;
Reactor Building Emergency Cooling Units AH-E-1A, 18 and IC power circuits; 4
: 6. Feeders to 480V AC-ESV CC-1A and IB;
Decay Heat Pumps DH-P-1A and IB, power circuits; 5.
: 7. Nuclear Instrumentation Circuits;
Borated Water Storage Tank Monitoring instrument circuits; 6.
: 8. Steam Generator Pressure Monitoring instrument circuits;
Feeders to 480V AC-ESV CC-1A and IB; 7.
: 9. Steam Generator Level Monitoring instrument circuits;
Nuclear Instrumentation Circuits; 8.
Steam Generator Pressure Monitoring instrument circuits; 9.
Steam Generator Level Monitoring instrument circuits;
: 10. Reactor Coolant Temperature (cold) Monitoring instrument circuits;
: 10. Reactor Coolant Temperature (cold) Monitoring instrument circuits;
: 11. Power, control, and control power circuits to the 480V AC ES-SH SWGR-IR IT;
: 11. Power, control, and control power circuits to the 480V AC ES-SH SWGR-IR IT; 12.
: 12. Reactor Coolant Temperature (H0T) Monitoring instrument circuits;
Reactor Coolant Temperature (H0T) Monitoring instrument circuits;
: 13. Reactor Coolant Pressurizer Level Monitoring instrument circuits;
: 13. Reactor Coolant Pressurizer Level Monitoring instrument circuits;
: 14. Decay Heat River Water Pumps DR-P-1A and IB control circuits;
: 14. Decay Heat River Water Pumps DR-P-1A and IB control circuits;
: 15. Nuclear Services River Water Pumps NR-P-1A,18 and 1C control circuits;
: 15. Nuclear Services River Water Pumps NR-P-1A,18 and 1C control circuits; 16.
: 16. Reactor Building Emergency River Water Pumps RR-P-1A and 18 power circuits; and
Reactor Building Emergency River Water Pumps RR-P-1A and 18 power circuits; and 17.
: 17. Reactor Coolant Pressurizer Level Monitoring instrument circuits.
Reactor Coolant Pressurizer Level Monitoring instrument circuits.
The in-situ fire loading within this zone consists primarily of cable insulation. In addition, eight steel drums, each 55 gal., are located in the southwest section of the zone for the collection of waste materials such as paper, plastic, and clothing. Maintenance materials such as rubber and plastic hose, vacuum cleaners, plastic buckets are kept behind a partial-height wall in the south section of the zone. Cable routings above these transient combustibles are such that only one redundant channel of cable trays (B channel) is located above or in the imediate vicinity of the steel drums containing waste in the southwest section and only one redundant channel of cable trays (A channel) is located above or in the immediate vicinity of the maintenance materials in the south section. Combustibles in other areas of this fire zone consists of cable insulation in trays and small quantities of pump lubricating oil The overall fire loading, the majority of which is cable insulation in trays, is approximately 49,500 RTV/ft2 which corresponds to a fire severity on the ASTM E-119 time-temperature curve of 29 minutes.
The in-situ fire loading within this zone consists primarily of cable insulation.
The cable insulation is contained in open bottom trays which are spread horizontally up to eight trays wide instead of being stacked vertically. At several locations the north-south r'uted o    trays bass over or under east-west routed trays. The maximum vertical stacking of trays occurs in the northwest section of the zone where three large and two small cable trays are stacked for a short distance. All cable trays are located in the upper portions of the rooms and corridors, and are readily accessible for manual fire suppression.
In addition, eight steel drums, each 55 gal., are located in the southwest section of the zone for the collection of waste materials such as paper, plastic, and clothing. Maintenance materials such as rubber and plastic hose, vacuum cleaners, plastic buckets are kept behind a partial-height wall in the south section of the zone.
Cable routings above these transient combustibles are such that only one redundant channel of cable trays (B channel) is located above or in the imediate vicinity of the steel drums containing waste in the southwest section and only one redundant channel of cable trays (A channel) is located above or in the immediate vicinity of the maintenance materials in the south section. Combustibles in other areas of this fire zone consists of cable insulation in trays and small quantities of pump lubricating oil The overall fire loading, the majority of which is cable insulation in trays, is approximately 49,500 RTV/ft2 which corresponds to a fire severity on the ASTM E-119 time-temperature curve of 29 minutes.
The cable insulation is contained in open bottom trays which are spread horizontally up to eight trays wide instead of being stacked vertically. At several locations the north-south r'uted trays bass over or under east-west o
routed trays. The maximum vertical stacking of trays occurs in the northwest section of the zone where three large and two small cable trays are stacked for a short distance. All cable trays are located in the upper portions of the rooms and corridors, and are readily accessible for manual fire suppression.
This fire area is protected by an area wide fire detection system and an area wide automatic sprinkler system providing full coverage. A hose station and portable fire extinguishers are provided in the fire area for manual fire extinguishment.
This fire area is protected by an area wide fire detection system and an area wide automatic sprinkler system providing full coverage. A hose station and portable fire extinguishers are provided in the fire area for manual fire extinguishment.
i I
i I


By letter dated February 11,, 1985, the applicant committed to either: 1) reroute certain cables outside of the fire area; 2) implement a repair procedure for other fire-vulnerable cables within the area 3) enclose some shutdown cables in a 1-hour fire-rated barrier; or 4) replace one division of the remaining shutdown-related cables with the " fire-rated" cable.
. By {{letter dated|date=February 11, 1985|text=letter dated February 11,, 1985}}, the applicant committed to either: 1) reroute certain cables outside of the fire area; 2) implement a repair procedure for other fire-vulnerable cables within the area 3) enclose some shutdown cables in a 1-hour fire-rated barrier; or 4) replace one division of the remaining shutdown-related cables with the " fire-rated" cable.
The licensee justified the exemption for the use of " fire-rated" cable on the basis of tests conducted on the " fire-rated" cable and the existing level of fire protection.
The licensee justified the exemption for the use of " fire-rated" cable on the basis of tests conducted on the " fire-rated" cable and the existing level of fire protection.
2.3 Evaluation The technical requirements of Section III.G are not met in this area (Fire Zone FH FZ 1) because certain shutdown-related cables delineated in the licensee's February 11, 1985, letter are not protected by a 1-hour fire-rated barrier and would not be free of fire damage after being involved in a fire.
2.3 Evaluation The technical requirements of Section III.G are not met in this area (Fire Zone FH FZ 1) because certain shutdown-related cables delineated in the licensee's {{letter dated|date=February 11, 1985|text=February 11, 1985, letter}} are not protected by a 1-hour fire-rated barrier and would not be free of fire damage after being involved in a fire.
The staff's concerns, discussed below, need to be resolved before we can find acceptable the use of " fire-rated" cable in lieu of conventional fire walls or fire-rated cable wrap. Some of the concerns are fully resolved but others require further data before a conclusion can be reached.
The staff's concerns, discussed below, need to be resolved before we can find acceptable the use of " fire-rated" cable in lieu of conventional fire walls or fire-rated cable wrap. Some of the concerns are fully resolved but others require further data before a conclusion can be reached.
2.3.1   Functional Capability We were concerned that the cable would not perform its intended function when exposed to the effects of a fire.
2.3.1 Functional Capability We were concerned that the cable would not perform its intended function when exposed to the effects of a fire.
By letter dated June 9, 1984, the licensee submitted the results of a fire test conducted by Underwriter's Laboratories, Incorporated. Representative samples of the cable were subjected to a 1-hour fire endurance and hose stream test in accordance with the method in ASTM E-119. During the fire test and for a period of 93 hours beyond, electrical measurements were taken to confirm the cable's electrical performance. The results confirm that the acceptance criteria of ASTM E-119 were met or exceeded. We, therefore, have reasonable assurance that the cables will function as designed until the fire is extinguished.
By {{letter dated|date=June 9, 1984|text=letter dated June 9, 1984}}, the licensee submitted the results of a fire test conducted by Underwriter's Laboratories, Incorporated. Representative samples of the cable were subjected to a 1-hour fire endurance and hose stream test in accordance with the method in ASTM E-119. During the fire test and for a period of 93 hours beyond, electrical measurements were taken to confirm the cable's electrical performance. The results confirm that the acceptance criteria of ASTM E-119 were met or exceeded. We, therefore, have reasonable assurance that the cables will function as designed until the fire is extinguished.
2.3.2 Mechanical Damage We were concerned that the heat produced in a fire would cause structural i features such as cable trays to collapse. The *falling debris might impact l the cable and cause its failure.                   ,
2.3.2 Mechanical Damage We were concerned that the heat produced in a fire would cause structural i
The area (Fire Zone FH FZ 1) is protected by a complete fire detection system that alarms in the control room. If a fire should occur, it would be l detected in its formative stages before significant temperature rise occurs.
features such as cable trays to collapse. The falling debris might impact l
The fire brigade would then extinguish the fire using manual fire fighting equipment. Additionally, if rapid fire propagation occurred, the available
the cable and cause its failure.
automatic sprinkler system would actuate to suppress the fire, reduce room temperatures, protect the shutdown-related cable and prevent debris formation. We therefore, have reasonable assurance that the " fire-rated" cable will not be mechanically damaged by falling debris during a fire.
The area (Fire Zone FH FZ 1) is protected by a complete fire detection system that alarms in the control room.
If a fire should occur, it would be l
detected in its formative stages before significant temperature rise occurs.
The fire brigade would then extinguish the fire using manual fire fighting equipment. Additionally, if rapid fire propagation occurred, the available automatic sprinkler system would actuate to suppress the fire, reduce room temperatures, protect the shutdown-related cable and prevent debris formation. We therefore, have reasonable assurance that the " fire-rated" cable will not be mechanically damaged by falling debris during a fire.


2.3.3 Higher Temperatures in Cable Trays In the proposed application, the " fire-rated" cable would be routed, in part, through cable trays containing conventional cable. We were concerned that a fire involving such cable would be more severe than the E-119 time-temperature curve. The fire test included such a configuration; therefore, this concern has been resolved.
. 2.3.3 Higher Temperatures in Cable Trays In the proposed application, the " fire-rated" cable would be routed, in part, through cable trays containing conventional cable. We were concerned that a fire involving such cable would be more severe than the E-119 time-temperature curve. The fire test included such a configuration; therefore, this concern has been resolved.
2.3.4 Applicable Cable Voltaaes In the early fire tests, the conductors of the " fire-rated" cable were energized at 110 Vac. We were concerned that the cable would be used at higher voltages (e.g. 600V). Subsequent fire tests were performed with the conductors energized at 480 Vac and 960 Vac. Therefore, this concern has been resolved.
2.3.4 Applicable Cable Voltaaes In the early fire tests, the conductors of the " fire-rated" cable were energized at 110 Vac. We were concerned that the cable would be used at higher voltages (e.g. 600V). Subsequent fire tests were performed with the conductors energized at 480 Vac and 960 Vac. Therefore, this concern has been resolved.
2.3.5 Changes in Electrical Characteristics We were concerned that the " fire-rated" cable would not provide the electrical performance characteristics that are necessary for successful operation in the various applications. For example, the " fire-rated" cable is proposed for power, control and instrumentation circuits.
2.3.5 Changes in Electrical Characteristics We were concerned that the " fire-rated" cable would not provide the electrical performance characteristics that are necessary for successful operation in the various applications.
For example, the " fire-rated" cable is proposed for power, control and instrumentation circuits.
The electrical characteristics of the cable (i.e. conductor and insulation) change with temperature increase. Thus, the insulation must be designed and the cable must be sized so that these changes do not affect the performance of the required function. The electrical performance criteria for each application (i.e. power, control or instrumentation) must be specified; the
The electrical characteristics of the cable (i.e. conductor and insulation) change with temperature increase. Thus, the insulation must be designed and the cable must be sized so that these changes do not affect the performance of the required function. The electrical performance criteria for each application (i.e. power, control or instrumentation) must be specified; the
" fire-rated" cable must then be shown to meet these criteria to assure that changes in the electrical characteristics of the " fire-rated" cable during a fire will not affect circuit operation.
" fire-rated" cable must then be shown to meet these criteria to assure that changes in the electrical characteristics of the " fire-rated" cable during a fire will not affect circuit operation.
Line 117: Line 150:
The extent of cable damage following the fire must be determined so that the electrical characteristics immediately after the fire can be established; then the acceptability of the " fire-rated" cable for further use can be determined. Special precautions may be needed to prevent further cable damage, or cables may need to be replaced, or certain functions may not be needed making the applicable cables unnecessary. These aspects of post-fire operability should be addressed in the licensee's analyses for each fire area. This information was not provided in the sample exemption request.
The extent of cable damage following the fire must be determined so that the electrical characteristics immediately after the fire can be established; then the acceptability of the " fire-rated" cable for further use can be determined. Special precautions may be needed to prevent further cable damage, or cables may need to be replaced, or certain functions may not be needed making the applicable cables unnecessary. These aspects of post-fire operability should be addressed in the licensee's analyses for each fire area. This information was not provided in the sample exemption request.


2.3.7 Immersion Resistance We were concerned that " wet short" conditions were not simulated in the
. 2.3.7 Immersion Resistance We were concerned that " wet short" conditions were not simulated in the
" fire-rated" cable tests but cables in cable trays may be immersed in water for a significant time. The sample exemption request is for stainless steel sheathed cables only. In our opinion, such cables would not be subject to failure by " wet shorts" and this concern is resolved.
" fire-rated" cable tests but cables in cable trays may be immersed in water for a significant time. The sample exemption request is for stainless steel sheathed cables only.
In our opinion, such cables would not be subject to failure by " wet shorts" and this concern is resolved.
2.3.8 Thermal Expansion Forces We were concerned that thermal expansion forces, and post-fire mechanical forces due to firefighting and recovery operations, were not simulated.
2.3.8 Thermal Expansion Forces We were concerned that thermal expansion forces, and post-fire mechanical forces due to firefighting and recovery operations, were not simulated.
For the distributed fire load in this area, a real fire would not result in temperatures approaching the E-119 time-temperature curve over a large portion of the fire area even if the automatic suppression system did not operate. Prompt action by the fire brigade and automatic suppression would further reduce the time-temperature curve. The hose stream tests with repeated application of hose stream forces has resolved this concern.
For the distributed fire load in this area, a real fire would not result in temperatures approaching the E-119 time-temperature curve over a large portion of the fire area even if the automatic suppression system did not operate. Prompt action by the fire brigade and automatic suppression would further reduce the time-temperature curve.
The hose stream tests with repeated application of hose stream forces has resolved this concern.
2.3.9 Post-Test Assessment of Operability We were concerned that no post-test assessment of the operability of the
2.3.9 Post-Test Assessment of Operability We were concerned that no post-test assessment of the operability of the
" fire-rated" cables had been made. Subsequent tests have shown that the
" fire-rated" cables had been made.
Subsequent tests have shown that the
" fire-rated" cable can remain functional during the fire and for at least 94 hours thereafter. Therefore, this concern is resolved.
" fire-rated" cable can remain functional during the fire and for at least 94 hours thereafter. Therefore, this concern is resolved.
2.3.10 Mechanical Damage Due to Delay in Automatic Suppression We were concerned that if the automatic suppression system did not operate as designed for a rapidly developing fire, the " fire-rated" cable could be damaged by debris. In our opinion, the probability of a severe, rapidly developing fore is low with the in-situ final configuration, and the cable would not be damaged even if the automatic suppression was delayed.
2.3.10 Mechanical Damage Due to Delay in Automatic Suppression We were concerned that if the automatic suppression system did not operate as designed for a rapidly developing fire, the " fire-rated" cable could be damaged by debris.
In our opinion, the probability of a severe, rapidly developing fore is low with the in-situ final configuration, and the cable would not be damaged even if the automatic suppression was delayed.
2.3.11 Improved Separation The staff suggested that it would be prudent to provide improved separation (i.e., better than required by Reg. Guide 1.75) between the " fire-rated" cable and its redundant counterpart. However, in our opinion, the lack of improved separation would not be a cause to den'y the exemption for the sample exemption request. This issue is resolved.
2.3.11 Improved Separation The staff suggested that it would be prudent to provide improved separation (i.e., better than required by Reg. Guide 1.75) between the " fire-rated" cable and its redundant counterpart. However, in our opinion, the lack of improved separation would not be a cause to den'y the exemption for the sample exemption request. This issue is resolved.
2.3.12 Continuous Cable in Each Fire Area The " fire-rated" cable should be continuous throur;h the fire area (i.e.,
2.3.12 Continuous Cable in Each Fire Area The " fire-rated" cable should be continuous throur;h the fire area (i.e.,
splices between " fire-rated" and non " fire-rated" cable should be made outside of the fire area boundaries). If not, the licensee should justify why the " fire-rated" cable should not be continuous through the fire area.
splices between " fire-rated" and non " fire-rated" cable should be made outside of the fire area boundaries).
If not, the licensee should justify why the " fire-rated" cable should not be continuous through the fire area.
The licensee should describe the splice and its protection to assure that it does not cause a loss of function due to fire or fire suppressants.
The licensee should describe the splice and its protection to assure that it does not cause a loss of function due to fire or fire suppressants.


3.0 Conclusions Based on our evaluation, we conclude that with adequate supporting information requested herein the use of " fire-rated" cable in a fire area with a distributed in-situ fire loading and protected by automatic suppression systems can be shown to provide an equivalent level of safety to that achieved by installing a 1-hour fire barrier per Section III.G.2.C of Appendix R.
, 3.0 Conclusions Based on our evaluation, we conclude that with adequate supporting information requested herein the use of " fire-rated" cable in a fire area with a distributed in-situ fire loading and protected by automatic suppression systems can be shown to provide an equivalent level of safety to that achieved by installing a 1-hour fire barrier per Section III.G.2.C of Appendix R.
e           e}}
e e}}

Latest revision as of 10:19, 12 December 2024

Forwards Sample Evaluation Re Use of Rockbestos fire-rated Cable in Fuel Handling Bldg Fire Zone FH-FZ-1,per Util 850211 & 14 Submittals.Exemption Requests W/Supporting Info Should Be Prepared for Each Fire Area.Schedule Requested
ML20133A024
Person / Time
Site: Crane 
Issue date: 07/22/1985
From: Stolz J
Office of Nuclear Reactor Regulation
To: Hukill H
GENERAL PUBLIC UTILITIES CORP.
References
CON-#385-967 OL, SP, NUDOCS 8508050306
Download: ML20133A024 (10)


Text

bb July 22,1985 Docket No. 50-289 DI_STRTRUTION WRussell a

w L PDR ACRS-10 Mr. Henry D. Hukill, Vice President ORB #4 Rdg RIngram and Director - TMI-1 HThompson 0 Thompson GPU Nuclear Corporation OELD JThoma P. O. Box 480 EJordan Gray File Middletown, Pennsylvania 17057 E81ackwood H0rnstein RFerguson TWambach

Dear Mr. Hukill:

DKubicki Glainas In our Safety Evaluation Report dated June 4, 1983, we granted exemptions to the technical requirements of Appendix R to 10 CFR 50. The exemptions were based, in part, on your comitment to install 1-hour fire-rated barriers around certain shutdown-related cables. By letter dated February 14, 1984, you proposed using fire-rated cable in lieu of fire barriers for certain applications in the plant. At our request, your letter dated February 11, IS85 provided a " worst-case" sample exemption request for one location in the plant to enable us to evaluate the viability of the proposal. The example also requested exemption for the protection of some barrier supports, but we have evaluated only the exemption for " fire-rated" cable. Enclosed is our sample evaluation of this information.

Based on our sample evaluation, we conclude that the use of Rockbestos

" fire-rated" cable in the Fuel Handling Building Fire Zone FH-FZ-1, can be shown to provide an equivalent level of safety to that obtained by installing 1-hour fire-rated barriers around vulnerable shutdown-related cables in this area. However, additional information should be provided in support of the actual exemption requests as indicated in our evaluation.

Exemption requests, with supporting information, should be prepared for each fire area in which fire-rated cable is being considered including the Fuel Handling Building. We also request that you provide a schedule for submitting these C

exemption requests.

Sincerely.

%m % x ca n

) a&\\

R.a '

Joh. c. f.<0t, Chief Operating Reactors Branch #4 Division of Licensing cc: See next page 32rr hdor g

/

ORB ORB #4:DL ORB # 'DL CH DE CHEM:DE mpson;cf JIFora JSt RFe guson VBenaroya 1/fr/85 7//9/85 7/

7/g85 7/W5 7

8508050306 850722 PDR ADOCK 05000289 1

F PDR

,-ee-4,-.,e-

,,,---,er

,e,

---r

.en.~

---,r

Mr. Henry D. Hukill Three Mile Island Nuclear Station GPU Nuclear Corporation Unit No I cc:

Mr. R. J. Toole Mr. Richard Conte 0&M Director, TMI-1 Senior Resident Inspector (TMI-1)

GPU Nuclear Corporation U.S.N.R.C.

Middletown, Pennsylvania 17057 P.O. Box 311 Middletown, Pennsylvania 17057 Richard J. McGoey Manager, PWR Licensing GPU Nuclear Corporation Regional Administrator, Region I 100 Interpace Parkway U.S. Nuclear Regulatory Commission Parsippany, New Jersey 70754 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. C. W. Smyth TMI-I Licensing Manager Mr. Robert B. Borsum GPU Nuclear Corporation Babcock & Wilcox P. O. Rox 480 Nuclear Power Generation Division Middletown, Pennsylvania 17057 Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 G. F. Trowbridge, Esq.

Shaw, Pittman, Potts & Trowbridge Governor's Office of State Planning 1800 M Street, N.W.

and Development Washington, D.C.

20036 ATTN:

Coordinator, Pennsylvania State Clearinghouse Ivan W. Smith, Esq., Chairman P. O. Box 1323 Atomic Safety and Licensing Board Harrisburg, Pennsylvania 17120 U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Mr. Earl B. Hoffman Dauphin County Commissioner Sheldon J. Wolfe, Esq., Chairman Dauphin County Courthouse Atomic Safety and Licensing Board Front and Market Streets U.S. Nuclear Regulatory Commission Harrisburg, Pennsylvania 17101 Washington, D.C.

20555 Dauphin County Office of Emergency Mr. Gustave A. Linenberger, Jr.

Preparedness Atomic Safety and Licensing Board Court House, Room 7 U.S. Nuclear Regulatory Comissjon Front and Market Streets Washington, D.C.

20555 Harrisburg, Pennsylvania 17101 Dr. James Lamb, III Mr. David D. Maxwell, Chairman Administrative Judge Board o'f. Supervisors 313 Woodhaven Road Londonderry Township Chapel Hill, North Carolina 17514 FRD#1 - Geyers Church Road Middletown, Pennsylvania 17057 Mr. David Hetrick Administrative Judge Mr. Thomas M. Gerusky, Director Professor of Nuclear Energy Bureau of Radiation Protection University of Arizona Pennsylvania Department of Tucson, Arizona 85721 Environmental Resources P. O. Box 2063 Harrisburg, Pennsylvania 17120

GPU Nuclear Corporation Three Mile Island, Unit 1 cc:

Thomas Y. Au, Esq.

Sen. Allen R. Carter, Chairman Office of Chief Counsel Joint Legislative Committee on Energy Department of Environmental Resources P. 0. Box 142 505 Executive House Suite 513 P. O. Box 2357 Senate Gressette Building Harrisburg, Pennsylvania 17120 Columbia, South Carolina 29202 Mr. Bob Stein, Director of Research Ms. Frieda Berryhill, Chairman Committee on Energy Coalition for Nuclear Power Plant P. O. Box 11867 Postponement 104 Blatt Building 2610 Grendon Drive Columbia, South Carolina 29211 Wilmington, Delaware 19808 Ms. Jane Lee William S. Jordan, III, Esq.

183 Valley Road Harmon, Weiss & Jordan Etters, Pennsylvania 17319 20001 S Street, N.W.

Suite 430 Ms. Marjorie M. Aamodt Washington, D.C.

20009 Mr. Norman Aamodt 200 North Church Street Lynne Bernabei, Esq.

Parkesburg, Pennsylvania 19355 Government Accountability Project 1555 Connecticut Ave., N.W.

Ps. Louise Bradford Washington, D.C.

20009 TMIA 1011 Green Street Michael W. Maupin, Esq.

Harrisburg Pennsylvania 17102 Hunton & Williams 707 East Main Street Mr. Marvin I. Lewis P. O. Box 1535 6504 Rradford Terrace Richmond Virginia 23212 Philadelphia, Pennsylvanic 19149 Jordan D. Cunningham, Esq.

Mr. Chauncey Kepford Fox, Farr and Cunningham Ms. Judith H. Johnsrud 2320 North 2nd Street Environmental Coalition on Nuclear Power Harrisburg, Pennsylvania 17110 433 Orlando Avenue State College, Pennsylvania 16801 Ms. Ellyn R. Weiss Harmon, Weiss & Jordan Mr. Bruce Molholt 2001 S Street, N.W.

Haverford College Suite 430 Haverford, Pennsylvania 19041 Wa'sh.ington, D.C.

20009 Mr. Donald E. Hossler Michael McBride, Esq.

501 Vine Street LeBoeuf, Lamb, Leiby & McRae Middletown, Pennsylvania 17057 Suite 1100 1333 New Hampshire Avenue, N.W.

Mr. Ad Crable Washington, D.C.

20036 Lancaster New Era 8 West King Street Lancaster, Pennsylvania 17602

GPU Nuclear Corporation Three Mile Island, Unit I cc:

Atomic Safety & Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Atomic Safety & Licensing Appeal Board Panel (8)

U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Docketing and Service Section Office of the Secretary U.S. Nuclear Regulatory Commission Washington, D.C.

20555 i

0 4

i i

i

l Enclosure SAMPLE EXEMPTION REQUEST THREE MILE ISLAND NUCLEAR STATION, UNIT 1 DOCKET N0. 50-289 1.0 Introduction 4

By letter dated February 14, 1984, the licensee proposed to use Rockbestos

" fire-rated" cable in lieu of installing 1-hour fire-rated barriers to protect certain shutdown-related circuits. At our request, the licensee identified some locations in the plant where the use of the " fire-rated" cable would represent a " worst-case" condition. A " sample" exemption request with supporting information was submitted by letter dated February 11, 1985.

This exemption is intended to be a test case to determine the viability of using " fire-rated" cable in other locations.

A specific exemption request is needed for each fire area where " fire-rated" cable is proposed in lieu of fire barriers, including a specific request for the Fuel Handling Building. The itens discussed in the following evaluation should be discussed for each specific request.

II 2.0 Evaluation of Fuel Handling Building - Fire Zone FH FZ I j

l 2.1 Exemption Peouested The licensee requested an exemption from Section III.G of Appendix R to 10 CFR 50 to the extent that it requires that redundant shutdown-related systems be separated by a 1-hour fire-rated barrier and be free of fire damage.

2.? Discussion 3

This fire area is bounded by walls, floor, and ceiling of reinforced concrete. These structural features separate this fire area from other plant locations which the licensee has identified as separate fire areas. Our i

evaluation of fire area boundary features will be covered in a separate SER.

1/

We have evaluated this exemption on the basis that fire rated cable will be installed within or throughout a fire area; however, the licensee designates this fire area as a fire zone.

l

. This fire area contains the following shutdown-related systems:

1.

Make-up and Purification Pumps MU-P-1A,18 and IC power circuits; 2.

Auxiliary 0i1 Pumps MU-P3A, 38 and 3C power circuits; 3.

Reactor Building Emergency Cooling Units AH-E-1A, 18 and IC power circuits; 4

Decay Heat Pumps DH-P-1A and IB, power circuits; 5.

Borated Water Storage Tank Monitoring instrument circuits; 6.

Feeders to 480V AC-ESV CC-1A and IB; 7.

Nuclear Instrumentation Circuits; 8.

Steam Generator Pressure Monitoring instrument circuits; 9.

Steam Generator Level Monitoring instrument circuits;

10. Reactor Coolant Temperature (cold) Monitoring instrument circuits;
11. Power, control, and control power circuits to the 480V AC ES-SH SWGR-IR IT; 12.

Reactor Coolant Temperature (H0T) Monitoring instrument circuits;

13. Reactor Coolant Pressurizer Level Monitoring instrument circuits;
14. Decay Heat River Water Pumps DR-P-1A and IB control circuits;
15. Nuclear Services River Water Pumps NR-P-1A,18 and 1C control circuits; 16.

Reactor Building Emergency River Water Pumps RR-P-1A and 18 power circuits; and 17.

Reactor Coolant Pressurizer Level Monitoring instrument circuits.

The in-situ fire loading within this zone consists primarily of cable insulation.

In addition, eight steel drums, each 55 gal., are located in the southwest section of the zone for the collection of waste materials such as paper, plastic, and clothing. Maintenance materials such as rubber and plastic hose, vacuum cleaners, plastic buckets are kept behind a partial-height wall in the south section of the zone.

Cable routings above these transient combustibles are such that only one redundant channel of cable trays (B channel) is located above or in the imediate vicinity of the steel drums containing waste in the southwest section and only one redundant channel of cable trays (A channel) is located above or in the immediate vicinity of the maintenance materials in the south section. Combustibles in other areas of this fire zone consists of cable insulation in trays and small quantities of pump lubricating oil The overall fire loading, the majority of which is cable insulation in trays, is approximately 49,500 RTV/ft2 which corresponds to a fire severity on the ASTM E-119 time-temperature curve of 29 minutes.

The cable insulation is contained in open bottom trays which are spread horizontally up to eight trays wide instead of being stacked vertically. At several locations the north-south r'uted trays bass over or under east-west o

routed trays. The maximum vertical stacking of trays occurs in the northwest section of the zone where three large and two small cable trays are stacked for a short distance. All cable trays are located in the upper portions of the rooms and corridors, and are readily accessible for manual fire suppression.

This fire area is protected by an area wide fire detection system and an area wide automatic sprinkler system providing full coverage. A hose station and portable fire extinguishers are provided in the fire area for manual fire extinguishment.

i I

. By letter dated February 11,, 1985, the applicant committed to either: 1) reroute certain cables outside of the fire area; 2) implement a repair procedure for other fire-vulnerable cables within the area 3) enclose some shutdown cables in a 1-hour fire-rated barrier; or 4) replace one division of the remaining shutdown-related cables with the " fire-rated" cable.

The licensee justified the exemption for the use of " fire-rated" cable on the basis of tests conducted on the " fire-rated" cable and the existing level of fire protection.

2.3 Evaluation The technical requirements of Section III.G are not met in this area (Fire Zone FH FZ 1) because certain shutdown-related cables delineated in the licensee's February 11, 1985, letter are not protected by a 1-hour fire-rated barrier and would not be free of fire damage after being involved in a fire.

The staff's concerns, discussed below, need to be resolved before we can find acceptable the use of " fire-rated" cable in lieu of conventional fire walls or fire-rated cable wrap. Some of the concerns are fully resolved but others require further data before a conclusion can be reached.

2.3.1 Functional Capability We were concerned that the cable would not perform its intended function when exposed to the effects of a fire.

By letter dated June 9, 1984, the licensee submitted the results of a fire test conducted by Underwriter's Laboratories, Incorporated. Representative samples of the cable were subjected to a 1-hour fire endurance and hose stream test in accordance with the method in ASTM E-119. During the fire test and for a period of 93 hours0.00108 days <br />0.0258 hours <br />1.537698e-4 weeks <br />3.53865e-5 months <br /> beyond, electrical measurements were taken to confirm the cable's electrical performance. The results confirm that the acceptance criteria of ASTM E-119 were met or exceeded. We, therefore, have reasonable assurance that the cables will function as designed until the fire is extinguished.

2.3.2 Mechanical Damage We were concerned that the heat produced in a fire would cause structural i

features such as cable trays to collapse. The falling debris might impact l

the cable and cause its failure.

The area (Fire Zone FH FZ 1) is protected by a complete fire detection system that alarms in the control room.

If a fire should occur, it would be l

detected in its formative stages before significant temperature rise occurs.

The fire brigade would then extinguish the fire using manual fire fighting equipment. Additionally, if rapid fire propagation occurred, the available automatic sprinkler system would actuate to suppress the fire, reduce room temperatures, protect the shutdown-related cable and prevent debris formation. We therefore, have reasonable assurance that the " fire-rated" cable will not be mechanically damaged by falling debris during a fire.

. 2.3.3 Higher Temperatures in Cable Trays In the proposed application, the " fire-rated" cable would be routed, in part, through cable trays containing conventional cable. We were concerned that a fire involving such cable would be more severe than the E-119 time-temperature curve. The fire test included such a configuration; therefore, this concern has been resolved.

2.3.4 Applicable Cable Voltaaes In the early fire tests, the conductors of the " fire-rated" cable were energized at 110 Vac. We were concerned that the cable would be used at higher voltages (e.g. 600V). Subsequent fire tests were performed with the conductors energized at 480 Vac and 960 Vac. Therefore, this concern has been resolved.

2.3.5 Changes in Electrical Characteristics We were concerned that the " fire-rated" cable would not provide the electrical performance characteristics that are necessary for successful operation in the various applications.

For example, the " fire-rated" cable is proposed for power, control and instrumentation circuits.

The electrical characteristics of the cable (i.e. conductor and insulation) change with temperature increase. Thus, the insulation must be designed and the cable must be sized so that these changes do not affect the performance of the required function. The electrical performance criteria for each application (i.e. power, control or instrumentation) must be specified; the

" fire-rated" cable must then be shown to meet these criteria to assure that changes in the electrical characteristics of the " fire-rated" cable during a fire will not affect circuit operation.

The electrical performance criteria for the various applications were not provided in the sample exemption request. However, we believe that acceptable designs can be developed.

2.3.6 Post-Fire Operability Because the " fire-rated" cable would be damaged by a fire, we were concerned that this damage would affect the long-term per,formance of shutdown functions following the fire.

The extent of cable damage following the fire must be determined so that the electrical characteristics immediately after the fire can be established; then the acceptability of the " fire-rated" cable for further use can be determined. Special precautions may be needed to prevent further cable damage, or cables may need to be replaced, or certain functions may not be needed making the applicable cables unnecessary. These aspects of post-fire operability should be addressed in the licensee's analyses for each fire area. This information was not provided in the sample exemption request.

. 2.3.7 Immersion Resistance We were concerned that " wet short" conditions were not simulated in the

" fire-rated" cable tests but cables in cable trays may be immersed in water for a significant time. The sample exemption request is for stainless steel sheathed cables only.

In our opinion, such cables would not be subject to failure by " wet shorts" and this concern is resolved.

2.3.8 Thermal Expansion Forces We were concerned that thermal expansion forces, and post-fire mechanical forces due to firefighting and recovery operations, were not simulated.

For the distributed fire load in this area, a real fire would not result in temperatures approaching the E-119 time-temperature curve over a large portion of the fire area even if the automatic suppression system did not operate. Prompt action by the fire brigade and automatic suppression would further reduce the time-temperature curve.

The hose stream tests with repeated application of hose stream forces has resolved this concern.

2.3.9 Post-Test Assessment of Operability We were concerned that no post-test assessment of the operability of the

" fire-rated" cables had been made.

Subsequent tests have shown that the

" fire-rated" cable can remain functional during the fire and for at least 94 hours0.00109 days <br />0.0261 hours <br />1.554233e-4 weeks <br />3.5767e-5 months <br /> thereafter. Therefore, this concern is resolved.

2.3.10 Mechanical Damage Due to Delay in Automatic Suppression We were concerned that if the automatic suppression system did not operate as designed for a rapidly developing fire, the " fire-rated" cable could be damaged by debris.

In our opinion, the probability of a severe, rapidly developing fore is low with the in-situ final configuration, and the cable would not be damaged even if the automatic suppression was delayed.

2.3.11 Improved Separation The staff suggested that it would be prudent to provide improved separation (i.e., better than required by Reg. Guide 1.75) between the " fire-rated" cable and its redundant counterpart. However, in our opinion, the lack of improved separation would not be a cause to den'y the exemption for the sample exemption request. This issue is resolved.

2.3.12 Continuous Cable in Each Fire Area The " fire-rated" cable should be continuous throur;h the fire area (i.e.,

splices between " fire-rated" and non " fire-rated" cable should be made outside of the fire area boundaries).

If not, the licensee should justify why the " fire-rated" cable should not be continuous through the fire area.

The licensee should describe the splice and its protection to assure that it does not cause a loss of function due to fire or fire suppressants.

, 3.0 Conclusions Based on our evaluation, we conclude that with adequate supporting information requested herein the use of " fire-rated" cable in a fire area with a distributed in-situ fire loading and protected by automatic suppression systems can be shown to provide an equivalent level of safety to that achieved by installing a 1-hour fire barrier per Section III.G.2.C of Appendix R.

e e