SUBJECT: COMMENTS ON NRC PROPOSED RULE ...

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- Table 2-1 AVAILABLE TIME BOli'lUlNG CASE HESIIIXS' I&-s ot of fsite power, loss of wjter t ldw to Hkh vessel or PWt ste3m generdtors Full p w t L 120 minutes 54 minutes . ~- . - ... . -. ~ L,ss i,t uitslte poser, loss of tiut st~~idby, one hour at ter 4.4 hours 3.2 houts water flow to BWH vessel or I steam generators shutdown iton, full power . . .. . . . .. ., . , . . . . .., . 1 . a ) ~ of ~ oftsitti power, loss c,f C'oiJ, reactor vessel head on, 9.1 hours 16.3 hours I rsidual heat removal systrm 15 t11u11s atter it~utdown from r~perdt ion full power Lc~ss uf ot tsi te power, loss of Hefiiel,ng, reactsr vessel head 75.9 hours 23.9 hours 1 r:sidual heat I .moval system off, 72 hours atter shutdown cq~er at ]on troin full power *Cr~tcrlon 1s t ~ m r to reduce reactor vesstl levcl to core midplane.
2.2.5 Spent Fuel Pool L I If sabotage actions disable the spent fuel pool cooling system, for the PWR example, over G h~urs is required to reach boiling temperatures even at the highest possiale decay heat levels (Ap- pendix A). OqJer 12 hours is required to boil off three feet of water. Thus, it is judged that spent fuel pool cooling systems may be completely protected by damage control means since cooling ,,.... ,-, , ,~ ,... of some sort could undoubtedly be restored within 12 to 24 hours and the decay heat level is likely .to be less than t.h.at used in this analysis. Although not specifi:
Page 1 and 2:
Annette Vietti-Cook, Secretary U.S.
Page 3 and 4:
No. (3) Comment aircraft impact, wi
Page 5 and 6:
No. (5) Comment December 14, 2007 P
Page 7 and 8:
NUCLEAR POWER PLANT DESIGN CONCEPTS
Page 9 and 10:
ABSTRACT . Using a modern design fo
Page 11 and 12:
CONTENTS (Continued) Traditional Co
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ILLUSTRATIONS (Continued ) Figure 7
Page 15 and 16:
Table TABLES (Continued) 8-2 Probab
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RCS RHRS RPS RSS RTS RWST SAFE SIS
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: A sahotaqe t-hreat nay arise from
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I Public risk clue to sabotage is,'
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Somewhat contrary to the physical s
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I General Program Flow and Scope 2.
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Baseline Plant Characterizatlon The
Page 29 and 30:
* Damage Control Options - In this
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Evaluation of Preliminary Reference
Page 33 and 34:
:iabotaye . Vault '~'rcc for Plant
Page 36 and 37:
Prom a fault tree, an equlvdlent ii
Page 38 and 39:
4. Reactor protrrt ion syster (PI'S
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loss-of-coolant accident (LoCA) rit
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mitigate or prevent damage to the c
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Vital - Area Analysis The primary e
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When the complement of the location
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. , 3 ..: 1. Hardening critical sys
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I Addition of Systems -- The final
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Table 4-1 Categorization of Design
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Although the attributes described a
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A summary of the initial findings o
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observation can be made for isolati
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Several options (i.4, 11.6, and 11.
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Table 4-5 Categorization of Design
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, . .,. . . - . . . . ~ Findings on
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For example, additional remote indi
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would be to use the plant fire prot
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with such events and because the co
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initial condition, the time availab
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' All reactor control rods are assu
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Option Function Table 5-3 Evaluatio
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the fifth option, which has only mi
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the problem, ( 3) assess the diffic
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other difficulties that were beginn
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Table 6-1 Cost Estimate Summary of
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of 4 to 13 minutes based upon data
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excavation, a base mat, and tank. T
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0 J @ a CONTAINMENT ELM;. PENETRATI
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RECIRC. O OVERHEAD CDNTAlMNT LCY-HE
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opq BORIC ACID STORAGE TANKS .
Page 105 and 106:
.. . 2 (ft I . . .'._ . ,, . ., ' .
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were considered, but their inclusio
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Table 6-4 Cost ~stimates for. Equip
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modified plant (see Appendix G) and
Page 113 and 114:
qp PRESSURIZER
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DHRS, startup of the diesel generat
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The compressor also supplies contro
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Table 6-6 Cost Estimates for Harden
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Table 6-8 Piping Connections to Rea
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I The normal letdown piping, being
Page 126 and 127:
7. PHYSICAL PROTECTION SYSTEH The p
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Secure central alarm station, Locks
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I is doors between the turbine hall
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Figure 7-4. Locations of Locked and
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,,.' Table 7-1 Characteristics of E
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with the baseline plant, there is a
Page 143 and 144:
KEY 'ENGINEERED SAFETY FEATURE WATE
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KEY 0 STAnDARD DOOR: CARD READER/AL
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KEY fl STANOAR0 DOOR: KEY Figure 7-
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Table 7-4 Characteristics of Interi
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2. Increase the number of individua
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last barrier to vital equipment is
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Vital Area mergmncy cwling piping/v
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are generally comparable with the b
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caution is appropriate. For example
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Table 8-3 Typical Permanent Staffin
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Plant Ares Control rom PYR containm
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. , access to both trains as part o
Page 169 and 170:
CHARGE PUMP Figure 8-3. CHARGE PUMP
Page 171 and 172:
Effectiveness of Hardened Decay Hea
Page 173 and 174:
the future to examine impacts or co
Page 175 and 176:
compartments are adjacent or access
Page 177 and 178:
If total plant costs are assumed to
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event that manual [peration is nece
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!X torque limiters on selected letd
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9. CONCLUSIONS AND RECOMMENDATIONS
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APPENDIX A Glossary of Terms Used i
Page 187 and 188:
system vulnerability) or to better
Page 189 and 190:
APPENDIX B Public Riek Due to Sabot
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where The risk due to sequence j le
Page 193 and 194:
of damage control or consequence mi
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4 3. Physically separate vital comp
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APPENDIX C The Design Study Technic
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Name Alan R. Kasper Tobias W. T. Bu
Page 201 and 202:
'5. W. Hickman, "Systems Analysis,
Page 203 and 204:
Page 205 and 206:
Page 207 and 208:
TAKING ADVANTAGE or NATURAL PROTECT
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4.11 SEI'AIU'PION OF SAFETY IICIATE
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. . . , ' . . . . . . , ., , , , .
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,.. . ,. Providing enhaxed protecti
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2 1 . 3 Desirable Attr~tutes of Can
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TABLE 1-1 (can't) 'The column head~
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. . ... . l I I. SYSTEM DES IG3 CHA
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CATECORlZATlOll OF DESICI~I ALT - ,
Page 225 and 226:
GENE RAL 3. DESCRIPTIOtG AND CISCUS
Page 227 and 228:
of war. The ring tunnel containment
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3.3 MARDENED CONTAINMENT BUILDING,
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. ' :, mcnt entry. These factors op
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3.4.5 Summary - - - of DSTSG - Inpu
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. . . , It was also pointed out dur
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3.6.5 Summary of DSTSG Input There
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. . . . . , , mcntator felt that co
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3.8.1 Disadvantages. If ,this conce
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systems and houzing them in separat
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. , in some G.S. ~lsnts. At San Cno
Page 248 and 249:
well as location of the spent fuel
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3d3.2 -. Sources This concept h.3::
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There were no side benefits idcntif
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3.14.4 - Disadvantages t The main d
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3.15.3 Advantages .. . The sabotage
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3.16.2 ---- Sources Physically sepa
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Indqpcndencc is considered low for
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3.18.2 Advantages The counter-sabot
Page 265 and 266:
Depending on the means of implement
Page 267 and 268:
power jumper cables, etc., to facil
Page 269 and 270:
epairs under satotace emergency con
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3.21.3 Advantages The alternate con
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The counter-sabotayc aspects of und
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3.22.4 Disadvantages > The disadvan
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3.23.4 . . Disadvantages This conce
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3.24.6 Discussion The discussion pr
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' There was no clear indication of
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Thc DSTSG considered inpacts for th
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3.27.6 Discussion This concept ellm
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The concept of a RHR system designe
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Appendix C contains a description o
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. System capacty is limited in time
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The DSTSS has raised questions on t
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controls and hardened enclosures, t
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. Summary Comparison of Ee$t Europe
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Applying Gernan Safety Philosophy a
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4.16 ALTERXhl'E CONTROL ROOF! ARRAN
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. Design of Kr;Z' Lh'R Safety Syste
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. Standby and Esergency Power Suppl
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This Addcndun cuntai ns sununar ies
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I CATEGORY: 1.2 HARDENED CONTAINMEN
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CATEGORY: 1.4 HARDENED ENCLOSURE OF
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CATEGORY: 1.6 HARDENED ULTIMATE HEA
Page 316 and 317:
CATEGORY: 1.8 HARDENED ENCLOSURE FO
Page 318 and 319:
CATEGORY: 11.2 SEPARATION OF PIPZNG
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CATEGORY: 11.4 SPENT FUEL STORED RE
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CATEGORY: 11.6 SEPARATE ROOMS OR AR
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CATEGORY: 11.8 ECCS COMPONENTS WITH
Page 326 and 327:
CATEGOPY : I I I. 1 ISOIAT ION OF L
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CATEGORY: 111.3 ALTERNATE CONTAINKE
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CATEGORY: 111.5 ADDITIOSAL PROTECTE
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CATEGORY: 111.7 TURBINE RUNBACK NUI
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PEASIUILI'fY STATE OF TIIE AIVI' PR
Page 336 and 337:
CATEGORY: IV.l HARDENED CECAY HEAT
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Systt:m st~ou~d rlnt bc rt,str ictc
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System Description Independent Safe
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. , 2. A sinqle system: : 3. A sing
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I period of 10 hours without operat
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the initial phase of shutdown cooli
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Actuation of the ISSS results in th
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prcsurizer relief valves. Gradually
Page 352:
Some of these fluid lines arc pro-~
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. ~ ,. : " The turbine is driven by
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. . coolant pressure that can be ob
Page 359 and 360:
Feedwater Storaye Tank Each feedwat
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ISSS A:mosphcr1c D G T ~ Val.io?, ?
Page 363 and 364:
A conceptudl arrdngement 1s st,~wn
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systems would he employed in thc BW
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As long as the time for ISSS opcrat
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., ! 4 I 3 1 2 - . ! I,. ,.Y- .,.I'
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Potential Safcguar
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SECTION 3.5 Reactor Vessel Head Ven
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FIGURE 2-12 : 2-13 5,: . .. . 2-14
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P;IR Systems AC Power 1.7 Reactor C
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DESIGN CHANGE Table 1.1. AC Power S
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DESIGN CHANGE Increase battery capa
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I I Replace I I (1) Table 1.5. Gene
Page 390 and 391:
Table 1.7. PWA AC Power Syst DESIGN
Page 392 and 393:
I I I I Table 1.9. PWR Auxtttary Fe
Page 394 and 395:
i Tahle 1.10. Emergency Core Coolin
Page 396 and 397:
1.. DESIGN CHANGE Table 1.12.BWRRes
Page 398 and 399:
DAMAGE CONTROL ACTIVITY Jrovide a s
Page 400 and 401:
Figure 2-1. AC Power System Design
Page 402 and 403:
2.2 SWITCHGEAR AN0 K CATEGORY I I1
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are discussed in mre detail in a la
Page 406 and 407:
2.5 UICSEL ft4CINE REV:SED COOLING
Page 408 and 409:
Figure 2-3. Diesel Cooling and Lubr
Page 410 and 411:
2.6.5 Discussion An emergency diese
Page 412 and 413:
equipnent. !%tor. controllers and d
Page 414 and 415:
Table 2-1. Safety-Related DC Loads
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fnstrunrntation channel powered fro
Page 418 and 419:
2.11.5 Oi scussion The concern over
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2.12.2 Source This concept was iden
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equipment during routine plant surv
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insider sabotage and the dlfflcul t
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2.16.3 Advantages The advantage of
Page 428 and 429:
2.17.1 Concept Thls concept 1nvolve
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2.18 COFPONEKT COOLING MOOIFICATION
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to accomplish both functions with o
Page 434 and 435:
2.19.4 . Disadvantages The lujor di
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VALVE C00113B WATER ISOLATION VALVE
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....,.. c., Frol Other Loads To Ult
Page 440 and 441:
g u Outslde Alr / I Roof or Ida11 a
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, . accessibility to the diesel and
Page 444 and 445:
. . .,,. . .. . .,. ,, ..* . . .. ,
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3.3.4 Disadvantages No disadvantage
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jI..'$ . $ 5 $!, .. . .:.;,: . ., I
Page 450 and 451:
Vmt Path A Figure 3-1. Reactor Vess
Page 452 and 453:
3.7.2 Source Thls concept was tdent
Page 454 and 455: Pressurl zer c + hxlllrry Elect. /
Page 456 and 457: 3.9 INCREASED EMERGEtiCY FEEOWATER
Page 458 and 459: pmvfded. In the case of a narltiple
Page 460 and 461: 3.11.3 Advantages The advantage of
Page 462 and 463: For operating plants which utilize
Page 464 and 465: 3.14.5 Discussion As mentioned in S
Page 466 and 467: 3.16.4 Dl sadvantages The disadvant
Page 468 and 469: utfll ttd f n the RHR suction 1 lne
Page 470 and 471: 0 The heat exchanger shell provides
Page 472 and 473: of two tube bundles imacrsed in a l
Page 474 and 475: 0 Provide an offsite reserve supply
Page 476 and 477: condtttons, is a straightforward ma
Page 478 and 479: REFERENCES '''power Plant Insulatto
Page 480 and 481: Introduction EVALUATION AND SUMMARY
Page 482 and 483: Table A-1 (Continued) Cdtryorlzntio
Page 484 and 485: . , 2.4 MULTIPLE UNIT V;lAL kC LRUS
Page 486 and 487: 3.1 CLASS 1E AUXILIARY STEAM TCRBIN
Page 488: envirorments. with the presence of
Page 491 and 492: NUCLEAR POWER PLANT DESIGN CONCEPTS
Page 493 and 494: Table of Contents List of Tables Li
Page 495 and 496: Fiq n-1 Fig C2-1 Fig C2-2 Fig C2-3
Page 497 and 498: 1.3 PURPOSE The purpose of this wor
Page 499 and 500: 2.1 DA.NAGE CONTROL ACTIONS The dam
Page 501 and 502: ased on a variety of events (e.y..,
Page 503: 2.2.4 Reactor Vessel Decay Neat Rem
Page 507 and 508: 5. Keeping damage control storage l
Page 511 and 512: V., ,"". van lour
Page 513 and 514: COMMENTS : . This may add another s
Page 515 and 516: ENGINEERING CONCERNS: The proper NP
Page 517 and 518: COMMENTS : I . . . . Hydraulic Limi
Page 519 and 520: ITEM: EVALUATION NO. 5 (PWR) Manual
Page 521 and 522: EVALUATION NO. 7 ITEM: (BWR) Substi
Page 523 and 524: , ; . ,. . ITEM : FUNCTION : EVALUA
Page 525 and 526: EVALUATION N e ITEM: (BWR) Provide
Page 527 and 528: ITEM: FUNCTION : EVALUATION NO. 12
Page 529 and 530: EVALUATION NO. 13 ITEM: (BWR 6 PWR)
Page 531 and 532: COMMENTS : . Any condensate used mu
Page 533 and 534: COMMENTS : Regulatoey concerns abou
Page 535 and 536: ENGINEERING CONCERNS: Some componen
Page 537 and 538: EVALUATION NO. 18 ITEM: (PWR) Steam
Page 539 and 540: ENGINEERING CONCERNS: A desiqn effo
Page 541 and 542: ITEM : FUNCTION : EVALUATION NO. 21
Page 543 and 544: EVALUATION NO. 22 ITEM: (BWR & PWR)
Page 545 and 546: F-G 0 OPERATIONAL CONSIDERAT1:ONS :
Page 547 and 548: ITEM: EVALUATION NO. 25 (PWR & BWR)
Page 549 and 550: 1 A 1: AVAllAR1.E TISE CASE SEI.ECT
Page 551 and 552: Case number: 2 Description: A charg
Page 553 and 554: Case number: 3 . . ~escription: The
Page 555 and 556:
Case number: 5 Description: The res
Page 557 and 558:
Case number: 6 Description: Loss of
Page 559 and 560:
TO Calculate the heat required for
Page 561 and 562:
Page 563 and 564:
Results: Assuming the initial condi
Page 565 and 566:
Case number: 10 Description: RHR pi
Page 567 and 568:
Case number: 12 Description: Drain
Page 569 and 570:
case Huther Table 8-22 AVAILAb1.E T
Page 571 and 572:
Page 573 and 574:
The heat required for each p h~se i
Page 575 and 576:
Page 577:
lr~ss-01 -cwlant yceater than charg
Page 580:
APPENDIX B: INITIAL APPROACH TO DAM
Page 583:
I i i i ~ClncheI :c .%r:a-;cw: ' w
Page 586 and 587:
however, not all systems listed by
Page 588 and 589:
Acquire Damage Assuming there are s
Page 590 and 591:
6. Establishing the Limits of Trans
Page 592 and 593:
TABLE 0-3: SABOTAGE TIME LINE RESUL
Page 594:
Hllog in fuel ull inuck LC
Page 598 and 599:
LC TIME MWIW ULSIW -ntsk:- l!*uf"l
Page 600 and 601:
3 lnqlne starts or rrtanpcs Ea star
Page 602 and 603:
2 Enqtce s:ops. wall nor car=/ load
Page 604 and 605:
" ., . Initratfan 0 sabotaqa event
Page 606 and 607:
0 enq-he starts or at:empts t3 Star
Page 608 and 609:
SXBCTACE XODE: 5tar:l-q alr tank de
Page 610 and 611:
inirration 0 Albms and indications
Page 612 and 613:
SYSTS..: Relidudl Heat Ramova?. jys
Page 614 and 615:
Initilz~on 0 Demand tar X. syeern.
Page 616 and 617:
Iaitiacion 0 Demand :sr Afi4 yYtel.
Page 618 and 619:
34-i~2 min. Note: Riarnq stem '~alv
Page 620 and 621:
SYSTZX: Auxa;;ar( Peedwe-er System
Page 622 and 623:
C~n=:?l Room Response u :ntar!al fo
Page 625 and 626:
:2itlrtion 0 Sabocaqe event occurs.
Page 627 and 628:
112-1147 min. IAsswrnq sp1ic:nq. no
Page 629 and 630:
Xiamo and :ndrcatrans 9-13 nm. Cont
Page 631:
SYSTPV: 48OV Class :E Electrical 3i
Page 634 and 635:
For each model (BWR and PWR), the f
Page 636 and 637:
FUNCTIONS - Primary Coolant Invento
Page 638 and 639:
Chemical and Volume Control System
Page 640 and 641:
electric power is interrupted, the
Page 642:
." ,.,- 4160 VAC (vital) 125 VDC TA
Page 645 and 646:
does not have an extensive power hi
Page 647 and 648:
TABLE C2-5 PAlN FEEDWATER SYSTEM i
Page 650 and 651:
ESW pumps are on standby with cooli
Page 653 and 654:
features (ESF) transformer. Table C
Page 655 and 656:
FIGURE C2-7 DC Electric Distributio
Page 657 and 658:
FIGURE CZ-8 Coinponent Coolli~g h'a
Page 659 and 660:
. ESW'S~S~~~. The ESW system could
Page 661 and 662:
C3. BOILING WATER REACTOR (BWR) APP
Page 663 and 664:
I - -1- -- .
Page 665 and 666:
via the main steam safety/relief va
Page 667 and 668:
250 VDC FUNCTIONS TABLE C3-3 HIGH P
Page 669 and 670:
125 VDC 4160 VAC (vital) Condensate
Page 671 and 672:
41 hU VAC 125 VIK' TABLE C3-5 CORE
Page 673 and 674:
I*.',. -.- taw Residual Iledt Remov
Page 675 and 676:
eactor vessel by manually dumping s
Page 677 and 678:
Service Water System
Page 679 and 680:
cooling on an individual basis. Suc
Page 681 and 682:
Emergency Service Water System FUNC
Page 683 and 684:
FIGURE C3-7 DC Electric Distributio
Page 685 and 686:
Therefore, onl: valves accessible f
Page 687 and 688:
, : %..- ~ DC 1. Reactor Water Leve
Page 689 and 690:
APPENDIX D: COMPUTER CALCULATIONS F
Page 691 and 692:
69 F i yur c 1)- 1 : HEACI'OR MOIIE
Page 693:
680.0 660.0 640.0 620.0 600.0 JBO.0
Page 696 and 697:
- - - - - - - - - STATION BLACKOUT
Page 698 and 699:
TIHE (SECONDS) XI0 j - 7 PHESSUHI Z
Page 700 and 701:
. LMTAI: 050141 [ 2Zon.tt I -1. I .
Page 704:
'-. - - - . - - - -- . . . HEAT S i
Page 707 and 708:
APPENDIX E: INDUSTRY SUR'JEYS At th
Page 709 and 710:
2. In the cases of the oil refineri
Page 711 and 712:
Concept De~e~lopment and Cost Estim
Page 714 and 715:
- PAGE ' 4.5 Cost Estimates for Iso
Page 716 and 717:
!;cl~crn;~tic Arrangemcrnt of ESF h
Page 718 and 719:
descriptions or descriptions of ope
Page 720 and 721:
2. SUWlARY Cost estimates for const
Page 722 and 723:
3. CONCEPT DEVELOPFIENT .3.1' .HARD
Page 724 and 725:
..: +". .. . . : ,. \,.L . . , .: f
Page 726 and 727:
., %W ; : ;,' : .? vent system cons
Page 728 and 729:
2 ft 6 in. 3 ft\ \ - N SLOPE SLOPE
Page 730 and 731:
Tank Capacity, Gal. Tank Diameter,
Page 732 and 733:
7 ft 6 in.
Page 734 and 735:
auxiliary feedwater and refueling w
Page 739:
................ ................ -
Page 748 and 749:
I .,I I , , . ............. .),.I.
Page 750:
I i , .. ! 'It-
Page 758:
LLYtL GMDL PLUS 73 it
Page 763 and 764:
and roof are of reinforced concrete
Page 766 and 767:
tection cabinets installed in the s
Page 768 and 769:
ndependent. Two ha? f-size tanks we
Page 770 and 771:
BORON INJECTION TANK No. Required T
Page 772 and 773:
Design Pressure, PSIG Design Temper
Page 774 and 775:
Doalgn Pranouto, PSIC 150 Design Te
Page 776:
. Provides for isolation of fluid l
Page 780:
I-- 38.7~1 (127 ftj Figare 3-21. U
Page 784 and 785:
I ( N.C.* I I I 4-kV CLASS 1E EMERG
Page 786 and 787:
, Alignment of reactor coolant pump
Page 788 and 789:
Electrical Power The major electric
Page 790 and 791:
The cooling air inlet and discharge
Page 792 and 793:
Design Temperature, "F Material of
Page 794 and 795:
Design Pressure, PSIS Deslqn Tcnper
Page 796 and 797:
DIESEL GENET(ATOR - LVBE OIL STORAG
Page 798 and 799:
Table 3-5 1:~:s the elping concecti
Page 800 and 801:
Loop J lC.L.1 Loop 1 lC.L.I-*:..mal
Page 802 and 803:
ability to isolate it to prevent lo
Page 804 and 805:
The excess letdown line is a small
Page 806 and 807:
4.1 GENERAL I 4. COST ESTIf4ATES Th
Page 808 and 809:
4.2.2 , Hardening Option 2, Reinfor
Page 810 and 811:
xcavat ion and Backfill Mat, 3 feet
Page 812 and 813:
TABLE 4-5 STUDY ESTIMATE, NOVEMBER
Page 814 and 815:
ITEM OF WORK TABLE 4-7 STUDY ESTIMA
Page 816 and 817:
The approach to the estimate, there
Page 818 and 819:
Substructure Excavation and Backfi
Page 820 and 821:
TABLE 4-10 STUDY ESTIMATE, NOVEMBER
Page 823 and 824:
6L:ained. In tk,e case of rne RHi+
Page 825 and 826:
TECHNICAL MPlORANDUn EVALUATION OF
Page 827 and 828:
TECHNICAL MEMORANWn ABGQNNE NATIONA
Page 829 and 830:
4.1 Sources of Information .4.2 Air
Page 831 and 832:
polar Plot for a11 hudiur hndira Ac
Page 833 and 834:
Thir report providu a revieu and ev
Page 835 and 836:
extenrively rtudied, but other crar
Page 837 and 838:
; 6 . ..,~ spective, presmt' polici
Page 839 and 840:
8 narios. mechaniraa, ad credibilit
Page 841 and 842:
ased on aircraft and topographical
Page 843 and 844:
IAU Safmty Gui& ad include the dete
Page 845 and 846:
4.1 Sources of Information 4. AIRCR
Page 847 and 848:
General Aviation refera to the oper
Page 849 and 850:
18 accounted for 81 percent of all
Page 851 and 852:
Table 1. Critical Civil Aviation Ac
Page 853:
Fig. 1 Polar Plot for all Canadian
Page 856 and 857:
2 5 procedures a d directions, misj
Page 858 and 859:
2 1 thane rerult umarired belw for
Page 860 and 861:
These race# aaruw tha: a crash can
Page 862 and 863:
hble 6 Detailed Crash btes - Fatal
Page 864 and 865:
DISTANCE FROM LANDING OR TAKE -OFF
Page 866 and 867:
the calculatiod where desirable. Bo
Page 868 and 869:
i are equivalent to randm craah eve
Page 870 and 871:
T PATH Fig. 5. Crash Sites Orthonor
Page 872 and 873:
accidents froll 1962 to 1966, 26 fi
Page 874 and 875:
Uircellaneous 0.01 mf* 0.02 mi2 tn*
Page 876 and 877:
4 5 large ones within 75 oiler. His
Page 878 and 879:
4 7 giw aircraft crashing into the
Page 880 and 881:
0 emergency core cooling system (EC
Page 882 and 883:
zero: Paat .xh?ience h a ahown that
Page 884 and 885:
5 3 lw it to deprearurirs the PHtS
Page 886 and 887:
mgklw imposed upon the plant struct
Page 888 and 889:
the calculatioru were repeated with
Page 890:
strength). The reaction load for th
Page 894 and 895:
Fig. 12 Displacements-Time-~Iiutori
Page 896 and 897:
cross-sectional area of the strikin
Page 898 and 899:
LOADING AREA REINPORCEYE STILL E'LA
Page 900 and 901:
4 6 lo-' 2 4 6 10 t? 2j3 PERIOD t s
Page 902 and 903:
Fig. 18 Comparinon of Response spec
Page 904 and 905:
I Fig. 22 Response Spectra. Compari
Page 906 and 907:
the gener.~?vicinity of the crash s
Page 908 and 909:
77 such an even nvironaent will be
Page 910 and 911:
, .';,,>,~robabilit~ . . . _ of occ
Page 912 and 913:
and conclurio 81 0 1 Aviation aircr
Page 914 and 915:
itself a coditional probability, co
Page 916 and 917:
acceptrblY -11, and the risk evalua
Page 918:
then aviation zones concentrate tra
Page 921 and 922:
Scenarios - Plan: methodologies for
Page 923 and 924:
REFERENCES 1. U.S. Nuclear Regulato
Page 925 and 926:
Crarrro, U. and Lucenet, C., "Zvalu
Page 927 and 928:
96 Viti, C., Olivieri, X., and Trav
Page 929 and 930:
Offslte Hazards: Aircraft Crash Typ
Page 931 and 932:
Offaite Hazards: Aircraft Crash Spe
Page 933 and 934:
so11.1tion of the dynamic analysic
Page 935 and 936:
I 104 airport. Inpact forciw functi
Page 937 and 938:
Offaite Hazards: Aircraft Crash Typ
Page 939 and 940:
Offsite rcraft Crash diagram and co
Page 941 and 942:
hi tr a numbar of techniques which
Page 943 and 944:
aircraft fraac is examined and it w
Page 945 and 946:
113 idual probabilities that an air
Page 947 and 948:
'Ihir paper giver a rrm~ry of extre
Page 949 and 950:
111 Offrite Rarardr craft Crash -pa
Page 951 and 952:
Internal: E. S. Beckjord C. E. Till
Page 953 and 954:
ABSTRACT The purpose of this projec
Page 955 and 956:
, . 5.0 HUMAN RELIABILITY ANALYSIS
Page 957 and 958:
Given an carthquakc large enough to
Page 959 and 960:
Relay chatter was not treated at al
Page 961 and 962:
6.1 lntroductlon SECTION 6 SUhlhlAR
Page 963 and 964:
were found to be important). These
Page 965 and 966:
6.3 Plant-spccllic lnslghts for LaS
Page 967 and 968:
11) We believe that, on balance, th
Page 969 and 970:
conservative but we are not certain
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SUBJECT: COMMENTS ON NRC PROPOSED RULE ...

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