ML20235Y381

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Rev 11 to Design Assessment Rept
ML20235Y381
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 02/28/1989
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20235Y344 List:
References
NUDOCS 8903140095
Download: ML20235Y381 (23)


Text

_______ __-_ _ _ _ _ _ _ _ _

I LIMERICK GENERATING STATION, UNITS 1 & 2 O DESIGN ASSESSMENT REPORT REVISION 11, PAGE CHANGES i

The attache 3 Revision 11 pages are considered part of a controlled copy of the Limerick Generating Station, DAR.

This material should be. incorporated into the DAR by following the instructions below.

Af ter the revised pages have been inserted, place the page that follows these instructions in the front of Volume 1.

REMOVE INSERT VOLUME 1 l

'Page s 7.1-2 3 thru 7.1-24 Pages 7.1-23 thru 7.1-24 Page 7.1-35 Page 7.1-35 Table 1.4-1 (Page 2 of 4) Table 1.4-1 (Page 2 of 4) l Table 4.2-3 Table 4.2-3 Table 5.9-1 (Page 1 of 2)- Table 5.9-1 (Page 1 of 2) l Table 5.10-1 (Page 1 of 2) Table 5.10-1 (Page 1 of 2) l Figure 5.6-1 (Sheets 1 and 2) Figure 5.6-1 (Sheets 1 and 2) -

Figure 5.6-2 (Sheets 1 and 2) Figure 5.6-2 (Sheets 1 and 2)

O Figure 5.6-3 Figure 5.6-4 (Sheets 1 and 2)

Figure 5.6-3 Figure 5.6-4 (Sheets 1 and 2) i i

VOLUME 2 I Table F.1-2 (Page 1) Table F.1-2 (Pages 1 and 2)

- Tab for Appendix K* i

- Appendix K, Page K-1 i

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  • Inse rt a'. cod of Appendix J.

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Re v . 11, 02/89 8903140095 890301 PDR ADOCK0500,{ay, P -

O I

THIS DAR SET HAS BEEN UPDATED TO INCLUDE REVISIONS THROUGH 11 DATED 02/89 0

O

LGS DAR 7.1.4 DOWNCOMER ASSESSMENT METHODOLOGY 7.1.4.1 Structural Model There are 87, 24-inch OD, steel pipe downcomers running vertically down from'the diaphragm slab. The downcomers are embedded in the diaphragm slab and extend downward to i El. 193'-11", which is approximately 12 feet below high water level, as shown in Figure 1.4-2. All downcomers are supported laterally at El 203'-5" by the downcomer bracing system. Any vertical loads are transmitted by the bracing system to the downcomers and therefore to the diaphragm slab.

The structural model considers th'e downcomer as a vertical pipe fixed at the underside of the diaphragm slab with a spring in the horizontal direction at bracing level. This model is shown in Figure 7.1-16. The inertial effect of the water in the submerged portion of the downcomer (12 feet) was approximated by the addition of a equivalent mass of water lumped at the appropriate nodal points. The model is evaluated for three spring values for a representative support stiffness provided by the bracing system to the downcomers. The bracing spring is set to 50 k/in, 350 k/in, and 15000 k/in to represent the tangential mode, the 9 radial mode, and rigid response of'the bracing system.

7.1.4.2 Loads The downcomer is subjected to static and dynamic loads due to normal, upset, emergency, and faulted conditions. Loading cases and combinations are described in Table 5.5-1. The basis for all hydrodynamic loads considered in the analysis is presented in Chapter 4.

7.1.4.3 Analysis Downcomers are analyzed for the specified loading conditions using the Bechtel computer program BSAP. The downcomers are analyzed for both the hydrodynamic loads acting directly on the submerged portions and the inertial forces due to containment responses to the hydrodynamic and seismic loads.

The hydrodynamic load analyses, due to SRV discharge and LOCA related loads acting on the submerged portion of the downcomers, G are performed using the mode-superposition time history 7.1-23 Rev. 2, 03/83

l l 1

LGS DAR 1

technique. The seismic and hydrodynamic load analyses, due to containment responses, are performed using the response-spectrum analysis procedure. Damping values used are equal to 2 percent s of critical 'for OBE and SRV loads, and 7 percent of critical for 1 SSE and LOCA loads.

7.1.4.4 Desion Assessment t The resultant stresses in the downcomers due to the load combinations described in Table 5.5-1 are compared with the allowable stresses in accordance with the criteria given in Reference 6.4-2.

7.1.4.5 Faticue Evaluation Of Downcomers In Wetwell Air Space A fatigue analysis of the downcomers was conducted in accordance with ASME Section III, Division 1 (1979 Summer Addendum), ',

subsection NB-3650. Only that portion of the downcomer in the air space of the suppression chamber need be evaluated for fatigue. Figures D.2-8 and D.2-9 of Appendix D show the number  ;

of cycles considered and the load histogram, respectively, i 7.1.5 BOP PIPING AND SRV SYSTEMS ASSESSMENT METHODOLOGY BOP piping and SRV systems were analyzed for the load combinations described in Table 5.6-1 using Bechtel computer program HE101. This program is described in FSAR Section 3.9.

Hydrodynamic load considerations are provided in Section 5.6.

Static and dynamic analysis of the piping and SRV systems are performed as described in the paragraphs below.

Static analysis techniques are used to determine the stresses due to steady state loads and/or dynamic loads having equivalent static loads.

Response spectra at the piping anchors are obtained from the dynamic analysis of the containment subjected to LOCA and SRV loading. Piping systems are then analyzed for these response spectra following the method described in Reference 7.1-8.

Alternatively, the multiple response spectra / independent support motion method of analysis may be used where distinct response spectra are applied to the piping system attachment points.

Time history dynamic analysis of the SRV discharge piping subjected to fluid transient forces in the pipe due to relief valve opening is performed using Bechtel computer code ME101. lll Rev. 11, 02/89 7.1-24 l

]

LGS DAR

(')

(_/'

7.1-2 Wilson, E. L, "A Computer Program for the Dynamic Stress Analysis of Underground Structures," USAEWES, Control j

Report 1-175, January 1968.

7.1-3 Desai and Abel, " Introduction to the Finite Element Method," Van Nostroid Reinold Co., 1972 7.1-4 " Technical Bases for the Use of SRSS Method for j Combining Dynamic Loads for Mark II Plants,"

NEDE-24010-P, General Electric Co, July 1977.

7.1-5 Caldwell, M.K. and Whittle, J.J. "In-Plant Test Report i for Adjacent Structure Response to Hydrodynamic ,

(Mark-II) Loads", Philadelphia Electric Company -  :

Limerick Generating Station, July 28, 1982.

7.1-6 Davis, W. M.. "MK II Main Vent Lateral Loads Summary Report," NETE-23806-P, General Electric Co., October j 1978.  ;

l p)

(,

7.1-7 T. E. Johnson, et al., " Containment Building Liner Plate Design Report," BC-TOP-1, Bechtel Corporation, San Francisco, December 1972.

1 7.1-8 " Seismic Analysis of Piping Systems," BP-TOP-1, Revision 3, Bechtel Power Corporation, San Francisco,  ;

January 1976.

7.1-9 IEEE Standard 344-1975, " Seismic Qualification of Class 1E Equipment for Nuclear Power Generating l Stations." .i 7.1-10 American Institute of Steel Construction, Manual of i Steel Construction, 7th Edition, 1970.

7.1-11 " Cable Tray and Conduit Raceway Seismic Test Program-Release 4", Test Report #1053-21.1-4, Volumes 1 and 2, ANCo Engineers, Inc., December 15, 1978. ,

1 7.1-12 " Development of Analysis and Design Techniques from l Dynamic Testing of Electrical Raceway Support Systems",

( Technical Report, Bechtel Power Corporation, July 1979.

7.1-35 Rev. 11, 02/89

{

l LGS DAR j l

l' T : TABLE 1.4-1 (Cont'd) (Page 2 of 4)

\_s! i Suppression Drywell Chamber VENT SYSTEM Number of downcomers 87(*)

Nominal downcomer diameter, ft 2 <

Downcomer area (each), fta 2.95 Downcomer submergence, ft Low water level 10' Norma 1' water level 11' High water level 12'-3" l Downcomer loss' coefficient (including exit loss) 2.23(8) l j SAFETY RELIEF VALVES Number 14 Spring Set Pressures, Mass Flow Rates: , i l'

Mass Flow (lbm/hr) at 103% of Spring Valve , Set Pressure (psial Set Pressure A 1150 917,000 i B 1150 917,000 C 1150 917,000 D 1140 909,000  !

E* 1140 909,000 .

F 1150 917,000 G 1150 917,000 H* 1130 901,500 J 1130 901,500 Rev. 11, 02/89 i

LGS DAR l

q TABLE 4.2-3 LGS PLANT UNIQUE POOLSWELL CODE INPUT DATA 1'

l l

l Downcomer area (each) 2.95 fta l Suppression pool free surface area 4973.89 fts (outside pedestal)

, Maximum downcomer submergence 12.25 ft Downcomer loss coefficient 1.23 l (without exit loss)

Number of downcomers 87 Initial wetwell pressure 15.45 psia Wetwell free air volume 149,425 ft8 Vent clearing time 0.7107 see Slug velocity in downcomer at' vent clearing 3.096 ft/sec Initial drywell temperature 1350F Initial drywell relative humidity 0.20 Downcomer friction coefficient, f 0.0115 (nominal)

Bubble initialization parameter (nominal) 50 1

O l Rev. 11, 02/89

_ _ _ _ _ _ _ _ --- -_ )

Page 1 of 2 LGS DAR TABLE 5.9-1 LOAD COMBINATIONS AND ALLOWABLE STRESSES FOR ELECTRICAL RACEWAY SYSTEM Allowable Equation Condition Load Combination Stress 1 Normal D+L+S RV Fs 2(1) Normal / Severe D+E (2) 3 Abnormal / Extreme D+E'+SRV+LOCA (2,3)

(1) Applies only to connections for fatigue considerations.

(2) The following equation is applicable for connections:

Sn n E0 + E0 < l.0

~

NOBE NSSE where:

O nE0

= Total number of load / stress cycles per earthquake.

NOBE = Allowable number of load / stress cycles per OBE event.

NSSE = Allowable number of load / stress cycles per SSE event.

(3) In no case shall the allowable stress exceed 9.90 P y in bending, 0.85 F in axial tension or compression, and 0.50 Fv in shear. Wkerethedesignisgovernedbyrequirementsof stability (local or lateral buckling), the actual stress shall not exceed 1.5 F 3 Notations:

Fg = Allowable stress for normal condition l D = Dead weight of raceway and cables L = A 200 lb concentrated live load is applied at any point on cable trays only between supports E = Load due to operating basis earthquake (OBE)

O Rev. 11, 02/89

Page 1 of 2" ]

1 LGS DAR l

) TABLE 5.10-1 LOAD COMBINATIONS AND ALLOWABLE STRESSES FOR HVAC DUCT SYSTEMS l DUCTS Allowable Equation Condition Load Combination Stress 1 Normal D+ L+S RV Fs 2 Normal D+PMSRV F3 3 Abnormal D+PT 1.25Fs 4 Normal / Severe D+PM+E 1.25F s 5 Normal / Severe D+ Pg +E +S RV 1.25F s 6 Normal D+Po Fs 7 Normal / Severe D+Po+E 1.25F s 8 Normal / Extreme D+Po+E' '(2) 9 Normal / Extreme D+PM+E ' +S RV (2) 10 Normal / Abnormal D+Po+P A+E ' +S RV+LOCA (2) 11 Normal / Abnormal When protection against tornado depressurization is required:

D+Po+Wo+SRV+LOCA (2)

)

'/

12 Ex treme/Ab normal For ducts inside drywell of containment, the following additional load combination is also ,

applicable:'

D+HA+Po+PA+E'+SRV+LOCA (2)

DUCT SUPPORTS Allowable Equation Condition Load Combination Stress 1 Normal E+L+SRV Ps 2 Normal / Severe D+E 1.25F s 3 Normal / Severe D+ E + S RV 1.25F s (1)l 4 Extreme / Abnormal D+E ' +S RV+LOCA (2)

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l PENE- TYPE OF ELEVATION DIMENSION LINE No. QTY SYSTEM FRATION PENE- l No. TRATION A B C X  !

COME X EMBEDOED 192'0" 192'4 " 192'0" 1'4" 19" HSB 120 4 gpgAy g RHR X EMBEDOED 192' 0 " 192'0" 192'0" 1'11" 24" HSB 117 4 ,

6" HS8-102 1 RCIC X 214 EMBEDOED 192'4 1/9" 192'0" 191'2 7/8" 0'11 5/8" v

19" HSB 109 1 HPCI X 200 EMBEDOED 193'4 " 192'0" 190'7" 1' 6" N X \

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LIMERICK GENERATING STATION UNITS 1 AND 2 DESIGN ASSESSMENT REPORT STRESS DIAGRAMS AND TABLES FOR PIPING SYSTEMS BELOW SUPPRESSION

. CHAMBER WATER LEVEL (UNIT 1)

SHEET 1 OF 2 F1GURE 5.61 REV.11,02/89

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PENE. TYPE OF ELEVATION DIMENSION LINE No. QTY SYSTEM rRATION PENE-No. TRATION A B C X E X 16" HBB 220 4 g$p y g EMBEDDED 192'4 " 192'0" 192'0" 1 '4" 24" HBB-217 4 RHR Xg, EMBEDDED 192'-0" 192'0" 192'0" 1'11" 6"-HBB-202 1 RCIC X 214 EMBEDDED 192'9 1/8" 192'0" 191'2 7/9 0'11 5/8" 16"-HBB 200 1 HPCI X 209 EMBEDDED 193'4 " 192'0" 190'7" 1 '4"

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UNITS 1 AND 2 DESIGN ASSESSMENT REPORT STRESS DIAGRAMS AND TABLES FOR PIPING SYSTEMS BELOW SUPPRESSION CHAMBER WATER LEVEL (UNIT 2)

SHEET 2 OF 2 FIGURE 5.61 REV.11,02/89 L-___-________________--__-

,p s .: sse PENE- TYPE OF ELEVATION l DWG LINE No. OTY SYSTEM TRATION PENE-No. No. TRATION A B B 4" HBD 187 1 HPCI X 212 EM8EDOED 207'4 " 190'11" HPC' X 236 EMBEDDED 207'6" 190'11" B 4".HBD 188 1 HPCI X 210 SLEEVE 207'4 " 192'4 "

A 24"-HBD 189 1 B 4"-HBD 171 2 kk((y k:lg8 EMSEDDED N 190'11" 190'11" B 10" HBD 189 2 kk((y k:lN EM8EDDED 219' 0" A 2 RHR X 204A,8 SLEEVE 219'0" 197'4 "

18" GBD 143 RHR X 226A,8 SLEEVE 207'.0" 199'111/2" A 4" GBD 144 2 RCIC x.215 SLEEVE 207'4 " 199'11" A 12" HBD 173 1 RHR X 240 EMBEDDED 207'3 1/4" 199'81/4" B 6" HBB 139 1 A 10" HBB 140 1 RHR X 238 SLEEVE 207'9" 199*11" A RHR X 239 SLEEVE 207'1" 199'11" 10" HBB 140 1

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SHEET 1 OF 2 FIGURE 5.6 2 REV.11,02/89

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B 10" HBD 260 2 kk((y k:lN EMBEDDED 219' 0" 199'.11" e 0 18" GBD 243 2 RHR x.204A,B SLEEVE 219'0" 199'.11" <

A 4" GBD 244 2 RHR X 226A,6 SLEEVE 207' D" 199'.11" e A RCIC x.215 SLEEVE 207'-6" 199'-11" d 12".HBD 273 1 B 6".HBB 239 1 RHR x.240 EMBEDDED 207'.6" 199'.11" <

A 10".HBB.240 1 RHR X 238 SLEEVE 207'9"- 199'.11" e A 10" HBB 240 1 RHR X 239 SLEEVE 207'.1" 199'11" <

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DWG.No. LINE No. OTY SYSTEM EL A A

12" 6 m & 3 M.S.R.V. DISCHARGE PlPING 186'6

O 8 00C 301 IN"*I 08C 201 11 UW C,8,1 M.S.R.V. DISCHARGE PIPING LINES A,D,E,F,G,H,K,L,M,N,5 186'4

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i I PENE. RADIUS ELEVATION DIMENSION DWG LINE No. OTY SYSTEM TRATION OF SPRAY l No. RING, R A B C X l A 6" GF,C 112 1 RHR X 206A 21'6" 2?2'41/2" 229' 113/B 230'6" 3'-8" B 6" GBC 112 1 RHR X 205B 32 '-8 " 222'-4 1/2" -

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SHEET 1 OF 2 FIGURE 5.64 REV.11,02/89

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SHEET 2 OF 2 FIGURE 5.6-4 REV.11,02/89

wnes* === en SU3 Maximum Calcw I .C./ 8" Normal /

Pipina System 0.C. Upset Eme

. Reactor Water Cleanup I.C. 10073 2l

< 0.C 10904 1{

0.C 9712 (

Residual Heat Removal I.C 11698 1-0.C. 12074 1(

0.C. 17123 11 Core Spray I.C. 11246 1C 0.C. 12200 if 0.C. 15041 19 Fuel Pool Cooling I.C. 6019 (

and Cleanup I.C. 13505 (

, D.C. 6577 9 High Pressure Coolant I.C. 11438 1!

Injection 14646 D.C. 1(

su Design Margin = 1 - Max. Stress Allowable Stress

'" I.C. = Inside Containment 0.C. = Outside Containment l

W %p w_ _ _ _ _ _ _ _ _ _ _ _ . - . _ _

, LCS DAR TABLE F.1-2 (Page 1 of 2)

(UNIT 1) l

)Y OF BOP PIPING STRESSES Stress Ratio '8'

= Maximum Stress Allowable Stress ed Str se (PSI)

Normal / Reference Stress ency Faulted Upset Emeroency Faulted Calculation 34 27081 .615 .938 .826 1-10-118 Rev. 2

}1 20698 .571 .528 .542 P1-37-52 Rev. 3 12 9712 .509 .339 .255 R1-37-53 Rev. O 13 16282 .697 .450 .485 1-10-05 Rev. 3

)7 23241 .671 .726 .646 1-10-658 Rev. 1 13 19928 .951 .645 .554 P1-10-75 Rev. 2

@ 14942 .670 .405 .397 1-20-02 Rev. 4 13 14573 .678 .494 .405 P1-20-54 Rev. 3

@. 17415 .836 .632 .484 P1-20-56 Rev. 1

@ 16996 .334 .187 .472 1-33-01 Rev. 3 0 21389 .750 .307 .594 1-33-02 Rev. 5 9' 10232 .299 .213 .233 1-33-62 Rev. 1 52 17089 .635 .409 .479 1-01-03 Rev. 4 0 20304 .814 .627 .564 P1-10-72 Rev. 1 l

SI APERTURE CARD Also Available On Aperture Cani Rev. 11. 02/89 890814009s -0 3 _

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Maximum Calcult I.C./'8' Normal /

Pipina System 0.C. Upset Eme7!

Reactor Water Cleanup I.C. 5449 10 0.C 11319 i ii 0.C.

Residual Heat Removal I.C. 11698 1 11 0.C. 16857 22 0.C. 16365 28 Core Spray I.C. 12956 12c 0.C. 12164 12C O.C. 12524 13 Fuel Pool Cooling I.C. 16806 24!

and Cleanup I.C. 6019 5:

0.C. 4191 1 41 High Pressure Coolant I.C. 17591 13:

Injection O.C, .16365 28

'5' Design Margin = 1 - Max. Stress Allowable Stress 4

I.C. = Inside Containment 0.C. = Outside Containment

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LGS DAR TABLE F.1-2 (Page 2 of 2)

-(UNIT 2) l

)Y OF BOP , PIPING STRESSES ll Stress Ratio = Maximum Stress Allowable Stress rd Stress (PSI)

Normal / Reference Stress

'ncy Faulted Upset Emeroency Faulted Calculation 11 27069 0.303 0.643 0.825 2-10-11, Rev. 4 29 12786 0.593 0.398 0.335 2-37-63, Rev. 4 13 16282 0.697 0.450 0.485 2-10-05, Rev. 3 25 23016 0.935 0.841 0.639 2-10-84, Rev. 4 0 25674 0.909 0.777 0.713 2-10-83, Rev. 5 0 19218 0.688 0.440 0.510 2-20-02, Rev. 4 32 15565 0.676 0.469 0.432 2-20-64, Rev. 5

@ 15462 0.696 0.487 0.429 2-20-63, Rev. 4 0 28986 0.467 0.673 0.805 2-33-02, Rev. 3 s@ 16996 0.334 0.187 0.472 2-33-01, Rev. O

)2 15395 0.233 0.546 0.428 2-43-02, Rev. 1

@ 22274 0.977 0.506 0.619 2-01-03, Rev. 4 G 25674 0.909 0.777 0.713 2-10-83, Rev. 5 l I SI APERTURE CARD Also Available On  ;

Aperture Card i i

l Rev. 11, 02/89 i

. ~ . . , . . .

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i LGS DAR APPENDIX K REVISION

SUMMARY

DESCRIPTIONS Appendix K provides a summary description of the significant design changes or issues that are incorporated in-each revision of.the~DAR. The sections, tables, or figures of the DAR which are affected are noted together with the narrative  ;

summary of each significant change. Changes apply to both units unless otherwise noted.

l K.1 REVISION 11

SUMMARY

DESCRIPTIONS K.l.1 TABLES 1.4-1 and 4.2-3 These tables were revised to reflect the change described in FSAR revision summary description B.13.6.

i l

'0

-l O

K-1 Rev. 11, 02/89

_ _ - _ - _ _ _ - _ _ _ _ _ _ _ .__- _ _-_-___ __ _- _ _---___-_- _-.__---_-__--_ - --_-_-_ _ _-__- -_.___ - - - ___-__O