Text

Forwards Update to 1996 FSAR for Donald C Cook Nuclear Plant Units 1 & 2,per Provisions of 10CFR50.71(e).Update Presents Changes Made from 950122 Through 960122
	ML17334B597
Person / Time
Site:	Cook
Issue date:	07/22/1996
From:	Fitzpatrick E; AMERICAN ELECTRIC POWER CO., INC.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17334B598	List: ML17334B597;
References
	AEP:NRC:0509S, AEP:NRC:509S, NUDOCS 9607290048
	Download: ML17334B597 (145)
	v • d • e

~~ J. ~~MML J.

A REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

)

ACCESSION NBR:9607290048 DOC.DATE: 96/07/22 NOTARIZED: NO DOCKET FACIL:50-315 Donald C.

Cook Nuclear Power Plant, Unit 1, Indiana M

05000315 50-316 Donald'.

Cook Nuclear Power Plant, Unit 2, Indiana M

05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.E American Electric Power Co., Inc.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards update to 1996 FSAR for Donald C Cook Nuclear Plant Units 1

& 2,per provisions of 10CFR50.71(e)

DZSTRZBUTZON CODE:

A053D COPZES RECEZVED:LTR

~

ENCL JO SZSE: Z +F9(D TITLE: OR Submittal:

Updated FSAR (50. 71) and Amendments NOTES:

RECIPIENT ID CODE/NAME PD3-1 PD INTERNAL: AEOD/DOA/IRB RGN3 EXTERNAL: IHS NRC PDR COPIES LTTR ENCL 1

0 1

1 1

1 RECIPIENT ID CODE/NAME, HICK J

ILE CENTER 0.

NOAC COPIES LTTR ENCL 1

1 2

2 1

1 0

D N

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE!

CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083)

TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 9

ENCL 8

American Electric Power 1 Riverside Plaza Columbus. OH 43215 2373 614 223 1000 PPP ANERlCAN-ELECTREC POWER July 22, 1996 AEP:NRC:0509S Docket Nos.:

50-315 50-316 U.

S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.

C.

20555 Gentlemen:

Donald C.

Cook Nuclear Plant Units 1 and 2

1996 FINAL SAFETY ANALYSIS REPORT UPDATE Attached are ten copies of the changed pages for the 1996 update 'to the Cook Nuclear Plant Final Safety Analysis Report (FSAR).

These pages are being transmitted to you according to the provisions of 10 CFR 50.71(e}.

Instructions for incorporating the update are included with each copy.

In addition to vertically barring the specific

change, changed pages have been dated "July 1996" in the lower right corner.

Uertical change bars next to the July 1996 date indicate that the information has only shifted pages.

We hereby certify that the information contained in this update to the FSAR, to our knowledge, accurately presents changes made to the plant from January 22,

1995, through January 22, 1996.

We note that we are in the process of performing a comparison of the FSAR to the plant design and operations.

Sincerely, u/4 E.

ED Fitzpatrick Uice President

/jen Attachment 9607290048 960722 PDR ADOCK 05000315 K

PDR

~

U.

S. Nuclear Regulatory Commission Page 2

AEP:NRC:0509S cc:

A. A. Blind H. J. Hiller NFEH Section Chief NRC Resident Inspector

- Bridgman J.

R. Padgett

Page VOLUME I Chapter 1

Introduction and Summa Fig.

Table Fig.

Fig.

Pacae

1. 0-1 1 ~ 0-2 1.0-3

1. 1-1

1. 1-2

1. 1-3 1 ~ 1-4 1-1 1.2-1 1.2-2" 1.2-3 1.2-4 1.2-5 l.2-1 (6 pages) 1.3-1 1.3-2 1.3-3 1.3-4 1 ~ 3-5 1.3-6 1.3-7 1.3-8 1.3-9 113-1 1 03-2 1'-3 1.3-4 1.3-5 1.3-6 103-7 1.3-8 1.3-9 1.3-10 1.3-11 1.4-1 1.4-2 1.4-3 1.4<<4 1.4-5

~

1.4-6 1.4-7 1.4-8 1.4-9 1.4-10 1.4-11 Date 1988 1994 1989 1982 1982 1982 1982 ORIG 1993 1993 1993 1991 1995 1989 1982 1982 1982 1984 1982 1982 1982 1994 1982 1995 1990 1990 1990 1990 1990 1990 1993 1993 1993 1982 1991 1991 1987 1987 1991 1982 1991 1991 1982 1987 1991

0

Page VOLUME I Chapter 1

Introduction and Summa Tabl Pacae

1. 4-12

1. 4-13

1. 4-14 1.4-15 1.4-16

1. 4-17 1.4-18 1.4-19 1.4-20 l.4-21" 1.4-22 1.4-1 (pg 1)

(pg>>

(pg 4) 1.5-1 1 ~ 6-0

1. 6-1 1.6-2 1.6-3 l.6-4

1. 6-5 1.6-6 1 ~ 6-7 1.6-8 1.6-9

1. 6-10

1. 6-11

1. 6-12

1. 6-13

l. 6-14 1.6-15 l.6-16

1. 6-17 1.6-18 1.6-19 1.6 "20 1.6-21

1. 6-22

1. 6-23

1. 6-24

l. 6-25 Table 1.6-1 (pg 1)

(pg 2)

(pg 3)

(pg 4)

(pg 5)

(pg 6)

(pg 7)

(pg 8)

(pg 9)

(pg 10)

Date 1991 1994 1994 1991 1993 1987 1987 1994 1992 1991 1991 1991 1991 1991 1991 1982

.1984 1983 1983 1982 1982 1983 1982 1983 1982 1982 1983 1982 1983 1982 1985 1985 1985 1985 1985 1992 1985 1985 1985 1985 1985 1992 1989 1989 1989 1989 1989 1989 1989 1989 1989 1989

Page 3

VOLUME I Chapter 1

Introduction and Summa Pacae Date Table 1.6-1 (pg 11)

(pg 12)

(pg 13)

(pg 14)

(pg 15)

(pg 16)

(pg 17)

(pg 18)

(pg-19)"

(pg 20)

(pg 21)

(pg 22)

(pg 23) 1.7-1

1. 8-1

1. 9-1 1989 1989 1989 1989 1989 1990 1989 1989 1989 1989 1989 1991 1993 1994 1989 1982

Page 4

VOLUME I Chapter 2

Site and Environment Table Table Table Table Table Table Table Table Table Table Table

-Table Table Table Table Table Fig.

Fig.

Pacae 2'-1 201-2 2.1-3

2. 1-4 2.1-5

2. 1-6 2 ~ 1 7

2. 1-8

2. 1-9 2'.1=10" 2 ~ 1-11 2.1-12 2 0 1-13 201-1

2. 1-2 2 ~ 1 3

2. 1-4 DELETED

2. 1-5

2. 1-6

2. 1-6a 201-7

2. 1-7a 2.1-8 2.1-8a

2. 1-8b

2. 1-9 2.1-10

2. 1-11

2. 1-12 201-1

2. 1"2 201-3

2. 1-4

2. 1-4a 2.1-4b 2.1-5 2.1-6

2. 1-6a 2.1-6b 211-7 2.1-7a

2. 1-7b 2.1"8

2. 1-8a 2.1-8b 2 ~ 1-9

2. 1-10 2.2-1 2 ~ 2 2 202-3 2.2-4 2.2-5 2.2-6 2 '-7 Date 1991 1993 1993 1982 1993 1993 1995 1995 1995 1995'995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1982 1982 1993 1982 1982 1993 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1993 1993 1994 1993 1995 1995 1995 1995 1993

Page 5

Chapter 2

Site and Environment VOLUME I Pacae Date Fige Fig.

Fige Fig.

Fig.

Fige Fig.

Fig.

Fige Fig.

Fige

Fig, Fige 2.2-8 2.2-9 2.2-10 2.2-11

2. 2-12 2.2-13 2.2-14 2.2-15 2.2-16

2. 2-17 2.2-18 2.2-19 2.2-20 2.2-21 2.2-22 2.2-23 2'-1 2 '-2 2

~ 3 3

2.3-4 2.3"5 2.3-1 203-2 2.4-1 2.4-2 2.4-3 2.4-4 2.4-5 2.4-6

2. 5-1 2.5-2 2.5-3 2.5-4 2.5-5 2.5-6 2.5-7 2'-8 2.2-9 2.2-10 Table 2.2-1 Table 2.2-2 Table 2.2-3 Table 2.2-4 Table 2.2-5 Table 2.2-6 Table 2.2-7 Tabl'b" 2.2'=8 Table 2.2-9 Fig. 2. 2-1 Fig. 2.2-2 Fig. 2.2-3 Fig. 2.2-4 Fig. 2.2-5 Fig. 2.2-6 Fig. 2.2-7 1995 1994 1993 1993 1993 1993 1993 1993 1993 1993

'1993 1993 1982 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1992 1982 1995 1982 1982 1982 1982 1982 1982 1984 1984 1982 1988 1982 1982 1982 1982 1982 1982 1982 1982

Page 6

VOLUME I Chapter 2

Site and Environment Pacae Date Table Fig.

Fig.

Fig:"

Fig.

Fige Fig.

Fig.

2. 5-1 (2pp) 2.5-1 2.5-1a 2.5-2 2.5-3 2.5-3a 2.5-3b 2.5-3c 2"; 5= 3d""

2.5-3e 2.5-3f 2 '-3g 2.5-3h 2.5-3i 2.5-3j

2. 6-1 2.6-2 2.6-3 2.6-4 2.6-5 2.6-6 2.6-7 2.6-8 2.6-9

2. 6-10

2. 6-11

2. 6-12

2. 6-13 2.6-14 2.6-15 2.6-16

2. 6"17 2.6-18 2.6-19 2.6-20 2.6-21 2.6-22 2.6-23 2.6-24 2.6-25 2.6-26 2.6-27 2.6-28 2.6-29 2.6-30 2.6-31 2.6-32 2.6-33 2.6-34 2.6-35 2.6-36 2.6-37 2.6-38 2.6-39 1989 1982 1982 1982 1982 1982 1982 1982

'1982

'982 1982 1982 1982 1982 1982 1993 1992 1992 1992 1992 1993 1992 1992 1992 1992 1993 1993 1993 1992 1992 1992 1993 1993 1993 1993 1993 1993 1992 1992 1992 1993 1992 1992 1992 1993 1993 1992 1993 1993 1992 1992 1992 1992 1992

0

Page 7

.VOLUME I Chapter 2

Site and Environment Pacae Table Table Table Table Table-Table Fige Fig.

Fige Fig.

Fig.

2 Fig.

2 Table Table Table Table Table Fig.

Fige 2.6-40 2.6-41 2.6-42 2.6-43 2.6-44 2.6-44a 2.6-1 2.6-2 2.6-3 2.6-4 2;6-5--

2.6-6 2 '-1 2.6-2 2.6-3 2.6-4

.6-5

.6-6

.6-7

.6-8

.6-9

.6-10

. 6-11

. 6-12 2 ~ 7 1 2 ~ 7 2

2.7-3 2.7-4 2.7-5 2 '-6 2'-7 2.7-8

2. 7-1 2.7-2 2.7-3 2.7-4

2. 7-5 (pg (pg (pg (pg 217-1 2 ~ 7 2

DELETED DELETED DELETED DELETED 1)DELETED 2)DELETED 3)DELETED 4)DELETED DELETED DELETED Date 1992 1992 1992 1993 1993 1993 1992 1992 1992 1992 1992" 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995

Page 8

Chapter 2

Site and Environment VOLUME I Parcae Date 2.8-1 2.8-2

2. 9-1 2.9-2 2.9-3 2.9-4 2.9-5 2.9-6 2.9-7

~ 2.9-8"

'.9-9

2. 9-10

2. 9-11

2. 9-12 2.9-13 2.9-14 2.9-15 2.9-16

2. 9-17

2. 9-18 Table 2.9-1 (3pp)

Table 2.9-2 (5pp)

2. 10-1

2. 10-2 1989 1982 1982 1982 1982 1992 1990 1983 1991 1994.

1995 1994 1994 1994 1994 1994 1994 1994 1995 1995 1994 1994 1994 1994

Page 9

VOLUME II Chapter 3

Reactor Unit 1 Pacae

3. 1-1 3.1-2 3

~ 1 3

3. 1-4

3. 1-5

3. 1-6

3. 1-7 3.1-8

3. 1-9

3. 1-10

~ i

3. 1-11 3 0 1-12 3 0 1-13

3. 1-14

3. 1-15 3.2" 1 312-2 302-3 3.2-4 3.2-5 3.2-6 3.2"7 3.2-8 3.2-9 3.2-10 3.2-11 3.2-12 3.2-13 3.2-14 3.2-15 3.2-16 3.2-17 3.2-18

3. 2-19 3.2-20 3.2-21 3 '-22 3.2-23 3.2-24 3.2-25 3.2-26 3.2-27 3.2-28 3.2-29 3.2-30 3

~ 2-31 Date 1994 1992 1994 1994 1994 1994 1994 1994 1994 1994-1990 1994 1994 1994 1994 1993 1982 1994 1982 1986 1982 1982 1982 1982 1982 1994 1982 1984 1982 1982 1982 1982 1983 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1995

Page 10 VOLUME II Chapter 3

Reactor Unit 1 Table Fig.

Fig.

Pacae 312-32 3

~ 2 33 3.2-34 3.2-35 3.2-36 3.2-37 3.2-38 3.2-39 3.2-40

3. 2=.43 3.2-42 3.2-43 3.2-44 3.2-45 3.2-46 3.2-47 3.2-48 3.2-49 3.2-50 3.2-51 3.2-52 3.2-53 3.2-54 3.2.1-1 (3pp) 3.2.1-1 3.2. 1-2 3.2. 1-3 3.2. 1-4 3.2.1-5 3.2.1-6 3.2. 1-7 3.2

~ 1-8 3.2.1-9 3.2.1-10 3.2.1-11 3.2. 1-12 3.2 '-13 3.2. 1-14 3.3-1 3'-2 3.3-3 3.3-4 3.3-5 3.3-6 3.3-7 3.3-8 3.3-9 3.3-10 3.3-11 Date 1982 1982 1983 1982 1982 1982 1982 1982 1982 1982.-

1982 1982 1983 1982 1987 1987 1994 1995 1995 1995 1995 1995 1995 1995 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1990 1992 1992 1982 1992 1992 1983 1983 1984 1990 1987

Page 11 VOLUME II Chapter 3

Reactor Unit 1 Table Table Table Table Fig.

Fige Fig.

Fig.

Fige Fig.

Fig.

Fige Pacae 3.3-12 3.3-13

3. 3-14 3.3-15 3.3-16 3.3-17 3.3-18 3.3-19 3.3-20 3>>3.-21--

303-22 303-23 3.3-24 3.3-25 3.3-26 303-27 3.3.1-1 (pg 1)

(pg 2)

(pg>>

3.3.1-2 3.3. 1-3 3.3.1-3a DELETED 3.3.1-1 3

~ 3 ~ 1 2 3

~ 3

~ 1-3 3.3.1-4 3.3. 1-11 3.3. 1-12 3

~ 3 0 1-13 3.3. 1-14 3 '.1-15 3.3. 1-16 3.3. 1-17 3.4-1 3.4-2 3.4.3 3.4.4 3.4.5 3.4-6 3.4-7 Date 1995 1982 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1993 1989 1990 1995 1990 1994 1990 1995 1995 1982 1984 1984 1984 1984 1984 1984 1984 1984 1984 1992 1990 1993 1993 1982 1982 1982 1993

Page 12 VOLUME II Chapter 3

Reactor Unit 1 Table Table Table Fig.

Fig.

Pacae 3.4-8 3.4-9 3.4-10 3.4-11 3.4-12 3.4-13 3.4-14 3.4 "15 3.4-16 3.. 4= 17 3.4-18 3.4-19 3.4-20 3.4-21 3.4. 1-1 (2pp) 3.4.1"2 3 ~ 4.1-3 3.4. 1-1 3.4.1-2 3.4. 1-3 3.4.1-4 3.4.1-4a 3.4. 1-5 3.4. 1-6 3.4.1-7 3.4.1-8 3.4.1-9 3.5-1 3.5.1-1 3.5.1-2 3.5.1-3 3.5.1-4 3.5. 1-5 3

~ 5. 1-6 3.5.1-7 3.5.1-8 3 '.1-9 3.5. 1-10 3.5. 1-11 3.5.1-12 3.5.1-13 3.5.1-14 3.5. 1-15 3.5. 1-16 3.5. 1"17 3.5. 1-18 Date 1993 1993 1982 1993 1987 1993 1993 1983 1982 1982....

1982 1982 1982 1982 1989 1989 1989 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1993 1995 1995 1995 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1990 1993

Page 13 VOLUME II Chapter 3

Reactor Unit 1 Table Fig.

Fig.

Table Table Table Fig.

Fig.

Table Table Table Table Fig.

Fig.

Pacae 3.5. 1-1 3.5. 1-1

3. 5 ~ 1-2 3.5.1-3 3.5.1-4 3.5.1-5 3.5.1-5a 3.5.1-6 3.5.1-7 3..5. 2=3..

3.5.2-2 3.5.2-3 3.5.2-4 3.5.2-5 3.5.2-6 3.5.2-1 3.5.2-2 3.5.2"3 3.5.2-1 3.5.2-2 3.5.3-1 3.5.3-2 3 '.3-3 3.5.3-4 3.5.3-5 3.5.3-6 3 '.3-7 3.5 '-8 3.5.3-9 3.5.3-10 3.5.3-11 3.5. 3-12 3.5. 3-13 3.5.3-14 3.5.3-1 (pg 1) 3.5.3-1 (pg 2) 3.5.3-1 (pg 3) 3.5.3-1 (pg 4) 3.5.3-1 3.5.3-2 3.5.3-3 Date 1995 1990 1990 1990 1990 1990 1992 1992 1992 1994-1992 1995 1995 1995 1995 1995 1991 1995 1995 1995 1995 1992 1990 1990 1992 1992 1993 1990 1992 1993 1990 1990 1992 1991 1992 1992 1990 1992 1990 1990 1990

Page 14 Chapter 3

Reactor Unit 2 VOLUME II Table Table Table Table Table Table Pacae

3. 1-1 3 ~ 1-2

3. 1-3

3. 1-4

3. 1-5 3.1-1 (Spp)

(Notes) 3

~ 1-2 (pgl)

3. 1-2 (pg2)

3. 1-2 (pg3) 3.1-2.. (pg4).;

~

301-3 3.2-1 302-2 302-3 3.2-4 3.2-5 3.2-6 3

~ 2 7

3.2-8 3.2-9 3.2-10 3.2-11 3

~ 2-12 3.2.13 3.2-14 3.2-14a 3.2-14b 3.2-15 3.2-16 3 02-17 3.2"18 3 '-19 3.2-20 3.2-21 302-22 3.2-23 3.2-24 3.2-25 3.2-26 3.2-27 3.2-28 3.2-29 3.2-30 3.2-31 3.2-32 3.2-33 3.2-34 3.2-35 Date 1991 1991 1991 1991 1991 1991 1994 1991 1991 1991 1989 1991 1982 1991 1982

.1991 1991 1982 1991 1991 1991 1991 1991 1991 1991 1994 1994 1994 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1994 1994 1995 1995 1995 1995

Page 15 Chapter 3

Reactor Unit 2 VOLUME II Pacae 3.2-36 302-37 3.2-38 3.2-39 3.2-40 3.2-41 3.2-42 3.2-43 3.2-44 3.2-45 3..2-.46...,.

3.2-47 3.2-48 3.2-49 3 '-50 3.2-51 3.2-52 3.2-53 3 '-54 3.2-55 3.2-56 3.2-57 3.2-58 3.2-59 3.2-60 3.2-61 3.2-62 3.2"63 3.2-64 3.2-65 3.2-66 3.2-67 3.2-68 3.2-69 3.2-70 3.2-71 3.2-72 302-73 3.2-74 3.2-75 3.2-76 3.2-77 3.2-78 3.2-79 3.2-80 3

~ 2-81 3.2-82 3.2-83 3.2-84 3.2-85 Date 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995

Page 16 Chapter 3

Reactor Unit 2 VOLUME II Pacae 3.2-86 3.2-87 3.2-88 3.2-89 3.2-90 3.2-91 3.2-92 3.2-93 3.2-94 Table 3.2-1

. Fig....3..2=3 Fig. 3.2-2 Fig. 3.2-3 Fig. 3.2-4 Fig. 3.2-5 Fig. 3.2-5a Fig. 3.2-6 Fig. 3.2-7 Fig.

3 '-8 Fig. 3.2-9 Fig. 3.2-10 Fig. 3. 2"11 Fig. 3.2-12 Fig. 3. 2-13 Fig. 3. 2-15 Fig.

3 '-16 Fig. 3.2-'17 Fig. 3.2-18 Fig. 3.2-19 Fig. 3.2-20 Fig. 3. 2-21 Fig. 3.2-22 Fig. 3.2-23 Fig. 3.2-24 Date 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1991-.,

1991 1991 1991 1991 1991 1991 1991 1982 1982 1982 1982 1982 1982 1982 1982 1982 1990 1982 1982 1982 1982 1982 1982

Page 17 Chapter 3

VOLUME III Reactor Unit 2 Pacae Date 3

~ 3 1

313-2 3

~ 3 3

3.3-4 3.3-5 3.3-6 3 ~ 3 7

3.3-8 3.3-9 3.3-10 3' 3

. 11>>

313-12 3.3-13 3.3-14

3. 3-15 3.3-16 3

~ 3-17 3.3-18

3. 3-19 3.3-20 3.3-21 303-22 313-23 3.3-24 3.3-25 3.3-26 303-27 3.3-28 3.3-29 3.3-30 3.3-31 303-32 3.3-33 3.3-34 3.3-35 3.3-36 3

~ 3 3 7 3.3-38 3.3-39 3.3-40 3.3-41 3.3-42 3.3-43 3.3-44 3.3-45 3.3-46 3.3-47 1991 1991 1991 1995 1991 1991 1991 1991 1993 1995 1991

~

1995 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1992 1995 1991 1991 1991 1995 1991 1991 1991 1991 1991 1991 1993 1991 1991 1991 1991 1991 1991 1991 1991 1995 1991 1991 1991

Page 18 Chapter 3

Reactor Unit 2 VOLUME III Table Table Table Table Table Table Table Table Fig.

Fig.

Pacae 3.3-48 3.3-49 3.3-50 3.3-51 3.3"52 3.3-53 3.3-54 3.3-55 3.3-56 3.3-57 3

3 58-. ~

3.3-59 3.3-60 3 '-61 3.3-1 (3pp) 3.3-2 (pg1) 3.3-2 (pg2) 3.3-3 3.3-4 3.3-5 3.3-6 3

~ 3 7

3

~ 3-1 303-2 3.3-3 3.3-4 3.3-5 3.3-6 3.3-7 3.3-8 3.3-9 3.3-10 Date 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1995 1991 1991 1991 1991 1991 1989 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991

Page 19 Chapter 3

Reactor Unit 2 VOLUME IlZ Fig.

Fig.

Pig.

Fig.

Pig.

Fig.

Pacae 3.3-11 3

~ 3 12 3

~ 3 13 3.3-14 3.3-15 3.3-16 303-17 3.3-18 3.3-19 3.3-20 3.. 3~21.-

303-22 3.3-23 3.3-24 3.3-25 3.3-26 313-27 3.3-28 3.3-29 3.3-30 3 ~ 3 3 1 313 32 3

~ 3 33 3.3-34 3.3-35 3.3-36 3 ~ 3 37 3.3-38 3.4-1 3.4-2 3.4-3 3.4-4 3.4-5 3.4-6 3.4-7 3.4-8 3.4-9 3.4-10 3.4-11 Date 1991 1991 1991 1991 1991 1991 1991 1991 1991 1995 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1982 1991 1991 1991 1993 1991 1991 1991 1991 1992 1991

Page 20 Chapter 3

Reactor Unit 2 VOLUME III Pa<ac 3.4-12 3.4-13 3.4-14 3.4-15 3.4-16 3.4-17 3.4-18 3.4-19 3.4-20 3

~ 4-21

3. 4~22..

3.4-23 3.4-24 3.4-25 3.4-26 3,4-27 3.4-28 3.4-29 3.4-30 3.4-31 3 '-32 3.4-33 3.4-34 3.4-35 3.4>>36 3.4-37 3.4-38 3.4-39 3.4-40 3.4-41 3.4-42 3.4-43 3.4-44 3.4-45 3.4-46 3.4-47 3.4-48 3.4-49 3 '-50 3.4-51 3.4-52 3.4-53 3.4-54 3.4-55 3.4-56 3.4-57 3.4-58 3.4-59 3.4-60 Date 1991 1991 1991 1993 1991 1991 1991 1991 1991 1991 1991.

1993 1991 1993 1991 1991 1991 1991 1993 1991 1993 1991 1991 1991 1991 1991 1991 1991 1993 1991 1991 1992 1991 1991 1993 1991 1991 1991 1991 1992 1991 1991 1991 1991 1991 1991 1991 1991 1991

Page 21 Chapter 3

Reactor Unit 2 VOLUME III Table Table Table Table.

Fig.

Pa<ac 3.4-61 3.4-62 3.4-63 3.4-64 3.4-65 3.4-1 (pg 1)

(pg 2)

(pg 3)

3. 4-2 3.4-3 (2pp) 3 4=4 3.4-1 3.4-2 3.4-3 3.4-4 3.4-5 3.4-6 3 '-7 3.4-8 3.4-9 3.4-10 3.4-11 3.4-12 3.4-13 3.4-14 3.5-1 3.5-2 3.5-3 3.5-4 3.5-5 3.5-6 3.5-7 3.5-8 3.5-9

3. 5-10 3.5-11 Date 1991 1991 1991 1991 1991 1992 1992 1991 1991 1991 1991...

1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1987 1991 1991 1991 1991 1991 1991 1991 1993 1991

Page 22 VOLUME III Chapter 3

Reactor Unit 2 Pacae

3. 5-12

3. 5-13 3.5-14 3.5-15 3.5-16

3. 5-17 3.5-18 3.5-19 3.5-20 Table 3.5.1-1 (2pp)

Table 3.5..1=2. (2pp)..

Table 3.5.1-3 Fig. 3. 5. 1-1 Fig. 3.5.1-2 Fig. 3.5 '-3 Fig. 3.5.1-4 3.5-26 3.5-27 3 '-28 Table 3.5.2-1 Date 1991 1991 1991 1991 1991 1991 1991 1987 1990 1991 1991..

1991 1983 ORIG 1991 1983 1991 1991 1991 1991

Page 23 Chapter 4

VOLUME III Reactor Coolant S stem Table Table Table Table Table Table Table Table Table Table Table Table Pacae

4. 1-1

4. 1-2 4.1-3 4.1-4 4.1>>5

4. 1-6

4. 1-7

4. 1-8

4. 1-9

4. 1-10

.4. 1".,11

4. 1-12

4. 1-13

4. 1-14 4.1-15 4.1-16 4.1-17

4. 1-18

4. 1-19

4. 1-20 4.1-21 4.1.22 4.1-23 4.1-24

4. 1-1

4. 1-2

4. 1-3 4.1-4 4.1-5

(

4.1-6 4.1-7

4. 1-8 4.1-9

4. 1-10

4. 1-11

4. 1-12 4.2-1 4.2-2 4.2-3 4.2-4 4.2-5 4.2-6 4.2-7 4.2-8 4.2-9

4. 2-3.0 4.2-11 4.2-12 pg 1) pg 2)

(pg 1)

(pg 2)

(3pp)

(2pp)

Date 1991 1991 1982 1982 1982 1982 1982 1982 1982 1982 1982*

1990 1990 1990 1990 1991 1982 1982 1989 1982 1982 1982 1982 1982 1990 1995 1990 1991 1991 1989 1989 1989 1989 1989 1990 1989 1989 1991 1982 1982 1982 1989 1982 1982 1982 1982 1994 1982 1989 1989

Page 24 Chapter 4

VOLUME III Reactor Coolant S stem Table Table Table Fig.

Figs Fig.

Fig.

Fige Fige Fig.

Fig.

Pacae 4.2-13 4.2-14 4.2-15

4. 2-16

4. 2-17 4.2"18 4.2-19 4.2-20 4.2-21 4.2-22 4.2-..23 4.2-24 4.2-25 4.2-26 4.2-27 4 '-28 4.2-29 4.2-30 4.2-31 4.2-32 4.2-33 4.2-34 4.2-35 4.2-36 4.2-1 (3pp) 4.2-2 4.2-3 4 ~ 2-1 4.2-1A 4.2-2 4.2-2A 4.2-3 4.2-4 4.2-4A 4.2-5 4.2-6 4.2-7 4.2-8 4.2-9 4.2-9 Ref.

4.3-1 4.3-2 4.3"3 4.3-4 4.3-5 4.3-6 4.3-7 4.3-8 4.3-9 (4pp)

Date 1989 1982 1982 1982 1995 1983 1991 1991 1991 1995 1982 1994 1982 1995 1982 1986 1982 1982 1982 1982 1982 1987 1987 1987 1989 1992 1994 1984 1988 1982 1982 1995 1982 1989 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1990 1982 1982

Page 25 Chapter 4

VOLUME III Reactor Coolant S stem Table Table Table Table Table Table Table Table Fig.

Fig.

Pacae 4.3-10 4.3-11 4.3-12

4. 3-13 4.3-14 4.3-15 4.3-16 4.3-17 4.3-18 4.3-19 4.3 4. 3-21 4.3-22 4.3-23 4.3-24 4.3-25 4.3-26 4.3-1 4.3-2 4.3-3 4.3-4 4.3-5 (2pp) 4.3-6 4.3-7 4.3-8 4.3-1 4.3-2 4.3-3 4.3-4 4.3-5 4.3-6 4.3-7 4.4-1 4.4-2 4.4-3 4.5-1 4.5-2 4'-3 4.5-4 4.5-5 4.5-6 4.5-7 4.5-8 4.5-9 4.5-10 4.5-11 4 ~ 5-12 Date 1982 1989 1989 1989 1989 1989 1989 1989 1989 1989 1989.

1989 1989 1989 1989 1989 1989 1990 1990 1989 1989 1990 1990 1990 1989 1982 1982 1982 1982 1982 1990 1990 1986 1988 1986 1982 1988 1982 1982 1993 1993 1982 1982 1982 1982 1982 1982

Page 26 Chapter 4

VOLUME III Reactor Coolant S stem Table Fig.

Fig.

Pacae 4.5-13 4.5-14

4. 5-15

4. 5-16

4. 5-17 4.5-18 4.5-19 4.5-20

4. 5-21 4.5-22

. 4. 5~23--

4.5-24 4.5-25

4. 5-1 (pg 1)

(pg 2)

(pg 3)

(pg 4)

4. 5-1

4. 5-2 4.5-3 Date 1982 1983 1982 1982 1982 1982 1982 1988 1988 1988 1988 1988 1988 1989 1989 1989 1990 1982 1982 1982

Page 27 Chapter 5

Containment S stem VOLUME IV Table Pacae

5. 0-1 5.1-1

5. 1-2 5.1-3

5. 1-4

5. 1-1 (2pp) 5.2-1 5.2-2 5.2-3 5.2-4 5.. 2.-.5.

5.2-6 5.2-7 5.2-8 5.2-9 5 '-10 5.2-11 5.2-12 5.2-13 5.2-14 5.2-15 5.2-16 5.2-17 5.2-18 5.2-19 5.2-20 5.2-21 5.2-22 5.2-23 5.2-24 5.2-25 5.2-26 5.2-27 5.2-28 5.2-29 5.2-30 5.2-31 5.2-32 5.2-33 5.2-34 5.2-35 5.2-36 5.2-37 5.2-38 5.2-39 5.2-40 5.2-41 5.2-42 5.2-43 5.2-44 5.2-45 Date 1989 1987 1982 1982 1982 1989 1989 1982 1982 1982 1982 1986 1982 1990 1986 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1990 1982 1987 1982 1982 1987 1987 1987 1982 1987 1987 1988 1987 1987 1987 1987 1995 1987 1990 1989

Page 28 Chapter 5

Containment S stem VOLUME IV Pacae 5.2-46 5.2-47 5.2-48 5.2-49 5.2-50 5.2-51 5.2-52 5.2-53 5.2-54 5.2-55 5 2.-.56-5.2-57 5.2-58 5.2-59 5.2-60 5.2-61 5.2-62 5.2-63 5.2-64 5.2-65 5.2-66 5.2-67 5.2-68 5.2-69 5.2-70 5.2-71 5.2-72 5.2-73 5.2-74 5.2-75 5.2-76 5.2-77 5.2-78 5.2-79 5.2-80 5.2-81 5.2-82 5.2-83 5 '-84 5.2-85 5 '-86 5.2-87 5.2-88 5.2-89 5.2-90 5.2-91 5.2-92 5.2-93 5.2-94 5.2-95 Date 1989 1989 1982 1988 1989 1989 1987 1995 1988 1989 1990 1987 1987 1991 1989 1988 1987 1987 1987 1987 1987 1995 1988 1988 1987 1988 1987 1987 1987 1987 1987 1988 1988 1990 1991 1990 1990 1990 1990 1990 1990 1990 1990 1993 1990 1990 1990 1990 1990 1990

Page 29 Chapter 5

Containment S stem VOLUME IV Table Table Table Table Table Table Table Fig.

Fig.

Pig.

Fig.

Fige Fig.

Pig.

Fig.

Pig.

Pacae 5.2-96 5 '-97 5.2-98 5.2-99 5.2-100

5. 2-101

5. 2-102 5.2-103

5. 2-104

5. 2-105 5. 2-. 106-

~

5.2-107 5.2-108 5.2-109 5.2-110 5.2-111

5. 2-112 5.2-113

5. 2-114 5.2-1 5.2-2 (2pp) 5.2-3 5.2-4 5.2-5 5.2-6 5.2-7 5.2-1 5.2-2 5.2-3 5.2-4 5.2-5 5.2.2-1 5.2 '-1A 5.2.2-2 5.2.2-2A 5.2.2-3 5.2.2-4 5.2.2-4A 5.2.2-4B 5.2.2-5 5.2.2-6 5.2.2-6A 5.2.2-6B 5.2.2-6C 5.2.2-6D 5.2.2-7, 5.2.2-8 5.2.2-9 5.2.2-10 5.2.2-10A Date 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1995 1990 1991 1990 1990 1990 1990 1990 1990 1990 1990 1982 1982 ORIG 1982 1988 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982

Page 30 Chapter 5

Containment S stem VOLUME IV Fig.

Fig.

Fig v.

Fig.

Fige Fig Fig.

Fig Fig.

Fig.

Pacae 5.2.2-11

5. 2. 2-11A 5.2.2-12 5.2.2-12A 5.2. 2-13 5.2.2-14 5.2.2-15 5.2.2-16 5.2.2-17 5.2.2-18 5.2.2 5.2.2-20 5.2.2-21 5.2.2-22 5.2 '-23 5.2.2-24 5.2.2-25 5.2.2-26 5.2.2-27 5.2.2-28 5 '.2-29 5.2.2"30 5.2.2-31 5.2.2-32 5.2.2-33 5.2.2-34 5.2.2"35 5.2.2-36 5.2.2-37 5.2.2-38 5.2.2-39 5.2.2-40 5.2.2-41 5.2.2-42 5.2.2-43 5.2.2-44 5.2.2-45 5.2.2-46 5.2.2-47 5.2.2-48 5.2.2-49 5.2.2-50 5.2.2-51

5. 2. 2-51A 5.2.2-51B 5.2.2-51C 5.2.2-51D 5.2.2-51E 5.2.2"52 5.2.2-52A 5.2.2-53 Date 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982

Page 31 Chapter 5

Containment S stem VOLUME IV Fig.

Fig.

Fige Fig.

Fig.

Fige Fig.

Fig.

Fige Fig.

Fig.

Fige Fig.

Fig.

Fige Fig.

Pacae 5.2.2-54 5.2.2-54A 5.2.2-54B 5.2.2-55 5.2.2-55A 5.2.2-56 5.2.2-56A 5.2.2-57 5.2.2-57A 5.2.2-58

.. 5.2.2-.58A 5.2.2-59 5.2.2-59A 5 '.2-59B 5.2.2-59C 5.2.2-59D 5.2.2-59E 5.2.2-60 5.2.2-60A 5.2.2-60B 5.2.2-60C 5.2.2-61 5.2.2-62 5.2.2-63 5.2.2"64 5.2.2-65 5.2.2-65A 5.3-1 5.3-2 5.3-3 5.3-4 5.3-5 5.3-6 5.3-7 5.3-8 5.3-9 5.3-10 5.3-11 5.3-12 5.3-13 5.3-14 5.3-15 5.3-16 5.3-17 5.3"18 5.3-19 5.3-20 5.3-21 5.3-22 5.3-23 Date 1995 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1991 1991 1982 1982 1982 1982 1982 1982 1982 1982 1984 1984 1982 1982 1982 1982 1982 1982 1982 1988 1982 1993 1984 1993 1982 1984 1984 1982 1982 1990 1982 1982 1982

Page 32 Chapter 5

Containment S stem VOLUME IV Table Fig.

Fig.

Pacae 5.3-24 5.3-25 5.3-26 5.3-27 5.3-28 5.3-29 5.3-30 5.3-31 5.3-32 5.3-33 5.3-34 5 ~ 3-1, (pg, 1)

(pg 2) 5.3-1 5.3-2 5.3-2A 5.3-3 5.3-4 5.4-1 5.4-2 5.4-3 5.4-4 5.4-5 5.4-6 5.4-7 5.4-8 5.5-1 5.5-2 5.5-3 5.5-4 5.5-5 5.5-6 5.5-7 5.5-8 5.5-9

5. 5-10

5. 5-11 5.5-12

5. 5-13 Date 1982 1982 1986 1986 1982 1988 1988 1988 1982 1988 1989 1993 1989 1982 1986 1986 1982 1982 1995 1995 1995 1995 1995 1995 1995 1995 1982 1982 1987 1993 1993 1993 1987 1993 1992 1992 1992 1987 1987

Page 33 VOLUME IV Chapter 5

Containment S stem Fig.

Fig.

Fig, Fig.

Fig.

Pacae

5. 5>>14

5. 5"15

5. 5 "16 S. 5-17 5.5-1 5.5-2 5.5-3 5.6-1 5.6-2 5.6-3 5.6-4 5..6-1 S. 7-1 5.7-2 5.7-3 5.7-4 5.7-5 5.7-6 5.7-7 5.7-8 5.7-1 5.7-2 Date 1987 1987 1993 1993 1985 1985 1982 1994 1993 1992 1986 1993 1982 1982 1982 1982 1982 1992 1982 ORIG 1982 1982

Page 34 Chapter 6

VOLUME IV En ineered Safet Features Table Pacae 6.1-1

6. 1-2

6. 1-3

6. 1-4 6.1-5

6. 1-6 6.1-7 6.1-8

6. 1-9

. 6 1-10

~

6.1-11

6. 1-1 6.2-1 6.2-2 6.2-3 6.2-4 6.2-5 6.2-6 6.2-7 6.2-8 6.2-9 6.2-10 6.2-11 6.2 12 6.2-13 6.2-14 6.2-15 6.2-16 6.2-17 6.2-18 6.2-19 6.2-20 6 ~ 2-21 6.2-22 6.2-23 6.2-24 6.2-25 6.2-26 6.2-27 6.2-28 6.2-29 6.2-30 6.2-31 6.2-32 6.2-33 6.2-34 6.2"35 6.2-36 6.2-37 Date 1989 1989 1989 1989 1989 1989 1989 1989 1989 1989 1989 1989 1982 1982 1982 1982 1993 1993 1993 1993 1988 1991 1992 1995 1995 1995 1995 1995 1995 1992 1982 1982 1990 1990 1990 1995 1982 1982 1982 1982 1982 1993 1993 1982 1993 1982 1982 1982 1993

Page 35 Chapter 6

VOLUME IV En ineered Safet Features Table Table Table Table Table Table Table Table Table Table Fig.

Fig.

, Fig.

Fig.

Table Table Table Table Fig.

Pacae 6.2-38 6.2-39 6.2-1 6.2-2 6.2-3 6'-4 6.2-5 6.2-6 (pg 1)

(pg 2)

(pg 3) 6.2=7.. (2pp)...

6.2-8 6.2-9

6. 2-10 (2pp) 6.2-1 6.2-1A 6.2-2 6.2-3 6.2-4 6.2-5 6.3-1 6.3-2 6.3-3 6.3-4 6.3-5 6.3-6 6.3-7 6.3-8 6.3-9 6.3-10 6.3-11 6.3-12

6. 3-13 6.3-1 6.3-2 6.3-3 6.3-4 (pg 1)

(pg 2) 6.3-1 Date 1982 1982 1995 1994 1993 1989 1991 1993 1989 1989 1991-1989 1989 1989 1993 1995 1982 1982 1991 1982 1982 1994 1994 1982 1994 1982 1982 1982 1986 1991 1982 1982 1982 1989 1991 1991 1992 1989 1982

Page 36 VOLUME V Chapter 7

Instrumentation and Control Pacae 701-1 7 ~ 1-2 7 ~ 2 1 7.2-2 7 ~ 2 3

7.2-4 7.2-5 7.2-6 702-7

. 7.2-..8....

7.2-9 7.2-10 7.2-11 7.2-12 7 ~ 2 13

7. 2-14 7.2-15

7. 2-16

7. 2-17 7.2-18 7 '-19 7.2-20 7.2-21 7.2-22 7.2-23 7 '-24 7.2-25 7.2-26 7.2-27 7.2-28 7.2-29 7.2-30 7.2-31 7.2-32 7.2-33 7.2-34 7.2-35 7.2-36 7 ~ 2 37 7.2-38 7.2-39 7.2-40 7.2-41 7.2-42 7.2-43 7.2-44 7.2-45 7.2-46 Date 1993 1982 1982 1990 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1994 1982 1982 1982 1982 1982 1982 1982 1990 1988 1982 1982 1986 1987 1982 1982 1992 1987 1992 1987 1987 1987 1987 1992 1994 1995 1987 1987 1987 1990 1987 1987 1987 1990

i 0

Page 37 VOLUME V Chapter 7

Instrumentation and Control Pacae Date Table Table Table Table Table Fig Fig.

Fige Fig.

Fig.

7.2-47 7.2-48 7.2-49 7.2-50 7.2-51 7 '-52 7.2-53

7. 2-1 (pg 1)

(pg 2)

~ -(pg-3)

(pg 4)

(pg 5) 7.2-2 (pg 1)

(pg 2)

(pg 3)

(pg 4)

(pg 5)

(pg 6) 702-3 7.2-4 7.2-5 (2pp) 7.2-69 7.2-2 7.2-3 7.2-4 7.2-5 7.2-6 7 ~ 2 7

7.2-8 7.2-9 7 ~ 3 1

7 ~ 3 2

7

~ 3 3

7.3-4 7'-5 7.3-6 7 ~ 3 7

7.3-8 7.3-9 7.3-10 7.3-11 7 0 3-12 7.3-13 7~3-1 7.4-1 7.4-2 1987 1987 1987 1987 1987 1987 1987 1989 1992 1989 1990 1990 1991 1992 1991 1991 1991 1991 1991 1991 1991 1994 1982 1982 1982 1982 1982 1982 1982 1982 1987 1990 1982 1982 1982 1992 1983 1982 1982 1990 1982 1982 1982 1982 1982 1991

Page 38 VOLUME V Chapter 7

Instrumentation and Control Pa<ac Date Table Table Fig.

Fig.

7.5-1 7.5-2 7.5-3 7.5-4 7.5-5 7.5-6 7.5-7 7.5-8

- 7.S~9

~

7.5-10

7. 5-11 7.5-12 7.5-13 7.5-14 7 '-15 7.5-16 7.5-17 7.5-18 7.5-19 7.5-20 7.5-1 7.5-2 (2pp) 7.5-1 7.5-2 7'-3 7.6-1 7.6-2 7.6-3 7.6-4 7.6-5 7.6-1 7.6-2 7.6-3

7. 7-1 7 ~ 7 2 7 ~ 7 3

7.7-4 7.7-5 7.7-6 7 ~ 7 7

7. 7-8 7.7-9 7.7-10 7

~ 7-11

7. 8-1 7.8-2 1982 1982 1982 1982 1982 1991 1995 1987 1989

~

1987 1982 1982 1991 1982 1982 1982 1982 1991 1982 1989 1989 1989 1982 1982 1982 1991 1991 1991 1991 1991 1982 1982 1982 1982 1982 1982 1982 1995 1993 1991 1991 1995 1986 1982 1992 1992

Page 39 VOLUME V Chapter 7

Instrumentation and Control Pacae Table 7.8-1 Table 7.8-2 Table 7.8-3 Table 7.8-4 Table 7.8-5 (2 pgs)

(2 pgs)

(pg 1)

(pg 2)

(pg 3)

(pg 4)

(pg 5)

(3 pgs)

Date 1992 1992 1992 1994 1993 1992 1992 1992 1992

Page 40 VOLUME V Chapter 8

Electrical S stems Fig Fig.

Fig.

Pacae 8 ~ 1-1 8.1-2

8. 1-3

8. 1-4

8. 1-5

8. 1-6 8.1-7 8.1-8

8. 1-9

..8. 1.-.1....,

8.1-1A

8. 1-1B

8. 1-2A 8.1-2B 8 '-1 8.2-1 8.3-1 8.3-2 8.3-3 8.3-4 8.3-5 8.3-6 8.3-7 8.3-8 8.3-9

8. 3-10 8.3-11 8.3-1 8.3-2 8.3-.3 8.4-1 8.4-2 8.4-3 8.4-1 8.5-1 9.5-2 8.6 "1 8.6-2 Date 1994 1982 1990 1990 1991 1991 1991 1987 1982 1986" 1994 1994 1994 1994 1990 1990 1990 1991 1990 1990 1990 1994 1994 1990 1990 1990 1990 1990 1990 1994 1990 1990 1990 1992 1991 1982 1986 1995

Page 41 Chapter 9

VOLUME V Auxilia and Emer enc 8 stems Pacae Date Table Table Table

9. 1-1 9.1-2

9. 1-3

9. 1-4 9.2-1 9.2-2 9.2-3 9.2-4 9.2-5 9.2-6

9. 2.=7,.

9.2-8 9'-9 9.2-10 9.2-11 9.2-12 9.2-13 9.2-14 9.2-15 9.2-16 9.2-17 9

~ 2-18 9.2-19 9.2-20 9.2-21 9.2-22 9.2-23 9.2-24 9.2-25 9.2-26 9.2-27 9.2-28 9.2-29 9.2-30 9.2-31 9.2-32 9.2-33 9.2-34 9.2-35 9.2-36 9.2-37 9.2-38 9.2-1 9.2-2 9.2-3 (pg 1)

(pg 2)

(pg 3)

(pg 4)

(pg 5)

(pg 6) 1992 1982 1990 1982 1982 1982 1991 1986 1982 1982 1988-1987 1982 1982 1995 1982 1982 1982 1982 1990 1992 1992 1994 1994 1982 1982 1995 1988 1982 1982 1982 1982 1993 1993 1982 1982 1993 1991 1982 1982 1995 1982 1990 1989 1989 1990 1989 1992 1989 1990

Page 42 Chapter 9

VOLUME V Auxilia and Emer enc S stems Table Table Fig.

Fig.

Table Table Table Table Fig.

Table Table Table Table Table Table Fig.

Pacae 9'-3 9.2-4 9.2-1 9.2-2 9.2-3 9.2-4 9.2-5 9.2-6 9.3-1 9.3-2 9.3-3 9.3-4 9.3-5 9.3-6 9.3-7 9.3-8 9.3-9 9.3-10 9.3-11 9 ~ 3-12 9.3-13 9.3-1 9.3-2 9.3-2 9.3-3 9.3-1 9.4-1 9.4-2 9.4-3 9.4-4 9.4-5 9.4-6 9.4-7 9.4-1 9.4-2 9.4-2 9.4-2 9.4-2 9.4-3 9.4-1 (pg 7)

(pg 8)

(pg 9)

(pg 10)

(pg 11)

(pg 12)

(pg 13)

(pg 14)

(pg 15)

(pg 16)

(pg"17)

(2pp)

(1pp)

(2pp)

(3pp)

(pg1)

(pg2)

(pg3)

(pg4)

Date 1989 1989 1989 1990 1989 1989 1995 1990 1989 1989 1989" 1989 1992 1982 1993 1984 ORIG 1982 1982 1982 1994 1994 1994 1994 1994 1994 1987 1986 1994 1990 1990 1990 1990 1991 1990 1991 1994 1995 1994 1983 1995 1982 1986 1990 1989 1995 1995 1989 1989 1990

Page 43 Chapter 9

VOLUME V Auxilia and Emer enc S stems Table Table.

Table Table Fig.

Fig.

Pacae 9.5-1 9.5-2 9.5-3 9.5-4 9.5-5 9.5-6 9.5-7 9.5-8 9.5-9 9.5-1

.9 5 ~..

9.5-3 9.5-4 9.5-1 9.6-1 9.6-2 9.6-3 9.6-4 9.6-5 9.6-6 9.6-7 9.6-8 9.6-9

9. 6-1 9.6-2 9.7-1 9'-2 9.7-3 9.7-4 9.7-5 9.7-6 9.7-7 9.7-8 9.7-9 9.7-10 9.7-11

9. 7-12

9. 7-13

9. 7-14

9. 7-15 9.7-16

9. 7-17

9. 7-18 9.7-19 9.7-20

9. 7-21 9.7-22 9.7-23 9.7-24 9.7-25 9.7-26 9.7-27 9.7-28 9.7-29 Date 1985 1994 1992 1982 1982 1982 1982 1982 1982 1990 1994

~

1993 1993 1995 1991 1983 1989 1987 1987 1988 1983 1983 1982 1992 1987 1982 1994 1982 1982 1994 1994 1995 1995 1992 1995 1995 1991 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994 1995 1995 1995 1995 1995

Page 44 Chapter 9

VOLUME V Auxilia and Emer enc S stems Table Table Table Table Table Table Fig.

Fig.

Table Table Table Table Table Table Table Table Fig.

Fig.

Pacae 9.7-30 9.7-31 9.7-32

9. 7-1 9.7-2 9.7-3 9.7-4 9.7-5 9.7-6 9.7-1 9 '~2 9.7-3 9'-4 9.7-5

9. 8-1 9.8-2 9.8-3 9.8-4 9.8-5 9.8-6 9.8-7 9'-8 9.8-9

9. 8-10 9.8-11

9. 8-12 9.8-13 9.8-14 9.8-15

9. 8"16

9. 8-17 9.8-18

9. 8-19 9.8-20

9. 8-21 9.8-22 9.8-23 9.8-24 9.8-25 9.8-26 9.8-27 9.8-28 9.8-29 9.8-30 9.8-1 9.8-2 (1pp) 9.8-2 (2pp) 9.8-2 (3pp) 9.8-3 9.8-4 (3pp) 9.8-5 9.8-6 9.8-1 9.8-2 9.8-3 9.8-4 Date 1995 1995 1995 1994 1994 1994 1994 1994 1994 1982 1994

~

1994 1994 1994 1994 1995 1995 1993 1995 1993 1993 1994 1993 1993 1993 1993 1994 1993 1993 1995 1993 1993 1994 1993 1993 1993 1993 1993 1987 1987 1987 1987 1994 1987 1993 1989 1991 1991 1989 1989 1993 1989 1993 1982 1991 1993

Page 45 Chapter 9

VOLUME V Auxilia and Emer enc S stems Fig.

Fig.

Pacae 9.8-5 9.8-6 9.8-7

9. 9-1 9.9-2 9.9-3 9.9-4 9.9-5 9.9-,6...

9.9-7 9.9-8 9.9-9 9.9-1 9.9-2

9. 10-1

9. 10-2

9. 10-3

9. 10-4 9.10-1 Date 1993 1985 1982 1992 1995 1995 1995 1995 1991 1991 1995 1995 1992 1989 1992 1987 1986 1987 1986

Page 46 VOLUME VI Chapter 10 Steam and Power Conversion S stem Fight Fig.

Fig.

Table Fig.

Fig.

Table Fig.

Pacae

10. 1<<1 10.1-2 10.2-1 10.2-2 10.2-3

10. 2-4 10.2-5 10.2-6

-.10. 2p 1-

~

10.2-1A 10.2-1B 10.2-1C

10. 3-1 10.3-2 10.3 "3 10.3-4 10.3-5 10.3-6

10. 3-1 10.3-1A 10.4-1 10.4-2 10.4-3

10. 5-1 10.5-2 10.5-3

10. 5-4 10.5-5 10.5-6 10.5-7

10. 5-1 10.5-1

10. 5-2 10.5-2A 10.5-3 10.5-3A

10. 5-4 10.5-4A

10. 5-5 10.5-5A 10.6-1 10.6-2 10

~ 6-3 10.6-4 10.6-1

10. 6-1 Date 1987 1982 1982 1983 1985 1991 1985 1988 1984 1991 1982 1992 1986 1982 1986 1994 1995 1984 1984 1984 1991 1985 1991 1986 1991 1982 1987 1990 1989 1993 1991 1995 1982 1982

~

1982 1982 1991 1991 1990 1982 1995 1982 1982 1991 1995 1982

Page 47

'OLUME VI Chapter 10 Steam and Power Conversion S stem Pacae Date

10. 7-1

10. 7-2

10. 8-1

10. 9-1

10. 10-1 10.11-1

10. 11-2

10. 11-3 1982 1982 1982" 1995 1995 1983 1988 1983

Page 48 Chapter 11 VOLUME VI Waste Disposal and Radiation Protection S stem Table Table Table Table Table Table Fig.

Fig.

Table Table Table Table Table Table Table Table Pacae

11. 1" 1

11. 1-2 11 01 "3

11. 1-4

11. 1-5 11

~ 1-6 1111-7

11. 1-8

11. 1-9

11. 1-.10-.

11. 1-11

11. 1-12

11. 1-13

11. 1-14

11. 1-15 11.1-16 11 01-17

11. 1-18

11. 1-1

11. 1-2 11.1-3 (pg 1)

(pg 2) 11.1-4

11. 1-5

11. 1-6

11. 1-1

11. 1-2

11. 1-2A 11.1-2B

11. 1-3

11. 1-4 11.2-1 11.2-2 ll.2-3 11.2-4 11.2-5 11.2-6 11.2-7 11.2-8 11.2-9 11.2-1 11.2-2 11.2-3 11 ~ 2-4 11.2-5 11

~ 2-6 11.2-7 11.2-8 Date 1985 1992 1982 1983 1994 1994 1992 1983 1995 1982 1994 1993 1985 1994 1985 1982 1994 1994 1989 1990 1990 1993 1989 1989 1989 1988 1994 1982 1993 1995 1988 1995 1983 1995 1995 1982 1982 1995 1995 1995 1995 1995 1995 1989 1995 1995 1989 1989

Page 49 Chapter 11 VOLUME VI Waste Disposal and Radiation Protection S stem Pacae Fig.

Table Table Table Table Table Table

11. 3-1 (pg5) 1113-2 11.4-1

11. 4-2 11.4-3 11.4-4 11.4-5 11.4-6 11.4-7 11.4-8 11.4-9 11.4-10 11.4-11 11.4-12 11.5-1

11. 5-2

11. 5-3 11.5-1

11. 5-2 11

~ 5-1 Table Table Fig.

11.2-1 11.3-1 11.3-2 11.3-3 11.3-4 11.3-5 11.3-6 1113-7 11.3-8

.. 11.3.-9..

11.3-10

11. 3-11 11.3-12 11 03-13

11. 3-14 11.3-15

11. 3-16 11.3-17 11.3-18

11. 3-1 (pgl)

11. 3-1 (pg2)

11. 3-1 (pg3)

11. 3-1 (pg4)

Date 1982 1990 1986 1988 1990 1992 1992 1995 1990 1990 1993 1990 1995 1995 1990 1992 1992 1993 1994 1990 1995 1995 1991 1991 1990 1995 1995 1993 1995 1995 1995 1995 1995 1995 1995 1993 1995 1987 1990 1983 1989 1989 1983

Page 50 Chapter 11 VOLUME VZ Waste Disposal and Radiation Protection S stem Fig.

Fig.

Pacae 11.6-1 11.6-2

11. 6-3 11.6-4

11. 6-1 11.6-2a 11.6-2b

11. 6-2c Date 1995 1988 1990 1993 1994 1986 1986 1990

Page 51 VOLUME VI Chapter 12 Conduct of erations Pa<ac

12. 1-1

12. 1-2 12.2-1 12.2-2 12 0 2-3

12. 2-4 12.2-5 12.2-6 1202-7

~ 12.2.8 12 03-1 12.4-1

12. 5-1

12. 6-1

12. 6-2

12. 6-3 1217-1 Date 1994 1982 1994 1988 1988 1988 1988 1988 1988 1988 1988 1983 1982 1991 1994 ORIG 1991

Chapter 13 VOLUME VI Initial Tests and 0 eration Pacae Table Table Table Table

, Table Table Table-Table Table Table Table Table Table Table Table Table Table Table Table

13. 1-1

13. 1-2

13. 1-3 13.1-4 13.1-1 (1pp) 13. 1-1 (2pp) 13.1-1 (3pp) 13. 1-1 (4pp) 13. 1-1 (5pp)

13. 1-1 (6pp) 13; 1-1

~ (7pp)

~

13. 1-1 (8pp) 13.1-1 (9pp) 13.2-1 13 02-2 1302-3 13.2-4 13.2-5 13.2-6 13.2-1 (lpp)

13. 2-1 (2PP)

13. 2-1 (3pp) 13. 2-1 (4pp) 13.2-1 (5pp) 13.2-1 (6pp) 13.2-1 (7pp) 13.3-1 13 03-2 13.3-3 13.3-4 13.3-5 13.3-1 (1pp) 13.3-1 (2pp) 13.3-1 (3PP) 13.4-1 Page 52 Date 1991 1991 1991 1982 1989 1989 1991 1989 1991 1989 1991.

1989 1989 1982 1991 1991 1991 1991 1991 1991 1991 1989 1991 1991 1991 1991 1982 1991 1982 1991 1982 1989 1991 1991 1983

Page 53 VOLUME VII Chapter 14 Safet Anal sis Unit 1 Table Table Table Table Fig.

Fig.

Pacae 14.0-1 14.0-2

14. 0-3

14. 1-1

14. 1-2 14.1-3

14. 1-4

14. 1-5

14. 1-6

14. 1 7.,

14. 1-8 14.1-9

14. 1-10

14. 1-11

14. 1-12 14.1-13

14. 1-1

14. 1-2 14. 1-3 (2pp)

14. 1-4

14. 1-1

14. 1-2

14. 1-3

14. 1-4 14.1-5 14.1-6

14. 1. 1-1

14. 1. 1-2

14. 1. 1-3

14. 1. 1-4

14. 1. 1-5

14. 1. 1-1

14. 1. 1-2

14. 1. 2-1

14. 1. 2-2

14. 1. 2-3

14. 1.2-4 14 '.2-5 14.1.2-6

14. l.2-1

14. 1. 2-2 14.1.2-3

14. 1.2-4

14. 1.2-5 14.1.2-6 14.1.2-7 14.1.2-8

14. 1.2-9 Date 1993 1993 1993 1993 1993 1993 1993 1993 1995 1993.

1993 1993 1995 1995 1995 1995 1995 1995 1995 1995 1990 1990 1990 1990 1990 1992 1993 1990 1994 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990

Page 54 VOLUME VII Chapter 14 Safet Anal sis Unit 1 Fig.

Fig.

Pa<ac 14.1.3-1 14.1.3-2 14.1.3-3

14. 1. 3-4 14.1.3-5

14. 1. 3-6

14. 1. 3-7

14. 1. 3-1

. 14. 1. 3-2 14.1.4=1.

14

~ 1. 5-1

14. 1. 5-2

14. 1. 5-3

14. 1.5-4

14. 1. 6-1 14.1.6-2 14.1.6-3

14. l.6-4

14. 1. 6-5

14. 1. 6-6

14. 1.6-7

14. 1. 6-8

14. 1. 6-1

14. 1. 6-2

14. 1. 6-3

14. 1. 6-4 14.1.6-5 14.1.6-6

14. l.6-7

14. l.6-8

14. 1. 6-9

14. 1. 6-10

14. 1. 6-11

14. 1. 6-12 14.1.7-1 14.1.7-2 14

~ 1 ~ 7-3

14. 1. 7-1

14. 1. 7-2

14. 1. 8-1 14.1.8-2 14.1.8-3

14. 1. 8-4

14. 1 ~ 8-5

14. 1. 8-1 14.1.8-2 14.1.8-3

14. 1; 8-4

14. 1. 8-5 (3pp)

(3pp)

Date 1993 1992 1992 1992 1990 1990 1992 1990 1990 1990-1990 1992 1992 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1982 1982 1990 1990 1995 1995 1990 1995 1995 1995 1995 1995

Page 55 VOLUME VII Chapter 14 Safet Anal sis Unit 1 Fig.

Fig.

Pacae

14. 1. 8-6 (3pp) 14.1.8-7 (3pp) 14.1.8-8 (3pp)

14. 1. 9-1

14. l. 9-2

14. 1. 9-3

14. 1. 9-1 14.1.9-2

14. 1. 10-1

14. 1.10.-.2-.

14. 1. 10-3

14. l. 10 "4

14. 1. 10-5 Fig.

Fig.

14. 1. 10-1 14 F 1.10-2

14. 1. 10-3

14. 1. 10-4

14. 1. 10-5 14.1.10-6 14.1.10-7

14. 1. 10-8

14. 1. 11-1

14. 1. 11-2

14. 1. 11-3

14. 1. 11-4

14. 1. 11-1 14 '.11-2 14.1.11"3

14. 1. 11" 4

14. 1. 11-5 14.1.11-6

14. 1. 11-7

14. 1. 11-8

14. 1. 12-1 14.1.12-2

14. 1. 12-3

14. 1. 12-4 14.1

~ 12-1

14. 1 ~ 12-2

14. 1. 13-1 14.1.13-2

14. 1. 13-3

14. l. 13-4

14. 1. 13-5

14. 1. 13-6 Table 14.1.10-1 Table 14.1.10-2 Table 14.1.10-3 Table 14.1.10-4 Date 1995 1995 1995 1990 1990 1990 1990 1990 1993 1993.

1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1990 1993 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1991 1991 1989 1982 1995 1995

Page 56 VOLUME VII Chapter 14 Safet Anal sis Unit 1 Pacae Date Table Fig-.

Fig.

Table Table Table Table Table Table

14. 1. 13-7

14. 1. 13-8

14. l.13-9

14. 1. 13-10

14. 1. 13-11

14. 1. 13-12

14. 1. 13-13

14. 1. 13-14

14. 1. 13-15 14. 1. 13-16

14. 1. 13-1

~14':1.. 13-1-'"

'4.

1. 13-2

14. 1. 13-3

14. 1. 13-4

14. 1. 13-5

14. 1. 13-6 14.2.1-1

14. 2

~ 1-2 14.2.1-3 14.2.1-4

14. 2. 1-5

14. 2. 1-6 14.2. 1-7

14. 2 ~ 1-8 14.2.1"9 14.2.1-10

14. 2. 1-11 14.2. 1-12 14

~ 2. 1-13

14. 2. 1-14 14.2. 1-1 14.2. 1-2 14.2.1-3 Deleted 14 '.1-4 14.2.2-1 14.2.2-2 14.2.2-3 14.2.2-4 14.2.3-1 14.2.3-2 14.2.3-1 14.2.3-2 14.2.4-1 14.2.4-2 14.2.4-3 14.2.4-5 14.2 '-6 14.2.4-7 14.2.4-8 14.2.4-9 1995 1995 1995 1995 1995 1995 1995 1995 1995 1990 1990 1982 1982 1982 1982 1982 1982 1990 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1993 1993 1993 1990 1990 1990 1990 1990 1990 1990 1990 1992 1990 1990 1992 1992

Page 57 VOLUME VII Chapter 14 Safet Anal sis Unit 1 Pig.

Table Fig".

Fig.

Table Fig.

Fig.

Table Table Table Pig.

Fig.

Pig.

Pacae 14.2.4-1 14.2. 5-1 14.2.5-2 14.2.5-3 14.2.5-4 14.2.5-5 14.2.5-6 14.2.5-7 14.2.5-8 14.2.5-9 14.2.5-1 14" 2 '5 1" 14.2.5-2 14.2.5-3 14.2.5-4 14.2.5-5 14.2.5-6 14.2.6-1 14.2.6-2 14.2.6-3 14.2.6-4 14.2.6-5 14.2.6-6 14.2.6-7 14.2.6-8 14.2.6-9 14.2.6-10 14.2.6-11 14.2.6-12 14.2. 6-13 14.2. 6-14 14.2. 6-15 14.2. 6-1 14.2. 6-1 14.2.6-2 14.2.6-3 14 '.6-4 14

~ 2. 7-1 14.2.7-2 14.2.7-3 14.2.7-4 14.2.7-5 14.2.7-6 14.2 '-7 14.2.7-8 14.2. 7-1 14.2.7-2 14.2.7-3 14.2.7-1 14.2.7-2 14.2.7-3 Date 1982 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990

'990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1995 1995 1995 1995 1995 1995 1982 1982 1987

Page 58 VOLUME VIE Chapter 14 Safet Anal sis Unit 1 Parcae Fig.

Fig.

Fige Fig.

Fig.

Table Fig.

Fig.

Fige Fig.

Fig.

Table Table Table Table Table Table Table Table Fige Fig.

Fig.

14.2.7-4 14.2.7-5 14.2.7-6 14.2.7-7 14.2.7-8 14.2.7-9

14. 2. 7-10 14.2. 7-11 14

~ 2. 7-12 14.2.8-1 14.2.8-2

. 14;2:8-3"-.

14.2.8-4 14.2.8-5 14.2.8-6 14.2.8-7 14.2.8-1 14.2. 8-1 14.2.8-2 14.2.8-3 14.2.8-4 14.2.8-5 14.2.8-6 14.2.8-7

14. 3. 1-1 14.3. 1-2 14 '.1-3 14.3.1-4 14.3.1-5 14.3.1-6 14.3, 1-7 14.3.1-8 14.3.1-9 14.3. 1-10 14.3. 1-11

14. 3. 1-lla

14. 3. 1-12 14

~ 3. 1-13 14

~ 3. 1-1 (pg 1) 14.3.1-1 (pg 2) 14

~ 3. 1-1 (pg 3)

14. 3. 1-2 14. 3. 1-3 (2pp) 14.3. 1-4

14. 3. 1-5 14.3.1-6

14. 3. 1-la

14. 3. 1-1b

14. 3. 1-1c Date 1987 1982 1982 1982 1982 1990 1990 1990 1990 1990 1990 1990 1995 1995 1995 1990 1990 1990 1990 1990 1990 1990 1990 1990 1993 1993 1993 1993 1993 1993 1993 1993 1993 1990 1992 1993 1993 1994 1994 1992 1990 1990 1990 1990 1990 1990 1990 1990 1990

Page 59 VOLUME VII Chapter 14 Safet Anal sis Unit 1 Fig.

Fig.

Fig-.

Fig.

Pig.

Fig.

Fige Fig.

Fig.

Pig.

Fig.

Pig.

Fig.

Fige Fig.

Fig.

Pig.

Fig.

Pacae

14. 3. 1-1d 14.3. 1-le 14.3. 1"1f 14.3. 1-1g 14.3.1-2a

14. 3. 1-2b 14.3.1-2c 14.3.1-2d 14.3. 1-2e

14. 3. 1-2f

~.14 3-1-2g-

~

14.3.1-3a 14.3.1-3b 14.3.1-3c

14. 3. 1-3d 14.3.1-3e 14.3.1-3f 14.3. 1-3g 14.3.1-4a 14

~ 3

~ 1-4b

14. 3. 1-4c 14 '.1-4d 14.3.1-4e 14.3. 1-4f 14.3.1-4g 14.3. 1-Sa 14.3.1-5b 14.3.1-5c

14. 3. 1-5d 14.3.1-5e 14.3.1-5f

14. 3. 1-5g

14. 3

~ 1-6a

14. 3. 1-6b 14.3.1-6c

14. 3. 1-6d 14.3.1-6e 14.3.1-6f 14.3. 1-6g 14.3.1-7a 14.3.1-7b

14. 3. 1-7c 14.3.1-7d 14.3. 1-7e 14.3.1-7f 14.3.1-7g 14.3.1-8a

14. 3. 1-Bb 14.3.1-8c Date 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990

Page 60 VOLUME VII Chapter 14 Safet Anal sis Unit 1 Pacae Fig.

Fig.

Pig.

Fig.:

Fig.

Pig.

Fig.

Pig.

Fig.

Pig.

Fige Fig.

Fig.

Pig.

Fig.

Fige Fig.

Fig.

Pig.

Fig.

14. 3. 1-Bd

14. 3. 1-Be 14.3.1-8f 14.3. 1-Bg

14. 3. 1-9a 14.3.1-9b 14.3.1-9c 14. 3. 1-9d 14.3. 1-9e 14.3. 1-9f 14.3.1-9g

14. 3. 1-lob 14.3. 1-10c 14

~ 3. 1-lod

14. 3. 1-10e

14. 3. 1-10f 14.3. 1-10g

14. 3. 1-lla 14.3. 1-lib 14.3.1-11c

14. 3. 1-lid 14.3. 1-lie 14.3. 1"llf

14. 3. 1-llg 14.3. 1-12a

14. 3. 1-12b 14.3.1-12c

14. 3. 1-12d 14.3.1-12e 14.3. 1-12f

14. 3. 1-12g

14. 3. 1-13a 14

~ 3

~ 1-13b

14. 3. 1-13c

14. 3. 1-13d 14.3.1-13e 14.3.1-13f

14. 3. 1-13g 14

~ 3. 1"14

14. 3. 1"15

14. 3. 1-16 14.3. 1-17 14.3. 1-18 14.3.1-19

14. 3.

1-20'4.F1-21 14.3. 1-22 14.3.1-23

- 14.-3..1-10a-Date 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990.

1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990

Page 61 VOLUME VII Chapter 14 Safet Anal sis Unit 1 Pacae "Table Table Table Table Table Table Table Table Table Table Table Table Table Fig.

Fig.

Fige Fig.

Fig.

Fig, Fige Fig.

Fig.

Fig, Fig, Fig.

Fig.

Fige 14.3.2-1 14.3.2-2 14.3.2"3 14.3.2-4 14.3.2-5 14.3.2-6 14.3.2-7 14.3.2-7a 14.3.2-7b 14.3.2-7c 14.3.2-7d "14:3;2-1-- "

14.3.2-2 14.3.2-3 14.3.2-4 14.3.2-5 14.3.2-6 14.3.2-7 14.3.2-8 14.3.2-9 14.3.2-10

14. 3. 2-11

14. 3. 2-12 14.3.2-13 14.3. 2-1 14.3.2-2 14.3.2-3 14.3.2-4 14.3.2-5 14.3.2-6 14.3.2-7 14 '.2-8 14.3.2-9 14.3.2-10

14. 3.2-11 14.3.2-12 14

~ 3. 2"13 14 '.2-14

14. 3. 2-15 14.3.2-16

14. 3. 2-17 14

~ 3. 2-18 14.3.2-19 14.3.2-20 14.3.2-21 14.3.2-22 14.3.2-23 14.3.2-24 14.3.2-25 14.3.2-26 14.3.2-27 14.3.2-28 Date 1990 1990 1990 1990 1990 1994 1995 1995 1995 1995 1995 1990 1990 1994 1990 1990 1990 1994 1995 1995 1995 1995 1995 1995 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990.

1990 1990 1990 1990 1990 1990 1990 1990

Page 62 VOLUME VIII Chapter 14 Safet Anal sis Unit 1 Fig.

Fig.

Fig-.

Fig.

Fige Fig.

Fig.

Fige Fig.

Fig.

Fige Fig.

Fig.

Pacae 14.3.2-29 14.3.2-30 14.3.2-31 14.3.2-32 14.3.2-33 14.3.2-34 14.3.2-35 14.3.2-36 14.3.2-37 14.3.2-38 14.3.2-39 14;8;2-40" 14.3.2-41 14.3.2-43 14.3.2-44 14.3.2-45 14.3.2-46 14.3.2-47 14 '.2-48 14.3.2-49 14.3.2-50

14. 3. 2-51 14.3.2-52 14.3.2-53 14.3.2-54 14.3.2-55 14.3.2-56 14.3.2-57 14.3.2-58 14.3 '-59 14.3.2-60

14. 3.2-61 14.3.2-62 14.3.2-63 14.3.2-64 14.3.2-65 14.3.2-66 14.3.3-1 14.3.3-2 14.3.3-3 14.3.3-4 14.3.3-5 14.3.3-6 14.3.3-7 14.3.3-8 14.3.3-9

14. 3. 3-10 14

~ 3. 3-11 Date 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990'995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994

Page 63 VOLUME VIII Chapter 14 Safet Anal sis Unit 1 Pacae

14. 3. 4-1 14.3.4-2 14 '.4-3 14.3.4-4 14.3.4-5 14.3.4-6 14.3.4-7 14.3.4-8 14.3.4-9 14.3.4-10 14.3.4-11 14.3:4-12 14.3.4-13 14.3.4-14 14.3.4-15 14.3.4-16 14.3.4-17 14.3.4-18 14.3.4-19 14.3.4-20 14

~ 3.4-21 14.3.4-22 14.3.4-23 14.3.4-24 14.3.4-25 14.3.4-26 14.3.4-27 14.3.4-28 14.3.4-29 14.3.4-30 14.3.4-31 14.3.4-32 14.3.4-33 14.3.4-34 14.3.4-35 14.3.4-36 14.3.4-37 14.3.4-38 14.3.4-39 14.3.4-40 14.3.4-41

14. 3.4-42 14.3.4-43 14.3.4-44 14.3.4-45 14.3.4-46 14.3.4-47 14.3.4-48 14.3.4-49 14.3.4-50 14.3.4-51 14.3.4-52 Date 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992" 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992

Page 64 VOLUME VEII Chapter 14 Safet Anal sis Unit 1 Pacae Date Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table 14.3.4-4 14.3.4-5 14.3.4-6 14.3.4-7 14.3.2-8 (2pp)

(2pp)

(2pp) 14.3.4-9 14.3.4-10

14. 3. 4-11 14

~ 3.4-12

14. 3. 4-13 14.3.4-14 14.3.4-15

14. 3. 4-16 14.3.4-17

14. 3-4-18

14. 3. 4-19 14.3.4-20 14.3.4-21 14.3.4-22 14.3.4-23 14.3.4-24 (2 pp)

(2 pp)

(2pp) 14.3.4-53 14.3.4-54 14.3.4-55 14.3.4-56 14.3.4-57 14.3.4-58 14.3.4-59 14.3.4-60

14. 3. 4-61 14.3 '-62 14 c.3;.4 ~

14.3.4-64 14.3.4-65 14.3.4-66 14.3.4-67 14.3.4-68 14.3.4-69 14.3.4-70 14.3.4-71 14.3.4-72 14 '.4-73 14.3.4-74 14.3.4-75 14.3.4-76 14.3.4-77 14.3.4-78 14.3.4-79 14.3.4-80 14.3.4-81 14.3.4-82 14.3.4-83 14.3.4-84 14.3.4-85 14.3.4-1 14.3.4-2 14.3.4-3 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992" 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992

Page 65 VOLUME VIII Chapter 14 Safet Anal sis Unit 1 Pacae Table 14.3.4-25 Table 14.3.4-26 Table 14.3.4-27 Table 14.3.4-28 Table 14 '.4-29 Table 14.3.4-30 Table 14.3.4-31 Table 14.3.4-32 Table 14.3.4-33 Table 14.3.4-34 Table 14.3.4-35 Table 14.3.4-36 Table-'14.-3; 4-37 Table 14.3.4-38 Table 14.3.4-39 Table 14.3.4-40 Table 14.3.4-41 Table 14.3.4-42 Table 14.3.4-43 Table 14.3.4-44 Table 14.3.4-45 Table 14.3.4-46 Fig. 14.3.4-1 Fig. 14.3.4-2 Fig. 14.3.4-3 Fig. 14.3.4-4 Fig. 14.3 '-5 Fig. 14.3 '-6 Fig. 14.3.4-7 Fig. 14.3.4-8 Fig. 14.3.4-9 Fig. 14. 3. 4-10 Fig. 14.3.4-11 Fig. 14. 3. 4-12 Fig. 14.3.4-13 Fig. 14.3.4-14 Fig. 14.3 '-15 Fig. 14.3.4-16 Fig. 14.3.4-17 Fig. 14.3.4" 18 Fig. 14.3.4-19 Fig. 14.3.4-20 Fig. 14. 3.4-21 Fig. 14.3.4-22 Fig. 14.3.4-23 Fig. 14.3.4-24 Fig. 14.3.4-25 Fig. 14.3.4-26 Fig. 14.3.4-27 Fig. 14.3.4-28 Fig. 14.3.4-29 Fig. 14.3.4-30 Fig. 14.3.4-31 Fig. 14.3.4-32 Fig. 14.3.4-33 Fig. 14.3.4-34 Fig. 14.3.4-35 Fig. 14.3.4-36 Fig. 14.3.4-37 Fig. 14.3.4-38 Fig. 14.3.4-39 (3pp)

(10pp)

(2pp)

Date 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992

1992, 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992

Page 66 Chapter 14 VOLUME VIZ?

Safet Anal sis Unit 1 Fig.

Fig.

Fig-.

Fig.

Fig, Fig.

Fig.

Fige Fig.

Fig.

Fige Fig.

Fig.

Fige Fig.

Fig.

Fig:

Fig.

Pacae 14.3.4-40 14.3.4-41 14.3.4-42 14.3.4-43 14.3.4-44 14.3.4.45 14.3.4-46 14.3.4-47 14.3.4-48 14.3.4-49 14.3.4-50 14.3 4-51.'4.3.4-52 14.3.4-53 14.3.4-54 14.3.4-55 14.3.4-56 14.3.4-57 14.3.4-58 14.3.4-59 14.3.4-60 14.3.4-61 14.3.4-62 14.3.4-63 14.3.4-64 14.3.4-65 14.3.4-66 14.3.4-67 14.3.4-68 14.3.4-69 14.3.4-70 14.3.4-71 14.3 '-72 14.3.4-73 14.3.4-74 14 '.4-75 14.3.4-76 14.3.4-77 14.3.4-78 14.3.4-79 14.3.4-80 14.3.4-81 14.3.4-82 14.3.4-83 14.3.4-84 14.3.4-85 14.3.4-86 14.3.4-87 14.3.4-88 14.3.4-89 14.3.4-90 14.3.4-91 14.3.4-92 14.3.4-93 Date 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992'992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1990 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992 1992

Page 67 VOLUME IX Chapter 14 Safet Anal sis Unit 1 Table Table Table Table Table Table Table Table Pacae

14. 3. 5"1 14.3.5-2 14.3.5-3 14.3.5-4 14.3.5-5 14.3.5-6 14.3.5-7 14.3.5-8 14.3.5-9

14. 3. 5-10 14:

3:5-11'4.3. 5-12

14. 3. 5-13

14. 3. 5-14

14. 3. 5-15 14.3. 5-16

14. 3. 5-17

14. 3. 5-18 14.3.5-19 14.3.5-20

14. 3. 5-21 14.3.5-22 14.3.5-23 14.3.5-24 14.3.5-25 14.3.5-26 14.3.5-27 14.3.5-28 14.3.5-29 14.3.5-30 14.3.5-31 14.3.5-32 14.3. 5-1 14.3.5-2 14.3.5-3 14.,3.5-4 14.3.5-5 14 '.5-6 14.3.5-7 14.3.5-8 Date 1995 1982 1986 1982 1982 1982 1982 1982 1983 1982 1983 1986 1982 1986 1982 1982 1982 1983 1982 1982 1982 1982 1982 1982 1982 1995 1995 1995 1995 1995 1995 1995 1990 1990 1990 1990 1990 1990 1990 1990

Page 68 VOLUME IX Chapter 14 Safet Anal sis Unit 1 Table Fig.

Fig.

Table Table Table Table Table Table Table Table Pacae 14.3.5-9 pg 1 pg 2

pg 3

14.3. 5-1 14.3.5-2 14.3.5-3 14.3.5-4 14.3.5-5 14.3.5-6 14.3.6-1 14.3.6-2 14

~-3-. 6-'3 14.3.6"4 14.3.6-5 14.3.6-6 14.3.6-7 14.3.6-8 14 '.6-9

14. 3. 6-10

14. 3. 6-11

14. 3. 6-12 14.3.6-13 14.3.6-14

14. 3. 6-15 14.3. 6"16

14. 3. 6-17

14. 3. 6-18 14.3.6-19 14.3.6-20 14.3.6-21 14 '.6-22 14 '.6-23 14.3.6-24 14.3.6-25 14.3.6-26 14.3.6-27 14.3.6'-28 14.3.6-29 14

~ 3. 6-1 14.3.6-2 14.3.6-3 14.3.6-4 14.3.6-5 14 '.6-6 14.3.6-7 14.3.6-8 Date 1995 1995 1995 1982 1982 1982 1982 1987 1987 1989 1982 1991 1989 1982 1982 1982 1982 1982 1982 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1991 1990 1991 1990 1990 1990 1990 1990 1990 1990 1990

Page 69 VOLUME IX Chapter 14 Sachet Anal sis Unit 1 Table Table Table Table Table Table Table Table Table Fig.

Fig.

Fig:"

Fig.

Pacae 14.3.6-9 14.3.6-10

14. 3. 6-11 14.3.6>>12 14.3.6-13 14 '.6-14 14.3.6-15

14. 3. 6-16 14.3. 6-17 (2pp) 14.3.6-1 14.3.6-2 14;3.'6"6-

14.3.6-7 14.3.6-8 14.3.6-9 14.3.6-10

14. 3. 6-11

14. 3. 6-12 14.3.6-13 14.3.6-14 14.3.6-14A 14.3.6-15 14.3.6-16 14.3.6-17

14. 3. 6-18 14.3.6-19 14.3.6-20 14

~ 3. 6-21

14. 3. 6-22 14.3.7-1 14.3.8-1 14.4.1-1 14.4.2-1 14.4.2-2 14.4.2-3 14.4.2-4 14.4.2-5 14.4.2-6 14.4.2-7 14.4.2-8 14.4.2-9 14.4.2-10 14.4.2-11 14.4.2-12

14. 4. 2-13 14.4.2-14 Date 1990 1990 1990 1990 1990 1990 1990 1990 1990 1982 1982 1990" 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1990 1993 1993 1990 1987 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1987 1982

Page 70 VOLUME IX Chapter 14 Safet Anal sis Unit 1 Table Table Table Table Table Fig.

Fig.

pig.

Fig.

pig.

Fig.

pig.

Fige Fig.

Table Table Pa<<ae 14.4.2-15 14.4.2-16 14.4.2-17 14.4.2-18

14. 4. 2-19 14.4.2-20

14. 4. 2-21 14.4.2-22 14.4.2-23 14.4.2-24 14.4.2-25 14.4";2-26 14.4.2-27 14.4.2-28 14.4.2-1 (8pp) 14.4.2-2 14.4.2-3 14.4.2-4 14.4.2-5 (4pp) 14.4.2-1 14.4.2-2 14.4.2-3 14.4.2-4 14.4.2-5 14.4.2-6 14.4.2-7 14.4.2-8 14.4.2-9 14.4.2-10 14.4.2-11 14.4.2-12 14.4 '-13 14.4.2-14

14. 4. 2-15 14.4.2-16 14.4.2-17 14.4.2-18 14.4.2-19 14.4.2-20 14.4.2-20A 14.4 '-21 14.4. 3-1 14.4.3-2 14.4.3-3 14.4.3-4 14.4.3-5 14.4.4-1 14.4. 4-1 14.4.4-2 Date 1982 1982 1982 1982 1982 1982 1982 1995 1982 1995 1982 1982 1982 1990 1990 1994 1990 1990 1990 1982 1982 1982 1982 1982 1982 1982 1995 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1995 1982 1990 1990 1993 1990 1990 1995 1990 1990

Page 71 VOLUME IX Chapter 14 Safet Anal sis Unit 1 Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Fig.

Fig.

Pacae 14.4.4-3 14.4.4-4 14.4.4-5 14.4.4-6 14.4.5-1 14.4.5-2

14. 4. 6-1 14.4.6-2 14.4.6-3 14.4.6-4 14.4.6-5 14.4";6-6 14.4.6-7 14.4.6-1 14.4.6-2 14.4.6-3 14.4.6-3a 14.4.6-4 14.4.6-4a 14.4.6-5 14.4.6-5a 14.4.6-6 14.4.6-6a 14.4.6-6b 14.4.6-6c 14.4.6-7 14.4.6-8 14.4.6-9

14. 4. 6-10

14. 4. 6-11 14.4.6-12 14.4. 6-13 14.4.6-14 14.4. 6-15 (2pp)

(3pp)

(2pp)

(5pp)

14. 4. 6-15a 14.4. 6-16 14.4.6-16a 14.4.6-17 14.4. 6-18 14

~ 4. 6-19 14.4.6-20 14.4.6-1 14.4.6-2 14.4.6"3 14.4.6-4 14.4.6-5 14.4.6-6 14.4.6-7 14.4.6-8 14.4.6-9 14.4.6-9a 14 '.6-9b Date 1990 1990 1990 1990 1990 1990 1994 1994 1994 1990 1993 1990 1993 1990 1990 1993 1993 1993 1993 1993 1993 1990 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994 1982 1982 1982 1982 1993 1993 1987 1987 1993 1993 1993

Page 72 VOLUME IX Chapter 14 Safet Anal sis Unit 1 Fig.

Fig.

Fig;-

Table Table Table Table Table Table Table Table Table Table Pacae 14.4. 6-10 14.4.6-10a 14.4.6-11 14.4. 6-11a 14.4.7-1 14.4.7-2 14.4. 8-1 14.4.9-1 14.4.9-2 14.4.9-3 14.4. 9-1

14. 4. 9-2-- '-

14.4. 10-1 14.4. 10-2 14.4.10-3 14.4. 10-4 14.4. 10-1 14.4. 11-1

14. 4. 11-2 14.4.11-3 14.4. 11-4

14. 4. 11-5 14.4.11-6

14. 4. 11-7 14.4.11-1 (pg (pg (pg (pg (pg (pg (pg (pg (pg (pg (pg 14.4.11-2

14. 4. 11-3 14.4.11-4 14.4.11-5 14.4.11-6

14. 4. 11-7

14. 4. 11-8

14. 4. 11-9 14A-1 14A-2 14A-3 14A-4 14A-5 14A-6 14A-7 14A-8 14A-9 14A-10 1) 2)

3) 4)

5) 6)

7) 8)

9) 10)

Date 1993 1993 1993 1992 1990 1990 1990 1990 1990 1990 1982 1982 1990 1990 1990 1990 1990 1990 1990 1994 1990 1990 1990 1990 1993 1993 1995 1993 1994 1994 1995 1990 1994 1994 1993 1994 1990 1990 1990 1990 1990 1990 1992 1992 1982 1982 1982 1982 1982 1982 1982 1982 1982

Page 73 VOLUME IX Chapter 14 Safet Anal sis Unit 1 Table Table Table Fig.

Fig.

~acae 14A-11 14A-12 14A-13 14A-14 14A-15 14A-16 14A-17 14A-18 14A-19 14A-20 14A-21 14A-22 14A-23 14A-24 14A-25 14A-26

14. G-1 14.G-2 14.G-3 14.G-4 14.G-5

14. G-6

14. G-7 14.G-8 14.G-9 14.G-10

14. G"11

14. G-12 14.G-1 14.G-2 14.G-3 14. G-1 (3pp) 14.G-1 Notes 14.G-2 Date 1982 1992 1992 1992 1992 1993 1993 1992 1992 1992 1992 1992 1992 1992 1992 1992 1987 1987 1987 1987 1987 1987 1987 1987 1987 1987 1987 1988 1987 1987 1987 1988 1988 1987

Page 74 VOLUME X Chapter 14 Safet Anal sis Unit 2 Pacae

14. 0-3.

14.0-2 14.0-3 14.0-4

14. 0-5

14. 1-1

14. 1-2

14. 1-3 14 r 1=4'4.1-5

14. 1-6 14.1-7 14.1-8

14. 1-9

14. 1-10

14. 1-11

14. 1-12 14

~ 1-13

14. 1-14 Table 14.1.0-1 Table 14. 1. 0-1 Table 14.1.0-1 Table 14. 1. 0-2 Table 14.1.0-3 Table 14. 1. 0-4 Table 14.1. 0-5 Table 14.1.0-6 Fig. 14.1.0-1 Fig. 14. 1 ~ 0-2 Fig. 14. l. 0-3 Fig. 14. 1. 0-4 Fig. 14. 1. 0-5 Fig. 14. 1. 0-6 Fig. 14.1.0-7

14. 1. 1-1 14.1.1-2

14. 1 ~ 1-3

14. 1. 1-4 14.1.1-5

14. 1. 1-6 14.1 Refe Table 14.1.1-1 Fig. 14. 1. 1-1 (pgl)

(pg2)

(pg3)

(3 pgs)

(2 pgs)

(3 pgs) rences Date 1995 1995 1995 1995 1995 1993 1995 1995 1993*

1993 1995 1993 1995 1995 1995 1995 1995 1995 1995 1993 1993 1995 1995 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1991 1991 1991 1991 1991 1991 1991 1992

Page 75 Chapter 14 VOLUME X Safet Anal sis Unit 2 Fig.

Fig Fig.

Fig.

Pacae

14. 1. 1-2

14. l.2A-1 14.1.2A-2

14. 1. 2B-1

14. 1.2B-2

14. 1.2B"3

14. 1. 2B-4

14. 1.2B-S

14. 1. 2B-6 14.1

~ 2B-7

. 14. 1.2B-.l

14. 1. 2B-2

14. 1. 2B-3

14. 1. 2B-4

14. 1.2B-5

14. 1. 2B-6 14

~ 1. 2B-7

14. 1.2B-B

14. 1. 2B-9

14. 1. 3-1 14.1.3-2 14.1.3-3 14.1.3-4 14.1.3-5

14. 1.3-6

14. 1. 3-7

14. 1. 3-1 14". 1. 3-2

14. l.4-1 14.1.5-1

14. 1.5-2 14.1.5-3

14. l. 5-4

14. 1. 5-5 Date 1992 1995 1995 1991 1993 1991 1991 1991 1991 1991 1991-,

1991 1991 1991 1991 1991 1991 1991 1991 1993 1991 1995 1995 1995 1995 1995 1991 1991 1991 1991 1991 1991 1991 1991

Page 76 VOLUME X Chapter 14 Safet Anal sis Unit 2 Table Table Fig.

Fig.

Table Fig.

Pacae

14. 1. 5-6 14.1 '-7 14.1.6-1

14. 1. 6-2 14

~ 1. 6-3

14. 1. 6-4 14.1.6-5 14.1.6-6 14.1.6-7 14.. 1. 6-..8 -...

14. 1. 6-9

14. 1.6-10

14. 1. 6-11

14. 1. 6-1 14.1.6-2 14.1.6-1 14.1.6-2 14.1.6-3

14. 1. 6"4 14.1.6-5

14. 1. 6-6

14. 1. 6-7 14.1.6-8 14.1.6-9

14. 1. 6-10

14. 1. 6-11

14. 1. 6-12 14.1.7-1

14. 1. 7-2

14. l. 7-3

14. 1. 7-4

14. 1. 7-5

14. 1.7-1 14. 1. 8A-1 14. 1. BA-2 Date 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991.

1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1992 1995 1995

Page 77 VOLUME X Chapter 14 Safet Anal sis Unit 2 Pacae Date Table Pig.

Fig.

Pig.

Fig.

Fige Fig.

Pig.

Fig.

Table Fig.

Pig.

Fig.

14. 1. 8B-1

14. 1. 8B-2

14. 1. 8B-3

14. 1. 8B-4 14.1.8B-5 14.1.8B-6 14.1.8B-1 (2pgs)

.14.1

~ 8B=1..(2pgs)...

14. 1. 8B-2

14. 1. 8B-3

14. 1. 8B-4 14.1.8B-S 14.1.8B-6 14.1.8B-7

14. 1. 8B-8

14. 1. 8B-9

14. 1. 8B-10

14. 1. 8B-11

14. 1. 8B-12

14. l.9-1

14. l. 9<<2 14.1.9-3

14. 1. 9-4

14. 1.9-5

14. 1. 9-6

14. 1. 9-1

14. 1. 9-1 14.1.9-2

14. 1. 9-3

14. 1. 10A-1

14. 1 ~ 10A-2 1991 1991 1995 1995 1993 1991 1995 1995-1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1991 1991 1995 1995 1991 1991 1991 1992 1992 1992 1995 1995

Page 78 Chapter 14 VOLUME X Safet Anal sis Unit 2 Pacae Date Table Table Table Table Fig.

Fig.

Table Fig.

Fig.

14. 1. 10B-1

14. 1. 10B-2

14. 1. 10B-3

14. 1. 10B-4 14.1.10B"5 14.1.10B-6

14. 1. 10B-7

14. 1. 10B-8

-14. 1. 10B 9.

14. 1. 10B-1

14. 1. 10B-2

14. 1. 10B-3

14. 1. 10B-4

14. 1. 10B-1

14. 1. 10B-2

14. 1. 10B"3

14. 1. 10B "4

14. 1. 10B-5 14.1.10B-6

14. 1. 10B-7 14.1.10B-8

14. 1. 11A-1

14. 1. 11A-2

14. 1. 11B-1

14. 1. 11B-2

14. 1. 11B"3 14.1.11B-4

14. 1. 11B-5

14. 1. 11B-1

14. l.11B-2 1991 1991 1993 1993 1991 1993 1993 1991 1991 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1995 1995 1991 1993 1991 1991 1991 1991 1991 1991

Page 79 Chapter 14 VOLUME X Safet Anal sis Unit 2 Fig.

Fig.

Table Fig.

Fig.

Table Table Table Table Table Table Fig.

Pa<ac

14. 1. 11B-3

14. 1. 11B-4

14. 1. 11B-5

14. 1. 11B-6

14. 1. 11B-7

14. 1. 11B-8

14. 1. 12-1 14.1.12-2 14.1.12-3

14. 1. 12-4 14.1-.12 14. 1. 12-1 14.1.12-1

14. 1. 12-2

14. 1. 13-1

14. 2-1 14.2.1-1 14.2.2-1 14.2.2-2 14.2.2-3 14.2.2-4 14.2.2-5 14.2.2-1 14.2.2-2 14.2.2-3

14. 2. 3-1 14

~ 2.4-1 14.2.4-2 14.2.4-3 14.2.4-4 14.2.4-5 14.2.4-6 14.2.4-7 14.2.4-8 14.2.4-9 14.2.4-1 14.2.5-1 14 '.5-2 14.2.5-3 14.2.5-4 14.2.5-5 14.2.5-6 14.2.5-7 14.2.5-8 14.2.5-9 14.2.5-10

14. 2

~ 5-11 14 '.5-1 14.2.5-2 (2pp) 14.2.5-1 Date 1991 1991 1991 1991 1991 1991 1991 1991 1995 1995 1991 1991 1992 1992 1991 1995 1993 1993 1993 1993 1994 1991 1991 1993 1993 1991 1991 1991 1991 1991 1994 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991

Page 80 Chapter 14 VOLUME X

'Safet Anal sis Unit 2 Fig.

Fig.

Table Fig.

Fig.

Table Fig.

Fig.

Pacae 14.2 '-2 14.2.5-3 14.2.5-4 14.2.5-5 14.2.5-6

14. 2

~ 6-1 14.2.6-2 14.2.6-3 14.2.6-4 14.2.6-5 14.-2v6-6 --

~

14.2.6-7 14.2.6-8 14 '.6-9

14. 2. 6-10

14. 2. 6-11 14.2.6-12 14.2.6-13 14.2.6-14 14.2. 6-15 14.2.6-16

14. 2. 6-17 14.2. 6 "1 14.2. 6-1 14.2.6-2 14

~ 2. 7-1 14.2.8-1 14.2.8-2 14.2 '-3 14.2.8-4 14.2.8-5 14.2.8-6 14.2.8-7

14. 2. 8-1 (3pp) 14.2. 8-1 14.2.8-2 14.2.8-3 14 '.8-4 14.2.8-5 14.2.8-6 14.2.8-7 14.2.8-8 Date 1991 1992 1992 1991 1991 1991 1991 1991 1991 1991 1991-1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1993 1991 1991 1991 1995 1995 1995 1995 1995 1991 1991 1991 1991 1991 1991 1991 1991

Page 81 VOLUME X Chapter 14 Safet Anal sis Unit 2 Table Table Table Table Table Table Table Table Table Table Fig o Fig.

Fig.

Pacae 14.3.1-1 14.3. 1-2

14. 3. 1" 3 14.3.1-4 14.3.1-5

14. 3. 1-6 14.3.1-7 14.3.1-8 14.3.1-9 14.3.;1-10-.

14.3. 1-11

14. 3. 1-12

14. 3. 1-13 14.3.1-14

14. 3. 1-15 14.3. 1-16 14.3.1-17 14.3.1-1 (2pp) 14.3.1-2 14.3.1-3 14.3.1-4 (2pp) 14.3.1-5 14.3. 1-6 14.3.1-7 14.3.1-8 14.3.1-9

14. 3. 1-10

14. 3. 1-30 14.3.1-31 14.3.1-1 14.3.1-2 14.3.1-3 14.3.1-4 14.3.1-5 14.3.1-6 14.3.1-7 14.3.1-8 14

~ 3. 1-9

14. 3. 1-10 14.3. 1-11

14. 3. 1-12 14.3. 1-13 14.3.1-14

14. 3. 1-15 14.3. 1-16 14.3. 1-17

14. 3. 1-18

14. 3. 1-19

14. 3. 1-20

14. 3. 1-21 Date 1995 1991 1991 1991 1991 1991 1991 1991 1993 1993 1995 1995 1995 1995 1991 1991 1994 1991 1991 1991 1991 1992 1994 1992 1992 1992 1992 1995 1995 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991

Page 82 VOLUME XI Chapter 14 Safet Anal sis Unit 2 Fig.

Fig.

'Fig.

Fig.

Table Table Table Table Table Table Table Table Table Table Table Table Table Pacae

14. 3. 1-22 14.3.1-23

14. 3. 1-24

14. 3. 1-25

14. 3. 1-26

14. 3. 1-27 14.3.1-28 14.3.1-29 14.3.1-30 14. 3~1 14.3.1-25

14. 3. 1-26 14.3. 1"27 14.3.1-28 14.3.1-29 14.3.1-'30 14.3.1-31 14.3. 2-1 14.3.2"2 14.3.2-3 14.3.2-4 14.3.2-5 14.3.2-6 14.3.2-7 14.3.2-7a 14.3.2-7b 14.3.2-7c 14.3.2-8 14.3.2-1 14.3.2-2 14.3.2-3 14.3.2"4 14.3.2-5 14.3.2-6 14.3.2-7 14.3.2-8 14.3.2-9

14. 3. 2-10

14. 3. 2-11 14.3.2-12 14.3.2-13 Date 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1995 1995 1991 1991 1991 1991 1991 1991 1992 1995 1995 1995 1994 1991 1991 1992 1994 1991 1991 1992 1994 1991 1995 1995 1995 1995

Page 83 VOLUME XI Chapter 14 Safet Anal sis Unit 2 Pacae Date Fig.

Fig.

Pig.

Fig.

Pig.

Fig.

Pig.

Fig.

Pig.

Fig.

14.3.2-1 14.3.2"2 14.3.2-3 14.3.2-4 14.3.2-5 14.3.2-6 14.3.2-7

'4.3.2-8

-14.3.2 14. 3. 2"10

14. 3. 2-11 14.3.2-12 14.3.2-13 14.3.2-14 14.3.2-15 14.3.2-16

14. 3. 2-17 14 '.2-18 14.3.2-19 14.3.2"20 14.3.2 "21 14.3.2-22 14.3.2-23 14.3.2-24 14.3.2-25 14.3.2-26 14.3.2-27 14.3.2-28 14.3.2-29 14.3.2-30 14.3.2-31 14.3.2-32 14.3.2-33 14.3.2-34 14.3.2-35 14.3.2-36 14.3.2-37 14.3.2-38 14.3.2-39 14.3.2-40 14.3.2-41 14.3.2-42 14.3.2-43 14.3.2-44 14.3.2-45 14.3.2-46 14.3.2-47 14.3.2-48 14.3.2-49 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991

Page 84 Chapter 14 VOLUME XI Safet Anal sis Unit 2 Fig.

Fig.

Fige Fige Fig.

Fig.

Fige Figi Fig.

Fig.

Pacae 14.3.2-50 14.3.2-51 14.3.2-52 14.3.2-53 14.3.2-54 14.3.2-55 14.3.2-56 14.3.2-57 14.3.2-58 14.3.2-59

-14.3.2-60

14. 3. 2-61 14.3.2-62 14.3.2-63 14.3.2-64 14.3.2-65 14.3.2-66 14 '.2-67 14.3.2-68 14.3.2-69 14.3.2-70 14.3.2-71 14.3.2-72 14.3.2-73 14.3.2-74 14.3.2-75 14.3.2-76 14.3.3-1 14.3.3-2 14.3.3-3 14.3.3-4 14.3.3-5 14.3.3-6 14.3.3-7 14.3.3-8 14.3.3-9 14.3.3-10

14. 3. 3-11

14. 3. 3-12 14.3.3-13 14.3.3-1 14.3.3-2 14.3.3-3 14.3.3-4 Date 1991 1991 1991 1991 1991 1991 1991 1991 1991 1991 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1995 1994 1995 1994 1995 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994 1994

Page 85 Chapter 14 VOLUME XII Safet Anal sis Unit 2 Pacae Date Fig.

Fig.

Table-Table Table Table Table Table Fig.

Fig.

14.3.3-5 14.3.3-6 14.3.3-7 14.3.3-8 14.3.4-1 14.3.5-1 14.3.5-2 14.3.5-3 14.3.5-4 14.3 5-1.

14.3.5-2 14.3.5-3 14.3.5-4 14.3.5-5 (3 pp) 14.3.5-6

14. 3. 6-1 14.3.7-1 14.3.7-2 14.3.7-3 14.3.7-4 14.3 '-5 14.3.7-6 14.3.7-7 14.3.7-8 14.3 '-9 14.3.7-10

14. 3. 7-11 14.3.7-1 14.3.7-2 14 '.7-3 14.3.7-4 14.3.7-5 14.3.7-6 14.3.7-7 14.3.7-8 14.3.7-9 14.3.7-10 14.3. 7-11 14.3.7-12 14.3.7-13

14. 3. 7-14 14.3.7-15 14.3. 7-16 14.3.7-17.

14. 3. 7-18 14.3. 7-19 14.3.7-20 14.3.8-1 14.3.8-2 14.3.8-3 14.3.8-4

14. 3. 8-1 14.3.8-2 14.3.8-3 14.4-1 14.A-1 1994 1994 1994 1994 1992 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1990 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1993 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1982 1985 1982 1982 1985 1982 1982 1993 1993 1993 1993 1982 1982 1982 1991 1989

Page 86 Chapter 14 Appendix J Safet Anal sis VOLUME XII Pacae Date ORIG

Page 87 Chapter 14 Appendix M

Safet Anal sis VOLUME XIII Pacae Date ORIG

CHAPTER 2 LIST OF TABLES 2.1-1 2 ~ 1 2 2.1-3 2.1-4 2.1-5 2.1-6 2.1-6a 2.1-7 2.1-7a 2.1-8 2.1-8a 2.1-8b 2.1-9 2.1-10 2.1-11 2.1-12 Population Trends of the Counties Surrounding the Donald C.

Cook Nuclear Plant Site Population Trends of Cities and Townships in Berrien County, Michigan Population Centers of 25,000 or More Within 60 Miles of the Donald C.

Cook Nuclear Plant Site DELETED Population Distribution, 1975 Population Distribution, 1990 Population Distribution, 1990 Projected Population Distribution, 2000 Projected Population Distribution, 2000 Projected Population Distribution, 2037 Projected Population Distribution, 2037 Transient Population Distribution, 1 Mile Increments, 1971 Agricultural Statistics Principal Industries (1992)

School Population Hospitals in Berrien County, 1993 2.2-1 2.2-2 2.2-3 2.2-4 2.2-5 2.2-6 2 ~ 2 7 2.2-8 2.2-9 Data Summary Sheet Meteorological Data Z/Q Ground Average Hours at Each Wind Speed and Direction, Hours at Each Wind Speed and Direction, Hours at Each Wind Speed and Direction, Hours at Each Wind Speed and Direction, Hours at Each Wind Speed and Direction, Hours at Each Wind Speed and Direction, S tability S tability Stability Stability Stability Stability Class:

A Class:

B Class:

C Class:

D Class:

E Class:

F July 1995

2.2-10 2.2-11 2.2-12 2.2-13 2.2-14 2.2-15 2.2-16 2.2-17 2.2-18 2.2-19 2.2-20 2.2-21 2.2-22 2.2-23 2.2-24 2.2-25 2.2-26 2.2-27 2.2-28 2.2-29 2.2-30 2.2-31 2.2-32 2.2-33 2.5-1 2.6-1 2.6-2 Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted CHAPTER 2 LIST OF TABLES (Cont'd)

Earthquakes with Epicenters Located Within 200 Miles of Plant Site Bibliography of Reports Produced as Part of Initial Phase of Donald C.

Cook Nuclear Plant Environmental Impact Assessment Bibliography of Reports Produced as Part of Pre-Operational Phase and Operational or Technical Specification, Appendix B, Required Studies of the Impact of Donald C. Cook Nuclear Plant Outfalls on Lake Michigan 2-vi July 1995

CHAPTER 3 TABLE OF CONTENTS Section Title 3.0 REACTOR 3.1-1 3.1 3.1.1 3.1.2 3.1.3

SUMMARY

DESCRIPTION Performance Obj ectives Principal Design Criteria Safety Limits 3.1-1 3.1-2 3.1-4 3.1-11 3.2 3.2.1 3.2.1 3.2.2 MECHANICAL DESIGN Mechanical Design and Evaluation References Core Component Tests and Inspections 3.2-1 3.2-1 3 '-54 3.2-44 3.3 3.3.1 3.3.2 3.3.3 3.3 '

3.3.1 3.3.2 3.3.3 NUCLEAR DESIGN Nuclear Design and Evaluation Physics Tests Anticipated Transients Without Trip Criticality of Fuel Assemblies References References References 3.3-1 3.3-1 3.3-24 3.3-25 3.3-25 3.3-26 3.3-26 3.3-27 3.4 3.4.1 3'.2 3.4 3.4.2 THEBMAL AND HYDRAULIC DESIGN Thermal and Hydraulic Evaluation for the Initial Core Thermal and Hydraulic Tests and Inspections References References 3.4-1 3.4-1 3.4-17 3.4-18 3.4-21 4

UNIT 1 3-i July 1995

CHAPTER 3 TABLE OF CONTENTS (Cont'd)

Section Title

~Pa e

3.5 3.5.1 3.5 3.5.2 3.5.2 3.5.3 3.5.3 CURRENT WESTINGHOUSE OFA RELOAD FUEL Fuel Mechanical Design 3.5.1 References Nuclear Design References Thermal and Hydraulic Design References 3.5-1 3.5.1-1 3.5.1-17 3.5.2-1

~ 3.5.2-6 3.5.3>>1 3.5.3-13 UNIT 1 3-ii July 199

CHAPTER 3 LIST OF TABLES Table 3120 1"1 3.2.2-1 Tl.@la Initial Core Mechanical Design Parameters Thermal and Hydraulic Design Parameters 3.3.1-1 3.3.1-2 3.3.1-3 Nuclear Design Data Reactivity Requirements. for Control Rods Calculated Rod Vorths, hp (Unit gl) 3.4.1-1 3.4.1-2 3.4.1-3 Thermal and Hydraulic Design Parameters Engineering Hot Channel Factors Sensitivity Analysis 3.5.1-1 3.5.1-2 3.5 '-1 3.5.2-2 3.5.2-3 3.5.3-1 Westinghouse 15 x 15 OFA Design Parameters Deleted Fuel Assembly Design Parameters, Cook Nuclear Plant-Unit 1, Cycle 14 Kinetics Characteristics, Cook Nuclear Plant Unit 1-With Westinghouse OFA Fuel Shutdown Requirements and Margins, Cook Nuclear Plant Unit 1 - Cycle 14 Cook Nuclear Plant Unit 1 Thermal-Hydraulic Design Parameters UNIT 1 3-iii July 1995

CHAPTER 3 LIST OF FIGURES

~Fl use 3.2.1-1 3.2.1-2 3.2.1-3 3.2.1-4 3.2 '-5 3.2.1-6 3.2.1-7 3.2.1-8 3.2.1-9 3.2.1-10 3.2.1-11 3.2.1-12 3.2 '-13 3.2.1-14 Title Core Cross Section Reactor Uessel and Internals Fuel Loading Arrangement Typical Rod Cluster Control Assembly Core Barrel Assembly Upper Core Support Structure Guide Tube Assembly Fuel Assembly and Control Cluster Cross Section Fuel Assembly Outline Spring Clip Grid Assembly Neutron Source Locations Burnable Poison Control Rod Drive Mechanism Assembly Control Rod Drive Mechanism Schematic 3.3.1-1 30311"2 3.3.1-3 3.3.1-4 3.3.1-5 to 3.3.1-10 3.3.1-11 3.3.1-12 3.3.1-13 Control Rod Pattern (Unit 1)

Cycle 1 Assemblywise Power (BOL)

Cycle 1 Assemblywise Power (MOL)

Cycle 1 Assemblywise Power (EOL)

These figures have been intentionally deleted.

Distribution of Burnable Poison Rods

- Number of B.P.

Rods per Assembly, Unit 1, Cycle 1 Arrangement of Burnable Poison Rods Within an Assembly, Unit 1, Cycle 1

Moderator Temperature Coefficient vs. Moderator Temperature, BOL, No Control Rods Inserted UNIT 1 3-iv July 1995

CHAPTER 3 LIST OF FIGURES (Cont'd)

~F1 uue 3.3.1-14 3.3.1-15 3.3.1-16 3.3.1-17 Title Moderator Temperature Coefficient vs. Moderator Temperature, BOL, All Control Rods Inserted Moderator Temperature Coefficient vs. Moderator Temperature, (EOL)

Doppler Coefficient vs.

Resonance Effective Temperature Doppler Contributions to the Power Coefficient vs.Power Level 3.4.1-1 3.4.1-2 3.4.1-3 3.4.1-4 3.4.1-4a 3.4,1-5 3.4.1-6 3.4.1-7 3.4.1-8 3.4.1-9 Thermal Conductivity of U02 (Data Corrected to 95 Percent Theoretical Density)

High Power Fuel Rod Experimental Program Comparison of W-3 Prediction and Uniform Flux Data W-3 Correlation Probability Distribution Curve Rod Control Cluster Assembly Outline Comparison of W-3 Correlation With Rod Bundle DNB Data (Simple Grid Without Mixing Vane)

Compaiison of W-3 Correlation with Rod Bundle DNB Data (Simple Grid With Mixing Vane)

Comparison of Non-Uniform DNB Data With W-3 Predictions Comparison of W-3 Prediction With Measured DNB Location Radial Power Distribution 3.5.1-1 3.5.1-2 3.5.1-3 3.5.1-4 3.5.1-5 3.5.1-5a Schematic Comparison of Westinghouse 15x15 OFA With ENC Fuel Assembly Dimensions Reactor Core Fuel Assembly Reload Pattern Plan View of Mid Grid to Guide Thimble Joint (Bottom View)

Elevation View of Mid Grid to Guide Thimble Joint Top Grid to Guide Thimble and Top Nozzle Attachment Top Grid to Guide Thimble and Removable Top Nozzle Attachment UNIT 1 3-v July 1995

CHAPTER 3 LIST OF FIGURES (Cont'd)

~Fi uee Title 3.5.1-6 3.5.1-7 3.5.1-8 3.5.1-9 3.5.2-1 3.5.2-2 3.5.3-1 3.5.3-2 3.5.3-3 Guide Thimble to Bottom Grid and Nozzle Joint Bottom Nozzle to Thimble Tube Connection Deleted Deleted Cook Nuclear Plant Unit 1 - Cycle 14 Example Core Loading Pattern Heat Flux Hot Channel Factor Normalized Operating Env'elope,

+ ECCS Limit - 2.15 Cook Nuclear Plant Unit 1 - Cycle 14 Measured vs. Predicted Critical Heat Flux - RE 1 Correlation TDC vs Reynoids Number for 26" Grid Spacing Improved Thermal Design Procedure Illustration UNIT 1 3-vi July 1995

CHAPTER 3 TABLE OF CONTENTS Section

~Pa e

3.0 REACTOR 3.1-1 3.1 3.1.1

SUMMARY

DESCRIPTION References 3.1-1 3.1-5 3.2 3.2.1 3.2.2 3.2.3 MECHANICAL DESIGN Fuel Reactor Vessel Internals Reactivity Control System 3 '

1 3.2-2 3.2-36 3.2-47 3.2 References 3.2-92 3.3 3.3.1 3.3.2 3.3.3 3.3 NUCLEAR DESIGN Design Bases Description Analytical Methods References 3.3-1 3.3-1 3.3-9 3 ~ 3 55 3.3-59 3.4 3.4.1 THERMAL AND HYDRAULIC DESIGN Design Bases 3.4-1 3.4-1 UNIT 2 3-i July 1995

CHAPTER 3 TABLE OF CONTENTS (Cont'd)

Section Title

~Pa e

3.4.2 3.4.3 3.4.4 Description Evaluation Testing and Verification 3.4-5 3.4-33 3.4-53 3.4.5 3.4 Instrumentation Application References 3.4-54 3.4-57 3.5 3.5.1 3.5.2 ANF FUEL DESIGN Fuel and Mechanical Design References Thermal-Hydraulic Design

" References 3.5-1 3.5-1 3.5-20 3.5-26 3.5-28 UNIT 2 3-ii July 199

CHAPTER 3 LIST OF FIGURES (Cont'd)

~Fl ure Title 3.4-7 3.4-8 3.4-9 3.4-10 3.4-11 3.4-12 3.4-13 3.4-14 3.5.1-1 3.5.1-2 3.5.1-3 3,5.1-4 Void Fraction Versus Thermodynamic Quality H-HSTAT/Hg-HSAT 100 Percent Power Shapes Evaluated at Conditions Representative of Loss of Flow All Shapes Evaluated with FNH 1 ~ 59 PWR Natural Circulation Test Comparison of a Representative W Two-Loop Reactor Incore Thermocouple Measurements with THING-IV Predictions Comparison of a Representative W Three-Loop Reactor Incore Thermocouple Measurements with THING-IV Predictions Hanford Subchannel Temperature Data Comparison with THING-IV Hanford Subcritical Temperature Data Comparison with THING-IV Distribution of Incore Instrumentation Fuel Bundle Assembly Fuel Bundle Assembly Bundle Overall Pressure Drop Rod Bow for ENC 17xl7 Fuel UNIT 2 3-vii July 1995

CHAPTER 3 TABLE OF CONTENTS 3.0 3.1-1 3.1 3.1.1 3.1.2 3.1.3

SUMMARY

DESCRIPTION Performance Ob)ectives Principal Design Criteria Safety Limits 3.1-1 3.1-2 3.1-4 3.1-11 3.2 3.2.1 3.2.1 3.2.2 MECHANICAL DESIGN Mechanical Design <<nd Evaluation References Core Component Tests and Inspections 3.2-1 3.2-1 3.2-54 3.2-44 3.3 3.3.1 3.3.2 3.3.3 3.3.4 3.3.1 3.3.2 3.3.3 NUCLEAR DESIGN Nuclear Design and Evaluation Physics Tests Anticipated Transients without Trip Criticality of Fuel Assemblies References References References 3.3-1 3.3-1 3.3-24 3 ~ 3~25 3.3-25 3.3-26 3.3-26 303-27 3.4 THERMAL AND HYDRAULIC DESIGN 3.4-1 3.4.1 Thermal and Hydraulic Evaluation for the Initial Core 3.4-1 3.4.2 3.4 3.4.2 Thermal and Hydraulic Tests and Inspections References References 3.4-17 3.4-18 3.4-21 UNIT 1 3-i July 1995

CHAPTER 3

TABLE OF CONTENTS (Cont'd) 3.5 3.5.1 3.5 3.5.2 3.5.2 3.5.3 3.5.3 CURRENT MESTINGHOUSE OFA RELOAD FUEL Fuel Hechanical Design 3.5.1 References Nuclear Design References Thermal and Hydraulic Design References 3.5-]

3.5.1-1 3.5.1-34 3.5.2-1 3.5.2-6 3.5.3-1 3.5.3-13 UNIT 1 3-ii July 1996

CHAPTER 3 LIST OF TABLES 3.2.1-1 3.2.2-1 Initial Core Hechanical Design Parameters Thermal and Hydraulic Design Parameters 3.3 l-l 3.3.1-2 3

~ 3

~ 1-3 Nuclear Design Data Reactivity Requirements for Control Rods Calculated Rod Worths, dp (Unit gl) 3.4.1-1 3.4.'

2 3.4.1-3 Thermal and Hydraulic Design Parameters Engineering Hot Channel Factors Sensitivity Analysis 3.5.1-1 3.5.1-2 3.5.2-1 3.5 '-2 3.5.2-3 3.5.3-1 Westinghouse 15 x 15 OFA Design Parameters Comparison of Burnable Absorber Rods Design Parameters Fuel Assembly Design Parameters, Cook Nuclear P'nt-Unit 1, Cycle 15 Kinetics Characteristics, Cook Nuclear Plant Unit 1 With Mestinghouse OFA Fuel Shutdown Requirements and Margins, Cook Nuclear Plant Unit 1

- Cycle 15 Cook Nuclear Plant Unit 1 Thermal-Hydraulic Design Parameters UNIT 1 3-iii July 1996

CHAPTER 3

LIST OF FIGURES Zig~

3.2,1-1 3.2.1-2 3.2.1-3 3.2.1<<4 3.2.1-5 3.2.1-6 3.2.1-7 3.2.1-8 3.2.1-9 3.c.1-10 3.2.1-11 3.2.1-12 3.2.1-13 3.2.1-14 3 '.1-15 3.3.1-1 3.3.1-2 3.3.1-3 3.3,1-4 3

~ 3 L

5 to 3.3.1-10 3.3.1-11 3 '.1-12 3.3.1-13 Core Cross Section Reactor Vessel and Internals Fuel Loading Arrangement Typical ".od Cluster Control Assembly Core Barrel Assembly Upper Core Support Structure Guide Tube Assembly Fuel Assembly and Control Cluster Cross Section Fuel Assembly Outline Spring Clip Grid Assembly Neutron Source Locations Burnable Poison Control Control Thimble Control Cycle 1

Cycle 1

Rod Drive Mechanism Assembly Rod Drive Mechanism Schematic Plug Assembly Rod Pattern (Unit 1)

Assemblywise Power (BOL)

Assemblywise Power (MOL)

Assemblywise Power (EOL)

These figures have been intentionally deleted.

Distribution of Burnable Poison Rods

- Number of B.P.

Rods per Assembly, Unit 1, Cycle 1

Arrangement of Burnable Poison Rods Withi.n an Assembly, Unit 1, Cycle 1

Moderator Temperature Coefficient vs. Moderator Temperature,

BOL, No Control Rods Inserted UNIT 1 3-iv July 1996

CHAPTER 3 LIST OF FIGURES (Cont'd) 3.3.1-14 3.3.1-15 3.3. 1-16 3.3.1-17 XirLa Moderator Temperature Coefficient vs. Moderator Temperature, BOL, All Control Rods Inserted Moderator Temperature Coefficient vs. Moderator Temperature, (EOL)

Doppler Coefficient vs. Resonance Effective Temperature Doppler Contributions to the Power Coefficient vs.Power Level 3.4. 1-1 3.4.1-2 3.4.1-3 3,4.1-4 3.4.1-4a 3.4.1-5 3.4.1-6 3.4.1-7 3.4.1-8 3.4.1-9 Thermal Conductivity of U02 (Data Corrected to 95 Percent Theoretical Density)

High Power Fuel Rod Experimental Program Comparison of W-3 Prediction and Uniform Flux Data W-3 Correlation Probability Distribution Curve Rod Control Cluster Assembly Outline Comparison of W-3 Correlation With Rod Bundle DNB Data (Simple Grid Without Mixing, Vane)

Comparison of W-3 Correlation with Rod Bundle DNB Data (Simple Grid With Mixing Vane)

Comparison of Non-Uniform DNB Data With W-3 Predictions A

Comparison of W-3 Prediction With Measured DNB Location Radial Power Distribution 3.5.1-1 3.5.1-2 3.5.1-3 3.5.1-4 3.5.1-5 3.5.1-5a Schematic Comparison of Westinghouse 15x15 OFA With ENC Fuel Assembly Dimensions Reactor Core Fuel Assembly Reload Pattern Plan View of Mid Grid to Guide Thimble Joint (Bottom View)

Elevation View of Mid Grid to Guide Thimble Joint Top Grid to Guide Thimble and Top Nozrle Attachment Top Grid to Guide Thimble and Removable Top Nozrle Attachment UNIT 1 3 v July 1995

CHAPTER 3

LIST OF FIGURES (Cont'd)

DghKR 3,5.1-6 3.5.1-7 3.5.1-8 3.5.1-9 3.5.2-1 3.5.2-2 3.5.3-1 3.5.3 2

3.5.3-3 Guide Thimble to Bottom Grid and Nozzle Joint Bottom Nozzle to Thimble Tube Connection Met Annular Burnable Absorber Rod Comparison of Borosilicate Glass Absorber Rod Mith MABA Rod Cook Nuclear Plant Unit 1 - Cycle 15 Example Core Loading Pattern Heat Flux Hot Channel Factor Normalized Operating Envelope, FQ ECCS Limit - 2.15 Cook Nuclear Plant Unit 1

- Cycle 14 Measured vs. Predicted Critical Heat Flux -

WRB 1

Correlation TDC vs Reynoids Number for 26" Grid Spacing Improved Thermal Design Procedure Illustration UNIT 1 3-vi July 1996

CHAPTER 3

TABLE OF CONTENTS 3.0 3.1-1 3.1 3.1.1 SURGERY DESCRIPTION References 3.1-1 3.1-5 3.2 3,2.1 3.2.2 3.2.3 MECHANICAL DESIGN Fuel Reactor Vessel Internals Reactivity Control Systeo 3.2-1 3 ~ 2 2

3.2-36 3.2-47 3.2 References 32-92 3.3 3.3.1 3.3.2 3.3.3 3.3 NUCLEAR DESIGN Design Bases Description Analytical methods References 3.3-1 3.3-1 3.3-9 3.3-55 3.3-59 3.4 3.4.1

'QKiRAL hND HYDRAULIC DESIGN Design Bases 3.4-1 3.4-1 VNIT 2 3-i July 1995

CHAPTER 3

ThBLE OF CONTENTS (Cont'd)

P~a 3.4.2 3.4.3 3.4.4 Description Evaluation Testing and Verification 3.4-5 3.4-33 3.4-53 3.4.5 3.4 Instrumentation Application References 3.4-54 3.4-57 3'. 5 3.5.1 3.5,2 ANF FUEL DESIGN DELETED Fuel and Mechanical Design (DELETED)

Thermal. Hydraulic Design (DELETED) 3.5-1 3.5-1 3'-2 UNIT 2 3-ii July 1996

CHAPTER 3 LIST OF FICURES (Cont'd) 3.4-7 3.4-8 3.4-9 3,4-10 3.4>>11 3.4-12 3.4-13 3.4-14 Void Fraction Versus Thermodynamic Quality H-HSTAT/Hg-HSAT 100 Percent Power Shapes Evaluated at Conditions Representative of Loss of Flow All Shapes Evaluated with FNH 1.59 PWR Natural Circulation Test Comparison of a Representative Q Two-Loop Reactor Incore Thermocouple Measurements with THINC-IV Predictions Comparison of a Representative g Three-Loop Reactor Incore Thermocouple Heasurements with THINC-IV Predictions Hanford Subchannel Temperature Data Comparison with THINC-IV Hanford Subcritical Temperature Data Comparison with THINC-IV Distribution of Incore Instrumentation 3,5 '-1 DELETED 3.5.1-2 DELETED 3.5.1-3 DELETED 3.5.1-4 Rod Bow for ENC 17x17 Fuel UNIT 2 3-vii July 1996 4

CHAPTER 4 LIST OF TABLES Table 4.1-1 4.1-2 4.1-3 4.1-4 4.1-5 4.1-6 4.1-7 4.1-8 4.1-9 4.1-10 4.1-11 4.1-12 Title System Design and Operating Parameters Reactor Coolant Syst: em Design Pressure Settings Reactor Vessel Design Data Pressurizer and Pressurizer Relief Tank Design Data Steam Generator Design Data Reactor Coolant Pumps Design Data Reactor Coolant Piping Design Parameters Pressurizer Valves Design Parameters Reactor Coolant System Design Pressure Drop Design Thermal and Loading Cycles Summary of Plant Outage for Yankee-Rowe (1964 to 1969)

Reactor Coolant System Codes 4.2-1 4.2-2 4.2-3 Materials of Construction of the Reactor Coolant System Components Reactor Coolant Water Chemistry Specification Steam Generator Water (Steam-Side)

Chemistry Specification for 100X Full Power 4.3-1 4.3-2 4.3-3 4.3-4 Summary of Estimated Primary Plus Secondary Stress Intensity for Components of the Reactor Vessel (Unit 1)

Summary of Estimated Cumulative Fatigue Usage Factors for Components of the Reactor Vessel (Unit 1)

Unit 1 Design Tube Sheet Stresses Due to Maximum Steam Generator Tube Sheet Pressure Differential (2485 psig).

Unit 1 Ratio of Allowable Stresses to Computed Stresses for a Steam Generator Tube Sheet Pressure Differential of 2485 psig 4-iii July 1995

CHAPTER 4 LIST OF TABLES Table 4.3-5 4.3-6 4.3-7 4.3-8

~Ttle 51,500 Sq. Ft.

Steam Generator Usage Factors (Individual Transients)

Primary and Secondary Boundary Components 51,500 Sq. Ft.

Steam Generator Usage Factors (Individual Transient)

Center of Tube Sheet Tube Sheet Stress Analysis Results for 51,500 Sq. Ft.

Steam Generators Limit Analysis Calculation Results Table of Strains, Limit Pressures, and Fatigue Evaluations for 51,500 Sq.'t.

Steam Generators 4.5-1 Reactor Coolant System Quality Control Program 4-iv July 1995

CHAPTER 4 LIST OF FIGURES

~Fi ure 4.2-1

4. 2-1A 4.2-2 4.2-2A 4.2-3 4.2-4 4.2-4A 4.2-5 4.2-6 4.2-7 4.2-8 4.2-9 Title Reactor Coolant System Flow Diagram Sheet 1

Reactor Coolant System Flow Diagram Sheet 2

Reactor Vessel Schematic Reactor Vessel Schematic Pressurizer Series 51 Steam Generator Repaired Steam Generator General Arrangement-Model 51F Steam Generator Reactor Coolant Pump Reactor Coolant Pump Flywheel Flywheel Characteristics Curve Reactor Coolant Pump Performance Characteristics Radiation Induced Increase in Transition Temperature for Mn-Mo Steel 4.3-1 4.3-2 4.3-3 4.3-4 4.3-5 4.3-6 4,3-7 Reactor Vessel Stress Analysis:

Areas Examined Reactor Vessel Stress Analysis:

Details

- Upper Reactor Vessel Stress Analysis:

Details

- Lower Primary.- Secondary Boundary Components Shell Locations of Stress Investigations Primary and Secondary Hydrostatic Test Stress History for the Center Hole Location Plant Heatup and Loading Operational Transients (with Steady-State Plateau)

Stress History for the Hot Side Center Hole Location Large Step Load Decrease and Loss of Flow Stress History for the Hot Side Center Hole Location 4.5-1 4.5-2 4.5-3 Surveillance Capsule Elevation View Surveillance Capsule Plan View Specimen Guide to Thermal Shield Attachment 4-v July 1995

CHAPTER 7 LIST OF TABLES Table 7.2-1 7.2-2 7.2-3 7.2-4 7'-5 Title List of Reactor Trips and Actuation Means of:

Engineered Safety Features, Containment and Steam Line Isolation and Auxiliary Feedwater Interlock Circuits Rod Stops Symbols and Abbreviations Process Control Block Diagram Drawing 108D087 Index 7.5-1 7.5-2 7.8-1 7.8-2 7.8-3 7.8-4 7.8-5 Engineered Safety Features Equipment Exposed Harsh Environment Type "A" Variables Provided the Operator for and Following an Accident Type "B" Variables Provided the Operator for and Following an Accident Type "C" Variables Provided the Operator for and Following an Accident Type "D" Variables Provided the Operator for and Following an Accident Type "E" Variables Provided the Operator for and Following an Accident to Manual Functions During Manual Functions During Manual Funct'ions During Manual Functions During Manual Functions During Process Instrumentation For RPS and ESF Actuation 7-iii July 1995

CHAPTER 7 LIST OF FIGURES

~Fi ure Title 702-2 7.2-3 7.2-4 7.2-5 7.2-6 7.2-7 7.2-8 7.2-9 Reactor Protection Systems Control Rod Bank Insertion Monitor Rod Deviation Comparator Pressurizer Pressure Protection System Pressurizer Level Protection Pressurizer Sealed Reference Leg Level System Steam Generator Level Protection Setpoint Reduction Function For Overpower and Overtemperature hT Trips 703-1 Simplified Block Diagram of Reactor Control System 7 '

1 7.5>>2 7.5-3 Containment Pressure Protection Environmental Conditions Inside Containment Loss-of-Coolant Accident Environmental Conditions Inside Containment Main Steam Line Break 7.6-1 7.6-2 7.6-3 InCore Instrumentation Details Typical Arrangement of Movable Miniature Neutron Flux Detector System (Elevation View)

Schematic Arrangement of InCore Flux Detectors (Plan View) 7-i.v July 1995

CHAPTER 9 TABLE OF CONTENTS Section 9.0 Title AUXILIARYAND EMERGENCY SYSTEMS

~Pa e

9.1-1 9.1 9.1.1 9.1.2 GENERAL DESIGN CRITERIA Auxiliary and Emergency Systems Criteria Related Criteria 9.1-2 9.1-2 9.1-3 9.2 9.2.1 9.2.2 9.2.3 9.2 CHEMICAL AND UOLUME CONTROL SYSTEM Design Bases System Design and Operation System Design Evaluation References 9.2-1 9.2-1 9.2-4 9.2-31

~

9.2-38 9.3 9.3.1 9.3.2 9.3.3 9.3.4 9.3.5 9.3.6 RESIDUAL HEAT REMOUAL SYSTEM Design Bases System Design and Operation System Design Evaluation Malfunction Analysis Tests:

Inspections Safety Limits and Conditions 9.3-1 9.3-1 9.3-2 9.3-6 9.3-11 9.3-11 9.3-12 9.4 9.4.1 9.4.2 9.4.3 9.4.4 SPENT FUEL POOL COOLING SYSTEM Design Bases System Design and Operation Design Evaluation Tests and Inspections 9.4-1 9.4-1 9.4-2 9.4-6 9.4-7 9.5 9.5.1 9.5.2 9.5.3 9.5.4 9.5.5 COMPONENT COOLING SYSTEM Design Bases System Design and Operation Components System Evaluation Minimum Operating Conditions 9-i 9.5-1 9.5-1 9.5-1 9.5-4 9.5-7 9'-9 July 1995

CHAPTER 9 TABLE OF CONTENTS (Cont'd)

Section 9.5.6 Title Tests and Inspections

~Pa e

9.5-9 9.6 9.6.1 9.6.2 9.6.3 SAMPLING SYSTEMS Design Basis

System Design

System Evaluation 9.6-1 9.6-1 9.6-2 9.6-7 9.7 9.7.1 9.7.2 9.7.3 9.7.4 REACTOR COMPONENTS AND FUEL HANDLING SYSTEM Design Bases System Design and Operation Design Evaluation Tests and Inspections 9.7-1 9.7-2 9.7-4 9.7-24 9.7-25 9.8 9.8.1 9.8.2 9.8.3 FACILITY SERVICE SYSTEMS Fire Protection System Compressed Air System Service Water Systems 9.8-1 9.8-1 9.8-21 9.8-24 9.9 9.9.1 9.9.2 9.9.3 9.9.4 AUXILIARYBUILDING VENTILATION SYSTEM General Description Design Basis System Descriptions Design Evaluation 9.9-1 9.9-1 9.9-1 9.9-2 9.9-8 9.10 9.10.1 9.10.2 9.10.3 9.10.4 9.10.5 9.10.6 CONTROL ROOM VENTILATION SYSTEM General Description Design Basis System Operation Design Evaluation Incident Control Tests and Inspections 9.10-1 9.10-1 9.10-1 9.10-2 9.10-4 9.10-4 9.10-4 9-ii July 1995

Table CHAPTER 14 LIST OF TABLES Title 14.1-1 14.1-2 14.1-3 14.1-4 14.1.10-1 14.1.10-2 14.1.10-3 14.1.10-4 14.1.13-1 14.2.1-1 14.2.1-2

~

14.2.1-4 14.2.1-5 14.2.3-1 14.2.3-2 14.2.5-1 14.2.6-1 14.2.7-1 14.2.7-2 14.2.7-3 14.2.8-1 Unit 1 Design Power Capability Parameters Used in Non-LOCA Safety Analyses Reactor Trip Points and Time Delays to Trip Assumed in Safety Analyses Summary of Initial Conditions and Computer Codes Used Instrumentation Drift and Calorimetric Errors Power Range Neutron Flux Time Sequence of Events (Manual Rod Control)

Time Sequence of Events (Automatic Rod Control)

Time Sequence of Events (Manual Rod Control)

Time Sequence of Events (Automatic Rod Control)

Potential Turbine - Generator Missiles Fuel Handling Accident Auxiliary Building Inventories and Constants of Significant. Fission Product Radionuclides Data and Assumptions for the Evaluation of the Fuel Handling Accident In The Auxiliary,Building Activities In Highest Rated Discharged Assembly (Curies At Time Of Reactor Shutdown) Fuel Handling Accident in Containment Parameters For Fuel Handling Accident In Containment Dose Calculation Volume Control Tank and Letdown Activities Gas Decay Tank Equilibrium Activity Limiting Steamline Break Statepoint Double Ended Rupture Inside Containment With Offsite Power Available Parameters Used in Analysis of the Rod Cluster Control Assembly Ejection Accident Loss of A.C. Power to the Plant Auxiliaries Steam Release Steam Line Break - Steam Release Steam Generator Tube Rupture

- Steam Release Time Sequence of Events Unit 1 14-v July 1995

CHAPTER 14 LIST OF TABLES Table Title 14.3.1-1 14.3.1-2 14.3.1-3 14.3.1-4 14.3.1-5 14.3.1-6 14.3.2-1 14.3.2-2 14.3.2-3 14.3.2-4 14.3.2-5 14.$.2-6 14.3.2-7 14.3.2-8 14.3.2-9 14.3.2-10 14.3.2-11 14.3.2-12 14.3.2-13 13.3.3-1 14.3.4-1 14.3.4-2 14.3.4-3 14.3 '-4 Large Break LOCA - Results Large Break LOCA - Cases Analysed Large Break Containment Data (Ice Condenser Containment)

Mass and Energy Release Rates Maximum SI Mass and Energy Release Rates Minimum SI Nitrogen Mass and Energy Release Rates Safety. Injection Flow Rate Plant Input Parameters Used in Small Break LOCA Analysis Small<<Break Loss of Coolant Accident Calculation Time Sequence of Events for Condition III Events Small-Break Loss of Coolant Accident Calculation Time Sequence of Events for Condition III Events Small-Break Loss of Coolant Accident Calculation Results HHSI Cross-Tie Valve Closed Time Sequence of Events for Condition III Events Small-Break"Loss of Coolant Accident Calculations Time Sequence of Events for Condition III Events Small-Break Loss of Coolant Accident Calculations Time Sequence of Events for Condition III Events 3X Main Steam Safety Valve Setpoint Tolerance Analysis for 3588 MWT with HHSI Cross-tie Valves Open Small-Break Loss of Coolant Accident Calculations 3X Main Steam Safety Valve Setpoint Tolerance Analysis for 3588 MWT With HHSI Cross-tie Valves Open Selected Input Parameters Donald C. Cook Ice Condenser Analysis Parameters Deck Leakage Sensitivity Cook Nuclear Plant Ice Condenser Design Parameters Structural Heat Sink Table Unit 1 14-vi July 1995

CHAPTER 14 LIST OF TABLES Table Ti.tie 14.3.4-5 14.3.4-6 14.3.4-7 14.3.4-8 14.3.4-9 14 '.4-10 14.3.4-11 14.3.4-12 14.3.4-13 14.3.4-14 14.3.4-15 14.3.4-16 14.3.4-17 14.3.4-18 14.3.4-19 14.3.4-20 14.3.4-21 14.3.4-22 14.3 '-23 14.3.4-24 14.3.4-25 Energy Accounting in Millions of BTU Material Property Data Unit 1/Unit 2 Steamline Break Mass/Energy Releases Inside Containment 102X Power DER (4e6 FT') Break Failure

- MSIV Unit 1/Unit 2 Steamline Break Mass/Energy. Releases Inside"Containment 102X Power Split (0.86 FT') Break Failure

- Auxiliary Feedwater Runout Protection Double-Ended Steam Line Break Parameters Steam Line Ruptures Lower Compartment Temperature Transient Results 0.35 FT'plit 30X Power 0.6 FT'plit 30X Power Key Parameters Affecting Split Steam Line Breaks TMD Input

'MD Flowpath Input Data Calculated Maximum Peak Pressures in Lower Compartment Elements Assuming Unaugmented Flow Calculated Maximum Peak Pressures In The Ice Condenser Compartment Assuming Unaugmented Flow Calculated Maximum Differential Pressures Across the Operating Deck of Lower Crane Wall Assuming Unaugmented Flow Calculated Maximum Differential Pressures Across the Upper Crane Wall Assuming Unaugmented Flow Sensitivity Studies for Cook Nuclear Plant-Peak Differential" Pressure (PSI) Break at Outlet Nozzle Peak Differential Pressure (PSI) Break at Side of Vessel.

Pressurizer Enclosure Nodalization Volumes Pressurizer Enclosure Nodalization Hydraulic Data Unit 1 14-vii July 1995

CHAPTER 14 LIST OF TABLES

~able Title 14.3.4-26 14.3.4-27 14a3.4-28 14.3.4-29 14.3.4-30 14a3.4-31 14.3.4-32 14.3.4-33 14.3.4-34 14.3.4-35 14.3.4-36 14.3.4-37 14.3.4-38 14.3.4-39 14.3.4-40 14.3.4-41 14.3.4-42 14.3.4-43 14.3.4-44 14.3.4-45 14.3.4-46 Differential Pressure Summary

- Break Mass Flow and Energy Flow Comparison of Peak Differential Pressures Fan Room - Backflow Contribution/Forward Flow Contribution Compartment Volume and Area Blowdown Mass and Energy Release Blowdown Mass and Energy Release 3425 MWT/Deps - Min SI/RHR X-Tie Closed Reflood Mass and Energy Releases 3425 MWT/Deps - Max SI/RHR X-Tie Open Reflood Mass and Energy Releases Reflood Transient Parameters Double Ended Pump Suction Reflood Transient Parameters Double Ended Pump Suction 3425 MWT/Deps - Min SI/RHR X-Tie Closed Post Reflood Mass and Energy Releases 3425 MWT/Deps - Max SI/RHR X-Tie Open Post Reflood Mass and Energy 1

Releases Mass and Energy Balances

- Minimum Safeguards 3425 MWT/Deps - Mins SI/RHR X-Tie Closed Mass and Energy Balances

- Maximum Safeguards.

3425 MWT/Deps - Max SI/RHR X-Tie Open Parameters Used in Bounding Steamline Break Mass/Energy Releases for Unit 1 and Unit 2 Steam Line Rupture in Steam Generator Doghouse 1973 Waltz MillPreliminary Test Conditions Peak Pressures/Differentials Effects of Varying Polytropic Exponent Calculated Maximum Peak Pressures Compared With Design Pressure Unit 1 14-viii July 1995

CHAPTER 14 LIST OF TABLES

~able Tibia 14.4.11-1 14.4.11-2 14.4.11-3 14.4.11-4 14.4.11-5 14.4.11-6 14.4.11-7 14.4.11-8 14.4.11-9

~

14A.2-1 14A.2-2 14A.3-1 14A.3-2 14A.4-1 14A.4-2 14A.4-3 14A.4-4 14A.5-1 14A.5-2 Unit 1 Revised Tritium Production in the Reactor Coolant 14-xiii July 1995 10 CFR 50.49 Environmental Qualification Equipment List Peak Environmental Qualification Conditions For LOCA, MSLB, and Feedwater Line Break Inside Containment Airborne Source Term Doses Integrated Doses Submerged Lower Volume - Observer at Center Beta Dose Factors Dose from Airborne Source After Attenuation (Thickness Unit Density)

Beta Dose Factors Dose From Airborne Source After Attenuation (Thickness of Aluminum)

Beta Dose Factors Dose From Airborne Source After Attenuation (Thickness of Steel)

Pipes considered In Calculating Outside Containment Doses Peak Environment Qualification conditions for HELB Outside Containment Core and Gap Activities Core Temperature Distribution Nuclear Characteristics of Highest Rated Discharged Assembly Activities in Highest Rated Discharged Assembly Curies at Time of Reactor Shutdown Parameters Used in the Calculation of Reactor Coolant Fission Product Activities Reactor Coolant Equilibrium Fission and Corrosion Product Activities Parameters Used in the Calculation of Reactor Coolant Fission and Corrosion Product Activities for Steam Generator Tube Rupture Radiological Analysis I

Reactor Coolant Equilibrium Fission and Corrosion Product Activities for Steam Generator Tube Rupture Radiological Analysis Tritium Production in the Reactor Coolant

CHAPTER 14 LIST OF TABLES Table Title 14A.7-1 14A.8-1 14A.8-2 Gas Decay Equilibrium Activity Concentration of Iodine Isotopes in the Recirculation Loop Radiation Sources Circulating in Residual Heat Removal Loop and Associated Equipment-Mev/cc-sec Unit 1 14-xiv

~

July 1995

TABLE OF CONTENTS

~Sects.o

~Pa e

14. 0 SAFETY ANALYSIS 14.0.1

SUMMARY

OF RESULTS 14.0-1 14.0-3 14.1 CORE AND COOLANT BOUNDARY PROTECTION ANALYSIS..........

14.1-1 14.1.0 PLANT CHARACTERISTICS AND INITIALCONDITIONS USED IN SAFETY ANALYSIS

~

0 '

~

14.1.0.1 PLANT CONDITIONS 14.1.0.2 INITIALCONDITIONS 14.1.0.3 POWER DISTRIBUTION 14.1.0.4 REACTIVITY COEFFICIENTS ASSUMED IN THE SAFETY ANALYSIS.

14.1-2 14.1-2 14.1-3 14.1-3 14.1-4 14.1.0.5 ROD CLUSTER CONTROL ASSEMBLY (RCCA) INSERTION CHARACTERISTICS 14.1-5 14.1.0.6 REACTOR PROTECTION SYSTEM (RPS)

SETPOINTS AND

~

TIME DELAYS 14.1-6 14.1.0.7 PLANT SYSTEMS AND COMPONENTS AVAILABLEFOR MITIGATION OF ACCIDENT EFFECTS 14.1-9 14.1.0.8 RESIDUAL DECAY HEAT 14.1-10 14.1,0.9 COMPUTER CODES UTILIZED 14.1.0.10 REFERENCES 14.1-11 14.1.14 14.1.1 UNCONTROLLED ROD CLUSTER CONTROL ASSEMBLY (RCCA)

BANK WITHDRAWAL FROM A SUBCRITICAL CONDITION 14.1.1.2 ANALYSIS OF EFFECTS AND CONSEQUENCES 14.1.

1.3 CONCLUSION

S 14.1.

1.4 REFERENCES

14.1.1.1 IDENTIFICATION OF CAUSES AND ACCIDENT DESCRIPTION 14.1.1-1 14.1.1-1 14.1.1-3 14.1.1-6 14.1.1-7 Unit 2 14-i July 1995

TABLE OF CONTENTS (Continued)

~Sect on 14.1.2A UNCONTROLLED ROD CLUSTER CONTROL ASSEMBLY (RCCA)

BANK WITHDRAWALAT POWER (MIXED CORE).. DELETED.......

~Pa e

14 '.2A-l 14.1.2B UNCONTROLLED ROD CLUSTER CONTROL ASSEMBLY (RCCA)

BANK WITHDRAWALAT POWER (FULL VANTAGE 5 CORE) 14.1.2B.1 IDENTIFICATION OF CAUSES AND ACCIDENT DESCRIPTION 14.1.2B.2 ANALYSIS OF EFFECTS AND CONSEQUENCES 14.1.2B.3 CONCLUSIONS 14.1.2B.4 REFERENCES 14.1.3 ROD CLUSTER CONTROL ASSEMBLY (RCCA) MISALIGNMENT (INCLUDING RCCA DROP) 14.1.3.2 ANALYSIS OF EFFECT AND CONSEQUENCES 14.1.

3.3 CONCLUSION

S 14.1.3.4 14.1.4 14.

1.5 REFERENCES

ROD CLUSTER CONTROL ASSEMBLY DROP UNCONTROLLED BORON DILUTION 14.1.3.1 IDENTIFICATION OF CAUSES AND ACCIDENT DESCRIPTION.....

14.1.2B-1 14.1.2B-1 14.1.2B-2 14.1.2B-5 14.1.2B-6 14.1.3-1 14.1.3-1 14e1.3-3 14.1.3-6 14.1.3-8 14.1.4-1 14.1.5-1 14.1.5.1 IDENTIFICATION OF CAUSES AND ACCIDENT DESCRIPTION 14.1.5-1 14.1.5.2 ANALYSIS OF EFFECTS AND CONSEQUENCES 14.1

~

5.3 CONCLUSION

S 14.1.5-2 14.1.5-6 14.1.6 14.1.6.1 LOSS OF REACTOR COOLANT FLOW 14.1.6.2 LOCKED ROTOR ACCIDENT 14.1.

6.3 REFERENCES

LOSS OF FORCED REACTOR COOLANT FLOW (INCLUDING LOCKED ROTOR) 14.1.6-1 14.1.6-1 14.1.6-5 14.1.6-11 Unit 2 14-ii July 1995

LIST OF TABLES Table Title 14.0-1 Occurrence Evaluated for Vantage 5 Fuel Transition 14.1.0-1 Range of Plant Nominal Conditions Used in Safety Analyses 14.1.0-2 Summary of Initial Conditions and Computer Codes Used 14.1.0-3 Summary of Initial Conditions and Computer Codes Used; Separate Full Vantage 5 Core Analyses 14.1.0-4 RPS Trip Points and Time Delays to Trip Assumed in Non-LOCA Safety Analyses 14.1.0-5 ESF Actuation Setpoints and Time Delays to Actuation Assumed in Non-LOCA Safety Analyses 14.1.0-6 Plant Systems and Equipment Available for Fault Conditions 14el.l-l Time Sequence of Events 14.1.2A-1 DELETED 14.1.2B-1 Time Sequence 14.1.5-1 Time Sequence of Events (Full Vantage 5 Core) of Events 14.1.6-1 14.1.6-2 14.1.7-1 Time Sequence of Events Time Sequence of Events Time Sequence of Events

. 14.l. 8A-1 DELETED 14.1.8B-1 Time Sequence of Events (Full Vantage 5 Core) 14.1.9-1 Time Sequence of Events 14.1.10A-1 DELETED 14.1.10A-2 DELETED 14.1.10A-3 DELETED 14.1.10A-4 DELETED Unit 2 14-vii July 1995

Table Title 14.1.10B-1 14.1.108-2 Time Sequence of Events (Full V-5 Core)

Time Sequence of Events (Full V-5 Core) 14.1.10B-3 Time Sequence of Events (Full V-5 Core) 14.1.10B-4 Time Sequence of Events (Full V05 Core) 14.1.11A-1 DELETED 14.1.11B-1 Time Sequence of Events (Full Vantage 5 Core) 14.1.12-1 Time Sequence of Events 14.2.2-1 14.2.2-2 14.2.2-3 14.2,4-1 Parameters for Liquid Radioactive Tank Failure Analysis Ground Water Activities Due to Liquid Radioactive Tank Failure Reactor Coolant Equilibrium Fission and Corrosion Product Activities Parameters Recommended for Determining Radioactivity Releases for Steam Generator Tube Rupture 14.2.5-1 Limiting Steamline Break Statepoint Double Ended Rupture Inside Containment with Offsite Power Available 14.2.5-2 14.2.6-1 Time Sequence of Events Parameters Used in the Analysis of the Rod Cluster Control Assembly E]ection Accident 14.2.8-1 14.3.1-1 14.3.1-2 14.3.1-3 14.3.1-4 14.3.1-5 14.3.1-6 14.3.1-7 Unit 2 Time Sequence of Events Large Break LOCA - Cases Analyzed Unit 2 Input Parameters Used in the Large Break LOCA ECCS Analysis Large Break LOCA ECCS Analysis Systems Modelling Large Break LOCA Containment Data (Ice Condenser Containment)

Large Break LOCA Analysis Time Sequence of Events Large Break LOCA Results Fuel Cladding Data Case A - Large Break LOCA C~ 0.6 Minimum Safeguards Mass and Energy Release Rates 14-viii July 1995

LIST OF TABLES Continued Table Title 14.3,1-8 Case F

- Large Break LOCA C

0.6 Maximum Safeguards Mass and Energy Release Rates 14.3.1-9 Case G

- Large Break LOCA C;0.6 Cross Tie Closed 3413 MWt Mass and Energy Release Rates 14.3.1-10 Nitrogen Mass Release Rates 14.3.2-1 14.3.2-2 14.3.2-3 14.3,2-4 14.3.2-5 14.3.2-6 14.3.2-7 Plant Input Parameters Used in Small Break LOCA Analysis Time Sequence of Events for Condition III Events Time Sequence of Events for Condition III Events Small Break Loss of Coolant Accident Calculation Small Break Loss of Coolant Accident Calculation Safety Injection Flow Rate with HHSI Cross Tie Valves Open Time Sequence of Events for Condition III Events 14.3.2-8 14.3.2-9 Small Break Loss of Coolant Accident Calculation Safety Injection Flow Rate With HHSI Cross Tie Valves Closed 14.3.2-10 Time Sequence of Events for Condition III Events 14.3.2-11 Small-Break Loss of Coolant Accident Calculations (3" Break) 14.3.2-12 Time Sequence of Events for Condition III Events (4" Break) 14.3.2-13 Small-Break Loss of Coolant Accident Calculations (4" Break) 14.3.5-1 14.3.5-2 Fuel Parameters and Core Gap Activities Activity in the Highest Rated Discharged Assembly for the Rerated Power of 3588 MWT 100 Hours Following Reactor Shutdown 14.3.5-3 Parameters Used in the Calculation of Reactor Coolant Fission and Corrosion Product Activities 14.3.5-4 Reactor Coolant Equilibrium Fission and Corrosion Product Activities 14.3.5-5 Parameters Used to Evaluate the Offsite Doses Due to a Large Break LOCA at 3588 MWT 14.3.5-6 Estimated Doses for 3588 MWT Power Operation Unit 2 14-ix July 1995

CHAPTER 14 LIST OF FIGURES

~Fk re 14.1.0-1

~Ttla Doppler Power Coefficient Used in Safety Analyses 14.1.0-2 RCCA Position Versus Time After Rod Drop Begins 14.1.0-3 14.1.0-4 14.1.0-5 14.1.0<<6 14.1.0-7 Normalized RCCA Reactivity Worth Versus RCCA Position Normalized RCCA Reactivity Worth Versus Time After RCCA Drop Begins Overtemperature and Overpower hT Protection Overtemperature and Overpower 4T Protection 1979 ANS Residual Decay Heat Used in Accident Analyses 14.1.1-1 Rod Withdrawal From Subcritical Nuclear Power and Heat Flux Versus Time 14.1.1-2 Rod Withdrawal From Subcritical Fuel Average and Clad Temperature Versus Time 14.1.2B-1 Rod Withdrawal at Power Nuclear Power Versus Time for Full Power, 80 PCM/Sec Insertion Rate, Maximum Reactivity Feedback 14.1.2B-2 14.1.2B-3 Rod Withdrawal at Power Pressurizer Pressure and Water Volume Versus Time for Full

Power, 80 PCM/Sec Insertion Rate, Maximum Reactivity Feedback Rod Withdrawal at Power Core Average Temperature and DNBR Versus Time for Full Power, 80 PCM/Sec Insertion Rate, Maximum Reactivity Feedback 14.1.2B-4 Rod Withdrawal at Power Nuclear Power Versus Time for Full Power, 4 PCM/Sec Insertion

Rate, Maximum Reactivity Feedback 14.1.2B-5 Rod Withdrawal at Power Pressurizer Pressure and Water Volume Versus Time for Full

Power, 4 PCM/Sec Insertion Rate, Maximum Reactivity Feedback Unit 2 14-x July 1995

CHAPTER 14 LIST OF FIGURES (Cont'd)

~Fi re Tit e 14.1.2B-6 Rod Withdrawal at Power Core Average Temperature and DNBR Versus Time for Full Power, 4 PCM/Sec Insertion Rate, Maximum Reactivity Feedback 14.1.2B-7 Rod Withdrawal at Power 100X Power, Minimum DNBR Versus Reactivity Insertion Rate 14.1.2B-8 Rod Withdrawal at Power 60X Power, Minimum DNBR Versus Reactivity Insertion Rate 14.1.2B-9 Rod Withdrawal at Power 10X Power, Minimum DNBR Versus Reactivity Insertion Rate 14.1.3-1 Dropped RCCA(s)

Nuclear power and Core Heat Flux Versus Time for a Typical

Response

in Automatic Control 14.1.3-2 Dropped RCCA(s)

Average Coolant Temperature and Pressurizer Pressure Versus Time for a Typical Response in Automatic Control Complete Loss of Flow Core Flow Coastdown Versus Time 14.1.6-2 Complete Loss of Flow Nuclear Power and Pressurizer Pressure Versus Time 14.1.6-3 Complete Loss of Flow Average Channel and Hot Channel Heat Flux Versus Time 14.1.6-4 Complete Loss of Flow DNBR Versus Time 14.1.6-5 Partial Loss of Flow 1/4 Faulted Loop and Core Flows Versus Time 14.1.6-6 Partial Loss of Flow 1/4 Nuclear Power and Pressurizer Pressure Versus Time 14.1.6-7 Partial Loss of Flow 1/4 Average Channel and Hot Channel Heat Flux Versus Time 14.1.6-8 Partial Loss of Flow 1/4 DNBR Versus Time Unit 2 14-xi July 1995

CHAPTER 14 LIST OF FIGURES (Cont'd)

~Ff.

re Title 14.1.6-9 1/4 Locked Rotor Core and Faulted Loop Flows Versus Time 14.1.6-10 1/4 Locked Rotor Reactor Pressure and Nuclear Power Versus Time 14.1.6-11 1/4 Locked Rotor A~erage Channel and Hot Channel Heat Flux Versus Time 14.1,6-12 1/4 Locked Rotor Clad Inner Temperature Versus Time 14.1.7-1 14.1.8B-1 Startup of an Inactive Reactor Coolant Loop Loss of Load Nuclear Power and Pressurizer Pressure Versus Time for Minimum Reactivity Feedback with Pressurizer Spray and PORVs 14.1.8B-2 Loss of Load Pressurizer Water Volume and DNBR Versus Time for Minimum Reactivity Feedback with Pressurizer Spray and PORVs 14.1.8B-3 Loss of Load Loop and Core Average Temperatures Versus Time for Minimum Reactivity Feedback with Pressurizer Spray and PORVs 14.1.8B-4 Loss of Load Nuclear Power and Pressurizer Pressure Versus Time for Maximum Reactivity Feedback with Pressurizer Spray and PORUs 14.1.8B-5 Loss of Load Pressurizer Water Volume and DNBR Versus Time for Maximum Reactivity Feedback with Pressurizer Spray and PORVs 14.1.8B-6 Loss of Load Loop and Core Average Temperatures Versus Time for Maximum Reactivity Feedback with Pressurizer Spray and PORVs 14.1.8B-7 Loss of Load Nuclear Power and Pressurizer Pressure Versus Time for Minimum Reactivity Feedback without Pressurizer Spray and PORVs 14.1.8B-8 Loss of Load Pressurizer Water Volume and DNBR Versus Time for Maximum Reactivity Feedback without Pressurizer Spray and PORVs Unit 2 14-xii July 1995

PLANT SITE

SUMMARY

1.1.1 SITE DESCRIPTION The approximately 650 acre site is located along the eastern shore of Lake Michigan in Lake Township, Berrien County, Michigan about 11 miles south-southwest of Benton Harbor.

The population density. of the area surrounding the site is relatively low.

The minimum distance from the reactor containment structures to the exclusion area is about 2000 feet, with the nearest continuously occupied resident located about 2850 feet south of the reactors.

The population center distance is about eight miles.

The area is primarily devoted to agricultural pursuits with some manufacturing in the Benton Harbor-St.

Joseph and Niles areas.

1.1.2 METEOROLOGY In order to obtain meteorological data for the determination of diffusion and dispersion at the site, a meteorological recording station was established on the site during the fall of 1966.

The analysis of three years data from the station is included in this report.

The site is extremely well ventilated with an extremely high percentage of strong winds and a very low occurrence of thermal inversions.

There is no strong preference for any particular wind direction.

1.1.3 GEOLOGY AND HYDROLOGY An investigation of site geology and hydrology was canpleted in 1966.

The geology of the region is regular with no faults within about 50 miles of the site.

The subsurface soils are adecyxate to support the structures and drainage of surface and ground waters is toward the t.

lake over almost the entire site area.

1 % 1 1 July g 19 82

1. 1.4 SEISMOLOGY The area is relatively inactive seismically with no major earthquake epicenters located within about 400 miles of the site.

There has been some minor activity closer to the site but no shocks within 50 miles have been large enough to cause significant structural damage.

For design purposes, a horizontal ground acceleration of 0.10g is used.

All equipment and structures necessary for plant safety have been designed to withstand the effects of a horizontal ground acceleration of 0.20g.

1.

The Seismic Instrumentation System consists of a control panel with three cassette mounted tape recorders, a magnetic tape playback

system, one horizontal and one vertical seismic trigger, three triaxial acceleraneters and associated electronic equipment.

The control panel is located in the main control room and features an event indicator which illuminates when the system becanes operative.

The magnetic tape playback system is also in the control roan.

This transfers the frequency, amplitude, and phase relationship as recorded on the tapes to a chart to facilitate quick engineering analysis as to the effect of the earthquake.

The seismic triggers are located in the chlorination building which is 500 feet south of Unit 1 and serve to initiate the operation of the system.

The acceleraneters are oriented such that both axes are pointed in the same direction and aligned along one axis.

The locations of which are as follows:

a) b)

c)

The chlorination building The top of the primary shield wall The bottom of the reactor pit 2.

The chlorination building was chosen as a site free from influences of the other structures such that in the event of seismic excitation the acceleraneter will effectively measure actual ground accel-eration.

1 ~ 1 2

July, 1982

The fuel handling system also provides capability for receivingg handling and storage of new,fuel.

Both the new'fuel storage facility and the spent fuel storage facility are shared by the two units..

1.3.6 TURBINE AND AUXILIARIES Each turbine is a tandem-canpound, four element, 1,800 rpm unit/

having one high pressure and three identical low pressure elements.

Combination moisture separator-reheaters are employed to dry and superheat the steam between the high and low pressure turbines.

The auxiliaries include deaerating surface condensers, steam jet air e)ectors, turbine driven main feed pumps, motor driven condensate

pumps, and six stages of feedwater heating.

1.3.7 ELECTRICAL SYSTEM The main generators are 1800 rpm, 3 phase, 60 cycle, hydrogen and water cooled units.

The main transformers deliver generator power to the 345 kV and 765 kV switchyards.

The station auxiliary power system consists of auxiliary transformers, 4160 v and 600 v switchgear, 600 v motor control centers, 120 v a-c vital instrument buses and 250 v d-c buses.

Two diesel generators are provided for each unit as on-site sources of power in the event of a,canplete loss of normal and reserve a-c power.

In addition, two storage batteries are provided for each unit as on-site sources of power in the event of a complete loss of normal d-c power.

Each diesel generator and battery has sufficient capacity to operate the equipment necessary for one unit to prevent undue risk to public health and safety should a loss-of-coolant accident occur.

1. 3-5

July, 1982

1.3.8 SAFETY FEATURES The engineered safety features provided for this plant have sufficient redundancy of components and power sources such that under the con-ditions of a loss-of-coolant accident they can maintain the integrity of the containment and keep the exposure of the public below the limits of 10 CFR 100, even when operating with partial effectiveness.

The safety features incorporated in the design of this plant and the functions they serve are summarized below.

a)

The Emergency Core Cooling System (ECCS) injects borated water into the Reactor Coolant System.

The ECCS limits damage to the core and limits the energy and fission products released into the containment following a loss-of-coolant accident.

b)

A steel-lined, domed, reinforced concrete containment vessel is anchored to a reinforced concrete foundation slab.

The contain-ment is'designed to remain virtually leaktight during the pressure transient following a loss-of-coolant accident.

c)

An Ice Condenser System reduces containment pressure and removes iodine radioactivity following a loss-of-coolant accident.

d)

A Containment Spray System is used to reduce containment pressure and to remove iodine from the containment atmosphere following a loss-of-coolant accident.

e)

The Containment Isolation System incorporates valves and controls on piping systems penetrating the containment structure.

The valves are arranged to provide two barriers between the Reactor Coolant System or containment atmosphere and the environment.

System design is such that failure of one valve to close will not prevent isolation, and no manual operation is required for immediate isolation.

Automatic Phase "A" isolation is initiated

l. 3-6

July, 1982

ML17334B597

Contents

Text

SUBJECT:

SUMMARY

SUMMARY

SUMMARY

System Design

SUMMARY

1.3 CONCLUSION

1.4 REFERENCES

3.3 CONCLUSION

1.5 REFERENCES

5.3 CONCLUSION

6.3 REFERENCES

Response

SUMMARY

Navigation menu

ML17334B597

Text

SUBJECT:

SUMMARY

SUMMARY

SUMMARY

System Design

SUMMARY

1.3 CONCLUSION

1.4 REFERENCES

3.3 CONCLUSION

1.5 REFERENCES

5.3 CONCLUSION

6.3 REFERENCES

Response

SUMMARY

Navigation menu

Search