ML17334B597

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)

Text

~~ 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 TITLE: OR Submittal: Updated COPZES RECEZVED:LTR ~ ENCL FSAR (50. 71) and Amendments JO SZSE: Z +F9(D NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME, LTTR ENCL PD3-1 PD 1 0 HICK J 1 1 0 INTERNAL: AEOD/DOA/IRB 1 1 ILE CENTER 0. 2 2 RGN3 1 1 EXTERNAL: IHS 1 1 NOAC 1 1 NRC PDR 1 1 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/4Fitzpatrick E. ED Uice President

/jen Attachment 9607290048 960722 PDR ADOCK 05000315 K PDR

~

U. S. Nuclear Regulatory Commission AEP:NRC:0509S Page 2 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 Pacae Date

1. 0-1 1988 1 0-2

~ 1994 1.0-3 1989

1. 1-1 1982

1. 1-2 1982

1. 1-3 1982 1 1-4

~ 1982 Fig. 1-1 ORIG 1.2-1 1993 1.2-2" 1993 1.2-3 1993 1.2-4 1991 1.2-5 1995 Table l.

1.3-1 2-1 (6 pages) 1989 1982 1.3-2 1982 1.3-3 1982 1.3-4 1984 1 3-5

~ 1982 1.3-6 1982 1.3-7 1982 1.3-8 1994 1.3-9 1982 Fig. 113-1 1995 Fig. 1 03-2 1990 Fig. 1 '-3 1.3-4 1990 Fig. 1990 Fig. 1.3-5 1990 Fig. 1.3-6 1990 Fig. 103-7 1990 Fig. 1.3-8 1993 Fig. 1.3-9 1993 Fig. 1.3-10 1993 Fig. 1.3-11 1982 1.4-1 1991 1.4-2 1991 1.4-3 1987 1.4<<4 1987 1.4-5 ~

1991 1.4-6 1982 1.4-7 1991 1.4-8 1991 1.4-9 1982 1.4-10 1987 1.4-11 1991

0 Page VOLUME I Chapter 1 Introduction and Summa Pacae Date

1. 4-12 1991

1. 4-13 1994

1. 4-14 1994 1.4-15 1991 1.4-16 1993

1. 4-17 1987 1.4-18 1987 1.4-19 1994 1.4-20 1992

l. 4-21" 1.4-22 1991 1991 Tabl 1.4-1 (pg 1) 1991 (pg>> 1991 (pg>> 1991 (pg 4) 1991 1.5-1 1982 1 ~ 6-0 .1984

1. 6-1 1983 1.6-2 1983 1.6-3 1982

l. 6-4 6-5 1982

1. 1983 1.6-6 1982 1 ~ 6-7 1983 1.6-8 1982 1.6-9 1982

1. 6-10 1983

1. 6-11 1982

1. 6-12 1983

1. 6-13 1982

l. 6-14 1.6-15 1985 1985

l. 6-16

1. 6-17 1985 1985 1.6-18 1985 1.6-19 1992 1.6 "20 1985 1.6-21 1985

1. 6-22 1985

1. 6-23 1985

1. 6-24 1985

l. 6-25 Table 1.6-1 (pg 1) 1992 1989 (pg 2) 1989 (pg 3) 1989 (pg 4) 1989 (pg 5) 1989 (pg 6) 1989 (pg 7) 1989 (pg 8) 1989 (pg 9) 1989 (pg 10) 1989

Page 3 VOLUME I Chapter 1 Introduction and Summa Pacae Date Table 1.6-1 (pg 11) 1989 (pg 12) 1989 (pg 13) 1989 (pg 14) 1989 (pg 15) 1989 (pg 16) 1990 (pg 17) 1989 (pg 18) 1989 (pg-19)" 1989 (pg 20) 1989 (pg 21) 1989 (pg 22) 1991 (pg 23) 1993 1.7-1 1994

1. 8-1 1989

1. 9-1 1982

Page 4 VOLUME I Chapter 2 Site and Environment Pacae Date 2

201-2

'-1 1991 1993 2.1-3 1993

2. 1-4 1982 2.1-5 1993

2. 1-6 1993 2~1 7 1995

2. 1-8 1995

2. 1-9 1995 2'.1=10" 1995'995 2 1-11

~

2.1-12 1995 2 0 1-13 1995 Table 201-1 1995 Table 2. 1-2 1995 Table 2 1 3~ 1995 Table 2. 1-4 DELETED 1995 Table 2. 1-5 1995 Table 2. 1-6 1995 Table 2. 1-6a 1995 Table 201-7 1995 Table 2. 1-7a 1995 Table 2.1-8 1995 Table 2.1-8a 1995

-Table 2. 1-8b 1995 Table 2. 1-9 1995 Table 2.1-10 1995 Table 2. 1-11 1995 Table 2. 1-12 1995 Fig. 201-1 1982 Fig. 2. 1" 2 1982 Fig. 201-3 1993 Fig. 2. 1-4 1982 Fig. 2. 1-4a 1982 Fig. 2.1-4b 1993 Fig. 2.1-5 1995 Fig. 2.1-6 1995 Fig. 2. 1-6a 1995 Fig. 2.1-6b 1995 Fig. 211-7 1995 Fig. 2.1-7a 1995 Fig. 2. 1-7b 1995 Fig. 2.1"8 1995 Fig. 2. 1-8a 1995 Fig. 2.1-8b 1995 Fig. 2 ~ 1-9 1993 Fig. 2. 1-10 1993 2.2-1 1994 2 ~2 2 1993 202-3 1995 2.2-4 1995 2.2-5 1995 2.2-6 1995 2 '-7 1993

Page 5 VOLUME I Chapter 2 Site and Environment Pacae Date 2 '-8 2.2-9 1995 1994 2.2-10 1993 Table 2.2-1 1993 Table 2.2-2 1993 Table 2.2-3 1993 Table 2.2-4 1993 Table 2.2-5 1993 Table 2.2-6 1993 Table 2.2-7 1993 Tabl'b" 2.2'=8 '1993 Table 2.2-9 1993 Fig. 2. 2-1 1982 Fig. 2.2-2 1993 Fig. 2.2-3 1993 Fig. 2.2-4 1993 Fig. 2.2-5 1993 Fig. 2.2-6 1993 Fig. 2.2-7 1993 Fige 2.2-8 1993 Fig. 2.2-9 1993 Fige 2.2-10 1993 Fig. 2.2-11 1993 Fig. 2. 2-12 1993 Fige 2.2-13 1982 Fig. 2.2-14 1982 Fig. 2.2-15 1982 Fig. 2.2-16 1982 Fig. 2. 2-17 1982 Fig. 2.2-18 1982 Fige 2.2-19 1982 Fig. 2.2-20 1982 Fige 2.2-21 1982 Fig. 2.2-22 1982 Fige 2.2-23 1992 2 '-1

'-2 1982 2 1995 2~3 3 1982 2.3-4 1982 2.3"5 1982 Fig, 2.3-1 1982 Fige 203-2 1982 2.4-1 1982 2.4-2 1984 2.4-3 1984 2.4-4 1982 2.4-5 1988 2.4-6 1982

2. 5-1 1982 2.5-2 1982 2.5-3 1982 2.5-4 1982 2.5-5 1982 2.5-6 1982 2.5-7 1982

Page 6 VOLUME I Chapter 2 Site and Environment Pacae Date Table 2 . 5-1 (2pp) 1989 Fig. 2.5-1 1982 Fig. 2.5-1a 1982 Fig. 2.5-2 1982 Fig. 2.5-3 1982 Fig. 2.5-3a 1982 Fig. 2.5-3b 1982 Fig. 2.5-3c 1982 Fig:" 2"; 5= 3d"" '1982 Fig. 2.5-3e '982 Fig. 2.5-3f 1982 Fig. 2 '-3g 1982 Fige 2.5-3h 1982 Fig. 2.5-3i 1982 Fig. 2.5-3j 1982

2. 6-1 1993 2.6-2 1992 2.6-3 1992 2.6-4 1992 2.6-5 1992 2.6-6 1993 2.6-7 1992 2.6-8 1992 2.6-9 1992

2. 6-10 1992

2. 6-11 1993

2. 6-12 1993

2. 6-13 1993 2.6-14 1992 2.6-15 1992 2.6-16 1992

2. 6" 17 1993 2.6-18 1993 2.6-19 1993 2.6-20 1993 2.6-21 1993 2.6-22 1993 2.6-23 1992 2.6-24 1992 2.6-25 1992 2.6-26 1993 2.6-27 1992 2.6-28 1992 2.6-29 1992 2.6-30 1993 2.6-31 1993 2.6-32 1992 2.6-33 1993 2.6-34 1993 2.6-35 1992 2.6-36 1992 2.6-37 1992 2.6-38 1992 2.6-39 1992

0 Page 7

.VOLUME I Chapter 2 Site and Environment Pacae Date 2.6-40 1992 2.6-41 1992 2.6-42 1992 2.6-43 1993 2.6-44 1993 2.6-44a 1993 Table 2.6-1 1992 Table 2.6-2 1992 Table 2.6-3 1992 Table 2.6-4 1992 Table- 2;6-5-- 1992" Table 2.6-6 1992 Fige 2 '-1 2.6-2 1992 Fig. 1992 Fige 2.6-3 1992 Fig. 2.6-4 1992 Fig. 2 .6-5 1992 Fig. 2 .6-6 1992 Fig. 2 .6-7 1992 Fig. 2 .6-8 1992 Fig. 2 .6-9 1992 Fig. 2 .6-10 1992 Fig. 2 . 6-11 1992 Fig. 2 . 6-12 1992 2~7 1 1995 2~7 2 1995 2.7-3 1995 2.7-4 1995 2.7-5 1995 2 '-6

'-7 1995 2 1995 2.7-8 1995 Table 2. 7-1 DELETED 1995 Table 2.7-2 DELETED 1995 Table 2.7-3 DELETED 1995 Table 2.7-4 DELETED 1995 Table 2. 7-5 (pg 1)DELETED 1995 (pg 2)DELETED 1995 (pg 3)DELETED 1995 (pg 4)DELETED 1995 Fig. 217-1 DELETED 1995 Fige 2 ~ 7 2 DELETED 1995

Page 8 VOLUME I Chapter 2 Site and Environment Parcae Date 2.8-1 1989 2.8-2 1982

2. 9-1 1982 2.9-2 1982 2.9-3 1982 2.9-4 1992 2.9-5 1990 2.9-6 1983 2.9-7 1991

~ 2.9-8" 1994.

'.9-9 1995

2. 9-10 1994

2. 9-11 1994

2. 9-12 1994 2.9-13 1994 2.9-14 1994 2.9-15 1994 2.9-16 1994

2. 9-17 1995

2. 9-18 1995 Table 2.9-1 (3pp) 1994 Table 2.9-2 (5pp) 1994

2. 10-1 1994

2. 10-2 1994

Page 9 VOLUME II Chapter 3 Reactor Unit 1 Pacae Date

3. 1-1 1994 3.1-2 1992 3~1 3 1994

3. 1-4 1994

3. 1-5 1994

3. 1-6 1994

3. 1-7 1994 3.1-8 1994

3. 1-9 1994

3. 1-10 ~ i 1994-

3. 1-11 1990 3 1-12 0 1994 3 1-13 0 1994

3. 1-14 1994

3. 1-15 1994 3.2" 1 1993 312-2 1982 302-3 1994 3.2-4 1982 3.2-5 1986 3.2-6 1982 3.2"7 1982 3.2-8 1982 3.2-9 1982 3.2-10 1982 3.2-11 1994 3.2-12 1982 3.2-13 1984 3.2-14 1982 3.2-15 1982 3.2-16 1982 3.2-17 1982 3.2-18 1983

3. 2-19 1982 3.2-20 1982 3.2-21 1982 3 '-22 1982 3.2-23 1982 3.2-24 1982 3.2-25 1982 3.2-26 1982 3.2-27 1982 3.2-28 1982 3.2-29 1982 3.2-30 1982 3 ~ 2-31 1995

Page 10 VOLUME II Chapter 3 Reactor Unit 1 Pacae Date 312-32 1982 3 ~ 2 33 1982 3.2-34 1983 3.2-35 1982 3.2-36 1982 3.2-37 1982 3.2-38 1982 3.2-39 1982 3.2-40 1982

3. 2=.43 1982.-

3.2-42 1982 3.2-43 1982 3.2-44 1983 3.2-45 1982 3.2-46 1987 3.2-47 1987 3.2-48 1994 3.2-49 1995 3.2-50 1995 3.2-51 1995 3.2-52 1995 3.2-53 1995 3.2-54 1995 Table 3.2.1-1 (3pp) 1995 Fig. 3.2.1-1 1982 Fig. 3.2. 1-2 1982 Fig. 3.2. 1-3 1982 Fig. 3.2. 1-4 1982 Fig. 3.2.1-5 1982 Fig. 3.2.1-6 1982 Fig. 3.2. 1-7 1982 Fig. 3.2 1-8

~ 1982 Fig. 3.2.1-9 1982 Fig. 3.2.1-10 1982 Fig. 3.2.1-11 1982 Fig. 3.2. 1-12 1982 Fig. 3.2 '-13 1982 Fig. 3.2. 1-14 1982 3.3-1 1990 3 '-2 1992 3.3-3 1992 3.3-4 1982 3.3-5 1992 3.3-6 1992 3.3-7 1983 3.3-8 1983 3.3-9 1984 3.3-10 1990 3.3-11 1987

Page 11 VOLUME II Chapter 3 Reactor Unit 1 Pacae Date 3.3-12 1995 3.3-13 1982

3. 3-14 1992 3.3-15 1992 3.3-16 1992 3.3-17 1992 3.3-18 1992 3.3-19 1992 3.3-20 1992 3>>3.-21-- 1992 303-22 1992 303-23 1992 3.3-24 1992 3.3-25 1993 3.3-26 1989 303-27 1990 Table 3.3.1-1 (pg 1) 1995 (pg 2) 1990 Table 3.3.1-2 (pg>> 1994 1990 Table 3.3. 1-3 1995 Table 3.3.1-3a DELETED 1995 Fig. 3.3.1-1 1982 Fige 3~3~1 2 1984 Fig. 3 ~ 3 ~ 1-3 1984 Fig. 3.3.1-4 1984 Fig. 3.3. 1-11 1984 Fig. 3.3. 1-12 1984 Fig. 3 3 1-13

~ 0 1984 Fige 3.3. 1-14 1984 Fig. 3 '.1-15 1984 Fig. 3.3. 1-16 1984 Fige 3.3. 1-17 1992 3.4-1 1990 3.4-2 1993 3.4.3 1993 3.4.4 1982 3.4.5 1982 3.4-6 1982 3.4-7 1993

Page 12 VOLUME II Chapter 3 Reactor Unit 1 Pacae Date 3.4-8 1993 3.4-9 1993 3.4-10 1982 3.4-11 1993 3.4-12 1987 3.4-13 1993 3.4-14 1993 3.4 "15 1983 3.4-16 1982 3.. 4= 17 1982 ....

3.4-18 1982 3.4-19 1982 3.4-20 1982 3.4-21 1982 Table 3.4. 1-1 (2pp) 1989 Table 3.4.1"2 1989 Table 3 4.1-3

~ 1989 Fig. 3.4. 1-1 1982 Fig. 3.4.1-2 1982 Fig. 3.4. 1-3 1982 Fig. 3.4.1-4 1982 Fig. 3.4.1-4a 1982 Fig. 3.4. 1-5 1982 Fig. 3.4. 1-6 1982 Fig. 3.4.1-7 1982 Fig. 3.4.1-8 1982 Fig. 3.4.1-9 1982 3.5-1 1993 3.5.1-1 1995 3.5.1-2 1995 3.5.1-3 1995 3.5.1-4 1993 3.5. 1-5 1993 3 5. 1-6

~ 1993 3.5.1-7 1993 3.5.1-8 1993 3 '.1-9 1993 3.5. 1-10 1993 3.5. 1-11 1993 3.5.1-12 1993 3.5.1-13 1993 3.5.1-14 1993 3.5. 1-15 1993 3.5. 1-16 1993 3.5. 1" 17 1990 3.5. 1-18 1993

Page 13 VOLUME II Chapter 3 Reactor Unit 1 Pacae Date Table 3.5. 1-1 1995 Fig. 3.5. 1-1 1990 Fig. 3. 5 1-2

~ 1990 Fig. 3.5.1-3 1990 Fig. 3.5.1-4 1990 Fig. 3.5.1-5 1990 Fig. 3.5.1-5a 1992 Fig. 3.5.1-6 1992 Fig. 3.5.1-7 1992 3 ..5. 2=3.. 1994-3.5.2-2 1992 3.5.2-3 1995 3.5.2-4 1995 3.5.2-5 1995 3.5.2-6 1995 Table 3.5.2-1 1995 Table 3.5.2-2 1991 Table 3.5.2"3 1995 Fig. 3.5.2-1 1995 Fig. 3.5.2-2 1995 3.5.3-1 1995 3.5.3-2 1992 3 '.3-3 1990 3.5.3-4 1990 3.5.3-5 1992 3.5.3-6 1992 3 '.3-7 1993 3.5 '-8 1990 3.5.3-9 1992 3.5.3-10 1993 3.5.3-11 1990 3.5. 3-12 1990 3.5. 3-13 1992 3.5.3-14 1991 Table 3.5.3-1 (pg 1) 1992 Table 3.5.3-1 (pg 2) 1992 Table 3.5.3-1 (pg 3) 1990 Table 3.5.3-1 (pg 4) 1992 Fig. 3.5.3-1 1990 Fig. 3.5.3-2 1990 Fig. 3.5.3-3 1990

Page 14 VOLUME II Chapter 3 Reactor Unit 2 Pacae Date

3. 1-1 1991 3 1-2

~ 1991

3. 1-3 1991

3. 1-4 1991

3. 1-5 1991 Table 3.1-1 (Spp) 1991 (Notes) 1994 Table 3 1-2 (pgl)

~ 1991 Table 3. 1-2 (pg2) 1991 Table 3. 1-2 (pg3) 1991 Table 3.1-2.. (pg4).; ~ 1989 Table 301-3 1991 3.2-1 1982 302-2 1991 302-3 1982 3.2-4 .1991 3.2-5 1991 3.2-6 1982 3~2 7 1991 3.2-8 1991 3.2-9 1991 3.2-10 1991 3.2-11 1991 3 ~ 2-12 1991 3.2.13 1991 3.2-14 1994 3.2-14a 1994 3.2-14b 1994 3.2-15 1991 3.2-16 1991 3 02-17 1991 3.2"18 1991 3 '-19 1991 3.2-20 1991 3.2-21 1991 302-22 1991 3.2-23 1991 3.2-24 1991 3.2-25 1991 3.2-26 1991 3.2-27 1991 3.2-28 1991 3.2-29 1991 3.2-30 1994 3.2-31 1994 3.2-32 1995 3.2-33 1995 3.2-34 1995 3.2-35 1995

Page 15 VOLUME II Chapter 3 Reactor Unit 2 Pacae Date 3.2-36 1995 302-37 1995 3.2-38 1995 3.2-39 1995 3.2-40 1995 3.2-41 1995 3.2-42 1995 3.2-43 1995 3.2-44 1995 3.2-45 1995 3 ..2-.46...,. 1995 3.2-47 1995 3.2-48 1995 3.2-49 1995 3 '-50 1995 3.2-51 1995 3.2-52 1995 3.2-53 1995 3 '-54 1995 3.2-55 1995 3.2-56 1995 3.2-57 1995 3.2-58 1995 3.2-59 1995 3.2-60 1995 3.2-61 1995 3.2-62 1995 3.2"63 1995 3.2-64 1995 3.2-65 1995 3.2-66 1995 3.2-67 1995 3.2-68 1995 3.2-69 1995 3.2-70 1995 3.2-71 1995 3.2-72 1995 302-73 1995 3.2-74 1995 3.2-75 1995 3.2-76 1995 3.2-77 1995 3.2-78 1995 3.2-79 1995 3.2-80 1995 3 ~ 2-81 1995 3.2-82 1995 3.2-83 1995 3.2-84 1995 3.2-85 1995

Page 16 VOLUME II Chapter 3 Reactor Unit 2 Pacae Date 3.2-86 1995 3.2-87 1995 3.2-88 1995 3.2-89 1995 3.2-90 1995 3.2-91 1995 3.2-92 1995 3.2-93 1995 3.2-94 1995 Table 3.2-1 1995

. Fig....3..2=3 1991-.,

Fig. 3.2-2 1991 Fig. 3.2-3 1991 Fig. 3.2-4 1991 Fig. 3.2-5 1991 Fig. 3.2-5a 1991 Fig. 3.2-6 1991 Fig. 3.2-7 1991 Fig. 3 '-8 3.2-9 1982 Fig. 1982 Fig. 3.2-10 1982 Fig. 3. 2" 11 1982 Fig. 3.2-12 1982 Fig. 3. 2-13 1982 Fig. 3. 2-15 1982 Fig. 3 '-16 1982 Fig. 3.2-'17 1982 Fig. 3.2-18 1990 Fig. 3.2-19 1982 Fig. 3.2-20 1982 Fig. 3. 2-21 1982 Fig. 3.2-22 1982 Fig. 3.2-23 1982 Fig. 3.2-24 1982

Page 17 VOLUME III Chapter 3 Reactor Unit 2 Pacae Date 3~3 1 1991 313-2 1991 3~3 3 1991 3.3-4 1995 3.3-5 1991 3.3-6 1991 3 3 7

~ 1991 3.3-8 1991 3.3-9 1993 3.3-10 1995 3' 3 1 1>>

. 1991 ~

313-12 1995 3.3-13 1991 3.3-14 1991

3. 3-15 1991 3.3-16 1991 3 ~ 3-17 1991 3.3-18 1991

3. 3-19 1991 3.3-20 1991 3.3-21 1991 303-22 1991 313-23 1992 3.3-24 1995 3.3-25 1991 3.3-26 1991 303-27 1991 3.3-28 1995 3.3-29 1991 3.3-30 1991 3.3-31 1991 303-32 1991 3.3-33 1991 3.3-34 1991 3.3-35 1993 3.3-36 1991 3 ~3 37 1991 3.3-38 1991 3.3-39 1991 3.3-40 1991 3.3-41 1991 3.3-42 1991 3.3-43 1991 3.3-44 1995 3.3-45 1991 3.3-46 1991 3.3-47 1991

Page 18 VOLUME III Chapter 3 Reactor Unit 2 Pacae Date 3.3-48 1991 3.3-49 1991 3.3-50 1991 3.3-51 1991 3.3"52 1991 3.3-53 1991 3.3-54 1991 3.3-55 1991 3.3-56 1991 3.3-57 1991 3 3 58-. ~ 1991 3.3-59 1991 3.3-60 1991 3 '-61 1991 Table 3.3-1 (3pp) 1991 Table 3.3-2 (pg1) 1995 Table 3.3-2 (pg2) 1991 Table 3.3-3 1991 Table 3.3-4 1991 Table 3.3-5 1991 Table 3.3-6 1991 Table 3~3 7 1989 Fig. 3 ~ 3-1 1991 Fig. 303-2 1991 Fig. 3.3-3 1991 Fig. 3.3-4 1991 Fig. 3.3-5 1991 Fig. 3.3-6 1991 Fig. 3.3-7 1991 Fig. 3.3-8 1991 Fig. 3.3-9 1991 Fig. 3.3-10 1991

Page 19 VOLUME IlZ Chapter 3 Reactor Unit 2 Pacae Date Fig. 3.3-11 1991 Fig. 3 3 1 2

~ 1991 Fig. 3 3 1 3

~ 1991 Fig. 3.3-14 1991 Fig. 3.3-15 1991 Fig. 3.3-16 1991 Fig. 303-17 1991 Fig. 3.3-18 1991 Fig. 3.3-19 1991 Fig. 3.3-20 1995 Fig . 3.. 3~21.- 1991 Fig. 303-22 1991 Fig. 3.3-23 1991 Fig. 3.3-24 1991 Fig. 3.3-25 1991 Fig. 3.3-26 1991 Pig. 313-27 1991 Pig. 3.3-28 1991 Fig. 3.3-29 1991 Fig. 3.3-30 1991 Fig. 3 3 3 1

~ 1991 Pig. 313 32 1991 Fig. 3 3 33

~ 1991 Fig. 3.3-34 1991 Fig. 3.3-35 1991 Fig. 3.3-36 1991 Fig. 3 3 37

~ 1991 Fig. 3.3-38 1991 3.4-1 1982 3.4-2 1991 3.4-3 1991 3.4-4 1991 3.4-5 1993 3.4-6 1991 3.4-7 1991 3.4-8 1991 3.4-9 1991 3.4-10 1992 3.4-11 1991

Page 20 VOLUME III Chapter 3 Reactor Unit 2 Pa<ac Date 3.4-12 1991 3.4-13 1991 3.4-14 1991 3.4-15 1993 3.4-16 1991 3.4-17 1991 3.4-18 1991 3.4-19 1991 3.4-20 1991 3 ~ 4-21 1991

3. 4~22.. 1991.

3.4-23 1993 3.4-24 1991 3.4-25 1993 3.4-26 1991 3,4-27 1991 3.4-28 1991 3.4-29 1991 3.4-30 1993 3.4-31 1991 3 '-32 1993 3.4-33 1991 3.4-34 1991 3.4-35 1991 3.4>>36 1991 3.4-37 1991 3.4-38 1991 3.4-39 1991 3.4-40 1993 3.4-41 1991 3.4-42 1991 3.4-43 1992 3.4-44 1991 3.4-45 1991 3.4-46 1993 3.4-47 1991 3.4-48 1991 3.4-49 1991 3 '-50 1991 3.4-51 1992 3.4-52 1991 3.4-53 1991 3.4-54 1991 3.4-55 1991 3.4-56 1991 3.4-57 1991 3.4-58 1991 3.4-59 1991 3.4-60 1991

Page 21 VOLUME III Chapter 3 Reactor Unit 2 Pa<ac Date 3.4-61 1991 3.4-62 1991 3.4-63 1991 3.4-64 1991 3.4-65 1991 Table 3.4-1 (pg 1) 1992 (pg 2) 1992 (pg 3) 1991 Table 3. 4-2 1991 Table 3.4-3 (2pp) 1991 Table. 3 4=4 1991...

Fig. 3.4-1 1991 Fig. 3.4-2 1991 Fig. 3.4-3 1991 Fig. 3.4-4 1991 Fig. 3.4-5 1991 Fig. 3.4-6 1991 Fig. 3 '-7 1991 Fig. 3.4-8 1991 Fig. 3.4-9 1991 Fig. 3.4-10 1991 Fig. 3.4-11 1991 Fig. 3.4-12 1991 Fig. 3.4-13 1991 Fig. 3.4-14 1991 3.5-1 1991 3.5-2 1987 3.5-3 1991 3.5-4 1991 3.5-5 1991 3.5-6 1991 3.5-7 1991 3.5-8 1991 3.5-9 1991

3. 5-10 1993 3.5-11 1991

Page 22 VOLUME III Chapter 3 Reactor Unit 2 Pacae Date

3. 5-12 1991

3. 5-13 1991 3.5-14 1991 3.5-15 1991 3.5-16 1991

3. 5-17 1991 3.5-18 1991 3.5-19 1987 3.5-20 1990 Table 3.5.1-1 (2pp) 1991 Table 3.5..1=2. (2pp) .. 1991..

Table 3.5.1-3 1991 Fig. 3. 5. 1-1 1983 Fig. 3.5.1-2 ORIG Fig. 3.5 '-3 1991 Fig. 3.5.1-4 1983 3.5-26 1991 3.5-27 1991 3 '-28 1991 Table 3.5.2-1 1991

Page 23 VOLUME III Chapter 4 Reactor Coolant S stem Pacae Date

4. 1-1 1991

4. 1-2 1991 4.1-3 1982 4.1-4 1982 4.1>>5 1982

4. 1-6 1982

4. 1-7 1982

4. 1-8 1982

4. 1-9 1982

4. 1-10 1982

.4. 1".,11 1982*

4. 1-12 1990

4. 1-13 1990

4. 1-14 1990 4.1-15 1990 4.1-16 1991 4.1-17 1982

4. 1-18 1982

4. 1-19 1989

4. 1-20 1982 4.1-21 1982 4.1.22 1982 4.1-23 1982 4.1-24 1982 Table 4. 1-1 1990 Table 4. 1-2 1995 Table 4. 1-3 1990 Table 4.1-4 1991 Table 4.1-5 ( pg 1) 1991

( pg 2) 1989 Table 4.1-6 1989 Table 4.1-7 1989 Table 4. 1-8 1989 Table 4.1-9 1989 Table 4. 1-10 (pg 1) 1990 (pg 2) 1989 Table 4. 1-11 (3pp) 1989 Table 4. 1-12 (2pp) 1991 4.2-1 1982 4.2-2 1982 4.2-3 1982 4.2-4 1989 4.2-5 1982 4.2-6 1982 4.2-7 1982 4.2-8 1982 4.2-9 1994

4. 2-3.0 1982 4.2-11 1989 4.2-12 1989

Page 24 VOLUME III Chapter 4 Reactor Coolant S stem Pacae Date 4.2-13 1989 4.2-14 1982 4.2-15 1982

4. 2-16 1982

4. 2-17 1995 4.2"18 1983 4.2-19 1991 4.2-20 1991 4.2-21 1991 4.2-22 1995 4.2-..23 .. 1982 4.2-24 1994 4.2-25 1982 4.2-26 1995 4.2-27 1982 4 '-28 1986 4.2-29 1982 4.2-30 1982 4.2-31 1982 4.2-32 1982 4.2-33 1982 4.2-34 1987 4.2-35 1987 4.2-36 1987 Table 4.2-1 (3pp) 1989 Table 4.2-2 1992 Table 4.2-3 1994 Fig. 4 2-1

~ 1984 Figs 4.2-1A 1988 Fig. 4.2-2 1982 Fig. 4.2-2A 1982 Fig. 4.2-3 1995 Fig. 4.2-4 1982 Fig. 4.2-4A 1989 Fig. 4.2-5 1982 Fige 4.2-6 1982 Fige 4.2-7 1982 Fig. 4.2-8 1982 Fig. 4.2-9 1982 Fig. 4.2-9 Ref. (4pp) 1982 4.3-1 1982 4.3-2 1982 4.3"3 1982 4.3-4 1982 4.3-5 1982 4.3-6 1982 4.3-7 1990 4.3-8 1982 4.3-9 1982

Page 25 VOLUME III Chapter 4 Reactor Coolant S stem Pacae Date 4.3-10 1982 4.3-11 1989 4.3-12 1989

4. 3-13 1989 4.3-14 1989 4.3-15 1989 4.3-16 1989 4.3-17 1989 4.3-18 1989 4.3-19 1989 4.3 1989 .

4. 3-21 1989 4.3-22 1989 4.3-23 1989 4.3-24 1989 4.3-25 1989 4.3-26 1989 Table 4.3-1 1990 Table 4.3-2 1990 Table 4.3-3 1989 Table 4.3-4 1989 Table 4.3-5 (2pp) 1990 Table 4.3-6 1990 Table 4.3-7 1990 Table 4.3-8 1989 Fig. 4.3-1 1982 Fig. 4.3-2 1982 Fig. 4.3-3 1982 Fig. 4.3-4 1982 Fig. 4.3-5 1982 Fig. 4.3-6 1990 Fig. 4.3-7 1990 4.4-1 1986 4.4-2 1988 4.4-3 1986 4.5-1 1982 4.5-2 1988 4 '-3 4.5-4 1982 1982 4.5-5 1993 4.5-6 1993 4.5-7 1982 4.5-8 1982 4.5-9 1982 4.5-10 1982 4.5-11 1982 4 ~ 5-12 1982

Page 26 VOLUME III Chapter 4 Reactor Coolant S stem Pacae Date 4.5-13 1982 4.5-14 1983

4. 5-15 1982

4. 5-16 1982

4. 5-17 1982 4.5-18 1982 4.5-19 1982 4.5-20 1988

4. 5-21 1988 4.5-22 1988

. 4. 5~23-- 1988 4.5-24 1988 4.5-25 1988 Table 4. 5-1 (pg 1) 1989 (pg 2) 1989 (pg 3) 1989 (pg 4) 1990 Fig. 4. 5-1 1982 Fig. 4. 5-2 1982 Fig. 4.5-3 1982

Page 27 VOLUME IV Chapter 5 Containment S stem Pacae Date

5. 0-1 1989 5.1-1 1987

5. 1-2 1982 5.1-3 1982

5. 1-4 1982 Table 5. 1-1 (2pp) 1989 5.2-1 1989 5.2-2 1982 5.2-3 1982 5.2-4 1982 5.. 2.-.5. 1982 5.2-6 1986 5.2-7 1982 5.2-8 1990 5.2-9 1986 5 '-10 1982 5.2-11 1982 5.2-12 1982 5.2-13 1982 5.2-14 1982 5.2-15 1982 5.2-16 1982 5.2-17 1982 5.2-18 1982 5.2-19 1982 5.2-20 1982 5.2-21 1982 5.2-22 1982 5.2-23 1982 5.2-24 1982 5.2-25 1982 5.2-26 1990 5.2-27 1982 5.2-28 1987 5.2-29 1982 5.2-30 1982 5.2-31 1987 5.2-32 1987 5.2-33 1987 5.2-34 1982 5.2-35 1987 5.2-36 1987 5.2-37 1988 5.2-38 1987 5.2-39 1987 5.2-40 1987 5.2-41 1987 5.2-42 1995 5.2-43 1987 5.2-44 1990 5.2-45 1989

Page 28 VOLUME IV Chapter 5 Containment S stem Pacae Date 5.2-46 1989 5.2-47 1989 5.2-48 1982 5.2-49 1988 5.2-50 1989 5.2-51 1989 5.2-52 1987 5.2-53 1995 5.2-54 1988 5.2-55 1989 5 2.-.56- 1990 5.2-57 1987 5.2-58 1987 5.2-59 1991 5.2-60 1989 5.2-61 1988 5.2-62 1987 5.2-63 1987 5.2-64 1987 5.2-65 1987 5.2-66 1987 5.2-67 1995 5.2-68 1988 5.2-69 1988 5.2-70 1987 5.2-71 1988 5.2-72 1987 5.2-73 1987 5.2-74 1987 5.2-75 1987 5.2-76 1987 5.2-77 1988 5.2-78 1988 5.2-79 1990 5.2-80 1991 5.2-81 1990 5.2-82 1990 5.2-83 1990 5 '-84 1990 5.2-85 1990 5 '-86 1990 5.2-87 1990 5.2-88 1990 5.2-89 1993 5.2-90 1990 5.2-91 1990 5.2-92 1990 5.2-93 1990 5.2-94 1990 5.2-95 1990

Page 29 VOLUME IV Chapter 5 Containment S stem Pacae Date 5.2-96 1990 5 '-97 1990 5.2-98 1990 5.2-99 1990 5.2-100 1990

5. 2-101 1990

5. 2-102 1990 5.2-103 1990

5. 2-104 1990

5. 2-105 1990 5 . 2-. 106- ~

1990 5.2-107 1990 5.2-108 1990 5.2-109 1990 5.2-110 1990 5.2-111 1995

5. 2-112 1990 5.2-113 1991

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

Page 30 VOLUME IV Chapter 5 Containment S stem Pacae Date Fig. 5.2.2-11 1982 Fig. 5. 2. 2-11A 1982 Fig. 5.2.2-12 1982 Fig. 5.2.2-12A 1982 Fig. 5.2. 2-13 1982 Fig. 5.2.2-14 1982 Fig. 5.2.2-15 1982 Fig. 5.2.2-16 1982 Fig. 5.2.2-17 1982 Fig. 5.2.2-18 1982 Fig v. 5.2.2 1982 Fig. 5.2.2-20 1982 Fig. 5.2.2-21 1982 Fig. 5.2.2-22 1982 Fig. 5.2 '-23 1982 Fig. 5.2.2-24 1982 Fig. 5.2.2-25 1982 Fig. 5.2.2-26 1982 Fig. 5.2.2-27 1982 Fig. 5.2.2-28 1982 Fig. 5 '.2-29 1982 Fig. 5.2.2"30 1982 Fig. 5.2.2-31 1982 Fig. 5.2.2-32 1982 Fig. 5.2.2-33 1982 Fig. 5.2.2-34 1982 Fig. 5.2.2"35 1982 Fig. 5.2.2-36 1982 Fig. 5.2.2-37 1982 Fig. 5.2.2-38 1982 Fig. 5.2.2-39 1982 Fig. 5.2.2-40 1982 Fig. 5.2.2-41 1982 Fig. 5.2.2-42 1982 Fig. 5.2.2-43 1982 Fig. 5.2.2-44 1982 Fig. 5.2.2-45 1982 Fig. 5.2.2-46 1982 Fig. 5.2.2-47 1982 Fig. 5.2.2-48 1982 Fig. 5.2.2-49 1982 Fig. 5.2.2-50 1982 Fige 5.2.2-51 1982 Fig 5. 2. 2-51A 1982 Fig. 5.2.2-51B 1982 Fig 5.2.2-51C 1982 Fig. 5.2.2-51D 1982 Fig. 5.2.2-51E 1982 Fig. 5.2.2"52 1982 Fig. 5.2.2-52A 1982 Fig. 5.2.2-53 1982

Page 31 VOLUME IV Chapter 5 Containment S stem Pacae Date Fig. 5.2.2-54 1995 Fig. 5.2.2-54A 1982 Fige 5.2.2-54B 1982 Fig. 5.2.2-55 1982 Fig. 5.2.2-55A 1982 Fig. 5.2.2-56 1982 Fig. 5.2.2-56A 1982 Fig. 5.2.2-57 1982 Fig. 5.2.2-57A 1982 Fig. 5.2.2-58 1982 Fig. .. 5.2.2-.58A 1982 Fige 5.2.2-59 1982 Fig. 5.2.2-59A 1982 Fig. 5 '.2-59B 1982 Fige 5.2.2-59C 1982 Fig. 5.2.2-59D 1982 Fig. 5.2.2-59E 1982 Fige 5.2.2-60 1991 Fig. 5.2.2-60A 1991 Fig. 5.2.2-60B 1982 Fig. 5.2.2-60C 1982 Fig. 5.2.2-61 1982 Fig. 5.2.2-62 1982 Fig. 5.2.2-63 1982 Fig. 5.2.2"64 1982 Fige 5.2.2-65 1982 Fig. 5.2.2-65A 1982 5.3-1 1984 5.3-2 1984 5.3-3 1982 5.3-4 1982 5.3-5 1982 5.3-6 1982 5.3-7 1982 5.3-8 1982 5.3-9 1982 5.3-10 1988 5.3-11 1982 5.3-12 1993 5.3-13 1984 5.3-14 1993 5.3-15 1982 5.3-16 1984 5.3-17 1984 5.3"18 1982 5.3-19 1982 5.3-20 1990 5.3-21 1982 5.3-22 1982 5.3-23 1982

Page 32 VOLUME IV Chapter 5 Containment S stem Pacae Date 5.3-24 1982 5.3-25 1982 5.3-26 1986 5.3-27 1986 5.3-28 1982 5.3-29 1988 5.3-30 1988 5.3-31 1988 5.3-32 1982 5.3-33 1988 5.3-34 1989 Table 5 3-1, (pg, 1)

~ 1993 (pg 2) 1989 Fig. 5.3-1 1982 Fig. 5.3-2 1986 Fig. 5.3-2A 1986 Fig. 5.3-3 1982 Fig. 5.3-4 1982 5.4-1 1995 5.4-2 1995 5.4-3 1995 5.4-4 1995 5.4-5 1995 5.4-6 1995 5.4-7 1995 5.4-8 1995 5.5-1 1982 5.5-2 1982 5.5-3 1987 5.5-4 1993 5.5-5 1993 5.5-6 1993 5.5-7 1987 5.5-8 1993 5.5-9 1992

5. 5-10 1992

5. 5-11 1992 5.5-12 1987

5. 5-13 1987

Page 33 VOLUME IV Chapter 5 Containment S stem Pacae Date

5. 5>>14 1987

5. 5" 15 1987

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

Page 34 VOLUME IV Chapter 6 En ineered Safet Features Pacae Date 6.1-1 1989

6. 1-2 1989

6. 1-3 1989

6. 1-4 1989 6.1-5 1989

6. 1-6 1989 6.1-7 1989 6.1-8 1989

6. 1-9 1989

. 6 1-10 ~ 1989 6.1-11 1989 Table 6. 1-1 1989 6.2-1 1982 6.2-2 1982 6.2-3 1982 6.2-4 1982 6.2-5 1993 6.2-6 1993 6.2-7 1993 6.2-8 1993 6.2-9 1988 6.2-10 1991 6.2-11 1992 6.2 12 1995 6.2-13 1995 6.2-14 1995 6.2-15 1995 6.2-16 1995 6.2-17 1995 6.2-18 1992 6.2-19 1982 6.2-20 1982 6 2-21

~ 1990 6.2-22 1990 6.2-23 1990 6.2-24 1995 6.2-25 1982 6.2-26 1982 6.2-27 1982 6.2-28 1982 6.2-29 1982 6.2-30 1993 6.2-31 1993 6.2-32 1982 6.2-33 1993 6.2-34 1982 6.2"35 1982 6.2-36 1982 6.2-37 1993

Page 35 VOLUME IV Chapter 6 En ineered Safet Features Pacae Date 6.2-38 1982 6.2-39 1982 Table 6.2-1 1995 Table 6.2-2 1994 Table 6.2-3 1993 Table 6 '-4 1989 Table 6.2-5 1991 Table 6.2-6 (pg 1) 1993 (pg 2) 1989 (pg 3) 1989 Table 6.2=7.. (2pp) ... 1991-Table 6.2-8 1989 Table 6.2-9 1989 Table 6. 2-10 (2pp) 1989 Fig. 6.2-1 1993 Fig. 6.2-1A 1995 Fig. 6.2-2 1982 Fig. 6.2-3 1982 Fig. 6.2-4 1991 Fig. 6.2-5 1982 6.3-1 1982 6.3-2 1994 6.3-3 1994 6.3-4 1982 6.3-5 1994 6.3-6 1982 6.3-7 1982 6.3-8 1982 6.3-9 1986 6.3-10 1991 6.3-11 1982 6.3-12 1982

6. 3-13 1982 Table 6.3-1 1989 Table 6.3-2 1991 Table 6.3-3 1991 Table 6.3-4 (pg 1) 1992 (pg 2) 1989 Fig. 6.3-1 1982

Page 36 VOLUME V Chapter 7 Instrumentation and Control Pacae Date 701-1 1993 7 1-2

~ 1982 7 ~2 1 1982 7.2-2 1990 7~2 3 1982 7.2-4 1982 7.2-5 1982 7.2-6 1982 702-7 1982

. 7.2-..8.... 1982 7.2-9 1982 7.2-10 1982 7.2-11 1982 7.2-12 1982 7 ~ 2 13 1994

7. 2-14 1982 7.2-15 1982

7. 2-16 1982

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

i 0

Page 37 VOLUME V Chapter 7 Instrumentation and Control Pacae Date 7.2-47 1987 7.2-48 1987 7.2-49 1987 7.2-50 1987 7.2-51 1987 7 '-52 1987 7.2-53 1987 Table 7. 2-1 (pg 1) 1989 (pg 2) 1992

~

-(pg-3) 1989 (pg 4) 1990 (pg 5) 1990 Table 7.2-2 (pg 1) 1991 (pg 2) 1992 (pg 3) 1991 (pg 4) 1991 (pg 5) 1991 (pg 6) 1991 Table 702-3 1991 Table 7.2-4 1991 Table 7.2-5 (2pp) 1991 7.2-69 1994 Fig 7.2-2 1982 Fig. 7.2-3 1982 Fige 7.2-4 1982 Fig. 7.2-5 1982 Fig. 7.2-6 1982 Fig. 7 2 7

~ 1982 Fig. 7.2-8 1982 Fig. 7.2-9 1982 7~3 1 1987 7~3 2 1990 7 3 3

~ 1982 7.3-4 1982 7 '-5 1982 7.3-6 1992 7~3 7 1983 7.3-8 1982 7.3-9 1982 7.3-10 1990 7.3-11 1982 7 3-12 0 1982 7.3-13 1982 Fig. 7~3-1 1982 7.4-1 1982 7.4-2 1991

Page 38 VOLUME V Chapter 7 Instrumentation and Control Pa<ac Date 7.5-1 1982 7.5-2 1982 7.5-3 1982 7.5-4 1982 7.5-5 1982 7.5-6 1991 7.5-7 1995 7.5-8 1987

- 7.S~9 ~ 1989 ~

7.5-10 1987

7. 5-11 1982 7.5-12 1982 7.5-13 1991 7.5-14 1982 7 '-15 1982 7.5-16 1982 7.5-17 1982 7.5-18 1991 7.5-19 1982 7.5-20 1989 Table 7.5-1 1989 Table 7.5-2 (2pp) 1989 Fig. 7.5-1 1982 Fig. 7.5-2 1982 Fig. 7 '-3 7.6-1 1982 1991 7.6-2 1991 7.6-3 1991 7.6-4 1991 7.6-5 1991 Fig. 7.6-1 1982 Fig. 7.6-2 1982 Fig. 7.6-3 1982

7. 7-1 1982 7~7 2 1982 7~7 3 1982 7.7-4 1982 7.7-5 1995 7.7-6 1993 7~7 7 1991

7. 7-8 1991 7.7-9 1995 7.7-10 1986 7 ~ 7-11 1982

7. 8-1 1992 7.8-2 1992

Page 39 VOLUME V Chapter 7 Instrumentation and Control Pacae Date Table 7.8-1 (2 pgs) 1992 Table 7.8-2 (2 pgs) 1992 Table 7.8-3 (2 pgs) 1992 Table 7.8-4 (pg 1) 1994 (pg 2) 1993 (pg 3) 1992 (pg 4) 1992 (pg 5) 1992 Table 7.8-5 (3 pgs) 1992

Page 40 VOLUME V Chapter 8 Electrical S stems Pacae Date 8 ~ 1-1 1994 8.1-2 1982

8. 1-3 1990

8. 1-4 1990

8. 1-5 1991

8. 1-6 1991 8.1-7 1991 8.1-8 1987

8. 1-9 1982 Fig ..8. 1.-.1...., 1986" Fig. 8.1-1A 1994 Fig. 8. 1-1B 1994 Fig. 8. 1-2A 1994 Fig. 8.1-2B 1994 8 '-1 1990 Fig. 8.2-1 1990 8.3-1 1990 8.3-2 1991 8.3-3 1990 8.3-4 1990 8.3-5 1990 8.3-6 1994 8.3-7 1994 8.3-8 1990 8.3-9 1990

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

Page 41 VOLUME V Chapter 9 Auxilia and Emer enc 8 stems Pacae Date

9. 1-1 1992 9.1-2 1982

9. 1-3 1990

9. 1-4 1982 9.2-1 1982 9.2-2 1982 9.2-3 1991 9.2-4 1986 9.2-5 1982 9.2-6 1982

9. 2.=7,. 1988-9.2-8 1987 9 '-9 9.2-10 1982 1982 9.2-11 1995 9.2-12 1982 9.2-13 1982 9.2-14 1982 9.2-15 1982 9.2-16 1990 9.2-17 1992 9 ~ 2-18 1992 9.2-19 1994 9.2-20 1994 9.2-21 1982 9.2-22 1982 9.2-23 1995 9.2-24 1988 9.2-25 1982 9.2-26 1982 9.2-27 1982 9.2-28 1982 9.2-29 1993 9.2-30 1993 9.2-31 1982 9.2-32 1982 9.2-33 1993 9.2-34 1991 9.2-35 1982 9.2-36 1982 9.2-37 1995 9.2-38 1982 Table 9.2-1 1990 Table 9.2-2 1989 Table 9.2-3 (pg 1) 1989 (pg 2) 1990 (pg 3) 1989 (pg 4) 1992 (pg 5) 1989 (pg 6) 1990

Page 42 VOLUME V Chapter 9 Auxilia and Emer enc S stems Pacae Date Table 9 '-3 (pg 7) 1989 (pg 8) 1989 (pg 9) 1989 (pg 10) 1990 (pg 11) 1989 (pg 12) 1989 (pg 13) 1995 (pg 14) 1990 (pg 15) 1989 (pg 16) 1989 (pg"17) 1989" Table 9.2-4 (2pp) 1989 Fig. 9.2-1 1992 Fig. 9.2-2 1982 Fig. 9.2-3 1993 Fig. 9.2-4 1984 Fig. 9.2-5 ORIG Fig. 9.2-6 1982 9.3-1 1982 9.3-2 1982 9.3-3 1994 9.3-4 1994 9.3-5 1994 9.3-6 1994 9.3-7 1994 9.3-8 1994 9.3-9 1987 9.3-10 1986 9.3-11 1994 9 ~ 3-12 1990 9.3-13 1990 Table 9.3-1 1990 Table 9.3-2 (1pp) 1990 Table 9.3-2 (2pp) 1991 Table 9.3-3 (3pp) 1990 Fig. 9.3-1 1991 9.4-1 1994 9.4-2 1995 9.4-3 1994 9.4-4 1983 9.4-5 1995 9.4-6 1982 9.4-7 1986 Table 9.4-1 1990 Table 9.4-2 (pg1) 1989 Table 9.4-2 (pg2) 1995 Table 9.4-2 (pg3) 1995 Table 9.4-2 (pg4) 1989 Table 9.4-3 1989 Fig. 9.4-1 1990

Page 43 VOLUME V Chapter 9 Auxilia and Emer enc S stems Pacae Date 9.5-1 1985 9.5-2 1994 9.5-3 1992 9.5-4 1982 9.5-5 1982 9.5-6 1982 9.5-7 1982 9.5-8 1982 9.5-9 1982 Table 9.5-1 1990 Table. .9 5 ~ .. 1994 ~

Table 9.5-3 1993 Table 9.5-4 1993 Fig. 9.5-1 1995 9.6-1 1991 9.6-2 1983 9.6-3 1989 9.6-4 1987 9.6-5 1987 9.6-6 1988 9.6-7 1983 9.6-8 1983 9.6-9 1982 Fig. 9. 6-1 1992 Fig. 9.6-2 1987 9.7-1 1982 9 '-2 1994 9.7-3 1982 9.7-4 1982 9.7-5 1994 9.7-6 1994 9.7-7 1995 9.7-8 1995 9.7-9 1992 9.7-10 1995 9.7-11 1995

9. 7-12 1991

9. 7-13 1994

9. 7-14 1994

9. 7-15 1994 9.7-16 1994

9. 7-17 1994

9. 7-18 1994 9.7-19 1994 9.7-20 1994

9. 7-21 1994 9.7-22 1994 9.7-23 1994 9.7-24 1994 9.7-25 1995 9.7-26 1995 9.7-27 1995 9.7-28 1995 9.7-29 1995

Page 44 VOLUME V Chapter 9 Auxilia and Emer enc S stems Pacae Date 9.7-30 1995 9.7-31 1995 9.7-32 1995 Table 9. 7-1 1994 Table 9.7-2 1994 Table 9.7-3 1994 Table 9.7-4 1994 Table 9.7-5 1994 Table 9.7-6 1994 Fig. 9.7-1 1982 Fig. 9 '~2 1994 ~

Fig. 9.7-3 1994 Fig. 9 '-4 1994 Fig. 9.7-5 1994

9. 8-1 1994 9.8-2 1995 9.8-3 1995 9.8-4 1993 9.8-5 1995 9.8-6 1993 9.8-7 1993 9 '-8 1994 9.8-9 1993

9. 8-10 1993 9.8-11 1993

9. 8-12 1993 9.8-13 1994 9.8-14 1993 9.8-15 1993

9. 8" 16 1995

9. 8-17 1993 9.8-18 1993

9. 8-19 1994 9.8-20 1993

9. 8-21 1993 9.8-22 1993 9.8-23 1993 9.8-24 1993 9.8-25 1987 9.8-26 1987 9.8-27 1987 9.8-28 1987 9.8-29 1994 9.8-30 1987 Table 9.8-1 1993 Table 9.8-2 (1pp) 1989 Table 9.8-2 (2pp) 1991 Table 9.8-2 (3pp) 1991 Table 9.8-3 1989 Table 9.8-4 (3pp) 1989 Table 9.8-5 1993 Table 9.8-6 1989 Fig. 9.8-1 1993 Fig. 9.8-2 1982 Fig. 9.8-3 1991 Fig. 9.8-4 1993

Page 45 VOLUME V Chapter 9 Auxilia and Emer enc S stems Pacae Date Fig. 9.8-5 1993 Fig. 9.8-6 1985 Fig. 9.8-7 1982

9. 9-1 1992 9.9-2 1995 9.9-3 1995 9.9-4 1995 9.9-5 1995 9.9-,6 ... 1991 9.9-7 1991 9.9-8 1995 9.9-9 1995 Fig. 9.9-1 1992 Fig. 9.9-2 1989

9. 10-1 1992

9. 10-2 1987

9. 10-3 1986

9. 10-4 1987 Fig. 9.10-1 1986

Page 46 VOLUME VI Steam and Power Conversion Chapter 10 S stem Pacae Date

10. 1<<1 1987 10.1-2 1982 10.2-1 1982 Fight 10.2-2 1983 10.2-3 1985

10. 2-4 1991 10.2-5 1985 10.2-6 1988

-.10. 2p 1- ~ 1984 Fig. 10.2-1A 1991 Fig. 10.2-1B 1982 Fig. 10.2-1C 1992

10. 3-1 1986 10.3-2 1982 10.3 "3 1986 10.3-4 1994 10.3-5 1995 10.3-6 1984 Fig. 10. 3-1 1984 Fig. 10.3-1A 1984 10.4-1 1991 10.4-2 1985 10.4-3 1991

10. 5-1 1986 10.5-2 1991 10.5-3 1982

10. 5-4 1987 10.5-5 1990 10.5-6 1989 10.5-7 1993 Table 10. 5-1 1991 Fig. 10.5-1 1995 Fig. 10. 5-2 1982 Fig. 10.5-2A 1982 Fig. 10.5-3 ~

1982 Fig. 10.5-3A 1982 Fig. 10. 5-4 1991 Fig. 10.5-4A 1991 Fig. 10. 5-5 1990 Fig. 10.5-5A 1982 10.6-1 1995 10.6-2 1982 10 6-3

~ 1982 10.6-4 1991 Table 10.6-1 1995 Fig. 10. 6-1 1982

Page 47

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

10. 7-1 1982

10. 7-2 1982

10. 8-1 1982"

10. 9-1 1995

10. 10-1 1995 10.11-1 1983

10. 11-2 1988

10. 11-3 1983

Page 48 VOLUME VI Waste Disposal and Chapter 11 Radiation Protection S stem Pacae Date

11. 1" 1 1985

11. 1-2 1992 11 01 "3 1982

11. 1-4 1983

11. 1-5 1994 11 1-6

~ 1994 1111-7 1992

11. 1-8 1983

11. 1-9 1995

11. 1-.10- . 1982

11. 1-11 1994

11. 1-12 1993

11. 1-13 1985

11. 1-14 1994

11. 1-15 1985 11.1-16 1982 11 01-17 1994

11. 1-18 1994 Table 11. 1-1 1989 Table 11. 1-2 1990 Table 11.1-3 (pg 1) 1990 (pg 2) 1993 Table 11.1-4 1989 Table 11. 1-5 1989 Table 11. 1-6 1989 Fig. 11. 1-1 1988 Fig. 11. 1-2 1994 Fig. 11. 1-2A 1982 Fig. 11.1-2B 1993 Fig. 11. 1-3 1995 Fig. 11. 1-4 1988 11.2-1 1995 11.2-2 1983 ll.

11.2-4 2-3 1995 1995 11.2-5 1982 11.2-6 1982 11.2-7 1995 11.2-8 1995 11.2-9 1995 Table 11.2-1 1995 Table 11.2-2 1995 Table 11.2-3 1995 Table 11 2-4

~ 1989 Table 11.2-5 1995 Table 11 2-6

~ 1995 Table 11.2-7 1989 Table 11.2-8 1989

Page 49 VOLUME VI Waste Disposal and Chapter 11 Radiation Protection S stem Pacae Date Fig. 11.2-1 1982 11.3-1 1990 11.3-2 1986 11.3-3 1988 11.3-4 1990 11.3-5 1992 11.3-6 1992 1113-7 1995 11.3-8 1990

.. 11.3.-9.. 1990 11.3-10 1993

11. 3-11 1990 11.3-12 1995 11 03-13 1995

11. 3-14 1990 11.3-15 1992

11. 3-16 1992 11.3-17 1993 11.3-18 1994 Table 11. 3-1 (pgl) 1990 Table 11. 3-1 (pg2) 1995 Table 11. 3-1 (pg3) 1995 Table 11. 3-1 (pg4) 1991 Table 11. 3-1 (pg5) 1991 Table 1113-2 1990 11.4-1 1995

11. 4-2 1995 11.4-3 1993 11.4-4 1995 11.4-5 1995 11.4-6 1995 11.4-7 1995 11.4-8 1995 11.4-9 1995 11.4-10 1995 11.4-11 1993 11.4-12 1995 11.5-1 1987

11. 5-2 1990

11. 5-3 1983 Table 11.5-1 1989 Table 11. 5-2 1989 Fig. 11 5-1

~ 1983

Page 50 VOLUME VZ Waste Disposal and Chapter 11 Radiation Protection S stem Pacae Date 11.6-1 1995 11.6-2 1988

11. 6-3 1990 11.6-4 1993 Fig. 11. 6-1 1994 Fig. 11.6-2a 1986 Fig. 11.6-2b 1986 Fig. 11. 6-2c 1990

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

12. 1-1 1994

12. 1-2 1982 12.2-1 1994 12.2-2 1988 12 2-3 0 1988

12. 2-4 1988 12.2-5 1988 12.2-6 1988 1202-7 1988

~ 12.2 .8 1988 12 03-1 1988 12.4-1 1983

12. 5-1 1982

12. 6-1 1991

12. 6-2 1994

12. 6-3 ORIG 1217-1 1991

Page 52 VOLUME VI Chapter 13 Initial Tests and 0 eration Pacae Date

13. 1-1 1991

13. 1-2 1991

13. 1-3 1991 13.1-4 1982 Table 13.1-1 (1pp) 1989 Table 13 . 1-1 (2pp) 1989 Table 13.1-1 (3pp) 1991 Table 13 . 1-1 (4pp) 1989

, Table 13 . 1-1 (5pp) 1991 Table 13. 1-1 (6pp) 1989 Table- 13; 1-1 ~ (7pp) ~ 1991 .

Table 13 . 1-1 (8pp) 1989 Table 13.1-1 (9pp) 1989 13.2-1 1982 13 02-2 1991 1302-3 1991 13.2-4 1991 13.2-5 1991 13.2-6 1991 Table 13.2-1 (lpp) 1991 Table 13. 2-1 (2PP) 1991 Table 13. 2-1 (3pp) 1989 Table 13 . 2-1 (4pp) 1991 Table 13.2-1 (5pp) 1991 Table 13.2-1 (6pp) 1991 Table 13.2-1 (7pp) 1991 13.3-1 1982 13 03-2 1991 13.3-3 1982 13.3-4 1991 13.3-5 1982 Table 13.3-1 (1pp) 1989 Table 13.3-1 (2pp) 1991 Table 13.3-1 (3PP) 1991 13.4-1 1983

Page 53 VOLUME VII Chapter 14 Safet Anal sis Unit 1 Pacae Date 14.0-1 1993 14.0-2 1993

14. 0-3 1993

14. 1-1 1993

14. 1-2 1993 14.1-3 1993

14. 1-4 1993

14. 1-5 1993

14. 1-6 1995

14. 1 7., 1993.

14. 1-8 1993 14.1-9 1993

14. 1-10 1995

14. 1-11 1995

14. 1-12 1995 14.1-13 1995 Table 14. 1-1 1995 Table 14. 1-2 1995 Table 14 . 1-3 (2pp) 1995 Table 14. 1-4 1995 Fig. 14. 1-1 1990 Fig. 14. 1-2 1990 Fig. 14. 1-3 1990 Fig. 14. 1-4 1990 Fig. 14.1-5 1990 Fig. 14.1-6 1992

14. 1. 1-1 1993

14. 1. 1-2 1990

14. 1. 1-3 1994

14. 1. 1-4 1990

14. 1. 1-5 1990 Fig. 14. 1. 1-1 1990 Fig. 14. 1. 1-2 1990

14. 1. 2-1 1990

14. 1. 2-2 1990

14. 1. 2-3 1990

14. 1.2-4 1990 14 '.2-5 1990 14.1.2-6 1990 Fig. l.

14. 2-1 1990 Fig. 14. 1. 2-2 1990 Fig. 14.1.2-3 1990 Fig. 14. 1.2-4 1990 Fig. 14. 1.2-5 1990 Fig. 14.1.2-6 1990 Fig. 14.1.2-7 1990 Fig. 14.1.2-8 1990 Fig. 14. 1.2-9 1990

Page 54 VOLUME VII Chapter 14 Safet Anal sis Unit 1 Pa<ac Date 14.1.3-1 1993 14.1.3-2 1992 14.1.3-3 1992

14. 1. 3-4 1992 14.1.3-5 1990

14. 1. 3-6 1990

14. 1. 3-7 1992 Fig. 14. 1. 3-1 1990 Fig. . 14. 1. 3-2 1990 14.1.4=1. 1990-14 1. 5-1

~ 1990

14. 1. 5-2 1992

14. 1. 5-3 1992

14. 1.5-4 1990

14. 1. 6-1 1990 14.1.6-2 1990 14.1.6-3 1990 l.

14. 6-4

14. 1. 6-5 1990 1990

14. 1. 6-6 1990

14. 1.6-7 1990

14. 1. 6-8 1990 Fig. 14. 1. 6-1 1990 Fig. 14. 1. 6-2 1990 Fig. 14. 1. 6-3 1990 Fig. 14. 1. 6-4 1990 Fig. 14.1.6-5 1990 Fig. 14.1.6-6 1990 Fig. l.

14. 6-7 1990 Fig.

Fig.

l.

14. 6-8

14. 1. 6-9 1990 1990 Fig. 14. 1. 6-10 1990 Fig. 14. 1. 6-11 1990 Fig. 14. 1. 6-12 1990 14.1.7-1 1990 14.1.7-2 1990 14 1

~ ~ 7-3 1990 Fig. 14. 1. 7-1 1982 Fig. 14. 1. 7-2 1982

14. 1. 8-1 1990 14.1.8-2 1990 14.1.8-3 1995

14. 1. 8-4 1995

14. 1 8-5

~ 1990 Fig. 14. 1. 8-1 (3pp) 1995 Fig. 14.1.8-2 (3pp) 1995 Fig. 14.1.8-3 (3pp) 1995 Fig. 14. 1; 8-4 (3pp) 1995 Fig. 14. 1. 8-5 (3pp) 1995

Page 55 VOLUME VII Chapter 14 Safet Anal sis Unit 1 Pacae Date Fig. 14. 1. 8-6 (3pp) 1995 Fig. 14.1.8-7 (3pp) 1995 Fig. 14.1.8-8 (3pp) 1995

14. 1. 9-1 1990 l.

14. 9-2 1990

14. 1. 9-3 1990 Fig. 14. 1. 9-1 1990 Fig. 14.1.9-2 1990

14. 1. 10-1 1993

14. 1.10.-.2-. 1993.

14. 1. 10-3 1993 l.

14. 10 "4

14. 1. 10-5 1993 1993 Table 14.1.10-1 1993 Table 14.1.10-2 1993 Table 14.1.10-3 1993 Table 14.1.10-4 1993 Fig. 14. 1. 10-1 1993 Fig. 14 F 1.10-2 1993 Fig. 14. 1. 10-3 1993 Fig. 14. 1. 10-4 1993 Fig. 14. 1. 10-5 1993 Fig. 14.1.10-6 1993 Fig. 14.1.10-7 1993 Fig. 14. 1. 10-8 1993

14. 1. 11-1 1990

14. 1. 11-2 1993

14. 1. 11-3 1990

14. 1. 11-4 1990 Fig. 14. 1. 11-1 1990 Fig. 14 '.11-2 1990 Fig. 14.1.11"3 1990 Fig. 14. 1. 11" 4 1990 Fig. 14. 1. 11-5 1990 Fig. 14.1.11-6 1990 Fig. 14. 1. 11-7 1990 Fig. 14. 1. 11-8 1990

14. 1. 12-1 1990 14.1.12-2 1990

14. 1. 12-3 1990

14. 1. 12-4 1990 Fig. 14.1 12-1

~ 1990 Fig. 14. 1 12-2

~ 1990

14. 1. 13-1 1991 14.1.13-2 1991

14. 1. 13-3 1989 l.

14. 13-4 1982

14. 1. 13-5 1995

14. 1. 13-6 1995

Page 56 VOLUME VII Chapter 14 Safet Anal sis Unit 1 Pacae Date

14. 1. 13-7 1995

14. 1. 13-8 1995 l.

14. 13-9

14. 1. 13-10 1995 1995

14. 1. 13-11 1995

14. 1. 13-12 1995

14. 1. 13-13 1995

14. 1. 13-14 1995

14. 1. 13-15 1995 14 . 1. 13-16 1990 Table 14. 1. 13-1 1990 Fig-. ~ 14':1.. 13-1-'" 1982 Fig. 1. 13-2 '4.

1982 Fig. 14. 1. 13-3 1982 Fig. 14. 1. 13-4 1982 Fig. 14. 1. 13-5 1982 Fig. 14. 1. 13-6 1982 14.2.1-1 1990

14. 2 1-2

~ 1995 14.2.1-3 1995 14.2.1-4 1995

14. 2. 1-5 1995

14. 2. 1-6 1995 14.2. 1-7 1995

14. 2 1-8

~ 1995 14.2.1"9 1995 14.2.1-10 1995

14. 2. 1-11 1995 14.2. 1-12 1995 14 2. 1-13

~ 1995

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

'-6 1990 1990 14.2.4-8 1992 14.2.4-9 1992

Page 57 VOLUME VII Chapter 14 Safet Anal sis Unit 1 Pacae Date Pig. 14.2.4-1 1982 14.2. 5-1 1990 14.2.5-2 1990 14.2.5-3 1990 14.2.5-4 1990 14.2.5-5 1990 14.2.5-6 1990 14.2.5-7 1990 14.2.5-8 1990 14.2.5-9 1990 Table 14.2.5-1 1990 Fig". 14" 2 '5 1" 1990 Fig. 14.2.5-2 '990 Fig. 14.2.5-3 1990 Fig. 14.2.5-4 1990 Fig. 14.2.5-5 1990 Fig. 14.2.5-6 1990 14.2.6-1 1990 14.2.6-2 1990 14.2.6-3 1990 14.2.6-4 1990 14.2.6-5 1990 14.2.6-6 1990 14.2.6-7 1990 14.2.6-8 1990 14.2.6-9 1990 14.2.6-10 1990 14.2.6-11 1990 14.2.6-12 1990 14.2. 6-13 1990 14.2. 6-14 1990 14.2. 6-15 1990 Table 14.2. 6-1 1990 Fig. 14.2. 6-1 1990 Fig. 14.2.6-2 1990 Fig. 14.2.6-3 1990 Fig. 14 '.6-4 1990 14 ~ 2. 7-1 1990 14.2.7-2 1990 14.2.7-3 1990 14.2.7-4 1990 14.2.7-5 1990 14.2.7-6 1995 14.2 '-7 1995 14.2.7-8 1995 Table 14.2. 7-1 1995 Table 14.2.7-2 1995 Table 14.2.7-3 1995 Pig. 14.2.7-1 1982 Fig. 14.2.7-2 1982 Pig. 14.2.7-3 1987

Page 58 VOLUME VIE Chapter 14 Safet Anal sis Unit 1 Parcae Date Fig. 14.2.7-4 1987 Fig. 14.2.7-5 1982 Fig. 14.2.7-6 1982 Fig. 14.2.7-7 1982 Fig. 14.2.7-8 1982 Fige 14.2.7-9 1990 Fig. 14. 2. 7-10 1990 Fig. 14.2. 7-11 1990 Fig. 14 2. 7-12

~ 1990 14.2.8-1 1990 14.2.8-2 1990

. 14;2:8-3"-. 1990 14.2.8-4 1995 14.2.8-5 1995 14.2.8-6 1995 14.2.8-7 1990 Table 14.2.8-1 1990 Fig. 14.2. 8-1 1990 Fig. 14.2.8-2 1990 Fig. 14.2.8-3 1990 Fige 14.2.8-4 1990 Fig. 14.2.8-5 1990 Fig. 14.2.8-6 1990 Fig. 14.2.8-7 1990

14. 3. 1-1 1993 14.3. 1-2 1993 14 '.1-3 1993 14.3.1-4 1993 14.3.1-5 1993 14.3.1-6 1993 14.3, 1-7 1993 14.3.1-8 1993 14.3.1-9 1993 14.3. 1-10 1990 14.3. 1-11 1992

14. 3. 1-lla 1993

14. 3. 1-12 1993 14 3. 1-13

~ 1994 Table 14 3. 1-1 (pg 1)

~ 1994 Table 14.3.1-1 (pg 2) 1992 Table 14 3. 1-1 (pg 3)

~ 1990 Table 14. 3. 1-2 1990 Table 14 . 3 . 1-3 (2pp) 1990 Table 14.3. 1-4 1990 Table 14. 3. 1-5 1990 Table 14.3.1-6 1990 Fige 14. 3. 1-la 1990 Fig. 14. 3. 1-1b 1990 Fig. 14. 3. 1-1c 1990

Page 59 VOLUME VII Chapter 14 Safet Anal sis Unit 1 Pacae Date Fig. 14. 3. 1-1d 1990 Fig. 14.3. 1-le 1990 Fig. 14.3. 1" 1f 1990 Fig. 14.3. 1-1g 1990 Fig. 14.3.1-2a 1990 Fig. 14. 3. 1-2b 1990 Fig. 14.3.1-2c 1990 Fig. 14.3.1-2d 1990 Fig. 14.3. 1-2e 1990 Fig. 14. 3. 1-2f 1990 Fig-. ~ .14 3-1-2g- ~

1990 Fig. 14.3.1-3a 1990 Fig. 14.3.1-3b 1990 Fig. 14.3.1-3c 1990 Fig. 14. 3. 1-3d 1990 Fig. 14.3.1-3e 1990 Fig. 14.3.1-3f 1990 Fig. 14.3. 1-3g 1990 Pig. 14.3.1-4a 1990 Fig. 14 3 1-4b

~ ~ 1990 Fig. 14. 3. 1-4c 1990 Fig. 14 '.1-4d 1990 Fig. 14.3.1-4e 1990 Fige 14.3. 1-4f 1990 Fig. 14.3.1-4g 1990 Fig. 14.3. 1-Sa 1990 Pig. 14.3.1-5b 1990 Fig. 14.3.1-5c 1990 Fig. 14. 3. 1-5d 1990 Fig. 14.3.1-5e 1990 Fig. 14.3.1-5f 1990 Fig. 14. 3. 1-5g 1990 Fig. 14. 3 1-6a

~ 1990 Fig. 14. 3. 1-6b 1990 Fig. 14.3.1-6c 1990 Fig. 14. 3. 1-6d 1990 Fig. 14.3.1-6e 1990 Fig. 14.3.1-6f 1990 Fig. 14.3. 1-6g 1990 Pig. 14.3.1-7a 1990 Fig. 14.3.1-7b 1990 Fig. 14. 3. 1-7c 1990 Fig. 14.3.1-7d 1990 Fige 14.3. 1-7e 1990 Fig. 14.3.1-7f 1990 Fig. 14.3.1-7g 1990 Fig. 14.3.1-8a 1990 Pig. 14. 3 . 1-Bb 1990 Fig. 14.3.1-8c 1990

Page 60 VOLUME VII Chapter 14 Safet Anal sis Unit 1 Pacae Date Fig. 14. 3. 1-Bd 1990 Fig. 14. 3. 1-Be 1990 Fig. 14.3.1-8f 1990 Fig. 14.3. 1-Bg 1990 Fig. 14. 3. 1-9a 1990 Fig. 14.3.1-9b 1990 Fig. 14.3.1-9c 1990 Fig. 14 . 3 . 1-9d 1990 Fig. 14.3. 1-9e 1990 Fig. 14.3. 1-9f 1990 Pig. 14.3.1-9g 1990 Fig.: - 14.-3 ..1-10a- 1990.

Fig. 14. 3. 1-lob 1990 Fig. 14.3. 1-10c 1990 Pig. 14 3. 1-lod

~ 1990 Pig. 14. 3. 1-10e 1990 Fig. 14. 3. 1-10 f 1990 Pig. 14.3. 1-10g 1990 Fig. 14. 3. 1-lla 1990 Pig. 14.3. 1-lib 1990 Fige 14.3.1-11c 1990 Fig. 14. 3. 1-lid 1990 Fig. 14.3. 1-lie 1990 Fig. 14.3. 1" Fig. 14. 3. 1-llg llf 1990 1990 Fig. 14.3. 1-12a 1990 Fig. 14. 3. 1-12b 1990 Fig. 14.3.1-12c 1990 Fig. 14. 3. 1-12d 1990 Fig. 14.3.1-12e 1990 Fig. 14.3. 1-12f 1990 Fig. 14. 3. 1-12g 1990 Pig. 14. 3. 1-13a 1990 Fig. 14 3 1-13b

~ ~ 1990 Fig. 14. 3. 1-13c 1990 Fig. 14. 3. 1-13d 1990 Fige 14.3.1-13e 1990 Fig. 14.3.1-13f 1990 Fig. 14. 3. 1-13g 1990 Fig. 14 3. 1" 14

~ 1990 Fig. 14. 3. 1" 15 1990 Fig. 14. 3. 1-16 1990 Fig. 14.3. 1-17 1990 Fig. 14.3. 1-18 1990 Pig. 14.3.1-19 1990 Fig. 14. 3. 1990 Fig. 1-21 1-20'4.F 1990 Fig. 14.3. 1-22 1990 Fig. 14.3.1-23 1990

Page 61 VOLUME VII Chapter 14 Safet Anal sis Unit 1 Pacae Date 14.3.2-1 1990 14.3.2-2 1990 14.3.2"3 1990 14.3.2-4 1990 14.3.2-5 1990 14.3.2-6 1994 14.3.2-7 1995 14.3.2-7a 1995 14.3.2-7b 1995 14.3.2-7c 1995 14.3.2-7d 1995 "Table "14:3;2-1-- " 1990 Table 14.3.2-2 1990 Table 14.3.2-3 1994 Table 14.3.2-4 1990 Table 14.3.2-5 1990 Table 14.3.2-6 1990 Table 14.3.2-7 1994 Table 14.3.2-8 1995 Table 14.3.2-9 1995 Table 14.3.2-10 1995 Table 14. 3. 2-11 1995 Table 14. 3. 2-12 1995 Table 14.3.2-13 1995 Fig. 14.3. 2-1 1990 Fig. 14.3.2-2 1990 Fige 14.3.2-3 1990 Fig. 14.3.2-4 1990 Fig. 14.3.2-5 1990 Fig. 14.3.2-6 1990 Fig. 14.3.2-7 1990 Fig. 14 '.2-8 1990 Fig, 14.3.2-9 1990 Fige 14.3.2-10 1990 Fig. 14. 3.2-11 1990 Fig. 14.3.2-12 1990 Fig. 14 3. 2" 13

~ 1990 Fig. 14 '.2-14 1990 Fig, 14. 3. 2-15 1990 Fig, 14.3.2-16 1990 Fig. 14. 3. 2-17 1990 Fig. 14 3. 2-18

~ 1990 Fig. 14.3.2-19 1990 Fig. 14.3.2-20 1990.

Fig. 14.3.2-21 1990 Fig. 14.3.2-22 1990 Fig. 14.3.2-23 1990 Fig. 14.3.2-24 1990 Fig. 14.3.2-25 1990 Fig. 14.3.2-26 1990 Fig. 14.3.2-27 1990 Fige 14.3.2-28 1990

Page 62 VOLUME VIII Chapter 14 Safet Anal sis Unit 1 Pacae Date Fig. 14.3.2-29 1990 Fig. 14.3.2-30 1990 Fig. 14.3.2-31 1990 Fig. 14.3.2-32 1990 Fig. 14.3.2-33 1990 Fig. 14.3.2-34 1990 Fig. 14.3.2-35 1990 Fig. 14.3.2-36 1990 Fig. 14.3.2-37 1990 Fig. 14.3.2-38 1990 Fig. 14.3.2-39 1990 Fig-. 14;8;2-40" 1990'995 Fig. 14.3.2-41 Fig. 14.3.2-43 1995 Fige 14.3.2-44 1995 Fig. 14.3.2-45 1995 Fig. 14.3.2-46 1995 Fig. 14.3.2-47 1995 Fig. 14 '.2-48 1995 Fig. 14.3.2-49 1995 Fig. 14.3.2-50 1995 Fig. 14. 3. 2-51 1995 Fig. 14.3.2-52 1995 Fig. 14.3.2-53 1995 Fig. 14.3.2-54 1995 Fig. 14.3.2-55 1995 Fig. 14.3.2-56 1995 Fig. 14.3.2-57 1995 Fig. 14.3.2-58 1995 Fig. 14.3 '-59 1995 Fig. 14.3.2-60 1995 Fige 14. 3.2-61 1995 Fig. 14.3.2-62 1995 Fig. 14.3.2-63 1995 Fige 14.3.2-64 1995 Fig. 14.3.2-65 1995 Fig. 14.3.2-66 1995 14.3.3-1 1994 14.3.3-2 1994 14.3.3-3 1994 14.3.3-4 1994 14.3.3-5 1994 14.3.3-6 1994 14.3.3-7 1994 14.3.3-8 1994 14.3.3-9 1994

14. 3. 3-10 1994 14 3. 3-11

~ 1994

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

14. 3. 4-1 1992 14.3.4-2 1992 14 '.4-3 1992 14.3.4-4 1992 14.3.4-5 1992 14.3.4-6 1992 14.3.4-7 1992 14.3.4-8 1992 14.3.4-9 1992 14.3.4-10 1992 14.3.4-11 1992 14.3:4-12 1992" 14.3.4-13 1992 14.3.4-14 1992 14.3.4-15 1992 14.3.4-16 1992 14.3.4-17 1992 14.3.4-18 1992 14.3.4-19 1992 14.3.4-20 1992 14 3.4-21

~ 1992 14.3.4-22 1992 14.3.4-23 1992 14.3.4-24 1992 14.3.4-25 1992 14.3.4-26 1992 14.3.4-27 1992 14.3.4-28 1992 14.3.4-29 1992 14.3.4-30 1992 14.3.4-31 1992 14.3.4-32 1992 14.3.4-33 1992 14.3.4-34 1992 14.3.4-35 1992 14.3.4-36 1992 14.3.4-37 1992 14.3.4-38 1992 14.3.4-39 1992 14.3.4-40 1992 14.3.4-41 1992

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

Page 64 VOLUME VEII Chapter 14 Safet Anal sis Unit 1 Pacae Date 14.3.4-53 1992 14.3.4-54 1992 14.3.4-55 1992 14.3.4-56 1992 14.3.4-57 1992 14.3.4-58 1992 14.3.4-59 1992 14.3.4-60 1992

14. 3. 4-61 1992 14.3 '-62 1992 14 c.3;.4 ~ 1992" 14.3.4-64 1992 14.3.4-65 1992 14.3.4-66 1992 14.3.4-67 1992 14.3.4-68 1992 14.3.4-69 1992 14.3.4-70 1992 14.3.4-71 1992 14.3.4-72 1992 14 '.4-73 1992 14.3.4-74 1992 14.3.4-75 1992 14.3.4-76 1992 14.3.4-77 1992 14.3.4-78 1992 14.3.4-79 1992 14.3.4-80 1992 14.3.4-81 1992 14.3.4-82 1992 14.3.4-83 1992 14.3.4-84 1992 14.3.4-85 1992 Table 14.3.4-1 1992 Table 14.3.4-2 1992 Table 14.3.4-3 1992 Table 14.3.4-4 (2pp) 1992 Table 14.3.4-5 (2pp) 1992 Table 14.3.4-6 1992 Table 14.3.4-7 (2pp) 1992 Table 14.3.2-8 (2pp) 1992 Table 14.3.4-9 1992 Table 14.3.4-10 1992 Table 14. 3. 4-11 1992 Table 14 ~ 3.4-12 1992 Table 14. 3. 4-13 1992 Table 14.3.4-14 1992 Table 14.3.4-15 (2 pp) 1992 Table 14. 3. 4-16 (2 pp) 1992 Table 14.3.4-17 1992 Table 14. 3-4-18 1992 Table 14. 3. 4-19 1992 Table 14.3.4-20 1992 Table 14.3.4-21 (2pp) 1992 Table 14.3.4-22 1992 Table 14.3.4-23 1992 Table 14.3.4-24 1992

Page 65 VOLUME VIII Chapter 14 Safet Anal sis Unit 1 Pacae Date Table 14.3.4-25 (3pp) 1992 Table 14.3.4-26 1992 Table 14.3.4-27 (10pp) 1992 Table 14.3.4-28 1992 Table 14 '.4-29 (2pp) 1992 Table 14.3.4-30 1992 Table 14.3.4-31 (2pp) 1992 Table 14.3.4-32 (2pp) 1992 Table 14.3.4-33 (2pp) 1992 Table 14.3.4-34 (2pp) 1992 Table 14.3.4-35 (2pp) 1992 Table 14.3.4-36 (2pp) 1992 Table-'14.-3; 4-37 1992 Table 14.3.4-38 1992 Table 14.3.4-39 (2pp) 1992 Table 14.3.4-40 (2pp) 1992 Table 14.3.4-41 1992 Table 14.3.4-42 1992 Table 14.3.4-43 1992 Table 14.3.4-44 1992 Table 14.3.4-45 1992 Table 14.3.4-46 (2pp) 1992 Fig. 14.3.4-1 1992 Fig. 14.3.4-2 1992 Fig. 14.3.4-3 1992 Fig. 14.3.4-4 1992 Fig. 14.3 '-5

'-6 1992 Fig. 14.3 1992 Fig. 14.3.4-7 1992 Fig. 14.3.4-8 1992 Fig. 14.3.4-9 1992 Fig. 14. 3. 4-10 1992, Fig. 14.3.4-11 1992 Fig. 14. 3. 4-12 1992 Fig. 14.3.4-13 1992 Fig. 14.3.4-14 1992 Fig. 14.3 '-15 1992 Fig. 14.3.4-16 1992 Fig. 14.3.4-17 1992 Fig. 14.3.4" 18 1992 Fig. 14.3.4-19 1992 Fig. 14.3.4-20 1992 Fig. 14. 3.4-21 1992 Fig. 14.3.4-22 1992 Fig. 14.3.4-23 1992 Fig. 14.3.4-24 1992 Fig. 14.3.4-25 1992 Fig. 14.3.4-26 1992 Fig. 14.3.4-27 1992 Fig. 14.3.4-28 1992 Fig. 14.3.4-29 1992 Fig. 14.3.4-30 1992 Fig. 14.3.4-31 1992 Fig. 14.3.4-32 1992 Fig. 14.3.4-33 1992 Fig. 14.3.4-34 1992 Fig. 14.3.4-35 1992 Fig. 14.3.4-36 1992 Fig. 14.3.4-37 1992 Fig. 14.3.4-38 1992 Fig. 14.3.4-39 1992

Page 66 VOLUME VIZ?

Chapter 14 Safet Anal sis Unit 1 Pacae Date Fig. 14.3.4-40 1992 Fig. 14.3.4-41 1992 Fig. 14.3.4-42 1992 Fig. 14.3.4-43 1992 Fig. 14.3.4-44 1992 Fig. 14.3.4.45 1992 Fig. 14.3.4-46 1992 Fig. 14.3.4-47 1992 Fig. 14.3.4-48 1992 Fig. 14.3.4-49 1992 Fig. 14.3.4-50 1992 Fig-. 14.3 1992'992 Fig. 4-51.'4.3.4-52 Fig. 14.3.4-53 1992 Fig. 14.3.4-54 1992 Fig. 14.3.4-55 1992 Fig. 14.3.4-56 1992 Fig. 14.3.4-57 1992 Fig. 14.3.4-58 1992 Fig. 14.3.4-59 1992 Fig. 14.3.4-60 1992 Fig. 14.3.4-61 1992 Fig. 14.3.4-62 1992 Fig. 14.3.4-63 1992 Fig, 14.3.4-64 1992 Fig. 14.3.4-65 1992 Fig. 14.3.4-66 . 1992 Fig. 14.3.4-67 1992 Fig. 14.3.4-68 1992 Fige 14.3.4-69 1992 Fig. 14.3.4-70 1992 Fig. 14.3.4-71 1992 Fig. 14.3 '-72 1992 Fig. 14.3.4-73 1992 Fige 14.3.4-74 1992 Fig. 14 '.4-75 1992 Fig. 14.3.4-76 1992 Fig. 14.3.4-77 1992 Fig. 14.3.4-78 1992 Fige 14.3.4-79 1990 Fig. 14.3.4-80 1992 Fig. 14.3.4-81 1992 Fig. 14.3.4-82 1992 Fig. 14.3.4-83 1992 Fig. 14.3.4-84 1992 Fig: 14.3.4-85 1992 Fig. 14.3.4-86 1992 Fig. 14.3.4-87 1992 Fig. 14.3.4-88 1992 Fig. 14.3.4-89 1992 Fig. 14.3.4-90 1992 Fig. 14.3.4-91 1992 Fig. 14.3.4-92 1992 Fig. 14.3.4-93 1992

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

14. 3. 5" 1 1995 14.3.5-2 1982 14.3.5-3 1986 14.3.5-4 1982 14.3.5-5 1982 14.3.5-6 1982 14.3.5-7 1982 14.3.5-8 1982 14.3.5-9 1983

14. 3. 5-10 1982 14: 3:5-11'4.

1983

3. 5-12 1986

14. 3 . 5-13 1982

14. 3 . 5-14 1986

14. 3. 5-15 1982 14.3. 5-16 1982

14. 3. 5-17 1982

14. 3. 5-18 1983 14.3.5-19 1982 14.3.5-20 1982

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

Page 68 VOLUME IX Chapter 14 Safet Anal sis Unit 1 Pacae Date Table 14.3.5-9 pg 1 1995 pg 2 1995 pg 3 1995 Fig. 14.3. 5-1 1982 Fig. 14.3.5-2 1982 Fig. 14.3.5-3 1982 Fig. 14.3.5-4 1982 Fig. 14.3.5-5 1987 Fig. 14.3.5-6 1987 14.3.6-1 1989 14.3.6-2 1982 14 . 6-'3

~ 1991 14.3.6"4 1989 14.3.6-5 1982 14.3.6-6 1982 14.3.6-7 1982 14.3.6-8 1982 14 '.6-9 1982

14. 3. 6-10 1982

14. 3. 6-11 1990

14. 3. 6-12 1990 14.3.6-13 1990 14.3.6-14 1990

14. 3. 6-15 1990 14.3. 6" 16 1990

14. 3. 6-17 1990

14. 3. 6-18 1990 14.3.6-19 1990 14.3.6-20 1990 14.3.6-21 1990 14 '.6-22 1990 14 '.6-23 1990 14.3.6-24 1990 14.3.6-25 1990 14.3.6-26 1990 14.3.6-27 1991 14.3.6'-28 1990 14.3.6-29 1991 Table 14 3. 6-1

~ 1990 Table 14.3.6-2 1990 Table 14.3.6-3 1990 Table 14.3.6-4 1990 Table 14.3.6-5 1990 Table 14 '.6-6 1990 Table 14.3.6-7 1990 Table 14.3.6-8 1990

Page 69 VOLUME IX Chapter 14 Sachet Anal sis Unit 1 Pacae Date Table 14.3.6-9 1990 Table 14.3.6-10 1990 Table 14. 3. 6-11 1990 Table 14.3.6>>12 1990 Table 14.3.6-13 1990 Table 14 '.6-14 1990 Table 14.3.6-15 1990 Table 14. 3. 6-16 1990 Table 14.3. 6-17 (2pp) 1990 Fig. 14.3.6-1 1982 Fig. 14.3.6-2 1982 Fig:" 14;3.'6"6- 1990" Fig. 14.3.6-7 1990 Fig. 14.3.6-8 1990 Fig. 14.3.6-9 1990 Fig. 14.3.6-10 1990 Fig. 14. 3. 6-11 1990 Fig. 14. 3. 6-12 1990 Fig. 14.3.6-13 1990 Fig. 14.3.6-14 1990 Fig. 14.3.6-14A 1990 Fig. 14.3.6-15 1990 Fig. 14.3.6-16 1990 Fig. 14.3.6-17 1990 Fig. 14. 3. 6-18 1990 Fig. 14.3.6-19 1990 Fig. 14.3.6-20 1990 Fig. 14 3. 6-21

~ 1990 Fig. 14. 3 . 6-22 1990 14.3.7-1 1993 14.3.8-1 1993 14.4.1-1 1990 14.4.2-1 1987 14.4.2-2 1982 14.4.2-3 1982 14.4.2-4 1982 14.4.2-5 1982 14.4.2-6 1982 14.4.2-7 1982 14.4.2-8 1982 14.4.2-9 1982 14.4.2-10 1982 14.4.2-11 1982 14.4.2-12 1982

14. 4 . 2-13 1987 14.4.2-14 1982

Page 70 VOLUME IX Chapter 14 Safet Anal sis Unit 1 Pa<<ae Date 14.4.2-15 1982 14.4.2-16 1982 14.4.2-17 1982 14.4.2-18 1982

14. 4. 2-19 1982 14.4.2-20 1982

14. 4. 2-21 1982 14.4.2-22 1995 14.4.2-23 1982 14.4.2-24 1995 14.4.2-25 1982 14.4";2-26 1982 14.4.2-27 1982 14.4.2-28 1990 Table 14.4.2-1 (8pp) 1990 Table 14.4.2-2 1994 Table 14.4.2-3 1990 Table 14.4.2-4 1990 Table 14.4.2-5 (4pp) 1990 Fig. 14.4.2-1 1982 Fig. 14.4.2-2 1982 Fig. 14.4.2-3 1982 Fig. 14.4.2-4 1982 Fig. 14.4.2-5 1982 Fig. 14.4.2-6 1982 Fig. 14.4.2-7 1982 Fig. 14.4.2-8 1995 Fig. 14.4.2-9 1982 Fig. 14.4.2-10 1982 Fig. 14.4.2-11 1982 pig. 14.4.2-12 1982 Fig. 14.4 '-13 1982 Fig. 14.4.2-14 1982 pig. 14. 4. 2-15 1982 Fig. 14.4.2-16 1982 Fig. 14.4.2-17 1982 Fig. 14.4.2-18 1982 Fig. 14.4.2-19 1982 pig. 14.4.2-20 1982 Fige 14.4.2-20A 1995 Fig. 14.4 '-21 1982 14.4. 3-1 1990 14.4.3-2 1990 14.4.3-3 1993 14.4.3-4 1990 14.4.3-5 1990 14.4.4-1 1995 Table 14.4. 4-1 1990 Table 14.4.4-2 1990

Page 71 VOLUME IX Chapter 14 Safet Anal sis Unit 1 Pacae Date Table 14.4.4-3 1990 Table 14.4.4-4 (2pp) 1990 Table 14.4.4-5 (3pp) 1990 Table 14.4.4-6 1990 14.4.5-1 1990 14.4.5-2 1990

14. 4. 6-1 1994 14.4.6-2 1994 14.4.6-3 1994 14.4.6-4 1990 14.4.6-5 1993 14.4";6-6 1990 14.4.6-7 1993 Table 14.4.6-1 1990 Table 14.4.6-2 1990 Table 14.4.6-3 1993 Table 14.4.6-3a 1993 Table 14.4.6-4 1993 Table 14.4.6-4a 1993 Table 14.4.6-5 1993 Table 14.4.6-5a 1993 Table 14.4.6-6 1990 Table 14.4.6-6a (2pp) 1994 Table 14.4.6-6b (2pp) 1994 Table 14.4.6-6c (2pp) 1994 Table 14.4.6-7 1994 Table 14.4.6-8 1994 Table 14.4.6-9 1994 Table 14. 4. 6-10 1994 Table 14. 4. 6-11 1994 Table 14.4.6-12 1994 Table 14.4. 6-13 1994 Table 14.4.6-14 1994 Table 14.4. 6-15 1994 Table 14. 4. 6-15a 1994 Table 14.4. 6-16 1994 Table 14.4.6-16a 1994 Table 14.4.6-17 1994 Table 14.4. 6-18 (5pp) 1994 Table 14 4. 6-19

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

Page 72 VOLUME IX Chapter 14 Safet Anal sis Unit 1 Pacae Date Fig. 14.4. 6-10 1993 Fig. 14.4.6-10a 1993 Fig. 14.4.6-11 1993 Fig. 14.4. 6-11a 1992 14.4.7-1 1990 14.4.7-2 1990 14.4. 8-1 1990 14.4.9-1 1990 14.4.9-2 1990 14.4.9-3 1990 Fig. 14.4. 9-1 1982 Fig;- 14. 4. 9-2-- '- 1982 14.4. 10-1 1990 14.4. 10-2 1990 14.4.10-3 1990 14.4. 10-4 1990 Table 14.4. 10-1 1990 14.4. 11-1 1990

14. 4. 11-2 1990 14.4.11-3 1994 14.4. 11-4 1990

14. 4. 11-5 1990 14.4.11-6 1990

14. 4. 11-7 1990 Table 14.4.11-1 (pg 1) 1993 (pg 2) 1993 (pg 3) 1995 (pg 4) 1993 (pg 5) 1994 (pg 6) 1994 (pg 7) 1995 (pg 8) 1990 (pg 9) 1994 (pg 10) 1994 (pg 1993 Table 14.4.11-2 1994 Table 14. 4. 11-3 1990 Table 14.4.11-4 1990 Table 14.4.11-5 1990 Table 14.4.11-6 1990 Table 14. 4. 11-7 1990 Table 14. 4. 11-8 1990 Table 14. 4. 11-9 1992 14A-1 1992 14A-2 1982 14A-3 1982 14A-4 1982 14A-5 1982 14A-6 1982 14A-7 1982 14A-8 1982 14A-9 1982 14A-10 1982

Page 73 VOLUME IX Chapter 14 Safet Anal sis Unit 1 ~acae Date 14A-11 1982 14A-12 1992 14A-13 1992 14A-14 1992 14A-15 1992 14A-16 1993 14A-17 1993 14A-18 1992 14A-19 1992 14A-20 1992 14A-21 1992 14A-22 1992 14A-23 1992 14A-24 1992 14A-25 1992 14A-26 1992

14. G-1 1987 14.G-2 1987 14.G-3 1987 14.G-4 1987 14.G-5 1987

14. G-6 1987

14. G-7 1987 14.G-8 1987 14.G-9 1987 14.G-10 1987

14. G" 11 1987

14. G-12 1988 Table 14.G-1 1987 Table 14.G-2 1987 Table 14.G-3 1987 Fig. 14 . G-1 (3pp) 1988 Fig. 14.G-1 Notes 1988 Fig. 14.G-2 1987

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

14. 0-3. 1995 14.0-2 1995 14.0-3 1995 14.0-4 1995

14. 0-5 1995

14. 1-1 1993

14. 1-2 1995

14. 1-3 1995 14 r 1993*

1-5 1=4'4.

1993

14. 1-6 1995 14.1-7 1993 14.1-8 1995

14. 1-9 1995

14. 1-10 1995

14. 1-11 1995

14. 1-12 1995 14 1-13

~ 1995

14. 1-14 1995 Table 14.1.0-1 (pgl) 1993 Table 14. 1. 0-1 (pg2) 1993 Table 14.1.0-1 (pg3) 1995 Table 14. 1. 0-2 (3 pgs) 1995 Table 14.1.0-3 1993 Table 14. 1. 0-4 1993 Table 14.1. 0-5 (2 pgs) 1993 Table 14.1.0-6 (3 pgs) 1993 Fig. 14.1.0-1 1993 Fig. 14. 1 0-2 1993 Fig. 14. l. 0-3

~

1993 Fig. 14. 1. 0-4 1993 Fig. 14. 1. 0-5 1993 Fig. 14. 1. 0-6 1993 Fig. 14.1.0-7 1993

14. 1. 1-1 1993 14.1.1-2 1991

14. 1 1-3 ~ 1991

14. 1. 1-4 1991 14.1.1-5 1991

14. 1. 1-6 1991 14.1 Refe rences 1991 Table 14.1.1-1 1991 Fig. 14. 1. 1-1 1992

Page 75 VOLUME X Chapter 14 Safet Anal sis Unit 2 Pacae Date Fig. 14. 1. 1-2 1992

14. l. 2A-1 14.1.2A-2 1995 1995

14. 1. 2B-1 1991

14. 1.2B-2 1993

14. 1.2B" 3 1991

14. 1. 2B-4 1991

14. 1.2B-S 1991

14. 1. 2B-6 1991 14.1 2B-7

~ 1991 Fig . 14. 1.2B-.l 1991-,

Fig. 14. 1. 2B-2 1991 Fig. 14. 1. 2B-3 1991 Fig. 14. 1. 2B-4 1991 Fig. 14. 1.2B-5 1991 Fig. 14. 1. 2B-6 1991 Fig. 14 1. 2B-7

~ 1991 Fig. 14. 1.2B-B 1991 Fig. 14. 1. 2B-9 1991

14. 1. 3-1 1993 14.1.3-2 1991 14.1.3-3 1995 14.1.3-4 1995 14.1.3-5 1995

14. 1.3-6 1995

14. 1. 3-7 1995 Fig. 14. 1. 3-1 1991 Fig. 14". 1. 3-2 1991

14. l. 4-1 1991 14.1.5-1 1991

14. 1.5-2 1991 14.1.5-3 1991 l.

14. 5-4

14. 1. 5-5 1991 1991

Page 76 VOLUME X Chapter 14 Safet Anal sis Unit 2 Pacae Date

14. 1. 5-6 1991 14.1 14.1.6-1

'-7 1991 1991

14. 1. 6-2 1991 14 1. 6-3

~ 1991

14. 1. 6-4 1991 14.1.6-5 1991 14.1.6-6 1991 14.1.6-7 1991 14.. 1. 6-..8 -... 1991.

14. 1. 6-9 1991

14. 1.6-10 1991

14. 1. 6-11 1991 Table 14. 1. 6-1 1991 Table 14.1.6-2 1991 Fig. 14.1.6-1 1991 Fig. 14.1.6-2 1991 Fig. 14.1.6-3 1991 Fig. 14. 1. 6" 4 1991 Fig. 14.1.6-5 1991 Fig. 14. 1. 6-6 1991 Fig. 14. 1. 6-7 1991 Fig. 14.1.6-8 1991 Fig. 14.1.6-9 1991 Fig. 14. 1. 6-10 1991 Fig. 14. 1. 6-11 1991 Fig. 14. 1. 6-12 1991 14.1.7-1 1991

14. 1. 7-2 1991 l.

14. 7-3

14. 1. 7-4 1991 1991 Table 14. 1. 7-5 1991 Fig. 14. 1.7-1 1992 14 . 1. 8A-1 1995 14 . 1. BA-2 1995

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

14. 1. 8B-1 1991

14. 1. 8B-2 1991

14. 1. 8B-3 1995

14. 1. 8B-4 1995 14.1.8B-5 1993 14.1.8B-6 1991 Table 14.1.8B-1 (2pgs) 1995 Pig. .14.1 8B=1 ..(2pgs)...

~ 1995-Fig. 14. 1. 8B-2 1995 Pig. 14. 1. 8B-3 1995 Fig. 14. 1 . 8B-4 1995 Fig. 14.1.8B-S 1995 Fig. 14.1.8B-6 1995 Fig. 14.1.8B-7 1995 Fig. 14. 1. 8B-8 1995 Fige 14. 1. 8B-9 1995 Fig. 14. 1. 8B-10 1995 Pig. 14. 1. 8B-11 1995 Fig. 14. 1. 8B-12 1995 l.

14. 9-1 l.

14. 9<<2 1991 1991 14.1.9-3 1995

14. 1. 9-4 1995

14. 1.9-5 1991

14. 1. 9-6 1991 Table 14. 1. 9-1 1991 Fig. 14. 1. 9-1 1992 Pig. 14.1.9-2 1992 Fig. 14. 1. 9-3 1992

14. 1. 10A-1 1995

14. 1 10A-2

~ 1995

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

14. 1. 10B-1 1991

14. 1. 10B-2 1991

14. 1. 10B-3 1993

14. 1. 10B-4 1993 14.1.10B"5 1991 14.1.10B-6 1993

14. 1. 10B-7 1993

14. 1. 10B-8 1991

-14 . 1. 10B 9. 1991 Table 14. 1. 10B-1 1993 Table 14. 1. 10B-2 1993 Table 14. 1. 10B-3 1993 Table 14. 1. 10B-4 1993 Fig. 14. 1. 10B-1 1993 Fig. 14. 1. 10B-2 1993 Fig. 14. 1. 10B" 3 1993 Fig. 14. 1. 10B "4 1993 Fig. 14. 1. 10B-5 1993 Fig. 14.1.10B-6 1993 Fig. 14. 1. 10B-7 1993 Fig. 14.1.10B-8 1993

14. 1. 11A-1 1995

14. 1. 11A-2 1995

14. 1. 11B-1 1991

14. 1. 11B-2 1993

14. 1. 11B" 3 1991 14.1.11B-4 1991

14. 1. 11B-5 1991 Table 14. 1. 11B-1 1991 Fig. 14. 1. 11B-1 1991 l.

Fig. 14. 11B-2 1991

Page 79 VOLUME X Chapter 14 Safet Anal sis Unit 2 Pa<ac Date Fig. 14. 1. 11B-3 1991 Fig. 14. 1. 11B-4 1991 Fig. 14. 1. 11B-5 1991 Fig. 14. 1. 11B-6 1991 Fig. 14. 1. 11B-7 1991 Fig. 14. 1. 11B-8 1991

14. 1. 12-1 1991 14.1.12-2 1991 14.1.12-3 1995

14. 1. 12-4 1995 14.1-.12 1991 "

Table 14. 1. 12-1 1991 Fig. 14.1.12-1 1992 Fig. 14. 1. 12-2 1992

14. 1. 13-1 1991

14. 2-1 1995 14.2.1-1 1993 14.2.2-1 1993 14.2.2-2 1993 14.2.2-3 1993 14.2.2-4 1994 14.2.2-5 1991 Table 14.2.2-1 1991 Table 14.2.2-2 1993 Table 14.2.2-3 1993

14. 2. 3-1 1991 14 2.4-1

~ 1991 14.2.4-2 1991 14.2.4-3 1991 14.2.4-4 1991 14.2.4-5 1994 14.2.4-6 1991 14.2.4-7 1991 14.2.4-8 1991 14.2.4-9 1991 Table 14.2.4-1 1991 14.2.5-1 1991 14 '.5-2 1991 14.2.5-3 1991 14.2.5-4 1991 14.2.5-5 1991 14.2.5-6 1991 14.2.5-7 1991 14.2.5-8 1991 14.2.5-9 1991 14.2.5-10 1991

14. 2 5-11 1991 Table 14 '.5-1

~

1991 Table 14.2.5-2 (2pp) 1991 Fig. 14.2.5-1 1991

Page 80 VOLUME X Chapter 14 'Safet Anal sis Unit 2 Pacae Date Fig. 14.2 '-2 1991 Fig. 14.2.5-3 1992 Fig. 14.2.5-4 1992 Fig. 14.2.5-5 1991 Fig. 14.2.5-6 1991

14. 2 6-1

~ 1991 14.2.6-2 1991 14.2.6-3 1991 14.2.6-4 1991 14.2.6-5 1991 14.-2v6-6 -- ~

1991-14.2.6-7 1991 14.2.6-8 1991 14 '.6-9 1991

14. 2. 6-10 1991

14. 2. 6-11 1991 14.2.6-12 1991 14.2.6-13 1991 14.2.6-14 1991 14.2. 6-15 1991 14.2.6-16 1991

14. 2. 6-17 1991 Table 14.2. 6 "1 1991 Fig. 14.2. 6-1 1991 Fig. 14.2.6-2 1991 14 2. 7-1

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

Page 81 VOLUME X Chapter 14 Safet Anal sis Unit 2 Pacae Date 14.3.1-1 1995 14.3. 1-2 1991

14. 3. 1" 3 1991 14.3.1-4 1991 14.3.1-5 1991

14. 3. 1-6 1991 14.3.1-7 1991 14.3.1-8 1991 14.3.1-9 1993 14.3.;1-10-. 1993 14.3. 1-11 1995

14. 3. 1-12 1995

14. 3. 1-13 1995 14.3.1-14 1995

14. 3. 1-15 1991 14.3. 1-16 1991 14.3.1-17 1994 Table 14.3.1-1 (2pp) 1991 Table 14.3.1-2 1991 Table 14.3.1-3 1991 Table 14.3.1-4 (2pp) 1991 Table 14.3.1-5 1992 Table 14.3. 1-6 1994 Table 14.3.1-7 1992 Table 14.3.1-8 1992 Table 14.3.1-9 1992 Table 14. 3. 1-10 1992

14. 3 . 1-30 1995 14.3.1-31 1995 Fig o 14.3.1-1 1991 Fig. 14.3.1-2 1991 Fig. 14.3.1-3 1991 Fig. 14.3.1-4 1991 Fig. 14.3.1-5 1991 Fig. 14.3.1-6 1991 Fig. 14.3.1-7 1991 Fig. 14.3.1-8 1991 Fig. 14 3. 1-9

~ 1991 Fig. 14. 3. 1-10 1991 Fig. 14.3. 1-11 1991 Fig. 14. 3. 1-12 1991 Fig. 14.3. 1-13 1991 Fig. 14.3.1-14 1991 Fig. 14. 3. 1-15 1991 Fig. 14.3. 1-16 1991 Fig. 14.3. 1-17 1991 Fig. 14. 3. 1-18 1991 Fig. 14. 3. 1-19 1991 Fig. 14. 3. 1-20 1991 Fig. 14. 3. 1-21 1991

Page 82 VOLUME XI Chapter 14 Safet Anal sis Unit 2 Pacae Date Fig. 14. 3. 1-22 1991 Fig. 14.3.1-23 1991

'Fig. 14. 3. 1-24 1991 Fig. 14. 3. 1-25 1991 Fig. 14. 3. 1-26 1991 Fig. 14. 3 . 1-27 1991 Fig. 14.3.1-28 1991 Fig. 14.3.1-29 1991 Fig. 14.3.1-30 1991 14 . 3~1 1991 14.3.1-25 1991

14. 3. 1-26 1991 14.3. 1" 27 1991 14.3.1-28 1991 14.3.1-29 1991 14.3.1-'30 1995 14.3.1-31 1995 14.3. 2-1 1991 14.3.2"2 1991 14.3.2-3 1991 14.3.2-4 1991 14.3.2-5 1991 14.3.2-6 1991 14.3.2-7 1992 14.3.2-7a 1995 14.3.2-7b 1995 14.3.2-7c 1995 14.3.2-8 1994 Table 14.3.2-1 1991 Table 14.3.2-2 1991 Table 14.3.2-3 1992 Table 14.3.2"4 1994 Table 14.3.2-5 1991 Table 14.3.2-6 1991 Table 14.3.2-7 1992 Table 14.3.2-8 1994 Table 14.3.2-9 1991 Table 14. 3. 2-10 1995 Table 14. 3. 2-11 1995 Table 14.3.2-12 1995 Table 14.3.2-13 1995

Page 83 VOLUME XI Chapter 14 Safet Anal sis Unit 2 Pacae Date Fig. 14.3.2-1 1991 Fig. 14.3.2"2 1991 Fig. 14.3.2-3 1991 Fig. 14.3.2-4 1991 Fig. 14.3.2-5 1991 Fig. 14.3.2-6 1991 Fig. 14.3.2-7 1991 Fig. '4.3.2-8 1991 Fig. -14.3.2 1991 Fig. 14. 3. 2" 10 1991 Fig. 14. 3. 2-11 1991 Fig. 14.3.2-12 1991 Fig. 14.3.2-13 1991 Fig. 14.3.2-14 1991 Fig. 14.3.2-15 1991 Fig. 14.3.2-16 1991 Fig. 14. 3. 2-17 1991 Pig. 14 '.2-18 1991 Fig. 14.3.2-19 1991 Fig. 14.3.2"20 1991 Fig. 14.3.2 "21 1991 Fig. 14.3.2-22 1991 Fig. 14.3.2-23 1991 Fig. 14.3.2-24 1991 Fig. 14.3.2-25 1991 Fig. 14.3.2-26 1991 Fig. 14.3.2-27 1991 Fig. 14.3.2-28 1991 Fig. 14.3.2-29 1991 Fig. 14.3.2-30 1991 Fig. 14.3.2-31 1991 Fig. 14.3.2-32 1991 Fig. 14.3.2-33 1991 Fig. 14.3.2-34 1991 Fig. 14.3.2-35 1991 Fig. 14.3.2-36 1991 Pig. 14.3.2-37 1991 Fig. 14.3.2-38 1991 Pig. 14.3.2-39 1991 Fig. 14.3.2-40 1991 Fig. 14.3.2-41 1991 Fig. 14.3.2-42 1991 Fig. 14.3.2-43 1991 Fig. 14.3.2-44 1991 Pig. 14.3.2-45 1991 Fig. 14.3.2-46 1991 Fig. 14.3.2-47 1991 Fig. 14.3.2-48 1991 Fig. 14.3.2-49 1991

Page 84 VOLUME XI Chapter 14 Safet Anal sis Unit 2 Pacae Date Fig. 14.3.2-50 1991 Fig. 14.3.2-51 1991 Fig. 14.3.2-52 1991 Fig. 14.3.2-53 1991 Fig. 14.3.2-54 1991 Fige 14.3.2-55 1991 Fige 14.3.2-56 1991 Fig. 14.3.2-57 1991 Fig. 14.3.2-58 1991 Fige 14.3.2-59 1991 Figi -14.3.2-60 1995 Fig. 14. 3 . 2-61 1995 Fig. 14.3.2-62 1995 Fig. 14.3.2-63 1995 Fig. 14.3.2-64 1995 Fig. 14.3.2-65 1995 Fig. 14.3.2-66 1995 Fig. 14 '.2-67 1995 Fig. 14.3.2-68 1995 Fig. 14.3.2-69 1995 Fig. 14.3.2-70 1995 Fig. 14.3.2-71 1995 Fig. 14.3.2-72 1995 Fig. 14.3.2-73 1995 Fig. 14.3.2-74 1995 Fig. 14.3.2-75 1995 Fig. 14.3.2-76 1995 14.3.3-1 1994 14.3.3-2 1995 14.3.3-3 1994 14.3.3-4 1995 14.3.3-5 1994 14.3.3-6 1994 14.3.3-7 1994 14.3.3-8 1994 14.3.3-9 1994 14.3.3-10 1994

14. 3. 3-11 1994

14. 3. 3-12 1994 14.3.3-13 1994 Fig. 14.3.3-1 1994 Fig. 14.3.3-2 1994 Fig. 14.3.3-3 1994 Fig. 14.3.3-4 1994

Page 85 VOLUME XII Chapter 14 Safet Anal sis Unit 2 Pacae Date Fig. 14.3.3-5 1994 Fig. 14.3.3-6 1994 Fig. 14.3.3-7 1994 Fig. 14.3.3-8 1994 14.3.4-1 1992 14.3.5-1 1993 14.3.5-2 1993 14.3.5-3 1993 14.3.5-4 1993 Table- 14.3 5-1. 1993 Table 14.3.5-2 1993 Table 14.3.5-3 1993 Table 14.3.5-4 1993 Table 14.3.5-5 (3 pp) 1993 Table 14.3.5-6 1993

14. 3. 6-1 1990 14.3.7-1 1993 14.3.7-2 1993 14.3.7-3 1993 14.3.7-4 1993 14.3 '-5 14.3.7-6 1993 1993 14.3.7-7 1993 14.3.7-8 1993 14.3 '-9 1993 14.3.7-10 1993

14. 3. 7-11 1993 Fig. 14.3.7-1 1982 Fig. 14.3.7-2 1982 Fig. 14 '.7-3 1982 Fig. 14.3.7-4 1982 Fig. 14.3.7-5 1982 Fig. 14.3.7-6 1982 Fig. 14.3.7-7 1982 Fig. 14.3.7-8 1982 Fig. 14.3.7-9 1982 Fig. 14.3.7-10 1982 Fig. 14.3. 7-11 1982 Fig. 14.3.7-12 1982 Fig. 14.3.7-13 1982 Fig. 14. 3. 7-14 1982 Fig. 14.3.7-15 1985 Fig. 14.3. 7-16 1982 Fig. 14.3.7-17. 1982 Fig. 14. 3. 7-18 1985 Fig. 14.3. 7-19 1982 Fig. 14.3.7-20 1982 14.3.8-1 1993 14.3.8-2 1993 14.3.8-3 1993 14.3.8-4 1993 Fig. 14. 3. 8-1 1982 Fig. 14.3.8-2 1982 Fig. 14.3.8-3 1982 14.4-1 1991 14.A-1 1989

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

Page 87 VOLUME XIII Chapter 14 Safet Anal sis Pacae Date Appendix M ORIG

CHAPTER 2 LIST OF TABLES 2.1-1 Population Trends of the Counties Surrounding the Donald C. Cook Nuclear Plant Site 2 1 2

~ Population Trends of Cities and Townships in Berrien County, Michigan 2.1-3 Population Centers of 25,000 or More Within 60 Miles of the Donald C. Cook Nuclear Plant Site 2.1-4 DELETED 2.1-5 Population Distribution, 1975 2.1-6 Population Distribution, 1990 2.1-6a Population Distribution, 1990 2.1-7 Projected Population Distribution, 2000 2.1-7a Projected Population Distribution, 2000 2.1-8 Projected Population Distribution, 2037 2.1-8a Projected Population Distribution, 2037 2.1-8b Transient Population Distribution, 1 Mile Increments, 1971 2.1-9 Agricultural Statistics 2.1-10 Principal Industries (1992) 2.1-11 School Population 2.1-12 Hospitals in Berrien County, 1993 2.2-1 Data Summary Sheet 2.2-2 Meteorological Data 2.2-3 Z/Q Ground Average 2.2-4 Hours at Each Wind Speed and Direction, S tab ility Class: A 2.2-5 Hours at Each Wind Speed and Direction, S tab ility Class: B 2.2-6 Hours at Each Wind Speed and Direction, Stability Class: C 2~2 7 Hours at Each Wind Speed and Direction, Stability Class: D 2.2-8 Hours at Each Wind Speed and Direction, Stability Class: E 2.2-9 Hours at Each Wind Speed and Direction, Stability Class: F July 1995

CHAPTER 2 LIST OF TABLES (Cont'd) 2.2-10 Deleted 2.2-11 Deleted 2.2-12 Deleted 2.2-13 Deleted 2.2-14 Deleted 2.2-15 Deleted 2.2-16 Deleted 2.2-17 Deleted 2.2-18 Deleted 2.2-19 Deleted 2.2-20 Deleted 2.2-21 Deleted 2.2-22 Deleted 2.2-23 Deleted 2.2-24 Deleted 2.2-25 Deleted 2.2-26 Deleted 2.2-27 Deleted 2.2-28 Deleted 2.2-29 Deleted 2.2-30 Deleted 2.2-31 Deleted 2.2-32 Deleted 2.2-33 Deleted 2.5-1 Earthquakes with Epicenters Located Within 200 Miles of Plant Site 2.6-1 Bibliography of Reports Produced as Part of Initial Phase of Donald C. Cook Nuclear Plant Environmental Impact Assessment 2.6-2 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

SUMMARY

DESCRIPTION 3.1-1 3.1.1 Performance Obj ectives 3.1-2 3.1.2 Principal Design Criteria 3.1-4 3.1.3 Safety Limits 3.1-11 3.2 MECHANICAL DESIGN 3.2-1 3.2.1 Mechanical Design and Evaluation 3.2-1 3.2.1 References 3 '-54 3.2.2 Core Component Tests and Inspections 3.2-44 3.3 NUCLEAR DESIGN 3.3-1 3.3.1 Nuclear Design and Evaluation 3.3-1 3.3.2 Physics Tests 3.3-24 3.3.3 Anticipated Transients Without Trip 3.3-25 3.3 ' Criticality of Fuel Assemblies 3.3-25 3.3.1 References 3.3-26 3.3.2 References 3.3-26 3.3.3 References 3.3-27 3.4 THEBMAL AND HYDRAULIC DESIGN 3.4-1 3.4.1 Thermal and Hydraulic Evaluation for the Initial Core 3.4-1 3 '.2 Thermal and Hydraulic Tests and Inspections 3.4-17 3.4 References 3.4-18 3.4.2 References 3.4-21 4

UNIT 1 3-i July 1995

CHAPTER 3 TABLE OF CONTENTS (Cont'd)

Section Title ~Pa e 3.5 CURRENT WESTINGHOUSE OFA RELOAD FUEL 3.5-1 3.5.1 Fuel Mechanical Design 3.5.1-1 3.5 & 3.5.1 References 3.5.1-17 3.5.2 Nuclear Design 3.5.2-1 3.5.2 References ~ 3.5.2-6 3.5.3 Thermal and Hydraulic Design 3.5.3>>1 3.5.3 References 3.5.3-13 UNIT 1 3-ii July 199

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

CHAPTER 3 LIST OF FIGURES

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

3.3.1-11 Distribution of Burnable Poison Rods - Number of B.P.

Rods per Assembly, Unit 1, Cycle 1 3.3.1-12 Arrangement of Burnable Poison Rods Within an Assembly, Unit 1, Cycle 1 3.3.1-13 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 Title 3.3.1-14 Moderator Temperature Coefficient vs. Moderator Temperature, BOL, All Control Rods Inserted 3.3.1-15 Moderator Temperature Coefficient vs. Moderator Temperature, (EOL) 3.3.1-16 Doppler Coefficient vs. Resonance Effective Temperature 3.3.1-17 Doppler Contributions to the Power Coefficient vs.Power Level 3.4.1-1 Thermal Conductivity of U02 (Data Corrected to 95 Percent Theoretical Density) 3.4.1-2 High Power Fuel Rod Experimental Program 3.4.1-3 Comparison of W-3 Prediction and Uniform Flux Data 3.4.1-4 W-3 Correlation Probability Distribution Curve 3.4.1-4a Rod Control Cluster Assembly Outline 3.4,1-5 Comparison of W-3 Correlation With Rod Bundle DNB Data (Simple Grid Without Mixing Vane) 3.4.1-6 Compaiison of W-3 Correlation with Rod Bundle DNB Data (Simple Grid With Mixing Vane) 3.4.1-7 Comparison of Non-Uniform DNB Data With W-3 Predictions 3.4.1-8 Comparison of W-3 Prediction With Measured DNB Location 3.4.1-9 Radial Power Distribution 3.5.1-1 Schematic Comparison of Westinghouse 15x15 OFA With ENC Fuel Assembly Dimensions 3.5.1-2 Reactor Core Fuel Assembly Reload Pattern 3.5.1-3 Plan View of Mid Grid to Guide Thimble Joint (Bottom View) 3.5.1-4 Elevation View of Mid Grid to Guide Thimble Joint 3.5.1-5 Top Grid to Guide Thimble and Top Nozzle Attachment 3.5.1-5a 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 Guide Thimble to Bottom Grid and Nozzle Joint 3.5.1-7 Bottom Nozzle to Thimble Tube Connection 3.5.1-8 Deleted 3.5.1-9 Deleted 3.5.2-1 Cook Nuclear Plant Unit 1 - Cycle 14 Example Core Loading Pattern 3.5.2-2 Heat Flux Hot Channel Factor Normalized Operating Env'elope,

+ ECCS Limit - 2.15 Cook Nuclear Plant Unit 1 - Cycle 14 3.5.3-1 Measured vs. Predicted Critical Heat Flux - RE 1 Correlation 3.5.3-2 TDC vs Reynoids Number for 26" Grid Spacing 3.5.3-3 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

SUMMARY

DESCRIPTION 3.1-1 3.1.1 References 3.1-5 3.2 MECHANICAL DESIGN 3 ' 1 3.2.1 Fuel 3.2-2 3.2.2 Reactor Vessel Internals 3.2-36 3.2.3 Reactivity Control System 3.2-47 3.2 References 3.2-92 3.3 NUCLEAR DESIGN 3.3-1 3.3.1 Design Bases 3.3-1 3.3.2 Description 3.3-9 3.3.3 Analytical Methods 3 ~ 3 55 3.3 References 3.3-59 3.4 THERMAL AND HYDRAULIC DESIGN 3.4-1 3.4.1 Design Bases 3.4-1 UNIT 2 3-i July 1995

CHAPTER 3 TABLE OF CONTENTS (Cont'd)

Section Title ~Pa e 3.4.2 Description 3.4-5 3.4.3 Evaluation 3.4-33 3.4.4 Testing and Verification 3.4-53 3.4.5 Instrumentation Application 3.4-54 3.4 References 3.4-57 3.5 ANF FUEL DESIGN 3.5-1 3.5.1 Fuel and Mechanical Design 3.5-1 References 3.5-20 3.5.2 Thermal-Hydraulic Design 3.5-26 References 3.5-28 UNIT 2 3-ii July 199

CHAPTER 3 LIST OF FIGURES (Cont'd)

~Fl ure Title 3.4-7 Void Fraction Versus Thermodynamic Quality H-HSTAT/Hg-HSAT 3.4-8 100 Percent Power Shapes Evaluated at Conditions Representative of Loss of Flow All Shapes Evaluated with FNH 1 59

~

3.4-9 PWR Natural Circulation Test 3.4-10 Comparison of a Representative W Two-Loop Reactor Incore Thermocouple Measurements with THING-IV Predictions 3.4-11 Comparison of a Representative W Three-Loop Reactor Incore Thermocouple Measurements with THING-IV Predictions 3.4-12 Hanford Subchannel Temperature Data Comparison with THING-IV 3.4-13 Hanford Subcritical Temperature Data Comparison with THING-IV 3.4-14 Distribution of Incore Instrumentation 3.5.1-1 Fuel Bundle Assembly 3.5.1-2 Fuel Bundle Assembly 3.5.1-3 Bundle Overall Pressure Drop 3,5.1-4 Rod Bow for ENC 17xl7 Fuel UNIT 2 3-vii July 1995

CHAPTER 3 TABLE OF CONTENTS 3.0 3.1-1 3.1

SUMMARY

DESCRIPTION 3.1-1 3.1.1 Performance Ob)ectives 3.1-2 3.1.2 Principal Design Criteria 3.1-4 3.1.3 Safety Limits 3.1-11 3.2 MECHANICAL DESIGN 3.2-1 3.2.1 Mechanical Design <<nd Evaluation 3.2-1 3.2.1 References 3.2-54 3.2.2 Core Component Tests and Inspections 3.2-44 3.3 NUCLEAR DESIGN 3.3-1 3.3.1 Nuclear Design and Evaluation 3.3-1 3.3.2 Physics Tests 3.3-24 3.3.3 Anticipated Transients without Trip 3 ~ 3~25 3.3.4 Criticality of Fuel Assemblies 3.3-25 3.3.1 References 3.3-26 3.3.2 References 3.3-26 3.3.3 References 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 Thermal and Hydraulic Tests and Inspections 3.4-17 3.4 References 3.4-18 3.4.2 References 3.4-21 UNIT 1 3-i July 1995

CHAPTER 3 TABLE OF CONTENTS (Cont'd) 3.5 CURRENT MESTINGHOUSE OFA RELOAD FUEL 3.5-]

3.5.1 Fuel Hechanical Design 3.5.1-1 3.5 & 3.5.1 References 3.5.1-34 3.5.2 Nuclear Design 3.5.2-1 3.5.2 References 3.5.2-6 3.5.3 Thermal and Hydraulic Design 3.5.3-1 3.5.3 References 3.5.3-13 UNIT 1 3-ii July 1996

CHAPTER 3 LIST OF TABLES 3.2.1-1 Initial Core Hechanical Design Parameters 3.2.2-1 Thermal and Hydraulic Design Parameters 3.3 l-l Nuclear Design Data 3.3.1-2 Reactivity Requirements for Control Rods 3 3

~ ~ 1-3 Calculated Rod Worths, dp (Unit gl) 3.4.1-1 Thermal and Hydraulic Design Parameters 3.4.' 2 Engineering Hot Channel Factors 3.4.1-3 Sensitivity Analysis 3.5.1-1 Westinghouse 15 x 15 OFA Design Parameters 3.5.1-2 Comparison of Burnable Absorber Rods Design Parameters 3.5.2-1 Fuel Assembly Design Parameters, Cook Nuclear P'nt-Unit 1, Cycle 15 3.5 '-2 Kinetics Characteristics, Cook Nuclear Plant Unit 1 With Mestinghouse OFA Fuel 3.5.2-3 Shutdown Requirements and Margins, Cook Nuclear Plant Unit 1 - Cycle 15 3.5.3-1 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 Core Cross Section 3.2.1-2 Reactor Vessel and Internals 3.2.1-3 Fuel Loading Arrangement 3.2.1<<4 Typical ".od Cluster Control Assembly 3.2.1-5 Core Barrel Assembly 3.2.1-6 Upper Core Support Structure 3.2.1-7 Guide Tube Assembly 3.2.1-8 Fuel Assembly and Control Cluster Cross Section 3.2.1-9 Fuel Assembly Outline 3.c.1-10 Spring Clip Grid Assembly 3.2.1-11 Neutron Source Locations 3.2.1-12 Burnable Poison 3.2.1-13 Control Rod Drive Mechanism Assembly 3.2.1-14 Control Rod Drive Mechanism Schematic 3 '.1-15 Thimble Plug Assembly 3.3.1-1 Control Rod Pattern (Unit 1) 3.3.1-2 Cycle 1 Assemblywise Power (BOL) 3.3.1-3 Cycle 1 Assemblywise Power (MOL) 3.3,1-4 Cycle 1 Assemblywise Power (EOL) 3~3 L 5 to 3.3.1-10 These figures have been intentionally deleted.

3.3.1-11 Distribution of Burnable Poison Rods - Number of B.P.

Rods per Assembly, Unit 1, Cycle 1 3 '.1-12 Arrangement of Burnable Poison Rods Withi.n an Assembly, Unit 1, Cycle 1 3.3.1-13 Moderator Temperature Coefficient vs. Moderator Temperature, BOL, No Control Rods Inserted UNIT 1 3-iv July 1996

CHAPTER 3 LIST OF FIGURES (Cont'd)

XirLa 3.3.1-14 Moderator Temperature Coefficient vs. Moderator Temperature, BOL, All Control Rods Inserted 3.3.1-15 Moderator Temperature Coefficient vs. Moderator Temperature, (EOL) 3.3. 1-16 Doppler Coefficient vs. Resonance Effective Temperature 3.3.1-17 Doppler Contributions to the Power Coefficient vs.Power Level 3.4. 1-1 Thermal Conductivity of U02 (Data Corrected to 95 Percent Theoretical Density) 3.4.1-2 High Power Fuel Rod Experimental Program 3.4.1-3 Comparison of W-3 Prediction and Uniform Flux Data 3,4.1-4 W-3 Correlation Probability Distribution Curve 3.4.1-4a Rod Control Cluster Assembly Outline 3.4.1-5 Comparison of W-3 Correlation With Rod Bundle DNB Data (Simple Grid Without Mixing, Vane) 3.4.1-6 Comparison of W-3 Correlation with Rod Bundle DNB Data (Simple Grid With Mixing Vane) 3.4.1-7 Comparison of Non-Uniform DNB Data With W-3 Predictions A

3.4.1-8 Comparison of W-3 Prediction With Measured DNB Location 3.4.1-9 Radial Power Distribution 3.5.1-1 Schematic Comparison of Westinghouse 15x15 OFA With ENC Fuel Assembly Dimensions 3.5.1-2 Reactor Core Fuel Assembly Reload Pattern 3.5.1-3 Plan View of Mid Grid to Guide Thimble Joint (Bottom View) 3.5.1-4 Elevation View of Mid Grid to Guide Thimble Joint 3.5.1-5 Top Grid to Guide Thimble and Top Nozrle Attachment 3.5.1-5a 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 Guide Thimble to Bottom Grid and Nozzle Joint 3.5.1-7 Bottom Nozzle to Thimble Tube Connection 3.5.1-8 Met Annular Burnable Absorber Rod 3.5.1-9 Comparison of Borosilicate Glass Absorber Rod Mith MABA Rod 3.5.2-1 Cook Nuclear Plant Unit 1 - Cycle 15 Example Core Loading Pattern 3.5.2-2 Heat Flux Hot Channel Factor Normalized Operating Envelope, FQ ECCS Limit - 2.15 Cook Nuclear Plant Unit 1 - Cycle 14 3.5.3-1 Measured vs. Predicted Critical Heat Flux - WRB 1 Correlation 3.5.3 2 TDC vs Reynoids Number for 26" Grid Spacing 3.5.3-3 Improved Thermal Design Procedure Illustration UNIT 1 3-vi July 1996

CHAPTER 3 TABLE OF CONTENTS 3.0 3.1-1 3.1 SURGERY DESCRIPTION 3.1.1 3.1-1 References 3.1-5 3.2 MECHANICAL DESIGN 3,2.1 3.2-1 Fuel 3~2 2 3.2.2 Reactor Vessel Internals 3.2.3 3.2-36 Reactivity Control Systeo 3.2-47 3.2 References 32-92 3.3 NUCLEAR DESIGN 3.3.1 3.3-1 Design Bases 3.3.2 3.3-1 Description 3.3.3 3.3-9 Analytical methods 3.3 3.3-55 References 3.3-59 3.4 'QKiRAL hND HYDRAULIC DESIGN 3.4.1 3.4-1 Design Bases 3.4-1 VNIT 2 3-i July 1995

CHAPTER 3 ThBLE OF CONTENTS (Cont'd)

P~a 3.4.2 Description 3.4-5 3.4.3 Evaluation 3.4-33 3.4.4 Testing and Verification 3.4-53 3.4.5 Instrumentation Application 3.4-54 3.4 References 3.4-57 3'. 5 ANF FUEL DESIGN DELETED 3.5-1 3.5.1 Fuel and Mechanical Design (DELETED) 3.5-1 3.5,2 Thermal. Hydraulic Design (DELETED) 3 '-2 UNIT 2 3-ii July 1996

CHAPTER 3 LIST OF FICURES (Cont'd) 3.4-7 Void Fraction Versus Thermodynamic Quality H-HSTAT/Hg-HSAT 3.4-8 100 Percent Power Shapes Evaluated at Conditions Representative of Loss of Flow All Shapes Evaluated with FNH 1.59 3.4-9 PWR Natural Circulation Test 3,4-10 Comparison of a Representative Q Two-Loop Reactor Incore Thermocouple Measurements with THINC-IV Predictions 3.4>>11 Comparison of a Representative g Three-Loop Reactor Incore Thermocouple Heasurements with THINC-IV Predictions 3.4-12 Hanford Subchannel Temperature Data Comparison with THINC-IV 3.4-13 Hanford Subcritical Temperature Data Comparison with THINC-IV 3.4-14 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 Title 4.1-1 System Design and Operating Parameters 4.1-2 Reactor Coolant Syst: em Design Pressure Settings 4.1-3 Reactor Vessel Design Data 4.1-4 Pressurizer and Pressurizer Relief Tank Design Data 4.1-5 Steam Generator Design Data 4.1-6 Reactor Coolant Pumps Design Data 4.1-7 Reactor Coolant Piping Design Parameters 4.1-8 Pressurizer Valves Design Parameters 4.1-9 Reactor Coolant System Design Pressure Drop 4.1-10 Design Thermal and Loading Cycles 4.1-11 Summary of Plant Outage for Yankee-Rowe (1964 to 1969) 4.1-12 Reactor Coolant System Codes 4.2-1 Materials of Construction of the Reactor Coolant System Components 4.2-2 Reactor Coolant Water Chemistry Specification 4.2-3 Steam Generator Water (Steam-Side) Chemistry Specification for 100X Full Power 4.3-1 Summary of Estimated Primary Plus Secondary Stress Intensity for Components of the Reactor Vessel (Unit 1) 4.3-2 Summary of Estimated Cumulative Fatigue Usage Factors for Components of the Reactor Vessel (Unit 1) 4.3-3 Unit 1 Design Tube Sheet Stresses Due to Maximum Steam Generator Tube Sheet Pressure Differential (2485 psig).

4.3-4 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 ~Ttle 4.3-5 51,500 Sq. Ft. Steam Generator Usage Factors (Individual Transients) Primary and Secondary Boundary Components 4.3-6 51,500 Sq. Ft. Steam Generator Usage Factors (Individual Transient) Center of Tube Sheet 4.3-7 Tube Sheet Stress Analysis Results for 51,500 Sq. Ft.

Steam Generators 4.3-8 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 Title 4.2-1 Reactor Coolant System Flow Diagram Sheet 1

4. 2-1A Reactor Coolant System Flow Diagram Sheet 2 4.2-2 Reactor Vessel Schematic 4.2-2A Reactor Vessel Schematic 4.2-3 Pressurizer 4.2-4 Series 51 Steam Generator 4.2-4A Repaired Steam Generator General Arrangement-Model 51F Steam Generator 4.2-5 Reactor Coolant Pump 4.2-6 Reactor Coolant Pump Flywheel 4.2-7 Flywheel Characteristics Curve 4.2-8 Reactor Coolant Pump Performance Characteristics 4.2-9 Radiation Induced Increase in Transition Temperature for Mn-Mo Steel 4.3-1 Reactor Vessel Stress Analysis: Areas Examined 4.3-2 Reactor Vessel Stress Analysis: Details - Upper 4.3-3 Reactor Vessel Stress Analysis: Details - Lower 4.3-4 Primary.- Secondary Boundary Components Shell Locations of Stress Investigations 4.3-5 Primary and Secondary Hydrostatic Test Stress History for the Center Hole Location 4.3-6 Plant Heatup and Loading Operational Transients (with Steady-State Plateau) Stress History for the Hot Side Center Hole Location 4,3-7 Large Step Load Decrease and Loss of Flow Stress History for the Hot Side Center Hole Location 4.5-1 Surveillance Capsule Elevation View 4.5-2 Surveillance Capsule Plan View 4.5-3 Specimen Guide to Thermal Shield Attachment 4-v July 1995

CHAPTER 7 LIST OF TABLES Table Title 7.2-1 List of Reactor Trips and Actuation Means of:

Engineered Safety Features, Containment and Steam Line Isolation and Auxiliary Feedwater 7.2-2 Interlock Circuits 7.2-3 Rod Stops 7.2-4 Symbols and Abbreviations 7 '-5 . Process Control Block Diagram Drawing 108D087 Index 7.5-1 Process Instrumentation For RPS and ESF Actuation 7.5-2 Engineered Safety Features Equipment Exposed to Harsh Environment 7.8-1 Type "A" Variables Provided the Operator for Manual Functions During and Following an Accident 7.8-2 Type "B" Variables Provided the Operator for Manual Functions During and Following an Accident 7.8-3 Type "C" Variables Provided the Operator for Manual Funct'ions During and Following an Accident 7.8-4 Type "D" Variables Provided the Operator for Manual Functions During and Following an Accident 7.8-5 Type "E" Variables Provided the Operator for Manual Functions During and Following an Accident 7-iii July 1995

CHAPTER 7 LIST OF FIGURES

~Fi ure Title 702-2 Reactor Protection Systems 7.2-3 Control Rod Bank Insertion Monitor 7.2-4 Rod Deviation Comparator 7.2-5 Pressurizer Pressure Protection System 7.2-6 Pressurizer Level Protection 7.2-7 Pressurizer Sealed Reference Leg Level System 7.2-8 Steam Generator Level Protection 7.2-9 Setpoint Reduction Function For Overpower and Overtemperature hT Trips 703-1 Simplified Block Diagram of Reactor Control System 7' 1 Containment Pressure Protection 7.5>>2 Environmental Conditions Inside Containment Loss-of-Coolant Accident 7.5-3 Environmental Conditions Inside Containment Main Steam Line Break 7.6-1 InCore Instrumentation Details 7.6-2 Typical Arrangement of Movable Miniature Neutron Flux Detector System (Elevation View) 7.6-3 Schematic Arrangement of InCore Flux Detectors (Plan View) 7-i.v July 1995

CHAPTER 9 TABLE OF CONTENTS Section Title ~Pa e 9.0 AUXILIARYAND EMERGENCY SYSTEMS 9.1-1 9.1 GENERAL DESIGN CRITERIA 9.1-2 9.1.1 Auxiliary and Emergency Systems Criteria 9.1-2 9.1.2 Related Criteria 9.1-3 9.2 CHEMICAL AND UOLUME CONTROL SYSTEM 9.2-1 9.2.1 Design Bases 9.2-1 9.2.2 System Design and Operation 9.2-4 9.2.3 System Design Evaluation 9.2-31 ~

9.2 References 9.2-38 9.3 RESIDUAL HEAT REMOUAL SYSTEM 9.3-1 9.3.1 Design Bases 9.3-1 9.3.2 System Design and Operation 9.3-2 9.3.3 System Design Evaluation 9.3-6 9.3.4 Malfunction Analysis 9.3-11

9.3.5 Tests

Inspections 9.3-11 9.3.6 Safety Limits and Conditions 9.3-12 9.4 SPENT FUEL POOL COOLING SYSTEM 9.4-1 9.4.1 Design Bases 9.4-1 9.4.2 System Design and Operation 9.4-2 9.4.3 Design Evaluation 9.4-6 9.4.4 Tests and Inspections 9.4-7 9.5 COMPONENT COOLING SYSTEM 9.5-1 9.5.1 Design Bases 9.5-1 9.5.2 System Design and Operation 9.5-1 9.5.3 Components 9.5-4 9.5.4 System Evaluation 9.5-7 9.5.5 Minimum Operating Conditions 9 '-9 9-i July 1995

CHAPTER 9 TABLE OF CONTENTS (Cont'd)

Section Title ~Pa e 9.5.6 Tests and Inspections 9.5-9 9.6 SAMPLING SYSTEMS 9.6-1 9.6.1 Design Basis 9.6-1 9.6.2 System Design 9.6-2 9.6.3 System Evaluation 9.6-7 9.7 REACTOR COMPONENTS AND FUEL HANDLING SYSTEM 9.7-1 9.7.1 Design Bases 9.7-2 9.7.2 System Design and Operation 9.7-4 9.7.3 Design Evaluation 9.7-24 9.7.4 Tests and Inspections 9.7-25 9.8 FACILITY SERVICE SYSTEMS 9.8-1 9.8.1 Fire Protection System 9.8-1 9.8.2 Compressed Air System 9.8-21 9.8.3 Service Water Systems 9.8-24 9.9 AUXILIARYBUILDING VENTILATION SYSTEM 9.9-1 9.9.1 General Description 9.9-1 9.9.2 Design Basis 9.9-1 9.9.3 System Descriptions 9.9-2 9.9.4 Design Evaluation 9.9-8 9.10 CONTROL ROOM VENTILATION SYSTEM 9.10-1 9.10.1 General Description 9.10-1 9.10.2 Design Basis 9.10-1 9.10.3 System Operation 9.10-2 9.10.4 Design Evaluation 9.10-4 9.10.5 Incident Control 9.10-4 9.10.6 Tests and Inspections 9.10-4 9-ii July 1995

CHAPTER 14 LIST OF TABLES Table Title 14.1-1 Unit 1 Design Power Capability Parameters Used in Non-LOCA Safety Analyses 14.1-2 Reactor Trip Points and Time Delays to Trip Assumed in Safety Analyses 14.1-3 Summary of Initial Conditions and Computer Codes Used 14.1-4 Instrumentation Drift and Calorimetric Errors Power Range Neutron Flux 14.1.10-1 Time Sequence of Events (Manual Rod Control) 14.1.10-2 Time Sequence of Events (Automatic Rod Control) 14.1.10-3 Time Sequence of Events (Manual Rod Control) 14.1.10-4 Time Sequence of Events (Automatic Rod Control) 14.1.13-1 Potential Turbine - Generator Missiles 14.2.1-1 Fuel Handling Accident Auxiliary Building Inventories and Constants of Significant. Fission Product Radionuclides 14.2.1-2

~ ~ Data and Assumptions for the Evaluation of the Fuel Handling Accident In The Auxiliary,Building 14.2.1-4 Activities In Highest Rated Discharged Assembly (Curies At Time Of Reactor Shutdown) Fuel Handling Accident in Containment 14.2.1-5 Parameters For Fuel Handling Accident In Containment Dose Calculation 14.2.3-1 Volume Control Tank and Letdown Activities 14.2.3-2 Gas Decay Tank Equilibrium Activity 14.2.5-1 Limiting Steamline Break Statepoint Double Ended Rupture Inside Containment With Offsite Power Available 14.2.6-1 Parameters Used in Analysis of the Rod Cluster Control Assembly Ejection Accident 14.2.7-1 Loss of A.C. Power to the Plant Auxiliaries Steam Release 14.2.7-2 Steam Line Break - Steam Release 14.2.7-3 Steam Generator Tube Rupture - Steam Release 14.2.8-1 Time Sequence of Events Unit 1 14-v July 1995

CHAPTER 14 LIST OF TABLES Table Title 14.3.1-1 Large Break LOCA - Results 14.3.1-2 Large Break LOCA - Cases Analysed 14.3.1-3 Large Break Containment Data (Ice Condenser Containment) 14.3.1-4 Mass and Energy Release Rates Maximum SI 14.3.1-5 Mass and Energy Release Rates Minimum SI 14.3.1-6 Nitrogen Mass and Energy Release Rates 14.3.2-1 Safety. Injection Flow Rate 14.3.2-2 Plant Input Parameters Used in Small Break LOCA Analysis 14.3.2-3 Small<<Break Loss of Coolant Accident Calculation 14.3.2-4 Time Sequence of Events for Condition III Events 14.3.2-5 Small-Break Loss of Coolant Accident Calculation 14.$ .2-6 Time Sequence of Events for Condition III Events 14.3.2-7 Small-Break Loss of Coolant Accident Calculation Results HHSI Cross-Tie Valve Closed 14.3.2-8 Time Sequence of Events for Condition III Events 14.3.2-9 Small-Break"Loss of Coolant Accident Calculations 14.3.2-10 Time Sequence of Events for Condition III Events 14.3.2-11 Small-Break Loss of Coolant Accident Calculations 14.3.2-12 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 14.3.2-13 Small-Break Loss of Coolant Accident Calculations 3X Main Steam Safety Valve Setpoint Tolerance Analysis for 3588 MWT With HHSI Cross-tie Valves Open 13.3.3-1 Selected Input Parameters 14.3.4-1 Donald C. Cook Ice Condenser Analysis Parameters 14.3.4-2 Deck Leakage Sensitivity 14.3.4-3 Cook Nuclear Plant Ice Condenser Design Parameters 14.3 '-4 Structural Heat Sink Table Unit 1 14-vi July 1995

CHAPTER 14 LIST OF TABLES Table Ti.tie 14.3.4-5 Energy Accounting in Millions of BTU 14.3.4-6 Material Property Data 14.3.4-7 Unit 1/Unit 2 Steamline Break Mass/Energy Releases Inside Containment 102X Power DER (4e6 FT') Break Failure - MSIV 14.3.4-8 Unit 1/Unit 2 Steamline Break Mass/Energy. Releases Inside"Containment 102X Power Split (0.86 FT') Break Failure - Auxiliary Feedwater Runout Protection 14.3.4-9 Double-Ended Steam Line Break Parameters 14 '.4-10 Steam Line Ruptures 14.3.4-11 Lower Compartment Temperature Transient Results 14.3.4-12 0.35 FT'plit 30X Power 14.3.4-13 0.6 FT'plit 30X Power 14.3.4-14 Key Parameters Affecting Split Steam Line Breaks 14.3.4-15 TMD Input 14.3.4-16

'MD Flowpath Input Data 14.3.4-17 Calculated Maximum Peak Pressures in Lower Compartment Elements Assuming Unaugmented Flow 14.3.4-18 Calculated Maximum Peak Pressures In The Ice Condenser Compartment Assuming Unaugmented Flow 14.3.4-19 Calculated Maximum Differential Pressures Across the Operating Deck of Lower Crane Wall Assuming Unaugmented Flow 14.3.4-20 Calculated Maximum Differential Pressures Across the Upper Crane Wall Assuming Unaugmented Flow 14.3.4-21 Sensitivity Studies for Cook Nuclear Plant-14.3.4-22 Peak Differential" Pressure (PSI) Break at Outlet Nozzle 14.3 '-23 Peak Differential Pressure (PSI) Break at Side of Vessel.

14.3.4-24 Pressurizer Enclosure Nodalization Volumes 14.3.4-25 Pressurizer Enclosure Nodalization Hydraulic Data Unit 1 14-vii July 1995

CHAPTER 14 LIST OF TABLES

~able Title 14.3.4-26 Differential Pressure 14.3.4-27 Summary - Break Mass Flow and Energy Flow 14a3.4-28 Comparison of Peak Differential Pressures 14.3.4-29 Fan Room - Backflow Contribution/Forward Flow Contribution 14.3.4-30 Compartment Volume and Area 14a3.4-31 Blowdown Mass and Energy Release 14.3.4-32 Blowdown Mass and Energy Release 14.3.4-33 3425 MWT/Deps - Min SI/RHR X-Tie Closed Reflood Mass and Energy Releases 14.3.4-34 3425 MWT/Deps - Max SI/RHR X-Tie Open Reflood Mass and Energy Releases 14.3.4-35 Reflood Transient Parameters Double Ended Pump Suction 14.3.4-36 Reflood Transient Parameters Double Ended Pump Suction 14.3.4-37 3425 MWT/Deps - Min SI/RHR X-Tie Closed Post Reflood Mass and Energy Releases 14.3.4-38 3425 MWT/Deps - Max SI/RHR X-Tie Open Post Reflood Mass and Energy 1

Releases 14.3.4-39 Mass and Energy Balances - Minimum Safeguards 3425 MWT/Deps - Mins SI/RHR X-Tie Closed 14.3.4-40 Mass and Energy Balances - Maximum Safeguards. 3425 MWT/Deps - Max SI/RHR X-Tie Open 14.3.4-41 Parameters Used in Bounding Steamline Break Mass/Energy Releases for Unit 1 and Unit 2 14.3.4-42 Steam Line Rupture in Steam Generator Doghouse 14.3.4-43 1973 Waltz Mill Preliminary Test Conditions 14.3.4-44 Peak Pressures/Differentials 14.3.4-45 Effects of Varying Polytropic Exponent 14.3.4-46 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 10 CFR 50.49 Environmental Qualification Equipment List 14.4.11-2 Peak Environmental Qualification Conditions For LOCA, MSLB, and Feedwater Line Break Inside Containment 14.4.11-3 Airborne Source Term Doses 14.4.11-4 Integrated Doses Submerged Lower Volume - Observer at Center 14.4.11-5 Beta Dose Factors Dose from Airborne Source After Attenuation (Thickness Unit Density) 14.4.11-6 Beta Dose Factors Dose From Airborne Source After Attenuation (Thickness of Aluminum) 14.4.11-7 Beta Dose Factors Dose From Airborne Source After Attenuation (Thickness of Steel) 14.4.11-8 Pipes considered In Calculating Outside Containment Doses 14.4.11-9

~ ~ Peak Environment Qualification conditions for HELB Outside Containment 14A.2-1 Core and Gap Activities 14A.2-2 Core Temperature Distribution 14A.3-1 Nuclear Characteristics of Highest Rated Discharged Assembly 14A.3-2 Activities in Highest Rated Discharged Assembly Curies at Time of Reactor Shutdown 14A.4-1 Parameters Used in the Calculation of Reactor Coolant Fission Product Activities 14A.4-2 Reactor Coolant Equilibrium Fission and Corrosion Product Activities 14A.4-3 Parameters Used in the Calculation of Reactor Coolant Fission and Corrosion Product Activities for Steam Generator Tube Rupture I

Radiological Analysis 14A.4-4 Reactor Coolant Equilibrium Fission and Corrosion Product Activities for Steam Generator Tube Rupture Radiological Analysis 14A.5-1 Tritium Production in the Reactor Coolant 14A.5-2 Revised Tritium Production in the Reactor Coolant Unit 1 14-xiii July 1995

CHAPTER 14 LIST OF TABLES Table Title 14A.7-1 Gas Decay Equilibrium Activity 14A.8-1 Concentration of Iodine Isotopes in the Recirculation Loop 14A.8-2 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 14.0.1

SUMMARY

OF RESULTS 14.0-3 14.1 CORE AND COOLANT BOUNDARY PROTECTION ANALYSIS.......... 14.1-1 14.1.0 PLANT CHARACTERISTICS AND INITIAL CONDITIONS USED IN SAFETY ANALYSIS ~ ~ ~ ~ 0 ' ~ ~ ~ ~ ~ ~ ~ 14.1-2 14.1.0.1 PLANT CONDITIONS 14.1-2 14.1.0.2 INITIALCONDITIONS 14.1-3 14.1.0.3 POWER DISTRIBUTION 14.1-3 14.1.0.4 REACTIVITY COEFFICIENTS ASSUMED IN THE SAFETY ANALYSIS. 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 AVAILABLE FOR MITIGATION OF ACCIDENT EFFECTS 14.1-9 14.1.0.8 RESIDUAL DECAY HEAT 14.1-10 14.1,0.9 COMPUTER CODES UTILIZED 14.1-11 14.1.0.10 REFERENCES 14.1.14 14.1.1 UNCONTROLLED ROD CLUSTER CONTROL ASSEMBLY (RCCA)

BANK WITHDRAWAL FROM A SUBCRITICAL CONDITION 14.1.1-1 14.1.1.1 IDENTIFICATION OF CAUSES AND ACCIDENT DESCRIPTION 14.1.1-1 14.1.1.2 ANALYSIS OF EFFECTS AND CONSEQUENCES 14.1.1-3 14.1.

1.3 CONCLUSION

S 14.1.1-6 14.1.

1.4 REFERENCES

14.1.1-7 Unit 2 14-i July 1995

TABLE OF CONTENTS (Continued)

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

BANK WITHDRAWAL AT POWER (MIXED CORE) .. DELETED....... 14 '.2A-l 14.1.2B UNCONTROLLED ROD CLUSTER CONTROL ASSEMBLY (RCCA)

BANK WITHDRAWAL AT POWER (FULL VANTAGE 5 CORE) 14.1.2B-1 14.1.2B.1 IDENTIFICATION OF CAUSES AND ACCIDENT DESCRIPTION 14.1.2B-1 14.1.2B.2 ANALYSIS OF EFFECTS AND CONSEQUENCES 14.1.2B-2 14.1.2B.3 CONCLUSIONS 14.1.2B-5 14.1.2B.4 REFERENCES 14.1.2B-6 14.1.3 ROD CLUSTER CONTROL ASSEMBLY (RCCA) MISALIGNMENT (INCLUDING RCCA DROP) 14.1.3-1 14.1.3.1 IDENTIFICATION OF CAUSES AND ACCIDENT DESCRIPTION ..... 14.1.3-1 14.1.3.2 ANALYSIS OF EFFECT AND CONSEQUENCES 14e1.3-3 14.1.

3.3 CONCLUSION

S 14.1.3-6 14.1.

3.4 REFERENCES

14.1.3-8 14.1.4 ROD CLUSTER CONTROL ASSEMBLY DROP 14.1.4-1 14.1.5 UNCONTROLLED BORON DILUTION 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 14.1.5-2 14.1 5.3

~ CONCLUSIONS 14.1.5-6 14.1.6 LOSS OF FORCED REACTOR COOLANT FLOW (INCLUDING LOCKED ROTOR) 14.1.6-1 14.1.6.1 LOSS OF REACTOR COOLANT FLOW 14.1.6-1 14.1.6.2 LOCKED ROTOR ACCIDENT 14.1.6-5 14.1.

6.3 REFERENCES

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 of Events (Full Vantage 5 Core) 14.1.5-1 Time Sequence of Events 14.1.6-1 Time Sequence of Events 14.1.6-2 Time Sequence of Events 14.1.7-1 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 Time Sequence of Events (Full V-5 Core) 14.1.108-2 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 Parameters for Liquid Radioactive Tank Failure Analysis 14.2.2-2 Ground Water Activities Due to Liquid Radioactive Tank Failure 14.2.2-3 Reactor Coolant Equilibrium Fission and Corrosion Product Activities 14.2,4-1 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 Time Sequence of Events 14.2.6-1 Parameters Used in the Analysis of the Rod Cluster Control Assembly E]ection Accident 14.2.8-1 Time Sequence of Events 14.3.1-1 Large Break LOCA - Cases Analyzed 14.3.1-2 Unit 2 Input Parameters Used in the Large Break LOCA ECCS Analysis 14.3.1-3 Large Break LOCA ECCS Analysis Systems Modelling 14.3.1-4 Large Break LOCA Containment Data (Ice Condenser Containment) 14.3.1-5 Large Break LOCA Analysis Time Sequence of Events 14.3.1-6 Large Break LOCA Results Fuel Cladding Data 14.3.1-7 Case A - Large Break LOCA C~ 0.6 Minimum Safeguards Mass and Energy Release Rates Unit 2 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 Plant Input Parameters Used in Small Break LOCA Analysis 14.3.2-2 Time Sequence of Events for Condition III Events 14.3.2-3 Time Sequence of Events for Condition III Events 14.3,2-4 Small Break Loss of Coolant Accident Calculation 14.3.2-5 Small Break Loss of Coolant Accident Calculation 14.3.2-6 Safety Injection Flow Rate with HHSI Cross Tie Valves Open 14.3.2-7 Time Sequence of Events for Condition III Events 14.3.2-8 Small Break Loss of Coolant Accident Calculation 14.3.2-9 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 Fuel Parameters and Core Gap Activities 14.3.5-2 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 ~Ttla 14.1.0-1 Doppler Power Coefficient Used in Safety Analyses 14.1.0-2 RCCA Position Versus Time After Rod Drop Begins 14.1.0-3 Normalized RCCA Reactivity Worth Versus RCCA Position 14.1.0-4 Normalized RCCA Reactivity Worth Versus Time After RCCA Drop Begins 14.1.0-5 Overtemperature and Overpower hT Protection 14.1.0<<6 Overtemperature and Overpower 4T Protection 14.1.0-7 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 Rod Withdrawal at Power Pressurizer Pressure and Water Volume Versus Time for Full Power, 80 PCM/Sec Insertion Rate, Maximum Reactivity Feedback 14.1.2B-3 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 Startup of an Inactive Reactor Coolant Loop 14.1.8B-1 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 lake over almost the entire site area.

t.

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) The chlorination building b) The top of the primary shield wall c) 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