Text

Forwards Rev 11 to Re Ginna Nuclear Power Plant UFSAR, Reflecting Changes to Facility & Info & Analyses Submitted to NRC or Prepared Per NRC Requirements Since Last Annual Update Submitted 931216
	ML17309A563
Person / Time
Site:	Ginna
Issue date:	12/16/1994
From:	Mecredy R; ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
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PRIGRITY ACCELERATED f(IDS PROCI'.SSIXG)

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9412200102 DOC.DATE: 94/12/16 NOTARIZED: NO DOCKET N

FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit. 1, Rochester G

05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas

& Electric Corp.

RECIP. NAME RECIPIENT AFFILIATION

~~ / /P/Pf JOHNSON,A.R.

Project Directorate I-3

SUBJECT:

Forwards rev 11 to "Updated Final Safety Analysis Rept," for R E Ginna Nuclear Power Plant.

P DISTRIBUTION CODE:

A053D COPIES RECEIVED:LTR ENCL TITLE: OR Submittal:

Updated FSAR (50.71) and Amendments SIZE:

+ I &CD I

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244 RECIPIENT ID CODE/NAME PDl-3 PD INTERNAL: AEOD/DOA/IRB RGNl EXTERNAL: IHS NRC PDR 1

1 1

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COPIES RECIPIENT LTTR ENCL ID CODE/NAME 1

0 JOHNSON,A 1

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U NO'I'E TO ALL"RIDS" RECIPIEY'TS:

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ENCL 8

ND ROCHESTER GASANDELECTRIC CORPORATION ~ 89 EASTAVENUE, ROCHESTER, N.Y. Idbd9-OMI AREA CODE7I6 546-27M ROBERT C. MECREDY Vice President Nvctear Operations December 16, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Attn:

Allen R. Johnson Project Directorate I-3 Washington, D.C.

20555

Subject:

Annual Submittal of Updated Final Safety Analysis Report (UFSAR), Revision 11 R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Johnson:

In accordance with 10CFR50.71(e),

Rochester Gas and Electric has prepared its 1994 annual revision to the Updated Final Safety Analysis Report (UFSAR).

Enclosed are the original and 10 copies of the revised

pages, together with a list of effective pages.

Change bars marked with an "11" indicate those revisions which have been incorporated.

The information presented in Revision 11 reflects changes to the facility as described in the UFSAR and information and analyses submitted to the Commission or prepared pursuant to Commission requirements since our last annual update submitted December 16, 1993.

Very uly yours GT/359 Robert C. Mecre y xc:

Mr. Allen R. Johnson (Mail Stop 14D1)

Project Directorate I;3 Washington, D.C.

20555 4

U.S. Nuclear Regulatory Commission, Region I 475 Allendale Road King of Prussia, PA 19406 Ginna SenioOr Oesident Inspector

'st412200102 9412ib PDR ADOCK 05000244 K

PDR

~ 0

'4

R. E.

GINNA NUCLEAR POWER PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revision 11 Instructions 12 94 The following Revision 11 instructions indicate replacement pages and additional or removed pages for the Updated Final Safety Analysis Report.

Remove the existing pages and insert the replacement and additional pages where indicated by these instructions.

Location Remove Pa es Insert Revision 11 Pa es VOLUME I List of Effective Pa es Cha ter 1

Cha ter 2

LEP-1/LEP-2 through LEP-15/LEP-16 1.2-5/1.2-6 ~

1.2-9/1.2-10 1.2-11/1.2-12 1.5-17/blank~

1.6-1/1 '-2~

through 1.6-11/blank 1.7-3/1.7-4~

Figure.1.7-1~

Sheet 2

1. 8-19/1. 8-20 1.8-45/1.8-46~

2.1-1/2.1-~

2.1-3/2.1-4 Figure 2.1-2~

LEP-1/LEP-2 through LEP-15/blank 1'-5/1.2-6~

1.2-9/1.2-10 1'-11/1 '-12 1.5-17/blank~

1'-1/1.6-&

through 1.6-11/blank 1.7-3/1.7-~

Figure 1.7-1 Sheet 2

1.8-19/1.8-20 1.8-45/1.8-4 2. 1-1/2. 1-2~

2.1-3/2.1-4~

Figure 2.1-2+

VOLUME II 3-vii/3-vii~

3-xvic/3-xvid 3-vii/3-viii 3-xvic/3-xvid

Location VOLUME III Remove Pa es 3-xxiii/3-xxi 3.1-21/3.1-22 3.1-23/3.1-24 3.2-5/3.2-6 through 3.2-9/3.2-1 3.2-17/3.2-18~

3.2-19/3.2-20~

3.3-17/3.3-18 3.4-3/3.4-4 3.4-5/3.4-8 3.5-7/3.5-~

3.5-9/3.5-10 3.7-27/3.7-28~

3.7-49/blan~

Figure 3.7-2

3. 8-111/3. 8-112 3-vi1/ 3-v1 1~

3-xvic/3-xvi~

3-xxiii/3-xxiv~

3.9-45/3.9-4~

3.9-56a/3.9-56M 3.9-56c/3.9-56 3.9-69/3.9-7~

3.11-13/3.11-14 M Insert Revision 11 Pa es 3-xxiii/3-xxiv 3.1-21/3.1-22~

3 '-23/3.1-24 3. 1-4 8a/blanW 3.2-5/3.2-6~

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3.2-19/3.2-20~

3. 3-17/3. 3-18~

3.4-3/3.4-~

3.4-5/3.4-3.5-7/3.5-8W 3.5-9/3 '-1 3;7-27/3 '-2

3. 7-49/blan~

Figure 3.7-24~

3 '-111/3.8-11 3-vii/3-viii+

3-xvic/3-xvi 3-xxiii/3-xxi 3 '-45/3.9-4 3.9-56a/3.9-5

3. 9-56c/blank 3.9-69/3.9-7 3 '1-13/3.11-1

Location Cha ter 4

VOLUME IV Cha ter 5

Remove Pa es

3. 11-19/3. 11-20 M~

3. 11-2 1/3. 11-22 3A-5/3A-6 through 3A-15/3A-16 4-i/4-ii 4-111/4-1~v 4.1-1/4.1-2 through 4.1-7/blank 4.2-1/4.2-~

through 4.2-45/blan~

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Sheet 2

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5.4-23/5.4-24~

Insert Revision 11 Pa es

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3. 11-2 1/3. 11-22 3A-5/3A-~

through 3A-15/3A-1 4-i/4-ii~~

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4. 1-1/4. 1 4. 1-3/4. 1-4 4.2-1/4.2 through 4.2-43/blan Figure 4.2-4.3-7/4.3-~

through 4. 3-13/b1a~

4.4-9/4.4-1~0 4.4-19/4.4-2~

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Sheet 2

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Location Cha ter 6

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through 6-xv/blan 6.2-7/6.2-8 through 6.2-25/6.2-26

6. 2-37/6. 2-38~

6. 2-75/6. 2-76 6.2-87/6.2-88~

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Figure 6.2-4 Figure 6.2-5 Figure 6.2-5 Figure 6.2-5 Figure 6.2-65

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Figure 6.4-1r 6.5-11/6.5-12 through 6.5-15/6.5-16 Insert Revision 11 Pa es Figure 6.2-35 Figure 6.2-4 Figure 6.2-44 Figure 6.2-4 Figure 6.2-47 Figure 6.2-49 Figure 6.2-Figure 6.2-Figure 6.2-56 Figure 6.2-6 Figure 6.2-71 Figure 6.2-7 through Figure 6.2-78 6.3-3/6.3-4 through 6.3-6a/blan 6.3-11/6.3-12 through 6.3-39/6.3-40 6.3-47/6.3-4 through 6.3-55/blan Figure 6.3-1 Sheet 1

Figure 6.4-1~

6.5-11/6 '-1 through 6.5-15/6-5-1

Location VOLUME V Cha ter 7

Cha ter 8

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7.2-37/7.2-3W/

7. 2-39/7. 2-40 M Figure 7.2-7.3-7/7.3-&

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7.5-,43/blank~

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7. 7-2 1/7,. 7-22 through 7.7-57/blan 8-1/8-ii~

8.1-9/8.1-10 8. 1-11/blank~

8. 3-5/8. 3-6 through 8.3-13/8.3-14 Insert Revision 11 Pa es 7-iii/7-iv through 7-vii/7-vii 7.2-39/7.2-4 Figure 7.2-4 7.3-7/7.3-~

through 7.3-19/7.3-20 7.4-3/7.4-4 through 7.4-9/7.4-1 7.4-21/7.4-2~~

7. 4-23/7. 4-24 7.5-1/7.5-~

7.5-9/blan~

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7. 5-31/blan~

7.5-43/blah~

7. 5-49/b1an~

7. 7-21/7. 7-2 2~

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8-i/8-ii

8. 1-9/8. 1-10 8.1-11/blank 8.3-5/8.3-~

through 8.3-13/8.3-14

Location VOLUME VI Remove Pa es 8.3-27/8.3-28 ~

through 8.3-39/8.3-40 Figure 8.3-1 through Figure 8.3-Figure 8.3-6 9-iii/9-iv~

through 9-ix/9-~

9. 1-7/9. 1-8 9 ~ 1-19/9. 1-20~

9 ~ 1-2 1/9. 1-2 2 9.1-26a/9.1-26b~

Figure 9.1-~

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9.2-17/9.2-1~

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Sheet 2

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9.1-7/9.1-8~

9. 1-19/9. 1-2W

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Sheet 3

Figure 9.2-Sheet 1

Sheet 2

Figure 9.2-.3 Figure 9.2-4 Sheet 1

Sheet 2

Location Remove Pa es Insert Revision 11 Pa Figure 9.2-6 Sheet 1

Sheet 3

9.3-23/9.3-24 through 9.3-59/9.3-60."

9.3-67/9.3-68~

Figure 9.3-1 Sheet 2

Figure 9.3-2 Sheet 1

Sheet 2

Figure 9.3-5 Figure 9.3-6~

Sheet 1

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Sheet 1

Sheet 2

Figure 9.3-11 Sheet 1

Figure 9.2-Sheet 1

Sheet 3

9.3-23/9.3-24~

through 9.3-59/9.3-60 9.3-67/9.3-6~

Figure 9.3-1 Sheet 2

Figure 9.3-Sheet 1

Sheet 2

Figure 9.3-Figure 9.3-6 Sheet 1

Figure 9.3-1~

Sheet 1

Sheet 2

Figure 9.3-1 Sheet 1

Sheet 3

Sheet 4

Figure 9.3-12 Figure 9.3-13 Sheet 2

Figure 9.3-15 Figure 9.3-17 9.4-29/9.4-30 Figure 9.4-2 Figure 9.4-through Figure 9.4-Figure 9.4-1 Figure 9.4-14 Sheet 3

Sheet 4

Figure 9.3-12 Figure 9.3-1 Sheet 2

Figure 9.3-15 Figure 9.3-17 9.4-29/9.4-3~

Figure 9.4-2 Figure 9.4-through Figure 9.4-Figure 9.4-10 Figure 9.4-14

Location Cha ter 10 Remove Pa es I

Figure 9.4-17 Figure 9.4-18 9.5-1/9.5-2 9.5-9/9.5-10 9.5-17/9.5-18 through 9.5-21/9.5-22 9.5-41/bien&

9.5-47/bla through 9.5-59/blan'.5-61/9.5-6 Figure 9.5-1 ~

Figure 9.5-2 Sheet 1

Sheet 2

Figure 9.5-Figure 9.5-4 10.1-7/10.1-&

10.1-9/10.1-1 Figure 10.3-&

Figure 10.3-4 Sheet 2

Figure 10.4-2+

Figure 10.4-~

Figure 10.4-4~

Sheet 1

Figure 10.4-5 10.5-3/10.5-.

through 10.5-13/10.5-1 Figure 10.5-1~

Figure 10.5-2 ~

Insert Revision 11 Pa s

Figure 9. 4-17Q Figure 9.4-18

9. 5-1/9. 5-2 9.5-9/9.5-10+

9 '-17/9.5 through 9.5-21/9.5-2 9.5-41/blank 9.5-47/blan through 9.5-59/blan 9 '-61/9.5-6 Figure 9.5-Figure 9.5-Sheet 1

Sheet 2

Figure 9.5-3 Figure 9.5-4~

10.1-7/10.1-8 10.1-9/10 F 1-10 Figure 10.3-1 Figure 10.3-4 Sheet 2

Figure 10.4-Figure 10.4-3~

Figure 10.4-4 Sheet 1

Figure 10.4-~

10 ~ 5-3/10. 5-4 through

10. 5-13/10. 5-14 Figure 10.5-1 Figure 10.5-2~

Location VOLUME VII Cha ter 11 Remove Pa es Figure 10.6-1.

Sheet 2

Figure 10.6-3 i Figure 10.7- /

Figure 10. 7-2<

Figure 10.7-Figure 10.7-6 Sheet 1

Sheet 2

Figure 10.7-Figure 10.7-10 Figure 10.7-1 Sheet 2

Figure 10.7-13

11. 1-7/blank~

11.2-5/11.2-6 through 11.2-15/11.2-16 11.2-25/11.2-26 Figure 11.2-1 Figure 11.2-2 Sheet 2

Figure 11.2-3 Sheet 1

Figure 11.3-Sheet

.2 11.4-1/11.4-2 through 11.4-5/11.4-6 ~

11.5-7/11.5-8 Figure 11.5-2 Insert Revision 11 Pa es Figure 10.6-Sheet 2

Figure 10.6-3 Figure 10.7-1 Figure 10.7-2 Figure 10.7-5 Figure 10.7-6 Sheet 1

Sheet 2

Figure 10.7-8 Figure 10.7-10 Figure 10.7-11 Sheet" 2

Figure 10.7-1 11.2-5/11.2-6 through 11.2-15/11.2-1 Figure 11.2-Figure 11.2-Sheet 2

Figure 11.2-3 Sheet 1

Figure 11.3-Sheet 2

11 '-1/11.4-through

11. 4-5/11

~ 4-6 11.5-7/11.5-8 Figure 11.5-2 Location Cha ter 12 Cha ter 13 Cha ter 14 VOLUME VIII Remove Pa es 12.1-1/12.1-2 12.2-1/12.2-2

12. 3-9/12. 3-10+

through 12.3-13/12.3-14

12. 3-25/blank 12.4-1/12. 4-~

12.4-11/12.4-12 13-i/13-ii~

through 13-v/blanks 13.1-1/13.1-2 through

13. 1-23/blank Figure 13.1-1&

through Figure 13.1-7 13.4-1/13.4-~

through 13.4-11/blan Figure 13.4-

14. 6-19/14. 6-20&

14.6-53/14.6-54 15-1/15-i~

through 15-vii/15-vii 15-xxi/blan~

15. 0-10a/blank~

15.1-9/15.1-10 15.2-1/15.2-2 Insert Revision 11 Pa es 12.1-1/12 '-2 12.2-1/12.2-&

12.3-9/12.3-10 X through

12. 3-13/12. 3-14 12.3-25/blank~

12 ~ 4-1/12

~4-2~

12.4-11/12.4-1&

13-i/13-ii~

.through 13-v/blan~

13. 1-1/13. 1-2 through 13. 1-19/13. 1-20 Figure 13.1-1 through Figure 13.1-11

13. 4-1/13. 4-2~

through 13.4-5/blank 14.6-19/14.6-20M 14.6-53/14.6-54 15-1/15-ii~

through 15-vii/15-viii 15-xxi/blank~

15. 0-10 a/blank 15 F 1-9/15 F 1-10 15.2-1/15 '-2 Location Remove Pa es Insert Revision ll Pa es 15.3-1/15.3-2M 15.4-15/15.4-16 15.4-37/blank 15.6-1/15.6-2 15.6-17/15.6-18 through 15.6-26e/15.6-26f 15.7-19/blank 15.3-1/15.3-2 15 '-15/15.4-16 15.4-37/blank 15.6-1/15.6-2 15.6-17/15.6-18 through 15.6-26e/15.6-26 Figure 15.6-71a 15.7-19/blank~

UPDATED Fl L SAFETY ANALYSIS RE QRT REVISION 9 12/92

0 O.

List of Effective Pages Page No.

Rev Page Ho.

Rev Page No.

Rev Page Ho.

Rev Page No.

Rev Page Ho.

Rev CHAPTER I 1-i 1-ii 1-i i i 1-iv 1-v 1-vi 1-v i i 1-viii 1-ix 1-x SECTION 1.1 1.1-1 1.1-2 SECTION 1.2 1.2-1 1.2-2 1.2-3 1.2-4 1.2-5 1.2-6 1.2-7 1.2-8 1 ~ 2-9 1.2-10 1.2-11 1.2-12 1.2-13 1.2-14 1.2-15 1.2-16 1.2-17 FIGURES 1.2-1 1.2-2 1.2-3 1.2-4 1.2-5,SH

. 1.2-5,SH 1.2-5,SH 3

1.2-5,SH 4

1.2-6,SH 1

1.2-6,SH 2

1.2-7 SH 1

0 5

0 10 2

10 10 7

7 10 5

5 5

5 1.2-7,SH 2

1.2-7,SH 3

1.2-8,SH 1

1.2-8,SH 2

1.2-8,SH 3

1.2-9,SH 1

1.2-9,SH 2

1.2-10 1.2-11 1.2-12 1.2-13 1.2-14 1.2-15,SH 1

1.2-15,SH 2

1.2-15,Sii 3

1.2-15,SH 4

1.2-16 1.2-17 1.2-18 1.2-19,SH 1

1.2-19,SH 2

1.2-19,SH 3

1.2-20,SH 1

1.2-20.SH 2

1.2-21,SH 1

1.2-21,SH 2

SECTION 1.3 1.3-1 1.3-2 1.3-3 1.3-4 1.3-5 1.3-6 1.3-7 1.3-8 1.3-9 1.3-10 1.3-11 1.3-12 1.3-13 1.3-14 1.3-15 1.3-16 1.3-17 1.3-18 1.3-19 SECTION 1.4 1.4-1 1.4-2 SECTION 1.5 1.5-1 1.5-2 1.5-3 1.5-4 1.5-5 1.5-6 1.5-7 1.5-8 1.5-9 1.5-10 1.5-11 1.5-12 1.5-13 1.5-14 1.5-15 1.5-16 1.5-17 SECTION 1.6 1.6-1 1.6-2 1.6-3 1.6-4 1.6-5 1.6-6 1.6-7 1.6-8 1.6-9 1.6-10 1.6-11 SECTION 1.7 1.7-1 1.7-2 6

6 6

6 0

10 0

0 0

0 10 0

0 1.7-3 1.7-4 1.7-5 1.7-6 1.7-7 1.7-8 1.7-9 1.7-10 1.7-11 1.7-12 1.7-13 1.7-14 FIGURES 1.7.1,SH 1.7-1, SH

1. 7-1, SH

1. 7-1, SH SECTION 1.8 1.8-1 1.8-2 1.8-3 1.8-4 1.8-5 1.8-6 1.8-7 1.8-8 1.8-9 1.8-10 1.8-11 1.8-12 1.8-13 1.8-14 1.8-15 1.8-16 1.8-17 1 ~ 8-18 1.8-19 1.8-20 1 ~ 8-20a 1.8-21 1.8-22 1.8-23 1.8-24 1.8-25 1.8-26 1.8-27 9

7 6

7 10 8

6 6

7 9

10 7

10 10 9

10 0

0 0

0 10 0

0 0

6 6

6 10 0

0 0

0 6

1.8-28 1.8-29 1.8-30 1.8-31 1.8-32 1.8-33 1.8-34 1.8-35 1.8-36 1.8-37 1.8-38 1.8-39 1.8-40 1.8-41 1.8-42 1.8-43 1.8-44 1.8-45 1.8-46 1.8-47 1.8-48 1.8-49 1.8-50 1.8-51 1.8-52 1.8-53 1.8-54 1.8-55 1.8-56 1.8-57 1.8-58 1.8-59 1.8-60 CHAPTER 2 2-l 2-i I 2-iii 2-iv 2-U 2-vi 2-vii 6

6 6

0 0

0 10 0

6 6

0 0

6 6

6 0

0 0

0 2

0 10 6

6 6

6 10 10 SECTION 2.1 2.1-1 2.1-2 2.1-3 2.1-4 2.1-5 2.1-6 2.1-7 FIGURES 2.1-1 2.1-2 2.1-3

2. 1-4 2.1-5 2.1-5a 2.1-6 2.1-7 2.1-8 SECTION 2.2 2.2-1 2.2-2 2.2-3 2.2-4 2.2-5 2.2-6 2.2-7 2.2-8 2.2-9 2.2-10 2.2-11 SECTION 2.3 2.3-1 2.3-2 2.3-3 2.3-4 0

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x 3-xi 3-xii 3-xiii 3-xiv 3-xv 3-xvi 3 xv la 3-xvib 3-xvic 3-xvid 3-xvie 3 xvii 3-xviii 3-xix 3-xx 3-xxi 3-xxii 3-xxiii 3-xxiv 3-xxv 3-xxvi 3-xxvii SECTION 3.1 3.1-1 3.1-2 3.1-3 3.1-4 3.1-5 3.1-6 3.1-7 3.1-8 3.1-9 3.1-10 3.1-11 3.1-12 3.1-13 3.1-14 3.1-15 3.1-16 3.1-17 3.1-18 3.1-18a 3'-19 6

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3.5-11 3.5-12 3.5-13 3.5-14 3.5-15 3.5-16 3.5-17 3.5-18 3.5-19 3.5-20 3.5-21 3.5-22 SECTION 3.6 3.6-1 3.6-2 3.6-3 3.6-4 3.6-4a 3.6-5 3.6-6 3.6-7 3.6-8 3.6-9 3.6-10 3.6-11 3.6-12 3.6-13 3.6-14 3.6-15 3.6-16 3.6-17 3.6-18 3.6-19 3.6-20 3.6-21 3.6-22 3.6-23 3.6-24 3.6-25 3.6-26 3.6-27 3.6-28 3.6-29 0

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.9-5 3.9-6 3.9-6a 3.9-6b 3.9-6c 3.9-7 3.9-8 3.9-9 3.9-10 3.9-11 3.9-12 3.9-13 3.9-14 3.9-15 3.9-16 3 '-17 3.9-18 3.9-19 3.9-20 3.9-21 3.9-22 3.9-23 3.9-24 3.9-25 3.9-26 3.9-27 3.9-28 3.9-29 3.9-30 3.9-31 3.9-32 3.9-33 3.9-34 3.9-35 3.9-36 3.9-37 3.9-38 3.9-39 3.9-40 3.9-41 3.9-42 3.9-43 3.9-44 3.9-45 3.9-46 3.9-47 3.9-48 3.9-49 3.9-50 3.9-51 3.9-52 3.9-53 3.9-54 3.9-55 3.9-56 3.9-56a 3.9-56b 3.9-56c 3.9-56d 3.9-57 3.9-58 3.9-59 3.9-60 3.9-61 3.9-62 3.9-63 3.9-64 3.9-65 3.9-66 3.9-67 3.9-68 3.9-69 3.9-70 3.9-71 3.9-72 3.9-73 3.9-74 3.9-75 3.9-76 3.9-77 3.9-78 3.9-79 3.9-80 3.9-81 3.9-82 3.9-83 3.9-84 3.9-85 6

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3A-7,SH 2:

3A-8 3A-9 APPENDIX 3$

38-i 38-ii 3B-iii 3B-iv 3B-v 3B-vi 38-vii 38-viii 38-1 38-2 3B-3 38-4 38-5 38-6 38-7 38-8 38-9 38-10

'3B-11 3B-12 3B-13 3B-14 3B-15 3B-16 3B-17 3B-18 3B-19 3B-20 3B-21 3B-22

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Rev APPENDIX 36 38-23 38-24 38-25 38-26 38-27 38-28 38-29 38-30 38-31 38-32 38-33 38-34 36-35 38-36 38-37 38-38 38-39 38-40 38-41 38-42 38-43 38-44 38-45 38-46 38-47 38-48 38-49 38-50 38-51 38-52 38-53 38-54 38-55 36-56 38-57 36-58 38-59 38-60 38-61 38-62 38-63 38-64 38-65 38-66 38-67 FIGURES 36-1 38-2 38-3 38-4 38-5 38-6 36-7 36-8 36-9 36-10 38-11 36-12 38-13 38-14 38-15 38-16 36-17 38-18 38-19 38-20 38-21 36-22 38-23 38-24 D-421-023 D-421-024 APPENDIX 3B.A 38.A-1 38.A-2 38.A-3 36.A-4 36.A-5 38.A-6 3B.A-7 38.A-B APPENDIX 38.8 36.8-1 38.8-2 36 Add-i 38 Add-ii 38 Add-1 38 Add-2 38 Add-3 38 Add-4 38 Add-5 38 Add-6 38 Add-7 36 Add-8 38 Add-9 36 Add-10 38 Add-11 38 Add-12 38 Add-13 38 Add-14 36 Add-15 38 Add-16 38 Add-17 38 Add-18 38 Add-19 APPENDIX 3C 3C-1 3C-2 3C-3 3C-4 3C-5 3C-6 3C-7 3C-8 3C-9 3C-10 3C-11 3C-12 3C-13 3C-14 3C-15 3C-16 3C-17 3C-18 3C-19 3C-20 3C-21 3C-22 3C-23 3C-24 3C-25 APPENDIX 3D 30-1 3D-2 3D-3 3D-4 30-5 3D-6 3D-7

'D-8 3D-9 30-10 3D-11 30-12 3D-13 3D-14 3D-15 3D-16 3D-17 3D-18 3D-19 3D-20 30-21 3D-22 3D-23 30-24 3D-25 3D-26 3D-27 3D-28 30-29 3D-30 3D-31 3D-32 3D-33 30-34 3D-35 APPENDIX 3E 3E-1 3E-2 3E-3 3E-4 3E-5 3E-6 3E-7 3E-8 3E-9 3E-10 3E-11 3E-12 3E-13 3E-14 3E-15 3E-16 3E-17 3E-18 3E-19 3E-20 3E-21 3E-22 3E-23 3E-24 3E-25 3E-26 3E-27 3E-28 3E-29 3E-30 3E-31 3E-32 3E-33 3E-34 3E-35 APPENDIX 3F 3F-i APPENDIX 3F.1 3F.1-1 3F. 1-2 APPENDIX 3F.2 3F.2-1 3f.2-2 3F.2-3 3f.2-4 3F.2-5 3F.2-6 3F.2-7 APPENDIX 3F.3 3F.3-1 3F.3-2 3F.3-3 3F.3-4 3F.3-5 3F.3-6 3F.3-7 3F.3-8 3F.3-9 3F.3-10 3F.3-11 3F.3-12 3F.3-13 3F.3-14 3F.3-15 3F.3-16 3F.3-17 APPENDIX 3F.4 3f.4-1 3F.4-2 3F

~ 4-3 3F.4-4 3F.4-5 3F.4-6 3F.4-7 3F.4-8 3F.4-9 APPENDIX 3F.5 3F.5-1 3F.5-2 3F.5-3 3F.5-4 3F.5-5 3F.5-6 3F.5-7 3F.5-8 3F.5-9 3F.5-10 3F.5-11 3F.5-12 3F. 5-13 3F.5-14 CHAPTER 4 4-i 4-ii 4-iii 4-iv 4-v SECTION 4.1 4.1-1 4.1-2 4.1-3 4.1-4 4.1-5 4.1-6 4.1-7 SECTION 4.2

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9 4.4-6 4.4-7 4.4-8 4.4-9 4.4-10 4.4-11 4.4-12 4.4-13 4.4-14 4.4-15 4.4-16 4.4-17 4.4-18 4.4-19 4.4-20 4.4-21 4,4-22 4.4-23 4.4-24 FIGURES 4.4-1 SECTION 4.5 4.5-1 SECTION 4.6 4.6-1 CHAPTER 5 5-i 5-ii 5-iii 5-iv 5-v 9

9 9

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5-vi 5-vii 5-viii SECTION 5.1 5.1-1 5.1-2 5.1-3 5.1-4 5.1-5 5.1-6 5.1-7 5'-8 5.1-9 5.1-10 5.1-11 5.1-12 5.1-13 5.1-14 5.1-15 5.1-16 5.1-17 5.1-18 FIGURES 5.1-1 SH 1

5.1-1 SH 2

5. 1-2 5.1-3 SECTION 5.2 5.2-1 5.2-2 5.2-3 5.2-4 5.2-5 5.2-6 5.2-7 5.2-8 5.2-9 5.2-10 10 10 9

9 5.2-11 5.2-12 5.2-13 5.2-14 5.2-15 5.2-16 5.2-17 5.2-18 5.2-19 5.2-20 5.2-20a 5.2-20b 5.2-21 5.2-22 5.2-23 5.2-24 5.2-25 5.2-26 5.2-27 5.2-28 5.2-29 5.2-30 5.2-31 5.2-32 5.2-33 5.2-34 5.2-35 5.2-36 5.2-37 5.2-38 5.2-38a 5.2-39 5.2-40 5.2-41 5.2-42 5.2-43 5.2-44 5.2-45 5.2-46 9

9 9

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6 6

6 10 10 10 0

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0 FIGURES 5.2-1 5.2-2 5.2-3 SECTION 5.3 5.3-1

5. 3-2 5.3-3 5.3-4 5.3-5 5.3-6 5.3-7 5.3-8 5.3-9 5.3-10 5.3-11 5.3-12 5.3-13 5.3-14 5.3-15 5.3-16 5.3-17 5.3-18 5.3-19 5.3-20 5.3-21 5.3-22 5.3-23 5.3-24 5.3-25 5'-26 5.3-27 5.3-28 5.3-29 5.3-30 5.3-31 10 0

0 FIGURES 5.3-1, SH 5.3-1, SH 5.3-2 5.3-3 5.3-4 SECTION 5.4 5.4-1 5.4-2 5.4-3 5.4-4 5.4-5 5.4-6'.4-7 5.4-8 5.4-9 5.4-10 5.4-11 5.4-12 5.4-13 5.4-14 5.4-15 5.4-16 5.4-16a 5.4-17 5.4-18 5.4-19 5.4-20 5.4-21 5.4-22 5.4-23 5.4-24 5.4-25 5.4-26 5.4-27 5.4-28 5.4-29 5.4-30 5.4-31 5.4-32 5.4-33 6

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Rev SECTION 5.4 5.4-34 5.4-35 5.4-36 5.4-37 5.4-38 5.4-39 5.4-40 5.4-41 5.4-42 5.4-43 5.4-44 5.4-45 5.4-46 5.4-47 5.4-48 5.4-49 5.4-50 5.4-51 5.4-52 5 '-52a 5.4-52b 5.4-52c 5.4-52d 5.4-52e 5.4-52f 5.4-52g 5.4-52b 5.4-52i 5.4-52) 5.4-53 5.4-54 5.4-55 5.4-56 5.4-57 5.4-58 5.4-59 5.4-60 5.4-61 5.4-62 5.4-63 5.4-64 7

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5 "Unnumbered Blank Page FIGURES 5.4-1 5.4-2 5.4-3 5.4-4 5.4-5 5.4-6 5.4-7 5.4-8 5.4-9 CUAPTER 6 6-i 6-ii 6-iii 6-iv 6-vi 6-vii 6-viii 6-ix 6-x 6-xi 6-xii 6-xiii 6-xiv 6-xv SECTION 6.1 6.1-1 6.1-2 6.1-3 6.1-4 6.1-5 6.1-6 6.1-7 6.1-8 6.1-9 6.1-10 6.1-11 6.1-12 6.1-13 6.1-14 6.1-15 6.1-16 0

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0 10 10 6.1-16a 6.1-17 6.1-18 6.1-19 6.1-20 6.1-21 6.1-22 6.1-23 6.1-24 6.1-25 6.1-26 6.1-27 6.1-28 FIGURES 6.1-1 6.1-2 6.1-3 6.1-4 6.1-5 6.1-6 6.1-7 6.1-8 6.1-9 6.1-10 SECTION 6.2 6.2-1 6.2-2 6.2-3 6.2-4 6.2-5 6.2-6 6.2-7 6.2-8 6.2-9 6.2-10 6.2-11 6.2-12 6.2-13 6.2-14 6.2-15 6.2-16 6.2-17 6.2-18 10 0

3 0

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6.2-19 6.2-20 6.2-21 6.2-22 6.2-23 6.2-24 6.2-25 6.2-26 6.2-27 6.2-28 6.2-29 6.2-30 6.2-30a 6.2-30b 6.2-30c 6.2-30d 6.2-31 6 '-32 6.2-33 6'-34 6.2-35 6.2-36 6.2-37 6.2-38 6.2-39 6.2-40 6.2-41 6.2-42 6.2-43 6.2-44 6.2-45 6.2-46 6.2-47 6.2-48 6.2-49 6.2-50 6.2-51 6.2-52 6.2-53 6.2-54 6.2-55 6.2-56 6.2-57 6.2-58 6.2-59 7

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10 6.2-60 6.2-61 6.2-62 6.2-63 6.2-64 6.2-65 6 '-66

'6.2-67 6.2-68 6.2-69 6.2-70 6.2-71 6.2-72 6.2-73 6.2-74 6.2-75 6.2-76 6.2-77 6.2-78 6.2-79 6.2-80 6.2-82 6.2-82 6.2-83 6.2-84 6.2-85 6.2-86 6.2-87 6.2-88 6.2-89 6.2-90 6.2-91 6.2-92 6.2-93 6.2-94 6.2-95 6.2-96 6.2-97 6.2-98 6.2-99 6.2-100 6.2-101 6.2-102 6.2-103 6.2-104 10 10 10 10 8

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10 6.2-105 6.2-106 6.2-107 6.2-108 6.2-109 6.2-110 6.2-111 6.2-112 6.2-113 6.2-114 6.2-115 6.2-116 6 '-117 6.2-118 6.2-119 6.2-120 6.2-121 FIGURES 6.2-1 6.2-2 6.2-3 6.2-4 6.2-5 6.2-6 6.2-10 6.2-11 6.2-12 6.2-13 6.2-13a 6.2-14 6.2-15 6.2-16 6.2-15 6.2-17 6'-18 6.2-19 6.2-20 6.2-21 6.2-22 6.2-23 6.2-24 10 10 10 10 10 10 10 10 10 10 10 0

0 7

7 7

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10 7

10 10 10 10 10 10 10 10 10 10 10 10 10 10 6.2-25 6.2-26 6.2-27 6.2-28 6.2-29 6.2-30 6.2-31 6.2-32 6.2-33 6.2-34 6.2-35 6.2-36 6.2-37 6.2-38 6.2-39 6.2-40 6.2-41 6.2-42 6.2-43 6.2-44 6.2-45 6.2-46 6.2-47 6.2-48 6.2-49 6.2-50 6.2-51 6.2-52 6.2-53 6.2-54 6.2-55 6.2-56 6.2-57 6.2-58 6.2-59 6.2-60 6.2-61 6.2-62 6.2-63 6.2-64 6.2-65 6.2-66 6.2-67 6.2-68 6.2-69 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10

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Rev FIGURES 6.2-70 6.2-71

'.2-72 6.2-73 6.2-74 6.2-75 6.2-76 6.2-77 6.2-78 6.2-79,SH 1

6.2-79,SH 2

6.2-80 SECTION 6.3 6.3-1 6.3-2 6.3-3 6.3-4 6.3-5 6.3-6 6.3-6a 6.3-7 6.3-8 6.3-9 6.3-10 6.3-11 6.3-12 6.3-13 6.3-14 6.3-15 6.3-16 6.3-17 6.3-18 6.3-19 6.3-20 6.3-21 6.3-22 6.3-23 6.3-24 6.3-25 6.3-26 10 10 10 10 10 10 10 10 10 10 10 8

6 6

10 10 10 6

6 5

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6 10 6

6 6

7 6

6 6

6 6.3-26a 6.3-27 6.3-28 6.3-29 6.3-30 6.3-31 6.3-32 6.3-33 6.3-34 6.3-34a 6.3-35 6.3-36 6.3-37 6.3-38 6.3-39 6.3-40 6.3-41 6.3-42 6.3-43 6.3-44 6.3-45 6.3-46 6.3-47 6.3-48 6.3-49 6.3-50 6.3-51 6.3-52 6.3-53 6.3-54 FIGURES 6.3-1,SH 1

6.3-1,SH 2

6.3-2 6.3-3 6.3-4 6

7 0

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7 5

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4 SECTION 6.4 6.4-1 6.4-2 6.4-3 6'-4 6.4-5 6.4-6 6.4-7 6.4-8 6.4-9 6.4-10 6.4-11 6.4-12 6.4-13 FIGURES 6.4-1 SECTION 6.5 6.5-1 6.5-2 6.5-3 6.5-4 6.5-4a 6.5-5 6.5-6 6.5-7 6.5-8 6.5-9 6.5-10 6.5-11 6.5-12 6.5-13 6.5-14 6.5-15 6.5-16 6.5-17 6.5-18 6.5-19 6'-20 10 0

10 10 10 10 6

6 6

6 6.5-21 6.5-22 6.5-23 6.5-24 6.5-25 FIGURES 6.5-1 6.5-2 6'-3 6.5-4 SECTION 6.6 6.6-1 6.6-2 6.6-3 6.6-4 CHlLPTER 7 7-i 7-i i 7-iii 7-iv 7-v 7-vi 7-vii 7-viii 7-ix 7-x SECTION 7.1 7.1-1 7.1-2 7.1-3 7.1-4 7.1-5 7.1-6 7.1-7 SECTION 7.2 7.2-1 7 ~ 2 2 702 3

7 ~.2-4 7.2-5 7.2-6 7.2-6a 7.2-7 7.2-8 7.2-9 7.2-10 7.2-11 7.2-12 7.2-12a 7.2-13 7.2-14 7.2-15 7.2-16 7.2-17 7.2-18 7.2-19 7.2-20 7.2-21 7.2-22 7.2-23 7 '-24 7.2-24a 7.2-25 7.2-26 7.2-27 7.2-28 7.2-29 7.2-30 7.2-31 7.2-32 7.2-33 7.2-34 7.2-35 7.2-36 7.2-37 6

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7.2-38 7.2-39 7.2-40 7.2-41 7.2-42 7.2-43 7.2-44 FIGURES 7.2-1 702-2 7.2-3 7.2-4 7.2-5 7.2-6 7.2-7 7.2-8 7.2-9 7.2-10 7.2-11 7.2-12 7.2-13 7.2-14 7.2-15 7.2-16 7.2-17 7.2-18 7.2-19 7.2-20 7.2-21 SECTION 7.3 7.3-1 7.3-2 7 ~ 3 3

7.3-4 7

7.

7-7 7

7 7

0 0

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10 5

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7 7.3-5 7.3-6 7.3-7 7.3-8 7.3-9 7 '-10 7.3-11 7 '-12 7.3-13 7.3-14 7.3-15 7.3-16 7.3-17

'.3-18 FIGURES 7.3-1,SH 1

7.3-1,SH 2

7.3-2 7.3-3 7.3-4 7.3-5 7.3-6 SECTION 7.4 7.4-1 7.4-2 7.4-3 7.4-4 7.4-5 7.4-6 7.4-7 7.4-8 7'-9 7.4-10 7.4-11 7.4-12 7.4-13 10 7

7 7

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Rev Page No.

Rev SECTION 7.4 7.4-14 7.4-15 7.4-16 7.4-17 7.4-18 7.4-19 7.4-20 7.4-21 7.4-22 7.4-23 7.4-24 7.4-25 7.4-26 7.4-27 7.4-28 SECTION 7.5 7.5-1 7.5-2 7.5-3 7.5-4 7.5-5 7.5-6 7.5-7 7.5-8 7.5-9 7.5-10 7.5-11 7.5-12 7.5-13 7.5-14 7.5-15 7.5-16 7.5-17 7.5-18 7.5-19 7.5-20 7.5-21 7.5-22 7.5-23 7.5-24 7.5-25 7'-26 7.5-27 nnum ere an 6

6 6

10 10 10 9

9*

9 10 9*

9 9

7.5-28 7.5-29 7.5-30 7.5-31 7.5-32 7.5-33 7.5-34 7.5-35 7.5-36 7.5-37 7.5-38 7.5-39 7.5-40 7.5-41 7.5-42 7.5-43 7.5-44 7.5-45 7.5-46 7.5-47 7.5-48 7.5-49 7.5-50 7.5-51 7.5-52 7.5-53 7.5-54 7.5-55 7.5-56 7.5-57 7.5-58 7.5-59 7.5-60 7.5-61 7.5-62 7.5-63 FIGURES 7.5-1 SECTION 7.6 7.6-1 7.6-2 7.6-3 age 9*

9*

9 9

10 9

9 9*

9 10*

10*

9 9

9 7.6-4 7.6-5 SECTION 7.7 7.7-1 7.7-2 7.7-3 7.7-4 7.7-5 7.7-6 7.7-7 7.7-8 7.7-9 7.7-10 7.7-11 7.7-12 7.7-13 7.7-14 7.7-15 7.7-16 7.7-17 7.7-18 7.7-19 7.7-20 7.7-21 7.7-22 7.7-23 7.7-24 7.7-24a 7.7-24b 7.7-24c 7.7-25 7.7-26 7.7-27 7.7-28 7.7-29 7.7-30 7.7-31 7.7-32 7.7-33 7.7-34 7.7-35 7.7-36 7.7-37 7.7-38 6

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0 7.7-39 7.7-40 7.7-41 7.7-42 7.7-43 7.7-44 7.7-45 7.7-46 7.7-47 7.7-48 7.7-49 7.7-50 7.7-51 7.7-52 7.7-53 7.7-54 7.7-55 7.7-56 7.7-57 FIGURES 7.7-1 7.7-2 7.7-3 7.7-4 7.7-4a 7.7-5 7.7-6 7.7-7 7.7-8 7.7-9 7.7-10 7.7-11 7.7-12,SH 1

7.7-12,SH 2

7.7-13 7.7-14 7.7-15 7.7-16 CHAPTER 8 8-i 8-ii 8-iii 8-iv 0

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SECTION 8.1 8.1-1 8.1-2 8.1-3 8.1-4 8.1-5 8.1-6 8.1-7 8.1-8 8.1-9 8.1-10 F 1-11 FIGURES 8.1-1 SECTION 8.2 8.2-1 8.2-2 8.2-3 8.2-4 8.2-5 8'-6 8.2-7 8.2-8 8.2-9 8.2-10 8'-11 8.2-12 8.2-13 8.2-14 8.2-15 8.2-16 8.2-17 8.2-18 FIGURES 8.2-1 5

7 7

10 10 10 10 10 10 10 10 6

10 6

.7 6

6 6

6 7

7 7

SECTION 8.3 8.3-1 8.3-2 8.3-3 8.3-4 8.3-5 8'-6 8.3-7 8.3-8 8.3-9 8.3-10 8.3-11 8.3-12 8.3-12a 8.3-13 8.3-14 8.3-15 8.3-16 8.3-17 8.3-18 8.3-19 8.3-20 8.3-21 8.3-22 8.3-23 8.3-24 8.3-25 8.3-26 8.3-27 8.3-28 8.3-29 8.3-30 8.3-31 8.3-32 8.3-33 8.3-34 8.3-35 8.3-36 8.3-37 8.3-38 8.3-39 8.3-40 8.3-41 8.3-42 5

5 6

9 10 10 9

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10 7

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10 10 10 7

7 8.3-43 8.3-44 8.3-45 8.3-46 8.3-47 8.3-48 8.3-49 FIGURES 8.3-1,SH 1

8.3-1,SH 2

8.3-2 8.3-3 8.3-4 8.3-5 8.3-6 8.3-7 8.3-8 CHAPTER 9 9-i 9-ii 9-iii 9-iv 9-v 9-vi 9-vii 9-viii 9-ix 9-x 9-xi 9-xii 9-xiii 9-xiv 9-xv 9-xvi 10 10 10 10 10 10 10 7

9 9

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Rev SECTION 9.1

9. 1-1 9.1-2 9.1-2a 9.1-3 9.1-4 9.1-5 9.1-6 9.1-7 9.1-8 9.1-9 9.1-10 9.1-11 9.1-12 9.1-13 F 1-14 9.1-15 9.1-16 9.1-17 9.1-18 9,1-19 9.1-20 9.1-21 9.1-22 9.1-23 9.1-24 9.1-25 9.1-26 9.1-26a 9.1-26b 9.1-26c 9.1-26d 9.1-26e 9.1-27 9.1-28 9.1-29 9.1-30 9.1-31 9.1-32 9.1-33 9.1-34 9.1-35 9.1-36 7

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9 9.1-37 9.1-38 9.1-39 9.1-40 9.1-41 9.1-42 9.1-43 9.1-44 9.1-45 9.1-46 9.1-47 9.1-48 9.1-49

9. 1-50 9.1-51 9.1-52 FIGURES 9.1-1 9.1-2 9.1-3 9.1-4 9.1-4a 9.1-5 9.1-6 9.1-7 9.1-8 9.1-9 9.1-10 9.1-11 0

0 2

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SECTION 9.2 9.2-1 9.2-2 9.2-3 9.2-4 9.2-5 9.2-6 9.2-7 9.2-8 9.2-9 9.2-10 9.2-11 9.2-12 9.2-12a 9.2-13 9.2-14 9.2-15 9'-16 9.2-17 9.2-18 9.2-19 9.2-20 9.2-21 9.2-22 9.2-23 9.2-24 9.2-25 9.2-26 9.2-27 9.2-28 9.2-29 9.2-30 9.2-31 9.2-32 9 '-33 9.2-34 9

10 10 10 10 10 10 10 10 10 10 10 10 9

9 10 9

9 9

10 10 10 10 10 10 10 10 FIGURES 9.2-1,SH 1

9.2-1,SH 2

9.2-1,SK 3

9,2-2,SH 1

9.2-2,SH 2

9.2-3 9.2-4,SH 1

9.2-4,SH 2

9.2-4,SH 3

9.2-5 9.2-6,SH 1

9.2-6,SH 2

9.2-6,SH 3

10 10 10 10 10 10 10 10 10 10 10 10 10 SECTION 9.3 9.3-1 9.3-2 9.3-3 9.3-4 9.3-5 9.3-6 9.3-7 9.3-8 9.3-9 9.3-10 9.3-11 9.3-12 9.3-13 9.3-14 9.3-15 9.3-16 9.3-17 9.3-18 9.3-19 9.3-20 9.3-21 9.3-22 9.3-23 9.3-24 9.3-25 9.3-26 9.3-27 9.3-28 9.3-29 9.3-30 9.3-31 9.3-32 9.3-33 9.3-34 9.3-35 9.3-36 9.3-37 9.3-38 9.3-39 9.3-40 9.3-41 9.3-42 9.3-43 9.3-44 9.3-45 9'-46 9.3-47 9.3-48 9.3-49 9.3-50 9.3-51 9.3-52 9 '-53 9.3-54 9.3-55 9.3-56 9.3-57 9.3-58 9.3-59 9.3-60 9.3-61 9 '-62 9.3-63 9.3-64 9.3-65 9.3-66 9.3-67 6

6 6

10 6

6 6

6 7

6 6

6 0

0 0

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9.3-68 9.3-69 9.3-70 9.3-71 9.3-72 9.3-73 9.3-74 9.3-75 FIGURES 9.3-1,SH 1

9.3-1,SH 2

9.3-2,SH 1

9.3-2.SH 2

9.3-3,SH 1

9.3-3,SH 2

9.3-4,SH 1

9.3-4,SH 2

9.3-4,SH 3

9.3-4.SH 4

10 10 10 10 10 10 10 10 10 10 nnum ere an age

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Rev Page No.

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Rev Page Ho.

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Rev FIGURES 9.3-5 9.3-6,SH 1

9.3-6,SH 2

9.3-6,SH 3

9.3-7 9.3-8,SH 1

9.3-8,SH 2

9 '-9.SH 1

9.3-9,SH 2

9.3-9,SH 3

9.3-10,SH 1

9.3-10,SH 2

9.3-11,SH 1

9.3-11,SH 2

9.3-11,SH 3

9.3-11,SH 4

9.3-12 9.3-13,SH 1

9. 3-13, SH 2

9.3-14 9.3-15 9.3-16 9.3-17 9.3-18 9.3-19 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 9

10 10 3

SECTION 9.4 9.4-1 9.4-2 9.4-3 9.4-4 9.4-5 9.4-6 9.4-7 9.4-8 9.4-9 9.4-10 9.4-11 9.4-12 9.4-13 9 '-14 9.4-14a 9.4-15 9.4-16 9.4-17 9.4-18 9.4-19 9.4-20 9.4-21 9.4-22 9.4-23 9.4-24 9.4-25 9.4-26 9.4-27 9.4-28 9.4-29 9.4-30 9.4-31 9.4-32 9.4-33 9.4-34 9.4-35 9.4-36 9.4-37 9.4-38 6

6 2

10 10 10 10 10 10 10 10 10 10 10 10 10 7

9 10 9

7 7

7 10 10 9

9 9

9 7

10 10 10 10 FIGURES 9.4-1 9.4-2 9.4-3 9.4-4 9.4-5 9.4-6 9.4-7 9.4-8 9.4-9 9.4-10 9.4-11 9.4-12 9.4-13 9.4-14 9.4-15 9.4-16 9.4-17 9.4-18 SECTION 9.5 9.5-1 9.5-2 9.5-3 9.5-4 9.5-4a 9.5-5 9.5-6 9.5-7 9.5-8 9.5-9 9.5-10 9.5-11 9.5-12 9.5-13 9.5-14 9.5-15 9.5-16 9.5-17 9.5-18 9.5-18a 9.5-19 9.5-20 9.5-21 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 6

6 6

10 10 6

9 9

10 9

9 10 10 9

9 9

10 10 9

9 9

9.5-22 9.5-23 9.5-24 9.5-25 9.5-26 9.5-27 9,5-28 9.5-29 9.5-30 9.5-31 9.5-32 9.5-33 9.5-34 9.5-35 9.5-36 9.5-37 9.5-38 9.5-39 9.5-40 9.5-41 9.5-42 9.5-43 9.5-44 9.5-45 9.5-46 9.5-47 9.5-48 9.5-49 9.5-50 9.5-51 9.5-52 9.5-53 9.5-54 9.5-55 9.5-56 9.5-57 9.5-58 9.5-59 9.5-60 9.5-61 9.5-62 9.5-63 9

9 9

10 10 10 10 10 10 9

9 9

9 9*

9 9

10 9

9 9

9 FIGURES 9.5-1 9.5-2,SH 1

9.5-2,SH 2

9.5-2a 9.5-2b 9.5-2c,SH 1

9.5-2c,SH 2

9.5-3 9.5-4 9.5-5.SH 1

9.5-5,SH 2

9.5-6 10 10 10 10 10 10 10 6

10 10 10 3

CHAPTER 10 10-i 10-ii 10-iii 10-iv 10-v 10-v i SECTION 10.1 10.1-1 10.1-2 10.1-3 10.1-4 10.1-5 10.1-6 10.1-7 10.1-8 10.1-9 10.1-10 10.1-11 10 7

7 7

6 6

7 10 10 SECTION 10.2 10.2-1 10.2-2 10.2-3 10.2-4 10.2-5 10.2-6 10.2-7 10.2-8 10.2-9 10.2-10 10.2-11 10.2-12 FIGURES 10.2-1 6

6 10 10 10 10 10 10 10 10 10 10 r

M 0

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Rev SECTION 10.3 10.3-1 10'-2 10'-3 10.3-4 10.3-5 10.3-6 10.3-7 10.3-8 10.3-9 10.3-10 FIGURES 10.3-1 10.3-2 10.3-3,SH 1

10,3-3,SH 2

10.3-4,SH 1

10.3-4,SH 2

SECTION 10.4 10.4-1 10.4-2 10.4-3 10.4-4 10.4-5 10.4-6 10.4-7 10.4-8 FIGURES 10.4-1 10.4-2 10'-3 10.4-4,SH 1

10.4-4,SH 2

10.4-5 SECTION 10.5 10.5-1 10.5-2 0

0 0

10 7

7 10 7

7 7

10 10 10 10 10 10 4

0 7

10 2

7 7

7 10 10 10 10 10 10 10.5-3 10.5-4 10.5-5 10.5-6 10.5-7 10.5-8 10.5-9 10.5-10 10.5-11 10.5-12 10.5-13 10.5-14 FIGURES 10.5-1 10.5-2 SECTION 10.6 10.6-1 10.6-2 10.6-3 10.6-4 10.6-5 10.6-6 FIGURES 10.6-1,SH 1

10.6-1,SH 2

10.6-2 10.6-3 SECTION 10.7 10.7-1 10.7-2 10.7-3 10.7-4 10.7-5

" nnum ere an Page 7

6 10 9

7 6

6 6

10 10 10 10 0

0 10.7-10.7-6a 10.7-7 10.7-8 10.7-9 10.7-10 10.7-11 10.7-12 10.7-13 10.7-14 10.7-15 10.7-16 10.7-17 10.7-18 10.7-19 10.7-20 10.7-21 10 '-22 10.7-23 10.7-24 10.7-25 10.7-26 FIGURES 10.7-1 10.7-2 10.7-3 10.7-4 10.7-5 10.7-6,SH 1

10.7-6,SH 2

10.7-7 10.7-8 10.7-9 10.7-10

10. 7-11, SH 10.7-11,SH 2

10. 7-12, SH 1

10. 7-12, S H 2 10.7-13 CHAPTER 11 11-i 11-i i 11-i i i 11-iv 11-v 9

6 9

6 6

10 6

7 6

6 6

6 7

7 10 9

10 10 10 10 10 10 9

10 10 10 10 10 10 10 7

10 7

10 6

SECTION 11.1 11.1-1 11.1-2 11.1-3 11.1-4 11.1-5 11.1-6 11.1-7 SECTION 11.2 11.2-1 11.2-2 11.2-3 11.2-4 11.2-5 11.2-6 11.2-7 11.2-8 11.2-9 11.2-10 11.2-11 11.2-12 11.2-13 11.2-14 11.2-15 11.2-16 11.2-17 11.2-18 11.2-19 11.2-20, 11.2-21 11.2-22 11.2-23 11.2-24 11.2-25 11.2-26 7

6 6

10 10 0

0 0

0 6

10 7

7 7

7 10 0

0 0

0 2

2 2

FIGURES 11.2-1 11.2-2,SH 1

11.2-2,SH 2

11.2-3,SH 1

11.2-3.SH 2

11.2-4 11.2-5 SECTION 11.3 11.3-1 11.3-2 11.3-3 11.3-4 11.3-5 11.3-6 11.3-7 11.3-8 11.3-9 11.3-10 11.3-11 11.3-12 FIGURES 11.3-1 11.3-2,SH 1

11.3-2,SH 2

SECTION 11.4 11.4-1 11.4-2 11.4-3 11.4-4 11.4-5 11.4-6 11.4-7 SECTION 11.5 11'-1 11.5-2 11.5-3 10 10 10 10 9

10 10 10 10 10 4

7 10 11.5-4 11.5-5 11.5-6 11.5-7 11.5-8 11.5-9 11.5-10 11.5-11 11 '-12 11.5-13 11.5-14 11.5-15 11.5-16 11.5-17 FIGURES 11.5-1 11.5-2 CHAPTER 12 12-i 12-ii 12-iii 12-iv SECTION 12.1 12.1-1 12.1-2 12.1-3 SECTION 12.2 12.2-1 12.2-2 12.2-3 12.2-4 12.2-5 12.2-6 12.2-7 10 10 10 10 10 10 10 7

10 10 7

10 7

10 10 0

10 6

10 10 SECTION 12.3 12.3-1 12.3-2 12.3-3 12.3-4 12.3-5 12.3-6 12.3-7 12.3-8 12.3-9 12.3-10 12.3-11 12.3-12 12.3-13 12.3-14 12.3-15 12.3-16 12.3-17 12.3-18 12.3-19 12.3-20 12.3-21 12.3-22 12.3-23 12.3-24 12.3-25 FIGURES 12.3-1 SECTION 12.4 12.4-1 12.4-2 12.4-3 12.4-4 0

0 0

10 0

0 10 10 3

3 10 10 0

0 0

4 0

0 4

7 10 0

0 0

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Rev SECTION 12.4 12.4-5 12.4-6 12.4-7 12.4-8 12.4-9 12.4-10 12.4-11 12.4-12 12.4-13 12'-14 12.4-15 12.4-16 12.4-17 12.4-18 12.4-19 12.4-20 12.4-21 12.4-22 12.4-23 12.4-24 12.4-25 SECTION 12.5 12.5-1 12.5-2 12.5-3 12.5-4 12.5-5 12.5-6 12.5-7 12.5-8 12.5-9 10 10 10 10 10 10 10*

10 FIGURES 12.5-1 CHAPTER 13 13-i 13-i i 13-i i i 13-iv 13-v SECTION 13.1 13.1-1 13.1-2 13.1-3 13.1-4 13.1-5 13.1-6 13.1-7 13.1-8 13.1-9 13.1-10 13.1-11 13'-12 13.1-13 13.1-14 13.1-15 13.1-16 13.1-17 13.1-18 13.1-19 13.1-20 13.1-21 13.1-22 13.1-23 FIGURES 13.1-1 13.1-2 13.1-3 13.1-4 10 10 10 10 6

10 6

10 10 10 7

7 7

7 10 10 7

7 10 10 10 10 10 10 10 10 10 10 10 10 7

13.1-5 13.1-6 13.1-7 SECTION 13.2 13.2-1 13.2-2 13.2-3 13.2-4 13.2-5 13.2-6 13.2-7 13.2-8 13.2-9 SECTION 13.3 13.3-1 SECTION 13.4 13.4-1 13.4-2 13.4-3 13.4-4 13.4-5 13.4-6 13.4-7 13.4-8 13.4-9 13.4-10 13.4-11 FIGURES 13.4-1 7

10 7

6 6

6 9

10 10 10 0

6 10 10 9

6 10 6

6 7

6 6

10 SECTION 13.5 13.5-1 13.5-2 13'-3 13.5-4 13.5-5 13.5-6 13.5-7 13.5-8 13.5-9 SECTION 13.6 13.6-1 CHAPTER 14 14-i 14-i i 14-i i i 14-iv 14-v 0

2 2

0 0

10 10 0

0 14-vi SECTION 14.1 14.1-1 14.1-2 14.1-3 14.1-4 14.1-5 14.1-6 14.1-7 14.1-8 14.1-9 14.1-10 14.1-11 14.1-12 14.1-13 14.1-14 14.1-15 14.1-16 14.1-17 14.1-18 14.1-19 14.1-20 14.1-21 14.1-22 14.1-23 14.1-24 14.1-25 14.1-26 SECTION 14.2 14,2-1 14.2-2 14.2-3 FIGURES 14.2-1 SECTION 14.3 14.3-1 SECTION 14.4 14.4-1 14.4-2 14.4-3 SECTION 14.5 14.5-1 14.5-2 SECTION 14.6 14.6-1 14.6-2 14.6-3 14.6-4 14.6-5 14.6-6 14.6-7 14.6-8 14.6-9 14,6-10 14.6-11 14.6-12 14.6-13 14.6-14 14.6-15 14.6-16 14.6-17 14.6-18 14.6-19 14.6-20 14.6-21 14.6-22 14.6-23 14.6-24 14.6-25 14.6-26 14.6-27 14.6-28 14.6-29 14.6-30 14.6-31 14.6-32 14.6-33 14.6-34 14.6-35 14.6-36 14.6-37 14.6-38 14.6-39 14.6-40 14.6-41 14.6-42 14.6-43 14.6-44 14.6-45 14.6-46 14.6-47 14.6-48 14.6-49 14.6-50 14.6-51 14.6-52 14.6-53 14.6-54 14.6-55 14.6-56 14.6-57 14.6-58

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Rev SECTION 14.6 14.6-59 14.6-60 14.6-61 14.6-62 14.6-63 14.6-64 14.6-65 14.6-66 14.6-67 14.6-68 14.6-69 14.6-70 14.6-71 FIGURES 14.6-1 SH 1

14.6-1 SH 2

14.6-2 SH 1

14.6-2 SH 2

14.6-2 SH 3 14 F 6-2 SH 4

14.6-3 14.6-4 SH 1

14.6-4 SH 2

14.6-5 14.6-6 14.6-7 SH 1

14.6-7 SH 2

14.6-7 SH 3 14.6-7 SH 4 14.6-8 SH 1

14.6-8 SH 2

14.6-9 SH 1

14.6-9 SH 2

14.6-9 SH 3 "Unnumbered Blank Page 14.6-9 SH 4 14.6-9 SH 5 14.6-10 SH 1

14.6-10 SH 2

14.6-11 14.6-12 14 '-13 SH 1

14.6-13 SH 2 14.6-13 SH 3

14.6-13 SH 4 14.6-13 SH 5 14.6-14 14.6-15 14.6-16 14.6-17 14.6-18 14.6-19 14.6-20 14.6-21 14.6-22 14.6-23 14.6-24 CHAPTER 15 15-i 15-ii 15-iii 15-iv v 15-vi 15-vi i 15-viii 15-ix 15-x 15-xi 15-xi i 15-xiii 15-xiv 15-xv 15-xv i 7

7 7

10 10 10 10 7

10 7

7 7

10 10 15-xvii 15-xviii 15-xix 15-xx 15-xxi SECTION 15.0 15.0-1 15.0-2 15.0-3 15.0-4 15.0-5 15.0-6 15.0-7 15.0-8 15.0-9 15.0-10 15.0-10a 15.0-11 15.0-12 15.0-13 15.0-14 15.0-15 15.0-16 FIGURES 15.0-1 15.0-2 15.0-3 SECTION 15.1 15.1-1 15.1-2 15.1-3 15.1-4 15.1-5 15.1-6 15'-7 15.1-8 15.1-9 15.1-10 15.1-11 10 7

7 7

7 9

10 10 6

6 6

10 6

6 6

9 4

10 4

4 4

4 15.1-12 15.1-13 15.1-14 15.1-15 15.1-16 15.1-17 15.1-18 15.1-19 15.1-20 15.1-21 15.1-22 15.1-23 15.1-24 15.1-25 15.1-26 15.1-27 15.1-28 15.1-29 15.1-30 15 '-31 15.1-32 15.1-33 15.1-34 15.1-35 15.1-36 FIGURES 15.1-1 15.1-2 15.1-3 15.1-4 15.1-5 15.1-6 15.1-6a 15.1-6b 15.1-6c 15.1-7 15.1-8 15.1-9 15.1-10 15.1-11 15.1-12 15.1-13 15.1-14 15.1-15 15.1-16 0

0 0

0 ~

7 7

7 4

4 4

15.1-17 15.1-18 15.1-19 15.1-20 15.1-21 15.1-22 15.1-23 15.1-24 15.1-25 15.1-26 15.1-27 15.1-28 15.1-29 15.1-30 15.1-31 15.1-32 15 '-33 15.1-34 15 '-35 15.1-36 15.1-37 15.1-38 15.1-39 15.1-40 15.1-41 15.1-42 15.1-43 15.1-44 15.1-45 15.1-46 15.1-47 15.1-48 SECTION 15.2 15.2-1 15.2-2 15.2-3 15.2-4 15.2-5 15.2-6 15.2-7 15.2-8 15.2-9 15.2-10 15.2-11 15.2-12 15.2-13 4

4 0

0 0

0'0 7

7 7

15.2-14 15.2-15 15.2-16 15.2-17 FIGURES 15.2-1 15.2-2 15.2-3 15'-4 15.2-5 15.2-6 15.2-7 15.2-8 15.2-9 15.2-10 15.2-11 15.2-12 15.2-13 15.2-14 SECTION 15.3 15.3-1 15.3-2 15.3-3 15.3-4 15.3-5 15.3-6 15.3-7 15.3-8 15.3-9 15.3-10 15.3-11 15.3-12 15.3-13 FIGURES 15.3-1 15.3-2 15.3-3 15.3-4.

15.3-5 15.3-6 15.3-7 15.3-8

, 15,3-9 15.3-10 SECTION 15.4 15.4-1 15.4-2 15.4-3 15.4-4=

15.4-5 15.4-6 15.4-7 15.4-8 15.4-9 15.4-10 15.4-11 15.4-12 15.4-12a 15.4-13 15.4-14 15.4-15 15.4-16 15 '-17 15.4-18 15.4-18a 15.4-18b 15.4-19 15.4-20 15.4-21 15.4-22 15.4-23 15.4-24 15.4-25 15.4-26 15.4-27 15.4-28 15.4-29 6'6 6

10 6

6 6

4 4

0 0

7 0

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10 10 10 0

10

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Rev SECTION 15.4 15.4-30 15.4-31 15.4-32 15 '-33 15.4-34 15.4-35 15.4-36 15.4-37 15.4-38 15.4-39 15.4-40 15.4-41 15.4-42 FIGURES 15.4-1 15'-2 15.4-3 15.4-4 15.4-5 15.4-6 15.4-7 15.4-8 15.4-9 15.4-10 15.4-11 15.4-12 15.4-13 15.4-14 15.4-15 15.4-16 15.4-17 15.4-18 15.4-19 10 10 10 10 10 10 10 10 10 10 10 10 10 10 4

4 4

0 0

10 10 10 10 SECTION 15.5 15.5-1 SECTION 15.6 15.6-1 15.6-2 15.6-3 15.6-4 15.6-5 15.6-6 15.6-7 15.6-8 15.6-9 15.6-10 15.6-11 15.6-12 15.6-13 15.6-14 15.6-15 15.6-16 15.6-17 15.6-18 15.6-19 15.6-20 15.6-21 15.6-22 15.6-23 15.6-24 15.6-25 15.6-26 15.6-26a 15.6-26b 15.6-26c 15.6-26d 15.6-26e 15.6-26f 15.6-27 15.6-28 15.6-29 15.6-30 15.6-31 15.6-32 15.6-33 0

7 6

6 6

6 7

7 7

7 10 10 7

7 7

9 7

7 7

10 7

7 0

0 0

15.6-34 15.6-35 15.6-36 15.6-37 15.6-38 15.6-39 15.6-40 15.6-41 15.6-42 15.6-43 15.6-44 15.6-45 15.6-46 15.6-47 15.6-48 15.6-49 FIGURES 15.6-1 15.6-2 15.6-3 15.6-4 15.6-5 15.6-6 15.6-7 15.6-8 15.6-9 15.6-10 15.6-11 15.6-12 15.6-13 15.6-14 15.6-15 15.6-16 15.6-17 15.6-18 15.6-19 15.6-20 15.6-21 0

0 0

0 10 0

0 0

4 4

4 15.6-22 15.6-23 15.6-24 15.6-25 15.6-26 15.6-27 15.6-28 15.6-29 15.6-30 15.6-31 15.6-32 15.6-33 15.6-34 15.6-35 15.6-36 15.6-37 15.6-38 15.6-39 15.6-40 15.6-41 15.6-42 15.6-43 15 '-44 15.6-45 15.6-46 15.6-47 15.6-48 15.6-49 15.6-50 15.6-51 15.6-52 15.6-53 15.6-54 15.6-55 15.6-56 15.6-57 15 F 6-58 15.6-59 15.6-60 15.6-61 15.6-62 15.6-63 0

0.

0 0

0 4

0 0

4 4

0 0

4 0

0 4

0 0

4 0

0 4

0 0

4 0

0 4

0 0

4 0

0 4

0 0

4 0

15.6-64 15,6-65 15.6-66 15.6-67 15.6-68 15.6-69 15.6-70 15.6-71 15.6-72

- 15.6-73 15.6-74 15.6-75 SECTION 15.7 15.7-1 15.7-2 15.7-3 15.7-4 15.7-5 15.7-6 15.7-7 15.7-8 15.7-9 15.7-10 15.7-11 15.7-12 15.7-13 15.7-14 15.7-15 15.7-16 15.7-17 15.7-18 15.7-19 15.7-20 15.7-21 15.7-22 15.7-23 FIGURES 15.7-1 SECTION 15.8 15.8-1 15.8-2 15.8-3 CHAPTER 17 17-i 17-i l SECTION 17.1 17.1-1 17.1-2 17.1-3 17.1-4 17.1-5 17.1-6 17.1-7 17.1-8 17.1-9 17.1-10 17 F 1-11 17.1-12 17.1-13 17.1-14 17 '-15 17.1-16 17.1-17 17.1-18 17.1-19 17.1-20 17.1-21 17.1-22 17.1-23 FIGURES 17.1-1 SECTION 17.2 17.2-1

Unnumbered Blank Page

GINNA/UFSAR 8.

Waste holdup tank.

9.

Various operations panels.

10.

Waste evaporator.

11.

Blender room.

12.

Spent resin tanks.

13.

Safety injection filters.

14.

Seal injection filters.

15.

Containment spray pumps.

16.

Nonregenerative heat exchanger.

17.

Seal return filter and cooler.

18.

Charging pump rooms and accumulator.

19.

Sodium hydroxide tank and leakoff tank.

20.

Safety injection pumps (three).

Auxiliar Buildin

- Intermediate Level See Fi ure 1.2-11 1.

Spent fuel pool filter and heat exchanger.

2.

Chemical and volume control system holdup tanks.

3.

Residual heat removal heat exchangers.

4.

Waste gas compressors and gas stripper.

5.

Gas decay tanks (four).

6.

Reactor coolant filter.

7.

Volume control tank.

8.

Concentrates holding tank and transfer pump.

9.

Demineralizer vault.

10.

High efficiency particulate air filters.

ll.

Nonregenerative heat exchanger.

12.

480-V bus 16 (vital bus)

~

13.

Charcoal filter unit.

14.

Motor control center 1D.

15.

Motor control center 1M.

Auxilia Buildin

- 0 eratin Floor See Fi ure 1.2-12 1.

Decontamination pit.

2.

Spent fuel storage pool, crane, and transfer canal.

3.

New fuel unloading area.

1.2-5 REV 2 12/86

GINNA/UFSAR 4.

New fuel storage racks.

5.

Crane bay.

6.

Refueling water storage tank (all levels).

7.

Component cooling pumps.

8.

Component cooling water heat exchangers and surge tank.

9.

Boric acid demineralizers.

10.

Monitor tanks and pumps.

ll.

Waste condensate tanks.

12.

Reactor makeup water tank and pumps.

13.

Drumming station and drum storage area.

14.

480-V bus 14 (vital bus).

15.

Auxiliary building supply fan and filter.

16.

Boric acid batching tank.

17.

Boric acid tank and pumps.

18.

Waste condenser demineralizer.

19.

Motor control center 1C.

20.

Motor control center 1L.

21.

Motor control center lE.

1.2.3.4 Intermediate Buildin See Fi ures 1.2-6 1.2-7 1.2-8 and 1.2-14.

4 The intermediate building surrounds the containment building to the west and north and joins the service building and turbine building. It is divided into two sections called the hot side (restricted area access) and the cold side.

Hot Side Restricted Area Access 10 The hot side is west of the containment building and joins the auxiliary building.

The intermediate building hot side extends from the spent fuel pool access to the Radiation Protection control desk and has three levels.

The area contains 10 the Radiation Protection control access

desk, the primary sample room, the postaccident sampling system sample panel, and the hydrogen recombiner panel.

It also contains ventilation units for several systems including the con-trolled access area exhaust fans and filter, main auxiliary exhaust fans and filter, auxiliary exhaust fan 1C, and the spent fuel pool charcoal filters.

1.2-6 REV 10 12/93

GINNA/UFSAR relay room is directly below the control room and houses relay racks and the MUX room.

The battery rooms and the air handling room are on the lowest level 3"

of the control building.

1.2.3.7 All-Volatile-Treatment Buildin The all-volatile-treatment building houses demineralizers and other equipment necessary for the condensate polishing system to allow all-volatile-treatment of secondary water (see Figure 1.2-16).

I7 The technical support center is located on the second floor of the all-volatile-treatment building and houses the computers and equipment, including emergency power supplies (diesel generator and batteries),

necessary to pro-vide the staff technical support during an emergency event (see Figure 1.2-17).

)7 1.2.3.8 Standb Auxilia Feedwater Pum Buildin The standby auxiliary feedwater pump building is located on the southeast corner of the auxiliary building and houses the two standby auxiliary feed-water pumps and the 10,000-gal condensate supply tank.

The building is a Seismic Category I concrete structure supported by caissons (see Figure 1.2-18).

1.2.3.9 Screen House The screen house is located north of the turbine building on Lake Ontario and houses the main circulating water inlet lines and pumps; the service water pumps (four); 480-V switchgear buses 17 and 18, the diesel fire pump, the motor-driven fire pump, and motor control centers 1G1 and 1G2 (see Figure 1.2-19).

1.2.3.10 Service Buildin The service building is located at the west end of the auxiliary building.

This building provides the office spaces for the administrative staff at Ginna Station (see Figures 1.2-20 and 1.2-21).

1.2-9 REV 7 12/91

GINNA/UFSAR The service building has two levels.

The basement level is comprised of store-

rooms, machine shops, maintenance

areas, etc.

The ground floor level of the service building houses the following areas:

1.

Radiation Protection.

2.

Chemistry.

3.

Engineering.

4.

Shift technical advisors.

5.

Cafeteria.

6

~

Mechanical equipment.

7.

Laboratories.

8.

First Aid room.

9.

Central records.

10.

Main office.

ll.

Quality control office.

12.

Maintenance office.

13.

Plant superintendent's office.

14.

Men's locker room.

15.

Women's locker room.

16.

Technical office.

17.

Planning office.

I 10, (10 The locker rooms are used as the change areas for donning or removing protec-tive clothing used in the auxiliary building, intermediate building, and containment.

1.2.3.11 Diesel Generator Buildin The diesel generator building adjoins the turbine building on the east end of 5

the north wall opposite the control building.

The building is a one-story reinforced-concrete structure that houses the emergency diesel generators.

1.2.4 NUCLEAR STEAM SUPPLY SYSTEM The nuclear steam supply system consists of a pressurized water reactor, reactor coolant system, and associated auxiliary fluid systems.

The reactor coolant system is arranged as two closed reactor coolant loops connected in REV 10 12/93

GINNA/UFSAR parallel to the reactor vessel, each containing a reactor coolant pump and a O

steam generator.

An electrically heated pressurizer is connected to one of the loops (loop B).

The reactor core is composed of uranium dioxide pellets enclosed in zircaloy tubes with welded end plugs.

The tubes are supported in assemblies by a grid structure.

The mechanical control rods consist of clusters of stainless steel clad absorber rods and guide tubes located within the fuel assembly.

The core fuel is divided into several regions.

The steam generators are'ertical U-tube units containing Inconel tubes.

Integral separating equipment reduces the moisture content of the steam at the turbine throttle to 0.25% or less.

The reactor coolant pumps are vertical, single-stage, centrifugal pumps equipped with controlled leakage shaft seals, Auxiliary systems are provided to add makeup water to the reactor coolant system, purify reactor coolant water, provide chemicals for corrosion inhibi-tion and reactor control, cool system components, remove residual heat when the reactor is shut down, cool the spent fuel storage pool, sample reactor coolant water, provide for emergency safety injection, vent and drain the reactor coolant system, and for other purposes..

1.2.5 REACTOR AND PLANT CONTROL The reactor is controlled by a coordinated combination of chemical shim and mechanical control rods.

The control system allows the plant to accept step load increases of 10% and ramp load increases of 5% per minute over the load range of 12.8% to 100%.

Similar step and ramp load reductions are possible over the range of 100% to 12.8%.

Complete supervision of both the nuclear and turbine generator plants is accomplished from the cen'tral control room.

This supervision includes the capability to test periodically the operability of the reactor protection system.

1.2-11 REV 5 12/89

GINNA/UFSAR 1.2.6 WASTE DISPOSAL SYSTEM The waste disposal system provides all equipment necessary to collect, process, and prepare for disposal all potentially radioactive liquid, gaseous, and solid wastes produced as a result of reactor operation.

Liquid wastes requiring cleanup before release are collected and processed by a vendor supplied demineralization system.

After appropriate cleaning and filtering, the liquid is collected in the chemical and volume control system monitor tank A for ultimate release to the circulating water discharge canal at a concentration below 10 CFR 20 limits.

The spent demineralizer resin is packaged and shipped from the site for ultimate disposal in an authorized location.

Liquid wastes were also processed by the waste evaporator system until 1990 when use of the evaporator was discontinued.

Gaseous wastes are collected and stored until their radioactivity level is low enough so that discharge to the environment does not create radioactivity con-centrations above 10 CFR 20 limits.

Solid wastes including evaporator concentrates are packaged and shipped from the site for ultimate disposal in an authorized location.

Wet solid wastes are solidified.

Dry solid wastes are shipped in bulk form to a vendor for volume 7

reduction and packaging for delivery to a disposal site.

Operating procedures generally limit normal effluents to within 10 CFR 50, Appendix I, limits.

Sanitary waste from Ginna Station is piped into the Town of Ontario, New York, sewer system.

1.2.7 FUEL HANDLING SYSTEM The reactor is refueled with equipment designed to handle spent fuel under water from the time it leaves the reactor vessel until it is placed in a cask for shipment from the site.

Underwater transfer of spent fuel provides an optically transparent radiation shield, as well as a reliable source of coolant for removal of decay heat.

1. 2. 8 TURBINE AND AUXILIARIES The turbine is a tandem-compound, three-cylinder, 1800-rpm unit having 40-in.

exhaust blading in the low-pressure elements.

Four combination moisture 1.2-12 REV 7 12/91

GINNA/UFSAR REFERENCES FOR SECTION 1.5 1.

P.

M.

Wood, E.

A. Bassler, et al.,

Use of Burnable Poison Rods in Westin house Pressurized Water Reactors, WCAP 7113, October 1967.

2.

Westinghouse Electric Corporation, Nuclear Desi n of Westin house Pressurized Water Reactor with Burnable Poison Rods, WCAP 9000 Series (Proprietary),

1968.

3.

Westinghouse Electric Corporation, Power Distribution Control of Westin house Pressurized Water

Reactors, WCAP

7208, (Proprietary),

October 1968.

4.

Connecticut Yankee Atomic Power

Company, Connecticut Yankee Charcoal Filter Tests, CYAP 101, December 1966.

5.

R.

E.

Adams and W.

E.

Browning, Jr.,

Removal of Radiodine from Air Streams b

Activated Charcoal, USAEC'Report ORNL 2872, Oak Ridge National Laboratory, April 1, 1960.

6.

R.

E.

Adams and W.

E.

Browning, Jr.,

Removal of Radioiodine from Air-Stream Mixtures, Report (ORNL Central Files No.)

CF 60-11-39, Oak Ridge National Laboratory, November 14, 1960.

7.

G.

H. Prigge, A lication of Activated Carbon in Reactor Containment,

, USAEC Report No.

DP 778, E. I. duPont deNemours

& Co.,

Savannah River Laboratory, September 1962.

II 8.

R.

E.

Adams and R.

D. Ackley, Removal of Elemental Radioiodine from Flowin Humid Air b

Iodized Charcoals (Abstract),

USAEC Report ORNL TM-2040, Oak Ridge National Laboratory, November 2,

1967.

9.

Westinghouse Electric Corporation, A Controlled Combustion S stem to Prevent H dro en Accumulation Followin a Loss-of-Coolant

Accident, WCAP 900 (Confidential),

1969.

1.5-17

O.

GINNA/UFSAR 1.6 MATERIAL INCORPORATED BY REFERENCE This section lists topical reports, which are referenced in the original and Updated FSAR and which have been submitted to the AEC/NRC, in support of the Ginna or other licensing applications and/or significant reviews.

It includes (9

the UFSAR section that cites the report when applicable.

Title UFSAR Sections L. S.

Tong, et al.,

HYDNA Di ital Com uter Pro ram for H dro-d namic Transient, CVNA 77, 1961.

Gilbert Associates, Inc., Structural Inte rit Test of Reactor Containment Structure, GAI Report No. 1720, October 3, 1969.

1.8 Gilbert Associates, Inc., Effects of Postulated Pi e Breaks Outside the Containment Buildin

, GAI Report No.

1815 transmitted by letter from K. W. Amish, RG&E, to A. Giambusso, NRC, November 1973.

3.11 R.

C. Daniel, et al., Effects of Hi h Burnu on Zircalo -Clad Bulk Uranium Dioxide Plate Fuel Element Sam les, WAPD 263, September 1965.

H. Amster and R. Saarez, The Calculation of Thermal Constants Avera ed Over a Win ner-Wilkins Flux S ectrum:

Descri tion of the SOFOCATE Code, WAPD TM-39, January 1957.

9.1 H. Bohl, E. Gelbard, and G. Ryan, MUFT-4--Fast Neutron S ectrum Code for the IBM-707, WAPD TM-72, July 1957.

9,1 W. R. Cadwell, PD 4

A Pro ram for the Solution of the Neutron Diffusion E uations in Two-Dimensions on the Phileo-2000, WAPD TM-230, 1961.

1.6-1 REV 9 12/92

GINNA/UFSAR Title UFSAR Sections J. A. Redfield, CHICK-KIN - A Fortran Pro ram for Intermediate and Fast Transients in a Water Moderated Reactor, WAPD TM-479, January 1965.

J. A. Redfield, J.

H. Murphy, V. C. Davis, FLASH-2:

A Fortran IV Pro ram for Di ital Simulation of a Multinode Reactor Plant Durin Loss'f Coolant, WAPD TM-666, April 1967.

3.6 W. R. Cordwell, PD -7 Reference

Manual, WAPD-TM-678, January 1967.

9.1 T. A. Porsching, J.

H. Murphy, J. A. Redfield, and V. C. Davis, FLASH-4:

A Full Im licit FORTRAN-IV Pro ram for the Di ital Simulation of Transients in a Reactor Plant, WAPD TM-840, March 1969.

3.6, 15.6 Westinghouse Electric Corporation, A Controlled Combustion S stem to Prevent H dro en Accumulation Followin a Loss-of-Coolant

Accident, WCAP 900 (Confidential),

1969.

1.5 D. G.

Sammarone, The Galvanic Behavior of Materials in Reactor

Coolants, WCAP 1844, August 1961.

9.3 R. F. Barry, The Revised LEOPARD Code-A S ectrum De endent Non-S atial De letion Pro ram, WCAP 2759, March 1965.

G. Hestroni, Studies of the Connecticut-Yankee H draulic Model, WCAP 2761, 1965.

4 ~ 4 R. F. Barry, LEOPARD - A S ectrum De endent Non S atial De letion 9.1 Code for the IBM-7094, WCAP 3269, September 1963.

G. Hestroni, H draulic Tests of the San Onofre Reactor Model, WCAP 3269-8, 1964.

4.4 L. E, Strawbridge, Calculations of Lattice Parameters and Criti-calit for Uniform Water Moderated Lattices, WCAP 3269-25, 1964.

1.6-2 REV 9 12/92

GINNA/UFSAR Title UFSAR Sections W. T. Sha, An Ex erimental Evaluation of the Power Coefficient in Sli htl Enriched PWR Cores, WCAP 3269-40, 1965.

W. T. Sha, An Anal sis of Reactivit Worth of the Rod Cluster Control Elements and Local Water Hole Power Densit Peakin WCAP 3269-47, 1965.

Lar e Closed C cle Water Reactor Research and Develo ment Pro ram uarterl Pro ress Re orts, WCAP 3738,

3739, 3750, 3269-2, 3269-5, 3269-6, 3269-12, and 3269-13, January 1963 through June 1965.

4.2 of Irradiated Uranium Dioxide, WCAP 6065, February 1965.

H. Chelemer, T. Weisman, and L. S.

Tong, Subchannel Thermal Anal sis of Rod Bundle Cores, WCAP 7015, January 1967.

H. Chelemer, J.

Weisman, and L. S.

Tong, Subchannel Thermal Anal sis of Rod Bundle Cores, WCAP 7015, Revision 1, January 1969.

4.4 P.

M. Wood, E. A. Bassler, P.

E. MacDonald, and D. F. Paddleford, 1.5 Use of Burnable Poison Rods in Westin house Pressurized Water

Reactors, WCAP 7113, October 1967.

M. J. Bell, et al., Investi ations of Chemical Additives for Reactor Containment S ra s, WCAP 7153 (Proprietary),

March 1968.

6.1, 6.2 6.5 L. F. Picone, Evaluation of Protective Coatin s for Use in Reactor 6.1 Containment, WCAP 7198-L (Proprietary), April 1969.

Westinghouse Electric Corporation, Power Distribution Control of Westin house Pressurized Water Reactors, WCAP 7208 (Propri-etary),

October 1968.

1.5 7 '

1.6-3 REV 9 12/92

GINNA/UFSAR Title UFSAR Sections Westinghouse Electric Corporation, Rochester Gas and Electric RE E. Ginna Unit 1 Reactor Vessel Radiation Surveillance Pro ram, WCAP 7254, May 1969.3 T. W. T. Burnett, Reactor Protection S stem Diversit in Westin -

7.1 house Pressurized Water Reactors, WCAP 7306, April 1969.

We'stinghouse Electric Corporation, Reactor Containment Fan Cooler Coolin Test Coil, WCAP 7336-L, July 1969.

6.2 Westinghouse Electric Corporation, Performance of Zircalo -Clad Fuel Rods Durin a Simulated Loss-of-Coolant Accident - Multirod Burst Tests, WCAP 7379-L, Vol. I (Proprietary),

September 5, 1969.

Westinghouse Electric Corporation, Sensitized Stainless Steel in Westin house PWR Nuclear Steam Su l S stems, WCAP 7477-L, WCAP 7477-L Addendum I, WCAP 7735 (Non-Proprietary),

accepted by the AEC May 15, 1973.

1.8 W. C. Gangloff, M. A. Mangan, An Evaluation of Antici ated 0 era-tional Transients in Westin house Pressurized Water Reactors, WCAP 7486-L, December 1970.'

Westinghouse Electric Corporation, Performance of Zircalo -Clad Fuel Rods Durin a Simulated Loss-of-Coolant Accident - Multirod Burst Tests, WCAP 7495-L, Vol. I and II (Proprietary), July 12, 1970.

Westinghouse Electric Corporation, Power Distribution Monitorin in the R.

E. Ginna

PWR, WCAP 7542-L, September 1970.

14.6 P.

F. Riehm, D. C. Garner, M. A. Mangan, Anal sis of Antici ated Reactor Transients Without Tri WCAP 7655, February 1971.

1.6-4 REV 9 12/92

GINNA/UFSAR Title UFSAR Sections Westinghouse Electric Corporation, R.

E. Ginna March 1971 Refuelin Shutdown Reactor Internals and Core Com onent Evalua-

tion, WCAP 7780, 1971.

1.8 Westinghouse Electric Corporation, Radiolo ical Conse uences of a Fuel Handlin

Accident, WCAP 7828, 1971.

F

15. 7 J.

Shefcheck, A lication of the THINK Pro ram to PWR Desi n, WCAP 7838, January 1972.

4.4 T. W. T. Burnett, et al.,

LOFTRAN Code Descri tion, WCAP 7907, June 1972.

15.0 6.2 Westinghouse Electric Corporation, LOFTRAN Code Descri tion WCAP 7907, October

1972, WCAP 7907 Supplement, May 1978.

5.2 H.

G. Hargrove, FACTRAN - A Fortran IV Code for Thermal Tran-sients in a Uranium Dioxide Fuel Rod, WCAP 7908, June 1972.

15.0 15.4 W. S. Hazelton, S. L. Anderson, and S.

E. Yanichko, Basis for Heatu and Cooldown Limit Curves, WCAP 7924, July 1972.

5.1 H. Chelemer, et al.,

THING IV - An Im roved Pro ram for Thermal H draulic Anal sis of Rod Bundle Cores, WCAP 7956, June 1973.

4.2 15.0, 15.4 H. Chelemer, et al.,

THING IV - An Im roved Pro ram for Thermal H draulic Anal sis of Rod Bundle Cores, WCAP 7956-P-A (Proprietary),

February 1989.

4,4 D.

H. Risher Jr.,

and R. F. Barry, TWINKLE - A Multidimensional 15.0, 15.4 Neutron Kinetics Com uter Code, WCAP 7979-P-A (Proprietary),

WCAP 8028-A (Non-Proprietary),

January 1975.

1.6-5 REV 9

12/92

GINNA/UFSAR Title UFSAR Sections L. E. Hochreiter, et alee A lication of the THINC IV Pro ram to 4.2 15.0, 15.4 L. E. Hochreiter, A lication of the THINK IV Pro ram to PWR

~Deci n, WCAP 8054-P-A (Proprietary),

Pebrnary

1989, WCAP 8195 (Non-Proprietary),

October 1973.

4.4 R.

D. Kelly, et al., Calculational model for Core Refloodin after a Loss-of-Coolant Accident WREFLOOD Code),

WCAP 8170 (Proprietary),

WCAP 8171 (Non-Proprietary),

June 1974.

15.6 J.

M. Hellman, Fuel Densification Ex erimental Results and Model for Reactor A lications, WCAP 8218, October 1973.

4.4 J.

M. Hellman, Fuel Densification Ex erimental Results and Models 15.6 for Reactor A lication, WCAP 8219, October 1973.

V. J. Esposito, D. Kesavan, and B. A. Maul, WFLASH-A FORTRAN IV Com uter Pro ram for Simulation of Transients in a Multi-Loo

PWR, WCAP 8261, Revision 1, July 1974.

15.6 F.

M. Bordelon, et alee LOCTA-IV Pro ram:

Loss-of-Coolant Transient Anal sis, WCAP 8301 (Proprietary),

WCAP 8305 (Non-Proprietary),

June 1974.

15.6 F.

M. Bordelon, et alee SATAN VI Pro ram:

Com rehensive S ace-Time De endent Anal sis of Loss-of-Coolant, WCAP 8302 (Pro-prietary),

WCAP 8306 (Non-Proprietary),

June 1974.

15.6 F. M. Bordelon and E. T. Murphy, Containment Pressure Anal sis 15.6 June 1974.

6.2 ECCS Evaluation Model - Summar WCAP 8339, July 1974.

15.6 1.6-6 REV 9 12/92

GINNA/UFSAR Title UFSAR Sections R. Salvatori, Westin house ECCS - Plant Sensitivit

Studies, WCAP 8340 (Proprietary),

WCAP 8356 (Non-Proprietary),

July 1974.

15. 6 Westinghouse Electric Corporation, Westin house ECCS Evaluation Model Sensitivit

Studies, WCAP 8341 (Proprietary),

WCAP 8342 (Non-Proprietary),

1974.

15.6 R. A. George, et al., Revised Clad Flattenin

Model, WCAP 8377 (Proprietary),

WCAP 8381 (Non-Proprietary),

July 1974.

4.2, 4.4 Westinghouse Electric Corporation, Antici ated Transients Without 15.8 Tri Anal sis for Westin house PWRs with 44 Series Steam Genera-

tors, WCAP 8404, September 1974.

Westinghouse Electric Corporation, Anal sis of Ca sule R from the 5.3 Rochester Gas and Electric R. E. Ginna Unit No.

1 Reactor Vessel Radiation Surveillance Pro ram, WCAP 8421, November 1974.

F.

M. Bordelon, et al.,

The Westin house ECCS Evaluation Model Su lementar Information, WCAP 8471 (Proprietary),

WCAP 8472 (Non-Proprietary),

January 1975.

15.6 H. Chelemer, et al.,

Im roved Thermal Desi n Procedure, WCAP 8567, July 1975.

4.2 H. Chelemer, et al.,

Im roved Thermal Desi n Procedure, WCAP 8567-P-A (Proprietary),

February 1989.

4,4 15.0, 15.1, 15.2, 15.3, 15.4 Westinghouse Electric Corporation, Fuel Rod Bow Evaluation, WCAP 8691, Revision 1, July 1979.

4.2, 4.4 J.

V. Miller, Ed.,

Im roved Anal tical Models Used In Westin house Fuel Rod Desi n Com utations, WCAP 8720, October 1976.

4.2, 4.4 1.6-7 REV 9 12/92

GINNA/UFSAR Title Westinghouse Electric Corporation, Westin house Revised PAD PAD Code Thermal Safet

Model, WCAP 8720, Addendum 2

(Proprietary),

transmitted by letter from E. P.

Rahe, Westinghouse, to C.

O.

Thomas, NRC, dated October 27, 1982.

UFSAR Sections 4.4 J. A. Fici, et al., Desi n Bases for the Thermal Over ower Delta T and Thermal Overtem erature Delta T Tri Functions, WCAP 8745 (Proprietary),

March 1977'.4 F. E. Motley, et al.,

New Westin house Correlation WRB-1 for Predictin Heat Flux in Rod Bundles with Mixin Vane Grids, WCAP 8762 (Proprietary),

WCAP 8763 (Non-Proprietary),

Jul'y 1976.

4.2 F.

E. Motley, et al.,

New Westin house Correlation WRB-1 for Predictin Heat Flux in Rod Bundles with Mixin Vane Grids, WCAP 8762-P-A (Proprietary), July 1984.

4,4 Westinghouse Electric Corporation, Fuel Rod Desi n Com utations, WCAP 8785, October 1976.

4.2 T. Delsignore, et al., Westin house ECCS Two-Loo Sensitivit Studies 14 x 14 WCAP 8854 (Non-Proprietary),

September 1976.

15.6 D. H. Risher, et al., Safet Anal sis for the Revised Fuel h

Rod Internal Pressure Desi n Basis, WCAP 8964, June 1977.

4.4 Emer enc Core Coolin S stem Small Break October 1975 Model, WCAP 8970-P-A (Proprietary),

WCAP 8971-A (Non-Proprietary),

January 1979.

15.6 Westinghouse Electric Corporation, Nuclear Desi n of Westin house 1.5 Pressurized Water Reactors with Burnable Poison Rods, WCAP 9000 Series (Proprietary),

1968.

1.6-8 REV 9 12/92

GINNA/UFSAR Title UFSAR Sections Westinghouse Electric Corporation, A Controlled Combustion S stem to Prevent H dro en Accumulation Followin a Loss-of-Coolant

Accident, WCAP 9001 (Proprietary),

February 1969.

6.2 R.

D. Kelly, C.

M. Thompson, et al., Westin house Emer enc Core Coolin S stem Evaluation Model for Anal zin Lar e LOCAs Durin 0 eration With One Loo Out of Service for Plants Without Loo Isolation Valves, WCAP 9166, February 1978.

15.6 C. Eicheldinger, Westin house ECCS Evaluation Model Februar 1978 Version, WCAP 9220 (Proprietary),

WCAP 9221 (Non-Proprietary),

February 1978.

I 15.6 C. Eicheldinger, Westin house ECCS Evaluation Model 1981 Version, WCAP 9220-P-A, (Proprietary),

WCAP 9221-A, Revision 1, (Non-Proprietary),

1981.

15.6 4.2 Westinghouse Electric Corporation, Westin house Reload Safet Evaluation Methodolo WCAP 9273-A, July 1985.

4 '

4,3 S. L. Davidson and J.

A. Iorii, eds., Verification Testin and Anal sis of the 17 x 17 0 timized Fuel Assembl WCAP 9401<<P-A (Proprietary),

WCAP 9402 (Non-Proprietary),

March 1979.

4,4 Westinghouse Electric Corporation, Reference Core Re ort 17 x 17 0 timized Fuel Assembl WCAP 9500, May 1982.

4.2 Westinghouse Electric Corporation, Mechanistic Fracture Evaluation of Reactor Coolant Pi e Containin a Postulated Circumferential Throu hwall Crack, WCAP 9558, Revision 2, (Proprietary),

WCAP 9570 (Non-Proprietary),

May 1981.

5.4 Westinghouse Electric Corporation, Metallur ical Investi ation of the Steam Generator Feedwater Pi in Cracks at the R. E. Ginna Nuclear Power Generatin

Station, WCAP 9563.

5.4 1.6-9 REV 9

12/92

GINNA/UFSAR Title UFSAR Sections Westinghouse Electric Corporation, Re ort for Small Break Accidents for Westin house NSSS S stem, WCAP 9600, June 1979.

15.6 Westinghouse Electric Corporation, Metallur ical Investi ation of Cracks in the Pressurizer Nozzle-to-Safe-End Weld of the R.

E. Ginna Nuclear Power Generatin

Station, WCAP 9663, February 1980.

Westinghouse Electric Corporation, Westin house Owner's Grou As etric LOCA Load Evaluation - Phase C,

WCAP 9748 (Pro-prietary),

WCAP 9749 (Non-Proprietary),

1980.

3.9, 4.2, 5.4, 6.2 Westinghouse Electric Corporation, Tensile and Tou hness Pro erties of Primar Pi in Weld Metal for Use in Mechanistic Fracture Evaluation, WCAP 9787, Revision 1, May 1981.

5.4 Westinghouse Electric Corporation, Probabilistic Anal sis and 0 erational Data in Res onse to NUREG 0737 Item III.K.3.2 for Westin house NSSS Plants, WCAP 9804, February 1981.

15.6 T. Mayer, Summar Re ort on Reactor Vessel Inte rit of Westin house 0 eratin

Plants, WCAP 10019, December 1981.

5c3 Westinghouse Electric Corporation, Anal sis of Ca sule T from the Rochester Gas and Electric Cor oration of R. E. Ginna Nuclear Plant Reactor Vessel Radiation Surveillance Pro ram, WCAP 10086, April 1982.

5.3 R. A. Weiner, et al.,

Im roved Fuel Performance Models for Westin house Fuel Rod Desi n and Safet Evaluations, WCAP 10851-P-A (Proprietary),

August 1988.

4,4 Y. S. Liu, et al.,

ANC: A Westin house Advanced Nodal Code, WCAP 10966-NP-A (Non-Proprietary),

September 1986.

4.3 1.6-10 REV 9 12/92

GINNA/UFSAR Title UFSAR Sections Westinghouse Electric Corporation, Westin house Small Break LOCA ECCS Evaluation Model Generic Stud with the NOTRUMP Code, WCAP 11145 (Proprietary),

May 1986.

15.6 T. Q. Nguyen, et al.,

ualification of the PHOENIX-P ANC Nuclear Desi n S stem for Pressurized Water Reactor

Cores, WCAP 11597-A, June 1988.

4.3 Westinghouse Electric Corporation, Loss of Residual Heat Removal Coolin While the RCS is Partiall

Filled, WCAP 11916, Revision 0, July 1988.

5.4 Westinghouse Electric Corporation, Advanced Di ital Feedwater Control S stem Median Si nal Selector for Rochester Gas and Electric Robert E. Ginna, WCAP 12347, September 1990.

7 '

Westinghouse Electric Corporation, Structural Evaluation of the Robert E. Ginna Pressurizer Sur e Line Considerin the Effects of 3.9 Thermal Stratification, WCAP 12928 (Proprietary),

WCAP 12929 (Non-Proprietary),

May 1991.

1.6-11 REV 9 12/92

GINNA/UFSAR Table 1.7-1 ELECTRICAL, INSTRUMENTATION, AND CONTROL DRAWINGS Drawing Number 03201-0102 21945-357 Title 120-Volt ac Instrument Bus One-Line Diagram 125-Volt dc Battery Intertie, TSC Battery - Vital Battery Systems, Two-Line Wiring Diagram Figure Number 8.3-4 8.3-8 J9-33013-623 Sheet 1

Sheet 2

Main One-Line Operating Diagram Main One-Line Operating Diagram 8.3-1, Sheet 1

8.3-1, Sheet 2

5.

33013-652 33013-653 33013-756 Sheet 1

Sheet 2

33013-1353 Sheet 1

Sheet 2

Sheet 3

Sheet 4

Sheet 5

Sheet 6

480-Volt One-Line Wiring Diagram 4160-Volt One-Line Diagram Electrical One-line Diagram, 125-Volt dc System Electrical Panel Arrangements, 125-Volt dc System Logic Diagram, Index and Symbols Logic Diagram, Reactor Trip Signals Logic Diagram, Turbine Trip Signals Logic Diagram, Electrical Protection Logic Logic Diagram, Emergency Generator 'B'tarting Logic Diagram, Safeguards Actuation Signals 8.3-3 8.3-2 8.3-6 8.3-7

)3.,

7 ~ 2 3

7.2-4 7.2-9 7.2-8 8.3-5 7.3-1, Sheet 1

Sheet 7

Logic Diagram, Safeguards Actuation Signals 7.3-1 Sheet 2

Sheet 8

Sheet 9

Logic Diagram, Safeguards Sequence Logic Diagram, Feedwater Isolation and Auxiliary Feedwater Pump Actuation Signals 7 ~ 3 3

7.3-2 Sheet 10 Logic Diagram, Nuclear Instrumentation Trip Signals 7.2-6 1.7-3 REV 9 12/92

GINNA/UFSAR Table 1.7-1 ELECTRICAL, INSTRUMENTATION, AND CONTROL DRAWINGS (Continued)

Drawing Number Title Figure Number 33013-1353 (Continued)

Sheet 11 Logic Diagram, Nuclear Instrumentation, Permissives, 7.2-11 and Blocks Sheet 12 Sheet 13 Sheet 14 Sheet 15 Logic Diagram, Pressurizer Trip Signals Logic Diagram, Logic Diagram, Steam Generator Trip Signals e

Reactor Coolant System Trip Signals Logic Diagram, Stops and Turbine Runbacks je2-7 7.2-10 7.2-5 7.7-5 1.7-4 REl7 7

22/92

VALVE OESIGNATORS IDKPINITI DMS)

OIAPHRASM SEAL VALVE NUMSER V

VENT X

NUNS INDICATE VALVE AD INTERTAC DRIP PAN Iswcww 'PITH PUMPs OUTLET CAN SE OTI'ICE WaLL)

DRAIN D

TC TEST CONNECTION SAMPLE S

PAIL OPEN CAN. CLOSED SI

( APERTURE CARD LOCXKD OPEN ~

Also Available On Aperture Card LOCXEO CLOSED THROTTLKO AMO LOCKED QE!

CONTAINMENT ISOLATION SAPKTT TH)ECTION SION PAI I'AIL AS !$

OREAXER LOCKED CLOSED

'REAMER LOCKED OPEN NOTES I, fOR OEHERAL NOTES REPKR TO DRAVIHS SIOIO TRAIT THIS DRAW)NO SUPERSEDES PORTIONS Of DRAWINOS STOIC IEST SHEETS I

ANO E REACH ROO ENT)

ROCHESTER GAS AND ELECTRIC CORPORATION R. E. GINNANUCLEAR POWER PLANT

.UPDATED FINALSAFETY ANALYSISREPORT Figure 1.7-1, Sheet 2

Symbol Legend Drawing 33013-2242, Sheet 2, Revision 5

REV 10 12/93 QC

'I 0

,r

GINNA/UFSAR 1.8.1.19.3 Pressure Tests All piping penetrations and personnel locks were pressure tested in the fabricator's shop to demonstrate leaktightness and structural integrity.

f6 In order to ensure that the joints in the liner plate and penetrations as well as all weld connections of test channels were leaktight, it was required that all welds be examined. by detecting leaks at 69 psig test pressure using a soap bubble test-or a mixture of air and Freon, and 100% of detectable leaks be arrested.

These tests were preliminary to the performance of the initial integrated leak rate test which ensured that the containment leak rate was no greater than 0.1$ of the contained volume in 24 hr at 60 psig.

The liner weld seams were also examined by pressurizing the test channels to design pressure (60 psig) with a mixture of air and Freon, and checking all seams with a halogen leak detector.

All detectable leaks were corrected by repairing the weld and retesting.

1.8.1.19.4 Quality Control Provisions The following quality control provisions were employed in the welding procedure for the liner:

The qualification of welding procedures and welders was in accordance with Section IX, Welding Qualifications, of the ASME Boiler and Pressure Vessel Code.

Contractor shall submit welding procedures to the Engineer for review.

The qualification tests described in Section IX, Part A, include guided bend tests to demonstrate weld ductility. All penetrations shall be examined in accordance with the requirements of the ASME Nuclear Vessels Code for Class B Vessels.

Other shop fabricated components including the reinforcement about openings shall be fully radiographed.

All nonradio-graphable joint details shall be examined by the liquid penetrant method.

Conformance to this code was adhered to in all applicable cases.

1.8.1.20 Safet Guide 20

- Vibration Measurements on Reactor Internals A vibration analysis and test program was developed for Ginna Station by Westinghouse Corporation.

The preoperational test program and its results are 1.8-19 REV 6 12/90

GINNA/UFSAR discussed in Section 14.6.

The results show that the vibration of the reactor internals for the Ginna plant are well within the existing criteria.

A program was conducted during the first refueling shutdown of the Ginna reactor (March 1971) to inspect and evaluate the performance of the reactor internals and core components.

This inspection program was based on an inspection of all components, with emphasis on the thermal shield area since the thermal shield has previously been the most vulnerable problem area.

The structures inside and outside of the lower internals, the upper internals, three control rod drive shafts, and all rod cluster control assembly control rods were inspected using a closed-circuit underwater television and/or boroscope.

All of the inspections performed by television were recorded on video tape; photographs were taken through the boroscope to record that portion of the inspection.

This inspection revealed no problem areas in any of the items inspected.

The inspection program is described in Westinghouse report WCAP 7780, Robert E. Ginna Nuclear Generating Station, March 1971 Refueling Shutdown Reactor Internals and Core Components Evaluation.

1.8

~ 1,21 Safet Guide 21 -

casu n

and Re ortin E fluents From Nuclear ower Plants Starting on January 1, 1972, plant effluent monitoring and reporting was prepared in the format given in Appendix A of Safety Guide 21 and submitted to the State of New York on a monthly basis.

A report in the format of Appendix A was provided to the AEC for the year 1971.

The Technical Specifi-

cations, as revised on March 1, 1972, follow the intent of Safety Guide 21 for measuring and recording the plant effluents and are being followed.

Plant records will be maintained to demonstrate that the sensitivity of analysis is within the limits given in the safety guide.

An onsite meteorological tower was fully operational early in 1965 and was used extensively in the collection of preoperational meteorological data.

During early 1972, the recording instrumentation was relocated inside the

1. 8-20 REV 6 12/90

)

GINNA/UFSAR accident.

There are no components of systems in unheated compartments.

Charcoal filter units 'are provided with spray systems to limit adsorber fires.

All cleanup systems are designed for ease of maintenance and ready removal of elements.

Lighting is provided in the housings and test probe holes for in-place testing are available.

Filter units were tested prior to startup of Ginna Station and are retested according to the schedules of the Technical Specifications.

These tests are subcontracted to a reliable vendor who prepares the report of test results.

Samples from the charcoal filter trays are sent for organic iodides and elemental iodine efficiency tests according to Table 2 of Guide 1.52.

1.8.2.31 Re ulator Guide 1.53 - A lication of the Sin le-Failure Criterion U

To Nuclear Power Plant Protection S stems This guide endorses'he use of IEEE Standard 379-1972, Trial-Use Guide for the Application of the Single-Failure Criterion to Nuclear Power Generating Station Protection Systems.

Subjects which are covered in the standard include identification of undetectable failures, analysis of channel inter-connections for failures which could compromise independence, testing to determine independence between redundant parts of the protection system, and analysis to show that no single failure can cause a loss of function due to improper connection of actuators to a power source.

Protection system failure analyses and reliability studies applicable to the Ginna plant were performed as described in the topical report WCAP 7486-L, An Evaluation of Anticipated Operational Transients in Westinghouse Pressurized Water Reactors.

This report was submitted to the AEC by Westinghousy in March 1971.

Subsequent evaluations have demonstrated the conformance of the Ginna Station design to this guide.

1.8.2.32 Re ulator Guide 1.54 -

ualit Assurance Re uirements for Protective Coatin s A lied to Water-Cooled Nuclear Power Plants Contemporary standards were specified to ensure that protective coatings applied would perform their functions under environmental conditions 1.8-45

GINNA/UFSAR experienced during normal operations and the design-basis accident and to do so without hazard of interfering with other nuclear components.

One standard specified was SP-5485 dated January 18, 1968, entitled Technical Specification, Painting of Structures and Equipment, Robert Emmett Ginna Nuclear Power Plant Unit No.

1, which includes techniques for preparation of surfaces to be painted,

sampling, thickness measurement and control, and a

detailed paint schedule including components and paint materials for plant structures and equipment.

Also, SP-5339 dated March 31, 1967, entitled Tech-nical Specification for Painting the Interior Surface of the Containment Vessel Dome for the Robert Emmett Ginna Nuclear Power Plant Unit No.

1, gives the specifications for the preparation, application, material, and paint sampling for the interior of the containment dome.

The painting of the containment structure and components inside the contain-ment was governed by Westinghouse process specification PWR 597755, dated Febru'ary 20, 1968.

This specification covered the application of paint systems to equipment and structures in containments which use additive spray systems for fission product removal and/or containment cooling.

Regulatory Guide 1.54 and related ANSI Standard N101.4 were published after

""'onstruction of the Ginna plant and thus were not available to be applied.

However, the previously referenced process specifications demonstrate that care was taken in the selection and application of protective coatings for the Ginna plant.

1.8.2.33 Re ulator Guide 1.55 Concrete Placement in Seismic Cate or I Structures All concrete placement for the Ginna plant was accomplished in accordance with the proposed specification for structural concrete for buildings ACI-301 and the detailed construction specification.

In accordance with the specification, the contractor submitted placing drawings, reinforcing bar details, and bar lists, etc., for engineer approval to ensure that the details were in general compliance with the engineering 1.8-46

GINNA/UFSAR Chapter 2

SITE CHARACTERISTICS 2.1 GEOGRAPHY AND DEMOGRAPHY 2.1. 1 SITE LOCATION AND DESCRIPTION The site is in the township of Ontario, in the northwest corner of Wayne

County, New York, on the south shore of Lake Ontario about 16 miles east of the center of the city of Rochester and 40 miles west-southwest of Oswego, at longitude 77'8.7'W and latitude 43'6.7'N.

The general location is shown in Figure 2.1-1.

The site, including the switchyard, comprises 488 acres owned by the Rochester Gas and Electric Corporation (RG&E).

Figures 2.1-2 and 2.1-3 show the site boundaries and their relationships to topographic and demographic features.

The surface of the land on the southern shore of Lake Ontario, at the site and east and west of it, is either flat or gently rolling. It slopes upward to the south from an elevation of about 255 ft above mean sea level (msl) near the edge of the lake; to 440 ft at Ridge Road (New York State Highway 104),

3.5 miles south of the lake; and then to about 1600 ft at the northern edge of the Appalachian Plateau, 30 to 40 miles to the south.

Southward from Ridge Road the terrain progressively

roughens, with a series of small abrupt hills, commencing about 10 miles south of the site.

Wayne County, in which the site is located, is primarily of an agrarian nature and sparsely populated.

The location is shown in Figure 2.1-1.

There are no substantial population centers, industrial complexes, transportation arteries, parks or other recreational facilities within a 3-mile radius of the Ginna site.

Roughly 70% of the county's 600 square miles are utilized for approxi-1 mately 2500 farms', which primarily produce apples,

grapes, cherries, dairy products, field crops, and vegetables.

About 34% of Wayne County's workers are "'employed in manufacturing operations, 18% in service industries, 16X in retail trade, 14X in agr.culture, and 18X in other occupations.

Typical industries are listed in Table 2.2-1.

2.1-1

GINNA/UFSAR Monroe

County, located adjacent to and west of Wayne

County, has many manufacturing activities. centered in and around Rochester.

Approximately 22%

of the county's 673 square miles is in urban development, about 28% is vacant,

wooded, or water surface, and 50X is farm land upon which dairy products, field crops, poultry, livestock, fruits, and horticultural specialities are produced.

Of Monroe County's workers, about 45% are employed in manufactur-

ing, 20X in service industries, 16% in retail trade, 1.4X in agriculture, and the rest in other activities.

Typical industries are listed in Table 2.2-2.

The land within a radius of 5 miles of the site is used for agricultural

purposes, principally for growing apples,

cherries, grapes, and field crops.

In Figure 2.1-3, the orchard areas are characterized by a square array of

trees, the open fields by relatively regular boundaries, and the woods by their dark color and irregular shape.

There are only a few dairy farms in a 5-mile radius of the plant.

They average between 50 to 75 milk cows per farm.

Part of the site is under lease for fruit farming.

2.1.2 EXCLUSION AREA AUTHORITY AND CONTROL The. site exclusion area is completely within the plant boundaries.

The distance from the containment to the nearest site boundary (excluding the boundary on the lakefront) is 1550 ft but the minimum exclusion distance is assumed to be 450 meters or 1476 ft.

The site boundary is shown in Figure 2.1-2.

No public highways or railroads traverse the exclusion area.

Rochester Gas and Electric Corporation owns and controls all of the land, including mineral rights, within the exclusion area.

Regarding the lakeshore 2

frontage within the exclusion area, RG&E, by New York State procedures, owns the land above 243.8 ft msl.

This is well below the average lake stage of 246 ft msl, but is above the extreme low water level of 242.23 ft msl and the lowest regulated level of 243 ft msl (see Section 2.4); however, since the low period is generally in the winter and the high period in the summer, it is not expected that there would be any beach use of this area.

The exclusion area is not defined over the'aters of Lake Ontario adjacent to the Ginna site.

While RG&E has not specifically defined an exclusion area over the water, arrangements have been made with the U.S. Coast

Guard, as documented in the Ginna Nuclear Emergency

Response

Plan, for the control of water traffic in the event of a plant emergency.

2. 1-2

GINNA/UFSAR 2.1.3 POPULATION DISTRIBUTION 2.1.3.1 Po ulation within Five Miles The population distribution by 1-mile increments within 5 miles of the plant, projected for the years

1970, 1980,

1990, and 2010, is shown in Figure 2.1-4

~

The 1970 estimates were based on a 1967 count of houses and electric meters and includes summer residents.

The estimates for 1980,

1990, and 2010 were made by the RG&E Rate and Economic Research Department and were derived from a study of past trends and probable future industrial, commercial, residential, and recreational development.

Updated population data based on preliminary estimates from the 1980 Census are shown on Figure 2.1-5.

Rochester Gas and Electric Corporation estimated that 10,864 persons resided within 5 miles of the plant in 1980, a density of 138 persons per square mile averaged over the entire area.

It should be noted that this figure compares favorably with the 1980 population projection of 10,934 persons shown in Figure 2.1-4.

Updated 1992 population estimates based on data obtained from the Center for Government Research and 1990 Census data are shown in Figure 2.1-5a.

Rochester Gas and Electric Corporation estimated that 11,277 persons resided within 5 miles of the plant in 1992. It should be noted that this figure is significantly lower than the 1990 population projection of 14,491 persons shown in Figure 2.1-4.

10 Based on the original FSAR for Ginna Station published in 1968, four schools were located approximately 3.5 miles south of the plant, and had a total enrollment of 2272 pupils and a teaching staff of 180.

The nearest offsite residence is about 2000 ft southwest of the plant, and there are two occupied farmhouses on the site.

The farms are owned by RG&E and the occupants have leases renewable annually at the option of RG6E.

One farmhouse is about 2200 ft southeast of the plant and the other is about 1500 ft south.

Both farmhouses are outside the exclusion area.

Other buildings (horse barns) are located about 800 ft east and 1400 ft south of the plant.

2.1-3 REV 10 12/93

GINNA/UFSAR 2.1.3.2 Po ulation Within Fort Miles The population distribution projections by 10-mile increments within 40 miles of the plant, for the years

1970, 1980,

1990, and 2010, are shown in Figure 2.1-6.

The 1970 estimates were based on extrapolations of the 1960 Census and a special census of Monroe County (Rochester area) dated April 1, 1964.

The estimates for 1980,

1990, and 2010 were made by the RG&E Rate and Economic Research Department and were derived from a study of past trends and probable future industrial, commercial, residential, and recreational development.

2.1.3.3 Transient Po ulation Based on the original FSAR, there is a summertime increase of about 500 people in the lakeside population within a 5-mile radius of the plant, and a summer-time increase of 4000 to 5000 people in the lakeside population within a 20-mile radius of the plant.

The nearest group of houses are summer cottages, 0.8 miles west.

Other groups are located at Bear Creek, 1.5 miles east, and at Ontario-on-the-Lake, 2 miles west.

Other than the summertime residents of the area, there are no large groups of transients within 5 miles of the site.

The only parks near the site are Webster Beach Park in Monroe County, approximately 6 miles west of the plant

site, and B. Forman Park in Wayne County, approximately 8 miles east of the plant site.

There are no federal recreational facilities in the area.

There are no state parks, public campsites, or special use areas within 10 miles of the plant.3 Wayne County does have a migrant labor population during the June-October

season, primarily for apple picking.

Approximately 115 farm-worker camps of five or more persons are scattered throughout Wayne County, with a total population of about 4400 migrants.

Information from Rural New York Farmworker Opportunities shows that there are only 12 camps, with about 130 migrants, located in the vicinity of the Ginna site.4 2.1.3.4 Low-Po ulation Zone The low-population zone specified for the Ginna site is the area within a 3-mile (4827 m) radius of the plant.

A review in 1981 of population estimates and projected growth estimates indicates that the population growth 2.1-4 REV 10 12/93

~

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