ML19269C732

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Amend 9 to Balance of Plant Standard Sar.Amend Concerns Classification of Components,Auxiliary Feedwater Sys, Containment Spray Sys & Emergency Diesel Fuel Oil Storage & Transfer Sys
ML19269C732
Person / Time
Site: 05000584
Issue date: 02/07/1979
From:
GIBBS & HILL, INC. (SUBS. OF DRAVO CORP.)
To:
Shared Package
ML19269C727 List:
References
NUDOCS 7902120134
Download: ML19269C732 (177)


Text

GIBBSSAR Amendment 9 Instruction Sheet The following instructional information is being provided to insert Amendment 9 into GIBBSSAR, the Gibbs & Hill standard safety analysis report. Please destroy the sheets removed and insert the new sheets as indicated below.

Remove the effective page listing from the front of each volum3 and the question status table from the front of volume 6 and insert the new effective page listing and question status table. Remove and insett other pages as indicated below:

?e0212004

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EFFECTIVE PAGE LISTING GTBBSSAP: VOLUME 1 1-i (0) (1) 1-11 e (0) 1-iii (0) 1-iv (0) 1-v (0) 1.1- 1 (0) (1) 1.1-2 (0) (1) (6)

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F1.2-7 (0) (2) (5) (6)

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EFFECTIVE PAGE LISTING GIBBSSA2: VOLUME 1 ,

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EFFECTIVE PAGE LISTING-GIBBSSAR: VOLUME 1 T1.8-2 Sh. 20 (1) (3) (4-deleted)

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1. 9- 1 (0) (1) (3) (4)
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F1.9-1 (0) (2) (6) 2-1 (0) (1) 2-il (0) 2-iii (0; 2-iv (0) 2-v (0) 2-vi (0) 2-vii (0) (1) 2-viii (0) 2-ix (0)

EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 1 2.1- 1 (0)

2. 2- 1 (0) 2.3-1 (0) (1)
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2. 3- 6 (0) (1) (3) 2.3-7 (0) ( 3) 2.3-8 (0) (1) 2.3-9 (0) (1) 2.3-9a (1) (3) 2.3-9b (1) 2.3-9c (1) 2.3-9d (1) 72.3-1 (0) (1) (3)

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EFFECTIVE PAGE LISTING GIBBSSAP: VOLUME 1 2.4-9 (0) 2.4- 10 (0) 2.4-11 (0) 2.0-12 (0) 2.4-13 (0) (2)

2. 4 (0) 2.5-1 (0)
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2. 5- 9 (0) 2.5-10 (0) 3-1 (0) 3-ii (0) 3-lii (0) 3-iv (0) 3-v (0) (1) 3-vi (0)-(1) 3-vii (0) 3-viii (0) 3-ix (0) 3-x (0) (1) 3-xi (0) (1) 3-xii (0) (2) 3-xiia (2) 3-xiii (0) 3-xiv (0) ( .)

3-xv (0) (2) 3-xvi (0) (2) 3-xvia (2) 3-xvii (0) 3-xviii (0) 3.1- 1 . ( 0) 3.1-2 (0) 3.1-3 (0) 3.1- 4 (0) 3.1-5 (0) (1) 3.1-6 (0) 3.1-7 (0) 3.1- 8 (0) 3.1-9 (0) 3.1-10 (0) 3.1-11 (0) 3.1- 12 (0) 3.1- 13 (0)

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(3) (4) 3.1-49 (0) (1) 3.1-50 - (0) 3.1-51 (0) 3.1- 52 (0) 3.1-53 (0) 3.1- 54 (0) 3.1-55 (0) (1) 3.1- 56 (0) (1) 3.1- 57 (0) 3.1-58 (0) (1) 3.1-59 (0) 3.1-60 (0) (1),,

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EFFECTIVE PAGE LISTING GIBESSAR: VOLUME 1 3.2-1 (0) 3.1- 2 (0) 3.2-3 (0) (4) 3.2-3a (4)

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3. 3- 3 (0) (1) (S) 3.3-4 (0) (1) (5)
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EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 1

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T3.5-11 sh. 1 (7)

T3.5-11 sh. 2 (7)

T3.5-11 Sh. 3 (7)

T3.5-11 Sh. 4 (7)

F3.5-1 (0)

F3.5-2 (0)

F3.5-3 (0)

F3.5-4 (0) (4)

3. 6- 1 (0) (1) (6) 3.6-2 (0) (1) (6) ( 9)
3. 6- 2a (6)
3. 6- 3 (0) (1) (7) 3.6-3a (7)
3. 6- 3b (7) 3.6-4 (0) (1) (7) 3.6-5 - (0) (1) (2) (7)
3. 6- Sa (7)

~

3.6-5b (7) 3.6-6 (0) (2) (4) (9)

3. 6- 7 (0) (1) (2-deleted)
3. 6- 8 (0) (2-deleted)
3. 6- 9 (0) (2-deleted) 3.6- 10 (0) (2) (4) (6) 3.6-11 (0) (1) (2) (4-deleted) 3.6-12 (0) (1) (2-deleted) 3.6- 13 (0) (1) (2-deleted) 3.6- 14 (0) ( 2) 3.6-15 (0) (2)

EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 1

3. 6- 15a (2) (4) 3.6- 16 (0) (1) (2)
3. 6- 16a (2) 3.6~17 (0) (1) 3.6-18 (0) 3.6- 19 (0) 3.6-20 (0) (6) (7)
3. 6- 20a (6) (7)
3. 6- 20b (6) 3.6-21 (0) (2) (4)
3. 6- 21a (2) (4) 3.6-22 (0) (2) 3.6-23 (0) 3.6-24 (0)

T3.6-1 Sh. 1 (0) (1) (6) (9)

T3.6-1 Sh. 2 (0) (1) (6) (9) 73.6-1 Sh. 3 (6)

T3.6-2 Sh. 1 (0) (7)

T3.6-2 Sh. 2 (7)

T3.6-3 (0)

F3.6-1.1 (0) (2-deleted)

F3.6-1.2 (0) (2-deleted)

F3.6-1A (2)

F3.6-1B (2)

F3.6-2 (0)

F3.6-3 (0)

F 3. 6 -4 (0)

F3.6-5 (0)

F3.6-6 (2)

F3.6-7 (2) '

F3.6-8 (6)

F3.6-9 (6)

F3.6-10 (6)

F3.6-11 (6)

F3.6-12 (6)

F3.6-13 (6)

F3.6-14 (6)

3. 7- 1 (0) (2) (4) (5) (8) 3.7-1a (2)
3. 7- 2 (0) (2)
3. 7- 3 (W (1) (2) (5) (6)
3. 7- 3a (2) (5) 3.7-4 (0) (1) 3.7- 5 (0) (6) 3.7-6 (0) (6) 3.7-7 (0) (2) (5)
3. 7- 7a (2)
3. 7- 8 (0)
3. 7- 9 (0) (4) (8)

EFFECTIVE PAGE LISTING GIBBSSAP- VOLUME 1 3.7-9a (4) 3.7- 10 (0) (1) (2) (4) (5) 3.7-10a (4) 3.7-11 (0) (1) (5) 3.7-12 (0) (5)

3. 7- 12a (5) 3.7-13 (0) (1) (5) 3.7-14 (0) 3.7- 15 (0) (8) 3.7-16 (0) (1) (5) (8) 3.7-17 (0) (5) (8) 3.7- 18 (0) (1) (5) (8) 3.7-19 (0) (1) (5) 3.7-20 (0) (5) (8)
3. 7- 20a (5) (8) 3.7-21 (0) (4) (5) 3.7-22 (0) (4) (5) (6) 3.7-23 (0) 3.7- 24 (0) (4) (5) (8) 3.7-25 (0) (5) 3.7-26 (0) (5)
3. 7- 26a (5) 3.7-27 (0) (5) 3.7-28 (0) (1) 3.7- 29 (0) (5) 3.7-30 (0) (1) (5) (8)
2. 7- 3 0a (5) 3.7-31 (0) (5) 3.7-31a (5) 3.7-32 (0) 3.7-33 (0) (5) 3.7- 34 (0) (1) (5) 3.7-35 (0) 3.7-36 (0) (5) 3.7- 37 (0) 3.7-38 (0) 3.7-39 _ (0) 3.7- 40 (0) 3.7-41 (0) (6) 3.7-42 (0) 3.7-43 (0) (1) 3.7- 44 (0) (5) 3.7-45 (0) (1) 3.7-46 (0) 3.7- 47 (0) (5) 3.7-48 (0) 3.7-49 (0) 4';#

3.7- 50 (0) (6) (8)

T3.7-1 (0) (1)

EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 1 T3.7-2 Sh. 1 (0)

T3.7-2 Sh. 2 (0) (1)

T3.7-3 , (0)

T3.7-4 (0)

T3.7-5 (0) (1)

T3.7-6 Sh. 1 (0) (1)

T3.7-6 Sh. 2 (0) (1) 3.7A-1 (0) (6) 3.7A-2 (0) (6) 3.7A-3 (0) (1) (6) 3.7A-4 (0) (6) 3.7A-5 (0) (1) (6) 3.7A-6 (0) (6) 3.7A-7 (0) (6) 3.7A-8 (0) (1) (6) 3.7A-9 (0) (6) 3.7A-10 (0) (6) 3.7A-11 (0) (6) 3.7A-12 (0) (6) 3.7A-13 (0) (1) (6) 3.7A-14 (0) (1) (6) 3.7A-15 (0) (1) (6) 3.7A-16 (0) (6) 3.7A-17 (0) (6) 3.7A-18 (0) (6) 3.7A-19 (0) (6) 3.7A-20 (0) (6) 3.7A-21 (0) (6) 3.7A-22 (0) (1) (6-deleted) 3.7A-23 (0) (6-deleted) 3.7A-24 (0) (6-deleted) 3.7A-25 (0) (6-deleted) 3.7A-26 (0) (6-deleted) 3.7A-27 (0) (6-deleted) 3.7A-28 (0) (6-deleted) 3.7A-29 (0) (6-deleted) 3.7A-30 (0) (6-deleted) 3.7A-31 (0) (6-deleted)

T3.7A-1 Sh. 1 (0) (1) (6)

T3.7A-1 Sh. 2 (0) (1) (6)

F3.7-1 (0)

F3.7-2 . (0)

F3.7-3 (0)

F3.7-4 (0)

F3.7-5 (0)

F3.7-6 (0)

F3.7-7 (0)

F3.7-8 (0)

F3.7-9 (0)

EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 1 F3.7-10 (0)

F3.7-11 (0)

F3.7-12 (0)

F3.7-13 (0)

F3.7-14 (0)

F3.7-15 ' ( 0)

F3.7-16 (0)

F3.7-17 (0)

F3.7-18 (5)

F3.7A-1 (0)

EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 2 3.8-7 (0) (4)

3. 8- 2 (0) (4) 3.8-3 (0) 3.8-4 (0)
3. 8- 5 (0) (4)
3. 8- 6 (0) (4) 3.8-7 (0)
3. 8- 8 (0) 3.8-9 (0) 3.8- 10 (0) 3.8-11 (0) 3.8-12 (0) (5) 3.8-13 (0) 3.8 14 (0) (5) 3.8-14a (5) 3.8- 15 (0) (1) 3.8- 16 (0) (1) (5) 3.8-16a (5) (8) 3.8- 17 (0) 3.8- 18 (0) (5) 3.8- 19 (0) ( 1) 3.8-20 (0) (1) 3.8-21 (0) 3.8-22 (0) (5) 3.8-22a (5) 3.8- 23 (0) 3.8- 24 (0) 3.8-25 (0) (5) 3.8-26 (0) (4) 3.8- 27 (0) ( 8) 3.8-27a (8) 3.8-28 (0) (1) (5) 3.8-28a (5) 3.8-29 (0) 3.8-30 (0) 3.8-31 (0) 3.8- 32 .(0) 3.8-33 (0) 3.8-34 (0) 3.8-35 (0) 3.8- 36 (0) 3.8-37 (0) 3.8-38 (0) 3.8-39 (0) (4) 3.8-40 (0) (3) (4) 3.8-41 (0) (4) 3.8-42 (0) 3.8-43 (0) (1) (4) 3.8- 44 (0)

EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 2 3.8-45 (0) (1) (4) 3.8-46 (0) (1) (4) 3.8-47 (0) 3.8-48 (0) 3.8-49 (0) 3.8-50 (0) 3.8-51 (0) (4) 3.8-52 (0) (4) 3.8-53 (0) 3.8-54 (0) (5) 3.8-55 (0) (1) (5) 3.8-56 (0) 3.8-57 (0) (1) 3.8-58 (0) (5)

3. 8- 58a (5) 3.8-59 (0) (1) 3.8-60 (0) 3.8-61 (0) (5) 3.8-61a (5) 3.8-62 (0) 3.8-63 (0) (1) 3.8-64 (0) (1) (5) 3.8-65 (0) (1) 3.8-66 (0) 3.8-67 (0) 3.8-68 (0) (1) (2) 3.8-68a (2) 3.8- 69 (0) (4) 3.8-70 (0) (5) 3.8-71 (0) (1) 3.8-72 (0) (4) (5) 3.8-73 (0) (4) 3.8-74 (0) 3.8-75 (0) 3.8-76 (0) (1) 3.8-77 (0) 3.8-78 .(0) 3.8-79 (0) 3.8- 80 (0) 3.8-81 (0) 3.8- 82 (0) (5) 3.8-83 (0) 3.8- 84 (0) 3.8-85 (0) 3.8-86 (0) 3.8- 87 (0) 3.8- 88 (0) 3.8- 89 (0) (5)
3. 8- 89a (5)

e EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 2 3.8-90 (0) (5) (6) 3.8-90a (.5) (6) 3.8-91 (0) (6) 3.8-92 (0) 3.8-93 (0) (4) 3.8-94 (0) (5) 3.8-95 (0)

T3.8-1 SH.1 (0)

T3.8-1 SH.2 (0) (1)

F3.8-1 (0) (3) (6-deleted)

F3.8-1A (6)

F3.8-1B (6)

F3.8-1C (6)

F3.8-1D (6)

F3.8-1E (6)

F3.8-1F (6)

F3.8-1G ( 6)

F3.8-1H (6)

F3.8-2 (0) (3) (5) (6) (8)

F3.8-3 (0) (3) (6)

F3.8-4 (0) (3)

F3.8-5 (0) (4)

F3.8-6 (0)

F3.8-7 (0) (6)

F3.8-8 (0)

F3.8-9 (0)

F3. 8 - 10 (3)

F3.8-11 (0) (5)

F3.8-12 (0)

F3. 8 - 13 (0) (5)

F3.8-14 (0)

F3.8-15 (0)

3. 9- 1 (0)
3. 9- 2 (0) (2)
3. 9- 2a (2) 3.9-3 (0) (2) 3.9-4 - -(0) (2) 3.9-5 (0) (2) 3.9-6 (0) (1) (2) 3.9-6a ( 2)
3. 9- 7 (0) (1) (2) 3.9-8 (0) (2),

3.9-8a (2)

3. 9- 9 (0) (2) 3.9-10 (0) (1) (2) 3.9-11 (0) (2) 3.9-12 (0) ( 2) 3.9- 13 (0) (1) (2) 3.9- 14 (0) ( 2) s

EFFFCTIVE PAGE LISTING GIBBSSAR: VOLUME 2 3.9-15 (0) 3.9- 16 (0) (1) 3.9- 17 (0) (1) (2) 3.9-18 (0) 3.9-19 (0) (1) (2) (4)

3. 9- 19a (2) (4-deleted) 3.9- 20 (0) (4) 3.9-21 (0) (2) 3.9-21a (2) 3.9-22 (2)

T3.9-1 SH.1 (0) (2)

T3.9-1 SH.2 (0) ( 2)

T3.9-2 SH.1 (0) (2) (4) (7)

T3.9-2 SH.2 (2) (4) (7) 73.9-2 SH.3 (2) (7) 73.9-2 SH.4 (7)

T3.9-3 SH.1 (0) (1) (2) (4) (7)

T3.9-3 SH.2 (0) (1) (2) (4) (7)

T3.9-3 SH.3 (0) (1) (2) (4)

T3.9-3 SH.4 (0) (1) (2) (4)

T3.9-4 SH.1 (0) (1) (2)

T3.9-4 SH.2 (0) (1) (2)

T3.9-4 SH.3 (0) (1) (2)

T3.9-5 SH.1 (0) (1) (2) (5)

T3.9-5 Sh.1a (2) (5)

T3. 9 -5 SH.2 (0) (1) (2) (5) (7)

T3.9-5 SH.2a 1 (5) 73.9-5 SH.3 (0) (1) (2) (5) (7)

T3.9-5 SH.4 (0) (1) (2) (5)

T3.9-5 SH.4a (2) (5)

T3.9-5 SH.4b (5) (7)

(UNNUMBERED PAGE) (0) (2-deleted)

F3.9-1 (0)

F3.9-2 (0)

F3.9-3 (0)

F3.9-4 (0)

F3.9-5 ,(0)

F3.9-6 (0)

F3.9-7 (0)

F3.9-8 (0) 3.10-1 (0) (9) 3.10 - 1a (9) 3.10-2 (0) (2) (9) 3.10-3 (0) (1) (2) 3.11-1 (0) (1) 3.11-2 (0) 3.11-3 (0) (1) 3.11-4 (0) 3.11-5 (0)

FFFFCTIVE MAGE LISTING GIBBSSAR: VOLUME 2 3.11-6 (0) 3.11-7 (0) 3.11-8 (0) (1) 3.11-9 (0) (1)

3. 11- 10 (0) (1) 3.11-11 (0) (1) 3.11-12 (0) 3.11-13 (0) (1)

T3.1 1- 1 SH.1 (0)

T3.11-1 SH.2 (0) .

T3.11-2 (0) (1)

T3.11-3 SH.1 (0) (8)

T3.1 1- 3 SH.2 (0) (8-deleted)

T3.1 1- 4 SH.1 (0) (8)

T3.11-4 SH.2 (8)

T3.1 1- 5 SH. 1 (6) (8)

T3.11-5 SH. 2 (6)

F3.11-1 (8)

F 3.1 1- 2 (8) 4-1 (0) 5-i (0) (1) (5) 5-11 (0) (1) (5) 5-iia (5) 5-iii (0) 5-iv (0) 5-v ( 1) (5) 5.1-1 (0)

T5.1-1 (0)

5. 2- 1 (0) (1) (5) 5.2-1a (5) 5.2-1b (5)
5. 2- te (5) 5.2-2 (0)
5. 2- 3 (0) 5.2-4 (0) (5) 5.2-4a (5)
5. 2- 5 (0) (5) 5.2-Sa (5)
5. 2- 5b (5) (7)
5. 2- Sc (5) (7)
5. 2- 5d (5) (7)
5. 2- 6 (0). (5) (7) 5.2-7 (0) (5) (7) 5.2-7a (5) (7)
5. 2- 0 (0) (5) (7) 5.2-Ga (5) (7) 5.2-9 (0) (5) (7) 5.2- 10 (0) (5) (7) 5.2-11 (0) (5) (7)

EFFECTIVE PAGE LISTING GIBBSSAP: VOLUME 2 5.2-12 (0) (5) (7)

T5.2-1 (5) (7)

T5.2-2 (7)

F5.2-1 (0) (5-deleted) 5.3-1 (0)

5. 4- t (0) 5.4-2 (0) (2)

TS.4-1 (0)

(UNNUMBERED CONTENTS PAGES) (0) (1-deleted) 6-i (1) 6-11 (1) 6-iii (1) 6-iv (1) (2) 6-iva (1) 6-v (1) 6-vi (1) 6-vii (1) (2) 6-viii (1) (2) 6-viiia ( 2) 6-ix (1) 6-x (1) 6-xi (1) (2) 6-xia (2) 6-xii ( 1) 6.1- 1 (0) 6.1-2 (0) (1) 6.1- 3 (0) (1) 6.1-4 (0) (1) (6) 6.1- 5 (0) 6.1-6 (0)

T6.1-1 SH.1 (0) ( 3) 76.1-1 SH.2 (3)

T6.1-1 SH.3 (3)

T6.1-2 SH.1 (0) (1)

T6.1-2 SH.2 (0) (1) 76.1-3 "(0) (1)

T6.1-4 (0) (1)

T6.1-5 (0)

T6.1-6 (G) (4) (9)

T6.1-7 (0) (1)

T6.1-8 (0) 6.2-1 (0) (1) (5) (7) (8)

6. 2- 1a (7) 6.2-2 (0) (1) (5) (7) 6.2-2a (5) (7)
6. 2- 3 (0) (7) 6.2-4 (0) (1) (7) (8)
6. 2- 5 (0) (1) (7) (8)

EFFECTIVE PAGE LISTING GIBBSSAP: VOLUME 2 6.2-6 (0) (7) 6.2-7 (0) (7) 6.2-7a (7)

6. 2- 8 (0) (7) 6.2-9 (0) (1) (7) 6.2-9a (7) (8) 6.2-10 (0) (1) (7) (8) 6.2-10a (8) 5.2-11 (0) (7) (8) 6.2-12 (0) (7) (8) 6.2-13 (0) (1) 6.2- 14 (0) 6.2-15 (0) (1) 6.2-16 (0) (1) (2) (8) 6.2-16a (8) 6.2- 17 (0) (1) (8) 6.2-18 (0) (8) 6.2-19 ( O'.

6.2- 20 th (1, 6.2-21 (0) 6.2-22 (0) (1) 6.2-23 (0) (1) (9) 6.2- 24 (0) (1) (9) 6.2-25 (0) (1) (4) (9)

6. 2- 2 5a (4) (9) 6.2- 26 (0) (1) (4) (7) (9) 6.2-27 (0) (1) (4) (7) (9) 6.2-28 (0) (1) (4) (7) (9) 6.2- 29 (0) (1) (4) (6) (7) (9)
6. 2- 2 9a (4) (6) (7) 6.2-29b (6) (7) (9)
6. 2- 29c (7) (9) 6.2-30 (0) (2) (4) (7) 6.2-31 (0) (1) 6.2-32 (0) (1) 6.2-33 -(0) (1) 6.2-34 (0) (1) 6.2-35 (0) (1) 6.2- 36 (0) (1) 6.2-37 (0) (1) 6.2-38 (0) 6.2-39 (0) (1) 6.2-40 (0) 6.2-41 (0) 6.2-42 (0) (1)
6. 2- 4 2a (1) 6.2-43 (0) (1) 6.2-44 (0) (1)

EFFECTIVE PAGE LISTING GIBBSSAF: VOLUME 2 6.2-45 (0) 6.2-46 (0) (1) (6)

6. 2- 47 (0) (1) (6) (9) 6.2-47a (9) 6.2-48 (0) (1) (9)
6. 2- 49 (0) (1) (6) (9) 6.2-49a (6) 6.2- 50 (0) (3) (6)
6. 2- 50a (3) ( 6-de leted) 6.2-51 (0) (3) (6) 6.2- 52 (0) (3) (6) 6.2-52a (3) (6-deleted) 6.2-53 (0) (3) (6) 6.2- 54 (0) (1) 6.2-55 (0) (1) 6.2- 56 (0) 6.2- 57 (0) 6.2-58 10) (1)
6. 2- 59 (0)

T6.2-1 (0) (7) (8)

T6.2-2 (0) (4) (7)

T6.2-3 (0) (1) (4) (7) 76.2-4 SH.1 (0) (1) (4) (7)

T6.2-4 SH.2 (7)

T6.2-5 (0) (8)

T6.2-6 SH.1 (0) (1) (7) (8)

T6.2-6 SH.2 (0) (1) (7) (8)

T6.2-6 SH.3 (7) (8)

T6.2-7 SH.1 (0) (1) (7)

T6.2-7 SH.2 (0) (1) (7) 76.2-7 SH.3 (7)

T6.2-8 (0)

T6.2-9 (0) (4) (7)

T6. 2- 10 A (0) (~) (7)

T6.2-10B (7)

T6.2-10C (7) 76.2-10D (7)

T6.2-11 (0) (1) (8)

T6.2-12 (0) (1) (8)

T6.2-13 (0) (1) (2)

T6.2-14 SH.1 (8)

T6.2-14 SH.2 (8) 76.2-14a SH.1 (0) (8-deleted)

T6.2-14a SH.2 (0) (8-deleted)

T6.2-14a SH.3 (0) (8-deleted) 76.2-14a SH.4 (0) (8-deleted)

T6.2-14a SH.5 (0) (8-deleted)

T6.2-14a SH.6 (0) (8-deleted) 76.2-14a SH.7 (0) (8-deleted)

EFFECTIVF PAGE IISTING GIPBSSAP: VOLUME 2 76.2-14a SH.8 (0) (8-deleted)

T6.2-14a SH.9 (0) (8-deleted)

T6. 2 -14a SH.10 (0) (8-deleted) 76.2-14a SH.11 (0) (8-deleted)

T6.2-14a SH.12 (0) (8 -deleted)

T6.2-14a SH.13 (0) (8-deleted) 76.2-14b SH.1 (0) (8-deleted)

T6.2-14b SH.2 (0) (8-deleted)

T6.2-14b SH.3 (0) (8-deleted)

T6.2-14b SH.4 (0) (8 -deleted)

T6.2-14b SH.S (0) (8-deleted)

T6.2-14b SH.6 (0) (8-deleted)

T6.2-14b SH.7 (0) (8-deleted)

T6.2-14b SH.8 (0) (8-deleted)

T6.2-14c SH.1 (0) (8-deleted)

T6.2-14c SH.2 (0) (8-deleted)

T6.2-14c SH.3 (0) (8-deleted)

T6.2-14c SH.4 (0) (8-deleted)

T6.2-14c SH.S (0) (8-deleted) 76.2-14d SH.1 g0) (8-deleted)

T6. 2- 14d SH.2 (0) (8-deleted)

T6.2-14d SH.3 (0) (8-deleted)

T6.2-14d SH.4 (0) (8-deleted)

T6.2-14d SH.S (0) (8-deleted)

T6.2-14d SH.6 (0) (8-deleted)

T6.2-14d SH.7 (0) (8-deleted)

T6.2-14d SH.8 (0) (8-deleted)

T6.2-14d SH.9 (0) (8-deleted) 76.2-14e SH.1 (0) (8-deleted)

T6.2-14e SH.2 (0) (8-deleted) 76.2-14e SH.3 (0) (8-dele ted) 76.2-14e SH.4 (0) (8-deleted)

T6.2-14e SH.S (0) (8-deleted)

T6.2-15a SH.1 (0) (1) 76.2-15a SH.2 (0) (1)

T6.2-15a SH.3 (0) (1)

T6.2-15a SH.4 (0) (1) 76.2-15b (0) (1)

T6.2-15c (0) (1)

T6.2-15d (0) (1) (2)

T6.2-16a SH.1 (0) (1)

T6.2-16n SH.2 (0) (1)

T6.2-16a SH.3 (0) (1)

T6.2-16a SH.4 (0) (1)

T6.2-16b (0) (1)

T6.2-16c (0) (1)

T6.2-16d (0) (1)

T6.2-17a SH.1 (0) (1)

T6.2-17a SH.2 (0) (1)

EFFECTIVE PAGE LISTING GIPBSSAR: VOLUME ?

T6.2-17a SH.3 (0) (1)

T6.2-17b (0) (1)

T6.2-17c (0) (1)

T6.2-17d (0) (1)

T6.2-17e (0) (1) (2)

T6.2-18 SH.1 (0) (4)

T6.2-18 SH.2 (c' (2) (4)

T6.2-18 Sh.2a (4) 76.2-18 SH.3 (0) ( 2)

T6.2-19 SH.1 (0) (4) (5)

T6.2-19 SH.1A (0)

T6. 2- 19 SH.2 (0) (1) (2) (3) (5)

T6.2-19 SH.2A (0) (2) (5)

T6.2-19 SH.3 (0) (1) (5)

T6.2-19 SH.3A (0) (1) (5)

T6.2-19 SH.4 (0) (1) (5)

T6.2-19 SH.4a (5)

T6.2-19 SH.4A (0) (1) (5)

T5.2-19 SH.4Aa (5)

T6.2-19 SH.5 (0) (1) (2) (5)

T6.2-19 SH.Sa (5) 76.2-19 SH.5A (0) (1) (5)

T6.2-19 SH.6 (0) (1) (5) (9)

T6.2-19 SH.6A (0) (1) (5) (9) 76.2-19 SH.7 (0) (1) (4) (5) 76.2-19 SH.7A (0) (1) (4) (5)

T6.2-19 SH.8 (0) (1) (5)

T6.2-19 SH.8a (5)

T6.2-20 (0)

T6.2-21 (0)

T6-2-22 (0)

T6.2-23 SH.1 (0)

T6.2-23 SH.2 (0) (1)

T6.2-23 SH.3 (0) (1) (2)

T6.2-23 SH.3a (2)

T6.2-23 SH.4 (0)

T6.2-24 (0) (3-deleted)

T6.2-25 (c) (2)

T6.2-26 (2)

T6.2-27 (2)

T6.2-28 SH.1 ( 2)

T6.2-28 SH.2 (2)

T6.2-29 (7) 76.2-30 (7)

T6.2-31 (?)

F6.2-1 (0)

F6.2-2 (0)

F6.2-3 (0)

FC.2-4 (0)

EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 2 F6.2-5 (0)

F6.2-6 (0)

F6.2-7 (0)

F6.2-8 (0)

F6.2-9 (0)

F6.2-10 (0)

F6.2-11 (0)

F6.2-12 (0)

F6.2-13 (0) (8-deleted)

F6.2-14 (0) (8-deleted)

F6.2-15 (0) (8-deleted)

F6.2-16 (0) (8-deleted)

F6.2-17 (0) (8-deleted)

F6.2-17A (8)

F6.2-17B (8)

F6.2-18 (0) (8-deleted)

F6.2-19 (0) (8-deleted)

F6.2-20 (0) (8-deleted)

F6.2-21A (0)

F6.2-21B SH. 1 (0)

F6.2-21B SH. 2 (6)

F6.2-21B SH. 3 (6)

F6.2-21C (0)

F6.2-21D (0) ( 2) v6.2-22A (0)

F6.2-22B (0)

F6.2-22C SH. 1 (0) (2)

F6.2-22C SH. 2 (6)

F6.2-22C SE. 3 (6)

F6.2-22D (0) (2)

F6.2-22E (0) (2)

F6.2-23A (0)

F6.2-23B SH. 1 (0)

F6.2-23B SH. 2 (6)

F6.2-23B SH. 3 (6)

F6.2-23C SH. 1 (0)

F6.2-23C SH. 2 (6)

F6.2-23C SH. 3 (6)

F6.2-23D (0)

F6.2-23E (0)

F6.2-23F (2)

F6.2-24 (0)

F6.2-25 (0) (2) (9)

F6.2-26 (0)

F6.2-27 (0) (6)

F6.2-28 SH.1 (0) (5) (6)

F6.2-28 SH.2 (0) (1) (S) (6)

F6.2-28 SH.3 (0) (2) (5) (6)

F6.2-28 SH.4 (0) (2) (5) (6)

EFFECTIVE PAGE LISTING GIBBSSAB: VOLUME 2 F6.2-28 SH.5 (0) (6)

F6.2-29 (0) (1)

F6.2-30 (1)

F_6.2-31 (1)

F6.2-32 (1)

F6.2-33 ( 1) r6.2-34 (1)

F6.2-35 (6)

6. 3- 1 (0) (5) 6.4-1 (0) (1) (2) 6.4-2 (0) (1) (2)
6. 4- 3 (0) 6.4-4 (0) (1) (2)
6. 4- 5 (0) (1) (2) 6.4-Sa (2)
6. 4- 6 (0) (1) (2) 6.4-7 (0) (1) (2) (5) 6.4-7a (5)
6. 4- 8 (0) (1) (2) 6.4-9 (0) (1) (2)
6. 4- 9a (2) 6.4-10 (1) 76.4-1 (0)

T6.4-2 (0)

T6.4-3 SH.1 (0) (2)

T6.4-3 SH.2 (0) (2)

F6.4-1 (0)

6. 5- 1 (0) (1) (4) (8) 6.5-2 (0) (1) (4) (8) 6.5-2a (8) 6.5-3 (0) (1) (4) 6.5-4 (0) (1) (4) (9)
6. 5- 5 (0) (1) (4) (9)
6. 5- Sa (9) 6.5-6 (0) (1) (4) (9)
6. 5- 7 (0) (1) (4) (9) 6.5-7a . (9)
6. 5- 8 (0) (1) (4) (9)
6. 5- 9 (0) (1) (4) (9) 6.5-10 (0) (1) (4) (9)
6. 5- 10a (9) 6.5-11 (0) (1) (4) 6.5-12 (0) (1) (4) 6.5- 13 (0) (1) (4) 6.5-14 (0) (1) (4) 6.5- 15 (0) (1) (4-deleted) 6.5-16 (0) (1) (4-deleted) 6.5-17 (0) (1) (4) (9) 6.5- 18 (0) (1) (9)

EFFECTIVE PAGE LISTING GIPESSAF: VOLUME 2 6.5- 19 (0) (1) (4) (6) (9)

6. 5- 19a (4) (9) 6.5-20 (0) (1) 6.5- 21 (0) (1) (4) 6.5-22 (0) (1) (4)

T6.5-1 SH.1 (0) (4) (6) (8)

T6.5-1 SH.1a (8)

T6.5-1 SH.2 (0) (4) (6) (8)

T6.5-1 SH.3 (0) (4) (6) (8) 76.5-1 SH.3a (8)

T6.5-1 SH.4 (0) (4) (6) (8)

T6.5-1 SH.5 (0) (4) (6)

T6.5-1 SH.sa (8)

T6.5-1 SH.6 (0) (4) (6) (8)

T6.5-1 SH 6a (8)

T6.5-1 SH.7 (0) (4) (6) (8)

T6.5-1 SH.8 (0) ( 4) (6) (8)

T6.5-1 SH.9 (0) (4) (6) (8)

T6.5-1 SH.10 (0) (4) (6) (8) 76.5-1 SH.11 (0) (4) ( 6-delet ed)

T6.5-1 SH.12 (0) (4) (6-deleted)

T6.5-1 SH.13 (0) (4) (6-deleted)

T6.5-1 SH.14 (0) (4) (6-delet ed)

T6.5-1 SH.15 (0) (4) (6-deleted)

T6.5-2 (0) (1) (4) 76.5-3 (0) (6) (9) 76.5-4 SH.1 (0) (9)

T6.5-4 SH.2 (0) (9)

T6.5-5 (0) (4) 76.5-6 (0) (4) (9)

T6.5-7 (5) (9)

F6.5-1 (0)

F6.5-2 (0)

F6.5-3 (5)

F6.5-4 (0) (5)

6. 6- 1 (0) ,

(UNNUMBERED PAGE) (0) 4 :, ,

EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 3 7-1 (0) (1) (2) 7-11 (0) (2) (3) 7-iii (0) (9) 7-iv (0) (1) (2) (9) 7-iva (9) 7-ivt (9) 7-ive (9) 7.1- 1 (0) (1) 7.1-2 (0) (1) 7.1- 3 (0) (1) (3) 7.1-4 (0) (1) (3) (9) 7.1- 5 (3) (1) (9)

/.1- 6 (0) (1) 7.1-7 (1) 7.1-6 (1) 7.1-9 ( 1) (3)

7. 1- 10 (1) 7.1-11 ( 1) 7.1-12 (1) 7.1- 13 ( 1) 7.1- 14 (1) (3) (4) 7.1- 15 ( 1) 7.1- 16 (1) 7.1-17 (1)
7. 1- 18 (1) 77.1-1 Sh. 1 (8) 77.1-1 Sh. 2 (8)

T7.1-1 Sh. 3 (8) 77.1-1 Sh. 4 (8)

T7.1-1 Sh. 5 (8) 77.1-1 Sh. 6 (8) 77.1-1 Sh. 7 (8) 77.1-1 Sh. 8 (8)

T7.1-1 Sh. 9 (8) 77.1-1 Sh. 10 (8)

7. 2- 1 (0) (1) 7.3-1 (0) (1) (3) (5) (6)
7. 3- 2 (0) (1) (5) 7.3-2a '( 1)
7. 3- 3 (0) (1) (5) (6) (9) 7.3-3a (6) (9) 7.3-4 (0) (1) (6) (9) 7.3-4a (6) 7.3-5 (0) (1) 7.3-6 (0) (1) ( 3) 7.3-7 (0) (3-deleted) 7.3-8 (0) (1) (3) (6)
7. 3- 9 (0) (1) 7.3- 10 (0) (1) (3) (6) (9) 7.3- 11 (0) (1) (3) 7.3- 12 (0) (1) (3)

EFFECTIVE PAGE LISTING GIEBSSAR: VOLUME 3 7.3- 13 (0) (2) (5) 7.3- 14 (0) (1) (2) (3)

7. 3- 14a (2) 7.3- 15 (0) (2) (3) (5) (6)
7. 4- 15a (1) (5) (6) 7.3-16 (0) (1) (6) 7 . 3- 1 t' a (6) 7.3-17 (0) (1) (9) 7.3-18 (0) (1) (2) 7.3- 19 (2) (3) 7.3-20 (2) 7.3-21 (2) 7.3-22 (2) (3) 7.3-23 (2) (3) 7.3-24 (2) (3) 7.3-25 (2) (3) 7.3-26 (2) (3)

F7.3-1 SH. 1 (0) (9)

F7,3-1 SH. 2 , ( 0) (9)

F7.3-1 SH. 3-9 (0) (1) (9)-deleted F7.3-1 SH. 10 (0) (1) (6) (9)

F7 3-1 SH. 11' (0) (2) (9) r1.3-1 SH. 12 i (0) (2) (9)

F7.3-1 SH. 13 (0) (2) (9)

F7.3-1 SH. 14 (0) (2) (9)

F7.3-1 SH. 15 (0) (2) (9)

F7.3-1 SH. 16 (0) (1) (9)

F7.3-2 SH. 1 (0) (1)

F7.3-2 SH. 2 (0) (1)

F7.3-2 SH. 3 (0) (1)

7. 4- 1 (0) (1) (6) 7.4-la (6) 7.4-2 '.0) (1) (6)
7. 5- 1 (0) (1) (6) 7.5-2 (1) 7.5-3 (1) (6) 7.5-4 (1) 17.5-1 SH. 1 (0) (1)

T7.5-1 SH. 2 (0) (1)

T7.5-1 SH. 3 (0) (1-deleted)

7. 6- 1 (0) (6) 7.6-1a (6) 7.6-1b (6)
7. 6- 2 (0) (6) 7.6-3 (0) (1) (6) 7.6-3a (6) 7.6-4 (0) (1) (6) 7.7- 1 (0) (1) (3) 7.7-1a (1) (2) (3) 7.7-lh (1) (2) (3) (4) 7.7-1c (2) (3) (4) (6)

EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 3 7.7-1d (3)

7. 7- 2 (0) (1) (2) (4) 7.7-3 (3)

F7.7-1 (1) (2)

F7.7-2 (2) 7.8-1 (0) ( i) (2) 7.8-2 (0) (1) (2) 7.8-2a (2) 7.S-3 (1) (2) 7.8-3a (2) 7.8-4 (1) (2)

7. 8- 5 (1) (2) 7.8-Sa (2)
7. 8- 6 (1) (2) 7.8-7 (1) (2) (3) 7.8-8 (3) 8-1 (0) (1) 8-ii (0) (1) 8-111 (0) (1) 8-iv (0) (1) 8.1- 1 (0) (1) '

8.1- 2 (0) 8.1-3 (0) 8.1- 4 (0) 8.1-5 (0) 8.1- 6 (0) 8.1-7 (0) 8.1- 8 (0) 8.1-9 (0) 8.1-10 '

(0) 8.1-11 (0) (1) 78.4-1 SH. 1 (0) (1) 78.1-1 SH. 2 (0) (1) 78.1-1 SH. 3 (0) (1-deleted) 8.2-1 (0)

8. 3- 1 (0) (1) 8.3-2 (0)
8. 3- 3 (0) (1) 8.3-4 (0).
8. 3- 5 (0) 8.3-6 (0)
8. 3- 7 (0) 8.3-8 (0) 8.3-9 (0) (1) 8.3- 10 (0) (1) 8.3- 11 (0) (1) i 8.3- 12 (0) 8.3- 13 (0) (1) 8.3-14 (0) (1) 8.3- 15 (0) (1) 8.3- 16 (0)

EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 3

8. 3- 17 (0) 8.3-18 (0) 8.3- 19 (0) (1) (2) 8.3-20 (0) (1) 8.3-21 (0) (1) 8.3-22 (0) (1) 8.3-23 (0) (1) 8.3-24 (0) (1) 8.3-25 (0) (1) 8.3-26 (0) (1) 8.3-27 (0) (1) 8.3-28 (0) (1)
8. 3- 28a (1) 8.3-29 (0) 8.3-30 (0) (1) 8.3-31 (0) (1) 8.3-31a (1) 8.3-32 (0) 8.3-33 (0) 8.3-34 (0) 8.3-35 (0) (1) 8.3-36 (0) (1) 8.3-37 (0) (1) 8.3-38 (0) (1) 6.3-39 (0) 8.3-40 (0) 8.3-41 (0) 8.3-42 (0) 8.3-43 (0) 8.3-44 (0) (1) 78.3-1 SH. 1 (0) 78.3-1 SH. 2 (0)

T8.3-1 SH. 3 (0)

T8.3-1 SH. 4 (0) 78.3-1 SH. 5 (0) 78.3-1 SH. 6 (0) 18.3-1 SH. 7 (0)

T8.3-1 SH. 8 (0) 18.3-1 SH. 9 (0) 78.3-2 SH. 1 ( 0)

T8.3-2 SH. 2 (0)

T8.3-3 SH. 3 (0)

T8.3-2 SH. 4 (0) (1)

T8.3-2 SH. 5 (0) 78.3-2 SH. 6 (0) 78.3-2 SH. 7 (0)

T8.3-2 SH. 8 (0) 78.3-3 SH. 1 (0)

T8.3-3 SH. 2 (0) 78.3-3 SH. 3 (0) 78.3-3 SH. 4 (0)

EFFECTIVE PAGE LISTING GIEBSSAR: VCLUME 3 78.3-3 SH. 5 (0) 78.3-3 SH. 6 (0)

T8.3-3 SH. 7 (0) 78.3-3 SH. 8 (0)

T8.3-3 SH. 9 (0) 78.3-3 SH. 10 (0)

T8.3-3 SH. 11 (0) 78.3-3 SH. 12 ( 0, 78.3-3 SH. 13 (0) 78.3-3 SH. 14 (0)

T8.3-3 SH. 15 (0)

T8.3-3 SH. 16 (0) 78.3-3 SH. 17 (0) 78.3-3 SH. 18 (0)

T8.3-3 EH. 19 (0) (1) 78.3-4 (0) 78.3-5 (0)

T8.3-6 SH. 1 (0)

T8.3-6 SH. 2 (0) 78.3-6 SH. 3 (0)

T8.3-6 SH. 4 (0)

T8.3-6 SH. 5 (0)

T8.3-6 SH. 6 (0) 78.3-6 SH. 7 (0) 78.3-6 SH. 8 (0)

T8.3-6 SH. 9 (0)

T8.3-6 SH. 10 (0)

T8.3-6 SH. 11 (0) 78.3-6 SH. 12 (0)

T8.3-7 SH. 1 (0) 78.3-7 SH. 2 (0)

T8.3-7 SH. 3 (0)

T8.3-7 SH. 4 (0)

F8.3-1 (0) (2)

F8.3-2 (0)

F8.3-3 (0)

F8.3-4 (0)

F8.3-5 (0)

F8.3-6 (0)

F8.3-7 (0)

F8.3-8 (0)

F8.3-9 (0)

F8.3-10 (0)

F8.3-11 (0) 8.4-1 (0) 78.4-1 SH. 1 (0) (1)

T8.4-1 SH. 2 (0) (1) 78.4-1 SH. 3 (0) (1) 78.4-1 SU. 4 (0) (1)

EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 3 (12 unnumbered contents pages Section 9) (0) (2-deleted) i (2) ii (2) ill (2) iv (2) v (2) vi (2) vii (2) viii (2) ix (2) x (2) xi (2) xia (2) xii (2) 9.1- 1 (0) (2) 9.1-2 (0) (2) 9.1- 2a (2) 9.1-3 (0) (2) (9) 9.1-4 (0) (2) 9.1- 5 (0) (2) 9.1-Sa (2) 9.1- 6 (0) (2) (6) 9.1-6a (2) (6) 9.1-7 (0) (1) 9.1- 7a (1) 9.1-8 (0) 9.1- 9 (0) (1) 9.1-10 (0) (1) (2) 9.1- 10a ( 1) 9.1- 11 (0) (1) (2) 9.1-12 (0) (1) (2)

9. 1- 13 (0) (1) (2)
9. 1- 14 (0) (1) 79.1-1 (0) (1) 79.1-2 (0) (1)

T9.1-3 SH. 1 (0) (1) 79.1-3 SH. 2 ,(1) 79.1-4 SH. 1 (0) (1) 79,1-4 SH. 2 (1)

T9.1-4 SH. 3 (0) (1) 79.1-4 SH. 4 (1)

T9.1-5 SH. 1 (0) (1)

T9.1-5 SH. 2 (0) (1)

F9.1-1 (0) (1) (2) (6-deleted)

F9.1-2 (0) (1) (2) (6-deleted)

F9.1-3 (0) (4) (6)

F9.1-3a SH. 1 (6)

F9.1-3a SH. 2 (6)

F9.1-3b SH. 1 (6)

EFFECTIVE PAGE LISTING GIBBESAR: VOLUME 3 F9.1-4 (0) r9.1-5 (2) (6)

9. 2- 1 (0) (6) (9) 9.2-la (6) (9) 9.2-2 (0) (9)
9. 2- 3 (0) (9) 9.2-4 (0) (1) 9.2-5 (0) (1) (9) 9.2-6 (0) (9) 9.2-7 (0) (4) (9) 9.2-8 (0) (2) (4) (9) 9.2-8a (9) 9.2-9 (0) (9)
9. 2- 10 (0) (4) (9) 9.2-11 (0) (6) (9) 9.2-12 (0) (1) (6) (9) 9.2- 13 (0) (1) (6) (9)
9. 2- 13a (6) (9)
9. 2- 14 (0) (1) (2) 9.2-15 (0) (1) 9.2-16 (0) (1) (6) (9)
9. 2- 17 (0) O) (9) 9.2- 18 (0) (1) (6) (9)
9. 2- 18a (6) (9) 9.2-19 (0) (9) 9.2-20 (0) (9) 9.2-20a (9) 9.2-21 (0) (9) 9.2-22 (0) (9) 9.2-23 (0) (1) (9) 9.2-24 (0) (9) 9.2-25 (0) (9) 9.2-26 (0) (1) (6) (9) 9.2-26a (6) 9.2- 27 (0) (1) (6) (9) 79.2-1 SH. 1 (0) (1) (9) 79.2-1 SH. 2 (1) (9)

T9.2-2 SH. 1 (0) (1) (9)

T9.2-2 SH. 2 ( 1) (9) 79.2-3 (0) (1) (9) 79.2-4 (0) 79.2-5 SH. 1 (0) (1) (6) 79.2-5 SH. 2 (0) (1) (6)

T9.2-6 SH. 1 (0) (1) (4) (9) 79.2-6 SH. 2 (0) (1) (2) (4) (9)

T9.2-6 SH. 3 (0) (1) (2) (4) (9)

T9.2-6 SH. 4 (1) (4) (9) 79.2-6 SH. 5 (1) (2) (4) (9) 79.2-6 SH. 6 (1) (2) (4) (9) 79.2-6 SH. 6a (9)

T9.2-7 SH. 1 (0) (1) (4) (9)

EFFECTIVF PAGE LISTIt1G GIBBSSAB: VCLUME 3 79.2-7 SH. 2 (0) (1) (2) (4) (9) 79.2-7 SH. 3 (0) (1) (2) (4) (9) 79.2-7 SH. 4 (1) (4) (9)

T9.2-7 SH. 5 (1) (2) (4) (9) 79.2-7 SH. 6 (1) (2) (4) (9) 79.2-7 SH. 6a (9) 79.2-8 SH. 1 (0) (1) (9)

T9.2-8 SH. 2 (0) (1) (9) 79.2-8 SH. 3 (0) (1) (9) 79.2-9 SH. 1 (0) 79.2-9 SH. 2 (0) 79.2-10 (0) (1) (6)

T9.2-11 (0) 79.2-12 (0) (1) 79.2-13 (0) (6-deleted)

T9.2-14 (2)

F9.2-1 (0) (6) (9)

F9.2-1a SH. 1 (6)

F9.2-2b SH. 1 (6}

F9.2-2 (0) (6) (9)

F9.2-3 (0) (2) (4) (6)

F9.2-4 (0) (2) (4) (6)

F9.2-4a SH. 1 (6)

F9.2-4a SH. 2 (6)

F9.2-4a SH. 3 (6)

F9.2-4b SH. 1 (6)

F9.2-4b SH. 2 (6)

F9.2-5 (0) (2) (9)

F9.2-6 (0) (2) (9)

F9.2-7 (0) (1) (6)

9. 3- 1 (0) (1) (4) 9.3-2 (0) (1)
9. 3- 3 (0) (4) 9.3-4 (0) (2) (4) 9.3-4a (2' (4) 9.3-4b (2?
9. 3- 5 (0) (1) (2) (4) 9.3-5A (2) 9.3-6 (0) 9.3-7 (0) (1) 9.3-8 (0) ( 2)
9. 3- Ea (2) 9.3-9 (0) (2)
9. 3- 9a (2) 9.3-Sb (2) 9.3- 10 (0) (2) (6)
9. 3- 10a (6) 9.3-11 (0) (1) (2) (6) 9.3-12 (0) (1) 9.3- 13 (0) (1) (6) 79.3-1 (0) ( 2)

EFFECTIVE PAGE LISTING GIBBESAF: VOLUME 3 T9.3-2 (0) (2)

T9.3-2 (cont.) (0) (2-deleted) 79.3-2 (cont.) (0) (2-deleted) 79.3-2 SH. 1 (0) (2-deleted) 79.3-2 SH. 2 (0) (2-deleted) 79.3-2 SH. 3 (0) (2-deleted)

T9.3-2 SH. 4 (0) (2-deleted) 79.3-3 (2) 79.3-4 SH. 1 (2) 79.3-4 SH. 2 (2) 79.3-4 SH. 3 (2) 79.3-4 SH. 4 (2) 79.3-6 (6)

F9.3-1 (0) (2)

F9.3-2 (2) (6)

F9.3-2a SH. 1 (6)

F9.3-2b SH. 1 (6)

F9.3-3 SH. 1 (6)

F9.3-3 SH. 2 (6)

F9.3-4 (6) 9.4-1 (0) (1) (6) (8) 9.4-la (6) (8-deleted)

9. 4- 2 (0) (1) (2) (5) (6) (8) 9.4-3 (0) (1) (6) (8) 9.4-3a (8)
9. 4- 4 (0) ( 2) (6) (8) 9.4-5 (0) (1) (2) (8) 9.4-6 (0) (1) (2) (8) 9.4-6a (2) (8) 9.4-6b (8) 9.4-7 (0) (1) (2) (3) (5) (8)
9. 4- 7a (1) (8) 9.4-8 (0) (1) (3). (5) (6) (8)
9. 4- 9 (0) (1) (2) (6) 9.4-9a (2) (6) 9.4-10 (0) (1) (2) (3) (5) (6)
9. 4- 10a (2) (3) 9.4-11 (0) (1) (2) (5) (6)
9. 4- 11a (6) 9.4- 12 (0) (1) 9.4-13 (0) (6) 9.4- 14 (0) (1) (2) (S) (6)
9. 4- 14a (6) 9.4-15 (0) (1) (3) (5) (6) 9.4- 16 (0) (1) (2) (3) (5) (6)
9. 4- 16a (2) 9.4- 17 (0) ( 1) (2) (6) 9.4- 18 (0) (1) (2) 9.4- 19 (0) (1) (2) (5) (6) 9.4-20 (0) (1) (2)
9. 4- 2 0a (2) (3)

EFFECTIVE PAGE LISTING GIBESSAB: VCLUME 3 9.4-21 (0) (1) (3) (5) (6) 9.4-22 (0) (1) (3) (5) (6) 9.4-23 (0) (1) (3)

9. 4- 2 3a (1) (3) 9.4-24 (0) (1) (2) (3) (5) 9.4-24a (2) (5) 9.4-25 (0) (2) (3) 9.4-25a (2) 9.4-26 (0) (1) (2) (5) (6) 9.4-27 (0) (1) (2) (3) 9.4-27a (3) 9.4-28 (0) (1) (3) f.6) 9.4-28a (6) 9.4- 29 (0) (1) 9.4-30 (0) (1) (2) (6) 9.4-31 (0) (1) (2) (6)
9. 4- 31a (2) (6) 9.4-32 (0) (1) (2) (6) 9.4-33 (0) (2) (3) (6) 9.4-34 (0) (6) 9.4-34a (2) (6) 9.4-35 (1) (2) (6) 19.4-1 (0) (1) (6)

T9.4-2 (0) (1) (6) 79.4-3 (0) (1) (2) (8) 19.4-4 SH. (0) (1) (2) (3) 79.4-4 SH. 2 (0) (1) (2) (3) 79.4-5 SH. 1 (0) (1) (3) 79.4-5 SH. 2 (0) 19.4-6 SH. 1 (0) (1) (2) (6)

T9.4-6 SH. 2 (0) (1) (2) (6) 79.4-6 SH. 2a (2) (6-deleted) 79.4-6 SH. 3 (0) (1) (2) (6-deleted)

TS.4-7 (0) (1) (6) 79.4-8 SH. 1 (0) (3) (5) 79.4-8 SH. 2 (0) (3) (5)

T9.4-8 SH. 3 (0) ( 2) 79.4-9 SH. 1 (0) (1) (2) (3) (5) 79.4-9 SH. 2 (0) (1) (2) (3) (5) 9.4- 10 (6) 9.4- 11 (6) 9.4-12 (6)

F9.4-1 (0) ( 2) (6) (8)

F9.4-2 (0) (1-deleted) (5) (6)

F9.4-3 (0) (1-deleted) (6)

F9.4-4 (0) (1-deleted)

F9.4-5 (0) (6) (9)

F9.4-6 (0) (3) (5) (6) (9)

F9.4-7 (0) (5)

F9.4-8 (0) (2)

F9.4-9 (0) (3) (5)

EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 3 F9.4-10 (0) (2) (5)

F9.4-11 (0) ( 2)

F9.4-12 (0) (3) (5)

F9.4-13 (0) (2)

F9.4-14 (0) (2) (5) (6)

F9.4-15 (C) (2)

F9.4-16 (0) (2) (8)

F9.4-17 (0) (2)

F9.4-18 (2)

9. 5- 1 (0) (1) (8)
9. 5- 2 (0) (8) 9.5-3 (0) (8) 9.5-4 (0) (1) (8) 9.5-5 (C (1) (8) 9.5-6 (Of (8) 9.5-7 (0) (8) 9.5-8 (0) (8)
9. 5- 9 (0) (8) 9.5-10 (0) (1) (8) 9.5-11 (0) (8) 9.5- 12 (0) (8) 9.5- 13 (0) (8) 9.5-14 (0) (1) (8) 9.5- 15 (0) (1) (8) 9.5- 16 (0) (1) (8) 9.5-17 (0) (8) 9.5- 18 (0) (8) 9.5- 19 (0) (1) (8) 9.5-20 (0) (1) (8) 9.5-21 (0) (1) (8) 9.5-22 (0) (1) (8) 9.5-23 (0) (1) (8) 9.5-23a (8)
9. 5- 23t (8) 9.5-23c (8) 9.5-23d (8)
9. 5- 2 3e (8) 9.5-23f (8) 9.5-23g (8)
9. 5- 2 3h (8) 9.5-23i (8) 9.5-23j (8)
9. 5- 2 3k (8) 9.5-231 (8) 9.5-24 (0) '(9) 9.5-24a (9) 9.5-25 (0) (1) (9)
9. 5- 25a (9) 9.5-25c (9)
9. 5- 25d (9) 9.5-26 (0) (1) (9)

EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 3 9.5-27 (0) (1) (9)

9. 5- 27a (9) 9.5-28 (0) 9.5-29 (0) (1) (6) 9.5-29a (6) 9.5-30 (0) (1) (6) 9.5-30a (6) 9.5-31 (0) (6) (9) 9.5-32 (0) (1) (6) (9)
9. 5- 3 2a (6) (9) 9.5-33 (1) 9.5-34 (3) (7) 9.5-34a (7) 9.5-35 (3) (6)
9. 5- 3 5a (6) 9.5-36 (3) 19.5-1 SH. 1 (0) (1) 79.5-1 SH. 2 (0) (1) 79.5-1 SH. 3 (0) 79.5-2 (0)

T9.5-3 SH. 1 (0) (1) (2) 79.5-3 SH. 2 (0) (1) 79.5-4 (0) (1) 1).5-5 (0) (1) 79.5-6 (3) 19.5-7 SH. 1 (8)

T9.5-7 SH. 2 (8) 79.5-8 +

(8)

F9.5-1 (0) (8 deleted)

F9.5-1A (8)

F9.5-12 (8)

F9.5-2 (0)

F9.5-3 (0)

F9.5-4 (0) (6)

F9.5-5 (0) (6)

F9.5-6 (3) (6)

F9.5-7 (3)

s EFFECTIVE PAGF LISTING GIBBSSAF: VOLUME 4 10-i (0) (1) (2) 10-ii (0) 10-1i1 (0) 10-iv (0) 10 -- v (0)

'0-vi (0) (1) 10-vii (0) 10.1-1 (0) (1) (6) 10.1-2 (0) (1) 710. 1-1 (0) (1) (2) (6) 710.1-2 Sh. 1 (0) (1) (2) (6)

T10.1-2 sh. 2 (0) (1) (2) (6)

F 10.1- 1 (0)

F10.1-2 (0)

F10.1-3 (0)

F 10.1- 4 (0)

F10.1-5 (0)

F 10.1- 6 (0) 10.2-1 (0) (1) 10.2-2 (0) (1) 10.2-3 (0) (1) 10.2-4 (0) (1) 10.2-5 (0) (1) 10.2-6 (0) (1) 10.2-7 (0) (1) 10.2-8 (0) (1) 10.2-9 (0) (1) 10.2-10 (0) (1) 10.2-11 (0) (1) 10.2-12 (0) (1) (5) 10.2-13 (0) (1) (5) 10.2-14 (0) (1) (2) (5) 10.2-14a (2) (5) 10.2-14b (2) (5) 10.2-14c (5) 10.2-15 (0) (1) (2) (5) 10.2-15a (2) (5) 10.2-16 (0) (1) (5) 10.2-17 (0) (1) (5) 10.2-18 (0) (1) (5) 10.2-18a (5) 10.2-19 (0) (1) 10.3-1 (0) (1) (6) 10.3-1a (6) 10.3-2 (0) (1) (6) 10.3-3 (0) (1) (6) 10.3-3a (6) 10.3-4 (0) (1) (6) (7) 10.3-5 (0) (1) (7)

EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 4 10.3-Sa (7) 10.3-6 (0) ( t? (6) 10.3-7 (0) (1) 10.3-8 (0) (1) (6) 10.3-8a (6) 10.3-9 (0) (1) (4) (5) 10.3-10 (0) (1) (4) (5)

T10.3-1 (1)

T10.3-2 (9)

F10,3-1 (0) ( 2) (6)

F10.3-1a Sh. 1 (6)

F10,3-1a Sh. 2 (6)

F10.3-1b Sh. 1 (6)

F10.3-1b Sh. 2 (6)

F10.3-2 (0) (6)

F10.3-2a Sh. 1 (6)

F10.3-2h Sh. 1 (6) 10.4-1 (0) 10.4-2 (0) 10.4-3 (0) 10.4-4 (0) 10.4-5 (0) 10.4-6 (0) (4) (6) 10.4-7 (0) (6) 10.4-8 (0) (6) 10.4-8a (6) 10.4-9 (0)'

10.4-10 (0) (6) 10.4-10a (6)

10. 4-11 (0) (6) 10.4-12 (0) ( 6) 10.4-13 (0) (1) 10.4-14 (0) (1) (6) 10.4-14a (1) 10.4-15 (0) (6) 10.4-15a (6) 10.4-16 (0) (1) 10.4-17 (0) (6) 10.4-17a (6) 10.4-18 (0) 10.4 -19 (0) (1) 10.4-20 (0) (1) 10.4-21 (0) (1) 10.4-22 (0) 10.4-23 (0) 10.4-24 (0) 10.4 -25 (0) 10.4-26 (0) (1) 10.4-27 (0) (6)

EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 4 10.4-27a (6) 10.4-28 (0) (1) (6) (9) 10.4-28a (6) 10.4-29 (0) (1) 10.4-30 (0) (1) (6) 10.4-31 (0) (1) (6) 10.4-31a (6) 10.4-32 (0) (1) (6) 10.4-32a (1) (6) 10.4-33 (0) (1) (6) 10.4-34 (3) 10.4-35 (3)

T10.4-1 Sh. 1 (0)

T10.4-1 Sh. 2 (0)

T10.4-1 Sh. 3 (0)

T10.4-2 Sh. 1 (0) (1)

T10.4-2 Sh. 2 (0) (1)

T10.4-2 Sh. 3 (0) (1)

T10.4-3 (1)

T10.4-4 Sh. 1 (6) (9)

T10.4-4 Sh. 2 (6) (S)

T10.4-5 (6)

F10.4-1 (0) ( 2)

F10.4-2 Sh. 1 (0) (2) (6)

F10.4-2 Sh. 2 (0)

F 10. 4-3 (0) (6)

F10.4-3a Sh. 1 (6)

F10.4-3a Sh. 2 (6)

F10.4-3b Sh. 1 (6)

F10.4-4 (0)

F10.4-5 (6)

F10.4-6 (6) 11-1 ( 2) 11-11 (2)11-114 (2) 11-iv (2) 11-v (2) 11-vi (2) 11-vii (2) 11-viii (2) 11-ix (2) 11-x (2) 11-xi (2) 11.1-1 (0) (2) 11.1-2 (0) (2) 11.1-3 (0) 12-deleted) 11.1-4 (0) (2-deleted) 11.1-5 (0) (2-deleted)

T11.1-1 Sh. 1 (0) (2)

EFFECTIVE PAGE LISTING GIBBSSAF: VOLUME 4 T11.1-1 Sh. 2 (0) (2-deleted)

T11.1-1 Sh. 3 (0) ( 2-delet ed)

T 11.1- 2 sh. 1 (0) (2)

T 1 1. 1- 2 Sh. 2 (0) (2)

T11.1-3 (0) ( 2)

T11.1-4 (0) (2-deleted) 11.2-1 (0) (2) (6) 11.2-1a ( 2) (6) 11.2-2 s)o (2) 11.2-3 (0) ( 2) 11.2-3a (2) 11.2-4 (C) (2) 11.2-4a (2) 11.2-5 (G) (2) 11.2-6 (0) ( 2) 11.2-7 (0) (2) 11.2-8 (0) (2) 11.2-9 (0) (2) 11.2-10 (0) ( 2) 11.2-10a (2) 11.2-11 (0) (2) (6) 11.2-11a (2) 11.2-12 (0) (2) 11.2-13 (2)

T11.2-1 Sh. 1 (0) (2) (6) (8)

T11.2-1 sh. 2 (0) (2) (6)

T11.2-2 (0) ( 2)

T11.2-3 Sh. 1 (0) (2)

T11.2-3 Sh. 2 (2)

T 11. 2- 4 Sh. 1 (0) ( 2)

T11.2-4 Sh. la (2)

T11.2-4 Sh. 2 (0) (2)

T 11. 2- 4 Sh. 2a (2)

T11.2-4 Sh. 3 (0) (2)

T11.2-4 Sh. 4 (0) (2)

T11.2-4 Sh. 5 (0) (2)

T11.2-4 Sh. 6 (0) (2) (8)

T11.2-4 Sh. 6a (2)

T 11. 2- 4 Sh. 7 (0) (2)

T11.2-4 Sh. 8 (0) ( 2)

T11.2-5 Sh. 1 (0) (2) (6)

T11.2-5 sh. 2 (0) (2)

T11.2-5 Sh. 3 (0) ( 2) (6)

T11.2-5 Sh. 4 (0) (2-deleted)

T11.2-5 Sh. 5 (0) (2-deleted)

T 11. 2- 5 Sh. 6 (0) ( 2) 111.2-5 Sh. 7 (0) (2) (6)

T11.2-5 Sh. 8 (0) ( 2)

T 11. 2- 5 Sh. 9 (0) (2) (6)

EFFECTIVE PAGE LISTING GIBBSSAF: VOLUME 4 T11.2-5 sh. 10 (0) ( 2)

T11.2-5 Sh. 11 (0) (2)

T11.2-5 Sh. 12 (0) (2)

T 11. 2- 5 Sh. 12a (2) (6)

T11.2-5 Sh. 13 (0) (2)

T11.2-5 Sh. 14 (0) (2) (6)

T 11. 2- 5 Sh. 15 (0) (2)

T11.2-5 Sh. 16 (0) (2) (6) 711.2-5 Sh. 17 (0) ( 2)

T 11. 2- 5 Sh. 18 (0) (2-deleted)

T11.2-5 Sh. 19 (0) (2)

T11.2-5 Sh. 20 (0) (2) (6)

T 11. 2-5 Sh. 21 (0) (2-dele ted)

T11.2-5 Gh. 22 (0) ( 2-dele ted)

T11.2-5 Sh. 23 (0) (2)

T11.2-5 Sh. 24 (0) (2) (6)

T11.2-5 Sh. 25 (0) ( 2-deleted)

T11.2-5 Sh. 26 (0) (2) (6)

T11.2-5 Sh. 27 (0) (2)

T 11. 2- 5 Sh. 28 (0) ( 2) (6)

T11.2-5 Sh. 29 (0) (2)

T11.2-6 sh. 1 (0) (2)

T 11. 2- 6 sh. 2 (2)

T11.2-7 (0) (2) (6)

T11.2-8 (0) (2)

T 11. 2-9 (0) (2)

T11.2-10 ( 2) (6)

T11.2-11 ( 6)

T11.2-12 (6)

T11.2-13 (6)

T11.2-14 (6)

T11.2-15 (6)

T11.2-16 (6)

T11.2-17 (6)

T11.2-18 (6) 711.2-19 (6)

T11.2-20 (6)

T11.2-21 (6)

T 11. 2- 2 2 (6)

T11.2-23 (6)

F11.2-1 (0) (2-deleted)

F 11. 2- 2 Sh. 1 (0) (2) ( 6-delet ed)

F11.2-2 Sh. 2 (0) (2-deleted)

F11.2-3 (0) (2) (6-deleted)

F11.2-4 (0) (2) (6-deleted)

F11.2-5 (0) (2) (6-deleted)

F11.2-6 (0) (2) (6-deleted)

F11.2-7 (0) (2) (6-deleted)

F11.2-8 (0) (2) (6-deleted)

EFFECTIVF PAGE LISTING GIPESSAP: VOLUME 4 F11.2-9 (0) (2-deleted)

F11.2-10 (0) (2) (6-de let ed)

F 11. 2- 11 (0) (2) (6-delet ed)

F11.2-12 (0) (2) (6-deleted)

F11.2-13 (0) ( 2) (6-deleted)

F 11. 2- 14 (0) (2) (6-de let ed)

F11.2-15 (0) (2) (6-deleted)

F11.2-16 (0) (2) (6-deleted)

F 11. 2- 17 (0) (2-deleted)

F11.2-18 (0) (2) (6-deleted)

F11.2-19 (0) ( 2) (6-deleted)

F 11. 2- 20 (0) '(2) ( 6-delet ed)

F11.2-21 (0) ( 2) (6-deleted)

F11.2-22 (0) (2) (6-deleted)

F11.2-23 (0) (2) ( 6 -de leted)

F11.2-24 (0) ( 2) l6-deleted)

F11.2-25 (0) (2) (6-deleted)

F11.2-26 (0) (2) (6-deleted)

F11.2-27 (0) ( 2-deleted)

F11.2-28 (0) (2-deleted)

F11.2-29 (0) (2-deleted)

F11.2-30 (0) ( 2-deleted)

F11.2-31 (0) ( 2-d ele ted)

F11.2-22 Sh. 1 (0) (2-deleted)

F11.2-23 sh. 2 (0) ( 2-deleted)

F11.2-24 Sh. 3 (0) ( 2-d eleted)

F11.2-25 Sh. 4 (0) (2-deleted)

F 11. 2- 26 Sh. S (0) (2-deleted)

F11.2-32 (2) (6)

F11.2-33 (2) (6)

F11.2-34 (2) (6) 11.3-1 (0) ( 2) (6) 11.3-1a (2) 11.3-2 (0) (2) 11.3-3 (0) ( 2) 11.3-4 (0) (2) 11.3-5 (0) ( 2) 11.3-6 (0) (2) (6) 11.3-7 (0) (2) 11.3-8 (0) ( 2) 11.3-9 (0) (2) 11.3-9a (2) 11.3-10 (0) (2) 11.3-11 (0) (2) 11.3-12 (0) ( 2) 11.3-12a (2) 11.3-13 (0) (2) 11.3-14 (0) ( 2) 11.3-14a (2)

EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME 4 11.3-15 (0) ( 2) 11.3-16 (0) (2) 11.3-16a ( 2) 11.3-17 (0) (2) 11.3- 18 (0) (2) 11.3-18a ( 2) 11.3-19 (0) (2)

T11.3-1 Sh. 1 (0) (2) (4) 711.3-1 Sh. 2 (0) (2) (4)

T11.3-2 (0) (2) (4)

T11.3-3 Sh. 1 (0) ( 2)

T11.3-3 sh. 2 (0) (2)

T11.3-3 Sh. 3 (0) (2)

T11.3-4 Sh. '

(0) (2)

T11.3-4 Sh. 2 (0) (2)- (6)

T11.3-4 Sh. 3 (0) ( 2)

T11.3-4 Sh. 4 (0) (2)

T11.3-5 Sh. 1 (0) (2)

T11.3-5 Sh. 2 (0) ( 2-deleted)

T11.3-6 Sh. 1 (0) (2)

T11.3-6 sh. 2 (0) (2-deleted)

T11.3-7 sh. 1 (0) ( 2)

T11.3-7 Sh. 2 (0) (2)

T11.3-7 sh. 3 (0) ( 2)

T11.3-8 (0) (2-deleted)

T11.3-9 (0) (2)

T11.3-10 (0) ( 2)

T11.3-11 (2) (4)

T11.3-12 (2) (4)

T11.3-13 Sh. 1 (2) (4)

T11.3-13 Sh. 2 (2) (4)

T 11. 3- 14 Sh. 1 (2) (4)

T11.3-14 Sh. 2 (2) (4)

T11.3-15 Sh. 1 (2) (4)

T11.3-15 Sh. 2 (2) (4)

T11.3-16 Sh. ! (2) (4)

T11.3-16 sh. 2 (2) (4) 711.3-17 sh. 1 (2) (4)

T11.3-17 sh. 2 (2) (4)

T11.3-18 Sh. 1 (2) (4)

T11.3-18 Sh. 2 (2) (4)

T11.3-19 Sh. 1 (2) (4)

T11.3-19 Sh. 2 (2)- (4)

T11.3-20 (2)

F11.3-1 (0)

F11.3-2 (0) (2)

F11.3-3 (0) (2)

F11.3-4 (0) (2}

F11.3-5 (0) (2)

EFFECTIVE PAGE LISTING GIBBSSAR: VCLUME 4 F11.3-6 sh. 1 (0) ( 2)

F11.3-6 sh. 2 (0) (2-deleted)

F11.3-7 Sh. 1 (0) (2)

F11.3-7 Sh. 2 (0) ( 2-deleted)

F11.3-8 Sh. 1 (0) (2)

F11.3-8 Sh. 2 (0) (2-deleted)

F11.3-9 Sh. 1 (0) (2)

F11.3-9 sh. 2 (0) (2-deleted)

F11.3-10 (0) (2)

F11.3-11 (0) (2)

F11.3-12 (0) (2)

F11.3-13 (0) ( 2)

F11.3-14 (0) (2)

F11.3-15 (0) ( 2)

F11.3-16 (0) (2)

F11.3-17 (0) (2-deleted)

F11.3-18 Sh. 1 (0) ( 2)

F11.3-18 Sh. 2 (0) (2-deleted)

F11.3-19 Sh. 1 (0) (2)

F11.3-19 Sh. 2 (0) (2-deleted)

F11.3-20 Sh. 1 (0) (2)

F11.3-20 Sh. 2 (0) ( 2-deleted)

F11.3-21 Sh. 1 (0) (2-deleted)

F11.3-21 Sh. 2 (0) (2-deleted)

F11.3-22 (0) (2)

F11.3-23 (0) (2)

F11.3-24 Sh. 1 (0) (2) (6)

F11.3-24 Sh. 2 (0) ( 2) (6) 11.4-1 (0) (2) 11.4-la (2) 11.4-2 (0) (2) 11.4-2a (2) 11.4-3 (0) 11.4-4 (0) (2) 11.4-4a (2) 11.4-5 (0) (2-deleted) 11.4-6 (0) (2-deleted) 11.4-7 (0) 11.4-8 (0) 11.4-9 (0) 11.4-10 (0) 11.4-10a (2) 11.4-11 (0) (2) 11.4-12 (0) (2)

T11.4-1 (0) ( 2)

T11.4-2 Sh. 1 (0) (2)

T1.1.4-2 Sh. 2 (2) 711.4-2 Sh. 3 (2)

T11.4-2 Sh. 4 (2)

EFE2CTIVE PAGE LISTING GTEBSSAR: VOLUME 4 T11.4-2 Sh. 5 ( 2) 711.4-2 Sh. 6 (: 5 T114 4-2 Sh. 7 (2) 711.4-2 Sh. 8 ( 2) 711.4-2 Sh. 9 (2)

T11.4-2 Sh. 10 ( 2)

T11.4-2 Sh. 11 (2)

T11.4-2 Sh. 12 (2)

T11.4-2 Sh. 13 ( 2)

T11.4-2 Sh. 14 (2)

T11.4-3 Sh. 1 (0) (2)-

T11.4-3 Sh. 2 (0) ( 2-delctad)

T11.4-4 (0) (2)

T11.4-5 Sh. 1 (2)

T11.4-5 Sh. 2 (2)

T11.4-5 Sh. 3 (2)

T11.4-5 Sh. 4 ( 2)

T11.4-5 sh. 5 (2)

T11.4-5 Sh. 6 (2)

T11.4-5 Sh. 7 (2)

T11.4-5 sh. 8 (2)

T11.4-5 Sh. 9 (2)

T11.4-5 Sh. 10 (2)

F11.4-1 (0) (2) (6)

F11.4-2 (2) (2) 11.5-1 (0) (2) 11.5-1a (2) 11.5-2 (0)

1. 5-3 (0) (2) (9) 11.5-3a (9) 11.5-4 (0) (2) 11.5-5 (0) (2) (9) 11.5-Sa (9) 11.5-6 (0) 11.5-7 ( 0)-

11.5-8 (0) 11.5-9 (0) (2) 11.5-10 (0) (2)

T11.5-1 Sh. 1 (0) (8)

T11.5-1 Sh. 2 (8)

T11.5-2 Sh. 1 (0)

T11.5-2 Sh. 2 (0)

T11.5-2 Sh. 3 (0)

T11.5-3 (0)

T11.5-4 (0) 11A-1 (2) (6) 11A-2 (6) 11 A- 3 (6) 11A-4 (6)

EFFECTIVE PAGE LISTI?JG GIPPSSAR: VOLUME 4 11A-5 (6) 11A-6 (6)

T11A-1 (6)

T11A-2 Sh. 1 (6)

T11A-2 Sh. 2 (6)

T11A-3 (6)

T11A-4 (6)

T11A-5 (6) 111A-6 . (6)

T11A-7 (6)

T11A-8 Sh. 1 ( 6)

T11A-8 Sh. 2 (6)

T11A-9 (6)

T11A-10 (6) 711A- 11 (6)

T11A-12 (6) 711A-13 (6) 711A-14 (6)

T11A-15 (6)

T11A-16 (6)

T11A-17 (6)

T11A-18 (6)

T11A-19 (6)

T11A-20 (6)

T11A-21 (6)

T11A-22 (6)

T11A-23 (6)

T11A-24 (6)

T11A-25 (6)

T11A-26 (6) 711A-27 (6)

T11A-28 (6) 711A-29 (6) 711A- 30 (6)

T11A-31 (6)

T11A-32 (6)

T11A-33 (6)

T11A-34 (6)

T11A-35 (6)

T11A-36 (6)

T11A-37 (6)

T11A-38 (6)

T11A-39 (6)

T11A-40 (6)

T11A-41 (6) 11E-1 (2) (6) 711B-1 Sh. 1 (2) (4) (6)

T11B-1 Sh. 2 (2) (4) (6)

T11B-1 Sh. 3 (2) (4) (6)

FFFECTIVE PAGE LISTING GIDPSSAF: VOLUME 4 T11D-1 Uh. 4 (2) (4) (6)

T11P-1 Sh. 5 ( 2) (4) (6)

T11D-1 rh. 6 (2) (4) (6) 1110-2 (2) (6)

T11D-3 Sh. 1 ( 2) 711B-3 Eh. 2 (2) 12-i (0) (1) 12-11 (0) ( 1)12-111 (0) (1) 12-iv (0) (1) 12-v (0) (1) 12-vi (0) (1) 12.1-1 (0) (1) 12.1-2 (0) (1) 12.1-3 (0) (1) 12.1-4 (0) (1) 12.1-5 (0) 12.2-1 (0) (1) 12.2-2 (0) 12.2-3 (0) (1) 12.2-4 (0) 12.2-5 (0) 12.2-6 ( 0) (6) 12.2-7 (0) (1) 12.2-8 (0) (1) (7) 12.2-9 (0) (6) 12.3-9a (6) 12.2-10 (0) 12.2-11 (0) (1) 12.2-12 (0) 12.2-13 (0) (1) 3 12.2-14 (0) (1) 12.2-15 (0) (1)

T12.2-1 (0) (1)

T12.2-2 (0) (1)

T 12. 2- 3 (0) (1)

T12.2-4 (0)

T12.2-5 Sh. 1 (0) (1)

T12.2-5 Sh. 2 (0) (1-deleted)

T 12. 2- 5 Sh. 3 (0) (1-deleted)

T12.2-5 sh. 4 (0) (1-deleted)

T12.2-5 Sh. 5 (0) ( 1-deleted) 712.2-5 sh. 6 (0) (1-deleted)

T12.2-5 sh. 7 (0) (1-deleted)

T12.2-5 Sh. 8 (0) (1-deleted) 712.2-6 Sh. 1 (0) (1)

T12.2-6 Sh. 2 (0) (1-deleted)

T12.2-6 Sh. 3 (0) ( 1-deleted)

T12.2-6 sh. 4 (0) (1-deleted)

EFFECTIVE PAGE LISTING GIBBSUAH: VCI.UME 4 712.2-6 Sh. 5 (0) ( 1-delet ed)

T12.2-7 (0) (1)

T12.2-8 (0) 712.2-9 (0) i12.2-10 sh. 1 (0) ( 1)

T12.2-10 rh. 2 (0)

T12.2-10 Mh. 3 (0) 712.2-11 (0) 712.2-12 (0) (1)

T 12. 2-13 Sh. 1 (0)

T 12. 2- 13 Sh. 2 (0)

T12.2-13 Sh. 3 (0)

T12.2-13 Sh. 4 (0) 712.2-14 Sh. 1 (0)

T12.2-14 Sh. 2 (0)

T12.2-14 Sh. 3 (0) 112. 2-15 Sh. 1 (0)

T12.2-15 Sh. 2 (0)

T 12. 2- 16 Sh. 1 (0) (1)

T12.2-16 Sh. 2 (0) (1)

T12.2-16 sh. 3 (0) (1)

. T 12. 2- 16 Sh. 4 (0) (1)

T12.2-16 sh. 5 (0) (If 112.2-16 Sh. 6 (0) (1)

T12.2-16 Sh. 7 (0) (1)

T12.2-16 sh. 8 (0) ( ,,

T 12. 2- 16 Sh. 9 (0) (1)

T12.2-16 Sh. 10 (0) (1)

T12.2-16 Sh. 11 (0) (1)

T 12. 2- 16 Sh. 12 (0) (1)

T12.2-16 Gh. 13 (0) (1)

T12.2-16 sh. 14 (0) (1)

T 12. 2- 17 Sh. 1 (0) (1)

T12.2-17 Sh. 2 (0) (1) 12.3-1 (0) 12.3-2 (0) (1) 12.3-3 (0) ( 1) 12.3-4 (0) (1) 12.3-5 (0) 12.3-6 (0) (1) -

12.3-7 (0) (1) 12.3-8 (0) 12.3-9 (0) 12.3-10 (0) (1) 12.3-11 (0) (1) 12.3-12 (0) 12.3-13 (0) (1) 12.3-14 (0) 12.3-15 (0) (1)

EFFECTIVE PAGE LISTING GIDBSSAR: VOLUME 4 12.3-16 (0) 12.3-17 (0) 12.3-18 (0) (1) (4) 12.3.18a (9) 12.3-19 (0) ,

12.3-20 (0) (2) 12.3-21 ( 2)

T12.3-1 (0)

T12.3-2 (0)

T12.3-3 Sh. 1 (0) (1) (8)

T12.3 3 Sh. 2 (0) (1) (8 deleted)

T12.3-4 Sh. 1 (8)

T 12. 3- 4 sh. 2 (8)

T12.3-4 Sh. 3 (8)

F12.3-1 (0) (2) (6)

F12.3-2 (0) (2) (6)

F12.3-3 (0) ( 2) (6)

F12.3-4 (0) (2) (4) (6)

F12.3-5 (0) (2) (6)

F12.3-6 (0) ( 2) (6)

F12.3-7 '0) (2) (4) (6)

F12.3-8 (0) (2) (6)

F 12. 3-9 (0) ( 2)

F12.3-10 (0) (2) 12.4-1 (0) 12.4-2 (0) (1) 12.4-3 (0) (2) (6)

T12.4-1 (0)

T12.4-2 (0)

T12.4-3 (0) ( 2) 12.5-1 (0) 13-i (0) (1) 13.1-1 (0) (1) 13.2-1 (0) (1) 13.3-1 (0) (1) (8) 13.3-2 (8) 13.3-3 (8) 13.3-4 (8) 13.3-5 (8) 13.3-6 (8) 13.3-7 (8) 13.3-8 ( 8) 13.u-1 (0) (1) 13.5-1 (0) (1) 13.6-1 (0) (1) 13.6-2 (0) (1)

F13.3-1 (8)

F13.3-2 (8)

F13.3-3 ( 8)

EFFECTIVE PAGE LISTING GIEESSAF: VCLUME 4 F 13. ,3- 4 (8)

F13.3-5 (8) e

EFFECTIVE PAGE LISTING GIBPSSAR: VOLUME 5 14-i (0) ( 2) 14-ii (0) 14-iii ( 2) 14.1-1 (0) (1) (2) 14.1-2 (0) (2)

T14-1 sh. 1 (0) (1)

T 14- 1 Sh. 2 (0) (2)

T14-1 sh. 3 (0)

T14-1 sh. 4 (0)

T 14- 1 sh. 5 (0)

T 14- 1 Sh. 6 (0) (1)

T14-1 Sh. 7 (0) (1) (2)

T14-1 Sh. 7a ( 2)

T 14- 1 sh. 8 (0) (2)

T1u-1 Sh. 9 (0) ( 2) 14.2-1 (0) 14 A- 1 (2) 14 A- 2 ( 2)

F14A-1 (2) r14A-2 ( 2)

F14A-3 (2) 15-i (0) 15-ii (0) 15-iii (0) 15-iv ( 0) 15-v (0) 15-vi (0) (3) 15-vil (0) ( 3) (6) 15-viia (6) 15-viii (0) 15-ix (0) 15-x (0) (2) (6) 15-xa (6) 15-xi (0) (2) 15.1-1 (0) 15.1-2 (0) 15.1-3 (0) (2) (4) (6) 15.1-4 , (0) (1) (4) (6)

T 15.1- 1 Sh. 1 (0) (1)

T15.1-1 sh. 2 (0) (1) (4) (6)

T 15.1- 1 sh. 3 (0) (4)

F15.1-1 (0) (4)

F 15.1- 2 (0) (4)

F 15.1- 3 (0) (4) r15.1-u (0) (4) 15.2-1 (0) (1) 15.2-2 (0) (1) (2) 15.3-1 (0) 15.4-1 (0)

EFFECTIVE PAGF LISTIt1G GIBDSSAR: VOLUMF 5 15.4-2 (0) (6) 15.4-3 (0) (4) 15.4-4 (0) (6) 15.4-5 (0) (1) (4)

T15.4-1 sh. 1 (0) (1) (4)

T15.4-1 Sh. la (1)

T15.4-1 Sh. 2 (0) (1) (4)

T15.4-1 Sh. 3 (0) (4)

F15.4-1 (0) (4)

F15.4-2 (0) (4)

F15.4-3 (0) (4)

F15.4-4 (0) (4)

F15.4-5 (0) (4)

F 15. 4- 6 (0) (4)

F15.4-7 (0) (4)

F15.4-8 (0) (4) 15.5-1 (0) 15.6-1 (0) (1) 15.6-2 (0) (1) (2) 15.6-3 (0) 15.6-4 (0) (2) (4) 15.6-5 (0) (1) (4) (6) 15.6-6 (0) 15.6-7 (0) (3) 15.6-8 (0) ( 3) 15.6-8a (3) 15.6-9 (0) (3) 15.6-10 (0) 15.6-11 (0) (2) (3) (6) 15.6-11a (2) (3) 15.6-12 (0) (2) (3) 15.6-13 (0) (1) (2) (3) 15.6-13a (6) 15.6-14 (0) (1) (3) (6)

T15.6-1 sh. 1 (0) (1) (4)

T15.6-1 Sh. 2 (0) (4)

T15.6-1 sh. 3 (0)

T15.6-2 (0) (3)

T15.6-3 (0) (3-deleted)

T15.6-4 Sh. 1 (0) (3)

T15.E-n Sh. 2 (0) 715.6-4 Sh. 2a (3)

T15.6-4 Sh. 2b (3)

T15.6-5 (0)

T15.6-6 (0)

T15.6-7 (0) ( 3)

T 15. 6- 8 (6)

T15.6-9 (6)

F15.6-1 (0) (4)

EFFECTIVE PAGE LISTING GIPPSSAR: VOLUME 5

.F15.6-2 (0) (4)

F15.6-3 (0) (4)

F15.6-4 (0) (4)

F15.6-5 (0) (3) v15.6-6 (0) (3)

F15.6-7 (0) ( 3) (6)

F15.6-8 (0) (3) (6)

F15.6-9 (0) ( 3) (6)

F15.6-10 (0) (3) (6)

F15.6-11 (0) ( 3)

F15.6-12 (0) (3) (6)

F15.6-13 (0) (3) (6)

F15.6-14 (0) (3)

  1. 15.6-15 (0) (3)

F15.6-16 (0) ( 3)

F15.6-17 (0) (3) (6)

F15.6-18 (0) (3) (6)

F15.6-19 (6)

F15.6-20 (6) 15.7 -1 (0) (2) 15.7-2 (0) 15.7-3 (0) (2) 15.7-4 (0) (2) (6) 15.7-4a (2) (6) 15.7-4b (6) 15.7-4c (6) 15.7-5 (0) (6) 15.7-6 (0) (2)

T15.7-1 Sh. 1 (0)

T 15. 7- 1 Sh. 2 (0)

T15.7-2 (0) (2)

T15.7-3 Sh. 1 (0) (2)

T15.7-3 Sh. 2 (2)

T15.7-4 Sh. 1 (2)

T15.7-4 Sh. 2 (2)

T15.7-4 Sh. 3 (2)

T15.7-5 (2) (7)

F15.7-1 (0) (2) (6)

F15.7-2 (0) (2) (6)

F15.7-3 (0) (2)

F15.7-4 (0) (2)

F15.7-5 (0) (2) (6)

F15.7-6 (0) (2) (6)

F15.7-7 (0) (2)

F15.7-8 -

(0) (2)

F15.7-9 (2) (6)

F15.7-10 (2) (6) 15.8-1 (0) 15.A-1 (3)

EFFECTIVE PAGE LISTItIG GIBBSSAR: VOLUME 5 15.A-2 ( 3) 15.A-3 (3) (4) 15.A-4 (3) (4) (6) 15.A-5 (3) (6) (7)

T15.A-1 Sh. 1 (3)

T15.A-1 sh. 2 (3) i (0) (1) ii (0) (1) iii (0) (1) iv (0) (1) v (0) (1) vi (0) (1) vii-A (0) (1) viii , (0) (1) ix (0) (1) x (0) (1) xi (0) (1) xii (0) (1) xiii-A (0) (1) xiv (0) (1) ,

xv (0) (1) xvi (0) (1) xvii (0) (1) xviii (0) (1) 0-1 (0) 0-2 (0) 1-1 ( 0) 1-2 (0) 1-3 (0) 1-4 (0) 1-5 (0) 1-6 (0) 1-7 (0) 1-8 (0) 2-1 (0)

B2-1 (0) 3/4 0-1 (0) 3/4 1- 1 (0) 3/u 2-1 (0) 3/4 3-1 (0) 3/4 3-2 (0) 3/4 3-3 (0) 3/4 3-4 (T 3. 3- 6) (0) (1) 3/4 3-5 (T3. 3-6 cont) (0) (1) 3/4 3-6 (T4. 3-3) (0) 3/4 3-7 (0) (1) 3/4 3-8 (0) 3/4 3-9 (T3. 3- 7) (0) 3/4 3-10 (T4.3-4) (0)

EFFECTIVE PAGF LISTIt1G GIBBCSAR: VOLUME 5 3/4 3-11 (0) 3/4 3-12 (0) 3/4 3-13 (T3. 3-9) (0) 3/4 3- 14 (T 4. 3- 6) (0) 3/4 3-15 (0) 3/4 4-1 (0) 3/4 4-2 (0) 3/4 4-3 (0) 3/4 4-4 (0) 3/4 4-5 (0) 3/4 4-6 (0) 3/4 4-7 (0) 3/4 4-8 (0) 3/4 4-9 (0) 3/4 4-10 (0) 3/4 4-11 (0) 3/4 4-12 (T4. 4-2) (0) 3/4 4-13 (0) 3/4 4-14 (0) 3/4 4-15 (0) 3/4 4-16 ( 0) 3/4 4-17 (0) 3/4 5-1 (0) 3/4 5- 2 (0) 3/4 5-3 (0) 3/4 5-4 (0) 3/4 5-5 (0) 3/4 5-6 (0) 3/4 6-1A (0) 3/4 6-2A (0) 3/4 6-3A (0) 3/4 6- 4A (0) 3/4 6-5A (0) 3/4 6-6A (0) 3/4 6-7A (0) 3/4 6-8A (0) 1/4 6-9A (0) 3/4 6-10A ' (0) 3/4 6-11A (0) 3/4 6-12A (0) 3/4 6- 13A (0) 3/4 6-14A (0) 3/4 6- 15A (0) 3/4 6-16A (0) 3/4 6- 17A (T3. 6- 1) (0) (1) 3/4 (-18A (T3.6-1 cont) (0) (1) 3/4 6-19A (T3.6-1 con t) (0) (1) 3/4 6-20A (T3.6-1 cont) (0) (1) 3/4 6-21A (T3.6-1 cont) (0) (1)

EFFECTIVE PAGE LISTING GIFBSSAP: VOLUME 5 3/4 6-22A (T3.6-1 cont) (0) 3/4 6-23A (T3.6-1 cont) (0) 3/4 6-24A (T3.6-1 cont) (0) (1) 3/4 6-25A (T3.6-1 cont) (0) (1) 3/4 6-26A (0) 3/4 6-27A (0) 3/4 6-28A (0) 3/4 6-29A (0) 3/4 6-30A (0) 3/4 6- 1B (0) 3/4 6-1C (0) 3/4 6-1D (0) 3/4 7-1 (0) 3/4 7-2 (T3. 7- 1) (0) 3/4 7-3 (T3. 7- 2) (0) 3/4 7-4 (T4. 7- 1) (0) 3/4 7-5 (0) 3/4 7-6 (0)

  • 3/4 7-7 (0) 3/4 7-8 (0) 3/4 7-9 (T4. 7- 2) (0) 3/4 7-10 (0) 3/4 7-11 (0) 3/4 7-12 (0) 3/4 7-13 (0) 3/4 7-14 (0) 3/4 7-15 (0) 3/4 7-16 (0) 3/4 7-17 (0) 3/4 7-18 (0) 3/4 7-19 (0) 3/4 7-20 (0) 3/4 7-21 (0) 3/4 7-22 (0) 3/4 7-23 (0) 3/4 7-24 (0) 3/4 8-1 (0) 3/4 E- 2 , ._, (0) 3/4 8-3 (0) 3/4 E-4 (0) 3/4 E-5 (0) 3/4 E- 6 (0) 3/4 8-7 (0) 3/4 E-8 (0) 3/4 6-9 (0) 3/4 E-10 (0) 3/4 8-11 (0) 3/4 9-1 (0) 3/4 9-2 (0)

EFFECTIVE PAGE LISTING GIBBSSAR: VOLUME S 3/4 9-3 (0) 3/4 9-4 (0) 3/4 9-5 (0) 3/4 9-6 (0) 3/4 9-7 (0) 3/4 9-8 (0) 3/4 9-9 (0) 3/4 9-10 (0) (1) 3/4 9-11 (0) 3/4 9-12 (0) 3/4 9-13 (0) 3/4 9-14 (0) 3/4 10-1 (0)

B3/4 0-1 (0)

B3/4 0-2 (0)

B3/4 1-1 (0)

B3/4 2- 1 (0)

B3/4 3-1 (0)

B3/4 3-2 (0)

B3/4 3-3 (0)

B3/4 4- 1 (0) (1)

B3/4 4-2 (0) (1)

B3/4 4-3 (0) (1)

B3/4 5-1 (0)

B3/4 6- 1A (0)

B3/4 6-2A (0)

B3/4 6-3A (0)

B3/4 6-4A (0)

B3/4 5-1 (0)

B3/4 6-1B (0)

B3/4 6- 1C (0)

B3/4 6-1D (0)

B3/4 7-1 (0)

B3/4 7-2 (0)

B3/4 7-3 (0)

B3/4 7-4 (0)

B3/4 7-5 (0)

B3/4 8-1 (0)

B3/4 9-1 (0)

B3/4 9-2 (0)

B3/4 10-1 (0) 5-1 (0) 5-2 (0) 5-3 (0) 6-1 (0) 171 (0) 17.1-1 (0) 17.2-1 (0)

TABLE 18.0-1 NRC QUESTION STATUS Response Transmitted Ouestion Number via Amendment 005.1 6 005.2 6 005.3 6

'005.4 6 005.5 This question to be withdrawn per meeting with NRC on 11-07-78 010.1 2 010.2 2 010.3 2 010.4 2 010.5 2 010.6 2 010.7 2 010~. 8 2 010.9 2 010.10 2 010.11 2 010.12 2 010.13 6 010.13A 8 010.14 6 010.15 6 010.16 8 010.17 6 010.18 6 010.19 6 010.20 6 010.21 6 010.22 6 010.23 6 010.24 6 010.25 6 010.26 6 010.27 6 010.28 6 010.29 6 010.30 6 010.31 6 010.32 6 010.33 6 010.34 7 Amendment 9

TABLE 18.0-1 (Continued)

NRC QUESTION STATUS

~

Response Transmitted Ouestion Number via Amendment 010.35 6 010.36 6 010.37 6 010.38 6 010.39 none received 010.40 6 010.41 6 010.42 none received 010.43 6 010.44 6 010.45 6' 010.46 6 010.47 6 010.48 3 6

010.49 6 010.50 6 010.51 6 010.52 6 010.53 6 010.54 6 010.55 6 010.56 6 010.57 6 010.58 6 010.59 7 010.60 6 010.61 6 010.62 6 010.63 6 010.64 8 010.65 6 010.66 7 010.67 6 010.68 ,

6 010.69 6 010.70 6 010.71 6 010.72 6 010.73 6 010.74 6 010.75 6 010.76 none received 010.77 none received Amendment 9

'iABLE 18.0-1 (Continued)

NRC QUESTION STATUS Response Transmitted u

Qugstion Number via Amendment 010.78 through 010.103 response by 3/5/79 022.1 2 022.2 8 022.3 2 022.4 2 022.5 2, 6 022.6 6 022.7 7 022.8 6 022,9 8 022.10 6 022.11 6 022.12 6 022,13 6 022.14 6 022.15 6 022.16 6 022.17 6 022.18 6 022.19 6 022.20 6 022.21 6 022.22 6 022.23 7 032.1 2 032.2 2 032.3 2 032.4 2 032.5 2 032.6 2 032.7 2 040.1 through 040.75 response by 3/5/79 111.1 2 111.2 2 111.3 2 111.4 2 111.5 4 111.6 4 111.7 2 111.8 2 111.9 2 111.10 2 111.11 2 Amendment 9

TABLE 18.0-1 (Continued)

IGC QUESTION STATUS Response Transmitted Question u Number via Amendment 111.12 4 111.13 4 111.14 2 111.15 2 111.16 2 111.17 2 111.18 2 111.19 4 111.20 4, 7 111.21 5 111.22 2 111.23 2 111.24 2 111.25 4 111.26 9 111.27 2 111.28 2 111.29 4 111.30 4 111.31 4 111.32 4 111.33 4 111.34 4 111.35 4 111.36 4 111.37 4 111.38 4 111.39 4 111.40 7 111.41 7 111.42 7 111.43 8 111.44 7 111.45 _

7 111.46 7 111.47 7 111.48 7 111.49 7 111.50 7 111.51 7 111.52 7 111.53 7 111.54 7 Amendment 9

a 3

TABLE 18.0-1 (Continued)

NRC QUESTION STATUS Response Transmitted Question Number via Amendment 111.55 9 111.56 9 121.1 2 121,2 2 121.3 5 121.4 5 121.5 5 122,1 4 122.2 4 122.3 5 122.4 4 122.5 4 122.6 5 122.7 9 122.8 9 122.9 9 122.10 9 122.11 9 131.1 2 131.2 4 131.3 2 General Comments A 6 General Comments E 5 131.1 5 131.2 5 131.3 .s 5 131.4 5 131.5 5 131.6 5 131.7 5 131.8 5 131.9 5 131.10 6 131.11 . 6 131.12 5 131.13 5 131.14 5 131.15 5 131.16 5 131.17 5 131.18 5 131.19 5 131.20 5 Amendment 9

TABLE 18.0-1 (Continued)

NRC QUESTION STATUS Response Transmitted Ouestion Number via Amendment 131.21 5 131.22 5 131.23 5 131.24 5 131.25 5 131.26 5 131.27 5 131.28 5 131.29 5 131.30 5 131.31 5 131.32 6 131.33 5 131.34 6 131.35 5 131.36 5 131.37 7 131.38 5 131.39 5 131.40 3 5 131.41 5 131.42 5 131.43 5 131.44 5 131.45 5 131.46 5 131.47 5 131.48 5 131.49 5 131.50 5 131.51 5 131.,52 8 131.53 5 131.54 . .

5 131.55 5 131.56 8 131.5,7 8 131.58 8 131.59 8 131.60 8 131.61 8 131.62 8 131.63 8 Amendment 9

TABLE 18.0-1 (Continued)

NRC QUESTION STATUS Response Transmitted Ouestion_Nmtber via Amendment 131.64 8 131.65 8 131.66 8 131.67 8 131.68 8 131.69 8 131.70 8 131.71 8 131.72 8 131.73 8 131.74 8 131.75 8 131.76 8 212.1 4 212.2 5 212.3 5 212.4 5 212.5 4 212.6 5 212.7 5 212.8 4 212.9 4 212.10 4 and 5 212.11 5 212.12 5 212.13 4 212.14 5 212.15 4 212.16 4 and 5 212.17 4 212.18 4 212.19 5 212.20 4 212.21 4 212.22 5 212.23 5 212.24 5 212.25 5 and 7 212.26 4 212.27 4 212.28 4 212.29 7 212 30 7 Amendment 9

TABLE 18.0-1 (Continued)

NRC QUESTION STATUS Response Transmitted Question Number via Amendment 212.31 7 212.32 7 212.33 7 212.34 7 212.35 8 212.36 7 212.37 7 212.38 7 221.1 7 222.1 8 222.2 8 222.3 8 222.4 Response to be submitted upon completion of analysis by 3/5/79 222.5 8 222.6 8 311.1 2 311.2 2 311.3 2 311.4 2 311.5 2 311.6 2 311.7 2 311.8 2 311.9 3 311.10 3 311.11 2 311.1 6 311.2 7 311.3 5 311.4 5 311.5 6 311.6 - -

5 311.7 5 311.8 6 311.19 8 311.20 8 311.21 8 320.1 2 320.2 2 321.1 6 321.2 r, Amendment 9

TABLE 18.0-1 (Continued)

NRC QUESTION STATUS Response Transmitted Ouestion Number via_ Amendment t

321.3 6 321.4 6 321.5 6 321.6 6 321.7 6 321.8 6 321.9 6 321.10 6 321.11 6 321.12 6 321.13 6 321.14 6 321.15 6 321.16 8 321.17 8 321.19 8 321.19 8 321.20 8 321.21 8 321.22 8 321.23 8 321.24 8 321.25 8 331.1 2 331.2 2 331.3 2 331.4 2 331.5 2,6 331.6 2 331.7 2 331.8 6 331.9 7 331.10 6 331.11 6 331.12 6 331.13 7 371.1 2 371.2 2 421.0 2 423.1 2 423.2 2 432.0 8 Amenone-nt 9

GIBBSSAR 1

TABLE 3.2.-1 (Sheet 6 of 21)

CLASSIFICATION OF COMPONENTS, AND SYSTEMS l 5 ANSI Construction Classi- Codes and System fication Standards Components _ (Note 1) (Note 21 Piping and valves

a. Fequired for the perfor- 2 g . 2) nance of safety functions of Safety Class 2 compo-nents which are not in service during any normal node of plant operation and are not testable
b. Pequired for performance 2 g. 2) of safety functions of Safety Class 2 components
c. Pequired for performance 3 g. 3) of safety functions of Safety Class 3 components Bypass line orifice 3 g. 3)

Auxi_liary Feedwater System Auxiliary feedwater storage 3 g.3) tank Pumps (motor- cnd 3 g. 3) turbine-driven)

Piping and valves 3 g. 3)

Amendment 5

GIBBSSAR 1 TABLE 3.2.-1 (Sheet 7 of 21)

CLASSIFICATION OF COMPONENTS, AND SYSTEMS l ANSI Construction Classi- Codes and System fication Standards Components (Note 1) (Note 2) gain Steam System Piping and valves from the 2 g. 2) from the steam generator 9 nozzle up to and including the main steam stop valves safety valves up to and 2 g. 2) including the discharge nozzle flange Power-operated relief valves 2 g.2)

(valve body only)

Cutside the containment from NNS e. 3) the nain steam stop valves 5 llh to the turbine generator set l Feedwater System Piping and valves

a. From containment isclation 2 g. 2) valves to the steam generators
b. From containment isolation 3 g. 3) valves to S including feedwater control and typass valves
c. Cutside the containment NNS e. 3) from the feedwater control valves to the feedwater pumps Amendment 9 O

GIBBSSAR 1

TABLE 3.2.-1 (Sheet 8 of 21)

CLASSIFICATION OF COMPONENTS, AND SYSTEMS l ANSI Construction Classi- Codes and System fication Standards Components (Note 1) (Note 2)

Emergency Diesel Fuel Oil Storage and Transfer System Transfer pumps 3 93)

Storage tanks 3 g. 3)

Day tanks 3 g. 3)

Diesel fuel oil filter 3 g. 3)

Diesel fuel oil strainer 3 g. 3)

Piping and valves

a. Eequired for continuous 3 g. 3) functioning of diesel generators
b. Formally or automatically NNS e. 3) isolated from Safety Class.3 components containment Spray System Refueling water storage tank 2 g. 2)

Containment spray pumps 2 g. 2)

Spray additive tank 2 gO 9

Amendment 9

GIBBSSAR 1 TABLE 3.2.-1 (Sheet 9 of 21)

CLASSIFICATION OF COMPONENTS, AND SYSTEMS l 5 ANSI Construction Classi- Codes and System fication Standards Components __ ___ (Note 1) (Note 2)

Piping and valves

a. Fequired only for injection 2 g. 2) of spray additive
b. Pequired for long-term 2 g. 2) recirculation of contain-nent sump water for spray
c. Spray additive tank drains 3 g. 3) and samples (up to first valve)
d. Normally or automatically NNS e. 3) isolated from parts of the system covered in a or b Chemical eductor 2 g. 2)

Spray nozzles 2 g. 2)

Containment sump valve 2 g. 2) isolation tanks Mini recirculation pipe orifice 2 g. 2)

Fing header line orifice 2 g. 2)

Amendment 5

GIBBSSAR 1 O

TABLE 3.2.-1 (Sheet 10 of 21)

CLASSIFICATION OF COMPONENTS, AND SYSTEMS l5 ANSI Construction Classi- Codes and System fication Standards

_____ __Co_gponents _

(Note 1) (Note 2)

C9Dtainment Isolation System

a. System piping and valves of all systems penetrating containment from first isola- 2 g. 2) 9 tion barrier inside contain-nent to the first isolation tarrier outside containment, which are included as part of containment ir.olation system gemineralized and Reactor Makeup Water _ System Reactor makeup water storage NNS g. 5) tank Reactor makeup water pumps NNS g. w)

Piping and valves NNS e.3)

Amendment 9 9

GIBBSSAR 3.6 Protection _Against Dynamic Effects _ Associated hith the Postylated Ruptur2 of PipiDS This section describes design bases and measures that have been used to ensure that the containment vessel and all essentiali 1 equipment inside or outside the containment, including components of the RCPB, ESF, and safety-related conponents, have been adequately protected against the effects of blowdown jets, reactive forces, and pipe whip resulting from postulated rupture of pipi 9 The criteria for protection against pipe whip within the containment conform to NRC Regulatory Guide 1. 46. ( d) The criteria for protection against pipe break outs'.de the containment conform to the guidelines contained in Branch Technical Positions APCSB-3-1 and MEB-3-1. (3)

The protection of safety-related structures, systems, and components against postulated piping failures in high- or moderate-energy fluid systems that operate during normal and upset plant conditions is ensured by the following: l 1

a. To the extent practicable, by separation or remote (h location from pipes subject to postulated ruptures
b. Where separation is not feasible, by isolation of the pipes subject to rupture
c. Where neither separation nor isolation is practicable, by an arrangement of pipe whip restraints and jet impingement barriers 3.6.1 Postulated Piping Failures in Fluid Systems Outside of Containment 3.6.1.1 Design Bases Any fluid system or piping run within the plant that, during normal operating plant conditions, has a maximun operating temperature exceeding 200 F or a maximun operating pressure exceeding 275 psig, or both, can be subject to a postulated pipe treak.

Any fluid system or piping run with normal operating conditions of 200 F or less and 275 psig or less can be subject to pipe cracks. The internal energy of the fluid in these systems is not sufficient to cause a pipe treak.

3.6-1 Amendment 1

GIBBSSAF Ruptures or cracks within high- or moderate-energy systems are not postulated to occur within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to or following a LOCA.

The essential systems and components which are required to shutdown the reactor and mitigate the consequence of a postulated 6 pipe rupture outside containment as defined in Table 15.4-12 of FESAP 414 uill be protected following a postulated piping failure outside the containment.

a. High-Energy Fluid Systems 7 he high-energy fluid systems subject co pipe breaks outside the containment building are identified in Tabic 3.6-1.

7here are no safety-related systems, structures or components located in the turbine building. Rupture of pipes located inside the turbine building will only be considered for cases where the impact of a whipping pipe or jet impingement force could cause damage to a safety-related structure adjacent to the turbine building e.g. auxiliary building wall. In those cases, the structure will be designed to withstand the effects of a postulated pipe rupture of a high energy fluid system in the turbine building, employing the use of energy absorbing material (EAM) and/or suitable structures.

For Main Steam and Feedwater lines as shown on Figures 3.6-1a and y 3.6-1b between the containment isolation valves and containment penetrations, breaks will not be postulated when the piping meets the requirements of ETP MEE 3-1, otherwise protection is provided in accordance with Eranch Technical Position APCSB 3-1 for 9 satety-related systems, structures or components by use of barriers.

b. Moderate-Energy Fluid Systems The noderate-energy fluid systems which are considered for eventual postulated through-wall pipe cracks are described in s ubsections 3. 6.1. 2, b. and 3.6.1.2,c. l1 Moderate-energy systens which are located inside the turbine generator building are not included because there are no safety related structures, systems or conponents located inside thel 1 turbine building.

Mode rate -energy fluid systems which are located outside the containment building are identified in Table 3.6-2.

W-414 3. 6- 2 Amendment 9

GIBBSSAR accordance with Reference (2) longitudinal breaks are not required at terminal points of seamless piping, nor at intermediate locations where stresses are below 0.8 (1. 2 S +S), and a minimun number of break locations must be satisfied. For pipe runs which are partially Class 1 and partially Class 2 and both parts run between the same two terminals used as anchor points for thermal analysis the longitudinal and circumferential pipe treaks are not postulated on the Class 2 portion 4. f the stress on Class 1 portion calculated us.'g Eq. 10 per NB-3653 are above 2.4 Se and the sum of the stresses calculate using Eq. 9 and 10 per 7 NC-3652 are below 0.8 (1.2 S +S).

3. Non-Nuclear Systems Breaks in non-nuclear class piping are postulated at the following locations in each piping or branch run.

a) At terminal ends of the run t) At each intermediate pipe fittings, welded attachment, and valve.

3.6-5b Agendment 7

GIBBSSAR g

3.6.2.1.2 Postulated Break and Leakage locations of Fluid System Piping Outside Containment

.~r

a. High-Energy Fluid Systems 2 Criteria for the protection of safety-related systems, structures, and components are provided in accordance with requirerents of Branch Technical Positioti MEB 3-1. In addition to meeting the criteria of position B.1.b, all piping in the containment penetration area will have a 100 percent volumetric 9 examination of all circumferential and longitudinal welds during cach inspection interval (IWA-24 00 of Section XI of the ASME Code.)

9 2

3.6-6 Amendment 9

TABLE 3.6-1 g (Sheet 1 of h l HIGH-FNEFGY FLUID SYSTEMS LOCATED OUTSIDE THE CONTAINMENT 6 (WFSTINGHOUSE-414)

Protection of Safety Operating Conditions System Reference systems 9 Eysters critical Portion Tempe rature Pressure Infgreation 1 Note P, Ettarks l Main steam From first restraint 548 F 1035 psia GIDBSSAR 10.3 (1) C (3) system beyond t he main steam stop valve to the 6 turbine building including the steam s upp1', line to auxiliary feedwater pump turbine g

Condensate and Piping downstream of 440 F** 130u psia

  • GIDPSSAR 10.4.7 ( 1) 0 (3)
  • Pressure downstream I feedwater condensate pumps of the steam syst ems up to containment acntrator feedwater 6 isolation valves pump; **+ecoerature downstream of hich pres- l 9 sure beater No. 1 i l6 Steam Piping from 500 F 1000 psia GIEBSSAR 10.4.8 ( 2) 0 ( 1) Heat exchanger outle: 19 gene rator containment isolat ion temperature approxi-nately 135 F DCV outlet blowdown and valve to the pressure pressure 275 psin 6 cleanup system control valve downstream of the heat exchanger 9

Process Tubing from contain- 650 F 2500 psia GIEbSSAR 9.3.2 --

Primary sampling i sampling ment isolation valve lines; 3/8-inch to press'2re control tubing; no breaks valve d';wnstream are postulated sample '.*oolere Auxiliary All pi sing within the >212 F Varies (See Note 1) (1) , (2) ,6 (3) 6 steam auxili tar and safety feature > buildings Main Steam AFW pump i'rbine 548 F 1035 psia GIBBSSAR 10.3.3.@ (2) & ( 3)

System steam supply up to cortrol valve 9 Amendment 9

TABLE 3.6-1 6

(Steet 2 (f M HIGh-TNEFGY FLUID SYSTEMS LOCATED OUTSIDE THE CONTAINMEN*

(WESTI NGHOUSE-414 )

Protection of Safety Operating Conditions System Referes.ce Systems systems Critical Portion Temperature Pressure ._InigImatior. 1 Note 31 _ Eemarks l9 Cond ensate All piping within the 200-211 F Atmos-retu rn (See Note 1) (1) , (2) ,5 (3) auxiliary and safety pheric features buildings Extraction None Varies Va rie s steam GIBBSSAP 10.3 --

Entire system loca-ted inside the turbine buildino Heater drain None varies system va ries (6ee Note 2) --

Entire system located inside the turbine Auxiliary APWS divcharge line building 40-100 F Varies GIBBSSAR 10.4.9 (2) & ( 3) feedwater between pump and aesin system feedwater header 6 CVCS letdown lintc up to 383/115 F 300 psig GIBBSSAR 9.3 (1) & (3) Including loop through PCV-111 the tube side of the of the letdown reheat heat exchanger Charging line 130 F 2400 psig (1) C (3) From charging pumps to containment penetration Alternate charging 130 F 2400 psig line (1) 5 (3) via SIS system up to valves 8803 A and B Reactor coolant pump 115 F 2400 psig seal injection line (1) & (3) From charging pumps to containment penetration Note 1 The auxiliary steam system provides process steam for equipment i.e., e va pora tors.

system consists of an auxiliary boiler and a piping distribution systemthat operateswith during pressureplantcontrol shu'.oowns, valve s as required.

The condensate retu rn system is a closed system with The collecting tank inside the turbine building. Condensatethe f unction is created atoflow collecting the condensed steam and returning it points to the auxiliary steam system and at to a equipment serviced by the auxiliary stnam.

Amendment 9 e O O

GIBBSSAR 3.10 Sgisgig_Qgalifigati2D_91 Efiggig_Cagggggy_I IQELE902Ghetion_and_glegtrigal_ggginggpt 3.10.1 Seismic Qualification Criteria The major items of seismic Category I instrumentation and electrical equipment which require seismic qualification are as follows:

a. 690 0-V switchgear (nuclear safety-related)
b. 6900 to 480-V transformers (associated with nuclear-saf ety-related buses)
c. 480-V switchgear motor control centers and starters (nuclear saf ety-related) 9
d. 125-V station batteries and safety-related racks (nuclear
e. 480-Vac to 125-vde battery sa f e ty-related) chargers (nuclear t.

125-Vdc panels and switchgear (nuclear safety-related) g.

125-Vdc to 120-Vac inverters (nuclear safety-related)

n. Instrument bus panels (nuclear safety-related)
1. Cantainment penetration assemblies
j. Nan-Class IE electrical equipment and supports, unless equipped with qualified restraining devices, when located near safety related equipment, 9 to prevent them f rom damaging the safety-related equipment during an SSE.
k. Diesel generator and accessories
1. Diesel generator control panels m.

Relay boards and racks (nuclear safety-related)

n. Instruments, instrument panels and racks (nuclear saf e ty-related) 9
o. Hat shutdown panel (used if control room is evacuated) 3.10-1 Amendment 9

GIBBSSAR O

p. Wire and cable racew13- and duct banks system (nuclear sa f e ty-rela ted)
q. Electrical supports (nuclear safety-related)

O 3.10-1a Amendment 9

GIBBSSAR

r. Motors (nuclear safety-related)
s. Instruments and controls for use in seismic Category I mechanical components and systems identified in Table 3.2-1. l9
t. Main control board Seisaic Category I instrumentation and other electrical equipment, including standby power system, are designed to maintain functional integrity during SSE and postaccident operation. Seismic design of the reactor protection system and ESF circuits is discussed in Section 3.10 of the NSSS SSAR.

Horizontal and vertical ground accelerations during an SSE are used to formulate floor-response spectra at each equipment location as described in subsection 3.7.2.1,c. Where practicable, equipment is tested in the operational condition.

Operability is verified during and after testing. Deformation criteria for electrical equipment is consistent with subsection 3.7.2.1,d.

Suppliers are required to furnish documentation of actual test results or, if an analytical approach is used, detailed conputations, to substantiate equipment capability to perform its intended f unction under the specified conditions.

Seismic Category I instrumentation and electrical equipment are to be seismically qualified in accordance with the procedures and documentation requirements specified in IEEE Standard 344-1975, Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations as augmented by Regulatory Guide 1.100, Seismic Qualification of Electric Equipment for Nuclear Power Plants. Where the requirements of 2 IEEE 344 conflict with those enumerated in subsection 3.7.2.1,c.,

the requirements of subsection 3.7.2.1,c. prevail.

The requirements of 10 CFR Part 50, Appendix A, GDC 2, Design Bases for Protection Against Natural Phenomena, are met as described in subsection 3.1.2.1,b. The requirements of 10 CFR Part 50, Appendix B, Criterion III, Design Control, are met as shown in section 17.1. The extent to which the recommendations for electrical control devices in NRC Regulatory Guide 1.29, Seismic Design Classification, Revision 1, are met is shown in subsection 3.2.1.

W-414 3.10-2 Amendment 9

GIBBSSAR TABLE 6.1-6 CCNTAINMENT SPRAY SYSTEM FLOW TIMES AND SCLUTION pH (KESTINGHOUSE-414)

Solution pH Af ter_Iniection Duration of Without Chem-Containment ical Addi- With Chemical Spray Injec- tive Tank Additive Tank tion Phase Stop Valve Stop Valve

_ (min) Failure Failure Mininum spray operation and ninimum ECCS operation 81.42 8.6 8.6 l9 Mininum spray operation and naximum ECCS operation 75.78 8.6 8.6 l9 Maxinum spray operation and ninimum ECCS operation 45.69 8.6 8.6 l9 Maxinum spray operation and naximum ECCS operation 43.23 8.6 8.6 l9 Amendment 9

GIBBSSAR 6.2.2 Containment Heat Pemoval Systems A completely redundant containment spray system, designed to provide emergency containment heat removal in the event of a LCCA, is provided. This system, in conjiinction with the emergency core cooling system, removes thermal energy from the containment environment following a LOCA or a main stcar .ine break inside the containment to reduce the containment pressure and temperature. The containment ventilation system is not designed for continued operation during a design basis LCCA. The containment ventilation system is designed for normal plant operation; it is described in subsection 9.4.6. Major components of the containment spray system include the refueling water storage tank, containment spray pumps, spray headers, nozzles, and containment recirculation sumps. g By reducing the pressure differential between the containment and the environment and, therefore, reducing the driving force forl 9 leakage of fission products from the containment atmosphere, the containment sprays also help to limit of fsite radiation levels.

The containment spray system also provides an effective means of removing postaccident radiciodine from the containment atmosphere. The fission product removal function of the spray systems is described in subsection 6.5.2 6.2.2.1 Design Bases The containment heat removal systems are designed and tested in accordance with GDC 38, 39, 40, and 50 of 10CFP Part 50, Appendix A. The sources and amounts of energy that are taken 9 into consideration in sizing each heat removal system are described in subsection 6. 2.1.1.

The containment spray system can remove sufficient energy to maintain the pressure below the containnent design pressure, even in the event and either a single of a single active failure during injection phase active or passive failure during recirculation phase. The systems are supplied from separate Class 1E power buses, described in Section 8.3. No single failure can cause loss of more than half of the installed 9 200 percent-cooling capacity.

The containment spray system is designed to permit periodic determination of proper functioning to demonstrate system readiness. Routine testing is performed periodically to verify the operability of active containment spray system components.

6.2-23 Amendment 9

GIBBSSAR O

The containment spray system is seismic Category I and ANSI safety Class 2. I1 Containment spray system components are designed to remain operable in the post-DBA environment. (Qualification criteria l 9 are discussed in Section 3.11.)

The containment spray system is designed to withs'.and the dynamic ef fects associated with a pipe rupture in a high-energy system.

The containment recirculation sumps provide a source of spray wate- during the recirculation phase of the containment spray sytvem operation, The sumps are designed to promote mixing of 9 ECC and CS system fluids thus providing for sufficient heat remotal capacity to maintain containment pressure below the design value for all cases of postulated loss-of-coolant occurrences.

The containnent spray system is the only heat removal system used to cool the containment environment during postaccident conditions.

6.2.2.2 System Design The containment spray system (flow diagram on Figure 6.2-25) consists of two separate and independent 100-percent-capacity lll trains. Each train consists of one pump, spray ring headers, nozzles, valves, connecting piping, a common refueling water storage tank, and a common spray additive tank. Water from the refueling water storage tank is used for containment spray during 9 the initial phase of a LOCA. After the supply of water from the refueling water storage tank is exhausted, water is recirculated from the containnent recirculation sumps.

The containment spray system is designated as ANSI Safety Class 2 and designed as a seismic Category I syster. Component design paraneters are presented in Table 6.2-18. The codes and standards used as a basis for the design are given in Table 3.2-1. , ,

A failure analysis of all active components of the heat removal systems during the injection phase and all active and passive compcnents during the recirculation phase shows that the failure of any single component does not prevent the system from 6.2-24 Amendment 9 h

GIBBSSAR fulfilling its design function. (This analysis is summarized in Table 6.5-4.) l 1

The system design permits f unctional testing of the containment spray pumps at 100 percent flow and integrity testing of individual components. The active valves are periodically exercised to verify operability.

The following are discussed in protection system signals and setsubsection 6.5.2: 'he plant points that actuate the containment spray system; the time, following the worst possible accident, that the containment spray system is assumed to be fully operational; the delay times, following receipt of the system actuation signals, that are inherent in bringing the system into service; and the extent to which the containment spray system and system components are required to be remote manually operated from the main control room.

Tests and inspections performed on system components are discussed in subsection 6.5.2.4.

The mechanical components of the containment spray system are described in this subsection. The parts of the syetem in contact with borated water are stainless steel or an equivalent corrosion-resistant material.

a. Refueling Water Storage Tank Tnis tank is located inside the auxiliary building and functions as a source of emergency horated cooling wa ter for injection purposes. The REST is of seismic Category I construction.

tank enclosure area The is designed to seismic Category I requirements and provides missile protection for the tank.

The tank is vented to of the auxiliary building.

The tank is normally used to fill the refueling canal for re fueling opera

  • ions.

it During all other plant operating periods, is aligned to the suction of the low head (RHR) and high head safety injection pumps, and cont inment spray pump 1.

of The tank is stainle s s steel construction, with a leak detection system. 4 The is tank the has a total capacity of 570,000 gallons; 500,000 gallons total usable volume for injection. A volume of 270,000

RHR, gallons is used during the first phase of injection whenl 9 high head safety injection and containment spray pumps take.

suction from the refueling water storage tank. A volume of 4' 6.2-25 Amendment 9

GIBBSSAR O

230,000 gallons is used during the second phase of injection when 4 only the containment spray pumps take suction from the refueling water storage tank. A volume of 9

6.2-25a Amendment 9 h

GIBBSSAR 70,000 gallons is not used for injection but provides margin andl 4 outlet nozzle coverage,

b. Containment Spray Pumps The containment spray pumps are of the vertical centrif ugal type, driven by electric motors connected to separate Class 1E buses, as described in Section 8.3. Two pumps are provided (on't for each tra in) , each having 100-percent-capacity, for complete 1 redundancy. They are located on the lowest elevation cf the safety features building.
c. Deleted g
d. Spray Nozzles See subsection 6.5.2.1 for a description of the spray nozzles and the size distribution of the droplets produced. There are four ring headers per train, physically located at different elevations at the uppermost part and supported from the containment dome. In addition, there are three headers per train 4 at lower floor elevations to ensure heat removal in subccrpartments that are enclosed.

The spray water flow path is as follows: water flows from the spray nozzles; falls through the containment atmosphere; washes the containment walls; passes through the operating floor grating; and washes down the reactor vessel head, steam gene rators, reactor coolant pumps and piping, primary shield walls, floors, and drains through floor drain systems, overflows the containment sump and thereby reaches the containment 9

recirculation sump.

6.2-26 Amendment 9

GIBBSSAR O

e. Contairment Recirculation Sumps l9 The containment recirculation sumps are enclosed by a protective 7

screen, as shown on Figure 6.2-27.

Redundant sumps are provided. The clogging of one sump does not prevent the redundant system from providing the required containment spray recirculation flow. The design of the sumps isl in accordance with Regulatory Guide 1.82. . 4 The sumps are located on the lovest floor elevation in the containment, exclusive of the reactor cavity. The sump intake is protected by an outer trash rack, a coarse screen, and a fine inner screen. The sump screens are not depressed below the floor elevation.

All floor drains from the upper regions of the containment terminate in the containment sump (leak detection sump) , thereby preventing direct streams of water, which may contain entrained 7 debr is , from impinging on the recirculation sump intake filter assentlies.

The trash rack is provided to prevent large debris from reaching the inner screens. The maximum design velocity of 0.2 ft/sec at llg thc coar se screen allows debris with a specific gravity of 1.05 4 or more to settle before reaching the fine screen. The available surface area used in determining the design coolant velocity is based on one-half of the free surface of the fine screen to conservatively account for partial blockage.

The trash rack and screens are designed to withstand the vibratory motion of the SSE without loss of structural integrity.

The fine screen is 7 resh, per linear inch, 0.041-inch wire.

This 0.102 inch square clear opening gives 51 percent open area. 4 The opening in the fine screen is based on the minimum clearance between grid assemblies and fuel rods in the reactor core.

in the recirculation sump is carefully l1 The pump intake design 7 established to prevent degrading ef fects such as vortexing on the pump performance.

Inse rvice inspection requirements for the sumps will include inspection of the trash racks, screens and pump suction inlet openings during every refueling outage. The inspection will be a visual examination of these areas for evidence of structural distress or corrosion.

6.2-27 Amendment 9 Ih

GIBBSSAR The screens are constructed from stainless steel or an equivalent resistant material to avoid degradation during pe riods of inactivity and to ensure compat8bility with the recirculated coolant. The containment sump collects the mixture of containment sprey and ECCS water; it is the only source of water for the ECCS and containment spray systems during the long-term core cooling and containment atmosphere cleanup period. To ensure that air binding of the ECCS pumps does not occur during the recirculation phase of a LOCA, the piping, from the containment recirculation sump to the first containment sump isolation valve, is arranged so that as water enters the line, 7 all air in the line is vented back into the containment.

Eoth containment recirculation sumps collect postaccident water spilled on the floor and overflowed from the containment sump at elevation 90 feet, 6 inches. If one recirculation sump is not '

operating, the other handles the total flow required to fulfill the minimum ESF functions.

Each containment recirculation sump is connected through separate suction pipes to one containment spray pump and one RHR pump.

Each suction pipe is inserted into a containment sleeve and creates, in conjunction with circular seals welded to both pipes, an extended containment barrier.

Since the contain.nent recirculation sumps are entirely within the containment subject and form part of the containment structure, they are to the same initial integrated leak rate testing at design pressure as the containment. Provisions are made in the 9 containment design to permit periodic leakage rate tests as discussed in subsection 6.2.6.1,C, to verify the contir ued leaktight integrity of the containment.

During post-LOCA conditions in the containment, particulate matter such as concrete, glass, metal chips, paint, and thermal insulation could be released. Some larger particles, such as wire or structural metal could fall into the recirculated water.

Paints and thermal insulation are selected for their resistance to post-LOCA containment environment, thus reducing the amount of debris collected in the sump area. The water entering the suction pipe may contain a small amount of particlea which have a l 9 diameter of less than 1/8 inch; it cannot clog the containment spray nozzles. (The diameter of each orifice is 3/8 inch, which 6.2-28 Amendment 9

GIBBSSAR is larger than the dianeter of the holes in the last series of screens in the containnent sump.)

During the recirculation phase, the containnent spray system can acconmodate snall quantities of debris, i.e, fragments of insulating materials, paint flakes or dust which may enter the suct ion lines.

Following a pipe rupture, parts of the component insulation will becone caslodged due to pipe severance or jet intercept or both. 6 Port ions of the dislodged insult. Lion will disintegrate while the remainder will stay structurally intact.

The disintegrated insulation, whether encapsulated mass-insulation or reflective insulation, will cre ce a potential 7 for strainer or drain line clogging.

Due to the weight of the insulation panels described below, dislodged but intact panels will not te carried or moved by the low-velocity drainage flow within the containment and are therefore not considered to present any further hazards to the containrcent recirculation system.

Analysis of the potential locations of the major pipe ruptures 6 where containment recirculation is required, indicates that all such locations are remote from the containment recirculation strainers. Further, the study indicates that there is no direct access between the break locations and the strainers.

Eith this arrangement, a large portion of the disintegrated insulation will becone trapped by the barriers created by gratings, piping, structures and other components, thereby ascertaining that the anount of insulation reaching the screens will be ninimized.

The four Main Steam lines are located above the operating deck on elevation 150'-11" and 171'-11" and have as such a potential for clogging the refueling canal drain, should a pipe break occur. 7 However, a large portion of these lines are shielded by the Steam g Generator Compartments and run an opposite sides of containment.l therehy limiting the direct access to the refueling canal,l 7 Fedundant drains are installed in the refueling canal as shown in g Figure 6. 2-35.

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GIBBSSAR The feedwater lines are all routed above the operating deck at elevation 1248-6", thereby ensuring that the insulation will not 6 reach the Refueling Canal. The line routing further provides a 6.2-29a Amendment 7

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full concrete floor separation between any break in the pipe and the containment recirculation strainers.

All Feactor Coolant pipe ruptures are confined within the Steam Generator Compartments or at the Peactor Vessel nozzles.

Dislodged Reactor Vessel Insulation will be confined inside the 6 incore instrumentation tunnel with no access to the recirculation screens.

Disintegratu' insulation within the Steam Generator Compartment, from either Reactor Coolant, Feedwater or Main Steam line breaks within these compartments, will to a large extent become trapped on tne numerous components or structures located within this compartment. Insulation reaching the lower elevation of this compartment will not te carried by the low velocity water draining through the labyrinth doorways.

To ensure the above assumptions, all safety class 1 components 7 will have either reflective or encapsulated insulation.

Safety class 2 and 3 components will have either encapsulated or jacketed mass-insulation. Khere it can be determined that a potentially hazardous amount of insulation may become dislodged as a result of a pipe rupture, the applicable portion will have lll encapsulated insulation to minimize the amount of insulation which will dislodge and disintegrate at a jet impact. 6 The reflective and the encapsulated insulation will be supplied in fully enclosed sections or segments.

All insulation will te designed and installed to withstand the effects of containment spray.

f. Spray Additive Tank and Eductor Nozzles are discussed in( 9 Chapter 6.5.

The following will be discussed in the FER: the materials used 1

- the insulation; the behavior of the insulation during andl after a LOCA; the tests performed or reference test reports that determine the behavior of the insulation under simulated LOCA conditions , and the methods of attaching the insulaticn to piping and components.

6.2-29b Amendment 9 h

GIBBSSAR 6.2.2.3 Design Evaluation A discussion of the drop size spectrum (mean drop size emitted) and the pressure drop across the nozzics is given in subsection 6.5.2. A discussion of the volume of the containment covered by the sprays, the spray system flow rate, the mean spray drop size, and an analysis of the heat removal capability of the containment spray, is given in subsection 6.5.2.

The Containment Spray pumps are designed to perform at rated 7 capacity against a total head which is the sum of the containment design pressure (50 psig) , plus nozzle elevation head ( 285 feet) ,l 9 plus nozzle pressure drop (40 psi) , plus line losses and margin.

One pump is sufficient to deliver the required quantity of cooling water. 7 Sufficient NPSH is available to the containment spray pumps for toth modes of operation, injection and recirculation.

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full concrete floor separation between any break in the pipe and' the containment recirculation strainers.

All Feactor Coolant pipe ruptures are confined within the Steam Generator Compartments or at the Peactor Vessel nozzles.

Oislodged Reactor Vessel Insulation will be confined inside the 6 incore instrumentation tunnel with no access to the rceirculation screens.

C1.sintegrated insulation within the Steam Generator Compartment, frcm either Reactor Coolant, Feedwater or Main Steam line breaks within these compartments, will to a large extent become trapped on the numerous components or structures located within this compartment. Insulation reaching the lower elevation of this compartment will not te carried by the low velocity water draining through the labyrinth doorways.

To ensure the above assumptions, all safety class 1 components 7 will have either reflective or encapsulated insulation.

Safety class 2 and 3 components will have either encapsulated or jacketed mass-insulation. Khere it can be determined that a pote n tially hazardous amount of insulation may becone dislodged as a result of a pipe rupture, the applicable portion will have lll encapsulated insulation to minimize the amount of insulation which will disludge and disintegrate at a jet impact.

6 The reflective and the encapsulated insulation will be supplied in fully enclosed sections or segments.

All insulation will te designed and installed to withstand the ef fe cts of containment spray.

f. Spray Additive Tank and Eductor Nozzles are discussed inl 9 Chapter 6.5.

The following will be discussed _in_the FER: the materials used for the insulation; the behavior of the insulation during andl after a LOCA; the tests performed or reference test reports that determine the behavior of the insulation under simulated LOCA conditions; and the methods of attaching the insulaticn to piping and components.

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GIBBSSAR

a. General Leakage-Rate Tests Containment leakage testing is in accordance with all the requircaents of 10 CFR Part 50, Appendix J, Primary Reactor Con *Linment Leakage Testing for Water-Cooled Power Reactors.

After the Containment is pressurized and the Containment airl 9 conditions are stabilized the following parameters are and recorded periodically for the duration of the test. measured

1. Containment absolute pressure 6
2. Containnent dry bulb temperature 3 Containment wet bulb temperature 4.

Keather conditions outside of containment.

b. Preoperational Leakage-Rate Tests After conpletion of containment construction and installation of all nechanical, fluid, electrical, and instrumentation systems penetrating the containrent pressure boundary, preoperational integrated leakage rate Type A tests, using tect a reduced pressure progran, are conducted in accordance with 10 CFR Part 50, Appendix J. Tests are performed at the calcula ted peak contair ment internal pressure and at a reduced pressure (for calculated peak containment internal pre ssure, see subs ect ion 6. 2.1) .

l6

c. Periodic Leakage-Rate Tests Periodic leakage-rate tests, Type A (at a reduced pressure of half of the calculated peak 'ontainment internal pressure), are 6 performed in accordance wAch the requirements Appendix J, including the retest schedules.

of 10 CFP Part 50,

d. Acceptance Criteria The naximum allowable leakage rate (La, as defined in 10 CFRl 1 Part 50, Appendix J) in a 24-hour period, - when related to the naxinum containment leakage under DBA conditions, is 0. 20 percent of the weight of contained air at the calculated peak containment internal pressure.

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The acceptatce criteria for all the leak tests are in accordance with 10 CFR Part 50, Appendix J.

9 The initial reduced pressure Type A integrated leak rate (Ltm) does not exceed 75 percent of the allowable reduced pressure leakage rate (Lt as defined in 10 CFR Part 50, Appendix J) .

O 6.2-47a Anendment 9

GIBBSSAR The periodic Type A reduced pressure integrated leak rate (Ltm) does not exceed 75 percent of Lt, as calculated in 10 CFR rart 50, Appendix J.

e. Containment Inspection A detailed visual inspection of the accessible interior and exterior surf aces of the containment structure is performed prior to any Type A integrated leakage-rate test L; uncover any evidence of structural deterioration which may affect either the containment structural inteority or leaktightness. The discovery of any significa.it deterioration prompts corrective actions in accordance with acceptable procedures. Inspection procedures are in accordance with 10 CFR Part 50, Appendix J.
f. Reports Test reports are prepared and submitted in accordance with the requirements of 10 CFR Part 50, Appendix J.
g. Corrective Action
1) If, at any time, it is determined that the acceptance criteria limits are exceeded, repairs will be initiated immediately.
2) Pepairs are made in accordance with the applicable codes stated in subsections 3.8.1 and 3.8.2. After the repairs have been completed, another test is performed.

Reactor operation is permitted after a successful retest which demonstrates conformance with the acceptance criteria.

The containment isolation system is designed to minimize the leakage of radioactive materials through fluid lines penetrating the containment, in the event of LOCA or main steam line rupture, to a rate low enough to ensure that offsite dosage is below thel limits specified in 10 CFR Part 100. 1 NFC GDC 52, 53, 54, 55, 56, and 57 are followed with respect to containment leakage rate testing.

isolation valves will be accomplished by normal Closure of containment operation.

However, systems that are required to maintain the plant in a safe shutdown condition during the test will be operable in their 9 normal mode, and will not be vented. Systems that are normally water filled and operating under post-accident conditions will not te vented.

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The status of each valved fluid line penetration during the l 9 containment integrated leakage-rate Type A test is shown in Table 6.2-23.

6.2.6.2 Containment Penetration Leakage Rate Test Containment penetration leakage testing is in accordance with the requirements of 10 CFR Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Kater-Cooled Power Peactors.

Test methods are in accordance with ANSI N45.4, Leakage-Rate Testing of Containment Structures for Nuclear Peactors, to the extent referenced in 10 CFR Part 50, Appendix J.

The leakage-rate tests, Type B, perforned on the various types of penetrations are described as follows:

1. The equipment hatch, personnel airlock, emergency airlock, and fuel transfer tube are provided with covers sealed by double gaskets arranged so that the space between the gaskets can be pressurized. See Figure 3.8-7. The seal is tested by either pressurized air or nitrogen at Pa and reasuring the rate of pressure loss or by pressurizing with a halogenated test gas to Pa and testing for leakage with a halide leak detector. The halide leak detection nethod is not used on stainless steel components.

g

2. The fuel transfer tube penetration consists of a sleeve 6

embedded in the Containment wall and welded to the liner through which the transfer tube passes. The sleeve is sealed to the transfer tute by two tellows expansion joints, one on each side of the penetration. See PESAP Figure 9.1-1 Fuel Transfer System and Figure 3.8-7.

A test connection is provided so that the space between the transfer tube and the sleeve with connecting bellows can be pressurized to Pa. Leakage of the bellows or attachment welds is _tected by measuring the rate of pressure loss.

3. 7he Containment recirculatidn 'tump penetrations consist of sleeves embedded in the Containment mat with the process pipe seal welded to the sleeve by a seal ring inside the Containment. The sleeve is welded to the Containment liner.

Each valve isolation tank is sealed to the process pipe downstream of the isolation valve by bellows expansion joint (see Figure 6.2.27) . All manways and flanges on the valve isolation tanks are provided with double o-ring seals to rermit leakage testing by pressurizing the space between the 6.2-49 Amendment 9 llk

GIBBSSAR TABLE 6.2-18 (Sheet 1 ef 3)

CONTAINMENT SPRAY SYSTEM COMPCNENT DESIGN PARAMETEBS CSEDSD2DL C9DtalDESDt_SFR y_ Pumps Quantity two Type vertical centrifugal Design flow rate, gpm 4,500 19 Cesign TDH, ft 600 Cesign pressure, psig 350 Design temperature, F 300 Pofueling Water _ Storage Tank Cuantity one Capacity, gal 570,000 l4 Design pressure, feet Atmospheric Design temperature, F 200 Amendnent 9

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TABLE 6.2-18 (Sheet 2 of 3)

CONTAINMENT SPRAY SYSTEM COMPCNENT DESIGN PARAMETEFS Chemical _ Eductor Cuantity two Motive side fluid torated water concentration, ppm of boron 2000 Design pressure, psig 325 Design temperature, F 300 Total flow, gpm 225 l9 0

Amendment 9 h

GIBBSSAR TABLE 6.2-18 (Sheet 3 of 3)

CONTAINMENT SPRAY SYSTEM COMPCNENT DESIGN PARAMETEFS Suction side fluid sodiun hydroxide solution Ccncentration 30 percent (by weight)

Design pressure, psig Hydraulic Head Design temperature, F Ambient Tctal flow, gpm 85 l9 EELGY_ Add tive_TaDh Quantity one Capacity, gal 7,000 l9 Concentration contents sodium nydroxide 30 percent (by weight)

Cenign pressure, psig 20 Derign temperature, F 150 ContginmeDt_ Scrav__ Nozzle Quantity per train 476 Flow per nozzle at 40 psi, gpm 15.2 Type Spraco 1713A or equivalent spray nozzle with the same drop size distribution. 2 Amendment 9

GIBBSSAR 6.5.1.4 Tests and Inspection Inspection and testing of the ESF atmosphere cleanup units are consistent with the inspection and test requirenents for the non-ESF unita. These requirements are described in subsection 9.4.1.4. The criteria for keeping occupational radiation exposures as low as reasonably achievable during replacement of filters and adsorbers is described in subsection 12.3.3,5. Equipment a re both factory and inplace tested as per Regulatory Guide 1.52 positions C.3 and C.S. The maintenance procedures are in accordance with position C.4.

6.5.1.5 Instrumentation Fequirements Each ESF atmosphere cleanup unit is provided with instrumentation in accordance with position C.2.G of NRC Regulatory Guide 1.52.

A pressure indicator connected across the filter train is provided to monitor the overall resistance of each cleanup unit.l4 Abno rmal differential pressure will alarm in the control room to alert the operator. Local pressure indicators are provided to monitor the resistance of each individual filter bank. High differential pressure will indicate clogged or dirty filters.

Each adsorber bed has a temperature-monitoring system. The system indicates bed temperature and actuates a high-temperature alarn in the control room in accordance with the temperatures listed in Table 6.5-1. The actions that are subsequently taken are also described in this table.

Flow elements are provided to measure the flow through each cleanup unit. Flow indicators are provided for local indication.

A pressure differential switch is located across each fan with a control room alarm for abnormal conditions. All fans are started manually, with automatic start of the standby fan.

4 Design details and the system logic are described in subsections 7.3.1 and 7.6.1.

1 6.5-3 Amendment 4

GIBBSSAF 6.5.1.6 Materials Each ESF filter housing is of all-steel construction and welded; also trazed or bolted, or a combination of both, in accordance with the design requirements of CRNL-NS1C-65. Specific information relating to commercial name, quantity, and chemical composition of the materials used is provided in the Utility-Applicants SAD. HEPA filters and prefilters are fabricated of glass fiter; adsorbers are fabricated of activated charcoal. Ductwork will be of sheet metal (galvanized steel) construction. Redundant ESF atmosphere cleanup units are provided for the systems outlined in subsection 6.5.1.1 ar d are physically separated to ensure that any radiolytic or pyrolytic deconposition of the materials used in or on a particular filter system does not interfere with the safe operation of that system or any ot her ESF ayaten.

6.5.2 Containment Spray System The containment spray system has, in addition to its heat removal 1 capabilities, the ability to scrub fission product from the post accident atmosphere of containment and to minimize the release of radioactive iodine to the environment. This section describes the iodine removal capability of the containment spray system and the analysis of the radiological consequences of the LOCA is lll given in Subsection 15.6.5.3.

6.5.2.1 Design Bases Following a loss of coolant accident, the release of radioactive iodine isctope (Cee Table 6.5-2) from the reactor con ainment will present a hazardous condition which will be alleviated by the containment spray system and will reduce the offsite doses well below the limits of 10 CFR Part 100. The sodium hydroxide solution is added to the borated spray water via a spray additive subsystem. Component sizing, layout, and the spray solution chemistry will be gcverned by the f ollowing principal criteria:

~

a. Nolumetric containment coverage, with one out of two redundant spray trains in operation, must be maximum.
b. The spray fall height above the operating floor used in the analysis was conservatively taken as the difference in elevaticn between the lowest ring header of the containment 9 dome and the operation floor. This distance is 140 feet.

1 6.5-4 Amendment 9

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c. The spray system will deliver the design flow rate of 1 4500 GPM, to one train of spray nozzles, despite a single 9 failure in the containment spray system.

1

d. The system will be capable of permanent removal of iodine from the containment atmosphere by absorption into the spray droplets and retention in the containment recirculation sump. l9
e. Components of the containment spray system as well as the spray additive subsystem will be designed to meet safety Class 2 and seismic Category I requirements.

6.5.2.2 System Design (for Fission Product Pemoval) t One of the containment spray system functions is fission product iodine removal from the containment atmosphere during the initial mode (injection phase) of system operation. This phase is initiated automatically by a containment pressure HI-3 signal, by manual action or by safety injection signal coincident with a HI containment temperat +e signal. Generation of the HI-3 signal is described in subsection 7.3.1.1.a. These signals will automatically open the discharge valves to the spray headers 9 which can also be opened manually from *ue control room. Prior to the containment spray actuation signal, the containment spray pumps will have received a signal to start from the safety injection "S" signal.

At this time each containment spray pump draws water from the Refueling Water Storage Tank. The quantity of water in the EWST is sufficient enough to provide water to both the containment spray system and emergency core cooling sy stem. Simultaneously with the start of the injection phase the valves of the spray cdditive tank discharge open to allow the flow of NaOH, which is drawn from the tank and is introduced by eductors into i containment spray pump suction pipe.

The spray additive tank outlet valves are closed during normal operation to prevent mixing of the NaOH with boric acid in the RWST. The REST is adequately vented to permit rapid drawdown.

Nitrogen gas cover inside the spray additive tank is provided by the nitrogen supply to ensure an adequate pressure inside the tank. Approximately 5 percent of each containment spray pump flow is branched through the pump bypass eductors, to draw sodium hydroxide from the spray additive tank and this flow is returned back to the pump suction line.

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A 30 pcreent by weight :olution of sodium hydroxide flow will bei l calibrated at 85 gpm per eductor to maintain the alkalinity ofl 9 the spray solution at the design pH range of 9.3-10.0. This l1 9

6.5-Sa Amendment 9

GIBBSSAR alkalinity will be maintained in this range during the entire injection phase.

The containment spray additive subsystem is composed of one spray additive tank, two chemical eductors, connecting piping, valves, and related instrumentation. The containment spray system is capable of delivering spray water to the containment atmosphere in sufficient quantity and with an optimum average droplet diameter to ensure adequate iodine removal from the contalnment atmosphere. The spray system is comprised of two independent trains each containing one spray pump, piping, spray headers, valving, spray nozzles and associated instrumentation. There are four ring headers per train, physically located at different elevations at the uppermost part and supported from the containment dome, and three auxiliary headers located at lower elevations to maximize sprayed volume coverage. All containment sp ay headers are equipped with- nozzles each spraying hoilzontally, vertically downward, upward at 45 degrees and 1 downward at 45 degrees. This arrangement provides a maximum volune spray coverage even if one of the containment spray trains fails to operate. The number of spray nozzles is based cn sprayed volumes required for each containment region and their respective flow rates as listed in Table 6.5-3. The nozzles are of a hollow type with 3/8 inch diameter orifice and designed to operate at a pressure drop of 40 psi. These nozzles produce droplets with a mean diameter less than 1000 microns at 40 psi differential pressure.

The nozzle spacing and orientation provides t ximum coverage of containment volume. The physical arrangement is shown in Figure 6. 5- 2. The histogram of the observed dropsize frequency is based on tests performed by Spray Engineering laboratory of the Spray Engineering Company's spray Company'sl nozzle type 1713a as shown in Figure 6.5-3. 19 In case of a LOCA and loss of offsite power, the maximum time to close containment spray pump breakers, including 10 seconds for a 1 diesel generator to come up to speed and voltage, will be 20 seconds after the safety injection signal actuation. The safety injection signal is actuated within the first second following the accident. The containment analysis will use value of 51.3 seconds for delivery through all spray nozzlesthe of at least the one train at rated flow due to the delay outlined below, 9 after double-ended reactor coolant pump suction pipe guillotine break and loss of offsite power.

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This delay includes:

a. Within the first second after the break, the safety' injection, "S" signal, is actuated.
b. Seven seconds after the break, the "P" signal is activated at 20 psig containment pressure.
c. Eleven seconds after the break, the opening of the containment spray pump isolation valves is initiated.
d. Twenty-one seconds after the break the containment spray 9 pump will be started, and the containment spray pump isolation valves will be fully open.
e. Twenty-six seconds after the break, the containment spray pump will be at full speed.

Between the 26th and 51st second, water will fill the CS piping and full flow or ':he f urthermost nozzle uill he achieved.

Duration of the injection phase of the containment spray flow depends on the total flow drawn from the RWSI at the flow rates required of the ECCS and containment spray system. This duration i.e.,

{lg is given in Table 6.1-6 for all modes of operation, combinations of maximum or minimum ECCS operation with one or two train containment spray system operation.

The suction of the containment spray pump will be automatically 1 switched to the recirculation sumps when the REST supply is nearly exhausted, that is, when its contents are reduced to 70,000 gallons. The automatic recirculation signal, described in subsection 7.3.1.1.b, will start the recirculation phase of the containment spray system, opening the motor operated valves in the suction lines from the containment recirculation sumps, where the injection water, reactor coolant and accumulator spillage 9 have collected. Af ter the ~ start of the recirculation phase, the motor operated valves from the REST will be automatically closed, isolating the RWST from the containment spray pumps. Water from the sumps will then be sprayed into the containment. The sumps are designed to promote continuous mixing of ECC and CS systems water, thus providing sufficient heat removal capacity to maintain containment pressure below the design value for all cases of postulated loss-of-coolant occurrences. Failure to switch a spray train at the RWST low level will be automatically detected by the low-low RWST water level which will be annunciated in the control room. At this time the control room 6.5-7 Amendment 9 llh

GIBBSSAR operator will manually switch the affected containment spray train to start the recirculation phase. This phase of operation will continue as long as necessary to ensure containment 9 depressurization.

6.5-7a Amendment 9

GIBBSSAR The regions of the containment covered by the spray and their respective volumes are listed in Table 6.5-3. These sprayed volumes are based on the free volume of each region from which the equipment and wall volumes are subtracted. Figure 6.5-3 is a 1

schematic of the containment that shows the locations of the spray nozzles, and spray regions, labeled A,B,C,D. The containment spray characteristics of each region inside the containment are described in Table 6.5-3.

The regions A,B,C,D consist of the following:

1) Region A The volume of 2,771,998 ft3 directly covered by spray l9 includes the volumes: 14

- above operating floor

- above refueling cavity

- refueling cavity 1

- pressurizer compartment

- reactor vessel head storage area steam generators compartments

2) Region B The volume of 93,945 ft3 covered by spray represents 4 45 percent of the total free volume between:

1

- floor between elevations 1718-11" and 150'-11" 1

3) Region C The volume of 37,000 ft3 covered by spray represents 4 16 percent of the total free volume between:

- floors el. 150'-11" and 124'-6" 1

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4) Region D The volume of 60,800 ft3 covered by spray represents' 24 percent of the total free volume between: 4

- floor elevations 124'-6" and 90'-6"

5) The volume not covered by spray includes the following:

1

- cavity beneath reactor vessel

- elevator

- reactor coolant drain collection tank, p umps, 4 and heat exchanger rooms

- incore instrumentation room 1

6. 5. 2. 3 Design Evaluation The containnent spray additive subsystem uses state-of-the-art technology for absorbing radioactive iodine from the containment l4 atmosphere. A favorable alkalinity level is established by the addition of sodium hydroxide solution to the spray water. The alkalinity increases the solubility of iodine so that the rate of 1 iodine absorption is limited mainly by the mass transfer rate through the gas film surrounding the spray water droplets.

Furthermore, the alakalinity level is such that it prevents the.

dissolved iodine from escaping from the containment recirculation 9 sump water.

Radiciodine, in its various forms, is the fission product of primary concern in the evaluation of a LOCA. The major benefit of the containment spray is its capacity to absorb elemental iodine from the containment atmosphere. To enhance iodine-absorption capacity of the spray, the spray solutionthe is adjusted to an alkaline pH which promotes iodine hydrolysis to 1 nonvolatile forms.

According to the known behavior of elemental iodine in highly dilute solutions, the hydrolysis reaction I + CH' "HIO + I~

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is nearly completed at ph>8. The iodine form is highly soluble, and HIO readily undergoes additional reactions to form iodate.

The overall reaction is 3I + 3H O , '5HI + HIO 2 2 3 1

The basic criteria used for design of the spray additive subsystem are explained as follows:

a. Alkalinity level of the spray solution during the injection phase is pH=10.5 for all modes of operation (fully ef fective spray and minimum safeguard operation) .
b. Volume of NaOH drawn from the spray additive tank during the injection phase is such that the final sump alkalinity is pH=8.6 (fully ef fective spray and minimum ECCS operation) .

The containment sump solution pH for each operational mode is given in Table 6.1-6, taking into consideration a single failure analysis. The single failure analysis for the spray additive subsystem is shown in Table 6.5-4.

O To determine the containment recirculation sump solution pH, all sources of borated water such as the RCS accumulators, the boron injection, the refueling water storage tank, and the weight of NaOH which would be lost in the containment " dead" volumes are taken into consideration. The " dead" volumes consist of the reactor cavity up to RCS piping, cc4ntainment (leak detection) sumps and areas below the recirculation sump as incore instrumentation and RC drain tank rooms. Significant quantities 9 of spray and injection water will not be trapped in SG subcompartments because vent paths allow for drainage. Escape of the post-LOCA water from the containment sunp into a low activity waste collection tank will be precluded by drain isolation valves and by deenergizina the sump pumps after the accident.

The mixing of the containment spray solution with the spilled water is considered complete in the containment sumps. Material compatibility is discussed in subsection 6.5.2.6.

6.5-10 Amendment 9

GIBBSSAR The analytical method used for determining the effectiveness of the sprays is taken from WASH-1329, "A Feview of Mathematical Models For Predicting Spray Removal of Fission Products in Peactor Containment Vessels"(1) as recommended in SRP 6.5.2. The assumptions used are explained below:

1) The removal mechanisms are assumed to be first order and independent of time and iodine concentration. SRP 6.5.2. 4 III.4.b states that iodine removal is to be assumed to be first order. To be independent of iodine concentration, the physical properties such as density, viscosity, and diffusivity as well as the partition factor, H, must be independent of iodine concentration. At low iodine concentrations, the physical properties are known to be independent of iodine concentration, however H is not (1).

6.5-10a Amendment 9

GIBBSSAR 4

6.5.2.4 Tests and Inspections The containment spray system will be designed to permit periodic testing to demonstrate system performance readiness. Each component of the system shall be subjected to preoperational, and operational testing andtoinspections as described in the following paragraphs. In addition routine inspection, periodic visual inspections will be 1 performed to check for corrosion and surface cracks in welds.

a. Preoperational Inspection and Testing Containment spray components will be inspected and tested in accordance with applicable codes as described in Section 3.2.

The environmental conditions for qualification tests are shown in Tables 3.17-1 and 3.11-4 and Figures 3.11-1 and 3.11-2. g The containment spray pumps will after installation to ensure be tested after fabrication and full operability and required performance. The performance curves and NPSH requirements will be supplied by shop tests to confirm pump design characteristics. After installation the pumps will be tested using refueling water by recirculating back to the RWST. This test will also check and verify the operability of the recirculation flow control valves. 1 The spray additive be eductors will tested and calibrated after fabrication addi tive for their solution.

performance using fluid comparable to the spray After installation, the spray additive system will be tested using refueling water as the test fluid. For evaluation of test data results, a correlation factor of 1.34 will be used (ratio of specific gravity of the NaCH solution to borated water) .

To verify maximum droplet mean diameter for spray nozzles, performance data will be provided after the manufacturer's shoptest.

6.5-17 Amendment 9

GIBBSSAR g

The spray nozzles will not be tested "in situ" with water. However, a containment spray system full flow ring header test was performed at Zion Nuclear Power Plants - Units 1 and 2 (Docket Numbers 50-295 and 50-304) . This test demonstrated that flow passing through the system was as designed, that there was no discernable movement in the ring headers when subjected to spray flow forces, and tha t the containment coverage was as predicted. After the spray headers are installed, air under pressure will be passed through test connections in order to check that the spray nozzles and ring headers are free of obstructions and are not clogged.

1

b. Operational Testing Poutine testing will be perforned periodically to verify the operability of active containment spray system components.
1) The spray additive system will be tested using refueling water as a test fluid. The test line from the RWS1 to the spray additive discharge line, upstream of the spray additive flow measuring element will be opened, along with the full flow test line from the discharge of the containment spray pumps which is recirculated back to the RWST. For evaluation of test data, the correlation factor is 1.34 (ratio of specific gravity of the NaOH solution and lh borated water).
2) Sequencing of valves and pumps will be tested by shutting the manual valve on the containment spray line inside the containment and the manual valve on the chemical l9 additive supply line and triggering a simulated actuation.

signal. All automatic valves and the pumps will be checked for proper sequencing.

3) Each pump will be run at full flow with the flow directed back to the RWST.
4) Spray nozzles will be tested by compressed air using test connections in the containment spray lines to check the spray nozzles for flow. Operators will confirm that all nozzles are free of costructions.
5) The RWST water is sampled periodically to monitor water chemistry. Provisions are made so that the water can be purified by circulating it through the purification loop of the spent fuel pool cooling and rurification system.

6.5-18 Amendnent 9

GIBBSSAR

6) To maintain an adequate supply and proper concentration 1 of NaOH in the spray additive tank, both the fluid level and the NaOH concentration will be checked usually once a month and once a year, respectively.
7) Means will be provided for intermittent detection of a RWST and CSS particulate material which could plug the spray ~

nozzles. The testing will be performed periodically using the test line returning water to the RWST. The discharge into the tank will be divided into two fractions, one for the major portion of the flow and the other to pass a quantity of water through test nozzles, identical withsmall the containment spray nozzles. This assures that there is no 9 particulate material in the RWST and CSS.

The flow rate through the test nozzles will be monitored and compared to the previously nozzles.

established flow rate obtained with open 6.5.2.5 Instrumentation Requirements 1

a. Containment pressure transmitters and temperature sensors are used for automatic actuation of the containment spray system (refer to Chapter 7) . Unless manually stopped, the system will operate indefinitely. 9 The actuation of system components is described in subsection 7.3.1.1,b and shown in the logic diagrams (Figure 7. 3-1) .
b. Four REST level channels will be provided and used for ECCS and containment spray system operation (refer to Chapter 7 of 6 RESAR-414) .

Two water level indicator channels will be provided for each containment sump. Both will be indicated in the control room to inform the control room operator on the water level stability in the containment sump during the recirculation phase.

1 Redundant level transmitters are provided for the spray additive tank with a low-level alarm and indication in the control room. The low level alarm will inform the operator to check the tank isolation valves and to inspect the system for leaktightness.

c. The containment spray pump discharge pressures will be indicated and recorded in the control room.

6.5-19 Amendment 9

GIBBSSAR O

A pressure indicator is provided at the eductor suction.

Instrumentation is provided to maintain and indicate the desired nitrogen blanket pressure in the spray additive tank.

d. Temperature of the REST will be indicated in the control 1
room,
e. A flow instrumentation monitor is located on the spray additive line upstream cf the eductor, with indication in the control room.

O 6.5-19a Artendment 9 h

GIBBSSAR TABLE 6.5-3 CONTAINMENT SPRAY CHARACTERISTICS 6

Unsprayed Paraceters Sprayed Peqions Recion Total A B C D E Total Volume-ft3 2,771,998 208,766 231,300 253,339 61,449 3,526,852l9 Sprayed 6 Containment 2,771,998 93,945 37,000 60,800 0 2,463,74319 Volume-ft3 Unsprayed Containment 0 114,821 194,300 192,539 61,449 563,109 6 volume-ft3 Spray Drops 140 17 23 28 -

19 Fall Height

-ft Spray System 6 Flow Pate-gpm 3,200 650 230 420 -

4,500 l9 Number of Nozzles per 338 68 23 47 -

476 Train ,

6 Amendment 9

GIBBSSAR g

TABLE 6.5-4 (Sheet 1 of 2)

SINGLE FAILUPE ANALYSIS-CCNTAINMENT SFBAY SYSTEM Component Malf unction Comment and Consequences

1. Containment Fail to start, One 100% pump per train Spray Pumps Pump - Pump casing provided. Operation of one rupture train required.
2. deleted [8
3. Spray Nozzles Clogged Adequate number of nozzles per train ensures effective spray coverage of the containment.
4. Auto Con- Fails to open Two valves provided.

tainment Operation of one is re-Spray Pump quired.

Discharge Valve g

opened on 2/4 HI-3 signal

5. Containment Fails to open One valve per train provided.

Spray Pump Operation of one train is Suction required.

Isolation valve

6. Recirculation Clogged one Sump per train provided. l 8 Sump Isolation One train has to remain Valve operable.
7. Containment Ruptures Two redundant trains are Spray Piping provided for full heat removal.
8. Valve on Fails to open Redundant valve will open Spray additive Tank Outlet Amendment 9

GIBBSSAR TABLE 6.5-4 (Sheet 2 of 2)

SINGLE FAILURE ANALYSIS-CONTAINMENT SPRAY SYSTEM Component Malfunction Comment and Consequences

9. Automatic One train fails There are redundant outputs electric and to operate from the Protection cabinets instrumenta- to each train. One train has tion trains to remain operable.

to actuate ESF equip-ment

10. Recirculation Fails to open Two valves provided.

sump i solation Operation of cae is valve required.

GIBBSSAR h

TABLE 6.5-5 CONTAINMENT SPRAY SYSTEM MATERIALS Component Ouantity Material 4

Spray Additive 1 SA-240 Type 304 Tank Becirculation Sump 2 ASTM A-580, Type 304 l4 Screen l4 Spray Pump Casing 2 SA-351 CF8M TP l9 Shaft SA-182 Gr. 316 4 Impeller SA-351 CF8M Chemical Eductor 2 SA-182 Gr. 304 9 Valves 2 1/2" and larger 31 SA-351 CF8 4 Valves 2" and smaller 60 SA-182 Type 316 Piping -

SA-312 Type TP 304 or O

SA-358 Class 1 9

Fefueling Water 1 SA-240 Type 304L Storage Tank Containment Spray Nozzles Austenitic Stainless Steel Stop Valves (Spray 4 SA-351 CF8 4 Additive Tank Discharge)

Valve Isolation Tank 2 SA-516 Gr. 70 9

All materials conform to ASME Section ITT Code Class 2 and are subject to manufacturers standards.

Amendment 9 h

GIBBSSAR TABLE 6.5-6 PRIMARY CONTAINNENT OPERATION FOLLOWING A DESIGN BASIS ACCIDEN1 General Type of Structure -

Beinforced Concrete Internal Fission Product Pemoval System -

Containment Spray System Primary Containment Free 4 volume (fts) -

3,526,852 l9 Time Dependent Parameters Conservative 4 Leak Rate of Primary Containment (% per day) 0.10 Leakage Fractions To Volume Outside the Containment (%) 100 l4 Effectiveness of Fission Product Removal Systems: Spray (iodine removal coefficient)

Elemental 33.5 hr-1*

4 Particulate 1.30 hr-1

  • For added conservatism 10 hr-1 is used in all accident analyses Amendment 9

GIBBSSAP O

TABLE 6.5-7 IODINE SPRAY REMOVAL CCEFFICIENT (hr-1) 6 Elemental Removal Coefficient Temperature (C) Begiga A B C D 100 30.2 169 161 177 110 29.7 169 161 177 9

120 28.8 168 160 175 130 27.8 167 159 173 140 26.6 165 157 170 Particulate Removal Coefficient h leggerature (C) RegioD 6 A B C D 100 2.37 2.10 2.53 3.26 110 2.27 2.09 2.52 3.23 9

120 2.15 2.09 2.57 3.21 130 2.01 2.08 2.50 3.18 140 1.80 2.07 2.48 3.14 Amendment 9

GIBBSSAR

7. INSTRUMENTATION AND CCNTROLS TABLES 7.1- 1 Applicable Standards & Codes for ISC Systems l9
7. 5- 1 Main Control Board Post Accident Monitoring 6 Indications 7-111 Amendment 9

GIBBSSAP h

7. INSTRUMENTATION AND CONTROLS FIGURES 7.3-1 Instrumentation and Control System Logic Diagrams
7. 3- 1 Sh. A Instrument Identifications
7. 3- 1 Sh . B Valve Identifications
7. 3- 1 Sh. C Logic Symbols 7.3-1 Sh. D Logic Symbols
7. 3- 1 Sh. 1 S.W. Pump Control Logic
7. 3- 1 Sh . 1A S.W. Non-Essential Loop Isolation Valves Control Logic
7. 3- 1 Sh. 1B S.W. System Instrument Diagram
7. 3- 1 Sh. 1C S.W. System Instrument Diagram gg 7.3- 1 Sh. 1D S.W. System Instrument Diagram
7. 3- 1 Sh. 2 C.C.W. Pump Control Logic
7. 3- 1 Sh. 2A C.C.W. System Instrument Diagram
7. 3- 1 Sh . 2B C.C.W. System Instrument Diagram
7. 3- 1 Sh. 2C C.C.W. System Instrument Diagram
7. 3- 1 Sh. 2D C.C.W. System Instrument Dicgram
7. 3- 1 Sh. 2E C.C.W. System Instrument Diagram 7.3- 1 Sh. 2F C.C.W. System Instrument Diagram 7.3-1 Sh. 2G C.C.W. System Instrument Diagram
7. 3- 1 Sh. 3 Unassigned 7.3-1 Sh. 4 Containment Spray System Pump Logic 7-iv Amendment 9

GIBBSSAR

7. 3- 1 Sh. 4A Containment Spray System Chemical Additive outlet valves Control Logic 7.3-1 Sh. 4B Containment Spray System Containment Sump Recire. Isolation Valves Control Logic 7.3-1 Sn. 4C Containment Spray System Containnent Spray Pumps Suction Valves Control Logic 7.3-1 Sh. 4D Containment Spray System Spray Header Discharge valves control Logic
7. 3- 1 Sh. 4E Containment Spray System Instrument Diagram 7.3-1 Sh. 4F Containment Spray System Instrument Diagram
7. 3- 1 Sh. 4G Containment Spray System Instrument Diagram 7.3-1 Sh. 5 Control Room HVAC Fan #9 Control Logic 7.3-1 Sh. 5A 9 Control Room HVAC Damper #1 Control Logic 7.3-1 Sh. SB Control Room HVAC Damper #11 Control Logic
7. 3- 1 Sh. SC Control Room HVAC Damper #29 Control Logic
7. 3- 1 Sh. SD Control Room HVAC A/C Unit Control Logic 7.3-1 Sh. SE Control Room HVAC Damper #21 Control Logic
7. 3- 1 Sh. SF Control Room HVAC Emergency Filter Unit Control Logic 7.3-1 Sh. SG Control Room HVAC Damper #27 Control Logic
7. 3- 1 Sh. 5H Control Room EVAC Emergency Pressurization Unit Control Logic 7.3-1 sh. 5J Control Room HVAC Emergency Pressurization Unit Inlet Damper 85 Control Logic
7. 3- 1 Sh. SK Control Room HVAC Emergency Filtration Unit Bypass Damper #7 Control Logic
7. 3- 1 Sh. 6 Control Room HVAC Normal Mode Instrument Diagram 7-iva Amendment 9

GIBBSSAR 7.3-1 Sh. 7 Control Poom HVAC Emergency Pecirculation Instrument Diagram

7. 3- 1 Sh. 8 Control Room HVAC Emergency Ventilation Mode Instrument Diaaram 7.3-1 Sh. 9 Control Foom HVAC Emergency Pressurization Mode Instrument Diagram
7. 3- 1 Sh. 9A Control Poom HVAC Emergency Pressurization Mode Instrument Diagram
7. 3- 1 Sh . 10 Auxiliary Feedwater System Motor Driven Pump Control Logic
7. 3- 1 Sh. 10A Auxiliary Feedwater System Turbine Driven Pump Steam Inlet Valve Control Logic
7. 3- 1 Sh. 10E Auxiliary Feedwater System Instrument Diaoram 9
7. 3- 1 Sh. 10C Auxiliary Feedwater System Instrument Diagram 7.3-1 Sh. 11 Safety Features Chilled Water Syster Pump Logic Diagram 7.3-1 Sh. 11A Safety Features Chilled Water System Instrument Diagram
7. 3- 1 Sh. 12 Main Steam Isolation Baypass Valve Control Logic
7. 3- 1 Sh. 13 Main Steam Isolation Valve Control Logic
7. 3- 1 Sh. 13A Auxiliary Feedwater Turbine Driven Pump Steam Header Supply Valve
7. 3- 1 Sh. 14 Feedwater Isolation Valve Control Logic 7.3 1 Sh. 15 Feedwater Bypass Control Valve Control Logic
7. 3- 1 Sh. 16 Containment Isolation System Valve Control Loaic
7. 3- 1 sh . 16A Containment Isolation System Valve Control logic 7-ivb Amendment 9

GIBBSSAR

7. 3- 1 Sh. 16B containment Isolation System Valve Control Logic
7. 3- 1 Sh. 16C Containment Isolation System Valve Control Logic 9
7. 3- 1 Sh. 16D Containment Isolation System Valve Control Logic 7.3-2 Location of Reactor Protection and Engineered Safety Features Instruments 7.7- 1 Main Control Board Functional layout 7.7-2 Main Control Board Cross Section l2 l

7-ive Amendment 9

GIBBSSAR 3

d. Component Cooling Water System This system is similar to the one used on CPSES Units 1 and 2. 1 The differences are as follows:
1) CPSES Units 1 and 2 provide two 100-percent-capacity pumps for each unit. Some of the primary plant cooling is provided by the CCWS and the rest is by the service water system.
2) The GIBBSSAR plant provides four 100-percent-capacity pumps and all the primary plant cooling is done by the CCWS, except for the emergency diesel generators and the CVCS chiller unit, which are cooled by the service water system. At plantsites with poor water quality, all cooling is done by the CCWS.

(See section 9.2.)

e. Service Water System j 3 This system is similar to the service water system in CPSES Units 1 and 2. CPSES Units 1 and 2 provide two 100 percent-capacity pumps for each unit which take their suction from the safe snutdown impoundment (SSI). GIBBSSAR provides four 100 percent-capacity pumps for this system. Equipment is designed and built to the specifications of GSH.
f. Standby Power Supply System l 3

This system is similar to CPSES Units 1 and 2. Equipment is designed and built to the specifications of GSH.

g. Control Poom Air-Conditioning Unit l 3

This system is similar to the CPSES Units 1 and 2 control system.

The system is designed and built to the specifications of GSH.

7.1-3 Amendment 3

GI"PSSAR h

3

h. Auxiliary Feedwater System l This system is similar to CPSES Units 1 and 2. Equipment isl 9 designed and built to the specifications of GSH. All of the creviously mentioned systems are described in subsection 7.3.1.1.

The follcwing safety-related systems are described in Section 9.4 and are in GSH's range of responsibility.

3

1. Uncontrolled Access Area Ventilation l This sys tem, used in CPSES Units 1 and 2, is not safety-related.

The cooling of the equipment is perforned by the use of safety-related auxiliary cooling units. In GIPBSSAR, the system is safety-related and provides ventilation to the safety-related switchgear rooms, battery rooms, inverters, and electrical penetration areas containing safety-related equipme nt. The system contains two 50-percent-capacity f ans for each separate fans emergency safeguard electrical bus. The system is designed and built to the specifications of GSH.

i. Controlled Access Area Ventilation l 3 This system is similar to the system used in CPSES Units 1 and 2l 9 for the auxiliary building, safeguards building, and llh fuel-handling ventilation systems.
k. Diesel Generator Ventilation i 3 This system is the same as CPSFS Units 1 and 2. The system is designed by, and built to the specifications of GSH.

7.1.2 Identification of Safety Criteria 7.1.2.1 The following design bases, criteria, Pegulatory Guides, and standards are implemented in the de sign of the systems listed in subsection 7.1.1, and are presented as 1 supplementary information to subsection 7.1.2 of the NSSS SSAP. The degree of. cQmpliance with each of these safety criteria is as outlined below.

7.1- 4 Amendment 9

GIBBSSAR

a. NPC Pequlatory Guide __1.11, "IDatrument Lines P_enetrgging Primary _ Reactor _Qgntaingent" The only instrument lines that penetrate the Primary Peactor Containment are for the reactor containment pressure transmitters, and these are designed in strict conformance with 9 subsection 6.2.4.1. l The following paragraph numbers correspond to like numbered paragraphs in Pegulatory Guide 1.11, and are presented to indicate the degree of compliance to this criteria.

c.1a There are four separate and independent pressure sensing lines, each of which can be tested individually.

C.1b Sensing lines are 0.25" O.D., 316 SS with 304 SS flexarmor and are leaktight, hence, no makeup or offsite doaes are expected.

C.1c The reactor containment pressure sensing lines do not have isolation valves. Isolation is provided by means of double sealed bellows 1 connected to a fluid-filled tube, thus protecting (in the case of line break inside or outside of containment) against leakage of the containment atmospnere.

C.1d Instrument lines are conservatively designed and of a quality at least equivalent to the containment and subject to strict quality control and regular inspections to assure integrity. Instrument lines will be located and protected so as to minimize the possibility of their being damaged accidentally and also to permit periodic visual inservice inspection, particularly outside containment. They will be protected or separated to prevent failure of one line from inducing failure of any other line.

7.1-5 Amendment 9

GIBBSSAR h

Co le As per response in C.1c, the arrangenent will not restrict an adequate response time of the connected instrumentation to an unacceptable degree.

C.2 The reactor containment pressure sensino lines are the only instrument lines penetrating reactor containment.

h. NEC_ Regulatory Guide _1.22,_" Periodic Testino of Protection System Actuation Functions" The plant protection system is supplied by the USSS vendor, which supplies outputs to actuate BOP safety-related equipment. The NSSS vendor periodically tests the plant protection system, and supplies output contacts to test the EOP actuated equipment devices.

The testing of the BOB ESF systems is in compliance with the requirements of NPC Pequlatory Guide 1.22.

The method of compliance utilized for the various y ESF and ESF supporting systems is discussed in subsection 7.3.2

c. NPC Pegulatory Guide 1.29 " Seismic Design classification" The following paragraph numbers correspond to like rumbered paragraphs in Pegulatory Guide 1.29, and are presented to indicate the degree of compliance to this criteria. Additional information concerning seismic criteria can be found in Chapter 3.

C.1 The instrumentation and control functions of each of the systems listed in subsection 7.1.1,. . including their f oundations and supports, and the structures in which they are located arn classified as seismic Category I and are designed to withstand the effects of the SSE and remain functional.

C.2 The non-safety-related, systems or components whose failure would unacceptably reduce the 7.1-6 Amendment 1

GIBBSSAR The redundancy requirement for the isolation of the lines penetrating the containment is satisfied by having two isolation valves in series. In this case, the power 6 supply for the valves comes from separate and independent buses, i.e. , one valve is powered from the Train A bus, and the other valve is powered from the Train B Bus.

4) Control Room Indication Each remotely operated containment isolation valve is provided with limit switches to give control room indication of valve status,
b. Containment spray Systen The containment spray system is outlined in detail in subsection 6.5.2. 1 Il Actuation of System Components The containment spray system consists of two separate and independent full-capacity safety-related loops, each 6 Cdpable of fulfilling the design requirements. The system is initiated automatically by a HI-3 signal by manual action or by safety injection signal coincident with a Hi containment temperature signal. Generation of 9 this HI-3 signal is described in subsection 7.3.1.1,a.

Manual initiation of containment spray is accomplished by actuating either of two sets of switches (two switches per set.) Both switches in a set must be actuated to obtain a manually initiated spray signal.

The sets are wired to meet separation and single-failure requirements of IEEE 279. Simultaneous operation of two switches is desirab1<. to prevent inadvertent spray actuation.

Prior to the containment spray actuation signal, the containment spray pumps have been started by safety injection signal S.

9 Receipt of the HI-3 or safety injectio3. signal concident with a Hi containment temperature signal initiates the following automatic action: the opening of the spray header discharge valves; and the opening of the chemical additive tank stop valves. -

W-414 7.3-3 Amendment 9

GIBBSSAR O

The changeover from the injection mode to the recirculation mode of operation for the c ontainment spray system is automatically initiated on a O

K-414 7.3-3a Amendment 9 h

GIBBSSAR two-out-of-four refueling water storage tank low-low level in conjunction with a HI-3 containment pressure signal or safety injection signal containment Hi temperature signal. coincident with al 9 The complete descripticn of the two out of four protection channel logic for the automatic changeover to recirculation mode is provided in RESAR 414 6 Section 6.3.2.2.

This automatic initiation of the containment spray recirculation mode results in the following actions:

a) Opening the containment spray sump recirculation valves b) Closing the containment spray pump suction valves from the RWST The system changeover may also be manually initiated from the control room.

The containment sump isolation valves are interlocked to prevent their being opened by operator action from the main 6 contro! board unless the corresponding RWST isolation valves are closed.

2) Control of System O*;;ation The containment spray system is desisned with on-off controls. Once the system is actuated, the pumps operate with constant flow.

9

3) Monitoring of System Operation The containment spray system is provided with control y room display instrumentation as described in Table 7.5-1. In addition, RWST level is indicated and alarmed in the control room as provided in Table 7.5-1 of RESSAR 414. Local indication is provided for chemical additive tank level and pressure, chemical 6 additive flow and pres sure, containment spray pump W-414 7.3-4 Amendment 9

GIBBSSAP h

discharge pressure and recirculation to the PKST flow. 6 Additional centrol room alarms are provided for refueling water storage tank low temperature and chemical additive tank high/ low pressure.

Each power-operated valve is provided with position indicating lights in the control roca.

O 7.3-4a Amendment 6

GIBBSSAR The following automatic operation occurs upon initiation of an S signal (Figure 7. 2-1 of RESAF-414 shows the logic for initiation of safeguards actuation signals) .

The two CCWS pumps in auto starts unless already running, the pumps selected for etandby operation by the pump control switch do not start.

The following automatic operations occur upon initiation y of a containment isolation phase B signal:

a) The valves on the interconnecting head 6r between the two safety-related loops close.

b) The non-safety-related loop isolation valves close.

c) The CCWS containment isolation valves close.

The two safety-related loops can be manually ieolated from each other at any time from the control room. The RHR heat exchanger discharge valves open automatically on initiation of the containment spray recirculation phase.

The reactor coolant pumps thermal barrier discharge header is provided with an excess flow check valve inside the containment to limit in-leakage of reactor coolant in the event of a thernal barrier rupture.-

The CCWS header to the ventilation chillers is provided with a high-flow monitor tv isolate the chillers in the event of a break in the non-nuclear-safety-related piping.

The CCWS surge tank vent valve closes automatically on a high-radiation signal from any one of the loops.

2) Control of System Operation The CCWS is designed to operate without throttling valves.

The CCWS surge tank level is used to detect system leakage. The control system for each half of the partitioned tank consists of the following:

a) Level indication local and control room W-414 7.3-9 Amendment 1

CIS3SSAR g

b) Level recordino c) Hioh-hign/ low-low alarms d) Automatic makeup from the demineralized water storage tank on low level Automatic makeup termination en high-level 6 e) f) Manual makeup from the Fire Protection System l 9

3) Monitoring of System Operation 3

The CCNS is provided with safety-related control room display instruttentation as described in Table 7.5-1. In addition, each heat exchanger outside containment is supplied with local tempcrature indication. Sufficient local flow indication is providcd to allow tiow balancing of the system. Each flow indicator has a low-flow alarm contact to alert the operator to a system malfunction. Flow indication and alarm is provided in the control room fcr containment spray and PHP heat 3 exchangers. In addition tr.e CCWF return line temperat ure from each PLP lube oil cooler is indicated lh and alarmed in the main control roon.

Fach power-operated valve is supplied with a control switch and indicating lights in the control room.

Fadiation monitors are provided with readout in the control room for each of the two system loops.

4) Secuencing Upon loss of offsite power, one pump from each train is automatically loaded onto the emergency diesel generators according to the sequence shown in Table 8.3-1.
5) Fedundancy separr.te switches and actuation circuitry is provided for redundant components which are physically and electrically separated from one another.

W-414 7.3-10 Amendment 9

GIBBSSAP

3) Monitoring of System Operation The auxiliary feedwater system is provided with display instrumentation, both in the control room and on the hot i shutdown panel es follows:

a) Steam generator level b) Auxiliary feedwater flow to each steam generator c) Pump flow for each auxiliary feedwater pump d) Pump discharge pressure for each auxiliary feedwater pump e) Pump suction pressure for each auxiliary feedwater pump f) Auxiliary feedwater storage tank level

4) Sequencing Upon loss of offsite power, each motor-driven pump is automatically loaded onto its repsective emergency diesel generators according to the sequence shown in subsectin 8.3-1.
5) Pedundancy separate switches and actuation circuitry are provided for redundaia components which are physically and electrically separated from one another.
7. 3.1. 2 Design Basis Information Preliminary logic and instrument diagrams are Figure 7.3-1. shown on i Figure 7.3-2 shows the location of the ESF instruments.

l9 The followine bases are established as specified in IEEE 279-1971:

W-414 7.3-17 Amendment 9

GIBPSSAP

a. Basis 1 The generating station conditions which require protective action are oiven in RESAR-414, subsection 7.3.1.2.
b. Pasis 2 The generating station variables that are required for monitorina in order to provide protective action are given in RFSAF-414, subsection 7.3.1.2.
c. Basis 3 No spatially dependent variables are used for engineered safety 1

feat ures actuation.

d. Bases 4, S, and 6 The normal operating limits, pretrip alarm setpoints, and alarm sets are designed so that they perform in an adverse e nvironment during normal, abnormal, and accident circumstances.
e. Bases 0 and 9 An actuation analysis is provided in P ES AP -414, 9

subsection 7.3.1.2, under the same headinos, 7.3.1.3 Final System Drawings Final system drawinos will be provided at the FDP.

2 K-414 7.3-18 Amendment 2

GIBBSSAR 9.2 Wgter Systeme This section provides a discussion of the following auxiliary water systens associated with the plant:

a. Service Water System (subsection 9.2.1)
b. Component Cooling Water System (subsection 9.2. 2)
c. Demineralized Hakeup Water (subsection 9. 2. 3)
d. Condensate Storage Facilities (subsection 9. 2. 6)
e. Plant Ventilation Chilled Water System (subsection
9. 2. 8)
f. Ventilation Safety Features Chilled Water System (subsection 9.2.9)

The Potable and Sanitary Water System (subsection 9. 2.4) , the Ultimate Heat Sink (subsection 9.2. 5) , and the Water Treatment System (subsection 9.2.7) will be described in the Utility-Applicant's SAR.

9.2.1 Station Service Water System 9.2.1.1 Design Bases The service water system removes heat from the ccmponent coolia water heat exchangers and, depending on the quality of site water available, certain other plant components. The service water system also acts as an alternate safety class water source to the auxiliary feedwater system, which is described in subsection 10.4.9. and an alternate NNS Seismic Category I water source to the fire protection system. The service water system supplies cooling water to meet the cooling requirements listed in 9 Table 9.2-1 and Table 9.2-2 during normal operation, shutdown, and during and after a postulated.. accident or loss of offsite power.

The choice of the service water system (once-through or closed cycle) is a function of the available ultimate heat sink (subsection 9.2.5) which is site-related, and will be presented in the Utility-Applicant's SAR. Freeze icing and other adverse environmental conditions protection which is site-related, will 6 be presented in the Utility-Applicant 8s SAP. See Table 9.2-5.

For the purpose of this document, however, it is assumed that an 9.2-1 Amendment 9

GIBBSSAR O

ultinate heat sink is available and meets the interface reouirements described in this Section. The service water ir t erfaces with the ultimate heat sink at the service water pump 6 in '.e t and at the service water discharge tunnel.

O 9.2-la Amendment 6 h

GIBBSSAF The service water syr,tt m is designed to accommoda te a range of inlet water design temperatures, i.e., 85 F, 95 F, and 100 F.

The service water design flow rate is established for the most stringent operating conditions. The component cooling water heat exchangers are resized to maintain the same heat exchange capacity over the whole temperature range with a constant service water ficw rate. The service water system design parameters presented in Table 9.2-3 are based on the. previously mentioned criteria and on cooling the component cooling water heat exchangers and emergency diesel generators,which are required to operate af ter a LOCA, and the nonessential CVCS chiller package.

However, for those sites where water quality is unacceptable, the service water system cools only the component cooling water heat exchangers. Service water system design parameters presented in Table 9.2-3 will be ammended to reflect the different flow conditions.

The service water system functions during normal operation and during and after a postulated accident or loss of offsite power.l9 Equipnent required for safe shutdown is included on two identical redundant loops, the essential cooling loops. Flow in each essential loop is supplied by pumps powered from the emergency buse s. Separate and independent emergency diesel generators supply power in the event of loss of primary and alternate offsite power. The onsite emergency power system is described in Section 8.3. The two essential loops are physically separated from each other and can be automatically or manually isolated.

The CVCS chiller unit is cooled on a nonessential loop, which can be automatically or manually isolated from the two essential loops.

The two essential service water loops are designated Safety Class 3 and in accordance with the ASME ESPV Code, The system is Seismic Category I and is protected Section III.

against the effects of a tornado.

9.2.1.2 System Description The service water system is shcwn in Figure 9.2-1, and consists of two separate and independent, full-capacity essential loops and one nonessential loop. Each of the essential loops is equipped with two 100 percent-capacity service water pumps which feed one component cooling water heat exchanger and one emergency diesel generator. The nonessential loop, which contains the CVCS chiller unit, can be supplied by the pumps of either essential loop supply to the fire protection system is provided 9 from the discharge of each loop to the ultimate heat sink.

9.2-2 Amendment 9

GIBBSSAR O

Under normal operation, a single service water pump supplying water to a component cooling water heat exchanger, emergency l 9 diesel generator of the same essential icop, and to the CVCS chiller unit cn the nonessential loop is adequate for normal plant operation. Should the operating service water pump trip, the second service water pump in the operating essential loop autonatically starts. In the unlikely event of a fault occurring in the operating essential loop, instrunentation logic is provided to automatically transfer operation to the other 9 essential loop. If system operation is transferred from one essential loop to the other, feed to the nonessential loop is realigned to the operating essential loop. In the event that one service water pump is taken out of service for naintenance, the second f ull-capacity punp in the name essential loop is available for service.

For normal cooldown, the service water system uses two service water pumps (one from each essential loop) to supply both compcnent cocling water heat exchangers, energency diesel generators, and the CVCS chiller unit. A slower but acceptable cooldown rate may also be accomplished with only one service water pump supplying water to one component cooling water heat exchanger, an energency diesel generator, and to the CVCS chiller unit. g Under accident conditions on receipt of an S signal, a pung in the second essential locp is started so that cooling water is supplied to both component cooling water heat exchangers and both energency diesel generators. Upon receipt of the containment isolation signal, Phase B, the nonessential loop is automatically isolated from the essential loops. Although only one essential loop is required to mitigate the consequence of an accident, ccoling water continues to be supplied to both essential loops.

A single failure of any component does not prevent the service water system from supplying water to one essential loop, as described in Table 9.2-4.

Chemical addition to the service water to protect system compcnents against corrosion depends on the water qua lity, the components to be cooled, and the nature of the service water system cycle. Corrosion protection of the service water systen is site-related and will be discussed in the Utility-Applicant's SAR. The effects of water level, sedinentation, and other environmental related effects are site-related and will also be discussed in the Utility-Applicant's SAP.

9.2-3 Amendment 9 lh

GIBBSSAR Flow indication is provided downstream of each of the components cooled by the service water system to detect abnormalities in the system flow rates. Abnormal flow conditions are annunciated in the control room. The detection of leakage through the component cooling water heat exchangers to the CCES is discussed in subsection 9.2.2.2. Although no radiation contamination of the service water system is anticipated, a radiation monitoring system is provided to ensure that any contamination will be detected.

9.2.1.3 Safety Evaluation The service water system is made up of two full-capacity essential loops and one nonessential loop. During emergency operation, the nonessential loop is automatically isolated from the essential loops. The two essential loops are separated each other by two remotely operated valves in series. from The essential loops are redundant in that the component cooling water heat exchanger and emergency diesel generator supplied with cooling water by one loop are sufficient to perform the minimum required safeguard function. Failure of the nonessential cooling loop has no adverse affect on the capability to safely shutdown the plant or to maintain the plant in a safe shutdown condition.

The performance of all components is monitored from the control room. Low flow, low pressure, high temperature, and high radiation level, all of which are indicative of system malfunction, are annunciated in the control room. Radioactive contamination of the service water system is not expected; however, a radiation monitoring system is provided to ensure that any contamination is detected. The radiation monitoring system is described in Section 11.5 The essential Seismic Category I service water loops of the system are designated ano _afety Class 3. The essential plant components cooled by the service water system are located in separate areas of the ESF area, which is inside the seismic Category I auxiliary building. At the interface between the service water system and the ultimate heat sink, the service water pumps are protected by a semisic Category I structure designed to withstand the possible effects of flooding. This building is site-related and will be describedand tornadoes in the Utility-Applicant's SAR. The piping from the service pump discharge is buried underground. water The piping and all supports are designed to Seismic Category I requirements. The amount of earth cover is sufficient to protect the piping from tornado generated missiles. These conditions together with the

9. 2- 4

GIBPSSAR classificaticn of the service water system as Seismic Category I ensure that the systen is capable of withet anding adverse environmental occurrences such as postulated earthquakes, tornadoes, and tornado-generated missiles. The non -

essential loop is classified NNS and is Seismic Category I.

The physical separation of the two essential loops precludes coincident dairage to redundant equipment in the event of a post ulated pipe rupture, equipment failure, or missile generation. Protection against dynamic effects associated with the postulated rupture of piping are discussed in Section 3.6.

9.2.1.4 Tests and Inspections Components in operation will te alternated periodically to enable testing and inspection. The standby components will he inspected g to find and correct incipient malfunctions. Sufficient instrumentation is provided to monitor system performance.

The service water components are positioned to allow access for g periodic examinations as required by the ASME ESPV Code.

9.2.1.5 Instrumentation A detailed descripticia of the instrumentation provided for the 9

service water system is included in subsection 7.3.1.

9 . 2.1. 6 Interface Requirements for the service water system are described in Table 9.2-5 9.2.2 Component Cooling Kater System 9.2.2.1 Cesign Bases The component cooling water sys ten. provides an intermediate barrier between those radioactive or potentially radioactive system couponents requiring cooling and the service water system.

The CCWS, a closed-loop system, is designed to perform the follcwing functions: to remove residual heat from the RCS via the FHR syctem during plant cooldown; to cool the letdown flow to the CVCS during normal operation; to cool ESF heat loads after an accident; and to dissipate heat rejected f rom various plant l 9 components in a manner that precludes direct leakage of radioactive fluids to the ultimate heat sink. The heat loads and 9.2-5 Amendment 9 lh

GIBBSSAR lll flow rates required to perform these various functions are listed in Tables 9.2-6 and 9.2-7.

The CCWS is designed to accommodate a range of inlet service water design temperature, i.e., 85 F, 95 F, and 100 F. The CCWS flow rates are established by the cooling requirements of plant compcnents under various operating modes. The CCHS heat exchangers are resized for each service water design temperature to maintain the same heat exchange capacity with a constant service water flow rate (subsection 9. 2.1) . The CCWS provides cooling water in sufficient quantity and within the temperature limits of 105 F during nornal plant operation and 120 F during reactor cooldown or after a postulated LOCA. With this design, three CCHS heat exchanger sizes, which become progressively smaller as the inlet service water decign temperature is reduced, are used. The largest heat exchanger design is used for the purpcse of space allocation within the ESF area. The CCHS design paraneters presented in Table 9.2-8 are based on the forementioned criteria and on cooling the various plant components listed in subsection 9.2.2.2.

The CCWS is required to function during normal operation and during and after a postulated LOCA. Equipment required for safe shutdown is included on two identical redundant loops, the essential cooling loops. Flow in each essential loop is supplied by ptmps powered from the emergency buses. Separate and independent emergency diesel generators supply power in the event of loss of primary and alternate offsite power. The onsite emergency power system is described in Section 8.3. The remaining plant components are cooled on a nonessential loop.

The two essential loops are physically separated from each other and can te automatically or manually isolated.

The CCWS is maintained at a higher pressure than the service water system to prevent leakage of the untreated service water which may contain impurities. This protects certain plant components cooled by the CCHS against possible chloride-induced stress corrosion.

The two essential loops of the system are designated safety Class 3 and in accordance with the ASME ESPV Code,Section III. All non-nuclear safety-related portions of the loop can te remotely isolated from the control room. The safety Class 3 portien of the loop is seismic Category I and protected 9 against the effects of tornado. The nonessential loop is classified NNS and is Seismic Category I.

9.2-6 Anendment 9

GIBBSSAF O

9.2.2.2 Systen Description The two essential loops of the CCES are shown on Figure 9.2-2; the portion of the nonessential loop outside of the containment is shown on Figure 9.2-3; the portion inside containment is shown on Figure 9.2-4.

The CCES consists of two separate and independent, full-capacity essential loops and one nonessential loop. Each of the ersential loops is equipped with two 100-percent capacity CCES pumps and one CCWS heat exchanger. The nonessential loop may to supplied by the pumps and heat exchanger of either essential loop.

All the components required to he cooled following a LOCA are included in each of the essential loops. The following is a comprehensive list of the components included on each loop:

a. CCW pump cooler i4
t. PHP heat exchanger
c. Containment spray pump cooler
d. FHF/ low-head safety injection (LHSI) pump ccoler 9 lll
e. Auxiliary feedwater pump ccoler
f. Centrifugal charging pump cooler
g. Safeguard chilled water system
h. Spent fuel pool heat exchanger The above components, except the spent tuel pool heat exchanger, are required to operate following a LCCA. The spent fuel heat exchangers are isolated after a LCCA on a phase E containment isolation signal, but they are included in the essential loops so that they may receive cooling water. ten hours later to prevent toiling of the spent fuel pool. The above is a complete list for 9 those sites with acceptable quality water available for use in the service water system. On sites with unsuitable quality water, the energency diesel generators will be cooled by the essential loops of the CCES and the size of the CCW heat exchangers will te increased accordingly. The essential loops are redundant in that the 9.2-7 Amendment 9 h

GIBBSSAR conponents supplied with cooling water by one loop are sufficient to perform the required safeguard functions. They are separated from each other by at least two valves at any interconnection.

'The remaining components requiring cooling water are included on the nonessential loop. Components cooled by the nonessential loop external to the containment are as follows:

a. Health physicist office and service area air conditioning 4
b. Instrument and service air aftercooler and compressor
c. Process sample heat exchangers
d. Becycle evaporator package
e. High activity waste evaporator package
f. Low activity waste evaporator package
g. Seal water heat exchanger 4
h. Letdown heat exchanger
1. Catalytic recombiners l9
j. Waste gas compressor package 4
k. Plant ventilation chillers
1. ETRS sample cooler 9
m. GFFC sample cooler The above is a list of components to be cooled for those sites with acceptable quality water available for use in the service 2

water system. On sites with unsuitable quality water, the CVCS chiller unit is cooled by the nonessential loop of the CCWS.

Compenents cooled by the nonessential loop in the ccntainment are as follows:

a. Reactor coolant pumps
b. Excess letdown heat exchanger
c. Reactor coolant drain collection tank heat exchanger .

1 9.2-8 Amendment 9

GIEBSSAR

d. Peactor coolant pump motor air coolers l4 0

9.2-8a Amendment 9

GIBBSSAR Under normal operation, a single CCES pump and single CCWS heat exchanger of the same essential loop are adequate for normal plant operation. If the operating CCWS pump trips, the second CCWS pump in the operating essential loop automatically starts. 9 In the unlikely event of a fault occuring in the operating essential loop instrumentation, logic is provided toi automatically transfer operation to a punp and heat exchanger of the other essential loop. If one CChs pump is taken out of service for naintenance, the second full-capacity pump in the same essential loop is available for service. Cooling water is normally supplied through the operating heat exchanger to both essential loops and to the nonessential loop; however, only one spent fuel pool heat exchanger is required for normal operation.

To facilitate cooldown, the CCES uses two CCHS pumps and two CCMS heat exchangers to supply cooling water to both essential loops and the nonessential loop. A slower but acceptable cooldown rate may be accomplished with only one CCES pump and one CCWS heat exchanger aligned to one essential loop and the nonersential loop. Under both conditions, the maximum component cooling water temperature at the CCW heat exchanger outlet is 120 F for a maximum period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, after which the temperature gradually returns to 105 F.

Under accident conditions, on receipt of an S signal, a pump in the other essential loop is started and flow from two pumps is supplied to all loops. Upon receipt of the containment isolation signal, Phase B, the nonessential loop is automatically isolated from the rest of the system, and the two e' Jential loops are isolated from each other. Although only one essential loop is required to mitigate the consequences of an accident, component cooling water is supplied to both essential loops. A single 9 failure of any component does not prevent the system fron supplying water to one essential loop, as described in Table 9.2-9.

A partitioned surge tank, vented to atmosphere, accommodates surges resulting from component cooling water thermal expansion and contraction, and it collects any water that may leak into the system from components being cooled. The CCWS surge tank is located at elevation 167 feet, 6 inches which assures proper operation of the CCES pumps. A drop or rise in the surge tank level during steady operation indicates leakages within the 9.2-9 Amendment 9

GIEBSSAR system. The surge tank level is indicated both locally and in the control rocm, where high and low levels are annunciated.

One chemical addition tank is supplied. Upon detection of 4 in-leakage, manual adjustments are nade at the component cooling surge tank, until dissolved solids and corrosion inhibitor design concentrations as specified in RESAR-414 Section 1.7.1. are achieved. 9 Makeup water is normally delivered to the surge tank from the demineralized water P*orage tank or the reactor makeup water storage tank, with automatic operation of the tank level control valves. Under emergency conditions, makeup water can be supplied 9 from the seismic Category I portion of the fire protection system. See subsection 9.2.3 and 9.5.1 and Figures 9.2-6 and 9.5-1A.

Radiation detectors monitor the CCWS. If the radiation level of the cooling water exceeds a predetermined value, an alarm is given in the control room and the vent on the CCWS surge tank is automatically closed. A vacuum breaker and a relief valve are provided to protect the surge tank.

9.2.2.3 Safety Evaluation The CCWS is comprised of two full-capacity essential loops and one nonessential loop. During emergency operation, the nonessential loop is automatically isolated from the essential loops. The two loops are separated from each other by two autogatically operated valves. The failure of the nonessential cooling loop has no adverse affect on plant capability to safely shutdown the plant or maintain the condition. plant in a safe shutdown' 9 Cne branch of the noncesential loop supplies a header which penetrates the reactor containment and supplies the reactor coolant pumps with the required cooling water.

of the nonessential locp provides cooling waterA second branch to the heat exchangers inside the containment. Each containment penetration is safety Class 2 and has an automatic isolation valve, position indicator and manual operator, located with! 9 outside the containment. One check valve is provided on the CCWS supply line inside the containment to prevent reverse flow, in case of a pipe rupture. CCW piping between the RC pump thermal barrier and the outer containment isolation valve is designed for full RC loop pressure and temperature.

H-414 9.2-10 Arendment 9

GIBBSSAR g

The performance of all conponents is monitored from the control room. Low flow, low pressure, high ten pe ratu re , and high radiation level, which are all indicative of system malfunctions, are annunciated in the control room.

Leakage from any system being cooled by the CCKS is detected by an increase in the level of the CCWS surge tank or by an increase in the system radiation level, when the system being cooled is contaminated. Details of the radiation-monitoring equipment are given in Section 11.5. Leakage from the CCWS to the service water systen or to the atmosphere is detected by a decrease in the CCES surge tank level.

A partition in the surge tank provides separate surge volumes for each essential loop. If one essential loop develops a leak and is taken out of service, the operation of the other loop is unaffected. If a leak develops in the nonessential loop, it can be isolated from the essential loops and operation is unaffected.

The partition is designed to maintain its integrity while one side of the surge tank is empty. All components of the CCWS are located inside of a Seismic Category 1 structure. The CCWS pumps, the heat exchangers, and the essential loops are in the ESF area. The components of the two essential loops are physically separated within the ESF area by a dividing structure. 9 The CCWS pumps are located at elevation 94 feet, 6 incnes, which is above the flooding level that can occur due to equipment failure within the building. These conditions, together with the classification of the CCWS as Seismic Category I, make the systen capable of withstanding adverse environmental occurrences such as postulated earthquakes, tornadoes, and tornado generated wissiles.

The physical separation of the two essential locps precludes coincident damage to redundant equipment in the event of a postulated pipe rupture, equipment failure, or missile generation. Protection against dynamic effects associated with the postulated rupture of piping are discussed in Section 3.6.

9.2.2.4 Tests and Inapections Periodic chemical exanination of the conponent cooling water is nade for pH, chloride content, and corrosion inhibitor content; if required, manual adjustment is made utilizing the chemical addition tank to meet the Westinghouse chemistry specifications 6 listed in PESAR-414 Section 1. 7 .1. Periodic visual inspection and preventive maintenance can be conducted as necessary without interruption of cooling system operation.

k-414 9.2-11 Amendment 9

GIBBSSAR Sufficient instrumentation is provided to monitor system performance.

The CCES components are positioned to allow access for periodic 1 examinations as required by the ASME Code.

The integegrity of the partition in the surge tank will be deternined periodically by raising the water level in one section of the tank to the high water level and observing if there is an 6 equalization of the levels. An equalizing of the levels would be indicative of a leak in the partition.

9.2.2.5 Instrumentation A detailed description of the instrunentation provided for the CCWS is included in subsection 7.3.1.

9.2.2.6 Interface Requirements The interface requirements for the conponent cooling water system is described in Table 9.2-10.

9.2.3 Demineralized Water Storage, Deaeration and Makeup System i 9.2.3.1 resign Basis This system furnishes deaerated demineralized water, for use as a reactor coolant and as secondary plant makeup, and demineralized water for use throughout the plant.

9.2.3.2 Systen Description The demineralized water storage, deaeration and makeup water system consists of a demineralized water storage ta nk , reactor makeup water storage tank, vacuum deaerator, and the demineralized and reactor nakeup water distribution systems. 9 Water from the demineralized water treatnent systen (subsection 9.2.7) is delivered directly to the demineralized water storage tank. She quality of water in the demineralized water storage tank is better than 2.0 micrombos/cn at 25 C; however, this water is saturated with oxygen. For water chemistry see Table 9.2-12.

The demineralized water is supplied'by two demineralized water transfer pumps to the demineralized makeup water distribution system or to the vacuum deaerator as shown on Figure 9.2-5. The 9.2-12 Amendment 9

GIBBSSAR denir.eralized water nakeup distribution system is shown on Figure 9.2-6.

The demineralized water transferred to the vacuum deaerator is deaerated to remove dissolved oxygen to a concentration of 0.1 ng/1, before it ir, supplied to the condensate storage tank, the reactor nakeur water storage tank, the auxiliary feedwater O

9.2-12a Amendment 6

GIEDSSAR storage tank, and REST, as required by their respective levels.

From the reactor makeup water storage tank the reactor makeup water system, shown also on Figure 9.2-6., provides demineralized deaerated water to the BCS, Steam Generator Blowdown System and auxiliary equipment. Two reactor makeup water pumps take suction from the reactor makeup water storage tank and these pumps discharge through a system of headers. As a minimum, one reactor makeup pump operates continuously. The system (including tanks, pumps, connections to the boric acid blender, the pressurizer relief tank, and the conponent cooling water surge tank) 9 is designed as non-Seismic Category I.

The reactor makeup water storage tank is provided with heating systems for freeze protection if required by site conditions.

Any freeze protection provided will be discussed in the 6 Utility-Applicant's SAS. The water temperature is continuously measured and indicated on the control roon panel.

The demineralized water storage tank, reactor makeup water storage tank, and the condensate storage tank are all non-nuclear safety-related, non-Seismic Category I tanks located outside the auxiliary building. Depending on the site, the tanks and associated piping, if necessary, are provided with heating 9 systems for freeze protection.

9.2.3.3 Safety Evaluation Sufficient storage capacity of 250,000 gallons in the demineralized water storage tank is available to supply makeup l 9 water for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in the event that the demineralized water treatment system is out of service.

The demineralized water treatment plant does not contain, treat, or produce any radioactive material; any waste produced by this system is transferred directly to the chemical waste disposal system.

9.2-13 Amendment 9

GIBBSSAP O

The reactor trakeup water storage tank (160,000 gallons) is of 6 sufficient size to provide the nakeup req ui rerrents of the compcnent cooling water system (50 gym)or the safety-related until corrective action can he 9 chilled water system (50 gprr) ta ke r. .

O 9.2-13a Amendment 9

GIDBSSAR 9.2.3.4 Tests and Inspections The equipment is initially inspected and testcd to ensure systen integrity and completeness.

9.2.3.5 Instrumentation Application The demineralized water makeup system is controlled from local panels. The system operation is designed to be fully autonatic with a provision for manual control. The final water quality is continuously monitored for conductivity, pH, and silica.

High-conductivity and high-silica concentrations are alarmed locally and in the control room. The pH is recorded locally.

Deviations from specified water quality cause the pumps to trip which prevents poor quality water from entering the demineralized water storage tank. Regeneration is manually initiated and proceeds autonatically until completion.

9.2.3.6 Interface Requirements The interface requirenents for the demineralized makeup water system are described in table 9.2-11.

9.2.4 Potable and Sanitary Water Systems The potable and sanitary water system supplies water for toilets, sinks, showers, drinking purposes, and miscellaneous plant use.

It is completely separated from the laundry and hot shower portion of the liquid waste processing systen.

This system will be presented in the Utility-Applicant's SAP.

9.2.5 Ultimate Heat Sink The ultimate heat sink is used to dissipate heat rejected fron the station service water system to pernit safe shutdown and cooldown of the plant and maintain it in a safe shutdown condition and to dissipate heat rejected from the plant in the event of an accident.

The system is site-related and will be presented in the Utility-Applicant's SAP.

9.2.5.1 Interface Requirements The interface requirements for the ultimate heat sink is described in Table 9.2- 14.

9.2-14 Amendment 2

GIBBSSAR O

9.2.6 Condensate Storage Facilities The condensate storage facility prinarily provides makeup and surge capacity for secondary system inventory changes caused by different operational conditions, thernal effects, and draining or filling of any part thereof.

9.2.6.2 System Description The condensate storage facility consists of one tank (Figure 9.2-7) of sufficient capacity tc accommodate systen surge, auxiliary feed and nakeup water requirenents.

The tank is constructed of coated carbon steel and designed in accordance with the requirements of API 620.

9.2.6.3 Safety Consideration The condensate storage tank is not required to ensure the follching:

a. The integrity of the RCPB
t. The capability to shut down the reactor lll
c. The capability to prevent or nitigate the consequences of accidents which can result in potential offsite exposures (guidelines of 10 CFR Part 100).

The tank is non-nuclear safety-related. The possibility exists that activity nay te present in the condensate storage tank. The activity is dependent on the percentage of failed fuel and ruptured stean. generator tubes. A detailed discussion on secondary site activity is presented in subsection 10.2.4.

Cepending on the site, the tank is provided with a heating systen to prevent freezing or icing.

9.2.6.4 Tests and Inspections Visual inspection is periodically perforned after construction.

9.2-15 A2endnent 1 llh

GIBBSSAR 9.2.6.5 Instrumentation Tank water level indication is provided, both locally and in the control room. Annunciation is provided in the control room for high and low water levels.

9.2.6.6 Interface Requirements RESAR-414 interface requirements for the condensate storage facility are only applicable when this tank is used to supply 6 auxiliary feedwater. Auxiliary feedwater is supplied from a separate storage tank. See Section 10.4.9.

9.2.7 Demincralized Kater Treatment Systen The demineralized water treatment system provides pretreated and i filtered water for use in the potable and sanitary water systen and as influent to the demineralized water storage, deaeration, ar.J makeup water systen.

The demineralized water treatment system is site-related and will be presented in the Utility-Applicant 8s SAR.

9.2.9 Plant Ventilation Chilled Water System 9.2.6.1 Design Bases The plant ventilation chilled water system is designed to provide an uninterrupted flow of cooling water to the following areas during normal cperation.

a. The controlled access supply units.
b. Nain Steam 6 Feedwater Auxiliary cooling units
c. Controlled Access Supply Equipment Room Auxiliary 9 Cooling Units
d. The charging pump rooms auxiliary cooling units
e. The containment recirculation air cooling units
f. the neutron-detector well cooling units During loss of offsite power, the controlled access supply units are not supplied with chilled water. '

9.2-16 Amendment 9

GIEBSSAR h

The system consists of four 33-1/3 percent-capacity chiller units and four 33-1/3-percent-capacity punps, both of which are individually connected to Class IE electrical buses supplied by the ensite standby cower system described in section 8.3. The chiller units are not required at sites where service water of a high quality and adequate temperature (below 90 F) is available.

Compcnent cooling water will be used instead of service water atl1 sites which have poor service water quality. The temperature limit of 90 F will still apply in these cases. l1 A chilled water expansion tank is connected to the demineralized water system and the return line of the chilled water system.

Sufficient redundancy is incorporated into the system design to effectively handle a single-failure of any of the active 9 con.penents.

The system is non-nuclear-safety-related, except as noted on Figure 9.4 9, and the portion inside the containment is designed to Seismic Category I rcquirements.

9.2.8.2 Systen Descripti( n 1he Flant ventilation chilled water system is shown schematically llh on Figure 9.4-9. The system design includes :

four 33-1/3-percent-capacity chiller units; four 33-1/3-percent-capacity pumps; a chilled water expansion surge tank; and associated piping, valves, and instrumentation.

The standby chiller unit and pump are canually started should any 9 single active component fail in the operating units.

During normal operation cooled water is delivered by the manually operated water pump-chiller unit arrangements via a piping system to all five areas specified in subsection 9.2.8.1. The water flow rate provided by the chillers is monitored and controlled and is contingent on the temperature of the air entering the cooling coil in each area being served. Automatically operated to the equipment 3 valves regulate the ficw of chilled water cooling the specified areas. The temperature of the chilled water is monitored, and kept constant.

9.2-17 Amendment 9

GIBBSSAR A recirculation line fitted with valves, flow meter, and a differential pressure transmitter links the outlet supply header of the chillers with the system return header and helps transport chilled water, when the dif ferential pressure becomes low back toll the suction side of the chilled water pumps. The chilled water expansion tank directly connects with both the demineralized water system and the plant ventilation chilled water system. It either provides makeup water to or receives water from the chilled water system depending upon thermal expansion, contraction or leakages occurring within the system. A valve 9 arrangement is provided at the demineralized water connection (see figure 9.4-9) to control the flow from the demineralized water system into the tank. The tank is prcvided with a vent and a drain connected to-the floor drain system. Expansion tank water levels are monitored and indicated in the control room at all times. Annunciators indicate design low-water levels.

After a containment isolation signal, the containnent isolation valves in the supply and return lines, which supply water to the containment recirculation and neutron detector well cooling coils, are automatically closed, as . required. The plant ventilation chillers and the recirculation pumps are autonatically shutdown upon reciept of a containnent isolation 9 signal, and during loss of offsite power.

After a loss of offsite power the emergency standby diesel generators automatically power the Class 1E electrical buses.

The plant ventilation system is anota needed for "safea plant shutdown. However, the containment portion of this system will operate during a loss of offsite power or shutdown to avoid possible damage, of non-safety related equipue nt. This requires 9 the operation of 'wo chillers. The plant veulitation system is automatically tripped on reciept of an "S" signal.

9.2-18 Anendment 9

GIBBSSAR O

a. Leakage and Centrol The chilled water system expansion tank accommodates surges resulting from tne thernal expansion or contraction of water. A significant drop (i.e. telow a predetermined value) in the expansion tank level during steady operaticn implies leakages within the system. The expansion tc.... level is indicated locally and in the control room. High- and low-water levels are annunciated in the control room. The demineralized water system O

9.2-18a Amendment 6 h

GIEBSSAR supplies makeup water, required when the tank level falls below a predetermined value, and a drain pipe discharges excesses to the floor drain system.

h. Components The plant ventilation chilled water system is non-nulcear safety-related and is shown on Figure 9.4-9.
1) Chiller Units Centrifugal compressor type water chilling units are used. The evaporator is a shell-and-tute heat exchanger cooled by the CCWS.

l9

2) Pumps The plant ventilation chilled water system pumps are cf the horizontal, centrifugal, single-stage type. They are fabricated of carbon steel.
3) Expansion Tank The expansion tank accommodates changes in chilled water volume. The tank is constructed of carbon steel.
4) Valves The valves provided in the plant ventilation chilled water system are S'pring-loaded relief valves are providedcarbon fabricated from steel.

for lines and conponents that could becone pressurized beyord their design limits.

5) Piping All chilled water . ping steel, with welded is fabricated from carbon ats and connections. Exceptions occur for certain ,mponents where flanged connections are used to facilitate maintenance.

9.2-1 Amendment 9

GIBBSSAR 9.2.8.3 Safety Evaluation The system is non-nuclear safety related and Seismic Category I in the containnent to avoid damage to adjacent safety related 9 equipment.

The performance 7f all essential equipment is monitored from the control room. Low or high flows, pressures, and temperatures which would reflect system galfunction are visually and audibly annunciated in the control room. Leakage in the system can be identified by control room indicators. The operator takes apprcpriate action to curt a continued deterioration of system conditions.

All the major components of the system including piping and its appurtenances, are located inside Seismic Category I structures.

The pumps are arranged in parallel and connected to the chiller units (in parallel) and are located in the primary plant 9 ventilation equipment area of the auxiliary building. Redundancy in equipment is sufficient to handle all conditions, ncrmal or adverse, attendant with the design modes of operation.

Failure of a single component of the plant ventilation chilled water system does not have an adverse effect on the ability to safely shutdown the plant or to maintain the plant in a safe shutdown condition.

9.2.8.4 Tests and Inspection Requirements Shop inspection and testing are performed for all rotating equipment and modular controls. The systen is initially tested for proper flow paths, flow capacities, and mechanical operabilities and is adjusted accordingly.

Periodic chemical examination of the chilled water is made for pH and corrosion-inhibitor content, and adjustments are made, if required. Sufficient instrumentation is provided to monitor system performance. Periodic visual inspection is conducted, as required, without interrupting system operation.

9.2-20 Amendment 9

GIBBSSAR O

9.2.8.5 Instrumentation Requirenents The systen is provided with instrumentation to allow the complete 9 monitoring of the system from the control roca.

The pumpc, and the chiller units (when these are provided) are started individually from switches in the equipment room.

Pressure transmitters located at the inlet and outlet of the 9 pumps permit the indication of these pressures in the control room. A low O

9.2-20a Amendment 9 lh

GIEBdSAR outlet pressure at any pump, implying malfunction of the unit, is 9 annunciated audibly and visually in the control room.

At sites where chiller units are employed, temperature sensors placed at the outlet of the chillers provide temperature indication locally and in the control room. The chillers are set to deliver water at a predetermined tenperature which is indicated by the temperature elements at the outlet side. Iarge deviations above the preset temperature, implying unit malfunction, are annunciated audibly and visually in the cantrol room. The standby chiller unit may he manually started by the operator.

A differential pressure transmitter located across the supply and return water lines monitors and indicates (in the controls room) pressure differentials. The transmitter also centrols thel1 modulating valve that regulates the recirculation flow to the return water line, which helps to maintain the constant head flow delivered by the pump. Flow elements and transmitters enable the displav of flow rates, locally and in the control roca. l Temperature elements located in the ductwork downstream of the 9 cooling coils, controls the modulating valves that regulate the water flow rates through these coils. The temperature in each area is indicated locally. The valves that regulate the flow into the charging pump rooms auxiliary cooling units are manually opened and closed from the control room.

h During loss of offsite power two chillers and two pumps are required to prevent damage to non-safety related equipment' inside the containnent and are manually powered by the Class IE 9 electrical bus. During a LOCA the containnent is isolated and the system tripped, automatically.

9. 2. S Ventilation S6fety Features Chilled Water System 9.2.9.1 Design Bases The ventilation safety features chilled water system is designed to provide a forced flow of cooling water to cooling coils located in the following areas during nornal and emergency conditions:
a. PHR pump room (elevation 72 feet, 6 inches)
b. Containment pump spray roon (elevation 72 feet, 6 inches) l9 9.2-21 Amendment 9

GIEESSAR h

c. Safety injection pump room (elevation 72 feet, 6 inches)
d. Component cooling water pump roon (elevation 94 feet, 6 inches) l9
e. Auxiliary feedwater purp room (elevaticn 94 feet, 6 inches) l9
f. Kater sampling station (later) 9 Spent fuel pool cooling pump room (elevation 94 feet, 6 inches) l9
h. Uncontrolled access areas (elevations 150 feet, 6 inches and 100 feet, 6 inches)
i. Controlled access area exhaust equipment roca (elevation 146 feet, 6 inches)
j. Control room (elevation 130 feet, 6 inches) l9 Chilled water delivered to each area is contingent on the mode of operation used at the particular tine.

The system is comprised of two independent trains. Each train O

consists of two 50-percent-capacity water pumps, one 100 percent-capacity chiller unit, associated piping, valves, and controls. The chiller units are not required at sites where cooling water, either service water of a high quality or CCE system water, is availahle at a temperature helow 700 Eachl9 train is connected to a separate Class IE electrical bus supplied by emergency standby diesel generators.

The return water line of each train is as shown in Figure 9.4-5 connected to a separate chilled water expansion tank. Each tank is connccted to the reactor water makeup water system, fire 9 protection system and the demineralized water system through a common header.

Fedundancy of equipnent and power supplies is incorporated into the system design to conpensate for a single failure of any compcnent. l9 The system is designed to Seismic Category I and ASME Code III tequirements, and classified as ANSI nuclear safety class 3. l9 9.2-22 Amendment 9 h

GIBBSSAR 9.2.9.2 System Description The ventilation safety feature chilled water system is shown schematically cn Figure 9.4-5 The system design includes two trains, each comprised of two 50 percent-capacity water pumps, one 100-percent-capacity centrifugal-type chiller unit, piping, valves, and controls. The trains are physically separated by the valve arrangements as shown in Figure 9. 4- 5. The pumps and chiller on a single train are sized to handle the total of postulated heat loads to which the train could be subjected. Consequently one train is normally operational while the other remains on standby.

During normal operation, cooled water is delivered by a manually started water purp-chiller unit arrangement via a piping network to the areas specified in subsection 9.2.9.1 (except areas specified in a, b, and c) . The PHR pump-room coils which are l interlocked with the PHR pumps are supplied during reactor startup, reactor shutdown and LOCA. The containment spray pump and safety injection pump room auxiliary cooling coils which are interlocked to the pumps are supplied following a LCCA or when the pumps are tested. The water flow rate of each pump train is 9 monitored cooling coil.

and is contingent on the chilled water supply to each Each of these water supplies is constant, except that through the uncontrolled access area and control roon cooling coils which are regulated by temperature modulated valves with provision for manual operation from the centrol room. The chilled water flow to each coil depends on the design tenperature for that area. The tenperature of the chilled water distributed to the areas served is monitored and indicated locally and in the control room. This temperature can te maintained constant by properly setting the chiller units when these are included in the system design. However, when service water or CCW system water, is used for coolir.7 this temperature may fluctuate. g Pedundant recirculation lines fitted with valves, flow meter, and differential pressure transmitter links the outlet supply header of the chillers with the system return header.

This aids in the transportation of cooled water not required back to the suction side of the chllled water punps.

by the cooling coils of The anount recirculation flow depends on the differential existing across the supply and return water lines. pressure l 1 lg 9.2-23 Amendment 9

GIEBSSAF g

The chilled water expansion / surge tanks are linked with the demineralized water system, the fire protection system, and the reactor nakeup water system. The fire protection or reactor 9 makeup water systems are utilized when demineralized water is not available. Their function is to provide makeup water to the chilled water system. Makeup water is required as a result of leakages or thermal contraction within the system, whereas receipt of water by the expansion / surge tanks is a result of water thermal expansion within the system. The tanks vent to the floor drain system via a common header. The piping system provided with the tanks is fitted with valves and controls which are cperated locally or remote manually from the control room.

Surge tank water levels are monitored at all times and displayed locally and in the control room. Annunciators indicate high and low levels. A failure in one loop does not affect the 9 performance of the other.

a. Leakaoe and Control The chilled water expansion tanks accommodate surges resulting from t .' ' thernal expansion or contraction of water. To maintain the desired pressurization within the system the tank is located at an elevation above all components in the system. A drop telow a predetermined level in either surge tank level during operation llh indicates leakage within the system. The water levels in the tanks are in?.icated locally and in the control room.

9 The fire protection system provides a seisnic Cateorgy I source of makeup water needed by the ventilation safety feature chilled water system during accident conditions and when the demineralized water system is nonoperational or overburdened, or both. An outlet header discharges excess water from the tanks to the floor drain system.

L. Components p

1) Chiller Units Centrifugal compressor type water enilling units are used in both trains. The evaporator is a shell-and-tube heat exchanger with the refrigerant in the shell side.

The condenser is of the shell-and-tube heat exchanger type and is cooled by CCWS water. 9 9.2-24 Amendment 9

GIEBSSAR 21 Pumps The pumps, used centrifugal type.

in both trains are of the horizontal

3) Expansion Tanks The expansion tanks are constructed of carbon steel, and are 9

sized to accommodate changes in chilled volume. water

4) Valves The valves fitted to the system piping are fabricated out of carbon steel.

9

5) Piping All chilled water piping steel with welded joints and is connections, fabricated out of carbon except for certain components where flanged connections are used to facilitate maintenance.

9.2.9.3 Safety Evaluation The system is designed to ANSI safety Class 3 and Seismic Category I. During an emergency mode, all the cooling coils 9 served by this system become functional automatically opening the valves that allow flow of chilled water through these coils.

9.2-25 Amendment 9

GIBBSSAR The performance of all essential equipment is acnitored fron the control rocm. Low or high flows, high or 1 pressure or temperature conditions, all of which would a rfect the systen adversely, are annunciated in the centrol room. Leakage in the systen can be identified, locally and in the control room by the water level indicators. The operator nust take appropriate acticn tc avoid further deterioration of the system conditions.

All the najor components of the system, including piping and its appurtenances, are located inside seismic Category I structures.

These structures which enclose the pumps and chiller units are designed to preclude coincident damage to redundant equipnent in the event of a postulated pipe rupture, equipment failure, or missile generation. The pumps and chiller units are located at an elevation which is above the highest water level that night occur as a result of equipment failure within the auxiliary building. Fedundancy in trains is sufficient to handle normal or adverse conditions conconitant with the design modes of operation. Standby equipment is autonatically started as thel6 failed unit becones inoperable. See Section 9.2.9.5. l9 Failure of a single component within the ventilation safety feature chilled water system does not have an adverse effect on the ability to either safely shut down the plant or to maintain llh it i r. a safe shutdown ccndition.

9.2.9.4 Tests and Inspections l1 Shop inspection and testing are pceforned for all rotating equipnent and modular controls. The s stem is initially tested for proper flow path, flow rapacities, and mechanical operatilities and is adjusted acccrJingly. Periodic chemical examination of the chilled water is made for pH and corrosion inhititor content; maneal adjustmen. is made, if necessary.

Sufficient instrumentat ion is provided tc nonitor the systen performance. Periodic visual inspection is conducted, as required, without interruptinc the. system operation.

9.2.9.5 Instrumentation The systen is providri with instrumentation that allows the nonitoring and control cf the system from the control room.

The two pumps and the chiller unit on a single train are interlocked and started manually from a switch in the control room. Pressure transmitters located at the inlet and outlet of l1 9.2-26 Amendment 9

GIBBSSAR the pumps permit indication of these pressures on the control l1 9.2-26a Amendment 6

GIBBSSAR O

room panels. A low differential pressure across any pump, inplying unit ralfunction, is annunciated audibly and visually in the control roon. The standby pumps-chiller a rra ngment is autonatically started as the failing equipment is tripped. l9 I6 At sites where chiller units are exployed, temperature sensors placed at the outlet of the chillers provide tenperature indication both locally and in the control room. The chillers are set to deliver water at a predetermined temperature khich is indicated by the temperature elements at the outlet side. Iarge deviations above the preset temperature, implying unit l1 malfunction, are annunciated audibly and visually in the control room. A differential pressure transmitter located across the supply to the return water line, helps detect any leaks in the systea and balance the flows. Flow elements and transmitters enable the indication cf flow rates, locally arc in the conrol 9 room.

Temperature elements located in the areas served by the uncontrolled access area cooling coils provide indication of temperature locally and in the control room. The valves that regulate flow into these cooling coils modulate as a function of 6 temperature. When a failure or LOCA occurs they go full open.

During loss of offsite power the functional unit is automatically O

powered by the class IE electrical bus. During a LOCA the cooling coils required for safe shutdown of the plant are autonatically supplied with chilled water whereas those not needed can be manually isolated from the control room. The 6

valves that physically separate the trains close automatically when a LCCA occurs.

High and low level of the expansion tanks are alarmed audibly 9

and visually in the control room 9.2-27 Anendment 9 h

GIPESSAR 1 TABLE 9.2-1 (Sheet 1 or 2) 6 SERVICE hn?"' TOTAL !! EAT LOADS (10 Btu /hr) l9 (Westinghouse - 414) 1 Plant Shutdown Plant Shutdown S t a rt u 2__ Nornal Oper. at 4 hrs. at 20 brs. FefueljDS_ I9 Number In Heat In Heat In Heat In lleat In Heat Spgggne nt Provided Serv. Load Serv. Load Se rv. Load Serv. Load Sggv2 Lead 1

1. Essential Cooling loop CCW Heat Fxchanger 2 2 153.42 1 106.00 2 337.77 2 174.3G 2 173. 71 l 9 Emergency diesel 2 - - - - - - - - - -

generator

2. 1:cnessential Cooling i Icops '

CVCS chiller unit 1 1 3.42 - - - - - -

Total 153.42 109.42 337.97 174.30 173.71 9

Total tassuming 153.42 109.42 192.99 127.63 127.19 single failure criteria-one 100%

train in operation) 1 Arendment 9

GIEBSSAR TAELE 9.2-1 1 (Sheet 2 of 2)

SERVICE WATEF TOTAL HEAT LOADS (106 Btu /hr) l9 (Westinghouse - 414)

Safety Safety Injection Loss of Power Ebase A Isolation Phase B IsolatiMD PecirculatioD Hot Shutdown Cooldown at 20 hre.

In Heat In Heat In Heat In Heat In Heat Comconent ferv. Load Serv. Load Se rv. Lgad Serv. Load Serv. 122$

1. Essential Cooling loop CCW Heat Exchanger 2 39.27 2 6.32 2 342.12 2 70.96 2 147.25 9 Energency diesel 2 36.0 2 36.0 2 36.0 2 36.0 2 36.0 generator
2. Nonessential cooling loop 1 cvcS chiller Unit -

Total 75.27 42.32 378.12 106.96 183.25 9

Total (assuming 56.61 23.66 214.06 88.73 118.59 single failure criteria-one 100% train in operation) 1 Amendment 9 O O e

GIPBSSAR TABLE 9.2-2 1

(Sheet 1 of 2)

SEEVICE WATER FLCW PATES (gpm)

(Westinghouse - 414)

Plant Shutdown Plant Shutdown St a rtur Eormal Opera di 4 hrs, at 20 hrs. Eeiugling l9 Number No. flow No. Flow No. Flow No. Flow No. Flow

[onconent Provided Cooled Pate Cooled Pate Cooled Pate Cooled Eate [ooled Pate 1

1. Essential Cooling loop CCW heat exchanger 2 2 30,000 1 15,000 2 30,000 2 30,000 2 30,000 9

Energency diesel generator 2 2 2,70C 1 1,350 2 2,700 2 2,700 2 2,700

2. bonessential Cooling loop CVCS chiller unit 1 1 1,000 1 1,000 1 1,000 1 1,000 1 1,000 Total 33,700 17,350 33,700 33,700 33,700 9

Total (ascuming single failure criteria- 17,350 17,350 17,350 17,350 17,350 One 100% train in operation) 1 Anendnent 9

GIEBSSAR TAELE 9.2-2 (Sheet 2 of 2)

SERVICE EATER FLOW FATES ( qptr) 1 (Eestinghouse - 414)

Safety Injection Safety Injection Ioss of Power Phase A Isolation Phase B Isolati9D Egeirculation riot Shut own sooldown at 22_hIJs No. Flow No. Flow No. Flow No. Flow No. Flow

[omponent Cooled Fate Cooled Fate ggoled Pate Cooled pate Cooled Pate

1. Essential Cooling Ioop CCE heat exchanger 2 19,000 2 19,000 2 19,000 2 30,000 2 30,000 9

Emergency Diesel 2 2,700 2 2,700 2 2,700 2 2,700 2 2,700 generator

2. Nonessential Cooling 1 loop i

1,000 - - - -

1 1,000 1 1,000 CVCS chiller unit ) l 22,700 21,700 21,700 33,700 33,700 Total 9

Total (assuming single failure 11,850 10,850 10,850 17,350 17,350 criteria-one 100% train in operation) 1 I

I l

Amendment 9 O O e

GIEESSAR TAELE 9.2-3 SEFVICE WATER SYSTEM DESIGN PAR AMETERS igtylce Eater Syster Purrs Cuantity four Type centrifugal Fluid purp(d service water Cesign ficw rate, gpm 19,000 l9 Cesign head (TCH) , ft 170 resign tenperature, F 150 Motor size, Ehp 1000 19 Design code ASME III Safety Class 3 Seisnic Category I Arendment 9

GIEDSSAF TABLE 9.2-4 SItiGLE FAILURE ANALYdIS OF SERVICE WATEF SYSTEM Effect on System (ogegnent Malfunction safeouard Performance Comments

1. Eervice water pumps stops pumping no effect Four 100-percent-capacity pumps are provided.

One is required.

2. Femotely operated stop a. Fails to close r.o effect Valve redundancy valves for redundant is provided.

header isolation b. Unwanted closure no effect Beader reduadancy is provided,

c. Fails to open no effect 11eader redundancy is provided.
3. Emergency diesel f ails to start no effect Pumps and stop generator valves for header isolation are redundant. Power for redundant com-poaent is supplied from a different diesel generator.
4. Component cooling loss of flow no effect Two 100 percent-teat exchanger capacity supply headers are provided.
5. Piping pipe rupture no effect Two 100 percent-capacity supply headers and two 100-percent-capacity return lines are provided.
  1. 9 e

GIBBSSAR TABLE 9.2-6 (Sheet 1 of 6)

COMPONENT COOLING WATER TCTAL !! EAT LOADS (IC' Btu /hr) l9 (Westinghouse - 414) 1 Plant Shutdown Plant Shutdown Elgglyr Normal Oper. at_4 hrs. at 20 hrs. Pefueling l9 Numbe r In Heat In F.st in Heat In Hea t In Heat Cceronent Provided Serv. Load Serv. Load perv. Load Serv 2 load Serv 3 load 1

1. Essential Cooling loop CCW pump cooler 4 2 0.36 1 0.18 2 0.36 2 0.36 2 0.36 9

FEF heat exchanger 2 1 27.0 - -

2 289.6 2 92.6 2 92.6 Containment spray 2 - - - - -

1 pump cooler FEF/LBSI pump cooler 2 1 0.03 - -

2 0.06 2 0.06 2 0.06 l9 EBSI pump cooler 2 - - - -

1 Auxiliary feedwater 2 2 0.30 - -

2 0.30 2 0.30 - -

pump cooler Centrifugal charging 2 1 0.08 2 0.17 2 0.17 1 0.08 - -

l9 pump cooler l1 Safeguard chilled 2 1 6.0 1 6.0 1 6.0 1 6.0 1 6.0 I9 water system 1 Spent fuel pool 2 1 25.5 1 25.5 1 25.5 1 25.5 1 25.5 l9 heat exchanger 1

Amendment S

GIPESSAP 1

T ABLE 9. 2-6 (Sheet 2 of 6)

COMPCNENT CCOLING WATER TOTAL HEAT LOADS (10* Etu/hr) l9 (Westinghouse - 414) 1 Plant Shutdown P la r.t Snutdown S t a rt ue U2rral coer, at 4 brs. at 20 hre. Eti2iliD2 I9 Number In Heat In Heat In Heat In Eeat In Heat Comronent Provided gegy, Load Serv. Load serv. Load Serv. Ioad serv 2 1982 1

2. Esnessential cooling Loop Evaporator concentrate 2 2 0.02 2 0.02 2 0.02 2 0.02 2 0.02 4

storage tank Instrument air aftercooler 2 1 0.25 1 0.25 1 0.25 1 0.25 1 0.25 9 I

and compressor service air aftercooler 1 1 0.20 1 0.20 1 0.20 1 0.20 1 0.20 4 and compressor Earple heat exchanger 7 1 0.22 1 0.22 1 0.22 - - - -

9 GFFD sample cooler 1 0.21 1 0.21 1 0.21 - - - -

Eoxon recycle evaporator 1 1 8.81 1 8.81 1 8.81 1 e.81 1 6.61 1 package Eigh activity waste 1 1 8.81 1 8.81 1 8.61 1 6.81 1 8.61 2 evaporator packagt low activity waste 1 1 9.00 1 9.00 1 9.00 1 9.00 1 9.00 l 4 evaporator package 2 seal water heat exchanger 1 1 2.4 1 2.4 1 2.4 1 2.4 1 2.4 1

Ietdown heater exchanger 1 1 33.50 1 20.0 1 11.6 1 C.2 1 6.2 Catatytic recombiner 2 1 0.07 1 0.07 1 0.07 1 0.07 - -

Plant ventilation chillers 4 3 13.5 3 13.5 3 13.5 3 13.5 3 13.5 9

Easte gas compresser 2 1 0.13 1 0.13 3 0.14 1 0.14 - -

package Amendment 9 9 9 e

1 GIEPSSAR TABLE 9.2-6 (Sheet 3 of 6)

CCMPONENT COCLING WATER TCTAL HEAT LCADS (106 Btu /hr) l9 (Westinghouse - 414) 1 Plant Shutdown Plant Shutdown Startur Normal OpeIz at 4 hrs. at 20 hrs. Fefuelipg l9 Number In Heat In Heat In Heat In Heat In Heat Gomocned Provided geIh 128$ EerV. lOM EHL LOdd ESIVA 19dd SefVA Load 1

Feactor coolant pumps 4 4 3.0 4 3.C 1 0.75 - - - -

Excess letdcwn heat 1 1 6.5 - - -

exchanger 12 Feactor coolant drain 1 1 2.23 1 2.23 -

collection tank heat 1 exchanger i

Feactor coolant pump 8 4 8 5.3 8 5.3 - - -

notor air cooler 9

Total 153.42 106.00 337.97 174.30 173.71 Total (83 76.71 -

(5) 168.98 87.15 86.86 Total c r > 147.08 106.00 192.94 127.63 127.19 Arendaent 9

GIBBSSAR 1

TABLE 9. 2-6 (Sheet 4 of 6)

CCNPCNENT COCLING WATER TOTAL HEAT LOADS (106 F t u/ hr) }9 (Westinghouse - 414)

Safety Injection Safety Injection loss of E9ERI 1 Phase A Isolation Phase P Isolation Fecirculation hg1_{DutdoED cooldoyg_gt 20.brs.

Max In Heat In Heat In Heat In I! eat In Heat Compgnent Serv. Load Se rv. Lgad Serv. Load Se rv . Ioad Gery, Igad

1. Issential Cooling loop CCW pump cooler 2 0.36 2 0.36 2 0.36 1 0.18 2 0.36 FER heat exchanger - - - -

2 335.8 - -

2 92.6 9 Cont ainment spray pump cooler 2 0.6 2 0.6 2 0.6 - - - -

FEP/IHSI pump l1 cooler 2 0.06 2 0.06 2 0.06 - -

2 0.06 i 9 Auxiliary feedwater pump cooler  ? 0.30 2 0.30 2 0.30 2 0.30 2 0.30 1

Centrif ugal chargir.g gump cooler - - - - - -

2 0.17 1 0.08 [9 Safegard chilled l1 sater system -

5.0 1 5.0 1 5.0 1 6.0 1 6.0 lg Spent fuel pool !1 beat exchanger 1 25.5 -

(6) -

(6) 1 25.5 1 25.5 l9 1

Amendment 9 O O e

GIEESSAR TABLE 9.2-6 1 (Sheet 5 of 6)

COMPCNENT COCLIhJ WAT ER TOTAL HEAT LOADS (106 Bt u/ hr)

(bestinghouse - 414)

)

Safety Injection Safety Injection Loss of Power Phase A Isolation Fhase P Isolation Pecirculation Hot Shutgpwg Cooldown at 20_bgst 1 Max In Heat In lleat In Heat In Heat in Heat iompone nt Serv. Load Serv. Loa d Serv. Lgad Serv. 12ad Eerv. Lead

2. Fonessential cooling loop Evaporator concentrate - - - -

storage tank - -

4 Instrument air aftercooler and compressor 1 0.25 - - - - 1 0.25 1 0.25 Service air aftercooler 1 0.20 -

and compressor Sample heat exchanger - - - - - -

1 0.22 - -

9 CFFD sample cooler - - - - - -

1 0.21 - -

Eoron recycle evaporator - - - - - 1 package Eigh activity waste - . _

evaporator package -

2 Low activity waste - - -

evaporator package - -

Seal water heat ex hanger -

(2) - - - -

1 2.4 1 2.4 9

Letdown heat exchanger -

(3) - - - -

1 20.0 1 6.2 catalytic recombiner -

1 Easte gas compressor package - - - - - - - - - -

Elant ventilation chillers 3 13.5 - - - -

3 13.5 3 13.5 l 9 Arendment 9

- GIEESSAF TABLE 9.2-6 1 (Eheet 6 of 6)

CCMPCNENT COOLING EATER TOTAL HEAT 1 CADS (10* Btu /hr) l9 (Westinghouse - 414)

Safety Injection Safety Injection Loss of P2WRI Ehase A Ingl3 tion Ibase F Isolation Fecirculati2D yot Shut down EggldnItag,2Q_ lins Max Heat 1 In Heat In Heat In Heat In lieat In ComponeDi Serv.

d ad serv. Load Sery. Load Serv. Igad serv. Ioad reactor coolant pumps 4 3.0 -

(4) - - - -

Excess letdown Leat - - - - - -

cxchanger -

(3) - -

Feactor coolant drain collection tank heat - - - 2.23 - -

- - - 1 exchanger Feactor coolant puTp 8 4.0 - - -

4 notor air coolers Total '

39.27 6.32 342.12 *0.96 s 147.25 Total (s) 19.64 5.66 196.06 35.48 73.63 9

38.61 5.66 196.06 70.73 100.59 Total (a)

Notes:

(1) Total is the heat load per one component cooling water heat exchanger with two 100% trains in operation.

(2) Total is the heat load for one component cooling water heat exchanger assuming single failure criteria (one 100% train in operation) .

(3) Assuming component cooling water flow is valved off on SS" signal.

(4) Flow terminated on HI-3 containment pressure ("p" signal)

(5) During normal operation ( 1) pump is used to cool both trains.

(6) Flow to SFP B/x's is restored (10) hr after phase B isolation, A this time the total heat on CCW syster, .

Amendment 9 9 9 e

GIBBSSAR TABLE 9.2-6 (Sheet 6a of f)

CCMPCNENT CCCLING MATER TOTAL HEAT IDADS (10* Btu /hr) l9 (Westinghouse - 414) including load of SF pool is less than at the beginning of cecirculation as shown. l9 Amendnent 9

GIEESSAR TAPLE 9.2-7 (Sheet 1 of 6) 1 CCMPONENT COOLING WATEE TCTAL FLOW RATES (gpm) l9 (westinghouse - 414) 1 Plant Shutdown Plant Shutdown S1artur No rmal ope r. At 4 hrs. at 20 hrs. Fefuelina l9 Number No. Flow No. Flow No. Flow No. Flow No. Flow

[ceporent Provided Cooled Fate Cooled Eaig Cooled Pate Cooled Eats Essiss Eats 1

1. Essential Cooling loop 4 4 144 4 144 4 144 4 144 4 144 CCh pump cooler 9

FEP heat exchanger 2 1 9000 - -

2 18,000 2 18,000 2 18,000 Containment spray pump cooler 2 (5) 160 2 160 2 160 2 160 2 160 1 12 2 12 2 12 2 3ER/LESI pump cooler 2 (5) '2 2 12l9 Auxiliary feedwater pump cooler 2 2 60 2 60 2 60 2 60 2 60 1 Centrifugal charging 2 -

(5) 110 2 110 2 110 (5) 110 (5) 110 l 9 pump cooler 1

safeguard chilled Eater system 2 1 1,000 1 1,000 1 1,000 1 1,000 1 1,000l9 Spent fuel pool 1 heat exchanger 2 1 5150 1 5150 1 5150 1 5150 1 5150 Amendment 9 9 9 e

GIEBSSAR 1 TABLE 9.2-7 (Sheet 2 of 6)

CCMPCNENT COCLING W ATER TOTAL ELOW RATES (gps) l9 (Westinghouse - 414) 1 Plant Shutdown Plant. Shutdown Startuo Normal Oper. at 4 hrs. at 20 hrs. Fef ge11D3__ ! 9 Number No. Flow No. Flow No. Flow No. Flow No. Floh 52EEGLiD1 Provided C221gd Fate Cooled Pate Cooled Pate Cooled Pate Cooled Egig y

2. Nonessential cooling Loop Evaporator concentrate storage tank 2 2 8 2 8 2 0 2 8 2 8 Instrument air af tercooler 4 and compressor 2 1 20 1 20 20 20 1 1 1 20 Service air afterccoler 1 1 75 1 75 1 75 75 and compressor 1 1 75 Eample heat exchanger 1 (5) 98 (5) 98 ( 5) 98 (5) 98 (5) 98 GFFD sample cooler 9 1 28 1 28 1 28 (5) 28 (5) 28 Eoron recycle evaporator 1 package 1 1 780 780 780 1 1 1 780 1 780 Bigh activity waste evaporator package 1 1 780 1 780 780 730 1 1 1 780 2 Low activity waste evaporator package 1 1 1000 1 1000 1 1000 1000 1 1 1000 4 seal water heat exchanger 1 1 372 1 372 1 372 1 372 1 372 {9 Ietdown heat exchanger 1 1 2083 1 1400 2083 984 1 1 1 984 y Catalytic recombiners 2 (5) 20 (5) 20 (5) 20 (5) 20 (5) 20 9 Elant ventilation chillers 4 3 2700 3 2700 3 2700 3 2700 3 2700 Easte gas compressor

. package 2 (5) 100 (5) 100 (5) 100 ( 5) 100 (5) 100 Feactor coolant pumps 4 4 864 4 864 1 216 864 9

( 5) - -

l Art ndment 9

GIEESSAF y TAELE 9.2-7 (Steet 3 of b)

CCy.PCNENT CCCLIbG 'a AT EF TCT AL FLCh FATES (gpx) l9 (We s t inghousc - 414) 1 Plant Shutdown Pl. ant S h utdow n startur Eorr al open__ at a hrs, gL10 hrs. Fat:Jallm_ l9 i;urret No. Elow No. Flow No. Flow 00. Ficw No. Flow l'^>VidCd E2 Sled F a r+- Cogle d Fate C oo le <1 Fate Cool;'s Eate Coglec L_it 1 E9EISL* l Il Excesc lettown test 330 9 Excharger 4 1 330 (5) 130 (5) 330 (L) 030 (5)  !

Fcactor coolant drain collecticr. tank te at (:; 225

<xetange 1 1 225 1 .;5 (!) 225 1 22' l' 4

FEaCtCr Coolant punp nctor air cooler 6 9 leC0 4 losJ 6 1600 6 16 ;s d 1'

,719 17,03d 35,071 3 4 , t. ; 0 33,7f' 9 etal 13,360 - (7) le,33d 17,610 1',37.

Octal (t) 25,080 17,33t 25,114 23,til 2;,743 Oct al (2 )

1;e rdTE tt 3

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GIPESSAR

'a ABLE 9.2-7 I (Sheet 4 of 6)

CCMPCNENT 'CCLING EATER ICTAL FLCW FATES (gpm) l (Westinghouse - 414) 1 Safety Injection Safety Injection I.oss of Power Phase A Isolation Ebate P Isolatigg gecirculati2D Ho* ShutdowD C2oldown at 29_tIst han No. Flow No. Flow No. Flow No. Flow No. Flow Comreneaj; gooled gag Cooled pate Cooled Pate E221e$ M2 C221ed EM

1. Essential Cooling Loop CCE pump cooler 4 144 4 144 4 144 4 144 4 144 FER teat exchanger - - - -

(6) 16,800 - -

2 18,000 I containment spray f purp cooler .2 160 2 160 2 160 2 160 2 160 1 FEP/lHSI pump 8 cooler 2 12 2 12 2 12 2 12 2 12 9

Auxiliary feedwater pumF cooler 2 60 2 60 2 60 2 60 2 60 i Centrifugal charging pump cooler 2 110 2 110 - -

2 110 (5) 110 l 9 Safeguard chilled lt sater system 1 1000 1 1000 1 1000 1 1000 1 1000 l 9 Spent fuel pool I heat exchanger 1 5150 - - - -

1 5150 . 515" Amendment 9

G A F ESS AF 1

TAPLE 9.2-7 (Stoet 5 of 6) ccMPCSENT C00 LING hATEF TCTAL FLCW RATES (gps) l9 (kestingnouse - 414)

Safety Injection Sa f ety Injection toss of Power _ ..

Phasa A Isolation PhaFe P Isolation Eecirculatign For St;utdosp Cooldowg a$,lj_tigg y Mdx

50. Flow No. FAow No. Floh No. Flow No. Flcw Component Cycled Pate cooled Pate Egglgd Pate Coolgj Patt E2olgd Egge
2. bonessential cooling loop Yvaporator concentrates 6 2 8 2 8 - - - -

2 storage tank Instrument and service - - 1 20 1 20 air aftercoolers 1 20 - -

4 75 - - - -

1 75 1 75 service air aftercooler and 1 corpressor 1 ( 3) - - - -

(5) 98 (5) id Sample heat e xc hanger y

( 3) - ~ - -

1 28 1 .:

GFFC sample cooler -

Eoron recycle evapcrator 7c0 73J j )

package -

( 3) - - - -

(5) 1 Eigh activity waste l2 (3) - - - -

(5) 760 t 76; l}

evaporator package -

Low activity waste 10;;

1000 - - - - 1 1000 1 j 4 evaporator package 1 seal water heat exchanger -

(3) - - - -

1 37 2 1 272 l ji letdown beat exchanger -

( 3) - - - - 1 34J0 1 Sia I l'

-Padwaste hydrogen recontiner PEG -

(3) - - - -

(5) 20 (') 20 l}

haste gas compressor l~

(3) - - - -

(5) 100 (5) 133 l package }

3 2700 3 21;C Flant ventilation chillers 3 2700 -

(4) - -

Amend:ent i

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GIBBSSAR 1

TAELE 9.2-7 (Sheet 6 of 6)

CCMPCNENT COOLING E ATER TOTAL TLOW RATES (gpm) l9 (Westinghouse - 414)

Saf ety Injection Safety Injection kgss of Power Ehase A Isolation Phase B Isolation Eecirculati2D Max Fot shutdown Cooldown at 22.blia No. Flow No. Flow No. Flow No. Flow No. Flow G2ILE2DED1 Cooled Eatg Egglgd Edis Cooled Eate S921ed Eats Cooled

_ fait reactor coolant punts 4 864 - - - -

(5) 864 (5) 8641 9 Excess letdown heat exchanger -

(3) - - - - - -

(5) 320 l 9 Feactor coolant drain collection tank heat 1 exchanger -

(3) - - - -

1 225 1 225 Feactor coolant purp notor air cooler 8 1000 - - - -

0 1600 8 1600 Total 12,903 3,086 18,176 16,706 36,420 9

Total (*) 6,452 1,543 9,088 8,353 18,210 Total (2) 12,156 2,338 9,588 15,921 23,181 Notes:

1 (1) Total is the required flow per component cooling water pump with two trains in operation.

(2) Total is the required flow for one component cooling water pump assuming single failure criteria (one train in operation) .

(3) Assuming component cooling water is valved off on "S" signal.

(4) Flow terminated on HI-3 containment pressure ("p" signal) 9 (5) Cooling flow maintained to components not is service.

(6) Flow used in P-T Analysis.

Arendment 9

GIEESEAP TAELE 9.2-7 (Sheet 6a of6)

CC 4PCNENT COOLING %ATEF TCT AL FLCW F ATES (gpm) l9 (Westinghouse - 414)

(7) curing normal operation (1) pump is used to suprly both trains. l9 Amendment 9

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GIEESSAR TABLE 9.2-2 (Sheet 1 of 3)

CCMPONENT CCOLING EATEP SYSTEM EESIGN PARAMETEFS

1. SCES Feat Fxchancer Cuantity two Type Straight tube 6 shell Faximum heat transferred, Btu /hr 196.06 x 10 * (1) l9 spelLSide Tube Side Fluid component service water water Maximur. inlet temperature, F 160 100(3)

Faximum outlet temperatur=, F 120 (2) 147 Faxinum flow rate, gpm 25,114(4) 15,000(4) resign terperature, F 225 225 Cesign pressure, psig 150 150 Cesign code ASME III ASME III Safety Class 3 3 Seiseic Category I I Amendment 9

GIEBSSAE TAELE 9. 2-8 (Steet 2 of 3)

CCMPCNENT CCCLING bATEP SYSTEM CESIGN FAFAMETEFS 2* SCh5 E9EE2 Cuantity four Type horizontal, centrifugal Fluid pump CCW resign flow rate, gpm 26,000 l 9 resign head (TCH) , ft 240 tesign te.tperature, F 200 Motor size, Enp 2000 l1 Cesign code ASME III Safety Class 3 Seismic Category I Availatle NPSP 60 feet seal cooling water component cooling water Fump cooler flow rate, gpc 36 l9 Arendment 9 O O e

GIEESSAR TABLE 9.2-8 (Sheet 3 of 3)

COMPCNENT CCOLING WATEF SYSTEM DESIGN PAR AMETERS

3. SCWs Eurne Tank Guantity cne Capacity, gal e700 (total)

?350 (per partition)

Cesign temperature, F 225 Cesign Fressure, psig 25(5) l9 Cesign code ASME III Eafety Class 3 Seiscic Category I

1. This is the maximum expected heat load and is pontulated to occur during initial recirculation after a LOCA with only one 9 heat exchrager in operation after single failure.
2. This is the .iximum expected CCES outlet temperature and is postulated tc occur claring the first 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of recirculation after a LOCA. Cnder normal plant operation, the expected compo-nent cooling w ter temperature at the outlet of the heat exchanger is 65 F min. and 105 F max.
3. The table is based on the assumption that site water is available I9 at 100 F. However, the CCES is designed to accommodate a range of inlet service water temperatures.
4. This is the naximum expected flow rate during the . plant shutdown at 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when cooling flow is maintained to components g not in service, postulating a single failure.
5. Design of the tank partition allows for one section of tank filled with water while the other section is empty.

Amendment 9

GIBBSSAR b) Storage Areas for Ion Exchange Resins Inused ion exchange resins are not stored in areas which contain or expose safety related equipment.

c) Hazardous Chemicals Hazardous chemicals are addressed in the Utility / Applicant's SAR. 8 d) Materiala Containing Radioactivity Materials which collect and contain radioactivity such as spent ion exchange resins, charcoal filters, and HEPA filters are stored in closed metal tanks located in areas which are free of ignition sources. Due to their potential hazard these areas are separated and enclosed by 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire barriers.

9.5-23.1

GIP 9SSAR O

9.5.2 Communicat ion Systems 9.5.2.1 Design Panes Intraplant and plant-to-of f site communicat ion syntemn are provided among the plant buildinos, switchyard, and the public telephone system. Te le phone s , I.ublic addrenn nprakern, and handsets are conven ient ly located to permit ef fect ive communications between personne l durinq no rma l operation, maintenance periods, startup operatlon, shutdown, and refueling of the plant. A two-way portable radio system is also provided for use by the fire brigade and other operations rersonnel 9 required to achieve safe plant shutdown.

Sound-powered telephone systems , independent of all external power sources, are provided in critical areas as a backup to the public address systems. These diverse means of communication are physically independent to prevent loss of all systems as a result of a single failure. Diverse capabilities for plant-to-of f site emeroency conmunications with public safety agencies are 9 provided. An emergency alarm system is installed which 1 rovides a unique alarm signal to ensure personnel evacuation.

9.5.2.2 System Dcscription lll Detailed description and drawings will be provided in the Utility Applicant's SAP. The intraplant and plant-to-offsite communication systems consist of the following systems:

a. Public Address System The public address system provides separate channels f or paging and party lines to permit communication throuchout the entire plant including the main office and control room. The system also permits two-way communication between two or more locations vital to the operation of the olant and the safety of personnel.

The page-party line loudspeakers are powered by individ ua l i amplifiers and power to this system is supplied from a source which is available upon loss of of f site power. The voice-paging channel output is clearly audible above the highest expected 3 noise levels under both normal and accident conditions. Separate and independent party lines permit communications between handsets only, thereby making the page channel available to others.

Three party lines are supplied in addition to the page channel.

All three lines are available at each handset location (except inl 9 9.5-24 Amendment 9 llh

GIBBSSAR elevat <rs) . A page party line (with only one party line) handset station is installed in each elevator to permit communication in an emergency situation. Selection of a desired channel is 9 achieved by means of a multiposition switch provided as part of each handset station. Both the page channel and the party line channels, which are independent, may be used siguitaneously without interference.

9.5-24a Amendment 9

GIBDsSAF O

b. Intraplant Telephone System An independent private automatic branch exchange ( P APX) dial telephone system is used for uninterrupted privat e conunun i ca t ionn between plant areas that are routinely occupied. It a l no nerve n areas vital to plant operation, which may l'c occupied on a nonroutine basis during certain modes of plant operatlon, such as fuel building, control rod drive equipment area, hot nhutdown panel area, switchyard, and the intake structure of the service water system.

The PABX telephone system is int egrated with the public address nage-party system through an isolat ing device to ensure that a sinale failure in either one of these two systems does not affect safe and reliable operat ion of the other system. Power is supplied to the PABX telephone system from a source which is available upon loss of offsite power. Also, if the PABX telephone system's normal ac power supply is lost, a telephone station in the control room, the hot shutdown panel A and D rooms and in the security central alarm station remains operable by deriving its power f rom the public telephone system.

9 The PABX telephone system is connected to the public telephone system by trunk lines. $

c. Intraplant Sound-Powered Telephone System A sound-powered telephone system, independent of all other systems and external power sources, is provided in critical areas to serve two purposes: to provide communicat ions and servr as a backup to the public address page-party system, and to provide unint err upt ible communication channels for maintenance, calibration, testing, and refueling activities. All sound pcwered telephone cables are routed in conduit s reserv'd only f or that function.

This system consi sts of three subsystems as follows:

Subsystem On3: Maintenance Loops - Consists of a two channel hard-wired communication link between the control area and critical plant areas.

Subsystem Two: Pefueling Loops - Consists of a two-channel hard-wired communication linP between the the Control Poom area, fuel handling area, and reactor operating floor. This subsystem is primarily provided for refueling 9.5-25 Amendment 9

GIBBSSAR operation. One channel of the refueling loop will be used primarily for refueling opera-tions while the second channel will be used for maintenance, ca11raation, and testing pur-poses. Subsystems one and two share the same conduit system.

Subsystem Three: Emergency Loops - Consists of a two-channel hard-wired communication link between the hot shutd)wn panels and safety-related equipment areas. This system is primarily provided for commt.nications in the unlikely event that the Control Poom becomes inaccessible.

Each emergency loop channel is routed in its own conduit system. No other systems, sound powered or otherwise, share these conduits.

The headset jack stations are conveniently located on panels in the Control Poom and in critical areas.

Communication can be established between the Control Foom and any 9 local panel or between two local panels by suitably plugging the headsets into jack stations which are mounted either in the panel or nearby. This system provides standby communication capability and does not depend on external sources of power other than the human voice.

The number and location of sound-powered telephone system receptacles are adequate to bring the plant to a hot shutdown or a cold shutdown panel and other areas. from the Control Poom or from the hot shutdown The sound-powered telephone system can be used as a backup to the public address page-party system in the critical equipment areas of the plant. One independent howle r loop per unit is provided for sound-powered signaling purposes.

d. Intraplant Portable Radio Transmitter-Peceiver System Two separate communication channe[s of unique wavelengths for the operating personnel, maintenance personnel, and fire fighting squad are provided to enable two-way radio voice communication between the Control Foom and va rious plant buildings. The Control Room is equipped with the hand-held transmitter-receivers. Portable transmitter-receivers operating on either one or both channels are provided for use by operations, maintenance, and fire fighting pe rsonnel for communication between various areas of the plant, required to 9.5-25a Amendment 9

GIBBSSAR O

aciieve safe plant shutdown. This system does nor interfere with tie communications capability of the plant security force.

"o improve reception from various plant buildings, fixed

epeaters, coaxial slotted cables, or both, are installed as required in these buildings. The fixed repeaters are protected from exposure fire damage, to the greatest extent practicable.

The use of switchyard remote supervisory carrier current equipment is discussed in the Utility-Applicant's SAP. The portetle radio carrier frequencies will not interfere with such equipment.

The portable radio communication is designed so as not to affect the actuation of protective relays.

e. Offsite Communication Systems Two diverse method s of plant-to-offsite commtinication are provided:
1) Public telephone system 9
2) Two-Kay Padio System O

The intraplant telephone system is directly connected to the public telephone system; each plant telephone is available for of fsite communication.

A two-way radio transmitter-receiver system is also provided for emergency communication between plant and offsite public safety agencies. It can be operated from the control room, remote hot shutdown panel 3 and panel B rooms and from the quardhouse.

This two-way radio is described in the security plan.

Tre two-way radio system and telephone system are independent, and provide reliable plant-to-of fsite communication. A failure of one system does not result in complete loss of offsite communications.

f. Emergency Evacuation Alarm System The evacuation alarm is generated by a solid state multifrequency audio ascillator capable of producing five distinctive tones which can be heard over all plant paging zones via the public 9.5-25b Amendment 9 k

GIBBSSAR address page party system. One of the distinctive tones, which sa ti sfies the NRC Pegulatory Guide 8.5 requirements, is designated for the evacuation alarm signal.

The evacuation alarm system, including the multifrequency audio oscillator, is powered by a source available upon loss of offsite power and provides a unique alarm signal to ensure personnel evacuation in case of an emergency. The alarm is initiated by the Control Room operator in the event of a plantsite evacuation emergency.

9.5.2.3 Evaluation The following evaluation is intended to establish the adequacy and redundacy of the plant communication system design:

a. Intraplant Systems Each intraplant system, i.e., the public address page-party system, PABX telephone system, sound-powered telephone system, and portable radio transmitter-receiver system, is designed to 9

provide the required intraplant communications during and after accident conditions as well as for plant operation fire fighting and maintenance purposes. Failure of any one of the above syst ems does not result in a failure of any other system. The power supply for the PAEX telephone system is provided from the on-ESF bus. Upon loss of total ac power to the PAEX telephone system, a telephone in the control room, the hot shutdown panel A and B rooms and in the security central alarm station remains operable by deriving power from the public telephone system.

Power supply for the public address page-party system is provided from a source available upon loss of offsite power. The PABX telephone and public address systems are connected through an amp 1 'fier device which acts as an isolating device. This ensures that any single failure in any one of these two systems does not result in a failure of the other system. The public address page-party system handsets and speakers are conveniently located to cover all critical areas. Each area of the plant is served by a separate public address page party system cirucit to confine the system outage to the area the faulty circuit serves.

The sound-powered telephone system is independent of all external power sources and its headset jack stations are conveniently leca ted throughout the plant. This system can be employed as a tackup to the public address page-party system in critical equipment areas of the plant. In addition, redundant components 9.5-25c Amendment 9

GIBBSSAR O

and cabling in the sound-powered telephone system are separated to prevent failure of both systems beause of a single f ailure.

The intraplant portable radio transmitter-receiver system is powered by rechargeable batteries and has two redundant channels.

This system can be employed as a hackup to the public address paae-party and sound powered systems in case of emergency, or if a communication line or trunk is severed, as a result of an accident.

b. Plant-to-Offsite Systems There are two independent plant-to-offsite communication systems available for the use of Control Room ope rators. The availability of these systems during and after the accident 9 condition is enhanced by the fact that cach enters the plant via different means.

The public telephone lines (trunk lines) are connected to the plant PABX telephone system. This extends the use of public telephor e lines throughout the plant.

The plan -to-offsite two-way radio communication system can ce used as a backup to the public telephone system. This provides &

W communication between the plant operator and public safety agencies. The power to this system is provided from a source available upon loss of offsite power. Also, there is an inherent redundancy in this system since it has two separate communication channels.

9.5-25d Amendment 9 lll

GIBBSSAR 9

9. 5. 2. 4 Inspection and Test Pequirements At the completion of installation, all communication systems are inspected, tested, and adjusted (if required) to ensure proper l 1 coverage and audibility under the maximum plant noise levels during the various operating conditions, including the accident 9 condition.

Since the communication systems (except the sound-powered telephone and offsite two-way radio systems) are used on a daily basis, periodic testing is not required. Periodic testing of the sound-powered telephone and offsite two-way radio systems are ccheduled to ensure their operability. 9 Preoperat ional and periodic testing demonstrate that the frequencies used for portable radio communication do not affect the actuation of protective relays.

Periodic testing of the emeroency evacuation alarm signal is in accordance with ANSI N2.3-1967, Immediate Evacuation Signal for Use in Industrial Installations Where Radiation May Occur.

A stock of spare parts is kept on the site for those components of the various communications systems that can be readily 9 repaired by the plant personnel.

9.5.3 Lighting Systems 9.5.3.1 Normal Lighting System Normal lighting for the plant buildings is supplied by a grounded, 208/120-V, three phase, four-wire distribution system.

Dry-type transformers, rated at 480-208/120-V, are connected to 480-V non-safety related motor control centers throughout the plan t. These transformers supply independent lighting panels 9 which are conveniently located throughout the plant to permit ef fi cient distributicn of the lighting load. A 480-V distribution system is used for roadway lighting Emergency interior and "exte'rior lighting uses 9 208/120-V systeu, similar to the system described a l in the preceding paragraph, as well as a 480-V system for security lighting with connections to the non-safety-related 9 diesel gene rator.

e 9.5-26 Amendment 9

GIRPSSAP O

System design is equal to, or exceeds, the requirements of IFS Lighting Handbook (5th edition) . Illumination sources containing mercury, such as floutescent, me rcury vapor, met al halide or high pressure sodium lamps are not used in areas where they are restricted such as in the containment, waste procensino area, and portions of the fuel handling area, sa tequa rd s area, auxiliary area and turbine building; incandescent or quartz iodine type fixtures are provided in these areas. When necessary, means are provided in floor drains to preclude mercury 9 cont amination of the radioactive waste processino system. If mercury or iodine in a lamp becomes activated, it is disposed through the radioactive waste processing system.

9.5.3.2 Emergency Lighting System AC and de emergency, reduced level, lighting is provided in locations where saf ety-related f unctions are performed or where personnel safety is involved. These areas include:

a. Control room
b. Diesel generator rooms
c. Battery rooms
d. Hot shutdown panel location l9
e. Safety-relat ed equipment locations
f. Hazardous areas
g. Primary access routes to and from the oreceding areas, fire areas and primary exits The ac-emergency lighting system consists of certain lighting fixtures that are part of and are powered from the normal power system; in the event of loss of offsite power, only these ac-emeroency lighting fixtures are automatically connected to the 9 non- saf tey-related diesel genera tor. Power is available to these lights as soon as the diesel generator has achieved rated voltage and frequency and has been connected to the distribution system.

As a backup to the ac-emergency lighting system an independent de-emergency, low level lighting system is provided in critical plant areas. The de system, conslsting of central battery fed lights and individual battery pack units, is automatically and immediately energized upon loss of ac power and automatically 9.5-27 Amendment 9 jgg

GIBBSSAR deenergized upon restoration of ac power. The most crucia l areas, such as the control room, major remote shutdown areas and vital access routes between them have lights energized from the non-Class IF station battery. In addition, these areas, as well as all areas that must be manned for safe shutdown and the access and egress routes between them and between all fire areas incorporate fixed, self-contained lighting consisting of sealed-beam or, where not restricted fluorescent units, with individual eight-hour minimum battery power supplies. Safe shutdown areas include those required to be manned if the control room must be evacuated. When remote sealed beam heads are used they are located in the same fire area as the battery pack that energizes them. Each battery pack unit contains an individual battery and an integral automatic charger.

Exit lights are energized from the ac-emergency lighting system 9 with de-emergency lighting provided nearby. Phosphorescent, non-electric exit and directional signs are used where required.

Suitable sealed-beam, battery-powered portable hand lights are provided for emergency use by the fire brigade and other personnel required to achieve safe plant shutdown. These units and spare batteries are located at strategic locations throughout the plant. Security lighting is discussed in the plant sec urity plan.

9.5.3.3 Failure Analysis Since the de and ac lighting systems are independent, a failure in one system does not cuase the other system to cease functioning. A restraining cable is used on each lighting fixture near safety related equipment inside critical plant areas which could become falling objects.

9.5.3.4 Inspection and Testing 9

The ac and oc emergency lighting systems and battery packs are inspected and tested periodically to assure availability at all time s. A regular program of periodic battery replacement is followed to assure reliable operation or the fixed battery packs and portable hand lights. Sealed beam lamps are periodically cleaned to assure maximum output and sufficient replacements are stocked at all times in the plant.

9.5-27a Amendment 9

GIBBSSAR O

9.5.4 Emergency Diesel Generator Fuel Oil Storage and Transfer System The function of the emergency generator fuel oil storage and transfer system, shown in Figure 9.5-2, is to supply fuel oil to the emergency diesel generators. Table 9.5-1 lists the design paraneters of the components.

9.5.4.1 Design Bases The system is partially housed in seismic Category I structures and partially installed underground. It is protected from natural phenomena and external missiles. Components installed underground are designed to operate submerged. Protection from the effects of breaks in high- and moderate-energy piping is in accordance with BTP APCSB3-1 and MEP 3-1. The diesel oil storage tank pit and missile shield is shown in Figure 9. 5-3.

Underground components are protected from corrosien by a bitunastic coating similar to that specified in AWWA C203-66.

The principal components of the emergency diesel generator fuel oil system are one diesel engine fuel oil storage tank, one fuel oil transfer pump, and one f uel oil day tank for each emergency diesel generator.

g The emergency dieser generator fuel oil storage tanks are sized to store sufficient supply of diesel oil for 7 days continuous operation of its associated emergency diesel generator system under maximum rated load conditions. Pated load definition is in accordance with IEEE 308-74. Diesel fuel is transferred from the diesel engine fuel oil storage tank to the fuel oil day tank by the fuel oil transfer pump. Each pump discharge line contains a strainer to minimize the transfer of solids to the day tanks.

Both the storage tank and the day tank are separately vented to the atmosphere and equipped with flame arresters.

The fuel oil day tanks are designed in accordance with NFPA 37 and are sized to provide sufficient fuel to operate the diesel gene rator for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Each diesel generator fuel oil system is separate, and there are no shared subsystems or components. The system is designed in accordance with ASME BGPV Code, Eection III, Class 3, and seismic Category I. Applicable quality assurance standards are presented in subsection 3.2.2. Component design permits adequate inspection, cleaning, maintenance, and repa irs .

9.5-28 h

GIBBSSAR Essential portions of the system are housed within seismic Category I structures and are protected fron the effects of pipe whip or jet impingement brea ks.

from high- and moderate-energy pipe

d. Instrumentation for monitoring, the standby status and performance of the system is provided in the control room, as described in subsection 7. 3.1.1, g.
e. Emergency diesel generator air starting compressor is located inside the auxiliary building and is not aff ected by the design maximum flood, tornado or tornado missiles.

Emergency diesel generator air starting compressor, air receiver,l and design parameters are to be specified by a diesel 6

generator manufacturer.

Failure mode and effect analysis for the emergency diesel generator air starting system are shown in Table 9.5-5.

9.5.7 Diesel Engine Lubrication System Each diesel engine lubrication system is designed to provide adequate engine lubrication under all operating conditions, including full-load operation. The system is internal to the diesel engine. The flow diagram and the system design parameters will be presented by the diesel engine vendor.

The design bases and safety provisions for the diesel engine are:l 9

a. The lubrication of the diesel engine is performed adequately.
b. The redundant diesel engine lubrication systems are separated and do not share any components in accordance with the requirements of 10 CFP Part 50, Appendix A, General Design Criterion 5. 9
c. System abnormal operation is detected and alarmed in the control room. In case of malfunctioning, the operator can switch to the redundant diesel generator.
d. Diesel engine protection devices are bypassed in the event of emergency operation as discussed in Section 8. 3.1.1c. l 9 9.5-31 Amendment 9

GIPDSSAR O

9

e. Periodic tests, described in Chapter 16.0 are made rol ensure the quality of lubricating oil. I I
f. The diesel engine lubrication system is located inside the auxiliary building and is not affected by the design maximum flood, tornado or tornado missiles in accordance with the requirements of 10 CFR Part 50, Appendix A, General Design 9

Criteria 2 and 4. Failure of a non-seismic Category I structure or component will not affect the safety related function of the

system,
c. The diesel engine lubrication system is classified as ANSI Safety Class 3 and designed to seismic category I requirements. System components will be desiged to comply with the ASME ESPV Code, Section III, class 3. However, when a component is commercially unavailable as ASME Class 3 design, the component will be designed, fabricated, erected, and tested to quality standards connensurate with the safety function to be 9 performed.
h. The temperature of the oil is automatically maintained above a minimum value by means of an independent recirculation loop including its over pump and heater, to enhance the diesel and starting reliability in the standby condition. ggg 9.5.8 Diesel Generator Combustion Air Intake and Exhaust System The emergency diesel generator combustion air intake and exhaust syster cupplies combustion air of raliable quality and sufficient quantity to the diesel engines, and exhausts the products of combustion from the diesel engine to the atmosphere and is shown in Figure 9.5-6.

9.5.8.1 Design Bases

a. The redundant emergency diesel generator combustion air intake and exhaust systems are separated and do not share any components.
b. The essential portions of the system are housed in a seisnic Category I structure and are protected from flood, torn ado or tornado mis sile s. Components have sufficient separation or shielding to protect the system from missiles and ficm pipe whip and iet impingement caused by cracks or breaks in hia' - and moderate-energy piping.

9.5-32 Amendment 9 h

GIEESSAR

c. The Diesel Generator Air Intake and Exhaust System is classified as ANSI Safety Class 3 and designed to Scismic Category I requirements. System components will be designed to 9 comply with the ASME BSPV Code,Section III, Class 3. I?o w e v e r ,

when a component is commerically unavailable as ASMF Class 3 design, t he component will be of the highest commercia l quality available frcm the chosen manufacturer.

9.5.E.2 System Description The emergency diesel generator combustion air intake and exhaust system consists of an intake pipe that brings outside combustion air and an exhaust pipe that discharges combustion gases to the envi ror. ment . Poth intake and exhaust pipes are designed for maximum diesel generator ratings and for continuous operation.

9.5-32a Amendment 9

GIBBSSAR TABLE 10.3-2 IXEJCAL MATERI6LS USED_ FOR_ MAIN STEAM AND FEEDWATER SYSTEM COMPONENTS ComEonents and Material Piping Material _ Specification

  • Carbon Steel SA106 GR B SA333 Grade 6 SA672 Fittings, F_ lances and Connections Carbon Steel SA105 SA350 LF2 SA420 GRWPL6 valves Carbon Steel SA105 SA216 WCB 9

folting Studs SA193 GR B7 Nuts SA194 GR 2H Kelding Material Ferritic SFA 5.1 SFA 5.2 SFA 5.5 SFA 5.17 SFA 5.18 SFA 5.20 Ehen components are non-nuclear safety related and fabricated to ANSI B31.1, the corresponding ASTM "A" designation materials may be substituted for the ASME "SA" designations. Similiarly, the AWS "A" designation may be substituted for the corresponding ASME "SFA" welding materials designations.

Amendment 9

GIBBSSAR The auxiliary feedwater system also supplies auxiliary feedwater to the steam generators during other modes of plant operation such as the following:

a. The auxiliary feedwater system maintains the proper water level in the steam generators during cold startup operation. The pumps supply feedwater until sufficient steam can be generated to operate the main feedwater pump turbines.
b. When the reactor is maintained in the hot shutdown condition for an extended period of time, the small amount of feedwater flow necessary to maintain the steam generators water inventory may be switched from the main feedwater pumps to the auxiliary feedwater system.

10.4.9.2 System Description

a. General The auxiliary feedwater system flow diagram is shown in Figure 10.4-3. The system includes an adequate storage of feed quality water, and adequate pumping capacity to supply the steam generators, and system piping.

The system supplies water to the steam generators where it is converted into steam by the heat transferred from the primary coolant which removes decay heat from the reactor core. A portion of the generated steam is used in powering the auxiliary feedwater pump t urbine. The remaining steam is dumped to the condenser or released to the atmosphere through the power-operated relief valves or the main steam safety valves.

A safety class auxiliary feedwater storage tank provides storage of deaerated feed quality water for immediate use. This amount 6 of water is sufficient to maintain the plant for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at hotl 9 standby, then cool the primary system at an average rate of 50 Fl 6 per hour down to 350 F hot leg temperature and 400 psig in 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> at which time the RHR system is capable of operation. 9 A floating diaphragm arrangement in the tank prevents air leakage into the liquid. The stainless steel tank is not corroded by deaerated demineralized water.

One supply line from the auxiliary feedwater tank supplies two electric-motor-driven pumps and turbine-driven pump. Backup source is station service water under all conditions described in 6 Table 9.4-4. The alternate backup is the condensate storage 10.4-28 Amendment 9

GIBBSSAR O

tank. All pumps are located in the auxiliary building, which is 6 designed to reismic Category I requirements.

O 10.4-28a Amendment 6 h

GIBBSSAR TABLE 10.4-4 AUXILIARY FEEDWATER SYSTEM REQUIREMENTS (WESTINGHOUSE -414)

(Sheet 1 of 2 The interface requirements of RESAR-414 Section 6.6 are satisfied as follows:

a. An auxiliary FW system is provided to ensure a source of SG feedwater.
b. AFW is required during startup, shutdown, hot standby and emergency conditions. 6
c. The system is safety Class 2 and 3, Seismic Category I and meets the requirements of GDC 34. See Scction 10.4.9.1 par.

e.

d. Utili7ation of multitrain power sources is discussed in Section 10.4.9.3 and Table 10.4-2. System actuation logic is discussed in Chapter 7.
e. System design parameters such as flow, maximum allowable flow delivery time and temperature are complied with and listed in Table 10.4-3.
f. Sufficient source of auxiliary FW for hot standby is specified in Section 10.4.9.2 Provision for long terml redundant sources of water le described in Section 10.4.9.3. 9
g. The automatic actuation of pumps and subsequent isolation of the SG blowdown and sampling systems is discur.ded in Section 10.4.9.5.
h. The system functions within the SG pressure range defined by the pressure at operating conditions down to 100 psia. 6
1. Sufficient auxiliary feedwater is available under any accident conditions to enable the plant to be taken to a safe condition. It is provided as a backup to the normal feedwater system and as a means for removing core residual heat in the event of a LOCA for small breaks.
j. The AFW system provide the primary means of feedwater addition to the SG in the event the control room becomes W-414 Amendment 9 f

GIBBSSAR O

TABLE 10.4-4 AUXILIARY FEEDWATER SYSTEM REQUIREMENTS (WESTINGHOUSE -414)

(Sheet 2 of 2) inaccessible. Necessary instrumentation and controls are provided in the hot-shutdown panels.

6

k. Sufficient redundancy is provided in the 1FW system to supply the required flow, while subjected to a single active failure in the short term-less than 24 aours. The system is also available during long term periods when the main feedwater system is out of operation. In the later case the system is designed to sustain a single active or passive failure.
1. The volume of condensate quality water is 290,000 gallons to maintain the plant for (4) hours at hot standby followed by 9 cooldown at tverage rate of 50 deg F/hr for (5) hours.
m. Instrumentation requirements and conformance with GDC 19 are presented in Section 10.4.9.5.
n. The AFW system is not connected directly to the S.G. See Figure 10.4-3. However, all components and piping from the 6 g

Containment isolation valves to the steam generator feedwater nozzles are designed in accordance with ASME III, Class 2.

o. The primary and secondary control of the system is described in Section 10.4.9.5.

W-414 Amendment 9 h

GIBBSSAR 11.4 solid Waste MaDanement system 11.4.1 Cesign Bases The solid waste canagement system is designed to receive, solidify, package, and temporarily store evaporator concentratec, spent demineralizer resin, Ro system concentrates, spent filter cartridge assemblies, and chemical drain tank contents for transportation to, and disposal at, licensed radioactive waste burial sites. Equipment is also provided for conpacting and packaging low-radiation-level miscellaneous solid compressible wastes that result from riant operations and maintenance. The radicactive waste packages from this system conform by design to the requirement: af 10 /TR Parts 20, 50, and 71 and of United States DepartRent of Transportation (DCT) 49 CFR Parte 170-178.

Compliance with NRC, DCT, and state regulations is determined according to radioactivity measurenent and the amount of waste processed. If radioactive levels are too high, corrective action is taken either by permitting radioactive decay diluticn or by shielding. 9 The design objectives of the solid-waste ganagement syster include the following:

a. To provide a means of solidifying radioactive liquids and encapsulating or compacting radioactive solid wastes 2 generated by reactor plant operations
t. To provide adequate equipment and storage area shielding for the protection of operating personnel pending shipment of waste to disposal facilities
c. To measure and reccrd the radiation levels of the solid waste processed for shipment from the site to disposal facilities
d. To provide a 3- to 6-month storage capacity for the processed wastes depending upon plant operation 2 Sect ion 3.2 indicates the seismic design classification of the structure housing the solid-waste managerent system. The solid wastc management system is not safety-related and is classified as ncnnuclear cafety (NNS) .

Volunes and activity levels of the solid wastes are presented in'l9 Tablec 11.4-1 through 11.4-4. Isotopic inventories for all waste categories have not been presented. Compressible waste isotopic 2 inventories and miscellaneous dry wastes such as tools are not 11.4-1 Amendment 9

GIBBSSAR O

identifiable because of the uncertainty of transport mechanisms, absorption, and so forth, and therefore the total activity 2 expe :ted is based on operating plant experience is presented, however, the Utility / Applicant shall nake filter replacement on a shielding criteria of maximum contact dose rate.

The solid waste managenent system is designed in accordance with the criteria presented in Branch Technical Position ETSB11.3. 9 For information regarding the waste solidification portion of the solid waste tranagerrent system, refer to the U/A SAR.

O 11.4-1a Amendment 9 h

GIEBSSAR 2

11.4.2 System Description 11.4.2.1 General Figures 11.4-1 and 11.4-2 indicate major flow patlis and equipment l2 for the solid-waste processing system.

l9 Processes of the system are the following:

a. solidification Process The waste solidification package process descripticn is addressed 9 in the Utility Applicant's SAR 11.4-2 Amendment 9

GIBBSSAP O

DELETED 9

9

11. <,- 3 Amendment 9 h

GIBBSSAR 9

b. Kaste From Spent Resin The spent resin sluice portion of the solid waste processing system consists of a spent resin storage tank, sluice pump, and sluice filter. The equipment is arranged so that the resin sluice water, after entering a demineralizer vessel, is returned to the spent resin storage tank for reuse. The system is 2 designed to transport spent resin to the spent resin storage tank withcut generating large volumes of liquid waste. This is accomplished by reusing the sluice water for subsequent resin sluicing operations.
c. Expended Filter Cartridge Handling Expended filter cartridges are removed for disposal by means of a filter transfer cask. The transfer cask is shielded to reduce operating personnel exposure.
d. Compactor Operation The compaction process involves the use of standard 55 gallon drums. The compactor is equipped with a dust shroud to prevent escape of radioactive particulate during the compaction process.

The shroud is connected to the building exhaust system. After the drum has been filled with compacted waste, it is sealed and transferred to the storage area.

e. Miscellaneous Contaminated Component Pandling (2 Large contaminated equipment and components are handled on a case-by-case basis. Components are decontaminated, wrapped by a waterproof membrane, and crated for structural support and handling before being transported, by licensed carrier, to an offsite burial ground.

11.4.2.2 Component Descriptions 2

2able 11.4-5 lists Solid Naste Management System component paraneters 11.4-4 Amendment 9

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DELETED 2

O 11.4-5 Amendment 2 h

GIBBSSAR DELETEC 2

11.4-6 Amendment 2

GIBBSSAR O

11.4.2.3 Operating Procedures

a. Easte Solidification Operaticn Cperation of the waste solidification package is addressed in the' 9 Utility Applicant's SAF g O

11.4-7 Amendment 9

GIBBSSAP DELETED 9

11.4-8 Amendment 9

GIEBSSAR DELETED 9

0 11.4-9 Amendment 9

GIBESSAP 9

b. Spent Resin Handling This part of the waste trocessing system sluices resin from the demineralizers and transports resin from the spent resin storage tank to the waste solidification plant.
1) Resin Sluicing Before resin sluicing begins, the demineralizer is valved out of service and the flow path aligned from the resin sluice pump through the process line of the demineralizer, through the screen at the top of the demineralizer, and back to the spent resin storage tank. 2 The resin sluice pump provides flush water for loosening the bed for sluicing. After approximately 10 minutes of back-flushing, the pump is shut of f and the valve in the back-flush circuit is closed. The sluice line is opened, and the resin sluice pump is restarted. The resin then flows to the spent resin storage tank. After the resin sluice pump is shut off, fresh resin is added via the resin fill line and the valve is closed.

The flow path is now aligned in the same manner as for resin flushing, e.g., through the process line, through the screen at the top of the demineralizer, and back to the spent resin storage talk. The pump is then started to remove resin fines, thould any remain. The valves are then realigned for norma? process operation. At no time are the resins sluiced through the spent resin sluice pump.

2) Pesin Transfer To Solidification System Ehen sufficient spent resin has been accumulated in the spent resin storage tank, the valves in the line to the waste solidification package are opened and all other 1 9 valves are closed. The tank is then pressurized with nitrogen. The solidification package valves are then 2 opened and the resin is transferred. During transfer e nitrogen is forced through the spargers in the tank 9 11.4-10 Aaendment 9

GIBBSSAR botten to level the resin and maintain the tank pressure. Ehen transfer to the waste solidification package is completed, the 9

transfer valves are closed and the tank pressure is relieved to the plant vent. The transfer valves are then flushed.

c. Expended Filter Cartridge Assembly Processing Operation The filter transfer cask is used to renove and dispose of radioactive spent filter cartridge assemblies in the following manner:
1) To change the filter, it is first valved out of service, vented and drained.
2) The filter transfer cask is positioned alongside the filter conpartnent concrete shield plug. The shield plug is lifted and placed down beyond the work perimeter. 2
3) The filter housing bolts are disengaged, and the filter housing head is moved to allow removal of the expended filter cartridge assembly.
4) The filter transfer cask is moved until the centerline of the cask is aligned with the centerline of the expended filter cartridge assenbly.
5) The filter transfer cask shielded base is renoved and the hoist lowered to engage the cartridge assembly.
6) The grappled cartridge assenbly is then raised into the shield cavity, and the shield base secured to contain any liquid or particulate that may drip curing transit. l 11.4-10a Amendment 9

GIBBSSAR

7) A monorail is used to move the filter transfer cask to the hatchway, through which the cask is lowered to the filter loading area.
8) The filter transfer cask is lowered until it is positioned above a disposable container. l9
9) Khen centered above the container opening, the contained expended filter cartridge assembly is lowered into the disposable container. The filter transfer cask is then decontaminated by allowing the decontamination water to enter the container.
10) The container is then moved to the fill area for-solidification l9
d. Compactor Operation l2 The compactor is used to compress low-radiation-level solid waste such as paper, disposable clothing, rags, towels, floor coverings, shoecovers, plastics, and respirator filters into drums. Compressible solid wastes are placed into the drums manually. The drum is placed on the drum support plate located at the front of the compactor and is centered by adjustable drum-locating pins. Before starting the operation, a shroud door with door lock must encloae the drun and the compressing cylinder rod and plate.

The assembly incorporates a fail-safe switch that does not permit the compaction operation when the compactor door is open. An operator initiates the compaction process by positioning an up/down switch in the down position, which energizes the hydraulic pump motor. The hydraulic pressure forces the ram down into the drum, thereby compressing the wastes. The shroud door is opened, the drum is removed, and additional wastes are added to the drum. The cycle is repeated until the drum is full. The lid is then installed, the clamping ring tightened, and the drum is stored pending shipnent.

Partially contaminated air during conpactor operation is evacuated by an integral blower, which directs airflow through a HEPA filter with air efficiency of greater than 99 percent. The filter outlet is connected to the auxiliary cuilding ventilation exhaust system.

11.4-11 Amendment 9 t

GIBBSSAR g The compactor ' hydraulic press and exhaust fan' is operated fron an integrally trounted electric control panel.

9 O

i

11.4-12 Amendment 9 O

GIBBSSAR TABLE 11.4-5 (Sheet 1 of 10)

SOLID EASTE MANAGENENT SYSTEM 2

Component Paraneters Code Safety Component pegigg _ Class Parameter TANKS

1. Spent resin storage ASME VIII NNS 9 tank Number 1 Usable volune, ft3 350 Type Vert.

Design pressure, psig 100 2

Design temperature, F 200 Material SS*

Diaphrage No

  • All stainless steel in this table is either type 304 or 316.

Amendment 9

GIBBSSAB TABLE 11.4-5 (Sheet 2 of 10)

SOLIC liASTE MANAGEMENT SYSTEM 2

Con.panent Paraneters Code Safety p.ggj9D Class Parageter E9EE9DSDt

2. Evaporator concentrates ASME VIII NNS 9 storage tank Nunter 2 Usable volume, 2000 gal (each)

Type Vert.

2 Design pressure, psig 150 Design temperature, F 250 h Material SS Diaphragm No Amendment 9 g

GIBBSSAR TABLE 11.4-5 (Sheet 3 of 10)

SOLID WASTE MANAGEMENT SYSTEM Component Parameters Code Safety Component Design _ Class 2 Parameter

3. Chemical drain API 620 NNS tank Nunter 1 Usable volume, gal 600 Type Vert.

Design pressure Atmos.

Design temperature, F 200 Naterial SS Diaphragm No 1

9 w.

Amendment 9

GIBBSSAR h

2 TABLE 11.4-5 (Sheet 4 of 10)

SOLIC KASTE MANAGEMENT SYSTEM DELETED 9

0 Arrendnient 9

GIBBSSAP TABLE 11. I4-5 (Sheet 7 of 10)

SOLID KASTE MANAGEMENT SYS'IEM Component Parameters Code Safety

[omESD2D1

_ Desion Class Parametg

3. Evaporator concentrates Mfg Std NNS tank pump Nunter 1 2

'Iype Canned Design pressure, psig 150 Design tenperature, F 250 g Design flow, gpm Fecirculation Mode 100 Frocess Mode 35 Design head, ft Pecirculation Mode 250 Process Mode 200 Material SS Amendment 2

GIBBSSAB TABLE 11.4-5 2 (Sheet 8 of 10)

SOLIC HASTE MANAGEMENT SYSTEM DELETEC 9 h Amendment 9

GIBBSSAR TABLE 11.4-5 (Sheet 9 of 10)

SOLID WASTE MANAGEMENT SYSTEM 2

Component Parameters Code Safety Component De sign Class Parameter

4. Kaste solidification package Utility Applicant's SAR 9

Amendment 9

GIBBSSAR TABLE 11.4-5 (Sheet 10 of 10)

SOLID WASTE MANAGEMENT SYSTEM Component Parameters Code Safety Component Design _ Class Parameter FILTEFS Spent resin sluice ASME VIII NNS filter Nurther 1 2 Design pressure, psig 150 Design temperature, F 200 Design ficw, gym 150 P at design flow, psi 5 Size of particles, 98 percent ret., microns (nominal) 25 Surface radiation level, R/hr 100 Materials Eousing SS Filtel Element Epoxy impreg-nated

'~ '

cellulose fiber Amendment 2

GIBBSSAR

j. Give an alarm on high radiation level by using a high-high set point alarm
k. Control the release of radioactive liquids, gases, and particulates produced in the operation of the plant by initiating prompt corrective action through automatic isolation systems, or via operator response Continuous monitoring means that the monitor operates essentially uninterrupted for extended periods. However, this does not mean that the monitors are maintenance free. Preventive maintenance is normally coordinated with plant shutdowns, and necessary maintenance or repair and calibration outages are minimized by equipment design. Consideration is gi ven to providing needed augmentation if conditions warrant.

The accomplishment of these general objectives by the continuously operating PERMS assists in maintaining for individuals in restricted and unrestricted areas, during both normal and accident conditions, exposure levels as low as reasonably achievable ( AL ARA) 11.5.2 System Description The RMS will be a current state-of-the-art system that has the PERMS and ARMS system integrated. The system will be dual dedicated microcomputers in communication with each other and a 9 distributed dedicated microprecessor for each system monitor.

11.5.2.1 Design Criteria The following criteria are used in the design of the RMS: l9

a. The system is of a digital rather than analog type. The digital system uses, adjacent to each detector element, microprocessors which preprocess the data and provide the capability of independent local readout when required. The hign-voltage supply is also located at this point. Such a system

~

allows computer handling of the data, and incorporates the most recent in solid-state processing equipment.

b. The digital system is subdivided into two groupings:
1) Monitors that serve as Reactor Coolant Pressure Boundary (RCPB) leak rate indicators; this group l 2 must be seismically qualified
2) Those not seismically qualified.

11.5-3 Amendment 9

GIBBSSAF The s eis tnically qualified channels are isolated f rom each other electrically with independent wiring to the central independent 9 pnysically separated consoles, so that each detector is unaffected by the operation of any other unit. Optical isolation at each detector provides channel independence.

O O

11.5-3a Araendment 9

GIBBSSAR

c. All monitors register full scale if exposed to radiation levels up to 100 times full-scale indication without foldover.
d. The PERMS readout and controls are located in the control room so that they will be convenient to the operator, enabling proper overview of plant conditions. Additional local indication and alarms, where necessary, are provided to alert operating personnel, e.g., waste processing system control panel.
e. Each monitor automatically provides the control room with a rea dout, a high alarm, a high-high clarm, and a failure / loss-of-background alarm as a minimum.

Each monitor's high alarm is set at a level determined by operating personnel to allow attention to be drawn to positive increases in activity.

The high-high release rates arealarm is plant within chosen to ensure that the instantaneous l 2 technical specifications. Tnese values are dependent upon the maximum anticipated flow rates.

The failure / loss-of-background alarm actuates if the monitor loses its power source, or if there isn't a normal background level as a result of signal circuit failure or other similar failures.

f. Alarm setpoints are under the administrative control of the plant manager, or his authorized delegate. l
g. The proper operation of each detector is checked as required with a check source that is built into each detector but controlled from the control room. These check sources show a reading of approximately 30 percent of full scale.
h. Backup monitors are provided by placing monitors in series in appropriate discharge paths, as described in this section and located as indicated by Table 11.5-1.
i. Diversity of monitor types and principles are used to the extent feasible to enhance system reliability.
j. The monitors are placed where they are readily accessible and where the background is determined to be the lowest for the area.
k. Adequate lead shielding is provided so that background radiation has reasonably minimal effect on detector capability to sense low activity levels. The minimum detectible concentration is deemed to be that count rate associated with the background

~

11.5-4 Amendment 2

GIBBSSAR h count rate plus two-times the background standard deviation.

Background is considered to be the larger of either 1 MR/bour of 1 meV gamma radiation, or the design maximum for the area, as given in Section 12.3.

1. Spare equipment is provided for those components requiring naintenance and natural replacement.
m. Equipment is placed indoors for protection from the effects of extreme winds, floods, tornadoes, or missiles, as aascribed in Chapter 3.
n. Environmental design conditions for the components, excluding detectors, are as follows:

II Ambient temperature range of -10 C to 50 C

2) Relative humidity of 30 percent to 100 percent (100 percent without visible water droplets)
3) Normal atmospheric pressure 15 psig g
q. Each analog channel has a minimum range of 5 decades. l9 11.5.2.2 Locations to be Monitored All normai and potential paths for release of radioactive material during normal reactor operation, including anticipated operational occurrences and accidents are being monitored as indicated by NRC Regulatory Guide 1.21. Based on this, monitors are provided for:
a. Process lines which may discharge radioactive fluids to the environs, in order to indicate and alarm when preestablished limits are reached or exceeded
b. Process lines which do not discharge directly to the environs, in order to indicate possible process system malfunctions, deteriorating performance, or failure by detecting increases in radioactivity levels e

11.5-5 Amendment 9

GIBBSSAR Section 11.5.2.5 lists the local locations of detectors: l2 Table 11.5-1 summarizes the detector information.

11.5.2.3 Anticipated Concentrations, Sensitivities, and Ranges The monitors use scintillation crystals (predominantly) or Geiger-Muller (G-M) tubes to detect either beta or gamma 11.5-Sa Amendment 9

GIBBSSAR radiatio n, or both over an energy range of at least 0.08 to 2.5 meV.

ANSI-N13.1, 1969 provides guidance on detector locations, sample line routes, and sampling of air streams.

The sensitivity and range of each detector, along with other pertinent factors such as preferred detector type, reference nuclide, and anticipated medium concentration are given in Table 11.5-1.

11. 5. 2. 4 Des cription of Liquid Process and Effluent Monitors, General Each channel of the system contains a completely integrated modular assembly.

When appropriate, in-line monitors are used. This provides complete monitoring of the Liquid as there is no possibility of improper sampling. consequently, pumps, which require maintenance, are not required, and auxiliary flow devices are unnecessary.

off-line monitors, when required because of temperature or other considerations allow for ease of chamber decontamination. If pressure differential cannot be used to assure proper off-line g flow, a quality pump is provided. A flow device is provided in W either case.

On-line (saddle or snowplow) type detectors may also be implemented. These have the same advantages as in-line monitors and, unlike off-line monitors since the existing piping is not altered, provide no additional flow blockages or sediment collection points. Their use is regulated by necessary sensitivity considerations.

Each in-line and off-line chamber as well as auxiliary piping is made of stainless steel of the necessary quality to conform to ASTM standards. In addition, all monitors, regardless of type, are capable of being decontaminated by rinsing in place.

11.5.2.5 Description of Liquid Process and Effluent Monitors, Specific The following paragraphs contain a brief description cf each of the liquid process and effluent monitors.

a. Auxiliary Steam condensate Monitor 11.5-6

GIBBSSAR 12.3.3.2 System Design Criteria Ihe atmosphere cleanup units remove contaminants from the exhaust air of the primary plant ventilation system (which includes the controlled-access exhaust, containment-purge exhaust, and f uel-handling building exhaust ventilation systems) , and from the hydrogen purge exhaust system.

These systens are described in Sections 9.4, 6.2, and 6.5. In addition to the use of the atmosphere cleanup units described previously, the emergency filtration units and emergency pressurization units of the control room HVAC system remove contaminants from the control room environment and prevent contaminants from entering the control room atmosphere during emergency modes of operation. The control room HVAC system is discussed in Sections 9.4.1 and 6.4.2 12.3.3.3 Component Design Criteria The components comprising the non-ESF atmosphare cleanup units are prefilter, HEPA filters (two) , iodine adsorbers, fans, isolation valves, and related instrumentation. Atmosphere cleanup units are comprised of the above components, with the addition of demister and heaters to maintain the relative humidity below 70 percent.

12.3.3.4 Testing, Isolation, and Decontamination Eacn atmosphere cleanup unit housing has permanent test connections for DOP (dioctyl phthalate) leak testing of the HEPA filters and refrigerant leak testing of the adsorber section.

Leak testing is performed semiannually on all units.

addition, a deluge system is provided to extinguish an adsorber In section fire if a charcoal adsorber is used. The operation of the deluge system is discussed in Section 9.5. Inspection and testing requirements for ESF and non-ESF filter housings are disc ussed in subsection 9. 4.1. 4. .The arrangement of these units allows access to the unit and equipment by personnel for maintenance and testing. All housings have multiple drains which are connected to the equipment and floor drainage system.

Decontamination water stations are in proximity to each unit to facilitate decontamination. Figures 6.5-1 and 9.4-17 illustrate typical layouts for ESP and non-ESF atmospheric cleanup units, respectively.

12.3-17

GIBBSSAR h 12.3.3.5 Maintenance All housings are designed to provide ample room fot maintenance of equipment and filters and to minimize the radiation exposure l 1 to personnel during filter replacement. The criteria for replacement of filters are established on the basis of maximum allowable resistance of the dirty filter or minimum radiation exposure to personnel, or both. Each Silter train is provided with a pressure indicator. High pressure actuates an alarm in tne control room. Each filter of the filter train is provided with a local pressure indicator. Upon reaching the maximum resistance, the filters are replaced. The maximum allowable resistance f or each type of filter is indicated in Table 9.4-4.

The criteria for replacement of the adsorber section is based on the deterioration of adsorber ability to remove radioactive iodine from the exhaust air. This efficiency is determined by laooratory testing of representative samples of the activated charcoal exposed simultaneously to the same service conditions as the adsorber section. Each sample has the same qualification and batch test characteristics as the system adsorber. Samples are tested periodically (approximately semiannually) in accordance g with Regulatory Position C6.b of Regulatory Guide 1.52. The W adsorber section is replaced after the last sample has been removed and tested, or if one of the samples fails to meet the requirements of NRC Regulatory Guide 1.52, Table 2.

12.3.3.6 Conformance to Regulatory Guide 1.52 The ESF and non-ESF atmosphere cleanup units conform to the regulatory positions and recommendations of Regulatory Guide 1.52 as shown in Table 6.5-1.

12.3.4 Ar e a Radiation and Airborne Radicactivity Monitoring Instrumentation The ABM system is part of a,n integrated system of the RMS 9

including the airborne radioactivity monitoring instrtmentation of the PERMS. This RM system is described in Section 11.5 i 12.3.4.1 Area Radiation Monitoring System Fixed, gamma-sensitive monitors are located throughout the plant for the protection of personnel. The following criteria govern monitor locations and design aad performance requirements:

a. Location Criteria 0

12.3-18 Amendment 9

GIBBSSAR Detectors are located in spaces that may be occupied and where there is potential for dose rates in excess of the radiation zone 12.3-18a Amendment 9

Cuestion 111.55 (3.6.2.1)

Section 3.6.2.1.2 (page 3.6-6) of the SSAR adopts Branch Technical Position MEB 3-1 as the basis for determining post ulated pipe break locations in high energy piping systems outside containment. An element of this BTP (position B. I.b) is the establishment of criteria for piping in the containment penetration area where pipe breaks need not be postulated.

Unfortunately, all the criteria are not ccatained in the BIP.

Therefore, commitment to the BTP is not sufficient, in and of itself, if pipe breaks are not to be postulated in the containment penetration area. 9 Therefo re, it will be necessary to expand section 3.6.2.1.2 of the SSAR to indicate that either:

(1) Pipe breaks will be postulated in the contairaent penetration area using the criteria of positions B.1.c and B.1.d; or (2) In addition to neeting the criteria of position B.1.b, all piping in the containment penetration area will have a 100 percent volumetric examination of all circumferential and longitudinal welds during each inspection interval (IWA-2400 of Section XI of the ASME Code.)

Fesponse 0111.55 (3.6.2.1)

See revised Section 3.6.2.1.2.a.

Q 111-61 Amendment 9

9999t.19 n 11111i6 t31k1111L The third paragraph of Section 3.6.1.1.a. (page 3.6.2) of the SSAR references portions of Section 3.6.2.1.2 which have been deleted. Fevise this paragraph to reference B1P MEB 3-1 9 directly.

ECBD9D22 lll_._56 13.6 111 1L See revised Section 3.6,1.1.a.

O Q 111-62 Amendment 9

GIBBSSAR Ques _ tion 122.7 Confirm that when ASTM material specifications are used foL' safety related components, the quality, control provisions of the ASME Code,Section III NA-3700 will apply.

89EDgnse 122 2 ] 9 ASME Section III, Subsection NCA-3800 (summer 1977) supersedes subsection NA-3700 (1977). The quality control provisions of ASME Section III, Subsection NCA-3800 will apply to all ASTM material specifications used for safety related pressure retaining components.

,c.

Q122-8 Amendent 9

GIBBSSAR puestion 122.8 Confirm that the new fracture toughness provisions of the Code, NC/ND-2300 will apply to steam and feedwater system materials.

List the steam and feedwater system materials as was done for ESF materials in GIBBSSAR Table 6.1.1. 9 ESSD9Dae 12228 The fracture toughness provisions of the Code NC/ED-2300 (summer 1978 Addenda) will apply to all pressure retaining material and mate rial welded thereto, in the main steam and to-dwater system.

A list of main steam and feedwater system materials are provided in GIBBSSAR Table 10.3-2.

O 0122-9 Amendent 9 O

GIBBSSAR D999t19D 12119 While GIBBSSAP (5. 2. 3 . 3) addresses Pequlatory Guides 1.50, 1.43, 1.34, 1.71 and 1.66 with regard to ferritic and low alloy steels of the reactor coolant precsure boundary within the scope of the 9 POP, we are unable to determine from the reactor coola nt system descriptions where these materials will be applied.

ESSPOPSe- 12229 A review of the reactor coolant system descriptions indicates there are no ferritic and low alloy steels of the reactor coolant pressure boundary which are within the scope of the BOP.

0122-10 Amendent 9

GIBBSSAR guesMon_B 2 3 10 Confirm that all stainless steel components subject to the provision of Regulatory Guide 1.44, Position C.3, will be in the solution annealed and water quenched condition.

Eespgnse 122 2 10 GCH's position concerning stainless steel components subject to the provision of Pegulatory Guide 1.44, Position C.3, requires that annealed and quenched materials be used and that the 9 material is not unduly sensitized during manufacture and installation, and that the material is protected against contaminants which would aid in causing cracks. Position C.3 of the Pegulatory Guide 1.44 requires testing to verify the nonsensitization of austenitic stainless steel forms other than

" plate sheets, bass, pipes and tubes". GSH also excludes from sensitization testing, those forgings, fittinas and other shaped prod ucts , which do not have inaccessible cavities or chambers which would preclude rapid cooling when water quenched, as denoted in GIBBSSAF S6ction 5.2.3.4. '

O Q122-ll Amendent 9 O

GIBBSSAR t

guestion 122.J1 ASMF Code Section III, Subsection NE 2331 requires that fracture toughness requirements be met at 30 F below the " lowest metal service temperature." What is the " lowest metal service temperature" for the GIBBSSAF containment materials subject to this requirements?

Pe spgnse_ _12 2.11 The " lowest metal service temperature" for the GIBBSSAR containment materials subiect to the fracture toughness requirements of ASME Code Section III, Subsection NE 2331 will not be lower than 60 F. The assumption upon which the 9 calculation of this temperatur a is based are as follows:

The plant is at the end of a re fueling outage

=

The reactor coolant pumps are not in operation The containment purge system is in operation

  • The outdoor ambient temperature is sustained at -40 F e

The outdoor wind velocity is 15 mph Also refer to subsection 9.4.6.1.e for a dis cussion of the operation of the containment purge system.

Q122-12 Amendent 9

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GISBSSAR- stow citaPru NSSS: CO f CA!WENT SPR AY NOT SPECIFIC O SYSTEM W - 414 E CE O

, ,. , , aa. O , FIGURE NO. e.2-25 -

q ., i ., ., s ,  ; ,

t ,

i  ;-

\

l MEGNING 0F IDENTIFJCATION L FIRST LETTER SU MERSURED OR INITIATED VARIABLE READO A ANALYSIS ALARM B BISTABLE C CONDUCTIVITY CONTROL 0 DENSITY OR SPECIFIC GRAVITT DIGITAL C0F E VOLTAGE OR EMF PRIMARY elf.

F FLOW _

G GAGING GLASS H HAND I CURRENT INDICAT03 J POWER K TIME OR TIME SCHEDULE CONTROL STA L LEVEL LIGHT M MOISTURE OR HUMIDlfi 0 ORIFICf. [iRE P PRESSURE OR VACUUM POINT 0 PCHER SUPPL R RADI0 ACTIVITY RECORD OR P S SPEED OR FREQUENCY SWITCH T TEMPERATURE TRANSMITTER U MULTIVARIABLE MULTIFUNCTI V VISCOSITY VALVE DAMPE H MONITOR HELL X TRIP UNCLASSIFIE Y STATUS SIGNAL MODI Z POSITION

?

i TTERS INSTRUMENTATION SYMBOLS k CEEDING LETTER DET. SYM. DESCRIPTION T OR PASSIVE FUNCTION 1 LOCALLY MOUNTED UTER OR DIFFERENTIAL ENT 2 MAIN BOARD MOUNTED 3

h AUXILIARY BOARD MOUNTED x SPECIFIED ION x BOARD DESIGNATION RACK MOUNTED TRICTION) y R--- SPECIFIC RACK R DESIGNATION OR QUANTITY INT AUXILIARY CONTROL 5 FUNCTION DESIGNATION N

OR LOUVER

. RELAY OR COMPUTE GIBBSSAR INSTRUMENTATION AND usss, o CONTROL SYSTEM Zy'iseeciric ! LOGIC DIAGRAM B&H OfFIGURENO. 7.3-1 SM.A

VALVE OPERATOR TYPES VALVE ACCESS DEF]NITIONS & ABB t DET. SYM. DESCRIPTION SYM.

. O LSO 1

)( AIR DIAPHRAGM ggg LSC H

2 )( ELECTRIC MOTOR S

-~

3 )( SOLEN 0ID __

FAI----FAIL NO-----NORMA NC-----NORMA 4 )( PISTON G

MANUAL GEAR 5 )( OPERATED

/

/

6 )(' SELF-CONTAINED PRESSURE REGULATOR 7 ( THROTTLING SERVICE

IES v1ATIONS DESCRIPTION VA_VE 30JY ~T3ES ,

LM NORMALLY CLOSED VALVE F' (TYPICAL)

LIMIT SHITCHES LS0-OPEN X GATE VALVE LSC-CLOSED LSI-INTERMEDIATE - -M GLOBE VALVE X V NEEDLE VALVE THREE HAY VALVE r

IS N

-+

CHECK VALVE Y OP N 9 ED DIRPHRAGM VALVE g_ BALL VALVE rx STOP CHECK VALVE ANGLE VALVE y DAMPER GIBBSSAR INSTRUMENTATION AND NSSS: O CONTROL SYSTEM RSecciric

  • LOGIC DIMMM -

Ya w 0 FIGURE NO. 7.3-1 SH.B

LOGIC SYMBOLS i DET. SYH. DESCRIPTION A

~

B X LOGIC OUTPUT X EXISTS IF 1 - *- AND ONLY IF ALL LOGIC C

- AND INPUTS A_.B.C. EXIST.

= LOGIC OUTPUT X EXISTS IF 2

C

==

[)X OR

._ AND ONLY IF ONE OR MORE LOGIC INPUTS A.B.C. EXIST.

LOGIC OUTPUT X EXISTS IF

" X AND ONLY IF LOGIC INPUT 3 -

}{

A.DOES NOT EXIST.

NOT S REPRESENTS " SET MEMORY" R REPRESENTS " RESET MEMORT A X q ,_ g -- MAINTRINED LOGIC OUTPUT X_ EXISTS AS S B *

= R -- MEMORY AS LOGIC INPUT B_ EXISTS.

X. CONTINUES TO EXIST REGAR SUBSEQUENT STATE OF A_UNTI MEMORY IS RESET (TERMINATE LOGIC INPUT B_ EXISTING LOGIC OUTPUT Y IF USED EXI X.DOES NOT EXIST AND Y DOE HMEN X_ EXISTS.

NOTE:

x OUTPUT Y~ IS NOT SH0HN IF IT IS NOT 'ISED.

o

DET. SYM. DESCRIPTION f s

(---) SHALL BE CODE LETTERS S - -_ ADJUSTABLE AS DEFINED BELOW FOR MODE OF TIME DELAY TIMER OPERAT]ON.

TD I---I !t ) 1S THE NORMAL DELAY (t 1 TIME WITH APPROPR] ATE UNITS (SEC , , H] N. . HR. ) .

A X ADJUSTABLE PU - PICK-UP 6 - - --TIME DELAY ,THE CONT]NUOUS EXISTANCE OF TD PICK-UP LOGIC ]NPUT A FOR A TIME PU (t ) CAUSES X TO EXIST HHEN (t ) (t_) EXPIRES.X_ TERMINATES WHEN.A_ TERM] NATES.

ADJUSTABLE 00 - DROP-0UT 7 -

-TIME DELAY THE INITIATION OF A__CAUSES TD DRO?-0UT X TO EXIST IMMEDIATELT.

X TERMINATES WHEN (t)

) EXPlRES AFTER A TERMINATES.

ON NOTE:

LESS OF THE OTHER MODES OF TlHER OPERATION T SHALL BE HANDLED BT APPROPRIATE EXPLANATORY NOTES.

TS WHEN NOT EXIST GIBBSSAR INSTRUMENTATION AND CONTROL SYSTEM '

Ejecciric LOGIC DIAGRAM Yaw l

D FIGURE NO. 7.3-1 SH.C

p_.

( I. LOGIC & LOOP DIAGRAM SYM

( DET. SYH. DESCRIPTION I b- CONTROL SWITCH LOGIC INPUT FROM EXTER 2 XX: REFERENCE DESCR XX 0F THE COMPONEN YY-Y: THE DRAWING NUM THE SIGNAL IS C LOGIC OUTPUT USED AS 1 EXTERNAL LOGIC.

3 -- ff_y XX: REFERENCE DESCRI 0F THE COMPONEN YY-Y: SYSTEM DRAWING SHEET NUMBER WH THE SIGNAL IS G LOGIC INPUT FROM INTER (FROM PROCESS DWG.T0 L 4

Q U

~~

X-REFERENCE NUMBER NOTE:

IF R LETTER APPEARS AF THEN THERE IS ANOTHER FROM THE SAME LOOP.

S -

- -(X ) LOGIC OUTPUT TO INTERN o

X

OLS DET. SYH. DESCRIPTION 6 - - - - * - -

LOGIC OUTPUT L REFERENCE TION R FROM WHERE ING.

ACTION RESULTING 7 FROM A LOGIC OUTPUT.

Vi TO AN TION 8 START + AUTO ~STOP CONTROL SWITCH,3 POSITION, MBER AND S NG URN TO M 0 E MAINTA]NED POSITION OF ALL NG. CONTROL SW1TCHES INDICATED BY LINE UNDER THE POSITION

]N WHICH SWITCH IS MAINTAINED.

C DW 9 HSD DEVICE LOCATED AT HOT SHUT DOWN PANEL.

R A NUMBER 10 TRANSFER OF CONTROL FERENCE U SW1TCH LOCATED AT HOT SHUT DOWN PANEL.

11 "S" SIGNAL REFER TO RESAR-tilti REFERENCE PHASE A ISOLATION FlG.7.2-1 SIGNAL PHASE B ISOLATION SIGNAL F.W. ISOLATION SIGNAL H.S. ISOLATION SIGNAL GIBBSSAR INSTRUMENTATION AND CONTROL SYSTEM -

Ejecciric LOGIC DIAGRAM Es w l

0 FIGURE NO. 7.3-1 SH.D

HS-A STA k HS-B REM HS-C STA HS-D PUMP al h -.-

HS-B REMOTE HS-E PUMP mi HS-B LOCAL lPS-DPUHPm2 h --.-

ns HS-B REMOTE g3

\

HS-E PUMP m2 g5 HS-B LOCAL g3 HS HS PUNP m2  % ~

TRIP /

CCW TRAIN B LOW HEADER \ 1 PRESS.

[

SW TRAIN 8 LOW HEADER \ + = O V

PRESS.

[ 3 =

=

S- SicnAt \ _

/

. , 8'giyn' , SERVICE WATER I PUMP NO. 1 I CONTROL LOGIC

b + 1 G _~

~

p V }

IM WATER L -

START

^

STOP

'n)k M

9 STOP h d h

PULLEO OUT h .

\

REMOTE --

'HSD STOP h V /

PULLED OUT LOCAL ) i LM / OPERATOR MANUAL CONTROLS

-D PUMP al PUMP =2 HS-B LOCAL REMOTE HS-R ST ART -4UTO ~STOP PULLED OUT HS-C START STOP AMENDHENT 9 GIBBSSAR INSTRUMENTATION NSSS: O CONTROL SYSTEM AND{

"?!,secciric8 LOGIC DIAGRAM -

[4 w a FIGURE NO. 7.3-1 SM.I

I t

HS- OPEN ) =

Z=

PHASE A ISOLAT10N SIGNAL

=

=

HS- R1110_. ) =

r u

HS- CLOSE ) =

l NOTES:

1. CONTROL LOGIC SH0HN FOR HV-SH007. CONTROL LOGIC FOR HV-SH008 THRU HV-SH010 SIMILAR.

, SERVICE WATER NO ISOLATION VALVES

I

= VALVE OPENS S = $$!!00fh j

=- R VALVE OL 00 VALVE CLOSE VALVE j ~

OPERATOR MANUAL CONTROLS HS- CLOSE +RUTO -0 PEN AMENDHENT 9 GIBBSSAR INSTRUMENTATION AND ESSENTIAL LOOP NSSS: O CONTROL SYSTEM ,

CONTROL LOGIC "$f"" 8 LOGIC DIAGRAM .

Ya w a FIGURE NO. 7.3-1 SH.1A '

t e i e e$

I r- + T O S H 5 $f g -

\ PUMP =2 z. so g L.

S/A S \ U=E UIn a SU ns C

h E E%5 55 f, =

I i i i MSO HSD PUMP l

I M 5Dd _ _ _ _ _ 4_ _ _ _4 _ _ __4 _ _ _ L _ __

e

' ~

S/R/S A '

N 'A

\j -

A _j !!h?'

PUMP = 1 PUMP SELECT I F- T--1 TO SER ICE db0 HRTER PUMP = 2 Q FROM'b WATER NOTE:

1. S] HILAR FOR LOOP B SERVIC

\

d 5

~

5 5

E E 2 2 -

~ m TO D,RRlN g E w e m o '

E S*E S"E s E EIE EIE T5

$ EEE NEE T Eb J

l i l MI i Vl p--!

y k-l l FRI H I

L _

l 9 __ J l k gy I

.s_

H r- g ~ ,

' l '/ l CONTD.

Al i , g

/I

'/ l SHEET 7.3-1 SH.1C s

ny X 'sTaitrnR" X Pls RVICE UMP =2 o

'A G

AMENDHENT 9 WATER SYSTEM GIBB5SAR INSTRUMENTATION AND (LOOP Al NSSS: O CONTROL SYSTEM

"%secciricj DIAGRAM

[4 w o FIGURE NO. 7.3-1 SH.lB. .

\

t h1 Ti

(

' 'ENERGENCY DIESEL ' '

/ GENERATOR PACKAGE SEE NOTE 1 L _J FROM FIG. 3 r - -- - -1 7.3.-1 SH. lB ' I 1 I HV 7g I 3 I I

/

I

/

H

\FAI h

T un

[h TO CVCS V 4 V l ('

l EET = 10 ~

'CCW HEA 0 0 EXCHANGER h$[!b!N$

TOLOObB' NOTE:

1. THE EMERGENCY DIESEL GENERATORS AND CVCS CHILLER UN]T WILL BE COOLED BY THE SERVICE WATER S1 STEM.

ON THOSE SITES WHERE WATER QUALITY IS UNACCEPTABLE FOR THIS PURPOSE CCW WILL BE USED INSTEAD

2. SIMILAR FOR LOOP"B" c SERVI l

/

h I

~~

FE FT J

U FAI CH ,___, H +--

1 A A AAA' AAA Y__Y Y Y Y' NsbnIs 4

V L _ _ _l I

l_.d I

I I

__J l

I I I I I FE I I I I h y l TS TE PT RE l

A0 SERVICE WATER l

  • F0 nkYa!"s A n ...

s0EE D AMENDMENT 9 WATER SYSTEM GIBBSSAR INSTRUMENTATION AND

[ LOOP A) NSSS: O CONTROL SYSTEM

" MPEGnc DIAGRAM r

[4 w a FIGURE NO. 7.3-1 SH.1C. (

$ FR0H LOOP A I

NU_

007 j PHASE A 4--- ISOLATION l SIGNAL F.C.

_1 18

./

PI n_\_

)( r ------i, I I I I p

i I _I _f7's l_ l l l s j l l I I I l t_i_______i__

,\_ CVCS CHILLER UNIT s!

H 008 SEE NOTE i

_ PHASE A k __ _ _ ISOLAT10N S]GNRL

. U FROH LOOP B.

y SERVICE

TO LOOP A "l_ ^

V I V I V I

$S0[AT$0N I i _ f_ sicNAL 4.___ J f,C, J l

V x f' x X"

! c 7

I I

d HV u oYo

~

F.C. ,

~

PHASE A sis S "

M t

V TO LOOP B RMENDMENT 9 WATER SYSTEM ,

GIBBSSAR INSTRUMENTATION ANDr usss, a CONTROL SYSTEM

" LSPECIFIC D1AGRAM CE o aaw a FIGURE NO. 7.3-1 SH.10.

Y l

HS-A STRRT h

(' HS-B REMOTE HS-C S1RRT h HS-D PUMP mi h MS-B REMOTE HS-E PUMP n1 HSD HS-B LOCAL

\

L __ , / ZA HS-D PUMP m2 h ^, gg xHSD HS-B REMOTE y 5 g3 HS-E PdMP m2 HS HS-B LOCAL 7

H "-

L_-

HS

=

\ PUMP m2 TRIP

\ 5

/

~

CCW TRAIN B LOW HEADER \ w' PRESS.

/

SW TARIN B LOH HEADER \ r-r G V

PRESS.

[ 3 <

=

r "S" SIGNAL \ ~

/

B'l igg l

/

\ = COMPONENT COOLING WATER PUMP #1

CONTROL LOGIC

I COMPONENT

-*- COOLING HATER

+

._ _ PCMP =1 I

START

+

+ STOP -

1sk M

x" STOP h h

M PULLED OUT .

REMOTE

)HSD

~

v i -

STOP ) =

~

LOCTL_ '

)HSD I i

\

' =

OPERATOR MANUAL CONTROLS PUMP al, PUMP =2 HS-B LOCAL REMOTE MS-A START W UTO STOP PULLEO OUT HS-C START STOP AMENDMENT 9 GIBBSSAR INSTRUMENTATION AND NSSS: O CONTROL SYSTEM Z3secciric 8 LOGIC DIAGRAM CE O eaw O FIGURE NO. 7.3-1 SM.2 (

\

s FROM SH. 28 1

--q F.O.

TO CCHS SURGE l

'4 h

TANK .

~~

FV TO CHEMICAL ' A2 l '

F' I ADDITION TANK

/- l l

G TO CCW HEAT l  ;  ; y /

EXCHANGER - {. 0 .  :

en e- e TO CCH PUMP = 2 a

6 COMPONENT C00LI

! (L

r- -

  • TO PUMP = 2 r- -> TO PUhP = 2 '

I I y

S/A/S S/A/S

) h i PUMP SELECT PUMP SELECT IHSD IMSD I I

t. _ _ _ _ __

SD j HSD SW SYSTEM I CCW SYSTEM N ADE S ADE P S l

!Nhgui

'S' SIGNAL PT l 1

N l c g l FROM CCW SYSTEM l L.O.

X CCW PUMP = 1 E FROM CCW SYSTEM WATER SURGE TANK

~

TO CCW PUMP = 2 NOTE:

1. COMPONENT COOLING WATER PUMP = 1, LOOP A SHOWN-CCW PUMP = 2. LOOP A. SIMILAR
2. CCW PUMP = 3 & 4, LOOP D SIMILAR RMENDHENT 9 GIBBSSAR INSTRUMENTATION AND.

G WATER SYSTEM _ CONTROL SYSTEM g g3 "!Oreciric j DIAGRAM s's w  : FIGURE NO. 7.3-1 SH.2A

r---

't I d

Q Q ll Vv L - -t- J TF G

I TO CCW SYSTEM FIG.7.3-? l/[ ll SH.2C l

~~

h X FE

\ CC

! Q Q

-\"/"" V I__ ._

I U g o- - t - -

I g

!!!Piau ix w:

FAI gy UlV l

-\

L____x av _ , _

~

\

_ FAI

~~

E

_\_

TO CCW' SYSTEM LOOP"B" f

I COMPONENT COOLING

A TO CCH SYS. /

m - LOOP"P" FC h HV TCV E

a.

T

_yg, M

7 Q

FROM CCH 7 1

$PS 1 &2 __

DISCH HEADER i H

\

~~

FROM -

Tj NON2 lgl l W' ig' HV ESSENTIAL Fdl LOOP

~ ~ - ~

HEAT __

HANGER HV al My

_x- _

TO Cbi SYS.

1 TO LOOP"B" SH. 2A RMENOMENT 9 GIBBSSAR INSTRUMENTATION AND nsss: O CONTROL SYSTEM e ATER SYSTEM M f E""' j DIAGRAM k "

CE O B4W D FIGURE NO. 7.3-1 SH.28.

i d

i FROM CCW SYS.

FIG.7.3-1

/

SH.20

%J L

/

4 JL x

FE FIS _-

x PS JL

-(*:  :*:

RHS1 PUMP

. SEAL HATER V "

re ris

__ A ___

\

I

  • TYPICAL FOR '

y ALL CCOLERS y AUXILIARY FEEDHATER

\

$I COOLERS COOLER

/

w PS _

U

^

x ,,

TO CCw SYS. <

FIG.7.3-1 [

SH.2D

! COMPONENT COOLING

'N

$ (

HV -

g--- -

PH.A x

FE FIS F.A. .

H h

x es _Q I U

) *'

l r -- - -

! A x

f  % v FT CONTRINHENT SPRRY F:lMP SEAL COOLER x

FE FIS FE

[ {

X l $I l

' 'in HEAT --

RHR/LHSI PUHP " --

COOLER ,

I0 PA g _-

hFROM CCW SYS.

gFIG.7.3-1 SH.2R n

AMEN 0HENT 9 GIBBSSAR INSTRUMENTATION AND

  • NSSS: O CONTROL SYSTEM WATER SYSTEM g;, SPECIFIC O

DIAGRAM ,

CE B4w a FIGURE NO. 7.3-1 SH.2C

. n n x

X FE FIS FIS OFE U

  • X TI U a x

PS CENTR PUMP SAFEGUARD CHILLED WATER SYSTEM COMPONENT COOLING WATER SYSTEh TD T f

JL TTO CCH SYS. 3 (FIG.7.3-1 SH.2C l U' PS V l 1 Hy V x  :-: x  :-:

F.0.

Ai --

x FE FIS

-~

FUGAL CHARGING

.0. COOLER x

r----- 7 l SPENT FUEL l i /

l POOL E"CHRNGER HEAT l /

L____ J PH.B ,

HV y HV F.C.

u Q

e \ FROM CCH SYS,

' / FIG.7.3-1 L.C.h ,h[ L.C.

L.C.h h L.C. AMEN 0 MENT 9 GIBBSSAR INSTRUMENTATION AND gig .g. // Hsss, a CONTROL SYSTEM SPECIFIC n' 3, DIAGRAM

[4 w a FIGURE NO. 7.3-1 SH.20

f I

Hv g- - -

M FIRE PR0!' CT10N >

SYSTEM X

F.O. -

3 7 q

-d Lv F.C. .C l

FROM CCW m . <

ORAIN TANK 7 '

l

, x i

1 M_ 'S I x  ::

U '

I v I {

' i I

] COMPONEN Su 0

I (

A ts I

g HV l

w_

l FAI l g-- - + H l rh y

TD CCHS U V ' fuia'i" n

FROM CCHS LOOP-SAFETY TRAIN A i

t COMPONENT COOLING

"V 1

r--

l un!"is F-U I

L 2 DEHINERAL] ZED f '

HATER

_ j_ 1 g F.0.

AV ,C,

[

tV l_

l l

PS l

l ts

][ x 3

. l _ V C00L]NG WATER I GE TANK LT j

l

) l A

tS x l m,

, y I

x FR i h] + - i l A l 7---- 3 TO CCHS \ ,

LO F TY AMENDMENT 9 FROM CCHS LOOP-SAFETY GIBBSSAR INSTRUMENTATION AND TRAIN B NSSS: O CONTROL SYSTEM '

WATER SYSTEM " !d"" e CE O DIAGRAM --

e4w O FIGURE NO. 7.3-1 SH.2E -

OUTSIDE i CONTAINMENT e m Ch.

l l FE le- J l4- j l

+- X i

X '

f>Al

s HV a r- (Nhfue

-a i EE s.

S 1-M M FAI FAI

< < >' a N

HV HV l

TO $CH SYSTEM J ENETRATION (TYPICAL) y/

NOTE:

1. REACTOR COOLANT PUMP NO. 4 SH0HN-REACTOR COOLANT PUMPS 1,2 4 3 SIMILAR j 1 INSTRUMENTATION APPLICATION FOR MOTOR RIR COOLERS

& UPPER & LOWER BEARING L.O. COOLERS SlHILAR TO j' THERMAL BARRIER COOLER.

I COMPONENT COOLING W

INSIDE CONTAINHENT OUTSIDE CONTAINHENT {

TO R.C. PUHPS a NO. 2 t. 3 m e OH THERHAL BARRIERS

  • R.C. PUMPS 1,2,43 TO . PUHP g A ,

V Vi

___J l l

! l l l

,_Y_ TY l

H H H THERHAL FAI FAI

_[ t j h)TAI X BARRIER COOLER

) ) a HV HV g

X r I gh l \

l_____pl__________s t _ _.

YY

_____l___J lLOWER BEARING L.0.

id g

~

J COOLER (-X (SEC NOTE 2) 4-X (0EE N TE _

Y-UPPER BEARING L.0.

(-X COOLER (SEC NOTE 2)

(-M-REACTOR COOLANT PUMP NO. 4 FROM R.C. PUHPS RHENDHENT 9 NO. 1.2 4 3 GIBBSSAR INSTRUMENTATION AND, nsss, o CONTROL SYSTEM  :

s01 secciric a DIAGRAM TER SYSTEM Ui" etw 8

o FIGURE NO. 7.3-1 SH.2F

) OUTSIDE I CONTAINHENT C TR hR

~~--

V l

CCH TEN 5 N N F.C.

PENETRATION HV (TYPICAL)

M en.a .--

TRR]N 8 b

CCH S STEM 4 A r.C.

HV TO CCNT CCH DRAI M M TR R

~~~- V y)--~TR kB A A onl?N % ; x F.C.

x F.C.

HV HV

'w

! COMPONENT COOL i

i INSIDE TRINHENT NOTF-

1. INSTRUMENTATION APPLICATION FOR '

REACTOR COOLANT ORRIN COLLECTION TANK HEAT EXCHANGER SlHILAR TO EXCESS LET00HN HEAT EXCHANGER FE vv ___ _

TE

[

l 1 l

l A I

EXCESS LET00HN HERI EXCHANGER NMENT 2

^

TANK '

X A f p

REACTOR COOLANT ORRIN COLLECTION TANK HEAT 4 '

EXCHANGER (SEE NOTE ,

, CONTAINMENT COMPONENT

> COOLING HATER ORRIN TANK RHEN0HENT S GIBBSSAR INSTRUMENTATION AND usss, o CONTROL SYSTEM j

NG WATER SYSTEM N DIAGRAM he' B4H O FIGURE NO. 7.3-1 SH.2G

k 4

HS-B REHOTE )

HS-A AUTO )

BLACKOUT SIGNAL \ =

/

"S" SIGNAL \ =

/ n _

~

=

m J J TRIPOFBOTHMA]N\

FEE 0 WATER PUMPS CLOSE BLOWDOWN 1/4STH.GENERATORN =

-.-- & SAMPLING LO-LO LEVEL / SYSTEM

/ ISOLATION VALVES HS-A START )

HS-A STOP )

n J

HS-A PULLEDOUT)

HS-C START =

)HSD HS-B LOCAL =

)HSD HS-C = =

STOP )

s. AUXILIARY FEEDWA

( DRIVEN PUMP TRAI TRAIN "B" PUMP S i

k i

=

. 3 , G  : ObhbRDR N R z f!!bbd$!kPUMP

!O!ORDR1EN hE h PUMP OPERATOR MANUAL CONTROLS

, HS-A ST ART + AUTO +STOP PULLED OUT HS-B REMOTE LOCAL HS-C START STOP AMENDHENT 9 GIBBSSAR INSTRUMENTATION AND ER MOTOR NSSS: O CONTROL SYSTEM -

"A" l$f" e LOGIC DIAGRAM MILAR B4w a FIGURE NO. 7.3-1 SH.10 ,'

[

HS-B REMOTE )

HS-A AUTO )

BLACK 0UT SIGNAL N -

=

n n v '

J 2/4STMGENERATOR\

LO-LO LEVEL CLOSE BLONDOHN

~ "

N0"E ISOLATION VALVES HS-A OPEN )

g

HS-A CLOSE ) r HS-C OPEN )  :

HS-B LOCAL ) '

HS-C CLOSE ) [ =

NOTES:

g' 1. SlHULTANE0US OPERATION OF BOTH AUXILIARY FEEDWA HANDSHITCHES IS REQUIRE 0 TO I OPEN THIS VALVE.

DRIVEN PUMP STEA TRAIN "A" (TRAIN

u DEENERGIZE S

R

=

=

]  :

jg}N O VALVE VALVE OPENS

[ = LVE CLOSE =

OPERATOR MANUAL CONTROLS HS-A CLOSE +RUTO +0 PEN HS-B REMOTE LOCAL HS-C CLOSE OPEN AMEN 0HENT S GIBBSSAR INSTRUMENTATION AND ER TURBINE nsss, a CONTROL SYSTEM l INLET VALVE LOGIC DIAGRAM i, heS2E"'h "B" SIMILAR) Baw a FIGURE NO. 7.3-1 SH.10A

MMM so VeVV

' - + "

!!!niF

@TAAA '

VVY LT LT L - - -j PT A C HS SD TRAIN "B PT yyg L _ _ 4._ _ _ 4 _ _ J T

4 , RAIN si mAAa MOT ro A A A r1 VY ' - -

V V Vo L__b-4__J PT i

V QQ7 g7 TURBINE DR i

i U k.J_a__m V . , aux

hn ( (

VVV L_ f _J FT

( >TO SG. =3 x x I

>TO SG. =2 FE II JL V

JL

>TO SG. =1 DRIVEN PUMP RA]N SD L_h__J > TO SG. =u

>TO SG. =3 v >TO SG. =2 X E g >TO SG. =1 l

% J FE l TO SG. =4 AMENDMENT 9 '

VEN PUMP lGIBBSSAR INSTRUMENTATION AND LIARY FEEDWATER !ssss. CONTROL SYSTEM SYSTEM ll,",recinc _IAGRAM U

{

jB4w d FIGURE NO. 7.3-1 SH.10B p

i

(

INSIDE OUTSIDE CONTAINHENT CONTAINHENT FE S.G. = 1 MJ " y y MAfN FT F- T '-7 FR

}

HSD NOTE:

1. S.G.
  • 2.S.G. = 3 AND S.G. = 4 SIMILAR TO S.G. = 1 I AUX

?

\

U i

_ _ _ _ L/E HSD HSD

/

/

y 3FROM HOTOR DRIVEN

' PUMP TRAIN A F.O.

FV V

~-~ L/R h HSD HSD

/

3FROM TURBINE F 0.4 ' DRIVEN PUMP F

i l AMENDMENT 9 GIBBSSAR INSTRUMENTATION AND LIARY FEEDWATER NSSS: O CONTROL SYSTEM SYSTEM "S g " " e DIAGRAM 4w a FIGURE NO. 7.3-1 SM.10C

1 1

I

~'

HS STANT) ,

m HS.  : V 3M10. )

BLACKOUT SIGNAL

\ 5 i

/

m .

v -

"S* SIGNRL  :

/

HS STOP)

VENTI _ATION SA

's CHILLED WATER

't (3 OTHER PUMPS SIMIL

\

't

s * $h!h h0kN!
g CHILLER UNIT

{

  • h!ER U CHILLER UNIT g OPERATOR HANUAL CONTROLS HS- START AUTO = STOP PULLEO OUT AMENDMENT 9 ETY FEATURES GIBBSSAR INSTRUMENTATION &

UMP usss, a CONTROL SYSTEM Ri "?lisreciric@ LOGIC DI%RM

&H O FIGURE NO. 7.3-1 SH.ll

i g ,___________,_._________,

C~ l s sicant d

1 I

i l l

h l v

\ ><

FAI

?

l l -

l A u

  • CHILLED V V s si LT ts to h S10N Q SURGE TANK '

f---

M # M k

/ \ l ElN i

I I , M ,

I I

[

kk TR CHILLED l (TY K [

P FR0ii CHILLED HATER SYSTEM COOLERS VENTILATION SAF f CHILLED WRTER S

/ (TRAIN B SIMILAR)

ROM DEMIN.

ATER SYSTEM

,_ _ _,_ _ __ _ q l r I- 7- 7 p- p--l- , l HI LO g,

HI LO I l FI FA FA in Ta Ti l M UU y h V

M M N "A" E m-l ATER PUMP h"VAPORATORj j CAL) {

l l FE l - I l I r- 7 )FROM CCH SYSTEM w.

i l TO CCW SYSTEM

! TRA]N "A" CHILLED UN]T TO CHILLED HATER oer SYSTEM COOLERS AMENDMENT S TY FERTURES GIBBSSAR INSTRUMENTATION &

"sss, a CONTROL SYSTEM ,

STEM

_ "?' #"" 8 DIAGRAM i'

[a w a FIGURE NO. 7.3-1 SH.11A '

k

(

HS- OPEN ) =

MAIN STERM ISOLATION SIDHAL

\ =g c =

(TRAIN R) 1 MRNURL STERMLINE ,3 ISOLRTION v (STSTEM ISOLRTION), ;_

HS- CLOSE )

HS- RUTO )  :

HAIN STERM x ISOLRTION VALVE OPENS MAIN STEAM ISOLATION BY CONTROL LOGIC f

= = S S  !$E o

R VALVE =((ALVEOPENS J DEENERGIZES OID r/ LVECLOSES)

NOTE:

1. TRR]N A LOGIC SHOWN.

TRA]N B LOGIC SlHILAR.

2. SlHULTANE0US OPEEiATION OF BOTH HANDSWITCHES IS REQUIRED TO OPEN ERCH HRIN STERM ISOLATION BYPRSS VALVE.

OPERATOR HRNURL CONTROLS HS CLOSE

  • RUTO +-OPEN RHEN0HENT 9 RSS VALVE GIBBS3RR INSTRUMENTATION & t nsss, a CONTROL SYSTEM i

"?;3 3"Ec' @ _

LOGIC DI% RAM

!aw a FIGURE NO. 7.3-1 SH.12

s i

h

( HS AUTO )

HAIN STEAH ISOLATION SIGNAL

\

(TRAIN A) z

=

HANUAL STEAMLINE ISOLATION n 73  ;

O v

(SYSTEH I SOL A T I ON)'

d% =

HS CLOSE ) [

HS OPEN ) r HS AUTO )

HAIN STEAM ISOLATION S]GNAL

\ "

(TARIN B) x "

m HANUAL STEAMLINE N V ISOLATION (SYSTEH ISOLATION), z O z HS CLOSE ) ~

HS OPEN )  :

MAIN STEAM ISOLATION VALVE l TYPICAL FOR ONE OF FOUR MAIN STEAM IS

/

+

!!S!!!!"?a'"

(TRAIN Al h4 VALVE CLOSES

+

VALVE OPENS L

M NOTE:

1. SlHULTANEOUS OPERATION OF BOTH HAND SWITCHES IS REQUIRED TO OPEN EACH HAIN STEAM ISOLATION VALVE.

!!S!!!!";a'" h4 (TRAIN 81 VALVE CLOSES -

VALVE OPENS OPERATOR MANUAL CONTROLS HS C L O S E --+ A U T O +-- OP E N HS CLOSE

  • AUTO *- OPEN M

AMENDHENT 9 ONTROL LOGIC GIBBSSAR INSTRUMENTATION &

LATION VALVES. CONTROL SYSTEM Nsssi o

% SPECIFIC LOGIC DIAGRRM

[4 w 0 FIGURE NO. 7.3-1 SH.13

k

(

HS- OPEN )

STERM SUPPLY 10

)

E =

R.F.W. TURBINE \ '

R"lA'""' /

HS- AUTO )  :

]

HS- CLOSE )

RUXILIARY FEEDWATER TURBINE DRI i STEAM SUPPLY VALVE I (TRAIN B SIMILAR)

P t

_S_

!O[ENDD
R VRLVE (ALVEOPENS)

ENERGIZES

010 [LVECLOSE]S J

OPERATOR MANUAL CONTROLS HS- CLOSE

  • AMLQ_ 4-OPEN AMENDMENT S GIBBSSAR INSTRUMENTATION &

EN PUMP usss, o CONTROL SYSTEM ,

"J;f'""'@ LOGIC DIAGRAM CE O  !

B4w a FIGURE NO. 7.3-1 SH.13R

\

J

~.

HS AUTO ) =

FEEDWATER \

ISOLATION VALVE \ _

CLOSE SIGNAL / n (TRA]N Ai / v HS CLOSE ) A =

_g _._

HS OPEN )  :

HS AUTO ) =

=

FEE 0 WATER ISOLATION VALVE \ _

CLOSE SIGNAL (TRAIN B) / m V

HS CLOSE M ' =

_g_

HS OPEN ) r FEEDWATER ISOLATION VALVE i TYPICAL FOR ONE OF FOUR FEEDHPTER IS i

4

I j

FEE 0 HATER ISOLATION VALVE CON CUIT (TRAIN Al "

  • VALVE CLOSES E t. 1 NN M

NOTE:

1. SIMULTANEOUS OPERATION OF BOTH HAND SWITCHES

'S REQUIRED TO OPEN EACH FEE 0 HATER ISOLATION VALVE.

FEEDWATER ISOLATION VALVE SOLEN 0ID CONTROL CIRCUIT "

(TRAIN B1 VALVE CLOSES S!E OE OPERATOR MANUAL CONTROLS HS CLOSE

  • AUTO +- OPEN HS C L O S E -* A U T O *-- OPE N M

AMENOMENT 9 NTROL LOGIC GIBBSSAR INSTRUMENTATION &

ATION VALVES. nsss: o CONTROL SYSTEM

%S"' 8 LOGIC DIAGRAM ,

[4 w a FIGURE NO. 7,3-1 S H . l ll

t HS CGNTROL =

f 3 $ -

=

---+ n FEE 0 HATER \

ILGLATION VALVE \ __

CLOSE SIGNAL (TRAIN Al G

J HS  :-

, CLOSE)

?.

]

) FEEDWAT VALVE C 1

i

\.

ENERGIZE

~ [ VALVE ~-

h0Ehl010 (MODULATES)

  • DE-ENERGIZE [ VALVE Sj[EOID (CLOSES j j OPERATOR MANUAL CONTROLS HS- CLOSE - CONTROL NOTES:
1. FEEDWATER ISOLATION LOGIC DUPLICATED WITHIN EACH TRAIN.
2. CONTROI LOGIC SHOWN FOR TRA]N A.

TRAIN B LOGIC SlHILAR.

3. S1HULTANEDiS OPERAT10N OF BOTH HANDSWlTPMES ]S REQUIRED TO OPEN EHLH r FEDWTER BYPASS CONTROL VALVd.

RHENDHENT-9 GIBBSSAR INSTRUMENTATION &

usss, u CONTROL SYSTEM R BYPASS CONTROL M, SPECIFIC LOGIC DINMM NTROL LOGIC gE4w 0 FIGuaE NO. 7.3-1 SH.1S

l

[

HS- OPEN )

  • PHASE A ISOLATION SIGNAL (TRRIN "A")

CONTAINMENT Alft MONITOR HIGH NkR 1 =

=

HS , Ptif ( )  :

e L

HS- CLOSE )  :-

NOTES:

1. CONTRni_ LOGIC SHOWN FOR TRAIN "A" A]R OPERHit0 VALVE. TRA]N "B" R]R OPERATED VALVE SlHILAR.
2. CONTROL LOGIC IS TYPICAL OF AIR OPERATED ISOLATION VALVE THAT CLOSES ON PHASE A ISOLATION SIGNAL OR CONTAINHENT HIGH RADIDACTIVITY.

f CONTAINMENT ISOL I

S " OfD AL.VE OPEN a

= 0$0 LVE CLOSE OPERATOR MANUAL CONTROLS HS- CLOSE + RUTO --OPEN AMEN 0HENT 9 GIBBSSAR INSTRUMENTATION AND nsss, a CONTROL SYSTEM i MfE""' j LOGIC DIAGRAM TION SYSTEM l

4w a FIGURE NO. 7.3-1 SM.16

k c

t HS- A'JT O M PHASE A \

ISOLAT]ON SIGNAL /

HS- CLOSE )

G J

CONTAINMENT'1;Gl\

FIAD I DACT l v i , ,

HS- OPEN f 1

.i CONTAINMENT ISOLAT10

i

\

CLOSE MOTOR Ef"2

M 8

OPEN HOTOR

" S '

%f"!'"

M OPERATOR HRNUAL CONTROLS HS- CLOSE -* AUTO <-OPEN NOTE:

1. CONTROL LOGIC SH0HN FOR TRAIN A HOTOR OPERATED VALVE: TRAIN B HOTOR OPERATED VALVE SIMILAR.
2. CONTROL LOGIC IS TYPICAL OF HOTOR OPERATED ISOLATION VALVE THAT CLOSES ON PHASE A ISOLATION SIGNAL OR CONT 9INHENT HIGH RADI0 ACTIVITY.

RHEN0HENT 9 GIBBSSAR INSTRUMENTATION & '

nsss, a CONTROL SYSTEM SYSTEM g,settiric 8 L%IC DI%MM l B4w a FIGURE NO. 7.3-! SH.16A

\

l HS OPEN f r

> S

=

~ R PHRSE B k  :

ISOLATIONSIGNRL[

ITRAIN B)

=

HS RUT 0)  :

n J

HS =

CLOSE)

CONTAINMENT

= !5[! NOD { VALVE ) _

_ VALVE (OPENS j '

DE-ENERGlZE [ VALVE ) "

QE010 (CLOSES j ,

OPERATOR MANUAL CONTROLS HS- OPEN = AUTO -- CLOSE NOTE

1. CONTROL LOGIC SH0HN IS TYP! CAL OF AIR OPERATED ISOLRT]ON VALVE THRT CLOSES ON PHASE B ISOLATION SIGNAL.

AMENDHENT-9 GIBBSSAR INSTRUMENTATION & '

usss, a CONTROL SYSTEM

?!!' "' @ LOGIC DIAGRAM .

ISOLATION SYSTEM gE O

i i

HS- gyJ3) =

=

=

0 PHASE B ISOLATION SIGNAL

\

(TRAIN "A*)

HS- CLOSE)

I=g =

HS- OPEN)

HS-

  • AUT0)

=

=

PHASE 8

\

(TRAIN *B")

ISOLATION $]GNAL[

HS- '

CLOSE)

I=g =

HS- OPEN) r 3

e CONTAINMENT ISOLA e

i

7

\

L NOTE:

1. CONTROL LOGIC SH0HN

_ CLOSE HOTOR ZL ]S TYPICAL OF HOTOR OPERATED VALVE OPERATE 0 ISOLATION VALVES THAT CLOSE ON PHASE "B" ISOLATION SIGNAL OPEN HOTOR -

~

OPERATED VALVE

~

CLOSE HOTOR _

~

OPERATED VALVE

OPEN HOTOR

OPERATED VALVE OPERATOR MANUAL CONTROLS HS- CLOSE = AUTO = OPEN HS- CLOSE = AUTO = OPEN AMEN 0HENT-9 GIBBSSAR INSTRUMENTATION &

ION SYSTEM nsss, a COM POL SYSTEM r

"%3""'"' @ LOGIC DIAGRAM l E4w a FIGURE NO. 7.3-1 SH.16C

I i

HS 5 OPEN) m J

HS AUT0)

PHASE A .

ISOLRTION S]GNAL '

Y:

MS CLOSE)  :

COMPONENT C00LI

! RESIDUAL HE AT REM 0', AL DUTLET VALVE CONTROL

i s

8Ei"JEl"atve M M

CLOSE HOTOR OPERATED VALVE OPERATOR MANUAL CONTROLS NOTE

1. CONTROL LOGIC SH0HN FOR TRAIN A HOTOR OPERATED VALVE.

TRAIN 8 HOTOR OPERATED VALVE SlHILAR.

2. CONTROL LOGIC IS TYPICAL OF HOTOR OPERATED VALVE THAT OPENS ON PHASE A ISOLATION SIGNAL.

AMENDHENT-9 GIBBSSAR INSTRUMENTATION &

usss, a CONTROL SYSTEM r G WATER SYSTEM g,secciric g L%IC DI%MM '

EAT EXCHANGER CE O .

GIC Baw a FIGURE NO. 7.3-1 SH.16D

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GlBBSSAR PLANT VENTIL ATiCN .

NSSS: CHILLED WATER SYSTEM ,

NOT SPECIFIC E W - 414 0 FLOW DI AGRA M  !

CE 1 O

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