ML20137G327
| ML20137G327 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 03/31/1997 |
| From: | GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20137G319 | List: |
| References | |
| NUDOCS 9704010376 | |
| Download: ML20137G327 (162) | |
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- GENuclearEnergy 1
i Rev. 4 ) March 1997 i t j Design i Control ! Document N [] g
Rsv. 4 ABWR Desi.en controloocument Effective pages of the DCD Fievision 4, March 1997 l ALL PAGES IN THE DCD ARE REV. 0 EXCEPT FOR THOSE LISTED BELOW: DCD TOC 1.0-5 4 2.11.3-6 3 i/ii 3 1.0-6 4 2.11.3-9 3 Effective Panes 1.0-7 1 Section 2.11.5 1 4 1.0-9 1 2.11.5-2 3 2 4 1.0-10 1 Section'2.11.6 3 4 1.0-11 1 2.11.6-1 3 4 4 4 2.11.6-3 3 l 1.0-12 5 4 1.0-13/14 1 2.11.6-5 3 1 6 4 Tier 1 Section 2.12.14 7 4 Section 2.2.4 2.12.14-3 1 l 8 2.2.4-2 3 Section 2.15.5 4 l 1 9 4 Section 2.7.1 2.15.5-1 3 2.7.1-3 1 2.15.5-2 3 10 4 2 7 I-4 1 2.15.5-1 3 11/12 4 Section 2.8.1 2.15.5-6 3 Introduction TOC 2.8.1-1 1 2.15.5-8 3 [ 1.0-i/ii 4 Section 2.8.3 2.15.5-9 3 LOT 2.8.3-1 1 2.15.5-14 3 1.0-iii/iv 1 Section 2.8.4 2.15.5-15 3 Sections 1.0 - 3.0 2.8.4-1 1 2.15.5-16 3 1.0-1 4 Section 2.11.3 2.15.5-17 3 1.0-2 4 2.11.3-1 3 2.15.5-19 3 1.0-3 4 2.11.3-5 3 2.15.5-20 'S 1.0-4 4 Eflective Pages 1
l ' Rev. 4 ACWR Design ControlDocument i l Effective pages of the DCD Revision 4, March 1997 ALL PAGES IN THE DCD ARE REV. O EXCEPT FOR THOSE LISTED BELOW: ! 2.15.5-21 3 2.15.12-6 1 Tier 2 i 2.15.5-23 3 2.15.12-9 1 l l I I 2.15.5-24 3 2.15.12-10 3 il 1 2.15.5-25 3 Section 3.2 2.15.5-34 i" I 3 3.2-2 1 3.2-3 1 Chapter 1 TOC Section 2.15.10 3.2-4 1 , 1.0- i 1 2.15.10-3 1 3.2-6 3 Section 1.1 ( 2.15.10-5 1 3.2-7 I I*I-3 1 2.15.10-6 1 3.2-8 1 Section 1.2 2.15.10-8 3 3.2-9 1 1.2-30 3 2.15.10-9 1 3.2 3 Section 1.3 2.15.10-10 1 3.2-11 1 1.3-6 4 2.15.10-11 2 3.2-12 3 Section 1.8 2.15.10-12 3 3.2-13 1 1.8-29 1 2.15.10-13 1 3.2-15 2 l I 8-34 1 1 2.15.10-14 3 3.2-17 3 1.8-35 1 2.15.10-15 1 3.2-22 1 t 1.8-38 1 l 2.15.10-16 1 3.2-23 3 1.8-39 1 l Section 2.15.12 Section 5.0 1.840 1 2.15.12-3 1 5.0-2 1 l 1.8-41 1 2.15.12-4 3 Appendix A 1M2 1 2.15.12-5 1 Appendix A-5 3 2 Effective Pages
i ._ RJV. 4 ABWR oesion controloocument l Effective pages of the DCD Revision 4, March 1997 ALL PAGES IN THE Dt, ARE REV. 0 EXCEPT FOR THOSE LISTED BELOW: 1.8-43 1 3.8-32 3
- 3 & 35 4 1.8-44 1 3.8-42 1 SB-36 4 1.8-45 1 3.8-60 1 SB-37 4 1.8-46 1 Section 3.9 SB-38 4 1.8-47 1 3.9-28 2 3B-39 4 1.8-51 1 3.9-29 1 SB-41 4 Section 1.9 3.9-30 1 3B-42 4 1
1.9-12 3 3.9-31 1 3B-47 4 Section 2.0 3.9-36 1 SB48 4 1 2.0-2 1 3.9-56, 1 3B-49 4 Section 2.3 3.9-84 1 3B-53 4 2.3-1 1 3.9-87 1 3B-54 4 2.3-6 1 3.9-98 3 3B-55 4 Chapter 3 TOC 3.9-118 3 3B-56 4 iii/iv 1 3.9-121 1 3B-57 4 Section 3.2 3.9-123 3 3B-58 4 3.2-43 3 3.9-127 3 SB-59 4 Section 3.3 3.9-128 3 SB-61 4 l 1 3.3-3 1 3.9-129 3 SB-62 4 Section 3.7 Section 3A SB-63 4 l 3.7-39. 1 SA-3 2 SB-64 4 l Section 3.8 Section 3B S & 66 4 3.3-31 3 3B-34 4 SB-68 4 Eflective Pages 3
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Rav. 4 AMR oesso ncontroloccament , i l Effective pages of the DCD Revision 4, March 1997 , ALL PAGES IN THE DCD ARE REV. 0 EXCEPT FOR THOSE LISTED BELOW: SB-70 4 SK-S 1 4A-17 4 S&71 4 SK-4 1 4A-18 4 S &72 4 SK-5 1 4A-20 4 ; SB-73/74 4 SK-6 1 4A-21 4 Section 3H.1 Attachment 3MA 4A-23 4 SH.1-4 1 SMA-14 3 4A-24 4 SH.1-5 1 SMA-15 3 4A-26 4 SH.1-7 1 SMA-16 3 4A-27 4 SH.1-13 1 Section 4.2 4A-29 4 SH.1 16 2 4.2-6 , 1 4A-30 4 Section 3H.2 4.27 1 4A-32 4 SH.2-2 1 Section 4.3 4A-33 4 SH.2-6 1 4.310 4 4A-35 4 i SH.2-12 1 Section 4A 4A-36 4 l l SH.2-30 1 4A-3 4 4A-38 4 Section 3H.3 4A-5 4 4A-39 4 SH.3-2 1 4A-6 4 4A-41 4 SH.3-5 1 4A-8 4 Section 4B i Appendix 31 4A-9 4 4B-1/2 4 I 31-17 3 4A-11 4 Section 4D Appendix 3K 4A 12 4 4D-1/2 4 j l SK-1 1 4A-14 4 Section 5.2 i , J SK-2 1 4A-15 4 5.2-41 1 I 4 Effective Pages
e -- e l Rsv. 4 ACWR oesign controlDocument ; i l Effective pages of the DCD Revision 4, March 1997 ! 1 ALL PAGES IN THE DCD ARE REV. O EXCEPT FOR THOSE LISTED BELOW: l l 1 5.2-44 6.3-51 1 4 6.3-74 4 / \ l 5.2-45 1 6.S52 4 6.3-75 4 5.2-53 1 6.3-53 4 6.3-76 3 i l Section 5.4 6.S54 4 6.3-77 4 i l 5.4-21 3 6.S55 4 6.3-78 4 l ! I l 5.4-27 3 6.S56 4 6.3-79 4 - 5.4-61 3 6.3-57 4 6.3-80 4 i Section 6 LOT 6.S58 4 6.S81 4 6.0-iii 4 6.S59 4 6.3-82 4 l l Section 6.2 6.S60 4 6.S83 4 l ! 6.2-12 3 6.3-61 4 6.3-84 4 l 6.241 1 6.362 4 6.3-85 4 6.2-82 1 6.3-63 4 6.S86 4 6.2-83 1 6.3-64 4 6.S87/88 4 6.2-84 1 6.S65 4 Section 6.4 6.2-85 1 6.3-66 4 6.4-8 3 6.2-86 1 6.3-67 4 Section 6.7 l l
- 6.2-87 1 6.S68 4 6.7-1 1 l l
6.2-183 3 6.S69 4 6.7-2 1 l Section 6.3 6.S70 4 Appendix 6C l l l l 6.S30 1 6.S71 4 6C-5 1 1 6.S32 4 6.3-72 4 Section 7.1 6.S50 4 6.S73 4 7.1-2 1 1 l I l Effective Pages S I
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. e Rov. 4 ABWR oesign controloocument l Effective pages of the DCD Revision 4, March 1997 i ALL PAGES IN THE DCD ARE R5V. O EXCEPT FOR THOSE LISTED BELOW: !
l 7.1-4 1 7B-4 1 9.3-24 1 l ! 7B-5 1 i l I Section 7.2 Chapter 9 LOT Section 9.4 l 1 ! 7.2-55 1 9.0-vAi 3 9.4-2 3 ! Section 7.3 Chapter 9 LOF 9.4-4 3 7.&57 3 9.0-viii 1 9.4-5 3
- I 7.3-58 3 Section 9.2 9.4-9 3 7.3-59 3 9.2-6 3 9.4-17 3 1
7.3-91 3 9.2 12 1 9.4-21 3 I I 7.3-92 3 9.2-20 3 9.4-22 3 l 7.3-96 1 9.2-31 3 9.4-23 3 Section 7.6 9.2-32 3 9.4-33 3
*/.6 7 1 9.2-33 3 9.4 1 Section 7.7 9.2-50 3 9.4-43 3 7.7-49 1 9 2-51 3 9.4-44 '3 l Appendix 7A 9.2-58 3 9.4-45 3 7A-4 1 9.2-60 3 9.4-47 3 7A-5 1 9.2-68 3 9.4-48 3 7A-7 1 Section 9.3 9.4-54 1 j 7A-8 1 9.3-9 1 Section 9.5 7A-9 1 9.3-13 3 9.5-9 3 l l
Appendix 7B 9.3-18 1 9.5-11 3 1 7B-1 1 9.3-21 1 9.5-12 3 6 , Effective Pages
. ~e Rzv. 4 ABWR oesign controsoocua.ent l Effective pages of the DCD Revision 4, March 1997 ALL PAGES IN THE DCD ARE REV. O EXCEPT FOR THOSE LISTED BELOW:
9.5-13 3 9A.6-79 3 Appendix 9C 9A.680 3 9C-1 3 Appendix 9A TOC 9A.681 3 9C 10 3 ! 9A.0-vi 3 9A.G82 3 Section 10.2 9A.0-viii 3 9A.483 3 10.2-11 1 Section 9A.4 9A.6-84 3 Section 11.5 9A.4-264 3 9A.6-85 3 11.5-23 1 [ 9A.4-287 3 9A.486 3 Section 11 A.2
.i 9A.4-292 3 9A.6-87 3 11A.2-1/2 4 ,
9A.4-293 3 9A.6-88 3 Section 11 A.4 9A.4-306 3 9A.6-89 3 11A.4-1/2 4 9A.4-314 3 9A.6-90 3 Section 12.2 9A.4-320 3 9A.6-91 3 12.2-32 1 9A.4-417 3 9A.6-92 3 12.2-33 1 9A.4-418 3 9A.6-93 3 12.2-66 1 9A.4-437 3 9A.6-94 3 Section 12.3 9A.4-438 3 9A.6-95 3 12.S-26 1 9A.4-450 3 9A.6-102 3 Section 13.6 : 9A.4-451 3 9A.6-103 3 13.6-1/2 4 9A.4-458 3 9A.6-104 3 Chapter 14 TOC l r 9A.4-459 3 9A.6-105 3 14.0-iv 1 Section 9A.6 A_ppendix 9B Section 14.2 9A.6-78 - 3 9B-15/16 1 14.2-60 3 l 1 Effective Pages 7 i
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$ e Rtv. 4 ABWR Desion controloocument l Effective pages of the DCD Revision 4, March 1997 ALL PAGES IN THF DCD ARE REV. O EXCEPT FOR THOSE LISTED BELOW:
14.2-61 3 14.3 1 14.3-44 1 l 14.2-140 1 14.S22 1 14.S-45 1 Section 14.3 14.S23 1 14.S-46 1 14.S1 1 14.S24 1 14.S47 1 l 14.3-2 1 14.S25 1 14.S-48 1 14.3-3 1 14.S26 1 14.3-49 1 14.3-4 1 14.S27 1 14.3-50 1 14.3-5 1 14.3-28 3 14.3-51 1 i 14.S6 1 14.3-29 3 14.S52 1 ! l 14.3-7 1 14.S30 1 14.S53 1 14.3-8 1 14.3-31 1 14.S54 1 14.3-9 1 14.S32 1 14.3-55 1 14.3-10 1 14.S33 1 14.S56 1 14.3-11 1 14.S34 1 14.S-57 1 l 14.3-12 1 14.S35 1 14.S58 1 l 14.S-13 1 14.S36 1 14.3-59/60 1 l l 14.S14 1 14.SS7 1 Section 15.1 ~ 14.3-15 1 14.3-38 1 15.1-9 3 14.3-16 1 14.S39 1 15.1-10 3 14.S17 1 14.3-40 1 Section 15.2 14.3-18 1 14.3-41 1 15.2-15 3 . 14.3-19 1 14.S42 1 Section 15.4 i 14.3-20 - 1 14.S43 1 15.4-7 1 i 8 Effective Pages
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&MR oesign controsoocument l Effective pages of the DCD Revision 4, March 1997 ALL PAGES IN THE DCD ARE REV. O EXCEPT FOR THOSE LISTED BELOW:
Section 15.6 3.S18 1 Section 4.0 15.67 3 3.3-19 1 4.0-2 3 I l 15.616 3 3.3-21 1 Section 5.0 l 15.G18 3 3.3-28 1 5.0-6 4 l 15.G26 3 3.3-29 1 Section B3.3 l l 15.6-27 3 3.3-42 3 B3.3-61 1 15.430 1 3.3-47 1 B3.S62 1 15.6-31 3 3.3-48 1 B3.S63 1 15.433 3 3.3-53 1 B3.S64 1 15.6-37 3 3.3-68, 1 Section B3.4 l 15.GS8 3 3.3-69 1 B3.4-8 3 15.440 3 Section 3.4 B3.4-9 3 15.645 3 3.4-3 3 Section B3.5 l Chapter 16 Section 3.5 B3.5-4 3 Section 2.0 3.5-2 1 B3.5-7 3 l 2.0-1 3 3.5-6 3 B3.5-9 1 Section 3.3 Section 3.6 B3.5-10 1 1 3.3-1 1 3.641 1 B3.5-17 3 l < 3.3-2 1 Section 3.7 - Section B3.7 3.S3 . 1 3.7-3 3 B3.7-4 3 ; l 3 S: 1 3.7-4 1 , B3.7-5 3 l 3.S6 1 3.7-6 3 B3.7-6 3 ; 1 3.3-12 3 3.7-8 3 B3.7-7 3 ? Effective Pages 9
I -. l o < fiJy. 4 l ABWR oesign contraroocument Effective pages of the DCD Revision 4, March 1997
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ALL PAGES IN THE DCD ARE REV. O EXCEPT FOR THOSE LISTED BELOW: ; B3.7-13 3 Section 19.4 Appendix 19P B3.7-17 3 19.4-12 3 19P-1/2 3 l Chapter 17 TOC 19.4-13 3 Attachment 190C l l 17.0-i 1 Section 19.8 19QC 3 3 1 i Section 17.3 19.8-7 3 Appendix 19R 17.3-6 1 19.8-35 1 19R-33 1 Appendix 18A Section 19.9 Section 20.3.15 I8A-1/2 1 19.9-11 3 20.3.15-37 4 Section 18A.6 Appendix 19C 20.3.15-38 4 18A.6-8 1 19C-1/,2 4 20.3.15-39 4 Appendix 18E Attachment 19EA Chapter 21 18E-1 1 19EA-33 1 21-11 3 18E-23 1 Appendix 191 21-12 3 Appendix 18F 191-3 3 21-26 3 18F-5 1 191-4 3 21 32 3 18F-6 1 19I-5 3 21-33 3 i 18F-7 1 191-8 3 21-73 3 l l 18F-10 1 191-9 3 21 100 3 1 I 3 I ISF-12 1 191-10 3 21-102 Appendix 18H 191-13 3 21-259 3 18H-7/8 4 Mendix 19M , 21 260 3 l Chapter 19 TOC 19M 1 1 21-261 3 19.0-ii 3 21-262 3 { l Effective Pages 10
a o Rett. 4 ABWR Design ControlDocument Effective pages of the DCD Revision 4, March 1997 l ALL PAGES IN THE DCD ARE REV. 0 EXCEPT FOR THOSE LISTED BELOW: 21-263 3 21-547 3 21-264 3 21-548 3 21-267 3 21-560 3 21-488 3 21-561 3 21-489 3 21-565 3 21-495 3 21-571 3 21-509 3 - 21-572 3 21-510 3 21-588 3 21-513 3 21-590 3 21-518 3 21-591 3 21-519 3 21-598 3 21-526 3 21-600 3 21-535 3 21-601 3 l 21-536 3 21-616 3 21-537 3 21-617 3 21-538 3 21-623 3 21-539 3 21-629 3 l 21-542.1 3 21-630 3 21 542.2 3 21-633 3 l 21-542.3 3 21-543 3 21-544 3 21-545 3 4 Effective Pages 11/12
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Rav. 4 . ACWR oesion centrosoocumentantroduction o 1 i introduction " Table of Contents ! l i 1 1.0 Purpose of the DCD....... .. .. .
....................................... .......... 1.0-1 >
1 i 2.0 Con te n ts of th e DCD ... . . .. ... . ........ .... . .......... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 1.0-1 [ 3.0 Uses of the DCD . ......... . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .. 1.0-2 j 3.1 I n Ge n e ral .. . .... . ... .. .. ... .... .. .. ..... .. . . . . . . . . . . .. 1.0-2 i [' l 3.2 Uses of the Certified Design Material.. . . . . . . . . .. . ... ... ....... ... ....... 1.0-2 > 3.3 Uses of the Approved Safety Analysis Material . ..... .. . . . . . . . . . . . . . ... ... 21.0-3 3.4 Use ofITAAC During Opention.. . . . . . . . . . . . . . . . . . . . . . . . . ... . . . 1.0 j i 3.5 Plant-Specific Changes to Certain Designated Material in Tier 2 (Tier 2 *) . . .. ... .1.0-4 l
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j 3.6 Proprietary and Safeguards Information.... .. ... .... . . ..... . . ....... ... ........... . 1.0-5 t j 3.7 References in Tier 2 to the Standard Safety Analysis Report. ... ...... ..... . .. . .. ... ...1.0-5 l 3.8 Severe Accident Issues . . . ...... ... ...... ..... .................... .................... ..... 1.0-5 ! t f I l I l l i I. 4 Introduction 1.0-i/ii l
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s -- , l Rsv. 4 l ABWR oesign controloocument/Introductio, introduction for Design Control Document 1.0 Purpose of the DCD The Design Control Document (DCD) contains information from various documents comprising the design certification application for the Advanced Boiling Water Reactor l (ABWR) standard design. The purpose of the DCD is to provide,in a single document, l design-related information to be incorporated by reference in the design cerdfication I rule for the ABWR standard design. l l This Introduction describes the purpose, contents, and uses of the DCD, and is ! consistent with the design certification rule. However, this Introduction is not l incorporated into the design certification rule and does not consdtute a legal j requirement. Licensing decisions shall be based upon the legal requirements in the design certification rule and 10 CFR Part 52. Additional guidance is prosided in the Statement of Consideration for the design certification mle and 10 CFR Part 52. I j 2.0 Contents of the DCD This document contains the DCD Introduction, the Certified Design Material (i.e., Tier 1), and the approved safety analysis material (i.e., Tier 2). Each is summarized I below. l The Introduction describa ce purpose, contents and uses of the DCD. The Certified Design Material (Tier 1) for the ABWR includes the following i I informadon: (1) Definitions and General Provisions; (2) Design Descripdons; (3) l Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC); (4) Significant Interface
- Requirements for interfaces of systems that are wholly or pardally outside the scope of l the ABWR standard design; and (5).Significant Site Parameters for the ABWR standard design plant. For ease of reference, Tier 1 inciudes a Table of Contents.
I The approved safety analysis material (Tier 2) includes, to the extent applicable for the ABWR standard design, the following information: (1) the infonnadon required for a final safety analysis report under 10 CFR 50.34(b); and (2) other relevant information j identified in 10 CFR 52.47(a), such as information related to the Three Mile Island l requirements under 10 CFR 50.34(f); technical resolutions of the Unresolved Safety Issues and medium and high priority Generic Safety Issues; and important features ; identified from the assessments for the ABWR design. For case of reference, Tier 2 l
- contains a general Table of Contents at the beginning, as well as a detailed Table of Contents before each chapter.
3 The Design Descriptions, Interface Requirements, and Site Parame'ers in Tier 1 are derived endrely from the provisions of Tier 2, but may be more general than the provisions in Tier 2. Therefore, compliance with the more detailed Tier 2 material Introduction 1. 0- 1 4
R3v. 4 ABWR' casion controloocumentantroduction i i provides a suflicient method, but not the only acceptable method, for complying with l the more general design provisions in Tier 1. The methods specified in Tier 2 shall be , followed unless a change is made in accordance with the change processes specified in the design certification mle for the ABMR. l 3.0 Uses of the DCD 3.1 in General The design certification rule for the ABWR can be referenced in an application for a combined license (COL) under 10 CFR Part 52, and in the subsequently issued COL. ; Because the DCD is incorporated by reference in the design certification rule for the ABWR, the provisions of the DCD are effective with respect to an application or license that references that rule, with certain exceptions as provided in the rule and described in Sections 3.2,3.3 and 3.4 below. The DCD describes structures, systems, and components (including any associated programmatic pr'ovisions) within the scope of the AB%R standard design, and the , requirements governing the interfaces between the ABWR standard design and the ! plant-specific design. An application for a COL that references the design certification , rule for the AB%R must provide a plant-specific safety analysis report (SAR) which shall include information about the part of the plant that is outside the scope of the AB%R ! standard design or which is othenvise required by a relevant provision of 10 CFR Part 52, but is not included in the DCD (see Section 3.6 below). Together, the DCD and plant-specific SAR will provide the technically relevantinformation required for a COL, . , or for an application for a COL, that references the design certification rule for the l ABWR. ,
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3.2 Uses of the Certified Design Material The following provisions describe the scope and uses of Tier 1 material:
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Desien Descriotions - The Desigr. Descriptions pertain only to the design of l structures, systems, and components of an ABWR standard plant and not to its operation, maintenance and administration. In the event of an inconsistency between the Design Descriptions and the Tier 2 material, the Design Descriptions shall govern.
- ITAAC - An applicant or holder of a COL shall perform and demonstrate conformance with the ITAAC prior to fuelload. An applicant for a COL may proceed at its own risk with design and procurement activities, and a holder of a COL may proceed at its own risk with design, procurement, construction and preoperational activities, even though the NRC Staff may not yet have agreed j l
that any particular ITAAC have been satisfied. In the event of a noncompliance with an ITAAC, the applicant or holder of a COL shall either take corrective 1.0-2 Introduction 1
s . Rtv. 4 ABWR oesign controi oocumentantroduction ! i l. i actions to successfully complete the ITAAC or request a change in the ITAAC m l accordance with the change processes specified in the design certification rule ! for the ABWR. 1 Interface Reauirements - The Tier 1 Interface Requirements identify the j significant criteria forinterfaces between systems within the scope of the ABWR i standard design and other systems that are wholly or partially outside the scope of the ABWR standard design. The Tier 1 Interface Requirements define the
- significant attributes and performance characteristics that the out-of-scope l portion of the plant must have in order to support.the certified design. The l l plant-specific SAR shall contain provisions which implement the Interface ;
Re,quirernents in accordance with 10CFR 52.79(b). Additionally, the plant- ! l specific application for COL shall contain additional ITAAC corresponding to l these implementing provisions. In the event of an inconsistency between the Tier 1 Interface Requirements and the Tier 2 material, the Tier 1 Interface Requirements shall govern. i - Site Parameters -The Tie'r1 Site Parameters identify the significant design l values for site-related information used for the ABWR standard design plant. Detailed design activities for structures, systems, and components within the scope of the ABWR standard design shall be performed with reference to the Site Parameters. For cases where a site-specific characteristic is not bounded by a Site Parameter, the COL applicant may request a change in the Site l l Parameters in accordance with the change processes in the design certification I rule for the ABWR. Design activities for structures, systems, and components l outside the scope of the ABWR standard design may be performed using site-specific design basis parameters. In the event of an inconsistency between the Tier 1 Site Parameters and the Tier 2 material, the Tier 1 Site Parameters shall govern. 3.3 Uses of the Approved Safety Analysis Material The following provisions describe the scope and uses of Tier 2 material: !
- Effect of Tier 2 - All of the information in Tier 2 is approved by the NRC, is i applicable (except as described bel 6wwith respect to COL License Information items and Conceptual Designs) to a license application or license that references the ABWR design certification rule, and is among the " matters resolved" under 10 CFR52.63(a)(4). Compliance with Tier 2 material is a sufficient but not a necessary method for complying with Tier 1 material. The l methods specified in Tier 2 shall be followed unless a change is made in ;
accordance with the change processes specified in the design certification rule 1 for the ABWR. l Introduction 1.0-3 l
. a R:v. 4 ACWR oesion controt oocumenttintroduction l
l - JOL License Information Items - Tier 2 identifies certain matters that need to be addressed by an applicant or licensee that refe'rences the design certification for the ABWR. These matters are designated as " COL License Information." The purpose of the COL License Infonnation items is to identify the type of information that must be addressed in plant-specific SARs that reference the design certification rule for the ABWR. These COL License Information items do not establish requirements; rather they identify an acceptable set of information, but not the only acceptable set ofinformation, for inclusion in a plant-specific SAR. An applicant may deviate from or omit these COL License Infonnation items, provided that the deviation or omission is identified and jus,tified in the plant-specific SAR. Afterissuance of a license, the COL License i Information items have no further effect to that licensee; instead, the corresponding provisions in the plant-specific SAR are applicable.
- Conceptual Desiens - Conceptual designs for those portions of the plant which are outside the scope of the ABWR standard design are described in various places throughout Tier 2 (see, for example, the. conceptual designs referenced l in Tier 2 Section 1.1.2). As provided by 10 CFR 52.47(a)(1)(ix), these conceptual designs are not a part of the design certification for the ABWR and are not applicable to a COL, nor to an application for a COL, that references the design certification rule for the ABWR.
3.4 Use of ITAAC During Operation . In accordance with 10 CFR 52.103(g), the Commission must find that the acceptance criteria in the ITAAC are met prior to operation. After the NRC has issued its finding in accordance with 10 CFR 52.103(g), the ITAAC do not, by virtue of their inclusion in the < DCD, constitute regulatory requirements for the COL holder or for renewals of the COL However, subsequent modifications must comply with Tier 1 Design Descriptions, unless changes are made in the Tier 1 Design Descriptions in accordance with the change processes in the design certification rule for the ABWR. 3.5 Plant-Specific Changes to Certain Designated Material in Tier 2 (Tier 2*) Certain information within sections of Tier 2. identified in Table 1 is designated with brackets, italicized text, and an asterisk (or similar symbol). A plant-specific change to any of this designated information shall require NRC Staff approval prior to implementing the change. A request for departure from Tier 2
- will be treated as a request for license amendment under 10 CFR 50.90 and 50.92. The requirement for prior NRC Staff approval will expire for some of the designated information, as indicated in Table 1, when the plant first achieves 100% power.
t l 1.M Introduction
Rev. 4 ABWR oesion contros oocumenttintroduction i N 3.6 Proprietary and Safeguards Inforrnation l The proprietary and safeguards information referenced in the DCD must be included as part of an application for a COL i 3.7 References in Tier 2 to the Standard Safety Analysis Report To enable Tier 2 to have the same section numbezing system as the Standard Safety Analysis Report (SSAR) for the ABWR, the SSAR secdon numbers were used in preparing Tier 2. In some instances, secdons or information from the SSAR, such as l details of the probabilistic risk assessment, were deliberately not incorporated in the DCD. Tier 2 references or cross-references to those sections in the SSAR shall not be construed as incorporating these sections, or the information therein, in Tier 2. 3.8 Severe Accident issues A proposed plant-specific departure from Tier 2, under Section B.5 of the change process in the design certification rule, affecting resolution of a severe accident issue , involves an unreviewed safety question if: (1) there is a substantial increase in the probability of a severe accident such that a particular severe accident pre.iously reviewed and determined to be not credible could become credible; or (2) there is a substantialincrease in the consequences to the public of a particular . severe accident previously reviewed. 1 i i I l l l
. i i
i l l Jntroduction 1.'0-5
mv. 4 AMR oesiun controioocument/ introduction Table 1 Designated Tier 2 Material Which May Not be Changed Without Prior NRC Staff Approval , Designated Reference"3 Designated Material Expiration t21 , Table 2 ASME Boiler and Pressure Vessel Code, Section Ill, Division First Full 2, Subsection CC/ACI 359 and Division 1, Subsection NE Power Tables 3 and 4 ANSI /AISC N-690 and ACI 349 First Full , Power Table 5 Motor-Operated Valves First Full Power . Table 6 Equipment Seismic Qualification Methods First Full Power Table 7 Piping Design Acceptance Criteria First Full Power Table 8 Fuel System: Design Criteria and First Cycle Design and .See Table 8 ! Methods Table 9 Instrument Setpoint Methodology; Regulatory Guide 1.105 First Full Power Table 10 EMS Performanco Specifications and Architecture First Full Power i Table 11 SSLC Hardware and Software Qualification First Full Power Tier 2, Self-test System Design Testing Features and Commitments First Full Subsections 7.1.1.2, Power 7.1.2.1.6, Table 1.8-21 Tier 2, Appendix 18E HFE Design and implementation Process First Full and Table 1.8-21 Power Note: (1) Tables 1 through 11 identify those Tier 2 sections, tables, and figures which, in whole or part, contain Tier 2* information. Within the identified secuans and tables, the part which is Tier 2* is designated by means of italicized print, brackets, and an asterisk (or similar symbol). The identified figures are designated as Tier 2* in their entirety (although only the tides of the figures are italicized, bracketed, and asterisked). In some cases, the designated Tier 2* information contains references to other sections, tables, or figures in Tier 2. A referenced section, table, or figure itself is not Tier 2*, unless the referenced section, table, or figure is designated somewhere in Tables 1 through 11. la some cases, the designated Tier 2* information contains references to external documents. The applicable provisions within the external documents shall be treated as Tier 2*. The parucular edition or revision of the external reference is identified with the external reference itself. If the reference does not identify a particular edition or revision, the a Table 1.8-19,1.8 20, pplicable provisions or 1.8 21 shall be treatedof asthe Tieredition 2*. or revision identified in Tier 2 (2) The requirement for prior NRC Staff approval expires as noted. g,0 5 Introduction
-. .. - . . ~ . . . . ~ - - - _ . _ _ - - - - -
s ~~ s RIV.1 ACWR oesion controioocumentnatroduction l Table 7 Piping Design Acceptance Criteria (1) Tier 2 Tables and l Commitment 11er 2 Sections (2) Figures (23 (33 l Intersystem LOCA 3.9.3.1 Pipe Support Jurisdictional Boundaries 3.9.3.4.1 Pipe Support Baseplete and Anchor Bolt Design 3.9.3.4 Use of Energy Absorbers and Limit Stops 3.7.3.3.1.7, Table 1.8-20 3.9.3.4.1(6)(a) Use of Snubbers 3.9.3.4.1 Decoupled Branch Pipe - Displacement Criteria 3.7.3.3.1.4 l Seismic Self-Weight Excitation 3.7.3.3.4 l l Supplementary Steel 3.9.3.4 Friction Forces 3.7.3.3.4 Gaps Between Pipe and Supports 3.7.3.3.4 Instrumentation Line Support Criteria 3.7.3.8.1.9, 3.9.3.4.1 j Pipe Defection Limits 3.9.3.4.1 l Pipe-Mounted Equipment Allowable Loads 3.9.3.1.21 1 As-Built Piping Verification 3.9.3.1.20,3.9.8 (Ref. 3.9-10) Pipe interferences 3.9.3.1.22 Postulated Break and Crack Location and 3.6.2.1.4.1 through Configuration 3.6.2.1.4.5, 3.6.2.1.5.2, 3.6.2.1.5.3 ( l Dynamic Analysis for Postulated Break 3.6.2.3.1, 3.6.2.3.2 l l Notes: (1) See Tier 2, Subsection 3.9.1.7. The change restriction noted in this subsection applies to the l' delineated commitments only in their application to piping design. l (2) The applicable portions of these sections, tables and figures are italicized on the sections, tables ! and figures themselves. See Note (1) of Table 1. (3) Tables " 8-21 and 3.2-3 are applicable to a commitment involving the ASME Code, Section III, and Tables 5.2-1 and 1.8-21 are applicable to a commitment involving the ASME Code, Section III, Code Cases. f l introduction I* 0 ' '
~
, a Rzv. 4 ABWR oesign controloocumenantroduction Table 8 Fuel System: Design Criteria and First Cycle Design and Methods UI Tier 2 Tables Commitment Tier 2 Sections (2) and Figures (2I Expiration m l Fuel System Design 4.2.2.1, 4.2.5 First Full (Reference 4.2-1) Power Fuel Assembly Design 4.2.2, 4.2.5 Figures 4.2-1, First Full (Reference 4.2-1) 4.2-2 Power Nuclear Design 4.3.2.1 Figure 4.3-1 First Full Power l Fuel Evaluation Methods and Results 4.2.3 Table 1.8-19 None (References 4.2 2, 4.2-3)
Equilibrium Cycle and Control Rod Patterns 4A.1, 4A.2, 4A.3 - First Full Power Fuel Licensing Acceptance C'riteria and Fuel 4.2, App. 4B Table 1.8-19, ,None Burnup Limits Table 1.8-21 Control Rod Licensing Acceptance Criteria App. 4C First Full Power Notes: (1) See Tier 2. Section 4.2. (2) The applicable portions of these sections, tables and figures are italicized on the sections, tables. and figures themselves. See Note (1) of Table 1. (3) The requirement for prior NRC Staff approval expires as noted. Table 9 Instrument Setpolit Methodology") Commitment Tier 2 Sectionst2) Tier 2 Tablestz Instrument Setpoint Methodology 7.1.2.10.9, 1.8-20 7.2.2.2.1(6), 7.3.2.1.2(3)(f), 7.3.4.(Ref. 7.3-2), 7.4.2.3.2(3)(f), 7.6.2.1.2(3)(f), 7.6.2.6.2(3)(f) Notes: (1) See Tier 2, Subsection 7.1.2.10.9. (2) The applicable portions of these sections and tables are italicized on the sections and tables themsch'es. See Note (1) of Table 1. 1.0 12 Introduction
I r t R1v. 0 l l ACWR Design controloocumenener2 l Table 131 Comparison of Nuclear Steam Supply System Design Characteristics (Continued) This Plant GESSAR NMP-2 Grand Gulf f ABWR BWR/6 BWR/S BWR/6 ! Design 1 278-8722 238-748 251-764 251-800 incore Neutron instrumentation (Chapters 4 and 7) Total number of LPRM detectors 208 164 172 176 l Number of incore LPRM penetrations 52 41 43 44 Number of LPRM detectors per 4 4 4 4 penetration Number of SRM penetrations 5 4 , 4 6 - Number of IRM penetrations 105 8 8 8 Total nuclear instrument penetrations 62 53 43 58 Source range monitor range 5 6 6 N/A ; Intermediate range monitor range 6 6 6 N/A ; Startup range neutron monitor 8 N/A N/A N/A , Power range monitors range Approximately 1% power to 125% power Local power range monitors 208 164 172 176 Average power range monitors 4 4 6 8 l Number and type of incore neutron 5 Sb-Be 7 Sb-Be 7 Sb-Be 7 Sb-Be source Reactor Vessel (Section 5.3) ' Material Low-alloy Low-alloy Low-alloy Low-alloy steet/ steel / steel / steel / stainless stainless stainless stainless andNi-Cr-Fe clad clad clad alloy clad i Design pressure (psig) 1250 1250 1250 1250 Design temperature ('F) 575 575 575 575 I Inside diameter (ft-in.) 23-2 19-10 20-11 20-11 Inside height (ft-in.) 68-11 70-4 72-5 72-7 Minimum base metal thickness 7.50 6.0 6.19 6.19 (cylindrical section) (in.) Minimum cladding thickness (in.) 1/8 1/8 1/8 1/8 l l l l l Comparison Tables 1.3-5 l
~
I \ ruv. 4 ACWR oesion controloocumenstrier2 i l Table 1.3-1 Comparison of Nuclear Steam Supply System Design Characteristics (Continued) ; l This Plant GESSAR NMP-2 Grand Gulf ABWR DWR/6 BWR/5 BWR/6 Design' 278-8722 238-748 251 764 251-800 Reactor Coolant Recirculation (Chapter 5) Number of recirculation loops 0 2 2 2 Design pressure inlet leg (psig) N/A7 1250 1650 1250 outlet leg (psig) 7 8 N/A 16508 1650 1650 8 l 15508 , 1550 15508 Design temperature ('F) N/A7 575 '575 575 I Pipe diameter (in.) N/A7 22/24 24 24 l Pipe material (ANSI) N/A 7 304/316 316k 304/316 Recirculation pump flow rate (gpm) 30,430/ 42,000 47,200 44,600 pump Number of jet pumps in reactor N/A7 20 20 24 Main Steamlines (Subsection 5.4.9) Number of steamlines 4 4 4 4 Design Pressure (psig) 1250 1250 1250 1250 Design temperature ('F) 575 575 575 575 Pipe diameter (in.) 28 26 26/28 28 Pipe material Carbon Carbon Carbon Carbon , steel steel steel steel 1 English units are utilized in this table since the data obtained from the comparative BWR operating ! facilities are in English units. 2 Parameters for the core loading in Figure 4.3-1 used in the sensitivity analysis. l 3 Proprietary information not included in DCD, (Refer to SSAR Section 1.3, Amendment 32). 4 Free-standing loaded tubes. 5 SI tdown through criticality. 6 Prior crhicailty to low power. 7 ABWR design utilizes reactor internal pumps (RIPS). 8 Discharge piping from discharge block valve to vessel. 9 Pump and discharge piping to and including discharge block valve.- l ' t t.36 Comparison Tables
o -- Rocr. 3 , ABWR oesign controtcocumenttrier1 \ . l
\ FROM SURGE TANK HECW HVAC 3
HVAC HECW 3 l , RCW y REACTOR BUILDING HVAC HECW 3 l ! SYSTEM (SAFETY RELATED ,, ELECTRICAL EQUIPMENT HVAC) i I l CONTROL BUILDING SAFETY RELATED EQUIPMENT :_: AREA HVAC SYSTEM 8 3 NNS TO CHEMICAL NNS 3 1 ]_ ADDITION TANK _ M. _ g y S N REFRIGERATOR o
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Figure 2.11.6a HVAC Emergency Cooling Water System (HECW-A) HVAC Emergency Cooling Water System 2.11.6 3
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) DIVISIONS B AND C ARE POWERED FROM CLASS 1E, ,
DIVISION 11 AND 111, RESPECTIVELY. I Figure 2.11.6b HVAC Emergency Cooling Water System (HECW-B and C) 2.11.6-4 HVAC Emergency Cooling W%er System
l Rtv. 0 ABWR oesign controloocumenener2 l I Table 381 Pool Swell Calculated Values Description Value
- 1. Air bubble pressure (maximum) 133.37 kPaG l
- 2. Pool swell velocity (maximum) P.0 m/s
- 3. Wetwell airspace pressure (maximum) 107.87 kPaG
- 4. Pool swell height (maximum) 7m l
I I l l I 1 e l Containment Hydrodynamic Loads 38-33
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YES V ( DEVELOP ABWR / DESIGN CH SOURCE V ABWR ABWR CONTAINMENT. > CONTAINMENT FACILITY MODEL DESIGN CH LOADS 1 Figure 3B-26 ABWR Chug Source Load Methodology Containment Hydrodynamic Loads 38-65
-4%CA -' '* "' ^
3 g 4 .a 3 g_4A 4 4a 4 - 'M* *-8 ' I ig Figure 3B-27 [ Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] . m P s A o tl3 R s-T 2 p a 4
= . a k ~
e S ; 8. E il a a. y 3 z w a
. - _ - - - - . - _ . - - _ - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ' - - - - - - - - - - ' - - - - - - - - " - ~ ^ - - - - - - - - - - - ^ ^ ~ - ~ ^ - - ' ^^ ^ ^~ ~ ~ ~ ~
e - O Rzv. 0 ABWR oesign controsoocumentirier2 A A A A. A A A A A A p 0.33 0.70 ACCESS TUNNEL (BOTTOM) A LINEAR LINEAR
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=,
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LINEAR
=_ ->
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I v v I lv v v v v v v v 1.0 1.0 Figure 3B-23 Spatial Load Distribution for CH Containment Hydrodynamic Loads 38-67
- . - - - - - - - - - - - -,, , n_-,---, --------, -- , ----- ----- - ,-,- - --,--- ,-------- --- , Figure 3B-29 [ Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] ll O l f O 4 A 4 e l 9 $ I
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1 o I a E
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(\ / h f CUUO , y l l l H = POOL DEPTH AT H.W.L l i y
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l I
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d a i Figure 3B-30 Circumferential Pressu're Distribution on Access Tunnel Due to CH l Containment Hydrodynamic Loads 38-69 l
~~
O e i R:v. 4 ABWR nesion controloccamentmer2 l l Figa, e 3B 31 [ Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] l l l l I l l l I l 1 l l l l 1 l 1 38-70 Containment Hydrodynamicloads l
g ,g. g ~ . .A% - 4' .. bi A M jy Figure 3B-32 [ Proprietary information not included in DCD (Refer to SSAR Appendix 3B, Amendment 34)] 9.
=
3 i d I e - E 3 3 n' O E t A {
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= 1
=
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l _ u a Mey. 4 > ADWR oesign controloocument/rier2 l i l Fi'3ulte 3B-33 [ Proprietary information not included in DCD (Refer to SSAR l Appendix 3B, Amendment 341] l l ? l t I ( l l l l l ! i I. i l l l
)
i 1 i l 1 i l 4 l 38 72 Containment Hydrodynamic Loads
l Rzv. 4 l ABWR oeriga controloocumenvrier2 l i i i i Figure 3B-34 [ Proprietary information not included in DCD (Refer to SSAR
- _ Appendix 3B, Amendment 34)]
l I i I I l l 1 I i l' i l l l t l l I e Containment Hydrodynamic Loads 3 8-73/74
i
~
S tJ i Rsv. o \ .ABWR oesion controloccamenener2 t L-l t f- 4 4 4 1 ' ~ NOTE: LOADING PATTERN IS SHOWN FOR QUARTER CORE ONLY ROTATIONAL 4 4 4 2 2 1 2 SYMMETRY APPLIES. 4 2 2 1 1 2 2 3
,4 4 4 1 2 1 '1 2 1 2 -4' l
4 2 2 1 2 1 2 3 1 2 1 'S 4 2 1 1 2 1 2 2 1 2 3 2 6 I 4 2 2 1 2 1 2 3 1 2 3 1 3 '7 - l- 4 2 1 1 2 1 1 2 1 2 3 1. 2 1 8 ! 4 l2 u 1 2 1 3 3 1 2 3 1 2 1 3 9 .
- __ _ _ _ __ _ i r
4 1 2 1 1 3 3 1 3 1 2 2 1 3 10 i 4 1 2 1 2 2 1 1 2 1 2 3 1 2 1 11 4 2 2 1 2 3 1 2 3 *1 2 1 1 2 3 2 12 ! 4 2 1 2 2 1 2 3 1 2 1 3 3 2 1 3 13 4 1 1 3 1 2 3 1 2 3 1 3 3 1 2 1 14 l 4 2 1 2 1 2 3 1 2 2 1 2 2 1 2 3 2 15 '
= j 4 1 2 1 2 3 1 2 1 1 2 3 1 2 3 2 16 1
4 l 2 1 l 2 3 l 1 2 l 2 3 l 3 2 l 1 2 l 3 2 3 17 I I 1 l !' I I I I I I i i j J --> 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 l l 4 BUNDLE TYPE ENRICHMENT NUMBER OF BUNDLES l 1 HIGH ENRICHMENT,3.18 WT % 308 ' 2 MEDIUM ENRICHMENT,2.18 WT *4 324 -; i I 3 LOW ENRICHMENT,1.23 WT % 148 : 4 NATURAL URANIUM,0.71 WT % 92 I f
*See Section 4.2 for, restriction to change this figure.- !
} 4 ' l . ii l_ lFigure 4.3-1 Core Loading Map Used for Response Analyses)* } Nuclear Design 4.3-9 e - . -u e n,w -
-w ,, n -+-
. . . . . .. ._..- .. . . . . _ - . . . . , . - . -.- .-_ _ - _.-._= -.. - .. -
a e R3v. 4 ABWR Deso.gn ControlDocumenVTier2 _7_. 1 Figure 4.3-2 [ Proprietary information not included in DCD (Refer to SSAR 1 Section 4.3, Amendment 31)] l l i j l l l . i a 1 l
)
i I l I l i l 4.3-10 NuclearDesign
l Rsv. 4 ABWR oesion controloocumentirier2 l l l Figure 4A-1a [ Proprietary information not included DCD (Refer to SSAR l Appendix 4A, Amendment 34)] ! 4 l l l l l I l
)
I 1
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l l l l 1 l l l l l l I I i 1 4 Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A 3
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$ 1.0 -
E W P . 5 E 0.5 = I ' ' ' ' O 1 5 9 13 17 21 ) l AXIAL NODES Figure 4A-1c Relative Axial Exposure at 8.5 GWd/t Cycle Exposure (Haling) 4A4 Typical Control Rod Patterns and Associated Power Distribution for ABWR
R>v. 4 ABWR Desm.a ControlDocument/ Tier 2 Figure 4A-1d [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] Figure 4A-le [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] l i I l 1 i I l . i e Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A-5 I
Rsv. 4 ABWR Design ControlDocumenVTier2 1 Figure 4A-2a [ Proprietary information not included.DCD (Refer to SSAR Appendix 4A, Amendment 34)] l l 1 I i I l 1 e 4A4 Typical Control Rod Patterns and Associated Power Distribution for ABWR
e -- .. Rev.o ABWR oesion controtoocumentmer2 i , 2.0 l l I 1.5 - 2 l 4
~
l g 1.0 ; I w b 2 m 0.5 , I t l L l + 1 i f f i l j 1 5 9 13 17 21 j AXIAL NODES
)
- I Figure 4A-2b Relative Axial Power at 9.0 GWd/t, Cycle Exposure (Haling) 2.0 l
l I l 1.5 E l 8 2 - 5 l y 1.0 - l E l l W i E 2 c 0.5 I l l t 1 I 0-1 5 9 13 17 21 AXIAL NODES 4 Figure 4A-2c Relative Axial Exposure at 9.0 GWd/t Cycle Exposure (Haling) Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A.7 l -
s e R1v. 4 ABWR oesign controloocumentmer2 Figure 4A-2d [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] Figure 4A-2e [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] l l l l l i l 4A,8 Typical Control Rod Patterns and Associated Power Distribution for ABWR
.. . . . , = _ = . -. .. . . - . - _ _ . ._ _.-. .~. - . - . . - .
i R1v. 4 ABWR Deso.gn ControlDocument/ Tier 2 , I \ Figure 4A-3a [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] l l l i l l i l i t F 1 4 I l 1 l l i i l l l l l l l 4 I Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A-9
~
Rzv. o ACWR oesign controloccamenttrier2 2.0 1.5 - 1 E l 2 1
~
Y E 1.0 - E s-0.5 - l , l 0 I ' ' ' ' 1 5, 9 13 17 21 l AXIAL NODES Figure 4A-3b Relative Axial Power at 0.2 GWd/t Cycle Exposure l l 2.0 l 1 1.5 = E 8 2 ' a a j 1.0 - W p a 0.5 1 I f f f 0 1 5 9 13 17 21 AXIAL NODES Figure 4A-3c Relative Axial Exposure at 0.2 GWd/t Cycle Exposure 4A 10 Typical Contro: Rod Patterns and Associated Power Distribution for ABWR
. -- 0 R2v. 4 ABWR oesign controloocumentmer2 Figure 4A-3d [ Proprietary information not included.DCD (Refer to SSAR Appendix 4A, Amendment 34)] Figure 4A 3e [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)]
.a Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A 11
. . . . . . . . . . . -. ..- .... .. .. - - .-. - _ . _ . . - = . . - . . . . . - - .
O . RJv. 4 i ABWR Design ControlDocument/ Tier 2 1 i j Figure 4A-4a [ Proprietary information not included.DCD (Refer to SSAR Appendix 4A, Amendment 34)] l l I l l l t l l l f l l I i i 1 l I l ^
"A*12 Typical Control Rod Patterns and Associated Power Distribution for ABWR
7 l l s ~ 0 Rsv. O ACWR oesign controloocumenvrier2 2.0 l l l l 1.5 E E l 2 - g - E 1.0 l s l P i 5 0.5 i l f f t l I 0 1 5 9 13 17 21 AX1AL NODES Figure 4A-4b Relative Axial Power at 1.1 GWd/t Cycle Exposure l 2.0 l 1.5 - , E 1 B Y 1.0 - s s 5 E 0.5 i I I f f 4 1 5 9 13 17 21 AXIAL NODES ( j Figure 4A-4c Relative Axial Exposure at 1.1 GWd/t Cycle Exposure Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A 13
s . l l R2t 4 Design Contsof Document / Tier 2 i i i Figure 4A-4d [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] Figure 4A-4e [ Proprietary information not included 'Jt3 ' Refer to SSAR Appendix 4A, Amendment 34}] l 4A-14 Typical Control Rod Patterns and Associated Power Distribution for ABWR
Rev.4 ACWR . Design ControlDocumentflier2 Figure 4A-Sa [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] f I l l l I i I 1 l 1
. 1 l
l l i I J Typical Control Rod Patterns and Associated Power Distribution for ABWR gA.g5 l , -
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R>v. o ABWR Design ControlDocument/ Tier 2 l 2.0 1.5 _ h e a s - - E 1.0 _
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a 0.5 - O I I I I i 1 5' 9 13 17 21 AXIAL NODES Figure 4A-5b Relative Axial Power at 2.2 GWd/t Cycle Exposure 2.0 1.5 - E , j
?n 2 '
5 , i 1.0 _ i E l
\
q . 0.5 I i l 0 1 5 9 13 17 21 AXIAL NODES Figure 4A Sc Relative Axial Exposure at 2.2 GWd/t Cycle Exposure i 4A-16 Typical Control Rod Patterns and Associated Power Distribution for ABWR
Rett. 4 ABWR Design controloocumenvrier2 Figure 4A-5d [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] i l Figure 4A Se [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] l I I Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A-17
. . - . . . . - _ . . - - - - - - . - . . - - . . . - - . - . - . - . _ . - . . . ~ . - . . . _ . . . . - j R1v. 4 ABWR oesign controlDocumattrier2 i Figure 4A-6a [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] 1 l l l l 1 I 4A-18 Typical Control Rod Patterns and Associated Power Distribution for ABWR l
Rev.O ABWR oesign conuotoocumenvrier2 l 2.0 1.5 _ h 2 ' \ d 5 1.0 - l l W p cc l 0.5 l 0 ' ' I 8 ' l 1 5 9 13 17 21 l AXIAL NODES Figure 4A-6b Relative Axial Power at 3.3 GWd/t Cycle Exposure l 2.0
. i l
l 1.5 - E R 2 ' 5
$ 1.0 -
)
E W p 5 E 0.5 4 4 0
' I I I '
1 5 9 13 17 21 AXIAL NODES Figure 4A-6c Relative Axial Exposure at 3.3 GWd/t Cycle Exposure Typical Control Rod Patterns and Associated Power Distrit>ution for ABWR 4A 19
~
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5 R>v. 4 ABWR oesion controloccamentmer2 1 Figure 4A-6d [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] t Figure 4A-6e [ Proprietary information not included DCD (Refer to SSAR ; Appendix 4A, Amendment 34)] ; l I a l 4A-20 Typical Control Rod Patterns and Associated Power Distribution for ASWR
.. . - .. .- ~ _ - . - .-_. . - . . . . . , . . . . .. . .__
e
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)
l l l l l 1 l l l l l Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A-21
Rsv. o ABWR Design ControlDocumenVTier2 1 2.0 _ I l 1.5 _ s E 2 a f I <
< 1.0 -
I l W 5 d E * , l 0.5 1 I I I I t 1 O 1 5 9 13 17 21 AX1AL NODES 1 I 1 Figure 4A-7b Relative Axial Power at 4.4 GWd/t Cycle Exposure l 1 2.0 l 1.5 W 8 o Q # w
$ 1.0 -
a sA 0.5 - l g 1 I i 1 ' O 1 5 9 13 17 21 AXIAL NODES l Figure 4A-7c Relative Axial Exposure at 4.4 GWd/t Cycle Exposure 4A-22 Typical Control Rod Patterns and Associated Power Distribution for ABWR
o/ ! Rev. 4 ABWR o,,;ga c,,,,o1cocumenener2 Figure 4A-7d [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] Figure 4A-7e [ Proprietary information not includ-d DCD (Refer to SSAR i Appendix 4A, Amendment 34)] l Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A-23 _1
... = . . . . = = - _ _ _ _ . - . . . - . . . - .-. - - .. .
Rsv. 4 ABWR oesign contraroocumenener2 1 Figure 4A 8a [ Proprietary information not included DCD (Refer to SSAR l Appendix 4A, Amendment 34)] i 9 i l I
\
1 I 1 i l k 4A-24 Typical Control Rod Patterns and Associated Power Distribution for ABWR
.. __ . = _ . - . _ _ _ - -- _ - _ _ _ - - .. - - -_.. - . - _ . . -
, -- ) Rsv. 0 ABWR oesign controloocumenuner2 2.0 1.5 . 5 a g 1.0 - W 3 E 0.5 0
' ' I ' '
- 1 5 9 13 17 21 AXIAL NODES Figure 4A-8b Relative Axial Power at 5.5 GWd/t Cycle Exposure 2.0 1.5 -
E 8 2 g 1
$ 1.0 -
Q W e 0.5 i t f t ' 0 1 5 9 13 17 21 AXIAL NODES Figure 4A-8c Relative Axial Exposure at 5.5 GWd/t Cycle Exposure Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A-25
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- . - ~ - - . _ _ _ . -
, - ;)
Rsv. 4 ABWR Desm.a ControlDocument/ Tier 2 Figure 4A-9a [ Proprietary information not included DCD (Refer to SSAR ' Appendix 4A, Amendment 34)] l l f r t l 1 l I l I l l l \ i l t t l Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A-27 l
- _ . _ _ _ _ _. -_ _ . _ . . . . _ _ . _ _ _ -. _ ___ _ ._ ~ . . _ _ _ .-. ._ _ _ _ . . _ .
l
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, cc ! E 2 { - E 1.0 - W p l 0.5 - 0 I I I I I 1 5 9 13 17 21 AXtAL NODES Figure 4A-9b Relative Axial Power at 6.6 GWd/t Cycle Exposure l l 2.0 1.5 . E 8' 2 ' 6 g 1.0 _
< i k
i 0.5 l 4 l i l i I i g 1 5 9 13 17 21
. AXIAL NODES Figure 4A-9c Relative Axial Exposure at 6.6 GWd/t Cycle Exposure 4A 28 Typical Control Rod Patterns and Associated Power Distribution for ABWR
e
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l Figure 4A 9d [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] l Figure 4A 9e [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] i i i i 1 I i l I l l l l l . l l Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A 29 l l
1 Riv. 4 ABWR oesion controloocumentmer2 Figure 4A-10s [ Proprietary information not included DCD (Refer to SSAR l Appendix 4A, Amendment 34)] l l l l l 1 l 4A 30 Typical Control Rod Patterns and Associated Power Distribution for ABWR
. -- , ) .-i
\
Rsv. O ABWR . Destgn ControlDocument/ Tier 2 2.0 1.5 - h i e 4 x j 1.0 - 3 2 x 0.5 - 0
' I I 8 1 1 5 9 13 17 21 AXIAL NODES Figure 4A-10b Relative Axial Power at 7.7 GWd/t Cycle Exposure 2.0 l
I
.I 1.5 -
8 e t$ N 1.0 = 4 . y 3 e 0.5 I- I I I I 0 1 5 9 13 17 21 AXIAL NODES Figure 4A-10c Relative Axial Exposure at 7.7 GWd/t Cycle Exposure Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A-31
s e Rsv. 4 ABWR Design ControlDocumentfTier2 Figure 4A-10d [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] Figure 4A-10e [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Ame'ndment 34)] i l i i 1 1 4A-32 Typical Control Rod Patterns and Associated Power Distribution for ABWR
, -- ,i Rzv. 4 ABWR Design ControlDocumentfrier2
[ Figure 4A-11a [ Proprietary information not included DCD (Refer to SSAR j Appendix 4A, Amendment 34)] i l t 1 1 i l l I i l Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A-33
s e R1v. O I ABWR Deso.gn ControlDocument/ Tier 2 i 2.0 1.5 = x a = 1.0 - E. e E 0.5 -
' I I I i 0
1 5 9 13 17 21 AXIAL NODES Figure 4A-11b Relative Axial Power at 8.0 GWd/t Cycle Exposure 2.0 1.5 - e 2 ' 6 l< 1.0 - E s-1 e l 0.5
' ' I I i 0
l 1 5 9 13 17 21 l AXIAL NODES Figure 4A-11c Relative Axial Exposure at 8.0 GWd/t Cycle Exposure M Typical Control Rod Patterns and Associated Power Distribution for ABWR
l e -- ,a Rev.4 l ABWR oesion controloocumentmer2 Figure 4A-11d [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] l Figure 4A-11e [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] t l l l r l l l l l l I l l i l l 1 I i Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A-35 i i
. , - a
RJK 4 ABWR oesign controsoocumentmer2 i 1 ! Figure 4A-12a [ Proprietary information not included DCD (Refer to SSAR . Appendix 4A, Amendment 34)] l i 4A46 Typical Control Rod Patterns and Associated Power Distribution for ABWR
. . .._ .- .- - .. . .- . - . . .. - . _. . - . . . ._, - . ~ . .- _
+ -- ,.
Rev.0 l t l ABWR oesion controtoacumenvrier2 l l 2.0 l 1.s _ , l l C l E e ~ d {m 1.0 l l B , 5 l E 0.5 t t t t t O 1 5 9 13 17 21 AXIAL NODES l l Figure 4A-12b Relative Axial Power at 8.4 GWd/t Cycle Exposure I l I 2.0 l l ! I l l 1.5 - l l w
'5v>
2 ' l a
.,,8 i
y 1.0 -
< l y l 8
c: 0.5 0 1 5 9 13 17 21 i AXIAL NODES t Figure 4A-12c Relative Axial Exposure at 8.4 GWd/t Cycle Exposure Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A 37 i
4. e-
-3 Rsv, 4 ABWR Design ControlDocument/ Tier 2 Figure 4A-12d [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)]
Figure 4A-12e [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] 4 l a i 1 4 i 4A-38 Typical Control Rod Patterns and Associated Power Distribution for ABWR
,s R>v. 4 ABWR Desma ControlDocumenVTier2 l
Figure 4A-13a [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] 1 i 1 I I i i 4 l l l Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A 39
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, e Rrv. o ABWR Design ControlDocumenVlier2 2.0 1.5 i
1.0 - a
- 0.5 -
I I I I i l 0 1 5 9 13 17 21 AX1AL NODES l Figure 4A-13b Relative Axial Power at 9.0 GWd/t Cycle Exposure i
- 2.0 9
8 i 1.5 - m 2 s. , gj 1.e -
! W p
j 0.5
- l t l l t t 0
1 5 9 13 17 21 AX1AL NODES ~ Figure 4A-13c Relative Axial Exposu're at 9.0 GWd/t Exposure } 4A40 Typical Control Rod Panerns and Associated Power Distribution for ABWR 4
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l REV.4 ABWR oesign controtoccumenener2 Figure 4A-13d [ Proprietary information not included DCD (Refer to SSAR Appendix 4A, Amendment 34)] Figure 4A-13e [ Proprietary information not included DCD (Refer to SSAR j Appendix 4A, Amendment 34)] l l I l l l l r 6 I Typical Control Rod Patterns and Associated Power Distribution for ABWR 4A-41
t b 6 to 1.60 1.55 - i 1.50 - lE O ^ M 2 E n E 1.45 - 9 = 4 . R E R 1.40 g - t = 8 g- 1.35 - e a E ? 11 4 ~
= i B -
1 I I I I I I I I E i g 1.30 Q s 0 1 2 3 4 5 6 7 8 9 10 g s- = ') CYCLE EXPOSURE (GWd/MT) c 5 3 l Figure 4A-14 Minimum Critical Power Ratio (MCPR) as a Function of Cycle Exposure g ~. i s i i i
._.-________._._._________.____.________-__m_ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _,
o -- ,. i azv. 4 ABWR oesign controloocumenener2 l l 4B Fuel Licensing Acceptance Criteria l 48.1 Introduction A set of fuel licensing acceptance criteria has been established for evaluadng fuel designs and for determining the applicability of generic analyses to these designs. Fuel design compliance with the fuellicensing ac eptance criteria consututes USNRC acceptance and approval of the fuel design for inidal core and reload applications without specific USNRC review. [Thefuellicensing acceptance criteria arepresented in Reference 4B-1. Any change to these criteria must have priorNRC review and approval.]* 48.2 References l 46-1 [SSAR Sections 4B.2 through 4B.16, Proprietary Infonnation, Amendment 35]* l l
- See Secdon 4.2.
FuelLicensing Acceptance Criteria 48 1/2
. . . - . ., - - . . - _ _ . . _ .= . - - . . -. .. .- .
e -- , Rsv. 4 ABWR oesign controlDocumentmer2 4D Reference Fuel Design Compliance with Acceptance Criteria [ Proprietary information not included in DCD (Refer to SSAR Appendix 4D, Amendment 35).] I i l Reference FuelDesign Compliance with Acceptance Criteria 40-1/2 1
. I
l ? l 4 - n an. 4 h ABWR Desien controloocumentmer2 Chapter 6 :
. List of Tables ;
l Table 6.1-1 Engincered Safety Features Compon ent Matedals..... ....... . . . ...... .. ......... . . . 6.1-5 l ! l Table 6.2-1 Con tainm ent Param e ters ........ ... .... . ... .... . ...... . .. .......................... . .. .. 6.2-103 6
. Table 6.2-2 Con tainmen t Design Parameters.......... ............... . ..... .. .. . . ... ... . . ... . .. . 6.2-10 4 r
l Table 6.2-2a Engineered Safety Systems Information for Containment Res ' An al yses . . . .. . . . .. .. .. . .... . . . . . . .. ... . .. . . .. . . .. . . .. ... ...... . ... ... .. ... .. ... .6.2-10
. .. ..5.. . . . . . . . p on l
l Table 6.2-2b Net Positive Suction Head (NPSH) Available to RHR Pumps.. ..... ........... .6.2-107 ! l Table 6.2-2c Net Positive Suction Head (NPSH) Available to HPCF Pumps.. .. ... . .. 6.2-108 Table 6.2-2d Seconday Containment Design and Performance Data.. . .. . .. . .. .. . . . 6.2-109 Table 6.2-3 Subcompartment Nodal Description ........... . . . . . . . . . . . . . . . . . . . . ... .... . . ......... 6.2-1 12 Table 6.2-4 Subcompartmen t Vent Path Descdption .... .. . ................. ... . .... .. .............. 6.2-114 r Table 6.2-4a Flow Loss Fac to r ....... ..... ... . ... ... ...... . .. . . ........ . . .. . ... .. .. .. .. . .. . ... . . .. .. 6.2-1 16 : t Table 6.2-4b Mass and Energy Release Rate ... ...................... .... .... .... . . .. . .... . . .. . . .. .. .. . .. . . . 6.2-1 18 [ t Table 6.2-5 Reactor Coolant Pressure Bounday (RCPB) Influent Lines Penetrating . Dnwell....................................................................................................6.2-123 i Table 6.2-6 Reactor Coolant Pressure Bounday (RCPB) Effluent Lines Penetrating [ D rywell . . ... .. . . . . . . . . ... .. .. .. .. . . . .. . . . .... . . .... . . . . .. . . . .. . . . . . .. . . . . . .... .. . . . . . . . . . . . 6.2- 1 23 Table 6.2-7 Containment Isolation Valve Information... . ... ... ..... . ... . ... .. . .... .......... . 6.2124 j i Table 6.2-8 Primay Containment Penetration List... . .. . . . . . . . . .. . . . . . . . . .. . . . . . . . . . . . . . . 6. 2- 1 7 2 Table 6.2-9 Secondary Containment Penetration List.. ... .... . ........ ....... ...... . ... . ... . 6.2-182 Table 6.2 '10 Poten tial Bypass Leakage Paths .... ............................. ............ . . .. ... . . . .... 6.2-184 - Table 6.Sl Significant Input Variables Used in the Loss-of-Coolant Accident Analysis.... 6.S26 Table 6.S2 Operational Sequence of Emergency Core Cooling System Maximum Core Fl ood er Li n e Break. . .. . . .... ... . .. .. .. . ........ .... . .. . .. .... ... ... . .... . . .. . . ... ... .. . . . 6.S28 Table 6.S3 Single Failure Evaluation .......... .... . .. ..... . .... ......... ...... . ... . . . ... . . . ... . 6.S29 Table 6.S4 Sum mary of Results of LOCA Analysis........ ....... .... ............... . .. .... .. ... ... 6.3-30 Table 6.15 - Key to Figu res . ..... .... . .. ....... .. . . .. . . . . .. .. .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6. 3-31 [ g Table 6.S6 Plant Variables with Nominal and Sensitivity Study Values .. .... ... .. . . .. . . . 6.S32 l l List of Tables 6.0-lii l
Rxv. O ABWR oasion controioocumenvrierz l List of Tables (Continued) Table 6.S7 ' MAPLH GR Versus Exposure .... . ..... .. ..... .... . ... .. .... ... . ...... ..... ... . ..... . 6.S33 Table 6.S8 Design Parameters for HPCF System Components.. . . . . . .. .. .. . . . . . .. . . .. . . . . 6.S3 4 l Table 6.S9 Design Parameters for RHR System Components.......... .... . . . .. ... .. ... . . 6.S36 Table 6.S10 Single Failure Evaluation With One HPCF Subsystem Out of Senice... . .. ... 6.S39 Table 6.S11 Single Failure Evaluation With One RHR/LPFL Subsystem Out of Senice... 6.S-40 1 Table 6.S12 Single Failure Evaluation With ECCS Division A Out of Senice..... ...... .. . .. . 6.S41 1 Table 6.S13 Single Failure Evaluation With ECCS Division B Out of Senice........ .. ........ . 6.3-42 Table 6.S14 Single Failure Evaluation With ECCS Division C Out of Senice...... ..... ... ... 6.S43 Table 6.S15 Single Failure Evaluation With Two ADS Valves Out of Senice .......... .... . .. 6.344 i Table 6.4-1 Identification of Failure /Effect in the Control Room Habitability Area HVAC Sys te m . .. . . . . . . . . . . . .. . .. .. . . . .. . ... . . ... .. .. . .. . . . . . . . . . . . . . . .. . . . . .. . . .. . . .. . . . . . .. . . .. . . . . 6. 4- 1 2
]
Table 6.4-2 Control Room Habitability Area HVAC System Failure Analysis .......... ......... 6.4-13 l l l Table 6.51 Summary of Major Standby Gas Treatment System Components........ . ..... ... 6.5-14 ; Table 6.5-2 Source Terms Used for SGTS Charcoal Adsorber Design.. . . .. ... . ........... .. 6.5-16 l Table 6.61 Examination Categories and Methods .... ............................... ............. .... .... 6.6-11 Table 6.7-1 Ni trog e n Gas De m a n d . ........... ........ ........... ........... . . . ............ .. ... ....... . . . . ... .... 6.7-5 . Table 6C-1 Debris Analysis Inpu t Parame ters .... ....... ......................... .... . .... ....... ... .. ....... 6C-6 Table 6C-2 Resul ts of An alysis . . .... ... .... ................. ... .. ... . . ... ... ....... . . .. . . .. . . ... . . . . .. . .. . . 6 C-6 l l l l l l 1 i l 6.0-iv List of Tables . r
. i
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! l Table 6.3-5 Key to Figures Appendix K Evaluation Models ! Bounding Values l l Main Main Main Steamline Steamline Steamline inside - RHR LPFL Core Bottom Outside Outside Contain- Feedwater Suction injection Flood Drain Contain- Contain-ment Line Line ) Line Line Line ment ment l Core Flow 6.3-12 6.3-21 6.3-21 6.3-21 6.3-44 6.3-21 6.3-21 6.3-67 Minimum 6.3-13 6.3-22 6.3-22 6.3-22 6.3-45 6.3-22 6.3-22 6.3-68 Critical Power Ratio l Water Level ?.3-14 6.3-23 6.3-30 6.3-37 6.3-46 6.3-53 6.3-60 6.3-69 in Fuel f Channel
- Water Level 6.3 15 6.3-24 6.3-31 6.3-38 6.3-47 6.3-54 6.3-61 6.3-70 i inside Shroud l
Water Level 6.3-16 '6.3-25 6.3-32 6.3-39 6.3-48 6.3-55 6.3-62 6.3-71 Outside Shroud Vessel 6.3-17 6.3-26 . 6.3-33 6.3-40 6.3-49 6.3-56 -6.3-63 6.3-72 1 Pressure i Flow out of 6.3-18 6.3-27 6.3-34 6.3-41 6.3-50 6.3-57 6.3-64 6.3-73 Vessel l Flow into 6.3-19 6.3-28 6.3-35 6.3-42 6.3-51 6.3-58 6.3-65 6.3-74 l Vessel l Peak 6.3-20 6.3-29 6.3-36 6.3-43 6.3-52 6.3-59 6.3-66 6.3-75 l Cladding Temperature 1 i i l l I I Emergency Core Cooling Systems 6.3 31 I
~~ g a RDv, 4 ABWR oesian controloscamenwier2 Table 6.3-6 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)]
'N 6.3-32 Emergency Core Cooling Systems >
f . -- g Rev.O ABWR Design controloccumentmer2 The following figure is located in Chapter 21: l Figure 6.3-7 High Pressure Core Flooder System P&lD (Sheets 1-2) I The following figures have been deleted: : 1 l Figure 6.3-8 Not Used (See Figure 5.4-8) Figure 6.3 9 Not Used (See Figure 5.4-10) l l [ l l Emergency Core Cooling Systems 6.3-49
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., R1v. 4 ABWR onion controloocumenttrier2 4 Figure 6.3-10 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] i l l l l l l 6.3-50 Emergency Core Cooling Systems
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s ~~ ,, ACWR Design ControlDocumenVTier2 Figure 6.3-11 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)J l l I l l 1 l f Emergency Core Cooling Systems 6.3-51
y n < ? 1' Rev.4 ABWR Deso.ga ControlDocument/ Tier 2 i i Figure 6.3-12 [ Proprietary information not included in DCD (Refer to SSAR 4 Section 6.3, Amendment 34)] : I i Figure 6.3-13 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] l l 1 l I
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1 4 - os , Retr. 4 l ABWR oesion controloocumentirier2 l
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Figure 6.3-14 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] 1
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I Figure 6.3-15 [ Proprietary information not included in DCD (Refer to SSAR 4 Section 6.3,' Amendment 34)] Emergency Core Cooling Systems 6.3 S3 i
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L,3 4 Rev. 4 ABWR oesion controloocumenener2 i Figure 6.3-16 IProprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] i i ) Figure 6.3-17 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] 6.3-S4 Emergency Core Cooling Systems
e -- es Rsv. 4 ABWR oesign controtoocumenvrier2 Figure 6.3-18 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] t l l l 1 i 1 Figure 6.3-19 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] l l 1 l l l Emergency Core Cooling Systems 6.3-55
s, e ACWR Design ControlDocumentmer2 Figure 6.3-20 [Proprieta nformation not included in DCD (Refer to SSAR lon 6.3, Amendment 34)] l i Figure 6.3-21 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] l
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6.3-56 Emergency Core Cooling Systems
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~ ABWR oesign controloocumentmer2 l
1 Figure 6.3-22 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] l l l ? l I l t l l i ! t l l Figure 6.3-23 [ Proprietary information not included in DCD (Refer to SSAR l Section 6.3, Amendment 34)]' I i l l l t 3 5 i Emergency Core Cooling Systems 6.3-57
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- Rsv. 4 ABWR oesign controtoccumentirier2 Figure 6.3-24 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)]
i Figure 6.3-25 [ Proprietary information not included in DCD (Refer to SSAR , Section 6.3, Amendment 34)] I 6.3-58 Emergency Core Cooling Systems
- .. -- ga Rsv. 4 ABWR Design controlDocumenorier2 I i Figure 6.3-26 [ Proprietary information not included in DCD (Refer to SSAR i Section 6.3, Amendment 34)] l I
f i 1 if Figure 6.3 27 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] Emergency Core Cooling Systems 6.3-59
Rzv. 4 ABWR Desion controloocumentmer2 Figure 6.3-28 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)} Figure 6.3-29 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] 6.340 Emergency Core Cooling Systems l
Rev. 4 ABWR oesion controloccamenvrier2 i l Figure 6.3-30 [ Proprietary information not included in DCD (Refer to SSAR l Section 6.3, Amendment 34)] 1 l l l l L ? l j l 1 1 i . i I l l ! i i ! l I l Figure 6.3-31 [ Proprietary information not included in DCD (Refer to SSAR ;
- Section 6.3, Amendment 34)] !
l I i l l l i l i ) Emergency Core Cooling Systems 6341
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. e j RJV 4 ABWR oesign controloocumenvrier2 Figure 6.3-32 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amenc ment 34)]
1 + a i t ! Figure 6.3-33 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)) 6.342 Emergency Core Cooling Systems
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Rev. 4 ACWR' Dess.gn ControlDocument/ Tier 2 Figure 6.3-34 (Proprietary information not included in DCD (Refer to SSAR ! Section 6.3, Amendment 34)] l i l l l l Figure 6.3-35 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] l l \ l !\ Emergency Core Cooling Systems g 3_g3
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Riv. 4 l l ABWR oesign controtoccumentmer2 l l Figure 6.3-36 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] 6 i l g
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l l l Figure 6.3-37 [ Proprietary information not included in DCD (Refer to SSAR l , Section 6.3, Amendment 34)] i l i i l i 6 3-64 Emergency Core Cooling Systems
Rett. 4 Design ControlDocument/ Tier 2 Figure 6.3 38 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] l . l l l l i . ! l l l l Figure 6.3-39 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] l l l Emergency Core Cooling Systems S 3.g5 I
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l Figure 6.3-40 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ; I i i l 1
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i Figure 6.3-41 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] 1 4 1 4 J 4 . i 6.3-66 Emergency Core Cooling Systems
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I l l l I l Figure 6.3-43 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment.34)] l . l l l l i 4 4 Emergency Core Cooling Systems 6.3-67 l l
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l R>v. 4 ABWR oesign controloccamentmer2 l l l l Figure 6.3-44 [ Proprietary information not included in DCD (Refer to SSAR ! Section 6.3, Amendment 34))) l l
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l l l l l i i l l i Figure 6.3-45 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] l b l 6.348 Emergency Core Cooling Systems
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l R1v. 4 ACS Design ControlDocumenVTier2 l l Figure 6.3-46 [ Proprietary information not included in DCD (Refer to SSAR j Section 6.3, Amendment 34)] I l l l 1 Figure 6.3-47 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] i i 1 l l i ( . l i l l 1 Emergency Core Cooling Systems 6.3-69
w 6 R2v. 4 ~ ABWR oesion controsoccumentmerz Figure 6.3-48 [ Proprietary information not included in DCD (Refer to SSAR 2 Section 6.3, Amendment 34)] l 1 1 i i Figure 6.3-49 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] 6.3-70 Emergency Core Coohng Systems
.e 4-Rev. 4 ABWR oesign controlDocumenvrier2 Figure 6.3-46 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)]
4 l i Figure 6.3-47 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] l l I 4 l l Emergency Core Cooling Systems 6.3 69
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ABWR oesign contratoocuareatmer2 l Figure 6.3-48 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] l l l 1 l l Figure 6.3-49 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] l . i 1 6.3-70 Emergency Core Coohng Systems
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- Figure 6.3-50 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] ,
i l l l l Figure 6.3-51 [ Proprietary information not included in DCD (Refer to SSAR l Section 6.3, Amendment 34)] j - l l l r I Emergency Core Cooling Systems 6.3-71
w . Rsv. 4 ABWR oesion controioocumenvrier2 Figure 6.3-52 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] l 1 l I Figure 6.3-53 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] l 1 l 6.3-72 Emergency Core Cooling Systems
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4 ,) i Rev.4 6BWR oesion controloocumentmer2 Figure 6.3 54 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] l l l i
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l Figure 6.3-55 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment.34)] l r l l l 4 Emergency Core Coohng Systems 63 73
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4: . Rett 4 ARWR oesign controloocumentirier2 Figure 6.3-56 [ Proprietary information not included in DCD (Refer to SSAR ! Section 6.3, Amendment 34)] i r i l 1 Figure 6.3-57 [ Proprietary information not included in DCD (Refer to SSAR Sectbn 6.3, Amendment 34)] 1
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l l Figure 6.3-59 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] i l l l Emergency Core Cooling Systems 6.3-75
_ . _ . _ _.. . . _ . _ . __ . . ~ . . _ _ - _ _ _ _ _ _ _ . _ _ _ _ _ . . _ . . _ _ _ _ . ee o i Rect. 4 ABWR oesion controloocumenvrien ; i Figure 6.3-60 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] f t l l Figure 6.3-61 [ Proprietary information not included in DCD (Refer to SSAR l Section 6.3, Amendment 34)] i ! 1 l l 6.3-76 Emergency Core Cooling Systems
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ABWR Desma ControlDocumentfTier2 l Figure 6.3-62 [ Proprietary information not included in DCD (Refer to SSAR l l Section 6.3, Amendment 34)] 1 l. 1 i 1 Figure 6.3-63 [ Proprietary information not included in DC(' IRefer to SSAR Section 6.3, Amendment 34)] l Emergency Core Cooling Systems g.3 77
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i Figure 6.3-65 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] I t . i l l l i 3 4 6.3-78 Emergency Core Cooling Systems
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e ,, i Rsv. 4 ABWR Design controloocumenener2 l l l Figure 6.3-66 [ Proprietary information not included in DCD (Refer to SSAR l Section 6.3, Amendment 34)] i l i l Figure 6.3-67 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] l l l I 1 J Emergency Core Cooling Systems 6 3*79
I R2v. 4 1 ABWR oesign controloocumentmer2 1 l l l Figure 6.3-68 [ Proprietary information not included in DCD (Refer to SSAR l Section 6.3, Amendment 34)] l l 1 I i l i l i i Fig'ure 6.3-69 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] i l 6.3-80 Emergency Core Cooling Systems
A -- e Rev. 4 ABWR Design ControlDocumenVTier2 Figure 6.9-70 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] Figure 6.3-71 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] l i i l Emergency Core Cooling Systems g_3_g ,
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l 1 Figure 6.3-72 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] 1 1
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q. l Rev.4 ABWR oesion controlDocumentmer2 l 1 Figure 6.3-74 [ Proprietary information not included in DCD (Refer to SSAR j Section 6.3, Amendment 34)] l l i l l . l i l l 1 l Figure 6.3-75 [ Proprietary information not included in DCD (Refer to SSAR i Section 6.3, Amendment 34)] l I 1 i j l s ( l Emergency Core Cooling Systems 6.3-83 l l
Figure 6.3-76 [ Proprietary information not included in DCD (Refer to SSAR Section 6.3, Amendment 34)] b l@2 W 4 0 s A e O m 3 I E T
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i i A single non-safety-related HVAC System supplies normal cooling for secondary containment in the Reactor Building. Within the Reactor Building the system is branched into three separate systems with valves and fire dampers for each branch (Subsection 9.5.5). Required emergency cooling for safety-related systems is prosided by room coolers on a divisional basis. 9.5.1.1.6 Smoke Control System l j The smoke control system for the plant provides major features as follows:
)
(1) Venting of fire areas to prevent undue buildup of pressure due to a fire. i (2) Pressure control across the fire barriers to assure that any leakage is into the fire area experiencing the fire. l (S) Pressure control and purge air supply to prevent back-flow of smoke and hot ; j - gases when fire barrier doors are maintained open for access for manual fire l i l ~ suppression activities. l (4) Augmented and directed clean air supply to provide a dean air path to the fire i for fire suppression personnel. l (5) Smoke control by fans and systems external to the fire area experiencing the l l fire. l (6) Removal ofsmoke and heat from the fire by exhaust fans and operating supply l fans to provide clean, cool air. l (7) Manually reset position of fire dampers in the smoke removal path. These features are provided by designing the HVAC Systems for the dual purpose of HVAC and smoke control. ASHRAE's " Design of Smoke Control Systems for Buildings" and NFPA's " Recommended Practice for Smoke Control Systems" (References 9.5-3 ! and 9.5-4) were used as the basis for the design of the smoke control features of the combined systems. The normal operating modes of the HVAC Systems are shown in Figures 9.4-1 through l 9.4-6. The pressure at the input of an air handling unit is held at atmospheric pressure by a ducted, direct supply from outside through a bag type filter. The systems are designed so the division of the air flow to the rooms within an HVAC/ fire area is determined by the supply and exhaust ducting and the adjustable volume, dampers. Other Auxiliary Systems 9.5 11 1 l
t + l Rzv. 3 l ABWR oesiuscontroloocumenvrier2 l l l i I The HVAC Systems in the fire areas not experiencing a fire continue to operate in their normal fashion so that the pressure in the other fire areas remains at a positive value. This assures that air leakage through any openings in the fire barriers surrounding the fire is to the fire. The magnitude of the differential pressure which must be maintaianed across a fire
- barrier. to provide aedquate smoke control varies with the intensity of the fire and the room height. For this reason, it is a COL license information requirement l (Subsection 9.5.13.10) that the required differential pressure value for each barrier be j calculated during the detailed design phase, the HVAC Systems be designed to provide l the required pressure, and that the capability be confirmed during pre-operational testing. Normally the differential pressure would not have to be more than about 6.4 mm of water, and it most likely would be less.
l l Entry to a fire is gained from an adjacent fire area which by design is at a positive pressure with respect to the area experiencing the fire. The pressure differential is sufficient to provide adequate velocity through the open door to carry the combustion . products back into the zone of the fire. The flow through the open door into the area
- . of the fire and out the area of the fire's exhaust duct system is maintained by the positive 9.5-12 Other Auxiliary Systems l
l l
l , 1 I ABWR Design ControlDocumenVTier2 11 A.2 Liquid Waste Management [ Proprietary information not included in DCD (Refer to SSAR Section 11A.2' , Ameudment 34).] I i l l l Liquid Waste Management 11A.2-1/2
. . . - - . . . . _ - - . . . . - . . - - . _ _ _ - . ~ _ - . . - . . - . . . . - . . - - . . - .
R1v. 4 l ABWR oesion controtoacumenener2 i i I i 11 A.4 Solid Waste Management System l [ Proprietary information not included in DCD (Refer to SSAR Section 11 A.4, ! Amendment 34).] l 1 , i l t I l l l l l . i i l l r l l l \ . Solid Waste Management System 11A.4-1/2
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- 9 I Rsv. 4 ABWR oesign contraroocumentmer2 13.6 Physical Security l 13.6.1 Prelirninary Planning Not Required.
13.6.2 Security Plan The portion of the physical security plan, which is in the ABWR Standard Plant scope, is not included in DCD (Refer to SSAR Subsections 13.6.3.1,13.6.3.2 and 13.6.3.3, Amendment 33). 13.6.3 COL License Information Safeguards Information not included in DCD (Refer to SSAR Subsection 13.6.3, Amendment 33). 1 l l i I l l 1 l I i 4 4 f I Physical Security 13.6-1/2 l
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a e> l TS Bases Control 5.4 5.0. ADMINISTRATIVE CONTROLS i
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5.4 Technical Specifications (TS) Bases Control 5.4.1 Changes to the Bases of the TS shall be made under appropriate ' administrative controls and reviews. i 5.4.2 Licensees may make changes to Bases without prior NRC approval ; provided the changes do not involve either of the following: ;
- a. A change in the plant-specific TS, or plant-specific DCD !
Tier 1 or Tier 2* information; or l l b. A change to the site-specific portion of the FSAR that l involves an unreviewed safety question as defined in i 10 CFR 50.59, or a change to Tier 2 of the plant-specific ;
- DCD that involves an unreviewed safety question as defined I in the design certification rule for the ABWR (Appendix A to l 10 CFR 52). ,
i Changes to'the Bases implemented without prior NRC approval shall ; be provided to the NRC on a frequency consistent with ! i 10 CFR 50.71. 5.4.3 The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR, which consists ! of the plant-specific DCD and the site-specific portion of the FS.AR. l l l 5.4.4 Proposed changes that meet the criteria of Specification 5.4.2.a l
- or Specificatin 5.4.2.b above shall be reviewed and approved by l the NRC prior to implementation.
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ABWR TS 5.0-6 Rev, 4, Design Control DocumentRiet 2
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! o -g j i
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Rsv. 4 ABWR oesign controloocumenener2 l ! Table 18H - 1 [ Proprietary information not included in DCD (Refer to SSAR ; , Appendix 18H, Amendment 34)] j l Table 18H - 2 [ Proprietary information not included in DCD (Refer to SSAR Appendix 18H, Amendment 34)] 1 l Table 18H - 3 [ Proprietary information not included in DCD (Refer to SSAk Appendix 18H, Amendment 34)] l Table 18H - 4 [ Proprietary information not included in DCD (Refer to SSAR Appendix 18H, Amendment 34)] l Table 18H - 5 [ Proprietary information not included in DCD (Refer to SSAR Appendix 18H, Amendment 34)] , Table 18H - 6 [ Proprietary information not included in DCD (Refer to SSAR Appendix 18H, Amendment 34)] l~ Table 18H - 7 [ Proprietary information not included in DCD (Refer to SSAR , ! Appendix 18H, Amendment 34)] l l Table 18H - 8 [ Proprietary information not included in DCD (Refer to SSAR l Appendix 18H, Amendment 34)] l Table 18H - 9 [ Proprietary information not included in DCD (Refer to SSAR Appendix 18H, Amendment 34)] Table 18H - 10 [ Proprietary information not included in DCD (Refer to SSAR
- j. Appendix 18H, Amendment 34)]
Table 18H - 11 [ Proprietary information not included in DCD (Refer to SSAR Appendix 18H, Amendment 34)] l Table 18H - 12 [ Proprietary information not included in DCD (Refer to SSAR Appendix 18H, Amendment 34)] l Table 18H - 13 [ Proprietary information not included in DCD (Refer to SSAR i Appendix 18H, Amendment 34)] l Table 18H - 14 [ Proprietary information not included in DCD (Refer to SSAR ) Appendix 18H, Amendment 34)] l l l N Supporting Analysis for Emergency Operation information and Controls 18H-7/8
l < -- <> Rw. 4 ABWR oesign controicocumenvrier2 l 19C Design Considerations Reducing Sabotage Risk l This Section is not included in DCD (Refer to SSAR Appendix 19C, Amendment 33). I l I f l i l l I l i l \ i l l l l i l l I i 1 l l Design Considerations Reducing Sabotage Risk 19C-1/2
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q _, Rev. 4 ACWR oesign controioocumentirier2 i l 3 Question 910.17 ' Response 910.10 stated that in-plant security communications requirements of 10 CFR 73.55(f) are outside the scope of the ABWR Standard Design and would be the responsibility of the certification users. NRC Information Notice 83-85, "Use ofPortable l a Radio Transmitters Inside Nuclear Power Plants," discussed concerns about .*he { potential for radio frequency interference (RFI) from portable radio transmitters to i cause reactor system malfunctions and spurious actuations. A capability for continuous ; communication between security personnel on patrol within vital areas of the plant and i the security alarm stations is required by 73.55(f)(1). Common practice is to use hand held radios to meet this requirement. As noted in Information Notice 83-83, , i ' administrative prohibitions on the use of portable radios in certain areas of the plant l may not adequately resolve tne concern, particularly for new designs that make
- l extensive use of solid state devices in instrumentation and control circuits. The ABWR Licensing Review Basis (August,1987) stated that the ABWR SSAR will not proside details but will identify design requirements for 73.55(f). Please address design requirements to assure that means can be provided for continuous communication between security personnel stationed within, or on patrol within, vital areas of the plant and the security alarm stations, without interference with plant instrumentation and control.
4 q Response 910.17 i Safeguards Information not included in DCD (see SSAR Subsection 20.3.15, I 1 Amendment 33). Question 910.18 Generic Letter 87-08 states that an uninterruptable power supply is preferred for alarm annunciator equipment and non-portable communications equipment. Industry standard ANSI /ANS-3.3-1988 states that intrusion detection aids (e.g., door alarms. fence alarms, and the alarm assessment [ closed circuit television) system) should also be supplied with uninterruptable power. Regulatory Guide 5.65 notes that an uninterruptable power supply for electrical locking devices on vital area doors is an 1 acceptable method for providing the prompt access to vital equipment required by 10 CFR 73.55(d)(7)(ii). Section 8.3 of the ABWR SSAR discusses onsite power systems, including non-class 1E vital AC power for important non-safety related loads, but makes 4 no mention of security system power requirements. The draft EPRI-ALWR Requirements Document quoted in ABWR SSAR Appendix 19B says that the security ' power subsystem shall be a non-interruptible power source. Therefore, we again request you to discuss what provisions for these security systems have been provided in the standard design, and provide interface criteria that will allow the security requirements for these systems to be accomplished without adversely interfering with safety systems. e Response 910.18 Safegunds Information not included in DCD Dee SSAR Subsection 20.3.15, Amendment 33). Question 910.19 Explain why the emironmental conditions parameters of ABWR SSAR Appendix SI should not apply to the design and qualification of security access control systems. Consider desirability of operable card reader controlled door locks in the event of a Response to fifteenth RAI- Reference 15 20.3.15 37
A c> Riv. 4 N:WR oesign controloocumentmer2 pipe break, such as occurred at Surry (NRC Augmenteo Inspection Team Report 50-281/8fM2). Response 910.19 Safeguards Information not included in DCD (see SSAR Subsection 20.3.15. Amendment 33). Question 910.20 The list of vital areas and vital equipment in Subsection 13.6.3.3 appears to include all l of the reactor coolant pressure boundary, including appropriate motor control centers j and power supplies; systems required for mitigation of transients; and support systems i (e.g., cooling water, instrumentation, control power) necessary for these systems to - . operate; as well as other safety related systems. Are there any exceptions to this i statement? Response 910.20 Safeguards Information not included in DCD (see SSAR Subsection 20.3.15, ; Amendment 33). j Question 910.21 l Subsection 13.6.3.4 still specifies door alarms only for doors at card reader locations. All doors and hatches connecting vital areas to non-vital areas should be alarmed (e.g., balanced magnetic switches with tamper-safe cabling), notjust doors at card reader locations, with the alarm hardware being on the vital side of the door. j Response 910.21 Safeguards Information not included in DCD (see SSAR Subsection 20.3.15, Amendment 33). Question 910.22 10 CFR 73.55(d)(7) also requires provisions to accommodate the potential need for rapid ingress or egress. Emergency exits should include provisions for exiting without use of keys or card readers. Please include appropriate language in Subsection 13.6.3.4. Response 910.22 Sr.feguards Information not included in DCD (see SSAR Subsection 20.3.15, Amendment 33). Question 910.23 Certain rooms are identified in Subsection 13.6.3.6, Bullet-Resisting Walls and Doors, Security Grills and Screens, as:
.. a particularly high security zone. Specific precautionary measures have been incorporated into the building design to minimize forcible access to this area."
I This seems to confuse two requirements of 10 CFR 73.55. Bullet-resisung bamers are required by 10 CFR 73.55(c)(6) for the control room. According to 10 CFR 73.55(c)(1), access to all the vital areas identified in Subsection 13.6.3.3 requires passage through two physical barriers of sufficient strength to meet the performance requirements of 10 20.3.15-38 Response to Fifteenth RAI- Reference 15
( ~- W J i R1v. 4 \ ABWR Design controloocumentmer2 ! l l l l CFR 73.55(a). As noted in Regulatory Guide 5.65, a vital area barrier is to be constnicted of materials that proside delay to forcible access from non4 ital areas. Response 910.23 Safeguards Information not included in DCD (see SSAR Subsection 20.3.15, Amendment 33). Question 910.24 The change made to Subsection 13.6.3.6 for Response 910.13 is too vague. Will the design of air exhausts, HVAC gratings, and other man-sized (i.e.,96 square inches) openings, in all physical barriers that separate vital areas from non4 ital areas, satisfy the > criterion in NUREG-0908 and Regulatory Guide 5.65 that the integrity of a vital area barrier containing them not be decreased? Response 910.24 Safeguards Information not included in DCD (see SSAR Subsection 20.3.15, Amendment 33). i Question 910.25 The meanings of some statements in Section 13.6.3 are unclear and may be unnecessary: (1) Subsection 13.6.3.1, Introduction, includes "the capability for detection of inoperability of vital equipment" as a concern of the physical security design : requirements. Is this what it was meant to say? This is not typically a physical : security function. What portions of Chapter 7 discusses this? (2) What is the intent of the last sentence of Subsection 13.6.3.3: "Hence, access control is considered separately."? 6 (3) The interface requirements of Subsection 13.6.3.7, Compatibility with the Remainder of the Plant, would be covered in the site security plans required by 10 CFR 50.34(c) and (d). Section 13.6.2 already states that the security plans are out of the scope of the ABWR Standard Plant design certification which means theywould be required to be provided by applicants referencing the certified design. Of the eleven items listed, only #3 appears to be a unique , ABWR interface requirement. If 13.6.3.7 is intended to clarify what additional security requirements those applicants ; would n eed to satisfy, th e list is in com ple te, as it omits ligh ting and oth er req uirem e n ts.
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1 Response 910.25 Safeguards Information not included in DCD (see SSAR Subsection 20.3.15, Amendment 33). i i t l Response to fifteenth RAI- Reference 15 20.3.15-39 l , I
4, . g I l Rev.0 ABWR oesign controtoccumenvrier2 1 I 4 i AC - ATMOSPHERIC CONTROL 1 (A - INSTRUMENT AIR I SA - SERVICE AIR 4 j HPIN - HIGH PRESSURE T314t19 T31-F040 j NITROGEN ! E T3h041
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j 1 I I i INSIDE T31-F025 T31-F002 PRIMARY l HVAC 7 C AC CONTAINMENT i HVAF X 240 i T31-F001 T31-F003 1 N2 BOTTLES ' j DIV.1 HPIN MSRVs l [][ P54-M03A {T[ P54-F007A X-71 A P54-F008A i G F54-F012A MSRVs T31 F042 P54-F203 X-72 P54-F200 P54-F208 d '- o AC P54 0128 MSRVs [_ P54-F003B {T_r] X 71B P54-F007B P54-F0088 v N2 BOTTLES DIV. 2 HPlN P54-F216 MSIVs X-70 PS2-F270 PS2-F271 PS2-F276 PS2-F277 HPiN C IA
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% N2 PURGE Figure 20.3.15-1 Compressed Gas Systems interconnections (Response to Question 430.217) 20.3.15-40 Response to Fifteenth RAI- Fv terence 15
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