Text

Forwards GE ABWR Dcd,Rev 3 (Filed in Category A),Abwr Cdm, Rev 8 (Filed in Category a) & ABWR Ssar,Amend 37,Rev 9 (Filed in Category K) to Incorporate Changes Ref in 960701 & s from Jf Quirk
	ML20117H331
Person / Time
Site:	05200001
Issue date:	08/30/1996
From:	Quirk J; GENERAL ELECTRIC CO.
To:	Joshua Wilson; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20117H333	List: ML20117H331; ML20117H349; ML20117H356;
References
	MFN-143-96, NUDOCS 9609090224
	Download: ML20117H331 (101)
	v • d • e

{{#Wiki_filter:--- f GENuclearEnergy Joseph F. Qun GeneralElectnc Company ABWR Lkensmg Managet 175 Cuttner Avenue. MC 782: San Jose. CA 951251014 PimectManager ABWRCerb6cabon 408 925-6219(phone) 408 925-4257(facsale) August 30,1996 MFN 143-96 Docket No. 52-001 Document Control Desk U.S. Nuclear Regulatory Commission Washington DC 20555 Attention: Jerry N. Wilson Nuclear Reactor Regulation (DRPM)

Subject:

Submittal of GE's ABWR DCD, Revision 3, ABWR CDM, Revision 8 and ABWR SSAR Amendment 37, Revision 9

Reference:

1. Letter (MFN 09+96) fromjoseph F. Quirk (GE) to Document Control Desk (NRC), " ABWR Design Control Document Changes," datedJuly 1,1996.

2. Letter (MFN 079-96) fromJ. F. Quirk (GE) to Document Control Desk (NRC), " Changes to Design Documentation for the Advanced Boiling Water Reactor (ABWR)," datedJune 10,1996.

3. Letter (MFN 039-96) fromJ. F. Quirk (GE) to Document Control Desk (NRC), " Submittal of Amendment 36, Revision 8, to GE's ABWR SSAR and Certified Design Material, Revision 7," dated March 22,1996.

4. Letter (MFN 004-95) fromJ. N. Fox (GE) to Document Control Desk JRC), " Submittal of Revision 2 to the ABWR Design Contr Document," datedJanuary 17,1995.

The purpose of the enclosed submittal of GE's ABWR DCD, Revision 3, ABWR CDM, Revision 8, and ABWR SSAR Amendment 37, Revision 9 is to incorporate the changes documented in References 1 and 2. This completes our submittals except for any adjustments that might be needed to reflect Commission decisions in the final rule. In accordance with direction of NRR/DRPM staff, GE is providing a total of twenty-eight (28) copies of this letter and its attachments and enclosures. The Document Control Desk is requested, also per direction of NRR/DRPM staff, to distribute twenty-one (21) copies to the recipients listed in Attachment 1. '50036 9609090224 960830 h PDR ADOCK 0520 1 S h A m

1 f I' lists the differences between the enclosed revisions of DCD and CDM/SSAR. This list supersedes the lists previously provided in Attachment 2 of { Reference 3 and Attachment 3 of Reference 4. As evidenced in Attachment 2, with the exception of several formatting differences and those areas in which the differences are intentional (e.g. Severe Accident /PRA, Tier 2* information, proprietary information, safeguards information), both SSAR Amendment 37, Revision 9, and CDM, Revision 8, are identical to the DCD Revision 3. Page change instructions for DCD, Revision 3, are provided in Attachment 3; for CDM, Revision 8, in Attachment 4 and for SSAR, Revision 9, in Attachment 5. The listing of effective pages of the DCD, which identifies the revision number that should show on each page upon update of the DCD by replacement of the change pages, is included in the DCD change pages for incorporating it ahead of the DCD Introduction. This listing supersedes that in Attachment 2 of Reference 4 as amended by GE letter of May 31,1995. Sincerely, oseph F. Quirk j Project Manager / ABWR Certification MC-782, (408) 925-6219 cc: (w/o attachments and enclosures) S. A. Hucik (GE) W. T. Russell (NRC) T. E. Quay (NRC) J. N. Wilson (NRC) D. C. Scaletti (NRC) S. M. Franks (DOE) F. A. Ross (DOE) Attachments and Enclosures l l 1 I J (

Distribution of enclosures - ABWR DCD, Revision 3, ABWR CDM, Revision 8 and ABWR SSAR Amendment 37, Revision 9 -with the cover letter and Attachments 1 through 5 Orranization File Center NRC PDR ACRS (M. El-Zeftawy) OGC DRPM/PERB DRPM/PSGB DRPM/PDST DRPM - D. C. Scaletti DRPM -J. N. Wilson DE/EMCB DE/EMEB DE/ECGB DE/EELB DSSA/SPLB DSSA/SRXB DSSA/SCSB DSSA/SPSB DRCH/HICB DRCH/HHFB DRCH/HQMB ADPR/TSB ) u

Difference Between DCD, Revision 3 and CDM, Revision 8 DCD Section/Pg Difference Tier 1 2.14.1-4 DCD Figure 2.14.1 cleaned up electronically. 2.15.10 Figures DCD figures updated electronicahy Section 3.2 Figures DCD drawings cleaned up - Continued I CDM-1 w_

[ Attichment 2 (Continued) Difference between DCD, Revision 3 and SS AR Amendment 37 (Revision 9) DCD Section/Pg Difference Tier 2 ii DCD utilizes Appendix 3K iv DCD and SSAR titles are different for Section 14.3 Chapter 1 i 1.1-1 Replaced " Advanced Boiling Water Standard Safety Analysis Report" with " Tier 2" in first paragraph of DCD 1.1-1 Replaced "SSAR" with " Tier 2" in second paragraph of DCD 1.1-3 Changed "ABWR SSAR" to " Tier 2 in beginning of DCD Section 1.1.5 and removed " final design approval (FDA) and" 1.2-1 Removed white space from DCD 1.3-6 Item 3 in footnote modified to fit DCD needs 1.6-1 Introductory sentence modified to meet needs of DCD 1.6-2 thru Changed "SSAR" to " Tier 2" in right-hand columns of DCD 1.6-6 1.7-1 Replaced "...the ABWR SSAR" with " Tier 2" in second line of DCD 1.7-2 Removed white space from DCD 1.7-3 Removed white space from DCD 1.8-12, 13 Bracketed and Italicized SRP 3.5.3,3.8.1 and 4.2 Appendices and j added "(ly and "(2)" superscript in DCD 1.8-24 Added two footnotes to Table 1.8-19 in DCD 1.8-25,26 Removed white space from DCD 1.8-27 Italicized 1.47 and added superscript (4) in DCD 1.8-29 Italicized 1.75 and added superscript (4) in DCD 1.8-29 Italicized 1.84 and added Superscript (1) in DCD 1.8-30 Italicized 1.89 and added superscript (2) in DCD 1.8-30 Italicized 1.92 and added supersenpt (1) in DCD 1.8-30 Italicized 1.100 and added superscript (2)in DCD l 1.8-31 Italicized 1.105 and added superscript (3) in DCD 1.8-34 Italicized 1.153 and added superscript (4)in DCD 1.8-34.1 Added notes to Table 1.8-20in DCD 1.8-42 Referenced footnote (9) under IEEE 338 and added footnote (9) to page 1.8-47 in DCD 1.8-45 Removed white space from DCD 1.8-46 Removed white space from DCD SSAR-1

Attr.chment 2 (Continued) Difference between DCD, Revision 3 and SS AR Amendment 37 (Revision 9) DCD Section/Pg Difference Italicized EC 801-2 and referenced note (3) in DCD j 1.8-35 thru 1.8-87 Italicized and bracketed the following codes and standards in DCD: ACI 349 EEE 830 AISC N690 EEE 845 ANS 7-4.3.2 EEE 1012 l ANS 57.5 EEE 1023 ANS 58.2 ANSI /HFS-100 EEE 1042 EEE 1050 X3.139 IEEE 1228 (Draft) X3.148 DOD 5000.2 X3.166 DOD AD/A223168 X3T9.5/84/49 DOE AR602-1 ANSI /NQA-2a DOE DI-HFAC-80740 ASTM C776 DOE ESD-TR-86-278 ASTM C934 DOE HDBK-761 A IEEE C37.90.2 DOE HDBK-763 EEE C62.41 DOE-STD-2167A EEE C62.45 DOD TOP 1-2-610 IEEE C63.12 MIL-H-46855B EEE 279 MIL-HDBK-217 EEE 323 MIL-HDBK-251 EEE 338 MIL-HDBK-759A EEE 344 MIL-STD-461C EEE 384 MIL-STD-462 EEE 518 MIL-STD-1472D EEE 603 MIL-STD-1478 IEEE 730 IEC 801-2 EEE 802.2 EC 880 EEE 802.5 EC 964 EEE 828 ISO 7498 EEE 829 and added the corresponding nine notes to page 1.8-47 1.9-1 Replaced "ABWR SSAR" with " Tier 2" 3 places in DCD 1.9-2 Removed white space from DCD 1.9-4 Changed Item 3.8 to "Not Used"in DCD 1.9-5 Changed Items 3.31-3.36 to "Not Used" in DCD 1.9-6 Changed Item 8.7 to "Not Used"in DCD 1.9-7 Changed " Deleted" to "Not Used" 9 places in DCD 1.9-8 Removed white space from DCD 1.9-9 Changed Item 9.29 to "Not Used"in DCD 1.9-10 Removed white space from DCD 1.9-10 Changed Item 14.3 to "Not Used" in DCD j SSAR-2 b t

Attechment 2 (Continued) Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) DCD Section/Pg Difference 1.9-10 Changed Item 15.8 to "Not Used"in DCD 1A-2,3 Unitalicized submittal list title names and added quotes in DCD 1A-5 Unitalicized " General Design Criteria" in DCD 1A-11 Italicized " Plant specific models..." added footnote in DCD 1A-19 Unitalicized " Additional information.. " and added quotes in DCD 1 A-36, 37 Unitalicized references and added quotes in DCD 1AA-3 Replaced "SSAR" with " Tier 2" 2 places in DCD 1AA-6 In second paragraph, replaced "0.983", with " estimated to be s 1 AA.4.3 high"in DCD ~ 1B Changed Title to "Not Used"in DCD IC-1 Changed italics to underline in DCD IC-2 Changed italics to underline in DCD 1C-5/1C.2.3.1.3 Changed "SSAR" to ' Tier 2" in DCD IC-9 Unitalicized referencesin DCD IC-10 Unitalicized requirements in DCD 1C-12 Unitalicized Item (b) and (c)in DCD Chapter 3 3.0-iii/iv Removed listing for Att. 3AA and added title for Appendix 3K in DCD 3.1-63 Third paragraph unitalicized " Radioactive Waste Mgmt + Process Rad. Mon."in DCD 3.2-8,9 Italicized first paragraph of Item (3), added footnote, italicized Item (4) (a)(b) and added footnote in DCD 3.2-9 Italicized last paragraph of section 3.2.5.3 and added footnote in DCD 3.2-17 Changed items 8,9,10 to "Not Used" in DCD 3.2-19 Changed Items 8, and 9 to "Not Used" in DCD 3.2-20 Changed Item 19 to "Not Used"in DCD 3.2-24 Changed Items 3, and 4 to "Not Used" in DCD 3.2-33 Changed items 5, and 6 to "Not Used" in DCD 3.2-36 Changed items 2,3(kl) and N1(1) (2) to "Not Used" in DCD 3.2-52 Changed item 6 to "Not Used"in DCD ~~ 3.2-63 Italicized text six places added footnote in DCD 3.3-3 Unitalicized referencesin DCD SSAR-3

Attrchment 2 (Continued) Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) DCD Section/Pg Difference 3.4-16 Unitalicized referencesin DCD 3.5-14 Unitalicized referencesin DCD 3.6-1 Last paragraph removed "this SSAR" replaced with ' Tier 2" in DCD i 3.6-2 Unitalicized title of Criterion 4 in DCD 3.6.1.1.1 3.6-12-17 Italicized text added foomote in DCD 3.6 20 Unitalicized item 2 in DCD 3.6.2.2.1 3.6-22-26 Italicized text added footnote in DCD j i 3.6-29 Changed "ABWR SSAR" to ' Tis 2" in second paragraph in DCD ~ 3.6-33, 34 Unitalicized references in DCD 3.7-8, 9 Italicized text, added footnot:in DCD 3.7-21 Italicized text 3 places, added footnote in DCD 3.7-22, 23 Italicized text, added footnote in DCD 3.7-24 First paragraph changed "SS AR" to ' Tier 2" in DCD 3.73.3.3.14 3.7-25 Italicized text, added footnote in DCD 3.7-26 Italicized text, added footnote in DCD 3.7-27 Italicized text, added footnote in DCD 3.7-28 Italicized text, added footnote in DCD 3.7-29 Italicized text, added footnote in DCD 3.7-30, 31 Italicized text, added footnote in DCD 3.7-32, 33 Italicized text, added footnote in DCD l 3.7-35-41 Italicized text, added footnote in DCD 3.7-40 Item (3) Changed "of this SSAR" to "of Tier 2" in DCD 3.7.3.12 3.7-40,41 Italicized text two places, added footnote on page 3.7-41 in DCD 3.7.3.13 3.7-46 Item (b) changed "the SSAR" to " Tier 2" in DCD 3.7-47 Unitalicized references Changed " Deleted" to "Not Used" in DCD 3.7-73 Changed " Deleted" to "Not Used" in DCD 3.8-2 Added italicized paragraph and footnote in DCD 3.8-3 Added itahcized paragraph and footnote in DCD 3.8-20 Italicized text, added footnote in DCD 3.8.2.2.3 SSAR-4 u

i. l Attechment 2 (Continued) l. Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) DCD Section/Pg Difference 3.8-22 Italicized text, added footnote in DCD 3.8.2.4.1.4 l 3.8-27 Added italicized paragraph and footnote in DCD 4 3.8-28 Added italicized paragraph and footnote in DCD 3.8-30 Italicized text, added footnote in DCD l 3.8-32 Unitalicized NCIG titles, put in quotes in DCD i 3.8.3.8 l 3.8-35 Italicized Item (1), added footnote in DCD 1 l 3.8-36 Italicized Item (2), added footnote in DCD l Unitalicized the rest of the Items in DCD 3.8-37 Unitalicized Items in DCD 3.8-38 Unitalicized firstline in DCD j Italicized textin two places in DCD t j Unitalicized lastitemsin DCD l 3.8-44 Italicized first paragraphin DCD 3.8.4.4.1 3.8-46 Added italicized sentence,3 places, added footnote in DCD 3.8-47 Italicized text, added footnote in DCD 3.8.5.2 3.8-54 Italicized Items 13,14,15 - Changed designation of item 15, and Changed " Deleted" to "Not Used" in DCD 3.8-55 Added footnotes in DCD 3.8-60 Italicized (1) thru (6), added footnote in DCD 3.8-61, 62 Italicized text, added footnote in DCD 3.8-72 Changed " Deleted" to "Not Used" in DCD 3.8-74 Changed " Deleted" to "Not Used" in DCD 3.8-77 Changed " Deleted" to "Not Used" in DCD 3.9-1 Italicized text, added footnote in DCD 3.9-7 Added Subsection and footnote in DCD 3.9-14 Italicized text three places and added footnote in DCD 3.9-23 Unitalicized Item (1)in DCD 3.9-24 Unitalicized Items (2) and (3)in DCD 3.9-28 Italicized text, added footnote in DCD 3.9-29 Italicized text, added footnote in DCD SSAR-5

Attechment 2 (Centinued) Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) DCD Section/Pg Difference 3.9-32 Italicized text, added footnote in DCD 3.9-36 Italicized text, added footnote in DCD 3.9-37 Italicized text, added footnote in DCD 3.9-41 Italicized text, added footnote in DCD 3.9-42 Italicized text, added footnote in DCD 3.9-45 Italicized sentences, added footnote in DCD 3.9-50 Italicized text, added footnote in DCD 3.9-51 Italicized text, added footnote in DCD 3.9-52 Italicized text, added footnote in DCD 3.9-53 Italicized text, added footnote in DCD 3.9-54 Italicized text, added footnote in DCD 3.9-55 Italicized sentence, added footnote in DCD 3.9-56 Italicized text, added footnote in DCD 3.9-77 Added first paragraph in DCD 3.9-77,78 Italicized text, added footnote in DCD 1 3.9-84 Italicized references 3.9-6,7,9,10,11 and unitalicized the rest of references in DCD 3.9-86 Italicized Event 12 and Note 6, added footnote in DCD 3.9-87 Removed commas from Heading 2 in DCD Italicized Event 3, Added footnote in DCD 3.9-87 Event 4 change " Deleted" to "Not Used"in DCD 3.9-88 Italicized Notes 7 and 9 and 12, added footnote in DCD 3.9-99 Changed "SSAR" to ' Tier 2" in table heading in DCD 3.9-139 Deleted "SS AR" under notes (a) and (d) in DCD 3.10-1 Added italicized paragraph and footnote in DCD 3.10-2 Italicized text, added footnote in DCD 3.10-3 Italicized text, added footnote in DCD 3.11-5 Italicized reference 2, added footnote in DCD 3.13-11 Changed "SSAR" to ' Tier 2" in DCD 3.13-14 Replaced "are less that 1% of" with "is a very small percentage of" in the last paragraph in DCD SSAR-6

1 j Attichment 2 (Continued) Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) l DCD Section/Pg Difference i Att 3AA Removed Att 3AA from DCD 3B-27 Replaced "SSAR" with ' Tier 2" in first paragraph in DCD i 3B.4.4.1 i 3B-31, 32 Unitalicized referencesin DCD i j 3B-34, 78 Replaced "provided under separate cover" with "not part of DCD i (Refer to SSAR)"in appropriate places in DCD 3D-4 Changed " Deleted" to "Not Used",2 places in DCD l 3D-5 Changed " Deleted" to "Not Used" in DCD 3E-24 Unitalicized paragraph headings in DCD i 3 E.6.1.2 l 3E-25 Unitalicized references and changed reference 10 to "Not Used"in i DCD j 3F-1 Changed title to "Not Used"in DCD 1 3H.0-vii Changed " Deleted" to "Not Used" all places in DCD l 3H.0-viii Changed " Deleted" to "Not Used" all places in DCD 3H.1-3 Italicized text, added footnote in DCD I l 3H.1-57/58 Removed blank pages from DCD 3H.1-62/63 Removed blank pages from DCD 3H.1-65 Removed blank pages from DCD 3H.1-68 Removed blank pages from DCD 3H.1-70 Removed blank pages from DCD 3 H.1-73 Removed blank pages from DCD 3H.1-75 Removed blank pages from DCD 3H.1-77 Removed blank pages from DCD 3H.1-88 Changed " Deleted" to "Not Used" in DCD 3H.1-104 Changed " Deleted" to "Not Used" in DCD 3H.2-2 Italicized text, added footnote in DCD 3H.2-21 Changed " Deleted" to "Not Used" in DCD 3H.3-2 Italicized text, added footnote in DCD 3H.4-6-13 Figures have been recreatedin DCD 3K Added entire appendix to DCD 3L-1 First paragraph replaced "SSAR" with " Tier 2" in DCD 3L-10 Removed Figure 3L-3 from DCD SSAR-7

l Attichm:nt 2 (Continued' Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) DCD Section/Pg Difference 3M-3 Unitalicized "3 meter board"in DCD 3M-5 Changed "SSAR Figure No." to " Tier 2 Figure No." in DCD 3M-6 Changed "in the SSAR" to "in Tier 2" in DCD 3M.7(1) 3M-7 Replaced "SS AR" with " Tier 2", 2 places in DCD 3M.8 3M-8 Added space between "approximately" and "0.93" last line in DCD 3M.10 3M-9 Unitalicized references in DCD 3MA-3 Replaced "SSAR" with " Tier 2" first line in DCD 3MA-10 Replaced "SSAR" with " Tier 2" first line in DCD 3MA-13 to end Changed "SS AR Figure" to " Tier 2 Figure" in DCD 3MA-32 Removed white space at top cf page from DCD 3MA-34 Removed white space at top of page from DCD Chapter 4 4.0-v Removed Figure 4.2-3 entry from DCD 4.1-2 Removed period from title from DCD 4.1.2.1.1 4.1-8 Unitalicized references in DCD 4.2-1 Added italicized paragraph with footnote; and italicized sentences added footnote in DCD 4.2-3-5 Italicized text, added footnote in DCD 4.2-5, 6 Italicized text, added footnote in DCD 4.2-6 Italicized text, added footnote in DCD 4.2-7 Italicized second sentence of Section 4.2.4 in DCD 4.2.3.1.2, 4.2.4 4.2-8, 9/10 Italicized figure titles, added footnote in DCD 4.3-2 Italicized sentence of first paragraph added footnote in DCD 4.3-7 Unitalicized referencesin DCD 4.3-9 Italicized figure title, added footnote in DCD 4.3-10 Replaced "provided under separate cover" with "not part of DCD (Refer to SSAR section 4.3)"in DCD 4.4-10 Changed " Deleted" to "Not Used" in DCD 4.4.3.5 4.4-17, 18 Unitalicized references in DCD 4.5-5 Unitalicized headingsin DCD 4.5.2.1 SSAR-8 w

.m--. Attochment 2 (Continued) Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) DCD Section/Pg Difference 4A-1 Italicized text, added footnote and unitalicized references in DCD 4A-3-42 Proprietary title was changed in DCD 4B-1/2 Added paragraph, italicized sentences, added footnote in DCD 4C-1, 2 Italicized text, added footnote in DCD 4D-1 Substituted DCD proprietary statement so that it refers to the SSAR Chapter 5 5.0-v Changed " Deleted" to "Not Used" in DCD ( 5.1-1-3 Unitalicized heading in DCD 5.2-49, 50 Unitalicized referencesin DCD 5.2-51-53 Italicized selected code cases in DCD 5.3-20 Unitalicized referencesin DCD 5.4-19 Removed white space from DCD l 5.4-58 Unitalicized referencesin DCD 1 5A-1 Removed white space from DCD 5A.2 l Att 5AA,5AB Removed Attachments from DCD Chapter 6 6.0-LOF Changed " Deleted" to "Not Used" in DCD 6.1-2 Changed " Deleted" to "Not Used" in DCD 6.1.1.1.3.6 6.2-6 Removed white space from DCD 6.2-19 Unitalicized headingsin DCD 6.2-10 Unitalicized headingsin DCD 6.2-27 Changed " Deleted" to "Not Used" in DCD l 6.2-71 Removed period after title in DCD l 6.2-81-87 Replaced numerical values with word values for consistency with Appendix 19Ein DCD l 6.2-102 Unitalicized references in DCD l 6.2-125-167 Changed "SSAR" to ' Tier 2"in DCD 6.2-211-212 Changed " Deleted" to "Not Used" in DCD 6.3-14/15 Unitalicized headings in DCD 6.3-25 Unitalicized referencesin DCD SSAR-9

Attechment 2 (Continued) Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) DCD Section/Pg Difference 6.3-32 Substituted DCD proprietary statement to refer to SSAR 6.3-45 Changed " Deleted" to "Not Used" in DCD 6.3-49 Changed " Deleted" to "Not Used" in DCD 6.3-50-87 Substituted DCD proprietary statement so that it refers to the SSAR 6.5-13 Changed " Deleted" to "Not Used" in DCD 6.5-13 Unitalicized references in DCD 6.6-2 Changed " Deleted" to "Not Used" in DCD 6A-1 Unitalicized heading in DCD 6B-2-9/10 Unitalicized table headings in DCD 1 6C-1-5 Removed white space from DCD j 6E-1 Removed white space from DCD j Chapter 7 7.1-2 Added italicized paragraph and footnote in DCD l 7.1-7-11 Italicized text added footnote in DCD j i 7.1-12 Changed item (k) from " Deleted" to "Not Used" in DCD 7.1-27 Changed " Deleted" to "Not Used" in DCD 7.1-31 Added italicized paragraph and footnote in DCD 7.2-5 Changed Item (8) to "Not Used"in DCD j 7.2-11 Changed Item (5) to "Not Used"in DCD l 7.2-32 Italicized Reg. Guide 1.105, added footnote in DCD 7.2-40 Changed Item (12)(d) to "Not Used" in DCD 7.2-56 Changed " Deleted" to "Not Used" in DCD j 7.3-56 Removed blank line from top of page in DCD 7.3-70 Unitalicized 3(a)in DCD 7.3-7' Unitalicized items (b), (c), (d) in DCD 7.3-72 Unitalicized (e), italicized (f) and added footnote in DCD 7.3-73-end Unitalicized alllistitems in DCD 7.3-96 Italicized reference 7.3-2 in DCD 7.4 Unitalicized listitems in DCD 7.4-24 Italicized Reg Guide 1.105 added footnote in DCD SSAR-10

i

(Centinued)

Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) { DCD Section/Pg Difference ] 7.5-11 Removed comma after "drywell" in first line of paragraph (j) in DCD 4 l 7.5-14 Unitalicized titles in first paragraph in table in DCD 7.5 24-27 Changed " Safety Analysis" to " Tier 2" in third column in DCD l 7.5-28 Replaced "S" with "T' in the right hand column and "S=SS AR" with 'T= Tier 2"in footnote in DCD ^ 7.6-15 Changed " Deleted" to "Not Used" in DCD 1 7.6-23-end Unitalicized listitems in DCD I sl 7.6-23 Italicized item 3f and added footnote in DCD j 7.6-27 Replaced "SSAR" with " Tier 2" 7.6-29 Changed " Deleted" to "Not Used" in DCD i 7.6-30 Italicized item (f) added footnote in DCD 7.6-46 Changed " Deleted" to "Not Used" in DCD j 7.7-26-end Unitalicized listitems in DCD j 7.7-54 Removed white space from DCD 7.7-67 Removed white space from DCD 1 7.7-77 Replaced "of the SSAR" with "of Tier 2" in first line of DCD 7.7-87 Moved this section from page 7.7-88 in DCD 7.7.2.I1 7.7-90 Changed " Deleted" to "Not Used" in DCD 7A-1 Added two italicized paragraphs with footnotes 7A-2-12 Italicized all of section 7A.2 and added footnotes on pages 7A-4 and 7A-7 in DCD 7A-8 Changed "the SS AR" to " Tier 2" in response (11) in DCD 7A-12-15 Italicized all of Section 7A.3 and added footnote in DCD 7A-16-20 Italicized Sections 7A.5 thru &a.7 and added footnote in DCD 7B-1-7/8 Italicized Sections 7B.1 thru 7B.3 added footnote in DCD 7C-2-5 Italicized Section 7C.2 and 7C.3 added footnote in DCD 7C-5 In first paragraph changed "less than 10E-6" to " extremely low" in DCD 7C-11-13 Italicized Section 7C.5 added footnote in DCD 7C-14 Unitalicized references in DCD Chapter 8 8.1-4 Changed item 3(d) to "Not Used"in DCD SSAR-ll m.

Attachm:nt 2 (Continued) Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) ' DCD Section/Pg Difference 8.2-6 Removed white space from DCD 8.2-9 Changed "the SSAR" to " Tier 2" in first paragraph in DCD 8.2-15 Changed "SSAR" to " Tier 2" on first line in DCD 8.3-2 Removed white space from DCD 8.3-23 Removed extra comma after outputs in fourth line of paragraph in DCD 8.3-55 Changed " Deleted" to "Not Used" in DCD 8.3-56 Changed " Deleted" to "Not Used" 8 places in DCD 8.3-56 Removed white spaces from DCD 8.3-57 Changed " Deleted" to "Not Used" in DCD 8.3-59 Changed " Deleted" to "Not Used" in DCD Chapter 9 9.0-iii Changed " Deleted" to "Not Used" in DCD 9.0-vii Changed " Deleted" to "Not Used",2 places in DCD 9.0-viii Changed " Deleted" to "Not Used" 2 places in DCD 9.1-2 Changed " Deleted" to "Not Used" in DCD 9.1-4 Removed white space from DCD 9.1-14 Removed white space from DCD 9.1-35 Removed white space from DCD 9.1-42 Removed white space from DCD 9.1-43 Removed white space from DCD 9.1-48 Changed " Deleted" to "Not Used" in DCD 9.1-54 Unitalicized 2 linesin DCD 9.1-55 Unitalicized 1 linein DCD 9.2-12 Removed white space from DCD 1 9.2-25 Removed white space from DCD 9.2-45 Removed white space from DCD 9.2-46 Removed white space from DCD 9.2-61 Changed " Deleted" to "Not Used" in DCD 9.2-67 Changed " Deleted" to "Not Used" in DCD 9.3-33 Changed " Deleted" to "Not Used" 3 places in DCD I SSAR-12

Att chm:nt 2 (Continued) Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) DCD Section/Pg Difference 9.4-46 Changed " Deleted" to "Not Used" in DCD 9.4-55 Changed " Deleted" to "Not Used" 2 places in DCD Unitalicized " Requirement" and " Compliance" throughout section in DCD 9.5-9 Changed Item (5) to "Not Used"in DCD 9.5-10 Changed " Deleted" to "Not Used" in DCD 9.5-13 Changed " Deleted" to "Not Used" in DCD 9.5-22 Removed white space from DCD 9.5-69 Removed probabilities from DCD at end of first paragraph 9.5.12.3.3 9.5-71 Changed " Deleted" to "Not Used" in Item (1) in DCD 9.5-74 Changed " Deleted" to "Not Used" in DCD 9.5.13.12 9.5-76 Unitalicized referencesin DCD 9A-TOC Changed " Deleted" to "Not Used" 48 places in DCD 9A.2-4 Removed white space from DCD 9A.2-5 Item (10) Changed " Deleted" to "Not Used" in DCD 9A.2-7 Changed "SS AR" to ' Tier 2" last line in DCD 9A.2-8, 9 Changed "SSAR" to ' Tier 2" at top of fifth column and footnote in DCD 9A.3-2 Changed " Deleted" to "Not Used" in DCD 9A.4 Changed " Deleted" to "Not Used" throughout Unitalicized " Water level (Flood) Design throughout in DCD 9A.4-239 Removed white space from DCD 9A.5-13 Changed " Deleted" to "Not Used" in DCD 9A.5-16,17 Changed " Deleted" to "Not Used" and unitalicized paragraph headings in DCD 9A.5-16 Removed "of the SSAR" from two places in DCD 9A.5-17 Removed Section 9A.5.8 from DCD 9B Unitalicized paragraph titles in DCD 9B-10 Unitalicized referencesin DCD 9C-9 Removed white space from DCD Chapter 10 10.2-7 Removed Table 10.2-1 from DCD 10.2-16 Unitalicized referencesin DCD SSAR-13

. (Continued) Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) DCD Section/Pg Difference 10.3-4 Unitalicized 5 titlesin DCD 10.4-19 Removed section numbers 10.4.5.9, 10.4.5.9.1, 10.4.5.9.2, 10.4.5.10, 10.4.5.10.1, 10.4.5.10.2 from DCD 10.4-34 Changed onentation of table in DCD Chapter 11 11.0-iv Removed 11A table listings from DCD 11.0-v/vi Removed 11A figure listings from DCD ~ 11.1-7 Unitalicized referencesin DCD 11.1-7 Removed reference 11.1-5 from DCD ~ 11.3-25, 26 Unitalicized references in DCD 11A Removed DCD 11 A List of Tables and List of Figures Chapter 12 12.2-12 Unitalicized referencesin DCD 12.3-23 In first paragraph replaced " Certified Design Material (GE Doctunent 25A5447)" with ' Tier 1"in DCD 12.3-26 Replaced "DAC 3.7b" with " Table 3.2b of Tier 1" for DCD and "DAC3.7b" with " Table 3.2b of the CDM" for the SSAR 12.3-30 Unitalicized referencesin DCD 12.3-35 Changed " Deleted" to "Not Used" in DCD 12.3-36 Changed " Deleted" to "Not Used" in DCD 12.3-37 Changed " Deleted" to "Not Used" in DCD 12.4-8 Unitalicized referencesin DCD 12.4-9/10 Replaced "SSAR" with ' Tier 2"in DCD 12A-3 Unitalicized paragraph heading in DCD 12A-4 Unitalicized references in DCD Chapter 13 13.0-iii/iv Removed Table 13.6-1 and 13.6-2 listings from DCD Removed List of Figures from DCD 13.5-4-7 Unitalicized paragraph titles in DCD Chapter 14 14.0-ii Changed " Deleted" to "Not Used" in DCD 14.0-iv Changed CDM to Tier 1,5 places, and revised title of Section 14.3 in DCD SSAR-14 a

l Attrchment 2 (Continued) Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) l DCD Section/Pg Difference j 14.2-7 Unitalicized Reg. Guides in DCD 14.2-60 Removed deleted paragraph section 14.2.12.1.30 from DCD j 14.2-159 Changed "SSAR" to " Tier 2" 2 places in DCD l 14.2-190 Removed " deleted" paragraph section 14.2.12.2.41 from DCD 14.2-191 Removed " deleted" paragraph section 14.2.13.3 from DCD 14.3 Relabeling consistent with change from CDM/SSAR to Tier 1/ Tier 2 l in DCD 14.3-1 Changed Section Title in DCD 14.3-1 Modified first paragraph to better reflect the Tier 1 information in DCD 14.3-24-58 Changed "SS AR entry" to " Tier 2 entry" and "SSAR value" to ' Tier 2 value"in DCD Chapter 15 15.0-il Changed " Deleted" to "Not Used" in DCD 15.0-vii Changed " Deleted" to "Not Used" in DCD 15.0-ix/x Removed 15C tablelistings from DCD 15.0-xiv Changed " Deleted" to "Not Used" in DCD 15.0-xv Removed Figure 15B-8 for DCD and replaced Figure 15B-8 title with " Deleted" for SSAR 15.0-xvi Removed 15C figure listings from DCD 15.0-10 Changed font of table body in DCD 15.0-17 Changed page from portrait to landscape in DCD 15.1-4 Removed the phrase (...less than 0.0088 failure per reactor year..) from DCD Removed the phrase (less than 7x10 failure per reactor year) from DCD Changed phrase (...less than once per reactor year... ) to "very low" in DCD 15.1-5 Replaced "less than once per 10,000 years" with "so low that it" in DCD 15.1-8 Removed less than 7x10-5 failure per reactor year in next to last sentence in DCD Replaced "less than 0.0088 times per year" with "very low frequency" in DCD Replaced "less than once per 10,000 years" with " extremely low" in DCD 15.1-20 Cleaned up figure in DCD 15.2-1 Deleted "less than 7x10-3 failures per reactor year" in DCD 15.2-1 Deleted "(0.0088 failures per reactor year)" in DCD SSAR-15 _j

Att chm:nt 2 (Continued) Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) DCD Section/Pg Difference 15.2-2 Replaced "(less than one failure every 11 years)" in DCD 15.2-5 Removed probability numbers 4 places from DCD 15.2-7 Removed white space from DCD I 15.2-9 Modified paragraph and removed probability numbers 4 places in DCD 15.2-26 Unitalicized references in DCD 15.2-36 Cleaned up figure in DCD 15.3-5 Replaced "(less than 7x10-5 failures per year)" with "very low" in DCD 15.3-5 Replaced "about 0.0088 failures per reactor year" with "very low" in DCD 15.4-8 Replaced "(less than 7x10-5 failures per reactor year)" with "very low" 15.4-8 Replaced "About 0.0088 failure per reactor year" with "very low" in DCD 15.4-11 Replaced numerical value of probability with " expected frequency is low"in DCD 15.4-13 Removed probability numbers (3 places) from DCD 15.4-17 Changed " Deleted" to "Not Used" in DCD 15.6-17 Changed "the SSAR" to " Tier 2"in DCD 15.6-22 Removed deleted paragraph 15.6.7.2 from DCD 15.6-22, 23 Unitalicized references in DCD 15.7-11 Unitalicized referencesin DCD 15.7-14 Changed " Deleted" to "Not Used" in DCD 15A-1 Changed "the SSAR" to ' Tier 2"in DCD 15A Unitalicized paragraph headings in DCD 15A-111 Changed " Deleted" to "Not Used" in DCD 15B-4 Unitalicized paragraph headings in DCD 15C-1/2 Changed " Deleted" to "Not Used" in DCD 15D-2 Removed "(processor flow rate = 10-'/h)" from DCD 15D-2 Revised text to eliminate probability in DCD 15D-3,15D 5-8 Eliminated DCD figure / table contents and refer to SSAR 15E Unitalicized paragraph headings in DCD 15E-10 Unitalicized references in DCD 1 15E-33 Cleaned up figure in DCD SSAR-16

_. ~... _ _ _. Attechment 2 (Continued) j Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) i DCD Section/Pg Difference l 15F-1 Unitalicized paragraph heading in DCD l Chapter 16 t l Throughout The header and footer on each page of the DCD are changed as t follows: The GE document number in the header from the SSAR, l 23A6100 Rev. x, is deleted. The SSAR amendment number in the footer is replaced with "Rev. O, Design Control Document / Tier 2" Where the phrase "of the SS AR" is used to describe information in the SSAR,it is replaced in the DCD with the phrase "of the DCD Tier 2" j 4.0 Where the phrase "of the SSAR" is used to describe the applicant's 1 5.0 SSAR, it is replaced in the DCD with the phrase "of the FSAR" Throughout Where the phrase "in the SSAR, Chapter (or Section) x" is used to j point to the section of the SSAR,it is replaced in the DCD with the l phrase "in DCD Tier 2, Chapter (or Section) x" l Where the phrase "ABWR SSAR analysis" is used to describe the safety analyses in the SSAR, it is replaced in the DCD with the phrase { "ABWR safety analysis" i Where the phrase " transient or accident analysis in the ABWR SSAR" i is used with no specific chapter or section reference, it is replaced in the DCD with the phrase " transient or accident analysis for the i ABWR" i B 3.8 Where the phrase " described in the SSAR" is used to refer to Chapter { 8 of the SSAR, it is replaced in the DCD with the phrase " described in DCD Tier 2, Chapter 8" Where the phrase " requirement of Section x of the SSAR" is used to refer to certain requirement specified in the SSAR, it is replaced in the j DCD with the phrase " requirements of DCD Tier 2, Section x" Chapter 17 i 17.0-TOC Removed blank spaces throughout in DCD 17.0-1 Deleted "of this Standard Safety Analysis Report" from first sentence j mTD l 17.1-5/6 Unitalicized referencesin DCD 17.3-5 Added period to last sentence of section in DCD l 17.3.9 j Chapter 18 18.0-i Moved Appendices heading to top of following page in DCD 4 18.4-11 Unitalicized textin DCD 18B-1 Unitalicized textin footnote in DCD 18C-8 Page layout change in DCD 18E-1 Added italicized second paragraph and footnote in DCD Added " Staff" after "NRC" in third line of second paragraph in DCD i A 4 SSAR-17 t

l Attichment 2 (Continued) i Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) DCD Section/Pg Difference I 18E-1 Italicized entire sections and added footnote in DCD. thm 18E-5 i 18E-7 Italicized entire table and added footnote in DCD thru 18E-28 18E-29 Italicized entire attachment and added footnote in DCD thru 18E-35 l 18E-36 thru 18E-40 Italicized entire tables and added footnote in DCD

i 18H-7/8 Substituted DCD proprietary notice to reference SSAR l

Chapter 19 f 19-il Changed " Deleted" to "Not Used" in DCD 1 j 19-iii Removed listing for 19.14 from DCD i 19-iv Removed listing for 19D from DCD 19-ix Removed listing for tables 19.3-7-19.3-9 from DCD 1 19-ix Removed listing for 19D tables from DCD i 19-xi Removed listing for Table 19E.3-8 from DCD Removed listing for 19FA from DCD i 19-xiii Removed listing for table 19P-1 thru 19P-7 from DCD 19-xv Removed listing for 19D tables from DCD j 19-xxiv Changed DCD Figures 19I-1 thru 19I-25 listing referencing SSAR 1 i 19-xxiv Changed " Deleted" to "Not Used" in DCD i i 19-xxiv DCD 19Q figure listing replaced with reference to SSAR i { 19-xxiv DCD 19QA figure listings replaced with reference to SSAR 19.1-2 Deleted numerical probabilities (4 places) and substituted word values (2 places)in DCD l 19.1-2 Unitalicized referencesin DCD t j 19.2-1 and 19.2-2 Replaced "this SSAR" with ' Tier 2"in DCD l 19.2-4 Unitalicized referencesin DCD l 19.2-8/9 Unitalicized referencesin DCD i 19.3-1 Removed "two events per year. This total consists of one planned { reactor shutdown and one transient which results in reactor scram. j The expected number of planned shutdowns is" from the second 4 paragraph of the DCD. Removed "are the same as those used in the j-GESSARII PRA (Reference 19.3.3) and" from the third paragraph i of the DCD. b SSAR-18 a 3 1

Attrchment 2 (Centinued) Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) DCD Section/Pg Difference 19.3-1 Deleted Subsections 19.3.1.2.1 through 19.3.1.2.3 and inserted statement "not part of DCD (refer to SSAR)" in DCD 19.3-6 Unitalicized references in DCD 19.3-12 Eliminated probability values in first paragraph in DCD 19.3-18 Replaced "no more than 10%" with "a small percentage" in last paragraph in DCD 19.3-20 Replaced "of 1.6E-7 per year" with "is extremely small" in DCD 19.3-22 Unitalicized references in DCD 19.3-23,19.3-29 thru Deleted DCD frequencies and added footnote referring to SSAR 19.3-31 19.3-31 Deleted tables from DCD 19.3-33 Deleted body of figure and added footnote referring to SSAR in DCD 19.4-3 Removed probabilities in three places and inserted word values in two placesin DCD 19.4-4 Unitalicized references in DCD 19.4-5 Removed "of the SSAR" two places in DCD 19.4-11 Removed last two sentences of second paragraph in DCD 19.4-12 Eliminated two probability values in last paragraph in DCD 19.4-12 and 19.4-13 Eliminated six probability values in DCD 19.4-13 Replaced "10-7 per year" with "very small" in DCD 19.5-3/4 Deleted " Examining the data in Table 19.3-6, the CCFP PI is 0.007. Therefore," from the fourth paragraph in DCD 19.6-1 Eliminated probability values in 5 places in DCD 19.6-3 Eliminated probability values in 2 places in the next to last paragraph in DCD 19.6-4 thru 19.6-5 Eliminated probability values in ten places in DCD 19.6-6 Unitalicized references in DCD 19.7-3 Replaced two numerical probabilities with word values in DCD 19.7-10 Unitalicized reference in DCD 19.8-1 Replaced "the Certified Design Material (Section 14.3)" with " Tier 1 ir, DCD 19.8-2 thru 19.8-23 Eliminated all probability values in DCD 19.8-24 Changed "Section" to " Attachment" and deleted "of the ABWR SSAR" under " vessel depressurization" in DCD SSAR-19

I Attschment 2 (Continued) Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) DCD Section/Pg Difference 19.9-6 Unitalicized referencesin DCD 19.9-7 Replaced "(i.e.,less than one foot) and also prevent accumulation in one area flowing to "with m" under item (3) (b) in DCD 19.9-7 Removed "with an unavailability of IE-3 per demand or less" from DCD 19.10-3 Deleted second sentence in DCD 19.10-3 and 19.10-4 Deleted "as 0.99" in second sentence, and deleted from third sentence on in DCD 19.14 Removed section 19.14 from DCD 19A-1 Replaced "SSAR" with " Tier 2" in 2 places in DCD 19A-1 Unitalicized references throughout in DCD 19A-21 thru 19A-23/24 Changed "SSAR" to " Tier 2" in right hand column in DCD 19B Changed "SSAR" to " Tier 2" throughout in DCD Unitalicized references and headings throughout in DCD 19B-9 Removed" Deleted"sectionsin DCD 19B-119 Removed "For the SSAR" in DCD 19C-1/2 Replaced " Safeguards information provided under separate cover" with "This section is not part of the DCD (refer to SSAR) " 19D-1/2 Removed entire Appendix 19D and replaced with "This section not part of the DCD (refer to SSAR)"in DCD 19E-vi Removed table 19E.3-8 from DCD 19E-xvi Removed Figure 19E.3-2 from DCD 19E.2-5 Changed " Deleted" to "Not Used" in DCD Removed " deleted" items from DCD 19E.2-11 thru Modified statement pertammg to probabilities in DCD 19.E.2-13 19E.2-19 Deleted "of the SSAR" in DCD 19E.2-25 Modified second sentence to eliminate failure rate and melded the second and third sentence for clarification in DCD 19E.2 Eliminated probability values and replaced them with word values throughout m DCD 19E.2-87 Unitalicized referencesin DCD 19E.2-101 Deleted "the ABWR SSAR" from the first sentence in DCD 19E.2-154-157 Unitalicized references in DCD SSAR-20

Attrchment 2 (Continued) Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) DCD Section/Pg Difference 19E.2-158 Extra page added with statement "In order to maintain consistency with the SSAR, this page has been intentionally left blank"in DCD ( 19E.2-188 Cleaned up figure in DCD 19E.2-259 Eliminated probabilities and added note " probabilities not part of thm DCD (refer to SSAR)"in DCD 19E.2-274 19E.3-1 Removed information from body of figures and added note "Not part i of DCD (refer to SSAR)"in DCD 19E.3-3 Replaced "98.6%" with "a very large percentage" in second i paragraph in DCD l 19E.3-5 Unitalicized references in DCD 'i f 19E.3-3 Replaced "the SSAR" with " Tier 2" in first paragraph in DCD l 19E.3-10 Removed table 19E.3-8 from DCD l 19E.3-3 Removed probabilities from DCD and added note " Probabilities not l 19E.3-9 part of DCD (refer to SSAR)" 19E.3-10 19E.3-11 Removed body of figure from DCD and added note " Figure is not l part of DCD (refer to SSAR)" ] 19E.3-12 Removed Figure 19E.3-2 from DCD 19EA Removed numerical probabilities from DCD and, where applicable, l 1 replaced with word values throughout i 19EA-29 Unitalicized referencesin DCD l 19EA-32 thru Deleted body of figures from DCD and added note " Figures not part i 19EA-37,19EA-39 of DCD (refer to SSAR)" i 19EA-40,19EA-45 19EA-46 19EB-2,19EB-3 Replaced numerical probabilities with word values in DCD 19EC-4 Unitalicized Referencesin DCD 19EC-4 Removed probabilities from DCD and added note " Probabilities not part of DCD (refer to SSAR)" 19EC-5 Removed numerical probabilities from DCD and, where applicable, l thru replaced with word values 1 19EC-14 l 19EC-26 Unitalicized referencesin DCD 19EC-29,19EC-30 Removed body of figures from DCD and added note " Probabilities 19EC-36 not part of DCD (refer to SSAR)" 19ED-26,27 Unitalicized referencesin DCD l i { SSAR-21 i

, (C@ntinued) Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) DCD Section/Pg Difference 19EE-3,19EE-5 Removed vacuum breaker related probabilities from DCD 19EE-6 19EE-11,19EE-12 Replaced numerical probabilities with word values in DCD 19EE-13 19EE-13 Unitalicized references in DCD 19EE-17 Removed probabilities from5CD and added note " Probabilities not part of DCD (refer to SSAR)" 19EE-16 Removed body of figures from DCD and added note " Probabilities 19EE-17/18 not part of DCD (Refer to SSAR)" 19F-16,17 Unitalicized references in DCD 19F Cleaned up several figures in DCD Figures 19FA-1/2 Removed attachment 19FA from DCD and added note 'This attachment is not part of the DCD (refer to SSAR)." 19G-1/2 Changed " Deleted" to "Not Used" in DCD 19H-4 Removed "of 3G (Table 19H-1)" from DCD 19H-14 Deleted last sentence of first paragraph from DCD 19H-15 Deleted DCD last sentence oflast paragraph and last sentence of fourth to last paragraph. 19H-17 Changed "the SSAR" to " Tier 2" and "ITAAC" to " Tier 1" in DCD 19H-20, 21 Unitalicized referencesin DCD 19H-23 Changed " probability" to " fragility" in footnote 1 and modified footnote 5 to eliminate specific values in DCD 19H-24 Removed fragilities from DCD and added note " Fragility not part of thru DCD. Refer to SSAR" 19H-32 1 19I-2, 191-3 Removed fragilities and corresponding probabilities in DCD 19I-4, 191-5 191-8, 191-9 19I-10 191-10 Unitalicized referencesin DCD 19I-11, 19I-12 Removed fragilities and HCLPF values from table of DCD and 19I-13 extended note to read " Fragilities and HCLPF values are not part of DCD (refer to SSAR)" 19I-14 Removed body of tables from DCD and added note "This table is not part of DCD (refer to SSAR)" 19I-15 Fragilities and HCLPF values deleted from table of DCD and added note "Fragi ities and HCLPF values are not part of DCD (refer to SSAR)" SSAR-22

4 i Att:chment 2 (Continued) Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) 4 I DCD Section/Pg Difference 191-16 Body of table deleted from DCD and added note "This table is not part of DCD (refer to SSAR)" 191-17/18 Deleted figures from DCD and added note " Figures 19I-1 through 19I-25 are not part of DCD (refer to SSAR)" 19J-1/2 Changed " Deleted" to "Not Used" in DCD 19K-2,19K-5 Replaced numerical probability values with word values in DCD 19K-8,19K-12 19K-17 19K-17,18 Unitalicized references in DCD 19K 19 thni Removed numerical values from tables of DCD and added note "Not 19K-21 part of DCD (refer to SSAR)" 19K-22 thru Removed numerical values in right hand column of DCD and added 19K-31/32 note "Not part of DCD (refer to SSAR)" 19L-1 Replaced "the ABWR Safety Analysis Report (SS AR)" with " Tier 2" in DCD 19L-2 Replaced numerical probability value with word value in DCD 19L-3 Removed "SSAR" from DCD 19L-8 Removed last sentence from item (3) from DCD 19L-8 Removed probability statement in last paragraph from DCD 19L-21 Deleted probabilities in second paragraph of DCD 19L-21/22 Deleted "SSAR" in DCD 19L-23 Replaced numerical values of probabilities with word values in DCD 19L-24 19L-26 Unitalicized references in DCD 19M-1,19M-2 Replaced numerical probability values with word values in DCD 19M-3,19M-7 19M-8 19M-1 Changed "1.0E-06 per year" to "an acceptably small criterion" in DCD 19M-9 Removed frec uencies from DCD and added note "Not part of DCD 19M-10 (refer to SSAR)". 19M-10,19M-11 Replaced numerical values of probabilities with word values in DCD 19M-12 19M-12 Unitalicized references in DCD 19M-13,19M-33 Removed frequencies from DCD and added note "Not part of DCD thru (refer to SSAR)". 19M-35 SSAR-23

i. i ) (Continued) Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) DCD Section/Pg Difference 19M-16 Deleted body of tables from DCD and added note "Not part of DCD thru (refer to SSAR)". l 19M-33 l 19M-38 thru Deleted body of figures from DCD and added note "Not a part of 19M-48 DCD (refer to SSAR)". 19N-4 Unitalicized textin DCD t i 19N-1,19N-12 Removed numerical probabilities from DCD j 19N-13 19N-15,19N-17 Replaced numerical probabilities with word values in DCD } 19N-18 l 19N-19 Unitalicized referencesin DCD 19P-1/2 Removed Appendix 19P in its entirety from the DCD and the SSAR and added notes appropriate to both j 19Q-2 In last paragraph of DCD replaced "the SSAR" with " Tier 2" and replaced "the Inspections, Test, Analysis, and Acceptance Criteria (ITAAC Requirement)" with ' Tier 1". l 19Q Replaced numerical probability values with word values throughout j mTD 19Q-39 Unitalicized references in DCD 19Q-45 Remoyed unavailability values from table of DCD and added note j "Not a part of DCD (refer to SSAR)" 1 19Q-57 Removed all figures from DCD and replaced with note " Figures 19Q-I thru 1 through 19Q-19 are not part of DCD (refer to SSAR)" 19Q-75n6 l 19QA-1 Removed all figures from DCD and replaced with note " Figures 19A-1 thru la through 19QA-20 ck are not part of DCD (refer to SSAR)" 19QA-412 l 19QB-4 Unitalicized references in DCD i l 19QB-5,19QB-6 Rempved probabilities from DC ' and added note "Not part of DCD l (refer to SSAR)". l 19QC-1 Unitalicized references in DCD 19R-1,19R-2 Replaced numerical values of probability with word values in DCD l 19R-3 19R-7 Unitalicized references in DCD l 19R-4 Replaced "SS AR" with " Tier 2" in DCD j 19R-24 19R-9 Replaced "2 hours" with "several hours" in fourth paragraph in DCD i i r j SSAR-24

l

(Continued)

Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) DCD Section/Pg Difference 19R-21,19R-22 Replaced numerical probaP tics with word values in DCD 19R-25,19R-27 19R-28,19R-29 19R-30,19R-31 19R-31 Deleted reliability goals from Utu and added note "Not a part of DCD (refer to SSAR)". 19R-35 Frequency / probability delad from DCD and added note "Not a part thru 19R-37 of DCD (refer to SSAR)'. 19R-47 thni 19R-53/54 Removed body of figures from DCD and added note "Not a part of DCD (refer to SSAR)". Chapter 20 Unitalicized text throughout DCD 20.1-1 Added new paragraph on relationship of SSAR and Tier 2 " names" in Chapter 20in DCD 20.1-32, 33 Removed extra space from DCD 20.3.3-60 Naned upimagein DCD 20.3.2-62 Ganed upimage in DCD 20.3.3-24 Changed " Deleted" to "Not Used" in DCD 20.3.4-38, 39 Removed from DCD l 20.3.6-27 Removed from DCD 20.3.8-37 Italicized item (1) and added footnote in DCD 20.3.8-51 and Italicized third and last paragraphs of response and added footnotes 20.3.8-52 in DCD 20.3.8-96 Changed " Deleted" to "Not Used" in DCD 20.3.9-1 thru Deleted responses from DCD and added " Response to Chapter 19" 20.3.9-15/16 questions not part of DCD (see SSAR Subsection 20.3.9)". 20.3.11-10 thru Deleted responses from DCD and added " Response to Chapter 19 20.3.11-11/12 questions not part of DCD (See SSAR Subsection 20.3.11)". 20.3.12-1 thru 20.3.12-Deleted responses from DCD and added " Response to Chapter 19 9/10 questions not part of DCD (see SSAR Subsection 20.3.12)". 20.3.12-5 Removed event / frequency table from end of response in DCD 20.3.14-15 Unitalicized textin footnotein DCD l 20.3.14-29 thru Deleted responses from DCD and added " Response to Chapter 19 20.3.14-32 questions not part of DCD (see SSAR Subsection 20.3.14)". 20.3.14-33 Cleaned up figure in DCD SSAR-25 l

I j Att: chm:nt 2 (Continu:d) l Difference between DCD, Revision 3 and SSAR Amendment 37 (Revision 9) l DCD Section/Pg Difference 20.3.15-37 Changed notation " Response to this question is provided under i thru separate cover" to " Safeguards Information not part of DCD (see 20.3.15-39 SSAR Subsection 20.3.15)" in DCD a l 20.3.16-30 Removed extra space from DCD e i 20.4-1 Unitalicized references in DCD i Chapter 21 21-103 and 21-127 Italicized note 32 and 29 of DCD, respectively, and added footnotes in figures 5.4-10 and 6.3-7 l t l h 8 I i 1 5 i i l i l 4 SSAR-26

ABWR Design Control Document Revision 3 - Page Change Instruction The following pages have been changed, please make the changes in your copy of the Design Control Document. Pages are listed below as page pairs (front and back), except Chapter 16, which is single-sided. Remove Pares Add Pares Remove Pares Add Pares Replace the cover sheet and insert DCD TOC in Chapter 3 (Cont) 3.8-31, 32 3.8-31, 32 Insert Effective Pages 1 thru 9 before DCD Introduction tab in Volume 1. 117,118 117,118 Ter1 123,124 123,124 127 thm 130 127 thru 130 2.2.4-1, 2 2.2.4-1, 2 31-17,18 3117,18 2.11.3 1,2 2.11.3-1,2 5,6 5,6 SMA-13 thru 16 SMA-13 thru 16 9,10 9,10 Chapter 5 2.11.5-1, 2 2.11.5-1, 2 5.4-21, 22 5.4-21, 22 2.11.61 thru 6 2.11.61 thru 6 27,28 27,28 61,62 61,62 2.15.51 thru 10 2.15.5-1 thru 10 13 thru 26 13 thru 26 Chapter 6 33,34 33,34 6.2-11,12 6.2-11, 12 2.15.10-7, 8 2.15.10 7,8 183,184 183,184 11 thru 14 11 thn 14 6.4-7, 8 6.4-7,8 2.15.12-3,4 2.15.12-3,4 Chapter 7 9,10 9,10 7.3-57 thru 60 7.3-57 thni 60 3.2-5, 6 3.2-5,6 91,92 91,92 9 thru 12 9 thru 12 17,18 17,18 Chapter 9 23,24 23,24 9.0-v/vi 9.0+/vi App A-5,6 App A-5,6 9.2-5, 6 9.2-5, 6 Tier 2 19,20 19,20 31 thru 34 31 thru 34 g 49 thru 52 49 thru 52 57 thru 60 57 thru 60 1.2-29,30 1.2-29,30 67,68 67,68 1.9-11,12 1.9 11,12 9 3-13, 14 9'S I3' I4 Chapter S 3.2-43,44 3.2-43, 44 (1)

ABWR Design Control Document Revision 3 - Page Change Instruction 'Ihe following pages have been changed, please make the changes in your copy of the Design Control Document. Pages are listed below as page pairs (front and back), except Chapter 16, which is single-sided. Remove Pares Add Pares Remove Pares Add Pares { Chapter 9 (Cont) Chapter 15 (Cont) 9.41 thru 6 9.4-1 thru 6 15.631 thru 34 15.631 thru 34 9,10 9,10 37 thru 40 37 thru 40 17,18 17,18 45,46 45,46 21 thru 24 21 thru 24 33,34 33, 34 Chapter 16 43 thni 48 43 thru 48 2.0-1 2.0-1 9.5-9 thru 14 9.5-9 thru 14 3.3-12 3.3-12 9A.0-v, vi 9A.0-v, vi 42 42 vii. viii vii, viii 3.4-3 3.4-3 9A.4-263,264 9A.4-263,264 287,288 287,288 291,292 291,292 3.7-3 3.7-3 293,294 293,294 6 6 305,306 305,306 8 8 313,314 313,314 319,320 319,320 4.0-2 4.0-2 417,418 417,418 437,438 437,438 B3.4-8 B3.4-8 449 thru 452 449 thru 452 9 9 457 thru 460 457 thru 460 B3.5-4 B3.54 9A.477 thru 96 9A.477 thru 96 7 7 101 thru 106 101 thru 106 17 17 i 9C 1,2 9C-1, 2 B3.7-4 B3.7-4 9,10 9,10 5 5 6 6 Chapter 14 7 7 13 13 14.2-59 thru 62 14.2-59 thru 62 g7 17 14.5-27 thru 30 14.3-27 thru 30 Chapter 19 Chapter 15

19., i; 19.g, ;

15.1-9,10 15.1-9,10 19.4-11 thru 14 19.4-11 thru 14 15.2-15,16 15.2-15,16 19.8-7, 8 19.8-7,8 15.G7,8 15.67,8 19.9 11,12 19-11,12 15 thru 18 15 thru 18 25 thru 28 25 thru 28 (2)

ABWR Design Control Document Revision 3 - Page Change Instruction The following pages have been changed, please make the changes in your copy of the Design Control Document. Pages are listed below as page pairs (front and back), except Chapter 16, which is single-sided. Remove Pares Add Pares Remove Pares Add Pares Chapter 19 (Cont) Chapter 21 (Cont.) 21-547 21-547 191-3 thru 10 191-3 thru 10 548 548 13,14 13,14 560 560 19P-1/2 19P-1/2 561 561 565 565 19QC 3,4 19QC-3,4 571 571 Gianter 21 E E 588 588 21 11 21-11 590 590 12 12 591 591 26 26 598 598 32 32 600 600 f3 601 601 73 100 100 616 616 102 102 617 617 259 259 623 623 260 260 629 629 261 261 630 630 263 263 633 633 264 264 267 267 488 488 489 489 495 495 509 509 510 510 513 513 518 518 519 519 526 526 535 535 536 536 537 537 538 538 539 539 542.1 542.1 542.2 542.2 542.3 542.3 543 543 544 544 545 545 (3)

5 ABWR Certified Design Material Rev. 8 - Page Change Instruction The following pages have been changed, please make the changes in your copy of the CDM. Pages are listed below as page pairs (front and back). Remove Pages Add Pages Remove Pages Add Pages 2.2.4-1, 2 2.2.+1, 2 l 2.11.5-1, 2 2.11.3-1, 2 5, 6 5, 6 9,10 9,10 2.11.5-1, 2 2.11.5-1, 2 l 2.11.6-1 thru 6 2.11.6-1 thru 6 1 2.15.5-1 thru 10 2.15.5-1 thru 10 13 thni 26 13 thru 26 33,34 33,34 2.15.10-7,8 2.15.10-7, 8 11 thru 14 11 thru 14 2.15.12-3,4 2.15.12-3,4 9,10 9,10 3.2-5,6 3.2-5,6 9 thru 12 9 thru 12 17,18 17,18 23,24 23,24 App A-5,6 App A-5,6 (1)

s ABWR Standard Safety Analysis Report, Amendment 37 Rev. 9 - Page Change Instruction The following pages have been changed, please make the changes in your copy of the SSAR. Pages are listed below as page pairs (front and back), except Chapter 16, which is single-sided pages only. Remove Pages Add Pages Remove Pages Add Pages Replace the cover sheet in each volume Chapter 9 (Cont) 9.2-5, 6 9.2-5, 6 O*P'" I 19,20 19,20 31 thru 34 31 thru 34 1.2-31,32 1.2-31,32 51 thru 54 51 thm 54 1.9 11,12 1.9-11,12 59 thru 62 59 thru 62 69,70 69,70 Chapter 3 9.3-13,14 9.3-13,14 3.2-43,44 3.243,44 9.4-1 thru 6 9.4-1 thru 6 3.8-29,30 3.8-29,30 9,10 9,10 17,18 17,18 3.9 97,98 3.9-97,98 21 thru 24 21 thru 24 117,118 117,118 31 thru 34 31 thru 34 123,124 123,124 43 thru 48 43 thru 48 tm 0 127 h 130 9.5-9 thru 14 9.5-9 thru 14 31-17,18 31-17,18 9A.0-v, vi 9A.0-v, vi 3MA-13 thru 16 ShiA-13 thru 16 9A.4-263,264 9AA-263, 2fA Chapter 5 287,288 287,288 291,292 291,292 5.4-21,22 5.4-21,22 293,294 293,294 27,28 27,28 307,308 307,308 61,62 61,62 315,316 315,316 321,322 321,322 Chapter 6 417 thru 420 417 thru 420 437 thru 440 437 thru 440 6.2-12,13 6.2 12,13 451,452 451,452 183,184 183,184 459,460 459,460 6.4-7, 8 6.4-7, 8 9A.677 thm 96 9A.6 77 thru % 101 thru 106 101 thru 106 Chapter 7 9G1, 2 9G1, 2 7.3-57 thru 60 7.3-57 thru 60 11,12 11,12 91,92 91,92 Chapter 14 Chapter 9 14.2-59 thru 62 14.2-59 thru 62 9.0-v/vi 9.0-vAi 169,170 169,170 (1)

4 ABWR Standard Safety Analysis Report, Amendment 37 Rev. 9 - Page Change Instruction 1 1 The following pages have been changed, please make the changes in your copy of the SSAR. Pages are listed below as page pairs (front and back), except Chapter 16, which is single-sided pages only. Remove Pages Add Pages Remove Pages Add Pages i Chapter 14 (Cont) Chapter 19 1 14.3-1,2 14.31,2 19-i, ii 19-i, ii j 29,30 29,30 vil/viii vii, viii Chapter 15 19.+11 thru 14 19.4-11 thru 14 15.1-9,10 15.1-9,10 19.8 7, 8 19.84, 8 15.2-15,16 15,16 19.9 11,12 19-11, 12 l ,6 mM,6 15.47,8 15.6 7,8 { 15 thru 18 15 thru 18 17,18 17,18 25 thm 28 25 thru 28 19D.4-7, 8 19D.4-7, 8 4 31 thm 34 31 thru 34 j 37 thru 40 37 thru 40 19D.6 5 tluu 8 19D.5-5 thru 8 i 45,46 45,46 231,232 231,232 Chapter 16 191-3 thru 6 191-3 thm 6 i 2.01 2.0-1 9,10 9,10 13 thru 20 13 thru 20 3.3 12 3.3-12 33,34 33, 34 3.4-3 3.4-3 1 19P-1/2 19P-1/2 s 3.5-6 3.54 19QC-3,4 19QC-3,4 3.7-3 3.7-3 6 6 Chapter 21 21-11 21-11 4 4.0-2 4.02 12 12 ] 26 26 B3.4-8 B3.4-8 32 32 9 9 33 33 73 73 j B3.5-4 B3.5-4 100 100 l 7 7 102 102 17 17 259 259 260 260 B3.7-4 B3.7-4 261 261 5 5 263 263 6 6 264 264 7 7 267 267 13 13 488 488 17 17 3 E (2)

b s ABWR Standard Safety Analyms Report, Amendment 37 hv. 9. Page Change Instruction The following pages have been changed, please make the changes in your copy of the SSAR. Pages are listed below as page pairs (front and back), except Chapter 16, which is single 4ided pages only, hmove Pages Add Pages Remove Pa;es Add Pages Chapter 21 (Cont) 21-489 21-489 495 495 509 509 510 510 513 513 518 518 519 519 526 526 535 535 536 536 537 537 538 538 539 539 542.1 542.1 542.2 542.2 542.3 542.3 543 543 544 544 545 545 547 547 548 548 t 560 560 561 561 l 565 565 571 571 572 572 588 588 590 590 591 591 598 598 600 600 601 601 j 616 616 617 617 623 623 629 629 630 630 633 633 (3)

25AS447 Rev. 3 ABWR Certified Design Material 2.2.4 Standby Liquid Control System Th-Standby Liquid Control (SLC) System injects neutron absorbing poison into the reactor using a boron solution, thus providing the safety-related function of backup reactor shutdown capability independent of the normal reactivity control system based on insertion of control rods into the core. The SLC System is designed to bring the reactor from full power to a subcritical condition without control rod movement, at any time in a core cycle, and at design basis conditions with the reactor in the most reactive xenon-free state. The SLC System operates over a range of reactor pressure conditions which bound the elevated pressures associated with an anticipated transient without scram (ATWS). Figure 2.2.4 shows the basic system configuration and scope. The SLC System consists of a boron solution storage tank, two positive displacement pumps, two motor-operated injection valves which are provided in parallel for redundancy, and associated piping and valves used to transfer borated water from the storage tank to the reactor pressure vessel (RPV). The borated solution is discharged through the high pressure core flooder (HPCF) Division B subsystem sparger. The SLC System uses a dissolved solution of sodium pentaborate as the neutron-absorbing poison. This solution is held in the storage tank which has a heater to maintain solution temperature above the saturation temperature.The heater has ) s automatic actuation and automatic shutoff. A test tank and associated piping and valves permit testing of the SLC System during plant operation. The tank is supplied with demineralized water, which is pumped in either a closed loop or is injected into the reactor. Key SLC System equipment performance requirements are: (1) Pump flow (minimum) 378 L/ min with both pumps operating 189 L/ min with one pump operating l (2) Maximum reactor pressure 8.72 MPaA (for injection) 8 (3) Pumpable volume in storage 23.1 m tank (minimum) The SLC System can be manually initiated from the main control room. Each of the two divisions is controlled by a separate switch. When it is manually initiated to inject a liquid neutron absorber into the reactor, the following devices and actions are initiated by each divisional switch: (1) The specified division injection valve is opened. Standby Liquid Control System 2.2.41

2SAS447 Rsv. 8 ABWR cenitiescesign unterias O (2) The specified dhision storage tank discharge valve is opened. (3) The specified division injection pump is started. (4) The reactor water cleanup isolation valves are closed. Both divisions of the SLC System are automatically initiated during an ATWS condition by safety system and logic control (SSLC) logic. With the storage tank at minimum level and both pumps operating, the system is designed to inject the minimum required boron solution. Each SLC System pump has an interlock which prevents operation if both the test tank outlet valve and the pump suction valve are closed. The SLC System provides borated water to the reactor core to compensate for the various reactivity effects. These effects are xenon decay, elimination of steam voids, changing water density due to the reduction in water temperature, Doppler effect in uranium, changes in neutron leakage, and changes in control rod worth. To meet this objective, it is necessay to inject a quantity of boron which produces a minimum concentration of 850 parts per million (ppm) by weight of natural boron in the reactor core at 20 C. To allow for potential leakage and imperfect mixing in the reactor system, an additional approximately 25% (220 ppm) is added to the above requirement, resulting in a total requirement of greater than or equal to 1070 ppm. The required concentration is thus achieved in a mass of water equal to the sum of the mass of water 3 in the RPV at normal water level (equal to or less than 455 x 10 kg) plus the mass of 3 water in the RPV shutdown cooling piping (equal to or less than 130 x 10 kg). The quantity of boron solution contained in the storage tank above the pump suction shutofflevel provides the required concentration of 1070 ppm when injected into the reactor. The SLC System pumps have sufficient net positive suction head (NPSH) available at the pump. The SLC System pumps are designed to produce discharge pressure to inject the solution into the reactor when the reactor is at pressure conditions corresponding l to the system relief valve (10.79 hfPaG), which is above peak ATWS pressure in the RPV. SLC System components required for RPV injection are classified as Seismic Category 1. Figure 2.2.4 shows the AShiE Code class for the SLC System piping and components. The SLC System is located in the Reactor Building. The storage tank, test water tank, the two positive displacement pumps, and associated vahing are located in the seconday containment on the floor elevation below the operating floor. Each of the two SLC System divisions is powered from the respective Class 1E division as shown on Figure 2.2.4. The power supplied to one motor-operated injection valve, 2.2.42 Standby Liquid Control System

2SAS447 Rev. 8 ABWR conmedoesion sterist bd 2.11.3 Reactor Building Cooling Water System Design Description The Reactor Building Cooling Water (RCW) System distributes cooling water through three physically separated and electrically independent divisions. The system removes heat from plant auxiliaries and transfers it to the Ultimate Heat Sink (UHS) sia the Reactor Senice Water (RSW) System. The RCW System removes heat from emergency core cooling equipment, including the emergency diesel generators (DGs) during a safe reactor shutdown cooling function. RCW System configurations are shown in Figures 2.11.3a,2.ll.3b, and 2.ll.Sc. Figure 2.11.3d shows the RCW System control interfaces. All components cooled by the RCW System are parts of other systems and are not part of the RCW System. Each RCW division includes two pumps which circulate cooling water through the equipment cooled by the RCW System and through three heat exchangers which transfer the RCW heat to the UHS via the RSW System. The RCW System performs a safe reactor shutdown cooling funcdon following either a lossef-coolan t acciden t(LOCA) or a loss-of-preferred-power (LOPP)or both. Assuming a single active failure in any mechanical or electrical division or RCW support system, [' which disables any one of the three RCW divisions, the other two divisions perform safe reactor shutdown cooling. Tables 2.11.3a,2.11.3b, and 2.11.Sc show which equipment receives RCW flow during various plant operating and emergency conditions. The tables also indicate how many heat exchangers are in senice under each condition. The RCW System is classified as safety-related except for those portions as shown on Figures 2.11.3a,2.ll.3b, and 2.11.Sc as non-nuclear safety. The RCW System responses to a LOCA signal are the following: (1) Starts any standby RCW pumps. (2) Opens any closed standby RCW heat exchanger outlet valves. (3) Opens all Residual Heat Removal (RHR) System heat exchanger cooling water outlet valves. (4) Closes all RCW containment isolation valves. (5) Closes valves to the following non-safety-related components (to Reactor l Water Cleanup System (CUW) and reactor internal pump (RIP) MG sets). ( ,\\ l Reactor Building Cooling Water System 2.11.3-1 l l j

25AS447 Rtv. 3 ABWR certifiedoesion Material O (6) Opens the RCW watec temperature pneumatic control valves (located downstream of RCW heat exchangers) and closes the RCW heat exchanger bypass valves. (7) Overrides the RCW pump trip signal from low surge tank and low stand pipe level. Safety-related valves separate the safety-related portions of the RCW System from the non-safety-related portions of the system. The separation valves to the non-safety-related RCW System are automatically or remote-manually operated, and their positions are indicated in the main control room. Component design parameters are: Division A/B Division C 3 3 l Discharge flow rate (per pump) 21420 m /h 21237 m /h Heat exchanger design basis heat 2 47.73 GJ/h 2 44.38 GJ/h removal capacities:(per heat exchanger) These heat removal capabilities include a 20% margin above the minimum required for design basis accident conditions. Consequently, plant operation is acceptable with heat exchanger capacities greater than or equal to 80% of these values. Figures 2.11.Sa,2.11.3b, and 2.11.Sc show the ASME Code Class for the RCW System piping and components. The safety-related portions of the RCW divisions are classified as Seismic Categog I. The piping to the fuel pool cooling (FPC) system heat exchangers and room coolers are classified as Seismic Category 1. The RCW pumps and heat exchangers are located in the lower floors of the Control Building. The equipment cooled by the RCW divisions are located in the Control Building, Reactor Building, Turbine Building, and Radwaste Building, (Figures 2.11.3a, 2.11.3b, and 2.11.Sc). Each of the three RCW divisions is powered from its respective Class lE division as shown in Figures 2.11.3a,2.11.3b, and 2.11.Sc. In the RCW System, independence is provided between the Class IE divisions and also between the Class IE divisions and non-Class 1E equipment. The safety-related portion of each mechanical division of the RCW System (Divisions A, B, C) is physically separated from the safety-related portions of the other divisions. 2.11.3 2 Reactor Building Cooling Water System ?.

2SAS447 Rev. 8 ABWR certifiedoesiga nateriai /^N ld MUWP RCW RCW OTHERS OTHERS RCW 3 SPCU RCW l RHR HX ] I (Reactor Budding) 1 I J Q I l M R SURGE TANK l DG HX ] (Reactor Buildng) L l (Reactor Building) ] 3 RCW l l l HECW u ~ ' Fuel Pool Cooling HX and Room Coolers ~ W L TO (Reactor Building) 3 NNS 'l J NNS 3 HECW l l OTHER (SAFETY-RELATED) HXs l (Reactor and Control Building) j N p FE MR y NNS, i CRD AND CUW PUMPS - r-i h-N, (R. ,, m n,, _ _ _ _3_lNNS_ j l j {NNSl3 l B 1 1 H___ __s (R= N) H--------i e i 0" i i ~g~ NON-SAFETY-RELATED HXs i ~~~~~~~ (Control Building) j NON-SA LA D HXs i M / i e M p M i w_q' DRvwELL EOUiPuENT COOLERS (__ ;_ J L_. NNS 2 d 2lNNSI I *** * "9I J NNS 2 j 2lNNS s :n RCW HX i R " FROM (Control Budding) 3 RCW RSW W Q RSW RM TO RSW RCW PUMP ( 0 RCW HX m (Control Building) 3RCW RS M RSW Ry TO RSW g RCW HX C W (Control Buinng) 3 RCW FROM RCW PUMP RSW M RSW (Control Buibng) NOTES:

1. ALL ELECTRICAL POWER LOADS FROM THE CLASS 1E COMPONENTS SHOWN

= PRIMARY CONTAINMENT ON THIS FIGURE ARE POWERED FROM CLASS 1E DIVISION I EXCEPT FOR THE A}

( OUTBOARD CONTAINMENT ISOLATION VALVE, WHICH LS POWERED FROM DIVISION 11. (/ Figure 2.11.3a Reactor Building Cooling Water System (RCW-A) Reactor Building Cooling Water System 2.11.3-S

25AS447 Rev. 8 ABWR certifiedDesign Material O M MUWP RCW OTHERS RCW RCW OTHERS 3 3 p FE SPCU RCW r -- - - - - - - 9 R 3 RHR HX (Reactor Building) W l J L I I SURGE TANK P ~ ~~~~ ~ ~ ~ ~ 7 (Reactor Building) L i OG HX 1 (Reactor Building) '~ t J 3RCW l __ _ _ _ _ _ _ _l l HECW ~ Fuel Pool Cooling HX and Room Coolers ~ W L Y (Reactor Building) 3 NNS NNS 3 q OTHER(SAFETY-RELATED)HXs I (Reactor and Control Building) ] RCW OTHERS OTHERS RCW NNS NNS FE R r---- 1 ~ CUW PUMP "lNNS I (Reactor Building) 3 I J NNSl3 r-oM L _ _ _ _ _ _ _l g ------i j F---d--a (Rea!",";,n,, i- - - - - - - - --l c l_ _J g i M l 1 h __q

Control. Reactor, and Turbine Building) p _ _ _ _ _ __]8 NON-SAFETY-RELATED HXs R

g gM gM gM i u w_q,_oaYwEtt EcuiPuENT cooteRS Le g_ e jai ( Reactor Building) NNSl2 2lNNS _] NNSl2 / 2lNNS r 2 m j RCW HX R l W (Control Building) 3RCW RSW ) R M TO RSW RCW PUMP RCW HX ( "9' . W (ControlBuilding) 3 RCW rm TO RSW asw t__ R RCW HX W (Control Building) 3RCW hO SW RCW PUMP TO RSW (Control Dueng) NOTES:

1. THIS DIVISION IS POWERED FROM CLASS 1E DIVISION 11,

= PRIMARY CONTAINMENT EXCEPT FOR THE CONTAINMENT OUTBOARD ISOLATlON VALVE, WHICH IS POWERED FROM OfVISION lit.

Figure 2.11.3b Reactor Building Cooling Water System (RCW-B) 2.11.3-6 Reactor Building Cooling Water System

. -= i 25AS447 R1v. 8 ABWR certitiesoesign uateriat i Table 2.11.3a Reactor Building Cooling Water Cooling Loads Division A l Hot l Standby Normal (loss of Operating AC Emergency Operating Mode / Components

Conditions Shutdown Power)

(LOCA) l RCW/RSW Heat Exchangnrs in Service 2 3 3 3 SAFETY-RELATED Emergency Diesel Generator A t t RHR Heat Exchanger A t l Others (safety-related)f NON-SAFETY-RELATED l CUW Heat Exchanger t l FPC Heat Exchanger A** Inside Drywell t i Others (non-safety-related) J Some of there cooling loads are serviced by only one or two RCW divisions.These components may be reassigned to other RCW divisions if redundancy and divisional alignment of supported and supporting systems is maintained and the design basis cooling capacity of the RCW divisions is assured. t Equipment does not receive RCW in this mode.

Equipment receives RCW in this mode.

l f HECW refrigerators, room coolers (RHR. RCIC, CAMS), RHR motor bearing and seal coolers, l and CAMS cooler. l

- Includes FPC room cooler.

O rY l Reactor Building Cooling Water System 2.11.3 9 l

2SAS447 Rsv. 2 ABWR certitiedoesign Materiat O Table 2.11.3b Reactor Building Cooling Water Cooling Loads Division B Hot Standby Normal (loss of Operating AC Emergency Operating Mode / Components

Conditions Shutdown Power)

(LOCA) RCW/RSW Heat Exchangers in 2 3 3 3 Service SAFETY-RELATED Emergency Diesel Generator B t t RHR Heat Exchanger B t Others (safety-related)f NON-SAFETY-RELATED RWCU Heat Exchanger t FPC Heat Exchanger B** Inside Drywell t Others (non-safety-related) Some of these cooling loads are serviced by only one or two RCW divisions.These components may be reassigned to other RCW divisions if redundancy and divisional alignment of supported and supporting systems is maintained and the design basis cooling capacity of the RCW divisions is assured. t Equipment does not receive RCW in this mode.

Equipment receives RCW in this mode.

f HECW refrig *rators, room coolers (RHR, HPCF, SGTS, FCS, CAMS), RHR and HPCF motor bearing and s sal coolers, and CAMS cooler.

- Includes FPC room cooler.

O 2.11.3-10 Reactor Building Cooling Water System

25AS447 Rev. 2 ABWR certitiedoesion unteriai O \\ 2.11.5 HVAC Normal Cooling Water System Design Description The Heating Ventilating and Air Conditioning (HVAC) Nonnal Cooling Water (HNCW) System delivers chilled water to the Drywell Cooling System and to non-safety-related fan coil units of building HVAC systems. Figure 2.11.5 shows the basic system configuration and scope. The HNCW System is classified as non-safety-related with the exception of the primary containment isolation function. The HNCW System pumps and refrigerators are located in the Turbine Building. The primary containment penetrations and isolation valves are classified as Seismic Category I, and ASME Code Class 2. The inboard containment isolation valves is powered from Class lE Division II, and the outboard isolation valves are powered from Class 1E Division I. In the HNCW System, p independence is provided is between Class IE divisions, and also between the Class lE ( divisions and non-Class IE equipment. The main control room has control and open/close status indication for the primary containment isolation valves. The safety-related electrical equipment that provides primary containment isolation and is located in the primary containment and the Reactor Building is qualified for a harsh environment. The primary containment isolation motor-operated valves (MOVs) shown on Figure 2.11.5 have active safety-related function to close and perform this function under differential pressure, fluid flow, and temperature conditions. The check valve (CV) for containment isolation shown on Figure 2.11.5 has an active safety-related function to close under system pressure, fluid flow, and temperature conditions. Inspections, Tests, Analyses and Acceptance Criteria Table 2.11.5 provides a definition of the inspections, tests, and/or analyses, together with associated acceptance criteria, which will be undertaken for the HNCW System. V HVAC Normal Cooling Water System 2.11.5-1

25A5447 Rev. 8 ABWR certifiedcesign Material O HNCW HVAC HVAC HNCW FROM SURGE TANK NNS NNS TCW V COOLING LOADS HNCW NNS - REACTOR BUILDING HVAC SYSTEM I - CONTROL BUILDING i i NON-SAFETY RELATED EQUIPMENT AREA HVAC SYSTEM i i l i HNCW DWC DWC HNCW j NNS NNS NOTE 1 NOTE 1 NOTE 1 I 7 7 / / DM DRYWELL / y -/ COOLING W [ -l I / r, l SYSTEM i / NNSI2 I 2lNNS NNS 12 6 2 NNS g' f E i PRIMARY PRIMARY CONTAINMENT CONTAINMENT I i I i REFRIGERATOR (S) ~~ ~ ~ NNS HNCW PUMP (S) A TCW V 2 NOTES:

1. THE INBOARD ISOLATION VALVE IS POWERED FROM CLASS 1E DIVISION 11, AND THE OUTBOARD ISOLATION VALVES ARE POWERED FROM CLASS 1E DIVISION 1.

O Figure 2.11.5 HVAC Normal Cooling Water System 2.11.5-2 HVAC Normal Cooling Water System

25A5447 Rw. 8 ABWR cerusaoestenuarist p 'L 2.11.6 HVAC Emergency Cooling Water System Design Description The Heating Ventilating and Air Conditioning (HVAC) Emergency Cooling Water (HEGV) System delivers chilled water to the: (1) Control Room Habitability Area HVAC System. (2) Control Building Safety-Related Equipment Area HVAC System. j (3) Reactor Building HVAC System (safety-related electrical equipment HVAC). Figures 2.11.6a and 2.ll.6b show the basic system configuration and scope. The HECW System is classified as safety-related except for the chemical addition tank and associated piping and valves. l The HEGV System is manually initiated. Each HEGV System refrigerator unit has a capacity of not less than 2.43 GJ/h. In s Division A, the refrigerator unit on standby automatically starts if the other refrigerator b i unit is stopped. In Divisions B and C, any refrigerator unit on standby automatically starts if any of the other refrigerator units in Divisions B or C is stopped. l Safety-related portions of the HEGV System are classified as Seismic Category I. Figures l 2.ll.6a and 2.ll.6b show the ASME Code class for the HEGV System piping and components. The HECW System pumps and refrigerator units are located in the Control Building. j Each of the three HECW System divisions is powered from the respective Class lE divisions as shown on Figures 2.11.6a and 2.11.6b. In the HEGV System, independence is provided between Class IE divisions, and also between Class lE divisions and non-Class lE equipment. Except for the connections to the chemical addition tanks, each mechanical division of the HECW System (Divisions A, B, C) is physically separated from the other divisions. The HEGV System has the following main control room (MCR) displays and controls: (1) Control and status indications for the refrigerator units and pumps shown on Figure 2.11.6a and 2.ll.6b. O (2) Parameter displays for instmments shown on Figures 2.11.6a and 2.ll.6b. HVAC Emergency Cooling Water System 2.11.6 1

2SAS447 Rett 2 ABWR certifiedcesign Materiai O The check valves (CVs) shown on Figures 2.ll.6a and 2.ll.6b have active safety-related functions to open, close, or both open and close under system pressure, fluid flow, and temperature conditions. The pneumatic-opemted valves shown in Figures 2.11.6a and 2.11.6b fail as follows in the event that either electric power to the valve-actuating solenoid is lost or pneumatic pressure to the valve is lost: the differential pressure control valves fail closed, and the flow control valves to the cooling coils fail open. Inspections, Tests, Analyses and Acceptance Criteria Table 2.11.6 provides a definition of the inspections, tests, and/or analyses, together with associated acceptance criteria, which will be undertaken for the HECW System. O l I I 1 i l O' 2.11.6-2 HVAC Emergency Cooling Water System

2SA5447 Rev. 8 ABV* i certifiedoesign uaterias b i HECW HVAC HVAC HECW FROM SURGE TANK 3 3 RCW REACTOR BUILDING HVAC 3g HECW 3 SYSTEM (SAFETY-RELATED ELECTRICAL EQUIPMENT HVAC) l l CONTROL BUILDING SAFETY-RELATED EQUIPMENT l_; AREA HVAC SYSTEM O 8 3 NNS TO CHEMICAL NNS 3 y-ADDITION _g_ g TANK V N REFRIGERATOR 3 HECW l JL RCW ) Y N REFRIGERATOR 3 HECW A RCW V NOTES: 1. DIVISION A IS POWERED FROM CLASS 1E, DIVISION 1. Figure 2.11.6a HVAC Emergency Cooling Water System (HECW-A) HVAC Emergency Cooling Water System 2.11.6-3

25A5 847 Rsv. 3 ABWR certifiedoesign uateriai HECW HVAC HVAC HECW FROM SURGE TANK 3 3 RCW j y REACTOR BUILDING HVAC l HECW 3 SYSTEM (SAFETY-RELATED -l ELECTRICAL EQUIPMENT HVAC) i I I l CONTROL ROOM HABITABILITY AREA HVAC SYSTEM l I I l CONTROL BUILDING SAFETY-RELATED EQUIPMENT l_l l AREA HVAC SYSTEM e 9 NNS 3 3 NNS TO CHEMICAL l 4 E-ADDITION --W-O TANK V N REFRIGERATOR o 3 HECW A RCW V N REFRIGERATOR 3 HECW A RCW V NOTES:

1. THIS FIGURE SHOWS ONE OF TWO SIMILAR DIVISIONS.

DIVISIONS B AND C ARE POWERED FROM CLASS 1E, DIVISION 11 AND lil, RESPECTIVELY. Figure 2.11.6b HVAC Emergency Cooling Water System (HECW-B and C) 2.11.6 4 HVAC Emergency Cooling Water System

CN 3 w lE Table 2.11.6 HVAC Emergency Cooling Water System b 6 t0 Inspections, Tests, Analyses and Acceptance Criteria Design Commitment inspections, Tests, Analyses Acceptance Criteria 4 1. The basic configuration for the HECW 1. Visualinspections of the as-built system 1. The as-built configuration of the HECW { System is shown on Figures 2.11.6a snd configuration will be conducted. System is in accordance with 2.11.6b. Figures 2.11.6a and 2.11.6b. e ,y 2. The ASME Code components of the 2. A hydrostatic test will be conducted on 2. The results of the hydrostatic test of the si HECW System retain their integrity under those Code components of the HECW ASME Code components of the HECW g internal pressures that will be System required to be hydrostatically System conform with the requirements in c experienced during service. tested bythe ASME Code. the ASME Code, Section 111. 3 3. Each HEWC System refrigerator unit has a 3. Type tests will be conducted on an as-3. Each HEWC System refrigerator unit has a capacity of not less than 2.43 GJ/h. built HECW System refrigerator units at a capacity of not less than 2.43 GJ/h. test facility. 4. In Division A, the refrigerator unit on 4. Tests will be conducted on each as-built 4. In Division A, the refrigerator unit on standby automatically starts if the other HECW System refrigerator unit in standby automatically starts upon receipt E refrigerator unit is stopped. In Divisions B Divisions A, B and C, using simulated of a simulated signalindicating that the { and C, any refrigerator unit en standby signals indicating another refrigerator other refrigerator unit is stopped. In s l automatically starts if any of the other unit is stopped. Divisions B and C, the refrigerator unit on refrigerator units in Division B or C is standby automatically starts upon receipt stopped. of a simulated signalindicating that any of the other refrigerator units in Divisions B or C is stopped. 5. Each of the three HECW System divisions 5. 5. is powered from the respective Class 1E a. Tests will be performed on the HECW a. The test signal exists only in the Class d,ivisions as shown on Figures 2.11.6a and System by providing a test signal in 1E division under test in the HECW 2.11.6b. In the HECW System, only one Class 1E division at a time. System. independence is provided between Class n 1E divisions, and between Class 1E

b. Inspections of the as-built Class 1E

b. In the HECW System, physical g

divisions and non-Class 1E equipment. divisions in the HECW System will be separation or electrical isolation exists y performed. between Class 1E divisions. Physical m. separation or electrical isolation exists { between these Class 1E divisions and non-Class 1E equipment. ~ 5 k !!t

r l l 1 t Table 2.11.6 HVAC Emergency Cooling Water System (Continued) b k Inspections, Tests, Analyses and Acceptance Criteria l I Design Commitment inspections, Tests, Analyses Acceptance Criteria l l 6. Except for the connections to the 6. Inspections of the as-built HECW System 6. Each mechanical division of the HECW l chemical addition tank, each mechanical will be conducted. System is physically separated from the division of the HECW System (Divisions other mechanical divisions of the HECW A, B, C) is physically separated from the System by structural and/or fire barriers, other divisions. with the exception connections to the chemical addition tank. 7. Main control room displays and controis 7. Inspections will be performed on the main 7. Displays and controls exist or can be provided for the HECW System are as control room displays and controls for the retrieved in the main control room as defined in Section 2.11.6. HECW System. defined in Section 2.11.6. 8. CVs designated in Section 2.11.6 as 8. Tests of installed valves for opening, 8. Based on the direction of the differential having an active safety-related function closing, or both opening and closing, will pressure across the valve, each CV opens, open, close, or both open and close under be conducted under system closes, or both opens and closes, system pressure, fluid flow. and preoperational pressure, fluid flow, and depending upon the valve's safety temperature conditions. temperature conditions. functions. [ y 9. The pneumatic-operated valves shown in 9. Tests will be performed on the as-built 9. The pneumatic actuated valves listed 2 l Figures 2.11.6a and 2.11.6b fail as follows valves by initiating loss of pneumatic below fail as specified when either electric [ in the event that either electric power to pressure and power to the actuating power to the valve actuating solenoid is the valve actuating solenoid is lost or solenoids. lost or pneumatic pressure to tne valve is pneumatic pressure to the valve is lost: lost: the differential pressure control the differential pressure control valves fait valves fail closed, and the flow control I closed, and the flow control valves to the valves to the cooling coiis fail open. k cooling coils fail open. r .b a a 9 Bi R. S 5 a = to a a O O O

m 25AS447 Rsv. 8 ABWR certifiedDesign Materisi \\ 2.15.5 Heating, Ventilating and Air Conditioning Systems Design Description Control Room Habitability Area HVAC System The Control Room Habitability Area (CRHA) Heating, Ventilating and Air Conditioning (HVAC) System provides a controlled environment for personnel comfort and safety, and for the operation of equipment in the main control area envelope (MCAE). The system consists of two (redundant) divisions. Each division consists of an air conditioning unit with two supply fans, two exhaust fans, and an emergency filtration unit with two circulating fans. The emergency filtration unit will l have at least 99% removal efficiency for all forms ofiodine (elemental, organic, particulate, and hydrogen iodide) from the influent system. Toxic gas monitors may be required in the outside air intakes of the CRHA HVAC System; these sensors are not in the Certified Design. Figure 2.15.5a shows the basic configuration and scope for the CRHA HVAC System. (G The CRHA HVAC System is classified as safety-related. The CRHA HVAC System operates in the following modes: (1) Normal operating. (2) High radiation. (3) Outside smoke. (4) Smoke removal. Normal Operating Mode In the normal operating mode, one air conditioning unit, one supply fan, and one exhaust fan operate in each division. The exhaust fan automatically starts when the supply fan is started. The MCAE is maintained at a minimum pressure of 3.2 mm water gauge above the outside atmosphere. High Radiation Mode On receipt of a Process Radiation Monitoring (PRM) System signal for high radiation in the outside air intake of the operating disision, the normal outside air intake dampers close, the exhaust air dampers close, the exhaust fan stops, the minimum outside air intake dampers open, and one fan of the emergency filtration unit starts. Heating Ventilating and Air Conditioning Systems 2.15.5 1

25A5447 Rxv. 8 ABWR ceninacesign uatorial O In the high radiation mode, a positive pressure of at least 3.2 mm water gauge is maintained in the MCAE relative to the outside atmosphere. Each emergency filtration unit treats a mixture of MCAE recirculated air and outside makeup air to 8 l maintain the positive pressure with not more than 3400 m per hour (@ one atmosphere absolute pressure,0 C) of outside air. The redundant disision of the CRIIA IWAC System starts on a low flow signal from the operating emergency filtration unit. The redundant division is connected to an outside air intake, which is separated from the other intake by a minimum of 50m. Outside Smoke Mode When smoke detection sensors in the operating outside air intake detect smoke, a signal will initiate MCAE air recirculation byisolating the outside air intake, closing the exhaust damper and stopping the exhaust fan. ] i Smoke Removal Mode The smoke remoni mode is manually initiated by closing the recirculation damper and starting both exhaust fans at high speed in conjunction with a supply fan. i ) The remaining discussion in this section is not mode-specific and applies (unless stated i otherwise) to the entire CRIIA IIVAC System. MCAE temperature is maintained between 21*C and 26 C, with a relative humidity between 10% and 60%, except when in the smoke removal mode. The CRHA HVAC System is classified as Seismic Category I. Tb GRHA HVAC System is located in the Control Building. Each of the two CRHA EWAC Sptem divisions, wita the exception of the motor operated dampers,is powered from the respective Cass IE division as shown on Figure 2.15.5a. Each pair of motor operated isolation dampers in series is powered from two independent Class lE divisions (one damper is powend from Class IE division II and the other damper is from Class IE disision III). In the CRHA HVAC System, independence is provided between Class 1E divisions, and also between the Class IE divisions and non-Class IE equipment. Each mechanical division of the CRHA IIVAC System (Disisions B and C) is physically separated from the other division, except for the common ducts in the MCAE. Fire dampers with fusible links in HVAC duct work close under air flow conditions. The CRHA HVAC System has the following displays and controls in the main control room: (1) Controls and status indication for the active safety-related components shown on Figure 2.15.5a. 2.15.5 2 Heating, Ventilating and Air Conditioning Systems

25AS447 Rtv. 2 ABWR certifiedDesign unterisi O (2) Parameter displays for the instruments shown on Figure 2.15.5a, except for the smoke detectors. Interface Requirements Toxic gas monitors will be located in the outside air intakes of the CRHA HVAC System, if the site is adjacent to toxic gas sources with the potential for releases of significance to plant operating personnelin the MCAE. These monitors should have the following requirements: (1) Be located in the outside air intakes of each division of the CRHA HVAC System. (2) Be capable ofde tecting toxic gas concentrations at which person nel protective actions must be initiated. Control Building Safety Related Equipment Area HVAC Systern The Control Building Safety-Related Equipment Area (CBSREA)HVAC System provides a controlled temperature emironment for the operation of equipment in the Control Building, excluding the MCAE. The system also limits hydrogen concentration in the battery rooms. The CBSREA HVAC System consists of three independent safety-A related divisions, each sening a designated area. Each division consists of an air ~ conditioning unit with two supply fans, and two exhaust fans. The CBSREA HVAC System also ventilates rooms that contain non-safety-related equipment and provides supplemental cooling in these rooms using non-safety-related fan coil units (FCUs). The basic system configuration and scope for the CBSREA HVAC System is shown on Figures 2.15.5b,2.15.5c and 2.15.5d. The CBSREA HVAC System is classified as safety-related except for the FCUs. The CBSREA HVAC System operates in the following modes: (1) Normal operating mode, including accident conditions. (2) Smoke removal mode. Normal Operating Mode In the normal operating mode, one air conditioning unit, one supply fan, and one exhaust fan of each division operate. The exhaust fan automatically starts when the supply fan is started. In the areas served by the CBSPIA HVAC System, the temperature is maintained below 40 C. Heating, Ventilating and Air Conditioning Systems 2.15.S-3

l 25AS447 Rtv. 8 ABWR certitiedoesign Materiai l 9 l Hydrogen concentration is maintained at less than 2% by volume in the batten rooms. Smoke Hemoval Mode The smoke removal mode is manuallyinitiated by closing the recirculation damper, l l and starting both exhaust fans in conjunction with a supply fan to allow outside air l purging of the affected Control Building area. The normal operating mode is used j to remove smoke from the battery rooms. The remaining discussion in this section is not mode-specific and applies (unless stated l otherwise) to the entire CBSREA HVAC System. l The CBSREA HVAC System is classified as Seismic Category I, except for the non-safety-l related fan coil units. The CBSREA HVAC System is located in the Control Building. i Each of the three CBSREA HVAC System divisions is powered from the respective Class IE division as shown on Figures 2.15.5b,2.15.5c and 2.15.5d. In the CBSREA HVAC System, independence is provided between Class IE divisions, and also between the Class IE divisions and non-Class IE equipment. Each mechanical division of the CBSREA HVAC System (Divisions A, B and C) is physically separated from the other divisions. CBSREA HVAC System Division B duct penetrations of Division IV firewalls are provided with fire dampers. Fire dampers with fusible links in HVAC duct work close under air flow conditions. The CBSREA HVAC System has the following displays and controls in the main control j room: (1) Controls and status indication for the active safety-related components shown on Figures 2.15.5b,2.15.5c and 2.15.5d. (2) Parameter displays for the instruments shown on Figures 2.15.5b,2.15.5c and 2.15.5d. Reactor Building HVAC System The Reactor Building (R/B) HVAC System provides a controlled environment for the operation of equipment in the Reactor Building. The Reactor Building HVAC System consists of three independent safety-related divisions. Each division is composed of the following systems: (1) R/B Safety-Related Equipment HVAC System. (2) R/B Safety-Related Electrica .{uipment HVAC System. 2.15.5 4 Heating, Ventilating and Air Conditioning Systems I i

i 25AS447 Rev. 3 ABWR certiriacesionusterist O (3) R/B Safety-Related Diesel Generator HVAC System. The Reactor Building IWAC System includes the following non-safety-related systems: (1) R/B Secondary Containment HVAC System. j (2) R/B Primary Containment Supply / Exhaust System. (3) R/B Main Steam Tunnel HVAC System. (4) R/B Non-Safety-Related Equipment HVAC System. (5) R/B Reactor Internal Pump (RIP) Adjustable Speed Drive (ASD) Control Panel HVAC System R/B Safety-Related Equipment HVAC System The R/B Safety-Related Equipment HVAC System provides cooling of safety-related equipment areas, and consists ofindependent fan coil units. Figure 2.15.5e shows the basic system configuration and scope. O The R/B Safety-Related Equipment HVAC System is classified as safety-related. O The Residual Heat Removal (RHR) System, High Pressure Core Flooder (HPCF) System and Reactor Core Isolation Cooling (RCIC) System pump room FCUs are automatically initiated upon startup of their respective room process pump. The Containment Atmospheric Monitoring System (CAMS) and Standby Gas Treatment System (SGTS) room FCUs are automaticallyinitiated upon isolation of the Reactor Building Secondary Containment HVAC System.The Flammability Control System (FCS) room FCUs are also initiated upon a manual FCS start signal. The temperature in the safety-related equipment areas is maintained below 40*C, except for the RHR, HPCF, and RCIC pump rooms, which are maintained below 66 C dwing pump operation. The R/B Safety-Related Equipment HVAC System is classified as Seismic Category I. The R/B Sakty-Related Equipment HVAC System is located in the Reactor Building. Each of the three divisions of the R/B Safety-Related Equipment HVAC System is powered from the respective Class IE division as shown on Figure 2.15.5e. In the R/B Safety-Related Equipment HVAC System, independence is provided between Class IE divisions, and also between the Class IE divisions and non-Class IE equipment. Each mechanical division (Divisions A, B, C) of the R/B Safety-Related Equipment , ( HVAC System is physically separated from the other divisions. Heating. Ventilating and Air Conditioning Systems 2.15.5-5

2SA5447 Rsv. 8 ABWR certifiedoesign nesteriai O The R/B Safety-Julated Equipment HVAC System has the following displays and controls in the main control room: (1) Controls and status indication for the FCUs shown on Figure 2.15.5e. The safety-related electrical equipment shown on Figure 2.15.5e located in the Reactor Building is qualified for a harsh emironment. R/B Safety-Related Electrical Equipment HVAC System The R/B Safety-Related Electrical Equipment HVAC System prosides cooling of safety-related electrical equipment areas, and consists of three independent divisions. Each division consists of an air conditioning unit with two supply fans, and two exhaust fans. Figures 2.15.5f,2.15.5g, and 2.15.5h show the basic system configuration and scope. The R/B Safety-Related Electrical Equipment HVAC System is classified as safety-related. Normal Operating Mode In the normal operating mode, the air conditioning unit, one supply fan, and one exhaust fan of each division operate. The exhaust fan automatically starts when the supply fan is started. In the areas served by the R/B Safety-Related Electrical Equipment HVAC System temperature is maintained below 40'C, except in the diesel generator (DG) engine rooms during DG operation. Smoke Removal Mode The smoke removal mode is manuallyinitiated by closing the recirculation damper, stopping the exhaust fan, opening the exhaust fan bypass damper to allow outside air purging of the affected area, and starting the smoke removal fan in conjunction with the supply fan. The normal operating mode is used to remove smoke from the DG day tank rooms. The R/B Safety-Related Electrical Equipment HVAC System is classified as Seismic Category I. The R/B Safety-Related Electrical Equipment HVAC System is located in the Reactor Building. Each of the three divisions of the R/B Safety-Related Electrical Equipment HVAC System is powered from the respective Class lE division as shown on Figures 2.15.5f, 2.15.5g, and 2.15.5h. In the R/B Safety-Related Electrical Equipment HVAC System, independence is provided between Class lE disisions, and also between the Class IE divisions and non-Class 1E equipment. Each mechanical division of the R/B Safety-Related Electrical Equipment HVAC System (Divisions A, B, C) is physically separated from the other divisions. 2.15.S-6 Heating. Ventilating and Air Conditioning Systems

25A5447 Rsv. 7 ABWR conisedoesinn nesterini A t + O Fire dampers with fusible links in HVAC duct work close under air flow conditions. The R/B Safety-Related Electrical Equipment HVAC System has the following displays and controls in the main control rooms: (1) Controls and status indication for the active safety-related components shown on Figures 2.15.5f,2.15.5g, and 2.15.5h. (2) Parameter displays for the instruments shown on Figures 2.15.5f,2.15.5g and 2.15.5h. R/B Safety-Related Diesel Generator HVAC System The R/B Safety-Related DG IWAC System provides ventilation for the DG rooms when the DGs operate, and consists of three independent divisions. Each division consists of a filter unit and two supply fans. Figure 2.15.51 shows the basic system configuration and scope. The R/B Safety-Related DG HVAC System is classified as safety-related. On receipt of a DG start signal, both DG supply fans start. When the DG is operating, ( the R/B Safety-Related DG HVAC System and the R/B Safety-Related Electrical \\ l Equipment HVAC System maintain the temperature below 50 C. The R/B Safety-Related DG IWAC System is classified as Seismic Category I. The R/B Safety-Related DG HVAC System is located in the Reactor Building. Each of the three divisions of the R/B Safety-Related DG IWAC System is powered from the respective Class IE division as shown on Figure 2.15.5i. In the R/B Safety-Related DG HVAC System, independence is provided between Class IE divisions, and also between the Class 1E divisions and non-Class 1E equipment. Each mechanical division of the R/B Safety-Related DG HVAC System (Divisions A, B, C) is physically separated from the other divisions. The R/B Safety-Related DG HVAC System has the following displays and controls in the main control room: (1) Controls and status indication for the active safety-related components shown on Figure 2.15.5i. R/B Secondary Containment HVAC System The R/B Secondary Containment HVAC System provides heating and cooling for the p secondary containment. Figure 2.15.5j shows the basic system configuration and scope. t\\ Heating, Ventilating and Air Conditioning Systems 2.15.5-7

25A5447 Rev. 8 ABWR certifiedoesign uateriai O Except for the secondary containment isolation dampers, the R/B Secontiary Containment HVAC System is classified as non-safety-related. Normal Operating Mode In the normal operating mode, two supply fans and two exhaust fans operate. The supply fans operate only when the exhaust fans are operating. The R/B Secondary Containment HVAC System maintains a negative pressure in the secondaiy containment relative to the outside atmosphere. The R/B Secondary Containment HVAC System isolation dampers are closed upon receipt of an isolation signal from the Leak Detection System (LDS) or a signal l indicating loss of secondary containment supply and exhaust fans. Smoke Removal Mode The smoke remoni mode is manually initiated by starting the standby exhaust and supply fans, opening the exhaust filter unit bypass dampers, and partially closing exhaust dampers for divisions not affected by fire. The R/B Secondary Containment HVAC System penetrations of secondary containment and isolation dampers are classified as Seismic Category I. The R/B Secondary Containment HVAC System is located in the Reactor Building, except for some of the R/B secondary containment HVAC supply and exhaust air components which are located in the Turbine Building. Each R/B Secondary Containment HVAC System isolation damper requiring electrical power is powered from the Class IE division, as shown on Figure 2.15.5j. In the R/B Secondary Containment HVAC System, independence is provided between Class IE divisions, and also between Class IE divisions and non-Class IE equipment. Fire dampers with fusible links in HVAC duct work close under air flow conditions. The R/B Secondary Containment HVAC System has the following displays and controls in the main control room: (1) Control and status indication for the active components shown on Figui a 2.15.5j. (2) Parameter displays for the instruments shown on Figure 2.15.5j. The exhaust duct secondary containment isolation dampers are located in the secondary containment and qualified for a harsh environment. 2.15.5-8 Heating, Ventilating and Air Conditioning Systems

2SAS447 Rsv. 8 ABWR cenitiedoesign unterist V. The pneumatically-operated secondary containment isolation dampers, shown on Figure 2.15.5j, fail to the closed position in the event ofloss of pneumatic pressure or loss of electrical power to the valve actuating solenoids. R/B Primary Containment Supply / Exhaust System The R/B Primary Containment Supply / Exhaust System removes inert atmosphere and provides air for primay containment prior to personnel entry, and consists of a supply fan, a filter unit, and an exhaust fan as shown on Figure 2.15.5j. The R/B Primary Containment Supply / Exhaust System is classified as non-safety-related. The R/B Primary Containment Supply / Exhaust System is located in the secondag containment R/B Main Steam Tunnel HVAC System The R/B Main Steam Tunnel HVAC System provides cooling to the main steam tunnel and consists of two FCUs. Each FCU has two fans. The FCUs are started manually. The R/B Main Steam Tunnel HVAC System is classified as non-safety-related. The R/B Main Steam Tunnel HVAC System is located in the Reactor Building. R/B Non-Safety Related Equipment HVAC System The R/B Non-Safety-Related Equipment HVAC System provides cooling to the non-safety-related equipment rooms. There are six air handling units in the system. Each consists of a cooling coil, fan (s) and filter, as required. The R/B Non-Safety-Related Equipment HVAC System is classified as non-safety-related, and is located in the Reactor Building. Reactor internal Pump ASD HVAC System The Reactor Internal Pump ASD HVAC System provides cooling to the RIP ASD power panels. The system consists of a two recirculating air conditioning units with cooling coils and four supply fans. The RIP ASD HVAC System is classified as non-safety-related, and is located in the Reactor Building. Turbine Island HVAC System The Turbine Island HVAC System provides heating, cooling, and ventilation for the Turbine Island. The Turbine Island HVAC System consists of the following non-safety-related systems. (1) Turbine Building (T/B) HVAC System. ( (2) Electrical Building (E/B) HVAC System. Heating Ventilating and Air Conditioning Systems 2.15.S-9

2SAS447 Rev. 2 ABWR certifiedoesiga unteriai O Turbine Building (T/B) HVAC System The T/B HVAC System provides cooling and ventilation for the Turbine Building. The T/B HVAC System consists of: (1) T/B supply system with an air conditioning unit and three supply fans. (2) T/B exhaust system with three exhaust fans. (3) T/B compartment exhaust system with two exhaust fans. l (4) T/B lube oil area exhaust system with two fans. (5) T/B unit coolers and electric unit heaters. The T/B HVAC System is classified as non-safety-related. The T/B HVAC System is located in the Turbine Building. Electrical Building (E/B) HVAC System The E/B HVAC System provides cooling and ventilation for the electrical equipment rooms. The system consists of two air conditioning units, supply fans, two exhaust fans, unit coolers and electric unit heaters. The E/B HVAC System is classified as non-safety-related. The E/B HVAC System is located in the Electrical Building of the Turbine Island. Radwaste Building HVAC System The Radwaste Building HVAC System provides a controlled emironment for personnel comfort and safety for the Radwaste Building areas. The system consists of: I (1) An air conditioning unit and two supply fans for the Radwaste Building control room l (2) An air conditioning unit with, two supply fans, and three exhaust fans for the process areas of the Radwaste Building. The Radwaste Building HVAC System is classified as non-safety-related, and is located in l the Radwaste Building. l l Service Building HVAC System The Service Building (S/B) HVAC System provides controlled emironment for personnel comfort in the S/B. The S/B HVAC System consists of two non-safety-related systems: (1) Clean Area HVAC System. 2.15.S-10 Heating, Ventilating and Air Conditioning Systems

1 25A5447 Rev. 3 ABWR certifiedeasie unteriai } Table 2.15.51 provides a definidon of the inspections, tests, and/or analyses, together with associated acceptance criteria, which will be undertaken for the Radwaste Building HVAC System. Table 2.15.5m provides a definition of the inspections, tests, and/or analyses, together with associated acceptance criteria, which will be undertaken for the Senice Building l HVAC System. i l i l l l l l l l l I i l I 1 i l 1 Heating, Ventilating and Air Conditioning Systems 2.15.5-13 l

b M ) TORNADO y OUTSIDE MISSILE TORNADO BARRIER [ MISSILE l M M EMERGENCY / FILTRATION TD TD i UNIT H_ M M F /h Qy TD ^ l MCAE SUPPbY l RECIRCULATION DAMPER l ME T l l M M 'l MCAE RETUbN l M C/BlMCAE O l h MCAE EXHAUST l l ) l l = ( EXHAUST FANS l MCAE SUPPLY MCAElC/B HECW p M i E C) Jk g -HECW NOTES: AIR CONDITIONING UNIT SUPPLY FANS 4 g

1. THIS FIGURE SHOWS ONE OF TWO IDENTICAL DMSIONS. ELECTRICAL 4

o POWER LOADS FOR THE COMPONENTS OF DMSION B EXCEPT MOTOR OPERATED ISOLATION DAMPERS ARE POWERED FROM CLASS 1E DMSION il. 4 ELECTRICAL POWER LOADS FOR THE COMPONENTS OF DMSION C EXCEPT E (. MOTOR OPERATED ISOLATION DAMPERS ARE POWERED FROM CLASS 1E DMSION lit. h h

2. EACH PAIR OF MOTOR OPERATED ISOLATION DAMPERS HAS ONE DAMPER e

POWERED FROM CLASS 1E DMSION !! AND THE OTHER DAMPER FROM to CLASS 1E DMSION lif 5 Figure 2.15.5a Control Room Habitability Area HVAC System h O O O

f L> V J w i-eng P h M RECIRCULATION DAMPER E TORNADO MISSILE BARRIER i. !/I a TD [ / 9 "ec* HVAC EQUIP m to d lp DIV A RCW PUMP SUPPLY FANS ~ 1/ A u AIR CONDITIONING UNIT ELEC EQUIP ${ DIVI w HECW D CHILLER DIV A ELEC EQUIP N V FCU TD BATTERY DIV I BATTERY l r NOTES: m NON-DIV [ o O ~

1. CLASS 1E ELECTRICAL SUPPLY AND EXHAUS f FANS 3

SHOWN ARE POWERED FROM CLASS 1E DIVISION 1. EXHAUST FANS TORNADO MISSILE

2. FCU COOLING WATER SUPPLIED BY THE HNCW SYSTEM.

BARRIER T U r { Figure 2.15.5b Control Building Safety-Related Equipment Area HVAC System (Division A) (

co kX b + m E RECIRCULATION DAMPER TORNADO MISSILE BARRIER !I A TD [ HECW HVAC EQUIP p_ DIV B RCW PUMP l. SUPPLY FANS DIV B '4-HECW AIR CONDITIONING UNIT ELEC EQUIP g DIV 11 y ELEC EQUIP DIV IV { y HECW 2 CHILLER g. DIV B TD 5 BATTERY DIV 11 E \\- 5' s Q NOTES: BATTERY i r DIV IV E D

1. CLASS 1E ELECTRICAL LOADS SHOWN ARE POWERED d

FROM CLASS 1E DIVISION 11. E. g EXHAUST FANS TORNADO MISSILE S

2. DIVISION B DUCT PENETRATIONS OF DIVISION IV BARRIER 4

FIREWALLS ARE PROVIDED WITH FIRE DAMPERS. { tn d T l Figure 2.15.5c Control Building Safety-Related Equipment Area HVAC System (Division B) { O O O

a k h %2 to E RECIRCULATION h. M DAMPER e TORNADO MISSILE g a BARRIER t i/l A TD p g [ HECW4q V l E p T g, HVAC EQUIP m DIV C {;; 9CW PUMP 3 l SUPPLY FANS AND HX DIV C M-HECW AIR CONDITIONING UNIT ELEC EQUIP { DIV lit v 2 HECW R CHILLER DIV C ELEC EQUIP TD BATTERY DIV 111 O \\ NOTES:

1. CLASS 1E ELECTRICAL LOADS SHOWN ARE P

Q POWERED FROM CLASS 1E DIVISION llL 4

2. FCU COOLING WATER SUPPLIED BY THE Si HNCW SYSTEM.

EXHAUST FANS TORNADO MIS $1LE E BARRIER t::: RT Figure 2.15.5d Control Building Safety-Related Equipment Area HVAC System (Division C) E. g

D h to E DIVISION A DIVISION B DMSION C RRA AmB REC I l l = l l l = = RCCA HUB m:FC I 1 I rm I I l e = cesA caso it:sc I I I e I I I rw = soTse scTsc I m I 2 I l E = k

B s

I = l ~ x: s-9 "U** E h

1. rw c00tmWATE 6 SUPPUED WNE RCW SYSEA 5-2 NORM.VENnLATONANDSOKERBOVAL6 ROV 0EDW

'g mEROSEm&RYCONTANENNWCSYSEA h en e a aECMCALPCWERLO4DSROMDMSKN3AB ANDCARE 3. 9 F0WERED ROM QASS 1E DMSIONS t,I, AND m, RESPECmH.Y. 2 2 e i i 1 J? 4 ir i Figure 2.15.5e Reactor Building Safety-Related Equipment HVAC System ii. O O O

O (') C ) V 's-k h i. In h. DAMPER DAMPER TORNADO MISSILE l)#h J h 3g 3g ) g TD FMCRD PANEL [ 9 HECW47 RGOM A SMOKE o"- 1r l REMOVAL 2. T FAN d l ) RSS PANEL m ROOM A { ELEC EQUIP SUPPLY FANS og - HECW g AIR CONDITIONING UNIT HVAC EQUIP { ROOMS y DIV A g s DG-A MCC AREA DG-A TD ENGINE ROOM DAYTANK C \\ l { ROOM 1r NOTES: Q

1. CLASS 1E ELECTRICAL LOADS SHOWN EXHAUST FANS TORNADO MISSILE ARE POWERED BY DIVISION 1.

BARRIER E= RT t. 5 Figure 2.15.5f Reactor Building Safety-Related Electrical Equipment HVAC System (Division A) k

t h 0 to k N DAMPER DAMPER g TORNADO MISSILE BARRIER /l TD FMCRD PANEL / HECW4] ROOM B ~ REMOVAL SMOKE V I T FAN f [p) ' ELEC EQUIP i ROOM _p DIV IV RSS PANEL l SUPPLY FANS ROOMB M-HECW AIR CONDITIONING ELEC EQUIP UNIT ROOM DIV 11 y RIP ASD RM B y HVAC EQUIP = ROOMS r DIV B E 5 DG-B 9 MCC AREA 5

sE DG-B TD E

,8 ENGINE ROOM s* DAY TANK C O h ROOM h y 3 NOTES: e

1. CLASS 1E ELECTRICAL LOADS SHOWN O

A E ARE POWERED BY DIVISION ll 8 W 5-EXHAUST FANS TORNADO MISSILE 'O BARRIER g M i ,5 Figure 2.15.5g Reactor Building Safety-Related Electrical Equipment HVAC System (Division B) E. O O O

e r% "N P k h 18 E a S. DAMPER DAMPER TORNADO MISSILE b BARRIER / d JL JL [ HECW4-1 SMOKE 9 8-3r l REMOVAL 9. s e ELEC EQUIP FAN m y ROOM M DIV I!! ^ RIP ASD ^ HECW blb AIR CONDITIONING UNIT HVAC EQUIP { ROOMS y DIV C m E DG-C MCC AREA DG-C TD ENGINE ROOM DAY TANK C \\ ROOM 3r l NOTES:

1. CLASS 1E ELECTRICAL LOADS SHOWN EXHAUST FANS TORNADO MISSILE d.

ARE POWERED BY DIVISION Ill. BARRIER E ? T U, ,5 Figure 2.15.5h Reactor Building Safety-Related Electrical Equipment HVAC System (Division C)

b tn TOINADOMSSLE DAmER e >) DESEL k N ceswTm 8 u RXM k TD [ e 10 FLTER SJFTLY LNT FRS u 1 0s POTES: to 5

1. THS F1GURE SHOWSONEOFTmEE DENnCAL DMSIONS.

ELECACAL POWER LOADS FOR DMSCPE A, E AND C ARE E FO*ERED FROM OASS 1E DMSKNS L ll AT R!, RESPECTPELY. d as D k 9 E a-e 5' E K 2 4 a j Figure 2.15.5i Reactor Building Safety-Related Diesel Generator HVAC System g 9 O O ^

O O O 1 s ) m 9 .OUISIDE g R/B I S. Q O { v R/B SECONDARY CONTAINME N T T/8 5 9 HNCW NOTE 1 NOTE 1 P P HVAC ACS lA! l#l E PRIMARY ~ j CONTAINMENT DMSION I ed SUPPLY FAN AREA SUPPLY FANS PRIMARY CONTAINMENT 4 DIVISION 11 d AREA y STACK HVAC ACS g ^ DMSION til AREA l_~,- -F H H NOTE 1 NOTE 1 99""' T J R 9lN 9N a EXHAUST FANS Q" H 6-g NOTES: lk w

1. THE OUTBOARD ISOLATION DAMPER R/B SECONDARY CONTAINMENT SOLENOID VALVES ARE POWERED BY

= CLASS 1E DIVISION L THE INBOARD T/B g. ISOLATION DAMPER SOLENOID VALVES = g ARE POWERED BY CLASS 1E DIVISION ll g = Figure 2.15.5j Reactor Building Secondary Containment HVAC System f

Table 2.15.Sa Control Room Habitability Area HVAC System b in 12 h inspections, Tests. Analyses and Acceptance Criteria Design Commitment inspections, Tests, Analyses Acceptance Criteria 1. The basic configuration of the CRHA 1. Inspections of the as-built system will be 1. The as-built CRHA HVAC System HVAC System is as shown on Figure conducted. conforms with the basic configuration 2.15.5a. shown on Figure 2.15.5a. 2. The emergency filtration unit have at least 2. 2. The emergency filtration unit iodine 99% removal efficiency for all forms of a. Test will be conducted on each as-removal efficiency is at least 99%. sodine (elemental organic, particulate, and built emergency filtration unit. hydrogen,odide). i

b. Tests in a test facility will be conducted on the iodine absorber material.

3. The exhaust fan automatically starts 3. Tests will be conducted on each division 3. The exhaust fan automatically starts when the supply fan is started, of the CRHA HVAC System by starting the when the supply fan is started. u supply fan. E k 4. The MCAE is maintained at a minimum 4. Tests will be conducted on the as-built 4. The MCAE is maintained at a minimum w pressure of 3.2 mm water gauge above CRHA HVAC System in the normal mode pressure of 3.2 mm water gauge above [ the outside atmosphere. of operation. the outside atmosphere. = 5. 5. 5. x = }. a. On receipt of a PRM System signal for a. Tests will be conducted on each CRHA a. Upon receipt of a simulated initiation 9 high radiation in the outside air intake HVAC System division using a signal the following occurs: { of the operating division, the normal simulated initiation signal. (1) Normal outside air intake g outside air intake dampers close, the dampers are closed. s-exhaust air dampers close, the 2 exhaust fan stops, the minimum (2) Exhaust air dampers are closed. { outside air intake dampers open, and (3) Exhaust fan is stopped. Q v one fan of the emergency filtration a 9 unit starts. (4) Minimum outside air intake y g dampers are opened. Ae I' (5) Emergency filtration unit fan is E d started. = it I.! E a E ~ O O O

Q) J Table 2.15.5a Control Room Habitability Area HVAC System (Continued) h E (3 g inspections, Tests, Analyses and Acceptance Criteria ( Design Commitment inspections, Tests, Analyses Acceptance Criteria 33 k b. In the high radiation mode, positive

b. Tests will be conducted on each

b. The MCAE is maintained at a positive d

pressure of at least 3.2 mm water division of the as-built CRHA HVAC pressure of at least 3.2 mm water [ gauge is maintained in the MCAE System in the high radiation mode. gauge relative to the outside y, relative to the outside atmosphere. atmosphere with outside makeup air lE Each emergency filtration unit treats a of not more than 3400 m /h (@ one 3 k mixture of MCAE recirculated air and atmosphere absolute pressure, O C). outside makeup air to maintain the positive pressure with not more than 3 Q 3400 m /h (@ one atmosphere g absolute pressure, O C) of outside air. 3 c. The redundant division of the CRHA c. Tests will be conducted on each c. The redundant division of the CRHA HVAC System starts on a low flow division of the as-built CRHA HVAC HVAC System starts on a low flow signal from the operating emergency System using simulated low flow signal from the operating emergency Mf filtration unit. signals. filtration unit.

d. The redundant division of the CRHA d.

Inspections will be conducted on the

d. The CRHA HVAC System outside air s

HVAC System is connected to an CRHA HVAC System. intakes are at least 50m apart. E outside air intake which is separated from the other by a minimum of 50m. 6. When smoke detection sensors in the 6. Tests will be conducted on each CRHA 6. Upon receipt of a simulated initiation operating outside air intake detects HVAC System division using a simulated signal the following occurs: smoke, a signal will initiate MCAE air smoke signal. a. Outside air intake dampers are closed. recirculation by isolating the outside a,ir intake, closing the exhaust damper, and b. Exhaust air dampers are closed. stopping the exhaust fan. c. Exhaust fan is stopped. @a s e to 9 it G !!L in

t Table 2.15.5a Control Room Habitability Area HVAC System (Continued) b inspections Tests. Analyses and Acceptance Criteria Design Commitment inspections, Tests, Analyses Acceptance Criteria 23 7. Each of the two CRHA System divisions is 7. 7. powered from the respective Class 1E a. Tests will be performed on the CRHA a. The test signal exists only in the Class division as shown on Figure 2.15.5a. In HVAC System by providing a test 1E division under test in the CRHA the CRHA HVAC System, independence.is signal in only one Class 1E division at HVAC System. provided between Class 1E divisions, and a time. between Class 1E divisions and non-Class 1E equipment. b. Inspection of the as-built Class 1E b. In the CRHA HVAC System, physical divisions in the CRHA HVAC System separation or electricalisolation exists will be performed. between Class 1E divisions. Physical separation or electricalisolation exists between these Class 1E divisions and non-Class equipment. 8. Each mechanical division of the CRHA 8. Inspections of the as-built CRHA HVAC 8. Each mechanical division of the CRHA g HVAC System (Division B and C) is System will be performed. HVAC System is physically separated d; physically separated from the other from the other mechanical division of the k division, except for the common ducts in CRHA HVAC System by structural and/or iP the MCAE. fire barriers. [ 9. Fire dampers with fusible links in HVAC 9. Type tests of fire dampers in a test facility 9. Fire dampers close under system air flow [ duct work close under air flow conditions. will be performed for closure under conditions. s system air flow conditions. E

10. Main control room displays and controls

10. Inspections will be performed on the main 10. Displays and controls exist or can be provided for CRHA HVAC System are as control room displays and controls for the retrieved in the main control room as defined in Section 2.15.5.

CRHA HVAC System. defined in Section 2.15.5. I n E 9 ti n& =u S 1:. Y E a a 3 D E. O O O

l Table 2.15.5e Reactor Building Safety-Related Diesel Generator HVAC System 3h E-RI to inspections, Tests, Analyses and Acceptance Criteria g a Design Commitment inspections, Tests, Analyses Acceptance Criteria M g-1. The basic configuration of the R/B Safety-1. Inspections of the as-built system will be 1. The as-built R/B Safety-Related DG HVAC Related DG HVAC System is as shown on conducted. System conforms with the basic E Figure 2.15.5i. configuration shown on Figure 2.15.5i. b 2. On receipt of a DG start signal, both DG 2. Tests will be conducted on each division 2. On receipt of a DG start signal, both DG supply fans start. of the as-built R/B Safety-Related DG supply fans start. a h HVAC System using a simulated DG start 9 signal. Ep 3. Each of the three divisions of the R/B 3. 3. Safety-Related DG HVAC System is a. Tests will be performed on the R/d

a. The test signal exists only in the Class powered from the respective Class 1E Safety-related DG HVAC System by 1E division under test in the R/B division as shown on Figure 2.15.5i. In the providing a test signal in only one Safety-Related DG HVAC System.

R/B safety-related DG HVAC system, in Class 1E division at a time. y , dependence,is provided between Class 1E divisions, and between Class 1E

b. Inspection of the as-built Class 1E t;. In the R/B Safety-Related DG HVAC r

divisions and non-Class 1E equipment. divisions in the R/B Safety-Related DG System, physical separation or p HVAC System will be performed. electrical isolation exists between 5 Class 1E divisions. Physical separation or electrical isolation exists between these Class 1E divisions and non-Class 1E equipment 4. Each mechanical division of the R/B 4. Inspections of the as-built R/B Safety-4. Each mechanical division of the R/B Safety-Related DG HVAC System Related DG HVAC System will be Safety-Related DG HVAC System is (Divisions A, B and C)is physically conducted. physically separated from the other separated from the other divisions. mechanical divisions of the R/B Safety-Related DG HVAC System by structural p and/or fire barriers.

t S

5. Main control room displays and controls 5. Inspections will be performed on the main 5. Displays and controls exist or can be I.i provided for R/B Safety-Related DG HVAC control room displays and controls for the retrieved in the main control room as y System are as defined in Section 2.15.5. R/B Safety-Related DG HVAC System. defined in Section 2.15.5. j-R m Y E t: E

Table 2.15.5f Reactor Building Secondary Containment HVAC System b in 03 Inspections, Tests, Analyses and Acceptance Criteria Design Commitment inspections, Tests, Analyses Acceptance Criteria 1. The basic configuration of the R/B 1. Inspections of the as-built system will be 1. The as-built R/B Secondary Containment Secondary Containment HVAC System is conducted. HVAC System conforms with the basic as shown on Figure 2.15.5j. configuration shown on Figure 2.15.5j. 2. The R/B Secondary Containment HVAC 2. Tests will be conducted on the R/B

2. The R/B Secondary Containment HVAC System maintains a negative pressure in Secondary Containment HVAC System in System maintains a negative pressure in the secondary containment relative to the the normal mode of operation.

the secondary containment relative to the outside atmosphere. outside atmosphere. 3. The R/B Secondary Containment HVAC 3. Tests will be conducted on the R/B 3. Upon receipt of a simulated signal, System isolation dampers are closed Secondary Containment HVAC System isolation dampers are automatically upon receipt of an isolation signal from using simulated LDS isolation and loss of closed. the LDS, or signal indicating loss of secondary containment supply and secondary containment supply and exhaust fans signals. 4 exhaust fans. 4. The smoke removal mode is manually 4. Tests will be conducted in the smoke 4. On manualinitiation of smoke removal s initiated by starting the standby exhaust removal mode. mode the following occurs: y and supply fans, operating the exhaust a. The standby exhaust fan starts. filter unit bypass dampers, and partially [ closing the exhaust dampers for divisions b. The standby supply fan starts. s not affected by fire. c. The filter unit bypass damper opens. E d. The exhaust dampers of divisions not affected by fire partially close to a y predetermined position. g e. The measured air flow rate and the g pressure in the ducts are at least equal D g to the values of the as-built smoke 3 removal analysis. E l S 2 j E- \\ a = I E ii iE l O O O l

25AS447 Rsv. 2 ABWR certifiedoesion ustuist s 8s00 mm 10500 mm 1XC mm--* 1300 mm o ,.................y....q

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PS ! !j "): O 5 n a 6 ~. a C './ 10s00 mm :

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! !I n+. / ,y A s <'s i i I i b i I i i Figure 2.15.10e Reactor Building Arrangement-Elevation-5100 mm l I Reactor Building 2.15.10-7 \\ I

2SAS447 Rett. 8 ABWR certitiesoesiga uateriai O ^ @0 54000 m n 1300 mm * +-10500 mm-* 8000 mm 1300 mm

9 8500 mm 8000 mm

+

105000 mm-*

g 7..................................................................; CUW/FPC se s e a 9 l 3 CUW CUW/FPC ~~' s, 10500 mm l \\ s 57000 mm l / s, y l CUW / Y d i n \\ l i j 4 OM m g pg l l g g(A) { B 8000 mm g h l BW I e l } Ogg o J l 270* h i l 90' 8000 mm l PS( 1 PS I (8) I / (C) hs Z 10500 mm l / l N / '8 l l l CRF l 'F l n U f2 l V RIP CRO l MAINTENANCE MAINTENANCE l .s k 180* 1300 mm A O Figure 2.15.10f Reactor Building Arrangement, Floor B2F-Elevation -1700 mm 2.15.10-8 Reactor Building

- =. 25AS447 Rev. 2 ABWR certified oesign staterial \\, J l l ^h O' 54000 mm 1300 mm-* +- +10500 mm+ 8000 mm + 1300 mm + + 1300 m-e-8500 m *- 8000 mm +

10500 mm+

) ,,N ,^' ~~,__ \\ [ 9500 mm 1 lg \\ l 8' \\ l g }f,R1 x @ -- \\ l .- ~~, h) l ~, \\,I ~' \\/ l x : Mi.'i, 10500 mm I I i !i ,l'g l,l ')J I 3 57000 mm li l @' $3+ l

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1 2SAS447 Rev. 8 ABWR certitiedoesiga uateriat O\\ m 8 8. 8 8 8 0 so m.z 1300 mm -* 10500 mm 8000 mm e 1300 mm-> 9-1300 m-> 8500 mm 4-8000 mm 4-4-10500 mm-> + ll..

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< w.......... _r = u.9....... i Ud n l WP l L_J I SGTS l c-I. y [-{; OG(A) N" { t yy l wwvm rwr l 8 TUNNEL 8 u,. i "t*[R]R Q i 2: l w x d/ I CUW/FPC

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57000 mm l s x / A I.J CLASS 1E \\ h BW/ INSTRUMENT 2 0 8000 B @g. M p PS(A) ) Y vu s 90* fg 8000 mm W. k I PS / ~ PS(C) 10503 mm l_ \\ f l& 4l ,$ M,,, g~ = BW ew l l A A At DG(B) l ~ ~ . DG(C) 'L :- p FCS(B) FCS(C) 7 r ................................q.... 4..e i F J"~ w w 180* A z BW O Figure 2.15.10j Reactor Building Arrangement, Floor 1F-Elevation 12300 mm 2.15.10 12 Reactor Building

I l 25AS447 Rtv. 3 ABWR cenitied Design Material O i ^ l 0* 54000 mm 1300 mm 8000 m Mm IM m 2 = = +--- 1300 mm r ~1.......... o o ....m.. %7, n l l r l FPC FPC BW l ir DG(A) 9500 m l l MAIN STEAM l ji HVAC dFI h d. ' ~ ~ "

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FPC E 57000 mm h )/ / CLASS 1E l Efu o INSTRUMENT g DIV IV 4 \\ B 8000 m B 1 i 0 33 m y N 90* t 8000 mm j i \\ u r: o ^ e IN " DG(B) l l DG(C) PANELS i PANELS '/ a i h t + + P T l DG(B) l@p \\,* l DG(C) HVAC ll,,, y ( , ' ', y HVAC [ \\ @o t x 180* ELEVATION 19600 mm 1300 mm / ('s.- Figure 2.15.10k Reactor Building Arrangement, Floor 2F-Elevation 18100 mm Reactor Building 2.15.10-13

25A5447 Rev. 8 \\ ABWR certifiedcesign nsaterial ^ l

h 0*

8 8 8 8 8 8 54000 mm 1300 mm 8500 mm 10500 mm 8000 mm 8000 mm 10500 mm 1300 mm 1300 mm g 6- - -a,----- - -IC. g a^& OG (AM j 9500 mm mi num -y y 9 ELECTRICAL EQUIPMENT $c 4 3 4 4 SGTS 10500 mm (C) 57000 mm fE 7 T l IOUIPMENT i ORC HVAC(A)

+

+ SGTS C04TAINME 4T "M ai l IBI PU IGE SUP lLY B 8000 m m M B l + f + ^ l 1 \\ 270* l 90* 8000 mm l SLC MS8V/ ME pi l ue Ai 2 lI ETY. SA N Y-EOb M l ISI EQU ihNT T 10500 mm l HVAC(C g i A lDNTMNME i f l

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y,% l + ' ~ ~.,,, 'b + g_ y i X 'EH A ^ ^ j {r' - ' A. PQ ^ i e' DG (C) DG (B) DAY 's TANK l v-um DAY @,s gj IgTAN o y L H 180* 8 1300 mm AM O Figure 2.15.101 Reactor Building Arrangement, Floor 3F-Elevation 23500 mm 2.15.10-14 Reactor Building

U C) U m /m e st e R l 8 8 8 8 j 24000mm

- 8000mm-*e 8000mm-+-

TMSL 21600mm r t- - t TMSL 17150mm 2F i .............L-ne PROCESS / ESS TMSL 13100mm 1F e COMPUTER u I B e MAIN CONTROL { l TMSL 7900mm B1F e 2 NON-DIV u ELECTRICAL [ TMSL 3500mm B2F EQUIPMENT ] RCW-A TMSL -2150mm B3F / NOTES: p

1. A GAP BETWEEN C/B AND RB AT RCW-A THE ELEVATION OF THE TOP OF TMSL -8200mm B4F BASEMATS IS NO LESS THAN 2m.

n

2. A GAP BETWEEN C/B AND T/B AT THE ELEVATION OF THE TOP OF T/B h

BASEMAT IS NO LESS THAN 6m. ( ? E- = u N E 2 Figure 2.15.12a Control Building Arrangement, Section A-A (

I b to NL C1 C2 C4 C5 C6 C7 56000mm 8000mmde 8000mm 4-- 10300mm 9700mm 9700mm---* TMSL 21600mm SUPPLY EXHAUST HVAC I T Hv^C jR STEAM TUNNEL EXHAUST XHAUST HVAC-B HVAC-B HVAC-A -xHAU HVAC-C i TMSL 17150mm 2F CRHAC EQUIPMENT ,I i-ACCESS N NON-OtV 8 PROCESS 8 SUPPLY SUPPLY 5 TMSL 12300mm GL 1F s ELECTRICAL EQUIPMENT 8 COMPUTER 8 HVAC-A HVAC-C ] ..___.__._______________I 8_ _ _ _ _ _ _ _ _ e a I l O I I

CONTROL

{ MAIN CONTROL 8 CONTROL PANELS ROOM CONTRAL PANELS ' BUILDING y [ r,s f /._f.-___,, ^M SS ELECTRICAL ELECT NON-DIV 5 TMSL 7900mm B1F e a gia. ELECTRICAL ELECT EQUIPMENT EQUIP ELECTR! CAL EOUtPMENT EQUtPMENT EQUIP 3 h h h TMSL 3500mm B2F DIV 11 DIV IV Divi DIV tai ] I T I y

HX AREA l' ACCESS g

h ] / TMSL -2150mm B3F RCW-B RCW-A RCW-A 55 2E TMSL -8200mm B4F 5 2 -5 4 Ei E. n e 8 B o

=

b Figure 2.15.12b Control Building Arrangement, Section B-B f e O O O

i yE"a0 >tN o n t ? E==i! ( t aJ - o b_ 4 w q[ygg > l m W w l I v o _ m m _ + d 0 T+ w u 0 3 r _ 2 o m Il c 1 -o n o n n J< 00 i t 7 T 9 a v v e tl l l ,,l . l l E _ l< F n n 1 0 0 r 0 A o 8 ^ sm o @~{: T s + m,~~ + l F _A t F n n n e I oV 0 m 00 e 8 g l n _li I i;l ' ' 'l l l ,I a rr sv A ,y m g h v n C _m M 0 id 79 l i u B + + l or tn m o h y< < 1 L< C X m 1 g I 2 E' _ k v 1 l 5 1 N<s <s" 2 e r Nm s ug i @ ~@ F m

4_

B m Oc o oU a4!eo 9 Gk t

D h .m in 9 i s 56000mm ~ 10300mm 9700mm 16000mm 9700m% I l a n 7 i ,p HVAC HVAC SUPPLY SUPPLY CRHA-B 8000mm CRHA-C V ( CHILLER CHILLER (~ u U NIT B UNIT A C j STEAM TUNNEL { ~ 8000mm y 24000mm 270* L g-90' 8 K ? hg o C .V EXHAUST EXHAUST NUST HVAC-A HVAC-C HVAC CRHA-C ] SUPPLY EXHAUST EXHAUST HVAC-B HVAC-B g C CRHA-B V K K y< K K igr u i i J > HV C A \\ SUPPLY HVAC-C A-E (! E Figure 2.15.12h Control Building Arrangement, Floor 2F-Elevation 17150 mm O e

2SAS447 Rev. 3 ABWR certifiedoesiga uateriai O) \\m l l I j Mm 1Mrrm l 13COnyn % f 13J0rmi N I g \\, ............,e....,....q 'I:s=.:::---------. L a ,. 1:: -sc i em ,n om l = x x es l l a o _i, FF,,,,- P p i ' A,<. l i tem tag > i o / 1 l r, aw l Q+ l v l A s i i { s d 1 i 1 nupmenumw ) canonm f A56 B < 10 C<50 D<250 E < 1aD F 21000 i Figure 3.2d Reactor Building Radiation Zone Map for Full Power and Shutdown Operations-Elevation -5100 mm Radiation Protection 3.2-5

i l r 2SAS447 Rev. 8 ABWR certifiedoesiga Materiat O i l j i 1 @o. 54000 mr.; t300 mm+- s- + 10500 mm-* 8000 mm + 1300 mm-* 8500 mm + -e-8000 mm + e 10500 mm., g I ^ -^ ^ ^ l l CUW/FPC 1 L C/B ORB ~~~' l l l O/B F/F F/F g.: ,1......j,, .y l l l CUW CUW/FPC / i j i ,0500 _ l l F/F,.- 57000 mm l l CUW / g pjp j j o Y pfp / 033 m

, ps B 8000 _

l [ f,"CL,l l A)lL g j B A g +270* I BW 1 F/F l a 90 8000 mm 5l PS g / ps l l IO) * / (C) l l C/C l F/D * / F/D l l ORE l o . e. ,/. l = = i E ' *....., c...... ' g= i j g, g j x h c......... ! a_., D"B -j '~ RIP CRO l MAJNTENANCE MAINTENANCE l I f L................................................................;. + 1300 mm 180* FULL POWER / SHUTDOWN A OPERATION (pSv/h) A56 B < 10 C < 50 D < 250 E < 1000 F21000 0 Figure 3.2e Reactor Building Radiation Zone Map for Full Power and Shutdown Operations, Floor B2F-Elevation -1700 mm 3.2-6 Radiation Protection

2SAS447 Rev. 3 ABWR certifiedoesign uateriai i l I A% So = 1Em -> + +1m m + Mm + 1Em + + =7._ g" \\, (t.y 'x,.~~...., ~~ l m. a g: i ', x 4 gg!NE'h*..' L'S " M'k ',( g g 7. i,,l \\l' l.d. l cm y.* f A. l :!;

== sm~ , \\, i i. ~+ l ll

,,=s i

~ ., ~

\\

i e .\\ 8 mm =F B l l 270* o lM'l g R. m i.

n (s

gl::n m

a

~~ \\

aa l

vm p. /G ',\\ l e = i l __1, b..........y....#,/ y \\ ,m _ x., ,. \\ 'x.. 3,'cm ~ 's _.g.,, * ,'? ~ ~.. 4. l '~~_, l ', l\\ H l'\\, ',,/ l\\ ~, ,/~, l \\ l \\ m ,, p - '~,' l \\ a ' s, ,/ i c-p i i 180* AM FULL POWER / SHUTDOWN OPERATION (pSv/h) As6 B < 10 C < 50 D < 250 E < 1000 F 21000 O. U Figure 3.2h Reactor Building Radiation Zone Map for Full Power and Shutdown Operations-Elevation 8500 mm Radiation Protection 3.2-9

25AS447 Rsv. 8 ABWR cenisedoesignuaturas O A+ 8 8 8 8 8 8 54000 m m 1300 mm + s -e 10500 mm 8000 mm 1300 mm+ 850mm m mm 1m mm. 1300 mm-9 w]

g................3]

gs ...........g. m.i L-.,.... f I F l I g l l C/c SGTS M mm l 1 MAIN 1 m [!ig OG(A) '1 STEAM F/C 1 X Qgi Mll l F/F I TUNNEL I W A/A g 4 i c/c 4 .g. gggp ! i .r_________, ,J',$..="****= D'*d.\\ 1 l J , '4 1050u mm , CUW /* #* F/D, 57000 mm n ~

\\

033 m

CLASS 1E
\\

= 0 8000 INSTRUMENT pjp Y l B !b '

r :I k PS((

l hh

v:e t

F/D 6I l ,! ) F/DJ l 90' a i

k g ',

8000 mm / / %l PSIB) \\ s j ' PS(C)>* 8 n 10500 mm N ** ...f/ N...'2 * - --- * * ~/ l A/A l l U V ....../D.......%g'. F y1 x ( ' cm [M A/A DG(B)

w

~ ~ DG(C)

= =

mm 4 FCS(B) FCS(C) = 8" r- + w w 1300 mm 180' FULL POWER / SHUTDOWN Ap OPERATION (pSvN B < 10 C < 50 D < 250 E < 1000 F 21000 Figure 3.2i Reactor Building Radiation Zone Map for Full Power and Shutdown Operations, Floor 1F-Elevation 12300 mm 3.2 10 Radiation Protection

25AS447 Rsv. 3 ABWR certifiedoesign unteriai 4 o A 0* 6 6 6 6 6 6 S4000nm = -o IEN 8500nm 10500rrm 8000rrm 8000nm 10500nm 13)0nm G0nm li~ M u g JL JL I pg 1 W FPC M [ DGuy 9500rrm FF e MANSTEAM -*== H/AC

i===

e TlifEL 'N 'I# A u A'A 1 4 4-cc a I FC i 8 i i pg 3 , f'#~~~~ DGuy Imam 8 i I s s PAMLS e 57000m i ___ f.," s,$ <'y} ' ' "NM s e,# CLASS 1E W 7 i==fy i i l l 'Is & g,s gg o" " 7i i FF B an nm l pg,, S nFC i u, B i i k$ l Jk l lm[ s /ms o '-v i m (v) N [,' l I i 8 O m an. U i. l W. l l g NA {U l M M y 10500nm i e i g e s gg ds, P# E.S s ,el P#ES l - _ _ _ -,---d l + w, 4 + w + ~ 9 lx. l \\ DG(B) igyl s a s, i DG(C) WAC a-e e \\s i WAC

==- U s , U ^ h1____________15 e' \\

== ______________N__'____'. x a l# ELEVATION 19800nm 130C'am FULL POVER/ SHUTDOWN OPERATION (pSv/h) As6 B < 10 C < 50 D < 250 E < 1020 F 21000 O Figure 3.2j Reactor Building Radiation Zone Map for Full Power and Shutdown Operations, Floor 2F-Elevation 18100 mm Radiation Protection 3.2 11 Y

2SAS447 Rsv. 8 ABWR certifiedDesign nsateriai A% 0* t 8 8 8 8 54000 m m 1300 mm i 8500 mm 10500 mm 8000 mm 8000 mm 10500 mm 1300 mm 1300 mm g OG (A)I ~ O a ( lg l u-E"") l TANK ^ 9500 mm g lr - - - - - - - - - - - - - - l g s 79 ELECTRICAL I l lll EQUIPMENT l j e u + I SGTS l l A/A l l (C) 10500 mm A/A l l fE 57000 mm TED C/C EQUIPMENT e j l HVAC(A) o 4 o e C 1TAINM: 4T Ii-SGTS l P 3GE SUP :,Y 3fj 1:f 8 N j 8 8000 m m p 8 i FIF 1 \\ + ^ l a 131 l M NTIk$ lCE l SLC c/C l l . o/C ^"E^ N ETY. ~f + 5AF TY-RELATED l RELATED EQUIPMENT l t ISI EQUIPMENT e gHVAC(B) l HVAC(C4 10500 mm ll A/A < e i A/A lO .l S, g o l s <q y S: i n, *} e igl Xi l ( .:: -n ^ ^ ^ ^ ^ l C/C e e 's ^lA l ,s \\ DG (C) OG (8) M....<.'......*.*.=...=...*.*.*.*..**.#v,'.........f. 's OAY OAY I 8 TA ' NK sm TANK \\ 180* COgN 1300 mm G A EXHAU T FULL POWER /SHUTOOWN F/F OPERATION (pSv/h) A56 8 < 10 C < 50 0 < 250 E < 1000 F 21000 Figure 3.2k Reactor Building Radiation Zone Map for Full Power and Shutdown Operations, Floor 3F-Elevation 23500 mm 12-12 Radiation Protection

m m \\ Q/ 2 h k C1 C2 C3 C4 CS C6 C7 N g Tg 4 56000mm k 8000mmHe 8000mm 4-10300mm 9700mm 9700m m--+ S TMSL 21600mm ..____.,,____.._____.T~~~~-~~~~~~~-~~~~, m m g -m. m.. SUPPLY EXHAUST HVAC 8 {" l HVAC-8 HVAC-B E T l EAM TUNNEL e E HAUST Nv^C EX AU T I XHAU TMSL 17150mm 2F l h h h CRHA-C 8 EQUIPMENT { NON-DIV ACCESS N ELECTRICAL EQUIPMENT U ' PROCESS SUPPLY SUPPLY " " ^ ~ ^ "#~ TMSL 12300mm GL 1F A R 5 l A ~ l l I I

CONTROL MAIN CONTROL CONTROL PANELS ROOM CONTROL PANELS BUILDING j

h h hh __ f TMSL 7900mm B1F 88 e ELECTRICAL ELECT NON DIV ELECTRICAL ELECT s EQUIPMENT EQUIP ELECTRICAL EQUIPMENT e [ EQUIPMENT EOUIP A A Al 2. TMSL 3500mm 82F l DIV ll DIV 8V D'V I D8V I'l .--_._._-----,.__---..------.---..-----,.w.i8 N --,m cj y s s

HX AREA s

ACCESS TMSL -2150mm B3F l g l l RCW-B RCW-A RCW-C f l &=, C C C 4. e a TMSL -8200mm B4F 8 s a e i I 3 ___=, e 9 g a--- s----------------------------------------.-----------------e As6 pSym B < 10 pSv/h 3; C < 50 pSv/h E D < 250 pSv/h ts j( E < 1000 pSv/h F 2 1000 pSv/h 5 w { Figure 3.2p Control Building Radiation Zone Map for Full Power Operations, Section B.B f

e s to il 8 8 8 8 8 56000mrr + --- 10300mm 9700mm

: 8000mm l

8000mm : 9700mm--* 0* f A a a l A A 8000mm l m ____ i I i i l l g + + + ,0-8000mm i t t I t 24000mm 270* l h l l 0 i E RCW-B E RCW-A RCW-C B t =

l e

w 4- ! X, l + + + p l c c c .=- ) l SUMP-B SUMP-A SUMP-C l l l I I I I I l OCo 180* A As6 pSvm B < 10 pSym C < 50 pSym n D < 250 pSym E < 1000 pSvm Bi F 2 1000 kSvm E D P I E 2 = R i E Figure 3.2q Control Building Radiation Zone Map for Full Power Operation, Floor B4F-Elevation -8200 mm g s-O O O

-s b e B ce 8 8 8 8 8 i g-56000mm ~10300mm 9700mm 16000mm 9700mrn--+ 0* f A OCA I I y' _,__________________ ______________,g-' HVAC I HVAC SUPPLY 8 8 SUPPLY C""#~ 8 0 l l 9RHA C l 8000mm i v ( CHILLER I F I i Chitter i OCB } l l t UNIT B I UNIT A t STEAM TUNNEL l 80 Omm l A ( l l ( A l E 24000mm 270* i INX,i 8 90* a i l -V EXHAUST EXHAUST t HVAC t NT i HVAC-A HVAC-C = HVAC 8 CRHA-C a SUPPLY EXHAUST EXHAUST ' 8 -- i HVAC-B HVAC-B CRHA-B I I l V l l 6 u ____.1_+________ j_#____4 p__________ 180* SUPPLY SUPPLY HVAC-A HVAC-C As6 pSv/h E B < 10 pSv/h 5i C < 50 pSv/h E. D < 250 pSv/h E < 1000 pSv/h J. F 2 1000 pSv/h = 5 w Figure 3.2v Control Building Radiation Zone Map for Full Power Operation, Floor 2F-Elevation 17150 mm ( J

Table 3.2a Plant Shielding Design b 2 tR3 Inspections, Tests, Analyses and Acceptance Criteria Design Commitment inspections, Tests, Analyses Acceptance Criteria 1. The plant design shall provide radiation 1. An analysis of the expected radiation 1. Maximum expected radiation dose rates shielding for rooms, corridors and levels in each plant area will be in each plant area (deep dose equivalent operating areas commensurate with their performed to verify the adequacy of the measured at 30 cm from the source of the occupancy requirements. shielding design. This analysis shall radiation, not contact dose rates) are no consider the following: greater than the dose rates specified for a. Confirmatory calculations shall the following zones, based on the access consider significant radiation sources requirgments of that area for plant (greater than 5% contribution) for an operation and maintenance. area. Radiation source strength in plant systems and components will be Zone Dose Rate Access determined based upon an assumed (uSv/h) Requirements l source term of 3,700 MBq/s offgas A <6 Uncontrolled, g release rate (after 30 minutes decay), l a 11.1 MBq/ gram-steam N-16 source unlimited access. g term at the vessel exit nozzle, and a B <10 Controlled, s core inventory commensurate with a unlimited access. E 4005 MW, equilibrium core at 51.6 w kW/ liter. Source terms shall be C <50 Controlled, limited adjusted for radiological decay and access 20 h/ week. buildup of activated corrosion and D <250 Controlled, limited wear products. access 4 h/ week.

b. Commonly accepted shielding codes, using nuclear properties derived from E

<1000 Controlled, limited well known references (such as access 1 h/ week. Vitamin C and ANSI /ANS-6.4) shall be F 21000 Restricted, p used to model and evaluate plant radiation environments. infrequent access. g = Authorizat, ion = { (1) For non-complex geometries, required. S g. point kernel shielding codes 3 (such as QAD or GGG) shall be T used. l a e if 1 l O O O

m 1 2SAS447 Rsv. 8 ABWR certisedvess nnesteria1 e 1 I Hatch Opening i s i i i or s/ I l /N { / \\ l Removable block Secondary wall BW containment l barrier for R/B and l MCAE for C/B (Note 2), or radiation zone boundary Sliding door [- Stairway D U -+- i i r- -T-l X l l Sump pit Typical floor designation: B3F-Basement,3rd floor l l NOTES:

1. Swing of door can be either way.

2. Divisional and secondary containment barriers and MCAE are fire barriers unless specified otherwise.

3. "*" Denotes watertight door.

Control and Instrumentation Cables: Fiber-optic Metallic Fiber-optic or metallic Legend for Figures Appendix A-5 l

4 25AS447 Rev. 2 ABWR certifiedcesign Materiai 1 O' i 1 Cables not ( l connected -( j ( _ ( I I I Sensor Switch O O Appendix A 6 Legend for Figures .}}

ML20117H331

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