ML20008F865
| ML20008F865 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 04/30/1981 |
| From: | Jackie Cook CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20008F862 | List: |
| References | |
| NUDOCS 8105120213 | |
| Download: ML20008F865 (1) | |
Text
{{#Wiki_filter:_ " p/ (, CONSUMERS POWER COMPANY APPLICATION FOR REACTOR CONSTRUCTION PERMIT AND OPERATING LICENSE ( DOCKET NO 50-329 DOCKET NO 50-330 AMENDMENT NO 89 Enclosed herewith, revising and supplementing the above-entitled application, are revised pages for incorporation in the Final Safety Analysis Report. The Final Safety Analysis Report was s'abmitted with Amendment 33 to the above dockets on November 18, 1977. The enclosed material consists of the following:
- 1) Revisions to various FSAR Sections and Staff Requests for Additional Information in response to certain Open Items associated with Staff review of the Midland Plant.
- 2) Revisions to the addendum to the volumes " Responses to NRC Questions" addressing items contained in the March 30, 1979 letter from S A Varga to S H Howell titled "Open Items Associated with Staff Review of Midland Plants, Inits 1 & 2 FSAR."
- 3) Revisions to the volume entitled " Responses to Post TMI-2 Issues and Events" to reflect the applicants positions on the issues in NUREG 0737.
- 4) Additional information the FSAR stated would be submitted by amendment.
- 5) Changes in various FSAR Sections resulting from routine design develop-ments.
- 6) Changes in various FSAR Sections resulting from ongoing FSAR Review Programs.
- 7) Ccrrection of minor errors and omissions.
- 8) Changes relating to the above (Tables of Contents, Figures, Tables, etc).
These new and revised pages bear the notation " Revision 33 4/81," and are marked in the margin to indicate where changes have been made. Additional pages and figures have been added as reflected on the revised Midland Plant FSAR " List of Effective Pages." Consumers Power Company
/
Dated April 30, 1981 B er [ -
/' l' James W Cook, Vice President Swornandsubscribedtobeforemeonth) 30th day of April 1981. <' _ .- m "
Notary Public, Jackson County, Michygan My commission expires September 8, 1964 oc1080-0055c100 g10512Ok 6
I Instructicus - Rev 33 Psga Nina l VOLDfE 16 pg 9.4-1 to 6, 6a,b, 7, 8, Sa,b, pg 9.4-1 to 6, 7, 8, 8a,b, 14a,b, 14a,b, 23, 24, 26a,b, 39, 40, 23, 24,-26a,b, 39, 40, 49, 50, 48a,b, 49, 50, 51 to 52b, 53 to 51 to 60, 63 60, 63 tb1 9.4-1 sh 1 to 4 same 4 tb1 9.4-16 sh 3 same 9.4-17 sh 1 to 5 same 9.4-18 sh 1, 2 same fig 9.4-1, 2, 5, 7 same fig 9.4-14, sh 1, 2 same fig 9.4-22 sh 1 pg 9.5-5 to 8, 13, 14, 30a to d, tue ' 35, 36, 41 fig 9.5-25 sh 1, 2 same fig 9.5-30 sh 1, 2 same O pg 9A-25, 26, 36 to 39, 42, 43, 86, 87, 92, 93, 114, 115 same VOLLHE 17 pg 10-111 to vi same pg 10.1-1, 2 same pg 10.3-1, 2, 5, 6, 9, 10 same pg 10.4-5, 6, 7 to 14, 14a,b, pg 10.4-5, 6, 6a,b, 7 to 61 15 to 59 tb1 10.4-2 same tb1 10. 4-3 tb1 10.4-3 sh 1, 2 tb1 10.4-8 tb1 10.4-8 sh 1, 2 tb1 30.4-9 sh 1, 2 same tb1 10.4-10 same tb1 .4-11 sh 1, 2 tb1 10.4-11 sh 1, 2, 3 f fig 10.4-3 sh 1, 2 same
\ 10.4-4 sh 1, 2 10.4-5 sh 1, 2 10.4-6 'a 1, 2 10.4-7 sh 1, 2
Instructions - Rev 33 Pcgs Tra i m fig 10.4-8 sh 1 same 10.4-9 sh 1 10.4-10 sh 1, 2 10.4-11 sh 1 10.4-12 sh 1 10.4-13 sh 1,'2 10.4-14 sh 2 fig 10.4-15 sh 1 fig 10.4-15 sh 1, 3 fig 10.4-18 sh 2 same 10.4-19 sh 2, 3 10.4-21 sh 1, 2 10.4-22 sh 1, 2 10.4-23 10.4-24 10.4-25 sh 2 Appendix 10A(Tab) pg 10A-1 same pg 10A-5 to 8, 11 to 16 pg 10A-5 to 8, 11 to 18 tb1 10A-1 pg 11-1 to iv same i O pg 11.1-5, 6, 11, 12 sane pg 11.2-1, 2, 7 to 10 same fig 11.2-1 sh 2 same fig 11.2-3 sh 1, 2 same fig 11.2-3A sh 1, 2 pg 11.3-3 to 6, 13 to 15 same tb1 11.3-1, 2 same pg 11.4-1, 2 same fig 11.4-1 same
- 11. 4-2 sh 4 pg 11.5-3, 4, 11 to 14 same tb1 11.5-3 sh 2 same 11.5-6 sh 1, 2 tb1 11.6-2 same fig 11.6-1 sh 1 to 4 same
Instructions - Rev 33 A ss Fcurteen ('3 Instructions for Q & R Volumes 1, 2, and 3 V VOLUME 1 Q&R LOEP-1 to 35 Q&R LOEP-1 to 36 Q&R CR-13, 14, 17, 18 same Q&R pg 2-1, 11 same Q&R pg 2.3-3, 4 same Q&R pg 2.5-3, 4 13, 14 same Q&R pg 3-1 to vi Q&R pg 3-1 to vi, vic, b Q&R pg 3.5-25
- Q&R pg 3.7-17, 18
=
Q&R tb1 3.7-1 to 4, 5 sh 1,2g 6 pg 3.8-1, 2, 13 same tb1 3.8-21 to 24 same fig 3.8-2 same pg 3.9-37, 38, 51, 52 pg 3.9-37, 38, 51 to 53 tb1 3.9-2 sh 1, 2, 5, 6, 7 same pg 4-1, 11 same pg 4.3-3, 4 same pg 4.4-5, 6, 13 same tb1 4A-1, 2 same VOLUME 2 Q&R pg 5-1, 11 same pg 5.2-23, 24, 38a to d same pg 5.3-17 pg 5.3-17, 18 tb1 5.3-3 sh 1, 2, 3 same pg 5.4-11 to 16, 19 to 22 same i pg 6-1 to iv same l
Instructicus - Rav 33 Pegn Tw21va pg 15-xiii, xiv same O' pg 15.0-1 to 9 pg 15.0-1 to 10 pg 15.1-3 to 8, 8a,b, 9 to 15 pg 15.1-3 to 8, 8a,b, 9 to 14 ; tb1 15.1-16 sh 1, 2 same pg 15.2-1 to 6, 6a,b, 7,8, 8a,b, pg 15.2-1 to 18 9, 10, 10a,b, 11 to 17 tb1 15.2-2 sh 2 same tb1 15.2-3, 7 to 10 same pg 15.3-3 to 6 same pg 15.4-1 to 6, 15, 16, 23 to 26b pg 15.4-1 to 6, 6a,b, 15, 16, 23 to 26d
'b1 15.4-2a, 3, 4, 4a, 9 to 14
. same fig 15.4-9, 10, 52, 52A same pg 15.5-1, 2, 3 same pg 15.6-3, 4, 7, 8, 9, 10 same O tb1 15.6-9, 10 same U
pg 15.7-5 to 8 same ! tb1 15.7-5 sh 2, 3 same pg 15.8-1 same VOLUME 20 pg 15B.1-5, 6 same pg 15D-1, 2 same pg 15E-27, 33, 34, 35, 43, 47, 53, 61, same 62, 73, 74, 85, 86 Appendix 15F (tab) l l pg 15F-3 to 6 same pg 16-1 to xiii pg 16-1 to xix pg 16.0-1 l l pg 16.1-1 to 8 same pg 16.2-1 to 18 pg 16.2-1 to 19 l _ ,_ . _ _ _ . _ _ _ . , _ _ _ _ . . . _ _ _ _ _ _ _ _ _ .
Instructi:ns - R v 33 , Pege Fifteen pg 6.2-17, 18, 27, 28, 41, 42 same pg 6.3-13, 14, 19, 20, 29, 30, same 33, 34, 65 to 68 pg 6.4-5, 6 same pg 6.8-7, 8 same-pg 7-1, 11 same , pg 7.1-21, 22, 23 same pg 7.2-3, 4 same pg 7.3-1, 2, 9, 10 same pg 7.4-3, 4 same pg 8-1, 11 some pg 8.1-3 same fig 8.2-1 same pg 8.3-1 to 4, 9, 10, 13, 14, same 21, 22 pg 9-1, 11 same i pg 9.0-1, 2 same pg 9.2-1, 2, 5, 6, 9, 10, 13 same pg 9.3-3, 6 same pg 9.4-5, 6 same I pg 9.5-3, 4 same s VOLUME 3 pg 10-1 same pg 10.3-5, 6 same pg 10.4-5, 6, 21, 22 same pg 11-1 same pg 11.5-1, 2 same pg 13-1 same pg 13.1-3 to 6 same
Instructions - Rev 33 Pags Sixtz n Pg 13.3-1 pg 13.3-1, 2 og 13.4-1, 2 same Pg 14-1 same Pg 14.2-3 to 6, 11, 12, 15, 16, same 25, 26 pg 14A-1, 2 pg 15-1 to iv same Pg 15.0-1 to l'+,19 to 27 same J ! pg 15.1-9 to 12 same pg 15.2-1, 2, 5, 6, 17 to 22 same Pg 15.3-3 same pg 15.4-11, 12, 17, 18, 21 to 24 same pg 15.6-5 to 8 same pg 15. 7-3, 4 same Pg 15D-1, 2, 5, 6 O pg 15E-3, 4 same same ADDEND 131 A l Pg A-3, 4, 9 to 12, 17 to 22, same 25 to 30, 37 to 40, 45, 46, 55, 56, 63, 64, 67 to 70, 81, 82, 87, 88, 91, 92, 103 to 108, 121 to 124 l O
o Instructions - Rav 33 Pags Savantoca , Instructions for TMI-2 VOLUME O LO?J 1 to 4 2ame pg i to vil same I NUREG 0694 (tab) I NUREG 0737 (tab) pg I-1 to 64 pg I-1 to 65 pg 11-11 to 16 same pg III-5 to 18, 27, 28 same l pg IV-1 to 4 same l NOTE: PLEASE RETURN YOUR ACKNOWLEDGEMENT FORM TO LINDA HULTQUIST ASAP! O i l l l t t 1 O
Instructions - Rev .33 Paga Eight fig 8.3-28, 29, 29A to F, 30, 31, same 45 to 53, 55 VOLUME 15 pg 9.1-1 to 4, 5 to 8,10a,b, pg 9.1-1 to 4, 4a,b, Sto 8, 10a,b, 11 to 16, 37 to 40, 43, 44 11 to 16, 37 to 40, 43, 44 tb1 9.1-10 sh 2, 3, 4 same pg 9.2-1 to 4, 9 to 12, 17 to 30, pg 9.2-1 to 4, 9 to 12, 17 tc 30, 31, 32, 32a,b,e to h, 33 to 44, 30s,b, 31, 32, 32a,b,e to h, 33 to 44,
; 47 to 50, 57, 58, 59 44a,b, 47 to 50, 57, 58, 59 .
tb1 9.2-8 sh 1, 2 same , tb1 9.2-9 sh 1, 2 same tb1 9.2-25 sh 3, 4 same fig 9.2-3 sh 1, 2 same fig 9.2-4 sh 1 same fig 9.2-7 sh 1, 2 same fig 9.2-9 sh 1, 2 same fig 9.2-12 sh 3, 4 same fig 9.2-18 sh 1, 2 same fig 9.2-19 same fig 9.2-25 sh 1 same pg 9.3-7, 8, 25, 26, 26a,b, same 27 to 30, 37, 38, 38a,b, 39 to 42, 42a, b, 61 to 64, l 64a, b, 65 to 68
- tb1 9.3-9 tb1 9.3-9 sh 1, 2 l tb1 9.3-10 sh 1, 2, 3 same tb1 9.3-11 sh 1, 2 same fig 9.3-31 ah 1, 2 same 9.3-32 sh 1 same 9.3-33 sh 1, 2 same 9.3-34 sh 1 same 9.3-40 sh 1, 2, 3 same
- 9.3-41 sh 1, 2 same J
9.3-42 same 9.3-43 sh 1, 2 same
. _ _ _ - _ . ._- . _ _ _ . . . _ . _ _ _ . . _ _ _ - _ _ _ . _ - . . . - _ _ _ _ _ ~ . _ ._ -_
CORSum8IS Iv,) Power u,, w c . CompBRy nc, ~su,., - ~5,a e.,s., and Construction General Offices: 1945 West Parnali Road, Jackson. MI 49201 e (517) 788-G4E3 April 30, 1981 , Harold R Denton, Director Office of Nuclear Reactor Regulation Division of Licensing US Nuclear Regulatory Commission Washington, DC 20555 MIDLAND PROJECT DOCKET NO 50-329, 50-330 AMENDMENT 89 FILE 0485.11 UFI 71*01*11 SERIAL 12160 Enclosed herewith is Amendment 89 to the Company's application for construc-tion permits and operating licenses, containing three (3) signed originals and sixty (60) copies of Revision 33 to the Final Safety Analysis Report. Revisior 33 of the FSAR contains updated FSAR material a: detailed in the application page. In addition, there is enclosed revised material to the following supplemental information furnished pursuant to Regulatory Guide 1.70, Revision 2:
- 1. Supplemental Reference Drawings (Piping and Instrument Diagrams) - Five (5) copies
- 2. Supplemental Reference D awings (Electrical and Instrumentation Control Drawings) - Three (3) c<. pies
- 3. Supplemental Reference Drawings (Piping Isometrics) - Five (5) copies Proof of service upon the parties listed in the revised Service List attached to Mr J E Brunner's October 28, 1980 letter is oeing provided under separate Cover.
James W Cook (Signed) v) JWC/GEC/acr CC RJCook, Resident Inspector oc1080-0055a100 _ -~ - - . _ _
CONSUMERS POWER COMPANY APPLICATION FOR h v REACTOR CONSTRUCTION PERMIT AND OPERATING LICENSE DOCKET NO 50-329 DOCKET NO 50-330 AMENDMENT NO 89 Enclosed herewith, revising and supplementing the above-entitled application, are revised pages for incorporation in the Final Safety Analysis Report. The Final _ Safety Analysis Report was submitted with Amendment 33 to the above dockets on November 18, 1977. The enclosed material consists of the following:
- 1) Revisions to various FSAR Sections and Staff Requests for Additional Information in response to certain Open Items associated with Staff review of the Midland Plant.
- 2) Revisions to the addendum to the volumes "Responsen to NRC Questions" addressing items contained in the March 30, 1979 letter from S A Varga to S H Howell titled "Open Items Associated with Staff Review of Midland
- Plants, Units 1 & 2 FSAR."
- 3) Revisions to the volume entitled " Responses to Post TMI-2 Issues and Events" to reflect the applicants positions on the issues in NUREG-0737.
T s 4) Additional information the FSAR stated would be submitted by amendment.
- 5) Changes in various FSAR Sections resulting from routine design develop-ments.
- 6) Changes in various FSAR Sections resulting from ongoing FSAR Review Programs.
- 7) Correction of minor errors and omissions.
- 8) Changes relating to the above (Tables of Contents, Figures, Tables, etc).
These new and revised pages bear the notation " Revision 33 4/81," and are marked in the margin to indicate where changes have been made. Additional pages and figures have been added as reflected on the revised Midland Plant FSAR " List of Effec.ive Pages." Consumers Power Company Dated April 30, 1981 By /s/ James W Cook James W Cook, Vice President Sworn and subscribed to before me on this 30th day of April 1981. O (S E A L) /s/ Parbara P Townsend Notary Public, Jackson County, Michigan My connission expires September 8, 1984 oc1080-0055b100
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES ( ,) This List of Effective Pages identifies those text pages, tables, figures, and tabs that are currently effective in the FSAR. Latest Latest Latest-Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. i VOLUME 1 LOEP-13 33 LOEP-59 33 LOEP-14 33 LOEP-60 33 i 12 LOEP-15 33 LOEP-61 33 ii 12 LOEP-16 33 LOEP-62 33 iii 32 LOEP-17 33 LOEP-63 33 iv 32 LOEP-18 33 LOEP-64 33 v 21 LOEP-19 '33 LOEP-65 33 vi 21 LOEP-20 33 LOEP-66 33 vii 32 LOEP-21 33 LOEP-67 33 viii 32 LOEP-22 33 LOEP-68 33 ix 21 LOEP-23 33 LOEP-69 33 x 21 LOEP-24 33 LOEP-70 33 xi 32 LOEP-24 33 LOEP-71 33 xii 21 LOEP-25 33 LOEP-72 33 xiii 15 LOEP-26 33 LOEP-73 33 xiv 21 LOEP-27 33 LOEP-74 33 xv 21 LOEP-28 33 LOEP-75 33 xvi 12 LOEP-29 33 Chapter 1 Tab xvii 32 LOEP-30 33 1-i 33 i xviii 32 LOEP-31 33 1-ii 30 l
. b) 's /
xix xx 26 32 LOEP-32 LOEP-33 33 33 1-iii 1-iv 33 30 xxi 12 LOEP-34 33 1-v 26 xxii 26 LOEP-35 33 1-vi 26 xxiii 26 LOEP-36 33 1-vii 0 xxiv 32 LOEP-37 33 1-viii 0 xxv 26 LOEP-38 33 1-ix 25 xxvi 26 LOEP-39 33 1.1 Tab xxvii 26 LOEP-40 33 1.1-1 1 xxviii 32 LOEP-41 33 1.1-2 33 xxix 52 LOJP-42 33 1.1-3 0 i xxx 32 LOEP-43 33 1.1-4 0 xxxi 26 LOEP-44 33 1.1-5 0 xxxii 26 LOEP-45 33 1.1 Tb1 Tab LOEP Tab LOEP-46 33 Tbl 1.1-1 l LOEP-1 33 LOEP-47 33 Sheet 1 15 l LOEP-2 33 LOEP-48 33 Sheet 2 15 LOEP-3 33 LOEP-49 33 Sheet 3 25 LOEP-4 33 LOEP-50 33 Sheet 4 13 LOEP-5 33 LOEP-51 33 Sheet 5 13 LOEP-6 33 LOEP-52 33 Sheet 6 13 LOEP-7 33 LOEP-53 33 Sheet 7 13 LOEP-8 33 LOEP-54 33 Sheet 8 13 LOEP-9 33 LOEP-55 33 Sheet 9 18 LOEP-10 33 LOEP-56 33 Sheet 10 17 LOEP-11 33 LOEP-57 33 Sheet 11 17 LOEP-12 33 LOEP-58 33 Sheet 12 17
]
! ' LOEP-1 Revision 33 l , 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Sheet 12a 30 Sheet 50 20 Sheet 73 13 Sheet 12b 22 Sheet 50a 22 Sheet 74 13 Sheet 13 19 Sheet 50b 26 Sheet 75 17 Sheet 14 19 Sheet 50c 26 Sheet 76 13 Sheet 15 19 Sheet 50d 26 Sneet 77 13 Sheet 16 19 Sheet 50e 33 Sheet 78 13 Sheet 17 19 Sheet 50f 30 Sheet 79 30 Sheet 18 15 Sheet 50g 26 Sheet 80 30 Sheet 19 15 Sheet 50h 26 Sheet 81 26 Sheet 20 27 Sheet 51 32 Sheet 82 26 Sheet 21 21 Sheet 52 27 Sheet 82a 24 Sheet 22 39 Sheet 53 27 Sheet 82b 24 Sheet 23 19 Sheet 54 33 Sheet 83 24 Sheet 24 24 Sheet 54a 33 Sheet 84 21 Sheet 25 19 Sheet 54b 30 Sheet 85 21 Sheet 26 19 Sheet 55 33 Sheet 86 21 Sheet 27 19 Sheet 56 27 Sheet 86a 33 Sheet 28 21 Sheet 57 27 Sheet 86b 27 Sheet 28a 19 Sheet 58 27 Sheet 87 30 Sheet 28b 30 Sheet 59 27 Sheet 88 25 Sheet 28c 32 Sheet 60 30 Sheet 89 33 Sheet 28d 19 Sheet 60a 30 sheet 90 25 Sheet 29 1: Sheet 60b 30 Sheet 91 25 Sheet 30 13 Sheet 61 32 Sheet 92 17 Sheet 31 13 Sheet 62 27 Sheet 93 21 Sheet 32 13 Sheet 62a 33 Sheet 94 21 Sheet 33 13 Sheet 62b 27 Sheet 95 33 Sheet 34 13 Sheet 62c 32 Sheet 96 33 Sheet 35 13 Sheet 674 32 Sheet 97 27 Shaet 36 13 Sheet 62e 32 Sheet 98 27 Sheet 37 13 Sheet 62f 33 Sheet 96a 32 Sheet 38 30 Sheet 62g 33 Sheet 98b 32 Sheet 38a 24 Sheet 62h 33 Sheet 99 32 Sheet 38b 24 Sheet 63 28 Sheet 100 27 Sheet 39 18 Sheet 64 32 Sheet 101 33 Sheet 40 26 Sheet 64a 32 Sheet 102 32 Sheet 41 24 Sheet 64b 32 Sheet 102a 33 Sheet 42 18 Sheet 65 17 Sheet 102b 33 Sheet 43 18 Sheet 66 17 Sheet 102c 33 Sheet 44 27 Sheet 66a 32 Sheet 102d 27 Sheet 45 25 Sheet 66b 32 Sheet 103 33 Sheet 46 25 Sheet 67 30 Sheet 104 32 Sheet 46a 25 Sheet 68 14 Sheet 104a 32 Sheet 46b 13 Sheet 69 16 Sheet 104b 32 Sheet 47 13 Sheet 70 13 Sheet 105 15 Sheet 48 14 Sheet 71 13 Sheet 106 15 Sheet 49 33 Sheet 72 13 Sheet 107 15 LOEP- 2 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) O Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Sheet 108 15 Fig. 1.2-1 33 Tb1 1.3-2 . Sheet 109 15 Fig. 1.2-2 29 Sheet 1 32 Sheet 110 18 Fig. 1.2-3 32 . Sheet 2 32 Sheet 111 21 Fig. 1.2-4 33 Sheet 3 33 1.1 Fig. Tab Fig. 1.2-5 32 Sheet 4 32 Fig. 1.1-1 27 Fig. 1.2-6 32 Sheet 5 32-Fig. 1.1-2 29 Fig. 1.2-7 33 Sheet 6 .33 Fig. 1.1-3 27 Fig. 1.2-8 33 Sheet 6a 33-Fig. 1.1-4 0 Fig. 1.2-9 33 Sheet 6b 33 Fig. 1.1-5 0 Fig. 1.2-10 18 Sheet 7 32 Fig. 1.1-6 0 Fig. 1.2-11 18 Sheet 8 32 Fig. 1.1-7 0 Fig. 1.2-12 7 Sheet 9 32 1.2 Tab Fig. 1.2-13 21 Sheet 10 32 1.2-1 30 Fig. 1.2-14 18 Sheet 11 33 1.2-2 32 Fig. 1.2-15 21 Sheet 12 33 1.2-3 32 Fig. 1.2-16 32 Sheet 13 32 1.2-4 32 Fig. 1.2-17 32 Sheet 14 33 1.2-5 32 Fig. 1.2-18 30 Sheet 15 32 1.2-6 32 Fig. 1.2-19 28 Sheet 16 32 1.2-6a 32 Fig. 1.2-20 32 Sheet 17 32. 1.2-6b 30 Fig. 1.2-21 26 1.4 Tab 1.2-7 33 Fig. 1,2-22 22 1.4-1 26 1.2-8 33 Fig. 1.2-23 15 1.4-2 30 s 1.2-9 33 Fig. 1.2-24 28 1.4-3 30 1.2-10 33 Fig. 1.2-25 0 1.4-4 33 1.2-11 33 Fig. 1.2-26 9 1.4-5 33 1.2-12 0 Fig. 1.2-27 18 1.5 Tab 1.2-13 26 Fig. 1.2-28 33 1.5-1 26 1.2-14 30 Fig. 1.2-29 33 1.5-2 26 1.2-15 33 Fig. 1.2-30 18 1.5-3 26
- 1.2-16 33 Fig. 1.2-31 24 1.6 Tab 1.2-17 33 Fig. 1.2-32 28 1.6-1 20 1.2-18 27 Fig. 1.2-33 14 1.6 Tbl Tab 1.2-18A 25 1.3 Tab Tb1 1.6-1 1.2-18B 25 1.3-1 18 Sheet 1 28 1.2-19 30 1.3 Tb1 Tab Sheet 2 32 1.2-20 30 Tb1 1.3-1 Tb1 1.6-2 1.2-21 30 Sheet 1 32 Sheet 1 33 1.2-22 30 Sheet 2 33 Sheet 2 33 1.2-23 30 Sheet 3 15 Sheet 3 33 1.2-24 30 Sheet 4 15 Sheet 4 33 1.2 Tb1 Tab Sheet 5 15 Sheet 5 33 Tb1 1.2-1 Sheet 6 32 Sheet 6 33 Sheet 1 18 Sheet 7 32 Tb1 1.6-3 10 Sheet 2 18 Sheet 8 32 Tb1 1.6-4 33 Sheet 3 18 Sheet 9 32 1.7 Tab 1.2 Fig. Tab Sheet 10 32 1.7-1 33 LOEP 3 Revision 33 4/81 y-e. - .-, _ _ . _ . . .. _ , _ - , - , . _ _ , . . _ , , - - - , , . . _ , , , , . , - , . y ,.mw_ . , , - , , _ _ _ _ , , ..,--,r _.,__ ,,y, y-, ,,, .wr ..,m,... -r,.._m
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued)
~
Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. 1.7-2 4 Sheet 5 19 Sheet 10 18 1.7 Tb1 Tab Sheet 6 19 Tb1 1.7-15 Tb1 1.7-1 Sheet 7 19 Sheet 1 33 Sheet 1 32 Sheet 8 19 Sheet 2 32 Sheet 2 32 Tb3 1.7-8a Sheet 3 32 Sheet 3 33 Sheet 1 29 Sheet 4 33 Sheet 4 33 Sheet 2 33 Sheet 5 33 Sheet 5 32 Sheet 3 32 Sheet 6 33 Sheet 6 32 Sheet 4 32 Sheet 6a 33 Sheet 7 32 Tb1 1.7-9 Sheet 6b 33 Sheet 8 32 Sheet 1 29 Sheet 7 33 Sheet 9 32 Sheet 2 32 Sneet 8 33 Sheet 10 32 Sheet 3 33 Sheet 9 33 Sheet 11 32 Sheet 4 33 Sheet 10 32 Sheet 12 32 Tb1 1.7-10 33 Sheet 11 33 Sheet 13 32 Tb1 1.7-11 Sheet 12 33 Tb1 1.7-2 Sheet 1 33 Sheet 13 33 Sheet 1 29 Sheet 2 33 Sheet 14 33 Sheet 2 32 Sheet 3 33 Sheet 15 32 Tb1 1.7-3 Sheet 4 33 Sheet 16 32 Sheet 1 32 Sheet 5 33 Sheet 17 32 Sheet 2 33 Sheet 6 33 Sheet 18 32 Sheet 3 33 Sheet 7 33 Sheet 19 33 Tb1 1.7-4 29 Sheet 8 33 Sheet 20 32 Tb1 1.7-5 32 Sheet 8a 33 Sheet 21 32 Tb1 1.7-6 Sheet 8b 33 Sheet 22 33 Sheet 1 33 Sheet 9 33 Sheet 23 33 Sheet 2 32 Sheet 10 32 Sheet 24 32 Sheet 3 33 Tb1 1.7-12 Tb1 1.7-16 Sheet 4 32 Sheet 1 33 Sheet 1 19 Tb1 1.7-7 Sheet 2 33 Sheet 2 19 Sheet 1 20 Sheet 3 33 Sheet 3 19 Sheet 2 20 Sheet 4 33 Sheet 4 19 Sheet 3 19 Sheet 5 33 Tb1 1.7-17 2 Sheet 4 19 Tb1 1.7-13 Tbl 1.7-18 2 Sheet 5 19 Sheet 1 33 Tb1 1.7-19 Sheet 6 19 Sheet 2 33 Sheet 1 2 Sheet 7 19 Tb1 1.7-14 Sheet 2 2 Sheet 8 19 Sheet 1 20 Sheet 3 2 Sheet 9 19 Sheet 2 19 Sheet 4 2 Sheet 10 19 Sheet 3 29 Tbl 1.7-20 2 Sheet 11 19 Sheet 4 18 Tb1 1.7-21 2 Tb1 1.7-8 Sheet 5 18 Chapter 2 Tab Sheet 1 20 Sheet 6 18 2-i 29 Sheet 2 20 Sheet 7 18 2-ii 26 Sheet 3 18 Sheet 8 18 2-iii 33 Sheet 4 19 Sheet 9 18 2-iv 3 LOEP 4 Revision 33 4/81
m _ _ MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) [~'\ Latest Latest Latest-Sheet ID Rev.' Sheet ID Rev. Sheet ID RC/ . 2-v 33 Sheet 1 0 xv 21 2-vi 33' Sheet 2 0 xvi 12 2-vii 33 Sheet 3 0 xvii 12 ! 2-viii 0 Sheet 4 0 xviii 121 2-ix 0 Tb1 2.1-7 0' xix 26 2-x 0 Tbl 2.1-8 xx 26
- 2-xi 15 Sheet 1 0 xxi 12 l 2-xii 15 Sheet 2 .0 xxii 26
! 2-xiii 18 Sheet 3 0 xxiii 26 ! ' 2-xiv 18 Sheet 4 0 . xxiv 26-2-xv 14 Tb1 2.1-9 -xxv 26 2-xvi 1 Sheet 1 0 xxvi 26 2-xvii 0 Sheet 2 0 atxvii 26 l 2-xviii 0 Sheet 3 0 xxviii 26 2-xix 7 Tb1 2.1 0 xxix 26 2-xx 19 Tb1 2.1-11 0 xxx 26 2-xxa 19 2.1 Eig. Tab xxxi 26 2-xxb 19 Fig. 2.1-1 33 xxxii H26
- 2 .
- xi 15- Fig. 2.1-1A 27 2.2 Tab l 2-xxii 15 Fig. 2.1-2 18 2.2-1 3 2-xxiii 15 Fig. 2.1-3 1 2.2-2 3 l 2-xxiv 33 Fig. 2.1-4 0 2.2-2a 3 2.1 Tab Fig. 2.1-5 0 2.2-2b 3 l [\ /}
l 2.1-1 33 Fig. 2.1-6 0 2.2-3 26 26 l 2.1-2 28 Fig. 2.1-7 0 2.2-4 2.1-3 33 Fig. 2.1-8 0 2.2-5 1 2.1-4 33 Fig. 2.1-9 0 2.2-6 1 l 2.1-5 33 Fig. 2.1-10 0 2.2-7 13 2 .1. - 6 33 Fig. 2.1-11 0 2.2-8 13 2.1-6a 27 Fig. 2.1-12 0 2.2-9 3 2.1-6b 3 2.2-10 13 2.1-7 0 VOLUME 2 2.2-10a 3 2.1-8 0 2.2-10b 3 2.1-9 0 i 12 2.2-11 1 2.1-10 0 si 12 2.2-12 0 2.1 Tb1 Tab iii 21 2.2-13 1 Tbl 2.1-1 0 iv 21 2.2-14 12 Tb1 2.1-2 v 21 2.2-15 11 Sheet 1 0 vi 21 2.2-16 11 Sheet 2 0 vii 21 2.2-17 11 Sheet 3 0 viii 21 2.2-18 11-Tbl 2.1-3 ix 21 2.2-19 11 l Sheet 1 0 x 21 2.2-20 - 3 Sheet 2 0 xi 21 2.2-21 11 l ? Tb1 2.1-4 0 xii 21 2.2-22 12 Tb1 2.1-5 0 xiii 15 2.2-23 12 Tb1 2.1-6 xiv 21 2.2 Tbl Tab 3 LOEP- 5 Revision 33 j 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID _Rev. Tb1 2.2-1 2.3-17 33 Tb1 2.3-12 Sheet 1 1 2.3-18 33 Sheet 1 0 Sheet 2 0 2.3-19 7 Sheet 2 0 Tb1 2.2-2 0 2.3-20 33 Tb1 2.3-13 Tb1 2.2-3 1 2.3-21 30 Sheet 1 0 Tbl 2.2-4 33 2.3-22 7 Sheet 2 0 Tb1 2,2-5 12 2.3-23 7 Tb1 2.3-14 7 Tb1 2.2-6 1 2.3-24 30 Tb1 2.3-15 7 Tb1 2.2-7 12 2.3-25 33 Tb1 2.3-16 0 Tb1 2.2-0 3 2.3-26 30 Tb1 2.3-17 7 Tb1 2.2-9 3 2.3-27 30 Tb1 2.3-18 7 2.2 Fig. Tab 2.3-28 30 Tb1 2.3-19 7 Fig. 2 2-1 1 2.3-29 33 Tb1 2.3-20 Fig. 2.2-2 1 2.3-30 7 Sheet 1 10 Fig. 2.2-3 0 2.3-31 7 Sheet 2 10 Fig. 2.2-4 1 2.3-32 7 Sheet 3 10 Fig. 2.2-5 1 2.3-33 7 Sheet 4 10 Fig. 2.2-6 3 2.3-34 7 Sheet 5 10 Fig. 2.2-7 0 2.3-35 7 Sheet 6 15 Fig. 2.2-8 0 2.3-36 7 Sheet 7 10 Fig. 2.2-9 1 2.3-37 9 Sheet 8 10 Fig. 2.2-10 7 2.3-38 7 Tb1 2.3-21 Fig. 2.2-11 0 2.3-39 33 Sheet 1 7 Fig. 2.2-12 0 2.3-40 9 Sheet 2 7 Fig. 2.2-13 0 2.3-41 7 Sheet 3 7 Fig. 2.2-14 0 2.3-42 9 Sheet 4 7 Fig. 2.2-15 0 2.3-43 7 Sheet 5 7 Fig. 2.2-16 0 2.3-44 7 Sheet 6 7 Fig. 2.2-17 0 2.3-45 7 Sheet 7 7 Fig. 2.2-18 1 2.3 Tb1 Tab Sheet 8 7 2.3 Tab Tb1 2.3-1 0 Sheet 9 7 2.3-1 0 Tb1 2.3-2 0 Sheet 10 7 2.3-2 7 Tb1 2.3-3 0 Sheet 11 7 2.3-3 14 Tb1 2.3-4 0 Sheet 12 7 2.3-4 ? Tb1 2.3-5 0 Sheet 13 7 2.3-5 7 Tbl 2.3-6 O Sheet 14 7 2.3-6 7 Tb1 2.3-7 0 Sheet 15 7 2.3-7 21 Tb1 2.3-8 0 Sheet 16 7 2.3-8 9 Tb1 2.3-9 Sheet 17 7 2.3-9 32 Sheet 1 0 Sheet 18 7 2.3-10 32 Sheet 2 0 Sheet 19 7 2.3-11 7 Tb1 2.3-16 Sheet 20 7 2.3-12 33 Sheet 1 0 Sheet 21 7 2.3-13 9 Sheet 2 0 Sheet 22 7 2.3-14 7 Tb1 2.3-11 Sheet 23 7 2.3-15 11 Sheet 1 0 Sheet 24 7 2.3-16 11 Sheet 2 0 Sheet 25 7 LOEP 6 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Sheet 26 7 Tb1 2.3-24 0 Fig. 2.3-13 7' Sheet 27 7 .Tb1 2.3-25 0 Fig. 2.3-14 7' Sheet 28 7 Tb1 2.3-26 0 Fig.-2.3-15 7 Sheet 29 7 Tb1 2.3-27 7 -Fig. 2.3-16 7 Sheet 30 7 Tb1 2.3-28' 7 Fig. 2.3-17 7 Sheet 31 7 Tbl 2.3-29 7 Fig. 2.3-19 0 Sheet 32 7 Tb1 2.3-30 0 Fig. 2.3-19 0 Sheet 33 7 Tb1 2.3-31 Fig. 2.3-20 0 Sheet 34 7 Sheet 1 7 Fig. 2.3-21 7 Sheet 35 7 Sheet 2 7 Fig. 2.3-22 0 Tb1 2.3-22 Tb1 2.3-32 2.4 Tab Sheet 1 7 Sheet i 7 2.4-1 30 Sheet 2 7 Sheet 2 7 2.4-2 30 Sheet 3 7 Tb1 2.3-33 2.4-3 32 Sheet 4 7 Sheet 1 7 2.4-4 32 Sheet 5 7 Sheet 2 7 2.4-4a 3 Sheet 6 7 Tb1 2.3-34 33 2.4-4b 3 Sheet 7 7 Tb1 1.3-35 0 2.4-5 0 Sheet 8 7 Tb1 2.3-36 0 2.4-6 0 Sheet 9 7 Tb1 2.3-37 7 2.4-7 0 Sheet 10 7 Tb1 2.3-38 2.4-8 0 Sheet 11 7 Sheet 1 3 2.4-9 0 ' [\m/ . } Sheet 12 7 Sheet 2 3 2.4-10 30 Sheet 13 7 Sheet 3 3 2.4-11 30 Sheet 14 7 Sheet 4 3 2.4-12 30 Sheet 15 7 Sheet 5 3 2.4-13 30 Sheet i 7 Tb1 2.3-39 2.4-14 33 Sheet 17 7 Sheet 1 11 2.4-15 32 Sheet 18 7 Sheet 2 11 2.4-16 32 Sheet 19 7 Sheet 3 11 2.4-17 32 Sheet 20 7 Sheet 4 11 2.4-18 0 Sheet 21 7 Sheet 5 11 2.4-19 18 Sheet 22 7 Sheet 6 11 2.4-20 33 Sheet 23 7 Sheet 7 11 2,4-21 27 Sheet 24 7 2.3 Fig. Tab 2.4-22 27 Sheet 25 7 Fig. 2.3-1 0 2.4-23 0 Sheet 26 7 Fig. 2.3-2 0 2.4-24 0 Sheet 27 7 Fig. 2.3-3 0 2.4-25 0 Sheet 28 7 Fig. 2.3-4 0 2.4-26 0 Sheet 29 7 Fig. 2.3-5 0 2.4-27 1 Sheet 30 7 Fig. 2.3-6 .0 2.4-28 0 Sheet 31 7 Fig. 2.3-7 0 2.4-29 1 Sheet 32 7 Fig. 2.3-8 0 2.4-30 1 Sheet 33 7 Fig. 2.3-9 0 2.4-31 0 Sheet 34 7 Fig. 2.3-10 0 2.4-32 27 Sheet 35 7 Fig. 2.3-11 0 2.4 Tb1 Tab Tb1 2.3-23 0 Fi g. 2.3-12 7 Tb1 2.4-1 f ' LOEP- 7 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Sheet 1 0 Fig. 2.4-18 1 xxiv 26 Sheet 2 0 Fig. 2.4-19 1 xxv 26 Sheet 3 0 Fig. 2.4-20 1 xxvi 26 Sheet 4 0 Fig. 2.4-21 1 xxvii 26 Tb1 2.4-2 0 Fig. 2.4-22 1 xxviii 26 Tb1 2.4-3 0 Fig. 2.4-23 1 xxix 26 Tb1 2.4-4 0 Fig. 2.4-24 1 xxx 26 Tb1 2.4-5 0 Fig. 2.4-25 1 xxxi 26 Tb1 2.4-6 0 Fig. 2.4-26 1 xxxii 26 Tb1 2.4-7 0 Fig. 2.4-27 1 2.5 Tab Tbl 2.4-8 Fig. 2.4-28 1 2.5-1 0 Sheet 1 1 Fig. 2.4-29 30 2.5-2 0 Sheet 2 1 Fig. 2.4-30 1 2.5-3 0 Sheet 3 1 Fig. 2.4-31 1 2.5-4 0 Sheet 4 1 Fig. 2.4-32 1 2.5-5 14 Tb1 2.4-9 Fig. 2.4-33 21 1.5-6 33 Sheet 1 0 Fig. 2.4-34 1 2.5-6a 14 Sheet 2 0 Fig. 2.4-35 21 2.5-6b 14 Sheet 3 0 Fig. 2.4-36 21 2.5-6c 33 Tb1 2.4-10 0 Fig. 2.4-37 32 2.5-6d 33 Tbl 2.4-11 Fig. 2.4-38 8 2.5-7 5 Sheet 1 0 2.5-8 5 Sheet 2 0 VOLUME 3 2.5-9 5 Tbl 2.4-12 0 2.5-10 5 Ib1 2.4-13 0 i 12 2.5-10a 5 Tb1 2.4-14 ii 12 2.5-10b 5 Sheet 1 32 iii 21 2.5-11 0 Sheet 2 32 iv 21 2.5-12 0 Sheet 3 32 v 21 2.5-13 33 2.4 Fig. Tab vi 21 2.5-14 33 Fig. 2.4-1 21 vii 21 2.5-15 18 Fig. 2.4-2 1 viii 21 2.5-16 18 Fig. 2.4-3 30 ix 21 2.5-17 18 Fig. 2.4-4 1 x 21 2.5-18 18 Fig. 2.4-5 21 xi 21 2.5-19 18 Fig. 2.4-6 1 xii 21 2.5-20 0 Fig. 2.4-7 1 xiii 15 2.5-21 0 Fig. 2.4-8 1 xiv 21 2.5-22 0 Fig. 2.4-9 1 xv 21 2.5-23 0 Fig. 2.4-10 1 xvi 12 2.5-24 0 Fig. 2.4-11 12 xvii 12 2.5-25 33 Fig. 2.4-12 1 xviii 21 2.5-26 33 Fig. 2.4-13 1 xix 26 2.5-27 33 Fig. 2.4-14 1 xx 26 2.5-28 33 Fig. 2.4-15 1 xxi 12 2.5-28a 33 Fig. 2.4-16 1 xxii 26 2.5-28b 18 Fig. 2.4-17 1 xxiii 26 2.5-29 30 LOEP- 8 Revision 33 4/81
MIDLAND 1&2-FSAR. LIST OF EFFECTIVE PAGES (continued) U,m Latest Latest Latest Sheet ID _Rev. Sheet ID Rev. Sheet ID Rev. 2.5-30 0 2.5-70a 15 Sheet 1 0 2.5-31 14 2.5-70b 15 Sheet 2 0 2.5-32 14 2.5-71 33 Sheet 3 0 2.5-33 33 2.5-72 32 Sheet 4 0 2.5-34 14 2.5-73 1 Tb1 2.5-7 19 2.5-34a 14 2.5-74 18 Tbl 2.5-8 2.5-34b 14 2.5-75 0 Sheet 1 19 2.5-35 5 2.5-76 1 Sheet 2 32 2.5-36 5 2.5-77 18 Sheet 3 19 2.5-37 5 2.5-78 33 Shece 4 19 2.5-38 5 2.5-78a 18 Sheet 5 19 2.5-38a 33 2.5-78b 18 Tb1 2.5-9 18 2.5-38b 5 2.5-78c 18 Tb1 2.5-10 2.5-39 30 2.5-78d 18 Sheet 1 18 2.5-40 1 2.5-78e 18 Sheet 2 18 2.5-41 0 2.5 ~i8f 18 Tb1 2.5-11. 18 2.5-42 0 2.5-79 8 Tbl 2.5-12 0 2.5-43 0 2.5-80 33 Tbl 2.5-13 0 2.5-44 0 2.5-81 8 Tbl 2.5-14 2.5-45 18 2.5-82 8 Sheet 1 18 2.5-46 18 2.5-83 33 Sheet 2 26 2.5-46a 18 2.5-84 8 Tb1 2.5-14A 14 O 2.5-46b 2.5-47 2.5-48 0 17 1 2.5-85 2.5-86 2.5-87 1 0 1 Tb1 2.5-15 Tb1 2.5-16 Tb1 2.5-17 0 26 2.5-49 0 2.5-88 0 Sheet 1 18 2.5-50 1 2.5-89 0 Sheet 2 0 2.5-51 18 2.5-90 14 Tb1 2.5-18 18 2.5-52 18 2.5-91 14 Tb1 2.5 19 18 2.5-53 18 2.5 Tb1 Tab Tb1 2.5-20 8 2.5-54 18 Tb1 2.5-1 Tbl 2.5-21 18 2.5-55 33 Sheet 1 0 Tb1 2.5-22 18 2.5-56 28 Sheet 2 0 Tb1 2.5-23 18 2.5-57 33 Tb1 2.5-2 Tbl 2.5-24 0 2.5-58 1 Sheet 1 14 Tb1 2.5-25 2.5-59 1 Sheet 2 14 Sheet 1 15 2.5-60 1 Sheet 3 14 Sheet 2 15 2.5-61 32 Tb1 2.5-3 Sheet 3 15 2.5-62 18 Sheet 1 0 Sheet 4 18 2.5-63 33 Sheet 2 0 Sheet 5 18 2.5-64 0 Sheet 3 0 Sheet 6 18 2.5-65 1 Tb1 2.5-4 Sheet 7 18 2.5-66 33 Sheet 1 0 Sheet 8 18 2.5-67 0 Sheet 2 0 Sheet 9 18 2.5 68 14 Sheet 3 0 Tb1 2.5-26 18 t 2.5-69 27 Tb1 2.5-5 0 2.5 Fig. Tab 2.5-70 27 Tb1 2.5-6 Fig. 2.5-1 1 LOEP- 9 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Fig. 2.5-2 21 Fig. 2.5-46 18 Fig. 2.5-92 30 Fig, 2.5-3 21 Fig. 2.5-47 18 Fig. 2.5-93 30 Fig. 2.5-4 21 Fig. 2.5-48 18 Fig. 2.5-5 21 Fig. 2.5-48A 14 VOLUME 4 Fig. 2.5-6 5 Fig. 2.5-49 32 Fig. 2.5-7 1 Fig. 2.S-50 32 i 12 Fig. 2.5-8 1 Fig. 2.5-51 1 ii 12 Fig. 2.5-9 1 Fig. 2.5-52 1 iii 21 Fig. 2.5-10 1 Fig. 2.5-53 32 iv 21 Fiq. 2.5-11 21 Fig. 2.5-54 1 v 21 E;g. 2.5-12 21 Fig. 2.5-55 1 vi 21 Fig. 2.5-13 21 Fig. 2.5-56 1 vii 21 Fig. 2.5-14 1 Fig. 2.5-57 1 viii 21 Fig. 2.5-15 1 Fig. 2.5-58 1 ix 21 Fig. 2.5-16 21 Fig. 2.5-59 1 x 21 Fig. 2.5-17 18 Fig. 2.5-60 18 xi 21 Fig. 2.5-18 1 Fig. 2.5-61 1 xii 21 Fig. 2.5-19 1 Fig. 2.5-62 0 xiii 15 Fig. 2.5-20 18 Fig. 2.5-63 1 xiv 21 Fig. 2.5-21 18 Fig. 2.5-64 1 xv 21 Fig. 2.5-22 1 Fig. 2.5-65 1 xvi 12 Fig. 2.5-22A 18 Fig. 2.5-66 8 xvii 12 Fig. 2.5-22B 18 Fig. 2.5-67 8 xviii 21 Fig. 2.5-23 21 Fig. 2.5-68 8 xix 26 Fig. 2.5-24 21 Fig. 2.5-69 8 xx 26 Fig. 2.5-25 21 Fig. 2.5-70 8 xxi 12 Fig. 2.5-26 21 Fig. 2.5-71 8 xxii 26 Fig. 2.5-27 14 Fig. 2.5-72 8 xxiii 26 Fig. 7.5-28 1 Fig. 2.5-73 8 xxiv 26 Fig. 2.5-29 1 Fig. 2.5-74 8 xxv 26 Fig. 2.5-30 1 Fig. 2.5-75 8 xxvi 26 Fig. 2.5-31 1 Fig. 2.5-76 8 xxvii 26 Fig. 2.5-32 1 Fig. 2.5-77 8 xxviii 26 Fig. 2.5-33 1 Fig. 2.5-78 la xxix 26 Fig. 2.5-34 21 Fig. 2.5-79 8 xxx 26 Fig. 2.5-35 21 Fig. 2.5-80 8 xxxi 26 Fig. 2.5-36 21 Fig. 2.5-81 18 xxxii 26 Fig. 2.5-37 26 Fig. 2.5-82 18 App 2A Tab Fig. 2.5-38 1 Fig. 2.5-83 16 2A-i 33 Fig. 2.5-39 1 Fig. 2.5-84 9 2A-ii 0 Fig. 2.5-40 1 Fig. 2.5-85 9 2A-1 0 Fig. 2.5-40A 15 Fig. 2.5-86 14 2A-2 0 Fig. 2.5-41 1 Fig. 2.5-87 14 2A-3 0 Fig. 2.5-42 1 Fig. 2.5-68 15 2A-4 0 Fig. 2.5-43 1 Fig. 2.5-89 19 2A-5 0 Fig. 2.5-44 1 Fig. 2.5-90 18 2A-6 0 Fig. 2.5-45 1 Fig. 2.5-91 18 2A-7 0 LOEP 10 Revision 33 h 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) f% Latest Latest Latest Sheet ID Rev. Sheet ID ,Rev. Sheet ID Rev. 2A-8 0 2A-40 0 2A-87 0 2A-9 0 2A-41 0 2A-88 0 2A-10 0 2A-42 0 2A-89 0 2A-11 0 2A-43 0 2A-90 0 2A-12 0 2A-44 0 2A-91 0 2A-13 0 2A-45 0 2A-92 0 2A-14 0 2A-46 0 2A-93 0 2A-15 0 2A-47 0 2A-94 0 2A-16 0 2A-48 0 2A-95 0 2A-17 0 2A-49 0 2A-96 0 2A-18 0 2A-50 0 2A-97 0 2A-19 0 2A-51 0 2A-98 0 2A-20 0 2A-52 0 2A-99 0 2A-21 0 2A-53 0 2A-100 0 2A-22 0 2A-54 0 2A-101 0 2A-23 0 2A-55 0 2A-102 0 2A-24 0 2A-56 0 2A-103 0 2A-25 0 2A-57 0 2A-104 0 2A-26 0 2A-58 0 2A-105 0 2A-27 0 2A-59 0 2A-106 0 2A-28 0 2A-60 0 2A-107 0 2A-29 0 2A-61 0 2A-108 0
- 2A-30 0 2A-62 0 2A-109 0 s 2A-31 0 2A-63 0 2A-110 0 2A-32 0 2A-64 0 2A-111 0 2A-33 0 2A-65 0 2A-112 0 2A-34 0 2A-G6 0 2A-113 -0 2A-35 0 2A-67 0 2A-114 0 2A-36 0 2A-68 0 2A-115 0 2A-37 0 2A-69 0 2A-116 0 2A-38 18 2A-70 0 2A-117 0 2A-38-1 18 2A-71 0 2A-118 0 2A-38-2 18 2A-72 0 2A-119 0 2A-38-3 18 2A-13 0 2A-120 0 2A-38-4 18 2A-74 0 2A-121 0 2A-38-5 18 2A-75 0 2A-122 0 2A-38-6 18 2A-76 0 2A-123 0 2A-38-7 18 2A-77 0 2A-124 0 2A-38-8 18 2A-78 0 2A-125 0 2A-38-9 18 2A-79 0 2A-126 0 l 2A-38-10 18 2A-80 0 2A-127 0 2A-38-11 18 2A-81 0 2A-128 0 2A-38-12 21 2A-82 0 2A-129 0 2A-38-13 21 2A-83 0 2A-130 0 2A-38-14 21 2A-84 0 2A-131 0 2A-38-15 21 2A-85 0 2A-132 0 i 2A-39 0 2A-86 0 2A-133 0
( LOEP- 11 Revision 33 4/81 l
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O ( Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. 2A-134 0 2A-181 0 2A-210-18 18 2A-135 0 2A-182 0 2A-210-19 18 2A-136 0 2A-183 0 2A-210-20 18 2A-137 0 2A-184 0 2A-210-21 18 2A-138 0 2A-185 0 2A-210-22 18 2A-139 0 2A-186 0 2A-210-23 18 2A-140 0 2A-187 0 2A-210-24 18 2A-141 0 2A-188 0 2A-210-25 18 2A-142 0 2A-189 0 2A-210-26 18 2A-143 0 2A-190 0 2A-210-27 18 2A-144 0 2A-191 0 2A-210-28 18 2A-145 0 2A-192 0 2A-210-29 18 2 A-2 16 0 2A-193 0 2A-210-30 18 2A-147 0 2A-194 0 2A-210-31 le 2A-148 0 2A-195 0 2A-210-32 18 2A-1(? O 2A-196 0 2A-210-33 18 2A-150 0 2A-197 0 2A-210-34 13 2A-151 0 2A-198 0 2A-210-35 18 2A-152 0 2A-199 0 2A-210+36 18 2A-253 0 2A-200 0 2A-210-37 18 2A-154 0 2A-201 0 2A-210-38 18 2A-155 0 2A-202 0 2A-210-39 18 2A-156 0 2A-203 0 2A-210-40 18 2A-157 0 2A-204 0 2A-210-41 18 2A-158 0 2A-205 0 2A-210-42 18 2A-159 0 2A-206 0 2A-210-43 18 2A-160 0 2A-207 0' 2A-210-44 18 2A-161 0 2A-?O8 0 2A-210-45 18 2A-162 0 2A-209 0 2A-210-46 18 2A-163 0 2A-210 0 2A-210-47 18 2A-164 0 2A-210-1 18 2A-210-48 18 2A-165 0 2A-210-2 18 2A-210 '.9 18 2A-166 0 2A-210-3 18 2A-210-50 18 2A-167 0 2A-210-4 18 2A-210-51 18 2A-168 0 2A-210-5 18 2A-210-52 18 2A-169 0 2A-210-6 18 2A-210-53 18 2A '70 0 2A-210-7 18 2 A -210-54 18 2A-171 0 2A-210-8 18 2A-210-55 18 2A-172 0 2A-210-9 18 2A-210-56 18 2A-173 0 2A-210-10 18 2A-210-57 18 2A-174 0 2A-210-11 18 2A-210-58 18 2A-175 0 2A-210-12 18 2A-210-59 18 2A-176 0 2A-210-13 18 2A-210-60 18 2A-177 0 2A-210-14 18 2A-210-61 18 2A-178 0 2A-210-15 18 2A-210-62 18 2A-179 0 2A-210-16 18 2A-210-63 18 2A-180 0 2A-210-17 1E 2A-210-64 18 LOEP- 12 Revision 33 4/81
> MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued)
Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev.
- 2A-210-65 18 2A-210-112 18 2A-210-159 18 l 2A-210-66 18 2A-210-113 18 2A-210-160 18 2A-210-67 18 2A-210-114 18 2A-210-161 18 2A-210-68 18 2A-210-115 18 2A-210-162 18 2A-210-69 18 2A-210-116 11 8 2A-210-163 18 2A-210-70 18 2A-210-117 18 2A-210-164 18 2A-210-71 18 2A-210-118 18 2A-210-165 18
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i MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) , Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. 2B-59 0 2C-1 0 xxxii 26 2B-60 0 2C-2 0 Chapter 3 Tab i 2B-61 0 2C-3 0 3-i 26 l 2B-62 0 2C-4 0 3-ii 8 2B-63 0 2C 5 0 3-iii 29 l 2B-64 0 2C-6 0 3-iv 33 2B-65 0 22-7 0 3-v 8 , 2B-66 0 2C-8 0 3-vi 32 ' 2B-67 0 2C-9 0 3-vii 8 2B-68 0 2C-10 0 3-viii 19 2B-69 0 2C-11 0 3-ix 32 2B-70 0 2C-12 0 3-x 32 2B-71 0 2C-13 0 3-xi 33 2B-72 0 3-xii 33 2B-73 0 VOLUME 5 3-xiii 33 2B-74 0 3-xiv 26 2B-75 0 i 12 3-xiva 30 2B-76 0 ii 12 3-xivb 26 2B-77 0 ili 21 3-xv 33 2B-78 0 iv 21 3-xvi 8 2B-79 0 v 21 3-xvii 30 2B-80 0 vi 21 3-xviii 30 2B-81 0 vii 21 3-xviiia 30 2B-82 0 viii 21 3-xviiib 26 2B-83 0 ix 21 3-xviiic 27 2B-84 0 x 21 3-xviiid 26 2B-85 0 xi 21 3-xviiie 32 2B-86 0 xii 21 3-xviiif 24 2B-87 0 xiii 15 3-xix 22 2B-88 0 xiv 21 3-xx 19 2B-89 0 xv 21 3-xxa 19 2B-90 0 xvi 12 3-xxb 19 2B-91 0 xvii 12 3-xxi 16 2B-92 0 xviii 21 3-xxii 30 2B-93 0 xix 26 3-xxiii 30 2B-94 0 xx 26 3-xxiv 17 2B-95 0 xxi 12 3-xxiva 14 2B-96 0 xxii 26 3-xxivb 21 2B-97 0 xxiii 26 3-xxivc 21 2B-98 0 xxiv 26 3-xxivd 21 2B-99 0 xxv 26 3-xxv 0 2B-100 0 xxvi 26 3-xxvi 32 2B-101 0 xxvii 26 3-xxvii 32 2B-102 0 xxviii 26 3-xxviii 19 2B-103 0 xxix 26 3-xxix 24 App 2C lab xxx 26 3-xxx 19 2C-i 0 xxxi 26 3-xxxi 19 LOEP 16 Revision 33 4/81 k
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. 3-xxxii 19 3.1-44 0 Sheet 10 30 3-xxxiii 30- 3.1-45 0 Sheet 11 30 3-xxxiv 19 3.1-46 0 Sheet 12 30 3.1 Tab 3.1-47 0 Sheet 13 30 3.1-1 0 3.1-48 0 Sheet 14 30 3.1-2 26 3.1-49 0 Sheet 15 30 3.1-3 0 3.1-50 0 Sheet 16 30 3.1-4 33 3.1-51 0 Sheet 17 30 3.1-5 33 3.1-52 0 Sheet 18 30-3.1-6 27 3.1-53 0 Sheet 19 30 3.1-7 30 3.1-54 0 Sheet 20 30 3.1-8 0 3.1-55 32 Sheet 21 30 3.1-9 0 3.1-56 0 Sheet 22 30 3.1-10 0 3.1-57 0 Sheet 23 32 3.1 0 3.1-58 0 Sheet 24 30 3.1-12 33 3.1-59 0 Sheet 25 33 3.1-13 0 3.1-60 28 Sheet 26 30 3.1-14 0 3.1-61 8 Sheet 27 30 3.1-15 33 3.1-62 8 Sheet 28 30 3.1-16 0 3.1-63 8 Sheet 29 30 3.1-17 0 3.1-64 0 Sheet 30 30 s 3.1-18 0 3.1-65 0 Sheet 31 30 3.1-19 0 3.1-66 26 Sheet 32 30 3.1-20 0 3.1-67 0 Sheet 33 30 3.1-21 0 3.1-68 30 Sheet 34 30 3.1-22 0 3.1-69 0 Sheet 35 30 3.1-23 0 3.2 Tab Sheet 36 30 3.1-24 27 3.2-1 0 Sheet 37 30 3.1-25 0 3.2-2 0 Sheet 38 33 3.1-26 33 3.2-3 1 Sheet 39 33 , 3.1-27 27 3.2-4 0 Sheet 40 33 l 3.1-28 0 3.2-5 0 Sheet 41 33 l 3.1-29 13 3.2-6 0 Sheet 42 30 3.1-30 0 3.2-7 0 Sheet 43 30 l 3.1-31 33 3.2-8 33 Sheet 44 30 ( 3.1-32 27 3.2-9 13 Sheet 45 30 3.1-33 0 3.2 Tbl Tab Sheet 46 30 3.1-34 0 Tb1 3.2-1 Sheet 47 30 3.1-35 26 Sheet 1 30 sheet 48 30 3.1-36 28 Sheet 2 33 Sheet 49 33 3.1-37 0 Sheet 3 30 Tbl 3.2-2 3.1-38 0 Sheet 4 30 Sheet 1 0 3.1-39 0 sheet 5 30 Sheet 2 -0 3.1-40 0 Sheet 6 30 Tb1 3.2-3 S.1-41 0 Sheet 7 33 Sheet 1 32 3.1-42 0 Sheet 8 30 Sheet 2 32 1 3.1-43 0 Sheet 9 30 Sheet 3 32 l i ( l LOEP- 17 Revision 33
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MIDLAND 1&2-FSAR LIST'OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID _Rev. Sheet ID Rev. Shent 4 32 3.5-3 15 Tb1 3.5-7 0 Sheet 5 32 3.5-4 15 Tb1 3.5-8 Tb1 3.2-4 3.5-4a 15 Sheet 1 3 Sheet 1 32 3.5-4b 15 Sheet 2 1 Sheet 2 32 3.5-5 1 Sheet 3 1 Tb1 3.2-5 3.5-6 0 Sheet 4 1 Sheet 1 0 3.5-7 0 Tb1 3.5-9 0 Sheet 2 0 3.5-8 33 Tb1 3.5-10 28 Tbl 3.2-6 3.5-9 26 Tb1 3.5-11 15 Sheet 1 32 3.5-10 33 Tbl 3.5-12 15 Sheet 2 J2 3.5-11 0 Tb1 3.5-13 7 Sheet 3 32 3.5-12 0 Tb1 3.5-14 7 Sheet 4 32 3.5-13 0 Tb1 3.5-15 7 Sheet 5 32 3.5-14 30 Tb1 3.5-16 3.3 Tab 3.5-15 0 Sheet 1 8 3.3-1 33 3.5-16 0 Sheet 2 8 3.3-2 32 3.5-17 0 Sheet 3 8 3.3-3 33 3.5-18 0 Sheet 4 8 3.3-4 0 3.5-19 8 Sheet 5 8 3.3 Tbl. Tab 3.5-20 32 Sheet 6 8 Tb1 3.3-1 32 3.5-20a 33 Sheet 7 8 3.3 Fig. Tab 3.5-20b 8 Sheet 8 8 Fig. 3.3-1 32 3.5-21 16 Sheet 9 8 Fig. 3.3-2 32 3.5-22 7 Sheet 10 8 3.4 Tab 3.5-23 30 Tb1 3.5-17 3.4-1 3 3.5-24 30 Sheet 1 8 3.4-2 25 3.5-25 33 Sheet 2 8 3.4-3 33 3.5-26 28 Sheet 3 8 3.4-4 8 3.5-27 28 Sheet 4 8 3.4-4a 8 3.5-28 28 Sheet 5 8 3.4-4b 8 3.5-29 26 Sheet 6 8 3.4-S 0 3.5-30 7 Sheet 7 8 3.4-6 8 3.5-31 32 Sheet 8 8 3.4-7 8 3.5 Tbl Tab Sheet 9 8 3.4 Tbl Tab Tb1 3.5-1 28 Tbl 3.5-18 26 Tb1 3.4-1 0 Tb1 3.5-2 Tb1 3.5-19 Tb1 3.4-2 0 Sheet 1 28 Sheet 1 28 Tbl 3.4-3 Sheet 2 33 Sheet 2 28 Sheet 1 32 Tb1 3.5-3 Sheet 3 18 Sheet 2 8 Sheet 1 8 Sheet 4 28 Sheet 3 8 Sheet 2 1 Sheet 5 18 3.4 Fig. Tab Sheet 3 1 Sheet 6 18 Fig. 3.4-1 20 Sheet 4 1 Sheet 7 18 Fig. 3.4-2 22 Sheet 5 1 Sheet 8 18 3.5 Tab Tb1 3.5-4 18 Sheet 9 18 3.5-1 0 Tb1 3.5-5 0 Sheet 10 18 3.5-2 0 Tb1 3.5-6 0 Sheet 11 19 LOEP- 18 Revision 33 4/81
MIDLAND.1&2-FSAR LIST OF EFFECTIVE PAGES (continued)
\ Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev.
Sheet 12 19 xxiv 26 3.6-32 0 Sheet 13 19 xxv 26 3.6-33 18 Sheet 14 19 xxvi 26 3.6-34 1 Sheet 15 18 xxvii 26 3.6-35 18 Sheet 16 18 xxviii 26 3.6-36 18 TBL 3.5-20 26 xxix 26 3.6-37 14 3.5 Fig. Tab xxx 26 3.6-38 .14 Fig. 3.5-1 0 xxxi 26 3.6-38a 33 Fig. 3.5-2 26 xxxii 26 3.6-38b 9 Fig. 3.5-3 0 3.6 Tab 3.6-39 33 Fig. 3.5-4 0 3.6-1 0 3.6-40 33 F_g. 3.5-5 0 3.6-2 0 3.6-41 14 Fig. 3.5-6 15 3.6-3 32 3.6-42 33 Fig. 3.5-7 15 3.6-4 32 3.6-42a 14 Fig. 3.5-8 15 3.6-4a 14 3.6-42b 14 Fig. 3.5-9 15 3.6-4b 8 3.6-43 19 Fig. 3.5-10 26 3.6-5 0 3.6-44 19 Fig. 3.5-11 26 3.6-6 32 3.6-45 19 Fig. 3.5-12 19 3.6-7 32 3.6-46 19 Fig. 3.5-13 26 3.6-8 32 3.6-46a 19 i Fig. 3.5-14 19 3.6-Y 33 3.6-46b 19 3.6-10 33 3.6-47' 0
'N VOLUME 6 3.6-10a 33 3.6-48 27 , 3.6-10b 33 3.6-49 9
' i 12 3.6-11 33 3.6-50 33 ii 12 3.6-12 33 3.6-50a 33 iii 21 3.6-13 28 3.6-50b 19 iv 21 3.6-14 33 3.6-50c 33 v 21 3.6-14a 15 3.6-50d 19 vi 21 3.6-14b 15 3.6-51 0 vii 21 3.6-15 0 3.6-52 0 viii 21 3.6-16 33 3.6-53 0 l ix 21 3.6-17 0 3.6-54 21 l x 21 3.6-18 0 3.6-55 26 ( xi 21 3.6-19 0 3.6 21 xii 21- 3.6-20 0 3.6-57 18
. xili 15 3.6-21 0 3.6-58 18
[ xiv 21 3.6-22 33 3.6 Tb1 Tab I xv 21 3.6-23 0 Tbl 3.6-1 , xvi 12 3.6-24 33 Sheet 1 32 i xvii 12 3.6-25 33 Sheet 2 32 xviii 21 3.6-26 0 Sheet 3 32 l xix 26 3.6-27 0 Sheet 4 32 xx 26 3.6-28 0 Sheet 5 32 xxi 12 3.6-29 0 Sheet 6 32 xxii 26 3.6-30 0 Sheet 7 32 xxiii 26 3.6-31 0 Sheet 8 32 LOEP- 19 Revision 33 4/81 1
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MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID __R e v . Sheet ID Rev. Tb1 3.6-2 Sheet 4 11 Fig. 3.6-16 16 Sheet 1 32 Tb1 3.6-12 Fig. 3.6-17 16 Sheet 2 32 Sheet 1 11 Fig. 3.6-18 32 Sheet 3 32 Sheet 2 11 Fig. 3.6-19 32 Sheet 4 32 Sheet 3 11 Fig. 3.6-20 16 Sheet 5 15 Sheet 4 11 Fig. 3.6-21 16 Sheet b 15 Tbl 3.6-13 Fig. 3.6-22 16 Sheet 7 32 Sheet 1 14 Fig. 3.6-23 16 Sheet 8 32 Sheet 2 14 Fig. 3.6-24 16 Sheet 9 32 Sheet 3 11 Fig. 3.6-25 16 Sheet 10 32 Tb1 3 3-14 30 Fig. 3.6-26 16 Sheet 11 32 Tb1 3.6-15 30 Fig. 3.6-27 16 Tb1 3.6-3 Tb1 3.6-16 Fig. 3.6-28 16 Sheet 1 9 Sheet 1 17 Fig. 3.6-29 16 Sheet 2 9 Sheet 2 17 Fig. 3.6-30 16 Sheet 3 9 Sheet 3 17 Fig. 3.6-31 21 Sheet 4 9 Sheet 4 17 Fig. 3.6-32 21 Tb1 3.6-4 Tb1 3.6-17 Fig. 3.6-33 16 Sheet 1 9 Sheet 1 17 Fig. 3.6-34 30 Sheet 2 9 Sheet 2 17 Fig. 3.6-35 30 Tb1 3.6-5 Sheet 3 17 Fig. 3.6-36 30 Sheet 1 0 Sheet 4 0 Fig. 3.6-37 30 Sheet 2 9 Tb1 3.6-18 Fig. 3.6-38 30 Sheet 3 0 S'.te e t 1 0 Fig. 3.6-39 30 Tb1 3.6-6 3heet 2 0 Fig. 3.6-40 30 Sheet 1 9 Tb1 3.6-19 Fig. 3.6-41 30 Sheet 2 9 Sheet 1 0 Fig. 3.6-42 30 Sheet 3 0 Sheet 2 0 Fig. 3.6-43 30 Tbl 3.6-7 Tb1 3.6-20 0 Fig. 3.6-44 30 Sheet 1 0 Tb1 3.6-21 0 Fig. 3.6-45 30 Sheet 2 9 Tb1 3.6-22 11 Fig. 3.6-46 30 Sheet 3 9 3.6 Fig. Tab Fig. 3.6-47 30 Tb1 3.6-8 Fig. 3.6-1 9 Fig. 3.6-48 17 Sheet 1 11 Fig. 3.6-2 9 Fig. 3.6-49 17 Sheet 2 11 Fig. 3.6-3 9 Fig. 3.6-50 17 Sheet 3 lt Fig. 3.6-4 9 Fig. 3.6-51 18 Tbl 3.6-9 Fig. 3.6-5 0 Fig. 3.6-52 17 Sheet 1 11 Fig. 3.6-6 9 Fig. 3.6-53 17 Sheet 2 11 Fig. 3.6-7 9 Fig. 3.6-54 17 Sheet 3 11 Fig. 3.6-8 16 Fig. 3.6-55 17 Tb1 3.6-10 Fig. 3.6-9 16 Fig. 3.6-56 17 Sheet 1 11 Fig. 3.6-10 16 Fig. 3.6-57 17 Sheet 2 11 Fig. 3.6-11 16 Fig. 3.6-58 18 Tb1 3.6-11 Fig. 3.6-12 32 Fig. 3.6-59 17 Sheet 1 11 Fig. 3.6-13 16 Fig. 3.6-60 17 Sheet 2 11 Fig. 3.6-14 11 r'i g . 3.6-61 17 Sheet 3 11 Fig. 3.6-15 11 Fig. 3.6-62 0 LOEP- 2 0 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) O Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Fig. 3.6-63 18 Fig. 3.6-109 15 3.7-7 33 Fig. 3.6-64 18 Fig. 3.6-110 15 3.7-8 32 Fig. 3.6-65 18 Fig. 3.6-111 15 '3.7-9 19 Fig. 3.6-66 18 Fig. 3.6-112 15 3.7-10 19 Fig. 3.6-67 18 Fig. 3.6-113 18 3.7-11 19 Fig. 3.6-68 18 3.7-12 32 Fig. 3.6-69 0 VOLUME 7 3.7-13 19 Fig. 3.6-70 0 3.7-14 33 Fig. 3.6-71 21' i 12 3.7-15 32 Fig. 3.6-72 21 ii 12 3.7-16 16 Fig. 3.6-73 22 iii 21 3.7-17 15 Fig. 3.6-74 21 iv 21 3.7-18 10 Fig. 3.6-75 21 v 21 3.7 Tb1 Tab Fig. 3.6-76 22 vi 21 Tb1 3.7-1 32 Fig. 3.6-77 21 vii 21 Tb1 3.7-2 0 Fig. 3.6-78 21 viii 21 Tb1 3.7-3 0 Fig. 3.6-79 21 ix 21 3.7 Fig. Tab Fig. 3.6-80 22 x 21 Fig. 3.7-1 0 Fig. 3.6-81 21 xi 21 Fig. 3.7-2 0 Fig. 3.6-82 8 xii 21 Fig. 3.7+3 0 Fig. 3.6-83 8 xiii , 15 Fig. 3.7-4 0 Fig. 3.6+84 22 xiv 21 Fig. 3.7-5 0 (-)'
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Fig. Fig. 3.6-85 3.6-86 22 22 xv xvi 21 12 Fig. 3.7-6 Fig. 3.7-7 0 0 Fig. 3.6-87 21 xvii 12 Fig. 3.7-8 0 Fig. 3.6-88 21 xviii 21 Fig. 3.7-9 0 Fig. 3.6-89 22 xix 26 Fig. 3.7-10 0 Fig. 3.6-90 22 xx 26 Fig. 3.7-11 C Fig. 3.6-91 21 xxi 12 Fig. 3.7 0 Fig. 3.6-92 21 xxii 26 Fig. 3.7-13 0 Fig. 3.6-93 13 xxiii 26 Fig. 3.7-14 0 Fig. 3.6-94 13 xxiv 26 Fig. 3.7-15 O. Fi g . 3.6-95 8 xxy 26 Fig. 3,7-16 -0 Fig. 3.6-96 8 xxvi 26 Fig. 3.7-17 0 Fig. 3.6-97 8 xxvii 26 Fig. 3.7-18 0 Fig. 3.6-98 8 xxviii 26 Fi g. 3. 7-19 0 Fig. 3.6-99 8 xxix 26 Fig. 3.7-20 0 Fig. 3.6-100 13 xxx 26 Fig. 3.7-21 0 Fig. 3.6-101 23 xxxi 26 Fig. 3.7-22 0 Fig. 3.6-102 22 xxxii 26 Fig. 3.7-23 0 Fig. 3.6-103 21 3.7 Tab Fig. 3.7-24 0 Fig. 3.6-103A 21 3.7-1 33 Fig. 3.7-25 0 Fig. 3.6-104 15 3.7-2 33 Fig. 3.7-26 0 Fig. 3.6-105 15 3.7-3 33 Fig. 3.7-27 19 Fig. 3.6-106 15 3.7-4 32 Fig. 3.7-28 19 Fig. 3.6-107 1E 3.7-5 33 Fig. 3.7-29 19 Fig. 3.6-108 15 3.7-6 33 Fig. 3.7-30 19
) LOEP- 21 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Fig. 3.7-31 19 3.8-8a 33 3.8-48 0 Fig. 3.7-32 19 3.8-8b 8 3.8-49 30 Fig. 3.7-33 0 3.8-9 0 3.8-50 33 Fig. 3.7-34 0 3.8-10 33 3.8-50a 30 Fig. 3.7-35 0 3.8-11 32 3.8-50b 30 Fig. 3.7-36 0 3.8-12 0 3.8-50c 33 Fig. 3.7-37 0 3.8-12a 32 3.8-50d 17 Fig. 3.7-38 0 3.8-12b 32 3.8-51 14 Fig. 3.7-39 0 3.8-13 0 3.8-52 17 Fig. 3.7-40 0 3.8-14 0 3.8-52a 8 Fig. 3.7-41 0 3.8-15 0 3.8-52b 8 Fig. 3.7-42 0 3.8-16 0 3.8-53 14 Fig. 3.7-43 0 3.8-17 0 3.8-54 17 Fig. 3.7-44 0 3.8-18 0 3.8-55 1 Fig. 3.7-45 0 3.8-19 18 3.8-56 15 Fig. 3.7-46 0 3.8-20 0 3.8-57 0 Fig. 3.7-47 0 3.8-21 28 3.8-58 0 Fig. 3.7-48 19 3.8-22 33 3.8-59 18 Fi g . 3.7-49 19 3.8-23 32 3.8-60 18 Fig. 3.7-50 19 3.8-24 32 3.8-61 14 Fig. 3.7-51 19 3.8-25 32 3.8-67 14 Fig. 3.7-52 19 3.8-26 29 3.8-63 26 Fig. 3.7-53 19 3.8-26a 29 3.8-64 32 Fig. 3.7-54 0 3.8-26b 13 3.8-65 32 Fig. 3.7-55 0 3.8-27 18 3.8-66 33 Fig. 3.7-56 0 3.8-28 33 3.8-66a 26 Fig. 3.7-57 0 3.8-29 0 3.8-66b 26 Fig. 3.7-58 0 3.8-30 28 3.8-67 33 Fig. 3.7-59 0 3.8-31 0 3.8-68 33 Fig. 3.7-60 0 3.8-32 14 3.8-69 14 Fig. 3.7-61 0 3.8-33 23 3.8~70 14 Fig. 3.7-62 0 3.8-34 32 3.8-70a 19 Fig. 3.7-63 0 3.8-35 14 3.8-70b 19 Fig. 3.7-64 15 3.8-36 30 3.8-70c 19 Fig. 3.7-65 15 3.8-36a 14 3.8-70d 33 Fig. 3.7-66 15 3.8-36b 14 3.8-71 8 Fig. 3.7-67 15 3.8-37 0 3.8-72 0 Fig. 3.7-68 24 3.8-38 33 3.8-73 0 3.8 Tab 3.8-39 33 3.8-74 1 3.8-1 0 3.8-40 33 3.8-75 0 ! 3.8-2 8 3.8-41 33 3.8-76 33 l 3.8-3 1 3.8-42 30 3.8-77 0 3.8-4 0 3.8-43 30 3.8-78 15 3.8-5 0 3.8-44 30 3.8 Tb1 Tab 3.8-6 0 3.8-45 30 Tb1 3.8-1 0 3.3-7 33 3.8-46 30 Tb1 3.8-2 0 3.8-8 33 3.8-47 0 Tb1 3.8-3 0 LOEP- 22 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Tb1 3.8-4 0 Tb1 3.8-27 Fig. 3.8-25 12 Tb1 3.8-5 0 Sheet 1 8 Fig. 3.8-26 12 Tb1 3.8-6 0 Sheet 2 8 Fig. 3.8-27 0 Tb1 3.8-7 0 Sheet 3 8 Fig. 3.8-28 0. Tb1 3.8-8 0 Sheet.4 8 Fig. 3.8-29 0 Tb1 3.8-9 0 Tb1 3.8-28 Fig. 3.8 26 Tb1 3.8-10 0 Sheet 1 8 Fig. 3.8-31 26 Tb1 3.8-11 0 Sheet 2 8 Fig. 3.8-32 26 Tbl 3.8-12 0 Tbl 3.8-29 Fig. 3.8-33 26 Tbl 3.8-13 0 Sheet 1 10 Fig. 3.8-34 5 Tb1 3.8-14 0 Sheet 2 10 Fig. 3.8-35 5 Tb1 3.8-15 0 Tb1 3.8-30 Fig. 3.8-36 7 Tb1 3.8-16 0 Sheet 1 30 Fig. 3.8-37 11 Tbl 3.8-17 0 Sheet 2 10 Fig. 3.8-38 23 Tb1 3.8-18 Sheet 3 10 Fig. 3.8-39 14 Sheet 1 19 Sheet 4 10 Fig. 3.8-40 7 Sheet 2 19 Tb1 3.8-31 33 Fig. 3.8-40A 26 Sheet 3 19 Tbl 3.8-32 33 Fig. 3.8-41 ?7 Sheet 4 19 Tb1 3.8-33 30 Fig. 3.8-42 18 Sheet 5 19 Tb1 3.8-34 33 Fig. 3.8-43 9 Tb1 3.8-19 Tbl 3.8-35 17 Fig. 3.8-44 30 Sheet 1 0 Tbl 3.8-36 33 Fig. 3.8-45 21 O Sheet 2 Tb1 3.8-20 Tb1 3.8-21 0 0 0 3.8 Fig. Tab Fig. 3.8-1 Fig. 3.8-2 24 26 Fig. Fig. Fig. 3.3-45A 3.8-46 3.8-46A 11 21 14 Tb1 3.8-22 Fig. 3.8-3 0 Fig. 3.8-47 17 Sheet 1 0 Fig. 3.8-4 0 Fig. 3.8-48 10 Sheet 2 0 Fig. 3.8-5 0 Fig. 3.8-49 1 Sheet 3 0 Fig. 3.8-6 0 Fig. 3.8-50 0 Tb1 3.8-23 0 Fig. 3.8-7 9 Fig. 3.8-51 0 Tb1 3.8-24 0 Fig. 3.8-8 1 Fig. 3.8-52 5 Tb1 3.8-25 Fig. 3.8-9 1 Fig. 3.8-53 21 Sheet 1 8 Fig. 3.8-10 5 Fig. 3.8-54 26 Sheet 2 8 Fig. 3.8-11 11 Fig. 3.8-55 18 Sheet 3 8 Fig. 3.8-12 0 Fig. 3.8-56 14 Sheet 4 8 Fig. 3.8-13 9 Fig. 3.8-57 5 Sheet 5 8 Fig. 3.8-14 0 Fig. 3.8-58 16 Sheet 6 8 Fig. 3.8-15 0 Fig. 3.8-59 21 Sheet 7 8 Fig. 3.8-16 21 Fig. 3.8-60 13 Sheet 8 8 Fig. 3,8-17 0 Fig. 3.8-61 18 Sheet 9 8 Fig. 3.8-38 14 ' Fig. 3.8-62 21 Sheet 10 8 Fig. 3.8-19 26 Fig. 3.8-63 11 Sheet 11 8 Fig. 3.8-20 7 Fig. 3.8-64 28 Tb1 3.8-26 Fig. 3.8-21 7 Fig. 3.8-65 28 Sheet 1 8 Fig. 3.8-22 0 Fig. 3.8-66 16 Sheet 2 8 Fig. 3.8-23 0 Fi g . 3.S-67 26 Sheet 3 8 Fig. 3.8-24 0 Fig. 3.8-68 21
) LOEP-23 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Fig. 3.8-69 26 3.9 Tab 3.9-31 27 Fig. 3.8-70 16 3.9-1 0 3.9-32 27 Fig. 3.8-71 21 3.9-2 0 3.9 Tbl Tab Fig. 3.8-72 21 3.9-3 3 Tb1 3.9-1 Fig. 3.8-73 16 3.9-4 27 Sheet 1 33 Fig. 3.8-74 16 3.9-4a 32 Sheet 2 33 Fig. 3.8-75 16 3.9-4b 3 Sheet 3 33 Fig. 3.8-76 16 3.9-5 26 Sheet 4 33 Fig. 3.8-77 16 3.9-6 19 Sheet 5 33 Fig. 3.8-78 16 3.9-7 19 Sheet 6 33 Fig. 3.8-79 16 3.9-8 33 Sheet 7 33 Fig. 3.8-80 16 3.9-8a 19 Sheet 8 33 3.3-8b 14 Sheet 9 33 VOLUME 8 3.9-9 8 Sheet 10 33 3.9-10 26 Sheet 11 33 i 12 3.9-11 26 Sheet 12 33 ii 12 3.S'-12 32 Sheet 13 33 iii 21 3.9-12a 32 Sheet 14 33 iv 21 3.9-12b 32 Sheet 15 33 v 21 3.9-13 26 Sheet 16 33 vi 21 3.9-14 8 Sheet 17 33 vii 21 3.9-15 12 Sheet 18 33 viii 21 2.9-16 28 Sheet 19 33 ix 21 3.9-17 28 Sheet 20 33 x 21 3.9-18 33 Sheet 21 33 xi 21 3.9-18a 32 Sheet 22 33 xii 21 3.9-18b 20. Sheet 23 33 xiii 15 3.9-18c 33 Sheet 24 33 xiv 21 3.9-18d 28 Sheet 25 33 xv 21 3.9-18e 28 Sheet 26 33 XVI 12 3.9-18f 20 Sheet 27 33 xvii 12 3.9-18g 26 Sheet 28 33 xviii 21 3.9-18h 20 Sheet 29 33 xix 26 3.9-19 26 Sheet 30 33 xx 26 3.9-20 0 Sheet 31 33 xxi 12 3.9-21 33 Sheet 32 32 xxii 26 3.9-22 G Tb1 3.9-2 xxiii 26 33.9-23 33 Sheet 1 0 xxiv 26 3.9-24 3 Sheet 2 1 xxv 26 3.9-24a 26 Tb1 3.9-3a 8 xxvi 26 3.9-24b 26 Tb1 3.9-3b xxvii 26 3.9-25 5 Sheet 1 30 xxviii 26 3.9-26 30 Sheet 2 30 xxix 26 3.9-27 18 Tb1 3.9-4 8 xxx 26 3.9-28 5 Tb1 3.9-Sa 29 xxxi 26 3.9-29 30 Tb1 3.9-5b xxxii 26 3.9-30 24 Sheet 1 26 LOEP- 24 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE FAGES (continued) fn k%- Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Sheet 2 8 Sheet 8 33 Sheet 31 14 Tb1 3.9-$ 8 Sheet 9 8 Sheet 32 14 Tb1 3.9-7 28 Sheet 10 30 Sheet 33 14 Tbl 3.9-8 Sheet 10a 33 Sheet 34 14 Sheet 1 19 Sheet 10b 16 Sheet 35 14 Sheet 2 26 Sheet 11 8 Sheet 36 14 Tb1 3.9-9 26 Sheet 12 28 Sheet 37 14 Tb1 3.9-10 26 Sheet 12a 24 Sheet 38 23 Tb1 3.9-10A Sheet 12b 24 Sheet 38a 23 Sheet 1 26 Sheet 12c 28 Sheet 38b 23 Sheet 2 27 Sheet 12d 24 Sheet 39 33 Sheet 3 32 Sheet 12e 28 Sheet 40 -14 Sheet 4 33 Sheet 12f 28 Sheet 41 14 Sheet 5 14 Sheet 12g 28 Sheet 42 14 Tb1 3.9-11 Sheet 12h 28 Sheet 43 14 Sheet 1 19 Sheet 13 24 Sheet 44 14 Sheet 2 19 Sheet 14 24 Sheet 45 33 Tb1 3.9-12 Sheet 14a 20 Sheet 46 30 Sheet 1 0 Sheet 14b 20 Sheet 47 33 Sheer 2 0 Sheet 14c 20 Sheet 48 14 Tb1 3.9-13 0 Sheet 14d 26 Sheet 49 23 Tb1 3.9-14 0 Sheet 14e 26 Sheet 30 23 I Tbl 3.9-15 33 Sheet 14f 20 Sheet 50a 23
\s- Tbl 3.9-15A 28 Sheet 14g 20 Sheet 50b 23 Tb1 3.9-16 0 Sheet 14h 20 Sheet 51 14 Tb1 3.9-17 Sheet 141 33 Sheet 52 16 Sheet 1 19 Sheet 14j 33 Sheet 53 16 Sheet 2 18 Sheet 14k 33 Sheet 54 16
! Sheet 2a 32 Sheet 141 33 Sheet 54a 16 Sheet 2b 21 Sheet 14e 33 Sheet 54b 16 l Sheet 2c 32 Sheet 14n 30 Sheet 55 14 Sheet 2d 32 Sheet 15 26 Sheet 56 16 Sheet 2e 32 Sheet 16 23 Sheet 56a 25 Sheet 2f 32 Sheet 17 23 Sheet 56b 16 Sheet 2g 32 Sheet 18 14 Sheet 56c 16 Sheet 2h 32 Sheet 19 14 Sheet 56d 16 Sheet 2i 32 Sheet 20 14 Sheet 57 16 Sheet 2j .", 2 Sheet 21 14 Sheet 58 14 Sheet 3 8 Sheet 22 14 Sheet 59 20 Sheet 4 16 Sheet 23 14 Sheet 60 14 Sheet 5 24 Sheet 24 14 Sheet 61 14 Sheet 6 26 Sheet 25 14 Sheet 62 14 Sheet 6a 24 Sheet 26 14 Sheet 63 16 i Sheet 6b 26 Sheet 27 14 Sheet 64 16 Sheet 6c 26 Sheet 28 14 Sheet 65 16 Sheet 6d 26 Sheet 29 14 Sheet 66 16 Sheet 7 14 Sheet 30 14 Sheet 67 14 l l l ()
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LOEP- 2 5 Revision 33 4/81 l
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Sheet 68 14 Sheet 96e 24 Sheet 120 24 Sheet 68a 26 Sheet 96f 30 Sheet 120a 24 Sheet 68b 16 Sheet 96g 26 Sheet 120b 24 Sheet 69 21 Sheet 96h 26 Sheet 121 20 Sheet 70 25 Sheet 96i 33 Sheet 122 20 Sheet 71 14 Sheet 96j 25 Sheet 123 20 Sheet 72 32 Sheet 96k 25 Sheet 124 27 Sheet 72a 27 Sheet 961 25 Sheet 125 30 Sheet 72b 16 Sheet 96m 33 Tb1 3.9-18 Sheet 73 14 Sheet 96n 25 Sheet 1 16 Sheet 74' 14 Sheet 96o 32 Sheet 2 16 Sheet 75 19 Sheet 90p 25 Sheet 2a 22 Sheet 76 28 3heet 97 32 Sheet 2b 32 Sheet 76a 28 Sheet 98 14 Sheet 3 21 Sheet 76b 20 Sheet 99 14 Sheet 4 4 Sheet 76c 20 Sheet 100 14 Sheet 5 4 Sheet 76d 20 Sheet 101 21 Sheet 6 19 Sheet 77 30 Sheet 102 16 Sheet 6a 24 Sheet 78 30 Sheet 103 14 Sheet 6b 32 Sheet 79 14 Sheet 104 21 Sheet 7 4 Sheet 80 14 Sheet 104a 21 Sheet 8 17 Sheet 81 30 sheet 104b 17 Sheet 9 26 Sheet 82 14 Sheet 105 21 Sheet 10 4 Sheet 82a 30 Sheet 106 21 Sheet 11 4 Sheet 82b 30 Sheet 106a 33 Sheet 12 4 Sheet 83 33 Sheet 106b 30 Sheet 13 4 Sheet 84 32 Sheet 106c 29 Sheet 14 4 Sheet 85 30 Sheet 106d 29 Sheet 15 4 Sheet 86 32 Sheet 106e 29 Sheet 16 4 Sheet 87 32 Sheet 106f 29 Sheet 17 4 Sheet 88 14 Sheet 107 33 Sheet 18 4 Sheet 89 27 Sheet 108 30 Sheet 19 4 Sheet 90 27 Sheet 109 21 Sheet 20 4 Sheet 91 30 Sheet 110 14 Tb1 3.9-19 0 Sneet 92 30 Sheet 111 26 Tbl 3.9-20 0 Sheet 93 14 Sheet 112 14 Tb1 3.9-21 Sheet 94 20 Sheet 112a 26 Sheet 1 5 Sheet 94a 20 Sheet 112b 26 Sheet 2 0 Sheet 94b 26 Sheet 113 33 Tb1 3.9-22 3 Sheet 94c 30 Sheet 114 30 Tb1 3.9-23 28 Sheet 94d 30 Sheet 115 30 Tbl 3.9-24 Sheet 95 33 Sheet 116 14 Sheet 1 33 Sheet 96 26 Sheet 117 16 Sheet 2 33 Sheet 96a 16 Sheet 118 26 Sheet 3 33 Sheet 96b 26 Sheet 118a 26 Tb1 3.9-25 8 Sheet 96c 26 Sheet 118b 30 Tb1 3.9-26 Sheet 96d 26 Sheet 119 28 Sheet 1 8 LOEP-26 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) l Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet-ID Rev. Sheet 2 8 Sheet 31 30 Tb1 3.9-31 25 Sheet 3 8 Sheet 32 16 Tb1 3.9-32 16 Sheet 4 8 Sheet 33 16 Tb1 3.9-33 Sheet 5 8 Sheet 34 30 Sheet 1 :21 Sheet 6 16 Sheet 34a 24 Sheet 2 21 Sheet 7 16 Sheet 34b 30 Tb1 3.9-34 Sheet 8 16 Sheet 34c 30 Sheet 1 33 Sheet 9 25 Sheet 34d 30 Sheet 2 33 Sheet 10 25 Sheet 34e 30' Sheet 3 33 Tb1 3.9-27 29 Sheet 34f 30 Sheet 4 33 Tb1 3.9-28 Sheet 34g 30 Sheet 5 33 Sheet 1 18 Sheet 34h 30 Tb1 3.9-35 28 Sheet 2 9 Sheet 35 26 Tb1 3.9-36 Sheet 2a 23 Sheet 36 16 Sheet 1 16 Sheet 2b 23 Sheet 37 . 2 46 Sheet 2 25-Sheet 3 9 Sheet 38 16 Sheet 3 16 Sheet 4 33 Sheet 39 16 Sheet 4 "16 Sheet 4a 33 Sheet 40 16 Sheet 5 16 Sheet 4b 30 Sheet 41 16 Tb1 3.9-37 16 Sheet 5 32 Sheet 42 16 Tb1 3.9-38 Sheet 6 32 Sheet 43 16 Sheet 1 16
- Sheet 7 32 Sheet 44 16 Sheet 2 30 (s
x
\
Sheet 8 Sheet 9 32 32 Sheet 45 Sheet 46 16 25 Sheet 3 Tb1 3.9-39 30 30 Sheet 10 32 Sheet 46a 25 Tb1 3.9-40 16 Sheet 11 16 Sheet 46b 17 Tb1 3.9-41 16 Sheet 12 16 Sheet 46c 17 Tb1 3.9-42 Sheet 13 16 Sheet 46d 27 Sheet 1 30 Sheet 14 26 Sheet 47 27 Sheet 2 16 Sheet 15 16 Sheet 48 33 Tbl 3.9 Sheet 16 16 Sheet 49 33 Sheet 1 25 Sheet 17 16 Sheet 50 16 Sheet 2 25 Sheet 18 27 Sheet 51 16 Tb1 3.9-44 Sheet 19 16 Sheet 52 16 Sheet 1 16-Sheet 20 16 Sheet 53 16 Sheet 2 16 Sheet 21 16 Tb1 3.9-29 Tb1 3.9-45 17 Sheet 22 30 Sheet 1 32 Tb1 3.9-46 33 Sheet 23 16 Sheet 2 32 Tb1 3.9-47 16 Sheet 24 30 Sheet 3 32 Tb1 3.9-48 24 Sheet 25 30 Sheet 4 32- Tbl 3.9-48a 24 Sheet 26 16 Tbl 3.9-29A Tb1 3.9-48b 26 i Sheet 27 16 Sheet 1 :45 Tb1 3.9-49 25 Sheet 28 30 Sheet 2 33 Tb1 3.9-50 16 Sheet 29 32 Tb1 3.9-29B Tb1 3.9-51 Sheet 30 32 Sheet 1 26 Sheet 1 16 Sheet 30a 32 Sheet 2 32 Sheet 2 16 Sheet 30b 32 Tbl 3.9-30 14 Sheet 3 16 i LOEP- 27 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Sheet 4 16 Tbl 3.9-68 30 xxi 12 Sheet 5 16 Tbl 3.9-68a 30 xxii 26 Sheet 6 25 Tb1 3.9-69 20 xxiii 26 Sheet 7 16 Tbl 3.9-70 32 xxiv 26 Sheet 8 16 Tb1 3.9-71 xxv 26 Sheet 9 21 Sheet 1 32 xxvi 26 Sheet 10 21 Sheet 2 21 xxvii 26 Sheet 11 21 Tb1 3.9-72 32 xxviii 26 Sheet 12 23 Tbl 3.9-73a 32 xxix 26 Sheet 13 23 Tb1 3.9-73b 32 xxx 26 Sheet 14 32 Tb1 3.9-73c 32 xxxi 26 Tb1 3.9-52 Tb1 3.9-73d 32 xxxii 26 Sheet 1 32 3.9 Fig. Tab 3.10 Tab Sheet 2 16 Fig. 3.9-1 33 3.10-1 0 TD1 3.9-53 Fig. 3.9-2 0 3.10-2 11 Sheet 1 16 Fig. 3.9-3 0 3.10-3 11 Sheet 2 16 Fig. 3.9-4 28 3.10-4 32 Tb1 3.9-54 16 Fig. 3.9-5 0 3.10-5 11 Tb1 3.9-55 16 Fig. 3.9-6 0 3.10-6 11 Tbl 3.9-56 16 Fig. 3.9-7 0 3.10-7 11 Tb1 3.9-57 16 Fig, 3.9-8 0 3.10-8 11 Tbl 3.9-58 Fig. 3.9-9 0 3.10-9 11 Sheet 1 29 Fig. 3.9-10 0 3.10-10 32 Sheet 2 29 Fig. 3.9-11 0 3.10-11 11 Sheet 3 29 3.10-12 13 Sheet 4 29 VOLUME 9 3.10-13 11 Sheet 5 29 3.10-14 14 Tb1 3.9-59 18 i 12 3.10-15 21 Tb1 'y.9-60 19 ii 12 3.10-16 21 Tb1 3.9-61 19 iii 21 3.10-16a 33 Tb1 3.9-62 iv 21 3.10-16b 21 Sheet 1 19 y 21 3.10-16c 21 Sheet 2 33 vi 21 3.10-16d 21 Sheet 3 19 vii 21 3.10-17 14 Sheet 4 19 viii 21 3.10-18 17 Sheet 5 33 ix 21 3.10-18a 33 Tb1 319-63 x 21 3.10-18b 32 Sheet 1 28 xi 21 3.10-18c 17 Sheet 2 19 xii 21 3.10-18d 17 Sheet 3 19 xiii 15 3.10-19 33 Sheet 4 28 xiv 21 3.10-20 33 Tb1 3.9-64 xv 21 3.10-21 33 Sheet 1 30 xvi 12 3.10-22 33 Sheet 2 29 xvii 12 3.10-23 33 Tbl 3.9-65 28 xviii 21 3.10-24 32 Tb1 3.9-66 20 xix 26 3.10-25 33 Tb1 3.9-67 30 xx 26 3.10--26 33 LOEP- 28 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) (G Latest Latest Latest Cheet ID Rev. Sheet ID Rev. Sheet ID Rev. 3.10-26a 33 3.10-54 13 3A-26 32 3 10-26b 33 3.10-55 27 3A-27 14 3.10-27 27 3.10 Tbl Tab 3A-28 30 3.10-28 27 Tb1 3.10-1 3A-29 33 3.10-29 27 Sheet 1 5 3A-30 33 3.10-30 30 Sheet 2 15 3A-31 0 3.10-30a 33 3.10 Fig. Tab 3A-32 32 3.10-30b 33 Fig. 3.10-1 22 3A-33 .28 3.10-30c 33 Fig.'3.10-2 26 3A-34 14 4 3.10-30d 33 Fig. 3.10-3 26 3A-35 30 3.10-31 30 Fig. 3.10-4 26 3A-36 30 3.10-32 33 Fig. 3.~10-5 8 3A-36a 30 3.1C-33 32 Fig. 3.10-6 8 3A-36b 30 3.10-34 32 3.11 Tab 3A-37 16 3.10 34a 33 3.11 Tb1 Tab 3A-38 33 3.10-34b 32 3.11 Fig. Tab 3A-39 33 3.10-35 32 App 3A Tab 3A-40 16 3.10-36 32 3A-1 33 3A-41 33 3.10-37 30 3A-2 33 3A-42 0 3.10-38 30 3A-3 0 3A-43 0 l 3.10-38a 30 3A-4 0 3A-44 33 3.10-38b 30 3A-5 0 3A-45 16 33 0 O' 3.10-38c 3.10-38d 3.10-38e 33 3A-6 3A-7 3A-8 0 0 3A-46 3A-47 0 0 32 Fig. 3A/1.34-1 0 3 3.10-38f 30 3A-9 0 Fig. 3A/1.34-2 0 3.10-38g 33 3a-10 33 3A-48 0 3.10-38h 33 3A-11 0 3A-49 0 3.10-38i 30 3A-12 26 3A-50 16 3.10-38j 33 3A-12a 17 3A-51 16 3.10-38k 30 3A-12b 17 3A-52 16 3.10-381 30 3A-13 0 3A-53' O 3.10-39 17 3A-14 32 3A-54 30 3.10-40 11 3A-15 16 3A-55 0 3.10-41 11 3A-16 0 3A-56 0 3.10-42 11 3A-17 4 3A-57 0 3.10-43 12 3A-18 0 3A-58 0 3.10-44 11 3A-19 4 3A-59 0 3.10-45 11 3A-20 4 3A-60 0 3.10-46 11 3A-21 26 3A-61 33 3.10-47 25 SA-22 26 3A-62 0 3.10-48 12 Fig. 3A/1.14-1 0 3A-63 28 1 3.10-49 12 Fig. 3A/1.14-2 0 3A-64 0 3.10-50 13 Fig. 3A/1.14-3 0 3A-65 32 3.10-51 11 3A-23 0 3A-66 32 3.10-52 11 3A-24 28 3A-66a 8 3.10-53 13 3A-25 27 3A-66b 8
) LOEP- 29 Re sion 33
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest 9 Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. 3A-67 32 3A-96 27 Fig. 3A/1.97-1 30 3A-68 32 3A-97 33 Fig. 3A/1.97-2 30 3A-69 0 3A-98 33 3A-132a 30 3A-70 0 3A-98a 33 3A-132b 30 3A-71 32 3A-98b 33 3A-133 18 3A-72 32 3A-99 33 3A-134 7 3A-73 26 3A-100 30 3A-135 33 3A-74 26 3A-100a 30 3A-136 30 3A-75 0 3A-100b 33 3A-137 0 3A-76 0 3A-101 0 3A-138 33 Tb1 3A.1.48-1 0 3A-102 0 3A-139 15 Tb1 3A.1.48-2 0 3A-103 33 3A-140 15 Tb3 3A.1.48-3 16 3A-104 0 3A-140a 33 Tb1 3A.1.48-4 17 3A-105 33 3A-140b 15 Tbl 3A.1.48-5 0 3A-106 16 3A-141 0 Tb1 3A.1.48-6 3A-107 18 3A-142 24 Sheet 1 0 3A-108 0 3A-142a 24 Sheet 2 0 3A-109 15 3A-142b 24 Tbl 3A.1.48-7 3A-110 0 3A-143 33 Sheet 1 17 3A-111 30 3A-144 33 Sheet i 18 3A-112 30 3A-145 14 3A-77 25 3A-112a 30 3A-146 18 3A-78 0 3A-112b 30 3A-147 33 3A-79 8 3A-113 14 3A-148 9 3A-80 8 3A-114 0 3A-149 14 3A-81 0 3A-11S 27 3A-150 18 3A-82 33 3A-116 33 3A-151 33 Tb1 3A.1.52-1 3A-117 33 3A-152 30 Sheet 1 33 3A-118 33 3A-152a 33 Sheet 2 33 3A118a 32 3A-152b 33 Sheet 3 33 3A118b 32 3A-153 32 Sheet 4 33 3A-119 0 3A-154 33 3A-83 33 3A-120 17 3A-155 16 3A-84 33 3A-121 19 3A-156 25 3A-84a 33 3A-122 20 3A-157 14 3A-84b 33 3A-123 0 3A-158 18 3A-85 16 3A-124 0 3A-159 18 3A-86 0 3A-125 33 3A-160 33 3A-87 0 3A-126 33 3A-161 32 l 3A-88 16 3A-127 0 3A-162 18 3A-89 30 3A-128 17 3A-163 35 3A-90 26 3A.129 32 3A-91 25 3A-130 25 VOLUME 10 3A-92 0 3A-130a 8 l 3A-93 0 3A-130b 30 i 12 3A-94 0 3A-131 30 ii 12 3A-95 17 3A-132 30 iii 21 LOEP- 3 0 Revition 33 4/81 i
i MIDLAND 1&2-FSAR LIST OF EFFECTIVE'PAGES (continued) I p3 _h Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. iv 21 3C-18 0 3C-65 ~ 0 v 21 3C-19 0 3C-66 0 vi 21 -3C-20 0 3C-67 0 vii 21- 3C-21 0 3C-69 0 viii 21 3C-22 0- 3C-69 0 ix 21 3C-23 0 3C-70 0 x 21- 3C-24 0 3C-71 0 xi 21 3C-25 O. 3C-72 0 xii 21 3C-26 0 3C-73 0 xiii 15 3C-27 0 3C-74 0 xiv 21 3C-28 0 3C-75 0 xv 21 3C-29 0 3C-76 0 1 xvi 12 3C-30 0 3C-77 0 xvii 12 3C-31 0 3C-78 0 xviii 21 3C-32 0 3C-79 0 xix 26 3C-33 0 3C-80 0 xx 26 30-34 0 3C-81 0 xxi 12 3C-35 0 3C-82 0 . xxii 26 3C-36 0 3C-83 0 xxiii 26 3C-37 0 3C-84 0 xxiv 26 3C-38 0 3C-85 0 xxv 26 3C-39 0 -3C-86 0 0 n) xxvi xxvii xxviii 26 26 26 3C-40 3 C -41 3C-42 0 0 0 3C-87 3C-88 3C-89 0 0 xxix 26 3C-43 0 3C-90 0 xxx 26 3C-44 0 3C-91 0 xxxi 26 3C-45 0 3C-92 0 App 3B Tab 3C-46 0 3C-93 0 App 3C Tab 3C-47 0 3C-94 0 3C-1 0 3C-48 0 3C-95 0 3C-2 20 3C-49 0 3C-96 0 3C-3 32 3C-50 0 3C-97 0 3C-4 0 3C-51 0 3C-98 0 3C-5 0 3C-52 0 3C-99 0 3C-6 0 3C-53 0 3C-100 0 3C-7 0 3C-54 0 3C-101 0 3C-8 0 3C-55 0 3C-102 0 3C-9 0 3C-56 0 3C-103 0 3C-10 0 3C-57 0 3C-104 0 l 3C-11 0 3C-58 0 3C-105 0 3C-12 0 3C-59 0 3C-106 0 3C-13 0 3C-60 0 3C-107 0-3C-14 0 3C-61 0 3C-108 0 3C-15 0 3C-62 0 3C-109 0 3C-16 0 3C-63 0 3C-110 0 3C-17 0 3C-64 0 3C-111 0 l LOEP- 31 Revision 33 1 4/81 i _. . . _ . . _ - - ., - _ _, ,_._ _ _ _ . . . . - _ , . _ _ . _ . _ - - - - - . . _ _ . - . ~ . _ .
MIDLAND 1&2-FSAR LIST GF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. 3C-112 0 3C-159 0 3C-206 0 3C-113 0 3C-160 0 3C-207 0 3C-114 0 3C-161 0 3C-208 0 3C-115 0 3C-162 0 3C-209 0 3C-11r> 0 3C-163 0 3C-210 0 3C-117 0 3C-164 0 3C-211 0 3C-118 0 3C-165 0 3C-212 0 3C-119 0 3C-166 0 3C-213 0 3C-120 0 3C-167 0 3C-214 0 3C-121 0 3C-168 0 3C-215 0 3C-122 0 3C-169 0 3C 216 0 3C-123 0 3C-170 0 3C-217 0 3C-124 0 3C-171 0 3C-218 0 3C-125 0 3C-172 0 3C-219 0 3C-126 0 3C-173 0 3C-220 0 3C-127 0 3C-174 0 3C-221 0 3C-128 0 3C-175 0 3C-222 0 3C-129 0 3C-176 0 3C-223 0 3C-130 0 3C-177 0 3C-224 0 3C-131 0 3C-178 0 3C-225 0 3C-132 0 3C-179 0 3C-226 0 3C-133 0 3C-180 0 3C-227 0 3C-134 0 3C-181 0 3 C-2.~. s 32 3C-135 0 3C-182 0 3C-229 0 3C-136 0 3C-183 0 3C-230 0 3C-137 0 3C-184 0 3C-231 0 3C-138 0 3C-185 0 3C-232 0 3C-139 0 3C-let 0 3C-233 0 3C-140 0 3C-187 0 3C-234 32 3C-141 0 3C-188 0 3C-235 0 3C-142 0 3C-189 0 3C-236 0 3C-143 0 3C-190 0 3C-237 0 3C-144 0 3C-191 0 3C-238 0 3C-145 0 3C-192 0 3C-239 0 32-146 0 3C-193 0 3C-240 0 3C-14"i 0 3C-194 0 3C-241 0 3C-148 0 3C-195 0 3C-242 0 3C-149 0 3Ce196 0 3C-243 32 3C-150 0 3C-197 0 3C-244 0 3C-151 0 3C-198 0 3C-245 0 3C-152 0 3C-199 0 3C-246 0 3C-153 0 3C-200 0 3C-247 32 3C-154 0 3C-201 0 3C-248 0 3C-155 0 3C-202 0 3C-249 0 3C-156 0 3C-203 0 3C-250 0 3C-157 0 3C-204 0 3C-251 0 3C-158 0 3C-205 0 3C-252 0 LOEP 32 Revision 33 4/81
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3C-253 0 3C-300 32 . Sheet 1 30 3C-254 0 3C-301 32 -Sheet 2 30 3C-255 0- 3C-302 0 Tb1 3D-2 30 3C-236 0 3C-303 0 Tbl 3D-3 30 3C-2a7 0 3C-304 20 Tb1 3D-4 30 3C-258 0 3C-305 20 Tbl 3D-5 30 3C-259 0 3C-306 32 Tb1 3D-6 30 3C-260 0 3C-307- 20 Tb1 3D-7 30 3C-261 0 3C-308 20 Tb1 3D-8 30 3C-262 0 3C-309 20 Tbl 3D-9 30 3C-263 0 3C-310 32 Tb1 3D-10 30 3C-264 0 3C-311 32 Tb1 3D-11 30 3C-265 0 3C-312 32 Tb1 3D-12 30 3C-266 0 3C-313 32 Tbl 3D-13 3C-267 0 3C-314 20 Sheet 1 33 3C-258 0 3C-315 20 Sheet 2 30 3C-269 0 3C-316 20 Sheet 3 30 3C-270 0 3C-317 20 Tb1 3D-14 30 3C-271 0 3C-318 20 Tb1 3D-15 .30 3C-272 0 3C-319 20 Tb1 3D-16 33 , 3C-273 0 3C-320 20 Tbl 3D-17 30 ( 3C-274 0 App 3D Tab Tb1 3D-18 3C-275 0 3D-i 19 Sheet 1 30 3C-276 32 3D-il 30 Sheet 2 30 3C-277 0 3D-iii 30 Tbl 3D-19 3C-278 0 3D-iv 30 Sheec 1 30 3C-279 0 3D-1 19 Sheet 2 30 3C-280 0 3D-2 19 Tbl 3D-20 3C-281 0 3D-3 19 Sheet 1 30 3C-282 0 3D-4 19 Sheet 2 33 3C-283 0 3D-5 19 Fig. 3D-1 19 3C-284 0 3D-6 33 Fig. 3D-1A 30 3C-285 0 3D-7 26 Fig. 3D-2 30 3C-286 0 3D-8 19 Fi g. 3D-3 19 3C-287 0 3D-9 19 Fig. 3D-4 19 3C-288 0 3D-10 30 Fig. 3D-5 30 3C-289 0 3D-ll 19 Chapter 4 Tab 3C-290 0 3D-12 19 4-i 33-3C-291 0 3D-13 33 4-ii 33 3C-292 0 3D-14 33 4-iii 33 3C-293 0 3D-15 33 4-iv 18 3C-294 0 3D-16 33 4-v 26 3C-295 0 3D-17 33 4-vi -26 3C-296 0 3D-18 30 4-vii 16 3C-297 32 3D-19 30 4-viii 33 3C-298 0 3D-20 30 4-viiia 33 3C-299 0 Tb1 3D-1 4-viiib 33 t/ LOEP- 33 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. 4-ix 32 4.2-18f 32 Fig. 4.2-12 26 4-x 32 4.2-19 9 Fig. 4.2-13 26 4-xi 32 4.2-20 32 Fig. 4.2-14 26 4-xii 32 4.2-21 14 Fig. 4.2-15 26 4-xiii 32 4.2-22 33 Fig. 4.2-16 26 4-xiv 32 4.2-22a 33 Fig. 4.2-17 0 4-xv 32 4.2-22b 26 Fig. 4.2-18 0 4-xvi 32 4.2-23 33 Fig. 4.2-19 0 4-xvii 32 4.2-24 33 Fig. 4.2-20 32 4-xviii 32 4.2-25 9 4-xix 32 4.2-26 9 VOLUME 11 4.1 Tab 4.2-27 33 4.1-1 15 4.2-28 9 i 12 4.1 2 15 4.2-29 9 11 12 4.1 Tbl Tab 4.2-30 9 iii 21 Tb1 4.1-1 4.2-31 32 iv 21 Sheet 1 33 4.2-32 33 v 21 Sheet 2 33 4.2-33 9 vi 21 Tb1 4.1-2 4.2-34 15 vii 21 Sheet 1 29 4.2-35 26 viii 21 Sheet 2 0 4.2-36 32 ix 21 4.2 Tab 4.2-37 26 x 21 4.2-1 0 4.2 Tb1 Tab xi 21 4.2-2 30 Tbl 4.2-1 32 xii 21 4.2-3 10 Tbl 4.2-2 32 xiii 15 4.2-4 9 Tbl 4.2-3 26 xiv 21 4.2-5 32 Tb1 4.2-4 0 xv 21 4.2-6 33 Tbl 4.2-5 15 xvi 12 4.2-7 33 Tb1 4.2-6 32 xvii 12 4.2-8 33 Tb1 4.2-7 9 xviii 21 t 4.2-9 33 Tbl 4.2-8 32 xix 26 4.2-10 26 Tbl 4.2-9 32 xx 26 l 4.2-10a 32 Tb1 4.2-10 32 xxi 12 4.2-10b 18 4.2 Fig. Tab xxii 26 4.2-11 9 FiJ. 4.2-1 32 xxiii 26 4.2-12 9 Fig. 4.2-2 0 xxiv 26 4.2-13 32 Fig. 4.2-3 0 xxv 26 4.2-24 32 Fig. 4.2-4 0 xxvi 26 i 4.2-15 32 Fig. 4.2-5 0 xxvii 26 4.2-16 15 Fig. 4.2-Sa 32 xxviii 26 4.2-17 33 Fig. 4.2-5b 32 xxix 26 i 4.2-18 9 Fig. 4.2-6 33 xxx 26 4.2-18a 33 Fig. 4.2-7 26 xxxi 26 l 4.2-18b 32 Fig. 4.2-8 26 xxxii 26 4.2-1dc 32 Fig. 4.2-9 26 4.3 Tab 4.2-18d 33 Fig. 4.2-10 26 4.3-1 0 4.2-18e 33 Fig. 4.2-11 26 4.3-2 33 LOEP-34 Revision 33 1 4/81 1
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) C' Latest Latest __ Latest Sheet ID Rev. Sheet ID Rev. Sheet-ID Rev. 4.3-2a 33 Sheet 1- 33 Fig. 4.3-15 0 4.3-2b 33 Sheet 2 33 Fig. 4.3-16 0 4.3-3 0 Tb1 4.3-3 30 Fig. 4.3-17 0 4.3-4 30 Tbl 4.3-4 0 Fig. 4.3-18 0 4.3-5 7 Tbl 4.3-5' O Fig. 4.3-19 7 4.3-6 0 Tb1 4.3-6 0- Fig. 4.3-20 _7 4.3-7 33 Tb1 4.3-7 0 Fig. 4.3-21 0 4.3-8 0 Tb1 4.3-8 0 Fig. 4.3-22 0 0.3-9 26 Tbl 4.3-9 7- Fig. 4.3-23 0 a.3-10 33 Tb1 4.3-10 0 Fig. 4.3-24 0 4.3-11 30 Tb1 4.3-11 0 Fig. 4.3-25 0 4.3-12 30 Tbl 4.3-12 0- Fig. 4.3-26 0 4.3-13 30 Tbl 4.3-13 33 Fig. 4.3-27 0 4.3-14 33 Tb1 4.3-14 30 Fig. 4.3-28 0 4.3-15 33 Tb1 4.3-15 30 Fig. 4.3-29 0 4.3-16 33 Tb1 4.3-16 30 Fig. 4.3-30 0 4.3-17 33 Tb1 4.3-17 30 Fig. 4.3-31 0 4.3-18 33 Tb1 4.3-18 0 Fig. 4.3-32 0 4.3-19 33 Tb1 4.3 19 0 Fig. 4.3-33 0 4.3-20 30 Tb1 4.3-20 30 Fig. 4.3-34 0 4.3-21 33 Tb1 4.3-21 30 Fig. 4.3-35 0 4.3-22 7 Tb1 4.3-22 0 Fig. 4.3-36 _7 4.3-23 7 Tb1 4.3-23 0 Fig. 4.3-37 0 O-N- 4.3-24 0 Tb1 4.3-24 0 Fig. Fig. 4.3-38 4.3-39 0 0 4.3-25 0 Tb1 4.3-25 0 4.3-26 0 Tb1 4.3-26 25 Fig. 4.3-40 0 4.3-27 33 Tb1 4.3-27 0 Fig. 4.3-41 0 4.3-28 25 Tb1 4.3-28 0 Fig. 4.3-42 0 4.3-29 0 Tb1 4.3-29 0 Fig. 4.3-43 7 I 4.3-30 27 Tb1 4.3-30 0 Fig. 4.3-44 0 4.3-31 0 Tb1 4.3-31 0 Fig. 4.3-45 0 4.3-32 0 Tb1 4.3-37 25 Fig. 4.3-46 0 4.3-33 25 4.3 Fig. Tab Fig. 4.3-47 0 i 4.3-34 28 Fig. 4.3-1 0 Fig. 4.3-48 0 4.3--35 5 Fig. 4.3-2 0 Fig. 4.3-49 0 l 4.3-36 33 Fig. 4.3-3 0 Fig. 4.?-50 0 4.3-37 0 Fig. 4.3-4 0 Fig. 4. 3-51 0 4.3-38 27 Fig. 4.3-5 0 Fig. 4.3-52 0 l 4.3-39 0 Fig. 4.3-6 0 Fig. 4.3-53 0 4.3-40 30 Fig. 4.3-7 0 Fig. 4.3-54 0 4 4.3-41 33 Fig. 4.3-8 0 Fig. 4.3-55 0 4.3-42 3 Fig. 4.3-9 0 Fig. 4.3-56 0 l 4.3-43 27 Fig. 4.3-10 0 Fig. 4.3-57 0 4.3-44 5 Fig. 4.3-11 0 Fig. 4.3-58 0 1 4.3 Tb1 Tab Fig. 4.3-12 0 Fig. 4.3-59 0 Tbl 4.3-1 30 Fig. 4.3-13 0 Fig. 4.3-60 0 Tb1 4.3-2 Fig. 4.3-14 0 Fig. 4.3-61 32 l LOEP- 3 5 Revision 33 j q- ) 4/61 l
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Fig. 4.3-62 7 Fig. 4.3-109 0 4.4-42 17 Fig. 4.3-63 7 Fig. 4.3-110 0 4.4-43 33 Fig. 4.3-64 7 Fig. 4.3-111 0 4.4-44 33 Fig. 4.3-65 7 4.4 Tab 4.4-45 33 Fig. 4.3-66 7 4.4-1 33 4.4-46 33 Fig. 4.3-67 0 4.4-2 18 4.4 Tb1 Tab Fig. 4.3-68 0 4.4-3 33 Tb1 4.4-1 Fig. 4.3-69 0 4.4-4 33 Sheet 1 32 Fig. 4.3-70 0 4.4-5 0 Sheet 2 18 Fig. 4.3-71 0 4.4-6 3 Tb1 4.4-2 0 Fig. 4.3-72 0 4.4-7 3 Tb1 4.4-3 0 Fig. 4.3-73 0 4.4-8 0 Tb1 4.4-4 0 Fig. 4.3-74 0 4.4-9 0 Tb1 4.4-5 32 Fig. 4.3-75 30 4.4-10 33 Tb1 4.4-6 0 Fig. 4.3-76 30 4.4-11 0 Tb1 4.4-7 0 Fig. 4.3-77 0 4.4-12 0 Tb1 4.4-8 32 Fig. 4.3-78 0 4.4-13 0 Tb1 4.4-9 32 Fig. 4.3-79 7 4.4-14 0 Tb1 4.4-10 0 Fig. 4.3-80 7 4.4-15 3 Tb1 4.4-11 Fig. 4.3-81 0 4.4-16 0 Sheet 1 10 Fig. 4.3-82 7 4.4-17 33 Sheet 2 10 Fig. 4.3-83 7 4.4-18 32 4.4 Fig. Tab Fig. 4.3-84 0 4.4-19 0 Fig. 4.4-1 3 Fig. 4.3-85 0 4.4-20 0 Fig. 4.4-2 3 Fig. 4.3-86 0 4.4-21 33 Fig. 4.4-3 0 Fig. 4.3-87 0 4.4-22 0 Fig. 4.4-4 0 Fig. 4.3-88 0 4.4-23 26. Fig. 4.4-5 0 Fig. 4.3-89 7 4.4-24 0 Fig. 4.4-6 0 Fig. 4.3-90 9 4.4-25 33 Fig. 4.4-7 0 Fig. 4.3-91 30 4.4-26 0 Fig. 4.4-8 0 Fig. 4.3-92 0 4.4-27 0 Fig. 4.4-9 0 Fig. 4.3-93 0 4.4-28 10 Fig. 4.4-10 0 Fig. 4.3-94 3 4.4-28a 10 Fig. 4.4-11 0 Fig. 4.3-95 0 4.4-28b 33 Fig. 4.4-12 0 Fig. 4.3-96 0 4.4-29 0 Fig. 4.4-13 32 Fig. 4.3-97 0 4.4-30 0 Fig. 4.4-14 0 Fig. 4.3-96 0 4.4-31 3 Fig. 4.4-15 0 Fig. 4.3-99 0 4.4-32 0 Fig. 4.4-16 0 Fig. 4.3-100 3 4.4-33 0 Fig. 4.4-17 0 Fig. 4.3-101 0 4.4-34 8 Fig. 4.4-18 0 Fig. 4.3-102 0 4.4-35 8 Fig. 4.4-19 3 Fig. 4.3-103 0 4.4-36 33 Fig. 4.4-20 0 Fig. 4.3-104 0 4.4-37 32 Fig. 4.4-21 0 Fig. 4.3-105 0 4.4-38 33 Fig. 4.4-22 0 Fig. 4.3-106 0 4.4-39 33 Fig. 4.4-23 0 Fig. 4.3-107 0 4.4-40 33 Fig. 4.4-24 0 Fig. 4.3-108 0 4.4-41 17 Fig. 4.4-25 0 LGEP- 3 6 Revision 33 4/81
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Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Fig. 4.4-26 0 Sheet 1 26 5.2-22b. 33 4.5 Tab Sheet 2 26 5.2-23 33 4.5-1 0 Tb1 5.1-7 5.2-24 26 4.5-2 33 Sheet 1 27 5.2-25 26 4.5-3 33 Sheet 2 27 5.2-26 33 4.6 Tab 5.1 Fig. Tab 5.2-26a 33 4.6-1 0 Fig. F.1-1 5.2-26b 33 . 4.6-2 0 Sheet 1 32 5.2-27 30 4.6-3 0 Sheet 2 30 5.2-28 26 4.6-4 27 Fig. 5.1-2 5.2-29 26 4.6-5 0 Sheet 1 .32 5.2-30 33 4.6 Tb1 Tab Sheet 2 30 5.2-31 33 Tb1 4.6-1 0 Fig. 5.1-3 30 5.2-32 26 Tb1 4.6-2 0 Fig. 5.1-4 0 5.2-33 26 Chapter 5 Tab Fig. 5.1-5 3 5.2-34 26 5-i 33 5.2 Tab 5.2 Tb1 Tab 5-ii 26 5.2-1 33 Tb1 5.2-1 32 5-iii 26 5.2-2 33 Tb1 5.2-2 5-iv' 30 5.2-3 33' Sheet 1 32 5-v 30 5.2-4 33 Sheet 2 32 5-vi 25 5.2-4a 33 Tb1 5.2-3 5-via 27 5.2-4b 10 sheet 1 8 5-vib 18 5.2-5 33 Sheet 2 0
- 5-vii 19 5.2-6 33 Sheet 3 0 l 5-viii 33 5.2-6a 33 Tb1 5.2-3A 8 l 5-ix 18 5.2-6b 33 Tb1 5.2-4 5-ixa 18 5.2-6c 33 Sheet 1 0 5.1 Tab 5.2-6d 33 Sheet 2 30 5.1-1 0 5.2-6e 33 Tb1 5.2-5 0 5.1-2 0 5.2-6f 30 Tb1 5.2-6 0 5.1-3 33 5.2-7 33 Tb1 5.2-7 33 5.1-4 30 5.2-8 26 Tb1 5.2-8 5.1 Tb1 Tab 5.2-9 33 Sheet 1 25 Tb1 5.1-1 5.2-10 33 Sheet 2 25 Sheet 1 33 5.2-11 0 Sheet 3 25 Sheet 2 30 5.2-12 0 sheet 4 25 Tb1 5.1-2 5.2-13 0 Sheet 5 25 Sheet 1 0 5.2-14 0 Sheet'6 25 Sheet 2 25 5.2-15 6 Sheet 7 25 Tb1 5.1-3 5.2-16 26 Sheet 8 25 Sheet 1 26 5.2-17 26 Sheet 9 25 Sheet 2 26 5.2-18 26 Sheet 10 25 Tb1 5.1-4 26 5.2-19 26 Sheet 11 25 Tb1 5.1-5 5.2-20 30 sheet 12 25 Sheet 1 27 5.2-21 33 Sheet 13 25 Sheet 2 27 5.2-22 33 Sheet 14 25 Tb1 S.1-6 5.2-22a 33 5.2 Fig. Tab i
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MIDLAND ]&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Fig. 5.2-1 30 5.4-2 33 5.4-35 33 Fig. 5.2-2 20 5.4-3 33 5.4 Thl Tab Fig. 5.2-3 20 5.4-4 33 Tb1 5.4-1 27 Fig. 5.2-4 30 5.4-5 33 Tb1 5.4-2 0 Fig. 5.2-5 30 5.4-6 32 Tb1 5.4-3 27 5.3 Tab 5.4-6a 8 Tb1 5.4-4 27 5.3-1 33 5.4-6b 27 Tb1 5.4-5 5.3-2 33 5.4-6c 33 Sheet 1 27 5.3-3 33 5.4-6d 30 Sheet 2 0 5,3-4 33 5.4-7 0 Sheet 3 0 5.3-5 33 5.4-8 0 Sheet 4 0 5.3-6 28 5.4-9 0 Sheet 5 0 5.3-6a 33 5.4-10 33 Tb1 5.4-6 5.3-6b 22 5.4-11 33 Sheet 1 30 5.3-7 33 5.4-12 27 Sheet 2 30 5.3-8 8 5.4-13 8 Tb1 5.4-7 30 5.3-9 8 5.4-14 33 Tb1 5.4-8 30 5.3-10 8 5.4-14a 28 Tbl 5.4-9 14 5.3-11 21 5.4-14b 8 Tb1 5.4-10 5.3-12 33 5.4-15 33 Sheet 1 19 5.3-13 33 5.4-16 0 Sheet 2 37 5.3-14 33 5.4-17 0 Sheet 3 33 5.3-15 33 5.4-18 33 Tb1 5.4-11 30 5.3-16 33 5.4-18a 30 Tb1 5.4-12 5.3 Tb1 Tab 5.4-18b 33 Sheet 1 9 Tbl 5.3-1 8 5.4-19 33 Sheet 2 30 Tbl 5.3-2 26 5.4-20 33 Tbl 5.4-13 28 Tb1 5.3-3 22 5.4-20a 33 Tb1 5.4-14 Tb1 5.3-4 8 5.4-20b 3 Sheet 1 14 Tbl 5.3-5 8 5.4-21 33 Sheet 2 14 Tb1 5.3-6 8 5.4-22 30 Tbl 5.4-14A 15 Tb1 5.3-7 5.4-25 30 Tb1 5.4-15 19 Sheet 1 26 5.4-24 33 5.4 Fig. Tab Sheet 2 22 5.4-25 33 Fig. 5.4-1 0 5.3 Fig. Tab 5.4-26 30 Fig. 5.4-2 27 Fig. 5.3-1 0 5.4-26a 33 Fig. 5.4-3 0 Fig. 5.3-2 8 5.4-26b 14 Fig. 5.4-4 0 Fig. 5.3-3 8 5.4-26c 30 Fig. 5.4-5 0 Fig. 5.3-4 8 5.4-26d 14 Fig. 5.4-6 0 Fig. 5.3-5 8 5.4-27 33 Fig. 5.4-7 0 Fig. 5.3-6 8 5.4-28 33 Fig. 5.4-8 0 Fig. 5.3-7 15 5.4-29 3 Fig. 5.4-9 0 Fig. 5.3-0 30 5.4-30 33 Fig. 5.4-10 32 Fig. 5.3-9 33 5.4-31 28 Fig. 5.4-11 32 Fig. 5.3-10 33 5.4-32 30 Fio. 5.4-12 0 5.4 Tab 5.4-33 0 Fig. 5.4-13 0 5.4-1 27 5.4-34 33 Fig. 5.4-14 0 LOEP- 3 8 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Fig. 5.4-15 21 6-vii 8 6.2-7 0 Fig. 5.4-16 3 6-viii 17 6.2-8 32 Fig. 5.4-17 3 6-ix 8 6.2-9 33 6-x 33 6.2-10 24 VOLUME 12 6-xi 19 6.2-11 15 6-nii 22 6.2-12 24 i 12 6-xiia 33 6.2-12a 24 , ii 12 6-xiib 22 6-2-12b
. 33 iii 21 6-xiii 26 6.2-13 12 iv 21 6-xiv 26 6.2-14 3 v 21 6-xv 11 6.2-15 32 vi 21- 6-xvi 33 6.2-16 32 vii 21 6-xvii 33 6.2-17 32 viii 21 6-xviii 33 6.2-18 33 ix 21 6-xix 33 6.2-18a 32 x 21 6-xx 33 6.2-18b 32 xi 21 6-xxi 33 6.2-19 32 xii 21 6-xxii 33 6.2-20 32 xiii 15 6-xxiii 33 6.2-21 33 xiv 21 6-xxiv 33 6.2-22 33 xv 21 6-xxv 33 6.2-22a 19 xvi 12 6-xxvi 33 6.2-22b 19 O xvii xviii xix 12 21 26 6-xxvii 6-xxviii 6-xxix 33 33 33 6.2-23 6.2-24 6.2-25 0
0 3 xx 26 6.1 Tab 6.2-26 0 xxi 12 6.1-1 0 6.2-27 0 xxii 26 6.1-2 30 6.2-28 0 xxiii 26 6.1-3 33 6.2-29 32 xxiv 26 6.1-4 33 6.2-30 0 xxv 26 6.1-5 33 6.2-31 0 xxvi 26 6.1 Tb1 Tab 6.2-32 0 xxvii 26 Tb1 6.1-1 30 6.2-33 0 xxviii 26 Tb1 6.1-2 30 6.2-34 33 xxix 26 Tb1 6.1-3 0 6.2-35 0 xxx 26 Tb1 6.1-4 33 6.2-36 0 xxxi 26 Tb1 6.1-5 6.2-37 0 xxxii 26 Sheet 1 33 6.2-38 0 Chapter 6 Tab Sheet 2 30 6.2-39 0 6-i 30 Sheet 3 30 6.2-40 0 6-ii 30 6.2 Tab 6.2-41 0 6-iii 15 6.2-1 0 6.2-42 0 6-iv 15 6.2-2 32 6.2-43' O 6-v 26 6.2-3 0 6.2-44 0 7 6-vi 30 6.2-4 32 6.2-45 0 6-via 15 6.2-5 1 6.2-46 32 6-vib 8 6.2-6 0 6.2-47 32 LOEP- 39 Revision 33 4/81
MIDLAND 1&2-FSI.R LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. 6.2-48 0 6.2-87 32 6.2-120 22 6.2-49 0 6.2-88 32 6.2-121 33 6.2-50 0 6.2-89 32 6.2-122 33 6.2-53 0 6.2-90 33 6.2 Tb1 Tab 6.2-52 32 6.2-91 33 Tb1 6.2-1. 6.2-53 32 6.2-92 33 Sheet 1 24 6.2-54 0 6.2-92a 32 Sheet 2 24 6.2-55 0 6.2-92b 2 Tbl 6.2-2 32 6.2-56 0 6.2-93 0 Tbl 6.2-3 32 6.2-57 3 6.2-94 32 Tbl 6.2-4 6.2-58 0 6.2-95 32 Sheet 1 24 6.2-59 0 6.2-96 32 Sheet 2 24 6.2-60 0 6.2-96a 32 Sheet 3 24 6.2-61 3 6.2-96b 8 Sheet 4 24 6.2-62 33 6.2-97 32 Sheet 5 24 6.2-63 32 6.2-98 0 Sheet 6 24 6.2-64 8 6.2-99 0 Sheet 7 24 6.2-65 33 6.2-100 33 Sheet 8 24 6.2-66 33 6.2-101 33 Sheet 9 24 6.2-67 33 6.2-102 33 Sheet 10 24 6.2-68 32 6.2-102a 2 Tb1 6.2-5 6.2-68a 32 6.2-102b 2 Sheet 1 24 6.2-68b 32 6.2-103 33 Sheet 2 24 6.2-69 0 6.2-104 33 Sheet 3 24 6.2-70 33 6.2-105 33 Sheet 4 24 6.2-71 33 6.2-106 33 Sheet 5 24 6.2-72 32 6.2-107 33 Sheet 6 24 6.2-72a 25 6.2-108 33 Sheet 7 24 6.2-72b 17 6.2-109 33 Sheet 8 24 6.2-73 32 6.2-110 33 Sheet 9 24 6.2-74 33 6.2-110a 33 Sheet 10 24 6.2-75 32 6.2-110b 33 Sheet 11 24 6.2-76 32 6.2-110c 33 Sheet 12 24 6.2-76a 33 6.2-110d 33 Sheet 13 32 6.2-76b 32 6.2-111 33 Sheet 14 32 6.2-77 32 6.2-112 33 Sheet 15 24 6.2-78 32 6.2-113 33 Tbl 6.2-6 6.2-79 32 6.2-114 30 Sheet 1 0 6.2-80 29 6.2-114a 30 Sheet 2 0 6.2-81 32 6.2-114b 33 Tbl 6.2-7 27 6.2-82 13 6.2-114c 17 Tbl 6.2-8 32 6.2-83 0 6.2-114d 15 Tbl 6.2-9 6.2-84 33 6.2-115 0 Sheet 1 32 6.2-85 32 6.2-116 0 Sheet 2 33 6.2-86 22 6.2-117 0 Tb1 6.2-10 6.2-86a 22 6.2-118 0 Sheet 1 32 6.2-86b 22 6.2-119 18 Sheet 2 32 LOEP 4 0 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued)
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' (/ Latest Latest . Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Sheet 3 12 Sheet 3 32 Tb1 6.2-29 Sheet 4 12 Tb1 6.2-23 Sheet 1 32 Tb1 6.2-11 Sheet 1- 23 Sheet 2 33 Sheet 1 12 Sheet 2 32 Tb1 6.2-30 Sheet 2 12 Sheet 3 32 Sheet 1 33 Sheet 3 12 Sheet 4 15 Sheet 2 33 Tbl 6.2-12 0 Sheet 5 15 Tb1 6.2-31 0 Tb1 6.2-13 Sheet 6 15 Tb1 6.2-32 0 Sheet 1 24 Tb1 6.2-24 Tb1 6.2-33 0 Sheet 2 24 Sheet 1 27 Tb1 6.2-34 Tb1 6.2-14 Sheet 2 0 Sheet 1 32 Sheet 1 13 Tbl 6.2-25 32 Sheet 2 32 Sheet 2 32 Tb1 6.2-26 0 Tb1 6.2-35 Sheet 3 32 Tbl 6.2-27 Sheet 1 0 Sheet 4 32 Sheet 1 30 Sheet 2 0 Sheet 5 14 Sheet 2 32 Sheet 3 0 Sheet 6 12 Sheet 3 30 Tb1 6.2-36 Sheet 7 24 Sheet 4 30 Sheet 1 0 Sheet 8 24 Sheet 5 30 Sheet 2 0 Tbl 6.2-15 Sheet 6 30 Sheet 3 0 Sheet 1 15 Sheet 7 30 Tb1 6.2-37 Sheet 2 15 Sheet 8 30 Sheet 1 33 1 V
') Sheet 3 32 Tb1 6.2-28 Sheet 2 Sheet 3 0
0 Sheet 4 32 Sheet 1 32 Tbl 6.2-16 Sheet 2 33 Tb1 6.2-38 Sheet 1 32 Sheet 3 18 Sheet 1 0 Sheet 2 11 Sheet 4 30 Sheet 2 0 Sheet 3 11 Sheet 5 33 Sheet 3 0 Tb1 6.2-17 Sheet 6 30 Tbl 6.2-39 Sheet 1 32 Sheet 7 30 Sheet 1 0 Sheet 2 32 Sheet 8 30 Sheet 2 0 Sheet 3 32 Sheet 9 30 Sheet 3 0 Sheet 4 32 Sheet 10 30 Tb1 6.2-40 i Sheet 5 12 Sheet 11 30 Sheet 1 0 l Tb1 6.2-18 0 Sheet 12 30 Sheet 2 0 Tb1 6.2-19 Sheet 13 30 Sheet 3 0 l 24 Tb1 6.2-41 Sheet 1 Sheet 14 30 Sheet 2 24 Tb1 6.2-28A Sheet 1 0 Tb1 6.2-20 Sheet 1 30 Sheet 2 0 Sheet 1 24 Sheet 2 33 Sheet 3 0 Sheet 2 24 Sheet 3 30 Tb1 6.2-42 19 Tb1 6.2-21 Sheet 4 30 Tb1 6.2-43 Sheet 1 0 Sheet 5 30 Sheet 1 32 , Sheet 2 0 Sheet 6 30 Sheet 2 32 Tb1 6.2-22 Sheet 7 30 6.2 Fig. Tab Sheet 1 32 Sheet 8 30 Fig. 6.2-1 23 Sheet 2 32 Sheet 9- 33 Fig. 6.2-la 26 LOEP 41 Revision 33 4/81
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MIDLAND 1"J-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Fig. 6.2-2 0 Fig. 6.2-49 0 Fig. 6.2-91 11 Fig. 6.2-3 0 Fig. 6.2-50 0 Fi g . 6.2-92 11 Fig. 6.2-4 0 Fig. 6.2-51 Ftg. 6.2-93 11 Fig. 6.2-5 0 Sheet 1 33 rig. 6.2-94 11 Fig. 6.2-6 0 Sheet 2 33 Fig. 6.2-95 11 Fig. 6.2-7 0 Fig. 6.2-52 Fig. 6.2-96 14 Fig. 6.2-8 0 Sheet 1 33 Fig. 6.2-97 24 Fig. 6.2-9 0 Sheet 2 33 Fig. 6.2-98 11 Fig. 6.2-10 0 Fig. 6.2-53 0 Fig. 6.2-99 11 Fig. 6.2-11 0 Fig. 6.2-54 0 Fig. 6.2-100 11 Fig. 6.2-12 0 Fig. 6.2-55 17 Fig. 6.2-101 11 Fig. 6.2-13 0 Fig. 6.2-56 17 Fig. 6.2-102 11 Fig. 6.2-14 24 Fig. 6.2-57 17 Fig. 6.2-103 11 Fig. 6.2-15 24 Fig. 6.2-58 23 Fig. 6.2-104 11 Fig. 6.2-16 0 Fig. 6.2-58A 26 Fig. 6.2-105 32 Fig. 6.2-17' O Fig. 6.2-59 30 Fig. 6.2-106 11 Fig. 6.2-18 0 Fig. 6.2-60 30 Fig. u.2-107 11 Fig. 6.2-19 24 Fig. 6.2-61 33 Fig. 6.2-108 11 Fig. 6.2-20 24 Fig. 6.2-62 0 Fig. 6.2-109 11 Fig. 6.2-21 12 Fig. 6.2-63 0 Fig. 6.2-110 11 Fig. 6.2-22 0 Fig. 6.2-64 32 Fig. 6.2-111 11 Fig. 6.2-23 11 Fig. 6.2-65 0 Fig. 6.2-112 11 Fig. 6.2-24 11 Fig. 6.2-66 0 Fig. 6.2-113 11 Fig. 6.2-25 11 Fig. 6.2-67 0 Fig. 6.2-114 11 Fig. 6.2-26 11 Fig. 6.2-68 33 Fig. 6.2-115 11 Fig. 6.2-27 11 Fig. 6.2-69 33 Fig. 6.2-116 11 Fig. 6.2-28 11 Fig. 6.2-70 33a Fig. 6.2-117 11 Fig. 6.2-29 11 Fig. 6.2-71 17 Fig. 6.2-118 11 Fig. 6.2-30 11 Fig. 6.2-72 14 Fig. 6.2-119 33 Fig. 6.2-31 11 Fig. 6.2-73 4 Fig. 6.2-120 33 Fig. 6.2-32 0 Fig. 6.2-74 4 Fig. 6.2-121 32 Fig. 6.2-33 0 Fig. 6.2-75 0 Fig. 6.2-122 14 Fig. 6.2-34 0 Fig. 6.2 -76 0 Fig. 6.2-123 14 Fig. 6.2-35 0 Fig. 6.2-77 0 Fig. 6.2-124 14 Fig. 6.2-36 0 Fig. 6.2-78 0 Fig. 6.2-125 14 Fig. 6.2-37 0 Fig. 6.2-79 33 Fig. 6.2-126 14 Fig. 6.2-38 0 Fig. 6.2-80 0 Fig. 6.2-127 14 Fig. 6.2-39 0 Fig. 6.2-81 0 Fig. 6.2-128 14 Fig. 6.2-40 0 Fig. 6.2-82 0 Fig. 6.2-129 14 Fig. 6.2-41 0 Fig. 6.2-83 21 Fig. 6.2-130 14 Fig. 6.2-42 0 Fig. 6.2-84 22 Fig. 6.2-131 14 Fig. 6.2-43 0 Fig. 6.2-85 26 Fig. 6.2-132 14 Fig. 6.2-44 0 Fig. 6.2-86 22 Fig. 6.2-133 14 Fig. 6.2-45 0 Fig. 6.2-87 21 Fig. 6.2-134 14 Fig. 6.2-46 0 Fig. 6.2-88 11 Fig. 6.2-135 20 Fig. 6.2-47 0 Fig. 6.2-89 11 Fig. 6.2-136 19 Fig. 6.2-48 0 Fig. 6.2-90 11 Fig. 6.2-137 24 LOEP- 4:2 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) f Latest Latest Lutest Sheet ID Rev. Sheet ID Rev. Sheet ID - Rev. Fig. 6.2-138 19 6.3-9 30 Sheet 1 17 6.3-10 33 Sheet 2 32 VOLUME 13 6.3-10a 15 Sheet 3 17 6.3-10b 15 Sheet 4 26 i 12 6.3-10c 27 Sheet 5 32 ii 12 6.3-10d 33 Sheet 6 15 iii 21 6.3-11 30 Shtet 7 32 iv 21 6.3 33 Sheet 8 15 v 21 6.3-13 30 Sheet 9 26 vi 21 6.3-14 0 Tbl 6.3-7 32 vii 21 6.3-15 32 Tbl 6.3-8 1 viii 21 6.3-16 21 Tb1 6.3-9 30 ix 21 6.3-17 33 Tb1 6.3-10 30 x 21 6.3-18 15 Tb1 6.3-11 xi 21 6.3-19 30 Sheet 1 32 xii 21 6.3-20 30 Sheet 2 12 xiii 15 6.3-21 15 Sheet 3 32 xiv 21 6.3-22 26 Sheet 4 32 xv 21 6.3-23 26 Tb1 6.3-12 xvi 12 6.3-24 17 Sheet 1 32 xvii 12 6.3-24a 28 Sheet 2 33 xviii 21 6.3-24b 17 Sheet 3 9 67-sI xix 26 6.3-25 15 Tb1 6.3-13 19
\- # xx 26 6.3-26 32 6.3 Fig. Tab xxi 12 6.3-27 30 Fig. 6.3-1 xxii 26 6.3-28 15 Sheet 1 27 xxiii 26 6.3-29 28 Sheet 2 27 xxiv 26 6.3-30 33 Fig. 6.3-2 27 xxv 26 6.3-31 15 Fig. 6.3-3 32 xxvi 26 6.3-32 15 Fig. 6.3-4 0 xxvii 26 6.3-33 33 Fig. 6.3-5 32 xxviii 26 6.3-34 15 Fig. 6.3-6 15 xxix 26 6.3 Tbl Tab 6.4 Tab xxx 26 Tbl 6.3-1 6.4-1 0 xxxi 26 Sheet 1 9 6.4-2 33 xxxii 26 Sheet 2 26 6.4-3 32 6.3 Tab Sheet 3 32 6.4-4 33 6.3-1 3 Sheet 4 9 6.4-4a 3 6.3-2 3 Sheet 5 30 6.4-4b 0 6.3-3 0 Tb1 6.3-2 6.4-5 0 6.3-4 0 Sheet 1 30 6.4-6 32 6.3-5 33 Sheet 2 30 6.4-7 32 6.3-6 15 Sheet 3 30 6.4-8 33 6.3-6a 15 Tb1 6.3-3 30 6.4-8a 15 6.3-6b 15 Tb1 6.3-4 32 6.4-8b 0 6.3-7 0 Tb1 6.3-5 33 6.4-9 0 6.3-8 3 Tb1 6.3-6 6.4-10 33 r-( ,/ LOEP- 43 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. 6.4 Tbl Tab 6.8-7 30 6B-31 3 Tbl 6.4-1 33 6.8 Tb1 Tab 6B-32 3 Tb1 6.4-2 0 Tb1 6.8-1 30 6B-33 33 Tb1 6.4-3 6.8 Fig. Tab 6B-34 3 Sheet 1 33 Fig. 6.8-1 20 6B-35 3 Sheet 2 33 Fig. 6.8-2 20 6B-36 3 6.4 Fig. Tab Fig. 6.8-3 32 6B-37 3 Fig. 6.4-1 32 Fig. 6.8-4 28 6B-38 3 Fig. 6.4-2 21 Fig. 6.8-5 28 6B-39 3 Fig. 6.4-3 26 Fig. 6.8-6 32 6B-40 33 Fig. 6.4-4 33 Fig. 6.8-7 28 6B-41 33 6.5 Tab Fig. 6.8-8 28 Tb1 6B-1 3 6.5-1 33 App 6A Tab Tb1 6B-2 3 6.5-2 33 Deleted 14 Tb1 6B-3 3 6.5-3 14 App 6B Tab Tbl 6B-4 30 6.5-4 33 6B-1 3 Tb1 6B-5 6.5-5 14 6B-2 33 Sheet 1 3 6.5-6 14 6B-3 3 Sheet 2 3 6.5-7 33 6B-4 3 Tb1 6B-6 6.5-8 33 6B-5 3 Sheet 1 3 6.5-9 29 6B-6 3 Sheet 2 3 6.5-10 14 6B-7 3 Tb1 6B-7 3 6.5-11 14 6B-8 3 Tbl 6B-8 3 6.5-12 14 6B-9 3 Tb1 6B-9 3 6.5 Tbl Tab 6B-10 3 Tbl 6B-10 3 Tb1 6.5-1 0 6B-11 33 Tbl 6B-11 3 Tb1 6.5-2 6B 12 30 Tbl 6B-12 3 Sheet 1 32 6B-13 33 Tb1 6B-13 3 Sheet 2 27 6B-14 30 Tbl 6B-14 3 Tb1 6.5-3 17 6B-15 33 Tbl 6B-15 3 Tbl 6.5-4 17 6B-16 33 Tbl CB-16 3 Tb1 6.5-5 32 63-16a 33 Fig. 6B-1 3 6.5 Fig. Tab 6B-16b 30 Fig. 6B-2 3 Fig. 6.5-1 21 6B-17 3 Fig. 6B-3 3 Fig. 6.5-2 20 6B-18 33 Fig. 6B-4 3 6.6 Tab 6B-19 3 Fig. 6B-5 3 6.6-1 28 6B-20 33 Fig. 6B-6 3 6.6-2 28 6B-21 33 Fig. 6B-7 3 6.7 Tab 6B-22 33 Fig. 6B-8 3 6.7-1 0 6B-23 33 Fig. 6B-9 3 6.8 Tab 6B-24 3 Fig. 6B-10 3 6.6-1 33 6B-25 33 Fig. 6B-11 3 6.8-2 33 6B-26 3 Fig. 6B-12 3 6.8-3 33 6B-27 33 Fig. 6B-13 3 6.8-4 30 6B-28 3 Fig. 6B-14 3 6.8-5 33 6B-29 3 Fig. 6B-15 3 6.8-6 33 6B-30 3 Fig. 6B-16 3 LOEP- 4 4 Revision 33 4/81
MIDLAND 1&2-FSAP LIST OF EFFECTIVE Po_4S (continued) O
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Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Fig. 6B-17 3 Tbl GD-12 32 Fig. 6E-8 26 Fig. 6B-18 3 Fig. 6D-1 32 . Fig. 6E-9 26 Fig. 6B-19 3 Fig. 6D-2 8 Fig. 6E-10 26 Fig. 6B-20 3 Fig. 6D-3 P Fig. 6E-11 H26 Fig. oB-21 3 Fig. 6D-4 8 . Fig. 6E-12 26 Fig. 6B-22 3 Fig. 6D-5 8 Fig. 6E-13 26 i App 6C Tab Fig. 6D-6 19 Fig. 6E-14 26 6C-1 28 Fig. 6D-7 19 Fig. 6E-15 26 6C-2 28 Fig. 6D-8 19 Fig. 6E-16 26 6C-3 3 Fig. 6D-9 19 Fig. 6E-17 26 6C-4 28 Fig. 6D-9A 22 Fig. 6E-18 26 6C-5 3 Fig. 6D-10 22 Fig. 6E-19 26 App 6D Tab Fig. 6D-ll 32 Fig. 6E-20 26 6D-1 33 Fig. 6D-12 32 Fig. 6E-21 26 6D-2 22 Fig. 6D-13 32 Fig. 6E-22 26 Tbl 6D-1 8 Fig. 6D-14 32 Fig. 6E-23 26 Tbl 6D-2 8 Fig. 6D-15 32 Fig. 6E-24 26 Tb1 6D-3 Fig. 6D-16 32 Fig. 6E-25 26 Sheet 1 32 Fig. 6D-17 32 Fig. 6E-26 26 Sheet 2 8 Fig. 6D-18 32 Fig. 6E-27 26 Tb1 6D-4 Fig. 6D-19 33 Fig. 6E-28 26 Sheet 1 32 Fig. 6D-20 32 Fig. 6E-29 26 26 [/)
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Sheet 2 Tb1 6D-5 Sheet 1 8 8 App 6E Tab 6E-1 6E-2 33 28 fig. Fig. Fig. 6E-30 6E-31 6E-32 26 26 Sheet 2 32 6E-3 26 Fig. 6E-33 26 Tb1 C~s-6 6E-4 26 Fig. 6E-34 26 Sheet 1 32 6E-5 26 Fig. 6E-35 26' Sheet 2 32 Tb1 6E-1 26 Fig. SE-36 26 Tb1 6D-7 Tb1 6E-2 Fig. 6E-37 26 Sheet 1 32 Sheet 1 22 Fig. 6E-38 26 Sheet 2 3? Sheet 2 21 Fig. 6E-39 26 Tbl 6D-8 Tbl 6E-3 17 Fig. 6E-40 26 Sheet 1 22 Tb1 6E-4 26 Fig. 6E-4'1 26 Sheet 2 22 Tb1 6E-5 26 Fig. 6E-42 26 Tb1 6D-9 Tbl 6E-6 26 Fig. 6E-43 26 Sheet 1 32 Tb1 6E-7 26 fig. 6E-44 26 Sheet 2 32 Tb1 6E-8 26 Fig. 6E-45 26 Sheet 3 32 Tbl 6E-9 26 Tb1 6D-10 Tbl 6E-10 33 VOLUME 14 Sheet 1 32 Fig. 6E-1 22 Sheet 2 32 Fig. 6E-2 22 i 12 Sheet 3 32 Fig. 6E-3 22 ii 12 Tb1 6D-ll Fig. 6E-4 22 iii 32 Sheet 1 32 Fig. 6E-5 28 iv 21 Sheet 2 32 Fig. 6E-6 28 v 21 Sheet 3 32 Fig. 6E-7 22 vi 21 (O) LOEP- 45 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. vii 21 7.1-9 33 7.2-26 33 viii 21 7.1-10 33 7.2-27 33 ix 21 7.1-11 33 7.2-28 33 x 21 7.1-12 33 7.2-29 33 xi 21 7.1-13 33 7.2-30 33 xii 21 7.1-14 33 7.2 Tb1 Tab xiii 15 7.1-15 33 Tb1 7.2-1 xiv 21 7.1-16 33 Sheet 1 0 xv 21 7.1-17 33 Sheet 2 0 xvi 12 7.1 Tb1 Tab Tb1 7.2-2 32 xvii 12 Tbl 7.1-1 Tb1 7.2-3 32 xviii 21 Sheet 1 33 Tb1 7.2-4 13 xix 26 Sheet 2 33 Tb1 7.2-5 13 xx 26 Sheet 3 33 7.2 Fig. Tab xxi 12 Tb1 7.1-2 21 Fig. 7.2-1 0 xxii 26 Tb1 7.1-3 Fig. 7.2-2 0 xxiii 26 Sheet 1 33 Fig. 7.2-3 0 xxiv 26 Sheet 2 33 Fig. 7.2-4 16 xxv 26 Sheet 3 33 Fig. 7.2-5 18 xxvi 26 7.1 Fig Tab 7.3 Tab xxvii 26 Fig 7.1-1 15 7.3-1 33 xxviii 26 7.2 Tab 7.3-2 33 xxix 26 7.2-1 33 7.3-3 33 xxx 26 7.2-2 33 7.3-4 33 xxxi 26 7.2-3 33 7.3-5 33 xxxii 26 7.2-4 33 7.3-6 33 Chapter 7 Tab 7.2-5 33 7.3-7 33 7-i 33 7.2-6 33 7.3-8 33 7-ii 33 7.2-7 33 7.3-9 33 7-iii 33 7.2-8 33 7.3-10 33 7-iv 33 7.2-9 33 7.3-11 33 7-iva 33 7.2-10 33 7.3-12 33 7-ivb 33 7.2-11 33 7.3-13 33 7-v 30 7.2-12 33 7.3-14 33 7-vi 30 7.2-13 33 7.3-15 33 7-vii 28 7.2-14 33 7.3-16 33 7-viii 33 7.2-15 33 7.3-17 33 7-ix 30 7.2-16 33 7.3-18 33 7.1 Tab 7.2-17 33 7.3-19 33 7.1-1 33 7.2-18 33 7.3-20 33 7.1-2 33 7.2-19 33 7.3 ~. 33 7.1-3 33 7.2-20 33 7.3 22 33 7.1-4 33 7.2-21 33 7.3-23 33 7.1-5 33 7.2-22 33 7.3-24 33 7.1-6 33 7.2-23 33 7.3-25 33 7.1-7 33 7.2-24 33 7.3-26 33 7.1-8 33 7.2-25 33 7.3-27 33 LOEP- 4 6 Revision 33 h 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) f jh
" Latest Latest Latest-Sheet ID Rev. Sheet ID Rev. Sheet ID Rev.
7.3 33 Tb1 7.3-4 32 7.4-22 '33 7.3-29 33 Tb1 7.3-5 7.4-23 33' 7.3-30 33 Sheet 1 32 7.4-24 33 7.3-31 33 Sheet 2 32 7.4-25 33 7.3-32 33 , Sheet 3 32 7.4-26 33-7.3-33 33 Sheet 4 32 7.4-27 33 7.3-34 33 Sheet 5 32 7.4-28 -33 7.~3-35 33 Sheet 6 12 -7.4-29 33 7.3-36 33 Sheet 7 12 :7.4-30 33 7.3-37 33 Sheet 8 12 7.4-31 33 7.3-38 33 Sheet '. 12 7.4-32 33 7.3-39 33 Sheet 10 32 7.4 Tbl Tab 7.3-40 33 Sheet 11 32 Tb1 7.4-1 7.3-41 33 Tb1 7.3-6 30 Sheet l' 30 7.3-42 33 7.3 Fig. Tab Sheet 2 30 7.3-43 33 Fig. 7.3-1 33 Tb1 7.4 30 7.3-44 33 Fig. 7.3-2 32 Tb1 7.4-3 30 7.3-45 33 . Fig. 7.3-3 30 7.4 Fig. Tab 7.3-46 33 Fig. 7.3-4 30 Fig. 7.4-1 0 7,3-47 33 Fig. 7.3-5 25 7.5 Tab. . 7.3 Tb1 Tab Fig. 7.3-6 25 7.5-1 33 Tbl 7.3-1 ~2 Fig. 7.3-7 19 7.5-2 33
- / Tb1 7.3-2 Fig. 7.3-8 30 7.5-3 33 k -) Sheet 1 33 Fig. 7.3-9 30 7.5-4 33 Sheet 2 32 Fig. 7.3-10 33 7.5-5 33 Sheet 3 32. 7.4 Tab 7.5-6 33 Tb1 7.3-3 7.4-1 33 7.5-7 33 Sheet 1 32 7.4-2 33 7.5-8 33 Sheet 2 32 7.4-3 33 7.5-9 33 Sheet 3 32 7.4-4 33 7.5-10 33 Sheet 4 32 7.4-5 33 7.5-11 33 Sheet 5 30 7.4-6 33 7.5 Tb1 Tab Sheet 6 32 7.4-7 33 Tb1 7.5-1 Sheet 6a 30 7.4-8 33 Sheet 1 30 SheJ. 6b 32 7.4-9 33 Sheet 2 30 Sheet 7 32 7.4-10 33 Sheet 3 33 Sheet 8 32 7.4-11 33 Sheet 4 30.
Sheet 9 33 7.4-12 33 Sheet 5 30 Sheet 10 30 7.4-13 33 Tb1 7.5-2 3heet 11 32 7.4-14 33 Sheet 1 33 Sheet 12 32 7.4-15 33 Sheet 2 33 Sheet 13 14 7.4-16 33 Tb1 7.5-3 Sheet 14 32 7.4-17 33 Sheet-1 33 Sheet 15 32 7.4-18 33 Sheet 2 33 Sheet 16 32 7.4-19 33 Sheet 3 33 Sheet 17 32 7.4-20 33 Sheet 4 33 Sheet 18 32 7.4-21 33 7.6 Tab () LOEP 47 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. , Sheet ID Rev. 7.6-1 33 7.7-30 33 Sheet 3 13 7.6-2 33 7.7 Tb1 Tab Sheet 4 13 7.6-3 33 Tb1 7.7-1 Tbl 7A-2 7.6-4 33 Sheet 1 0 Sheet 1 13 7.6-5 33 Sheet 2 10 Sheet 2 , 13 7.6-6 33 Sheec 3 10 Sheet 3 13 7.6-7 33 Tb1 7.7-2 Sheet 4 13 7.6-8 33 Sheet 1 33 Sheet 5 21 ' 7.6-9 33 Sheet 2 33 Sheet 6 13 7.6-10 33 Sheet 3 27 Tb1 7A-3 7.6-11 33 Tb1 7.7-3 30 Sheet 1 13 7.6-12 33 7.7 Fig. Tab Sheet 2 13 7.6-13 33 Fig. 7.7-1 0 Sheet 3 13 7.7 Tab Fig. 7.7-2 0 Sheet 4 13 7.7-1 18 Fig. 7.7-3 0 Sheet 5 13 7.7-2 26 Fig. 7.7-4 0 Fig. 7A-1 14 7.7-2a 2 Fig. 7.7-5 3 Fig. 7A-2 30 7.7-2b 30 Fig. 7.7-6 0 Fig. 7A-3 30 7.7-3 0 Fig. 7.7-7 0 Chapter 8 Tab 7.7-4 0 Fig. 7.7-8 27 8-i 18 7.7-5 30 Fig. 7.7-9 27 8-ii 33 7.7-6 0 Fig. 7.7-10 27 8-iii 33 7.7-7 0 Fig. 7.7-11 30 8-iv 19 7.7-8 0 Fig. 7.7-12 30 8-v 33 7.7-9 30 7.8 Tab 8-vi 33 7.7-10 30 7.8-1 2 8-vii 33 7.7-11 26 7.8-2 2 0-viii 33 7.7-12 0 7.8-2a 2 8.1 Tab 7.7-13 3 7.8-2b 30 8.1-1 30 l 7.7-14 3 7.8-3 33 8.1-2 32 7.7-14a 3 7.8-4 30 0 8.1-3 7.7-14b 3 7.8-5 30 8.1-4 33 7.7-15 0 7.8-6 0 8.1-5 33 ! 7.7-16 0 7.8-7 0 8.1-6 33 l 7.7-17 0 7.8 Fig. Tab 8.1-7 33 7.7-18 0 Fig. 7.8-1 2 8.1-8 33 7.7-19 0 Fig. 7.8-2 0 8.1-9 33 7.7-20 0 Fig. 7.8-3 0 8.1-10 33 7.7-21 27 Fig. 7.8-4 0 8.1-10a 2 7.7-22 0 Fig. 7.u-5 2 8.1-10b 25 ( 7.7-23 32 App 7A Tab 8.1-11 32 30 14 7.7-24 7A-1 8.1-12 32 7.7-25 30 7A-2 30 8.1-13 32 7.7-26 30 7A-3 14 8.1 Fig. Tab 7.7-27 33 Tbl 7A-1 Fig. 8.1-1 0 l 7.7-28 33 Sheet ~. 13 8.2 Tab 7.7-29 33 Sheet 2 30 8.2-1 10 l LCEP 48 Revision 33 4/81 l
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) f\ b Latest Latest Latest Sheet ID Rev. Sheet ID -Rev. Sheet ID Rev. 8.2-2 32 8.3-14 32 8.3-39 33 8.2-3 32 8.3-15 32 8.3-40 33 8.2-4 24 8.3-16 33 8.3-41 0-8.2-5 19 8.3-16a 33 8.3-42 0 8.2-6 19 8.3-16b 18 8.3-43 0 i 8.2-7 33 8.3-16c 28 8.3-44 15 8.2-8 27 8.3-16d 8 8.3-45 33 8.2-9 30 8.3-17 33 8.3-46 33 8.2 Fig. Tab 8.3-18 32 8.3-47 33 Fig. 8.2-1 33 8.3-19 32 8.3-48 33 Fig. 8.2-2 33 8.3-20 32 8.3-49 30 Fig. 8.2-3 0 8.3-20a 33 8.3-50 30 Fig. 8.2-4 0 8.3-20b 33 8.3-51 18 Fig. 8.2-5 3 8.3-21 3 8.3 Tb1 Tab Fig. 8.2-6 3 8.3-22 26 Tb1 8.3-1 Fig. 8.2-7 3 8.3-22a 3 Sheet 1 30 Fig. 8 . 2--8 3 8,3-22b 3 Sheet 2 33 Fig. 8.2-9 33 8.3-23 0 Sheet 3 33 Fig. 8.2-10 33 8.3-24 33 Sheet 4 33 Fig. 8.2-11 16 8.3-25 33 Sheet 5 33 Fig. 8.2-12 33 8.3-26 20 Sheet 6 33 8.3 Tab 8.3-26a 20 Sheet 7 33 [2
'x-h 8.3-1 8.3-2 0
33 8.3-26b 8.3-26c 8.3-26d 30 30 33 Sheet 8 Sheet 9 Sheet 10 33 33 33 8.3-2a 32 8.3-2b 32 8.3-27 33 Sheet 11 33 t 8.3-3 18 8.3-28 33 Sheet 12 33 l 8.3-4 33 8.3-28a 15 Sheet 13 33 ! 8.3-5 33 8.3-28b 13 Sheet 14 33 ! 8.3-6 33 8.3-29 33 Sheet 15 33 8.3-7 33 8.3-30 33 Tb1 8.3-2 8.3-8 33 8.3-31 33 Sheet 1 28 8.3-8a 33 8.3-32 0 Sheet 2 32 8.3-8b 33 8.3-33 10 Sheet 3 28 8.3-9 18 8.3-34 15 Sheet 4 28 8.3-10 18 8.3-35 33 Sheet 5 28 8.3-11 33 8.3-36 33 Sheet 6 32 8.3-12 33 8.3-36a 33 Tb1 8.3-3 8.3-12a 33 8.3-36b 33 Sheet 1 33 8.3-12b 33 8.3-36c 33 Sheet 2 32 8.3-12c 24 8.3-36d 33 Sheet 3 28 8.3-12d 24 8.3-36e 32 Sheet 4 28 8.3-12e 33 8.3-36f 27 Sheet 5 33 8.3-12f 33 8.3-37 33 Sheet 6 33 8.3-12g 24 8.3-38 27 Sheet 7 30 8.3-12h 24 8.3-38a 27 Sheet 8 30 8.3-13 1 8.3-38b 27 Tb1 8.3-4 14 s / LOEP 49 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet 10 Rev. Sheet ID _Rev. Sheet ID Rev. Tb1 8.3-5 Fig. 8.3-21 20 8A-4 0 Sheet 1 14 Fig. 8.3-22 20 8A-5 0 Sheet 2 14 Fig. 8.3-23 20 Tbl 8.3-6 19 Fig. 8.3-24 20 VOLUME 15 Tbl 8.3-7 27 Fig. 8.3-25 20 Tb1 8.3-8 0 Fig. 8.3-25A 30 i 12 Tb1 8.3-9 0 Fig. 8.3-26 30 ii 12 Tb1 8.3-10 0 Fig. 8.3-27 30 iii 21 Tb1 8.3-11 Fig. 8.3-28 33 iv 21 Sheet 1 18 Fig. 8.3-29 33 y 21 Sheet 2 33 Fig. 8.3-29A 33 vi 21 Tb1 8.3-12 33 Fig. 8.3-29B 33 vii 21 Tb1 8.3-13 30 Fig. 8.3-29C 33 viii 21 Tbl 8.3-14 33 Fig. 8.3-29D 33 ix 21 Tb1 8.3-15 33 Fig. 8.3-29E 33 x 21 8.3 Fig. Tab Fig. 8.3-29F 33 xi 21 Fig. 8.3-1 30 Fig. 8.3-30 33 xii 21 Fig. 8.3-2 Fig. 8.3-31 33 xiii 15 Sheet 1 33 Fig. 8.3-32 0 xiv 21 Sheet 2 33 Fig. 8.3-32A 333 xy 21 Fig. 8.3-3 Fig. 8.3-33 24 xvi 12 Sheet 1 33 Fig. 8.3-34 24 xvii 12 Sheet 2 33 Fig. 8.3-35 24 xviii 21 Fig. 8.3-4 Fig. 8.3-36 24 xix 26 Sheet 1 27 Fig. 8.3-37 32 xx 26 Sheet 2 27 Fig. 8.3-38 0 xxi 12 Fig. 8.3-5 25 Fig. 8.3-39 29 xxil 26 Fig. 8.3-6 0 Fig. 8.3-40 29 xxiii 26 Fig. 8.3-7 20 Fig. 8.3-41 33 xxiv 26 Fig. 8.3-8 20 Fig. 8.3-42 33 xxy 26 Fig. 8.3-8a 20 Fig. 8.3-43 18 xxvi 26 Fig. 8.3-8b 20 Fig. 8.3-44 18 xxvii 26 Fig. 8.3-8c 30 Fig. 8.3-45 33 xxviii 26 Fig. 8.3-8d 23 Fig. 8.3-46 33 xxix 26 Fig. 8.3-9 30 Fig. 8.3-47 33 xxx 26 Fig. 8.3-10 30 Fig. 8.3-48 33 xxxi 26 Fig. 8.3-11 20 Fig. 8.3-49 33 xxxii 26 Fig. 8.3-12 30 Fig. 8.3-50 33 Chapter 9 Tab Fig. 8.3-13 30 Fig. 8.3-51 33 9-i 16 Fig. 8.3-14 30 Fig. 8.3-52 33 9-ii 30 Fig. 8.3-15 30 Fig. 8.3-53 33 9-iii 32 Fig. 8.3-15A 30 Fig. 8.3-54 26 9-iv 30 Fig. 8.3-16 30 Fig. 8.3-55 33 9-v 32 Fig. 8.3-17 30 App 8A Tab 9-vi 32 Fig. 8.3-10 30 8A-1 0 9-via 30 Fig. 8.3-19 0 8A-2 0 9-vib 30 Fig. 8.S-20 30 8A-3 0 9-vii 30 LGEP- 50 Revision 33 4/81
MIDLAND 1&2-FSAR I LIST OF EFFECTIVE PAGES (continued) O Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. 9-viii 30 9.1-20 0 Sheet 3 33 9-ix 30 9.1-21 0 Sheet 4 33 9-x 15 9.1-22 0 9.1 Fig. Tab 9-xi 26 9.1-23 0 Fig. 9.1-1 9-xii 30 9,1-24 0 Sheet 1 30 9-xiii 30 ~ 9.1-25 O Sheet 2 32 9-xiv 30 9.1-26 0 Fig. 9.1-2 0 9-xv 30 9.1-27 0 Fig. 9.1-3 0 9-xvi 30 9.1-28 0 Fig. 9.1-4 0 9-xvil 27 9.1-29 0 Fig. 9.1-5 0 l 9-xviii 27 9.1-30 0 Fig. 9.1-6 0 l 9-xix 27 9.1-31 0 Fig. 9.1-7 0 9-xx 26 9.1-32 0 Fig. 9.1-8 0 9-xxi 30 9.1-33 -0 Fig. 9.1-9 0 9-xxii 27 9.1-34 0 Fig. 9.1-10 0 9-xxiii 29 9.1-35 9 Fig. 9.1-11 17 9-xxiv 26 9.1-36 9 Fig. 9.1-12 17 9-xxv 25 9.1-37 9 Fig. 9.1-13 17 9-xxvi 25 9.1-38 33 Fig. 9.1-14 ' 14 9.1 Tab 9.1-39 33 Fig. 9.1-15 32 9.1-1 33 9.1-40 18 Fig. 9.1-16 19
- 9.1-2 33 9.1-41 16 9.2 Tab 9.1-3 33 9.1-42 16 9.2-1 33 (s - 9.1-4 33 9.1-43 16 9.2-2 33 9.1-4a 33 9.1-44 33 9.2-3 33
- 9.1-4b 33 9.1 Tbl Tab 9.2-4 30 1 9.1-5 15 Tbl 9.1-1 32 9.2-5 30
! 9.1-6 33 Tb1 9.1-2 9.2-6 30 9.1-7 33 Sheet 1 17 9.2-7 30 l 9.1-8 32 Sheet 2 17 9.2-8 30 9.1-8a 27 Tbl 9.1-3 0 9.2-9 33 9.1-8b 27 Tb1 9.1-4 0 9.2-10 33 9.1-9 27 Tb1 9.1-5 3 9.2-11 33 9.1-10 32 Tbl 9.1-6 0 9.2-12 33 9.1-10a 32 Tb1 9.1-7 9.2-13 30 9.1-10b 33 Sheet 1 0 9.2-14 30 9.1-11 33 Sheet 2 0 9.2-15 30 9.1-12 33 Sheet 3 0 9.2-16 30 l 9.1-13 33 Sheet 4 0 9.2-17 33 l 9.1-14 33 Tbl 9.1-8 3 9.2-18 33 9.1-15 33 Tb1 9.1-9 9.2-19 33 9.1-16 33 Sheet 1 18 9.2-20 33 9.1-16a 29 Sheet 2 18 9.2-21 33 9.1-16b 2 Sheet 3 18 9.2-22 30 0.1-17 17 Tbl 9.1-10 9.2-23 33 9.1-18 0 Sheet 1 30 9.2-24 30 9.1-19 0 Sheet 2 33 9.2-25 33
) LOEP-51 Revision 33 4/81
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MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Shect ID_ Rev. Sheet ID Rev. Sheet ID Rev. 9.2-26 33 Tb1 9.2-1 30 Tb1 9.2-25 9.2-27 33 Tbl 9.2-2 30 Sheet 1 30 9.2-28 33 Tbl 9.2-3 Sheet 2 30 9.2-29 33 Sheet 1 30 sheet 3 33 9.2-30 33 Sheet 2 30 Sheet 4 30 9.3-30a 33 Tbl 9.2-4 Sheet 5 30 9.3-30b 33 Sheet 1 30 Tbl 9.2-26 9.2-31 33 Sheet 2 30 Sheet 1 27 9.2-32 30 Tbl 9.2-5 Sheet 2 27 9.2-32a 30 3heet 1 30 sheet 3 27 9.2-32b 33 Sheet 2 30 Tb1 9.2-27 27 9.2-32c 30 Tb1 9.2-6 30 Tb1 9.2-28 3 9.2-32d 30 Tb1 9.2-7 30 Tbl 9 2-29 9.2-32e 30 Tb1 9.2-8 Sheet 1 3 9.2-32f 33 Sheet 1 33 Sheet 2 3 9.2-32g 33 Sheet 2 30 Tb1 9.2-30 30 9.2-3;h 33 Tb1 9.2-9 9.2 Fig. Tab 9.2-33 33 Sheet 1 33 Fig. 9.2-1 0 9.2-34 33 Sheet 2 30 Fig. 9.2-2 9.2-35 33 Sheet 3 30 Sheet 1 32 9.2-36 33 Sheet 4 30 Sheet 2 32 9.2-37 33 Sheet 5 30 Fig. 9.2-3 9.2-38 33 Tb1 9.2-10 Sheet 1 33 9.2-39 33 Sheet 1 0 Sheet 2 33 9.2-40 33 Sheet 2 0 Fig. 9.2-4 9.2-41 33 Tb1 9.2-11 32 Sheet 1 33 9.2-42 33 Tbl 9.2-12 Sheet 2 28 9.2-43 33 Sheet 1 0 Fig. 9.2-5 28 9.2-44 33 Sheet 2 0 Fig. 9.2-6 30 9.2-44a 33 Tb1 9.2-13 30 Fig. 9.2-7 9.2-44b 33 Tbl 9.2-14 O Sheet 1 33 9.2-45 32 Tb1 9.2-15 0 Sheet 2 33 9.2 32 Tbl 9.2-16 0 Fig. 9.2-8 , 9.2-47 32 Tb1 9.2-17 Sheet 1 30 ! 9.2-48 33 Sheet 1 0 Sheet 2 30 9.2-49 32 Sheet 2 0 Fig. 9.2-9 9.2-50 30 Sheet 3 0 Sheet 1 33 9.2-51 30 Sheet 4 0 Sheet 2 33 9.2-52 30 Tbl 9.2-18 Fig. 9.2-10 l 9.2-53 30 Sheet 1 3 Sheet 1 30 i 9.2-54 30 Sheet 2 7 Sheet 2 30 9.2-55 30 Tbl 9.2-19 23 Fig. 9.2-11 9.2-56 30 Tb1 9.2-20 32 Sheet 1 29 9.2-57 33 Tb1 9.2-21 32 Sheet 2 29 9.2-58 30 Tb1 9.2-22 32 Sheet 3 29 9.2-59 33 Tbl 9.2-23 0 Fig. 9.2-12 9.2 Tbl Tab Tbl 9.2-24 30 Sheet 1 29 i LOEP- 52 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) O Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. , Sheet 2 29 9.3-16 0 9.3-55 32 32 Sheet 3 33 9.3-17 0 9.3-56 Sheet 4 33 9.3-18 14 9.3-57 32 Fig. 9.2-13 12 9.3-19 28 9.3-58 32 Fig. 9.2-14 3 9.3-20' 28 9.3-59 32 Fig. 9.2-15 3 9.3-21 28 9.3-60 32 Fig. 9.2-16 12 9.3-22 28 9.3-61 32 Fig. 9.2-17 12 9.3-23 ~28 9.3-62 33 Fig. 9.2-18 9.3-24 28 9.3-63 32~ Sheet 1 33 9.3-25 33 9.3-64 33 Sheet 2 33 9.3-26 30 9.3-64a 33 Fig. 9.2-19 33 9.3-26a 30 9.3-64b 32 Fig. 9.2-20 9.3-26b 30 9.3-65 30 Sheet 1 28 9.3-27 32 9.3-66 33 Sheet 2 28 9.3-28 0 9.3-67 33 Fig. 9.2-21 9.3-29 33 9.3-68 30 Sheet 1 29 9.3-30 0 9.3 Tb1 Tab Sheet 2 27 9.3-31 0 Tb1 9.3-1 Fig. 9.2-22 9.3-32 0 Sheet 1 32 Sheet 1 28 9.3-33 3 Sheet 2 9 Sheet 2 27 9.3-34 0 Sheet 3 9 Fig. 9.2-23 3G 9.3-35 0 Sheet 4 30 I_J
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Fig. 9.2-24 Sheet 1 29 9.3-36 9.3-37 32 33 Tb1 9.3-2 Tb1 9.3-3 19 Sheet 2 30 9.3-38 33 Sheet 1 30 Fig. 9.2-25 9.3-38a 33 Sheet 2 17 Sheet 1 33 9.3-38b 33 Tb1 9.3-4 0 Sheet 2 29 9.3-39 32 Tb1 9.3-5 0 Fig. 9.2-26 3 9.3-40 33 Tb1 9.3-6 9.3 Tab 9.3-41 33 Sheet 1 32 9.3-1 3 9.3-42 33 Sheet 2 32 9.3-2 30 9.3-42a 33 Tb1 9.3-7 9.3-3 30 9.3-42b 33 Sheet 1 32 9.3-4 30 9.3-43 32 Sheet 2 0 9.3-5 30 9.3-44 0 Sheet 3 0 9.3-6 0 9.3-45 29 Sheet 4 32 9.3-7 19 9.3-46 29 Sheet 5 32 9.3-8 33 9.3-47 28 Sheet 6 0 9.3-8a 26 9.3-48 0 Sheet 7 0 9.3-8b 22 9.3-49 29 Sheet 8 32 9.3-9 19 9.3-50 29 Sheet 9 32 9.3-10 0 9.3-50a 28 Tb1 9.3-8 32 9.3-11 0 9.3-50b 3 Tb1 9.3-9 9.3-12 30 9.3-51 32 Sheet 1 33 9.3-13 30 9.3-52 32 Sheet 2 33 9.3-14 30 9.3-53 32 Tbl 9.3-10 9.3-15 0 9.3-54 32 Sheet 1 0
) LOEP- 53 ' Revision 33 4/81
MIDLAND 1&2-FSAR , 1 LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Sheet 2 0 Fig. 9.3-32 ix 21 Sheet 3 28 Sheet 1 33 x 21 Tb1 9.3-11 Sheet 2 32 xi 21 Sheet 1 32 Fig. 9.3-33 xii 21 Sheet 2 33 Sheet 1 33 xiii 15 Sheet 3 32 Sheet 2 33 xiv 21 Tb1 9.3-12 0 Fig. 9.3-34 xv 21 Tb1 9.3-13 0 Sheet 1 33 xvi 12 Tb1 9.3-14 9 Sheet 2 32 xvii 12 Tb1 9.3-15 14 Fig. 9.3-35 32 xviii 21 Tb1 9.3-16 30 Fig. 9.3-36 xix 26 9.3 Fig. Tab Sheet 1 32 xx 26 Fig. 9.3-1 28 Sheet 2 32 xxi 12 Fig. 9.3-2 32 Fig. 9.3-37 xxii 26 Fig. 9.3-3 30 Sheet 1 32 xxiii 26 Fig. 9.3-4 30 Sheet 2 27 xxiv 26 Fig. 9.3-5 30 Fig. 9.3-38 xxv 26 Fig. 9.3-6 30 Sheet 1 29 xxvi 26 Fig. 9.3-7 32 Sheet 2 32 xxvii 26 Fig. 9.3-8 32 Fig. 9.3-39 26 xxviii 25 Fig. 9.3-9 32 Fig. 9.3-40 x).ix 26 Fig. 9.3.-10 32 Sheet 1 33 xxx 26 Fig. 9.3-11 32 Sheet 2 33 xxxi 26 Fig. 9.3-12 32 Sheet 3 33 xxxii 26 Fig. 9.3-13 32 Fig. 9.3-41 9.4 Tab Fig. 9.3-14 32 Sheet 1 33 9.4-1 3 Fig. 9.3-15 24 Sheet 2 33 9.4-2 33 Fi9 9.3-15 24 Fig. 9.3-42 33 9.4-3 3 Fig. 9.3-17 Fig. 9.3-43 9.4-4 33 Sheet 1 28 Sheet 1 33 9.4-5 33 Sheet 2 28 Sheet 2 33 9.4-6 33 Fig. 9.3-18 27 Fig. 9.3-44 0 9.4-7 33 Fig. 9.3-19 27 Fig. 9.3-45 9.4-8 33 Fig. 9.3-20 0 Sheet 1 32 9.4-8a 33 Fig. 9.3-21 0 Sheet 2 32 9.4-8b 2 Fig. 9.3-22 0 Fig. 9.3-46 30 9.4-9 8 Fig. 9.3-23 0 9.4-10 30 Fig. 9.3-24 0 VOLUME 16 9.4-11 30 Fig. 9.3-25 0 9.4-12 30 Fig. 9.3-26 0 i 12 9.4-13 30 Fig. 9.3-27 0 ii 12 9.4-14 30 Fig. 9.3-28 0 iii 21 9.4-14a 33 Fig. 9.3-29 14 iv 21 9.4-14b 30 , Fig. 9.3-30 0 v 21 9.4-15 30 Fig. 9.3-31 vi 21 9.4-16 32 Sheet 1 33 vii 21 9.4-17 32 Sheet 2 33 viii 21 9.4-18 32 LOEP- 54 Revision 33 h 4/81 l
. MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) h-V Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev.
9.4-18a 32 9.4-56 33 .Tb1 9.4-14 9.4-18b 32 9.4-57 33 Sheet 1 30 9.4-19 23 9.4-58 33 Sheet 2 30 9.4-20 0 9.4-59 33 Sheet 3 30 9.4-21 27 9.4-60 30 Sheet 4 30 9.4-22 0 9.4-61 30 Sheet 5 30 9.4-23 33 .9.4-62 30 Tb1 9.4-15 9.4-24 33 9.4-63 33 Sheet 1 30 9.4-25 30 9.4 Tbl Tab Sheet 2 30 9.4 32 Tb1 9.4-1 Tbl 9.4-16 9.4-26a 33 Sheet 1 32 Sheet 1 30 9.4-26b 30 Sheet 2 33 Sheet 2 30 9.4-27 26 Sheet 3 33 Sheet 3 30 9.4-28 25 Sheet 4 32 Tb1 9.4-17 9.4-28a 25 Sheet 5 32 Sheet 1 33 9.4-28b 25 Sheet 6 32 Sheet 2 33 9.4-29 0 Tb1 9.4-2 Sheet 3 33 9.4-30 26 Sheet 1 0 Sheet 4 30 9.4-31 27 Sheet 2 8 Sheet 5 30 9.4-32 2 Tb1 9.4-3 Tb1 9.4-18 9.4-32a 2 Sheet 1 29 Sheet 1 33 9.4-32b 2 Sheet 2 29 Sheet 2 30 O 9.4-33 0 Sheet 3 29 Sheet 3 30 9.4-34 29 Tbl 9.4-4 29 Sheet 4 30 9.4-35 29 Tbl 9.4-5 9.4 Fig. Tab 9.4-36 2 Sheet 1 32 Fig. 9.4-1 33 9.4-36a 2 Sheet 2 32 Fig. 9.4-2 33 9.4-36b 2 Sheet 3 32 Fig. 9.4-3 30 9.4-37 32 Sheet 4 32 Fig. 9.4-4 32 9.4-38 30 Tb1 9.4-6 Fig. 9.4-5 32 9.4-39 33 Shea* 1 30 Fig. 9.4-6 33 9.4-40 32 Sheet 2 27 Fig. 9.4-7 33 9.4-41 30 Sheet 3 27 Fig. 9.4-7a 32 9.4-42 30 Sheet 4 27 Fig. 9.4-8 30 9.4-43 30 Tbl 9.4-7 32 Fig. 9.4-9 30 9.4-44 30 Tbl 9.4-8 Fig. 9.4-10 30 9.4-45 30 Sheet 1 27 Fig. 9.4-10A 30 9.4-46 30 Sheet 2 25 Fig. 9.4-11 27 9.4-47 30 Tb1 9.4-9 30 Fig. 9.4-12 32 9.4-48 30 Tb1 9.4-10 27 Fig. 9.4-13 9.4-49 30 Tb1 9.4-11 29 Sheet 1 32 9.4-50 33 Tb1 9.4-12 0 Sheet 2 27 9.4-51 33 Tbl 9.4-13 Sheet 3 27 9.4-52 30 Sheet 1 32 Fig. 9.4-14 9.4-53 33 Sheet 2 32 Sheet 1 33 9.4-54 30 Sheet 3 32 Sheet 2 33 9.4-55 33 Sheet 4 32 Fig. 9.4-15 O LOEP 55 Revision 33
) 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Sheet 1 29 9.5-28 10 Fig. 9.5-10 25 Sheet 2 29 9.5-29 10 Fig. 9.5-11 25 Fig. 9.4-16 28 9.5-30 10 Fig. 9.5-12 25 Fig. 9.4-17 22 9.5-30a 15 Fig. 9.5-13 25 Fig. 9.4-18 9.5-30b 33 Fig. 9.5-14 25 Sheet 1 27 9.5-30c 33 Fig. 9.5-15 25 Sheet 2 27 9.5-30d 21 Fig. 9.5-16 25 Fig. 9.4-19 9.5-30e 21 Fig. 9.5-17 25 sheet 1 27 9.5-30f 15 Fig. 9.5-18 25 Sheet 2 27 9.5-31 27 Fig. 9.5-19 25 Fig. 9.4-20 26 9.5-32 15 Fig. 9.5-20 25 Fig. 9.4-21 28 9.5-33 30 Fig. 9.5-21 25 Fig. 9.4-22 29 9.5-34 30 Fig. 9.5-22 25 Sheet 1 33 9.5-35 33 Fig. 9.5-23 25 Fig. 9.4-23 18 9.5-36 28 Fig. 9.5-24 9.5 Tab 9.5-37 30 Sheet 1 27 9.5-1 0 9.5-38 21 Sheet 2 27 9.5-2 25 9.5-39 30 Fig. 9.5-25 9.5-3 0 9.5-40 21 Sheet 1 33 9.5-4 0 9.5-41 33 Sheet 2 33 9.5-5 32 9.5 Tb1 Tab Fig. 9.5-26 30 9.5-6 33 Tbl 9.5-1 Fig. 9.5-27 32 9.5-7 28 Sheet 1 10 Fig. 9.5-28 15 9.5-8 33 Sheet 2 10 Fig. 9.5-29 9.5-9 19 Tb1 9.5-2 1 Sheet 1 32 9.5-10 0 Tbl 9.5-3 0 Sheet 2 32 9.5-11 15 Tbl 9.5-4 30 Fig. 9.5~30 9.5-12 20 Tbl 9.5-5 0 Sheet 1 33 9.5-12a 20 Tbl 9.5-6 0 Sheet 2 33 9.5-12b 15 Tbl 9.5-7 10 Fig. 9.5-31 15 9.5-13 33 Tbl 9.5-8 30 Fig. 9.5-32 32 9.5-14 2G Tb1 9.5-9 Fig. 9.5-33 29 9.5-15 32 Sheet 1 21 Fig. 9.5-34 29 9.5-16 10 Sheet 2 30 App 9A Tab 9.5-17 30 Sheet 3 21 9A-i 23 9.5-18 10 Tbl 9.5-10 10 9A-ii 23 9.5-19 30 Tbl 9.5-11 15 9A-iii 24 9.5-20 30 9.5 Fig. Tab 9A-iv 24 9.5-21 10 Fig. 9.5-1 19 9A-1 23 9.5-22 27 Fig. 9.5-2 24 9A-2 26 9.5-23 27 Fig. 9.5-3 24 9A-3 23 9.5-24 27 Fig. 9.5-4 19 9A-4 23 9.5-24a 27 Fig. 9.5-5 24 9A-5 23 9.5-24b 27 Fig. 9.5-6 25 9A-6 23 9.5-25 10 Fig. 9.5-7 25 9A-7 73 9.5-26 29 Fig. 9.5-8 25 9A-8 23 9.5-27 29 Fig. 9.5-9 25 9A-3 23 LOEP- 56 Revision 33 h 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) I (~'/ Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. 9A-10 23 9A-45 23 9A-90. 23 9A-ll 23 9A-46 23 9A-91 23 9A-12 23 -9A-47 23 9A-92 23 9A-13 23 9A-48 23 9A-93 33 9A-14 23 9A-49 23 9A-94 23 9A-15 23 9A-50 .23 9A-95 23 9A-16 23 9A-51 23 9A 23 9A-17 - 23 -9A-52 23 9A-97 23 9A-18 23 9A-53 23 9A-98 23 9A-19 23 9A-54 23 9A-99 23 9A-20 23 9A-55 23 9A-100 23 9A-21 24 9A-56 23 9A-101 23 9A-22 23 9A-57 23 9A-102 23 9A-23 24 9A-58 23 9A-103 23 9A-24 23 9A-59 23 9A-104 23 9A-25 33 9A-60 23 -9A-105 23 9A-26 23 9A-61 23 9A-106 23 9A-27 24 9A-62 23 9A-107 23 Tb1 9A-1 9A-63 23 9A-108 23 Sheet 1 26 9A-64 23 9A-109 23 Sheet 2 26 9A-65 23 9A-110 23 Sheet 3 26 9A-66 23 9A-111 23.
'[~} .s-Sheet 4 Sheet 5 26 26 9A-67 9A-68 23 28 9A-112 9A-113 23 23 Sheet 6 26 9A-68a 28 9A-ll4 23 Sheet 7 26 9A-68b 28 9A-115 33 Sheet 8 26 9A-69 23 9A-116 23 Sheet 9 23 9A-70 23 9A-117 23 Sheet 10 23 9A-71 23 9A-ll8 23
. Sheet 11 23 9A-72 23 9A-119 23 9A-28 23 9A-73 23 9A-120 23 9A-29 23 9A-74 32 9A-121 24 9A-30 23 9A-75 23 9A-122 23 9A-31 23 9A-76 23 9A-123 23 9A-32 23 9A-77 23 9A-124 23 9A-33 23 9A-78 23 9A-125 23 ' 9A-34 23 9A-79 23 Fig. 9A-1 23 9A-35 23 9A-80 23 Fig. 9A-2 26 - 9A-36 23 9A-81 23 Fig. 9A-3 23 9A-37 33 9A-82 23 Fig. 9A-4 26 9A-38 23 9A-83 23 Fig. 9A-5 26 9A-39 33 9A-84 23 Fig. 9A-6 26 9A-40 23 9A-85 23 Fig. 9A-7 26 9A-41 23 9A-86 23 Fig. 9A-8 26 9A-42 23 9A-87 33 Fig. 9A-9 26-9A-43 33 9A-88 23 Fig. 9A-10 26 9A-44 23 9A-89 23 Fig. 9A-ll 26 (') LOEP- 57 Revision 33 4/81 wir- g-w - y wa w y w -+y -rw- q - e--W- r-w-- v- 1 y e -%< -sm-p-+--e--- - - - -
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MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. 26
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Fig. 9A-12 xxii 26 10.2-4 0 Fig. 9A-13 23 xxiii 26 10.2-5 10 Fig. 9A-14 23 xxiv 26 10.2-6 15 Fig. 9A-15 23 xxv 26 10.2-6a 32 Fig. 9A-16 23 xxvi 26 10.2-6b 15 Fig. 9A-17 26 xxvii 26 10.2-7 32 Fig. 9A-18 26 xxviii 26 10.2-8 30 Fig. 9A-19 26 xxix 26 10.2-9 0 Fig. 9A-20 26 xxx 26 10.2-10 30 Fig. 9A-21 26 axxi 26 10.2-11 30 Fig. 9A-22 26 xxxii 26 10.2-12 30 Fig. 9A-23 23 Chapter 10 Tab 10.2-13 3 Fig. 9A-24 23 10-i 16 10.2 Tb1 Tab Fig. 9A-25 26 10-ii 30 Tb1 10.2-1 0 Fig. 9A-26 26 10-iii 33 10.2 Fig. Tab Fig. 9A-27 26 10-iv 33 Fig. 10.2-1 Fig. 9A-28 26 10-v 33 Sheet 1 32 Fig. 9A-29 23 10-vi 30 Sheet 2 32 Fig. 9A-30 10-vii 30 Fig. 10.2-2 Sheet 1 30 10-viii 25 Sheet 1 28 Sheet 2 32 10-ix 25 Sheet 2 28 Sheet 3 32 10-x 25 Fig. 10.2-3 Sheet 4 27 10-1 0 Sheet 1 32 10.1 Tab Sheet 2 32 VOLUME 17 10.1-1 0 Fig. 10.2-4 10.1-2 33 Sheet 1 32 i 12 10.1-3 30- Sheet 2 32 ii 12 10.1 Tbl Tab Fig. 10.2-5 32 iii 21 Tb1 10.1-1 10.3 Tab iv 21 Sheet 1 0 10.3-1 0 v 21 Sheet 2 32 10.3-2 33 vi 21 Sheet 3 0 10.3-3 30 vii 21 Sheet 4 32 10.3-4 30 viii 21 Tb1 10.1-2 30 10.3-5 33 ix 21 10.1 Fig. Tab 10.3-6 30 x 21 Fig. 10.1-1 30 10.3-7 30 xi 21 Fig. 10.1-2 30 10.3-8 3 0-xii 21 Fig. 10.1-3 30 10.3-9 33 xiii 15 Fig. 10.1-4 0 10.3-10 30 xiv 21 Fig. 10.1-5 0 10.3-11 30 xv 21 Fig. 10.1-6 0 10.3-12 30 xvi 12 10.2 Tab 10.3-13 30 xvii 12 10.2-1 3 10.3 Tb1 Tab xviii 21 10.2-2 12 Tb1 10.3-1 xix 26 10.2-2a 12 Sheet 1 30 xx 26 10.2-2b 12 Sheet 2 30 xxi 12 10.2-3 0 Tb1 10.3-2 LOEP- 58 Revision 33 h 4/81 l l l l
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest . Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID. Rev. Sheet 1 30 10.4-20 33 Tb1 10.4-3 Sheet 2 30 10.4-21 33 Sheet 1 33 33
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Tb1 10.3-3 0 10.4-22 Sheet 2 33-Tb1 10.3-4 0 10.4-23 33 Tb1 10.4-4 0 Tb1 10.3-5 10.4-24 33 Tb1 10.'4 Sheet 1 20 10.4-25 33 Sheet 1 0 Sheet 2 32 10.4-26 33 Sheet 2 0 Sheet 3 30 10.4-27 33 Tb1 10.4-6 10.3 Fig. Tab 10.4-28 33- Sheet 1 30 Fig. 10.3-1 10.4-29 33 Sheet 2 30 Sheet 1 32 10.4-30 30 Tb1 10.4-7 0 Sheet 2 26 10.4-31 33 Tb1 10.4-8 Fig. 10.3-2 10.4-32 33 Sheet 1 33 Sheet 1 27 10.4-33 33 Sheet 2 33 Sheet 2 27 10.4-34 33 Tb1 10.4-9 Fig. 10.3-3 10.4-35 33 Sheet 1 0 Sheet 1 32 10.4-36 33 Sheet 2 33 Sheet 2 32 10.4-37 33 Tb1 10.4-10 39 Fig. 10.3-4 10.4-38 33 Tb1 10.4-11 Sheet 1 32 10.4-39 33 Sheet 1 33 Sheet 2 32 10.4-40 33 Sheet 2 33 Fig. 10.3-5 17 10.4-41 33 Sheet 3 33
\ Fig. 10.3-6 16 10.4-42 33 Tb1 10.4-12 18
~l 10.4 Tab '.0 . 4 -4 3 . 33 10.4 Fig. Tab 10.4-1 0 10.4-44 33 Fig. 10.4-1 10.4-2 29 10.4-45 33 Sheet 1 30 10.4-3 29 10.4-46 33 Sheet 2 32 10.4-4 29 10.4-47 33 Fig. 10.4-2 10.4-4a 29 10.4-48 33 Sheet 1 32 10.4-4b 10 10.4-49 33 Sheet 2 32 10.4-5 33 10.4-50 33 Fig. 10.4-3 10.4-6 32 10.4-51 33 Sheet 1 33 10.4-6a 33 10.4-52 33 Sheet 2 33 10.4-6b 33 10.4-53 33 Sheet 3 32 10.4-7 33 10.4-54 33 Fig. 10.4-4 10.4-8 33 10.4-55 33 Sheet 1 '33 10.4-9 33- 10.4-56 33 Sheet 2 33 10.4-1C 33 10.4-57 33 Fig. 10.4-5 l 10.4-11 30 10.4-58 33 Sheet 1 33 l 10.4-12 33 10.4-59 33 Sheet 2 33 10.4-13 30 10.4-60 33 Fig. 10.4-6 10.4-14 33 10.4-61 33 Sheet 1 33
, 10.4-15 33 10.4 Tb1 Tab Sheet 2 33 l 10.4-16 33 Tb1 10.4 1 Fig. 10.4-7 10.4-17 33 Sheet 1 29 Sheet 1 33 10.4-18 33 Sheet 2 0 Sheet 2 33 ! 10.4-19 33 Tb1 10.4-2 0 Fig. 10.4-8 (_) LOEP- 59 Revision 33 4/S1 f
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev .__ Sheet ID Rev. Sheet 1 33 Fig. 10.4-23 33 11-1 0 Sheet 2 30 Fig. 10.4-24 33 11.1 Tab Fig. 10.4-9 Fig. 10.4-25 11.1-1 0 Sheet 1 33 Sheet 1 29 11.1-2 0 Sheet 2 32 Sheet 2 33 11.2-3 32 Fig. 10.4-10 Fig. 10.4-26 11.1-4 32 Sheet 1 33 Sheet 1 32 11.1-5 0 Sheet 2 33 Sheet 2 32 11.1-6 33 Sheet 3 32 Fig. 10.4-27 26 11.1 'I O Fig. 10.4-11 Fig. 10.4-28 11.1-8 0 Sheet 1 33 Sheet 1 28 11.1-9 0 Sheet 2 30 Sheet 2 28 11.1-10 0 Fig. 10.4-12 App 10A Tab 11.1-11 33 Sheet 1 33 10A-i 33 11.1-12 33 Sheet 2 27 10A-1 30 11.1-13 0 Fig. 10.4-13 10A-2 30 11.1-14 0 Sheet 1 33 10A-3 30 11.1-15 0 Sheet 2 33 10A-4 30 11.1-16 0 Sheet 3 29 10A-5 33 11.1 Tb1 Tab Fig. 10.4-14 10A-6 30 Tbl 11.1-1 0 Sheet 1 32 10A-7 33 Tb1 11.1-2 0 Sheet 2 33 10A-8 30 Tb1 11.1-3 0 Fig. 10.4-15 10A-9 30 Tb1 11.1-4 0 Sheet 1 33 10A-10 30 Tb1 11.1-5 0 Sheet 2 32 10A-11 30 Tb1 11.1-6 0 Sheet 3 33 10A-12 33 Tbl 11.1-7 Fig. 10.4-16 10A-13 33 Sheet 1 0 Sheet 1 32 10A-14 33 Sheet 2 0 Sheet 2 30 10A-15 33 Tb1 11.1-8 0 Fig. 10.4-17 10A-16 33 Tbl 11.1-9 0 Sheet 1 30 10A-17 33 Tb1 11.1-10 0 Sheet 2 30 10A-18 33 Tbl 11.1-11 0 Fig. 10.4-18 Tbl 10A-1 33 Tbl 11.1-12 0 Sheet 1 30 Chapter 11 Tab Tb1 11.1-13 C Sheet 2 33 11-i 33 Tb1 11.1-14 Fig. 10.4-19 11-ii 33 Sheet 1 0 Sheet 1 29 11-iii 33 Sheet 2 0 Sheet 2 33 11-iv 33 Tb1 11.1-15 Sheet 3 33 11-v 0 Sheet 1 32 Fig. 10.4-20 32 11-vi 0 sheet 2 5 Fig. 10.4-21 11-vii 0 Tb1 11.1-16 5 Sheet 1 33 11-viii 0 Tb1 11.1-17 25 Sheet 2 33 11-ix 19 11.2 Tab Fig. 10.4-22 11-x 19 11.2-1 33 Sheet 1 33 11-xa 19 11.2-2 33 Sheet 2 3? 11-r.b 19 11.2-3 0 Fig. 10.4-22A 32 11-xi 6 11.2-4 0 LOEP- 60 Revision 33 h 4/S1
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued). Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. 11.2-5 0 11.3-1 0 Fig. 11.3-2 11.2-6 0 11.3-2 . 2'7 Sheet 1 32 11.2-7 0 11.3-3 0 Sheet 2 32 11.2-8 33 11.3-4 33 Fig. 11.3-3 0 11.2-9 27 11.3 33 Fig. 11.3-4 24 11.2-10 33 11.3-6 20 Fig. 11.3~s 7 11.2-11 '27 11.3-7 20 Fig. 11.3-6 7 11.2 Tb1 Tab 11.3-8 20 Fig. 11.3-7 21 Tb1 11.2-1 11.3-8a 27 Fig. 11.3-8 14 Sheet 1 0 21.3-8b 13 Fig. 11.3-9 13 Sheet 2 -0 11.3-9 0 Fig. 11.3-10 3 Sheet 3 0 11.3-10 0 11.4 Tab-Sheet 4 27 11.3-11 0 -11.4-1 33 Sheet 5 27 11.3-12 0 11.4-2 0 Sheet 6 27 11.3-13 33 11.4-3 30 Sheet 7 27 11.3-14 33 11.4-4 30 Sheet 8 0 11.3-15 33 11.4-4a 20 Tb1 11.2-2 13 11.3 Tb1 Tab 11.4-4b 17 Tb1 11.2-3 Tb1 11.3-1 33 11.4-5 4 Sheet 1 13 Tb1 11.3-2 0 11.4-6 4 4 Sheet 2 13 Tb1 11.3-3 0 11.4-7 '4 Tb1 11.2-4 0 Tb1 11.3-4 0 11.4-8 4 /h Tb1 11.2-5 0 Tb1 11.3-5 0 11.4-9 4 ( ,) Tb1 11.2-6 Tb1 11.3-6 11.4 Tb1 Tab Sheet 1 0 Shebt 1 0 Tb1 11.4-1 3G Sheet 2 0 Sheet 2 0 Tb1 11.4-2 Tb1 11.2-7 0 Tb1 11.3-7 11 Sheet J 0 Tbl 11.2-8 10 Tb1 11.3-8 13 Sheet 2 0 Tbl 11.2-9 27 Tb1 11.3-9 10 Tb1 11.4-3 0 Tb1 11.2-10 10 Tb1 11.3-10 10 Tbl 11.4-4 0 11.2 Fig. Tab Tb1 11.3-11 27 Tb1 11.4-5 30 Fig. 11.2-1 Tb1 11.3-12 10 Tb1 11.4-6 Sheet 1 28 Tbl 11.3-13 10 Sheet 1 30 Sheet 2 33 Tb1 11.3-14 27 Sheet 2 30 Fig. 11.2-2 Tb1 11.3-15 10 Sheet 3 30 Sheet 1 27 Tb1 11.3-16 10 Sheet 4 30 Sheet 2 27 Tb1 11.3-17 10 Sheet 5 30 Fig. 11.2-3 Tbl 11.3-18 27 Tb1 11.4-7 0 Sheet 1 33 Tb1 11.3-19 27 Tb1 11.4-8 4 Sheet 2 33 Tb1 11.3-20 10 Tb1 11.4-9 17 Fig. 11.2-3A Tb1 11.3-21 L7 11.4 Fig. Tab Sheet 1 33 Tb1 11.3-22 10 Fig. 11.4-1 33 Sheet 2 33 Tb1 11.3-23 10 Fig. 11.4-2 Fig. 11.2-4 26 Tb1 11.3-24 10 Sheet 1 29 Fig. 11.2-5 G Tbl 11.3-25 27 Sheet 2 26 Fig. 11.2-6 27 11.3 Fig. Tab Sheet 3 29 11.3 Tab Fig. 11.3-1 0 Sheet 4 33 i LOEP- 61 Revision 33 x/ 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet 'D Rev. Sheet ID Rev. Fig. 11.4-3 1 11.6-7 32 12-1 33 Fig. 11.4-4 18 11.6 Tbl Tab 12-11 33 Fig. 11.4-1 32 Tb1 11.6-1 32 12-iii 33 11.5 Tab Tb1 11.6-2 33 12-iv 8 11.5-1 19 Tb1 11.6-3 32 12-v 19 11.5-2 32 11.6 Fig. Tab 12-vi 33 11.5-3 32 Fig. 11.6-1 12-vii 33 11.5-4 33 Sheet 1 33 12-viii 33 11.5-5 32 Sheet 2 33 12.1 Tab 11.5-6 32 Sheet 3 33 12.1-1 30 11.5-6a 32 iheet 4 33 12.1-2 30 11.5-6b 32 12.1-2a 30 11.5-7 30 VOLUME 18 12.1-2b 30 11.5-8 30 12.1-3 33 11.5-9 30 i 12 12.1-4 0 11.5-10 30 ii 12 12.1-5 20 11.5-11 33 iii 21 12.1-6 20 11.5-12 33 iv 21 12.2 Tab 11.5-13 30 v 22 12.2-1 28 11.5-14 33 vi 21 12.2-2 28 11.5-15 32 vii 21 12.2-3 28 11.5 Tb1 Tab viii 21 12.2-4 28 Tbl 11.5-1 ix 21 12.2-5 0 Sheet 1 30 x 21 12.2-6 0 Sheet 2 30 xi 21 12.2-7 33 Tb1 11.5-2 xii 21 12.2-8 20 Sheet 1 32 xiii 15- 12.2 Tb1 Tab Sheet 2 32 xiv 21 Tb1 12.2-1 28 Tb1 11.5-3 20 xv 21 Tb1 12.2-2 0 Tb1 11.5-4 xvi 12 Tb1 12.2-3 0 Sheet 1 32 xvii 12 Tb1 12.2-4 0 Sheet 2 20 xviii 21 Tb1 12.2-5 0 Sheet 3 20 xix 26 Tb1 12.2-6 30 Sheet 4 20 xx 26 Tb1 12.2-7 0 Tb1 11.5-5 xxi 12 Tb1 12.2-8 0 Sheet 1 32 xxii 26 Tb1 12.2-9 0 Sheet 2 32 xxiii 26 Tb1 12.2 1c 32 Tb1 11.5-6 xxiv 26 Tb1 12.2-11 32 Sheet 1 33 xxv 26 Tb1 12.2-12 28 Sheet 2 33 xxvi 26 Tb1 12.2-13 0 11.6 Tab xxvii 26 Tb1 12.2-14 0 11.6-1 6 xxviii 26 Tb1 12.2-15 11.6-2 32 xxix 26 Sheet 1 28 11.6-3 28 xxx 26 Sheet 2 28 11.6-4 32 xxxi 26 Sheet 3 28 11.6-5 32 xxxii 26 Tb1 12.2-16 11.6-6 32 Chapter 12 Tab Sheet 1 28 LOEP- 6 2 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) O Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Sheet 2 0 Tb1 12.3-2 Fig. 12.3-20 14 Sheet 3 0 Sheet 1 33 Fig. 12.3-21 17 Sheet 4 30 Sheet 2 32 Fig. 12.3-22 32 Sheet 5 0 Tb1 12.3-3 30 Fig. 12.3-23 32 Sheet 6 28 Tb1 12.3-4 0 Fig. 12.3-24 32 12.3 Tab Tb1 12.3-5 Fig. 12.3-25 14 , 12.3-1 0 sheet 1 27 Fig. 12.3-26 0 ' 12.3-2 27 Sheet 2 27 Fig. 12.3-27 0. 12.3-3 33 Sheet 3 27 Fig. 12.3-28 14 12.3-4 8 Sheet 4 27 Fig. 12.3-29 0 12.3-4a 33 Sheet 5 27 Fig. 12.3-30 0 12.3-4b 8 Sheet 6 27 Fig. 12.3-31 1 12.3-5 0 Sheet 7 27 Fig. 12.3-32 1 12.3-6 0 Sheet 8 27 Fig. 12.3-33 1 12.3-7 9 Sheet 9 27 Fig. 12.3-34 1 12.3-8 4 Sheet 10 27 Fig. 12.3-35 1 12.3-9 33 Sheet 11 27 Fig. 12.3-36 1 ' 12.3-10 0 Sheet 12 27 Fig. 12.3-37 0 12.3-11 27 Sheet 13 27 Fig. 12.3-38 0 12.3-12 33 Sheet 14 27 Fig. 12.3-39 23 12.3-13 33 Sheet 15 27 Fig. 12.3-40 15 12.3-14 0 Sheet 16 27 Fig. 12.3-41 21 12.3-15 0 Sheet 17 27 Fig. 12 3-42 26 A, m 12.3-16 0 Sheet 18 27 Fig. 12.3-43 27 12.3-17 33 Sheet 19 27 12.4 Tab 12.3-18 0 Sheet 20 27 12.4-1 0 12.3-19 33 Sheet 21 27 12.4-2 32 12.3-20 32 12.3 Fig. Tab 12.4-3 33 12.3-21 32 Fig. 12.3-1 26 12.4-4 8 12.3-22 32 Fig. 12.3-2 1 12.4-5 0 12.3-22a 32 Fig. 12.3-3 0 12.4 Tbl Tab 12.3-22b 32 Fig. 12.3-4 21 Tbl 12.4-1 12.3-23 30 Fig. 12.3-5 0 Sheet 1 13 12.3-24 30 Fig. 12.3-6 5 Sheet 2 13 12.3-25 33 Fig. 12.3 / 0 Tb1 12.4-2 12.3-26 32 Fig. 12 . ',-8 0 Sheet 1 32 12.3-27 30 Fig. 12.3-9 21 Sheet 2 13 12.3-28 32 Fig. 12.3-10 0 Tb1 12.4-3 32 12.3-29 30 Fig. 12.3-11 0 Tb1 12.4-4 32 12.3-30 30 Fig. 12.3-12 0 Tb1 12.4-5 0 12.3-31 30 Fig. 12.3-13 21 Tbl 12.4-6 0 12.3-32 30 Fig. 12.3-14 0 Tb1 12.4-7 32 12.3-33 30 Fig. 12.3-15 0 Tb1 12.4-8 33 12.3-34 30 Fig. 12.3-16 32 12.5 Tab 12.3-35 30 Fig. 12.3-17 14 12.5-1 33 12.3 Tbl Tab Fig. 12.3-18 17 12.5-2 29 Tbl 12.3-1 0 Fig. 12.3-19 32 12.5-3 11 O' LOEP- 63 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. 12.5-4 33 13.1-17 30 13.2-29 33 1?. 5-5 30 13.1-18 33 13.2-30 32 12.5-6 30 13.1-19 30 13.2-31 32 12.5-7 30 13.1-20 33 13.2-32 32 12.5-e 30 13.1-21 33 13.2-33 32 12.5-9 33 13.1-22 33 13.2-34 32 12.5-10 11 13.1-23 30 13.2-35 32 12.5-11 29 13.1-24 33 13.2-36 32 17.5-12 29 13.1-25 30 13.2-37 32 12.5-13 29 13.1-26 30 13.2-38 32 12.5-14 33 13.1-27 30 13 2 Tb1 Tab 12.5-15 29 13.1 Tbl Tab Tb1 13.2-1 32 12.5-16 29 Tbl 13.1-1 30 Tb1 13.2-2 32 12.5-17 29 13.1 Fig. Tab 13.2 Fig. Tab 12.5-18 29 Fig. 13.1-1 30 Fig. 13.2-1 33 12.5-19 11 Fig. 13.1-2 33 Fig. 13.2-2 33 12.5.-20 29 Fig. 13.1-3 33 Fig. 13.2-3 33 12.5-21 29 Fig. 13.1-4 30 Fig. 13.2-4 33 12.5-22 33 13.2 Tab 13.3 Tab 12.5-23 33 13.2-1 32 13.3-1 5 12.5-24 29 13.2-2 33 13.4 Tab 12.5 Fig. Tab 13.2-3 32 13.4-1 30 Fig. 12.5-1 26 13.2-4 32 13,5 Tab Chapter 13 Tab 13.2-5 32 13.5-1 33 13-i 33 13.2-6 32 13.5-2 30 13-ii 33 13.2-7 32 13.5-3 29 13-iii 33 13.2-8 32 13.5-4 13 13-iv 33 13.2-9 32 13.5-5 33 13.1 Tr.b 13.2-10 L2 13.5-6 33 13.1-1 33 13.2-11 32 13.5-7 33 13.1-2 32 13.2-12 32 13.5-8 33 13.1-3 32 13.2-13 32 13.5 Fig. Tab 13.1-4 0 13.2-14 32 Fig. 13.5-1 30 13.1-5 18 13.2-15 32 Fig. 13.5-2 3 13.1-6 33 13.2-16 32 13.6 Tab 13.1-7 33 13.2-17 32 13.6-1 7 13.1-8 32 13.2-18 32 App 13A Tab 13.1-9 32 13.2-19 32 13A-i 1 13.1-10 33 13.2-20 32 13A.1-1 33 13.1-11 32 13.2-21 32 13A.1-2 30 13.1-12 33 13.2-22 32 13A.1-3 30 13.1-12a 32 13.2-23 32 13A.1-4 30 13.1-12b 32 13.2-24 32 13A.1-5 30 13.1-13 30 13.2-25 32 13A.1-6 30 13.1-14 30 13.2-26 32 13A.1-7 33 13.1-15 30 13.2-27 32 13A.1-8 33 13.1-16 30 13.2-28 32 13A.1-9 30 LOEP 64 Revision 33 4/81
MIDLAND 1&2-FSAR 1 LIST'OF EFFECTIVE PAGES (continuedl. Lates', Latest Latest Sheet ID- Rev. Sheet ID Rev. Sheet ID Rev. 13A.1-10 '33 13A.2-26 33 13A.2-73 30 13A.1-11 30 13A.2-27 33 13A.'2-74 30 13A.1 30 ' 13A.2-28 33 .13A.2-75 30
'13A.1-13 30 13A.2-29 30 13A.2-76 30 13A.1-14 30 13A.2-30 30 13A.2-77 30 ,
13A.1-15 30 13A.2-31 30 -13A.2-78 30 13A.1-16 33 13A 2-32 30 13A.2-79 '33 13A.1-17 30~ 13A.2-33 30 13A.2-80. 30 13A.1-18 30 13A.2-34 30 13A.2 30 13A.1-19~ 33 13A.2-35 30 13A'.2-82 33 13A.1-20 33 13A.2-36 33 13A.2-83 30 13A.1-21 33 13A.2-37 33 13A.2-84 33 13A.1-22 33 13A.2-38 33' 13A.2-85 33 13A.1-23 30 13A.2-39 33 , 13A.2-86 33 13A.1-24 30 13A.2-40 33 13A.2-87 30 13A.1-25 30 13A.2-41 30 13A.2-88 33-13A.1-26 30 13A.2-42 33 13A.2-89 33 13A.1-27 30 13A.2-43 33 13A.2-90 33 13A.1-28 30 13A.2-44 -30 13A.2-91~ 33 13A.1-29 30 13A.2-45 30 13A.2-92 33 13A.1-30 30 13A.2-46 30 13A'.2-93 33 13A.1-31 30 13A.2-47 30 13A.2-94 33 O 13A.2-1 13A.2-2 13A.2-3 33 33 30 13A.2-48 13A.2-49 13A.2-50 30 30 30 13A.2-95 13A.2-96
~13A.2-97 33 33-33 13A.2-4 30. 13A.2-51 33 13A.2-98 33 13A.2-5 33 13A.2-52 33 13A.2-99 33 13A.2-6 30 13A.2-53 30 .13A.2-100 33 13A.2-7 33 13A.2-54 33 13A.2-101 33 13A.2-6 30 -13A.2-55 33 13A.2-102 33 13A.2-9 30 13A.2-56 33 .13A.2-103 33 13A.2-10 30 13A.2-57 30 13A 2-11 30 13A.2-58 30 VOLUME 19 13A.2-12 30 13A.2-59 30 13A.2-13 30 13A.2-60 30 i 12 13A.2-14 30 13A.2-61 '30 ii 12 13A.2-15 30 13A.2-62 33 iii. 21 13A.2-1G 33 13A.2-63 33 iv 21 13A.2-17 30 13A.2-64 30 v 21 13A.2-18 30 . 13A.2-65 30 vi 21 .13A.2-19 30 13A.2-66 30 vii 21 13A.2-20 30 13A.2-67 30 viii 21 13A.2-21 30 13A.2-68 30 ix 21 13A.2-22 30 13A.2-69 30 x 21~
13A.2-23 30 13A.2-70 33 xi 21 13A.2-24 33 13A.2-71 30 xii 21~ 13A.2-25 33 13A.2-72 30 xiii 15
) LOEP- 65 Revision 33 4/81 ,
a
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) l Latest Latest Latest S_heet ID Rev. Sheet ID Rev. Sheet ID Rev. ' xiv 21 14.2-17 0 14A.1-14 30 xv 21 14.2-18 0 14A.1-14a 32 xvi 12 14.2-19 33 14A.1-14b 30 xvii 12 14.2-20 30 14A.1-15 30 xviii 21 14.2-21 30 14A.1-16 21 xix 26 14.2-22 30 14A.1-17 20 xx 26 14.2-25 30 14A.1-18 20 xxi 12 14.2-24 30 14A.1-19 23 xxii 26 14.2-25 30 14A.1-20 29 xxiii 26 14.2-26 30 14A.1-21 20 l xxiv 26 14.2-27 33 14A.1-22 20 xxv 26 14.2-28 33 14A.1-23 30 xxvi 26 14.2-29 30 14A.1-24 20 xxvil 26 14.2-30 33 14A.1-24a 30 xxviii 26 14.2-31 33 14A.1-24b 20 xxix 26 14.2 Tb1 Tab 14A.1-25 32 xxx 26 Tb1 14.2-1 14A.1-26 27 xxxi 26 Sheet 1 30 14\.1-27 27 xxxii 26 Sheet 2 33 14A.1-28 30 i Chapter 14 Tab Sheet 3 33 14A.1-29 20 14-i 33 Sheet 4 33 14A.1-30 21 l 14-ii 33 Tbl 14.2-2 33 14A.1-30a 21 14-iii 0 Tbl 14.2-3 33 14A.1-30b 21 14-iv 0 Tb1 14.2-4 14A.1-31 0 14.1 Tab Sheet 1 19 14A.1-32 29 14.1-1 0 Sheet 2 19 14A.1-33 27 14.2 Tab 14.2 Fig. Tab 14A.1-34 20 1 14.2-1 0 Fig. 14.2-1 18 14A.1-35 0 14.2-2 0 Fig. 14.2-2 32 14A.1-36 30 14.2 1 0 App 14A Tab 14A.1-37 30 14.2
- 32 14A.1-1 33 14A.1-38 0 14.2-5 32 14A.1-2 33 14A.1-39 0 14.2-6 18 14A.1-3 20 14A.1-40 30 14.2-7 20 14A.1-4 20 14A.1-41 30 14.2-8 20 14A.1-5 20 14A.1-42 30 j 14.2-9 20 14A.1-6 20 14A.1-43 30 '
14.2-10 33 14A.1-6a 20 14A.1-44 30 l 14.2-11 33 14A.1-6b 20 14A.1-44a 30 14.2-12 20 14A.1-7 0 14A.1-44b 30 14.2-13 20 14A.1-8 20 14A.1-45 30 14.2-14 33 14A.1-9 0 14A.1-46 30 1ce.2-14a 30 14A.1-10 0 14A.1-47 30 1 14.2-14b 20 14A.1-11 30 14A.1-48 30 14.2-15 20 14A.1-12 30 14A.1-49 0 14.2-16 18 14A.1-12a 30 14A.1-50 10 14.2-16a 18 14A.1-12b 30 14A.1-51 21 14.2-16b 18 14A.1-13 30 14A.1-52 0 LOEP 66 Revision 33 ) 4/81 l l 1
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (cositinued) Latest Latest Latest Sheet ID Rev. Sheet ID. Rev. Sheet ID Rev. 14A.1-53 0 14A.3-2a 32 15-xviii 30 14A.1-54 33 14A.3-2b 19 15-xix 30 14A.1-55 33 14A.3-3 0 15-xx 30 14A.1-56 21 14A.3-4 0 15-xxi 30 14A.1-56a 21- 14A.3-5 0 15-xxii 30 14A,1-56b 21 14A.3-6 33 15-xxiii 30 14A.1-57 33 14A.4-1 0 15-xxiv 30 14A.1-58 0 14A.4-2 0 15-xxv 30 14A.1-59 30 14A.4-3 0 15-xxvi 30 14A.1 30 14A.4-4 19 15-xxvii 30 14A.1-60a 30 14A.4-5 19 15-xxviii 30 14A.1-60b 30 14A.4-6 0 15-xxix 32 14A.1-61 0 14A.4-7 0 15.0 Tab , 14A.1-62 33 14A.4-8 0 15.0-1 33 14A.1-63 23 14A.4-9 19 15.0-2 33' 14A.1-64 0 14A.4-10 0 15.0-3 33 14A.1-65 32 14A.4-11 0 -15.0-4 33 14A.1-66 32 14A.4-12 0 '15.0-5 33 14A.1-67 30 14A.4-13 21 15.0-6 33 14A.1-68 30 14A.4-14 0 15.0-7 33 14A.1-69 30 14A.4-15 33 15.0-8 33 14A.1-70 30 14A.4-16 0 15.0-9 33 l 14A.1-70a 30 14A.4-17 0 15.0-10 33
) 30 14A.4-18 0 15.0 Tb1 Tab x_/ 14A.1-70b 14A.1-71 0 14A.4-19 19 Tbl 15.0-1 14A.1-72 0 14A.4-20 30 Sheet 1 3 14A.1-73 30 14A.4-21 19 Sheet 2 3 i 14A.1-74 32 Chapter 15 Tab Sheet 3 2 14A.1-75 21 15-1 32 Sheet 4 4 14A.1-76 27 15-ii 32 Sheet 5 2 14A.1-77 33 15-iii 9 Sheet 6 2 14A.1-78 33 15-iv 7 Tbl 15.0-2 14A.1-79 33 15-v 3 Sheet 1 32 14A.1-80 33 15-vi 26 Sheet 2 32 14A.1-81 33 15-vii 26 Sheet 3 9 14A.1-82 33 15-viii 3 Tb1 16.0-3 14A.2-1 0 15-ix 30 Sheet 1 13 14A.2-2 0 15-x 18 Sheet 2 13 14A.2-3 0 15-xi 18 Tbl 15.0-4 14A.2-4 19 15-xii 18 Sheet 1 2-14A.2-5 0 15-xiia 18 Sheet 2 32
- 14A.2-6 0 15-xiib 18 Tb1 13.0-5 14A.2-7 0 15-xiii 33 Sheet 1 0 14A.2-8 0 15-xiv 33 Sheet 2 0 14A.2-9 33 15-xv 11 Tb1 15.0-6 14A.3-1 0 15-xvi 19 Sheet 1 32 14A.3-2 19 15-xvii 30 Sheet 2 13
() LOEP 67 Revision 33 4/81
MIDLAND 1&'-FSAR i LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Sheet 3 32 15.1 Fig. Tab Tb1 15.2-10 7 Tb1 15.0-7 18 Fig. 15.1-1 0 Tb1 15.2-11 15.0 Fig. Tab Fig. 15.1-2 0 Sheet 1 7 Fig. 15.0-1 0 Fig. 15.1-2A 12 Sheet 2 7 Fig. 15.0-2 0 Fig. 15.1-3 7 15.2 Fig. Tab Fig. 15.0-3 0 Fig. 15.1-4 7 Fig. 15.2-1 0 Fig. 15.0-4 9 Fig. 15.1-5 3 Fig. 15.2-2 0 15.1 Tab Fig. 15.1-6 3 Fig. 15.2-3 2 15.1-1 0 Fig. 15.1-7 7 Fig. 15.2-3A 12 15.1-2 32 Fig. 15.1-8 7 Fig. 15.2-4 7 15.1-3 33 Fig. 15.1-8A 10 Fig. 15.2-5 2 15.1-4 33 Fig. 15.1-9 19 Fig. 15.2-6 7 15.1-5 33 Fig. 15.1-10 19 Fig. 15 C -7 7 15.1-6 33 Fig. 15.1-11 19 Fig. 15.2-8 15 15.1-7 33 15.2 Tab 15.3 Tab 15.1-8 33 15.2-1 33 15.3-1 2 15.1-8a 33 15.2-2 33 15.3-2 2 15.1-8b 10 15.2-3 33 15.3-3 33 15.1-9 33 15.2-4 33 15.3-4 0 15.1-10 33 15.2-5 33 15.3-5 0 15.1-11 33 15.2-6 33 15.3-6 33 15.1-12 33 15.2-7 33 15.3-7 16 15.1-13 33 15.2-8 33 15.3-8 0 15.1-14 33 15.2-9 33 15.3 Tb1 Tab 15.1 Tb1 Tab 15.2-10 33 Tb1 15.3-1 2 Tb1 15.1-1 0 15.2-11 33 Tb1 15.3-2 2 Tb1 15.1-2 0 15.2-12 33 Tb1 15.3-S 0 Tb1 15.1-3 32 15.2-13 33 Tb1 15.3-4 2 Tb1 15.1-4 0 15.2-14 33 Tb1 15.3-5 16 Tb1 15.1-5 7 15.2-15 33 15.3 Fig. Tab Tbl 15.1-6 7 15.2-16 33 Fig. 15.3-1 0 Tb1 15.1-7 7 15.2-17 33 Fig. 15.3-2 0 Tbl 15.1-8 7 15.2-18 33 Fig. 15.3-3 0 Tb1 15.1-9 19 15.2 Tb1 Tab Fig. 15.3-4 0 Tb1 15.1-10 24 Tb1 15.2-1 0 Fig. 15.3-5 0 Tb1 15.1-11 19 Tb1 15.2-2 Fig. 15.3-6 0 Tb1 15.1-12 7 Sheet 1 18 Fig. 15.3-7 0 Tb1 15.1-12A 10 Sheet 2 18 Fig. 15.3-8 2 Tbl 15.1-13 19 Tb1 15.2-3 33 Fig. 15.3-9 2 Tb1 15.1-14 7 Tb1 15.2-4 Fig. 15.3-10 2 Tbl 15.1-15 Sheet 1 18 Fig. 15.3-11 2 Sheet 1 7 Sheet 2 18 15.4 Tab Sheet 2 7 Tb1 15.2-5 2 15.4-1 33 Tbl 15.1-16 Tbl 15.2-6 0 15.4-2 33 Sheet 1 33 Tb1 15.2-7 33 15.4-3 33 Sheet 2 18 Tb1 15.2-8 7 15.4-4 33 Tbl 15.1-17 7 Tb1 15.2-9 33 13.4-5 33 LOEP 68 Revision 33 4/81 i . .
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) A Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. 15.4-6 33 Tbl 15.4-9 0 Fig. 15.4-31' O 15.4-6a 33 Tb1 15.4-10 0 Fig. 15.4-32 0 15.4-6b 33 Tb1 15.4-11 33 Fig. 15.4-33 0 15.4-7 0 Tb1 15.4-12 33 Fig. 15.4-34 0 15.4-8 0 Tbl'15.4-13 0 Fig. 15.4-35 0 15.4-9 0 Tbl-15.4-14 0 Fig. 15.4-36 0 15.4-10 0 Tb1 15.4-15 3 Fig. 15.4-37 0 15.4-11 0 Tb1 15.4-16 0 . Fig. 15.4-38 0 15.4-12 0 Tb1 15.4-17 Fig. 15.4-39 0 15.4-13 0 Sheet 1 18 Fig. 15.4-39A 12 15.4-14 0 Sheet 2 18 Fig. 15.4-40 0 15.4-15 0 Sheet 3 18 Fig. 15.4-41 0 15.4-16 33 Sheet 4 18 Fig. 15.4-42 0 15.4-17 0 Tb1 15.4-18 18 Fig. 15.4-43 0 15.4-18 0 15.4 Fig. Tab Fig. 15.4-44 0 15,4-19 0 Fig. 15.4-1 3 Fig. 15.4-45 0 15.4-20 0 Fig. 15.4-1A 12 Fig. 15.4-46 0 15.4-21 3 Fig. 15.4-2 0 Fig. 15.4-47 0 I 15.4-22 12 Fig. 15.4-2A 13 Fig. 15.4-48 0 15.4-23 33 Fig. 15.4-3 0 Fig. 15.4-49 2 15.4-24 33 Fig. 15.4-4 0 Fig. 15.4-50 8 15.4-25 21 Fig. 15.4-5 3 Fig. 15.4-51 8 O 15.4.26 15.4-26a 15.4-26b 33 33 33 Fig. 15.4-6 Fig. 15.4-7 Fig. 15.4-8 3 0 0 Fig. 15.4-52 Fig. 15.4-52a 33 15.5 Tab 33 15.4-26c 33 Fig. 15.4-9 33 15.5-1 33 15.4-26d 33 Fig. 15.4-10 33 15.5-2 9 15.4-27 0 Fig. 15.4-11 0 15.5-3 33 15.4-28 0 Fig. 15.4-12 0 15.6 Tab i 15.4-29 0 Fig. 15.4-13 0 15.6-1 30 l 15.4-30 0 Fig. 15.4-14 0 15.6-2 28 15.4-31 0 Fig. 15.4-15 0 15.6-2a 12 < 15.4-32 2 Fig. 15.4-16 0 15.6-2b 3 l 15.4-33 8 Fig. 15.4-17 0 15.6-3 0 15.4-34 32 Fig. 15.4-18 0 15.6-4 33 15.4-35 18 Fig. 15.4-19 0 15.6-5 25 15.4 Tb3 Tab Fig. 15.4-20 0 15.6-6 25 Tb1 15.4-1 0 Fig. 15.4-21 0 15.6-6a 25 l Tb1 15.4-2 9 Fig. 15.4-22 0 15.6-6b 25 l Tb1 15.4-2a 33 Fig. 15.4-23 0 15.6-7 33 Tb1 15.4-3 0 Fig. 15.4-24 0 15.6-8 33 Tb1 1 4 . '. - 4 33 Fig. 25.4-25 0 15.6-8a 32 li '. 15.4-4a 33 Fig. 15.4-26 0 15.6-8b 8 Tb1 15.4-5 13 Fig. 15.4-27 0 15.6-9 32
- Tb1 15.4-6 13 Fig. 15.4-28 0 15.6-10 33 Tb1 15.4-7 13 Fig. 15.4-29 0 15.6-11 30 TLI 15.4-8 13 Fig. 15.4-30 0 15.6-12 30 LOE, . 6 9 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) Latest Latest Latest O Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. 15.6-13 30 Sheet 1 29 xxxii 26 15.6-14 30 Sheet 2 18 App 15A Tab 15.6-15 30 Tb1 15.7-2 18 15A-1 0 15.6-16 30 Tb1 15.7-3 29 15A-2 0 15.6 Tb1 Tab 'rb1 15. 7-4 29 15A-3 0 Tbl 15.6-1 0 Tb1 15.7-5 Tb1 15A-1 Tb1 15.6-2 3 Sheet 1 30 Sheet 1 0 Tb1 15.6-3 Sheet 2 33 Sheet 2 0 Sheet 1 0 Sheet 3 33 Sheet 3 0 Sheet 2 18 Tb1 15.7-6 18 Tb1 15A-2 32 Tb1 15.6-4 18 Tb1 15.7-7 30 Tb1 15A-3 32 Tb1 15.6-5 0 15.8 Tab Tb1 15A-4 32 Tb1 15.6-6 0 15.8-1 33 Tb1 15A-5 0 Tb1 15.6-7 App 15B Tab Sheet 1 18 VOLUME 20 15B.1-1 30 Sheet 2 32 15B.1-2 27 Sheet 3 32 i 12 15B.1-3 0 Tbl 15.6-8 18 ii 12 15B.1-4 27 Tb1 15.6-9 33 iii 21 15B.1-5 33 Tbl 15.6-10 iv 21 15B.1-6 33 Sheet 1 18 v 21 15B.1-7 27 Sheet 2 10 vi 21 15B.1-8 27 Sheet 3 18 vii 21 15B.1-9 0 Sheet 4 18 viii 21 15B.1-10 0 Tb1 15.6-11 ix 21 15B.1-11 0 Sheet 1 30 x 21 15B.1-12 0 Sheet 2 30 xi 21 Tb1 15B-1 0 Tb1 15.6-12 0 xii 21 Tb1 15B-2 0 Tb1 15.6-13 30 xiii 15 Tb1 15B-3 0 Tb1 15.6-14 0 xiv 21 Tb1 15B-4 O Tb1 15.6-15 3 xv 21 Fig. 15B-1 9 15.6 Fig. Tab xvi 12 Fig. 15B-2 9 Fig. 15.6-1 0 xvii 12 App 15C Tab Fig. 15.6-2 3 xviii 21 15C-1 9 Fig. 15.6-3 3 xix 26 15C-2 9 Fig. 15.6-4 8 xx 26 15C-3 17 15.7 Tab xxi 12 15C-4 9 15.7-1 0 xxii 26 15C-5 17 15.7-2 0 xxiii 26 15C-6 17 15.7-3 0 xxiv 26 Tb1 15C-1 9 15.7-4 20 xxv 26 Tbl 15C-2 9 15.7-5 33 xxvi 26 Tbl 15C-3 15.7-6 33 xxvii 26 Sheet 1 9 15.7-7 33 xxviii 26 Sheet 2 9 15.7-8 33 xxix 26 Tb1 15C-4 9 15.7 Tb1 Tab xxx 26 Tb1 15C-5 9 Tb1 15.7-1 xxxi 26 Tb1 15C-6 9 LOEP 7 0 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) ( V , Latest Latest Latect Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. Tb1 15C-7 9 Tbl 15D-5 10 15E-11 11. Tb1 15C-8 9 Tb1 15D-6 10 15E-12 11 Tb1 15C-9 11 Tb1 15D-7 10 15E-13 11 Tb1 15C-10 9 Tb1 15D-8 10 15E-14 11 Tb1 15C-11 Tb1 15D-9 10 15E-15 11 Sheet 1 9 Tb1 15D-10 10 15E-16 30 Sheet 2 9 Tbl 15D-11,12 10 15E-17 30 Tb1 15C-12 Tb1 15D-12A 19 15E-18 30 Sheet 1 9 Tb1 15D-13 32 15E-19 11 Sheet 2 9 Tbl 15D-14 10 15E-20 11 Tb1 15C-13 Tb1 15D-15 10 15E-21 11 Sheet 1 9 Tb1 15D-16 10 15E-22 11 Sheet 2 9 Thl 15D-17 10 15E-23 11 Tb1 15C-14 Tb1 15D-18 10 15E-24 11 Sheet 1 9 Tb1 15D-19 10 15E-25 11 Sheet 2 9 Tb1 15D-20 10 15E-26 11 Tb1 15C-15 Fig. 15D-1 10 15E-27 33 Sheet 1 9 Fig. 15D-2 10 15E-28 11 Sheet 2 9 Fig. 15D-3 10 15E-29 11 Tbl 15C-16 17 Fig. 15D-4 10 15E-30 11 Fig. 15C-1 9 Fig. 15D-5 10 15E-31 11 Fig. 15C-2 9 Fig. 15D-6 10 15E-32 11 Fig. 15C-3 9 Fig. 15D-7 32 15E-33 33 k Fig. 15C-4 9 Fig. 15D-8 10 15E-34 33 Fig. 15C-5 9 Fig. 15D-9 10 15E-35' 33 Fig. 15C-6 9 Fig. 15D-10 10 15E-36 11 Fig. 15C-7a 9 Fig. 15D-11 10 15E-37 11 Fig. 15C-7b 9 Fig. 15D-12 10 15E-38 12 Fig. 15C-8 9 Fig. 15D-13 10 15E-39 11 Fig. 15C-9 9 Fig. 15D-14 10 15E-40 11 Fig. 15C-10 9 Fig. 15D-15 10 15E-41 11 Fig. 15C-10A 17 Fig. 15D-16 10 15E-42 11 Fig. 15C-11 17 Fig. 15D-17 32 15E-43 33 App 15D Tab Fig. 15D-18 10 15E-44 11 15D-1 30 Fig. 15D-19 10 15E-45 26 15D-2 33 Fig. 15D-20 10 15E-46 11 15D-3 10 App 15E Tab 15E-47 33 15D-4 10 15E-1 11 15E-48 11 15D-5 19 15E-2 11 15E-49 11 15D-6 19 15E-3 11 15E-50 11 15D-7 33 15E-4 11 15E-51 11 Tb1 15D-1 10 15E<-5 11 15E-52 11 Tb1 15D-2 10 15E-6 11 15E-53 33 Tb1 15D-3 15E-7 11 15E-54 11 Sheet 1 10 15E-8 11 15E-55 11 Sheet 2 10 15E-9 11 15E-56 11 Tb1 15D-4 10 15E-10 11 15E-57 11 { LOEP 71 Revision 33
4/81 s
9-- ,, - - w, ,.,,,..~y. .- -, ,, _m ,.,.-,.y , - ,, ..w . , _ _ , _ _ _ = ._ c . .y,-
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued [ Latest Latest Latest O Sheet ID _Rev. Sheet ID Rev. Sheet ID Rev. 15E-58 11 TBL 15F-3 30 16.2-8 33 15E-59 11 Fig. 15F-1 30 16.2-9 33 15E-60 11 Fig. 15F-2 30 16.2-10 33 15E-61 33 Fig. 15F-3 30 16.2-11 33 15E-62 11 Fig. 15F-4 30 16.2-12 33 15E-63 11 Fig. 15F-5 30 16.2-13 33 15E-64 11 Fig. 15F-6 30 16.2-14 33 15E-65 11 Fig. 15F-7 30 16.2-15 33 15E-66 12 Fig. 15F-8 30 16.2-16 33 15E-67 11 Chapter 16 Tab 16.2-17 33 15E-68 11 16-i 33 16.2-18 33 15E-69 30 16-ii 33 16.2-19 33 15E-70 11 16-iii 33 16.3/4 Tab 15E-71 11 16-iv 33 16.3/4-1 33 15E-72 12 16-v 33 16.3/4-2 33 15E-73 33 16-vi 33 16.3/4-3 5 15E-74 33 16-vii 33 16.3/4.1-1 33 15E-75 11 16-viii 33 16.3/4.1-2 33 15E-76 12 16-ix 33 16.3/4.1-3 33 15E-77 11 16-x 33 16.3/4.1-4 33 15E-78 12 16-xi 33 16.3/4.1-5 33 15E-79 11 16-xii 33 16.3/4.1-r; 33 15E-80 11 16-giii 33 16.3/4.1-7 33 15E-81 11 16-xiv 33 16.3/4.1-8 33 h 15E-82 11 16-xv 33 16.3/4.1-9 33 15E-83 11 16-xvi 33 16.3/4.1-10 33 15E-84 11 16-xvii 33 16.3/4.1-11 33 15E-85 33 16-xviii 33 16.3/4.1-12 33 15E-86 12 16-xix 33 16.3/4.1-13 33 15E-87 11 16.1 Tab 16.3/4-1-14
. 33 15E-88 11 16.0-1 33 16.3/4.1-15 33 Tb1 15E-1 11 16.1-1 33 16.3/4.1-16 33 Tb1 15E-2 16.1-2 33 16.3/4.1-17 33 Sheet 1 11 16.1-3 33 16.3/4.1-18 33 Sheet 2 11 16.1-4 33 16.3/4.1-19 33 Sheet 3 11 16.1-5 33 16.3/4.1-20 33 Sheet 4 11 16.1-6 33 16.3/4.1-21 33 Tb1 15E-3 11 16.1-7 33 16.3/4.1-22 33 App 15F Tab 16.1-8 33 16.3/4.1-23 33 15F-1 30 16.2 Tab 16.3/4.1-24 33 15F-2 30 16.2-1 33 16.3/4.1-25 33 15F-3 33 16.2-2 33 16.3/4.1-26 33 15F-4 33 16.2-3 33 16.3/4.1-27 33 15F-5 30 16.2-4 33 16.3/4.1-28 5 15F-6 33 16.2-5 33 16.3/4.1-29 33 TBL 15F-1 30 16.2-6 33 16.3/4.1-30 33 TBL 15F-2 30 16.2-7 33 16.3/4.1-31 33 LOEP 7 2 Revision 33 4/81 l
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) r-'N Latest Latest Latest Sheet ID _ Rev. Sheet ID Rev. Sheet ID Rev. 16.3/4.1-32 33 16.3/4.3-28 33 16.3/4.4-15 33 16.3/4.1-33 33 16.3/4.3-29 33 16.3/4.4-16 33 16.3/4.1-34 33 16.3/4.3-30 33 16.3/4.4-17 33 16.3/4.1-35 33 16.3/4.3-31 33 16.3/4.G-18 33 16.3/4.1-36 33 16.3/4.3-32 33 16.3/4.4-19 33 16.3/4.1-37 33 16.3/4.3-33 33 16.3/4.4-20 33 16.3/4.2-1 33 16.3/4.3-34 33 16.3/4.4-21 33 16.3/4.2-1 33 16.3/4.3-35 33 16.3/4.4-22 33 16.3/4.2-3 33 16.3/4.3-36 33 16.3/4.4-23 33 16.3/4.2-4 33 16.3/4.3-37 33 16.3/4.4-24 33 16.3/4.2-5 33 16.3/4.3-38 33 16.3/4.4-25 33 16.3/4.2-6 33 16.3/4.3-39 33 15.3/4.4-26 33 16.3/4.2-7 33 16.3/4.3-40 33 16.3/4.4-27 33 16.3/4.2-8 33 16.3/4.3-41 33 16.3/4.4-28 33 16.3/4.2-9 33 16.3/4.3-42 33 16.3/4.4-29 33 16.3/4.2-10 33 16.3/4.3-43 33 16.3/4.4-30 33 16.3/4.2-11 33 16.3/4.5-44 33 16.3/4.4-31 33 16.3/4.2-12 33 16.3/4.3-45 33 16.3/4.4-32 33 16.3/4.2-13 33 16.3/4.3-46 '33 16.3/4.4-33 33 16.3/4.2-14 33 16.3/4.3-47 33 16.3/4.4-34 33 16.3/4.3-3 33 16.3/4.3-48 33 16.3/4.4-35 33
-, 16.3/4.3-2 33 16.3/4.3-49 33 16.3/4.5-1 33 16.3/4.3-3 33 16.3/4.3-50 33 16.3/4.5-2 33 16.3/4.3-4 33 16.3/4.3-51 33 16.3/4.5-3 33 16.3/4.3-5 33 16.3/4.3-52 33 16.3/4.5-4 33 16.3/4.3-6 33 16.3/4.3-53 33 16.3/4.5-5 33 16.3/4.3-7 33 16.3/4.3-54 33 16.3/4.5-6 33 16.3/4.3-8 33 16.3/4.3-55 33 16.3/4.5-7 33 16.3/4.3-9 33 16.3/4.3-56 33 16.3/4.5-8 33 16.3/4.3-10 33 16.3/4.3-57 33 16.3/4.5-9 33 16.3/4.3-11 33 16.3/4.3-58 33 16.3/4.5-10 33 16.3/4.3-12 33 16.3/4.4-1 33 16.3/4.6-1 33 16.3/4.3-13 33 16.3/4.4-2 33 16.3/4.6-2 33 16.3/4.3-14 33 16.3/4.4-3 33 16.3/4.6-3 33 16.3/4.3-15 33 16.3/4.4-4 33 16.3/4.6-4 33 16.3/4.3-16 33 16.3/4.4-5 33 16.3/4.6-5 33 16.3/4.3-17 33 16.3/4.4-6 33 16.3/4.6-6 33 16.3/4.3-18 33 16.3/4.4-7 33 16.3/4.6-7 33 16.3/4.3-19 33 16.3/4.4-8 33 16.3/4.6-7a 33 16.3/4.3-20 33 16.3/4.4-9 33 16.3/4.6-7b 33 16.3/4.3-21 33 16.3/4.4-10 33 16.3/4.6-8 33 16.3/4.3-22 33 16.3/4.4-11 33 16.3/4.6-9 33 16.3/4.3-23 33 16.3/4.4-12 33 16.3/4.6-10 33 ,
16.3/4.3-24 33 16.3/4.4-12a 33 16.3/4.6-11 33 16.3/4.3-25 33 16.2/4.4-12b 33 16.3/4.6-12 33 16.3/4.3-26 33 16.3/4.4-13 33 16.3/4.6-13 33 16.3/4.3-27 33 16.3/4.4-14 33 16.3/4.6-14 33
/
('# ) LOEP -7 3 Revision 33 4 4/81
- , . , . . _ _ r e , - - ,e -- _.--.,,y --- . - - - - - , .r- - ,
MIDLAND 1&2-FSAR LIST OF HFFECTIVE PAGES (continuedJ~ Latest Latest Latest O Sheet 'D Rev. Sheet ID Rev. Sheet ID Rev. 16.3/4.6-15 33 16.3/4.7-26 33 16.3/4.10-5 33 16.3/4.6-14 33 16.3/4.7-27 33 16.3/4.10-6 33 16.3/4.6-17 33 16.3/4.7-28 33 App 16.3/4A Tab 16.3/4.6-18 33 16.3/4.7-29 33 16.3/A-1 33 16.3/4.6-19 33 16.3/4.7-30 33 16.3/A-2 33 16.3/4.6-20 33 16.3/4.7-31 33 16.3/A-3 33 16.3/4.6-21 33 16.3/4.7-32 33 16.3/A-4 33 16.3/4.6-22 33 16.3/4.7-33 33 16.3/A-5 33 16.3/4.6-23 33 16.3/4.7-34 33 16.3/A-6 33 16.3/4.6-24 33 16.3/4.7-35 33 16.3/A-7 33 1G.3/4.6-25 33 16.3/4.7-36 33 16.3/A-8 33 16.3/4.6-26 33 16.3/4.7-37 33 16.3/A-9 33 16.3/4.6-27 33 16.3/4.8-1 33 16.3/A-10 33 16.1/4.6-28 33 16.3/4.8-2 33 16.3/A-11 33 16.3/4.6-29 33 16.3/4.8-3 33 16.3/A-12 33 16.3/4.6-30 33 16.3/4.8-4 20 16.3/A-13 33 16.3/4.6-31 33 16.3/4.8-5 33 16.3/A-14 33 16.3/4.6-32 33 16.3/4.8-6 33 16.3/A-33 33 16.3/4.6-33 33 16.3/4.8-7 33 16.3/A-16 33 16.3/4.6-34 33 16.3/4.8-8 33 16.3/A-17 33 16.3/4.6-35 33 16.3/4.8-9 33 16.3/A-10 33 16.3/4.6-36 33 16.3/4.0-10 33 16.3/A-19 33 16.3/4.7-1 33 16.3/4.8-11 33 16.3/A-20 33 16.3/4.7-2 33 16.3/4.8-12 33 16.3/A-21 33 16.3/4.7-3 33 16.3/4.8-13 33 16.3/A-22 33 16.3/4.7-4 33 16.3/4.8-14 33 16.3/A-23 33 16.3/4.7-5 33 16.3/4.9-1 33 16.3/A ,24 33 16.3/4.7-6 33 16.3/4.9-2 33 16.3/A-25 33 16;3/4.7-7 33 16.3/4.9-3 33 16.3/A-26 33 16.3/4.7-8 33 16.3/4.9-4 33 16.3/A-27 33 16.3/4.7-9 33 16.3/4.9-5 33 16.3/A-28 33 16.3/4.7-10 33 16.3/4.9-6 33 16.3/A-29 33 16.3/4.7-11 33 16.3/4.9-7 33 16.3/A-30 33 16.3/4.7-12 33 16.3/4.9-8 33 16.3/A-31 33 16.3/4.7-13 33 16.3/4.9-9 33 16.3/A-32 33 16.3/4.7-14 33 16.3/4.9-10 33 16.3/A-33 33 16.3/4.7-15 33 16.3/4.9-11 33 16.3/A-34 33 16.3/4.7-16 33 16.3/4.9-12 33 16.3/A-35 33 16.3/4.7-17 33 16.3/4.9-13 33 16.3/A-36 33 16.3/4.7-18 33 16.3/4.9-14 33 16.3/A-37 33 16.3/4.7-19 33 16.3/4.9-15 21 16.3/A-38 33 16.3/4.7-20 33 16.3/4.9-16 21 16.3/A-39 33 16.3/4.7-21 33 16.3/4.9-17 33 16.3/A-40 33 16.3/4.7-22 33 16.3/4.10-1 33 16.3/A-41 33 16.3/4.7-23 33 16.3/4.10-2 33 16,3/A-42 33 16.3/4.7-24 33 16.3/4.10-3 3 16.3/A-43 33 16.3/4.7-25 33 16.3/4.10-4 33 16.5 Tab LOEP- 7 4 Revision 33 4/81
MIDLAND 1&2-FSAR LIST OF EFFECTIVE PAGES (continued) s t Latest Latest Latest Sheet ID Rev. Sheet ID Rev. Sheet ID Rev. 16.5-1 33 17.1-8 33 16.5-2 33 17.1-9 33 16.5-3 33 17.1-10 33 16.5-4 33 17.1-11 33 16.5-3 33 17.1-12 33 16.5-6 33 17.1-13 33 16.5-7 33 17.1-14 33 16.5-8 33 17.1-15 33 16.6 Tab 17.1-16 33 16.6-1 33 17.1-17 33 16.6-2 33 17.1-18 33
, 16.6-2a 33 17.1-19 .33 16.6-2b 33 17.1-20 33 16.6-3 33 17.1-21 33 16.6-4 33 17.1-22 33 16.6-5 33 17.1-23 33 16.6-6 33 17.1-24 33 16.6-7 33 17.2 Tab 16.6-8 33 17.2-1 33 16.6-9 33 17.2-2 33 16.6-10 33 17.2-3 20 16.6-11 33 17.2-4 20 N 16.6-12 33 17.2-5 18 i 16.6-13 33 17.2-6 18 16.6-14 33 17.2-7 18 16.6-15 5 17.2-8 18 16.6-16 33 16.6-17 33 16.6-18 33 16.6-19 33 16.6-20 33 33.6-21 33 16.6-22 33 16.6-23 33 16.7 Tab Chapter 17 Tab 17-i 33 17-ii 33 17-iii 33 17.1 Tab i
17.1-1 33 17.1-2 33 17.1-3 33 17.1-4 33 ' 17.1-5 33
! 17.1-6 33 17.1-7 33 LOEP 75 Revision 33 4/81
MIDLAND 1&2 PSAR s CHAPTER 1 [v) INTRODUCTION AND GENERAL DESCRIPTION OF PLANT TABLE OF CONTENTS Section Title Page
1.1 INTRODUCTION
. . . . . . . . . . . . - . . . . 1.1-1 1.1.1 GENERAL DESCRIPTION . . . . . . . . . . . 1.1 1.1.2 THE FINAL SAFETY ANALYSIS REPORT. . . . . 1.1-2 1.1.2.1 Organization and Format. . . . . . . . . . 1.1-2 1.1.2.2 Approach to Design Bases . . . . - . . . 1.1-3 1.2 GENERAL PLANT DESCRIPTION. . . . . . . . . . 1.2-1 1.2.1 STATION SITE. . . . . . . . . . . . . . . . 1,2-1 1.2.1.1 Location . . . . , . . . . . . . . . . 1.2-1 A
1.2,1.2 Site Ownership . . . . . . . . . . . . 1.2-1 1.2.1.3 Access to Site . . . . . . . . . . . . 1.2-1.
~
l (J ) 1.2.1.4 l.2.2 Site Environs. FACILITY ARRANGEMENT.
- 1. 2'-1 1.2-2 1.2.3 PRINCIPAL DESIGN CRITERIA . . . . . . . . 1.2-4 1.2.3.1 General Criteria . . . . . . . . . . . 1.2-5 1.2.3.2 Site Design Basis Conditions . . . . . 1.2-5 1.2.3.3 Pressure Vessels . . . . . . . . . . . 1.2-6 32 1.2.3.4 Piping, Puraps, Valves, and Heat Exchangers . . . . . . . . . . . . . . ' l.2-6 1.2.3.5 Reactor Design . . .. . . . . . . . . . 1.2-6 t
1.2.3.6 Civil / Structural Design Codes and Standards for Seismic Category I Structures . . . . . . . . . . . . . . 1.2-6 1.2.3.7 Electrical Systems . . . . . . . . . . 1.2-6a l33 1.2.3.8 Protection Systems . . . . . . . . . . 1.2-6a . l30
- 1.2.3.9 Radwaste Systems . . . . . . . . . . . 1.2-7
.i fN 1
V l-i Revision 33 4/81 9 _ , .. .y__ , ,,m,- , , . , , . , , , , ,,,.3 _, ,,..,_c , , , .
r MIDLAND 162-FSAR Table -of- contents (continued)
-Section. Title Page 1.2.3.10 Shielding. . . . . . . . . . . . . . . 1.2-7 1.2.3.11 Emergency Core Cooling Systems . . . . 1.2-8 1.2.4 REACTOR
SUMMARY
DESCRIPTION . . . . . . . 1.2-8 1.2.5 REACTOR COOLANT SYSTEM SUKMARY DESCRIPTION . . . . . . . . . . . . . . . 1.2-9 1.2.6 ENGINEERED SAFETY FEATURES (ESP)
SUMMARY
DESCRIPTION . . . . . . . . . . . . . . . 1.2-10 1.2.6.1 Containment Summary Description. . . . 1.2-10 1.2.6.2 Emergency Core Cooling Systes. Summary Description . . . . . . . . . 1.2-12 1.2.6.3 Auxiliary Feedwater System . . . . . . 1.2-14 1.2.7 SAFETY-RELATED PLANT INSTRUMENTATION AND CONTROLS -
SUMMARY
DISCRIPTION. . . . 1.2-14 1.2.7.1 Introduction . . . . . . . . . . . . . 1.2-15 1.2.7.2 Reactor-Pr9tection System - Summary Description. . . . . . . . . . . . . . 1.2-15 1.2.7.3 Engineered Safety Features Actuation System - Summary Description . . . . . 1.2-15 1.2.7.4 System Required for Safe Shutdown - Summary-Description. . . . . . . . . . 1.2-16 1.2.7.5 Safety-Related Display Instrumen-tation - Summary Description . . . . . 1.2-16 1.2.8 ELECTRICAL POWER SYSTEMS SUEMARY l DESCRIPTION . . . . . . . . . . . . . . . 1.2-16 1.2.8.1 Transmission and Generation Systems Summary Description. . . . . . . . . . 1.2-16 1.2.8.2 Electrical Power Distribution Systems Summary Description. . . . . . . . . , 1.2-17 1.2.9 AUXILIARY SYSTEMS
SUMMARY
DESCRIPTIONS. . 1.2-17 Revision 30 i 10/80 1-ii {
MIDLAND 162-FSAR N Table of contents icontinued) i Section Title _ Page 1.2.9.1 Puel Handling and Stcrace - Summary ' Description. .... ......... 1.2-17 1.2.9.2 Water Systems Summary Description. . . 1.2-18 1.2.9.3 Process Auxiliary Systems Summarv l Description. ............ . 1.2-19 L 1.2.9.4 Ventilation systems-Summary Description. ............ . 1.2-19 l 30' r 1.2.9.5 Diesel Generator Puel Oil-System i Summary. . ........ . . . . . . 1.2-21 l30 1.2.10 STEAM AND POWER CONVERSION SYSTEM
SUMMARY
DESCRIPTION . . ......... 1.2-22 1' 1.2.11 RADIOACTIVE WASTE MANAGEMENT. . . . . . . 1.2-23 1.2.12 PROCESS STEAM SYSTEM
SUMMARY
DESCRIPTION . ............. . 1.2-23 l30 i 1.3 COMPARISOM-TABLES. .... ......... 1.3-1 1.3.1 COMPARISON WITH SIMILAR FACILITY DESIGNS. 1.3-1 ! 1.3.2 COMPARISON OF FINAL AND PRELIMINARY INFORMATION . ........ . . . .. . . 1.3-1 1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS . . 1.4-1 . 1.4.1 APPLICANT . . . .. . . ......... 1.4-1 1.4.2 ARCHITECT - ENGINEER. . ......... 1.4-1 1 l 1.4.3 NUCLEAR STEAM SUPPLY SYSTEM MANUFACTURER. 1.4-2 1.4.4 CONSULTANTS AND OUTSIDE CONTRACTORS . . . 1.4-2 ! 1.4.5 DIVISION OF RESPONSIBILITY. . . . . .. . 1.4-5 33 1.4.5.1 Applicant / Owner. . . ......... 1.4-5 e 1.4.5.2 Plant Architect / Engineer-Constructor.. 1.4-5 30 1.4.5.3 Nuclear Steam Supply System (NSSS1 Supplier . . ..... . . . . . . . . 1.4-5 4. 1-111 Revision 33 4/81 i
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MIDLAND 162-FSAR Table of-Contents (continued) g Section. Title _ Page 1.4.5.4 Turbine-Generator Supplier . . . . . . 1.4-5 1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATIoM. . . . . . . . . . . . . . . . . 1.5-1 1.5.1 XENON OSCILLATIONS. . . . . . . . . . . . 1.5-1 1.5.2 THERMAL HYDRAULIC PROGRAMS. . . . . . . . 1.5-1 1.5.3 FUEL ROD CLAD FAILURE . . . . . . . . . . 1.5-1 1.5.4 INTERNAL VENT VALVES, . . . . . . . . . . 1.5-1 1.5.5 CONTROL ROD DRIVE LINE TEST . . . . . . . 1.5-2 1.5.6 ONCE-THROUGH STEAM GENERATOR TEST . . . . 1.5-2 1.5.7 SELF-POWERED DETECTOR TESTS . . . . . . . 1.5-2 1.5.8 BLOWDOWN FORCES ON INTERNALS AND CORE. . 1.5-3 1.6 MATERIAL-INCORPORATED BY REFERENCE . .. . . 1.6-1 ! 1.7 ELECTRICAL, INSTRUMENTATION, AND CONTROL DRAWINGS . . . . . . . . . . . . . . . . . . 1. 7 - 1 l 1.7.1 BOP ELECTRICAL DRAWINGS . . . . . . . . . 1. 7- 1 1.7.2 BOP INSTRUMENTATION AND CONTROL DRAWINGS. 1. 7 - 1 1.7.3 DRAWINGS SUB?;ITTED BY NSSS VENDOR . . . . 1.7-2 l l 1 Revision 30 1-iv 10/80 l l
MIDLAND 162-FSAR
- 1. INTRODUCTION AND GENERAL DESCEIPTION OF PLANT
/~N
(.
1.1 INTRODUCTION
This final safety analysis report (FSAR) is subt.itted pursuant to the Atomic Energy Act of 1954, as amended (the act) , and the regulations of the Nuclear Regulatory Commission set forth in Part 50 of Title 10 of the Code cf Federal Regulations in support of the application of Consumers Power Ccmpany (CPCo) , the applicant, for a Class 103 license to acquire, possess, and use . Midland Plant Units 1 and 2 located partially within the city of 1 Midland in Midland County, Michigan. 1.1.1 GENERAL DESCRIPTION Unit 1 and Unit 2 each consist of a pressurized water reactor, a turbine-generator, and associated auxiliaries. Unless specifically stated otherwise, discussions and design parameters included in this safety analysis report refer to Unit 1. Unit 2 is identical except as noted. Shared items are so identified. Units 1 and 2 are sometimes referred to as the facility. The facility will be located along the south shore of the Tittabawassee River south of the city of Midland, Michigan. The site is adjacent to the Dow Chemical company's (Dow) pain industrial complex in Midland. The location is shown in Figures () 2.4-1 and 2.4-2. The facility consists of two units having a total combined capability of approximately 1,300MWe and 4 x 100 lb/hr of process steam. The process steam will be supplied to Dow and the electricity will be supplied to CPCc's system. The containment for the nuclear steam supply system (NSSS) is a post-tensioned, reinforced concrete structure with a steel liner to provide leaktightness. The centainment is designed and constructed by Bechtel Power Corporation (Bechtel) . The NSSS is a pressurized water reactor type manufactured by the Babecck & Wilcox company (E6W) . i The reactor core is rated for an output of 2,452MWt which is de-1 fined as the rated output in the licensing application. When the reactor coolant pump heat input of 16MWt is added to the core output, the resulting rated NSSS output is 2,468MWt. The expected maximum core output is 2,552MWt with an expected NSSS output of 2,568MWt. Analysis of possible of f site radiological consequences of postulated design basis accidents uses an assumed core power of 2,552MWt. The Unit 1 turbine-generator is rated for operation at the NSSS rated output of 2,468MWt with a correspcnding electrical output f% () 1.1-1 hevision 1 11/77
MIDLAND 1&2-FSAR of 504.8MWe. Process steam is provided to Dow by using extraction steam from the high-pressure turbine under normal operation, and main steam from the main steam header. The Unit 1 turbine-generator has a maximum calculated design capability of 595.2MWe assuming an input of 2,46SMWt with a corresponding' steam flow to Dow of approximately 2.5 x 10 6 lb/hr. About 4 x 10 lb/hr of process steam can be provided to Dow at the Unit 1 turbine-generator rated level of 504.8MWe. The Unit 2 turbine-generator is rated for operation at the NSSS rated output of 2,468MWt with a corresponding electrical output of 852MWe. The Unit 2 turbine-generator has a maximum calculated design capability of 886MWe assuming an input of 2,568MWt which is approximately 104% of the rated steam flow. The turbine-generators for both Units 1 and 2 are being supplied by the General Electric Company. Unit 1 construction completion and initiation of fuel loading is scheduled for December 1983, and commercial operation is scheduled for July 1984. Unit 2 construction completion and 33 initiation of fuel loading is scheduled for July 1983, and commercial operation is scheduled for December 1983. 1.1.2 THE FINAL SAFETY ANALYSIS REPORT 1.1.2.1 Organization and Format This final safety analysis report (FSAR) for the Midland facility I adheres to Regulatory Guide 1.70, Standard Format and Content of Safety Aaalysis Reports for Nuclear Power Plants, Revision 2, preparFJ by the office of Standards Development of the U.S. Nuclear Regulatory Commission and issued in' September 1975, except as noted in the text, per agreement with the NRC in the June 2, 1976 letter from R.S. Boyd of the NRC to S.H. Howell of
- CPCo, The FSAR is paginated to provide flexibility when incorporating changes to text and figures. All text, tcLle, and figure pages are numbered in accordance with Regulatory Guide 1.70 Revision 2 requirements; e.g., Page 1.1-1 is the first page of Section 1.1.
Tables and figures are numbered in a similar manner; e.g., Table 1.1-1 is the first table in Section 1.1. Tables and figures are placed at the end of each two digit section. In some cases, appendixes are included at the end of a chapter to provide supplemental information. Topical reports and other documents referenced in the text are listed at the end of each section. Topical reports and other documents incorporated into the application by reference '.re also listed in Section 1.6. 1.1-2 Revision 33 4/81
MIDLAND 1&2 - FSAR TABLE 1.1-1 PART 1 (continued) FSAR Bechtel Fig. No. FSAR Figure Title Dwg. No. f b 6.2-131 Reactor Vessel Pressurg Differential N/A Response for a 4.27 ft Cold Leg Break 6.2-132 Reactor Vessel Pressure Differential N/A Response for a 4.27 ft 2 Cold Leg Break 14 6.2-133 Reactor Vessel Pressure Differential N/A Response for a 4.27 ft2 Cold Leg Break 6.2-134 Reactor Vessel Pressure Differential N/A Response for a 4.27 ft 2 Cold Leg Break 6.2-135 Primary Shield Plug Detail C-370 6.2-136 Reactor Building Spray Solution Flow Path' N/A to Containment Sump During Recirculation 15 6.2-137 Temperature History - Containment Liner N/A
& Wall for Maximum Containment Atmospheric Temperature 6.2-138 Illustration of Jet Area Directed into N/A I9 Reactor Vessel Cavity for Subcompartment i
() 6.3-1 Sh 1 Pressurization Makeup and Purification Units 1 & 2 M-7v3 Sh 1 f 27 6.3-1 Sh 2 Makeup and Purification Units 1 & 2 M-703 Sh 2 6.3-2 Decay Heat Removal and Core Flooding M-710 System Units 1 & 2 6.3-3 HPI Flow vs RCS Pressure N/A 6.3-4 LPI Flow vs RCS Pressure N/A 6.3-5 HPI Pump Performance Curves N/A 3 6.3-6 HPI Flow Splits for HPI Line Break Affected N/A Train i l 6.4-1 Definition of Control Room Envelope M-525 Sh 3 6.4-2 Definition of Control Room Envelope ' M-525 Sh 4 i 6.4-3 Control Room Equipment Arrangement J-725 l 6.4-4 HVAC Area 3 Auxiliary Building M-527 Sh 3
- Equipment Room Plan at El 685'-0" 33 h(N (sheet 49)
Revision 33 4/81 , l
. . . ., . . - - . , , , , ..c , . - . - - . - , - - ~ . , - -
MIDLAND 1&2 - FSAR TABLE 1.1-1 PART 1 (continued) FSAR Bechtel Fig. No. FSAR Figure Title Dwg. No. 6.5-1 Hydrogen Vent Exhaust System Inside M-531 Sh 3 Containment 6.5-2 Hydrogen Vent Exhaust Piping Outside the M-527 Sh 2 Containment 6.8-1 This figure has been deleted. ' 6.8-2 This figure has been _eleted. 6.8-3 Reactor Building Penetration M-421 Sh 1 Pressurization Unit 1 6.8-4 Reactor Building Penettation M-421 Sh 2 Pressurization Unit 1 20 6.8-E Reactor Building Penetration M-421 Sh 3 Pressurization Unit 1 6.8-6 Reactor Building Penetration M-422 Sh 1 Pressurization Unit 2 6.8-7 Reactor Building Penetration M-422 Sh 2 Pressurization Unit 2 6.8-8 Reactor Building Penetration M-422 Sh 3 Pressurization Unit 2 6D-1 Maximum Steam Generator Cavity Differential N/A Pressure as a Function of Number of Nodes for Worst Case Hot Leg Break 6D-2 17 Node Model of Steam Generator N/A g Compartment for Nodal Sensitivity Study 6D-3 21 Node Model of Steam Generator N/A Compartment for Nodal Sensitivity Study 6D-4 25 Node Model of Steam Generator N/A Compartment for Nodal Sensitivity Study 6D-5 34 Node Model of Steam Generator N/A l Compartment for Nodal Sensitivity Study 6D-6 22 Node Model of Reactor Vessel Cavity for N/A Node Sensitivity Study 19 O (sheet 50) Revision 20 4/79
MIDLAND 1&2 - FSAR TABLE 1.1-1 PART 1 (continu-d) FSAR Bechtel Fig. No. FSAR Figure Title Dwg. No. C! 6E-42 Lateral Forces on Reactor Coolart Pump N/A Adjacent to Pressurizer Due to a 4.27 ft2 Ptimp Discharge Break 6E-43 Moments on Reactor Coolant Pump Adjacent N/A to Pressurizer Due to a 4.27 ft2 Pump 26 Discharge Break - 6E-44 Uplift Force on Reactor Coolant Pump N/A Adjacent to Pressurizer Due to a 4.27 ft2 Pump Discharge Break 6E-45 Section and Plan View of Seal Plate N/A 7.1-1 Isolation Device Schematic N/A l15 7.2-1 Reactor Protection System N/A 7.2-2 Typical Pressure Temperature Boundaries N/A 7.2-3 Typical Power Trip Based on Imbalance and N/A Flow Function ( 7.2-4 Reactor, Trip Switch Schematic and Parts List N/A 16 7.2-5 Reactor Coolant Flow Measurement N/A Sensor to Process Connections 7.3-1 Deleted N/A l33 7.3-2 Engineered Safety Features Actuation J-299 Sh 1 System - RBIS-II, RBSAS, RBCAS, and RBIS-I 7.3-3 Engineered Safety Features Actuation J-299 Sh 2 System - MSLIS 7.3-4 Engineered Safety Features Actuation J-29? Sh 2 System - AFWAS, RAS, Loss of R.C. Pump - 7.3-5 Engineered Safety Features Actuation J-299 Sh 4 ' System - CRIS 7.3-6 Engineered Safety Features Actuation J-299 Sh 5 13 System - D.G. Start, LOP /ECCAS feq. (sheet 50e) Revision 33 4/81
MIDLAND 1&2 - FSAR TABLE 1.1-1 PART 1 (continued) FSAR Bechtel Fig. No. FSAR Figure Title Dwg. No. 7.3-7 Engineered Safety Features Actuation J-299 sh 6 System - F.P.V.A.S. 7.3-8 Engineered Safety Features Actuation J-299 Sh 8 System - ECCAS, Sig Cond Cabl.7ets 7.3-9 Engineered Safety Features Actuation J-299 Sh 9 System - Reverse Feedwater from Steam Generators A & B 18 7.3-10 Typical Block Diagram of the RFFMS for N/A One Main Feedwater Line 7.4-1 Control Rod Drive Control System N/A l1 7.7-1 Integrated Control System N/A 7.7-2 Unit Load Demand Control, Integrated N/A Control System 7.7-3 Integrated Master Control, Integrated N/A Control System 7.7-4 Steam Generator-Feedwater Control System N/A l13 7.7-5 Reactor Control Integrated Control System N/A 7.7-6 Evaporator Steam Demand Development N/A 7.7-7 ICS Configuration for Croscover Operation N/A 7.7-8 Process Steam Transfer System - Mode 1 J-590 1 7.7-9 Process Steam Transfer System - Mode 2 J-591 l l 7.7-10 Process Steam Transfer System - Mode 3 J-592 7.7-11 Deleted l30 l 7.7-12 Control Logic Pressurizer Heater Bank N/A 13 2, 3, 4 7.8-1 Nuclear Instrumentation System Figure N/A l12 7.8-2 Nuclear Instrumentation Flux Range Figure N/A 7.8-3 Nuclear Instrumentat7:n Detector Locations N/A Figure (sheat 50f) Revision 30 10/80
MIDLAND 1&2 - FSAR TABLE 1.1-1 PART 1 (continund) FSAR Bechtel y Fig. No. FSAR Figure Title , Dwa. No. I ( 8.3-13 Time-Current Characteristics Protection N/A System and Penetration Assembly - Low Voltage Power 8.3-14 Time-Current Characteristics Protection N/A System and Penetration Assembly - Low Voltage Power 8.3-15 Time-Current Characteristics Protection N/A System and Penetration Assembly - Low Voltage Power 8.3-15A Time-Current Characteristics Protection N/A System and Penetration Assembly - Low 20 Voltage Power 8.3-16 Time-Current Characteristics Protection N/A System and Penetration Assembly - Low Voltage Power 8.3-17 Time-Current Characteristics Protection N/A Gystem and Penetration Assembly - Low
-s Voltage Power \~- 8.3-18 Time-Current Characteristics Protection N/A System and Penetration Assembly - Low Voltage Power 8.3-19 Time-Current Characteristics Protection N/A System and Penetration Assembly - Low Voltage Power 8.3-20 Time-Current Characteristics Protection N/A l
System and Penetration Assembly - Low Voltage Power 8.3-21 Time-Current Characteristics Protection N/A
- System and Penetration Assembly - Low l Voltage Power l
l 8.3-22 Time-Current Characteristics Protection N/A System and Penetration Assembly - Low Voltage Power 8.3-23 Time-Current Characteristics Protection N/A i System and Penetration Assembly - Low ! Voltage Power I O (sheet 53) Revision 27 3/80 \ -- _ __ _
MIDLAND 1&2 - FSAR TABLE 1.1-1 PART 1 (continued) PSAR Bechtel Fig. No. FSAR Figure Title Dwg. No. 8.3-24 Time-Current Characteristics Protection N/A System and Penetration Assembly - Low Voltage Power 8.3-25 Tine-Current Characteristics Protection N/A System and Penetration Assembly - Low Voltage Power 8.3-25A Time-Current Characteristics Protection N/A System and Penetration Assembly - Low 30 Voltage Power 8.3-26 Time-Current Characteristics Protection N/A System and Penetration Assembly - Low Voltage Power 8.3-27 Time-Current Characteristics Protection N/A System and Penetration Assembly - Low Voltage Power 8.3-28 Time-Current Characteristics Protection N/A System and Penetration Assembly - Low Voltage Control l 8.3-29 Time-Current Characteristics Protection N/A System and Pene* ration Assembly - Low Voltage Power 8.3-29A Time-Current Characteristics Protection N/A 30 System and P( netration Assembly - Low Vol tage Control l 33 30 8.3-?9B Time-Current Characteristics Protection N/A System and Penetration Assembly - Low Voltage ' Control l 33 30 8.3-29C Time-Current Characteristics Protection N/A System and Penetration Assembly - Low 33 Voltage Control g 8.3-29D Time-Current Characteristics Protection N/A 30 System and Penetration Assembly - Low Voltage Control i 33 8.3-29E Time-Current Characteristics Protection N/A 30 System and Penetration Assembly - Low Voltage Control l 33 O (sheet 54) Revision 33 4/81
MIDLAND 1&2 --FSAR TABLE 1.1-1 PART 1 (continund) FSAR Bechtel Fig. No. FSAR Figure Title Dwg. No.
~3 8.3-29F Time-Current Characteristics Protection N/A System and Penetration Assembly - Low 30 Voltage Control l 33 8.3-30 Time-Current Characteristics Protection N/A System and Penetration Assembly - Low Voltage Control
- i j 8.3-31 Time-Current Characteristics Protection N/A System and Penetration Assembly - Low Voltage Control 8.3-32 Time-Current Characteristics Protection N/A System and Penetration Asserably - Low 1 Voltage Control 8.3-32A Tise-Current Characteristics Protection N/A System and Penetration Assembly - 3 CRD Stator 8.3-37 Typical Synchronizer Input Circuit from a N/A Diesel Generator and its Associated Class 12 lE 4160V Bus l13 8.3-38 Typical Synchronizer output Circuit for N/A i
Class lE Breaker Control , 8.3-39 Single Line.Diagran 250 and 125VDC E-21 13 l Systems Unit 1 e l i l l l l i (sheet 54a) Revision 3 3 4/81-
MIDLRND 1&2-FSAR O THIS PAGE INTENTIONALLY LEFT BLANK i l l (sheet 54b) ! Revision 30 l 10/80 ! _ _u
MIDLAND 1&2 - FSAR TABLE 1 1-1 PART 1 (continued) ,
/~ FSAR Bech tel k ,h/ Fig. No FSAR Figure Title Dwg. No 2,
8.3-40 Single L'7e Diagram 250 and 125VDC' E-22 13 Systems Unit 2 8.3-41 Deleted 1 33 8.3-42 Deleted 8.3-43 Diesel Generator Local Control Panel J-877 Sh 1 18 Alarms 8 3-44 Logic Diagram Diesel Generators J-877 Sh 2 8.3-45 Logic Diagram Tilesel GeneratoTs J-879 Sh 1 8.3-46 Logic Diagram Diesel Generators J-879 Sh 2 8.3-47 Logic Diagram Diesel Generators J-879 Sh 3 8.3-48 Logic Diagram Diesel Generators . J-879 Sh 4 33 8.3-49 Logic Diagram Diesel Generators J-879 Sh 5
/N Logic Diagram Diesel Generators J-879-Sh.6
() 6.3-50 8.3-51 Logic Diagram Diesel Generators J-879 Sh 7 8.3-52 Logic Diagram Diesel Generators J-879 Sh 8 8.3-53 Logic Diagram Diesel . Generators J-880 8.3-54 Single Line Diagram - Separation Group E N/A { 20 8.3-55 Reactor Coolant Pumps Load J-884 Sh 2 Shedding to Prevent Startup 33 Transformer Overload 9.1-1 Sh 1 Fuel Pool Cooling and Purification M-41' 7
- 9.1-1 Sh 2 Fuel Pool Cooling and Purification M-414B 9.1-2 New Fuel Handling Tool N/A 9.1-3 R.V. Closure Head Handling N/A l13 9.1-4 Reactor Internals (Plenum) Handling N/A 9.1-5 Fuel Handling Bridge N/A l \ 9.1-6 Fuel Transfer System N/A d
9.1-7 New Fuel Elevator N/A 1 (she.et Revision 55)33 4/81 . . - -. . .
MIDLAND 1&2 - FSAR TABLE 1.1-1 PART 1 (continuedl FSAR Bechtel Fig. No. FSAR Figure Title Dwg. No. 9.1-8 Rod Handling Container Assembly N/A 9.1-9 Rod Assembly Handling Tool N/A 9.1-10 Typical Double Yoke Concept Cask Lifting N/A Rig 9.1-11 Cask Drop into Railroad Bay N/A 9.1-12 Cask Drop into Cask Washdown Area N/A 9.1-13 Cask Drop into Cask Loading Pit N/A 9.1-14 Fuel Pool Liner Plate Attachments N/A l14 9.1-15 Spent Fuel Pool Storage Racks N/A Plan Arrangement 19 9.1-16 Spent Fuel Pool Storage Rack N/A Assembly 9.2-1 Schematic Diagram Service Water System N/A 9.2-2 Sh 1 Service Water Cooling Tower and Pump M-418A Structure Units 1 % 2 v.2-2 Sh 2 Service Water Cooling Tower and Pump M-418B Structure raits 1 & 2 9.2-3 Sh 1 Service Water Reactor and Auxiliary M-419A Building Units 1 & 2 9.2-3 Sh 1 Service Water Reactor and Auxiliary M-419A Buildings Units 1 & 2 9.2-4 Sh 1 Service Water Turbine Building Unit 1 M-420 Sh 1A 9.2-4 Sh 2 Service Water Turbine Building Unit 2 M-420 "h 1 B 9.2-5 Service Water Turbine Building Units 1&2 M-420 Sh 2 9.2-6 Service Water Pump Impeller Elesction N/A 9.2-7 Sh 1 Component Cooling Water Unit 1 M-416 Sh 1A 9.2-7 Sh 2 Component Cooling Water Unit 1 M-417 Sh 1B 27 9.2-8 Sh 1 Component Cooling Water Unit 1 M-416 Sh 2A 9.2-8 Sh 2 Component Cooling Water Unit 1 M-416 Sh 2B (sheet 56) Revision 27 3/80
l MIDLAND 1&2 - FSAR TABLE 1.1-1 PART 1 (continued) I FSAR Bechtel Fig. No. FSAR Figure Title Dwg. No. 9.5-22 Deleted - 25 ! 9.5-23 Deleted 4 9.5-24 Sh 1 Single Line Diagram Lighting Distribution E-551 Sh 1 27 9.5-24 Sh'2 Single Line Diagram-Lighting Distribution E-551- Sh 2 9.5-25 Sh 1 Emergency Diesel Generator Fuel Oil- M-452 Storage and Transfer System Units 1 & 2 Sh LA 33 9.5-25 Sh 2 Emergency Diesel Generator Fuel < Oil M-452 Sh is
, Storage and Transfer System Units 1 & 2 9.5-26 Emergency Diesel Generator Cooling Water N/A System 9.5-27 Energency Diesel Generator Starting System N/A
! 9.5-28 Emergency Diesel Generator Lubrication N/A System
- () 9.5-29 Sh 1 Chemical and Oily Waste System M-470 Sh 2A I
9.5-29 Sh 2 Chemical and Oily Waste System M-470 Sh 23 26
- 9.5-30 Sh 1 Chemical and Oily Waste System M-470 Sh 1A P
9.5-30 Sh 2 Chemical and Oily Waste System M-470 Sh 1B 9.5-31 Emergency Diesel Engine Fuel Oil Piping N/A 13 Schematic 9.5-32 Emergency Diesel Fuel Oil Piping from N/A 15 Storage Tanks to and from Day Tanks 9.5-33 Single Line. Diagram Evacuation System E-557 Sh 1 30 9.5-34 Single Line Diagram Evacuation System E-557 Sh 2 9A-1 Fire Protection.- Circulating Water A-114 Intake Structure and: Chlorination Building
- Floor Plans at El 600'-0" and 634'-8" 24
! 9A-2 Fire Protection - Service Water Pump A-115 Structure Plans and Section I (sheet 62a) Revision 33 l 4/81
MIDLAND 1&2 - FSAR-TABLE 1.1-1 PART 1__(continued) FSAR Bechtel Fig. No. FSAR Figure Title Dwg. No. 9A-3 Fire Protection - Diesel Generator Building A-118 Plan and Sections 9A-4 Fire Protection - Reactor and Auxiliary A-120 Buildings Plan at El 5688-0" 9A-5 Fire Protection - Reactor and Auxiliary A-121 Building Plan at El 584'-0" 9A-6 Fire Protection - Reactor and Auxiliary A-122 Buildings Plan at El 599'-0" 9A-7 Fire Protection - Reactor and Auxiliary A-123 Buildings Plan at El 614'-0" 9A-8 Fire Protection - Reactor and Auxiliary A-124 Buildings Plan at El 614'-0" 9A-9 Fire Protection - Reactor and Auxiliary A-125 Buildings Plan at El 646'-0" 9A-10 Fire Protection - Reactor and Auxiliary A-126 Buildings Plan at El 659'-0" 9A-ll Fire Protection - Reactor and Auxiliary A-127 Buildings Plan at El 673'-6" and 685'-0" 9A-12 Fire Protection - Auxiliary Building Solid A-128 Sh 1 Radwaste and Railroad Bay 9A-13 Fire Protection - Equipment Location - A-128 Sh 2 Solid Radwaste Building 25 9A-14 Fire Protection - Auxiliary Building A-129 Section A-A 9A-15 Fire Protection - Auxiliary Building A-130 Section E-E 9A-16 Fire Protection - Auxiliary Building A-131 Section F-F 9A-17 Fire Protection - turbine Building Unit 1 A-132 Plan at El 614'-0" 9A-18 Fire Protection - Turbine Building Unit 1 A-133 Plan at El 634'-6" (sheet 62b) Revision 27 3/80
MIDLAND.1&2 - FSAR TAPLE'l.1-1 PAPT 1-(continued) ,
/) PSAR ~ Bechtel \s) rio. No. FSAR-Fiaure Title Dwg. No.
10.3-4 Sh 2' Fain-Stean &' Turbine Stean - Unit 2 M-432.Sh 2B l 32 10.3-5 t'ain Stean Line' Isolation Valves - JN/A Actuator - Hydraulic Circuit j
'10.3-6 Main Stean Line Isolation' Valves - .N/AL Logic.Diagran 10.4-1 Sh 1 Auxiliary Stean Systen'- Unit 1 'M-433A 10.4-1 Sh'2. Auxiliary Stean Systen'- Unit-:l' .M-433B
. :2 6 -
10.4-2 Sh 1 Auxiliary Stean Systen-- Unit 2 -M-434A 10.4-2 Sh 2 Auxiliary Stean Systen - Unit 2' ;M-434B.- M-446A-10.4-3 Sh 1 Circulating Water - Units 1 & 2' 27 10.4-3 Sh 2 Circulating Water - Units 1 & 2 M-446B
-s 10.4-3 Sh 3 Circulating Water - Units 1 &L2 M-446C l 32 .x_, 10.4-4 Sh 1 Condensate Denineralizer Systen - Unit 1 M-440A 10.4-4 Sh 2 Condensate Denineralizer Systen - Unit 1 M-440B 10.4-5 Sh 1 Condensate Denineralizer. Regeneration - M-441A Unit 1 .
10.1-5 Sh 2 Condensate Denineralizer Regeneration - M-441B' , Unit i 10.4-6 Sh 1 Condensate Denineralizer Systen - Unit 2 M-442A-26 10.4-6 Sh 2 Condensate Denineralizer Syster - Unit 2 M-442B: { 10.4-7 Sh 1 Condensate Denineralizer Regeneration - M-443A_ Unit 2 10.4-7 Sh 2 Condensate Denineralizer Regeneration - M-443B Unit 2 10.4-8 Sh 1 Condensate and Feedwater Systen - Unit l' M-438 Sh 1A 10.4-8 Sh 2 Condensate and Feedwater Systen - Unit.1 M-438 'Sh IB ..f r 10.4-9 Sh 1 Condensate and Feedwater Systen - Unit 1 M-438 :Sh 2A-D
- - .(sheet 62e)
Revision 32- [ 1/81
MIDLAND 1&2 - FSAR , TABLE 1.1-1 PART 1 (continued) FSAR Bechtel Fig. No. FSAR Figure Title Dwg. No. 10.4-9 Sh 2 Condensate and Feedwater System - Unit 1 M-438 Sh 2B 10.4-10 Sh 1 Condensate and Feedwater System - Uni t 1 M-438 Sh 3A 10.4-10 Sh 2 Condensate and Feedwater System - Unit 1 M-438 Sh 3B 10.4-10 Sh 3 Condensate and Feedwater System - Unit 1 M-438 Sh 4 10.4-11 Sh 1 Condensate and Feedwater System - Unit 2 M-439 Sh 1A 10.4-11 Sh 2 Condensate and Feedwater System - Unit 2 M-439 Sh 1B 26 10.4-12 Sh 1 Condensate and Feedwater System - Unit 2 M-439 Sh 2A 10.4-12 Sh 2 Condensate and Feedwater System - Unit 2 M-439 Sh 2B 10.4-13 Sh 1 Condensate and Feedwater Syst.em - Unit 2 M-439 Sh 3A 10.4-13 Sh 2 Condensate and Feedwater System - Unit 2 M-439 Sh 3B 10.4-13 Sh 3 Condensate and Feedwater System - Unit 2 M-439 Sh 4 10.4-14 Sh 1 Plant Heating Auxiliary and Reactor M-456 Sh 2A Buildings 32 10.4-14 Sh 2 Process Steam Evaporator System M-462 Sh 1B 10.4-15 Sh 1 Process Steam Evaporator System M-461 Sh 2A 27 10.4-15 Sh 2 Process Steam Evaporator System M-461 Sh 2B 10.4-15 Sh 3 Process Steam Evaporator System M-461 Sh 2C l 33 10.4-16 Sh 1 Process Steam Evaporator System M-461 Sh 3A 10.4-16 Sh 2 Process Steam Evaporator System M-461 Sh 3B 10.4-17 Sh 1 Process Steam Evaporator System M-461 Sh 4A 26 10.4-17 Sh 2 Process Steam Evaporator System M-461 Sh 4B 10.4-18 Sh 1 Process Steam Evaporator System M-461 Sh 5A 10.4-18 Sh 2 Process Steam Evaporator System M-461 Sh 5B 10.4-19 Sh 1 Process Steam Evaporator System M-461 Sh 6 l 14 10.4-19 Sh 2 Process Steam Evaporator System M-461 Sh 7 l 26 (sheet 62f} Revision 33 4/81
T i MI DLAND 1 & 2 - FS AR TApLE 1.1-1 PART l_(continued) _ Bechtel if'- ' FSAR Fig. No. FSAR Figure Title Dwg. No. ( 10.4-19 Sh 3 Process Steam Evaporator System M-461 Sh 8
-M-460
~
10.4-20 -Process Steam, Supply and Return System Sh 1 10.4-21 Sh 1 Procesc Steam, Supply'and Return system ~ M-460 Sh 2A 10.4-21 Sh 2 Process Steam, Supply and Return System M-460' Sh12B 26 l 10.4-22 Sh 1 Process Steam, Supply and Return System M-460 Sh 3A 10.4-22 Sh 2 Process Steam, Supply and Return System M-460 Sh 3B i 10.4-22A Process Steam, Supply and Return System M-460 Sh 4 i 10.4-23 Process Steam Heat Balance N/A 10.4-24 Cooling Pond Blowdown and' Makeup-System M-464 10.4-25 Sh l' Feedwater Chemical Addition System M-444A 10.4-25 Sh 2 Feedwater Chemical Addition System M-444B O N- 10.4-26 Sh 1 Auxiliary Steam Boiler System M-430 Sh 1A 27
, 10.4-26 Sh 2 Auxiliary Steam Boiler System M-430 Sh.lB 10.4-27 Auxiliary Steam Boiler System M-430 Sh 2 10.4-28 Sh 1 Auxiliary Steam Boiler System M-430 Sh 3A 10.4-28 Sh 2 Auxiliary Steam Boiler System M-430 Sh 3B 11.2-1 Sh 1 Liquid Waste Units 1 & 2 M-407 Sh 1A l
l 11.2-1 Sh 2 Liquid Waste Units 1 & 2 M-407 Sh 1B 26 l 11.2-2 Sh 1 Liquid Waste Units 1 & 2 M-407 Sh 2A l i 11.2-2 Sh 2 Liquid Kaste Units 1 & 2 M-407 Sh 2B
- 11.2-3 Sh 1 Liquid Waste Units 1 & 2 M-407 Sh 3A 11,2-3 Sh 2 Liquid Waste Units 1 & 2 M-407 Sh 3B l.
11.2-3A Sh 1 Liquid Waste Units 1 & 2 M-407 Sh 4A g 11.2-3A Sh 2 Liquid Waste Units 1 & 2 M-407 Sh 4B i l m.) ! (sheet 629) Revision 33 4/81
MIDLAND 1&2 - FS AR TABLE 1.1-1 PART 1 (continued) FSAR Bechtel Fig. No. FSAR Figure Title Dwg. No. 11.2-4 Liquid Waste Evaporator M-427 11.2-5 Boron Recovery System Block Diagram N/A 11.2-6 Liquid Waste System Block Diagram N/A 11.3-1 Potential Sources of Gaseous Releases N/A O l I l l l O (sheet 6 2h) Revision 33 4/81
MIDLAND l&2 - FSAR TABLE 1.1-1 PART 2 (continued) T Bechtel FSAR {/ s_ Dwg. No. FSAR Figure Title Fig. No. C-654 Reactor Building Unit 2 - Steel Framing 3.8-45A 12 Plan at El. 685'-0" C-663 Missile Shield 3.8-47 13 C-666 Refueling Canal & Liner Plat Plait and 3.8-43 Sections ; 9 C-676 Reactor Coolant System Pipe Restraints 3.8-34 C-S30 Auxiliary Building Tornado Missile 3.5-6 Protection Plan Near Roof 15-C-831 Auxiliary Building Tornado Missile 3.5-7 l-Protection - Typical Section l C-836 Linear Component Support Attachments 3.8-64 (Sheet 1) 21 C-836 Linear Component Support Attachments 3.8-65 (Sheet 2) () C-997 Benchmark Locations for Subsidence Monitoring Program 2.5-88 C70-94 Linear Component Support Attachments 3.8-64 '15 (Sheet 1) C70-261 Linear Component Support Attachments 3.8-64 (Sheet 1) E-1 Plant Single Line 8.3-1 E-21 Single Line Diagram 250 and 125VDC 8.3-39 3 Systems Unit 1 E-22 Single Line Diagram 250 and 125VDC 8.3-40 13 Systems Unit 2 E-23 Sh 1 Single Line Diagram 120VAC Control, 8.3-2 Sh l' Instrument and Preferred Power System Unit 1 and Common 33 E-23 Sh 2 Single Line Diagram 120VAC Control, 8.3-2 Sh 2-Instrument and Preferred Power System Unit 1 and Common O (sheet 86a) Revision 33 , 4/81 1
MIDLAND 1&2 - FSAR TABLE 1.1-1 PART 2 (continued) Bechtel FSAR Dwg. No. FSAR Figure Title Fig. No. E-24 Sh 1 Single Line Diagram 120VAC Control, 8.3-3 Instrument and Preferred Power System 13 Unit 2 and Cormon E-551 Sh 1 Single Line Diagram Lightine Distribution 9.5-24 Sh 1 l 19 e i O (sheet 86b) Revision '.7 3/80
MIDLAND 1&2 - FSAR T _ABLE 1.1-1 PART 2 (continued) A Bechtel FSAR Dwg. No. FSAR Figure Title Fig. No. J-299 Sh 9 Eng.ircared Safety Features Actuation _ 7.3-9 l18 System - Reverse Feedwater From Steam 15 i
)
Generators A & B l J-590 Process Steam Transfer System - Mode 1 7.7-8 J-591 Process Steam Transfer System - Mode 2 .7.7-9 1 J-592 Process Steam Transfer System - Mode 3 7.7-10 J-593 Deleted l 30 J-725 Control Room Equipment Arrangement 6.4-3 l1 J-877 Sh 1 Diesel Generator Local Control Panel 8.3-43 18 Alarms J-877 Sh 2 Logic Diagram Diesel Generator Breakers 8.3-44 l 19 J-878 Sh 1 Logic Diagram 4.16kV Bus Undervoltage 8.3-4 Sh 1 Relays O
\/ J-878 Sh 2 Logic Diagram 4.16kV Bus Undervoltage 8.3-4 Sh 2 27 Relays J-879 Sh 1 Logic Diagram Diesel Generators 8.3-45 J-879 Sh 2 Logic Diagram Diesel Generators 8.3-46 J-879 Sh 3 Logic Diagram Diesel Generators 8.3-47 J-879 Sh 4 Logic Diagram Diesel' Generators 8.3-48 J-879 Sh 5 Logic Diagram Diesel Generators 8.3-49 J-879 Sh 6 Logic Diagram Diesel Generators 8.3-50 33 J-879 Sh 7 Logic Diagram Diesel Generators 8.3-51 J-379 Sh 8 Logic Diagram Diesel Generators 8.3-52 J-680 Logic Diagram Diesel Generators 8.3-53 J-98a Sh2 Reactor Coolant Pumps Load Shedding 8.3-55 to Prevent Startup Transformer i
Overload , ()'^ M-1 Equipment Location - Reactor & Auxiliary Bldgs Plan at El. 568'-0" 1.2-2 '15 l (sheet 89) Revision 33 4/81
MIDLAND 1&2 - FSAR TABLE 1.1-1 PART 2 (continued) Bechtel FSAR Dwg. No. FSAR Figure Title Fig. No. M-2 Equipment Location - Reactor & Auxiliary 1.2-3 Bldgs Plan at El. 584'-0" M-3 Equipment Location - Reactor & Auxiliary 1.2-4 Bldgu Platt at El. 599'-O" M-4 Equipment Location - Reactor & Auxiliary 1.2-5 Bldgs Plan at El. 614'-0"
; 15 M-5 Equipment Location - Reactor & Auxiliary 1.2-6 i Bldgs Plan at El. 634'-6" M-6 Equipment Location - Reactor'& Auxiliary 1.2-7 Bldgc Plan at El. 645'-0" M-7 Sh 1 Equipment Location - Reactor & Auxiliary 1.2-8 Bldgs Plan at El. 659'-0" M-7 Sh 2 Equipment Location - Reactor & Auxiliary 1.2-9 Bldgs Plan at El. 674'-0" and 685'-0" M-8 Equipment Location - Auxiliary Building 1.2-10 Section A-A M-9 Equipment Location - Reactor and Auxiliary 1.2-11 Bldgs - Section B-B M-10 Equipment Location - Reactor Building 1.2-12 Section C-C and D-D M-11 Sh 1 Equipment Location - Auxiliary Building 1.2-13 Section E-E M-11 Sh 2 Equipment Location - Auxiliary Building 1.2-14 Section F-F M-12 Sh 1 Equipment Location - Auxiliary Building 1.2-15 Solid Radwaste and Railroad Bay 13 Equipment Location - Auxiliary Building, 11.4-4 Solid Radwaste and Railroad Bay M-12 Sh 2 Equipment Location - Solid Radwaste 1.2-16 Building Equipment Location - Solid Radwaste Bldg 11.4-5 M-14 Equipment Location - Turbine Bldg - 1.2-17 15 Unit 1 Plan at El. 614'-0" O
(sheet 90) Revision 25 10/79
MIDLAND 1&2 - FSAR TABLE 1.1-1 PART 2'(continued)
'D 'Bechtel FSAR-Dwg. Nr. FSAR Figure Title Fig. No.
M-268 . Auxiliary and Turbine Building Plumbing' 9.3-29
.M-269 Turbine Building. Plumbing ~ 9.3-30 M-400 Sh 1 Piping and Instrumentation Diagram. Legend .l.1-1 M-400 Sh 2 Piping and-Instrumentation Diagram' Legend 1.1-2 M-400 Sh 3 Piping and Instrumentation Diagram 1 Legend 1.1-3' - ,
30' M-401A Reactor Coolant and Pressure Control-Unitil:5.1-l'Sh 1 27 M-401B Reactor Coolant and Pressure' Control-Unit lr5.1-1 Sh 2. l 30 M-402A Reactor Coolant and Pressure Control-Unit2-5.1-2JSh 1 27' Reactor Coolant and Pressure Control-Unit 2'5.1-2-Sh 2
~
M-402B M-403 Sh lA Makeup and Purification Unit 1 9.3-31. Sh' l._ l 26 M-403 Sh 1B Makeup and Purification Unit l- 9.3-31 Sh 2' 27 M-403 Sh 2A Makeup and Purification Unit 1 9.3-32 Sh 1 M-403 Sh 2B Makeup and Purification Unit-l' 9.3-32'Sh-2' . M-404 Sh lA Makeup and Purification Unit 2 9.3-3 3 Sh ~ 1- l: 26 M-404 Sh 1B Makeup and Purification Unit 2 9.3-33 Sh 2 M-404 .Sh 2A Makeup and Purification Unit 2 9.3-34 Sh 1 ; M-404 Sh 2B Makeup and Purification Unit 2 -9.3-34 Sh 2 M-405A Chemical Addition System 9.3-40-Sh 1 l' M-405B Chemical Addition Systen.' .9.3-40 Sh'2 j M-405C Chemical Addition' System 9.3-4 0 Sh 3. l 3 0
~
M-406 Sh 1 Reactor Plant Sample System . 9.3-3 M-406 Sh 2 Reactor Plant Sample System 9.3-4 l M-406 Sh 3 Reactor Plant Sample System ' 9.3-5 M-406 Sh 4 Reactor Plant Sample ' System 9.3-6 l (N l \~ I e (sheet 95) 4 Revision 33 4/81-
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MIDLAND 1&2 - FSAR TABLE 1.1-1 PART 2 (continued) FSAR Bechtel Fig. No. Dwg . N o . FSAR Figura Title M-407 Sh lA Liquid Waste Units 1 & 2 11.2-1 Sh 1 Sh 1B Liquid Waste Units 1 & 2 11.2-1 Sh 2 M-407 M-407 Sh 2A Liquid Waste Units 1 & 2 11.2-2 Sh 1 26 M-407 Sh 2B Liquid Waste Units 1 & 2 11.2-2 Sh 2 M-407 Sh 3A Liquid Waste Jnits 1 & 2 11.2-3 Sh 1 Sh 3B Liquid Waste Units 1 & 2 11.2-3 Sh 2 M-407 M-407 Sh 4A Liquid Waste Units 1 & 2 ll.2-3A Sh 1 33 M-407 Sh 4B Liquid Waste Units 1 & 2 11.2-3A Sh 2 Sh 1 Boron Recovery Units 1 & 2 9.3-35 M-408 Sh 2A Boron Recovery Units 1 & 2 9.3-36 Sh 1 M-408 Sh 2B Boron Recovery Units 1 & 2 9.3-36 Sh 2 M-408 Sh 3A Boron Recovery Units 1 & 2 9.3-37 Sh 1 26 M-408 Sh 3B Boron Recovery Units 1 & 2 9.3-37 Sh 2 M-408 Sh 4A Boron Recovery Units 1 & 2 9.3-38 Sh 1 M-408 Sh 4B Boron Recovery Units 1 & 2 9.3-38 Sh 2 M-408 M-408 Sh 5 Boron Recovery Unit 1 & 2 Riser Diagram 9.3-18 M-408 Sh 6 Boron Recovery Unit 1& 2 Riser Diagram 9.3-19 Radwaste Gas - Unit 1 & 2 11.3-2 Sh 1 26 M-409A
- 11. 3-2 !;h 2 M-409B Radwaste Gas - Unit 1 & 2 M-410 Decay Heat Removal and Core Flooding-Unit 1 5.4-10 18 M-411 Decay Heat Removal and Core Flooding-Unit 2 5.4-11 Reactor Building Spray Unit 1 6.2-51 Sh 1 M-412A Reactor Building Spray Unit 1 6.2-51 Sh 2 M-412B Reactor Building Spray Unit 2 6.2-52 Sh 1 M-413 A O
(sheet 96) Revision 33 4/81
MIDLAND 142 - FSAR TABLE 1.1-1 PART 2 (continued)
)
Bechtel FSAR Fiqure Title FSAR Fiq. No.
- Dwo. Mo.
M-444B Feedwater Chemical Addition Systen 10.4-25 Sh 2 .l 27 M-445 Sh 1 Stean Plant Sanple Systen - Unit 1 9.3-7 M-445 Sh 2 Stean Plant Sample Systen - Unit 1 9.3-8 M-445 Sh 3 Stean Plant Sanple Systen - Unit 1 9.3-9 9.3-10 14 M-445 Sh 4 Stean Plant Sanple Systen - Unit 1 M-445 Sh 5 Stean Plant Sanple Systen - Unit 2 9.3-11 M-445 Sh 6 Stean Plant Sanple Systen - Unit 2 9.3-12 M-445 Sh 7 Stean Plant Sanple Systen - Unit 2 9.3-13 M-445 Sh 8 Stean Plant Sanple Systen - Unit 2 9.3-14 M-446A Circulating Water - Units 1 & 2 10.4-3 Sh 1 27 M-446B Circulating Water - Units 1 & 2 10.4-3 Sh 2 73 (_ "-466C Circulating Water - Units 1 & 2 10.4-3 Sh 3 32 M-448 Sh 1 Instrunent and Serv :e Air 9.3-1 M-448 Sh 2 Instronent and Sers ce Air 9.3-2 M-449 Sh lA Plant Water Storage and Transfer 9.2-18 Sh 1 27 M-449 Sh 1B Plant Water Storage and Transfer 9.2-18 Sh 2 M-449 Sh 2 Plant Water Storage and Transfer 9.2-19 M-452 Sh 1A Energency Diesel Generator Fuel Oil 9.5-25 Sh 1 Storage and Transfer Systen Units 1 & 2 33 M-452 Sb 1B Energency Diesel Generator Fuel Oil 9.5-25 Sh 2 Storage and Transfer Systen Units 1 & 2 , M-453 HVAC Reactor Building Unit 1 9.4-10 M-454 Sh 1 HVAC Auxiliary Building Units 1 & 2 9.4-3 M-454 Sh 2 HVAC Auxiliary Building Units 1& 2 9.4-4 M-454 Sh 3 HVAC Auxiliary Building Units 1 & 2 9.4-5 (~N
\ ]
M-454 Sh 4 HVAC Auxiliary railding Units 1& 2 9.4-6 (sheet 101) Revision 33 n nm n
MIDLAND 152 - FSAR TABLE 1.1-1 PAPT 2 (continued) Pechtel FSAR Dwn. Mo. FSAR Finure Title Fig. No, M-454 Sh 5 HVAC Auxiliary Building Units 1 & 2 9.4-7 M-454 Sh 6 HVAC Auxiliary Puilding Units 1 & 2 9.4-7A l 32 .-455 Sh 1 HVAC Turbine Building Unit 1 9.4-8 "-455 Sh 2 HVAC Turbine Building Unit 2 9.4-9 M-456 Sh 1A Plant Heating Turbine Building 9.4-13 Sh 1 "-456 Sh 1B P'. ant Heating turbine Building 9.4-13 Sh 2 27 M-456 Sh 1" Plant Heatino Turbine Puilding 9.4-13 Sh 3 't -4 5 6 Sh 2A Plant Heatino Auxiliary and Reactor 10.4-14 Sh I l 29 Buildinos M-456 Sh 2B Plant Heating Auxiliary and Reactor 9.4-14 Sh 2 Buildings M-456 Sh 3A Plant Heating Office and Service Buildings 9.4-15 Sh 1 27 M-456 Sh 3B Plant Heating Office and Service Buildings 9.4-15 Sh 2 M-456 Sh 4 Plant Heating Miscellaneous Structures 9.4-16 l N-457 Sh 1 A Chilled Water Auxiliary Building 9.2-20 Sh 1 28 M-457 Sh 1B Chilled Water Auxiliary Building 9.2-20 Sh 2 M-457 Sh 2A Chilled Water Safeguards Equiprent Unit 1 9.2-24 Sh 1 27 M-457 Sh 2B Chilled Water Safeguards Equipnent Unit 2 9.2-24 Sh 2
"-457 Sh 3A Chilled Water Safeouard Equipnent Unit 2 9.2-25 Sh 1 M-457 Sh 3B Chilled Water Safequard Equipment Unit 2 9.2-25 Sh 2 !i-457 Sh 4A Chilled Water Turbine Buildinq Unit 1 9.2-21 Sh 1 27 V-457 Sh 4B Chilled Water Turbine Building Unit 1 9.2-21 Sh 2 !!-457 Sh SA Chilled Water Turbine Building Unit 2 9.2-22 Sh 1 't-457 Sh 5B Chilled Water Turbine Building Unit 2 9.2-22 Sh 2 l 27 M-457 Sh 6 Chilled Water Office and Service Building 9.2-23 l 13 P-458 Sh lA Fire Protection 9A-30 Sh 1 27 '1-458 Sh 1B Fire Protection 9A-30 Sh 2 (sheet 102)
Revision 32 1/81
MIDLAND 1&2 --FSAR TABLE 1.1-1 PART 2 (continued) FSAR Bechtel Fig. No. Dwg. No. FSAR Figure Title 9A-30 Sh 3 M-458 Sh IC Fire Protection 27 M-458 Sh 2 Fire Protection 9A-30 Sh 4 M-459 Sh lA Domestic Water 9.2-12. Sh 1 B Domestic Water 9.2-12 Sh 2-M-459 Sh 26 M-459 Sh 2 Domestic Water 9.2-12 Sh.3 M-4 59 Sh 3 Domestic Water .9.2-12 Sh'4 Sh 1 Process Steam, Supply and Return System 10.4-20 M-460 M-460 Sh 2A Process Steam, Supply and Return System 10.4-21.Sh 1 M-460 Sh 2B Process Steam, Supply and Return System 10.4-21 Sh 2' 26 M-460 Sh 3A Process Steam, Supply and Return System 10.4-22 Sh 1 M-460 Sh 3B Process Steam, Supply and Return System 10.4-22 Sh 2 M-460 Sh 4 Process Steam, Supply and Return System 10.4-22A- l14-M-461 Sh lA Process Steam Evaporator System 9.4-14 Sh 1 l29 Sh 1B Process Steam Evaporator System = 10.4-14 Sh 2 M-461 M-461 Sh 2A Process Steam Evaporator System 10.4-15 Sh 1 Sh 2B Process Steam Evaporator System 10.4-15 Sh 2 M-461 M-461 Sh 2C Process Steam Evaporator System 10.4-15 Sh - 3 l 33 f Sh 3A Process Steam Evaporator System 10.4-16 Sh 1 M-461 Sh 3B Process Steam Evaporator System 10.4-16 Sh 2 M-461 M-461 Sh 4A Process Steam Evaporator System 10.4-17 Sh 1 28 Sh 4B Process Steam Evaporator System 10.4-17 Sh 2 ' M-461 i i M-461 Sh SA Process Steam Evaporator System .10.4-18 Sh 1 \ M-461 Sh 5B Process Steam Evaporator System 10.4-18 Sh 2 Process Steam Evaporator System 10.4-19 Sh 1 l14
)
s_/ M-461 Sh 6 (sheet 102a) Revision 33 ~ 4/81
r 4 MIDLAND 1&2 - FSAR TABLE 1.{-1 PART 2_(continued) Bechtel FSAR Dwg. No. FSAR Figure Title Fig. No. M-461 Sh 7 Process Steam Evaporator System 10.4-19 Sh 2 26 M-461 Sh 8 Process Steam Evaporator System 10.4-19 Sh 3 M-462 HVAC Reactor Building Unit 2 9.4-10A i 12 M-463 Sh 1A Miscellaneous Gas System Hydrogen 9.3-41 Sh 1 Supply M-463 Sh 1B Miscellaneous Gas System Hydrogen 9.3-41 Sh 2 Supply M-463 Sh 2A Miscellaneous Gas System Carbon Dioxide 9.3-43 Sh 1 Supply M-463 Sh 2B Miscellaneous Gas System Carbon Dioxide 9.3-43 Sh 2 Supply M-463 Sh 3 Miscellaneous Gas System Nitrogen Supply 9.3-42 M-464 Cooling Pond Blowdown and Makeup System 10.4-24 M-465 St 1 HVAC-Control Room-Battery Room-Switchgear 9.4-1 h and Cable Spreading Room M-465 Sh 2 HVAC-Control Room-Battery Room-Switchgear 9.4-2 and Cable Spreading Room M-466 HVAC Access Control and Computer Area 9.4-12 M-467 Sh 1 HVAC Office and Service Buildings 9.4-17 M-467 Sh 2 HVAC Of fice and Service Buildings 9.4-18 Sh 1 27 M-467 Sh 3 HVAC Of fice and Service Buildings 9.4-18 Sh 2 M-468 Sh 1 HVAC Diesel Generator Building and Service 9.4-11 Water Pump Structure M-468 Sh 2 Miscellaneous Structures HVAC 9.4-20 M-468 Sh 3A Miscellaneous Building HVAC System (Evap- 9.4-19 Sh 1 crator and Auxiliary Boller Building) 27 M-468 Sh 3B Miscellaneous Building H'/AC System (Evap- 9.4-19 Sh 2 orator and Auxiliary Boiler Building) M-468 Sh 4 M.scellaneous Structure HVAC (Guard House) 9.4-21 l 15 (sheet 10 2b) Revision 33 4/81
, .m. . . _ .. _ .. . . . . _ . . . _ . . . _ . -
I MIDLAND 162 FSAR- ; 1 TAGLE'l.1-1 PART 2.(continued)- 1 I ) Bechtel FSAR Dwg. No. FSAR Figure Title . Fig. No.
- M-468 Sh 5 Miscellaneous Structures HVAC- 9.4-22 i 15 9.4-22 Sh 1- l 33
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, M-468 Sh 6 ' Miscellaneous' Structures HVAC l M-469A Boron Recovery Regasifier 9.3-45 Sh 1-26 M-469B Boron Recovery Regasifier - 9. 3-4 5 Sh 2 ~ M2 470 Sh 1A Chemical and Oily Waste System 9.5-30 Sh l' M-470 Sh 1B Chemical and Oily Waste System 9.5-30 Sh 2 ! M-470 Sh 2A Chemical and Oily Waste System _9.5-29 Sh'1 i M-470 Sh 2B Chemical and Oily Waste System. 9.5-29 Sh 2 l l
'9 O
(sheet 10 2c) Revision 33 4/81
MIDLAMD 162-FSAR O l l THIS PAGE INTENTIONALLY LEFT BLANK i i l i l l t (sheet 102d) Revision 27 l 3/80 i l
- t. _ . _ _ . _ . - . - - _ . . _ . . . . _ _ . _ . . _ _ _ . _ . - _ _ _ _ . , _ _ _ _ _ _ _ . - _ - , , - . . _ _ . . . - . _ _ _ _ _ _ . - - _ . - . - ._. _ _ . . _ _ _ _ _ _ _ _ -
i MIDLAND 1&2 - FSAR TABLE 1.1-1 PART 2 (continued) Bechtel FSAR Ci Dwg. No. FSAR Figure Title -Fig. No. I P-472 Sh 1 -Miscellaneous Instrumentation Reactor 6.2-119 l 12 Building Unit 1 M-472 Sh 2 Miscellaneous Instrumentation Reactor 6.2-120 Building Unit 2 M-478 Sh' 1 iPreliminary Process Steam Radiation. 11.6-1 Sh'If Monitoring On-Line Monitoring System. M-478 Sh 2 Preliminary. Process Steam Radiation' 11.6-1 Sh 2: Monitoring On-Line-Monitoring Systen
. 32 l
'M-478 Sh 3 Preliminary Process Steam Radiation .11.6-l'Sh 3-Monitoring On-Line Monitoring System l
l M-478 Sh 4 Preliminary Process Steam Radiation ll.6-l'Sh 4 Monitoring Or-Line Monitoring System. N-507 Sh~3 Typical-Layout of Safety Related Filter- 12.3-41 ! Units Typical Layout of Non-Safety Related s M-509 () Sh 2 -12.3-39 ! Filter . Units -(Elevation) M-511 Sh 2 Typical Layout of:Non-Safety Related :12.3-40! I Filter Units (Plan View). M-525 Definition of Control Roon Envelope
~
l Sh 3 6.4-1 I I M-525 Sh 4 Definition of Control Room Envelope 6.4-2 i M-527 Sh 2 Hydrogen Vent Exhaust System Outside the 6.5-2 l13 Containnent ]1 i' M-527 S h -3 HVAC Area 3 Auxiliary Building . 6.4-4 33 Equipment Room Plan at El. 685'-0" I l -M-531 Sh 3 Hydrogen Vent Exhaust Systen Inside.
~
. 6 . 5 Containrent !
i
- M-601 Sh 3 Reactor Coolant and Pressure Control 5.4-15 i System Unit I f
M-703 Sh 1 Makeup and Purification Units 1 & 2 6.3-1 Sh 1 M-703 Sh 2 Makeup and Purification Units 1 & 2
. . 27 1 6.3-1.Sh 2
() M-709 Radwaste Gas System - Unit 1 & 2 11.3-3 l ! (sheet-103)
' Revision 3 3 4/81
MIDLAUD 1&2 - FSAR TABLE 1.1-1 PART 2 (continued) Pechtel FSAR Dwg. No. FSAR Figure Title Fig. No. M-710 Decay Heat Renoval and Core Flooding 6.3 . Systen Units 1 & 2 .-725 Solid Waste Flow Diagran 11.4-3 M-754 Sh 1 Plow Diagran - Heating, Ventilation and 11.3-4 Air Conditioning Auxiliary Building -- Unit 1& 2 M-754 Sh 2 Flow Diagran - Heating, Ventilation and 11.3-5 Air Conditioning Auxiliary Building - Unit 1 & 2 M-754 Sh 3 Flow Diagran - Heating, Ventilatior, and 11.3-6 Air Conditioning Auxiliary Building - Unit 1& 2 13 "-754 Sh 4 Plow Diaqran - Heating, Ventilation and 11.3-7 Air Conditioning Auxiliary Building - Unit 1 & 2 M-754 Sh 5 Plow Diagran - Heating, Ventilation and 11.3-8 Air Conditioning Auxiliary Building - Unit 1& 2 .t-754 Sh 6 Plow Diagran - Heating, Ventilation and 11.3-9 Air Conditioning Auxiliary Building - Unit 1 & 2 ^1-782 Energency Boration System - Units 1 & 2 9.3-46 30 SK-A-195 Personnel Traffic Patterns Plan of 12.3-31 El. 568'-0", 584'-0", and 599'-0" SK-A-196 Personnel Traffic Patterns Plan El 614'-0" 12.3-32 SR-A-197 Personnel Traffic Patterns Plan El 634'-6" 12.3-33 13 SK-A-198 Personnel Traffic Patterns Plan El 646'-0" 12.3-34 SK-A-199 Personnel Traffic Patterns Plan El 659'-0" 12.3-35 SM-A-200 Personnel Traffic Patterns Plan El 674'-0" 12.3-36 and 685'-0" l1 SK-G-351 SAP Finite Flement Mesh for Equipnent 3.8-29 30 Ilatch (sheet 104) Revision 32 1/81
MIDLAND 1&2-FSAR , Electrical control,~ instrumentation, and indication as applied to protection systems conform to Criteria for l33 g Protection Systems for Nuclear Power Generating
'- Stations, IEEE Std 279 and IEEE Standard Criteria for l 33 the Periodic Testing of Nuclear Power Generating Station Class lE Power and Protection Systems, IEEE Std 338. l33
- b. For protection systems provided by the_NSSS supplier:
The reactor protr etion system is designed to the 4 requirements of IEEE Std 279, Criteria for Protection Systems.for Nuclear Power Generating Stations, and in conformance to various applicable General Design Criteria and other requirements as identified in Section-7.2. The emergency core cooling actuation system is also designed to the requirements of IEEE Std 279, and in conformance to various applicable General Design Criteria and other requirements as identified in Section 7.3. 1.2.3.9 Radwaste Systems The waste processing systems collect and process liquid and gaseous and solid wastes produced as a result of reactor operation and prepare them for retention, disposal, recycle, or (~' release. criteria are applied. In performing this function, the following limiting 10 CFR 20, Standards for Protection Against Radiation 10 CFR 50, Licensing of Production and Utilization Facilities, Appendix I, Numerical Guide for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low As Is Reasonably Achievable' for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents 10 CFR 71, Packing -of Radioactive Material for Transport, and Transportation of Radioactive Materials Under Certain Conditions i 1.2.3.10 Shielding The primary objective of the shielding design is to protect > operating personnel and the general public from radiation 25 sources. Shielding is designed to limit the dose to plant personnel and visitors during normal operation, including anticipated operational occurrences, to as low as reasonably achievable and to limit the dose to plant personnel in tre
- control room in the unlikely event of an accident to within the requirements of 10 CFR 50, Appendix A, General Design Criterion
- 19. Shielding is also provided to limit the dose to persons at the boundary of the restricted area to the' requirements of 10 CFR I.
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1.2-7 Revision _33 4/81
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MIDLAND 1&2-FSAR
- 20. Sections 12.1 and 12.3 contain additional information on chielding design bases and system operaticns.
1.2.3.11 Emergency Core Cooling Systems The basic design criteria being used to evaluate the performance of the emergency core cooling system are in accordance with 10 CFR 50.46 and Appendix K to 10 CFR 50. The principal design basis for the ECCS (core flooding system, high-pressure injection mode of the mal.eup and purification cystem, and low-pressure injection mode of the decay heat removal cystem) is Generhl Design Criterion 35 for providing protection for the core over the entire spectrum of break sizes. Very small breaks that would not actuate the engineered safety features mode of operation will be accommodated by the normal makeup system as rcquired by General Design Criterion 33. The valver and piping ured in the ECCS subsystems are safety class components in cccordance with General Design Criterion 1. The components, valves, and piping of the ECCS inside containment ware designed to function properly during all phases of plant operaticn including accident environments in accordance with 10 CFR 50, Appendix A, General Design Criterion 4. Piping in the l 33 d; cay heat removal and core flooding system that penetrates the containment is equipped with containment isolation valves in accordance with 10 CFR 50, Appendix A, General Design Criteria 54, 55, 56, and 57. The containment isolation valves cre designed to remain functional following a safe shutdown l33 certhquake. The containment isolation valves of the makeup and purification system provide isolation of lines which penatrate the containment to minimize the release of radioactive materials to the ctmosphere. The piping, valves, and components in this system are designed to maintain their structural integrity during and ofter the safe shutdown earthquuke. l33 1.2.4 REACTOR
SUMMARY
DESCRIPTION The reactor core is comprised of an array of fuel assemblies which are identical in mechanical design, but different in fuel enrichment. Three enrichments are employed in a three region Core. The core is cooled and moderated by light water at a pressure of 2,185 psig in the reactor coolant system. The moderator / coolant contains boron as a neutron poison. The concentration of boron 1.2-8 Revision 33 4/81
MIDLAND 1&2 -FSAR in the coolant is varied as required to control relatively slow
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reactivity changes including the effects of fuel burnup. Additional boron, in the. form of burnible poison rods, is employed in the first core to establish the desired initial reactivity. The fuel rods consist of slightly enriched uranium dioxide cylindrical pe'llets contained in slightly cold worked Zircaloy-4 tubing which is plugged and seal welded at the ends to encapsulate the fuel. All fuel rods are pressurized with helium during fabrication to reduce stresses and strains in order to increase fatigue life. The control rod assemblies each consist of a group of ' individual absorber rods festened at the top end to a common hub or spider assembly. These assemblies are of two types, those with rods containing full langth absorber material to control the reactivity of the core under operating conditions, and those with-rods containing a part length absorber section to control-axial power distribution. The control rod drive mechanisms for the control rod assemblies are of the inductance stator / roller nut type. They are so designed that upon a loss of power to the stator, the control rod assembly is released to shut down the reactor. Reactor internals support the core, maintain fuel alignment, g limit fuel assembly movement, maintain alignment between fuel [-s
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} assemblies and control rod drive mechanisms, direct coolant flow past the fuel elements and to the pressure vessel head, and provide gamma and neutron shielding.
Instrumentation is provided in and out of the core to monitor the nuclear, thermal-hydraulic, and mechanical performance of the reactor and to provide inputs to automatic control functions. The reactor core design together with corrective actions of the reactor control, protection, and emergency cooling systems ensure that attained. peak loct.1 power densities do not lead to fuel I damage during normal operation or faults of moderate frequency, cause failure of more than a small fraction of fuel rods due to infrequent faults, or prevent acceptable heat transfer during transients associated with limiting faults. 1.2.5 REACTOR COOLANT SYSTEM
SUMMARY
DESCRIPTION The reactor coolant system is arranged as two closed loops connected in parallel to the reactor vessel. Each loop-consists of one 36 inch id outlet pipe (hot leg), 'one steam generator, and 33 two 28 inch id inlet pipes (cold legs), with one reactor coolant pump in each cold leg. An electrically heaced pressurizer is connected to one of the loops. A high-pressure safety injection line is connected to each of the four cold legs. The reactor a 1.2-9 Revision 33 4/81 f
MIDLAND 1&2-FSAR coolant system operates at a nominal 2,185 psig at the core outlet. The reactor coolant enters the reactor vessel through four inlet nozzles, turns and flows downward between the reactor vessel shell and the core support barrel, and enters the lower plenum. The coolant then turns and flows upward and continues parallel to the axis of the fuel assemblies to remove the heat generated within the fuel. The coolant continues its upward flow, then turns and leaves the reactor vessel through the two outlet n>zzles and the hot leg pipes, which lead to the steam generators. The coolant flows through the tube side of t le two steam generators, where heat is transferred to the secon ary system. Reactor coolant pumps return the reactor coolant to the reactor vessel. The pressure in the reactor coolant system is controlled oy regulating the temperature of the coolant in the pressurizer, where steam and water are held in thermal equilibrium. Steam is formed by the prescurizer heaters or condensed by the pressurized spray to reduce pressure variations caused by expansion and contraction of the reactor coolant due to system temperature changes. Components of the reactor coolant system are designed and will be l operated so that no deleterious pressure or thermal stress will be imposed on the structural materials. Necessary consideration will be given to the ductile characteristics of the materials at low temperatures. 1.2.6 ENGINEERED SAFETY FEATURES (ESF)
SUMMARY
DESCRIPTION 1.2.6.1 Containment Summary Description The containment structure and rapporting ESF systems reduce and control the release of fission products from the containment to the environment following postulated accidents within the containment structure. Supporting engineered safety features systems for the containment consist of the reactor building spray system, the recirculation air cooling system, the combustible gas control system, the reactor building isolation system, the penetration pressurization system, and the main steam isolation system. The containment structure is a post-tensioned reinforced concrete structure in the shape of a cylinder with an ellipsoidal dome and a reinforced concrete foundation slab with a steel liner to provide leaktightness. It completely encloses th2 reactor coolant system; i.e., the reactor vessel, the steam generators, the reactor coolant loops, and portions of the auxiliary systems. The containment also encloses the core flood tanks and the combustible gas control system. The containment design provides means for the integrated leakage rate testing of the containment 1.2-10 Revision 33 O 4/81
MIDLAND 1&2-FSAR structure and all penetrations, including provisicns for local es leakage rate testing of individual piping, electrical, and access () s penetrations of the containment. The reactor _ building spray system (RBSS)Lis designed to assist in maintaining containment pressure and temperature following a loss-of-coolant accident to acceptably low levels. The RBSS has two independent loops, each consisting of a pump and a spray header. The punps take suction from the borated water storage tank in the injection mode and from the reactor building emergency sump in the recirculation mode. The RBSS sprays borated water with trace levels of hydrazine into the containment 13 to reduce the airborne fission product inventory in the containment atmosphere following a loss-of-coolant accident. The recirculation air cooling system is designed to assist in maintaining containment pressure and temperature following a loss-of-coolant accident to acceptably low levels. The recirculation air cooling system has two independent loops, each loop consisting of two recirculating air cooling units. The air
- cooler units are cooled by the safety-portion of the service water system.
The combustible gas (hydrogen) control system is designed to maintain the combustible gas concentration below the lower flammability limit of hydrogen (4% by volume) following a loss-of-coolant accident. The hydrogen venting system consists of an exhaust line for removing hydrogen from the containment. () (_/ The thermal hydrogen recombiners utilize a recirculating mode of operation and allow the recombination of hydrogen and oxygen as the containment atmosphere circulates through them. The reactor building isolation system is comprised of valves located in lines and ducts penetrating the containment which receive an isolation command from the engineered safety features actuation system (ESFAS) under either a high containment pressure condition, low reactor coolant system pressure (ECCAS), or a high 15 containment atmosphere radiation condition. The containment heat removal systems (i.e., the reactor building spray system and the recirculation air cooling system) are designed such that either system can provide adequate cooling to the containment atmosphere. One loop of the spray system and one loop of the air cooling system can provide adequate cooling of the containment atmosphere following a loss-of-coolant accident. The main steam line isolation valve system is described in Subsections 5.4.5 and '/.3.3 and Section 10.3. l 33 The penetration pressurization system is described in Section 6.8.
'~' l.2-11 Revision 33 4/81
MIDLAND 162-FSAR 1.2.6.2 Emergency Core Cooling System Summary Description The principal mechanical components of the emergency core cooling system which provide core cooling immediately following a loss-of-coolant accident are two core flood tanks, the high-pressure (makeup) safety injection pumps, the low-pressure . (decay heat removal) pumps, and the associated valves, tanks, and piping. In order to prevent fuel rod damage that would impair effective cooling of the core, the emergency core cooling system is designed to cool the reactor core and provide additional shutdown capability following initiation of the following accident conditions:
- a. Pipe breaks and valve failures in the reactor coolant system which cause a discharge larger than that which can be made up by the normal makeup system, up to and including the instantaneous circumferential rupture of the largest pipe in the reactor coolant system
- b. Rupture of a control rod drive mechanism causing a control rod assembly ejection accident
- c. Pipe breaks and valve failures in the steam system, up to and including the instantaneous circumferential rupture of the largest pipe in the steam system
- d. A steam generator tube rupture lh]
The acceptance criteria for the consequences of each of these accidents are described in Chapter 15 in the respective accider.t j analyses sections. I In order to ensure that the emergency ccre cooling system will perform its desired function during the accidents listed above, it is designed to tolerate a single active failure during the short term immediately following an accident, or to tolerate a single active or passive failure during the long term following an accident. 1.2.5.2.1 Core Flooding System The core flooding system provides core protection continuity for intermediate and large reactor coolant system pipe failures. It autcmatically starts flooding the core when the reactor coolant system pressure drops below 600 psig. The core flooding system ic self-contained, self-actuating, and passive in nature. The discharge pipe from each core flooding tank (CFT) is attached directly to a reactor vessel core flooding nozzle. Each core flooding line at the outlet of the CFTs contains an electric motor operated stop valve adjacent to the tank and two check 1.2-12 O
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MIDLAND 1&2-FSAR 1.2.7.1 Introduction -
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( ,;) To preclude unsafe conditiona for equipment or personnel,' plant protection systems monitor selected plant parameters in order to initiate a reactor protection system trip and/or actuation of the engineered safety features actuation system. Multiple independent channels monitor each of the selected plant . parameters. The plant protection system logic is designed to initiate automatic protective action whenever the monitored parameters reach a limiting safety system setting. Redundancy is provided in all parts of the plant protection system to assure that no sing'.e failure will prevent protective action when it is required. Plant protection systems are designed in conformance to IEEE Std 279, Criteria for Protection Systems for Nuclear Power Generating Stations. Sufficient redundancy is installed also to permit periodic testing of plant protection systems so that a single failure or removal from service of any one protection system component or portion of a system does not preclude protective actions when required. 1.2.7.2 Reactor Protection System - Summary Description gs The reactor protection system (RPS) is comprised of four
' 5 1 independent and redundant protection channels which perform
\' / protective action on the control rod drive control system (CRDCS) after plant parameters exceed preset limits or the operator manually initiates the protection action. The RPS protects the reactor core by interrupting power to the control rod drive 4 system which causes all reactor shim and safety control rods to 26 drop into the core. Trip. action is accomplished when any two of four reactor protection channels determine-a reactor trip is required.
The instrumentation and controls of the RPS are designed to permit periodic testing while retaining the required capability for accomplishing their protective function. Independence of redundant instrumentation and controls is provided so that a l33 single failure within the system will not prevent the RPS from accomplishing its protective function. i 1.2.7.3 Engineerec Safety Features Actuation System - Summary Description The engineered safety features actuation system (ESFAS) includes the arrangement of components that. perform protective actions on the engineered safety features systems after plant parameters exceed preset limits or the operator manually initiates the protective action.
.V 1.2-15 Revision 33 4/81
MIDLAND 1&2-FSAR The instrumentation and controls of the ESFAS are designed to permit periodic testing while retaining the required capability for accomplishing their protective functions. Independence of redundant instrumentation and controls is provided so that a cingle failure within, the system will not prevent the ESFAS from cccomplishing its protective functions. 1.2.7.4 Systems Required for Safe Shutdown - Summary Deccription The systems required for safe shutdown are those systems which cre required to shut down the reactor and maintain the reactor in c sate shutdown condition. The instrumentation and controls of these systems are designed to permit testing while retaining the required capability for cccomplishing their safe shutdown function. Separation and independence of redundant instrumentation and controls are provided so that a single failure within the system will not prevent these systems from accomplishir.g their required functions. 1.2.7.5 Safety-Related Display Instrumentation - Summary Description The safety-related display instrumentati.on provides information to enable the operator to perform the required safety functions. The instrumentation provided monitors c;nditions in the reactor coolant nystem, the containment, the ivactor protection system, the engineered safety features actuation system, and the systems required for safe shutdown throughout planned operations, inticipated operational occurrences, and accident and post-accident conditions. Detailed descriptions of the display 3 instrumentation are included in Section 7.5. 1.2.8 ELECTRICAL POWER SYSTEMS
SUMMARY
DESCRIPTION 1.2.8.1 Transmission and Generation Systems Summary DeFCription The main generator is an 1,800 rpm, 3 phase, 60 cycle, cynchronous unit. The generator is connected directly to the turbine shaft and is equipped with an excitation system coupled directly to the generator shaft. Power from the generator is stepped up by the unit main transformers from 22kV to 345kV for Unit 1 and from 24kV to 345kV for Unit 2. The transformers are connected by overhead lines to n 345kV switchyard common to both units. This switchyard is connected to the transmission network by five 345kV transmission lines terminating at Livingston, Hampton, Manning, Thetford, and l 33 1.2-16 Revision 33 4/81
MIDLAND 1&2-FSAR Kenowa substations, which form a part of the CPCo 345kV grid. (~3 This grid is in turn connected with utilities in Illinois, () Indiana, Ohio, and Canada. 1.2.8.2 Electric Power Distribution Systems Summary Description Electric power is supplied from the switchyard to the onsite power. system for the electrical auxiliaries of each unit through two independent circuits. Each circuit supplies power through a separate startup transformer. Each.startup transformer feeds one 6.9kV and.one 4.16kV bus of each unit. Power is supplied to auxiliaries at 6.9kV, 4.16kV, and 480V levels. The pcwer distribution system includes Class lE and non-Class 1E ac and dc power systems. The class lE power system supplies equipment used to shut down the reactor and limit the release of radioactive material following a design basis accident. The Class lE ac system for each unit consists of two independent and redundant load groups and four independent 120Vac preferred power supply systems. The load groups include 4.16kV switchgear, 480V load centers, and motor control centers. The 120Vac preferred power supply systems include static inverters supplied from battery systems and distribution panels. Voltages listed are nominal values. _s One independent diesel generator is provided as a standby source , g i for each Class lE ac load group of each unit. Each generator has s_s' sufficient capacity to operate all the equipment of one unit which is necessary to prevent undue risk to public health and safety in the event of a design basis accident. The non-Class lE ac system includes 6.9kV switchgear, 4.16kV switchgear, 480V load centers, and motor control centers. Direct current power for the Class 17 dc loads of each unit is supplied by two independent Class 1E 125Vdc batteries and associated battery chargers. One 250V center-tapped non-Class lE battery and associated battery chargers supply 250 and 125Vdc power for the non-Class lE dc system loads. These systems are discussed individually in Chapter 8. 1.2.9 AUXILIARY SYSTEMS
SUMMARY
DESCRIPTION 1.2.9.1 Fuel Handling and Storage Summary Description New fuel is stored in vertical racks within the fuel storage area in the auxiliary building. Space is provided for storage of 132 l 23 new fuel assemblies to service both units. Subsection 9.1.1 discusses and evaluates the criteria for the design of new fuel storage. A 1.2-17 Revision 33 4/81
MIDLAND l&2-PSAR The stainless steel lined, reinforced concrete spent fuel pool provides for a maximum normal average of 4-2/3 cores. (Note that 27 this leaves sufficient storage space for a full core if core offload is necessary.) Spent fuel assemblies are stored in vertical racks so spaced as to preclude criticality in a nonborated cooling water environnent. The design criteria and evaluation of the spent fuel storage facility are discussed in Subsection 9.1.2. Control of the spent fuel pool water temperature during normal operation is accomplished by circulating the spent fuel pool water through heat exchangers cooled by the component cooling water system. Emergency makeup is provided by supplying essential service water to the pool to maintain its water level. Purification and clarification of the spent fuel pool water is by the use of a filter, strainers, and an ion exchanger. A description and evaluation of the spent fuel pool cooling and purification system is presented in Subsection 9.1.3. The fuel handling system, as further discussed in Subsection 9.1.4, provides for the safe handling of fuel and control rod assemblies and for the required assembly, disassembly, and storage of reactor internals. These systems include a main fuel handling bridge located inside the containment above the refueling cavity, the fuel transfer carriage, the upending machines, the fuel transfer tube, a fuel handling bridge in the spent fuel storage area, and various devices used for handling and storing the reactor vessel head and internals. The f uel handling system is designed to provide a safe, ef fective means of transporting and handling fuel from the time it reaches the site in an unirradiated condition until it leaves the site af ter postirradiation cooling. The reactor is refueled with equipment capable of handling spent fuel under water from the time it is removed from the core until it is placed in a cask for shipment from the site. The system is designed and constructed to minimize the possibility of mishandling or maloperation that could cause fuel assembly damage and/or significant fission prod uct release. Underwater transfer of spent fuel provides an optically transparent radiation shield, as well as a reliable source of coolant for removal of decay heat. The use of borated water ensures that the water in the reactor vessel is not diluted during fuel transfer operations. 1.2.9.2 Water Systems Summary Description i Water systems in operation at the facility include the service water system, decay heat removal system, component cooling water system, demineralized water system, domestic water system, ultimate heat sink, condensate storage facility, primary makeup water storage, borated water storage, circulating water system, plant heating system, safeguards chilled water system, and auxiliary chilled water system. Except for the circulating water system, which is discussed in Subsection 10.4.5, all the water systems are covered individually in Section 9.2. g Revision 27 l 1.2-18 3/80 1
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.i ; [!i; m.,. CONSUMERS POWER COMPANY l 3
-y MIDLAND PLANT UNITS 1 & 2 t3'lon 11
& ' FINAL SAFETY ANALYSIS REPORT i i
e jy 8 j Equipment Location - Evaporator Building Operating Floor El. 653'-6" (M-22 Sh 2, Rev 6) FSAR Figure 1.2-29 4/81 Revision 33 j
O J i i MIDEAND 1&2-FSAR TABLE 1.3-1 $ CODEPARISON OF MIDEAND FRA*. .,AES WITH SIMILAR DES!CBfS* pretas gdland Rancho Seco Ocomoe Turkey Poirj Seactor and Reactor Coolan} System lHFEEter. 4Ta'n) Roted heat output (core), part 2,452 2,772 2.564 2,200 nasimum overpower, 1 12 12 14 11 i Beactor coolant pressure 2,200 2,200 2,200 2,250 0 (operating), pela 1 32 Power distribution factore
. Heat generated in fuel and .! cladding, % 97.3 97.3 97.3 97.4
, F A h (nue' ear) 1.7e 1.70 1.78 1.77 4 DNB ratio at rated conditione 2.50 1.75(w-3) 2.0 1.81 DNS ratio at design overpower 2.07 1.39(w-3) 1.55 - l 32 l ) Coolant flow 1 ' Total flowrate. Ib/hr a 10' 131.3 137.8 131.3 101.5 l# Ef fective flow area for heat 4 transfer, it' . 44.9 49.17 49.19 41.4
; Average velocity along fuel 32
- rode, ft/e 15.5 16.5 15.73 14.3 i
Coolant temperature Nominal inlet (voesel) 555.2 556.5 554 546.2 Nominal outlet (vessel) 602.8 607.7 604.7 602.1 Moeinal outlet (core) 605.9 --- 605.5 604.5 l 12 1 Maaimum fuel temperature, 'F 3,900 4,400(hotspot) 4,250 4,400(overpower} ILeet transfer at 100% power Active heat transfer surface area, ft' 49,130 49,734 49,734 42,460 Average heat flux, Btu /hr/f t' 166,000 185,090 173,470 171,600 l 32 Average thersel output, kW/ft 5.47 6.10 5.65 5.5 8 Core sechanical design parametere ruel assemblies 177 177 177 157 1 l Design CpA canless CKA cantese CRA canleen RCC cantees i (eheet 1) povision 32 1/81 1 i t
-- y .
< !4DIAND 1&2-FSAR TABLE 1.3-1 (continued)
System Midland M ncho Seco Oconee Turker Point Rod pitch, in. 0.568 0.568 0.568 0.563 overall dimensions, in. 8.587 sq 8.536 sq 8.536 sq 8.426 sq Mumber of grida per assembly 8 8 8 7 Fuel rods Number 36,816 36,816 36,816 32,028 Outside diameter, in. 0.430 0.430 0.430 0.422 clad thickness, in. 0.0265 0.0265 0.0265 0.0243 Clad material Eircaloy-4 Eircoloy-4 Eircaloy-4 Eircoloy Fuel pe11sta Material UOy, sintered U0 2, sintered U0 2, sintered UO 2, sintered Density, % of theoretical 95.0 92.5 93.5 94,93.92 ] 33 Diameter, in. 0.3686 0.370 0.370 0.3659,0.3659,0.3649 I control rod assemblies (CRA) Neutron absorber 5%Cd-15%1n-80%Ag 5%Co-15%1n-80%Ag 5%Cd-15%1n-80%Ag 5%Cd-1511n-80%Ag Cladding material 304SS-cold worked 304SS-c314 worked 304SS-cold worked 30455-cold esrked Clad thickness, in. 0.021 0.021 0.021 0.019 Number of assemblies 61 61 61 53 Number of control rode per assembly 16 16 16 20 Burnable poison rou assemblies (BPRA) 68 68 68 68 Muclear Design Data Structural characteristics 207.486 176,000 Fuel weight as UOy, Ib 93.1 ot tric tons 204,820 Coro diameter, in. (equivalent) 128.9 128.9 128.9 119.5 Core height, in. 144 144 33 (active fue1) 141.8 144 Performance characteristics Loading technique 3 region 3 region 3 region 3 region Fuel discharge burnup, NWd/atU average first cycle 13,746 14.250 14.250 13.000 ] 32 equilibrium core average 27,789 --- --- 24,500 l (sheet 2) 33 povtston 4/81 O O O
MIDLAND 1&2-FSAR TABLE 1.3-2 (continued) s {. ! FSAR Item Reference Reason for Change Decay heat removal 5,4.7.1.1.2 A low flow interlock is 11-8 pumps low flow provided through flow measurement l19 protection on the pump discharge to protect the pump from damage due to 18 low flow. Decay heat renoval 5.4.7.1.1.5 A motor operated control butter-system fly valve was installed in each decay heat removal train at the discharge of the decay heat removal system cooler. Motor operators were installed on the cross-connection gate valves. 18 These motor operated valves, in conjunction with the control butterfly valves, provide for compliance with the single-failure criterion in the event of a core flood line break in one train and a power failure in the other.
-_ PORV isolation valves 5.4.13 The pressurizer power operated
[sj Q&R 211.35 relief system was revised \m/ to reflect redundant class lE motor operated PORV isolation valves and controls. These valves close either manually or automatically on a coin-cident indication of PORV - not closed and low RCS pres-sure to ensure isolation in the event of a stuck open 30 PORV. Emergency RCS 5.4.15 Two Class lE remote manual venting solenoid valves with Class lE controls are provided for the existing high point vents on each hot leg and the pres-surizer to provide capability for venting post-accident noncondensible gases. (
/
(sheet 3) Revision 33 4/81
MIDLAND 1&2-FSAR TABLE 1.3-2 (continued) FSAR Item Reference Reason for Change Reactor building 6.2.1 The reactor building spray cpray system chemistry was changed from NaOH and Na2 S2O3 to Na,PO and hydrazine for pH control and iodine renoval. The change allows the pH range of 7.0-7.5 to be attained rather than the 9.0-9.5 range discussed in the PSAR. The change also provides a more reliable and positive means of chemical addition. 6.2.2.1.2.2 The reactor building spray system was modified to include two spray pumps, two hydrazine transfer pumps, and one chemica) addition tank. The changes were made to implement the change in spray chemistry. 18 Containment 6.2.4.2, Flued head fittings are used penetrations Fig. 6.2-5, in lieu of welded penetration Fig. 6.2-60 seal cup design to reduce the number of welds and permit inservice inspectioa per the ASME' Boiler and Pressure Vessel Code Section XI. A second penetration seal on the outside of containment will not be added. Combustible gas 6.2.5 To comply with NRC Regulatory control system and Guide 1.7, the combustible gas hydrogen purge system control system was revised to include two recombiners per reactor building. The hydrogen vent system was designed as nonseismic except for the containment isolation portion of the system. O (sheet 4) Revision 32 1/81
MIDLAND 1&2-FSAR TABLE 1.3-2 (continued) FSAR Item Reference Reason for Change Decay heat 6.3.3.5 The decay heat removal system l removal system has been upgraded te prevent boron precipitation in the reactor vessel during long-term core cooling following a postulated LOCA. This 18 capability has been provided through the dump-to-sump line of the decay hea' removal system. Hazardous gas 6.4, The original intent of limiting monitoring system 7.3, toxic gas concentrations to
, Q&R 312.36 threshold limit values (TLV) can not be met by commercially available equipment. The 39 current design meets the intent of current NRC requirements of Regulatory Guides 1.78 and 1.95 and Standard Review Plan 6.4.
3' Control room 6.4, Control room habitability (HVAC) habitability 9.4.1 system is revised to include ESF filter trains for outside air makeup and recirculation air filtration and a pressurization system. These changes are incorporated in the design to comply with NRC Regulatory Guides 1.52, 1.78, and 1.95 and SRP 6.4. High-pressure 6.3.2.2.2 The HPI lines are cross con-injection system nected downstream of the HPI 18 ' line isolation valves to mitigate the emergencies of the small break LOCA analysis. Reactor building 6.8 The system has been modified i penetration to provide nitrogen to the - pressurization pressurized water storage system tanks and air pressurization.penetra-tions for a period of 30 days post-accident. This system replaced the instrument air system that was originally intended to provide this capability. 1 (sheet 5) Revision 32 1/81-
MIDLAND 1&2-FSAR TABLE 1.3-2 (continued) PSAR Item Reference Reason _ for Change Anticipatory re- 7.2 An anticipatory reactor trip actor trip system system which is independent (ARTS) of the RPS has been provided 33 to give additional RCS over-pressurization protection. Engineered safety 7.3 The ESPAS system has been 18 feature actuation expanded to include the auxiliary feedwater actuation l19 cystem (ESPAS) 18 system (AFWAS), fuel pool l ventilation actuation system (FPVAS), loss of offsite power 13 and emergency core cooling actuatien system sequencers (LOP l19 and ECCAS sequencers), main l 18 steam line isolation system 119 (MSLIS), control room isolation 18 system (CRIS), and diesel generator start logic (DG start) . Reacter building 7.3.3.1 Reactor building isolation l32 isolation valve valves will remain closed position after reset after reset of actuation of actuation signals signals rather than reopening automatically. This feature allows the plant 18 operator to determine, on an individual basis, the need to reopen reactor building isolation valves. Auxiliary feedwater 7.4.1.1.1, The auxiliary feedwater system 32 system steam generator 7.4.2.1 steam generator level control level control system is added to minimize operator actions required during 18 operation of the auxiliary feedwater system. Pressurizer heaters 7.4.1.1.6 The design was revised to include Class 1E redundant pressurizer heater controls and power supplies. This 18 change was made to provide power to the pressurizer heaters which have been iden-tified as a system required for safo shutdown. O (sheet 6) Pev i r. ion 33 4/8]
MIDLAND 1&2-FSAR TADI.I: 1.3-2 (continued) FSAR Item Reference Reason for Change i AuxiLirry shutJown 7.4.3 An auxiliary shutdown panel l32 panel has been added to the plant design to aid the operators 18 in the event of control room evacuation. 1 l l l t l I I l l ( sheet 6a) nevision 33 4/81
s.. - * - - - . - . . _ _ - MIDLAND If,2-FSAR O' f (sheet 612)33 Revision 4/81 _ _ . . ~ . . - _ . _ - ..- . - .. .--. - - -. . . _ . - - . - . . -
i MIDLAND 1&2-FSAR TABLE 1.3-2 (continued) t,-~b ( / FSAR. Item Re ference _ Reacon for Change Borated water storage- 9.2.8 The borated water. storage system was modified to include two 500,000 gallon storage tanks, one for each unit, in lieu of the 650,000 gallon storage tank. 1g The material of construction was changed from aluminum to stainless steel. This change provided separation between units. Service water 9.2.1.2 The service water system could 133 system - reactor Table ncit maintain the pressure in the building air cooling 9.2-3 air cooling units above the boiling unit booster pumps point during postulated accident conditions, as required in FSAR Subsection 6.2.2.2. Four air cooling unit booster pumps, normally not operating, 26 and backpressure devices are now provided to maintain the pressure in the coolers above
' boiling and thus permit heat removal from the containment (s ) during accident conditions.
Makeup and purifi- 9.3.4 The system has been modified. cation system to provide two additional filters in the letdown system ,' ahead of the purification system demineralizers to remove crud prior to reaching the 18 demineralizers. The current design has removed interconnections between the-Unit 1 and Unit 2 purification systems. This change provides for separation of units. t 1 (sheet 11) Revision 33 4/81
MIDLAND 1&2-FSAR TABLE 1.3-2 (continued) FSAR Item Reference Reason for Change The maximum weight percent boric acid was reduced from 7.0 to 3.5. This change lowers the boric acid precipitation temperature to about 50F and reduces che heat tracing requirements. This change also results in several system changes to include three boric 18 acid tanks per unit versus a single tank used in the original design, increased volumes of the boric acid tanks from 1,000 ft' per tank to 1,200 ft ', and increased flowrate of the boric acid pumps from 0-10 gpm to 0-25 gpm. Auxiliary HPI 9.3.4.2.3.9 The system has been modified to pressurizer spray provide an auxiliary high-pressure spray to the pres- 3 surizer. This change permits safety grade depressurization of the RCS during ccid shutdown 33 under emergency conditions. Chemical addition 9.3.8 The system was changed to utilize cystem LiOH in lieu of KOH as a pH control. This change was made as recommended by B&W to be consistent with their water chemistry requirements. . 18 l The chemical addition system has l been downgraded to nonseismic-Category I because the system is not required for safety shutdown. H;at tracing for 9.3.8.2 Auxiliary building HVAC systems ch:mical addition maintain equipment and piping 26 system - boric acid containing 3.5 weight percent crystallization boric acid at a minimum of 60F, I 30 which is 8F above the precipi-tation temperature for that weight percent. Immersion heaters provide additional heating 26 capability. Therefore, heat tracing for both equipment a.1d piping was eliminated. (sheet 12 }33 Pevision 4/81
MIDLAND 1&2-FSAR
' TABLE 1.3-2 (continued)
[h i
') Item FSAR Reference -Reason for Change Emergency boration 9.3.10 The emergency boration system system (Subsection 9.3.10) has been added to provide 6 weight percent boric acid to the reactor coolant, through the 30 makeup system, in the event of an emergency shut-down.
Spent fuel pool 9.4.2 The spent fuel pool HVAC system HVAC has been modified to provide timely isolation of the normal exhaust system and switchover to the standby ESF filtration system upon receiving the FPVA signal. The standby ESF fil-tration systen is designed to meet requirements of NRC Regu- 18 latory Guide 1.52. This design was provided to ensure that.any significant activity released from 3 postulated fuel handling accidu.it is filtered through [ h the ESF filter system prior.to \s / release to the environment. . Engineered saf-ty 9.4.5 The engineered safety features features ventila- ventilation system has been tion system revised to include the ESF~ ' pump room filtration system which is designed to minimize the release of unfiltered radioactivity to the atmosphere due to postulated ESF pump seal failure. Air room HVAC system is-added 30 Reactor building 9.4.6 HVAC as a minipurge system for purging the containment during plant operation. The primary shield cooling system was deleted and replaced by a cavity cooling system to pro-
' ride appropriate temperature
.C the primary shield wall.
(sheet 13) Revision 32 1/81
MIDLAND 1&2-FSAR TABLE 1.3-2 (continued) FSAR Item Reference Reason for Change Fire protection system 9.5.1 The fire protection system is not designed to seismic Category I requirements except as discussed in Subsection 9.5.1. It is also no longer a backup source of water supply to the auxiliary feedwater system or fuel pool. As a result,.the fire pumps were 18 relocated from the service water pump structure to the circulating water pump structure. As an alternative design, an automatic carbon dioxide system is provided in lieu of an automatic sprinkler system for the l32 diesel generator rooms, and electri-cal penetration rooms. Main steam supply 10.3 Unit 1 and 2 main steam lines system are provided with two 36 inch intertie connections down stream of of the main steam isolation valves. Four 36 inch power operated valves provide the physical separation of Unit 1 18 and 2 main steam systems. Two 26 inch lines branch from the intertie linas to carry steam from the Unit 1 and 2 steam systems to the process steam evaporators. l (sheet 14) Revision 33 4/81
MIDLAND l&2-FSAR University'of: Michigan; ge" McNamee, -Porter & - Seely .
.(
w - - Consulting Engineers, Ann,Arborf Soil mechanics and_ Dr. Izzat M. -Idriss; Dames & - foundation engineering . Moore, Inc.; Michigan Drilling
. Conpany, Detroit, Michigan; :l30
~ Soiliand Material Engineers,. ~
Inc. , Detroit, . Michigan; l302 Walter H. Flood.& Co.; .- ' Pittsburgh Testing Laboratory, Pittsburgh,' Pennsylvania;- ' United-States Testing Co. Inc., Hoboken, N.J.; Dr. Newnatk; Dr.~ Peck;
.Dr. Henderon;-Rock and Soil '
30 Instrumentation;1Dr. Woods; Dr..Davison Geophys ics Weston Geophysical,'Inc., Weston,: Massachusetts; Inservice inspection ' Southwest Research._ Institute; B&W; Hartford Stean Boiler.
-Inspection and- Insurance Co.; Raymond:R..Maccary Process stean evaporator Ihr. Victor D. Sande'rs,' Con-simula t ion sulting Engineer, Thermo- 30 N - dynamics, Sherman Oaks, California Process steam radiation NUS Corp.
monitoring study Dr. A.A. Moghissi, Phoenix Technology Corp. L-Aircraft impact damage study NUS Corp.
.J O ~
DBA environmental testing Oak Ridge National Labora-of coatings tory, Union Carbide Corp. Me teorology EG&G, Environmental Consultants; Professor-D.J. Portman, University: of Michigan Containment suep model testing - Western Canada Hydraulic Laboratories
'30~
L Site emergency planning - General Physics Corp. Equipment qualification Commonwealth Associates, Inc. I (' 1,4_3 Revision 30 10/80: t i 2 e _._-__.__._l
MIDLAND 1&2-FSAR Accident analysis Science Applications, Inc.; Ebasco Services, Inc. Plant reliability Holmes & Narver Welding procedures Clarence E. Jackson, Ohio State University Site geology Professor James H. Fisher 30 Reactc* hold-down stud failure Teledyne Engineering analy: ; Services System analysis EDS Nuclear, Inc. Auxiliary feedwater reliability Pickard, Lowe & Garrick Computer applicatians Scientific Systems Services, Inc. Meteorological dsta (processing, Dames and Moore; I-Ming Aron l33 reports, checking, and verifi-cation) Nearby industrial, transporta- NUS Corp. tion, and military facilities Quality assurance program 30 NUS Corp. evaluation Quality assurance program audit Nuclear Audit & Testing Company; Management Analysis Co. Reactor cavity analysis Science Applications, Inc., Knoxville, Tennessee Dewatering and underpinning R. Laughney; C. Gould; 30 Consulting Engineers Environmental studies Lawler, Matusky & Skelly 32 Engineers Classroom instruction in Associated Technical Training reactor fundamentals and plant Services, Tamassee, South system for cold license can- 33 Carolina didates 1.4-4 Itevision 33 4/81
MIDLAND 1&2-FSAR 1.4.5 DIVISION OF RESPONSIBILITY f V 1.4.5.1 Applicant / Owner The ultimate responsibility for the proper design, engineering review, construction, and operation of the plant rests-with the applicant, Consumers Power Ccmpany (CPCo). CPCo is assisted and advised by the parties described below concerning acceptable means of meeting all applicable criteric. 1.4.5.2 Plant Architect / Engineer-Constructor Bechtel Associates Professional Corporation has been engaged by CPCo to perform professional engineering services and Bechtel Power Corporation has been engaged to perform procurement, construction, and other services for the balance of plant equipment,-systems, and structures not included under the scope of the NSSS contract. Bechtel Power Corporation is also responsible for the installation of the NSSS components to be provided by the NSSS supplier with the exception of the reactor coolant system. 1.4.5.3 Nuclear Steam Supply System (NSSS) Supplier The Babcock & Wilcox Company (3&W) has been engaged by'CPCo to design, manufacture, and deliver the NSSS. The NSSS includes the (/) N-reactor coolant system, reactor auxiliary system components, nuclear and certain process instrumentation, as well as the reactor protection system. In addition, B&W will furnish technical assistance for erection, initial fuel loading, testing, and initial startup of the nuclear steam supply systems. The B&W Construction Company is responsible for the installation of the reactor coolant system. 1.4.5.4 Turbine-Generator Supplier General Electric Company has been engaged by CPCo to-design, manufacture, and deliver the turbine-generator for the facility. O 1.4-5 Revision 33 4/81
' MIDLAND 1&2-FSAR' TABLE'1.6-2 b)
( B&W TOPICAL REPORTS B&W Report Topical FSAR Approval Reoort Title Revision Reference Status BAW-10000 Correlation of 0 4.4 . Accepted by 24 Critical Heat Flux NRC 2-21-73 in a Bundle Cooled by Pressurized Water BAW-10001 Incore Instrumentation O' 7 Accepted by l33 Test Program NRC 2-73 BAW-10003A Qualification Testing 4 7 Accepted.by of Protection System NRC 10-10-75 Instrumentation i 26 BAW-10008 Reactor Internals Pt 1, 3.9 Accepted by Stress and Deflection Rev 1 NRC 9-20-72 Due to LOCA and 24 Maximum Hypothetical Earthquake BAW-10010 Stability Margins for Pt 3, 4 Accepted by (l3 N- Xenon Oscillations - Rev 1 NRC 12-70 Two- and Three-Dimen- 33 sional Digital Ana-lyses BAW-10013A Study of Intergranu- 1 5.2.3 Accepted by lar Separations in NRC 10-11-72 Low-Alloy Steel Heat-Af fected Zones Under Austenitic SS Weld Cladding BAW-10021 TEMP - Thermal Energy 0 4.4 Accepted by Mixing Programs NRC-12-29-70 0 5.4 Accepted by 24 BAW-10027 Research and Develop-ment Report for the NRC 3-24-72 Once-Through Steam Generator BAW-10029A CRDM Test Program 3 3.9 Accepted by NRC 2-25-76 (sheet 1)
, ) Revision 33 4/81 i
,- . . - - . . . - , . . , - . .- , - . . - - - , ,- ,, ,~, . . , . - - , --
MIDLAND 1&2-FSAR TABLE __1.6-2 (continued) i B&W Report Topical FSAR Approval 24 Report Title Revision Feference Status BAW-10035A Fuel Assembly Stress 1 4 Accepted by l 26 and Deflection Due NRC 1-29-75 to LOCA and Seiseic Excitation BAW-10036 Correlation of CHF in 0 4.4 Accepted by a Bundle Cooled by NRC 2-21-73 24 Pressurized Water BAW-10037 Reactor Vessel Model 2 4.4 Accepted by Flow Tests NRC 12-19-72 BAW-10038 Prototype Vibration Supp. 1 5 Accepted by 33 Measurement Program Rev 0 NRC 4-4-79 for Reactor Internals Accepted by 24 BAW-10039 Prototype Vibration 0 3.9 Measurement Program NRC 7-6-74 for Reactor Supp. 1 3.9 Under review Internals Rev 0 Submitted 8-79 l26 BAW-10043 Overpressure Pro- 0 5.2 Under review tection for B&W's Submitted PWRs 5-72 Methods of Compliance 1 5.3 Accepted by 24 BAW-10046A with the Fracture NRC 7-77 Toughness Requirements of Operational Requirements of App G (10 FFR 50) Design of Rc etor 1 3.9 Accepted by BAW-10051 Internals and Incore NRC 7-6-73. Accepted by 24 Ins trument Nozzles Supp. 1 3.9 for Flow Induced NRC 4-79 Vibration 133 (sheet 2) Revision 33 4/81
MIDLAND 1&2-FSAR (~'s TABLE 1.6-2 (continued)
- (
B&W Report Topical FSAR - Approval Report Title Revision Reference Status BAW-10064 Mult17 ode Analysis of 1- 6.3 Accepted by Core Flooding Tank -NRC 11-75
~Line Break for B&W's
- 2,568 MWt1 Internals Vent Valve Plant BAW-10069A RADAR - Reactor 1 15.4.3 Accepted by Thermal and Hydraulic NRC 9-74 Analysis During Reactor Flow Coast-
, down BAW-10070 POWER TRAIN - General- 0 15- Under review Hybrid Simulation for Submitted Reactor Coolant and 7-73 Secondary System Transient Response 24 Accepted by [/) N-BAW-10076PA CADD - Computer Application to Direct Digital 2 15.4.3 NRC 5-75 Simulation of Tran-sients in Water Reactors BAW-10083PA B&W Model for 1 4 Accepted by Predicting In-Reactor NRC 5-16-77 Densification bah-10084PA Program to Determine 2 4 Accepted by In-Reactor Performance NRC 6-6-78 of B&W Fuels Cladding Creep Collapse BAW-10092 CRAFT Fortran 3 6.2 Submitted to 33 Program for Digital NRC 1-81 Simulation of a Multinode Reactor 24 Plant during a LOCA l e (sheet 3) 4 ()' Revision'33 4/81 v -w-q y-wm rr )-- *-
+wm-- m -a e v e - yqvi----4 -+a = w-gg Ttc'='m(-& - e Tv = +--WW----pW
, 7 9 y-M = m - + - ww e s' -ee.TT=cTv*-- 'M- P
MIDLAND 1&2-FSAR TABLE 1.6-2 (continued) O BaW Report Topical FSAR Approval R port Title Revision
~
Reference Status 24 BAW-10093 REFLOOD - Description 0 6.2 Accepted by of Model for Multi- NRC 6-18-75 node Reflood Analysis BAW-10094 THETA 1-B - Computer 2 15.0 Accepted by l33 Code for Nuclear NRC 8-77 Reactor Core Thermal Analysis BAW-10095A B&W Revisions to 1 6.2 Accepted by 24 CONTEMPT Computer NRC 2-25-78 Program for Predicting Containment Pressure-Temperature Response to a LOCA BAW-10096A B&W's NPGD QA Program 3 17.1 Accepted by 1 33 for Nuclear Equipment NRC 7-77 BAW-10098P CADDS - Computer Appli - 1 15 Under review 24 cation to Direct Digital Submitted Simulation of Transients 12-77 in PWRs W/O Scram Analysis of Anticipated 1 15.0 Under review 33 BAW-10099 Transients Without Scram Submitted l 24 5-77 l33 BAW-10103A ECCS Analysis of B&W's 3 6.2 ' Accepted by l24 177 F.A. Lowered Loop NRC 2-18-77 l26 NSSS Accepted by NRC 24 BAW-10104 B&W's ECCS Evaluation 3 6.3 Model 2-18-77 BAW-10106 QUENCH - Digital 0 15 Accepted by l33 Program for Analysis NRC 12-24-76 24 of Core Thermal Transients (sheet 4) Revision 33 i 4/81
MIDLAND 1&2-FSAR f -'s TABLE 1.6-2 (continued) B&W Report Topical FSAR Approv'l a Report Title Revision Reference Status BAW-10110 CHATA - Core Hydraul- 1 15.4.3 Under review ics and Thermal Analysis Submitted 5-77 BAW-10lllA Summary Description 0 1 Accepted by of the B&W Integrated NRC 12-13-76 Nuclear Design System BAW-10112A ETOGM - Epithermal 0 4 Accepted by Cross Section Generation NRC 10-76 Code Using ENDF/B Data BAW-10113A THOR - Tnermal Cross 0 4 Accepted by Section Generation Code NRC 10 Using.ENDF/B Data 24 BAW-10ll4A PROLIB - Code to Create 0 4 Accepted by Production Library of NRC 11-18-76' O Nuclear Data for Design Calculations BAW-10115A NULIF - Neutron Spectrum 0 -4 Accepted by Generator, Few Group NRC 1-77 Constant Calculator and Fuel Depletion Code BAW-10ll6A Assembly Calculations 0 4 Accepted.by and Fitted Nuclear NRC 5-77 Data BAW-10117PA Babcock & Wilcox Version 0 4 Accepted by of PDQ07 User's Manual NRC 10-76 BAW-10118A Core Calculationn 0 4.3 Accepted by Techniques and NRC 9-79 27 Procedures , BAW-10119PA Power Peaking Nuclear 0 4 Accepted by. 24
- Reliability Factors NRC 11-78 gs (sheet 5)
(
) Revision 33
4/81 4
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MIDLAND 1&2-FSAR TABLE 1.6-2 (continued) B&W Report Topical FSAR Approval Rwport Title Revision Reference Status 24 BAW-10120P Comparison of Core 0 4.3 Accepted by Physics Calculations NRC 6-14-79 with Measurements ~ 26 BAW-10124A FLAME 3-A - Three Dimen- 0 15.4.3 Accepted by sional Nodal Code for NRC 5-28-76 Calculating Core Reactivity and Power Distribution BAW-10125PA Verification of the 0 4.3 Accepted by Three-Dimensional NRC 5-28-76 FLAME Code BAW-10128 TRAP Fortran Program 0 15 Under review for Digital Simulation Submitted of the Transient Beha- 8-26-76 vior of the OTSG and Associated Reactor Coolant System 26 BAW-10132P Reactor Coolant System 0 1.5.8 Accepted by l 33 Hydrodynamic Loading NRC 10-78 During a Loss-of-Coolant 24 Accident BAW-10133P Mark C Fuel Assembly 1 1.5.8 Under review LOCA - Seismic Analysis Submitted 26 l 5-79 l BAW-10087PA TACO-Fuel Performance 2 4 Accepted by 33 Analysis NRC 9-77 l l l l (sheet 6) Revisica 33 4/31
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i 1 . 1. MIDLAND.1&2-FSAR . i TABLE-1.6-3'
-CPCO TOPICAL REPORTS 4
FSAR Section~ ' Report Approval
~
CPCo Topical ,
. Report No. Title Reference- Status CPC-1-A Consumers. 17.2 17.l' Approved'by 10.
Power Company (CPC) Quality NRC Assurance ' Program Topical i Report i f i e T L A i e d i b i
- k i
I Revision 10 a j 6/78 a ? 1
MIDLAND 1&2-FSAR TABLE 1.6-4 VENDOR TOPICAL REPORTS 18 Report Topical FSAR Approval Report Title Revision Reference Status EDR-1(P) Ederer, Inc. 2 9.1.4.3.10 Accepted by II 29
-A Generic Topical NRC 1-2-80 (EDE-1(NP) Report for Nuclear 33 -A) Safety-Related X-SAM Cranes i 18 WCAP- Reactor Contain- 7-69 6.2.2.2 Submitted 7336-L ment Cooler Coil 7-69 22 Test O
1 . Revision 33 4/81
MIDLAND 1&2-FSAR 1.7 ELECTRICAL, INSTRUMENTATION, AND CONTROL DRAWINGS A ( ,) Tables 1.7-1 through 1.7-21 contain a -listing of nonproprietary electrical, instrumentation, and control (EI&C) drawings which are incorporated in the FSAR by reference. These tables indicate those drawings.which are considered to be necessary to evaluate the safety-related features in Chapters 7 and 8 and Section 3.10. There are no proprietary EI&C drawings applicable. When appropriate, reference is made to the specific paragraphs in the text which discuss the drawing. When necessary, the drawing lists will be updated in future amendments until initial fuel 33 loading. l4 1.7.1 BOP ELECTRICAL DRAWINGS Tables 1.7-1 through 1.7-8A list applicable BOP electrical l 25 drawings. Table Title 1.7-1 BOP Notes, Symbols, and Details 1.7-2 BOP Logic Diagrams, Electrical Auxiliary Distribution System 1.7-3 BOP Single Line Diagrams 1.7-4 BOP Schematic Three Line Meter and Relay Diagrams 1.7-5 . BOP Schematic Two Line Meter and Relay Diagrams h 1.7-6 SG/ Schematic Diagrams, Electrical Auxiliary [M
\- L stribution System BOP Electrical Layout Drawings 1.7-7 1.7-8 BOP Cable Tray Seismic Support Drawings 1.7-8A BOP Communication Location Drawings l 25 1.7.2 BOP INSTRUMENTATION AND CONTROL DRAWINGS Tables 1.7-9 through 1.7-15 list applicable BOP instrumentation and control drawings.
Table Title 1.7-9 BOP Control Board and Panel Arrangement Drawings 1.7-10 BOP System Logic Diagrams 1.7-11 BOP Equipment Logic Diagrams 1.7-12 BOP System and Equipment Loop Diagrams 1.7-13 BOP Instrument Location Drawings
! 1.7-14 BOP Installation Details 1.7-15 BOP Equipment Schematic Diagrams 4
f) Revision 33 l.7-1 4/81 i i
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MIDLAND 1&2-FSAR 1.7.3 DRAWINGS SUBMITTED BY NSSS VENDOR Tables 1.7-16 through 1.7-21 list applicable drawings submitted by tae NSSS vendor. Table Title 1.7-16 NSSS ECCAS 1.7-17 NSSS Logics, ICS, NSS-12 1.7-18 NSSS Logics, ICS, NSS-13 1.7-19 NSSS CPC RPS Schematics 1.7-20 NSSS CPC RPS Logics 1.7-21 NSSS Control Rod Drive System, NSS-12 and -13 l l l O l l l l l l l l Revision 4 1/78 1.7-2
MIDLAND'1&2-FSAR-TABLE 1.7 -1 (continued) Drawing and Sheet Rev. Date Title Remarks-E-042-A 48 1-26-81 Conduit and' Tray Notes, Ref FSAP Table 133 Symbols and Details ~ 1.7-7 2 14 33 3 0 4 3 - SA 4 32 7 9 7A 1 i 8 16 333 8A 1 132 10 11 27 10A 8 132 10B 3 11B 9 33 11C 7 12 5 32 13A 1 t 17A 3 18A 10 33 18D 1 23 5 23A 2 32 - 23B 1 26 6 33 4 .l 18 40 6 1 32 41 8 ! 33 42A 2 32 44 2 46 2 51 3 18 [ I 56 3 , 57 2 32 ! 57A 2 g 39 . 58 0 60 4 32 60A 3 61 0 18 i 62 0 l 63 2 1- 27 64 5 32 64A 0 (sheet 3)
- Revision 33 l 4/71 l
l I
. - - - _._., . . _ . _ , _ . . _ - . . , .-._.- - .-_ _ -. ~. _...--- _ . . - _ . - - - - - - - , . - . - - . - - - - - - . - ~ . - . - . , ~ - - - - - . - - - - . - , - + , - - . - , - -
MID N 1&2-FSAR TABLE 1.7-1 (continued) O Drawing and Sheet Rev. Date Title Remarks 65 2 66 2 67 0 68 6 18 69 0 69A 0 69B 1 69C 2 25 69D 2 70 2 71 2 72 2 73 4 74 3 75 2 76 4 77 2 78 4 79 2 32 80 5 84 1 85 2 89 1 90 2 91 2 92 2 l E-042-B 1 Sh i 1 l ii 1 33 iii 1 100 10 l 27 ! 100A 2 l 101 7 18 102 3 103 2 104 2 1 19 105 6 106 8 27 106A 1 1 32 107 8 108 6 18 108A 0 (sheet 4) Revision 33 4/81
1 MIDLAND 1&2-FSAR 1. TABLE 1.7-3 (continued) () Drawing and Sheet Rev. Date Title Remarks-S 2 6 7 7 8 8 8 9 9 10 9 11 9 11A 4 12 6 13 6 14 7 29 15 5 16 8 , 17 5 18 5 19 5 20 5
. :21 5 22 6 23 6
{ E-021 7 12-22-80 250 and 125Vdc Systems, Ref FSAR 8.3.2 l33 Unit 1 l19 E-022 7 12-22-80 250 and 125Vdc Systems, Ref FSAR 8.3.2 l33; Unit 2 l19 . E-023-1 6 02-28-81 120Vac Instrument and Ref FSAR 8.3.1 133 i Preferred Systems, Unit 1 l18 E-023-2 2 02-28-81 120Vac Instrument and Ref FSAR 8.3.1 l33 Preferred Systems, Unit 1 l27 E-024-1 6 02-28-81 120Vac Instrument and Ref FSAR 8.3.1 33
-2 0 Preferred Systems, Unit 2 E-025-1 4 07-31-80 Synchronizing Diagram E-025-2 4 07-31-80 Synchronizing Diagram 33 E-031 10 01-08-81 120Vac Distribution Ref FSAR 8.3.1 Panels,' Unit 1 32 3 9 4 9 5 9 33 6 8 O : :
(she,et 2) Revision 33 4/81 l= . - - _ _ - _ _ . . - - _
MIDLAND'l&2-FSAR TABLE 1.7-3 (continued) Drawing and Sheet Rev. Date Title Remarks E-032 13 01-08-81 120Vac Distribution Ref FSAR 8.3.1133 Panels, Unit 2 and Common 32 3 10 4 9 5 9 6 10 33 7 10 8 10 13 9 14 9 36 3 27 37 2 38 3 l 33 E-033 8 08-19-80 DC Distribution Panel Ref FSAR 8.3.2 Schedule 6 6 30 7 6 12 6 13 6 17 2 18 2 27 < 19 2 l 20 2 E-034 4 11-21-80 Electrical Penetration Ref FSAR 8.3.1 l 32 Schedule (19 l E-035 11 08-19-80 480V Distribution Panel Ref FSAR 8.3.1 l 30 Schedule l27 5 6 6 6 28 6 29 6 29 56 7 1 57 8 58 7 61 6 62 5 27 63 4 69 2 29 70 2 O (sheet 3) Revision 33 4/ 81
MIDLAND 1&2-FSARS TABLE 1.7-4 BOP SCHEMATIC THREE LINE METER AND RELAY DIAGRAMS i Drawing No. Rev Date Title Remarks E-053 7 04-01-80 4,160V Class 1E System Ref FSAR 8. 3.1.1. 9 l 2 9 TABLE 1.7-5 SCHEMATIC TWO LINE METER AND RELAY DIAGPAMS Drawing No. Rev Date Title Remarks E-058-1 6 07-31-80 Class 1E 125Vdc System Ref FSAR 8.3.1.2 l32 and'8.3.2 O Revision 32 1/81 \ _ _ _ . _ . . _ . . _ _ , _ . . _ . . - . . _ _ . . . . ~ . . _ _ _ _ _ _ _ . _ . . _ _ _ _ . . . . . _ . - . . , . _ _ . _ . _ . _ . . . - . , _ _ , , , _ _ . . . . . . _ , , . . _ . _ -
MIDLAND 162-PSAR TABLE 1.7-6 BOP SCilEMATIC DIAGRAMS, ELECTRICAL .*UXILIARY DISTRIBUTION SYSTEM Drawing and 18 Sheet Rev. Date Title Remarks E-071 2 08-03-79 Typical 6.9 and 4.16kV Ref FSAR l25 Circuit Breaker Internal 8.3.1.1.9 Schematic E-072 2 07-05-77 Typical 480V Circuit Ref FSAR Breaker Internal Schematic 8.3.1.1.9 1 2 18 2 2 E-073 4 02-06-81 6.9 and 4.16kV Bus Ref FSAR l 35 Incoming Breaker From 8.3.1.1.9 Station Power Transformer a 18 1 1 2 3 33 3 4 4 2 18 5 1 7 4 8 1 18 9 2 E-074 4 02-06-81 6.9 and 4.16kV Bus Ref FSAR i 33 Incoming Breaker From 8.3.1.1.9 18 Startup Transformer 1 3 2 3 3 4 4 4 2 33 l 5 6 3 7 4 8 1 8A 2 9 1 10 1 118 (sheet 1) Revision 33 4/81 1
MIDLAND 1&2-FSAR TABLE 1.7-6 ( contir.ued ) Drawing and Sheet Rev. Date f f.tle
" Remark _s_ l l
E-075 5 10-24-80 6.9 and 4.16kV Bus Under- Ref FSAR 32 i Voltage Relays 8.3.1.1.9, 18 8.3.1.2.4 l19 4 3 5 4 25 SA 0 6 4 7 3 32 E-076 6 09-29-80 4,160-480V Station Power Ref FSAR and CRD Transformer 8.3.1.1.9, 18 Feeder Breakers 8.3.1.2.4 1 5 l29 4 5 5 4 6 5 7 5 32 8 5 9 5 10 0 l18 E-077 3 05-11-79 4.16kV Bus Incoming Ref FSAR -l27 Breakers 8.3.1.1.9, l18 . 8.3.1.2.4 1 3 25 I 2 2 2A 1 l 3 1 ! E-078 6 04-21-80 Diesel Generator Ref FSAR l29 Breakers 8.3.1.1.9, ' 18 1 8.3.1.2.4 1 4 2 5 29 3 5 4 5 1 (sheet 2) Revision 32 l 1/81
MIDLAND 1&2-FSAR TABLE 1.7-6 (continued) O Drawing and Sheet _ Rev. Date Title Relaa rks E-080 7 07-23-80 460V MCC Feeder Breakers Ref FSAR 133 8.3.1.1.9 1 4 2 3 25 3 5 3A 3 4 2 5 2 l33 7 5 25 E-081 3 12-21-78 Diesel Generator Ref FSAR Protection 8.3.1.1.9, 8.3.1.2.4 1 2 18 2 1 3 3 4 2 E-082 6 03-20-81 480V Load Center In- Ref FSAR l33 coming Breakers 8.3.1.1.9 4 3 l33 5 3 ll 21 6 5 33 E-083 8 02-23-81 480V Load Center Feeder Ref FSAR Breakers to 460V MCCs 8.3.1.1.9 25 4 5 . 5 7 33 6 7 7 3 8 2 21 E-091 3 10-24-80 6.9 and 4.16kV Bus Auto Ref FSAR Transfer 8.3.1.1.9 1 3 32 2 0 E-097 7 10-18-80 Low Voltage AC Ref FSAR Distribution Panels 8.3.1.1.9 33 1 3 2 4 3 3 (sheet 3) Revision 33 4/81
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MIDLAND 1&2-FSAR TABLE 1.7-8a ' BOP COMMUNICATION LOCATION DRAWINGS *UI a Drawing and Sheet Rev Date Title Remarks E-561 9 6/2/78 Lighting and Communi- See FSAR cation, Auxiliary Subsection Building, Units 1 and 2, 9.5.2.2.1 Elevation 568'-0" E-562 8 5/9/78 Lighting and Communi- See FSAR cation, Reactor hnd Subsection Auxiliary Buildings, 9.5.2.2.1 Units 1 and 2, Elevation 584'-0" 25 E-563 9 10/23/78 Lighting and Communi- See FSAR cation, Reactor and Subsection Auxiliary Buildings, 9.5.2.2.1 i Units 1 and 2, Elevation 599'-0" r- E-564 11 8/22/78 Lighting and Communi- See FSAR (3) cation, Reactor and Auxiliary Buildings, Subsection 9.5.2.2.1 Units 1 and 2, Elevation 614'-0" E-565 7 5/9/78 Lighting and Communi See FSAR cation, Reactor and Subsection Auxiliary Buildings, 9.5.2.2.1 Units 1 and 2, Elevation 634'-6" E-566 9 3/4/80 Lighting and Communi- See FSAR l 29 cation, Reactor and Subsection Auxiliary Buildings, 9.5.2.2.1 Units 1 and 2, 25 Elevation 646'-0" E-567 7 12/4/79 Lighting and Communi- See FSAR l 29 cation, Reactor and Subsection Auxiliary Buildings, 9.E.2.2.1 25 Units 1 and 2, Elevation 659'-0" k- (sheet 1) Revision 29 7/80
TABLE 1.7-8a (continued) Drawing j and Sheet Rev Date Title Remarks ! 1 E-568 6 5/9/78 Lighting and Communi- See FSAR l cation, Reactor and Subsection i Auxiliary Buildings, 9.5.2.2.1 Units 1 and 2, Elevation 673'-6" and i 685'-0" E-569 7 2/6/79 Lighting and Communi- See FSAR l cations Control Subsection . 25 Room 9.5.2.2.1 E-570 4 7/12/79 Lighting and Communi- See FSAR ! Cdtions Access Control Subsection l Area Elevation 634'-6" 9.5.2.2.1 ; i E-572 4 6/13/77 Lighting and Communi- See FSAR cation, Reactor and Subsection Auxiliary Buildings, 9.5.2.2.1 Units 1 & 2, Partial Plans ! 1 7 Lighting and Communi- See FSAR ! 33 E-573 11/6/80 Subsection cations Solid Radwaste i Building Elevations 9.5.2.2.1 634'-6" and 652'-0" E-574 7 7/2/79 Lighting and Communi- See FSAR i 25 cations Cooling Pond Lubsection Makeup Water Intake 9.5.2.2.7 and Pump Structure Plans ! I j E-575-1 5 8/13/80 Lighting and Communi- See FSAR i 32 cations Evaporator and Subsection Auxiliary Boiler 9.5.2.2.1 Building, Elevation 25 634'-6" E-575-2 5 6/25/80 Lighting and Communi- See FSAR l 32 cations Evaporator and Subsection Auxiliary Boiler 9.5.2.2.1 Building, Elevation 25 1 653'-6" Lighting and communi- See FSAR i29 E-575-3 4 4/14/80 cations Evaporator and Subsection Auxiliary Boiler 9.5.2.2.1 25 Building, Eleva'-ion 653'-6" O (sheet 2) Revision 3 3 4/81
-_ ._--- . . _____ _ _ . . . , . _ , . _ . _ ,_ - - . _ - - __ . - . , _ , - . . . . _ _ . - . . - _ , _ . . _ _ . _ _ . . _ . . .__ __ , . _ . . . - , , _ - . _ _.,,., m ..
O d 1 j v 1 MIDLAND l&2-FRAR I
- TARLF. 1.7-9 (continued) 1 s
Dr awing
- tio . Rev. .Date Title Remarks J-750 6 09-03-80 Main Control Roon Floor 132
- Penetration at Elevation 3 674' 6" and Control 2 >
Panel Layout j J-908 6 03-22-79 Local Control Panel ICll4 Ref FSAR 6.2.4.2, 7.3.3.2, 7.4.1.1, 7.4.3, 7.4.3.1, l21 , Auxiliary Shutdown Panel Table 7.5-1 & 7.5-2, 9.2.1.2, 9.2.2.2, 9.2.6.2, 9.3.4.2, 10.4.9.2 ' 2' j Arrangement (Unit'l) -
- J-909 6. 03-22-79 Local Control Panel 2C114 Ref FSAR 6.2.4.2, 7.3.3.2, 7.4.1.1,^7.4.3, 7.4.3.1, .
. l21 i Auxiliary Shutdown Panel Table 7.5-1 & 7. 5-2, 9. 2.1.'2, . 9. 2. 2. 2, 9. 2. 6. 2, . 9. 3. 4. 2, 10.' 4.9. 2
. .Arrangenent (Unit 2) 2-J-922 4 04-02-80 Local Control Panel IC150 ' - Ref FSAR 6.2.2.2, 6.2.4.2,:6.2.5.2, 9.4.6.2 cl29 i Reactor. Building Heatino '
- .and. ventilation Panel 2, i Arrangement J-923 4 04-02-80' Local Con
- col Panel 2C150 Ref FSAR 6.2.2.2, 6.2.4.2, 6.2.5.2, 9.4.6.2 129
! Reactor Bualding fleating and ventilation Panel 2 i Arrangement t 5 09-28-79 Local Control Panel OC1'S 1 .Ref FSAR 9.4.1.2, 9.4.2.2 '121, l J-924 127 , Auxiliary Building Heating " and Ventilation Panel. 2.
. Arrangement J-933 4 08-14-79 Local Control Panel 0ClR0 -Ref FSAR 9.4.8.2 :l27; i
I: . J-939 2 01-39-79 ' Local Control Panel IC175A Ref FSAR 9.4.7.2-J-940 2 01-30-79 Local control Panel IC1750 Ref FSAR 9.4.7.2 21 j- J-941 2 01-30 Local Control Panel 2C175A.Ref PSAP 9.4.7.2' i j J-942 2 01-30-79 Local Control Panel 2C175R Ref FSAR 9.4.7.2 1 J-946- 3 03-17-80 Vertical. control Panel 0C29 J-954 1 03-12-81 Control Panel.lC31, .nef PSAR'.7.5.1, 5.2.2.R,.7.4, 7.6, , 33; . ' Arrangement
^
l- 1 _i Table 1.7-9-. ,} '(sheet'3) i Eevision 33.. 4/81 i
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. .:~
Mint. ann 1&2-FSAR TABLE 1.7-9 (continued) Drawinq tio . new. Date Title penarks J-955 1 03-12-81 Control Pa.1el 2C31 I<ef PSAR 7.5.1, 5.2.2.8, 7.4, 7.6 33 Arrangenent 2717-1002 4 09-08-78 ESFAS Ceneral Arrangement Ref FSAR Tables 7.5-1 and 7.5-2 Sh 1 (IC43, 2C43) 2717-1002 4 09-08-78 ESPAS General Arranqement REF FSAR Tables 7.5-1 and 7.5-2 Sh 2 (IC44, 2C44) g 2717-1002 4 09-08-78 ESPAS General Arrangement Ref PSAR Tables 7.5-1 and 7.5-2 Sh 3 (IC35, 2C35) 2717-1002 4 09-08-78 CSFAS Go-eral Arranqement Ref FSAR Tables 7.5-1 and 7.5-2 Sh 4 ( Alarm Panels) 2717-1002 4 09-08-78 ESFAS General Arrangenent Ref FSAR Tables 7.5-1 and 7.5-2 gg Sh 5 (Test Panel. Auto / Manual Switch Panel) ESFAS General Arrangement Ref r'SAR Tables 7.5-1 and 7.5-2 l13 2717-1002 4 09-08-78 Sh 6 (nameplate Arranqement) l18 Table 1.7 4 (sheet 4) Fevision 33 4/01 9 9 9
MIDLAND 1&2-FSAR l l l TABLE 1.7-10 1 BOP S'ISTEM LOGIC DIAGRAMS Drawing No. Rev. Date Title RemarksD8 J-299-01 7 09-09-80 Engineered Safety Figure 7.3-2 J-299-02 7 09-09-80 Features Actuation Figure 7.3-3 32 J-299-03 7 09-09-80 System (BOP) Figure 7.3-4 J-299-04 8 10-31-81 Figure 7.3-5 J-299-05 7 05-09-80 Figure 7.3-6 J-299-06 7 10-31-81 Figure 7.3-7 33 ' J-299-07 7 09-09-80 Table 7.3-3 J-299-08 7 09-09-80 Figure 7.3-8 J-299-09 3 09-09-80 Figure 7.3-9 01 Reference FSAR Subsections 5.4.7.2, 6.2.2.1, 6.2.4.2, 6.8.2.3, 7.3.3.2, 7.4.1.1.7, 9.2.1.2, 9.2.2.2, 9.2.10.2, 9.3.4.2, 9.4.1.2, 15 9.4.2.2, 9.4.5.2, 10.3.2.3, 10.4.7.2, and 10.4.9.2. 2 O O Revision _33 4/81
MIDLAND 1&2-FSAR TABLE 1.7-11 BOP EQUIPMENT LOGIC DIAGRAMS Drawing No. Riv ., Date Title Remarks J-001-1 2 05-21-76 Logic Diagram Legend and While this drawing is not specifically referenced in the FSAR, it is Notes submitted as an aid in understanding the logic diagrams. J-001-2, 2 1 01-26-76 Logic Diagram Legend and While this drawing is not specifically referenced in the FSAR, it is J-001-3, & Notes submitted as an aid in understanding the logic diagrams. J-001-4 J-004-3 0 08-06-80 Logic Diagram, Reactor Ref FSAR 7.4.1.16 Coolant Pressurizer 30 Heater J-006-1 2 02-02-81 Reactor Coolant Ref FSAR 5.4.13 s-vv: 'O 02-02-81 PORV Valves 33 J-006-3 1 02-02-81 J-006-4 1 02-02-81 J-007-1, 7 11-24-80 Makeup Pump Ref FSAR 9.3.4.2 32 J-007-2, 6 11-24-80 g 33 J-007-3 4 02-19-80 l J-008 3 02-19-80 Reactor Coolant Letdown Ref FSAR 7.6.1, 7.6.1.4, 9.2.2.2, 9.3.4.2 l 29 Cooler Inlet Valve 5 J-009 2 02-19-80 Reactor Coolant Letdown Ref F3AR 6.2.4.2, 9.3.4.2 Shutoff Valve J-011 2 12-12-77 Reactor Coolant Pump Seal Ref FSAR 6.2.4.2, 9.3.4.2 Injection Valve J-012 3 02-19-80 Reactor Coolant Pump Seal Ref FSAR 6.2.4.2, 9.2.2.2, 9.3.4.2 l 32 Rett:rn Valve J-014 4 08-15-80 High-Pressure Injection Ref FSAR 6.2.4.2, 9.3.4.2 l 32 Valve 16 J-015-1. 3 01-08-79 Makeup and Purification Ref FSAR 6.2.4.2 9.3.4.2 J-015-2 0 01-08-79 System Isolation Valve 33 J-016 3 12-05-78 Makeup Tank Isolation Ref FSAR 9.3.4.2 16
alve Table 1.7-11 (sheet 1)
Pcvision 33 4/01 O O O
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l' O G /. MIDLAND 1&2-FSAR
.I TABLE 1.7-11 (continued)
Drawing 2 No. Rev. Date Title Remarks J-017-1 & 6 03-20-81 Decay Heat Removal Pump Ref FSAR 5.4.7.2 ll 33 J-017-2 5 03-20-81 J-018-1 & .4 11-27-78 Decay Heat kemoval Heat Ref FSAR 5.4.7.2 18 J-018-2 2 11-28-78 Exchanger Discharge Valve J-019-1 4 05-16-78 Decay Heat Removal Heat Ref FSAR 5.4.7.2, 7.1.2.5 Exchanger Bypass Valve J-019-2 4 05-16-78 Decay Heat Removal Heat Ref FSAR 5.4.7.2, 7.1.2.5 11 Exchanger Bypass Valve J-020-1 & 5 11-27-78 Low-Pressure Injection Rcf FSAR 5.4.7.2, 6.2.4.2,.7.1.2.5 18 J-020-2 Valve J-021-1 4 08-07-80 Decay Heat Cooldown Ref FSAR 5.4.7.2, 6.2.4.2 J-021-2 3 11-27-78 Isolation valve 32 J-022-1 5 08-13-80 Core Flood Tank Outlet Ref FSAR 5.4.7.2, 7.1.1.5, 7.6.1, 7.6.1.3 J-022-2 4 11-27-78 Bleck Valve J-025-2 0 1C-15-80 Dilution Flow Indication Ref FSAR 7.6.1.5 l 33 J-026-1 & 3 11-27-78 Reactor Building Spray Ref FSAR 6.2.2.1 J-026-2 Pump J-027 3 11-27-78 Reactor Building' Spray Ref FSAR 6.2.2.1, 6.2.4.2 Valve 18 J-028-1 & 2 '11-27-78 Borated Water Storage Tank Ref FSAR 5.4.7.2, 6.2.2.1 J-028-2 Outlet Valve J-029-2. & 3 11-27-78 Reactor Building Emergency. Ref FSAR 5.4.7.2, 6.2.2.1, 6.2.4.2 J-029-2 Sump outlet Valve J-031 2 08-16-77 Fuel Pool Cooling Pump Ref FSAR 9.1.3.2 2
~
J-035-1 3 07-21-80 Component Cooling Water .Ref FSAR 9.2.2.2 J-035-2 3 07-21-80 Pump '32 J-036-1 3 07-21-80 Component Cooling Water Re f FSAR 9.2.2.2 J-036-2 3 07-21-80 Spare Pump l2 I Table 1.7-11 ( i (sheet 2) revision 33
, t/81 9 g- . _ _ - . , __. .p
MIDLAUD A&4-FSAR TABLE 1.7-11 (continued) Drawing No. Rev. L =. Title Remarks J-040 1 07- -77 Component Cooling Water Ref FSAR 9.2.2.2 Decay lieat Cooler Llock 2 valve J-041 1 07-05-77 Component Cooling Water Ref FSAR 9.2.2.2 Heat Exchanger Bypass Isolation Valve J-043-1, 2 31-12-80 Component Cooling Water Ref FSAR 9.2.2.2 J-043-2, 2 11-12-r0 Loop Isolation valve 33 J-043-3, 0 11-12-E9 J-043-4 0 11-12-80 J-044 1 07-05-77 Camponent Cooling Water Ref FSAR 6.2.4.2, 9.2.2.2 - System Reactor Building Isolation Valve J-045-1, 3 03-12-80 Service Water Pump Ref FSAR 9.2.1.2 J-045-2, 3 03-12-80 32 J-045-3 3 0'l-12-80 J-046-1. 3 03-12-80 Spare Service Water Pump Ref FSAR 9.2.1.2 J-046-2, 3 03-12-80 J-046-3 2 03-12-80 l33 J-050-1& 2 08-21-78 Service Water Pump Pit Ref FSAR 9.2.1.2 J-050-2 Sluice Gate Motor 14 J-051-1& 3 08-10-78 Gervice Water System Ref FSAR 9.2.2.2 J-051-2 Loop Isolation valve J-052 2 12-17-79 Service Water System Ref FSAR 9.2.1.2 l 27 Turbine Plant and Cooling l 2 3 Tower Isolation valve l 14 J-053 2 08-21-78 Diesel Generator Cooler Ref FSAd 9.2.1.2 l 18 Isolation Valve Service Water System Ref FSAR 9.2.1.2 1 21 J-054 2 04-17-79 Emergency Cooling Pond Return Valve l2 Table 1.7-11 (sheet 3) Fevision 33 4/R1 0 9 9
... , . _ _ - . ~ . . ~ ~ . - - . . . -. - .. - - . _ . - ~ . - - ~ . . - . . - . . - .- ~-- . . - . . . . ..
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~ ~
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6 J MIDLAND 1&2-FSAR , 1 i ? TABLE 1.7-11 (continued) 1 2 Drawing No. Rev. Date Title Remarks J-055 2 11-16-78 Service Water System CCW Ref FSAR 9.2.1.2 l18 - Heat Excbunger Block Valve l2 J-056 2 01-04-80 Service water to Ref FSAR 9.2.1.2 -l Circulating water Pumps and Chemical Injection 2 System Isolation Valve 1 J-058 2 11-16-78 Reactor Building Air Ref FSAR 6.2.2.2, 6.2.4.2, 9.2.1.2 18 Cooler Isolation valve , J-085 1 02-21-80 Service Water Eystem Ref FSAR 9.2.1.2 l } Strainers J-102 1 12-27-77 Reactor Coolant Letdown Block valve Ref FSAR 7.6.1, 7.6.1.4, 9.2.2.2, 9.3.4.2
-l5 '
J-118 1 06-25-80 Main Steam Units 1 and 2 kef FSAR-Table 7.3-3 30 Crosstie Valves J-132-1, 6 11-03-80 Auxiliary Feedwater Pump- Ref FSAR 7.4.1, 7.4.1.1, 9.2.1.2, 10.4.t.2 [ 2 1 J-132-2, Turbine 2
- J-132-3, &
1 J-132-4 j J-133-1 6 11-03-80 Auxiliary Feedwater Pump- Ref F3AR 7.4.1, 7.4.1.1,.9.2.1.2, 10.4.9.2 3 J-133-2 5 11-03-80 Electric 32 ; J-136 3 11-03-80 Auxiliary Feedwater Pump . Ref FSAR 10.4.9.2 Recirculating Valve- l gg ; J-138-1 4 01-09-81 Steam Generator Main Ref.FSAR 6.2.4.2, 10.4.7.2 33 J-138-2 5 01-09-81 Feedwater Isolation Valve
- l. J-138-2A 1 01-09-81
. J-138-3 4 09-10-79 l 29
- J-138 4 4 09-10-79 J-139-1, 3 03-11-81 Main-Auxiliary'Feedwater Aef FSAR 10.4.9.2 J-139-2 0 03-11-81 Crosstie Isolation Valve 33 -
} 5 '.01-09-81 Auxiliary Feedwater- Ref FSAR 7.4.1.1, 10.4.9.2 ! J-141-1, J-141-2 -System Valves l gg 4 5' 7 Table 1.7-11 (sheet 4 ) - Fevision 33
-4/81
? 5
MIDLAND 1&2-FSAR TAPLE 1.7-11 (continued) J Drawing 2 ] No. Rev. Date Title Remarks l J-167 3 11-12-80 Reactor Building Collec- Ref FSAR 6.2.4.2 l 33 i tion lleader Isolation Valve l2 4
- J-168-1, 0 12-17-79 Main Steam Line Block bef FSAR Table 7.3-3 j* 33
! J-168-2 1 01-;r-80 Valvo Unit 1 J-173-1 & 3 11-27-78 Reactor Building Isola- Ref FSAR 6.2.2.1. o.2.4.2, 9.1.3.2 l 18
, J-173-2 tion Valve - Motor l2 Operated I i
t 14 4 J-174 1 08-10-78 Reactor Bu11 ding Isola- Ref FSAR 6.2.2.1, 6.2.f.2 3 i tion valve - Air operated l2 J-175 1 08-29-78 Reactor Coolant Letdown Ref FSAR 6.2.4.2, 9.3.4.2 l 14 ] Ccoler Isolation Valve l2 1 i 1 i 4 I, i i i Table 1.7-11 l (sheet 5) - Pevision 33 4/01 i e 4 i O O O
,- - - . . - - .. - . - . ~ - ~. . - . - , _ . - - . . . - - . _ , . -- _ --
4 . ( D l R MIDLAND 1&2-FSAR i I f- TABLE 1.7-11 (continued) J f Drawing No. Rev. Date Title Remarks l2 l 2' J-176 1 12-12-77 Reactor Coolant Pump Seal Ref FSAR 6.2.4.2, 9.3.4.2 l5-Return Shutoff Valve 12-J-177-1 & 3 03-06-79 Reactor Building Isola- Ref FSAR 5.4.7.2, 6.2.4.2, 6.8.2.3, 9.2.6.2 32 J-177-2 4 06-19-80 tion valve Solenoid - Valve 12 . J-178 4 05-30-79 Typical Safety-Related Ref FSAR 5.4.7.2 l 27 Motor Operated Valve 18 , J-179 1 11-27-78 BWST Recirculation and Ref FSAR 6.2.2.1 Purification Outlet and 2 Return Valves 4 J-184 5 01-12-79 Typical Solenoid Valve, Ref FSAR 5.4.7.2, 6.8.2.3 1 18
- Energize to Open l2 J-185 2 12-04-80 Typical Solenoid valve, Ref FSAR 9.2.2.2 1 33 Energize to close 12 J-188 1 11-16-78 Emergency Diesel Oil Ref FSAR 9.5.4.2 -
Transfer Pump gg J-189 0 02-07-79 Reactor Building Spray Ref FSAR 6.2.2.1 Systeta Hydrazine Pumps l 14 i J-198-1 2 06-19-80 Penetration Pressurization Ref FSAR 6.2.4.2, 6.8.2.3 - I 32 4 System Valve l2 I i J-203 3 12-12-78 Auxiliary Feedwater Pump Ref FSAR 6.2.4.2, 10.4.9.2 l 18 i Turbine Main Steam Supply Block Valve l2 I 3 a J-215 1 09-12-78 Reactor Building Vent Ref FSAR 6.2.4.2 . l 14 Header Isolation Valve- Il 2
- J-221 5 08-28-80' High-Pressure Penetration Ref FSAR 6.2.4.2, 6.8.2.3 l 32 Pressurization %31ve-
- j. J-226-1 & 3 03-13-80 Condensate Storage Tank Ref FSAR 10.4.9.2 I29-1 J-226-2 Auxiliary Fewhater Supply , 2 Valve a
1 k ' Table 1.7-11 (sheet 6) Revision 33
~4/81 y y ,. -. . , - - . . , . - , p
MIDLAND 1&2-FSAR TABLE 1.7-11 (continued) Drawing 2 No. Rev. Date Title Remarks J-227-1, 5 11-03-80 Service Water System Ref FSAR 10.4.9.2 32 J-227-2, 5 11-03-80 Auxil4.ary Feedwater Supply J-227-3 1 03-13-80 Valve J-230 1 11-29-78 Feedwater Startup Drain Ref FSAR 6.2.4.2, 10.4.7.2 18 Valve J-231 3 03-13-80 Motor Driven Auxiliary Ref FSAR 10.4.9.2 l 29 Feedwater Pump Condensate i Storage Tank Block Valve I 2 J-232-1 & 5 11-24-80 Standby Makeup Pump Ref FSAR 9.3.4.2 32 J-232-2 1 18 J-234-1, 4 01-09-81 Steam Generator Auxiliary Ref FSAR 6.2.4.2, 10.4.9.2 J-234-2, 4 01-09-81 Feedwater Isolation Valve - 33 J-234-3 5 01-09-81 Motor Operated J-235 2 11-27-70 High-Pressure Injection Ref FSAR 9.3.4.2 2 Supply Valve J-237-1 & 3 C6-11-79 Makeup Pump Auxiliary Ref FSAR 9.3.4.2 l 25 J-237-2 Lube Oil Pump l 2 J-238-1 & 3 06-11-79 Spare Makeup Pump Ref FSAR 9.3.4.2 l 25 J-238-2 Auxiliary Lube Oil 2 Pump J-151 2 11-It-78 Reactor Building Air Ref FSAR 6.2.2.2, 6.2.4.2, 9.2.1.2 l 18 Cooler Throttling Valve J-252-1 1 03-17-80 Auxiliary Feedwater Ref FSAR 10.4.9.2 J-252-2 1 03-17-80 Isolation valve 32 J-252-3 1 03-17-80 J-253-1 3 08-11-80 Decay Beat Return Re f FSAR 5.4.7.2, 6.2.4.2, 7.6.1, 7.6.1.2 J-253-2 3 08-11-80 Isolation Valve J-258 2 02-21-79 Main Steam T,ine Isolation Ref FSAR 6.'.. 2, 10.3.2.3 l 21 valve Alarms and Status I 2 Light l Table 1.7-11 (sheet 7) Revision 33 4/81 O O O
f
- i. ~ -
)
1 j' 4 MIDLAND 1&2-FSAR e i TABLE 1.7-11 (continued) I 4 3 2
! Drawing i No. Rev. Date Title Remarks Re f . FSAR 7.4.1.1, 10.4.9.2 l 33-J-261-1 & 3 02-20-01 Auxiliary Feedwater Flow i J-261-2 Control valve Indication
.{ 2 i J-262 1 07-18-77 EF5AS Subsystem Manual i Bypass Status Lamp j i J-263 0 02-24-78 Decay Heat Removal System Ref FSAR 5.4.7.2 l18 ' Dump to Sump Valves .2 J-264 2 05-30-79 Low Pressure Injection Ref FSAR 5.4.7.2. l 27 Crosstie Valves i 2- }. i 1. J-298 1 05-16-78 Core Flood Tank Vent Valve Ref FSAR 5.4.7.2, 7.1.2.5 lSf J-420-1 2 05-05-80 Service water Pump Cooling Ref FSAR 9.4.8.2 I 32 J-420-2 2 12-12-78 Fans l 18 ~
! J-421-1 2 05-05-80 Service water Standby Ref FSAR 9.4.8.2 32 J-421-2 1 08-03-78. Pump Cooling Fan j'
1 J-422-1, 1 12-12-78 Traveling Screen Room Ref FSAR 9.4.8.2.4 j' i J-422-2 1 12-12-78 Cooling Fans J-423-1 &. 2 05-05-80 Diesel Generator Supply Ref FSAR 9.4.7.2 J-423-2 1 J-429-1, 1 05-05 Typical Modulating Valves .Ref FSAR 9.4.8.2.4 J-429-2, 0' and Dampers-J-429-3 0 33 J-460-1, 0 04-15 Recirculating Air Cooling..Ref FSAR 9.2.1.2.4 J-460-2' O -Unit Booster Pumps and. Reactor Building Return Bypass Valves J-502-1, 0 12-04-80 RCP Seal Cooler CCW Isola- Ref FSAR 9.2.2.2 J-502-2 0 tion Valve J-504- 0 12-04-80 CCW Radiation Monitor Ref FSAR 9.2.2.2 Isolation valve Table 1.7-11
~ (sheet 8 )
Revision 33'
'4/81
MIDLAND 1&2-FSAR TABLE 1.7-11 (continued) Drawing No. Rev. Date Title Remarks J-806-1 & 1 04-28-77 Component Cooling Water Ref FSAR 9.4.5.2 J-806-2 Pump Room Unit Cooler J-807 1 03-24-78 Spare CCW Pump Room Unit Re f FSAR 9.4. 5.2 2 Cooler J-808-1 & 1 04-28-77 Makeup Pump Room Unit Ref FSAR 9.4.5.2 J-808-2 Cooler J-809 0 01-13-76 Spare Makeup Pump Unit Ref FSAR 9.4.5.2 Cooler 7-810 2 02-22-80 Auxiliary Feedwater Electric Pump .'aom Unit Ref FSAR 9.4.5.2 l2 Cooler J-811 2 01-08-79 1uxiliary Feedwater Steam Ref FSAR 9.4.5.2 Driven Pump Room Unit Cooler Table 1. ~i- 11 (sheet Sa) Revision 33 4/81 O O O
.i I
O O O .
.I MIDLAND 1&2-FSAR
~
THIS SHEET INTENTIONALLY LEFT BLANK. .a p. l
's I
s ; - e. i ' Table ~1.7-11 r(sheet 8b)
~
l' l
-Revision'33 :l I
4/51 -- s c
- . _ . . _ . _ _ = - _ . . . . . _ - - - - _ ..--.a_.--__.._._-. .. - - _ .- ._ _ . -.
MIDLAND 1&3-FSAR TABLE 1.7-11 (continued) Drawing No. Rev. Date Title Remarks J-812 1 04-28-77 Decay Heat Removal Heat Ref FSAR 9.4.5.2 2 Exchanger Room Unit Cooler J-813 1 04-28-77 Engineered Safeguards Pump Ref FSAR 9.4.5.2 Boom Unit Cooler J-824 1 01-08-79 Safeguards Chilled Water Ref ESAR 9.2.10.2 l18 Pump l 2 J-825 1 03-27-79 Switchgear and Battery Ref FSAR 9.4.1.2 l21 Room Unit Coolers l5 J-629-1, 3 10-13-78 Auxiliary Building Safety- Ref FSAR 9.2.10.2 l 18 J-829-2, Related Chiller Indication J-829-3, and Alarms 5 J-829-4, & J-629-5 J-831 1 08-08-77 Fuel Area Safety Isolation Ref FSAR 9.4.2.2 l 2 Dampers l J-832-1 & 2 12-28-78 Fuel Area Emergency Ref FSAM 9.4.2.2 I 2 J-832-2 Exhaust Fan i 18 J-834-1 & 2 03-02-79 Reactor Building Recircu- Ref FSAR 6.2.2.2 l 21 J-834-2 2 01-10-79 lating Air Cooling Unit 18 Fan 2 J-841-1 & 3 01-12-81 Reactor Building Isolation Ref FSAR 6.2.4.2 33 J-841-2 2 01-13-81 Dampers Motor Operated J-854 3 09-09-80 Control Room A/H Unit Ref FSAR 9.4.1.2 32 J-855 2 07-18-77 Control Roor. A/H Unit Ref FSAR 9.4.1.2 Discharge and Return 2 Dampers J-856 4 09-08-80 Control Room Recirculating Ref FSAR 9.4.1.2 1 32 Air Fan l 21 Table 1.7-11 (sheet 9) Revision 33 4/81 O O O
t i , l MIDLAND 1&2-FSAR TABL4 1.7-11 (continued) Drawing 2 No. Rev. Date Title Remarks J-857 4 04-02-79 Control Room Recirculating Ref FSAR 9.4.1.2 21 Air Filter Fan Discharge and Suction Dampers J-858 2 07-18-77 Control Room Recirculating Ref FLAR 9.4.1.2 Air Filter Fan Bypass Damper 09-08-80 Control Room Makeup Air 12 J-859 4 Ref FSAR 9.4.1.2 Supply Fan J-860 2 07-18-77 Control Room Makeup Air Ref FSAR 9.4.1.2 Supply Fan Discharge and '2 Suction Dampers J-861 2 07-28-77 Control Room Makeup Air Ref FSAR 9.4.1.2 Supply Fan Bypass Damper J-862 3 09-10-80 control Room outside Air Ref FSAR 9.4.1.2 1 32 Intake and Switchgear. Room Air Supply Isolation 2 Dampers J-863-1 & 3 02-01-79 Cable Spreading Roca Re f FSAR 9.4.1.2 ' 21 J-863-2 Supply and Contrni Room 2' Exhaust Dampers J-864 4 02-01-79 Control Room Emergency Ref FSAR 9.4.1.2 21 Makeup Air Supply Valve 2 J-865 2 07-18-77 Control Room A/H Humidi- Ref FSAR 9.4.1.2 fier Steam Supply Isola-tion valve J-867 3 09-08-80 Battery Room Exhaust Fan Ref FSAR 9.4.1.2 l 32' and Discharge Damper l 2 27 , J-869 B 06-20-79 Control Room Pressurizing Ref FSAR 9.4.1.2 '2 System Flow Control Valve Table 1.7-11 (sheet 10) ' Revision 32 1/81
MIDLAND 1&2-FSAR TABLE 1.7-12 BOP SYSTEM AND EQUIPMENT LOOP DIAGRAMS Drawing Title Remarks 5 No. Rev. Date J-300-1 3 05-22-79 Loop Diagran Legend and While loop 127 Notes diagrans are 5 not specifically J-300-2 0 05-22-79 Loop Diagran Legend and referenced in 125 Notes the PGAR text, 130 they are 25 J-300-3 0 06-06-79 Loop Diaqran Legend and supplied to Notes provide repre- 3 sentative loop J-302-4 3 02-17-81 Reactor Coolant Systen details to clarify instru-ment instal-lation J-302-5 0 01-29-81 Reactor Coolant Systen 33 J-302-6 0 01-29-81 Reactor Coolant Systen J-302-7 0 01-29-81 Reactor Coolant Systen J-303-06 1 01-19-79 Makeup and Purification, 5 Units 1 & 2 J-303-07 1 01-19-79 Makeup and Purification, l14 Units 1 & 2 15 J-303-08 1 07-13-79 Makeup and Purification, Units 1 & 2 2 07-13-79 Makeup and Purification, 25 l J-303-09 Units 1 & 2 J-303-16 0 01-12-81 Makeup and PurifL:ation, Units 1 & 2 33 J-303-17 0 01-12-81 Makeup and Purification, Units 1 & 2 J-316-02 3 06-11-79 Component Cooling Water, i 27 Units 1 & 2 15 J-316-04 2 06-11-79 Component Cooling Water, l 27 i Units 1 & 2 15 (sheet 1) Revision 33 4/81
.- - . . =. - . . -- .-
4
. MIDLAND 1&2-FSAR 1 ;.
TABLE 1.7-12 (continued) v Drawing 5 No. Rev. Date Title Remarks J-316-05 1 06-11-79 Component Cooling Water, [ 27 Units 1 & 2 5 J-316-06 0 10-06-77 Component Cooling Water, Units 1 & 2 J-316-08 2 _04-03-80 Component Cooling Water, l 32 Units 1 & 2 15 J-316-09 2 03-11-81 Component Cooling Water, l 33 Units 1.& 2 l5 J-316-ll 2 02-12-81. Component Cooling Water, l 33 l Units 1-& 2 l 14. ' J-318-07 3 03-18-81 Serv 'e Water Cooling l 33 Tow and Pump Service 5 Stru cure
- Ds_/
J-319-05 4 07-22-80 Service' Water, Reactor, and Auxiliary Building 32 5 J-321-07 1 07-18-79 Reactor Building Pene- l 25 4 tration Pressurization' 5 4 Units 1 & 2 J-337-07 3 01-07-81 Feedwater and Condensate, l33-Unit 2 J-337-17 2 07-23-79 Feedwater and Condensate, 25 Unit 2 J-337-25 2 01-07-81 Feedwater and Condensate, 1 33 Unit 2 1 25 J-337-26 2 01-07-81 Feedwater and Condensate, 33 Unit 2 5 l J-337-29 2 08-13-80 Feedwater and Condensate, t Unit 2 J-337-30 2 08-13-80 Faedwater and Condensate, . Unit 2 i lO (sheet 2)
- Revision 33 l 4/81 l
MIDLAND 1&2-FSAR TABLE 1.7-12 (continued) O Drawing 5 No. Rev. Date Title Remarks J-337-31 2 08-13-80 Feedwater and Condensate, Unit 2 32 J-337-32 1 08-13-80 Feedwater and Condensate, Unit 2 l 19 J-338-19 3 01-07-81 Feedwater and Condensate, l 33 Unit 1 l J-338-20 2 06-05-79 Feedwater and Condensate, 25 Unit 1 J-338-22 2 07-23-79 Feedwater and Condensate, Unit 1 J-338-27 2 08-13-80 Feedwater i1d Condensate, ', 21 Unit 1 15 J-338-28 3 01-07-81 Feedwater and Condensate, l 33 Unit 1 15 J-338-29 2 07-10-80 Feedwater and Condensate, Unit 1 J-338-30 2 08-13-80 Feedwater and Condensate, Unit 1 32 J-338-31 2 08-13-80 Feedwater and Condensate, Unit 1 J-338-32 1 08-13-80 Feedwater and Condensate, Unit 1 l 19 J-342-1 0 01-12-81 Emergency Boration System l33 J-342-2 0 01-12-81 Emergency Boration System l J-352-05 3 07-31-79 Emergency Diesel Fuel Oil l 27 Storage and Transfer l5 J-357-05 1 03-10-80 Chilled Water System 29 J-357-06 1 02-22-80 Chilled Water System
~
J-365-01 2 09-13-79 Control Roon IIVAC l (sheet 3) Revisi)n 33 4/81
4 MIDLAND 1&2-PSAR ( k TABLE 1.7-12 (continued)_ Drawinq
'No. Rev. Date Title Remarks
- J-365-06 3 08-04-80 Control Room HVAC 32 ,
J-365 3 08-05-80 Control Room HVAC J-368-01 3 03-10-80 Miscellaneous Structure l 29 HVAC 18 J-368-02 1 02-13-79 Miscellaneous Structure l HVAC J-368-03 2 03-10-80 Miscellaneous Structure l 29 HVAC l 18 . i J-368-04 1 11-21-78 Miscellaneous Structure $4 HVAC J-369-1 0 02-05-81 Post-Accident Monitoring J-369-2 0 02-05-81 Post-Accident Monitoring J-369-3 0 02-05-81 Post-Accident Monitoring J-369-4 0 02-05-81 Post-Accident Monitoring J-373-3 1 08-14-79 Service Water Systen J-383-1 0 12-23-80 Auxiliary Feedwater J-383-2 0 12-23-80 Auxiliary Feedwater J-383-3 0 12-23-80 Auxiliary Feedwater 33 J-383-4 0 12-23-80 Auxiliary Feedwater J-392-1 3 09-30-80 Instrument Rack UN 1C166 J-392-2 3 09-30-80 Instrument Rack UN 1C166 J-392-3 2 09-30-80 Instrument Rack UN 1C166 i J-392-4 2 09-30-80 Instrument Rack UN 1C166 J-393-1 3 09-30-80 Instrument Rack UN 2C166 O (sheet 4) Revision 33 4/81
., . . . . . . _ . _ . . , _ ~ _ _ . _ - . . _ . _ _ _ _ _ . _ . _ - _ _ _ _ _ . . _
MIDLAND 1&2-FSAR TABLE 1.7-12 (continued) Drawing No. Rev. Date Title Renarka J-393-2 3 09-30-80 Instrument Rack UN 2C166 J-393-3 2 09-30-80 Instrument Rack UN 2C166 J-393-4 2 09-30-80 Instrument Rack UN 2C166 33 l J-397 1 03-03-81 Instrument Rack Power Diagram O i l i I ( Rey?3**" t Sy 33 4/81
-.n - - I MIDLAND 1&2-PSAR TABLE 1.7-13
) BOP INSTRUMENT LOCATION DRAWINGS Drawing No. Rev. Da te Tj tle Remarks J-3101 8 08-05-80 Area 1, Elevation 568'-0" While instrument location drawings J-3102 6 07-08-80 Area 1, Elevation 584'-0" are not specifically J-3103 7 06-25-80 Area 1, Eleva tion 584 '-0" referenced in the PSAR text, 32 J-3104 6 08-13-80 Area 1, Elevation 599'-0" they are supplied to aid .
J-3105 5 06-18-80 Area 1, Eleva tion 599'-0" in determining seismic and J-3106 5 06-11-80 Area 1, Elevation 614'-0" environmental criteria and J-3107 4 08-05-80 Area 1, Eleva tion 614 '-0" to illustrate , instrument J-3108 1 06-20-79 Area 1, Eleva tion 624 '-0" location and 27 separation J-3109 6 08-05-30 Area 1, Eleva tion 634 '-6" where applicable 32 J-3110 6 08-05-80 Area 1, Elevation 634'-6" J-3111 4 03-17-80 Area 1, Elevation 634'-6" 29 J-3112 4 03-21-80 Are a 1, Fleva tion 645 '-0" J-3113 3 03-21-80 Area 1, Elevation 645'-0" J-3115 3 08-11-80 Area 1, Eleva tion 659 '-0" 32 J-3116 3 08-13-80 Area 1, Eleva tion 6 59 '-0"
.7-3124-1 4 03-20-81 Area 2, Elevation S93'-6" l33 J-3124-2 1 08-01-80 32 J-3125 2 03-23-81 Area 2, Eleva tion 62 6 '-0" J-3126 3 03-26-81 Area 2, Elevation 640'-0" Ref Fig. 7.2-5*
J-3127 2 03-20-81 Area 2, Elevation 659'-0" 33 J-3128 2 03-20-81 Area - 2, Eleva tion 685 '-0" J-3130 1 01-28-81 Solid Radwaste Building
' 32 (d
- J-3132 2 08-05-80 Safety-Rela ted Yard Piping (sheet 1)
Revision 33 4/81
MIDLAND 1&2-FSAR TABLE 1.7-13 (continued) O Drawing No. Rev. Date Title Remarks J-3133 2 08-05-80 Sa fety-Rela ted Yard Piping J-3134 6 08-15-80 Area 3, Elevation 568'-0" J-3135 5 08-15-80 Area 3, Eleva tion 584 '-0" J-3136 5 08-13-80 Area 3, Elevation 599'-0" J-3137 2 08-05-80 Area 3, Eleva tion 614 '-0" J-3138 2 08-13-80 Area 3, Elevation 614'-0" J-3139 3 12-23-80 Area 3, Eleva tion 63 4 '-6" 33 J-3140 3 12-23-80 Area 3, Elevation 634'-6" J-3141 1 08-05-80 Area 3, Elevation 634' J-3143 1 08-05-80 Area 3, Elevation 659'-0" J-3147 2 08-05-80 Area 3, Elevation 685'-0" J-3148 1 08-05-80 Area 3, Elevation 704'-0" J-3150-1 4 02-23-81 Area 4, Elevation 593'-6" J-3150-2 1 02-23-81 J-3151 2 02-18-81 Area 4, Elevation 626'-0" J-3152 3 02-23-81 Area 4, Eleva tion 640 '-0" Ref Fig. 7.2-5 I J-3153 2 02-23-81 Area 4, Elevation 659'-0" ( J-3154 2 02-18-81 Area 4, Eleva tion 6 85 '-0" l J-3398 1 08-08-80 Diesel Generator Building Section 32 J-3199 2 08-05-80 Diesel Generator Building Section J-3204 7 12-23-80 Service Water Pump Structure, Elevation 634'-6" 33 J-3205 6 12-23-80 Service Water Pump Structure Below Eleva tion 63 4 '-6" O t l (sheet 2) Revision 33 4/81
t r
.La n
i ; 4
- - /
1 ' MIDLAND 1&2-FSAR
.t TABLE 1.7-15 BOP EQUIPMENT SCHEMATIC DIAGFMS _
Drawing f 18 6 ' and Remarks Sheet Rev. Date Title
' l 32 ' /I
- j. E-139 4 09-16-80 Steam Generator Recirculation Pugs Ref FSAR 8.3.1.2 t
2 l 19 i {' E-153 5 07-23-80 Auxiliary Feedwater Ref FSAR 7.4.1.1, 8.3.1.2, 9.2.1.., 10.'4.9.2 l 32 ! ! Turbines t 19. [
- 17. ;
1 3 2 4 [, 3 1 4 4 '32- I f 5 -3 .; 6 4 , 7 '3 27 i' 8 3 I 9 3 29 1 i i 10 3 ! 11 3 27 I 12 3 [ ' t 13 2 i
. - _ h l 29 E
3 E-154 3 GJ-13-80 Motor Driven Auxiliary. Ref FSAE 7.4.1.1, 8.3.1.2, 9.2.1.2 10.4.9.2 ,
+
Feedwater Puer. - 27 1 2 l ! 2 1 , l 3 1 21 [
,A
! 4 1 i 5' 2 l 27 ' !
+
I 6 1 7 1 21 f 8 1 ; g.
; 9 1 127 I i 10 O . I.
j 11 'O 1 12 1 l 29 4 l 21. j l E-155 5 06-04-80 Main Feedwater. Isolation Ref FSAR 6.2.4.2, 10.4.7.2 ll30 I I and Startup Draic Valves j_ 1. 1 , 21
'i1 i 1A 5 ! 2 5 3o , ! 3 5 1
1 Table 1.7-15 ( (sheet 1) .[ 1 Revision 33 4/81, t i e
MIDLAND 162-FSAR TABLE 1.7-15 (continued) Drawing and 18 Sheet Rev. Date Title Remarks 4 0 5 0 0 0 7 0 8 0 30 9 1 10 1 11 1 12 1 E-158 7 11-08-80 Auxiliary Feedwater Ref FSAR 6.2.4.2, 7.4.1.1, 10.4.9.2 System Valves 1 1 29 2 2 3 2 32 4 3 5 2 6 1 29 7 2 3 8 3 9 2 29 10 1 11 1 22 12 3 13 3 14 4 14A 1 32 15 3 16 3 17 4 18 2 29 19 2 20 2 21 2 1 27 22 3 1 32 23 2 l 27
' 24 2 25 2 29 26 3 27 3 I 32 28 3 29 2 l29 Table 1.7-15 (sheet 2)
Revision 32 1/81 O O O
l l 9 9 9 MIDIAND 1&2-PSAR t l TABLE 1.7-15 (continued) i k Drawing and 18 Ot.ea t Rev. Date Title Penarks 30 1 l 29 30A 1 1 22 31 2 1 32 2 33 2 l 29 i 34 2 1 32 ' 35 2 29 36 1 37 1 ' 38 1 32 39 2 40 1 E-185 2 05-16-79 Service Water Pumps Vent Ref PSAR 9.2.1.2 Valves 27 ! 2 1 3 1 4 1 18 5 1 6 1 E-186 5 05-02-80 Service Water Purps Ref FSAR 8.3.1.2, 9.2.1.2 , 1 2 2 2 3 3 29 4 3 S 3 Ref FSAR 8.3.1.2, 9.2.1.2 I E-187 6 10-23-80 Spare Service Water Punp l 32 l 27 1 21 ! 2 2 3 3 29 l' 4 5 S 3 g 32 6 3 29 E-191 6 12-03-80 Service Water Punp Pit Ref FSAR 9.2.1.2 i Sluice Gates 1 6 32 f i 2 5 3 3 l 29 Table 1.7-15 (sheet 3) Revision 32 1/81
MIDLAND 1&3-FSAR TABLE 1.7-15 (continued) Drawing and 18 Sheet Rev. Date Title Remarks E-192 4 12-03-80 Service Water System Ref FSAR 9.2.1.2 Loop Isolation Valves 33 2 1 3 3 E-193 5 10-18-80 Service Water System Ref FSAR 9.2.1.2 H 32 Plant Isolation Va'"es 1 3 29 2 3 3 2 3A 0 32 4 2 5 2 6 2 7 1 29 E-194 5 12-03-80 Diesel Generator Cooler Ref FSAR 9.2.1.2 Isolation Valves 33 1 5 2 2 29 E-195 3 03-21-80 Service Water System Ref FSAR 9.2.1.2 Emergency Cooling Pond 18 Return Valves 1 3 2 2 29 E-196 3 03-24-80 Service Water System Ref FSAR 9.2.1.2 Component Cooling Water Heat Exchanger Block ' 18 Valve 1 3 29 2 1 l 18 E-198 3 03-21-80 Reactor Building Air Re f FSAR 6. 2. 2. 2, 6.2.4.2, 8.3.1.2, 9.2.1.2 Cooler Throttling Valves 9 2 2 Table 1.7-15 (sheet 4) Revision 33 4/81 O O O
MIDLAND 1&2-FSAR TAst.E 1.7-15 (continued) Drawing and 18 Sheet Rev. Date Title Remarks E-199 3 03-24-80 Reactor Building Air Ref FSAR 6.2.2.2, 6.2.4.2, 8.3.1.2, 9.2.1.2 - Cooler Isolation Valves 1 3 29 2 2 3 3 4 2 E-200 4 10-26-80 Service Water to Circula- Ref FSAR 9.2.1.2 ting Water Pumps and Chemical Injection System 27 Isolation Valves 1 4 2 4 32 E-203 0 02-12-81 Component Cooling Water Ref PEAR 8.3.1.2, 9.2.2.2 l 33 to RCP Solenoid Valve 1 5 2 0 E-205 5 07-28-80' Component Cooling Water Ref FSAR 8.3.1.2, 9.2.2.2 Pumps L 4 2 4 3 5 4 5 5 5 # 6 5 7 3 E-206 3- 07-28-80 Spare C g onent Cooling Ref FSAR 8.3.1.2, 9.2.2.2 Water Pump 1 3 2 3 3 3 4 3 5 3 6 2 Table 1.7-15 (sheet 51
-Fevision 33 4/81
MID N 1&2-FSAR TABLE 1.7-15 (continued) Drawing 18 and Sheet Rev. Date Title Remarks E-209 3 03-24-80 Component Cooling water Ref FSAR 9.2.2.2 l 29 Decay Heat Cooler Block l3 2 Valve I 1 3 1 29 2 1 1 18 E-210 3 03-24-00 Component Cooling Water Ref FSAR 9.2.2.2 l 29 Heat Exchanger Bypass 18 Isolation valve 1 3 l 29 2 1 l 21 E-211 3 08-07-80 Component. Cooling Water Ref FSAR 8.3.1.2 Letdown Cooler Block l 32 valves 18 1 2 2 3 l# l 32 E-212 3 02-12-81 Cornponent Cooling Water Ref FSAR 9.2.2.2 Loop Isolation valves 1 3 2 2 3 0 4 0 5 0 6 0 33 7 0 8 0 E-213 4 02-12-81 Component Cooling Water Ref FSAR 6.2.4.2 8.3.1.2, 9.2.2.2 Reactor Building Isolation valves 1 4 2 2 3 4 4 4 g 5 3 1 29 6 3 7 0 8 0 33 9 0 10 0 Table 1.7-15 (sheet 6) Revision 33 4/01 O O O
e e e }} i MIDIAND 162-FSAR TABLE 1.7-15 (continued) Drawing and Sheet Rev. Date Title Remarks E-214 4 10-23-80 Reactor Coolant Pumps Ref FSAR 8.3.1.2 32 1 2 18 2 1 3 2 4 2 32 5 2 6 4 l21 ; 7 0 s
'f Table 1 7-15
' (sheet 6a)
Revision 3J 4/81
l MIDLAND lE2-PSAR i i , t I i i l l 6 THIS SHEET INTENTIONALLY LEPT f1ANK l i i, ! i 4 1 i . a I 1 i i i 1 i i Table 1.7-15 l (sheet 6b) Revision 33 ; 4/81 l 1 G G G
} i 4 j MIDLAND 1&2-FSAR TABLE 1.7-15 (continued) Drawing and 13 Sheet Rev. Date Title Remarks . f E 215 5 10-23-80 Reactor Coolant Pump Ref FSAR 8.3.1.2 . Ausiliary control ! 1 5 2 5 37 3 5 4 5 5 5 E-216 4 03-17-81 Reactor Coolant Pumps Ref FSAR 8.3.1.2 ac Lube oil % s 33 i 1 4 4 2 s ] 18 E-217 3 04-16-79 Reactor Coolant Pumps Ref FSAR 8.3.1.2 < dc Lube 013 Pumps 27 ! 1 3 2 2 1 18 a ' I E-218 5 06-05-80 Reactor Coolant Pressur- Ref FSAR 8.3.1.2 I iter Heaters 1 3 < 2 4 3 3 4 2 29 5 2 6 3
'7 2 8 4 9 2 10 1
- Il 0 12 0 30 i 13 0 3
14 0 15 0 E-220 3 03-21-79 Reactor Coolant Pump Power Ref FSAR 7.2.1.2 Monitoring System l 21 1 0 18 2 2
'3 2 l 21 Table 1.7-15 (sheet 7) fevision 33 4/81 4
MIDLAND 1&2-FSAR TABLE 1.7-15 (continued) Drawing and 18 Sheet _ Rev. Date Title Remacks 4 1 8 5 1 l 21 E-222 4 03-23-81 Reactor Coolant Pressur- Ref FSAR 8.3.1.2 l 33 izer Spray Valve 18 1 1 2 2 3 0 21 E-223 2 03-21-79 Reactor Ccolant Pressur- Re f FS Mt 8. 3.1. 2 izer Electrically Operated gg Reli,ef Valve E-224 4 01-27-81 Reactor Coolant Pump Ref FSAR 8.3.1.2 { 33 Space Heaters l 18 , E-225 2 03-21-79 Air Operated Valves Ref FSAR 6.2.2.1, 6.2.4.2 l 21 1 2 2 2 j 29 3 1 21 4 1 5 0 18 E-226 4 11-04-80 Reactor Coolant System Ref FSAR 8.3.1.2 Motor Operated Valves 1 2 32 2 3 3 3 4 2 E-227 3 03-17-81 Reactor Coolant and Ref FSAR 6. 2.4.2, 8.3.1.2 33 Pressurizer System 18 Solenoid Valves 1 1 2 0 27 3 2 E-231 4 09-16-80 Makeup Pumps Ref FSAR 8.3.1.2, 9.3.4.2 l 32 1 3 27 2 2 3 1 20 Table 1.7-15 (sheet 8) Revision 33 4/81 O O O
. - - - . - . - - . - . - - .--- . . - . . . - . - . . _ . ~ . _ . - . - ~ . - - . .
[ f
+
1 r MIDLAND 1&2-FSAR . 6 1
- ?
I i . TABLE 1.7-15 (continued) .i 1 f -l = Drawing .j l and 18 . I Sheet Rev. Date Title Remarks ! ]
.?
8 4 3 27 .} l 5 3 i 6 4 32 7 2 27 .i
'8 2 -
3 9 3 l 32' f 10 0 20 11 0 12 1 32 [ E-232 1 6 4 09-16-80 Spare Makeup Pump Ref FSAR 8.3.1.2, 9.3.4.2 l33 '[ 2 3 } 27 ! 3 4 1 .l20-I 4 ! 5 4 27 ! l 6- 3
- 7 3 20
! 8 1 ' 32 9 3
.10 0. L 11 0 20 4 12 1 l . .1 32 4- E-233 3 07-03-79 Makeup Pump Auxiliary Ref FSAR 8.3.1.2, 9.3.4.2 [
t Lube oil Pump - l 1 3 27 2 3 f 3 2 ~ 1 4 1 20 - 5 0- f 27 r E-234 4 .10-23-80 Spare Makeup Pump. Ref FSAR 8.3.1.2, 9.3.4.2 'h 32 i- Auxiliary Lube Oil
- Pump 27 l l l 1 4 ;
2 4 I 3 4 32. 3 4 1 5 1 .L i ! l r 1 I ! Table 1.7-15 {; (sheet 9). .. ! t Revision 33 -
~
l- 4/01 j
MIDLAND 1&2-FSM: TABLE 1.7-15 (continued) Drawing and 18 Sheet Rev. Date Title Remarks E-235 3 10-23-80 Reactor Coolant Letdown Ref FSAR 6.2.4.2, 8.3.1.2, 9.3.4.2 Cooler Isolation Valves 32 2 2 E-236 1 11-09-78 Reactor Coolant Pump Seal Ref FSAR 6.2.4.2, 9.3.4.2 Return Shutoff Valve l 18 E-237 2 03-23-79 Reactor Coolant Letdown Ref FSAR 7.6.1.4, 8.5.1.2, 9.2.2.2, 9.3.4.3 Cooler Inlet valves 1 2 2 2 21 E-238 2 03-21-79 Reactor Coolant Letdown Ref FSAR 6.2.4.2, 9.3.4.2 Shutoff Valves 1 2 2 1 E-240 3 08-03-78 Reactor Coolant Pump Seal Ref FSAR 6.2.4.2, 9.3.4.2 18 Injection Valves E-241 3 10-23-80 Reactor Coolant Pump Seal Ref FSAR 6.2.4.2, 8.3.1.2, 9.2.2.2, 9.3.4.2 Return Valves 32 2 3 E-242 3 10-19-80 High-Pressure Injection Ref FSAR 6.2.4.2, 9.3.4.2 l 32 Valves 1 2 27 2 2 3 3 ' 32 4 2 27 E-243 5 01-21-80 Makeup Pump Recirculation Ref FSAR 6.2.4.2, 9.3.4.2 Isolation valves 1 4 21 2 5 ! 27 Table 1.7-15 (sheet 10) Revision 32 1/81 O O O
,j Q ["N '% '( (r MIDLAND 1&2-FSAR TABLF 1.7-15 (continued) Drawing and 18 - Sheet Rev. Date Title Remarks E-244 4 10-23-80 Makeup and Purification Ref FSAR 9.3.4.2 System Isolation Valve 1 3 32 2 2 3 1 E-246 2 03-21-79 Reactor Coolant Letdown Ref FSAR 7.6.1.4, 8.3.1.2, 9.2.2.2, 9.3.4.2 l 21 131ock Valve l E-248 1 11-14-7e liigh-Pre ssu re Injection Ref FSAR 9.3.4.2 Supply valv 18 2 1
'-249 2 02-27-79 Decay lleat Removal Pumps Ref FSAR 5.4.7.2, 8.3.1.2 1 2 2 2 3 2 21 4 2 5 2 6 2 7 0 E-250 3 12-28-79 Decay Ifeat Removal System Ref PSAP 5.4.7.2, 7.1.2.5 Motor Operated Valves 1 3 2 1 3 1 27 4 0 5 2 6 2 7 1 l 18 E-251 2 03-09-79 Core Flooding Tank Sample Ref FSAR 5.4.7.2, 6.2.4.2, 8.3.1.2 21 Line Isolation Valves E-252 4 02-26-81 Decay lleat Penoval Low- Pef FSAR 5.4.7.2, 6.2.4.2, 7.1.2.5 g 33 -
Pressure Injection valves l 21 1 2 18 2 1 3 2 4 2 27 Table'l.7-15 (sheet 11) Revision 33 4/01
MIDLAND 162-FSAR TABLE 1.7-15 (continued) Drawing and 18 Sheet Rev. Date Title Remarks 5 1 6 2 27 7 2 Ref FSAR 5.4.7.2, 6.2 4.2, 7.6.1.2, 8.3.1.2 l 32 E-253 4 10-24-80 Decay Heat Cooldown and Return Isolation Valves 27 J 3 2 1 3 4 4 1 5 3 6 4 7 4 8 4 9 4 10 3 32 11 3 12 0 13 0 14 0 16 0 17 0 18 0 E-254 4 12-20-80 Core Flooding Tank Outlet Ref FSAR 5.4.7.2. 7.6.1.3, 8.3.1.2 7.1.2.5 and Gas Sample Valves 1 4 1A 0 2 3 132 E-255 4 11-11-80 Reactor Building Spray Ref FSAR 6.2.2.1 8.3.1.2 Pump 27 1 2 2 3 3 2 32 3A 2 4 3 5 3 E-256 3 04-21-80 Reactor Building Spray Ref FSAR 6.2.2.1 6.2.4.2 Valves 29 1 3 2 3 Table 1.7-15 (sheet 12) Revision 33 4/81 8 9 e
f% 8 (~ (%/ 's% % MIDLAND 162-FSAR TAnr.E 1.7-15 (continued) Drawing and 18 Sheet Rev. Date Title Remarks F-257 4 03-06-81 Borated Water Storage Ref FSAR 5.4.7.2, 6.2.2.1, 8.3.1.2 l33 Tank Recirculation and Outlet Valaes l 21 1 4 l 33 2 1 3 2 21 4 4 5 1 33 6 1 1 18 E-258 3 12-28-79 Reactor Buildirq Emeraency Ref FSAR 5.4.7.2, 6.2.2.1, 6.2.4.2 Sump outlet Valves 27 1 3 2 1 E-260 1 11-14-78 Reactor Building Motor Ref FSAR 6.2.2.1, 6.2.4.2, 8.3.1.2 Operated Isolation Valve 18 1 1 2 1 E-313 2 02-06-81 Radwaste Gas Vent Header Ref PSAR 6.4.4.2, 8.3.1.2 Isolation valves 33 2 1 127 E-318 1 03-21-79 Spent Fuel Pool Coolino Ref FSAR 9.1.3.2 Purnp 21 2 1 E-322 3 02-05-80 Fuel Pool Cooling Ref FSAR 6.2.4.2, 9.1.3.2 Purification System val os 2 2 3 2 E-325 3 11-04-80 Penutration Pressuri- Re' FSAR 6.2.4.2, 6.8.2.3, 8.3.1.2 33 zation Systen 27 1 2 2 1 29 3 2 4 1 27 Tanle 1.7-15 (sheet 13) Revision 33 4/83
MIDLRND 162-PSAR TABLE 1.7-15 (continued) Drawing 18 and Sheet Rev. Date Title Remarks 5 2 7 1 8 1 9 1 33 10 1 11 1 12 1 13 1 E-347 7 02-23-81 Boron Recovery Systen Ref FSAR 6.2.4.2, 8.3.1.2 l33 Reactor Duilding Collection Header 18 Isolation Valve 1 1 , 32 l 2 2 3 2 ll33 4 0 1 8 E-352 2 09-26-80 Main Sterm Line Valves Ref PSAR 6.2.4.2, 10.3.2.3 1 1 2 1 32 4 1 5 1 6 2 7 1 8 1 9 1 10 1 11 0 12 0
- 13 0 14 0 l 27 E-370 5 10-23-80 Reactor Nuclear Instru- l 32
' mentation Protection ; tg 1 0 g27 2 4 4 32 3 4 5 5 2 l27 Table 1.7-15 (sheet 14) Revision 33 4/81 O O O _ --
k i 4 1 l i MIDLAND 1&2-PSAR 1 1 TABLE 1.7-15 (continued) 1 I i
- Drawinq 18
! and i S5eet Rev. Date Title Remarks I 17 1 1 18 1 i 19 1 27 3 20 1 i 21 1 l 22 1
! 23 2 29 24 1 25 1 27 26 1 4 27 2 6 29
! 28 1 29 1 27 1
E-438 4 01-27-81 Reactor 3ailding Recircu- Ref FSAR 6.2.2.2, 8.3.1.2 l33 ' lating Air Cooling Unit 21 i Fans 1 4 33 { 2 2 h27 3 1 33 32 5 E-439 1 08-07-80 Reactor Building Ref FSAR 6.2.4.2, 8.3.1.2 l 32 ] 1 Isolation Dampers 18 < 1 1 2 1
- 3 1
) d 4 5 1 1 ? 6 1 7 1 32
- 8 1 a
9 1 i 10 1 I 11 1 l 12 1 i E-440 5 10-07-80 Reactor Building li&V Ref PSAR 6.2.5.2, 8.3.1.2 j 32 1 1 4 j 2 3 ,29 i } Table 1.7-15 (sheet 19) Fevision 33 a 4/P1 i 4
MIDLAND 162-FSAR TABLE 1.7-15 (continued) s Drawing and 18 i Sheet Rev. Date Title Remarks i
, 3 3 -l 4 4 5 3 32 L 2 7 4 8 3 29 j 10 4 11 3 29 12 3
- 13 5 32 14 4 15 3 16 3 29 17 3 18 3 18A 2
< 19 4 32 20 3 21 3 29 22 4 23 4 24 3 32 25 4 26 3 27 3 28 3 284 1 .
i 29 3 29 d 30 2 . 31 3 32 3 33 3 33A 1 34 4 32 35 3 36 0 i 37 0 E-452 5 11-21-80 Auxiliary Building H&V Ref FSAR 8.3.1.2, 9.4.2.2 32 1 3 Table 1.7-15 (sheet 20) Revision 32 1/81 O O O
@ @ 9 MIOLAf1D l&2-PGAR TAB!# 1.7-15 (continued 1 Drawing and 18 Sheet Pev. Date Title Remarks 2 2 3 5 4 2 5 3 6 2 7 4 8 1 9 3 10 3 11 3 32-12 (
13 2 14 3 15 1 15A 2 16 2 17 3 18 4 19 2 21 2 27 22 1 23 2 24 2 25 3 26 2 32 27 3 28 0 29 4 30 3 31 3 ' 27 32 2 ! 33 2 i .[ 34 1 l32 I C-456 3 08-21-80 Control Rcom Outside Pef 'SAR 9.4.1.2 l32 l Makeup and Crergency Make- l
- up Air l18 !
l 3 2 1 32 4 3 6 2 .: l Table 1.7-15 l (sheet 21) [ Revision 32 i 1/81 I..___,.__.__._-.,_.-- _ _ _ _ _ . - - - - . - . _ . . - . _ . . . _ . . - - . - . . . _ - . . _ _ . , . - - . _ . _ . - - . . - .._ ._ _..._~ ._. __ _ __._.. _ . _. ___ __ _ _ -
MIDLAN1) 1&2-FSAR TABLE 1.7-15 (continued) Drawing and 18 Sheet P;ih Date Title Rerna rk s 7 2 32 8 2 29 9 1 27 10 3 11 1 32 12 1 13 1 14 0 l 29 E-457 3 12-29-80 Control Room Air HandlinrJ Ref FSAR 8.3.1.2, 9.4.1.2 32 4 1 1 2 3 29 5 1 6 1 7 2 32 E-458 1 08-07-80 Control Room Area Ref FSAR 9.4.1.2 l 32 Recirculation and Exhaust l 18 Air l 1 1 2 1 4 1 4A 0 5 0 6 1 7 0 9 1 32 10 1 11 1 12 1 14 1 15 1 17 1 18 1 24 1 02-06-81 Miscellaneous Building Pef FSAR 8.3.1.2, 9.4.7.2, 9.4.8.2 6 33 E-468 8 18 nge 2 33 42 l 21 43 1 Table 1.7-15 (sheet 22) Revision 33 4.'81 O O O
O e e MIDLAf4D 1&2-FSAR , i TAR!,E 1.7-15 (continued) l Drawing and 18 Sheet Fev. Date Title Penarks 47 1 i 48 4 l32
- l
- 49 5 33 51 3 52 2 53 3 32 54 4 55 3 29 56 3 3 ;
57 l33 58 0 127 l E-478 3 08-07-80 Auxiliary Puilding Safe- Ref FSAR 8.3.1.2, 9.2.10.2 l32' quard Chillers -l 1 ; 1 27 2 2 ! 3 3 3A 1 4 3 32 5 3 6 1 27 7 1 ; c-480 3 08-07-80 Auxiliary Duilding. Safe- Ref FSAR 9.2.10.2 guards Chilled Water Pumps 32 2 3 : 3 1 j E-485 4 11-08-80 Encineered Safequards Unit Pef FSAR 9.4.1.2, 9.4.5 ; Coolers 27 I 3
- 1 2 3 3 3 29 4 3
, 5 3 6 3 7 3 l32^ 8 4 I 9 3 10 3
.l29 :
l i Table 1.7-15 , fsboet 21)
- Revision 33
'4/01 i S
MIDLA!1D 1&2-FSAR TABLE 1.7-15 (continued) Drawing 18 and Sheet Rev. Date ?itle Remarks 11 2 12 3 29 E-487 4 08-18-80 Plant Water Storage and Pef PSAR 6.2.4.2, 9.2.6.2 29 Transier System 27 1 3 29 2 2 3 2 4 1 27 5 2 6 2 7 3 8 2 32 8A 2 9 2 10 1 11 2 27 12 2 13 2 14 3 u 15 2 l 29 15A O 16 2 27 17 0 I Table 1.7-15 (sheet 24) Revision 32 1/81 O O O
MIDLAND 1&2-FSAR
/\ Table of Contents (continued)
Section Title Page 2.3.3.4 Service and Maintenance. . . . . . . . 2.3-24 7 2.3.3.5 Data Reduction Procedures. . . . . . . -2.3-24 2.3.3.6 Meteorological Data Recovery . . . . . 2.3-25 33 2.3.3.7 Joint Frequency Distributions of Wind Direction and Speed by Atmospheric !3 Stability Class. 2.3-25 l 30 2.3.3.8 Representativeness of Meteorological Data Collection Period Compared to Expected Long-Term Conditions. . . . . 2.3-25 33 2.3.3.9 Operational Meteorological Monitoring Program. . . . . . . . . . . . . . . . 2.3-28 r 2.3.4 SHORT-TERM (ACCIDENT) DIFFUSION ESTIMATES 2.3-29 2.3.4.1 Objective. . . . . . . . . . . . . . . 2.3-29 (,_ 2.3.4.2 Calculations . . . . . . . . . . . . . -2.3-29 2.3.5 LONG-TERM (ROUTINE) DIFFUSION ESTIMATES . 2.3-33 2.3.5.1 Objective. . . . . . . . . . . . . . . 2.3-33 2.3.5.2 Calculations . . . . . . . . . . . . . 2.3-41 References. . . . . . . . . . . . . 2.3-42 2.4 HYDROLOGIC ENGINEERING . . . . . . . . . . . 2.4-1 2.4.1 HYDROLOGIC DESCRIPTION. . . . . . . . . . 2.4-1 2.4.1.1 Site and Facilities. . . . . . . . . . 2.4-1 2.4.1.2 Hydrosphere. . . . . . . . . . . . . . 2.4-1 2.4.2 FLOODS. . . . . . . . . . . . . . . . . . 2.4-2 2.4.2.1 Flood History. . . . . . . . . . . . . 2.4-2 2.4.2.2 Flood Design Considerations. . . . . . 2.4-3 2.4.2.3 Effects of Local Intense Precipitation 2.4-3 . Revision 33 2-iii 4/81
MIDLAND 162-FSAR T'ble of Contents (continued)
- Section- Title Page 2.4.3 PROBABLE MAXIMUM FLOOD (PMF) . . . . . . . 2.4-4 2.4.3.1 Probable Maximum Precipitation (PMP) ,
. 2.4-4a l3 2.4.3.2 Precioitation Losses . . . . . . . . . 2.4-5 2.4.3.3 Runoff and Stream Course Models. . . . 2.4-5 2.4.3.4 Probable Maximum Flood Flow. . . . . . 2.4-5 2.4.3.5 Maximum Water Level. . . . . . . . . . 2.4-8 2.4.3.6 Concurrent ki:'d wave Activity. . . . . 2.4-9 2.4.3.7 Bullock Creek PMF. . . . . . . . . . . 2.4-11 2.4.4 POTENTIAL DAM FAILURES, SEISMICALLY INDUCED . . . . . . . . . . . . . . . . . 2.4-12 2.4.5 PROBABLE MAXIMUM SURGE AND SEICHE FLOODING. . . . . . . . ... . . . . . . . 2.4-12 2.4.6 PROBABLE MAXIMUM TSUNAMI FLOODING . . . . 2.4-13 2.4.7 ICE EFFECTS . . . . . . . . . . . . . . . 2.4-13 2.4.8 COOLING WATER RESERVOIRS. . . . . . . . . 2. 4 -14 2.4.9 CHANNEL DIVERSIONS. . . . . . . . . . . . 2.4-16 2.4.10 FLOOD PROTECTION REQUIREMENTS . . . . . . 2.4-16 2.4.11 LOW FLOW CONSIDERATIONS . . . . . . . . . 2.4-17 2.4.11.1 Low Flow in the Titcabawassee River. . 2.4-17 1 2.4.11.2 Low Water Resulting From Suroes ,
Seiches, or Tsunami. . . . . . . . . . 2.4-18 2.4.11.3 Historical Low Water . . . . . . . . . 2.4-18 2.4.11.4 Future Controls. . . . . . . . . . . . 2.4-19 2.4.11.5 Plant Requirements . . . . . . . . . . 2.4-19 2.4.11.6 Heat Sink rependability Requirements . 2.4-19 O 2-iv Revision 3 12/77 L
MIDLAND 1&2-FSAR Table of Contents (continued)
,_/
Section Title Page 2.4.12 DISPERSION, DILUTION, AND TRAVEL TIMES OF ACCIDENTAL RELFASES OF LIOTTID EFFLUENTS IN SURFACE WATERS. . . . . . . . . . . . . . . -2.4-20' 33 2.4.13 GROUNDWATER . . . . . . . . . . . . . . . 2.4-21 2.4.13.1 Description and Onsite Use . . . . . . 2.4-21 2.4.13.2 Sources. . . . . . . . . . . . . . . . 2.4-25 2.4.13.3 Accident Effects . . . . . . . . . . . 2.4-28 2.4.13.4 Monitoring or Jafeguard Requirements . 2.4-30 l26 2.4.13.5 Design Bases for Subsurface Hydrostatic Loading. . . . . . . . . . . . . . . . 2.4-30 2.4.14 TECHNICAL SPECIFICATIONS AND EMERGENCY OPERATIONS REQUIREMENTS . . . . . . . . . 2.4-30 ! References. . . . . . . . . . . . . 2.4-31 2.5 GEOLOGY, SEISMOLOGY, AND GEOTECHNICA ENGINEERING . . . . . . . . . . . . . . . . 2.5-1 2.5.1 BASIC GEOLOGY AND SEISMIC DATA . . . . . 2.5-1 2.5.1.1 Regional Geology . . . . . . . . . . . 2.5-1 2.5.1.2 Site Geology . . . . . . . . . . . . . 2.5-14 I 2.5.2 VIBRATORY GROUND MOTION . . . . . . . . . 2.5-29 2.5.2.1 Seismicity . . . . . . . . . . . . . . 2.5-29 2.5.2.2 Geologic Structures and Tectonic Activity . . . . . . . . . . . . . . . 2.5-34a 26 2.5.2.3 Correlation of Earthquake Activity with Geologic Structures or Tectonic Provinces . . . . . . . . . . . . . . 2.5-36 2.5.2.4 Maximum Earthquake Potential . 2.5-38 l5 2.5.2.f Seismic Wave Transmission Characteristics of the Site . . . . . 2.5-38 4 Revision 33 2-v 4/81
1 l MIDLAND 1&2-FSAR ! l l Table of Contents (continued) Section _,, Title Page 2.5.2.6 Safe Shutdown Earthquake (SSE) . . . . 2.5-38a 5 2.5.2.7 Operating Basis Earthquake (OBE) . . . 2.5-39 2-5.3 SURFACE FAULTING . . . . . . . . . . . . 2.5-39 2.5.4 STABILITY OF SUBSURFACE MATERIALS AND FOUNDATIONS . . . . . . . . . . . . . . . 2.5-40 2.5.4.1 Geologic Features . . . . . . . . . . 2.5-40 2.5.4.2 Properties of Subsurface Materials . . 2.5-40 2.5.4.3 Exploration . . . . . . . . . . . . . 2.5-44 2.5.4.4 Geophysical Survey . . . . . . . . . . 2.5-50 2.5.4.5 Excavation and Backfill . . . . . . . 2.5-51 2.5.4.6 Groundwater Conditions 2.5-52 l18 2.5.4.7 Response of Soil and Rock to Dynamic Loading . . . . . . . . . . . . . 2.5-53 l18 2.5.4.8 Liquefactidn Potential . . . . . . . . 2.5-57 2.5.4.9 Earthquake Design Basis . . . . . . . 2.5-61 2.5.4.10 Static Stability . . . . . . . . . . . 2.5-61 2.5.4.11 Design Criteria . . . . . . . . . . . 2.5-68 2.5.4.12 Techniques to Improve Subsurface Conditions . . . . . . . . . . . . . 2.5-68 2.5.4.13 Subsurface Instrumentation . . . . . . 2.5-68 2.5.4.14 Construction Notes . . . . . . . . . . 2.5-70 15 2.5.5 STABILITY OF SLOPES . . . . . . . . . . . 2.5-70a l15 2.5.5.1 Slope Characteristics . . . . . . . . 2.5-71 2.5.5.2 Design Criteria and Analysis 2.5-71 l18 2.5.5.3 Logs of Borings . . . . . . . . . . . 2.5-72 Revision 33 2-vi 4 /8,1
l MIDLAND 1&2-FSAR S Table of Contents (continued) Section Title Page 2.5.5.4 Compacted Fill . . . . . . . . . . . . 2.5-72 2.5.6 EMBANKMENTS AND DAMS . . . . . . . . . . 2.5-73 l 2.5.6.1 General . . . . . . . . . . . . . . . 2.5-73 2.5.6.2 Exploration . . . . . . . . . . . . . 2.5-74 l 2.5.6.3 Foundation and Abutment Treatment . . 2.5-75 2.5.6.4 Embankrent . . . . . . . . . . . . . . 2.5-76 2.5.6.5 Slope Stability . . . . . . . . . . . 2.5-78e l18 2.5.6.6 Seepage Control . . . . . . . . . . . 2.5-81 2.5.6.7 Diversion and Closure . . . . . . . . 2.5-82 2.5.6.8 Instrumentation . . . . . . . . . . . 2.5-82 s 2.5.6.9 Construction Notes . . . . . . . . . . 2.5-83 C-/) 2.5.6.10 Operational Notes . . . . . . . . . . 2.5-84 References. . . . . . . . . . . . . 2.5-85
- 2A TABLE OF DRILL HOLES AND BORING LOGS 2B LABORATORY TEST RESULTS l
i 2C GEOPHYSICAL SURVEY REPORT 1 Revision 33 2-vii 4/81
MIDLAND 1&2-FSAR CHAPTER 2 SITE CHARACTERISTICS TABLES Section and Number Title Section 2.1 2.1-1 Census Population and Projections by Counties Within 10 Miles of the Midland Plant 2.1-2 Resident Population Within 10 Miles of the Midland Plant 2.1-3 Incorporated Cities with Population 1,000 Within 50 Miles of the Midland Plant 2.1-4 Census Population and Projections by Counties Within 50 Miles of the Midland Plant 2.1-5 Resident Population Between 0 and 50 Miles of the Midland Plant 2.1-6 Estimated Daily Transient Population Within 5 Miles of the Midl?nd Plant 2.1-7 Total Estimated Population Distribution Including Daily Transients 2.1-8 Public Facilities Within 5 Miles of the Midland Plant 2.1-9 Public Institutions Within 5 Miles of the Midland Plant 2.1-10 Estimated Cumulative Resident Population for 1980 2.1-11 Estimated Cumulative Resident Population for 2020 Section 2.2 2.2-1 Industrial Facilities Within 5 Miles of the Midland Site 2.2-2 State Approved Roads for Trucks 2.2-3 Locations and Storage Capabilit.ics of Bulk Fuel Oil and Gasoline Storage Facilities O 2-viii
MIDLAND 1&2-FSAR F_lgures (continued)
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Section and Number Title 2.5-61 Proct'or Test and Borrow Locations 2.5-62 Creek and Drainage Locations 2.5-63 Piezometer Section P1 2.5-64 -Piezometer Section P2 2.5-65 Percent Compaction vs Depth 2.5-66 Summary of Fielt Density Tests 2.5-67 Summary of Field Density Tests 2.5-68 Summary of Field Moisture Tests 2.5-69 Summary of Field Moisture Tests 2.5-70 Gradation Curve for 12 Inch Thick Crushed Stone Bedding Under Riprap 2.5-71 Gradation Curve for 12 Inch. Thick Crushed Stone Bedding Under Riprap 2.5-72 Gradation Curve for 12 Inch Thich Crushed Stone Bedding Under Riprap 8 2.5-73 Gradation Curve for 12 Inch Thick Crushed Stone Bedding Under Riprap 2.5-74 Gradation Curve for 12 Inch Thick Crushed l Stone Bedding Under Riprap 2.5-75 Gradation Curve for 12 Inch Thick Crushed Stone Bedding Under Riprap 4 l 2.5-76 Gradation Curve for 12 Inch Thick Crushed Stone Bedding Under Riprap 2.5-77 Gradation Curve for 12 !nch Thick Crushed Stone Bedding Under Riprap 2.5-78 Dike Section Z 2.5-79 Dike Section I l Revision 15 ' j 2-xxiii 31/78 i
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MIDLAND 1&2-FSAR Figures (continued) Section and Number Title 2.5-80 Dike Section I 2.5-81 Dike Section G 8 2.5-82 Dike Section G 2.5-83 Deleted i 33 2.5-84 Dike Piezometer P2-1 8 2.5-85 Dike Piezometer P2-2 2.5-86 Bouguer Anomaly Map of the North Central United States 14 2.5-87 Basement Providence Map 2.5-88 Benchmark Locations for Subsidence Monitoring 15 Program 2.5-89 Load Intensity and Settlement Versus Time for Turbine B 2.5-90 Load Intensity and Settlement Versus Time 18 for Auxiliary Building 2.5-91 Load Intensity and Settlement Versus Time for Reactor Containment Building 2.5-92 Piezometer Elevation and Pond Elevation Versus Time for Dike Area 3g 2.5-93 Piezometer Elevation and Pond Elevation Versus Time for Dike Area 2-xxiv Revision 33 4/01 fh
MIDLAND 1&2-FSAR
- 2. SITE CHARACTERISTICS 2.1 GEOGRAPHY AND DEMOGRAPH_Y 2.1.1 SITE LOCATION AND DESCRIPTION 2.1.1.1 Specification of Location' The location of the plant site is discussed in Subsection 1.2.1.1. Its location with respect to manmade features is discussed in subsections 1.7.1.4 and 2.1.1.2.
The site topog4aphy is flat with a gentle slope eastward toward ~ ' l33 the Tittabawassee River. The locations of the centers of the two containment buildings are shown in the table below: , Universal Transverse Local Site Containment Latitude and Mercator Coordinates Coordinates Building Longitude Zone T16 (ft) 1 43*-35'-10"N N 4,829,440 M S 4,825.00 84*-13'-23"W E 724,190 M E 160.00 2 43 -35'-10"N N 4,829,440 M S 4,825.00 84*-13'-20"W E 724,260 M E 380.00
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Locations shown on construction drawings are all related to local site coordinates. Local site coordinates can be converted to Michigan state plane coordinates south zone by the relationships: SPN = 765,133.567 4 SN Cos B + SE Sin B SPE - 2,029,080.624 - SN Sin B + SE Cos B where - SPN = State plane north coordinate SPE = State plane east coordinate SN = Site north coordinate SE = Site east coordinate B = 0*-2'-57.9331" All property within the site, including mineral rights, is owned in fee by Consumers Power Company. Certain easements and leases to'others have been granted by CPCo to expedite plant l 2.1-1 Rcvision 33 l 4/81 i
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MIELANE 162-FSAR construction and operation. Easements or leases acquired with the property or granted following acquisition are as follows: 75-171 - An easement, 17 feet wide, to Midland County Poad Commission for Gordonville Foad. The easement is in addition to the 33 foot easement granted prior to acquisiticn for a total road easement of 50 feet. 76-191 - Easement to Dcw on the access road property for electric, communication, or pipelines, and access to brine well lease 4266 and waste treatment ponds northeast of the access road. 76-192 - A 40 foot wide easement to Dow along easement 75-171, west property line, and northwesterly dike for electric, communication, or pipelines. 76-193 - An easement to Dow of varying width along the north and east dikes for electric, communication, pipe, or railway lines. 4266 - A lease to Dow for one acre parcel of land in the NE 1/4, NE 1/4, NE 1/4 of Section 33 for an existing brine well. Negotiations are underway to vacate five existing drain easements on the site and combine these easements into a single 80 foot - wide drain easement for the relocation of the Waite and DeBolt l28 drain and Branch No. 1 around the south and west sides of the pond dikes. The relocation of the drains and construction of the pond and dikes has been carried out under letter agreements with local authorities. All of the above easements and leases are situated outside the perimeter fence. A portion of cnly easement 76-193 falls within the exclusion area. All easements granted to Dow contain a clause similar to the following: Notwithstanding any other provisions of this easement, exercise by Grantee of the easement and right herein granted shall be subject at all tites to (a) such rules, regulations, orders, permits, licenses and decrees as may from time to time be established or issued by the United States Nuclear Pegulatory Commission and/or other governmental agency, tribunal or court having jurisdiction over the site on which Grantor is constructing an electric generating plant, which site includes the subjact land, and over the construction and operation by Grantor of an electric generating plant on such site, and (b) Grantor's authcrity to determine all activities on the subject land, including Revision 28 h 2.1- 2 5/80
MIDLAND 1&2-FSAR
- exclusion or removal of personnel and property - (g) from the subject land.
2.1.1.2 Site Area Map The plant property line, which is also the site boundary, the location of principal Dow facilities within the exclusion area boundary, and the location of principal plant structures are shown in Figures 2.1-1, 2.1-1A, and 2.1-2, respectively. The site encompasses 1,235 acres. There are no industrial, 27 commercial, institutional, recreational, or residential structures, except for Dow brine well 28 (see Subsection 2.1.1.1), within the site boundary. The plant exclusion area is discussed in Subsection 2.1.2. The site is bordered to the north and east by-the Tittabawassee River. A railroad spur for plant use, which connects to the Chesapeake and Ohio main lines, crosses the Tittabawassee River l33 east of the site and runs westerly to the plant (see Figures 2.1-1 and 2.1-2). Gordonville Road, which is the only road immediately adjacent to the site, . runs along the southern property line next to the cooling pond. Normal vehicular access to the rite is via the access road from Poseyville Road as shown in Figure 2.1-1. This {'q is a private road owned and maintained by Consumers Power Company. Additional access is provided from Poseyville Road via 33 Miller Road through a normally locked gate at the east end of Miller Road or from Gordonvilla Road through a normally locked i gate at the dike access road t a the top of the south cooling pond dike. 2.1.1.3 Boundaries for Establishing Effluent Release Limits The boundary used to establish technical specification limits for i the release of gaseous effluents from the Midland plant is the exclusion area boundary and the perimeter fence where the ! exclusion area boundary is within the perimeter fence. The perimeter fence is located outboard of the patrol road on top of the outer dikes. See Figure 2.1-1 for layout of the exclusion j area and the top of the dike. Virtually the entire plant site, with the ex::eption .of the access corridor in Section 28, is enclosed by the perimeter fence to control casual access to the site. In addition, there is a fenced-in area surrounding the immediate plant area within the Midland site. Access to the plant area will be continuously and actively controlled by CPCo. Only specifically authorized personnel will be permitted access to the plant area. O 2.1-3 Revision 33 4/81
MIDLAND 1&2-FSAR The area between the perimeter fence and the water's edge in the case of the Tittabawassee River and the top of the northwesterly bank in the case of Bullock Creek is owned in fee by CPCo. There is no commercial river traf fic and little pleasure boat traffic on the adjoining water areas. Two parcels of property owned by Dow are included within this area: the area west of the containments across Bullock Creek which contains Dow Chemical Company's wastewater tertiary treatment pond and two tanks with associated piping, valves, and 29 equipment for storage of condensate and demineralized water being returned from Dow Chemical Company to Consumers for supplying process steam and also the clarifier area north of the containments across the Tittabawassee River. See Figure 2.1-1 for location of the Dow property. Normally, there will be no persons working in the Dow owned portion of this area. Access to these portions will be controlled by gates and Dow personnel or contractors entering the area will be controlled by, and in contact with, Dow security personnel. The Dow Emergency 29 Communications and Control Center is continuously manned by a minimum of two persons and will have direct communication with CPCo's Midland plant. The nearest gaseous release point to the described boundary is the auxiliary building stack which is located approximately at the northernmost edge of the Unit 2 containment. The minimum distancc of this release point to the boundary is 500 meters (see Figure 2.1-1) . For location of all potential release points for radioactive gaseous effluents see Figure 11.3-10. 2.1.2 EXCLUSION AREA AUTHORITY AND CONTROL 2.1.2.1 Authority The exclusion area as defined in 10 CFE 100.3(a) is described as a " race track" shaped area formed by two semicircles each with a radius of 519 meters centered on each of the two containment buildings and joined by tangents parallel to the line joining the centers of the containments. The minimum distance from the outside face of either of the containment buildings to the nearest edge of the exclusion area is 500 meters. (See Figure 2.1-1 for layout of the exclusion area on the property.) The majority of the area is owned by Consumers. Portions et the area as shown in Figure 2.1-1 include two segments of land owned by Dow and portions of the Tittabawassee River and Bullock Creek. With respect to ownership of property within the exclusi'on area owned by Dow, Dow has made the following statement: All Dow Chemical Company property which is situated within the 500 meter radius is cwned, in fee simple, by the Dow Chemical Compaay. Revision 33 2.1-4 4/81
MIDLAND 1&2-FSAR This determination was made after a thorough 7-~ examination of pertinent property records by 33
.(sj qualified personnel.
By terms of Section 2 of _ the General Agreement between Dow
-Chemical Company and Consumers Power Company dated. June 21, 1978; Dow will revise its emergency plan covering evacuation of the 27 personnel in Dow's Midland plant and other necessary action in connection with a radiological emergency at the Midland nuclear plant, and will be in a position to promptly carry out any applicable provisions of its . emergency plan whenever required to do so by the terms of the Midland. Plant Units 1 and 2 Site l33 Emergency Plan.
l30 Dow has also agreed to cooperate. fully with Consumers to ensure that all conditions of license for operation of the generating plant are met insofar as Dow property, facilities, personnel, and activities may be affected. As noted in Subsection 2.1.1.1, all Consumers property within the exclusion area is owned in fee including mineral rights, and only a portion of easement 76-193 to Dow is within the exclusion area. Arrangements have been made with local and state law enforcement agenciec for removal and exclusion of the public from those portions of the Tittabawassee River and Bullock Creek within the exclusion area in the event of an emergency. 2.1.2.2 Control of Activities Unrelated to Plant Operation Activities taking place within the exclusion area and unrelated to plant operation will be restricted to the construction, operation, and maintenance of communication, electric, and pipelines on easement 76-193, operation and maintenance of the , tanks for storage of condensate and demineralized water, and 27 associated piping, valves, and equipment, and the wastewater treatment pond west of the reactor building across Bullock Creek, and operation and maintenance of the clarifiers on the Dow property north of the reactor building across the river.
-Normally there are no Dow Chemical personnel working in the Dow Chemical controlled portion of the exclusion area. Access to 3 .
those areas (i.e., the area including the wastewater treatment pond and tanks for storage of condensate and demineralized water' 27 and associated piping, valves, and equipment, west of the reactor building across Bullock Creek, and the clarifier area north of the reactor building across the river).will be controlled by gates on the access routes on the east and west side of the 3 river, and Dow personnel or contractors' entry into the area will be controlled by Dow security personnel, in the continuously manned Dow Emergency Communications and'. Control Center. A 27 minimum of two persons are on dut/ in this center 24 hours per day. l3 2.1-5 Revision 33 4/81
MIDLAND 1&2-FSAR Those employees or contractor personnel who do enter the exclusion area for periodic equipment surveillance or maintenance 3 will maintain radio contact with the Dow Emergency Communications i 30 and Control Center dispatcher. If the need arises, the Midland plant will, via a direct hot line, request the Dow dispatcher to 27 evacuate the exclusion area in accordance with the agreements as
- discussed in Subsection 2.1.2.1. Evacuation notification will be via direct radio contact with those employees within the 3 exclusion area.
Dow personnel or contractors working in that portion of easement 76-193 within the exclusion area will likewise be in radio communication with the Dow Emergency Communications and Control Center and vill evacuate the area at the direction of Dow's 27 dispatcher. Jowever, access to this property will be across Consumers property providing the Midland plant with direct knowledge of their presence in the exclusion area. Control and evacuation of those portions of the Tittabawassee River and Bullock Creek within the exclusion area will be by state and local law enforcement agencies as noted in Subsection 2.1.2.1. 2.1.2.3 Arrangements For Traffic Control There are no public highways or railways within the exclusion area. All roads within the exclusion area are private roads owned and controlled by either Consumers Power Company or Dow Chemical Company. Control of traffic on Dow owned roads within the exclusion area by Consumers in the event of an emergency, is under the same agreement referred to in Subsection 2.1.2.1. The only railway within the exclusion area is the Consumers owned spur tracks serving the power block area. All rail traffic on these spur tracks will be under the control of Consumers. Portions of the Tittabayassee River and Bullock Creek are included within the exclusion area. There is no commercial river traffic on these areas and little pleasure boat traffic. Arrangements have been made with the Midland County Sheriff's Office and the Bay City post of the Michigan State Police for l 16 removal and exclusion of river traffic in the event of an emergency. 2.1.2.4 Abandonment _ ,or Relocation of Roads There are no public roads remaining within the site boundaries or the exclusion area. Those portions of Miller Road, Sasse Road, River Road, and Stewart Road which previously traversed the 'ite have been abandoned by governmental action. The access road across the S 1/2 of ~_' action 28 from the site to Poseyville Road is a private road owned, maintained, and controlled by Consumers. , 1 1 kevision 33 2.1-6 4/a1 l
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A-FINAL SAFETY ANALYSIS REPORT C"J" '** 'U .u"*. .x . o. Site Plan i f l (To Be Provided By Amendment)f l l FSAR Figure 2.1-1 4/81 Revision 33
MIDLAND 1&2-FSAR
-s TABLE 2.2-4 DOW CORNING STORAGE TANK DESCRIPTION Number of Tanks , and Quantity on Chemical (gallons) Symbol
, Fuel oil (#6) 1 9 1,000,000 1
- 29 125,000 2 l Hydrofluoric acid 1.9 10,000 3 Methyl chloride 4@ 20,000 4 I Anhydrous hcl 3@ 30,000
- 2) 5 1 i Chlorosilanes'* Numerous 10,000 to 20,000 and 6 33
- 3@ 60,000 Acetylene al l 24 Ammonia 1@ 10,000 7 ,
- Miscellaneous Numerous 100,000 total storage of solvents 8 i
84See Figure 2.2-5 for location tr>This storage in rail cars instead of tanks 24 ? Ubow Corning plans to expand the storage facilities for acetylene in 1981. Additional infoi-mation on new acetylenc , storage capacity will be provided by amendment. (*Chlorosilanes hydrolyze in the atmosphere to release HC1. 33 ! The release of anhydrous hydrochloric acid bounds the release of this chemical. I i t Revision 33 4/81
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TABLE 2.2-5 CHEMICAL COMPOUNDS STORED OR TilANSFERRED AT THE DOW CHEMICAL COMPANY, MICHIGAN DIVISION, MIDIAND, MICHIGAN Distance to Nuclear Plant Maximum Storage Conditions Control Room Quantity Temperature Pressure Compound Container (meters) (tons) (*C) (psig) Chlorine Storage sphere 2,440 2,000 -34 0 Railroad tank 800 90 25 82 car s O Anhydrous Tank 1,220 125 -29 150 h hydrochloric Railroad tank 800 75 -29 150 6 acid car g e Vinyl Horton sphere 1,700 550 25 43 Y chloride Railroad tank 800 85 25 43 y car g Mbthyl Tank 2,250 65 0 0 bromide Railroad tank 800 70 25 17 car Bromine Tank 1,200 90 45 0 l12 Railroad tank 800 50 25 0 car Ammonia Railroad tank 800 80 25 135 am
)} $ car mr N. Methyl Railroad tank 800 88 25 70 0 chloride car U
9 9 9
i l MIDLAND 1&2-FSAR is taking place. It is a measure of the depth of the atmosphere ! I-sT on a daily basis into which contaminants may be readily mixed. (-) The mixing depth is usually shallowest during the early morning hours and greatest in late afternoon. At Flint,(24) the highest average morning value, 518 meters, occurred in the winter and the lowest value, 280 meters, occurred in the summer. Maximum mean depth in the afternoon, 1,697 meters, was in summer and minimum mean depth, 762 meters, was in winter. Wind speeds averaged through the mixing d(pth ranged from 7 to 15 miles per hour, therefore creating favorable dispersion conditions (Table 2.3-5) . Periodically, a high-pressure system in the lower atmosphere will stagnate over a region and result in lower mixing height and limited vertical diffusion. The occurrence of limited dispersion episodes (also called stagnation periods) throughout the contiguous United States has been objectively determined by Holzworth.(25) The critical limiting conditiona used are mixing heights less than 1,000 meters, average mixing layer wind speed less than 4.0 meters per second, and this combination was satisfied continuously for at least 2 days. There was a total of two episodes in six episode days at Flint during the 1960-1964 pet 3od,(a*) much less frequent than most other parts of the country. 2.3.1.2.10 Ultimate Heat Sink O Meteorological data used in the ultimate heat sink analysis have been described in Subsection 9.2.5. 2.3.1.2.11 Other Regional Meteorological Conditions for Design and Operating Basis The regional meteorological conditions used for the design of the Midland plant heating, ventilating, and air conditioning. systems as described in Section 9.4 are: Summer: Design temperature: 96F dry bulb, 79F wet bulb Wind speed: 7-1/2 miles per hour Winter: Design temperature: -10F Wind speed: 15 miles per hour The following safety-related outdoor components are designed on the basis of -30F minimum temperature: borated water storage facility (Subsection 9.2.8), chemical storage tanks for the reactor building spray system (Subsection 6.5.2), and the main steam isolation valves and atmospheric vent valves (Section
- 10. 3 ) .
Selection of the above temperatures was made after reviewing the 3 ASHRAE Handbook of Fundamentals, 1972 (Chapter 20); the Carrier r' kN) s Revision 7 2.3-11 3/78
MIDLAND 1&2-FSAR System Design Manual, 1972; and Saginaw, Midland, and Flint weather data. Unsed on this review, the wet and dry bulb temperature range celected abo /e will be adherred to more than 99% of the year. Further, the time during which the temperatures are outside the range will be separated over the year which further shortens the 3 time duration of each excursion outside the range. Also, the design temperatures are outside temperatures, and temperatures to which sa fety-related equipment will be exposed is dampened depending on the equipment location, size, operating status, etc. The -30F temperature is also based on the lowest recorded in the area (see Subsection 2.3.2.1.2). 2.3.2 LOCAL METEOROLOGY 2.3.2.1 Normal and Extreme Values of Meteorological Parameters 2.3.2.1.1 Wind Direction and Speed The normals, means, and extremes of wind direction and wind speed for Flint, Michigan are shown in Table 2.3-6. These data demonstrate that southwesterly flow prevails during most months; however, a secondary maxinum frequency from the west-northwest occurs during February through April. The prevailing southwesterly direction results from the presence of the high-pressure systems over the southeastern United States. The northwesterly secondary maximum is primarily the result of migratory anticyclones moving into the region from Canada. The distribution of wind direction and speed is an important factor when considering transport conditions relevant to area diffusion climatology. Annual and seasonal distribution of sur face wind direction and speed for the period 1966 through 1975 33 based on 3 hourly' surface weather observations for Flint (26) are presented in Figures 2.3-1 through 2.3-5. The annual distribution pattern (Figure 2.3-1) shows the predominance of northwest the southwest winds. The seasonal distribution shows predominant winds are westerly during winter and southwesterly during summer while spring and fall are transition periods. The annual distribution for the period 1975-1976 (Figure 2.1-6) l33 exhibits similar predominant einds. Atmospheric dilution is directly proportional to the wind speed (other factors remaining constant). The average annual wind speed is 8.7 knots (see Table 2.3-20, sheet 8). Seasonal 133 summaries show winter having the maximum average wind speed of 9.8 knots and summer the minimum average wind speed of 7.3 xnots. Calms were present 2.4% ef the time while strong winds above 21 knots cccur less the - 1% of the time on annual basis. Calma
- occurred primarily during the summer months with a frequency of Revision 33 2.3-12 4/81
MIDLAND 1&2-FSAR Fog Index Number = AT ('_ ) es -es V where AT = the temperature of the water less the temperature of the ambient air, "F l7
- e. = saturation vapor pressure at ambient air temperature, millibars 133
- c. = actual vapor pressure of the ambient air, millibars 17 The Feg Index Number is multiplied by the probability of occurrence of fog _ as a function of ,the Index Number to calculate the percent of time steam fog or stratus occurs. This study combined fog and stratus which is fog at it.ast fifty feet above ground level. If natural fog exist s, fog or stratus due to the Midland pond is expected 14.8% of the time in winter. When natural fog exists, pond fog only contributes to the density of 7 the fog and not to the frequency of occurrence. On an annual basis the predicted frequency of this type of fog is 8.4%.
Without natural fog present, fog due to the cooling pond is pred icted 43.5% of the time during winter months. On an annual basis, the comparable frequency is 25% and the maximum frequency i of this pond-induced fog or stratus is associated with west-southwest winds. The second analysisRW yielded frequencies of occurrence of (3 dif ferent categories of fog that relate directly to reduced 7 i (_,/ visibility and does not include stratus. Eight specific locations in the vicinity of the cooling pond were selected. The l l calculations made use of a 6 year record (1949-1954) of hourly meteorological observations made at Tri-City Airport. The procedure involved the determination, every 3 hours, of pond sur face temperature , sensible heat loss, and evaporative heat loss to the ats.osphere with a cooling lake performance model developed by Ryan and harleman.um s. According to the surface isotherm pattern produced by this model
- and the wind direction, the pond surface was divided into an appropriate array of 40 contiguous 300 by 300 meter squares, each of which was treated as a source of heat and moisture. Then the Gaussian diffusion equation was used to calculate heat and water vapor diffusion from each of the sources to each of the eight loca tie rts that were downwind from the lake 'for that hourly calculation. Plume buoyancy effects were partially accounted for by using diffusion coefficients for the Brookhaven Bg (unstable) diffusion category for plumes as long as they remained over the pond. The quantitles obtained from all 40 source squares were l7 summed for each location.
The occurrence of fog and the amount of condensed water were determined from the standard saturation vapor versus temperature relationship after the new temperature was calculated by taking
- into account the diffused sensible heat. Liquid water contents Q Revision 33 2.3-17 4/81 1
4
- - - - - - - - - - - - - _ - _ - - - - _ - - _ . . - - - . - _ - . - - - _ - = - - - - . _ - _ _ . - _ - . - . - - _ - _ _ _ - - . _ - - - - - - . _ . .
MIDLAND 162-FSAR were converted to visibility by a relationship due to floughton and Radford.0" Finally, the results were tabulateu according to teven visibility categories (from less than 1/16 mile to 1 mile or more), month, and time of day for each location. A summary of the findings is shown in Figure 2.3-7 which is a map of the cooling pond and its vicinity with the eight locations identified as A, B, C, D, E, F, F, and 11. Each location has three numbers. The first is the annual average of the sum of the l7 number of hours of fog due to the operation of the cooling pond end the number of hours during which its operation would add to natural fog and cause a further reduction in visibility. The second nunber is the computed average annual number of hours with fog specifically attributable to the pond. The third number is the computed average annual hours of fog at below freezing temperatures. Like the first number listed, it is the sum of both tne number of hours of fog due to operation of the pond and the number of hours in which its operation would add to natural fog and cuase a f arther reduction in visibility. Except for tne three locations on Gordonville Road (along the south edge of the cooling pond) fog caused by the pond alone would nave occurred on an annual average of less than 50 hours per year. The three Gordonville Road locations nave annual averages of 73, 82, and 98 hours per year. Tne occurrences of cooling pond fog with natural fog are all less than an average of 200 nours per year except at two Gordonville Road locations whien have values of 216 and 270 hours per year. Of the total number of fogs that occur, on an annual average, about 254 would occur with temperatures below freezing for the locations nearest tne pend (C, E, F, and G). For the stations further to the west (A, l7 B, and D), the percentage varies from 16 to 18, while at location li the percentage ic only about 10. Results of the more recent Portman analysis that can be compared to the earlier Bechtel study (i.e., number of hours of fog due to the operation of the cooling pond) indicate that the Portman 7 results are less conservative and more realis tic. The Portman results are also in general agreement with observations made at the Dresden Nuclear Power Station by Murray and Trettel, Inc.02) For neaJ1y two full winters of observations at the cooling pond there, tney tound about 13 days each winter when "the steam tag was observed to have remained at or near the ground and to travel beyond the pond boundary for short periods of time. . . .The inland travel distance ranged from approximately 100 feet to approximately 1.5 miles." Those ooservations are good only for the Dresden pond for t he winters of 1972 and 1973. However, the general agreement of the present results with suen observations support their validity. I Revision 33 2.3-18 4/81
MIDLTtND 1&2-FSAR _ 2.3.2.2.2.2 Icing Buildup From Pond Fog x_/ Rime is a milky granular deposit of ice that forms when super cooled water drops impinge upon exposed surfaces. The Bechtel report (273 predicted 0.4 inch of rime deposition in 10 hours on poles and wires. Similarly, the report predicted an accumulation of 0.05 millimeter in 10 hours on road surfaces. 2.3.2.2.3 Topographical Description The topography of the site area is comparatively flat with elevations ranging from 600 to 800 feet above mean sea level within a 5 mile radius and 600 to 1,200 feet ~within a 50 mile radius of the plant. Maximum elevations occur to the north of the plant. Figures 2.3-8 and 2.1-4 are topographic maps of the site showing the topographic features within 5 and 50 miles of the site-area respectively. Figures 2.3-9 and 2.3-10 chow the topographic elevation profile within 5 miles of the site. Thus, topographically induced or altered winds should not have a significant impact on either the short-term or long-term diffusion estimates for the site. , 2.3.2.3 Local Meteorological Conditions for Design and 5 Operating Bases The local meteorological data collected as a result of the 2 year ()s ( onsite monitoring activities are within the regional climatic extremes of record. Therefore, these more conservative regional meteorological data described in Subsection 2.3.1.2.11 were used for all design and operating basis considerations. 2.3.3 ONSITE METEOROLOGICAL MEASUREMENTS PROGRAM The data collection period for the preoperational meteorological program was from March 1, 1975, to February 28, 1977. 2.3.3.1 Meteorological Site Characteristics Onsite meteorological data were collected from three different locations which are shown in Figure 2.3-11. These include a 91.5 meter tower and two satellite locations with 10 meter towers. 2.3.3.1.1 91.5 Meter Tower The 91.5 meter tower is located northwest of a parking lot, about 3 1,150 feet west of the nearest containment (Figure 2.3-11) . The distances from the tower to the pond dikes are about 1,200 feet _s to the south and 1,050 feet to the southeast. The elevation of
, Revision 7 2.3-19 3/78
MIDLAND 1&2-FSAR the top of the dike is 632 feet mean sea level (msl) and the elevation of the base of the tower is 614 feet msl. The grade 30 level at the containment is at 634 feet msl. The top of the containment is 787 feet msl. The cooling pond was under various stages of construction during the 2 year period (March 1975 to February 1977) of meterological data collection. During that period the pond was not filled with water and, in fact, there were only several spots in the pond which were covered with shallow rainfall. The tower is located 1,050 feet from the nearest dike of the cooling pond. Any pond construction activities were held at least 1,050 feet away from the tower, and the effect of the construction activities on the tower measurements would be minimal. Due to space limitation within the site, parking is allowed in an area in the northeast through south to southwest sectors, but this parking lot is separated by a fence from the general area surrounding the base of the tower. The distance from the tower 3 base to the nearest car parked just outside the fence is approximately 130 feet. The ground area within the fence is primarily clay. The nearest buildings to the tower are the warehouse, field office, and change house. These buildings are located east of the tower location at a distance of approximately 600 feet. The distance is greater than five times the building heights measured from the tower base. Bullock Creek diversion flows from southwest to northeast in the area west of the tower location. The diversion is 150 feet wide at the top of its banks. The distance from the tower to the nearest bank is approximately 50 feet. With the maximum water level in the diversion which occurs in Spring season, the tower is at least 90 feet from the water in the diversion. In addition, two ponds owned by Dow Chemical Company are located west of the diversion at a d# stance of, at least, 200 feet from the tower. l 2.3.3.1.2 North Station This tower was located on the bank of the Tittabawassee River 30 about 800 feet northeast of the containment. The tower provided meteorological data for winds from the northeast quadrant after they have traversed the Dow Chemical Company plant site and the Tittabawassee River. The base of the tower was 600 feet msl. The water elevation in the Tittabawassee River is estimated to be 30 590 feet msl approximately 50% of the time. l 33 Revision 33 2.3-20 4/81 1
, ,- . - . - ..- - . _ . . _ _ . . - . _ _ - . - - . _ - - -.- - ~ - - 4 MIDEAND 1&2-FSAR t from the 91.5 meter' tower from March 1, 1975 to-3 / h February 28, 1977, wereLrecorded on' magnetic tape as the primary ' \s / record. Analog strip charts were.used as backup snd read when required to fill in missing data points due.to magnetic tape
- system outages. When backup' data were4 read!from charts,1they were put on coding forms, key. punched, and merged with the. site
- magnetic tape data onto a new tape or disk. A data listing from
[ i the procesced magnetic tape record containing all the data recorded'was made for. checking purposes. Diagnostic and check l computer programs were.then run on the composite data. LA final processed data tape was then made and -stored Lfor use in running. j the various modeling programs. J , The' data from the north and south stations were allfrecorded on ] analog charts which were manually read.and the data put on coding j' forms. After key punching and editing,Lthe processed data were: ! put on raagnetic tape or disk for storage and used for the _various, j report requirements. i 4-2.3.3'.6 Meteorological Data Recovery ] 30 - The meteorological data recovery rates for each parameter are i 4 listed in Table 2.3-27. The-joint frequency data recovery for 10 i to M0 meter temperature difference, 10 meter. wind speed, and wind * ! direction for the March 1, 1975, through February _28, 1977 period ! was better.than 94%, meeting the.90% data recovery. goal required } by Regulatory Guide 1.23. These joint frequency data were-the j. primary data used to compute X/Q values in Subsections 2.3.4 and' 4 2.3.5. 4 l l 2.3.3.7 Joint Frequency Distributions of Wind Direction 30~ , ! and Speed by Atmospheric Stability Class l l Joint frequency distributions of wind direction and wind speed by: ~ atmospheric stability class on a seasonal and biennial basis for the period March 1, 1975, to February 28, 1977, are provided-in Tables 2.3-21 and 2.3-22. Table 2.3-21 provides the joint frequency distributions for data from the 10 meter level. wind l speed and wind direction and the temperature difference-between 10 meters and 60 meters; Table 2.3-22 provides the' joint frequency distributions with 60 meter wind speeds and wind direction and temperature difference between.10 meters and l 60 meters. f 2.3.3.8 Representativeness of Meteorological' Data ' Collection l Period Compared to Expected Long-Term conditions 30 ? l 2.3.3.8.1 National Weather Service Site Description l The National Weather Service (NWS) station selected to assess the j temporal representativeness of the onsite data was Bishop Airport 2.3-25 . Revision 13
- 4/81 1
1 i !._.-..-.-,_....._. . - -- _.._. - -_._..._ - - -. -,-__._ .-,._......-,._._.. -..-.,- - -..-.. _ ~ ..--
MIDLAND 1&2-FSAR at Flint, Michigan, which is the nearest regularly reporting class A weather station of the NWS. This station is 235 meters above mean sea level (MSL) and is located about 60 miles SSE of the Midland plant site. Wind speed and direction at this site are measured 6 meters above the ground surface, while temperature and precipitation are measured 1.5 meters above the ground surface. 2.3.3.8.2 Temporal Representativeness of Climatological Data l 30 The procedure used for determining the temporal representativeness of the 1975-1977 oasite data was to compare the data collected onsite to that collected at the Flint, l7 Michigan, National Weather Service station for the same period m25 and also to compare the data collected at Flint during that 2 year period with the 10 year baseline data (March 1, 1967 through February 28, 1977).H4 Figure 2.3-19 presents a comparison of the seasonal and annual frequency of occurrence of various wind speed classes for the 2 year onsite data period to the 2 year and 10 year baseline Flint data period. The comparison shows that the frequency distributions of speeds at the two locations are very similar. Figure 2.3-20 shows a comparison of the seasonal and annual frequency of occurrence of wind directions for the same time period at the same locations. Again, the frequency distributions are very similar. These two figures suggest that mechanical dispersion at the two sites for the 2 year sample period is similar. The 2 year distributions are chown to be similar to the longer term data. A direct comparison between onsite and offsite stability occurrences are not meaningful because of the different methodologies used to determine stability classes (Subsection 2.3.2.1.6). However, a comparison betweun the 2 year period STAR program stabilities and the 10 year baseline STAR program stabilities can be made. Table 2.3-35 shows the frequency distribution of stability classes for the 2 year study period and the 10 year baseline period at Flint, Michigan. The table shows l a close agreement between the frequencies of occurrence of stability classes for the two time periods. To present the valuet of the climatological parameters (temperature, wind speed, and wind direction) measured onsite and at Flint during the study period (March 1, 1975 through February 28, 1977) in relation to the corresponding values over the 10 year period, the monthly value of each meteorological parameter averaged over the 2 year period was plotted along with the average of that parameter for the same calendar month over the 10 year baseline period from Flint, Michigan. In addition, the standard deviation along with the maximum and minimum monthly averages of the sample set from the 10 year baseline period was plotted for each parameter used in this part of the study. The 2.3-26 Revision 30 O 10/80 L
MIDLAND 1&2-FSAR
; -s 2.3.4 SHORT-TERM (ACCIDENT) DIFFUSION ESTIMATES 2.3.4.1 Objective To evaluate the dispersion potential of the atmosphere in the Midland site area, calculations were made of concentrations of.
effluents normalized by the source strength of the power plant release. These atmospheric dilution factors were calculated using the meteorological data collected on site from March.1, 1975 to February'28, 1977. The parameters used.were 10 meter to 60 meter temperature difference and 10 meter wind spet;d and direction. The short-term models'are based on the NRC design basis accident (DBA) model aI:d Regulatory Caide 1.4.00 Six different estimates, corresponding to six dif ferent time - periods, were made of the X/Q values. These time periods were 1 hour, 2 hours, 8 hours, 16 hours, 3 days (72 hours), _and 26 days (624 hours). 4 Atmospheric diffusion estimates developed for use in evalr.ating accidents for the aforementioned periods after the release are summarized in Table 2.3-28. This table includes estimates for the vorst case value, the first percentile, the fifth percentile, and the fif tieth percentile levels, and the arithmetic mean value for the above mentioned average intervals. i 2.3.4.2 Calculations .; 2.3.4.2.1 Accident Diffusion Estimates - O to 8 Hour l7 The governing equation for a ground level release for the 0-8 hour time period when invariant wind is assumed is: jK = I (5) - g rua yag F where 33 0.5 A 0.5 A
" + if 1+
r v, a, '
* *y %
<3
=3* 0.5>A
, if 1+ 23
' S 8:
l l l
\s ,- Revision 33 2.3-29 4/81 l
l l
MIDLANO 1&2-FSAR X = effluent concentration (pCi/m3) Q = source strength (pci/s) h u = wind speed (m/s) ay = horizontal standard deviation of plume concentration distribution at downwind distance from release (meters) az= vertical standard deviation of plume concentration distribution at downwind distance from release (meters) A = minimum cross-sectional area of containment (1,700 m2) This source-normalized effluent concentration is a function of both wind speed and atmospheric stability class. The method by which calculations were made during calm wind conditions is discussed in Subsection 2.3.4.2.3. The functional form of a y and a, by stability class was determined from Reference 35. The stability class was determined from AT (60m - 10m) data in accordance with Regulatory Guide 1.23 (Appendix 3A). Calculations of X/Q were taade for all combinations of wind speed and stability classes for the following six distances: 300 meters, 500 meters (exclusion area boundary), 1,600 meters (distance to low population zone), 10 miles, 30 miles, and 50 miles. To obtain the hourly estimate of worst case X/Q values for these distances, Equation 5 was evaluated for each hourly meteorological data point, using the distance to the area perimeter in the direction that the wind was blowing. This procedure resulted in a table of X/Q values which were ordered from greatest to least. The worst case X/Q was then read from the top of the list. Proceeding down the table, from the worst case X/Q, when 1% of the total number of X/Q values in the table were encountered, that value was taken as the first percentile value of X/Q; i.e., the. value of X/Q which is exceeded 1% of the l time. Similarly, the fifth and fiftieth percentile values of X/Q are taken as the value for which 5 and 50% of the calculated X/Q j values were larger respectively. The arithmetic mean X/Q is the l average value for the respective time period. The 8 hour average estimate of X/Q values was obtained using the l following steps:
- a. Categorize, according to direction, each of eight hourl '
meteorological data points
- b. Evaluate (by Equation 5) eight sequential X/Q values using the distance to the area perimeter in the direction that the wind was blowing for the eight points Revision 7 2.3-30 3/78
MIDLAND 1&2-FSAR similarly applied. However, no elevated release credit was taken (}
%J for low wind speed situations.
2.3.5.1.2 Long-Term Representative Dispersion and Topography Effects Subsection 2.3.3.8 presents the comparison between onsite 133 meteorology and climatological representative data. The ay and az values used in this analysis are the standard values which were developed for flat terrain regions. Since the topography surrounding the Midland' plant is flat, the use of these values should produce representative results. 2.3.5.1.3 Meteorological Data Meteorological data were taken onsite at the 91.5 meter tower from March 1, 1975, through February 28, 1977. A complete description of the onsite meteorological monitoring program, along with instrument accuracy and adequacy, can be found in Sunsection 2.3.3.2. The degree to which this data base at the 91.5 meter tower is representative of actual site conditions is discussed in Subsection 2.3.3.9. g ) The mixed mode release analysis specified in Regulatory Guide 1.111 requires that the wind speed be determined at the point of release. Because the measured wind velocities are at heights other than the point of release, a power law wind profile was used for interpolation (Subsection 2.3.5.1.5). 2.3.5.1.4 Joint Frequency Distributions for Mixed Mode Analysis The calculational methodology used to develop the joint frequency distributions of meteorological variables used in the analyses is j described below, i Joint frequency distributions give the frequency of time, over a specified period, that specified classes of wind speed, wind I direction, and atmospheric stability coexisted. t Wind direction, as measured at the 10 meter level, was classified into sixteen 22.5 degree sectors centered on the cardinal compass points. Wind speed, as measured at the 10 meter level, was categorized into seven classes as shown below: l l l ( ,)
\
l Revision 33 2.3-39 4/81
- - - - 4 -w- ,, ~- - - ~
9m ,, g 9 m- e-s -. - - - - - * -
MIDLAND 1&2-FSAR Wind Speed Interval Median Used Class Number Range (mphl in Calculations (mph) 1 0.0 < u 5 1.0 0.5 2 1.0 < u $ 3.0 2.0 3 3.0 < u 5 7.0 5.5 4 7.0 < u 5 12.0 10.0 5 12.0 < u $ 18.0 15.5 6 18.0 < u $ 24.0 21.5 7 24.0 < u 25.0 2.3.5.1.5 Power Law Wind Profile To describe the variation of wind speed with height in the model, the following power law was used: (*o) ug (z,f I . for 0 $ m i1 (21) g =l( 2j , and z g < z2 l9 where O ( z) = height at elevation 1 (meters) l z2 = height at elevation 2 (meters) uj = wind speed at height zq(m/s) u2 = Wind apeed at height z2(m/s) m = a nondimensional variable which depends on thermal stability This technique was used to determine wind speeds at the point of release and at the effective plume height for elevated releases at the Midland plant from the onsite data. To determine the variation of m with lapse rate at the Midland plant, Equation 21 was solved for m in terms of the hourly-averaged wind speeds at the 10 e.nd 60 meter levels. m = log u60 - log u no (22) log (60) - log (10) Revision 9 2.3-40 5/78
\ h
[V J U. 1 NIDLAND lin2-FSAR 1 TABIE 2.3-34 ANNUAL AVERACE X/Q (s/m 8) VALUES - TURSINE BU11 DING VENTS - CROUND LEVEL WITHOUT TERRAIN AD?USTRENT FACTOR"' Control Boundarym Iow Population Zone Downwind Distance Ground Level Distance Ground Level Downwind Distances (miles) sector feeters) X/OS feeters) X/o 2 3 4 5 10 N 500 0.70364E-05 1,600 0.11277E-05 0.64478E-06 0.261188-06 0.178?'R-06 0.13199E-06 0.51306E-07 j NNE 500 0.63744E-05 1,600 0.10371E-05 0.4n365E-06 0.23434E-06 0.15863E-06 0.11694E-06 0.44826E-07
- NE 500 0.62642E-05 1,600 0.10390E-05 0.399325-06 0.153615-06 0.153615-06 0.11253E-06 0.42401E-07 ENE 500 0.56659E-05 1,600 0.94643E-06 0.35957E-06 0.20433E-06 0.13636E-06 0.99473E-07 0.37049E-07 E 579 0.45214E-05 1,600 0.93132E-06 0.35185E-06 0.19992E-06 0.13343E-06 0.973498-07 0.32671E-07 ESE 484 0.18506E-05 1.600 0.732558-06 0.27023E-06 0.15109E-06 0.99749E-07 0.721945-07 0.26297E-07 SE 1,530 0.60441E-06 1,600 0.56705E-06 0.20787E-06 0.11565E-06 0.76097E-07 0.54934E-07 0.19861E-07 33 SEE 1,970 0.27011E-06 1.970"' O.27011E fA 0.13092E-06 0.71620E-07 0.465745-07 0.33323E-07 0.11735E-07 s 1,921 0.16774E-06 1,921"' O.16744E-06 0.78416E-07 0.42858E-07 0.27849E-07 0.199146-07 0.69995E-08 SSW 1,970 0.16683E-06 1,970"' O.16683E-06 0.81191E-07 0.44540E-07 0.29019E-07 0.207922-07 0.73537E-08 SW 1,450 0.3015r1-06 1,600 0.26156E-06 0.93990E-07 0.51531E-07 C.33571E-07 0.24056E-07 0.85161E-08 WSW 500- 0.28236E-05 1,600 0.45502E-06 0.16492E-06 0.91014E-07 0.59567E-07 0.42834E-07 0.15320E-07 J
W 500 0.23016E-05 1,600 0.38966E-06 0.14378E-06 0.80244E-07 0.52917E-07 0.38267E-07 -0.13911E-07 WNW 500 0.34430E-OL 1,600 0.565885-06 0.21475E-06 0.12223E-06 0.816',2E-07 0. 06375-07 0.22276E-07 NW 500 0.460445-05 1,600 0.73717E-06 0.28794E-06 0.168115-06 0.11423E-06 0.84442E-07 0.326135-07 NNW $00 0.53128E-05 1.600 0.84933E-06 0.33542E-06 0.197115 06 0.13449E-06 0.99696E-07 0.38784E-07 , "'This table uses to meter level (10-60 T) onsite meteorological data for the period March 1,1975, t through February 28, 1977.
!
- control boundary as shown in Figure 2.3 11
$ *E-06 a 10*
"' Distance measured to site boundary Table 2.3 34 Revision 33 4/81 I
4 MIDLAND 1&2-FSAR elevation.627,25, including wind setup, the maximum potential
- ,; runup of the standing waves was determined.to be:at ' (V-)
elevation 637.-l. This wave activity results in a maximum dynamic borizontal force of.4.8 kips per foot against the front of the l structure in addition.to existing hydrostatic forces. Runup on.the 3.5 horizontal to l.0 vertical riprapped dike slopes adjacent to the service water pump structure was calculated using the procedures given in Section 7.2'i of Reference 8. R. Tup was found equal to 3.2 feet above the stillwater level of 6 .25, including setup. Since the dike crest-is at elevation 633,-no-overtopping results from the above runup. 8 2.4.6 PROBABLE MAXIMUM TSUNAMI FLOODING Not applicable. 3 2.4.7 ICE CFFECTS A detailed study has been performed to determine the. ice produced effects and forces that are reasonably'possible at the Midland site. The only safety-related facility that can be affected by. potential icing effects is the service water' pump structure, located on the north. side of the cooling pond. Ice in the pond could result in two types of loading: collision by windblown ice - which could be floating free in the pond, or thrust caused by thermal expansion of the ice sheet. Based upon Midland (s ~T,/ climatological data 02) and an observation of ice thickness-on Saginaw Bay,033 it is estimated that ice could develop on the cocling pond to a thickness of 2.5 feet with a frequency of about once every 100 years in-case the plant is not in operation . In computing ice drag loads, calculations covered not only the 100 year ice thickness combined with a 1. year wind speed, but
- - also examined all combined occurrences of ice thickness and wind speed which could result in a once-in-100 year joint' occurrence.
The worst case occurs with an ice thickness of 16. inches (94% chance of occurrence) and a wind speed of about 71 mph (1.1% chance of occurrence). This would produce loadings of 375 kips, or 1.5 kips per foot across the front of both the circulating water intake structure and the service water pump structure, and
- 1.8 kips per foot across the front of the circulating water i discharge structure. In determining the thrust caused by thermal i expansion of the ice sheet, ice thermal loads of_12.5 kips per i linear foot could occur on any structure on the pond. This load was determined assuming a 30 inch ice cover which- has a probability of occurrence less than once every 100 years. The water surface of the pond was assumed to be at elevation 627.
[ The service water pump structure is designed to withstand the ice l load and the static load. Surface ice formation in the vicinity of the service water pump 30 structure does not affect its operation. The water entrance for (3 ' ( -) 2.4-13 Revision 30 y 10/80 o y - eren 4 --Nc
- vver*-We-1 vy-- ++n-gns *,w -'
? Maa 9 -
p &- , yy g m. v-- y 4$ f yy'.y+ g -em=-oo me v re w T%'"v'9 '-"W- " * " ' T-
MIDLAND 1& 2-FSAR the service water pump structure is well below the mininum operating water level. Hence, it is not affected by strface ice f orma t io n. Problems associated with the intakes being blocked by 30 submerged floes or ice jams have been determined to be unlikely to occur. 2.4.8 COOLING WATER RESERVOIRS The main cooling pond has t en sized to provide capacity sufficient to satisfy the plant full power operation cooling needs during an assumed 100 day drought period with no stream withdrawals mode from the Tittabawassee River. The maximum operating water level in the pond is elevation 627 and the minimum level is elevation 618. The surface areas at the above elevations are 880 and 860 acres respectively. The maximum pond bottom ?levation is 615, which results in a minimum cperating depth of 3 feet. When full, the pond has a total storage volume of approximately 12,600 acre-feet. Of this total volume, approximately 7,900 acre-feet are considered usable during the 100 day drougnt. An cdditional 2,800 acre-feet are included to provide the 3 foot minimum water depth. The remaining storage volume of 1,900 acre-feet includes the deeper areas of the pond and is considered dead storage unavailable for plant cooling operations. The usable storage volume is equal to the estimated evaporative and seepage losses occurring during the 100 day drought. Pond losses due to evaporation have been computed 00 to be 8 feet or about 7,000 acre-feet during the 100 day drought. A soils investigation program found the reservoir site to be underla > n by soil strata of low permeability with occasional pockets of more pervious sandy soil confined to the uppermost soil, generally to a depth less than 15 feet. A cutoff wall of suitable impervious materials and, where necessary, a Bentonite slurry trench has been located within the dike. Estimated pond losses due to seepage are considered minimal, not to exceed 0.5 cfs. A ponU seepage loss of about 0.35 cfs (250 acre-feet / year) is reported l32 in Subsection 2.5.6.6.4. For design purposes, a seepage loss of 4 cfs or approximately 800 acre-feet was assumed for a 100 day drought period. The usable pond storage volume of 7,900 acre-feet is therefore adequate to provide for about 7,000 acre-feet evaporation losses and 800 acre-feet seepage losses during a 100 day drought period. The main purpose of the cooling pond is to supply and receive cooling water for the circulating water system. Normally, the cooling pond is also used as the service water system heat sink. As shown in Figure 2.4-3, the pond has an internal baffle dike which is provided to improve the flow and cooling characteristics of the pond. In addition, the baffle dike reduces the wave generating fetch and hence reduces the required freeboard. O 2.4-14 Revision 33 4/81
~
MIDLAND 162-FSAR
,- ~s 2.4.11.4 F11ture Controls
/ \
-l The cooling pond is sized to sustain plant operation for 100 days and shut down in the event the river flow is too low to permit withdrawal. The probability of a drought exceeding 100 days and causing the plant to shut down is very small. No plans are known for any projects upstream or downstream of the plant site which would significantly affect the low flows of the Tittabawassee River at the Midland site.
2.4.11.5 Plant Requirements The service water system provides treated cooling water for various components during normal plant operation and provides cooling water to engineered safety features aquipment during a design basis accident. A description of the service water system including water requirements is included in Subsection 9.2.1. The service water pumps take suction from the open channel connecting the er.ergency cooling water reservoir to the service water pump structure. The emergency cooling water reservoir is a depressed area in the main cooling pond which will provide 272 acre-feet of storage capacity in the event of loss of the cooling pond. The stored quantity of water available is sufficient without makeup for the safe shutdown and cooldown of both units for a period of at least 30 days in both normal and emergency conditions, as described in Subsection 9.2.5. (O~') The sump invert elevation for the service water pumps is elevation 593.25. During normal operation, the water surface of the cooling pond is at elevation 627, which provides a pump submergence of 33.75 feet. The minimum design operating water level for the emergency cooling water reservoir is at elevation 602.5 following the design basis accident after 30 days. Under this condition, the pump submergence is 9.25 feet. The minimum required pump submergence is 5.25 feet. The major requirement for offsite water is makeup for the 10 main cooling pond, supplied from the Tittabawassee River. The cooling pond has been sized to provide capacity sufficient to satisfy the plant's full power operation cooling needs during both an assumed 100 day drought period and normal operating l conditions. The above analyses were based on no stream withdrawals made from the river due to lev river flow. 2.u.11.6 Heat Sink Dependability Requirements Provisions for warning of impending low flow, comparison of minimum flow estimates with project requiren.ents, and low water safety factor are not applicable because the ultimate heat sink r- is independent of the Tittabawassee River during plant operation.
\' / Revision 18 2.4-19 2/79
. , , , , . . . ., . , , _ _ , ~ .
f MIDLAND 1&2-FSAR The discussion of the ultimate heat sink design bases and conformance to Regulatory Guide 1.27 is provided in detail in c. Subsection 9.2.5 and Appendix 3A, respectively. The normal plant water supply and the onsite storage of all necessary shutdown cooling water is discussed in Subsection 2.4.11.5. 2.4.12 DISPERSION, DILUTION, AND TRAVEL TIMES OF ACCIDENTAL RELEASES l27 OF LIOUID EFFLUENTS IN SURFACE WATERS 27 With the exception of two condensate storage tanks, other tanks that may potentially contain quantities of radioactive effluent are located within buildings or are protected with dikes to prevent the possibility of contaminating surface water directly. The two condensate tanks are located approximately 75 feet north of the cooling pond and the volume of each tank is 300,000 gallons. Failure of these tanks would result in the release of their contents to the cooling pend. The condensate storage tank may contain radioactivity in the event of steam genera tor tube leak. However, because the amount or water received from the condenser will be smaller than the amount of water supplied to the condenser, the condensate storage concentrations will be much smaller than steam concentrations discussed Section 11.1. It is anticipated that the concentrations in the condensate storage tank will be at or below 10 CPR 20.106 concentration limits to an unrestricted area. l33 Thus the initial dilution afforded by the cooling pond and the ' subsequent dilution at the discharge point will ensure that the concentrations in the nearest surface water supply will be much lower than the 10 CFR 20.106 limits. l33 2.4.13 GROUNDWATER 2.4.13.1 Description and Onsite Use The site is located in the lower peninsula of Michigan near the center of the Michigan Basin, a broad, shallow structural basin of Paleozoic sedimentary rocks up to 14,000 feet thick. These rocks are covered by unconsolidated Pleistocene glacial drift that regionally is about 200 to 300 feet thick. Details of the regional and site geology are discussed in Subsection 2.5.1. 2.4.13.1.1 Regional Aquifers 2.4.13.1.1.1 Drift Aquifers Most of the groundwater development of Michigan's lower peninsula is in the sand and gravel zones present in the glacial deposits, with rural areas depending almost entirely on these aquifers for water supply. Several municipalities such as Ann Arbor, Northville, Alma, St. Louis, and Cadillac all get a part of their 2.4-20 O Revision 33 4/81
MIDLAND 1&2-FSAR 2.5.1.1.2.4 Cenozoic
'N 1
s/ Pleistocene unconsolidated surface deposits rest unconformably on the Mesozoic and Paleozoic rocks throughout the lower peninsula of Michigan. These extensive surface deposits are attributable to the last major period of continental glaciation, the Wisconsin stage. active in Michigan from 50,000 to 13,000 years ago!83 During the numerous periods of glacial advance and retreat of the Wisconsin stage, drift of various types was deposited across the state, including till, outwash, and gle.ciolacustrine deposits. Figure 2.5-2 shows the surface deposits present in the region. Glacial deposits across the state range in thickness from only a few feet in the northern portion to over 400 feet in the central portion of the state. Beneath the site the glacial drift ic approximately 350 feet thick and consists primarily of outwash and till. A detailed discussion of the glacial ceposits at the site is presented in Subsection 2.5.1.2.2. 2.5.1.1.3 Regional Geologic and Tectonic Structures The north central United States is situated in the central portion of the continental craton of E?rth America, the stable core of the continent. The craton is composed of two major tectonic divisions: the Precambrian Canadian Shield to the north 5 and the Paleozoic age sedimentary strata to the south.m The i contact between these major divisions is roughly located along the Canadian-United States border. To the north a complex g-')g ( mixture of metamorphic, igneous, and cedimentary rocks of the . Canadian Shield is present in most of the eastern two-thirds of Canada. These rocks have been stable for at least the last 500 million years and contain some of the most ancient rock units exposed on earth. To the south the geologic structure of the Paleozoic portion of the craton is characterized by essentially flat lying sedimentary rocks modified only by a series of broad shallow structural basins separated by low arches. These sedimentary strata of the craton are present under the central United States. l I l ! 2.5.1.1.3.1 Michigan Basin Michigan's entire lower peninsula, as well as part of the upper peninsula, eastern Wisconsin, northern Illinois, Indiana, Ohio, and parts of Canada, are underlain by a broad, shallow, structural depression tectonic province with an area of approximately 122,000 square miles which is known as the Michigan Basin (see Figure 2.5-6). The Michigan Basin underwent nearly I continuous subsidence and deposition from the Cambrian through ! Pennsylvanian Periods m (see Subsection 2.5.1.1.2). The general 14 shape of the existing basin was first formed in Ordovician tirae, and has remained fairly constant since the end of Niagarun l (Silurian) time.m2) The maximum accumulation of sedin2nts la the center of the basin is over 14,000 feetSH (see Figure 2.5-5).
\- Revision 34 2.5-5 10/78
MIDLAND 1&2-FSAR The forces which produced this nearly continuous subsidence for a period of almost 300 million years were undoubtedly different than those beneath the surrounding structural highs or the Canadian Shield. The arches and domes surrounding the Michigan Basin remained as cssentially stable areas throughout most of the Paleozoic. The Wisconsin dome to the west was a structural high at the beginning of the Cambrian *M , whereas the Michigan area was part of a large basin which included the Illinois Basin.5" Lockett*" indicates the structural highs which form the boundaries on the southern half of the Michigan Basin were more or less positive features throughout the entire Paleozoic era. Green *M indicated that the positive regional structures in the Indiana-Ohio area are cue to subsidence of the Appalachian, Michigan, and Illinois Basins, rather than uplif t between the basirs. Eardley*" indicates that the Kankakee and Findlay Arches formed during the Ordovician. Green S " discusses the Cincinnati Arch geologic area and states: Subsidence in the Michigan basin began near the close of Niagaran (middle Silurian) time. Before that subsidence, the area of Indiana, 3g Ohio, and southern Michigan is considered to have been part of a sea floor which sloped gently toward the southeast from Illinois to Pennsylvania and Virginia. This relatively flat sea floor may be considered as having then been a structural shelf. Green also indicates that a broad shelf area over 150 miles wide existed between the Illinois and Michigan Basins until Mississippian time. There is general agreement that the " arches" between the Illinois, Michigan, and Appalachian casins have resulted from " resistance to subsidence" rather than from actual uplift. Development of the Michigan Basin was most rapid during the upper Silurian. About 30% of the total Paleozoic sediments was accumulated during this time. Only small patches of lower revonian sediments are known in the basinmo and the area was probably a low land mass during most of this time. During middle and upper Devonian, deposition resumed and over 3,000 feet of sediments accumulated in the central part of'the basin. Deposition continued into the Mississippian without interruption. l 33 There was a short break in sediment accumulation during mid-Mississippian, and another longer break in late Mississippian which continued through mid-Pennsylvanian time. Ham and 14 Wilson *C state: Revision 33 2.5-6 4/81
MIDLAND 1&2-FSAR The period of slight tectonic activity within the Michigan Basin
/ ; roughly correspond in time with tectonic activity elsewhere
(_/ within the Central Stable Region, but this is also true for tectonic events in orogenic belts outside the Central Stable Region (i.e., the Appalachian Bacin and the Ouachita fold belt). The markedly different magnitude of tectonic activity in Illinois, Kansas, Nebraska, Texas. and Okiahoma from that experienced by the Michigan Basin combined with the size of the basin (over 120,000 square miles) supports the concept of the Michigan Basin being a tectonic province as defined in 10 CFR 100, Appendix A. The basin is and has been a persistent, qq distinct region which has been geologically and structurally distinguishable from the remainder of the Central Stable Region since the upper Silurian over 400 million years ago. There is nothing in the seismic history of the region which suggests that the Michigan Basin should not be considered to be a tectonic province. The seismic history of the Michigan Basin clearly demonstrates that it is a region which has experienced very few events in the past 350 years, the period for which records are available. All of the events which have occurred were small (maximum intensity VI). All the data indicate that the Michigan Basin can be readily separated from the remainder of the Central Stable Region for the purposes of evaluating the potential for future vibratory ground motion. l5 2.5.1.1.3.2 Intrabasin Structural Features j 2.5.1.1.3.2.1 Polds Within the Michigan Basin, numerous small anticlinal flexures are present, trending generally northwest-southeast, and occurring throughout the basin (Figure 2.5-7). The knowledge of the existence of these flexures is based mostly upon data obtained from exploratory arilling for oil, primarily in Silurian and Devonian age strata. These fold structures are described by Ells" in reference to a (33 1930 paper by Newcombe as:
. . . irregular, elongate plunging anticlines with local domes superimposed. In cross section the folds were said to be asymmetrical with the strong dip toward the basinward side . . . .
The dips off-structure were shown to vary in the different fields from 125 to 200 feet per mile, and from 50 to 75 feet per mile on the gentle side. These northwest-southeast trending flexures are best defined in the eastern, southeastern, and central portions of the Lower
, 5 Peninsula.
7
> Pevision 33 2.5-6c 4fg1
MIDLAND 1&2-FSAR The origin of these intrabasin structures is not known, and several mechanisms have been postulated. While the method of 5 structural development is not fully understood, there is general agreement on the age (Paleozoic) of the features. Ells (88 l33 summarizes the type and origin of these structures: l5 O 2.5-6d Revision 33 4/81 l - - . - . .
MIDLAND 1&2-FSAR 7s Salt is presently being mined adjacent to the plant site, as well , ( ) as in many other locations in Michigan. Due to the close
't./ proximity of the salt mining and the possibility of related subsidence, a detailed investigation was performed which is discussed in Subcection 2.5.1.2.5.4. Figure 2.5-12 shows the locations of salt wells in the site area. Based on these studies it was concluded that subsidence due to salt extraction will not be significant at the site.
Oil wells present in the vicinity of the site are shown in Figure l33 2.5-13. Oil and gas fields within 50 miles of the site are shown in Figure 2.5-14. Wells completed near the site show no potential for oil production is present beneath the site. Any subsidence due to producing oil fields in the area will not be significant to the operation of the Midland plant. A discussion of oil and gas production relative to the Midland site is presented in Subsection 2.5.1.2.5.4. 2.5.1.1.5.3 Uplift The Michigan Basin has been relatively stable since the close of the Paleozoic era (see Subsection 2.5.1.1.4). Unloading dssoCiated with the last major retreat of glacial ice is apparently responsible for observed crustal uplift in the northeastern United States and Canada. Correlations of glacial lake shorelines, in conjunction with radiocarbon dating, indicate (/N that this rebound began at a fairly rapid rate with the greatest
,) adjustment occurring from 8,000 to 4,500 years ago.'33 Since that time, uplift has been slight. Estimates made by Gutenburgt24) in 33 1933 indicate the mean differential uplift in the Lake Huron area has been on the order of 6 inches per 100 miles per 100 years.
Tabulated data of records from 91 gages on the Great Lakes, giving years of record and movement per 100 years, can be found in Moore. t2 s' In this 1948 report, the average length of time l33 covered by these records is 52 years. The average rate of movement indicated at principal gages on each of the Great Lakes was 0.03 foot per 100 years and a maximum rate of 0.06 foot per 100 years. Movements recorded by U.S. Coast and Geodetic Survey and U.S. Lake Survey during this same period are on the same l 33 order as thoce indicated by the lake gages. Gutenburg,( 2 41 Moore,t 2 s 6 and Price 1261 believe minor regional uplift is still slowly occurring. The extent and rate of recent uplift near the site area have been negligible for a long period of time, with the overall rate in the region decreasing with time. MacLean, t 2 7: in 1961, reviewed the previous studies of uplift occurring as a result of glacial unloading and restudied the available data. He concluded " modern land uplift due to post-glacial isostatic rebound can occur only northeast of the fs Nipissing Zero Isobase." This line is based on Pleistocene lake (J)
\
2.5-13 Revision 33 4/81
MIDLAND 1&2-FSAR levels and is located about 70 miles north of the site, trending roughly northwest-southeast. He also concluded that the evidence on which the previously published rates of uplift are based is erroneous. More recently (1970) an international committee composed of personnel of the U.S. Lake Survey, the Canadian Hydrographic Service, and the Geodetic Survey of Canada has carried out extensive studies of changes in water levels of the Great Lakes caused by crustal movements. t28: Gage records used by the committee include records kept since 1860. The results of their investigation are shown in Figure 2.5-15 by lines of equal uplift for the northern United States and Canada. As the figure indicates, Michigan it experiencing a vertical movement of up to 1 foot per 100 years in the northern portion of the state to static conditions in the southern portion. In the site area, a rate of rise of 0.25 foot per 100 years is estimated. Minor crustal movement in the form of rebound is occurring in the site area and is at a decreasing rate. Crustal uplift is occurring at such a slow rate and over such a broad area that it will have no effect on the Midland site. 2.5.1.2 Site Geology The site area is characterized by low topographic relief and graded streams, typical of a glaciated plain. Surface materials at the site consist of outwash, till and glacial lake deposits, 350 feet thick that were deposited during the Wisconsin glacial stage. The materials were laid down either directly from the melting ice (till) or in front of the ice sheet (outwash and glacial lake deposits). - Beneath the glacial deposits are approximately 13,000 feet of indurated, nearly horizontally lying, Paleozoic sedimentary rocks (see Figure 2.5-3). A nearly complete' depositional history of the region from Cambrian to Pennsylvanian is present in these i strata. This section will discuss materials encountered during the site subsurface investigations. A discussion of rocks older than Pennsylvanian which occur in the site area can be found in Subsection 2.5.1.1.2. Subsurface investigations performed at the site in connection with the Midland plant include soil and rock borings, groundwater studies, and a geophysical survey. Figures 2.5-16 and 2.5-17 show the locations of borings in relation to the power block structures. Logs of borings drilled for the site investigations are presented in Appendix 2A. Selected samples of both soil and rock were laboratory tested to determine their static and/or dynamic properties, the resulta of which are presented in Appendix 26. The geophysical survey can be found in Appendix 2C and is discussed in Subsections 2.5.1.2.5.1 and 2.5.4.7. 2 .5-14 f<evision 33 O 4/81
MIDLAND 1&2-FSAR , mile of-the plant site calculated a slope of 0.02 inch per'100 f-feet. The plant structures can safely withstand a uniform slope ( of 1 inch per 100 feet.across the site. .This is not necessarily a limiting value, and yet far exceeds the slope produced by the estimated maximum settlements predicted in either the-Woodward-Clyde study or the General Analytics report.. The j necessity for an elasto-plastic analysis to determine the possible subsidence.due to a solution mined cavity was. _ considered. Dr. Keshavan Nair of Woodward-Clyde and Associates, a specialist in this field, indicated that an elasto-plastic analysis of a disk-shaped cavity which would provide values of-displacement is not available. However,.Reyes and Deere tam have l33 conducted elasto-plastic analyses for' circular openings using an incremental formulation. Their results indicate that the ! vertical displacement at the cavity face may increase by a factor of two. It was also observed that the yielding near the vicinity of the cavity had very little effect on the stress distribution at distances of twice the radius of the cavity. Analyses which. would best approximate elasto-plastic conditions are not necesrary since subsidence with a factor of two greater than the elastic case would still be much less than the values obtained ' using the empirical data of the National Coal Board of 4 England. I Summarizing the above results:
- a. Slope based on Woodward-Clyde report: 0.004 in. per 100 ft
- b. Slope based on General Analytics 0.02 in. per 100 ft l1 04 Report
- c. Slope which the plant structures can 1 in. per 100 ft withstand:
Therefore, the structural design can tolerate 50 to 250 times the maximum predicted slope projected from very conservative methods as used in both of the referenced reports. If subsidence at the-i ground surface did occur, local curvature of the foundation soils l under the plant structures is not expected. Since no curvature is predicted due to subsidence, there will not be any increment
- of flexural strain produced in the structure foundations, and there will not be any rotation of the structures relative to each -
other. A surface and subsurface subsidence monitoring system has been 18 l implemented at the Midland plant site (see Figures 2.5-24 and j 2.5-25). A total of 25 shallow benchmarks were installed in the h33 near surface clay strata (till) at the site (see Subsection 2.5.1.2.2). In addition, two deep benchmarks extending through, 18 l and isolated from, the glacial drift, were installed in the [ bedrock beneath the site. These two deep benchmarks will monitor 33 ! any subsidence which may occur in the Suginaw formation, i occurring at a depth of 250 feet or more beneath the site. The benchmark design is shown in Figure 2.5-26. First order surveys l18-
.\
2.5-25 Revision 33 4/81 i:
MIDLAND 1&2-FSAR will be made at least annually for the operational life of the plant to detect subsidence near the plant. Results of the survey 18 information are contained in Table 2.5-26. No subsidence has been detected by the system. In summary, future subsidence at the site, if any, will provide no offset displacements at the surface; rather a subsidence over a broad area would occur.
- a. Both the Woodward-Clyde and General Analytics reports predict maximum subsidence settlements of less than 1 inch over an area greater than the plant site; this is substantially less than the estimated allowable strains the structures can safely withstand.
- b. The Dow Chemical survey records indicate that ne subsidence has occurred at the site since they began their surveying in 1958.
- c. Creep rates, as shown in Figure 16 of the General Analytics report,0 3) indicate subsidence takes place in the early period of the cavity life; the two nearest salt wells, 10 and 17, were drilled in 1955 and 1961, and it is reasonable to assume that most subsidence, if any, from these salt well cavities has already occurred.
- d. Analyses which would best approximate the actual elasto-plastic conditions are not necessary because such solutions would indicate subsidence with a maximum factor of two greater than the elastic case, and this value would still be much less than the values obtained using the empirical data of the National Coal Board of
! England. ( e. No futurq salt mining operations will be conducted I within 1/2 mile of the plant site,
- f. Only Salt Wells 9, 10, 17, 19, and 20 are included within this 0.5 mile radius. All of these wells have been abandoned and plugged.
- g. Extraction of brine and the reinjection of the waste i
brine into the Sylvania Sandstone occurs over a large area, and therefore exclusion of the brine operations is not ilscluded. l It is therefore concluded that subsidence will not be a hazard to l the plant structures. \ l l l l @ 2.5-26 Revision 53 4/81
i i .. MIDLAND 1&2-FSAR I 2.5.1;2.5.4.2 Coal l , h coal deposits of commercial quality _and thickness are present in 10 eastern Michigan counties with some lesser reserves.in a few other eastern counties. Coal. production in the state has been i exclusively from the Saginaw ' formation of Pennsylvanian age and . l mainly where the formation is less than 200 feet from the ground I surface. Due-to a combination of limited lateral extent, thick glacial drift, high water table, and increased competition from other sources, coal mining in Michigan decreased almost continually'from 1907. Presently a single small surface coal j mine is in operation in the_ state near Williancton (60~ miles ! south of the site).M" Figure 2.5-11 shows the locations of known' commercial coal reserves for the site vicinity. As can be seen in the figure, no known reserves are present beneath the site. Drilling information from areas adjacent to the site substantiate the lackL of potentially minable coal.- The nearest commercial coal mining operation was 2-1/2 miles east of the Midland site. :This mine, known as the Randall mine, extracted coal from a 2 foot thick seam present about 230 feet below the surface. During its operation a total. of 358 acres were mined in both Midland and Bay Counties. The mine was abandoned in 1937j2st 2.5.1.2,5.4.3 . Oil and Gas i O . Oil and gas production occurs in Michigan, primarily from Ordovician, Silurian, and Devonian. age strata. Most of the production is associated with the northwest-southeast trending anticlinal folds described in Subsection 2.5.1.1.3. Figure . 2.5-13 shows all known oil wells within 10 miles of the site and l33 Figure 2.5-14 shows oil and gas fields within 50 miles of the site. i
, The Larkin Field, 5 miles north of the site and covering an area i of 20 acres, is the closest recorded oil producing area. This field has been abandoned since 1945. It consiated of only two production wells which pumped a total of about 7,000 barrels.*
i The most extensive oil producing fields in the site vicinity are j the Mt. Pleasant and Porter oil fields located about 10 miles-4 southwest of the site and having a combined area of over.12,000 l acres. The 1975 (latest available information) total quantity _of oil taken from the 267 active wells in these two fields was-nearly 200,000 barrels /S i The Kawkawlit. field, also still active, located 10 miles east of the site covers over 6,400 acres and produced 145,000 barrels in , 1975 from 300 separate wells. Oil _ fields in the-area obtain most of their production from the Dundee formation of middle Devonian
- age with minci amounts being produced from the Sylvania (also i middle Devonian), Black River (middle Ordovician), and Berea '
2.5-27 Revision 33 4/81
- - ~ . - . - - . . . - , . _ , . - . . . . . , . - - - . - . - . . . - . . . . ~ . - - . - . . . - , - . , - . - . - _ . ,
~
I MIDLAND 1&2-FSAR formations (late Devonian) (see Figure 2.5-3). The Dundee formation is approximately 3,600 feet below the surface, with the most shallow producing strata, the Berea formation, at a depth of about 2,500 feet. Nearby wildcat wells, shown in Figure 2.5-13, show that no potential oil or gas reserves are present in the vicinity of the site. Any subsidence associated with nearby oil fields, will not present a problem to the Midlcnd plant. 2.5.1.2.5.5 Unstable Materials Thick sequences of halite, anhydrite, and carbonate rocks occur in the sedimentary units of the Michigan Basin. Sinkholes are abundant in several areas of Michigan, roughly along the perimeter of the Lower Peninsula. Devonian age limestones are most affected by solutioning (see Figure 2.5-3). Solution features are found where these Devonian limestones approach the 18 ground surface (see Figure 2.5-4). The nearest area where these conditions exist is in the Detroit vicinity, 100 miles south of the site. No natural solution caverns are known to be present in the central portion of the state where the limestone, halite, and anhydrite are deeply buried. In Midland County the Devonian age Traverse Group, the most shallow carbonate rocks of significant l18 thickness, is about 2,000 feet below the surface. Significant deposits of halite and anhydrite are even deeper. The relatively impervious soil and nonscluble rock formations overlying these l 18 materials, combined with the high groundwater levels, prevent the rapid movement of groundwater and act as a deterrent to the development of solution cavities in the site area. 2.5.2.2.6 Behavior of Site Materials During Prior Earthquakes The behavior of the surficial geologic materials at the site during prior earthquakes was evaluated by studying existing ground conditions, and by comparing the recorded effects of the maximum historical intensity near the site on soils and rock with similar physical properties to those at the Midland site. An analysis of the maximum historical earthquake is presented in subsection 2.5.2.1. There is no evidence at or near the site of any ground failure, such as fissuring, lurching, subsidence, or landsliding generated by historic earthquakes. None should be expected since the soils ara dense and the maximum historical intensity near the site is only IV to V (MM, see Subsection 2.5.2.1.2). 2.5.1.2.7 Site Groundwater Conditions Groundwater conditions present beneath the site are discussed in Subsection 2.4.13. 1 2.5-28 Revision 33 0 l 4/81 t
MIDLAND 1&2-FSAR Groundwater is present in both the glacial deposits and the underlying bedrock at the site. The glacial drift deposits O contain two distinct aquifer zones as delineated during the site investigation, (see subsection 2.5.1.2.2) the upper brown sand (Unit a) and the lower sand and gravel (Units d and e). Between-these two zones is an essentially impermeable lacustrine clay and clayey till zone,.which restricts flow between the two zones. The uppermost bedrock unit at the site is generally an aquiclude 4 t J 3 4 4
, v 2.5-28a Revision 33 4/81
a4" A MIDLAND 1s2-FSAR O l l l l THIS PAGE INTENTIONALLY LEFT BLANK l l l l l l l Revision 18 2.5-28b 2/79
-- .. ~ _. - -- - . _ . ~- . - .- - - -.
l MIDLAND 1&2-FSAR l i t' t the epicenter. Therefore, intensity in the site area was ' probably no greater than IV-V. The May 26, 1909, shock centered near Rockford, Illinois - 275 miles southwest of the site, was felt from Missouri to Michigan and from Minnesota to Indiana.- According to Hobbs"*' this shock was reported mainly in the western part of Michigan , and there were no reports from the vicinity'of the site. The , closest town to the site at which the shock was reported was Lansing: At the state capitol, Dr. A. C. Lane, then the, state geologist, sitting in his private office felt the-jar and noted the time of the shock as 8:29 a.m. Mr. Harry R. Wright, his 3 secretary, in an adjoining room observed a . ,. 3 bookcase swaying on its base and also felt the vibration. Mr.-W. F. Cooper in the Jama rocm. determined with his watch that the duration of' , the shock was six seconds. Across the street and on the fif th floor of a neighboring building, Hollis H. Brooks sat tilted back in
.a swivel chair, and feeling-the shock brought.
his chair to a safer position. This description corresponds to about intensity III; thereforc, the shock was probably not felt in the, site area.
) Three large shocks in eastern Canada have been felt in Michigan. 33 L They occurred in 1870, 1925, and 1935. These shocks were mainly of epicentral intensities IX and X, and were located about 400-800 miles from the site. Isoseismal maps drawn by' Smith"S for the earthquakes in 1925 and 1935 show that the site area experienced intensity II in 1925 and III in 1935.
A series of shocks has occurred in the Anna, Ohio, area about 220 , miles south of the site. A thorough study of these events appears in Earthquake History of Ohio by Bradley and Bennett.(5'8 This report suggested a possible correlation might exist-between the earthquake zones and known geologic trends in Ohio. The
, report noted that the Anna area:
i . . . . lies just about where the Cincinnati i Arch bifurcates into the Kankakee and Findlay
; Arches (It should be noted, however, that this is a somewhat' gentle structure). The earthquakes also are west of the hinge zone separating the Ohio-Indiana Platform and the 1 Appalachian Basin. This hinge zone corresponds to the gravity contours, which show relatively smaller gradients toward the east and relatively larger gradients toward the west. It is possible that the composition i
V 2.5-33 Revision 33 4/81
, _ _ _ . _ . . . _ _ _ _ . , _ _ . - _ _ . _ . . - ~_ . . - _ .
MIDLAND 1&2-FSAR of the basement rocks differs systematically east and west of this line. g However, no definite correlation of the earthquake data with tha more prominent geological and geophysical features of the state was made in this report 2.5.2.1.4 Seismic Risk Map Figure 2.5-28 is the seismic risk map showing areas of the conterminous United States most vulnerable to earthquakes. The map was made by a group of recearch geophysicists headed by Dr. S. T. Algermissen of the U.S. Coast and Geodetic Survey and issued in January 1969.mu The map divides the conterminous United States into the following four zones: Zone 0: Areas where there is thought to be no reasonable expectancy of earthquake damage Zone 1: Areas of expected minor damage Zone 2: Areas where moderate damage could be expected Zone 3: Areas where major destructive earthquakes may occur The zones are based principally on the known distribution of damaging earthquakes, their intensities, and geological considerations. I The Midland site lies well within Zone 1 where only minor damage should be expected. According to this map, minor damage corresponds to intensities V and VI (MM). 1 2.5.2.1.5 Historical Maximum Intensity at the Site ! There is no physical evidence of any fissuring, liquefaction, l landsliding, landspreading, lurching, or caving of banks to l indicate that past earthquakes have disturbed either the surficial deposits or the substrata beneath the site. None should be expected to have occurred in view of the low I intensities experienced historically in the region. The maximum
- intensity for any earthquake in the lower peninsula of Michigan is intensity VI. The maximum intensity the site has experienced I historically is estimated to be V.
Revision 14 2.5-34 10/78 I
MIDLAND 1&2-FSAR No- additional analysis to specifisally take account of the site' soil column is ' undertaken. () This is becauseithe peak acceleration - (% by which the postulated SSE event is partially characterized depends upon a relationship between peak. acceleration and intensity derived from records on ~ a broad spectrum- of soil' conditions and is generally considered to be conservative. 2.5.2.6 Safe Shutdown Earthquake (SSE). The maximum intensity which the Midland site has experienced in historical times is V, as a result of the 1811-1812 New Madrid shocks , 575 miles from the site. The strongest historical earthquake within 50 miles of the' aite was an epicentral intensity V shock in 1872. The nearest earthquake of intensity VII or higher, was an intensity VII-VIII shock about 205 miles from the site, near Anna, Ohio. - Obviously, the site is located in a quie t seismic region. The maximum earthquake . for the site, as described in Subsection 2.5.2.4, is intensity VI, which corresponds to an acceleration of - 0.0 6g on both the Neumann(5 53 and the Trif unac and Brady(.ssi l ~33 intensity-acceleration curves. This indicates that a peak horizontal acceleration value of 0.10g for the SSE- (the minimum- l30 allowed ) would be adequate for the site. Neumann's curve, which relates intensities to a maximum- ground ' g acceleration, has been accepted in the past for the design of numerous nuclear power plants founded on firm materials. This 7-]s g A curve is based on data obtained from structures founded on . varied ' types of material including deep alluvium at El Centro, ~ Cali forn ia . 1 4 i (N (j 2. 5- 38 a Revision 33 4/81
- --. ra" ,,- , ---,
MIDLAND 162-FSAR O 1 THIS PAGE INTENTIONALLY LEFT BLANK 1 i l l l i 2/78 1
"*"--w '
. - ,, ___ ""wWg-,,, 'MWWwgy,.,-,,,_ _
1 l l MIDLAND 162-FSAR ) 2.5.4.7.2 onsite seismic Work (A) Based on Weston Geophysical Engineers, Inc., onsite seismic survey measured shear and compression wave velocities, soil I properties, and E values for the very low strain levels caused by seismic investigation work were as follows (see Subsection
- 2. 5. 4. 4) :
From Ground From Approximately Surface to 50 Feet to Approximately Approximately 50 Feet Deep 140 Feet Deep (Sand) (Silty clay) Dry density ()h/f t3) 110 135 Shear wave velocity (ft/s) 850 2,300 compression wave velocity 5,200 6,100 (ft/s) Poisson'a Ratio 0.49 0.r_ Modulur, of elasticity 7.34 x 106 63 x 106 (lb ' f t2) 2.3.4.7.3 Dynamic E Based on Seismic Survey and Published Data Although the above dynamic E value (Subsection 2. 5. 4. 7.1) was based on laboratory tests, it appeared conservative in comparison with the results of the site seismic survey. For a depth of p]. (
\-
approximately 50 to 140 feet below existing ground surf ace, the shear wave velocity was measured at approximately 2,300 ft/s. The shear modulus (G) calculated from this velocity was approximately 20 x 106 In/ft2 for the low strain levels of site seismic survey work. As this value corresponded reasonably well with the cyclic shear strain versus shear modulus divided by unconfined shear strength data published by Idriss and Seed,(663 the published data were used to correlate strain level with bulk modulus and thus dynamic E. Assuming that the shear stress resulting from an earthquake equaled the total weight of the column of soil above the depth in question multiplied by the l33 maximum acceleration coefficient, then at a depth of 50 feet where the site soils have an average unconfined shear strength of approximately 8,000 lb/fta, the dynamic E was determined equal to
- the following:
I I Ea rthquake Acceleration Assumed E at 50 Feet at Surf ace Poisson's Ratio Depth (1b/ f t 2) 0.05q 0.4 30 x 106 0.10g 0.4 22 x 106 i 0.15g 0.4 17 x 106 ! (O _/ 2.5-55 Revision 33 4/81
MIDLAND 162-FSAR It was recommended (59) that these E values be varied by 150% during analysis to check the effect and allow for possible variation in E from the computed values. 2.5.4.7.4 Short-Term Static E and Dynamic E Based on Additional Laboratory Testing Subsequently, static and dynamic laboratory testing was performed to develop more refined data. Two available undisturbed samples were subjected to a comprehensive testing by cyclic triaxial, resonant column, and static triaxial tests. Sample descriptions, soil properties, and laboratory E values in terms of cyclic shear strain a re presented in Table 2. 5-7. No marked variation between laboratory static E and dynamic E was apparent from the test results. Based on these test results, the laboratory dynamic or short-term static E values for various shear strain levels are as follows: Shear Strain Dynamic or Short-Term E, (1b/ f t2 ) (%) Boring 14 at 587.5 Boring 15 at 546.6 1.0 1.0 x 106 0.32 x 106 0.1 3.4 x 106 1.0 x 106 0.01 11.5 x 106 3.0 x 106 8 0.001 39.2 x 106 9.0 x 10 l28 An overall review of the previously outlined field and laboratory testing and analyses indicates the following:
- a. The initial dynamic E value of 2.92 x 106 lb/ft2, corresponding to a shearing strain of 0.02%, developed by the first set of dynamic triaxial tests is conservative and has not been substantiated by subsequent studies.
- b. The dynamic E values evaluated based on the seismic survey and published data are the E values that would be expected for the site soils on the basis of their strength characteristics. For an acceleration of 0.12g, the dynamic E value at a depth of 50 feet should be assumed equal to 20 x 106 lb/ft2 150%. This value assumes the cyclic shear strain will be approximately 0.005%.
- c. The final set of laboratory tests indicates that the laboratory static and dynamic E values are approximately equal for short-term loading conditions. At least one of these tests indicates similar E values at comparable strain levels as would be expected from item b above.
Revision 28 2.5-56 5/80
MIDLAND 1&2-PSAR
- d. The field seismic survey indicates that the upper limit h' of the dynamic E is on the. order of 60 x lo s lb/f t 2 for
[~'/
\_ very low strains.
Au the average unconfined shear strength of the in situ soils supporting the subject foundations is approximately 8,000 lo/f t2, it is considered appropriate to increase laboratory E values la proportion to their unconfined strengths to give interpolated E values for soil with an 8,000 lo/ft2 strength. Considering all other data available, averaging test results and adjusting from laboratory measured E values to probable field valaes, by a correction f actor of 1.5, the field E value for various strain levels is estimated to be as follows: Cyclic Shear Strain E (4) (lb/ft2)
.001 45 x los
.01 14 x 10s
.1 4. 4 x 10 s 1.0 1.3 x~10s The U value is related to cyclic shear strain in the above values by the eguation:
E = 1. 3 x lo s g-0 5 (2) 1-4 fg As the cyclic shear strain during seismic loading will be in the ( ,) range at 0.001 to 0.0l$, it is concluded that the E value of 22 x 10s lb/ft2 +50% is appropriate for the seismic analysis of 33 st ructures f ounded on in-situ soil. Soil-structure interaction under seismic loading is discussed in Subsection 3.7.2. 2.5.4.8 Liquefaction Potential It is scea from Figures 2.5-20 and 2.5-21 that sand pockets exist at tne Midland plant between the approximate elevations of 603 and 575. These pockets vary in thickness from very small to about 25 feet. A dense layer of sand also exists between the approximate elevations of 360 and 250. The stratum of granular soils below elevation 360 is highly confined and exhibits high densities, as determined by laboratory testing and standard penetration testing reported by Dames & Moore tssi and as inferred from shear wave velocity data reported
< by Weston Geophysical (see Appendix 2C). These granular soils would not liquefy under any anticipated seismic loading.
Liquefaction potential for the upper layer of sand was evaluated for the plant area by two methods. The first inethod(87, 883 is fs based on simplified procedures and made use of standard pene tration test data. The second methodism is based on the (V) 2.5-57 Revision 33 4/81
MIDLAND 162-FSAR relationship between field values of cyclic stress ratio and standard penetration test blowcounts, established from data of various sites where liquefaction or no liquefaction was known to have taken place. Established values of the operating basis earthquake (OBE) acceleration and the safe shutdown earthquake (SSE) acceleration were 0.06g and 0.12g respectively. The maximum acceleration (0.12g) provides a very conservative basis for evaluating liquefaction potential. A detailed discussion of the above criteria is presented in subsection 2.5.2. The liquefaction study is based on five cycles of strong motion, a value that is conservative for earthquake intensity VI (MM) at the site.(een 2.5.4.8.1 Liquefaction Potential Based on Simplified Procedure and Standard Penetration Test Data The blowcount obtained from the standard penetration test can be used as a measure of the relative density of sands in situ. ( 70) The liquefaction potential of the sands can in turn be evaluated on the basis of relative density.(se) Standard penetration test data were obtained from the boring logs where sand pockets were encountered. The location of these borings is shown in Figure 2.5-40. Curves of constant relative density versus depth (70) are constructed and superimposed on the blowcount data, as shown in Figures 2. 5-41 and 2.5-42. The liquefaction potential is assessed below on the basis of the relative density and standard penetration test data shown in Figures 2.5-41 and 2.5-42 and the simplified procedure in Reference 68. The minimum relative density required to prevent liquefaction is evaluated by the following equation: i [amaxk i D = 32.5 x\ g /x rd X 'v (3) 1
#d X C r X a v 2"3 where D = minimum relative density required to prevent liquefaction am ,, = peak ground surface acceleration g = acceleration of gravity rg = stress reduction coefficient "v = total overburden pressure (lb/ f t2) 3 v = effective overburden pressure (lb/ f t2)
Revision 1 2.5-58 11/77
MIDLAND 162-FSAR Table 2.5-15 shows equivalent fluid weights used in design for ('N
\m-)
the active case (nonrigid walls) as conservatively derived by Dames & Moore for sand and clay above and below the water table. 2.5.4. 10. 2. 2 At-Rest Earth Pressure Piqid walls and walls sufficiently, restrained can cause at-rest soil pressures to develop. At-rest pressures are those pressures developing at a point in the ground not subject to any lateral movement. For in sit 2 clean sands, the theoretical at-rest earth pressure coefficient k varies from about 0.35 for dense sands to about 0.5 for loose sands. However, backfilling and compaction processes may cause the lateral ea.-th pressure to increase the above theoretical at-rest value. Table 2.5-15 shows equivalent fluid weights used in design for at-rect case (rigid walls) as derived by Dames & Moore for sand and clay above and below the groundwater table. For sandy soils, the results are based on k of 0.5 2.5.4.10.2.3 Passive Earth Pressure When a wall is pushed into the backfill, the horizontal stresses in the soil will increase until the shear strength of the soil is fully mobilized. The horizontal si.ress developed under this condition is known as the passive earth pressure. However, the a movement necessary to-develop full passive pressure is quite
) large. This movement is on the order of 5% of the height of the wall. Eecause movements of this magnitude cannot normally be tolerated, a factor of safety of two is usually applied to the total passive pressure. Design values for passive pressure are included in Table 2.5-15. l8 2.5.4.10.2.4 Dynamic Earth Pressure During earthquakes, active and at-rest pressures will increase, while, under worst conditions, the passive pressure will -reduce.
The simplified design procedures for dynamic soil loads are based on the Mononobe-Okabe analysis of dynamic pressure in dry cohesionless' materials. See Seed and Whitman.(71) Based on the Mononobe-okabe approach, dynamic lateral pressures were estimated for sand backfill. These pressures, along with the method used to combine them with active, at-rest, or passive preseures, are 'shown in Figure 2.5-45 for clean sand backfill under the water table. O V 2.5-63 Revision 33 4/81
MIDLAND 162-FSAR 2.5.4.10.2.5 Surcharge Load Due To Adjacent Structures Surcharge loads caused by adjacent structures can generally be k defined both in magnitude and area of application. The pressure developed by adjacent structures is additive to the lateral pressure directly applied by the backfill material. This additional earth pressure can best be determined by using methods derived from the theory of elasticity which are available for most loading shapes encountered in engineering applications. Suitable solutions are given by Bowles.c72) If the wall is considered to be rigid, the earth pressure will be twice that due to the elastic solutions as described and accounted for in this reference. 2.5.4.10.2.6 Live Load Surcharge The lateral earth pressures due to live load depend on the load intensity, location, and shape; therefore, these lateral pressures can best be determined by elastic methods. Several possible load configurations that may be anticipated are t veni by Bowles.C72) Surcharge pressures caused by dead or live loads were added to the pressures shown in Figure 2.5-45. 2.5.4.10.3 Settlements This section deals with the evaluation of vertical ground movements (heave or settlement) under the plant facilities caused by construction. An excavation up to 40 feet below the original ground surface was made to enable the construction of the containment and portions of the auxiliary building. A large area fill up to 35 feet high, measuring approximately 1,000 feet by 1,100 feet, has been placed as shown ir Figure 2.5-46. Heavy structural loads will be applied on this fill. The groundwater table at the plant area will be raised to elevation 627 when the cooling water reservoir is filled. The ef fects of the above construction operations on ground movements at the Midland site are as follows:
- a. First, when the site was excavated to depths of 40 feet, the resulting removal of material caused the underlying soils to rebound upward.
- b. Next, as the large area fill was placed and structures were constructed, the resulting loads recompressed the prior upward rebound and then caused additional settlement.
- c. Finally, raising the groundwater table will reduce the net foundation pressures. However, some settlement will 2.5-64 O
~_
MIDLAND 162-FSAR continue until equilibrium is reached under the net increase in load. Ultimate heave or settlement values were estimated by calculating the stress chunges from elastic half-space theory and then computing the settlement or heave using Terzaghi's theory of one-dimensional consolidation. Parameters to establish the analytical model are discussed in the following subsections. 2.5.4.10.3.1 Plant Layout and Loads As shown in Figure 2. 5-47, the two units and the contiguous structures occupy a total area measuring approximately 600 feet by 600 feet. Preconstruction grade at the site is approximately elevation 603. Finished grade at the plant site is 31 feet higher, at elevation 634. Compacted fill was used to raise the original ground surface to grade elevation. Each containment was founded on a circular mat having a diameter of 128 feet and located at a depth of 20 feet below original ground surface. Portions of the auxiliary building were established 40 feet below original ground surface on the layer of very stiff to hard cohesive soils. The mat foundation grades for the rest of the auxiliary building, the turbine building, and g3 associated facilities were placed at various elevations on t
) compacted fill. The building loads superimposed by the structures on undisturbed soil or compacted fill are given in the soil pressure plan, Figure 2.5-47.
2.5.4.10.3.2 Subsurface conditions The plant site was essentially flat, and the ground surface was at about elevation 603. A detailed description of soil conditions together with generalized soil profiles through the plant site is given in Subsection 2.5.4.3.5. For the purpose of analysis, the soil profile is divided into the layering system shown in Table 2.5-16. 2.5.4.10.3.3 Soil Parameters The soil compressibility parameters esed in the settlement calculation are presented together with soil profile in Table
- 2. 5- 16. The normalized compression and swelling indexes (c c .r /1+eb) were evaluated by two methods. The first method 1 used, presented by Dames S Moore,(se) is based on laboratory consolidation t.asts with adjustments for the effects of sample.
disturbance as discussed in subsection 2.5.4.2.9. O
\s- Revision 1 2.5-65 11/77
MIDLAND 162-FSAR The other method is based on mathematical relationships among compression index, constrained modulus, and Young's Modulus as illustrated by Lambe and Whitman.(73) Young's nodulus (E = 6 00 Su) ( 7 * ) is based on a statistical relationship with the unconfined compressive strength or undrained shear strength. The undrained shear strength used is interpreted conservatively from the summation plot of shear strength vs elevation givea in Figure 2.5-33. The sampling of overconsolidated glacial clays is usually dif ficult due to the stiffness of the clays. Sample disturbance is inevitable. This evidence is clearly shown from all the laboratory consolidation test curves. Furthermore, experience indicated that the estimated soil compressibilities from consolidation tests are influenced and increased by the specimen l33 preparation of trimming and ring fitting. On the other hand, the empirical compressibilities are derived from shear strength test results, which are not affected by sample disturbance to the same degree as laboratory consolidation test results. The normalized compression and swelling indexes (cc .r/1+eo) adopted in settlement calculations are the weighted average values derived from both methods. 2.5.4.10.3.4 Groundwater Conditions For settlement evaluation, the static groundwater level is conservatively estimated at or near the existing ground surface before construction. The post-construction long-term water level in the plant area is taken to be elevation 627. This elevation will be the maximum operational level of the filled cooling pond. l l 2.5.4.10.3.5 Analysis i l The settlement evaluation for the plant structures was made from l I a consideration of the fcllowing cases:
- a. Settlements due to placement of fill to grade and application of building net loads prior to flooding of the cooling water reservoir, water level at elevation 603 (short-term condition)
- b. Settlements duc to fill and building net loads af ter reservoir is filled, wa ter level at elevation 627 (long-term condition) l Heave from pressure relief due to excavation of overburden soils i
cbove the foundations is not analyzed because: 1) pressure relief due to excavation would decrease quickly to zero by the subsequent placement of fill and building loads, 2) the heave associated with stress reduction is relatively small compared to the settlement due to large area fill and building loads, and is essentially elastic due to the highly overconsolidated nature of 2.5-66 Revision 33 9 i 4/81
MIDLAND 1&2-FSAR t .2.5.5.~1 Slope Characteeistics ( ~% As discussed in Subsection 2.5.4.10, most of the plant'
\m / facility foundations were established on compacted fill ~. Fills up to-approximately 35 feet thick were required to attain.the final l32 plant elevation of 634. The downstream soil slopes of the plar.t area fill have a slope of 3 horizontal to 1. vertical and are separated from the Seismic Category I plant structures by about 500 feet. Figure 2.5-46 depicts the location of fills relative to plant facilities. Two representative cross-sections, K and-T, are shown in Figures 2.5-49 and 2.5-50. Apart from the. plant--
area fill slopes, there were no other cut or fill, soil ~,.and rock slopes, either natural or manmade, associated with the power-plant facilities. Temporary excavation slopes were made for mat foundation placement of the containment structures and portions-of the auxiliary building as shown in Figure 2.5-37. The maximum' depth of excavation was about 40 feet and the slopes of 1.5 horizontal to 1 vertical, determined by slope stability. analysis before 33 construction, were utilized. The excavation slopes remained stable during and after the placement of mat foundation. The excavated area has been completely backfilled with compacted fill 32 to final plant grade of elevation 634. Slopes of 1.5 horizontal to 1 vertical were originally designed for 40 foot depth of excavation. Therefore, the factor of safety of the remaining excavation slope will be appreciably greater than the minimum (g designed. Furthermore, these slopes are temporary and have no ( ,/ bearing on the function of the completed plant. 2.5.5.2 Design Criteria and Analysis-The embankment at the olant area is an integral part of the entire cooling pond dike. The plant embankment sections shown.in Figures 2.5-49 and 2.5-50, associated with cooling pond dike sections which are discussed in Subsection 2.5.6.4.1, were selected based upon 1) slope stability, 2) seepage control, and
- 3) the best use of excavated mater'ials which were excavated in the course of construction of the cooling pond. The embankment consists of up to six zones of different materials. These zones and materials are listed in Table 2.5-10. They are discussed in 18 detail in Subsection 2.5.6.4.1.
The embankment is supported directly on the existing subsurface soil and the foundation area was prepared by clearing all organic and loose sand to the limits of the embankment. To control seepage through the dike foundations, a cutoff trench was excavated to a minimum depth of 2 feet into an underlying snil of low permeability along the entire length of the embankment. Localized sand pockets encountered above soil of Icw permeability were excavated. This trench, whose shape is shown g- in Figures 2.5-49 and 2.5-50, was backfilled with compacted core V 2.5-71 Revision 33 4/81
MIDLAND 1& 2-FSAR material. A slurry trench cutoff was substituted where an appreciable depth of the sand and unf avorable groundwater conditions made a compacted fill cutoff impractical. About 400 linear feet of slurry trench cutoff was constructed in two sections along the north plant dike. A plan view of the slurry trench locations is shown in Figure 2.5-46. Profiles through the trench site are shown in Figures 2.5-51 and 2.5-52. The detailed placement of slurry trench and slurry properties is discussed in Subsection 2.5.6.3. The stability analyt.is for the plant embankment slope under various conditions was not performed on the two representative cross-sections as shown in Figures 2.5-49 and 2.5-50. Section G, Figure 2.5-53, the highest portion of the dike with a normal crest width, was selected as representative of the most unf avorable conditions and used for stability analysis. Soil properties selected for design, various stability conditions, and methods of analysis are presented in Subsection 2.5.6.5. Results 9f stability analysis for Section G are tabulated in Table 2.5-20. Because the stability a:;alysis was performed on the most unfavorable section, the actual factor of safety over the plant embankment slope is appreciably greater than the minimum specified. 2.5.5.3 Logs of Borings The logs of Sorings and test pits together with drilling and sampling methods that were completed for the evaluation of slopes, foundations, and borrow materials to be used for slopes, are discussed in oubsection 2.5.4.3. Borings specifically related to the power plant area are described in Subsection 2.5.4.3.4. The information which indicates elevations, depths, soil and rock classification, groundwater 1cvels, sampling method, and blowcounts from standard penetration tests is shown on each individual boring log. The boring logs are presented in Appendix 2A. 2.5.5.4 Compacted Fill The material, placement, compaction specifications, construction procedures, and control of earthwork fill required to construct plant embankment slopes are comparable to those of the cooling l 18 pond dikes (see Subsection 2.5.6.4). 2.5-72 Revision 32 O 1/ul
MIDLAND 1&2-FSAR and 3) the best use of materials which were excavated in the g'~% course of construction of the cooling pond. The embankment t } consists of up to six zones of different materials. These zones and materials are listed in Table 2.5-10 and described in the 10 following paragraphs. The Zone 1 cor'e material consists of glacial till and lacustrine clay obtained from the area of the emergency cooling water reservoir and the southwest region of the cooling pond site. Figure 2.5-61 shows the-Zone 1 borrow areas. Surficial sand and silty sand are excluded from Zone 1 as are any materials with less than 20% passing the number 200 sieve. Zone 2 materials were taken from the designated borrow and excavation areas and consist of random material not suitable for Zone 1, providira it is free of organic material or humus. Figure 2.5-61 she ; the Zone 2 borrow areas. Zone 1 and Zone 2 materials are compacted accordin'g to the requirements shown in Table 2.5-21. Zone 3 is intended to be free draining and therefore is constructed with clean sands. Zone 3 is used as a chimney drain separating the low permeability Zone 1 material and the random Zone material. Sands available at the site did not meet the specifications; therefore, all the Zone 3 material was imported from Mt. Pleasant, Michigan. Construction equipment was prohibited from crossing over the Zone 3 material to avoid [%/s) contamination with finer impervious materials. The gravel size materials for Zone 4, 4A, and 4Z were not found on the site and had to be imported. They consisted of crushed rock obtained from the Inland Steel Company quarry, Manistique, Michigan. These materials did not require moisture conditioning or specific compaction effort beyond normal passage of construction equipment. The gravel size Zone 4 material is used as a filter at the outlet of the horizont"' drain, as bedding under Zone 5 riprap, and as surface court _ on the dike crest. Zone 5 riprap was also imported and consisted of lime rock from the Inland Steel Company quarry near Manistique, Michigan. The riprap was placed by end dumping at the dike crest and spreading with a dozer. The riprap was used for slope protection as discussed in Subsection 2.5.6.4.2. The Zone 6 topsoil was all obtained onsite and consisted of the material which was stripped off the borrow and excavation areas throughout the site. The Zone 6 material was placed by end dumping and bulldozer spreading. Control tests as described in Subsection 2.5.4.5 were regularly performed on the dike materials. Table 2.5-12 lists the number 18 of tests actually performed durino dike construction. Figure 2.5-61 shows the locations of the Proctor Density tests. i D)
\'
2.5-77 Revision 18 2/79 l i l i i I l
MIDLAND 1&2-FSAR 7.5.6.4.2 Compaction Equipraent i Several types of compaction equipment were used to compact a h 1 foot lift of similar Zone 1 material in 1973 on tne test pads. They consisted of the following series. 18 SERIES A - The following three types of compaction equipment were used on the test pads located at grid coordinates S4600 and E1450.
- 1. Bros roller, having four pneumatic rubber tires on one axle, which has been loaded to a gross weight of 50 tons, pulled by a Terex 8240 Dozer 33
- 2. A smocth steel drum vibratory roller, Raygo Rumbler, pulled by a Michigan 280 tractor with the following specifications :
Gross weight 20,000 lb Drum diameter 60 in Drum length 100 in Dynamic vibration force 45,000 lb Vibration frequency 1,100-1,500 vpm
- 3. A CF43 Vibroplus Sheepsfoot roller, pulled by a Michigan 280 tractor with the following specifications:
Static weight 12,000 lb Centrifugal force 11.5 tons Total applied load at 35,000 lb 1,600 vpm Vibration frequency 1,400-1,600 vpm Diameter of drum 63 in Length of drum 75 in 18 Each roller made four passes over its respective test pad. All the material placed in the test pads corresponds to the same compaction curve with optimum moisture content being 10.3% and the maximum dry density being 124.7 lb/ft3 The ASTM L 1557-66T compaction method, modified to achieve a compaction energy of 20,000 ft-lb/ft3, of soil was used. The results of the tests are tabulated below: Passing Mois- Dry Compac- #200 Test ture Density tion Sieve Pad (%) (lb/ft3) (%) (%) Roller Type 1 10.9 110.2 88.4 64 50 ton rubber tire 1 17.9 112.5 90.2 50 ton rubber tire 1 12.0 111.4 89.3 50 ton rubber tire 2.5-78 4/81
MIDLAND 1&2-FSAR 2.5.6.5.2 Soil Properties.
\_,/ The soil properties used in the slope stability analyses are listed in Table-2.5-22. The higher density values listed in the table represent the upper limit of measured densities and were used when stability analyses included horizontal earthquake forces. The slope prctection materials, Zone 4, 4A, and 4Z crushed stone, 5 and SA riprap and topsoil, were assumed to act only as surcharge on the slope and were assurued to have %' = 0.
The cohesive strength of the glacial till was ignored in the-stability analysis except for the earthquake analysis of the emergency cooling water reservoir slope and deep seated failures including the dike and the emergency cooling water reservoir. 2.5.6.5.3 Stability Analysis Eccause of the considerable variation in foundation soil characteristics throughout the cooling pond site and the variable dike height required at various locations around the dike, critical dike sections were selected as representative of the most itnfavorable conditions and used for stability analysis. Figures.2.5-53, 2.5-59, and 2.5-60 show these cross-sections. Section G, Figure 2.5-53, represents the portion of the greatest dike height with a normal crest width, and Section I, Figure 2.5-59, represents the portion of the greatest dike height with a wide crest supporting a railroad siding. Section 3, Figure 2.5-60, is a cambined dike and emargency cooling water reservoir ( ,s) slope section. This section was analyzed to investigate the possibility of a deep seated failure which would jeopardize the operation of the emergency cooling water reservoir. The general criteria for cooling pond dike construction called for excavation of a cutoff trench along the entire length of the dike fully penetrating any surficial sands and into either - lacustrine clay or glacial till. At those sections where cutoff trenches are provided and the surficial sands occurred, the dike foundation includes a layer of loose sand for which 9' was about 320, soil 7 of Table 2.5-22. The foundation used in slope stability calculations for Sections G and I was conservatively taken to consist of about 13 feet of loose sand over the glacial till. Three critical periods during the life of the dike were studied ! for stability purposes: the construction phase, the full reservoir condition, and rapid drawdown conditions. The cc'struction period could be critical if the excess pore pressures developed during construction are not dissipated before the dike reaches substantial height. Because the dike is relatively low and the construction occurred in stages over several years, this problem did not occur. I) (_/ Revision 8 2.5-79 4/78
-- e - -. ,,,--,,..,--,-,e, -,,m. c ,w- ,- ,
MIDLAND 1&2-FSAR Under full reservoir conditions the upstream slope is initially the critical slope but after sufficient time the downstream slope may become critical. The upstream slope was studied and found to be safe. Because of the presence of a sloping chimney drain, the downstream slope is not critical. Rapid drawdcun conditions for both inner and outer slopes were studied. Surcharge may also be imposed on the dike at some locations. The l3 entire dike has a roadway along the crest and a portion of the northeast dike has a railroad in addition to the road. For sections of the dike where only the road exists (like Section G) a surcharge of 500 lb/fta, simulating the roadway load, was used in stability analyses. For portions of the dike with the railroad, a surcharge of 1c 200 lb/f ta is used. The conditions studied are presented in Table 2.5-20. The minimum factors of safety for each trial section were computed by the " Modified Swedish Slip Circle - Method of Slices" and the Simplified Bishop Method of analysis and are shown in Table 2.5-20 along with the minimum required factors of safety. Part of the stability analyses were performed with the Bechtel CE-533 06)U7) program and the rest of the analyses were made using the ICES Slope Stability program. Because the stability analysis was performed on dike sections with most unfavorable geometry, the actual factor of safety over most of the dike will be greater than the minimums specified. 2.5.6.5.4 Results of Stability Analysis The short-term (construction phase) stability of the dikes was determined by total stress analysis using undrained shearing strengths of foundation clays and recompacted clays at the anticipated placement moisture content. Because of the low height, relatively flat slopes, and absence of water in the l 33 cooling pond during construction, the dikes were stable during construction. The long-term stability of the dikes was analyzed usina ef fective stress parameters. For analyses of full and partial pool conditions, Tittabawassee River flood conditions, and earthauake forces, the locations of the phreatic lines were based on the conservative assumptions of straight lines from the inner slope water level to the Zone 3 sloping chimney dr ain. The stability of the dikes under seismic loading was studied by i the pseudostatic method where the effect of an earthquake was l 33 approximated by a horizontal force equal to the product of the i weight of the dike material and a seismic coefficient. The I seismic coefficient adopted for these Seismic Category II structures was 0.06g (OBE). l Revision 33 2.5-80 4/81 1 1 1
~ . - _ . . - - ..- .
1 -
. MIDLAND 1&2-FSAR 4
.The piezometers have beer installed at the locations shown in l-8
- /"' Figures 2.5-63 and_2.5-f4.. Section P1 is a typical high dike 1 section with a compacted cutoff' trench and Section P2'is a i- section with a slurry trench. Section-P2 is located adjacent to
; the' emergency cooling water reservoir.
l' . i Ten piezometer -tubes ~ with Casagrande or: pneumatic (TERRA-Tech). l8 type piezometers have been installed at each.section. The i appropriate depth for each piezameter tube is shown in Figures 2.5-63 and~2.5-64. I The piezometers have been installed before cooling pond' filling' .
! to observe initial piezometric heads. A detail of two typical .82 piezometers as installed is shown in Figures 2.5-84 and.2.5-85.
I During the filling, piezometric'1'e vel readings were.taken either weekly or at 2. foot water level intervals, whichever was more i frequent, and until steady-state conditions were reached. Thereafter, readings have-been made monthly.- The piezometer-readings will be made more often immediately after high floods,- earthquakes, and rapid drawdown. 4 ' i Initial piezometric head readings to establish the phreatic. i surface plus other readings during pond filling will be provided ' 8 l after the pond is filled. i 2.5.6.9 Construction Notes
- ) The partially complated northeast dike was exposed during the -
construction shutdown period. ' Frost in the Midland area can I I penetrate 4 feet or more. A study was made to determine-frost-i penetration depth into the fill before resuming the earthwork operation. In June and July 1973, soil test borings were made l 33-at approximately 500 foot intervals along the partially completed northeast dike. Borings 902, 904, 905,'918, and 921 were made in. the Zone 1 material of the dike, and borings 903 and 920 were l made in the Zone 2 material. The penetration depth ranged from j 20 to 72 feet. In each boring, undisturbed Shelby tube samples were taken continuously to a depth of 12 feet to penetrate i through the partially completed dikes. Bulk samples were taken l from borings adjacent to the borings listed above. The locations of these borings are shown in Figure 2.5-17. The boring logs are presented in Appendix 2A. Boring 904 was drilled by Soil and Materials Engineers, Inc. who j also performed tests on the samples. The test results are
- discussed in Subsection 2.5.4.14 and presented in' Table 2.5-17.
l All other borings were drilled by Raymond International, Inc.,
- and the samples were tested by the Pittsburgh Testing Laboratory
, at the site. !. The study basically consisted of determining the percent l compaction from the ground surf ace to a depth of 12' feet. Ten compaction curves, determined by ASTM D 1557-66T modified-to get !O , 2.5-83 Revision 33 l 4/81
*y%.-.-,-e,g ,,9-%r..-..-p,,g.mi ,.me,_---.w,.e,ea,,
,e--.,y r. ,m -,r.,,...,m., , , . . , , . , , - . . ..-,,,,.,,-,-,,*,.,m~~,...----,,_ , , ,
MIDLAND 162-FSAR 20,000 f t-lb of compactive energy per cubic foot of soil, were established frcM the retrieved bulk fill samples. For each of several borings, the soil density values were determined for small thicknesses from the ground surface to a depth of 6 or 12 feet so that a continuous profile of percent compaction could be drawn. A number of the tube samples were unsuitable for density determination because of disturbance caused by gravel present in the fill. The percent compaction versus depth plot, deternined from the comparison between the measured in situ soil density value and its respective compaction curve, is presented in Figure 2.5-65. The percent compaction for in situ fills was equal or greate chan the minimum required 95% compaction criteria except for tour localized spots. In conclusion, no damage to the dike during the shutdown period was found. This is confirmed by the observation that the dikes used as a haul road for loaded scrapers did not result in significant distress. The single exception was a low area on the inner half of the dike betweca Stations 6+00 and 8+00 which showed distress. However, it showed no further distress after being undercut by 2 feet. During the reconditioning of the dike, it was necessary to scrape off only the upper few inches of soil that had been disturbed by erosion. It was not necessary to take off more than 2 feet except where the surface showed distress when subjected to scraper traffic. The excellent condition of the dike af ter 3 years is attributed to the grade to which the surface was sloped to drain water and to the low permeability of the soil when compacted to the existing density values. 2.5.6.10 Operational Notes The cooling pond dike embankments have been completed but the cooling pond and emergency reservoir will not be filled until the spring of 1978. F 2.5-84 4/78
MIDLAND 162-FSAR APPENDIX 2A i l TABLE OF BORING LOGS t l l 2A-i Revision 33 l l 4/81
~
MIDLAND 1&2-FSAR Table of Contents (continued) O. . Section Title Page 3.5.2.4 Missile Barriers Within Plant Structures Other Than containment . . 3.5-27 3.5.3 BARRIER DESIGN PROCEDURES . . . . . . . . 3.5-28 7: References . . . . . . . . . . . . 3.5-30 3.6 PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING . . . 3.6-1 3.6.1 POSTULATED PIPING FAILURES IN FLUID SYSTEMS INSIDE/OUTSIDE CONTAINMENT .. . 3.6-1 3.6.1.1 Design Bases . . . . . . . . . . . . . 3.6-2 3.6.1.2 High and Moderate Energy Piping .. . 3.6-6 3.6.1.3 Safety Evaluation . . . . . . . . . . 3.6-8 29 3.6.2 DETERMINATION OF BREAK LOCATIONS AND I DYNAMIC EFFECTS ASSOCIATED WITH THE i POSTULATED RUPTURE OF NON-NSSS PIPING . . 3.6-9 3.6.2.1 Criteria Used to Define Break and Crack Location and Configuration . . . 3.6-9 3.6.2.2 Analytical Methods to Define Forcing Functions and Response Models . . . . 3.6-13 l8 3.6.2.3 Dynamic Analysis Methods to Verify Integrity . . . . . . . . . . . . . . 3.6-14a l8 3.6.2.4 Guard Pipes . . . . . . . . . . . . . 3.6-14b l8 3.6.2.5 Summary of Analyses for High Energy Fluid System Piping . . . . . . . . . 3.6-14b l8 3.6.2.6 Summary of Analyses for Moderate Energy Piping Systems . . . . . . . . 3.6-50c l 26 3.6.3 DETERMINATION OF BREAK LOCATION AND DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF NSSS PIPING . . . . 3.6-51 3.6.3.1 Criteria Used to Define Break and Crack Location and Configuration . . . 3.6-51 3.6.3.2 Analytical Methods to Define Forcing ("N () Functions and Response Models . . . . 3.6-54 3-iii Revision 29 7/80
MIDLAND 1&2-FSAR Table of Contents (continued) Section Title Page 3.6.3.3 Dynamic Analysis Methods to Verify Integrity and Operability . . . . . . 3.6-55 18 3.6.3.4 Material to Be Submitted for the Operating License Review . . . . . . . 3.6-56 References . . . . . . . . . . . . 3.6-57 l 26 3.7 SEISMIC DESIGN . . . . . . . . . . . . . . . 3.7-1 3.7.1 SEISMIC INPUT . . . . . . . . . . . . . . 3.7-1 3.7.1.1 Design Response Spectra . . . . . . . 3.7-1 3.7.1.2 Design Time-Histo,ry . . . . . . . . . 3.7-1 ! 15 I 3.7.1.3 Critical Damping Values . . . . . . . 3.7-1 3.7.1.4 Supporting Media for Seismic Category I Structures . . . . . . . . . . . . . . 3.7-2 3.7.2 SEISMIC SYSTEM ANALYSIS . . . . . . . . . 3.7-2 3.7.2.1 Seismic Analysis Methods . . . . . . . 3.7-2 3.7.2.2 Natural Frequencies and Response Loads 3.7-3 ! 33 ! 3.7.2.3 Procedure Used for Modeling . . . . . 3.7-3 3.7.2.4 Soil Structure Interaction . . . . . . 3.7-4 3.7.2.5 Development of Floor Response Spectra 3.7-5 3.7.2.6 Three Components of Earthquake Motion 3.7-5 3.7.2.7 Combination of Modal Respons,es . . . . 3.7-5 3.7.2.8 Interaction of Nonseismic Category I Structures with Seismic Category I Structures . . . . . . . . . . . . . . 3.7-5 3.7.2.9 Effects of Parameter Variations on Floor Response Spectra . . . . . . . . 3.7-6 l8 3.7.2.10 Use of Constant Vertical Static Factors . . . . . . . . . . . . . . . 3.7-6 l Revision 33 3-1v 4/81 l
MIDLAND l&2-FSAR 7-~g CHAPTER 3 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS
-TABLES Section and Number Ti tle Section 3.1 None
! Section 3.2 3.2-1 Design Criteria Summary 5.2-2 Code Requirements for Components and Quality Groups (Balance' of Plant) . 3.2-3' Major Components Design Code i
-4 General Items. Design Code
- 3.2-5 NSSS Fluid Systems' Classification and Correlation 3.2-6 Equipment Safety Classifications for NSSS Supplied.
Equipment
- O Section 3.3 3.3-1 ~ndo Wind Protected Components and Tornado atent Enclosures Section 3.4 3.4-1 Water Level (Flood) Design 3.4-2 Typical Representative . Internal Flooding Analysis 1- Results 3.4-3 Doots and Other. Penetrations on the Walls Between the Turbine Building and Auxiliary Building Below 33 Grade Level Section 3.5 i 3.5-1 Reactor Building Missile Characteristics (NSSS) ,
3.5-2 Missile Characterietics (Other Than NSSS) 3 . 5- 3 Unit 1 Damage Probability P for Seismic Category 1 8 Equipment Due to Turbine Missiles
\._ / Revision 33 3-xi 4/81 4 - - . . , . . . , - - . . . , . . . _ - . . , , - . , . , - , , . . , . , , . . . , , , . , . . . - . , . . ,. . , , , ~ .
MIDLAND 1&2-FSAR f 9 P l l THIS PAGE INTENTIONALLY LEFT BLANK i 1 Revision 33 3-xti 4/81
MIDLAND 1&2-FSAR Tables'(continued) Section and . Number ' Title 3.5-4 Compressive Strengths of. Concrete Used in Barriers-Considered'in Turbine Missile Study , 2.5-5 Missile Dimensions 3.5-6 Design Overspeed. Burst-Velocity'and' Kinetic Energy of Missiles 3.5-7 Destructive Overspeed Burst-Velocity and Kinetic Energy of Missiles 3.5-8 Unit 2 Damage Probability P4 for Seismic 133
, Category I Equipment Due' to Turbine Missiles. l8 3.5-9 Tornado - Generated Missiles Considered in Design of Seismic Category I. Structures 3.5-10 Missile Barriers foe Tornado, Accident, and Site Proximity Missiles 3.5-11 Protection of Safety-Related Equipment Located outdoors 3.5-12 Aircraft Impact Characteristics
~
3.5-13 Number of Operations and Crash Densities 3.5-14 Aircraft Crash Probability Parameters
- Annual Probabilities of Unacceptable Aircraf t 3.5-15 Impacts 3.5-16 Damage Probabilities P'and 2 P 3 for Seismic Cate- l 33 i gory I Equioment Due ta Turbine Missiles l 8.
3.5-17 Damage Probabilities P2 and P3 for Seismic Cate- l 33 i gory I Equipment Due to Turbine Missiles 0 3.5-18 Tornado Missile Barriers - Summary of Thicknesses [. and Corresponding Strengths ~ of 1 alls and Roofs of Buildings 3.5-19 Missiles Inside Containment l18 3.5-20 Thickness of Walls and Roofs Privided to > Prevent Local Structural . Damage Due . to 26
N Missiles for a Specified Concrete Compressive Strength
!' Revision 33 3-xiii 4/81 (
MIDLAND 1&2-1'SAR Tables (continued) Section and Number Title Section 3.6 3.6-1 liigh Energy Lines Insiae Containment Requiring Failure Analysis 3.6-2 liigh Energy Lines Outside Containment Requiring Failure Analysis O I 1 l l 1 Revision 26 3-xiv 1/80
MIDLAND 1&2-FSAR Tables (continued) V)
/
Section and Number Title 1 3.6-21 Reactor Coolant System Primary Piping Break Loca tions for a 177 FA Plant Consumers Power 4 Company - NSS-12 (Unit 2) i 3.6-22 RCS Limited Displacement Rupture Break Area 33 Data Section 3.7 3.7-1 Seismic Category I Structure Foundation Parameters 3.7-2 Natural Frequencies Below 33 Cycles Per Second 3.7-3 OBE Seismic Responses Section 3.8 l 3.8-1 Containment Structure Stresses and Section t Resultants l ) Loads = D+F (Initial Transfer of Prestress) 3.8-2 Containment Structure Stresses and Section-Resultants l Loads = D+F (Sustained Prestress) l i 3.8-3 Containment Structure Stresses and Section Resultants Louds = D+F+L+T (Winter) 3.8-4 Conta;nment Structure Stresses and Section Resultants Loads = D+F+L+T (Summer) 3.8-5 Containment Structure Stresses and Section Resultants l Loads - D+F+L+P+T (Winter) 3.8-6 Containment Structure Stresses and Section l Resultants Loads = D+E+L+P+T (Summer) 3.8-7 Containment Structure Stresces and Section Resultants Loads = D+F+L+P e l i f',j 5
"} 3.8-8 Centainment Structure Factor Loaded Section Resultants
-Loads - 1.05D +-F + 1.5P + T (Winter) l Revision 33 3-xv 4/81
MIDLAND 1&2-FSAR Tables (continued) O Section and Number Title 3.8-9 Containment Structure Factor Loaded Section Resultants Load = 1.05D + F + 1.5P + T (Summer) 3.8-10 Containment Structure Factor Loaded Section Resultants Load = 1.05D + F + 1.25P + T & 1.25E (Winter) 3.8-11 Containment Structure Factor Loaded Section Resultants Load = 1.05D + F + 1.25P + T + 1.25E (Summer) 3.8-12 Containment Structure Factor Loaded Section Resultants Load = 1.05D + F + T + 1.25E (Winter) 3.8-13 Containment Structure Factor Loaded Section Resultants Load = 1.05D + F + T + 1.25E (Summer) 3.8-14 Containment Structure Factor Loaded Section Resultants Load = D + F + P + T + E' (Winter) 3.8-15 Containment Structure Facter Loaded Section Resultants Load = D + F + P + T + SS (Summer) 3.8-!6 Containment Structure Factor Loaded Section Resultants Load = D + F + T + E' (Winter) 3.8-17 Containment Structure Factor Loaded Section Resultants Load = D + F + T + E' (Summer) 3.8-18 Test Frequencies for Concrete and Concrete Materials 3.8-19 Auxiliary Building Summary of Governing Design Loads and Allowable Capacity for Representative Sample of Principal Reinforced Concrete Members
. Revision 8 3-xv1 gj7g l
MIDLAND 162-FSAR Criterion 2 - DESIGN BASYS FOR PROTECTION AGAINST NATURAL THENOMENA QJ Structures, systems, and components important to safety shall be designed to withstand the effects of natural phenomer a such ae earthquakes, tornadoes, hurricanes, floods, tsunami, and seiches without loss of capability to perform their safety functions. The design bases for these structures, systems,.and components shall reflect: (1) Appropriate consideration of the most severe of the natural phenomena that have been historically reported for the site and surrounding area, with sufficient margin for the limited accuracy, quantity, and period of time in which the historical data have been accumulated, (2) appropriate. combinations of the effects of ncrmal and accident condition 3 with the effects of the natural phenomena and (3) the importance of the safety functions to be cerformed.
RESPONSE
Design bases for protection against natural phenomena are in accordance with General Design Criterion 2. Structures, systems, , and components important to safety are designed to withstand the effects of credible natural phenomena such as earthquakes, tornadoes, and floods without loss of 'the capability to perform those safety functions necessary to cope with appropriate combinations of natural phenomena and plant conditions. The natural phenomena and their magnitude are selected in accordance with their probability of occurrence at this specific site. The (-)g designs are based upon the most severe of the natural phenomena recorded for the site, with an appropriate margin to account for uncertainties in the historical data. The natural phenomena postulated in the design are presented in Sections 2.3, 2.4, and
- 2. 5. The design criteria for the structures, systems, and components aff ected by each natural phenomenon are presented in Sections 3.2, 3.3, 3.4, 3.5, 3.7, and 3.8. Those combinations of natural phenomena and plant-originated accidents that are considered in the design are identified in Sections 3.8, 3. 9, 3.10, and 3.11.
i f*
-- l 3.1-3 1
MIDLAND 1&2-FSAR Criterion 3 - FIRE PROTECTION Structures, systems, and components important to safety shall be d1 igned and located to minimize, consistent with other safety rcquirements, the probability and effect of fires and explosions. Noncombustible and heat resistant materials shall be used wharcver practical throughout the unit, particularly in locations such as the containment and control room. Fire detection and fighting systems of appropriate capacity and capability shall be provided and designed to minimize the adverse effects of fires on etructures, systems, and components important to safety. FirOfighting systems shall be designed to assure that their rupture or inadvertent operation does not significantly impair the safety c apability of these structures, systems, and components.
RESPONSE
StrLetures, systems, and components important to safety are da:;igned to meet the requirements of General Design Criterion 3. Fire protection systems meeting the requirements of General 33 Design Criterion 3 are provided. The plant is designed to minimize the probability and effect of fires. Noncombus tible and fire-re tardant materials are used in the containment, control room, components of safety features cystems, and throughout the unit wherever practicable-to reduce fire potential. Equipment and facilities for fire protection, including detection, alarm, and extinguishment, are provided to protect both plant equipment and personnel from fire and the racultant release of toxic vapors. Both automatic and manual types of firefighting equipme ; are provided. Fire protection is provided by automatic deluge, sprinkler, and carbon dioxide systems, standpipe system, and portable 25 extinguishers, as appropriate to location and type of equipment. Firefighting systems are designed to assure that their rupture or inndvertent operation will not significantly impair systems important to safety. The fire protection system is provided with test valves and facilities for periodic te s t ing . All equipment is accessible for periodic inspection. Tha fire protection system is described in Appendix 9A. l33 3.1-4 0 Revision 33 4/81
MIDLAND 162-FSAR Criterion. 4 - ENVIRONMENTAL AND MIST}ILE DESIGN BASES () Structures, systems, and components important to safety shall be designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant accidente. These structures, systems, and components shall be appropriately protected against dynamic effects, including the effects of missiles, pipe whipping, and discharging fluids, that may result from equipment failures and from events and cenditions outside the nuclear power unit. R ES PONSE Environmental and missile design bases are in accordance with General Design Criterion 4. . Structures, systems, and components important to safety are designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including less-of-coolant accidents, assuming that non-related cataclysmic events do not occur simultanecusly. These structures, systems, and components are appropriately protected against dynamic effects, including the effects of missiles, pipe whipping, and discharging fluids, that may resu? from equipment failures or from postulated events occurring inside or outside the nuclear power unit. Discussion of dynamic effects associated with the postulated O rupture of piping is contained in Section 3.6. Missile protection is discussed in Section 3.5. Reactor coolant pump integrity is discussed in Subsection 5.4.1. Section 3.11 l33 contains a discussion of design environmental conditions. Flood level is discussed in dubsection 2.4.2 and flood protection is di scussed in Subsection 3.4.2. i i !O #*l~b Revision 33
- 4/81
MIDLAND 162-FSAR Criterion 5 - SHAHING OF STRUCTURES, SYSTEMS, A12) COMPONENTS Structures, systems, and components important to safety shall not be shared among nuclear power units unless it can be shown that cuch sharing will not significantly impair their ability to perform ' heir safety functions, including, in the event.of an cccident in one unit, an orderly shutdown and cooldown of the remaining units.
RESPONSE
Structures, systems, and components are shared only to the extent t! at such sharing does not affect the safecy-related capabilities of the system or component to perform adequately in the separate reactor facilities. Shared structures, systems, and components (including related power and instrumentation systems) are as follows:
- a. Fuel pool and fuel pool cooling system (Section 9.1)
- b. Service water system (Subsection 9.2.1)
- c. Building heating, cooling, and ventilating systems (Section 9.4)
- d. Plant heating (Subsection 9.4.11)
- e. Fire protection system (Subsection 9.5.1)
- f. Makeup demineralizer system, demineralizer water storage and transfer system (subsection 9.2.3)
- g. Cooling water pond and service water pump structure (Subsection 10. 4. 5)
- h. Parts of the chilled water system associated with the other systems described here (Subsection 9.2.9)
- 1. Domestic water
- j. Parts of the component cooling water system associated with the waste gas and liquid radwaste systems 27
- k. Primary makeup water system
- 1. Auxiliary building, administration building, control room, laboratories, turbine building, diesel generator building, rolid radwaste building, oily water treatment building, evaporator and auxiliary boiler building, combination shop building (Sections 1.2 and 3.8)
- m. Radioactive waste treatment system (Chapter 11)
- n. Instrument and service air system (Subsection 9. 3.1) 3.1-6 Revision 27 O
3/80
l i i ! MIDIAND 162-FSAR l 1 I instrumentation. Axial, radial, or azimuthal neutron flux ! changes will be detected by the nuclear instrumentation. O Individual control rods or groaps of . control rods can be positioned to suppress and/or correct flux changes. ' Instrumentation and controls are discussed in chapter 7. I l O l O 3.1-11
MIDLAND 162-FSAR Criterion 13 - INSTRUMENTATION AND CONTROL . , , Instrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions cs appropriate to assure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment and its associated systems. Appropriate controls shall be provided to maintain these variables and systems within prescribed operating ranges. RijPONSE Instrumentation has besn provided to monitor variables and cystems over their anticipated range for normal operatica, for cnticipated operational occurrencee, and for accident conditions cc appropriate to ensure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment and its associated systems. Appropriate controls have been provided to maintain these variables and systems within prescribed operating ranges. Adequate instrumentation and controls are provided to maintain operating variables within prescribed ranges for normal operation cnd to monitor accident conditions as appropriate to ensure cdequate safety. NSS9 instrumentation systems include the nuclear instrumentation cystem, which monitors the neutron flux level from the source rcnge to 125% of rated power; the nonnuclear process instrumentation, which measures temperatures, pressures, flows, tnd levels in the reactor coolant system, steam system, and rcactor auxiliary systems; and the incere instrumentation system, which measures neutron flux at specific locations within the reactor core. Instrumentation is provided for monitoring containment pressure cnd airborne radiation and hydrogen concentrations during normal operation and accident conditions. The containment sump water level is also monitored..
- a. Protection Systems The protection systems, which consist of the reactor protection system and the engineered safety features actuation system, perform the most important safety functions. The protection systems extend from the process sensing instruments to the final actuating devices, such as circuit breakers and pump or valve motor contactors (see response to General Design 33 Criterion 20).
O 3.1-12 Revision 33 4/81
MIDLAND 162-FSAR Critorion 15 - REACTOR COOLANT SYSTEM DESIGN (,s) The reactor coolant system and associated auxiliary, control, and protection systems shall be designed with sufficient margin co assure that the design conditions of the reactor coolant pressure boundary are not exceeded during any condition of normal operation, including anticipated operational occurrences.
RESPONSE
The reactor coolant system (RCS) and associated auxiliary, control, and protection systems have been designed with suf ficient ' margin to ensure that the design conditions of the reactor coolant pressure boundary are not exceeded during any condition of normal operation, including anticipated abnormal operational occurrences. 33 An analysis and evaluation of all normal and abnormal operating
- conditions and transients is integrally related to all RCS and I associated systems design. For all anticipated transients, plots of critical variables (e.g. , temperature and pressure) are generated for critical components. Also, for each transient, the number of lifetime cycles is determined. All of the results of these analyses are invoked as functional requirements on the detailed design of the affected systems. Margins for uncertainties are included in 1) the basic analysis assumptions,
- 2) the assessment of lifetime cycles, and 3) the code-dictated procedures for stress analysis.
7-s
-- The reactor coolant system is discussed in Chapter S.
D l (v 3.1-15 Revision 33 4/81
MIDLAND 162-FSAR Criterion 16 - CONTAINMENT DESIGN Reactor containment and associated systems shall be provided to establish an essentially leaktight barrier against the uncontrolled release of radioactivity to the environment and to assure that the containment design conditions important to safety are not exceeded for as long as postulated accident conditions require. R ES PONS E - The containment and associated systems are designed to meet the requirements of General Design Criterion 16. The containment and associated systems are provided to establish an essentially leaktight barrier against uncontrolled release of radioactivity to the environment. The containment and associated systems assure that containment design conditions important to safety are not exceeded for as long as postulated accident conditions require. The containment structure encloses the entire reactor coolant system. It is designed to sustain, without loss of required
' integrity, all eff ects of gross equipment failures, up to and including the worst of a spectrum of loss-of-coolant accidents, and secondary sfstem breaks, coupled with a partial loss of the redundant safety features systems (minimum safety features) for the duration of each postulated accident. Engineered safety faatures, consisting of the emergency core cooling system, containment spray system, and the containment emergency cooling system, then serve to cool the reactor core and return the containment to near atmospheric pressure. The reactor containment structure and engineered safety features systems are designed to assure the required functional capability of containing any uncontrolled release of radioactivity.
Containment systems are discussed in Section 6.2. l l 1 3.1-16 0 l
MIDLP.ND 157-FSAR channels may be evaluated without disrupting overall plant operation. l l I l l l l i I i 3.1-25 1
MIDLAND 152-FSAR _ Criterion 22 - PROTECTION SYSTEM INDEPENDENCE The protection system shall be designed to assure that the I Cffects of natural phenomena, and of normal operating, maintenance, testing, and postulated accident conditions on redundant channels do not result in loss of the protection function, or shall be demonstrated to be acceptable on some other defined basis. Design techniques, such as functional diversity or diversity in component design and principles of operation, shall be used to the extent practical to prevent loss of the protection function. R ES PONS E - The protection systems have been designed to ensure that the offects of natural phenoment and of normal operating, maintenance, testing, and postulated accident conditions on redundant channels do not result in loss of the protection function. Design techniques, such as functional diversity, have been used to the extent practicable to prevent loss of the protection function. The protection systems are designed so that no loss of function will occur under normal and accident conditions. Qualification testing has been performed to ensure that the systems will be completely operable under all postulated conditions. Other design features incorporated into the protection systems cfford added reliability. There is complete independence between redundant portions of the systems, except for some NSSS and steam generator redundant sensors which may share common censor-to procese connections. In such cases, the sensing lines cre separated after leaving the sensor-to-process connection and are protected against damage that cculd result from a credible cause. Apart from these exceptions, there is not only electrical independence, but physical independence as well. Redundant portions of different channels (cabling, modules, sensors, etc) are physically separated. Each channel is entirely self-contained with its own power supply so that internal spreading l33 of fire will not disrupt more than one channel. The testing and maintenance features incorporated into the systems enable the technician to test each channel independently. He can also perform maintenance on a single channel without disrup-ting system operation. Functional diversity is employed in the reactor protection system (RPS) design to the cxtent required by IEEE Std 279-1971. The cngineered safety features actuation system (ESFAS) employs functional diversity for initiation of several ESEAS subsystems, including MSLIS, AFWAS, ECCAS, and.CRIS, by utilizing diverse trip parameters. The owner-supplied ESFAS subsystems comply with IEEE Std ;79-1971 and the ECCAS complies with IEEE Std 279-1971. Both the BPS and the ESFAS are fully discussed in Chapter 7. 3.1-26 O Revision 33 4/81
MIDLAND l&2-FSAR 4 Criterion 27 - COMBINED REACTIVITY CONTROL SYSTEMS CAPABILITY' i P( 'T x_/ The reactivity control systems shall be designed to have a combined capability, in conjunction with poison addition'by the , emergency core cooling system, of reliably controlling reactivity changes to assure that under postulated accident conditions and j with appropriate margin for stuck rods the capability to cool the core is maintained.
; RESPONSE The reactivity control. systems have been designed to have a combined capability, using control rods in conjunction with' ; soluble poison (boron) addition-by the emergency core cooling
- system, of reliably controlling reactivity. changes to ensure that, under postulated accident conditions and with appropriate margin for stuck rods, the capability to cool the core is maintained.
The reactivity control system consists of'ccr. trol rods and soluble boron addition. The reactor is designed so that the fully inserted control rods will provide a shutdown margin of at least 1% Ak/k with the single most reactive control rod fully 1 withdrawn. i The borated water storage tank (BWST) provides the source of injection water for the emergency core cooling systems. The borated water in the BWST is maintained at a minimum boron concentration of 2,270 ppm. When injected into the reactor coolant system, this borated water can maintain subcritical teactor conditions. - If the control rod with the greatest reactivity worth is stuck 33 out, the safety grade emergency boration system provides 6 weight percent boric acid to the reactor coolant system (RCS) following a design basis tornado or a safe shutdown earthquake with loss of offsite' power. The boric acid from the EBS, in 30 conjunction with borated water from either the chemical addition system or the borated water storage tank makeup system will provide enough boron to the RCS, without letdown, to maintain the reactor at the minimum 1% Ak/k subcritical condition during hot 33 shutdown and to achieve cold shutdown. Controls for the control rods are discussed in Chapter 7. Boron addition is discussed in Subsection 9.3,4. l33 I i i O 3.1-31 Hevision 33 4/81
MIDLAND 162-FSAR Criterion 28 - REACTIVITY LIMITS The reactivity control systems shall be designed with appropriate limits on the potential amount and rate of reactivity increase to lh casure that the effects of postulated reactivity accidents can neither (1) result in damage to the reactor coolant pressure boundary greater than limited local yielding nor (2) sufficiently disturb the core, its support structures or other reactor pressure vessel internals to impair significantly the capability to cool the core. These postulated reactivity accidents shall include consideration of rod ejection (unless prevented by positive means) , rod dropout, steam line rupture, changes in reactor coolant temperature and pressure, and cold water cddition. R ES PONS E The reactivity control systems have been designed with appropriate limits on the potential amount and rate of reactivity increase to ensure that the effects of postulated reactivity cccidents can neither result in damage to the reactor coolant pressure boundary greater than limited local yielding nor suf ficiently disturb the core, its support structures, or other reactor pressure vessel internals to impair significantly the capability to cool the core. These postulated reactivity accidents include consideration of rod ejection, steam line rupture, changas in reactor coolant (RC) temperature and pressure, and cold water addition. The reactor design meets this criterion with safety features that limit the maximum reactivity insertion rate. These include rod group withdrawal interlock, soluble boron concentration reduction interlock, maximum rate of dilution water addition, and dilution time cutoff. In addition, the rod drives and their controls have on inherent feature that limits overspeed in the event of malfunctions. Ejection of the control rod of maximum worth will not lead to coolant boundary rupture or to internal damage that would interfere with emergency Core cooling. Provisions have been included to isolate a ruptured steam line in a time and manner ensuring that the core will remain intact for ef fective core cooling. The reactor system has been designed to avoid any postulated reactivity accidents that would result in a reactor coolant temperature or pressure change of sufficient magnitude to damage the reactor coolant pressure boundary. The design of the RC syst1m ensures that no credible addition of cold water to the core would Oamage the system. The reactor system is discussed in Chapter 5, and controls are l 27 discussed in Chapter 7. Accident conditions are evaluated in Chapter 15. 3.1-32 Revision 27 3/80
. - . . _ _ - _ - - - - = - - - ,
MIDIAND 182-FSAR boundary during all modes of normal reactor operation by O two valves, each of which 'ils either normally closed or capable of automatic closure. safety class 4 - is applied to water and steam-containing components not part of the reactor coolant pressure boundary nor included in Safety classes 1, 2, or 3 but part of the systems or portions of systems that contazn or may contain radioactive material.. 3.2.2.2.2 Program II - Electrical Systems Classification safety class 1 - applies to electrical,, instrumentation,-and. control systems or portions of systems which must function to: '!
- a. Provide a protection system function j b. Initiate, monitor, and control cquipment required to 2
place the reactor in a safe shutdown condition and
- maintain the safe shutdowa conditicn i c. Initiate, monitor, and centrol equipment required to 4
prevent release of radioactivity in excess of.the , guideline exposure of 10 CFR.100, during normal or abnormal conditions
- d. Initiate, monitor, and control equipment required to O- compensate for an abnormal condition
- e. Prevent unwanted operation of equipment which could allow an abnorm 91 condition to occur, which could not be compensated for.by operation of other systems or portions of systems
) safety class 2 - applies to all systems which are not Safety class 1. i , 3.2.2.2.3 Program III - Mechanical Equipment Classification Mechanical equipment is defined as that which provides a physical i support, foundation, restraint, or barrier and can be integral or nonintegral with fluid or electrical equipment. Mechanical equipment is also defined as that which provides a required ancillary function to fluid or electrical equipment. For purposes of this classification method, mechanical equipment
, is separate from electrical and fluid systems and is not included in the fluid or electrical systems classifications.-
safety class 1 - shall be applied to mechanical equipment whose f ailure to function properly or to retain integrity' could result
- o 3.2-7 4
i 4 L
MIDLAND 1&2-FSAR in failure to adequately complete a safety function. Mechanical cquipment in Safety Class 1 is that which serves to provide:
- a. Support or restraint for nuclear fuel within the reactor vessel
- b. Critical functions in the support and handling of nuclear fuel outside the reactor vessel
- c. Complementary functions for mechanical or electrical equipment to permit such equipment to execute its safety function Safety class 2 - shall be applied to mechanical equipment not in Safety Class 1, and therefore applies to mechanical equipment whose failure could not result in failure to adegaately complete a safety function.
3 2.2.2.4 Program IV - Core Components Classification Regulatory Guide 1.26, Quality Group Classifications and Utandards, states in part that group B standards should be cpplied to systems or portions of systems that are required for reactor shutdown and residual heat removal. This Regulatory Guide also states that components of the reactor coolant pressure boundary be assigned to quality group A. See Appendix 3A for a 33 discussion of conformance to Regulatory Guide 1.26. Since Regulstory Guide 1.26 addr3sses quality standards based on the importance of an item to safety only, this principle has been utilized to define the safety classifications for core l 12 components. tafety Class 1 - since the core and core components are not part l 12 of the reactor coolant precsure boundary, no core component shall be classified as a safety-related fluid system. Safety class 2 - shall be applied to those components whose l 12 intended safety function is as follows:
- a. To provide the capability to shut down the reactor and maintain it in a safe shutdown condition
- b. To allow the removal of residual heat
- c. Required for.the proper function of items a and b above Safety Class 3 - shall be applied to assemblies, subassemblies, l 12 components, or parts that do not perform or support a safety function.
Table 3.2-5 defines the correlation of safety classes, seismic categories, and code application for fluid system componentc. 3.2-8 Revision 33 4/81
1 MIPLAND 1&2-FSAR TABLE 3.2 DESIGN CRITERIA
SUMMARY
lu Design FSAR Quality Code / Seismic System / Component Section Location Group Standard Category SEISMIC CATEGORY I STRUCTURES Concrete 3.8.1 Containment I Containment C NA ACI-318:23 1 30 building . AWS Dl.1 Crane supports C NA ACI-318t2: I AISC AWS Dl.1 Liner plate C NA ACI-3182i I
, AISC AWS Dl.1 Penetration sleeve C NA ACI-37.812: I Personnel lock, C NA ACI-31882 I emergency airlock, AISC equipment hatch ASME 30 Containment 3.8.3 Internal Structures l
NSSS supports C NA ACI-318:2i I AISC AWS Dl.1 Other internal C NA ACI-318(2) I structures AISC AWS D1.1 Auxiliary 3.8.4 A NA ACI-318:23 I Building AISC AWS D1.1 Diesel Generator 3.8.4 G NA ACI-313(2i y Building AISC AWS D1.1 ( (sheet 1)
- Revision 30
! 10/80 1
?
- - - - , . - . - . . . , , . , - . . . , , . . . , , , - - , ..,,.a - . - , , - --.----,-,..-r - .. , , - - . .- --
!!IDLAND 1&2-FSAR TABLE 3.2-1 (continued)
Design FSAR Quality Code / Seismic System / Component Section Location Group Standard Category S7rvice Water 3.8.4 W, U NA ACI-318:21 y l Pump Structure, AISC R7ta.(ning Walls, NeiS Dl.1 Volve Pits, and Metering Pits S7rvice Water HA W NA AWWA I Sluice Gates C-501-57 30 Foundations for NA U NA ACI-318 I Control Room AISC Pressurization AWS Dl.1 Tanks Foundations for NA U NA ACI-318 I , Pcnetration AISC Pressurization AWS Dl.1 Trnks Foundations for 3.8.4 O NA ACI-318 t2 I Borated Water AISC Storage Tank AWS Dl.1 13 (sheet 2) Revision 33 4/81
MIDLAND 1&2-FSAR
-s TABLE 3.2-1 (continued) q,,)
- Design FSAR Quality Code / Seismic 4 System / Con.ponent - Section Location Group Standard Category Pressurizer 5.4.10 Vessel C (7) III-A I Spray nozzle C (7) NA NA ,
Manway gaskets C (73 III-A I
.0 Heater bundle 5.4.10 C (7) III-A I pressure retaining portion 8.
Pressurizer 5.4.11 Relief Discharge System 1 Pressurizer C D VIII NA quench tank Piping arrd valves Pressurizer to C A III-i I discharge valve Discharge valve C C III-3 I to seismic ess anchor and relief n) valves to seismic ancaor Seismic anchor C D B31.1 NA to quench tank Reactor Coolant 5.4.12 System Valves BOP C A III-l I Spray control 5.4.13 C (73 III-1 I valve Safety valve 5.4.13 C (73 III-l I 33 Electrical C (73 III-l I : actuation relief valve i (sheet 7) Revision 33 4/81 4
- , , , - - - . - - - ,,w-., - ,. .--, --.,--,.w,- ,-,.r , . - , ..n,..~e- ,, . . . . , . , - , - , . . - , - , , - --.n , -. , ,
MIDLAND 1&2-FSAR TABLE 3.2-1 (continued) Design h FSAR Quality Code / Seismic System / Component Section Location Group Standard Category ENGINEERED SAFETY FEATURES R^ actor Building 6.2.2.1 Spray System Spray pumps A B III-2 I 13 Spray pump A NA NEMA MG-1 I motorc Piping Spray header C B III-2 I Other 0,C,A B III-2 I l 13 Spray nozzles C NA NA NA I 30 vclves Motor operated A B III-2 I Other A,C B III-2 I Tcnks 13 Hydrazine A B III-2 I Borated water 0 B III-2 I storage III-2 l 30 Recirculating Air 6.2.2.2 Cooling Units Motors C C IEEE-323/ I l 30 334/344 Fcns C C AMCA I Cooling coils C C III-3 I l 1 l Combustible Gas 6.2.5 Control l Hydrogen C NA IEEE-323/344 I l 30 l recombiners Motors A NA NEMA MG-1 NA Fand A NA AMCA NA D; misters A NA MSAR-71-45 NA '
"O '
Electric heater A NA NEC, UL NA HEPA filter A NA HSI-306 NA Ccrbon adsorber A NA CS-8T NA Ductwork A NA SMACNA NA Dampers A NA ANSI N509 NA l 30 (sheet 8) Revision 30 10/80
MIDLAND 1&2-FSAR TABLE 3.2-1 (continued) O
\ /
Design FSAR Quality Code / Seismic System / Component Section Location Group Standard Category AUXILIARY SYSTEMS - AIR CONDITIONING, HEATING, COOLING AND VENTILATION SYSTEMS 4 Control Room Area 9.4.1 Ventilation System Control Room IIVAC System , Supply and
, recirculation Motors A NA IEEE-344 I FansN A NA NA I Cooling coils A C III-3 I Heating coils A NA NA I Ductwork A NA SMACNA I i
Dampers A NA ANSI N509 I 30 Damper A NA IEEE*>323/ I actuators 344/383/ 384 Isolation damp- A NA IEEE-323/ I er actuators 344/382 Filtration Motors A NA IEEE-323/ I l 30 334/344 Fans A NA AMCA I Prefilters A NA UL Class 1 I HEPA filters A NA HSI-306, I MIL-F-59068D Carbon adsorber A NA CS-8T I Elect.ric heater A NA IEEE-344/323 I Ductwork A NA SMACNA I 30 Dampers A NA ANSI N509 I Damper A NA IEEE-323/ I actuators 344/383/ 384 Normal smoke exhaust' Motors A NA NEMA MG-1 NA Fans A NA AMCA NA Ductwork A NA SMACNA NA Dampers A NA ANSI N509 NA l 30 (sheet 25) Q Revision 33 4/81 l l . - - . . _ . . .-- . , -. . . . . . - . - . - . .-
MIDLAND 1&2-FSAR TABLE 3.2-1 (continued) Design FSAR Quality Code / Seismic System / Component Section Lc ation Group, Standard Catecory Pressurization system Tank U C III-3 I Piping and valves U,A C III-3 I Switchgear and B".ttery Room HVAC System Exhaust system Motors A NA IEEE-323/ I 334/344 Exhaust fans A NA A!!CA I Ductwork A NA SMACNA I Dampers A NA ANSI N509 I 30 Iaolation damp- A NA IEEE-323/ I er actuators 344/382 Exhaust damper A NA IEEE-323/ I actuators 344/383/ 384 Unit coolers Motors A NA IEEE-344 I Fanem A NA NA I Cooling coils A C III-3 I Ductwork A NA SMACNA I 30 Dampers A NA ANSI N509 I Cable Spreadirig Room Supply and Exhaust System 30 Supply I 30 Ductwork A NA SMACNA NA Exhaust Motor A NA IEEE-334 NA l 30 Fans A NA AMCA NA Ductwork A NA SMACNA NA Dampers A NA ANSI N509 NA l 30 (sheet 26) Revision 30 10/80
4 l' MIDLAND l&2-FSAR I _ TABLE 3.2-1 (continued) De' sign l~ FSAR Quality _ Code / Seismic
- System / Component. Section Location Group Standard. Category STEAM AND POWER CONVERSION SYSTEM l
i Turbine-Generator 10.2 T NA NA 51 NA ! Main Steam 10.3 l System 1 i Piping I' Penetration (SG C/O B- III-2 I to isolation l valves) l To auxiliary.FW A C III-3 I pump turbine' (downstream of penetration) 4- Turbine bypass T D .B31.1 NA (condenser and atmos- 30
, pheric dump)
Other T D B31.1 NA Valves Main steam O B III-2 I 1 isolation {' SG safety and O B III-2 I dump Turbine bypass T D B31.1 -NA { (condenser and atmos-l pneric dump valves) 30 Atmospheric. O B III-2 I power opera-i- ted vent valves Other T,0 0 B31.1 NA 4 Main Condenser 10.4.1 T D HEI~ NA (sheet 37)
- Revision 30
; 10/80 i
i 4
, ~ - . . . - . ~ . ,_.-_.,._._._.,,.-._-._-,__._.--.._,.___,..,,_,..,,r,-,._..,_.,,..._,_,_._...,_- _ . ~ , - , . , . . , , _ ,
MIDLAND 1&2-FSAR TABLE 3. 2 -1 (continued) Design FSAR Quality Code / Seismic System / Component Section Location Group Standard Category Condenser Evacu- 10.4.2 ntion System Piping and vaaves T D B31.1 NA Air ejector con- T D HEI NA densers Air ejectors T D HEI HA Turbine Gland 10.4.3 5ealing System Piping and valves T D B31.1 UA Steam packing T D IIEI NA exhauste r Slower T D ASilRAE NA Turbine Bypass 10.4.4 System Piping and valves Condenser dump T m NA I Atmospheric dump O D B31.1 NA Power operated O B III-2 I 30 atmospheric vent Other T D B31.1 NA Circulating Water 10.4.5 System Pumps X D HI NA Piping U D AWWA C201-66 NA Valves X D AWWA C504-70 NA Vacuum pumps T D HI NA 3a, Vacuum tanks T U ASME VIII NA Traveling screens X D NA NA (sheet 38) Revision 33 , 4/81
MIDLAND 1&2-FSAR TABLE 3.2-1 (continued) Design FSAR Quality . Code / Seismic System / Component Section Locacion Group Standard Category Condensate 10.4.6 Deminera lizer -l System Regeneration T D VIII NA tanks Pumps T D HI NA Piping and valves T D B31.1 NA Condensate and 10.4.7 Feedwater Sistem Main feedwater T D HI NA pump and driver Feedwater booster T D HI NA pump and driver Condensato pump T' D HI NA and driver SG recirculation C D B31.1 NA' l9 pump Piping Penetration C B III-2 I SG recirculation C B/D III-2/B31.1 I/NA l9 Other T D B31.'l NA Valves SG recirculation C B/D III-2/B31.1 I/NA l9 Containment C B III-2 'I isolation Other. T D B31.1 NA Feedwater heateru T t4A HEI,VIII HA Deaerator storage T NA HEI,VIII .NA { tank i l Auxiliary Feed- 10.4.9 , water System Turb 3 driven A C III-3 I l auxiliary PW ! pump Motor drivea A C III-3 I l auxiliary FW i pump Auxiliary FW A NA NA .I pump turbine b (sneet 39) l \ Revision 33 4/81 l
MIDuAND 1&2-FSAR TABLE 3.2-1 (continued) Design h FSAR Quality Code / Seismic System / Component Section Location Group Standard Category Auxiliary FW A NA f.EEE-323/344 I l 3v pump motor Piping and valves To penetration A C III-3 I Penetration to C D III-2 I stuam generator Process Steam 10.4.10 Evaporator System Lou- and high-pres- E D VIII NA sure evaporators TEMA-C Low- and high-pres- E D VIII NA sure heaters TEMA-C Low- and high-pres- E D VIII NA sure b3 owdown TEMA-R coolers Deae ra to rs E NA VIII NA Low- and high- E NA HI NA pressure evaporator feed pumps Vacuum pumps E NA liI NA Storage tanks O NA VIII NA Low- and high- E D VIII NA pressure drain tanks Cooling Pond 10.4.11 Blowdown and Makeup System Pumps I D 11 1 NA Piping and valves 0,X,Y D B31.1 NA AWWA C-301 l Feedwater 10.4.12 Chemical Addition System Ammonium hydro- T D VIII NA xide storage tank (sheet 40) ' Revision 33 4/81
MIDLANit ,1& 2-FSAR TABLE 3.2-1 (continued)
' \ Design
[/
\~ e FSAR Quality Code / Seismic-i System / Component Section : Location Group . Standard Category l Ammo".ium hydrox- T D VIIX NA >
ide and hydrazine j .. mix tanks Pumps T D HI ' t04 Pump. r Jtors T -NA NEMA MG-1 NA i i i Auxiliary .. team 10.4.13 Boiler System Auxiliary boilers T D ABMA - 104 1 NFPA Piping and valves T D B31.1 NA , Fans T D AMCA- NA I 4 ll d 1 1 I 1 0 t d t i f l i i (sheet 41) !\ Revision 33
'4/81 l
4 e m . mw, rwww-- es-rs v -w.newsw w w-,e-w ,~ s e r-ms w- s -, - e w- + w wee a-t-o wws,n wo--vv-wv m ew w w- ww- esw n m e,, ww---wn,- --
- w. + m s v eve -w - e - -r--
m MIDLAND 1&2-FSAR TABLE 3.2-1 (continued) Design FSAR Quality Code / Seismic System / Component Section Location Group Standard Category RADIOACTIVE WASTE MANAGEMENT Liquid Waste 11.2 Managenent System LWS pumps A D HI NA LWS filters A D III-3 NA LWS drain tanks A D VIII NA LWS conc monitor A D VIII NA tanks Laundry drain A D VIII NA tanks LWS receiver A D API-650 NA tanks LWS monitor A D API-650 NA tarus Chemical waste A 9 VIII NA receiver tanks LWS evaporator A D VIII NA LWS demineralizers A D VIII NA Piping and valves A,T D B31.1 NA Gaseous Waste 11.3 Management System Radwaste gas surge A C III-3 I I tank l Radwaste gas decay A C III-3 I tanks Radwaste gas com- A D VIII NA l ! compressor, after- HI coolers, and moisture separators
' heet 42)
F, vision 30 10/80
MIDLAND 1&2-FSAO .
'IN - TABLE 3.2-1 (continued) \j UllC : Uniform Building Code UL:' Underwriters' Laboratories Seismic Category I: Construction in c cordance with seismic requirements'of' Regulatory Guide 1.29 and Appendix A to 10 CFR 100 NA: Not Seismic Category I anSee referenced FSAR section for ' additional codes and standards applicable to these structures.
(MThese components and associated supportiag structures must be designed to retain structural integrity during and af ter a Seismic Category I event but do not have to retain operability for protection of public safety. . The design basis requirement is prevention of struct;.ral collapse and damage to equipment and structures required for protection of the public safety. WFor other applicable codes and standards see 'Section 7.1 and referenced FSAR sections. " (5? Air handling unit fans and unit cooler fans are not rated in accordance with AMCA. The entire unit is rated in accordance with ARI. MRefer to Subsection 10.2.1.3 for further discussion of turbine-generator codes and standards, i (DRefer to Table 3.2-6 l 30
- is)See Response to Regulatory Guide 1.143 in Appendix 3A. l 33 4
SThe engine-mounted fuel and cooling water lines are composed i of either ASTM A 53 or A 106,' Grade A seamless steel pipe. 27 For pipe sections to be bent or formed, ASTM A 106 Grade B is used, with the compatible 106 Grade A pipe. 4 t (sheet 49) (' ') Revision 33 4/81
MIDLAND.1&2-PSAR 3.3 WIND AND TORNADO LOADINGS 3.3.1 WIND LOADINGS This section describes the calculation of design wind loadings used for Seismic Category I structures and the techniques used to develop these loadings. 3.3.1.1 Design Wind Velocity A design wind velocity of 85 mph at 30 feet above grade is used for the design of Seismic Category I structures. As described in Subsection 2.3.1.2.8, this velocity is more conservative than l33 wind velocities (historically) observed near the plant site. This velocity also agrees with Figure 1(b) of.the ASCE Paper 3269.8" This design wind velocity is considered to have a 100 year recurrence interval. Factors of 1.1 for pressure and 1.0S for 32 velocity are used in conjunction with the design wind velocity for all Seismic Category I structures. The variation of design wino velocity with height from grade is in accordance with Table 1(a) of ASCE Paper 3269 for a basic wind velocity of. 85 mph. 3.3.1.2 Datermination of Applied Forces
> n/
s-The procedures used to calculate applied static forces for use in design are in accordance with ASCE Paper 3269. These procedures specify the calculation of a dynamic pressure. This pressure is calculated by use of Equation 6 of ASCE Paper 3269. In addition, these procedures specify the use of wind pressure coefficients, which modify the dynamic prassure, that~are a function of i building geometry in order to determine a design pressure distribution. The wind pressure coefficients used are those specified in ASCE Paper 3269 for the most severe case of building orientation with respect to wind direction and for the j appropriate building geometry. l In any case, the windward and leeward wind pressure-coefficients [ total at least 1.3. The design sind loadings for each Seismic Category I structure are shown in Figure 3.3-1. 3.3.2 TORNADO LOADINGS This section describes the calculation of design loadings due to the design basis tornado (DBT) for the structures, systems, and ccmponents listed in Table 3.3-1. These structures, systems, and components are hereafter called " safety-related structures" in this section. I (3
\~ l 3.3-1 hevision 33 4/81 i
.. .. - , , . . . . , _ _ , . - . , , . , c.. . _ . - ., ,. , ,. ,
MIDLAND 1&2-FSAR 3.3.2.1 Applicable Design Parameters The properties of the DBT are given to be:
- a. A maximum wind speed of 360 mph
- b. A maximum rotational speed of 290 mph
- c. A translational speed range of from 5 to 70 mph
- d. A radius of maximum rotational speed of 150 feet from the center of rotation
- e. A preesure drop of 3 psi at a rate of 2 psi /s followed 3 by a pressure rise of 3 psi at a rate of 2 psi /s In lieu of items a through d above, safety-related structures other than the containment are subjected to a uniform wind velocity of 360 mph, as accepted for the construction permit.
The bases for these parameters are given in Subsection 2.3.1.2.6. Compliance with Regulatory Guide 1.76 is discussed in Appendix 3A. The plant is located in Region I. The postulated missiles associated with the DBT, their maximum velocities, and their zones of strike capabilities are given in Subsection 3.5.1.4. 3.3.2.2 Determination of Forces on Structures The procedures used to calculate applied static forces for use in design from the DBT wind velocities are in accordance with Sections 3.5 and 3.6 of BC-TOP-3-A.m These sections of BC-COP-3-A also address shape coef ficients (wind pressure coefficients) and the pressure distribution on flat surfaces and round structures. The design loadings due to the DBT wind for each safety-related structure are shown in Figure 3.3-2. Venting calculations are being performed in accordance with Section 4.6 of BC-TOP-3-A.m All compartments housing 32 safety-related systems and components will be designed to withstand a differential pressure of at least the pressure indicated by the venting analysis. The procedures used to protect safety-related structures against tornado generated missile impact loadings are described in Subsection 3.5.3. The calculated DBT wind loading, differential pressure ' loading, and missile loadings are combined in accordance with Section 3.4 of BC-TOP-3-A in order to develop the total tornado loading that produces the most adverse effect on Revision 32 O 3.3-2 1/81
MIDLAND 1&2-FSAR A waterproof membrane is provided on the exterior building (} (_,/ surf aces up to elevation 632.0 for the auxiliary building and containments. The amount of water that could seep through the exterior concrete walls above elevation 632.0 is insignificant because of low external hydrostatic pressure and because the duration of water levels above elevation 632.0 is less than i day. Removable watertight barriers are used as a means of flood protection for areas af fected by water f rom overtopping flow generated by wind-wave action. These areas are identified in Figure 3.4-1. These barriers are lightweight, watertight, and 20 approximately 2 feet high. These will be located in the vicinity of the areas to be protected and will be readily accessible. Details of these removable flood barriers arc provided in 1 22 Figure'3.4-2.. I i Subsection 2.4.10 refers to the procedures for installing i 20 removable flood protection barriers. 22 Figure 3.4-1 shows protection type and location along with building identification. 3.4.1.3 Analysis Procedures for External Flooding The design of all safety-related structures, as described in Section 3.8, includes factors to protect, to the maximum extent
)
(N practicable, the safety-related systems, equipment, and components from the' probable maximum flood and the highest groundwater level including wave run-up. Subsection 3.8.6.3 enumerates the combinations of loadings which consider hydrostatic loads and coincident wind loads. Subsection 3.8.6.3.1 9 states that lateral hydrostatic pressure loads and bouyant forces resulting from the PMF 'have been applied (where applicable) to Seismic Category I structures. Section-2.4 is ref erenced as providing f urther discussion. 3 Subsections 2.4.3.5 and 2.4.3.6 discuss the hydrological considerations of the PMF including the maximum wa ter level and the effect of concurrent wind wave activity. This discussion-indicates that it is the concurrent wind wave activity which produces overtopping flow and qualitatively - evaluates the expected quantity and depth of this flow. Baced upon tre evaluation i n Subsection 3.8.1.6, no dynamic l33 hydrostatic loads were applied to the Seismic Category I structures and no dynamic ef fects on foundation properties were 3 considered to occur due to the PMP. O t i Revision 33
\#
3.4-3 4/81
w l l MIDLAND 1&2-FSAR 3.4.2 PROTECTION FROM INTERNAL FLOODING Flooding levels and spray effects are determined for each h postulated failure in all moderate and high energy systems. The results were found not sufficient to either impair the functioning of essential systems and components or produce significant damage to essential structures. The effects, other than flooding, of postulated failures of high energy piping inside containment are discussed in Section 3.6. The containment and all essential equipment located within are designed to withstand the environment associated with the design basis event inside containment. Flooding, as a result of component failure in the circulating water system, is discussed in Subsection 3.4.2.5.1. 3.4.2.1 Internal Flooding Criteria The structures, systems, and components necessary to achieve and maintain cold shutdown and to mitigate the consequences of postulated failures are to be prote:ted. These systems are comprised of not only the piping and mechanical components but also the electrical components, the control room (including its habitability systems), certain other ventilation systems, actuation equipment, and the diesel fuel system. Flooding shall not prevent the cold shutdown of the plant. Also, those areas that need to be occupied for cold plant shutdown shall remain habitable and accessible. 3.4.2.2 Design Assumptions The following assumptions were used in the flooding analysis:
- a. Failures in moderate energy piping systems, cutside of the containment, are postulated in accordance with Branch Technical Position MEB 3-1. High energy piping system failures are postulated as discussed in Section 3.6.
- b. Post-LOCA passive failures are limited to critical cracks in piping, sprung flanges, leaking packing, seals, and the like.
- c. A 10 minute delay is assumed for those situations that involve operator action in the control rcom.
- d. An addit'ional 30 minute delay is assumed for those situations that involve operator action at a location not immediately adjacent to the control room or some other centinuously manned area.
Revision 8 3.4-4 4/78
, .. .- . . . - . . ~ . - . ._ - .~. ~ - - t. II l i MIDLAND 162-FSAR t ! since all cad assemblies are preassembled #in accordance
- with - accepted industry standards and 'are shop tested at
~
a pressure above~ 3,100 psi, which is well above normal-operating pressure. i i Potential missiles resulting.from contained fluid energy , are identified in Tables 3.5-1 and 3.5-2. i c. Missiles Propelled by Jet of1 Escaping Fluid Potential missiles propelled by a jet of-escaping fluid: may be the-result of the failure of a CRDM. For the purpose of analysis, it is postulated that;an' entire CRD assembly becomes' a jet propelled missile.- An . individual ' CRD assembly is bolted to each nozzle of the reactor ' vessel closure head and is in contact with the contained fluid energy of the vessel. Should.it ever be generated, this class'of missile (the most significant type in terms of available kinetic energy) jwould be, subjected to a significant; jet.of escaping fluid. The jet imparts an impulse to the missile as the jet expands
- into the containment. The velocity of the-jet-is .
assumed to be constant at the maximum orifice-velocity. As the assembly moves further from the' rupture, the jet expands _ and the weight of the fluid ~actually striking.' the CRD assembly decreases. The angle of jet expansion is an important assumption in determining the expected velocity of this potential missile.c a-*);For subcooled O water and steam blowdown situations, the jet area expands uniformly at a half angle'of about 15*,-whereas , steam / water blowdown- expands much more- rapidly. because . of large-scale water flashing.(*,s> For the purpose of a conservative analysis, a jet expansion half angle of 100-is assumed. The RCS' temperature and pressure ~are - assumed to be 600F and 2,200 psia, and the velocity of ' the fluid jet was calculated using Moody choked flow-parameters and.C,=1.0. It is assumed that an entire CRD assembly is ejected from the closure head of the reactor vessel due to a severe failure in either the nozzle bolting material of the CRD, the CBD nozzle,oor the~CRD assembly material itself. In the unlikely event of a severe material failure in any one of these locations,.a complete or+ partially complete CRD assembly could be forced out of the reactor vessel closure head and cculd-be propelled by the force of a jet: of escaping ' reactor coolant. Such materials as the CRD nozzle bolting material,fthe CRD nozzle material, and the CRD assembly material itself are selected to be compatible with and to operate in the environment associated -with the reactor vessel.' Quality standards relative to material selection, fabrication, and inspection are specified to ensure the 3.5-7
..-.-.-,-_-,,-.--.u_..-.--..-:.-
. e MIDLAND 1&2-FSAR safety functions of the assemblies essential to accident prevention. All welding has been performed by personnel qualified under ASME Code, Section IX, Welding Qualifications. The preceding, along with proper field installation and periodic inservice inspections, ensures that the probability of missiles being generated from CRD assemblies is essentially negligible.
Instruments and instrument connections attached to the RC piping, steam generator, pressurizer, and other pressure retaining c,mponents are considered potential jet propelled missiles. Instrument, drain, and vent connections to piping and other components are welded in place. These piping system appurtenances are prevented from becoming missiles by quality controls which ensure that equipment and components are installed correctly, and by providing retention features in addition to the single welded joint. The energies associated with these potential missiles are included in Tables 3.5-1 and 3.5-2.
- d. Missiles Generated by Rotational Energy The RC pumps are the principal source of rotational energy within the containment. The primary source of missiles from the RC pumps is the pump motor flywheel.
Subsection 5.4.1.7 covers the method used to implement General Design Criterion 4 with regard to the flywheels of the RC pump motors. The method used to implement GDC 4 is based on the principles of fracture mechanics and on the requirement for a sufficiently small probability of flywheel failure. Acceptability,of the reactor coolant pumps is based on the guidance of Regulatory Guide 1.14 and is discussed in Appendix 3A. l 33 In addition to the flywheel, the RC pump impeller and motor rotor have been reviewed for potential missile generation. The review concluded that no failure of the components would cause the generation of missiles external to the pump and motor that would be capable of significantly damaging other components in the vicinity. Pumps in systems outside the containment have been evaluated for missiles associated with overspeed failure. The maximum no-load speed of electric motor driven pumps is controlled by the operating speed of their motors. Because of this, no event that results in a decrease in suction head would increase pump speed over that of the no-load condition. In addition, there are no avents that could result in a significant Revision 33 h 3.5-8 4/81
MIDLAND 162-FSAR increase in pump suction head. Therefore, overspeed can (~'s be expected to be limited to less than 120% of rated (_,/ s peed. Typical missiles associated with pumps outside the containment are listed in Table 3.5-2. The following general methods are used in the design, manufacture, and inspection of equipment to assure that the potential for generating missiles is minimized.
- a. All pressurized equipment and sections of piping that, from time to time, may become isolated under pressure will be provided with pressure relief valves if required for system protection.
- b. Where required by code, volumetric testing, coupled with periodic inservice inspections of materials used in components and equipment, adds further assurance that any material flaws that could permit the generation of missiles will be detected before accidental failure can occur.
3.5.1.2 Internally Generated Missiles Inside Containment Refer to Subsection 3.5.1.1 which discusses internally generated missiles both inside and outside of containment. I) \/ 3.5.1.3 Turbine Missiles The turbine generators store large amounts of kinetic energy in their rotors. In the event of a major mechanical f ailure, this energy will transform into rotational and translational energy of rotor fragments which may damage the surrounding stationary parts. If the energy absorbing capacity of the stationary parts is inadequate, the fragments will escape as missiles. These missiles may impact various plant structures and systems, including those housing the safety-related equipment. This section discusses the probability of such an undesirable occurrence, and measures taken to reduce the same. A statistical analysis is performed to establish that these probabilities are l 26 within acceptable limits. 3.5.1.3.1 Turbine Characteristics, Placement, and Orientation With Relation to Vital Plant Systems Detailed descriptions of the turbine and generator are presented in Section 10.2. Placement and orientation of the low-pressure turbine units in relation to the rest of the plant facilities are shown in Figure 3.5-1. Unit 1 turbines rotate in a clockwise direction when viewed from west to east, and Unit 2 turbines rotate in a clockwise direction when viewed from east to west. s_) Revision 26 3.5-9 1/80
MIDLAND 162-FSAR General plant layout at various elevations is shown in Figures 1.2-2 through '1.2-33. Systems considered in the analysis are l33 chown in the above figures and are listed in Table 3.2-1, with the exception that the borated water storage tanks are not included in the turbine missile analysis. When the safety- f 13 related component (or components) is~ located inside a compartment, the whole compartment is taken to be the target. For example, in the case of the reactor coolent system composed of reactor vessel, steam generators, pressurizers, and coolant pumps, the entire reactor building is considered as the target. l 26 Table 3.5-3 lists the targets along with their floor elevations and locations. The locations are identified by reference to cdjacent column line numbers. Concrete walls and roofs are considered as barriers. Ultimate compressive strengths of concrete of the barriers r.re presented in Table 3.5-4. 3.5.1.3.2 High-Pressure and Low-Pressure Turbine Failures Experience and analysesca) show that in the event of a rotor fracture, fragments of the high pressure section and the generator rotors would be contained within their respective casings. There is no recorded incident of the release of external missiles from a high-pressure casing. Further, the relatively low design stresses in an 1,800 rpm integral-wheel high-pressure nuclear turbine make it unlikely to fail at any speed to which it is capable of being driven. In General Electr$ c low-pressure turbines, the energy stored in the hypothetical tragments of the wheels is of the same order as the energy absorbing capability of the stationary parts. This leads to the possibility of the release of missiles with an energy equal to the initial kinetic energy less that absorbed by the stationary parts. Accordingly, the discussion here will be limited to the geaeration of missiles by low-pressure turbine wheels only. 3.5.1.3.3 Failure Mechanisms Two broad catenories of turbine wheel rupture are the design overspeed failures and the destructive overspeed failures. 3.5.1.3.3.1 Design Overspeed Failures Failures of this type can occur during startup or normal operation and they are characterized as occurring at or below 120% of the rated speed. Nuclear turbines operate at relatively low temperatures, and high temperature rupture is not considered. Revision 33 3.5-10 4/81
MIDLAND 1&2-FSAR L
.3.5.1.6 Aircraft flazards 3.5.1.6.1 General Aircraf t operations near the Midland nuclear power station site are described in Subsection 2.2.2.5. This information indicates l 33 that detailed investigation;of the potential hazards from operation at Tri-City and Barstow airports and -along four federal civil airways and one military airway as 'well as miscellaneous direct flight operations is needed. ,
i O i i r Revision 33 3.5-20a 4/81 *
, _ . . . _ . - - . _ . . . . _ _ . _ - _ _ . _ _ - _ . . . _ _ . _ _ _ . . _ . . . _ . . , _ . _ _ . ~ _ . - _ _ _ , - _ _ _ . . _ _ _ _ _ - - . . . _ _ _ . . . . _ . _ . , _ _ _ . - - -
MIDLAND 152-FSAR O l l THIS PAGE INTENTIONALLY LEFT BLANK l l [ Revision 8 s 3.5-20b 4/78
MIDLAND 1&2-FSAR plant. Local practice areas are north and east of the airports ( and hence flights to these areas would not go near the plant. For a uniform aircraf t distribution, the crash distribution 7 parameter is given by the reciprocal of the circumference of the circle going through the plant. Therefore, for.Barstcw 1/p is 2 (5.4.5)n or 33.9 mi, while for Tri-City it is 2 (9.3 i )n or 1 33 58.4 miles. Air carrier and military aircraft tend to fly along airways ~and in landing tend to line up with the runway at greater distances 7 than do general aviation aircraft. From a review of approach. patterns to the Tri-City Airport it was determined that only operations on runway 14/32 (ranning 140*/320*) could come near the plant. As indicated in Subsection 2.2.2.5, this runway is I 33 used less than 20% of the time. A plane landing on runway 14 would be at an altitude of 1,500 feet or more when' near the plant. For an aircraft at 1,500 feet with a glide ratio of 10, the reciprocal crash density, using the relation given above, is 4.46 mi. 3.5.1.6.7 Results The parameters used to calculate impact probability are (N summarized in Tables 3.5-13 and 3.5-34. For air carrier and ( ,) military operations at Tri-City, only 20% were considered to pass near the plant and contribute to the impact probability. The results of the probability calculation are summarized in Table 3.5-15. The total probability of potentially unacceptable impact is 0.75 x 10 4 . 7 The probability analysis performed is based on aircraft activity ( and crash rates for the 1972-1977 time period. While aircraft i activities are expected to increase in the future, crash rates, l in particular those for general aviation, are expected to decrease. Various projections of airport activity near Midland show an annual air traffic increase of 4 to '6%.qn,223 On the other hand, the general aviation fatal crash rate has decreased by an average of more than 6% over the 1971 to 1975 time period. t s) Based on this, it is concluded that the aircraft impact probability will remain essentially constant over the life of the Midland nuclear power station. l 3.5.2 STRUCTURES, SYSTEMS, AND COMPONENTS TO BE PROTECTED Structures, systems, and components that are identified as Seismic Category I in Table 3.2-1 are protected from missiles in accordance with criteria presented in subsections 3.5.1.3, 3.5.1.4, 3.5.1.5, 3.5.1.6, and 3.5.2.1, except that the borated s water storage tank and portions of the auxiliary building roof l ) and siding are not tornado protect'ed. These criteria apply to l 28
'"' turbine missiles, missiles generated by natural phenomena, i l 33 Revision 33 3.5-25 4/81
\ i
MIDLAND 1&2-FSAR cissiles generated by events near the site, aircraf t hazards, and internal missiles. Additional information regarding spent fuel l 15 ctorage protection from tornado missiles is provided in l 28 Table 3.5-10. Additional discussion of the capability of the ultimate heat sink to withstand the ef fects of missiles is provided in Subsection 9.2.5. Jet impingement and' pipe whip from high energy piping systems are discussed in Section 3.6. Safety-related structures, systems, and components inside containment as well as the method of protection for each item are tabulated in 15 Table 3.5-19. 3.5.2.1 Protection of Safety-Related Structures, Systems, and Components from Internal Missiles As discussed in Subsections 3.5.1.1 and 3.5.1.2, all structures, systems, and components were examined and situations identified where, in the event of a definable failure, a source of constrained energy could be converted into the kinetic energy of a potential missile. The resultant missiles were then evaluated for their potential for damaging safety-related structures, systems, and components according to the following criteria:
- a. Protection is provided against potential missiles that could cause a LOCA.
- b. Protection is provided against potential missiles that could result in the loss of ability to control the consequences of a LOCA, includir.g the capability for core cooling and for retention of containment integrity.
- c. Protection is provided against potential missiles that could jeopardize the funccions necessary to bring the reactor to a safe shutdown condition.
- d. Protection is provided against potential missiles chat could result in the release of radioactivity with resultant doses in excess of 10 CFR 100 limits.
- e. Protection is provided against missiles which could render uninhabitabl.e those areas of the plant which must remain occupied during safe shutdown conditions.
Where required, protection against a postulated missile is provided through use of barriers, separation, restraint of potential missiles, strategic orientation, or equipment design. Missile barriers are discussed in Subsections 3.5.2.2, 3.5.2.3, and 3.5.2.4. 3.5.2.2 Missile Barriers Within Containment Specially designed barriers, secondary shield walls, refueling canal walls, various structural beams, and floors act as missile barriers separating each reactor coolant loop from other protected components and missile sources. These barriers, as l18 3.5-26 Revision 28 5/80
. MIDLAND 1&2-FSAR TABLE 3.5-2 (continued)_ , Cross- Missile Sectional Impact Maximum Kinetic Description Area Weight Area Velocity Energy (Systems) (in.2 ) (lb) (in.2) (ft/s) (ft/lb) Cooling pond 354.0 2,475 354.0 77.0 228,046.0 makeup pump
#0P-10A Circulating 1,288.23 17,180.09 1,288.23 746,010.0 26 52.86 water pump
#0P-01A Circulating 1,536.11 6,000 1,536.11 62.3 361,903.0 water pump l32 i
#2P-01A 28 S/G feedwater 108.9 422.26 108.9 320.2 672,802.0 l32 pump #2P-04A l28 O
V-(sheet 2) Revision 33
,4/81
HI.DLAND 1&2-FSAR 3.6.2 DETERMINATION OF BREAK LOCATIONS AtiD DYNAKIC EFFECTS
/'% ASSOCIATED WITH THE POSTULATED RUPTURE OF NON-NSSS
( ,) PIPING The NRC has reviewad and accepted the criteria of Subsection 3.6.2.1 as indicated by S. At Varga's September 24, 1976 letter to S. H. Howell-of CPCo. 3.6.2.1 Criteria Used to Define Break and Crack Location and Configuration 3.6.2.1.1 ASMS Section III, Class 1 Piping The analytical results presented in Subsection 3.6.2.5 for ASME Class 1 piping are based on break locations selected per the crite ria of Subsection 3. 6.2.1. 2. Selection of break location will be verified (by amendment) utilizing the following criteria': l33 For ASME Section III Code Class 1 piping, pipe breaks are postulated to occur at terminal ends and at all intermediate locations throughout a piping system where the following criteria are met:
- a. The stress range Sn as calculated by Equation 10 of Paragraph NB-3653 exceeds 2.4 Sm, or
[) v
- b. The cumulative usage factor exceeds 0.1 When all the stresses and usage factors calculated for a piping run between terminal ends are less than the criteria above, a :
minimum of two break locations are postulated based on the ' highest stress. Where a piping system has been modeled and analyzed as a whole and all the stresses and usage factors are maintained below the corresponding threshold values, a break is not postulated at any. branch connection unless it is one of the two highest stress intermediate points in the pip i og run. Once a high energy piping system has be;n analyzea and break 33 locations have been identified and evaluated, the postulated intermediate break locations will not be altered upon subsequent stress reanalysis, provided there have been no major changes in the routing of the high energy piring in the vicinity of the original intermediate breaks. However, if the reanalysis results in stresses or usage factors in excess of Criterion a or b above, tnen breaks will be postulated at the specific points wnere the criteria are exceeded. These breaks will be evaluated, and mitigative devices added where necessary. In any case, the minimum number of intermediate break locations discussed above will be maintained. (~'#)
'~ Revision 33 3.6-9 l 4/81 ,
- - - - , , ,. , . - -, ,n- -. , ,- - - ,
-n - , - -- ,-n-
MIDLAND 1&2-FSAR At each postulated break location, circumferential breaks are cssumed to occur in pipes larger tnan 1 inch and longitudinal breaks are assumed to occur in pipes 4 inches and larger except:
- a. Longitudinal breaks are not postulated at. terminal ends if the pipe does not have a longitudinal weld at that location.
- b. Longitudinal breaks are not postulated where the criterion for a minimum number of breaks must be satisfied. For seamed pipe, longitudinal breaks are oriented along the pipe seam. In instances where the seam orientation is not known, slot breaks at any point around the pipe are assumed.
3.6.2.1.2 ASME Section III Class 2 and 3 Piping (Other Than Between Containment Isolation Valves) Breaks are postulated to occur at the following locatione in ASME Section III Class 2 and 3 piping:
- a. At the terminal ends of the pressurized portions of the run
- b. At intermediate locations selected by either one of the following methods:
- 1. At all locations where the stress, S, exceeds 0.0 h (1.2S h + SA)*
where S = stresses under the combination of loadings associated with the normal and upset plant condition loadings, as calculateo from the sum of Equations 9 and 10 in Cabarticle NC-3600 of the ASME Boiler and Pressure Vessel Code, Section III
- 2. At each location of potential high stress, such as pipe fittings (elbows, tees, reducers, etc),
valves, fJanges, and welded attachments
- c. If there are not at least two intermediate postulated break locations in a piping run due to application of the criteria above, then a minimum of two break locations are chosen based on highest stress. When the piping system is modeled and analyzed as a whole and the 33 stresses are maintained below the pipe break allowables as presented above, a break is not postulated at a branch connection unless it is one of the two highest stress intermediate points in the piping run.
3.6-10 Revision 33 G 4/81
MIDLAND 1&2-FSAR , Once a high energy-piping system has_been analyzed and break. fx locations have been identified and evaluated, the postulated () is,termediate break locations will not be altered upon subsequent stress reanalysis of the piping system, provided there have been no major changes in the routing of the high energy piping in the vicinity of the original intermediate breaks. However, if the. reanalysis reveals the existence of stress' in excess of 33 Criterion b.1 above, then breaks will be postulated at the specific points where the criterion was exceeded. These breaks ! will be evaluated, and mitigative devices added where necessary. In any case, the minimum. number of intermediate break' locations J discussed in Item c above will be-maintained.
~
At each postulated break location, circumferential breaks are assumed to occur. in pipes larger than 1 inch and longitudinal' - breaks are assumed to ccccc in pipes 4 inches and larger except: ..
- a. Longitudinal breaks are not postulated at tcrminal ends if the pipe does not have a longitudinal weld at that location.
I
- b. ' Longitudinal . breaks are not postulated where the criterion for a minimum number of breaks must be
! catisfied.
t For piping systems, or portions of systems, within enclosures, breaks are postulated in accordance with the above criteria, and l 33 it is demonstrated by l l 7 i l l l f l l l ( 3.6-10a Revision 33 4/81 i
MIDLAND 1s2-FSAR O THIS PAGE INTENTIONALLY LEFT BLANK O t l t l [ i Revision 33 3.6-10b 4/81
' MIDLAND 1&2-FSAR analysia Jthat such enclosure 'is- adequately designed to prevent
(~'% any damage to essential structures and equipment from the effects (,,) of pipe whip, jet impingement, pressurization of the enclosure compartment, environmenta1' conditions, and flooding associated with the escape of the contained fluid. Piping restraints within s the enclosure may be accounted for in' limiting the ef fects of the - postulated pipe rupture. 3.6.2.1.3 Nonnuclear Class Piping Breaks are postulated to odcur at the locations as specified for-ASME Section III Class 2 and 3 - piping , in accordance with-Subsection-3.6.2.1.2, if the nonnuclean piping is analyzed, hung, and supported to withstand the full SSE loadings. I" For nonnuclear. - class piping systems'where stress information is not available, breaks are postulated to occur.at the following locations:
- a. The terminal ends
- b. Each intermediate location of potential high stress 'or fatigue, such as pipe fittings -(elbows, tees, reducers, etc), valves, flanges, and. welded attachments 3.6.2.1.4 Piping Penetrating' Containment
-~s Pipe breaks are not postulated in portionc~ of high energy piping g ) extending from the containment penetration to the first piping
'~' restraint beyond the first-isolation valve outside containment, providing the following requirements are met:
- a. The following / ? sign stress and fatigue limits are not exceeded:
For ASME Code Section III Class 1 Piping There is no ASME Section III Class 1 piping penetrating the containment; therefore, no break criteria are provided. For ASME Code Section III Class 2 Piping The maximum stress ranges, as calculated by Equations 9 and 10 in Paragraph NC-3652, ASME Code Section III, ! considering normal and upset plant conditions do not exceed 0.8 (1.2Sn + Sa).
- b. The piping is anchored reasonably close to the first isolation valve such that occurrence of a pipe break outside containment beyond these restraints she 'l
- neither impair operability of the valves nor the i integrit/ of the containment penetration. Terminal ends of the piping runs extending beyond thece portions of L.)
3.6-11 Revision 33
.4/81
MIDLAND 1&2-FSAR high energy piping are considered to originate at a point adjacent to these anchors.
- c. Welded pipe support attachments to those portions of piping penetrating containment are avoided to eliminate stress concentrations.
- d. The number of piping circumferential and longitudinal stelds and branch connections is minimized.
- e. The extent of piping run is reduced to the minimum length pructicable,
- f. The design at points of pipe fixity (e.g., pipe anchors or welded connections at containment penetrations) does not require welding directly to the outer surface of the piping (e.g., flued integrally forged pipe fittings are acceptable designs) .
The maximum stress values calculated for the main steam and main feedwater lines extending f rom the containment penetration to the first piping restraint beyond the first isolation valve and for the makeup and purification letdown line f rom the containment penetration to the first isolation valve outside containment compared to BTP MEB 3-1 maximum allowables and the ASME Code maximum allowables are as follows: 8 Maximum Maximum Maximem Allowable Allowable No Break Zone Calculated Stress Stress per Piping Stress (per Ref. 3) ASME Code Mnin steam line 0.8 (1.2 Sn +Sg) 2.4 S n Main feedwater line 0.8 (1.2 Sn +Sg) 2.4 S h Mrkeup and purification 0.8 (1.2 S n +Sg) 2.4 S n letdown line A progran of augmented inservice inspection will be applied to the following piping:
- a. The main steam lines f rom the containment penetration to the first pipe restraint (anchor) beyond the first isolation valve outside containment. Also included is a 15 2 inch diameter bypass line around the isolation valve and an 8 inch branch line to the atmospheric dump valve.
- b. The main feedwater lines from the first pipe restraint
.( ancho r ) before the first isolation valve outside containment to the containment penetration Revision 33 3.6-12 4/81
MIDLAND 1&2-PSAR sc. The mtkeup and purificat' ion lines extending from the
/) first isolation valve outside containment to the
- ' ( ,/ containment penetration. 15 Piping'which is 1-inch ~ nominal diameter and
- smaller, and therefore exempt from pipe break-analysis in accordance with' 28 Regulatory Guide 1.46, will be excluded from'the piping which is subject tofaugmented inservice inspection.
i' This augmented inspection will require-that each circumferential,. longitudinal, and branch pipe weld be inservice examined once each 10 years. In lieu of implementing requirements;for'a 100% volumetric examination, examinations will be performed in accordance with the rules contained in the Winter 1977 version of I_b the ASME. Code, Section XI. Therefore,-for welds in piping where the nominalEthickness exceeds 1/2 inch, a surface examination and a volumetric examination will be performed, and welds in piping where the nominal thickness is 1/2 inch or less will only have a surface examination. 3.6.2.1.5 Location of Postulated Moderate Energy Piping Failures Through-wall leakage crack locations are postulated in accordance' with BTP MZB 3-1 for all moderate' energy piping located in areas containing systems important to safety.
~O 3.6.2.2 Analytical Methods to Define Forcing Functions and_
( ) Response.Models Analyses are performed for the pipe failures postulated in-Subsection 3.6.2.1. Analysis of jet thrust forces which result in the event of a pipe rupture is described in BN-TOP-2, m Section 2.2 and fluid jet impingement forces are discussed in , Sec tion 2. 3 of BN-TOP-2. Impulsive loading and impact combi'ned ' with impulsive loading are described in Sections 3.2 and 3.3 of BN-TOP-2 and in BC-TOP-9A."" Alternatively, nonlinear time history dynamic analyses are performed. 1 The criteria for the dynamic analyses are as follows:
- a. An analysis of the pipe run or branch is performed ~for !
each longitudinal anu circumferential postulated rupture l at the break locations determined in accordance with the l criteria of Subsection 3.6.2.1.
- b. The loading condition of a pipe run or branch prior to postulated rupture in terms of internal pressure, temperature, and stress state is that condition associated with reactor operating at 100% power. j l
('~\ l
\s / l 3.6-13 Revision 28 '
5/80
MIDLAND 1&2-FSAR
- c. For a circumferential rupture, pipe whip dynamic analyses are only performed for that end (or ends, of the pipe or branch that is connected to a contained fluid energy reservoir having sufficient capacity to develop a jet stream.
- d. Dynamic analytic methods used for calculating the piping and piping / restraint system response to the jet thrust developed after a postulated rupture adequately account for the effects of:
- 1. Mass and stiffness properties of the piping system, restraint system, major components, and support walls
- 2. Transient forcing function (s) acting on the piping system ar.d jet thrust on affected structures
- 3. Elastic and inelastic deformation of piping ana/or restraint
- e. Allowable design strain limits as described in BC-TOP-9 A '"I are used.
- f. An increase of minimum specified yield strength (Sy) may be used to account for strain rate effects in inelastic nonlinear analyses, as described in BC-TOP-9A.UU
- g. When energy balance analysis is used, the pipe and restraint is assumed to have plastic impact as explained 8 in BN-TOP-2, Revision 2. The maximum response after several cycles is considered as follows:
- 1. For piping systems where the blowdown thrust force is monotonic in nature (e.g., piping connected to primary coolant system) or decreasing overall, no 1 33 magnification factor is required.
8
- 2. For piping systems where the blowdown thrust force is increasing overall, but not monotonically, a l 33 magnification factor, as described in BN-TOP-2, Revision 2, is used.
When energy absorbing material is used in the pipe whip restraint structure, the following criteria are used:
- a. 'rhe deformation limit for energy absorbing material is 8 50% of original height or 90% of ultimate strain test value, uhichever is less.
- b. Collapse of the cells under axial compression occurs by local wall buckling in a plane perpendicular to the axis. This proceeds in a uniform pattern until all cells have buckled many times. Crushing load is relatively constant as the core progressively fails up to at least 50% of original height. The energy absorbed Revision 33 3.6-14 4/81
MIDLAND 162-FSAR 3.6<2.5.1 Main Steam System and Steam Line to Turbine Driven
/ Auxiliary Feed Pump b} 3.6.2.5.1.) General Description The main steam system piping, as shown in Figures 10.3-1 through 10.3-4, consists of the four 26 inch lines which combine into two 36 inch main steam supply lines from each containment. They supply high-pressure steam to the turbines and secondary steam to the process steam evaporators. In addition, there are two 6 inch steam lines per containment which supply steam to the turbine driven auxiliary feedwater pump in the event of an emergency; i.e. , auxiliary feedwater actuation signal (AFWAS) . Saismic and quality classification of the main steam system and steam line to the turbine driven auxiliary feed pump are indicated in Figures 10.3-1 through 10.3-4.
3.6.2.5.'1.2 Evaluation and Identification of High Energy Portions The high energy portion of the main steam piping inside containment consists of all the 26 and 36 inch piping from the once-through steam generator (7TSG) connections to the containment wall. The high energy portion of the steam supply line to the turbine driven auxiliary feedwater pump consists of the section of 6 inch piping from the 26 inch main steam piping connection to the first normally closed motor operated valve
-~
(MOV) inside the containment as tabulated below:
\ '# Fiqure No. Line No. MOV No.
10.3-1 6"-1 EBB-13 074 6"-1 EBB-14 077 10.3-3 6"-2 EBB-13 074 6"-2 EBB-14 077 i The motor operated valves on the stcam line to the auxiliary feed pump turbine driver, tabulated above, are closed during all , normal modes of operation. The piping downstream of these Movs will not be pressurized except in an emergency, when the turbine driven auxiliary feed pump is required to function. This section of piping as well as the auxiliary feed pump turbine driver have been designed to withstand the transients associated with going
- from a cold unpressurized condition to full power steam operation (refer to Subsection 10.4.9) . Since the steam line te the auxiliary feed pump turbine driver downstream of the-aforementioned.MOVs is never pressurized during normal plaat operation, no breaks or critical cracks are postulated in this section of piping.
() O i 3.6-15 i
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MIDLAND 1&2-FSAR 3.6.2.5.1.3 Analysis of Postulated Breaks The effects on the RCS following a main steam line rupture are provided in Subsection 15.1.5. The main steam system piping and 133 Cteam line to the auxiliary feed pump turbine driver have been evaluated for postulated breaks as shown in Figures 3.6-1 through 3.6-4. The protection against postulated pipe break effects is given in Table 3.6-3 and discussed in Subsection 3.6.2.5.1.5. The blowdown thrust force at each break location has been conservatively calculated using the methodology of the BN-TOP-2 t2' superheated steam model with the OTSG being the cource of blowdown. Due to the short run of each steam line to the auxiliary feed pump turbine driver (approximately 3 feet in length), a break is postulated on the OTSG side of the MOV and at the connection to the 26 ..nch main steam line, but no intermediate breaks are postulated (refer to Figures 3.6-2 and 3.6-4). 3.6.2.5.1.4 Shutdown Procedures Detection and shutdown procedures for various sizes of steam line breaks are provided as part of Subsection 15.1.5. A summary of the time history sequence of events for a steam line break is presented in Tables 15.1-7, 15.1-8, and 15.1-9. l33 3.6.2.5.1.5 Plant Design Features All of the main steam system piping and high energy portion of the steam line to the auxiliary feedwater turbine driver has been restrained as shown in Figures 3.6-1 through 3.6-4 and Table 3.6-3. All of the safety-related structures surrounding this piping (i.e., the primary and secondary shield walls, the concrete pads and grating at elevation 640'-0", the containment walls, the pressurizer spray valve enclosure, and miscellaneous internal steel beams, columns, and grating) have been designed to withstand the fluid jet loading resulting from associated piping ruptures. In both containment buildings a concrete pad at elevation 640'-O' and strengthened grating have been provided to protect safety-related electrical cable trays at lower elevations from direct impingement by a fluid jet associated with main steam pipe breaks, even though there are no main steam postulated break locations outside the secondary shield walls below approximately elevation 697'-9". Inside both containments, there is adequate ccparation between safety-related systems so that no jet impingement barriers are required, other than the protection afforded by existing surrounding structures. O 3.6-16 Revision 33 4/81
MIDLAND 162-FSAR All safety-related structures within the containm?nt have been' (N \ designed to withstand the highest differential pressurization resulting. from any of the above postulated breaks (refer to subsection 3. 8.3) . A break postulated at any of the specified locations does not constitute a breach cf containment integrity. Containment integrity is described in Subsection 6.2.4. 3.6.2.5.4 Decay Heat Return ' Piping - 3.6.2.5.4.1 General Description The decay heat. removal system return piping, as shown in Figures 5.4-10 and 5.4-11, is designed to provide a return path of cooling to the reactor coolant system when the plant in in a cold shutdown condition as described in Subsection 5.4.7. The supply portion of the decay heat removal system was discussed as part of subsection 3.6.2.5.3. The decay heat removal system seismic and quality classification is indicated in Figures 5.4-10 and 5.4-11. 3.6.2.5.4.2 Evaluation and Identification of High Energy Portions The high energy portion of the decay heat return piping starts at the reactor coolant system hot leg connection and continues to the first normally closed motor operated valve and bypass valve s (valves 045 and 093 in Figure 5.4-10 and valves 046 and 094 in (') Figure 5.4-11) . The piping downstream of these valves is only pressurized when the reactor coolant system is less than 350 psig. This constitutes less than 1% of the total plant operating time and thus will be treated as " moderate energy" rather than "high energy" piping. 3.6.2.5.4.3 Analysis of Postulated Breaks The effects on the reactor coolant system following a postulated loss-of-coolant accident, such as the decay heat return line postulated ruptures, are given in Subsection 15.6.5. The decay heat return piping has been evaluated for postulated breaks as shown in Figures 3. 6-10 and 3. 6-11. The protection against postulated pipe break effects is given in Table 3.6-6 and discussed in subsection 3.6.2.5.4.5. The blowdcun thrust forces were conservatively calculated using the cold water model as presented in BN-TOP-2.ca) 3.6.2.5.4.4 Shutdown Procedures A break at any of the postulated break locations in the nigh energy portion of the decay heat return piping constitutes a 12 inch hot leg loss-of-coolant accident. A wide spectrum of hot leg rupture sizes has been analyzed and the procedure for (O ! t V 3.6-21
MIDLAND 162-FSAR tripping the reactor, injecting emergency cooling water, and bringing the plant to a safe shutdown condition is included as psrt of subsection 15.6.5. In the event of decay heat return piping rupture, suction water for the decay heat pumps is provided by one of two redundant lines from the BWST reactor building sump headers. The decay heat removal supply piping is vnived and physically arranged such that either pump P-60A or P-60B can be used to inject shutdown cooling water through either 33 cupply header (refer to Figures 5.4-10 and 5.4-11) . 3.6.2.5.4.5 ?lant Design Features All of the high energy portion of the decay heat return piping hcs been restrained as shown in Figures 3.6-10 and 3.6-11 and Table 3.6-6. All of the safety-related structures surrounding this piping (i.e., sump protection walls, secondary and primary shield walls) have been designed to withstand the fluid jet loading resulting from associated piping ruptures. In the Unit 1 containment, there is adequate separation between safety-related systems so chat no jet impingement barriers are required other than the protection afforded by surrounding structures. In the Unit 2 containment, a steel plate barrier has been provided west of the secondary shield wall to physically separate the DHR cupply line, 10"-2CCB-25, core flooding line, 14"-2ECB-1, and electrical cable trays, from the decay heat return piping. 3.6.2.5.4.6 Environmental Evaluation The containment and secondary shield subcompartment prescures and temperatures resulting from a spectrum of reactor coolant system breaks are addressed as part of Subsection 6.2.1.2. All safety-related components required for post-accident conditions have been designed for operation with the worst environmental condition postulated to which they will be subjected following a pipe break. All safety-related structures within the containment, as well as the containment itself, have been drsigned to withstand the highest differential pressurization resulting from any reactor coolant system postulated breaks. 3.6.2.5.5 Main Feedwater System Piping Inside Containment 3.6.2.5.5.1 General Description The main feedwater system, as shown in Figures 10.4-8 through 10.4-13, is designed to provide a continuous feedwater supply to the once-through steam generators as described in Subsection 10.4.7. The main feedwater and condensate system seismic and quality classification is indicated in Figures 10.4-8 through 10.4-13. O 3.6-22 Rev.'nion 33 4/81
MIDLAND 162-FSAR t 3.6.2.5.5.2 Evaluation and Identification of High Energy" Portions ( The high energy portion of the main feedwater and condensate ( j system.inside the contalament consists.of all piping between the containment and the OTSG feedwater ring header. 3.6.2.5.5.3 Analysis of Postulated Breaks i The effects on the reactor coolant system from a postulated main feedwater line break are given in Subsection 15.2.8. The main feedwater system piping inside containment has been evalsated as shown in Figures 3.6-12 and 3.6-13. The protection against postulated pipe break effects is given in Table 3.6-7 and discussed in Subsection 3.6.2.5.5.5. The blowdown thrust forces were conservatively calculated using the cold water model presented in BN-TOP-2.ca) 3,6.2.5.5.4 Snutdown Procedures , A break at any of the postulated-break locations downstream of the containment isolation valve (at the inside face of the containment) will constitute uncontrolled blowdown of one OTSG. Emergency procedures for shutdown fcllowing a postulated main feedwater break are summarized in Subsection 15.2.8. (m) 3.6.2.5.5.5 Plant Design Features All of the high energy portion of the main feedwater system has been restrained against pipe whip resulting from breaks at the postulated break locations as shown in Figures 3.6-12 and 3.6-13 and Table 3.6-7. All of the safety-related structures in the 1 vicinity of this piping (i.e., primary and secondary shield wall, containment wall, and concrete pad at elevation 626'-0" south of the secondary shield wall) have been designed to withstand the pipe whip restraint loadings and fluid jet loadings resulting from these associated piping ruptures.
! Inside the Unit 1 containment, a steel jet impingement barrier attached to PR-8, as shown in Figure 3.6-12, has been provided to
! physically separate the service water supply (10"-1HBC-102) and l return ( 10"- 1HBC- 103) piping at q elevation 607'-6" from the main feedwater line (18 "- 1 ELB- 1) in the vicinity of node point 28 BM. This safety-related service water piping services the containment recirculating air cooling units which are required to operate following mai n feedwater piping ruptures. Also a steel structure , supported from the containment floor has been provided to l physically separate the RCS letdown line (3 "-1 CCA-19) piping l at t elevation 594'-5-1/8" from the main feedwater line (14"-1ELB-3) in the vicinity of postulated break location 100 (ref er to Figure 3. 6-12) . i
~s s
3.6-23 l l
MIDLAND 1&2-FSAR Inside the Unit 2 containment, two jet impingement barriers have been provided to separate the main feedwater system piping from currounding safety-related components (refer to Figure 3.6-13) as follows:
- a. A jet impingement barrier has been provided, supported from the south face of the secondary shield wall beneath postulated break location 340 BE to physically separate the main feedwat line (18"-2ELB-4) from the service water (10"-2HBC-89 and 10"-2HBC-90) supply and return piping to the containment recirculating air cooling units.
- b. A jet impingement barrier has been provided to physically separate the main feedwater line (18"-2ELB-1) from the service water supply / return piping (10"-2HBC-89 and lO"-2HBC-90) in the vicinity of postulated break locations 025 BM and 030 BM. .
3.6.2.5.5.6 Environmental Evaluation All safety-related components required for post-accident conditions have been designed for operation with the worst cnvironmental conditions postulated to which they will be subjected following a pipe break. The design envelope for components required for post-accident operation inside containment is provided in Subsection 3.11.1. As part of the containment structure design analysis, an 18 inch main feedwater double-ended guillotine pipe break was postulated l33 cnd the resulting pressure / temperature transient determined (refer to Section 6.2). All safety-related structures within the containment have been designed to withstand the highest differential pressurization from any of the postulated main feedwater breaks. Due to the 15 second closing of main feedwater containment isolation valves inside and outside containment (valves 044, 045, 060, 061 in Figure 10.4-10 and valves 044, 045, 060, 061 in Figure 10.4-13), breaks postulated at any of the locations specified inside containment do not consti tuta a breach of containment integrity. 3.6.2.5.6 Auxiliary Feedwater Syster 3.6.2.5.6.1 General Description The auxiliary feedwater system, as shown in Figures 10.4-10 and 10.4-13, is designed to provide sufficient water supply to the OTSG to maintain the plant in a hot standby condition or remove decay heat as described in Subsection 10.4.9. Seismic and O 3.o-24 Revision 33 4/81
L7. e n MIDLAND 1&2-FSAR quality classification of the auxiliary feedwater system is ( V indicated in Figures 10.4-10 and 10.4-13. 3.6.2.5.6.2 Evaluation and Identification of High Energy Portions . The high energy portion of the auxiliary feedwater system inside the containment consists of all piping between the containment wall and the connection to each OTSG. The blowdown thrust forces were conservatively determined by assuming flow reversal from the OTSG and assuming the check valve near the OTSG nozzle fails to close. ) 3.6.2.5.6.3 Analysis of Postulated Breaks . The auxiliary feedwater system piping inside containment has been evaluated for porculated break locations as shown in Figures 3.6-14 and 3.6-15. The protection against postulated pipe break effects is given in Table 3.6-8 and discussed in Subsection 3.6.2.5.6.5. The blcwdown thrust forces. associated with the - postulated auxiliary feedwater piping breaks were conservatively calculated using the cold water model presented in BN-TOP-2.G 3.6.2.5.6.4 Shutdown Procedures
, A break at any of the-postulated break locutions inside the containment will constitute partial or total loss of feedwater
- - ~~-
(%) flow to the affected OTSG. The events following a postulated break in the auxiliary feedwater system depend upon the plant conditions at the time of the break. The auxiliary feedwater i piping and auxiliary feedwater OTSG inlets will be used for normal cooldowns, whereas the main feedwater OTSG nozzles are used for initial OTSG fill and startup. , In the event that the plant is initially in a normal cooldown mode using the auxiliary feedwater pumps and an auxiliary feedwater line break occurs inside the containment, the pressure and weter level within the affected OTSG will drop. As scan as 30 the pressure difference between the faulted OTSG and the unaffected OTSG reaches a preset value, the feed-only-good generator (FOGG) signal overrides the auxiliary feedwater 33 actuation system (AFWAS) open signals and commands the auxiliary feedwater control and isolation valves of the affected OTSG to
; close as discussed in Subsection 7.3.3.2.6. Auxiliary feedwater 30 is maintained to the unaffected OTSG.
j 1-
.I l
1 5
)
3.6-25 Revision 33 4/81 _ . _ _ . - ~ , _ _ _ _ , _ _ . . . _ _ _ _ _ , _ . . . . , _. ...._ . _ _ __._
MIDLAND 162-FSAR 3.6.2.5.6.5 Plant Design Features All of the auxiliary feedwater system piping has been restrained f against pipe whip resulting from breaks at the postulated break locations as shown in Figures 3. 6-14 and 3.6-15 and Table 3.6-8. All of the safety-related structures in the vicinity of this piping have been designed to withstand the pipe whip restraint loadings and fluid jet loadings resulting from these associated piping ruptures. Inside the Unit 1 containment, a jet impingement barrier has been provided to physically separate the auxiliary feedwater line in the vicinity of postulated break locaticn 245 from the incore instrumentation tank and instrument tubes. Also, pipe whip restraints PR-1 and PR-2 as shown in Figare 3.6-14 have been designed to withstand the fluid jet loading due to breaks at node points 100 and 105 BM, in order to shield the auxiliary feedwater pump turbine steam line, 6"-1 EBB-13, and pressurizer auxiliary spray line, 2-1/2"-1CCA-16, from the resulting fluid jet. Inside the Unit 2 containment a steel jet impingement barrier supported from the elevation 640'-0" platform has been provided to protect the safety-related cable trays in the vicinity of postulated break location 235 from the resulting fluid jet. 3.6.2.5.6.6 Environmental Evaluation All safety-related components required for post-accident conditions have been designed for operation with the worst environmental conditions postulated to which they will be subjected following a pipe break. The design envelope for components required for post-accident operation inside containment is provided in Subsection 3.11.1. All safety-related structures within the containment have been designed to withstand the highest differential pressurization from any of the postulated auxiliary feedwater breaks. Breaks postulated at any of the locations specified inside containment do not constitute a breach of containment integrity. Containment integrity is discussed in Subsection 6.2.4. 3.6.2.5.7 Pressurizer Spray and Relief Lines 3.6.2.5.7.1 General Description The pressurizer relief line piping, as shown in Figures 5.1-1 and 5.1-2, is designed to relieve excess pressurizer (RCS) pressure to the quench tank. The pressurizer spray piping, also shown in Figures 5.1-1 and 5.1-2, is designed as a mechanism of reducing pressurizer (RCS) pressure by condensing steam within the pressurizer with RCS cold leg water during normal plant operation 3.6-26
4 MIDLAND 1&2-FSAR-
- b. All auxiliary feedwater pump discharge piping up to'the
] f~] x_/ containment wall, including the crossover piping to the. main feedwater system i The steam supply line-to the auxiliary feedwater pump turbine is l maintained in a cold nonpressurized condition during all normal modes of operation. The turbine driven auxiliary feedwater pump is used only in the event of an emergency-(i.e., AFWAS signal as described in Subsection 7.3.3.2.6). As described in Subsection l33
- 3.6.2.5.1, since the steam supply line to.the turbine driven auxiliary feedwater pump is never pressurized during normal. plant operation, no breaks or critical' cracks are postulated in this piping and this pipe is excluded from the discussions in this section.
4 r 3.6.2.5.11.3 Analysis of Postulated Ereaks Breaks in piping of the auxiliary feedwater system, described in item a above, have been postulated at points shown in Figures 3.6-34, 3.6-39, and 3.6-40 bined on the stress levels of Table 1.6-14 (by amendment). A summary of protection against postulated pipe break effects is shown in Table 3.6-14 (by 33 amendment). Due to the low blowdewn thrust forces associated with breaks postulated in the auxiliary feedwater pump suction piping, the normal piping supports and hangers have been designed l to withstand the rupture loading in lieu of adding separate , -'g gapped restraints to perform this function.
\~
4 Breaks in piping of the auxiliary feedwater system, described in ( item b above, have been postulated at points shown in Figures + 3.6-36 through 3.6-38 and 3.6-41 through 3.6-44 based en the i stress levels of Table 3.6-15 (by amendment). A succury of the l33 i protection against postulated pipe break effects is shown in l Table 3.6-15 (by amendment) and further discussed as part of i 33 Subsection 3.6.2.5.11.5. 1 1 ! I l l l 3.6-38a Revision 33 1 4/81
e- -- ---- - - - - - - MIDLAND 1&2-FSAR O THIS PAGE INTENTIONALLY LEFT BLANK 9 Sevision 9 3.6-3Sb 5/78
1 1 MIDLAND 1&2-FSAR Pressure transients were determined using the methodology of BN-TOP-4, Rev. O.N Flow is assumed to be steady-state, using (\_,)/ the Moody results of Reference 5 with 5 L/D=0. Compartment vent paths are shown in Figures 1.2-3, 1.2-4, and 1.2-5 and described in Subsection 3.6.2.5.11.5. 5 A break in the electric driven feedwater pump suction line results in a more severe pressure / temperature transient in the pump room than a break in the discharge line. This is because mass-energy release from the pump discharge is limited by the pump runout. The details of the calculation for this compartment are as follows:
- a. Forward Flow Upon receiving a low pump discharge flow alarm, the control room cperator isolates the deaerating storege tank by remotely closing one of the redundant suction valves. A time of 10 minutes is assumed for this action.
- b. Reverse Flow The water contained between the pump discharge check valves and the line break is emptied into the pump room at the flowrate calculated for forward flow. Figure 3.6-45 (by amendment) shows the pressure transient 133 f-^s resulting from this break.
( )
# The pressure transient resulting from a suction break inside the compartment housing the electric driven auxiliary feedwater pump is used for design of the compartment housing the turbine driven pump. This is conservative because the latter has a much larger free volume available for expansion, while the mass-energy release rates and vent area are the same for both compartments.
The maximum pressure transient in the pipeway results from a break in the suction line from the deaerating storage tank and is snown in Figure 3.6-46 (by amendment). The details of the 1 33 calculation are as follows:
- a. Forward Flow No isolation is assumed since Dreaks may be postulated between the redundant suction line isolation valves.
The valve between the deaearating storage tank and the break is considered to be the single active failure,
- b. Reverse Flow The feedwater remaining between the pump discharge check valve and the line break is emptied into the pipeway using the flowrate calculated for forward flow.
p
\ -) 3.6-39 Revision 33 4/81 e.m.
MIDLAND 1&2-FSAR The maximum pressure transient in the tendon service shaft also results from a break in the auxiliary feedwater pump suction line from the decerating heater storage tank and is shown in Figure 3.6-47 (by amendment). The details of this calculation 1 33 concerning upstream isolation, downstream isolation, and flowrates are identical to the assumptions made for the pipeway pressure transient analysis discussed above. 3.6.2.5.11.4 Shutdown Procedures The events following a postulated break in the auxiliary feedwater depend upon the plant conditions at the time of break. The technical specifications will not permit use of the turbine driven auxiliary feedwater pump during hot standby except in Gmergencies. In the event of a postulated failure in the piping essociated with the electric driven pump, the break is isolated Cnd the turbine driven pump is started. Since the turbine-generator is not paralleled to the offsite grid during hot standby, availability of offsite power is assumed. This permits use of the main feed pumps in the event that the turbine driven auxiliary feed pump fails to start. Emergency shutdown is not lequired following a failure outside the containment in the auxiliary feedwater system during normal or hot standby operation. 3.6.2.5.11.5 Plant Design Features lf Due to the low blowdown thrust forces associated with breaks in piping of the AFW, as described in item a above, the normal piping hangers and supports have been designed to withstand the rupture loadings and thus prevent pipe whip. All of the AFW piping, as described in item b above, located outside of the motor driven AFW pump room has been restrained as
@hown in Figures 3. 6-35 through 3. 6-38 and 3. 6-41 through 3.6-44 (by amendment) . The walls, floor, and ceiling of the motor 33 driven AFW pump room have been designed to withstand the fluid jet impingement and pipe whip loadings associated with postulated AFW pump discharge piping ruptures within the motor driven pump room.
The following pressure relief panels, watertight doors / relief panels, or vent openings are provided as shown at the following coordinates in Figure 1.2-3.
- a. Pressure relief panel and watertight door / relief panel at coordinates D-5
- b. Pressure relief panel and watertight door / relief panel at coordinates C-5 S
3.6-40 Revision 33 l 4/81
MIDLAND 1&2-FSAR
- c. Pressure relief panel at coordinates C-4 and watertight door / relief panel at coordinates C-5
(~') s
- d. Pressure relief panel and watertight dcor/ relief panel at coordinates D-4
- e. Watertight door / relief panel at coordinates C-5
- f. Vent openings connecting the Unit 1 and 2 pipeways through elevation 584'-0" at coordinates D-4 and D-5
- g. "ent openings connecting the Unit 1 tendon service shaft
. ;h the Unit 1 pipeway at coordinates D-5 and the Unit 2 tendon service shaft with the Unit 2 pipeway at coordinates D-3 Also, as shown in Figure 1.2-5, pressure relief panels are provided at coordinates F-3 and F-6. These open to the tendon service shaft on the north side of the auxiliary building and allow venting to the atmosphere.
All panels, watertight doors / relief panelc, and openings allow pressure venting of the compartment in which the break occurs. Also, the AFW pump room enclosures are designed as isolated compartments, able to withstand the combined effects of jet impingement, pipe whip, differential pressure, and steam-water
<- flooding. In most cases the equivalent static pressure,
('-w') determined from the pressurization transient, governs the design since jet impingement and pipe whip effects are local. The tendon service shaft in the south end of auxiliary building has been sealed as much as possible at elevation 614'-0" to prevent steam flooding of the auxiliary building in areas other than the pipeways and the elevation 584'-0" hallway connecting the pipeways. Watertight doors have been provided as shown in , Figure 1.2-3 at coordinates C-5, E-4, and E-5 for this same l reason. l As a result of the analysis of postulated auxiliary feedwater system piping breaks, the following system denign features have [ been provided:
- a. Two check valves are provided in each auxiliary feedwater line inside containment to prevent steam generator blowdown outside containment (refer to F.gures 3.6-14 and 3.6-15).
j
- b. Redundant high-low flow alarms are provided on the auxiliary feedwater pump Jiccharge to indicate the occurrence of a suction or discharge line break.
( A portion of the nonsafety-related AFW pump suction piping and l 14
,_ the crossover piping to the main feedwater system is physically .
l l ('# ) Revision 14 3.6-41 10/78 l l
MIDLAND 1&2-FSAR located within the turbine building and tunnel between the cuxiliary building and turbine building. No special protection is pcovided to preclude damage in the event of a tornado or noismic event. In the event of damage to this portion of the AFW ig tuction piping which impairs flow to the AFW pumps, the backup cervice water supply to the AFW pumps would be initiated. (See Subsection 10.4.9.2.3.) The piping tunnel, south wall of the
.tuxiliary building, and turbine building wing walls are all adequately designed to withstand the fluid jet impingement and pipe whip loadings associated with AFW pipe breaks. All penetrations in the south wall of the auxiliary building wall have been sealed to prevent steam flooding from the turbine building into the auxiliary building.
3.6.2.5.11.6 Environmental Evaluation When taking pump suction from the deaerating heater storage tank (at approximately 300F), the auxiliary feedwater system postulated breaks constitute the laraest source of steam flooding in the auxiliary building. The floor, walls, and ceiling of all compartments containing AFW piping have been designed and vented to withstand the differential pressurization associated with postulated AFW system breaks. Water and steamtight doors and penetrations, as vell as carefully placed rupture disks on HVAC penetrations, have been provided to minimize the effects of steam flooding from Subcompartment A (containing a high energy pipe break) into Subcompartment B (containing safety-related components). Level alarms have been located in each of the AFW pump rooms as well as the auxiliary building pipeway to aid in rapidly identifying the location of the break. The auxiliary building pipeway and hallway design is further discussed in Subsection 3.8.4.1.1. l33 All safety-related components located within the auxiliary building elevation 584'-0" hallway and pipeways required for post-accident conditions have been designed for operation with the worst environmental conditions postulated to which they will be subjected following a pipe break. The design envelope for components required for post-accident operation within the auxiliary building is provided in Section ' 3.11. All safety-related components within one of the AFW pump rooms are assumed o be rendered inoperative following a break postulated to occur within that pump room. 3.6.2.5.12 MI'&P System Injection Piping Outside Containment 3.6.2.5.12.1 General Description The injection portion of the MU&P system, as shown in Figures 9.1-32 and 9.3-34, consists of the discharge piping from the three makeup pumps designed to provide normal makeup and 3.6-42 Revision 33 4/81 lh
MIDLAND 1&2-FSAR.
=will not fail. The piping within the turbine building has not.
j\s,-)- been ' restrained against -the loadings associated with pipe breaks since the effects of pipe whip have been analyzed and: found to lxt
. acceptable.
The'offects on the-reactor-coolant system from a postulated main-f eedwater- line break are given in Subsection 15.2. P..
- 3. G. 2. 5.14. 4 Shutdown Procedures A postulated break at any location within the turbine building will constitute a controlled blowdown of.one OTSG. The reduction in OTSG- heat tr ansfer capability will result in an increase ' in ICS tenperature and-pressure and consequently a high RCS. pressure.
i reactor trip. This results in a turbine trip which is assumed to cause loss of offsite power. .Both the feedwater and: steam side of loth OTSGs-ara isolated due to the MSLIS. Auxiliary feedwater is supplied to both OTSGs. The RCS is. cooled by steam relief through the - atmospheric dump valves. 'Cubsection .15.2.8 further discusses feedwater line breaks. 2.6.2.5.14.5 Plant Design Features The structure housing the main feedwater system break exclusion ("% area is a physically separate structure which houses thi main (^,) foodwater isolation valves ann associated' main feedwater piping. Redundant feedwater isolation valves are provided insid - containment. There is no other safety-related equipmen located-inside the main feedwater isolation valve chamber. . At tue time , the structure was designed and built, there was no'NRC criteria to consider the environmental effects of a breck in the containment penetration break exclusion zone piping. Per NRC requirements, the feedwater valve chamber stru;ture has to be 9 designed for tornado missile protection. In 7.ddition, the 4 isolation valve in the no break zone has to be protected from any postulated turbine building pipe breaks (in any breaks postulated outside the exclusion area). The present isolation valve structure meets these two requirements and excludes the possibility of modification of this completed structure to a
, vented break exclusion zone enclosure.
Protection of the control room from the full effects of ary nipe , break of the nonseismic piping in the turbine buildinc is oiscussed in Subsection 3.G.2.5.10.5. The main feedwater isolation valve chambers are located approximately 90 feet east and west of the control room as shown on rigures 1.2-5 and 1.2-G. No breaks are postulated in the main feedwater piping in the isolation valve chamber since provisions of Subsection 3.G.2.1.1 are met. Revision 9 5/78 3.6-49
MIDLAND 1&2-FSAR 3.6.2.5.14.6 Environmental Evaluation Due to the large vent areas and remote location to safety-related ccmponents, subcompartmental pressurization resulting from main feedwater breaks within the turbine building is acceptable. The temperature transient on the south auxiliary building wall due to a main feedwater pipe break within the turbine building is less severe than that due to a main steam line break. The effects of the temperature transient on the auxiliary building wall due to a main steam line break have been analyzed and found not to damage the concrete. 3.6.2.5.15 Steam Supply Piping to the Radwaste Evaporators and Degasifiers 3.6.2.5.15.1 General Description 19 The steam supply piping to the radwaste evaporators and degasifiers is shown in Figures 10.4-26, 11.2-4, and 9.3-39. The l33 steam supply for the radwaste evaporators and degacifiers is provided from an auxiliary steam boiler system header shown in Figure 10.4-26 and physically located within the turbine building. This portion of the auxiliary steam system is designed 19 to provide heating steam to the radwaste evaporators and degasifiers as described in Subsection 9.3.7 and Section 11.2. The auxiliary steam supply piping system seismic and quality classification is indicated in Figures 10.4-26, 11.2-4, and 9.3-39. II 33 3.6.2.5.15.2 Evaluation and Identification of High Energy Portions The high energy portion of the steam supply piping to the radwaste evapcrators and degasifiers starts at the steam piping system within the turbine building and continues over the roof of the auxiliary building to the radwaste evaporators (OE-28 and 19 OE-29) physically located within the auxiliary building at elevation 659'-0" ( refer to Figures 3.6-93 and 3.6-94) and to the radwaste degasifiers (OM-99A&B) physically located within the cuxiliary building at elevation 634'-6" (refer to Figure 3.6-89). The portion of the auxiliary steam system piping within the turbine building was analyzed for the effects of pipe breaks on the south wall of the auxiliary building, similar to the main steam piping inside the turbine building (Subsection 3.6.2.5.10). The portion of the steam supply piping to the radwaste evaporators and degasifiers on the roof of and within the cuxiliary building has been analyzed for breaxs postulated at cvery tee, elbow, and fitting. 3.6-50 Revision 33 4/81
__ - - . . , , . , ~ . - . ... . , _. -- . MIDLAND 1&2-FSAR I , . l
- 3.6.2.5.15.3 Analysis of Postdlated Breaks 1
( Breaks postulated in'the radwaste evaporator and degasifier' steam' supply piping constitute a 4, 6,-or 10 inch secondary pipe break accident. The effects on the reactor coolant system from such. a 1 postulated break are enveloped by the wide _ spectrum of' main steam II line -breaks postulated amd analyzed in Subsections. 3;6.2.5.10 and l l 15.1.5. The'present design includes a pressure control valve l (0PV-2636) (Figure 9.3-39) operated by downstream pressure and 1 33 physically located within the turbine building to ensure that the- :
, pressure within the stema piping to the radwaste evaporators and 19 degasifiers on the auxiliary building roof and within the-l auxiliary building is never greater than 100 psig. Also within '
- the turbine building, a flow orifice (OFO-2635) (Figure 9.3-39) l33 has been provided to limit blowdown into the auxiliary'bu',1 ding in the event of a piping rupture within-the auxiliary building.
, The steam supply piping to the radwaste evaporators and' 19 L degasifiers has been analyzed for breaks postulated at every tee, elbow, and fitting. The blowdown thrust force at each break location has been conservatively calculated using the methodology i
of the BN-TOP-2 m cold w' ster model. 128 3.6.2.5.15.4 Shutdown Procedures
- A break at any of the postul'ated break locations in the steam II supply piping to the radwaste evaporators and degasifiers j constitutes a 4, 6, or 10 inch steam line accident. All of this.
- piping is seismic Category II and is nonsafety-related. A break i postulated on the downstream side of valve OPV-2636 I (Figure 9.3-39) would be detected by low evaporator pressure l 33 i (refer to Figures 11.2-4 and 9.3-39), low boron recovery system l degasifier pressure (refer to Figure 9.3-39A), and high upstream j steam flow (OFI-3066B). Isolation of the break would be i
accomplished by remote manual operation of the steam supply valves physically located within the~ turbine building. 3.6.2.5.15.5 Plant Design Features < 19 The portions of the steam supply piping to the radwaste i evaporators and degasifiers within the auxiliary building are physically remote from any safety-related components within the plant. Thus, this piping was not restrained from whipping. Postulated ruptures of portions of the radwaste steam supply
- piping within the turbine building were considered in the design
, of the south wall of the auxiliary building. However, because the blowdown thrust forces fo~r breaks postulated downstream of valve OPV-2636 (Figure 9.3-39) within the turbine building are so. 133 ) small (< 5.0 kips), the jet impingement and whipping loads are i enveloped by the postulated main steam line breaks as discussed 19 , I in Subsection 3.6.2.5.10. ' i O 3.6-50a Revision 33 4/81 i w- -ew-g-m.-y,-m w ear er- - v erw.w,, w . -re % w er*-re-uw ueN -W 'er e gwee w ww we' P-m *"= y=utu'" t T rg*w e g's-*t-w*-w'cgge vtirwV- e 7-e.ve. eeww w y e-ev y. ..,9 ew%.)m g-* 9 g - 3 r w g e. - w w.m y --- r - ug =-t-emg % g-y + es.acew
MIDLAND 1&2-FSAR The portion of the steam supply piping to the radwaste cvaporators and degasifiers on the auxiliary building roof will ba restrained against pipe whip because it passes beneath the n in steam line tornado missile shield in the vicinity of the cafety-related portion of the main steam piping (refer to 10"-0GBD-234 in Figures 3.6-101 and 3.6-97). 3.6.2.5.15.6 Environmental Evaluation The subcompartment pressure / temperature transient analysis p:rformed for a 26 inch main steam line break inside the turbine building, discussed in Subsection 3.6.2.5.10.3, envelopes any of the auxiliary steam line breaks postulated inside containment. , The column line F wall of the tornado missile shield on the tuxiliary building roof is open from approximately olevation 704'-0" to the centerline elevation of the main steam 19 piping and provides venting of the steel tornado missile shield from any breaks postulated in the radwaste steam supply piping b neath the missile shield. The balance of the steam supply piping to the radwaste evaporators and degasifiers on the cuxiliary building roof is cpen to the atmosphere. The steam piping to the radwaste evaporators and degasifiers is physically located in the north end of the auxiliary building above or with acccess to elevation 659'-0". Because the north wall of the auxiliary building (above elevation 634'-6") is a sheet metal steel structure, no venting is provided. This piping is isolated by watertight doors and walls from all safety-related areas within the plant. 3.6.2.5.16 Other High Energy Systems Systems or Portions of Systems Not Subject to Analysis Systems or portions of systems which are located remote to any safety-related components within the plant are not analyzed for pipe breaks which could affect plant safety. These systems include all high energy systems in the yard buildings remote from the containments. Also included are the high energy portions, within the turbine building, of the following systems which are also located remote.to any safety-related equipment:
- 1. Main feedwater and condensate system (see Subsection 3.6.2.5.14)
- 2. Portions of the auxiliary feedwater system (see Subsection 3.6.2.5.11)
- 3. Turbine extraction system (see Figures 10.2-1 through 10.2-4)
Revision 19 3.6-50b 3/79
, MIDLAND 1&2-FSAR
- 4. Condensate tiernineralizer system (see Figures 10.4-4 3
through 10.4-7)
- 5. Auxiliary steam boiler system (see Figures 10.4-26 l33 and 10.4-27)
- 6. Main stea:n piping downstream of the turbine stop valves (see Figures 10.3-1 through 10.3-4) 16 3.6.2.6 Summary of Analyses for Moderate Energy Piping Systems Moderate energy systems are addressed for flooding and spray-effects in Section 3.4. Worst case radiological consequences are addressed in Chapter 15.
f l, O Revision 33 3.6-50c 4/81
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=
4 _
+4 MIDLAND 1&2-FSAR O
l I l l l THIS PAGE INTENTIONALLY LEFT BLANK Revision 19 3/79 3.6-50d
MIDLAND 1&2-FSAR 3.7 , SEISMIC DESIGN A
> 4 V 3.7.1 SEISMIC INPUT 3.7.1.1 Design Response Spectra The site horizontal design response spectra are shown in Figure 3.7-1 for the operating basis earthquake (OBE) and Figure 3.7-2 for the safe shutdown earthquake (SSE). Seismic responses used for design in the period range from 0.2 to 0.6 seconds and are increased by 50% from the. values given in l33 Figures 3.7-1 and 3.7-2 to compensate for differences between the site design response spectra (Housner-developed) and Newmark-developed response spectra. The vertical design response spectra are defined by multiplying the horizan+'l site design response spectra by two-thirds. The site design response spectra are applied at the various foundation elevations of Seismic Category I structures.
The derivation of these site design response spectra is discussed in Subsection 2.5.2. Compliance with Regulatory Guide 1.60 is discussed in Appendix 3A. The term " safe shutdown earthquake" is synonymous with the terms
" maximum earthquake" er " design basis earthquake." The term
" operating basis earthquake" is synonymous with the terms "one-half safe shutdown earthquake" or " design earthquake."
\ 3.7.1.2 Design Time-History 15 A modified Taft N21E, 1,52 record is the basis for time-history analyses. Comparisons of the site design spectra with the free field spectra aP. foundation levels of Seismic Category I structures, derived from this time-history for the SSE for the 115 damping values shown in Figures 3.7-1 and 3.7-2, are shown in Figures 3.7-3 to 3.7-8. The response spectra derived from the 15 time-history are calculated at the frequencies specified in Section 2.5.1 of BC-TOP-4-A.
The comparisons show that the response spectra derived from the time-history envelop the site design response spectra for the 115 damping values used in analyser.. Similar comparisons for the OBE and the vertical OBE and SSE are identical except for constant scale factors applied throughout the frequency range of interest.
- 3.7.1.3 Critical Damping Values The damping values (percent of critical damping) used for Seismic category I structures, systems, and components are provided in the discussion of compliance with Regulatory Guide 1.61 in Appendix 3A, In the consideration of damping value of soil, the radiation damping values are calculated in accordance with
() 3.7-1 Revision 33 4/81
MIDLAND 1&2-FSAR Table 3-2 of BC-TOP-4-A. The material (hysteretic) damping values are normally small in comparison with radiation damping. 33 Therefore, the analysis was performed without using the foundation material damping. 3.7.1.4 Supporting Media For Seismic Category I Structures A tabulation of Seismic Category I structures and the foundation cmbedment depth, depth of soil over bedrock, soil layering characteristics, effective width of the foundation, total structure height, soil shear wave velocity, soil shear modulus, l 32 cnd soil density is provided for each Seismic Category I structure in Table 3.7-1. 3.7.2 SEISMIC SYSTEM ANALYSIS 3.7.2.1 Seismic Analysis Methods Seismic Category I systems are analyzed by use of the modal cuperposition method. Design system responses are calculated by use of the above technique in conjunction with the site design response spectra. The response spectra applicable at locations in a system are calculated by use of the above technique in conjunction with the design time-history. The lumped mass model l 15 used for analysis of the containment is shown in Figure 3.7-9 and for the auxiliary building in Figures 3.7-10 and 3.7-11. The model used for analysis of the service water pump structure is 24 ahown in Figure 3.7-68. These system models include the impedance functions applicable to a uniform foundation medium specified in Table 3-2 of BC-TOP-4-A in order to consider the 33 effects of the foundation medium in the seismic analyses. Soil-structure interaction is included as described in Subsection 3.7.2.4. The models selected for analysis are considered to be composed of an adequate number of dynamic degrees of freedom (DDOF) because the number of DDOF is based upon seismic system 15 responses approaching asymptotic values with increases in the number of DDOF. The response analyces consider all modes cxtracted from the model with frequencies less than 33 cps. Maximum relative seismic displacements are considered in accordance with the techniques specified in Section 5.3 of l 19 BC-TOP-4-A and Section 3D.4 of Appendix 3D. l 33 i If significant, loadings, such as those due to hydrodynamic effects, are considered in the seismic system analysi,. Tests or other empirical methods are not used in lieu of analysis for Seismic Category I systems. 3.7-2 Revision 33 O 4/81
MIDLAND.1&2-FSAR Computer programs used in the seismic analysis are the following: O s'~'f -Spectra Modal Analysis of Plane Frames Spectral Response of. Plane Frames Time-History Analysis l15 Response Spectra Composite Damping for Soil-Structure Systems Bechtel Structural Analysis Program l24 Verification for these programs is presented in Appendix 3C. 3.7.2.2 Natural Frequencies and Response Loads Table 3.7-2 is a tabulation of natural frequencies below 33 cps calculated for the containment and the auxiliary building. Figures 3.7-12 to 3.7-26 show design responses and the first three eigenvectors for the east-west and vertical directions determined from the seismic analyses of the containment. Figures 3.7-27 to 3.7-32 show design ~ response spectra for the east-west and vertical directions at cri.tical major Seismic Category I equipment support elevations determined from the seismic analyses of the containment. Figures 3.7-33 to 3.7-47 show design responses and the first three eigenvectors for the east-west and vertical directions determined from the seismic analyses of the auxiliary building. Figures 3.7-48 to 3.7-53 show design response spectra for the east-west and vertical [/) s-directions at critical major Seismic Category I equipment support elevat i ons determined from the seismic analyses of the auxiliary building. 3.7.2.3 Procedure Used for Modeling Major Seismic Categcry I structures considered in conjunction with foundation media are defined as " seismic systems." Seicnic systems are modeled by use of the following criteria:
- a. Dynamic degrees of freedom (DDOF) are located at elevations of major structural discontinuities.
Examples of these discontinuities include floor elevations or elevations of significant building section property changes.
~
- b. DDOF are located at elevations of mass concentrations.
Examples of these concentrations include points of support for the nuclear steam supply system and equipment in the containment or the auxiliary building crane.
- c. Additional DDOF are located at intermediate elevations to ensure a mathematically stable model and in order to define a sufficient number of modes for use in further analysis.
[ 'ss evision 33 3.7-3 4/81 l l
.- . . = . - .. - -- - . . . - . --.-. - - . . . _. - - . - - - .
MIDLAND 1&2-FSAR In the seismic modeling, the procedures used for the subsystem l3 ll 6: coupling are in accordance with Section 3.2 of BC-TOP-4-A. An i 15 equipment, component, or system is usually lumped into the supporting structure mass if its estimated mass is less than 3 one-tentn of tnat of the supporting mass or, for supporting structures having continuous mass distributions, 0.03 of the d fundamental mode ef fect ive mass. Lumped mass models as s hown in Figures 3.7-9, 3.7-10, 3.7-11, and I 3.7-68 are used. These models are less complex than detailed thr e-dimensional models. Torsional effects of eccentric masses are considered in the structural design as stated in 32 Subsection 3.7.2.11. Also, the effects of multiple components of input motion are considered in the system design rather than the s:2ismic analysis as stated in Subsection 3.7.2.6. t 3.7.2.4 Soil-Structure Interaction l 15 The effect of soil-structure interaction is taken into account by coupling the structural model with the foundation media. The lumped parameter representation, which used impedances to represent the dynamic effects of the soil, was employed in the formation of analytical models. The impedance functions are represented by the equivalent spring stiffnesses and radiation damping coefficients as specified in Table 3-2 of BC-TOP-4-A. A nominal soil dynamic modulus of elasticity of 22,000 ksf and a Poisson's ratio of 0.42 were used as uniform foundation media properties to compute the soil impedanca function in the analyses. These soil dynamic properties are based upon field explorations and laboratory testing with adjustment for soil strain dependency due to free field surface accelerations of the range postulated at the site, as described in Subsection 2.5.4.7. Table 3.7-1 provides the extent of embedment, the depth of soil i over bedrock, and tne extent of layering of the soil stratum typical for all structures. The site characteristics are marked by an absence ot slanted layering. The ratio of structure width to depth of foundation media over bedrock is in the range of one-half for al] Seismic Category I structures and provides l 15 adequate depth tor the impedance function approach. The site arrangement of the Seitnic Category I structures is such that only 30% of the containment exterior wall line, 70% of the cuxiliary building exterior wall line, and 50% of the service water pump structure exterior wall line are embedded in fill materials placed over natural grade that are much less ' tiff than the supporting media. The small ratio of structure emb+dment d pth to structure width for all Seismic Category I structures further reduces the influence of the embedment ef fect es discussed in Appendix H of BC-TOP A. The margin of frequency brondening in the response spectra generation and other conservative approaches throughout the entire seismic analysis provide adequate consider 5 tion for the minor embedment effect at this site. ; 3.7-4 Revision 32 1/81
MIDLAND 1&2-FSAR Seismic Category I structures were' analyzed indepandently:without j coupling with other. structures in the soil' structure interaction
-(]/, analyses. This is conservative for the containment and the auxiliary building where the building masses are of about the same order of magnitude. Other Seismic category I-structures are physically separated by sufficient distance so that through-soil interaction will.be insignificant.- -
3.7.2.5 Development of Floor Response Spectra The floor response spectra for three components of motion,- two horizontal and one vertical, are computed from the time-history motion at various floors or other locations of interest. These motions are obtained from the time-history analysis of the structure as described in Subsection 3.7.2.1 for the normal soil modulus specified in Subsection 2.5.4.7. -The floor spectra are 1 computed at 49 frequencies as tabulated in Table 5-1 ef '3 BC-TOP-4-A as well as the structural frequencies up to 33' cps. The spectra are smoothed to provide a curve which envelops all of the computed values. The zero period acceleration (ZPA) for the floor response spectra are based on the spectra response analysis ZPA for the nominal soil case specified in Subsection 2.5.4.7. 3.7.2.6 Three Components of Earthquake Motion f This is addressed in Regulatory Guide 1.92. Compliance with ( Regulatory Guide 1.92 is discussed in Appendix 3A. L 3.7.2.7 Combination of Modal Responses This is adcressed in Regulatory Guide 1.92. Compliance with Regulatory Guide 1.92 is discussed in Appendix 3A. Additional material for the piping design is addressed in Appendix 3D. 33 3.7.2.8 Int'eraction of Nonseismic Category I Structures With Seismic Category I Structures The interfaces between seismic Category I'and nonseismic Category I structures and plant equipment are cesigned for the seismic responses calculated for these structures. The seismic responses are combined in accordance with the techniques specified in Sections 4.3 and 5.3 cf BC-TOP-4-A. l32 The collapse of any isolated nonseim mic Category I structure will not impair the safety function of Seismic Category I structures or components. Nonseismic Category I structures whose . failure could impair the safety function of Seismic Category ! structures or components are analyzed and designed to prevent failure under SSE conditions. These structures are designed in accordance with 8 the applicable codes and standards for normal conditions and are (~%
7-5 Revision 33 4/81
MIDLAND 1&2-FSAR checked for the SSE load in accordance with the following procedure: The structure is idealized using a lumped mass model. Dynamic degrees of freedom are located at elevations of major structural 9 discontinuities and mass concentrations. The response spectrum technique as discussed in BC-TOP-4-A Section 4.2 is used witP. cite design response spectra for SSE as discussed in Subs 9ction 3.7.1.1, as input to compute the structural responses. Adjacent non-Seismic Category I steel structures are analyzed l 32 using a 5% damping value. The structures are then checked for the loading combination with unit load factors of dead load, operating live load, and seismic loads as obtained from the dynamic analysis. g Allowable strusses for concrete structures are limited to the ultimate Icoisting capacity as calculated from the ACI 318-71 l 32 code. 8 Allowable stresses for steel structures are in general limited to 1.5 times the AISC specification allowables provided they do not l 32 exceed 0.9 times the mininum specified yield stress. Limited local yielding is permissible when demonstrated that overall 8 structural integrity is maintained. 3.7.2.9 Effects of Parameter Variations on Floor Response Spectra The procedures used 'o develop floor response spectra are described in Subsection 3.7.2.5. To account for the uncertainties in the structural frequencies (as a result of uncertainties in such paraneters as caterial nroperties of the structure and soil, damping, values, and soi. structure 33 interaction techniques), the respc se spectra are computed based on the same nominal nodel properties for both the operating basis earthquake and the safe shutdown earthquake. The peaks are broadened by +15%, as recommended by Regulatory Guide 1.122,. 3.7.2.10 Use of Constant Vertical Static Factors Constant vertical load factors are not used for the design o f Seismic Category I systems. 3.7.2.11 Method Used to Account for Torsional Effects Seismic Category I structures are designed to minimize eccentricities that could cause significant torsional or coupled hcrizontal motions. Torsional loadings are considered in the design of Seismic Category I structures by the application of the design horizontal seismic loadings obtained from the decoupled ceismic system analyses a' an eccentricity no less than the 3.7-6 O Revision 33 4/81
MIDLAND 1&2-FSAR greater of the calculated eccentricity or 5% of the width of the [~) structure normal to the direction of the input motion under consideration. 3.7.2.12 Comparisons of Responses All structures were analyzed using the response spectrum method. The time-history method with the modified Taft record, discussed l15 in Subsection 3.7.1.2, was used in the development of floor response spectra. A comparison of maximum structural response accelerations calculated using the time-history analysis and l15 response spectrum method for the containment and the auxiliary building is presented in Table 3.7-3. 3.7.2.13 Methods of Seismic Analysis of Seismic Category I Dams The Midland plant does not utilize Seismic Category I dams. 3.7.2.14 Determination of Seismic Category I Structure Overturning Moments Structural overturning is considered in accordance wi'.h the procedures specified in Section 4.4.1 of BC-TOP-4-A. l'hes e procedures consider three components of input motion and provide 7s a conservative consideration of vertical and lateral seismic ( ) forces. 3.7.2.15 Analysis Procedure for Damping Composite modal damping due to different elements of a model having different damping characteristics is considered in accordance with the procedures specified in Sections 3.2 and 3.3 of BC-TOP-4-A except that damping values are as specified in Sr.bsection 3.7.1.3. 3.7.3 SEISMIC SUBSYSTEM ANALYSIS In the present discussion the term " seismic subsystem" refers to Seismic Category I structures, systems, and components that are not considered in conjunction with foundation media in forming a soil-structure interaction model for seismic analysis or not 1 designated as " seismic systems" in Subsection 3.7.2. Unless otherwise stated, the scope of the term "NSSS subsystems" includes all items cove red in the NSSS scope of supply and supplied by the NSSS vendor, and is not limited to the reactor coolant system. s 3.7-7 Revision 33 4/81
3 MIDLAND 1&2-FSAR 3.7.3.1 Seismic Analysis Methods 3.7.3.1.1 Subsystems Other Than NSSS ,, Saismic Category I subsystems other than piping are analyzed by use of the response spectrum method as discussed in Section 5.3.1 of BC-TOP-4-A, except that individual modal responses for modes with frequencies below 33 cps may be combined by use of their absolute values. Alternatively, seismic responses may be enlculated using the peak value of the appropriate response tpectra. The seismic analysis of Seismic Category I piping is p2rformed in accordance with Appendix 3D. l19 3.7.3.1.2 NSSS Seismic Subsystems Major reactor coolant loop components (reactor vessel, steam garerators, piping, pumps, and pressurizer) are analyzed using a thlae-dimensional model as described below. Detailed stress ana.yses for the individual components, including the reactor pressure vessel, piping, pumps, steam generators, and pressurizer, are performed for the design conditions. A three-dimensional seismic analysis is performed on the reactor coolant loop to determine piping and component nozzle seismic stresses. An idealized mathematical model of a single loop consisting of lumped masses connected by elastic members is used. The loop includes the reactor, steam generator, pressurizer, two coolant pumps with associated piping, and the secondary shield wall with attached coolant system re traints or supports. Using the elastic properties of the piping and components, a reduced flexibility matrix is generated. All flexibility calculations l32 include the effects of torsional, shearing, bending, and axial deformations as well as changes in flexibility due to curved m:mbers and internal pressure. Flexibility factors are calculated in accordance with ASME Section III. All lumped masses include the weight of the contained water. The offect of primary system pressurization on stiffness is accounted for in accordance with ASME Section III; i.e., elbow stiffness due to pressurization. Nonlinear responses are e/aluated for gapped pipe whip restraints only. The seismic analysis uses the response spectra and the normal mode approach. Natural frequencies and mode shapes are calculated by the modified Jacobi technique or the tridiagonal mathod, depending on the size of the dynamic matrix. The mathematical model is shown in Figures 3.7-54 through 3.7-63. D2 tails of the seismic analysis of other components are discussed in Subsection 3.7.3.3.2. 3.7-8 Revision 32 O 1/81
I MIDLAND 1&2-FSAR f-(- 3.7.3.8 Analytical Procedures for Piping Systems
\
_{
\-- 3.7.3.8.1 Subsystems Other Than NSSS Section 3D.2 of Appendix 3D describes the design' criteria and Lthe 19 analy tical techniques - applicable - to piping . systems. Appendix 3D also discusses relat i .ve displacements between piping and support points.
~
3.7.3.8.2 NSSS Seismic Subsystems The basic analytical techniques.for piping are the'same as those described . in Subsection 3.7.3.1.2. Care is taken with the spacing of lumped. mass points when piping analysis is' performed so-that the loads are evenly distributed. The primary piping is ircluded in the reactor coolant system model and modeled to one common input point; therefore, only one seismic input at all anchor points is considered within the model. 3.7.3.9 Multiply Supported cquipment and Components' with Distinct Inputs 3.7.3.9.1 Subsystems Other Than NSSS Section 5.3 of BC-TOP-4-A describes the approaches used for multiply supported subsystems. Section 3D.4 of App.endix 3D ' 19 C,_D / discusses the methods for piping subsystems. i 3.7.3.9.2 NSSS Seismic Subsystems There are no NSSS subsystems which ar^ considered as multiply r supported. See Subsections 3.7.3.1.2 and 3.7.3.8.2 forL
- i. discussion of the analysis methods used.
I 3.7.3.10 Use of Constant Vertical Static Factors i 3.7.3.10.1 Subsystems Otner Than NSSS Constant vertical load factors are applied only to subsystems that can be categorized as rigid or as noted in Subsection 3.7.3.5.1. 1 t 3.7.3.19.2 NSSS Seismic Subsystems i This method is not used except in unusual cases. When it is used, it is applied as follows: The iundamental f requency of the subsystem is shown to be greater f"$s than 33 cps in the vertical direction. If this is true, the Revision 19' 3.7- 13 3/79
MIDLAND 1&2-FSAR vertical acceleration of the support is applied as a constant acceleration to the component to oe analyzed. In other words, no dynamic amplification is assumed (e.g., mass of component x acceleration of support). The results of this analysis are combined with the other directions as defined in Subsection 3.7.3.6. 3.7.3.11 Torsional Effects of Eccentric Masses 3.7.3.11.1 Subsystems Other Than NSSS If significant, torsional effects such as valves or other eccentric masses are taken into account in the seismic piping analysis by the techniques discussed in Section 3D.2 of 19 Appendix 3D. 3.7.3.11.2 NSSS Seismic Subsystems All eccentric masses including valves and valve operators are included in the mathematical models. 3.7.3.12 Seismic Category I Buried Piping Systems, Underground 10 Cable Systems, and Tunnels The general techniques used for seismic analysis of Seismic l 32 Category I buried piping systems, underground cable systems, and tunnels are described in Section 6.0 of BC-TOP-4-A. The effect 30 of differential building movements on the seismic analysis of piping is addressed in Section 3.D.4 cf Appendix 3D. The Seismic l 32 Category I buried piping, underground cable systems, and tunnels are designed to remain functional when subjected to seismic loads 30 combined with other applicable loadings. 3.7.3.13 Interaction of Other Piping with Seismic Category I Piping Appendix 3D, Subsection 3.D.3.4, describes the techniques used to l30 consider the interaction of Seismic Category I piping with nonseismic Category I piping. 3.7.3.14 Seismic Analysis for Reactor Internals The reactor internals and fuel assemblies have been evaluated for their ability to withstand the ef fects of a loss-of-coolant accident ( LOCA ) , blowdown, operating basis earthquake (OBE), safe shutdown earthquake (SSE), and the simultaneous occurrence of the SSE and LOCA. Analysis of the reactor internals and the methods sed are described in Subsection 3.9.2.5. l32 Revision 33 3.7-14
MIDLAND 1&2-FSAR l l Equation-(a) assures that the containment has the capacity.to g f-w). withstand pressure loadings at least 50% greater than those calculated for the postulated loss-of-coolant accident alone. Equation (b) assures that the containment has the capacity to withstand loadings at 25% greater than those calculated for the postulated loss-of-coolant accident with a coincident OBE. Equation (c) assures that the containment has the capacity to withstand loadings 25% greater than those calculated for the OBE coincident with rupture of any attached piping. Equation (d) assures that the containment has the capacity to withstand the DBT loading. Equations (e) and ( f) assure that the . containment has the capacity to withstand either the postulated loss-of-coolant accident or the rupture of any attached piping coincident with the SSE. Equation (g) assures that the containment has the capacity to withstend the PMF loading. 3.8.1.4 Design and Analysis Procedure Containment loadings are categorized as either global or local. [~N The effects of global loadings are evaluated using axisymmetric
\s- models of the shell. The effects of local loadings are evaluated using the properties of the affected local areas in conjunction with an appropriate analysis technique. For the containment wall and dome, the value of fc given in Table 3.5-4 is used in all 8 analyses.
3.8.1.4.1 Analysis of Loads i l The FINEL program is used to analyze the effects of axisymmetric global load combinations including the aonlinear transient temperature gradient on the containment shell. This program can consider the cracking of concrete, yield of reinforcing steel, l and the inability of soil to resist tension. See }33 Subsection 3.8.1.4.8 for a description of the FINEL program. I i j The FINEL model of the containment shell is shown in Figures 3.8-25 and 3.8-26. The ASHSD program is used to analyze the effects of nonaxisymmetric global loadings on the containment shell. The ASHSD model of the containment is shown in Figure 3.8-27. Sec 33 Subsection 3.8.1.4.8 for a description of the ASHSD program. i l "S Revision 33 3.8-7 4/81 l
. - -- - - - ,. -. . __ - . . ~ , - - - , - . .,
MIDLAND 1&2-FSAR 1he ef fects of local loadings or discontinuities are considered in accordance with one of the following techniques depending upon the nature of the local loading or discontinuity:
- a. Large penetrations are analyzed in accordance with the methods specified in Subsection 3.8.1.4.7.
- b. She butt.resses and other tendon anchorage regions are treated in accordance with Bechtel Topical Reports BC-TOP-7-A and BC-TOP-8, Rev. 1.
- c. Small penetrations are analyzed in accordance with Part II of BC-TOP-1, Eev. 1.
- d. Brackets are analyzed in accordance with Part III of BC-TOP-1, Rev. 1.
- e. Pipe restraint embedments are analyzed in accordance with the applicable pertions of BC-TOP-9-A and the KSHEL program. See Subsection 3.8.1.4.8 for a description of 33 the KSHEL program.
- f. Additional reinforcing steel around small penetrations and embedments is designed by classical methods.
- g. P.adial tension due to curvature in post-tensioning tendons in the wall and dome is evaluated as explained 8
in Subsection 4.5.9 of BC-TOP-5A and illustrated in exampic DE-2 3.8.1.4.2 Boundary Conditio:ts The shell analyses for global loadings use the finite element technique. The models include the foundation media about 100 feet below the base slab and about the same distance in the radial direction measured from the edge of the base slab. Total fixity is specified at the bottom row of soil nodes and zero radial movement is specified for soil nodes along the vertical boundary lines. 3.8.1.4.3 Effects of Expected Variation in Physical Material Properties Wherever critical, the bounding values of physical properties auch as soil modulus, the modulus of clasticity, and Poisson's ratio of concrete are considered in the analyses to develop design internal loadings. Revision 33 3.8-8 4/81
I l MIDLAND 1&2-FSAR 3.8.1.4.4 Analysis of Creep, Shrinkage, and crac. king of Concrete-To consider creap deformations, the modulus of elasticity of cencrete under sustained loads such as dead load and prestress is differentiated from the modulus of elasticity of concrete under transient loads such as internal accident pressure and earthquake ! loads. The following equation is used to include the effect of creep and shrinkage: Ucs " Uci X gs+Ei (l) # { where E s and Eci are sustained and instantaneous moduli of elasticStyofconcreterespectively. Es and Ei are austained and
- instantaneous strains in concrete, respectively, for all l
4 ( l 4 j' I t i i l O Revision 33 3.8-8a 4/81 i 4
. . . , ,.._,-.,_.,.-..,,,--,-,.m . .m _s. .,,., ,,_.__ % ,, ,.,__.,y. <..., _ _ m,,...,,,y,,,,-.,,,m,.,-.,.,,..~,.vm,,-, ,, , . _ . _ . - - -
a w _ _ _.A_. . .- _ 4 _ __ -_ MIDLAND 152-FSAR O l I THIS PAGE INTENTIONALLY LEFT BLANK l l l Revision 8 3.8-8b 4/78 1
MIDLAND 1&2-FSAR- [ long-term loads, such as thermal. load, dead load, and prestress.
\ Figure 3.8-28 shows the relationship of strain versus duration of loading. When the effect of creep and shrinkage is included, the value of sustained modulus of elasticity of concrete is about one-half the value of instantaneous modulus of elasticity.
A minimum of 0.25% reinforcing is provided in two perpendicular directions on the exterior faces of the wall and dome for proper crack control. Since, in' general,.there is no tensile stress due to temperature on the inside faces of the containment, reinforcing is not required at the inside face for purposes of crack control. 3.8.1.4.5 Analysis of Membrane Shear Subsection 3.8.1.5.1.4 describes the criteria for treatment of tangential membrane shear. 3.8.1.4.6 Design of Steel Liner System The steel liner system and its anchors are designed in accordance with Part I of BC-TOP-1, Rev. 1, except for the following:
- a. The nominal anchor spacing in the cylindrical portion is (j)
\ 14 inches rather than the 15 inches referenced in BC-TOP-1, Rev. 1.
1 l b. The liner plate material is ASTM A 285 rather than ASTM A 442 as referenced in BC-TOP-1, Rev. 1. l l c. The design pressures and temperatures are those applicable to the Midland plant rather than the 55 psig and 280F referenced in BC-TOP-1, Rev. 1. These exceptions have minimal impact upon the design of the steel j liner system. T 3.8.1.4.7 Analysis of Large Thickened Penetrations I Large penetrations are categorized as having an inside diameter greater than or equal to 2-1/2 times the containment wall ! thickness. The opening diameter is determined by functional requirements. The increase in wall thickness and the extent of the thickened wall are determined by the magnitude of the forces and moments around the opening and the allowable stress levels for the concrete and reinforcing steel, i h V l I 3.8-9 l l
MIDLAND 1&2-FSAR The points on the outermost boundaries of the analytical model are located at a sufficient distance from the opening so that the b havior of the model along the boundary is compatible with that of the shell. Experience gained from past analyses has shown that boundary lines extending two penetration diameters beyond the edge of the opening provided sufficient model dimensions to catisfy compatibility requirements. To reduce the size of the analytical model, toundary lines follow the axes of symmetry of the penetration opening whenever possible. Boundary conditions are imposed on the analytical model by cpecifying nodal forces and/or displacements obtained from the global analyses. The equipment hatch is the only large thickened penetration in the containment wall. The region of the shc11 adjacent to the cquipment he tch is analyzed by the Bechtel computer program SAP 1.9. 7he solid elcment is used for the analysis of the equipment hatch. Four layers of solid elements of varying thickness are u;ed to describe the structure. To obtain acceptable bending b;havior it is necessary to keep the relative width-to-thickness ratios of these elements below approximately 10/1 or 12/t. Truss elements are used to model the tendons. Figure 3.8-29 shows the boundaries and general configuration of the analytical model for the equipment hatch analyzed by the SAP prog ram. See Subsection 3.8.1.4.8 for a description of the SAP 33 program. Loadings applied to the equipment hatch model include the following: Drad Load (D) and Seismic Loads (E)- The weight of the dome and wall above the upper bounuary is applied as nodal point forces or element pressure. In addition, the weight of the structure within the confines of the model boundaries is considured by cpecifying the mass density of the material and the gravitational acceleration. Seismic loadings are considered in the same manner. Prestressing Loads (F) - Vertical and horizontal prestressing forces, including curvature effects, are applied as nodal point forces. Thermal Gradients (T and T ) - Analysis of the penetration region for a bilinear temperature distribution (i.e., composed of two linear portions) through the thickness is included in the analysis. Pressure (P ) - Internal press 9re is specified as element pressure acting outwcrd and applied normal to the inside surface Revision 33 3.8-10 4/81
MIDLAUD 162-FSAR as the percentage of flat and elongated particles. Maximum a2.owable flat and elongated particles in any sample shall not h'N exceed 15%. For work after 4/1/77 the coarse aggregate is tested in accordance with CRD-C 119, Methods of Test for Flat and Elongated Particles in Coarse Aggregate, and shall contain less than 15% by weight, flat and elongated particles. A ratio of three to one (length to width) is employed in. determining flat and elongated particles. The maximum size of coarse aggregate is in accordance with ACI 318-63 Section 403 (b) and Section 804 (a) (for work prior to 6/1/73) or ACI 318-71 Section 3.3.2 (for work after 6/1/73) . 3.8.1.6.1.1.3 Mixing Water The mixing water does not contain more than 250 ppm of chlorides as Cl as determined by ASTM D 512, Chloride Ion in Industrial l28 Water and Industrial Waste Water. For work prior to 4/1/77 a comparison of the mixing water with
- distilled water for time of setting and compressive strength is made in accordance with AASHTO T 131, Time of Setting of Hydraulic Cement by Vicat Needle, or AASHTO T 154, Time of Setting of Hydraulic Cement by Gillmore Needle, and in accordanco
- with AASHTO T 106, compressive Strength of Hydraulic Cement i
Mortars. gJ For work after 4/1/77 a comparison of the mixing water properties is made with distilled water by performing the following tests:
- a. Soundness, in accordance with ASTM C 151-74, Autoclave Expansion of Portland Cement, obtained for the mixing water shall not yield an increase in length of more than 0.10% above those obtained for distilled water.
- b. Time of setting results, in acccrdance with ASTM C 191-74, Time of Setting of Hydraulic Cement by Vicat Needle, obtained for the mixing water shall be within 110 minutes for initial setting time and *1 hour for final setting time of those obtained for distilled water. The penetration of the 1mm readle is determined every 10 minutes instead of every 15 minutes as specified in ASTM C 191 Section 5.2.
- c. Compressive strength results, in accordance with ASTM C 109-75, Compressive Strength of Hydraulic Cement Mortars, obtained for the mixing water shall not be lower than 90% of those obtained for dietilled water.
Revision 28 3.8-21 5/80
MIDLAND 1&2-FSAR 3.8.1.6.1.1.4 Admixtures The concrete contains an air entraining agent, a water reducing cgent, and may contain a pozzolan; no other admixtures are permitted. Air entraining agents conform to the requirements of ASTM C 260-66, or ASTM C 260-69, Standard Specification for Air Entraining Admixtures for Concrete. The water reducing and retarding agent conforms to ASTM C 494-68 os: ASTM C 494-71, Standard Specification for Chemical Admixtures fur Concrete, Type A or Type D. Pozzolans conform to the requirements of ASTM C 618-68T or ASTM C 618-72, Standard Specification for Fly Ash and Raw or 133 Calcined Natural Pozzolans for Use in Portland Cement Concrete, and are sampled and tested in accordance with ASTM C 311-68, Methods of Sampling and Testing Fly Ash. Approximately 15% by weight of pozzolan will be used to replace cement in the concrete mixes. 3.8.1.6.1.1.5 Grout The materials for cement grout used for general grouting purposes chall conform to the foregoing requirements for materials for concrete. 3.8.1.6.1.1.6 Storing Materials Aggregate is stored and maintained in such a manner as to avoid the inclusion of any foreign materials in the concrete. No muddy or oil leaking traction equipment is allowed to operate on the storage piles. The placing of the material in storage and its removal therefrom is done in such a manner as to maintain the uniformity of the grading. All fine aggregate (sand) is required to have a uniform and stable moisture content of not more than 7% by weight (oven dry weight basis) when delivered to the batching plant bins. The stockpiles at the point of suppli arc provided with suitable drainage facilities arranged in such a manner as to give a minimum of 24 hours drainage prior to use of the aggregate. Aggregate is stockpiled at the batch plant site before the start of concrete operations in a sufficient quantity to permit continuous placement of concrete. Fine and coarse
~
aggregate storage piles are built and maintained to prevent regregation and excessive breakage. Suitable bulkheads or spaces are provided betwecn specific size groups of aggregate to preclude mixing of the different size groups; the bottom of ctorage areas intended to be used as the primary or a'ctive etorane (these are the areas from which the aggregate bins will normally be charged) are paved. Revision 33 3.8-22 4/81
1 MIDLAND 1&2-FSAR 1 of testing is shown in Table 3.8-18; the temperature of cemen*, delivered to the jobsite does not exceed 150F. ('~N Aggregate is tested f conformance to ASTM C 33 with the tests and frequencies spec fled in Table 3.8-18. . Mixing water is-tested tor conformance to the requirements of Subsection 3.8.1.5 1.1.3. The frequency of testing is as shown in Table 3:8-1A The manufacturer or shipper of admixtures is required to submit an infrared spectrophatometry analysis on each shipment. A certificate of compliance for each delivery is also required. Fly ash is sampled and tested to the requirements of- ASTM C 618 at the frequency shown in Table 3.8-18. Tests for cement alkalies are not required. i Concrete is sampled in accordance with ASTM C 172, Sampling Fresh Concrete, and tested for slump in accordance with ASTM C 143, Slump of Portland Cement Concrete, for compliance with specified requirements. The frequency of slump testing is as shown in Table 3.8-18. Concrete temperature and air content are measured for compliance to the requirements of Subsections 3.S.1.6.1.2.2 and 3.8.1.6.1.2.1. Air content is determined in accordance with 18
~s ASTM C 231-74, Air Content of Freshly Mixed Concrete by the Pressure Method. Unit weight of concrete iE determined in accordance with ASTM C 138-74. Test frequencies are as shown in lI i
Table 3.8-18. Compressive strength cylinders are cast from representative samples taken from the discharge of the batch plant stationary mixer or, when applicable, from the chute of the concrete truck mixers. Cylinder sampling procedures are in accordance with 18 ASTM C 172, Sampling Fresh' Concrete. Slump, air content, unit i weight, and temperature of the concrete are recorded when l cylinders are cast. Cylinders are madu, cured, and tested in accordance with ASTM C 31 and ASTM C 39 for establishing conformance to required strength. The frequency of testing is'as shown in Table 3.8-18. i Concrete cylinders are maintained at a temperature of 60 to SOF prior to stripping,-stripped within 24 hours after casting, marked and stored in the curing room or tank until the designated date of testing. Cause for concrete rejection is in accordance
- ' with ACI 318-63, Paragraph 504, for work prior to 6/1/73 and ACI 318-71, Paragraph 4.3.3, for work after 6/1/73.
() 3.8-27 Revision 18 2/79 4
, , , _ - - - - . - - - , - ~ , - - % , ,,.-,--p_,--,p ., ,-n.w -m,,.. -.-_,,.y- we, .w .,,,- ,- ,m_,_ ,-,-,-,,,yo ,y. , -c-- --,-.y%% -.
MIDLAND 1&2-FSAR 3.8.1.6.2 Reinforcing System h 3.8.1.6.2.1 Materials for Reinforcing System All reinforcing steel conforms to ASTM A 615-68 Grade 60, ASTM A 615-72 Grade 60, or to the latest applicable ASTM A 615, l33 cnd are required to have a minimum elongation of 7% on a full cize 8 inch loag specimen for bar sizes No. 11, 14, and 18. R duced bar sections are required to have a minimum elongation of 9% in 3 2 inch specimen. All bar-to-bar and bar-to-p?.a'.s. splicing material conforms to ASTM A 513 or ASTM A 519 Grades 3008 through 1030. The ladle analysis of each heat of reinforcing bar is required. Walded steel reinforcement splices are not normally permitted. However, ahen welded splices are required, the ladle analysis of the reinforcing bar heats is required, and the maximum carbon content allowed is 0.50%. All reinforcing steel is tagged to ensure traceability to Ccrtified Material Test Repur'= (CMTRs) during prodaction and while in transit. Subsequent t o acceptance by receiving inspection at the jobsite, procedural control is used to ensure traceability to CMTRs. For reinforcing steel procured before 6/1/73, one full diameter tensile test bar from each bar size is tested for each 50 tons or fraction thereof from each heat except that for bar sizes No. 14 and 18 the frequency is 100 tons. For reinforcing steel procured. after 6/1/73, one full diameter tensile test'bar from each bar eize is tested for each 50 tons or fraction thereof of reinforcing bar produced from each heat of steel. The tensile test procedures are in accordance with ASTM A 370. The acceptance standards are the tensile requirements of Table 2 of ASTM A 615. For reinforcing steel procured before 6/1/75, if a test specimen fails to meet the tensile requirements of ASTM A 615 the material represented by the test is rejected. For reinforcing steel procured after 6/1/75, if a test specimen fails to meet the tensile requirements of ASTM A 615, two additional specimens from the same heat and of the same bar size are tested. If either of the two additional specimens fails to meet the tensile requirements, the material represented by the tests is rejected. B:nd tests are made on bar sizes No. 3 through 11 in accordance with ASTM A 615. For bar sizes 14 and 18, shipped after May 15, 1977, bend tests are made on full size test specimens in accordance with ASTM A 615, Supplemental Requirement S-1. O Revision 33 3.8-28 4/81
MIDLAND 162-FSAR edge by more than 1/2 inch offset in 24 inches. The template ()
\ j used to measure the local deviations shall not be more than 1 to 2 feet longer than the area of the deviation itself.
The dome shall be in accoriance with the following tolerances when the pieces are checked on the ground before erection. An 8 foot long template curved to the required radius shall not show deviations of more than 3/4 inch when placed against the completed surface of the dome within a single plate section and not closer than 12 inches at any point to a welded seam. When the template is placed across one or more welded seams, the deviation shall not exceed 1 inch. The effect of change in plate thickness or of weld reinforcement shall be excluded when determining durations. The elevation of the dome shall be checked by taking measurements every 15 degrees on at least three radial locations. The elevations shall be within 13 inches of the theoretical elevatione and shall be referenced to the shell-dome connection line. A template curved to the regt41 red radius and placed against the outside erected surface of the dome shall not show more than 1/8 inch inward deviation and 1/4 inch outward deviation from the theoretical curve between two stiffeners.
,-s General liner plate tolerances also apply for the tolerance
( ; requirements for penetration assemblies. A 28 inch long template curved to the required radius shall not show deviations of more than 1/4 inch when placed against the completed surface of the shell within a single plate section. The individual penetrations and penetration assemblies shall be located within 11 inch of their theoretical elevation and circumferential location. Measurement of the tolerance of 11 inch may be measured on the jig prior to erection. , support brackets are located within i1 inch of their theoretical location. Measurement of the 11 inch may be measured on the jig prior to erection. The erection of the embedded floor beams and thickened floor I plate is within t1/2 inch of the theoretical location. The floor liner plate shall not have more than 1-5/8 inch bow across the i width of plate.
?rior to welding, the liner plate joints are aligned and retained i in position by the use of bars,. jacks,-clamps, tack welds, or cemporary attachmente.
The misalignment of completed joints is specified not to exceed l 10% of the plate *hickness or '/16 inch, whichever is greater. l 3.8-37 l t
. . -, m. _ . _ _ , , . .. , _ , _ , - . , , _ . _ _ , - . _ , , _ _ _ _ . _ . - _ . , . _ _ . . _ _ _ _ _ _ . , _ . , _ _ _ - _ _ _ _ _
MIDLAND 1&2-FSAR Any offset within the allowable tolerances provided above are fairec at a 3 to 1 taper over the width of the finished weld, or if necessary, by adding additional weld metal beyond what would otherwise be the edge of the weld. 3.8.1.6.4.2.2 Welding The edges of liner plate material are prepared by chipping, machining, grinding, sawing, or oxygen cutting. All edges are prepared and cleaned of foreign matter prior to welding. If manual flame cutting is used, the edges may be ground slightly. Tack welds used to secure alignment are either removed completely when they have served their purpose, or their stopping and ctarting ends are prepared by grinding or other suitable means so that they are satisfactorily incorporated into the final weld. Tack welds are made by quelified welders using qualified welding procedures. When tack welds are to become part of the finished weld, they are visually examined and defective welds removed. The welding material is selected, procured, identified, inspected, stored, and issued in accordance with the requirements of ASME Section III, Division 1. All liner plate seams, attachment of the leak chase system, and cadwelds are erected and welded in accordance with the applicable portions of Part UW of Section VIII of the ASME Boiler and Pressure Vessel Code, Division 1, 1971 Edition plus applicable addenda. Specifically, Paragraphs UW-26 through UW-38 inclusive apply in their entirety. All welders are qualified in accordance with Section IX of the ASME Code, 1971 Edition, plus applicable addenda. Malson studs welded to the thickened liner plate are in accordance with AWS Dl.1-72, Code for Welding in Building Construction. For fabrication, liner plate penetration assemblies are welded in accordance with Class 1, Subsection '?E of Section III of the ASME 33 Boiler and Pressure Vessel Code, 1971, as a minimum requirement, but a code stamp is not required. The attachment of penetration assembly to the liner plate is in accordance with Section VIII. For erection, liner plate penetration assemblies are welded in accordance with Class 1, Subsection NE of Section III of the ASME Boiler and Pressure Vessel Code, 1971, as a minimum requirement, 33 but a code stamp is not required. The attachment of penetration acsemblies to the liner plate is in accordance with Section VIII of the ASME Code. Lifting lugs, scaffold clips, and attachments for erection of the liner plate may be field welded to the liner plate with the approval of the responsible field engineer. These are only Revision 33 3.8-38 4/81
m MIDLAND 1&2-FSAR () (~N attached by properly qualified welders using ASME Code qualified welding procedures. Brackets and lugs permanently welded to liner plate steel are P-1 material as shown on Table Q-11.1 of Section IX of the ASME Code
.and attached using a qualified welding procedure.
Form ties and other similar items may be welded to the channel and angle stiffeners, but under no circumstances to the steel liner plate. All welding to channels and angle stiffeners are performed by certified welders. 3.8.1.6.4.3 Examinati'on of Liner Plate All liner plate welds performed in the field are subjected to nondestructive examinations. Examination frequency, examination te:hnique, and acceptance standards are in accordance with the ASME Code, Proposed Section III, Division 2, copyright 1973, with the following additions an2 exceptions: In addition to the requirements f ar radiographic examination, at least one 12 inch spot radiograph is taken in the first 10 feet of welding completed in a flat, vertical, horizontal, and overhead position by each welder. r Permanent stamping of location and identification of radiographic (3) film on the liner plate is not required. Each radiograph location is recorded on the plate rollout drawing. Magnetic particle examination is required where unwelded backing strip splices and intersections are permitted in liner plate welds. Liquid penetrant inspection is used to closely examine welds judged to be of questionable quality on the basis of initial visual examination, and to confirm +he complete removal of all defects from areas which have been prepared for repair welding. Liquid peneurant testing is also used to examine liner welds where neither radiographic nor magnetic examination is feasible. All welds are visually examined for uniformity, width, surface condition, and quality. The shop inspection and testing of all liner penetrations and reinforcement around such penetrations comply with Subsection B of Section III, Nuclear Vessels of the ASME Code. A code stamp is not required. The shop inspection and testing of walds for attachments to the thickened liner plate are examined by visual inspection. Welds which on the basis of visual examination are judged to be cf questionable quality are additionally tested by either dye f~'t penetrant or magnetic particle inspection. In addition to the d Revision 33 3.8-39 4/81
MIDLAND l&2-FSAR above requirement, a minimum of 10% of all welding by each welder is progressively examined either by dye penetrant or by magnetic particle inspection. When magnetic particle or dye penetrant inspection discloses welding which does not comply with the requirements of Article NB-5300 of Section III of the ASME Code, two additional spots are examined in the same area as the original test. If the two additional spots examined show welding which meets the minimum quality requirements of this section, the welding rcpresented is judged acceptable. The defective welding disclosed by the first of the three tests is removed and repaired by welding. If either of the two additional spots examined show welding which does not comply with the minimum quality requirements of this caction, the welding represented is rejected or completely rstested, and defective welding corrected. The rewelded joints or weld-repaired areas are completely retested. 3.8.1.6.5 Quality Assurance and Quality Control The material manufacturers' quality assurance programs are in accordance with Section 17.1. Material used in the construction of the containment is controlled and marked, and identification is maintained in accordance with Section 17.1. 3.8.1.7 Testing and Inservice Surveillance Requirements 3.8.1.7.1 Preoperational Structural Integrity Test Following construction the containment is proof-tested at 115% of the design pressure. Refer to Appendix 3A for a discussion of 33 compliance with Regulatory Guide 1.18. During this test, daflection measurements and concrete crack inspections are made to determine that the actual structural response is within the limits predicted by the design analyses. Subsequent to the test, a final test report will be issued. It will include a 33 description of the test procedure, instrumentation and its locations, and a detailed evaluation of the test results. An abstract of the Structural Integrity Test is provided in Chapter 14, 3.8.1.7.2 Preoperational Integrated Leak Rate Test Following construction of the containment, an integrated leak rate test of the containment and its penetrations is conducted. 32 This test is discussed in Subsection 6.2.6. An abstract of the Integrated Leak Rate Test is provided in Chapter 14. Revision 33 3 . 84- 4 0 4/81
MIDLAND 1&2-FSAR 3.8.1.7.3 Inservice Tendon Surveillance ( ',
\ ,,/ The inservice tendon surveillance program consists of evaluating the general condition of the post-tensioning system. Data on strand corrosion level and tendon lift-off forces are obtained and analyzed. The surveillance program provides assurances of the continuing ability of the structure to meet its design functions.
Refer to Appendix 3A for a discussion of conformance to Regulatory Guide 1. 35. 33 The Midland plant consists of two containment structures which are essentially identical. In accordance with-Paragraph C.2 of NRC Regulatory Guide 1.35, the selected tendons of Unit 1 containment shall be subject only to items a, b, and 1 in the program description of Section 9.3 of BC-TOP-5-A. 3.8.1.7.4 Liner Plate Surveillance The liner plate surveillance program demonstrates that the liner plate, its anchors, and the connections between the liner plate and its anchors are not strained in excess of allowable design values. This is accomplished by monitoring displacements of the liner and examining the liner near penetrations for any indication of excessive strains. (7 v
) The program will comply with BC-TOP-5-A, Rev. 3.
3.8.2 STEEL CONTAINMENT The containment is a prestressed, reinforced concrete structure, as described in Subsection 3.8.1; therefore, this section does not apply. 3.8.3 CONCRETE AND STEEL INTERNAL STRUCTURES OF STEEL OR CONCRETE CONTAINMENTS 3.8.3.1 Description of the Internal Structures j' Presented here is the discussion on the reactor support system, steam generator support system, reactor coolant pump support system, reactor coolant pipe restraints, primary shield wall, secondary shield walls, pressurizer supports, refueling canal walls, operating and intermediate floors inside the containment, missile shields, polar crane supporting elements, incore l instrumentation tunnel, and letdown cooler enclosure. The l I discusnion concentrates on the primary structural aspects and their ability to perform safety-related functions. 7~ r 1 ( ,) Revision 33 3.8-41 4/81
MIDLAND 1&2-FSAR 3.8.3.1.1 Reactor Vessel Supports . The reactor pressure vessel support system is shown in Figure 3.8-30. The cylindrical skirt and annular flange supporting the reactor vessel, which are described in Subsection 3.9.3.4.2, are mounted on 5-1/2 inch thick annular sole plate segments. These plates rest on ledges which form part of the primary shield wall. The reactor vessel is connected to the sole plates with ninety-six 2-1/2 inch diameter bolts. These bolts extend through the bottom flange of the reactor skirt, sole plates, and the cnchor plate which is embedded in concrete. Each bolt is 7'-4" long. Lateral and torsional loads are resisted by shear pins, l30 and shear lugs, and transmitted to the primary shield wall. The bolts offer resistance against overturning moments and uplift forces on the reactor vessel. 3.8.3.1.2 Steam Generator Supports The steam generator support system details are shown in Figure 3.8-31. The steam generator skirt is mounted on 3 inch thick annular sole plate segments and attached to the base by forty-eight 2-1/2 inch diameter anchor bolts. These bolts offer resistance against overturning moments and uplift forces and are embedded through a 30 by 15 inch concrete curb into the containment base slab. Lateral and torsional loads are resisted by bolts and shear lugs. In the upper regions (near elevation j 30 657), the steam generator is restrained against lateral movements by built-up steel members that are supported on the refueling canal walls and secondary shield walls. In order to allow for radial thermal growth during normal operation, shims are set during the hot functional test, and stainless steel plates are machined to dimensions for the hot position. There is a 30 1/32 inch gap between the shims and steam generator durir.g the hot conditions. 3.8.3.1.3 Reactor Coolant Pump Supports and Stops The reactor coolant pumps are each supported by the cold leg segment of reactor coolant piping, two constant force hangers, and a system of snubbers. These devices permit movements due to thermal growth during normal operation, while restraining the pumps in the event of a LOCA or seismic event. The constant force hangers are supported by steel beams which in turn are supported by the refueling canal walls and secondary shield walls, and control the forces transmitted to the coolant pipe during thermal growth. The snubbers resist dynamic loads d:veloped during a LOCA or a seismic disturbance. They transmit loads to the refueling canal walls and secondary shield walls. The support system, including the snubbers and constant force hangers, is shown in Figure 3.8-32. 3.8-42 Revision 30 O 10/80
MIDLAND l&2-FSAR loads, thermal loads, and LOCA leads. These loads include l 30 r' dynamic effects. The directions of the reversible loadings are ( ' '1) chosen to give the largest possible load at each support. Loads and loading combinations are presented in Sut;section 3.8.6. The supports are designed as Seismic Category I structures, using loads supplied by the NSSS vendor. The supports are connected to steel embeds which are anchored in the' secondary shield walls and refueling canal walls. The design standards used for the design of the bolts, baseplates, and embedments for the seismic Category I structural supports were the AISC (seventh edition), ACI 316-71, Appendix XVII of ASME III, and Code Case 1644-5. 17 The ASME Subsection NF hangers were designed per ASME Subsection NF-3220 and Appendix F, Section III of the ASME Boiler and Pressure Vessel Code. When designing linear component support bolted connections, including component-to-component and component-to-plant structure connections, the effects of prying due to the flexibility of the connection are considered. The following equation from The AISC 15 Manual of Steel Construction, 1970 Edition is used for high-strength bolts.
"100bdj'-14wtj' Q=F (see Figure 3.8-64, Detail 1)
,_3 62adb+21wtj. l25-( where V) Q = prying force per fastener F = externally applied load per fastener w = length of flange tributary to each bolt 15 d = nominal bolt diameter a = distance from fastener to edge of flange, not to exceed 2 t = thickness of flange b = distance from web face to fastener line All of the bolt materials used are similar in chemical .
composition and mechanical properties (see Table 3.8-32) to A-490 with the exception of A-449, which was not exposed to prying and therefore was not subject to the prying equation. Because of this cimilarity in properties, it is reasonable to assume that the AISC prying action equation for A-490 bolts also applies the 37 ' the A-540 and A-354 bolts. Bolt preload does not tend to affect the prying on the bolts as is shown in Figure 17.6 of Reference 3, page 263. Therefore, it is permissible to neglect the preload which was the design approach and agrees with Appendix XVII, 2461.1 of the ASME Code, Section III, which permits the exclusion of bolt preload effects in bolt stress calculations. V' 3.8-49 Revision 30 10/80
MIDLAND 1&2-FSAR For seismic Category I structural supports, the allowable stresses were 0.6 f for tension and 0.4 Fy for shear under normal conditions. yThe faulted condition allowable stresses were 0.9 Fy for tension and 0.5 Fy for shear. Please refer to 17 Table 3.8-32 fur values of F y (yield stresses). The interaction equation used for combined tension and shear in bolts other than anchor bolts was as follows: 2 2; s l
/f t)l+j( f y .
-< 1 30 (Ft/ (Fy fy and f t are the cal :ulated stresv;s. Fy and F g are the allowable stresses for shear and tension, respectively (see 17 Table 3.8-32).
For expansion anchors, the inte rac tion equation was as follows: g/f y 2+ f t2 g pt l 30 Ft is the allowable tension load (see Table 3.8-34) and fy and l 33 ft are the calculated chear and tension loads, respectively. The more conservative equation used for the grouted anchors was as follows: f f _t_ + _v_ s 1 Ft Fy j7 Fy is the allowable shear load and the other terms are the same as in the expansion anchor equation (see Table 3.8-35). The steel embedments were designed per the appropriate specifications and design guides as stated previously, using the applicable load equation from FSAR Subsection 3.8.6.3. The ultimate pullout has not been determined for the embedments. Only the allowable capacity was checked against the controlling load equation per the FSAR commitment. There were no test reports on Midland for embedments. Figure 3.8-64, Detail 4 and 5 and Figure 3.0-65, Details C, 7, 8, 30 and 9 show typical connections subject to prying. In Detail 5, the total additional bolt stress due to prying is 18.4 ksi for a total of 71.1 ksi, which is less than the 94.8 ksi allowable q tOnsile stresc. For Detail 7, the additional bolt stress is 6.3 kai for a total of 43.1 ksi, which is less than the 90.0 ksi allowable tensi]e stress. Detail 8 is not subject to prying duc 15 to the absence of significant tensile load on connection (0.6 kips per bolt). For those connections where prying is considered negligible due to the rigidity of the connection, two approaches are used. For all cases other than the ASME Subsection NF hangers, the 3.8-50 Revision 33 O 4/81
? MIDLAND 1&2-FSAR
<"' a. 650 k/f t vertical line load applied at two places -180*
apart
- b. 190 k/ft vertical line load applied at'two places'180*
apart, and a 600 psi pressure acting on the entire cavity The primary shield wall and cavity were also analyzed for a 3,000 psi uniform internal pressure. The results-indicate that
', load is more critical-than the other two. Under this condition, the concrete is allowed to crack locally in high stress areas, and the maximum stress in the reinforcing steel is-limited to 90% of ultimate strength.
3.8.3.4.3 Secondary Shield Walls-Steam Generator Compartments. The secondary shield walls and the refueling canal walls forming the steam generator compartments are designed for the equivalent static internal pressure differential distribution shown in Figure 6.2-23, Figures 6.2-88 through 6.2-95, and Figures 6.2-113 11 through 6.2-118, due to the most severe of the postulated breaks
. listed in Subsection 3.6.3. The compartments are also designed i for the seismic loadings described in Section 3.7. Forces.cn.
localized areas of the walls from impingement of escaping fluid or loadings from restraints due to the postulated pipe breaks
~s listed in Subsection 3.6.3~are considered.
k/I The steam generator compartment walls were analyzed with a finite element model using BSAP computer code. This analytical model is 10 shown in Figure 3.8-49. The walls are connected to the l foundation by reinforcing steel and are assumed fixed at the
- base. The maximum stress in the reinforcing steel.is limited to l 90% of yield stress. Loads used in the analysis include dynamic loads from postulated pipe breaks, as well as seismic, temperature, and operating loads. The walls are designed assuming a stress-free temperature of 70F. The compartment temperatures and resultant gradients shawn in Figure 3.8-50 were considered in the analysis. The governing loads (Mu, Pu) and the safety factors of the provided rebars are shown in Tables 3.8-29 10 and 3.8-30.
I D V Revision 33 3.8-50c 4/81
I MIDLAND 152-FSAR O THIS PAGE INTENTIONALLY LETT BLANK O P Revision 17 3.8-50d 1/79
l MIDLAND 1&2-FSAR ASTM A 366-71 Specification for Zinc Coating (Hot Dip) '
/^ ' on Assembled Steel Products ASTM A 440-70a Specification for High-Strength Structural Steel 14 ASTM A 441-70a Specification for High-Strength Low-Alloy Structural Manganese Vanadium Steel ASTM A 449-76b Specification for Quenched and Tempered Steel Bolts and Studs ASTM A 478-76 Specification for Chromium-Nickel Stainless and Heat-Resisting Steel ?
Weaving Wire ASTM A 479-75 Specification for Stainless and Heat-Resisting Steel Bars and Shapes for Use in Boilers and Other Pressure Vessels ; ASTM A 480-74a, 75 Specification for General Requirements for Flat-Rolled Stainless and Heat-Resisting Steel Plate, Sheet, and Strip ASTM A 490-67 Specification for Quenched and Tempered l 28 to 76a Alloy Steel Bolts for Structural Steel Joints ASTM A 500-74a Specification for Cold-Formed Welded and Seamless Carbon Steel Structural Tubing ] in Rounds and Shapes ASTM A 501-71a, 76 Specification for Hot-Formed Welded and Seamless Carbon Steel Structural Tubing ASTM A 515-74b Specification for Pressure Vessel Plates, 14 Carbon Steel for Intermediate and Higher Temperature Service ASTM A 516-72 Specification for Pressure Vessel Plates, j Carbon Steel for Moderate and Lower Temperature Service 1 l ASTM A 540-76 Specification for Alloy-Steel Bolting Material for Special Applications l ASTM A 563-76a Specification for Carbon Steel Nuts ASTM A 569-72 Steel, Carbon (0.15 maximum, percent) Hot-Rolled Sheet and Strip, Commercial Quality 26 ASTM A 670-75 Specification for Hot-Rolled Carbon Steel ('N Sheet and Strip, Structural Quality
- N >l Revision 32 3.8-65 1/81
MIDLAND l&2-FSAR ASTM A 572-72, 73, Specification for High-Strength, Low-Alloy 76 Columbian-Vanadium Steels of Structural Quality ASTM A 588-75 Specification for High-Strength Low-Alloy Structural Steel with 50,000 psi Minimum Yield Point to 4 Inches Thick ASTM A 614-73 Specification for Special Requirements for Bolting Material for Nuclear and Other Special Applications ASTM C 31-69 Making and Curing Concrete Test Specimens in the Field ASTM C 33-71a Specification for Concrete Aggregates ASTM C 39-71 Test for Compressive Strength of cylindrical Concrete Specimens 14 ASTM C 40-66 Tests for Organic Impurities in Sands for Concrete ASTM C 70-73 Test for Surface Moisture in Fine Aggregates ASTM C 87-69 Test for Effect of Organic Impurities in Fine Aggregate on Strength of Mortar ASTM C 88-71a Test for Soundness of Aggregates by Use of Sodium Sulf ate or Magnesium Sulf ate RSTM C 94-72, 78a Specification for Ready-Mixed Concrete 1 33 ASTM C 109-75 Test for Compressive Strength of Hydraulic Cement Mortars (Using 2-Inch or 50-mm Cube Specimens) ASTM C 117-69 Test for Materials Finer Than No. 200 (75 am) Sieve in Mineral Aggregates by Washing ASTM C 123-69 Test for Lightweight Pieces in Aggregates ASTM C 127-68 Test for Specific Gravity and Absorption of Coarse Aggregate ASTM C 128-68 Test for Specific Gravity and Absorption of Fine Aggregate 1 ASTM C 131-69 Test for Resistance to Abrasion of Small Si7e Coarse Aggregate by Use of tLO Los Angeles Machine Revision 33 3.8-66 4fg1
MIDLAND 1&2-FSAR ASTM-C 140-75 Sampling and Testing Concrete Masonry f] Units ASTM C 142-71 Test for Clay Lumps and Friable Particles.
- in Aggregates ASTM C 143-74 Test for Slump of Portland Cement 14 Concrete
~
ASTM C 144-70 Specification for Aggregate for Masonry
' Mortar 1
ASTM C 150-72,78a Specification for Portland Cement l1e ASTM C 151-74 Tests. for. Autoclave Expansion of Portland Cement i ASTM C 156-71 Tests for-Water Retention by Concrete Curing Materials ASTM C 171-69 Specification.for Sheet Materials for , Curing Concrete ! ASTM C 172-71 Sampling Fresh Concrete ASTM C 183-76 Sampling Hydraulic Cement ASTM C 191-74 Test for Time of Setting of Hydraulic [N Cement by Vicat Needle (Including Tentative Revision) ASTM C 207-49 Specification for Hydrated Lime for-(1968) Masonry Purposes 14:_ ASTM C 227-71 Test for Potential Alkali Reactivity of Cement-Aggregate Combinations (Mortar-Bar Method) ; i ASTM C 231-74 Test for Air Content of Freshly Mixed i Concrete by the-Pressure Method ASTM C 235-68 Test for Scratch Hardners of Coarse Aggregate ASTM C 260-69, 77 Specification for Air-Entraining 133 Admixtures for Concrete-l ASTM C 289-71 Test for Potential Reactivity.of Aggregates (Chemical Method) jg l ! ASTM C 295-65 Recommended Practice for Petrographic Examination of Aggregates for Concrete-i () 3.8-67 Revision 33 4/81
, _ . . . . - - - ~ , . . . . _ . _ . . , ._ _ - _ ,.~ , . .. , _ . _ .,_.... . ,_ _ , . _ ,._.. .._,_ __ _ . _ . . _ - . - _ _
M7DLAND 1&2-FSAR ASTM C 309-74 Specification for Liquid Membrsne-Forming l Compounds for Curing Concrete ASTM C 311-68 Sampling and Testing Fly Ash or Natural ;g Pozzolans for Use as a Mineral Admixture in Portland Cement Concrete ASTM C 494-71, 80 Specification for Chemical Admixtures for 133 Concrete 14 ASTM C 566-67 Tension Testing of Carbon Graphite ' (R1972) Mechanical Materials 133 ASTM C 567-71 Test for Unit Weight of Structural Lightaelght Concrete ASTM C 618-72 Specification for Fly Ash and Raw or Calcined Natural Pozzolan for Use as a 14 Mineral Admixture in Portland Cement Concrete ASTM D 395-69 Tests for Rubber Property - Compression (R1975) Set l 33 ASTM D 412-68, 75 Tests for Rubber Properties in Tension ASTM D 422-63 Particle-Size Analysis of Soils ASTM D 423-66 Test for Liquid Limit of Soils ASTM D 424-59 Tests for Plastic Limit and Plasticity (R1971) Index of Soils 133 ASTM D 512-67 Tests for Chloride Ion in Water and Waste Water ASTM D 854-58 Test for Specific Gravity of Soils ASTM D 1556-64 Test for Density of Soil in Place by the Sandcone Method 14 ASTM D 1557-70 Tests for Moisture-Density Relations of Soils, Using 10-Pound ( 4. 5-kg ) Rammer and 18-Inch (457-mm) Drop ASTM D 1751-71 Specification for Preformed Expansion Joint Fillers for Concrete Paving and Structural Construction (Nonextruding and Resilient Bituminous Types) Revision 33 3.8-68 4/81
MIDLAND 1&2-FSAR
- 8. All liva _ loads transmitted by internal structures b)
\ ,/ c. .Seismis Loads Selsmic loads for safe shutdown earthquake load and the operating basis earthquake load were considered.. A more detailed. discussion:is presented'in Section<3.7.
- d. Pipe Rupture Loads Pipe rupture : loads include the jet impingement forces from postulated pipe breaks, differential pressures tlutt might build up across compartments, and loads due.to pipe whipping or pipe restraint. Pipe rupture effects are further discussed in Section 3.6.'
i ! e. Thermal Loads Thermal loads include the temperature gradients through the spent fuel pool walls and floor, the primary and secondary shield walls, forces en internal structures-due to the thermal expansion and contraction of the i liner plate, piping, and equipment, including increases in water temperature during operating and accident conditions.
- f. Wind and Tornado Loads
{N) Wind and tornado loads were considered and are discussed
' ' ' in detail in Section 3.3. Tornado missile effects are discussud in Subsection ?.5.3.
All structures whose failure could endanger Seismic Category I structures, systems, or equipment, are
~
designed to withstand the effects of the wind and tornado loadings and to provide protection of Seismic l Category I systems and components from tornado missiles. I The structures are analyzed for tornado loading not coincident with the safe shutdown earthquake.
- g. Hydrostatic Loads Lateral hydrostatic pressure loads and buoyant forces resulting icom the displacement of groundwater or probable maximum flood (PMF) have been applied to the structures and are accounted-for in the design and discussed further in Section 2.4.
The following variables are used in the loading combination equations: U = Required strength to resist design loads or their related internal moments and forces
%.) 3.e-voc Revision ,,
3/79
MIDLAND 1&2-FSAR For the ultimate load capacity of a concrete section: U is calculated in acecrdance with ACI 318-63 Part IV-8 for design calculations initiated prior to February 1, 1973 U is calculated in accordance with ACI 318-71 for design calculations initiated after February 1, 1973 Fy = Specified minimum yield strength for structural steel 33 f s = Allowable stress for structural steel; fs is calculated in accordance with the AISC Code, 1963 Edition for design calculations initiated prior to February 1, 1973. O l 1 Revision 33 3.8-70d 4/81
MIDLAND 162-FSAR 3.8.6.3.4 other Loadings. () ~ In additicn to the previous load combinations listed, the . structures were checked . for overturning, sliding, and flotation utilizing the load combinations and minimum safety factors indicated below: Minimum Factor of Safety Load. Combination Overturning Sliding Flotation D+H+E 1.5 1.5 --- D+H+W 1.5 1.5 --- D + H + E' 1.1 1.1 --- D + H + W' 1.1 1.1 --- D+B --- --- 1.1 where H is the lateral earth pressure 3.8.6.4 Design and Analysis Procedures Design and analysis procedures for the containment including the base slab are discussed in subsection 3.8.1.4. For all othar Seismic Category I structures including foundations and containment internals, the basic techniques used for analysis and design are the conventional methods used in engineering _ practice such as the theory of concrete structures or beam theory, and those based on plate and shell theories of different (s_/) degrees of approximation. These are discussed in more detail in Subsections 3.8.3.4, 3.8.4.4, and 3.8.5.4. The seismic analysis of these structures is covered in Section ! 3. 7. The structures are proportioned to maintain elastic l behavior when subjected to various combinations of dead loads, [ live loads, wind loads, tornado loads, and LOCA loads. The upper limit of elastic behavior is the yield strength of the effective load carrying structural materials. 1 l ! 3.8.6.5 Structural Acceptance Criteria The fundamental acceptance criterion for the containment is the
- successful completion of the structural integrity test, with l measured responses within the limits predicted by analyses. The limits are predicted based on test load analyses, test load combinations, and code allowance values for stress, properties, and construction tolerances as described in Subsection 3.8.1. In this way, the margins of safety associated with the design and construction of the containment are, as a minimum, the accepted margins associated with nationally recognized codes ' of practice.
1 O 3.8-75 l
MIDLAND 162-FSAR The structural integrity test is planned to yield information on both the overall response of the containment and the response of localized areas, such as major penetrations and buttresses, which cre important te its design functions. The design and analysis methods, as well as the type of construction and construction materials, are chosen to allow ccsessment of the structure's capability throughout its service life. Additionally, surveillance testing provides further ccsurance of the structure's continuing ability to meet its dcsign functions. The containment internals and other Seismic Category I structures cnd foundations are designed to meet the structural acceptance criteria discussed in Subsections 3.8.3.5, 3.8.4.5, and 3.8.5.5. The limiting values of stress, strain, and gross deformations are established by the following criteria:
- a. *o maintain the structural integrity when subjected to the worst load combinations
- b. To prevent structural deformations from displacing the seismic Category I equipment to the extent that it suffers a loss of function The allowable stresses are those specified in the applicable codes. The stress contributions due to earthquakes are included in the load combinations described in Subsections 3.8.1.3 t 33 3.8.6.3.
3.8.6.6 Materials, Quality Control, and Special Constructi6n Techniques l1 The materials, quality control, and special construction techniques are the same as those presented in Subsection 3.8.1.6 for containment. 3.8.6.7 Testing and Inservice Inspect $1on Requirements The testing and inservice surveillance planned for the containment is presented in Subsection 3.8.1.7. Testing and inservice surveillance are not planned and not required for the internal structures because the internal structures are not directly related to the concept of containment. No structural preoperational testing of the other Seismic Category I structures is planned. During the life of the plant, , periodic inspections of structures will be made to employ visual inspection for apparent structural deterioration, such as large cracks and excessive deflection of structural members, All seam Revision 33 3.8-76 4/81
i (A V) -b TABLE 3.8-31 SHELL STRESS ON THE BWST DUE TO NOZZLE LOADS l 37 i Membrane Membrane Allowable plus Bending Allowable Stress (psi) per ASME III (max) . per ASME III Nozzle Load Case Description (max) Code Stress (psi) Code 1 3"# level transmitter nozzles Normal Deadweight + 5,713 18,800 10,720 28,200 pressure 'j$ 1 Upset Normal +0BE 5,789 20,680 11,797 31,020 Faulted Normal +SSE 6,244 37,600 19,093 45,120 20"7 heater nozzle Normal Deadweight + 4,363 18,800 10,073 28,200 pressure Upset Normal +0BE 4,761 20,680 11,759 31,020 Faulted Normal +SSE ",878 37,600 21,875 45,120 j Timperature element nozzle Normal Deadweight + 14,221 18,800 10,073 28,200 ! pressure 97 4 Upset Normal +GBE 14,295 20,680- 11,759 31,020 Faulted Normal +SSE 14,733 37,600 21,875 45,120 l Level switch nozzles Normal Deadweight + 14,221 18,800 10,073 28,200 pressure 97 Upset Normal +OBE '14,295 20,680 11,759 31,020 Faulted Normal +SSE 14,733 37,600 21,875 45,120 Inlet and outlet nozzles Normal Deadweight + None"> 18,800 10,073~ 28,200 lI 37 i pressure Upset Normal +0BE 20,680 11/759 31,020 g5 Faulted Normal +SSE 37,600 21,875 45,120 i . Overflow nozzle Normal Deadweight + None"> 18,800 10,073 28,200 li 37 .; pressure , Upset Normal +0BE 20,680 11,759 31,020 l j$ Faulted Normal +SSE 37,600 21,875 45,120 i Drain nozzle Normal Deadweight + None"' 18,800 10,073 28,200' pressure l 37 a Upset Normal +0BE 20,680 11,759 31,020 Faulted Normal +SSE 37,600 21,875 45,120 15 1
"' Bottom penetrations.(heavily reinforced) l 17
~
$ Revision 17 , 1/79
MIDLAND 1&2-FSAR TABLE 3.8-32 STRUCTURAL BOLT PROPERTIES 17 Yield Stress Ultimate Stress Material (ksi) (ksi) Comments A-540, 130 145 Values taken from Grcde B23, Class 3 26 ASTM. A-354, 130 150 1/4 to 2-1/2" 33 Grade BD diameter 115 140 Over 2-1/2" diameter A-490 130 150 Values taken from ASTM A-449 92 120 1/4 to 1" diameter 26 81 105 Over 1 to 1-1/2" diameter Values taken from ASTM O O Revision 33 4/81
amm g_m m aa mwmu_aea,ama-v mu-mu,aaa ,m s- a-L_as__k-MA - o,,, +Ledr M&JamA4z san pA,ma au- - - ,sm.Ame dem,- eA,naAAa & Os .- 4 ,a m- -,a_4nm 4 . MIDLAND 1&2-FSAR i ! i N t l l l I ( l I h i E 4 e 1 b i
?
t h
@ Revision 30 10/80
MIDLAND 1&2-FSAR TABLE 3.8-34 ALLOWABLE DESIGN LOADS (kips) FOR 17 WEDGE AND STUD TYPE ANCHORS Tension (T), (kips) Shear (S), (hips) l 33 Embed- f 'c , (psi)hl f'e , (psi)M) Anchor ment Minihum 17 Diameter E (in) (in) 3,000 4,000 25,000, 3,000 4,000 25,000 __lin) Spacing l 32 1/4 1-1/8 0.25 0.30 0.32 0.30 0.4 0.4 3 3/8 1-5/8 0.5 0.5 0. 6 ' O.8 1.0 1.1 4 1/2 2-1/4 1.0 1.2 1.4 1.3 1.5 1.7 5 17 5/8 4 2.0 2.0 2.2 2.2 2.2 2.4 6 2-3/4 1.6 1.8 1.8 2.2 2.2 2.4 3/4 5 3.0 3.3 3.4 3.0 3.3 3.4 7-1/2 4 2.6 2.9 3.0 3.0 3.3 3.4 132 3-1/4 2.4 2.7 2.7 3.0 3.3 3.4 7/8 5-1/2 3.5 4.0 4.5 4.0 40 4.5 9 4 3.0 3.4 3.4 4.0 4.0 4.5 1 6 4.0 4.8 5.6 5.0 5.0 5.6 10 17 4-1/2 3.6 4.1 4.1 5.0 5.0 5.6 (" Values are based on manufacturer's data. l l I Revision 33 4/81
MIDLAND 1&2-FSAR TABLE 3.8-35 ALLOWABLE DESIGN LOADS (kips) FOR GROUTED ANCHOR BOLTS Anchor Embed- Hole Size Tension (T) (kips) Diameter ment (in.) f'c (psi) Shear (kips) (inches) (inches) (D=2d41/2") 3,0C_0 4,000 f5,000 (S) 5/8 4 1.75 1.6 2.2 2.7 3.0 3/4 5 2.00 2.4 3.1 3.9 3.6 7/8 6 2}}